ML20101F208

Rev 16 to Surveillance Instruction SI-114.2, ASME Section XI ISI Program Unit 2

ML20101F208
Person / Time
Site:	Sequoyah
Issue date:	02/08/1992
From:	Goulart J TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20101F196	List: ML20101F193 ML20101F201 ML20101F208
References
SI-114.2, NUDOCS 9206240331
Download: ML20101F208 (182)

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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT q SURVEILLANCE INSTRUCTION SI-114.2 ASME SECTION II INSERVICE INSPECTION PROGRAM t UNIT 2 Revision 16 PREPARED / PROOFREAD BY Jefferv Goulart DATE: 12/18/9J_ } SIGNATURE: O N f // RESPONSIBLEORGANlZATION: ' I il7d* OJ 4<.i t v OANm 7/Thtd APPROVED BY: 68# DATE: A 8-f 's EFFECTIVE DATE: DON 6 f REVISION DESCRIPTION: General revision to define organization ia responsibilities, incorporate support modifications, CCHx changeout, and RTD modification and UHI [ modification; incorporated all punchlist items: O, j_ O-A, 0-B, 0-C and 0-D; removed Appendix G, " Support Load Criteria"; added reference to Code Cases N-402, N-426, and N-461; correctM various typographical erros; revised Exam Tables to better define weld numbers, support numbers, valves and other components subject to examination in ISI interval; revised (, Augmented Inspection Sections added augmented exam U tables, responsible organization, inspections completed, and sequence of order; revised section on fi Successive Inspections, added Successive Inspection h Table, Revised Notice of I wication (NOI) Section, added section on Corrective Action, revised Requests for Relief (RFR) to reflect Nuclear Regulatory Commission (NRC) Safety Evaluation Report (SER) Summary J Evaluation, added four additional RFRs 'ISI-15, -16, -17, and -18), revised various ISI Drawings. m 9 ( P4 M J 1401C/COC3

-_~ suand shece - SI-ll4.2 SURVEILLANCE ASME SECTION %I Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 2 of J?S p TABLE OF CONTENTS P_agm Owner Statement. 4 0.1:- Prerequisites. 5 O.2 Precautions. 5 1.0 Statement of Applicability 5 2.0 Purpose. 6 3.0 Inspection Intervals and Inspection Periods. 9 6 4.0. Codes of Record and Code Cases _. 39 7 5.0 Method of Implementation and Responsibilities. 8 F- ; 6.0 Abbreviations and Definitions. 16 7.0 Components Subject to Examination - ASME Code Class 1. 18 2, 8.0 Corponents Subject to Examination - ASME Code Class 2. 44 9.0 Components Subject to Examination - ASME Code Class 3. + 56 - 'j 10.0 Authorized Inspector 62 11.0 Examination Methods and Calibration Blocks f.{' 62 7 -12.0 Qualifications of Nondestructive Examination Personael 62 ? j-13.0 Acceptance-Criteria.. 63 14.0 Repairs and Replacements e 63 15.0 Pump and Valve Testing. a-63 ] 16.0 Records and_ Reports.......... 63 L' 5 e 17.0 Notification of Indication 67 18.0 Corrective Action Program. 4 x 69 19,0. Requests for Relief. 70 20.0 Augmented Inspections. 70 21.01: Interface Documents.. 78 22.0 --Developmental References 78 [1 . 3 40M4 (NP 198) 1401C/COC3 -+v- + W g-W v ps wi a --u. Tr re---ww -r<' rr y v--W--e-riir--- v --T -w-g

... ~,. ~ - -. Sraodcrd Ebces SI-114.3 ' SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION-INSERVICE INSPECTION PROGRAM Page 3 of 125 TABLE OF CONTENTS (Continued) Enge APPENDICES Appendix A - Tables. 81 Appendix B - Data Sheets 110-- Appendix C - Notification of Indication-Form 111 Appendix D - Guidelines for Determining Piping Component Support Examination Boundaries. 112 Appendix E - Fleid Corrected Drawing Transmittal Form. 124 SOURCE NOTES 125 ATTACHMENTS Revision _ - Drawing List O ................... - Valve Tables 0 Requests for Rellof O r 74t 5 I 1. . i >2\\1 Ij i J b e i f w + w l'A AOC&3 (NP 2/91) . _u-1401C/COC3 A ....,,. _ -, _. _.. ~. _,, -,., - -

'.asdzad Shers I SI-114.2 S!IhVEILLAN' :E ASME SECTION XI Revision 26 INSTRUCTIO'l INSERVICE INSPECTION PROGRAM Page 4 of 125 L. OWNER STATEMENT Ownt : Tennessee Valley Authority Address of Corporate Offices Chattanooga Office Coreplex 1101 Market Street Chattanooga, Tennessee 37402-2801 Hnme and Address of Nuclear Power Plants Seguoyah Nuclear Plant P.O. Box 2000 Soddy Daisy, Tennessee 37379 24 Aprs. cable Nuclear Power Units: Sequoyah Nuclear Plant, Unit 2 Cornmercial Operation Date: June 1, 1982 ( h.\\ {, s i ,4.) I L. g. L i .) r. l L l l l m 'M 1 m 'l 5 jmC4 (NP 2,91) 1401C/COC3 1

Soodad $ket SURVEILLANCE SI-114.3 ASME SECTION XI INSTRUCTION Revision 16 INSERVICE INSPECTION PROGRAM Page 5 of 125 0.1 PREMEQUIEXIES 0.1.1 When craft support of minor or similar maintenance (examples: scaffolding, insulation removal, buffing of welds using I Scotchbrito pads, and cleaning bolts) is required to facilitate performance of this surveillance instruction (SI), a work request (WR)/ work order (WO) may be used. This WR/WO shall be processed in accordance with Sequoyah Standard practice (SSP) 6.21 and the system code for SI-114.2 (system code 114.2) will be referenced on the WR. Additional WRs are required to remove fire barrier insulation foam in sleeves, piping support clamps, steam generator support rings, reactor coolant pump flywheel access covers and plugs, etc. {l 0.1.2 Contact Radiological Control (RC) for radiation work permit (RWP)/ALARA preplanning requirements. l 0.1.3 controlled copies of ASME Section XI Code Classification Drawings and ISI Drawings are issued through DCRM. 0.2 EttgAutions +- 0.2.1 Safety belts should be worn when working from scaffolding or ladders in accordance w1L AI-56. i l 0.2.2 Protective clothing, such as long-sleevo shirts or gloves, should be worn except in RWP areas when working around hot pipes and equipment. 0.2.3 Care should be exercised when climbing on plant structures and piping to ensure firm footing. Flexing of instrument lines and electrical conduit, for example, could cause equipment damage as well as bodily injury resulting from a fall. Walking on insulation shall be avoided. m 0.2.4 Efforts should be made to ensure proper planning to reduce delays and radiation exposure in performance of the work. 0.2.$ Read and observe all applicable precautions as indicated in J Sequoyah Nuclear Plant (508) Administrative Instruction AI-8 t " Access to Containment," and SSP 12.8 " Foreign Material Exclusion." 1.0 STATEMENT OF R PLICADILITY e i This program outlines requirements for performing the first 10-year interval inservice nondestructive examinations (NDEs) of the SON Unit 2, American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 (equivalent) components (and their supports) containing water, steam, or ~ radioactive material (other than radioactive waste management systems). The program has been organized to fulfill inservice examination l requirements of Standard (STD) 6.10 and comply as practical with the 3 requirements of Section XI of the ASME Boller and Pressure Vessel Code. In add) tion, this program implements applicable portions of the SON (um pr 230 a 1401C/COC3 -m -c-~_ _, - s

su nbrd swei SI-114.2 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 6 of 125 ~, Technical Specifications. The Inservice Inspection (ISI) Program satisfies the requirements of Surveillance Requirements 4.4.5.0 and 4.4.10 and partially satisfL ' the requirements of Surveillance Laquirement 4.0.5. Inspection frequencies are in accordance with Appendix A of this instruction and are generally scheduled to coincide with outage periods. ) The requirements of this program are applicable beginning at the date of i commercial operation of the unit. 2.0 EUREQSE The ISI Program shall be used for planning inspections and examinations of SON ASME Class 1, 2, and 3 (equivalent) interval. components for the first ISI The examinations required by this program will establish acceptance of components for continued service. 3.0 INSPECTION INTERVALS AND INSPECTIOH_uilllODS The inservice examinations required by ASME Section XI shall be performed during each 10-year interval of service (inspection interval). The inspection intervals reprecent calendar years after the unit has been placed into commercial service. The commercial operation L, date for Unit 2 is June 1, 1982. The inspection interval may be decreased or extended by as much as one year. If the unit is out of service continuously for six months or more, the inspection interval may { be extended for an equivalent period. This SI may ha performed in any L mode and is applicable for all operational modes. The inspection interval shall be separated into three inspection ij perluds. Except for examinations that may be deferred to the end of the inspection interval, the required examinations shall be performed in accordance with the following schedule. L. Minimum Examinations Maximum Examinations Inspection Period Completed. Percent _ _Comoleted. Percent 3 Years 16 34 7 Years 50 67 q 10 Years 100 100 The examinations deferred to the end of the inspection interval shall be completed by the end of the inspection interval. y a b N )A 40M4 @P 190 1401C/COC3

SuaJard Meet SI-114.3 SURVEILLANCE ASME RECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 7 of 125 On August 21, 1985 SON Unit 2 vent off line and remained off line until e May 13, 1988. In accordance with IWA-2400(c) TVA will extend the first interval by 996 days. As a result of this extension, the first interval will end on Februar* ??, 1995. The period duration will be as follows: First period 'J at 1, 1982 through May 31, 1985 Second period: Jure 1, 1985 through February 21, 1992 Third period: February 22, 1992 through February 21, 1995 4.0 CORES OP RECORD ANp__CQDX_CASIS Preservice examinations were conducted in accordance with the 1974 Edition, Summer 1975 Addenda, of ASME Section XI. 51-114 was the Preservice Inspection (PSI) Program for SON Units 1 and 2. The SON Unit 2 operating license (Iow power) was issued on June 26, 1981. Thus, as a minit'1 the ISI Program shall not be prepared to a Section XI Code Edition and Addenda prior to the 1974 Edition, Summer 1975 Addenda. In accordance with 10 CFR Part 50.55a(g)(4)(iv), this program was prepared to meet the requirements of the 1977 Edition, Summer 1978 Addenda, of Section XI of the ASME Boiler and Pressure Vessel Code. Steam Generator Tubing Examination requirements are in accordance with Regulatory Guide 1.83, Rev. 1, and Technical Specification and Surveillance Requirement 4.4.5. In accordance with 10 CFR Part 50.55a(b)(2), the extent of examination for piping welds, Examination Categorlea B-J and C-F, is in accordance with the 1974 Edition, Summer 1975 Addenda of ASME, Section XI (Examination Categorir 9-J, C-F and C-G). Extent of examination is defined as criteria for th< . election i j' of Class 1 and Class 2 components for examination and as criteria for determining which Class 2 components may be exempt from examination. The extent of examination specifies the length of weld to be examined. L-See Section 19.0 and Attachment 3 of this program for requests for relief information. ( }, The qualifications of NDE examination personnel shall be as per paragraphs IWA-1600, IWA-2300, and Table IWA-1600-1 of ASME Section XI 1983 Edition, Winter 1985 Addenda. TVA will use the 1984 Edition of ASNT ( SNT-TC-1A for certification of NDE personnel as approved by the Nuclear Regulatory Commission's (NRC's) letter from S. C. Black to O..D. Kingsley, Jr., dated January 38, 1990. (TAC No. 72833) TVA will use the following Code cases which have been approved by the NRC per Regulatory Guide 1.147 and as outlined on the applicable NDE procedure: L N-209, Conditional Acceptrnce of Identifiable Isolated or Random Rounded Indications N-234, Time Between Ultrasonic Calibration Checks i IA 40MJ (NP 291) J 1401C/COC3 l

htno&Jd Sheet SI-114.3 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 8 of 125 N-235, Ultrasonic Calibration Checks per Section V N-307-1, Revise 6 Ultrasonic Volume for Class 1 Bolting, Table 1 IWB-2500~1, Examination Category B-G-1, When the Examinations are Conducted from the Center Drilled Hole N-308, Documentation of Repairs and Replacements of Components in Nuclear Power Plants N-401-1, Eddy Current Examination { N-402, Eddy Current Ca11bration Standard Sinterial i N-416, Alternative Rules for Hydrostatic Testing of Repair or b Replacernent of Class 2 Piping N-426, Extent of VT-1 Examinations, Category D-G-2 of Table IWB-2500-1. N-435-1, Alternative Examination Requirements for Vessels with Wall Thickness 2 Inches or Less N-461, Alternative Rules for Piping Calibration Block Thickness Code Cases N-341, Certification of Level III NDE Examiner, and N-356, I Certification Period for Level III NDE Personnel, were authorized for TVA use by NRC by memorandum from Gary L. Zech to S. A. White, dated i January 25, 1988. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Wolds, was authorized for TVA use by HRC by memorandum from Suzanne C. Black to 0. D. Kingsley, Jr., dated December 13, 1989. TVA will utilize Regulatory Guide 1.150, Rev. 1, " Ultrasonic Testing of Reactor Vessel Wolds During Preservice and Inservice Examinations," for its examinations as outlined in the applicable NDE procedure. i 5.0 METHOD OF IMPLEMENTATION AND RESPONSIBILITIES 11 'j Any revisions to this nrocrarn _ initiated by other grag.ps shall be subenitted to ISI Proggnms for approval prior to incorporatipij,hg I.Dvisions into this orootAtg. t -e 5.1 ISI Progr.gna 5.1.1 ISI Program Responsibilities: I p' l A. Defining ASME Section XI Code classification 1, 2, and 3 (equivalent) boundarles in accordance with n l 10 CFR 50.2(v), Regulatory Guide 1.26 R3, ASME Section XI and guidelines in 10 CFR 50.55a. n B. Preparing / revising ASME Section XI color-coded boundary classification drawings to identify the ASME Section XI w Code classification 1, 2, and 3 (equivalent) boundaries l A4 m4 (NP1H) 1401C/COC3

5utJ2rd Deet SI-114.2 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 9 of 125 within each plant system as defined in 5.1.1.A. These drawings are to be used for all ASMZ Section XI progran activities only. See Attachment 1 for drawing list. C. Preparing /revleing ASME Section XI drawings which identify the Class 1, 2, and 3 equivalent components (including supports) that require inservice and/or preservice condestructive examination (NDE) to satisfy ISI Progrmn requirements. See Attachment 1 for drawing list. D. Preparing / revising SON ISI Programs as required. E. Ensuring that these programs provide detailed irstructions for ISI including the following information b as a minimum: 1. The ASME Section XI Code of Record for ISI. 2. The inspection interval. 3. A list of the Section XI bounoary classification drawings (for ISI only). 4. A 110t of the ISI drawings. I 5. An examination schedule in tabular form and provide the 40-year sample, the 10-year interval sample, I and the samples for the threo perioda within the interval. 6. Augmented oramination requirements based on other codes / standards, regulatory guides, etc, 7. The NDE method to be used for each component. k .s 8. The ASME Section XI examination category fer each component. .3 g 9. Copies of all requests for relief. 10. Name and address of owner. 11. Name and address of generating plant. e 12. Name or number designation of the unit. w 13. Commercial operating date for the unit. 14. A description of the system for maintaining status of completed work. L ,1 f# U 1401C/COC3

Suodard %bert SI-114.3 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 10 of 125 15. Discussion of scan plans which provide details of required component examinations such as component identifier, NDE procedure, calibration block, drawing number, etc. F. Ensuring that Notification of Indication (NOI) Form is included as an appendix within ISI Programs. G. Preparing / revising component support tables, identifying each support, its types, and its operations characteristics. H. Providing PSI and/or ISI ASME Section XI interpretations as requested by various site organizations or as required in program development and implementation. I. ISI Programs shall be responsible for preparing and revising the initial piping component support examination boundaries, Appendix D. 5.1.2 ISI Programs PRISIM Responsibilitiest A. Providing a list of components requiring examination during each period of the 10-year interval that includes the components that muLt be examined during a specific refueling outage. This list will be provided to the i Site Quality Organization and the Inspection Services Organization in accordance with plant schedules. D. Providing any additional samples required due to examinations performed. C. Approving scan plans and revisions affecting component selection or the NDE method. ( 5.1.3 ISI Procrams Recuest for Relief Responsibilitigst i A. Determining if a request for relief is required because t of areas which are inaccessible or partially l} inaccessible for examination or because it is determined that conformance with ASME Code requirements is impractical. B. Ensuring that requests for relief include supporting Information on the need for relief and any alternate E examinations are documented. C. Submitting Requests for Relief to Site Licensing. 5.2 The Inspection Services Oraanization (ISO) 5.2.1 ISO Shell be Responsible for E A. Preparing / revising PRISIM data base to include all components within the ISI Program Instruction for SON. hA 40004 (NP 2N) a 1401C/COC3

Nisedstil Sht rt 1 f SI-114.3 aURVEILLANCE ASME SECTION X2 Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 11 of 125 g B. Preparing / revising scan plans for each refueling outage of an inspection interval utilizing PRISIM. C. Providing Level III approval of each scan plan revision and maintaining a scan plan revision history log. D. Submitting scan plans to the Site Quality organization in accordance with plant schedules. E. Any areas that are inaccessible or partially inaccessible for examination will be evaluated by NDE Level III examination personnel to determine if a request for relief should be submitted to the NRC. This information shall be provided to ISI Programs. b F. NDE Level III shall compare completed examination results to the requirements of the scan plan, identify any limitations or impractical examinations, and provide notification to ISI Programs for possible action in accordance with Section 19.0 of this program. 5.2.2 ISO Responsibilities When ND1_ Performed by Contractorst L A. Ensuring the adequacy of prospective contractor's QA programs in accordance with the TVA NQA Plan, k B. Ensuring the preservice and/or inservice examinations are performed in accordance with TVA NDE procedures or { performed in accordance with contractor procedures that have been authorized for use by ISO. C. Contract preparation, administration, and supervision will be the responsibility of 150. Inspection plans submitted by outside contractors shall be reviewed and approved by ISO prior to use. I 5.3 Ihe Site Ouality Orcanizetion (S00) 5.3.1 SOO Responsibilities on Scheduled Examinatioast Providing a list of the components to be scheduled for q examination during each refueling outage to the Inspection ] Services Organization. This will be provided in accordance with plant schedules. 5.3.2 SOO Responsibilities on Distribution of Sean Plang Submitting copies of the approved scan plan to site 1 management and to the authorized Nuclear Inservice Inspector (ANII). n b t l 1401C/COC3

w:d:,d swei 51-114.2 SURVEILLANC: : ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 12 of 125 5.3.3 SOO Responsibilitiea_on Performance of.NDE A. Performing HDE in accordance with ISI Program Instructions, applicable scan plan, and NDE procedures utilizing personnel certified in accordance with QMP-102.4. B. Ensuring that the services of an Authorised Inspection Agency (AIA) are used when performing Code-required examinations through a contract established with an AIA. Duties of the AIA inspector are described in IWA-2000, Section XI, of the ASME Code. C. Arranging for the AIA representative to have access to l' O any documents and all parts of the plant and offices (subject to plant security and health physics requirements) necessary for performing his required duties. D. Notifying the ANII prior to starting examinations. E. Preparing NOIs for examination results which, when evaluated by Level II or III examination personnel, do u, not meet the acceptance criteria of the NDE procedure. NOIs do not apply to PSI NDEs following repair and replacement activities. F. Ensuring that NOIs are forwarded to Plant Management as notification of discrepant conditions and for disposition. A copy is to be sent to ISI Programs. G. Ensuring that NOIs are closed by performing followup examinations as required by the disposition. H. Documenting follow-up examination by recording examination report number on NOI form prior to closure. I. Ensuring that original of the closed NOI la filed with the original examination report and a copy is sent to (, ISI Programs. J. Preparing examination report for completed examinations 4 in accordance with the format in the NDE procedure. 1. Ensuring that all scan plan examinations are completed prior to the completion of each refueling outage. 2. Ensuring that status of completed examinations are recorded in the scan plan. 3. Ensuring that report number, date of examination, ~ examiners initials and any comments or discrepancies (NOI number) are recorded in the scan plan. l VA 4Wo4 (Nr 191) 1401C/COC3

Swodne %bett SI-114.3 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 13 of 125 a 4. Submitting the original examination reports to DCRH as QA records. K. Ensuring that ISI Programs is notified of any areas that are inaccessible or partially inaccessible for examination. This information vill be evaluated by Level III examination personnel to determine If a request for relief should be submitted to the NRC. This information shall be provided to ISI Programs Supervisor. L. An NDE Level II or III Individual shall evaluate the NDE results in accordance with ASME Section XI, IWA-3000. The results shall be compared with recorded results of the preservice NLE and previous inservice NDE results. 5.3.4 EQ.0 Responsib1Ilties on Reports: A. Preparing ISI Summary Report including Form NIS-1 in accordance with requirements of ASME Section XI IWA-0000. B. Ensurir7 that Form NIS-1 is signed by the ANII. C. Submitting Inservice Inspection Summary Report within 90 days of the completion of the inservice inspection (refueling outage) to Site Licensing. D. Completing the Site Final Report cover sheet in Appendir B following each refueling outage when Inservice examinations are performed. E. Submitting the Final Report which contains the Summary Report to DCRM as a OA record. i; 5.3.5 500 Responsib1Ilties When NDE Performed hv Contractors: fj{ A. Ensuring that contractors are familiar with the ISI t' Program Instruction being used. B. Ensuring contractors are certified using guidelines of L, OMP-102.4. C. Maintaining surveillance of contractor ISI or PSI activities to verify compliance with the contract and applicable ISI Program Instruction requirements. e 7-5.3.6 SOO Responsibilities With PSI Conducted in Manufactuttr's Ehns ~ 1 The 500 is responsible for ensuring records are identified and documented as are TVA-generated reports in accordance with this instruction. Other report formats may be utilized provided the minimum required information is contained therein. 1 f^ # "#

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kaadud Shtcl i SI-114.3 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 14 of 125 5.3.7 EOO Resp 2nsibilities for Component. Support Banndaries u. The S00 shall be responsible for determining the ernmination beundary for new or modified supports. 5.4 Elte Docurint Control and Records Management (DCRM1 DCRM shall be responsible for issuing controlled copies of ASME Section XI Code Classification Drawings and ISI Drawings to specified distribution lists. DCRM shall be responsible for providing controlled copies of ISI Program instructions to SQO, the Authorized Nuclear Inspection / Authorized Nuclear Inservice Inspector (ANI/ANII), ISI Programs Supervisor, and to the Site Licensing Manager as requested. 5.5 Steam Genentor Maintenance and Tgshnolocy SGMT shall be responsibic f or ensuring the adequacy of the technical and administrative requirements related to steam generator tubing contained in Sections 7.3.8, 20.4, 20.6, and 20.13. SGMT is responsible for the selection of steam generator tubes to be examined for Section XI credit. 5.6 Site Licensine Manaaer Site Licensing Manager is responsible for submitting ISI Program Instruction, revision, requests for relief and reports to the NRC for review and/or approval. All ASME Section XI correspondence t shall include ISI Programs on distribution. ([ 5.7 Plant.. Manager Plant Manger is responsible for approving and issuing SI-114.2. \\ The Plant Manager is responsible for designating the organization responsible for preparing dispositions for NOIs. L I S.8 Elig Encineering Site Engineering is responsible for designing, fabricating, erecting, and constructing all structures, systems, and components to quality standards commensurate with the importance of the safety function to be performed. Design for access in accordance with the ASME Code, Section XI, must be satisfied. p Site Engineering is responsible for evaluating and providing a disposition for indications initiated by a Notification of Indication (NOI). h1 l ]VA 40W4 (NP 190 1401C/COC3

.%ued.rd Meet SI-114.2 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 15 of 125 5.9 PSI Conducted in Manufacturer's Shop If examinations were performed in the manufacturer's shop, they may serve as PSI examinations provided: A. They were performed after hydrostatic test of vessels. B. They were conducted under conditions and with methods expected to be employed for subsequent ISI examinations. 5.10 Ienlementatl2D ISI Programs, ISO, and 500 utilize a computerized data base system, PRISIM, for status and Section XI credit of completed ISI examinations. PRISIM data base is utilized to provide a listing of r p, components requiring examination during the 10-year ISI interval, t each period and scan plans for a specific refueling outage. All specific FDE procedures used during the inspection program shall be reviewed and approved in accordance with the NDE Procedures Manual, QMP-110.5. NDE procedures will be implemented in accordance with SSP 3.1. Whenever an unacceptable indication is discovered, Section 17.0 of this procedure and the form in Appendix C shall be utilized. In those cases where an outside contractor is furnishing inservice examination services, the contractor will normally initiate the form in Appendix C under the supervision of the S00 ( Representative. See Section 17.0 of this program. \\ 5.11 Scan Plan The scan plan should include as a minimum references to components to be examined, methods of examinations, examination procedures, and calibration standards. Prior to performing examinations on a l system or component, the scan plan shall be approted by ISI Programs and an NDE Level III individual from ISO. ISO shall submit scan plans to S00 in accordance with plant schedules. S00 shall submit copies of the approved scan plan to Site Management 'j and to the Authorized Nuclear Inservice Inspector. When inservice examinations are implemented by lustructions other than this program 'e.g., maintenance instructions), copies of the instruction data sheets shall be submitted to S00 by the performing i organization to allow these examinations, if applicable, to be included in the reports discussed in Section 16.0. l During implementation phases (usually outage periods), it may become necessary to change the scan plan. Scan plan changes can be initiated by S00, ISO, and ISI Programs, or by other personnel involved with the implementation of the scan plan. All changes shall be coordinated with an S00 Representative and, as needed, with the appropriate plant planning and scheduling personnel for facilitating the use of supporting craft personnel. Revisions to 4 the scan plan shall be controlled in the same manner as the original. ISO shall maintain a scan plan revision history log. 'UA 4(@4 (NP 2S1) J 1401C/COC3 ~

m_ .~ %odard Sket SI-114.3 SURVEILLANCE ASME SECTION XI Revision 16 ) I'JSTRUCTION INSERVICE INSPECTION PROGRAM Page 16 of 125 However, interim working copies may be hand written to allow g, examinations to be performed before a formal revision is issued. These changes shall be approved by an ISI Programs Specialist and a NDE Level III. Both individuals shall aign and date all such changes. 5.12 Pipina Confiouration Chances When major portions of existing piping are replaced or whole new systems are added, a system walkdown should be performed by ISI Programs to identify the piping configuration, welds, and components that will be included in the inspection program. If variations in configuration are discovered or modifications (including additions and deletions), replacements, or repairs are made during the service life of the unit, these changes shall be marked on field corrected copies of the appropriate drawings. These fleid corrected copies shall be used in the performance of examinations. Copies of these field corrected drawings shall be transmitted to ISI Programs by SQO using a drawing transmittal form as in Appendix E of this program. A file and transmittal number log of the corrected drawings and transmittal forms shall be maintained by the 500 for future reference. ISI Programs shall be responsible for reviewing the proposed change, revising the drawings as necessary, and lasuing the revised drawing prior to the next refueling outage. The transmittal form shall be returned to the S00 after the referenced drawings have been revised by an ISI Programs representative. The ISO scan plan shall be revised as l necessary to reflect these field corrected drawings (interim l working drawings) and any PSI /ISI examinations performed due to these variations in configuration. ( 6.0 ABBREVIATIONS AND DEFINITIONS l 6.1 AIA - Authorized Inspection Agency. L; 6.2 AI - Authorized Inspector (may denote an ANI or ANII). 6.3 ANI - Authorized Nuclear Inspector. l 6.4 ANII - Authorized Nuclear Inservice Inspector. l 6.5 Type A Examination Boundary: The type of boundary to be used for I those supports that are attached to building floor, walls, ceiling, or embedded plate. 6.6 Type B Examination Boundary: The type of boundary to be used for those supports that are attached to another existing support. 6.7 Type C Examination Boundary: The type of boundary to be used for those supports that are attached to existing steel. 6.8 Type D Examination Boundary: The type of boundary to be used for J those supports that are attached to an intervening element. 1 ,fA 40@J (NP 2SO 1401C/COC3

tandard Stret 51-114.2 FURVEILLANCE ASMI SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 17 of 125 6.9 Notice of Indication (NOI) - A form used to report any discrepant conditions found during the performance of nondestructive examination. Used for ISI examinations only. 6.10 Scan Plan - A schedule of examinations required to be performed during a particular period of time. 6.11 NDE - Hondestructive Examination. 6.12 WR/WO - Work Request / Work Order. 6.13 PER - Problem Evaluation Report. 6.14 Program for ISI Data Management (PRISIM) - a mainframe computer program for scheduling, tracking, maintaining status, and reporting of ISI examinations performed on a site / unit basis. It has the capability to allow categorization of these examinations by areas as needed for Code credit, NUREG credit, additional exam credit, augmented credit, etc. 6.15 Components - Denotes items in a power plant such as vessels, t iping systems, pumps, valves, and component supports. 6.16 Normal Operation - Normal plant operation conditions include recct.r startup, operation at power, hot standby, and reactor cooldown to cold shutdown conditions. Test conditions are excluded. 6.17 Pressure-Retaining Material - Applies to items such as vessel heads, nozzles, pipes, tubes, fittings, valve bodies, bonnets, ( disks, pump casings, covers, and boltings which join pressure-setaining items. 6.18 Repair - Those operations involving welding, heat treatment, or defect removal which are required to restore an item to a safe and satisfactory operating condition. 6.19 Replacement - Replacements include spare and renewal components, or parts of a component (e.g., valve body bonnet, disc, bolting). It also includes the addition of components such as valves and system lj changes such as rerouting of piping. For the purpose of this procedure, the term replacement shall apply where attachment to the pressure boundary is by welding or mechanical means. 6.20 FIR - Finding Identification Report. 6.21 SCAR - Significant Corrective Action Report. 6.22 Examination - Denotes the performance of all visual observation and nondestructive examination. 6.23 Inservice Inspection (ISI) - Ins; oh required by ASME Section XI during the service lifetime of the power unit. U 'l ) jA JMC4 (NP 290 1401C/COC3 l \\

Standa J Sherl SZ-114.3 SURVEZLLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 18 of 125 6.24 Nondestructive Examination (NDE) - Methods used for the detection 3 and evaluation of discontinuities and the measurement of physical dimensions and condition of items. These methods include radiography, ultrasonic, eddy current, 11guld penetrant, magnetic particle, inservice visual, and welding visial. These methods do not impair the serviceability of the items. 6.25 Preservice Inspection (PSI) - Inspections required by ASME Section XI to be completed prior to initial plant startup, or inspections required by ASME Section XI if a component is replace, added, repaired, or altered during the service lifetime of a power unit. 7.0 COMPONENTS SHI! JECT TO EXAMINATION--ASME CODE CLASS 1 (EQHlyJJ,Elgl r The ASME Code Class 1 (equivalent) components to be examined during the inspection interval are outlined in the following paragraphs. The entire length of each weld described shall be examined for the first 10-year ISI Interval unless otherwise noted. When a portion of a weld length is to be examined during an inspection period, the areas examined each i inspection period shall be documented on the examination data sheets. g, Components exempted f rom examination are discussed in Section 7.7 of this program. Appendix A, Table A, provid' additional information such as reference drawing numbers and ASME Section XI, Table IWB-2500-1, examination categories. 7.1 Egutqtor Vessel 7.1.1 Reactor Vessel Seam Welds 7.1.1.* Circumferential Shell Welds [ There are four circumferential welds (each i approximately 50 feet in length) in the vessel cylindrical shell, three of which are located i behind the thermal shleid. The entire length of ( each of these welds will be ultrasonically examined during the third inspection period using remote inspection devices from the vessel ID with the core internals removed. The vessel shell sections are machined forgings fabricated of A-508, Class 2, manganese-molybdenum steel and are clad with weld deposited austenitic w stainless steel. r 7.1.1.2 L2ngitudinal Shell Welda There are no longitudinal shell welds associated with the reactor vessel. . t v4 4Mv4 (NP :so 1401C/COC3

su:ard sheer SI-114.2 i SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 19 of 125 7.1.1.3 Closure Head circumferential Wgld The entire length of the closure head cap weld (approximately 41 feet in length) will be manually ultrasonically examined from the head outside diameter. The length of weld to be examined each Inspection period is included in Table A of Appendix A. The closure head ring is fabricated of A-508, Class 2, manganese-molybdenum steel. The closure head hemispherical section is fabricated of A-533, Gr. B, Class 1, manganese-molybdenum steel. Both sections are clad with weld deposited austenitic stainless steel. 7.1.1.4 Lower-Head Circumferentiel Weld f' The entire length of the lower head circumferential weld (approximately 38 feet in length) will be ultrasonically examined during the third inspection period using remote inspection devices from the k vessel inside diameter with the core internals removed (see Request for Relief ISI-5). f The lower-head sections are fabricated of A-533, Gr. B, Class 1, manganese-molybdenum. seal, and are clad with weld deposited austenitic stainle steel. 7.1.1.5 Closure Head Meridional Weld y The closure head does not include any meridional welds. J 7.1.1.6 Lower-Head _ Meridional Welds 1 ij There are six meridional welds (each approximately 4 feet in length) located in the lower head. The entire length of each of these welds will be ultrasonically examined during the third inspection period using remote inspection devices from the vessel inside diameter with the core internals removed. The lower-head section material is fabricated of A-533, Gr. B, Class 1, manganese-molybdenum steel and clad with weld deposited austenitic stainless y steel. 7.1.1.7 Shell-to-Flagge Weld The entire length of the shell-to-flange weld l (approximately 50 feet in length) will be l d ultrasonically examined from the vessel inside I y 'A 4mm4 (NP 2f>O 1401C/COC3

Stardad Sheet J SI-114.2 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 20 of 125 diameter using remote inspection devices during the third inspection period (see Request for Relief ISI-10). j 1 The vessel flange section is fabricated of A-508, Class 2, manganese-molybdenum steel and is clad internally and on the gasket face with weld deposited austenitic stainless steel. 7.1.1.8 Closure Head-to-Flance Held and Flex Area The entire length of the head-to-flange weld (approximately 45 feet in length) will be manually, ultrasonically examined from the head outside diameter. The entire length of the closure M4 head-flex area will be surface examined during the inspection intervt.1. The length of weld to be examined ea:h inspection period is included in Table A of Appendix A (see Request for Relief ISI-18). i The closure head flange section is fabricated of ( A-508, Class 2, manganese-molybdenum steel and is clad internally and on the gasket face with veld deposited austenitic stainless steel. 7.1.1.9 Reonir Welds Base metal weld repairs in the beltline region [ where the repair depth exceeds 10 percent nominal of the vessel wall shall be ultrasonicelly examined. There are no base metal repair welds in the beltline region of the Unit 2 reactor vessel. 7.1.2 Reactor Vessel Nozzle-to-Vessel Welds There are four inlet nozzles (27.500 inch ID) and four outlet nozzles (29.937-inch ID). The eight nozzle-to-vessel welds will be ultrasonically examined from the inside diameter using remote inspection devices. The four outlet nozzle-to-vessel welds shall be ultrasonically examined from the nozzle bore when the upper internals are-removed during the first inspection period. The inlet nozzles are not accessible until the core barrel is removed. The four inlet nozzle-to-vessel welds shall be ultrasonically examined from the nozzle bore and from the vessel shell inside diameter during the third inspection period when the core barrel has been removed. The outlet nozzle-to-vessel welds shall also be ultrasonically examined from the vessel shell inside diameter during the third inspection period when the core barrel has been removed. (A proposed examination schedule change has been submitted to NRC in accordance with Request for Relief ISI-15.) 't .k*^ d"*' WP 2* O 1401C/COC3

Stardard Meet l SI-114.2 SURVEILLANCE ASHE SECTION XI Rovision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 21 of 125 The nozzle forgings are fabricated of A-508, .as 2, manganese-molybdenum steel and are clad with ;14 deposited austenitic stainless steel. 7.1.3 Reactor Vesagl Nozzle Inside P.edius Section The eight nozzle inside radius sections (including thw outlet nozzle integral extensions) shall be ultrasonically examined at the same time as the examination of the nozzle-to-vessel welds (see Section 7.1.2). Nozzle forging material is identified in Section 7.1.2 of this program. 7.1.4 Reactor Vessel Partial Penetration Welda The vessel includes 4 Upper Head Injection (UHI) nozzles (capped in Unit 2 Cycle 4 UHI removal), 1 vent pipe nozzle, 78 control rod drive nozzles, and 58 instrumentation nozzles with partial penetration welds. Approximately 25 percent of each group of nozzles shall be visually examincd from the vessel outside diameter in accordance with visual examination method VT-2. This 25 percent shall include 1 upper head injection nozzle, 1 vent pipe nozzle, 20 control rod drive nozzles, and 15 instrumentation nozzles. Examination of these nozzles during the inspection interval shall be distributed among the inspection periods in accordance with Table A of Appendix A. { 7.1.5 Reactor vessel Ngizle-to-Safe Eqi Weld 1 The inlet and outlet nozzle-to-safe end welds shall be ultrasonically examined from the inside diameter using remote inspection devices. The ultrasonic examination shall be performed at the same time as the examination of the nozzle-to-vessel welds conducted f rom the nozzle bore (see ,} Section 7.1.2). w All of the nozzle-to-safe end welds shall also be liquid penetrant examined during the inspection interval coincident with the ultrasonic examinations. The SQN Unit 2 Report- " Evaluation of Cracking in Reactor Vessel Nozzle Stainless Steel Buttering"--states that Unit 2 nozzle-to-safe end welds 2-RC-17SE and 2-RC-24SE shall be examined during the first inspection interval (see j memorandum from D. W. Wilson to H. L. Abercrombie, dated j August 1, 1986 (L18 860730 899)). The rechining nozzles will be examined during the normal ISI intervals. Each nozzle safe end weld is a stainless steel type 304 weld build up (buttering). VA 40W4 (NP 290 1401C/COC3

- _ ~ _ _. Sund,td Sheet SI-114.2 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 22 of 125 7.1.6 Reactor Vessel Pressure Retalnino Bolting _ Larger Than Two Inches In Diameter During each refueling outage all closure studs, nuts, and washers are removed. All of the 54 closure studs, nuts, washers, and ligaments between the vessel flange stud holes shall be examined during the inspection interval in accordance with Table A of Appendix A. The closure nuts shall be magnetic particle examined. The closure studs shall be ultrasonically and magnetic particle examined. The ligaments between the vessel flange stud holes shall be ultrasonically examined. The closure washers shall be i i visually examined in accordance with visual examination method VT-1. The bolting may be examined either (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed. 't Provisions for this examination are included in 0-MI-MRR-068-005.0. Where needed the examinations of the studs should be identified with the particular stud in accordance with the unique identification system for the studs and nuts. L The 7-inch diameter studs, nuts, and washers are fabricated of SA-540, Gr. B23 Nickel, chrome-molybdenum steel. 7.1.7 Reactor Vessel Pressure Retainino Boltino Two Inches And Smaller In Diameter l 4 There is no pressure retaining bolting two inches or smaller in diameter. 7.1.8 Reactor Vessel Inteorally welded Attachments There are no integrally welded vessel supports. 7.1.9 Reactor Vess31 Interior The vessel interior shall be visually examined in accordance with visual examination method VT-3. These examinations shall include the space above and below the reactor core that is made accessible for examination by removal of congonents during normal refueling outages. The examinations shall be performed at the first refueling outage and subsequent refueling outages at approximately three-year intervals. 7.1.10 Reactor Vessel Removable Core Support Structures The visually accessible attachment welds and visually accessible surfaces of the core support structure shall be visually examined in accordance with visual examination method VT-3. This examination may be deferred to the third 1 JVA 40mM (NP 190 1401C/CQC3

Sundosd SBres SI-114.3 ~~ SURVEILLANCE ASME SECTION XI Revision '6 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 23 of 125 inspection period. The structure shall be removed from the I y, reactor vessel for examination. The removal of the core support structure is implemented by MI-1.4. 7.1.11 Reactor Vessel Control Rod Drive Housinca There are 78 control rod drive housings penetrating the closure head. Each housing includes a pressure retaining dissimilar metal butt weld. There are 20 peripheral control rod drive housings. Two (10 percent) of the peripheral housing butt welds shall be ultrasonically examined during the inspection interval in accordance with Table A of Appendix A. The housings consist of a 6-inch OD adapter of A-182, 304SS and a 4-inch OD body Ki of SD-167. 7.1.12 Reactor Vessel Auxiliary HenLMsg Each of the four auxiliary head adapters includes a pressure retaining dissimilar metal weld. The four dissimilar metal i~ welds shall be ultrasonically and liquid penetrant examined during the inspection interval in accordance with Table A of Appendix A. The adapters consist of a SA-182, 304SS upper portion and a SB-166 lower portion. See Section 7.4.4.6 for information on RV auxiliary head adapter circumferential pipe cap welds. The pipe cap welds are included in the reactor [ coolant system. 7.2 Pressurizer 7.2.1 Pressurizer Circumferential Shell-to-Head Welds There are two circumferential shell-to-head welds, each L approximately 24 feet in length. The entire length of each veld shall be ultrasonically examined during the inspection [ interval in accordance with Table A of Appendix A. l All vessel shell and head sections are fabricated of SA-533, Class 2, manganese-molybdenum steel and are clad with austenitic stainless steel. 7.2.2 Pressurizer Lonaltudinsi Shell-to-Head Welds {lI L There is one longitudinal weld intersecting each circumferential shell-to-head weld. One fo t of each longitudinal weld shall be ultrasonically examined during the inspection periods in accordance with Table A cf Appendix A. The one foot of weld er: mined during each examination shall include the length of weld as measured from the point of intersection of the longitudinal weld with the circumferential head-to-sht01 weld. [a ,} V^ 4M*4 (NP l*I) 1401C/COC3

$tseJuJ Sheet SI-114.1 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 24 of 125 The vessel shell section material is identified in Section 7.2.1. 7.2.3 Pressutiler Circunferential and MeridiangLJieed Hel43 There are no pressurizer circumferential or meridional head welds. 7.2.4 Pressurizer N21219-to-VesitLWfelds and Nazzle Inside Radlug Secti.gn The pressurizer includes three 6-inch safety valve nozzles, one 6-inch relief valve nozzle, one 4-inch spray nozzle, and one 14-inch surge nozzle. All of the nozzlo-to-vessel welds, including nozzle inside radius section, shall be i ultrasonically examined during the inspection interval in accordance with Table A of Appendix A. The nozzles are f abricated of SA-508, Class 2, manganese-molybdenum steel. 7.2.5 Pressurizer Heater Penetration Helda There are 78 heater penetration welds located in the pressurizer lower head. Approximately 25 percent of the heater penetration welds (20 welds) shall be visually examined during the inspection interval in accordance with visual examination method VT-2. Examination of these penetrations during the inspection interval shall be distributed among the inspection periods in accordance with Table A of Appendix A. 1 7.2.6 Er.gssurizer Nozzle-to-Safe End Welds Each of the six nozzles identified in Section 7.2.4 includes a welded forging safe end. All of the nozzle-to-safe end welds shall be ultrasonically and liquid penetrant examined during the inspection interval in accordance with Table A of Appendix A. Safe end connections are SA-182, Gr. F-316L forgings. 7.2.7 Pressurizer Pressure Eg.t11ning._Roltino Larcer Than Two . Inches In Diameter There is no pressure retaining bolting larger than 2 inches in diameter. 7.2.8 Pressurizer Pressure Retainino Boltina Tw? Inches And Smaller In Dieseter ~ All of the pressurizer manway bolts shall be visually examined in accordance with visual examination method VT-1. The examinations during the inspec".lon interval shall be in accordanco with Table A of Appendix A. The bolts may be 1 I _f^'**"#2*) 1401C/COC3

y 4@kY s,..w su v SI-ll4.2 SURVEILLANCE ASME SECTION XI Revision 16 i n INSTRUCTION INSERVICE INSPECTION PROGRAM Page 25 of 125 (, I ~ examined in place under tension or when the bolts are removed. It is preferable to perform the examinations when the bolts are removed if possible. Removal of the manway cover is performed in accordance with 0-MI-MXX-068-004.0 and provides for examination of bolting. The manway includes 16 bolts at 1.88 inches in diameter. 7.2.9 htalurizer Inteorally Welded SupplLt_h11AChmtD13 7.2.9.1 hessurizer Support Skirt The entire length of the pressurizer support skirt-to-vessel weld (approximately 23 feet in length) shall be surface examined (magnetic r particle) during the inspection interval in accordance with Table A of Appendix A. The support skirt is approximately 1.5 inches thick and is fabricated of SA-516, Gr, 70, carbon steel plate. 7.2.9.2 Pressurizer Seismic Lugs There are four (4) integrally welded seismic lugs { on the pressurizer, whose design base thickness is i greater than 5/8 inch. All four (4) lugs shall be surface examined during the inspection interval in r accordance with Table A of Appendix A. \\~ 7.3 Steam Generator:Liil 7.3.1 Steam Generator Primary Side Circumferential And Meridienttl Head Welds There are no steam generator primary side circumferential or meridional head welds. 7.3.2 Steam Generator Primary Tubeshttt-to-Head Weld Each steam generator includes a tubesheet-to-head weld (approximately 36 feet in length). The entire length of each weld shall be ultrasonically examined during the inspection interval. The entire length of a tubesheet-to-head weld shall be examined during the first and second inspection periods. The entire length of the two remaining welds shall be examined during the third inspection period. See Table A of Appendix A for examinations during the inspection interval. The tube plate is a SA-508, Class 2, steel forging, clad on the primary side with NiCrTe alloy. The hemispherical chamber is a SA-216, Gr. WCC casting, clad with austenitic stainless steel.

• 04 (Nr 2a;O 1401C/COC3

Sundssd Sheet SI-114.2 SURVEILLANCE ASME SECTION XI Ravision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 26 of 125 7.3.3 Steam Generator Primary Nozzle Inside Radius Section The steam generator primary nozzles are an integral part of the vessel. Each steam generator consists of two integrally cast nozzles. The nozzles are fabricated to SA-216, Gr. WCC. The primary nozzle inside radius section of all nozzles shall be ultrasonically examined. In accordance with the SON Unit 2 NRC Safety Evaluation Report [I dated February 7, 1991, Enclosure Paragraph 2.4 (page 6) stat?, "that delaying the volumetric examination of the nozzle sections until tne third inspection period of the first inspection interval and then following the Code j requirements is acceptable." See Request for Relief ISI-6. t i 7.3.4 Steam Generator Primary Nozzle-to-Safe End Welds p Each steam generator includes two nozzles with buttered safe ends. Each nozzle-to-safe end weld from each generator shall be ultrasonically and liquid penetrant examined during the inspection interval in accordance with Table A of Appendix A. The nozzles have buttered 308L safe ends. m 7.3.5 Eipam Generator Primary Pressure Retainino Bolting Larggr i Than Two Inches In Diameter There is no pressure retaining bolting larger than two inches in diameter. 7.3.6 Steam Generator Primary Pressure Retainino Boltino Two Inches And Smaller In Diameter Each steam generator includes two manways. Each manway f includes 16 connections at 1.88 inches in diameter. All

• r the manway bolting (all bolts, studs, and nuts) from each

] steam generator manway shall be visually examined in accordance with visual examination method VT-1. The examinations shall be distributed during the inspection l interval in accordance with Table A of Appendix A. J The bolting may be examined in place under tension or when they are removed. It is preferable to perform the examinations when the bolting is removed if possible. Removal of bolting is performed in accordance with 0-MI-MXX-068-003.0 and provides for examination of bolting. r L 7.3.7 Steam Generator Primary Inteorally Welded SuppoIt Attachments W There are no integrally welded vessel supports. The four main support pads are secured to the steam generator field support system by high strength bolts. ' 'A 4Mo4 (NP 191) 1401C/COC3 i l

Stasdard Shece SI-114.2 SURVEILLANCE ASME SECTION XI Rovision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 27 of 125 7.3.8 Steam Generator Tubing Steam Generator Maintenance and Technology (SGMT) shall be responsible for ensuring the adequacy of the technical and administrative requirements related to steam generator tubing contained in this program. Each steam generator tube bundle consists of 3,388 NiCrFe alloy (Inconel SB-163) U-tubes of 0.875 0.D. by 0.050 average wall thickness. During the inspection interval, steam generator tubing shall undergo eddy current examinations. Other NDE methode may be ut131 zed to improve characterization of an indication but eddy current shall be utilized to determine f' compliance with acceptance criteria. These examinations shall be performed in accordance with the SON Technical Specifications and satisfy Surveillance Requirement 4.4.5.0. The initial and additional samples (as required) identifying the steam generator tubes to be examined shall be supplied by SGMT for inclusion in the scan plan. The Steam Generator Maintenance and Technology Supervisor is responsible for the selection of steam generator tubes to be examined. 7.3.8.1 Steam Generator Sample Selection And Inspection Each steam generator shall be determined operable during the shutdown by selecting and inspecting at j least the minimum numbec of steam generators specified in Table 1 of Appendix A. 7.3.8.; Steam Generator Tube Seple Selection and Insreaction [C.2) The steam generator tube minimum sample size inspection result classification, and the l, corresponding action required shall be as specified in Table 2 of Appendix A. The ISI of j steam generator tubes shall be performed at the frequencies specified in Section 7.3.8.3, and the inspected tubes shall be verified acceptable per j the acceptance criteria of Section 7.3.8.4. The J full length of a minimum of S (as defined by Appendis A, Table 2) tubes selected for inspection will be examined [TVA commitment to NRC ~ L44 850617 801). Note that the hot leg inspection sample and the cold leg inspection sample do not necessarily involve the same tube, (i.e., it does not preclude making separate entries from tF-5 t and cold leg sides and selecting different t on the hot leg and cold leg sides to meet the } minimum sample). The tubes selected for each ISI J shall include at least 3 percent of the total YA m4 (NP 2NQ 1401C/COC3

_,.m Sand rd Shees SI-114 3 ~ SURVIILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 28 of 125 number of tubes in all steam generators; the tubes g, selected for these inspections shall be selected on a random basis excepts a. Where experience in similar plants with similar water chemistry indicates critical j areas to be inspected, then at least 1/2 S (as defined by Appendix A, Table 2) tubes inspected shall be from these critical areas. b. The first sample of tubes selected for each inspection (subsequent to the PSI) of each steam generator shall includes 1. All nonplugged tubes that previously had f-detectable wall penetrations greater than 20 percent. 2. Tubes in those areas where experience has indicated potential problems. 3. A tube inspection (pursuant to Section 7.3.8.4.a.8) shall be performed en ~ each selected tube. If any selected tube does not permit tne passage of the eddy j current probe for a tube inspection, this shall be evaluated and recorded and an adjacent tube shall be selected and l subjected to a tube inspection. I c. The tubes selected as the second and third samples (if required by Table 2 of Appendix A) {' during each ISI may be subjected to a partial tube inspection provided: f 1. The tubes selected for these samples L include the tubes from those areas of the [f tube sheet array where tubes with imperfections were previously found. .h 2. The inspections include those portions of the tubes where imperfections were previously found. d. The results of each sample inspection shall be l classified into one of the following three categories t .. i ,s f^ *** @# 1* O 1401C/COC3

Sund td Sket SI-114.2 SURVEILLANCE ASME SECTION XI Roviolon 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 29 of 125 i Catecory Inspection Results r-C-1 Less than 5 percent of the total tubes { inspected are degraded tubes and none i of the inspected tubes are defective. C-2 One or mere tubes, but not more than 1 percent of the total tubes inspected l are defective, or between 5 and 10 percent of the total tubes inspected are degraded tubes. C-3 More than 10 percent of the total tubes inspected are degraded tubes or more than 1 percent of the inspected tubes are defective. NOTE: In all inspections, previously degraded tubes must exhibit significant (10 percent) further wall penetrations to be included in the above percentage calculations. 7.3.8.3 Inspection Precuencies The above required ISIS of steam generators shall l, be performed at frequencies indicated in the following paragraphs and in such a manner that the maximum allowable time between eddy current inspections on individual steam generators is 72 months. I a. The first ISI shall be performed after 6 Effective Full Power Months but within 24 calendar months of initial criticality. Subsequent ISIS shall be performed at f; intervals of not less than 12 nor more than {j 24 calendar months after the previous inspection. If two consecutive inspections following service under All Volatile Treatment l ili conditions, not including the PSI, result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the j inspection interval may be extended to a maximum of once per 40 months. b. If the results of the ISI of a steam generator conducted in accordance with Table 2 of s Appendix A at 40-month intervals f all in Category C-3, the inspection frequency shall } be increased to at least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspections satisfy ( f^ *"*' @# 1'O 1401C/COC3

LaoJord Sheet SI-114.2 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 30 of 125 the criteria of section 7.3.8.3.a; the interval may then be extended to a maximum of once per 40 months. c. Additional, unscheduled ISIS shall be performed on each stoam generator in accordance with the first sample inspection specified in Table 2 of Appendix A during the shutdown subsequent to any of the following conditions. 1. Primary-to-secondary tubes leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Technical Specification 3.4.6.2. ~F 2. A seismic occurrence greater than the Operating Basis Earthquake. 3. A loss-of-coolant accident requiring actuation of the engineered safeguards. 4. A main steam line or feedwater line break. 7.3.8.4 Acceptance Criteria a. As used in Section 7.3.82 1. Imperfectins means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings f or specifications. Eddy-current testing { indications below 20 percent of the nominal tube wall thickness, if detectable, may be considered as f imperfections. L 2. Dearadation means a service-induced ( cracking, wastage, wear or general L corrosion occurring on either inside or outside of a tube. 3. Deoraded Tuhg means a tube containing imperfections greater than or equal to 20 d percent of the nominal wall thickness ~ caused by degradation. 4. Percent Decradatiom neans the percentage of the tube wall thickness affected or removed by degradation. h .m 5. Defect means an imperfection of such j} severity that it exceeds the plugging limit. A tube containing a defect is defective. f^ d*"* WP l'O 1401C/COC3

Stardzad Sheet SI-114.2 SURVEILLANCE ASME SECTION XI R:visien 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 31 of 125 =_ 6. Pluccina Limit means the imperfection depth at or beyond which the tube shall be removed from service because it may become unserviceable prior to the next inspection and is equal to 40 percent of the nominal tube wall thickness. 7. Un erviceablg describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolaat accident, or a steam line or feedwater line break as specified in Section 7.3.8.3.c. M 8. Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to tne point of exit (cold leg side) (i.e., tube end to tube end). Entries may be made from either the hot or cold leg sides and separate entries on the ~ hot leg and cold leg sides on different tubes are allowed. 9. Preservice Inspection (PSI) means a tube inspection of each steam generator tube ( performed by eddy current techniques prior {~ to service to establish a baseline condition of the tubing. This inspection shall be performed prior to initial power operation using the equipment and techniques expected to be used during subsequent ISIS. 1 k. b. The steam generator shall be determined operable after completing the corresponding actions (plug all tubes exceedirg the plugging i limit and all tubes containing through-wall cracks) required by Table 2 of Appendix A. 7.4 Elping All ASME Code Class 1 piping systems to be examined are fabricated I of stainless steel. The reactor coolant main loop piping straight L lengths are centrifugal cast and the elbows are static cast. The reactor vessel auxiliary head adapter is included in Sections 7.1.12 and 7.4.4.6. Specific material specifications for each piping system are included on the welt isometric. See Request for Relief ISI-3 for Class 1, longitudinal, circumferential, pipe branch connection velds, examination categories B-F and B-J, which ,j have interference problems for volumetric examination. a .m

- - _ -... -. -. ~. - . 5dahrJ Sheet .SI-114.2 ~ SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM-Page 32 of 125 .The following Class'1 piping systems are subject to examination: A Reactor Coolant Main Loop (RX) Other (RC) Chemical and Volume Control (CVC) -Residual Heat Removal (RHR) Safecy Injection (SI) Upper Head Injection (UHI) 1 The UHI System.wus temoved from service during Unit 2 Cycle 4. For reference to the ac$'A.le of excginations performed on this system, j see' revision 14 of '.wis instruction. Reference sections 7.1.12 and 7.4.4.6. @l;f! 7.4.1 Pipino Dissimilar Metal Welds There are no Class 1 dissimilar metal velds. 7.4.2 Pipino Pressure Retainino Boltino Larcer Than 2 Inches In D1amtar There is no piping pressure retalcing bolting larger than. 2 inches in diameter. 7.4.3 Pipino Pressure Retainino Baltino 2 Inches and Smaller in Diameter The following systems contain bolted piping flange 6 connections. All of the bolts or studs and nuts in each l flange connection shall be visually examined during the inspection interval in cecordance with visual examination method VT-1. The examinations shall be distributed during the inspection interval in accordance with Table A of Appendix A. I The bolting may be examined in place under tension or when a the bolting is removed. 7.4.3.1 Reactor Coolant System Ploino Bolting -The Reactor Coolant System piping includes bolted flange connections. w 7.4.3.2 Chemical and Volume Centrol Svstem Pipino Bolting The Chemical and Volume Control System (seal water y injection) piping includes bolted flange connections. ~ 7.4.3.3 RHR System Pipino Boltinc The RHR System piping does not include any bolted connections. 1vA 4mma pe 2m) 401C/COC3

NaaderJ ShecI SI-114.2 SURVEILLANCE ASME SECTION XI Revision 16 INSTRDCTION INSERVICE INSPECTION PROGRAM Page 33 of 125 7.4.3.4 Safety Iniection System Pipina Bolting The Safety Injection System piping includes bolted flange connections. 7.4.4 Circumferential and_ Longitudinal Picina Welds All Class 1 piping is seamless. Circumferential pipe welds four inches and greater nominal pipe size selected for examination shall be ultrasonically and 11guld penetrant examined. Circumferential pipe welds less than 4-inch nominal pipe size selected for examination shall be liquid penetrant examined. The examinations performed during the inspection interval shall include approximately 25 percent of the 40-year sample of circumferential welds. The examinations shall be distributed during the inspection interval in accordance with Table A of Appendix A. 7.4.4.1 Reactor Coolant System Main Looo Ploing Circumferential Welds The Reactor Coolant System hain Loop piping includes circumferential pipe welds 4 inches and [ greater nominal pipe size. The welds selected for examination shall be ultrasonically and liquid penetrant examined durin the inspoction interval } in accordance with Table A of Appendix A. There are no Class 1 pipe welds less than 4-inch nominal I. pipe size in the Reactor Coolant System Main Loop f piping. Two circumferential welds in the Reactor Coolant Main Loop piping, RC-23S1 (Loop 31 and RC-31S1 (Loop 4) are located inside the reactor vessel shield wall and are inaccensible for (, examination. See Request for Relief ISI-7. 7.4.4.2 Reactor Coolant System Ploinc Circumferential Welds I Reactor Coolant System piping includes g circumferential pipe welds 4 inches and greater nominal pipe size. The welds selected for examination shall be ultrasonically and liquid penetrant examined during the inspection interval in accordance with Table A of Appendix A. There are pipe welds less than 4-inch nominal pipe size. The welds selected for examination shall be liquid penetrant examined during the inspection interval in accordance with Table A of Appendix A. 1 .J l ! '^ 4*m4 (NP 290 1401C/COC3 l

Staettd Sheet 5I-114.2 SURVEILLANCE ASME SECTION XI Ravision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 34 of 125 7.4.4.3 Chemleal and volume Control Systen Ploina _,i circumferential Welds The Chemical and Volume Control System piping (including seal water injection) includes circumferential welds less than 4-inch nominal pipe size. The welds selected for examination shall be liquid penetrant examined during the inspection interval in accordance with Table A of Appendix A. There are no Class. 1 pipe welds 4 inches and greater in the CVCS system. 7.4.4.4 RHR System Picing Circumferential Welds The RHR System piping includes circumferential welds 4 inches and greater nominal pipe size. The welds selected for examination shall be ultrasonically and 11guld penetrant examined during the inspection interval in accordance with Table A of Appendix A. There are no Class 1 pipe welds less than 4-inch nominal pipe size in the RHR system. 7.4.4.5 Safety Injection System Ploino Circumfgrgntial W 141 _.9 The Safety Injection System piping includes circumferential pipe welds 4 inches and greater nominal pipe size. The wolds selected for examination shall be ultrasonically and liquid penctrant examined during the inspection interval in accordance with Table A of Appendix A. There are pipe welds less than 4-inch nominal pipe size. The velds selected for examination shall be 11guld penetrant examined during the inspection interval in accordance with Table A of Appendix A. 7.4.4.6 Reactor Vessel Auxiliary Head Adapter Cao Welds e ~ The graylock connectors were removed from service during Unit 2 Cycle 4 and replaced with welded pipe caps. One of these four circumferential pipe cap welds (= 5.5 in.) shs11 be ultrasonically and liquid penetrant examined during the inspection interval in accordance with Section 7.4.4.2 of Table A of Appendix A. See Section 7.1.12 for information on reactor vessel auxiliary head aJapter dissimilar metal welds. 7.4.5 Branch Pipino Connection Welds The entire length of each branch pipe connection weld selected for examination shall be examined. Branch pipe J connection welds exceeding 2 inches nominal pipe size t l selected for examination shall be ultrasonically and liquid [*^ ""#

• " l' O 1401C/COC3

StasJstd Sheet SI-114.2 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INCERVICE INSPECTION FROGRAM Page 35 of 125 penetrant examined. Branch pipe connection welds 2 inches ~* nominal pipe size and smaller selected for examination shall be liquid penetrant examined. The examinations performed during the inspection interval shall include approximately 25 percent of the branch pipe connection welds. The examinations shall be distributed during the inspection interval in accordance with Table A of Appendix A. FOTE: In the case of branch pipe connections 2 inches nominal pipe size and smaller, the welds of all the systems affected have been combined and shall be evenly distributed over the four inspection intervals. 'p 7.4.5.1 Reactor Coolant System Main L220 Branch Pipg Canpection Welfa The Reactor Coolant System Main Loop piping includes a branch pipe connection weld exceeding 2 inches nominal pipe size. This weld shall be ultrasonically and liquid penetrant examinea during the inspection interval in accordance with Table A of Appendix A. There are branch pipe connection welds 2 inches nominal pipe size and smaller. The welds selected for examination shall be liquid penetrant examined during the inspection interval in accordance with Table A of Appendix A. I NOTE: Each of these brar9h pipe connections 2 inches nominal pipe size and smaller has a special boss. This is a special boss for use with temperature elements with an outside diameter (OD) of 0.875 inch. The i special boss has an OD = 2 1/2 inches [ 1.01 inch with an inside diameter (ID) of 0.9 inch reamed to provide 0.015 inch - 0.020 inch clearance with 0.010 inch misalignment. Assuming the worst I* possible case (the weld to pipe fails), the largest hole is that for a 2-inch pipe } (any schedule). Therefore, it shall be ,j treated as a 2-inch branch pipe for ASME Section XI purposes. See contract 68C60-91934, (N2M-2-8) drawing nos. 205C470 and 206C471 and installation detail N2M-2-50. 7.4.5.2 Rgaetor Coolant System Branch Ploe Connection Welds The Reactor Coolant System piping 3ncludes branch '{ pipe connection welds exceeding 2 inches nominal J pipe size. The welds selected for examination shall be ultrasonically and liquid penetrant ^ " ' " U 1401C/COC3

~~- - -. -. _ - -.. -.~.. - - _ - Stardud Sheet -SI-114.2 SURVEILLANCE ASME SECTION.XI Revision 16 INSTRUCTION -INSERVICE INSPECTION PROGRAM Page 36 of 125 hk examined during the inspection interval,in accordance with Table"A of Appendix A. There are-branch pipe. connection welds 2 inches. nominal pipe size and smaller. The welds selected for examination shall be liquid penetrant examined i during the inspection interval'in accordance with Table A of Appendix'A. -p.. 7.4.5.3 Chemical and Vo'ume Control System Branch Pipe 1 l L. Cnspection Welds The_ Chemical and Volume Control System piping Includes branch pipe connection welds exceeding 2 inches nominal pipe _ size. The welds selected for examination shall be ultrasonically and liquid ^ f penetrant examined during the inspection interval in accordance with Table A of Appendix A. ~ There is a branch pipe connection weld 2 inches nominal pipe size and smaller. This weld is not scheduled for examination this interval. When this wold is selected for examination it shall be -11guld penetrant examined. ~ 7.4.5.4-RHR' System Branch Pipe Connection Welds I The RER System piping includes branch pipe connection welds exceeding 2 inches nominal pipe size. The welds selected for examination.shall be [~ ultrasonically and liquid penetrant examined during the inspection interval in accordance with

I-Table A of Appendix A.

There are branch pipe connection welds 2 inches nominal pipe size and smaller.in the RER System. These1 welds are not scheduled for examination this interval. When. these welds are' selected for examination they shall be liquid penetrant examined. 7 7.4.5.5 Safety Iniection System Branch Pipe Connection ( FJtida The Safety Injection System piping includes branch pipe connection welds exceeding 2 inches nominal i-pipe size. The welds selected for examination shall be ultrasonically and liquid penetrant ~ (( examined during the inspection interval in [ accordance with Table A of Appendix A. There are t branch pipe connection welds 2 inches nominal ' pipe size and smaller. The welds selected for I examination shall be 11guld penetrant examined during the inspection interval in accordance with Table A of Appendix A. l-I l~- [v4 4mma (Nr z90 l g 14DIC/COC3

SueJ4rd Sheet SI-114.2 SURVEILLANCE ASME SECTION XI Ravision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 37 of 125 7.4.6 Eining Socket Welds The entire length of each socket weld selected for examination shall be liquid penetrant examined. The examinations performed during the inspection interval shall include approximate?; 25 percent of the ancket welds. The examinations snall be distributeo during the inspection interval in accordance with Table A of Appendix A. 7.4.6.1 Reactor Coolant System Piping Socket Welds The Reactor Coolant System piping includes socket welds. The welds selected for examination shall r be examined during the inspection interval in accordance with Table A of Appendix A. 7.4.6.2 Chemical and Volume Control System Ploino Socket Welds The Chemical and Volume Control System piping includes socket welds. The welds selected for examination shall be examined during the inspection interval in accordance with Table A of Appendix A. 7.4.6.3 RHR System Pipino Socket Welds The RHR System piping includes socket welds. The velds selected for examination shall be examined 7 during the inspection interval in accordance with Table A of Appendix A. 7.4.6.4 Safety Iniection System Piping Socket Welds L The Safety Injection System piping includes socket welds. The welds selected for examination shall be examined during the inspection interval in accordance with Table A of Appendix A. 7.4.7 Pipinn and Valve Inteorallv Welded Support Members k 13 Integrally welded support members include the support attachments of piping required to be examined by Examination Category B-J. Included are those supports j which have attachment velds to the valve and piping pressure retaining boundary and those attachments whose suoport base material design thickness is 5/8 inch and greater. The entire length of each support attachment weld selected for examination shall be surface examined. 1 VA 4NM4 (NP 191)

sueduo sheet SI-114.2 ~ SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 38 of 125 The examinations performed during the inspection interval shall include 100 perceut of the integrally welded support members. The examinations shall be distributed during the inspection interval in accordance with Table A of Appendix A. 7.4.7.1 Reactor Coolant System Plo!no and Valve Inteorall_v Welded Support Members The Reactor Coolant System piping includes integrally welded support members. All of these shall be examined during the inspection interval in accordance with Table A of Appendix A. 7.4.7.2 Chemical and Volume Control System Ploino and Valve Inteorally Welded Support Members The Chemical and Volume Control System piping includes an integrally welded support member. This support shall be examined during the inspection interval in accordance with Table A of Appendix A. 7.4.7.3 RHR System Pipino and Valve Intecrally Welded Support Members The RER System piping includes integrally welded support members. All of these supports shall be examined during the inspection interval in accordance with Table A of Appendix A. 7.4.7.4 Safety Iniection System Pipino and Valve Integrally Welded Support Members The Safety Injection System piping includes [ integrally welded support members. All of these L shall be examined during the inspection interval in accordance with Table A of Appendix A. Integrally welded support 2-SIH-20-IA was evaluated during the second period to require a reexamination for the next three periods per INB-2420. This w113 require the integral attachment to be examined in the third period of the first interval and the first two periods in f the second interval (see Table D of Appendly A). l (See Section 7.8.) 7.4.8 Pipino and Valve Component Euoports All piping and valve component supports of piping required to be examined by Examination Category B-J shall be visually examined during the inspection interval in accordance with visual examination methods VT-3 and VT-4 as applicable. This examination includes integrally welded ]VA 4&N4 (NP 2Sy 1401C/COC3

Su2Jud Sket SI-114.2 SURVEILLANCE ASME SECTION XI Revision 16 ~ INSTRUCTION INSERVICE INSPECTION PROGRAM Page 39 of 125 and nonintegrally welded component suppcrts. Component 2, supports extend from the piping and valves up to and including the attachment to the supporting structure. The setting of snubbers, shock absorbers, and spring-type hangers shall be verified in accordance with the applicable NDE procedure with the acceptance criteria identified in the Scan Plan (see PRISIM data base) or the applicable work instruction. For reference the acceptance ranges are listed in the component support acceptance range drawings in Attachment 1. The examinations shall be distributed during the inspection interval in accordance with Table A of Appendix A. 7.4.8.1 Reactor Coolant System Piping and Valve Component Supports The Reactor Coolant System piping includes component supports. All of these shall be examined during the inspection interr.1 in accordance with Table A of Appendix A. 7.4.8.2 Chemical and Volume Control System Pipino and Valve Component Supports The Chemical and Volume Control System piping inc1vdes componert supports. All of these shall be exaained during the inspection interval in accordance with Table A of Appendix A. 7.4.8.3 RRR System Pipino and Valve Component Supports 1 The RER System piping includes component supports. All of these shall be examined during j the inspection interval in accordance with Table A .) of Appendix A. 7.4.8.4 Safety Injection System Pipino and Valve Component { Supports The Safety Injection System piping includes component supports. All of these shall be examined during the inspection interval in a accordance with Table A of Appendix A. e 7.4.8.5 Reactor Coolant System Main Loop Pipino and Valve l Component Supports j The Reactor Coolant System Main Loop Piping l includes component supports. All of these shall l be examined during the inspection interval in accordance with Table A of Appendix A. ~ l yA dmW4 (NP 191) 1401C/COC3 y 1

sunwa swei SI-114.2 p SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 40 of 125 6 7.5 Reactor Coolant Pumos (4) - RCP 7.5.1 BCP Pressure Retainino Boltino Larger Than Two Inches In Dianetir The main flange on each pump includes 24 bolts of 4-1/2 inches in diameter and 30-1/2 inches in length. All of the bolts from each pump shall be ultrasonically examined during the inspection interval. Bolting may be examined either (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed. Flange ligaments between threaded bolt holes shall be b-visually examined (VT-1) once during the inspection interval if the conneccion is disassembled at any time during the inspection interval. If the bolts are removed at any time during the inspection interval, each bolt shall be magnetic particle (MT) examined and all threads in the base material shall be visually examined (VT-1) once during the inspection interval. This examination may be deferred until the end of the interval. The main flange bolts are fabricated of 4340 steel, heat treated to A-540, GR. 24. Provisions for this examination are included in MI-2.2. 7.5.2 RCP Pressure Retainino Boltino 2 Inches and Smaller in Qiameter ~ Each RCP includes two sets of pressure retaining bolting 2 inches and smaller in diameter. The bolting sets include the number 1 seal housing and cartridge seal assembly bolting. The Number 1 seal housing and cartridge seal assembly bolting includes 12 HEX head cap screws at 2 -{ inches in diameter. The number 1 seal assembly bolting from sach pump shall be visually examined in accordance with visual examination method VT-1. The cartridge seal assembly bolting is Class 2 (8 socket head cap screws at 1.5 inches in diameter) and does not require examination (see memo to C. R. Brimer from 7. A. Bianco dated [ January 10, 1987, No. B25870109045). LI The bolting may be examined in place under tension or when r3 moved. It is preferable to perform the examinations when the bolts are removed if the connection (s) is disassembled. Removal of bolting is performed in accordance with MI-10.2.2 and MI-10.2.3 and provides for examination of bolting. ~ D'^ #"*4 U# 1* O 1401C/COC3

. _ - - _ _ - ~ SunJ5rd Sicet l SI-114.2 SURVEILLANCE .ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTIOF PROGRAM Page 41 of 125 f All of the bolting from one RCP shall be examined during the first inspection period, and all of the bolting from a i different pump shall be examined during the second inspection. period. All of the bolting from the remaining. two pumps shall be examined during the third inspection period. 7.5.3 RCP Inteorally Welded Support Members There are three Unit 2 reactor coolant pumps, serial numbers 566 (RCP-1 casing), 704 (RCP-3 casing), and 709 (RCP-4 casing), with integrally weJoed supports. Each pump ..has three integrally welded pump feet. These integrally welded pump feet whose design base is ) 5/8 of an inch shall be surface examined during the inspection interval in accordance with Table A of Appendix-A. The examination shall cover 100 percent of the required area of each support attachment. All of the supports from one RCP shall be examined during the first inspection period, and all of the supports from a different pump shall be examined during the second inspection period. All of the supports from the remaining pump shall be examined during the third inspection period. 7.5.4 RCP Component Suo_ ports Three of the RCPs have three cast feet integrally welded to the pump casing, the fourth pump has integrally cast feet. L' These feet are bolted to the support system. All component supports fiom each pump shall be visually examined during j the inspection interval in accordance with visual 7 -{ examination method VT-3 and Table A of Appendix A. Support components extend from the RCP to and including the l attachment to the supporting structure.- h All of_the supports from one RCP shall be examined during u-f the first inspection period,.and all of the supports from a rj different pump shall be examined during the second -j j inspection period. All of the supports from the remaining two pumps shall be examined during the third inspection

period, 7.5.5

'RCP Casino Welds a The Unit 2 RCPs pumps do not include casing welds, 4 b 7.5.6 RCP Casina If a pump is disassembled for maintenance during the inspection interval, the internal pressure boundary surfaces shall be visually examined in accordance with visual examination method VT-1. Disassembly of RCP's is performed in accordance with MI-2.2 and provides for these visual examinations. v4 40004 (Nr 290

l SI-114.2 SUPVEILLANCE ASME SECTION XI Rsvision 16 NSTRUCTION INSERVICE INSPECTION PROGRAM Page 42 of 125 If during the inspection interval a pump from either Unit 1 or Unit 2 is not disassembled for maintenance, a pump from one unit shall be examined from the exterior by ultrasonic thickness measurements (see Request for Relief ISI-1). 7.6 Valves A tabulation of valves is contained in Attachment 2. 7.6.1 Valve Pressure Retainino Boltino Larger Than 2 Inches in Di ameter There are no valves with pressure retaining bolting larger than 2 inches in diameter. 7.6.2 Valve Pressure Retaining Boltino 2 Inches and Smaller in Di amete r The following systems contain valves with bolted bonnet connections. All of the bolts or studs and nuts in each connection not excluded in accordance with Code Case N-426 1 shall be visually examined during the inspection interval in accordance with visual examination method VT-1. The '~ examinations shall be distributed during the inspection interval in accordance with Table A of Appendix A. The bolting may be examined in place under tension or when the bolting is removed. It is preferable to examine the bolting when removed if possible. Valve disassembly is ,[ performed in accordance with MI-6.15 and provides for examination of bolting. I { 7.6.2.1 Reactor Coolant System Valve Boltino ~ The Reactor Coolant System includes valves with bolted bonnet connections. All of these shall be examined during the inspection interval in accordance with Table A of Appendix A. L 7.6.2.2 Chemical _and Valume Control System Valve Boltino The Chemical and Volume Control System includes l valves with bolted bonnet connections. All of these have been excluded from exar.ination in accordance with Code Case N-426. p L 7.6.2.3 Residual Heat Removal System Valve Boltino The Residual Heat Removal System includes valves with bolted bonnet connections. All of these shall be examined during the inspection interval in accordance with Table A of Appendix A. hVA JM04 (NP 2SI) p

sunura sace: SI-114.2 SURVEILLANCE ASME SECTION XI R2 vision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 43 of 125 7.6.2.4 Safatv Iniection System Valve Bolting The Safety Injection System includes valves with bolted bonnet connections. All of these shall be examined during the inspection interval in accordance with Table A of Appendix A. 7.6.3 Valve Inteorally Welded Suonort Members Il (! Examination of valve integrally welded support members is included in Section 7.4.7. 7.6.4 Valve Comoonent Supports Examination of valve component supports is included in ,j Section 7.4.8. 7.6.5 Valve Body Welds There are no valves with body welds. 7.6.6 Valve Bodies tL-The internal pressure boundary surfaces of valve bodies exceeding 4-inch nominal pipe size shall be visually I examined in accordance with visual examination method l VT-1. Examinations are limited to one valve within each group of valves that are of the same constructional design (i.e., globe, gate, or check valve), manufacturing method, and that are performing similar functions in the system. t See Request for Relief ISI-2. When it becomes necessary to disassemble any valve, subject to internal surface v_sual examination, for normal maintenance purposes, the interior surface of the valve body will be visually examined and the results recorded. A tabulation of valves by groupings is presented in ? Table 1 of Attachment 2. Disassembly of valves is performed in accordance with 0-MI-MVV-000.008.0 and provides for examination of valve internal pressure boundary surfaces. Listings of valve examinations are on the Valve Interior Examination Drawing in Attachment 1. 7.7 Exemoted Components Components exempted from examination include component connections, piping, and associated valves and their supports that are one inch nominal pipe size and smaller, except for steam generator tubing; components connected to and part of the reactor m coolant pressure boundary (defined in 10 CFR 50, Section 50.2(V): revised January 1, 1975) but exempted from Class 1 requirements by vA 4WM4 (NP 190 A

.n ~ ~.. ~c _~x

Sundard Shecs-SI-114.2 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION

-INSERVICE. INSPECTION PROGRAM' Page 44 of 125 regulations of the-regulatory authority having jurisdiction at the plant sites reactor vessel head connections and associated piping, 2-inch nominal.pipo size and smaller, made inaccessible by control rod drive penetrations. 7.8 Successive Examinations Areas of flaw indications evaluated in accordance with IWB-3122.4 + and SSP-3.4 that qualify for continued service shall be'reezamined during the next three inspection periods listed in the inspection schedules. If the reexaminations reveal that the flaw indications remain essentially unchanged for three successive inspections, then the component examination schedule may revert to the original schedule. Exceptions to this requirement may occur when the examination schedule is dictated by.an augmented inspection j, requirement. Components requiring successive examinations shall be scheduled for examination in accordance with Table D of Appendix A.' 7.9 System Pressure Tests d All ASME Code Class 1 (equivalent) system pressure tests shall be in accordance with Technical Instruction (TI) 89, " Inservice L Testing Required by ASME Section XI." 8O' ' COMPONENTS SUBJECT-TO EXAMINATION - ASME CODE CLASS 2 (EOUIVALENT) j ' The ASME Code Class 2 (equivalent) components to be examined during the 4 inspection interval are outlined in the following paragraphs. Extent of -examination for piping welds will be in accordance with paragraph IWC-2411 and 1 ble IWC-2520 of the 1974 Edition, Summer 1975 Addenda, ASME Section XI (examination categories C-F and C-G). t.' Components that are exempted from examination in accordance with IWC-1220 of ASME Section XI are discussed in rection 8.13 of this program. 3 Where examinations specify a percentage of the total length of weld to be examined, the creas(s) examined shall be documented in the examination report. Where a percertage of weld length is not referenced,=the entire weld length shall be examined. 4 Table B in Appendix A supplies additional information such as reference drawing numbers and ASME Section XI Table-IWC-2500-1 examination categories. e i 8.1 Steam Generators (4 ) i 8.1.1 Steam Generator Secondary Side Circumferential Sh l1 Welds t i e r There are three circumferential shell welds at gross l]- structural discontinuities on each generator. The entire length of these three shell welds from one steam generator

i shall be ultrasonically examined during the inspection U

1401C/COC3

5treJard Sicer SI-114.2 SURVEILLANCE ~ ASME SECTION 33 RSvision 16 4 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 45 of 125 i interval. The number of welds to be examined during each inspection period shall be in accordance with Table B of Appendix A. One of the three welds on each steam generator is partially inaccessible for examination due to the upper steam generator support arrangement (weld nos. SGW-D1, D2, D3, and D4; see Request for Relief ISI-4). The weld selected for examination shall be ultrasonically examined on a best-effort basis. The vessel shell sections are fabricated of SA-533, Gr. A, Class 1, stee'. plate. 8.1.2 Steam Generator Secondary Side Circumferential Head Welds h Each steam generator incluces a circumferential head-to-shell weld. The entire length of one head-to-shell weld shall be ultrasonically examined during the inspection interval in accordance with Table B of Appendix A. The weld selected for examination may be from the generator selected for examination by Section 8.1.1. ~ The vessel head section is fabricated of SA-533, Gr. A, Class 1, steel plate. 8.1.3 Steam Gemerator Egnandary Side TubeJheet-to-Shell Weld I bach steam generator includes a tubesheet-to-shell weld. The entire length of one tubesheet-to-shell weld shall be ultrasonically examined during the inspection interval in accordance with Table B of Appendix A. The weld selected l for examination may be from the generator selected for t examination by Section 8.1.1 The tube plate is a SA-508, Class 2, steel forging. 8.1.4 Steam Generator Secondary Side Nozzle-to-Vessel Welds and z Fozzle-to-Vessel Inside Radius 'b Each steam generator includes one feedwater nozzle (3.62 inches nominal wall thickness) and one main steam nozzle (3.62 inches nominal wall thickness). All of the nozzle-to-vessel welds from each generator shall be ultrasonically and magnetic particle examined during the inspection interval in accordance with Table B of Appendix A. The nozzle inside radius sections on each nozzle will be ultrasonically examined once during the inspection interval. ~ Weld MSW-1 during the second period was evaluated to require a reexamination in the third period per IWC-2420 (

Reference:

CAQR CHS 900013). This weld shall be ultrasonically examined in accordance with Table D of Appendix A. See Section 8.14. N^d*M4(NP29t) 1401C/COC3

Stao&rd Sheet SI-114.3 SURVEILLANCE ASNZ SECTION XX Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 46 of 125 The nozzles are fabricated of SA-508, Class 2, steel. 8.1.5 Steam Generator Secondary Side Inteorally Welded Sueoort Attachments There are no integrally welded vessel support attachments. 8.1.6 Steam Generator Secondary Side Component Supports There are no component supports (including mechanical and hydraulic supports) which require examination. 8.1.7 Steam Generator Secondary _ Side Pressure Retaining Bolting Exceedino 2 Inches in Diameter hh There is no steam generator secondary side bolting exceeding 2 inches in diameter. 8.2 RHR Heat Exchancers (2) - RHRHX 8.2.1 RHREX Circumferential Welds 8.2.1.1 RRREX Shell Circumferential Weld There is one circumferential shall wcld located j at a gross structural discontinuity on each L RHRHX. The entire length of this shell weld from one heat exchanger shall be ultrasonically examined during each inspection interval in accordance with Table B of Appendix A (see Request for Relief ISI-16). The RHRHX shell section is fabricated from SS, SA-182, F304. 8.2.1.2 RRREX Head Circumferential Weld \\ L There is one circumferential head-to-shell weld per RRRHX. The entire length of one head-to-shell weld sball be ultrasonically examined during the inspection interval in accordance with Table B of Appendix A. The veld selected for examination may be f rom the heat exchanger selected for examination by section 8.2.1.1. The channel cylinder section (shell) and channel head are one inch thick fabricated from SS, SA-240, TP-304. I 8.2.1.3 RHREX Tubesheet to Shell Weld There are no RHRHX tuberheet-to-shell welds. I tvA 40004 (NP 191} 1401C/COC3

sushrd Shnt SI-114.2 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 47 of 125 8.2.2 RRRHX Nozzle-to-Vessel Welds The channel cylinder section of each RHRHX includes one inlet nozzle (14-inch ID) and one outlet nozzle (14-inch ID) over 1/2-inch nominal thickness. A total of four nozzle-to-vessel welds from the two RHREX will be liquid penetrant examined during the inspection interval. The nogzle-to-vessel welds and nozzle inside radius sections will not be ultrasonically examined during the inspection 'i interval. See Request for Relief ISI-13.

i The nozzles are 2.5 inches thick, fabricated from SS, SA-240, TP-304.

8.2.3 RHRHX Intearally Welded Support Attachmenta , sd There are two integrally welded support attachments (1-inch) on each RHRHX whose base material exc?eds 1/2-inch nominal thickness. A total of two support pad-to-vessel welds from the RHREX will be liquid penetrant examined during each inspection interval in accordance with Table B of Appendix A. The welds selected for examination may be conducted on one heat exchanger and shall cover 100 percent of the required area of each support attachment. l-The support pad is fabricated from SS, SA-240, TP-304. I 8.2.4 PHREX Component Supports There are two component supports en each RHRHX which are in contact vi h the vessel. All component supports from each heat exchanger shall be visually examined during the inspection interval in accordance with visual examination me thod VT-3. t This examination includes integrally welded and nonintegrally welded component supports. Component supports extend from the heat exchanger to and including the attachment to the supporting structure. l The examinations shall be distributed during the t inspection interval in accordance with Table B of u Appendix A. 9 There are no mechanical (snubbers) and/or hydraulic (shock absorbers) supports which are in contact with the vessel. 8.2.5 FHREX Pressure Retaining Boltina Exceedino 2 Inches in Diameter There is .o RHRHX bolting exceeding 2 inches in diameter. 1 IVA 40%J (NP 2MI) 1401C/COC3 u

~ ~.. ~. -,~ e-- l ' Standsed Sheet SI-114.2 SURVEILLANCE ASME SECTION XI Rsvision 16-INSTRUCTION INSERVICE INSPECTION PROGRAM Page 48 of 125 8.3-Recenerative Heat Exchancer Section 8.3-has been deleted from this program in accordance with IWC-1220 (c) of ASME Section XI. See Request for Relief ISI-12. 8.4 Excess Letdown Heat Exchancer 5 Section 8.4 has been deleted from this program in accordance with IWC-1220 (c) of ASME Section XI.. See Request for Relief ISI-12, 8.5 Centrifugal Charoina Pumo (CCP) Tank /(Boron Injection Tank (BIT)) 1.QAD.1 NOTES-The CCP tank was formerly identified es the BIT tank-This change occurred in Unit 2 Cycle 4 refueling ou. ge. As a transition, both ids are being retained for traceability. t 8.5.1 CCP Tank (BIT) Circumferential Shell and Head Welds There are two circumferential head-to-shell welds located at structural discontinuities on the CCP Tank. These welds shall be ultrasonically examined during the inspection interval in accordance with Table B of Appendix A. The examination shall cover 100 percent of the weld length. 4 The head and shell are SA-264 material consisting of i 'c, SA-516, GR70 steel backing outside with 1/8 inch SA-240, } TP304L cladding inside. 8.5.2 CCP Tank (BIT) Nozzle-to-Vessel Welds e I' -There are-two nozzles, one located on each head with a 6-inch inside diameter whose nominal thickness (2.00 in.) {]f. is-greater than 1/2 inch. These nozzle-to-vessel welds p shall be ultrasonically and. surface examined during the inspection interval in accordance with Table B of g g. Appendix A. The examination shall cover 100 percent of . gj the weld length. The nozzles are f abricated to SA-350, LF2. ,/ 8.5.3 CCP Tank (BIT) Inteorally Welded Supports There are four integrally welded support attachment pads j welded-to the shell, whose base material design thickness ~ l. is 5/8 inch and therefore requires surface examination in accordance with Table IWC-2500-1 of ASME Section XI. j'i f _ l' i tvumn <w 2nn 1401C/COC3 y i-,- --4 .-eg rw g-r r %..-,--.e---, ,m._ +-...--w -.-p w -..e.-

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Sund:rJ Sheet SI-114.2 SURVEILLANCE ASME SECTION XI Ravision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 49 of 125 8.5.4 CCP Tank (BIT) Component Supports There are four component supports associated with the CCP tank. All of these supports shall be visually examined (VT-3) during the inspections interval in accordance with Table B of Appendix A. 8.5.5 CCP Tank (BIT) Pressure Retaining Bolting Exceedino Two Inches in Diameter There are 16 manway cover studs at 2-1/2 inches in diameter. All 16 studs shall be ultrasonically examined during the inspection lucerval in accordance with Table B of Appendix A. The studs may be examined in place under tension or when they are removed. It is preferable to h3 perform the examinations when the studs are removed. 8.6 UEI Water Accumulator Section 8.6 has been deleted from this program in accordance with IWC-1220 (a) of ASMI Section XI. This component has also been removed from service. L 8.7 UHI Surae Tank Section 8.7 has een deleted from this program in accordance wi _. IWC-1220 (a) of ASME Sectiou XI. This component has also been removed from service. ( 8.8 Seal Water Iniection Filters Section 8.8 has been deleted from this program in accordance with IWC-1220 (c) of ASME Section XI. See Request for Relief ISI-12. ~ 8.9 Elpips f' Material specifications for each piping system are stated on the weld map isometrics. The following Class 2 piping systems are subject to examination: 1' Li Residual Heat Removal (RHR) Safety Injection (SI) } Main Steam (MS) ,) Feedwater (FW) Containment Spray (CS) q Upper Head Injection (UHI) - The UHI system was removed j2 from service during Unit 2 Cycis 4. For reference to the schedule of examinations performed on thic system, see Revision 14 of this instruction. 8.9.1 Pipina and Valve Intecrally Welded Support Members Integrally welded support members include the support attachments of piping required to be examined by Examination Category C-F. Included are those supports ~5140%4 (NP 2NI) 0 1401C/COC3

- -.. ~ -. ' Standard Sheet SI-ll4.2 SURVEILLANCE ASME SECTION XI Ravision 16 i INSTRUCTION INSERVICE INSPECTION PROGRAM Page 50 of 125 which have attachment welds.to the valve and piping pressure retaining boundary, and those attachments whose support base material design thickness exceeds 3/4 1pth (see PRISIM data base). The entire length of each support ?ttachment veld selected for examination shall be surface examined. The examinations performed during the inspection interval shall include 100 percent of the integrally welded support members. The examinations shall be distributed during the inspection interval in accordance with Table B of f Appendix A (see Request for Relief ISI-17). .i a 8.9.1.1 Residual Heat P'emoval System Ploina and Valve Intearally Welded Supoort Members p The Residual Heat Removal System piping does not include any integrally welded support members. 8.9.1.2 Safety Injection System Ploino and Valve Integrally Welded Support Members I ~{ The Safety Injection System piping includes integrally velded support members. All of these shall be examined during the inspection interval in accordance tith Table B of Appendix A. 8.9.1.3 Main Steam System Ploino and Valve Inteorally Welded Suonort Members -L The Main Steam System piping includes integrally welded support members. All of these shall be examined during the inspection interval in accordance with Table B of Appendix A. 8.9.1.4 Feedwater System Ploino and Valve Inteorall_v Welded Sucoort Members The Feedwater System piping includes integrally welded support members-All of these shall be [. examined during the inspection interval in l accordance with Table B of Appendix A. fai 8.9.1.5 Containment Sorav System Pipina and Valve Intearally Welded Supoort Members g The Containment Spray System piping does-not include any integrally welded support members. l. s l 8.9.2 Pipina_ and Valve Component Suc_ c_ orts All piping and valve component supports shall be visually examined during the inspection interval in accordance with visual examination methods VT-3 and VT-4. This examination includes integrally welded and nonintegrally r-l < ^# "I 1401C/COC3 r

Standard Sheet SH-114.3 SURVEZLLANCE ASME SECTION XI Revisjon 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 51 of 125 welded component supports. Component supports artend from the piping and valves to and including the attachment to the supporting structure. The setting of snubbers, shock absorbers and spring-type hangers shall be verified in accordance with the applicable NDE procedure with the acceptance criteria shown in the Scan Plan (see PRISIM data base) or the applicable work instruction. For reference the acceptance ranges are listed in the component support acceptance range drawings in Attachment 1. The exsninations shall be distributed during the inspection interval in accordance with Table B of Appendix A. 8.9.2.1 Residual Heat Removal System Pipino and Valyg Comoonent Supports The Residual Heat Removal System piping includes component supports. All of these shall be examined during the inspection interval in accordance with Table B of Appendix A. 8.9.2.2 Enfety Injection System Ploina and Valve Component Supports The Safety Injection System piping includes component supports. All of these shall be examined during the inspection interval in accordance with Table B of Appendix A. 8.9.2.3 Main Steam System Ploing and Valve Component Suonorts f-The Main Steam System pip 3 ng includes component , [, supports. All of these shall be examined during the inspection interval in accordance with Table B of Appendix A. 1 8.9.2.4 Feedwater System Pipina and Valve Component l Supports L ~l The Feedwater System piping includes component a supports. All of these shall be examined during L' the inspection interval in accordance with Table B of Appendix A. l I 8.9.2.5 Containment Sorav System Picina and Valve l Component Suonorts J The Containment Spray System piping includes ] component supports. All of these shall be J examined during the inspection interval in accordance with Table B of Appendix A. I Iv4 40ws (Np z93) j 1401C/COC3

SunJard Slect SI-ll4.2 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 52 of 125 l 4 8.9.3 Pressure-Petainino Bolting There is no Class 2 Pressure-Retaining Bolting larger than two inches in diameter. 8.9.4 circumferential and Loncitudinal Pipe Welds Selection of welds for examis.3 tion is based on Table IWC-2520, Paragraph IWC-1220, and Paragraph IWC-2411 (Summer 1975 Addenda). All of the welds selected shall be examined during the in=pect3on interval and distributed in accordance with Table B of Appendix A. The entire length of each weld selected for examination shall be ultrasonically and/or surfaced examined. p uircumferential and longitudinal piping welds in piping with a nominal wall thickness of 1/2 inch or less shall be surface examined. Circumferential and longitudinal piping welds in piping with a nominal wall thickness greater than 1/2 inch shall be ultrasonically and surfaced examined. The areas subject to examination include circumferential + pipe welds at structural discontinuities, within 3 pipe diameters of the centerline of rigid pipe anchors, anchors at the penetration of primary containment or at rigidly anchored components, and longitudinal weld joints in pipe fittings. 8.9.4.1 Eg11 dual _ Heat Removal Pipino \\' The Residual Heat Removal Piping Lystem includes Class 2 circumferential end longitudinal piping welds with a nominal vall thickness greater than 1/2 inch subject to examination. The welds selected for examination shall be ultrasonically ( and surfaced examined each inspection interval in L accordance with Table B of Appendix A. The RER piping system includes the circumferential sud longitudinal pipe welds with a nominal wall thickness of 1/2 inch or less. The welds selected for examination shall be surface examined each inspection interval in accordance with Table B of Appendix A. 8.9.4.2 Safety Injection Ploing The Safety In3ection Piping System includer Class 2 circumierential piping welds with a nominal wall thickness greater thsn 1/2 inch subject to examination. The welds selected for examination shall be ultrasonically and surface examined each inspectian interval in accordance with Table B of Appendix A. The safety injection piping system includes the circumferential and s longitudinal pipe welds with a nominal wall TVA 4M)4 (NP 2M) 1101C/COC3 n " - - - - - - - - - - --------~

Sushid Skel l SI-114.2 SURVEILLANCE ASME SECTION XI R0 vision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 53 of 125 thickness of 1/2 inch or less. The welds selected for examination shall be surfaced examined each inspection interval in accordance with Table B of Appendix A. 8.9.4.3 Main Steam Piping The Main Steam Piping System includes Class 2 circumferential and longitudinal piping welds with a nominal wall thickness greater than 1/2 inch subject to examination. The circumferential and longitudinal piping welds i selected for examination shall be ultrasonically and surfaced examined each inspection interval in accordance with Table B of Appendix A. There are ~ no circumferential and longitudinal pipe welds with a nomiral wall thickness of 1/2 inch or less in the Main Steam System. 8.9.4.4 Feedwater Ploino The roedwater Piping System includes Class 2 circumferen ial and longitudinal piping welds 4' with a nominal wall thickness greater than 1/2 inch subject to examination. Tne circumferential and longitudinal piping welds selected for examination shall be ultrasonically and surfaced examined each inspection interval in accordance with Table B of Appendix A. The one longitudinal weld is on loop 4 at the reducing elbow (18 in. x 16 in.) The feedwater piping system includes one circumferential pipe weld with a nominal wall thickness of 1/2 inch or less scheduled for the 40-year sample. This circumferential weld has not been scheduled for examination this interval. There are no longitudinal pipe welds with a nominal wall thickness of 1/2 inch or less in the feed water system. J 8.9.4.5 Containment Sorav Piping The Containment Spray Piping System includes Class 2 circumferential and longitudinal piping welds with a nominal wall thickness of 1/2 inch or less, subject to examination. The w circumferential and longitudinal pipe welds selected for examination shall be surface examined each inspection intarval in accordance with Table B of Appendix A. There are no circumferential and longitudinal pipe welds with } a nominal wall thickness greater than 1/2 inch in the Containment Spray System. a {^ 40M4 (NP191) I 1 1401C/COC3

Sundard Sheet SI-114.2 ~ SURVEILLANCE ASME SECTION XI Revision 16 i INSTRUCTION INSERVICE INSPECTION PROGRAM Page 54 of 125 8.9.5 Branch Ploina Connection Welds l There are no Class 2 branch pipe connection welds. 8.10 Pumps 8.10.1 RHR Pumps (2) - RHRP r-8.10.1.1 RRRP Intearally Welded Supports There are no integrally welded supports _f associated with the RERP. t 8.10.1.2 RHRP Support Components y. !"R Each RERP includes one component support bolted l' to the pump feet which are integrally forged with the pump. The component support from each pump shall be visually examined during the inspection interval in accordance with visual examination method VT-3. Support components-I- extend from the RHRP to and including the attachment to the supporting structure. W Both of the RHRP support components shall be examined during the inspection interval. 8.10.1.3 RRRP Supports - Mechanical or Hydraulic ( There are no mechanical or hydraulic supports asscciated with the RERP. r' 8.10.1.4 RRRP Pressure Retainino Boltino o The stuffing box extension to pump casing ,'I connection bolting is not greater than two inches in diameter. m IL. acuraction includ:a 24 studs at 1-1/4 inches 4 In diameter with nuts and washers. The studs are'fabri'ated to SA-193, GR. B7, and the nuts c to SA-194, GR. 2H. J-RJ 8.10.1.5 RRRP Casina Welds The RHRP does not include any casing welds. The casing is a one piece forging fabricated to i SA-182 F304. 8.10.2 CVCS Centrifuaal Charaina Pumos (2) -CCP i i Examination of these pumps, and their associated component j supports, pressure retaining bolting, and casing welds are exempted under previsions outlined in table IWC-2500-1 and i i f JVA 40004 (NP 2.91) r - 1401C/COC3 l

Surdard Shees SI-114.2 SUR?EILLANCE ASME SECTION XI Rsvision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 55 of 125 accompanying footnotes, examination categories C-C, C-G, which limit the exam requirements to con.ponents in piping examined under examination category C-F. 8.10.3 CVCS Positive Displacercient Pumofl) PDP/ Reciprocating Charoino Pump w Examination of these pumps, and their associated component supports, pressure retaining bolting, and casing welds are exempted under previsions outlined in table IWC-2500-1 and accompanying footnotes, examination categories C-C, C-G, which limit the exam requirements to components in piping examined under examination category C-F. 8.10.4 Safety Injection Pumps (2) SIP .- ( l Examination of these pumps, and their associated component supports, pressure retaining bolting, and casing welds are exempted under previsions outlined in table IWC-2500-1 and accompanying footnotes, examination cctcgor'es C-C, C-G, which limit the exam requirements es c :..;4& snts in piping examined under examination category C-F. 8.11 Valves Systems including ASME Code Class 2 valves subject to examination are identified in Section 8.9. A tabulation of valves is presented in Attachment 2. I {, 8.11.1 Valve Intecrally Welded Supports Examination of valve integrally welded support members is included in Section 8.9.1. 8.11.2 Valve Con.oonent Succorts Examination of valve component supports is included in Section 8.9.2. 8.11.3 Valve Pressure-Retainino Boltino There is no Class 2 pressure-retaining bolting greater than 2 inches in diameter. u 8.11.4 Valve Body Welds p There are no Class 2 valves with body welds. 8.12 System Pressure Test All ASME Code Class 2 (equivalent) system pressure tests shall be in accordance with TI-89, " Inservice Testing Required by ASME Section XI." rvA 40004 (NP 2M) u, 1401C/COC3 1

SuedATd bbtfl. SI-114.2 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 56 of 125 8.13 Exempted Components 8.13.1 Exempted Components (Except Pipino Welds) Components exempted from examination includes (a) components of systems or portions of systems that during normal plant operating conditions are not required to operate or perform a system function but remain flooded under static conditions at a pressure of at least 80 percent of the pressure that the component or system will be subjected to when required to operates or (b) components of systems or portions of systems, other than RHR Systems and Emergency Core Cooling Systems, that are not required to operate above a pressure of 275 psig or abov: a temperature of 200*F; or (c) component connections (including nozzles in vessels and pumps), piping and associated valves and vessels (and their supports) that are 4 inch nominal pipe size and smaller. 8.13.2 Exemoted Components (Ploino Welds On1_) v Piping exempted from examination includes (a) Piping systems whers both the design pressure and temperature are ~ equal to or less than 275 psig and 200*F, respectively; (b) piping systems or portions of systems other than emergency core cooling systems which do not function during normal reactor operation; (c) piping that is 4-inch nominal pipe size and smaller. 8.14 Euccessive Examinations Components with flaw indications evaluated in accordance with l IWC-3000 and SSP-3.4 that qualify for continued service shall be reexamined during the next inspection period listed in the i inspection schedule. If the reexamination reveals that the flaw indications remain essentially unchanged the component examination schedule may revert to the original schedule. Exceptions to this requirement may occur when the examination schedule is dictated by an augmented inspection requirement. Components requiring l3 succe sive examinations shall be scheduled for examination in 4 j accordance with Table D of Appendix A. l ( j' 9.0 C.QMPONENTS SUBJECT TO EIAMINATION - ASME CODE CLTSS 3 (EOUIVALENT) I ia ASME Code Class 3 (equivalent) component supports and restraints within [ Ehe boundaries identified in Sections 9.1 and 9.2 for components exceeding 4-inch nominal pipe size shall be visually examined, VT-3, during each inspection period. 1 Mechanical and hydraulic snubbers, spring loaded and constant weight supports within the boundaries identified in section 9.1 for components exceeding 4-inch nominal pipe size shall be visually examined, VT-4 j during each inspection period. J A acm pe 2st) 1401C/COC3

Sundard Sket SI-114.2 SURFEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 57 of 125 9.1 Pipino and Valve Cocoonent Supportg All piping and valve component supports ahall be visually examined during each inspection period in accordance with visual examination methods VT-3 and VT-4. This examination includes integrally welded and nonintegrally welded component supports. Component supports extend from the piping and valves to and including the attachment to the supporting structure. The setting of snubbers, shock absorbers and spring-type hangers shall be verified in accordance with the applicable NDE procedure with the acceptance criteria shown in the Scan Plan (see PRISIM data base) _[ or the applicable work instruction. For reference, the acceptance ranges are listed in the component support acceptance range drawings in Attachment 1. The examinations (100 percent) shall be conducted during each inspection period during tne inspection h Interval in accordance with Table C of Appendix A. 9.1.1 Auxiliary Feedwater System Pipino and Valve Component Sueoorts The Auxiliary Feedwater System piping includes component supports. All of these shall be examined during each inspection period in accordance with Table C of Appendix A. 9.1.2 Chemical and Volume Control System Ploine and Valve Component Suvoorts i. The Chemical and Volume Control System piping component f supports are not required to be examined because there is { no examination category for this piping. This piping is TVA Safety Class D. (The change in support numbers during the second period was due to new class boundaries.) 9.1.3 Component Coolino System Ploina and Valve Component Suerorts t The Component Cooling System piping includes component supports. All of these shall be examined during each inspection period in accordance with Table C of Appendix A. L 9.1.4 Containment Sprav System Pipino and Valve Component Suoc_ orts I Lv The Containment Spray System piping has no component supports. (The change in support numbers during the ~ second period was due to new class boundaries.) o b 9.1.5 Essential Raw Coolina Water System Ploine and Valva Component Supports The Essential Raw Cooling Water System piping includes component supports. All of these shall be examined during each inspection period in accordance with Table C of a Appendix A. f^ ' "" #" I 1401C/COC3

+ - =. - I 8 Standcid Sheet SI-114.3 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 58 of 125 9.1.6 f.ugl Pool Coolino System Pinino and Valve Comeonent ^ Suecorts The Fuel Pool Cooling System Piping component supports are examined in accord.snce with SI-114.1, Unit 1 Program. i e 9.1.7 .RHR System Pipiro and Valve Component Suonorts The RHR System piping has no component supports. (The change in support numbers during the second period was due to new code class boundaries.) 9.1.8 Safety Iniection System Ploino and Valve Component Supports 4 The Safety. Injection System piping has no component N supports.- (The change in support numbers during the-L second period was due to new code cl,a boundaries.) s I 9.2 Equipment Component Supports The equipment component support and the_ associated integrally welded support attachment will be (VT-3) examined together. 9.2.1 Containment Soray Heat Exchancer (2) Suonort - CSH (ERCW) There is one component support on each CSH. These supports shall-be (VT-3) examined during the inspection interval in accordance with Table C of Appendix A. l- { 9.2.2 Nonrecenerative Letdown Heat Exchancer (1) Support - NRLIDC (CCS) There is one component support on the NRLHX. This support L shall be (VT-3) examined during the inspection interval in accordance with Table C of Appendix A. 9.2.3 Gas Stripper and Boric Acid Evaporator (1) - CSBAE (CCS) 'a-9.2.3.1 GSBAE Evaporator Condenser (1) Suocort - EC There are two component supports on the EC. These support.s shall be (VT-3) examined during i the inspection interval in accordance with w Table C of Appendix-A. p 9.2.3.2 GSBAE Distillate Cooler (1) Supoort - DC (CCS) \\ w There are two component supports on the DC. These supports shall be (VT-3) examined during the inspection' interval in accordance with Table C of Appendix A. F L 6 TVA 40004 (NP 2,91)-

Sta:&rd Sheet SI-114.2 SURVEILLANCE ASME SECTION XI Rovision 16 ~ INSTRUCTION INSERVICE INSPECTION PROGRAM Page 59 of 125 9.2.3.3 GSBAE Vent Cooler Support (1) - VC (CCS)_ There are two component supports on the VC. These supports shall be (VT-3) examined during the inspection interval in accordance with Table C of Appendix A. 9.2.3.4 GSBAE Support S dme (1) - SF (CCS) The SF consists of one component support. This support shall be (VT-3) examined during the inspection interval in accordance with Table C of Appendix A. 9.2.4 Component Coolino Surce Tank (1) Support - CCST (CCS) {~ There is one component support on the CCST. This support shall be (VT-3) examined during the inspection interval in accordance with Table C of Appendix A. 9.2.5 Comoonent Coolino System Positive Displacement Charoing Pumo Oil Cooler (1) Supoort - PEOC (CCS) There are two component supports on the PDOC. These supports shall be (VI-3) examined during the inspection interval in accordance with Table C of Appendix A. i 9.2.6 Component Cooline Water Gross Failed Fuel Detector (1) f Support - GFFD (CCS.1 \\~ There is one component support on the GFFD. This support shall be (VT-3) examined during the inspection interval in accordance with Table C of Appendix A. ~ 9.2.7 Centrifucal Charoino Pumo Gear Oil Cooler (2) Support - CCPGOC (ERCW) There are two component supports on each CCPGOC. These supports shall bo (VT-3) examined during the inspection interval in accordance with Table C of Appendix A. 9.2.8 Centrifucal Charcino Pumo Oil Cooler (2) Support - CCPOC ( ; (ERCW) Li There are two component supports on each CCPOC. These supports shall be (VT-3) examined during the inspection j interval in accordance with Table C of Appendix A. 9.2.9 Waste Gas Compressor Heat Exchancer (1) Support - WGCHX (CCS) There are two component supports on the WGCHX. These supports shall be (VT-3) examined during the inspection 5/ interval in accordance with Table C of Appendix A. 7VA 40%4 (NP 2M4 j w

htsaJard Shere 4 SI-114.2 SURVEILLANCE ASME SECTION XI Revisiot 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 60 of 125 3 9.2.10 Cank1Lugal Charaina Pump _Htihan1EAL1eal Cooler (4) Support - CCPMSC (CCS; There is one component support on each CCPMSC. These supports shall be (VT-3) examined during the inspection interval in accordance with Table C of Appendix A. 9.2.11 E111LEwnp Seal Cooler (2) Support -__FjiESC (CCS1 There is one component support on each RHRSC. These supports shall be (VT-3) examined during the inspection interval in accordance with Table C of Appendix A. 9.2.12 Safety Injection Pwrp_Q11 Cooler (2) Support - SIEQC R RCW_1 i l There are two component supports on each SIPOC. These supports shall be (VT-3) examined during the inspection interval in accordance with Table C of Appendix A. 9.2.13 SAIAlv Injection Pumu Seal Cooler (4) Support - SIPSE (ERCW) There is one component support on each SIPSC. These e supports shall be (VT-3) examined during the inspection 4 interval in accordance with Table C of Appendix A. 9.2.14 Cg2P2ngnt CooliA2 SYlitm Seal Water HeALIxchnoser (11 Support - SWIC: (CCS) There is one component support on the SWIDC. This support sFall be (V7-3) examined during the inspection interval in

1. cordance eith Table C of Appendix A.

9.2.15 Component Coolina System Thermal Barrier Booster Pump (2) S2222I1. - TBBP (CCS ) Thire are two component supports on each TBBP. These 4 supports shall be (VT-3) examined during the inspection C interval in accordance with Table C of Appendix A. l J 9.2.16 Turbine Driven Auxiliary Feedwater Pump (1) Support. TDAFP (AFW) There are two component supports on the TDAFP. These supports shall be (VT-3) examined during the inspection q. Interval in accordance with Table C of Appadix A. "l 9.2.17 Motor Dr1Yan Aug1]iary Feedwa gt_1. pro (2) Support - @LAff (AFW) g ' 1 There are two comp m ; supports on ecch MG 7P. These supports shall be (vf-3) examined during th9 inspection ,] interval in accordance with Table C of Appendix A. L) A *>4 (N P 2A O 1401C/COC3

m Stredard Stret SI-114.2 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 61 of 125 9.2.18 Compenent Cooltna System Water Pumps (3) Support - CCSNE (CCS) There is one component support on each CCSWP. These j r;pports shall be (VT-3) examined during the inspection i interval in accordance with Table C of Appendix A. 9.2.19 C2rpong.nt Cooling Heat Exchanger (2) Support - CCHX (CCS1 l 5 There is one component support on each CCHX. These supports shall be (VT-3) examined during the inspection j interval in accordance with Table C of Appendix A. 9.2.20 Esser.tial Raw Coolina Water System Strainer (21_ Support - ERCHS (CRCH1 y, There is one component support on each ERCWS. These supports F. hall be (VT-3) examined during the inspection interval in accordance with Table C of Appendix A. 9.2.21 Essential Raw C93211R2_., Hater SyjLtem Pump Station Ptump Espports These supports are examined in accordance with SI-114.1, Unit 1 Program. 9.2.22 Fuel Pool Coolina And Cleanino System - Spent Fuel Pit Pumps These supports are examined in accordance with SI-114.1, Unit 1 Program. 9.2.2? Fuel Pool Cooling And Cleaning System - Spent Fuel Pit Feat ExchaDSEI l These supports are examined in accordance with SI-114.1, Unit 1 Program. l 9.2.24 RHR Feat Exchanger Secondary Side (2) Supports - RHRHSZH (CCS) ,1 There are two component supports on each RHRHSIIX. These y; supports shall be (VT-3) examined during the inspection (, interval in accordance with Table C of Appendix A. 9.2.25 ERCW Screen Wash Pume Support These supports are examined in accordance with SI-114.1, Unit 1 Program, i 9.3 System Pressure Testa l l All ASME Code Class 3 (equivalent) system pressure tests shall be f in accordance with TI-89, " Inservice Testing required by ASME Section XI." i VA 4M94 (NP 2%) 1401C/COC3

se.sa s6,ee SI-114.2 SURVEILLANCE ASME SECTION XI RQvision 16 INSTRUCTION INSERVICE XhSPECTION PROGRAM Page 62 of 125 I 10.0 AUIDORIZED IN3fECIQJ[ TVA shall employ an Authorized Inspection Agency in accordance with ASME Section XI for inservice examinations, repairs, and replacements of ASME Code Class 1, J and 3 (equivalent) components at SON. The Authorized Inspector (s) shall verify, assure, or witness that code requirements have been met. He shall have the prerogative and authorization to require requalification of any operator or procedure when he has reason to believe the requirements are not being met. TVA shall provide access for the Authorized Inspector (s) in accordance with IWA-2140 of ASME Section XI. TVA's interf ace with the Authorized Inspector for 151, Repairs and Replacements is defined in STD-6.10, SSP-13.3, AI-19 Parts IV and VI. 11.0 EXAMIEATIDH_METHQDS_ AND CALIDEATIDH_RLQC];5 11.1 Etnalnation Methada g NDE examinations shall be performed in accordance with this program as scheduled in Appendix A, the applicable Scan Plan, t QMP-102.4, and QMP 110.5. Requirements for NDE methods shall be { in accordance with IWA-2210 through IWA-2233 of ASME Section XI. If during an examination it is determined by an NDE Level III that a full cod 6 exam cannot be performed, the fact shall be documented on the data sheet and a best effort examination shall be performed. ISI Programs shall be informed in writing of the limited exam. l Data must be provided on the exam sheet so as to determine the percentage of the eram done. 11.2 Calibration Blogis Calibration blocks will be used for ultrasonic examinations (a L calibraticn tube will be used for eddy current examination of steam gene. tor tubing). The blocks will be fabricated to the general requirements of ASME Section V and ASME S9ction XI. The blocks shall be fabricated of the material to be examined or equivalent P numbers. Mill test reports shall be obtained and retained by ISO for all calibration blocks. The blocks shall i employ drilled holes and/or notches for cali.bration reflectors M (See Request for Relief ISI-9). ISO shall maintain as built calibration block drawings. The calibration blocks shall be stored at the plant site and raaintained by S00 personnel. 1 12.0 QUALIFICATIONS OF NDE PEREQHHEL i Personnel performing NDE operations shall be qualified in accordance with IWA-2300 of ASME Section XI as required in QMP 102.4. VA 4M04 (NP 2My 1401C/COC3 .~

__ = _ _ __ M.eduJ Sheel SI-114.2 SURVEILLANCE ASME SECTION XI Rovision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 63 of 125 13.0 ACCEPTANCE _CRIIERIA All acceptance standards for ASME Code CI :ss 1, 2, and 3 (equivalent) components shall be in accordance with IWA-3000, IWD-3000, IWC-3000, or IWD-3000 of ASME Section XI, except where ASME Section III examinations are employed to satisfy ASME Section XI requirements. 14.0 JtEPAIR.S_AND REPLACEggEtg All ASRI Section XI components and their supports (ASME Classes 1, 2, and 3) shall be repaired in accordance with the Repair and Replacement Program implemented by AI-19 Parts IV and VI and SSP-13.3. l l ASME Section XI repairs and replacements may be coordinated as necessary with ISI Programs. fn 15.0 PUMP AND VALVE TESTING Pump and valve testing shall be in accordance with TI-89, " Inservice j Testing Required by ASME Section XI." ti 16.0 RECORDS AND REPORTS i 16.1 Repair and Replacemfnt Reports Repair and Replacement Form NIS-2 reports shall be prepared in accordance with AI-19, Parts IV and VI, and SSP-13.3. 16.2 Report for ISI of Class 1 and 2 Comp.22fELA SQO shall prepare an ISI Report for Class 1 and 2 components to be submitted within 90 days after the completion of the ISI to the NRC Region II office in accordance witL IWA-6220, ASME Section XI. The ISI Report shall have a cover sheet providing the-following information: 1. Date of document completion. 2. Name and address of owner. l 3. Name and address generating plant. L 4. Name or number assigned to the nuclear power unit by TVA. 5. Commercial operation date for unit. All reports shall provide the following information as a minimum. 1. Numbers assigned to the components by the state. 2. Nstional Board Number assigned to the components by the manufacturer. t lJVA J0M4 (NP 191) i 401C/COC3 ~ , _... _ - ~ -.. _.. - _ _. _. - - -

Suzdard Sheet SI-114.2 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 64 of 125 I 3. Names of the components and descriptions including size, capacity, material, location, and drawings to aid identification. 4. Name and address of principal manufacturer (e.g., Westinghouse, GE, etc.) and the principal contract number which will identify the subcontractors, Manufacturer's component identiflcation numbers. S. Date of completion of the examination. 6. Name of ANII who witnessed or otherwise verified the examinations and his employer and business address, when required. I }4 7. Abstract of exam' nations, conditions observed; and corrective measures recommended or takon. 8. Signature of ANII, when required. 9. Owner's Data Report for ISI, Form NIS-1, as shown in ( Appendix II, of ASME Section XI and Forms HIS-2 as identifled above in E^ction 16.1. SOO shall submit the Inservice Inspection Report to the plant manager for retention as part of the final report discussed in Section 16.3. 500 shall submit applicable summaries of the report i with a cover sheet as described above to the NRC via SON Site { Licensing. l" 16.3 Site Firal Report I ( A detailed report of all examinations shall be prepared by S00 (and/or the performing or responsible organization) and should contain, but not be limited to, the following informations i [, Cover Sheet - Data Sheet 1 in Appendix B will be completed and used as a cover sheet for the Site Final Report and to document the review process. Iw p + I l s ~> J VA 4Mo4 (NP 2SI)

Suzdard Sheet SI-114.2 SGRVEILLANCE ASME SECTION XI R: vision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 65 of 125 Table of Contents I. Introduction - The introduction should include the following information: Plant, unit number, PSI or ISI and cycle number, systems, components and vessels examinations were performed on, organization examinations were performed by, dates examinations were performed, ASME Section XI Code of Record. I II. Summary - The summary should include a brief description of the overall inspection. III. Summary of Notifications - The summary of notifications shall give a short summary of each notification report { along with the indication discrepancy and its location. !d It should also contain the final disposition including a I' reference to the corrective action taken and the date of completion. IV. Examination Plen - 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, Weld Siso, Reference Drawing, Examination Method, Procedure, Calibration Block, date of examination and result of examination. V. Summary of Personnel Certifications -f VI. Calibration Sheets VII. Examination Data Sheets 6-VIII. Copy of the ISI Report as Discussed in Section 16.2 For eddy current examination of heat exchanger tubing, the report shall include a record indicating the tube (s) examined (this may be marked on a tube sheet sketch or drawing), the extent to which r each tube was examined, the location and depth of each reported indication, and the identification or the operator (s) and data L, evaluator (s) who conducted each examination or part thereof, and magnetic media and strip charts as applicable, i All prc.edures and equipment shall be identified sufficiently to permit duplication of the examination at a later date. This shall include initial calibration data for the equipment and any I significant changes. l s. l f^

1. U 1401C/COC3 o

l l -. ,, -_ ~. ~ ' ~~

s 40 erd swes SI-114.3 SURVEILLANCE ASME SECTION XI Revision 16 i INSTRUCTION INSERVICE INSPECTION PROGRAM Page 66 of 125 All required and pertinent information will be recorded on the y appropriate data sheets by the performing organisation. When portions of the inspection work are contracted, a detailed report will be submitted to TVA by the contractor with all pertinent and required information. TVA will retain the original copies of all raw data taken. S00 shall review and submit the Site Final Report in accordance with SSP 8.2, " Surveillance Test Program," for retention as a quality assurance record in accordance with SSP-2.9, " Records Management." 16.4 Eecords for ASME Code Class 1, 2 and 3 (EqulyAlgntl The following records are OA Records and shall be retained in accordance: 1. Site Final Report - SSP-2.9 2. NDE Procedures - OMP 110.5 3. Calibration Block Drawings - OMP 105.4 The following drawings are retained as OA records: I 1. ASME Section XI Boundary Classification Drawings i 2. ASME Section XI ISI Drawings f ( 16.5 Ragords of System Pressure Tests Records of the visual examinations conducted during system leakage { or hydrostatic tests shall consist of an itemitation of the number and location of leaks found in a system and the corrective actions

taken, 16.6 Augmented Examination Reports m

Augmented examination special reports shall be submitted to the ' j NRC Region II Office within the time period specified for each augmented eram2 nation. For specific details on records, reports and reporting see Section 20.0, Augmented Inspections. The status of augmented examinations requested by ISI Programs end implemented by SQO shall be maintained in a computerized data base (PRISIM). 16.7 Status of Completed Examinatiorg ISO maintains a computer based status listing (PRISIM data base) of the examinations completed for ASME Section XI credit for examinations performed baring the inspection period and interval. l This listing as a minimuA sientifies the component examined, ASME class, examination method, and outage cycle when the examination l was performed. This listing may also be used to identify i components to be inspected in the future. va amo4 (NP 230 1401C/COC3 l

. - - ~. ~ -. -.. Sund,rd Shret SI-114.2 SURVEILLANCE ASME SECTION XI Revision 16 IPSTRUCTION INSERVICE INSPECTION PROGRAM Page 67 of 125 17.0 FDTIFICATION OF INDICATION i 17.1 The Notification of Itdication (NOI) form in Appendix C of this program is to be used to (1) notify Plant Management of an indication found during the performance o'. scheduled ISI examinations that will require evaluation and a disposition in accordance with plant procedures, (2) notify ISI Programs that an indication that exceeds the acceptance criteria of Article 3000 of the ASME Section XI Code has been documented on an examination report form contained within the NDE procedure used for examination, (3) provide ISO and SQO with a method to track examination reports that require reexamination or a documented disposition for closure, and (4) as a final product, with the ) disposition provided under plant procedures added to Part II of the form, provide ISI Programs a method of determining if additional Code exa.ninations are required. 17.2 Functionally an NOI Form shall be initiated and processed as follows. 17.2.1 Part 1 of an NOI Form will be initiated by the NDE Examiner when an indication exceeds the acceptance criteria of the NDE Procedure being used to perform a scheduled ISI examination. The Examiner will sign and date the NOI Form. The Field Supervisor, in the case of contracted examinations, will review the information in Part I and sign and date the NOI Form as approving the information. The S00 Representative will review for accuracy, sign, and date the NOI Form. 17.2.2 After completion of Part I, SQO shall send the original NOI Form and a copy of the Examination Report to Site Engineering as a notification to plant management that an indication requiring evaluation has been found. A prompt determination of any impact on operability must be made in [{ accordance with plant procedures. SQO shall also send a L; copy to ISI Programs as notification that a potential exists for additional examinations to be performed per -] ASN2 Section XI. 1J 17.2.3 Site Engineering shell be responsible for evaluating and providing a disposition for the endication in accordance with plant procedures. The disposition shall be documented in detail on an administrative centrol program document (PER, FIR, SCAR, WR/WO, etc.) if required by ] Section 18.0. J 17.2.4 Site Engineering shall include the final disposition on the NOI Form in Part II, sign and date the NOI Form, and ~ return the original to the SQO Representative. Reference to any PERs, FIRS, SCARS, HR/W0s, etc., shall be included. f 'jlVA 4M04 (NP 2"n) 1401C/COC3

$u2da#J Mut l SI-114.2 SURVEILLANCE ASKE SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 68 of 125 j 17.2.5 The S00 Representative shall immediately, upon receipt, provide a copy of the NOI Ferm bearing the recorded disposition to ISI Programs for determination of additional examination requirements. 17.2.6 Upon notification f rom ISI Programs, the 500 Representative shall check "yes" or "no" for edditional examinations, and he shall close the NOI Form in Part III by reexamination, in the case where work was performed as a part of the disposition, or by verification of the disposition if no physical work was required to remove or modify the indication. 17.2.7 The original NOI Form shall be filed with the original examination report. A copy of the form shall be sent to .!j ISI ProgramJ for closure of their files. The reexamination report, if applicable, shall reference the NOI number. The NOI Form shall reference the reexamination report number. 17.3 Additional Sample _Salection for CC-1 and CC-2 NOIs After an NOI has been dispositioned and returned to the 500 ~~ representative, a copy shall be forwarded to ISI Programs for evaluation to determine if additional examinations shall be required. If it is determined that additional examinations tre required, these examinations shall be performed during the same outage as the initial examinations. A sample is defined as those items (welds, areas, or parts) as described or intended in a E, particular examination category and item number and within the same system. For component support samples, the additional p, examinations may also be limited to component supports within the same examination method (VT-3, and VT-4). The initial sample is the sample scheduled for examination at a particular outage for Section XI credit. For eteam generator tubing, additional samples {I shall be per Section 7.3.8. L. 17.3.1 Evaluation For First Additional Sample A first additional sample shall be selected for those examinations performed in the initial sample that reveal indications exceeding the Lorresponding acceptance standards of INX-3000 of ASME Section XI. The first additional sample shall include approximately the same number of items examined in the initial sample. The first additional sample shall be selected from the ten year interval sample. The items selected should be from those items that have the longest service time from its previous inservice examination. q If a system contains a sample within the same examination category and item number as the initial sample which had the indication and is not scheduled for examination this outage, this system sample shall be evaluated to determine lvA 4CKW4 (NP 191) 1401C/COC3

._ ~ SteadotJ Shres S3-114.3 SURUEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 69 of 125 if it should be examined this outage to provide a representative sample from each system within a particular examination category and item number. This evaluation should consider, but is not limited to, the type of indication found in the initial sample and similar system design and operating parameters. The ISI Programs representative shall submit the additional sample to the S00 Representative for addition to the scan plan. 17.3.2 EvaluAtlon for Second Additional Sample A second additional sample shall be selected for those examinations performed in the first additional sample that reveal indications exceeding the corresponding acceptance standards of INX-3000 of ASME Section XI. The second additional sample shall include all the remaining items of the ten-year interval sample not examined in the initial or first additional samnle during this outago. If no items remain in the ten year interval sample (e.g., Accelerated Field Held Program) and indications were found t { in the first additional sample, a notification of snmple results shall be made to Site Engineering as described in Section 17.3.3. The ISI Programs representative shall submit the secord additional sample to the S00 Representative for addition to the scan plan. 17.3.3 Hptification of Sample Results to Site Encineering After completion of the second additional sample examinations, ASME Section XI code requirements for additional examinations are complete. If eraminations performed in the second additional sample reveal indications exceeding the corresponding acceptance l standards of INX-3000 of ASME Section XI, Site Engineering

• hall be notified.

Site Engineering shall be notilled to l avaluate the indications and make recommendation (s) for f urther action, if needed, within this and/or other r systems. This notification shall be cesc to the Site Engineering Operations Support by ISI Programs for coordination with the applicable Site Engineering staff. Included in the i notification should be a summary of the indications found, number of examinations and number of indications in each sample, type of examination performed, examination f, category and item number, copies of the NOIs, and any l A other pertinent information. 18.0 CORRECTIVE ACTION PROGRAM Any corrective action required as a result of ISI examinations shall be handled in accordance with SSP-3.4, SSP-3.6, SSP-3.7, or SSP-6.21, 4 lvA 40u4 (Nr:su 1401C/COC3 -. ~....

_ =. Seasdard Shecs SI-114.2 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 70 of 125 19.0 REQ 13STS FOR RELIEI Where TVA has determined that certain code requirements or examinations are impractical, TVA will submit written requests for relief to NRC with information to support the determinations and any proposed alternate examinations. The impractical code requirements or examinations shall be identified in this program, and references to particular requests for relief shall be included. When impractical examination requirements are identified in the field, ISO shall notify ISI Programs such that the information may be included in this program and requests for relief may be prepared if necessary. Requests for relief shall be submitted to the NRC via SON Site Licensing. Sequoyah Unit 2 Requests for Relief are contained in Attachment 3. p TVA submitted 14 Requests for Relief (ISI-1 to ISI-14) from Code requirements. ISI-1, ISI-3 to ISI-6, ISI-8 to ISI-10, ISI-13, and ISI-14 were granted. ISI-11 was withdrawn, ISI-12 was not needed, and ^ two, ISI-2 and ISI-7, were postponed. For more detailed information on Requests for Relief, see Safety Evaluation Report, dated February 7, 1991 from F. J. Hebdon, NRC, to 0. D. Kingsley, Jr. (A02 910211 001), and Safety Evaluation Report, dated April 19, 1990, from Suzanne Black, NRC, to O. D. Kingsley, Jr. (A02 900426 005). On August 21, 1991, TVA submitted Request for Relief ISI-15 to the NRC requesting a response by June 1, 1992. TVA has now identified three (3) other areas where code requirements are impractical. These Requests for Relief are identified as ISI-16, -17, and -18. These relief requests shall be submitted to the NRC with j Revision 16 of this program. 20.0 AUGMENTED INSPECTIOES Augmented inspections are performed in addition to ASME Section XI Code requirements. The augmented inspections may be required by the NRC or self-imposed by TVA. Augmented examinations of components that require reporting (verbal or written) to the NRC shall be the responsibility of the organization designated in the particular examination. These reports shall be submitted to the NRC Region II Office within the time period specified for each augmented examination. Each augmented exam shall state the required reporting time and the document requiring the information to be included in the report. See Table E of Appendix A for examination schedules. e 20.1 Feedwater Nozzle-to-Ploe Welds and Ad_iacent Pipe ard Nozzle Areas The requirements of NRC IE Bulletin 79-13 were satisfied during the Unit 2 Cycle 1 outage. Due to the safety-related ramifications of the steam generator nozzle transition section cracking problem, TVA will perform an augmented inspection (reference memorandums L29 831222 836 and L29 840105 856, and memorandum from D. F. Goetcheus to J. T. Lewis (S57 880902 911)) of four feedwater nozzle transition pieces during the inspection f ^ '"*' @# 1"U 1401C/COC3

_ = _ _ ~ - - - - -. _ - -. - - ~ _.___ { suJa;, sun SI-114.2 { ~ SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTI0N PROGRAM Page 71 of 125 interval as listed below. The augmented examination of the steam generator nozzle transition section shall include 100 percent I volume of the transition pieces, the nozzle-to-transition piece welds, transition piece-to-pipe welds, and base metal adjacent to I each weld for a distance of two wall thicknesses. These welds shall be ultrasonically examined, and ultrasonic sensitivities should be equivalent to those required by NRC-IE Bulletin 83-02. Results of the examination shall be included in the ISI Report discussed in Section 16.3. FEEDWATER N0ZZLE TRANSITION PIECE EXAM SCHEDULE Cycle Exaninstion Areas 1 IE Bulletin 79-13 completed 2 1 nozzle-to-pipe weld and adjacent pipe and nozzle area 3 All nozzle transition section pieces and welds 4 All nozzle transition section pieces and welds 5 All nozzle transition section pieces and welds 6 All nozzle transition section pieces and welds 20.2 RPV Nozzle Safe Ends The augmented examination requirements of the RPV nozzle-to-safe ~~ end welds are included in the final report " SON - Evaluation of cracking in reactor vessel nozzle stainless steel buttering." TVA reinspected nozzles 2RC-17SE and 2RC-24SE at the first regulatory scheduled cold shutdown outage. The examinations for Unit 2 will be monitored at the normal ISI intervals (see Section 7.1.5) for dissimilar metal welds as required by Section XI of the ASME Code. This augmented examination does not require a special report. Results of the examination shall be included in the ISI Report discussed in Section 16.2. t 20.3 Feactor Coolant Pump Flywheel The augmented examination requirements of the reactor coolant pump flywheel are included in Regulatory Position C.4.b of Regulatory Guide 1.14 (1) an in-place ultrasonic examination of the areas of higher stress concentration at the bore and keyway at approximately 3-year intervals during the refueling or maintenance shutdown coinciding with the ISI schedule as required by Section XI of the ASME Code, and (2) a surface examination of all i exposed surfaces and complete ultrasonic examination at 4 approximately 10-year intervals during the plant shutdown coinciding with the ISI schedule as required by Section XI of the j ASME Code. This examination is performed in accordance with Sequoyah Technical Specifications and satisfies Surveillance Requirement 4.4.10a. This augmented examination does not require a special report unless the ex&mination reveals a flaw. If the examination and L evaluation indicate an increase in flaw size or growth rate greater than predicted for the service life of the flywheel, the results of the examination and evaluation should be submitted to the NRC for evaluation.- Refer to Regulatory Guide 1.14 for 1 [A 4NM4 (NP 190 1401C/COC3

Luadard Sheet SI-114.2 SURVEILLANCE ASME SECTION XI Rayleion 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 72 of 125 Information to be included. The examination results shall be p.. included in the ISI Report discussed in Section 16.2, The flywheel consists of 2 plates, approximately 5 inches and j 8 inches thick, bolted together. Each plate is fabricated from i vacuum degassed A-533, GR. B, Class 1, steel. The 3-year in place RCP examinations shall be recorded using the 1 RCP motor serial number and exam ID: RCP Motor S/N - BOREKEY (i.e., 4S-81P352 - BOdEKEY) For the 10 year exam the ID's shall be: RCP Motor S/N - SUR (i.e., 4S-81P352 - SUR) f RCP Motor S/N - VOL (i.e., 4S-81P352 - VOL) See Augmented Examination Table Appendix A, Table E for RCP flywheel scheduled examinations. 20.4 Steam Generator Tubino IC.21 Steam Generator Maintenance and Technology (SGMT) shall be responsible for ensuring the adequacy of the technical and administrative requirements of this section. Refer to Technical 7 i Specifications Surveillance Requirement 4.0.5 and 4.4.5.0 and Sections 7.3.8 and 16.0 of this program for information to be included. Plant management shall report this information to the NRC Region II Office within the time period specified. See Plant Instruction AI-18 series for reporting instructions, a. Tube Plugging Report - Following each inservice inspection of stesm gener5+.or tubes, the number of tubes plugged in each steam generator-shall be reported to the NRC within 15 days of steam generator manway closure. b. Inservice Inspection Results Report - The complete results of the steam generator tube ISI shall be submitted to the NRC in a special report pursuant to Technical Specification 6.9.2 within 12 months following completion of the inspection (S/G l manway closure). Steam Generator Maintecance and Technology shall prepare this special report and submit the report to the NRC Region II Office within the stated time period. This special report shall include: 1. Number and extent of tubes inspected. 2. Location and percent of wall-thickness penetration for each indication of an imperfection. 3. Identification of tubes plugged. c. Category C-3 Feport - Results of steam generator tube if ^ #

1. U 1401C/COC3

SundarJ nect SI-114.2 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 73 of 125 = inspections which fall into Technical Specification Category C-3 require prompt notification of the NRC pursuant to Technical Specification 6.9.1 prior to resumption of plant operation. The vritten followup of this report shall provide a description of investigations conducted to determine cause of the tube degradation and corrsetive measures to prevent recurrence. 20.5 EEV. Nozzle Cladding All vessel nozzles cladding shall be ultrasonically examined at the end of each 10-year inspection interval, using techniques at least as sensitive as those used to conduct the supplemental examinations performed prior to fuel loading. These examinations 1 are performed during the automated reactor vessel nozzle 4 inspection. This examination is performed in accordance with SQN Technical Specifications and satisfies Surveillance Requirement 4.4.10b. This augmented examination does not require a special report. Results of the examination shall be reported to the NRC via the ISI Report discussed in Section 16.2. Nozzle forging material and cladding is identified in Section 7.1.2. 20.6 Steam Generator Feed Rina and J-Tubes Steam Generator Haintenance and Technology shall be responsible for ensuring the adequacy of the technical and administrative requirements of this section. The carbon steel J-tube nozzles have been replaced with Inconel 600 J-tube nozzles. This material is resistant to erosion corrosion damage. Inspection of the J-tube nozzles is not necessary. An ultrasonic thickness check of the feed ring header and tee shall be performed on a frequency of avory 10 years. This augmented examination is self-imposed by TVA (S01 860515 828) and does not require a special report. Results of the examination shall be included in the ISI Report discussed in Section 16.3. 20.7 Control Rod Guide Tube Flexures Mschanical Maintenance shall be reponsible for ensuring the adequacy of the technical and administrative requirements of this r section. Any revisions or waivers of this examination plan as l-- stated in this section shall be the responsibility of the Hechanical Maintenance Supervisor or his designee. e Due to the potential of intergranular stress corrosion craching of L guide tube flexures, the following control rod guide tube flexure augmented examination plan shall be initiated (see Westinghouse [ reference nemorandums A27 840123 022 and LO1 840723 035). The ( control rod guide tube flexures shall be visually examined in accordance with visual examination method VT-3 (see section 11.1) during each refueling outage. These exarinations shall be performed in accordance with SMI-0-68-15. At each scheduled refueling outage the tops cf all guide tubes shall be visually examined to assure that all fi zures are in their proper TVA 40004 (N? 2SI) IC01C/COC3

NasJasd Sheet SI-114.2 SURVEILLANCE ASH 2 SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 74 of 125 a orientation. If any flexure heads are discovered to be broken from their stems, the heads should be retrieved and flexureless inserts installed. If flerureless laserts are not lustalled after a break has occurred, a safety evaluation will be required to confirm continued safe plant operation. A copy of the VT data sheets shall be forwarded to the appropriate cognizant engineer. The PRISIM identifiers for the control rod guide tube flexures are: CRDTUBEFLEX - A07 CRDTUBEFLEX - E09 CRDTUaEFLEX - GOS CRDTUBEFLEX - J11 CRDTUBEFLEX - LO7 This augmented examination is self-imposed by TVA and does not require a report. Results of the examination shall be included in the ISI Report discussed in Section 16.3. 20.8 Rod Control cluster Assemb1v (PCCA).Claddinc Wear Measurements PWR Fuel Engineering shall be responsible for ensuring the adequacy of the technical and administrative requirements of this section. The RCCA rodlet cladding wear for both SON units has been examined via the eddy current measurement NDE technique. Encircling ccils were used for total area loss determinations and profilometry data taken to charactarize wear scars. SON Unit 2 RCCAs were inspected for rodlet cladding wear in February 1989. SON Unit 1 RCCAs were inspected in April 1990. Results uere documented (L38 890511 800 } and L36 901030 800). Summaries were provided f or the ISI Reports discussed in Section 16.2. Because TVA has cladding wear data for each unit's RCCAs and has implemented an axially repositioning program, RCCA inspections need only to be done periodically in the future when identified by PWR Fuel Engineering. When performed, the results will be i reviewed, the wear data bases updated, and specific repositioning plans revised as necessary. Any RCCA with excessive rodlet cladding wear will be replaced. l. RCCA wear examinations via NDE techniques are self-imposed by TVA and do not require a special report. An examination summary shall 'j be included in the ISI Report discussed in Section 16.3 whenever j the RCCAs are inspected for either SON unit. 20.9 AcceleraLgd Fleid Weld Program IC.11 - Complete In accordance with R. L. Gridley's January 30, 1987 memorandum to B. J. Youngblood (L44 670130 804), TVA committed to implement an {. Accelerated Field Weld Program for SON Units 1 and 2. This L augmented and accelerated program requires completion of 100 percent of ASME Class 1 and 2 piping, piping support, and I h 4xna (NP 91) i 1401C/COC3

s o Jua sher SI-114.2 SURVEILLANCE ASME SECTION XI Ravision 1C INSTRUCTION INSERVICE INSPECTION PROGRAM Page 75 of 125 La component (reactor vessel, steam generator, pressurizer, and !] reactor coolant pumps) support fiela welds that are in the first 10-year program in the two (2) consecutive refueling outages following restart. The Accelerated Field Weld Program was ccmpleted during the Unit 2 Cycle 4 refueling outage, see Request for Relief ISI-14. The results were included in the ISI Report discussed in Section 16.2. 20.10 Thimble Tube Guide Sice Engineering shall be reponsible for ensuring the adegeacy of the technical and administrative requirements of this section. Due to the potential thiuning of thimble tube guides as reported on NRC Bulletin 88-09 and Information liotice No. 87-44 supplement 1, TVA performed an augmented examination of the thimble tubes using Eddy Current Examination (ET) during the Unit 2 Cycle 3 refueling outage. See R. W. Forte nbe rry 's July 21, 1988 memorandum to S. J. Smith (S57 880721 821) and J. F. Murdock's June 3, 1988 memorandum to J. B. Hosmer (L29 880531 914'/. Future examinations shall be to examine all thimble tubes at each outage until a wear data base has been established. Results of the examinations shall be forwarded to Site Engineering. See P. G. Trudel's February 27, 1989 memorandum to M. J. Burzynski (B25 890227 002). Results of the exatirations shall be included in the ISI Report discussed in Sectisa 16.3. 20.11 Epamination of Piping Connected to the Reactor Coolant System Due to Thermal Stresses - Complete Due to the potential thermal stresses on unisolatable piping attached to the RCS (see NRC Bulletin 88-08), TVA has examined the L following areas:

1) the four 1.5-inch high head injection lines,

2) the 2-inch pressurizer spray line from the charging path,

{

3) the 3-inch alternate charging path, and 4) the 3-inch normal

["a charging path. All of the welds up to the first valve have been PT examined, and the 3-inch line has been UT examined as well. These examinations were conducted during Cycle 3 shutdown period. The SQN Project Engineer has prepared a report to Licensing, who in turn prepared a report to the NRC. (See memorandums B29 880906 008, S08 890230 843, L44 880824 802, and E25 880319 014.) 20.12 Eggmination of Pressuri.ter Surce Line Dut,to Occurrence of Thermal Stratificatio.D - Complete The requirements of IEB 88-11 were satisfied during the Unit 2 Cycle 3 refueling outage. The following paragraphs are being retained for historical information only.

• ^#*"' @'1*I 1401C/COC3

.-_ __ -= M3dard %Mtt SI-114.2 ) SURVEILLANCE ASME SECTION XI Rsvision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 76 of 125 rA Due to the thermal stratification of the pressuriser surge line (see NRC Bulletin 08-11) TVA performed a visual inspection on the pressurizer surge line. This examination should determine any gross discernable distress or structural damage in the entire pressut.ar surge line, including piping, pipe supports, pipe whip restraints, and anchor bnits. This examination was scheduled and performed per SMI-0-68-4. The results of the examination are to be coordinated in accordance with SMI-0-68-4. NE Operations Support submitted the resul's of the examination to Nuclear Technology and Licensing for submittal to the NRC within 30 days af ter completion of the examinations. 20.13 Examination of Row 1 and Row 2 of the Steam Generatara Steam Generator Maintenance and Technology shall be responsible for ensuring the adequacy of the technical and administrative requirements of this section. The following augmented examinations requiroments are self imposed by TVA and, therefore, do not require a special report. However, they shall be included within the report to NRC specified in Section 20.4. This augmented examination is being performed to satisfy the requirements in the recurrence control of CAQR No. SQP880312. nonpluggtd and nonheat-treated Row 1 and 2 U-bend regions i shall be examined by rotating pancake coil eddy current examinations during each scheduled Inservice Inspection of S/G g tubing. The probe type utilized shall have been qualified for the detection of U-bend primary water stress corrosion cracking. 20.14 Examination of Base Material Transition Adjacent to Weld No. 2.BC-023 On RC Puy No. 3 Cold Leg ( This augmented examination is being performed to satisfy the requirements of CAQR No. SQP890138. The base material adjacent to Weld No. 2RC-023 on the RC Pump f No. 3 cold leg nozzle shall be 11guld penetrant (PT) examined. The inspection area shall include a distance of two inches from the edge of the pipe weld toward the nozzle. The inspection area shall cover the 0*-90' azimuth of Quadrant I, with the orientation viewed from the cold leg nozzle of the pump. a The PT examination will be performed during the Unit 2 refueling outage for Cycles 4, 5, and 6. The results of the examinatior. will be submitted to Sequoyah Nuclear Engineering (Project Engineer) by S00 for evaluation and flaw growth comparison in accordance with Table IWB-3518-2. Any revisions or waivers of this examination plan shall be approved by Nuclear Engineering. ~ \\ vA 4&m4 (Nr zw; 1401C/COC3 w -w ._w. ._pw -r. y 4

suv1,ed sb,ce SI-114.2 j SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROG.*W. Page 77 of 125 This requirement has been added at the requast of a memorandum g. from P. G. Trudel to L. E. Martin dated April 17, 1989 (B25 890417 024). J ] The PRISIM identifier for base material adjacent to Weld No. 2RC-023: RCP3BM-2RC-023. The results of this examination shall be included in the ISI

f..

Report discussed in Section 16.3. i I 20.15 Main Feedwater Isolation Valves + 1. Site Engineering shall be responsible for ensuring the adequacy of the technical and administrative requirements of this section. Due to the bonnet iLdications found by previous inspections, MFIVs I> I' 2-FCV-3-33, -47,-87, and -100 shall receive an at.gmented magnotic particle (MT) examination during the following Unit 2 scheduled refueling outages: [ _

• ) nit 2 Cycle 5: Examine 2-FCV-3-47 an1 -87 Unit 2 Cycle 6:

Examine 2-FCV-3-33 and -100 The bonnet indications were determined not to be service related and were identified as artifacts of the casting process used to produce the valve bonnets. The purpose of the reexamination is to verify that no progression of the damage is occurring. The examinations shall be performed in accordance with the followings i The results of the magnetic particle examination will be a. compared to the previous examination record for evidence of propagation based on the measured length of the indication. If the indication seems to have grown, the ends ok the indication will be examined optically either in. situ or by replication and laboratory examination for evidenca of growth. l L b. If measuring the indication shows growth but no evidence of crack extensions can be visually seen, the ends of the indication shall be stenciled with a low stress punch, and the \\;j bonnet or body shall be reinspectJd in the following outage. If there is definite evidence of crack propagation based on c. visual inspection, it shall be refstred to Site Ecgineering n' (Mechanical / Nuclear). Engineering H'1 evaluate the condition and recommend that the bonnet or boc, affected be weld repaired or replaced, as necessary. "Defin3te evidence" is considered to be fatigue-type cracking emanating from the end i of the previous indication or stress corrosion cracking. In either case, the propagated cracking would be free of the high temp.iratura corrosion product present in the previous examination ( d. If thers is no evidence of growth associated with the i reinspection, no further inspection is required. , ~ A 40C04 (NP 191)

StoderJ SNet SI-114.3 SURVE8LLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 78 of 125 This augmented examination is self-imposed by TVA (B25 891228 008) and does not require a rpecial report. Results of tbc j examinations shall be ferwarded to Site Ennineering (Mechanical / Nuclear) for their evaluation and/or disposition by S00. The results shall be incJuded in the ISI keport discussed in Section 16.3. 21.0 INTERFACE DOCUMENTS 21.1.1 Quality Methods Procedure: QMP-102.4, Qualification and Certification Requirements for NOA NDE Personnel 21.1.2 Quality Methods Procedure: QMP-110.5, Nondestructive Examjustion erocedures Approved for Use on CSSC Items at All Nuclear Plants 21.1.3 Quality Methods Procedure QMP-105.4, Control of Calibration Blocks. 21.1.4 Lequoyah Nuclear Plant Administrative Instructions AI-8, AI-18 (Series), AI-19 (Part IV and Part VI), and AI-56. 21.1.5 Sequoyah Nuclear Plant Site Standard Practice SSP-2.9, SSP-3.1, SSP-3.4, SSP-3.6, SSP-3.7, SSP-6.21, SSP-7.2, SSP-8.2, SSP-12.8, and SSP-13.3. 21.1.6 Sequoyah Nuclear Plant Technical Instruction TI-89. 21.1.7 Sequoyah Nuclear Plant Special Majutenance Instructions, { SMI-0-68-04, and SMI-0-68-15. 21.1.8 Sequoyah Nuclear Plant Maintenance Instructions 0-MI-MRR-068-005.0, MI-1.4, 0-MI-MXX-068-004.0, 0-MI-MXX-068-003.0, MI-2.2, MI-10.2.2, MI-10.2.3, MI-6.15, 0-MI-MVV-000.008.0. I k 22.0 DEVELOPMENTAL REFERENCES 22.1.1 Memorandum from D. W. Wilson to N. L. Abercrombie, dated August 1,1986 "Sequoyah Nuclear Plant, Units 1 and 2, " Indications in Class 1 Welds" (L18 860730 899). f 22.1.2 Memorandum from V. A. Blanco to C. R. Brimer dated January 10, 1987 (B25 870109 045). l $2.1.3 Menarandum from G. C. Zech to S. A. White dated January 25, g I' l Lj 1988 allowing use of code cases N-341 and N-356. l 22.1.4 Memorandum from P. G. Trudel to M. J. Bur 2ynski dated l February 27, 1989 (B25 890227 00L). l 22.1.5 Memorandum from R. L. Gridley to B. J. Youngblood dated l January 30, 1987 (L44 870130 804). l l IVA On4 (NP 2S1) 1401C/COC3 u- ~ e ..n,,~r.- m

Staodard SDart SI-114.3 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 79 of 125 22.1.6 pg NRC Bulletin 88-09 and Information Notice 87-44 supplement 1, " Thimble Tube Thinning in Westinghouse Reactors." 22.1.7 Memorandum from R. W. Fortenberry to S. J. Smith dated July 21, 1988 (S57 880721 821). 22.1.8 Memorandum from J. F. Murdock to J. B. Hosmer dated June 3, 1988 (L29 880531 914). 22.1.9 NRC Bulletin 88-08, " Thermal Stresses on Piping Connected to Reactor Coolant Systems." 22.1.10 NRC Bulletin 88-11, "Pr6ssurizer Surge Line Thert 21 Stratification." 22.1.11 Memorandum from D. F. Goetcheus to J. T. Lewis dated September 2, 1988 (S57 880902 911). 22.1.12 Letter from S. C. Black to 0. D. Kingsley, Jr., dated January 18, 1990, " Nuclear Quality Assurance Plan" (TAC No. 72833), allowing the use of 1984 Edition of ASNT. SNT-TC-IA for certification of NDE personnel. 22.1.13 Memorandum from P. G. Trudel to L. E. Martin dated April 17, 1989 (B25 890417 024). 22.1.14 Memorandum from S. C. Black to 0. D. Kingsley, Jr., dated December 1.',,1989, allowing the use of Code Case N-460. [! 22.1.15 Memorandum from F. J. Hebdon to 0. D. Kingsley, Jr., dated February 7, 1991 (A02 910.41 001). 22.1.16 Memoraadum from S. C. Black to 0. D. Kingsley, Jr., dated April !9, 1990 (A02 900426 005). I 22.1.17 Menorand v. from P. G. Trudel to R. L. Lumpkin, Jr.. dated [ December 28, 1989 (B25 891228 008). (; 22.1.18 Memorandum from G. J. Pitz1 to G. L. Belew, dated January 5, [) 1984 (L29 840105 856). 22.1.19 Memorandum from T. F. Ziegler to R. C. Parker dated December 27, 1983 (L29 831222 836). %2.1.20 NRC Bulletin 83-02, " Stress Corrosion Cracking in Large-Diameter Stainless Steel Recirculation System Piping at BNR Plants." .i 22.1.21 NRC Bulletin 79-13, " Cracking in Feedwater System Piping." 22.1.22 Memorandum from D. F. Goetcheus to G. L. Belew dated May 15, 1986 (S01 860515 828). 22.1.23 Memorandum from R. S. Howard, Westinghouse, to J. P. Darling dated July 9, 1984 (LO1 840723 035). \\VA 4N34 (NP 190 1401C/COC3

{ ud Skes SI-114.2 Ci?VEILLANCE ASME SECTION XI Revision 16 INSTRUCTIOL INSERVICE INSPECTION PROGRAM Page 80 of 125 22.1.24 l Memorandum from J. L. Tain, Westinghouse, to J. A. Raulston dated January 19, 1984 (A27 840123 022). 22.1.25 Memorandum from W. E. Pennell to R. A. Sessoms dated August 10, 1987 (B41 870810 003). 22.1.26 Memorandum from J. A. Kirkebo to Site Directors dated June 24, 1987 (L29 870528 815). 22.1.27 Memorandum from J. A. Domer to NRC dated June 17, 1985 (L44 850617 801) 22.1.28 Memorandum from J. L. Wilson to NRC dated Au7ust 21, 1991 (S10 910821 848). i' 22.1.29 Memorandum from R. R. Calabro to Those listed dated May 16, 1989 (L38 890511 800). 22.1.30 Memorandum from R. R. Calabro to Those listed dated October 30, 1990 (L36 901030 800). 22.1.31 Memorandum from P. G. Trudel to M. J. Ray dated September 6, 1988 (B29 880906 008). 3, 22.1.32 Memorandum from L. E. Martin to P. G. Trudel dated August 30, 1988 (SOS 880830 843). 22.1.33 Memorandum from M. J. Ray to NRC dated August 24, 1988 (L44 880824 802). 22.1.34 Memorandum from P. G. Trudel to S. J. Smith dated August 19, 1988 (B25 880819 014). 22.1.35 Instruction Manual - 173-inch ID Reactor Pressure Vessel - Rotterdam Dockyard Company, Contract No. 68C60-91934, H2M-2-3. L. 22.1.36 Westinghouse Technical Manual - Pressurizer, TM 1440-C225, Contract No. 68C60-91934, H2M-2-0. p) 1 22.1.37 Westinghouse Technical Manual - Vertical Steam Generators, TM 1440-C224, Contract No. 68C31-91934, N2M-2-4. 22.1.38 Westinghouse Instruction Manual - Auxiliary Heat Exchangers, Contract No. 68C60-91934, N2M-2-25. e 22.1.39 Westinghouse Instruction Book - Reactor Coolant Pump, Contract Mo. 68C60-91934, N2M-2-5. 22.1.40 Ingersoll-Rand Instruction Manual - Residual Heat Removal Pumps, Contract No. 68C60-91934, N2M-2-30. '1 I] 4M34 (NP r*O 1401C/COC3

9 m. r r-~ {

== _pp%.-. Y APPENDIX A f b TABLE A h( g SEQUOYAH INSERVICE INSPECTION PROGRAM ] CLASS 1 COMPONENTS m s gg Program Section XI MM CH Reference Eram Exam .'t Insp. Interval Inspection Periods Reference

• 1 n ta Cemeonent Section Method Cate.corv 40 Yr. Samole Sample 3 vrs. 7 vrs.10 vrs.

Dw. No. g g A. Reactor Vessel to I

1. Circumferential 7.1.1.1 UT B-A 4/50 ft.

4/50 ft. 0 0 4 ISI-0298-8 Shell Welds

2. Closure Head 7.1.1.3 UT B-A 41 ft.

41 ft. 13 ft. 14 ft. 14 ft. ISI-OiO1-A Cire Weld g w i

3. Lower Head 7.1.1.4 UT B-A 38 ft.

38 ft. 0 0 383 ft. 151-0298-8 gg Cire Wald tog 5 tn

4. Lower Head 7.1.1.6 UT B-A 6/4 ft.

6/4 ft. 0 0 6/4 ft. 15I--0298-B y t9 Me rldlonal 29O Welds 0, o

5. Shell-to-Flange 7.1.1.7 UT B-A 50 ft.

50 ft. O ft. O ft. 502 ft. 151-0298-B w 2: M Weld y i M 8

6. a. C1csure Head-7.1.1.8 UT B-A 45 ft.

45 ft. 15 ft. 15 ft. 15 ft. ISI-0301-A h to-Flange Veld

b. Closure Head 7.1.1.8 MT B-A 45 ft.

45 ft. 0 0 45 ft. ISI-0301-A to Flange Flex Area EN

7. Nozzle-to 7.1.2 UT B-D 8

8 43 0 1 4 Inlets ISI-0298-h j <, 4 i Versel Welds Outlets (Bore & ISI-0297-A , m H, (Bore) Shell ID) ISI-0392-A g H g *g 4 Outlets 0 3 y (Shell ID) o o n u I The four outlet nozzle-to-norale welds examination from the vessel shell shall be done in the third inspection period. us t 2See Request for Relief ISI-10 3See Request for Relief ISI-5

^ g-a, ( g f APPENDIX A E-TABLE A z SEQUOYAH INSERVICE INSPECTION PROGRAM k 3 b CLASS 1 COMPONENTS wm E@ = H< Program Section XI se n Reference Exam Enam ist Insp. Interval Inspection Periods Reference Component Section Method Cateoorv 40 Yr. Samole S ample 3 vrs. 7 vrs.10 vrs. Dwo. No. @n w n A. _Rg3ct or V_essel (Cont'd) 4

8. Inside Radius 7.1.3 UT B-D 8

8 4 0 8 (4 Inlets ISI-0298-8 Sections Uutlets 4 Outlets) 151-0008-B (includes integral ISI-0392-A entensions on the ISI-0297-A y outlet nor:1es) "o

9. Vessel Pene-7.1.4 VT-2 3-E 141 37 12 12 13 ISI-0097-C trations and ISI-0319-C M@

Attachments

• "n m

10. Nozzle-to-Safe 7.1.5 UT, PT B-F B

8 .I O 4 151-0298-8 "g

• o End Ve'.ds w

Outlet Inlet OM

11. Closure Studt 7.1.6 UT. MT B-G-1 54 54 18 18 18 15I-0304-B and Puts 7.1.6 MT 3-G-1 54 54 il 18 18 151-0304-8 E

O

12. Ligaments 7.1.6 UT B-G-1 54 54 18 18 18 15I-0304-8 Between Threaded Stud Holes

13. Closure Washers 7.1.6 VT-1 B-G-1 54 54 18 18 18 151-0304-B

14. Vessel Interior 7.1.9 VT-3 B-N-1 1

1 1 1 1 151-0293-B 7y" ibb

15. Removal Core 7.1.10 VT-J B-N-3 See Program Section 7.1.10 w

Support Structure mE% "0 Q nM WH O O Nw

- ~.. . ~ L __i 'w q_.

m. _..

i . o-. g APPENDIX A TABLE A .E, -z SEQUOYAH INSERVICE INSPECTION PROGRAM } CLASS 1 COMPONENTS g, k gQ = HA Program Section XI wM Cp Reference Enam Exam ist Insp. Interval Inspection Periods Reference h Comoonent Sect *on Method Cateoorv 40 Yr. Sample Sampie 3 vrs. 7 vrs.10 vrs. Dwe. No. @n M A. Reactor Vessel (Cont'd)

16. Control R"'

7.1.11 UT B-O 2 2 0 1 1 ISI.0097-C Drive Hous.:gs ISI-0?00-A i

17. RV Aux Head 7.1.12 UT, PT B-F 4

4 1 1 2 ISI-0097-C y ~ Adapters !!I-0318-A g B. Pressurizer Eww nM N 1. Ci rcumferential 7.2.1 UT B-B 2/24 ft. 2/24 ft. 12 ft. 12 ft. 24 ft. ISI-0396-C ym Shell-to-Head mn Welds O" O wo 2. Longitudinal 7.2.2 UT B-B 2/1 ft. 2/1 ft. II O II -= ISI-0396-C @g Shell-to-Head w Welds

• o o

3. Nozzle-to-Vessel 7.2.4 UT B-D 6 6 2 2 2 ISI-0396-C y w Welds and Inside Radius Section 4 Heater 7.2.5 VT-2 B-E 78 20 6 7 7 ISI-0309-A Penetrations ao w m oaw e<s O 5 7.* i 2 o"" 8 0 0 = I The one foot of longitudinal weld selected for examination is that section of weld intersecting t's circumferential shell-to-head weld examined. c

~ 7,. r-yJ i U W es L..-.~ ~- S I E APPENDIX A h TABLE A '2 SEQUOYAH INSERVICE INSPECTION PROGRAM k d m CLASS 1 COMPONENTS e# Program Section XI Cy Reference Enam Exam 1st Insp. Interval Inspection Periods Reference Cteoonent Section Method Cateaorv 40 Yr. Samole Samrie 3 vrs. 7 vrs. 10 vrs. Dwo. No. @ n B. Pressurizer (ContH) 5. Noz zle-to-Safe 7.2.6 UT, PT B-F 6 6 2 2 2 ISI-0396-C End Welds 6. Pressure 7.2.8 VT-1 8-G-2 1 mwy/ 1swy/ 16 0 0 151-0299-8 E Retaining Bolting 16 bolts 16 bolts E 7. Integrally 7.2.9 MT B-H 23 ft. 23 ft. 7 ft. 8 ft. 8 ft. ISI-0396-C Welded Support "N Skirt E" E 8. Seismic Lugs 7.2.9 MT B-H 4 4 0 0 4 ISI-0395-C O" 4 wo l C. Steam Generators w= Ex w 1. Primary 7.3.2 UT B-B 4/36 ft. 4/36 ft. 1 1 2 ISI-0401-C Head-to-Tube O Sheet Weld E 2. Primary Nozzles 7.3.3 di B-0 81 1 I 8 0 4 41 ISI-0401-C Inside Radius Section 3. Primary Nozzle-7.3.4 UT. PT B-F 8 8 2 3 3 ISI-0401-C EEU to-Safe End Welds $$w w a0a 4. Pressure 7.3.6 VT-1 8-G-2 4 gens./2 wy 8 swy 2 2 4 151-0299-B ^ E 'u E Retaining Bolting kw N O 5. Tubing 7.3.8 ET B-Q See Program Sections 7.3.8 and 20.4. ISI-0398-C w" w I See Program Section 7.3.3. and Request for Relief 151-6.

. - = b L., i - W u 'I E g APPENDIX A h lf TA5LE A -2 v-SEQUDYAH INSERVICE INSPECTION PROGRAM h wm CLASS 1 COMPONENTS $0 l Program Section XI. E. Reference Exam Exam 1st Insp. Interval. Inspection Feriods Reference w" Component Section Method Cateoorv 40 Yr. Sample Sample 3 vrs. 7 v rs. 10 v rs. Dwo. No. O i M D. Pipino t t i 1. Pressure Retainino Boltina i

a. Reactor Coolant 7.4.3.1 VT-1 B4-2

'54 Sets 5 Sets 0 2 3 ISI-0013-C 4 4 System "z i m l M

b. Chemical and 7.4.3.2 VT-1 B-G-2 4 Sets /4 Bolts 4 Sets 1

1 2 MSG-0008-C O l Volume Control I nE I System (SWI) "6 w

• J$ M

c. Safety 7.4.3.4 VT-1 B-G-2 4 Sets /4 Bolts 4 Sets 1

1 2 ISI-0002-C E" injection System MO 0o 2. Ci rcumferential w= Ox Welds 'o i M o

a. Reactor' 7.4.4,1 UT/PT B-J 62 175 5

75 5 ISI-0008-B O [ Coolant System [ Main Loops Cires 24" { I

b. Reactor Coolant System Cins 14" IES I

Nom. Size 7.4.4.2 UT/PT B-J 66I 162 5 5 6 ISI-0318-A $10 t i .w Cires <4* ISI.-0013-C as E % l. 20 3 1 Nom. Size 7.4.4.2 PT B-J 1 53 1 1 3 ISI-0013-C

• E" w

w o o N 1S1-0008-B mw n o t i 8 I w The change in weld numbers during the second pericd was due to new code class boundaries. 2The change in weld numbers due to the removal of the UHI system in U2C4. 3The change in weld numbers second period due to RfD MOD U2C4-I j dihe change in bolted connections was due to U2C4 RTD N00. [ j Sihe second inspection period sample was increased by one weld which was due to the substitution of Weld RC-33 for j SIF-128 (see RrR ISI-3). t

m. m .m ( '?' ' '} 't YY f APPENDIX A' 4 .h t1 TABLE A h 3 L3 SEQUOYAH INSERVICE INSPECTION PROGRAM 5 l[ CLASS 1 COMPONENTS wm i 's E$ i l W ;ll Program Section XI C* O{" Reference Exam Exam ist Insp. Interval Inspection PerioA Reference Comoonent Section Method Cateoorv 40 Yr. Samrle Sample 3 vrs. 7 vrs. 10 vrs. Dwo. No. @n w n D. Pipina (Cont'd) i

c. Chemical and i

Volume Control System Cires 14" Nom.' Size 7.4.4.3 N/A E, Cires <4" M i Nom. Size 7.4.4.3 PT 8-J 60 151 4 5 6 ISI-0009-C E MSG-0008-C n5 "5

d. Residual Heat z" m Removal System Cires 14" l.

Nom. Size 7.4.4.4 UT/PT B-J 45 11 3 4 4 ISI-0003-C E o t

• M

e. Safety

.o " I Injection E l System Cires O } 14" Nom. Size 7.4.4.5 UT/PT B-J 721 1 4 17

• 4 5

6 6 ISI-0002-C' E Cires <4" Nom. Size 7.4.4.5 PT B-J 38 10 3 4 3 ISI-4002-C 3 t L

• o w m 4

or aw g o.* a 8n Onp I n The change in weld numbers during the second period was due to new code class bounhries, w 8 2 The change in weld nur.bers due to the removal of the UNI system in U2C4. U 3The change in weld numbers second period due to RTD MOD U2C4 4 The first inspection period sample was decreased by one weld which was due to the substituttor. of Weid RC-33 for SIF-128 U ?e RFR 151-3). . - - - -. ~ 4

3 r- -, ' f.. j. r- % gy. y = u 3 n 1.. p APPENDIX A Et TABLE A N 9 SEQUOYAH INSERVICE INSPECTION PROGRAM .k. 4 w-} CLASS 1 COMPONENTS E$ gn H< sq M Program Section XI fE Reference Enam Enam 1st Insp. Interval Inspection Periods Reference Component Section Method-Cateaorv 40 Yr. Sample Samole 3 vrs. 7 v rs. 10 vrs. Dwa. No. @n w M j. D. Ploing (Cont'd) l

f. RV Aun Head Adapter Cap 2

-Welds (UHI '1. Caps) "2; j Cires J. 4" 7.4.4.6 These welds are examined as a part of the RC System. Section 7.4.4.2. due to the U2C4 N -i M00. l i 55' 3. Branch Ploe M% [ Connection } Welds Ew y" 1 mO l I

a. Reactor Coolant gw O

y System - Main @x Loop Welds y" >2" Nom. Size 7.4.5.1 UT/PT B-J 1 1 0 1 0 -151-0008-8 { Welds 12". E' j Nom. Size 7.4.5.1 PT B-J 13 4 1 ? 2 151-0008-8 E I l

b. Reacter Coolant System Welds-ISI-0008-B jf

>2" Nom Size 7.4.5.2 UT/PT B -J 6 2 0 1 1 ISI-0013-C l l Welds'12" ISI-0008-B Nom. Size 7.4.5.2 PT B-J 7 21 0 1 1 ISI-0013-C @ 5' E i '$ LO uw .o O es u i n O l N es,w o l O y n N, w n I The change in weld numbers during the second period was due to new code class boundaries. i ~ 1 I

3 Q ~. t ~ ~}*, ~ ~~ 't 4 APPD' DIX A H TABLE A u-k u SEQUOYAH INSEkv CE U!SPECTION PROGRAM m 9 el CLASS i COMPONENTS NN C$ Program Sectior. XI Reference Enam Exam ist Insp. Interval Inspection Periods Reference Com onent ._. _.Section Meth d Catecorv 40 Yr. Samole Samole 3_yn. 7 v rs. 10 v rs. Dws. No. @n _2 M D. E}pj.cg (Cont'd)

c. Chemical and l

Volume Control l System Welds >2" Hom. Sire 7.4 *i.3 UT/PT B-J 3 1 0 0 1 ISI-0009-C m Welda 12" ISI-0013-C Q Nem. Size 7.4.5.3 PT 1-J 1 - See Note 1 n5

d. Residual Heat 5m Recoval y"

System Welds >2" Nom. Size 7.4.5.4 UT/PT 2-J 3 1 0 1 0 ISI-.0003-C O Welds 12" ISI-0003-C Noci. Size 7.4.5.4 PT B-J 2 - See Note 1 o

e. Safety O

Injection System Welds >2* Nom. Size 7.4.5.5 UT/PT 8-J 5 1 0 1 0 ISI-0002-C Welds 12" Nom. Stre 7.4.5.5 PT B-J 11 2 1 1 0 ISI-0002-C m to m EIY

• r :A

= i. wo. s ts w ao >% Ha n H s n m oo" IExaminations not scheduled this interval. .I t

,~ ;-- r q 1 '~ f . Ls 8' APPENDIX A v = E 1 Y TABLE A t c. 3 g SEQUOYAH INSERVICE INSPECTION PROGRAM 3 . '} ' I um 4 CLASS 1 COMPONENTS } O H <: Program Section XI WM Reference Euam Exam 1st Insp. Interval Inspection Periods Reference Comoonent Section Method Cateaorv 40 Yr. Samole Sample 3 vrs. 7 vrs. 10 vrs. Dwa, No. @n s M D. Pipinr1 (Cont'd) 4 Socket Welds 70 *I-

a. Reactor 7.4.6.1 PT B-J 1

18,2,3 0 15 3 151-0008-8 1 Coolant ISI-0013-C E System "m=

b. Chemical and 7.4.6.2 PT B-J 2401 60,3 18 42 U

MSG-0003-C 1 Volume Control om ISI-0009-C System wzm mm

c. Residual Heat 7.4.6.3 PT 8-J 18 53 "G

m 1 4 0 ISI-0003-C Removal System w U M z o 1 zM

d. Safety 7.4.6.4 PT B-J 1711 43,3 14 20 0

ISI-0002-C m" Injection System O m 5 m=m oow $bb m"%

• 8L Nn o

I The change in weld numbers during the second period was due to new code class boundaries. mw n O 2 p Change in weld number in second period was due to RTD N00 in U2C4. 3Change in number scheduled during the second and third period due to accelerated FW Program.

[~ ~' T ~~' i 1 -2> r d h! APPENDIX A-TABLE A .h [ SEQUDYAH INSERVICE' INSPECTION PROGRAM, h .g CLASS 1 COMPONENTS' NN _ Program Section XI. E. Reference ~ Exam Exam 1st Insp. Interval ' Inspection Periods Reference

y Comoonent Section Method Cateoorv 40 Yr. Samole -

samole 3 vrs. 7 vrs. 10 vrs. Dwo.'No @n u M= D. Pigirig (Cont'd) 5. Pipino and Valve Inteorally Weldgd lypoort Members g 1 z 5,2 1 5 2.4 2 3 0 MSG-0013-C N

a. Reactor 7.4.7.1 PT B-K-1 Coolant E

System M$ "N

b. Chemical and 7.4.7.2 PT B-K-1 1

1 0 1 0 MSG-0015-C , E cn Volume Control System . O" o -z.

c. Residual Heat 7.4.7.3 PT B-K-1 33 3

3 *4 0 3 0 MSG-0010-C @g t Removal System .o - wo:

d. Safety 7.4.7.4 PT B-K-1 61 I6 '4 1

5 0 MSG-0009-C Injection System 5EN .i 1b eE% w I The change in support numbers during the second period was due to new code class boundaries. O@*y M 2Change in integral attachment in second period was due to RTD MOD U2C4. Ew g 3Change in integral attachments in second period due to RhR support MOD in U2C4. p 4Change in number scheduled during the second and third period due to accelerated FV Program. t ?

{~7 T ~, Ji-. ~~ -~- g_ 's APPENDIX A-g- .f t.. . TABLE A I 9 SEQUOYAH INSERVICE INSPECTION PROGRAri } CLASS 1 COMPONENTS ' Hm E@ wN n Program Section XI C "e n Reference ! Exam ' Exam 1st Insp. Interval Inspection Periods Reference d Comoonent Section Method Cateaorv 40 Yr.' Sample Samole '3 vrs, 7 vrs. 10 vrs. Dwo. No. '@n-M D. Ploina (Cont'd) 6. Pipina and Valve Component Supports 50 e2 ~

a. Reactor 7.4.8.1 VT+3, B-K-2 I

1 50,2,5 0 50 0 MSG-0013-C y ~ Coolant VT-4 M System <5$

b. Chemical and 7.4.8.2 VT-3,

.B-K-2 1302 2 130 5 38 92 0 MSG-0012-C ~ ' Volume Control VT-4 "z m i System MO gH

c. Residual Heat 7.4.8.3 VT-3, B-K-2 15 -

155 4 11 0 MSG-0010-C Removal System VT-4 0 .z H + o j

d. Safety 7.4.8.4 vi-3, B-K-2 91,3 gj2,3,5 27 64 0

MSG-0009-C E 2 ' Injection VT-4

• w System

e. RCS Main 7.d.8.5 VT-3, B-K-2 72 275 0

7 0 ISI-0302-C Looping Piping VT-4 ISI-0321-B j o'o w m r e M.. e<e. .e w w l w o05 IChange in supports due to RTD 100 in U2C4. y g 2 u The change in support numbers during the second period was due to new code class boundaries. .S w A 3Eight of the supports examined in the first period as CC-1 are now CC-2. w' * ' 8 dChange in supports due to RHR support HDD in U2C4. 63 5Change in number scheduled during the second and third period due to accelerated fW Program. ,i -n

' pm c, g-(pg . 4 w w. w 4 g APPENDIX A r. [ t 4. TABLE A ) 3, SEQUOYAH INSERVICE. INSPECTION PROGRAM-V- e Hm 1 CLASS 1 COMPONENTS n mw l NN Program Section XI: hE- + Reference Exam. -Exam .lst Insp. Interval. Inspection Periods Reference Component Section Method 'CabooEy 40 Yr. Samole Samole 3 vrs. 7 vrs.10 vrs. Dwo. No. kn w I M' E. Reactor Coolant Pumps ( ). Pressure-7.5.1 UT B-G-1 96 24 24 48 151-0307-8 Retaining Bolting B-G-1 See Note 1 15!-0307 8 ~ g I 2. Pressure-7.5.1 VT-II Retaining MTI E l Bolting Deferral to end of interval is ' permissible when bolts are removed 5 $' i "N-3. Pressure-7.5.2 .VT-1 BE-2 4 Sets /1 Set 4 sets I set 1 set' 2 sets ISI-0307-8 5m Retaining Bolting O" o i m 2. 4. Integrally-7.5.3 PT B-K-1 3 pumps /3 feet 9 feet 3 3 3 151-0326-8 - Eg Weldea Supports per pump Mg 5. Component 7.5.4 VT-3, B-K-2 4 pumps /3 feet 12 feet 3 3 6 151-0326-B O Supports per pump (1 pump) (1 Pump) (2 Pumps) k a 6. Casing 7.5.6 VT-1 or B-1.-2 4 See Program Section 7.5.6, 7.9 and RFR ISI-1 151-0307-8 4 (UT and I VT-2). awm c wam $bb w oE5 ao wo. u ts u n o' t sg yWhen disassembled, bolt's shall be magnetic particle examined; threads in the base material and flange ligaments nH a g between threaded bolt holes shall be visually examined. g m t h -v -+#

p p, .~ ,, y .g. i E.. APPENDIX A I TABLE A I' 9 SEQUOYAH INSERVICE INSPECTION PR GRAM ( Hm el CLASS 1 COMPONENTS E@ b Yh _ Program 'Section XI Reference Exam Exam ist Insp. Interval Inspection Periods ' Reference w Comoonent Section' Method Cateaorv 40 Yr; Samole Sample 3 vrs. 7 vrs. l') vrs. Dwa.'No. @n M F. Valves 1. Pressure Retaining Bol ting E 3,3 2 23,3 0 0 3 151-0013-C N

a. Reactor 7.6.2.1 VT-1 B-G-2 Coolant System E'55 i

b. Chemical and 7.6.2.2 VT-1 B-G-2 03 03 0

0 0 ISI-0009-C Volume Control 5 'm System i

c. Residual Heat 7.6.2.3 VT-1 B-G-2 6

6 1 2 3 ISI-0003-C E Removal System EH

• o "

14 '3 - 1 14,3 4 6 4 ISI-0002-C 5 1

d. Safety 7.6.2.4 VT-1 B-G-2 Injection System 2.

Integrally 7.6.3 PT B-K-1 Totals are included in D.5 of this table. Welded Support Members 3. Component 7.6.4 VT-3, B-K-2 Totsis are included in D.6 of this table. EEE [ Supports VT-4 $1b e05 w 8 "8L 5 R-I n In the second period 4 of the CC-1 valves became CC-2, two of which were examined in the first period, e 8 2 rd period due to U2C4 RTD N00. Changes in the 1 e 3Changes in the third period due to use of Code Case N-426.

m ~y k. .a ~' y g Q -a i -~ I. APPENDIX A' k, TABLE A . 'z ' l .SEQUOYAH INSERV!CE INSPECTION PROGRAM. ir b CLASS 1 COMPONENTS sm 2 0 5@ H4 Program 'Section XI -wM E Reference Exam-Exam ist Insp. Interval Inspection Periods Reference Component Section Method - Cateoorv ' 40 Yr. Samole Sa_mple 3 vrs; 7 vrs.10 vrs. Dwa. No. On s M F. Valves (Cont'd) 4. Valve Bodies 7.6.6 VT-1 B-M-2 See Table 1 of. Attachment 2. >4" N.P.S. G h11El 7.9 VT-2' B-P See Program Section 7.9. H Pressure Tests tn M M n Ci w 'Mg s -- = D1 5 Cn M M 4a - =.. t U s g a s MO C1 M = t NM D 9 H tQ < I y e >== w , 8 CW 4

• O
• o o.O N

N O 'M N o m 0 p~ m e

i v:l~ 4. -~a a' C + ? w d g APPENDIX A g. { TABLE B x" 3 SEQUOYAH INSERVICE INSPECTION PROGRAM k j CLASS 2 COMPONENTS wm-i~ .o g. Program' Section XI @p Reference Exam ' Exam 1st Insp Interval' Inspection Periods Reference d Comoonent Section Method Cateoorv 40 Yr. Sample Samole 3 vrs. 7 vrs. 10 vrs. 'Dwo. No. .@ n i M j A. Steam Generators 1. Circumferential 8.1.1 UT C-A 4 Gens./3 Welds 3 1 1 1-ISI-0401-C Shell Welds (12) + 2. Circumferential 8.1.2 UT C-A 4 Gens./1 Weld 1.wid/46 ft 15' 15' 1(* l Head Velds ' (4) . ISI-0401-C y,

o x

3. Tubesheet-to-8.1.3 UT C-A 4 Gens./1 Veld I wid/36 ft 12' 12' 12' ISI-0401-C E$ Shell Weld (4) "z:

m 4

Norale-to Vessel and Inside Radius """O

a. Nozzle-to-8.1.4 UT, MT C-B 4 Gens /2 Nor 8

1 3 - 4 ISI-0401-C Ew Vessel Welds (B) ' U$

b. Inner Radius 8.1.4 UT C-B 8

8 1 3 4 ISI-0401-C. @y B. Heat Exchancert

• o" OO So 1.

Residual Heat Removal Heat Exchanger (2) RHRHX

a. RHRHX Circum-8.2.1.1 UT C-A 2 Ht. Ex./1 Weld 1 wid/113" 37" 38" 38"

.ISI-0289-A 7EU k ferential y Shell Weld

• TC a

ew* o wo-D M 3 H* O ~ O M LJ W + w w ~," w m v e --

~. - _.._ f-3 ~ ' - - ~ = APPENDIX A TA8LE B

h.,

3 SEQUDYAH INSERVICE INSPECTION PROGRAM I' [ w rn CLASS 2 COMPONENTS M$ WM Program Section XI Reference Exam Exam -1st Insp. Interval Inspection Periods Reference w i Cggponent Section Method Cateoorv 40 Yr. Samole Samole 3 vrs. 7 vrs. 10 vrs. Dwo. No On u ( M l B. Heat Exchangers (Cont'd) L

b. RHRHX Circum-8.2.1.2 UT C-A 2 Ht. Ex./1 Weld I wid/113" 37" 38" 38" ISI-0289-A ferertial (2)

' Head Weld ~" E M

c. RHRHX E

Nozzle-to-8.2.2 PTI C-8 2.Ht. Ex./2 noz. 4 1 1 2 ISI-0289-A n 5.' Vessel Weld (4) "N i w m: rn

d. RHRHX

" O" Integrally-8.2.3 PT 'C-C 2 Ht E=./2 Wids 2 0 1 1 ISI-0289-A "w Welded (4) O Supports EH w i

• o l

e. RHRHX "O

Component 8.2.4 .YT-3 C-E 2 Ht. Ex./ 4 1 1 2 ISI-0289-A O Supports 2 Spris. (4) 1 [ 1: 5. L I aw e** oo* w n onw n 8 I w See Request for Relief 151-13, PT examination only. w I + 4 I i 4 4

g _.- m7-p- y y y y t 3c_ APPENDIX A bi '.'ABLE B-E ^ ,[ SEQUOYAH INSERVICE INSPECTION PROGRAM _2 m CLASS 2 COMPONENTS w 'ca ' k s E @' i Program Section XI' M& Reference Exam Exam ist Insp. Interval Inspection Periods Reference Comoonent Section Method Cateaorv__40 Yr. Samole Sample 3 vrs. 7 vrs.10 vrs. Dwo. No. @n .w C. Tanks M { 1. CCP Tank (Boron Injection l Tank) (1) i j

a. CCP Tank 8.5.1 UT C-A 1 Tank /2 Welds 2

1 0 1 ISI-0074-A ) Circumferential ] Shell/ Head Q Weld l' -

b. CCP Tank 8.5.2 MT UT C-B 1 Tank /2 Nor.

2 0 1 1 ISI-0074-A $ en Norale to Vessel Welds gM. l C. CCP Tank 8.5.3 ST-' C-C'- 1 Tank /4 IA's 4 0 2 2 ISI-0074-A l Integrally 4 Weided Supports E g-

d. CCP Tank 8.5.4 VT-3 C-E 4

4 1 1 2 ISI-0074-A .o Component Supports [

e. CCP Tank 8.5.5 UT C-D 1 Hwy /16 Studs 1 Mwy 1

0 0 ISI-0074-A Pres $ure 4 Retainirg } Bolting >2" Dia. 4 5EN fe ? L ~ 8 e.: ? 8 m-O r, - O O M ue l i

(~

~- .u, . ~. 3 m.. APPENDIX A 2 =f C- : TABLE B ~ g SEQUOYAH INSERVICE INSPECTION PROGRAM wb CLASS 2 COMPONENTS w 3 a ~ y g.. Program ~ Section XI-Reference Eram Exam ' ist Insp. Interval Inspection Periods Reference ~ Component Section Method .g r ttqorv 40 Yr. Samole Sanol e 3 vrs. 7 vrs.10 vrs. Dwo. No. '. @ n i a M I D. Einin_g i 1. Intearally Welded. Suooorts

a. Safety

.8.9.1.2 ' PT C-C 3,2 1 3 2,3 1 2 0 MSG-0009-C y 1 Injection System 4ne;. t b.. Main Steam 8.9.1.3 MT C-C 10 103 1 6 3 HSG-0017-C "T-J System. w*m mM

c. Feedwater 8.9.1.4 MT C-C 5

5 0 3 2 MSG-0015-C "O - System w O 1 O*- w z g.. 8: E mwm i os aw so < a egg

• o.' '

ow ts u 4) .o I P% M The change in support numbers during the second period was due to new code class boundaries, 8 2 p There are 4 safety injection IAs, only 3 can be examined, IA 2-SIH-10-IA is inaccessible (see RFR 151-17). 3 Change in number scheduled during the second and third period due to accelerated FW Program. i. i i b ~.

~ 9r. n,. y y .f"""*"** Ty ' s ...M i 4 Ai ~ 4 #4 ' N [I APPENDIX A h TABLE B ~ w. SEQUOYAH INSERVICE INSPECTION PROGRAM ~ w w: [. 9 j CLASS 2 COMPONENTS' 5 s Mw ~ Program Section XI C". g t'- Reference Exam' Exam ist Insp. Interval Inspection Periods Reference .w Comoonent Section Method Cateocrv 40 Yr. Samole Sample 3 vrs. 7 vrs.10 vrs. Dwa. No. @nm D. Ploina (Cent'd) 2. Picino' and Valwe Comoonent SuppoCt1

a. Residual 8.9.2.1 VT-3, C-E 85 853 27 56 25 MSG-0010-C y

Heat Removal VT-4 System 'E55

b. Safety 8.9.2.2 VT-3, C-E 57 4 1

57 3.4 18 39 0 HSG-0009-C M% 1 Injection VT-4 ym System ~ @ Q". 4 's @"

c. Main Steam 8.9.2.3 VT-3.

C-E 46 *4 I 46 2,3,4 11 35 0 MSG-0017-C 1 System VT-4 4 @g .w

d. Feedwater 8.9.2.4 VT-3 C-E 30 303 10 20 0

MSG-0016-C E System VT-4 "o

e. Containment 8.9.2.5 vi-3 C-E 5

53 1 4 0 MSG-4011-C Spray System VT-4 .E E N Ihb I ewa !he change in component supports during the second period was due to new code class bouncades. M 2 w Support 2-MSH-312, 428 and 429 were CC-2 in the first period. They became NNCC 'n the second period. $p 3Change in nur.ber scheduled during the.second and third period due to accelerated FW Program. n 8 4 y Change a n number due to exemption in IWC-1220(a). W 5Added supports for valve operators.

= _ _. t. h j ,r . t. -{ a. $I

m~,

A I. ' APPENDIX A' E-y TABLE 8 g SEQUOYAH INSERVICE INSPECTION PROGRAM k '] CLASS 2 COMPONENTS i gm s l y g. t ~ Program Section XI C .g "t* - Reference Exam Eram 1st Insp. Interval Inspection Periods Refe rence - Component Section Method Cateoorv 40 Yr. Samole Samole 3'vrs. 7 vrs. 10 vrs. Dwa. No. k n-g M-D. Pipino (Cont'd) 3. Ci rcumferential' and Longitudinal Welds Residual Heat Removal $ystem a. 2 M 1. RHR Circs >1/2" iJom. Wall Thickness E 8.9.4.1 UT. PT C-F 27' 6I 1 2 3 ISI-0003-C MK " i5 2. RHR Long. >1/2" Nom. Wall Thickness' "m 2 8.9.4.1 UT. PT C-F 61 21 1 0 1 ISI-0003-C y" t MO 3 RHR Circs 11/2" Nom. Wall Thickness' 301~ H z 8.9.4.1 PT C-F 1221 8 11 11 ISI-0003-C @x w-

• o 4.

RHR Long.11/2" Nom. Wall Thickness o" 8.9.4.1 PT C-F-491 12I 1 4 7 ISI-0003-C-b. Safety Injection System 1. SIS Cires.>1/2" Nom. Vall Thickness 8.9.4.2 UT. PT C-F 411 101 3 3 4 ISI-0074-A i 1 ISI-0002-C owm i-2. SIS Cires 11/2" Nom. Wall Thickness eow j$5 i w 8.9.4.2 PT 'C-F 521 1 13 ' 2 5 6 - ISI-0002-C g" % k h S E *w n.g ~E$- on U Ut I The changes in weld numbers during the second period was due to new code class boundaries. y,, y w r

e~ .- ~. r j f} p i APPENDIX A I-TABLE 8 g SEQUOYAH INSERVICE INSPECTION PROGRAM g CLASS.2 COMNNENTS u',. [ s g@ 22 ~ Program Section XI C"- Reference ' Exam Enam ist Insp. Interval Inspection Periods Reference h Comoonent Section Method Cateoorv 40 Yr. Stuncle Symole 3 vrs. 7 vrs.10 vrs. Dwo. No. Qg M D. Pfoina (Cont'd) 9 3. SIS Long.11/2" Nom. Wall Thickness 8.9.4.2 PT C-F 23I 51 0 2 3 ISI-0002-C 1 4 c. Main Steam System E 1. MS Cires >1/2" Nom. Wall Thickness M Q 8.9.4.3 UT, Mi C-F 13I 41 02 2 2 ISI-0015-C y[. l t "N 2. MS Long. >1/2" Nom. Wall Thickness "z m ' 8.9.4.3 UT, MT C-F 61 21 0 1 1 ISI-0015-C yM ~ MO 1 i d. Feedwater System s C wz o 1. FW Cires >l/2" Nom. Wall Thickness Eg i 4 0 2 2 CHM-2403-C ~ 8.9.4.4 UT, MT C-F 161 ow 2. FV Long. >l/2" Nom. Wall Thickness E 8.9.4.4 UT, MT C-F ll 1 1 0 0 CHM-2403-C i 3. FW Cires, i 1/2" Nom.' Wall Thichness t 8.9.4.4 MT C-F t 0 See Note 3 e. Containment Spray Systen.

• M or e u

$bb y 1. CS Cires (1/2" Nom. Wall Thickness yE% d.9.4.5 PT C-F 6 1 1 0 0 ISI-0007-C y @ *u O ow A 2. CS Long. 11/2" Nom. Wall Thickness 8.9.4.5 PT C-F 2 1 0 1 0 ISI-0007-C U = I The changes in weld ntanbers during the second period was due to new code class boundaries. 2 Weld MSF-10 is now NNCC and it was examined in the first period as CC-2. 3 Examinations not scheduled this interval, t 1 i a

L., '[._ h-.ed --~ r; rg-~ y . l M ' 'I i t y, g APPENDIX.A it j i-TABLE B SEQUOYAH INSERVICE INSPECTION PROGRAM y' 2 g CLASS 2 COMrONENTS ,y 3 W M' Program Section XI 'Cy;

Reference:

Enam' Exam ist Insp. Interval Inspection Periods Reference Component Section Method Caigaorv 40 Yr. Sample Samole 3 vrs. 7 vrs.10 vrs. Dwo. No. M _ i E. Pumps 1. Residual Heat Removal Pumps'(2) RHRP s a. RHRP Support Components 8.10.1.2 VT-3 C-E 2 2 1 1 0 151-0352-B 'y Cn F. System ' M E PrgJsure Test 8.12 VT-2 C-H See Program Section 8.12 'N $ N Ids Cn Cn M M . 4a ~ =. O N a M O O SU 4 'O $6 En ae-d2 4 i e>N H + en H s CO

• M unu l

O H o MO OO N W N U1 ) r x- , _ _ _ _ - - - - - - - - _ -. - _ _ _ _ _ _ _ - -. ~ _ _. _. - _ -. -. -.. -... - -

e, ,- ~ ~,. <7--

n Es 2 LW L -d L_

a LR' L 3 y m_. APPENDIX A 2 -., . f [ -TABLE C [2 SEQUOYAH INSERVICE INSPECTION PROGRAM C tj CLASS 3 COMPONENTS- - $ $q w F NN Program Section XI C*' Reference Exam-Exam 1st'Insp. Intenal 'Inspectidn' Periods-Reference l G t< ' g l Comconent Section Method Cateaorv' 40 Yr. Sawle Sample 3 vrs. 7 vrs. 10 vrs. Dwa. No. @n i M { A. Syst=m Pressure Tes_ti s 1 1. All ASME-9.0 VT-2 0-A. D.9 N/A N/A 100% 100% 100% N/A Code Class 3 D-C f (Equivalent) [ 2 g y O. Dmuonent $9pports z' "m M. l 1. Auxiliary 9.1.1 VT-3 D-A' 39I 393 39 39 39 ISI-0146-C yE Feedwater System VT-4 i w j 2. Chemical and 9.1.2 VT-3 0-4 1 %M 02 1 0,2 0 0 0 - y" Volume Control System VT-4 O" o 3. Component 9.e.3 VT-3 D-A, D-B 1733 1 ~= 173 - 165 173 173 ISI-0154-C @M Cooling System VT-4 4

• o "

w 4. Containment 9.1.4 VT-3 D-B OI 01 0 0 0 j Spray System VT-4 i j 5. Essential Raw 9.1.5 VT-3 D-A, D-B 3031 3033 280 301 303 ISI-0158-C Cooling Water System -VT-4 e t 55N il f A. g

s - 9 y

aw* co. y wp,N . n ow-t N I The change in support numbers was' due to new code class boundaries. 8 2The supports are not required to be examined, due to no examination ::ategor; from this piplog. TVA Safety Class D. U w LM 4 h ~ J ~r. w q a,-- r ,-i .-w- =

s m ... 4; : g: 1- ~, L.7 a L.., L s> - un +- - g APPENDIX A 4. ~ TABLE C g j .SEQUOYAH INSERVICE INSPECTION PROGRAM' X m wm 2\\ g CLASS 3 COMPONENTS l $. = QQ' Program Section XI Reference Exam-Exar - 1st Insp. Interval. Inspection Periods Reference Corponent -Section MethodCahgory 43 Yr Samole Ses_le 3 vrs. 7 vrs. 10 vrs. D_wg d u -

@ n w

t M B. Compo~ent Sup22th (Cent'd) 1 6. Residual Heat 9.1.7 VT-3 D-B 1 0-01 0 0 0 1 ' Removal System VT-4 ] 7. Safety 9.1.8 VT-3 D-B 01 01 0 0 0 E' Injection VT-4 i System N l'5$

8. -Equipment 9.2 VT-3 D-A 59I 59,2 53 59 59 See "k

1 s supports j Component $m supports " &" 2 E -Q 3 -g = i w i E o Ow i 4 't 7E$ i -2 f. MN o I a ss u The change in support numbers during the second inspection period was due to new code class boundaries. 2 o-The change in support numbers due to change out of ctmponent cooling heat exchanges,' and the RHR heat exchanger class 3 support not included until the second period. U sn r I

w. c. ,a

-. g 24 L.;

tw- "y-3- s, %~ S g-E' [. AFPENDIX A g-- TABLE D W l- '3 SEQUDYAH INSERVICE. INSPECTION PROGRAM K' wm' 1 l [s SUCCESSIVE EXAMINATIONS 2 N N' cH 4 Program Successive-Successive Eaamination Periods Reference Exam ' Exam Exam Program' Examined .lst 2nd 3rd Reference- @ n' Comoc9ent Section Method Category-Reference Section U/C U/C U/C -U/C Dwo. No. M j 2-SIH-20-IA 7.4.7.4 PT B-K-1 'IWB-2420 U2C4 U2C5 or 6' U2C7 or 8 UZC9 or10 MSG-0009-C 4 MSV-1 8.1.4 UT C-B IWC-2420 U2C4 U2C5' or C6 N/A N/A ISI-0401-C i 5 H 0 i. . En M M. 4 n,, b.- ,A 4 w Z 03 in M. I M -n-e4 O i M M 4 O f

g )(

H i m M O. i' .O M 4 l t -m u m 9 OM & 4 8 ( } 8 >N N aH NW O O .A b s O i w 131 t$ N t O Ow %O r% @ O 'O H w N (19 1 i s e ,9 .wi. g .c-

~,- ,, u_w g-~ >;m - - ~ r~ J 3 L L_i -L M W - L,._J. V- -- ll

• g' APPENDIX A

{l t TABLE E l j SEQUOYAH; INSERVICE INSPECTION PROGRAM' k* v g AUGMENTED EXAMINATIONS ,gg t >= U N' -i og Program Q t* l Reference Exam Examination Schedule g + } Component Section Method Cvele 1 Cycle 2 Cvele'3 Cvele 4 Cvele 5 Cvele 6 Dwo. No. ' @n Ref. M i + Feedwater Nozzle-20.1 UT (See Program X X X X CHM-2403-C To-Pipe Welds and i Section 20.1) Adjacent Pipe and Nozzle Areas w RPV Nozzle 20.2 UT,PT X X ISI-0298-B ~N - sc. Safe Ends M' <:bb Reactor Coolant 20.3 UT.PT X" X X X X .-ISI-0306-B Pump Flywheel (Note: -See Dwg. ISI-0403-A for examinations that have ISI-0403-A .ym have been performed.) MM Mk j Steam Generator 20.4 See Program Section 20.4. g-4 3 Tubing g@ @g m" RPV Nozzle 20.5 UT X .ISI-0298-8 E Cladding ISI-0297-A ISI-0392-A { i l Steam Generator 20.6 UT See Program Section 20.6. ISI-0358-A feedring and J-Tubes y i + Control Rod Guide 20.7 VT Cach Refueling Outage Tube Flexures I -y y $ 1 l Rod Control Cluster 20.3 ET See Program Section 20.8. a< a en ew g - Assembly (RCCA) gE% @ @ *u Cladding Wear i N Measurements ow l o g U vi + L

^ L,e 'LR .L ) I~"A % n q. g-k ~~a L ~~ ' ~ ?. APPENDIX A k TABLE E' ]r SEQUOYAH INSERVICE INSPECTION PROGRAM k g AUGMENTED EXAMINATIONS .g,

• C

~~ .mw-n H <: a5 Program nn o ~ Reference Exam Examination Schedule Ref. -@ n ' Comoonent Section Method Cvele 1 Cvele 2 Cvele 3 Cvele 4 ' Cvele 5 Cvele 6 'Dwo. No. 't i e i f Accelerated Field 20.9 Complete I Weld Program t Thimble Tube 20.10 ET Each refueling outage. See Program Section 20.10. Guide y m i Enamination of 20.11 Complete M Piping connected to the Reactor M$. Coolant System Due 7 f to Thermal Stresses zm .y" NO i Examination of 20.12 Complete O Pressurizer Surge Line Due to @g Occurence of Thermal =o " ' Stratification O" Examination of 20.13 See Program Section 20.13. Row I and Row 2 Steam Generator Tubing i Examination of Base 20.14 PT X X X 151-0307-B Material Transition

• 8 5 "

Adjacent to Weld or aw I j$$ e No. 2 RC-023 on RC yE% Pump No. 3 Cold Leg S $ *u nn os n Main feedwater 20.15 MT X X } Isolation Valves See Program Section 20.15. U sn 4 I

L. tl : C~:.i. O -- ~~ ~ g APPENDIX A ( ^ .TACLE 1 .wm'- g ' Minimum Number of Steam Generators To Be O Inspected During Inservice Inspection Only Q @_ c: s. y t< lG E ss n No. of Steam Generators per Unit Four~ M First Inservice Inspection Two Second & Subsequent Inservice Inspections Onel 4 Table Notation: y E

1. Each of the other two steam generators not inspected during the first inservice inspections shall be inspected during

'y the second and third inspections,- The fourth and subsequent inspections shall follow the instructions described below: 'Em 1 - The inservice inspection may be limited to one steam generator on a rotating schedule encompassing 12% of the j tubes if the results of the first or previous inspections indicate that all steam generators are performing in a g' M like manner. Note that under some circumstances, the operating conditions in one or more steam generators may be found to be more severe than those in other stean generators. Under such circumstances the sample sequence shall be modified to inspect the most severe conditions. y 5 O E

ee 1 ;i. L.

8 28L ~ n b U, - w o .v--

e. m - ~ f-' [f (f.. ~' f~.,a y..__. c g j. APPENDIX A h-TABLE 2~ I f Steam Generator Tube Inspection I d 5N-g,- 1st Samole Inspection 2nd Sample Inspn tion 3rd Samole Inspection yg Sai.tple Size , Result Action Required Resul t Action Required -Result Action Required CH I l A minimum of S C-1 None N/A N/A N/A' N/A Qn j Tubes per S.G. M j C-2 Plug defective tubes C-1 None N/A N/A y and' inspect additional Plug defective tubes C-1 None 4 l 25 tubes in this S.G. C-2 and inspect addi-C-2 Plug defective tional 45 tubes in tubes this S.G. C-3 Perform action y Perform action for for C-3 result y' C-3 C-3 result of first of first sample y sample N/A N/A yg C-3 Inspect all tubes this All other M %' S.G., plug defective S.G.s are None M/A N/t. ym tubes and inspect 25 C-1 M "o O tubes in each cther S.G. Some S.G.s M s C-2 but no Perform action for N/A N/A additional C-2 result of @g Prompt notification to S.G. are C-3 second sample H .a NRC pursuant to technical Additional Inspect all tubes in specification 6.6.1 S.G. is C-3 each S.G. and plug N/A N/A . O defective tubes. j Proept notification to NRC pursuant to technical spect-fication 6.6.1 S-M% Where n is the number of steam generators inspected during an inspection. 77" ibH g mH HWb O OO+ l OUM M o,, o, N H g .o g g m + m

$tseJard Shees SI-114.2 SURVEILLANCE-ASME SECTION XI P.svision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 110 of 125 .- id APPENDIX B DATA SHEET 1 L i SFQUOYAH NUCLEAR PLAITI !y UNIT 2, CYCLE SITE FINAL REPORT i. .l ' (. 1 {. t I f c>. Prepared by: i 1 i Approved by: 1 i 4 -J i i 1- 't i i ? J q b' ]^ " " ") 1403C/CoC3

- SuaJordhes - l Revision 16 SZ-114.2 =SURTEILLANCE ASME SECTION XI INSTRUCTION INSERVICE INSPECTION PROGRAM Page 111 of 125 t APPENDIX C NOTIFICATION OF INDICATION PART I - FINDINGS NOI No. Plant / Unit ISI Dwg./Sh. No. Examination Report No. Component ID. Description of Indication (Sketch / Photograph if Required for Clarification): i R Signature of Examiner / Certification Level Date Signature of Field Supervisor (Contractor): Date Signature of S00 Representative Date PART II-DISPOSITION 1 i i-b DCN NO. WR/WO NO. PER NO. = FIR NO. SCAR NO. Other i -Disposition Prepared /Reccrded By- + Date r L PART III ADDITIONAL EXAMINATIONS W P Additional Sample Requiredt Yes No Attach list of items in additional sample, if required. VERIFICATION OF CLOSURE Verification of Completed Corrective Action Required by Disposition Reexamination Report Number, if Applicables Comments: Qq Signature of SQO Representative: 'j Date J I JVA 40004 (NP 191) 1403C/COC3 "-~

Sundard Sheet SI-114.2 SURVEILI.ANCE ASME SECTION XI Revision 16 INSTRUCTION-INSERVICE INSPECTION PROGRAM Page 112 of 125 t APPENDIX D I i GUIDELINES FOR DETERMINING PIPING COMPONENT SUPPORT EXAMINATION BOUNDARIES i r t .i . f(: 1 6 u ti i L .h! i, "l ci e i '.)a LJ VA 40004 (NP 2,91) l t.-.,._..-

Suzdasd Sheet i SI-ll4.2 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 113 of 125 i APPENDIX D 1.0 PURPOSE This instruction defines and establishes the controls and responsibilities for the determination of ASME Section XI component support examination boundaries. 2.0 SCOPE This in.Lruction applies only to the piping component supports included in the appropriate plant instruction for preservice/in-service inspection (hereafter, ISI Program) for Sequoyah Nuclear Plant.

3.0 REFERENCES

J c' 3.1 Memorandum from W. E. Pennell to R. A. Sassoms dated August 11, 1987 (B41 870810 003) 3.2 Memorandum 'c m J. A. Kirkebo to Site Directors dated June 24, 1987 (L29 870528 ?15) 4.0 DEFINITIONS ~ 4.1 Intervenino Element: Items that lie in the component support load path between the pressure retaining component and the component 4 supports, between two component supports, or between the component support and the building structure. Items such as: diesel engines, i electric motors, pumps, valve operators, coolers, access structures, [. etc. For the purposes of this instruction, an intervening element is to be considered the same as " existing steel." 4.2 Existino Steel: Building steel that is identified on a support drawing as " existing." 4.3 TyDe A Examination Boundary: The type of boundary to be used for those supports that are attached to building floor, walls, ceiling, m or embedded plate. 4.4 Type B Examination Boundary: The type of boundary to be used for those supports that are attached to another existing support. 4.5 Type C Examination Boundary: The type of boundary to be used for those supports that are attached to existing steel. ~ 4.6 Tvoe D Examination Boundary: The type of boundary to be used for L. those supports that are attached to an intervening element. 4 5.0 RESPONSIBILITIES 5.1 ISI Programs is responsible for the initial review of ASME Section XI component support drawings and determining the I examination boundary for those supports. The Site Quality Organization (SQO) shall be responsible for determining the examination boundary for new or modified supports. ^"*'@#1H) 1403C/COC3

, - -,., ~ > .. - ~ - Stasdud Sheet -- I -1 SI-114.2 SURVEILLANCE A3ME SECTION XI Revision 16 INSTRUCTION-INSERVICE INSPECTION PROGRAM Page 114 of 125 APPENDIX D This instruction shall be revised by ISI Programs when' deemed necessary by ISI Programs Supervisar or his designee. 5.2.ISI Programs or its designee is responsible for determining the acceptance range for all component supports in the ISI Program that require acceptance ranges. 5.3 S00 is responsible for examination of component supports within the examination boundary as set forth by this instruction. Any examiner,. inspector, or engineer may request boundary clarification e I where questions exist by submitting the Component Support Examination Boundary Clarification Request Form to ISI Programs. 6.0 IMPLEMENTATION d .6.1 Determination of Component Support Examination Boundgry 6.1.1 general J 6.1.1.1 ISI Programs ar t SQO shall use the following ni i methodology to determlae the component support I-examination boundary. { 1) In all cases involving attachments welded to-pressure retaining components and/or supports welded to building structure / existing steel, the r. weld shall be included within the examination f! boundary. i 2 ^; Concrete bolt anchors, such as " red-head" or I b "rawl" anchors, are not included within the Section XI code boundary and, therefore, do not fall within the examination boundary. Even though anchors may be listed on a support bill of materials, they are not required to be examined. (This note pertains to anchors only, [. not the associated bolting.)

3). All shims and lugs adjacent to the supported pipe shall be examined. Even though the shims and lugs may not be listed on the support bill of materials, they are required to be examined.

~]! 4) For component supports that do not have a bill l of materials, items to be examined shall be s described in the PRISIM data base with the specific ISI support number. i. vA 4mM4 (NP191) 1403C/COC3

~ Star &rd Saeet SI-114.2 l SURVEILLANCE ASME SECTION XI R3 vision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM. Page 115 of 125 APPENDIX D pe

5) Notification of Indication (NOI) forms shall be used to report unacceptable indications on component supports only if the criteria in A, B, and C, below, are met.-

A) the component support falls within the scope of ASME Section XI. B) the component support is part of the inservice inspection examination sample. C) the indication falls within the component-support's examination boundary as set forth ps by this instruction. Indications that do not meet the criteria in A, { B, and C, above, should be noted by other means, such as, MR's, WR's, etc.

6) This instruction is intended to deal with piping supports only. Therefore, equipment support drawings will be provided in the ISI Program that depict the examination boundtcv l-for each equipment support.

6.1.1.2 For each component support to be reviewed for examination boundary determination, obtain the ( latest configuration controlled drawing (CCD) of the 4 support. If a CCD does not exist, obtain the latest as-constructed drawing of the support. If an as-constructed drawing does not exist, obtain the latest as-designed drawing of the support. For new or modified v :-7 orts, the drawing included in the work instruction may be utilized. Using the drawing, classify the support in one of the following categories j 1. Support is shown as being attached to building floor, wall, ceiling or embedded plate. 2. Support is shown as being attached to " existing support." 3. Support is shown as being attached to " existing steel." q 4. Support is shown as being attached to an J intervening element. Af ter classifying the support in one of the categories, proceed to the corresponding section 2 to complete the boundary determination. VA 4mm4 (se z90 1403C/COC3 w.

Susdard Stret 91-114.2 SURVEILLANCE ASME SECTION XI Rovision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 116 of 125 u-APPENDIX D 6.1.1.3 As each support is categorized, the category identifier, as dufined below, will be input with the respective support in the PRISIM data base. 6.1.1.4 As supports are added or revised in the PRISIM data base, this instruction shall be used to determine or i revise the examination boundary for that support. 6.1.2 Supports Attached to Buildino rioor. Wall Cellina, or Embedded Plate For sup, orts attached to building floor, wall, ceiling or embedded plates, the boundary shall be defined as the 'g point (s)/ area (s) of contact between the support and the building structure, along the support load path (s), up to, but _, Including the pressure retaining component. In audition to the requirements of 6.1.1.1, each itwai in the support bill of materials, except concrett anchors, is to be included within the boundary. This category of supports shall be considered Examination Boundary Type A and so designated in the PRISIM data base. 6.1.3 Supports Attached to Existina Supports NOTE: For clarity, Support A la the support being reviewed for boundary determination and Support B is the t { " existing support" to which Support A is attached. The boundary of Support A shall be defined as the point (s)/ l area (s) of contact between Support A and Support B, along the support load path (s), up to, but not including, the pressure o retainitg component. In addition to the requirements of 6.1.1.1, each item in Support A bill of materials is to be included witnin the boundary. This category of supports shall be considered Examination Boundary Type B and so designated in the PRISIM data base. In the PRISIM data base, Support B will be identified as the support to'which Support A is attached. (" Examine to Support B.") 6.1.4 Supports Attached to Existina Steel e F,r supports attached to existing steel, the boundary shall in defined as the point (s)/ area (s) of contact between the support and " existing steel", along the support load path (s), p p up to, but not including the pressure retaining component. In addition to the requirements of 6.1.1.1, all items listed on the support bill of materials are to be included within the boundary. L_ !TVA dmoi pe 2NO 1403C/COC3 ~.

. _ ~ Sund,rJ Shres SI-114.2 SURVEILLANCE ASME SECTION XI Revision 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 117 of 125 APPENDIX D This category of supports Jhall be considered Examination Boundary Type C and so designated in the PRISIM data base. 6.1.5 Supports Attached to IntervtD.ino Element For supports attached to an intievening element, the boundary shall be defined as the attachment portion (i.e., welds, solting, pins. clamps, etc. ) to the pressure retaining component and all support members up to, but not including, the intervening eJtment. In addition to the requirements of 6.1.1.?, all ita as listed in *he support bill of materials are to be included within the boundary. 4 This category of supports shall be considered Examination Boandary Type D and so designated in the PRISIM data base. 6.1.6 EMR22rts Attacht d t.o Various Structures In many cases, one component support is attached to more than one type of structure. These supports will have more than one Examination Boundary Tyge designator in the PRISIM data base. In all cases, hewevca, the examination boundary for each component support she.11 includes

1) All items listed on the support's bill of materials, i

except concrete anchors.

2) All shims and lugs adjacent to the supported pipe.

6.2 Site Implementation 6.2.1 S00 shall obtain the lates: CCD of the support. If a CCD does not exist, the latest as-Constructed drawing shall be I obtained. If an as-constructed drawing does not exist, the b latest as-designed drawing shall be obtained. If during the performance or an examination, significant differences are identified between the support drawing and the support field configuration, S00 shall access the Domign Change Document Tracking System (DCDTS) to identify any outstanding change documents on that component supporti L For each component support that does have an outstanding change docunented listed on the DCDTS, SQO shall 6etermine through the work package project engineer if the work has been completed on that particular support. If the work has m. been completed, 500 shall obtain the change document support drawing. If the work has not been completed, the examination shall be delayed until the work has been completed. i WA 4NK'4 (Nr 190 1403C/COC3

SueJud Nhe b I I e====

=

r 1 L I l PCS FOR 1 HORIZONTAL RESTRA TNT.L TO PIPE 2 1 1/2" x 2 15/16', C. S. PL A TE, 6' LG. (A212-A) i i 7/8 " x 6 ', C. S. FLA TE 8 " LG. 1 W12 x 27 x 3 '-9 5/8' LG. e

• 2 @

3/8" C.S. STIFFENER PLA TE FOR W12 x 27 BOUNDARY: EXAMINE WELD BETWEEN LUG AND PIPE AND ALL BILL OF MA TERIALS ITEMS. t svA 40004 (NP 2st) 1403C/COC3

a %endetJ Shes SI-1.4.2 SURVEILLAllCE ASME SECTIOli XI Revision 16 IIISTRUCTION INSERVICE INSPECTIOli PROGRAM Page 123 of 125 ) APPENDIX D EXAMPLE - TYPG~D GTAMINA TION BOUNDARY ~ \\ l 1 l t / a ~~~ f [T ( ) p l b o n I J ( t v R DED 'N V EXISTING MAIN FLANGE R.C. PUMP #1 l ,,PCS FGR 1 GUIDE 1 T. S. S 'x 6 " x 3/8 ". 4 *-1/2 ' LG. 2 1/2 " x 3 ' C. S. PLA TE. 9 3/16 " L G. 1 1/2 " x 3 " C. S. PLA TE. 9 ' LG. 4 7/B'O S.S. S TUD. 3 7/8 " L G. W/ (2) HEX NUTS 1 l ' x 12 " C. S. PLA TE. 20 1/2 ' LG. ,], 1 l ' x 4 1/2 " C. S. PL A TE. 12 ' L G. q J BOUNDARY: EXAMINE ALL BILL OF MA TERIALS ITEMS. a ]A ma W 291) 1403C/COC3

hezd rd Shtte SI-114.2 SURVEILLANCE ASHE SECTION XI R vision 16 ~ INSTRUCT!?N INSERVICE INSPECTION PROGRAM Page 124 of 125 APPENDIX E FILLD CORRECTED DRAWING (S) TRANSMITTAL TO: iSI Progr ams, NM Transmittal Numbers (Year) (Sequential) Unit / Outage or Date U1/ The drawing (s) listed below from SI-114.2 have been field marked with variations in configuration which were discovered during the course of insersice or preservice wxaminations. Please revise the controlled copy of this/these drawing (s) in the SI prior to the next refueling outage, p 1. 7. 2. 8. 3. 9. 4. 10 5. 11. 6. 12. i. Signature of Examiner /Date Signature of Fleid Supervisor RETURN TO: SITE QUALITY ORGANIZATION Drawings have been revised as necessary to reflect the appropriate j,

changes, k

Signature of ISI Programs Repres,entative . I' Date l i l ? l [lVA 4Mo4 (NP 191) 1403C/COC3 l

sux&rd haces SI '.14.2 SURVEILLANCE ASME SECTION XI Rt.bslon 16 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 125 of 125 2 SOURCE NOTES f., Requirements IMPLEMENTING .Stattatnt__ SOURCE DOCUME!!I STATEMENT.. All STD 6.10 All All Applicable ASME Boiler and Pressure All Articles Vessel Code - Section XI 1974 Edition, Summer 1975 Addenda, 1977 Edition, Summer 1978 Addenda All Applicable ASME Boiler and Pressure All e to Articles Vessel Code - Section V All Applicable FSAR - SON All Chapters Surveillance Requirements Technical Specifications All

4. 0. 5, 4. 4. 5. 0, thru Unit 2 - SON 4.4.5.5, 4.4.10 10CFR50.55a Code Federal Regulations All 10CFR50 t.

As Applicable U.S.N.R.C. Regulatory All { Guides 1.14, 1.26, ( 1.83, 1.147, and 1.150 Provide a revised Response to NRC C.1 ISI Program to NRC dated 1/30/87 within 6 mos. following R. L. Gridley to NRC Unit restart L44 8"S130 804 (' NCO 870 038 004 L; Docket Nos. 50-327 and 50-328 Revise the ISI Program Response to NRC C.2 to reflect full-length dated 6/17/85 Steam Generator Tube J. A. Domer to NRC Inspections L44 850617 801 NCO 850 284 004 Alf Code Cases N-209, N-234, All U N-235, N-307-1, N-308, N-401-1, N-402, N-416, N-426, N-435-1, N-461, N-341, N-356, N-460 W f VA 40004 (Nr191) 1403C/COC3

hundard Sbtes SI-114.2, Attachmsnt 1 ~ SURVEILLANCE Revision 0 INSTRUCTION LIST OF DRAWINOS - UNIT 2 Page 1 of 7 e i 1 l ISI Programs 1 A. MAINTAIN a listlng of drawings for ISI examinations. B. UPDATE listing as necessary. C. OBTAIN concurrence trom Site Quality Manager or hl's designee. SOM l "' D. CONCUR with listing by signing below. ISI Programs E. FORWARD to SPS for updating Table of Contents, etc. SPS L F. FORWARD to DCPJ4. DCRM 4 G. DISTRIBUTE per SSP-2.7. f i i I L l [L ' l / ~ Site Quality Manager / Designee Date l 1 l l 1 s } l Y {WA 40004 (NP 2NO 1404C/COC3

SeeJud $ket SI-114.2, Attachment 1 SURVEILLANCE Rev1alon 0 INSTRUCTION LIST OF DRAWINGS - UNIT 2 Page 2 of 7 ~ LIST 00 DRAWINGS - UNIT 2 The drawings listed below are for the performance of ISI examinations. These drawings are issued through Document Control and Records Management (DCRM). These drawings shall receive controlled distribution. Individual copies may be obtained from DCRM. r Drawino No. Reactor Vessel i ISI-0304-B Reactor Vessel Stud Locations and Details ISI-0298-B Reactor Vessel Seam Welds L ISI-0301-A Reactor Vessel Closure Head ISI-0300-A Control Rod Drive Housing ISI-0392-A Reactor Vessel Inlet Nozzles ISI-0237-A Reactor Vessel Outlet Nozzles ISI-0097-C Closure Head Penetrations ISI-0318-A Auxiliary Head Adapter /UHI Cap Welds ISI-0319-C Reactor Vessel Bottom Head Penetrations 7 i DIAwing ll21 Eressurizg.I i ISI-0396-C Pressurizer ISI-0299-B Pressurizer and Steam Generator Manway Bolting ISI-0309-A Pressurizer Heater Penetrations Erawino No. Steam Generators ISI-0398-C Steam Generators Tube Sheet Arrangement ISI-0401-C Steam Generator (* ISI-0299-B Pressurizer and Steam Generators Manway Bolting

• [

ISI-0350-A Steam Generator /Feedwater Transition Spool Piece ISI-0358-A Steam Generator Feedwater Ring Header Drawino Nai HgAt Exchancers ISI-0289-A Residual Heat Removal Heat Exchanger ISI-0231-B Centrifugal Charging Pump Oil & Gear Cooler Support ISI-0235-A Safety Injection Pump Oil Cooler Support FBI-0212-B CCS Waste Gas Compressor Heat Exchanger Support ISI-0230-A CCS Gross Failed Fuel Detector Support ISI-0229-A CCS Positive Displacement Pump Oil Cooler Support ISI-0258-A CCS Seal Water Heat Exchanger Support ISI-0233-B Centrifugal Charging Pump Mechanical Seal Cooler Support ISI-0360-C RHR Pump Seal Cooler Support i l ISI-0361-A Safety Injection Pump Seal Cooler Support i ISI-0259-A Containment Spray Heat Exchanger Support ISI-0226-B Gas Stripper & Boric Acid E"aporator Package Support TA on4 (NP 191) 1404C/COC3 L.

Standard Sheet SI-114.2, Attachmant 1 SURVEILLANCE Revision 0 INSTRUCTION LIST OF DRAWINGS - UNIT 2 Page 3 of 7 LIST OF DRAWINGS - UNIT 2 Drawino Nqt dgat Exchangers (Continued) ISI-0257-A Non-Regenerative Letdown Heat Exchanger Support ISI-0261-B Component Cooling Heat Exchauger ISI-0266-A Essential Raw Cooling Water Strainer Support ISI-0291-B RHR Heat Exchanger Secondary Side Support l Drawino No. Elp.ing and Valve Weld Isometries c ISI-0008-B Reactor Coolant Piping (Main Loops) ISI-0002-C Safety Injection System ISI-0013-C Reactor Coolant System ISI-0009-C Chemical and Volume Control System ISI-0003-C Residual Heat Removal System MSG-0008-C Seal Water Injection (Chemical and Volume Control System) CHM-2403-C Feedwater System ISI-0015-C Main Steam System ISI-0007-C Containment Spr:r 'ystem Class 1 and 2 Pipino and Valve Drawino No. Hypoort Drawings ' l MSG-0013-C Reactor Coolant System MSG-0012-C Chemical and Volume Control System i-MSG-0015-C Seal Water Injection (Chemical and Volume Control) MSG-0010-C Residual Heat Removal System MSG-0009-C Safety Injection System i MSG-0017-C Main Steam System [ MSG-0016-C Feedwater System E MSG-0011-C Containment Spray System ISI-0302-C Reactor Coolant System Support Locations / ISI-0321-B Reector Coolant System (Main Loop) Crossover l Leg Restraint l l i Class 3 Ploino and Valve i Erawino No. Suppert Drawings ] ISI-01'46-C Auxiliary Feedwater System ISI-0158-C Essential Raw Cooling Water System l ISI-0154-C Component Cooling Water System TSI-0155-A Essential Raw Cooling Water System Support Detail 1 i l 0 l o l ivA 4 mci (NP L96 1404C/COC3

SuaJerd Shc0 SI-114.2, Attachment 1 SURVEILLANCE Havision 0 INSTRUCTION LIST OF DRAWINGS - UNIT 2 Page 4 of 7 "m LIST OF DRAWINGS - UNI 1 2 Drawino No. Pumps ISI-0307-B Reactor Coolant Pump Main Flange and Lower Seal House Bolt Pattern ISI-0326-B Reactor Coolant Pump Support ISI-0306-B Reactor Coolant Pump Motor Flywheel Examination ISI-0352-B RHR I> ump Support Locations ISI-0238-A CCS Thermal Barrior Booster Pump Support ISI-0253-B Turbine Driven Auxiliary Feedwater Pump Support ISI-0263-B Motor Driven Auxiliary Feedwater Pump Support {g ISI-0260-A Component Cooling Water Pump 2A-A & 2B-B Support Diawina No. Tanks ISI-0074-A Centrilugal Charging Pump Tank (Formerly BIT Tank) ISI-0227-B Component Cooling surge Tank Drawino_Fo< Miscellaneous i ISI-0403-A Reactor Coolant Pump Flywheel Examinations ISI-0405-A Support Acceptance Ranges ISI-0402-A Valve Interior Examinations I l 1 J l .d. 3 i .a s AdMS4 (NPlat) a 1404C/COC3 l

%:Jud Sheet S1-114.2, Attachmsnt 1 SURVEILLANCE R3 vision 0 INSTRUCTION LIST OF DRAWINGS - UNIT 2 Page 5 of 7 LIST OF DRAWINGS ASME Section XI Drawing,h Boundary Claajltification Drawincs s v 17W600-3-ISI Mechanical Instruments and Controls 17H600-6-ISI Hochanical Instruments and Concrols 17W600-13-ISI Mechanical Instruments and Cont a ls 47W600-7.6-ISI Mechanical Instruments and Controle 1,2-47W600-27-ISI Mechanical Instruments and Controls 1-47W600-28-ISI Hechanical Instruments and Controls D 2-47W600-28-ISI Mechanical Instrenents and Controls g f~ 47W600-29-ISI-Mechanical Instruments and Controls 47W600-30-ISI Machanical Instruments and Controls 47W60d-31-ISI Mechanical Instruments and Controls 47W600-32-ISI Mechanical Instruments and Controls 47W600-34-IS1 Mechanical Instruments and Controls 47WG00-35-ISI Mechanical Instruments and Controls 47W600-62-ISI Mechanical Instruments and Controls 47W600-C4-ISI Mechanical Instruments and Controls 47W600-65.ISI Mechanical Instruments and Controls 47W600-75-ISI. Mechanical Instruments and Controls { 47W600-80-ISI Mechanical instruments and Controls a 47W600-82-IS1 Mechanical Instruments and Controls 47W500-f,8-ISI Mechenical Instruments and Controls 47W600-92-ISI Mechanical Instruments and Controls 47W600-93-ISI Mechanical Instruments and Controls 47W600-102-ISI Mechanical Instruments and Controls 47W600-113-ISI Mechar.ical Instruments and Controls 47W600-114-ISI Mechanical Instruments and Controls ~ 47W600-115-ISI Mechanical Instruments and Controls 47W600-116-ISI Mechanical Instruments and Controls [ 47W600-117-ISI _ Mechanical Instruments and Controls L 47W600-118-ISI Mechanical Instruments and Controls 47WbOO-128-ISI Mechanical Instruments and Controls 47H600-129-ISI Mechanical Instruments and Controls 47W600-130-ISI Mechanical Instruments and Controls 47W600-131-ISI Mechanical Instruments and Controls 47W600-132-ISI Mechanical Instruments and Controls 17W600-134-ISI Mechanicol Instruments and Controls ,I 47W600-136-ISI Mechanical Instrumeuts and Controls 47W600-1:s7-ISI Mechanical Instruments and Controls l' ; 44W6902142-ISI Mechanical Instruments and Controls Ij 47W600-143-ISI Mechanical Insuruments and Controls 47W600-144-ISI Mechanical Instruments and Conta'ols p1 47W600-152-ISI Mechanical Instruments and Controls 47W600-154-ISI Mechanical Instruments and Controls 47W600-159-ISI Mechanical Instruments and Controls 47W600-163-ISI Mechanical Instruments and Controls 47W600-164-ISI Mechanical Instruments and Controls 47W600-165-ISI Mechanical Instruments and Controls -fA 4N (NP 2M) 1404C/COC3

f su=JudSire SI-).14.2, Attachmsnt 1 SURVEILLANCE Rovision 0 INSTRUCTIC;I LIST OF DRAWINGS - UNIT 2 Page 6 of 7 LIST OF DRAWINGS ASM_Striisn_XI gnaghg_ph R3undary Classification 9rawinga (Continued) i 47W600-157-Isi Machanical Instruments nad Controls 47W600-168.ISI Mechanical Instruments and Controls 47W600-169-ISI Mechanical Instrumerts and Controls 1,2-47W600-171-ISI Mechanical Instruments and Controis 47W600 '72-ISI Mechanical Instrvments and Controls ) 47W600-174-ISI Mechaelcal Instruments and Controls 47W600-175-ISI Mechanical Instruments and Controls [4 47W600-181-ISI Mechanical Instruments and Controls 47H600-200-ISI Mechanical lastrume'ats and Controls l 47W600-227-ISI Mechanical Instruments and Controls 47W600-228-ISI Mechanical Instruments and Controls 47W600-201-ISI Mechanical Instruments and Controls 47W600-244-ISI Mechaulcal Instruments and Controls 47W600-276-ISI Mechanical Instruments and Controls 47W600-279-ISI Mechanical Instruments and Contro1r 47W600-285-ISI Hechanical Instruments and Controls 47W600-286-ISI Mechanical Instruments and Controls l 47H600-287-ISI Mechanical Instruments end Controls 1 47W600-289-ISI Mechanical Instruments and Centrols 47W600-294-ISI Mechanical Instruments and Controls 47W625-1-ISI Radiation Sampling System 47W625-2-ISI Radiation Sampling System 47W625-3-ISI Radiation Sampling System 47W625-4 ?ST Radiation Sampling System 47Wr25 9r E3diation Sampling System 47< '5-SI Radiation Sampling System t 1,4 4lo?.J. 1-ISI Main & Reheat Steam 1, e Cc id ISI Steam Generator Blowdown System i 1,2-4/H 03-1-ISI Feedwater 1,2-47H803-2-ISI Anzi11ary Feedwater System 1,2-47W803-3-ISI Auxiliary Feedwater System 1-47W809-1-ISI Chemical & Volume Control System 2-47W809-1-ISI Chemical & Volume Control System 1,2-47W809-2-ISI CVCS Chemical Control 1,2-47W809-3-ISI CVCS 1,2-47W809-4-ISI CVCS 1,2-47W809-5-ISI CVCS Chemical Control f,2-470809-7-ISI Flood Mode Boration Makeup System 1,2-47W810-1-ISI Residual Heat Removal System 1-47W811-1-ISI Safety Injection System 2-47W811-1-ISI Safety Injection System ( ~} I 1-47W811-2-ISI SI.: Upper Head Injection System 2-47W811-2-ISI SIS rpper Head Injection System 1,2-47W812-1-ISI Containment Spray System fi 1,2-47WB13-1-ISI Reactor Coolant System i-1,2-47W819-1-ISI Primary Water F^ '"*8 WP 190 1404C/COC3

Susdard Sheet SI-114.2, Attachment 1 SURVEILLAFCE Revision 0 INSTRUCTION LIST OF DRAWINGS - UNIT 2 Page 7 of 7 4 LIST OF DRAWINGS ASME Section XI Drawina Nq. Boundary _Classific? tion Drawings (Continued) 1,2-47W830-1-ISI Waste Disposal System 1,2-47W832-3-ISI Fire Protection & Raw Service Water 1,2-47W845-1-ISI Essential Raw Cooling Water System 1,2-47H845-2-ISI Essential Raw Cooling Water System 1-47W845-3-ISI Essential Raw Cooling Water System 2-47W845-3-ISI Essential Raw Cooling Water System 1,2-47W845-4-ISI Essential Raw Cooling Water System b" 1,2-47H845-5-ISI Essential Raw Cooling Water System 1,2-47W845-6-ISI Essential Raw Cooling Water System 1,2-47W850-10-ISI Fire Protection 1,2-47W851-1-ISI Floor & Equipment Drains 1,2-47W855-1-ISI Fuel Pool Cooling & Cleaning System 1,2-47W856-1-ISI Demineralized Water & Cask Decon System 1,2-47W859-1-ISI Component Cooling System 1,2-47W859-1-1-ISI Component Cooling System '~ 1-47W859-2-ISI Compenent Cooling System 2-47W859-3-ISI Comp ent Cooling System 1,2-47W869-4-ISI Component Cooling System i 1,2-47W860-1-ISI Sodium Hypochlorite System 1,2-47W862-1-ISI Steam Generator Layup Water Treatment 1,2-47W865-5-ISI Air conditioning Chill Water a L 6 e m i l t L 1V^ d>N4 PP 190 1404C/COC3 L

Sutderd Sheet SI-114.2, Attachmsnt 2 SURVEILLANCE Rsvision 0 INSTRUCTION VALVE TAELES Page 1 of 8 ISI Programs A. MAINTAIN a listing of valves requiring ISI examinations. B. UPDATE listing as necessary. C. OBTAIN concurrence from Site Ouality Manager or his designee. l SOM j D. CONCUR with listing by signing below. ISI Programs E. FORWARD to SPS for updating Table of Contents, etc. SPS F. FORWARD to DCRM. DCRM l G. DISTRIBUTE per SSP-2.7. l L / Site Quality Manager / Designee Date I. I i -l) e j a VA 40C04 (NP 2/91) I

~ n r---. m-L.~ LJ ws m.. l. r 3 i ATTACHMENT 2 I[ j TABLE I rj O VALVES SUBJECT TO THE REQUIREMENTS OF EXAMINATION M co CATEGORY 8-M-2 0F TABLE IWB-2500-10F SECTION XI

1. 2 Valve Code Valve Piping Valve Valve Valve Group ISI Dwg No. Vendor Material Valve Forging QR cM No.

Class Cat. System Size Type Act No. (Veld Map) Dwo No. Vendor Spec. Function Castino oh H 63-560 1 AC-Act SIS 10" Ck SA 2 ISI-0002-C 94-12892 Darling ASTM A5161 PSIV 63-561 1 AC-Act SIS 10" Ck SA 2 ISI-0002-C 94-12892 Carling ASTM A516l PSIV 63-562 1 AC-Act SIS 10" Ck SA 2 ISI-0002-C 94-12892 Darling ASTM A516l PSIV 63-563 1 AC-Act SIS 10" Ck SA / ISI-0002-C 94-12892 Darling ASTM A516I PSIV 63-622 1 AC-Act SIS 10" Ck SA 2 ISI-0002-C 94-12892 Darling ASTM A516l PSIV 63-623 1 AC-Act SIS 10" Ck SA 2 ISI-0002-C 94-1289 Darling ASTM A5161 PSIV 63-624 1 AC-Act 515 10" Ck SA 2 ISI-0002-C 94-12892 Darling ASTM A5161 PSIV 63-625 1 AC-Act SIS 10" Ck SA 2 ISI-0002-C 94-12892 Darling ASTM A5161 PSIV 63-640 1 AC-Act SIS /RHR 8" Ck SA 2 ISI-0003-C 94-12892 Carling ASTM A516I PSIV 63-643 1 AC-Act SIS /RHR 8" Ck SA 2 ISI-0003-C 94-12892 Darling ASTM A5161 PSIV 63-558 1 AC-Act SIS 6" Ck SA 3 ISI-0002-C 78704 Velan ASTM A182 PSIV Forging D3 63-559 1 AC-Act SIS 6" Ck SA 3 ISI-0002-C 78704 Velan A'TM A182 PSIV Forging 4 63-632 1 AC-Act $15 6" Ck SA 3 ISI-0002-C 78704 Velan ASTM A182 PSIV Forging 63-633 1 AC-Act SIS 6" Ck SA 3 ISI-0002-C 78704 Velan ASTM A182 PSIV Forging y 63-634 1 AC-Act SIS 6" Ck SA 3 ISI-0002-C 78704 Velan ASTM A182 PSIV Forging 63-635 1 AC-Act SIS 6" Ck SA 3 ISI-0002-C 78704 Velan ASTM A182 PSIV Forging 63-641 1 AC-Act SIS /RHR 6" Ck SA 3 ISI-0003-C 78704 Veian ASTM A182 PSIV Forging 63-644 1 AC-Act SIS /RHR 6" Ck SA 3 ISI-0003-C 78704 Velan A3TM *182 PSIV Forging 68-563 1 C RCS 6" Rel SA 4 ISI-0013-C H51688 Crosby ASTM A182/ See A3512 Note 2 68-564 1 C RCS 6" Rel SA 4 ISI-0013-C HS1688 Crosby ASTM A182/ See A3512 Note 2 68-565 1 C RCS 6" Rel SA 4 ISI-0013-C H51688 Crosby ASTM A182/ See A3512 Note 2 yy$ FCV 74-1 1 A-Act RHR 14" Gate NO 5 ISI-0003-C E-1-144831 Copes-Vulcan ASTM A182 PSIV Forging j$$ FCV 74-2 1 A-Act RHR 14" Gate MO 5 ISI-0003-C E-1-144831 Copes-Vulcan ASTM A182 PSIV Forging g ow $ " ~~ ny NOTES: o y c' 8 I Seal plate manufactured to ASTM A240 F304 Body to ASTM A351 grade CF-8. g 's 2Nozzle manuf actured to ASTM A182 F316 - Forging body manuf actured to ASTM A351 CRBM - Casting n E: N

C C C C C ~' I G u E ATTACHMENT 2 4. m 3 TABLE 2 5 i re O CLASS 1 VALVE INF0cf% TION yy f yy SIZE VALVE BOLTING VLV BODY E$ SYS VLV NO (IN) TYPE ISI DWG NO VENDOR VENDOR DWG NO (= 2" >2" WELDS IAI Q"E a CVC 62-560 2 CKV MSG-0008-C SH1 EDWARD D-464529 R5 N/A N/A NONE N/A

• Q CVC 62-561 2

CKV MSG-0008-C SH2 EDWARD D-464529 R5 N/A N/A NONE N/A CVC 62-562 2 CKV MSG-0008-C SHS EDWARD D-464529 R5 N/A N/A NONE N/A t'VC 62-563 2 CKV MSG-0008-C SH3 EDWARD D-464529 R5 N/A N/A NONE N/A CVC 62-564 2 GATE MSG-0008-C SH1 EDWARD D 464532 R5 N/A N/A NONE N/A CVC 62-565 2 GATE MSG-0008-C SH2 EDWARD D-464532 R5 N/A N/A NONE N/A CVC 62-566 2 GATE MSG-0008-C SH5 EDWARO D-464532 R5 N/A N/A NONE N/A CVC 62-567 2 GATE MSG-0008-C SH3 EDWARD D-464532 R5 N/A N/A NONE N/A CVC 62-576 2 CKV MSG-0008-C SH1 EDWARD D-464529 R5 N/A N/A NONE N/A CVC 62-577 2 CKV MSG-0008-C SH2 EDWARD D-464529 R5 N/A N/A NONE N/A 4' CVC 62-578 2 CKV MSG-0008-C SH4 EDWARD D-464529 R5 N/A N/A NONE N/A CVC 62-579 2 CKY MSG-0008-C SHS EDWARD D-464529 R5 N/A N/A NONE-N/A CVC 62-6592 3 CKV ISI-0009-C Sh2 BORG-WARNER 80290 5/16" N/A NONE N/A N CVC 62-6602 3 CKV ISI-0009-C SH2 BORG-WARNER 80290 5/16" N/A NONE N/A CVC 62-661 2 CKV ISI-0009-C SH2 EDWARD C-464529 R5 N/A N/A NONE N/A E CVC 62-7162 3 CKV ISI-0009-C SH2 BORG-WARNER 80290 5/16" N/A NONE N/A B CVC 62-7172 3 CKV ISI-0009-C SH2 BORG-WARNER 80290 5/16" N/A NONE N/A RHR 63-543 2 CKV ISI-0003-C SH8 EDWARD C-464529 R5 N/A N/A NONE N/A RHR 63-545 2 CKV ISI-0003-C SH8 EDWARD C-464529 R5 N/A N/A NONE N/A SIS 63-547 2 CKV ISI-0002-C SH12 EDWARD C-464529 R5 N/A N/A NOME N/A SIS 63-549 2 CKV ISI-0002-C SH12 EDWARD C-464529 R5 N/A N/A NONE N/A SIS 63-551 2 CKV

SI-0002-C SHS EDWARD C-464529 R5 N/A N/A NONE N/A SIS 63-553 2

CKV ISI-0002-C SH6 EDWARD C-464529 R5 N/A N/A NONE N/A SIS 63-555 2 CKV ISI-0002-C SH6 EDWARD C-464529 R5 N/A N/A NONE N/A SIS 63-557 2 CKV ISI-0002-C SH4 CDWARD C-464529 R5 N/A N/A NONE N/A [E$ SIS 63-558 6 CKV 151-0002-C SH7 VELAN 78704 1 1/4" N/A NONE N/A $$h SIS 63-559 6 CKV ISI-00C2-C SH7 VELAN 787C4 1 1/4" N/A NONE N/A wE$ w SIS 63-560 1D CKV ISI-0002-C SHS ANCHOR / DARLING 94-12892 1 3/8" N/A NONE N/A o@* w o "o' N N 8 I Integrally welded attachment. E 2Exempt from examination requirements of Category B-G-2 O th Code Case N-426. Ea N

~ - - L .s u _ o; w ta 2 h ATTACHMENT 2 ) ^z TA8LE 2 (Continued) $y ~E CLASS 1 VALVE INFORtuTION wm 5s SIZE n< VALVE BOLTING VLV BODY ED SYS VLV N0 (IN) TYPE ISI DWG NO VENDOR VENDOR CVG NO <- 2" >2" VELOS IAI Q" B6 SIS 63-561 10 CKV ISI-0002-C SH6 ANCHOR / DARLING 94 12892 1 3/8" N/A NONE N/A EQ SIS 63-562 10 CKV ISI-0002-C SH6 ANCHOR / DARLING 94-12892 1 3/8" N/A NONE N/A SIS 63-563 10 CKV ISI-0002-C SH4 ANCHOR / DARLING 94-12892 1 1/8" N/A NONE LA SIS 63-5812 3 CKV ISI-0002-C SH7 VELAN 78409 3/4" N/A NONE N/A SIS 63-582 1 1/2 GATE ISI-0002-C SH8 ROCKWELL INTERNATIONAL D-478072 N/A N/A NONE N/A SIS 63-583 1 1/2 GATE ISI-0002-C SH9 ROCKVELL INTERNATIONAL D-478072 N/A N/A NOME N/A i SIS 63-5E4 1 1/2 GATE ISI-0002-C SH10 ROCKVELL INTERNATIONAL D-478072 N/A N/A NONE N/A SIS 63-585 1 1/2 GATE ISI-0002-C SH11 ROCKVELL INTERNATIONAL D-478072 N/A N/A NONE N/A j SIS 63-586 1 1/2 CKV ISI-0007-C SH8 EDWARD C-465347 R2 N/A N/A NONE N/A SIS 63-587 1 1/2 CKV ISI-0002-C SH9 EDWARD C-465347 R2 N/A N/A NONE N/A SIS 63-588 1 1/2 CKV ISI-0002-C SH10 EDWARD C-465347 R2 N/A N/A NONE

• A 2

4 SIS 63-589 1 1/2 CKV ISI-0002-C SH11 EDWARD C-465347 R2 N/A N/A NONE N/A D' SIS 63-622 10 CKV ISI-0002-C SHS ANCHOR / DARLING 94-12892 1 3/8" N/A NONE N/A SIS 63-623 10 CKV ISI-0002-C SH6 ANCHOR / DARLING 94-12892 1 3/8" N/A NONE N/A p SIS 63-624 10 CKY ISI-0002-C SH6 ANCKR/ DARLING 94-12892 1 3/8" N/A NONE N/A SIS 63-625 10 CKV ISI-0002-C SH4 ANCHOR /LARLING 94-12892 1 3/8" N/A NONE N/A SIS 63-632 6 CKY ISI-0002-C SH6 VELAN 78704 1 1/4" N/A NONE N/A SIS 63-633 6 CKV ISI-0002-C SHS VELAN 78704 1 1/4* N/A NONE N/A SIS 63-634 6 CKV ISI-0002-C SH6 VELAN 78704 1 1/4" N/A NONE N/A SIS 63-635 6 CKV ISI-0002-C SH4 VELAN 78704 1 1/4" N/A NONE N/A RHR 63-640 8 CKV ISI-0003-C SHS ANCHOR / DARLING 94-12892 1 3/8" N/A NONE N/A RHR 63-641 6 CKV ISI-0003-C SHS VELAN 78704 1 1/4" N/A NONE N/A RHR 63-643 8 CKV ISI-0003-C SH6 ANCHOR / DARLING 94 12892 1 3/8" N/A NONE N/A RHR 63-644 6 CKV ISI-0003-C SH6 VELAN 78704 1 1/4" N/A NONE N/A RCS 68-549 2 GATE ISI-0013-C SH10 EDWARD D-464532 N/A N/A NONE N/A 7 5' " RCS 68-550 2 GATE ISI-0013-C SH10 EDWARD D-464532 N/A N/A NONE N/A j$$ RCS 68-553 2 GATE ISI-0013-C SH10 EDWARD % 464532 N/A N/A NONE N/A a"% g RCS 68-554 2 GATE ISI-0013-C SH10 EDWARD D-464532 N/A N/A NONE N/A o@* u o' x 8 I Integrally welded attachment. E 2Exempt f rom examination requirements of Category B-G-2 with Code Case N-426. $e N i

L, _ p-- .y., n m fi h' E ATTACm ENT 2 h ^z TABLE 2 (Continued) U i t CLASS 1 VALVE INFORMATION yy El 4 SI2E MLVE 60LTING VLV BODY SYS VLV W+ (IN) TYPE ISI DWG NO VENDOR VENDOR OWG NO 2" >2* VELDS IAI Q"E a RCS 68-557 2 GATE ISI-0013-C SH11 EDWARD D-464532 N/A N/A NONE N/A %Q RCS 68-558 2 GATE ISI-0013-C SH11 EDWARD D-464532 N/A N/A NONE N/A KCS 68-563 6 RELF ISI-0013-C SH3 CROSBY H-51688 1" N/A NONE N/A RCS 68-564 6 RELF ISI-0013-C SH3 CROS8Y H-51688 1" N/A NONE N/A RCS 68-565 6 RELF 151-C013-C SH3 CROSBY H-51688 1" N/A NONE N/A CVC 68-580 3 GATE ISI-0099-C SH1 VELAN 13920 N/A N/A NONE N/A RCS 68-581 2 GATE ISI-0013-C SH11 CDWARD 0-464532 N/A N/A NONE N/A RCS 68-582 2 GATE ISI-0013-C SH11 EDWARD D-464532 N/A N/A NONE N/A CVC FCV-62-692 3 GATE ISI-0009-C SH1 HASONEILAN/WORTHINGTON CPI-1855,A8425 7/8" N/A NONE N/A CVC FCV-62-702 3 GATE ISI-C009-C SH1 MASONEILAN/WORTHINGTON CPI-1855,A84757 7/8" N/A NONE N/A CVC FCV-62-842 2 GATE ISI-0009-C SH2 HASONEILAN A-8474,A-8475 7/8" N/A NONE N/A RCS FCV-68-3322 3 GATE ISI-G013-C SH3 VELAN 02-405-0494-2 3/4" N/A NONE N/A M RCS FCV-68-3332 3 GATE ISI-0013-C SH3 VELAN 02-405-0494-2 3/4" N/A NONE N/A y RHR FCV-74-1 14 GATE ISI-0003-C SH7 COPES-WLCAN E-1-144831 R4 1 3/4" N/A NONE N/A RHR FCV-74-2 14 GAiE ISI-0003-C SH7 COPES-WLCAN E-1-144831 R4 1 3/4" N/A NONE N/A UHI FCV-87-7 2 GATE ISI-0001-C SH2 COPES-WLCAN L-170203 R2 1 1/8" N/A NONE N/A UHI FCV-87-8 2 GATE ISI-0001-C SH1 COPES-WLCAN L-170203 R2 1 1/8" N/A NONE N/A RCS PCV-68-34002 4 BALL ISI-0013-C SH1 FISHER 50A2159 7/8" N/A NONE N/A q RCS PCV-68-340A 3 GLB ISI-0013-C SH3 TARGET ROCK 1052020-3 N/A N/A NONE N/A RCS PCV-68-34082 4 BALL ISI-0013-C SH1 FISHER 50A2159 7/8" N/A NONE N/A RCS PCV-68-334 3 GLB ISI-0013-C SH3 TARGET ROCK 1052020~3 N/A N/A NONE N/A 5NO .b ww+ o, $,'w owo I o h Integrally welded attachments. 8 2 Exempt f rom examination requirements of Category B-G-2 in accordance with Code Case N-426. n

e N

p 7 r e p ~ b r-ATTACHMENT 2 0 a TABLE 3 [? i CLASS 2 VALVE INFORMATION aa SIZE VALVE BOLTING VLV B00Y @M .SYS VLV N0 FIN) TYPE ISI DWG NO VENDOR VENDOR DWG NO <= %" >2" WELDS IAI Q" sE MS FCV-1-4 32 GATE ISI-0015-C SH1 ATWOOD & MORRILL CO 21245-H 2" N/A NONE N/A

• Q MS FCV-1-11 32 GATE ISI-0015-C SH2 ATWOOD & MORRILL CO 21245-H 2"

N/A NONE N/A i MS FCV-1-22 32 GATE ISI-0015-C SH2 ATWOOD & MORRILL CO 21245-H 2" N/A NONE N/A l MS FCV-1-29 32 GATE ISI-0015-C SH1 ATWOOO & HDRRILL CO 21245-H 2" N/A NONE N/A MS 1-619 6 GATE ISI-0015-C SH1 WALWORTH A-6603-41282 7/8" N/A NONE N/A MS 1-620 6 GATE ISI-0015-C SH2 W4LWORTH A-6609-M-1288 7/8" N/A NONE N/A i MS 1-621 6 GATE ISI-0015-C SH2 WALWORTH A-6609-M-1283 7/8" N/A NONE N/A HS 1-622 6 GATE ISI-0015-C 5H1 WALWORTH A-6609-* 1288 7/8" N/A NONE N/A MS 1-512 6 SAF ISI-0015-C/2 CROSBY H-55095 1.3/8" N/A NONE N/A MS 1-513 6 SAF ISI-0015-C/2 CROSBY H-55095 1 3/8" N/A NONE N/A MS 1-514 6 SAF ISI-0015-C/2 CROSBY H-55095 1 3/8" N/A NONE N/A MS 1-515 6 SAF ISI-0015-C/2 CROSBY H-55095 1 3/8" N/A NONE N/A M 4 MS 1-516 6 SAF ISI-00'5-C/2 CROSBY H-55095 1 3/8" N/A NONE N/A N MS 1-517 6 SAF ISI-0015-C/2 CROSBY H-55095 1 3/8" N/A NONE H/A MS 1-518 6 SAF ISI-0015-C/2 CROSBY H-55095 1 3/8" M/A NONE N/A Q MS 1-519 6 SAF ISI-0015-C/2 CROSBY H-55095 1 3/8" h/A NONE N/A MS 1-520 6 SAF ISI-0015-C/2 CROSBY H-55095 1 3/8" N/A NONE N/A MS 1-521 6 SAF ISI-0015-C/2 CROSBY H-55095 1 3/8" N/A NONE N/A MS 1-522 6 SAF ISI-0015-C/1 CROSBY H-55095 1 3/8" N/A NONE N/A MS 1-523 6 SAF ISI-0015-C/1 CROSBY H-55095 1 3/B* N/A NONE N/A MS 1-524 6 SAF ISI-0015-C/1 CROSBY H-5509$ 1 3/8" N/A NONE N/A MS 1-525 6 SAF ISI-0015-C/1 CROSBY H-55095 1 3/8" N/A NONE N/A HS 1-526 6 $AF ISI-0015-C/1 CROSBY H-55095 1 3/8" N/A NONE N/A MS 1-527 6 SAF ISI-0015-C/1 CROSBY H-55095 1 3/8" N/A NONE N/A MS 1-528 6 SAF ISI-0015-C/1 CROSBY H-55095 1 3/8" N/A NONE N/A g $8 $ MS 1-529 6 SAF ISI-0015-C/1 CROSBY H-55095 1 3/8" N/A NONE N/A j $h MS 1-530 6 SAF ISI-0015-C/1 CROSBY H-55095 1 3/8" N/A NONE N/A ,E% s MS 1-531 6 SAF ISI-0015-C/1 CROSBY H-55095 1 3/8" N/A NONE N/A o @ *w l MS PCV-1-5 6 GATE ISI-0015-C SH1 COPES-VULCAN B-149093 R7 Yes N/A NONE N/A "o' co y tv fi I Integrally welded attachment. M j T

-~ w I ( L___ _; f ATTACHHENT 2 h ^z TABLE 3 E v s e: CiASS 2 VALVE INFORMATION N 05 5h $12E +4 < VALVE BOLTING VLV BODY @Q $YS VLV N0 FIN) TYPE ISI DWG NO VENDOR VENDOR OWG to <= 2" >2" VELOS IAI QC oI MS PCV-1-12 6 GATE ISI-0015-C SH2 COPES-VULCAN 8-149093 R7 Yes N/A NONE N/A

• Q MS PCV-1-23 6

GATE ISI-0015-C Sh2 COPES-VULCAN 8-149093 R7 Yes N/A NONE N/A HS PCV-1-30 6 GATE ISI-0015-C SH1 COPES-VULCAN B-149093 R7 Yes N/A NONE N/A N FCV-3-33 18 GATE CHM-2403-C Sh1 WALWORTH A-6614-M-150 1 1/2" N/A NONE N/A N FCV-3-47 18 CATE CHM-2403-C SH2 WALWORTH A-6614-M-150 1 1/2" N/A NONE N/A FW FCV-3-87 18 GATE CHM-2403-C $H2 WALWORTH A-6614-N-150 1 1/2" N/A NONE N/A N FCV-3-100 18 GATE CHM-2403-C *Hi WALWORTH A-6614-M-150 1 1/2" N/A NONE N/A N 3-508 16 CKV CHH-2403-C SH2 VALWORTH A-11332-M-32A 1 3/4" N/A NONE N/A N 3-509 16 CKV CHM-2403-C SH2 WALWORTH A-11332-M-32A 1 3/4" N/A NONE N/A N 3-510 16 f.KV CHM-2403-C SH1 WALWORTH A-11332-M-32A 1 3/4" N/A N0OT N/A 4 W 3-511 16 CKV CHH-2403-C SH1 WALWDRTH A-11332-M-32A 1 3/4" N/A NONE N/A RHR 74-514 8 CKV ISI-0003-C SH2 CRANE K-7422 7/8" N/A NONE N/A "8 RHR 74-515 8 CKV ISI-0003-C SH3 CRANE K-7422 7/8" N/A NONE N/A '4 RHR 74-520 8 GATE ISI-0003-C SH2 ALOYC0 E-47381 3/4" N/A NONE N/A RHR 74-521 8 GATE ISI-0003-C Sd3 ALOYC0 E-47381 3/4" N/A NONE N/A Q RHR 74-524 8 GATE ISI-0003-C SH2 ALOYC0 E-47381 3/4" N/A NONE N/A RHR 74-525 8 GATE ISI-0003-C SH3 ALOYC0 E-47381 3/4" N/A NONE N/A RHR FCV-63-72 18 GATE ISI-0003-C SH1 ANCHOR / DARLING 94-13300 1 1/4" N/A NONE N/A RHR FCV-63-73 '18 GATE 151-0003-C SH1 ANCHOR / DARLING 94-13aa0 1 1/4" N/A NONE N/A RHR FCV-63-172 12 GATE ISI-0003-C SHS VELAN 88907-2 1 7/8" N/A NONE N/A RHR FCV-74-3 14 GATE ISI-0003-C SH4 ANCHOR / DARLING 94-13298 1 1/8" N/A NONE N/A RHR FCV-74-16 8 BUTF ISI-0003-C SH2 FISHER GOVERNOR C0 F-41304 5/8" N/A NONE N/A RHR FCV-74-21 14 GATE ISI-0003-C SH4 ANCHOR / DARLING 94-13298 1 1/8" N/A NONE N/A RHR FCV-74-28 8 BUTF ISI-0003-C SH3 FISHER GOVERNOR CO c-41304 5/8" N/A NONE N/A RHR FCV-74-32 8 BUTF ISI-0003-C SH2 FISHER GOVERNOR C0 F-41304 5/8* N/A NONE N/A yy$ RHR FCV-74-33 8 GLOB 15I-0003-C SH2 ANCHOR / DARLING 93-13435 3/4" N/A NONE N/A j1L RHR FCV-74-35 8 GATE I51-0003-C SH3 ANCHOR / DARLING 93-13435 3/4" N/A NONE N/A aE% g RHR HCV-74-34 8 GATE ISI-0003-C SH3 ANCHOR / DARLING 93-13435 3/4" N/A NONE N/A @ *u osn 8" I !ntegrally welded attachment. a N

G, 7 ~ ~ W "~* E E ATTACHMENT 2 h 's IABLE 3 (Continued) [ m, T } CLASS 2 VALVE INFORMATION yy n% SIZE VALVE 8OLTING VLV 80DY gM SYS VLV N0 flN) TYPE ISI DWG NO VENIQR VENDOR LVG NO <= 2" >2" WELOS IAI Q r* Eh RHR HCV-74-36 8 GATE ISI-0003-C SH2 ANCHOR / DARLING 93-14074 3/4" N/A NONE N/A

• Q RHR HCV-74-37 8 GATE ISI-0003-C SH3 ANCHOR / DARLING 93-1343S 3/4" N/A NONE N/A SIS FCV-63-1 16 GATE ISI-0002-C SHI CRANE K-7634-15,16 7/8" N/A NONE N/A SIS FCV-63-8 8

GATE ISI-0002-C SH3 ANCHOR / DARLING 94-1329S 7/8" 'N/A NONE N/A SIS FCV-63-11 8 GATE ISI-0002-C SH3 ANCHOR / DARLING 94-1329S 7/8" N/A NONE N/A SIS FCV-72-41 8 C/,TE ISI-0002-C SH3 ALOYC0 E-48836 Yes N/A NONE N/A SIS 63-502 12 CKV ISI-0902-C SH! ALOYC0 048276,K742,1C 1" N/A NONE N/A SIS FCV-63-67 10 6hTE ISI-0002-C SH4 VELAN 88W6 R.01 1 3/8" N/A NONE N/A SIS FCV43-80 10 GATC ISI-0002-C SH6 VELAN 88926 R.31 1 3/8" N/A NONE N/A SIS FCV-63-93 8 GATE 151-00024 SH1 VELAN 8806-1 1 3/8" N/A NONE N/A SIS FCV-63-98 10 GATC 151-00024 SH6 VELAN 88936 R.D1 1 3/8" N/A NONE N/A SIS FCV-63-118 10 GATE ISI-0002-C SH5 VELAN 88926 R.DI 1 3/8" N/A NONE N/A M 'IS FCV-7E-40 8 GATE ISI-0002-C SH3 ALOYC0 E-48836 Y7s N/A NONE N/A '4 SIS FCV-63-94 8 GATE 151-0002-C SH2 VELAN 88806-1 1 3/8" N/A NONE N/A CS FCV-72-20 12 CATE ISI-0007-C SH1 ALOYC0 E-48840 Yes N/A NONE N/A y CS FCV-72-23 12 GATE ISI4007-C SH1 ALOYC0 E-48840 Yes N/A NONE N/A 55$ e 'a 15 mO5 w o $ *w o o' N N 8 0 I Integrally welded attachment. ,I a w m

St:nJard Sheet SI-114.2, Attachmant 3 CURVEILLANCE Revision 0 INSTRUCTION REQUESTS FOR RELIEF Page 1 of 42 ISI Programs A. MAINTAIN a listing of Requests for Relief. B. UPDATE listing as necessary. C. OBTAIN concurrence from Site Quality Manager or his designee. SOM l{ D. CONCUR with listing by signing below. ISI Programs E. FORWARD to SPS for updating Table of Contents, etc. SPS L F. FORWARD to DCRM. Ii DCEM i G. DISTRIBUTE per SSP-2.7. I -[ i I / Site Quality Manager / Designee Date 3 I 2 e + J .a i v4 40c04 (NP 2s1) 1406C/COC3 i

Susard Sheet SI-114.2, Attachment 3 SURVEILLANCE Rsvision O INSTRUCTION REQUESTS FOR RELIEF Page 2 of 42 4 Y BEOUEST FOR RELIEF ISI-1 Components: Reactor coolant pumps (four per unit) Class: ASME Code Class 1 (Equivalent) Functions Circulates reactor coolant Inspection Recuirements ASME Section XI, Table INB-2500-1, examination category B-L-2, item No. B12.20, visual examination of pump internal pressure boundary surface. Basis for Relieft In absence of required maintenance, disassembly of a M reactor coolant pump solely to perform a visual examination of internal surfaces is impractical. This vould represent an unnecessary employee erposure to high radiation and contamination areas and an excessive expense to TVA. 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 100 to 300 mrem / hour, and pump internal dose tates will average 10 to 20 rem / hour. The benefit received from this major effort is k minimal considering employee exposure, potential damage to safety-related equipment, and cost in dollars. In addition, the two units at Sequoyah Nuclear Plant will operate under similar conditions. Therefore, we feel that if a pump from one of the units is disassembled for maintenance during a ten-year interval, the visual examination performed will be representative of the pump condition for each unit. This would avoid unnecessary employee exposure to the high radiation dose rates noted above. We conclude that if one pump is disassembled for maintenance during the 10-year interval, the visual ,i examination performed satisfies examination category B-L-2 requirements for both units. Disassembly of the pump solely for visual examination is impractical. a I vA 4mx4 (np r90 1406C/COC3

Sts>dard Shres SI-114.2, Attachmsnt 3 SURVEILLANCE Revision 0-INSTRUCTION REQUESTS FOR RELIEF Page 3 of 42 REOUEST FOR RELIEF ISI-1 (Continued) Alternate Inspectinn The internal surface of the reactor coolant pump casing will be visually examined whenever the surfaces are made accessible when a pump is disassembled for maintenance purposes. If during the ten-year interval a purnp from either unit is not disassembled for maintenance, a pump frcm oba unit shall be examined from the exterior. This shall be accomplished by ultrasonic thickness measurements of the pump casing. Safety Evaluation Summarve Request for Relief 1SI-1 has been approved with the following additional augmented requirements: (a) The required visual examinations are conducted under Category B-L-2 If a reactor coolant pump from one of two units is disassembled for maintenance; i (b) If during the 10-year interval, a pump from either unit is not disassembled for maintenance, a pump from one unit shall be examined from { the exterior by ultrasonic thickness measurements; i (c) Visual examination of the pump casing for leakage is conducted in conjunction with system leakage and hydrostatic tests under Category B-P. I Reference Memorandum from F. J. Hebdon, NRC, to O. D. Klagsley, TVA, dated February 7, 1991 (A02 910211 001). Memorandum from Suzanne Black, NRC, to 0. D. Kingsley, TVA, dated April 19, 1990 (A02 900426 005). I l VA 4WM4 (NP l.90 1406C/COC3 1

Sundard Sket 1 SI-114.2, Attachment 3 SULVEILLANCE Revision 0 ~ .\\ INSTRUCTION RECUESTS FOR RELIEF Page 4 of 42 + 1 t ) 5, PEOUEST FOR RELIEF 131-1 } i e hAN L2m2naents: Valves exceeding four-inch nominal pipe size s Class: ASME Code Class 1 (Equivalent)

- v

' t: Various.iunctiens tequirement: ASME Section XI, Table IWB-2500-1, examinatiou ,j-category B-M-2, item No. B12.40, visual examination j{ of valve internal pressure boundary surface n y y c_ Relief: During routine maintenance, visual examinations of valve body interral pressure boundary surfaces are performc0 and documented under existing plant i administrative procedures. Most Clnss 1 valves, p particularly containment isolation valves, are disassembind frequently for maintenance. In addition, the two units at Sequoyah Nuclear Plant will operate under similar conditions. If a valve I from one of the units is disassembled for maintenance within a ten-year interval, we feel that the visual examination performed would be representative of both units and would be sufficient to satisfy the i. examination requirements for both units for that particular valve classification as defined in examination category B-M-2. We conclude that f one valve in each group of valves of the same constructional design and manufacturci trat perlorm similar functions is disassembled from either unit during the ten-year interval, the visual examination performed satisfies examination category B-M-2 requirementa of both units. f, Alternate Inspecticn: If a valve from a particula. classitication bas not been disassembled as the end of the inspection interval approaches, a case-by-case study will be made to datermiae the practicality . disassembling a k valve from one of the uults solel, for visua. .) examination (determine if draining the vessel would be 2eqtised, etc.). If necessary, a zequest for relief will be issued at that time. e J ] (Continued) .J l A 4MN @P 2NQ 1406C/COC3 u

~. Staadard Sheet - SI-114.2, Attachment 3 ' SURVEILLANCE Revision 0-INSTRUCTION REQUESTS FOR RELIEF Page 5~of 42 a I'1 REOUEST FOR RELIEF ISL-1 q (Cs inued) Safety Evaluatlor. Summary i -Request for Relief ISI-2 has bees approved with the following additional augmented requirements (a) one comparable valve in either unit is examined. If a certain type of valve is not. examined at either unit, relief should be requested on a case-by-case basis near the end of the interval. References Memorandum from F. J. Siebdon, NRC, to O. D. Kingsley, TVA, dated ,.g February 7, 1991 (A02 910211 001). Memorandum from Suzanne Black, NRC, to O. D. Kingsley, TVA, dated April 19, 1990 (A02 900426 005). 1 9 l l 1 a I a. e = ~ o e ^ " W "O 1406C/COC3 .V, ,J, .A

~ - -. - ~. _. .. -.. - ~.. -.. 1 susaud shuf SI-114.2, Attachman 3 SURVEILLANCE Ravision 0 LINSTRUCTION REQUESTS FOR RELIEF = Page 6 of 42 g .1 I (5) REOUEST FOR RELIEF ISI-3 _a 2 components: Pressure-retaining welds in piping . Class: ASME Code Class 1 and 2 (Equivalent) Functf<m:- Pressure-retaining component = Inspection Recuirementt ASME Section XI, Table IWB-2500 1 examination categories B-F (icem No. B5.50), J (item Nos. B9.10, B9.20, and BV.30), and C-F ' tem Nos. C5.10, .1 C5.20, and= C5.30), volumetric examination of longitudinal, circumferential, and pipe branch connection welds. 1 i-RApir for-Reliefs In somo-cases it will be impractical to inspect all welds frou boch sides, i.e.,-nonremovable hanger interference or valve and pump casings adjoining the welds. These welds will be noted on the ultrasonic examination data sheets and on attachment A of this i request for relief. 31 ternate Inspection: In addition to the visual examination performed q during system leakaga and hydrostatic pressure tests,

'l{

L a "best effort" ultrasonic examination and a surface examination will be-performed on accessible areas of the weld (s). r Where there is int.erference or problems from one direction only, consideration will be given to performing an angle beam examination for 2T + js (creater than two' wall thicknesses from one edge of ws d) from the accessible side-of the wold in order to examine the entire weld cross-section. if -- t L -Safety Evaluation Summary - Request for Relief ISI-3 has been approved in the following manners Eram Catecoty B-F \\pproved with no additJ7nal augmented requirements. B-J Approved with a substitutica for Safety j Injection Held SIF-128 , ({; deld R$-33-has been substituted for SIF-128 for inspection during this f 3-luterval.

Reference:

- Memorandum from F. J. Hebdon, NRC, to 0. D. Kingsley, TVA, dated ,'~ February 7, 1991 (A02 910211 001). Memorandum from Suzanne Black, NRC, to 0. D. Kingsley, TVA, dated April 19, 1990 (A02 900426 005). l A4 44pe2so-y 1406C/COC3

_..r-.-.,. s 3 L, 5 E. O D 3 e a a E y REOUEST FOR RELIEF 151-3 (Continued) MM A_(tachment A g sa M2 CH O w WELD Pf"'SICAL CODE @n N11M_QI.R_ 1[ZE ( L t1_ATL DRAWING NUMBER CONF 13URATION 1[ANZLIMITATIQN_3 1[AN REMARKS M RHRF-12S 6" B-J SS ISI-0003-C Nozzle / Elbow 4/No scan B3% No scan 4 due to nozzle geometry (Sheet 5) 3/No scan S:00-7:00 No scan 3 from 5:00-7:00 due to inner radius RCF-23 4" B-J SS ISI-0013-C Elbow / Safe-end 4/No scan 75% No scan 4 due to safe-end geometry (Sheet i) 3/ Limited scan Scan 3 limited by inner radius of I elbow RCW-29 SE 14" B-F SS/CS ISI-0308-A Nozzle / Safe-end 3/ Limited at 90% Scan 3 limited by 1" WGS at 12:00, (Sheet 1) 12:00, 3:00, 3:00, 6:00, and 9:00 g 6:00 and 9:00 No scan 4 due to nozzle geometry o 4/No scan M SIF-128 10" B-J SS 151-0002-C Valve / Tee 3 and 4/No scan 0% No scan 3 and 4 due to valve-(5heet 4) to-tee geometry RCW-24 SE 4" B-F SS/CS ISI-0308-A Nozzle / Safe-ent 4/No scan 40% No scan 4 due to safe-end geometry g (Sheet 1) 3/ Limited Scan 3 limited by nozzle curvature RC-3 31" B-J SS 151-0008-8 Saf e-end/ Elbow 3/No scan 50% No scan 3 due to nozzle geometry M 4/1/2 node H RC-1 S2 29

• B-J SS 151-0008-B Pipe / Elbow 3/ Limited 9:30 98%

Scan 3 limited by one inch nczzles N and 10:30 at 9:30 and 10:30 RC-2 29" B-J SS 151-0008-8 ELL-SE No scan from 50% No scan due to nozzle geometry nozzle side RC-2-SE 29" B-F SS ISI-0008-B SE-Nozzle Ho scan from 50% No scan due to nozzle g u etry nozzle side y g RC-3-SE 31" B-F SS ISI-0008-8 Nozzle-SE No sc a from 50% No scan due to nozzle geometry ygm g nozzle side jg4 g RC-10 29" B-J SS 151-0008-8 ELL-SE No scan from 50% No scan due to nozzle geometry to,, y q o nozzle side og; u n PJ K ii e, W

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maard sheet SI-ll4.2, Attachmant 3 SURVEILLANCE Revision 0 INSTRUCTION REQUESTS FOR RELIEF Page 9 of 42 1 4 REOUEST FOR RELIEF ISI-3 (Continued) NOTLr-1. LS following seam number indicates longitudinal seam. 2. SE following seam number indicates safe end weld. 8. Categories determined in accordance with ASME XI 77S78. 4. P= Pipe, V= Valve, E= ELL, T= TEE, R= Reducer, F= Flange, NaNozzle, Pen P= Penetration Process Pipe, Pen F= Penetration Flued Head, and SE= Safe End EF 5. Scans 3 and 4 are perpendicular to circumferential welds. Scans 5 and 6 are perallel to circumferential welds. Scans 7 and 8 aro perpendicu4ar to longitudinal welds. Scans 9 and 10 are parallel to longitudinal welds. 6. Limitations are expressed in o' clock references. In general, the exact limitation is noted rather than a percentage of the required examinations. 7. Actual percentages indicate the approximate area of examination i coverage obtained. 8. Because of the attenuation resulting from inherent coarse grain structure in cast stainless steel the examination is limited to 6 b the 1/2V technique. Also physical restrictions prevent the eram from both sides of the weld. P 9. Detail description of limitations are noted. L.. 1 } -t d^ ' ) 1406C/COC3

stssdud Sheet SI-114.2, Attachmsnt 3 SURVEILLANCE Revision 0 INSTRUCTION REQUESTS FOR RELIEF Page 10 of 42 I REOUEST FOR RELIEF ISI-4 CREED.ntnt s - Steam generator (four per unit) CIA 11: ASME Code Class 2 (Equivalent) -l Inspection Requirement: ASME Section XI, Table IWB-2500-1, examination category C-A, item No. C1.10, volumetric examination of circumferential shell welds. Basis for Relief: One circumferential shell veld on each generator is inaccessible due to the upper steam generator support brackets (weld Nos. SGW-Dl, -D2, -D3 and -D4). See b' ' attached drawing CH-M-2345-B for weld location. Also attached drawing CH-M-2345-B for weld location. Also attached are drawings showing arrangements of the i support brackets. One weld on one generator will be l examined on a "best effort" basis for the baseline and during the four in-service inspection intervals in accordance with IWC-2411 and Table IWC-2500-1. ~ Alternate Inspection: None Safety Evaluation Summary; Request for Relief ISI-4 has been approved with no additional augmented requirements. L

Reference:

Memorandum from F. J. Hebdon, NRC, to O. D. Kingsley, TVA, dated 7 February 7, 1991 (A02 9107.11 001). Memorandum from Suzanne Black, NRC, to 0. D. Kingsley, TVA, dated April 19, 1990 (A02 900426 035). l1 t k. = L, 9 (VA #M44 (NP191) 1406C/COC3

..m. .m....... ~.... _._. _ Sundard Sheet 3^' SI-ll4.2,' Attachment 3 SURVEILLANCE Rsvision 0 INSTRUCTION . REQUESTS FOR RELIEF Page 11 of 42 .,.~ e< REQUEST FOR RELIEF ISI-5 -Component: Reactor Pressure Vessel gings: ASME Code Class 1 (Equivalect) y. ]' Inspection Recuirement: ASME Section 22, Table'IWB-2500-1, examination category B-A, item No. Bl.20, 100-percent preservice - baseline volumetric examination of Icwer head dollar j-weld, under conditions and'with equipment and .). techniques equivalent to those expected to be employed during inservice inspection. - y< - -j3 Basis for Relief: TVA will employ automated remote inspection devices to examine most of the reactor vessel welds. These examinations will be conducted from the vessel inside diameter. However, the lower head weld on each reactor pressure vessel is partially inaccessible for examination from the vessel inside diameter due to -4 instrumentation tubes which penetrate the lower head jj (wold No. WOl-02). Portions of the weld can be examined from one side (as permitted by T-441.3.2.4, Art'cle 4 of Section 33) and will include 100 percent i of the examination volume in accordance with Table IWB-2500-1 and June IWB-2500-3 of Section XI. These -I. portions of the veld will be reexamined during the inservice intervals in accordance with the LL_ examination category B-A of Table INB-2500-1. Alternate Inspectio.n A 100-percent baseline examination of the weld will be conducted from the vessel outside diameter. This will be accomplished by performance of a manual ultrasonic examination. A remote ultrasonic .h examination will be conducted from the vessel inside i ~l diameter on all accessible areas of the weld. Safety Evaluatica Summary j Request for Relief ISI-5 has been approved with no additional augmented requirements except to. notify NRC of the percentage examined. References Memorandum from F. J. Hebdon, NRC, to O. D. Kingsley, TVA, dated February 7, 1991 (A02 910211 001). Memorandum from Suzanne Black, NRC, to O. D. Kings 19y, TVA, dated + April 19, 1990 (A02 900426 005). d ]Tva4mmaprz9: 3 i 1406C/COC3 a:

Seehrd Sheei SI-ll4.2, Attachmant 3 SURVEILLANCE Rsvision O INSTRUCTION REQUESTS FOR RELIEF Page 12 of 42 REOUEST FOR RELIEF ISI-6 Component Steam Generator (four per unit) Class: ASME Code Class 1 (Equivalent) Inspection Requirement: ASME Section XI, Table IWB-2500-1, examination category B-D, item no. B3.140, volumetric exardnation of nozzle inside radius section on the primary side. Basis for Relief Each steam generator consists of two integrally cast nozzles and two integrally cast manways. Relief from the inspection requiremeat above is based on EPRI f! report NP-4242, "Long-Term Inspection Requirements for Nuclear Power Plants", dated March 1986. This report presents a linear fracture mechanics analysis which predicts that cracks of size.025 inch (which is greater than the allowable reference flow size) will propagate to only slightly greater than one sixteenth of the noszle wall thickness during the entire life of the plant. The report proposes that ~ ' ' the nozzle inner radius be examined at least at half the plant life, and subsequently, at the regular code j inspection intervals. The primary chamber radistion exposure dose rate is generally on the order of 30 rem /hr. As a result, individual " stay-time in the chamber would be limited to a degree where meaningful results from alternative surface and visua; examinations could not be achieved. In addition, the presence of the interior surface austenitic stainless-steel cladding which has a higher ductility than the base ASME-SA-216 grade WCC casting material raises the possibility of under cladding cracking which would not be visible with a surface examination. Alternate Inspection: TVA will initiate examination of the steam generator nozzle inner radius sections in accordance with the applicable Section XI Code during the second e inspection interval. This will provide for examinat.on of all the steam generator nozzle inner radii by the period ending at half the plant life. j-M' a ^ 4 + W (Continued) ~ .) ^ #"" ## 1'O 1406C/COC3

Sundard Sheet 3I-114.2, Attachment 3 -SURVEILLANCE Revision 0 INSTRUCTION-REQUESTS FOR RELIEF Page 13'of 42 ~. REOUTST FOR RELIEF ISI-6 (Continued) Hafety Evaluation Summary - Request for-Relief ISI-6 has been approved in the-following manner - (a): Delaying'the volumetric examination of the nozzles sections until the third inspection period of the first inspection interval and then + following.the code requirements is acceptable. 1 Reference Memorandum from F. J. Hebdon, NRC, to 0. D. Kingsley, TVA, dated 1 - February.7, 1991 (AU2 910211 001). . W Memorandum from Suzanne Black, NRC, to 0. D. Kingsley, TVA, dated . April-19, 1990 (A02 900426 005). I w I t l - t 1 ,~L f ( L i 8 s 1 w E 5 i,

L i-I5A 40004 (NP 231) 1406C/COC3 r

l .w-e. --e=.-,.e w- =-e ,ym w-w e e + - yr Dmim!ry ce

• m

'-1v1-+'e-? + ~4 -y3%e w-w --..

._= SuoJard Sheet. SI-114.2, Attachmant 3 SURVEILLANCE Revision 0 INSTPrCTION -REQUESTS FOR RELIEF Page 14 of 42 e REOUEST FOR RELIEF ISI-7 Comoonent: Reactor Coolant Loop Piping Welds (2) Class: ASME Code Class 1 (Equivalent) Insoection Renuirement: ASME Section XI, IWB-2500-1, examination category B-J, item No. B9.10, volumetric examination of circumferential welds. Banis for Relief: Two circumferential shell welds in the reaccor coolant loop piping (RC-23S1 and -31S1, loops 3 and

4) are located inside the reactor vessel shield wall 1

I2 and are inaccessible for baseline and inservice examination (see attached drawings). Both welds have undergone shop'rediographic examinations. Since the baseline inspection serves as a reference to future inservice-inspections and both welds will be E t inaccessible for inserv3ce inspections, the shop radiographic examinations coupled with the Section III hydrostatic test will provide adequate proof of integrity or the system welds. Inservice system leakage and hydrostatic testing will prove i weld integrity during the life of the plant. Alternate Inspectign: None L Safety Evaluation Summary: -Request for Relief IEI-7 is not necessary at this time. Relief should not be requested until the fourth inspection interval'ISI Plan is made.

Reference:

Memorandum frr= ?. J. 'Sb/on, NRC, to 0. D. Kingsley, TVA, dated February 7, 1091 (Auz ?10211 001). Memorandum from Suzanne Black, !!2C, to 0. D. Kingsley, TVA, dated 'i April'19, 1990 (A02 90042f 0051 s i a t i u

• I l

l P L E 4 m pr2m) 1406C/COC3 c-a.c+, -,e.- r ww .e -= v 1

SusbrJ Sheet SI-114.2, Attachmsnt 3 SURVEILLANCE Revisioa O INSTRUCTION REQUESTS FOR RELIEF Page 15 of 42 1 .i REOd ST FOR RELIEF IMI-B SQN Unit 2 reactor coolant pump casings do not contain pump casing welds. Request for Relief ISI-8 is only applicable to Sequoyah Unit 1. Cpmoonent: Reactor coolant pumps (four per unit) 1 ClA11: ASME Code Class 1 (Equivalent) Inspection Re rirement: ASME Section XI, IWB-2500-1, examination category f B-L-1, item No. B12.10, volumetric examination of pressure-retaining welds in pump casing. Basis for Relief: Each reactor coolant pump cesing consists of a two-piece welded type 304 SST casting. The present capability of ultrasonic testing is not sufficient to I examination cast material of this thickness and achieve meaningful results. Alternate Inspection: All four welds will be surface examined for the preservice baseline, and one weld will be surface examined during each inspection interval. f

Reference:

Memorandum from F. J. Rebdon, NRC, to 0. D. Kingsley, TVA, dated i-February 7, 1991 (A02 910211 001). i Memorandum from Suzanne Black, NRC, to 0. D. Kingsley, TVA, dated [ April 19, 1990 (A02 900426 033). t i 1 e J 1 I s 8 k 4NX)4 (NP 1'JI) j 1406C/COC3

hans shces SI-114.2, Attechment 3 SURVEILLANCE Revision 0 IFSTRUCTION REQUESTS FOR RFLIEF Page 16 of 42 2 BEOUEST FOR RELIEP ISI-9 Component: Uncladded vessel welds in ferritic material less than two inchou in thickness. ClAAan ASME Code Class 1 and 2 (Equivalent) Inspection Requirements Ultrasonic examination of welds, paragraph T-530 of ASME Section V, Article 5, 1977 Edition, Summer 1978 Addenda as referenced in paragraph IWA-2232 (c) of ASME Section XI 19*,1 Edition Summer 1978 Addenda. Basis for Relief: Paragraph T-533.2(a) of Article 5 of ASME Gection V g4 requ.res that the basic calibration block include a basic calibration hole drilled parallel to the contact surface. However, paragraph T-533.2(b) permits the use of other calibration reflectors provided equivalent responses to that from the basic calibration hole are demonstrated. TVA currently uses 5% notches in lieu of side drilled holes. Although the use of the 5% notch cannot be shown to be equivalent in all cases to the applicable 1 side-drilled holes, TVA considers that examinations are technically acceptable based on the calibration requirements of paragraph III-3430 of Appendix III to j the 1977 Edition, Summery 1978 Addenda of ASME Section XI. The calibration notches for ferritic material are 10%t when t J s less than.312" and .104t.009t2 for material.312"-6" thick. TVA's use of 5% notches is considered equivalent to the latest approved code examination techniques. l Alternate Inspection: TVA proposes to continue the use of notches located on the I.D. and 0.D. surfaces at a nominal depth of 5%t as reference reflectors. Safett Evaluation Summaty: Request for Relief ISI-9 has been approved with no additional augmented requirements. L R,eference: Memorandum from F. J. Hebdon, NRC, to O. D. Kingsley, TVA, dated February 7, 1991 (A02 910211 001). Memora'dum from Suzanne Black, NRC, to O. D. Kingsley, TVA, dated April 19, 1990 (A02 900426 005). I b v^ 40004 (Nr:m) 1406C/COC3 l

Suhdard S$ces SI-114.2, Attachment 3 __ SURVEILLANCE Revision 0- -INSTRUCTION REQUESTS FOR RELIEF Page 17 of 42 E REOUEST FOR RELIEF ISI-lg Components: Reactor vessel flange to upper shell

• eld

~ Class: ASME code Class 1 (Equivalent) t Inspection Eeouirkment: ASME Section XI, Table IWB-2500-1, examination category B-A, item No. Bl.30, volumetric from flange face ,. 5( Basis for Religi:1 The res.ctor vessel flangt-to-upper shell weld is located-behind the core berrel and is therefore i p inaccessible until the core barrel is removed. The vessel flange-to-upper shell weld is 41.9 inches below the flange face. Due to the location of - the vessel flange-to-upper shell weld, TVA intends to address the weld as a reactor vessel shell weld. e We have reviewed the Sequoyah Reactor Vessel Stress Esport entitled Analysis of-the Main Closure Including Core Support Ledge (Document ^[ No. 30616-1105) purposely to determine a fatigue , I, usage _ factor for the vessel' flange to shell weld. This analysis does not provide a usage factor specifically for the weld because the analysis considers veld and base material to be homogeneous and equal !.n elasticity, strength,-and fatigue []. properties. Instead, the analysis provides usage factors at critical locations. f The maximum fatigue usage factor in the vessel in the 3~ vacinity of the flange to shell weld as found in'the above analysis is 0.00662 and this value can be -j conservatively used for the weld. We consider the i valve of 0.00052 to be extremely low compared to the code allowed fatigue usage factor of 1.0. n. We conclude that the distance (41.9") from the flange face to the flange-to-upper shell weld coupled with present ultrasonic techniques and the very low fatigue usage factor that the flange-to-upper shell weld s'aould be treated as a reactor vessel shell weld. ~Afternake Insocction: A remoto ultrasonic examination of the weld will be j] conducted from the vessel inside diameter near the end of the inspection interval. (Continued) ,JA M4 (NP 2,90 ~ 1406C/COC3

- SueJard Stect SI-114.2, Attachment 3 SURVEILLANCE Revision 0 INSTRUCTION REQUESTS FOR RELIEF Page 18 of 42 REOUEST FOR RELIEF ISI-10 (Continued) Safety Evaluatipn Summary: Request for Relief ISI-10 has'ceen approved with no additional augmented requirements.

Reference:

Memorandum from F. J. Hebdon, NRC, to 0. D. Kingsley, TVA, dated february 7, 1991 (A02 910211 001). Mcmorandum from Suzanne Black, NRC, to O. D. Kingsley, TVA, dated Jpril 19, 1990 (A02 900426 005). I i f' J 3J 1 l-J n suas me 2m, 1406C/COC3

StsadasJ Sheet SI-114.2, Attachmant 3 O ~ SURVEILLANCE Revision 0 INSTRUCTION . REQUESTS FOR RELIEF Page 19 of 42-- y EEOUEST FOR RELIEF ISI.11, (Withdrawn) i. - f E pi s. t k .)'.i. 1 l T ~ VA.40004 (NP 2.91) 1406C/COC3

Nasaard Mecn SI-114.2, Attachment 3 SURVEILLANCE Revision 0 INSTRUCTION REQUESTS FOR RELIEF Page 20 of 42 REOUEST FOR RELIEF ISI-12 This Request For Relief was not needed. See NRC Safety Evaluation Report dated February 7, 1991 (A02 910211 001). Components: 1. Lacess Letdown Heat Exchanger - Chemical and Volume Control System (CVCS) 2. Regenerative Hcat Exchanger - CVCS Class: ASME Oude Class (Equivalent) 'j' Inspection Requirement: ASME Section XI, Table IWC-2500-1, Examination p Category C A, item Nos. C1.10, C1.20, and C1.30, volumetric examination of essentially 100 percent of each circumferential weld at gross structural discuntinuities (head-to-shell and tubesh,et-to shell weld) and categories C-C and C-E, Item No. C 3.10, surface examination and visual examinae'sn of integrally welded support attachmente. Basis for Rtiief: The excess letdown heat exchanger (ELHX) and the ragenerative heat exchanger (REX) were scheduled for il examination during the first inspection period in accordance with the In-service Inspection (ISI) Programs SI-114.1 and SI-114.2. The ELEX circumferential head weld was scheduled for ~ ultrasonic (UT) examination in the first three-year inspection period. For the RHX there are six circumferential tubesheet-to-shell welds. Of these, two each of the circumferential head welds and tube sheet-to-shell welds were to be examined in the first period by UT 1978 Addenda, Table IWC-2500-1 Examination Category C-A requires a volumetric t, examination of 100 percent of the required welds. i'j The ELEX weld was examined ultrasonically from one side for almost the entire length, except where the head's flanged nozzle-inlet and outlet welds ] interfered with the examination (see attached . ) drawing). This allowed for an DT examination of 90 percent of the weld from the one side. From the opposite side, the head taper and head closure studs and nuts severely restricted access to the weld area and as a result no meaningful results could be obtained. The UT was performed on a best-effort ,] basis aad supplemented with a 11guld-penetrant test (PT) over 100 percent of the eeld area. (Cratinued) 'A 40004 gNP 2.91) 1406C/COC3

m m_. 1 susera sket : l SI-ll4.2, Attachmant 3 I SURVEILLANCE Revision 0 INSTRUCTION . REQUESTS FOR RELIEF Page 21 of 42 r~ t' REOUEST FOR RELIEF ISI-12 (Continued) 4 In the case of the RHX when examinations were performed, the state-of the-art UT examination - capabilities did not allow the achievement of Ip meaningful results because of the component fabrication processes involved. The RHX is a centrifugally cast stainless steel, SA-351, CF8 vessel. In addition, the examinations were hindered by supports which were essentially nonremovable from the area of two of the four welds . ht because of the location in the heat exchanger room and-their position on'the vessel (see attached drawings). As a result, a PT was performed 'in place of the required UT. On the two restricted welds examined, only 75 percent of the weld lengths were surf ace examined because of supports coverir,g part of the weld areas. ' t" Ir accordance with 10 CFR 50.2(v) of the Code of Federal Regulations, the REX and the ELHX are defined [ d. to be within the reactor coolant pressure boundary (RCF3) (ASME Class 1)- Secondly, 10 CFR 50.55.2(c) further states: "(2) Components which are connected to the reactor coolant system and are part of the g reactor coolant p essure boundary defined in 50.2(v) need not meet LLose requirenents (Class I c) requirements), providedt (11) The component la or can be isolated from the reactor coolant system by two valves (both closed, both open, or one closed and the other open). Each open valve must be capable of j automatic actuation and, assuming the other valve is L open, its closure time must be such that, in the event of postulated failure of the component during normal reactor operation, each valve remains operable 3 and the reactor can be shutdown and cooled down in an orderly manner, assuming makeup is provided by the reactor coolant makeup system only." As a result of ~ I_ #f this paragraph, the RHK, ELEX, and the connecting

f bt piping to the Reactor Coolant System (RCS) and piping out to the containment isolation valves would be exempt from ASME Class 1 examination requirements.

j-p.' j. L a-4 (Continued) 'I ]IVA 40004 (NP 2,98) 1406C/COC3 .--~ -. -..

m.. _.m.. m... m_, Stradard Sheet SI-114.2,' Attachment 3 SURVEILLANCE Revision 0 TINSTR9CTION' REQUESTS FOR RELIEF Page 22 of 42 -u ~ REOUEST FOR RELIEF ISI-12 (Continued) Sequoyah Nuclear. Plant units 1 and 2 ISI programs, SI-114.1 and SI-314.2, classify components for examination in accordance with Regulatory Guide 1.26i r,; j Revision 3. The guidelines of Regulatory Guide 1.26, +

4 paragraph C.1, classify components which are exempted

.by 10 CFR 50.55A(c) (2)11 from ASME Class 1 .ffa examination requirements (such as the REX, ELHX,'and -} associated piping) as ASME Class 2 equivalent. The Sequoyah Final Safety Analysis Report' (FSAR), Section 9.3.4.1.7, further describes the REX, ELHX, and associated piping as "not rtquired to

• unction during a loss-of-coolant accident."

{

Additional system design considerations are tha ' t? following: 3;f -1. The ELHX is not used during normal plant I operations and is isolated from the RCS by three valves, two normally closed gate valves and a check valve. i 2. The RHX is isolated from the RCS by two check - valves. - Leakage from the RCS is prevented by the [ two check valves in series which were leak-tested ,q-during the preoperational test program. Leakage also can be detected by monitoring for signs of f. system incoming leakage and by monitoring the RCS i for signs of outgoing leakage (FSAR 6.3-26). . [- 3. .There are no leakage problems into the CVCS from -I , h. {/. the RCS because of the higher pressure at which. ? the CVCS is generally maintained (FSAR'6.'3-27). p; In addition, the inlot and outlet piping (one inlet i and one outlet) associated with the ELHX is 1-inch t a 7 nominal pipe size (NPS) and 3-inch NPS for the REX. I Both of these are less than the-4-inch NPS which, in ) accordance with IWC-1220(c), is exempt frc:n the examination requirements in Table INC-2500.-i (Class

2) of ASME Section 23.

Also note that the Winter b ]; 1980 Addenda, paragraph INB-1220(b) (2) exempts from .j i examination components and their connections in [: - piping of 1-inch nominal pipe size and smaller. (Having ona inlet and one outlet pipe, each 1-NPS or 3 j. smaller). q (Loneinued) A mos p 2m) 1406C/COC3 =

~= Staadstd Sheet - SI-114.1, Attachment 3 .5URVEILLANCE R3 vision 0 INSTRUCTION. REQUESTS FOR RELIEF Page 23 of 42 REQUEST FOR RELIEP ISI-12 (Continued) 4 TVA also feels that the ALARA considerations to perform the liquid penetrant (PT) examinations on the ELHX and REX are excessive for the benefits received from the inspections..The actual radiation exposures to perform the first inspection period examinations alone were 2,200 NREM and 6,600 MREM respectively. I t Note that, in addition to the requirements in Examination Category C-A, Table IWC-2500-1, Examination Category C-H requires that all pressure retaining components be pressure tested in accordance with IWC-5000. This results in a system pressure test conducted each 10-year interval during a system functional test for the ELHX and a systea hydrostatic test performed Lach inspection interval for the REX. Based on the component classifications as defined in 10.CFR 50.55, the nonsafety related function as ~ stated in Sequoyah FSAR, the design of the heat exchangers and their supports preventing 100-perewnt examination coverage, and the ALARA considerations in view of the small benefit realized, TVA requests relief from the ASME Section XI examination g requirements as shown in Table IWC-2500-1, Fvamination Category C-A, C-C, and C-E. [' . Alternate Inspection: None. _g.- o. f i v-I 1 g p m,, 1406C/COC3 l

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• O' FLANGES.

SA 182 F:316. .v. /_SEE DETAIL A ~ '.L \\ fa 8 k, ^~ ELHX-1 3 m w E .750"- E.- Q[/j-I' 9-16-&, CDRKEAT FOR FQSIA44t MMA inilt Ql{ ~ HO. DATE-agvisions cx'o see. un { . TENNESSEE VALLEY AUTHORITY w 3 9,2i. 0,0. ....,SEOUOYAH. NUCLEAR PLANT ll? E' l'! g UNITS #I 8 #2 i $ $. L.

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Saashrd Snect SI-ll4.2, Attachmant 3' SURVEILLANCE Revision O INSTRUCTION REQUESTS FOR RELIEF Page 28 of 42 [f .REOUEST FOR RELIEF ISI:11 14 Cgmponents: Residual Hest Removal Heat Exchanger (two per unit) i Class: ASME Code Class'2 (Equivalent) Insoection Recuirements.ASME Section XI, Table IWC-2500-1, examination category C-B, item no. C2.20, nozzles in vessels with .over 1/2 inch in nominal wall thickness; surface and volumetric examination. ^ Basis for Relief 'Each heat exchanger consists of an inlet-outlet head __ g chambor with one inlet and one outlet nozzle and two integrally attached support brackets. Volumetric examination of the nozzle-to-vessel welds and the nozzle inner radil is inhibited by the {.- shell-to-tubesheet weld, shell-to-head weld, and the {- integral supports as shown in the attached sketches. Proximity of the welds and inner radius sections do not allow for the achievement of meaning results from a volumetric examination. Alternate Examination: The nozzle-to-vessel welds will be examined utilizing a surface examination only. Safety Evaluation Summary:

I

-[ Request for Relief ISI-13 has been approved with no additional augmented requirements. I

Reference:

Memorandum from F. J. Hebdon, NRC, to 0. D. Kingsley, TVA, dated s . February 7, 1991 (A02.910211 001). 7 Memorandum from Suzanne Black, NRC, to 0. D. Kingsley, TVA, dated April 19, 1990 (A02 900426_005). c I- [I 1 'ii. Yl ' ) ' e 't 5-j. _) ^ ) 1406C/COC31 )

/ ..p s it v %s e ' Q, ot 4., % 4,'. 9-IMAGE EVALUATION ,4 S, - \\//o// (*'[ tigf/* </ f)? diGft[* 4 TEST TARGET (MT-3) ll J' q g p,,Y Qlk ' l.0 Ea R

1. 32, 12.2 L

i s== y l,l liF=- v.8 mi== ' l.25 I l.4 q!!i1.6 1 4 150mm 4 6"

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y e>9)e< (0 e %a# i [' g / / 'fif ' ( g g y g. R %'t / O / Q, ot IMAGE EVALU ATION y TEST TARGET (MT-3) g$ Q kh I.0 t M e31 h AI E u l' W Tli 1.8 li!!I-1.25 l' l.4 lt 1.6 1 _1=. i 4 150mm 4 6" t 4E*4< / 4% / ,'/ /y v,g v ,e,g;p~f / QN f4j;f;;, f\\ ' ~ ~~ ~ ~ ~ - i o\\N qe v y/ ( mp ,,; x,:.

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w 0 e Y j NOTES FOR VESSEL WILL BE ESTABLISHED W ASME CO2 (EOUHALENW AT t INLET NOZZLE. PORTION Or WELO

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NOTE: FOR UNIT I OWG SEE g

1. 2 (37" TO 75")
2. 3 (75" TO II3"):

CHM-2404-A (IN A CL'OCKWISE DIRECTION) c~ Q* 3h zo INLET INLET - ' RHRW-l6-Y-Z. RHRW-I 9-Y-IA \\- RHRW-l8-Y-IA RHRW-l4-Y 0 0

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. FasJ5sd Na SI-114.2, Attachment 3 SURVEILLANCE Revision 0 INSTRUCTION REQUESTS FOR RELIEF Page 30 of 42 ro* i TLR)C5fE[T r W OW'06 an.. / //// '/// /////// / ///// / 28 3/d * \\\\ ' (( \\ S 25/16* /l-

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' Sundard Shres SI-li4.2, Attachmant 3 SURVEILLANCE Revision 0 INSTRUCTION REQUESTS FOR RELIEF Page 31 of 42 Eggqest for Relief ISI-14 i Componegtal Various (see Appendix A, tables A and B of this instruction) Class: ASME Code Class 1 & 2 (equivalent). Insoection Recuirement: Tables IWB-2412-1 and IWC-2412-1 of ASME Section XI require that for the first inspection interval the percentages of examinations completed shall be as follows 1) first inspection period (after 3 years) a minimum of 16% and a maximum of 34%, 2) second inspection period (at 7 years) a minimum of 50% and maximum of 67% and 3) third inspection period (at 10 years) a minimum of 100% and a maximum of 100%. Basis for Relief The NRC is requiring TVA to implement an augmented and accelerated field weld program, requested by i NRC's letter dated November 14, 1986 " Draft Safety Evaluation on Helding for Sequoyah Units 1 & ?". TVA ~ will not be able to maintain the required percentages on certain systems, categories and item numbers during the second and third periods. This is documented on TVA"a response to Mr. B. J. Youngblood on January 30, 1987 (L44 870130 804). TVA stated on j part 4 of response to item 3 that TVA would try to 3 maintain the required percentages as required by ASME Code, and if it was not possible TVA would submit a Request for Relief (RFR). In order to comply with the requirements of the NRC's augmented and accelerated field weld program TVA L! Requests relief from the Code percentages requirements, j [ Alternate Insoections: The percentages required by the code will not be met l i on the second and third period of the first inspection interval.- In some cases SON U-2 will have zero (0) exams during the third period with 100% of l the examinations completed by the second per!od (see ip Appendix A, Tables A and B of this instruction). SON 1 U-2 will revert to the code required percentages and ) schedule during the second inspection interval. J The code required percentages will not be on examination categories B-J, B-K-1, B-K-2, C-C and C-E (refer to Appendix A tables A and B). 13 (Continued) d j A 40004 (NP 2SI) 1406C/COC3

SuoJard Sheet SI-114.2, Attachment 3 SURVEILLANCE Revision 0 INSTRUCTION REQUESTS FOR RELIEF Page 32 of 42 Request for Relief ISI-14 (Continued) Safety Evaluation Sumtnary: kequest for Relief ISI-14 has been approved with no additional augmented requirements. Referencer Memorandum from F. J. Hebdon, NRC, to 0. D. Kingsley, TVA, dated i February 7, 1991 (A02 910211 001). Memorandum from Suzanne Black, NRC, to 0. D. Kingsley, TVA, dated April 19, 1990 (A02 900426 005). l b y I i. I 1 't j l w i l i 4 l e l [ i I i J l l I VA 40004 (NP 2/91) l 1406C/COC3 i

-. ~... -~. - _ _ -... Stat &rd Sheet SI-114.2, Attachment 3 SURVEILLANCE Revision O INSTRUCTION REQUESTS FOR RELIEF Page 33 of 42

7" REOUEST FOR RELIEF ISI-15 Components Reactor Vessel (RV) Outlet Nozzle-to-Vessel Wolds, RV i

Nozzle Inside Radius Section, and RV Nozzle-to-Safe End Welds Class: American Society of Mechanical Engineers (ASME) Code i Class 1 I j Inspection Requirement: Table IWB-2500-1 Examination Category B-D, Full Penetration Welds of Nozzles in Vessols - Inspection Program B ? Item No. B3.90 Nozzle-to-Vessel Helds Item No. B3.100 Nozzle Inside Radius Section Footnote 3 (1st Inspection Interval) - "At least 25 percent but not more than 50 percent (credited) of the nozzles shall be examined by the end of 1st inspection period and remainder by L? the end of inspection interval." f Footnote 4 (Successive Inspection Intervals 2nd, 3rd, and 4th) "At least 25 percent but not more than 50 percent (credited) of the nozzles shall be examined by the end of 1st inspection period and the remainder by the end of 3rd inspection period of each inspection interval." f Footngit_1 (Deferral of Inspection to End of Interval) - "If examinations are conducted from inside the component and the nozzle weld is examined by straight beam ultrasonic method from the nozzle bore the remaining examinations required to be conducted from the shell inside diameter may be performed at or near the end of each inspection interval." Examination Category B-F, Pressure Retaining ] Dissimilar Metal Welds J Item No. B5.10 Nozzle-to-Safe End Welds e + Footnote 2 (Successive Inspection Intervals 2nd, 3rd, 4th) "For the reactor vessel nozzle safo-ends, the examinations may be performed l .3 coincident with the vessel nozzle examinations required by Examination Category B-D." l (Continued) ~ 1 l l r /A 4Mo4 (NP191) 1406C/COC3 l

't SODJarJ Mcct sI-114.2, Attachment 3 SURUEZLLANCE <evision 0 INSTRUCTION REQUESTS FOR RELIEF ' age 34 of 42 REOUEST FOR RELIEF ISI-15 (Continued) Basis for Reli 1: Sequoyah Nuclear Plant (SON) is a four-loop t pressurized water reactor with four inlet and four outlet RV nozzles. The RV nozzle-to-vessel welds and inside radius sections are ultrasonically examined {,. from the RV inside diameter using automated Inspection devices. With the RV core barrel in place, the outlet nozzles are accessible for examination from the nozzle bore only. The inlet nozzles are inaccessible for examination until the core barrel is removed. I

i..

SQN is in the second period of the first ten-year inspection interval. During the first period, the accessible volumes of the nozzle-to-vessel welds and insido radius sections on SQN's fouc outlet nozzles were ultrasonically examined from the nozzle bore. The remaining examinations for the four inlet and four outlet nozzles are to be completed during the third period, thus satisfying the requirements of Table IRB-2500-1, Examination Category B-D, Item Nos. B3.90 and B3.100, Footnotes 3, 4, and 5. In addition to the RV nozzle examinations, the RV 6 nozzle-to-safe end welds are ultrasonically examined using an automated inspection device when the nozzle i is examined from the bore. During the first period, the nozzle-to-safe end welds on four outlet nozzles g were ultrasonically examined from the inside diameter and surface examined from the outside diameter. The nozzle-to-safe end welds on the four inlet nozzles will be similarly examined during the third { inspection period. This will satisfy the t requirements of Table IWB-2500-1, Examination Category B-F, Item No. B5.10, Footnote 2. The ASME Code provides for the continuation of the first and third period examinations during the second, third, and fourth inspection intervals, thus establishing a ten-year examination frequency. TVA proposes to alter the inspection schedule by performing an additional examination of the RV ~ i, nozzle-to-vessel welds and inside radius sections for SQN's four outlet nozzles during the third inspection l period of the fi.rst inspection interval. In addition, the razzle-to-safe end welds for the outlet nozzles would also be examined during the third inspectior period of the first interval. Pe rfo rmance of these additional examinations will thereby establish a new ten-year examination schedule for the l.m. secon4, third, and fourth inspection intervals. The (Continued) MVA 4xc4 ge zso 1406C/COC3 l

Standard Sheet SI-114.2, Attachment 3 SURVEILLANCE Revision 0 INSTRUCTION REQUESTS FOR RELIEF Page 35 of 42 l i ) REQUEST FOR RELIEF ISI-15 i 1 (Continued) Basis for Reliefs ten-year examination frequercy required by the code (Centinued) would continue to be maintaiaed. Additional benefits include: One-time installation and removal of the automated inspection device from the RV flange rather than twice during and inspection 3 serval. Performance of additional RV outlet nozzle examinations during the first inspection interval, Performance of additional RV outlet nozzle-to-safe end weld examinations during first inspection interval. An overall reduction in personnel radiation exposure (one automated examination versus two), I thus supporting as low as reasonably achievable considerations. A reduction in the number of times automated devices and associated materials and equipment must be decontaminated (reduces generation of radwaste). A cost saving to TVA of 1.8 million dollars over the 40-year life of the plant. t In consideration of TVA's performance of additional examinations during the first interval f-k and the radiation exposure required to perform inspections under the current Section XI examination schedule (second, third, and fourth q intervals), it is concluded that compliance with p" the specified requirements would result in an unnecessary hardship without a compensating increase in the level of quality and safety. Alternate Insoection: SON's four RV outlet nozzles will be ultrasonically examined twice during the first inspection interval. The second examination would occur during the third j period. This includes examination of the outlet nozzle-to-vessel welds by the straight beam ultrasonic method from the nezzle bore and examination of the outlet nozzle inner radius secticas. These examinations will be in addition-to the examinations required to be conducted on the !j (Continued) fA 4mm4 O& 2ss) 1406C/COC3 u

SushrJ Sket 51-114.2, Attachm2nt 3 SURVEILLANCE Revision 0 INSTRUCTION REQUESTS FOR RELIEF Page 36 of 42 v. REQUEST FOR RELIEF ISI-15 (Continued) Alternate Inspection: outlet nozzle-to-vessel welds and inner radius (Continued) section f rom the RV shell inside diameter during the third inspection period. SON's four RV outlet nozzle-to-safe end welds will also be examined twice during the first inspection interval (third period). The examinations will include an automated ultrasonic examination from the inside diameter and a surface examination from the outside diameter. During the second, third, and fourth inspection intervals, all RV nozzle-to-vessel welds and inside radius sections and RV nozzle-to-safe end welds will be examined during the third inspection period. ELD 1ua '~ Lequest for Relief ISI-15 was submitted to the NRC on August 21, 1991, with a request for a response by June 1, 1992.

Reference:

Memorandum from J. L. Wilson, TVA, to the NRC, dated August 21, 1991 (S10 910821 848), r I r i m { t L = c. W b u]v4 4m*4 WP 2so 1406C/COC3

Sui &rd Sheet AI-114.2, Attachmant 3 SURVEILLANCE Rsvision 0 INST'RUCTION REQUESTS FOR RELIEF Page 37 of 42 Recuest for Relief ISI-16 Components: Residual Heat Removal Heat Exchanger (two per unit) Class: ASMI Code Class 2 (Equivalent) Irsoection Requirement: ASMI Section II, Table IWC-/500-1, Examination Category C-A, Item No. C1.10 volumetric examination of circumferential shell welds. Basis for Relief Each heat exchanger consists of an inlet-outlet head chamber with one inlet and one outlet nozzle, two integrally attached support brackets and a circumferential vessel shell-to-flange weld. The design configuration of the nozzles and support brackets restricts examination of the vessel-to-flange weld (see attached drawing). The vessel shell weld is 113 inches in length. The weld examinations distributed in three segments, identified ast are rJRW-16-A-1, 37 in.: RHRW-16-A-2, 38 ir..; and RHRW-16-A-3, 38 in. RHRW-16-A ' was ultrasonically examined in the first inspection period and achieved approximately 81% examination volume coverage. RRRW-16-A-2 was examined in the second period and achieved approximataly 64% examination volume t coverage. RHRW-16-A-3 is scheduled for examination i during the third period with an estimated examination 4 volume coverage of 82%. Based on the examinations 4 performed and an estimation of the remaining third period examination, apprcximately 75% examination i volume coverage of the RER heat exchanger circumferential weld will be achieved. j Alternate Insoection: In addition to the visual examination performed ( during system leakage and hydrostatic pressure tests, TVA will perform a "best effort" ultrasonic examination on one vessel-to-flange weld on one heat exchanger * - 9hieve as much code coverage as possible aa ,ca' eve meaningful results, Etatus: Request for Relief ISI-16 submitted to the NRC as a J part of Revision 16 of this program. = d i [^ '"*' *P 1' O 1406C/COC3

Sundr+J Sheet ' l' SI-114.2, Attachment 3 -SURVEILLANCE Revision O INSTRUCTIO3 REQUESTS FOR RELIEF Page 38 of 42 s a, _ so' 2 m. 7 2 S E i x w Y a ta T w w 6-m ~ 1 A,N 7 d l k ^ ,hg o a s a o'e D b = w x n Q x "9 x do .a O Z q NA J

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mu . - ~. ~ - - -. - ,!j : -Staedud Sheet - SI-114.2, Attachment 3 SURVEILLANCE Revision 0 INSTRUCTION. REQUESTS FOR. RELIEF Page 39 of 42 f REOUEST FOR RELIEF ISI-17 -l comoonentst Integrally Helded Support Attachments Classt ASHI Codc Class 2 (Equivalent) c -Inspection Requirement

• ASME Section XI, Table IWC-2500-1, Examination Category C-C, Item No. C3.40, piping integrally welded support attachments, surface examination.

l Basis for Relief: Due to the design vintage of Sequoyah Nuclear Plant it will be impractical to inspect all of the i integrally welded attachments of-certain component 97 supports. The integrally welded support attachments may have access limitations as well as nonremovable hanger (pipe clamp) interference. These limitations will be noted on the attached listing of this relief request. Alternate Inspectign: TVA will perform a best-effort surf ace examination. In addition, the supports shall receive a visual examination as practical. Erntust Request for Relief ISI-17 submitted to the NRC as a part of Revision 16 of this program. l-4 4 l t l-i l l-a I i 3- [f v^ **** ("r 2'o 140cceCoC3

Sunbro Sbect SI-114.2, Attachment 3 SURVEILLANCE Revision 0 INSTRUCTION REQUESTS FOR RELIEF Page 40 of 42 REQUEST FOR RELIEF ISI-17 ATTACHMENT A Component Exam Drawing Code System ID Cat. No. Coverace Limitations Fcedwater 2-FDH-245-IA C-C MSG-0016-C 54% A>:cesa limited due to feedwater piping penetration in valve room. Limitation on i lutegrally welded lugs due to nonremovable pipe clamp and restraint and pipe penetration. Feedwater 2-FDH-2 8 4 -I A C-C MSG-0016-C 71% Access limited due to feedwater piping penetration in i containment. Limitation on integrally welded attachment due to i permanent support attachment at the piping penetration. Safety 2-SIH-10-IA C-C MSG-0009-C C% Totally Injection inaccessible. Integral attachment i 'l installed in a wall , l in fan room. Process pipe goes through AC duct which is 4 to 5 l inches from wall making integral l attachment i inaccessible for surface examination. 3 e [A4Mm4WP2S4 1406C/COC3

StandarJ Sheet SI-114.2, Attcchmant 3 SURVEILLANCE Revision 0 INSTRUCTION REQUESTS FOR RELIEF Page 41 of 42 Request for Relief ISI-18 Components: Reactor Pressure Vassel Closure Head-to-Flange Wald Classt ASME Code Class 1 (Equivalent) l Inspection Requiremgnt ASME Section XI, Table IWB-2500-1, Examination Category B-A, It2m No. Bl.40, Volumetric Examination [ Basis for Relieft The Reactor Pressure Vessel (RPV) closure head-to-flange weld WOB-09, is 45 feet in length. The weld examinations are distributed in three segments of 15 feet lengths each inspection period. The weld segments are identified as WO8-09A s (0" - 180"),'W08-09B (180" - 360") and WO8-09C (360" - 540"). Due to the design configuration of the closure head, no examinations may be performed from the flange side. Limited examinations from tha head side are due to the head lifting lugs located at O*, 120', and 240' (see attached drawing). WOB-09A was ultrasonically examined in the first inspection perloo and achieved approximately 40% examination volume coverage. HOB-09B was examined in the second inspection period and achieved approximately 40% examination volume coverage. WO8-09C is scheduled for examination during the third period with an estimated examination volume coverage of 40%. It should be noted that approximately 100% of the " weld" i volume was examined from the OD surface f rom the closure head side. However, the required 1/2T base metal area was not completely examined on the flange side. Due to the limited scanning area, TVA will be able to achieve approximately 40% examination coverage of the RPV closure head-to-flange weld. Alternate Examination 1 In addition to the visual examination performed during system leakage and hydrostatic pressure tests, TVA will perform a best-effort ultrasonic examination to achieve as much code coverage as possible and achieve meaningful results. In addition, TVA will perform a 100% surface examination (MT) of all accessible areas of the closure head-to-flange weld ( flex area in the third inspection period. Etatus: Request for Relief ISI-18 shall be submitted to the NRC as a part of Revision 16 of this program. ,e M _j 1406C/COC3 1

.O } 2 E v I b ASME CC-l (EOUIVALENT) a I Eh NOTES: 0g /) FOR UNIT I DWG SEE CHM-2358-A 0 i

2) REFER TO DRAWINGS o

~ ~ ~ ISI-0008-B SH. I AND

• Q ISI-0304-B SH.I FOR O' LOCA TION

~ WO9-1OA (O "- l56 ") a -1OB (156"-324")

'N

-10C (324"-492") 'N WO8-09A (0 "- 180 ") 0 -098 (l80"~360") 9 -09C (360"-540") N , -- FLEX AREA g WOB-09A -FLEX N -G98-FLEX ~ h -09C-FLEX }g t 5 H 2 RPG II-24-91 ADDED FLEX IOCNTIf!ERS PytB JCis ?n i RPG 3-17-a 9 ADOEO PCTE 2 MA KEC CLB erv. av o^ te ccscasPTrDro ac*o ste. APP. TEMESSLE VALLEY AUTh09ITY ., u m Q SEGUOYAH NUCLEAR PLANT '8 ?- l-

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