Text

Rev 0 of PSL-201, St Lucie Nuclear Power Plant,Unit 2 Second ISI Interval ISI Selected Component Schedule.
	ML17228A247
Person / Time
Site:	Saint Lucie
Issue date:	07/24/1993
From:	Anderson E; FLORIDA POWER & LIGHT CO.
To:	;
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ML17228A245	List: ML17228A244; ML17228A246; ML17228A247;
References
	PSL-201, NUDOCS 9308110242
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NUCLEAR ENGINEERING DEPARTMENT EQUIPMENTj SUPPORT>.AND. INSPECTIONS GROUP P.O. Box 14000 JUNo BEAcH, FLoRIDA 33408 St. Lucie Niiclear Power Plant Unit 2 SECOND INSERVICE. 1NSPECTION INTERVAL PROGRAM PLAN-"AND,SCHEDULE Prepared by Florida Power and Light Company, Code Programs Section i For N

St. Lucie Nuclear Power'Plant, 10 Miles South of Ft. Pier'ce'on A1A Ft.'Pierce, Florida 33034 Commercial Service Date: August 8, 1983 NRC Docket Number: 50-389 Document Number: PSL-200 Reyision Number: 0 Date: July 24, 1993 Prepared by:

r. Specialist Inservice Inspection Revyeyyed by:

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SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION ~ REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 LIST OF EFFECTIVE PAGES SECTION PAGES CHANGE DATE Cover Sheet 1 thru 1 0 July 24, 1993 List of Effective Pages 2thru 2 0 July 24, 1993 Table of Contents 3 thru 8 0 July 24, 1993

'ecord of Revision 9 fhru 9 0 July 24, 1993 Abbreviations 10 thru 12 0 Ju/y 24, 1993 Glossary of Terms 13 fhru 16 0 July 24, 1993 Abstract 17 fhru 17 July 24, 1993 SECTIONS July 24, 1993 1 Introduction 18 thru 26 July 24, 1993 2 Class 1 Systems 27 thIQ 38 July 24, 1993 3 Class 2 Systems 39 thru 48. July 24, 1993 4 Class 3 Systems . 49 fhru 55 July 24, 1993 5 Component Supports 56 fhru 58 July 24, 1993 6 Augmented Examinations 59 thru 60 July 24, 1993 7 Relief Requests 61 thru 64 July 24, 1993 8 Acceptance Criteria 65 thru 73 July 24, 1993 9 ASME Code Boundaries 74 thAI 77 July 24, 1993 10 Repairs and. Replacemeri ts 78 thru S1 July 24, 1993 11 Records 82 thru 90 APPENDICES A Class 1 Tables 91 1>>28 0 July 24, 1993 B Class 2 Tables 92 29-40 0 Ju/y 24, 1993 C Class 3 Tables 9341-45 0 July 24, 1993 D Class 1 Support Tables 9446-49 0 July 24, 1993 E Class 2 Support T dies 9550- 54 .0 July 24, 1993 F Class 3 Supp Tables 96 55- 59 0 July 24, 1993 G Relief Regu sts 97- 272 0 July 24, 1993 Page 2 of 272

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SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 TABLE OF CONTENTS LIST OF EFFECTIVE PAGES ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 2 TABLE OF CONTENTS ......................................... 3 RECORD OF REVISION.......................................... 9 ABBREVIATIONS ........................................... 10 GLOSSARY, OF TERMS.....................'................... 13 ABS TRAC T ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ o e ~ ~ o r ~ ~ ~ 17 1e0 INTRODUCTION o ~ ~ ~ ~ ~ ~ ~ r ~ ~ ~ r ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ r '

r ~ ~ ~ ~ r ~ ~ e ~ r ~ ~ 18 1.1 Inspection Intervals .................................. 18 1.1.1 First Inspection Interval ........................... 18 1.1.2 Second Inspecfion Interval .............;......... 18 1.2 Inspection Period ..................................... 18 1.3 Applicable Documents ................................ 19 1.4 Program Exclusions/Exceptions ......................... 20 I

1.4.1 Inservice Testing Program ................. 20 1.4.2 Steam Generator Eddy Current Testing Program ... 21 1.4.3 Snubber Examination and Testing Program ... 21 1.4.4 Inservice System Pressure Test Program 21 1.4.5 Repair and Replacement Program ........... 21 1.5 Applicable Code Editions and Addenda ................... 21 1.5.1 Preservice Inspection 21 1.5.2 First Inspection Interval .......... 21 1.5.3 Second Inspection Interval 22 1.5.4 Subsequent Code Edition and Addenda ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 22 1.6 System Quality Group Classifications .................... 22 1.6.1 Quality Group A ..................... 22 Qualify Group B .....................

~ ~ ~ ~ ~ ~ 0 1.6.2 ~ i ~ ~ ~ ~ 0 23 Page 3 of 272

SECOND INSPECTION INTERVAL'SL<<200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 1.6.3 Quality Group C............ 23 1.6.4 Quality Group D ............ ~ ~ ' ~ ~ ~ ~ r l ~ ~ ~ ~ ~ e ~ ~ ~ ~ 23

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7 1.6.5 Application 23 1.6.6 Optional Construction ~ ~ ~ ~ 23 1.6.7 Piping Penetrating Containment ~ ~ ~ ~ 23 1.6.8 Classificafion Diagrams ...... 24 1.7 Inspecfron Program B............................ 24 1.7.1 Class 1, 2 and 3 Components 24 1.7.2 Component Supports ............................ 25 1.8 Development of Inspection Plan.........................

1.9 Class MC Componenfs ................................ 26 1.10 Substitute Examinations 26 2.0 CLASS 1 SYSTEMSICOMPONENTS 27 2.1 ASME Code Exempfions Employed ...................... 27 2.2 Component/Piping Examination Basis .................... 27 2.2.1 Category B-A ................ 27 2.2.2 Category B-B 29 2.2.3 Category B-D ................

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30 2.2.4 Cafegory B-E ............ 31 2.2.5 Category B-F ................ 31 2.2.6 Category B-G-1 32 2.2.7 Category B-G-2 33 2.2.8 Category B-H B-J

................ 34 2.2.9 Cafegory 34 2.2.10 Category B-K-1 35 2.2.11 Category B-L-1 and B-L-2 ...... 35 2.2.12 Category B-M-1 and B-M-2 36 2.2.13 Category B-N-1, B-N-2, and B-N-3 36 2.2.14 Category B-0 ................ 37 2.2.15 Category B-P........ 37 2.2.16 Category B-Q................ 38 3.0 CLASS 2 SYSTEMSICOMPONENTS 39 3.1 ASME Code Exemptions Employed ... 39 3 1 1 IWC 1221 I 39

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3.1.2 IWC 1222 ~ . 40 Page 4 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 3 1<<3 I <<C <<230

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ << ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 40 3;2 Component/Piping Examination Basis 40 3.2.1 Category C-A .. 40 3.2.2 Category C-B .. 41 3.2.3 Category C-C .. 43 3.2.4 Category C-D .. 43 3.2.5 Category C-F-1 . 44 3.2.6 Category C-F-2 . 45 3.2.7 Category C-G .. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ <<<< ~ 46 3.2.8 Category C-H .. 47 4.0 Class 3 Systems/Components 49

'.1 ASME Code Exemptions Employed 49 4.1.1 IWD-1220.1 .... 49 4.1.2 IWD-1220.2 .... 49

. 4.2 Component/System Examination Development 49 4.2.1 Category D-A ............. 49 4.2.2 Category D-B ..;.......... 51

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

4.2.3 Category D-C 53 4.2.4 System Pressure Tests 54 5.0 CLASS 1, 2, and 3 COMPONENT SUPPORTS 56 5.1 ASME Code Exemptions Employed <<

~ << ~ 56 5.2 Support Examination Development 56 5.2.1 Category F A 56 5.2.2 Category F-B 56 5.2.3 Category F-C ....... 56 5.3 Narrative Discussion 56 5.3.1 Category F-A, F-B, F-C......................... 57 6.0 AUGMENTED EXAMINATIONS 59 6.1 Class 1 .................. 59 6.1.1 Reactor Coolant Pump .......................... 59 6.1.2 Steam Generator Tubes ......................... 59 Page 5 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 6.1.3 Reactor Pressure Vessel ................... 59

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6.1.4 NRC Bullefin 88-11 ~ ~ ~ o ~ 60 6.1.5 LER 93-04............................... ~ ~ ~ ~ ~ 60 6.2 Class 2 ........................................... 60 6.2.1 Standard Review Plan 6.6 ....................... 60 6.2.2 NRC Bulletin 79-13 ...................;......... 60 7:0 RELIEF REQUESTS ....................................... 61 7.1 First Ten Year Inspection Interval ...................... 61 7.2 Second Irispection Interval............................ 61 7.3 Relief'Request Format ............................... 61 8.0 ACCEPTANCE CRITERIA ................................... 65 8.1 Acceptance by Examination ............................ 65 8.2 Accepfance by Repair ................................. 65 8.3 Acceptance by Replacement ............................ 65 8.4 Acceptance by Analytical Evaluation ..................... 66 8.4.1 Class 1 Components 66 8.4.2 Class 2 Components 66 8.5 Accepfance by Engineering Evaluation .................... 66 8.6 Acceptance by Correction .............................. 67 8.7 Acceptance by Supplemental Examination ~ ~ ~ e ~ ~ r ~ r ~ e ~ ~ ~ ~ ~ ~ 68 8.8 Acceptance Criteria in Course of Preparation ............... 68 8.9 Additional Examinafions ............................... 68 8.9.1 Class 1 68 8.9.2 Class 2 69 8.9.3 Class 3 69 8.9.4 Component Supports ~ ~ ~ ~ 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 70 8.10 Defects Found Outside Section XI Examination ~ ~ ~ ~ ~ ~ ~ ~ e)l ~ ~ 70 Page 6 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 8.11 Minimum Thread Engagement .......................... 71 9.0 BOUNDARY CLASSIFICATIONS .............................. 74 9.1 Program Boundary Diagrams ........................... 74

~e 9 .2 Color Couing 74 10.0 REPAIRS, REPLACEMENTS and MODIFICATIONS ............... 78 10.1 Repairs ................. 78 10.1.1 Repair Operations ...... 78 10.1.2 Prc "sure Testing ....... 78 10.1.3 Baseline Examinations 78 1 0.2 Replacements ..................................... 79 10.2.1 Replacement Operations . 79 10.2.2 Engineering Approval .'. 79 10.2.3 Preservice Examinations . 79 1 0.3 A C'e Modifications 80 1 0.4 Evaluation ......................................... 80 1 O.G Access 80 10.6 Construction Codes ................................. 80 10.7 Authorized Nuclear Inservice Inspector .................. 81 10.8 Implementations .................... 81 11.0 RECORDS ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ 0 ~ ~ 82 1 1.1 General ........................... 82 11.2 Inservice Inspection Summary Report ... 82 1 1.3 Cover Sheet ....................................... 82 11.4 Summary Report Submittal 82 LIST OF FIGURES FIGURE 11-1 Form NIS-1 Report................................. 84 Page 7 of 272

SECOND INSPECT/ON INTERVAL PSL<<200 INSERVICE INSPECT!ON REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 FIGURE 11-2 Form NIS-2 Report................................. 85 FIGURE 11.3 Form NIS-BB Report ............................... 88.

UST OF TABLES TABLE 1-7 Inspection Program B ............................. 25 TABLE 7-1 Relief Request Status ............................... 63 TABLE 8-1 Corrective Action................................. 71 TABLE 8-2 CLASS 1 ACCEPTANCE STANDARDS ................. 72 TABLE 8-3. CLASS 2 ACCEPTANCE STANDARDS ................. ....72 TABLE 8-4 CLASS 3 ACCEPTANCE STANDARDS ................. 73 TABLE 8-5 COMPONENT SUPPORT ACCEPTANCE STANDARDS 73 TABLE 9-.1 Program Boundary Drawings........................'. 75 TABLE 10-1 Construction Codes ................................ 81 APPENDICES APPENDIX A Class 1 Summary Tables ........................... 91

.APPENDIX B Class 2 Summary Tables ............................ 92 APPENDIX C Class 3 Summary Tables ....... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 93 APPENDIX D Class 1 Support Summary Tables e e ~ ~ r ~ ~ r e r r ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 94 APPENDIX E Class 2 Support Summary Tables ~ ~ ~ e ~ ~ e e ~ ~ ~ ~ ~ ~ ~ ~ r ~ r ~ ~ 95 APPENDIX F Class 3 Support Summary Tables ~ ~ ~ ~ ~ ~ ~ ~ ~ r ~ ~ ~ ~ ~ ~ ~ ~ r ~ ~ 96 APPENDIX G Relief Requests ................................... 97 Page 8 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 RECORD OF REVISION REVISION DATE AFFECTED REASON FOR REVISION No. PAGES July 24, 1993 Enfire Updated Inservice Inspection Document Program Plan as required by 10 CFR 50.55a(g)(4) for the Second Ten Year Inservice Inspection Interval Page 9 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 ABBREVIATIONS Listed below are the abbreviations utilized in this document:

ANII Authorized Nuclear Inservice Inspector ANSI American Nuclear Standard Institute

'ASME American Society of Mechanical Engineers B&PV Boiler & Pressure Vessel Code Branch Connection CCW Component Cooling Wafer CCW Counterclockwise CEDM Confrol Element Drive Mechanism CFR Code of Federal Regulafions CH Charging System CHR Containment Heat Removal CPS Code Programs Section CRS Code Required Surface CRV Code Required Volume CTMT SPRAY Containment Spray CVCS Chemical & Volume Control Sysfem CW Clockwise ECCS Emergency Core Cooling System ECT Eddy Current Testing (Examination)

ESI Equipment Support and Inspections FPL Florida Power & Light Company FPS Fuel Pool System FSAR Final Safety Analysis Report Feedwater System HPSI High Pressure Safety Injection HS High Stress HX Heaf Exchanger Page 10 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 ID Inside Diameter IE'S/

Inspection and Enforcement Inservice Inspection 1ST Inservice Testing JPN Juno Nuclear Engineering LER License Event Report

'LPSI Low Pressure Safety Injection LS Long Seam MOV Motor Operated Valve MSIV Main Steam Isolation Valve MS Main Steam System MT Magnetic Particle Testing (Examination)

NIA Not Applicable NDE Nondesfrucfive Examination NPS Nominal Pipe Size OD Outside Diameter PDS Program Boundary Drawings P&ID Piping and Instrumentation Diagram PSI Preservice Inspection PIO Part of PSL-2 St. Lucie Unit 2 PT Liquid Penetrant Testing (Examination)

QA Quality Assurance QC Qualify Confrol QP Quality Procedure PZR Pressurizer RCS Reactor Coolant System RCP Reactor Coolant Pump RHR Residual Heat Removal RPV Reactor Pressure Vessel SD Structural Discontinuity Page 11 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 SDC Shutdown Cooling SDCHx Shutdown Cooling Heat Exchanger SG Steam Generator SRP Standard Review Plan SIS Safety Injection System Thickness of Component, Pipe, etc.

'TE Terminal End USNRC United States Nuclear Regulatory Commission UT Ultrasonic Testing (Examination) ~

Visual Testing (Examination)

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SECOND /NSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 GLOSSARY OF TERMS ASSESS - fo determine by evaluation of data compared with previously obtained data such as operating data or design specifications.

AUTHORIZED INSPECTION AGENCY - an organization thatis empowered by an enforcement authority to provide inspection personnel and services as required by Section XI.

AUTHORIZED NUCLEAR INSERVICE INSPECTOR - a person who is employed and has been qualified by an authorized Inspection Agency to verify that examinations, tests and repairs (that do notinclude welding or brazing) are peiformed iii ac"'ordance with fhe rules and requirements of Section XI.

AUTHORIZED NUCLEAR INSPECTOR - an employee of an authorized Inspection Agency who has been qualified in accordance with NCA-5000 of Section lll.

COMPONENT. - an, item in a nuclear power plant such as a vessel, pump, valve or piping system.

COMPONENT STANDARD SUPPORT - a support consisting of one or more generally mass-produced units usually refened to as catalog items.

COMPONENT SUPPORT - a metal support designed to transmit loads from a component to the load-carrying building or foundation structure.

Component supports include piping supports and encompass those structural elements relied upon to either support the weight or provide structural stability to components.

CONSTRUCTION -an all-inclusive term comprising materials, design, fabrication, .

examination, testing, inspection and certification required in the manufacturer and installation of items.

CONSTRUCTION CODE - the body of technical requirements that governed the construction of the item.

DEFECT - a flaw (imperfection or unintentional discontinuity) of such size, shape, orientation, location or properties as fo be rejectable.

DISCONTINUITY - a lack of continuity or cohesion; an intenuption in fhe normal physical structure of material or a product.

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SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 ENFORCEMENT AUTHORITY - a regional or local governing body, such as a State or Municipality of the United States or a Province of Canada, empowered to enact and enforce Boiler and Pressure Vessel Code legislation.

ENGINEERING EVALUATION- an evaluation ofindications that exceed allowable acceptance standards to determine if fhe margins required by the

.Design Specification and fhe Construction Code are maintained.

EVALUATION- the process of determining the significance of examination or of fest results, including the comparison of examination or test results with applicable acceptance criteria or previous results.

EXAMINATION CATEGORY - a grouping of items to be examined or este'd.

FLAW - an imperfection or unintentional discontinuity that is detectable by nondestructive examination.

GENERAL CORROSION - an approximately uniform wastage of a surface of a component through chemical or electro-chemical action, free of deep pits and cracks.

GROSS STRUCTURAL DISCONTINUITY- definedin NB-3213.2. Examples include junctions between shells of different thickness, cylinder shell-to-conical shell junctions; HANGER - an item that carnes the weight of components or piping from above with fhe supporting member being mainly in tension.

IMPERFECTION - a condition of being imperfect; a departure of a quality characteristic from its intended condition.

INDICATION - fhe response or evidence from the application of a nondestructive examination.

INSERVICE EXAMINATION - the process of visual, surface, or volumetric examination performed in accordance with the rules and requirements of Section XI.

INSERVICE INSPECTION - methods and actions for assuring the structural and pressure-retaining integrity of safety-related nuclear power plant components in accordance with the rules of Section XI.

INSERVICE TEST - a test to determine the operational readiness of a component or system.

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SECOND INSPECT!ON INTERVAL PSL<<200

/NSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 INSPECTION - verification of the performance of examinations and tests by an Inspector NSPECTION PROGRAM- the plan and schedule for performing examinations or tests.

INSPECTOR - an Authorized Nuclear Inservice Inspector, except for those instances where so designated as Authorized Nuclear Inspector.

INSPECTION INTERVAL - a duration of time, 10-years.

INSPECTION PERIOD - a duration of time within an inspection interval, as determined by Plant Technical Specifications andlor Inspection Program B of Section XI.

ITEM - a material, part, appurtenance, piping sub-assembly, component or component support.

MAINTENANCE - routine servicing or work undertaken to correct, adjust or prevent an abnormal or unsatisfactory condition.

NONDESTRUCTIVE EXAMINATION - an examination by the visual, surface or volumetric method.

NOMINAL PIPE SIZE - a designation assigned for the purpose of convenient specification of pipe size.

OPERATIONAL READ/NESS - The ability of a component or system to perform ifs intended function when required.

OWNER - fhe organization legally responsible for the operation, maintenance, safety and power generation of fhe nuclear power plant.

AUTHORITY - a federal government agency, such as the United'EGULATORY States Nuclear Regulatory Commission, that is empowered to issue and enforce regulations affecting the design, construction, and operation of nuclear power plants.

RELEVANT CONDITION - a condition observed during a visual examination that requires supplemental examinations, corrective measures, repair, replacement or analytical evaluation. Relevant conditions do not include fabrication marks, material roughness, and other conditions acceptable by material, design and manufacturing specifications of the component.

REPAIR - the process of restoring a nonconforming item by welding, brazing, or meta/ removal such that existing design requirements are met.

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SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 REPAIR ORGANIZATION - the organization that replaces or repairs components or systems under the provisions of the Owners's Qualify Assurance Program. The Owner may be the repair organization.

SUBSEQUENT PERIOD -is the, next following period, even ifitisinthe following interval.

SUPPORT - (1) an item used to position components, resist gravity, resist dynamic loading, or maintain egui%brium of components; (2) anitem that carries fhe weight of a component or piping from below with fhe supporting members being mainly in compression.

STRUCTURAL DISCONTINUITY - As used in this program: includes pipe weld joints to vessel nozzles, valve bodies, pump casings, pipe f!t'!!igs ~

(such as tees, elbows, reducers, flanges, efc. conforming fo ANSI B16.9) and pipe branch connections and fittings.

TERMINAL ENDS - the extremities of piping runs that connect of structures, components, or pipe anchors, each of which acts as a rigid restraint or provides af least 2 degrees of restraint to piping thermal expansion.

TEST - a procedure to obtain information through measurement or observation to determine the operational readiness of a component or system while under controlled conditions.

VARIABLESPRING TYPE SUPPORT - a spring type support providing a variable supporting force throughout a specified deflection.

VERIFY - to determine that a particular action has been performed in accordance with fhe rules and requirements of Section XI either by witnessing the action or by reviewing records.

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SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION 'EVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 ABSTRACT This document describes the updated bases and plans for fhe Second Ten-Year Inservice Inspection Interval for St. Lucie Nuclear Power Plant, Unit No. 2.

This program identifies those components and/or systems (including supports) which are classified ASME Code Class 1, Class 2, and Class 3, and subject to examination and testing, 'set forth in the applicable Edition of the ASME Boiler ppd Pressure Vessel Code, to the extent practical within the limitations of design, geometry and materials of construction of the components as stated in 10 CFR 50.55a (b)(2).

The program was developed and prepared to meet the latest ASME Boiler and Pressure Vessel Code,Section XI Edition, endorsed by 10 CFR 50.55a (b)(2), on a date 12 months prior to the start of the Second Inspection Interval, except

. design and access provisions and preservice examination requirements set forth in 10 CFR 50.55a (g)(4).

The applicable Code Edition is the 1989 Edition, hereafter referred to as the Code.

Where an examination required by Section Xlis determined fo beimpractical, the basis for this determination is included- within this program in the form of a Request for Relief.

Summary Tables for each system subject to-examination is included, which provides Code classification, Code examination category, Code item number, types of components, examinations to be performed, and the number of examinations required to be examined for the interval.

Additional requirements for augmented inspections are also addressed.

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SEC C ON INTERVAL PSL-200 INSERVICE /NSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 1.0 /NTRODUCTION This document details the Inservice Inspection Program Plan and schedule for the Second Ten-Year Inservice Inspection Interval for St. Lucie Nuclear Power Plant, Unit No. 2.

The Construction permit for St. Lucie Nuclear Power Plant Unit 2 was issued on May 2, 1977. Florida Power and Light Company is the Owner of Record.

The Operating License for St. Lucie Nuclear Power Plant Unit 2 was issued on April 6, 1983.

The Commercial Service Date for St. Lucie Nuclear Power Plant Unit 2 was August 8, 1983.

1.1 INSPECTION INTERVALS 1.1.1 First Inspection Interval The First Inservice Inspection Interval became effective on August 8, 1983 and ended on August 8, 1993.

1.1.2 Second Inspection Interval The Second Inservice Inspection Interval becomes effective on August 8, 1993 and is scheduled to end on August 8, 2003.

1.2 INSPECTION PERIODS The Second Inservice Inspection Interval is divided into three successive inspection period as determined by calendar years of plant service within theinterval. Identified below are the period dates for fhe second inspection interval.

PERIOD START END August 8, 1993 August 8, 1996 August 8, 1996 August 8, 2000 August 8, 2000 August 8, 2003 Page 18 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 1.3 APPLICABLE DOCUMENTS The Inservice Inspection Program Plan for ASME Code Class 1, Class 2 and Class 3 systems and components (and their supports) was developed after giving due consideration to the following documents and subject to the limitations and modifications listedin 10 CFR 50.55a(b), and to fhe extent practical within the limitations of design, geometry and materials of construction.

10 CFR 50.55(a) Code of Federal Regulations, dated August 6, 1992 ASME Boiler and Pressure Vessel Code, Sections V, 1989 Edition, "Nondestructive Examination"

. ASME Boiler and Pressure Vessel Code, Section Xl, 1989 Edition, "Rules for Inservice Inspection of Nuclear Power Plant Components" USNRC Regulatory Guides The following list of Regulatory Guides are applicable fo the PSL-2 ISI Program Plan:

1. 14 Reactor Coolant Pump Flywheel Integrity Revision 1, August 1975 1.26 Quality Group Classifications and Standards for Water-Steam, and Radioactive-Waste-Containing Components of Nuclear Power Plants, Revision 3, February 1976 1.65 Materials and Inspections for Reactor Pressure Vessel Closure Studs, October 1973 1.83 lnservice Inspection ofPressurized Water Reactor Steam Generator Tubes, Revision 1, July 1975 1.150 Ultrasonic Testing of Reactor Vessel Welds during Preservice and Inservice Examinations, Revision 1, 1983 St. Lucie Unit 2 Final Safety Analysis Report Page 19 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE /NSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 Sf. Lucie Unit 2 Technical Specifications, Docket number 50-389, Sections 4.0.5, 3/4.4.5, 3/4.4.11, 3/4.7.9-USNRC Standard Review Plan 6.6, Section /.8, Augmented Inservice Inspection of Class 2 Welds.

Branch Technical Position APSCB 3.1, paragraph B.2.c(4)

USNRC Bulletins 88-11 Pressurizer Surge Line Thermal Stratification USNRC Informational Notices 93-20 Thermal Fatigue Cracking of Feedwafer Piping to Steam Generators, dated March 24, 1993 ASME Code Cases N-307-1 Revised Ultrasonic Examination Volume for Class 1 Bolting, Table IWB-2500-1, Examination Category B-G-1, When Examinations are Conducted from the Center-Drilled Hole N-355 Calibration Block for Angle Beam Ultrasonic Examination of Large Fittings in accordance with Appendix Il/-3410.

N-460 Alternative E'xamination Coverage for Class 1 and Class 2 Welds.

N-481 Alternative Examination Requirements for Cast Austenitic Pump Casings.

N-498 Alternative Rules for10-Year Hydrostatic Pressure Testing for Class 1 and Class 2 Systems.

1.4 PROGRAM EXCLUSIONSIEXCEPTIONS Inservice Inspection Programs, Plans and Schedules that are outside the scope of this document are as follows:

1.4.1 Inservice Testing Program The program for Inservice Testing of Class 1, Class 2, and Class 3 Pumps and Valves is addressed separately, in accordance with 10CFR50.55a(f).

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SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 1.4.2 Steam Generator Eddy Current Tesfing Program The program for Steam Generator Eddy Current Tubing is governed by the requirements of the St. Lucie Plant Technical Specificafions, Secfion 3/4.4.5.

1.4.3 Snubber Examination and Test Program The program for fhe examination and testing of safety-relafed Snubbers is governed by fhe St. Lucie Plant Technical Specifications, Section 3/4.7.9.

1.4.4 Inservice System Pressure Test Program The program for Inservice System Pressure Testing of ASME Code Class 1, Class 2 and Class 3 componenfs and systems is addressed in a separate document.

1.4.5 Repair and Replacement Pro gram The Repair and Replacement Program for ASME Code Class 1, Class 2 and Class 3 component and systems is addressed by Plant procedures.

1.5 APPLICABLE CODE EDITIONS AND ADDENDA Piping and interconnecting welds to components were installed in accordance fo the rules of ASME Section III, 1977 Edition through Summer 1977 Addenda, for those system classified as Class 1, 2, arid 3.

1.5.1 Preservice Inspection The Preservice Inspecfion was conducted in accordance with the 1977 Edition through Summer 1978 Addenda of the ASME B&PV Code,Section XI.

1.5.2 First Inspecfion Interval The First Ten-Year Inservice Inspection was conducted in accordance with fhe 1980 Edifion thru Winter 1980 Addenda of Section XI, except for system pressure tests, performed to Winter 1981 Addenda.

Page 21 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 1.5.3 Second Inspection Interval Pursuant to Title 10, Part 50, Section 55a(g)(4), of the Code of Federal Regulations, the Inservice Inspection requirements applicable to nondestructive examination andsystem pressure testing for the Second Inservice Inspection Interval is based on the rules set forth in fhe 1989 Edition of Section XI, that was endorsed twelve months prior to the start of the second inspection interval.

1.5.4 Subsequent Code Editions and Addenda As permitted by 10 CFR 50.55a(g)(4)(iv), FPL may elect to meet the requirements sef forth in subsequent Editions and Addenda of Section XI that are incorporated by reference into 10 CFR 50.55a(b)(2), subject to the applicable limitations and modification and subject to USNRC approval.

Portions of Editions and Addenda may also be used provided that all related requirements fo the respective Edition and Addenda are met. FPL intends to continually evaluate and apply, as appropriate, changes in adopted Code Editions and Addenda which provides the continuing assurance of the quality and safety of pressure containing components and systems.

1.6 SYSTEM QUALITYGROUP CLASSIFICATIONS System safety classifications, design and fabrication requirements meet the intent of 10 CFR 50.2v and Regulatory Guide 1.26, as identified within fhe St. Lucie Unit 2 FSAR.

, Water, steam and radioactive containing components (other than turbines and condensers) are designated Qualify Group A, B, C or D in accordance with their importance to safety.

1.6.1 Quality Group A Qualify Group A system boundaries are developed based on 10 CFR 50.2(v), and the St. Lucie Unit 2 FSAR, and applies to the reactor coolant pressure boundary components.

Page 22 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 1.6.2 Qualify Group B Quality Group B system boundaries are developed based on Regulatory Guide 1.26 and the St. Lucie Unit 2 FSAR, and applies to those components of the Reactor Coolant System notin Qualify Group A.

1.6.3 Quality Group C Quality Group C system boundaries are developed based on Regulatory Guide 1.26 and the St. Lucie Unit 2 FSAR, and applies to those components that are notin Qualify Group A or B.

1.6.4 Quality Group D Qualify Group D applies to those components not related to nuclear safety.

1.6.5 Application Application of the rules of Section XI are governed by the group classification criteria as defined above. The rules of IWB, IWC, and IWD were applied to those systems whose components are classified ASME Class 1, 2, or 3, (Qualify Group A, B, or C).

1.6.6 Optional Construction of an Component Optional construction of a component within a system boundary to a classification higher than the minimum class established in fhe component Design Specification shall not fhe overall system classification by which the applicable 'ffect rules of Section XI are determined.

1.6.7 Piping Penetrating Containment The portions ofpiping that penetrates fhe containment vessel which is required to be constructed to Class 1 or 2 rules for piping and which may differ from fhe classification of fhe balance of the piping system, need not affect the overall system classification that determines the applicable rules of Section XI.

Page 23 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 1.6.8 Classification Diagrams System Qualify Group classification interfaces between components of different quality groups are designated on

. various system piping andinstrument diagrams (PID s). These designations are transferred fo Color Coded Program Boundary Diagrams which show the specific pressure boundaries for the Class 1, Class 2, and Class 3 systems subject fo nondestructive examination and testing. See Section 9.0.

1.7 INSPECTION PROGRAM B The inspection intervals comply with IWA-2432, Inspection Program With the exceptions of fhe examinations identified in 1.7.1, the reguired examinations in each examination category shall, be completed in accordance with Table 1-7.

1.7.1 Class 1, Class 2, and Class 3 Components The required examinations in each Examination Category shall be completed during each inspection interval, in accordance with IWB-2412-1, IWC-2412-1, and IWD-2412-1, with the following exceptions:

(1) Examination Categories B-N-1, B-P, B-Q, C-H, and the system pressure test requirements of D-A, D-B and D-C; (2) the percentage required by Note 2 of Examination Category B-D; (3) fhe examinations that may be deferred to the end of an inspection interval, as specified in Table IWB-2500-1.

(4) .If there are less than three items to be examined in an Examination Category, fhe items may be examined in any fwo periods, or in any one period if there is only one item, in lieu of fhe percentage reguirements of Table 1-7 below.

(5) Where components, (example; steam generators, and pressurizer), cover several examination categories, program optimization will be performed to examine all items at the same time to reduce costs and radiation exposure.

Page 24 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 1.7.2 Component Supports The required examinations shall be completed in accordance with the inspection schedule established for the components under IWB, IWC, and /WD.

TABLE 1-7 INSPECTION PROGRAM B Inspection . Inspection Minimum 'aximum Interval Period Calendar Examination Examination Years of Plant Completed, % =-.Credited, %

Service Within (Note (1)g fhe Interval St. Lucie Unit 2 16 34 Second Inservice

'nspection 50 67 Interval 10 100 100 Note: (1) Except as noted in Table IWB-2500-1, B1.30.

Note: (1) The examination of shel/-to-flange welds may be performed during the first and third inspection periods in conjunction with fhe nozzle examinations of examination category B-D. At least 50% of shell-to-flange welds, shall be examined by the end of the First Inspection Period, and fhe remainder by the end of the Third Inspection Interva/.

(2) At least 25% but not more than,50% (credited) of the nozzles shall be examined by fhe end of the first inspection period, and the.

remainder by fhe end of fhe lastinspection period, of the respective inspection interval. (See paragraph 1.7.1 (2)).

1.8 DEVELOPMENT OF INSPECTION PROGRAM PLAN Section 2 through 6 details the narrative description of the St. Lucie Unit 2 Inservice Inspection Program Plan basis for Class 1, Class 2, Class 3, Component, including Component Supports and Augmented Examinations of components and/or systems subject to.

examination/test.

Page 25 of 272

SECOND INSPECTION INTERVAL PSL-200

/NSERVICE /NSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 1.9 Class MC Components 10 CFR 50.55a presentlyincorporates only those portions of Section XI that address inservice inspection requirements for Class 1, Class 2, and 3 components and their supports. The regulation does not currently'address the inservice inspection of containments. Since this amendment is only intended to update current regulatory requirements to include the latest ASME,Code Edition and Addenda, the requirements of Subsection IWE would not be imposed upon Commission licensees by this amendment.

As per the above Subsection IWE of Section XI is exempted, and therefore will not be addressed in this Program.

The incorporation by reference Subsection IWE info 50.55a'is presently the subject of a separate rule making action.

Reference:

Federal Register, Vol. 57, No. 152, Dated August 6, 1992 1.10 SUBSTITUTE HNMINATIONS FPL may substitute items scheduled in this Program Plan for others not previously scheduled when the original selection was part of the additional sample. This substitution may be done due to such conditions as limited physical access, high radiation levels, etc.

Such changes will be noted in fhe Summary Report submittal; Specific examinations that are required, and can not be completed within fhe periodlinferva/ wil/ be identified within the Summary Report, and as applicable, may be the subject of a request for relief..

Page 26 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 20 CLASS -1 SYSTEMS/COMPONENTS The Class 1'system boundaries subject fo examination and testing were developed based upon the requirements of 10 CFR 50.2(v) and FPL PSL FSAR. The Class 1 components and systems (including supports) subject to examinafion and tesfing are described in detail below:

2.1 ASME Code Exemptions Employed IWB-1220 - The following components (or parts of componenfs) are exempfed from fhe volumetric and surface examination requirements of IWB-2500'a)

Compon;nts that are connected to the Reactor Coolant System and part of the reacfor Coolant pressure boundary and that are of such a size and shape so fhat upon postulated rupture the resulting flow of coolant from the reacfor coolant system under normal plant operating conditions is within fhe capacity of makeup sysfems which are operable from on-site emergency power.

(b) 1. Piping of 1" nomina/ pipe size and smaller, except steam generator tubing; and

2. Components and their connections in piping of 1" nominal pipe size and smaller.

(c) Reactor Vessel head connections and associafed piping, 2" nominal pipe size and smaller, made inaccessible by control rod drive penefrafions.

2.2 Component/Piping Examination Development Class 1 components subject fo examination are identified in Appendix A.

The Class 1 Summary Tables satisfy the requirements of IWA-2420 (a) (1) through (6) respectively.

A narrative discussion of Class 1 components subject to examination and testing are described in detail below:

2.2.1 Category B-A Pressure Retaining Welds in Reacfor Vessel.

All examinations are performed from the inside diameter surface using remote examination equipment and automated volumetric examination techniques. The addifional requirements of Regulatory Guide 1.150 are incorporated.

I Page 27 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 Items B1.11 B1.12 - Shell Welds Scope of Examination - 100% of all longitudinal and circumferential shell welds (does not include shell to flange weld).

2 B1.11 Circumferential shell welds 9 B1.12 Longitudinal shell welds Subject of Relief Request Number 1 Items B1.21 B1.22 - Bottom Head Welds Scope of Examination - 100% of accessible length of circumferential and meridional head welds.'

B1.21 Circumferential head weld 6 B1.22 Meridional head welds Subject of Relief Request Number 1 Items B1.21 B1.22 - To Head Welds Scope of Examination - 100% of accessible length of circumferential and meridional head welds.

1 B1.21 Circumferential head welds 4 B1.22 Meridional head welds Subject of Relief Request Number 1 and 14 Item B1.30 - Shell-to-Flan e Weld Scope of Examination - 100% of fhe shell to flange weld.

1 Circumferential shell to flange weld Note: The examination may be performed during the first and third inspection periods in conjunction with the nozzle examinations of Code Category B-D (Program B). At least 50% of the weld shall be examined by the end of the first inspection period, and fhe remainder by the end of the third inspection period.

Subject of Relief Request Number 1 and 14 Page 28 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 Item B1.40 - Head fo Flan e Weld Scope of Examination - 100%.of fhe head to flange weld.

1 Circumferential head to flange weld Subject of relief Request Number 1 and 14 Item B1.51 - Re air Welds Belt/inc Re ion Not applicable fo St. Lucie Unit 2.

2.22 Category B-B - Pressure Retaining welds in vessels other than Reactor Vessels.

Allexaminations are performed from the outside diameter surface of the components.

Pressurizer: Items B2.11 B2.12 Shell fo Head Welds

. Scope of Examination - 100% of both shell to head welds and 1 ft. on one intersecting longitudinal weld at each circ. we/d.

2 B2.11 Circumferential welds 4 B2.12 Longitudinal welds, (2) required

'he following Code Cases were imp/emented for the Repair of fhe Pressurizer and RTD Nozzles during the First Inspection Interval:

N-432, Repair Welding Using Automatic or Machine Gas .

Tungsten-Arc Welding (GTAW) Temperbead Technique, Section X/, Division 1.

N-20-1, SB-163 Nickel-Chromium-Iron Tubing (Alloys 600 and 690) and Nicke/-Iron-Chromium AlloySOO at a Specified Minimum Yield Strength of 40.0 ksi, Section II/, Division 1, Class 1.

Subject of Relief Request Number 14 Pressurizer: Items B2.21 B2.22 Head Welds Scope of Examination - 100% of 1 circumferential and 1 meridional weld per head.

No B2.21 head circumferential welds No B2.22 head meridional welds Page 29 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 Steam Generator: Items B2.31 B2.32 Head Welds Scope of Examination - 100% of one circumferential and one meridional weld per head.

The examinations are limited to one vessel among the group of vessels performing a similar function). SG-2A will be examined.

5 B2.31 Circumferential welds per generator (1 examined on SG-2A) 9 B2.32 Meridional welds per generator (2 examined on SG-2A)

Subject of Relief Request Number 2 and 14 Steam Generators: Items B2.40 Tubesheet to Head Welds Scope of Examination: 100% of one weld on one vessel. (SG-2A selected) 1 Tubesheet to head weld per vessel Subject of Relief Request Number 14 Items B2.51 B2.52 B2.60 B2.70 B2.80 - Heat Exchan er Welds Not applicable to St. Lucie Unit 2.

2.2.3 Category B-D, Full Penetration Welds of Nozzle in Vessels (Program B)

Reactor Vessels: Items B3.90 B3.100 <<Nozzle to Vessel Welds and Nozzle Inside Radius Section Scope of Examination - 100% of all nozzles 6 B3.90 RPV Nozzle Welds 6 83.100 RPV Nozzle Inner Radius Subject of Relief Request Number 1 and 14 Pressurizer: Items B3.110 B3.120 - Nozzle to Vessel Welds and Nozzle Inside Radius Sections Scope of Examination - 100% of all nozzles 6 B3.110 PRZ Nozzle Welds 6 B3.120 Nozzle Inner Radius Page 30 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 Subject of Relief Request Number 3 and 14 Steam Generators: Items B3.130 B3.'140 - Nozzle to Vessel Welds and Nozzle Inside Radius Sections Scope of Examination - 100% of all nozzles 6 B3.130 Nozzle to Vessel Welds (3 per vessel) 6 B3.140 Nozzle Inner Radius (3 per vessel)

Subject of Reli.f Request Number 3 and 14 Heat Exchan er: Items B3.150 B3.160 Not applicable fo St. Lucie Unit 2.

2.2.4 Category B-E, Pressure Retaining Partial Penetration Welds in Vessels Items B4.11 B4.12 B4.13 - Vessel Nozzles Control Rod Drive Nozzles Instrumentation Nozzles Scope of Examination - Visual VT-2 examination on 25%'of all partial penetration welds each interval. These examinations and tests are part of fhe Plant Pressure Test Program. See paragraph 1.4.4 for details.

B4.11 Vessel nozzles B4.12 Control rod drive nozzles B4. 13 Instrumentation nozzles Pressurizer: Item B4.20 - Heater Penetration Wefds Scope of Examination - Visual VT-2 examinations on all heater penetration welds each interval. These examinations and tests are part of the Plant Pressure Test Program. See paragraph 1.4;4 for details.

B4.20 Heater penetration welds 2.2.5 Categogr B-F - Pressure Retaining Dissimilar Metal Welds Reactor Vessel: Items B5.10 B5.20 B5.30 Nof Applicable to St. Lucie Unit 2.

Page 31 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 Pressurizer: Items B5.40 B5.50 B5.60 <<Nozzle fo Safe End Butt Welds > or = 4'-'NPS (4" NPS Socket Welds Scope of. Examination - .100% of all dissimilar metal welds each interval.

6 B5.40 Safe End Buff Welds No B5.50 & B5.60 Subject of Relief Request Number 14 Steam Generator: Items B5.70 B5.SO B5.90 Not Applicable to St. Lucie Unit 2.

Heat Exchan er: Ifems B5.100 B5.110 B5.120 Not Applicable to St. Lucie Unit 2.

Pi in: Items B5.130 B5.140 B5.150 - Dissimilar Metal Butt Welds )

or = 4" NPS ( 4" NPS Socket Weld Scope of Examination - 100% of all welds each interval.

15 B5.130 > or = 4" NPS dissimilar buff welds 10 B5.140 < 4" NPS dissimilar butt welds No B5.150 No dissimilar socket welds Subject of Relief Request Number 5 22.6 Category.B-G Pressure Retaining Bolting, Greafer Than 2 in. In Diameter Reactor Vessel: Items B6.10 B6.30 B6.40 B6.50 Scope of Examination - 100% of required exams each interval.

.Volumetric examinations are .conducted from the center-drilled holes, subject of Code Case N-307-1.

54 B6.10 Nuts B6.20 Studs in Place - Not applicable to Sf. Lucie Unit 2 54 B6.30 Studs 54 B6.40 Threads in Ligaments 108 B6.50 Washers Subject fo Relief Request Number 14 Page 32 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 Pressurizer: Items B6.60 B6.70 B6.80 Not applicable to St. Lucie Unit 2 Steam Generators: Items B6.90 B6.100 B6.110 Not applicable to St. Lucie Unit 2 Heaf Exchan er: Items B6.120 B6.130 B6.140 Not applicable to St. Lucie Unit 2 Pi in: Items B6.150 B6.160 B6.170

-'of applicable to St. Lucie Unit 2 Pum s: Items B6.180 B6.190 B6.200 Scope of Examination - 100% of the below listed items in one Reacfor Coolant Pump in fhe interval.

Volumetric examinafions are conducfed from fhe center-drilled holes, subject of Code Case N-307-1.

64 B6.180 Sfuds (16 Studs per pump) 4 B6.190 Pump Flange Surfaces 64 B6.200 Nuts, Washers (16 Nuts per pump)

Note: For heat exchanger, piping, pumps, and valves, examinations are limifed to components selected for examination under categories B-B, B-J, B-L-2 and B-M-2.

Valves: Items B6.210 B6.220 B6.230 Not applicable fo St. Lucie Unit 2 2.2.7 Category B-G Pressure Retaining Bolting, 2 in. And Less in Diamefer Items: B7.10 B7.20 B7.30 B7.40 B7.50 B7.60 B7.70 B7.80 Scope of Examination - Visual VT-1 examination each interval limited to components selected for examination under B-B, B-J, B-L-2, and B-M-2.

8 B7.10 RPV 2 B7.20 PRZ Page 33 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE /NSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 8 B7.30 SG-AIB B7.40 Hx - Not Applicable PSL-2 11 '7.50 Piping F/ange Bolting (9) selected B7.60 Pump - Not Applicable PSL-2 27 BT.TO Valves (7) selecfed B7.80 CRD Housing - Not Applicable PSL-2 Subject of Relief Request Number 14 2.2.8 Category B-H, Integral Affachments for Vessels Reactor Vessel: Item B8.10 - Inte ra/i Welded Affachment, Nc '.."pp/I"able to St. Lucie Unit 2. Nozzle Lugs are forged wifh fhe vessel nozzle.

Pressurizer: Item B8.20 - Infe ra/i Welded Attachment Scope ofExamination - 100% surface exam ofsupport skirt to vessel:

weld.

Steam Generator: /tern B8.30 - Inte ra/i Welded Affachment Scope of Examination - 100% surface exam of the support skirt fo .

vessel weld of one of the fwo'sfeam generators (SG-2A) selected.

Heat Exchan er: Item B8.40 - Inte ra/i Welded Attachment Nof Applicable to St. Lucie Unit 2.

2.2.9, Category EM, assure Retaining Welds in Piping Items: B9.11 B9.12 B9.21 B9.22 B9.31 B9.32 B9.40 Scope of Examinafion.- All dissimilar meta/ pipe welds,-high stress welds, terminal ends, plus an additional number of piping welds so fhat '25% of all nonexempt circumferential and branch connecfion pipe welds are examined. All longifudina/ pipe welds intersecting. any of the selected circumferential welds will also be examined.

229 B9.11, 67 selected 123 B9.21, 32 selected 7 B9.31, 1 selected 15 B9.32, 4 selected 157 B9.40, 72 selected 531 Circ. Welds subject fo examination, 176 selected (33%)

Page 34 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 64 Long. Welds subject to examination, 26 selected (40%)

See Appendix A Tables for details.

Subject of Relief Request Number 2, 5, 6 and 14 2.2.10 Category B-K-1, Integral Affachments fo Piping Pumps 8 Valves Ifems: B10.10 B10.20 Scope of Examination - All integrally welded attachmr.nts with a design thickness of 5/8 inch and greafer. The examinations include only the welded affachments fo piping required to be examined under.=". m.'nafion Category B-J and the welded affachments to pumps associated with this piping. The multi-component concept is not applicable to this examination category.

8 B10.10 Integral Attachments 16 B10.20 Infegral Affachments Item: B10.30 Nof applicable to St. Lucie Unit 2.

2.2.11 Category B-L-1, Pressure Refaining Weldsin Pump Casings, B-L-2, Pump Casings Item: B12.10 Scope of Examination: 100% volumetric examination of all welds in one of the four Reacfor Coolant Pumps. Code Case N-481 will be utilized as an alternate to the examination requirements. A Visual VT-1 examinafion of the external surfaces of fhe welds of one pump casing during fheinferval shall be selected. The pump selected shall be based on pump disassembly for maintenance under B-L-2 or end of inspection interval, whichever comes first.

- 8 Welds subject to exam, 2 per Pump, 2 required Item: B12.20 Scope of Examination: Visual examination ofinterior surfaces of one of the four Reactor Coolant Pumps when disassembled for maintenance. Pump to be identified when pump is disassembled.

- 4 Pumps, 1 required Page 35 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 2.2.12 Category B-N-1, Pressure Retaining Welds in Valve Bodies, B-N-2, Valve Bodies Items: B12.30 B12.40 Not applicable to St. Lucie Unit 2.

Item: B12.50 Scope of Examination - Visual VT-3 examination of at least one valve in a group of valves once per interval when disassembled for maintenance or repair. Valves to be identified when valve is disassembled.

Group 1 (4) 12" Check Valves, 1 required Group 2 (4) 12" Gate Valves, 1 required Group 3 (5) 10" Gate Valves, 1 required Group 4 (4) 6" Check Valves, 1 required 2.2.13 Category B-N-1,. Infenor of Reactor Vessel, B-N-2,: Integrally Welded Core Support Structures and Inferior Affachments to Reactor Vessels, B-N-3, Removable Core Support. Structures.

Item: B13.10 Scope of Examination - Visual VT-3 examination of accessible areas (areas above and below the reactor core made accessible for examination by removal of components during normal refueling),

once each inspection period.

Items: B13.20 B13.30 B13.40 Not applicable to St. Lucie Unit 2.

Item: B13.50 Scope of Examination - Inferior attachments within the beltline region (once per interval).

6 Inferior Affachments Item: B13.60 Scope of Examination - Interior affachments beyond the beltline region (once per interval).

14 Interior Attachments Page 36 of 272

SECOND /NSPECTION /NTERVAL PSL-200 INSERVICE INSPECTION 'EVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 Item: B13.70 Scope of Examination - Visual examinafion of accessible surfaces of core supporf structures when removed from the vessel (once per interval). Performed in conjunction with examination Category B-A.

2.2.14 Category B-O, Pressure Retaining Weldsin Confro/Rod Housings Item: B14.10 Not applicable to St. Lucie Unit 2, no welds exist.

2.2.15 Category B-P, AllPressure Retainin g Components Items: B15.10 B15.11 B15.20 B15.21 B15.30 B15.31 B15.50 B15.51 B15.60 B15.61 B15.70 B15.71 Scope of Examinafion - System pressure tests are conducted on Class 1 sysfems and components, as follows:

(a) A S stem Leaka e Test /WA-5211(a) -is conducted prior to plant startup following each reactor refueling outage.

The pressure retaining boundary subject to the leakage test corresponds fo the reactor coolant system boundary, as established with all valves aligned as required by approved plant operating procedures for startup and normal reactor operation. The VT-2 examinafion boundary extends to include the second closed valve at fhe boundary extremity, which may be a check valve opposing Reactor Coolant sysfem pressure.

The test is conducfed at system operating temperature and pressure.

(b) A S stem H drostafic Test: will be performed in accordance with alfernate examination techniques of Code Case N-498 Alternative Rules for 10-Year Hydrostatic Pressure Testing for Class 1 Systems, Section X/, Division 1 as noted below:

As an alternative to the 10-Year hydrostatic pressure test required by Table IWB-2500-1, Category B-P, FPL willperform the following:

(1) A system leakage fest (IWB-5221) shall. be conducted at or near the end of each inspection interva/, prior to reactor startup.

Page 37 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 (2) The boundary subject fo test pressurization during the system leakage test shall extend to all Class 1 pressure retaining components within the system boundary.

(3) Prior to performing VT.-2 visual examination, the system shall be pressurized to nominal operating pressure for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for insulated systems and 10 minutes for non-insulated systems. The system shall be maintained at nominal operating pressure during the performance of the VT-2 visual examination. FPL does nof intend to remove insulation (i.e. mechanical connections) for the sole purpose of testing.

(4) Test '-";p"futures and pressures shall not exceed limiting conditions for hydrostatic test curve as contained in fhe plant Technical Specifications.

(5) The VT-2 visual examination shall include all components within fhe boundaryidenfifiedin (2) above.

All ASME Section XI Pressure Testing requirements are controlled by site procedures. The system boundaries subject to system leakage and system hydrostatic tests are shown on the Color Coded Program Boundary Diagrams (See Section 9.0). Details of fhe system pressure test program are defined in paragraph 1.4.4.

2.2.16 Category B-Q, Steam Generator Tubing Item: B16.10 - Steam Generator Tubin in Sfrai ht Tube Desi n Not applicable to St. Lucie 2 Item: B16.20 - Steam Generator'ubin in U-Tube Desi n Scope of Examination - The extent and frequency. of examination is.

governed in accordance with fhe St. Lucie 2 Plant Technical Specifications.

Page 38 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 3.0 CLASS 2 SYSTEMSlCOMPONENTS The Class 2 System Boundaries were developed based upon the requirements .

of Regulatory Guide 1.26 and the FPL - PSL-2-FSAR.

The Class.. 2 components and systems (including supports) subject to examination and testing are described in detail below:

3.1 ASME Code E'xempfions Employed IWC-1220 - The following components (or parts of components) are

. exempted from the volumetric and surface examination requirements of IWC-2500; 3.1.1 IWC-1221 - Components within RHR, ECC and CHR systems (or portions of systems).

(a). Vessels, piping, pumps, valves, and.other components NPS 4 and smaller in all systems except high pressure safety injection systems of pressurized water reactor plants.

(b) Vessels, piping, pumps, valves, and other components NPS 1 1/2 and smaller in high pressure safety injection systems of pressurized water reactor plants.

(c) Component connections NPS 4 and smaller (including nozzles, socket fittings, and other connections) in vessels, piping, pumps, valves, and other components of any size in all systems except high pressure safety injection systems of pressurized water reactor plants.

(d) Component connections NPS 1 1/2 and smaller (including nozzles, socket fittings, and other connections) in vessels, piping, pumps, valves, and other components of any size in high pressure safety. injection systems of pressurized water reactor plants.

(e) Vessels, piping, pumps,'alves, other components, and component connections of any size in statically pressurized, passive (i.e., no pumps) safety injection systems of pressurized water reactor plants.

(f) Piping and other components of any size beyond fhe last shutoff valve in open ended portions of systems that do not contain water. during normal. plant operating conditions.

Page 39 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 3.1.2 IWC-1222 - Components within systems (or. portions of systems) other than RHR, ECC and CHR systems

.. (a) Vessels, piping, pumps, valves,'nd other components NPS 4and smaller.

(b) Component connections NPS 4 and smaller (including nozzles, "

socket fittings, and other connections) in vessels, piping, pumps, valves, and other components of any size.

(c) Vessels, piping, pumps, valves, other compon.nts, and component connections of any size in systems or portions of systems that operate (when fhe system function is required) at a pressure equal to or less than 275 prig ","-. at a. temperature equal to or less than 200 degrees F.

(d) Piping and other components of any size beyond the last shutoff-valve in open ended portions of systems that,do not contain water during normal plant operating conditions.

3.1.3 IWC-1230 - Concrete Encased Components.

Piping support members and piping support components that are encased in concrete shall be exempted from the examination requirements of IWC-2500.

3.2 Component/Piping Examination Development Class 2 components subject to examination are identified in Appendix B.

The Class 2 Summary Tables satisfy fhe requirements of IWA-2420 (a) (1) through (6) respectively.

A narrative discussion of Class 2 components subject to examination and testing are described in detail below:

3.2.1 Category C-A, Pressure Retaining Welds in Pressure Vessels Item C1.10 - Shell Circumferential Welds Scope of Examination: 100% of all welds at gross structural discontinuities only. The examinations are limited to one vessel among a group of vessels. Components applicable fo:

Steam Generators 2A and 2B - Second extension ring to lower shell, intermediate shell to cone, cone to upper shell, dome to torus welds.

All volumetric, examinations are performed from the Outside Diameter surface of SG-2A.

Page 40 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 Shutdown Cooling Heat Exchanger - Allvolumetric examinations are performed manually from the Outside Diameter surface of 2A Heat Exchanger.

Areas examined include,fhe flange fo body weld on the primary waterbox of one Heat Exchanger (2A).

Subject to Relief Request Number S Item C1.20 - Head Circumferential Welds Scope of examination: 100% of head-to-shell welds, (limited to one vessel of multiple vessels). Components applicable to:

Steam Generators 2A and 2B - Weld to be examined on SG-2A - Top head to upper shell weld.

Shutdown Cooling Heat Exchanger - Not applicable.

Subject to Relief Request Number S Item C1.30 - Tubesheet to Shell Welds Scope of examination: 100% of fubesheet to shell welds (limited to one vessel of multiple vessels). Components applicable to:

Steam Generators 2A and 2B - Welds to be examined on SG-2A-Secondary extension ring to tubesheet, stay cylinder dome to tubesheet weld.

Shutdown Cooling Heat Exchanger - Weld to be examined on heat exchanger 2A - Body fo tubesheet weld.

3.2.2 Category C-B, Pressure Retaining Nozzle Welds in Vessels Item C2.10 and C2.11 Not applicable fo PSL-2.

Item C2.20 C2.21 and C2.22 Nozzles without Reinforcing Plate in Vessels > 1/2" T.

Subject to Relief Request Number 9 Page 41 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE /NSPECTION REVISION '0 PROGRAM PLAN AND SCHEDULE July 24, 1993 Item C2.21 - Nozzle fo Shell or Head Welds Scope of Examination - All nozzles at terminal ends of piping runs

,(limited to one vessel of multiple vessels).

Applicable to Steam Generators 2A and 2B. The Main Steam and Feedwafer Nozzles of SG-2A shall be examined.

Item C2.22 - Nozzle Inside Radius Section Scope of Examination - All nozzles at terminal ends of piping runs (limited to one vessel of multiple vessels).

Applicable to Steam Generators 2A and 2B. The Main Steam and Feedwater Nozzle Inner Radius Sections ofSG-2A shall be examined.

Item C2.30 C2.31 C2.32 & C2.33 Nozzles with Reinforcing Plate in Vessels > 1/2" T.

Item C2.31 - Reinforcin Plate Welds to Nozzle and Vessel Scope of Examination - All nozzles at terminal ends of piping runs (limited fo one vessel. of multiple vessels).

Applicable to Shutdown Cooling Heat Exchanger 2A and 2B." Inlet and Outlet Nozzles of Heat Exchanger 2A shall be examined.,

Item C2.32 Nozzle to Shell or Head Welds When Inside of Vessel is Accessible > 1/2 inch.

Not applicable to PSL-2 Item C2.33 - Nozzle.to Shel/ or Head Welds When Inside of Vessel is Inaccessible Scope of Examination '- Visual VT-2 of fell tale hole in reinforcing plates .,

(limited to one vessel of multiple vessels). Examination performed in with system pressure test program. 'ccordance Applicable to Shutdown Cooling Heat Exchanger 2A and 2B. Inlet and Outlet nozzle reinforcing plates of Heat Exchanger. 2A shall be examined.

Page 42 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECT/ON REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 3.2.3 Category C-C - Integral Affachmenfs for Vessels, Piping, Pumps 8 Valves

/tern C3.10 - Pressure Vessels fnte ra/i Welded Attachments Scope of Examination - 100% of required areas of each welded attachment (conducted on one vessel of multiple vessels).

Applicable to SG-2A and 2B - Eight welded attachments per generator. All attachments on SG-2A will be examined.

Item C3.20 - Pi in Inte ral/ Welded Attachments Scope of Examination - 100% of required areas of welded attachments (limited to attachments of components examined under C-F-1 and C-F-2) > 3/4" T. Multiple component concept is not applicable.

7 Integral attachments selected.

22 Integral attachments, 7 selected Item C3.30 - Pum s Inte ra/i Welded Affachments Scope of Examination - 100% of required areas of each welded attachment (limited to attachments of components examined per C-F and C-G).

Applicable to Containment Spray Pumps 2A and 2B. Three integral attachments per pump. The exams wil/ be performed on Pump 2A.

Item C3.40 - Valves lnte ra/i Welded Affachments Scope of Examination - 100% of required areas of each welded attachment (limited to attachments of those components required to be examined under Examination Categories C-F-and C-G).

Not applicable to St. Lucie Unit 2 3.2.4 Category C-D - assure Retaining Bolting > 2" in Diameter Items C4.10 C4.20 C4.30 & C4.40 Not applicable to St. Lucie Unit 2 Page 43 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION 'EVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 3.2.5 Category C-F Pressure, Retaining Welds in Austenitic Sfainless Sfeel or High Alloy Piping.

Items C5.10 C5.11 C5.12 C5.20 C5.21 C5.22 C5.30 C5.40 C5.41 and.

C5.42 Welds are selected for examination as'defined below. Refer fo'Appendix B for a summary of welds selected for examination.

(1) Recluiremenfs for examination of welds in piping < NPS 4 apply to PWR high pressure safety injection systems i'n accordance'ith fhe exemption criteria of IWC-1220.

(2) The welds selected for examination shall include'7.5%, buf not less fhan 28 welds, of all austenitic stainless sfeel of high alloy welds not exempted by IWC-1220. (The Category Total includes.

65 pipe to pipe welds, not exempted by IWC-1220, and are not required to be nondestructively examined per Examination Category C-F-1). These welds, however, were included in the total weld count fo which the 7.5% sampling rate was applied);

The Tofal welds.selected for examination is based on adding non-

exempt circumferential welds fo exempt circumferential welds and multiply by 7.5%.

Non-Exempt Welds 71S Exempt Welds 644 1362 x 7.5% = 102 minimum recluired The examinafions shall be distributed as follows:

(a) The examinations shall be disfributed among the 'Class 2 systems prorated, to fhe degree practicable, on the number of nonexempt austenitic stainless steel or high alloy welds .

in each sysfem (i.e., if a system contains 30% of the nonexempt welds, then 30% of fhe nondestructive examinations recluired by Examination Category C-F-1 should be performed on that system);

(b) Within a system, the examinations shall be cfistrrbufed among terminal ends and structural discontinuities (See

.Note (3)j below prorated, to the degree practicable, on the number of nonexempt terminal ends and sfrucfural discontinuities in that system; and Page 44 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 (c) Within each system, examinations shall be distributed between line sizes piorated to the degree practicable.

(3) Structural discontinuifies include pipe weld joints to vessel nozzles, valve bodies, pump casings, pipe fiffings (such as elbows, tees, reducers, flanges, etc., conforming to ANSI B16.9),

and pipe branch connecfions and fiftings.

(4) The welds selected for examination shall be reexamined during sub."equent inspections over the service lifefime of the piping component.

Subject to Relief Request Number 10 3.2.6 Category C-F Pressure Retaining Welds in Carbon or Low Alloy Steel Piping Items C5.60 C5.61 & C5.62 Not applicable to PSL-2 Items C5.50 C5.51 C5.52 C5.70 CG.SO C5.81 & C5.S2 Welds are selected as defined below. Refer to Appendix B for a complete summary of welds selected for examination.

(1) Requirements for examination of welds in piping < NPS 4 apply to PWR high pressure safety injecfion sysfems in accordance wifh the exemption criteria of IWC-1220.

(2) The welds selected for examination shall include 7.5%, but not less than 28 welds, of all carbon and low alloy steel welds not exempted by IWC-1220. (Some welds not exempted by IWC-1220 are not required to be nondestructively examined - per Examination Category C-F-2. These welds, however, shall be included in the total weld count to which the 7.5% sampling rate is applied).

12S C5.51, 42 selected 20 C5.S1, 6 selected 148 Items, 48 selected (32%)

42 C5.52, 18 selected (42%)

Page 45 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 Total C-F-2 Circumferential Welds 148 times 7.5% = 11.1 minimum welds required. The Total number of welds selected exceed the Code Required minimum due to Augmented Examination requirements.

The examinations shall be distributed as follows:

(a) The examination shall be distributed among the Class 2 systems prorated, to the degree practicable, on the number of nonexempt carbon and low alloy steel welds in each system (i.e., if a system contains 30% of the nonexempt welds, then 30% of the nondestructive examinations required by Examination Category C-F-2 should be performed on that"\

system);

(b) Within a system, the examination shall. be distributed among terminal ends and-structural discontinuities (See Note (3)J below prorated, to the degree practicable, on the number of nonexempt terminal ends and structural discontinuities in that system; and (c) Within each system, examinations shall be distributed between line sizes prorated to the degree practicable.

(3) Structural discontinuities include pipe weld joints to vessel

-nozzles, valve bodies, pump casings, pipe fittings (such as elbows, tees, reducers, flanges, etc., conforming to ANSI B16.9),

and pipe branch connections and fittings.

(4) The welds selected for examination shall be reexamined during subsequent inspection intervals over the service lifetime of the piping component.

(5) Only those welds showing reportable preservice transverse indications need to be examined for transverse reflectors.

Subject to Relief Request Number 10 3.2.7 Category C-G - Pressure Retaining Welds in Pumps and Va/ves Items C6.10 & C6.20 Nof applicable to PSL-2 Page 46 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 3.2.8 Category C-H - AN-Pressure Retaining Components.

Items C7.10 C7.20 C7.30 C7.40 C7.50 C7.60 C7.70 & C7.80 h

Scope of Examination - The pressure retaining components within the Class 2 system boundaries are subjected.to System Pressure Tests in accordance with IWC-5210 and visually examined (VT-2) per IWA-5240.

The tests are conducted as follows:

(a) S stem Functional Test IWA-5211(b) - For those systems or portions of systems not required to operate during normal reactor operation, but for which periodic system or component functional tests are peiformed as required by fhe Plant Technical and/or the Pump and Valve (IST) program, a VT-2 'pecifications examination is performed at least once during each period during the system or component functional test.- The boundary subject to pressurization during a System Functional Test includes only those pressure retaining components within the system boundary pressurized under the test mode required during fhe performance of fhe periodic system (or component) functional test. Nominal operating pressure of the system functional test is acceptable as system test pressure.

'he (b) A S stem H drosfafic Tes willbe performedin accordance with.

alternate examination techniques of Code Case N-498 Alternative Rules for 10-Year Hydrostatic Pressure Testing for, Class 2 Systems,Section XI, Division 1 as noted below:

As an alternative to the 10-year hydrostatic pressure test required by Table IWC-2500-1, Category C-H, FPL will perform the .

following:

(1) A system pressure test shall be conducted at or near the end of each inspection interval or during the same inspection period of each inspection interval of Inspection Program B.

(2) All ASME* Section XI Pressure Testing requirements are controlled by site procedures. The boundary subject to test.

pressurization during the system pressure test shall extend to all Class 2 components" included in those portions of systems required to operate or support fhe safety system function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required.

Page 47 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 (3) Prior to performing VT-2 visual examination, the system shall be pressurized fo nominal operating pressure for a minimum of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for insulated systems and 10 minutes for non-insulated systems. The system shall be maintained at nominal operating pressure during the performance of fhe VT-2 visual examination.

(4) The VT-2 visual examination shall include all.components within the boundary identified in (2) above.

Page 48 of 272

SECOND INSPECTION INTERVAL PSL-200

. INSERVICE /NSPECTION REVISION '0 PROGRAM PLAN AND SCHEDULE July 24, 1993 4.0 CLASS 3 SYSTEMSICOMPONENTS The Class 3 system boundaries subject to examination and testing were developed. based upon the requirements of Regulatory Guide 1.26, and the FPL PSL-2-FSAR. The Class 3 components and systems subject to examination and testing are described in detail below:

4.1 ASME Code Exemptions Employed 4.1.1 IWD-1220.1 - Integral attachments of supports and restraints to components that are 4" nominal pipe size and smaller within the system boundaries of Examination Categories D-A, D-B and D-C of Table IWD-2500-1 shall be exempt from the visual examination VT-3, except foi" the Auxi%ary Feedwater System.

4.1.2 IWD-1220.2 - Integral attachments of supports and restraints to components exceeding 4". nomina/ pipe size may be exempted provided:

(a) The components are located in systems (or portions of

. systems) whose function is not required in support of reactor residual heat- removal, containment, heat removal, and emergency core cooling; and (b) The components operate at a pressure of 275 psig or less and at a temperature of 200'93'C), or less.

4.2 Component/System Examination Development Class 3 components subject fo examination are identified in Appendix C.

The Class 3 Summary Tables satisfy the requirements, of IWA-2420 (a) (1) through (6) respectively.

A narrative discussion of Class 3 components subject to examination and testing are described in detail below:

4.2.1 D-A Systems in Support of Reactor Shutdown Function Item D1.10 - Pressure Retainin Com onenfs Scope of Examination - Perform System Inservice Test and Visual (VT-2) examination on pressure retaining components within fhe system boundary containing operating pressure during. system operation each inspection period.

Page 49 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECT/ON REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 Scope of Examination - Perform an System Hydrostatic Pressure Test and Visual (VT-2) examination on pressure retaining components at or near the end of each inspection interval.

Item D1.20 - Inte ral Attachments to Com onent Su orts and Restraints Scope of Examination - Perform Visual (VT-3) examination on all integrally welded attachments each inspection interval.

Note: In the case of multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined.

14 Integral Affachments, (14) selected Item D1.30 - Inte ral Attachments to Mechanical and H draulic Snubbers Scope of Examination - Perform Visual (VT-3) examination on all integrally welded affachments each inspection interval.

Note: In the case of multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined.

Not applicable to St. Lucie Unit 2 Item D1.40 - Inte ral Affachments to S rin T e Su orts Scope of Examination - Perform Visual (VT-3) examination on all integrally welded affachments each inspection interval.

Note: /n the case of multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined.

Integral Affachment (1) selected

/fern D1.50 - Inte ral Attachments to Constant Load T e Su orts Scope of Examination - Perform Visual (VT-3) examination on all integrally welded attachments each inspection interval.

Note: In fhe case of multiple components within a system of similar design, function, and service, the integral attachment of only one of Page 50 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 the multiple components shall be examined.

Not applicable, to St. Lucie Unit 2 Item D1.60 - Inte ral Affachment to Shock Absorbers Scope of Examination - Perform Visual (VT-3) examination on all integrally welded attachments each inspection interval.

Note: In the case of multiple components within a system of similar design, function, and service, the integral affachment of only one of the multiple components shall be e arained.

'I Not applicable fo St. Lucie Unit 2 4.2.2 D-B Systems in Support of Emergency Core Cooling, Containment Heat Removal, Atmosphere Cleanup, and Reactor Residual Heat Removal

!tern D2.10 - Pressure Retainin Com onents Scope. of Examination - Perform a System Functional Test and Visual (VT-2) examination on pressure retaining 'components within fhe system boundary at nominal operating pressure each inspection perIod.

Scope of Examination - Perform an System Hydrostatic Pressure Test and Visual (VT-2) examination on pressure retaining components at or near fhe end of each inspection interval.

Item D2.20 - Inte ra/ Affachments fo Com onent -

Su orts and Restraints Scope of Examination - Perform Visual (VT-3) examination on all integrally welded attachments each inspection interval.

Note: In the case of multiple components within a system of similar design, function, and service, the integral affachment of only one of the multiple components shal/ be examined.

66 Integral Affachmenfs, (48) selected Page 51 of 272

SECOND /NSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 Item D2.30 - Inte ral Affachments to Mechanical and H draulic Snubbers Scope of Examination - Perform Visual (VT-3) examination on all integrally welded attachments each inspection interval.

Note: In the case of multiple components within a system of similar design, function, and service, theintegral affachment of only one of the multiple components shall be examined.

1 Not applicable to St.'Lucie Unit 2 Item D2.40 - Inte ral Attachments fo S rin T e Su orts Scope of Examination - Perform Visual (VT-3) examination on all integrally welded affachments each inspection interval.

Note: In fhe case of multiple components within a system of similar design, function, and service, theintegral affachment of only one of the multiple components shall be examined.

6 Integral Affachment (6) selected Item D2.50 - Inte ral Affachments fo Constant Load T e Su orts Scope of Examination - Perform Visual (VT-3) examination on all integrally welded attachments each inspection interval.

Note: In the case of multiple components within a system of similar design, function, and service, the integral affachment of only one of the multiple components shall be examined.

Not applicable to St. Lucie Unit 2 Item D2.60 - Inte ral Attachment fo Shock Absorbers Scope of Examination - Perform Visual (VT-3) examination on all integrally welded attachments each inspection interval.

Note: In fhe case of multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined.

Not applicable to Sf. Lucie Unit 2 Page 52 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 4.2.3 D-C.Systems in Support, of Residual Heat. Removal from Spent Fuel Storage Pool Item D3.10 - Pressure Retainin Com onents Scope of Examination - Perform an System Inservice Test and Visual (VT-2) examination on pressure retaining components within the system boundary containing operating pressure during system operation each inspection period.

Scope of Examination - Perform an System Hydrostatic Pressure Test and Visual (VT-2) examination on pressure retaining components at or near the end of each inspection interval..

Item D3.20 << Inte ral Affachments fo Com onent Su orts and Restraints Scope of Examination - Perform Visual (VT-3) examination on all integrally welded attachments each inspection interval.

Note: In the case of multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined.

8 Integral Affachments, (5) selected Item D3.30 - Inte ral Attachments to Mechanical and H draulic Snubbers Scope of Examination -.Perform Visual (VT-3) examination on all integrally welded attachments each inspection interval.

Note: In fhe case of multiple components within a system of similar design, function, and service, fheintegral attachment of only one of the multiple components shall be examined.

Not applicable to St. Lucie Unit 2 Item D3.40 - Infe ral Attachments to S rin T e Su orts Scope of Examination - Perform Visual (VT-3) examination on all integrally welded affachmenfs each inspection interval.

Note: In the case of multiple components within a system of similar Page 53 of 272

SECOND /NSPECT/ON INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 design, function, and service, the integral attachment. of, only one of ~

fhe multiple components shall be examined.

J Not applicable to St. Lucie Unit 2 Item D3.50 - Inte ral Attachments to Constant Load T e Su orts Scope of Examination - Perform Visual (VT-3) examination on all integrally welded attachments each inspection inferva/.

Note: In the case of multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined.

Not applicable to St. Lucie Unit 2 Item D3.60 - Inte ral Attachment to Shock Absorbers Scope of Examination -. Perform Visual (VT-3) examination on all integrally welded attachments each inspection interval.

Note: ln the case of multiple components within a system of similar design, function, and service, the integral attachment of only one of the multiple components shall be examined.

Nof applicable fo St. Lucie Unit 2 4.2.4 System Pressuie Tests - Class 3 The pressure retaining components within fhe boundary of each system specified for Examination Categories D-A, D-B and D-C are pressure tested and visually examined (VT-2), for leakage during the following tests:

(a) S stem Inservice Test INfA-5211(c) - Eor systems required to operate during normal plant operation, a VT-2 examination is conducted at least once each period while the system is in operation and at operating pressure. The boundary subject fo test pressurization during a S stem Inservice Test extends to those pressure retaining components under operating pressures during normal system operation.

OI Page 54 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION, REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 (b) S stem Functional Test NVA-5211/)- For those systems or portions of systems not required to operate during normal operation, but for.which periodic system or component =

'eactor functional fesfs are performed as required by the Plant Technical Specifications and/or the Pump and Valve (IST)

~hi p g V7..2* i ti dd i gth yt ip,f d th*t~dft tU ti p t.

The boundary subject to pressurtzation during a ~Sstem Functional Test includes ~onl those pressure retaining components within the system boundary pressurized under.

the test mode required during the performance of the periodic.

system (or component) functional test; Nominal operating pressure of .the system functional test is acceptable as the

"<<stem test pressure.

and (c) S sfem H drostatic Test IWA-5211(d) -is performed on Class 3 systems oncein each interval. The boundary subject to test

. pressurization extends up to and includes the first normally closed valve or valve capable of automatic closure as required to perform the safety-related system funcfion.

The system pressure requirements. are defined in sub-article IWD-5223 of the Code. The VT-2 examination performed during a system hydrostatic fest is used to satisfy the system pressure test requiremenfs of (a) and (b) above for that period in which it is conducted.

All ASME Section XI Pressure Testing requirements are controlled by site procedures. The boundaries subject to system pressure tests; (Functional, Inservice and Hydrostatic), are shown. on Color Coded Program Boundary Diagrams. (See Secfion 9.0).

Page 55 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECT/ON REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 5.0 CLASS 1, CLASS 2 AND CLASS 3 COMPONENT SUPPORTS << IWF Component supports selected for examination shall be the supports of those components that are required fo be examined under IWB, /WC and IWD.

For multiple components within a system of similar design, function, and service, fhe supports of only one of the multiple components shall be examined.

Class 1, Class 2 and Class 3 supports receive a Visual (VT-3) examination to determine their general mechanical and structural conditio;n, and when required, conditions relating to their operabi%ty. The supports subject to examination have been selected in accordance with sub-article IWF-2510 of "the code. (Refer to Appendix.D, E, and F for Summary Tables). =

5.1 Supports E'xempt From Examination Exemptions are as stated in IWB-1220, IWC-1220 and IWD-1220.

5.2 Support Examination Development 5.2.1 Class 1 Component Supports Class 1 component supports subject to examination are identified in Appendix D.

5.2.2 Class 2 Component Supports Class 2 component supports subject to examination are identified in Appendix E. I 5.2.3 Class 3 Component Supports Class 3 component supports subject to examination are identified. in.

Appendix F.

The Class 1, Class 2 and Class 3 Summary Tables satisfy the requirements of IWA-2420 (a) (1) through (6) respectively.

5.3 Narrative Discussion A narrative discussion of Class 1, Class 2 and Class 3 component supports subject fo examination are described in detail below:

In order to assure that a represented sample of supports within each Code Class is examined, Code Examination Categories F-A, F-B, and F-C, as previously included in fhe earlier Edition of Section X/ has been used in Page 56 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 this update program to define fhe following:

F-A C/ass 1 Component Supports F-B Class 2 Component Supports F-C Class 3 Compori ent Supports

$.3.1 Category F-A, F-B and F-C Supports Item F1.10 - Mechanical Connections to Pressure Retainin Com onenfs and Buildin Structure 97 C/ass 1 Supports, 31 Selected 217 Class 2 Supports, 57 Selecfed 278 Class 3 Supporfs, 81 Selected Item F1.20 - Weld Connections to Buildin Structure No Class 1 Supports No Class 2 Supports No Class 3 Supports Item F1.30 - Weld and mechanical Connections at Intermediate Joints in Multi-connected Inte ral and Non-infe ral Su orfs 5 Class 1 Supports, 2 Selected No C/ass 2 Supports 1 C/ass 3 Supports, 1 Selected Item F1.40 - Clearances of Guides and Sto s Ali nment of Su orfs Assembl of Su ort Items No C/ass 1 Supports No C/ass 2 Supports No C/ass 3 Supports Ifem F1.50 - S rin Su orts and Constant Load Su orts 48 C/ass 1 Supports, 18 Selected 22 C/ass 2 Supports, 8 Selected 10 Class 3 Supports, 6 Selected Item F1.60 Slidin Surfaces No C/ass 1 Supports 3 C/ass 2 Supports, 1 Selecfed 13 C/ass 3 Supporfs, 2 Selecfed Page 57 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 Item F1.70- Hot or Cold osifion of S rin Su orts and Constant Load

~Su orts Note: The VT-3 examination of Hot or Cold positions will be performed in conjunction with fhe VT-3 examination of Item F1.50.

Page 58 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 6.0 AUGMENTED EX'AMINATIONS The following is the detailed description of fhe St. Lucie Unit 2 Inservice Inspection Program Plan Basis for Augmented Examination of additional components/systems.

6.1 Class 1 6.1.1 Reactor Coolant Pump As required by Plant Technical Specification 4.4.11 each Reactor Coolant Pump Flywheel is examined per the requirements of Regulatory Guide 1.14, Position C.4.b. The bore and keyway areas of each. Reactor Coolant P ~m~" ~!ywheel are examined ultrasonically once each period.

Additionally, the flywheels receive a 100% volumetric examination (UT) and a surface examination at or near the end of each Inspection Interval.

In Place Volumetric Bore and Ke a 017 003240 02-017-008 018 003380 02-018-008 019 003520 02-019-008 020 003660 02-020-008 100% surface and volumetric at/or Near End of Interval 017 003250 01-017-009 018 003390 02-018-009 019 003530 02-019-009 020 003670 02-020-009 6.1.2 Steam Generator Tubes The Steam Generator tubing surveillance requirements are contained in Plant Technical Specification 3/4.4.5. Compliance is detailed in a separate Program Plan.

6.1.3 The Reactor Vessel (including the Closure Head)

Examinations are performedin accordance with Regulatory Guide 1.150, Rev. 1.

Page 59 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 A

6.1.4 Prtessunzer Surge Line Thermal Sfratification, NRC Bulletin 88-11.

FPL willperform a Visual VT-1 examinafion of fhe pressurizer surge line for general conditions during the inferval.

6.1.5 LER 93-04 Per LER 93-04, FPL will perform 100% visual VT-1 examination of the four (4) pressurizer steam space nozzles, during the second inspection interval.

001670 (4) Nozzles scheduled for 3rd Period 6.2 Class 2 6.2.1 STANDARD REVIEW PLAN 6.6 (a) Welds in those portions of systems addressed in USNRC Branch Technical Position APCSB 3.1 para. B.2.4(c);

(b) Welds in those portions of systems addressed in SRP 6.6 para.

I.8.

In addressing the augmented examination requirements, referenced in (a) and (b) above, pipe-to-pipe welds and longitudinal seams are required to be examined. 'dditionally, the Code Categoiy (C-F) boundary is extended past the code class boundary (MSIV) fo the first resfraint providing at least two degrees of restraint to piping thermal expansion. The welds and supports thus affected are specifically identified fhrough Examination Notes in the Main Steam and Boiler Feedwater examination Tables.

6.2.2 NRC BULLETIN 79.-13 Augmented Feedwafer Examinations, as a result of a continuation of NRC Bulletin 79-13, and NRC Informational Nofice 93-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators.

FPL willperform a confinuous enhanced ulfrasonic examination starting af the Feedwafer Nozzle ramp and extending 'out to a point of 1 diameter on fhe elbow. Examinations will be performed in conjunction with fhe Code examination schedule as identified within fhe examination Tables.

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SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION . REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 7.0 RELIEF REQUESTS 7.1 FIRST INSPECTION INTERVAL During the First Ten Year Inservice Inspection Interval there were cases where component configuration andlor interference prevented the. code required volume or surface area from being examined. In each case where such limitations were encountered, fhe details were documented on a Request for Relief.

7.2 SECOND INSPECTION INTERVAL A detailed review of the 'previous submitted Requests for Relief was performed, and based on this review, those Requests for relief on items which remain applicable for fhe Second Inservice Inspection interval are included in Appendix G of this program.

Note: Examination volume or surface area that cannot be examined due to interference by another component or part geometry, a reduction in examination coverage on any weld will be considered acceptable provided fhe reduction in coverage for that weld is less than 10%. Subject of Code Case N-460.

In cases where parts of the required examination 'areas cannot by effectively examined because of a combination of component design or current inspection technique limitations, FPL willcontinue fo evaluate the development of new orimproved examination techniques with the intent of applying these techniques where a practical improvement on the examination can be achieved.

7.3 RELIEF REQUEST CONTENT Examination volume or surface areas interference that does not meet the coverage requirements of Code Case N-460, will be documented in the form of a Relief Request per 10 CFR 50.55a (g)(4)(iv). Each Request for Relief will contain the following information:

A. Component Identification - describes fhe Code Class, Code Examination Category (if applicable) and a brief description; B. Examination Requirement - describes the Code Item Number(s) and fhe examination requirements; C. Relief Requested - provides an description of the relief from fhe requirements of the Code that can not be complied with; \

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SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION, REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 D. Basis for Relief - describes justification to support the reason relief is being requested; E. Alternative Examination - describes examination(s) or Tests that FPL proposes to use in lieu of the current requirements; F. Implementation Schedule - denotes fhe interval, period, and/or outage (which everis applicable), that FPL proposes to implement the relief; G. Attachments to the Relief - identify all Figures, Tables, Sketches, Photographs, etc., attached to the Request for Relief. All attachments should be referenced within fhe applicable text.

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SECOND INSPECTION INTERVAL PSL-200 INSERVICE .INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 TABLE 7-1 RELIEF REQUEST STATUS Relief Requested Sfafus Relief Request (include a document Number and Description reference ifapproved) 1 Reactor Vessel & Incomplete Code Essenfially same as Closure Head pressure required Volume first Ten Year interval retaining welds 2 Steam Generator Removed, only one weld required to be pressure retaining welds examined in second interval, no relief required.

. 3 Pressurizer. Full Incomplete Code Essentially same as Penetration welds of required Volume first Ten Year interval Nozzles fo Vessels 4 Intersecting longifudinal Addifional surface New Request for welds of circumferential examination Relief welds requirements 5 RCP Safe End to Pipe Incomplefe Code Essentially same as welds and Nozzle to Safe required Volume first Ten Year inferval end welds > 4" 6 Pressure retraining Incomplete Code Essenfially same as welds in Piping > 4" required Volume first Ten Year interval Removed, not required due to changes in Table IWB-2500-1 cafegories B-L-1, B-L-2; B-M-1, and B-M-2.

8 Pressure Retaining lncomplefe Code Essenfially same as Welds in Shutdown required Volume first Ten Year interval Cooling Heat exchanger 9 Pressure Retaining Incomplete Code Essenfially-same as Nozzle Welds in Steam required Volume first Ten Year interval Generator 10 Pressure retaining Incomplete Code Essentially same as Welds in Piping required Volume or first Ten Year interval Surface Removed, nof required per IWC-1221 12 Not Used Page 63 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 Relief Requested Status Relief Request (include a document Number and Description reference if approved) 13 UT Calibration Blocks Deviations of Cal Essentially same as Blocks from first Ten Year interval Appendix III requirements 14 RPV and Closure Head Percentage New Request for Steam Generators requirements of IWB- Relief Pressurizer and.RC Pumps 2412

- Welds, Bolting, Integral Sequence of Attachments component exams consistent with First Interval 15 Alternate Volumetric Volumetric Exams in Essentially same as Exams of Outlet Nozzle lieu of required first Ten Year interval Safe Ends surface examinations 16 Article IWA-4000 Proposed Alternate New, Request for Repair Procedures for preparation and Relief Article IWA-6000 submiffal of Records and Reports summary reports Article IWA-7000 Replacement 17 Reactor Pressure Reestablish new 10- New Request for Vessel Nozzle to Vessel year Interval Relief Welds Examination requirements for the Reactor Pressure Vessel Page 64 of 272

SECOND INSPECTION INTERVAL PSL-200

/NSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 8.0 ACCEPTANCE CRITERIA Indications detected byinservice examinations, shal/ be compared against the acceptance criteria of Section XI as defined in Tables 8-2 through 8-5).

8.1 Acceptance by Examination Components whose examination either confirms the absence of flawslconditions or reveals indications that do not exceed the acceptance criteria of (a) below, shall be acceptable for continued service. Verified changes of flaws/conditions from prior examinations shall be recorded in accordance with Section 6 of this program.

(a) ~

acceptable to the acceptance criteria identified in Tables 8-2 through 8-5.

Acceptance of components for continued service with indicationslconditions exceeding the acceptance criteria of 8.1 (a) above shall be in accordance with the 8.2 through 8.4.

8.2 Acceptance by Repair Components whose volumetric or surface examination reveals defecfslconditions that exceed the acceptance criteria of Tables 8-2 through 8-5 shall be unacceptable for continued service until removed by mechanical methods or the component repaired fo the extent necessary to meet fhe acceptance criteria in 8.1. Repairs are further covered by Section 10.0.

Note: The additional examination requirements of IWB-2430 IWC-2430 or IWF-2430, (as applicable) shall be performed for service induced defectslconditions, and/or those construction or manufacturing defects determined by Nuclear Engineering to be detrimental to fhe quality- or" safety of the component'system.

8.3 Acceptance by Replacement As an alternative to repair requirements of 8.2, the component, or fhe portion of the component containing the defectlcondition shall be replaced.

Replacements are further covered by Section 10.0.

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SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 8.4 Acceptance by Analytical Evaluation Components whose volumetric orsurface examination reveals defects that.

exceed the acceptance criteria of Tables 8-2 through 8-5 are acceptable for continued service without defect removal, repair or replacement if an analytical evaluation meets fhe acceptance criteria of IWB-3600 or IWC-3600 as applicable.

Where the acceptance criteria of IWB-3600 or IWC-3600 are satisfied, the area containing the defect shall be subsequently reexamined in accordance with 8.4.1 or 8.4.2.

Note: reexamination shall be accomplished only on service induced defectslcondifions.

8.4.1 Class 1.Components Pursuant to the Section XI Code, sub-article IWB-2420 (b), in the case, where examinations reveal the presence of service-induced defects that exceed the acceptance standards and fhe componentis analyzed as acceptable for continued service, the areas containing such defects shall be reexamination during the next three (3) inspection periods of Inspection Plan B'(IWB-2412-1). Provided the defect remain essentially unchanged for three successive inspection periods, fhe component examination schedule will revert to the original schedule of successive inspections.

8.4.2 Class 2 Components Pursuant to the Section XI Code, sub-article IWC-2420 (b), in fhe case, where examinations reveal fhe presence of service-induced defects that exceed fhe acceptance standards and fhe component is analyzed as acceptable for continued service, the areas containing such defects shall be reexamination during the next inspection period of Inspection Plan B (IWB-2412-1). Provided fhe defects remain essentially unchanged for the next inspection period, the component examination schedule willrevert to fhe original schedule of successive inspections.

8.5 Acceptance by Engineering Evaluation Examinations that reveal indications exceeding the acceptance criteria identified in Tables 8-2 through 8-5 will be submitted to Nuclear Engineering for evaluation and disposition:

Page 66 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION . REVISION 0 PROGRAM PLAN AND SCHEDULE July 24,. 1993 A. Indications found fo be accepfable by the materials and welding criteria specified in Section IIIEdifion applicable to the construction of fhe component shall be acceptable for continued service.

B. Indicafions determined fo be acceptable by the FPL Design and/or Manufacturer's Specifications shall be acceptable for continued service.

C. Indications believed to be surface anomalies (e.g fabricafion marks, scratches, surface abrasion, material roughness or other conditions are acceptable for. continued service provided fhe indication is removed by light flapping and/or grinding (surface preparation), and fhe maferial removed does not violate the design minimum wall thickness.

D. Ifthe evaluations conducted on a component support demonstrafes that fhe support was funcfional for its intended safety function addifional exams are nof required, however repair or replacement may still be required.

Nuclear Engineering evaluafion and/or disposition may include the need for corrective measures, repairs, analytical evaluation, or replacement, as appropriafe.

8.6 Acceptance by Correction Component supports whose examinafions reveal condifions described in IWF-3410(a) shall be unacceptable for continued service until such conditions are correcfed by one or more of the following:

(a) adjustment and reexamination for conditions such as:

1. detached or. loosened mechanical connecfions;

2. improper hot or cold positions of spring supports and constant load supporfsl

3. misalignment of supporfs; or

4. improper displacement settings of guides and stops.

A component support or portion of a component support which is unacceptable per Table S-5, for continued service may be analyzed and/or tested to the extent necessary fo substantiate ifs integrity forits intended service. Nuclear Engineering has performed an evaluation of minor deficiencies encountered during a visual examination of pipe hangers or supports, and has provided a set of standard corrective measures to be Page 67 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 taken asidentifiedin Table 8-1. These corrective measures are considered to be normal maintenance and may or may not require reexamination following completion of these actions 8.7 Acceptance by Supplemental Examination Volumetric, visual, or surface examinations that detect indications requiring evaluation may be supplemented by other examination methods and techniques fo determine fhe character of the indicafionlcondition.

Components containing indications andlor relevant conditions shall be acceptable for continued service if the results of supplemental examinations meets the acceptance requirements of 8.1.

8.8 Acceptance Criteria in Course of Preparation Ifacceptance criteria for a particular component, examination category, or examination method are not specified, defects that exceed the acceptance criteria for materials and welds specified in fhe Section III Edition applicable to the construction of the component shall be evaluated to determine disposition.

8.9 Additional Examinations 8.9.1 CLASS 1 The additional examination requirements identified in IWB-2430, shall be performed for service induced defectslcondifion, andlor those construction or manufacturing defects determined by Nuclear Engineering to be detrimental to fhe quality or safety of the componentlsystem only. When this situation exists additional .

examinations shall include the following:

a. The remaining welds, areas, or parts within fhe same Code Item Number for:

1. The existing period

2. The next subsequent inspection period, even if fhe period falls within the next interval.

b. Ifthe examinations for thatinspection item are not scheduled in the subsequent period, fhe mostimmediafe period containing scheduled examinations shall be taken as the subsequent period.

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SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, f993

c. If the additional examinations reveals service induced defects/conditions, the examinations shall be further extended all welds, areas, or parts of similar. design, size, and to'nclude function.

Additional examinations willbe performed before the end of fhe outage..

S.9.2 CLASS 2 The additional examinafion requiremenfs identified in IWC-2430 shall be perFormed for service induced defectslcondition, and/or fhose construction or manufacturing defects determined by Nuclear Engineering to be defrimental fo the quality or safefy of the component/system only. When this situation exists additional examinations shall include the following:

a. An additional number of components or areas, within the same examination category, approximately equal to the number of components or areas examined initially.

b. If fhe additional examinations reveals service induced defects/conditions, the examinations shall be further extended fo include remaining number of similar components or areas within fhe'ame examination category.

c. Additional examinations of welds, areas, or parfs may be limited to welds, areas, or parts of similar design, size, and funcfion.

Addifional examinations willbe performed before fhe end of fhe outage.

8.9.3 CLASS 3 There are no addifional examination requiremenfs identified in IWD-2000, therefore additional examinafions shall be performed for service induced defects/condifion, and/or those construction or manufacturing defects defermined by Nuclear Engineering fo be detrimental to the quality or safety of the component/system only. When this situation exists additional examinations shall include the following:

a. An additional number of components or areas, within the same examination item number, system, and line, and will include fhe following:

1. The next component or area, upstream and downsfream of the initial defect or condition.

Page 69 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993

2. If the additional examinations reveals service induced defectslcondifions, fhe examinations shall be further extended to include remaining number of similar components or areas within the same item number, system or line.

b. Additional examinations of welds, areas, or parts may be limited fo welds, areas, or parts of similar design, size, and function.

Additional examinations willbe performed before the end of the outage.

8.9.4 COMPONENT SUPPORTS The additional examination requirements identified in IWF-2430, shall be performed for service induced defecfslcondition, andlor those construction or manufacturing defects determined by . Nuclear Engineering to be detrimental to fhe quality or safety of fhe comp onentlsystem only. When this situation exists additional examinations shall include fhe following:

a. The component supports immediately adjacent to the initially identified support with the defect!condition.

c. Additional supports equalin number and similarin type, design, and function to those initially examined.

d. When these additional examinations reveals defectlconditions,'he remaining supports within fheitem number, system or line shall be

, examined.

e. Additional examinations of supports may be limited to supports within the same system or line of the same type, design, and function.

Additional examinations willbe performed before the end of the outage.

8.10 DEFECTS FOUND OUTSIDE SECTION XI EX'AM/NATION Defecfslconditions that are found outside the course of a Section XI examination, shall be compared. against the acceptance standards of Tables 8-2 through 8-5, as applicable.

Page 70 of 272

SECOND INSPECTION INTERVAL PSL-200 INSER VICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 8.11 MINIMUMTHREAD ENGAGEMENT Acceptance criteria for bolting thread engagement is nof addressed by Section XI. Nuclear Engineering has reviewed the requirements applicable to thread engagement for safety related bolted connections, and has determined that the minimum acceptance criteria for thread engagement willbe no exposed threads on the nut. Ref. document no. JPN-PSL-88-070, Rev. 0 Bolting that does not meet this criteria shall be unacceptable for further service until Nuclear Engineering has completed an evaluation for acceptability, or the condition has been corrected.

TABLE 8 CORRECTIVE ACTION DEVIATION CORRECTIVE ACTION REEXAMINATION Damaged, missing, corroded or loose Replace with new cotter pin or retainer or cotter pins and retainers tighten as necessary Mild rust/corrosion on spherical Clean and lubricato with graphite bearings Gross rust/corrosion on spherical Replace spherical bearing 8 restako Yos bearing Mild rust/corrosion on hanger/support Clean and reinspect for furthor degradation. Yes Repaint support

-Paint on tags, indicators etc. Remove paint with solvent No Foreign material, corrosion on load pin Clean toad pin with scotch brito pad or No equivalent. Whip clean and apply a light film of machine oil Spherical bearing Is loose or dislodged Reseat spherical bearing and rostake Yes Misalignment of hanger/support loosen pipe clamp 8 realign In accordance with Yes original drawing.

Standard nut, used as a lock nut, does lock nut shall havo at least 50% thread No not have full thread engagement engagement.

Replace as necessary Yes Spherical bearing Is frozen Lubricate and work bearing until looso. No Repiaco if necessary Yos Page 71 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 TABLE 8 CLASS 1 ACCEPTANCE STANDARDS EXAMINATION COMPONENT OR PART EXAMINED ACCEPTANCE CATEGORY STANDARD B-A Welds in Reactor Vessels IWB4510 B-B Welds in Other Vessels IWB4510 B-D Vessel Nozzle Weids IWB4512 B-E Partial Penetration weids In Vessels IWB4522 B-F, B4 Dissimilar and Similar Metal Welds fn Piping IWB4514 B4-1 Bolting > 2" dia. IWB4515/3517 BN-2 '- Bolting (2" dia. IWB4517 B-H, B-K-1 Integral Attachments for Piping, Valves, Pumps & Vessels IWB4516 B-L-1, B-M-1 Welds in Pumps & Vaiveh IWB4518 B-L-2, B-M-2 Pump Casings 8 Valve Bodies IWB4519 B-N-1 B-N-2 Intorlor Surfacos & Internal Components of Reactor Vessels IWB4520 B-N4 Control Rod Drive Housing Welds IWB4523 B-P Pressuro Retaining Boundary< IW84522 B-Q Steam Generator TubIng IWB4521 TABLE 8 CLASS 2 ACCEPTANCE STANDARDS EXAMINATION ACCEPTANCE COMPONENT OR PART EXAMINED CATEGORY STANDARD C-A Welds in Pressure Vessels IWC4510 C-B Nozzlo Welds In Vessels IWC4511 Integral Attachments for Vosseis, Piping, Pumps and IWC4512 Valves C-D Bolting IWC4513 C-F-1,C-F-2 Welds In Piping IWC4514 Welds In Pumps and Valves IWC4515 C-H Pressure Retaining Components IWC4516 Page 72 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 TABLE 8% - CLASS 3 ACCEPTANCE STANDARDS EXAMINATION COMPONENT OR PART EXAMINED ACCEPTANCE CATEGORY STANDARD D-A Pressure Boundary (VT-2) "No Leakage *Mfg.

Integral Attachments (VT4) Code 8 Applicable Standards D-B Pressure Boundary (VT-2) "No Leakage 'Mfg.

Integral Attachments PTQ) Code & Appllcablo Standards D-C Pressure Boundary (VT-2) IWA4250 'Mfg. Code &

Integral Attachments (VT4) Applicable Standards

-

ASME Section XI Acceptance Standard in course of preparation.

Defined as no leakage from. the pressure boundary, in excess of that which is expected and determined to be within acceptable limits, i.e., at valve packing, bolted'connections, pump seals, etc.

TABLE 8 COMPONENT SUPPORT ACCEPTANCE STANDARDS EXAMINATION COMPONENT OR PART EXAMINED ACCEPTANCE CATEGORY STANDARD F-A Supports IWF441 0 Page 73 of 272

SECON D INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 9.0 BOUNDARY CLASSIFICATIONS'he Class 1, 2 and 3, Quality Group A, B, and C classification interfaces between components of different quality groups applicable to St. Lucie 2, are designated on various system piping and instrument diagrams (P8ID's).

These diagrams identify the system breaks by a boxed-in letter either an A, B or C, on the piping and instrument diagrams.

9.1 Program Boundary Diagrams The Section XI, Inservice Inspection Program Boundary Diagrams included within this program are color'coded to illustrate the Class 1, 2 and 3 boundaries as they apply to lnservice Inspection pressure boundaries. The boundaries are determined in accordance with paragraph 1.6 of this document. The rules of IWB, IWC and IWD are applied to these Drawings in order to determine those component/systems subject, to examination/test. The applicable color code schemes are defined in paragraph 9.2 below. Components subject to surface, volumetric and visual examination are listed in the Inspection plan tables. Component supports subject to visual examination are listed in the Inspection plan tables. (Class 1, 2 and 3 respectively).

9.2 Color Coding In order to distinguish between the different classifications, the following color codes are used.

Class 1 - Red Class 2 - Blue Class 3 - Green Table 9-1 provides a listing of the program boundary drawings by identification number, reference PBID number and title.

Page 74 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 TABLE 9 PROGRAM BOUNDARY DRAWINGS Drawing Number Reference Drawing Title 02-PB-01 2998-G-078 SHT.110 REACTOR COOLANT SYSTEM 02-PB-OIA 2998-G-078 SHT.107 REACTOR COOLANT 2998-G-078 SHT.108 SYSTEM 2998-G-078 SHT.109 02-PB-02 2998-G-078 SHT.120 CHEMICAL & VOLUME CONTROL SYSTEM 02-PB-02A 2998-G-078 SHT.122 CHEMICAL 8 VOLUME CONTROL SYSTEM 02-PB-03 2998-G-078 SHT.121 CHEMICAL & VOLUME CONTROL SYSTEM 02-PB-03A 2998-G-078 SHT.121 CHEMICAL &, VOLUME CONTROL SYSTEM 02-PB-04 2998-G-078 SHT.122 ,CHEMICAL & VOLUME CONTROL SYSTEM 02-PB-05 2998-G-078 SHT.130 SAFETY INJECTION SYSTEM 02-PB-05A 2998-G-078 SHT.130 SAFETY INJECTION SYSTEM 02-PB-05B 2998-G-078 SHT.130 SAFETY INJ ECTION ~

SYSTEM 02-PB-06 2998-G-078 SHT.131 SAFETY INJ ECTION SYSTEM 02-PB-06A 2998-G-078 SHT.131 SAFETY INJECTION SYSTEM 02-PB-07 2998-G-078 SHT.140 FUEL POOL COOLING SYSTEM 02-PB-08 2998-G-078 SHT.153 SAMPLING SYSTEM 02-PB09 2998-G-078 SHT.160 WASTE MANAGEMENT 2998-G-078 SHT.163 02-PB-10 2998-G-079 SHT.1 MAIN STEAM 8 2998-G-079 SHT.2 AUXILIARYSTEAM SYSTEM Page 75 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE Ju/y 24, 1993 TABLE 9 PROGRAM BOUNDARY DRAWINGS Drawing Number Reference Drawing Title 02-PB-11 2998-G-080 SHT.2 FEEDWATER AND CONDENSATE SYSTEM 02-PB-11A 2998-G-080 SHT.2 FEEDWATER AND CONDENSATE SYSTEM 02-PB-'I2 2998-G-082 CIRCULATING &

INTAKE COOLING WATER SYSTEM 02-PB-12A 2998-G-082 CIRCULATING &

INTAKE COOLING WATER SYSTEM 02-PB-1 2B 2998-G-082 CIRCULATING &

INTAKE COOLING WATER SYSTEM 02-PB-13 2998-G-083 COMPONENT COOLING SYSTEM 02-PB-13A 2998-G-083 COMPONENT COOLING SYSTEM 02-PB-1 3B 2998-G-083 COMPONENT COOLING SYSTEM 02-PB-14 2998-G-084 FIREWATER, DOMESTIC 8 MAKE-UP SYSTEMS 02-PB-15 2998-G-085 SHT.1 SERVICE &

2998-G-085 SHT.2 INSTRUMENT AIR SYSTEMS 02-PB-16 2998-G-086 SERVICE 8 INSTRUMENT AIR SYSTEMS 02-PB-17 2998-G-088 CONTAINMENT SPRAY

& REFUELING WATER SYSTEMS 02-PB'-1 7A 2998-G-088 CONTAINMENT SPRAY

& REFUELING WATER SYSTEMS Page 76 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 TABLE 9 PROGRAM BOUNDARY DRAWINGS Drawing Number Reference Drawing Titie 02-PB-17B 2998-G-088 CONTAINMENT SPRAY 8 REFUELING WATER SYSTEMS 02-PB-18 2998-G-092 MISCELLANEOUS SAMPLING SYSTEM 02-PB-19, 2998-G-862 HVAC 02-PB-20 2998-G-078 SHT.132 SAFETY iNJECTION SYSTEM 02-PB-20A 2998-G-078 SHT.132 SAFETY INJECTION SYSTEM 02-PB-21 2998-G-078 SHT.111 REACTOR COOLANT PUMP 02-PB-22 2998-G-078 SHT.150 SAMPLING SYSTEM Page 77 of 272

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ST. IMCC PIANT 0147 2 OOOE OOIPIARY CIACRAM fCCOWATIR ANO DATQ CRAIII SY: DRAWNO IRA10UO APIN04CO 8Y; REV. IRASS 5 (C) CRCIN CCNOOISA'IC SIS'tDIS 02~1 0 10 ~ at jf aaaep aha at It ae aa 'i 'tae ~ ehteetee a 'at ae, ea 1r.eh a: tf a' at aee w htf teaeea C aetwaaa O'C 'ttta>> la fat ata ta flare r a ae'I ~ I'aeeta 'tt." ~ aaea e ata tat tlteaa t a ea a 3 a* tha tth at 4 ff

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LLICC PLANT VIVT 2 CLASS (A) RSD CDCC DOIJNDARY DIACRAII CLASS 2 (8) SIAR CSICIJLATIIO a INTuC DRAWHO 14JNDSD CLASS 5 (C) CRSOI COCLRIO VATSR STSTDI 02~ 2A 10 ~ . <<<<V vc<<tcc <<<< C 'V>> ll l I I >>C.f O'I Ql <> ~ ttca<<l V>> IC* lt I>> I Vl ~ -V<<VVI II ~ >>>> t l. <<V l<< IA t>>c <<>>. VV>> ~ \ 8VV>>V<<ill I <<VC>> +VIVVII t I I ~ct V ~ ttt ~ V* . ~ ~ ~ I ~ .CC<<e I W VIVV VCI IVV 'I tc ~ ' >> IIet<<V g l l ~,t,i <<V c .<<< /It H ~ 'lt ll t .t<<wC CIC I VA lc ~ tc~ VC c"t>>s) V << I NNCW-70 3 (I) OOOUNC HX 02 P812 C 7 58 21502 I ~70 IM I 24M 74 NC j 2l $8 2ISCS (I) N (9M) 2 I/2'R SH 21577 j8 $8 21212 (TA) 21 SH 21522 (955) ATTN PIATP A A I 54 CW 12 I 0 8~21210 (944) l NC j 8-58-n252 (>> WATER POMP N 58-21209 (S) I 5-Cw-99 S-V-21204 (474) f VA ~ j 8-58-21255 (I) VA 8 j 21 58 21504 (I) I SS I-SS N SH 21514 (944) 3 SH 21207 (941) 21-SAI 21 581 VA I VA I 24 21 SH 21597 (945) I I& 47 5/4'8 VA ~ YA ~ SITAKE COQUNC I 1~215 WATD( PUMP 8-SH 21424 (945) 5/4 I SS l 21 582 1 21 YA I YA I 58 2 8 SH-2ISIT (944) 2I-SH-21520 (945) 21 58 21254 (I) 2I-58-21505 (I) 8 SH 21425 (945) N-SH 21244 (945) a-SH-21429 (945) I I Cw 219 a-SH-21247 (944) 11% 57 2'-V-21525 2'1-V-21524 S-V-21455 (955) (957) (957) f N V-21452 (955) f 3 DI 21514 (945) I-~-49 N WATER POMP SH 21271 (945) 8-SH 2ISI5 (945) 5 SH 21270 (945) WA'KN POMP I IW 57 IWCW-70 WANII PIAIP WAIER PIRO 11 CW 47 OATG ERAISI 8Y: APPROVED 87: CEASS I (A) REO ST. IUCC PIANT VNT 2 CODE 80ONOAR'7 DIACRAM 11ASS 2 (4) SUlE CNCOIATNC 8 SITAKE ORA1180 NOMOQO (SASS 5 (C) CA(IN COOUNC WAIB! 5\STDI 02 POINT 10 ~ tt ~ ~I P ~ I I~ I'QIT I'ENT 2I V-I4$55 (CP) 2I-V-IQ17 (025P) Q Y-14541 (0KP) I' 8 Y IQ00 (625P) Q V IQ26 (025P) CON THNMENT Q V 14540 (025P) 2I-QI IQ07 (I) I VQI7 2N4R-IQ29 (I) TIWCV 14 2 ~ fc 2P4ICV ll I I VENT 2I V IQ27 (IKQP) 2I SR IQ42 (I) Q V 14S54 (dXP) I' Q V IQ50 (d25P) Q V IQ59 (02%) I'QIT 21-V-I QOS (dn ) Q SR ll516 (I) I'QIT 21 WIQ16 (62SP) 4 49 II-WI4550 (d25) 2I-V IQ57 (42S) Q V I455$ (024) Q V IQOS (42S) 8 V 14519 (025) 8-WILSIS (425) Q V-IQ20 (025) Q-WIQQ (025) I 6 CC 40 2 f IEAK TEST LEPJI IEST QAV 14 Il 2I MV 14 15 LO ~Wll 15 LO LO 2I MV 14 10 QMV 1412 LO Q MV I ~ ll LO 8 V-1441$ (42$ ) 2I V 14567 (02S) 2I V IQ04 (625) 8 V IQ52 (024) 2I Y IQ21 (024) 8 NCW'14 7 Q V IQ55 (024) Q Y IQ4S (d24) LO 21-MY 14-9 fE Q V IQ24 (024) 2I-WIQ40 (024) 14 12 0 8 V IQ25 (624) 14 I a-V-IQIO (624) Q V IQSI (025) 21 V 21 14549 (424) 58 14548 (5) 11 ~ CC 20 8-V LINN (410) Q V 14547 (424) Q V IQII (024) O14 12 8 Q-V IQIS (424) 8 Y I ~ 10S (010) Q-V 14522 (024) V 14400 (625) Q V-IQ12 (42l) 2A 21 20' SR IQSO (4) I4'G7 COMPONENT 21 (77P) COOUNO s-v-I 4461 (e25) SURGE Y IQ52 (025} TANK 2! V IQ02 (024) Q Y IQ55 (424) 2I Y 1412S (d27) Lo f Q-58 14551 (4) I IO C 45 fO IO Q-se-14127 (0) ff T T LO s-QI-1<120 (e) LO f S-58-14550 (4) SHUTDOWN HEAT EXOHANOERS INCV145A Q I 2IWC 10 2I 58 14529 (4) LO f a-58-14526 (4) I 14 CC 21 I-~14 02~5A (D I) Q 58 IQ57 (5} f LO S-WIQ40 (625) I fc Q 58-14565 (5) IO I-20-CC 17 COMPONENT CXXXA'0 02~5A (0 I) Q W14150 (424) 4 10 8 V IQ$ 4 (024) Q WIQSS (024) 1-20 CC-24 REIMRN IRACER A OXIPONQIT OXUNC 02~ISA 0-1 SR IQ59 (4) COMPCNQI T CCOUNO Q Y 14501 (025) I 20-CC 27 02~154 E I 5 WIQ02 (024) I DR 70 S-48-14467 (5)f LO 1~14 50 fP 2I-WI4505 (No) I 1~25 Q V 14565 (024) IE 4-10 8 g V IQ04 (d24) Q-WI4502 (410) CLASS CLASS I (A) 2 (0) CLASS 5 (C) RQI 44ME CREEN CODE ~ 5'f. LUCE PLANT 11167 2 TIACRAM CC44NXNNT COOUNO STSITM DRANINO IAIL4NR 02-PSI5 REV. 0 10 441" 4 ~ 14>> FN Ft'FI 4"N 4 NN I 4ltl4-4 Ot 4I ~ IICW ~ tf ~ OFF' 4I t ~ 11 44444 ff I" '1444 FFOI" Fftt F4 1 4144 4 fl 4 4 I F 4 O' r I 4 fl - ~ I ~ 44 OF fktO IO44 ~ 4>> ga FOFII ION.' .t f4f~ 414't I 4 4 4 Ft I <<4 4 I 11 ~ 4 f 44N a 441 't j 4.4.. ~ FIO I 4 4QFFtf>> tFFf )FI ~ ' IVFIIW\44 W f444 . 'f 'I I 44 11'O ~ ~f I OOF H if4 "44 114' 441 4 1 N,V,. I 4 I s,l IOF t IB 4( NFFF I 4 ~ 4 ltl ~ I OOqOI. 4 Ifl I C . 4 4 ~ 44't'4 t'l 41* =.I N ~4 . 444144 FIOCO a 4 4 ~ . IOIF 4 ktt I'., IIFFI ~ 144414 I lt ~ 414fkIF II,I OO 'I ~ IF OFF f44 - NF 44 ~ ~ I MF 4 j f 4 OtfOf ' I IVN944~ I '41 44 ) ,e I SE-25 I I IM227 N' 12'ED 21 Y 14211 (624) NI07 (IA) S SS-14100 (LC) 74V-N$72 (325) FC 24V 14436 (025) 24V 14213 (02$ ) 3/4 DRA94 I I' 14'UEL LO 21-V-141 dS (024) 14'r POOL HEAT 21 Y 14140 (024) 2458 '14149 (IA) I'ENT EXCHANGER SLF X 24 24Y-NI44 (024) RED. S-V 14159 (425) 24V N212 (624) x X 12 RCO 8 Y 14171 (624) 24 Y-14170 (02S) I'R COMPONENT COOUNC WATER 8 V 145d2 (02$ ) HEAT EXCHANGER 2A I' ~ 24V I42I4 (024) 24V 14210 (024) 30 X 24 S 58 14439 (IA) 24Y N$ 03 (025) 24V-I4172 (024) LO I'RAII I I CC-I02 RED. I.V n. 3/I. DILAN 2458-14177 (IC) 24V 14155 (625) 21 V-14157 (02l) 24V 1420$ (02$ ) 24Y-14215 (d2l) 8 V-NSQ (d2l) ~I.V 24S414170 (IA) $ LO 24SS 14150 (IA) 0- 24V 14504 (024) 24HCY ll 8A I 16 CC 109 27 V N179 (02l) 8 Y-14160 (d24) Y I-Im231 24V-14575 ($ 25) 4SE 20 2 8 V ll214 (424) 8 Y-Il17$ (62$ ) I '12 CC 'ld N 18 MW1410$ (625) 8 24V Nddl (62l) 24V 14174 (424) 24Y IH74 (024) 112 CC 19 W 14 LC 16 8 I I-1~103 I VENT 21 I 12 CC QO DR NV-N- I D 416 CC 110 20 ~ 02-FSQ (F-0) CdtSNENT CCCUIC COOLFIC I 84CC 17 SJPPLY HEAIXR A SADLY HEA001 8 W 21 17 14 W-14 19 420 00 10 24Y-14173 (02$ ) 24V 14473 (02S) I' 21 HCV I DR 14 08 24V-I 4102 (025) NC I 'I CC 24V 104 CCLIPCNENT COCUNC WATER HEA'T EXCHANGOE 28 14154 (02$ ) I OI I 24CC 12 8 2458 Y 14101 (024) 14100 (IA) 02 PSIS (C 9) I 21400 17 24V-N1$5 (42$ ) 2I NV14 1 DR CCNPCIRN7 COCUIC I 12l CC 21 NV 14 2 ~ 02~3 (C-0) I 20 CC S V 14153 (d2$ ) I 214CC-2 NC CONPO5NT DXUIO I 84CC 27 2I V 14455 (d2$ ) S 58 lau(0) LO 02~3 (C 9) I 20 CC 27 I' 10 21-58 Il'1$2 (0) 21 V-N290 (000) 24VN250 (400) LO 54V-1 4207 (625) 24V 1414$ (0$ 5) 8 Y NISI (0$ 0) 58 '14148 (d) I' I-'14-CC IN f 24Y N479 (024) 2I V NNI (025) S V 14149 (425) 24HCV 144 8 I 0 I D 3/4' S Y 14NT (056) f 14'O V 14500 (410) FC 3 tt 21 21 V 14291 (024) I I I4CC 112 21 V llN2 (d24) 24Y-I41$ 0 (024) I' 3/4 Y 8 V-I4301 (400) 8 V lllld (024) V 14501 (410) 84CV 14 10 24V N145 (02$ ) 21 I I I/2~1 1-1 I/2~03 V-I4001 (Q45) 21 V 14002 (1$ 4$ ) 21 3/rO M t COMPONENT 21-V-'14259 (420) 24Y 14271 (420) t COOUNC Ill52 (424) 24Y-N502 (32$ ) N' PUMPS 21 V 21 V 14551 ($ 2$ ) 24V N200 (024) IW 230 11 CC 778 2B 8 V 14272 (024) I 24V 14522 (d24) 8 V N140 (425) 24Y (02l) 21 V IQ20 (d24) 12l 21 V NQ2 (425) 14139 14 CO$ 0 D 3/4 Y I D 0 I'/4 3/r D S V-N300 (424) 24MV 14 a-W-I4 3 2A S V N209 (400) LO 21 V 14131 (024) 24V 14130 (025) S V 14QO (624) 24Y N134 (d24) I D V I4$21 (024) 24V-14523 (624) 8 Y N135 (024) at 21 ~ S 58 N120 (18) 155 N IA I-SS 141C 3/4 D 3/4 D S 58 1413$ (16) f LO I 24-0'A2 124 CC $1 2458 14137 (18) LO 2I-V 1405 (d24) I-SS-14-18 TEMP. SIRAdtTR 4FC 14 TA I-T0-1475 1-24 043$ 24V 14202 (427) 24V-N274 (027) H 1-2-0405 I 2 CC 06 CATO CRANN SY: APPROVED SY; I (A) RED 2998 MOSS REV. 14 ~T CLASS ST. UIOE PLANT LART 2 24V 14261 (d24) 24V N273 (024) CIASS 2 (8) 0LVE CODE 8048OARY OACRAM DRAINIO NLINSER COOMNC STSIEM 4XASS 3 (C) CREEN 02~3A 10 I Iohr .. <<IO I \~ ff O II Z>> N 'l lp ~o rth I>>I I P- n ~ I:>> I f <<O>> I fl q 'I I O~ Al 4>>f<<<< O ~ I O Oll l j N N lt ~ AO lt ~ <<l ~, n~., ..*NI>>o>> I a tt 'I ~ ' f1hh O Ig A OO'>> )>>I I hl 'O OAO h li A 5>> ,.1 OO.,O<< tj All h . ~" OI II ~I I Od ii I II I<< l>>ON 1'1 j R II W I,. OO ~ ~ lf l OO .I I' All <<4 OO 'OO<<OO j ' I If 11 *-; - A. IOAIO>><< IOO)l I f>>OOIL Il ) AAOO)I hg>><<>>O O Ih 'I ~ l>>KOOO ~ l h O A 2 V 14245 (024) 2-Qt-14244 (2) 5/4'TNT 2 V-1455d (024) 10' 0 2-V 14552 (015) 2 Y 14449 (d25) IO' I' 0 2-V-14242 (024) 2 V 14240 (024) I DR (TTP) 2-V-14245 (024) b 2 SS 14240 (S) j 2 Y 14250 (02S) 2 V \l249 (d24) 2-50-14241 (5) 2-SB 04254 (5) j NC 2 V 14251 (024) 0'225 2 TCV-j 2-V-14255 (025) 2-58-14252 (5) ~ISO 2-58 14255 (S) j H TIASCOA POWTR 8 ISCNT CO. OATK. DRAW SY: APPRCNKO 8% CTASS 1 (A) ~ RED ST. LUOS PLANT IRNT 2 CIATS 2 (0) 04IIS COOS SCVIOARY CIACNAN CTASS 5 (C) CR(QI CAPCNQIT COCUNO STSIDI 10 lt 1 I HCV 15 I II V ISI44 (1224) 3 V ISI2d (154)) CAID DRAIN BY: APPRWCD BY. CIASS I (A) ICD 221d ~4 RCV. Il S'f IDCR! PWII IRRI 2 CCCC BOlROARY OIACRAII CIASS 2 (d) BCCC fSIEIIAIKR. DCIRSRC CIASS 2 (C) CRCDI t NARC~ SISIDfS D V 181287 (044) V 18105 (957P) 121414 HCV Id I ID 21 V-ISI288 (054) S I 5/4 IA 74 3-V-ISI245 (054) 15518 2 ISAH TKST I 2SA 12 ISK 185 MV 18708 (047P) D V ld704 (SIT) D-SH-Id707 (985) ~ CATE ORAIRI BY APPRCVEO BY' ClASS I (A) ISTI 2990 2889 ~S SNL I 5HT. RCY 11 2 RSV. IS St, IDOC RIANT IART 2 CCCC BCIAGARY ISACRAll CIASS 2 (d) IACS CRAVNC IAARSTL SIRIICS R IISTISAIDIT CSASS 5 (C) CRKDI AAI STSITIIS 82 0815 )0 N 4 N r 1 i k V r k IBBT 2 STEAM OPERATOR STEAM SLOWDOWN SYSTEM CENERATORS 2A 1282 a-V-25127 ($07) CF 2AI aII I I/2 145I 41/2 8 82 a-v-25101 (52$ P) 2 21-Y 25120 ($ 2JP) I I 8 91 a V 25102 ($07) 45/5-8 95 lEAK 11890 IEST IEST I 5/5 8 92 lEAK 24Y 25274 ($22P) TEST 2l-V-25276 ($259) a Y 25275 {$22P) a V 25275 ($ 259) REACTOR CCNTA9IU(N7 BNLO0IC I I/O a Y-'I7260 I-SE-17-2A 4FCV-245 a FC 6'ENT 4FCY 247 I FCV 249 I SE 17 IA 4O426 2I SR 17221 (IA) DAY TANK 2AI DAY TAIO{ 2A2 n (SESEL OL (KESEL CSL STORAGE TRANSFER PUMP TANK 2A 2A 24Y-17206 (eu> a Y-17200 (007) a-Y 17201 (609) SS-I7 IA I 2~5 I I I/2~11 2l V-I7205 (106) DRAM a-V-1 7200 (627) a V 17207 (607) a-v 17250 (1525) 2I V 17251 (1526) 0 VENT a-v-17200 (e09) II/2 D 11/2 D a a SN I7255 ($51) 4O425 a V 17220 (609) lc V 17217 (42$ ) 1-2 DO-15 LC 21 Y 'l7202 (607) A a Y-1721d (607) a-v-17209 (ecd) LO I h-06410 (7ESEL {SL 2l SR 17222 (18) 'TO WAS'IE STORAGE 120022 TANK 28 IC a Y-17219 (660) 24V-Inld (509) a Y 17212 (607) 42%0-6 EIES(L OL a V-17217 (607) I $ 00 4 a a-v-172M (027) lL SS 17 18 TRANSFER PUVP 28 I I I/O 00 12 2-V-1 lac (666) Ul~ a-V-17247 I SE-17 28 a v 1721$ (606) 21 V 17210 (607) EMERCENCY DESEL CENQIATOR SYSTOI I SE 17 18 V 1727d (62$ > a SN 17215 (317) 21 DAY TANK 281 DAY TANK 282 I-l I 2 DO 50 I I/2' I I I/2~55 2I V-17202 (1525) a-v-17205 {1524> DAIL DRAMI BY.'PPROVED Ba CLASS I (A) RED 2994-~ AEY. 12 Sl. IUCK PlANT 1557 2 CSASS 2 (0) SUJE COCE BOUIOARY CIACRAM CPA5INO 15116NRI REV. CLASS 5 (C) CREOI HSCEMANEOUS STSIDIS 02 P810 0 10 N gt N ~ ~ . IIDYD I ~ I' D. ~ I ~ II IY' I DI 'ID IWI Y II %AID% ODIID hl It D DI ~ ~I ~1 'II 5/4'ENT I V-nel (1547) 5 V 74I2 (1545) II-v-nJJ (IJ24) 21-v-nJJ (1547) I 1-1 2-CS 91 IMP '10 IC AIM I SR 07-2A 21 V 7400 (1224) WANWAY 21 V 29422 (1545) JI V 29451 (IJ45) 29.v-n45 5 FAL 24' I M-Y-7408 (IJJJ) (1224> I I/2~1 255 I H4g 50 HYDRAZSIE STORACE tANK 3-V 7402 (1524) D V 7410 (1524) V V V V 5 V 7444 (1525) 2I V 7442 (1525) S-V-7445 (1525) 'I I SE 07 JA J/4 2I V W45 (1525) NC JI V 7407 (1524) V 7247 (IJ24) LC 21 Fo 21-v-n48 (1524) HIT>RATS': PUMP 2A S-SN-7252 (1096) 2I-Y 7415 (1227) 5/4 DR a-V-7405 (I 524> l,o 2'R I SRW 28 Lo 21-SN 7240 (1196) LC a-V-7409 (I 525) D V 7250 (IJIJ) JI V 7249 ('1524) FE 21 V 7415 (1524) I I ~97 07-21 V 7250 (IJ24) JI V 7414 (1524) M-SN-nJJ (N90) I 2~84 I SENT JS I 2 M 80 NC Fo 21-V 7258 (045) H EFIAJILE PIR84 2Q 21 Y 7411 (1524) IOOSIE REMOVAL SYSTEM (SS> I 50 REACTOR 07 IA AUICUAR'7 BURDSIC 2t V-7402 (1524) 21 Y 7554 (112S) 5 V 7141 (1547) CONTAINMENT SPRAY RECRCRATION SAFEIT RIRCIKN I/2 21 5/4 V 7450 ('l624) V V D V 7449 (1625) I 2W dl I ~JI LO I 2 M 222 I-2-9-222 02- 4 r-4 21 v 7179 (L024) 21 V 7128 (1624) 2l V 7145 (1554) I-12~15 I 12~9 Lo 1-12 S 412 &07-IA CONTAJIM(>IT SPRAY PUMP 5 V 7140 (1524) 2l Y 7144 (1525) S-V-TIJT (1525) I OR D V 7448 (1025) D V 7156 (ldl5) I/2'R I 50 07 18 5 V 7405 (1524) 5 V TIJJ CONTAINMENT SPRAY ~ (1517) JI-V 7220 C127) S-V-7455 (le22) I/2 V S-V-7452 (102J) 42 I 2~ LO 2l V 7152 (N27) i PUMP RECRCRATION I 2 8 224 2l V 7555 (1125) 2!-V 7125 (ld24) D-Y 7120 ('l024) m-V-TIJD (1 004) C 8'4'ON I 12 CS 14 112 CS 8 LO I-I2-8-41 4 S$ 47 IS TASDIENT SPRAY PUMP S-V-TIJ4 (L024> 2N V-7120 (1525) D V 7151 (1525) 74 V 7122 (I525) 3 V 7124 (1015) 2I V 7451 (ldJJ) I OR I V I CR ( 14- SAIEIY NRC I SAIEIT 74EC F- ILCRDA POWER 8 UCHT Co. OAK; DRAWN Slh AFtRCVEO BY: CASS I (A) REO SL MICR PIANT 4907 2 CEDE SCUNONlY OtACRNI CASS 2 (8) SLOE DRAWNO NIWSOD CCNTANIRNT SPRAY 8 REV. CASS 5 (C) CRGN REIIRLNC WAIIR SISIEMS 02 9817 0 0 O~fli W K WK'lW P~ ~- P tWAktol ~ ~ 4t'h%. 4 W l4) e ellHAAlg ~ QAWM.F- ~ ~H/ t r( s~mswA a~aa , i t )IA ~ gem sr I. ~ AQ K f' ~ I j ~ saao~ ~~~ r~ pYW 4 4809I >OO % Af '&%%DE aft& L Wa/l 4~~ JWW40'O~M~~A'HW I3 A 12 24 OLITSOE RISGE MAMNLf CONTAINMENT CONTARIllENT i I 4~57 Riv-72clt (Nfos) OYIRILOW I 5-CS-S2 le 45-05-72 2iv 7159 0409) REFVQJNC WATER TAN( 2I V-7102 (IIOIA) 21 Y 7147 (1525) LC 2l'ANNLf 21 V-7170 (IIOD) I-PCS-SS 47 LAB-DVI BCIDC 10 CHARCNC ROMPS 9 V 7155 (1409) 2I V 1105 (N09) ~7 21 Y 7949 (1525) 24V 7104 (Nol) 9 V 7101 (Iell) 8-Y 7105 (1425) ~1 118 ~eS I-2~95 ce cv co cb FC I 24V-7171 (1525) I~ C7 iLCV 07 IIA INDY 'Is j 2 I Nvor IA I DR I OR 29 V 7205 (152S) 9 Y 7209 (152S) REACTOR 8 V 7519 (IS2S) AUXUARY BOB(XNG 24Y 7515 (1525) I'R I'NT 24Y 7219 (IS24) I YTNT 21 Y 7174 (Ieeo) NC I I I'R 02~ I gN 1-249 S04 24 CS S I------ ~ S-Y 7517 (1525) I a-v-7120 (Ieeo) C 3 V 7210 (1525) iMY-07-2A 24Y-YIIS (Ieeo) OCN I'R I 24 C45 B V 7175 (152S) I 2405-2 21 V 7520 (IS25) I'ENT 21 V 7227 (IS24) I ice 102 RETLIELRI0 I 249 509 21 V 7172 (Ieeo) NC I I 24 CS 4 21-V 7422 (1409) CAVITY N V rl25 (1409) 0 2 I-MY-07-20 I------ CUARDPIPE (IYP) 32 I CR 9 V 7177 (1525) a-Y-7195 (IDOL) 2I V 7424 I 5 CS 94 I-4-cs-es (IIOD) CONTANllENT CONTARSRENT I 405-49 ASME CODE 80IAIDANC5 ILCNDA PCIRR R IICHT CO. DAIT'RAINBY; APPROVED BY: LC 21 Y 7195 (NDI) 2@4-~ Rfv. Il CLASS I (A) RCD Sl. IMCC PLANT INDY 2 02/07790 cA0 OCDC <<NNDIRY DIACRAM CLASS 2 (9) DLIJS DRAMNO IDASOC CCNTANISIIT SPRAY 0 CLASS 5 (C) CRII RLIIRLNC WAITR SYSILMS 02~ 7A 10 I 'I L CONTABdffENT SPRAY HEADERS (179 NOZZLES FOR HEADER A IB 178 FOR HEfe(R 8) H Y 7528 (1525) ~ 24 Y 7514 (1525) 8 V 7527 (1525) I 'VDIT CIPPKD (TYP.) I 8 CS 17 I ~ 52 21 ~ V 7520 (1525) i I 18 SPRAY NOZ11KS 15 SPRAY NOZZIKS I-8-CS-28 21 V 7505 (1525) ~ 2l V 7504 (1525) 25 Y i 58 7502 (1525) SPRAY NOZZLES ~24 5 ~ V 7508 (1525) ~ i 55 SPRAY NCZZLKS 2I Y-7508 (1525) i 80 SPRAY NCZZLXS 9 451 B V 7510 (1525) t&PBC58 E-d 21-V 7217 (1525) 3 ~41d (1524) 5/4'TTIT S-V-7512 (1525) I-I<%5-15 8-V&F157 (\ 525) ~ 1~12 I 10 CS 12 a-V-7158 (1525) I Sf NIZ 02 PUB E 8 5/4 DRAIN 2F-Y 07524 (1524) 21 V 7400 (1424) I 12 Sf 405 I FCV 07 IA 25 V 7142 (1514) I 12~15 FO LC NC S-V-7155 (1555) 5 TEST 21 V 7207 (1505) 21 V 7155 (f525) 21 V 7150 (1524) Zf-V-7151 (IS24) I DR FK m-V-7522 O52O 07 ld Zf-V-7521 (1524) I-FCY-07-18 ZI V 7152 (f555) I 12~10 5 V TIES (1514) I 12-CS 18 SAFETY PAECIICN A LO I NV TKST 07 4 ZP V Tldd (1501) I I 2! Y 7151 (1525) B V 7218 (1525) 21-V-7154 (1524) 21-V 7155 (1524) CCNTADIIIENT OCFITABILIENT ) ) ASMK COCK BCISICAF8ES CLASS I (A) CASS 2 (8) RED BLIIE Zffffd ~ REV. 14 ST LUCE PIANT Vfffv 2 CCCE BOUNDARY CIACRAU CCNTANVOIT SPRAY 8 DATQ CRAWN BY: DRANNO IEINEXTC APPROVED BY: RKV. CLASS 5 (C) CREOI REIELlflC WATER SlfSTEMS 02 PBIIB 0 10 rrttttrtrttt&rtttrtr ' 't tttrtt Itlt trwltt Awe >>UUP trfffttttt tttt rt t ~ ~ t tt ~ ttt M Akttr th trtttl t ~ rr'ate ittrUtr -*f fl'tttttr. II rt~ <<It ~tlrr ~ ttl~ctrt lt U ~ J ~. I trUUUttft ~ ~ FIST (11P.) I J/0-HS 6 CON TAINMENT DCIIE AREA HJ/~I I-FSE-27 6 CON TAFBIENT I-FSE 27 9 eamu RIZER AREA I FSI 27 10 1 ~27101 (IJL2 I FSE 27 10 2BI AREA RCP 2AI AREA S-V-27102 (I JI2) N 7-FSE-27-I J I-J/~0 RCP IW/INIIS-0 2 282 AREA RCP 2A2 AREA 27 I'I I-2/0-NS-7 DOME AREA I-FSE-27-12 FC 1%5S I SISS)E CONTAINMENT HCV 20 'I I FCY 20 2 OUTSOE CONTAINMENT I 1~2 FC NJSE 27 19 bfSE 27 10 27 17 I-fSE 27 16 IM-20 $ IM20 4 J/6-SS 070 fC SANPUNC PS00 (N 2) I 1~$ I-FCV 20 S I fCV-20 0 ~(C 2) J/0-SS 07$ SY I Jt C SYI 4 C SY I 0 C SYI BC BY I 4 C I SISIOE I OUTSS)E CONTASSIENT CONTASIMENT BY I 80 SY I 8 C SY I 4C ) BY I 4 C CON TAINMGIT AIR RAOIATY)N MONITORDIC S'ISTEM SY I *C UNIT 0 2A UIST 0 2B IIIORDCEN SAMPUNC NIOROCOI SAMPUNC S ANALYZER CUBICLE 4 ANALYZER CU(DOLE SYI 8 C I/4 IINNNC I/O'VBNC SYISC I/0'lJONC SY I 4 C H DAIG DRAMI SY; APPROVED SY; IIORROGEN SAMPUNC SYSTEM CLASS I (A) RED ST. LUCK PLANT UNIT 2 02/00/IO PIP CLASS 2 (6) SLCS CAGN OCDE BOIMIARYNACRAM INSCIILNKCVS SAICSJIC SISTGIS DRAMNC NUMB'EV. CLASS $ (C) 02-7810 0 8 9 10 VDDlVV Vt 4hSOIV VDI, D - DV IVVTD~ ~ lDV, IVVDDDIVVVlVV\DDDD If VVDDDVDVDDV&VV1 W@3VV~WV.~ Sm~ W VV ~D W VVW W DXVVDDVV VD~araDf ~ l VVl VADllIVVVI' I-TCV 25 2 IM 25-1 DATE: DRAIRI BY: APPROVED BY: CLASS I (A) am 2998 C-552 REV. d ST LDCE PLANT LRAT 2 CLASS 2 (5) BLOC CODE BLSRCARY DIACRAM NVAC ClASS 5 (C) CREEN e 29 400 02~ (H I) V 3933 0 ~1 37 V 3139 Y-3147 V&149 3/4 Sl 473 V 3934 LC T @V~I I Ot LC Q 3241 V 2 FC I-S-TKD ~ 9 491 3/4 SM 9444 I 9 437 V 37J7 1 V~2 ~739 V 3442 LC FC Y 3242 VM738 I 944 y 3547 V-3559 SAFElY SAFETY I/2 9 395 DLXCTKNT ItLECTICN TANK 281 TANK 2B2 VL'7 VLT VLT- VLT HJ VLT 3341 3341 3331 JJJI 3342 3342 VLT VLT I 9 524 2 9~ RVT RLTVRN 3332 3332 I/2 9&5 1/2 9-442 1/2 Sl 434 02~ HTAIXR AM TR4-318 OM 314 I I Ol 3/8 SS 554 Ol I 3/0-$ 5-557 a \ I 07 9808 2 3 02-9808 f-3 I 9 fC V-3549 V 03040 (1345) HS~ V V-03003 (1345) 21 lD lD Y 3235 1 $ 2~10 V J245 V-3244 3/4-S 291 349 289 V V V~ V 3880 I ~9 y 3431 PAI 1 9 451 V~41 V 3444 3/4 9 290 tt ~ I I ~0 LO 21-50 03 y~ D 3/4 9 288 Y 3241 0 9<<514 LO 2t ~12 y ~/=- 11 9 Ill ~517 I 0S V 3910 4 3/4 S 254 10 T A 12 9 150 12 RC 152 V 3414 aI tt 2 12 9 1$ 1 ~ 17-RC 1$ 3 I V 3237 OI ~47 I Ot aI I V 3740 Y-3811 Y J417 V ~I I I V 3814 Ol V 3912 Ot V 3000 I I D 1 9-2$ 3 D 19751 Ot 1 9 120 Y 3955 sl 1'IO Y 391'I 1-S 480 1-S-$ 34 QTFTRTNCC ORAIIOI05 CATT: ORAHN 8Y: APPROVE 87: CLASS 1 (A) RTD 2990 ~70 SNT 132 RLY. 0 5T. WCE RIANT LIIRT 2 CIASS 2 (0) RLIIC CCCC 80LtleARY QACRAN DRATDKt 147VTKTR RLV. CLASS 3 (C) CRTTN SAFETY 4420710M 515764 02-9820 0 10 O' <<C'>> tP ~ ~ J. <<<< I'3 p<> wi e s'Iv 4 Sl <<4<<l -, ~ 'll <<.E:Q II I - <<II<<ak 'lS E ~ S ~ rtl<<ESV Q t" we<< tse<<<<<<vp s Is PS PE<<a<<4 VS stw>>e t.p<<t 4>> 4<< <<ew'E) jj wtw<<EE ste>>t E PI Eh<<<<.E I>> 't*4>>E<< 'll V J I p>>I, .<<<<tt<< sl <<<<pet<<. J. II <<<<Ea ~ s P Ee >>sl <<<<<<'p P>>S P S 'll <<E E>>j t<<tl>>S "<<<<Itt * . V EI I >> <<<> tlt<<\SIP L- -:-'t>>t<<~ ~ 'Ep<<e<<st<<vt<<\II<<<<J t<< IV >><<Slur ~ C << t WV I ESA>>l (0 l.. I~ <<>>e' ~ t ' ~ I>> <<>>SEI<< ttt<<l W S VVI C-l t V ~ . <<<<4<< .I ~ - <<. <<.as'ts.e el I<<el l<< I~ . P'et S' S'I ~ ~ 'lt<< 'E<<tt <> <<s<<J 4>>t '<<It: .v e <<<<<< <<t 4 V 5117 V&119 V-2847 V O'I27 V 5120 Y~S I t @V~II 4 Ol Ol I LC LC I 9-497 FC ~ 9 404 FC I-S 455 I Sl 454 V 575S S 450 I 9 440 Y 5112 V-5822 LC Ol FC I v 52n 'ID I Sl 448 V-5754 I/2-9-591 Ol ~~ I/2-9-509 SAFElY SAFETY SIXCTION INACTION TANK 2A2 TANK 2A'I LC FC VLT VLT- VLT VLT VLT- 'VLT 5511 ddt I 551 2 5212 VW758 5522 I/2-9-592 12-9 522 Sl Std V 52IS SIWtd I C4 SVMIS DH Std S// W W I \ Ol 4 Ol ~ I I 4I 2/8 SS SSS 5/8 55-554 V&491 9 (1545) 9-~ (ISIS) FC 02-PSOS S-5 ls 487 V&214 I-S-811 I SE 05 IA Y~S ) VM224 ID 5/M 285 5/4-9 287 V V V 5882 V 2854 FC FC I(I 19 047 Y 5411 I 9 845 ~24 FAI 0 54S 284 Y~I4 D 24-9284 2 LO FAI LO I Ol I 5/4 9 254 I I 9 220 V / - /- HCV-5428 VM785 249122 154%-257 I 3 ddtd HCV V-5250 // O 9-SLEDS-00 V 5258 0 9 ltd SS SIS 12& 89518 I 914 'l54 19 8 9112 12 9 148 12 RC a V-2118 c 4I M A 7~7 I Ol 4I I V M V-5857 V 5802 V 5801 I 4 V 5808 0 192ID 0 Y 5884 D I 9247 ~2 I S 12S 2S 400 ISdtt 1511 t 4 1-9-538 H 02 P820 (Art) RTNHCE DRAwHCS FLDROA PCWLR 8 UCHT CO. CATO DRAWN IM APPRCVTO 87; QASS I (A) REO 2098 ~78 SHT. '152 REV. 0 ST LICE PLANT Villi 2 CLASS 2 (S) SLOE CCOE BSROAAY EIACRAll CLASS 5 (C) CROII SAIETY OIXCTKH SISITN 10 <<44544<<ff . O<<YW 4 It ~. 4 ~ P! .: 443<<5<<ftf <<4 I 344 Yk,ji 4 I 4<<343<<l tf o 4<<444 53<< 4<<<<l 'I ~ ~ 444 4 kt<<IOY.AOO I 4 WW kf<<fWf <<1'l*~ .44fffh<<k 4<<f<< 4* 4g ~ 1 1 ~ I '4 1 I'.<<k<<O 4 fft<<344 j(

~~<<4 34 4<<PY 44 4~~
~~4<<<<f 4 I-n i<<44k 4~~

~4 3 1<< fk I 514 I Of! . 44 I<<4*..vt khf '..45-4 k '4 t 4<<t I .3 ~ 44 Of<<4 4<<\ l I 4 I<<t ~ I 'I ~I I ' 'l ! ~ '4- ~ 44 1 I OIA I, 5 143 ' 415. 41 Ikey k' 344- 44 3 <<44 4 ll ~ 4 ~ 1Y t h p I 1 4444<<fffk 43 - ~ ~ - I << I 4 k 44 534 414<<k 4 ~ lt j lt O ~ OO ' I Ol <<4<<44- 4 l= <<414 OOI ~ '. I 3444 . 0 TISRIST BEARTIC IXI K) V-1292 (V-1205) Y-1500 V 1208 (V 1551) (V CQ) RlN ft 1180 V 1298) (V 1505) 5/4~241 V 1299) fE VAPCR SKAL 5/4RC 102 5/4 RC 277 1150 (V 1545) DRAIN CAWlY (V-7542) IlR IN (V-7561) i'j V 1540 CCNTROLLSO 5/4RC 229 8LtfD lff 1~257 5/4RC ITS CA WTY V 1552 185 )~Rf lj j=) Pv-Lug Nl VPT 1152 v-1284 5/ ~~~ 48401-5 5/4-RC 180 5/4~ 257 V-QSO 5/4~255 BS IVER Nl P'9 j:=") LONfJt SCAL CAVITY K! V 1548 5/4~225 V 15 7 I SO-Ol 1 F;=> im p=j 5/4-RC 245 I 5/4-RC-240 V 1558 8/LI 500N (250) (V-1557) (IPT 1141) (251) (V 1282) (VPT 1171) (252) LOWER SEAL 5% (V-1759) (IPT 1181) HEAT EXCHANGER V-1280 V (V 1281) 514814112 Ill 51480 '112 &.l RTTTRTNCE DRAMAS DAlf: DRAlN BY: APPROVKD BY: CLASS 1 (A) RTD 2094~78 SNT lll RCV 1 ST. (LICE PLANT LIAT 2 CLASS 2 (8) CCDE BCARSIARY 11ACRAll BLLR.'LASS RCACTOR COOLAN'f PLINP 5 (C) OR(TN 10 I 4 9 fs ~ IPLA&ll'%~A%. h<AI k l A ae~avw /~erik ~ ' %~M'e F 4 LPQ PUMP 28 CISCHARGE 02 PB05A (E 7) 5/8 55-517 V 5155 IPSI PUMP 2A 02~ (CW) ISCHARCE V 5127 ~ IDSL LPSL 8 CRIT SPItAY PUMPS 28 INB fUTW LSIE (AM) V 5155 IPN, LPSL R CIMT SPItAY PUMPS 2A MIB fLOW LNE 02~ (8-2) I/2-SW 2 V 5150 DAADQN COCLPIO SUDDEN IBB: ChPBXA (C I) 5/0 ~IS V 5151 PURftCAIILTI TT.IER 2A ~ BET 02-PBOIA (N-5) I/2 SS 411 V 5151 PURTICASCN fLWt 2A OUlLET ION KXCHQICGt BAST I/2 SS 510 V 5155 02 PBO2A (0-5) PLPLNCACLII fBTER 28 DURST 02~ (8 10) I/2 SS 005 V SISS PIJRACADON KN NCHHANLBR CUILET/ PLIBACADCN IILTDL 28 PILET V 51ST 02~ (~) DATG DRAIII 81'. APPROVED BY. CLASS I (A) IUD 2275 ~78 IHT, 150 ILLY. I ST. LUCC PLANT UIWT 2 CLASS 2 (8) BLUE COCE BOLROARY CUORAM DRAIINO IIJMBGU REV. SAMPUNO SYSTEM CLASS 5 (C) CRSI 02 P822 0 e' SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 10.0 REPAIRS, REPLACEMENTS AND MODIFICATIONS 10.1 REPAIRS Repairs are performed in accordance with FPL's Design Specification and the original Construction Code of the component or system. Later Editions and Addenda of the Construction Code or of Section III, either in their entirety or portions thereof, and Code cases may be used. 10.1.1 REPAIR OPERATIONS Code repairs are performed in accordance with approved procedures or instructions that meet the requirements of IWAQ000. Repair operations shall be performed in accordance with a program delineating essential requirements of the complete repair cycle and shall include the following: (a) The NDE method that revealed the flaw and the description of the flaw. (b) The fiaw removal method, method of measurement of the cavity created by removing the flaw and dimensional requirements for reference points during and after the repair. (c) Weld procedures and postweld heat treatment, and.the non-destructive examination program to be used after the repair. (d) Evaluation as described in 10A (e) The repair programs shall be subject to review by the enforcement and regulatory authorities having jurisdiction at the plant site. 10.1.2 PRESSURE TESTING After repairs by welding on the pressure retaining'oundary, a system pressure test shall be performed in accordance with IWA-5000 (and when required by lWA-4700). 10.1.3 BASELINE EXAMINATIONS When required by Section XI, the repaired area shall be reexamined to establish a new preservice record. The examination shall include the method that detected the flaw. Page TS of 272 SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 10.2 REPLACEMENTS Replacements are performed using approved procedures or instructions in accordance with IWA-7000. All procedures for the installation of renewal, spare, and replacement parts shall be in accordance with IWAP100. 10.2.1 REPLACEMENT OPERATIONS The Program for replacements shall include the following: (a) The applicable Edition and Addenda of Section XI. (b) A Description of the Items being replaced and the Codes to which they were constructed (c) A description of the work to be performed. (d) The Code Edition, Addenda and Code Cases applicable to materials, design manufacture, and installation. (e) any special requirements pertaining to materials, welding, heat treatment, and nondestructive examination requirements. (f) the test and acceptance criteria to be used to verify the acceptability of the replacement. (g) The documentation required by IWA-7600. (h) The application of the ASME Code Symb'ol Stamp in accordance with IWA-7300. 10.2.2 ENGINEERING APPROVAL-Replacements that involve substitution of materials, dimensional-changes, process changes, deviations to specifications or changes to. design codes require engineering approval. 10.2.3 PRESERVICE EXAMINATIONS Prior to the systems return to service a preservice inspection shall be made in accordance with IWB-2200, IWC-2200, IWD-2200, and IWF-2200 for the component and part replaced. Page 79 of 272 SECOND INSPECTION. INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, f993 10.3 MODIFICATIONS The performance of modifications is controlled in accordance with Quality Procedure QP 3.4. 10.4 EVALUATION When. the repair, replacement or modification is required because of failure of a part or component pressure boundary, an evaluation shall be done to ensure that the replacement is suitable and the repair procedure selected is suitable. The cause of failure shall be evaluated in accordance with the Code. When equipment cannot be restored to design configuration, equipment substitutions are needed, or conditional use is necessary; and plant modifications are deemed inappropriate for various reasons, the necessary engineering evaluations shall be documented. 10.6 ACCESS Components of the Reactor Coolant System were designed to provide access to permit inservice inspection in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, 1971 Edition and Addenda through the Summer 1973. Adequate access and clearances for examination and tests shall be considered by Nuclear Engineering as part of the processing of design or arrangement changes of system components in accordance with Quality Procedure QP 3.4. 10.6 CONSTRUCTION CODES Components, parts, and piping shall be procured to the requirements of the construction code of record as indicated in the original purchase order specification. Later editions and addenda of the Code may be used provided they are in accordance with IWA-7210. The design and analysis of piping, components and supports shall meet the design code of record as identified in the FSAR or design specification. Welding activities shall meet'the requirements of the original construction, code. Alternatively, Nuclear Engineering may specify that the use of a later edition of the construction code, or Section III, as identified in the welding control manual may be used. Note: Later editions and addenda may be used provided that they have been endorsed by the USNRC and are incorporated in 10 CFR so.ssa(g). Page 80 of 272 SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 10.7 AUTHORIZED NUCLEAR INSERVICE INSPECTOR The services of an Authorized Inspection Agency shall be used when making all repairs. FPL shall notify the ANII prior to starting the repair, replacement or modification and keep the inspector informed of the progress of the work so that necessary inspections may be performed. 10.8 IMPLEMENTATION All ASME Section XI Class 1, 2, and 3 Repairs and Replacements are controlled by site procedures. l TABLE 'IO-1 CONSTRUCTION CODES COMPONENTS CODE SECTION EDITION/ADDENDA CLASS Piping Section III 71S73 123 Components Section III 71S73 123 Components Section Vill 71S73 2 3 Note: Applicable Construction Code Edition and Addenda will be checked for the affected component. Page S1 of 272 SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24,'993 11.0 RECORDS 11.1 GENERAL'xaminations, tests, replacements, and repair records are prepared in accordance with the requirements of the ASME Boiler and Pressure Vessel Code,Section XI. 11.2 INSERVICE INSPECTION

~~SUMMARY~~
REPORT An Inservice Inspection Summary Report will be prepared at the completion of each inspection conducted during a refueling outage.
Examinations, tests, replacements, and.repairs conducted since the preceding summary report shall be included.
Each Summary Report will contain the following:
~~a. Refueling outage number (when applicable).~~
~~b. Owner's Data Report for Inservice Inspections, Form NIS-1, Figure 11-1.~~
~~c. Owner's Data Report for Repairs or Replacements, Form NIS-2, Figure 11-2.~~
~~d. Owner's Data Report for Steam Generator Tube Inspections, Form NIS-BB, Figure 11-3.~~
~~Subject of Relief Request Number 16 11.3 COVER SHEET Each Summary Report will have a cover sheet providing the following information:~~
~~a. date of document completion~~
~~b. name and address of Owner~~
~~c. name and address of generating plant~~
~~d. name and number designation of the plant~~
~~e. commercial service date for the unit Page S2 of 272~~
~~SECOND INSPECTION INTERVAL'SL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 11.4~~
~~SUMMARY~~
REPORT SUBMITTAL Ninety days (90) following the units return to service, FPL shall forward a Summary Report of the Inservice Inspection activity to=-the Nuclear Regulatory Commission in accordance with IWA-6220.
Subject of Relief Request Number 16 Page 83 of 272
SECOND INSPECTION INTERVAL PSL-200 INSERVICE /NSPECTION . REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, f993 FORM NIS-1 OWNERS'ATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
~~1. Owner: Florida Power and Light Company 700 Universe Blvd.~~
~~Juno Beach, Florida 33408~~
~~2. Plant: St. Lucie Plant 6501 South Highway A1A Jensen Beach, Florida 34957~~
~~3. Plant Unit: 2 4. Owner Certificate of Authorization (if required) N/A~~
~~5. Commercial Service Date: 08/08/1983 6. National Board Number for Unit:~~
~~N/A~~
~~7. Components Inspected:~~
Manufacturer Component or Manufacturer or Installer State or National ppurtenance or Installer Serial No. Province No. Board No.
Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 x 11 in. (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number.
of sheets is recorded at the top of this form.
FIGURE 11-1 NIS-1 Owner's Data Report Page S4 of 272
SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION . REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 FORM NIS-1 OWNERS'ATA REPORT FOR INSERVICE INSPECTIONS 8: Examination Dates: to
~~9. Inspection Period Identification:~~
~~10. Inspection Interval Identification:~~
~~11. Applicable Edition of Section XI~~
~~12. Date/Revision of Inspection Plan:~~
~~13. Abstract. of Examinations and Tests. Include a list of examinations and tests and a statement concerning status of work required for inspection Plan.~~
~~14. Abstract of Results of Examinations and Tests.~~
~~15. Abstract of Corrective Measures.~~
We certify that a) the statements made ln this report are correct b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section Xf, and c) corrective measures taken conform to the rules of the ASME Code, Section XL Certificate of Authorization NO. (If applicable) ~
Expiration Date Date 19 Signed by Owner: Florida Power and Light Company Signed Date: 199 OWNER OR OWNER'S DESIGNEE, TITLE CERllFICATE OF INSERVICE INSPECTION I, the undersigned, holding. a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and/ or the State or Province of and employed by have Inspected the components described in this OWNERS'ata Report during the period to and state that to the best of my.knowledge and.belief, the Owner has performed examinations and taken corrective measures described ln the .
Owners'ata Report In accordance with the requirements of the ASME Code, Section Xl.
By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, and neither the inspector nor his employer shall be liable in any manner for any peisonal Injuiy or property damage or loss of any kind arising from or connected with this inspection.
COMMtSSION NUMBER Inspector's Signature National Board, State, Province, and Endorsements Date: 19 Page S5 of 272
SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 FORM NIS-2 OWNERS'EPORT FOR REPAIRS OR REPLACEMENTS As Required by, the Provisions of the ASME Code Section XI
~~1. OWNER: Florida Power and Light Company DATE:~~
~~P.O. Box 14000 Juno Beach, Florida 33408 SHEET'F~~
~~2. PLANT: St. Lucie Plant VNIT¹: 2 6501 South A1A Jensen Beach, FL. 34t;57 (REPAIR ORGANIZATION P.O. NO., JOB NO., ctc.) .~~
~~3. WORK PERFORMED BY: TYPE CODE SYMBOL STAMP:~~
AUTHORIZATION NO.:
EXPIRATION DATE'.
IDENTIFICATION OF SYSTEM:
~~6. (a) APPLICABLE CONSTRUCTION CODE: EDITION ADDENDA CODE CASE (b) APPLICABLE EDITION OF SECTION XI UTILIZED FOR REPAIR OR REPLACEMENT~~
6. IDENTIFICATION OF COMPONENTS REPAIRED OR REPLACED AND REPLACEMENT COMPONENTS Name of Name of Manufacturer National Other Year Replaced ASME Component Manufacturer Serial Board Identification Built Repaired Codo Number No. or Stamped Replacemont IY or N)
~~7. DESCRIPTION OF WORK:~~
~~8. TEST CONDUCTED: HYDROSTATIC [] PNEUMATIC []~~
NORMAL OPERATING PRESSURE [] OTHER []
PRESSURE'SIG TEST TEMP: DEGREES F FIGURE 11-2 NIS-2 Report Page S6 of 272
SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 NIS-2 REPORT CONTINUED
~~9. REMARKS:~~
CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this conforms to the rules of the ASME Code Section XI (Repair/Replacement)
Type Code Symbol Stamp: NIA--
Certificate of Authorization No.: Expiration Date: NIA Signed OWNER OR OWNERS'ESIGNEE, TITLE Date, 19 CERTIFICATE OF INSERYICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of MARTIN COUNTY, FLORIDA and employed by ARKWRIGHT MUTUAL INSURANCE COMPANY of NORWOOD, MASSACHUSETTS have inspected the components described in this Owners'eport during period to and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this in accordance with the requirements of the ASME Code,Section XI.
Owners'eport By signing this certification neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners'eport. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.
Commissions Inspector's Signature National Board, State, Province and Endorsements DATE: 1 19 Page 87 of 272
SECOND INSPECTION /NTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 Eddy Current Summary of Results Plant:
Examination Dates: Through Total Tubes Steam Total Total Ind. Total Ind. Plugged as Total Generator Tubes z 20% > 40% Preventive Tubes Inspected to 39%, to 100% I"laintenance Plugged Location of Indications Steam U Bends Egg crates Partial Top of Tube Generator DHB to DCB 1to7 Supports Sheet to N H/L C/L 8 and 9 Eggcrate H/L C/L . H/L C/L Certification of Record t
We certify that the statements in this record are correct and the tubes inspected were tested in accordance with the requirements of Section XI of the ASME Code.
FLORIDA POWER and LIGHT COMPANY Organization Date: Prepared By:
S/G Eddy Current Coordinator Date: Reviewed By:
Inspections Supervisor FIGURE 11-3 NIS-BB Report Page 88 of 272
SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION, REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 STEAM GENERATOR TUBES PLUGGED
'STEAM GENERATOR A STEAM GENERATOR B ROW LINE REMARKS ROW LINE REMARKS Page S9 of 272
SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 Steam Generator Eddy Current Examination Results PLANT:
EXAMINATION DATES: THROUGH ROW LINE % TUBE =
ORIGIN LOCATION WALL'ENETRATION Page 90 of 272
SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 APPENDIX A CLASS 1
~~SUMMARY~~
TABLES Page 91 of 272
DATE: 07/24/93 ST. IUCIB NUCLEAR PLANT UNIT 2 PAGE: 1 REVISION: 0 INSERVZCE INSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XZ SUNMARY TABLE A CATEGORY B-A - PRESSURE RETAINING WELDS IN REACTOR VESSEL
¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS B1 . 12 LONGITUDINAL SHELL WELDS VOLUMETRIC 001 REACTOR PRESSURE 0 9 9 0 0 9 0 0 0 Includes VESSEL 001 0% 100% 100% essentially 100%
of weld length, all welds, B1.21 CIRCUMFERENTZAL HEAD WELDS VOLUMETRIC 001 REACTOR PRESSURE 0 2 2 0 0 2 0 0 0 Accessible length VESSEL 001 0¹ 100% 100% of all welds, deferral permissible VOLUiiRIC 002 REACTOR PRESSURE 001 1 1 1 0 0 0 0 0 VESSEL CLOSURE HEAD 100% 100k 100'C ITEM TOTAL 3 3 1 0 2 0 0 0 33% 100% 100%
81.22 MERIDIONAL HEAD WELDS VOLUiiRIC 001 REACTOR PRESSURE 001 6 6 . 0 0 6 0 0 0 Accessible length VESSEL 0¹ 100% 100% of all welds, deferral permissible VOLUiiRZC 002 REACTOR PRESSURE 001 4 4 4 0 0 0 0 0 VESSEL CLOSURE HEAD 100% 100% 200%
ITEM TOTAL 10 10 4 0 6 0 0 0 40% 100% 100't BID 30 SHELL-TO-FLANGE WELD VOLUMETRIC 001 REACTOR PRESSURE 001 1 1 0 0 0 0 0 100% of weld, VESSEL 0% 100% 200% Partial Deferral Permissible, See Code footnote (3)
B1.40 HEAD-TO-FLANGE WELD VOLUMETRIC 002 REACTOR PRESSURE 001 1 1 1 0 0 0 0 0 100% of weld, SURFACE VESSEL CLOSURE HEAD 100% 100% 100t Partial Deferral Permissible, See footnote <3)
0 DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 2 REVISZON: , 0 INSERVICE INSPECTION PLAN'FOR THB SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XZ SUYMARY TABLE A CATEGORY B-A - PRESSURE RETAINING WBLDS IN REACTOR VESSEL
¹ OF COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ZTEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER CONTENTS CATEGORY TOTAL 24 24 6 0 18 0 0 0 25't 100% 100't
DATE: 07/24/93 ST. LUCIB NUCLEAR PLANT UNIT 2 PAGE: 3 REVISION: 0 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XI
~~SUMMARY~~
TABLB A CATEGORY 8 PRESSURE RETAINING WFLDS IN VESSELS OTHER THAN REACTOR VESSELS
¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COi4PLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER CO)IENTS 82.11 PRESSURIZER-CIRCUMFERENTIAL VOLUMETRIC 005 PRESSURIZER 014 2 2 2 0 0 0 0 0 both welds, SHELL-TO-HEAD WELDS 100 t 100t 100t essentailly 100t of the weld length
82. 12 PRESSURIZER-LONGZTUDINAIi VOLUMETRIC 005 PRESSURIZER 014 4 2 2 0 0 0 0 1 foot of one SHELL-TO-HEAD WELDS 100t 10 0t' 100t weld, Per head, that intersects the circ. weld.
82. 31 STEAM GENERATORS (PRIMARY VOLUiiRZC 003 STEAN GENERATOR 0 5 1 0 0 0 0 1 0 One weld per SIDE) -CIRCUMFERENTIAL HEAD 2A PRIX)ARY SIDE 014 Ot Ot 100t head, 100t weld WELDS length, limited One Vessel VOLUiiRIC 004 STEAN GENERATOR 0 5 0 0 0 0 0 0 0 28 PRIMNARY SIDE III**1t 1*'1*l+t %l****t ITEM TOTAL 10 1 0 0 0 0 1 0 Ot Ot 100t 82.32 STEAM GENERATORS {PRIMARY VOLUMETRIC 003 STEAN GENERATOR 0 9 2 0 0 0 0 2 0 One weld per SIDE) -MERIDIONAL HEAD WELDS 2A PRZMNARY SIDE 014 Ot Ot 100t head.100t of weld length, limited to -ne vessel VOLUMETRIC 004 STEAM GENERATOR 0 9 0 0 0 0 0 0 0 28 PRIYaaRY SIDE **1**et * ~ 1 ~ Iet ~ I ~ Iltt ITEM TOTAL 18 2 0 0 0 0 2 0 Ot Ot 100t
82. 40 STEAM GENERATORS (PRIMARY VOLUMETRIC 003 STEAM GENERATOR 014 1 1 0 0 0 0 1 0100tof weld SIDB)-TUBBSHEBT-TO-HEAD WELD 2A PRIYNARY SIDE Ot Ot 100t length, limited to One Vessel VOI UNETRZC 004 STEAM GENERATOR 1 0 0 0 0 0 0 0 28 PRIYNARY SIDE ~ 040 ~ 4t 41*i I ~ t *111 ~ It
DATE: 07/24/93 ST, LUCZE NUCLEAR PLANT UNIT 2 PAGE: 4 RBVISZON: 0 INSERVICE INSPECTION PLAN FOR THB SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XZ S~iY TABLE A CATEGORY B-B - PRESSURE RETAINING OLDS IN VESSELS OTHER THAN REACTOR VESSELS ASME ¹ OF COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEN DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION 'EQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS ITEM TOTAL 2 1 0 '
0 0 1 0 0% 0% 100%
CATEGORY TOTAL 36 8 4 0 0 0 4 0 50% 50% 100%
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGB: 5 REVISION: 0 INSERVICE INSPECTION PIAN 'FOR THB SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XI
~~SUMMARY~~
TABLE A CATEGORY B-D - FULL PENETRATION WELDS OF NOZZLES IN VESSELS INSPECTION PROGRAM B ASME I OF COMPONENTS SEC. XI ZONE RBL )) OP NO SCHEDULED/COMPLETED ITEM )) ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS B3. 100 REACTOR VESSEL-NOZZLE INSIDE VOLUMETRIC 001 REACTOR PRESSURB 014 6 6 0 0 6 0 0 0 All Nozzlcs, 25t RADIUS SECTION VESSEL 0't 100t 100t to 50t 1st period, Remainder end Interval B3.110 PRESSURIZER-NOZZIE-TO-VESSEL VOLUMETRIC 005 PRESSURIZER 003 6 6 6 0 0 0 0 0 All Nozzles, 25t WELDS 014 100t 100t 100t to 50t 1st Period, Remainder end Interval.
B3.120 PRESSURIZER-NOZZLE INSIDE VOLUMETRIC 005 PRESSURIZER 0 6 6 6 0 0 0 0 0AllNozzles, 25t RADIUS SECTION 014 100t 100t 100t to 50t 1st Period, Remainder end Interval.
B3. 130 STEAM GENERATORS (PRIMARY VOLUMETRIC 003 STEAM GENERATOR 014 3 3 0 0 0 0 3 0 All Nozzles, 25t SIDE) -NOZZLE-TO-VESSEL WELDS 2A PRIMMARY SIDE Ot Ot 100't to 50t 1st Period, Remainder end Interval.
VOLUMETRIC 004 STEAM GENERATOR 003 3 3 0 0 0 0 3 0 2B PRIYNARY SIDE Ot Ot 100t ITEM TOTAL 6 6 0 0 0 0 6 0 Ot Ot 100t B3. 140 STEAM GENERATORS (PRIMARY VOLUMETRIC 003 STEAM GENERATOR 014 3 3 0 0 0 0 3 0 All Nozzlcs, 25t SIDE) NOZZLE INSIDE RADIUS 2A PRIYMARY SIDB Ot Ot 100t to 50t 1st SECTION Period, Remainder end Interval.
VOLUMETRIC 004 STEAM GENERATOR 0 3 3 0 0 0 0 3 0 2B PRI~~ Y SIDE Ot 100t 6 6 0 0 0 0 6 0 Ot Ot 100t t B3.90 REACTOR VESSEL NOZZM-TO-VESSEL WELDS VOLUMETRIC 001 REACTOR PRESSURE 001 VESSEL 0 6 6 0 Ot 0 6 100t 0 0 0 All Nozzlcs, 25t 100t to 50t 1st Period, Remainder cnd Interval,
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE:
REVISION: 0 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XI SUiiRY TABLE A CATEGORY B D FULL PENETRATION WELDS OF NOZELES IN VESSELS INSPECTION PROGRAM B
¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS CATEGORY TOTAL 36 36 12 0 12 0 12 0 33't 66% 100%
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 7 REVISION: 0 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CODS EDITION: 89 CLASS 1 SECTION XI SUNCKY TABLE A CATEGORY B-F - PRESSURE RETAINING DISSIMILAR METAL WFLDS
¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS B5. 130 PIPING-DISSIMILAR METAL BUTT VOLUMETRZC 008 REACTOR COOLANT 005 1 1 1 0 0 0 0 0 All welds.
WELDS )i 4 INCHES NOMINAL PIPE SURFACE PIPING, LOOP A SG-2A 100't 100t 100t TO RCP-2A2 VOLUMETRIC 009 REACTOR COOLANT 005 1 0 0 1 0 0 0 SURFACE PIPING, LOOP A FROM Ot 100t 100\
RCP-2A2 TO RPV VOLUMETRIC 010 REACTOR COOLANT 005 1 1 1 0 0 0 0 0 SURFACE PIPZNG, LOOP B SG-2B 100t 100t 100t TO RCP-2B1 VOLUMETRIC 011 REACTOR COOLANT 005 1 1 1 0 0 0 0 0 SURFACE PIPING, LOOP B FROM 100't 1008 100t RCP-2B1 TO RPV VO~iZC 012 REACTOR COOLANT 005 1 1 1 0 0 0 0 0 SURFACE PIPING, LOOP A SG-2A 100't 100t 100t TO RCP 2A1 VOI UMETRIC 013 REACTOR COOLANT 005 1 1 0 0 0 0 1 0 SURFACE PIPING, LOOP A FROM Ot Ot 100t RCP-2A1 TO RPV VOLUiiRZC 014 REACTOR COOLANT 005 1 1 0 0 0 0 1 0 SURFACE PIPING, LOOP B SG-2B 0't Ot 100't TO RCP-2B2 VOLUMETRIC 015 REACTOR COOLANT 005 1 1 0 0 0 0 1 0 SURfACE PIPING, LOOP B Ot Ot 100t RCP 2B2 TO RPV VOLUMETRIC 016 PRESSURIZER 1 1 0 0 1 0 0 0 SURFACE SURGE LINE Ot 100t 100t VOLUMETRIC 021 LOOP 2A1 SAFETY 0 1 1 0 0 0 0 1 0 SURFACE INJECTION PIPING, 0't Ot 100 t INSIDE CTMT VOLUMETR C 022 LOOP 2A2 SAFETY 0 1 0 0 0 0 1 0 SURFACE INJECTZON PIPING, Ot Ot 100t INSIDE CTii'
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 8 REVISION: 0 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XZ SUGARY TABLE A CATEGORY B-F PRESSURE RETAINING DISSIMILAR METAL WELDS ASME ¹ OF COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS B5. 130 PIPING-DISSIMILAR METAL BUTT VOLRKTRIC 023 LOOP 2B1 SAFETY 0 1 1 0 0 0 0 1 0 All welds.
WELDS )>> 4 ZNCHBS NOMINAL PIPE SURPACE INJECTION PIPING, Ot Ot 100t SIZE INSIDE CRK VOLUMETRIC 024 LOOP 2B2 SAFETY 0 1 1 0 0 0 0 1 0 SURFACE INJECTION PIPING, Ot Ot 100t INSIDE CIST VOLUiiRIC 028 LOOP 2B SHUTDOWN 0 1 1 0 0 0 0 1 0 SURFACE COOLING LINE Ot Ot 100t VOLUMETRIC 029 LOOP 2A SHUTDOWN 0 1 1 1 0 0 0 0 0 SURFACE COOLING LINE 100t 100t 100t ITEM TOTAL 15 15 5 0 2 0 8 0 33t 46t 100t B5. 140 PIPING-DISSIMILAR METAL BUTT VOLUMETRIC 006 REACTOR COOLANT 1 1 1 0 0 0 0 0 All welds.
WELDS ( 4 ZNCHES NOMINAL PIPE SURFACE PIPZNG, LOOP A FROM 100t 100t 100t SIZE RPV TO SG-2A SURFACE 026 LOOP 2B1 SPRAY 0 1 1 0 0 1 0 0 0 LINE Ot 100 t 100t SURFACE 027 LOOP 2B2 SPRAY 0 1 1 0 0 0 0 1 0 LINE Ot Ot 100t SURFACE 030 PRESSURIZER 0 1 1 1 0 0 0 0 0 AUXILIARY SPRAY 100t 100t 100t SURFACE 031 L7IARGING LINE TO 0 1 1 0 0 1 0 0 0 LOOP 2B1 Ot 100t 100t SURFACE 032 CHARGING LINE TO 0 1 1 0 0, 1 0 0 0 LOOP 2A2 Ot 100t 100t V
SURFACE 033 LOOP 2A1 PRIMARY 0 1 1 1 0 0 0 0 0 DRAIN 100t 100t 100t
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 9 REVISION: 0 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECI'ION XI SUYNARY TABLE A CATEGORY B-P - PRESSURE RETAINING DISSIMILAR METAL WELDS
¹ OF COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP,REQ 1ST PER 2ND PER 3RD PER COMMENTS B5. 140 PIPING-DISSIMILAR METAL BUTT SURFACE 034 LOOP 2A2 PRIMARY 0 1 1 0 0 0 0 0 All welds.
WELDS ( 4 INCHES NOMINAL PIPE DRAIN 0%' 100t 100t SIZE SURFACE 035 LOOP 2B1 PRIMARY 0 1 1 0 0 0 0 1 0 DRAIN 0't Ot 100 t SURFACE 036 LOOP 2B2 PRIMARY 0 1 1 0 0 0 0 1 0 DRAIN Ot Ot 100't ITEM TOTAL 10 10 3 0 4 0 3 0 30t 70t 100t B5.40 PRESSURIZER-NOZZLE-TO SAFE END VOLUMETRIC 005 PRESSURIZER 0 3 3 3 0 0 0 0 0 All welds.
BUTT WELDS )>> 4 INCHES NOMINAL SURFACE 014 100t 100t 100't PIPE SIZE VOLUMETRIC 016 PRESSURIZER 014 1 1 1 0 0 0 0 0 SURPACE SURGE LINE 100t 100't 100t VOLUiiRIC 025 COMBINED 0 1 1 1 0 0 0 0 0 SURFACE PRESSURIZER SPRAY 100t 100t 100t LINE VOLUMETRIC 038 PRESSURIZER 014 1 1 1 0 0 0 0 0 SURFACE RELIEF LINE 100t 100t 100t 6 6 6 0 0 0 0 0 100t 100t 100t CATEGORY TOTAL 31 31 14 0 6 0 11 0 64t 100t
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGEr 10 REVZSIONr 0 ZNSERVZCE INSPECTION PLAN 'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XI
~~SUMMARY~~
TABLE A CATEGORY B-G 1 - PRESSURE RETAINING BOLTING GREATER THAN 2 INCHES IN DIAMETER
¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRZPTZON EXAM METHOD SYSTEM DESCRZPTZON REQ CNP REQ 1ST PER 2ND PER 3RD PER CO%ANTS B6. 10 REACTOR VESSEL-CLOSURE HEAD SURFACE 001 REACTOR PRESSURE 0 1 1 0 0 0 0 1 0 All nuts, VESSEL 0% Ot 100% deferral permissible footnote (6)
B6.180 PUMPS-BOLTS AND STUDS VOLUMETRIC 017 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 Exams limited to PUMP 2Al l I ****8 t *** t 't ~ tttttti components selected under Cat. B-L-2.
VOLUiiRIC 018 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 PUMP 2A2 ttttttrr ~ tttttrrr *lit*8 ~
VOLUiiRIC 019 REACTOR COOLANT 0 1 1 1 0 0 0 0 0 PUMP 2B1 100% 100% 100%
VOL~i IC 020 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 PUMP 2B2 tttttt8 ****ltd I 1 *l 't t Q ITEM TOTAL 4 1 1 0 0 0 0 0 100't 100% 100%
B6.190 PUMPS-FLANGE SURFACE. WHEN VISUAL 017 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 Exams limited to CONNECTION DISASSEMBLED PUMP 2A1 ttttttg llttttg **tl~ tQ components selected under B-L-2.
VISUAL 018 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 PUMP 2A2 ttltttt ttttttg I ~ ttt t%
VISUAL 019 REACTOR COOLANT 0 1, 1 0 0 1 0 0 0 PUMP 2B1 08 100% 100%
VISUAL 020 REACTOR COOLANT 0 0 0 0 0 0 0 0 PUMP 2B2 ll ttt% Ill* t'0
~ ~ lttttt%
ITEM TOTAL 4 1 0 0 0 0 0 0% 100% 100%'
B6.200 PUMPS NUTS, BUSHZNGS, AND VISUAL 017 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 Exams limited to WASHERS PUMP 2A1 t\tttt$ tttttt$ it'll\ components selected by Cat.
B-L-2 ~
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNZT 2 PAGE: 11 REVZSZON: 0 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XI
~~SUMMARY~~
TABLE A CATEGORY B-G PRESSURE RETAINING BOLTING GREATER THAN 2 INCHES IN DIAMFTER ASME ¹ OF COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COF34ENTS B6.200 PUMPS NUTS, BUSHINGS, AND VISUAL 018 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 Exams limited to WAS HERS PUMP 2A2 IIII~ *$ *1*4*1$ I0 l*Ie8 components selected by Cat.
B-L-2.
VISUAL 019 REACTOR COOLANT 0 1 1 1 0 0 0 0 0 PUMP 2B1 100% 100% 100%
VISUAL 020 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 PUMP 2B2 4401 11% ~ 110 ~ 0 'C 14*1St)
ITEM TOTAL 4 1 1 0 0 0 0 0 100% 100% 100%
B6.30 REACTOR VESSEL-CLOSURE STUDS, VOLUMETRIC 001 REACTOR PRESSURE 0 1 1 0 0 0 0 1 0 All studs, WHEN REMOVED SURFACE VESSEL 0% 08 100% Deferral Permissable B6.40 REACTOR VESSEL-THREADS ZN VOLUMETRIC 001 REACTOR PRESSURE 014 1 1 0 0 1 0 0 0 All threads in FLANGE VESSEL 0% 100% 100% flange, when dissassembled.
B6. 50 REACTOR VESSEL-CLOSURE VISUAL 001 REACTOR PRESSURE 0 1 1 0 0 0 0 1 0 Deferral WASHERS, BUSHINGS VESSEL 0% Ot 100% Permissible, See footnote (5)
CATEGORY TOTAL 16 7 2 0 2 0 3 0 28% 57% 100%
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 12 REVISION: 0 INSERVICE INSPECTION PLAN FOR THB SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XZ
~~SUMMARY~~
TABLE A CATEGORY B-G 2 PRESSURE RETAINING BOLTING 2 INCHES AND LESS IN DIAMETER ASME E OP COMPONENTS SEC. XI ZONE REL 8 OF NO. SCHEDULED/COMPLETED ITEM 9 ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRZPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COKKNTS B7. 10 REACTOR VESSEL-BOLTS STUDS'ND VISUAL 002 REACTOR PRESSURE 001 8 8 2 0 4 0 2 0 All bolts, studs NU1'S VESSEL CLOSURE HEAD 25% 75% 100% and nuts.
B7. 20 PRESSURIZER-BOLTS, STUDS, AND VISUAL 005 PRESSURIZER 014 2 2 2 0 0 0 0 0 bolts, studs NUTS 100% 100%
100'll and nuts.
B7. 30 STEAM GENERATORS-BOLTS, STUDS, VISUAL 003 STEAM GENERATOR 014 4 4 0 0 0 0 4 0 All bolts, studs AND NUTS 2A PRIYNARY SIDE 03 0% 100% and nuts, limited to Exam Cat B-B.
VISUAL 004 STEAM GENERATOR 0 4 0 0 0 0 0 0 0 2B PRIYMARY SIDE eeeee*$ eI+eI*$ PA+11 ~ Q ITEM TOTAL 8 4 0 0 0 0 4 0 0't 0't 1008 B7.50 PIPING-BOLTS, STUDS, AND NUTS VISUAL 005 PRESSURIZER 014 3 3 3 0 0 0 0 0 All bolts, studs 100% 100k 100% and nuts. limited to Exam Cat. B-J.
VISUAL 028 LOOP 2B SHUTDOWN 0 2 1 0 0 0 0 0 COOLING LINE 0% 1008 100%
VISUAL 029 LOOP 2A SHUTDOWN 0 2 1 0 0 1 0 0 0 COOLING LINE 0% 100% 100\
VZSUAL 033 LOOP 2A1 PRIMARY 0 1 1 1 0 0 0 0 0 DRAIN 100% 100% 100%
VISUAL 034 LOOP 2A2 PRIMARY 0 1 1 1 0 0 0 0 0 DRAIN 1008 100% 100%
VISUAL 035 LOOP 2B1 PRIMARY 0 1 1 1 0 0 0 0 0 DRAIN 100% 100% 100\
VISUAL 036 LOOP 2B2 PRIMARY 0 1 1 1 0 0 0 0 0 DRAIN 100% 100% 100%
ITEM TOTAL 11 9 7 0 2 0 0 0 77% 100% 100t B7.70 VALVES BOLTS, STUDS, AND NUTS VISUAL 021 LOOP 2A1 SAFETY 3 3 0 0 0 0 3 0 All bolts, studs ZNJECTION PZPING, 0% 0% 100% and nuts. Limited INSIDE CTMT to Exam Cat.
B-M-2.
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 13 REVISION: 0 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XI SU>WARY TABLE A CATEGORY B G 2 - PRESSURE RETAINING BOITING 2 INCHES AND LESS IN DIAMETER
¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS B7. 70 VALVES BOLTS, STUDS, AND NUTS VISUAL 022 LOOP 2A2 SAFETY 3 0 0 3 0 0 0 All bolts, studs INJECTION PIPING, 0% 100% 100% and nuts. Limited INSIDE CIÃI' to Exam Cat.
B-M-2.
VZSUAL 023 LOOP 2B1 SAFETY 3 0 0 1 0 2 0 INJECTION PIPING, 0 0% 33% l.00%
INSIDE CIA' VISUAL 024 LOOP 2B2 SAFETY 3 3 3 0 0 0 0 INJECTION PZPZNG, 100i' 100% 100¹ INSIDE CTMT VISUAL 028 LOOP 2B SHUTDOWN 5 4 0 0 3 0 1 0 COOLING LINE 0 0% 75%
100'ISUAL 029 LOOP 2A SHUTDOWN 3 2 2 0 0 0 0 0 COOLING LINE 100% 100% 100%
VISUAL 037 LETDOWN LINE 0 3 1 0 0 1 0 0 0 FROM LOOP 2B1 0% 100% 100%
VISUAL 038 PRESSURIZER 0 4 4 0 0 0 0 4 0 RELIEF LINE 0% 08 100%
ITEM TOTAL 27 23 5 0 8 0 10 0 21% 56% 100%
CATEGORY TOTAL 56 46 16 0 14 0 16 0 34% 65% 1008
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGB: 14 REVISION: 0 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XZ SUaaRY TABLE A CATEGORY B-H INTEGRAL ATTACHMENTS FOR VESSELS
¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PBR 2ND PER 3RD PER COYAENTS B8. 20 PRESSURIZER-INTEGRALLY WELDED SURFACE 005 PRESSURIZER 014 1 1 1 0 0 0 0 0 100% of ATTACHMENTS 100% 100% 100% attachment weld length 5/8'r greater B8. 30 STEAM GENERATORS-INTEGRALLY SURFACE 003 STEAM GENERATOR 014 1 1 0 0 0 0 1 0 Limited to One WELDED ATTACHMENTS 2A PRIMARY SIDE 08 100% Vessel, 1008 of attachment weld length SURFACE 004 STEAM GENERATOR 0 1 0 0 0 0 0 0 0 2B PRZ WARY SIDE 111%1 ~ $ ******( *Il*llf ITEM TOTAL 2 1 0 0 0 0 1 0 0't 0% 100%
CATEGORY TOTAL 3 2 1 0 0 0 1 0 50% 50% 100%
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 15 REVISION: 0 INSERVICE INSPECTION PLAN 'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XI SUÃ4ARY TABLE A CATEGORY B-J - PRESSURE RETAINING FIELDS IN PIPING ASME ¹ OF COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDULED/COi4PLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRZPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS B9. 11 CIRCUMFERENTIAL PIPE MELDS )>> VOLUiiRIC 001 REACTOR PRESSURE 014 12 12 0 0 12 0 0 0 25% of all Circ 4 IN. NOMINAL PIPE SIZE SURFACE VESSEL 0 0% 100% 100i butt welds, Essentially 100%
of the weld VOLUMETRIC 006 REACTOR COOLANT 3 1 0 0 0 0 1 0 SURFACE PIPING, LOOP A FROM 014 0% 0% 100%
RPV TO SG-2A VOLUMETRIC 007 REACTOR COOLANT 0 3 1 1 0 0 0 0 0 SURFACE PIPING, LOOP B FROM 100% 100% 100%
RPV TO SG-2B VOLUaaRIC 008 REACTOR COOLANT 005 7 5 2 0 1 0 2 0 SURFACE PIPING, LOOP A SG-2A 0 40% 60¹ 100%
TO RCP-2A2 006 014 009 REACTOR COOLANT 0 'OLUiiRZC 2 1 0 0 1 0 0 0 SURFACE PIPING, LOOP A FROM Ot 1008 100%
RCP-2A2 TO RPV VOLUMETRIC 010 REACTOR COOLANT 006 7 2 2 0 0 0 0 0 SURFACE PIPING. LOOP B SG-2B 0 100% 100% 100%
TO RCP 2B1 VOLUMETRIC 011 RFACTOR COOLANT 005 2 1 1 0 0 0 0 0 SURFACE PIPZNG, LOOP B FROM 0 100% 100% 100%
RCP 2B1 TO RPV VOLUMETRIC 012 REACTOR COOLANT 006 7 2 1 0 0 0 1 0 SURFACE PIPING, LOOP A SG-2A 0 50¹ 50% 100%
TO RCP-2A1 VOLTAIC 013 REACTOR COOLANT 0 2 1 0 0 0 0 1 0 SURFACE PIPING, LOOP A FROM 0% 0% 100¹ RCP 2AI TO RPV VOLUMETRIC 014 REACTOR COOLANT 006 7 2 0 0 1 0 1 0 SURFACE PIPING, LOOP B SG 2B 0 0% 50¹ 100'¹ TO RCP-2B2
DATE: 07/24/93 ST. LUCZE NUCLEAR PLANT UNIT 2 PAGE: 16 REVISION: 0 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XZ SUhmARY TABLE A CATEGORY B-J PRESSURE RETAINING WELDS ZN PIPING
¹ OP COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDUIED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS B9. 11 CIRCUMFERENTIAL PIPE WELDS >>> VOLUMETRIC 015 REACTOR COOLANT 0 2 1 0 0 0 0 1 0 25% of all Circ 4 IN. NOMINAL PIPE SIZE SURPACE PZPING, LOOP B 0% 0% 100% butt welds, RCP-2B2 TO RPV Essentially 100t of the weld VOLUMETRIC 016 PRESSURIZER 0 9 7 1 0 6 0 0 0 SURFACE SURGE LINE 14% 100% 100%
VOLUMETRIC 021 LOOP 2A1 SAFETY 0 21 I 0 0 0 0 7 0 SURFACE INJECTION PIPING, 006 0% 0% 100%
ZNSIDE CTMT VOLUMETRIC 022 LOOP 2A2 SAPETY 0 19 4 0 0 3 0 1 0 SURFACE INJECTION PIPING, 006 Ot 75% 100't INSIDE CTMT VOLUiiRIC 023 LOOP 2B1 SAFETY 0 28 6 0 0 0 0 6 0 SURFACE INJECTION PIPING, 006 0% 0% 100%
INSIDE CIMT VOLUMETRIC 024 LOOP 2B2 SAFETY 0 19 3 3 0 0 0 0 0 SURFACE INJECTION PIPING, 006 100'C 100% 100't INSIDE CTMT VOLUMETRIC 025 COMBINED 0 13 4 4 0 0 0 0 0 SURFACE PRESSURIZER SPRAY 100% 100% 100%
LINE VOI UMETRIC 028 LOOP 2B SHUTDOWN 0 34 1 0 0 0 0 1 0 SURPACE COOLING LINE 006 0% 0% 100%
VOLUMETRIC 029 LOOP 2A SHUIDOWN 0 20 0 0 0 0 0 0 0 SURFACE COOLING LINE I ~ 1 I II V ~ 1***St) *%***It VOLUMETRIC 038 PRESSURIZER 0 12 6 0 0 0 0 6 0 SURFACE RELIEF LINE 0% 0% 100%
ITEM TOTAL 229 67 15 0 24 '0 28 0 22% 58% 100%
9.12 LONGITUDINAL PIPE WELDS )~ 4 VOLUMETR C 001 REACTOR PRESSURE 12 2 0 0' 0 0 0 Each Long weld IN. NOMINAL PIPE SIZE SURFACE VESSEL 0 0% 100% 100't intersecting circ, weld req'd by B-F & B-J
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 17 REVISION: 0 INSERVICE INSPECTION PLAN 'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XZ
~~SUMMARY~~
TABLE A CATEGORY B-J - PRESSURE RETAINING WELDS IN PIPING
¹ OF COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COK4ENTS B9w12 LONGITUDINAL PIPE WELDS >~ 4 VOLUMETRIC 006 REACTOR COOLANT 2 0 0 0 0 0 0 0 Each Long weld ZN. NOMINAL PIPE SIZE SURFACE PIPING, LOOP A FROM F 11'% i ~ 40 ~ 0% *14%11) intersecting RPV TO SG-2A circ. weld req'd by B-F & B-J VOLTAIC 007 REACTOR COOLANT 0 2 0 0 0 0 0 0 0 SURFACE PIPING, LOOP B FROM 114*11$ 4+IIPt) %*****8 RPV TO SG-2B VOLUMETRIC 008 REACTOR COOLANT 0 10 10 4 0 4 0 2 0 SURFACE PIPING, LOOP A SG-2A 014 40% 80% 100%
TO RCP-2A2 VOLUMETRIC 009 REACZOR COOLANT 006 2 2 0 0 2 0 0 0 SURFACE PIPING, LOOP A FROM 0% 100% 100%
RCP 2A2 TO RPV VOLUMETRIC 010 REACTOR COOLANT 0 10 2 2 0 0 0 0 0 SURFACE PIPING, LOOP B SG-2B 1008 100% 100%
TO RCP-2B1 VOL'PiKTRZC 011 REACTOR COOLANT 006 2 2 2 0 0 0 0 0 SURFACE PIPING, LOOP B FROM 0 1008 1008 100%
RCP-2B1 TO RPV VOLUMETRIC 012 REACTOR COOLANT 0 10 2 2 0 0 0 0 0 SURFACE PIPING, LOOP A SG-2A 100% 100% 100%
TO RCP-2A1 VOLUMETRIC 013 REACTOR COOLANT 0 2' 0 0 0 0 2 0 SURFACE PIPING, LOOP A FROM 0% 0% 100 8 RCP-2A1 TO RPV VOLlWiiRIC 014 REACTOR COOLANT 0 10 2 0 0 0 0 2 0 SURFACE PIPING, LOOP B SG-2B 0% 0% 100%
TO RCP 2B2 VOLUMETRIC 015 REACTOR COOLANT 0 2 2 0 0 0 0 2 0 SURFACE PIPING, LOOP B 0% Ot 100%
RCP-2B2 TO RPV
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 18 REVISION: 0 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECI'ZON XZ
~~SUMMARY~~
TABLE A CATEGORY B-J - PRESSURE RETAINING WELDS IN PIPING
¹ OP COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ZTEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER CORKNTS ITEM TOTAL 64 26 10 0 8 0 8 0 38% 69% 100%
B9.21 CIRCUMFERENTIAL PIPE WELDS ( 4 SURFACE 006 REACTOR COOLANT 0 2 0 0 0 0 0 0 0 25% of Cix'c. Butt IN. NOMINAL PIPE SIZE PIPING, LOOP A FROM ***IIIt 111 ~ ~ IS IIIIIIwelds, RPV TO SG 2A Essential)y 100%
of the weld SURFACE 026 LOOP 2B1 SPRAY 0 25 6 0 0 6 0 0 0 LINE 0% 100% 100%
SURFACE 027 LOOP 2B2 SPRAY 0 25 6 0 0 5 0 1 0 LINE 0% 83% 100%
SURFACE 028 LOOP 2B SHUTDOWN 0 13 3 3 0 0 0 0 0 COOLING LINE 100% 100't 100t SURFACE 029 LOOP 2A SHUTDONN 0 16 0 0 0 0 0 0 0 COOLING LINE *I~ I ~ I% IIIIII% 111111%
SURFACE 030 PRESSURIZER 0 7 6 2 0 0 0 4 0 AUXILIARYSPRAY 33% 33% 100%
SURFACE 031 CHARGING LINE TO 0 6 0 0 0 0 0 0 0 LOOP 281 I ~ 11 ~ 10 IIIIIIV I *I ***)
SURFACE 032 CHARGING LINE TO 0 9 3 0 0 3 0 0 0 LOOP 2A2 Ot 100% 100%
SURFACE 033 LOOP 2A1 PRIMARY 0 DRAIN 1 0 IIIIII'IIII' 0 0 0
~
0 IIIIII) 0 0 SURFACE 034 LOOP 2A2 PRIMARY 0 1 0 0 0 0 0 0 0 DRAIN ~ 111 ~ ~ Q *I~ ~ II4 IIIIII'URFACE 035 LOOP 2B1 PRIMARY 0 1 1 0 0 0 0 1 0 DRAIN 0% 0% 100k SURFACE 036 LOOP 2B2 PRZMARY 0 1 0 0 0 0 0 0 0 DRAIN IIII ~~$ ll I I'
~ ~ I ~ IIII' 0
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 19 REVISION: 0 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XZ SUYMARY TABLE A CATEGORY B-J - PRESSURE RETAINING WELDS IN PIPING ASME ¹ OF COMPONENTS SEC. XI ZONE RBL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COKKNTS B9.21 CIRCUMFERENTIAL PIPE WELDS ( 4 SURFACE 037 LETDOWN LINE 0 8 5 2 0 3 0 0 0 25% of Circ. Butt IN. NOMINAL PIPE SIZE PROM LOOP 2B1 40% 100% '00% welds, Essentially 100%
of the weld SURFACE 038 PRESSURIZER 0 8 2 0 0 0 0 2 0 RELZEF LINE 0% 0% 100%
ITEM TOTAL 123 32 7 0 17 0 8 0 21% 75% 1008 B9.31 BRANCH CONNECTION WELDS )~ 4 VOLUMETRIC 006 REACTOR COOLANT 1 0 0 0 0 0 0 0 25% of all Branch IN. NOMINAL PIPE SIZE SURFACE PIPING'OOP A FROM <<<<*<<<<1$ << ~ <<<<<<<<$ <<<<<<<<<<<<g Conn weids RPV TO SG-2A Essentially 100%
of the weld VOLUMETRIC 007 REACTOR COOLANT 0 2 1 0 0 0 0 1 0 SURFACE PIPING, LOOP B FROM 006 0% 0% 100%
RPV TO SG-2B VOLUMETRIC 009 REACZOR COOLANT 0 1 0 0 0 0 0 0 0 SURFACE PIPING, LOOP A PROM <<<< ~ <<<<<<8 <<<<<<<<<<<<) **<<<<1*$
RCP-2A2 TO RPV VOLUMETRIC 011 REACTOR COOLANT 0 1 0 0
<<<<<<<<<<<<)
0 0
<<<<<<<<<<<<8 0, 0
<<<<<< ~ <<<<)
0 SURFACE PIPING. LOOP B FROM RCP-2B1 TO RPV VOLUMETRIC 013 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 SURPACE PIPING, LOOP A PROM <<<<<< ~ << ~ 0 <<<<<<<<<<<<\ <<<< ~ <<<<<<)
RCP-2A1 TO RPV VOLUMETRIC 015 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 SURFACE PIPING, LOOP B <<<<<<<<<<<<$ <<<<<<<<**) *<< ~ <<<<<<%
RCP-2B2 TO RPV ITEM TOTAL 7 1 0 0 0 0 1 0 t 0% 0% 100%
89 ~ 32 BRANCH CONNECTION WELDS ( 4 SURFACE 006 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 25% of Branch IN. NOMINAL PIPE SZZE PIPING, LOOP A FROM <<<<<<<<<< ~ t <<<<<<<<<<<<t "***<<~ % Conn. welds>
RPV TO SG 2A Essentially 100%
of the weld
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 20 REVISION: 0 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XZ
~~SUMMARY~~
TABLE A CATEGORY B-J - PRESSURE RETAINING WELDS IN PIPING
¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION RE{} COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS B9. 32 BRANCH CONNECTION WELDS ( 4 SURPACE 008 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 258 of Branch IN. NOMINAL PIPE SI2E PIPING, IMP A SG-2A IIIIII( 111111$ Conn. welds ~
TO RCP-2A2 Essentially 100%
of the weld SURFACE 009 REACZOR COOLANT 0 1 0 0 0 0 0 0 0 PIPING, LOOP A FROM *~ IIII) 1*litt) I~
RCP-2A2 TO RPV IIII'URFACE 010 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 PIPING, LOOP B SG-2B ~ *~ ~ I ~ 8 IIIIII% I l*lI 1(
TO RCP-2B1 SURFACE 011 REACTOR COOLANT 0 2 2 0 0 2 0 0 0 PIPING, LOOP B FROM 100% 1008 RCP-2B1 TO RPV SURFACE 012 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 PIPING, LOOP A SG 2A *I~ *I~ Q ***II *8 TO RCP-2A1 IIIIII'URFACE 014 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 PIPING, LOOP B SG-2B llttt 0 ~ IIIIII% 11 ~ III%
TO RCP-2B2 SURFACE 015 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 PIPING, LOOP B ~ tt ~ tt% *111 ~ It 1*1 ~ ~ IV RCP 2B2 TO RPV VOLUMETRIC 028 LOOP 2B SHUTDOWN 006 3 2 2 0 0 0 0 0 SURFACE COOLING LINE 100% 100% 100%
SURFACE 029 LOOP 2A SHUTDOWN 0 3 0 0 0 0 0 0 0 COOLING LINE ~ ttttt% 11 ~ I ~ I% I ~ ~ ~ 11'0 ITEM TOTAL 15 4 2 0 2 0 0 0 50% 100% 1008 B9.40 SOCKET WELDS SURFACE 028 LOOP 2B SHUI'DOWN 0 12 3 0 0 0 0 3 0 25% of Socket COOLING LINE 0% 0% 100% welds, Essentially 100%
of the weld
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGB: 21 REVISION: 0 INSERVICE INSPECTION PLAN 'FOR THE SECOND INTERVAI CODE EDITION: 89 CLASS 1 SECTION XI
~~SUMMARY~~
TABLE A CATEGORY B-J - PRESSURE RETAINING WBLDS IN PIPING ASME ¹ OF COMPONENTS SEC. XZ BONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS B9.40 SOCKET WBLDS SURFACE 029 LOOP 2A SHUTDONN 0,10 0 0 0 0 0 0 0 25% of Socket COOLING LINE PPPPPP% PPPPPP% ~ PPPPP% welds, Essentially 100%
of the weld SURFACE 030 PRESSURIZER 0 23 21 6 0 4 0 11 0 AUXILIARY SPRAY 28% 47'0 100%
SURFACE '31 CHARGING LINE TO 0 19 7 0 0 I 0 0 0 LOOP 281 0% 100% 100%
SURFACE 032 CHARGING LINE TO 0 42 8 2 0 3 0 3 0 LOOP 2A2 25% 628 100t SURFACE 033 LOOP 2A1 PRIMARY 0 5 0 0 0 0 0 0 0 DRAIN ~ 11* ~ P8 11 ~ 1 ~ 18 PPP11 ~ 8 SURFACE 034 LOOP 2A2 PRIMARY 0 5 0 0 0 0 0 0 0 DRAIN 11 ~ 1 ~ P% PPPPPP8 PPPPPP%
SURFACE 035 LOOP 281 PRIMARY 0 5 3 0 0 3 0 0 0 DRAIN 0%'00% 100%
SURFACE 036 LOOP 2B2 PRIMARY 0 5 0 0 0 0 0 0 0 DRAIN * ~ ~ ***8 **1*1*$ *~ PPPP8 SURFACE 037 LETDONN LINE 0 31 30 17 0 6 0 7 0 FROM LOOP 2B1 56\ 76% 100%
ITEM TOTAL 157 72 25 0 23 0 24 0 34% 66% 100%
CATEGORY TOTAL 595 202 59 0 74 0 69 0 29% 65%'00%'
DATE: 07/24/93 ST. IUCIE NUCLEAR PLANT UNIT 2 PAGE: 22 REVISION: 0 INSERVICE ZNSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XZ SI04ARY CATEGORY B-K INTFGRAL ATTACHMENTS FOR PIPING PUMPS AND VALVES 5 OF COMPONENTS SEC. XI ZONE REL 5 OP NO. SCHEDULED/COMPLETED ITEM 8 ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COiiENTS B10. 10 PIPING-INTEGRALLY WELDED SURPACE 023 LOOP 2B1 SAFETY 0 2 2 0 0 0 0 2 0 25% of pipe ATTACHMENTS INJECTION PIPING, 0% 0% 100'0 intergral INSIDE CIIfT attachments req'd under B-J SURFACE 024 LOOP 2B2 SAFETY 0 0 0 0 0 INJECTION PIPING, 100% 100't INSIDE CTMT 100'URFACE 028 LOOP 2B SHUTDOWN 0 2 2 1 0 1 0 0 0 COOLING LINE 50% 100'C 100%
ITEM TOTAL 8 8 5 0 1 0 2 0 62% 75%
100'0.
20 PUMPS-INTEGRALLY WELDED SURFACE 017 REACTOR COOLANT 0 0 0 0 0 0 Limited pump ATTACHMENTS PUMP 2A1 100% 100% 100t integral attach required by B-L-2.
SURFACE 018 REACZOR COOLANT 0 4 4 0 0 4 0 0 0 PUMP 2A2 0% 100% 100%
SURFACE 019 REACTOR COOLANT 0 4 4 0 0 4 0 0 0 PUMP 2B1 0% 200% 100%
SURFACE 020 REACTOR COOLANT 0 4 4 0 0 0 0 4 0 PUMP 2B2 0% 08 100%
ITEM TOTAL 16 16 4 0 8 0 4 0 25% 75% 100%
CATEGORY TOTAL 24 24 9 0 9 0 6 0 37\ 75% 100%
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 23 REVISION: 0 INSERVZCE INSPECTION PLAN 'FOR THE SECOND ZNTERVAL CODE EDITION: 89 CLASS 1 SECTION XI SUI4ARY TABLE A CATEGORY B-L 1 - PRESSURE RETAINING WELDS IN PUMP CASING
¹ OF COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COKKNTS B12.10 PUMPS-PUMP CASING WELDS VISUAL 017 REACTOR COOLANT 0 2 0 0 0 0 0 0 0 Essentially 100t PUMP 2A1 1 ~ 0 1 lk It ~% I1 k t t ~ II1*%It of weld length, Limited to One VISUAL 018 REACTOR COOLANT 0 2 0 0 0 0 0 0 0 PUMP 2A2 Oi1011t OiO ~ 0 ~ t **%litt VISUAL 019 REACTOR COOLANT 0 2 0 0 0 0 0 0 0 PUMP 2B1 ~~ I~ I~ t II I It
~ ~ ~~ 0004t VISUAL 020 REACTOR COOLANT 0 2 2 0 0 0 0 2 0 PUMP 2B2 Ot Ot 100t ITEM TOTAL 8 2 0 0 0 0 2 0 Ot Ot 100t'ATEGORY TOTAL 8 2 0 0 0 0 2 0 Ot 100't
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 24 REVISION: 0 INSERVICE INSPECTION PLAN 'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECI'ION XZ SUiiRY TABLE A CATEGORY B-L PUMP CASINGS ASME ¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER CO'aaTS B12.20 PUMPS-PUMP CASINGS VISUAL 017 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 Limited to One PUMP 2A1 **it~ I% 1 ~ 1110% "+~ ~ ~% Pump, when disassembled for maintenance.
VISUAL 018 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 PUMP 2A2 ~ I ~ ~ I~ t ~ I ~ 111% I 1 1 1 1 1$
VISUAL 019 REACTOR COOLANT 1 0 0 0 0 0 0 0 PUMP 2B1 I ~ o1 ~ p% *I~ II~ 0 ****I13 VISUAL 020 REACTOR COOLANT 1 1 0 0 0 0 1 0 PUMP 2B2 0% 0% 100%
ITEM TOTAL 4 1 0 0 0 0 1 0 Ot Ot 100%
CATEGORY TOTAL 4 1 0 0 0 0 1 0" 0% 0% 100%
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 25 REVISION: 0 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XI SUKQRY TABLE A CATEGORY B-M VALVE BODIES
¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRZPTION EXAM METHOD~SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS 0Limited1vlv. in B12. 50 VALVES-VALVE BODIES EXCEEDING 4 INCHES NOMINAL PIPE SZEE VISUAL 021 LOOP 2A1 SAFETY INJECTION PIPING, 3 0 IIIIII'lI 0 0 0
~ ~ 1%
0 0 IIIIII' group of vlv.,
INSIDE CTMT when dissem. for maint.
VISUAL 022 LOOP 2A2 SAFETY 3 0 0 0 0 0 0 0 INJECTION 1111 ~ IQ PIPING'NSIDE CIMT IIIIII'IIIII'ISUAL 023 LOOP 2B1 SAFETY 3 0 0 0 0 0 0 0 INJECTION PIPING, IIIIII'IIIIIV**1*11%
INSIDE CIMT VISUAL 024 LOOP 2B2 SAPETY 3 0 0 0 0 0 0 INJECTION PIPING, ~ 1$ IIIIII'111 IIIIII)
INSIDE CIMT VISUAL 028 LOOP 2B SHUTDOWN 3 0 0 0 0 0 0 0 COOLING LINE 111111% IIIIIIV IIIIIIV VISUAL 029 LOOP 2A SHUTDOWN 007 2 0 0 0 0 0 0 0 COOLING LINE 11 ~ III% **IIIIV llllllg ITEM TOTAL 17 0 0 0 0 0 0 0 III I II) II ***I e IIIIII%
CATEGORY TOTAL 17 0 0 I~ ~ III'*I 0 '
~ ~
0 Ie 0
I ~ IIII' 0
DATEl 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 26 REVISION: 0 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XI
~~SUMMARY~~
TABLE A CATEGORY B-N INTERIOR OF REACTOR VESSEL ASME ¹ OF COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS B13.10 REACTOR VESSEL-VESSEL INTERIOR VISUAL 001 REACTOR PRESSURE 0 10 26 8 0 10 0 8 0 Once every VESSEL 30% 69% 100% inspection period CATEGORY TOTAL 10 26 8 0 10 0 8 0 30% 69% 100%
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 27 REVISION: 0 INSERVZCE INSPECTION PLAN'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECI'ZON XI
~~SUMMARY~~
TABLE A CATEGORY B-N INTEGRALLY WELDED CORE SUPPORT STRUCTURES AND INTERIOR ATTACHMENTS TO REACTOR VESSEL ASME ¹ OP COMPONENTS SEC. XI ZONE REL ¹ OP NO. SCHEDUIED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS B13. 50 REACTOR VESSEL (PWR) -INTERIOR VISUAL 001 REACTOR PRESSURE 0 6 6 0 0 6 0 0 0 Accessible welds, ATTACHMENTS WITHIN BELTLINE VESSEL 0% 100% 100% Performed in REGION con)unction with Exam Cat B-A.
B13.60 REACIOR VESSEL (PWR)-INTERIOR VISUAL 001 REACTOR PRESSURE 0 14 14 0 0 14 0 0 0 Asscesible welds, ATTACHMENTS BEYOND BELTLINE VESSEL 0% 100% 100'C Performed in REGION con)unction with Exam Cat B-A CATEGORY TOTAL 20 20 0 0 20 0 0 0 0% 100% 100t
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 28 REVISION: 0 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XI SUhmARY TABLE A CATEGORY B-N REMOVABLE CORE SUPPORT STRUCTURES
¹ OF COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS B13. 70 REACTOR VESSEL (PHR) -CORE VISUAL 001 REACTOR PRESSURE 0 6 6 0 0 6 0 0 0 100i'ccessible SUPPORT STRUCTURE VESSEL 0% 100% surfaces.
Performed in con). with Exam CATEGORY TOTAL 6 6 0 0 6 0 0 0 O'C 100% 100%
SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24,. 1993 APPENDIX B CLASS 2
~~SUMMARY~~
TABLES Page 92 of 272
DATE: 07/24/93 ST. LUCZE NUCLEAR PLANT UNIT 2 PAGE: 29 REVISZON: 0 INSERVICE ZNSPECTZON PLAN 'FOR THE SECOND INTERVAL CODE EDITION 89 CLASS 2 SECTION XZ
~~SUMMARY~~
TABLE B CATEGORY C-A - PRESSURE RETAINING WELDS IN PRESSURE VESSELS
¹ OF COMPONENTS SEC. XI ZONE REL ¹ OF NO ~ SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS C1. 10 SHELL CIRCUMFERENTIAL WELDS VOLUMETRIC 041 STEAM GENERATOR 5 4 0 0 0 0 4 0 Gross structural 2A SECONDARY SIDE 0% 0% 100 t discontinuity welds, Limited to One vessel.
VOLUiiRIC 042 STEAM GENERATOR 0 5 0 0 0 0 0 0 0 2B SECONDARY SIDE 1*1 1 %*( ****~ *8 **1141't VOLUMETRIC 055 SHUTDOWN COOLING 008 1 1 0 0 0 0 1 0 HEAT EXCHANGER 2A 0% 0% 100%
VOLUMETRIC 056 SHUTDOWN COOLING 0 1 0 0 0 0 0 0 0 HEAT EXCHANGER 2B *1*1I11$ ~ 'kl144$ %kI%'Al)
ITEM TOTAL 12 5 0 0 0 0 5 0 O'C 0% 100%
Cl. 20 HEAD CIRCUMFERENTIAL WELDS VOLUiiRIC 041 STEAM GENERATOR 1 1 0 0 0 0 1 0 Head-to-shell 2A SECONDARY SIDE 0% 0% 100% weld, Limited to One vessel among vessels, VOLUMETRZC 042 STEAM GENERATOR 0 1 0 0 0 0 0 0 0 2B SECONDARY SIDE **1***) 1esee*f ~~p~1~Q 2 1 0 0 0 0 1 0 0% 0% 100'C C1.30 TUBESHEET-TO-SHELL WELDS VOLUMETRIC 041 STEAM GENERATOR 2 2 0 0 0 0 2 0 2A SECONDARY SIDE 0 0% 0% 100%
VOLUMETRIC 042 STEAM GENERATOR 0 2 0 0 0 0 0 0 0 2B SECONDARY SIDE *l11f*t **@Alt) II1lt1$
VOLUMETRIC 055 SHU1'DOWN COOLING 008 1 1 0 0 0 0 1 0 HEAT EXCHANGER 2A 0% 100'
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 30 REVISION: 0 INSERVZCE INSPECTION PLAN FOR THE SECOND ZNTERVAL CODE EDITION: p 89 CLASS 2 SECTION XZ
~~SUMMARY~~
TABLE B CATEGORY C-A - PRESSURE RETAINING WELDS IN PRESSURE VESSELS
¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COmIBNTS Cl. 30 TUBESHEET-TO-SHELL WELDS VOLUMETRIC 056 SHUTDOWN COOLING 0 1 0 0 0 0 0 0 0 HEAT EXCHANGER 2B ~~ 1i1*$ *Ill*I) I ~0~0 I\
6 3 0 0 0 0 3 0 0% 0% 100%
CATEGORY TOTAL 20 9 0 0 0 0 9 0 0% 0¹ 100'
DATE: 07/24/93 ST. LUCZE NUCLEAR PLANT UNIT 2 PAGE: 31 REVISION: 0 INSERVICE INSPECI'ZON PLAN 'FOR THE SECOND ZNTERVAL CODE EDITION: 89 CLASS 2 SECTION XI
~~SUMMARY~~
TABLE B CATEGORY C-B - PRESSURE RETAINING NOZZLE WRLDS IN VESSELS ASME ¹ OF COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COI(ENTS C2. 21 NOZZLE-TO-SHELL (OR HEAD) WELD VOLUiiRIC 041 STEAM GENERATOR 009 2 2 0 0 0 0 2 0 Nozzles at 1/2 IN. NOMINAL THZCKNESS SURFACE 2A SECONDARY SIDE 0% 0% 100\ terminal ends of
~ WITHOUT REINFORCING PLATE pipe run, Limited One vessel under VOLUMETRIC 042 STEAM GENERATOR 0 2 0 0 0 0 0 0 '
SURPACE 2B SECONDARY SIDE t0 ~ 4 ~ 1% I ~ ~ P ~ 1% I ~ 0 ~ ~ 4%
ITEM TOTAL 4 2 0 0 0 0 2 0 0% 0% 1008 C2.22 NOZZLE INSIDE RADIUS SECTION > VOLUMETRIC 041 STEAM GENERATOR 0 2 2 0 0 0 0 2 0 Nozzles at 1/2 IN. NOMINAL THICKNESS 2A SECONDARY SIDE 014 0\ 08 100% terminal ends of WITHOUT REINFORCING PLATE pipe run. Limited One vessel under VOLUMETRIC 042 STEAM GENERATOR 0 , 2 0 0 0 0 0 0 0 2B SECONDARY SIDE ~ ~ 1011% ~ I0 ~ 11% 11 ~ 00*%
ITEM TOTAL 4 2 0 0 0 0 2 0 0% 0% 100%
C2.31 REINFORCING PLATE WELDS TO SURFACE 055 SHUTDOWN COOLING 4 4 0 0 0 0 4 0 Nozzles at NOZZLE AND VESSEL > 1/2 IN. HEAT EXCHANGER 2A 0% 0% 100% terminal ends of NOMINAL THICKNESS pipe run. Limited One Vessel under SURFACE 056 SHUTDOWN COOLING 0 4 0 0 0 0 0 0 0 HEAT EXCHANGER 2B ~ It1ll) ~ *1*~ ~ $ *%**ltt 8 4 0 0 0 0 4 0 0% 0% 100%
C2. 33 NOZZLE-TO-SHELL (OR HEAD) VISUAL 055 SHUTDOWN COOLING 2 2 0 0 0 0 2 0 Nozzles at WELDS WHEN INSZDE OF WELD ZS HEAT EXCHANGER 2A 08 100% terminal ends of INACCESSIBLE > 1/2 ZN. NOMINAL pipe run. Limited THZCKNESS One Vessel under
DATE: 07/24/93 ST. LUCIB NUCLEAR PLANT UNIT 2 PAGE: 32 REVISION: 0 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 2 SECTION XI
~~SUMMARY~~
TABLE B CATEGORY C-B - PRESSURE RETAINING NOZZLE WELDS IN VESSELS
¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OP NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS C2.33 NOZZLE-TO-SHELL (OR HEAD) VISUAL 056 SHUTDOWN COOLING 0 2 0 0 0 0 0 0 0 Nozzles at WBLDS WHEN INSIDB OF WELD IS HEAT EXCHANGER 2B *Itk*~ 't 1 1*401( ~ ++~~+t terminal ends of INACCESSIBLE > 1/2 IN. NOMINAL pipe run. Limited THICKNESS One Vessel under 4 2 0 0 0 0 2 0 0% 0% 100%
CATEGORY TOTAL 20 10 0 0 0 0 10 0 0% 0% 100%
DATE: 07/24/93 ST. LUCIB NUCLEAR PLANT UNIT 2 PAGE: 33 REVISION: 0 INSERVZCE INSPECTION PLAN 'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 2 SECTION XI
~~SUMMARY~~
TABLE B CATEGORY C C - INTEGRAL ATTACHMENTS FOR VESSELS PIPING PUMPS AND VAIVES ASME ¹ OF COMPONENTS SEC. XZ BONE REL ¹ OF NO~ SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PBR COMMENTS C3.10 PRBSSURE VESSELS-INTEGRALLY SURFACE 041 STEAM GENERATOR 014 8 8 0 0 0 0 8 0 Limit to 1 vessel WELDED ATTACHMENTS 2A SECONDARY SIDE 0 0\ 100% in case of multiple vessels of similar SURFACE 042 STEAM GENERATOR 0 8 0 0 0 0 0 0 0 2B SECONDARY SIDE ***41%) tt14ll) lf1111)
ITEM TOTAL 16 8 0 0 0 0 8 0 0% O'C 100 8 C3.20 PIPING-INTEGRALLY WELDED SURFACE 045 SAFETY INJECTZON 0 1 1 1 0 0 0 0 0 Limited to ATTAC784BNTS PIPING TO SZ TANK 100% 100% 100% attachments of components e SURFACE 046 SAPETY INJECTION 0 PIPING TO SI TANK 4 0 0 0
II***) *II**I) 0 0 0 0 t11*'I'll) required under 2A1 SURFACE 061 HPSI PUMP 2A TO 0 2 1 1 0 0 0 0 0 HEADER A 100% 100% 100%
SURPACE 063 MAIN STEAM LINE 0 3 1 0 0 0 0 0 2A1 INSIDE 0% 100% 100%
CONTAINMBNT SURFACE 064 MAIN STEAM LINE 0 2 0 0 0 0 0 0 0 2B1 INSIDE 0~ ***1) %0 ~ l% ~ $ 1* ~ I'Ii)
CONTAIhMENT SURFACE 065 MAIN STEAM LINE 0 1 1 0 0 1 0 0 0 2A1 OUTSIDE 0% 100% 100%
CONTAINMENT SURFACE 066 MAIN STEAM LINE 0 1 0 0 0 0 0 0 0 2B1 OUTSIDE 1**441% *4Al**% **1~ **0 CONTAINMENT
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 34 REVISZON: 0 INSBRVICE INSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 2 SECTION XZ
~~SUMMARY~~
TABLE B CATEGORY C C - INTEGRAL ATTACHMENTS FOR VESSELS PIPING PUMPS AND VALVES
¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS C3. 20 PIPING-INTEGRALLY WELDED SURFACE 067 MAIN FEEDWATER 0 1 1 0 0 0 0 1 0 Limited to TO SG 2A1 INSIDE Ot Ot 100t attachments of CONTAINMENT components required under SURFACE 068 MAIN FEEDWATER 0 2 1 0 0 0 0 1 0 TO SG 2B1 INSIDE Ot Ot 100t CONTAINMENT SURFACE 087 COMBINED HPSI 0 3 1 1 0 0 0 0 0 DISCHARGE 100t 100t 100t' SURFACE 093 HPSZ 2A 1 0 0 0 0 0 0 0 DISCHARGE TO SDC 1 1111*t llll**t 11*lilt LOOP 2A SURFACE 094 HPSI HEADER B TO 0 1 0 0 0 0 0 0 0 SDC LOOP 2B *ll*llt Ill*lit **11**t ITEM TOTAL 22 7 3 0 2 0 2 0 42t 71'00t C3. 30 PUMPS INTEGRALLY WELDED VZSUAL 097 CONTAINMENT 0 3 3 0 0 0 0 3 0 Limited to ATTACHMENTS SPRAY PUMP 2A 0't Ot 100't attachments of components required under VISUAL 097 CONTAINMENT 0 3 0 0 0 0 0 0 0 SPRAY PUMP 2B 11 ~ 11*t 1**1**t **11~ lt ITEM TOTAL 6 3 0 0 0 0 3 0 Ot Ot 100 t CATEGORY TOTAL 44 18 3 0 2 0 13 0 16t 27t 100t
DATE: 07/24/93 ST. LUCZB NUCLEAR PLANT UNIT 2 PAGE: 35 REVISION: 0 INSERVZCE INSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 2 SECTION XZ SUiiRY TABLE B CATEGORY C F 1 PRESSURE RETAINING WBLDS IN AUSTENZTZC STAINIiESS STEEL OR HIGH ALLOY PIPING
¹ OF COMPONENTS SEC. XI ZONE RBL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS C5.11 CIRCUMFERENTIAL PIPE WBLDS > VOLUMETRIC 043 I PSZ PUMP 2A 0 68 10 3 0 4 0 3 0 7.5t of non OR ~ to 3/8 IN. NOM. WALL SURFACE DISCHARGE HEADER 30t 70t 100t exempt welds,
. THICKNESS FOR PIPING > NPS 4 PIPING 7.5t based on exempt a VOLUiiRIC 044 LPSZ PUMP 2B 0 78 10 3 0 3 0 4 0 SURFACE DISCHARGE HEADER 30t 60t 100't PIPING VOLUiiRIC 045 SAPETY INJECTION 0 14 1 1 0 0 0 0 0 SURFACE PIPING TO SI TANK 100t 100t 100t VOLUMETRIC 046 SAFETY INJECTION 0 15 2 0 0 2 0 0 0 SURFACE PIPING TO SI TANK Ot 100t 100't 2A1 VOLUMETRIC 047 SAFETY INJECTION 0 2 1 0 0 0 0 1 0 SURFACE PIPING TO SI TANK Ot Ot 100t 2B1 VOLUMETRIC 048 SAFETY INJECTION 0 16 1 0 0 1 0 0 0 SURFACE PIPING TO SZ TANK Ot 100'00t 2B2 VOLUMETRIC 051 SHUTDOWN COOLING 0 2 0 0 0 0 0 0 0 SURFACE LINE A INSIDE ***1~ *t ***t**t ii*ae**)
CONTAIhMENT VOLUMETR1C 052 SHUTDOWN COOLING 0 2 0 0 0 0 0 0 0 SURFACE LINE B INSIDE 4*IIiiIt 11***at Aklkllt CONTAINMENT VOLUMETRIC 061 HPSI PUMP 2A TO 0 14 2 0 0 0 0 2 0 SURFACE HEADER A Ot 0't 100t VOLUMETRIC 062 HPSZ PUMP 2B TO 0 10 2 1 0 1 0 0 0 SURFACE 50t 100t 100t ITEM TOTAL 221 29 8 0 11 0 10 0 27t 65t 100t C5,21 CIRCPi4FERENTIAL PIPING WBLDS > VOLUMETRIC 061 HPSI PUMP 2A TO 0 20 3 0 0 0 0 3 0 7.5t of non 1/5 IN. NOM. THICKNESS FOR SURFACE HEADER A Ot Ot 100t exempt welds, PIPING > OR ~ TO NPS 2 AND c 7.5t based on OR & TONPS 4 total exempt &
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 36 REVISION: 0 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 2 SECTZON XZ
~~SUMMARY~~
TABLE B CATEGORY C-F PRESSURE RETAINING MFLDS IN AUSTENITIC STAINLESS STEEL OR HIGH ALLOY PIPING or e NPS 4
¹ OF COMPONENTS SEC. XI ZONE REL ¹ OP NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION RE{} COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS C5. 21 CIRCUMFERENTIAL PIPING HELDS > VOLUMETRIC 062 HPSI PUMP 2B TO 0 10 3 0 0 3 0 0 0 7.5t of non 1/5 IN. NOM. THZCKNESS FOR SURFACE HEADER B 0% 100% 100% exempt welds, PZPING > OR ~ TO NPS 2 AND ( 7.5% based on OR ~ TONPS 4 total exempt 6 VOLUMETRIC 087 COMBINED HPSI 0 83 14 14 0 0 0 0 0 SURFACE DISCHARGE 100\ 100'C 100%
VOLUMETRIC 088 CHARGING PUMP 2A 0 6 0 0 0 0 0 0 0 SURFACE DISCHARGE TO AUX. **II**$ ***%*if **It%*4 .
HPSI VOLUMETRIC 093 HPSI 2A 0 45 5 0 0 0 0 5 0 SURFACE DISCHARGE TO SDC 0% Ot 100%
LOOP 2A VOLUMETRIC 094 HPSZ HEADER B TO 0 65 10 0 0 0 0 10 0 SURFACE SDC IMP 2B 0% 0% 100%
VOLUMETRIC 095 HPSZ 2A 0 24 4 0 0 0 0 4 0 SURFACE DISCHARGE TO SDC 0% O'C 100%
LOOP 2B VOLUiiRZC 096 HPSI 2B 2 0 0 0 0 0 0 0 SURPACE DISCHARGE TO SDC 1I1N ~ *0 *01%1 ~ 0 141440$
LOOP 2B ITEM TOTAL 255 39 14 0 3 0 22 0 35% 43%
100%'5.30 SOCKET HELDS SURFACE 087 COMBINED HPSZ 0 82 8 8 0 0 0 0 0 7.5% of non DISCHARGE 100% 100% 100% exempt welds, 7.5% based on exempr. 6 SURFACE 088 CHARGING PUMP 2A 0 46 4 1 0 3 0 0 0 ~
DISCHARGE TO AUX. 25% 100% 100't HPSI
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGB: 37 REVISION: 0 INSERVZCE INSPEC1'ZON PLAN 'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 2 SECTION XZ
~~SUMMARY~~
TABLE B CATFGORY C-F PRESSURE RETAINING WELDS IN AUSTENITIC STAINLESS STEEL OR HIG'H ALLOY PIPING
¹ OP COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS C5.30 SOCKET WELDS SURFACE 089 CHARGING PUMP 2B 0 17 4 0 0 4. 0 0 0 7.5% of non DISCHARGE TO AUX. 0% 100% 100% exempt welds, HPSZ 7.5% based on exempt 6 SURFACE 090 CHARGING PUMP 2C 0 28 4 0 0 4 0 0' DISCHARGE TO AUX. O'C 100% 100%
HPSI SURFACE 091 COMBINED 0 21 4 0 0 4 0 0 0 CHARGING PIMP 08 100% 100%
DISCHARGE TO HPSZ SURFACE 092 COMBINED 0 15 2 0 0 2 0 0 0 DISCHARGE TO HPSI 0% 100% 100%
TZE IN LOOP 2B SURFACE 096 HPSZ 2B 0 18 4 0 0 0 0 4 0 DISCHARGE TO SDC 0% 0% 1008 LOOP 2B ITEM TOTAL 227 30 9 0 17 0 4 0 308 86% 100%
C5.41 PIPE BRANCH CONNECTIONS OF SURFACE 061 HPSI PIMP 2A TO 0 5 2 0 0 0 0 2 0 7.5% of non BRANCH PZPZNG (CIRCIMFERENTAIL HEADER A 08 0% 100% exempt welds, WELDS) ) OR t TO NPS 2 7.5% based on exempt & non SURFACE 062 HPSZ PUMP 2B TO 0 3 0 0 0 0 0 0 0 HEADER B tttttt8 ttttt ~8 ttttlt)
SURFACE 088 CHARGING PUMP 2A 0 3 1 0 0 1 0 0 0 DISCHARGE TO AUX. 0% 1001 100%
HPSZ SURFACE 089 CHARGING PUMP 2B 0 1 0 0 0 0 0 0 0 DISCHARGE TO AUX. *tt tt%
~ tttttt% tttttt%
HPSI
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 38 REVISZON: 0 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 2 SECTION XZ SUYMARY TABLE B CATEGORY C-F PRESSURE RETAINING WELDS IN AUSTENITIC STAINLESS STEEL OR HIGH ALLOY PIPING
¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COUNTS C5.41 PIPE BRANCH CONNECTIONS OF SURFACE 090 CHARGING PUMP 2C 0 2 1 0 0 1 0 0 0 7.5% of non BRANCH PIPING (CIRCUMFERENTAIL DISCHARGE TO AUX. 0% 100% 100% exempt welds, WELDS) > OR ~ TO NPS 2 HPSZ 7.5% based on exempt & non SURFACE 094 HPSZ HEADER B TO 0 1 0 0 0 0 0 0 0 SDC LOOP 2B 1**1*13 1****18 *'1 1**1$
ITEM TOTAL 15 4 0 0 2 0 2 0 08 50% 100%
CATEGORY TOTAL 718 102 31 0 33 0 38 0 30% 62% 100%
DATB: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 39 REVISION: 0 INSERVICE INSPECTION PLAN 'FOR THB SECOND INTERVAL CODE BDZTZON: 89 CLASS 2 SECTION XZ SUYBARY TABLE B CATEGORY C-F PRESSURE RETAINING WELDS IN CARBON OR LOW ALLOY STEEL PIPING ASMB ¹ OF COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS C5.51 CIRCUMPBRENTIAL PIPING WELDS > VOLUMETRIC 063 MAIN STEAM LINE 0 15 3 2 0 0 0 1 0 7.5% of non OR ~ TO 3/8 IN. NOM. WALL SURFACE 2A1 INSIDE 66% 66't 100% exempt welds, THICKNESS FOR PIPING > NPS 4 CONTAIhMENT 7.5% based on exempt & non VOLUMETRIC 064 MAIN STEAM LINE 0 17 5 0 0 2 0 3 0 SURFACE 2B1 INSIDE 0\'0% 100%
CONTAINMENT VOLUMETRIC 065 MAIN STEAM LINE 0 30 7 4 0 3 0 0 0 SURFACE 2A1 OUTSIDE 571'00% 100%
CONTAINMENT VOLUMETRIC 066 MAIN STEAM LINE 0 30 11 0 0 0 0 11 0 SURFACE 2B1 OUTSIDE 0% 0't 100%
CONTAINMENT VOLUMETRIC 067 MAIN FEEDWATER 0 12 4 0 0 4 0 0 0 SURFACE TO SG 2A1 INSIDE 09 '00% 100%
CONTAIhMENT 068 MAIN FEEDWATER 0 14 2 0 0 0 2 0 VOLUMETRIC SURFACE 'O SG 2B1 INSIDE 4
50% 50% 100%
CONTAINMENT VOLUMETRIC 071 MAIN FEEDWATER 0 5 4 2 0 2 0 0 0 SURFACE TO SG 2A1 OUTSIDE 50% 100% , 100%
VOLUMETRIC 072 MAIN FEEDWATER 0 5 4 0 0 0 0 4 0 SURFACE TO SG 2Bl OUTSIDE 0% 0%
CONTAINMENT 100%'TEM TOTAL 128 42 10 0 11 0 21 0 239 50% 100%
C5.52 LONGITUDINAL PZPING WELDS > OR VOLUMETRIC 063 MAIN STEAM LINE 0 17 3 2 0 0 0 1 0 2 't 100% INTERSECTING AT THE
~ TO 3/8 ZN. NOM. WALL SURFACE 2A1 ZNSZDE 66% 66%
THICKNESS FOR PIPING > NPS 4 CONTAINMENT CIRCUMFERENTIAL WELD.
DATE: 07/24/93 ST. LUCIE NUCI EAR PLANT UNIT 2 PAGE: 40 REVISION: 0 INSERVZCE INSPECTION PLAN'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 2 SECZ'ION XI
~~SUMMARY~~
TABLE B CATEGORY C-F PRESSURE RETAINING WELDS IN CARBON OR LOW ALLOY STEEL PIPING ASME 8 OF COMPONENTS SEC. XZ ZONE REL 5 OF NO. SCHEDULED/COMPLETED ITEM 5 ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTZON REQ COMP REQ 1ST PER 2ND PER 3RD PER COPÃEHTS C5.52 LONGITUDINAL PIPING WELDS > OR VOLUMETRIC 064 MAIN STEAM LINE 0 19 9 0 0 5 0 4 0 2.5t AT THE
~ TO 3/8 ZN. NOM. WALL SURFACE 2B1 INSIDE Ot 55t 100t INTERSECTING THICKNESS FOR PIPING > NPS 4 CONTAINMENT CIRCUMFERENTIAL VOLUMETRIC 065 MAIN STEAM LINE 0 3 3 3 0 0 0 0 0 SURPACE 2A1 OUTSIDE 010 100t 100t 100t CONTAINMENT VOLUiiRIC 066 MAIN STEAM LINE 0 3 3 0 0 0 0 3 0 SURFACE 2B1 OUTSIDE 010 0't Ot 100t CONTAINMENT ITEM TOTAL 42 18 5 0 5 0 8 0 27t 55t 100t CS. 81 CIRCUMFERENTIAL BRANCH VOLUMETRIC 065 MAIN STEAM LINE 0 10 3 2 0 1 0 0 0 7.5t of non CONNECTION WELDS OF BRANCH SURFACE 2A1 OUTSIDE 66t 100t 100t exempt welds, PIPING > OR ~ to NPS 2 CONTAINMENT 7.5t based on exempt a non VOLUiiRIC 066 MAIN STEAM LINE 0 10 3 0 0 0 0 3 0 SURFACE 2Bl OUTSIDE Ot Ot 100t CONTAIhMENT ITEM TOTAL 20 6 2 0 1 0 3 0 33t 50t 100t CATEGORY TOTAL 190 66 17 0 17 0 32' 25t 5lt 100t
SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 APPENDIX C CLASS 3 8JSIMARY TABLES Page 93 of 272
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 41 REVISION: 0 INSERVZCE INSPECTION PLAN'FOR THE SECOND INTBRVAI CODE EDITION: 89 CLASS 3 SECTION XI SUiiRY TABLE C CATEGORY D-A - SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCI'ION
¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP RBQ 1ST PER 2ND PER 3RD PER COMMENTS Dl. 20 INTEGRAL ATTACHMBNT- VISUAL 102 COMPONENT 3 3 0 0 '
0 3 0 MULTIPLE STREAMS COMPONENT SUPPORTS AND COOLING - SHUTDOWN Ot Ot 100t MAY APPLY.
RESTRAINTS COOLING HX 2A INLET VISUAL 103 COMPONENT 0 2 2 0 0 0 0 2 0 COOLING - SHUTDOWN Ot Ot 100t COOLING HX 2B INLET VISUAL 105 COMPONENT 0 4 4 1 0 3 0 0 0 COOLING-SHUTDOWN 25t 100t 100't COOLING HX 2A DISCHARGE VISUAL 106 COMPONENT 0 3 3 1 0 1 0 1 0 COOLING - SHUTDOWN 33t 66t 100t COOLING HX 2B e VISUAL DISCHARGE 180 LETDOWN HEAT EXCJ JANG ER 0 2 2 2 0 100t 0
100t 0 0 100t 0
ITEM TOTAL 14 14 4 0 4 0 6 0 28t 57t 100t Dl. 40 ZNTEGRAL ATTACHMENT - SPRING VISUAL 105 COMPONENT 0 1 1 1 0 0 0 0 0 MULTIPLE STREAMS TYPE SUPPORTS COOLING-SJRJTDOWN 100t 100t 100t MAY APPLY.
COOLING HX 2A DISCHARGE CATEGORY TOTAL 15 15 5 0 4 , 0 6 0 33t 60t 100t
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 42 REVISION: 0 INSERVZCE INSPECTION PLAN'FOR THE SECOND iNTERVAL CODE EDZTZON: 89 CLASS 3 SECTION XI SUYiiRY TABLE C CATEGORY D-B - SYSTEMS IN SUPPORT OF EMER.CORE COOLING CONT.HT REMVL ATMOS CLEANUP AND REACTOR RHR
¹ OP COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS D2. 20 INTEGRAL ATTACHMENT- VISUAL 200 COMPONENT 0 2 2 2 0 0 0 0 0 MULTIPLE STREAMS COMPONENT SUPPORTS AND COOLING WATER HX 2A 100t 100t 100't MAY APPLY.
~ RESTRAINTS & 2B INLET HEADER VISUAL 101 COMPONENT 0 5 5 0 0 5 0 0 0 COOLING WATER HX 2A 0't 100t 100t
& 2B DISCHARGE VISUAL 107 COMPONENT 0 2 2 1 0 0 0 '1 0 COOLING WATER PUMPS 50t 50t 100t 2Ag 2B & 2C INLET VISUAL 108 AUXILIARY 0 2 2 2 0 0 0 0 0 FEEDWATER PUMP 2C TO 100t 100t 100t MAIN FEEDWATER VISUAL 110 0 2 2 2 0 0 0 0 0 CONDENSATE-SUCTION 100t 100't 100t TO AUX. FEEDWATER PUMP 2A & 2B VISUAL 111 AUX. FEEDWATER 0 10 10 0 0 10 0 0 0 PUMPS 2A & 2B 04'00t 100t DISCHARGE VISUAL 112 CIRCULATING 0 9 9 0 0 0 0 9 0 WATER FROM INTAKE Ot Ot 100t COOLING WATER PUMPS VISUAL 113 CIRCULATING 0 1 1 1 0 0 0 0 0 WATER TO CCW HEAT 100t 100t'00t EXCHANGER 2A VISUAL 114 CIRCULATING 0 1 1 1 0 0 0 0 0 WATER TO CCW HEAT lOOt 100t 100t EXCHANGER 2B VISUAL 181 COMPONENT 0 4 4 4 0 0 0 0 0 COOLING WATER HEAT 100t 100t 100t EXCHANGER 2A
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 43 REVISION: 0 INSERVICB INSPECTION PLAN POR THE SECOND INTERVAL CODE EDITION: 89 CLASS 3 SECTION XZ S~iY TABLE C CATEGORY D-B - SYSTEMS IN SUPPORT OF EMER.CORE COOLING CONT.HT REMVL ATMOS CLEANUP AND RFACTOR RHR 5 OF COMPONENTS SEC. XZ ZONE RBL g OF NO. SCHEDULED/COMPLETED ITEM 8 ITEM DESCR1PTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COmZENTS D2. 20 INTEGRAL ATTACHMENT VISUAL 182 COMPONENT 4 0 0 0 0 0 0 0 MULTIPLE STREAMS COMPONENT SUPPORTS AND COOLING WATER HEAT IIIIII' 11111$ IIIIII'AYAPPLY RESTRAINTS EXCHANGER 2B VISUAL 183 COMPONENT 0 4 4 4 0 0 0 0 0 COOLING WATER PUMP 100% 1008 100%
2A VISUAL 183 COMPONENT 4 0 0 0 0 0 0 0 COOLING WATER PUMP ~~ IIII) 11 ~ 11 ~ 8 ~
2B IIIII'ISUAL 183 COMPONENT 0 4 0 0 0 0 0 0 0 COOLING WATER PUMP *11 ~ I ~ Q *~
2C IIII'IIIII'ISUAL 187 SHUTDOWN COOLING 0 2 2 0 0 2 0 0 0 HEAT EXCHANGER 2A 0% 100'C 100%
VISUAL 187 SHUTDOWN COOI ING 0 2 0 0 0 0 0 0 0 HEAT EXCHANGER 2B 1*11 ~ If ~ ~ ~ 111% I ~ *~ I ~ %
VISUAL 188 INTAKE COOLING 0 2 0 0 0 0 0 0 0 WATER PUMP 2A IIIIII'111118 111111$
VISUAL 188 1NTAKE COOLING 0 2 0 0 0 0 0 0 0 WATER PUMP 2B IIIIII( 111 ~ Il) IIIIII)
VISUAL 188 ZNTAKE COOLING 0 2 2 0 0 0 0 2 0 WATER PUMP 2C 0% Ot 100%
VISUAL 189 COMPONENT 0 2 2 0 0 0 0 2 0 COOLING WATER SURGE 0% Ot 100\
ITEM TOTAL 66 48 17 0 17 0 14 0 35% 70% 100%
D2.40 INTEGRAL ATTACHMENT SPRING VISUAL 100 COMPONENT 0 2 2 2 0 0 0 0 0 MULTIPLE STREAMS COOLING WATER HX 2A 100'8 100\ 100% MAY APPLY.
& 2B INLET HEADER
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 44 REVISION: 0 INSERVICE INSPECTION PLAN 'FOR THB SECOND INTERVAL CODB EDITION: 89 CLASS 3 SECTZON XI
~~SUMMARY~~
TABLE C CATEGORY D-B - SYSTFMS IN SUPPORT OF EMER.CORE COOLING CONT.HT REMVL ATMOS CLEANUP AND REACTOR RHR g OF COMPONENTS SEC. XZ ZONE REL 9 OF NO. SCHEDULED/COMPLETED ITEM g ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PBR COUNTS D2 40
~ INTEGRAL ATTACHMENT - SPRING VISUAL 107 COMPONENT 4 4 0 0 2 0 2 0 MULTIPLE STREAMS TYPE SUPPORTS COOLING WATER PUMPS 0% 50% 100% MAY APPLY.
2A, 2B Ec 2C INLET ITEM TOTAL 6 6 2 0 2 0 2 0 33% 66% 100%
CATEGORY TOTAL 72 54 19 0 19 0 16 0 35% 70% 100%
DATE: 07/24/93 ST. LUCIB NUCLEAR PLANT UNIT 2 PAGE: 45 REVISION: 0 INSERVICB INSPECTION PLAN'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 3 SECTION XZ
~~SUMMARY~~
TABLE C CATEGORY D-C - SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL PROM SPENT FUBI STORAGE POOL
¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ZTEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS D3. 20 INTEGRAL ATTACHMBNT- VISUAL 104 SPENT FUEL POOL 0 2 2 2 0 0 0 0 0 MULTIPLE STREAMS COMPONENT SUPPORTS AND COOLING HX 2A 1008 100% 100% MAY APPLY.
RESTRAINTS DISCHARGE PIPING VISUAL 184 FUEL POOL 1 0 0 0 0 0 0 0 COOLING PUMP 2A 1 ~ 0 ~ OO$ Oee*14$ 1 1441 ~ Q VISUAL 184 FUEL POOL 0 1 1 0 0 1 0 0 0 COOLING PUMP 2B 0% 100% 1008 VISUAL 185 FUEL POOL 2 0 0 0 0 0 0 0 COOLING HEAT t ***t 0 Q I *4 ~ I 4 8 11**1~ $
EXCHANGER 2A VISUAL 185 FUEL POOL 0 2 2 0 0 0 0 2 0 COOLING HEAT 08 Ot 100%
BXCHANGER 2B ITEM TOTAL 8 5 2 0 1 0 2 0 408 60% 100%
CATEGORY TOTAL 8 5 2 0 1. 0 2 0 408 60% 100%
SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE Ju/y 24, 1993 APPENDIX D
CLASS 1 SUPPORT
~~SUMMARY~~
TABLES Page 94 of 272
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 46 REVISION: 0 INSERVICE INSPECTION PLAN 'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XZ
~~SUMMARY~~
TABLE D CATEGORY F-A - CLASS 1 SUPPORTS
¹ OF COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTiON EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER CO~~S Fl. 10 MECHANICAL CONNECTIONS TO VISUAL 021 LOOP 2A1 SAFETY 0 1 0 0 0 0 0 0 0 25% required PRESSURE RETAINING COMPONENTS INJECI'ION PIPING eeeeeaQ ~ 144 ~ 4% 4111 ~ 1%
AND BUILDING STRUCTURE INSIDE CTMZ VISUAL 022 LOOP 2A2 SAFETY 0 1 1 0 0 0 0 1 0 INJECTION PIPING, 0% 0% 100%
INSIDE CTMT VISUAL 023 LOOP 2B1 SAFETY 0 2 0 0 0 0 2 0 INJECTION PIPING, 0% 0% 100%
INSIDE CTM1' VISUAL 024 LOOP 2B2 SAFETY 0 1 1 0 0 0 0 0 INJECTION PIPING, 100% 1008 1008 INSIDE CIÃF VISUAL 025 COMBINED 0 2 1 1 0 0 0 0 0 PRESSURIZER SPRAY 100% 100% 100%
LINE VISUAL 026 LOOP 2Bl SPRAY 0 11 3 0 0 3 0 0 0 LINE 08 100% 100%
VISUAL 027 LOOP 252 SPRAY 0 11 3 0 0 3 0 0 0 LINE 08 100% 100%
VISUAL 028 LOOP 2B SHUTDOWN 0 1 1 1 0 0 0 0 0 COOLING LINE 100% 100% 1008 VISUAL 029 LOOP 2A SHUIDOWN 0 2 1 1 0 0 0 0 0 COOLING LINE 1008 100% 100%
VISUAL 030 PRESSURZZER 0 13 3 0 0 0 0 3 0 AUXILIARYSPRAY 0% 0% 100%
VISUAL 031 CHARGING LINE TO 0 6 2 0 0 2 0 0 0 LOOP 2B1 0% 100% 100%
VISUAL 032 CHARGING LINE TO 0 28 6 2 0 2 0 2 0 LOOP 2A2 33 8 66% 100'C
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 47 REVISION: 0 INSERVZCE INSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XI SUGARY CATEGORY F-A - CLASS 1 SUPPORTS ASME ¹ OF COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS Fl. 10 MECHANICAL CONNECTIONS TO VISUAL 033 LOOP 2A1 PRIMARY 0 1 1 I 0 0 0 0 0 258 required PRESSURE RETAINING COMPONENTS DRAIN 100% 100% 100%
. AND BUILDING STRUCTURE VISUAL 034 LOOP 2A2 PRIMARY 0 1 1 0 0 1 0 0 DRAIN 0% 100' 100%
VISUAL 036 LOOP 2B2 PRIMARY 0 1 1 0 0 0 0 1 0 DRAIN 0't 0% 100%
VISUAL 037 LETDOWN LINE 0 12 3 1 0 1 0 1 0 FROM LOOP 2B1 334 66% 100%
VISUAL 186 AUXILIARY 0 1 0 0 0 0 0 0 0 FEEDWATER PUMP 2A 1*ttttt 11 ~ 1114 I ~ litt(
VISUAL 186 AUXILIARY 1 0 0 0 0 0 0 0 FEEDWATER PUMP 2B IIIIII) IIIIII't I ~ I ~ It)
VISUAL 186 AUXILIARY 0 1 1 1 0 0 0 0 0 FEEDWATER PUMP 2C 100% 100% 100%
ITEM TOTAL 97 31 9 0 12 0 10 0 29'7% 100't F1.30 WELD AND MECHANICAL VISUAL 003 STEAM GENERATOR 0 1 1 0 0 0 0 1 0 Limited to one CONNECTIONS AT INTERMEDIATE 2A PRIMARY SIDE 0% 0% ~ 100% component in a JOINTS IN MULTZCOa~aCTED group of INTEGRAL AND NONINTEGRAL components VISUAL 004 STEAM GENERATOR 0 1 0 0 0 0 0 0 0 2B PRZMMARY SIDE ttttttt tttttt) ttttttg VISUAL 005 PRESSURIZER 1 1 1 0 0 0 0 0 VISUAL 026 LOOP 2B1 SPRAY 0 1 0 0 0 0 0 0 0 LINE ttttttt tttttt) ~ ttt It~
VISUAL 027 LOOP 2B2 SPRAY 0 1 0 0 0 0 0 0 0 I INE ~ ttttt) 11* ~ ttt IIIIII'
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 48 REVISION: 0 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XI
~~SUMMARY~~
TABLE D CATEGORY F-A - SUPPORTS
¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COYMENTS ITEM TOTAL 5 2 1 0 0 0 1 0 50t 50t 100t F1.50 SPRING SUPPORTS AND CONSTANT VISUAL 016 PRESSURIZER 0 3 1 0 0 1 0 0 0 25t required LOAD SUPPORTS SURGE LINE Ot 100t 100t VISUAL 017 REACTOR COOLANT 0 4 0 0 0 0 0 0 0 PUMP 2A1 ttkkt*t 11 ~ 11*t eeet*at VISUAL 018 REACTOR COOLANT 0 4 0 0 0 0 0 0 0 PUMP 2A2 ****** t 4 %***% t I 0 1%**t VISUAL 019 REACTOR COOLANT 0 4 4 0 0 4 0 0 0 PUMP 281 Ot 100t 100t VISUAL 020 REACTOR COOLANT 0 4 0 0 0 0 0 0 0 PUMP 2B2 ****1*t 'll11%At l**'lilt VISUAL 021 LOOP 2A1 SAFETY 0 1 0 0 0 0 1 0 INJECI'ION PIPING Ot Ot 100t INSIDE CTMI' VISUAL 022 LOOP 2A2 SAFETY 0 3 1 0 0 1 0 0 0 INJECTION PIPING, 0't 100't 100t INSIDE CTÃP VISUAL 023 LOOP 2B1 SAPETY 0 2 1 0 0 0 0 1 0 INJECTION PIPING, Ot Ot 100t INSIDE CTMT VISUAL 024 LOOP 2B2 SAFETY 0 2 1 1 0 0 0 0 0 INJECTION PZPING, 100t 100t 100t INSIDE CTMT VISUAL 025 COMBINED 1 0 0 0 0 0 0 0 PRESSURZEER SPRAY lit lit
~ ~ *0 ~ ~ *t *%%*1*t LINE V1SUAL 026 LOOP 2B1 SPRAY 0 3 1 0 0 1 0 0 0 LINE Ot 100t 100t
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 49 REVISION: 0 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 1 SECTION XI
~~SUMMARY~~
TABLE D CATEGORY F-A - SUPPORTS
¹ OF COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COKhENTS F1.50 SPRING SUPPORTS AND CONSTANT VISUAL 027 LOOP 2B2 SPRAY 0 3 0 0 0 0 0 0 0 25% required LOAD SUPPORTS LINE ~ 1@1 ~ 4$ ~~ I ~ II% **4*10%
VISUAL 028 LOOP 2B SHUTDOWN 0 3 1 1 0 0 0 0 0 COOLING LINE 100% 100'00%
VISUAL 029 LOOP 2A SHUIDOWN 0 3 1 1 0 0 0 0 0 COOLING LINE 100% 100'0 100%
VISUAL 030 PRESSURIZER 2 1 1 0 0 0 0 0 AUXILIARY SPRAY 100% 100\ 100%
VISUAL 037 LETDOWN LINE 0 3 3 2 0 1 0 0 0 FROM LOOP 2B1 66 8 100% 100'0 VISUAL 038 PRESSURIZER 0 2 2 0 0 0 0 2 0 RELIEF LINE Ot 0\ 100%
ITEM TOTAL 48 18 6 0 8 0 4 0 33% '77% 100%
CATEGORY TOTAL 150 51 16 0 20 0 15 0 31% 70% 100 ~
SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 APPENDIX E CLASS 2 SUPPORT
~~SUMMARY~~
TABLES Page 95 of 272
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 50 REVISION: 0 ZNSERVICE INSPECTION PLAN 'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 2 SECTION XZ
~~SUMMARY~~
TABLE E CATEGORY F-B CLASS 2 SUPPORTS 8 OF COMPONENTS SEC. XZ ZONE REL g OF NO. SCHEDULED/COMPLETED ITEM 0 ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS Fl. 10 MECHANICAL CONNECTIONS TO VISUAL 043 LPSZ PUMP 2A 0 15 3 1 0 0 0 2 0 PRESSURE RETAINING COMPONENTS DISCHARGE HEADER 33t 33t 100t AND BUILDING STRUCTURE PIPING VISUAL 044 LPSZ PUMP 2B 0 22 6 0 0 3 0 3 0 DISCHARGE HEADER Ot 50t 100t PIPING VISUAL 045 SAFETY INJECTION 0 7 2 1 0 1 0 0 0 PIPING TO SZ TANK 50t 100t 100t 2A2 VISUAL 046 SAFETY INJECTION 0 14 3 0 0 3 0 0 0 PIPING TO SZ TANK Ot 100t 2A1 100\'ISUAL 047 SAFETY INJECTION 0 1 1 0 0,0 0 1 0 PIPING TO SI TANK Ot Ot 100t 2B1 VISUAL 048 SAFETY INJECTZOiN 0 4 1 0 0 1 0 0 0 PIPING TO SZ TANK 0\ 100\ 100't 2B2 VISUAL 061 HPSI PUiMP 2A TO 0 7 2 2 0 0 0 0 0 HEADER A 100t 100t 100t VISUAL 062 HPSI PUMP 2B TO 0 5 1 0 0 1 0 0 0 HEADER B Ot 100t 100't VISUAL 063 MAIN STEAM LINE 0 1 0 0 0 0 0 0 0 2A1 INSIDE I ~ III~ t 111000t I 1*1 ~ 0 't CONTAINMENT VISUAL 064 MAIN STEAM LINE 0 3 1 1 0 <<0 0 0 0 2B1 INSIDE 100t 100t 100t CONTAINMENT VISUAL 065 MAIN STEAM LINE 0 4 1 1 0 0 0 0 0 2A1 OUTSIDE 100t 100t 100t CONTAIN<<<<ENT
DATE: 07/24/93 ST. IUCZE NUCLEAR PLANT UNIT 2 PAGE: 51 REVISION: 0 INSERVZCE INSPECTION PLAN'FOR TIK SECOND INTERVAIi CODE EDITION: 89 CLASS 2 SECTION XZ
~~SUMMARY~~
TABLE E CATEGORY F-B - CLASS 2 SUPPORTS
¹ OF COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION,REQ COMP REQ 1$ T PER 2ND PER 3RD PER COSKNTS F1. 10 MECHANICAL CONNECTIONS TO VISUAL 066 MAIN STEAM LINE 0 4 1 0 0 0 0 1 0 PRESSURE RETAINING COMPONENTS 2B1 OUTSIDE Ot Ot 100t AND BUILDING STRUCIURE CONTAINMENT VISUAL 067 MAIN FEEDNATER 0 2 1 1 0 0 0 0 0 TO SG 2A1 INSIDE 100t 100t 100t COiNTAINMENT VISUAL 068 MAIN FEEDWATER 0 3 1 1 0 0 0 0 0 TO SG 2B1 INSIDE 100't 100t 100t CONTAINMENT VISUAL 069 CHARGING PUMP 2A 0 1 1 1 0 0 0 0 0 VISUAL 069 CHARGING PUMP 2B 0 1 0 0 0 0 0 0 0 VISUAL 069 CIQIRGING PUMP 2C 0 1 0 0 0 0 0 0 VISUAL 071 MAIN FEEDNATER 0 1 1 1 0 0 0 0 0 TO SG 2A1 OUTSIDE 100t 100 t' 100t CONTAINMENT VISUAL 072 MAIN FEEDWATER 0 1 1 0 0 0 0 1 0 TO SG 2B1 OUTSIDE Ot Ot 100t CONTAINMENT VISUAL 087 COMBINED HPSI 0 39 10 10 0 0 0 0 0 DISCHARGE 100't 100t 100't VISUAL 088 CHARGING PUMP 2A 0 14 4 0 0 4 0 0 0 DISCHARGE TO AUX. Ot 100t 100t HPSZ VZSUAL 089 CHARGING PUMP 2B 0 5 1 0 0 1 0 0 0 DISCHARGE TO AUX. Ot 100t 100t HPSI VISUAL 090 CHARGING PUMP 2C 0 2 0 0 0 0 0 0 0 DISCHARGE TO AUX. **11t ~ t lltOIII*t **%II*t HPSI
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 52 REVISION: 0 INSERVZCE INSPECTION PLAN 'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 2 SECTION XZ
~~SUMMARY~~
TABLE E CATEGORY F B - CLASS 2 SUPPORTS
¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ iTEN DESCRZPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS Fl. 10 MECHANZCAL CONNECTIONS TO VISUAL 091 COMBINED 0 7 2 0 0 2 0 0 PRESSURE RETAINING COMPONENTS CHARGING PUMP 08 100%' 100%
AND BUILDING STRUCZURE DISCHARGE TO HPSI VISUAL 092 COMBINED 1 0 0 0 0 0 0 DISCHARGE TO HPSZ 111 ~ I ~ 0 ~ I ~ I ~ I% I ~ III~ 0 TZE IN LOOP 2B VISUAL 093 HPSI 2A 0 18 5 0 0 0 0 5 0 DISCHARGE TO SDC 0% 0% 100%
LOOP 2A VZSUAL 094 HPSI HEADER B TO 0 15 4 0 0 0 0 4 0 SDC LOOP 2B 0% 0% 100%
VISUAL 095 HPSI 2A 0 8 2 0 0 0 0 2 0 DISCHARGE TO SDC 0% 0% 100%
LOOP 2B VISUAL 096 HPSI 2B 1 0 0 0 0 0 0 0 DISCHARGE TO SDC IIIIII'IIIIIQ LOOP 2B IIIIII'ISUAL 097 CONTAINMENT 0 3 1 0 0 0 0 1 0 SPRAY PUMP 2A 08 0% 100%
VISUAL 097 CONTAIL7KNT SPRAY PUMP 2B 3 0
~ IIIII'IIlla'II 0 0 0
~
0 0 0
~ 11$
VISUAL 098 HPSI PUMP 2A 0 2 1 0 0 0 0 1 0 VISUAL 098 HPSI PUMP 2B 0 2 0 0 0 0 0 0 0 ITEM TOTAL 217 57 20 0 16 0 21 0 358 63% 100'8 F1.50 SPRING SUPPORTS AND CONSTANT VISUAL 044 LPSZ PUMP 2B 0 1 1 0 0 0 0 1 0 At least 25%
LOAD SUPPORTS DISCHARGE HEADER Ot Ot 100%
PIPING
0 DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 53 REVISION: 0 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CZASS 2 SECTION XI SUaaRY TABLE E CATEGORY F B CLASS 2 SUPPORTS
¹ OF COMPONENTS SEC. XI ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS F1.50 SPRING SUPPORTS AND CONSTANT VISUAL 046 SAFETY INJECI'ZON 0 1 1 0 0 1 0 0 0 At least 25%
LOAD SUPPORTS PIPING TO SI TANK Ot 100% 100%
2A1 VISUAL 048 SAFETY INJECTION 0 1 1 0 0 1 0 0 0 PIPING TO SI TANK 0% 100% 100%
2B2 VISUAL 061, HPSI PUMP 2A TO 0 1 0 0 0 0 0 0 0 HEADER A IIIIII% ~ I ~ I ~ IV IIIIII)
VISUAL 063 MAZN STEAM LINE 0 5 1 1 0 0 0 0 0 2A1 INSIDE 100% 100¹ 100%
CONTAINMENT VISUAL 064 MAIN STEAM LINE 0 5 1 0 0 0 0 1 0 2B1 INSIDE 0't 0% 100 t CONTAINMENT VISUAL 067 MAIN FEEDWATER 0 2 1 1 0 0 0 0 0 TO SG 2A1 INSIDE 1008 100% 100%
CONTAINMENT VISUAL 068 MAIN FEEDNATER 0 5 1 1 0 0 0 0 0 TO SG 2B1 INSIDE 1008 100% 100%
CONTAZNMENT VISUAL 100 COMPONENT 0 1 1 1 0 0 0 0 0 COOLING HATER HX 2A 100% 100% 100%
8 2B INLET HEADER ITEM TOTAL 22 8 4 0 2 0 2 0 50% 75% 100%
F1.60 SLIDING SURFACES VISUAL 044 LPSZ PUMP 2B 0 1 0 0 0 0 0 0 0 At least 25%
DISCHARGE HEADER ~~ 1*I~ 0 11 ~ I ~ ~ 0 11 ~ I~ I%
PIPING VISUAL 094 HPSZ HEADER B TO 0 2 1 1 0 0 0 0 SDC LOOP 2B 100%' 100% 100%
DATE: 07/24/93 ST. ZUCZE NUCLEAR PLANT UNIT 2 PAGE: 54 REVISION: 0 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 2 SECTION XZ SUYNARY TABLE E CATEGORY F-B CLASS 2 SUPPORTS
¹ OF COMPONENTS SEC. XI ZONE RBL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COWKTS ITEM TOTAL 3 1 1 0 0 0 0 0 100% 100% 100%
CATEGORY TOTAL 242 66 25 0 18 0 23 0 37't 65't 100%
SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 APPENDIX F CLASS 3 SUPPORT
~~SUMMARY~~
TABLES Page 96 of 272
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 55 REVISION: 0 INSERVZCE INSPECTION PLAN 'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 3 SECTION XZ
~~SUMMARY~~
TABLE F CATEGORY F-C - CLASS 3 SUPPORTS
¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRZPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS Pl. 10 MECHANICAL CONNECTIONS TO VISUAL 100 COMPONENT 0 17 3 3 0 0 0 0 0 At least 25'00%
PRESSURE RETAINING COMPONENTS COOLING WATER HX 2A 100%
AND BUILDING STRUCTURE & 2B INLET HEADER 100'ISUAL 101 COMPONENT 0 15 5 5 0 0 0 0 0 COOLING WATER HX 2A 100t 100'00%
& 2B DZSCKQtGE VISUAL 102 COMPONENT 0 14 5 3 0 0 0 2 0 COOLING - SHUTDOWN 60% 60% 100%
COOLING HX 2A INLET VISUAL 103 COMPONENT 0 13 2 2 0 0 0 0 0 COOLING - SHUTDOWN 100% 100'00%
COOLING HX 2B INLET VISUAL 104 SPENT FUEL POOL 0 5 2 2 0 0 0 0 0 COOLING HX 2A 100% 100% 100%
DZSL7iARGE PIPING VISUAL 105 COMPONENT 0 18 7 4 0 2 0 1 0 COOLING-SHUTDOWN 57% 85% 100%
COOLING HX 2A DISCHARGE VISUAL 106 COMPONENT 0 24 5 4 0 0 0 1 0 COOI ING-SHUTDOWN 80% 80% 100%
COOLING HX 2B DISCHARGE VISUAL 107 COMPONENT 0 19 4 4 0 0 0 0 0 COOLING WATER PUMPS 100% 100% 100%
2A, 2B & 2C INLET VISUAL 108 AUXILIARY 0 19 i4 4 0 0 0 0 0 FEEDWATER PUMP 2C TO 100% 1000 100%
MAIN FEEDWATER VISUAL 109 0 9 2 2 0 0 0 0 0 CONDENSATE-SUCTION 100% 100% 100%
TO AUX. FEEDWATER PUMP 2C
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGB: 56 REVISION: 0 INSERVZCE INSPECTION PLAN 'FOR THB SECOND INTERVAL CODE EDITION: 89 CLASS 3 SECTION XZ SUGARY TABLE F CATEGORY F C - CLASS 3 SUPPORTS AS ME ¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ZTEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COiO4ENTS Fl.lo MECHANICAL CONNECTIONS TO VISUAL 110 9 3 2 0 0 0 1 0 At least 25%
PRESSURE RETAINING COMPONENTS CONDENSATE-SUCTION 66% 668 100%
AND BUILD1NG STRUCZURB TO AUX. FEEDWATER PUMP 2A & 2B VISUAL 111 AUX. FEEDWATER 0 21 10 6 0 0 0 4 0 PUMPS 2A & 2B 60% 608 100'C DISCHARGE VISUAL 112 CIRCULATING 0 16 7 6 0 0 0 1 0 WATER FROM INTAKE 85% 85% 1008 COOLING WATER PUMPS VZSUAL 113 CIRCULATING 0 14 1 1 0 0 0 0 0 WATER TO CCW HEAT 100% 1008 100%
EXCHANGER 2A VISUAL 114 CIRCULATING 0 11 1 1 0 0 0 0 0 WATER TO CCW HEAT 100\ 100%
EXCHANGER 2B 100%'ISUAL 115 CIRCULATING 0 11 0 0 0 0 0 0 0 WATER-CCW HEAT EXCH. 11 ~ ~ *~ \ ~ ttttt% 1111 ~ 1%
2A & B DZSCHARGB VISUAL 180 LETDOWN HEAT 0 2 2 2 0 0 0 0 0 EXCHANGER 100% 100% 100%
VISUAL 181 COMPONENT 0 4 4 4 0 0 0 0 0 COOLING WATER HEAT 1008 100% 1008 EXCHANGER 2A VISUAL 182 COMPONENT o o o o o o o COOLING WATER HEAT tttttt) ~ *11*~ $ ttttttf EXCHANGER 2B VISUAL 183 COMPONENT o 4 4 4 o o o o 0 COOLING WATER PUMP loot 1008 100%
2A VISUAL 183 COMPONENT 4 0 0 0 0 0 0 0 COOLING WATER PUMP tttttt) tttttt( tttttt) 2B
DATE: 07/24/93 ST. LUCIS NUCLEAR PLANT UNIT 2 PAGE: 57 REVISION: 0 INSERVICE INSPECTION PLAN 'FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 3 SECTION XZ SUYMARY TABLE F CATEGORY F C - CLASS 3 SUPPORTS
¹ OF COMPONENTS SEC. XZ ZONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COYMENTS Fl. 10 MECHANICAL CONNECTIONS TO VISUAL 183 COMPONENT 0 4 0 0 0 0 0 0 0 At least PRESSURE RETAINING COMPONENTS COOLING WATER PUMP I ~ IIII% IIIIIIV 25'IIIII%
AND BUILDING STRUCTURE 2C VISUAL 184 FUEL POOL 0 1 0 0 0 0 0 0 0 COOLING PUMP 2A ~ 11% IIIIII% IIIIII'11 VISUAL 184 FUEL POOL 0 1 1 1 0 0 0 0 0 COOLING PUMP 2B 100% 100% 100¹ 185 FUEL POOL 2 0 0 0 0 0 0 VISUAL COOLING HEAT 0 0 IIIIII'IIIII)I Ill I8 ~
EXCHANGER 2A VISUAL 185 FUEL POOL 0 2 2 2 0 0 0 0 0 COOLING HEAT 100% 100% 100%
EXCHANGER 2B VISUAL 186 AUXILIARY 1 0 0 0 0 0 0 0 FEEDWATER PUMP 2A IIIIII' ~ 11'Il) I IIIIIQ VISUAL 186 AUXILIARY FEEDWATER PUMP 2B 0 0 IIIII$ ~
0 IIIIII'IIIII' 0 0 0 0 VISUAL 186 AUXILIARY 0 1 1 1 0 0 0 0 0 FEEDWATER PUMP 2C 100% 100% 100%
VISUAL 187 SHUTDOWN COOLING 0 2 2 2 0 0 0 0 0 HEAT EX&iANGER 2A 100% 100% 100%
'VISUAL 187 SHUTDOWN COOLING 0 HEAT EXCHANGER 2B 2
IIIIII'III 0 0 0
~ IQ 0
IIIIII'ISUAL 0 0 188 INTAKE COOLING 0 2 0 0 0 0 0 0 0 WATER PUMP 2A II Ill(
~ 111 ~ II) I II If ~ ~
VISUAL 188 INTAKE COOLING 0 2 0 0 0 0 0 0 0 WATER PUMP 2B IIIIII% I ~ ~ ~ II% ~~ I ~ lit VISUAL 188 INTAKE COOLING 0 2 2 2 0 0 0 0 WATER PUMP 2C 100 ' 100% 100%
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 58 REVISION: 0 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CODE EDITION: 89 CLASS 3 SECTION XI SUaaRY TABLE F CATEGORY F C CLASS 3 SUPPORTS OF COMPONENTS SEC. XI ZONE REL 5 OP NO. 'CHEDULED/COMPLETED ITEM 8 ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS Fl. 10 MECHANICAL CONNECTIONS TO VISUAL 189 COMPONENT 0 2 2 2 0 0 0 0 0 At least 25%
PRESSURE RETAINING COMPONENTS COOLING WATER SURGE 100% 2008, 100%
AND BUILDING STRUCTURE TANK ITEM TOTAL 278 81 69 0 2 0 10 0 85%'7% 100%
F1.30 WELD AND MECHANICAL VISUAL 103 COMPONENT 0 1 1 0 0 0 0 1 0 At least 25%
CONNECTIONS AT INTERMEDIATE COOLING - SHUTDOWN 0% 08 100%
JOINTS IN MULTICONNECTED COOLING HX 2B INLET INTEGRAL AND NONINTEGRAL P1.50 SPRING SUPPORTS AND CONSTANT VISUAL 105 COMPONENT 0 5 1 1 0 0 0 0 0 At least 25%
LOAD SUPPORTS COOLING SHUTDOWN 100% 100%'00%
e VISUAL COOLING HX 2A DISCZIARGE 106 COMPONENT 0 2 2 2 0 0 0 0 0 COOLING-SHUTDOWN 100% 100% 100%
COOLZNG HX 2B DISCHARGE VISUAL 107 COMPONENT 0 3 3 3 0 0 0 0 0 COOLING WATER PUMPS 100% 100% 100t 2A, 2B Ea 2C INLET ITEM TOTAL 10 6 6 0 0 0 0 0 100% 100% 1008 Fl ~ 60 SLIDING SURFACES VISUAL 101 COMPONENT 0 5 0 0 0 0 0 0 0 At. least 25k COOLING WATER HX 2A 1111 ~~$ ~~ 1111( * ~ ~ *11) 6( 2B DISCHARGE VISUAL 107 COMPONENT 0 0 0 0 0 0 0 0 1 ~ ~ 4 ~ 1% 111111% ~ 1111 ~ 0 COOLING WATER PUMPS 2A, 2B Ec 2C INLET
DATE: 07/24/93 ST. LUCIE NUCLEAR PLANT UNIT 2 PAGE: 59 REVISION: 0 INSERVZCB INSPECTION PLAN FOR THB SECOND INTERVAL CODE EDZTZON: 89 CLASS 3 SECI'ZON XI
~~SUMMARY~~
TABLE F CATEGORY F-C - CLASS 3 SUPPORTS
¹ OF COMPONENTS SEC. XI BONE REL ¹ OF NO. SCHEDULED/COMPLETED ITEM ¹ ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS F1.60 SLIDING SURFACES VISUAL 109 1 0 0 0 0 0 0 0 At least 25%
CONDENSATE-SUCTION tttltt) tttttt) 11*111$
TO AUX. FEEDWATER PUMP 2C VISUAL 112 CIRCULATING 0 2 2 1 0 0 0 1 0 WATER FROM INTAKE 50't 50% 100%
COOLING WATER PUMPS VISUAL 115 CIRCULATING 0 4 0 0 0 0 0 0 0 WATER-CCW HEAT EXCH. ttttttf **1111) tttttt) 2A & B DISCHARGE ITEM TOTAL 13 2 1 0 0 0 1 0 50% '0% 100'C CATEGORY TOTAL 302 90 76 i 0 2 0 12 0 84a 86% 100%
SECOND 'INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 APPENDIX G
'REQVESTS FOR REL'IEF FROM CODE'REQVIREMENTS Page 97 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 1 A. COMPONENT IDENTIFICATION:
Class: 1 Reactor Vessel and Closure Head Pressure Retaining Welds B. EXAMINATION REQUIREMENTS:
ITEM NO. EXAMINATION REQUIREMENTS CAT.
8-A 81.10 Essentially 100% volumetric examination of all longitudinal and 81.11 circumferential shell welds (does not Include shell to flange weld).
81.12 8-A 81.20 Essentially 100% volumetric examination of accessible length of 81.21 circumferential and meridional head welds.
81.22 8-A 81.30 Essentially 100% volumetric examination of the shell to flange weld.
8-A 81.40 Essentially 100% volumetric and surface examination of head to flange wold C. RELIEF REQUESTED:
Relief is requested from the ASME Boiler and Pressure Vessel Code required volume due to the following:
1) Configuration and permanent attachments prohibit 100% ultrasonic examination coverage of the required examination volume. Additional ultrasonic techniques are employed, where practical, to achieve the code required volume. See attached table summary of coverage achieved and limitations.
~~2) Interference from search unit wedge-to-component near surface interface noise, and Page 98 of 272~~
~~ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 1~~
~~3) Component geometric interferance with the scanning equipment and/or geometric shadowing of examination areas.~~
D. BASIS FOR RELIEF:
10 CFR 50.55a (g) (4), recognizes that throughout the service life of a nuclear power facility, components which are classified as ASME Code Class 1 shall meet the requirements, except design and access provisions requirements, set forth in Section XI, to the extent practical within the limitiations of design, geometry and materials of construction of the components.
2. NDE procedures implemented during the St. Lucie Unit 2 RPV examinations required full vee path calibration of the 46'hear wave scans to compensate for limitiations encountered in the near surface and those due to geometric shadowing. Those examination volumes which receive other than 100% of the ASME Code required coverage are identified within this Request for Relief. Generally, interface noise inhibits resolution capibilities at the near surface for about 1/2 to 2 inches of metal path for longitudinal wave examinations. It should be noted that electronic gating does not result in any examination limitations since the entire instrument screen presentation is monitored during the examinations, video taped, and reviewed independently following the examinations.
Described below, coupled with the Tables and Figures, detail the examination limitations by weld description. The accompanying Figures graphically depict the locations and extents of the limitiations with respect to weld metal and associated base material. The Table quantifies the limitations in terms of present code required volume which is effectively covered.
RPV LOWER HEAD MERIDIONAL WELDS Mechanized scanning of the Lower Head Meridional welds 101-164A through F is limited due to interference from the core support lugs and flow skirt. Figure 1.1 is a roll out inside view showing inside surface scan limitations. Figure 1.2 provides a side section view of peel segment welds showing limitations caused by core support lugs and flow skirt support. Figure 1.3 provides a graphic view of a typical Page 99 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 1 meridional weld showing transverse scan limitiations in the area behind the flow skirt.
RPV CIRCUMFERENTIAL SHELL WELDS The mechanized examination of the Lower Shell-to-Lower Head weld 201-141 is limited due to interference from the core support lugs and antirotation lugs. Figure 1.1 is a roll out view showing the inaccessible scan surfaces from the vessel inside surface and shows the volume of material not examinable from the inside surface where scanning was limited by lug interference.
Examination of the Middle Shell-to-Lower Shell weld 101-171 is limited due to interference from the surveillance specimens. Figure 1.1 is a roll out view of weld 101-171 depicting areas where parallel examination scans can not be performed.
The Upper Shell-to-Flange weld 101-121 is exmained from the shell side and from the flange seal surface. The 0'nd 60'hell side examinations are limited due to near surface interface noise; however, this volume is effectively examinable using the 45'ull vee path beam.
Beams directed nearly perpendicular to the weld plane from the flange seal surface compensated for the straight beam and angle beam examination limitations on the flange side of the weld. Due to the flange configuation, no transverse examination scans can be performed on the flange side of the weld. Transverse examinations are also limited on the shell side of the weld due to near surface interface noise but the near surface volume is effectively examinable with 45'ull vee path scans. Figure 1.6 shows the limitations to the shell side examination and depicts the coverage obtainable from the seal surface examination. Also shown is the tapered surface where transverse examination is prohibited.
RPV LONGITUDINAL SHELL WELDS The examinations of the Lower Shell Vertical welds 101-142A, B and C are limited due to near surface interface noise. Those volumes shadowed by the interface noise are effectively examinable with the vee path scans, except for a small area of interference from the 45'ull core barrel antirotation lugs in the case of welds 101-142B and C.
Figure 1.1 shows the limitation of the 45'ee path examination. The Page 100 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 1 examination of weld 101-142C is also limited due to interference of the surveillance capsules. This volume is effectively examinable by the vee path beam. The 0'nd 60'eam limitations are shown on 45'ull Figure 1.5.
Examination of the Middle Shell Vertical welds 101-124A, B and C are limited by near surface interference noise in the case of 0'nd however, the 45'ull vee path scans obtain full coverage. The 60'eams; 60'xamination of weld 101-124C is further limited by interference from the surveillance capsules as shown on Figure 1.1.
Examination of the Upper Shell Vertical welds 101-122A, B and C are limited by interference from the inlet nozzle inner radius blend and the outlet nozzle integral extension as shown on Figure 1.1 However, the
~
examinations are complemented by the Nozzle-to-Shell weld examinations. Figure 1.5 shows 45'overage of the volumes not, effectively examinable by 0'nd 60'ue to near surface interface noise.
RPV NOZZLE TO SHELL WELD The inlet and outlet Nozzle-to-Shell welds are examined from the shell side and from the nozzle bore. The Nozzle Bore examinations are limited due to near surface interface noise; however, surface wave examinations are performed on the nozzle inner radius sections. The shell side transverse examinations of the outlet nozzles are limited due to interference from the nozzle integral extentions. Limitations to the Inlet Nozzle examinations are shown on Figure 1.7 and limitations to the Outlet Nozzle examinations are shown on Figure 1.8.
RPV CLOSURE HEAD The Closure Head-to-Flange weld 101-101 is examined from one side due to flange. Figure 1.10 provides the scan path for this weld.
The Closure Head Dome weld 102-101 is limited due to instrument nozzles, penetrations, and CEDM's, see Figure 1.13.
Page 101 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 1 The extent of examination volume achieved ultrasonically and the alternate scans performed (see Examination Coverage Table) coupled with the system pressure tests provied assurance of an acceptable level of quality and safety.
E. ALTERNATIVE EXAMINATIONS OR TESTS:
~~1) Periodic System Pressure tests per Category B-P, Table IWB-2500-1~~
~~2) Inservice Hydrostatic tests per Table IWB-2500-1~~
~~3) Conduct Mechanized Ultrsonic Examinations to the extent practical ~~~
F. IMPLEMENTATION SCHEDULE:
Second Inservice Inspection Interval August 8, 1993 to August 08, 2003 G. ATTACHMENTS TO THE RELIEF:
~~1) Examination Coverage Table~~
~~2) Examination Limitation Drawings.~~
Suamary Examination Beam Beam Percent Figure Description of Examination number Area Angle Direction Coverage No. Coverage and Limitations identification 000020 Bottom Head 0 LAII 62% 1&2 Examination of IWB-2500-3 E-Peel Segment CW/CCW 62% F-G-H volume limited along Weld 9 30 Deg. 45'0'0/70' CW/CCW 62% length of weld near flow NO. 101-154A CW/CCW 62% skirt-lower head attachment.
WRV 62%
45'T UP/DN 69%
60'T UP/DN 70%
50/70 T UP/DN 72%
000030 Bottom Head O'am 50% 1,2,3 Examination of IWB-2500-3 E-Peel Segment CW/CCW 54/62% F-G-H volume limited along Weld 9 90 Oeg. 45'0'0/70' CW/CCW 54/62% length of weld near flow No. 101-1548 CW/CCW 54/62% skirt-lower head attachment WRV 62% and at flow skirt support 45'T UP/ON 69% bracket.
60'T UP/DN 70%
50/70 T UP/DN 72%
Page 102 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 1 Stannary Examination Beam Beam Percent Figure Description of Examination nwher Area Angle Direction Coverage Ho. Coverage and Limitations Identification 000040 Bottom Head O'am 62% 1&2 Examination of IWB-2500-3 E-Peel Segment O'M/CCW 62/ F-G-H volume limited along Weld oI150 Deg. 45'0'0/70RV CM/CCW 62% length of weld near flow No. 101-154C CW/CC'M 62% skirt-lower head attachment.
62/
45'T UP/DN 69%
60 T UP/DN 70%
50/70'T UP/DN 72%
000050 Bottom Head O'am 58% '1.2.3 Examination of IMB-2500-3 E-Peel Segment CW/CCW 54/62% F-G-H volune limited along Weld 9210 Deg. 45'0'0/70' CW/CCW 54/62% length of weld near flow No. 101-'154D CW/CCW 54/62% skirt-lower head attachment WRV 62% and at flow skirt support 45 T UP/DN 69% bracket.
60 T UP/DN 70%
50/70'T UP/DN 72%
000060 Bottom Head O'am 62% 182 Examination of IWB-2500-3 E-Peel Segment CW/CCW 62% F-G-H volwe limited along Weld 9270 Deg. 45'0'0/70' CW/CCW 62% length of weld near flow No. 101-154E CW/CCW 62/ skirt- lower head attachment WRV 62%
45'T UP/DN 69%
60 T UP/DN 70%
UP/DN 72%
000070 Bottom Head O'am 58% 1,2,3 Examination of IMB-2500-3 E-Peel Segment 45'0O CW/CCW 54%/62% F-G-H volume limited along Weld 9 330 Deg. CW/CCW 54%/62% length of weld near flow No. 101-154F 50/70RV CM/CCW 54%/62% skirt- lower head attachment 63/ and at flow skirt support 45 T UP/DN 69% bracket.
60'T UP/DN 70%
50/70'T UP/DN 72%
000080 Bottom Head-to- O'am 93% 184 Examination of IWB-2500-3 E-Lower shell 450 CW/CCM 100%/86% F-G-H volwe limited along Circ. Weld 60'0/70' CW/CCW 100%/88% length of weld below core No. 201-141 O'M/CCW 100%/84% barrel anti-rotation lugs.
WRV 93%
45 T UP/DN 93%
60 T UP/DN 93%
50/70 T UP/DN 93%
000110 Lower Shell O'am 87% 1&5 Examination of IWB-2500-2 A-Long. Weld 8225 CW/CCW 100%/85% B-C-D volume limited from one Deg. 45'0'0/70' CW/CCW >OO//77/ side along length of weld No. 101-142C CW/CCW 100%/87% near reactor vessel material WRV 100% specimen tubes.
45 T UP/DN 100%
60'T UP/DN 100%
50/70'T UP/DN 100%
Page 103 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 1 Sunna ry Examination Beam Beam Percent Figure Description of Examination number Area Angle Direction Coverage No. Coverage and Limitations Identification 000120 Lower Shell-to- O'am 92/. Examination of IWB-2500-2 A-Intermediate CW/CCW 92% 8-C-D volune limited along Shell Circ. 45'0'0/70RV CW/CCW 92% length of weld near vessel Weld CW/CCW 92% material specimen tubes.
Ho. 101-171 85%
45'T UP/DN 85/
60 T UP/DN 85/.
50/70 T UP/DN 83%
000150 Intermediate O'am 74% 185 Examination of IWB-2500-2 A-Shell Long. CW/CCW 100%/70% 8-C-D voiunc limited along Weld 8255 Deg. 45'0'0/70' CW/CCW 100%/55% length of weld near vessel No. 101-124C CW/CCW 100%/74% material specimen tubes.
WRV 100%
45 T UP/DH 100%
60 T UP/DH 100%
50/70'T UP/DN 1005 000170 Upper Shell O'am 95% Examination of IWB-2500-2 A-Longitudinal CW/CCW 100%/96% B-C-D volune limited at Weld ol15 Deg. 45'0'0/70' CW/CCW 100/96% intersection with the Ho. 101-122A CW/CCW 100%/99% adjacent outlet nozzle WRV 97% integral extension.
45'T UP/DN 79/
60 T UP/DN 74%
50/70'T UP/DH 95%
000180 Upper Shell O'am 96% Examination of IWB-2500-2 A-Longitudinal CW/CCW 100%/98% B-C-D voiune limited at Weld oI 135 Deg. 45'0'0/70' CW/CCW 100%/98% intersection with the No.101-1228 CW/CCW 100% adjacent inlet nozzle inner WRV 98% blend.
45 T UP/DN Br%
60 T UP/DH 83%
50/70'T UP/DN 97%
000190 Upper Shell O'am 96% Examination of IWB-2500-2 A-Longitudinal CW/CCW 100%/98% 8-C-D volune limited at Weld 8255 Deg. 45'0'0/70' CW/CCW 100%/98% intersection with the No. '101-122C CW/CCW 100% adjacent inlet nozzle inner WRV 98% blend.
45 T UP/DH Bri 60 T UP/DN 83%
50/70 T UP/DH 97/
000200 Upper Shell-to- O'am 70/ 186 Examination of IWB-2500-2 A-Flange CW/CCW 87% B-C-D volune for Transverse Circumferential 45'0'0/70'0 CW/CCW 80% flaws is limited above the Weld CW/CCW 707 weld by the inside surface No. 101-121 WRV 50% taper.
45'T UP/DH 50%
60 T UP/DN 50%
50/70 T UP/DN 50%
Page 104 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 1 Summry Examination Beam Beam Percent Figure Description of Examination nwber Area Angle Direction Coverage No. Coverage and Limitations Identification 000210 Outlet Nozzle 0I 0 WRV 28/i Examination of IWB-2500-7-A-0 Dcg. Hozzlc- 45'T Shell 28/ B-C-0-E-F-G-H-I and M-N-0-P to-Shell Weld. 60 T SheLL 28% volunes transverse No. 105-121a 50/70'T Shell 28% examination from shell is limited by the integral extension.
000240 Outlet Nozzle 8 0 WRV Sh@L L 28/i Examination of IMB-2500-7-A-180 Deg. 45 T Shel l 28/>> B-C-D-E-F-G-H-I and N-N-0-P Nozzle-to-Shell 60 T SheLL 28/i volumes transverse Meld 50/70'T Shell 28% examination from shell is No. 103-1218 Limited by the integral extension.
000790 Flange to Torus O'WRV 80/i 9,10,11 Examination of IWB-2500-5 Weld 45 A Flange 100/70/ volune limited at Ho. 101-101 60 A Shroud 70/60% intersection of flange flex 45 UP/DOWN 100/50% radius, shroud, shroud hold 60 UP/DOWN 100/100% down lugs, and head lifting lugs.
000800 Peel Segment 0 WRV 80% 10 & 13 Examination of IMB-2500-3 weld volume limited by location of 0I 0'01-104-A 45'0'hell 45 T 60'T CW/CCW O'M/CCW 100/80%
100/80% shroud and at intersection of 45 UP/DOWN 100/60/. adjacent weld 101-101 and 60' UP/DOWN 100/50% shroud.
Peel Segment WRV 80/ 10 & 13 000810 Weld 0I 45 T CM/CCW 100/80%
60'T 90'01-104-8 CW/CCW 100/80%
45'00 UP/DOWN 100/60%
UP/DOWN 100/50%
0 WRV 000820 Peel Segment 45 T 80% 10 & 13 Weld 9 60 T CW/CCW 100/80%
180'01-104-C 45'0' CWICCM 100/80%
UP/DOWN 100/60%
UP/DOWN 100/50%
WRV 000830 Peel Segment 45'T 80/i 10 & 13 Weld 0j 60 T CW/CCM 100/80%
270'01-104-0 CWICCW 100/80/i UP/DOWN 100/60%
UP/DOWN 100/50%
000840 Dome Weld 0 LAN 40% 9 & 13 Examination of IWB-2500-3 Ho. 102-101 45 35/90% volume limited by location of 60'5'0'W/CCW CM/CCW 25/80% shroud and at intersection of UP/DOWN 20/35% adjacent weld 101-101 and UP/DOWN 10/80% shroud.
Page 105 of 272
60' 90' 120 135 180'40'55'70' 300 ' 360' I I I AREA OF ID TAPER 101-121 NOZZLE INTERFERENCE I WITH VERTICAL WELD TRANSVERSE SCANS C3
~ 101-122A ~ 101-122B ~ 101-122C
~ RPV MATERIAL SPECIMEN TUBES 33'53'3 106-121
~ 101-124A ~ 101-1248 101-124C ~
~ 101-171 SKIRT SUPPORT
~ 101-142A 97'04
~ 101-14 28 277 284'63' 300'60'LOW CORE BARREL O
60'3 0 101-142C ANTI ROTATION LUG 120 180
~ 201-141 90'30 150'60'05'10'50'70'80'25'30'LOVI SKIRT 40 85 UPPER EDGE FLOW SKIRT 101-154A 101-1548 101-154C 101-154 D 101-154E 101-154F LOWER EDGE 101-151 ROLL OUT INSIDE VIEW INACCESSIBLE SCANNING SURFACES FIGURE 1.1
FLOW SKIRT SUPPORT 11.3'8.1'ORE SUPPORT LUGS FLOW SKIRT EXAM UMITATION SIDE SECTION VIEV!
PEEL SEGMENT WELDS 79.82 WELDS 101-154A THRU F FIGURE 1.2
PARALLEL EXAM SECTION AT BOTTOM OF WELD TRANSVERSE EXAM rf FLOW SKIRT SUPPCRT EXAM UMITATION SECTION AT SKIRT SUPPORT I I I I II I I IIII I I I I I SECTION AT TOP OF WELD PEEL SEGMENT WELDS AT 90, 210, AND 330 AZIMUTH TOP VIEWS WELDS 101-154A THRU F'IGURE 1.3
CORE BARREL ANTI ROTATION LVG (TYP 6 PLACES)
I/2 t TRANSVERSE PARALLEL EXAMINATION EXAMINATION UMI TATION UMITATION CORE SUPPORT LUGS 1/2 t FLOW SKIRT SUPPORT LOWER HEAD TO LOWER SHELL CIRCUMFERENTIAL YIELD FlGURE lA
RPV MATERIAL SPECIMEN INTERMEDIATE ANO LOWER SHELL VERTICAL WElDS AT 255 VESSEL AZIMU iH PARALLEL EXAMINATION LIMITATION (0,'5, 60,'0/70'CW BEAMS)
WElD 101-124C FIGURE 1.5
FROM SEAL SURFACE FLANGE IO TAPER (360')
NO TRANSVERSE PARALLEL EXAMINATION EXAMINATION UMITATION LIMI TATlON SHELL WELD 101-121 FIGURE 1.6
INLET NOZZLES NO UMITATION TRANSVERSE EXAMINA'RON 0', 45,'0'AND 50/70'FROM SHELL) 50/70'FROM BORE) 15'EAM UMITATION AT 90'ND 270'OZZLE AZIL/VTH 45 BEAM UMITATION AT O'AND 180'NOZZLE AZIMuTH PARALLEL EXAMINATION (15'AND 45'FROM BORE)
FIGURE 1.7
TRANSVERSE EXAMINATION (If, 45', 60,'0/70'FROM SHELL)
NO EXAMINATION FOR 360'OZZLE AZIMUTH OUTLET NOZZLES EXAMINATION FROM BORE ON PREVIOUS OUTAGE WELDS 105-121A + B FIGURE 1.8
102-101 101-101 FROM O.D.
OF I.D.
SECllON A-A RGURE 1.9
WELD REQUIRED VOLUME AND SCAN PATHS FOR CLOSURE HEAD VIELD AND PEEL YIELDS O.D. SURFACE SCAN PATH LEGEND HEAD II PARRALLEL SCAN J. PERPENDICULAR SCAN 45'l O'- CAUBRATED LONGITUDINAL 60'3.
23 60oJ 45+
23" 6" I.D. SURFACE 0 WRV ULTRASONIC EXAMINATION V, OF RPV FLANGE CLOSURE 11 II HEAD 'AELD 10 6" 101-104 A-D 0
101-101 6"
FLANGE 45 II 60 II 23" CLAD ( I.D. SURFACE CLAD ID PRESSURE RETAINING SURFACE O.D. SURFACE PSL RPV CLOSURE HEAD WEl DS FIGURE 1.10
FLANGE SCAN FLEX DIRECTION AREA SHROUD SCAN LOCATION DIRECTION WOW 1/2 T 1/2 T 6.2 60 60 WELD NO. 101-101 FlGVRE 1.11
FLANGE FLEX AREA LIMITATIONS (TYPICAL)
SHROUD LUG WELD CROWN 16' I/4" 6 2/10" 2 5/10 FLANGE UP RPV STUD HOLE N LUGS LOCATED AT SHROUD STUD HOLES; LUG LUG III 3O
/f 8
$ 12 g 39 NOTE: LUGS ARE SPACED 38"
$ 17 21 f 4844 APART LOCATED BY ADJACENT RPV STUD HOLES.
III g g 25 III 53 EXAMINED FROM STUD HOLE 0 THROUGH 28 CLOCKNSE LOOKING DOWN.
FIGURE 1.12
101-10%-C SAN OOO QO
~" 0 oQo 0
HA% 72 "o'Q 52Q Q20Q7 Q15 12Q22 16Q 23 Q
O" 0
4O, Oa 61Q Q2 270 90 60 Q6
'2O Os7 51Q Q19 Q14
,O O-Oss 76
< 0 < Q43 Q 2~O P o o oQOo O42O Q
O O 56+ 69 0 0 ooo o 070
, oQOo 0 O 0
101-10+-A 0
FlGVRE 1.13
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 2 Relief Request Number 2 is no longer required for the second inspection interval.
The 1989 Code Edition requires only one weld to be examined. The one weld selected does not require a request for relief.
Page 119 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 3 A. COMPONENT IDENTIFICATION:
l Class: 1 Identification of components: Pressurizer Description of components: Full Penetration Welds of Nozzle in Vessel-Inspection Program B B. EXAMINATION REQUIREMENTS:
ITEM NO. EXAMINATION REQUIREMENTS CAT.
B-D 83.110 Essentially 100% volumetric exam of nozzle to vessel welds in pressurizer C. RELIEF REQUESTED:
Relief is requested from the ASME Boiler and Pressure Vessel Code required volume.
D. BASIS FOR RELIEF:
Configuration and permanent attachments prohibit 100% ultrasonic examination of the required volume. Additional ultrasonic techniques are employed where practical, to achieve the Code Required Volume.
NOZZLE - TOP OF PRESSURIZER Due to the close proximity of Pressurizer Nozzle orientation, as identified in Figures 1 and 2 attached, the ultrasonic scan distance of 8.0" for 45',
and 12.0" for 60'an not be accomplished.
Page 120 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 3 PRESSURIZER SURGE NOZZLE Figure 3 identifies the 60'ngle beam scan limitations affecting the examination, due to 10 Pressurizer Heater Penetrations.
The extent of examination volume achieved ultrasonically and the alternate scans performed (see Examination Coverage Table) coupled with the system pressure tests provide assurance of an acceptable level of quality and safety.
E. ALTERNATIVE EXAMINATIONS OR TESTS:
~~1) Periodic System Pressure tests.~~
~~2) Conduct Ultrasonic Examinations to the extent practical.~~
F. IMPLEMENTATION SCHEDULE:
Second Inservice Inspection Interval August 8, 1993 to August 08, 2003 G. ATTACHMENTS TO THE RELIEF:
~~1) Examination Coverage Table~~
~~2) Scan limitation figures.~~
Examination coverage Examination Area Beam Coverage Fig. Description of Limitations Identification Angle (cRv)
PZR spray Nozzle-to- 70% One Nozzles are mutually interfering, when other Upper head weld No. 60'0o side nozzle is directly opposite on scan line 103-601 PZR Safety Valve Nozzle- 80% one 1&2 Nozzles are mutually interfering, when other to-Upper Head Weld No. side nozzle is directly opposite on scan line 108.601-A 454 95% one side Page 121 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 3 Examination coverage Examination Area Beam Coverage Fig. Description of Limitations identification Angle (CRV)
PZR Safety Valve Nozzle-60'5o 70% one, 1&2 Nozzles are mutually interfering, when other to-Upper Head Weld No. side nozzle is directly opposite on scan line 108-601-B 85% one side PZR Safety Valve Nozzle-60'5o 70% one 182 Nozzles are mutually interfering, when other to-Upper Head Weld No. side nozzle Is directly opposite on scan line 108-601 95% one side PZR Safety Valve Nozzle- 60o 80% one Nozzles aro mutually interfering, when other to-Upper Head Weld No. side nozzle is directly opposite on scan line 108401-D PZR Surge line Nozzle 600 60% one Scan obstructed by ten Heater attachments.
Weld NO. side 105-651 45o 100% one side Page 122 of 272
NOTE: SCAN PATH OF EACH NOZZLE ARE NOTED BY DOTTED LINES.
SCAN PATH 8" FROM WELD Q PER NDE 5.1 (FOR 45 )
NOZZLE NELDS ON THE TOP OF PRESSURIZER, ZONE-5 AREAS WHERE DOTTED UNES INTERSECT NOZZLES SHOW SCAN LIMITATIONS 180 LUG 108-601-A
/
/
40 108-601-B I
ji I
m4.0".
4"
~X r 1 X-106 601 C
~L.~~
90'ANWAY ~i g/
< 8 1/.-
/
108-601-D M 10 3/4" L LUG 270ELD NO. I03-601, 108-601-A, 108-601-B, 108-601-C AND 108-601-0 45'EXAM SCAN OBSTRUCTIONS FIGURE 3.1
NOZZLE WELDS ON THE TOP OF PRESSURIZER, ZONE-5 NOTE: SCAN PATH OF EACH NOZZLE IS SHOWN BY DOT1ED UNES, SCAN PATH ~ 12" FROM Q (FOR 0'-60')
AREAS WHERE DOTTED UNES INTERSECT NOZZLES SHOW SCAN UMITATIONS LUG
/ ~ 108-601-A ri7 3/4" 180'0'ANV/AY o / 108-601-C p Z.'/4'I 270
/
I 7 /
1/4" ~ ~ /
8 1/+" /'
I
+W 108-601-D ~ /
10 3/4" LUG 00 WELD NO. 103-601, 108-601-A, 108-601-B, 108-601-C AND 108-601-D 60'EXAM SCAN LIMITATIONS FIGURE 3.2
SCAN PATH LIMITED BY TEN (10)
PRESSURIZER HEATER PENETRATIONS.
AFFECTS 60 SCAN ONLY.
SCAN PATH 12'RESSURIZER BOTTOM HEAD A-1 9"
160'-4 C-I 11.5" B-I 90'10-270'-2 10' 11.5 11.5" C-2 C-3 9"
04
+A-3 WELD NO.
105-651 12 DIA. TYP.
WELD NO. 105-65I 60'CAN OBSTRUC'nONS'GURE 3.3
ST. LUCIE UNIT 2 SECOND /NSPECTION INTERVAL RELIEF REQUEST NUMBER 4 A. COMPONENT IDENTIFICAT/ON:
Class: 1AND 2 Identification of components: Longitudina/ Welds Description of components: Intersecting Longitudinal We/ds of Selected Circumfereri tia/ Welds B. EXAMINATIONREQUIREMENTS:
EXAMINATION EXAMINATION EXAMINATION CATEGORY ITEM NUMBER DESCRIPTION B-J B9.12 Nominal Pipe Size 4.0 inch or Greater.
B9.22 Nominal Pipe Size c 4.0 inch.
C-F-1 C5.12 > 3/8 inch Nomina/ Wall Thickness for Piping > NPS 4.0inch.
C5.22 > 1/5 inch Nominal Wall Thickness for piping > NPS 2.0inch and ( NPS 4.0 inch.
C5.42 Branch Piping > 2.0 inch C-F-2 C5.52 Longifudinal Welds > 3/8 inch Nominal Wall Thickness for Piping > 4.0 inch C5.62 > 1/5 inch Nominal Wall Thickness for piping > NPS 2.0 inch and < NPS 4.0 inch.
C5.82 Branch Piping > 2.0 inch C. RELIEF REQUESTED:
Relief is requested from fhe additional ASME Code Required Surface Examinafion requirements for fhe following:
Class 1 to include at least a pipe-diameter length but no more than 12 inch of each longitudinal welds infersecting the circumferential welds required to be examined by Examination Categories B-F and B-J.
Page 126 of 232
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 4
~~2. Class 2 to include 2.5 t at the intersecting circumferential weld required to be examined under Examination Categories C-F-1 and C-F-2.~~
D. BASIS FOR RELIEF:
Longitudinal welds are fabricated during original manufacturing under controlled shop conditions, which. produce higher quality and more uniform residual stress patterns.
~~2. Longitudinal piping welds undergo heat treatment in the shop, which enhances fhe material properties of the weld and reduces the residual stresses created by welding.~~
3. For Austenitic stainless steel piping, the intergranular stress corrosion cracking (IGSCC) problem, or for that matter any stress corrosion problem, has not occurred to any significant extent in PWR piping, due to fhe nonoxygenafed environment, nor to carbon steel piping in PWR's.
4. Results of previous weld inspections through out the indust indicates that longitudinal welds have not been a safety concern, nor has there been any evidence of longitudinal weld defects compromising safety at nuclear power plants.
~~5. Longitudinal welds have not been shown to be susceptible to any particular degradation mechanism.~~
6. The only areas of a longitudinal weld which may be considered suspect are the ends of the weld where it is adjacent to the field fabricated circumferential welds. These areas fall within the volumetric examination boundaries of the adjacent circumferential welds.
7. The man-rem exposure and cost associated with the inspection of longitudinal welds is dependent on the time it would take to removefreinstall insulation and interferences, locate fhe weld, prepare the weld for examination and perform the examination.
Page 127 of 232
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 4 The volumetric and surface examination costs and man-rem for the selected Class 1 and Class 2 longitudinal welds are estimated to cost $34,496.00, and 25 man-rem for the second inspection interval.
8. Based on the above arguments, there is little, if any, technical benefit to performing inservice inspections on longitudinal piping welds. In addition, there are substantial radiationexposure and cost considerations associated with these inspections.
E. ALTERNATIVE EXAMINATIONS OR TESTS:
FPL proposes to eliminate the examination requirements for surface examination on Class 1 and 2 longitudinal piping welds beyond those inspections which are required for the adjacent circumferential weld.
FPL also proposes to enhance the volumetric examinations at the intersection point of circumferential and longitudinal welds by including both transverse and para/lel scans within fhe length of longitudinal weld which falls within the circumferential weld examination volume.
Circumferential welds with intersecting longitudinal welds willbe noted to document the extent of the examination.
The extent of volumetric examinations performed coupled with the system pressure tests provides assurance of an acceptable level of quality and safety.
F. IMPLEMENTATION SCHEDULE:
Second Inservice Inspection Interval August 8, 1993 to August 8, 2003 G. ATTACHMENTS TO THE RELIEF:
None Page 128 of 232
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 5 A. COMPONENT IDENTIFICATION:
Class: 1 Reactor Coolant Pump Suction and Discharge Safe end to pipe welds.
Pressure Retaining Dissimilar Metal Welds, Pressure 'retaining welds in Piping.
B. EXAMINATION REQUIREMENTS:
EXAM ITEM NO. EXAMINATION REQUIREMENTS CAT.
BJ B9.1 1 Essentially 100% volumetric and surface examination of Circumferential welds for >4" nominal pipe size.
B-F B5.130 Essentially 100% volumetric and surface examination of nozzle-t~afe end butt welds NPS 4 or larger.
C. RELIEF REQUESTED:
Relief is requested from the ASME Boiler and Pressure Vessel Code required volume as identified in Figure IWB-2500-8.
D. BASIS FOR RELIEF:
Configuration and permanent attachments prohibit 100% ultrasonic examination coverage of the required examination volume. Additional ultrasonic techniques are employed, where practical, to achieve the Code required volume. The attached Table summarizes the percent of coverage achieved and reference specific Figures included within the request identifying typical configurations Both the pump casing and the safe-end are fabricated from SA-351-CFSM material, which is centrifugally cast stainless steel. This material consists of relatively large grains in columnar structures that are aligned radially.
Page 129 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 5 INLET The geometry of the welds varies considerably. Figure 1 illustrates the inlet safe-end configuration in that the wall thickness of the elbow is 6/40" thicker than the safe-end. Thus, the elbow-to-safe-end weld tapers down to the safe-end, and within a short distance another taper is caused by the joining of the safe-end to the pump. The configuration of the safe-end weld conditions provide essentially no access limitations on the shop weld from the elbow side, but are significantly more prohibitive from the safe-end side including the surface conditions on the field weld. Most of the OD surface is not sufficiently flat to permit adequate search unit contact.
The taper is often so steep that the ultrasonic beam either changes to an ineffective angle or misses the area of interest entirely. The transition between weld taper and flat base material is so abrupt that search unit liftoffoccurs, causing substantial gaps in the beam coverage.
OUTLET The outlet safe-end configuration Figure 2 tapers gently upward from the pipe to the safe-end and further into the pump casing which is of an even greater thickness. The geometric configuration poses no significant access limitation except for the safe-end to pump field weld where beam interrogation is possible from one side only.
SUPPLEMENTARY TECHNIQUE FPL has employed a full scale mock-up in lieu of the standard code calibration block. The mock-up was constructed of identical material with a duplication of the construction field weld and a duplication of the shop weld welding parameters considered necessary for this application. (See Figure 3)
This mock-up is considered invaluable toward the understanding and the qualification of acoustical interfaces that could cause beam scatter, beam redirection, mode conversion and verification of sound beam penetration.
The mock-up design accommodates a calibration from the carbon steel side to be used for the shop weld and a calibration from the safe-end material to be utilized for field weld examinations.
Page 130 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 5 The examination technique essentially complies with the provisions of Section XI. The shape and slope of the distance amplitude curve (DAC) is established using side drilled holes while examination sensitivity is established by ID notch (10%) response.
Inside (ID) diameter reflector detection ability is enhanced by increasing the beam impingement angle. Figure 3A and 3B provides illustration of impingement angle for axial and circumferential scan calibration.
The extent of examination volume achieved ultrasonically and the alternate scans performed (see Examination Coverage Table) coupled with the system pressure tests provide assurance of an acceptable level of quality and safety.
E. ALTERNATIVE EXAMINATIONS OR TESTS:
~~1) Surface examination per categories B-F and B-J.~~
~~2) Ultrasonic examinations will be performed to the maximum extent possible by the employment of a full scale mock-up in lieu of the standard calibration block.~~
~~3) Periodic system pressure tests.~~
F. IMPLEMENTATION SCHEDULE:
Second Inservice Inspection Interval August 8, 1993 to August 08, 2003 G. ATTACHMENTS TO THE RELIEF:
~~1) Examination Coverage Table~~
~~2) Typical limitation figures.~~
~~3) RR-5 attachment ultrasonic examination technique and preservice inspection results.~~
Page 131 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 5 Examination Coverage Examination Area 'eam Coverage Fig. Description of Limitations Identification Angle (CRV) 2A2 Inlet Field from Examination limited by Weld Safe end to Safe End configuration.
Pump weld No. 0% from RC-115K Pump side 2A2 RCP Inlet 100% Examination limited by shop weld Elbow- from configuration.
to-safe end weld Elbow Number 0% from RC-115-1501-771-A safe end 2A2 RCP Outlet 45'5'5'5'5'6'0%
100% Examination limited by Field weld, Safe from pipe configuration.
end to Pipe weld 30% from Number safe end RC-116-701-771 2B1 RCP Inlet. 100% Examination limited by shop weld elbow- from configuration.
to-safe end weld Elbow No. 0% from RC-1 16-1 501-771-B safe end 2B1 RCP Outlet 100o Examination limited by Field weld, Safe from configuration.
end to Pipe weld Elbow No. 0% from RC-121-5 safe end 2B1 RCP Outlet l 2 Examination limited by Shop weld, Safe Pipe 00'rom configuration.
end to Pipe weld and Safe No. end RC-1 21-901-771 Page 132 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 5 Examination Coverage Examination Area Beam Fig. Description of Limitations Identification Angle (CRV) 2A1 RCP Inlet 100% Examination limited by whop weld Elbow- from configuration.
to-safe end weld elbow no. 45'5'5'5'overage 20% from RC-112-1 501-771-C safe end 2A1 RCP Outlet 100% Examination limited by Shop weld, Safe from Pipe configuration.
end to Pipe weld and Safe No. end RC-112-1 066-771 2B2 RCP Inlet 100% Examination limited by shop weld Elbow- from configuration.
to-safe end weld Elbow No. 0% from RC-124-1 501-771-D safe end 2B2 RCP Inlet 100% Examination limited by Shop weld safe from pipe configuration.
end to Pipe weld 30% from No. safe end RC-124-1 301-771 Page 133 of 272
INLET CONFIGURATION RGURE 1 8-2 B-1
~ICAL A-1 INCONEL CONTOURS BU TTERING
(
/
I I
I l I l l I I l I I l I I
( I I
l 'l I ( I I SA-351 ELBOW l SHOP WELD / FIELD WELD I
/ l I CFBM l l 3OS I SA-351 l ss l I I CFBM \ 'l I INCONEL l I l / \ I I
\ I (
SAFE ENO / I PUMP I ( 'l I ( I SAFE
\ SA-351 I END CFBM (
l I I I
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l \ I ( I I
l I I I I r
I
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7 3.
1 I(-
I I
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CLAD SUBJECT OF REUEF REQUEST NO. 5
OUTLET CONF'IGURATION FIGURE 2 FIELD /
PUMP VELD SHOP CASING / VELD PIPE SAFE
)
SUBJECT OF'ELIEF REQUEST 5
0 IC
FULL SCALE MOCK-UP F'IGURE 3 308 SA-516 INCONEL VELD VELD i GR 70 l~00 SA-351 CFSM
~ o o
SA-351 CFSM g o CIRCUMFRENTIAL AXIAL SCAN SCAN CALIBRATION CALIBRATION IMP INGMENT 40 IMP INGMENT POOR
~~RESPONSE~~
~~INCIDENT 40 40 INCIDENT GOOD~~
~~RESPONSE~~
SUBJECT OF'ELIEF REQUEST 5
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 5 NUCLEAR ENGINEERING DEPARTMENT EQUIPMENT, SUPPORT AND INSPECTIONS GROUP P.O. BOX 14000 JUNO BEACH, FLORIDA 33408 St. Lucie Nuclear Power Plant Unit 2 SECOND INSERVICE INSPECTION INTERVAL ULTRASONIC EXAMINATIONTECHNIQUE AND RESULTS FROM PRESERVICE INSPECTION OF REACTOR COOLANT PUMP SAFE END WELDS Prepared by Florida Power and Light Company Code Programs Section For St. Lucie Nuclear Power Plant 10 Miles South of Ft. Pierce on AlA Ft. Pierce, Florida 33034 Commercial Service Date: August 8, 1983 NRC Docket Number: 50-389 Document Number: RR-5 Revision Number: Date: July 24, 1993
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL
.RELIEF REQUEST NUMBER 5 1.0 EXAMINATIONITEMS I
Each Reactor Coolant. Pump Safe End area consists of two welds;,Pump-to-Safe End and Safe End-to-Pipe or Elbow (as applicable). Figure 1 shows the weld materials, geometry and the adjacent components. Each Pump has an Outlet Safe End and an Inlet Safe End.
Both the Pump Casing and the Safe End are fabricated from SA 351 CF8M material, which is centrifugally cast stainless steel. This material consists of relatively large grains in columnar structure that are aligned radially. The piping connected to the Outlet Safe End consists of a carbon steel (SA-516 Grade 70) pipe with 304 stainless roll bonded claddi~!g on the interior. The pump inlet divers in that an elbow exists on the pipe side.
Although the elbow is fabricatedPom pipe material, it is thicker, 3.6inches as opposed to 2.8 inches for the straight pipe. All other fabrication parameters are essentially the
'ame.
The geometry of the completed weld varies considerably. The Outlet Safe End.
configuratio tapers gently upward Pom the pipe (2.8 inches thick) to the Safe End (3.2 inches thick) and further into the pump casing which is of an even greater thickness. The Inlet Safe End'divers in that the wall thickness of the elbows is 6/10 inches thicker than the Safe End. Thus, the Elbow-to-Safe End Weld tapers down to the Safe End, and within a short distance another taper is caused by thejoining of the Safe End to the pump. (See Figure 1).
2.0 EXAMINATIONACCESS 2.1 RCP INLET SAFE END WELDS (SHOP AND FIELD)
The geometric conflguration of the Safe End Weld conditions provide essentially no access limitations on the examinations of the shop welds from the elbow side, but are significantly more prohibitive from the safe end side including the surface conditions on the field weld. (See Figure 1)
The geometric configuration of the Safe End welds have significant access limitations on the examinations of the field weldsPom the Safe End side, and are-essentially prohibitive from the pump side.
Most of the outside (OD) diameter surfaces is not sufficientl flat to permit adequate search unit contact. The taper is often so steep that the ultrasonic beam either changes to an ineffective angle or misses the area ofinterest entirely. The Page 138 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 5 transition between weld taper and flat base material is-so abrupt that search'unit liPoffoccurs, causing substantial. gaps in beam coverage. The two welds are so close together that limited space frequently exists in between for the required search unit positioning.
2.2 RCP OUTLET SAFE END WELDS (SHOP AND FIELD)
The geometric configuration poses no significant access limitation except for the Safe End-to-Pump field weld where beam interrogation is possible Pom only one side (see Figure 2). The beam focus range is sufficientl wide to accommodate the mild taper upward with respect to scan direction, inside (!D) diam ter reflector detection ability is enhanced by increasing the beam impngement angle. (See Figure 3A AND 3B) 3.0 SUPPLEMENTARY ULTRASONIC TECHNIQUE - FULL SCALE MOCK-UP Considering the variety of materials employed in the weldjoints (Figure 1), a full scale mock-up was deemed necessary in lieu of the Code calibration block (see Figure 3). The mock-up is constructed ofidentical materials with a duplication ofas much ofthe welding parameters as possible. The benefits of the mock-up are twofold:
3.1 There are six distinct acoustical interferences that will cause beam scatter, beam redirection and mode conversion. A mock-up is invaluable toward the understanding and the quantification of such phenomena, and verij7cation of sound beam penetration; 3.2 The original calibration block, although fabricated from Safe End material was not acoustically similar to the actual weld area. A welded mock-up essentially duplicates all parameters, particularly heat input.
The mock-up design accommodates a calibration from the carbon steel side to be used for the shop weld examination and a calibration from Safe End material to be utilized forfield weld examinations (see Figure 3).
The examination technique is substantially in compliance with the provisions of ASME Section XI, Appendix III, Supplement 7. The shape and slop ofthe distance amplitude curve (DAC) is established using side drilled holes while examination sensitivity is established by the inside (ID) diameter notch (10%) response.
Page 139 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 5 4.0 ULTRASONIC EX4MINATIONPERFORMANCE
.Examination calibration consists of a triple distance amplitude correction (DAC) .to effectively accommodate all conceivable examination conditions (see Figure 3).
4.1 FIRST CALIBRATION The first calibration comprises contact on the carbon steel surface with the'sound beam aimed toward side drilled holes aligned in the centerline of the inconel weld. The response from these three holes are used to establish the shape and slope of the DAC. The search unit is then positioned to mmimize a response from the inside (ID) diameter notch located in the Safe End (beam passing through the inconel weld). This response, ideally, should be adjusted to the level of the DAC; however, the notch yields only a 20% full screen height (FSH) signal. At that cathode ray tube (CRT) distance, the DAC level would be about zero..Since DAC points below 20% FSH are of little value, the notch response is simply marked, as is, without a sensitivity adjustment.
4.2 'ECOND CALIBRATION The second calibration comprises search unit contact on the opposite end of the block with the sound beam aimed at the side drilled holes aligned parallel with and adjacent to the 308 stainless weld. This calibration establishes the shape and slope of the DAC through SA 351 CF8M Safe End material. In this case, the notch signal is "gained-up" (+ 6 db) to meet the DAC level.
4.3 THIRD CALIBRATION The third calibration is performed in the same manner but in this case the search unit is rotated 180 degrees to aim at the same holes with the sound bea'm passing through the 308 stainless weld prior to impinging, on the. holes. This is performed to determine the extent of acoustic difference, ifany.
Scanning is performed on the carbon steel side at twice the calibration sensitivity.
Scanning on the austenitic materials utilizes the straight 351 material calibration as this is the. more sensitive of the two. Material noise levels prevent the usual double sensitivity (+- 6 db); scan speed is reduced accordingly.
Page 540 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 5
~~5.0 BACKGROUND~~
The centrrJr cally cast stainless Safe End material is renowned, within the industry for it'.
~
high acoustic impedance. Consultations with Combustion Engineering, Southwest Research Institute and Nuclear Energy Services confrrmed that the "State of the Art" techniques involved the, use of special search units. Florida Power and Light Nondestructive Examination (NDE) stag evaluated four diferent search units designed for, this application and retained for use that which exhibited the superior performance.
Industry research has shown that refracted longitudinal wave interrogation of cast stainless structure achieves the greatest penetration. Further, beam incident angles are limited to the 40 to 45 degree range.
The search unit is contoured to enhance the beam focus. Additional contouring is not a viable option because the conical weld surfaces areinsu+ciently uniform (the surfaces have been smoothed by hand grinding). We cannot utilize other examination angles for the technical reasons cited earlier. We cannot miniaturize the search unit because the low (1.0 Mhz) examinationPequency ~ould cause deleterious beam divergence and smaller search units do not provide suilr cient power to penetrate the materials..
6.0
~~SUMMARY~~
OF EX4MINATIONVOLUME ACHIEVED (PRESERVICE)
SAFE END WE'D SHOP WEM* SHOP WELD* FIELD FIELD ELBOW SIDE SAFE END WELD**
. SIDE SAFE END PUMP SIDE SIDE A-1 INLET 10'0 . 20 30 30 A-2 INLET 100 20 B-1 INLET 100 10 Page 441 of 272
ST. LUCIE UNIT 2 INSPECTION INTERVAL 'ECOND RELIEF REQUEST NUMBER 6 SAFE END WELD SHOP TED* SHOP WE'D* FIELD FIELD PIPE SIDE SAFE END WELD** WELD**
WELD SAFE END PUMP SIDE SIDE B-2 INLET 100 10 A-1 OUTLET 100 100 100 A-2 OUTLET 100 30 50 B-1 OUTLET 100 100 100 B-2 OUTLET 100 30 50 Includes examination Pom Field Weld surface, where possible Includes examination from Shop Weld surface, where possible a
Page 142 of 272
0 0
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 6 7.0 CONFIGURA.TION PROFILES The actual achievable examination coverage of the lower one-third volume of the Safe End welds is illustrated by a sectional view as viewed along the weld axis with the volume coverage achieved consistent with the configuration profile at that location.
Further, the actual examination coverage achieved by sound transmission through the Safe End welds is illustrated by a cross-sectional of each weld consistent with the configuration profile at that location as illustrated by sketches.
Examination Coverage Examination Area Beam Fig. Description of Limitations Identification Angle (CRV) 2A2 Inlet Field 20% from 1 Examination limited by Weld Safe end to Safe End 3 confi guration.
Pump weld No. RC- 0% Pom RC-115-4 45'5'5'overage Pump side 5 6
7 8
9 10 configuration.
2A2 RCP Inlet shop 100% from 2 Examination limited by weld Elbow-to-safe Elbow 3 end weld no. 0% from 4 RC-115-1501-771-A safe end 5 6
7 8
9 configuration.
10 2A2 RCP Outlet 100% Pom ll Examination limited by Field weld, Safe pipe 30 % 12 end to Pipe weld Pom safe 13 No. end 14 RC-1 15-701-771 15 Page 143 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 5 Examination Coverage Examination Area Beam Coverage Fig. Description of Limitations Identification Angle (CRV) 2BI RCP Inlet shop from 16 Examination limited by weld Elbow-to-safe Elbow 17 "
confi guration.
end weld No. 0% from 18 RC-115-1501-771-B safe end 19 20 21 22 23 24 2B1 RCP Outlet 100% Pom 25 Examination limited by Field weld, Safe 45'5'5'5'5'00%
Elbow 26 confi guration.
end to Pipe weld 0% from 27 No. safe end 28 RC-121-5 29 2B1 RCP Outlet 100% from 27 Examination limited by Shop weld, Safe end Pipe and 28 configuration.
to Pipe weld No. Safe end 29 RC-121-901-771 2Al RCP Inlet shop 100% from 30 Examination limited by weld Elbow-to-safe elbow 31 configuration.
end weld no. 20% from 32 RC-1 12-1501-771-C safe end 33 34 35 36 37 2AI RCP Outlet 100% from 38 Examination limited by Shop weld, Safe end Pipe and 39 configuration.
to Pipe weld No. Safe end 40 RC-112-1066-771 Page 144 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 5 Examination Coverage Examination Area Beam Fig. Description of Limitations Identification Angle (CRV) 2B2 RCP Inlet shop 45'5'overage 100% from 41 Examination limited by weld Elbow-to-safe Elbow 42 configuration.
end weld no. 0% from 43 RC-124-1501-771-D safe end 44 45 46 47 48 49 2B2 RCP Inlet Shop 100% from 50 Examination limited by weld safe end to pipe 30 % 51 'onfiguration.
Pipe weld No. from safe 52 RC-124-1301-771 end 53 54 Page 145 of 272
PARTIAL COVERAGE FROM SAFE END SIDE OO 375' 5%
/
/ CODE VOLUME
/
/
/
I l
I t
1
\
/
/
/
/
//
/
r 225'35'ELD NO. RC-115-4 RCP 2A2 INLET FlELD WELD, EXTENT OF EXAMINATION-SECTIONALVIEW FIGURE 5.1
FULL COVERAGE FROM ELBOW SIDE 0'75'5'ODE VOLUME ID OD 90'25'35
'80 WELD hl0. 1501-771-A RCP 2A2 INLET SHOP WELD, EXTENT OF EXAMINATION-SECTICNALVIEW FIGURE 5.2
SCAN LlhUT I I
I I
I I
\ -I I I
\ \ I I '! I
\ I
\ I '! I I I ELBOW SHOP WELD SAFE ENO '!
FIELD WELD PUMP
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WELD NO. RC-115-0 AND 1501-771-A RCP 2A2 INLET SAFE END WELDS, PRORLE AND EXTENT OF COVERAGE AT 000 FIGURE 5.3
SCAN LLIIT I
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I I
I l l I l
l l I I
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\ I \ I I I I I 'l ELBOW SHOP WELD I ENO 1 FIELD WELD PUMP I \ I
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'AELD NO. RC-115-4 AND 1501-771-A RCP 2A2 INLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT 045'IGURE 5.4
SCAN LIMIT I
I I
I I
I l I l I I I I I '1 I I I I ELBOW SHOP WELD I SAFE END FIELD WELD PUMP l
l I I I \ I I I \ I I I \ I l I I l I I l I l I 'l I l
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EXAMINATION COVERAGE (CUT AWAY VIEW)
W'ELD NO. RC-115-4 AND 1501-771-A RCP 2A2 INLET SAFE END WELDS. PRORLE AND EXTENT OF COVERAGE AT 090'IGURE 5.5
SCAN LIMIT TYPICAL CONTOURS INLET 1
I I I I
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ELBOW 0 SHOP 'hELD I SAFE END
'1 FIELD VELD I PUMP CASING SA-351 308 SA-351 1
INCONEL I SA-351 CFBM SS CF8M 1 'IELD I CFUM WELD I o 1 I
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CLAD WELD NO. RC-115-4 AND 1501-771-A RCP 2A2 INLET SAFE END TELOS. PROFILE AND EXTENT OF COVERAGE AT 135'IGURE 5.6
SCAN UMIT l
l I I I \
/- I I I \ I l I 'l I ELBOW SHOP WELD SAFE END flELD VELD I PUMP l I l I l I I l I
\ I / I I I l I l I I f I I \
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I WELD NO. RC-115-4 AND 1501-771-A RCP 2A2 INLET SAFE END TELOS, PROflLE AND EXTENT OF COVERAGE AT 180'IGURE 5.7
SCAN UNIT I
l \ I l I I I I I I ELBOW 'l SHOP BELD I
SAFE ENO l I PUMP I
I l f I I l I I l I I I I f l I l I I I I I l I I l I l I l I I I-I I
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VIELD NO. RC-115-4 ANO 1501-771-A RCP 2A2 INLET SAFE ENO TELOS, PROFILE AND EXTENT OF COVERAGE AT 225'IGURE 5.8
SCAN LIMIT I
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WELD NO. RC-115-0 AND 1501-771-A RCP 2A2 INLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT 270'lGURE 5.9
SCAN UMIT I
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I l I
\ I
\ \ I l I l I
'l SHOP WELD I \ I ELBOW I SAFE END RELD WELD PUMP l l I I I 'l I I I I I 'l I I 'l I
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VELD NO. RC-115-4 AND 1501-771-A RCP 2A2 INLET SAFE END WELDS, PRORLE AND EXTENT OF COVERAGE AT 315'IGURE 5.10
ESSENTIALLY 1007+ ACHIEVED FROM PIPE SIDE 305 ACHIEVED FROM SAFE END SIDE 04 45 270'D CODE VOLUME 225'35'80'ELD NO. 701-771 RCP 2A2 INLET SHOP WELD, EXTENT OF'XAMINATION-SECTIONALVIEW FIGURE 5.1'I
SCAN LIMIT LILIITEO SCAN I AREA I I
\ I l l I I I I I I l I ( PUMP PIPE OP WELD SAFE END FIELD WELD l ( I
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WELD NO. 115-5 AND 701-771 RCP 2A2 OUTLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT 030'IGURE 5.12
TYPICAL CONTOURS OUTLET I
SCAN UMIT I I
I
\ I 1 I I
\ I I \ I I I I PIPE SHOP WELD I SAFE 0 FIELD WELD I PUMP CASING SA-51 6 308 I INCONEL I SA-351 GR-70 SA-351 WELD CFSM CFBM \ I WELD I
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304 SS ROLL BONDED WELD NO. 115-5 AND 701-771 RCP 2A2 OUTLET SAFE END WELDS. PROFILE AND EXTENT OF COVERAGE AT 060'GURE 5.13
SCAN LIMIT
, LIMITED SCAN I I
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WELD NO. 115-5 AND 701-771 RCP 2A2 OUTLET SAFE END WELDS. PROFILE AND EXTENT OF COVERAGE AT 160 FIGURE 5.14
I SCAN UMIT I I
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I 1' I I \ I 1 1 I I I PIPE SHOP WELD FIELD WELD I PUMP
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WELD NO. 115-5 AND 701-771 RCP 2A2 OUTLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT 285 FIGURE 5.15
FULL COVERAGE ACHIEVED FROM ELBOW SIDE PARTIAL (180') COVERAGE ACHIEVED FROM SAFE END SIDE 04 375 <5 CCOE VOLUME 270 ID OD 90'25
'35'80'ELD NO. 1501-771-B RCP 281 INLET SHOP WELD, EXTENT OF EXAMINATION-SECTIONALVIEW FIGURE 5.16
SCAN LIMIT SCAN LIMIT I
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\ I SHOP WELD
\ I I l I I I SAFE END FIELD WELD I PUMP I I I I I I I 'l I I I I l I I I l
l
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WELD NO. 1501-771-B AND 121-4 RCP 2B1 INLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT 000 F1GURE 5.17
SCAN LILIIT I
l I
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'l l I l l I l J g I I 'I I I I ELBOW SHOP WELD / SAFE END FIELD WELD PUMP l
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WELD NO. 1501-771-B AND 121-4 RCP 2B1 IIILET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT 045'IGURE 5.18
SCAN LIMIT I
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I
'l I
I I I l I I l I I I ELBOW 1 SHOP WELD I AFE END F LD WELD I PUMP I I I I
\ I I I
\ I I I I 'I I l I 'l I l I I I
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WELD NO. 1501-771-8 AND 121-4 RCP 281 INLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT O90 FIGURE 5.19
I I
I I
I I
I l I I
I I I I
\ I I ELBOW SHOP WELD I I PUMP SAFE END
'l I I I I I
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WELD NO. 1501-771-8 AND 121-4 RCP 2B1 INLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT 135'IGURE 5.20
SCAN LIMIT I I
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\ I I 1 1 I
l I I \ I I I l l I ELBOW SHOP WELD SAFE ENO FIELD WELD PUMP I
l I l I I '! I l I I \ I I I \
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WELD NO. 1501-771-8 AND 121-4 RCP 281 INLET SaFE ENO WELDS, PROFILE ANO EXTENT OF COVERAGE AT 180'IGURE 5.21
I I
I I
I
'l I
'l l I l \ l I
\ 'l I I l I
'I I I ELBOW SHOP WELD I SAFE END FIELD WELD I PUMP l I I I l I I
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\ I I I I I I I I
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I I I
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WELD NO. 1501-771-8 AND 121-4 RCP 281 INLET SAFE ENO WELDS, PROFILE AND EXTENT OF COVERAGE AT 225'IGURE 5.22
I I
SCAN UMIT I
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1 1 I r
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I I I I I I
\ I I I EL80W SAFE END FIELD WELD I PUMP 1 1 SHOP WELD I 1 1 I I I
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WELD NO. 1501-771-8 AND 121-4 RCP 281 INLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT 270'IGURE 5.23
SCAN UMIT I
I UMISSO SCAN l
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l I
\ I I
l I l f I I
'l I I ELBOVl SH0 AFE END FIELD Vt'ELD PUMP FIELD I I I
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I
'l I
/
IAELD NO. 1501-771-B AND 121-4 RCP 2B1 INLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT 315'GURE 5.24
ESSENTIALLY 100K COVERAGE FROM SAFE END SIDE p4 375
'5'ODE VOLUME ID 225'35 180'hELD NO. RC-121-5 RCP 2B1 OUTLET FIELD WELD, EXTENT OF EXAMINATION-SECTIONAI. VIEW FIGURE 5,25
ESSENTIALLY 100K COVERAGE FROM BOTH SIDE 0'" WIDE BAND,OF RESTRICTED SCAN OUE TO NOEZLE IN SCAN PATH APPUCABLE TO CARBON SIDE ONLY.
375 45 CODE VOLUME 270 ID 90'25'80 WELD NO. 90]-77I RCP 2BI OUTlET SHOP WELD, EXTENT Of EXAMINATION-SECTIONALVIEW FIGURE 5.26
SCAN ARC I
SCAN LIMIT I I
I
\ I l I l I I I I I l I PIPE l SHOP WELD I I END FIELD WELD I PUMP
( I I I I l I I I 1 I I I I I l I I \ I I l I I I I I I I
WELD NO. 121-5 AND 901-771 RCP 281 OUTLET SAFE END WELDS, PRORLE AND EXTENT OF COVERAGE AT 045 FIGURE 5.27
SCAN LIMIT I
SCAN LIMIT I I
I I
I l I
'I I I I l I I l I l I I PIPE l
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I I
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l I I I I I I I I l
'II WELD NO. 121-5 AND 901-771 RCP 2B1 OUlLET SAFE ENO WELDS, PROFILE AND EXTENT OF COVERAGE AT 180'IGURE 5.28
I SCAN LIMIT I I
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l
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l FIELD W'ELD
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I I
I I I I l I I I l I I
'I l I I
'l I
I I
'I WElD NO. 121-5 AND 901-771 RCP 281 OUTLET SAFE END WELDS, PRORLE AND EXTENT OF COVERAGE AT 270 FIGURE 5.29
WELD NO. 1501-771-C RCP 2A1 INLET SHOP WELD, EXTENT OF EXAMINATION-SECTIONALVIEW 0
375 45 CODE VOLUME ID 225'35 180 FULL COVERAGE ACHIEVED FROM ELBOW SIDE RGURE 5.30
SCAN UMIT
~g ppl SCAN UMIT gpss.
q5 I
GE I
l ~e<1' I
\ I I l I I
I I
\ I l \ I l I ELBOW SHOP WELD SAFE ENO l FIELD WELD PUMP I I I I I
\ l I I I
\
l I I
l I 'l I
\ I I
\ I l I I 'l
'l \ I I ~- I '(
l I l I
/ /
/ /
/ /
/ /
/ /
BOTTOM NOT ADEQUATELY COVERED OUE TO STEEP IMPINGEMENT ANGLE WELD NO. 1501-771-C AND 112-4 RCP 2A1 INLET SAFE END WELOS, PROFILE AND EXTENT OF COVERAGE AT 045 FIGURE 5.31
SCAN UMIT SCAII UMIT SURFACE INSUFFICIENIEY SMCCIN FCR SURFACING I
I
\
l l I f I f
'l l f f f l l I f '1 I f f f f f I ELBOV/ SHOP WELD SAFE END RELO LO PUMP f I l f f f l f f l I l f f I l l I I f l I f l f l f f \ f f f \
l \ I l I
-f" I
I
/ /
/ /
/ /
/ /
/ /
BOTTOM NOT ADEQUATELY COVEREO OUE TO STEEP IMPINGEMENT ANGLE WELD NO. 15D1-771-C AND 112-4 RCP 2AI INLET SAFE END WELDS, PRORLE AND EXTENT OF COVERAGE AT 090 FIGURE 5.32
SCAN UMIT SURFACE INSUFFICIENILY SMOOIN FOR SURFACING I
I l I
'l
\
r I I I I
\ I I I I I i I \ I
'I I I ELBOW SHOP %E SAFE ENO PUMP l g \
l I i '! I l I I I l j FI l I
'l I I I I \
I I I I l \ t I \ I l
I l I
/ /
/ /
/ /
/ /
/ /
BOTTOM NOT ADEQUATELY COVERED DUE TO STEEP IMPINGEMENT ANGLE WELD NO. 1501-771-C AND 112-4 RCP 2AI INLET SAFE DID WELOS, PROFILE AND EXTENT OF'OVERAGE AT 135 FIGURE 5.33
SCAN LIMIT SCAN UMIT I
I I
l i I I
\ I I I
\ l I I l I
'I I I i I
\ I \
I I I ELBOW SHOP Yic SAFE END PUMP
'l I
\ l I I I
\ l l l I I I
'l l I I I
\ I 'l I
\ \ I I l I I \ l l \ I I \ I I
I
/ /
/ /
/ /
/ /
/ /
ROOT NOT COVEREO DUE TO STEEP IMPINGEMENT ANGLE YiELD NO. 1501-771-C ANO 112-4 RCP 2Al INLET SAFE ENO WELOS, PROFILE ANO EXTENT OF COVERAGE AT 180 FIGURE 5.34
SCAN UMIT SCAN LIMIT SCAN UMIT I
I I
1 l I I I I 1 I I
\ I I I I I \ I 1
I ELBOW SHOP WELD SAFE ENO FIE WELD PUMP I I 1 1 I I I I I \ I 1 I I I I \ I l I I 1 I
'1 I I I I I l I I' I
I
/ /
/ /
/ /
/ /
/ /
ROOT NOT CDVEREO DUE TO STEEP IMPINGEMENT ANGLE WELD NO. 1501-771-C AND 112-4 RCP 2A1 INLET SAFE END WELOS. PROFILE AND EXTENT OF COVERAGE AT 225 FIGURE 5.35
SCAN UNIT SCAN UMIT I
I I
1 1 I I \ I
\ I I 1 I
1 I I '1 I
\ I I 1 I I I
'1 I I I ELBOW OP WELD SAFE END I PUMP 1 I 1 I \ I I I I I I 1 I
1 1 I I I 1
1 I
1 I I 1 I \ I 1 \ I I I WELD NO. 1501-771-C AND I12-4 RCP 2AI INLET SAFE END llELDS. PROFILE AND EXTENT OF COVERAGE AT 270 FlGURE 5.36
SCAN UMIT SCAN LIMIT I
I
\ I I I \
I I I
\ I
\ I I l I I \ I I I I l I I 'l I EL80V/ SH W'ELD SAFE END FIELD VELD I PUMP
\ l I I l I
'l \ I I I
\ I I \
I
'l I I l I I l I I
\ I
\
'I.'
I
/ /
/ /
/ /
/ /
//
WELD NO. 1501-771-C AND 112-4 RCP 2A1 INLET SAFE END llELDS. PROFILE AND EXTENT OF COVERAGE AT 315 FlGURE 5.37
'AELD NO. 1066-771 RCP 2A1 OUTLET SHOP WELD, EXTENT OF EXAMINATION-SECTIONALVIEW 0
CODE VOLUME 270 ID 90 OD 225 135 180 FULL COVERAGE ACHIEVED FROM BOTH SIDES RELIEF 5.38
SCAN UMIT I
I I
\
l I I l /
I I l I
'l / I 'l I
l / I 'l I
\ / I I
\ / I SAFE END
'l FIELD WELD I PIPE SHOP WELD PUMP l 'l
'l l I I l I I I /
\ I I
I
\ I I
'l I I I l / I 'l I
\ I I 'l l l / I WELD NO. 112-5 AND 1066-771 RCP 2Al OUTLET SAFE END WELDS. PROFILE AND EXTENT OF COVERAGE AT 110 RGURE 5.39
SCAN UMIT I SCAN UMIT I I
I I I 1 1 I I
'1 I
\
I I I
\
\ I I 1
\ I I PIPE SHOP WELD I I SAFE END FIELD WELD I PUMP 1 1 I I I 1
I I 1
I I \ I
\ I I \ I I I 1 I 1 I 1
1 I
'1
'1 1
1
/
WELD NO. 112-5 AND 1066-771 RCP 2Al OUTLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE 175'HROUGH 320 (TYPICAL)
FIGURE 5.40
VELD NO. 1501-771-D RCP 282 INLET SHOP WELD, EXTENT OF'XAMINATION-SECTIONALVIEW 375'5'ODE VOLUME ID 225'35'80'ULL COVERAGE. FROM ELBOW SIDE flGURE 5.41
SCAN UMIT I
I I
I I
\ I f
l I I \ I I
'l I PUMP SHOP LD I SAFE END FIELD WELD ELBOW l I I I I I \ I I I
'l I l I
'l
\ I l I l l I l \ I
\ I
\ I
\ I I
I l I I
l I IX X WELD NO. 1501-771-0 AND 124-2 RCP 2B2 INLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT 000 FIGURE 5.+2
SCAN LIMIT I
I I
I II l I l I I
'I g II I \
l I g ELBOW SHOP WELD / SAFE END FIELD WELD PUMP j
I g I l I l I
\ i i l I l
I l
\ t I
I 'l
\ g l i I I' l -= ~
\ ~ ~
'I I I I I I I I I l I l
I l
/
WELD NO. 1501-771-D AND 124-2 RCP 282 INLET SAFE END WELDS. PROFILE AND EXTENT OF COVERAGE AT 045 FIGURE 5.43
SCAN LIMIT I
SCAN UMIT l
I I I l I I '!
ELBOW l SHOP WELD SAFE END \ FIE WELD PUMP I
l I I I I \ I I l I I \ I
\ I I
\ I l I
'i I l I I I
' 'II I
I I
l I l I
\ I I
l
/X WELD NO. 1501-771-0 AND 124-2 RCP 282 INLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT 090 FIGURE 5.44
SCAN UMIT I
I I
I l I I
I I I
\ I I I I \ I
'I l I \
ELBOW l SHOP WELD I I . SAFE END FIELD WELD PUMP
\ \ I I 1 I
l I I f l l I I l I l l I I 'l I
'I l I I l I l I I l \
I I l
\ I I
\ I l I
\ I I
WELD NO. 1501-771-D AND 124-2 RCP 2B2 INLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT 135 FIGURE 5.45
SCAN UMIT SCAN UMIT I
I
\ I I
l I I I l I I I I I I l I I l I ELBOW SHOP WELD I SAFE END \ IELD WELD PUMP l I I 'l I I I I I I l I I l I l I I l I I
'I l l I l I I ~
I
'l I I
l I I
'l I I
\ I
/
WELD NO. 1501-771-D AND 124-2 RCP 2B2 INLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT 180 FIGURE 5.46
SCAN UMIT I
I I
l l I
\ l I l I I l I l I I l I I I
\ I I l I ELBOW SHOP WELD I I SAFE END l FIELD WELD I PUMP l I I l I l I I l I l I I I I I 'l I l I \ I I
l I I I I \ ~
I ~
I I
l I
'l I I
\
\ I
\ I
/
W'ELO NO. 1501-771-0 ANO 124-2 RCP 282 INLET SAFE ENO WELDS, PROFILE ANO EXTENT OF COVERAGE AT 270'IGURE 5.47
SCAN LLIIT I
I I
I l I I I 'l I I
I I I I I l I ELBOW SHOP WELD I I SAFE END 1 FIELD WELD I PUMP I \ I I I I I I l I I I 'l I I
I I I I
~ ~ ~ ---- ~ ~ ~ --- ~ I I
l I I
l I I
'l I I
'l I
/
WELD NO. 1501-771-D AND 124-2 RCP 2B2 INLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT 225 FlGURE 5.48
SCAN LIMIT I
I
'l l I l l I l I I I l \ I I l I
\ I I l I
'l l I I I ELBOW SHOP WELD SAFE END FIELD WELD I PUMP
'l \ I I \
'l \ I l I I l I I I l l I I 'l I I I I 1 I I l I
\ 'I I I 1 I I I
\ I I
l I l I I
I I
I WELD NO. 1501-771-D AND 124-2 RCP 282 INLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT 315 FIGURE 54S
WELD NO. 1301-771 RCP 282 OUTLET SHOP WELD. EXTENT OF EXAMINATION-SECTIONALVIEW 0
375 45 CODE VOLUME 270 ID 90 225 135 180 100Fe COVERAGE ACHIEVED FROM PIPE SIDE RGURE 5.50
I I
SCAN UMIT I
I I
SCAN AREA I
'l I
I
\ 1 I 1 '1 I I 1 I I \ I 1 1 I '1 I
PIPE SHOP WELD SAFE END \ FIELD WELD PUMP 1 I 1 I 1 I
1 I I 1 I
I \ I I I I 1 I I 1
'1 I I I I I
'1 '1 I I
I
~
I I
I I I I I I I
I I
WELD NO. 124-5 AND 1301-771 RCP 2B2 OUTLET SAFE END WELDS, PRORLE AND EXTENT OF COVERAGE AT 060 FIGURE 5.51
I I
I SCAN UMIT I
I j
I l l I l l I l l 'l I 'l I
l 'l I I l I PUMP PIPE SHOP 'OELD SAFE EI'ID FIELD YiELD l i l \ I \ J
'I I I 'l I
1 l I t \ I I I l I
\ l I I I
\ l I I
\ I \ I I l C I
I i
I I
I I
WElD NO. 124-5 AND 1301-771 RCP 2B2 OUTLET SAFE END YIELDS, PRORLE AND EXTENT OF COVERAGE AT 140 FIGURE 5.52
I I
SCAN UMIT I f
I I
1
(
\ I 1 I I I
\ \ I I l I 1 I I 1 I
PIPE SHOP W'ELD SAFE END \ FIELD WELD PUMP 1 I ( f 1 I I 1 I
I I I
\ I I 1 I
I I f
\ I I 1 I
'1 1 I I I 1 I I 1 I
I I I WELD NO. 124-5 AND 1301-771 RCP 2B2 OUTLET SAFE END WELDS, PRORLE AND EXTENT OF COVERAGE AT 160 F1GURE 5.53
I I
I I
SCAN UMIT I
I I
\ I l \ I I \ I l l l I l I PIPE SHOP WELD ENO l FIELD WELD PUMP l I I l \ I \ I l \ I l I
'l l I I \ I l I \ I l I I I I I \ I l \ I I I I I I I
I I
WELD NO. 124-5 ANO 1301-771 RCP 282 OUTLET SAFE END WELOS, PROFlLE ANO EXTENT OF COVERAGE AT 180 FIGURE 5.54
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 6 A. COMPONENT IDENTIFICATION:
Class: 1 Reactor Coolant and Safety Injection System Piping and Branch Connections Pressure retaining welds in piping B. EXAMINATION REQUIREMENTS:
EXAM ITEM NO. EXAMINATION REQUIREMENTS CAT.
B9.1 1 Essentially 100% volumetric and surface examination of Circumferential welds for >4" nominal pipe size.
B9.12 Essentially 100% volumetric and surface examination of Longitudinal weids for
>4" nominal pipe size.
BJ B9.31 Essentially 100% volumetric and surface examination of branch pipe connections NPS 4 or larger.
C. RELIEF REQUESTED:
Relief is requested from the ASME Boiler and Pressure Vessel Code required volume as identified in Figure IWB-2500-8 through 11, as applicable.
D. BASIS FOR RELIEF:
Configuration, permanent attachments and/or structural interferences prohibit 100% ultrasonic examination of Code required volume. Additional ultrasonic techniques are employed where practical to achieve the Code Required Volume. The attached Table summarizes the percent of coverage achieved and references specific Figures that shows the extent of the limitations.
The extent of examination volume achieved ultrasonically and the alternate scans performed (see Examination Coverage Tabte) coupled with the system pressure tests provide assurance of an acceptable level of quality and safety.
Page 200 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 6 E. ALTERNATIVE EXAMINATIONS OR TESTS:
~~1) Surface examination per category B-J.~~
~~2) Ultrasonic examinations will be performed to the maximum extent possible.~~
~~3) Period system pressure tests.~~
F. IMPLEMENTATION SCHEDULE:
Second Inservice Inspection Interval August 8, 1993 to August 08, 2003 G. ATTACHMENTS TO THE RELIEF:
~~1) Examination Coverage Table~~
~~2) Scan limitation figures.~~
Page 201 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 6 Table Examination Area Identification Beam Coverage Fig. Description of Limitations 60'xamination(CRV)
Angle Loop 2A Hot Leg, Elbow-to-inlet 100% Both welds from Scan limited from nozzle nozzle Extension piece (field pipe side side due to Nozzle OD weld) and Nozzle Extension 450 30% of shop weld from transition taper.
Piece-to-nozzle (shop weld) Weld Nozzle side Nos. Supplemental RC-1 23-201-258 Both sides B Hot Leg to Shutdown Cooling 450 one side only NA One side only due to Branch connection Weld No. 60'00% configuration RC-123-205-771 Supplemental Page 202 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 6 Table Loop 2A2 Intermediate Cold leg 45'0'xamination 100% both welds from Scan limited from nozzle Steam Generator Nozzle-to- pipe side side due to nozzle OD extension (shop weld) and 98% of field weld from transition taper.
Extension-to-Elbow (field weld) Nozzle side Weld Nos. 0% of shop weld from RC-115-1 nozzle side RC-1 15-401-258-B Supplemental both sides Loop 2A2 Intermediate Cold leg 33% Scan limited to a length of Longitudinal Seam No. 4" due to pipe support.
RC-115-1 09-722-LS-A 45'5'A RCS Loop A 2A2 RCP to Reactor 93% Longitudinal seam Vessel Longitudinal Seam Weld 45'C 90% obstructed by welded No. attachment (lugs) on weld RC-115-1 03-722-LS-A centerline.
RCS Loop B 2B1 RCP to Reactor 45oA 59% Longitudinal seam Vessel Longitudinal Seam Weld 45'C 59 obstructed by welded No. attachment (lug), on weld RC-1 21-1 03-722-A and bumper attached to sleeve at biological shield penetration.
Page 203 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 6 Examination Table Loop 2A1 Intermediate Cold leg 45oA 100% both welds from Scan limited from nozzle Steam Generator Nozzle-to- pipe side side due to nozzle OD extension (shop weld) and 30% of shop weld from transition taper.
Extension-to-Elbow (field weld) nozzle side Weld Nos.
RC-112-401-258-A 60'A Supplemental both sides Pipe to Valve V-3227 Weld No. 45'A 63% from pipe side Limited by pipe to valve RC-151-FW-1 60oA configuration 45'C 0% from valve side Valve V-3227 to Pipe Weld No. 45oA 88% from Pipe side Limited by configuration Sl-148-FW-5 60'A 0% from Valve side 45'C Pipe to Valve V-3624 Weld No. 45'A 100% Pipe side NA Limited by configuration SI-148-FW-1 45'C 0% from valve side Valve V-3217 to Pipe Weld No. 45'A 81 from pipe side Limited by configuration Sl-149-FWC 45'C 0% from valve side 60'A Page 204 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 6 Examination Table Pipe to Valve V-3614 Weld No. 45'A 100% from pipe side NA Limited by configuration Sl-149-FW-1 45'C 0% from valve side Valve V-3237 to Pipe Weld No. 45oA 100% from pipe side 9 Limited by configuration SI-1 50-FWP 45'C 0% from valve side 60'A Valve V-3247 to Pipe Weld No. 45'A 45% from pipe side 10 limited by configuration SI-1 51-FW-4 45'C 20% from valve side Pipe to Valve V-3644 Weld No. 45'A 63% from pipe side 11 Limited by configuration SI-1 51-FW-1 45'C 0% from valve side 60'A Valve V-3261 to pipe Weld No. 45'A 63% from pipe side 12 Limited by pipe to valve SI-518-FW-1 45'C 38% from valve side configuration Page 205 of 272
~FI 100%
D VELD PIPE SIDE EXT. SIDE EXT SIDE 45'0/
60'SHOP 45'ND 60'00%
VE D 100/ EXT. SIDE 45'ND 45'AND 60'NOZZLE SIDE 60'0%
3 I/2'IPE
'XTI PIECE NOZZLE WELD NO. RC-123-201-258 (SHOP WELD)
WELD NO. RC-li2-401-25B-A (FIELD WELD)
TYPICAL CONFIGURATION - S/G INLET NOZZLE WELDS STEAM GENERATOR INLET NOZZLE PIPING WELDS TYPICAL SCAN LIHITATIONS FIGURE 6.1
SHOP WELD 100/ 45'AND 60'FROM EXT. PIECE SIDE 0/ FROM NOZZLE SIDE FIELD SHOP VELD VELD 100/ FIELD VELD 45 A, BOTH SIDES 1 60 A, 100/ ELBOV SIDE 5/8'o 45'o'5 ELBOV EXT. PIECE OUTLET NOZZLE TYPICAL CONFIGURATION S/G OUTLET NOZZLE VELD NO. RC-115-401-258-B BISHOP WELD)
VELD NO. 115-I(FIELD WELD>
STEAM GENERATOR OUTLET NOZZLE PIPING WELDS FIGURE 6.2
MELD NO. RC-115-109-722-A LQQP 2A2 CL-TO-RV SCAN OBSTRUCTIONS RC-115-109-722-A OBSTRUCTED BY LUG 16'40'67 1/2' RC-)15-109-722-B FIGURE 6.3
WELD NO. RC-]21-103-722 "A LOOP 2BI CL-TO-RV SCAN OBSTRUCTIONS RC-1 21-103-722-A 87'BSTRUCTED 53'Y BY BUNPER LUG 16'oQ 167 I/2' RC-121-103-722-B F'IGURE 64
ZONE ll COLD C OFFSET SUFFICIENT TO OBSTRUCT LONG SEAN OVER 53'O ALL ANGLES. ZONES 9, 13'AMD 1'5, BUMPER OBSTRUCTS 30 DC SUPPLEMENTAL SCAN ONLY.
LUG C3)
REER (3)
CL HOT Q COLD PIPE OD I
PIPE ID I WELD NQ. RC-121-103"722-LS-A SCAN OBSTRUCTIONS REACTOR COOLANT COLD LEG TO REACTOR VESSEL TYPICAL LUG AND BUMPER ARRANGEMENT ZONES 9, ll. 13 AND 15 FIGURE 6,5
CODE REOIIRED Vn.UIR: HISSED DY 45'I/2 V EXAN COCC COVCRAOC IRII ACHIEVED VELD NO, RC-151"F W-1 SCAN LINIT*TION FIGURE 6.6
VALVE F'LOW PIPE 45 AND 60 I/2 V 88% IN ONE DIRECTION (PIPE) 0% IN OTHER DIRECTION (VALVD WELD NO, Sl-I48-FW-5 F'IGURE 6'
WELD NO. SI-149-F'V-4 NOT EXAHINED 45% I/8 V TECHNIQUE 60% 3/4 V TECHNIQUE EXAHINED WELD AND PIPE SIDE ONLY 81/ FROH ONE DIRECTION 0/ I RON OTHER DIRECTION F'IGURE 6.8
VALVE CRV MISSED PIPE WELD HO. Sl-150-FW-4 CRU ACHIEVED 100K~ FROM PIPE SIDE Oio FROM VALUE SIDE FIGURE 6.9
VELD NO. SI-151-FV-4 1.45 1,3 45/ F'RON ONE SIDE (PIPE) 20/ F'RON OTHER SIDE (VALVE) 95' I/2 V TECHNIQUE F'IG 6.10
VELD NO. RC-151-FW-1 PIPE FLGV VALVE 45'ND 60'I/2 V EXAM 63% FROM ONE SIDE (PIPE>
0/ FROM OTHER SIDE (VALVE)
FIGURE 6.11
WELD NO. SI-518-FW-I
,925
~ 75 .775 45 1 I/2 V TECHNIQUE 63% FROH ONE DIRECTION 38% FROM OTHER DIRECTION FIGURE 6.12
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 8 A. COMPONENT IDENTIFICATION:
Class: 2 Shutdown Cooling Heat exchangers Pressure Retaining Welds B. EXAMINATION REQUIREMENTS:
EXAM ITEM NO. EXAMINATION REQUIREMENTS CAT.
C-A C1.10 Essentially 100% volumetric examination of shell circumferential welds at gross structural discontinuity C. RELIEF REQUESTED:
Relief is requested from the ASME Boiler and Pressure Vessel Code required volume as identified in Figure IWC-2500-1.
D. BASIS FOR RELIEF:
Ultrasonic examination of welds No. 1-2701 (flange to body) and 1-2702 (body to tubesheet) are partially obstructed by inlet and outlet nozzle reinforcing pad. Approximately 78/e of Code Required volume is achieved.
The extent of examination volume achieved ultrasonically coupled with the system pressure leakage tests provide assurance of an acceptable level of quality and safety.
E. ALTERNATIVE EXAMINATIONS OR TESTS:
~~1) Conduct examinations to the extent practical per IWC-2500-1~~
~~2) Perform System Pressure Test as required by IWC-2500-1 Page 218 of 272~~
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 8 F. IMPLEMENTATION SCHEDULE:
Second Inservice Inspection Interval August 8, 1993 to August 08, 2003 Page 219 of 272
1-2701 1-2702 F1GURE 8.1
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 9 A. COMPONENT IDENTIFICATION:
Class: 2 Steam Generator 2A Pressure Retaining Nozzle Welds in Vessels B. EXAMINATION REQUIREMENTS:
EXAM ITEM NO. EXAMINATION REQUIREMENTS CAT.
c-B C2.21 Surface and volumetric examlnatlon of nozzle to shell welds for nozzles without reinforcing plate, >1/2" thick C. RELIEF REQUESTED:
Relief is requested from the ASME Boiler and Pressure Vessel Code required volume as identified in Figure IWC-2500M(b).
D. BASIS FOR RELIEF:
Configuration and permanent attachments prohibit 100% ultrasonic examination of Code required volume. Additional ultrasonic techniques are employed where practical to achieve the Code Required Volume. The attached Table summarizes the percent of coverage achieved and references the specific Figure within the relief providing the extent of the limitations.
The extent of examination volume achieved ultrasonically and the alternate scans performed (see Examination Coverage Table) coupled with the system pressure tests provide assurance of an acceptable level of quality and safety.
Page 221 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 9 E. ALTERNATIVE EXAMINATIONS OR TESTS:
~~1) Periodic System Pressure tests per IWC-2600-1~~
~~2) Perform to the extent practical the volumetric and surface examinations's required by IWC-2500-1.~~
F. IMPLEMENTATION SCHEDULE:
Second tnservice Inspection Interval
. August 8, 1993 to August 08, 2003 G. ATTACHMENTS TO THE RELIEF:
Examination Table Examination Beam Coverage Fig. Description of Limitations Area Angle (CRV)
Identification Steam Nozzle to 45'00% one Examination limited by Head side configuration to one side.
Weld No. 100% one SG-2A-105-201 Side 60'00%
Feedwater due Examination limited by Nozzle to Head to full configuration and welded Weld NO. Vee (one attachment SG-2A-111-221 sided) 98% one sided 46'0'age 222 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 9 E. ALTERNATIVE EXAMINATIONS OR TESTS:
~~1) Periodic System Pressure tests per IWC-2500-1~~
~~2) Perform to the extent practical the volumetric and surface examinations as required by IWC-2500-1 ~~~
F. IMPLEMENTATION SCHEDULE:
Second Inservice Inspection Interval August 8, 1993 to August 08, 2003 G. ATTACHMENTS TO THE RELIEF:
Examination Table Examination Beam Coverage Fig. Description of Limitations Area Angle (CRV)
Identification Steam Nozzle to 45 100% one Examination limited by Head side configuration to one side.
Weld No. 60 100% one SG-2A-1 05-201 side Feedwater 100% due Examination limited by Nozzle to Head to full configuration and welded Weld NO. Vee (one attachment SG-2A-111-221 sided) 60 98% one sided Page 222 of 272
SG-2A-111-221 SG-2A-105 201
~ E.
SG-2A-105-201-IR ~ CLASS 2 CLASS 1 FIGURE S.1
FEEDWATER NOZZLE 4
STEAM GENERATOR SHELL 5 I/2" NOZZLE TO LUG WELD NO. 111-221 STEAM GENERATOR FEEDWATER NOZZLE SCAN OBSTRUCTION FIGURE 9.2
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 10 A. COMPONENT IDENTIFICATION:
Class: 2 Main Steam and Safety Injection System Piping Pressure Retaining Welds in Piping B. EXAMINATION REQUIREMENTS:
EXAM ITEM NO. EXAMINATION REQUIREMENTS CAT.
C-F-1 C5.11 Essentially 100% volumetric and surface examination of circumferential welds C-F-2 C5.81 Essentially 100% surface examination of circumferential welds C. RELIEF REQUESTED:
Relief is requested from the ASME Boiler and Pressure Vessel Code required volume or surface.
Examination coverage Examination Exam Coverage Fig. Description of Area Method Limitations Identification Pipe PT 93% Examination limited by longitudinal welded attachment Seam Weld No. UT MS-1-FW-1-LS 46'A 86%
MS-33-FW-1-LS 46'C 83%
Page 226 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 10 Examination coverage Examination Exam Coverage Fig. Description of Area Method Limitations Identification Pipe to Valve PT 37% from Limited due to (V-3144) UT Pipe and configuration Sl-146-FW-2 45'A Valve 45'C Sides Valve (V-3144) PT 65% from Limited due to to pipe UT Pipe Side configuration SI-110-FW-1 45'A 57% from 45'C Valve Side Pipe to Elbow PT 80% CRV NIA 4" of total SI-110-8-SW-1 UT Achieved circumference missed 45'A due to I-Beam of top 45'C Valve (V-3654) PT 40% from Limited due to to pipe UT Pipe side configuration SI-213-FW-2 45oA 20% from 45'C Valve Side Pipe to Valve PT 40% from Limited due to (V-3654) UT Pipe side configuration SI-213-FW-1 45oA 20% from 45.C Valve side D. BASIS FOR RELIEF:
Ultrasonic and surface examination partially obstructed by welded attachments.
The extent of examination volume achieved ultrasonically and the alternate scans performed coupled with the system pressure tests provide assurance of an acceptable level of quality and safety.
Page 226 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 10 E. ALTERNATIVE EXAMINATIONS OR TESTS:
~~1) Periodic System Pressure tests~~
~~2) Perform volumetric and surface examination to the extent practical F. IMPLEMENTATION SCHEDULE:~~
Second Inservice Inspection Interval August 8, 1993 to August 08, 2003 Page 227 of 272
MS-I-FW-1-LS) "A" MAIN STEAM UNE OUTSIDE CONTAINMENT LONGITUDINAL SEAM MS-33-FW-1-LS) "B MAIN STEAM UNE OUTSIDE CONTAINMENT LONGITUDINAL SEAM LD NO.
MS-1-FW-1 D.S.
vl 9'-10" 11'-10" 27 S 27 z
O I
~ Vl Vl
/ I v wnr nz rem A
I CVCC n I Nr Vl Vl O
ZZ 0 C
Vl r'r'r'r'r'r'IGURE LONGSEAM 4 Vl gI I
Vl SDE VIEW OF WELDED SUPPORT ATTACHMENT SADDLE WITH TRUNNIONS SCAN PATH COMPLETELY OBSTRUCTED FROM 9'-10" TO 12'-1 D.S. AND 23'-18 TO 26'-2" D.S. BY 11ELD SUPPORT ATTACHMENT SADDLE 10.1 YOUTH TRVNNIONS.
WELD NO. SI-146"i'W-2 VALVE PIPE 45' I/2 V TECHNIQUE F'IGURE I0.2
VELD NO. SI-110-FW-I
~ 725 45 I I/2 V TECHNIQUE FIGURE 10.3
WELD NO. SI-213-FW-2 VALVE PIPE 45 11/2 V 40/ FROM PIPE SIDE 20% FROM VALVE SIDE FIGURE 10A
VELD NO. Sl-213-FW-1 VALVE P 1PE 45' 1/2 V F'IGURE 10.5
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 12 Relief Request 12 is not used.
Page 233 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 13 A. COMPONENT IDENTIFICATION:
CLASS: 1 and 2 Code Examination Category: N/A Ultrasonic Calibration Blocks Asme Section XI, Appendix III B. EXAMINATION REQUIREMENTS:
III-3400 The basic calibration blocks shall be made from the same nominal diameter and nominal wall thickness or pipe schedule as the pipe to be examined.
III-3411 The calibration block shall be fabricated from one of the materials specified for the piping being joined by the weld.
C. RELIEF REQUESTED:
Relief is requested from the ASME Code, Appendix III, requirements, III-3400 and III-3411 which requires:
~~1) the calibration block to be the same nominal diameter and wali thickness or pipe schedule;~~
~~2) be fabricated from one of the same materials as the piping being joined. Relief is requested for the following:~~
CAL. BLOCK COMPONENT DEVIATION FROM CODE I.D. NUMBER DESCRIPTION UT-4A Hot Leg Different Material Primary Coolant Piping Page 234 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 13 CAL. BLOCK COMPONENT DEVIATION FROM CODE I.D. NUMBER DESCRIPTION UT-45 Main Steam Piping Different Diameters Welds Different Thickness D. BASIS FOR RELIEF:
UT-4A Primary Coolant Piping, Hot Leg SA-533 Grade A is comparable to SA-516 Grade 70 (piping material),
as provided by ASME Section XI, Appendix III, Article III-3411 (c).
~~2. UT-45 Main Steam Piping Welds The subject piping welds are of two sizes:~~
a) 34" diameter, 1.250 " wall b) 36.625" diameter, 1.234" wall. The requirements of ASME code are such that two blocks, one of each diameter would be required.
c) The wall thickness is essentially the same, therefore there is little or no change in the sensitivity.
d) The small difference in diameter is not ultrasonically noticeable.
~~4. The proposed calibration blocks have been in use since the plant was built, their continued use would tend to provide consistent results.~~
Page 235 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 13 E. ALTERNATIVE EXAMINATIONS OR TESTS:
Perform the Code required examinations using the proposed calibration blocks as defined above.
F. IMPLEMENTATION SCHEDULE:
Second Inservice Inspection Interval August 8, 1993 to August 08, 2003 Page 236 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 14 A. COMPONENT IDENTIFICATION:
Class: Component Identification:
Reactor Pressure Vessel and Closure Head Steam Generator - Primary Side Pressurizer Reactor Coolant Pump Steam Generator - Secondary Side B. EXAMINATION REQUIREMENTS:
Exam Cate o Exam Item No: Exam Descri tion:
B-D B3.90 RPV Nozzle - Vessel Weld B3.100 RPV Nozzle Inside Radius B3.110 Pressurizer Nozzle - Vessel Weld B3.120 Pressurizer Nozzle Inside Radius B3.130 Steam Generator Nozzle - Vessel Weld B3.140 Steam Generator Nozzle Inside Radius B-B B2.11 Pressurizer Shell - Head Welds 82.'12 Pressurizer Long Welds B2.31 Steam Generator Circ Head Welds B2.32 Steam Generator Meridional Welds B2.40 Steam Generator Tubesheet - Head Welds B-F B5.40 Pressurizer Nozzle - Safe End B-G-1 B6.50 RPV Threads in Flange 8-G-2 B7.20 Pressurizer Bolts, Studs, Nuts B7.30 Steam Generator Bolts, Studs, Nuts B7.50 Pressurizer Bolts, Studs, Nuts Page 237 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 14 Exam Cate o: Exam Item No: Exam Descri tion:
B-H B8.20 Pressurizer Integral Attachments B8.30 Steam Generator Integral Attachments B-J B9.11 Circumferential Pipe Welds C. RELIEF REQUESTED:
Florida Power and Light Company (FPL) request relief from the following:
~~1. percentage requirements of IWB-2412 Inspection Program B~~
~~2. the sequence of component examinations established during the first inspection interval D. BASIS FOR RELIEF:~~
~~FPL has extensive experience in the operation of pressurized water reactors, (PWR's), (two Westinghouse and two Combustion Engineering Design Units).~~
2. With over 70 years of operating experience, FPL has not identified any defects in the Reactor Pressure Vessel, Steam Generator and/or Pressurizer, that would indicate that an examination schedule change from one period to another period would decrease the quality, safety, and/or the structural integrity of the plant in any way.
3. Cost of performing selected examinations on the same component, within each period in order to satisfy the percentage requirements of Section XI has become an economic hardship, with no compensating increase in the quality or safety of the unit, based on the recorded examination and test results to date.
Example: performance of two of the six nozzles in the first period of an inspection interval to meet the 26% to 60%
requirement of Table IWB-2500-1, exceeds $ 400,000.00 for the examinations only. This cost does not take into consideration the support required to make the vessel ready for the examinations.
Page 238 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 14 The cost of performing the entire reactor Pressure Vessel examination of essentially 100% of the required examinations including all nozzles is $ 700,000.00.
Performance of the entire examination activity would save as a minimum FPL $ 400,000.00 on this examination activity alone.
~~4. In the case of the Reactor Pressure Vessel, FPL performed the 1st.~~
period examinations again in the 2nd. period, in conjunction with the mechanized inspection activity, in order to reestablish the 10-year inspection interval FPL performed essentially 100% of the
~ Reactor Pressure Vessel ~
5. Continued performance of these components is further assured through the examination frequency of the other FPL units, which are still on the original schedule established during their first inspection interval.
~~6. FPL also proposes to perform the Reactor Pressure Vessel Closure Head examinations in the First period, which will provide an additional gauge of the condition of the Unit 2 Reactor Vessel.~~
E. ALTERNATIVE EXAMINATIONS OR TESTS:
FPL proposes to reschedule examinations for the Reactor Pressure Vessel, Steam Generator and Pressurizer, such that all major examinations are performed at one time within a specified period.
FPL proposes the following schedule:
Reactor Pressure Vessel All in the 2nd. period, in conjunction with the 10-year automated examination activity.
Steam Generator All examinations to be scheduled in the 3rd. Period.
Pressurizer All examinations to be scheduled in the 1st. Period.
Page 239 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 'l4 F. IMPLEMENTATION SCHEDULE:
The Second Inservice Inspection Interval August 8, 1993 to August 8, 2003 G. ATTACHMENTS TO THE RELIEF:
Reactor Pressure Vessel Reschedule Examination Table Steam Generator Vessel Reschedule Examination Table Pressurizer Vessel Reschedule Examination Table REACTOR PRESSURE VESSEL TABLE ITEM IDENTIFICATION RESCHEDULED FROM NEW SCHEDULE 1st and 2nd 2nd 101-121 Shell-Flange 105-1 21-A Nozzle-Shell 1st and 2nd 2nd 105-121-B Nozzle-Shell 1st and 2nd 2nd ON-IR-A Inner Radius 1st Period 2nd ON-IR-B Inner Radius 1st Period 2nd 401-128-A Outlet Noz-Ext 1st Period 2nd 401-128-B Outlet Noz-Ext 1st Period 2nd FL-01-54 Threads in 1st Period 2nd Base Metal REACTOR PRESSURE VESSEL CLOSURE HEAD TABLE ITEM IDENTIFICATION RESCHEDULED FROM NEW SCHEDULE 101-101 Flange to Torus 3rd 1st Page 240 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 14 STEAM GENERATOR TABLE ITEM IDENTIFICATION RESCHEDULED FROM NEW SCHEDULE SG-2A-'I 01-254-8 1st 3rd Meridional Weld SG-2A-202-271 1st 3rd Primary Ext. Ring SG-2A-201-246 1st 3rd Primary Ext. Ring SG-2A-1 04-261 1st 3!'d Inlet Noz-Head SG-2A-.1 02-261-A 1st 3!'d Outlet Noz-Head SG-2A-102-261-B 1st 3rd Outlet Noz-Head SG-2A-1 01-244-B 1st 3I'd Ext. Ring Long. Weld SG-2A-IN-IR '1st 3rd Inlet Noz Inner Radius SG-2A-ON-IR-A 1st 3rd Outlet Nozzle SG-2A-ON-IR-B 1st 3rd Outlet Nozzle SG-2A-PMS-A 1st 3!'d Manway Studs SG-2A-PMN-A 1st 3rd Manway Nuts SG-2A-PMS-B 1st 3!'d Manway Studs SG-2A-PMN-B 1st 3!'d Manway Nuts Page 241 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 14 STEAM GENERATOR TABLE ITEM IDENTIFICATION RESCHEDULED FROM NEW SCHEDULE RC-1 14-201-258 1st 3rd Nozzle Extension RC-116-401-258-B 2nd 3rd SG Nozzle-Nozzle Ext.
RC-116-1 2nd 3rd Nozzle Ext-Elbow RC-115-103-742-LS-A 2nd 3rd Long. Seam RC-116-103-742-LS-B 2nd 3rd Long. Seam RC-112-401-258-A 1st 3rd SG Nozzle-Nozzle Ext SG-2A-203-246 1st 3rd 2nd Ext. Ring to Tubesheet SG-2A-101-241 1st 3rd 2nd Ext. Ring-lower SG-2A-1 02-221 2nd 3rd Int. Shell-Cone SG-2A-111-221 2nd 3rd FW Nozzle-Cone SG-2A-111-221-IR 2nd 3rd Long. Seam SG-2A-103-221-A 1st 3rd Key Bracket SG-2A-103-221-B 2nd 3rd Key Bracket Page 242 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 14 STEAM GENERATOR TABLE ITEM IDENTIFICATION RESCHEDULED FROM NEW SCHEDULE SG-2A-1 04-221-A 1st 3rd Clevis Bracket SG-2A-105-221-A 2nd 3rd Support Bracket SG-2A-104-221-8 2ncl 3rd Clevis Bracket Page 243 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST, NUMBER 14 PRESSURIZER TABLE ITEM IDENTIFICATION RESCHEDULED FROM NEW SCHEDULE 501-671 2nd 1st Top Head-Upper Shell 503-671-B 3!'CI 1st Safety Valve Nozzle 503-671-C 2ncl 1st Safety Valve Nozzle 108-601-A 2nd 1st Safety Valve Nozzle SVN-IR-A 2ncl 1st Inner Radius SV-1200 3!'Cl 1st Safety Valve to Flange 108-601-B 2ncl 1st Relief Valve Nozzle RVN-IR 2ncl 1st Inner Radius 108-601-C 2nd 1st Safety Valve SVN-IR-B 2nd 1st Inner Radius SV-1201 3!'Cl 1st Safety Valve to Flange 108-601-D 2nd 1st Safety Valve Nozzle SVN-IR-C 2ncl 1st Inner Radius SV-1202 3!'d 1st Safety Valve to Flange Page 244 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 14 PRESSURIZER TABLE ITEM IDENTIFICATION RESCHEDULED FROM NEW SCHEDULE MS-01 3rd 1st Studs MN-01 3rd 1st Nuts 101-622-A 2nd 1st Upper Shell Long.
101-642-A 2nd 1st Lower Shell Long.
304-671 2nd 1st Lower Shell to Lower 103-651 2nd 1st Support Skirt 105-651 2nd 1st Surge Nozzle SRGN-IR 2nd 1st Inner Radius RC-514-671 2nd 1st Safe End-Nozzle RC-506-671 3rd 1st Nozzle-Safe End Page 245 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 14 REACTOR COOLANT PUMP TABLE ITEM IDENTIFICATION RESCHEDULED FROM NEW SCHEDULE 02-019-N-001-016 2nd 1st Nuts 02-0'I 9-S-001-016 2nd Studs Page 246 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 15 A. COMPONENT IDENTIFICATION:
Class: I Identification of Components: Inlet and Outlet Nozzle to Pipe Transition Welds Description of Components: Reactor Coolant Piping B. EXAMINATION REQUIREMENTS:
Examination Category: B-J Examination
~~Description:~~
Pressure Retaining Welds in Piping Examination Item Number: B9.11 Item Exam Method Extent of Examination Number B9.11 Surface Nominal Pipe Size 4 inch or Greater, includes and 100% of Circumferential Weld Volumetric C. RELIEF REQUESTED:
Relief is requested from the conduct of the ASME Code Required Surface Examination Method for the following weld configurations.
Summary Weld Weld Size Number Identification Description 000330 401-128-A Outlet Nozzle to Extension 42 I ~
000340 RC-114-1 Outlet Nozzle Extension to 42 I I Pipe 000350 201-128-A Inlet Nozzle to Extension 30 I ~
RC-112-6 II 000360 Inlet Nozzle Extension to 30 Elbow 000370 201-1 28-B , Inlet Nozzle to Extension 3 0 II Page 247 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 16 Summary Weld Weld Size Number Identification Description 000380 RC-121-6 Elbow to Inlet Nozzle 30II Extention 000390 401-1 28-B Outlet Nozzle to Extension 42" 000400 RC-123-1 Outlet Nozzle Extension to 42" Pipe 00041 0 201-1 28-C Inlet Nozzle to Extension 30II 000420 RC-124-6 Inlet Nozzle Extension to 30II Elbow 000430 201-128-D Inlet Nozzle to Extension 3 Q II I~
000440 RC-115-6 Elbow to Inlet Nozzle 30 Extention D. BASIS FOR RELIEF:
Performance of the surface examinations on the Reactor Pressure Nozzle to Pipe Transition welds involves excessive costs, manhours and man/rem with little or no compensating increase in the level of quality and safety.
2. Changes in Section XI Code Required Volume (CRV) has reduced the volumetric portion to the inner one-third of the weld thickness, while still requiring the surface examination on the outside surface. In most cases this is considered the most efficient and less expensive way of examining these welds. In the case of the Reactor Coolant piping, this is not the case due to the size of the piping, location of the welds (access), man/rem exposure due to the close proximity of the welds in relation to the RPV, the cost of insulation removal, erecting scaffolding, and not to mention the increased time of the examiner to conduct the surface examination.
Page 248 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 15
3. FPL has developed an alternate volumetric examination technique to effectively examine the outside surface of the Reactor Vessel Nozzle to Pipe Transition welds from the inside surface of the component in lieu of the surface examination.
This volumetric examination will accomplish more than the current surface examination previously performed at St. Lucie. The surface examination used is the Magnetic Particle examination method, which is limited to defects open to,,or just below the surface. The alternative volumetric (ultrasonic) examination method proposed by FPL, will not only examine the surface area, but the entire volume below the surface.
~~4. This technique was used successively at FPL's Turkey Point Units 3 and 4, and during the St. Lucie Unit 1 and 2 examinations during the last inspection interval ~~~
5. FPL has over 70 years of operating experience with pressurized water reactors, between our four operating plants. These welds have been examined starting with the preservice examination and within each inservice inspection interval without identifying any flaws with either the volumetric and/or surface examination technique, on any of our units.
E. ALTERNATIVE EXAMINATIONS OR TESTS:
Conduct a Full Vee (ultrasonic) examination technique to effectively examine the outside surface of the Reactor Vessel Nozzle Pipe to Transition welds, from the Inside surface, in lieu of the surface examination as defined in the proposed attachment to this request.
~~2. Conduct system pressure test as required by IWB-2500-1.~~
~~3. The extent of examination required and the proposed examination technique, coupled with the system pressure tests provides assurance of an acceptable level of quality and safety.~~
Page 249 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 15 F. IMPLEMENTATION SCHEDULE:
Second Inservice Inspection Interval August 8, 1993 to August 8, 2003 All examinations to be conducted during the second period of the second inspection interval in conjunction with the remote mechanized ultrasonic examination of the Reactor Pressure Vessel.
G. ATTACHMENTS TO THE RELIEF:
Alternate Volumetric Examination Attachment Page 260 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 15 NUCLEAR ENGINEERING DEPARTMENT EQUIPMENT, SUPPORT AND INSPECTIONS GROUP P.o. BOX 14000 JUNO BEACH, FLORIDA 33408 St. Lucie Nuclear Power Plant Unit 2 SECOND INSERVICE INSPECTION INTERVAL ALTERNATE VOLUMETRICEXAMINATION OF REACTOR COOLANT PIPING IN LIEU OF SURFACE EXAMINATIONS Prepared by Florida Power and Light Company Code Programs Section For St. Lucie Nuclear Power Plant 10 Miles South of Ft. Pierce on AIA Ft. Pierce, Florida 33034 Commercial Service Date: August 8, 1983 NRC Docket Number: 50-389 Document Number: RR-15 Revision Number: Date: July 24, 1993
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 16
1. 0 BACKGROUND To perform ultrasonic weld examinations, the ultrasonic search unit is applied to the pipe base metal adjacent to the weld. Angulation wedges cause the ultrasonic beam to rePact at the pipe surface and propagate into the weld at a predetermined angle. As the ultrasonic beam passes through the pipe walI and the volume of the weld metal, the ultrasonic instrument displays echos from reflecting surfaces. The degree of success depends on the examination material, the strength of the ultrasonic beam, and beam angle with respect to the orientation of the reflecting surface.
Figure I Page 252 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 15 2.0 FULL VOLUME EXAMINATION When full volume examinations are required, the ultrasonic beam is monitored during the entire beam path, i.e. entry to inside surface impingement. Conditions permitting, the beam is further monitored after it reflects, at the inside surface and continues to propagate in a vee path toward the outside surface.
FULL VEE OR PUL1 VOLVIIS Figure 2 Page 253 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 15 3.0 ULTRASONIC CHARACTERISTICS During propagation the ultrasonic beam exhibits three main characteristics; divergence, attenuation, and scattering. Calibration will generally compensate for these beam characteristics, to a degree. A fourth, recently recognized characteristic is the fact that entry surface "noise" causes a "blind zone" immediately under the ultrasonic search unit.
This blind zone contains a multitude of entry surface signals Pom:
~~a. the angulation wedge;~~
~~b. the coupling material; C. surface irregularities; and~~
~~d. from the examination material grain structure.~~
Depending on the examination parameters this blind zone can represent from a few mils to as much as an inch of the ultrasonic beam path where flaws could exist un-noticed.
SEAACH UNIT CNZRY SVAtACC BLIND ZONm Figure 3 Page 254 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 15 4.0 ENHANCEMENT OF EXAMINATION There are two ways to enhance the examination of the entry surface.
The most commonly employed technique is to extend the ultrasonic calibration to a full vee path or beyond. This allows the observation of the outside surface in a relatively noise-free segment of the ultrasonic beam. See Figure 2.
The simplest and least expensive approach would be to examine the outside entry surface with another nondestructive examination method. Thus, we rely on the ultrasonic method only for that portion of the examination volume where it has proven reliability.
This is the essence of the ASME Section XI examination requirements. Even though the ultrasonic portion of the examination volume has been reduced to the inner one-third of the wall thickness, See Figure 4, the surface examination of the outside surface is still mandated. See Figure 5.
For most piping welds this approach is tire simplest and least expensive. But this is not so when applied to the Reactor Vessel Nozzle Extension welds, due to their location.
Figure 4 Page 255 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 15 Figure 5 Page 256 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 16 5.0 PROPOSED ULTRASONIC TI."CHNIQUI"
.Florida Power and light Company (FPL) proposed the use of an alternate ultrasonic examination techniques to effectively examine the outside surface of the Reactor Vessel
.¹zzle to Safe-End welds at our Turkey Point Units 3 and 4. This examination accomplished more than the current surface examination method prescribed by current Code. The ultrasonic examination proposed investigated the outside surface of the Code required Surface in two directions circumferentially and in two directions axially covering 100% of the weld plus one inch on each side.
This alternate examination technique was initially submitted under Request for Relief Number 2, for Turkey Point Plant Units 3 and 4, and was granted by the Nuclear Regulatory Commission.
During the last submittal of the St. Lucie Unit 1 updated Inservice Inspection Program, FPL proposed and was granted use of this technique. '
CL4 lg Figure 6 Page 257 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 15 TAIN~ 4414 ~
OI 1 44TI OO Figure 7 Page 258 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 15 6.0 QUALIFICATIONOF TECHNIQUE In order to qualify this technique, Southwest Research Institute (Swri) was requested by FPL to designed and fabricated a weld mock-up calibration block that duplicated, to the extent possible, the as-built configuration of the Turkey Point Nozzle to Pipe welding process, cracks were initiated in the block at specific locations on the inside and outside surfaces. The lengths and depths of these cracks were tightly controlled in order to allow the cracks to be used for qualification purposes. The crack depths ranged Pom approximately 0.100 inch (I/2 the maximum allowable Code depth for the pipe thickness) to approximately 0.200 inch (maximum allowable Code flaw depth). The crack lengths were controlled at 0.5 inch which is within the 0.65 inch allowed by Code for liquid penetrant indications. The cracks were investigated and demonstrated to be detectable and recordable to the satisfaction of the Authorized Nuclear Inservice Inspector (ANII) prior to performance of the actual examinations.
A high resolution 45 degree shear wave search unit was used. The examination sensitivity was established using 0.10 inch deep notch (3.6%t).
8.0 EX4MINATIONRESULTS No recordable indications were detected during the performance of these examinations.
Page 259 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 16 A. ARTICLE IDENTIFICATION:
Article IWA-4000 Repair Procedures Article IWA-6000 Records and Reports Article IWA-7000 Replacement B. ARTICLE REQUIREMENTS:
IWA-4800 The records required by IWA-6000 shall be completed for all repairs.
IWA-7520 (8) Completed Owner's Report for Repairs or Replacements, Form NIS-2 IWA-6210 (c) The Owner shall prepare inservice inspection summary report for Class 1 and 2 pressure retaining components and their supports.
IWA-6220 (c) Inservice inspection summary reports shall be required at the completion of each inspection conducted during a refueling outage. Examinations, tests, replacements, and repairs conducted since the preceding summary report shall be concluded.
IWA-6220 (d) Each summary report shall contain the following:
(2) Owner's Report for lnservice Inspections, Form NIS-1 (3) Owner's Report for Repair or Replacement, Form NIS-2 IWA-6230 Within 90 days of the completion of the inservice inspection conducted during each refueling outage Page 260 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 16 C. RELIEF REQUESTED:
Relief is requested from the following:
~~1. Preparation of the Owner's Report for Inservice Inspection, Form NIS-1.~~
~~2. Preparation of the Owner's Report for Repair or Replacement, Form NIS-2.~~
~~3. Submittal of thesummary reportwithin 90 days following completion of the inservice inspection conducted during each refueling outage.~~
D. BASIS FOR RELIEF:
Florida Power and Light Company (FPL) feels that the summary report required by IWA-6000 does not contain the information necessary to assure compliance with Code requirements, and therefore does not provide a compensating increase in the quality and/or safety of the St.
Lucie operating plant.
The summary report does not furnish evidence of compliance with the ASME Boiler and Pressure Vessel Code,Section XI, Inspection Program B, percentage requirements as mandated by IWB-2412, IWC-2412, and IWD-2412.
Class 3 components are excluded from the summary report submittal.
Both a Final Report and Summary Report must be prepared, reviewed and approved in order to comply with sub-article's IWA-6220 and IWA-6310 respectively.
The preparation, review, approval and certification of each record and report, within the time frame of 90 days following completion of each refueling outage, increases sustantiately the costs associated with inservice inspection activities, and puts an unreasonable time constraint on FPL without a increase in assurance of Code compliance.
Page 261 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 16 E. ALTERNATIVE EXAMINATIONS OR TESTS:
As an alternate to the requirements of IWA-6000, Florida Power and Light Company proposes the following:
~~1) REPAIR/REPLACEMENT PLAN Repair/Replacement plans shall meet the requirements of IWAP140 (1992 Edition), to the extent required, for all Code Classes.~~
Each Repair/Replacement Plan shall be given a unique identification number. The unique identification number may be the number of the document utilized for the repair and/or replacement as required by FPL procedures or instructions. (i.e., NCR, CNR, PCM, MEP, CWO, PWO, etc.,).
All other requirements of IWA-4000 (1989 Edition) which are applicable to the repair or replacement shall be met.
2) REPAIR/REPLACEMENT CERTIFICATION RECORD As an alternate to the NIS-2 Report, following completion of the repair or replacement FPL shall prepare and certify the Repair/Replacement Plan Certification Record, Form NIS-2A, attached.
The completed Form NIS-2A shall become part of the Repair/Replacement Plan and shall be maintained in accordance with IWA-6300.
FPL shall maintain an index and update regularly the status of the index of all Repairs/Replacement Plans for all Code Classes. The index shall identify the unique identification number and the interval and period during which the repair or replacement was completed.
The index shall be maintained in accordance with IWA-6300, and be made available upon request for review by the enforcement and regulatory authorities having jurisdiction at the plant site.
Page 262 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 16
3)
~~SUMMARY~~
REPORT A Summary Report shall be prepared and submitted to the regulatory and enforcement authorities having jurisdiction at the plant site within 120 days following the end of the Inspection Period as identified in Program B.
The Summary Report shall include examinations, tests, repairs and replacements results for all ASME Class items which have been completed since the previously submitted Summary Report. The Summary Report shall contain the following:
~~a. Summary Report Cover Sheet, Form NIS-1A, attached~~
b. Abstract of examination and tests information, Form NIS-1B, attached C. Listing of examinations, Form 1C, that were not performed to the extent identified by the inspection plan for the inspection period, and when or if they are planned for a later date.
~~Additionally, any alternate examinations (IWA-2240), from those identified within the inspection plan, were performed.~~
~~d. A listing of all flaws that require analytical evaluation, Form NIS-1D, attached~~
~~e. Abstract of all Code Classes of repairs and replacements Form NIS-2B, which were required due to an item(s) having exceeded an acceptance criteria of IWX-3000.~~
F. IMPLEMENTATION SCHEDULE:
This request for relief will be utilized for the entire Second Inservice Inspection Interval.
August 8, 1993 to August 8, 2003 Page 263 of 272
ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 16 G. ATTACHMENTS TO THE RELIEF:
Form NIS-1A Owner's ASME Section XI Summary Report Form NIS-1B Abstract of Examination and Tests Form NIS-1C Examinations Not Performed as Identified in the Inspection Plan Form NIS-1D Identification of Items with Flaws Which Required Analytical Evaluation for Continued Acceptability Form NIS-2A Repair/Replacement Plan Certification Record Form NIS-2B Abstract of Repairs and Replacements Page 264 of 272
FORM NIS-1A OWNER'S ASME SECTION XI
~~SUMMARY~~
REPORT As required by the provisions of the ASME Code Rules Page of port Identification Number Revision Date Owner (Name and Address of Owner)
Plant (Name and Address of Plant)
Plant Unit 5. Refueling Outage Number 6. Commercial Service Date Current Inspection Interval Q First Q Second Q Third Q Fourth Q Other Inspection Interval Date: From to Inspection Period Q First Q Second Q Third Inspection Period Date: From to Applicable Edition of Section XI Addenda Date/Revision of Inspection Plan Edition and Addenda of ASME Section XI applicable to Repairs and Replacements, if different than the Inspection Plan CERTIFICATE OF COMPLIANCE We certify that the statements made In this Summary Report are correct, and that the examinations, tests, repairs, replacements, and corrective measures represented by this report conform to the rules of the ASME Code,Section XI.
Certificate of Authorization No. (if applicable) Expiration Date Date 19 Signed (Owner's Representative and Title)
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and employed by of have inspected the components described in this Owner's Data Report during the period to and state that to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the rules of ASME Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, repairs, replacements, or corrective measures described in this report.
Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.
Commissions inspector's Signature National Board, State, Province, and Endorsements Date 19 Page 265 of 272
FORM NIS-1 B ABSTRACT OF EXAMINATION AND TESTS As required dy the provisions of the ASME Code Rules Page of CODE TOTAL ITEMS TOTAL TOTAL TOTAL EXCLUSIONS, EXAMINATION SUBJECT TO EXAMINATIONS EXAMINATIONS EXAMS OR CATEGORY EXAMINATION REQUIRED FOR REQUIRED FOR CREDITED % DEFERRALS INTERVAL THIS PERIOD FOR INTERVAL B-A 26 26 DEFERRED TO 2ND PERIOD B-B 37 B-D 36 36 B-F 31 31 B-G-1 16 B-G-2 56 46 16 B-H 595 202 59 B-K-1 24 24 19 B-L-1 10 B-L-2 B-M-1 B-M-2 17 WHEN DISSEMBLED FOR MAINTENANCE B-N-1 24 B-N-2 22 22 B-N-3 C-A 20 C-B 20 10 C-C 18 C-F-1 718 102 31 C-F-2 190 66 17 D-A 15 15 D-B 75 57 21 D-C F-A 150 51 16 F-B 242 66 25 F-C 303 90 76 Page 266 of 272
FORM NIS4C EXAMINATIONS NOT PERFORMED AS IDENTIFIED IN THE INSPECTION PLAN As required by the provisions of the ASME Code Rules Page of EXAMINATION ITEM ITEM DATE OF METHOD OF CATEGORY NUMBER DESCRIPTION RESCHEDULED ALTERNATE EXAMINATION EXAM PERFORMED Page 267 of 272
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FORM HIS-1D IDENTIFICATION OF ITEMS WITH FLAWS WHICH REQUIRED ANALYTICAL EVALUATION FOR CONTINUED ACCEPTABILITY As required by the provisions of the ASME Code Rules Page of EXAMINATION ITEM ITEM DESCRIPTION FLAW FLAW FOUND CATEGORY NUMBER CHARACTERIZATION DURING (IWA-3300) SCHEDULED XI EXAM/TEST (YES OR NO)
Page 268 of 272
FORM NIS-2A REPAIRIREPLACEMENT PLAN CERTIFICATION RECORD As required by the provisions of the ASME Code Rules Page of REPAIR/REPLACEMENT PLAN NUMBER OWNER'S CERTIFICATE OF COMPLIANCE We certify that the represented by repair or replacement Repair/replacement Plan Number conforms to the rules of the ASME Code, Section XI ~
Type Code Symbol Stamp Certificate of Authorization No. Expiration Date Signed Date 19 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and employed by of have inspected the components described in Repair/Replacement Plan No. during the period to , and state that to the best of my knowledge and belief, the Owner has performed all the activities described in the Repair/Replacement Plan in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the activities described in the Repair/Replacement Plan. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.
Commissions Inspector's Signature National Board, State, Province, and Endorsements Date 19 Page 269 of 272
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FORM NIS-28 A8STRACT OF REPAIRS AND REPLACEMENTS As required by the provisions of the ASME Code Rules Page of ASME REPAIR ITEM DESCRIPTION FLAW DATE REPAIR CLASS OR DESCRIPTION OF FOUND COMPLETE REPLACE REPLACEMENT WORK DURING PLAN SCHEDULED NUMBER SECTION XI EXAM/TEST (YES/NO)
Page 270 of 272
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ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 17 A. COMPONENT IDENTIFICATION:
Class: 1 Reactor Pressure Vessel Nozzle-to-Vessel Welds B. EXAMINATION REQUIREMENTS:
Examination Category: B-D Examination Item Number: B3.90 Examination
~~Description:~~
At least 25%, but not more than 50%, of the volumetric examination of the Nozzle-to-Vessel welds shall be examined by the end of the first inspection period, and the remainder by the end of the inspection interval.
C. RELIEF REQUESTED:
Relief is requested from the ASME Code requirements to examine at least 25% of the Vessel-to-Nozzle welds during the first examination period.
FPL proposes to conduct the entire Reactor Pressure Vessel examination requirements during the Second Inservice Inspection Period.
D. BASIS FOR RELIEF:
During the First 10 Year interval the nozzles that were examined during the first period, as identified above, were reexamined during the second period, in conjunction with the automated Reactor Pressure Vessel examinations.
Page 271 of 272
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ST. LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 17 The intent of the ASME Code is to assure the structural integrity of safety related components. This is accomplished by performing nondestructive examinations, as required by Table IWB-2500-1, over the extent of a specific inspection interval.
Performance of the examination requirements in the first and third inspection periods provides an undue cost burden. Performance of the 25% to 50% examination requirements, as specified in the Code, by the automated examination technique, cost in excess of $ 300,000,00 to
$ 400,000.00 dollars more than performance of the entire vessel examinations of $ 700,000.00.
FPL, during the first 10 Year Interval, performed a reexamination of the 25% to 50% code examinations, in conjunction with the remaining vessel examinations, in order to establish an examination interval consistent with the entire Reactor Vessel requirements.
FPL believes that since these welds will still be examined at 10 year intervals, an acceptable level of quality and safety is assured.
E. ALTERNATIVE EXAMINATIONS OR TESTS:
Conduct 100% Nozzle-to-Vessel Examinations during Second Examination Period, in conjunction with the remaining Reactor Vessel examinations.
F. IMPLEMENTATION SCHEDULE:
Second Inservice Inspection Interval August 8,1993 to August 08,2003 Page 272 of 272
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