ML20127P546
| ML20127P546 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/16/1992 |
| From: | Crane E TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20127P527 | List: |
| References | |
| SI-114.1, NUDOCS 9302010313 | |
| Download: ML20127P546 (194) | |
Text
{{#Wiki_filter:n i ~ TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SURVEILLANCE INSTRUCTION SI-114.1 ASME SECTION 3CI INSERVICE INSPECTION PROGRAM UNIT 1 Revision 20 PREPARED / PROOFREAD BY: Ernie Crane DATE: /8 /C 8 SIGNATURE: M RESPONSIBLE ORGANIZA Sit!D adization APPROVED BY: DATE:' 22 [* EFFECTIVE DATE: I / U REVISION DESCRIPTION: Revised Sections 5.3, 5.8, and Augmented Section 20.0' for clarification of responsibilities. Corrected typo in Section 16.6. Revised Sections 7.1.2, 7.1.3,-7.1.5, and Attachment 4 on the scheduling of the reactor > vessel nozzle-to-vessel welds, nozzle inside radius sections, and nozzle to safe end welds. . Revised organization titles ISI Programs to ASME Section XI Programs. Moved 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 6. _ Revised Appendiz D, Sections 6.1.1, 6.1.2, 6.1.4, 6.1.6, and 6.2.1. Added-Developmental References 2 2.1. 4 2, 2 2.1'. 43, _. and 22.1.44. -Added-definition for augmented examination.- Revised Sections 20.1 and 20.11 to add examination requirements by Nuclear Engineering. Revised Augmented Section 20.0 per memorandum (L29 920828 800). l 9302010313 930128 PDR ADOCK 05000327 G PDR 1328C/COC3 m
SI-114.1 SURVEZLLANCE- ASME SECTION XI Rsvision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 2 of 102 TABLE OF CONTENTS Pace Owner Statement . . . . . . . . . . . . -. . .:.'. . . . . . .. . 4 0.1 Prerequisites . . .-. . . . . . . . . . . . . . . .. . . . . .. . 5 0.2 Precautions . . . . . . . . . . . . . . . . . . . . ... . ... 5 1.0 Statement of Applicability . . . . . . . . . . . . . . . . ... 5 2.0- Purpose . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 6 I 3.0 Inspection Intervals and Inspection Periods . . . . . . . . . . . 6 i
;I 4.0 Codes of Record and Codo Cases . . . . . . . ... . . . . . . .. 7 ; 5.0 Method of Implementation and Responsibilities . . . . . . . . ~ . 9 f
6.0 Abbreviations and Definitions . . . . . . . . . . . . . . . . .. 17
. 7.0 Components Subject to Examination - ASME Code Class 1 . . . . .. 19 8.0 Components Subject to Examination - ASME Code Class 2 . . . .. . 40-9.0 Components Subject to Examination - ASME Code Class 3 . . . . . . 52 10.0 Authorized Inspector . . . . . . . . . . . . . . . . . . . . . .. 58' 11.0 Examination Method and Calibration Blocks . . . . . .. . . ... 58 12.0 Qualifications of Nondestructive Examination Personnel .. . . . 59-13.0 Acceptance Criteria . . . . . . . . . . .. . . . . .. . . .. . .
59 14.0 Repairs and Replacements
. . . . . . . . . . . . . . . . . . . . 59 15.0' Pump and Valve Testing . . .. . . . . . . . . . . . . . . . . .. 59 16.0 Records and Reports . . . . . . . . . . . . . . . . . . . . .. . 59 s
17.0 Notification of Indication . . . . . . . . . . . . . . . .' . .. 62 18.0 Corrective Action Program . . . . . . . . . . . . . . . . . . . . 65 . l. 19.0 Roquests for Relief .
. . . . . . . . . . . . ... . .. . ._. .. 65 20.0 Augmented Inspections . . . . . . . . . . . . ' . .. . . .. . .. 65 21.0 . Interface Documents . . . . . . . .. . . . ... . . . . . . . .. 81 22.0 Developmental References . . . . . . . .. . . . . . . . .. . . 18 2 -
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'SI-114.1 SURVEILLANCE ASME SECTION XI R3 vision 20-INSTRUCTION. INSERVICE INSPECTION-PROGRAM ~ page 3 of 10?-
TABLE' OP CONTEHIS (Continued) EAgn APPENDICES-Appendix A - Tables . . . .................... 85 Appendix B - Data Sheets- .................... 87 Appendix L' - Notification of Indicatj r a Form . . . . . . . . . .- 88 Appendix D - Guidelines for Determin8.ng Piping Component Support Examination Boundaries . . . . 89 Appendix E - Field Corrected Drawing Transmittal Form . . .... 101
- SOURCE NOTES . . . . . . . ................... 102 ATTACHMENTS , Revisiqa Attachment 1 - Drawing List . .................. 2 Attachment 2 - Valve Tables . . . ................ 2 Attachment 3 - Requests for Relief ............... 3 Attachment 4 - Component Tables . . . . . . . . . . . . . . . . . 0 +
Attachment 5 - Successive Examinations. ............. 0 . Attachment 6 - Augmented Examinations . ............. 0 4-
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SI-114.1' SURVEILLANCE ASME SECTION XI Rovision 20-INSTRUCTION INSERVICE INSPECTION PROGRAM. Page 4 of 102 OWNER STATEMENT Owner Tennessee Valley Authority Address of Corporate Office: Chattanooga Offlee Complex 1101 Market Street Chattanooga, Tennessee - 37402-2801 - Name and Address of Nuclear Power Plants Sequoyah Nuclear Plant P.O. Box 2000 Soddy Daisy, Tennessee 37379 Applicable Nuclear Power Units: Sequoyah Nuclear Plant, Unit 1 Commercial Operation Date: July 1, 1981 h 4 l-l- 1328C/COC3
.-t; SI-114.1 SURVEILLANCE ASME SECTION XI R3vis10s 20
. INSTRUCTION INSERVICE INSPECTION PROGRAM Page:S of 102 0.1 PREREQUISITES 0.1.1 When craf t support of minor- or similar maintenance (examples -
scaffolding, insulation removal, buffing of welds using scotchbrite pads, and cleaning bo'ats) 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 Huclear Plant (SON) Standard Practice ' (SSP) 6.21 and the system code for SI-114.1 (system code.114.1) will be referenced on the WR. - Additional WRs are required to remove fire barrier insulation foam in sleeves, piping support clamps,- steam generator support rings, reactor coolant pump flywheel access covers and plugs, etc. 0.1.2 Contact Radiological Control (RC) for radiation work permit (RRP)/ ALARA preplanning requ.irements. 0.1.3 Controlled copies of ASME Section XI Code Classification Drawings and ISI Drawings are issued through DCRM. 0.2 Preenutions 1-0.2.1 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 RRP areas when working around hot pipes and '. equipment. 0.2.3 Care should be exercised when climbing on plant structures and piping to ensure firm footing. Flexing of instrument lines and electrical conduit, for example, could cause equipment damage as well as bodily injury resulting from a fall. Walking on-insulation shall be avoided. 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 Read and observe all applicable precautions as indicated in SON Administrative Instruction AI-8, " Access to Containment," and SSP-12.8, " Foreign Material Exclusion."' 1.0 STATEMENT OF APPLICABILITY Jrhis program outlines requirements for performirg the first 10-year interval inservice nondestructive examinations (NDEs) of the SQN Unit 1, American Society of Mechanical Engineers (ASME)-Code Class 1, 2, and 3
-(equivalent) components (and-their supports) containing water, steam, or radioactive material (other than radioactive waste management systems).
The program has been organized to fulfill inservice examination requirements of Standard (STD) 6.10 and comply as practical with the requirements of Section II of the ASME Boiler and Pressure Vessel Code. 1328C/COC3 e
SI-114.1 SURVEILLANCE ASME SECTION XI R3visica 20 INSTRUCTION INSERVICE INSPECTION PROGRAM _ Page 6 of 102 , In addition, this progran implements applicable portions of the SON. Technical Specifications. The Inservico Inspection-(ISI) Program satisfies the requirements of Surveillance Requirements: 4.4.3.2.4,. 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-commercial operation of the unit. 2.0 PURPOSE The ISI Program shall be used for_ planning inspections and examinations of SON ASME 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 INSPECTION INTERVALS AND INSPECTION PERIODS The inservice examinations required by ASMI Section 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 1 is July 1, 1981. 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 in 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 -Haximum Examinations Inspection Period Completed. Percent Comoleted. Percent 3 Years 16 34 7 Years 50 67 10 Years 100 100-The examinations deferred to the end of the inspection interval shall'be completed by the end of_the inspection interval. l l .' i 1328C/COC3
s.* SI-114.1 SURVEILLANCE ASME SECTION XI Revision 20
- INSTRUCTION Page 7 of 102 INSERVICE INSPECTION PROGRAM On August 26, 1985 SON Unit 1 went off line and remained off line until November 10, 1988.- In accordance with IWA-2400(c) TVA vill extend-the first interval by 1,173 days.- As a result of this extension, the first interval will end on September 15, 1994. The period duration will be as- .
follows:
, First period July 1, 1981 through June 30, 1984 Second period: July 1, 1984 throogh September 15, 1991 Third period September 16, 1991 through September 15, 1994 4.0 CODES OP RICORD AND CODE CASIS ~'
Preservice examinations were conducted in accordance with the 1974 Edition, Summer 1975 Addenda, of ASME Section XI. SI-114 was the Preservice Inspection (PSI) Program for SON Units 1 and 2. The SON Unit 1 operating license (low power) was issued on February-29, 1980. Thus, as a minimum the ISI Program shall not be prepared to a-Section XI Code Edition and Addenda prior to the 1974 Edition, Summer 1975 Addenda. In accordance with 10 CFR Part 50.55a(g)(4)(iv), this program was
, prepared to meet the requirements of the 1977 Edition, Summer 1978-Addenda, of Section XI of the ASME Boiler and Pressure Vessel Code.
Steam Generator Tubing Examination requirements are in accordance with Technical Specification,' Surveillance Requirement 4.4.5 and a modification of Regulatory Culde 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-F is in accordance with the 1974 Edition, Summer 1975 Addenda of ASME, Section XI (Examination Categories B-J, C-F and C-G). Extent of examination is defined as criteria for the 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 be examined. See Section 19.0 and Attachment'3 of this program for requests for relief information. NDE techniques, qualification of personnel, weld 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, IWA-3000i INB-3000, IWC-3000, IWD-3000, and INF-3000, as well as all~ portions of Appendices III, IV, and VI of ASME' Section XI. Certification of NDE personnel'will 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 O. D. Kingsley, Jr., dated January 18, 1990 (TAC No. 72833). 1128C/COC3
-SI-114.1 SURVE2LLANCE .ASME SECT 20N XI- Revision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 8;of 102 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 N-234, Time Between Ultrasonic Calibration Checks N-235, Ultrasonic Calibration Checks per 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
, N-401-1, Eddy turrent Examination
. N-402, Eddy Current Calibration Standard Material N-416, Alternative Rules for Hydrostatic Testing of Repair or Replacement of Class 2 Piping N-426, Extent of VT-1 Examinations, Category B-G-2 of Table IWB-2500-1.
N-435-1, Alternative Examination Requirements for Vessels with Wall Thickness 2 Inches or Less N-461, Alternative Rules for Piping Calibration Block Thickness Code Cases N-341, Certification of Level III NDE Examiner, and N-356, Certification Period for Level III NDE Personnel, were authorized for TVA use by NRC by memorandum from G rf L. Zech to.S. A. White dated January 25, 1988. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Helds, was authorized for TVA use by_ NRC by memorandum from Suzanne C. Black to 0. D. Kingsley, Jr., dated December 13, 1989. TVA will utilize Regulatory Guide 1.150, Rev. 1, " Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservico Examinations," for its examinations as outlined in the applicable NDE procedure. 132BC/COC3 1:
SI-114.1 SURVEILLANCE ASME SECTION XI Pavision 20 1 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 9 of 102 l j i 5.0 METi10D OP IMPLEMENTATION AND RESPONSIBILITIES Any revisions _ initiated by othat_ groups shall be submitted to ASME Section XI Procrams foe approval erlor to incoroorntlna the revisions into thls prootgm. 5.1 ASME Section XI Procrams -1 5.1.1 ASME Section XI Program Responsibilitiess ; A. Defining ASME Section XI Code Class 1, 2, and 3 (equivalent) boundaries in accordance with 10 CTR 50.2(v), Regulatory Guide 1.26 R3, ASME Section XI and guidelines 1 in 10 CFR 50.55a. l B. Preparing / revising ASME Section XI color-coded boundary cls*sification drawings to identify the ASME Section XI Code Classification 1, 2, and 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 Section XI drawings which
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identify the Class 1, 2, and 3 equivalent components (including supports) that require inservice and/or preservice nondestructive examination (NDE) to satisfy ISI Program requirements. See Attachment 1 for drawing ' list. D. Preparing / revising SQN ISI Programs as required. E. Ensuring that these programs provide detailed instructions for ISI including the following information as a minimum:
- 1. The ASME Section 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 examin .c 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 component.
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SI-114.1
~ SURVEILLANCE ASME SECTION XI R3 vision 20
' INSTRUCTION INSERVICE INSPECTION PROGRAM Page 10 of 102
- 9. Coplos of all requests for relief.
- 10. Name and address of owner.
- 11. Name and address of generating plant.
- 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. Discussion of scan plans whic!. provide details of required component examinatlons such as component identifier, NDE procedure, calibratlon block, draw 1ng number, etc.
F. Ensuring that Notification of Indication (NOI) rorm is 't included as an appendix within the ISI program. G. Providing PSI and/or ISI ASME Section XI interpretations as requested by various site organisations or as required in program development and implementation. H. ASME Section XI Programs shall be responsible for preparing and revising the initial piping component suppet t examination boundaries, Appendir D. .
,k . 5.1.2 ASME Section 22 Programa PRISIM Responsib111tles . A. Providing a list of components requiring examination.
during each period of the 10-year interval that-includes the components that muAt be examined during a specific refueling outage._ This listing shall include-the component identifier, ASME Section XI examination category and item number, examinatlon method, drawing number, sheet number, and examination requirement source. This list will be provided to the Site Quality Organization and the Inspection Services Organization 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'llating of components identified in 5.1.2.A. 5.1.3 ASME Section XI Procrans Renuest for Relief- Responsibilitiest 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 conformanco with ASME Code requirements is impractical.- 1328C/COC3
SI-114.1
' SURVEILLANCE. TASME SECTION XI R3 vision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page.11 of 102.
B. Ensuring that requests for relief include supporting information on the need for relief and any alternate-examinations are documented. C. Submitting Requests for Relief to Site Licensing. 5.2 Ihn_Jnspection Services Organization (ISO) 5.2.1 ISQ_Ehall be ResponsiblL fn A. Preparing / revising PRISIM data base to include all components within the ISI Program Instruction for-SON. B. Preparing / revising scan plans for each refueling outage of an inspection interval utilizing 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 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 Site Quality Organization in accordance with plant schedules. E. Any areas that are inaccessible or partially inaccessible for examination will be evaluated by NDE. Level III. personnel to determine if a request for relief sho.1d be
, submitted to the NRC. Site Enginaering should be consulted where structural support members are inaccessible. This information shall be provided to ASMt Section XI Programs.
F. NDE Level III shall compare completed examination results to the requirements of the scan plan,' identify-any limitations or mpractical~ examinations, and provide notification to ASME Section XI Programs for possible-action in accordance with Section 19.0 of this program. G. 7reparing/ Revising NDE procedures. H. Preparing / Revising the qualification / certification program for NDE personnel. 5.2.2 ISO Reeggysibilities When NDE Performed by Contractors: A. Ensuring the adequacy of prospective contractor's QA programs in accordance with the TVA NOA Plan. B. Ensuring the preservice and/3r inservice examinations are performed in accordance with TVA NDE procedures or performed in accordance with contractor procedures that t have been authorized for use by ISO.
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SI-114$1-
- SURVEILLANCE ASME SECTION XI Revision 20-INSTRUCTION INSERVICE INSPECTION PROGRAM Page 12 of 102 C. Contract preparation and administration will be the responsibility of ISO. Inspection plans submitted by:
outside contractors shall be reviewed and approved by ISO prior to use. D. Approving contractor's written practices for qualification and certification of NDE personnel and approving. certifications of contractor's NDE personnel utilized for-the performance of PSI /ISI as specified in QMP-102.4. 5.3 The Site.Ouality Oreantration (S00) 5.3.1 S00 Responsibilities on Scheduled Examinations: A. Providing a list of the components to be scheduled for examination during each refueling outage to the
, Inspection Services Organisation. This will be provided in accordance with plant schedules.
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B. Initiating a pre-outage meeting on augmented examinations
-- per Section 20.0.
5.3.2 S00 Responsibilities on Sean Plans A. Approving all scan plans and scan plan revisions. B. Submitting copies of the approved scan plan to site
- management.and to the authorized Nuclear-Inservice Inspector (ANZI).
5.3.3 S00 Reseensibilities on Performance of NDE A. Performing NDE in accordance with ISI Program Instructions, applicable scan plan, and NDE procedures
. utilising personnel certified in accordance with OMP-102.4.
B. Ensuring that the services of an Authorized Inspection Agency (AIA) are used when-performing Code-required examinations through a contract established with an AIA. Duties of the AIA inspector are described in IWA-2000, Section XI, of the ASME Code. C. Arranging for the AIA representative to ha've access to any documents and all parts of the plant and offices (subject to plant security and health physics requirements) necessary;for performing his required-duties. l- D. ~ Notifying the ANII prior to starting examinations. l l E. Preparing NOIs for examination results which, when ! evaluated by Level II or III examination personnel, do not meet the acceptance criteria of the NDE' procedure. NOIs do not apply.to PSI NDEs following repair and
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replacement activities. l -- 1328C/COC3
-i SI-114.1 SURVEILLANCE ASHI SECTION XI Revision 20-INSTRUCTION: INSERVICE INSPECTION PROGRAM Page 13.of 102 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 on NOI form prior to closure. I. Ensuring that original of the closed NOI-is filed with the original examination report and a copy is sent to ASME Section XI Programs, J. Preparing examination reports. for completed examinations in accordance with the format in the NDE procedure..
- 1. Ensuring that all scan plan examinations are completed prior to the completion of each refueling
, outage.
- 2. Ensuring that status of completed examinations are recorded in the scan plan.
Ensuring that report number, date of examination, 3. examiners initials and any comments or discrepancies 2 (NOI number) are recorded in the scan plan. *
- 4. Submitting the original examination reports to DCRM :
as OA records. K. Ensuring that ASME 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 ASME Sect!on XI Programs. L. Jus NDE T,evel II or III-individual shall evaluate- the NDE results in accordance with ASME Section XI, IWA-3000. The results shall be compared with recorded results of the preservice NDE and. previous inservice NDE results. 5.3.4 SOO Responsibilities on Reports: A. Preparing ISI Summary Report including Form NIS-1 in accordance with requirements of ASME Section XI IWA-6000.
- B.- Ensuring that Form NIS-1 is signed by the ANII.
C. Submitting Inservice Inspection Summary Report within 90 days of the completion of the inservice inspection (refueling outage) to Site Licensing. 1328C/COC3
SI-114.1'
-SURVEILLANCE ASME SEC110N XI' Revision 20 INSTRUCTION- INSERVICE INSPECTION PROGRAM Page 14 of 102 D.' Following each refueling outage when inservice examinations are performed, the Site Final Report Cover Sheet in-Appendix B-shall be completed by S00 and submitted to the plant with the final report discussed in b -6 Section 16.0.
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 record. 5.3.5 300 Responsib111tles When NDE Performed by Contractorat
't A. Ensuring that contractors are familiar with the IFI
, Prcyram Instruction being used.
. ..' B. Ensuring contractors are certified using guidelines of QMP-102.4.
C. Maintaining surveillance 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. 5.3.6 SOO Responsibilities With PSI Conducted in Manufacturer's Shop SQo is responsible for ensuring records are identified and documented as are TVA-generated reports in accordance with this instruction.- Other report formats may be ut111ted - provided the minimum required information is contained therein. 5.3.7 390 Responsibl11tles for Comeonent Suoport Boundarles-SQO shall be responsible for determining the examination boundary for new or modifiud supports. 5.4 Site Document Control and Records Management (DCRM) DCRM shall be responsible for issuing controlled copies of ASME Section XI Code Classification Drawings and ISI Drawings to
.specified distribution lists.
DCRM shall be responsiblo for providing-controlled copies of ISI Program instructions to S00, the Authorized Nuclear Inspection / Authorized Nuclear Inservice Inspector (ANI/ANII), ASME Section XI Programs Supervisor, and'to the Site Licersing Manager as requested. f 1328C/COC3
5' SI-114.1' JSURVEILLANCE .ASME SECTION XI Revisien 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page,15 of 102' 5.5 Steam Generator Maintenance and Technolpay (SGHT) -, A.- Providing a' list of steam generator tubes to be examined for;a-specific refueling outage. This listing 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 S00 and ISO in accordance with plant schedules.
- 5. 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, and 20.6. 5.6 Site Licensing Manager Site Licensing Manager is responsible for submitting ISI Program Instructions, revisions, requests for relief an6 reports to the NRC-.
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for review and/or approval. All ASME Section XI correspondence shall include ASME Section XI Programs on distribution. 5.7 Plant Mananer Plant Manager is responsible for approving and ' issuing SI-114.1. l
, The Plant Manager 1s-responsible for designating the organization responsible for preparing dispositions for NOIs.
5.8 Site Engineering
, Site Engineering is' responsible for designing, fabricating, i-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 Engineerfsg is respotsible for evaluating and providing a disposition for indications initiated.hy~a Notification of , Indication (NOI). Site Engineering is responsible.for providing specific written-details for any augmented requirements which they are responsible-for as stated in Section 20.0-and to determine if a post examination meeting is required. Site Engineering is responsible far determining critical areas of examination to ensure structural integrity has not been compromised and identifying these areas to the NDE Level III when requested. 1328C/COC3
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SI-114.1 SURVEILLANCE- ASME SECTION XI Ravision~20
-INSTRUCTION : INSERVICE' INSPECTION PROGRAM Page 16 of 102 a
Site Engineering is responsible for evaluating and making recommendations for further action on samples with indications - af ter-the second additional sample has been performed and submitted by ASME Section XI Programs. S.9 EHJ_ Conducted in Manufacturer's Shop If examinations were performed in the manuf acturer's shop, they may serve as PSI examinations provided: A. They were performed after hydrostatic test of vessel. B. They were conducted under conditions and with methods expected to be employed for subsequent ISI examinations. 5.10 lE211 mentation ASME Section XI Programs, ISO, and S00 utilize a computerized data
'l base system, PRISIM, for status and Section XI credit of completed ISI examinatione 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.
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All specific NDE procedures used during the inspection program shcll be reviewed and approved in accordance with the NDE Procedures Manual, QMP-110.5. NDE procedures will be implemented in accordance with SSP 3.1. <
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Whenever aa unacceptable indication is discovered, Section 17.0 of
, this procedure and the form in Appendix C shall be utilized. In those cases where an outside contracter is furnishing inservice examination services, the contractor will normally initiate the form in Appendix C under the supervision of the SQO Representative. See Section 17.0 of this program.
5.11 Sean Plan The scan plan should include as-a minimum references to-components to be examined, methods-of examinations, examination procedures, and calibration standards. Prior to performing examinations on a system or component, the scan plan shall be approved by S00 and an NDE Level III individual from ISO._ ISO shall submit scan plans to 500 in accordance with plant schedules. SQO shall submit copies of the approved scan plan to Site Management and to the Authorized 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 organization 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 involvca with the implementation of the scan plan. All 1328C/COC3
, - __ _ ~ _ _ . . -- _
.. . - - - . . -. . -. .. . _ ~ ~ ~ - = ~
SI-114.1 SURVEILLANCE ASME SECTION XI Revision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 17 of-102
. changes shall be coordinated with an 500 Representative and,Jas
-needed, with the= appropriate plant plaining and scheduling personnel for facilitating the use of supporting craft = personnel.
Revisions to the scan plan shall-be controlled-in the.same manner as the original. ISO shall maintain a 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 an NDE Level III. Both individuals shall sign and date all such changes. ! 5.12 Piping Co.pflouration Changga When major portions of oxinting piping are replaced or whole new systems are added, a system walkdown should be performed by ASME Section XI Programs to identify the piping configuration, welds, i and components that will be included in the inspection program. If variations in configuration are discovered or modifications P l (including additions and deletions), replacements, or repairsLare 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 c7trected drawings shall be transmitted to ASME Section XI Programs by SQO using a drawing f. transmittal form as in Appendix E of this program. _A file and ~ transmittal number log of the corrected drawings and transmittal n forms shall be mairsained by SQO for future reference. ASME Section XI Programs shall be responsible for reviewing the proposed change, revising the drawings as necessary, and issuing the revised drawing prior to the next refueling outage. The transmittal-form shall be returned to the SQO after the referenced drawings have been revised by an ASME Section XI Programs representative. The ISO mean 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 ADEREYIATIONS AND DEFINITIONS r 6.1 AIA - Authorized Inspection Agency. 6.2 AI - Authorized Inspector (may denote 3n ANI or ANII). 6.3 ANI - Authorized Nuclear Inspector. 6.4 ANII - Authorized Nuclear Inservice Inspector.
-6.5 Iype A Examination Boundary: The type of boundary to be used for those supports that are attached to-building floor, walls, ceiling, or embedded plate.
6.6 Type B Examination Boundary: -The type of boundary to be used for those supports that are attached to another existing support. 6.7 Iype C Examination Doundary: The type of boundary to be used for those supports that are attached to existing steel. 1328C/COC3
81-114.1 SURVEILLANCE. ASME SECTION XI -Rsvision 20: INSTRUCTION. _ INSERVICE INSPECTION PROGRAM Page.18 of 102 6.8 Type D Examination Bounderve The type of boundary to be used for those supports that are attached to an intervening element.. 6.9 Notice of Indichtion (NOI) - A form used to report any discrepant. conditions found during the performance-of nondestructive examination.. Used for ISI examinations only. 6.10 Scan Plan - A schedule of examinations required to be performed during a particular period of time. 6.11 NDE - Hondestructive Examination. 6.12 WR/WO - Work Request / Work Order. 6.13 PER - Problem Evaluation Report. 6.14 Program for ISI Data Management (PRISIM) - A mainframe computer program for scheduling, tracking, maintaining status, and reporting
, of ISI examinations performed on a site / unit basis. It has the capability to allow categorization of these examinations by areas +
as needed for Code credit, additional exam credit, augmented credit, etc.
~ 6.15 Components - Denotes items in a power plant such as vessels, piping systems, pumps, valves, and component supports.
6.16 Normal Operation - Normal plant operation conditions' include reactor startup, operation at power, hot standby, and reactor cooldown to cold shutdown conditions. Test conditions are ercluded. 6.17 Pressure-Retaining Material - Applies to items such as vessel heads, nozzles, pipes, tubes, fittings, valve bodies, bonnets, disks, pump casings, covers, and boltings which join pressure-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,Ldisc, 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 replacen.ent shall apply where attachment to the. pressure boundary is by welding or mechanical means. 6.20 FIR - Finding Identification Report 6.21 SCAR - Significant Corrective Action Reports 6.22 Examination - Denotes the performance of all visual observation and nondestructive examination. 6.23 Inservice Inspection (ISI) - Inspection required by ASME Section XI during the service -lifetime of the power unit. [ 1328C/COC3
SI-11'4.1L
, SURVEILLANCE ASME SECTION'XI Revision 20
-INSTRUCTION INSERVICE INSPECTION PROGRAM. Page 19 of 102 6.24 Nondestructive Exnmination (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 psrticle, inservice visual, and welding visual. These methods do not impair the serviceability of the items.
6.25 Preservice Inspection (PSI) - Inspections required by ASME-Section XI to be completed prior to initial plant startup, or-inspections required by ASME Section XI Af a component 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 rate testing. Augmented NDE includes all NDE which is not required by the ASME Section XI l except (1) fabrication and installation NDE performed in accordance with design specification or construction code requirements, and ' (2) leak rate testing required by 10 CFR 50, Appendix J.
. 7.0 COMPONENTS SQBJECT TO EXAMINATION--ASME CODE CLASS 1 (EOUIVALENT)
The ASME Code Class 1 (equivalent) components to be examined during the
~'
inspection interval are outlined in the following patagraphs. The entire length of each-weld described shall be. examined for the first 10-year ISI
, interval unless otherwise noted. When a portion of a wold length is to be examined during an inspection period, the areas examined each inspection period shall be documented on the examination data sheets.
Components exempted from examination are discussed in Section 7.7 of this program. Table A of Attachment 4 provides additional information such as reference drawing numbers and ASME Section XI, Table INB-2500-1, examination categories. 7.1 Reactor Vessel 7.1.1 Esactor Vessel Seam welds 7.1.1.1 Circumferentiel Shell-Welds There are four circumferential. welds (each approximately 50 feet in length) in the vessel cylindrical shell, three of which are located behind the thermal shield, The entire length of each of these welds will be ultrasonically examined during the third inspection period using remote inspection devices from the vessel ID with the core internals removed. The vessel shell sections are machined forgings fabricated of A-508, Class 2, manganese-molybdenum steel and are clad with weld deposited austenitic stainless steel. 1328C/COC3-r-~ e e- y
SI-114.1 s SURVEILLANCEJ 'ASME SECTION'XI R3 vision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 20 of 102' 7.1.1.2 Lonoitudinal Shell Welds
~
There are no longitudi'nal shell welds associated with-the: reactor vessel. 7.1.1.3 Closure Head Circumferantitl Weld The entire length of the closure head cap' weld
, (approximately 41 feet'in length) will be manually ultrasonically examined from the head outside ;
diameter. The length of weld to be examined each inspection period is included in Table A of Attachment 4. During the conduct of the Unit 1 preservice examination a flaw indication in the closure head weld was observed (weld 09-10). F?nw evaluation and acceptability was based on Code Case N-209-(see Nonconforming Report 6P for additional information
; concerning flaw evaluation and location). In
, a6dition to the examinations above, the flaw indication volume shall be examined during each inspection period. This provides examination of the
~
flaw indication volume for three successive inspection periods. Should these successive s t examinations reveal that the flaw indication has remained essentially unchanged, then the'eramination
~
frequency may revert to that of Examination _ Category B-A of Table INB-2500-1 of ASME
'~
Section XI. If the successive examinations reveal
, that the flaw indication size has increased, then.
technical justification shall be presented-to'NRC for allowing continued operations. , The closure head ring is fabricated of A-508, Class 2, manganese-molybdenum steel. The closure head hemispherical:section'is fabricated of A-533, Gr. B, Class 1, manganese-molybdenum steel. -Both sections are clad-with weld deposited austenitic stainless steel. 7.1.1.4 Lower-Head Circumferential neli-The entireflength of tho lower head circumferential. weld (approximately-38 feet in length) will be ultrasonically examined during the third inspection period using remote inspection devices.from.the-vesselu1nside' diameter with the core internals removed 1(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 wald-deposited austenitic stainless steel, 1328C/COC3
JSI-114.1 SURVE1LLANCE. ASKE SECTION XI. Revision 20 INSTRUCTION ' INSERVICE INSPECTION PP0 GRAM -Page 21Lof=102 7.1.1.5 Closure-Head Merldlonal Weld The closure head does not include any meridional welds.- l 7.1.1.6 Lower-Hggd.Merldlonal Welds I There are six meridional wolds (each approximately 4 feet in length) located in the lower head. The entire length of each of these welds will be-
- ultrasonically examined during the third inspectionJ l_ period using remote inspection devices from the vessel inside diameter with the core internals remcved.
The lower-head section material is fabricated of A-533, Gr. B. Class 1, manganese-molybdenum steel and clad with weld deposited austenitic stainless
, , steel, i 1
- . 7.1.1.7 Shell-To-Flance Weld l
l_ The entita length Jf the shell-to-flange weld P (approximately 50 feet in length) will be L ~~ ultrasonically examined from the vessel inside ~ diameter using remote inspection devices during the. third inspection period (see Request for Relief i
, ISI-10) 1 l The vessel flange sectian is fabricated of A-508, Class 2, manganese n olybdenum steel and-is clad internally and on the gasket face with. weld deposited austenitic stainless steel.
7.1.1.8 Closure Head-To-Flapoe Wglo and Flex Area l The entire length of the head-to-flange weld j (approximately 45 feet in length) will be manually, ultrasonically examined from the head outside l- diameter. The entire-length of the closure [ head-flex area will be surface examined during the: inspection interva,1 The length of weld to be-examined each inspection period.is included in Table A of Attachment 4. ] The closure head flange section is fabricated of A-508, Class 2,~ manganese-molybdenum steel and is clad internally and on the gasket face with weld i deposited austenitic stainless steel. L 4 l 132BC/COC3
SI-114.1 SURVEILLANCE ASME SECTION XI R: vision 20-INSTRUCTION INSERVICE INSPECTION PROGRAM Page 22 of 102-I 7.1.1.9 Repair Welds Base metal weld repairs in the beltline region where
~
the repair depth exceeds 10 percent nominal of the-
" vessel _ wall shall be_ ultrasonically examined. There are no base metal _ repair welds in the beltline region of the Unit 1 reactor vessel.
7.1.2 Empetor Vessel Nozzle-To-Vessel Welds There are four inlet nozzles (27.500 inch ID) and four outlet nozzles (29.937-inch ID). The eight nozzle-to- vessel welds :1 will be ultrasonically examined from the inside c'lameter ! using remote inspection devices. The four outlet nozzle-to-vessel welds shall be ultrasonically examined from the nozzle bore when the upper inte-'als are removed during the first inspection period. " The inlet nozzles are not accessible until the core barrel is removed. The four-in2et nozzle-to-vessel welds shall be ultrasonically examined-from the nozzle boro and from the vessel shell inside diameter during the third-inspection period when the core barrel has been removed. The outlet " nozzle-to-vessel welds shall also be ultrasonically examined from the vessel shell inside diameter _ during the third inspection period when the core barrel has been removed. T'1e examination schedule has. changed. See Request for Relief ISI-14 for background information. The new schedule requires that the four inlet and four outlet nozzle to vessel welds 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 nozzle forgings are fabricated of A-508,' Class 2, manganese-molybdenum steel _ and are clad with weld deposited austenitic stainless steel. 7.1.3 Reactor Vessel Nozzle Inside Radius Section The eight nozzle inside radius sections (including the outlet-nozzle integral extensions) shall be ultrasonically examined at the same time as the examination of the nozzle-to-vessel welds (see Section 7.1.2). For background information,-see-Request for Relief ISI-14. Nozzle forging material is identified in Section 7.1.2 of-this prograr . 7.1.4 Reactor Vessel Partial Penetration Welds-The vessel includes 4 Upper-Head Injection (UHI) nozzles (capped in Unit 1 Cycle 4 UHI removal), 1 vent pipe nozzle, 78 control rod drive nozzles, and 58 instrumentation nozzles with partial penetration welds. Approximately 25 percent of each group of nazzles shall'be visually examined from the 1328C/COC3
M SI-lle.1-
,, ' SURVEILLANCE ASME SECTION XI R0 vision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM- Page 23 of 102 ]
vessel outelde diameter in accordance with visual examination methed VT-2. .This 25 percent shall include 1 UHI nozzle,. I vent. pipe nozzle, 20 control rod drive nozzles, and 15 instrumentation nozzles. Examinatiou of these ' nozzles during the inspection interval shall be distributed-among-the. inspection periods in accordance with Table A of Attachment 4. 7.1.5 Peactor Vessel Nozzle-To-Safe End Welds The inlet and outlet nozzle-to-safe end welds shall be , ultrasonically examined from the inside diameter using remote inspection devices. The n;crasonic examination shall be-performed at the same time as the examluation of the nozzle-to-vessel welds conductSd from the nozzle bore (see Section 7.1.2).
! All of the nozzle-to-safe end welds shall also be liquiG penetrant examined during the inspection interval coincident
*?
with the ultrasonic examinations. The SON Unit 2 Report--
" Evaluation of Cracxing in Reactor Vessel Nozzle Stainless
, Steel Buttering"--states that Unit i nozzle-to-safe end welds RC-0)-SE and RC-32-SE shall be examined during the first inspection interval (see memorandum from D. W. Wilson to H. L. Abercronble, dated August 1, 1986 (L18 860730 899)).
The remaining nozzles will be examined during the normal ISI-intervals. r The examination schedule has changed.. For background information, see Request for Relief.ISI-14. The now schedule
~
requires that four inlet and four outlet nozzle-to-safe end welds be examined during the third inspection period. Each nozzle safe end weld is a etainless steel type 304 weld- 4 build up (buttering). 7.1.6 Reactor Vessel Pressure Retaininn Boltino Larcer Than Two
+
Inches In Diameter During each refueling outage all closure studs, nuts, and washers are removed. . All of the 54 closure studs, nuts, washers, and ligaments between the vessel flange stud . holes - shall be examined during the inLpection 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 examined. The ligaments between.the vessel flange stud holes"shall be ultrasonically examined. The closure washers shall be visually examined in accordance with visual examination method VT-1. The bolting may be examined either-(a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed. t 132BC/COC3
S!.114.1 SURVEILLANCE ASME SECTION XI R: vision 20 INSTRt!CTION INSERVICE 1HSPECT10N PROGRAM Page 24 of 102 Provisions for this examination are included in 0-MI-MRR-068-005.0, Where needed the examinations of the stude should be identified with the particular stud in accordance with the unique adentification system for the studs and nuts. The 7-inch dinmeter studs, nuts, and washers are fabricated of Sa-540s Gr. B23 Nickel, chrome-molybdenum steel. 7.1.7 EgAct20.1 CAB 11.ELeD ADLeletNining_l)A11dng_TyAJnchel and EmAllt.t.itLDIDMLCI There is no pressure retaining bolting two inches or smaller in diameter. 7,1.8 EeAgtDI_VeAlcl_lnLegtallyJtidcu Attachnents There are no integrally walded vessel supports. 7.1.9 Etantor VesseLlntarigt The vessel interior shall be visually examined in accordance with visual examination method VT-3. These examinations shall include the space above and below the reactor core that is made accesrible for examination oy removal of components during normal retuoling outages. The examinations shall be performed at the first refueling L outage and subsequent refueling outages at-approximately three-year intervals. 7.1.10 EcAct0JJAADALEenyAbislarA_gDpport Structurla The visually accessible attachment wolds and visually accessible surfaces of the core support structure shall be visually examined in accordance with visual emnmination , method VT-3. This examination may be deferred to the third inspection period. The structure shall be removed from the reactor vessel for examination. The removal of the core support structure is implemented by M1-1.4. 7.1.11 Renator vennel_Cnntrol Rod Drive Housinos There are 70 control rod drive housings penetrating the closure head. Each housing inrludes a pressure retaining discimilar metal butt weld. There ana 20 peripheral control rod drive housings. Two (10 perconf+ of the peripheral housing butt welds shall be ultrasonically examined during the inspection interval in-accordance with Table A of Attechment 4. The housings consist of a 6-inch OD adapter of A-182, 304SS and-a 4-inch OD body of SB-167. 1328C/COC3
51-114.1 SURVEILhANCE ASME SECTION XI R v1 Lien 20 INSTRUCTION INSERVICE INSPECTION PROGRAM page 25 of 102 7.1.12 EtAtt 0I_.YAAne l Au r i_11Ary_Jie a d J.dapicI.A Each of the four auxiliary head adapters includes a pressure retaining dissimilar metal weld. The four dissimilar metal welds shall be ultrasonically and liguld penetrant examined
~
during the inspection interval in accordance with Table A of Attachment 4. The adapters consist of a SA-182, 30456 upper portion and a SB-166 lower portion. See Section 7.4.4.6 for information on RV auxillary head adapter circumferential pipe cap welds. The pipe cap welds are included in the reactor coolant system. ( 7.2 Pressurizer 7.2.1 Ergasurizer Circumferential Shg11-To-Head yelds
There are two circumferential shell-to-head wolds, each approximately 24 feet in length. The entire length of each weld shall be ultrasonically examined during the inspection laterval in accordance with Table A of Attachment 4.
" All vessel shell and head sections are fabricated of SA-533, Class 2, manganese-molybdenum steel and are clad with
, austenitic stainless steel.
7.2.2 Eressurizer Longitudinal Shg11:To-Head Welds There is one longitudinal veld intersecting each ' circumferential shell-to-head weld. One foot of each longitudine1 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-shell weld. The vessel shell section material is identified in Section 7.2.1. 7.2.3 Eressurizer CircumikIERtial and Merldlonal He3d Welds There are no pressuriser circumferential or meridional head welds. 7.2.4 Pressur)2er Nortle-To-Vessel Welds and Nortle Inside Radlyg Section The pressuriser includes three 6-inch safety valve nozzles, one 6-inch relief valve nozzle, one 4-inch spray nossle, and one 14-inch nurge nozzle. All of the nossle-to-vessel welds, including nozzle inside radius section, shall bel ultrasonically examined during'the inspection' interval in accordance with. Table A of Attachment 4. 1328C/COC3
SI-114.1 4 $URVEILLANCE ASME SECTION XI Rsvisics 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 26 of 102 The nossles are fabricated of SA-508, Class 2, manganese-molybdenum steel. ? 7.2.5 RItaggIlger JIenter Penetration Welda , t
~~
There are 78 heater penetration welds located in the ; pressuriser lower head. Approximately 25 percent of the heater penetration welds (20 welds) shall be visually examined during the inspection interval in accordance with visual examination method VT-2. Examination of these penetrations during the inspection interval shall be distributed among the inspection periods in accordance with Table A of Attachment 4.
"i.2.6 Erg 31utiger_Nostle-To-Safe End Welds i
Each of the six nomsles identifled in Section 7.2.4 includes a welded forging safe end. All of the nossle-to-safe end welds shall be ultrasonically and liquid penetrant examined M during the inspection interval in accordance with Table A of i ;, Attachment 4. Safe end connections are SA-182, Gr. F-316L forgings. 7.2.7 Pressurizer Preigure Retaining Joltino Larcer Than Two ; lashes..In DiametgI There la no pressure retaining bolting larger than 2 luches in diameter. 7.2.8 Pressurizer Pressurg_Retalning.Boltino Two Inches and Smaller In.Elametet 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 be11n , 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 cove- la performed in accordance with 0-MI-MXX-068-004.0 and provides for examination of bolting. The manway includes 16 bolts at 1.88 luches in diameter. 7.2.9 RIggsuriggr IntegIAlly Welded Support Attachments 7.2.9.1 RIggiurizer-Eupport skirt The entire-length of the pressuriser support skirt-to-vessel weld (approximately_23 feet in length) shall be surface examined (magnetic particle) during the inspectiou interval in accordance with Table A of Attachment 4. 1328C/COC3
SI-114.1 [
. SURVEILLANCE ASME SECTION XI R;visios 20 INSTRUCTION INSERVICE INSPECTION PROGRAM page 27 of 102 r
The support skirt is approximately-1.5 inches thick and is fabricated of SA-516, Gr. 70, carbon steel plate. 7.2.9.2 Prennu1133r Seismic Lugg . l There are four (4) integrally welded seismic lugs ! on the pressurizer, whose design base thickness is greater than 5/8 inch. All four (4) lugs shall be - surf ace examined during the inspection interval in accordance with Table A of Attachment 4. 7.3 SicAm_.Gfne r a tor s (11 7.3.1 $1 tam _ Generator Primary Side Circumf.tIsatial And Beridional litA1.ticlda There are no steam generator primary side circumferential or ,, meridional head welds.
,t 7.3.2 S.tgca SentInto.r Primary TubgzhngMo-11ead.. 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 4 inspection periods. The entire length of the two remaining welds shall be examined during the third inspection period. See Table A of Attachment 4 for examinations during the
, inspection interval.
s The tube plate is a SA-508, Cless 2,' steel forging, clad on the primary side with HlCrFo alloy. The hemispherical chamber is a SA-216, Gr. WCC casting, clad with austenitic stainless steel. 7.3.3 Steam General 2r Primary Nozzles Ingide_ Radius Section The steam generator primary nozzles are an integral part of the vessel. Each steam generator consists of two integrally cast nozzles. The nozzles are fabricated to SA-216, Gr. WCC. The primary nozzles inside radius section of all , nozzles shall be ultrasonically examined. In accordance with the SQN Unit 1 NRC Safety Evaluation Report dated February 7, 1991, Enclosure Paragraph 2.3 (page 4) states-
"that delaying the volumetric examination of the nozzle sections _until the third inspection period of the first-inspection interval and then following the Code requirements-is acceptable." See Reguest fcr Relief ISI-6.
1328C/COC3
GI-114.1 SURVE!LLANCE ASKE SECTION X1 Revision 20 , INSTRUCTION INSERVICE INSPECTION PRdGRAM Page 28 of 102 7.3.4 EteAt!L.GantIAtor Primary NonigdgdA{e End He3ds ! Each steam generator includes two nostles with buttered safe ends. Each nossle-to-safe end wold from each generator shall be ultrasonically and 11guld penetrant examined during the inspection interval in accordance with Table A of , l Attachment 4. ' The nossles have buttered 308L safe ends. t 7.3.5 EtnAtLGinerator Primatr.frasaure Reininin9 Daltina 1BIstI Than Two Inches In Diameter There is no pressure retaining botting larger than two ' inches in diameter. $ 7.3.0 Eteam Gengrator Primary PresgMro Retninina_Ballina Two Inches and Smallar In Diameter Each steam generator includes two manways. Each manway r. 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 la performet in accordance with 0-MI-MXX-068-003.0 and provider-for examination of bolting.
- 7.3.7 Steam Generator Prtmary Int 6crt11y 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 strengtt bolts.
7.3.8_ Eteam Generatgr_ Tubing See Augmented Inspection Section-20.4 for steam generator tubing examination information. 7.4 Eining
?
All ASME Code Class 1 piping systems tt be examined are fabricated of stainless steel. The reactor coolar.t; main loop piping straight lengths are-centrifugal cast and.the elbows are static catt. 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, and pipe branch connection welds, examination categories B-F'and B-J, which have ' interference problems for volumetric es amination. 1328C/COC3
. _ _ - . = , -_. _ .- - - .__ -.
SI-114.1 I'EUA's LLPJCE ASMC SECTION XI Rcvialen 20 '
" MW. M M INSERVICE INSPECT 20H PROGRAM Page 29 of 102 9
# following Class 1 piping systems are subject to examination: '
6dactor Coolant Main Loop (RX) Other (RC)
+
Chemical and Volume Control (CVC) Residual llent Removal (RHR) Safety Injection (SI) Upper llead Injection (UHI) The Ull! System was removed from service during Unit 1 Cycle 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. 7.4.1 Piping _Elssimijnr_ Metal Helda There are no Class 1 dissimilar metal welds. 7.4.2 Elpino Pressure Retalning Bolting _ Larger Then 2 Inches. lu
; Diameter i
There is no piping pressure retaining bolting larger than 2 inches in diameter. i 7.4.3 Elp,ina Prengnre_Retmining_BD1 ting 2_Inchts_and__ Smaller in D1Amt. LEI ~ The following systems contain bolted piping flange connections. All 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 luspection interval in,acco-dance with Table A of ,
Attachment 4. -+ The bolting may be examined in place under tension or when the bolting is removed. 7.4.3.1 Beactor conlant System Ploing Baltina The Reactor Coolant System piping includes b Ited flange connections. 7.4.3.2 Chamical_and volume control Svttem Pipina Bolting The Chemical and Volume Control System (seal water injection) piping includes bolted flange connections. 7.4.3.3 ElllLSynem Piping Bolting The RHR System piping does not include any bolted connections.
.h 1328C/COC3
s!-114.1
. SURVE!LLANCE ASME SECTION XI Rsvision 20 INSTRUCTION 1HSERVICE INSPECTION PROGRAM Page 30 of 102 7.4.3.4 gafety injection Systnm Piping Bolting The Safety Injection System piping includes-bolted flange connections. ~
7.4.4 Circumferential and Longitudinal Ploina Wgida All Class 1 piping is seamless.- Circumferential pipe welds four inches and greater nominal pipe size selected for examination shall be ultrasonically .
- and liquid penetrant examined. Circumferential pipe welds less than 4-inch nominal pipe site selected' for examination shall bo liquid penetrant examined.
The examinations performed during thi inspection interval, shall include approximately 25 percent of the 40-year sample of circumferential welds. The examinations shall be
,,. distributed during the inspection interval in accordance with Table A of Attachment 4.
7.4.4.1 Reactor Coolant System Main Loon Piping; Circumferential Welds-
~
The Reactor Coolant System Main Loop piping.
, includes circumferential pipe welds 4 inches and greater nominal pipe size. The welds selected for
+
-examination shall be ultrasonically and liquid
~?
penetrant examined during the inspection interval in accordance with Table A of Attachment 4. 'There
, are no Class 1 pipe welds-less than 4-inch nominal pipe size in the Reactor Coolant System Hain Loop piping. Two circumferential welds in the Reactor-
; Coolant Main Loop pipingi RC-23S1 (Loop 3) and RC-31S1 (Loop 4) are located inside the reactor-
?'
vessel shield wall and are inaccessible for examination. See Request for Relief ISI-7. 7.4.4.2 Feactor Coolant System Pipino Circumferential Welds
. Reactor Coola'nt System piping includes circumferential.pi nominal pipe size.pe weldsll
~The inches welds and greater selected for .
examination shall be ultrasonically and 11guld-_ - penetrant examined during the inspection intervall in accordance with1 Table A of Attachment- 4. - Thero-are pipe welds less than 4-inch nominal pipe sise. The1 welds selected for examination;shall be 11guld penetrant examined during the inspection interval in accordance with-Table A of Attachment 4. 1328C/COC3:
SI-114.1
. SURVEILLANCE ASME SECTION XI R:visien 20' INSTRUCTION INSERVICE INSPECTION PRDORAM Pag 6 11 of 102 7.4.4.3 Chemical and Volume Control System Piping Circumferemtlal Welds The Chemical and Volume Control System piping (including seal water injection) includes circumferential welds less than 4-inch nominal pipe size. The welds selected for examination shall be liquid penetrant examined during the inspection interval in accordance with Table A of ,
Attachment 4. There are no Class 1 pipe welds 4 inches and greater in the CVCS system. 7.4.4.4 EHR System Pipjna circumferential Welda The RHR System piping includos circumferential - welds 4 inches and greater nominal-pipe size. The i
' volds selected for examination shall be ultrasonically and liquid penetrant examined during 3, ^
the inspection interval in accordance with Table A of Attachment 4. There are no Class 1 pipe welds less than 4-inch nominal pipe size in the RHR system. 7.4.4.5 Safety Injection S,ygtem Pinino Circumferential Welda The Safety Injoction 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 Table A of Attachment 4. There are pipe welds less than 4-inch nominal pipe size. The welds selected for examination shall be liquid
- penetrant examlued during the inspection interval in accordance with Table A of Attachment 4.
7.4.4.6 Reactor Vessel Auxillary Head Adapter Can Welds The graylock connectors were removed from service in Unit 1 Cycle 4 and replaced with. welded pipe caps. One of these four circumferential pipe cap welds (approximately 5.5 in.) shall be ultrasonically and 11guld 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 Piping C RDECilan E Welds The entire length of each branch pipe connection weld selected for examination shall be examined. Branch pipe connection welds exceeding 2 inches nominal pipe size selected for examination shall be ultrasonically. and liquid 4 1328C/COC3
S!.114.1 SURVEILLANCE .ASME SECTION XI R:visica 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 32 of 102 ' 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 velds. The examinations shall be distributed
- during the inspection interval in accordance with Table A of Attachment 4 EQII: In the case of branch pipe connections 2 inches '
nominal pipe size and smaller, the welds of all the systems affected have been combined and shall be evenly distributed over the four inspection ' intervals. 7.4.5.1 Reactor Conlant System Main Loon Branch Ploe CDanection Wglda The Reactor Coolant System Main Loop piping includen a branch pipe connection veld exceeding 2 inches nominal pipe size. This weld.shall be ultrasonically and liquid 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 11guld. # penetrant examined during the inep9ction interval in t,cordance with Table A of Attachment 4. - HQIE: 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 clernents with an outside diameter (OD) of 0.875 inch. The special boss has an OD = 2-1/2 inches i .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 concract 6BC60-91934, (N2M-2-8) drawing Nos. 206C470 and 206C471 and installation detail
- N2M-2-50.
7.4.5.2 Reactor Coolant System Branch Pine Coi.nection Weldg The Reactor Coolant System piping includes. branch pipe connection welds exceeding 2 inches nominal:- pipe size. The welds selected for. examination shall be ultrasonically and liquid penetrant examined during-the inspection interval in accordance with Table A of Attachment 4. There are branch pipe connection welds 2 inches nominal pipe size and smaller. The welds selected-for 1328C/COC3 .
H SI-114.1 SURVEILLANCE ASME SECTION XI R:visica 20 1HSTRUCTION INSERVICE INSPECTION PROGRAM Page 33 of 102 examination shall be liquid penetrant examined - during the inspection interval in accordance with Table A of Attachment 4. 7.4.5.3 Chmieni and Volume Control Eystem Branch Pine Connection Helds The Chemical and Volume Control System piping
" includes branch pipe connection welds exceeding 2 inches nominal pipe size. The welds selected for examination shall be ultrasonically and 11guld penetrant examined during the inspection interval
-in accordance with Table A of Attachment 4.
There is a branch pipe connection wold 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. 9 7.4.5.4 RHR System I B gnch Pine Connection Welds The RHR System piping includes branch pipe connection welds exceeding 2 inches nominal pipe size. The welds selected for examination shall be ultrasonically and 11guld penetrant examined during the inspection interval in accordance with Table A of Attachment 4. There are branch pipe connection welds 2 inches hominal pipe size and smaller in the RHR System. These welds are not scheduled for examination this interval. When these welds are selected for examination they shall be liquid penetrant examined. 7.4.5.5 Safety Injection System Branch Pipe Connection Heldt 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 11guid 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. 7.4.6 Pining f.2eket Welds The entire length of each socket weld selected for examination shall be liquid penetrant examined. 1328C/COC3
61-114.1 SURVEILLAllCE ASME SECTION XI Rsvisica 20 INSTRUCTION INSERVICE INSPECTION PLOGRAM Page 34 of 102 The examinations performed during the inspectior. 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 RfAC12f_C9AlanLJystem Piping _G2gket Helda The Reactor Coolant System piping includes socket velds. The velds 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 control Syjituttipina Gockti HaldA The Chemical and VoluAo Control System piping includes socket velds. The welds selected for examination shall be examined during the , inspection incerval in accordance with Table A of Attachment 4. 7.4.6.3 E}&_Eyjlem Pipino Sothet Heldt The RHR System piping includes socket volds. The welda selected for examination shall be examined during the inspection interval in accordance with .. Table A of Attachment 4. 7.4.%.4 Enfetv..Iniection System Piping _.Enchti_Waldt The Safety Injection System piping includes socket welds. The welds selacted for examination shall be examined during the inspection interval in accordance with Table A of Attachment 4. 7.4.7 piping _and Valye Intmorally Helded SuPEDI.1 MtlDhAIA Integrally welded support members include the support . attachments of piping raquired 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 suonort base material , desion thickng3s is 5/B inch and orantar. The. entire length of each support attachment weld selected for examination shall be surface examined. The examinations performed during the inspection interval. shall include 100 percent of the integrally welded support members. The examinations shall be distributed during the inspection interval in accordance with Table A of Attachment 4. 1328C/COC3- l
57-114.1 SURVE1LLANCE 'ASME SECTION XI R3 vision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Pcg3 35 of 102 't 7.4.7.1 Enactor coolant Evstem'Plolna and Valve Intacta11v ' : Welded Egyport Mem'bgIA . t The Reactor Coolant System piping Ancludes-integrally welded support members.. All of these y shall be examined during the inspection interval in accordance with Table A of-Attachment 4. 7.4.7.2 themical_and Volume control System Pipino and Valve f intearally welded succort Members The Chemical and Volume Control' System piping does not include any integrally welded support members. 7.4.7.3 RIIR System Pipina and Valve Intearally.Helded-Support Membang The RHR System piping includes integrally welded ! support members. All of these supports shall-be examined during the inspection interval in , accordance with Table A of Attachment 4.- 7.4.7.4 Safety Iniection System Ploina and Valve Intearally Welded Support MembgI3 The Safety Injection' System piping includes-integrally welded support members. All of these- , .shall be examined during the inspection interval _in accordar.ca with Table A of Attachment 4. - 7.4.8 Plolna and Valve component 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 includesLintegrally welded'and nonintegrally , '! welded component-supports. Component supports extend from the piping and. valves up to and: including-the attachment.to the supporting structure. The setting of snubbers, shock absorbers, Land = spring'-typel hangers shall be~ verified in accordanceLwith the/ applicable. NDE procedure with the-acceptance criteria-identified in the: Scan Plan (see PRISIM data base)'or the_ applicable work instruction. For -information, the acceptance ranges are- listed in ths . f 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.- 1328C/COC31 e
SI-114.1 SURVEILLANCE ASME SECTION XI R3visian 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Pcg3 36 cf 102 7 4.8.1 Reactor Coolant System Ploino and Valve Component Supports The Reactor Coolant System piping includes component supports. All of these shall be examined during the inspection interval in accordance with Table A of Attachcant 4. 7.4.8.2 Chemical hnd Volume Control System Pipino and Valve Component Supports The Chemical and Volume Control System piping includes component supports. All of these shall be examined during the inspection interval in accordance with Table A of Attachment 4. 7.4.8.3 RHR System Ploino and Valve Component Suonerts The RHR System piping includes component Aupportd. All of these shall be sramined during the inspection interval in accordance with Table A of Attachment 4. s.4.8.4 Safetv_Iniection Syjigm Ploinc and Va)ve CompoARDt Supoorts The Safety Injection System piping includes component supports. All of these shall be examined during the inspection interval in accordance with Table A of Attachment 6. 7.4.8.5 Reactor coolant System Main Looo Pipino and Valve Comoonent_S,upports The Reactor Coolant System Main Loop Piping includes component supports. -All of these shall be examined during the inspection interval in accordance with Table A of Attachment 4. 7.5 Reactor Coolant Pumps 141 - RCP 7.5.1 BCP Pressure Retalnino Boltino Larcer Than Twt Inches In Di amete r Tuo main flange on each pump includes 24 bolts of 4-1/2 inches in diameter and 30-1/2 inches in length. All the bolts from each pump shall be ultrasonically examined during the' inspection interval. Bolting may be examined either (a) in place under tension, (b) when the connection is disassembled, or (c) when the bolting is removed. Flange ligaments between threaded bolt holes shall be visually examined (VT-1) once during the inspection interval-if the connection is disassembled at any. tine during the inspection interval. 1328C/COC3 L
SI-114.1 SURVEILLANCE ASME SECTION XI R3 vision 20 INSTRUCTION INSERVICE INSPECTION PROGkAM Pcg3 37 of 102 If the bolts are removed at any time during the inspection interval, each bolt shall be magnetic particle (MT) examined ' and all threads in the base material shall be visually examined (VT-1) once during the inspection interval. This examination may be deferred until the end of the interval. The main flange bolts are fabricated of 4340 steel, heat , treated to A-540, GR. 24. Prov3sions for this examination are included in MI-2.2. 7.5.2 BCP PreAanri_Entaining_.Doltina 2 inches and_Jmaller in Diameter Each RCP includes two sets of pressure retaining bolting 2 inches and smaller An diameter. The bolting sets include the number 1 seal housing and cartridge seal assembly bolting. The Number 1 seal housing and cartridge seal assembly bolting includes 12 HEX head cap screws at 2 inches in diameter. The number 1 seal assembly bolting from 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. Drimer f rom 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 from one RCP shall be examined during the i first inspection period, and 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 chall'be examined during the third inspection period. 7.5.3 Ecr Integrally Walded Support Members There are no integrally welded support components associated with the RCP. 7.5.4 RCP Comppngnt Supporta E'ach RCP includes three-integrally cast pump feet bolted to the support system. All component supports from each pump shall be visually examined during the inspection interval in accordance with visual examination method VT-3. Support components extend from the RCP to and including the attachment to the supporting attucture. All of the supports from one RCP shs11 be examined during the first inspection period, and all of the supports from a different pump shall be examined during the second s 1328C/COC3
SI-114.1 i SURVEILLANCE ASME SECTION XI Rovision 20 t INSTRUCTION- 1HSERVICE INSPECTION PE9 GRAM P:gs 38 of 102 j . Inspection period. All of the supports from the remaining - [ two pumps shall be examined durlug the third inspection ' period. . t 7.$.$ RCP Casina Helds i Each Unit 1 RCP casing includes a 2-piece welded type 304SST -i casting. The. casing welds cannot be ultrasonically examined. 3 and achieve meaningful results due to limitations of examining integra1Ay cast material. The entire length of i one RCP casing weld shall be 11guld penetrant examined during the inspection interval.- This examination may be li; deferred to the thitd inspection period (see Request for
- Relief ISI-8). 'I i
7.$.6 BCP Casing a pump is disassembled for maintenance during tho' inspection interval, the internal pressure boundary surfaces-shall be visually examined in accordance with visual examination method VT-1. Disassembly of RCP's la performed in accordance with MI-2.2 and provides for these visual- , t examinations. i If during the inspection interval a pump from either Unit 1 or Unit 2 is not disassembled for maintenance, a pump from , one unit shall be examined from the exterior by ultrasonic j eg thickness measurements (see Request for Relief ISI-1)( d l 7.6 yalven A tabulation of valves is contalped in Attachment 2. 7.6.1 Valve Pressure Retainina Boltina Larger Than 2 Inches in Diameter 5 There are no valves with pressure' retaining-bolting larger. a than 2 inches in diameter. 7.6.2 Valve Pressure Retainina Boltina 2 Inches and Smaller in 4 Diameter . The following systems contain' valves with bolted bonnet ~ l connections. -All of the bolts or stude and nuts in-each ! connection not excluded in accordance with Code Case N-426 shall be visually examined duringlthe inspection-interval in- 1 accordance with visual examination method VT-1.- Thel
- 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-the bolting is-removed. lit is preferable to examine the-
- bolting when removed:1f possible. 1 Valve disassembly is -i performed in accordance with MI-6.15 and provides for ;
examination of bolting.. 1 1328C/COC31
.--s, + .a. ... m ,, ,_,,,,---,y c - - - - _ a ,g, . , , . , . . . , , % _.
S!-114.1 SURVE!!.f A Wet. ASME SECTION XI -Ravialca 20-IFCrRUCTION INSERVICE INSPECTION PROGRAM Pcg3 39 of 102 7.6.2.1 Reactor Coolant System Valve Bolting The Reactor Coolant System includes valves with bolted bonnet connections. All of these shall be + examined during the luspection interval in accorCance with Table A-of Attachment 4. 7.6.2.2 [htmical and Volume ContIp1 System Valve Bolting The Chemical and Volume Control System includes valves with bolted bonnot connections. All of these have been excluded from examination in accordance with Code Case H+426 during the inspection interval. 7.6.2.3 E.esidual Heat.Renoval (kIIR) Syntem Valve Dolting The RHR 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 Bafety Iniection Sygtem Valve Bolting The Safety Injection System includes valves with bolted bonnet connections. All of these shall be examined during the inspection interval in accordance with Table A of Attachment 4. 7.6.3 Valve Intt2ra11y Welded _Espport Memberg Examination of valve integrally welded support members is included in Section 7.4.7. 7.6.4 Valve Component Supporia Examination of valve component supports is included in Section 7.4.8. 7.6.5 Valve Body Welda There are no valves with body welds. 7.6.6 Valve Bodies The internal pressure boundary surfaces of valve bodies exceeding 4-inch nominal pipe size shall be visually . examined in accordance with visual examination method VT-1. Examinations are limited to one valve within each group of- 'l valves that are of the same'constructional design (i.e., globe, gate, or check valve), manufacturing method,-End that are performing similar functions in the system. 15;8C/COC3-l
SI-114.1 SURVEILLANCE ASME SECTION XI R3visica 20 ; INSTRUCTION INSERVICE INSPECTION PR3 GRAM Page 40 of 102 .l When it becomes necessary to disassemble any valve, subject ! to internal surface visual examination, for normal .j maintenance purposes, the interior surface of the valve body i will be visually esamined and the results recorded. j See Request for Rollef ISI-2. ! A tabulation of valves by groupings is presented in Table 1 of Attachment 1. Disassembly of valves is performed in l accordance with 0-MI MVV-000.008.0 and provides for examination of valve internal pressure boundary surf aces. Valve examinations are listed on Valve Interlor Examination Drawings in Attachment 1. 7.7 Exgspied_Camponents Components exempted frem examination include component connections, piping, and associated valves and their supports that are one inch nominal pipo 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.J(V); revised January 1, 1975) but exempted from Class 1 requiremtats by regulations of the regulatory authority having jurisdiction at the plant sites reactor. vessel head connections and associated piping, 2-inch nomical pipe size and smaller, made inaccessible by :ontrol rod drive penotrations. ' 7.8 Euannasive Examinatigag Areas of flaw indications evaluated in accordance with IRB-3122.4 and SSP-3.4 that qualify for continued service shall be reexarnined during the next three inspection periods listed in the inspection schedules. If the re-examinations 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 Pressure Testa All,ASME Code Class 1 (equivalent) system pressure tests shall be in accordance with SSP-8.5. 8.0 CQMPONENTS SUBJECT TO EYAMINATION - ASME CODE CMSS E KQUIVALENT) 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 accordance with paragraph IWC-2411 and Table IWC-2520 of the 1974 Edition, Summer 1975 Addenda, ASME Section XI-(examination categories C-F and C-G). Components that are exempted from examination in accordance~with IWC-1220 of ASME Section XI are discussed in Section 8.13 of this program. 1328C/COC3~ L_ _ _
51-114.1- , SURVEILLANCE ASME SECTION XI Rsvision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 41 of 102 t Where examinations specify a percentage of the total length of weld to be examined, the areas (s) examined shall be documented in the examination report. Where a percentage of weld length is not referenced, the entire weld length shall be examinad. f Table B in Attachment 4 supplies additional information such as reference : drawing nuinbers and ASME Section XI Table-IWC-2500-1 examination ' categories. 8.1 Eteam GengIAtors (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 welds from one steam generator-shall be ultrasonically examined during the inspection interval. The number of welds to be examined during each inspection period 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 D4s see Request for Relief ISI-4). The weld selected for . examinaL.ca shall be ultrasonically examined on a best-effort basis. , The vessel shell sections are fabricated 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. Tho , 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 Generator Secondary Side Tubesheet-To-Shell Wold Each steam generator includes a.tubesheet-to-shell weld. The entire length of one tubeshsst-to-shell weld shal; ,e ultrasonically examined during the inspection interval in accordance with Tahle B of Attachment 4. The weld selected for examination may be from the generator' selected for examination by Section 8.1.1 The tube plate is a SA-508, Class 2, steel forging. 1328C/COC3
SI-114.1 SURVEILLANCE ASME SECTION XI Rovision 20 i INSTRUCTION INSERVICE INSPECTION PROGRAM Page 42 of 102 8.1.4 gleam Generator Sacondary Side Nozzle-To-Vessei Welds and Norzle-To-Vessel Inside Radius Each steam generetor includes one feedwater nozzle (3.62 inches nominal wall thickness) and one main steam nossle (3.C2 inches nominal wall thickness). All of the nozzle-to-vessel welds from each generator shall be ultrasonically and magnetic perticle 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 lbspection interval. (References CAQR CHS 900013). . The nozzles are fabricated of SA-508, Class 2, steel. 8.1.5 Steam Centrator Secondary Side Integrally Welded Support Attachments There are no integrally welded vessel support attachments. 8.1.6 Steam Generator Seconogry. Side comoonent Supports There are no component supports (including mechanical and hydraulle supports) which are lu contact with the vessel. ' 8.1.7 Steam Generator Sgggndary Side Pressure Retainino Bolting Exceedino 2 Inches in Diameter There is no steam generator secondary side bolting exceeding 2 inches in diameter. ' 8.2 RHR Heat Exchangers (2) - RHRHX 8.2.1 RHRRX.Circumferential Welds 8.2.1.1 RHRHX Shg11 circumferential Weld There is one circumferential shell weld located at a gross structural discontinuity on each RHREX. The untire length of this shell weld from one heat exchanger shall be ultrasonically examined during each inspection interval in accordance with Table B of Attachment 4 (see Request for Relief ISI-16). ' The kHRHX shell-section is fabricated from SS, SA-182, F304.
- 8 2.1.2 RHRHY Head Circumferential Weld ThereLis one circumferentla'l head-to-shell weld per RHRHX. The entire length of one head-to- shell weld shall be ultrasinically examined during the inspection inter al in accordarce with Table B of Attachment 4. The weld selected for'sramination may be 'from the heat exchanger. selected for examination by section o.2.1.1.
1328C/COC3
~ . . . - .- . _
S!-114.1 SURVEILIANCE ASME SECTION XI R;;visicn 20 INSTRUCTION INSERVICE INSPECIION pR) GRAM Page 43 of 102 ; The channel cylinder suction (shall) and channel head are one inch thick fabricated from SS, SA-240, TP-304= 8.2.1.3 RHRnX Tubenhget to Shell_Etid i There are no BHRRX tubesheet-to-shell welds. 8.2.2 julR)DLIQIIJ e - t o -VJ2Ji 'til .HeldA dL9 channel cylinder section of each RHRHX includes one inlet not:1e (14-inch 24) and one ontiet nossle (14-inch ID) over 1/)4 inch nocir.nl thickness. A total of four nossle 'we+vossel meldC from the two RHRHX wl:1 be liquid " penetrant examfuwJ during the inspection interval. the nozzle-to-vessel welde and nomale inside radius secolons will not be ultrasonically examined during the inspection interval (see Requests for Rollst ISI-13). The nossles are 2.5 inches thich, fabricated from SS, SA-240, TP-304. 8.7.3 El[hH,! Intggtg11v Welded Suppati. Attachtqtati There are two integrally welded support attachments (1-inch) on each.RHREX yhose base material exceeds 1/2-inch nominal thickness. A total of two support pad-to-vessel welds from the RHRHX will be liquid penetrant examined during each inspection interval in accordance with Table B of Attachmont 4. The welds seiected for examination may be conducted on one heat exchanger and shall cover 100 percent of the required area of each suoport attachment. The support pad La fabricated from SS, SA-240 TP-304. 8.2.4 RHRHX Component Suppgita There are two component supports on each RHRHX which are in contact with the vessel. All component supports from each heat exchanger shall be visually examined during the inspection interval in accordance with visual examination method VT-3. This examination includes integrally welded and nonintegrally welded component supports.- Component supports extend frca Lhe heat exchanger to and including the attachment to the supporting structure. The examinations whall be distributed during the inspection interval 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. 1328C/COC3
_ _ - _ . - . _. . _.. _-_m ..~._ _ _ _ ___ - _ _ . ~ . _ _ . _ . . SI-114.1 i SURVEILLANCE- ,ASME SECTION XI R3 vision 20-INSTRUCTION INSERVICE INSPECTION PROGRAM Pcg3 44 of 102_ t 4
- 8. 2. 5 - R11RHX_ Pressure Retaldna Bolting Eggggdino 2 Inches in Diameigt '
i There'As no RHRitX bolting exceeding 2 inches In diameter. 8.3 Renenerative Heat Exchanggt i Section 8.3 has been deleted from this program in accordance with ! IWC-1220 (c) of ASME Section XI (see Request for Rollef ISI-12). .l I 8.4 gggggg, Letdown Hggt Exchanggi Section 8,4 has been deleted from this program Jn accordance with IWC-1220 (n) of ASME Section XI (are Request for Rollef ISI-12). ; 8.5 C.entri f ugal_CbAIsina_ Pump ( CCP) Tank /(Roron.. Injection Tank BIT) (one) NOTE: The CCP tank was formerly identitled as the BIT tank. This chango occurred in Unit 1 Cycle 4 refueling outage. As a " transition, both ids are being retained'for traceability. y 8.5.1 CCP Tank (BIT) clacumferentini Shell and Head Weldt ~f There are two circumferential head-to-shell welds located at ! structural discontinuities on the CCP Tank. These welds , shall be ultrasonically examined during the inspection , interval in accordance with Table B of-Attachment'4.. The: i examination shall cover 100 percent of the weld length.. The head and shell are SA-264 material consisting of SA-516, O GR70 steel backing outside wit.h 1/8 inch SA-240, TP304L cladding inside. . - 1 8.5.2 CCP Tank (BIT) Nostle-to-Vessel Nelds. k There are two nossles, 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 shallL be ultrasonically and surface examined during the inspection Interval in accordance with Table B of Attachment 4.' The ! examination shall cover-100 percontiof the-weld length. -{ The nossles are fabricated to SA-350s LF2. 8.5.3 CCP Tank (BIT)_Integra11v Weldes Supports There are.four integrally welded support attachment, pads = .
- velded to the.shell, whose basefmaterial design.-thickness'is
~
5/8 inch and therefore. requires surface examination in accordance with Table IWC-2500-1 of-ASKE Section XI.. > 8.5.4 CCP Tank(BIT) Component Supggg;g
' Mere are four component-supports associated with the-CCP 5 tank. All of.these supports shall.be visually. examined- t (VT-3) during the inspections interval in accordance with:
Table B of Attachment 4. 1328C/COC3 ~ w, .. . . .a-----.- __, .u .. . - . . - 4.,.-. w. . .._ u._ u. . _-
SI-114.1 SURVE1LhANCE ASME SECTION XI R: vision 20 INSTRUCTION INSERVICE INSPECTION Pn0 GRAM Page 45 of 102 8.5.5 CCP Tank (BIT) Pressuty Retainino Boltino Exceeding _ Igg c inches in Diameter ' There are 16 manway cover stude 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.
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8.6 UHI Water ACCDmulALRI 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 USI Surge Tank Section 8.7 has been deleted from this program in accordance with IWC-1220 (a) of ASME Section XI. This component has also been ' removed from service. 8.8 Seal Water In_Itetion F11 Liga Section 8.8 has been deleted from this program in accordance with . IWC-1220 (c) of ASHE Section XI (see Request for Relief ISI-12).
- 8.9 Elping Material specifications for each piping system are stated on the weld map isometrica. 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) - The UHI system was removed from service during Unit 1 Cycle 4. For reference to the schedulo.of examinations performed on this system, see Revision 14 of this instruction. 8.9.1 Piping and Valve Integrally Welded Support Members Integrally welded support members include the support attachments of piping required to be examined by Examination Category C-F. Included are those supports which have attachment welds to the valve and piping pressure retaining l boundary, and those attachments whose. support base material I deslan thickness exceeds 3/4 inch (see PRISIM data base). j The entire length of each support attachment weld selected for examination shall be surfacs examined. 1328C/COC3
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SI-114.1-SURVEILtANCE ASHE SECTION XI R visica 20 INSTRUCTION INSERVICE INSPECTION PROGRAM page 46 of 102 The examinations performed during the inspection interval shall include 100 percent of the integrally welded support members. The examinations shall be distributed during the inspection interval in accordance with Table B of Attachment 4 (see Request fot Rollef 181-17). 8.9.1.1 Rgsidual Heat Removal iRHR) SyJiem. pipino and YAly1 Integrally Welded Support Memhgra The RHR System piping does not include nr.y integrally welded support members. 8.9.1.2 Enfaty_Iniection System Pining and Valve Integrally Eg1ded Support Memberg The Safety Injection System piping includes integrally welded support members. All of these shall be examined during the inspection interval in accordance with Table d of Attachment 4. 8.9.1.3 Main Steam System Piping and Valve Inteorally Welded Sypport MembgIn The Main Steam System piping includes integrally welded support members. All of these shall be examined during the luspection interval in accordance with Table B of Attachment 4. 8.9.1.4 Feedwater System Pinip2_gna Valve Inteorally Welded Support Members The Feedwatwr System piping includes'ip*7grally welded support members. All of these shall be examined during the inspection interval in accordance with Table B of Attachment 4. 8.9.1.5 Containment Sorav System Pipino and Valve-Integrally Welded Suncort Memkggg The Containment Spray System piping does not include any integrally welded support members.- 8.9.2 P.1p1Do and Valve Comnonent SuppgIts 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 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 132BC/COC3
SI-114.1 SURVEILLANCE ASME SECTION XI R3visics 20 2NSTRUCTION INSERVICE INSPECTION PROGRAM Pega 47 cf 102 instruction. For information the acceptance ranges are listed in the component supports 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 Eg31 dual ligat Removal ( P.itR ) System Pipino and Valve CQErnatnt Supports The RNR System piping includes component supports. All of these shall be examined during the inspection interval in accordance with Table B of L Attachment 4. 8.9.2.2 Hafety Iniection Systgm Pipjag_and_Yalve C2mnonent ERDP91tt The Safety injection System piping includes component supports. A13 of th2se shall be examined during the inspection interval in accordance with Table B of Attachment 4. 8.9.2.3 Main Steam System Pipino and Valve ComDannnt Sunports The Hain Steam System piping includes component supports. All of these shall be examined during the inspection interval in accordance with Table B of Attachment 4. 8.9.2.4 EntAwater System Pipiro and Valve Component SuPPorta The Tendwater System piping includes component, supports. All of these shall be examined during the inspection interval in accordance with Table B of Attachment 4. ' 8.9.2.5 Cnntainment Soray System Pipino and valve'Comnonent Eupports 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 Pressure-Retainino Boltino There is no Class.2 Pressure-Retaining Bolting larger than two inches in diameter. 1328C/COC3
51-114.1 SURVEILLANCE ASME SECTION XI R3visicn 20 INSTRUCTION INSERVICE INSPECTION PR3 GRAM Page 48 of 102 , 8.9.4 Circumf eIant1& Land Lonaltudinel Pipit.Hels13 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 1 accordance with Table B of Attachment 4.
- Tne entire length of each weld selected for examination shall be ultrasonically and/or surfaced examined. ;
Circumferential and longitudinal piping welds in piping with , a nominal wall thickness of 1/2 inch or less shall be surface examined. Circumferential and longitudinal piping welds in piping with a nominal wall thickness greater than 1/2 inch shall be ultrasonically and surfaced examined. The areas subject to examination include circumferential pipe welds at structural discontinuities, within 3 pipe diameters of the centerline of rigid pipe anchors, anchors at the penetration of primary containment or at rigidly anchored components, and longitudinal weld joints in pipe fittings. o 8.9.4.1 Residual Heat Removal (RHR) Pinino The RHR Piping System. includes Class 2 circumferential and longitudinal piping welds with a nominal wall thickness greater than 1/2 inch subject to examinatiou. The welds selected for examination shall be ultrasonically and surfaced examined each inspection interval in accordance with Table B of Attachment 4. The RHR piping system includes the circumferential and longitudinal pipe welds with a nominal wall thickness of 1/2 inch or less. The welds selected for examination shall be surface examined each inspection interval in accordance with Table B of Attachment 4. , 8.9.4.2 Safety Injection' Pining 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 circumferential and longitudinal pipe-welds with a nominal wall thickness of 1/2 inch or , less. The welds selected for examination shall be surfaced examined each inspection interval in
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accordance with Table B of Attachment 4 132BC/C0C3
SI-114.1 SURVE!LLANCE ASME SECTION XI R3vicien 20 , INSTRUCTION INSERVICE INSPECTION PROGRAM Page (9 of 101 8.9.4.3 Main Steam Piping The Main Steam Piping System includes Class 2 circumferential and longitudinal piping welds with a nominal wall thickness greater than 1/2 inch subject to examination. The circumferential and longitudinal piping welds 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 velds with a nominal wall thickness of 1/2 inch or less in the Main Steam System. 8.9.4.4 Teedwater Plnino The Feedwater Piping System includes Class 2 circumferential and longitudinal piping welds with-a nominal wall thickness greater than 1/2 inch subject to examination. The circumferential and longitudinal piping welds selected for examination ' shall be ultrasonically and surfaced examined each inspection interval in accordance with Table B of Attachment 4. The one longitudinal wold is on Loop 4 at the reducing elbow (18 by 16 inch). The feedwater piping system includes circumferential t pipe welds with a nominal vall thickness of 1/2 inch or less. The circumferential weld scheduled for the 40-yaar sample has not been scheduled for examination this interval. There are no longitudinal pipe walds with-a nominal vall' thickness of 1/2 inch or less in the feedwater-system. 8.9.4.5 ComtA.ntnCAt 4 Sorav Piping The Containment Spray-Piping System includes Class 2 circumferential and longitudinal piping welds with a nominal wall thickness of 1/2 inch or' less, subject to examination. The 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 a nominal wall g' thickness greater than 1/2 inch in the Centainment Spray System. 8.9.5 Branch Pipino Connection Welds i There are no Class 2 branch pipe connection welds. ! l
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l E SI-114.1 SURVEILLANCE ASME SECTION XI Rovision 20 INSTRUCTION INSERVICE INSPECTION PR3 GRAM Page 50 of 102 8.10 Eump.1 8.10.1 EHR Pumps (2) - RHRP , 8.10.1.1 RHRP Intigt.gilyllelded Supporig There are no integrally welded supports associated with the RHRP. i i 8.10.1.2 EHER_Eupport components 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 ,o and including the attachment to the supp<rting structure.
.T Both of the RHRP support components shall be examined during the inspection interval. .
A 8.10.1.3 BHRP Supports - Mtchanical or Hydraulic There are no toechanical or hydraulic supports associated with the RHRP. 8.10.1.4 EHBP Pressure Retainino Bolting 1 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. 8.10.1.5 EHRE_Casina welds \1 The RHRP does not include anyfcasing welds. The casing is a one piecs. forging fabricated to SA-182 F304, b 8.10.2 CVCS Centrifugal charoina Pumps (2) ccf 4 CM Examination of_those pumps, and their associated component - supports, pressure retaining bolting, and casing welds are exempted under previsions outlined in table IWC-2500-11and
- 3. . accompanying footnotes, Examination Categories C-C, C-G, which limit the eram requirements to components-in piping ;
examined under Examination Category C-F. '
.1328C/COC3
SI-114.1 SURVEILLANCE ASME SECTION XI POvisics 20 INSTRUCTION INSERVICE INSPECTION PROGRAM P g) 51 cf 102 8.10.3 CVCS Positive Displacement Pump (1).PDP/ReciproEA11D9 ChkC9ADG EMBB Examination of these pumps, an$ their associated component supports, pressure retaining bolting, and casing welds are exempted under previsions outlined in table IWC-2$0P-1 and accompanying footnotes, examination categories C-C, C-G, which limit the exam requirements to components in piping examined under enamination category C-F. 8.10.4 Safety Injectinn Punos (2) SIP Examination of these pumps, and their associated component supports, pressure retaining bolting, and casing velds are exempted under previsions outlined in table IhC-2500-1 and accompanying footnotes, examination categories C-C, C-0, _ which limit the euam seguirements to components in piping examined under examination category C-F. 8.11 Ealyga Systems including ASKE Code Class 2 valves subject to examination are identified in Section 8.9. A tabulatics of valves is presented in Attachment 2, Table 3. 8.11.1 yalve Integrally Welded Suppgrag Examination of velve integrally velded support members is included in Section 8.9.1. 8.11.2 Valve camponent Supporta Examination of valve component supports is included in Section 8.9.2. 8.11.3 Valve _Eressure-Retalning Bolting There is no Class 2 pressure-retaining bolting greater than 2 inches in diameter. 8.11.4 Valve Body Welds There are no Class 2 valves with body welds. 8.12 System Pressure Test All ASME Code Class 2 (equivalent) system pressure testa shall be in accordance with SS'-8.5. 8.13 Exempted Componenta 8.13.1 Exempted Components (Except Ploine Welds) Components exempted from examiaation includes (a) components of systems or portions of systems that during normal plant operating conditions are not required 132BC/COC3 J<
SI-114.1 SURVEILLANCE ASME SECTION XI R visica 20
' INSTRUCTION INSERVICE INSPECTION PROGRAM Page 52 of 102 l to operate or perform a system function but remain flooded under static conditions at a pressure of at least 60 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 Cor6 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
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(including nozzles in vessels and pumps), piping and associated valves and vessels (and their supports) that are 4 inch nominal pipe size-and smaller. 8.13.2 Eggepted Components (Pipino Helds 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 Examinat.iDAR 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-
- g. Inspection schedule. If the reexamination revenis-that the flaw indications remain essentially unchanged the component examination schedule may revert *o 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. ' 9.0 CQMEQ}{ENTS SUBJECT TO EXAMINWilDN - ASME COD,RJ{, ASS 3 - (EOUIVALENT) ASME Code Class 3 (equivalent) component supports and restraints within the boundaries identified in Sections 9.1 and 9.2 forl components exceeding 4-inch nominal pipe wise shall'be visually examined, VT-3, during each inspection period.- Mechanical and hydraulic anubbers, -spring loaded and constant weight supports within the boundaries identified in section 9.1 for components exceeding 4-inch nominal pipe size shall be visually examined, VT-4 during each inspection period. 9.1 Pipino and valve component Suncorts 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 examinttjon includes integrally wolded and nonintegrally welded component supports. Component supports extend from the piping and valves to and including the attachment
*o the supporting structure. The setting of snubbers, shock absorbers and spring-type hangers shall be verified in accordan'ce 1328C/COC3 is Dl -
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SI-114.1-SURVEILLANCE ASME SECTION XI Rsvision 20 , INSTRUCTION INSERVICE INSPECTION PROGRAM 'Page 53 of'102 with the applicable NDE procedure with the acceptance criteria shown in the Scan Plan (see PRISIM data base) or the applicable ' work-instruction. For information 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.
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9.1.1 Auxillery Feedwater System Piping and Valve Component
!blEpAI11 The Auxiliary Feedwater System piping includes component '
supports. All of these shall be examlued during each inspection period in accordance with Table C of Attachment 4. 9.1.2 Chemical and Volume control System Ploino and Valve Component Supports The Chemical and Volume Control 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 now class boundaries.) 9.1.3 Component Coolino System Ploinc and Valve Comoonent Sup.gqIls. The Component Cooling System piping-includes component supports. All of these shall' be examined during each inspection period in accordanca with Table C of Attachment 4. 9.1.4 Containment Soray System Ploing and Valve Component Supports 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 System Pipino and Valve Component Suonorts The Essential Raw Cooling Water System piping includes component supports. All of these shall be examined during-each inspection period in accordance with Table C of Attachment 4 I 9.1.6 Fuel Pool Coolina System Ploina and Valve Comoonent SuoDorts I The Fuel Pool Cooling System piping includes component-supports. All of these shall be examined during each inspection period in accordancs with Table C of I Attachment 4. u
- l 1328C/COC3 l
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-SI-114.1 SURVEILLANCE ASME SECTION XI R0visicn 20 INSTRUCTION INSERVICE INSPECTION. PROGRAM Page 54 of 102 k
i-9.1.7 ElIR SvAtem Piping and Valve Component Supports 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 Injectinn System Elpina and Valve comoonent Suonorts The Cafety 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 Equipment Component Supports ; The equipment component support and the associated integrally wolded support attachment will be (VT-3) examined together. 9.2.1 C9ntainment Sorav Heat Exchanger (2) Support - CSH (ERCW) There is ons component support on each CSH. These supports: shall be (VT-3) examined during the inspection interval in accordance with Table C of Attachment 4. 9.2.2 Nonrocenerative Letdown Egat Exchanger (1) Support - NHLHX - (CCS) There is one component support on the NRLHX. This support shall be (VT-3) examined during the inspection interval in- .i accordance with Table C of Attachment '4. 9.2.3 Gas Stripoer and Boric Acid Evaoorator (1) - GSBAE (CCS)- 9.2.3.1 GSBAE Eganorator' Condenser (1) Support - EC There are two component supports on the EC. These supports shall be (VT-3) examined during the inspection. interval in accordance with Table C of Attachment 4. 9.2.3.2 GSBAE Distillate Cooler (1) Suncert - DC (CCS)
'There are two component supports on the DC.
These supports-shall be (VT-3) examined during-the inspection interval in accordance with Table C of Attachment 4. 9.2.3.3 GSBAE vent Cooler (1) Supoort - VC (CCS)- There are two component supports on the VC. These supports shall be (VT-3) examined during the inspection interval in accordance with Table C of Attachment 4. _ 1328C/COC3
SI-114.1 SURVEILLANCE ASME-SECTION XI . . Rsvisica 20 INSTRUCTION INSERVICE INSPECTION pR) GRAM Page 55 of 102-9.2.3.4 GSBAE Suoport Frame 'll Suonort - SF (CCS) The SF consists of ose component support. This-support shall be (VT-3) examined during the inspection interval.in accordance with Table C of Attachment 4 9.2.4 Component Coolina Surge Tank (1) Supoort - CCST (CCEl. There is one component support on the CCST. This support-shall be (VT-3) examined during the inspection interval in accordance with Table C of Attachment 4. 9.2.5 Component Coolino System Positive Displacement Charcing-Pump _Dil cooler (1) Suonort - 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 4. 9.2.6 Component Coolina Water Gross Failed Fuel Detector (1) Support - GFFD (CCS) There is one component' support on the GFFD. This support shall be (VT-3) examined during the inspection interval in - accordance with Table C of Attachment 4. 9.2.7 Centrifuoal Charcina Pumo Gear 011 Cooler (2) Sucoort - CCPGOC (ERCW) There are two component supports on each CCPGOC. These supports shall be (VT-3) examined during the inspection interval in accordance with Teble C of Attachment 4.- - 9.2.8 Centrifuaal Charaino Pumo 011 Cooler (2) Suonort - CCPOC (ERCW) There are two component supports on each CCPOC. These supports shall be (VT-3) examined during the. inspection; interval in accordance with Table C of Attachment 4. 9.2.9 Waste Gas comoressor Heat Exchancer (1) Suonort - WGCHX (CCS) There are two component supports on the WGCHX. These supports shall be (VT-3) examined during the inspection interval in accordance with Table C of Attachment 4. 9.2.10 Centrifuaal Charaina Pump Mechanical Seal Cooler (4) Eupp.g,rt - CCPMSC (CCS) There.is one component support on each CCPMSC. These supports shall be (VT-3) examined cering the inspection interval in accordance with Table C of Attachment 4. I 1328C/COC3 1
'SI-114;1! \
SURVEILLANCE ~ ~ASME SECTION XI/ Revision 201- ! INSTRUCTION. INSERVICE' INSPECTION PROGRAM- Page 56 of_102'
'1 4
9.2.11- RHR Pumo Sg d Cooler-(2) Suonort - RHRSC~(CCS)
.There Asione component' support.on'ench'RHRSC. These
- supports 'shall be (VT-3)- examined during the inspection -
interval-in-accordance with Table C_of; Attachment _4.
- l. (
9.2.12 Safety Iniection Pumo 011 Cooler (2) Support. - SIPOC'(BRCW) There are two component supports on each SIPOC.; These 1 supports _ shall be (VT-3) _ examined during the -inspection : interval-in accordance with Table C of Attachment 4. 9.2.13 Enfety Iniection Pumo seal cooler'(4) Suonort-SIPSC (ERCW) t There is one component support on each SIPSC.- These supports shall be (VT-3)-examined during the inspection interval in accordance with . Table C of Attachment 4. { 9.2.14 Component Coolina System Seal Water Heat Exchancer (11-Support - SWHX (CCS) There is one component support on the SWHX. L This support shall be (VT-3) examined during the inspection interval in? accordance with Table C of' Attachment 4. - t 9.2.15 Component Coolina System Thernal'Earrier Booster'Pumo (2) Support - TBBP (CCS) There are two component. supports on each TBBP. These supports shall be (VT-3) examined during the inspection 1 interval in-accordance with Table C of Attachment 4. 9.2.16 Turbine Driven Auxiliary Feedwater Pumo-(11 Suonort - TDAFP (AFW) There are two1 component supports on the TDAFP.-;These supports shall-be-(VT-3)-examined during:the inspection. , interval in accordance with Table C of Attachment;4. . 9.2.17 Motor Driven' Aux 111arv Feedwater Pumo (2)'Suocort - MDAFP (AFW)' There are two component'suppo'rts on each MDAFP. These-supports shall be_(VT-3) examined;during the Inopection' interval- in accordance with Table C of Attachment 4. - , 9.2.18 Component'Coolina System Water Pumos (3) Supeort - C.CSWP- (CCS ) 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. ~ 1328C/COC3 ,
SI-114.1 SURVEILLANCE' ASME SECTION XI Rsvisica 20 INSTRUCTION, INSERVICE-INSPECTION P34 GRAM Paga 57 cf-102 9.2.19 Component Cooling Heat Exchang3r (4) Support - CCHX (CCEI There is one component support on each CCKX. These supports shall be (VT-3) examited during the inspection-Interval in accordance with Table C of Attachment 4. 9.2.20 Essential Raw Coo 11no Water System Strajner Support (2) Sunoort - ERCWS (ERCW) There is one component support on each ERCHS. These supports shall be (VT-3) examined during the inspection interval in accordance with Table C of Attachment 4. 9.2.21 Essential Raw Coolina Water System Pumo Station Pumo IB)' Succort - ERCMP (ERCW) There is one component support on each ERCWP. These supports shall be (VT-3) examined during the inspection interval in accordance with Table C of Attachment 4. 9.2.22 Fuel Pool Coolino And Cleaning System - Spent Fuel Pit Pumps (3) Support - SFPP (FPC) There is one component support on each SFPP. These supports shall be (VT-3) examined during the inspection interval in'accordance with Table C of Attachment 4.- 9.2.23 Fuel Pool Coolino And Cleanino System - Spent Fuel Pit Heat Exchancer (2) Suonort - SFPHX (FPC) There are two component supports on each SFPHX. These supports shall be (VT-3) examined during the inspection interval in accordance with Table C of Attachment 4. 9.2.24 RHR Heat Exchancer Secondary Side (2) Supports - RHRHSXH (CCS) There are two component supports on each RHRHSHX. These supports shall be (VT-3) examined during the inspection interval in accordance with Table C of Attachment 4. 9.2.25 ERCW Screen Wash Pumo (4) Support - ERCWSWPH (ERCW) There is one component support on each ERCWSNPH. These supports shall be (VT-3) examined during the inspection-interval in accordance with Table C of Attachment 4. 9.3 System Pressure Tests
- All ASME Code Class 3 (equ1v'alent) system pressure tests shall be in accordance with SSP-8.5.
I 1328C/COC3
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SI-114.1^- , SURVEILLANCE' -ASME SECTION XI LR; vision 20: INSTRUCTION INSERVICE INHPECTION PROGRAM. Peg 3L58Ecf 1023
+e 10.0 AUTHORIZED INSPECIQE
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e
'TVA shall emplop an Authorized. Inspection Agencyjiniaccordance withLASME-Section XI for inservice examinations, repairs, and replacements'of ASME-Code Class:1,t2 and 3 { equivalent)= components-at SON.1 The Authorized Inspector (s)'shall-verify, assure, or witness _that code requirementsj l have been met. He'shall-have the prerogativejandl authorization to. +
require requalification of any operator or-procedure when_he has; reason 1 to believe the requirements are not being met. TVA shall provide access for the Authorized Inspector (s) in accordance with IHA-2140 of ASME Section XI. TVA's interface with the Authorized Inspector for ISI, Repairs and j Replacements ls defined in STD-6.10 and SSP-6.9. ' 11.0 EXAMINATION METIIODS AND CALIBRATION BLQCES i i 11.1 Examination Methods NDE examinations shall be performed in accordance with-this.
.4-program as scheduled'in Attachment 4, the applicable-Scan Plani QMP-102.4,'and OMP-110.5. Requirements for NDE methods shall be o+
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 code exam. coverage _cannot.be achieved, the-fact'shall be-documented on the data sheet and a bsst-effort examination shall 4 be performed. ASME Section XI Programalshall be informed in-writing of the limited exam.
, Data must'be provided on the exam sheet to determine the percentage of code exam' coverage achieved.
11.2 CALIBRATION BLOCKS Calibration blocks will'be used for ultrasonic-examinations.(a-calibration tube will_be used for eddy-current examination of. a steam generator tubing).- The _ blocks lwill- be f abricated~ to the general requirements of ASME Section V.and ASME Section XI.'LThe
. blocks shall be fabricated-of'the-materia 1Lto be examined or:
equivalent P numbers. Mill _ test repcrts:shall-be obtained and= retained by NOA for all calibration blocks. The blocks shall employ drilled holes _and/or notchesiforicali.bration: 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 SQO personnel.-
-12.0 OUALIFICATIONS OF NDE PERSONNEL U
-i Personnel. performing NDE operations shall1b1 qualified in accordance with IWA-1600,=IHA-2300, and Table IWA-1600-1 of ASME Section XI11986- .
l Editio3 as required in_QMP'102.4.
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^ vl d 1328C/COC37 I [
SI-114.1 SURVEILLANCE ASPE SECTION XI- Rsvisien 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 59 of 102-13.0 ACCEPTANCE CRITERIA All acceptance standards for ASME Code Class 1, 2 and 3'(equivalent) components shall be in accordance with IWA-1000, IND-3000, IWC-3000, or IND-3000 of'ASME Section XI, except where ASME Section III: examinations ,, are employed to satisfy ASME Section XI requirements. 14.0 REPAIRS AND REPLACEMQ{IS All ASME Section XI components and their supports, ASME Classes 1,-2,. and 3 (equivalent) shall be repaired and replaced in accordance with the Repair and Replacement Program implemented by SSP-6.9. ASME 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 REPORTS 16.1 Repair and Replacement Reports Repair and Replacement Form NIS-2 reports shall be prepared in accordance with SSP-6.9. 16.2 Report for ISI of Class 1 and 2 Components S00 shall. prepare an ISI Report for Class 1 and 2 components to be submitted within 90 days af ter 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. Name and address generating plant.
4. Name or number assigned to the nuclear power unit by TVA. S. 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, capacity, material, location, and drawings to aid identification.
1328C/COC3 n
SI-114.1 SURVEILLANCES ASNE-SECTION XI Rsvision 20 INSTRUCTION INSERVICE' INSPECTION PROGRAM Page 60 of 102
- 4. Name and address of principal ~ manufacturer (e.g.,
Westinghouse, GE, etc.)-and the principal contract number which will identify the subcontractors. _ Manufacturer's component identification numbers.
- 5. Date of completion of the examination.
- 6. Name of ANII who witnessed or otherwise verified the examinations and his employer and business address, when required. '
- 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 NIS-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 discussed in - Section 16.3. SQO shall submit applicable summaries of the report with a cover sheet as described above to the NRC via SQN Site Licensing. 16.3 Eite Final Report A detailed report of all examinations shall be prepared by S00 (and/or the performing or responsibla organization) and should contain, but not be limited to, the following information Cover Sheet - Data Sheet 1 in AppendiT B will be completed and us4d 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: Plant, unit number, PSI _or ISI-and cycle number, systems, components and vessels examinations were performed on, organization examinations were performed by, dates examinations were performed, ASME Section ZI Code-of Record. II. Summary - The summary should' include a brief description of the overall inspection. III. Summary of Notifications - The summary of notifications shall'give a short summary of each notification report along with the indication discrepancy and_its location. It-should also contain the final lisposition including a - reference to the corrective accion taken and the'date of, completion.
'1328C/COC3
SI-114.1. SURVEILLANCE' 'ASME SECTION XI R3visien 20 INSTRUCTION- INSERVICE INSPECTION. PROGRAM Page 61 of 102 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, Weld Size, Reference Drawing, Examination _ Method, Procedure, Calibration 14ock, date of examination and-result of examination. V. Summary of-Personnel Certifications VI. Calibration Sheets VII. Examination 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 organization. _ When portions of the insyvstion work are contracted, a detailed report will be submitted to TVA by the contractor-with all pertinent and required information. TVA will retain the original copies of all raw data taken.- S00 shall review and submit the Site Final Report in accordance-with SSP 8.2,_" Surveillance Test Program," for retention as a quality assurance record in accordance with SSP-2.9, " Records Management." 16.4 Records for ASME Code Class 1, 2 and 3 (Eaulvalentl 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 The following drawings are retained as QA records: c
- 1. ASME Section XI Boundary Classification Drawings:
- 2. ASME Section XI ISI Drawings 16.5 Records of System Pressure Tests Records of the visual examinations conducted during system-leakage' or hydrostatic tests shall consist of an itemizatice of the number and location of leaks found in a system and.the corrective actions taken.
1328C/COC3 l
l SII114.li SURVEILLANCEf ASME SECTION-XI- Rsvision 20 INSTRUCTION __ INSERVICE INSPECTION PROGRAM Page 62 of'102-16.6 Augmented Examination Reports For specific details _~on records, reports.and reporting see Section 20.0, Augmented' Inspections.. 16.7 Etatus of Completed Examinations 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 NOTIFICATION OF INDICATION 17.1 The Notification of Indication (NOI) form in Appendix C of this program is to be used tot (1) notify plant management of an indication found during the performance _of scheduled ISI examinations that will require evaluation and a disposition in accorcance with plant procedures, (2) notify ASME Section XI Programs that an indication-that exceeds the acceptance criteria of-Article 3000 of the ASME Section XI Code has been documented on. an examination report form contained within the NDE procedure usedl , for examination, (3) provide ISO and SQO with a method to track examination reports.that require reexamination or a documented-disposition for_ closure, and (4) as~a final product, with the disposition provided under plant procedures added to Part II of g the form, provide ASME Section XI Programs a method of determining
-if additional Code examinations are required.
17.2 Functionally an NOI Form shall be initiated and. processed as ! follows. 17.2.1 Part l'of an NOI Form willobe initiated by the NDE Examiner when an indication--exceeds the' acceptance criteria of the NDE Procedure being.used to perform _a-scheduled ISI examination. The Examiner will-sign'and. date the NOI Form. The Field Supervisor, in the case of-contracted examinations, will review the information in Part I and sign and date the NOI Form as approving-the information. The SQO Representative will review for-accuracy, sign and date the NOI' Form. 17.2.2 After completion of Part=I,'SQO shall send the original NOI Form and a copy of the Examination Report to Site-
~
Engineering as a notification to plant management that an indication requiring. evaluation bas'been found.. A prompt
-determination of any impact on operability must_be made in accordance with plant procedures. S00 shall'also send a-copy to ASME_Section XI Programs as notification that a _.
potential exists for additionti examinations to be performed per ASNZ.Section XI. 1328C/COC3
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SI-114.1 SURVEILLANCE .ASME SECTION XI R vision 20 INSTRUCTION INS)MVICE INSPECTION PROGRAM- Page 63 of;102 17.2.3 Site Engineering shall be responsible for evaluating and providing a disposition for the indication inTaccordance 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 NOI Form and return the original to the SQO Representative for closure. Reference to any PERs, FIRS, SCARS, WR/HOs, etc., shall be included. 17.2.5 The SQO Representative shall immediately, upon receipt, provide a copy of the NOI Form bearing the recorded disposition to ASME Section XI Programs for determination of additional examination requirements. 17.2.6 Upon notification from ASME Section XI Programs, the SQO Representative shall check "yes" or "no" for additional examinations, and he shall close the NOI Yotm in Part III by reexamination, in the case where work was performed as a part of the disposition, or by verification of the disposition if no physical work was required to remove or ! modify the indication. 17.2.7 The original NOI Form shall be filed with the original
, examination report. A copy of the form shall be sent to ASME Section XI Programs for closure of their flies. 'The reexamination report, if applicable, shal1~ reference the NOI number. The NOI Form and original examination report .) '
shall reference the reexamination report number. 17.3 Additional Samole ~ Selection for ASME_ Code Class 1 and 2 NOIg After a NOI has been dispositioned'and returned to the SQO Representative, a copy shall be forwarded to ASME Section XI-Programs for evaluation to determine if additional examinations - shall be required. If it is determined that additional examinations are-required, these examinations shall be performed during the same outage as the initial examinations. A sample is ; defined as those items.(welds, areas, or parts)-as described or. ! intended in a particular examination category and item number and- l within the same system. For. component support-samples, the ; additional examinations may also be llmited to component supports H within the same examination method (VT-3, and VT-4). The initial- 1 sample is the sample scheduled for examination at a particular outage for Section XI credit. For steam generator tubing, ' additional samples shall be per Section 7.3.8. 17.3.1 Evaluat12R_for First Additional Samole A first additional sample shall be selected fcr those-1 examinations performed in the initial sample that reveal ' indications exceeding the corresponding acceptance standards of IWX-3000 of ASME Section XI. The first 1328C/COC3
-SI-114.1-SURVEILLANCE- ASME'SECTION XI- R3visien.20 INSTRUCTION INSERVICE INSPECTION l PROGRAM Page-64-of-102 additional sample shall include approximately_the same number of items examined in the_ initial sample. The first additional sample shall be selected from~ the ten year interval sample. The items selected should be from those-items that have the longest service time from its previous inservice examination.
If a system contains a sample within the same_ examination category and item number as the initial sample which had the indication and is not scheduled for examination ~this outage, this system sample shall be evaluated to determine if it should be examined this outage to provide a representative sample from each system within a'particular examination category and item number. This evaluation ' should consider, but is not limited to, the type of~ indication found in the initial sample and-similar system design and operating parameters. The ASME Section XI Programs Representative shall submit the additional sample to the SQO Representative f or addition to the scan plan. 17.3.2 Evaluation for Second Additional samole 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 IWX-3000 of ASME Section XI. The second additional sample shall include all the. remaining items of the ten-year interval sample not' examined in the initial or first_ additional sample during this outage. If no items remain in the ten-year interval sample (e.g., Accelersted Field Weld Program) and indications were found-in the first additional sample, 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 submitLthe second additional sample to the SQO Representative for addition to the scan plan. 17.3.3 Notification of- Samole Results to Site Engineering - After completion of the second additional. sample examinations, ASME Section XI code requirements:for additional examinations ar6 complete. If examinations; ' performed in the'second additional sample reveal indications exceeding the corresponding acceptance ctandards of INX-3000 of ASME Section XI, Site Engineering chall be notified. Site Engineering shall be notified to evaluate the indicatious 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 _An the notification should be a summary 1328C/COC3: i?
SI-114.1 SURVEILLANCE ASME SECTION XI Rsvision 20-INSTRUCTION INSERVICE INSPECTION PROGRAM Pega 65 of 102 of the indications found, number of examinations and number of indicacions in each sample, type of examination performed, examination-category and item number, copies of the NOIs, and any other pertinent information. 18.0 CQERECIJPE ACTION PROGERf 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 REOUESTS FOR RELIEE Where TVA has determined that certain code requirements or examinations are impractical, TVA will submit written requests for relief to NRC with information to support the determinations and any proposed alternate examinations. The impractical code requirements or examinations shall be identified in this program, and references to particular requests.for relief shall be included. When impractical examination requiremente are identified in the field, ISO shall notify ASME Section XI Programs such that the information may be included in this program and requests for relief may be prepared if necessary. Requests-tor relief shall be submitted to the NRC via SON Site Licensing. SON Unit I requests for relief are contained in Attachment 3. TVA submitted 13 requests for relief (ISI-1 to ISI-13) from Code requirements. ISI-1, ISI-3 to ISI-6,.ISI-8 to ISI-10, and ISI-13 were granted. ISI-11 was withdrawn, ISI-12 was not needed, and two, IGI-2 and ISI-7, were' postponed. For more detailed information on requests for relief, see Safety Evaluation Report, dated February 7, 1991, from F. J. Hebdon, NRC, to 0. D. Kingsley, Jr. (A02 910214 009), and Safety Evaluation Report dated October 21, 1991, from F. J.-Hebdon to D. A. Nauman (A02 911024 003). Response from NRC on Request for Relief ISI-14 stated that relief is not required during the first 10-year inspection interval. For more information, see memorandum from F. J. Hebdon, NRC, to Dr. Mark O. Medicrd, TVA, dated August 31, 1992 (A02 920903 005). TVA has now identified four (4) other areas where code requirements are impractical. These requests for relief are identified ~as ISI-15, -16,
-17, and -18. These relief requests were submitted to the NRC with Revision 17 of this program.
20.0 AUEMElggD EXAMINATIONS Augmented examinations are performed in addition to ASME Section XI code requirements. The augmented examinations may be required by the NRC or: be self-imposed by TVA. Typical sources include generic letters, IE Bulletins, technical specifications,-vendor recommendations, and industry experience. Attachment 6 provides a schedule for augmented examinations. 1328C/COC3
w SI-114.1
~ SURVEILLANCE ASME SECTION XI Revision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM page 66 of.102 9
The responsible organization or owner shall have technical and-
. administrative responsibility for each augmented examination identified in this section. This responsibility shall includa scheduling any examinations through the Site Quality Organization, tracking the status ' of examinations, and reporting completed examinations. Responsible organizations requesting inclusion of augmented examinations in this section shall submit a written request to the Supervisor,'ASME Section XI Programs. The written request shall-include ~ specific details cuch as requirement source, identification of components requiring examination, examination frequency, examination method,- examination area / volume, acceptance criteria, types of flaws anticipated, areas of high suspect, probability of failure, and reporting requirements.
Copies of the written request shall be submitted to ISO and the S00 to facilitate nondestructive exnmination procedure preparation, establishment of training programs, and personnel familiarization.
- Prior to each refueling outage, a meeting shall be initiated by the SQO. Meeting attendees shall include the responsible organizations,
,, 500, ISO, ASME Section XI Programs, and Site Engineering. The meeting agenda should include examination plans and schedules, updates on industry experience, and any additional portinent information. rollowing the completion of the augmented examination, the 500 shall " report to the responsible organization items such an examination results and changes in results from previous examinations. The responsible
, organization shall determine if a meeting with the 500 and/or other appropriate organizations is necessary to discuss itema such as e
n additional examinations to be conducted during the current outage, '~ trends, lessons learned, and identify any future actions such as changes la the frequency of examination. Augmented examinations that require reporting to the NRC shall be the responsibility of the responsible organization. 20.1 Feedwater Nozzle-to-Pipe Welds and Adiacent Ploe/Fittinos and Hozzle Areas Responsible Organization: Site Engineering. The requirements of NRC IE Bulletin 79-13 were satisfied during ' the Unit 1 Cycle 1 outage. Due to the safety-related ramifications and the assessments concluded in Incident Investigation (II) No. II-S-92-027 of the steam generator nozzle transition section cracking problem and potential'for cracking in adjacent components within the feedwater piping system, TVA will perform an augmented inspection as determined by Site Engineering. This shall include the four feedwater nozzle 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 nozzle-to-transition piece welds, ; transition piece-to-elbow welds, 4-inch feedwater/ auxiliary I feedwater tee-to-pipe velds, and base metal adjacent to each weld l for a distance-of two wall thicknesses. These welds shall be l 1328C/COC3
i SI-114.1-SURVEILLANCE AFME SECTION XI Revision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 67 of 102 volumetrically examined by the ultrasonic method, supplemented with radiographic examination when specified by Site Engineering. Ultrasonic acceptance criteria shall be in accordance with ASME Section XI, 1986 Edition IWC-3414 for Class 2 welds, respectively.
^
The results of the examination will be submitted to Site Engineering for evaluation and trending of flaw sizes and growth rates. The results of this examination shall be included in the ISI_ Report discussed in Section 16.3. Inspection of the transition pieces, the nozzle-to-transition piece welds, 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 N0ZZLE TRANSITION PIECE EXAM SCHEDULE i Cycle Examination Areas ~~ 1 IE Bulletin 79-13 completed .. 2 1 nozzle-to-pipe weld and adjacent pipe and nozzle area 3 1 nozzle-to-pipe weld and adjacent pipe and nozzle area 4 All nozzle transition section pieces and welds 5 All nozzle transition section pieces and welds 6 All nozzle transition section pieces and welds Inspection of the 4-inch feedwater/ auxiliary 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_ refueling outage. Loops 1 and 3 are to be inspected each odd numbered outage beginning with the Cycle 7 refueling outage. 20.2 RPV Nozzle Safe Ends Responsible Organization: Site Engineering. The augmented examination requirements of the RPV nozzle-to-safe end welds are included in the final report " SON - Evaluation of cracking in reactor vessel nozzle stainless steel buttering." The examinations for Unit 1 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 Reactor Coolant Pump F]vwheel Responsible Organization: Site Engineering. 1328C/COC3
. . - = . .
SI-114.1 SURVEILLANCE ASME SECTION XI Rsvision 20 INSTRUCTION. INSERVICE INSPECTION PROGRAM Page 68 of 102 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 those areas accessible for examination without having to remove the flywheel from the housing) and complete ultrasonic examination at approximately 10-year intervals during the plant shutdown coinciding with the ISI schedule as required by Section XI of the ASME Code. This examination is performed in accordance with SON Technical Specifications and satisfies 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 examination 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 Motor S/N - BOREKEY (i.e., 4S-81P352 - BOREKEY) For the 10-year exam, the ID's shall bei RCP Motor S/N - SUR (i.e., 4S-81P352 - SUR) RCP Motor S/N - VOL (i.e., 4S-GlP352 - VOL) See Augmented Examination Attachment 6 for RCP flywheel scheduled examinations. 20.4 Steam ___ Generator Tubina Responsible Organization: Corporate Steam Generator Maintenance and Technology-(SGMT). . Refer to Technical Specification Surveillance Requirements 4.0.5 and 4.4.5.0. Each steam generator tube bundle consists of 3,388 NI CrFe alloy (Inconel SB-163) U-tubes of 0.875 OD 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 characterization of an indication, but eddy current shall be utilized to determine compliance with acceptance 1328C/COC3
SI-114.1 SURVEILLANCE ASKE SECTION XI Revision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 69 of 102 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 SGMT Supervir.or is responsible for the selection of steam generator tubos to be examined. 20.t.1 Steam Generator Simole Selection And Inspection 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 Appendir A.
; 20.4.2 Etcam Generator Tube Samole Selection and Inspection [C.2) , The steam generator tube minimum sample size inspection result classification, and the corresponding action required shall be as specified in Table 2 of Appendix A.
The ISI of steam generator tubes shall be performed at the t frequencies specified in Section 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 of Appendix A) tubes selected for inspection will be examined (TVA commitment to NRC L44 350617 801). Note that the hot leg inspection sample and the cold leg inspection sample do not necessarily involve the same tube, (i.e., it does not preclude making ^ separate entries from the hot and cold leg sides and selecting different tubes on the hot 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 4 number of tubes in all steam generatorst the tubes selected for these inspections shall be selected on a random basis excepts
- a. Where experience in similar plants with similar water chemistry indicates critical areas to be inspected, then at least 1/2S (as defined by Table 2 of Appendie 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.
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SI-114.1 SURVEILLANCE. ASME SECTION XI Revision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM page 70 of 102
- 3. A tube inspection (pursuent to Section 20.4.4.a.8) shall be performed on each selected tube. If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be evaluated and recorded and an adjacent tube shall be selected 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 ISI may be subjected to a partial tube inspection provided:
- 1. The tubes selected for these samples include the tubes from those areas 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.
4
- d. The results of each car.:ple itspection shall be classified into one of the following three categories:
Cateoory Inspection Results C-1 Less than 5 percent of the total tubes inspected are degraded tubes and none of the inspected tubes are defective. C-2 One or more tubes, but not more than 1 percent of the total tubes inspected are defective, or between 5 and 10 percent of the total tubes
. inspected are degraded tubes.
C-3 More than 10 percent of the total tubes inspected are degraded tubes or more than 1 percent of the inspected tubes are defective. NOTE: In all inspections, previously degraded tubes must exhibit significant (10 percent) further wall penetrations to be included in the above percentage calculations. 20.4.3 Inspection Frecuencies The above required ISIS of steam generators shall be performed at frequenclos indicated in the following paragraphs and in such a manner that the maximum allowable time between eddy current inspections on individual steam generators is 72 months. 132BC/COC3
___ - - - - - - ~ ~ ~ ~ SURVEILLANCE INSTRUCTION ASME SECTION XI SI-114.1 INSERVICE INSPECTION PROGRAM Page 71 of Revision 20 i 102 L) l
- a. l Full Power initial Months but withins 24 criticality.
ve of calendar r ath Subsequent ISIr shall be performed at intervals of not less than 12 nor emor ' than 24 calendar months after the previous inspection. service under All Volatile TreatmentIf two consecutive inspe . conditions, including the PSI, result in all inspection r not esults inspections dernenstrato thst served upreviously ve obt'alli 1 degradation has occurred, the nal inspection intdeg be extended to a maximum of once per 40 erval.may month L s, b. If the results of the ISI of a steam generator 40-month intervals fall in Category , the C 3 conducted inspection once frequency per 20 months. shall be increased to at l east frequency shall apply until the subsequent nspections iThe increase in in natisfy tho criteria of section 20.4.3.as the it
. n erval may then months. be extended to a maximum of once per 40 c.
Additional, unscheduled ISIS shall be perf ormed on sample inspection specified inxATable 2 of App s during the shutdown subsequent to anyooflowing conditions. the f l 1. Primary-to-secondary tubes leaks (not incl uding leaks originating from tube-to- tube sheet in excess of the limits of Technical Specifi welds) 3.4.6.2. cation 2. A seismic Basis occurrence greater than theaOper Earthquake. ng ti 3. A theloss-of-coolant accident requiring actuati engineered safeguards. on of 4 20.4.4 Acceptance criteria A main steam line or feedwater line break . a. As used in Section 20.42 1. Imoerfection means an exception to the di mensions, fabrication drawings or specificationsfinish red by Eddy or con the nominal tube wall thickness, a le, if detect bcurre may be considered as imperfections. 1 1328C/COC3
SI-114 01 SURVEILLANCE ASME SECTION XI Revision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 72 of 102
- 2. Decradation means a service-induced cracking, wastage, wear or general-corrosion occurring on either inside or outside of a tube.
- 3. Dearaded Tube means a tube containing imperfections greater than or equal to 20' percent-of the nominal wall thickness caused by degradation.
- 4. Egtssnt Degradation means the percentage of the tube wall thickness affected or removed by degradation.
- 5. Defect means an imperfection of such severity that.
It exceeds the plugging limit. A tube containing a defect is defective.
- f. Pluggino 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. Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in Section 20.4.3.c.
- 8. Tube Insnection means an inspection of the steam generator tube'from the point of entry (hot leg side) completely around the U-bend to the point of exit (cold leg side) (i.e., tube end to tube end). Entries may be made from either the. hot or cold leg sides and separate entries on the hot. leg and cold leg sides on different tubes are allowed.
- 9. Preservice Inspection (PSI) means a tube inspection of each steam generator tube performed by eddy current techniques prior to service to establish a baseline condition'of the tubing.
This inspection shall be performed prior to initial power operation using the equipment and-techniques expected to be used during subsequent ISIS.
- b. The stoam 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.
132BC/coC3
M SI-114.1 SURVEILLANCE ASME SECTION XI Revision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 73 of 102 20.4.5 Reoorting Corporate SCHT shall be responsible for preparing and submitting reports. 20.4.5.1 Technical Specification Plant management shall report this informaticu to the NRC within the time period specified. See Plant Instruction AI-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 of steam generator manway closure,
- b. Inservice Inspection Results Report-The complete results of the steam generator.
tube ISI shall be submitted to the NRC in a + special report pursuant to Technical
^
Specification 6.9.2 within 12 months following completion of the inspection-(steam generator manway closure). This special report shall includes
- 1. Number and extentLof tubes inspected.
- 2. Location and percent of wall-thickness penetration'for each indication of an imperfection.
- 3. Identification.of tubes plugged.-
- c. Category C-3 Report Results of steam generator tube inspectionsi which fall into Technical Specification Category C-3 require prompt notification of the NRC pursuant to-Technical Specifier.tlon 6.6.1 prior to resumption of plant operation.
'The written followup of.this report shali-provide a description of investigations conducted to determine cause of the tube degradation and. corrective measures to prevent recurrence.
-132BC/COC3
SI-ll4.1 SURVEILLANCE ASME SECTION XI R visica 20 INSTRUCTION INSERVICE INSPECTION PROGRAM- Ptga 74 of.102' 20.4.5.2 ASME Section XI Reporting Requirements-
-For-eddy current examination of heat exchanger Ltubing, the report shall include a. record indicating the tube (s).or.amined (this may be marked on a tube sheet sketch or drawing), the
~ ~
extent to which each tube was examined,.the. axial 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 RPV Nozzle Claddina Responsible Organization: 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 autamated reactor vessel nozzle 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 NRC via the ISI Report discussed in Section 16.2. Nozzle-forging material.and cladding is identified in Section 7.1.2. A special preservice examination of the reactor-vessel nozzles'was-conducted to evaluate the extent of-underclad cracking.- The examination utilized:a 70* angle beam and 0* beam manual contact technique. All indications found vers demonstrated to be acceptable'in accordance with ASME Code Section XI criteria. (Reference FSAR Section 5.4.1.1.) 20.6 Steam Generator Feed Rino and J-Tubes Responsible Organization: Corporate Steam Generator Maintenance and Technology. The carbon steel J-tube nozzles have been replaced.with Inconel 600 J-tube nozzles. This material is resistant to' erosion' corrosion damage. Inspection of the J-tube nozzles 1s not necessary. An ultrasonic thickness checkf of the feed ring header, and tee shall be performed on a frequency of every 10 years. .This augmented examination is self-imposed by TVA (S01 860515.828) and
'does not require a'special report. Results of-the examination shall be included in the ISI. Report discussed in Section 16.3.'
1328C/COC31
SI-ll4.1 SURVEILLANCE ASME SECTION XI Revision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 7S.of 102 1 20.7 Control Rod-Guide Tube Flexures Responsible Organization: Corporate Outage Support.- Any revisions or valvers 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 and LOl 840723 035). The control rod guide tube flexures shall be visually examined in accordance with visual examination method VT-3 (see Section 11.1) during each refueling outage. These 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 copy of the VT data sheets shall be forwarded to the appropriate cognizant engineer. The PRISIM identifiers for the control rod guide tube flexures are CRDTUBEFLEX-A07 CRD'JUBEFLEX-E09 CRDTUBEFLEX-GOS CRDTUBEFLEX-J11 CRDTUBEFLEX-LO7 This augmented examination is self-imposed by TVA and does not require a report. Results of the examination shall be included in the ISI Report discussed in Section 16.3. 20.8 Rod Control Cluster Assembly (RCCA) Claddine Wear Measurements Responsible Organization: Corporate PWR Fuel Engineering. The RCCA rodlet cladding wear for both SQN units has been examined via the eddy current measurement NDE technique. Encircling coils were used for total area loss determinations and profilometry data taken to characterize wear scars. SQN Unit 2 RCCAs were-inspected for rodlet cladding wear in February 1989. SQN Unit 1 RCCAs were inspected in April 1990. Results were documented (L38 890511 800 and L36 901030 800). Summaries were provided for the ISI Reports discussad 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 1328C/COC3
SI-114.1 SURVEILLANCE ASME SECTION XI Rsvisien 20 INSTRUCTION. INSERVICE INSPECTION PROGRAM .-Ptga 76 of 102 PWR Fuel Engineering. . When performed, the results will be reviewed, the wear data bases updated,-and specific repositioning-plans revised as necessary. Any RCCA'with excessive rodlet cladding wear will be replaced. RCCA wear 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 Accelerated Field Weld Program (C.1] - COMPLETE Responsible Organization: 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 Field Weld Program for SON Unita 1 and 2. This augmented and accelerated program requires completion of. 100 percent of ASME Classes 1 and 2 piping, piping support, and component (reactor vessel, steam generator, pressurizer, and reactor coolant pumps) support field welds that are in the first 10-year program in the two (2) consecutive refueling outages following restart. The Accelerated Fleid Weld Program was completed during the Unit 1 Cycle 5 refueling outage. .The results were included in the ISI Report discussed in Section 16.2. , 20.10 Thimble Tube 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 1 Cycle 4 refueling outage. . See R. W. Fortenberry's-July 21, 1988 memorandum to S. J. Smith (S57.880721 821) and J. F. Murdock's June 3, 1988 memorandum to J..B. Hosmer (L29 880531 914).- Future examinations shall be to examine all thimble tubes at each outage until a wear data base has been established. Results of the examinations shall be forwarded to Site Engineering. See l P. J. Trudel's April 20, 1990 memorandum to M. J. Burzynski (B25 900420 008). Results of the examinations shall be; included in the ISI Report discussed in Section 16.3. 1328C/COC3
SI-114.1-SURVEILLANCE' 'ASME SECTION XI Rsvision 20' INSTRUCTION INSERVICE INSPECTION PROGRAM Page 77'of 102 20.11 Examination of Pipino Connected to Ahe Reactor Coolant System Due to Thermal Stresses Responsible Organizationt Site Engineering. Due to the potential thermal stresses on unisolatable piping attached to the RCS (see NRC Bulletin 88-08), TVA has examined Lhe following areas: 1) the four 1.5-inch head injection lines,
- 2) the 2-inch pressurizer spray line from the charging path,
- 3) the 3-inch alternate charging path, and 4) the 3-inch normal charging path. All of the welds up to the first valve have been PT examined, and the 3-inch lines have been UT examined as well.
These examinations were conducted during the Cycle 3 forced outage period. The SON Project Engineer has prepared a report to Licensing, who in turn prepared a report.to the NRC (see memorandums B29 8809006 008, S08 880830 843, L44 860824 802, and D25 880819 014). Due to the assessments concluded in Incident Investigation No. II-S-92-027 of the steam generator nozzle transition section cracking problem and NRC Bulletin 88-08, similar conditions were evaluated for the Chemical and Volume Control System (CVCS), Safety Injection System (SIS) and Reactor Coolant System (RCS). 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 88-0E) 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 FCV 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 1 forced 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 ualess otherwise revised or waived by Site Engineering. Additional telds and/or inspection techniques may be added by Site Engineering where further evaluation indicates a potential for thermal stratification. Ultrasonic (UT) examinations shall include 100 percent volume of the welds and base metal adjacent to each weld for a distance of two wall thicknesses, where accessible (fittings, elbow interdose and valves may prevent full circumference evaluation). Liquid penetrant (PT) examinations shall include the welds and base metal adjacent to each weld for a distance of one-half (1/2)-luch. UT and PT acceptance criteria shall be in accordance with ASME Section XI, 1986 Edition, IWB-3614 and IWC-3514 for Class 1 and 2 welds, respectively.
SI-ll4.1 SURVEILLANCE ASME SECTION XI Rsvision 20 INSTRUCTION. INSERVICE INSPECTION PR3 GRAM :Page 78 of 102 The results of the examination will be submitted to Site Engineering for evaluation and trending. The results of this examination shall be included in-the ISI Report discussed .in Section 16.3. Inspection of cold leg Loop 1, Weld CVCF-?l3 and cold leg Loop 4, Weld CVCF-246 shall be performed by tn examination method and scheduled for inspection at_each consecutive refueling outage. Inspection of cold leg Loop 1, Weld SIF-145; cold leg-Loop 2, Weld SIF-168; cold leg Loop 3, Weld SIF-184; and cold leg Loop 4, Weld SIF-128 shall be performed by the UT examination-methd and scheduled for inspection at the Cycle 5 refueling outage with supplemental inspections performed as specified by Nuclear Engineering.
'L Inspection of pressurizer spray line, Weld RCF,-23; hot leg surge line Loop 2, Weld RC-33; and pressurizer surge line, Weld RC-35 shall be performed by the UT examination method and scheduled for inspection as noted below.
Pressurizer spray line, Weld RCF-23, shall be inspected'every fourth refueling outage beginning with refueling-outage 6.- Hot leg surge line Loop 2, Weld RC-33, shall be inspected every fourth refueling outage beginning with refueling outage 10. Pressurizer surge line, Weld RC-35, shall'be inspected every fourth refueling outage beginning with refueling' outage 12. Inspection of hot leg Loop 1, Weld RHRS-209-shall be performed-by the UT examination method and scheduled for inspection once during each 10 year inspection interval beginning with-the
~
second inspection interval. Inspection of hot leg Loop 2 Weld SI-1772 and hot leg Loop 4-Weld SI-1735 shall be performed by the PT examination method and scheduled for inspection once during each 10-year inspection. Interval. Inspection of the welds adjacent to FCV 62-54 for the Loop 3 excess letdown supply line shall be performed by the PT examination method end scheduled for inspection every fif th _ _ refueling outage beginning with refueling outage 6. For Unit 1,
.the wold numbers to be inspected are ICX-2593 and ICX-2594 (Reference Weld Map 1-CVC-509-lW).
1328C/COC3-
- - ~- - _ . _ . .
S1-114.1 SURVEILLANCE ASME-SECTION XI Rsvision 20 ) INSTRUCTION INSERVICE INSPECTION PROGRAM Pags 79 of 102 20.12 Examination of Pressurizer Surce Line Due _io Occurrenat of Thermal Stratification - COMPLETE Responsible Organization: Site Engineering. The requirements of IE Eulletin 8811 were satisfied duritag the UIC4 refueling outage. The following information is being retaiaed for historical purposes. Due to the tnermal stratification of the pressurizer surge line (see NRC Bulletin 88-11) TVA performed a visual inspection on the pressurizer surge line.- This examination should determine any gross discernable distress or structural damage in the entire pressurizer surge line, including piping, pipe supports, pipe whip restraints, and anchor bolts. This examination was scheduled and perfarmed per SMI-0-68-4. The results of the examination were in accordonce with SMI-0-68-4. Nuclear Engineering 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 exan.inations. ' 20.13 Pressurizer Relief Line Repair Welds GEd_hdioinina Areas Responsible Organization: Site Engineering. The augmented examination requirements of the pressurizer relief line (draw bead welds) are included in the Technical Specifications 4.0.5 and 4.4.3.2.4. The pressurizer relief line repair welds (RCT-24P and RCF-24H) and adjoining areas shall be examined in accordance with TVA procedure N-UT-25 using improved ultrasonic detection and evaluation procedures prior to entering Mode 4 whenever the plant has been in cold shutdown for 72 hours or more if the er: 'ination has not been performed in the previous six months. In the event these 6-month period examinations find the piping free of unacceptable indications for 3 successive inspections, the inspection interval'shall be extended to 36 month
. intervals (12 months to coincide with a scheduled refueling outage). In the event these 36-month period examiaations find the piping free of unacceptable indications for 3 successive inspections, the inspection interval shall be extended to 80-month periods. This procedure has been qualified in accordance with NRC IE Bulletin 83-02 by demonstrating proficiency-in detecting Intergranular Stress Corrosion Cracking (IGSCC). All future examinations of the pressurizer relief lino repair welds will be performed using this procedure or a procedure with ultrasonic sensitivities equivalent to those required for detecting IGSCC.
The report shall be submitted with the ISI Report discussed in Section 16.2. See examination history below: 1328C/COC3
l S1-114.1 SURVEILLANCE ACME SECTION YI R: vision 20 INSTRUCTION INSERVICE IHSPECTIOtt PROGRAM Pcg3 80 of 102 Examination History Date Examinationa
,_ HtIf_l'ArlpInd._ _ IMWdattLl91LPat10dA 9-26-?O (Examination Perforu d Start of first 6-month period by 51-284) 5-15-81 (Examination Performed End of first 6 month period by $1-284) Start of second 6-month period 1-25-82 (Examination Performed End of second 6-month period by 51-284) Start of third 6-month period 11-1-82 (Examinstion Performed End of third 6-month period by S1-284) Start of first 36-month period 9-14-85 (Examination Performed End of first 35-month period by SI-284) Start of second 36-month period 8-2-88 (Examination Performed End of second 36-month porlod by SI-114.1) Start of third 36-month period XX-XX-91 (Examination Performed End of third 36-month period by SI-114.1) Start of first 80-month p6riod 20.14 bey _C1gsure _ Heao C1reumf erentigl_litid QfQ1-101 t
Responsible Organization: Site Engineering. See subsection 7.1.1.3 of this program for augmented examination requirements. This augmented examination does not require a special report. Results of the examination shall be i cluded ht the ISI Report discussed in Section 16.2. See the foliowing tables RV Head Flaw Examination Dates by *ycle: Cycle 2 (W09-10D) First Period Cycle 4 (WO9-10B-TLAW) Second Period Cycle 6 (WO9-10B-FLAW) Third Period ( 20.15 Main Feedwate.t lsolation Valves - COMPLETE Responsible Organization: Sito Engineering. The augmented examination requirements of the Main Feedwater Isolation Valves were satisfied during the Unit 1 Cycle 5 refueling outage. This information is being retained for historical purposes. 4 1328C/COC3
'r4
___..m__ ...m_ -
.. - - .. - - - - - - . - . . . . . . - - ..i
SI-114.1 SURVEILbANCE ASME SECTION XI Revisien 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Peg 2 81 of 102-Due to the bonnet indications found by previous inspections, MTIVs 1-PCV-3-33 and 1-YCV-3-4*/ received an augmented magnetic particle (MT) examination during Unit 1 Cycle 5 refueling outage. The bonnut indications were determined not to be service reinted and were identified as artifacts of the casting process used to produce the valve bonnets. The purpose of the re-examination is o 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 indiention seems to have grown, the ends of the indication will be examined optically either in situ or by
- repilcation and laboratory examination for evidence of growth. I
- 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 referred to Site Engineering.
SQN Nucitar Yngineering will evaluate the condition and recommend that the bonnet or body affected be weld repaired or replaced, as necessary. " Definite evidence" is considered to be fatigue-type cracking emanating from the end of the previous indication or stress corrosion cracking. In either
- case, the propagated cracking wculd be free of the high temperature corrosion product present in the previous examination.
- d. If there is no evidence of growth associated with the reinspection, no further inspection is required.
This augmented examination was-self-imposed by TVA (B25 891228 008) and did not require a special report. Results of the examinations were forwarded to Site Engineering by 800 and included in the ISI Report discussed in Section 16.3. 21.0 INTEHFACE DQCLR(ENTS 21.1.1 Quality Methods Procedure: QMP-102.4, Qualifica' tion and' Certification Requirements for NQA NDE Personnel 21.1.2 Quality Hethods Procedure: QMP-110.5, Administration of Hondestructive Examination Procedures. 21.1.3 Quality Methods Procedure: QMP-105,4, Control of Calibration Standards. 21.1.4 SON Administrative Instructions AI-8 and AI-18.5 (Series). 1328C/COC3-
i f SI-114.1 SURVEILLANCE ASME SECTION XI Revision 20 l 2NSTRUCTION INSERVICE INSPECTION PROGRAM Pcg3 82_of 102 1 21.1.5 SON fite Standard Practice SSP-2.9, SSP-3.1, SSP-3.4, SSP-3.6, l SSP-3.7, SSP-4.5, SSP-6.9, SSP-6.21, SSP-8.2, SSP-8.5, SSP-8.6, SSP-9.3, SSP-12.58, eco SSP-12.8. 21.1.6 SON Special Maintenance Instructions SMI-0-66-04 and SMI-0-08-15. 21.1.7 SON Maintenance Instructions: 0-MI-MRR-066 005.0, MI-1.4, 0-MI-MXX-068-004.0, 0-MI-MXX-068-003.0, MI-2.2, MI-10.2.3, MI-6.15, 0-MI-HVV-000.008.0. 22.0 EVELQPMENTAL REFERENCKS 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 Welds" (L18 860730 899).
22.1.2 Memorandum from V. A. Dianco to C. R. Brimer dated January 10, 1987 (B25 870109 045). 22.1.3 Memorandum f rom G. C. Zech to S. A. White dated January 25, 1988 allowing use of code cases N-341 and H-356, 22.1.4 Memorandum from P. G. Trudel to M. J. Dursynski dated April 20, 1990 (D25 900920 008). 22.1.5 Memorandum from R. L. Orldiey to D. J. Youngblood dated January 30, 1987 (L44 870130 804). 22.1.6 NRC Bulletin 88-09 and Information Notice 87-44 supplement 1,
" Thimble Tube Thinning in Westinghouse Reactors."
22.1.7 Memorandum from R. W. Fortenberry.to S. J. Smith dated July 21, 1988 (S57 880721 821). 22.1.8 Memorandum from J. F. Murdock to J. D. Hosmer dated Juno 3, 1988 (L29 880531 914). 22.1.9 NRC Bulletin _88-08, " Thermal Strasses on Piping Connected to Reactor Coolant Systems," and Supplement 1 22.1.10 NRC Bulletin 88-11,'" Pressurizer Surgo Line Thermal Stratification." 22.1.11 Memorandum from D. F. Goetcheus to J. T. Lewis dated September.2, 1988 (S57 880902 911). 22.1.12 Letter from S. C. Black to 0. D. Kingsley,=Jr., dated January 18, 1990, " Nuclear Quality Assurance Plan" (TAC Ho. 72833), allowing-the use of 1984 Edition of ASNT SNT-TC-IA for certification of NDE personnel. 22.1.13 Memorandum from P. G. Trudel to L. E. Martin dated April 17, 1989 (B25 890417 024). 1328C/COC3
SI-114.1 SURVEILLANCE ASME SECTION XI Revision 20 INSTRUCT!0H INSERVICE INSPECTION PROGRAM Page 83 of 102 22.1.14 Memorandum from S. C. Black to 0. D. Kingsley, Jr., dated December 13, 1989, allowing the use of Code Case H-460. 22.1.15 Memorandum from T. J. Hebdon to 0. D. Kingsley, Jr., dated February 7, 1991 (A02 910214 009). 22.1.16 Memorandum from P. J. Hebdon to D. A. Nauman dated October 21, 1991 (A02 911024 C03). 22.1.17 Memorandum f rom P. G. Trudel to R. L. Lumpkin, Jr., dated December 28, 1989 (B25 891228 008). 22.1.18 Memorandum from G. J. Pital to G. L. Be',ew dated January 5, 1984 (L29 840105 856). 22.1.19 Memorandum from T. T. Ziegler to R. C. Parker dated December 27, 1983 (L29 831222 836).- 22.1.20 NRC Bulletin 83-02, " Stress Corrosion Cracking in Large-Diameter Stainless Stool Recirculation System Piping at BWR Plants." 22.1.21 NRC Bulletin 79-13, " Cracking in Teedwater System Piping." 22.1.22 Memorandum from D. T. Goetcheus to G. L. Below dated May 15, 1986 (801 860515 828). 22.1.23 Memorandum from R. S. Howard, Westinghouse, to J. P. Darling dated July 9, 1984 (Lol 840723 035). 22.1.24 Memorandum from J. L. Tain, Westinghouso, 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,
?.987 (B41 870810 003).
22.1.26 Memorandum f rom 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 f rom R. R. Calabro to Those listed dated May 16, 1989 (L38 890511 800).. 22.1.30 Memorandum from R. R. Calabro to Those listed dated October 30, 1990 (L36.901030 800). 22.1.31 Memorandum from P. G. Trudel to M. J. Ray dated September 6, 1988 (B29 880906 008). 22.1.32 Memorandum from L. E. Martin to P. G. Trudel dated August 30, 1988'(S08 880830 843). 1328C/COC3
SI-114.1- . SURVEILLANCE ASME SECTION XI R3 vision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Pcgs 84 of 102 22.1.33 Memorandum from M. J. Ray to NRC dated August 24, 1988 . (L44 880824 802). i 22.1.34 Memorandum from P. G. Trudel to S. J. Smith dated August 19, 1988 (B25 880819 014). E 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 - Pressuriser, TM 1440-C225, Contract No. 68060-91934, H2M-2-6. t 22.1.37 Westinghouse Technical Manual - Vertical Steam Generators, TM 1440-C224, Contract No. 68C31-91934, H2M-2-4. 22.1.38 Westinghouse Instruction Manual - Auxiliary Heat Exchangers, Contract No. 68C60-91934, H2M-2-25. l 22.1.39 Westinghouse Instruction Book - Reactor Coolant Pump, Contract No. 68C60-91934, N2M-2-5. , 22.1.40 Ingersoll-Rand Instruction Manual - Residual Heat Removal Pumps, Contract No. 68C60-91934, H2M-2-30. 22.1.41 Memorandum from D. F. Goetcheus to G. J. Pitz1 dated March 23, 1992 (WO3 920323 059). 22.1.42 Memorandum from F. J. Hebdon, NRC, to Dr. Mark O. Medford, TVA, dated August 31, 1992 (A02 920903 005). 22.1.43 Incident Investigation (II).No. II-S-92-027. F 22.1.44 Memorandura from G. J. Pit:1 and M. L. Turnbow to N. C. Kasanas and D. R. Keuter, " Review of Augmented Nondestructive Examinations (NDEs) not Presently Included in the Inservice Inspection (ISI) Programs," dated September 1, 1992 (L29 920828 800).
.e P
k 1328C/COC3 I
cu APPENDIA A hs
. u w TABLE 1 4 O Minimum Number of Steae Generators To Be Inspected During Inservice Inspection Only wm 5$
Y$ Cw No. of Steam Generators per Unit n t-First Inservice Inspection four U" o5 Second & Subsequent Inservice Inspections Two
*Q Onel Table Notation:
- 1. Each of the other two steam generators not inspected during the first inservice inspectio-s shall be inspected during I the second A third inspections. The fourth and subsequent inspections shall follow the instructions described below: w
=
- The inservice inspection may be 11eited to one steam generator on a rotating schedule encompassing 121 of the
- tubes if. the results of the first or previews inspections indicate that all steam generators are performing in a N w
- like sanner.. Note that under some circumstances, the operating conditions in one or more steam generators may be $p
' found to be more severe than those in other steam generators. Under such circumstances the sasele sequencs sna11 n on be modified to inspect the most severe conditions.
w Z o9 n2 de O 2 8
=
7::
* ;E. 2.
w
u APPENDIX A . u" TABLE 2
" Steam Generator Tube Inspection n u.
Ist Sample Inspection 2nd Samle Inse-etion Sample Sire Result Action Required Result Actice Required 3rd Saple Inspecion Result Acticn Rewired 5$ H< w t2 A minimust of 5 C-1 None N/A N/A N/A N/A Nt* Tubes per S.G. C-2 Plug defective tubes C-1 NMe N/A
$p N/A o=
and inspect additional Plug defective tubes C-1 Nee 25 tubes in this S.G. C-2 and inspect addi- C-2 Plug defective EQ tional 45 tubes in tubes this S.G. C-3 Perform action for C-3 result of first snie C-3 Perform action for C-3 N/A N/A result of first sample. ,
=
C-3 Inspect all tubes this All other 5.G., plug defective S.G.s are None N/A N/A Q
- e tubes and inspect 25 C-1 $p tubes in each other S.G. Some S.G.s o cs C-2 but no Perform action for N/A N/A "8 %
adJitional C-2 result of w Prompt notification to S.G. are C-3 second samle 5Q NRC pursuant to technical Additional Inspect all tub-es in as o specification 6.6.1 S.G. is C-3 each S.G. and plug N/A N/A Ed defective tubes. eo Prompt notification to NRC pursuant to E:
=x technical speci- "
ficatico 6.6.1 ir O S - M% Where n is the number of steam generators inspected during an inspection. O
,n.
9 0 w G <9 e e- p CB M Clp om em Cm O *
.3 Y nu H
O N
51 114.2 SURVEILLANCE- ASME-SECTION XI Revision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 87 of 102
- APPENDIX B DATA SHEET 1 4
SEQUOYAH HUCLEAR PLANT UNIT 1, CYCLE SITE FINAL REPORT Prepared by: Approved by: , a . 1502C/COC3
51-114.1 SURVEILLANCE A$ME SECTION XI INSTRUCTION Revision 20 INSERVICE INSPECTION PROGRAM Page 88 of 102 APF7RDIX C UOTIFICATI0d 0F INDICATION PART I - FINDINGS NOI No. Plant / Unit ISI Dwg./Sh. No. ___ Examination Report No. Component ID ., ; Description of Indication (Sketch / Photograph if Required for Clarification): Signature of Examiner / Certification Levels Date Signature of Fleid Supervisor (Contractor): Signature of 500 Representatives Date Date PART II-DISPOSITION DCN NO. WR/NO NO. PER NO. FIR No. SCAR NO. Other Disposition Prepared / Recorded By Date PART III ADDITIONAL EXAMINATIONS Additional Sample Requiredt Yes No Attach list of items in additional sample, if required. VERIFICATION OF CLOSURE Verification of Completed Corrective Action Required by Disposition Reexamination Report Number, if Applicables Comments: Signature of.500 Representatives Date
-1502C/COC3
SI-114.1 SURVEILI.ANCE ASME SECTION XI Revision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 89 of 102 I APPENDIX D CUIDELINES TOR DETERMINING PIPING ; COMPONENT SUPPORT EXAMINATION BOUNDARIES a L
-1502C/COC3. .
' d W M wmy, , ,
S1-114.1 SURVEILLANCE ASME'SECTION XI Rovision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM- Page 90 of 102 APPENDIX D 1.0 EUREQBB This instruction defines and establishes the controls and-responsibilities for the determination of ASME Section XI component support examination boundaries. 2.0 EgpEE This instruct),n applies only to the piping component supports included in the appropriate plant instruction for preservice/ inservice inspection (hereafter, ISI program) for Sequoyah Nuclear Plant. 3.0 BEFERENCES 3.1 Memorandum from W. E. Pennell to R. A. Seasoms 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 Intervenino Element: Items that lie 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 as diesel engines, electric motors, coolers, valve actuators, 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 Existino Steels Building steel that is identified on a support drawing as " existing." 4.3 Iype A Examina.tlen Boundaryl The type of boundary to be used for those supports that are attachod to building floor, walls, ceiling, or embedded plate. 4.4 yype B Examination Boundary: The type cf boundary to be used for those supports that are attached to another existing support. 4.5 Type C Examination Boundary: The type of' boundary to be.used for-those supports that are attached to existing steel. 4.6 Tyne D Examination BOXndAtys The type of boundary to be une$ for those. supports that are attached to an intervening element.
'5.0- RESPONSIBILITIE,3 5.1 ASME Section XI Programs is responsible.for the initial review of-ASME Section XI component support' drawings and determining the
< examination boundary for those supports.- The Site Quality. Organisation-(SQO).shall be responsible for determinlag the 1502C/COC3.
1 l 51-114.1 i SURVEILLANCE ASME SECTION XI Revision 20 ) INSTRUCTION INSERVICE INSPECTION PROGRAM Page 91 of 102 APPEITDIX D ' examination boundary for new or modified supports. 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 Programn 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 IMPLEME17TATION 6.1 p_gtermination of component support Examination Boundary 6.1.1 Etattal 6.1.1.1 ASME Section XI Programs and 500 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 weld shall be included within the examination boundary.
- 2. Concrete bolt anchors, such as " red-head" or "rawl"_ anchors, are not included within-the Section XI code boundary and, therefore, do not fall within the examination boundary. Even though anchors may be listed on a support bill of materials, they are not required to be examined. (This note pertains to anchors only, not the associated bolting.)
- 3. All shims and lugs adjacent to the supported pipe shall be examined. Even though the shims and lugs may not be listed on the support bill of materials, they are required to be examined.
4 For component supports that do not have a bill of materials, items to be examined shall be described in the PRISIM 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. p0 (COC3.
l . SI-114.1 SURVEILLANCE ASME SECTION XI Revision 20 INSTRUCTION INSERVICE INSPECTIDH PROGRAM Page 92 of 102 APPENDIX D
- 5. Notification of Indication (NOI) forms shall be used to report unacceptable indications on compoAent supports only if the criteria in A, B, and C, below, are met.
A. the component support falls within the scope w of ASKE Section XI. B. the component support is part of the inservice inspection examination sample. C. the indleation 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, MR's, WR's, etc.
- 6. This instruction is intended to deal with piping supports only. Therefore, equipment support drawings will be provided in the ISI program that depict the examluation 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 culst, obtain the latest as-constructed drawing of the support. If an as-constructed drawing does not exist, obtain the latest as-Gesigned drawing of the support. For new or modified supports, the drawing included in the work instruction may be utilised. 'Using the drawing, classify the support in one of_the following categories:
- 1. Support is shown as beir; att-also to building floor, wall, ceiling or embeaoed plate.
4
- 2. Support is shown as being attached to " existing support."
- 3. Support is shown as being attached to " existing steel."
- 4. Support is shown as being attached to en intervening element.
After classifying the support in one of the categories, proceed to the corresponding section to complete the boundary determination. 1502C/C0C3
t SI-114.1 SURVEILLANCE ASMZ SECTION XI Revision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 93 of 102 t APPENDIY 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 PRIS!H data base. S.1.1.4 As supports are added or revised in the PRISIM data I base, this instructiot shall be used to determine or revise the examination boundary for that support. 6.1.2 Engngrts. Attached to Buildino. Floor. Vall&,Cellino _or Embedded..plata Tor supports attached to building floor, wall, celling 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 rategory of supports shall be considered Examination ", Boundary Type A and so desirsated in the PRISIM data base. 6.1.3 Suecorts Attached to Erintino supoorts EQII: 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, 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.")
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6.1.4 Suyoorts Attmehed to Existino Steel For supports attached to existing steel, the boundary _shall be defined as the point (s)/ area (s) of contact-between the support and " existing steel", along the support load path (s),' 7 up.to, but not including.the pressure retaining component. In addition to the requirements of 6.1.1, all11tems listed on the support bill' of materials are to be included within the qu _ 1502C/COC3
SI-114.1 , SURVEILLANCE ASMC SECTION XI R vision 20 ~ IHSTRUCTION INSERVICE INSPECTION PROGRAM Pega 94 of 102 APPENDIX D boundary. For TVA designed supports, the examination ) boundary may be determined from TVA drawings. These drawings ! should be referenced on ASME Section XI Program drawings. ' This category of supports shall be considered Examination Boundary Type C and so designated in the PRISIM data base. 6.1.5 Sapports At.tshed to Interstning Elemera 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 j component and all support members up.to, but not including, i the intervening element. In addition to the requirements of 6.1.1, all items listed in the support bill of materials are '! to be included within the boundary. This category of supports shall os considered Examination Doundary Type D and so designated in the PRISIM data base. 6.1.6 Surnorts. Attached to Various__S.tIRC.tRIAA i In many cases, cne 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 datn
., 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. These drawings should be referenced on ASME Section XI Program drawings. ;
- 2. All shims and lugs adjacent to the supported pipe.
6.2 Site Implementation 6.2.1 500 shall obtain the latest CCD of the support. If a CCD , does not exist, the latest as-constructed drawing shall be obtained. If an as-constructed drawing does not exist, the J atest as-designed drawing shall be obtained. If during the performance of an examination, significant differences are identified between the support drawing and the support field configuration, 500 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 project engineer if the work has been completed on'that particular support. If the work has P 1502C/COC3
{- 81-114.1 5 SURVEILLANCE ASME SECTION XI R:vialen 20 INSTRUCTION INSERVICE INSPECTION PRDGRAM Pcg) 95 et 102 APPENDIX D k f been completed, 500 shall obtain the change document support drawing. If the work has not been completed, the examination shall be delayed until the work has been completed. As an alternative to obtaining the latest as configured drawfugs and the bill of materials, the component support examination boundary may be defined as the attachment to the-component, up to and including the attachment to the floor, vall, and ceiling. 6.2.2 For variable spring hangers, constant force supports, and snubbers, the examiner or engineer shall use the drawing obtained per 6.2.1 above to verity that the thermal movement and support type given on the support drawing matches the corresponding luformation given in the Scan Plan or implementing instruction (WR, WP, etc.). If the movement and support type do not matcht
- a. The examiner as S00 Representacive shn11 contact ASME Section XI programs. When immediate actlon is required ASME Section XI programs may provide verbal lustructions to the requesting examiner or 600 Representative to enable them to perfo m the examination. Verbal lastructions 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 Clarification Request Form to ASME Section XI Programs. 800 or ASME Section XI Programs, upon receipt of a request, shall review the discrepancy and make any necessary changes to the examination boundary. If a request has been submitted (when verbal instructions were not requested), the request will be completed and returned to the requesting examiner;or engineet to enable them to perform the examination. A support shall not be examined until any discrepancies on that support are eliminated. .Any changes in the Examination Boundary Type will be incorporated in the PRISIM data base.
FQue See Examples 2-5 of Section 7.0 example boundaries of each examination boundary type. 7.0 EXAMPLM Form - Component Support Examination Boundary Clarification Request 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 1502C/COC3-
81-114.1 SURVEILLANCE ASME SECTION XI Revision 20 INSTRUCTION INSERVICT INSPECTION PROGRAM Page 96 of 102 APPENDIX D COMPONENT SUPPORT EXAMINATLQ1LDSUNDARY CLARiflCATION RtourST FORM Plants Unitt Dates Component Support No. Rev. Person Requec:tingt __ Requests eenemennesseenanneenneeeeeeeeeeeeeeeeeeeeeeeeeeeeeeeenenneeeeeeeeeeeeeeeeeeeena Responding ASME Section XI Programs Representativet Dates Responset Did " Examination Boundary Type" changet Yes No 1502C/COC3
SI-114.1 SURVEILLANCE ASME SECTION XI Revision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 97 of 102 APPEITDIX D EXAMPLE - TYPE A EXAMINA TION BOUNDARY EXIST-CONC W/EMB Pl. (12 X 3/4) fDWG-4BN1374-R6 W
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PCS FOR 1 UNIDIRECTIONAL St PPORT 1 @ l ' BEAM A TTACH LESS BOL T. BE-200 (IN0ERT$D) i @ l' s ROD X 3'4' W/JN G HN TOE-10' E0E .1 1/4 *'@ 1 @ 18' PIPE CLAMP BE-124 4 4 BOUNDARY: EXAMINE WELO TO EMBEDOED PLA TE AND ALL
- BILL OF MA TERIALS ITEMS. .
1502C/COC3 . i
51-114.1 SURVEILLANCE ASME SLCTION XI Revision 20 INSERVICE INSPECT 10H PROGRAM Page 98 of 102 INSTRUCTION APPENDIX D
. EXAMPLE - TYPE B (AND A) EXAMINA TION BOUNDARY' EXIST 1NG H1Ok25 SUPPT.
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1 @ TS 5 x 5 x 1/2 x'4*-0* ^ 1 @ PL. 3/4 " x 10 ' x O-10 ' LG W/4 13/16' @ HOLES. i 4 @ 3/4 ' @ BOL TS . 4 3/4 ' RAWLS S. O.E.F. f6010
. .. 1 BOUNDARY: EYAMINE ALL ITEMS ON BILL OF HATERIALS EXCEPT 1 17 (ANCHORS) . ALSO -EXAMINE SHIMS, ;
DO NOT: EXAMINE ' EXISTING' WSO 'X ' 25.
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. . 1502C/COC3
4 58-114e1 SURVEILLANCE ASME SECTION XI Revision 20 INSTRUCTION INSERVICE INSPECTION PROGRAM Page 99 of 102 ; APPENDIX D i EXAMPLE - TYPE C EXAMINA TION BOUNDARY ; l p==============================4 l
\ W30 x 210 (EXIST.)
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s=====. == _~ .:_~ ~ __ POS FOR i HORTZONTAL RESTRhINT L TO PIPE 2 @ 1 1/2' x 2 15/16', C. S. PLA TE, S' LG. '(A212-A) 1 @ 7/8 ' x 6 ', C. S. PL.A TE B ' LG, , 1 W12 x 27 x 3 '-9 5/B' LG. 2 3/B
- C. S. STIFFENER PLA TE FOR W12 x 27 BOUNDA R Y. _ EXAMI E WELO BETWEEN LUG AND PIPE AND ;
ALL BILL OF HATERIALS ITEMS. 1502C/COC3
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,, r SI-114.1 !
SURVEILt.ANCE ASME SECTION XI Revision 20- : INSTRUCTION INSERVICE INSPECTION PROGRAM. Page 100 of 102 APPENDIX D
. EXAMPLE - TYPE D EXAMINA TION BOUNDARY _-
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r PCS FOR 1 GUIDE
- 1 @ T. S. 6'x - 6 ' x 3/B ', 4 *-1/2 ' L G -
2 @ 1/2 ' x 3 ' C. S. PLA TE. 9 3/16' LG. ' i @ 1/2 ' x 3
- C. S. PLA TE. 9 ' LG, 4 @ 7/B'@ S. S. STUO. 3 7/B' LG. W/(2) HEX NUTS' '
1 @ l ' x 12 ' C. S. PLA TE. 20 1/2
- LG.
1 @~ l ' x 4 1/2' C. S. PLA TE. 12',,LG. , _BOUNDAR Y* EXAMINE, ALL BILL OF HA TERIALS ITEMS. , , 1502C/COC3i
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S!.114.1 . SURVE!LLANCE ASME SECTION XI Rovlsion 20 ; INSTRUCTION INSERVICE INSPECTION PROGRAN Page 101 of 102 > APPENDIX E FIELD CORRECTED DRAWING (S) TRANSMITTAL 70s ASHI section XI Programs Transmittel Numbert (Year) (Seg'iential) Plants SON Unit / Outage or Date U1/ _ The drawing (s) listed below from $1-114.1 have been flo2d marked with variations in configuration which were discovered during the course of inservice or preservico examinations. Please revise the controlled copy of this/these drawing (s) in the SI prior to the next refueling outage.
- 1. 7.
- 2. ___ 8: ,
3. 1 9.
- 4. 10
- 5. 11.
- 6. 12 -
Signature of Examiner /Date A signature of Field Supervisor RETURN 70s SITE QUALITY ORGANIEATION urawings have been revised as necessary to reflect the appropriate changes. Signature of ASME Section XI Programs Representative Date ' 1502C/COC3 a
' i SI-114.1-SURVEILLANCE ASKE SECTION XI Revision 20 INSTRUCTION- INSERVICE INSPECTION PROGRAM Page 102 of 102 SOURCE NOTES Requirements _ IKPLEME!TTING
= Statement RQURCE D00UMr1{I STATE @ L All STD 6.10 1 11 All Applicable ASKE Boiler and Pressure All Articles Vessel Code - Section XI 1974 Edition, Summer 3975 Adilenda,1977 Edition, Summer 1978 Addenda .
All Applicable ASME Boiler and Pressure -All Articles Vessel Code - Section V-All Applicable FSAR - SON All Chapters Surveillance Requirements Technical Specifications All 4.0.5, 4.4.5.0 - 4.4.5.5, Unit 1 - SQN 4.4.3.2.4, 4.4.10 e 10CTR50.55a Code Federal Regulations All 4 10CTR50 As Applicable U.S.N.R.C. Regulatory' All Guides 1.14, 1.26, 1.83, t 1.147, and 1.150 Provide a revised Response to NRC . C.1 ! ISI Program to NRC . dated 1/30/87
- within 6 mos. following. R. L. Gridley to NRC
. Unit restart L44 870130 804 NCO 870 038 004'
- 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 Casest N-209, N-234, All N-235,-N-307-1, N-308, N-401-1, N-402, N-416, N-426, N-435-1,.
N-461, N-341, N-356, N-460 _ O, IWA-1000,'INA-2200, ASME Bo!!'er and Pressure-
'All IWA-2300,-INA-2600, - Vesse1~ Code - Section XI IWA-3000,-IWB-3000, 1986 Edition
- IWC-3000, IWD-3000, Response Trom NRC' Dated._
INF-3000, Appendices 4/24/92 (A02 920429 005) III,:IV,and VI
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1502C/COC3-m- , , , .', .4 U y - E d, r, , ,,w.,'-- ~ , .- -- ., . +--
-1, SI-114.1, Attcchme:t 1 SURVEILLANCE R;visica 2
, INSTRUCTION LIST OF DRAWINGS - UNIT 1 Page 1 of 7
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ASME Section II Programs , I A. MAINTAIN a listleg of drawings for ISI emannications. B. UPDATE listing as necessary. C. ODTAIN concurrence from Site Qaality Manager or his designeo. SOM D. CONCUR with listing by signing below. ASME Sectjor. II Programs E. FORWARD to SPS for updating Table of Contents, etc. SPS T. FORWAED to DCRM. DCRM . G. DISTRIBUTE per SSP-2.7. N/4rJok Site Quality'M"anager/D'esignee i nhh2. Date F 1500C/COC3
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S!-114.1, Att: chm:nt 1 i SURVEILLANCE R: vision 2 i INSTRUCTION LIST OT DRAWINGS - UNIT 1 Page 2 of 7 l LIST OF DRAWINGE - tJNIT 1 i The drawings listed below are for the performance of 152 examinations. These I drawings are issued through Document Control and Records Management (DCRM). These drawings shall receive controlled distributloa. Individual copies may be obtained from DCRM. Drawino !!o. Elector Vessgl CHH-2341-B Reactor Vessel Stud Locations and Datails CIN-2343-D Reactor Vessel Seam Wo W CID4-23 58-A Reactor Vessel Closura Head CIN-2359-A Control Rod Drive Hoeging CIN-2360-A Reactor Vessel Inlet Nozzles CIN-2361-A Reactor Vessel Outlet Nozzles CIN-2651-C CRD, UP1 and Vent Pipe Penetrations ISI-0014-A Aux 111ary Head Adapter /UHI Cap Holds MSG-0004-C Reactor Vessel Bottom Head Penetrations Drawino.Not Pressurlser ISI-0394-C Pressuriser MSG-0002 B Pressuriser and Steam Generator Hanway Bolting MSG-0006-A Pressuriser Heater Penetrations Drawlno No. $113m Generatgn ISI-0397-C Vertical Steam Generators Tube Sheet Arrangement ISI 0399-C Steam Generator HSG-0002-B Pressuriser and Steam Generators Hanway Bolting MSG-0005-A Steam Generator /Teodwater Transition Spool Plece ISI-0357-A Steam Generator Teedwater Ring Header Drawino No. Heat Exchangers
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CID4-2 4 04 -A Residual Heat. Removal Heat Exchanger Channel Welds and Support ISI 0231-B Centrifugal Charging Pump Oil & Gear Cooler Support ISI-0235-A Safety Injection Pump 011 Cooler Support ISI-0232-B CCS Waste cas Compressor Heat. Exchanger Support ISI-0230-A CCS Gross Tailed fuel Detector Heat Exchanger Support ISI-0229-A CCS Positive Displacement Pump 011 Cooler Support ISI-0237-A CCS Seal Water Heat Exchanger Support ISI 0233-B Centrifugal Charging Pump Hechanical Seal Cooler Support 1500C/C0C3
i 81-114.1, Attachmsnt I ! SURVE!LLANCE R3 vision 3 ! l INSTRUCTION LIST 07 ORAWINGS - UNIT 1 page 3 of 7 LIST OF DPAWINGS - UNIT 1 r i DIAYI.DU FOA lital E2 changers (Continued)
\
ISI-0234-C RHN pump Seal Cooler Suppott ISI-0236-A Safety Injection Pump Seal Cooler Support ISI-021$-A Containment Spray Heat Exchanger Support ' ISI-0226-B Cau Stripper & Boric Acid Evaporator Package Support 1 ISI-0216-A Hon-Regenerativo Letdown Heat Exchanger Support
- ISI-0284-B Component Cooling Heat Exchanger ISI-0285-A Essential Raw Cooling Water Strainer Support 151-0287-8 Spent Fuel pit Heat Exchanger .
ISI-0290-B RHR Heat Exchanger Secondary Side Support Drawino No. Pipina and Valve Held Isomettles ' CHH-2333-B Reactor Coolant Pipjng (Main Loops) CEM-2333-C Safety Injection System ISI-0369-C Reactor Coolant System-CKH-2335-C Chemical and Volume Control System < CKH-2336-C Residual Heat Removal System CEM-2338-C Seal Water Injection (Chemical and Volume ; Control System) CHH-2339-C Feedwater System CHH-2340-C Main Steam System s CKH-2422-C Containment Spray System Class 1 and 2 Pipino and Valyg Drawino No. Support Drawingg ISI-0370-C Reactor Coolant System CEH-2433-C Chemical and Volume Control System CEM-2434-C Seal Water Injection (Chemical and Volume Control) CKH-2435-C Residual Heat Removal System CHH 2436-C Safety Injection System CKH-2438-C Main Steam System CKH-2439-C Feedwater System CKH-2440-C Containment Spray System ISI-0303-C Reactor Coolant System Main Loop Support Locations l l-l l- I 1500C/C0C3' l l
SI-114.1, Attachm3nt 1 SURVEILLANCE Revision 2 INSTRUCTIDH LIST OF DRAWINGS - UNIT 1 Page 4 of 7 M ST or DRAW 1NCS U}llI_1 Class 3 Pipino and valge Drawina No. Eupport Drnwinga. ISI-0113-C Avrillary Toedwster System ISI-0123-C Essential Raw Cooling Water System ISI-0126-C Component Coollag Water System ISI 0127-C Tuol Pool Cooling System ISI-0283-A Essential Raw Cooling Water System Diesel Generator Support Detail Drawina No. Punos - CIIM-2 67 5-B Reactor Coolant Pump Main Tiange and Lower Seal House Bolt Pattern HSO-0003-B Reactor Coolant Pump Casing Weld ISI-0325-B Reactor Coolant Pump Support ISI-0305-B Reactor Coolant Pump Motor Flywheel Examination 181-0353-B RHR Pump Support Locations ISI-0238-A CCS Thermal Barrier Booster Pump Support ISI-02$6-B Turbine Driven Auxiliary Teedwater Pump Support ISI-0262-B Hotor Driven Auxiliary Teedwater Pump Support ISI-0281-A Component Cooling Water Pump Support 151-0286-B ERCH Pump Support 1S1-0288-8 Spent ruel Pump Support ISI-0296-B ERCH Screen Wash Support Drawing..Nni Tanks ISI-0069-A Centrifugal Charging Pump Tank (Tormerly BIT Tank) ISI-0227-B Component Cooling Surge Tank Drawina N2A B11CA11eneous ISI-0403-A Reactor Coolant Pump Flywheel Schedule ICI-0404-A Component Support Acceptance Ranges ISI-0402-A Valve Internal Examinations 1 1500C/COC3~
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$1-114.1, Attochment 1 SURVEILLANCE Revision 2 INSTRUCTION LIST OF DRAW! HGS - UNIT 1 Page 5 of 7 LIII.DI ,QPAMINCL ASMILStetion XI B Vndart_ R CIA 111M cA119h AI.DY1ESA ;
Dravino No, 17H600-3-161 Hechanical Instruments and Controls 17H600-6-ISI Hechanical Instruments and Controls 17H600-13-ISI Hechanical Instruments and Controls , 47W600-26-ISI Mechanical !ustruments and Controls 1,2-47W600-27-ISI Mechanical Instruments and Controls 1-47W600-28-ISI Mechanical Instruments and Controls 2 47H600-28-ISI Mechanical Instruments and Controls 47W600-29-ISI Mechanical Instruments and Controls 47W600-30-ISI Mechanical Instruments and Controls 47W600-31-ISI Hechanical Instruments and Controls 47H600-32-ISI Mechanical Instruments and Controls 47W600-3 4 -I SI Mechanical Instruments and Controls 47H600-35-ISI Mechanical Instruments and Controls 47W600-62-ISI Mechanical Instruments and Controls 47H600-64-ISI Hochanical Instruments and Controls 47W600-65-ISI Mechanical Instruments and Controls 47W600-75-ISI Hochanical Instruments and Controls 47W600-80-ISI Hechanical Instruments and Controls 47H600-82-ISI Mechanical Instruments and Controls 47W600-88-ISI Hochanical Instruments and Controls , 47H600-92-ISI Hochanical Instruments and Controls 47H600-93-ISI Mechanical Instruments and Controls 47W600-102-ISI Mechanical Instruments and Controls 47W600-113-ISI Hechanical Instruments and Controls 47W600-114-ISI Hochanical Instruments and Controls 47H600-115-ISI Mechanical Instruments and Controls 47H600-116-ISI Mechanical Instruments and Controls 47W600-117-ISI Hechanical Instruments and Controls 47H600-118-ISI Mechanical Instruments and Controls 47W600-128-ISI Hechanical Instruments and Controls 47W600-129-ISI Mechanical Instruments and Controls 47H600-130-ISI Mechanical' Instruments and Controls ' 47W600-131-ISI Mechanical Instruments and controls 47H600-132-ISI Mechanical Instruments and Controls 47W600-134-ISI Mechanical Instruments and Controls 47W600-136-ISI Mechanical Instruments and Controls -t 47W600-137-ISI Mechanical Instruments and Controls - 47W600-142-ISI Mechanical Instruments and Controls ' 47W600-143-ISI Mechanical Instruments and Controls 47W600-144-ISI Mechanical Instruments and Controls 47W600-152-ISI Hechanical Instruments and Controls 47W600-154-ISI Mechanical Instruments and Controls 47H600-159-ISI Mechanical Instruments and Controls 47W600-163-ISI Hechanical Instruments and Controls 47W600-164-ISI Mechanical Instruments and Controls 47W600-165-ISI Mechanical Instruments and controls-47H600-167-ISI- Mechanical' Instruments and Controls ; 1500C/COC3
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SI-114.1, Attactanent 1 SURVEILLANCE Revision 2 INSTRUCTION LIST OF DRAWINGS - UNIT 1 Page 6 of.7 LIST OF DRAWIROS KSMS gegtinn.,%L_Roundary Classiflg glon Drevinga e f1LLlh e? V ' 168-181 Mechanical Instruments and Controls ,, 4 M *u-169-ISI Mechanical Instruments and Controls 1,5-47W600-171-ISI Mechanical Instruments and Controls M~ q ' 47H600-172-ISI Mechanical Ir.struments and Controls 47W600-174-ISI Mechanical Instruments and Controla-47H600-17 5-ISI Mechanical Instruments and Controlo 47W600-181-ISI Mechanical Instruments and Controls 47W600-200-ISI Mechanical Instruments and Concrols 47H600-227-ISI Hochanical Instruments and Controls 47H600-228-ISI Hechanical Instruments and Controls 47H600-241-ISI Mechanical Instrament- and Controls 47H600-244-ISI Mechanical Instrument. and Controls 47H600-276-ISI Mechanical Instr unents and Cont rola 47W600-279-ISI Hechanical Instruments and Cont .ls 47W600-285-ISI Machanical In6truments and Controls 47W600-286-ISI Mechanical Instruments and Controla 47W600-287-ISI Hechanien1 Instruments and Controls 47W600-2 89-ISI Mechanical Instruments and Controla 47W600-294-ISI H6chanical Instruments and Controla 47F600-1148-ISI Mechanical Instruments and Controls p' 47A625-1-IGI Radiation Sampling System 4 */W625-2-ISI Radiation Sampling System 47W625-3-ISI Radiation Sampling System 47W625-4-ISI Radiation Sampling Systeat 47W62 5-7-ISI Radiation Sampling System 47W625-15-ISI Radiation Sampling System 1,2-47W801-1-ISI Main and R-Feat Steam 1,2-47W801-2-ISI Steam Gener.cor Blowdown Systmn 1,2-47WB03-1-ISI Feedwater 1,2-47H803-2-ISI Auxiliary Feed- %* a. stem 1,2-47W803-3-ISI Auxiliary Feeds w ' g em 1-47H809-1-ISI Chemical and Voluu Conttal System 2-47W809-1-ISI Chemical and Volums Control System 1,2-47W809-2-IGI CVCS Chemical Control 1,2-47W809-3-ISI CVCS 1,2-47W809-4-ISI CVCS 1,2-47h8.9-5-ISI CVCS Chemical Control 1,2-47W809-7-ISI Flood Mode Boration Makeup System 1,2-47W810-1-ISI Residual Heat Removal System 1-47W811-1-ISI Safety Injection System 2-47H811-1-ISI Safety Injection System 1-47W811-2-ISI SIS Upper-Head Injection System 2-$7H811-2-ISI SIS Upper-Head Injection System 1,2-47W8'.2-1-ISI Containment Spray System 1,2-47Hf.13-1-ISI Reactor Coolant System 1,2-47W819-1-ISI Primary Hater 1500C/COC3
,_m_ _ _ _ _ - _ _ - - - - - ---- - ~ - - ~ ^ - - - - " - - - '^
4 . SI-114.1, Att: chm:st-1 .,
. ,EILLANCE Revision 2 1hSTRUCTION LIST OF DRAWINGS - UNIT 1 Page 7 of 7 LIST OF DRAWINGS ASME sention XI Boundary classiflention Drawings
- b Drawino No. ,
c 1,2-47W830-1-ISI Waste Disposal System 1,2-47W832-3-ISI Fixe 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 1,2-47W845-4-ISI Essential Raw Cooling Water System 1,2-47W845-5-ISI Essential Raw Cooling Water System 1,2 47W845-6.ISI Essential Raw Cooling Water System- , 1,2-47WB50-10-ISI Fire Protection 1,2-47W851-1-ISI Floor and Equipment Drains 1,2-47W855-1-ISI Fuel Pool Cooling and Cleaning System 1,2-47W856-1-ISI Demineralized Water-and Cask Decon System 1,2-47W859-1-ISI Component Cooling System 1,2-47W859-1-1-ISI Component Cooling System 1-47W859-2-ISI Component Cooling System 2-47W859-3-ISI Component Cooling System 1,2-47H859-4-ISI Component Cooling System 1,2-47W860-1-ISI Sodium I?rpochlorite System , 1,2-47W862-1-ISI Steam Generator Layup Water treatment ' 1,2-47W865-5-ISI Air-Conditioning Chill Water 1500C/COC3
i SI-114.1,' Attachment 2
-SURVEILLANCE Revision 3 VALVE 7 ABLES Page -1_' of . 8.
INSTRUCTION ASME Section II Programs A. MAINTAIH a listing of valves requiring ISI examinations. B. UPDATE listing as necessary. C. OBTAIN concurrence from Site Quality Manager or his designee. SQM 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. W / l3 / h 3- ' Site Quafit"y Manager / Designee D a'te 1501C/COC3
ATTACHMENT 2 TABLE 1 Class 1 Valve Information Valve Code Valve Piping Valve Valve Valve Group ISI Dwg No Vendor w ot No. Class Cat. Material Valve Forging / System Sire Twee Act No. (Veld Man) Dwo No. Vendor Soec. Function Castine @$. H <: 63-560 23 et 1 AC-Act SIS 10* Ck SA 2 Darling 63-561 1 AC-Act SIS 10" Ck SA 2 C % 2333-C 94-12892 C % 2333-C 94-12892 Darling ASTM AS16I ASTM A516I PSIY PSIV N5-63-562 1 AC-Act SIS 10" Ck SA 2 d C* 63-563 AC-Act SIS C h 2333-C 94-12892 Darling ASTM A516I PSIV o E. 1 10" Ck SA 2 C h 2333-C 94-12892 Darling ASTM A516I PSIV 63-622 63-623 1 AC-Act SIS AC-Act SIS 10* Ck SA 2 CHM-2333-C 94-12892 Darling ASTM A516I PSIV WQ 1 10" Ck SA 2 CHM-2333-C 94-12892 Darling 63-624- 1 AC-Act SIS ASTM A516I PSIV 10" Ck SA 2 C h 2333-C 94-12892 Darling
'63-525 ASTM A516I PSIV 1 AC-Act SIS 10" Ck SA 2 CHM-2333-C 94-12892 Darling ASTM A5161 PSIV 63-640 1 'AC-Act SIS /RHR B" Ck 2 63-643 SA C % 2336-C 94-12892 Darling ASTM A516I PSIV 1 AC-Act SIS /RHR 8" Ck SA 2 CHM-2336-C 94-12892 Darling ASTM A516I PSIV 63-558 1 AC-Act SIS 6" Ck SA 3 C E 2333-C 78704 63-559 Velan ASTM A182 PSIV Forging
^1 AC-Act SIS 6" Ck SA 3 CHM-2333-C 78704 Velan 63-632 1 AC-Act SIS 6" ASTM A182 PSIV Forging Ck SA 3 C % 2333-C 78704 Velan ASTM A132 PSIV forging 63-633 1 AC-Act SIS 6" Ck SA 3 OM-2333-C 78704 Velan 63-634 1 AC-Act SIS 6" Ck ASTM A182 PSIV Forging SA 3 CHM-2333-C 78704 Velan ASTM A182 PSIV Forging 63-635 1 AC-Act SIS 6" Ck SA 3 C%2333-C 78704 Yelan 4 63-641 1 AC-Act SIS /RHR 6" Ck ASTM A182 PSIV Forging . p*
SA 3 C % 2336-C 78704 Velan 63-644' 1 AC-Act SIS /RHR 6" ASTM A182 PSIV Forging Ck SA 3 CHM-2336-C 78704 Yelan ASTM A182 PSIV Forging es 68-563 1 C-Act RCS 6" Re1 SA 4 ISI-0369-C H51688 Crosby ASTM A182/ See N A3512 Note 2 68-564 1 C-Act RCS 6" Re1 SA 4 ISI-0369-C H51688 Crosby ASIM AlB2/ See 5 et 68-565 A3512 Note 2 0' 1 C-Act RCS 6" Re1 SA 4 ISI-0369-C H51688 Crosby ASTM A182/ See FCV 74-1 1 A3512 Note 2 A-Act RHR 14' Gate MD 5 C h 2336-C E-1-144831 Copes-Vulcan ASTM A182 FCV 74-2 1 A-Act 14" PSIV Forging RHR Gate 4 5 C % 2336-C E-1-144831 Copes-Vulcan ASTM A182 PSIV Forging NOTES: 1. Seal plate manufactured to ASTM A240 F3041 bonnet manufactured to ASTM A516.
- 2. Nozzle manufactured to ASTM A182 F316 - Forging, Body manufactured to ASTM A351 CR8M - Casting.
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ATTACMENT 2 TABLE 2 C1 css 1 V;.1va Ixf;rmation Stre V1v wm SYS Viv No. (In) Type ~ ISI DWG No. Valve Bolting Body E$ Vendor Vendor Dwo No. <=2" > 2" Velds IA yg CVC 62-560 2 CKV CHM-2338-C/1 Edward CVC 62-561-- 2 CKV C M-2338-C/2 Edward D-464529 R5 D-464529 R5 N/A N/A Hone N/A b N/A N/A None N/A CVC 62-562.- 2 CKV C % 2338-C/4 Edward CVC 62-563 2 CKV CHM-2338-C/3 Edwarif 0-464529 R5 D-464529 R5 N/A N/A N/A None N/A Ob CVC 62-564 2 GATE C % 2338-C/1 N/A None N/A *Q Edward D-464532 R5 N/A N/A None N/A CVC 62-565 -2 GATE C h 2338-C/2 Edward D-464532 R5 N/A N/A None N/A Cyc 62-566 2 GATE C%2338-C/4 Edward D-464532 R5 N/A N/A None N/A CVC 62-567 2 GATE CHM-2338-C/3 Edward 0-464532 R5 N/A CVC 62-576 N/A None N/A 2 CKV C W 2338-C/1 Edward D-464529 R5 N/A N/A None N/A CVC 62-577 2 CKY C % 2338-C/2 Edward D-464529 R5 N/A CVC 62-578 N/A None N/A 2 CKV C % 2338-C/3 Edward D-464529 R5 N/A N/A None N/A CVC 62-579 2 CKY CHM-2338-C/4 Edward D 464529 R5 N/A N/A None N/A CVC 62-659I 3 CKV C W 2335-C/1 Borg-Wagner 80290 5/16" CVC 62-660I 3 CKV C % 2335-C/1 N/A None N/A Borg-Wagner 80290 5/16" N/A None N/A CVC' 62-661 2 CKY C h 2335-C/1 Edward C-464529 R5 N/A
. CVC 62-716I N/A None N/A 3 CKV -C % 2335-C/1 Borg-Vagner 80290 5/16" N/A None N/A CVC 62-717I 3 CKV C % 2335-C/1 Borg-Wagner 80290 5/16" <
CVC 68-580 3 GATE C h 2335-C/2 Veland N/A None N/A > 13920 N/A N/A Mone N/A CVC FCV-62-691 3 GATE OtM-2335-C/2 Masonellan/Woethington CPI 1855 A84257 7/8" N/A None N/A E M CVC FCV-62-70I 3 GATE CHM-2335-C/2' Masonellan/Worthington CPI 1855. A84757 7/8" N/A None N/A g CVC FCV-62-84I 2 GATE CHM-2335-C/1 Masonellan A8474. A8475 7/8" N/A None N/A P RCS 68-549 2 GATE ISI-0369-C/1 Edward 0-464532 N/A N/A None N/A RCS 68-550- 2 GATE ISI-0369-C/1 Edward D-464532 N/A E-RCS 68-553 N/A None N/A M 2 GATE 151-0369-C/1 Edward D-464532 N/A N/A None N/A " RCS 68-554 2 GATE ISI-0369-C/1' Edward D-464532 N/A N/A Mone N/A RCS 68-557 2 - GATE ISI-0369-C/1 Edward D-464532 N/A N/A None N/A RCS 68-558 2 GATE ISI-0369-C/1 Edward D-464532 N/A N/4 None N/A RCS 68-563 6 RELF ISI-0369-C/3 Crosby H-51688 1" N/A None N/A RCS 68-564 6 RELF 15I-0369-C/3 Crosby H-51688 1" N/A None N/A RC5 68-565 6 RELF ISI-0369-C/3 Crosby H-51688 1" N/A None N/A RCS 68-581 2 GATE ISI-0369-C/1 Edward D-464532 N/A RCS 68-582 N/A None N/A 2 GATE ISI-0369-C/1 Edward D-464532 N/A N/A None N/A
- 1. Exempt from Examination Requirements of Category 8-G-2 in accordance with Code Case N-426 Ye *o e
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yq ATTAOf9ENT 2 zj i TABLE 2 (Continued) d Class 1 valv3 Inftrmation
- i. l Site Viv Mm SYS Vlv No. (In) Tvoe ISI DWG No. Vender Valve Bolting Body 'E @
Vendor Dwo No. > 2* (.2" Velds IA gy Rr5 FCV-68-3321 ' 3 GATE ISI-0369-C/3 Velan RCS FCV-68-3331 3 GATE ISI-0369-C/3 Velan 88406 88406 3/4* 3/4" N/A hone N/A bN RCS PCV-68-3400) 4 BALL ISI-0359-C/2 Fisher N/A None N/A U RCS PCV-68-340A 3 GLB ISI-0369-C/3 Target Rock 50A2159 7/8* N/A None N/A 'o{- ' RCS PCV-68-3408I 4 , BALL ISI-0369-C/2 Fisher 1052020-3 50A2159 N/A 7/8" N/A N/A None Mone N/A N/A
*O RCS PCV-68-334 3 GLB ISI-0369-C/3 Target Rock 1052020-3 N/A N/A None N/A RHR 63-543 2 CKV C h 2336-C/6 Edward C-464529 R5 RHR .63-545 N/A N/A None N/A 2 CKY CHM-2336-C/6 Edward C-464529 R5 N/A N/A None N/A RHR 63-640 8 CKV C % 2336-C/6 Anchor / Darling 12892 RHR 63-641 1 3/8" N/A None N/A I
6 CKV CHM-2336-C/6 Velan 78704 1 1/4" N/A None 't/A RHR 643 8 CKV C % 2336-C/6 Anchor / Darling 94-12892 RHR 63-644- 1 3/8" N/A None N/A 6 CKV C % 2336-C/6 - Velan 78704 1 1/4* N/A None N/A' RHR- FCV-74-1 14 GATE CHM-2336-C/1 Cepes-Vulcan E-1-144831 R4 RHR FCV-74-2 1 3/4" N/A None N/A 14 GATE C W 2336-C/1 Cepes-Vulcan E-1-144831 R4 1 3/4" N/A None N/A SIS 63-547 2 CKV C W 2333-Cn Edward C-464529 R5 N/A SIS 63-549 2 CKV C % 2333-C/7 Edward N/A None N/A C-464529 R5 N/A N/A None N/A <. SIS 63-551 2 CKV C % 2333-C/9 Edward C-464529 R5 N/A N/A None N/A SIS 63-553 2 CKV C W 2333-C/10 Edward C-464529 R5 N/A N/A None N/A g SIS 63-555 2 CKV C h 2333-C/10 Edward C-454529 R5 N/A N/A None N/A 4 M SIS 63-557 2 CKV C W 2333-C/9 Edward C-464529 R5 N/A SIS 63-558 N/A None N/A q 6 CKV C%2333-Cn Velan 78704 1 1/4" SIS 63-559 6 CKV CHM-2333-C/7 Velan 78704 1 1/4" N/A None N/A N/A None N/A g SIS .63-560 10 CKV C 6 2333-C/9 Anchor / Darling e SIS 63-561 94-12892 1 3/8" N/A None N/A M 10 CKV C h 2333-C/10 Anchor / Darling 94-12892 1 3/8" N/A None N/A " SIS 63-562 10 CKV C % 2333-C/10 Anchor / Darling 94-12892 1 3/8" N/A None N/A SIS 63-563 10 CKV CHM-2333-C/9 Anchor / Darling 94-12892 1 3/8" N/A None N/A SIS 63-581I 3 CKV C W 2333-C/1 Velan . 78409 3/4" N/A None N/A SIS 63-592 1.5 GATE CHM-2313-C/1 Rockwell International D-478072 N/A N/A None N/A SIS 63-583 1.5 GATE C W 2333-C/2 Rockwell International D-478072 N/A SIS 63-584 N/A None id/A 1.5 GATE C W 2333-C/2 Rockwell International D-478072 N/A N/A None N/A
- 1. Enempt from Enamination Requirements of Category B-G-2 in accordance with Code Cass N-426.
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ATTACHMENT 2 TABLE 2 (Continued) Class 1 valve Information , Site V1v Mm SYS' Viv No. (In1 Tvee ISI DWG No. Valve Bolting Body E@ Vendor Vendor (W No. <=2" > 2" Velds IA - .y g SIS 63-585 1.5 GATE CHM-2333-C/1 Rockwell International D-478072 . N/A cw. SIS 63-586 N/A None N/A' O t* 1.5 CXV ' CHM-2333-C/1 Edward C-465347 R2 SIS 63-587 1.5 CKV Ch2333-C/2 Edward C-465347 R2-N/A N/A N/A None N/A N/A None N/A U" O SIS 589 1.5 CXV C h 2333-C/1 . Edward SIS 63-588 1.5 CKV C W 2333-C/2 Edward C-465347 R2 N/A N/A' None N/A '*O' ' SIS 63-622 C-465347 R2 N/A' N/A None N/A 10 CKV C % 2333-C/9 Anchor / Darling 94-12892 1 3/8"N/A None N/A SIS-63-623 10 CKV Oei-2333-C/10 Anchor / Darling 94-12892 1 3/8" SIS 63-624 N/A None N/A 10 CKV C E 2333-C/10 Anchor / Darling 94-12892 1 3/8" N/A None N/A SIS 63-625- 10 CKV C % 2333-C/9 Anchor / Darling 94-12892 1 3/8"
. SIS 63-632 N/A Mone N/A 6 'CKV CHM-2333-C/10 Velan 78704 1 1/4" N/A- None' N/A SIS 63-633 -6 CKV C W 2333-C/9 Velan 78704 1 1/4*
SIS 63-634 N/A None N/A 6 CKV C h 2333-C/10 Velan 78704 1 1/4" N/A None N/A
"$15 63-635' 6 CKV C % 2333-C/9 Velan 78704 1 1/4" N/A None N/A
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y-ATTAtiftENT 2 TABLE 3 Class 2 Valve Information V1v m Sire valve Bolting Body SYS Viv No. (In1 Tyce IST DWG No. Vendor Vendor Dwo No. <=2" > 2* Velds IA
+4 < -
mM CS FCV-72-20 Aloyco CS FCV-72-23 12 CA1E CHW2422-C/1 12 GATE C5N-2422-C/1 Aloyco E-48840 E-48840 Yes N/A None N/A bN N 3-508 Yes N/A None N/A l4, F 16 CKV CHS2339-C/2 Valworth A-11332-432A 1 3/4" N/A None N/A o5 N 3-509 16 CKY CHN2339-C/2 Walworth A-11332- 532A 1 3/4" N/A Hone N/A N 3-510 16 CKV C h 2339-C/1 Valworth A-11332-4 32A 1 3/4" N/A None N/A *Q
~N 3-511 16 CKV CHH-2339-C/1 Walworth A-11332-&32A 1 3/4" N FCV-3-033 N/A None N/A 18 GATE CHM-2339-C/1 Walworth A-6614-4150 1 1/2" N/A None N/A N FCV-3-047 18 GATE CHM-2339-C/2 Valworth A-6614-M-150 1 1/2" N FCV-3-087- 18; GATE C h 2339-C/2 N/A None N/A Walworth A-6614-M-150 1 1/2* N/A' None N/A N FCV-3-100 18 GATE CtM-2339-C/1 WalwortF - A-6614-4150 1 1/2" N/A None N/A MS 1-512 6 SAF CHM-2340-C/2 Crosby 1 3/8" MS 1-513 6- SAF C h 2340-C/2 Crosby H-55095 N/A None .N/A 1-514 H-55095 1 3/8* N/A None N/A
' MS 6 SAF C W 2340-C/2 Crosby MS 1-515 6 SAF C h 2340-C/2 Crosby H-55095 1 3/8* .N/A None N/A W55095 1 3/8" N/A None N/A MS 1-516 6 SAF CHM-2340-C/2 Crosby H-55095 1 3/8" N/A None N/A MS 1-517 6 SAF CHS2340-C/2 Crosby H-55095 1 3/8" N/A None N/A MS 1-518 6 SAF CHS2340-C/2 Crosby 4 H-55095 1 3/8" N/A None N/A g_
MS 1-519 6 SAF C h 2340-C/2 Crosby H-55095 1 3/8* * 'A None N/A MS 1-520 6 SAF C h 2340-C/2 Crosby 4 W55095 1 3/8" N/A None N/A M' MS 521 6 SAF C h 2340-C/2 Crosby H-55095 1 3/8" N/A None N/A 1-522 6 g. MS SAF C h 2340-C/1 Crosby H-55095 1 3/8" N/A- None N/A > MS 1-523 '6 SAF CHM-2340-C/1 Crosby H-55095 1 3/8" N/A- None N/A MS 1-524 6 SAF- CW2340-C/1 Crosby H-55095 1 3/8* N/A' None N/A E M MS 1-525 6 SAF C h 2340-C/1 Crosby W55095 1 3/8" N/A None N/A " HS 1-526 6 SAF C h 2340-C/1 Crosby W55095 1 3/8" N/A None N/A MS 1-527 6 SAF C W 2340-C/1 Crosby W55095 1 3/8" N/A None N/A HS 1-528 6 SAF . CHN2340-C/1 . Crosby H-55095 1 3/8" N/A None N/A MS 1-529 6 SAF C h 2340-C/1 Crosby W55095 1 3/8" N/A- None N/A MS 1-530 6 SAF C h 2340-C/1 Crosby W55095 1 3/8" N/A None N/A 55" 1 li. L - 8 ." % g o8L A "' 8 #
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ATTACHMENT 2 TABLE 3 (Continued) Class 2 Valve Information Size V1v wm' SYS Viv No. fin) Tvee ISI ING Ns. Vendor Vendor Dwo No. Valve Bolting Body
<=2" > 2" Veldt lA gg H<
wM MS 1-531 6 SAF C % 2340-C/I Crosby MS~ 1-619 6 GATE C % 2340-C/1 Valworth H-55095 A-6609-M-1288 1 3/8" N/A None N/A b5 MS '1-620 6 GATE C % 2340-C/2 Walworth A-6609-M-1288' 7/8" 7/8" N/A N/A None None N/A N/A d" o5 MS ;1-621 6 GATE C h 2340-C/2 Va1 worth MS 1-622 A-6609-M-1288 7/8" N/A None N/A EQ 6 GATE C h 2340-C/1 Walworth A-6609-M-1288 7/8" N/A None N/A
' MS FCV-1-04 32 GATE C h 2340-C/1 Atwood and Morrill Co . 21245-H 2" MS FCV-1-11 N/A Hone N/A 32 GATE C % 2340-C/2 Atwood and Morrill Co 21245-H 2" N/A None N/A MS FCV-1-22 32 GATE C h 2340-C/2 Atwood and Merrill Co 21245-H 2" MS FCV-1-29 N/A Mone N/A 32 GATE C W 2340-C/1 Atwood and Morrill Co .21245-H 2* N/A None N/A MS PCV-1-05' 6 GATE C % 2340-C/1 Copes-Vulcan 8-149093 R7 Yes N/A None N/A MS PCV-1-12 6 GATE C%2340-C/2 Copes-Volcan 8-149093 R7 MS PCV-1-23 Yes N/A Mene N/A 6 GATE C h 2340-C/2. Copes-Vulcan 8-149093 R7 Yes N/A None N/A MS PCV-1-30 6 GATE C % 2340-C/1 Copes-Vulcan 8-149093 R7 Yes N/A None N/A RHR 74-514 8 CKV C h 2336-C/3- Crane K-7422 7/8" RHR 74-515. N/A None N/A 8 CKV C W 2336-C/3 Crane K-7422 7/8" N/A None N/A RHR' 74-520 8 GATE C % 2336-C/3 Aloyco E-47381 3/4" RHR 74-521 N/A None N/A <
8 GATE Ch2336-C/3 Aloyco E-47381 3/4" N/A None N/A RHR 524 8 GATE CHM-2336-C/3 Aloyco E-47381 3/4" N/A None N/A g RHR 74-525 8 GATE CHM-2336-C/3 Aloyco E-47381 3/4" N/A None N/A < M. RHR FCV-63-172 12 GATE C E 2336-C/4 Velan 88907-3 1 7/8" N/A None N/A q RHR FCV-63-72 18 GATE CHM-2336-C/2' Anchor / Darling 94-13300 N/A None N/A RHR FCV-63-73 18 GATC CHM-2336-C/2 Anchor / Darling 94-13300 l'1/4" 1 1/4" N/A None N/A g RHR FCV-74-03 p 14 GATE C h 2336-C/5 Anchor / Darling 94-13298 1 1/8" N/A' None N/A M RHR FCV-74-16 8 BUTF C%2336-C/3 Fisher Governor Co F-41304 5/8" N/A None N/A 8'8 RHR FCV-74-21 14 GATE CHM-2336-C/5 Anchor / Darling 94-13298 1 1/8" .N/A RHR FCV-74-28 None N/A 8 BUTF CHM-2336-C/3 Fisher Governor Co F-41304 5/8* N/A None N/A RHR FCV-74-32 8 BUTF CHM-2336-C/3 Fisher Governor Co F-41304 5/8" N/A- None N/A RHR TCV-74-33 8 GLOS C h 2336-C/3 Anchor / Darling 93-13435 3/4" N/A None N/A
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ATTAC m ENT 2 TABLE 3 (Continued) Class 2 Valve Information SIIe Viv MM Valve Bolting Body SYS Viv N3. (In) Tvee ISI DWG No. Vendor Vendor Dwe No. <=2= > 2* Welds IA 5$ yg RHR HCV-74-36 RHR HCV-74-37 8 GATE C%2336-C/3 8 GATE C % 2336-C/3 Anchor / Darling Anchor /Darilng 93-14074 93-13435
-3/4" 3/4" N/A None . N/A N/A None- N/A bb SIS 63-502 SIS FCV-63-01 12 CKV C h 2333-C/6 Aloyco D48376 K74221C 1" N/A None N/A Nh
'O~
16 CATE C h 2333-C/6 Crane K-7634-15.16 7/8" SIS FCV-63-08 8 GATE CHM-2333-C/6 Anchor / Darling 94-13295 7/8" N/A None C/A N/A None N/A
*O SIS FCV-63-11 8 GATE C h 2333-C/6 Anchor /Darllr.g 94-13295 7/8" N/A None ,N/A SIS FCV-63-118 10 GATE C % 2333-C/4 Velan 88926 R.01 1 3/8" N/A . None N/A SIS FCV-6347 10 GATE C % 2333-C/4 Velan 88976 R.01 1 3/8" SIS FCV-63-80 N/A None N/A 10 ' GATE C % 2333-C/5 Velan BS926 R.D1 1 3/8" N/A None NJ A SIS FCV-63-93 8- GATE C % 2333-C/3 Velan 88806-1 1 3/8" N/A SIS FCV-63-94 8 GATE C % 2333-C/3 None.. K/A
'Velan 88306-1 1 3/8" N/A None N/A SIS FCV-63-98 10 GATE C % 2313-C/5 Velan 88926 R.01 1 3/8" N/A None N/A SIS FCV-72-40 8 GATE C h 2333-C/6 Aloyco E-48836' Yes N/A Nene N/A
' SIS. FCV-72-41 8 GATE C h 2333-C/6 Aloyco 'E-48836 RHR FCV-74-35 Yes N/A None N/A 8 ' GATE Dei-2336-C/3 Anchor / Darling 93-13435 3/4" N/A None N/A RHR HCV-74-34 8 GATE CW2336-C/3 Anchor /Daritag 93-13435 3/4" N/A None N/A <
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SI-114.1, Attachment 3 SURVEILLANCE Revision 3 INSTRUCTION REQUESTS FOR RELIEF Page'l of 48
-ASME Section II Programs A. MAINTAIN a listing of Requests for Relief.
B. UPDATE listing as necessary. C. OBTAIN concurrence from Site Quality Manager or his designee. SOM ' D. CONCUR with listing by signing below. ASME Section XI Programs E. FORWARD to SPS for updating Table of Contents, etc. SPS
- F. FORWARD to DCRM.
DCRM ' G. DISTRIBUTE per SSP-2.7. J _/ El l @3-Site Quality Manager / Designee- Date 1503C/COC3
.e
SI-114.1, Attachment 3 SURVEILLANCE Revision 3 INSTRUCTION REQUESTS FOR RELIEF Page 2 of 48 REOUEST FOR RELIEF ISI-1 Components: Reactor coolant pumps (four per unit)~ , Class ASME Ccde Class 1 (Equivalent) y_H.nciltD Circulates reactor coolant. Inspection Requirement ASME Section XI, Table IWB-2500-1, examination category B-L-2, item no. B12.20, visual examination of pump internal pressure boundary surfaces. Basis for Relfelt In absence of required maintenance,-disassembly of a reactor coolant pump solely to perform a_ visual examination of internal surfaces is impractical. This would represent an unnecessary employee exposure to high radiation and contamination areas-and an excessive expense to TVA. Time required for this major-task of disassembly, examination, and reassembly would consume at least three weeks of 24,-hours-per-day work. Radiation dose rates of the pump exterior will average 100-300 mrem /hovr, and pump internal dose rates will-average 10-20 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 disassembled for maintenance during a 10-ycar interval, the visual examination performed will be representative of the pump condition for each unit. This would avoid unnecessary employee exposure to the high-radiation dose rates noted above.= We conclude that if one pump is disassembled for maintenance during the 10-year interval, the visual examination-performed satisfies examination category B-L-2 requirements for both units._ Disassembly of the pump solely for visual examination is impractical. (Continued) 1503C/COC3
SI-114.1, AttcchmInt 3 ' SURVEILLANCE R, vision 3 INSTRUCTION REQUESTS FOR RELIEF Page 3 of 48 PJQUEST FOR PELIEF ISI-1 (Continued) Alternate Inseection: The internal surfaces of the reactor coolant pump casing will be visually examined whenever the surfaces are made accessible when a pump is disassembled for maintenance purposes. If during the-10-year interval a pump from either unit is not d h assembled for maintent.nce, a pump from one unit shall be examined from the exterior. This shall be accomplished by ultrasonic thickness measurements of the pump casing. Safety Evaluation Summarve Request for Relief ISI-I has been approved with the following additional augmented requireme nts. (a) the required visual examinations are conducted under Category B-L-2 If a reactor coolant pump from one of two units is disassembled for maintenant:e; (b) If during the 10-year interval, a. pump from either unit is not disassembled for maintenance, a pump from one unit shall'be examined from the.exterlot by ultrasonic thickness measurements; (c) Visual oxumination of the pump casing for leakage is conducted in conjunction with system leakage and hydrostatic tests under Category B-P. 3 References Memorandum from F. J, Hebdon, NRC, to 0. D. Kingsley, TVA, dated Februery 7, 1991 (A02 910214 009). 8 1503C/COC3 l
._ __ _____-_-____.m. _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
SI- 114.1, Attachment 3 SURVEILLANCE INSTRUCTION Revision 3 REQUESTS FOR RELIEF Page 4 of 48 REQUEST FOR RELIEF ISI *z components: Valves exceeding 4-inch nominal-pipe size Cl as.s ASME Code Class 1 (Equivalent) Function: Variou% functions. d Inspection Recuirement: ACME Section XI, Table INB-2500-1, exsmination category B-H-2, item no. B12.40, visual examination of valve internal pressure boundary surfaces. Basis fer Relief: 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 at Sequoyah Nuclear Plant will operate under similar conditions. If a valve from one of the units is disassembled for maintenance within a 10-year interval, we feel that the visual examination perfor'med would be representative of both units and would be sufficient to satisfy the examination requirements for both units for that particular 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 is disassembled from either unit during the 10-year interval, . the visual examination performed satisfies examination category B-H-2 requirements for both units. Alternate Inspection: 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 disassembling 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 1 relief will be issued at that time. (Continued) 1503C/COC3
SI-114.1, Attachment 3 SURVEILLANCE Revision 3 INSTRUCTION REQUESTS FOR RELIEF ' Page 5 of 48 EEOUEST FOR RELIEP 15f-2 (Continued) Rafety Evaluation Summary Reguest for Relief ISI-2 has been approved with the following additional ' augmented requirements. (a) one comparable valve in cir.her unit is examined. If a certain type of valve is not examined at either unit, relief should be reguested on a case-by-case basis near_the end of the interval, (b) periodic inservice testing of the valves is conducted in accordance with INV, and (c) visual examination of the valves for leakage is conducted in conjunction with system leakage and hydrostatic tests under Category:B-P.
Reference:
Memorandum from F. J. Hebdon, NRC, to 0. D. Kingsley, TVA, dated February 7, 1991 (A02 910214 009). ob. o I l i 1503C/COC3
SI-114.1, Attachment 3 SURVEILLANCE Revision 3
-!NSTRUCTION REQUESTS FOR RELIEF Page 6 of 48 REOUEST FOR RELIEF ISI-3 "omponents: Pressure-retaining welds in piping Claan ASKM Code Class 1 and 2 (Equivalent)
Function: Pressure-retaining component. In.spection Requirement: ASME Section XI, Table IWB-2500-1, examination categories B-F (item no. B5.50), B-J (item nos. B9.10,-B9.20, and B9.30), and C-F (item nos. C5.10, C5.20, and C5.30), volumetric examination of longitudinal, circumferential, and pipe branch' connection welds. Basis for Relief: In some cases it will be impractical to inspect all welds from both sides, i.e., nonremovable hnnger interference or valve and pump casings adjoining the welds. These veldh will be noted on the ultrasonic examination data sheets. (See the attached listing) Alternate Insoection In addition to the visual examination performed during system leakage and hydrostatic pressure tests, a "best effort" ultrasonic examination will be performed. Where there is interference or problems from~one direction only, consideration will be given to perforening an angle beam examination for 2T + (greater than two wall thicknesses from one edge of weld) from the accessible side of the veld in order-to exsmine the entire weld cross-section. Safety Evaluation Summar_e v Request for Relief ISI-3 has been approved Jn the following manners
- Eram Cateoory B-F Approved with no additional augmented requirements.
BJ Approved with no additional augmented
- requirements
( C-F Relief was not necessary. References Memorandum from F. J. Uebdon, NRC, to 0. D. Kingsley, TVA, dated February 7, 1991 (A02 910214 009). l e l 1503C/COC3
7 S
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E" MOUEST FOR RELIEF ISI-3 4" w (Continued) o 1.2 3 4 5 6 7 WELD . CODE-9 CODE NUMBER QL, !!A_IL . .. NUMBER CCNF,
. DRAWING- Pl#. . SCAN / LIMITATIONS $ LAM REMARKS RHRF-125 BJ $$ CHM 2336 E/N 4/ No scan 831 No scan 4 due to nozzle geometry SHT*4 3/5:00-7:00 No scan 3 from 5:00-7:00 due to inner rad.
RCF-23 BJ: 'SS CHM 2334 E/SE L4/No scan 751 No scan 4 due to SE geometry se .
.SHid6 3/ Limited Scan 3 inner rad 4" pipe elbow FDSW-17A CF
$c Citt2339 - P/ PEN 3.5 &6/11:30,
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CS 961. No scan 3.5,&6 at 11:30,12:30, 5:30 SHT#2 12:30, 5:30, 6:30 6:30 due to lugs: No scan 4 due to N. H
'4/No scan penetration "
RCW SF CS/SS CHM 2363 N/SE 344/11mited SE 'SHT81-801 Scan 3&4 limited to 1/2 node due to - SE & norrie geometry 20% of weld not s scanned _, n. t-RCV .SF CS/SS CHM 2363 N/SE ' 344/14elted 80% Scan 3&4 Ilmited to 1/2 node due to SE SHT*1 SE & norrie geometry 20% of weld N s not scanned RHRF- BJ - $$" CHM 2336 V/E- 3/Nc scan 109 831 No scan 3 due to valve geometry SHT84 - ~4/5:00-7:00. No scan 4 from 5:00-7:00 due to
' inner rad. --
MSF-11 :CF 'CS -CHM 23407 N/E 3/No scan 991 No scan 3 due to nozzle geometry SHT*2< 4/270?,la' No scan 4 at 270* for 1" RC-3 BJ '$$ CHM 2333, E/SE 3/Mo scan 501 _ (Notn 8) No scan 3 due to nozzle -
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- p. geometry N' RC-151' .8J SC 0912333 - P/E- l 4/2:30 to 3:30 ' 921 (Note 8) No scan 4 from'2:30 to - '
g- SHT#1 3:30 due to permanent restraint 725' s n-jgg RCF-19 BJ .SC - O M2334 'V/E- '3/No s'can aw-831 -No scan.3 due to valve geometry w R w SHT#6 4/2:00-4:00.- No scan 4 from 2:00-4:00 due to of a_ w: i Inner rad. n -- n,, . , L* p.
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SI-114.1, Attachm3nt 3 SURVEILLANCE Rsvision 3 INSTRUCTION- REQUESTS FOR RELIEF Page 8 of 48 REOUEST POR RELIEP ISI-3 (Continued) NOTES: 1. LS following seam number indicates longitudinal seam.
- 2. SE following seam number indicates safe end weld.
- 3. Categories determined in accordance with ASME XI 77578.
- 4. P= Pipe, V= Valve, E= ELL, T= TEE, R= Reducer, F= Flange, N= Nozzle, Pen P= Penetration Process Pipe, Pen F= Penetration Flued Head, and SE= Safe End.
- 5. Scans 3 and 4 are perpendicular to circumferential welds. Scans 5:
and 6 are parallel to circumferential wolds. 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.1
- 7. Actual percentages indicate the approximate area of examination coverage obtained. .
- 8. Because of the attenuation resulting from inherent coarse grain structure in cast stainless steel the examination is limited to the 1/2V technique. Also physical restrictions prevent the exam from both sides of the weld.
- 9. Detail description of limitations are noted.
1503C/COC3
SI-114.1, Attcchmsnt 3
- SURVEILLANCE - Revision 3 INSTRUCTION REQUESTS FOR RELIEF Page 9 of 48 REQUEST FOR RELIEF ISI-4 C2mPantnt Steam generator (four per unit). j CIAAA: ASME Code Class 2 (Equivalent)
Inspection Requirement: ASME Section XI, Table IWB-2500-1, examination category C-A, item no. C1.10, volumetric examination of circumferential shell welds. Basis for Relieft One circumferential shell weld on each generator is inaccessible due to the upper steam generator support brackets (weld Nos. SGW-DI, SCW-D2, SGW-D3, and SGW-D4). See 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 inspection and during the four inservice inspection intervals in accordance with IRC-2411 and Table IWC-2500-1. ; Alternate Inspection: None. Egfety Evaluation Summary: Request for Relief ISI-4 has been approved with no additional augmented requirements. References Memorandum from F. J. Hebdon, NRC, to 0. D. Kingsley, TVA, dated I February 7, 1991 (A02 910214 009). ' Memorandum from F. J. Hebdon, NRC, to D. A. Nauman, TVA, dated October 21, 1991 (A02 911024 003). 4 1503C/COC3 I
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. SI-114.1, Attachment 3 SUR\EILLANCE' Revision 5 INSTkUCTION- REQUESTS FOR RELIEF Page 10 of 48 R
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SI-114.1, Att: chm:nt 3 - SURVEILLANCE' Revision 3 INSTRUCTION, REQUESTS FOR RELIEF Page 12 of 48-4v m cewt hren y . I
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SI-114.1, Attachment 3' SURVEILLANCE Revision 3 INSTRUCTION REQUESTS FOR RELIEF Page-13 of 48 REOUEST FOR RELIEF ISI-5 Comoonent Reactor Pressure Vessel Class: ASMI Code Class 1 (Equivalent) Inspection Requirementst ASME Section XI, Table IWB-2500-1, examination category B-A, item no.-Bl.20, 100-percent preservice volumetric examination of lower head dollar veld, under conditions and with equip.nent and techniques equivalent to those expected to be employed during inservice inspection. Basis for Relief: TVA will employ automated remote inspection devices to examine most of the reactor vessel-welds. These-examinations will be conducted from the vessel laside diameter. However, the lower head weld on each reactor pressure vessel is partially inaccessible for examination from the vessel inside diameter due to instrumentation tubes which penetrate the lower head (weld No. WO1 see attached drawings). Portions of the weld can be examined from one side (as permitted by T-441.4, Article 4 of Section XI) and will include 100 percent of the examination volume in accordance with INB-3511.1 of Section V. These portions of the weld will be reexamined during the inservice intervals in accordance with examination category B-A of Table IWB-2500-1. Alternate _Inspectient A 100-percent preservice examination of the veld will
'be' conducted from the vessel outside diameter. This will be accomplished by performance of a manual ultrasonic examination. A remote ultrasonic examination will be conducted from the vessel inside diameter on all accessible areas of the weld.-
Safety Evaluation Summarvt 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 910214 009). s 1503C/COC3
' SURVEILLMICE-St-114.1, AttacFaent 3 INSTRUCTION Revision 3 REQUESTS FOR RELIEF Page 14 of 48
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SI-114.1,-Attachm2nt 3 SURVEILLANCE- Revision 3 INSTRUCTION REQUESTS FOR RELIEF .Page 15 of 48 vent' pipe NIX-27.28)- control, rod mechanism housing (MX-25.26) shroud support gyp ,j cl ud . closure head cap (Hg.): ) -t i _ head torus section closure nut I closure head flange (MK-32 ) r%
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bottern shell course ( g (( core (MX-20) supp! p"q art block i s g 39 82 CiHT $s . Instrumentation Bottom head ring nozzles (MX-23 24) 53 1 - Bottom head cap
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1503C/COC3
SI-114.1, Attachm3nt 3 SURVEILLANCE Revision 3 INSTRUCTION, REQUESTS FOR RELIEF Page 16 of 48 REOUEST FOR RELIEF ISI-6 CS m antAtt Steam Generator (four per unit) Cinist ASME Code class 1 (Equivalent) ' Inspection Requirement: ASME Section XI, Table IWB-2500-1, examination category B-D, item no. B3.140, volumetric examination l of nozzle inside radius section on the primary side. Basis for Rellels Each steam 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 linmar fracture mechanics analysis which predicts that cracks of size .025 inch (which-is greater-than the allowable reference flow size) will propagate to only slightly greater than'one sixteenth of the nozzle wall thickness during the entire life of the plant. The report proposes that the nozzle inner radius be examined at least at half the plant life, and subsequently, at the regular code inspection intervals. The primary chamber radiation exposure dose rate is ' generally on the order of 30 rem /hr. As a result, individual " stay-time in the chamber would be limited to a degree where meaningful results from alternative surface and visual examinations could not be achieved. In addition, the presence of the interior surface austenitic stainless steel cladding which has 1 a higher ductility than the base ASME-SA-216 grade WCC casting material raises =the possibility.of under cladding cracking which would not be visible with a surface examination. . 3 Alternate Inspection: TVA will initiate examination of the steam generator nozzle inner radius sections in accordance with the applicable Section XI Code during the second inspection interval. This will provide for examination of all the steam generator nozzle inner radii by the period ending at half the plant life. l (Continued) 1503C/COC3
-SI-114.1, Attachm$nt 3_-
SURVEILLANCE. Revision 3 INSTRUCTION REQUESTS FOR RELIEF - Page 17 of 48 , REOUEST FOR RELIEF ISI-6-(Continued) Safety Evaluation Summary Request for Relief ISI-6 has been approved in the following manners (a) Delaying the volumetric examination of the nozzle sections until-the third inspection period of the first inspection interval and then following the Code requirements is acceptable. References ~ Memorandum from F. J. Hebdon, NRC, to 0. D. Kingsley, TVA, dated February 7, 1991 (A02 910214 009). 1503C/COC3
SI-114.1, Attachmant 3
-SURVEILLANCE. Revision 3 INS'. AUCTION REQUESTS FOR RELIEF Page 18 of 48 EEOUEST FOR RELIEF ISI-7 component: Reactor Coolant Loop Piping Helds (2)
CIA 21: ASME Code Class 1 (Equivalent) Inspection Requirements: ASME Section XI, IWB-2500-1, examination category B-J, item no B9.10, volumetric examination of-circumferential welds. Basis for Reliti Two circumferential shell welds in the reactor coolant loop piping (RC-23S1 and RC-31S1, loops 3 and
- 4) are located inside the reactor vessel shield wall-and are inaccessible for preservice and inservice examination (see attached drawings). Both welds have undergone shop radiographic examinations. Since the preservice inspection serves as a reference to future-Anservice inspections and both welds will be inaccessible for inservice inspections, the shop radiographic examinations coupled with the ASME 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 the life of tra plant. Alternate Inspection: None. Safety Eva?uation Summary: Request for Relief ISI-7 was concluded that relief was not necessary at this time. Relief should not be requested until the fourth inspection = interval ISI Plan is made.
Reference:
Memorandum from F. J. Hebdon, NRC, to O.'D. Kingsley, TVA, dat'ed February 7, 1991 (A02 910214 009). l-l t l l I l l 1503C/COC3 I l' , i
- . , Attachment 3 CURVEILLANCE Revision 3 INSTRUCTION ptgutsis rop pggggy p, , 3, ot 4g
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81-114.1o Attachment 3
$URVE!LLANCE< Revision 3 INSTRUCTION REQUESTS TOR RELIEF- Page 20 of 48
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51-114.1, Attachmsnt 3 SURVEILLAHCE Revision 3 1HSTRUCTIDH REQUESTS FOR RELIET page 21 of 48 PEOUEST FOR PELIEF J$hl Cncrantatt Reactor coolant pumps (four per unit) Clanas ASME Code Class 1 (Equivalent) Insp.ct110JLRt21L11tunts ASME Section XI, !WD-2500 1, examination category B-L-1, item no. D12.10, volumetric examination of pressure-retalning velds in rump casing. R411s for Re11til Each reactor coolant pump casing consists of a 1 two-place welded type 304 SST casting. -The present capability of ultrasonic testing la not sufficient to , examine cast material of this thickness and achieve meaningful results. AlttI.DAte._In spe ction All four welds will be surface examined during the preservice inspection, and one veld will be surface r examined during each inspection laterval. EA111Y_CYRIMA112n SMMAIX1 1 Request for Rollef ISI-8 has been approved Vith the following additional augmented requirements: (a) One reactor coolant pump casing veld la surface examined during each inspection interval. (b) The pump casing is visually inspected for leakage in conjunction with system leakage and hydrostatic tests under Category B-P. References Memorandum from F. J. Hebdon, NRC, to 0. D. Kingsley, TVA, dated February 7, 1991 (A02 910214 009). Memorandum from Susanne Black, NRC, to 0. D. Kingsley, TVA, dated April 19, 1990 (A02 900426 005). 1 4 I
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l 1 SI-114.1, Attachment 3 SURVEILLANCE Revision 3 INSTRUCTION REQUESTS FOR RELIET page 22 of 48 _RIoutsT r0R REttEr 151-9 Cnegonent: Uncladded vessel velds in ferritic material less than 2 inches in thickness. Claint ASHI Code Class 1 and 2 (Equivalent) Inspection Pt quirerent: Ultrasonic examination of velds, paragraph T-530 of ASME Section V, Article 5, 1977 Edition, Summer 1978 Addenda as referenced in paragraph IWA-2232 (c) of ASME Section XI 1977 Edition Summer 1978 Addenda. Rasis for_Enlitis 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. However, paragraph T-533.2(b) permits the use of other callbration reflectors provided equivalent responses to that from the basic calibration hole are demonstrated. TVA currently uses 5% notches in lieu of sido drilled holes. Although the use of the 5% notch cannot be shown to be equiva'lont 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, 1977 Edition, Summer 1978 Addenda of ASME Section XI. The calibration notches for ferritic material are 10%t when t is less than .312" and .104t .009t for material .312"-6" thick. TVA's use of 5% notches is considered equivalent to the latest approved code exAnination techniques. Alternate Inspac.Lignt TVA proposes to continue the use of notches located-on the I.D. and O.D. surfaces at a nominal depth of 5%t as reference reflectors. Safety Evaluation Sitmmary: 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 910214 009). 1503C/COC3 s ( - e - He - r T-- -
S!.114.1, Attachm:nt 3 SURVEILLANCE Revision 3 INSTRUCTION Rf00ESTS TOR RELIEF Page 23 of 48 PEOUEST POR PILIEF 151-10 CampantnLA: Reactor vessel flange to upper shell weld Clh11: ASME Code Class 1 (Equivalent) Inspection Pequirement: ASME Section XI, Table IWB-2500-1, examination ' category B-A, item no. Bl.30, volumetric from flange face. Basis.far.Rellels The reactor vessel flange-to-upper shell veld is located behind the core barrel and is therefore inaccessible until the core barrel is removed. The vessel flange-to-upper shell weld is 41.9 inches below the flange face. Due to the location of the vessel flange-to-upper shell veld, TVA intends to address the veld as a reactor 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 usags factors at critical locations. The maximum fatigue usage factor in the vessel in the vicinity of the flange to shall weld as found in the above analysis is 0.00662 and this value can be conservatively used for the weld. We consider the value 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 wold coupled with present ultrasonic techniques and the ve.y low fatigue usage factor that the flange-to-upper shell veld should be treated as a reactor vessel shell weld. Alternate Inspartiga A remote ultrasonic examination of the veld will be conducted from the vessel inside diameter near the end of the inspection interval. (Continued) 1503C/COC3
$1-114.1, Attechm:nt 3 SURVEILLANCE Revision 3 INSTRUCT 10H REQUESTS TCH RELIET Page 24 of 48 PEQUEST_ TOR RELitr 151-10 (Continued)
Enitty_Inlyatton Ems Request for Rollef ISI-10 has been approved with no additional augmented requirements. t References Memorandum from T. J. Hebdon, NRC, to 0. D. T.ingsley, TVA, dated February 7, 1991 (A02 910214 009). , e 1503C/COC3 e ye. w- w . - -,y... ._w,,p.- an -- - ,,
i 81-114.1, Attachment 3 SURVEILLANCE Revision 3 INSTRUCTION REQUESTS FOR RELIEF Page 25 of 48 FEOUEST TOR RELIET ISI-11 This Request has been Withdrawn l I b 1 >
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$URVE!LLANCE _ _ Revision 3 l 2NSTRUCTION REQUESTS FOR RELIEF page 26 of 48 y
RE00EST FOR RELIEF ISf .i This Request For Rollef was not needed. See NRC Safety Evaluation Report dated February 7, 1991 (A02 910214 009). Componentat 1. Excess Letdown Heat. Exchanger - Chemical and A Volume Control System (CVCS)
- 2. Regenerative Heat Exchanger - CVCS l
Clata ASME Code Class 2 (Equivalent) Innocetion__Rt quirement ASME Section XI, Table IWC-2500-1, Examination Category C A, item Nos. C1.10, C1.20, and C1.30, volumetric examination of essentially _100-percent of each circumferential weld at gross structural-discontinuities (head-to-shell and tubesheet-to-shell weld) and categories-C-C and C-E, item Nos. C3.10, surface examinations of lategrally velded support attachments. Basis for Rglitis The excess letdown heat exchanger (ELHX) and the regenerative heat' exchanger (RHX) were scheduled for examination during the first inspection period in ' sceordance wlth the In-service Inspection (ISI).
" Programs SI-114.1 and SI-114.24 The ELHX circum.-
forential head weld was scheduled for ultrasonic (UT) examination in the first_three-year inspection period. For the RHX there are six circumferential head welds and six circumferential tubesheet-to-shell- _ welds. Of these, two each of the circumferential head welds and tubesheet-to-shell welds were~to be examined in the first period by UT examination. ASME , Section XI 1977 Edition,- Summer 1978. Addenda, Table IWC-2500-1 Examination; Category C-A requires a volumetric examination of- 100 percent of the required-welds.
- The ELHX weld was examined ultrasonically from one
' side.for almost the entire length, except where the head's flanged nostle-inlet and outlet welds interfered with the examination (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_nutsLseverely restricted access to.the weld areal and asfa result no meanlagful results could be obtained. - The UT was performed on a best-ef fort ~
basis and supplemented with a liquid-penetrant test (PT) over 100 percent of the weld _ area. (Continued) 1503C/C0C3
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51 114.1, Attachment 3 SURVEILLANCE ' INSTRUCTION REQUESTS TOR RELIEF Page 17 of 48 REQlffjT FOR PJLIEP ISI-11 (Continued) t In the case of the RHX when examinations were performed, Lho state-of-the-art UT examination capabilities did not allow the achievement of meaningful results because of the component fabrication processes involved. The REX la a centrifuga11y cast stainless steel, SA-351, CTS vessel. In addition, the examinations were hindered by supports which were essentially ' nonremovable from the area of two of the four welds because of the location in the heat exchanger room and their position on the vessel.(see attached drawings). As a result, a PT was performed in place of the required UT. On the two restricted welds examined, only 75 percent of the veld lengths were surface examined because of supports covering part of r the weld areas. In accordance with 10 CTR 50.2(v) of the Code of rederal Regulations, the RHX and the ELHX are defland to be within the reactor coolant pressure boundary (RCPB) (ASME Class 1). Secondly, 10 CTR 50.55(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 (Clars 1 require-e ments), provided (11) The component la or can be isolated from the reactor _ coolant s} stem 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,.n i the event of postulated failure of the component during normal reactor operation, each valve remains operable and the reactor can be shutdown and cooled down in an orderly manner, assuming makeup la provided by th,e reactor coolant makeup system only." As a result of this paragraph, the REX, ELHX, and the connecting piping to the Reactor Coolant System (RCS) and piping ' out to the containment isolation valves would be exempt from ASME Class 1 examination requirements. 1503C/C0C3
SI-114.1, Attachment 3 SURVEILLANCE Revision 3 INSTRUCTION REQUESTS FOR RELIEF Page 28 of 48 P10 VEST FOR PELIIr IEI-12 (Continued) Sequoyah Nuclear plant units 1 and 2 ISI programs, SI-114.1 and SI-114.2, classify components for examination in accordance with Regulatory Guide 1.26, Revision 3. The guidelines of Regulatory Guide 1.26, paragraph C.1, classify components which are exempted by 10 CTR $0.55A(c)(2)11 from ASME Class 1 examina-tion requirements (such as the RIIX, ELIIX, and associated piping) as ASME Class 2 equivalent. The Sequoyah Final Safety Analysis Report (TSAR), Section 9.3.4.1.7, further describes the RHX, ELifX, and associated piping as "not required to function durity a loss-of-coolant accident." Additional system design consf$erations 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.
- 2. The RitX la isolated from the RCS by two check valves. Leakage from the RCS la prevented by the two check valves in series which were leak tested during the preoperational test program. -Leakege also can be detected by monitoring for signs of system incoming leakage.and by monitoring the RCS for signs of outgoing leakage (TSAR 6.3-26).
- 3. There are no leakage problems into the CVCS from the RCS because of the higher pressure at which the CVCS is generally maintained (TSAR 6.3 27).
In addition,' the inlet and outlet piping (one inlet and one outlet) associated with the Ef4HX is 1-inch nominal pipe size (NPS) and 3-inch UpS 'for the REX. Both of these are less than the 4-luch NPS which, in accordance with IWC-1220(c), is exempt from the examination requirements in Table IWC-2500-1 (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 sl e and smaller. (Having one inlet and one outlet pipe, each 1-NPS or-smaller.) 1501C/COC3
l i GI-114.1, Attachment ? SURVEILLANCE Revision 3 ! INSTRUCTION REQUESTF. TOR RELIEF Page 29 of 48 l l I EEOUEST-TOR RELIrr ISI-12 (Continued) TVA also feels that the ALARA considerations to perform the 11guld penetrant (PT) examinations on the ELHX and RHX 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. i Note that, in addition to the requirements in Eman.ination Category C-A, Table IHC-2500-1, Examination Category C-H requires that all pressure retaining components tnt pressure tested in accordance with IHC-5000. This results in a system pressure test conducted each 10-year Interval during 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 TSAR, the design of the heat exchangers and their supports preventing 100-percent ,- examination coverage, and the ALARA considerations in view of the small benefit reall ed, TVA requests relief from the ASME Section XI examination requirements as shown in Table IHC-2500-1, Examination Category C-A only-(Class 2). , Alternate Inspertiant None. t i 1503C/COC3 y-, , .
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s SI-114.1, Attachment 3 SURVEILLANCE Revision 3 INSTRUCTION REQUESTS TOR RELIEF Page 34 of 48 REOUEST FOR REL1Er 151-13 Compantails Residual float Removal liest Exchanger (two per unit) Clata ASME Code Class 2 (Equivalent) In5ptat10A_Et. grit.tecat i ASME Section XI, Table IWC-2500-1, examination category C-B, item no. C2.20, nossles in vessels with over 1/2-inch in nominal wall thickness; surface and volumetric examination. Ha118.,_ Lot _.Eg1131: Each heat exchanger consists of an Anlet-outlet head chamber with one inlet and one outlet nozzle and two integrally attached support brackets. Volumetric-examination of the nozzle-to-vessel velds and the nossle inner radil is inhibited by the shell-to-tubesheet weld, shell-to head weld, and the integral supports as shown In the attached sketches. Proximity of the welds and Anner radius sections do not allow for the achievement of meaning results from a volumetric examination. Alternate traminatinn The nossle-to-vessel welds will be examined utilising a surface only examination. Eaftty Evaluation E y;g!iggy: l Request for Rollef ISI-13 has been approved with no additional augmented requirements. References Memorandum from F. J. liebdon, NRC, to 0. D. Kingsley, TVA, dated February 7, 1991 (A02 910214 009). 1503C/COC3
m NOTES
- 1. Replace the Y in the weld and support numbers with the ED appropiale heat exchanger GG
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- 2. Rep ace the Z in the welds number with the appropiate area Of the weld exacined (1, 2. or3) . . ,
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$2-114.1, Attachment 3 SURVEILLANCE Revision 3 INSTRUCTION REQUESTS FOR RELitr page 38 of 48 RIQUEST.FOR_ RELIEF 191-14 C2nponents: Reactor Vessel (RV) Outlet Nossle-to-Vessel Welds, RV Nossle Inside Radius Section, and RV Nossle.to-$sfe End Welds Class American Society of Mechanical-Engineers (ASME) Code Class 1 Inspection Reeuirement: Table IWB-2500-1 Esamination Category B-D) rull Penetration Wolds of ,
Nossles in Vessels Item No. B3.90 Nossle-to-Vessel Welds Item Ho. B3.100 Nossie'Inside Radius Section s F rsetnote 3 (1st Inspection Interval) "At least i 25 percent but not more then.50 percent I (credited) of the nossles shall be examined by the end of 1st inspection period and remainder by the end of inspection interval." Footnote 4 (Successive Inspection Intervals 2nd, 3rd, and 4th) "At least 25 percent but not more
- than 50 percent (credited): of the nossles. shall f be examined by the end of 'ist inspection period and the remainder by the end of 3rd inspection period of each inspection interval. ,
e Footnote _S'(Deferral of Inspection to End of Interval) "If examinations are conducted from-inside the component and the nossle weld is examined by straight beam ultrasonic method from ! the nossle bore the remaining examinations required to be conducted from the shell inside diameter may be performed at or ne st tho' end of each inspection interval." ' Examination Category B-F; Pressure Retaining : Dissimilar Metal Welds ' Item No. 35.10 Nossle-to-Safe End Helds Footnote 2 (Successive Inspection Intervals 2nd, s 3rd, and 4th)' "For the reactor vessel nossle safe-endsf. the examinations may be performed coincident with the vessel nossle examinations required by Examination Category B-D." - ' - - I
-(Continued) 1503C/COC3 -. ,m- , _ , ., - m_ , .y.f-... ,- - _ r , ~ ,,,-.e ,..,,.m,_ _ , . ,,. , , b.,-- --c,,-#
l 51-114.1, Attachment 3 , SURVEILLANCE Revision 3 INSTRUCTION REQUESTS FOR RELIEr Page 39 of 48 FIQllIST FOR_Fil LfSI-14 (Continue Ralla_fgr Relieft Sequoyah Nuclear Plant (SON) is a four-loop pressurised water reactor with four Anlot and four outlet RV nossles. The RV nozzle-to-vessel welds and inside radlus sections are ultrasonically examined from the RV inside diameter using automated inspection devices. With the RV core barrel la place, the outlet nossles are accessible for examination from the nozzle bore only. The inlet nosales are inaccessible for examination until the core barrel is removed. SON 1s in the second period of the first ten-year ' inspection Interval. During the first period, the accessible volumes of the norslo-to-vessel welds and inside radius sections on SON's tour outlet nossles were ultrasonically examined f rom the nossle boro. The remaining examinations for the four Anlet and four outlet nossles are to be completed during the third period, thus satisfying the requirements of Table IWB-2500-1, Examination Category B-D, Item Nos. B3.90 and B3.100, rootnotes 3, 4, and 5. In addition to the RV nomsle examinations, the RV nossie-to-safe end welds are ultrasonically examined using an automated inspection device when-the nossle is examined from the bore. During the first period, the nossle-to-safe end welds on four outlet nossles were ultrasonically examined from the inside diameter and surf ace examined from the outside diameter. The nossle-to-safe end welds on the four inlet nossles will be almilarly examined during the third luspection period. This will satisfy the requirements of Table IWB-2500-1, Examination Category B-r, Item No. B5.10, rootnote 2. The ASME Code provides for the continuation of the first and third period examinations during the second, third, and fourth inspection intervals, thus establishing a ten-year examination frequency. TVA proposes to alter the inspection schedule by performing an additional examination of the RV nossle-to-vessel welds and inside radius sections for SQN's four outlet nossles during the third inspection period of the first inspection interval. In addition, the nozzle-to-safe end welds for the outlet nossles would also be examined during the-third laspection period of the first interval. Performance of these additional examinations will thereby establish a new ten-year examination schedule for the second, third, and fourth inspection intervals. The ten-year examination frequency required by the code (Continued) 1503C/COC3 <~s - g n ~ - _ -m - _
t ' SI-114.1, Attachment 3 SURVEILLANCE Revision 3 INSTRUCTION REQUESTS FOR RELIEF Page 40 of 48 EIOUEST TOR RELIEF,_lEl-ll (Continued) Antin for Reliefs would continue to be maintained. Additional benefits (Continued) include:
- One-time installation and removal of the automated inspection device from the RV flange rather than twice during and luspection interval.
t
- Performance of additional RV outlet nossle examinations during the first inspection laterval.
- Performance of additional RV outlet nossie-to-safe end weld examinations during the first inspection interval.
- An overall reduction in personnel radiation exposure (one automated examination versus two),
thus supporting as low as reasonably achievable considerations. A reduction in the number of times automated devices and associated materials and equipment ' must be decontaminated (reduces generation of , radwaste).
- A cost saving to TVA of 1.8 million dollars over the 40-year life of the plant.
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 the specified 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 nossles 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 nossie-to-vessel welds by the straight beam ultrasonic method from the possle bore and examination of the outlet nossle lunar radius sections. These examinations will be.in addition to the examinations required to be conducted on the r (Continued) 1503C/COC3
, _. ~ , _ - -- -
87-114.1,=Att0chment 3
$URVE!LLANCE Revision 3' INSTRUCTION- REQUESTS TOR REL1ET Page 41 of 48-gr0UEST FOR RELfEP ISI-14 (Continued)
Alternate Inspections outlet nossie-to-vessel welds and inner radius section from the RV shell inside-diameter during the third inspection period. SON's four RV outlet nossle-to-safe end welds will also be examined twice during the first inspection interval (third period). The examinations will include an automated ultrasonic examination from the inside diameter and a surface examination from the outside diameter. During the second, third, and_ fourth inspection intervals all RV nossle-to-vessel welds, inside radius sections and RV nossle-to-safe end welds will be examined during the third inspection period. 1.tA_tEli Request for Rollof ISI-14 was submitted to the NRC on August 21, 1991, with a request for a response by June 1, 1992. References Memorandum from J. L. Wilson, TVA, to the NRC, dated August 21, 1991 (S10 910821 848). NRC Responsel Memorandum from T. J. . Hebdon, NRC, to Dr. Mark O. Medford, TVA, - dated August 31, 1992 (A02 920903 005). Staff Evaluations The proposed inspection sequence meets the Code scheduling
- requirements for the subject RPV outlet nossle-to-vessel welds, outlet nossle inner radius sections, and nossle-to-safe end welds at SON Units 1-and 2 for the first 10-year inspection interval. Therefore, relief'is not.regJired.
' during the first 10-year inspection interval.
In response to the Licensee's request to defer the subject l examinations for . _ the second inspection interval, the examination schedule change 'for the second inspection interval must be evaluated to-future editloos and addendaEof the-ASME Code as defined by 10'CTR 50.55a(g)(4) and 10'CTR 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 time period between. -
specific weld examinations does not exceed 10 years ~ plus Code-allowed
- extensions. With the large population of operating reactors, 'the examination of nossles 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.' -z Proposed alternatives to Code requirements can only be authorised for examinations _ in .the .present ' interval.' . Therefore, a separate relief request g will have to be submitted for the next (second) 10-year ISI interval af terlthe.
- applicable Code for the second interval has' been established.
L i , l
,1503C/C0C3
SI-114.1, Attachment 3 SURVEILLANCE Revision 3 INSTRUCTION REQUESTS f0R RELIEF page 42 of 48 RIQursT ron RtLIrr IsI-Is Cnepang.ntat Main Steam System Integrally Welded Support Attachments CIAlt ASME Code Class 2 (Equivalent) Ingreetion_Rtquitrag.nt ASME Section XI, Table IWC-2500-1, Examination Category C-C, Item No. C3.40, piping Integrally Welded Support Attachments, Surface Examination. RA111_Lar_P111ti It will be impractical to surface examine certain integrally welded attachment welds due to the design configuration of'the Main Steam System supports. Examination of piping integrally welded support attachments 1-MSH-303-IA, 1-MSH-343-IA, 1-MSH-383.IA, and HSH-423-IA la prohibited for the following reasons (1) The physical location of the supports is very close to the wall. (2) Disassembly of the supports is prohibited without cutting the support. (3) The Integral attachment welds.are obscured behind bars. Therefore, a surface examination is not possible and only a small percentage of the integral attachment weld is accessible for a visual examination, (4) SON outage personnel worked five shifts attempting to remove the support _ clamp.for 1-MSH-303-IA without success. After removal of the clamp bolting, there was not sufficient clearance to remove the brackets that clamp around the pipe due to the building structure and design configuration of the supports. Alternate Inspection TVA will perform a VT examination of the componen't supports as practical. Statng: Request for Relief ISI-15 submitted to the NRC as a part of Revision 17 of this program.
- 1503C/COC3
_ . . . + -
SI-114.1, Attachment 3 SURVEILLANCE Revision 3 INSTRUCTION REQUESTS FOR RELIET Page 43 of 48 4 REOUEST FOR RELIEF 151-16 componenta Residual Heat Removal Heat Exchanger (two'per unit) Plaaan ASKE Code Class 2 (Equivalent) Inaggrilmn Renuirement ASME Section XI, Table IWC-2500-1, Examination Category C-A, Item Ho. C1.10, Volumetric Examination of Circumferential Shell Welds. Resis for Relief Each heat exchanger consists of an inlet-outlet head chamber with one-Anlet and one outlet nossle and two-integrally attached support brackets-and a circumferential vessel shell-to-flange veld.- The design configuration of the nossles and support brackets restricts examination of the vessel-to-flange weld (see attached drawing). The vessel shell weld is 113 inches in longth. The weld examinations are. distributed la three segments, Identified ast RHRW-16-A-1, 37 - An. ; RHRW-16-A-2, 3 8 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 coverage. RHRW-16-A-2 ' was examined in the second period and achieved
-approximately 71% examination volume coverage.
RHRW-16-A-3 is scheduled for examination ~during the. third period with an estimated examination volume coverage of 82%. Based on the examinations performed and an estimation of the remaining third' period examination, approximately 78% examination volume coverage of-the RHR heat exchanger.circumferential veld will be achieved. Alternate Inspection In addition to the visual examination performed during system leakag,e 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 much Code coverage as possible and achieve meaningful results. Sittg33 - Request for Relief ISI-16 submitted to the NRC as a part of Revision 17 of this program. J 1503C/COC3
^
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' CM ecTEs Rur-ucENCE MAWItCS 0* FM VESSEL VILL.BE ESTABLISHED ' CMTRACT tJO 68C60-?!934 (N2M-2-25) QQ AT t Itt.ET NOZZLE. PORTION Of WELO AUX. IEAT EXCHANGER MANUAL
~ t-EXAMINED AS FOLLOWSu #1 (0
- TO 37 *) : E K-
#2 ' (37' TO 75 *]: f3 (75* TO I13*] s u V AWIfG 12. 15588 *
(IN A CLOCKWISE DIRECTION] ASTE CC-2 (EDLIIVALENT) - ' ItLET ItLET . - R m W-16-Y-Z RmW-59-Y-IA RmW-14-Y h.lJ-w - RmW-18-Y-IA
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-- M RmfD0f-I9-Y' ET Rm W-17-Y-Z TLET RmW-15-Y s acc e-2.-es - aco errraocr ows f, CAM T=y.
RMfD04 OR RMW-XX-Y-Z * * ''*** ' " " ' ' I " I *^ ' "*
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2 nec es-ro-or accro exec etass s noor cao oarc 'xc as WELD /ID StPPmTA * ^^ '-**' cowarcr o~c ror *ersin : ma nc ae wrv s-s-en arrisc wrto ser. a eco corrs roc l na A W B HX- nov.. ere carr orscarrrrae co as are t; " " * * " ' ' " " * ' ' " " ' " ' "
.8 . PmTIM 0F" WELD EXAMI- - =e w m tED (l,2,W3) FM kELOS TWES$EC VALLEY AummITY:
Q i g R ';< RmW-16-Y-Z G RMW-I7-Y-Z SEQUOYAH NUCLEAR PLANT o
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- h. RESIDUA!. IEA T REMOVAL hEA T EXCHAtJGER.
ceas , etv CHAMEL WELDS AND StFPORT ~. u , g M r", *Ts M T swnstreo an eovto \ sscr nrs s e m Lrt _ _ _ nrc___ sM rr , or e s><rr<st == g'. pggrgpx _ roc _, y a, o***iw w *rv n oarr,- CHM-2404-A 05 ( 3 e to e
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l j SI-114.1, Attachment 3 I SURVEILLANCE Revision 3 ; INSTRUCTION REQUESTS FOR RELIEr page 45 of 48 ' REOUEST TOR RELIEP ISI-17 Cacpanents: Integrally Welded Support Attachments , Class: ASME Codo Class 2 (Equivalent) 1 Inapletion Requirenents ASME Section XI, Table IWC-2500-1, Examination Category C-C, Item No. C3.40, Piping Integrally Helded Support Attachments, Surf ace Examination. Basis for Relief: Due to the design vintage of Sequoyah Nuclear Plant it will be impractical to inspect all of the ' integrally welded 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 examination data sheet and on the attached listing of this Rollef Request. Alternate Inspections TVA will perform a best-effort surface examination. - In addition, the supports shall receive a visual-examination (VT-3) as practical. Status Request for Relief ISI-17 unbmitted to the NRC as a part of Revision 17 of this program. 4 (. t l l l L - i l l t I i' 1503C/COC3
51-114.1, Attachment 3 SURVEILLANCE Revision 3 INSTRUCTION REQUESTS FOR RELIEF Page 46 of 48 I REQUEST FOR RELIEF ISI-17 Cornponent Exarn Drawing Code
, Jystem ID Cat. No. Coveregg Limitations
-t Teodwater TDil-204.I A C-C CID4-2 43 9-C 0% Access limited due to ~
penetration at wall in ; valve room. Support designs snubber stiffener plate prohibits access to integral attachments for surface exam and , allows only a best . effort visual examination. t L 1503C/COC3 4 + v ~ ., - - - , , - , _ -- , ,, . . , - , ,,----,,--.--r,. -.m., , ,, . - .,.--r, ,-r._,
SI-114.1, - Attachment 3 SURVEILLANCE Revision 3 INSTRUCTION REQUESTS FOR RELIEF Page 47 of 48 FIQEE*t_LOLJJLIEP ISI-18 CorrontntAt Reactor Pressure Vessel Closure Head-to-Tlange Nold Clais: ASME Code Class 1 (Equivalent) Intre e ti on___Reggigenent: ASME Section XI, Table IWH-2500-1, Examination Category B-A, Item No. Bl.40, Volumetric Examination. Ragts . for Rolleft The Reactor Pressure Vessel (RPV) closure head-to-flange veld, H08-09, is (5 feet in length. The veld examinations are performed from the OD surface and d.stributed in three segments of 15 feet lengths each inspection period. The veld segments are identified as H00-09A (0" - 100"), H08-09B (180" - 360") and H08-09C (360" - 540"). Due to the design configuration of the closure head, no examinations may be performed f rom the flange side. Limited examinations from sne ring side are due to the head lifting lugs located at 0*, 120', and 240' (see attached drawing). These limitations are denoted on the examination data sheets. H08-09A was ultrasonically examined in the first inspection period and achieved approximately 40% examination volume coverage. H08-09B was examined in the second N inspection period and achieved approximately 40% examination volume coverage. H08-09C is scheduled for examination during the third petiod 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 ring side. However, the required 1/2T base metal area was not cc.apletely examined on the flange side. Due to extreme limited scanning area, TVA will be able to achieve approximately 40% examination coverage of the RPV closure head-to-flange weld. Alt 2Innte Inspection: In addition to t s visual examination performed during system leakage and hydrostatic pressure tests, TVA will perform a best-effort ultrasonic examination to achieve as much code coverege as possible and achieve meaningful results. In addition TVA will perform a 100% surf ace examination (MT) of the closure head-to-flange weld flex area, of all accessible areas, in the third inspection period. Etatuit Request for Relief ISI-18 subeitted to the NRC as a part of Revision 17 of this program. 1503C/COC3 _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ' - - - - - - - - - ' - " - - - ^ " - - - - - ^ " - - - - - ^ ' ' ' - - - ~ ~ ~ ^ - - - - - - ^ - - - - - - - -
' SI-114.1, . Attochm2nt 3
' SURVEILLdNCE'
- Revision 3 INSTRUCTION REQUESTS FOR RELIEF 'Page 48 of 48 g- ;;
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SI 114.1,- Attcchmint 4 SURVEILLANCE- Revision 0 INSTRUCTION- COMPONENT TABLES - UNIT 1 Page.1 of 23 ASME Section XI Programs A. MAINTAIN a listing of components for ISI examinations. B. UPDATE listing as necessary. C. OBTAIN concurrence frcm Site Quality Manager or his designee. SOM D. CONCUR with listing by signing below. ASMS Section II Programs ! E. FORWARD to SPS for updating Table of Contents, etc. SPS F. FORWARD to DCRM. DCEM G. DISTRIBUTE per SSP-2.7.
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Sito Quality Manager / Designee Date 1 i i i 1537C/COC3'
TABLE A SEQUOYAH INSERVICE INSPECTION PROGRAll CtASS 1 COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Esam Enam No. Length No. Length Inspection Periods Comoonent Reference "E Section Method Cateoorv Velds /of Weld Velds /of Weld 3 vrs. 7 vrs. 10 vrs. Dwo. No. A. Reactor Vessel gg EN
- 1. Circumferential Shell Welds OE wg 7.1.1.1 UT B-A 4/50 ft. 4/50 ft. 0 0 4 O H-2343-8 @g
- 2. Closure Head n Circ Weld 7.1.1.3 UT B-A 41 ft. 41 ft. 13 ft. O ft. 28 ft. CHM-2358-A
- 3. Lower Head Circ Weld 7.1.1.4 UT B-A 38 ft. 38 ft. O ft. O ft. 383 ft. CHM-2343-8
- 4. Lower Head Merldlonal . Welds 7.1.1.6 UT 8-A 6/4 ft. 6/4 ft. 0 0 6 CHM-2343-8 Q
g
- 5. Shell-to-Flange Weld 7.1.1.7 UT B-A O
50 ft. 50 ft. O ft. O ft. 50 ft.2 CHM-2343-8 "
- 6. Closure Head- H to-Flange Weld 7.1.1.8 UT B-A 45 ft. 45 ft. 15 ft. 15 ft. 15 ft. CHM-2358-A N Closure Head-to- E Flange Flen Area 7.1.1.8 MT B-A 45 ft. 0 0 M
45 ft. 45 ft. CHM-2358-A
- 7. Noz zl e-to- t Vessel Welds 7.1.2 8-D 4l UT 8 8 41 0 CHH-2343-8 h Outlets Inlets CHM-2350-A y (Bore CHM-2351-A
& Shell "
ID) 4 Outlets (Bore & Shell ID) I 2 The four outlet nor:1e-to-vessel welds examination from the vessel shell shall be done in the third inspection period. *o *e m See Request for Relief 151-10. 4 See Request for Relief ISI-5. $o *e6- M See Request for Relief ISI-14 for background information on esamination of all nor:1es from the bore and shell ID in the third inspection period. u"%
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TABLE A SEQ'JOYAH INSERVICE IW;'ECTION PROGRAM CLASS 1 COMPOtENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Esam Exam No. Length No. Length Inspection Periods Reference Component Section Method Cateoorv Velds /of Weld Welds /of Weld 3 vrs. 7 vrs. 10 vrs. Dws. No. gg A. Engler Vessel (cont'd) EO
- 8. Inside Radius OE Sections (Includes 7.1.3 UT B-D 8 8 4
*E' Integral Estensions 0 81 C % 2343-8 @ (; -
Outlet (4 Inlet CHM-2350-A to on the Outlet Nozzles) 4 Outlet) CHM-2351-A
- 9. Vessel Pene-trations and C % 2651-C Attachments 7.1.4 YT-2 8-E 37 37 12 12 13 MSG-0004-C
- 10. Nozzle-to-Safe End Welds 7.1.5 UT,PT B-F 8 4 83 8 0 0 99-2343-8 g Outlet (4 Inlet o 4 Outlet) g 11.- Closure Studs 7.1.6 UT.MT B-G-1 54 54 18 18 18 CHM-2341-B E and Nuts 7.1.6 MT B-G-1 54 54 18 18 18 095-2341-8 ,
- 12. Ligaments Between E t*
Threaded Sted t1 Holes 7.1.6 UT 8-G-1 54 54 18 18 18 CHM-2341-8 13.' Closure Washers 7.1.6 VT-1 8-G-1 54 54 18 18 18 CHM-2341-8
- 14. Vessel Interior 7.1.9 VT-3 S-N-1 1 1 1 1 1 091-2343-8 y
- 15. Removable Core "
Support Structure 7.1.10 VT-3 B-N-3 See Program Section 7.1.10 I 5ee Request for Rollef 151-14 for background information on examination of all nor:1es in the third Inspection period. 550 1 :!. L . m :'. :: P,f 2" e t: II e n .3-O e-O
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y n TABLE A ' SEQUDYAH INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS . Progran . Section XI 40 Yr. Sample .1st Insp. Interval Reference.Eman Enam No. Length No. Length Inspectton Periods Component . Reference 'y $ Section Method Cateoorv Welds /of Weld Welds /of Weld .3 vrs. 7 ves. 10 vrs. Dwo. No. to w A. Reactor Vessel (cont'd) $N c: w
- 16. Control Eod-Drive Housings ' 7.1.11 UT B.0 2 2 0 .I O m 2651-C
' Oet-2359-A O E:
wg' 1
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- 17. RV Aun Head Adapters 7.1.12 UT.PT B-F 4- 4 1 1 2 .. O W 2651-C ISI-0014-A
- 8. Pressurfrer
- 1. Circumferential ..
Shell-to-Head @ Welds 7.2.1 UT 8-8 ' gi 2/24 ft. 2/24 ft. 12 ft. 12 ft. 24 ft. 1SI-C394-C o
- 2. Longitudinal 2: . -
Shell-to-Head-7.2.2 .b"
.< Welds -UT B-8 2/1 ft.I 2/1 ft. 1 '0 1 ISI-0394-C q 3.' Nozzle-to-Vessel y; Welds and Inside E' M'
' Radius Section 7.2.4 UT 5-0 6 6 2 2 2 "~
ISI-0394-C 4.' Heater 't
- Penetrations 7.2.5 VT-2 . B-E 78 20 6 7 7 MSG-0006-A- 'E.
; 5. Norale-to-Safe U.
End Welds; 7.2.6 UT.PT 5-F. 6 6 2' 2, 2 ISI-0394-C. " 1 0ne foot of the longitudinal weld selected for esamination is that section of weld intersecting the circumferential . shell-to-head weld esamined.
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TABLE A SEQUDYAH INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Exam Esam 'No. Length No. Length Inspection Periods Component Section Method Cateoorv Velds /of weld Reference yQ Velds /of Veld 3 vrt. 7 vrs. 10 vrs. Dwa. No. m :o H<
- 8. Pressurizer (cont'd) gM
- 6. Pressure Retain-ing Bolting OE ag 7.2.8 .VT-1 8-G-2 1 Ny/ 1 Ny/ 16 0 0 MSG-0002-8 @ p; 16 bolts 16 bolts M
- 7. Integrally Walded Support Skirt 7.2.9.1 HT 8-H 23 ft.
23 ft. 7 ft. 8 ft. 8 ft. ISI-0394-C
- 8. Seismic Lugs 7.2.9.2 MT B-H 4 4 0 4 0 ISI-0394-C C. Steam Generators o o
- 1. Primary Head-to-Tube Sheet Weld 7.3.2 UT B-8 4/36 ft. 4/36 ft. I 1 2 ISI-0399-C z m
- 2. Primary Notzles Inside Radius b Section
- 3. Primary Norale-7.3.3 tlT B-D 81 81 0 e 81 ISI-0399-C f
N to-Safe End Welds 7.3.4 UT PT B-F 8 8 2 3 3 ISI-0399-C *
- 4. Pressure Retain- t ing Bolting 7.3.6 VT-1 B-G-2 4 Gens./2Ny 8 Ny 2 2 4 MSG-0002-8 E
- 5. Tubing. 7.3.8 ET . B-Q See program sections 7.3.8 and 20.4 ISI-0397-C w
I See Program Section'7.3.3 and Request for Rollef ISI-6. I5"w il f 2
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y TABLE A SEQUOYMI INSERVICE INSPECTION PROGRAM CtA55 i COMPONENTS Prograa . Section XI 40 Yr. Sample 1st Insp. Interval Reference ~Eram Exam No. Length No. Length Inspection Periods Corconent Section Method Cateoorv Velds /ef Weld Reference - yE Velds /ef Veld 3 vrs. 7 vrs. 10 vrs. Dwo. No. gg
.D. Pionna "
CM'
- 1. ECg11ure Retainina - OE Solting wg O~
- a. Reactor Coolant *O System 7.4.3.1 VT-1 84-2 5 Sets 2 5 Sets 2 2 1 2 15I-0369-C
- b. Chemical and Volume Control System (SWI) 7.4.3.2 VT-1 B-G-2 4 Sets /4 Bolts 4 Sets 1 1 1 C m -2338-C
- c. Safety O Injection g System 7.4.3.4 VT-1 84-2 4 Sets /4 Bolts 4 Sets o 1 1 2 C m -2333-C u
- 2. Circumferential Velds !3 4
- a. Reactor Coolant 5ystee Main Loops >-
Cires 14" 7.4.4.1 UT/PT S-3 63 16 5 5 6 Cm-2333-8 E' M-m.
- b. Reactor Coolant ,
System Cires 2.4" Nom. Size 7.4.4.2 UT/PT B-J 651 171 c 5 5 7 15I-0369-C 2 Cires <4" Mou. Size 7.4.4.2 PT B-J 203 53 2 2 y 1 15I-0369-C I C m-2333-8 "' The change added to RCin System welds numbers' during af ter UIC4 Mod.the third' period was due to' the RV Aus Head Adapter Cap Velds (tHI Caps) being 2 3 The enange in bolted connections was due to the UIC4 RTD Mod. The change in weld num6ers was due to the UIC4 RTD Mod. IEO
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TABLE A SEQUDYAH INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Eram ' Eram No. Length No. Length Inspection Periods Component Section Method Cateoorv Welds /of Veld Reference .yE Velds /of Veld 3 vrs. 7 vrs. 10 vrs. Dwa. No. gg D. Plot M (cont'd)- EU n t" c.' Cheelcal'and Volume Control U"5 System Cires 14" 9 Nom. Size 7.4.4.3 . N/A O Cires (4" Nom. Size 7.4.4.3 PT B4 62 15 5 5 5 O S 2335-C
- d. Residual Heat Removal System Cires 14" Nom. Sire 7.4.4.4- UT/PT 84 49 13 4 4 5 C & z335-C
- e. Safety Injection 4
System Cires 14" O. Nom. Sire 7.4.4.5 I'! UT/PT 84 841 21I 7 6 8 CHM-2333-C 4 Cires <4" Nom. Sire 7.4.4.5 PT 54 33 8 2 2 4 H CHH-2333-C g
- f. RV Aux Head Adapter Cap 5 Welds (UHI Caps)
Cires 14" 7.4.4.6 These welds are examined as a part of the RC System, Section 7.4.4.2. due to 4 the UIC4 Mod. e M
'E w
I The change in weld'ntsnbors was due to new code class boundaries.
'8 58 SS EEY e;;
e A 0 { 5 % n if n a
,8 _.
- j;
- i.
t...'ir' TABLE A- .
. SEQUDYMi INSERVICE INSPECTION PROQtAM ,
CLASS 1 COMPONENTS
- Program = Section XI 40 Yr. Sample 1st Insp. Intervs.1 -
' Reference Eram . Isas . No. Length No. Length
' Inspection Periods Cesconent Section Method 'Categorv' Welds /of Weld Reference H in Welds /of Weld 3 vrs. 7 vrs. 10 vrs. Dwa. No. .6$,
' O. Plolog (cont'd) H <=
c m"
- 3. Branch'Ploe Connection Welds. QF
- a. Reactor Coolant
.w"'
.o E
- - Systee -
Main Loops
*O'
~
- i. -Velds >2"-
, -Nom. Sira '7.4.5.1 UT/PT.. 84 1 1 0 1 0 - CHM-2333-8 Welds 12"
' Nom. Sire 7.4.5.1 PT . 54 12 '3 1 -2 'O OM-2333-8 ~
b.' Reacter CoolantT n r
- 1. System 0-1 Welds'>2* -
E. , OM-2333-8 Nom. Stre 7.4.5.2 - UT/PT - 54 6 2 0 l@ Welds 12" . 1 1 ISI-0359-C'- M
-Nom.:Stre 7.4.5.2 OM-2333-8 ' $l PT 84 7 2 0 1 1 15I-0369-C :. g- ..
- c. Chemical'and-
- Volume Control 5 f System E
- Welds >2"
- Nom. Sire . 7.4.5.3- UT/PT-:54 3 S 1 0 0 1 CHM-2335-C.
. Welds 12" Nom. Stre 7.4.5.3' PT ;84 -1 See Note 1 - - -
DM-2335-C - M n
.:L t
IEsaminatt'on not echeduled this interval.
' av se in -
sp . e M W3 4 9-
- e oa. N- .
O D H: o'.
. - 4.# < i
- .o
'N-n . g; O a
- y
'k, '
l p.
.s. ,
+
t f-..5- 3- .g. , w ,
- 4g3 y er e<, p-_x-_ y ( [ A. ' 7 ., or a e e r .,# ., 3 - m g- ( c s..nm.,,.. o ,w.., .p 3 ~w..Ay Y,
L
.i.e -
,$','-c TABLE A .
^ SEQUDYMI INSER5' ICE INSPECTION PROGRMI CLASS 1 COMPONENIS
' Program . .
?xtion XI 40 Yr. Sample 1st Insp. Interval .
. Reference Enam Enam .'No. Length No. Length ..
Inspection Periods Component ' Reference ..._y E . section Method Cateoorv Welds /of Weld Welds /of weld 3 vrs. 7 vrs. 10 vrt. Owo. No. in x D. Plo'ine (c'ont'd). s <= C"H"
.3. Branch' Ploe Connection Welds (cont'd) .
.O h.
- d. Residual Heat'
,E o
Removal System ' *O Welds >2" ~ Nom. Size 7.4.5.4 UT/PT' B4 3 1 0 0
. Welds 12' 1 CHM-2336-C Nom. Size 7.4.5.4 PT 84 2 See Note 2 - - -
' CHM-2335-C
- s. Safety. Injection - -
' System 8-Welds >2"-
Nom. Size 7.4.5.5-.. .UT/PT 84' 5 2- 0 Welds 12? . 1 1 O m-2333-C z hom. Size 7.4.5.5 PT .54 11 2 0 D" 1 1 CM-2333-C .
- 4. Socket Welds ~"
-a. Reactor- D
"~
Coolant- M System 7.4.6.1 PT ' B4 ISI-0369-C ": 711 171 0 0 17 O M-2333-8'. s-E
- 1
. ~ l f 2The change in weld nimbers was due to the (11C4 RTD Mod. ' Esaminations not schedvied this interval.-
* *e w on Sp eM
- p. p ' a.
- oE}O' w~
t~ :g-
;e.
n_ . g,, 8:
.I~ i .
d
.u.
. _ = _ ,,m.m. t .m ._s. _.m - _ . - - m..
TABLE A i SEQUDYAH INSERVICE INSPECTION PROGRAM '
. Cl. ASS 1 COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Enam Esam No. Length No. tength Component Inspection Periods Reference Section Method Cateaorv Welds /of Veld Velds /of Veld 3 vrs. 7 vrs. 10 vrs. Dwe. No. U$
D. Pipina (cont'd) yg EN 4.'12cket Velds .OE
- b. Chemical and
-g g za Volume Control t1 '
System 7.4.6.2 PT B4 246 62 19 19 24 CHM-2335-C
- c. Residual CHM-2335-C Heat Removal System 7.4.6.3 PT B4 18 5 1 2 2 CHrt-2336-C
- d. Safety o Injection System g
7.4.6.4 PT 84 189 47 15 16 o 16 CHM-2333-C u
- 5. Pipina and Valve en Intearally Velded k ivooort Meeters g
- a. Reactor E Coolant t1 Systea
- 7.4.7.1 PT B4-1 6I 61 2 1 3 ISI-0370-C '
- b. Chemical and ~
volume Control E System 7.4.7.2 PT B-K-1 02 02 0 0 y 0 CHPS-2434-C y
- c. Residual Heat Removal .
Systee- 7.4.7.3 PT' B4-1 32 32 0 1 2 CHM-2435-C I 2 The change in weld ntunbers was due to the UIC4 RfD Mod. 1he change in weld numbers due to removal of a support. *o w to i1b "A 8L
?., o ' .5 35 .n if n .g e
. 4, TAetE A
. SEQUDYAH INSERVICE INSPECTION PROGtMI
. CLASS 1 COMPONENTS 4
Program . ' Section XI 40 Yr. Sample 1st Insp. Interval
' Reference. Enam' .Esam . No. ' Length No. Length Inspection Perlods Coseonent Reference w Os Section Method Cateaorv Welds /of Veld Welds /of Veld 3 vrs. 7 vrs. 10 vrs. Dwo. No. $5 D. Pisine (cord *d) r 1 ;- NN c.
- d. Safety- OE Injection System 7.4.7.4 Lo ** E ~
PT B-K-1 51 51 1 2 2 CHM-2436-C '% Q
- 6. Ploina and Valve Component supports
,4-
- a. Reactor Coolant System 7.4.8.1 VT-3, 8-K-2' . 552 552 13 22 23 ISI-0370-C- n-VT-4 'O
- b. Cheelcal - k.
, and Voline -@ es Control
-System 7.4.8.2 VT-3. B-K-2 126I 126I 37 41 48 Oft-2433-C VT-4 Det-2434-C c.. Residual $""
Heat Removat .._ Q un System 7.4.8.3 VT-3. 8-K-2 163 163 4 5 7 094-2435-C ' ., VT-4,
...k' n
e.*
'I The change la support numbers was due to new code class boundaries.
2 The change in weld numbers was due to the UIC4'RTD Mod. t 3 The change in support numbers was due to support removal modifications. EEN-1 ;i. 2. _. O"" E*
- n-o g-
~
e d}.g ,, n I
.R ih i ..
l '
- E o
7 g n~ "
's- f
A-
.f TAB 8.E A SEQUDYAH INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS Program- Section XI 40 Yr. Sample 1st Insp. Interval '
Reference - Exam Esas No. Length No. Length Inspection Periods Component Section Method' Cateoorv Velds /of Veld Reference Velds /of Weld' 3 vrs . ' 7 vrs . 10 vrs. Owo. No. gg mw D. Ploine (cont'd) +4 < - Mt c w's "- d.' Safety n r* Injection .*4 " L Sy: tem 7.4.8.4 VT-3, B-K-2 1, oE. VT-4 91 911 16 36 39 CHM-2436-C. *O. i
- e. RCS Main 7.4.8.5 VT-3 5-K-2 7 7 0 4 3
. Loop Piping VT-4 ISI-0333-C -
E. Reactor Coolant Pumos
- 1. Pressure-Retain- n 0
Ing Bolting 7.5.1 UT B-G-1 96 96 24 24 48 099-2675-8 D
- 2. Pressure-Retain- VT-1 ~O ing Bolting 7.5.1 MT B-G-1 See Note 2 ts CHM-2675-8 5
- 3. Pressure-Retain-Ing Bolting. 7.5.2 VT-1 5-4-2 4 Sets 4 Sets 1 Set
- 4. Component
.1 Set- 2 Sets .. CHM-2675-8
- "h-es Supports- 'm 17.5.4 VT-3 ' B-K 4 Pumps /3 ft. 12 ft. 3 3 6 e per pusqp (1-pump)(1-pump)(2-pumps) I$1-0325-8
- 5. Casing Velds 7.5.5 PT B-t-1 4 1 0 0
.1 1 MSG-0003-8 Q
=
'I 2
The change'la support numbers was due to new code class bounderles. When disassembled, bolts shall be magnetic particle esamined, threads In the base material and flange ligaments between threaded belt holes shall be visually enamined. 550.
% ;i. A NE
, ay a
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'.:Y
- 2. -
iii 8 n "
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"I
'l
_ - -:---. a v s e, 3 *- - - 4 e a-w a % y
n TABLE A SEQUDYAH INSERtICE INSPECTION PROGRAM CLASS 1 COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Component Reference Enam Enam No.' Length No. Length Inspection Periods Reference Section Method Cateoorv Velds /of Weld Velds /of Weld 3 vrs. 7 vrt. 10 vrt. Dwo. No. OE
- 6. Casing' 7.5.6 VT-1 or 8-L-2 4 See Program Section 7.5.6, 7.9 and MSG-0003-8 (UT &
RFR 151-1 E" VT-2) QE F. Valves gg gn n
- 1. Pressure Retain-ing Bolting
- a. Reactor Coolant System 7.6.2.1 VT-1 8-G-2 32 1 3,2 1
1 2 0 ISI-0369-C
- b. Chemical and Q
. Volume E
. Control S System -7.6.2.2 VT-1 M 5-G-2 02 02 0 0
- c. Residual 0 CHM-2335-C 4 Heat Removal H System -P 7.6.2.3 VT-1 B-G-2 6 6 to 0 3 3
- d. Safety CHM-2336-C E sn Injection i System 7.6.2.4 VT-1 B-G-2 142 142 5 6 3 OM-2333-C E E
I 2The change in valve bolting numbers was due to the UIC4 RTD Mod. Tne change in valve bolting numbers'is in accordance with Code Case N-426. 550 11' "
, 2.'
O Mo
.~ 1a
=
M a
.e .n O
.u ,
w
- TABLE A SEQEYAH INSERVICE INSPECTION PROGRAM CLASS 1 COMPONENTS Program Section XI 40 Yr. Sarple 1st Irsp. Interval Reference Exam Es'am No. Length .~o . Length Inspection Perleds Reference w tn Conconent' Section Method Catecorv Welds /of weld Velds /of Vefd 3 vrs. 7 vrs. 10 ves. DW No. @j
.e<
F. Valves (cont'd) - @[
' n t~
' 2. Integrally Welded " d t' Support Mes6ers 7.6.3 PT 8-K-1 Totals are included in D.S of this table. o E-
- Q:
- 3. Component Supports 7.6.4 VT-3, 8-K-2 Totals are included in D.6 of this table'.
VT-4
- 4. Valve Badles
>4" N.P.S. 7.6.6 VT-1 8-M-2 See Table 1 of Attachment 2 o
G. System Pressure Test 7.9 VT-2 B-P See Program Section 7.9 .O 4 e21
.g.
g i; 1 C 3 n N 1EL
- '. i
*8L R o' 5 5' M- K4 -U T R e:
n u I
TABLE 8', SEQUOYMi INSERVICE INSPECTION PROGRAM + CLASS 2 COMPONENTS - c Program . Section XI 40 Yr. Sample : 1st Insp. Interval Reference Exam Eman No. Length . No. Length Inspection Periods Reference Camoonent Section Method Cateocrv Welds /of Veld Weids/of V_g1J _3.. yrs. 7 vrs. 10 vrs. Dwo. No. lyE m yr A. Steam Generators.- LN N~
- 1. Circumferential Uh
~Shell Welds 8.1.1 C-A UT 4 Gens /3 Welds (12) 3 1 1 1 ISI-0399-C. 'Eo' M
- 2. Circumferential Head Wolds 8.1.2 UT C-A 4 Gens /1 Weld (4) 1 Weld /46 ft. IS' 15' 16' ISI-0399-C
- 3. Tubesheet-to-
- 'Shell Weld 8.1.3 UT C-A 4 Gent /1 Weld (4) 1 Weld /36 ft. 12' 12' 12' ISI-0399-C-
~
- 4. Norale-to-Vessel n Veld and Inside o Radius $-
o.
.a. Norrle-to-
= Vessel Welds 8.1.4 UT,MT C-8 4 Gens /2Nor(8) 8 2 3 3 ISI-0399-C * "[.
- b. Nozz1e-to- 'h' Vessel
.Inside Radius 8.1.4 UT C-8 4 Gens /2Nor(8) 8 1 4 3 ISI-0399-C' >
w B.-Heat Exchanaers- E:
, m
- 1. Residual Heat Removal 8 Heat Exchancers (2) g
- a. RHRHX Circum-
- ferential U.
'Shell Weld 8.2.1.1 .. UT C-A 2Ht.En./Tweld(2) I weld /113" 37" -38" 38" CHM-2404-A ~*
er aw.
>+ -.
- "L
- 8 ;. -
E[
' to '. ;g-p V
g. f e. n *
. ga T ,
4 y g " e- ' ' - Ir" c- Y y- ,S- % -. -eev % + = e- * . e e %.-w
TABLE 8
,s
-SEQUDYAH INSERVICE INSPECTION PROGRAM CLASS 2 COMPONENTS Program'
' Reference Enam .. Section Exam XI 40 No.Yr.' Sample ~ 1st Length' No.- Insp. Interval Inspection Periods-l Reference' Length
- Hm.
' Camponent Section Method Cateoorv Welds /of Weld Welds /of Weld 3 vrs. 7 vrs. 10'vrs. Dwo. No. .j $.
H <: B. Heat Euchanoers (cont'd) ~ E $5 o ra
- b. RHRHX Cireum- '
.forential. .
d "'
. o5-Head Wold 8.2.1.2 UT' C-A 2Ht.En./1 Weld (2). I weld /113" 37" 38" 33* CHM-2404-A *Q
- c. RHRHX Norale-to-Vessel Welds 8.2.2 PII C-8 2Ht.Ex./2Nor.(4) 4 1 , 1 2 CHM-2404-A '
4
-: d. ' RHRHX Integrally -
- Velded ' On
' Supports 8.2.3 PT C-C 2Ht.Es./2 Welds- 2 1 0 1 CHM-2404-A E.
(4)
- e. RHRHX Component . -
['! . Supports ' 8.2.4 VT-3 C-E 2Ht.En./2 Sprts. 4 1 -1 2 CHM-2404-A : y
-(4) g.
C. Tanks $ E' m
- 1. CCP Tank (Boron-Injection ,
-Tank) (1)
M.
- a. CCP Tank- "
Ci rcumferential . Shell/ Head H Weld '8.5.1 UT- '.C-A 1 Tank /2 Welds 2 1 0 1 ISI-0069-A I See Request for Relief 151-13, PT examination only. - .e w m ; ; i
. J .* M -
- - :; t. .
.o.
.O -
p a;;
- eg
- . g ..
5 . if W
.g ,
e. g . kr
--'iM-.'
- p =4sg 7
=wi ~
qg ,y g ig g9h g g %vc , , , 4.. . ,, _,
TA8LE 8 SEQUDYAH INSERVICE INSPECTION Mt0 GRAM CLASS 2 COMPONENTS
' Program .
Section XI 40.Yr. Sample ~ 1st Insp. Interval Reference Exam i Eram No. Length No. Length Inspection Periods
Reference:
.. y h '
'Camponent Section -Method Cateoorv ' Welds /of Weld Walds/of Weld 3 vrs. 7 vrs. 10 vrs . Dwo. No. en so '
-C. Tanks (cont'd) '. NNL c-w
- b. CCP Tank :q p;
. Nozzle -- w g-to Vessei '@ n
. es -
Welds .8.5.2 UT.MT C-B' 1 Tack /2Nor; 1 1 0 ISI-0069-A
- c. .. CCP Tank
' Integrally Welded -
Supports .8.5.3 PT C-C 1 Tank /4IA 4 0: 2 2 ISI-0069-A n'
-d. CCP Tank
'. Component. Ih.
.. g
' Supports. '8.5.4 VT-3 C-E 4 .4 1 .1 2 ISI-0069-A z-19
, s. CCP Tank Pressure 5'
Retalning g Bolting "g
>2" Dia. 8.5.5 UT C-0 I Ny/16 Studs 1Ny " ta 1 0 0 ISI-0069-A to .
tn D. Ploine s-
- 1. Intearally Weided Sucoorts
{;
- a. Residual Heat ' "
Removal .. ' **.. System 8.9.1.1' PT C-C- 01 01 0. 0 0' CHM-2435-C: I The change in support ' numbers duringlthe second period was due to new code class boundaries.
.5EO~
t f '. n*2'
- g ;.,
O mo' - - . y $. e,, .
- Ut O .
l
- o g. '
D' n =0;- O
.y O'
... . . . - . .- . .2 -
TABLE B SEQUDYAH INSERVICE INSPECTION PR0rAAM ' CLASS 2 COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval
~ Reference Exam Exam No. Length- No. Length Inspection Periots Conoonent Reference w c1 Section Method Cateoorv Welds /of weld Velds /of Weld 3 vrs. 7 vrs. 10 vrs. Dwo. No. %h H<
D. Ploino (cont'd) . EC
- b. Safety Injec- n t*
tion System 8.9.1.2 41 '3 d C* PT C-C 43 1 0 0 4 CHM-2435-C oE'
- c. Main Steam Systom 8.9.1.3 MT C-C 1,11 ' 101 0 4 6 CHM-2438-C
- d. Feedwater System 8.9.1.4 MT C-C 5*4 1
5*4 1 2 1 2 CHM-2439-C
- 2. Ploina and Valve Component Suooorts n
- a. Residual Heat k av Removal System 8.9.2.1 VT-3, C-E 851 ,2 851 ,2 25 27 33 CHM-2435-C es VT-4 4
- b. Safety injection System 8.9.2.2 371 , 2 "5
VT-3 C-E 571
- 2 18 22 17 CHM-2436-C G.
VT-4 en
- c. Main Steam t System 8.9.2.3 VT-3, C-E 4615 461 , 5 8 16 22 CHM-2438-C VT-4 @
w e I w 2 The change in support numbers was due to new code class boundaries. 3 The change in support nienbers was due to new code class boundaries in accordance with IWC-1220 (a). 4 The change in support numbers was due to mods of the IAs and new code class boundaries in accordance with IWC-1220 (a). The change in support numbers was due to mods of the IAs. 5 The change in support numbers was due to mods.
=o so on
- E) E E-
% ~~ .
O* O
- mo m
u Y Q . T g g: n e W-9 v-
TABLE 8 , SEQUOYAH INSERVICE INSPECTION PROGRAM CLASS 2 COMPONENTS Progran Section XI 40 Yr. Sample 1st Insp. Interval Reference Esam Exam No. Length No. Length Inspection Periods Comoonent Section Method Catecorv Velds /of Veld Reference Velds /ef Veld 3 vrs. 7 vrs. 10 vrs. Dwa. No. yy m :o D. Ploing (Continued) H <: g$ n t~
- d. Feedwater ' H t*'
Systee 8.9.2.4 VT-3, VT-4 C-E 311 311 10 10 11 O S 2439-C 55
- e. Containment Spray Systes B.9.2.5 VT-3, C-E 5 5 1 2 2 CHM-2440-C VT-4
- 3. Circumferential and Longitudinal . O o
- a. Residual Heat Removal Systee
- 1. RHR Clres >1/2" Noe. Vall Thickness E.
8.9.4.1 IS UT.PT C-F 271 7I 2 2 3 CHM-2336-C 4
- 2. RHR Long. >1/2" Nom. Wall Thick, ness 8.9.4.1 UT PT C-r 61 21 1 1 0 CHM-2335-0 ta
- 3. RHR.Cires 11/2" Nom. Vall Thickners c 8.9.4.1 PT C-F 1181 301 9 10 11 CHM-2336-C
- 4. RHR Long. 11/2" Nom. Wall Thickness 8.9.4.1 C-F 48I N
PT 121 3 4 5 0 6 2335-C y w l The change in weld numbers was due to new code class boundaries. 550' t 1.L-O
- O *
** .y tau ' rr M E M i e
- n. e O
.Q .,
w
y TABLE B SEQUDYAH INSERVICE INSPECTION PROGRAM CLASS 2 COMPONENTS Program Section XI 40 Yr. Sample 1st Insp. Interval Reference Enam Eram No. Length No. Length Inspection Periods Conconent Section Method Cateoorv Velds /ef Veld Velds /of Veld 3 vrs. 7 vrt. 10 vrs. them. No. Reference gg mm D. Pipino (cont'd) +4 < EU
- b. Safety Injectior System O"
- 1. SIS Clres >1/2" Nom. Wall Thickness
-E O
3 8.9.4.2 UT.PT C-F 401 101 3 3 4 N334 ts
- 2. SIS Cires 11/2= Nom. Vall Thickness 8.9.4.2 PT C-F 541 141 4 5 5 CHM-2333-C
- 3. SIS Long. 11/2" Nom. Vall Thickness 8.9.4.2 PT. C-F 241 -6I I I 4 33 < b
- c. Main Steam System- g
- 1. MS Cires >1/2" Nom. Val) Thickness E to 8.9.4.3 UT,MT C-F 131 41 1 1 2 C m-2340-C 5
- 2. MS Long. >1/2" Nom. Vall Thickness 9 8.9.4.3 UT,HT C-F 5 2 0 2 O Citt-23404 h
- d. Feedwater Systen E
- 1. FW Clres >1/2" Nom. Vall Thickness 8.9.4.4 UT,MT C-F 15 4 1 2 1 CHM-2339-C c
=
- 2. FW Long >1/2" Neun. Vall Thickness E 8.9.4.4 UT.MT- C-F 1 1 0 0 1 CHM-2339-C *'
I The change in weld numbers was due to new code class boundaries. 55O
% ;i. l.
.7, r O
8L
- Ni o e.s .W a
.8 +
g .". 4 % - . - . -- . - _ _ , _ . _ , . _ . _ . . - _ _ . _ _ , _ . m -
TABLE 8 SEQUCYMi INSERVICE INSPECTION PROGRAM CLASS 2 COMPONENTS Program Reference Esan Section XI 40 Yr. Sample 1st Insp. Interval Component Enne No. Length No. Length Inspection Periods Reference Section Method Catecorv Veldt /of Veli Velds /of Weld 3 vrt. 7 vrr. 10 vrt. Dws. y@ Ms. D. Elging (cont'd) gg
- d. Feedwater System (cont'd) ON OE
*g
- 3. FV Cires 11/2" Nom. Wall Thickness 8.9.4.4 MT C-F 1 O es8' 0 See Note 1
- e. Containment Spray System
- 1. CS Cires 11/2* Nom. Wall Thickness 8.9.4.5 PT C-F 6 1 0 1 0 CHM-2422-C
- 2. CS Long. 11/2" Nom. Wall Thickness 8.9.4.5 PT C-F O
2 1 0 0 1 x CHM-2422-C E. Puser 3
=
!3
- 1. Residual Heat Removal (2) RHRP 4
- a. RHRP Ceeponent supports N 8.10.1.2 VT-3 C-E 2 2 tn 0 1 ISI-C353-8 F. System Pressure 1
E sn In1 8.12 VT-2 C-H See Program Section 8.12 . c 5 n I w Examination not scheduled this Interval.
?50 2 li. 2.
.? ~ .
"8L No O M M
$ E e
n li u- e A' e
TABLE C SE7J0YAH INSERVICE INSFECTION PROGRAM CtASS 3 COMPONENTS Prograsi Reference Esan Section XI 40 Yr. Sample 1st Insp. Interval Component Enam No. Length No. Length Section Method Cateoorv Weldt/of Veld Inspection Periods . Reference y@ Welds /of Veld 3 vrs. 7 ves. 10 vrs.~ A. Pipino Dws. Ms. gg
- 1. All ASME 9.0 VT-2 D-A, D-8, M/A D
Cia:s 3 D-C N/A 1001 100% 1001 N/A flw F (Equivalent) Og- ~ B. Comoonent in lupports
- 1. Auxillary 9.1.1 VT-3, 0-A 381 Feedwater 381 38 35 VI-4 38 ISI-4113-C System
- 2. Chemical and 9.1.2 VT-3 N/A 0 I=2 8
Volume Control VT-4 021 0 0 0 Systee
~~
235 Y ts
- 3. Component 9.1.3 Cooling VT-3 D-A D-8 2551 4 2551 4 ,2 W 231 2554 5.
VT-4 ISI-0126-C g Systee
- 4. Containment 9.1.4 YT-3 D-8 01 t,s Spray System 01 0 0 vi-4 0 "
t
- 5. Essential Raw 9.1.5 VT-3 D-A, D-8 Cooling Water 3674 3671 *4 248Ia4 331 3674 System YT-4 873 ISI-0123-C E
.H I w 2 The change in support numbers was due to new code class boundaries.
3 Examinations performed during cycle 3B corrective actionsand forCHS-8700-10 CAQRs CHS-8700-05The for support
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c 3 H ~- I 2 The change in support num6ers was due to new cods class boundaries. t' Examinations examinations performed during not identifled cycle during the38 asperled. first corrective actions for CAQR's 015-8700-06 and CHS 8700-10 for support 3 Change in support number due to CCHK modification. IEI 2 2. -
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