ML20127P636
| ML20127P636 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/16/1992 |
| From: | Goulart J TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20127P527 | List: |
| References | |
| SI-114.2, NUDOCS 9302020025 | |
| Download: ML20127P636 (191) | |
Text
{{#Wiki_filter:.. 51-114.2
$URVIILLANCE ASME SECTION XI R:visin 19 INSTRUCTION INSERVICE INSPECTION PROGRAM P:g3 1 cf 101 RECEWED f JttN 11 199z TENNESSEE VALLEY AUTHORITY 4 141 NUCLEAR PLANT . JtEGULATORY LK'Eff9NG SURVEILLANCE INSTRUCTION SI-114.2 ASME SECTION XI INSERVICE INSPECTION PROGRAM UNIT 2 Revision 19 PREPARED /PR00 TREAD BY: Jefferv coulart DATE: 12- 2 'l2.
SIGNATURE: - db-[/ ' 6 A
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RESPONSIBLE ORGANIZATI 13 M Si-le/02falltv_Oreanization . APPROVED BY /d Md DATE: M ETTECTIVE DATE: / /4'1 REVISION DESCRIPTION: Revised sections 5.3, 5.8, and augmented section 20.0 for clarification of responsibilities. Corrected typo in Section 16.6. Revised Sectiens 7.1.2, 7.1.3, 7.1.4, and Attachment 4 on'the scheduling of the reactor vessel nozzle-to-vessel velds, nozzle inside radius sections, and nozzle to safe end welds. Revised organisation title ISI Programs to ASME Section XI Programs. Hoved Section 7.3.8 to Augmented Section 20.4. Revised Appendix A for editorial changes and transferred information to attachments 4, 5 and 6. Added Attachments 4, 5, and 5. Added References' 22.1.42, 22.1.43 and 22.1.44. Revised Sections 20.1 and 20.11 to add examination requirements by Nuclear Engineering. . Revised Appendiz D, Sections 6.1.1, 6.1.2, 6.1.4, 6.1.6, and 6.2.1. Revised Augmented-Section 20.0 per Memorandum', L29 920828 800. 9302020025 930128 1401C/COC3 PDR .ADDCK 05000327 0 PDR t
, 32-114.2 SURVEILLANCE ASME SECTION XI R:visica-19 INSTRUCTION INSERVICE INSPECTION PROGRAM Pcg3 2 of 101 i IABLE 07 COMTENTS EagR l' ?
Dwner Statement . . ...... ............. .... 4 0.1 Prerequisites . . . . . . . . . . . . . . . . . . . . . . . . . . 5 0.2 Precautions . . . .... .................... 5 1.0 Statement of Applicability .............. . .... 5 2.0 Purpose . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 3.0 Inspection Intervals and Inspection Periods . . . . . . . .... 6 4.0 Codes of Record and Code Cases ............. .-. . . 7 5.0 Method of Implementation and Responsibilities . . . . . . . . . . 8
- 6.0 Abbreviations and Defluitions . .......... . . . .... 17
. 7.0 Components Subject to Examination - ASNE Code Class 1 . . .... 18 8.0 Components Subject to Esamination - ASME Code Class 2 . . . . . .. 39 9.0 Components Subject to Examination - ASME Code Class 3 . . .... . 52 l 10.0 Authorised Inspector ...................... 57 11.0 Ermalnation Methods and Calibration Blocks . . . . . . . .... 57 12.0 Qualifications of Nondestructive Examination Personnel . .... . 58 13.0 Acceptance Criteria . . . . . . . . . . . . . . . . . . . - .... 58 14.0 Rephlrs and Replacements ............... . .... 58 15.0- Pump and valve Testing ................. .... 58 ; 16.0 Records and Reports . ................. . - .... 58-i 17.0 Notification of Indication ........ . . . . . . . ... . . 61 , 18.0 Corrective Action Program . ........ . . . . . . . . . . . .- '64 19.0 Requests for Relief . . . . . .............. . ... 64 20.0 Augmented Examinations. . . . . . . . . . . . . . . . . ... . . . 65 21.0 Interface Documents . . . . . . . . . . . . . . . . . . . . .. . 80-22.0 Developmental References ......... . . . . . .- . . ... 80 I 1401C/COC3 '
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SI-114.2
- SURVEILLANCE ASME SECTION XI R3 vision 19 INSTRUCTION INSERVICE INSPECTION PROGRAM P093.3 of 101 ,
ZABLE OF CQHIKEIS (Continued) EAge Ij APPENDICES Appendix A - Tables . . . . . . . . . .. . . . . . . . . . .. . . 84 Appendix B - Data Sheets . . . . . . . . . . . . . . . . ... . 80 $ Appendix C - Notification of Indication Form . . . . . . . . . . 87 Appendiz D - Guidelines for Determining Piping Component Support Examination Doundaries . . . . . . . . . . . 88 Appendix E - Tield Corrected Drawing Transmittal Form . .. ... 100 SOURCE HDTES . ... . .... . . . . . . . . . . . . . . . . . 101 ATTACIDENTS Rey _laigm Attachment 1 - Drawing List . . . . . . . . . . . . . . . . . . . 2 Attachment 2 - Valve Tables . . . . . . . . . . . . . . . . .-. . 1 Attachment 3 - Requests for Relief .. . . . . . .. . . . . .. 2 Attachment 4 - Component Tables . . . . . . . . . . . . . . . . . 0 Attachment 5 - Successive Examinations. . . . .. . . . . . . .. O Attachment 6 - Augmented Examinations . . . . . . . . . . . . . . 0 1401C/COC3-
81-114.2 l SURVEILLANCE ACME SECTION XI R visl@3 19 , INSTRUCT 20H INSERVICE INSPECTION PROGRAM Page 4 of 101 OWNER STATEMENT I v s owner: Tennessee Valley Authority , Address of Corporate Offices Chattanooga Office Compler 1101 Harket Street Chattanooga, Tennessee 37402-2801 Hame and Address of Huclear Power Plants Sequoyah Nuclear Plant P.O. Box 2000 Coddy Daisy, Tennessee 37379 - Appilcable Nuclear Power Units: Sequoyaa Nuclear Plant, Unit 2 Commercial Operation Date June 1, 1982 i P f 1401C/COC3 '
51-114.2 SURVEILLANCE ASME SECTION XI R0visics 19 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 5 of 101 0.1 22121091511ZS 5 0.1.1 When craft support of minor or similar maintenance (examples scaffolding, lasulation removal, buffing of welds using Scotchbrite 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 Nuclear Plant (SON) Standard Practice (SSP) 6.21 and the system code for 61-114.2 (system code 114.2) will be referenced on the WR. Additional WRs are required to remove fire barrler insulation foam in sleeves, piping support clamps, steam generator support rings, reactor coolant pump flywheel access covers and plugs, etc. 0.1.2 Contact Radiological Control (RC) for radiation work permit (RRP)/ALARA preplanning requirements. r 0.1.3 Controlled copies of American Society of Mechanical Engineers ' (ASME) Section XI Code Classification Drawings and ISI Drawings are issued through DCRM. 0.2 Ernsantiona 0.2.1 Safety belts should be worn when working from scaffolding or ladders in accordance with SSP-12.58. 0.2.2 Protective clothing, such as long-sleeve shirts or gloves, should be worn except in RWP areas when working around hot pipes and' equipment. 0.2.3 Caro 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 avolded. 0.2.4 Efforts should be made to ensure proper planning to reduce delays and radiation exposure in performance of the work. 0.2.5 Road and observe all applicable precautions as indicated in SQN Administrative-Instruction AI-8 " Access to Containment," and SSP 12.8 " Foreign Material Exclusion." 1.0 $TATDENT OF APPLICABILITY This program outlines requirements for performing the first 10-year interval inservice nondestructive examinations (NDEs) of the SON Unit 2, ASKE Code Class 1, 2, and 3 (equivalent) components (and.their supports) containing water, steam, or radioactive maturial (other than radioactive . " waste management systems). The program has been organized to fulfill inservice examination requirements of Standard (STD) 6.10 and comply as practical with the requirements of Section XI of the ASME Boiler and Pressure Vessel Code. In addition, this program implements applicable
. portions of the SON Technical' Specifications.: The Inservice Inspection 1401C/COC3
, 51-114,2 SURVE!LLANCE ASME SECTION XI R;visi!3 19 INSTRUCTION INSERVICE INSPECTION PROGRAM P g3 6 af 101 (ISI) Program satisfies the requirements of Surveillance Requirements 4.4.5.0 and 4.4.10 and partially satisfies the requirements
[ of Surveillance Requirement 4.0.5. Inspection frequencies are in accordance with Attachment 4 of this instruction and are generally scheduled to coincide with outage periods. The requirements of this program are applicable beginning at the date of coppercial operation of the unit. 2.0 EUREQS3 The ISI Program shall be used for planning inspections and examinations of SON ACME Class 1, 2, and 3 (equivalent) components for the first ISI interval. The examinations required by this program will establish acceptance of components for continued service. 3.0 1RSPECTION_ INTERVALS AND ,DISfICIIDF PERIQDS The inservice examinations required by ASME Sect ion XI shall be performed during each 10-year interval of service (inspection interval). The inspection intervals represent calendar years after the unit has been placed into commercial service. The commercial operation 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 be performed lu any mode and is applicable for all operational modes. The inspection interval shall be separated into three inspection periods. 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. Minimum Examinations Maximum Examinations 1 Direction Perloj Corpleted, Percent. _Comnleted. Percent _ 3 Years 16 34 7 Years 60 67 10 Years 100 100 The examinations dei' erred to the end of the inspection interval shall be completed by the end of the inspection interval. On August 21, 1985 SON Unit 2 vent off line and remained off line until 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 February 21, 1995. The period daration will be as follows: First period: June 1, 1982 through May 31, 1985 Second period June 1, 1985 through February 21, 1992 Third period February 22, 1992 through February 21, 1995 1401C/COC3 , um
$1-114.2' !
SURVEILLANCE ASME SECTION XI R;visica 19 INSTRUCTION INSERVICE INSPECTION PROGRAM Pcg3 7 of 101
- f 4.0 CQDXs or RECQED AND CODE.C&SES l
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;, Preservice examinations were conducted in accordance with the 1974 i t Edition, Summer 1975 Addenda, of ASME Section XI. 83-114 was the Preservice Inspection (PSI) Program for SON Units 1 and 2.
The SON Unit 2 operating license (Iow power) was lasued on , June 26, 1981. Thus, as a minimum the ISI Program shall not be prepared i to a Section XI Code Edition and Addends prior to the 1974 Edition, : Summer 1975 Addenda. l In accordance with 10 CrR Part $0.55a(g)(4)(iv), this program was { prepared to meet the requirements of the 1977 Edition, Summer 1978 Addenda, of Section XI of the ASME Boller and Pressure Vessel Code. . Steam Generator Tubing Examination requirements are in accordance with l Technical Specification and Surveillance Requirement 4.4.$ and a modification of Regulatory Guide 1.83, Revision 1. -In accordance with , 10 CFR Part 50.55a(b)(2),. the extent of examination for piping welds, Examination Categories B-J and C-T, is in accordance with the 1974 Edition, Summer 1975 Addenda of ASME, Section XI (Examination Categoriec ., B-J, C-r and C-G). Extent of examination is defined as criteria for tho' i* selection 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 l be examined. . See Section 19.0 and Attachment 3 of this program for request for relief ! information. NDE techniques, qualification of personnel, ws1d reference system, and standards for examination evaluation will be in accordance with the 1986 Edition of ASME Section XI. This will include all portions of IWA-1600, + IWA-2200, IWA-2300, IWA-2600, INA-3000, IWB-3000, IWC-3000, IWD-3000, and IWr-3000, as well as all portions of Appendices III, IV, and'VI of ASME ; Section XI. Certification of NDE personnel vill be in accordance with the 1984 Edition of ASNT SNT-TC-1A as approved by the Nuclear Regulatory Commission's (NRC's) letter from S. C. Black to 0. D. Kingsley, Jr., dated January 18, 1990 (TAC No. 72833). TVA 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 , procedures N-209, Conditional Acceptance of Identifiable Isolated or Random ~ Rounded Indications H-234, Time Between Ultrasonic Calibration' Checks N-235, Ultrasonic Calibration Checks pee Section V N-307-1, Revised Ultrasonic volume for Class 1 Bolting, Table . ; 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 t
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4 51-114.2 SURVE!LLANCE ASME SECTION XI R3visica 19 INSTRUCTION INSERVICE INSPECTION PR3 GRAM PCg3 8 01-19-10l 33 leltd9L 2 N-401-1, Eddy Current Examination { N-402, Eddy Current Calibration Standard Material H-416, Alternative Rules for Hydrostatic Testing of Repair or Replacement of Class 2 Piping N-426, Extent of VT-1 Examinations, Category B-0-2 of Table IWB-2500-1. H-435-1, Alternative Examination Requirements for Vessels with Hall Thickness 2 Inches or Less N-461, Alternative Rules for Piping Calibration Block Thickness Code Cases N-341, certification of Level !!! NDE Examiner, and N-356, ' Certification Period for Level III NDE Personnel, were authorized for TVA use by HRC by memorandum from Gary L. Zech to S. A. White, dated ' January 25, 1988. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds, was authorized for TVA use by NRC by memorandum from Susanne C. Diack to 0. D. Kingsley, Jr., dated December 13, 1989. TVA will utilise Regulatory Gulds 1.150, Rev. 1, " Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations," for its examinations as outlined in the applicable NDE procedure. 5.0 BEIllDD OF IMPLEMEMIATION AND_RESEQRSIBII,lIJES Any-_ revisions to th1LPLDSIAm _ initiated by other glogg _ghall bg Suhmitted to AS$: Section II Pro 9IEm!L.!RLAEEIgyal_ prior to incorPDIAtlD2 1,he revisinna_iniD th1LEIDSIAID. 5.1 ASME Siction_XI Programa j 5.1.1 AEME Section XI PI ngIsas A. Defining ASME Section XI Code class 1, 2, and 3 (equivalent) boundaries in accordance with 10 CFR 50.2(v), Regu3 story Guide 1.26 R3, ASME Section XI and guidelines in 10 CFR 50.55a. B. Preparing / revising ASME Section_XI color-coded boundary classification drawings to identify the ASME Section XI Code classification 1, 2, aad 3 (equivalent) boundaries within each plant system as defined in 5.1.1.A. These drawings are to be used for all ASME Section XI program activities only. See Attachment 1 for drawing list. C. Preparing / revising ASME Sec tion XI drawings which identify the Class 1, 2, and equivalent components (including supports) that require inservice and/or preservice NDE to satisfy ISI Program requirements. See Attachment 1 for drawing liat. 1401C/COC3
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$1-114. 2 .
. SURVEILLANCE- ASME SECTION XI R visics 19 INSTRUCTION INSERVICE INSPECTION PROGRAM P;g) 9 Cf Klol i-
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D.. Preparing / revising SON !$1 Programs as required. [i E. Ensuring that these programs provide-detailed. instructions for ISI including the following information as a minimums
; 3. The ASME Rection XI Code of Record for ISI.
- 2. The inspection interval.
- 3. A list of the Section XI boundary classification drawings-(for ISI only).-
- 4. A list of the ISI drawings.
- 5. An examination schedule,in tabular form and provide the 40-year. sample, - the 10-year interval sample, ,
and the samples for the three periods within the interval.
- 6. Augmented examination' requirements based on other-codes / standards, regulatory' guides, etc.
- 7. The NDE method to be used.for each component.
- 8. The ASME Section XI examination category for each t
component.
- 9. Copies of_all roguests for relief.- ,
- 10. . Name and address of owner.- -i
- 11. Name and address of generating plant.
i
- 12. Name or number designation of-the unit.. ,
- 13. Commercial operating date for the unit. '
- 14. A description of the system for maintaining status of completed work. '
- 15. DiscussionLof= scan plans which provide details of required component. examinations:such:ss' component- ',
identifier, NDE procedure,' calibration block, drawing number,-etc. '
. T. Ensuring that Notification of Indication (NOI) Form is-included as an appendis within the ISIiProgram.
G. providing PSI and/or;ISI ASME Section XI interpretations-1 as:roguested by various-site organizations or as required in program development and implementation. H. - ASME-Section XI Programs shall be responsible:for preparing and revising the initial piping component support _ examination boundaries,__Appendir D. 1401C/COC31
SI-114.2 SURVEILLANCE ASME SECTION XI R visica 19 INSTRUCTION INSERVICE INSPECTION PROGRAM.- Pcgs 10 cf 101 [
-5.1.2 ASME Eeetion rf Programa PR[SIM Responsibilitiest
[; A. Providing a list of4 components requiring examination-during each period of the 10-year laterval that includes the components that mugt be examined during a specific refueling outage. This listing shall-' include the component-identifier, ASME Section XI examination category and item number, examination method, drawing number, sheet number, and examination requirement source. This list will be provided to the Site Quality Organisation (S00) and the Inspection Services _ : Organisation (ISO) in accordance-with plant schedules.. ' B. Providing any additional samples required due to examinations performed. C. Approving revisions to scan plans affecting component selection or any provision of the listing of_ components identified in 5.1.2.A. 5.1.3 ASME section rf Proorama Request for Relief Rampangibilities: A. Determining if a request for relief.is required because
~
of' areas which are inaccessible'or partially 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 examinations are documented. C. Submitting Requests for Rollef to Site Licensing. 5.2 The. Insgeetion servigts orcanl2ation (150) , 5.2.1 150 Shall be Respons'Ible fort
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A. Preparing / revising PRISIM data base to include all components within the ISI Program Instructionifor-SON. B. Preparing / revising scan plans.for.each refueling _ outage , of an inspection interval utilising PRISIM. .This includes providing. additional _Information by_NDE Level III personnel to complete scan plan preparation
-such.as NDE procedure references, calibration standard references, and ultrasonic examination scanning angles.-
C. Providing Level'III approval of each scan plan revision, which affects the additional information supplied in ' 5.2.1.B, and maintaining a scan plan revision history log.
- D. Submitting scan plans to the S00 in accordance with plant schedules.-
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! - SI-114,2 SURVEILLANCE ASME SECTION XI R3vish2 19 - INSTRUCTION INSERVICE INSPECT!cM PaoGRAM P gs.1 of 101 2 i E.- Any areas that are inaccessible or partially inaccessible for examination will be evaluated by NDE Level !!!
.- [ examination personnel to determine if a request for relief i should be submitted to the NRC.. Site Engineering should be consulted where structural support members are-Inaccessible.This information shall be provided to ASME-Section XI Programs.
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 ASME Section XI Programs for possible action in accordance with Se: tion 19.0 of this program. G. Preparing / Revising _NDE Procedures.- H. -Preparing / Revising program for qualification / i certification of NDE personnel. 5.2.2 ISO Responsibilities When RE Forformed by Contractors A. Ensuring the adequacy of prospective contractor's QA. programs in accordance with the TVA NQA Plan. 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 authorised for use by ISO. C. Contract preparation. administration, and supervision will be the responsibility of 250. -Inspection plans submitted. by outside contractors shall be reviewed and approved by ISO prior to use. D. Approving contractor's written practices;for gum 11fication and certification of NDE personnel and_ approving certifications of contractor's NDE personnel utilised for the performance of PSI /ISI as-specified in QMP-102.4. 5.3 2'he site cuality oroanization is00) 5.3.1 S00 Responsibilities on Scheduled Examinationat A. Providing a list of:the components-to be scheduled for examination during each refueling outage to the ISO. This will,be provided in accordsnee with plant schedules.' B. Initiating a pre-outage meeting on augmented examinations _per-Section 20.0.- 5.3.2 EQo Responsibilities'en Sean E sus
-A.- Approving all scan plans and all scan' plan revisions.
B.- Submitting copies of the aIproved scan plan. to site management and to_the authorized Nuclear Inservice Inspector.(AN!!). 1401C/COC3'
SI-114.2 , SURVEILLANCE ASME SECTION XI R3visiO2 19 INSTRUCTION INSERVICE INSPECTION PN) GRAM P g) 12 Cf %1*lOf b stl8d9s. 5.3.3 EQQ. Reap.Qallbilities on PerfoInanc.e of ND_E ( A. Performing NDE in accordance with ISI Progran Instructions, applicable scan plan, and HDE procedures utilising personnel certified in accordance with OMP-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 sepresentative to have access to any documents and all parts of the plant and offices (subject to plant security and healt.h physics requirements) necessary for performing his required duties. D. Notifying the ANII prior to starting examinations. E. Preparing N0ls for examination results which, when evaluated by Level II or III examination personnel, do not meet the acceptance criteria of the NDE procedure. N01s 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 ASME Section XI 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 en N0! form prior to closure. I. Ensuring that original of the closed N01 la flied with the original examination report and a copy is sent to ASME Section XI Programs. J. Preparing examination report for completed examinations in acco dance 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 ant any comments or discrepancies (N01 nurber) are recorded in the scan plan.
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SI-114.2 SURVEILLANCE ASME SECTION XI R;vis1:3 19 INSTRUCTION INSERVICE INSPECTION PRJGRAM P g] 13 cf k( lot N ltlteht
- 4. Submitting the original examination reports to DCRM as QA records.
. E. Ensuring that ASKE Section XI Programs is notified of any areas that are inaccessible or partially inaccessible for examination. This information will 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 ASKE Section XI Programs Supervisor. L. Am NDE Level II or !!! Andividual shall evaluate the NDE results in accordance with ASME Section XI, IWA-3000. The results shall be compared with recorded results of the preservice NDE and previous inservice NDE results. 5.3.4 500 Respangibilities on Per d at A. Preparing ISI Suminary Report including Form NIS-1 in accordance with requirements of ASKE Section XI IWA-6000. B. Ensuring that Torm 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 Repert cover sheet in Appendix B following each refueling outage when inservice examinations are performed.
E. Preparing the Site Final Report which includes all pertinent PSI /ISI data such as Personnel Certifications, Examination Data Sheets, and the PSI /ISI Summary Report. F. Submitting the Final Report which contains the Summary Report to DCRM as a QA rect ro. 5.3.5 SQ.Q Responsibilities When 3 E FerfoImed by contragtgra: A. Ensuring that contractors are familiar with the ISI - Program Instruction being used. D. Ensuring contractors are certified using guidelines of QHP-102.4. C. Maintaining curveillance of contractor ISI or PSI activities to verify compliance with the contract and applicable ISI Program Instruction requirements. D. Ensuring that the elements of Subsection 5.3.3 are completed. 1401C/COC3
51-114.2 SURVEILLANCE ASKE SECTION XI R visica 19 INSTRUCTION INSERVICE INSPECT!0H PROGRAM P;go 14 cf 101 5.3.6 EQQ_Rgsponalbilit[gs With PSI conducted _in Manufaglurer's Sh22
, The S00 is responsible for ensuring records are identified-and documented as are TVA-generated reports is accordance with this instruction. Other roport formats may be utilised provided the minimum required 1 formation is contained therein.
5.3.7 EQO.Responsibilitigt for Compament Support BARDd&Ilta The 800 shall be responsible for determining the examination boundary for new or modified supports. 5.4 Eite Document control and Records Management _IDf.flil DCRM shall be responsible for issuing controlled copies of ASKE 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 500, the Authorised Nuclear Inspection / Authorised Nuclear Inservice Inspector ( ANI/AH!!), ASME Section XI Programs Supervisor, and to the Site Licensing Manager as roguested. 5.5 Sit.AHLJtAcrator Maintinancg_And TechnelD.QX A. Providing a list of steam generator tubes to be examined for a specific refueling outage. Thio'ilating shall include the component identifier, ASME Section XI examination category and item number, examination method, drawing and sheet number, and examination requirement source. This list will be provided to the 800 and ISO in accordance with plant schedules. B. Providing any additional samples required due to examinations performed. C. Approving revisions to scan plans affecting tube selection or any provision of the listing of tubes identified in 5.5.A. D. SGMT shall be responsible for 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. 5.6 Bite Licensing Manager Site Licensing Manager is responsible for submitting ISI Program Instruction,. revisions, requests for relief and reports to the NRC for review and/or appreval. All ASME Section XI correspondence shall include ASME Section XI Programs on distribution. 5.7 Plant Manager Plant Manager is responsible for approving and issuing SI-114.2. 1401C/COC3I
= - = _ _ _ - . .- -
St-114.4 ^ SURVEILLANCE ASME SECTION XI R3 vision 19 INSTRUCTION INSERVICE INSPECTION PROGRAM Popo 15 of 101 The plant Manager is responsible for designating the orge .wation responsible for preparing dispositions for NOIs. I i 5.8 Elte Engineering Site Engineering is responsible for deuigning, fabricating, j 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. Site Engineering is responsible for evaluating and providing a disposition for indications initiated by a Notification of Indication (NOI). Nuclear Engineering is responsible for providing specific written details for any augmented requirements for which they are responsible per Section 20.0, and determining if a post examination meeting is required. Site Engineering is responsible for determining critical areas of examination to ensure structoral integrity has no been compromised and identifies these areas to the NDE Level III when requested. Site Engineering is responsible for evaluating and making recommendations for further action on camples with indications af ter the second additonal sample has been performed and submitted by ASME section XI programs. i 5.9 EE1._ Conducted in Manuineturer's shop If examinations were performed in the manufacturer's shop, they may serve as PSI examinations provided: A. They were performed after hydrostitic test of vessels. B. They were conducted under conditions and with methods expected to be employed for subsequent ISI examinations. 5.10 Implementation ASME Section XI Programs, ISO, and S00 utilize a computerized data base system, PRISIM, for status and Section XI credit of completed ISI examinations and augmented examinations. PRISIM data base is utilized to provide a listing of components requiring examination during the 10-year ISI interval, each period and scan plans for a specific refueling outage. All specific NDE procedures used durlsg the inspection program shall be reviewed and approved in acecrdance with the NDE Procedures Manual, QMP-110.5. NDE precedures will be implemented in accordance with SSP 3.1. Whenever an unacceptable indication la discovered, Section 17.0 of this procedure and the form in Appendlz C shall be utilized. In those cases where an outside contractor is furnishing inservice 1401C/C0C3
SI.114.2 SURVEILLANCE ASME SECTION XI R3 visits 19 INSTRUCTION INSERVICE INSPECTION PROGRAM peg 2 16 of 101 examination services, the contractor will normally initiate the form in Appendix C under the supervision of the S00 i Representative. See Section 17.0 of this program. S.11 Schn_E1An 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 system or component, the scan plan shall be approved by 500 and an NDE Level !!! Andividual from ISO. ISO shall submit scan plans to 800 in accordance with plant schedules. 500 shall submit copies of the approved scan plan to Site Management and to the Authorised Nuclear Inservice Inspector. When inservice examinations are implemented by instructions other than this program (e.g., maintenance instructions), copies of the instruction data sheets. shall be submitted to S00 by the performing orgtaisation to allow these examinations, if applicable, to be included in the reports discussed in Section 16.0. During implementation phases (usually outage periods), it may become necessary to change the scan plan. Scan plan changes can be initiated by 500, ISO, and ASME Section XI Programs, or by other personnel involved with the implementation of the scan p.an. All changes shall be coordinated with an 500 Representative and, as needed, with the appropriate plant planning and scheduling personnel for f acilitating the use of -supporting craf t pe rsonnel. Revisions to the scan plan shall be controlled in the samt manner as the original. ISO shall maintain e scan plan revision history log. However, interim working copies may be hand written to allow examinations to be performed before a formal revision is issued. These changes shall be approved by an ASME Section XI Programs Specialist and a NDE Level III. Both individuals shall sign and date all such changes. 5.12 Pipino configuration chan211 When major portions of existing piping are replaced or whole new systems are added, a system walkdown chould be performed by ASME Section XI 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 additicun and deletions), s eplacements, 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 field corrected copies shall be used in the performance of examinations.- Copies of these field c orrected drawings shall be transmitted to ASHE Section XI Prograris by 500 using a drawing transmittal form as in Appendix E of this program. A filo-and transmittal number log of the correctso drawings and transmittal forms shall be maintained by the SQO for future reference. ASME Section XI Programs shall be responsitie for reviewing the_ proposed change, revising the drawings as necer.sary, and issuing the revised drawing p rior to the next refueling ot tage. The transmittal form i 1401C/COC3
p
' SI-114.2 SURVEILLANCE ASKE' SECTION XI R:visita 19 INSTRUCTION INSERVICE INSPECTION PA9 GRAM Pag) 17 of 101 +
shall be returned to the 800 after the referenced drawings have been revised by an ASHE Section XI Programs representative. The t ISO scan plan shall be revised as necessary to reflect these field
; corrected drawings (interim working drawings) and any PSI /ISI examinations performed due to these variations in configuration.
6.0 hijngyJATIONS AND DEFINITIQ)@ 6.1 AIA - Authorized Inspection Agency. 6.2 AI - Authorized Inspector (may denote an ANI or ANII). 6.3 ANI - Authorised Nuclear Inspector. 6.4 ANII - Authorized Nuclear Inservice Inspector. 6.5 Iype A Inminatian Dounda,Iys The type of boundary to be used for those supports that are attached to building floor, walls, ceiling, or embedded plate. 6.6 Zype D Examination. Boundary: The type of boundary to be used for those supports that are attached to acother existing support. 6.7 Type C Examination Boundarva The type of boundary to be used for those supports that are attached to esisting steel. 6.8 Iype D Examl Dation Boundar_y The type of boundary to be used for those supports that are attached to an intervening element. 6.9 Notice of Indication (NOI) - A form used to report any discrepant conditions found during the performance of NDE. Used for ISI examinations only. 6.10 Scan Plan - A schedule of examinations required to be performed during a particular period of time. 5.11 NDE - Nondestructive Examination. 1 6.12 RR/WO - Work Request /Hork Order. 6.13 PER - Problem Evaluation Report. 6.14 Program for ISI Data Management (PRIS3M) - a mainframe computer program for scheduling, tracking, mairchinlug status, and reporting of ISI examinations performed on a site / unit basis. It has the capability to allow categorisation of these examinations by areas as needed for Code credit, additional exam credit, augmented credit, etc. 6.15 Components - Denotes items in a power plant such as vessels, piping systems, pump;, valves, and component supports. 6.16 Normal Operation - Normal plant operation conditions include reactor startup, operation at power, lot standby, and reactor cooldown to cold shutdown conditions. Test conditions are excluded. 1401C/COC3
SI-114.2 SVRVEILLANCE ASME SECTION XI kevision 19 INSTRUCT!0H INSERVICE INSPECTION PH/ GRAM Pegs 18 of 101 K i-6.17 Pressure-Retaining Material - Applies to items such as vessel heads, nossles, pipes, tubes, fittings, valve bodies, bonnets, disks, pump i casings, covers, and boltings which join pressure-retaining 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 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 - Tinding Identification Report. j 6.21 SCAR - Significant Corrective Action Report. + i 6.22 Examination - Denotes the performance of all visual observation and NDE. 6.23 Inservice Inspection (ISI) - Inspection required by ASME Section XI ' during the service lifetime of the power unit. 6.24 Nondestructive Examination (NDE) - Methods used for the detection and evaluation of discontinuities and the measurement of physical , dimensions and condition of items. These methods include radiography, ultrasonic, eddy current, liquid penetrant, magnetic particle, inservice visual, and weldini visual. .These methods do not impair the serviceability of the items. 6.25 Preservice Inspection (PSI) - Inspectlans required by ASME Section XI to be completed prior to initial plant startup, or inspections required by ASME Section XI if a compcnent is replaced, added, repaired, or altered during the-service lifetime-of a power unit.- ' 6.26 Augmented NDE - NDE includes visual, surface, and volumetric examination methods as well as leak race testing. Augmented NDE includes all NDE which is not' required by the ASME Section XI except I (1) fabrication and installation NDE performed in accordance with , design specification or construction code requirements, and (2) leak
- rate testing required by 10 CTR 50, Agpendix J.
~ 7.0 CQBPONENTS SUBJ];CT TO EXAMINATION--ASME CODj LLASS l'(EOUIVALENT)
The ASME Code Class 1 (equivalent) components to be examined during the
-inspection-interval are outlined below. The entire length'of each weld described shall be examined for the first 10-year IS!_ interval unless otherwis* noted.- When a portion of a weld langth -is to be examined during an inspection period,- the areas era:ained each inspection period shall be
- documented on the examination data sheets. .
Components exempted from examination are dia cussed in Section 7.7 of this - - program. LTable A'of Attachment 4 provides-additional.information such as
-reference drawing numberst and ASKE.Section'YI,. Table-iNB-2500-1; examination categories.-
1401C/COC3 -1 1
SI.114.2 SURVE!LLANCE ASHE SECTION XI R;visica 19 INSTRUCTION INSERVICE INSPECTION PROGRAM Pcg) 19 cf 101 7.1 Reactor Vessel 7.1.1 Reactor Vessel Eeam Welds 7.1.1.1 gircumferentiAL Ehe11 Welds There are four circumferential welds (esch approximately 50 feet long) in the vessel cylindrical shell, three of which are located 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 veld deposited austenitic stainless steel. 7.1.1.2 Loneltudinal Shell Welds There are no longitudinal shell welds associated with the reactor vessel. 7.1.1.3 Closure Head circunferential Weld The entire length of the closure head cap weld (epproximately 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 Attachment 4. 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 veld deposited austenitic stainless steel. 7.1.1.4 L2Egr-Head circumfereratial Weld The entire length of the lower head circumferential weld (approximately 3f feet in length) will be ultrasonically examinto during the third inspection period using remote inspection devices from the vessel inside diameter with the core internals removed (see Request for Relief ISI-5). The lower-head sections-are fabricated of A-533, Gr. B, Class 1, manganese-molybdenum steel, and are clad with weld deposited austenitic stainless steel. 1401C/COC3
$1-114.2 {
R:visica 19 SURVEILLANCE ASME SECTION XI INSTRUCTION- INSERVICE' INSPECTION Pt>0 RAM pcg3_20 cf 101 1
, 7.1.1.5 Closure Head Merldlonal_Ms,14
'f'i The closure head does act include any meridional j welds.
7.1.1.6 Lower-Head Merldlonni .felds i t i
'. 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 examinsd during the third inspection period using remote inspection devices from the ; vessel inside diameter with the core internals removed. i The lower-head section material is fabricated of A-533, Gr. B, Class 1, manganese-molybdenum steel ' and clad with veld deposited austenitic stainless l steel. 7.1.1.7 Shell-to-Flange. Held 1 i The entire length of the shell-to-flange weld (approximately 50 fear in length) will be ultrasonically examined from the vessel inside - diameter using remote inspection devices during the g third inspection perico (see Request for Rollef 151-10). The-vessel flange section is fabricated of A-508, I Class 2, manganese-molybdenum steel and is clad. Internally and on the gasket f ace with veld , deposited austenitic stainless steel. 7.1.1.8 closure Head-to-Flangt- Weld and Tier Area > The entire length- of t he 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 head-flex area will bc surface examined during the inspection interval.- The length of weld to be examined each inspectJ on period is included in Table A of Attachment 4.(see Request for Relief ; ISI-18). ~j The closure head flange section is f abricated of A-508, Class 2,~ mange.tese-molybdenum steel and-is clad internally and of'the gasket face with weld deposited' austenitic : tainless st' eel. ' I 7.1.1.9 Repair Welds i i Base metal weld repains in the beltline regio, i where the repair depth exceeds 10 percent nomin,1 l of the vessel wall aba11:be' ultrasonically . . . l- examined. There are 30 base metal repair welds in-I: ~the beltline region of the Unit.2 reactor vessel.- ' 1401C/COC3-d + W %= g 9 --me. ., r o , g e, 9 c--.,4'y+cp4.ig3, ty==W-M; i- *- T-
$1-114.2 SURVEILLANCE ASKE SECTION XI R vis100 19 INSTRUCTION INSERVJCL INSPECTION pB} GRAM pag) 21 cf 101
+ 7.1.2 Ranetor.ygmatl.Norale-to-Vengg1 Welds e ! There are four inlet noestes (27.500 inch ID) and feur outlet possles (29.937-inch ID). The eight nossle-to-vessel velds will be ultrasostcally examiced from the inside diameter using remote inspection devices. The four outlet nousle-to-vessel volds shall be ultrasonically examined from the nozzle bore when the upper internals are removed during the first inspection period. The inlet nossles are not accessible until the core barrel is removed. The four Anlet nossle-to-vessel wclds shall be ultrasonically examined from the nozzle bore and from the vessel shell Anside diameter during the third inspection period when the core barrel has been removed. The outlet nozzle-to-vessel welds 6 hall also be ultrasonically examined f rom the vessel shell insado diameter during the third inspection period when the core barrel has been removed. The examination schedule has changed. Ese Request for Rollef 187-15 for background information. The new schedule requires that the four lplet 4sd four outlet nossle 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 nossle forgings are fabricated of A-508, Class 2, manganese-molybdenum steel and are clad with veld deposited austenitic stainless steel. 7.1.3 Reactor Vessel Nottle Inside Pd igt Section The eight nossle inside radius sections (including the outlet nozzle integral exteneicus) shall be ultrasonically examined at the same time as the examination of the nozzle-to-vessel velds (see Section 7.1.2). Nossle forging material is identifled in Section 7.1.2 of this program (for background information, see Raquest for Relief ISI-15). 7.1.4 Reactor vessel Part{al Penetra_t,1.gnJ@ The vessel includes 4 Upper Heto Injectica (UHI) nossles (copped in Unit 2 Cycle 4 UHI samoval), 1 vent pipe nozzle, 78 control rod drive nozzles, sud 58 instrumentation nousles with partial penetration welds. Approximately 25 percent of each group of nossles shall be visually examined from the vessel outside diameter in acetrdance with visual-examination method VT-2. This 25 percent shall include 1 UHI nostle, 1 vent pipe nost e, 20 control rod drive nossles, and 15 instrumentation nousles. . Examination of these nossles during the inspection interval shall be distributed among the inspectit.n periods in accordance with' Table A of Attachment 4. 1401C/COC3
SI-114.2
," SURVEILLANCE . ASME SECTION XI ,
R3 visits 19
~ INSTRUCTION INSERVICE INSPECTION PR) GRAM Pcg3 22 et 101
+
4 7.1.5 Reactor Vessel Morale-to-Enfo rod Welds [ 4 6 l The inlet and outlet nossle-to-Aafe end welds shall be . 1 ultrasonically examined from the inside diameter using ( remote inspection devices. The ultrasonic examination shall i be performed at the same time se the examination of the ' nossle-to-vessel welds conducted from the nossle boro (see Section 7.1.2). , All of the nossle-to-safe end welds shall also be 11guld 'I penetrant examined during the inspection interval coincident > vith the ultrasonic examinations. The SON Unit 2 Report- " Evaluation of Cracking in Reactor Vessel Nossle Stainless Steel Buttering"--states that Unit 2 nostle-to-safe end welds 2-RC-175E'and 2-RC-24SE shall be examined during the first inspection interval (see I memorandum from D. W. Wilson to H, L. Abercrombie, dated August 1, 1986 (L18 460730 899)). The remaining mostles will be examined during the normal ISI intervals. The examination schedule has changed. See Request for Relief 151-15 for background information. The new schedule requires that four inlet and four outlet nozz1c-to-safe end- , welds be examined during the third inspection period. ; Each nossle safe end weld is a stainless steel type 304 weld build up (buttering). 7.1.6 Reactar Ver;tl Pressure Retalnino Boltino Larcar Than Two Inchen In V amttgr ; 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. itspection interval in . accordance with Table A of Attachment 4.. The closure nuts ' shall be magnetic particle examined. The closure studs shall be ultrasonically and magnetic particle eunmined. .The , ligaments-between the vessel flange stud holes shall be ultrasonically examined.- The-closure washers'shall bo visually examined in accordance with visual' examination method VT-1. The bolting may be examined either (n) in place under tension, (b) when~the connection is , disassembled, or (c) when the lolting is removed. Provisions for this examinatior are . included in 0-HI-MRR-068-005.0. Where needtd the examinations of the-studs should be identified with the,particular stud in-accordance with the unique.iden11fication system for the- ' studs and nuts. The 7-inch diameter studs, nuts, and washers are f ab'ricated of SA-540,-Gr. 823 Nickel, chrome-molybdenum steel. l 1401C/COC3
1 51-114.2 SURVEILLANCE ASME SECTION XI R visic3 19 j INSTRUCTION INSERVICE INSPECTION PHICRAM pcge 23 cf 101 i 7.1.7 Reactor Vessel Pressure Rginini.a Boltina.Two Inches And l Emaller In Diameter ? There is no pressure retaining bolting two inches or smaller l An diameter. I 7.1.8 Reactor Vessel Intecrally Weldy1_ Attachments ! Thero are no integrally welded vessel supports. 7.1.9 Etattpr Vessel 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 l that is made accessible for examination by removal of ! components during normal refueling outages. The examinations shall be performe$ at the first refueling outage and subsequent ref ueling outages at approximately three-year intervals. 7.1.10 Egaetor Vessel Removable Core Gjpport Structures The visually accessible attachment welds and visually accessible surfaces of the coro support structure shall be visually examined in accordance with visual examination method VT-3.. This examination may be deferred to the third inspection period. The structtre shall be removed from the , reactor vessel for examination. The removal of ths. core support structure is implements 3 by MI-1.4. 7.1.11 Fenetor Vessel control Red Drive stousinga 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 contro3-rod drive housings. Two (10 percent) of the peripheral housing butt welds shall be ultrasonically examined during the inspection interval in accordance .Sth Table A of Attschment 4. The housings consist of a 6-inch OD adapter of A-182, 304SS and a 4-luch OD body of SD-167. 7.1.12 Eggetor Vessel Aux 111ary Head Adapters Each of the four auxiliary head adapters includes a pressure retaining dissimilst metal we16. The four dissimilar metal welds shall be- ultrasonically rod 11guld penetrant exanined during the inspection interval in accordance with Table A of Attachment 4. The adapters consist of a SA-182, 304SS upper portion and a SB-166 lower portion. Swe Section 7.4.4.6 for.information on RV auxiliary head adapter cjtcumferential pipe cap welds. -The pipe cap welds are included in the reactor coolant system. 1401C/COC3
SI-114.2
, SURVEILLANCE ASME SECTION XI R:visita 19 INSTRUCTION INSERVICE INSPECTION PLOGRAM Pcg] 24 of 101 7.2 RILAintligI 7.2.1 PJgrantiggtJCircumferential Shell-to-Head Welds
{ There are two circumferential shell-to-head welds, each approximately 24 feet in length The entire length of each weld shall be ultrasonically examined during the inspection interval in accordance with Table A of Attachment 4. All vessel shell and head sections are f abricated of SA-533, Class 2, manganese-molybdenum steel and are clad with ' austenitic stainless steel. 7.2.2 Pressurirer Lonoitudinal Shell-to-Head Helds There is one longitudinal weld intersecting each circumferential shell-to-head weld. One foot of each longitudinal weld shall be ultrasonically examined during the inspection periods in accordance with Table A of Attachment 4. The one foot of weld examined 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-she'l weld. The vessel shell section material is identified An Section 7.2.1. 7.2.3 EIg11gIlzer Circumferential ani Heridional Head Welds There are no pressuriser circumferential or meridional head welds. 7.2.4 Ett11 Miller Norrie-to-Vessel Helds and Notale Inside Radius Eastian The pressuriser includes three 6-inch safety valve nossles, one 6-luch rollet valve nomsle, one 4-inch spray nossle, and one 14-inch surge nossle. All of the nozzle-to-vessel welds, including nomsle inside radius section, shall be ultrasonically examined during the inspection interval in accordance with Table A of Attachn.vnt 4. The nossles are fabricated of SA-508, Class 2, manganese-molybdenum steel. 7.2.5 Pressuriser Hester Pengtration Melds There are 78 heater. penetration welds located in the pressuriser lower head. Appro Amately 25 percent of the heater penetration welds (20 wolds) shall be visually examined during the inspection. interval in accordance with. visual examination method VT-2. tramination of these . penetrations during the inspection interval shall be distributed among the inspectica periods in accordance with Table A of Attachment 4. 1401C/COC3
51-114.2 SURVE1LLANCE ASME SECTION XI R:vis103 19 1HSTRUCT10H INSERVICE 1HSpECT10N PROGRAM p g) 25 of 101 I 7.2.6 Ersseurisgr Horrie-to-Safe End ift.lda ' Each of the six nossles identified in Section 7.2.4 includes
. a welded forging safe end. All of the nossle-to-safe end )
welds shall be altrasonically and liquid penetrant examined during the inspection interval in accordance with Table A of Attachment 4. Safe end connections are SA-182, Cr. T-316L forgings. 7.2.7 Pressurlrer Pressure Retainino Boltino Latoer Than "wo Inches In Diameter There is no pressure retaining bolting larger than 2 inches in diameter. 7.2.8 Et211uriter Pressure Retalnino Deltl oDTwo Inchtg._).nd SmalltI_.hL.D.1ADfiti All of the pressuriser manway bolts shall be visually examined in accordance with visual examination method VT-1. The examinations during the inspection interval shall be in accordance with Table A of Attachment 4. The bolts may be 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 Pressuriner Integt.gily Welded Sunnort Attachments 7.2.9.1 Pressurifer Support Slig,t 2he entire length of the pressuriser support skirt-to-vessel weld (approximately 23 feet in length) shall be surface examined (magnetic particle) during the inspection interval in accordance with Table A of Attachment 4. The support skirt is epproximately 1.5 inches thick and is fabricated of EA-516, Gr. 70, carbon steel plate. 7.2.9.2 Pressuriter seismie Luss There are four (4) intsgrally wuoed. seismic lugs on the pressuriser, whose design base thickness is
. greater than 5/8 inch. All four (4) lugs shall.be surface examined duria2 the inspection-interval in accordance'with Table A of Attachment 4.-
1401C/COC3 *
+
SI-114.2
' SURVEILLANCE ASME SECTION XI R visics 19-INSTRUCTION- INSERVICE INSPECTION PROGRAM P:g) 26 cf 101 7.3 Steam Gentrators (4) j 7.3.1 Steam Generator Primary Side circumferential And Mer1412nal
- Head Welds There are no steam generator primary side circumferential or 9
meridional head welds. 7.3.* Steam Generator Primary Tubesheet-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. 4 See Table A of Attachment 4 for examinations during the inspection interval. The tube plate is a SA-508, Class 2, steel forging, clad on the primary side with NiCrFe alloy. The hemispherical chamber is a SA-216, Gr. WCC casting, clad with austenitic stainless steel. 7.3.3 Steam Generator Primary Nozzle Insida Radius Secting The steam generator primary norsles 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 pr.imary nozzle inside radius section of all nozzles shall be ultrasonically examined. -In accordance with the SON Unit 2 NRC Safety Evaluation Report dated February 7, 1991, Enclosure Paragraph 2.4 (page 6) states "that delaying the volumetric examination of the nozzle sections until the third inspection period of the first luspection interval and then following the Code requirements is acceptable." See Reguest for Relief ISI-6. 7.3.4 Steam Generator Primary Nozzle-to-Safe End Walda Each steam generator includes two nozzles with buttered' safe ends. Each nozzle-to-safe end weld from each' generator shall be ultrasonically and 11guld penetrant examined during the inspection interval in accordance with Table A of Attachment 4. The nozzles havo buttered 308L safe ends. 7.3.5 Steam Generatpr Primary Presagre Retninine Boltina Larcer Than Two Inches In Diametgr There is no pressure retaining bolting larger than two inches in diameter. 1401C/COC3
SI-114.2 SUkVEILLANCE INSTRUCTION ASME SECTION XI R visita 19
-INSERVICE INSPECTION PROGRAM Page 27 of 101 7.3.6 'Ettam Generator Primary Pressure Retalnino Bo}tino two JAches And Smaller.In Diamel g h
( Each_ steam generator includes two manways. Each manway includes 16 connections at 1.88 inches in diameter. All 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' interval in accordance with Table A of Attachment 4.
- 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. 7.3.7 Steam Generator Primary Inteorally Welded Support Attachments 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. 7.3.8 Steam Generator Tubing See Augmented Section 20.4 for steam generator tubing _ examinations. 7.4 Piping All ASME Code Class 1 piping systems to be examined are fabricated-of stainless steel. The reactor coolant main loop piping straight 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. weld isometric. See Request for Relief ISI-3 for Class 1, longitudinal, circumferential, pipe branch connection welds, examination categorie- B-F and-B-J, which have interference problems for volumetric eraa, nation. The following Class 1 piping systems are subject to examinations Reactor Coolant Main Loop (RX) Otlaer (RC) Chemical and volume control (CVC) Residual Heat Removal (RHR) Safety Injection (SI) Upper Head Injection (UHI) The UHI System was removed from service during Unit 2 Cyc12 4. For reference to the schedule of examinations performed on this system, see Revision 14 of this instruction. Reference Sections 7.1.12 and 7.4.4.6. 1401C/COC3
4 i (*y
'i SI-114.2'-
y : SURVCILLANCE; ASME SECTION XI R visica 19 , INSTRtfCTION ^ INSERVICE INSPECTION PROGRAM' Pag) 28 of:101- i
-.. ~
i 7.4.1.'Ejpino DIEsimilar Metal Welds. 1
-There,are no Class 1 dissimilar metal welds.
7.4.2~ Pipine Pressure Retalnino Boltina Larcer Than 2 Inches In Di ameter '
,' There is no piping pressure retaining bolting larger than 2 inches in diameter.
7.4.3 Pleine Pressure Retalnino Boltina 2 Inches and Smaller in 1 Diameter
- 4 The following systems contain bolted piping flange. j connections. A11'of the bolts or studs and nuts in each flange connection 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. Attachment 4. , i The bolting may be examined in place under tension or.when the bolting is removed. 7.4.3.1 Reactor Coolant-System'Pleine Boltina The Reactor Coolant-System piping includes bolted
= flange connections.
7.4.3.2 ChRmleal and Volume Control System Ploino Boltina The Chemical and Volurns . Control System (seal water
' injection) piping includes bolted flange' -
connections. s 7.4.3.3 RHR Svalem Pipino Bolting The RHR System piping does not include any bolted; .
-e 'ections. ^
7.4.3.4. Safety Iniection System Pleine Boltina The Safety Injection System piping includes bolted-flange connections. 7.4.4 Circumferential ' and Lonaltudins1: Ploine Welds -
-All Class;1 piping is seamless.-
- Circumferential pipe welds'four-inches and' greater nominal'
-pipe size' selected'for examination shall be ultrasonically
.uwl 11guld penetrantfexamined.: Circumferential pipe-welds lessL thanL 4-inch nomina 11 pipe elze selected for examination shal)Rbe liquid-penetrant examined..
1401C/COC3 s +m ,. , , m-
$1-114,2 SURVEILLANCE ASME.SECTION XI R;visica 19 ' INSTRUCTION IN$ERVICE INSPECTION PROGRAM Pcg) 29_cf 101 The examinations performed during the inspection interval shall 2nclude approximately 25 percent of the 40-year sample il of circriferential welds. The examinations shall be distributed during the inspection interval in accordance with Table A of Attachment 4.
7.4.4.1 Reactor Coolant Evstem Main Looo Pleing Circumferential Welds The_ Reactor Coolant System Main Loop piping includes circumferential pipe welds 4 inches and greater nominal pipe size. The velds selected for examination shall be ultrasonically and liquid penetrant examined during the inspection interval' in accordance with Table A of Attachment 4. There are no Class 1 pipe velds less than 4-inch nominal pipe aise in the Reactor Coolant System Main Loop piping. Two circumferential welds in the Reactor Coolant Main Loop piping, RC-23S1 (Loop 3) and RC-31S1 (Loop 4) are located inside the reactor vessel shield wall and are inaccessible for examination. See Requast for Relief ISI-7. 7.4.4.2 Reactor Coolant System Pipino Circumferential Welds Reactor Coolant System piping includes 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 Tahle A of Attachment 4.. There are pipe welds less than 4-inch nominal pipe size. The welds selected for examination chall be 11guld penetrant examined during the inspection interval in accordance with Table A of Attachment 4. 7.4.4.3 Chemical and Volume Control System Piping Circumferential Welig 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 11guld penetrant examined during the inspection interval in accordance with Table A of Attachment
- 4. There are no Clast 1 pipe welds 4 inches and greater in the CVCS system.
7.4.4.4 EHR System Ploino Circ umferential Welds The RHR System piping includes circumferential welds 4 inches and greater nominal pipe size. The welds selected for exanination shall be ultrasonically and liquid penetrant examined during the inspection interval in accordance with Table A 1401C/COC3 i
SI-114.2' I SURVEILLANCE ACME SECTION XI. R:visiC2 19 INSTRUCTION INSERVICE INSPECTION PL) GRAM Pag) 30 cf-101 l' of1Attachmentj4~. _There are_no Class 1 pipe welds
. ,, less than 4-inch nominal pipe sise_in the-RHR'
_3- system. l 7.4.4.5 -Safety Iniection svAtem Pipino circumferential Egigg: The Safety 2njection~ System piping. includes 1 circumferertial pipe welds 4 inches and greater' nominal pipe mise. The welds selected for' examination shall be ultrasonically .and;11guld
~
penetrant examined during the inspection interval in accordance with Table k of Attachment 4. : There are pipe welds less than 4-inch nominal pipe mise.: The welds selected for examination shall be 11guld penetrant examined during the inspection interval in accordance with Table A of Attachment 4. 7.4.4.6 Eeactor vessel Aurillarv Head Adanter Can Welds The greylock connectors were removed from service-during Unit 2 Cycle 4 and replaced with weldeu pipe caps. One of these four circumferential pipe cap welds (a15.5 in.)'shall be ultrasonically and liquid penetrant examined during the inspection ' interval in accordance with Section 7.4.4.2 of Table A of Attachment 4. See Section 7.1.12 for-information on reactor vessel auxiliary head adapter dissimilar metal welds. 7.4.5 Branch Pipino connection Weld 3 The entire _ length of each branch pipe connection weld ' selected for exhmination shall be exe- (ned. Branch pipe connection welds exceeding 2 inches nominal pipe size . .. selected for examination.shall be ultrasonically'and liquid 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 :
Attachment 4. EQIg -In the case of brauch pipe connections 2 inches nominal pipe size and smaller,1the welds of-all-the-systems affected have been combined and shall be-evenly distributed ovet the four inspection-intervals. 1401C/COC3 . I * -
'~
SI-114.2 SURVEILLANCE ASME SECTION XI R3visicn 19 INSTRUCTION INSERVICE INSPECTION PROGRAM Pig) 31 cf 101 7.4.5.1 Reactor Coolant System Main Loon Branch Ploe i Connection Helds ) The Reacter Coolant System Main Loop piping
' includes a branch pipe connection weld exceeding 2 -inches nomitsal pipe size. This' veld shall be ultrasonically and 11guld penetrant examined during the inspection Interval in accordance with
- Table A of Attachment 4. 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 Attachment ~ 4.
EqII: Each of these branch 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 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 possible case (the weld to pipe falls), the largest hole is that for a 2-inch pipe (any schedule). Therefore, it shall be treated as a 2-inch branch pipe for ASME Section XI purposes. See contract 68C60-91934, (N2M-2-8) drawing nos. 206C470 and 206C471 and installation detail.N2M-2-50. 7.4.5.2 .Etactor Coolant Systen Branch Pine Connection Welds The Reactor Coolant Sistem piping includes branch pipe connection welds exceeding 2 inches nominal pipe size. The welds selected for examination shall be ultrasonically and 11guld penetrant e=amined during the inspection' interval in accordance with Table A of Attachment 4 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 inspect 2on interval in accordance with Table A of Attachment 4. 7.4.5.3 Chemical and Volume Control System Branch Ploe Connection 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 s.ltrasonically and.11guld-penetrant examined dusing the inspection interval in accordance with Table 4 of Attachment 4. There is a branch pipe connection veld 2 inches nominal pipe size and smaller. This weld is not scheduled for examination this interval. When-this weld is selected for examination it shall be liquid penetrant examined. 1401C/COC3
l SI-114.2 SURVEILLANCE ASME SECTION XI R visi;3 19 INSTRUCTICH INSERVICE INSPECTION PROGRAM P:g) 32 cf 101
'7.4.5.4 RHR.Sytism Branch Pipe Connection Welds
( The RHR System piping. includes branch pipe
! connection velds exceeding 2 inches nominal pipe size. The welds selected for examination shall be ultrasonically and liquid panetrant examined during the inspection interval in accordance with Table A of Attachment 4. There are branch pipe connection welds 2 inches nominal pipe size and smaller in the RHR System. These welds are not scheduled for examination this interval. When these welds are se3ected for examination they shall be liquid penetrant examined.
7.4.5.5 Enfety Injection System Branch Ploe Connection Mgigg The Safety injection 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 accordanco with Table. A of Attachment 4. There are branch pipe connection velds 2 inches nominal pipe size and smaller. The welds selected for examination shall be 11guld penetrant examined during the inspection interval in accordance with Table A of Attachment 4. 7.4.6 Pipino Socket Nelda The entire length of each socket veld selected-for examination shall be 11guld penetrant examined. The examinations performed during the inspection interval shall include approximately 25 percent of the socket welds. The examinations shall be distributed during the inspection interval in accordance with Table A of Attachment 4. 7.4.6.1 Reactor Coolant Systen Pleine Socket Welds The Reactor Coolant System piping includes socket welds. The welds selected for examination shall be examined during the inspection interval in accordance with Table A of Attachment 4. 7.4.6.2 Chemical and Volume Ce ntrol System Pleine Socket Nelds The Chemical and Volume Control System piping includes socket welds. Tne welds selected for examination shall be examined during the inspection interval in accordance with Table A of Attachment 4. 1401C/COC3 1
n 51-114.2
+[ R:visics 192 .
- SURVEILLANCE ASME SECTION XI' INSTRUCTION: INSERVICE. INSPECTION PROGRAM Pcg3 33 cf '9&,loi .
J'Ot$ fil2tIkL .{
.i 7.4.6.3 FHR System Ploino Sochet Welds *
]l 9
The RHR System piping ~1ncludes socket welds.--The welds selected for examination shall -be z ezamined
'during the inspection interval in accordance with 4 Table'A of Attachment 4.
~
7.4.6.4 Safety Iniection System Piping Socket Welds. 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 Attachment 4. , 7.4.7 Ploina and Valve Inteorally Welded Support Members Integrally welded support members include the support attachments of piping required to be examined by Examination Category B-J. Included are those supports-which have attachment welds to-the valve and piping-pressure retaining boundary.and those attachments yhose gngport base material desiga_ thickness is 5/8 inch and-greater. .The entire-length _of each support attachment weld selected for examination shall be surface examined.- The examinations performed during the inspection interval 1 shall include 100 percent of-the integrally welded support members. 1The examinations shell be distributed'during the-inspection interval in accordasco with Table A of Attachment 4. 7.4.7.1 Reactor Coolant System Pipino and Valve Inteorally~- Welded Support Members The Reactor Coolant System' piping includes integrally welded support-members. All of-these shall.be examined during the l inspection intervali in accordance with T(ole A of Attachment 4.1 t 7.4.7.2 Chemical and Volume 'C3ntrol -System Ploino and Valve Integrally Welded Support Members The Chemical: and Volvme Control: System piping includes ' an integra13y welded support. member.; This'aupport shall bs-examined during the? inspection interval An'accordance with Table A of-Attachment 4.. 7.4.7.3- RHR System Ploino and-Valve Inteorally Welded-Suecort-Members The RHR System piping includes integrally welded' support members. All of these supports shall bel examined during the inspection interval in: accordance with Table A of Attachment 4. 1401C/COC3 1 g,,. ,
..nv
SI-114.2 [ SURVEILLANCE: 'ASME SECTION XI R;visitn 19' INSTRUCTION _ INSERVICE INSPECTION PROGRAM PCg334of94./01l4L C2]IrlEt 7.4.7.4 Safety Iniection System Pipino and Valve Inteorally Welded Sunoort Members I The Safety Injection System piping includes integrally welded support members. All of these shall be examined during the inspection interval in accordance with Table A of Attachment 4. Integrally welded support 2-SIH-20-IA was evaluated during the second period to require a reexamination for the next three periods per IWB-2420. This will require the integral attachment to be examined in the third period of the first interval and the first. two periods in the second interval (see Attachment 5). (See Section 7.8.) 7.4.8 Pipino and Valye comoonent Supports 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 and nonintegrally welded component supports. Component , supports extend from the piping and valves up to and lucluding the attachment to tho supporting structure. The setting of snubbers, shock absorbers, and spring-type hangers shall be verified in 3:cordance with the applicable NDE procedure with the acceptance criteria identified in the Sean Plan (see PRISIM data base) or the applicable work instruction. For reference tbs 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 Attachment 4. 7.4.8.1 Reactor Coolant System Pipino and Valve Component SuPPEta The Reactor Coolant System-piping includes component supports. All of these shall be examined during the inspection interval in accordance with Table A of Attachment 4. 7.4.8.2 Chemical and volume control System Pioina and Valve Component Suoncnta The Chemical and Voln.ne Control System piping includes-component sV2 Ports. All of these shall be examined during tie inspection interval in accordance with Table A of Attachment 4. f-1401C/C0C3
SI-114.2
. SURVEILLANCE ASME SECTION XI R:visiC3 19
' INSTRUCTION ' INSERVICE INSPECTION PROGRAM PCg3 35 cf 14L 101 MS izlO3-7.4.8.3 EHE_ System Pipino and valve comoonent Supoorts I The RHR System piping includes component supports. All of the se shall be examined during the inspection interval in accordance with Table A of Attachment 4.
7.4.8.4 Safety Iniection System Pipino and Valve Component Suonerts The Safety Injection System piping includes compotent supports. All of these shall be examined during the inspection interval in accordance with Table A of Attachment 4. 7.4.8.5 Reactor Coolant System Main toen Ploing and_.yalyg Component Suvoorts The Reactor Coolant i fatem Main Loop Piping includes component suppc-ts. All of these shall be examined during ths inspection interval in accordance with Table A of Attachment 4. 7.5 Eeactor Coolant Pumos (4) - RCP 7.5.1 RCP Pressure Retainino Boltino-Larcer Than Two Inches In RiameteI 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 thi bolting is removed. Flange ligaments between threaded bolt holes shall be visually examined (VT-1) once during the inspection interval if the connection 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 esgnetic particle (MT) examined and all threads in tie 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 fabr icated of 4340 steel, heat treated to A-540, GR. 24. Provisions for this examination are included in MI-2.2. 1401C/COC3
SI-114.2 SURVEILLANCE ASME SECTION XI R:visi"n 19' INSTRUCCION INSERVICE INSPECTION PROGRAM P g3 36_ cf 1HL 801
; OR3 lE{Dl9L I
7.5.2 ECP Pressure Retalnino Boltin2 2 Inches and Smaller 12-Diametti 6
!. 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 :artridge 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 each 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. Prlmer from V. A. Bianco dated January 10, 1987, No. B25870109045).
The bolting may be examined in place under tension or when removed. 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-10.2.3 and provides for examination of bolting. All of the bolting f rom one RCP shall be examined during the first inspection period, aad all of the bolting from a 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 fiembgra There are three Unit 2 reacto- coolant pumps, serial numbers 566 (RCP-1 casing), 704 (RCP-3 casing), and 709 (RCP-4 casing), with integrally welded supports. Each pump. has three integrally welded pump feet. These integrally welded pump feet whose design base is 15/8 of an inch shall be surface examined during the inspection interval in accordance with Table A of Attachment 4. 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, n.2d all of the supports from a dif ferent pump shall be examinad during the second inspection period. All of the supports from the remaining ~ pump shall be examined during che third inspection period. 7.5.4 RCP Component Suncorts Three of the RCPs have three csst feet integrally welded to the pump casing, the fourth pump has integrally cast feet. These feet are bolted to the support system. All component supports from each pump shall be visually examined during 1401C/COC3
n' SI-114.2 SURVEILLANCE ASHE SECTION XI R;visitn 19 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 37 of 14L lol
$l5 Ithths.
the inspection interval in accordance with visual 1 examination method VT-3 and Table A of Attachment 4. Support components extend from the RCP to and including the attachment to the supporting structure. All of the supports from one RCP shall be examined during the first inspection period, a.1d all of the supports from a dif ferent pump shall be examinod during _ the second inspection period. All of the supports from the remaining two pumps shall be examined during the third inspection period. 7.5.5 RC2_casina welds The Unit 2 RCPs pumps do not include casing welds. 7.5.6 RCP Chi 1D2 If a pump is disassembled for maintenance during the inspection laterval, the internal presstre boundary arrfaces shall be visually examined in accordance with visual examination method VT-1. Disast.embly of RCP's is performed in accordance with M!-2.2 ar$ provides for these visual examinations. If during the inspection interial a pimp 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 Larcer Than 2 Inches in Riameter There are no valves with pressare retaining bolting larger than 2 inches in diameter. 7.6.2 Yalve Pressure Retainino Boltina 2 Inches and Emm11er in Diameter 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 shall be visually examined during the inspection interval in accordance with visual exanination method VT-1. The examinations shall be distribeted during the inspection interval in accordance with Ttble A of Attachment 4. The bolting may be examined ir 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. 1401C/COC3
SI-114.2 SURVEILLANCE ASME SECTION XI R:vis103 19 INSTRUCTION -INSERVICE INSPECTION PROGRAM P;g] 38 cf 1HL h>l Ocs azjzikt 7.6.2.1 Emmeter Coolant Systep valve Boltino I, The Reactor Coolant S/ stem includes valves with
- bolted bonnet connections. All of these shall be examined during the inspection interval in accordance with Table A of Attachment 4.
7.6.2.2 Chemieni and Volume CSntrol System Valve Boltino The Chemical and Volume Control System includes valves with bolted bonnet connections. All of these have been excluded from examination in accordance with Code Case N-426. 7.6.2.3 ERAldual Heat Removal System Valve Bolting 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 Attachment 4. 7.6.2.4 Safety Iniection System Valve Boltina n The Safety Injection System i'cludes valves with bolted bonnet connections. All of these shall be examined during the inspection interval in accordance with Table A of Attachment 4. 7.6.3 Valve Inteorally Welded SuecoI; Members Examination of valve integrally wsided support members is included in Section 7.4.7. 7.6.4 Valve Component Supports Examination of valve component supports is included in Section 7.4.8. 7.6.5 Valve Body Welds There are no valves with body welds. 7.6.6 Valve B d ga The internal pressure boundary surfaces of valve bodies exceeding 4-inch nominal pipe size shall be visually examined in accordance with v11ual examination method VT-1. Examinations are limited to one valve within each group.of valves that are of tha same constructional design (i.e.,' globe, gate, or check valve), manufacturing method, and that are performing similar functions in the system. See Request for Relief ISI-2. 1401C/COC3
SI-114.2 SURVEILLANCE ASME SECTION XI R; visit 3 19 INSTRUCTION INSERVICE INSPECTION PROGRAM P g3 39 cf '>(lot
- Ols It}sk%E When it becomes necessary to disassemble any valve, subject to internal surface visual examination,'for normal-i 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 Exempted Camponents 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 coolant pressure boundary (defined in 10 CFR 50, Section 50.2(V); revised January 1, 1575) but exempted from Class 1 requirements by regulations of the regulatory authority having jurisdiction at the plant site; reactor vessel head Connections and associated piping,- 2-inch ncminal pipe size and smaller, made inaccessible by control rod drive penetrations,. 7.8 Successive Examinations Areas of flaw indications evaluated in accordance with INB-3122.4 and SSP-3.4 that qualify for continued service shall be reexamined during the next three inspection pericos 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-requirement. Components requiring successive examinations shall be-scheduled for examination in accordance with Attachment 5. 7.9 System Pr.q1gure Tests All ASME Code Class 1 (equivalent) system pressure tests shall be in accordance with SSP-8,5. 8.0 COMPONENTS SUBJECT TO EXAMINATION - ASME CODE CLASS 2 (EOUIVALENT) The ASME Code Class 2 (equivalent) components to be examined during the inspection interval are outlined in the following paragraphs. Extent of examination for piping welds will be in acc rdance with paragraph IWC-2411 and Table IWC-2520 of the 1974 Edition, Summer 1975 Addenda, ASME Section XI (examination catogories C-F and C-G). Components that are exempted from examinatica in accordance with IWC-1220 of ASME Section XI are discussed in Section 8.13 of this program. 1401C/COC3
. SI-114.2 SURVEILLANCE ASME SECTION XI R3visien 19 INSTRUCTION INSERVICE INSPECTION PROGRAM P g3 40 of 11Ll0I Ot$ Isle!l12 Where examinations specify a percentage of the total length of weld to be examined, the areas (s) examined shall be documented in the examination l report. Where a percentage of weld length 10 not referenced, the entire t veld length shall be examined.
Table B in Attachment 4 supplies additional information such as reference drawing numbers and A3ME Section XI Table-IWC-2500-1 examination categories. 8.1 Steam Generators (4) 8.1.1 Steam Generator Secondary Side circumferential Shell Welds There are three circumferential shell welds at gross structural discontinuities on each generator. The entire length of these three shell wolds from one steam generator shall be ultrasonically examined during the inspection interval. The number of welds to be examined during each inspection pt riod shall be in accordance with Table B of Attachment 4. 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 ve ssel shell sections are f abricated of SA-533, Gr. A, Class 1, steel plate. 8.1.2 Steam Generator Secondary Side circumferential Head Welds Each steam generator includes 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 Attachment 4. 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 Generetor Secondary Sidt Tubesheet-to-Shell Wald Each steam generator includes a tubesheet-to-shell weld. The entire length of one tubenheet-to-shell weld shall be ultrasonically examined during the inspection interval in accordance with Table B of Attachment 4. The weld selected for examination may be f rom ths generator selected for examination by Section 8.1.1 The tube plate is a SA-508, Class 2, steel forging. 1401C/COC3
SI-114.2 SURVEILLANCE' ASME SECTION XI R visita 19 INSTRUCTION INSERVICE INSPECTION PROGRAM P g3 41 ef '116101 nit (O f4E-8.1.4 Ettaa_ERDerator Second.gry Side Norrle-to-Ves.sel Welds-and
, Hstrie-to-Vessel Inside Radius i,
Each steam generator includes one feedwater nozzle (3.62 inches nominal vall 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 Attachment 4. 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 (References CAQR CHS 900013). This weld shall be ultrasonically examined in accordance with Attachment 5. See Section 8.14. The nozzles are fabricated of SA-508, Class 2, steel. 8.1.5 Steam __ Generator Secondary Sidu,Iny grally Welded Suppgit Attachmen_tn There are no integrally welded vessel support attachments. 8.1.6 Eteam Generator Secondary Side Component _ Supports There are no component supports (including mechanical and hydraulic supports) which require examination. B.1.7 Steam Generator Secondary Side Pressure Retainino Boltino Exceedino 2 Inches in Diameter There is no steam generator stcondary side bolting exceeding 2 inches in diameter. 8.2 RHR ligat Exchanggrs (2) - RU3)]X 8.2.1 FHRHX Circumferential Welds 8.2.1.1 FHRHX Shell Circumferential Weld There is one circumferential shell weld located at a gross structural discontinuity.on each RHREX. The entire length of this shell weld from one heat exchanger shall inn u? trasonically examined during each inspection interval in accordance with Table B of ' Attachment 4 (see Request for Relief ISI-16). The RERHX shell section is f abricated from SS, SA-182..F304. 1401C/COC3
p 5 k < SIS 114.2
. SURVEILLANCE. ASHE SECTION XI- R:visic3'19-
;INSTRUCTIONE INSERVICE; INSPECTION PROGRAM- P g3 42 ef'94J )Cl ,
- Asie/p/,( .
8.2.1.2' RHRHX Head Circumferer&lal Weld ,
,i There is one circumfetential head-to-shell weld
_per RHREX. The entiro'longth of one head-to-shell weld shall.be ultrasonically _ examined during~ the inspection _ interval-in accordance with, Table B of-Attachment 4. The weld selected-fori examination may be from 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. B.2.1.3 .RHREX Tubesheet to Shell Weld There are no RHREX tubesheet-to-shell welds. 8.2.2 RHRHX Nozzle-to-Vessel Welda- - The channel cylinder section of each RHREX includes one-inlet-nozzle (14-inch 1ID) and one outlet nozzle-(14-inch-ID) over 1/2-inch nominal thickness; 'A total of fouri nozzle-to-vessel welds from the.two RHREX will be liquid: penetrant examined during the inspection interval.1_The nossle-to-vessel. velds and nossle inside radius sections. will not be ultrasonically exemined~during.the' inspection interval. ~ See' Request forl Relief ISI-13. The nossles.are 2.5 inches thick, fabricated from SS, SA-240,1TP-304. 8.2.3 RHRHX Intecrally Welded Support Attachmgat3 There are;two-integrally; welded support attachments (1-inch) on each RHRHX whose. base. material' exceeds-1/2-inch
. nominal thickness. A total _of:two: support pad-to-vessel welds from the RHREX will be 11guld penetrant examined; during each_luspection: interval-in'accordance with Table B of Attachment.4. The welds selected.for_. examination may be conducted on one heat exchanger and shall cover- 100 percent < ~
of the required area of each sJpport attachment.. , The support pad is_ fabricated from SS,1SA-240, TP-304. 8.2.4 EHRRY Comoonent Suenoett There are two. component supposts1on each RHRHX which'are'in contact with - the vessel.: All component: supports from each- - heat exchanger sha11'be._visua]Iy examined during the? Inspection interval in accordaace with visual-examination method VT-3. - 1401C/COC3.
~
_J
- 51-114.2 SURVEILLANCE ASME SECTION XI R;v101:3 19 INSTRUCTION INSERVICE INSPECTION PROGRAM P093 43 Cf *96-101 AD /2/2//ft ~
This examination includes integrally welded and uonintegrally welded component supports. Component { supports extend.from the heat exchanger _to and including
- the attachment to the supporting structure.
The examinations shall be distributed during'the inspection loterval in accordance with-Table B of Attachment 4. There are no mechanical (snubbers) and/or hydraulic (shock absorbers) supports which.are in contact with the vessel. 8.2.5 RHRKX Pressure Retninino Boltine Exceeding 2 Inches ID DinmeteI There is no RHREX bolting exceeding 2 inches in diameter. 8.3 Engenerative Heat ExchanatI Section 8.3 has been deleted from this program in accordance with IWC-1720 (c) of ASME Section XI. See Request for Relief ISI-12, 8.4 Excess Lgtdown Heat Exchancer 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))- (One) NOTE: The CCP tank was formerly identified as the BIT tank. This change occurred in Unit 2 Cycle 4 refueling outage. As a transition, both ids are being -retained for traceability. 8.5.1 CCP Tank (BIT) Circumferential Shell and Head Welds There ero two circumferential head-to-shell welds located at structural discontinuities on the CCP Tank. These welds shall be ultrasonically examited during the inspection interval in accordance with Teble B of Attachment 4.' The , examination shall cover 100 percent of the weld length. The head and shell are SA-264 material consisting of 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 There are two nozzles, one located on each head with a 6-inch inside diameter whose nominal thickness (2.00 in.) is greater than 1/2 inch. These nozzle-to-vessel welds shall be ultrasonically and sveface examined during the inspection interval in accordance with Table B of Attachment 4. The examinatior shall cover 100 percent of the weld length.- l The nozzles are fabricated to SA-350, LT2. 1401C/COC3'
SI-114.2 SURVEILLANCE ASME SECTION XI' P.cvicica 19-INSTRUCTION INSERVICE INSPECTION PROGRAM P;g) 44 of'9&,lol 0KS tzfn/4t 8.5.3 CCP Tank (BIT) Intearelly Welded Suonerts i There are;four integrally welded support attachment pads wolded to the shell, whose base material design thickness is 5/8 inch and_ therefore requires surf ace examination in accordance with Table IWC-2500-1 of ASME Section XI. 8.5.4 CCP Tank (BIT) Component Suonorts There are four component supports associated with the CCP tank. All of these supports shall be visually examined (VT-3) durirg the inspections interval in accordance with Table B of Attachment 4. 8.5.5 CCP Tank (BIT) Pressure Retainino Boltina Exceedina 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 interval in accordance with Table B of Attachment 4. The studs may be examined in place under tension or when they are removed. It is-preferable to. perform the examinations when the studs are removed. 8.6 UHI Water Accumulgt,gt Section 8.6 has been deleted from this program in accordance with IWC-1220 (a) of ASME Section XI. This component has also been removed from service. 8.7 UHI Surce Tagh Section 8.7 has been deleted from this program in accordance with IWC-1220 (a) of ASMI Section 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 Pipino Material specifications for each pipiu; system are stated on the weld map isometrics. The following Class 2 piping systems are
~
subject to examination: Residual Heat Removal (RHR) Safety Injection (SI) Main Steam (MS) Feedwater (FW) Containment Spray (CS) Upper Head Injection (UHI) - Ine UHI system was removed from service during Unit 2 Cycle 4. For reference to the schedule of examinatloas-performed on this system, see Revision 14 of this instruction. 1401C/COC3
l . SI-114.2-S11RVEILLANCE ASKE SECTION XI R; visits 19-INSTRUCTION INSERVICE INSPECTION PROGRAM Page 45 of 11L lot 8.9.1 Elpino and Valve Inteorally Weided Suenort Members GCS }9L a zize $ Integrally welded support members include the support attachments of piping required to be examined by Examination Category C-F. Included are those supports which have attachment welds to the valve and piping ' pressure retaining boundary, and those attachments whose support base material desion thickness exceeds 3/4 inch (see PRISIM data base). The entire length of each support attachment weld selected for examination shall be surf ace 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 accorda.1ce with Table B of Attachment 4 (see Request for Relief ISI-17). 8.9.1.1 Eg2] dual Heat Removal System fleing and Valve Integrally Welded Support Members The Residual Heat Removal System piping does not include any integrally welded support members. 8.9.1.2 Safety Iniection System Pipino and Valve Inteorally Welded Svocort Members The Safety Injection System piping includes integrally welded support members. All of these shall be examined during the inspection interval in accordance with Table B of Attachment 4. 8.9.1.3 Main Steam System Ploina and Valve Inteorally Welded Support Members The Main Steam System piping includes integrally. welded support members. All of these shall be examined during the inspection interval in accordance with Tabla B of Attachment 4. 8.9.1.4 Feedwater System Pirino and Valve Inteorally Welded Suncort Members The Feedwater Systen piping includes integrally. welded support members. All of these shall be examined during the inspection interval in accordance with Tab 13 B of Attachment-4. 8.9.1.5 Containment Spray System Pip [no and Valve Inteorally Welded Sucoort Members The Containment Spray System piping does not include any integrally welded support members. 1401C/COC3
SI-114.2
, SURVEILLANCE ASME SECTION XI R; visit: 19 INSTRUCTION INSERVICE INSPECTION PROGRAM P:ga 46 cf 1HL 101 0PS tiltel9s 8.9.2 Pipino and Valve component Surports l 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 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 verifie$ in accordance with the applicable NDE procedure with the acceptance criteria shown in the Sean 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 B of Attachment 4. 8.9.2.1 Residual Heat Removal-System Pipino and Valve Component Suenorts 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 Attachment 4. 8.9.2.2 gafety Iniection Syniem Piping and Valve Component Suecorts The Safety Injectior System piping includes component supports. All of these shall be-examined during the inspection interval in accordance with Table B of Attachment 4. 8.9.2.3 Main Steam System Ploine and Valve Component Suonorts - The Main Steam Syste.a piping includes component supports. All of these shall be examined during the inspection interval in-accordance with Table B of Attachment 4. B.9.2.4 Feedwater System Plytno and Valve Comeonent Suoverts The Feedwater Systen piping-Ancludes component. supports. All of ttise shall be examined during the inspection intez<a1 in accordance with Table B of Attachmett 4. 1401C/COC3
- 51-114.2 SURVEILLANCE' ASME SECTION XI R visien 19 INSTRUCTION- INSERVICE INSPECTION PROGRAM Page 47 of 96 loj.
OCS1 3l tift 2 _ 4 8.9.2.5 Containment Sorav Syptem P12 ]ng and Valve-
.. Component Supports i
The Containment Spray System piping includes component supports. All of these shall be examined during the inspection interval in
, accordance with Table B of Attachment 4.
8.9.3 Pressute-Retainino Boltino There is no Class 2 Pressure-Retaining Bolting larger than two inches in diameter. 8.9.4 CircumfeIgntial and L2Rgitudinal Pine Helds Selection of welds for examination 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 inspection interval and distributed in accordance with Table B of Attachment 4. The entire length of each weld selected for examination shall be ultrasonically and/or surfaced examined. Circunferential 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 discostinuities, 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 Residual Heat Removal Pinino-The Residual Heat Ramoval-Piping System includes Class 2 circumferential and longitudinal piping welds with a nominal wall thickness greater than 1/2 inch subject to'axamination. The welds selected for examinttion shall be ultrasonically and surfaced examinto each inspection interval in accordance with Table B of Attachment 4. The RER piping system includes the circumferential and longitudinal pipe welds with a nominal wall thickness of 1/2 inch or less. The welds selected for examinacion shall be surf ace examined each inspection interval in accordance with Table B of Attachment 4. i l 1401C/COC3
51-114.2 SURVEILLANCE ASME SECTION XI 'R;visica 19. INSTRUCTION INSERVICE INSPECTION PROGRAM Ptg3 48 of-NL Jol
$U lt)ttf42, 8.9.4.2 Safety Inicetion Plulna l[ The Safety Injection piping System includes Class 2 circumferential piping welds with a nominal wall thickness greater than 1/2 inch subject to examination. The welds selected for
' examination shall be ultrasonically and surface examined each inspection interval in accordance with Table B of Attachment 4. The safety injection piping system-includes the circumfer- ,tial and longitudinal pipe welda with a nomina 7 all thickaess of 1/2 inch or less. The welds selected for examination shall be surf aced examined each inspection interval in accordance with Table B of Attachment 4. 8.9.4.3 Main Steam Ploino 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 longitudin,a1 piping welds selected for examination shall be ultrasonically and surfaced examined each inspection interval in accordance with Table B of Attachment 4. There are no circumferential and longitudinal pipe welds with a nominal wall thickness of 1/2-inch or less in the Main 4 team System. 8.9.4.4 Feedwater Pining The Feedwater Piping System includes Class'2 circumferential and longitudinal piping welds with a nominal wall thickness greater than 1/2 luch subject to' examination. The circumferential and'1ongitudinal piping welds-selected for examination shall be ultrasonically and surf aced examined each inspection interv.1 in accordance with Table B of Attachment 4. 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. 1401C/COC3
SI-114,2 SURVEILLANCE ASME SECTION XI R;vicien'19
-INSTRUCTION INSERVICE INSPECTION PROGRAM Pcg3 49 cf '94. /0/
ses selvht-8.9.4.5 containment Sorav PJoina js ' 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 circumferential and longitudinal pipe welds selected for examination shall be surface examined each inspection interval in accordance with Table B of Attachment 4. There are no circumferential and longitudinal pipe welds with 6 nominal wall thickness greater than 1/2 inch in the Containment Spray System. 8.9.5 Eranch Ploine Connection Welds There are no Class 2 branch pipe connection welds. 8.10 Pumps 8.10.1 RHR Purnos (2) - RHRP 8.10.1.1 RHRP Integrally Welded Supports There are no integrally welded supports associated with the RHRP. 8.10.1.2 RHRP Suenort Comoor.ents Each RHRP includes one component support bolted 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 extend from the RHRP to and including the attachment to the supporting structure. Both of the RHRP support components shall be examined during the inspection interval. 8.10.1.3 RHRP Suuports - Mechanical or Hydraulle There are no mecha:lcal or hydraulic supports-associated with the RHRP. 8.10.1.4 RHRP Pressure Retaj=ino Boltino The stuffing box extension to pump casing connection bolting is not greater than two inches in diameter. The connection includes 24 studs at 1-1/4 inches-in diameter with nuts and washers. The studs' are fabricated to SA-193, GR. B7, and the nuts to SA-194, GR. 2H. 1401C/COC3
SI-114.2 SURVEILLANCE ASME SECTION XI R;visign'19 INSTRUCTION INSERVICE INSPECTION PROGRAM P gi S0 cf'9a,jol OCS ttfitht. 8.10.1.5 EHRP Casino Welds i The RHRP does not include an} casing welds.- The I casing is a one ple:e forging fabricated to SA-182 F304. 8.10.2 ,CVCS Centrifuoal Charoino Pumps (2) CCP 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. 8.10.3 CVCS Positive Displacement _Pumofli PDP/Reciprocatino. Charoino Pumo Examination of these pumps, and their associated component supports, pressure retaining bolting, and casing welds are exempted under previsions cut'ined in table IWC-2500-1 and accompanying footnotes, ex.ni ation 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 Pumos (2) SI? 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 eram requirensnts to components in piping examined under examination entegory C-F. 8.11 Valven Systems including ASMI Code Class 2 valves subject to examination are identified in Section 8.9. A tabulation of valves is presented in Attachment 2. 8.11.1 Valve Inteorally Welded Suoverts Examination of valve integrally welded support members is included in Section 8.9.1. 8.11.2 Valve Comeonent Supperta Examination.of valve component supports is included in Section 8.9.2. 8.11.3 Valve Pressure-Retainino BoltLng There is no Class 2 pressure-retaining bolting greater than 2 inches in diameter. 1401C/COC3
SI-114.2 SURVEILLANCE ASME SECTION XI R2vition 19 INSTRUCTION INSERVICE INSPECTION PROGRAM P ga 51 of '98- lol 00$ ll{tIl9L B.11.4 Valve Body Welds ', There are no Class 2 valves with body welds. 8.12 Eyltem Pressure Test All ASME Code Class 2 (equivalent) system pressure tests shall be in accordance with SSP-8.5. 8.13 Emp_ted Comtanents 8.13.1 EAgapted components (Excent Pipina Weldal 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 above a temperature of 200'F; or (c) component connections (including nozzles in vessels and pumps), piping at6 associated valves and vessels (and their supports) that are 4 inch nominal pipe size and smaller. 8.13.2 Exempted Components (Pinina Kelds Only) Piping exempted from examination includes (a) Piping systems where 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 Successive Examinations Components with flaw indications evaluated in accordance with IWC-3000 and SSP-3.4 that qualify for continued service shall be reexamined during the next inspection period listed in the 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 examir ation schedule is dictated by an augmented inspection requirement. Components requirJng successive examinations shall be scheduled for examination in accordance with Attachment 5. 6 1401C/COCS
SI-114.2 SURVEILLANCE ASME SECTION XI- R:visica 19
-INSTRUCTION INSERVICE INSPECTION PROGRAM p:ga 52 of 'St/pl k' sit ltI{n 9.0 CQ&QHENTS SUBJECT TO EXAMINATIQN - ASME CODE CLASS 3 fEOUIVALENT)
(. ALME Code Class 3 (eguivalent) component supporte and restraints within i the 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. Mechanical and hydraulic snubbers, spring loaded and constant weight supports within the boundaries identified in 6ection 9.1 for components exceeding 4-inch nominal pipe size shall be visually examined, VT-4 during each inspection period. 9.1 Ploing and Valve Component _ Supports All piping and valve component supports shall be visually examined during each inspection period in accordance with visual examination methods VT-3 and VT-4. This examination includr.a integrally welded and nonintegrally welded component supports. Component supports extend from the piping and valves to rad including the attachment to the supporting structure. Tae setting of snubbers, shock absorbers and spring-typo 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 the inspection interval in accordance with Table C of Attachment 4. 9.1.1 Auxiliary Feedwater System Ploino and Valve Comoonent Suonerts The Auxiliary Feedwater System piping includes component supports. All of these shall be examined during each inspection period in accordance with Table C of Attachment 4. 9.1.2 ChAE1Ea1 and Volume Control System Pipino and Valve Comoonent Suenorts The Chemical and Volume Contaol System piping component 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 Campanent Coolino System Pipino and Valve comoonent Supports The Component Cooling System piping includes component supports. All of these shall be examined during each inspection ptriod in accordance with Table C of Attachment 4. 1401C/COC3
61-114.2 SURVEILLANCE ASME SECTION XI R visitu 19
' INSTRUCTION INSERVICL INSPECTION PROGRAM - P g) 53 of 44.lol Os refeln 9.1.4 Containment' Spray System Pipj;g[ nnd Valve Component 522291.LA
, The Containment Spray System piping has no component supports. (The change in support numbers during the second period was due to new class boundaries.) 9.1.5 Essential Raw Coolina Water Efstem Pipino and Valve Opmponent Suoports The Essential Raw Cooling Hater System piping includes component supports. All of these shall be examined (nring each inspection period in accordance with Table C of Attachment 4. 9.1.6 Eyel Pool Cooling System Pipino and Valve Component Supports The Fuel Pool Cooling System Piping component supports are examined in accordance with SI-114.1, Unit 1 Program. 9.1.7 RHR System Ploina and Valve Component Suenorts 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 Ploina and valve Comoonent Suenorts The Safety Injection System piping has no component supports. (The change in support numbers during the second period was due to new code class boundaries.) 9.2 Eguipment Comoonent Supports The equipment component support and the associated integrally welded support attachment will be (VT-3) examined together, 9.2.1 Containment Sprav Heat Exchancer (2) Support - CSH (ERCW) There is one component support on each CSH. These supports shall be (VT-3) examined duri.rj the Inspection interval in accordance with Table C of Attachment 4. 9.2.2 Nonrecenerative Letdown Heat.Txchancer (1) Supeort - NRLHX (CCS) There is one component support on the NRLHX. This support shall be _(VT-3) examined during the inspection interval in accordance with Table C of At tachment 4. 1401C/COC3
87-114.2 SURVE1*,tANCE ASKE SECTIOi! XI R;visie3 19 INSTRUCTION - INSERVICE INSPECTION PROGRAM p:g3 54 of'94,/of Ofs Itlttl1z i 9.2.3 Qag_,1tI1pper and Boric Aeld F,.egppIntor i11 - CSfAK,,{Cfil 9.2.3.1 GEBAE Evangrator cond t nger (1) Support - EC There are two composent supports on the EC. These supports shall be (VT-3) examined during the inspection interval in accordance with i Table C of Attachment 4. I 9.2.3.2 GSD.AE_Ritt,iMate coolor (Dhort - DC (CCE) There are two compoaent supports on the DC. These supports shall be (VT-3) examined during the inspection interval in accordance with Table C of Attachment 4. 9.2.3.3 GSRAK_Yent cooler Eupp2I.t (1) VC fCCS) There are two compo1ent supports en the VC. These supports shell be (VT-3) examined during the inspection inte. val in accordance with Table C of Attachment 4. 9.2.3.4 GSDAt Eupport Frage_11) - SF (CCB) The SF consists of one component support. This support shall be (VT-3) examined during the inspection interval in accordance with Table C of Attachment 4. 9.2.4 Comp.pnent coolino_Eurge Taph f1) Suppnrt - CCST (CCS) There is one component supporc on the CCST. This support
- shall be (VT-3) examined during the inspection interval in accordance with Table C of Attachment 4.
9.2.5 C9222ntat cooliner SyAtem Positive Displacement Ch&Ining Egnp_QJ1 Coolgr (1) Supeort - PDOC (CCS) There are two component supports on the PDOC. These supports shall be (VT-3) examined during the inspection interval in accordance with table C of Attachment o.. 9.2.6 Component cooling.,,}fater gig 33,_Eg11gd Fuel Detector f1) Eypport - GFFD (CCS) There is.one component support on the GrTD. This support shall be (VT-3) examined during the inspection interval in accordance with Table C of Attachment 4. 9.2.7 Centtiingal_shargina Pump Gear 011 Cooler (2) Support - CCPGOC (ERCH) There are two component supports on each CCPGOC. These supports shall be (VT-3) exmnined during the inspection - interval in accordance with table C of Attachment 4.. 1401C/COC3
[- . 51 144.2 SURVE!LLANCE ASME SECTION XI 3 Visit 3 19 3HSTRUCTION INSERVICE INSPECTION PROGRAM P:g) 55 o' M lOf s% lift), Int-9.2.8- C3ALIljagal Charoine Pump 011 Cooler (2) SupporL- CCPDC f2RCW) a-
- [ There are two component supports on each CCPOC. These supports shall be (VT-3) examined during the inspection laterval in accordance with Thble C of Attachment 4.
l-9.2.9 )fatte cas comprestar Heat Exghanggr (1) Eupport - WCC)g LCC11 There are two componert supports on the WGCHX. These supports shall be (VT-3) exara'.ned during the inspection interval in accordance with Table C of Attachment 4.
, -l 9.2.10 CentrifugaLCh&I.gino Pume Mechanical Real Cooier (41 -
Sypport - CCPFJC fCCE) There is one component support on each CCPMSC. -These supports shall be (VT-3) examined durit.g the inspection-Anterval in accordance with Table C of Attachment 4. 9.2.11 RHR Pump-Seal' cooler (2) EupItort RHESCJ.CC11 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 Attachment.4.
, 9.2.12 SaftlyJ njection Pumo 011-Cooler (2) Egypsrt - EIPOC (ERClu-There are two component supports on each SIPOC. These supports shall be . (VT-3) exar:Aned during the inspection interval in accordance with Table C of Attachment 4.
9.2.13 Safety injection P,ggo Esal egoler (4) Eupport SIPSC fERCW) There is-one component support on each SIPSC. These supports.shall be (VT-3) enamined during the inspoetion interval in accordance with Table C of
Attachment:
4. 9.2.14 Engpangnt Coolino Eyetem Sea 1 3ater_ Heat Exchanaer_,(.1,1 Suonert - EWHX fCCEl-There is one component suppor: on the SWHX. This support shall be (VT-3) examined-during the inspection intertal in accordance with Table C of Attachment 4. 9.2.15 - Component coolino Syltem Thainal Barrier Bootter Pume_,{11I. Cupport - TBBP fCCEl-There ats two component' supports on each TBBP. - These supports shall be (VT-3)-exa. tined during the inspection interval in accordance with Jable C of. Attachment 4.: 1401C/C003
61-114.2 SURVEILLANCE ASHE SECTI0tt XI R visita 19 IllSTRUCTIOlt IllSERVICE !!1SPECT!Ulf PROGRAM peg) 56 cf % /cf blS IZltif47 9.2.16 Iggbine Drlyen Augillary A drater Pump (1) EurPAIL :: TDArP (ArW1 These are two component supports on the TDAPp. These supports shall be (VT-3) exam.ined during the inspection interval in accordance with Thble C of Attachment 4. 9.2.17 Bator Driven Auxillaty reedwater Pump (2) E up.P2 r t - PDATP 1hfM1 There are two component supports on each MDAPp. These supports shall be (V1-3) examined during the inspection interval in accordance with Table C of Attachment 4. 9,2.18 CaltpADRALCAD1 lag. lyltem Weter Pwers (3) Support - CCEHE LCCEl There is one component support on each CCSWP. These supports shall be (VT-3) examined during the inspection interval in accordance with Table C of Attachment 4. 9.2.19 Ct.mnonent Coolina Heat Exchangit_{2.)._$2pport - CCirX f CCS) There is one component suppor on each CCIIX. These supports shall be (VT-3) examined during the inspection interval in accordance with Table C of Attechment 4. 9.2.20 Eigential Raw Cooling Enter Evstem Etrainer (21 Suonert - EP.CHS ..iXRCH1 There is one component support on each ERCWS. These supports shall be (VT-3) exan tned during the inspection interval in accordance with Table C of Attachmen*. 4. 9.2.21 Egagntlai Raw Coolina Water Eystem Puto Station Pump Supports These supports are examined in accordance with SI-114.1, Unit 1 program. 9.2.22 fue] Pool Coolina And Cleaning _. System - S. pent Puel Plt Pumps These supports are examined la accordance with SI-114.1, Unit 1 Program. 9.2.23 Egel Pool coolina And cleanita system - Spent ruel Pit Heat ExEhADSAI These supports are examined in accordance with SI-114.1, Unit 1 Program. 1401C/COC3
51-114.2
, SURVEILLANCE ASME SECTION XI R3visies 19 INSTRUCTION INSERVICE INSPECTION PROGRAM P:ga 57 cf'tt,/of Ors idadet 9.2.24 EHR_ lit.AL_EEchfager Secondary Side (2) Supports - PHRHSXH 3
NN \ t There are two component supports on each PHRHSHX. These supports shall be (VT-3) examined during the inspection interval in accordance with Table C of Attachment 4. 9.2.25 EPCW Screen Wash Pump 52222I1 These supports are examined in accordance with SI-114.1, Unit 1 Program. 9.3 Sy1LtELEmanIe Tests All ASME Code Class 3 (equivalent) system pressure tests shall be in accordance with SSP-8.$. 10.0 AUIll0RIZED_IESfICIQE TVA shall employ an Authorized Inspection Agency in accordance with ASME Section XI for inservice examinations, repairs, and replacements of ASME Code Class 1, 2 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 pot. TVA shall provide access for the Authorized Inspector (s) in accordance with IWA-2140 of ASME Bection XI. TVA's interface with the Authorized Inspector for ISI, Repairs and Replacements is defined in STD-6.10 and SSP-6.9. 11.0 IDLAMlHATION. METHODS _ AND CALIBRATION BLOCKS la.1 ExaminAtlen Methods RDE examinations shall be performed la accordance with this program as scheduled in Attachment 4, the applicable Scan Plan, QMP-102.4, and QMP 110.5. Requiremerts 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 code exam cannot be performed, the f act shall be documented on the data sheet, and a bsst effort examination shall be performed. ASME Section XI Programs shall be informed in writing of the limited exam. Data must be provided on the eram sheet su as to determine the percentage of the eram done. 11.2 Calibration Blocks Calibration blocks will be used for ultrasonic examinations (a calibration tube will be used for edJf current examination of steam generator ' tubing). The blocks elli be fabricated to the. general requirements of ASME Section V and ASME Section XI. The blocks shall be f abricated of the mat arla1 to be examined or equivalent P numbers. Mill test repcrts shall be obtained and 1401C/COC3
SI-114.2 SURVEILLANCE ASME SECTION XI R' visit 2 19 /o/ INSTRUCTION INSERVICE INSPECTION PROGRAM Pcg3 58 cf ,9ff wl 44-mMn retained by ISO for all calibration b3ocks. The blocks shall employ drilled holes and/or notches for calibration reflectors {' (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 maintained by S00 personnel. 12.0 OUALIFICATIONS OP NDE PERSDEHIL Personnel performing NDE operations shall be qualified in accordance ' with IWA-1600, IWA-2300, and Table IWA-1600-1 of ASME Section XI 1986 Edition as required in OMP 102.4. 13.0 ACCEEIANCE CRITERIA All acceptance standards for ASME Ccdc Class 1, 2, and 3 (equivalent) components shall be in accordance with IWA-3000, IWB-3000, IWC-3000, or 1ND-3000 of ASME Section XI, except where ASME Section III examinations are employed to satisfy ASME Section XI requirements. 14.o EEPAIRS.AND REPLACEMEEIS All ASME Section XI componente and their supports (ASME Classes 1, 2, and 3) shall Le repaired and replaced in accordance with the Repair and Replacement Program implemented by SSP-6.9. ASHZ Section XI repairs and replacements may be coordinated as necessary with ASME Section XI Programs. 15.0 PUMP _AND VALVE TESTING Pump and valve testing shall be in accordance with SSP-8.6. 16.0 RECORDS _AND REPORIE 16.1 Erygir_and Replacgpent Reports Repair and Replacement Form HIS-2 reparts shall be prepared in accordance with SSP-6.9. 16.2 Report for ISI of Clag i and 2 Camp,qntatt-500 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 in accordance with 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.
- 3. Rame and address generating plant.
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_ _ _ _ _ _ _ . - _ - _ - _ _ - - - _ - _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ - - - - ~ - - - - - - - - - ~ ~ ~ - ~ ~ - -
' 51-114.2 SURVEII.t.ANCE ASME SECTION XI R3 vision 19 INSTRUCTION INSERVICE INSPECTION PR) GRAM P ga 59 cf b /Of
>cs izin/u I
- 4. Name or number assigned to the nuclear power unit by TVA.
i 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. National Board Number assigned to the components by the manufacturer.
- 3. Names of the components and descriptions including size, cepseity, material, location, and drawings to aid identification.
- 4. Name and address of principal manufScturer (e.g.,
Westinghouse, GE, etc.) and the principal contract number which will identify the subcontra: tors. Manufacturer's component identification numbers.
- 5. Date of completion of the examina:lon.
- 6. Name of ANII who witnessed or otherwise verifjed the examinations and his employer and business address, when required.
- 7. Abstract of examinations, conditions observed; and corrective measures recommended or taken.
8 Signature of ANII, when required.
- 9. Owner's Data Report for ISI, Form HIS-1, as shown in Appendix II, of ASME Section XI and Forms NIS-2 as identified above in Section 16.1.
500 shall submit the Inservice Inspection Report to the plant manager for retention as part of the final report discursed in Section 16.3. 500 shall submit applicable summaries of the report with a cover sheet as described above'to the NRC via SON Site Licensing. 16.3 Site Final RepoJA A detailed report of all examinations shall be epared by S00 l (and/or the performing or responsible organisai on) and should contain, but not be limited to, - the 1311owing i . formation Cover Eheet - Data Sheet 1 in Appendic B will t>e corrpleted and used as a cover sheet for the Site Final Report and to document the review process. Table of Contents I. Introduction - The introduction should include the following information: Planc, unit number, PSI or ISI and cycle number, systems, componants and vessels examinations 1401C/COC3
52-114.2 SURVEILLANCE ASHE SECTION XI R:visics 19 ' INSTRUCTION INSERVICE INSPECTION PROGRAM P:g) 60 cf 14L /0/ I OWS ltltll4E , were performed on, organisation examinations were performed by, dates examinations were performed, ASKE l~ Section XI Code of Record. i s
!!. Summary - The summary should include a brlef 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 dia:repancy and its location. It should also contain the final disposition including a reference to the corrective action taken and the date of ' completion. IV. Examination Plan - The Examination Plan shall give a detailed description of all areas subject to examination during the inspection. It should contain the following information Examination Area, Code Category, Wald Sise, Reference Drawing, Examination Method, Procedure, Calibration Block, date of examination and result of examination. V. Summary of Personnel Certifications VI. Calibration Sheets VII. Ermninstion Data Sheets VIII. Copy of the ISI Report as Discussed in Section 16.2 All procedures 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 significant changes. All required and pertinent information will be recorded on the appropriate data sheets by the performing organisation. When portions of the inspection work are cantracted, a detailed report will be submitted to TVA by the contractor with all pertinent and required information. TVA will retais 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 Progtam," for retention as a quality assurance record in accordanca with SSP-2.9, " Records Management." 16.4 Records for ASME code class 1, 2 and 1 (Eculvalent) The following records are QA Records and shall be retained in accordance
- 1. Site Final Report - SSP-2.9
- 2. NDE Procedures - QMP 110.5
- 3. Calibration Block Drawings - QMP 105.4 ,
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81-114.2 SURVEILLANCE ASME SECTION XI R3vimien 19 INSTRUCTION INSERVICE INSPECT 20H PROGRAM Pega 61 of % /of f OCs jg{gyqg The following drawings are retained aa QA recordat i 1. ASME Section XI Boundary Classification Drawings
- 2. ASME Section XI ISI Drawings 16.5 Regnion of System Preature Tests Records of the visual examinations conducted during system leakage or hydrostatic tests shall consist of an itemisation of the number and location of leaks found in a system and the corrective actions taken.
16.6 AugacattLIxelnation RegntLa for specific details on records, reports and reporting see Section 20.0, Augmented Inspections. 16.7 glatu.p of Completed EEA31DA11211 ISO maintains a computer based status listing (PRISIM data base) of the examinations completed for ASME Section XI credit for examinations performed during the inspection period and interval. This listing as a minimum identifies the component examined, ASME class, examination method, and outage cycle when the examination was performed. This listing may also be used to identify components to be inspected in the future. 17.0 EQTlflCATION_OF INDICAT1QJf 17.1 The Notification of Indication (NDI) form in Appendix C of this program is to be used tos'(1) notify ?lant Management of an Indication found during-the performance of scheduled ISI examinations that will require evalue:lon and a disposition in accordance with plant procedures, (2) notify ASME Section XI Programs that an indication that exceods the acceptance criteria of Article 3000 of the ASME Section XI Code has been documented on an examination report form contained eithin the NDE procedure used for examination, (3) provide ISO and 500 with a method to track exan.ination 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 ASME Section XI prcgrams.a method of determining if additional Code examinations are a equired. 17.2 Functionally an NOI Form shall be initiated and processed as follows. 17.2.1 Part 1 of an N01 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 N01 Torm. The Fleid Supervisor, in the case of contracted examinations, will review the information in i 1401C/COC3
,. SI-114.2-SURVEILt.ANCE ASME SECTION XI ROvisi@3 19 INSTRUCTION -INSERVICE INSPECTION P30. GRAM P g3 62 et 101 I !
I Part ! and sign and date the NOI Form as approving the-information. The 500 Representative will review for . l accuracy, sign, and date the .10I Form.
}
l'. 17.2.2 After completion of Part I, S?O shall' send the. original NOI Form and a copy of the Examination Report to Site ( l
' Engineering as a r.otification 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. 500 shall also send a copy to ASME Section XI Programs as notification that a potential exists for additional examinations to be performed per ASME Section XI. -
17.2.3 Site Engineering shall be responsible _for evaluating and. providing a disposition for the indication in accordance . with plant procedures. The disposition shall be . documented in detail on an administrative control' program ; document (PER, FIR, SCAR, WR/WO, etc.) if required by. Section 18.0. , 17.2.4 Site Engineering shall include the' final disposition on the NOI Form in Part II, sign and date the N01 Form,-and return the original to the SQ3 Representative. Reference- - to any PERs, FIRS, SCARS, WR/40s, etc., shall be 31uded. , 17.2.5 The 500 Representative shall immediately, upon receipt, provide a copy of the.N01 roam bearing the recorded disposition to ASME Section ).I Programs for determination of additional examination-requirements. 17.2.6 Upon notification from ASME Eoction XI Programs', the 500- ' Representative shall' check "3es" or "no" for additional examinations, and he shall close'the N01 Form in Part 111 by reexamination, in the case where work was performed at ~ a part of the disposition, or by verification of the disposition if.no physical wtrk was required to remove or modify the indication. 17.2.7 The original NOI Form shall 1e' filed with the original examination report. 'A copy of the form shall'be_sent to. ASME Section XI Programs for closure of their flies. The -f reexamination report,~if applicable, shall reforence-the NOI number. The N01 Form sha11 reference the_ - reexamination report number., 17.3 Moltional Eamole Eelection for ASME CODE CLASE 1 ' AND 2 KQh Af ter an NOI- has been dispositioned a nd returned to the 500 representative, a copy shall be forwt.rded to ASME.Section XI-Programs for evaluation;to determine if. additional' examinations shall be required. If it_is determined that additional- 1 examinations:are required,'these examinations-shall be performed-- during the same outage as the. initial examinations. A1 sample is-defined as those items (welds, areas.._or parts)Las described or- ; intended in__a particular examination category and_ item number and '
'1401C/COC3
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l SI-114.2 l SURVEILLANCE ASME SECTION XI R: visit 2 19 l INSTRUCTION INSERVICE INSPECTION pf." GRAM p:g) 63 of 101 within the same system. For component support samples, the
, additional examinations may also be limited to component supports I within the same extamination method (VI-3, and VT-4). The initial ; sample is the sample scheduled for examination at a particular outage for Section XI credit. For steam generator tubl.ng, additional samples shall be per Sect 1)n 7.3.8.
17.3.1 Evaluation For rirst AdditlenAl ShPPJA A first additional sample she'.1 be selected for those examinations performed in the initial sample that reveal indications exceeding the corresponding acceptance standards of INX-3000 of ASMT Section XI. The first additional sample shall inclujo approximately the same number of items examined in the initial sainple. The first additional sample shall be so".ected from the ten year interval samplo. The items JJ1ected should be from those items that have the longest strvice time from its previous inservice examination. 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 scieduled for examination this outage, this system sample sl:all be evaluated to determine if it should be examined this outage to provide a representative sample from each system within a particular examination category and iten number. This evaluation should consider, but is not Jimited to, the type of indication found in the initial sample and similar system design and operating parameters. The ASME Section XI programs representativo shall submit the additional sample to the 300 Representative for addition to the scan plan. 17.3.2 Evaluation for Seggnd Addit 1CdEREPl1 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 1HX-3000 of ASMt Section XI. The second additional sample shall inc1tde all the remaining items of the ten-year interval sample not examined in the initial or first additional sample dtring this outage. If no items remain in the ten year interval sample (e.g., Accelerated Field Held prograe) and indications were found in the first additional samp;e, a notification of sample results shall be made to Site Engineering as described in Section 17.3.3. The ASME Section XI programs representative shall submit t he second additional sample to the S00 Representative for addition to the scan plan. l l i, 1401C/C0C3'
SI-114.2 EURVEILLANCE ASME SECTION XI R;visics 19 INSTRUCTION INSERVICE INSPECTION PR) GRAM Pag) 64 cf 101 17.3.3 Notificatisn of sap 2 e1 Pesults to site Engineering ( After completion of the second additional sample examinations, ASME Section XI code requirements for additional examinations are complete. If examinations performed in the second additional sample reveal indications exceeding the corresponding acceptance standards of IHX-3000 of ASME Section XI, Site Engineering shall be notified. Site Engineering shall be notified to evaluate the indications and make recommendation (s) for further action, if needed, within this and/or other systems. This notification shall be sent to the Site Engineering Operations Support by ASME Section XI Programs for coordination with the applicable Site Engineering staff. Included in the notification should be a summary of the indications found, number of examinations and number of indications in each sample, type of examination performed, examination category and item number, copies of the NOIs, and any other pertinent information. 18.0 CQJtRECTIVE ACTLON.PROGEAM 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, 19.0 EKQUT&TS FOR.RELlyJ Where TVA has determined that certain code requirements or examluations are impractical, TVA vill 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 la this program, and references to particular reg':ects' for relief shall be included. When impractical examination requirements are identified in t he field, ISO shall notify ASME Section XI Programs such that the information may be included in this program and requests for relief may be 7,,repcrad if necessary. Requests for relief shall 13 submitted to the ERC via SQN Site Licensing. SON Unit 2 Requests for Relief are contained in Attachment 3. TVA submitted 14 Requests for Relief (ISI-1 to ISI-14) from Cede requirements. ISI-1, ISI-3 to ISI-6, ISI-E to 151-10, 151-13, and-ISI-14 were granted. ISI-11 was withdrawn, ISI-12 was not needed, and two, ISI-2 and ISI-7, were postponed. For aore detailed information on Requests for Relief, see Safety Evaluation Report, dated February 7, 1991 from T. J. Hebdon, FRC, to 0. D. Kingsley, Jr. (A02 910211 001), and Safety Evaluation Report, drted April 39, 1990, from Susanne Blaci,- NRC, to 0. D. Kingsley, Jr. (A02 900426 00E). Response from NRC on Request for Relief ISI-15 stated that religf is not required during the first 10-year incpection interval. For mote information, see memorandum from T. J. Hebdon, NRC, to Dr. Mark O. Medford, TVA, dated August 31, 1992 (A02 970903 005). 1401C/COC3
. 81 114.2 SURVEILLANCt ASKE SECTION XI R visics 19 INSTRUCTION INSERV2CE INSPECTION PT,90 RAM P g3 65 of 101 TVA has now identified three (3) other arent where code requirements are impractical. These Requests for Relief are identified as ISI-16, -17,
{' and 18. These relief requests were submitted to the NRC with Revision 16 of this program. 20.0 AucMENTED E 4 MIEATIONS Augmented examinations are performed in addition to ASME Section XI code requirements. The augmented examinations may be required by the NRC or be self-imposed by TVA. Typical sources include generic letters, IE
. Bulletins, technical specifications, vendor recommendations, and industry experience. Attachment 6 provides a schedule for augmented examinations.
The responsible organisation or owner shall have technical and administrative responsibility for each augmented examination identified in this section. This responsibility shall include scheduling any examinations through the Site Quality Organ.sation, tracking the status of examinations, and reporting completed en sminations. Responsible organizations requesting inclusion of augmaated examinations in this section shall submit a written request to the Supervisor, ASME Section XI Programs. The written request shall include specific details such as requirement source, identification of comp:nents requiring examination, examination f requency, examination method, examination area / volume, acceptance criteria, types of flaws anticipated, areas of high suspect, probability of failure, and reporting requirements. Copies of the
- written request shall be submitted to ISO and the 500 to facilitate NDE procedure preparation, establishment of training programs, and personnel familiarization.
Prior to each refueling outage, a meeting sna11 be initiated by the S00. Heeting attendees shall include the sosponsible organisations, 500, ISO, ASME Section XI Programs, and Site Engineering. The meeting agenda should include examination plans anf schedules, updates on industry experience, and any additional pertinent information. Following the completion of the augmented esamination, the S00 shall report to the responsible organization itens such as examination results and changes in results f rom previous examit stions. The responsible organization shall determine if a meeting vith the 800 and/or other appropriate organizations is necessary to tiscuss items such as additional examinations to be conducted dusing the current outage, trends, lessons learned, and identify any future actions such as changes in the frequency of examination. Augmented examinations that require reporting to the NRC shall be the responsibility of the responsible organisation. i 4 1401C/COC3
SI-114.2 SURVEILLANCE ASKE SECTION XI R:visiC3 19 INSTRUCTION INSERVICE INSPECTION pHOGRAM peg 3 66 of 101 20.1 feedwatgg Nor:1e-to-Pipe Welds and Adjarent Pipe /rlttinos and Nortle ArgA3 { l Responsible Organisations Site Enginesring. SON Huclear Engineering shall be responsible for ensuring the adequacy of the technical and administrative requirements of this section. The requirements of NRC IE Bulletin 79-13 were satisfied during the Unit 2 Cycle 1 outage. Due to the safety-related ramifications and the assessments concluded in Incilent Investigation (II) No. II-S-92-027 of the steam generator no 181e transition section cracking problem and potentia' for cracking in adjacent components within the feedwster piping system, TVA will perform an augmented inspection as determined by Site Engineering. This shall include the four feedwater nozzio transition pieces and associated piping components with inspections being performed during the intervals as listed below. The augmented examination of the steam generator nozzle transition and feedwater piping shall include 100 percent volume of the transition pieces, the nossle-to-transition piece welds, transition piece-to-elbow welds, 4-inch feedwater/ auxiliary feedwater tee-to-pipe welds, and base metal adjacent to each weld for a distance of two wall thicknesses. These welds shall be volumetrically examined by the ultrasonic method and supplemented with radiographic examination when specified by Site Engineering. Ultrasonic acceptance criteria shall be in accordance with ASME Section XI 1986 Edition, and IWC-3514, for Class 2 welds, respectively. The results of the exa nination will be submitted to Site Engineering for evaluation and trending of flaw sizes and growth rates. The results of this ertmination shall be included in the ISI Report discussed in Sectien 16.3. Inspection of the transition pieces, nozzle-to-transition piece wolds, transition piece-to-elbow welds, and the associated base metal shall be scheduled for inspection at each consecutive refueling outage unless otherwise revised or waived by Site Engineering. FEEDWATER H0ZZLE TRANSITION pIEC1 EXAM SCHEDULE Cyrig Examination Areat 1 IE Bulletin 79-13 completed 2 1 nossle-to-pipe weld and a djacent pipe and nozzle area 3 All nozzle transition section pieces and welds 4 All nozzle transition sect 11n pieces and welds S All nozzle transition section pieces and welds 6 All nozzle transition section pieces and welds Inspection of the 4-inch feedwater/aucillary feedwater tee-to-pipe welds and the associated base metal shall be inspected to the following schedule unless otherwise revised or waived by Site Engineering. Loops 2 and 4 are to be inspected each even numbered outage beginning with the Cycle 6 Refue3ing Outage. Loops 1 and 3 are to be inspectei each odd numbered outage beginning with the- Cycle 7 Refueling Outage.
-1401C/COC3
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SI-114.2 SURVEILLANCE ASME SECTION XI R;visics 19 , INSTRUCTION INSERVICE INSPECTION PROGRAN P:gs 67 of 101 l 20.2 RPV E2111e Safe Ends i Responsible Organisations Site Engineering. The augmented ) esamination requirements of the RPV nossle-to-safe end welds are included in the final report "SQN - Evaluation of cracking in reactor vessel nossle stainless steel buttering." TVA reinspected nossles 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 16.3. 20.3 Peactor Coolant Pumo Plywheel Responsible Organisation Site Engineering. Engineering shall be responsible for ensuring the adequacy of the technical and administrative requirements of this section. 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 exposed surfaces (exposed areas are considered as thoss areas accessible for examination without having to remove :he flywheel from the housing) and complete ultrasonic eranination at approximately 10-year intervals during the plant shutdown coinciding with the ISI schedule as required by Section 31 of the ASME Code. This examination is performed in accordance with SQN Technical Specifications and satisf16s Surveillance Requirement 4.4.10a. This augmented examination does not require a special report unless the examination reveals a flaw. If the examination and 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 information to be included. The exanination results shall be included in the ISI Report discussed in Section 16.2. The flywheel consists of 2 plates, approximately 5 inches and 8 inches thick, bolted together. Each plate is fabricated from vacuum degassed A-533, GR. B, Class 1. steel. The 3-year in place RCP examinations shall be recorded using the RCP motor serial number and exam ID: RCP Hotor S/N - BOREKEY (i.e., 45-81P352 - BOREKEY) 1401C/C0C3
SI-114.2 SURVEILLANCE ASKE SECTION XI R; vision 19 INSTRUCTION INSERVICE INSPECTION PROGRAM Pcg3 68 of 101
. Por the 10-year exam, the ids shall bei j RCP Motor S/N - SUR (i.e., 4S-81P352 - SUR)
; RCP Motor S/N - VOL (i.e., 45-81P352 - VOL)
See Augmented Examination Attachment 6 for RCP flywheel scheduled examinations. 20.4 Steam GentIAtor Tubing [C-2) Responsible Organizations Corporate Steam Generator Maintenance and Technology (SGMT). Refer to Technical Specifications Surveillance Requirements 4.0.5 and 4.4.5.0. Each steam generator tube bundle consists of 3,388 NiCrPe 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 methods may be utilized to improve characterisation of an indication but o6cy current shall be utilised to determine 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 steas generator tubes to be examined. 20.4.1 Eteam Generator Sample Selt atign_And inapection Each steam generator shall be determined operable during the shutdown by selecting and inspecting at least the minimum number of steam generators specified in Table 1 of Appendix A. 20.4.2 Steam Generator Tube Samole Selection and Inspection [C.2) The steam generator tube minimum sample site inspection result classification, and tts corresponding action required shall be as specified in Table 2 of Appendix A. The ISI of steam generator ttbes shall be performed at the f requencies specified in Sect ion 20.4.3, and the inspected tubes shall be verified acceptable per the acceptance criteria of Section 20.4.4. The full length of a minimum of S (as defined by Table 2 c2 Appendix A) tubes selected for inspection will be examir ed [TVA commitment to NRC L44 850617 801). Note that the hot leg inspection sample - and the cold leg inspection r ample do not necessarily involve the same tube, (i.e., it does not preclude making separate entries from the hot and cold ' leg side; and [ 1401C/COC3
m SI-114.2 SURVEIbLANCE ASHE SECTION XI R;visica 19 INSTRUCTION INSERVICE INSPECTION PROGRAM pag] 69 Cf 101 selecting different tubes on the het leg and cold leg sides to ' meet the minimum sample). The tubes selected for each ISI shall
}' include at least 3 percent of the total number of tubes in all steam generators; thb tubes selected for these inspections shall be selected on a random basis except
- a. Where experience in simalsr plants with similar water chemistry indicates criti;al areas to be inspected, then at least 1/2 S (as dafined by Table 2 of Appendix A) 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 include:
- 1. All nonplugged tubes that previously had '
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 20.4.4.a.8) shall be performed or each selected tube. If any ,
selected tube does net permit the passage of the eddy current probe for a tube inspection, this
' shall be evaluated and recorded and an adjacent tubo shall be selectal and subjected to a tube inspection,
- c. The tubes selected as the second and third samples (if required by Table 2 of Appendix A) during each IbI may be subjected to a partial tube inspection provided:
- 1. The tubes selected for these samples include the tubes from those aress of the tube sheet array where tubes with imperfections were previously found.
- 2. The inspections include those portions of the tubes where imperfections were previously found.
- d. The results of each samp3 e inspection shall be classified into one of t1e following three categories:
Category Inspq2 tion Resulte C-1 Less than 3 percent of the total tubes inspected are degraded tubes and none of the inspected tubes are defective. 1401C/COC3
$1-114.2 SURVE!bbANCE ASKE SECTION XI R;visSc3 19 1NSTRUCTION INSERVICE INSPECTION PR*4 RAM P g) 70 cf 101 C-2 One or more tubes, but not more than
,. 1 percent of the total tubes inspected I 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 ev'sibit significant (10 percent) further wall 1<nnetrations to be included in the above percentage calculations. 20.4.3 Ingpection PrecugnCign The above required ISIS of stekm generators shall be performei at frequencies indicated in the following paragraphs And in such a manner that the maximum allowable timo between eddy current inspactions on individual steam generators is 72 months.
- a. The first ICI shall be potformed after 6 Effective Full Power Months but within 24 calendar months of initial.
criticality. Subsequent ISIS shall be performed at intervals of not less thar 12 nor more than 24 calendar months after the previous inspection. If two consecutive inspections icilowing service under All Volatile Treatment 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 dsgradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of-once per 40 months.
- b. If the results of the ISI af a steam generator conducted in accordance with Tablo 2 of Appendix A at 40-month intervals fall 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 the criteria of section 20.4.2.a; the interval may then be extended to a maximum of cuce per 40 months.
- c. Additional, snacheduled ISIS shall be performed on each steam 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.
1401C/C0C3
SI-114.2 SURVEILLANCE ASME SECTION XI R0vistc3 19 INSTRUCTION INSERVICE INSPECTICH PH> GRAM Pag] 71 cf 101
- 1. Primary-to-secondary tabea leaks (not including leaks originating from tube-to- tube sheet welds) j in excess of the limits of Technical Specification
. 3.4.6.1.
- 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 lino break.
20.4.4 Agingiance criteria
- a. As used in Section 20.43
- 1. Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings cr specifications. Eddy-current testing indications below 20 percent of the nominal tube wall thickness, if detectable, may be considered as imperfections.
- 2. Degrada11nn means a service-induced cracking, >
wastage, wear or genersi corrosion occurring on either inside or outside of a tube.
- 3. gegfAded Tube means a tube containing imperfections greater than or equal to 20 percent of the nominal wall thickness caused by degradation.
- 4. Percent D.F.2IAdation moins the percentage of the tube wall thickness af fected or removed by degradation.
- 5. Defect means an imperfection of such severity that it exceeds the pluggirg limit. A tube containing a defect is oefective.
- 6. Elu2gina 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. Unggrviceable 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 Earth 7aake, a loss-of-coolant accident, or a steam 31ne or feedwater line break as specified in Section'20.4.3.c. 1401C/COC3
-4
. SI-114.2
, SURVEILLANCE ASME SECTION XI R;visica 19 2NSTRUCT30N INSERVICE INSPECTION PRJGRAM Pag] 72 of 101 i
- 8. Tube Inspectism means an inspection of the steam
. generator tube from the point of entry (hot leg
( side) completely aroual the U-bend to the point of exit (cold leg side) (4.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 dif ferent. tubes are allowed.
- 9. Ettgervice Innvecting (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.
- b. The steam generator shall be determined operable after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 2 of Appendix A.
20.4.5 Pecortino Corporate Steam Generator Maintenance and Technology shall ; be responsible for preparing and submitting the reports. 20.4.5.1 Technical Specificatton Plant management shall report this information to the NRC within the time period specified. See Plant Instruction A1-18 series for reporting instructions,
- a. Tube Plugging Report - Following each inservice-inspection of. steam generator tubes, the number of tubes plugged in each steam generator shall be reported to the NRC within 15 days c f steam generator manway closure.
- b. Inservice Inspec:lon Results Report - The complete results of the steam generator tube ISI shall be sut nitted to the NRC in a special report parsuant to Technical Specification 6. 3.2 within 12 months following comple tion of the inspaction (S/G manway closure). This special report shall include
- 1. Number and txtent of tubes inspected.
- 2. Location and percent of wall-thickness penetration for each indication of an imperfection.
1401C/COC3
, SI-114,2 SURVEILLANCE ASME SECTION XI R; visit 3 19 INSTRUCTION INSERVICE INSPECTION PROGRAM pag 3 73 cf 101
- 3. Identification of tubes plugged. [
l' ' l
- c. Category C-3 Report - Results of steam generator tube inspections which fall intu Technical Specification Category C-3 require ,
prompt notification of the NRC pursuant to Technical Specification 6.6.1 prior to-resumption of plant operation. The written followup of this report shall provide a description of investigations conducted to determine cause of the tubo degradation and corrective measures to prevent recurrence. 20.4.5.2 ASME Section XI Reporting Requirements For eddy current' esamination of heat exchanger tubing, the report shall include e record indicating the tube (s) examined (this may be marked on a tube sheet sketch or drawing), the extent to which each tube was examined, the asial location and depth of penetration of each reported degraded tube, and the identification or the operator (s) and data evaluator (s) who conducted each examination or part thereof, and magnetic media and strip charts as applicable. 20.5 rey _Hpgsle cladding Responsible Organisations Site Engineering. 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 are performed during the automated reactor vessel nossle inspection. This examination is performed in accordance with SON 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. Nossle forging material and cladding is identified in Section 7.1.2. A special preservice examination of the reactor vessel nossles was conducted to evaluate the extent of underclad cracking. The examination utilised a 700 angle beam and 00 beam manual contact technique. A11' indications foJnd were demonstrated to be acceptable in accordance with ASME Code Section XI criteria. (Reference FSAR Section 5.4.1.1) 20.6 Eteam Generator Feed Rino and J-Tubes Responsible Organisation: Corporate Steam Generator Maintenance and Technology. 1401C/COC3
51-114.2 SURVEILLANCE ASME SECTION XI R3visica 19 INSTRUCTION INSERVICE INSPECTION PR3 GRAM Peg) 74 cf 101 The carbon steel J-tubo nossles have been replaced with Inconel 600 J-tube nossles. This material is resistant to erosion corrosion i damage. Inspection of the J-tube nossles is not necessary. An ultrasonic thickness check of the feed ring header and too shall be performed on a frequency of every 10 years. This augmented examination is self-imposed by TVA (Sol 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._RoLQ.glje Tube rie.xures R5sponsible Organisations Corporate Outage Support. Any revisions or waivers of this examination plan as stated in this section shall be the responsibility of the Refueling Project Manager or his designee. Due to the potential of intergranular stress corrosion cracking of guide tube flexures, the following control rod guide tube flexure augmented examination plan shall be initiated (see Westinghouse reference memorandums A27 840123 022 und Lol 840723 035). The control rod guide tube flexures shall ao visually examined in accordance with visual examination method VT-3 (see Section 11.1) during each refueling outage. These examinations shall be performed in accordance with SMI-0-68-15. At each scheduled refueling outage, the tops of all guide tubes shall be visually examined to assure that all flexures are in their proper orientation. If any flexure heads are discovered to be broken from their stems, the heads should be retrieved and flexureless inserts installed. If flexureless inserts are not installed after a break has occurred, a safety evaluation will be required to confirm continued safe plant operation. A coFy of the VT data sheets shall be forwarded to the appropriate cognisant engineer. The PRISIM identifiers for the control rod guide tube flexures are: CRDTUBEFLEX - A07 CRDTUBEFLEX - E09 CRDTUBEFLEX - G05 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 Assembiv (RCCA) C}nddino Wear Measurements: Responsible Organizations Corporate FdR Fuel Engineering. The RCCA rcolet cladding wear for bot) SON units has been examined via the eddy current measurement NDE technique. Encircling coils were used for total area loss determirations and profilometry data 1401C/COC3 -
SI-114.2
$URVEILLANCE ASME SECTION XI R3visics 19 INSTRUCTION INSERVICE INSPECTICH PR^ GRAM pcg> 75 of 101 taken to characterise wear scars. S04 Unit 2 RCCAs were inspected for rodlet cladding wear in February 1989. SON Unit 1 RCCAs were
{; inspected in April 1990. Results were documented (L36 890511 800 and L36 901030 800). Summaries were provided for 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 reviewed, the wear data bases updated, and speelfic repositioning plans revised as necessary. Any RCCA with excessive rodlet cladding wear will be replaced. RCCA voar examinations via NDE techniques are self-imposed by TVA and do not require a special report. An examination summary shall be included in the ISI Report discussed in Section 16.3 whenever the RCCAs are inspected for either SON unit. 20.9 Angelerated Field Held Prooram fc.11 - Complete Responsible Organisation Site Engineering. In accordance with R. L. Gridley's January 30, 1987 memorandum to B. J. Youngblood (L44 870130 804), TVA committed to implement an Accelerated Fleid Weld program for SON Units 1 and 2. This augmented and accelerated program requires completion of 100 percent of ASME Class 1 and 2 piping, piping support, and component (reactor vessel,. steam generator, pressuriser, and reactor coolant. pumps) support fleid welds that are in the first 10-year program in the two (2) consecutive refueling outages following restart. The Accelerated Field Wald program was completed during the Unit 2 Cycle 4 refueling outage, see Request for Relief IS!-14. The results were included in the ISI Report discussed in Section 16.2. 20.10 Thimble _.luhe Guide Responsible Organization Site Engineering. Due to the potential thinning of thimble tube guides as reported on NRC Bulletin 88-09 and Information Notice 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 r4 fueling outage. . Sea R. W. Fortenberry's July 21, 1988 memorandum to S. J. Smith (S57 880721 821) and J. F. Murdock's June 3, 1988 memoranfam 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 bet a established. Results of the examinations shall be forwarded t) Site Engineering. See
- p. G. Trudel's February 27, 1989. memorandum to M. J. Bursynski (B25 890227 002).
1401C/COC3
. SI-114.2 SURVEILLANCE ASKE SECTION XI R3 vision 19 INSTRUCTION INSERVICE INSPECTION PROGRAM Pag 3 76 of 101 Results of the examinations shall be included in the ISI Report discussed in Section 16.3.
20.11 Examination of Pipina_ Connected to the Reactor Coolant Syltem Due to Thermal Stressig i Responsible Organisation Site Engineering. Due to the potential thermal stresses on unisolatable piping attached to the RCS (see NRC Bulletin 88-08), TVA has examined the following areast 1) the four 1.5-inch high head injection lines, 2) the 2-inch pressuriser spray line from the charging path, 3) the 3-inch alternate charging path, and 4) the 3-inch normal charging path. All of the welds up to the first valve have been PT examined, and the 3-inch line have been UT examisad as well. These examinations were conducted during Cycle 3 -buttown period. The SON Project Engineer has prepared a report to Licensing, who in turn prepared a report to the NRC. (See memorandums B29 880906 008, 808 880830 843, Lie 880824 802, and BIS 880819 014.) Due to the assessments concluded in Incident Investigation (II) , No. II-S-92-027 of the steam generator nossle transition section cracking problem and NRC Bulletin 88-08, similar conditions were evaluated for the Chemical and Volume Control System, Safety , Injection System and Reactor Coolant System. Potential for cracking in these systems, in particular the Alternate Charging Line, are the cases that resulted in the cracking of welds at Farley (NRC Bulletin 88-08) and the elbow at Tihange (NRC Bulletin 88-08, Supplement 1). The thermal cycling stresses can be quite severe at these locations with leakage across the closed FCVs, and it is possible for a crack to initiate and grow substantially in a single fuel cycle. As some of the fatigue crack mechanisms are much more likely than others to occur and result in crack development, a graded approach regarding inspection frequency has been recommended by Site Engineering. This graded approach couples the likelihood of occurrence with the severity of the postulated event. Some of these welds and adjacent base metal were base line examined during the Unit 2 Cycle 5 outage due to the feedwater transition piece cracking problem. TVA will perform an augmented inspection of the areas noted with inspections being performed during the intervals as listed below, unless otherwise revised or waived by Site Engineering. Additional welds and/or inspection techniques _maybe added by Site Engineering where further evaluation Indicate a potential for thermal stratification. Ultrasonic (UT) examinations shall 13 clude 100 percent volume of. the welds and base metal adjacent to each weld for a distance of two wall thicknesses.where accessibit (fittings, elbow interdose, and valves may prevent full circumfenence evaluation). Liquid-penetrant' (PT) examinations shall include the welds and base metal adjacent to each weld for a distance of one-half (1/2) inch. UT 1401C/COC3
4 51 114.2 i SURVEILLANCE ASKE SECTION XI R:vinics 19 ' 2NSTRUCTION INSERVICE INSPECTION p!DGRAM pega 77 of 101 i f and pT acceptance criteria shall be li accordanes with ASME Section XI, 1986 Edition, IWB-3514 ani 3WC-3514, for Class 1 and 2 ' welds, respectively. l The results of the examination will ic submitted to Site ' Engineering for evaluation and trendi ng. The results of this examination shall be included in the :51 Report discussed in : Section 16.3.
- Inspection of cold leg Loop 1, Weld CVCF-213, and cold leg Loop 4, ;
Weld CVCF-246, shall be performed by the UT examination method and ' ' scheduled for inspection at each consecutive refueling outeget f I Inspection of cold leg Loop 1, Wold AIF-145s cold leg Loop 2, Wold ' SIF-16Bs cold leg Loop 3, Weld S!r-184; and cold leg Loop 4, Weld S!r-128, shall be performed by_the UT examination method and scheduled for inspection at the Cycle 6 refueling outage with supplemental inspections performed as specified by Site Engineering. Inspection of pressuriser spray line, Weld RCF-23; hot leg surge line Loop 2, Weld RC-33; and pressura ser surge line, Wald RC-35 shall be performed by the UT examinat'.on method and scheduled for inspection as noted below. pressuriser spray line, Wold AJr-23, shall be inspected every fourth refueling outage beginning with refueling-outage 6. Hot leg surge line loop 2, Wsid RC-33, shall be inspected overy fourth-refueling outage ~beginning with refueling outage 10. Pressuriser surge line, Wold RC-35 shall be inspected every fourth refueling outage beginning with refueling outage:12. Inspection of hot leg Loop 1, Weld RFRS-209,-shall be performed by the UT examination method-and scheduled for inspection once during each 10-year inspection interval, beg 4nning with the second-inspection interval. Inspection of hot leg Loop 2 Wald SI.6980 and hot leg Loop 4 Weld: SI-1941 shall be performed by the PT Jammination method and scheduled fos inspection once during each 10-year' inspection interval. Inspection of the welds adjacent to ICV 62-54 for,the Loop 3 excess letdown supply line shall be gerformed.by the PT-examination method and sche 6uled for inspection every_fifth refueling outage beginning with refueling outage 6. For Unit 2, the weld numbers to be inspected are 2CX-1674 and 2CX-1675 (reference weld map 2-CVC-509-1H). 1401C/COC3 '
S1-114.2 SURVEILLANCE ASHE SECTION XI R3visics 19 2NSTRUCTION INSERVICE INSPELTION PROGRAM P g3 78 of 101 20.12 Examinal,lan. ef Presurirgr_ Surge Line Dud 2 Occurrtage of Thermal i Etratificatloa Complete Responsible Organisation Site Engineering. 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. Due to the thesmal stratification of the pressuriser surge line (see NRC Bulletin 88-11) TVA performed a visua2 inspection on the pressuriser surge line. This examination should determine any gross discernable distress or structural damage in the entire pressuriser surge line, including piping, pipe supports, pipe whip restraints, and anchor bolts. This examination was scheduled and performed per SMI-0-68-4. The results of the examination were coordinated in accordance with SMI-0-68-4. NE Operations Support submitted the results of the-examination to Nuclear Technology and Licensing for submittal to the NRC within 30 days af ter completion of the examinations. 20.13 gramination of Row I and Row 2 of the steam Generatorm Responsible Organisations Corporate Steam Generator Maintenance and Technology. The following augmented examinations requirements 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. All nonplugged and nonheat-treated Rce 1 and 2 U-bend regions shall be examined by rotating pancake coil addy current examinations during each scheduled Inservice Inspection of S/G tubing. The probe type utilised shall have been qualified for the detection of U-bend primary water stress corrosion cracking. 20.14 Ethmination of Base Maintial Transition Ad_iacent to Weld Ent.2RC-023 On RC Pumo No. 3 Cold Leg s Responsible Organisations Site Engineering. .This augmenteG examination is being performed to satisfy the requirements of CAQR No. SVP890138. The base material adjocent to Weld No. 2RC-023 on the RC Pump No. 3 cold leg rossle shall be PT examined. The inspection-area shall include a distance of two inches from tte edge of the pipe. we3d toward the nossle. The inspection area shall cover the O'-90* azimuth of Quadreo*. I, with the orientation viewed from the cold log noasle of the pump. ( 1401C/COC3
~_ -
SI-114.2 SURVEILbANCE ASKE SECTION XI R0visics 19 INSTRUCTION INSERVICE INSPECTION PROGRAM pegs 79 et 101-The PT examination will be performed furing the Unit 2 refueling outage for Cycles 4, 5, and 6. The results of the examination will be submitted to Site Engineerang (Project Engineer) by 500 for evaluation and flaw growth comparison in accordance with Tablo IWB-3518-2. Any revisions or waivers of this examination plan shall be approved by Site Engineering. This requirement has been added at the request of a memorandum from P. G. Trudel to L. E. Martin dated April 17, 1989 (B25 890417 024). The PRIS1H identifier for base material adjacent to Weld No. 2RC-023: RCP3BM-2RC-023. The results of this examination shall be included in the ISI Report discussed in Section 16.3. l 20.15 Main reedwater Inointion valven Responsible Organisations Site Engineering. Due to the bonnet indications found by previous inspections, MFIVs 2-rCV-3-33,
-47,-87, and -100 shall receive an auymented magnetic particle (MT) examination during the following Unit 2 scheduled refueling outages:
Unit 2 Cycle 5: Examine 2-rCV-3-47 a nd -87 Unit 2 Cycle 6: Examine 2-rCV-3-33 uad -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 purpcse of the reexamination is to verify that no progression of the damage is occurring. The examinations shall be performed in accordance with the followings
- a. The results of the magnetic particle examination will be 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 of the indication will be examined optically either in situ or by replication and laboratory examir ation for evidence of growth.
- 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 bonnet or body shall be reinspected in the following outage.
- c. If there is definite evidence of crack propagation based on visual inspection, it shall be riferred to Site Engineering.
Site Engineering will evaluate t)e condition and recommend that the bonnet or body affected be veld repaired or replaced, as necessary. " Definite evidence" is considered to be f atigue-type cracking emanating f rom the end 1401C/COC3
SI-114.2 SURVEILLANCE ASME SECTION XI R:vicica 19 INSTRUCTION INSERVICC INSPECTION PR> GRAM Ptg3 80 of 101 I= of the previous indication or stress corrosion cracking. In either case, the propagated crackang would be free of the high temperature corrosion product pre sent in the previous , examination,
- d. If there is no evidence of growth associated with the reinspection, no further inspection is required.
This augmented examination is self-imposed by TVA (B25 891228 008) and does not require a special report. Results of the examinations shall be forwarded to Site Engineering for their evaluation and/or disposition by S00. The results shall be included in the ISI Report discussed in Section 16.3. 21.0 INTERFACE DJCl&Q2IS 21.1.1 Quality Methods Procedure QMP-102.4, Qualification and Certification Requirements for NQ3 NDE Personnel. 21.1.2 Quality Methods Procedure QMP-117.5, Administration of Hondest.ructive Examination Procedures. 21.1.3 Quality Methods Procedure QMP-105.4, Control of Calibration Standards. 21.1.4 SON Administrative Instructions AI-8, AI-18.5.
. 21.1.5 SON Site Standard Practice SSP-2.5, SSP-3.1, SSP-3.4, SSP-3.6, SSP-3.7, SSP-4.5, SSP-6.9, SSP-6.21, SSP-7.2, SSP-8.2, SSP-8.5, SSP-8.6, SSP-9.3, SSP-12.58, and ESP-12.8.
21.1.6 SON Special Maintenance Instruction SMI-0-68-15. 21.1.7 SON Maintenance Instructions 0-MI-MRR-068-005.0, MI-1.4, 0-MI-MIX-0 6 8-0 04. 0, 0-MI-MXX-0 6 8 -C 03. 0, MI-2. 2, MI-10. 2. 3, MI-6.15, 0-MI-MVV-000.008.0. 22.0 DEVELOPlfElfIAk_ERTIRKHCIS 22.1.1 Memorandum from D. W. Wilson to H. L. Abercrombie, dated August 1,1986 "Sequoyah Nuclear Plant, Units 1 and 2,
" Indications in Class 1 Helds" (L18 860730 899).
22.1.2 Memorandum from V. A. Blanco to C. R. Brimer da.54 January 10, 1987 (B25 870109 045). 22.1.3 Memorandum frna G. C. Zoch to S. 7. White dated venuary 25, 1988 allowing use of code cases N 341 and N-356. 22.1.4 Memorandum from P. G. Trudel to M. J. Bursynski dated February 27, 1989 (B25 890227 002). 22.1.5 Memorandum from R. L. Gridley to I . J. Youngblood dated January 30, 1987 (L44 870130 804). 1401C/COC3
. 51-114.2 SURVEILLANCE ASKE SECTION XI RVisic3 19 INSTRUCTION INSERVICE INSPECTION PR0 GRAM Pcg3 81 of 101 a
22.1.6 NRC Bulletin 88-09 and Information Notice 87-44 supplement 1,
" Thimble Tube Thinning in Westinghouse Reactors."
22.1.7 Hemorandum from R. W. Fortenberry to S. J. Smith dated July 21, 1988 (S57 880721 821). 22.1.8 Memorandum from J. F. Hurdock to ti. B. Hosmer dated June 3, 1988 (L29 880531 914), 22.1.9 NRC Bulletin B8-08, " Thermal Stresses on Piping Connected to Reactor Coolant Systems," and Supplement 1. 22.1.10 NRC Bulletin 88-11, "Pressuriser lurge Line Thermal Stratification." 22.1.11 Hemorandum from D. T. Goetcheus to J. 7. Lewis dated Septen6er 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 une of 1984 Edition of ASNT. SNT-TC-IA for certification of NfE personnel. I 22.1.13 Hemorandum from P. G. Trudel to L. E. Hartin dated April 17, 1989 (B25 890417 024). l 22.1.14 Hemorandum from S. C. Black to 0. D. Kingsley, Jr., dated December 13, 1989, allowing the tse of Code Case N-460. 22.1.15 Hemorandum f rom F. J. Hebdon to C . D. Kingsley, Jr. , dated February 7, 1991 (A02 910211 001). 22.1.16 H2morandum from S. C. Black to 0. D. Kingsley, Jr., dated April 19, 1990 (A02 900426 005). 22.1.17 Memorandum from P. G. Trudel to I. L. Lumpkin, Jr., dated December 28, 1989 (B25 891228 00(). 22.1.18 Hemorandum from G. J. Pit:1 to G. L. Below, 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). 22.1.20 NRC Bulletin 83-02, " Stress Cortcsion Cracking in Large-Diameter Stainless Steel Recircu3stion System Piping at BWR Plants." 22.1.21 NRC Bulletin 79-13, " Cracking in Teedwater System Piping." 22.1.22 Hemorandum from D. F. Goetcheus to G. L. Belew dated May 15, 1986 (501 860515 828). 22.1.23 Hemorandum from R. S. Howard, Wetcinghouse, to J. P. Darling dated July 9, 1984 (LO1 840723 025). 1401C/COC3
.SI-114.2 SURVEILLANCE 'ASPE SECTION XI- Ravinien 19 INSTRUCTION INSERVICE INSPECTION PROGRAM Paqs 82 of 101 22.1.24 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 August 21, 1991 (S10 910821 848). 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 f rom P. G. Trudel to M. J. Ray- dated September 6, 1988 (B29 880906 008). 22.1.32 Memorandum f rom L. E. Martin to P. G. Trudel dated August 30, 1988 (808 880830 843). 22.1.33 Momorandum from M. J. Ray to NRC dated August 24, 1988
'L4# 880824 802).
22.1.34 ...e.orandum f rom 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, N2M-2-3. 22.1.36 Westinghouse Technical-Manual - Pressurizer, TH 1440-C225, Contract No. 68C60-91934, N2M-2-6. 22.1.37 Westinghouse Technical Manua) - 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. 22.1.39 Westinght.ae Instruction Book - Ranctor Coolant Pump, Contract No. 6BCt0-91934, H2M-2-5. 22.1.40 Ingersoll-Rand Instruction Manual - Residual Heat Removal Pumps, Contract No. 68C60-91934, 32M-2-30. 22.1.41 Memorandum from D. F. Goetcheus to'G. 5. Pit:1 dated March 23, 1992 (H03 920323 059). i 1401C/COC3
SI-114.2 SURVEILLANCE ASME SECTION XI R;visica 19 INSTRUCTION. INSERVICE INSPECTION PEJGRAM P:g) 83 cf 101-22.1.42: Memorandum from F. J. Hebdon, NRC, to Dr. Mark O. Medford, TVA, dated August 31, 1992 (A02 920903 005). i.
>i 22.1.43 Incident Investigation (II) No. II-S-92-027.
22.1.44 Memorandum from G. J. Pit:1 and H. L. Turnbow to N. C. Kazanas and D. R. Keuter, " Review of Augmented Nondestructive Examinations (NDEs) Not Presently Included in the Inservice (ISI) Programs," dated September 1, 1992 (L29 920828 800) { 4 1401C/COC3
. APPENDIk A U TABLE'l O
Minimum Number of Steam Generators To Be n Inspected During Inservice Inspection Only wm zg NN cu g t- -- No. of Steam Generators per Unit Four "6 zg First Inservice Inspection
, Two Second & Subsequent Inservice Inspections One l Table Notation:
- 1. Each of the other two steam generators not inspected during the first inservice inspections shall be inspected during *'
the second and third inspections. The fourth and subsequent inspections shall follow the instructions described below: m
- The inservica inspection may be limited to one steam generator on a rotating schedule encompassing 12% of the E
<=
tubes
.like if the results of the first or previous inspections indicate that all steam geverators are performing in a 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 steam generators. Under r:sch circumstances the sample sequence shall Mg be modified to inspect the most severe conditions. w 2m MM M 3a a* zn lll 8 w Or eM
>=
[(*
- e. -
1 H
.. --- - ~-
APPENDIX A TABLE 2 w Steam Generator Tube Inspection 5 O wa-ist Sample Inspection 2nd Sample Inspection EN Sample Size Result Action Required 3rd Sample Inspection H< Result Action Required Result Action Required A minimum of 3 C-1 E[ Tubes per S.G. None N/A N/A N/A N/A g c*C* C-2 Plug defective tubes C-1 None N/A N/A oE y . and inspect additional Plug defective tubes C-1 %Q Ngne 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 for C-3 result of first sample C-3 Perform action for N/A N/A C-3 result of first g z sample M 0-3 Inspect all tubes this All other N S.G., plug defective S.G.s are None N/A N/A.
$p t* bes and inspect 25 C-1 n ta tubes in each other S.G. Some S.G.s Mg w
C-2 but no Perform action for N/A N/A Prompt notification to additional C-2 result of $$ S.G. are C-3 second sample MoO NRC pursuant to technical Additional- Inspect all tubes in O o, - specification 6.6.1 S.G. is C-3 each S.G. and plug N/A N/A yM defective tubes. zx Prompt notification to NRC pursuant to .o w technical speci- . ficatj,on 6.6.1 8 w 5 - M1 Where n is the number of steam generators inspected during an inspection. $ 550 1 li. L e, . tit O + ' D M O.. M
SI-114,2 SURVEILLANCE ASME SECTION XI- R: vision 19 INSTRUCTION INSERVICE INSPECTION PROGRAM .Page 86 of 101 1 APPENDIX B - }[ DATA SHEET 1 i-SEQUOYAH NUCLEAR PLANT UNIT 2, CYCLE SITE FINAL REPORT Prepared by: Approved by: 1403C/COC3
SI-114.2 SURVEILLANCE ASME SECTION XI Rsvision 19. INSTRUCTION INSERVICE INSPECTION PROGRAM ~ Page 87 of 101 i APPERDIX C 1 NOTIFICATION OF INDICATION l. PART I - FINDINGS-NOI No. Plant / Unit ISI Dvg./Sh. No. Examination Report No. Component ID __ Description of Indication (Sketch / Photograph if Required for Clarification): Signature of Examiner / Certification Level Date Signature of Field Supervisor (Contractor): Date Signature of S00 Representatives Date PART II-DISPOSITION DCN NO. WR/WO NO. PER NO. FIR NO. SCAR NO. Other-Disposition Prepared / Recorded By
-Date PART III ADDITIONAL EXAMINATIONS Additional Sample Required: Yes No Attach llat of items in additional sample, if required.
VERIFICATION OF CLOSURE Verification of Completed Corrective Action Required by Disposition Reexamination Report Number, if Applicables Comments: Signature of SQO Representatives Date 1403C/COC3
SI-114.2 i SURVEILLANCE ASME SECTION XI R;visien 39 i INSTRUCTION INSERVICE INSPECTION PROGRAM- Page 88 of.101 2 a 9 ' s APPENDIX D GUIDELINES POR DETERMINING PIPING COMPONENT SUPPORT EXAMINATION BOUNDARIES s 5 J
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APPENDIX D f I' o j 1.0 PURPOSI-This instruction defines and establishes the controls'and responsibilities for the determination of ASME Section XI component support examination boundaries. 2.0 SCOPE This instruction' applies only to the piping :omponent supports included in the appropriate plant instruction for preservice/in-service: inspection (hereafter, ISI Program) for Sequoyah Nuclear Plant.
3.0 REFERENCES
3.1 Memorandum from W. E. Pennell to R.1A. Sessoms dated August 10, 1987 (B41 870810 003) 3.2 Memorandum from J.-A. Kirkebo to Site Directors dated June 24, 1987 (L29 870528 815) 4.0 DEFINITIONS 4.1 Intervelino Element: Items that=11e in the component support load path between the pressure retaining component and-the component supports, between two component supports,.or between'the component support and the building structure. Items such~ast~ diesel engines,- electric motors, valve actuators, coolers, instrument racks and access structures. For the purposes of this instruction, an intervening element is to be considered the same as " existing steel."_ 4.2 Existina Steel Building steel that is identified on a support-drawing as " existing." 4.3 Type A Examination Boundary: The type of boundary to be used for those supports that~are attached to building floor, walls, ceiling,_ or embedded plate. 4.4 Tyve B Examination Boundary: The type of boundary to be used for-those supports that are attached to another existing support. 4.5 Tvoe c Examination Boundary: The type of boundary to be used for those supports that are attached- to exi sting steel. 4.6 Tvoe D Examination Boundary: The type.of' boundary to be used'for-those supports that are attached to an-intervening element. 5.0 RESPONSIBILITIES 5.1' ASME Section XI Programs is. responsible for the initial review of
-ASME Section XI component-support drawlsgs and determining-the examination boundary for those supports. The Site' Quality Organization (SQO) shall be responsible _ for determining' the .
examination' boundary for new or modified supports. 1403C/C0C3 s
^
SI-114.2 SURVEILLANCE ASME SECTION XI Rsvision 19 INSTRUCTION INSERVICE INSPECTION PROGRAM page 90 of 101 APPENDIX D l' L i This instruction shall be revised by ASME Section XI Programs when deemed necessary by ASME Section XI Programs Supervisor or his designee. 5.2 ASME Section XI 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 where questions exist by submitting the Component Support Examination Boundary Clarification Request Form to ASME Section' XI Programs. 6.0 IMPLEMENTATION 6.1 Determination of Comoonent Suonort Examination Boundar_v 6.1.1 General 6.1.1.1 ASME Section XI Programs and SQO shall use the , following methodology to determine the component support examination boundary.
- 1) In all cases involving attachments welded to pressure retaining. components and/or supports .
welded to building structure / existing steel, the l weld shall be included within the examination boundary.
- 2) Concrete bolt anchors, such as "ted-head" or "rawl" anchors, are not included within the l Cection 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.)
j 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 of materials, items to be examined shall be described in the PFISIM data base with the specific ISI support number. For TVA designed supports, the examination boundary may be determined from TVA drawings. These drawings should be referenced on ASME Section XI. program drawings.
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,, APPENDIX D t
- 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 f alls within the scope of ASHI Section XI. B) the component support is part of the inservice inspection examinatJon sample. C) the indication falls within the component support's examination boundary as set forth by this instruction. Indications that do not meet the criteria in A, B, and C, above, should be noted by other means, such as, HR's, WR's, etc.
- 6) This instruction la intended to deal with piping supports only. Therefore, equipment support drawings will be provided in the ISI Program that depict the examination boundary 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 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 supports, the drawing included in the work instruction may be utilized. Using the drawing, classify the support in one of the following categories:
- 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."
- 4. Support is shown er being attached to an intervening element.
After classifying the support in one of the ' categories, proceed to the corresponding section to complete the boundary determination. 1403C/COC3
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' INSTRUCTION INSERVICE INSPECTION PROGRAM Page 92 of-101 h
APPENDIX D 6.1.1.3 As each support is categorised, the category _ identifier, as defined 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. revise the examinatiou boundary for that support.. 6.1.2 Supports Attached to Bu11dino Floor. Wall, ceilina, or Embedded Plate For supports attached to building floor, wall, ceiling or embedded plates, the boundary shall be defined as the point (s)/ area (s) of contact between the support and the building structure, along the support load path (s) up to, but not including the pressure retaining component. In addition to the requirements of 6.1.1.1, each item in the support bill of materials, except concrete anchors and material used as a spacer to allow for grouting between the base plate and the building floor, wall, or ceiling, 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 Sunnorts Attached to Existina Sunnorts NOTE: For clarity, Support A is the support being reviewed for boundary determination and Support B is the
" existing support" to which Support A is attached.
The boundary of Support A shall be defined as the point (s)/ area (s) of contact between Support A and Support B, along the support load path (s), up to, but not including, the pressure retaining component. In addition to the. requirements of-6.1.1.1, each item in Support A bill of materials is to'be included within 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 Existino Steel-For supports attached to existing steel, the boundary shall be defined as the point (s)/ area (m) of' contact between the support and " existing steel", along the support load path (s), 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. 1403C/COC3
SI-114.2 SURVEILLANCE ASME SECTION XI R; visits 19 INSTRUCTION INSERVICE INSPECTION PR) GRAM Page 93 of 101 APPENDIX D This category of supports shall se considered Examination Boundary Type C and so designated in the PRISIM data base. 6.1.5 Suoverts Attneted to Intervening _ Element For supports attached to an intervening element, the boundary-shall be defined as the attachment portion (i.e., welds, bolting, pins, clamps, etc.) to the pressure retaining component and all support members up to, but not including, the intervening elen. ant. In addition to the requirements of 6.1.1.1, all items listed in the support bill of materials are to be included within the boandary. This category of supports shall be considered Examination Boundary Type D and so designate 3 in the PRISIM data base. 6.1.6 Supports Attached to various Stractures In many cases, one component support is attached to more than one type of structure. These supports will have more than one Examination Boundary Type designator in the PRISIM data base. In all cases, however, the examination boundary- for each component support shall include: *
- 1) All items listed on the support's bill of materials, except concrete anchors. For TVA designed supports, the examination boundary may be determined from TVA drawings. The drawings should be referenced on ASME Section XI program drawings.
- 2) All shims and. lugs adjacent to the supported pipe.
6.2 Site Implementation 6.2.1 SQO shall obtain the latest CCD af the support. If a CCD does not exiet, the latest as-constructed drawing shall be obtained. If an us-constructed drawing does not exist, the latest as-designed drawing shall be obtained. If during the performance of an examination, significant differences are identified between the oupport trawing and the support field configuration, SQO shall access the Design Change Document Tracking System (DCDTS) to identify any outstanding change documents on that component support. For each component support that does have an outstanding change documented listed on the DCDTS, S00 shall determine through the. work package projec; engineer if the work has been completed on that particult; support. If the work has been completed, SQO shall obtair the change docunent support drawing. If the work has not been completed, the examination shall be delayed unti?. the work has been completed. As an alternative to obtaining the latist as configured drawings and the bill of material, the conponent support examination 1403C/COC3
SI-114.2 SURVEILLANCE ASME SECTION XI R0visite 19-INSTRUCTION INSERVICE INSPECTION PROGRAM- Page 94 of 101 l APPENDIX D f boundary may be defined as the attachment to the component up to and including the attachment to the floor, wall, and ceiling. 6.2.2 Tor variable spring hangers, constant force supports, and snubbers, the examiner or engineer shall'une the drawing, obtained per 6.2.1 above to verify that the thermal movement and support type given on the support drawing matches the corresponding information given in the Scan Plan or implementing instruction (WR, WP etc.). If the movement and support type information do not satch: (a) The examiner as S00 Representative shall contact ASME Section XI Programs. When immediate action is required, ASME Section XI Programs may provide verbal instructions to the requesting examiner or SQO Representative to enable them to perform the examination. Verbal instructions shall be confirmed within 14 working days using the Component Support Clarification Request Form. (b) The examiner or engineer may submit a Component Support Examination Boundary Clarifl:ation Request Form to ASME Section XI Programs. SCO or ASME Section XI Programs, upon receipt of a request, shall review the discrepancy and make any necessary changss to the examination boundary. If a request has aeen submitted (when verbal instructions were not reques:ed), the request will be completed and returned to th e requesting examiner or engineer to enable them to S arform the examination. A support shall not be exauined until any discrepancies on that support are eliminated. -Any changes in the Examination Boundary Type w311 be incorporated in the PRISIM data base. NOTE: See Examples 2-5 of Section 7.0 example boundaries of each examination boundary type. 7.0 EXAFTLES Form - Component Support Examination Boundary Clarification Roquest Form Example 2 - Type A Examination Boundary Example 3 - Type B Examination Boundary Example 4 - Type C Examination Boundary Example 5 - Type D Examination Boundary 1403C/COC3
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APPENDIX D-
- {
.- j COMPONENT SUPPORT EXAMINATION BOUNDARY CLARIFICATIQH
' REQUEST FORM Plant: Units- Dates
- Component Support No.3- Rev.:
Person Requestinge Request: k enemmeneennemee***eneme***emenenemeaneeenneeeeeeeeeemeni wenee*****eneeeeeeeeee- . Responding ASME Section XI Programa Representatives Dates Responses Did " Examination Boundary Type" change Yes No-1403C/COC3 g 4 -
SI-114.2 SURVEILLANCE ASME SECTION XI R: visit:3 19 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 96 of_101 APPENDIX D EXAMPLE - TYPE A EXAMINA TION COUNDARY EXIST-CONC W/EMB PL. (12 X 3/4) DWG-4BN1374-RS
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=
_ __s.__e.___ __ lJetJ l _ 4" (TYP.) C _
.. ...:. ..c . . .... _ - .. . .
.. . ..........,.e C : : .3
+ C 18" PIPE 5 8 PCS FDR 1 UNIDIRECTIONAL SUPPORT 1 & 1
- BEAM ATTACH LESS BOLT. BE-200 (INVERTED) 1 @ 1* O ROD X 3'4' W/JN G HN TOE-10' EDE-1 1/4"O
-1 @ 18' PIPE CLAMP BE-124 BOUNDARY: EXAMINE WELD TO EMBEDDED PLATE AND ALL
- BILL DF MA TERIALS ITEMS. .
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SI-114,2 i SURVEILLANC ASME SECTION XI R;visica 19 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 97 of 101 i APPEEIX D 1 ) 1
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EXAMPLE - TYPE $7hAb A) EXAMINA TION BOUNDARY
- EXISTING W10x25 SUPPT.
W/1-CCH-XXX EXIST. e , CONC. s , c =
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4 e F _ _
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.. . . . .x . . . . . , . . . .
. am 1. . . . G....Q ;w.c wt ...:ir.
PCS FOR : UNIDIRECTTONAL SUPPORT . 2 @ WS x 20 x 3'-11 3/B' ' ' ' ~ WS x 20 x l '-7 1/B' '
~
i @ . 1 @ W6 x 20 x 1*-7 1/B' 1 @ TS 5 x 5 x 1/2 x 4 '-O' 1 @ PL . 3/4 " x 10 '-10 ' LG W/4 13/16" Q HOLES 4 @ 3/4' @ BOL TS 4 @ 3/4 ' RAWLS 5. C #6010 . BOU DARY* EXAMINE ALL ITEMS ON BILL OF HATERIALS EXCW'T
#7 (ANCHORS) . ALSO EXAMINE SHIMS.
4 DO NOT EXAMINE
- EXISTING' W10 'x 25.
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1 SI-114.2 SURVEILLANC:: ASME SECTION XI R0visie3 19
' INSTRUCTION- INSERVICE. INSPECTION PROGRAM Page 98 of 101 I
APPENDIX D EXAMPLE - TYPE C EXAMINA TION BOUNDARY p========_==.._=_=======_==__: _;
\
W30 x 210 (EXIST.. ) \ l I t_____ __..___ ______ _,r_,,_____s
., 11 11 i 11 11 D % si 11 W
\ 11 11 7 (14EXIST.)
x 142
.s il 11
- s II - 11
\Ji h-/. 11 1
il il
, 11
@~ ll 11 11
,_________.______._______&_ m ___,
' W30 x eso (EXIST.) '
I TYP.>b9 - I e===== ==_: . ______ _______ : , PCS FOR l ' HORIZONTAL RESTRAINT L TO PIPE 2 @ 1 1/2" x 2 15/16*, C. S. PLA TE. S' LG. (A212-A) 1 @ 7.s'B ' x 6 ' C. S. PLA TE B" LG. . 1 Q W12 x 27 x 3'-9 5/B' LG. 2 @ 3/B' C.S. STIFFENER PLA TE FOR W12 x 27 BOUNDARY: EXAMINE WELD BETWEEN LUG AND PIPE AND ALL BILL OF HATERIALS . ITEMS. 1403C/COC3
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~ INSTRUCTION INSERVICE INSPECTION PROGRAM Page 99 of 101
,. APPENDIX D i
EXAMPLE - TYPE D EXAMINATION BOUNDARY l , [ - l / 4 gf .--
% J
/
p '
'm __
9 % THREADED N - d HOLES "y EXISTING MAIN FLANGE R.C. PUMP f.1 .
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PCS FOR 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' LG. 1- @ 1/2 ' x 3
- C. S. 'PLA TE. 9' LG.
4 @ 7/B 'O S. S. STUD. 3 . 7/B' ' LG. W/ (2) HEX NUTS
.1 @ l ' x 12 " C. S. PLA TE. 20 1/2' LG.
l ' x 4 1/2 " C. S. PLA TE. 12.', ,L G. 1 @ , l BOl/NDARY: EXAMINE. ALL BILL OF MATERIALS ITEMS. . i 1403C/C0C3
. . ~ . ~ , .. ~. . . .- - .. -. . . . ,- ~ .. .
1.
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APPENDIX Ei
- FIELD CORRECTED DRAWING (S) TRANSMITTAL L
TO: -ASME Section XI Programs Transmittal' Number < (Year);(Seguential): Plants-- SON Unit / Outage or Dates- U2/ G The drawing (s) listed below from SI-114.2 have been field marked with variations in configuration which were discovered during the. course of inservice or preservice examinations. Please revise the controlled copy off this/these drawing (s) in the SI prior to the next refueling outage.
- 1. 7.
- 2. 8.
t
- 3. 9. -
e
- 4. ___ 10 5
- 5. 11.
, 6.- 12. Signature of Examiner /Date , Signature of Field Supervisor ___ I RETURN TO: SITE QUALITY ORGANIZATION - i Drawings have been revised as necessary to reflect the appropriate changes. < Signature of ASME Section XI Programs Reprecentative Date E l 1403C/COC3
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4
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SI-114.2-SURVEILLANCE- ASME SECTION XI .R vicica 19 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 101 of 101-
,, SOURCE NOTES
't Requirements IMPLEMENTING Statement SOURCE DOCUMENT STATEMERT__
All STD 6.10 All All Applicable ASME Boller and Pressure All Articles Vessel Code - Section XI 1974. Edition, Summer 1975 Addenda, 1977 Edition, Summer 1978 Addenda All Applicable ASME Boller and Pressure All Articles Vessel Code - Section V All Applicable FSAR - SON All Chapters Surveillance Requiremente Technical Specifications All 4.0.5, 4.4.5.0, thru Unit 2 - SON 4.4.5.5, 4.4.10 10CTR50.55a Code Federal Regulations All 10CFR50
. As Applicable U.S.N.R.C. Erjulatory All Guides 1.14, 1.26, 1.83, 1.147, and 1.150 Provide a revised Response to NRC C.1 I5I Program to NRC dated 1/30/87 within 6 mos. following R. L. Gridley to NRC Unit restart L44 870130 804
.NCO 870 032 004 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 All Code Cases N-209, N-234, All N-235, N-307-1, N-308, N-401-1, N-402, N-416, N-426, h-435-1, N-461, N-341, N-356, F-460 IWA-1600, IWA-2200, ASME Boller and Pressure Vessel All IWA-2300, IWA-2600, Code - Section XI 1986 Edition IWA-3000, INB-3000, Response From NRC Dated IWC-3000, IWD-3000, 4/24/92 (AG2 920429 005)
IWF-3000, Appendices III, IV, and VI 1403C/COC3 L---- .- - - - - _4
j. SI-114.2, Att:chment 1 SURVEILLANCE R visi$n 2-INSTRUCTION LIST OT DRAWINGS - UNIT 2 Page 1 of 7 t-f ASME Section II Programs-A. MAINTAIN a listing of drawings for ISI examinations.- D. UPDATE listing na necessary. C. OBTAIN concurrence from Site Quality Manager or his designee. SOM D. CONCUR with listing by signing below. ASME Section II Programs E. FORWARD to SPS for updating Table of Contents, etc. SPS F. FORWARD to DCRM. DCRM G. DISTRIBUTE per SSP-2.7. JJJNA Site Quality Ma'nage:-/ Designee i ak/n Date 1404C/COC3
SI-114.2, Attcchment'l SURVEILLANCE R3 vision 2-INSTRUCTION LIST OF DRAWINGS - UNIT.2. -Page 2 of 7 . 4 . LIST OF 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. Drawino No. Emmetor vessel ISI-0304-B Reactor Vessel Stud Locations and Details ISI-0298-B Reactor Vessel Seam Nelds ISI-0301-A Reactor Vessel Closure Head ISI-0300-A Control Rod Drive Housing ISI-0392-A Reactor Vessel Inlet Nozzles ISI-0297-A Reactor Vessel Outlet Nozzles ISI-0097-C Closure Head Penetrations ISI-0318-A Auxiliary Head Adapter / UNI Cap Holds ISI-0319-C Reactor Vessel Bottom Head Penetrations Drawino No. Pressuriser ISI-0396-C Pressuriser ISI-0299-B Pressurizer and Steam Generator Manway Bolting ISI-0309-A Pressurizer Heater Penetrations Drawino No. Steam Generatong 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 No. Heat Exchangggg ISI-0289-A Residual-Heat Removal Heat Exchanger ISI-0231-B Centrifugal Charging Pump 011 and Gear Cooler Support ISI-0235-A Safety Injection Pump 011 Cooler Support. LISI-0232-B CCS Waste Gas _ Compressor Heat Exchanger Support ISI-0230-A CCS Gross Falled Fuel Detector. Support' ISI-0229-A CCS Positive Displacement Pump 011-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 ISI-0361-A Safety Injection-Pump Seal Cooler Support ISI-0259-A Containment Spray Heat' Exchanger Support ISI-0226-B- Gas Stripper and Boric Acid Evaporator Package Support 1404C/COC3
.S1-114.2, Attcchm:nt 1 SURVEILLANCE R visica 2 INSTRUCTION LIST OF DRAWINGS - UNIT 2 Page 3 of-7 -f LIST OF DRAWINGS - UNIT 2 Drawino No. Hgat Exchancers (Continued)
ISI-0257-A Non-Regenerative Letdown Heat Exchanger Support ISI-0261-B Component Cooling Heat Exchanger ISI-0268-A Essential Raw Cooling Water Strainer Support ISI-0291-B RHR Heat Exchanger Secondary Side Support 1 Drawino No. Pipino and Valve Weld Isometries 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 Spray' System Class 1 and 2 Pipino and Valve Drawino No. EMEPort-Drgvingg MSG-0013-C Reactor Coolant System MSG-0012-C Chemical _and Volume Control System MSG-0015-C Seal Water Injection (Chemical and volume Control) MSG-0010-C Residual Heat Removal System MSG-0009-C Safety Injection System MSG-0017-C Main Steam System MSG-0016-C Feedwater System MSG-0011-C Containment Spray System-ISI-0302-C Reactor Coolant System Support Locations ISI-0321-B Resctor Coolant System (Main Loop) Crossover Le7 Restraint Class 3 Pipino and Valve Drawino No. Enocort Drawinog-ISI-0146-C Auxiliary Feedwater System ISI-0158-C. Essential Raw Cooling Water System ISI-0154-C Component Cooling Water System-ISI-0255-A Essential Raw Cooling Water System Support Detail 1404C/COC3
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-SURVEILLANCE Revision 2 INSTRUCTION LIST OF DRAWINGS - UNIT 2 Page 4 of 7 j LIFT OF DRAWINGS - UNIT 2 i
Drawino N6. 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 Pump Support Locations ISI-0238-A CCS-Thermal Barrier Booster Pump Support ISI-0253-B Turbine Driven Auxiliary Feedwater Pump Support ISI-0263-B Motor Driven Auxiliary'Feedwater Pump Support ISI-0260-A Component Cooling Water Pump 2A-A and 2B-B Support Drawino No. Ignka ISI-0074-A Centrifugal Charging Pump Tank (Formerly-BIT Tank) ISI-0227-B Component Cooling Surge Tank Drawino No. Miscellaneous ISI-0403-A Reactor Coolant Pump Flywheel Examinations ISI-0405-A Support Acceptance Ranges ISI-0402-A Valve Interior Examinations 1404C/COC3
SI-114.2,-Atttchment l' SURVEILLANCE . Revision 2 INSTRUCTION LIST OF DRAWINGS.- UNIT 2 Page 5 of 7 . 4 { LIST OF DRAWIKGS l' ASMC Section XI Drtwino No. Boundary Classiffeation Drawingi 17H600-3-ISI Mechanical Instruments and Controls 17W600-6-ISI Mechanical Instruments and Controls 17H600-13-ISI Mechanical Instruments and Controls 47W600-26-ISI Mechanical Instruments and Controls 1,2-47W600-27-ISI Mechanical Instruments and Controls 1-47H600-28-ISI Mechanical Instruments and Controls 2-47W600-28-ISI Mechanical Instruments and Controls 47W600-29-ISI Mechanical Instruments and Controls 47W600-30-ISI Mechanical Instruments and Controls 47W600-31-ISI Mechanical Instruments and Controla 47W600-32-ISI Mechanical Instruments and Controls 47W600-34-ISI Mechanical Instruments and Controls 47W600-35-ISI Mechanical Instruments and Controls 47W600-62-ISI Mechanical Instruments and Controls 47W600-64-ISI Mechanical Instruments and Controls 47W600-65-ISI Mechanical Instruments and Controls 47W600-75-ISI Hechanical Instruments and Controls 47W600-80-ISI Mechanical Instruments and Controls 47W600-82-ISI Mechanical Instruments and Controls 47W600-88-ISI Mechanical Instruments and Controls 47W600-92-ISI Mechanical Instruments and Controls 47W600-03-ISI. Mechanical Instruments and Controla 47W600-102-ISI Mechanical Instruments and Contro1r 47W600-113-ISI Mechanical Instruments and Controls 47W600-114-ISI Mechanical Instruments and Controls 47W600-115-ISI Mechanical Instruments and Controls 47H600-116-ISI Mechanics 1 Instruments and Controls 47W600-117-ISI Mechanical Instruments and Controls 47W600-118-ISI Mechanical Instruments and Controls 47W600-128-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 Centrols 47W600-134-ISI Hechanical Instruments and Controls 47W600-136-ISI Mechanica1' Instruments and Controls 47W600-137-ISI Mechanical Instruments and Controls 47W600-142-ISI _Hechanical Instruments and Controls 47H600-143-ISI' Mechanical Instruments and Controls 47W600-144-ISI Mechanical Ins' ruments and Controls 47W600-152-ISI Mechanical Instruments and Centrols 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 Centrols 47W600-165-ISI Mechanical Instruments and Centrols 1404C/COC3
SI-114.2, Attechm:nt 1
-SURVEILLANCE Revision 2
, INSTRUCTION LIST OF DRAWINGS - UNIT 2 Page'6 of 7 ', LIST OF DRAWINGS
&SME Section XI Drawino No. Roundary Classification Drawines (Continued) 47W600-167-ISI Mechanical Instruments and Controls 47W600-168-ISI Hechanical Instruments and Controls 47W600-169 ISI Mechanical-Instruments and Controls 1,2-47W600-171-ISI Mechanical Instruments and Controls-47W600-172-ISI Mechanical Instruments and Controls 47W600-174-ISI Mechanical Instruments and Controls 47W600-175-ISI Hechanical Instruments and Controls 47W600-181-ISI Hechanical Instruments and Controls 47W600-200-ISI Mechanical Instruments and Controls 47W600-227-ISI Mechanical Instruments and Controls 47W600-228-ISI Mechanical Instruments and Controls 47W600-241-ISI Mechanical Instruments and Controls 47W600-244-ISI Mechanical Instruments and Controls 47W600-276-ISI Mechanical Instruments and Controls 47W600-279-ISI Mechanical Instruments and Controls 47W600-280-ISI Mechanical Instruments and Controls 47W600-286-ISI Mechanical Instruments and Controla 47W600-287-ISI Mechanical Instruments and Controls 47W500-289-IST Mechanical Instruments and Controls 47W600-294-ISI Mechanical Instruments and Centrols 1-47W600-1148-ISI Mechanical Instruments and Ccntrols 47W625-1-ISI Radiation Sampling System 47W625-2-ISI Radiation Sampling System 47W625-3-ISI Radiation Sampling System 47W625-4-ISI Radiation Sampling System 47W625-7-ISI Radiation Sampling System 47W625-15-ISI Radiation Sampling System i 1,2-47W801-1-ISI Main and Reheat Steam 1,2-47H801-2-ISI Steam Generator Blowdown System 1,2-47W803-1-ISI Feedwater 1,2-47W803-2-ISI_ Auxiliary Feedwater System 1,2-47W803-3-ISI Auxiliary Feedwater System 1-47W809-1-ISI Chemical and Volume Control Eystem 2-47W809-1-ISI Chemical and 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 1,2-47W809-7-ISI Flood Mode Boration Makeup System 1,2-47H810-1-ISI Residual Heat Removal System 1-47W811-1-ISI Safety Injection System 2-47W811-1-ISI Safety Injection System 1-47W811-2-ISI SIS Upper Head Injection System-2-47W811-2-ISI SIS Upper Head Injection System 1,2-47H812-1-ISI Containment Spray System 1,2-47W813-1-ISI Reactor Coolant System 1,2-47W819-1-ISI Primary Water 1404C/COC3
4 _![ SI-114.2,:Attachmant 1
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SURVEILLANCE Revision _2 INSTRUCTION- LIST OF DRAWINGS - UNIT _2 Page-7 of 7 4
,e LIST OF DRAWINGS ASME Section XI Drawino No. Boundary Classification Dravinos (Continued)'
1,2-47W830-1-ISI Waste Disposal System
, 1,2-47W832-3-ISI Fire Protection and Raw Service Water
_1,2-47W845-1-ISI -Essential Raw Cooling Water System-1,2-47W845-2-ISI Essential Raw Cooling Water System ' 1-47W845-3-ISI Essential Raw Cooling Water System 2-47W845-3-ISI Essential Raw Cooling Water System 1,2-47H845-4-ISI Essential Raw Cooling Water System s 1,2-47W845-5-ISI Essential Raw Cooling Water System A 1,2-47H845-6-ISI Essential. Raw Cooling Water System 1,2-47H850-10-ISI Fire Protection 1,2-47W851-1-ISI Floor and Equipment Drains 1,2-47W855-1-ISI Fuel Pool Cooling and Cleaning System 1, 2-4 7W8 56.-1-ISI Demineralized Water and Cask Decon System 1,2-47H859-1-ISI Component Cooling System 1,2-47W859-1-1-ISI Component' Coo'.ing System 1-47W859-2-ISI Component Cov.11ng System 2-47W859-3-ISI Component Cooling System 1,2-47W859-4-ISI Component Cooling System 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: i f i 1404C/COC3L i
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- SI-114. 2, . Attcchm3nt' 2 f-
, SURVEILLANCEI R2vicica --l' l INETRUCTION VALVE. TABLES -Page 1-of-.8;
.] .
ASME Section II-Programs A. ' MAINTAIN a listing of' valves-requiring ISI examinations.
.B. UPDATE listing as necessary.
C.- OBTAIN concurrence from Site Quality Manager or'his designee.
-SON D. CONCUR-with listing by signing.below. .
ASME Section II Programs t E. FORWARD to SPS for updating Table of Contents, etc. SPS F. FORWARD to DCRM. DCRM G. DISTRIBUTE per SSP-2.7. AMA Site Quality Hanager/ Designee-i ninh2 . fDate i 1 1405C/COC3- ,
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L A?TACWtENT 2 TABLE 1 VALVES SUEL1ECT TO THE REQUIcEMENTS OF EXAMINATICM CATEGORY B-M-2 CF TABLE IVS-2500-1 DF SECTION XI Valve Code Valve Piping Valve Valve Valve Group ISI Dwg Mo. Vender .* es No. Class Cat. System Size Tvoe Act Mr Weld Mao) Dw2 W. Katerial Valve Ferging g$ Yeafor Scec. Tw'etica Castiac e< 63-560 AC-Act w tw 1 SIS 10* 63-561 .1 AC-Act SIS 10" Ck Ck SA SA 2 2 ISI-0002-C 94-12892 Darling ISI-0002-C 94-12892 Darling ASTM A5161 p$ty yp 63-562 ASTM A516I PSIV 4 63-563 63-622 1 1 AC-Act AC-Act 2-Act SIS SIS SIS 10* 10" Ck Ck SA SA 2 2 ISI-4002-C 54-12892 ISI-0002-C 94-12892 Darling Darling ASTM A516I ASTM A5161 PSIV p3ty zg
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.I 10" Ck S4 2 ISI-0002-C 94-12892 Carling ASTM A516I PSIV 63-623 1 AC-Act SIS 10* Ck SA 2 ISI-0002-C 94-1289 Darling ASTM A5163 PSIV 63-624 1 AC-Act SIS 10* Ch 2 ISI-0002-C 94-12892 63-625 SA Darling ASTM A516I PSIV AC-Act SIS 10" ASTM A516 I 1
63-640 Ck SA 2 ISI-0002-C 94- 2892 Darling FSIV 1 AC-Act SIS /RHR 8" Ck SA 2 151 M 3-C 94-12892 Carling 63-643 ASTM A516I PSIV 1 AC-Act- SIS /RHR 8* Ck SA 2 ISI-4003-C 94-12872 Darling ASTM ASISI 63-553 AC-Act PSIV 1 SIS 6* Ck SA 3 ISI-0002-C 78704 Velan ASTM A182 PSIV Ferging 63-559 1 AC-4ct ' SIS 6* Ck 54 3 151-00C2-C 78704 Velan 63-632 ASTM A182 PSIV Forging 1 AC-Act SIS 6" Ck SA 3 ISI-0002-C 737C4 Velan 1 63-633 1 .AC-Act SIS 6* ASTM A182 PSIY Forging 63-634 Ck SA 3 ISI-0002-C 78704 Velan ASTM A182 PSIV Forging 1 AC-Act SIS 6" Ck SA 3 ISI-0002-C 78704 Velan 63-635 1 AC-Act SIS 6* ASTM A152 PSIV Forging 63-641 Ck 5A 3 ISI-0002-C 78704 Yelan ASTM A152 PSIV Forging < 1 AC-Act SIS /RHR 6* Ck 3 ISI-0003-C 78704 63-644 1 AC-Act SIS /RHR 6* Ck SA S4 3 ISI-0003-C 78704 Velan ASTM A182 PSIV Forging $ 68-563 1 C RCS 6* Re1 SA 4 ISI-0013-C H51688 Velan Crosby ASTM A152 PSIV Forging g ASTM A182/ See 68-564- 1 C RC* 6" Re1 SA 4 151-0013-C H51683 Crosby A3512 ASTM A182/ Ecte 2 See y is A35;2 Note 2 68-565 1 C RCS 6" Re1 SA 4 ISI-0013-C H51683 Crosby ASTM A182/ See Q os A35i2 Mate 2 FCV 74-1 1 -A-Act RHR 14" Gate MD 5 ISI-0003-C E-1-144331 Copes-Vulcan ASTM A152 PSIV Forging FCV 74-2 1 A-Act RHR 14' Gate PU 5 ISI-0003-C E-1-144331 Copes-Vulcan ASTM A182 PSIV Forging pTES: 2 Seal plate mantefactored to ASTM A240 F304 Body to ASTM A351 grade CF-8. Nozzle manttfactured to ASTM A182 F316 - Forging body manufactured to ASTM A351 CR3M - Casting N
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A77DCHMEN7 2 ' TABLE 2 CLASS 1 valve INFORMATION < SIZE SYS VLV N0 VALVE BOLTING VLV BODY wm-f!N) . TYPE ISI OWG NO VENDOR VENDOR DWG NO <- 2* >2* bTLOS IAI gg CYC 62-560 '2 CKV MSG-0003-C SH1 a< 1 CYC 62-561 2 EDWARD D-464529 R5 N/A N/A NONC R/A NN CKV MSG-0008-C SH2 EWARD D-464529 R5 N/A CVC 62-562 2 CKV MSG-0003-C SMS E NARD D-454529 R5 N/A N/A N/A NONE NONE h/A N/A NE CVC 62-563 CYC 62-554 2 2 CKY MSG-0003-C SH3 GATE MSG-0005-C SH1 EWARD D-464529 R5 N/A N/A NONE N/A *i o { EDWARD D-464532 R5 N/A N/A DONE N/A .. n CVC 62-565 2 GATE MSG-0005-C SH2 EW ARD D-464332 R5 N/A N/A NONE N/A " CVC 62-566 2 GATE MSG-0003-C Sh5 EWARD D-454532 R5 N/A N/A NONE N/A
~
CVC 62-567 7 GATE M W OOOS-C SH3 EDWARD D-464532 R5 N/A N/A lOME N/A CVC 62-576 2 CKV MSG-0003-C SH1 EWARD D-464529 R5 N/A N/A ' 7ONE N/A CVC 62-577. 2 CKV M5G-0008-C SH2 EWARD D-464529 R5 N/A N/A NONE N/A , CVC 62-578 2 CKY MSG-0003-C SH4 EDWARD D-454529 R5 M/A N/A NONE N/A CVC 62-579 2- CKY MSG.4008-C SMS EWARD 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 CVC 62-6602 3 CKY ISI-0009-C SE2 BORG-WARNER 80290 5/16* N/A N0rE N/A CYC 62-661 2 CKY ISI-0009-C SH2 EDWARD C 464529 R5 N/A N/A Nrygg M/A CVC 62-7162 3 CKY ISI-0009-C SH2 BORG-WARNER 80290 5/16" N/A NONE N/A CVC 62-7172 3 CKY ISI-0009-C SH2 BORG-WARNER 80290 5/16' N/A NOME N/A y RHR 63-543 2 CKY ISI-0003-C SH8 EWARD C-454529 R$ N/A N/A lote N/A t* RHR 63-545 2 CKY ISI-0003-C SHS EDWARD C-464529 R5 N/A N/A NOME N/A 515 63-547 2 CKY ISI-0002-C SM12 EWARD C-464529 R5 N/A N/A NONE N/A SIS 63-549 2 CKY ISI-0002-C SH12 EDWARD C-454529 R5 N/A N/A NONE N/A y SIS 63-551 2 CKV ISI-0002-C SH5 EDWARD C-464529 R5 N/A N/A NONE N/A te SIS 63-553 2 CKY ISI-0002-C SH6 EDWARD C-464529 R5 N/A N/A NONE N/A SIS 63-555 2 CKV 151-0002-C SH6 EWARD C-464529 R5 N/A N/A NOME N/A Q et SIS 63-55/ 2 CKY 'ISI-0002-C SH4 EDWARD C-464529 R5 N/A N/A NONE N/A SIS 558 6 CKV ISI-0002-C SH7 VELAN 78704 1 1/4" N/A NONE N/A sis.63-559 6 CKY ISI-0002-C SH7 VELAN 787D4 1 1/4" N/A fONE N/A SIS 63-560 1D CKY 'ISI-0002-C SHS ANCHOR / DARLING 94-12892 1 3/8" N/A NONE N/A I Integrally welded attachment. 2 Enempt from esaminatico requirements of Category 8-G-2 with Code Case N-426. 2 M.
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ATTAONEN7 2 TABLE 2 (Continued) CLASS 1 VALVE INFORfuTION SIZE SYS VLV N0 (IN) TYPE ISI WG NO VENDOR VALVE BOLTI% VLY BODY wm VENNut WG NO <- 2* >2* btLDS IA1 5g SIS 63-561 10 CKY ISI-0002-C SH6 ANC WPJDARLING 94-12892 1 3/8* N/A
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4 515 63-562 10 CKV DE F/A EU ISI-0002-C SH6 ANCHOR /DARLIE 94-12892 1 3/8* N/A NONE N/A SIS 63-563 10 CKY ISI-0002-C SH4 ANCHOR /DARLI M 94-12S92 1 3/8" N/A NONE N/A g t= SIS 63-5812 o-{ 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 SMS ROCKWELL INTERNATIONAL D-478072 N/A N/A SIS 63-583 1 1/2 GATE ISI-0002-C SH9 ROCWELL INTERNATIONAL D-478072 N/A N/A NONE IONE N/A N/A
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- 515 63-5B1 1 1/2 GLTE ISI-0002-C SH10 ROCKWELL INTERNATIONAL D-478072 N/A N/A NONE N/A SIS 63-585 1 1/2 GATE ISI-0002-C SH11 ROCWELL INTERNATIONAL D-478072 N/A N/A NONE N/A SIS 63-586 1 1/2 CKY ISI-0002-C SMS EWrRD C-465347 R2 N/A N/A 90NE N/A SIS 63-587 1 1/2 CKV ISI-0002-C SH9 - EWARD C-465347 R2 N/A N/A NOME N/A SIS 63-588 1 1/2 CKY ISI-0002-C SM10 EWARD C-455347 R2 N/A N/A NONE N/A SIS 63-589 1 1/2 CKY ISI-0002-C SH11 EEVARD C-465347 R2 N/A N/A NONE N/A
$15 63-622 10 CKY ISI-0002-C SH5 ANCHOR /DARLI C 94-12892 1 3/8* N/A NOME N/A SIS 63-623 10 CKY ISI-0002-C SH6 ANCH09/ DARLING 94-12392 1 3/8* N/A NONE N/A SIS 63-624 10 CKV I%I-6002-C SH6 ANCHOR / DARLING 94-12892 1 3/8* N/A NONE N/A SIS 63-625 10 CKY ISI 4002-C SH4 ANCHOR / DARLING 94-12892 1 3/8* N/A NONE N/A SIS 63-632 6 CKY ISI-0002-C SH6 VELAN 7B704 1 1/4* N/A NONE N/A SIS 63-633 6 CKY ISI-C002-C SHS VELAN 78704 1 1/4" N/A NONE N/A N
t* 515 63-634 6 CKV ISI-0002-C SH6 YELAN 78704 1 1/4" N/A SIS 63-635 6 CKY ISI-0002-C SH4 VELAN 78704 1 1/4* M/A NONE NONE fn/A N/A h RHR '63-640 8 CKV ISI-0003-C SHS ANCIOR/ DARLING 94-12892 1 3/8* N/A N/A
'RHR 63-641 6 CKY ISI-0003-C SH5 VELAN 78704 1 1/4* N/A NOME N/A N
NGNE OF RHR 63-643 8 RHR 63-644 6 CKY ISI-000%C SH6 ANCIOR/ DARLING ' CKY ISI-0003-C SH6 YELAN 94-12892 78704 1 3/8* M/4 1 1/4* N/A WJNE NONE N/A N/A k U2 RCS 68-549 2 GATE ISI-0013-C SH10 E WARD D-464532 N/A N/A MONE N/A ' RCS 68-550 2 L fE ISI-0013-C SH10 EDWARD D-464532 N/A N/A NONE N/A RCS 68-553 2 GATE ISI-0013-C SH10 EITJARD D-464532 N/A N/A ENE N/A RCS 68-554 2 GATE ISI-0013-C SH10 EDWARD D-464532 N/A N/A NONE N/A I Inte9 rally welded attactment. 2 Enempt from emanination rvquirements of Category 8-G-2 with Code Case N-426. 4 a b M o8L y .y
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ATTACmENT 2 TABLE 2 (Continued) CLASS 1 VALVE INFORM TION SIZE SYS YLV N0 FIN) VALVE BOLTING VLV BCDY w es TYPE ISI M NO VENDOR YENDOR M NO <
- 2* >2* WELUS IAT gg RCS 68-557 +4 <
2~ GATE ISI-0013-C SH11 EWARD D-464532 N/A N/A N/A RCS 68-558 2 GATE ISI-001I-C SH11 EWARD D-464532 N/A N/A NOME NONE N/A EO r) t* RCS 68-563 6 RELF ISI-0013-C SH3 CROSBY H-51688 1* N/A RCS 68-564 NONE N/A 6 RELF ISI-0013-C SH3 CROSBY H-51683 1* N/A NONE M/A do "E RCS 68-565 6 RELF ISI-0013-C SH3 CROSBY H-51653 1* M/A NONE M/A CYC 68-580 3 CATE ISI-0009-C SH1 YELAN T3920 N/A N/A NOME N/A Q RCS 68-581 2 GATE ISI-0013-C SH11 EWARD D-464532 N/A M/A fore M/A Pr5 68-582 2 GATE ISI-0013-C SM11 EDWARD D-464532 N/A N/A NOME N/A WC FCV-62-692 3 GATE ISI-0009-C SH1 M SONEILAN/WORTHINGTON CPI-1855,AS425 7/8" N/A NONE N/A CVC G4TE ISI-0009-C SH1 M SONEILAN/WORTMINGTON CPI-1855,A84757 7/8" N/A FCV-62-7%23GATE CVC FCV-62-84 ISI-0009-C 542 MSONFILAN A-8474,A-6475 NONE N/A 7/8' M/A NOME M/4 RCS FCV-68-3322 3 GATE ISI-0013-C SH3 VELAN 02-405-0494-2 3/4* N/A NONE N/A RCS FCV-68-3332 3 GATE . ISI-0013-C SH3 VELAN 02-405-0494-2 3/4* N/A WJNE M/A RHR FCV-74-1 .~4 GATE ISI-0003-C SH7 COPES-VULCAN E-1-144831 R4 1 3/4" N/A NONE N/A RHR FCV-74-2 14 GATE ISI-0003-C SH7 COPES-VULCAN E-1-144831 R4 1 3/4* N/A NONE N/A UHI FCV-87-7 2 GATE ISI-0001-C SHZ COPES-VULCAN L-170203 R2 1 1/8* M/A NONE M/A iMI FCV-87-8 2 GATE ISI-0001-C SH1 COPES-VULCAN L-170203 R2 1 1/8" N/A DONE N/A 4 RCS PCV-68-34002 4 BALL ISI-0013-C SH1 FISHER RCS PCV-68-340A 3 GLB ISI-0013-C SH3 'TARCET ROCK 50A2159 7/8" N/A PONE N/A b 1052020-3 R/A N/A NOME M/A N RCS PCV-68-34082 4 BALL ISI-0013-C SHI FISHER 50A2159 7/3' N/A NONE N/A RCS PCV-68-334 3 GLB ISI-0013-C SH3. TARGET ROCK 1052020-3 M/A N/A NOME M/A i; m a-I Integrally welded attachments. 'l 2 Enempt from eranination require %tnts of Category B-G-2 in accordance with Code Case N-426. l
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ATTADiMENT 2 1ABLE 3 CLASS 2 VALVE INFORMATION SIZE- VALVE BOLTING VLV B00Y wM SYS VLV N0 (IN1 TYPE ISI DWG NO IAI VENDOR VENDOR OWG NO < = 2* >2* kTtOS @$ H< MS FCV-1-4 32 GATE ISI-0015-C SH1 ATWOOD & MDRRILL CD 21245-H 2* MS FCV-1-11 32 GATE ISI-0015-C SH2 ATV000 & MDRRILL CD 21245-H 2* N/A N/A FONE NONE N/A N/A EU OP MS FCV-1-22 32 GATE ISI-0G15-C SH2 ATV000 & f0RRILL CD 21245-H 2* N/A NONE N/A NU w MS FCV-1-29 32 GATE ISI-0015-C SH1 ATV000 & MDRRILL CD 21245-H 2* N/A NOME N/A O MS 1-619 MS 1-620 6 6
~ GATE GATE ISI-0015-C SH1 WALWORTH ISI-0015-C SH2 VALWORTH A-6609-W12SB A-6609-W1288 7/8*
7/8* N/A N/A NONE NOME N/A diA
*O MS 1-621 6 GATE ISI-0015-C SHZ WALWORTH A-6609-W 1288- 7/8* N/A NONE N/A MS 1-622 6 GATE ISI-0015-C SH1 WALWORTM A-6609-W 1238 7/B* N/A NCNE N/A MS 1-512 6 SAF ISI-0015-C/2 CROSBY W55095 1 3/8" N/A NONE N/A MS.1-513 6 SAF ISI-0015-C/2 CROSBY W55095 1 3/8" N/A NONE N/A MS 1-514 6 SAF ISI-0015-C/2 CROSBY W55095 1 3/S* N/A IONE N/A MS 1-515 6 SAF ISI-C015-C/2 CROSBY W55095 1 3/8" h/A NONE N/A MS 1-516 6 SAF ISI-0015-C/2 CROSEY H-55095 1 3/8* N/A NONE N/A ~S M 1-517 6 SAF ISI-0015-C/2 CROSBY W55095 1 3/B* N/A NONE N/A MS 1-518 6 SAF ISI-0015-C/2 CROSBY W 55095' 1 3/8* N/A NONE K/A MS 1-519 6 SAF ISI-0015-C/2 CROSBY H-55095 1 3/8* N/A NOME N/A MS 1~520 6 SAF ISI-0015-C/2 CROSBY H-55095 1 3/8" N/A NOME N/A 4 y
MS 1-521 6 SAF ISI-0015-C/2 CROSBY W55095 1 3/S* N/A NONE N/A F MS 1-522 6 .SAF ISI-0015-C/1 CROSBY. W 55095 1 3/8" N/A PONE N/A N MS 1-523 6 SAF IS W W C/1 CROS8Y H-55095 1 3/8* N/A PONE N/A MS 1-524 6 g SAF 1sI-00T M CROSBY H-55095 1 3/8* N/A NONE N/A p. . MS 1-525 6 SAF ISI-0015-C/1 CROSBY H-55095 1 3/8' N/A NONE N/A m '$ MS 1-526 6 SAF ISI-0015-C/1 CROSBY W55095 1 3/8* N/A NOME N/A E MS 1-527 6 SAF ISI-0015-C/1 CROSBY W55095 1 3/8- N/A NONE N/A m MS 1-528 6 SAF ISI-0015-C/1 CROSBY W55095 1 3/8* N/A NONE N/A MS 1-529 6 SAF ISI-0015-C/1 CROSBY H-55095 1 3/8* N/A NONE N/A MS 1-530 6 SAF ISI-0015-C/1 CROS8Y W55095 1 3/8* N/A NONE N/A "5 1-531 6 SAF ISI-0015-C/l CROSSY W55095 1 3/8" N/A PONE N/A MS. PCV-1-5 6 GATE ISI-0015-C SH1 COPES-VULCAN B-149093 R7 Yes N/A NONE N/A I Integrally welded attactwent. 1 12.
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ATTAtie'ENV 2 TABLE 3 CLASS 2 VALVE sNFORMATION SIZE SYS- VLV NO (IN) TYPE VALVE BOLTING VLV BOOT +
- in ISI DWG NO VENDOR <= 2*
VENDOR tvG NO >2* VELD 5 IAI 5$ MS PCV-1-12 6 GATE +4 <: ISI-0015-C SH2 COPES-VULCAN B-149093 R7 Yes N/A N/A MS PCV-1-23' 6 MS PCV-1-30 G8TE 15I-0015-C SH2 COPES-VULCAN B-149C33 R7 Yes N/A NONE MONE N/A E" 6 G*TE 151-0015-C SM1 COPES-VULCAN B-149093 R7 Q t* Yes N/A N/A W FCV-?-33 W FCV-3-47 18 18 GATE GATE CHM-2403-C SH1 WALWORTH CHM-2403-C $P2 WALWORTH A-6614-M-150 A-6614-St-150 1 1/2* 1 1/2* M/A NONE NOME N/A o{ W ' FCV-3 18 GATE CHM-2403-C SHZ WALWORTH A-6614-M-150 1 1/2* N/A N/A NONE NONE N/A N/A
*O W FCV-3-100 18 GATE CHM-2403-C SHI WALWORTH A-6614-M-150 1 1/Z* N/A FV 3-50S 16 CKV NONE N/A CHM-2403-C SH2 WALWORTH A-11332-M-32A 1 3/4* N/A NONE N/A W 3-509 16 CKY CHM-2403-C 5H2 WALWORTH N 3-510 16 CKY A-11332-M-32A 1 3/4* N/A ' NONE N/A CHM-2403-C SH1 WALWORTH A-11332-M-32A 1 3/4* N/A NONE N/A N 3-511 16 CKV CHM-2403-C SH1 VALWORTH RHR 74-514 8 CKY A-11332-fl-32A 1 3/4* N/A IONE N/A ISI-0003-C SHZ CRANE K-7422 7/8* N/A IONE N/A RHR 7A-515 8 CKY 'ISI-0003-C SH3 CRANE K-7472 RHR 74-520 ' 8 1/B* N/A NONE N/A GATE ISI-0003-C SH2 ALOYCO RHR 74-521 8 E-47381 3/4* M/A NOME N/A GATE 151-0003-C SH3 ALOYCO RHR 74-524 8 GATE E-47381 3/4" N/A NONE N/A ISI-0003-C SH2 ALOYC0 E-473St 3/4" N/A NONE N/A RHR 74-525 8 GATE ISI-0003-C SH3 ALOYCO RHR FCV-63 18 GATE E-47381 3/4* N/A NONE N/A [
RHR FCV-63-73 18 15I-0003-C SH1 ANCHOR / DARLING 94-13300 1 1/4" NK. MONE N/A t* GATE ISI-0003-C SH1 ANCHOR / DARLING RHR FCV-63-172 12 GATE 94-13300 1 1/4" N/A NONE N/A N ISI-0003-C SHS VELAN 88907-2 1 7/8* N/A NONE N/A RHR FCV-74 14 GATE 15I-0003-C SH4 ANCHOR /DAPLI E 94-13298 1 1/S* N/A RHR FCV-74-15 8 BUTF 151-0003-C SH2 FISHER GOVERNOR CD F-41304 5/8* N/A NONE NONE N/A N/A h t8 RHR FCV-74-21 14 GATE RHR FCV-74-28 8 151-0003-C SH4 ANCHOR / DARLING 94-13295 1 T/8" N/A NONE N/A E RHR FCV-74-32 8 BUTF -15I-0003-C SH3 FISHER GOVERNOR CD BUTF F-41304 5/8* N/A NONE N/A to RHR FCV-74-33 8 GLOS ISI-0003-C SH2 FISHER GOVERNOR CD F-41304 5/8* N/A NONE N/A RHR FCV-74-35 8 ISI-0003-C SH2 ANCHOR / DARLING 93-13435 3/4* N/A NONE N/A GATE ISI-C003-C SH3 ANCHOR /DARLI M 93-13435 3/4* N/A IONE N/A RHR HCV-74-34 8 GATE 151-0003-C SH3 ANCHOR / DARLING 93-13435 3/4* N/A NONE N/A I Integrally welded attachment. o w in 337
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SURVEILLANCE R3visiten 2 - INSTRUCTION REQUESTS TOR RELIEF Page 1 of 44 k -p i ASME Section II Programs l A. MAINTAIN a listing of Requests for Rollef. i B. UPDATE listing as necessary. C. OBTAIN concurrence from Site Quality Manager or his designee. SOM D. CONCUR with listlng by signing below. ASME Section XI Programs l E. FORWARD to SPS for updating Table of Contents, etc. SPS T. FORWARD to DCRM. DCRM G. DISTRIBUTE per SSP-2.7. Y /- 13l/hp Site Quality Manager / Designee Date 1406C/C0C3
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E SI-114.2, Attechm nt 3 SURVEILLANCE R3 vision 2 INSTRUCTION REQUESTS FOR RELIEt Page 2 of 44 i
} REOUEST FOR RELIEF 151-1 f
1 I Components: Reactor coolant pumps (four per unit) I C1333: ASME Code Class 1 (Equivalent) runction: Circulates reactor coolant Inapection Requitrarmit ASHE Section XI, Table IWB-2500-1, examination ; catagory B-L-2, item No. B12.20, visual examination ' of pump internal pressure boundary surface. - Dasis for Relieft In absence of required maintenance, disassembly of a reactor coolant pump solely to perform a visual examination of internal surfacea is impractical. This would represent an unnecessary employee exposure to high radiation and contamination arent 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 Jnternal dose rates will
- average 10 to 20 rem / hour.
The benefit received from this major effort is 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 disasssmbled for maintenance during a ten-year interval, the visual examination performed will be representative of the pump condition for each uait. 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 examination performed satisfies examination category B-L-2 requirements for both units. ' Disassembly of the pump solely for visual examination is impractical. 1406C/COC3
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3 St.114.2, Attechment 3 , SURVEILLANCE R0VisiCn 2 ! INSTRUCTION REQUESTS FOR RELIEF page 3 of 44 ; t [ REQUEST POR R.ELittlSI .1 (Continued) Alteniste Inspsttinn The internal surface _of the reactor coolant pump casing will be visually examined whenever the surfaces are nede accessible when a pump is disassembled for maintenance purposes. If during the ten-year interval a pump f rom either unit is not disassembled for malutenance, a pump from one unit shall be examined from the exterior. This shall be accomplished by ultrasonic thickness measurements of ' the pump casing. Rafety Evnly311gn Summary } Request for Relief 181-1 has been approved with the f ollowing additional ' augmented requirements: (a) The required visual examinations are conducted under Category B-L-2 Af a reactor coolant pump from one of two units is disassembled for maintenances (b) If during the 10-year interval, a pump f rom either unit is not disassembled for maintenance, a pump f rom one unit shall be exam).ned f rom the exterior by ultrasonic thickness measurements; (c) Visual examination of the pump casing for leakage is- conducted in conjunction with system leakage and hydrostatic tests under Category D.P. References Memorandum from T. J. Hebdon, NRC, to 0. D. Kings. ley, TVA, dated February 7, 1991 (A02 910211 001). Hemorandum from Susanne Black,-NRC, to O. D. Klugsley, TVA, da:.sd I April 19, 1990 (A02 900426 005). 1406C/COC3
EI-114.3, Attcchmsnt 3 SURVE!LLAh*CE R3 vision 2 INSTRUCTION REQUESTS TOR RELIEl Page 4 of 44 i 1- EgourcT roR RgLIEF ISI-2 '
\
CDEP2ntnts: Valves exceeding four. inch nominal pipe size Clata ASKE Code Class 1 (Equivalent) ' EEREt12D Various functions ID2gettisn Requirxmants ASME Section XI, Table IWB-2500-1, examination category B-H-2, item No. B12.40, visual examination , of valve internal pressure boundary surface. ' JJaala.LQI_Relitf During routine maintenance, visual examinations of valve body internal pressure boundary surfaces are performed and documented under existing plant administrative procedures. Most Class 1 valves, particularly containment isolation valves, are disassembled frequently for maintenance. In addition, the two units et Sequoyah Nuclear Plant will operate under similar conditions. If a valve 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 examination requirements for both units for that particalar valve classification as defined in examination category B-M-2. . We conclude that if one valve in each group of valves of the same constructional design and manufacturer that perform similar functions in disassembled from either knit during the ten-year interval, the visual examination performed satisfies examination category B-H-2 requirements of both units. Al!.ttnate InantatiSD: If a valve from a particular classification has not been disassembled as the end of the inspection interval approaches, a case-by-case study will be made to determine the practicality of disacsembling a valve from one of the units solely for visual examination (determine if draining the vessel would be required, etc.). If necessary, a request for relief will be issued at that time. (Continued) ' 1406C/COC3
I 51-114.2, Attachmont 3 ! SURVEILLANCE Revision 2 INSTRUL' TION REQUESTS FOR RELIEF Page 5 of_44 - S 4 i' ' REOUEST FOR RELIEP'ISI-2 (Continued) Sh[nty. Evaluation Streary: Request for Relief 15!-2 has been approved with the following additional augmented requirements (a) one comparable valve in either unit is exami od. 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 T. J. Hebdon, NRC, to 0. D. Kingsley, TVA, dated February 7, 1991 (A02 910211 001). Memorandum from Susanne Black, NRC, to 0. D. Kingsley, TVA, dated April '19, 1990 (A02 900426 005). t h 1406C/COC3
EI-114.2, Attachment 3 ! SURVEILLANCE Rovision 2 INSTRUCTION REQUESTS FOR RELIEF Page 6 of 44 d. i f EEQUEST TOR RELIEP ISI-3 CatP_2nents: Pressure-retaining welds in piping ' ClD11: ASME Code Class 1 and 2 (Equivalent) FunctlRD: Pressure-retaining component Inipection Reuulrement ASME Section XI, Table IWB-2500-1, examination categories B-F (item No. B5.50), B-J (item 1%s. B9.10, B9.20, and 39.30), and C-F (item Hos. C5.10, C5.20, and C5.30), volumetric examination of longitudinal, circumferential, and pipe branch connection velds. Basis for Relle{s In some cases it will be impractical to inspect all welds from both 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 request for relief. Alternate Inspection In addition to the visual examination performed during system leakage and hydrostatic pressure tests, a "best ef fort" ultrasonic examination and a surf ace
' examination will be performed on accessible areas of the weld (s).
Where there is interference or problems from one direction only, consideration will be given to performing an angle beam examination for 2T + (greater than two wall thicknesses from one edge of weld) from the accessible side of the weld in order to examine the entire weld cross-section. < 03{pfy Evaluation Summary: Request for Relief ISI-3 has been approved in the following manner: Eram cateoory B-F Approved with no edditional augmented requirements. B-J A? proved with a stbstitution for Safety Injection Weld SIF-128 Weld RC-33 has been substituted for SIF-128 for inspection during this interval. References -Memorandum from F. Ji Hebdon, NRC, to 0. D. Kingsley, TVL, dated February 7, 1991 (A02 910211 001). Memorandum from Suzanne Black, NRC, to 0. D. Kingsley, TVA, dated April 19, 1990 (A02 900426 005). 1406C/COC3 i
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REQUEST FOR RELIEF ISI-3 (Continued) w en A_tly1Wt A Ek UN CM WELD OE -! NUM3ER 11ZE CA_T2 !%_IL DRAWING NUMBER PHYSICAL CCOE .b O CONFIC4FATION SCAN / LIMITATIONS 5[#! REMMlv5 *O RHRF-125 6' 8-J SS ISI-0003-C Norrie/ Elbow 4/No scan 83% No scan 4 due to norrie geometry (Sheet 5) 3/No scan 5:00-7:00 No scan 3 from S:00-7:00 due to inner radius - RCF-23 4* B ,3 $$ ISI-0013-C Elbow / Safe-end 4/No scan 75% No scan 4 due t6 safe-end geometry
.(Sheet 1) 3/ Limited scan Scan 3 Ilmited by inner radius of elbow RCW-29 SE 14" 8-F SS/CS ISI-0308-A Norrie/ Safe-end 3/ Limited at 901 Scan 3 timited by 1* WGS at 12:00, (Sheet 1) 12:00, 3:00, 3:00, 6:00, and 9:00 m 6:00 and 9:00 No scan 4 due to norrie geometry 4/No scan t1 SIF-128 10" 8-J SS ISI-0002-C Valve / Tee 3 and 4/No scan 0% No scan 3 and 4 due to valve- N (Sheet 4) to-tee geometry
- RCW-24 SE 4" 8-F - $$/CS ISI-0308-A Norrie/ Safe-end 4/No sean 40% No scan 4 due to safe-end geometry o (Sheet 1) 3/ Limited Scan 3 Ilmited by ner:1e curvature "
RC-3 31" B ,3 151-0008-8 fg SS Safe-end/ Elbow 3/No scan 50% No scan 3 due to norrie geometry 4/1/2 node RC-1 S2 29
- 8-J SS 151-0008-8 Pipe / Elbow 3/ Limited 9:30 98% Scan 3 limited by one inch norzies w and 10:30 at 9:30 and 10:30 RC-2 29* 8-J $$ ISI-0003-8 ELL-SE No scan from 50% No scan due to nettle geometry norrie side RC-2-SE 29" 8-F SS ISI-0008-8 SE-Mctrle ' No scan from 50% No scan due to nozzle geometry norrie side
$ RC-3-SE 31" 8-F $5 'ISI-9008-8 Norste-SE No scan from a
50% No scan due to norrie geometry ywm norrie side 29" y ,< L RC-10 B-J $$ 151-0008-8 ELL-SE No scan from 501 No scan due to nortle geometry o norrie side ag
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62-114.2, Attachment 3 ! SURVEILLANCE R0 Vision 2 ; INSTRUCTION REQUESTS TOR REL!E' Page 9 of 44 s i REOUEST FOR HELIEF ISI-3 (Continued)- NOTES: 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. PcPipe, V= Valve, EsELL, T= TEE, R= Reducer, T=Tlange, H=Nossle, Pen P= Penetration Process Pipe, Pen FmPenetration T1ued liead, and SErSafe End
- 5. Scans 3 and 4 are perpendicular to circumferential welds.
Scans 5 and 6 are parallel to circumferential weJds. Scans 7 and 8 are perpendicular 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 coverage obtained.
- 8. Because of tha attenuation resulting from inherent coarse grain structure in cast stainless steel the examination is limited to the 1/2V techulgue. Also physical. restrictions prevent the exam from both sides of the weld.
- 9. Detail description of limitations are noted.
e (= L 1406C/COC3
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SI-114.2, Attcchm3nt 3 SURVEILLANCE Rovision 2 INSTRUCTION REQUESTS TOR RELIEr Page 10 of 44 l RIDutsT rog_ggLIrr Isi-4 {' Campantnis Steam generator (four per unit) CIAAll ASME Code Class 2 (Equivalent) Inspection Reguirements ASME Section XI, Toole IWB-2500-1, examination category C-A, item No. C1.10, volumetric examination of circumferential shell welds. Basis for Relltf One circumferential shell weld on each generator is inaccessible due to the upper steam generator support brackets (weld Non. SGW-D1, -D2, -D3 end -D4). See attached drawing CH-M-2345-B for veld location. .-Also attached drawing CH-M-2345-B for weld location. Also attached are drawings showing arrangements of the
-support brackets. One weld on one generator will be 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 insptetion: Hone EAfety Evaluation _Enamaryt- ' Request for Relief ISI-4 has been approved with no additional augmented requirements. Reference Hemorandum from T. J. Hebdon, HRC, to 0. D. Kingsley, TVA, dated Tehruary 7, 1991 (A02 910211 001). Hemorandum from Suzanne Black, NRC, to 0. D. Kingsley, TVAi dated ~ April 29, 1990 (A02 900426 005). 9 5 1406C/COC3
SI-114.2, Attcchm:nt 3 SURVEILLANCE Revision 2 INSTRUCTION REQUESTS FOR RELIE/ Page 11 of 44 RIQUEST FOR RELIEF _ISI-S Camponent Reactor Pressure Vessel i R2A11: ASKE Code Class 1 (Equivalent) Inapartion Reguirement: ASKE Section XI, Table INB-2500-1, examination category B-A, item No. Bl.20, 200-percent preservice baseline volumetric examination of lower head dollar veld, under conditions and with equipment and techniques equivalent to those expected to be employed during inservico inspection. Satis __for Rglig[ TVA vill employ automated remote inspection devices to examine most of the reactor vessel welds. These examinations will be conducted from the vessel 8uside diameter. However, the lower head eeld on each reactor pressure vessel is partie .y inaccessible for examination from the vessel inside diameter due to instrumentation tubes which penetrate the lower head (weld No. WO1-02). Portions of the weld can be examined from one side (as permitted by T-441.3.2.4, Article 4 of Section XI) and will include 100 percent of the examination volume in accordance with Table IWB-2500-1 and June IRB-2500-3 of Section XI. These portions of the weld will be reexamined during the inservice intervals in accordance with the examination category B-A of Table IRB-2500-1. Alternnte Inspection A 100-percent baseline examination of the wold will be conducted from the vessel outside dimneter.- This-will be accomplished by performance of a manual ultrasonic examination. A remote ultrasonic examination will be conducted f rom the vessel inside diameter on all accessible areas of the weld. Safety _Iypluation Summary
- Request for Relief ISI-5 has been approved with no additional augmented requirements except to notify NRC of the percentage examined.
Reference:
Memorandum from F. J. Hebdon, NRC, to 0. D. Kingsley, TVA, dated February 7, 1991 (A02 910211 001). Memorandum from Susanne Black, NRC, to 0. D. Kingsley, TVA,' dated April 19, 1990 (A02 900426 005). 1406C/COC3
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. SI-114.2, Attachment 3 SURVEILLANCE Revision 2 INSTRUCTION REQUESTS FOR RELIT? Page 12 of 44
{- , j BEQUISI_IOR RELIEP 151-6 t t CDEp2 Rani Steam Generator (four per unit) C1311: ASME Code Class 1 (Equivalent) IrutptgL19D Enquittaint: ASME Section XI, Table IWD-2500-1, examination category B-D, item so. B3.140, volumetric examination of nozzle inside radius section on the primary side. RAE11_fgI_pelief: Each atoam generator consists of two integrally cast nozzles and two integrally cast manways. Relief from the inspection requirement above is based on EPRI report NP-4242, "Long-Term Inspection Requirements for Nuclear Power Plants", dated March 1986. This report presents a linear f racture mechanics analysis which predicts that cracks of size '.025 inch (which , is greater than the allowabic reference flow slie) will propagate to only slightly greater than one [ sixteenth of the nozzle wall thickness during the entire life of the plant. The report proposes that the nosale inner radius be examined at least at half the plant life, and subsequently, at the regular code - inspoetioti intervals. The primary chamber radiation exposure dose rate is genera 11y'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 aurface and visual examinstions 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 i cladding cracking which would not be visible with a surface examination. AlicInste Insptstlant TVA will initiato examination of the steam generator nossle inner radius sections in accordance with the applicable Section XI. Code during_the second inspection interval ~. This will~ provide for examination of all the- steam generator nozzle inner radii by the period ending at half the plant life. P (Continued)~ 1406C/COC3
SI-114.2, Attachmant 3 . SURVEILLANCE Revision 2 INSTRUCTION REQUESTS FOR RELIET Page 13 of 44 I f BEOUEST FDP PELIEF ISI-6 (Continued) Enfety Evaluation Sygegry: Request for Rollef ISI-6 has been approved in the following manners (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.
Reference:
Memorandum from F. J. Nobdon, NRC, to 0.' D. Kingsley, TVA, dated February 7, 1991 (A02 910211 001). Memorandum from' Suzanne Blace,.NFC, to 0. D. Kingsley, TVA, dated April 19, 1990 (A02 900426 005). t t f k I e l l 1406C/COC3- -
SI-114.2, Attachment 3 SURVEILLANCE Revision 2 INSTRUCTION REQUESTS FOR RELIEF Fage 14 of 44 REQUEST FOR RELIEF IEI-7 Component Reactor Coolant Loop Piping Welds (2) Clata: ASKE Code Class 1 (Equivalent) InArzgtlon_ Requirement: ASME Section XI, IWB-2500-1, examination category B-J, item No. B9.10, volumetric examination of circumferential welds.- Eggjs for Re11el Two circumferential shell welds in the reactor coolant loop piping (RC-23S1 and -3151, loops.3 and
- 4) are located inside the reactor vessel shleid wall and are inaccessible for baseline and inservice examination (see attached drawings). Both welds have undergone shop radiographic examinations. Since the baseline inspection serves as a reference to future i inservice inspections and both welds will be inaccessible for inservice inspections, the shop radiographic examinations coupled with the Section III hydrostatic test will provide adequate .
proof of integrity of the system welds. Inservice system _ leakage and hydrostatic testing will prove-weld integrity during tne life-of the plant. ; Alternate In&IAlt1RD: None Safety.Ev.gluation Summary: Roguest for Relief ISI-7 is not necessary at this time. Rollef should not be requested until the fourth inspection interval'ISI Plan is made.
Reference:
Memorandum from F. J. Hebdon, NRC, to 0. D. Kingsley, TVA, dated- ' February 7,_1991 (A02 910211 001). Memorandum from Susanne Black, NRC, to 0. D. Kingsley, TVA, dated April 19, 1990 (A02 900426 005). i 1406C/COC3
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S!-114.2, Attechm3nt 3 SURVEILLANCE Rovision 2 , INSTRUCTION REQUESTS FOR RELIE* Page 1$ of 44 { t PIQUEST FOR R E!ET..I M -; 50!! Unit 2 reactor coolant pump casings do not contain pump casing welds. Request for Relief 182 8 is only applicable to Sequoyah Unit 1. Cptpangnt Reactor coolant pumps (four per unit) : CIAAAt ASME Code Class 1 (Equivalent) Inspfatlan Enguilletatt ASME Section XI, !WB-2500-1, examination category B-L-1, item No. B12.10, volumetric examination of ' pressure-retaining welds in pump casing. Dai1LioLFelief: Each reactor coolant pump casing consists of a two-piece welded type 304 SST casting. The present capability of ultrasonic testing is act sufficient to examination cast material of this thickness and achieve meaningful results. Alternate Inspections All four velds will be surface examined for the preservice baseline, and one veld will be surface examined during each inspection interval. References Memorandum from T. J. Hebdon, NRC, to 0. D. Klugsley, TVA, dated Tobruary 7, 1991 (A02 910211'001). Memorandum from Susanne Black, NRC, to 0. D. Kingsley, TVA, dated April 19, 1990 (A02 900426 005). i l S-
- - 1406C/COC3 A
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S1-114.2, Attcchm3nt 3 SURVEILLANCE R3 vision 2 INSTRUCTION REQUESTS FOR RELIEF Page 16 of 44 f i d' EEQUIST TOR RELIEF ISI-9 ) Cternatn.t: Uncladded vessel welds in ferritic material less than ' two inches in thickness. ClA11: ASME Code Class 1 and 2 (Equivalent) Inspiclinn E1221reteent: Ultrasonic examination of welds, paragraph T-530 of ASME Section V, Article 5, 1977 Edition, Summer 1978 Addenda as referenced in paragraph IHA-2232 (c) of ASME Section XI 1977 Edition Summer 1978 Addenda. DAsin for Relief: Paragraph T-533.2(a) of Article 5 of ASME Section V requires that the basic calibration block include a basic calibration hole drilled parallel to the contact surface. Hotrever, 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 side-drilled holes, TVA considers that examinations are technically acceptable based on the calibration requirements of paragraph III-3430 of Appendix III to-the 1977 Edition, Summery 1978 Addenda of ASME Section XI. The calibration notches for ferritic material are 10%t when t is 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.
Alternate Inspe.ntinas 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 refluctors. Salety Evaluation Summary: Request for Relief ISI-9 has been approved with no additional augmented requirements. References 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, 1940 (A02 900426 005).
.1406C/COC3
6 SI-114.2, Attechm3nt 3 SURVEILLANCE R3 vision 2 INSTRUCTION REQUESTS FOR RELIEF page 17 of 44 EEQUEST roR.RELIEr ISI-10 RgEponents: Reactor vessel flange to upper shell weld CIA 1A: ASME Code Class 1 (Equivaltat) Insp.21 tion Requirements ASME Section XI, Table IWD-2500-1, examination category B-A, item No. Bl.30, volumetric from flange face Basis for Felief The reactor vessel flange-to-upper shell weld is located behind the core barrel and is therefore inaccessible until the core barrel la 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 veld as a roactor vessel shell weld. We have reviewed the Sequoyah Reactor Vessel Stress Report entitled Analysis of the Main Closure Including Core Support Ledge (Document , No. 30616-1105) purposely to determine a fatigue 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 weld and base material to be homogeneous and' equal in elasticity, strength, and fatigue properties. Instead, the analysis provides usage ' factors at critical locations. The maximum fatigue usage factor in the vessel in the vacinity of the flange to shell weld as found in the above analysis is 0.00662 and this value can be conservatively used for the weld. He consider the valve of 0.00662 to_be extremely low compared to the code allowed fatigue usage factor of 1.0. We conclude that the distance (41.9") from the flange face to the flange-to-upper shell weld coupled with
-present ultrasonic techr.iques and the very low fatigue usage factor that the flange-to-upper shell weld should be treated as a reactor vessel shell weld.
Alternatt_Jngsgat1 Ant A remote ultrasonic exanination of the weld will be , conducted from the vessel inside diameter ner,r the ! end of' the inspection interval. l (Continued) l p I 1 1406C/COC3
SI-114.2, Attachment 3 SURVE!LLANCE R3 vision 2 INSTRUCTION REQUESTS FOR RELIEF Page 18 of 44 s [ REOUEST TOR RELIEF 1f1-10 (Continued) Bafety Evaluation Summary Request for Relief 151-10 has been approved with no additional augmented requirements. Reference Hemorandum from F. J. Hebdon, NRC, to 0. D. Kingsley, TVA, dated rebruary 7, 1991 (A02 910211 001). > Memorandum from Susanne Black, NRC, to 0. D. Kingsley, TVA, dated. April 19, 1990 (A02 900426 00$). f e
+
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. SI-114.2, Attcchment 3 SURVEILLANCE R; vision 2 2NSTRUCTION- REQUESTS FOR RELIEF Page 19 of 44 i
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! FIQUIST FOR RELIEF 151 g (Withdrawn) 4 b
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i' SI-114.2, Attechment 3 SURVEILLANCE McVision 2 INSTRUCT 20N REQUESTS FOR PELIL? Page 20 of 44 .- F10VIII..IDJL,RIkigr 1sI-12 This Request For Relief was not needed. See NRC ' Safety Evaluation Report dated February 7, 1991 (A02 910211 001). C2cp2Rania: $
- 1. Excess Letdown Heat Exchanger - Chemical and i Volume Control System (CVCS) 4
- 2. Regenerative Heat Exchanger - CVCS l i
CIAEAl ASME Code Class 2 (Equivalent) In3Pfalinn_Enguirement: ASME Section XI, Table IHC-2500-1, Examination ! Category C-A, item Nos. C1.10, C1.20, and C1.30, I volumetric examination of essentially 100 percent of each circumferential weld at gross structural discontinuities (head-to-shell and tubasheet-to shell weld) and categories C-C and C-E, Item No. C.3.10, surf ace examination and visual examination of integrally welded support attachments. Ralls for_ Relief The excess letdown heat exchanger (ELHX) and the regenerative heat exchanger (RHX) were scheduled for examination during the first. inspection period in accordance with the In-service Inspection (ISI) Programs SI-114.1 and SI-114.2. -The ELHX circumferential head weld was scheduled for vitrasonic (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-). requires a volumetric examination of 100 percent of the required welds. The ELEX wold 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 exart.lnation (see attached drawing). This allowed for an UT 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 porformed on a-best-effort basis and supplemented with'a liquid-penetrant test (PT) over 100 percent of the weld area. (Continued) 1406C/COC3
SI-114.2, Attachm30t 3 SURVEILLANCE R visicn 2 s INSTRUCTION REQUESTS FOR RELIT? page 21 of 44 i f I, ELOUEST FOR RELIEF ISI-12 (Continued) In the case of the RHX when examitations were performed, the state-of-the-art UT examination _ capabilities did not allow the achievement of meaningful results because o'. the component fabrication processes involved. The RHX is a centrifuga11y cast stainless steel, SA-351, CF8 vessel. In addition, the examinations were hindered by supports which were essentially nonremovable f rom the area of two of the four welds because of the location in the heat exchanger rora and their position on the vessel (see attached drawings). As a result, a PT was performed in place t of the required UT. On the two restricted welds examined, only 75 percent of the weld lengths' vere surface examined because of supports covering part of the weld areas. In accordance with 10 CPR 50.2(v) of the Code of Tederal Regulations, the RHX and the ELHX are defined to be within the reactor coolant pressure boundary (RCpB) (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 reactor coolant pressure boundary defined in 50.2(v) need not meet these requirements (Class 1 requirements), provided (11) The component is 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 automatic actuation and, assuming the other valve is open, its closure time must be such that, in the event of postulated f ailure of the compot.ent during normal reactor _ operation, each valve remains operable 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 . this paragraph, the RHX, ELHX, and the connecting piping to the Reactor Coolant System (RCS) and pipbg out to the containment isolation valves would be. exempt from ASME Class 1 examination requirements. (Continued) 1406C/COC3
.SI-114.2, Att chment 3 SURVEILLANCE Rsvisica 2 INSTRUCTION REQUESTS FOR RELIE.' Page 22 of 44' REOUEST.FOR_RELIrr 18I-12 I (Continued)
' Sequoyah Nuclear Plant units 1 and 2 ISI programs, SI-114.1 and SI-114.2, classify components zor examination in accordance with Regulatory Guide 1.26, Revision 3. The guiSelines of Regulatory Guide 1.26,- paragraph C.1, classify componenta which are exempted by 10 CFR 50.55A(c) (2)11 from ASME Class 1 examination requirements (such as the RHX, ELHX, and associated piping) as ASME Class 2 equivalent. The Sequoyah Final Safety Analysis Report (FSAD), Section 9.3.4.1.7, further describes the RIIX, ELIIX, and associated piping as "not required to function during a loss-of-coolant accident." Additional system design considerations are the following:
- 1. The ELHX is not used during normal plant operations and is isolated from the RCS by three valves, two normally closed gate valves and a check valve. ,
t
- 2. The REX 1s isolated from~the RCF'by two check j valves. Leakege from the RCS is prevented by the 1
two check valves in perles whica waro leak-tested-during the preoperational test program. ; Leakage also can Le detected by monitoring for signs of sysk
- incoming leakage and by monitoring the RCS for e.gns of outgoing leakoge -(FSAR 6.3-26). i 3 There are R.- leakagn problems into the CVCS from the F.CS hecause of the higher pressere 4.t 3hich the tVCS is generally maintained (FSAR 6.3-27).
In addition, the inlet end outlet piping (one inlet
.nd one outlet) associated with the'ELHX is-1-inch nominal pipe size (NPS) and 3-inch NPS for.the REX.
Both of'these are less than the 4-inch NPS which,~in accordance with IWC-1220(c), is exempt from the examination requirements in Table IWC-2500-11(Class
- 2) of ASME Section XI. Also note that the Winter 1980 Addenda, paragraph IWB-1220(b) (2) exempts from
. examination components and their connections in piping of 1-inch nominal pipe size and smaller.
(Having one inlet and ono outlet pipe, each 1-NPS or
-smaller).
(Continued) 1406C/COC3 a
s 9 SI-114.2,_Attechment 3 p SURVEILLANCE R3visio2 2-INSTRUCTION REQUESTS FOR RELIEF Page 23 of 44-l (- REOUEST FOR REtIEF ISI-12
!L (Continued)
TVA also feels that the'ALARA considerations to-perform the liquid petetrant-(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 MREM and 6,600 MREM respectively. Note that, in addition to the requirements:in-- Examination Category C-A, Table IHC-2500-1, Examination Category C-H requires that all- pressure retaining components be pressure. tested'in accordance with IHC-5000.' This results In a system pressure test conducted each 10-year intervalfduring a system functional test for the ELHX and a system hydrostatic-test performed each inspection ' interval for the RHX. 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-percent-examination coverage, and the.ALARA considerations in
' view of the small benefit realised, TVA_ requests relief from the ASMI Section XI examination-requirements as shown in Table IHC-2500-1, Examination Category C-A, C-C, and C-E.
Alternate Inupection: None. 1
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SI-114.5, Atttchncat 3 SURVEILLANCE .Ravision 2 INSTRUCTION REQUESTS FOR RELIEr Page 28 of 44-e {' EEQUEST FOR RELIEF IST-13 Components: Residual Heat Removal Heat Exchanger (two per unit) Clasm: ASHE Code Class 2 (Equivalent) Inspectinn_Egguirement: 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. EAlls for Re11el: Each heat exchanger consists of an inlet-outlet head charaber 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 integra1' 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: Request for Relief ISI-13 has been approved'with no additional augmented requirements.
Reference:
Memorandum from F. J. Hebdon, NRC, toLO.!D. Kingsley. TVA, dated February 7, 1991 (A02 910211 001). Memorandum from Sizanne Black, NRC, to 0. D.-Kingsley, TVA, dated April 19, 1990 (A02 900426 005). 1406C/CJC3
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-INSTRUCTION REQUESTS FOR RELIET- Page 30 of 44
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. -SI-114.2, Attcchm:nt 3 SURVEILLANCE Rcvision 2 1NSTRUCTION REQUESTS FOR RELIEF Page 31'of 44-Request for Relief ISI-la Camponentar Various (see Appendix A, tables A and B of_this instruction)
Cla111 ASME Code Class 1 & 2 (equivalent). Inspectjsn Recuirement: Tables IRB-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 Felief The NRC is requiring TVA to implement an augmented and accelerated field weld program, requested by URC's letter dated November 14, 1986 " Draft Safety. Evaluation on Welding for Sequoyah Units 1 & 2". 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"s response to Mr. B. J. Youngblood on January 30, 1987 (L44 810130 804). TVA stated on part-4 of response to item 3 that TVA would try to 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
-Requests relief from the Code percset.yes requirements.
Alternato Inspectionst The percentages required by the code wil.' not.be met on the second and third period of the first inspection interval. In some cases SQH U 2 will have zero (0) exams during the third period with 100% of-the examinations completed by the second period (see Appendix A, Tables A and B of this instruction). SQN U-2 will revert to the cude required percentages and schedule during the second inspection interval. The code required percentages will not be on examination categorios B-J, B-K-1, B-K-2, C-C and C-E (refer to Appendix tables A and B). (Continued) 1406C/COC3 '
SI-114.2, Attechmsnt 3 SURVEZLLANCE R3 vision 2-INSTRUCTION REQUESTS FOR RELTEl' Page 32 of 44 - {- Request for Relief ISI-14
-t1 (Continued)
AAfety Evaluation fymmary: Request for Relief ISI-14 has been approved with no additional augmented requirements. 4 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 0. D. Kingsley, TVA, dated April 19, 1990 (A02 900426 005). I e e 1405C/COC3
i SI-114.2, Attachment 3 SURVEILLANCE R3 vision 2 INSTRUCTION REQUESTS FOR RELIEl' Page 33 of 44 {' EEOUEST FOR RELIEF _ISI-15 C2D2QntRLas Reactor Vessel (RV) Outlet Nossle-to-Vessel Welds, RV Nozzle Inside Radius Section, and RV Nozzle-to-Safe-End Welds CIA 11: American Society of Mechanical Engineers (ASNI) Code Class 1 ID121CALDn Requirement: Table IHD-2500-1 , Examination Category B-D, Full Penetration Welds of Nozzles in Vessels - Inspection Program B Item No. B3.90 Nozzle-to-Vessel Welds Item No. B3.100 1:ozzle Inside Radius Section Footnote 3 (1st Inspection Interval) "At least 25 percent but not more then 50 percent (cradited) of the nozzles shall be examined by the end of lat inspection period and remainder by the end of inspection interval." Footnote 4 (Successive Inspection Intervals 2nd, 3 rd, and 4 th) "At least 25 percent lut~not more-than 50 percent (credited) of the nozzles shall bs examined by the end of lat inrpection-period and the remainder by the end of 3rd inspection period of each inspection interval." rootnote 5 (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.examinationc; required = to be conducted from the- she11'inside diameter may be performed at or near-the end of each inspection interval." Examination Category B-F, Pressure' Retaining Dissimilar Metal Helds Item No. B5.10 Nozzle-to-Safe End Welds Footrote.2 (Successive Inspection Intervals 2nd, 3rd, 4th) - "For the reactor vessel nozzle safe-ends, the examinations may'be performed coincident with the vessel nozzle examinations-required by Examination Category B-D." ' (Continued) i 1406C/COC3
'n SI-114.2, Attechm:nt 3
'i SURVEILLANCE Revisian 2-INSTRUCTION. REQUESTS FOR RELIE? page 34 of 44
?L-I REOUEST FOR RELIEF ISI-15 5 (Continued)
Basis for Relief Sequoyah Nuclear Plant (SON) is a four-loop 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. 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 inside radius sections on SON's four outlet nozzles were ultrasonically examined from the nozzlo 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 nozzle-to-safe end welds are ultrasonically examined using an automated inspection device when the_ nozzle in examined from the bore. During the first period, the nozzle-to-safe end welds on four outlet nozzles were ultrasonically examined from the inside diameter and surface examined from the outsido 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-
-requirements of Table INB-2500-1, Examination Cat (gory B-F, Item No. B5.10, Footnote 2.
The ASHI 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 additionar examination of the RV nozzle-to-vessel welds and inside; radius sections for SQN's four outlet nozzles during the third inspection period of the first inspection interval. In addition, the nozzle-to- safe end weldb for the outlet nozzles would-also be examined during the third ~ inspection period of the first interval. Performance-of. these additional 'exan.inations wil1 thereby
~
establish a new ten-year examination schedule for the second, third, and fourth inspection intervals. The (Continued) 1406C/COC3 a_o
51-114.2,'Attcchm:nt 3 SURVEILLANCE- R3violon 2 INSTRUCTION REQUESTS FOR RELILE page 35 of 44 l* REOUEST FOR RELIEF ISI-15 (Continued) Dasis for Reliefs ten-year exam! nation f requency required by the code (Continued) would continue to be maintained. Additional benefits include: One-time installation and removal of the automated inspection device from the RV flange 1 rather than twice during and inspection interval. Performance of additional RV outlet nozzle examinations during the first inspection interval. Performance c' additional RV outlet nozzle-to-safe end wold examinations during the first inspection interval. An overall reduction in personnel radiation exposure (one automated examination versus two), thur supporting as low as reasonably achievable considerations. A reduction in the number of times automated devices and associated materials and equipment must be decontaminated (reduera gent ation of radwaste). A c at saving to TVA of-1.8 million dollars over the 40-year life of the plant. In consideration of TVA's performance of additional examinations during the first interval and the radiation exposure required to perform inspections under the current Section XI examination schedule (second, third, and fourth intervals), it is concluded'that compliance with tus spacified requirements would result.in an unnecessary hardship without a compensating increase in the level of quality and safety. Alternate Inspection: SON's four RV outlet nozzles will be ultrasonically examined twice during the first inspection interval. The second examination would occur during the third period. This includes examination of the outlet nozzle-to-vessel welds by the straight beam. ultrasonic method from the nozzle bore and examination of the outlet nozzle inner radius sections.t These examinations will be in' addition to the examinations required-to be' conducted on the (Continued) 1406C/COC3
SI-114.2, Attechmsnt 3 SURVEILLANCE- Revision 2 INSTRUCTION REQUESTS FOR RELIEF .Page 36 of 44 s l' REOUEST FOR RELIEF ISI ,li
; (Continued)
A11grnate Inspections outlet nozzle-to-vessel v' ids and inner radius (Continued) section from the RV shel. Anside 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 surf ace 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 tozzle-to-safe end welds will be examined during the third inspection period. Status: Request for Relief ISI-15.was submitted to the NRC on August 21, 1991, with a-request for a response.by June 1, 1992.
Reference:
Nemorandum from J. L. Wilson, TVA, to the NRC, dated-August 21, 1991 (S10 910821 848). NRC Responses Memorandum from F. J. Hebdon, NRC, to Dr. Mark O. Medford, TVA,- dated August 31, 1992 (A02 920903 005) Staff Evaluation: The proposed insp3ction sequence meets the Code scheduling requirements for the sub$ set RPV outlet nozzle-to-vessel welds, outlet nozzle inner radius sections, and nozzle-to-safe end welds at SQN Units 1 and 2 for the first 10-year inspection interval. Therefore, relief is not required during the first 10-year inspection interval. 4
' In response to the Licensee's request to defer the subject examinations for the second inspection interval, the examination schedule change ' for the second inspection interval must be evaluated to future editions and addenda of the ASME Code as defined by 10 CIR 50.55a(g)(4) and 10 CFR 50.55a(b)(2). At the present time, the staff believes that this relief request could be considered acceptable for subsequent inspection intervals, if the tire period between -
specific weld examinations does not exceed 10 years plus Code-allowed extensions. With the large population of operating reactors, the examination of nozzles of a given vessel being. distributed between an outage in the first period and an outage in the third period can be eliminated and concentrated in an outage in'the third period of the interval. Proposed alteraatives to Code requirements can only be authorized for examinations in the present. interval. Therefore, a separate relief request will have to be submitted for the next - (second)- 10-year ISI interval _af ter . the - applicable Code for the second interval has been established. 1406C/COC3
S1-114.2, Attechmtnt 3 SURVEILLANCE Revision 2 INSTRUCTION REQUESTS FOR RELIEl- Page 37 of 44 Request for fellef ISI-16 Components: Residual Heat Removal Heat Exchanger (two per unit) ~ CIA 111 ASME Code Class 2 (Equivalent) Inspection Requirement: ASME Section XI, Table IWC-2500-1,-Examination Category C-A, Item No. C1.10 volumetric examination of circumferential shell welds. Basis f.gr 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 circumferentini 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 are distributed in thren segments, ident*fied as RHRW-16-A-1, 37 in.; RHRd-16-A-2, 38 in.; and RHRW-16-A-3, 38 in. RHRW-16-A-1 was ultrasonically examined in the first inspection period and achieved , approximately 81% examination volume coverage. RHRW-16-A-2 was examined in the second period and achieved approximately f4% examination volume coverage. RHRW-16-A-3 la scheduled for examination during the third period with an estimated examination volume covsrage of 82%. Based on the examinations performed and an estimation of the remaining third period examination, approximately 75% examination volume coverage of the RHR heat exchanger circumferential weld will be achieved. Alternate Inspection: 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 to achieve as nuch code' coverage as possible and achieve meaningful results. Status Request for Relief.1SI-15 submitted to the NRC av a part of Revision 16 of thic program.~ 1406C/COC3
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1 S1 114.2, Attechm2nt 3 SURVEZLLANCE Rsvision 2-INSTRUCTION REQUESTS FOR RELIET Page 39 of 44 EEQUEST POR RELIEF ISI-17 Components: Integrally Helded Support Attachments Claggi ASME Code Class 2 (Equivalent) In1Efetion Requirement ASME Section XI, Table IWC-2500-1, Examination Category C-C, item No. C3.40, piping integrally-welded support attachments, surface examination. Basis t'or Relief t Due to the design vintage of Sequoyah' Nuclear Plant-it will be impractical to inspect all of the integrally weldr,d attachments of certain component 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 relle! - request. Alternate Inspection: TVA will perform a best-effort surface examination. In addition, the supports-shall receive a visual examinstion as practical. Status: Request for Rallef ISI-17 submitted to the NRC as a part of Revision 16 of this program. 1406C/COC3
SI-114.2,1 Attachm:nt 3 , SURVEILLANCE Rovision 2
-INSTRUCTION REQUESTS FOR RELIEJ Page 40 of 44~
-1 REOUEST FOR P3 LIEF 1E1-17 ATTACHMENT A Component Exam Drawing Code Eystem ID Catt No. Coveregg Limitations reedwater 2-FDH-245-IA C-C MSG-0016-C 54% Access limited due-to feedwater piping penetration in valve room. Limitation on integrally welded lugs due to nonremovable pipe riamp and restraint and pipe penetration.- Feedwater 2-FDH-284-IA C-C MSG-0016-C 71% Access limited due:to feedwater piping penetration in containment. Limitation on-integrally welded attachment due to permanent support' attachment at the-piping penetration. Safety 2-SIH-10-IA C-C MSG-0009-C 0% Totally Injection insccesalble. Integral attachment installed in a wall in fan room.- Process pipe goes through AC duct which-is 4 to 5-inches from wall making integral attachment inaccessible for surf ace examination. 14C6C/COC3
SI-114.2, Attechm)nt 3 SURVEILLANCE Rovision 2 INSTRUCTION REQUESTS FOR RELIEP Page 41 of 44 Recuest for Relief ISI-18 CSFRAR2n111 Reactor Pressure Vessel Closure Head-to-Flange Weld Classt ASME Code Class 1 (Equivalent) Inspection Requirement: ASME Section XI, Table IRB-2500-1, Examination Category B-A, Item No. Bl.40, Volumetric Examination RAAis~for Relief: The Reactor Pressure Vessel (RPV) closure head-to-flange weld WO8-09, is 45 feetLin length. The weld examinations are distributed in three segments of 15 feet lengths each inspection period. The veld segments are identified as WOB-09A (0" - 180"), WO8-09B (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 the head side are due to the head lifting lugs. located at 0*, 120', and 240' (see attached drawing). WO8-09A was ultrasonically examined in the first inspection period and achieved approximately 40% examination volume coverage. WOB-09B was examined in the second inspection period and acaleved 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" volume was examined from the OD-surface from the closure head side. However, the required 1/2T base metal area was not completely examined on the flange side.- Due to the limited'acanning area, TVA will be able to achieve approximately 40% examination coverage of the RPV closure head-to-flange weld. Alternate Examinationt 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% turface' examination (MT) of all accessible areas of the closure head-to-flange weld flex area in the third inspection period. ELAIMA: Request-for Relief ISI-18 shall be submitted to the NRC as a part of Revision 16 of this program. 1406C/COC3 e
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WO9-10A (0"- 156 ")
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51-114.2, Attcchment 3 SURVEILLANCE- R; vision 2 INSTRUCTION REQUESTS FOR RELIEF Page 43 of 44 (1 REOUEST FOR RELIEF 2-ISI-19 Components Pressure-retaining welds in piping Class ASME Code Class 1 (equivalent)
-Function Pressure-retaining component Inspection Requirement ASME Section XI, Table INB-2500-1, examination categories B-F (item No. B5.30) and B-J (item-No. B9.31), volumetric and surf ace examinations _ of nozzle-to-safe end welds and pipe. branch connection welds.
Basis for Relief: The ultrasonic examination of the nozsle-to-safe end welds (RC-19-SE, RC-26-SE and RC-27-SE) and branch connection welds (CVCW-01 and RCW-13) are limited-due to configuration of the components. The configuration limits the ultrasonic examination coverage for each weld.. These limitations are noted on the ultrasonic examination sheet and on attachment A of this request for relief. Alternate Inspection: In addition to the visuel examination (VT-2), performed during system leakage'and hydrostatic pressure tests, a "best effort" ultrasonic-examination and a surface examination will be performed on accessible areas of these velds. 1406C/COC3
REQLEST FDR RELIEF 2-151-19 w cs EN ATTAOMNT A gg c-O" VELD NUMBER $1ZE CAT [ W NATFRIAL DRAWING NUMBER PHYSICAL
' CONFIGURATION SCAN / LIMITATIONS CODE
$G3 REMARKS w{
o 3 RC-19-SE 31" B-F SS ISI-0401-C Norrie-safe No scan form 2S% No scan due to nozzle end norrle side configuration RC-26-SE- 29" B-F $5 ISI- 401-C Nortle-safe No scan from 25% No scan due to nor:1e end nozzle side configuration RC-27-SE 31" B-F $$ ISI-0401-C Nozzle-safe No scan from 25% N, -:an due to norzle end nor:1e side . Nration CWCV-01 3" 8-J SS ISI-0009-C Nor:1e/ Pipe Scan from nortle 40% O9 der to nozzle side only weld configuration RCV-13 4" B-J SS ISI-0013-C Nozzle / Pipe Scan from norrie 50% No sca., se to nortle > side only weld configuration @ N w o w Notes: 1. Categories determined in accordance with ASME Section XI. m M
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? f'\ ! , 1
'_ INSTRUCTION UNIT 2 Page 1 of 25 c;; ii s .1 W j; .
U-I i 1 ASME Section II Programs I
~1
.l A. MAINTAIN a listing of components for JSI examinations.
.1 B. UPDATE listing as necessary.
r . \ C. OITTAIN concurrence from Site Quality Manager or his designee.
-!g SON b D. ' CONCUR with listing by signing below.
ASNE Section II Programs E. FORWARD to SPS for updating Table of Contents, etc.
.SPS F. FORWARD to DCRM.
DCEN G. E1:5 TRIBUTE per SSP-2.7. M1D& i:2hals Site Quality Ma' nager /D'esignee . Datie - i , 2 i k ' 1402C/COC3 e- . k-S
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ATTACHMENT O TABLE A SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS Program h etion XI Reference . Exam' Eram ist Insp. Interva? Inspection Periods Component Section Method Cateaorv 40 Yr. Samole Samole 3 vrs. 7 vrt. 10 vrs. Reference Dwo. No. y y-us w A. Reactor Vessel wN c: w
- 1. Circumferential Shell Velds 7.1.1.1 UT B-A 4/50 ft. 4/50 ft. 0 0 4 151-029B-8 0E w
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- 2. Closure Head 7.1.1.3 UT B-A 41 ft. 41 ft. 13 ft. 14 ft. 14 ft. ISI-0301-A
*O Cire Weld
- 3. Lower Head 7.1.1.4 UT B-A Cire Veld 38 ft. 38 ft. 0 0 383 ft. 151-0298-8
- 4. Lower Head 7.1.1.6 UT B-A 6/4 ft. 6/4 ft. 0 0 6/4 ft. 151-0298-8 Merldlonal Welds
- 5. Shell-te-Fiange 7.1.1.7 UT B-A 50 ft. 50 ft. 502 ft.
Weld O ft. O ft. 151-0298-8
- 6. a. Closure Head- 7.1.1.8 UT B-A S.
to-Flange Weld 45 ft. 45 ft. 15 ft. 15 ft. 15 ft. ISI-0301-A 4 w t1
- b. Closure Head 7.1.1.8 MT B-A 45 ft. 45 ft. 0 0 ISI-0301-A to Flange 45 ft.
H$ w Flex Area "
- 7. Norale-to 7.1.2 $
Vessel Welds UT B-D 8 8 41 0 4dInlets ISI-0298-8 Q Dutlets (Bore & ISI-0297-A (Bore) $ ell ID) ISI-0392-A 4 tiets (Bore & Shell ID) I The four outlet nor:1e-to-norrie 2 5ee Request for Relief 151-10 welds examinatico from the vessel shell shall be done in the third inspection period. 3 See Request for Relief ISI-5 4 See Request for Relief ISI-15 for background information on examination of all norries from the bore and shell ID in
~ the third inspection period.
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;* *4 y ATTACt9 TENT 4 TABLE A SEQUDYAH INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS Program Section XI Reference Eman Enam ist Insp. Interval Inspection Periods Component Section Method Cateoorv 40 Yr. Sample Sample 3 vrs . 7 v re . 10 vrs .
Reference Dwo. No. gg m so :
' A. Rgactor Vestgl (Cont'd) Y LN
- 8. Inside Radius 7.1.3 UT B-D 8 8 55 Sections 4 0 8I TISI-0198-8 - UC:
(includes integral Outlets (4 Inlets . 151-0008-B 4 Outlets)L ISI-0392-A Q %- extensions on the m: outlet nozzles) ISI4297-A
- 9. Vessel Pene- 7.1.4 VT-2' D-E 141 37 12 12 trations and 13 ISI-0097-C Attachments . ISI4319-C
- 10. Norrie-to-Safe 7.1.5 UT. PT B-F 8 8 4 0 8I End Welds ISI-0298-8 Outlet (4 Inlets 4 Outlets) t
- 11. Closure Studs 7.1.6 UT. MT B-G-1 54 54 18 18 18 151-0304-8 and Nuts 7.1.6 MT B-G-1 n
54 54 18 18 18 151-0304-B' O
'12. 1.lgaments 7.1.6 UT B-G-1 54 54 k
Between Threaded 18 - 18 18 ISI-0304-8 - @@ Stud Holes um
'I$
u
- 13. Closure Washers 7.1.6 VT-1 B-G-1 54 54 18 18 18 151-0304-8 4
- 14. Vessel Interior 7.1.9 VT-3 8-N-1 1
'E 1 1 1 1 151-0298-B E
- 15. Removal Core 7.1.10 V7-3. B-N-3 See Program Section 7.1.10 Support Structure I
See Request for Rclief 151-15 for background information on examination of all nozzles in the third inspectico period. 550 1 i."'4 M O
$ M M "o>
~ ?; '%
8
=
..ii.
9
. . t- ".4- ,
.. L:
AVTACAMEM7 4 VABLE A
.SEQUOY#df INSE;iVITC
- nPECTION PROGRAM CLASS 1 COMPONENTS Program .Section XI Reference Erm Enam ist Insp. Interval Inspection Periods Component Section Method Category 40 Yr Samole Reference yE Samole 3 vrs. 7 vrs.10 vrs. Dw2. No. yg A. Peactor Vessel (Cont'd) wM cw
- 16. Control Rod 7.1.11 UT 8-0 2 2 0 OE '
i Drive Housings 1 1 ISI-0097-C ISI-03004 ug
@ n,
- 17. RV Aux liead 7.1.12 UT, PT B-l' 4 N 4 1 2 Adapters 1 ISI-0097-C
-ISI-0318-A. "
- 8. Pretsurirer
- 1. ' Circumferential 7.2.1 UT B-B 2/24 ft. 2/24 ft. 12 ft.
- Shell-to4fead 12 ft. 24 ft. ISI-0396-C helds
- 2. Longitudinal 7.2.2 UT B-8 2/1 ft.
She11-to49ead 2/1 ft. 13 0 11 ISI-0396-C Welds o" e:rle-to-Vessel 7.2.4 - UT B-0 6 6 2
,esds and I.eside 2 2 ISI-0396-C D Radius.Section @O-y 23
- 4. Heater 7.2.5 VT-2 B-E 78 4 20 6 7 7 ISI-0309-A N Penetrations E
I lhe one foot of longitudinal weld selected for examination is that section of weld intersecting the circumferential ' shell-to-head weld examined. 55N 1: *li. . p.a a:.O* O s3 M n e. n . n B O S. m
~ .k
AVTACHMENT 4 TABLE A SEQUQYAH INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS Program Section XI Reference Exam Exas 1st Insp. Interval Inspection Periods Reference Comoonent' Sectico Method Cateoory 40 Yr. Sasele Sample 3 vrs. 7 vrs.10 vrs. Dwo. No. MQ G :o H <: -
- 8. Pressurirer (Cont'd)
EU
- 5. 'Norale-to-Safe 7.2.6 UT, PT B-F 6 6 2 2 2 O End Welds ISI-0396-C
'wh~
@. n
- 6. Pressure 7.2.8 VT-1 B-G-2 1 mwy/ 1 swy/
t1 - 16 0 0 ISI-0299-B Retaining Bolting 16 bolts 15 bolts
- 7. Integrally- 7.2.9 MT B-H 23 ft. 23 ft. 7 ft. 8 ft. 8 ft. ISI-0396-C Welded Support Skirt
- 8. Seismic Logs 7.2.9 MT B-H 4 4 0 4 0 ISI-0396-C C. Steam Generators
.1. Primary 7.3.2 UT B-B 4/36 ft. 4/36 ft. I 1 2 ISI-0401-C o Head-to-Tube O Sheet Weld h
c: o -
- 2. Primary Nortles 7.3.3 8I Inside Radius UT B-D 81 0 4I 4I ISI-0401-C DE:
Section ' .H d ' u H-
- 3. Primary Norrie- 7.3.4 UT. PT B-F to-Safo End Welds 8 8 2 3 3 ISI-0401-C E' "g
e
- 4. Pressvee 7.3.6 VT-1 B-G-2 4 gens./2 swy 8 mwy 2 2 4 s
Retaining Bolting ISI-0299-B
- 5. Tubing 7.3.8 ' ET B-Q See Program Sections 7.3.8 and 20.4. ISI-0398-C
'I See Program Section'7.3.3. and Request for Relief ISI-6.
s 1 ;L 2 o, '.'r.
.$ O M S.
- ow e- "
n' 8 E O- ii - a a b
ATTOCHMENT 4 TABLE A SEQUDYAH INSERVICE INSPECTION PROGPAM CLASS 1 COMPONENTS Program Section XI Reference Exam Exam ist Inso. Interval Inspection Periods
' Component Section Method Categorv 40 Yr. Sample Reference '@ $
Samole 3 vrs. 7 vrs. 10 vrs. Dwo. No.__ gg D. Ploino EN~ o t*
- 1. ,P,rtn vre Retainino Boltino
- a. Reactor Coolant 7.4.3.1 VT-1 54 Sets
~h System B-G-2 54Sets 0 2 3 ISI-0013-C *O
- b. Chemical and 7.4.3.2 VT-1 B-G-2 4 Sets /4 Bolts 4 Sets 1 1 2 Volume Control MSG-0005-C System (SWI)
- c. Safety 7.4.3.4 VT-1 B-G-2 4 Sets /4 Bolts 4 Sets 1 1 2 ISI-0002-C-Injection System
- 2. Circumferential Welds
- a. Reactor'. o 7.4.4.1' UT/PT B-J 61 175 5 75 5 ISI-0008-8 Coolant System Main Loops k' Cires 14" @@
y
- b. Reactor w Coolant System Cires >4a "y tw Nom. Size 7.4.4.2 UT/PT B-J 662 152 5 5 6 Cires <4" ISI-0318-A E Nom. Sire 7.4.4.2 PT ISI-0013-C B-J 201 3 531 1 1 3 ISI-0013-C 151-0008-8 I
2 The change in weld nusers during the second period was due to new code class boundaries. 3 1he change in weld numbers due to the removal of the UHI system in U2C4 4 The change in weld numbers second period due to RTD MDD U2C4. 5 The change in bolted connections was due to U2C4 RfD MOD. The second inspection period sample was increased by one weld which was due to the substitution of Weld RC-33 for SIF-128 (see RFR ISI-3). 550-2 i. . a, ,* Ps . o O M n ay-n. O a. O a b-
. . .. o-,.. . . +-
ATTACHMEET 4 TABLE A SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS Program Section XI Reference Eram Enam 1st Insp. I'eterval Inspection Periods Comognent Section Method Calecorv 40 Yr. Sample Samp]e 3 vrs. 7 vrs. 10 vrs. Reference $$
- 0. Pipina (Cont'd)
Dws. No. yg wM
- c. Chemical and EU e c-Volume Control H&.
System Cires O5 M 14" Nom. Size 7.4.4.3. N/A Cires (4* Nom. Size 7.4.4.3 PT B-J 60 151 4 5 6 IS14009-C MScr 0008-C
- d. Residual Heat Removal System
-Cires 14" Nom. Size 7.4.4.4 UT/PT B-J 45 11 3 4 4 ISI-0003-C
- e. Safety Injection Systen Cires n O
>4* Nom.' Size 7.4.4.5 UT/PT B-J 721 171 = 4 54 6 6 ISI-0002-C k Cires (4*
Nns. Stre 7.4.4.5 PT B-J 38 10 3 4 3 ISI-0002-C
@E y !!
u 4 n 5 I
'2 The change in weld numbers during the second period was due to new code class boundaries.
3 The change in weld numbers due to the removal of the LHI system in U2C4. 4 The change in weld numbers second period due to RfD t00 U2C4 The first inspection period sample was decreased by one weld which was due in the suP 1 *stion of Sfeld RC-33 for SIF-128 (see RFR ISI-3). EO 1 12 H ?J ,' $~ 0 5 N n- "oy A m N 8 w if
l
.. _ _ w. . ,,
...i.~. .~ ~.
ATTACHMENT 4
' TABLE A-SEQUOYAH INSERVICE INSPECTION PR0rgan CLA 1 COMPONENTS Program Section XI Reference Exam Enam . 1st insp. Interval Inspection Periods
~ Component Section Method Cateoorv 40 Yr. Sarole Sample 3 vrs. 7 vrs.10 vrs.
Reference Dwo. No. EE D. Piping (Cont'd) gg se n p
- f. RV Aun Head Adapter Cap M Welds (tNI Oo M Caps)
' Cires 2, 4" 7.4.4.6 These welds are examined as a part of the RC System, Section 7.4.4.2. due to the UIC4 N00.
- 3. Branch Plot Connection Welds
- a. Reactor Coolant System - Main loop Welds
.>2" Nom. Size 7.4.5.1 UT/PT B-J 1. 0 1 1 0 151-0008-B o Velds 12" O Nom. Sire 7.4.5.1
- b. Reactor Coolant PT B-J 12 3 1 1 1 ISI-0008-8 gf System Welds
>2" Nom. Size 7.4.5.2 UT/PT 151-0008-8 hh4 B-J 6 2 0 1 1 ISI-0013-C w Welds 12"' ISI-0005-0 Nom. Sire 7.4.5.2 PT B-J 7 21 0 1 1 ISI-0013-C "h
M 1 1he change in weld numbers during the second period was due to new code class boundaries. IEU.
? ;i. J.
v P.% o a 8 'u
~
oy n " n m $ o 1 a - a
.- -.~.... - - ~.--. - __ ._ _ . _ .
p-. L i L _. , , + .~. & ATTACHPtENT 4 TABLE A SEQUDYAH INSERVICE INSPECTION PROGRAM CLASS.1 COMPONENT $ Program Section XI-Reference Eram Enam Comoonent Section Method Cateeorv 40 Yr. Sample 1st Insp. Interval Samole Inspection Periods 3 vrs. 7 vrs. 10 vrs. Reference Dwo. No. yy. mw D. Piping (Cont'd) 'N N cw
- c. Chemical and Volume Control System Welds y(t~.
w
.@n ,
. >2" Nom.-Sire 7.4.5.3 UT/PT B-J 3 1 0 0 to Welds <2" 1 151-0009-C
-Nom. Sire 7.4.5.3 PT B-J 1 - See Note 1 - - -
I'd-0013-C
- d. Residual Heat Removal System Welds
>2" Now.. Size 7.4.5.4 UT/PT B-J 3 1 0 0 Welds 12" 1 ISI-0003-C
**om. Sire "7.4.5.4 PT- B-J 2 - See Note 1 - - -
ISI-0003-C
- e. Safety Injection n O
System Welds
~)2" Nom.-51 e 7.4.5.5 UT/PT B-J 5 0 4
1 0 ISI-0002-C Welds $2" 1 w es Nom. Size 7.4.5.5 PT 8-J 11 2 .1 4 1 0 ISI-0002-C u5 H, . E-- I Examinations not scheduled this' interval. EN 2L. " 8 g E ~~'
- q. n
=
*W 8 .g
-a O II .
.e b
, m _ _______.__-.__.m -_-_.L--,-
- :3.. -x--- ,
7'
.nl: .
M*J c-e ;. m , " . ~y y
; s.
y~ ATTACHMENT 4 TABLE A _. SEQUDYAH INSERVICE INSPECTION PROGtAM ' CtASS i COMPONENTS Program Section XI '
- Reference' Eman Enam ist Insp. Interval Inspection Periods Component Section Method Cateoorv 40 Yr. % 1e Samole 3 vrs. 7 vrs. 10 vrs.
Referenc'e' Dwo. No. yE '
- en se
'O. Piping (Cont'd) N N'
- cM i
-4. . Socket Welds ' g t* ; _
uE. o*
-a. Reactor 7.4.6.1 B-J 70l *2 18I 2.3 Coolant PT 0 15 3 151-0008-8. *O e 5ystem ISI-0013-C' b.' Chemical and '7.4.6.2 PT B-J 2381 601 3 18 42 0 Volume Control MSG-0008-C.
' System ISI-0009-C'
- c. Residual Heat 7.4.6.3 PT 84 18 53 1 4 0 ISI-0003-C
' Removal System
- 'd. Safety 7.4.6.4 ' PT 84 1711 431 '3 14 29 0
' Injection ISI-0002-C System o' 1 O
].
as un e *
- Hg u- : .;
M G. I The change in weld numbers during the second period was due to new code class boundaries.
.2Change in weld no6er in second period was doe to RTD MOD in U2C4.'
3 i Change in number scheduled during the second and third period due to accelerated FW Program.
*o se en er - e M :
..k- .
3o : ma ~;
.R. ; m og
- n. ": ;l ;
o:
'k s t* -
,A
.f' bl.. ' .1l _ ._ _ .a a _.2. _._,._n? -
,m, , e. . . . . . , ., , , ,&
ATTAC}#*ENT 4 TABLE A SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS Program Section XI Reference Eram Enam 1st Insp. Interval Inspection Periods Comeonent Reference H of
'Section Method Cateoorv 40 Yr. Samole Sample 3 vrs. 7 vrs. 10 vrs. DW. No. N@
D. Ploino (Conted) H< EU
- 5. Ploino and Valve O" Inteorally Welded w" Svooort Members Q M
- a. Reactor 7.4.7.1 PT B-K-1 521 51 2,4 2 3 0 Coolant MSG-0013-C System
- b. Chemical and 7.4.7.2 PT. B-K-1 1 1 0 0 Volume Control 1 MSrA 015-C System
- c. Residual Heat 7.4.7.3 PT B-K-1 33 33*4 0 3 0 MSG-0010-C Removal System
- d. Safety n Injection 7.4.7.4 PT B-K-1 61 6I 'd 1 5 0 MSG-0009-C- O r System k wM d.
H M I 2 The change in support numbers during the second period was due to new code class boundaries. 3 Change in integral attachment in second period was due to RTD MOD U2C4. d Change in integral attachments in second period due to RHR support MOD in U2C4 Change in number scheduled during the second and third period due to accelerated W Program. f 1:5. 4 v b w :.
- D M 8 O R "
n ; n
.m
. . . . .s . ;6n ..
ATTACHMENT 4 TABLE A SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS Program Section XI Reference Exam Exam ist Insp. Interval Inspection Periods
. Component Reference w tn Section Method Cateoorv 40 Yr. Samole Samnie 3 vrs. 7 vrs. 10 vrt. Dwa. No.
D. Pipina (Cont'd) @ H <:@ '.. ED
- 6. Ploina and Valve 0 C" Component Supports w o
- a. Reactor 7.4.8.1 VT-3, B-K-2 501 ,2 501 2.5 0 50 0 Coolant VT-4 MSG-0013-C System
- b. Chemical and 7.4.8.2 VT-3, B-K-2 1302 33o2.5 38 92 0 Volume Control VT-4 MSG-0012-C System
- c. Residual Heat 7.4.8.3 VT-3, B-K-2 135 135 ,6 4 9 0 MSG-0010-C-
' Removal System VT-4
- d. Safety 7.4.8.4 YT-3, B-K-2 912 ,3 912 ,3,5 27 64 0 Injection M W OOO9-C n VT-4 O System
- e. RCS Main 7.4.8.5 VT-3, B-K-2 72 72,5 0 7 0 g O .'
Looping Piping VT-4 ISI-0302-C M 151-0321-B 64 g u N-5 I Change in supports due to RTD MDD in U2C4 n 2 3 The change in support numbers during the second period tras due to new code class boundarie?. 4 Eight of the supports examined in the first period as CC-1 are now CC-2. 5 Change-in supports due to RHR support 700 in U2C4. 6 Change in number scheduled during the second and third period due to accelerated FW Program. Change in number of component supports during the third period was due to modification to delete supports during U2C5.
*o se cn or # M p- '
M ? t."
"* D M O
R " h n U. n M .- a m- .-~_.i - - - _
- u. -
., , , -.m ATTACHMENT 4 TABLE A SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS Program Section XI Reference Eram Exam ist Insp. Interval Inspection Periods Conconent Section Method Catenerv 40 Yr. Sample Reference w ts '
Sample 3 vrs. 7 vrs.10 vrs. O m. No. $$ H< E. Reactor Coolant Pumn1 E U .'
- 1. Pressure- 7.5.1 UT B-G-1 % % 24 24 48 151-0307-8 '-h Retaining Bolting o
* "to
- 2. Pressure- 7.5.1 VT 1I B-G-1 See Note 1 Retaining MT 7 ISI-0307-8 Bolting Deferral to end of interval is permissible when bolts are removed
- 3. Pressure- 7.5.2 VT-1 B-G-2 4 Sets /1 Set 4 sets 1 set Retaining i set 2 sets ISI-0307-8 Bol ting
, '4. Integrally- 7.5.3 'f B-K-1 3 pumps /3 feet 9 feet 3 3 3 151-0326-8 Welded Supports per pisap
- 5. Component 7.5.4 VT-3, B-K-2 4 pumps /3 feet 12 feet n 3 3 6 ISI-0326-8 o Supports per pump (1 pump) (1 Pump) (2 Pumps)
- 6. Casing' 7.5.6 cok VT-1 or B-t-2 (UT and 4 See Program Section 7.5.6, 7.9 and RFR ISI-1 15I-0307-8 5$
VT-2) Hg' M H G. I When disassembled, bolts shall be magnetic particle esamined; threads in the base material and flange ligaments between threaded bolt holes shall be visually esamined. 550 2 li.' ~ L
~
N
~:.
a' mo> Ms Q ;T n ' 0: n. C u n
.A-4 .._ i. _ _ . _ _ _ . . _ . _ _ . . . _._ ._ __ _ . _ _ _. ._.
A1TACHMENT 4 TABLE A SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS Program Section XI Reference Enam Eram 1st Insp. Interval Inspection Periods Component section Method Cateoorv 40 Yr. Sample Reference wM
' Sample 3 vrs. 7 vrs. 10 vrs.
F. Valves Dwa. No. .E$ H< 1. EU Pressure Retaining OE w Bolting n tv
- a. Reactor 7.6.2.1 VT-1 B-C-2 33 2 32,3 0 0 3 151-0013-C
' Coolant Svstem
- b. Chem' *. and 7.6.2.2 YT-1 8-G-2 03 03 0 0 0 ISI-0003-C Volu w cntrol
. Sys ts
- c. Residual Heat 7.6.2.3 VT-1 8-6-2 6 6 1 2 3 Removal System ISI-0003-C
- d. Safety 7.6.2.4 VT-1 B-G-2 141 '3 141 ,3 4 Injection 6 4 ISI-0002-C n System O.
- 2. Integrally 7.6.3 PT B-K-1 Totals are included in D.5 of this table. SO Velded Support CE Members H$-
u
- 3. Component 7.6.4 VT-3, H B-K-2 Totals are included in D.6 of this table.
Supports VT-4 E y I 2 In the second period 4 of the CC-1 valves became CC-2, two of whlch were examined in the first period. Changes in the third period due to U2C4 RTD MDD. 3 CFanges in the third period due to use of Code Case N-426. 550. 1! li. 2
~ ,~ 2,'
8 *aL
. Row f
a
]
u
- r. .
9T b
. M
^
.. ... . .. 2 .,
ATTACIMENT 4
~ TABLE A SEQUDYAH INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS -
Program Section XI Reference Exam Enam ist Insp. Interval Component Inspection Periods Reference M t9 '- Section Method Cateoorv 40 Yr. Samole Sample 3 vrs. 7 vrs.10 vrs. Dws. No. EN H< F. Valves (Cont'd) 4 EU Vah e Bodies 7.6.6 VT-1 B-M-2
>4" N.P.S. See Table 1 of Attachment 2.
G. Syling 7.9 VT-2 84 See Program Section 7.9.
@k to
, Pressure Tests a
O i cO z= M t9
~
y .. b. M mxm er eH e taa y pd ta. eM
" (M O
- CM'
~ MO
~ . , .
'8 g - g.
e-D
- et -
b-
re: ,
. .m -.
6 ATTACHMENT 4 TABLE 8 SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS 2 COMPOWENTS Program Section XI Reference Exam Exam 1st Insp. Interval Inspection Periods Comconent Reference H es Section Method Cateoorv 40 Yr. Samole Sample 3 vrs. 7 vrs.10 vrs. Dwo. No. @h
+4 <: -
'A. $leam Generators EU n t'
'1. Cie cumferential 8.1.1 UT C-A 4 ~, ens./3 Welds 3 1 ISI-0401-C d g{3-1 1 Dell Welds (12)
- 2. Circumferential 8.1.2 UT C-A 4 Gens./1 Weld I wid/46 ft IS' 15' 16' M'
Head Welds ISt-0401-C (4)
- 3. Tubesheet-to- 8.1.3 UT C-A 4 Gens./1 Weld I wid/36 ft 12' 12' 12'
'Shell Weld 'ISI-0401-C (4) 4 Norrle-to Vessei and Inside Radius
- a. Norrle-to- 8.1.4 UT, MT C-8 4 Gens /2 Nor 8 1 3. 4 ISI-0401-C Vessel Velds (8)
- b. Inner Radius 8.1.4 UT C-8 8 8 1 3 4 ISI-0401-C B. Heat Exchanoe_r1 O
- 1. o Residual Heat Removal Heat- k Exchanger (2) 59 RHRHX OR Hy-
- a. RHRHX u H
Circum- 8.2.1.1 C-A 2 Ht. Ex./1 Weld I wid/113"
~
ferential UT 37" 38" 38" ISI-0289-A $: Shell Weld Q
*e m os
- b. <;* ;5 O *
.g O n aoy u
n 8 w li ^
.O
.. i . --n' - -
ATTACHMEDT 4 TABLE B i SEQUDYAH INSERVICE INSPECTION PROGRAM CLASS 2 COMPONENTS
-Program Sectior: XI Reference Exam Exam 1st Insp. Interval Inspection Periods '
Component Section Method Catecorv 40 Yr. Sample Reference Nm Scmole 3 vrs. 7 vrs. 10 vrs. DwoJ No. y$ H <: -
- 8. Heat Exchancers (Cont'd)
- b. RHRHX 0 ""
Circum- 8.2.1.2 UT C-A 2 Ht. Ex./1 Weld 1 wld/113" 37" 38" 38" 15I-0289 4 w oE ferential (2) Head Wald *Q
- c. RHRIDC Nozzle-to- 8.2.2 PTI C-8 2 Ht. Ex./2 nom. 4 1 1 2 ISI-0289-A Vessel Weld (4)
- d. RHRHX Integrally- 8.2.3 PT C-C 2 Ht. Ex./2 W1ds 2 0 1 1 151-0789 4 Welded (4)
Supports
- e. kHRHX Component 8.2.4 VT-3 C-E 2 Ht. Ex./ 4 n
' Supports 1 1 2 ISI-0239-A o 2 Spris. (4)
EO
.n n "D
u ' H
.g.
F, I See Request for Relief !$1-13. PT examination only, 5EO
% ?-4 H
. u " ~.
#3 u O
- h. O E . "
g a
. .n
.r
--- - - - - . - -- mm_.._ _ _ _ . . . _
- e. -
_ + , ..x. . ATTADNENT 4 TCBLE B SE(TJ0YAH INSERVICE INSEECTION PROGRAM CLASS 2 COMP 0hTNTS Program Section XI Reference Eram inam ist Insp. Interval Inspection Periods Component Section Method Cateoorv 40 Yr. Sample Sample Reference wm 3 vrs. 7 vrs. 10 vrt. Dwn. No. $@; C. Tanks H<
*M
- 1. CCP Tank (Boron N" Injection ' d t*
Tank) (1) o
*O n
- a. CCP Tank 8.5.1 UT C-A 1 Tank /2 Welds 2 1 0 1 ISI-0074-A Circumferential Shell/ Head Weld
- b. CCP Tank 8.5.2 MT, UT C-8 1 Tank /2 Nor. 2 0 1 1 ISI-0074-A Nortle to Vessel Welds
- c. CCP Tank 8.5.3 ST C-C 1 Tank /4 IA's 4 0 2 2 Integrally ISI-0074-A .
Welded Supports
- d. CCP Tank 8.5.4 VT-3 C-E 4 4 1 1 2 ISI-0074-A Component n Supports o
- e. CCP Tank 8.5.5 C-0 1 Mwy/16 Studs @
Pressure UT 1 Mwy 1 0 0 ISI-0074-A gg Retaining wn Bolting H g-
>2" Dia. u H
b i;
??*
1 li. L
~ u.
* ~8'u 8
n O MO>'
- n. u. , , _
[ J.-. . . .. - _ _ . -
.., . ,. ,_ 'y x+ _
ATTAC}ffENT 4 TABLE B SEQUOYAH INSERVICE INSPECTION PROGRAM CULS$ 2 COMPONENTS Progra+- Section XI Referent? Eram Eram- 1st Insp. Interval Inspection Periods Component Section viethod Catecorv 40 Yr. Sam,le Reference wm Sarole 3 vrs. 7 vrs.10 vrs. Dwo. No _, gQ
~
- 0. Plolna +4 <
E ".,
- 1. Intecrally Velded n t~
Svoports d C '. o Ec
- a. Safety 8.9.1.2 PT C-C 321 31 2.3 1 2 0 Injection MSG-0009-C System
- b. Main Steam 8.9.1.3 MT C-C 10 103 1 6 3 MSG-0017-C System
- c. Feedwater 8.9.1.4 MT C-C 5 5 0 3 2 FA-0016-C System n
O ( Ee G"n u 64 5 i; I 2 The change in support nosbers during the second period was due to new code class boundaries. 3 There are 4 safety injection IAs, only 3 can be examined. IA 2-SIF-10-IA is inaccessible (see RFR ISI-17). Change in number scheduled during the second and third period due to accelerated TV Program. 550
'2L ""
l.
~ ;; a -
, u
~ OP A -- 3' 8
~
.F .
. ,.__ - _ _ _ _ _ _ _ _ _ - _ - _ . - _ . - - . - - - = - - - - - -
~-
g -1 <
-;, ;- ,+ .m ,.
..7 ATTA09ENT 4'-
TABLE 8 }. SEQUDYAH INSERVICE INSPECTION Pft0GtAM CLASS 2 COMPONENTS Program. . Section XI-
-Reference Esam Enam Ist Insp. Interval Inspection Periods
. Component 'Section Method Cateoory 40 Yr. Sample Reference ' w in -
Sasele 3 vrs. 7 vrs. 10 vrs. Dwo. No. 'E $. , D. Pipino (Cont'dl +4 < '
. c" ."
- 2. Ploina and._ Valve O Coseonent Suororts .yC, gk .
- a. Residual- 8.9.2.1 VT-3. C-E- 826 823 6 25 55 25 Heat Removal VT-4 MSG-0010-CL 5ysten
' b. Safety 8.9.2.2 VT-3.- C-E 571 ** 571 3=4 18 39 0 MSG-0004-C Injection VT-4 System .
- c. Main Steam 8.9.2.3 VT-3 C-E 461 *4 ' 461 2.3.4 11 35 0 MSG-0017-C System VT-4
- d. Feedwater 8.9.2.4 VT C-E 30 -303 10 ' 20 0 System MSG-0016-C o YT-4 o.
- e. Containment 8.9.2.5 VT-3 C-E 5 53 4 Spray. System YT-4 1 0 MSG-0011-C g o'
- w eg ' .
N .. c - "q
-I M
. 2 The change in component supports' during the second' period was due to new code class boundaries. . .
50pport 2-MSH-312, 428 and 429 were CC-2 in the first period.. They became NMCC in the second period. 3Crange in number scheduled during the second arv' third period due to accelerated FW Program. 4 Change in number due to esemption in IWC-1220(a). 5Added supports for valve operators. 6 . Change in number of component supports during the third period was due to modification' to delete supports during UZC5. 4 1 i..wl.'_ i o O .. o-p~ y -' MC>' {. a: y 4 a. m b g LF%_'- gN ser g4 j4g d'4- 4 ie 4i..,. .%.g -3es.rs. - M! ,.s- '-'ef - d-*a -n m - -- ,u'% m. i"h.___--_.____-.a___ mahi_m.x_2._--r- . . - - - -
4, ,g '#O -
.' '- 4 ATTACHMENT 4 TABLE B SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS 2 COMPONENTS Program Section XI Reference Enam Enam 1st Insp. Interval Inspection Feriods Comoonent Section Method Cateoorv 40 Yr. *,asele Sample Reference w tn 3 vrs. 7 vrs.10 vrs. Dwa. No.
i.;4 <= - D. Ploino (Cont'd) 3. E" Circumferential and g t* Longitudinal Welds w"'
- a. Residual Heat Removal System okM
- 1. RHR Cires >1/2" Nom. Wall Thickness 8.9.4.1 .UT, PT C-F 271 6I 1 2 3 IST-0003-C
- 2. RHR Long. >1/2" Nom. Wall Thickness 8.9.4 1 UT PT C-F 3 61 21 0 1 1 ISI-0003-C
- 3. RHR Cires <1/2" Nom. Wall Thickness 879.4.1 PT C-F 1221 30% 8 11 11 IS!4003-C
- 4. RHR Long. <1/2" Nom. Wall Thickness 8!9.4.1 PT C-F 481 2 121 4 o 1 7 ISI-00034 o
- b. Safety Injection Systee G 1.
@o
, mn
$15 Circs >1/2" Nom. Wall Thickness 8.4.4.2 UT, PT C-F 41I 101 3 3 4 ISI-4074-4 M$
w ISI-0002-C H
- 2. SIS Cires 11/2" Nom. Wall Thickness $-
8.9.4.2 PT C-F 521 131 2 5 6 ISI-0002-C " I 2 The changes in weld numbers during the second period was due to new code class boundaries. The change in weld number during third period due to RHR modification U2CS. IEN 2 2. .
" 8 ~~
Row a: ~ . - {' 0 ir
~
-a I
ATTACHMENT 4 TABLE B SEQUDYAH INSERVICE INSPECTION PROGRAM CLASS 2 COMPONENTS Program' Section XI Reference.Enam Enam ist insp. Interval Inspection Periods Comoonent Reference H ** Section Method Cateoorv 40 Yr. Sanele Sample 3 vrs. 7 vrs.10 vrs. D. Piping (Cont'd) Dwo. No. E$ H<
.EU
- 3. SIS Long. 11/2" Nom. Wall Thickness O '
8.9.4.2 PT C-F 23i 51 0 2 3 ISI-0002-C U~
- c. Main Steam System -x g
.1. MS Cires >1/2" Nom. Wall Thickness 8.9.4.3 UT MT C-F 131 1 02 2 2 ISI 6 M
- 2. MS Long. >1/2" Nom. Wall Thl.kness 8.9.4.3 UT. MT C-F 61 21 0 1 1 ISI-0015-C
- d. Feedwater System
- 1. IV Circs >1/2" Nom. Wall Thickness 8.9.4.4 UT MT C-F 161 4 0 2 2 CHM-2403-C o
- 2. IV.Long. >1/2" Nom. Wall Thickness 'o 8.9.4.4 UT MT C-F 11 0 0 4~
1 1 CHH-2403-C gQ
- 3. FV Cires. i 1/2" Nom. Wall Thichness w tr 8.9.4.4 MT C-F 1 O See Note 3 H$
u
- e. Containment Spray System e
-5
- 1. CS Cires 11/2" Nom. Wall Thickness N 8.9.4.5 PT C-F 6 1 1 0 0 ISI.0007-C
- 2. CS Long. 11/2" Nom. Wall lhickness B.9.4.5- PT C-F 2 1 0 1 0 ISI-0007-C
~1 2 The changes in weld numbers during the second period was due to new code class boundaries.
3Weld MSF-10 'is now NNCC and it was examined in the first period as CC-2. Enaminations not scheduled this interval. 5YO 15.2 *
~7 % "8'. n
-3 .o e Eor; 8 o. y.
~ /
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. . .~ .: . L. - . 2 ATTAQf9ENT 4 TABLE B
~
SEQUOYAH INSERVICE INSPECTION PROGPAM CLASS 2 COMPONENTS Program Section XI Reference Exam Eram 1;t Insp. Interval Inspection Periods Component Reference w on - Section Method Cateaorv 40 Yr. Sasele Sarole 3 vrs. 7 vrs.10 vrs. D w. No. .gg
' E.' h g < ..
yD
- 1. Residual Heat Removal Pianos (2) RHRP n t* ^
d C _.
- a. RHRP Support Components ok 8.10.Y.2 VT-3 C-E 2 2 1 1 0 151-0352-8
*Q
- r. System Pressure Test 8.12 VT-2 C-H See Program Section 8.12 n
O Ee M t9 3. n b 5 175. 1 14
~ E %.
A O' "8u O noy n - .
~ e Un to 8
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.. ... - ..e~- . . . .
ATTACHMECT 4
- TABLE C' SEQU3YAH INSERVICE INSPECTION PROGRAM CLASS 3 COMPONENTS Program Section XI Reference . Esam Exam Component Section ' Method Category 40 Yr. Sasele ist Insp. Interval Samole Inspection Periods 3 vrs. 7 vrs. 10 vrs.
Reference -
- Dwe. No.
yy gg. A. System Pressure Tests EO
- 1. All ASME 9.0 VT-2 D4, D-8 N/A N/A q t~
100% 100% 100% N/A w Code Class 3 D-C (Equivalent) ' @ne9 B. Component Supoorts
- 1. Auxiliary . 9.1.1 VT-3 D-A 391 391 39 39 39 Feedwater System ISI-0146-C VT-4
- 2. .. Chemical and 9.1.2 VT-3 D-A 01 ,2 02 1
0 0 0 volume Control System VT-4
- 3. . Component 9.1.3 VT-3 D-A, D-8 1731 1731 165 Cooling System 173 173 ISI-0154-C VT-4 :
- 4. n Containment' 9.1.4 VT-3 D-B DI 01 0 0 0 0 Spray System
' 5. Essential Raw 9.1.5 VT-4 0-A, D-8 .'.,J5 1 3 f.
Cooling Water System VT-3 VT-4 3051 3 280 301 305 ISI-0158-C wE "A E-E I The change in support numbers was due to new code class boundaries. 2 3 The supports are not required to be enemined, due to no esamination category from this piping, TVA Safety Class D. the change in support number was due to addition of support in second period.
"NO s'.54 m
5 ,8-n ---
~
n o .m g 0- ii a e 6 _ _ _ . _ _ . _ _ _ _ . _ . _ _ _ . _ . _ . _ _ _ _ _ _ _ _ _ _ _ .[
. - , , . . - ~ a . . .
ATTAD MENT 4 ' TABtE C SEQUGYAH INSERVICE INSPECTION PROGRAM CLASS 3 COMPONENTS Program. Section XI Rererence-' Exam Eram 1st Insp. Interval Inspection Periods Reference M to - Component Section Method Cateoorv 40 Yr. Sample Sarole 3 vrs. 7 vrs. 10 vrs. Dwtr. No. Eh' H< B. Component' Supports (Cont'd) EU.
- 6. . Residual Heat 9.1.7 VT-3 D-B 01 01 0 0 0 C-Removal System VT-4 o 5:
mn
- 7. Safety 9.1.8 VT-3 D-8 OI 01 0 0 0 Injection VT-4 System
- 8. Equipment 9.2 VT-3 0-A 591 supports 591 ,2 53 59 59 See Component supports-Attachment I S
4
- wn tii e'
~
n 5 I 2 The change'in support numbers'during the second inspection period was due to new code clatz boundaries. The change in support numbers due to change out of component coollag heat enchanges, and the RHR heat exchanger class 3 support not included untti the second period. y g gl 2 L l-
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SI-114.2, Att chment 5 SURVEILLANCE R*,visica O INSTRUCTION SUCCESSIVE EXAMINATIONS Page 1 of 2 i ASME Section II Programs A. MAINTAIN a listing of cuccessive examinations. B. UPDATE listing as necessary. C. OBTAIN concurrence from Site Quality Manager or his designee. SOM D. CONCUR with listing by' signing below. ASME Section II Programs E. FORWARD to SPS for updating Table of Contents, etc. SPS T. FORWARD to DCRM. > DCRM G. DISTRIBUTE per SSP-2.7. h / / JY 92-Site Quality Manager / Designee Date 2217C
e
~y ATTACHMENT 5 w SEQUDYAH INSERVICE INSPECTION PROGRAM U SUCCESSIVE EXAMINATIONS n
Program Reference Exam Eram Successive Successive Examination Periods EE Exam Program _. Component Section Method Cateacr1 Reference section Examined U/C
--t tr/C 2nd 3rd Reference %$
wM U/C U/C Ibes. No. C 2-SIH-20-IA 7.4.7.4 PT S-K-1 IWB-2420 UZC4 U2C5 or 6 U2C7 or 8 U2C9 or10 M5G-0009-C
.O"-
MSW-)' 8.1.4 UT C-8 IWC-2420 =n' U2C4 U2CS or C6 N/A N/A ISI-0401-C H sn f 2 a M M M E 4 725-1 *14 u O U H n,~ M P N
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_;. SI-114.2, Attachment 6 SURVEILLANCE. R visica 0 I INSTRUCTION AUGMENTED ' EXAMINAU CNS Page 1 of *, i.. i 1 1 ASME Section II Programs , MAINTAIN a listing of augmented ereminations. A. B. UPDATE listing as necessary. C. OBTAIN concurrence from Site Quality Manager or his desiquee. SOM D. CONCUR with listing by signang below.
+
ASME Section II Programs E. FORWARD to SPS for updating Table of Contents, etc. SPS F. FORWARD to DCRM. DCRM G. DISTRIBUTE per SSP-2.7. L
$ L.-
Site Quality Mana'ger/Decignee t_l2ltf42 Date
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/ric t rV pi oh Cw e e ea ou o(Wne is n i n Rs r a
e s zd zn y e rg eg e t ygm t en apee tt aaos oE rl oF G g rn oi Gn ll n1 ne w i oF o6ir s w i cl dPazjrdd - vwt a N e cp t mn ai Md d mr r Cudu e ad te eds c eode eeee eeeh Pa Vf am eu eb Va Pl ee nb dsaa t u t e ou osl e C FTAh Fftt RS RP ST RC SF CT RACM u" en - g ;
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-OffAOerNT 6 SEQUOYAN IN',ERVitE INSPEC? ION PROGRMI AUGMENTED EXmtIntTIONS u
I e Program 0 Reference Esan Evanination Schedufe Ref. w es Coseenent section Method Cycle 1 Cvele 2 cycle 3 Cvele 4 cvele 5 cvele 6 Dwe. no. gg. Accelerated Field 5 <= - 20.9 Conclete Weld Frogram E" Thistle Tube . Qt* E 20.10 ET Each refueling cutage. See 'rogram Section 20.10. o* Guide *O-n. Enamination of 20.11 Ceselete Piping connected to the Reactor Coolant System Due to Thermal Stresses Enamination of welds 20.11 TJT E X CVCF-213 and CVCF-246 Esamination of SIF-145, 20.11 UT X N M SIF-168,' 51F-184. SIF-128 D M Examination of RCF-23 -20.11 UT Esaarination of welds 20.11 PT I I {E 2CX-1674 2CX-1675 g Csamination of 20.12 Complete O Pressuriner Surge Line Due to E Occurence of Thermal Stratification Esamrination of. . 20.13 See Program Section 20.T3. Row 1 and Row 2 Steast Generator Tubing Examination of Base- 20.14 PT- X X X ISI-C307-8 Material Transition Adjacent to Weld No. -2 RC-023 en RC. Puup No.- 3 Cold Leg e"e. e<* nain reedwater 20.is ni X X
*70 w .- -
Isolation Valves . See Program Section 20.15.
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