ML17228A247

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:
Shared Package
ML17228A245	List: ML17228A244 ML17228A246 ML17228A247
References
PSL-201, NUDOCS 9308110242
Download: ML17228A247 (450)

Text

NUCLEAR ENGINEERING DEPARTMENT EQUIPMENTj SUPPORT>.AND.

INSPECTIONS GROUP P.O.Box14000 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: NRC Docket Number: Document Number: Reyision Number: 0 Date: July 24, 1993 August 8, 1983 50-389 PSL-200 Prepared by: r.Specialist Inservice Inspection Revyeyyed by: Sup rvisor Inspection Section Approved by:/7.upervisor Code Programs Section Reviewed by: Authorized Nuc ear lnservice Inspector 9308ii0242 930804 PDR ADOCN 05000389 8 PDR I t~J fl t I 1 1.'SUGAR aQ GN GH" ol<QGF, i"~i~3%AC'.~~'.'jh~i~~~QiC)a"w>adA I~'>~<~O'QA(7'"QO 2~~cSPi'P'>-hG l'TV<OQ C fgQl'.c,, iles 7, 930.'c.NS;~6<~'il~g&r i 0'.OQ=R'f'%PQQQ5~%~ED l'J Crq 0 pC'e'.paG'".'B'R c.8.5(Q C Cr850)Q~)QR,RSl~i~A a l!l~-

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 List of Effective Pages Table of Contents'ecord of Revision Abbreviations Glossary of Terms Abstract SECTIONS 1 Introduction 2 Class 1 Systems 3 Class 2 Systems 4 Class 3 Systems.5 Component Supports 6 Augmented Examinations 7 Relief Requests 8 Acceptance Criteria 9 ASME Code Boundaries 10 Repairs and.Replacemeri ts 11 Records APPENDICES 1 thru 1 2thru 2 3 thru 8 9 fhru 9 10 thru 12 13 fhru 16 17 fhru 17 18 thru 26 27 thIQ 38 39 thru 48.49 fhru 55 56 fhru 58 59 thru 60 61 thru 64 65 thru 73 74 thAI 77 78 thru S1 82 thru 90 0 0 0 0 0 0 July 24, 1993 July 24, 1993 July 24, 1993 July 24, 1993 Ju/y 24, 1993 July 24, 1993 July 24, 1993 July 24, 1993 July 24, 1993 July 24, 1993 July 24, 1993 July 24, 1993 July 24, 1993 July 24, 1993 July 24, 1993 July 24, 1993 July 24, 1993 July 24, 1993 A Class 1 Tables B Class 2 Tables C Class 3 Tables D Class 1 Support Tables E Class 2 Support T dies F Class 3 Supp Tables G Relief Regu sts 91 1>>28 92 29-40 9341-45 9446-49 9550-54 96 55-59 97-272 0 0 0 0.0 0 0 July 24, 1993 Ju/y 24, 1993 July 24, 1993 July 24, 1993 July 24, 1993 July 24, 1993 July 24, 1993 Page 2 of 272

'I-,a 78(3, (33," i XQ&9>c.O kB..a'L B~~~i-l P,7 S~

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 A BS TRA C 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.................

1.4.2 Steam Generator Eddy Current Testing Program 1.4.3 Snubber Examination and Testing Program 1.4.4 Inservice System Pressure Test Program 1.4.5 Repair and Replacement Program...........

20...21...21 21 21 1.5 Applicable Code Editions and Addenda...................

21 1.5.1 1.5.2 1.5.3 1.5.4 Preservice Inspection First Inspection Interval..........

Second Inspection Interval Subsequent Code Edition and Addenda 21 21 22~~~~~~~~~~~22 1.6 System Quality Group Classifications

....................

22 1.6.1 1.6.2 Quality Group A.....................

Qualify Group B.....................

~~~~~~0 22~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 1.6.4 1.6.5 1.6.6 1.6.7 1.6.8 Quality Group C............

Quality Group D............

Application

.......Optional Construction Piping Penetrating Containment Classificafion Diagrams......~~'~~~~r l~~~~~e~~~~~7~~~~~~~~23 23 23 23 23 24 1.7 I nspecfron Program B............................

24 1.7.1 Class 1, 2 and 3 Components 1.7.2 Component Supports............................

24 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 2.2.2 2.2.3 2.2.4 2.2.5 2.2.6 2.2.7 2.2.8 2.2.9 2.2.10 2.2.11 2.2.12 2.2.13 2.2.14 2.2.15 2.2.16 Category B-A................

Category B-B 0~~~~~~~~~~~~~e Category B-D................

Cafegory B-E............

Category B-F................

Category B-G-1 Category B-G-2 Category B-H................

Cafegory B-J Category B-K-1 Category B-L-1 and B-L-2......Category B-M-1 and B-M-2 Category B-N-1, B-N-2, and B-N-3 Category B-0................

Category B-P........

Category B-Q................

~~27 29 30 31 31 32 33 34 34 35 35 36 36 37 37 38 3.0 CLASS 2 SYSTEMSICOMPONENTS 39 3.1 ASME Code Exemptions Employed...39 3 1 1 IWC 1221 0~~~~~~~I~~~~~~~~~~0~~~0~~~~~~3.1.2 IWC 1222...................................

~.39 40 Page 4 of 272 SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993~1<<3 I<<C<<230~~~~~~~~~~~~~~~~~~<<~~~~~~~~~~~~~~~~~~3 40 3;2 Component/Piping Examination Basis 40 3.2.1 Category C-A..3.2.2 Category C-B..3.2.3 Category C-C..3.2.4 Category C-D..3.2.5 Category C-F-1.3.2.6 Category C-F-2.3.2.7 Category C-G..3.2.8 Category C-H..~~~~~~~~~~~~~~~~~~~~~~~~~~~~<<<<~40 41 43 43 44 45 46 47 4.0 Class 3 Systems/Components 49'.1 ASME Code Exemptions Employed 49 4.1.1 IWD-1220.1

....4.1.2 IWD-1220.2

....49 49.4.2 Component/System Examination Development 49 4.2.1 Category D-A.............

4.2.2 Category D-B..;..........

4.2.3 Category D-C.............

4.2.4 System Pressure Tests~~~~~~~~~~~~~~~~49 51 53 54 5.0 CLASS 1, 2, and 3 COMPONENT SUPPORTS 56 5.1 ASME Code Exemptions Employed<<~<<~56 5.2 Support Examination Development 56.2.1 Category F A 5 5.2.2 Category F-B 5.2.3 Category F-C.......56 56 56 5.3 Narrative Discussion 56 5.3.1 Category F-A, F-B, F-C.........................

57 6.0 AUGMENTED EXAMINATIONS 59 6.1 lass 1..................

C 59 6.1.1 Reactor Coolant Pump..........................

6.1.2 Steam Generator Tubes.........................

59 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...................

6.1.4 NRC Bullefin 88-11........................

6.1.5 LER 93-04...............................

~~~~~59~~~o~60~~~~~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 8.4.2 Class 2 Components 66 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 8.9.2 Class 2 8.9.3 Class 3 8.9.4 Component Supports~~~~0~~~~~~~~~~~~~~~~~68 69 69 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 9~e.2 Color Couing 74 10.0 REPAIRS, REPLACEMENTS and MODIFICATIONS

...............

78 10.1 Repairs.................

78 10.1.1 Repair Operations

......10.1.2 Prc"sure Testing.......10.1.3 Baseline Examinations 78 78 78 0.2 Replacements

.....................................

1 79 10.2.1 Replacement Operations

.10.2.2 Engineering Approval.'.10.2.3 Preservice Examinations

.79 79 79 1 A C'e 0.3 Modifications 80 1 0.4 Evaluation

.........................................

80 O.G Access 1 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 General...........................

1 82 11.2 Inservice Inspection Summary Report...82 1.3 Cover Sheet.......................................

1 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.................................

TABLE 8-2 CLASS 1 ACCEPTANCE STANDARDS.................

TABLE 8-3.CLASS 2 ACCEPTANCE STANDARDS.................

TABLE 8-4 CLASS 3 ACCEPTANCE STANDARDS.................

TABLE 8-5 COMPONENT SUPPORT ACCEPTANCE STANDARDS 71 72....72 73 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.......APPENDIX D Class 1 Support Summary Tables APPENDIX E Class 2 Support Summary Tables APPENDIX F Class 3 Support Summary Tables~~~~~~~~~~~~~~~~~93 e e~~r~~r e r r~~~~~~~~~~94~~~~~~~~~r~~~~~~~~r~~96~~~e~~e e~~~~~~~~r~r~~95 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 No.DATE AFFECTED REASON FOR REVISION PAGES July 24, 1993 Enfire Document Updated Inservice Inspection 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 ANSI'ASME B&PV CCW CCW CEDM CFR CH CHR CPS CRS CRV CTMT SPRAY CVCS CW ECCS ECT ESI FPL FPS FSAR HPSI HS HX Authorized Nuclear Inservice Inspector American Nuclear Standard Institute American Society of Mechanical Engineers Boiler&Pressure Vessel Code Branch Connection Component Cooling Wafer Counterclockwise Confrol Element Drive Mechanism Code of Federal Regulafions Charging System Containment Heat Removal Code Programs Section Code Required Surface Code Required Volume Containment Spray Chemical&Volume Control Sysfem Clockwise Emergency Core Cooling System Eddy Current Testing (Examination)

Equipment Support and Inspections Florida Power&Light Company Fuel Pool System Final Safety Analysis Report Feedwater System High Pressure Safety Injection High Stress Heaf Exchanger Page 10 of 272

SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 ID IE'S/1ST JPN LER'LPSI LS MOV MSIV MS MT NIA NDE NPS OD PDS P&ID PSI PIO PSL-2 PT QA QC QP PZR RCS RCP RHR RPV SD Inside Diameter Inspection and Enforcement Inservice Inspection Inservice Testing Juno Nuclear Engineering License Event Report Low Pressure Safety Injection Long Seam Motor Operated Valve Main Steam Isolation Valve Main Steam System Magnetic Particle Testing (Examination)

Not Applicable Nondesfrucfive Examination Nominal Pipe Size Outside Diameter Program Boundary Drawings Piping and Instrumentation Diagram Preservice Inspection Part of St.Lucie Unit 2 Liquid Penetrant Testing (Examination)

Quality Assurance Qualify Confrol Quality Procedure Pressurizer Reactor Coolant System Reactor Coolant Pump Residual Heat Removal Reactor Pressure Vessel Structural Discontinuity Page 11 of 272 SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 SDC SDCHx SG SRP SIS'TE USNRC UT Shutdown Cooling Shutdown Cooling Heat Exchanger Steam Generator Standard Review Plan Safety Injection System Thickness of Component, Pipe, etc.Terminal End United States Nuclear Regulatory Commission Ultrasonic Testing (Examination)

~Visual Testing (Examination)

Page 12 of 272 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.Page f3 of 272 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.Page 14 of 272

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.'EGULATORY AUTHORITY-a federal government agency, such as the United 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.Page 15 of 272

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 ifitisin the 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.

VARIABLE SPRING 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.Page 16 of 272 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.

Page 17 of 272 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, 2000 August 8, 1996 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 1.26 1.65 1.83 1.150 Reactor Coolant Pump Flywheel Integrity Revision 1, August 1975 Quality Group Classifications and Standards for Water-Steam, and Radioactive-Waste-Containing Components of Nuclear Power Plants, Revision 3, February 1976 Materials and Inspections for Reactor Pressure Vessel Closure Studs, October 1973 lnservice Inspection of Pressurized Water Reactor Steam Generator Tubes, Revision 1, July 1975 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 N-460 Calibration Block for Angle Beam Ultrasonic Examination of Large Fittings in accordance with Appendix Il/-3410.Alternative E'xamination Coverage for Class 1 and Class 2 Welds.N-481 N-498 Alternative Examination Requirements for Cast Austenitic Pump Casings.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).

Page 20 of 272 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 QUALITY GROUP 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'ffect fhe overall system classification by which the applicable rules of Section XI are determined.

1.6.7 Piping Penetrating Containment The portions of piping 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 Interval.Inspection Period Calendar Years of Plant Service Within fhe Interval Minimum'aximum Examination Examination Completed,%=-.Credited,%(Note (1)g St.Lucie Unit 2 Second Inservice'nspection Interval 10 16 50 100 34 67 100 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-2-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.All examinations 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 Alloy SOO 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-1

-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-2-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 of Examination

-100%surface exam of support 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, All Pressure 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 will perform 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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 Tubin g 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 rin g 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-All volumetric 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 of SG-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'ccordance with system pressure test program.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-1-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-2-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)(b)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);"\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'pecifications and/or the Pump and Valve (IST)program, a VT-2 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'he system test pressure.(b)A S stem H drosfafic Tes will be 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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)(c)S stem Functional Test NVA-5211/)-

For those systems or portions of systems not required to operate during normal'eactor operation, but for.which periodic system or component=functional fesfs are performed as required by the Plant Technical Specifications and/or the Pump and Valve (IST)p g V7..2*i ti ip,f d th*t~d~hi dd i gth yt p tU ti ft 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 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 will perform 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, durin g 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 will perform 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.Page 60 of 272 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 will continue 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;\Page 61 of 272 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.Page 62 of 272 SECOND INSPECTION INTERVAL PSL-200 INSERVICE.INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 TABLE 7-1 RELIEF REQUEST STATUS Relief Request Number and Description 1 Reactor Vessel&Closure Head pressure retaining welds Relief Requested Incomplete Code required Volume Sfafus (include a document reference if approved)Essenfially same as first Ten Year interval 2 Steam Generator Removed, only one weld required to be pressure retaining welds examined in second interval, no relief required..3 Pressurizer.

Full Penetration welds of Nozzles fo Vessels 4 Intersecting longifudinal welds of circumferential welds 5 RCP Safe End to Pipe welds and Nozzle to Safe end welds>4" 6 Pressure retraining welds in Piping>4" Incomplete Code required Volume Addifional surface examination requirements Incomplefe Code required Volume Incomplete Code required Volume Essentially same as first Ten Year interval New Request for Relief Essentially same as first Ten Year inferval Essenfially same as 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 Welds in Shutdown Cooling Heat exchanger 9 Pressure Retaining Nozzle Welds in Steam Generator 10 Pressure retaining Welds in Piping lncomplefe Code required Volume Incomplete Code required Volume Incomplete Code required Volume or Surface Essenfially same as first Ten Year interval Essenfially-same as first Ten Year interval Essentially same as first Ten Year interval 12 Removed, nof required per IWC-1221 Not Used Page 63 of 272 SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 Relief Request Number and Description 13 UT Calibration Blocks 14 RPV and Closure Head Steam Generators Pressurizer and.RC Pumps-Welds, Bolting, Integral Attachments 15 Alternate Volumetric Exams of Outlet Nozzle Safe Ends 16 Article IWA-4000 Repair Procedures Article IWA-6000 Records and Reports Article IWA-7000 Replacement 17 Reactor Pressure Vessel Nozzle to Vessel Welds Relief Requested Deviations of Cal Blocks from Appendix III requirements Percentage requirements of IWB-2412 Sequence of component exams consistent with First Interval Volumetric Exams in lieu of required surface examinations Proposed Alternate for preparation and submiffal of summary reports Reestablish new 10-year Interval Examination requirements for the Reactor Pressure Vessel Status (include a document reference if approved)Essentially same as first Ten Year interval New Request for Relief Essentially same as first Ten Year interval New, Request for Relief New Request for Relief 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 f laws/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.Page 65 of 272 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 will revert 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 III Edifion 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.If the 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 If acceptance 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.If the examinations for thatinspection item are not scheduled in the subsequent period, fhe mostimmediafe period containing scheduled examinations shall be taken as the subsequent period.Page 68 of 272 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 to'nclude all welds, areas, or parts of similar.design, size, and function.Additional examinations will be 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 will be 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 will be 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 will be 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 MINIMUM THREAD 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 will be 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 8-1-CORRECTIVE ACTION DEVIATION Damaged, missing, corroded or loose cotter pins and retainers Mild rust/corrosion on spherical bearings Gross rust/corrosion on spherical bearing Mild rust/corrosion on hanger/support-Paint on tags, indicators etc.Foreign material, corrosion on load pin Spherical bearing Is loose or dislodged Misalignment of hanger/support Standard nut, used as a lock nut, does not have full thread engagement Spherical bearing Is frozen CORRECTIVE ACTION Replace with new cotter pin or retainer or tighten as necessary Clean and lubricato with graphite Replace spherical bearing 8 restako Clean and reinspect for furthor degradation.

Repaint support Remove paint with solvent Clean toad pin with scotch brito pad or equivalent.

Whip clean and apply a light film of machine oil Reseat spherical bearing and rostake loosen pipe clamp 8 realign In accordance with original drawing.lock nut shall havo at least 50%thread engagement.

Replace as necessary Lubricate and work bearing until looso.Repiaco if necessary REEXAMINATION Yos Yes No No Yes Yes No Yes No Yos Page 71 of 272 SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE July 24, 1993 TABLE 8-2-CLASS 1 ACCEPTANCE STANDARDS EXAMINATION CATEGORY B-A B-B B-D B-E B-F, B4 B4-1 BN-2 B-H, B-K-1 B-L-1, B-M-1 B-L-2, B-M-2 B-N-1 B-N-2 B-N4 B-P B-Q COMPONENT OR PART EXAMINED Welds in Reactor Vessels Welds in Other Vessels Vessel Nozzle Weids Partial Penetration weids In Vessels Dissimilar and Similar Metal Welds fn Piping Bolting>2" dia.'-Bolting (2" dia.Integral Attachments for Piping, Valves, Pumps&Vessels Welds in Pumps&Vaiveh Pump Casings 8 Valve Bodies Intorlor Surfacos&Internal Components of Reactor Vessels Control Rod Drive Housing Welds Pressuro Retaining Boundary<Steam Generator TubIng ACCEPTANCE STANDARD IWB4510 IWB4510 IWB4512 IWB4522 IWB4514 IWB4515/3517 IWB4517 IWB4516 IWB4518 IWB4519 IWB4520 IWB4 523 IW 84522 IWB4 521 TABLE 8-3-CLASS 2 ACCEPTANCE STANDARDS EXAMINATION CATEGORY C-A C-B C-D C-F-1,C-F-2 C-H COMPONENT OR PART EXAMINED Welds in Pressure Vessels Nozzlo Welds In Vessels Integral Attachments for Vosseis, Piping, Pumps and Valves Bolting Welds In Piping Welds In Pumps and Valves Pressure Retaining Components ACCEPTANCE STANDARD IWC4510 IWC4511 IWC4512 IWC4513 IWC4514 IWC4515 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 CATEGORY D-A D-B D-C COMPONENT OR PART EXAMINED Pressure Boundary (VT-2)Integral Attachments (VT4)Pressure Boundary (VT-2)Integral Attachments PTQ)Pressure Boundary (VT-2)Integral Attachments (VT4)ACCEPTANCE STANDARD"No Leakage*Mfg.Code 8 Applicable Standards"No Leakage'Mfg.Code&Appllcablo Standards IWA4250'Mfg.Code&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 8-5-COMPONENT SUPPORT ACCEPTANCE STANDARDS EXAMINATION CATEGORY F-A COMPONENT OR PART EXAMINED Supports ACCEPTANCE STANDARD 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 9-1-PROGRAM BOUNDARY DRAWINGS Drawing Number 02-PB-01 02-PB-OIA 02-PB-02 02-PB-02A 02-PB-03 02-PB-03A 02-PB-04 02-PB-05 02-PB-05A 02-PB-05B 02-PB-06 02-PB-06A 02-PB-07 02-PB-08 02-PB09 02-PB-10 Reference Drawing 2998-G-078 SHT.110 2998-G-078 SHT.107 2998-G-078 SHT.108 2998-G-078 SHT.109 2998-G-078 SHT.120 2998-G-078 SHT.122 2998-G-078 SHT.121 2998-G-078 SHT.121 2998-G-078 SHT.122 2998-G-078 SHT.130 2998-G-078 SHT.130 2998-G-078 SHT.130 2998-G-078 SHT.131 2998-G-078 SHT.131 2998-G-078 SHT.140 2998-G-078 SHT.153 2998-G-078 SHT.160 2998-G-078 SHT.163 2998-G-079 SHT.1 2998-G-079 SHT.2 Title REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMICAL&VOLUME CONTROL SYSTEM CHEMICAL 8 VOLUME CONTROL SYSTEM CHEMICAL&VOLUME CONTROL SYSTEM CHEMICAL&, VOLUME CONTROL SYSTEM ,CHEMICAL&VOLUME CONTROL SYSTEM SAFETY INJECTION SYSTEM SAFETY IN JECTION SYSTEM SAFETY IN J ECTION~SYSTEM SAFETY IN J ECTION SYSTEM SAFETY INJECTION SYSTEM FUEL POOL COOLING SYSTEM SAMPLING SYSTEM WASTE MANAGEMENT MAIN STEAM 8 AUXILIARY STEAM SYSTEM Page 75 of 272 SECOND INSPECTION INTERVAL PSL-200 INSERVICE INSPECTION REVISION 0 PROGRAM PLAN AND SCHEDULE Ju/y 24, 1993 TABLE 9-1-PROGRAM BOUNDARY DRAWINGS Drawing Number 02-PB-11 02-PB-11A 02-PB-'I2 02-PB-12A 02-PB-1 2B 02-PB-13 02-PB-13A 02-PB-1 3B 02-PB-14 02-PB-15 02-PB-16 02-PB-17 02-PB'-1 7A Reference Drawing 2998-G-080 SHT.2 2998-G-080 SHT.2 2998-G-082 2998-G-082 2998-G-082 2998-G-083 2998-G-083 2998-G-083 2998-G-084 2998-G-085 SHT.1 2998-G-085 SHT.2 2998-G-086 2998-G-088 2998-G-088 Title FEEDWATER AND CONDENSATE SYSTEM FEEDWATER AND CONDENSATE SYSTEM CIRCULATING

&INTAKE COOLING WATER SYSTEM CIRCULATING

&INTAKE COOLING WATER SYSTEM CIRCULATING

&INTAKE COOLING WATER SYSTEM COMPONENT COOLING SYSTEM COMPONENT COOLING SYSTEM COMPONENT COOLING SYSTEM FIREWATER, DOMESTIC 8 MAKE-UP SYSTEMS SERVICE&INSTRUMENT AIR SYSTEMS SERVICE 8 INSTRUMENT AIR SYSTEMS CONTAINMENT SPRAY&REFUELING WATER SYSTEMS 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 9-1-PROGRAM BOUNDARY DRAWINGS Drawing Number 02-PB-17B 02-PB-18 02-PB-19, 02-PB-20 02-PB-20A 02-PB-21 02-PB-22 Reference Drawing 2998-G-088 2998-G-092 2998-G-862 2998-G-078 SHT.132 2998-G-078 SHT.132 2998-G-078 SHT.111 2998-G-078 SHT.150 Titie CONTAINMENT SPRAY 8 REFUELING WATER SYSTEMS MISCELLANEOUS SAMPLING SYSTEM HVAC SAFETY iNJECTION SYSTEM SAFETY IN JECTION SYSTEM REACTOR COOLANT PUMP SAMPLING SYSTEM Page 77 of 272

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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 Components ComponentsSection III Section III Section Vill 71S73 71S73 71S73 123 123 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:

Component or ppurtenance Manufacturer or Installer Manufacturer or Installer Serial No.State or Province No.National 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: OWNER OR OWNER'S DESIGNEE, TITLE 199 CERllFICATE OF INSERVICE INSPECTION COMMtSSION NUMBER Inspector's Signature National Board, State, Province, and Endorsements 19 Date: 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.

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 SHEET'F 1.OWNER: Florida Power and Light Company DATE: P.O.Box 14000 Juno Beach, Florida 33408 2.PLANT: St.Lucie Plant 6501 South A1A Jensen Beach, FL.34t;57 VNIT¹: 2 (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 Component Name of Manufacturer Manufacturer Serial Number National Board No.Other Identification Year Built Replaced Repaired or Replacemont ASME Codo Stamped 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 Date, 19 OWNER OR OWNERS'ESIGNEE, TITLE 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 Owners'eport in accordance with the requirements of the ASME Code,Section XI.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 National Board, State, Inspector's Signature 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 Plant: Eddy Current Summary of Results Examination Dates: Through Steam Generator Total Tubes Inspected Total Ind.z 20%to 39%, Total Ind.>40%to 100%Total Tubes Plugged as Preventive I"laintenance Total Tubes Plugged Location of Indications Steam Generator U Bends DHB to DCB Egg crates 1to7 H/L C/L Partial Supports 8 and 9 H/L C/L.Top of Tube Sheet to N Eggcrate 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: Date: Prepared By: S/G Eddy Current Coordinator 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 PLANT: Steam Generator Eddy Current Examination Results EXAMINATION DATES: THROUGH ROW LINE%TUBE WALL'ENETRATION

=ORIGIN LOCATION 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 REVISION: 0 ST.IUCIB NUCLEAR PLANT UNIT 2 INSERVZCE INSPECTION PLAN FOR THE SECOND INTERVAL CLASS 1 SECTION XZ SUNMARY TABLE A PAGE: 1 CODE EDITION: 89 CATEGORY B-A-PRESSURE RETAINING WELDS IN REACTOR VESSEL SEC.XZ ITEM¹ITEM DESCRIPTION ZONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED 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 VESSEL 001 0%100%100%Includes 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 0¹100%100%of all welds, deferral permissible VOLUiiRIC 002 REACTOR PRESSURE 001 VESSEL CLOSURE HEAD 1 1 1 0 100%0 0 0 0 100k 100'C ITEM TOTAL 3 3 1 0 33%2 0 100%0 0 100%81.22 MERIDIONAL HEAD WELDS VOLUiiRIC 001 REACTOR PRESSURE 001 VESSEL 6 6.0 0 0¹6 0 0 0 Accessible length 100%100%of all welds, deferral permissible VESSEL CLOSURE HEAD 100%VOLUiiRZC 002 REACTOR PRESSURE 001 4 4 4 0 0 0 100%0 0 200%ITEM TOTAL 10 10 4 0 40%6 0 100%0 0 100't BID 30 SHELL-TO-FLANGE WELD VOLUMETRIC 001 REACTOR PRESSURE 001 VESSEL 1 1 0 0 0%0 100%0 0 100%of weld, 200%Partial Deferral Permissible, See Code footnote (3)B1.40 HEAD-TO-FLANGE WELD VOLUMETRIC 002 REACTOR PRESSURE 001 SURFACE VESSEL CLOSURE HEAD 1 1 1 0 100%0 0 100%0 0 100%of weld, 100t Partial Deferral Permissible, See footnote<3) 0 DATE: 07/24/93 REVISZON: , 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN'FOR THB SECOND INTERVAL CLASS 1 SECTION XZ SUYMARY TABLE A PAGE: 2 CODE EDITION: 89 CATEGORY B-A-PRESSURE RETAINING WBLDS IN REACTOR VESSEL SEC.XI ITEM¹ZTEM DESCRIPTION ZONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER CONTENTS CATEGORY TOTAL 24 24 6 0 18 0 25't 100%0 0 100't DATE: 07/24/93 REVISION: 0 ST.LUCIB NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 1 SECTION XI

SUMMARY

TABLB A PAGE: 3 CODE EDITION: 89 CATEGORY 8-8-PRESSURE RETAINING WFLDS IN VESSELS OTHER THAN REACTOR VESSELS SEC.XZ ITEM¹ITEM DESCRIPTION ZONE REL¹OF NO.¹OF COMPONENTS SCHEDULED/COi4PLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER CO)IENTS 82.11 PRESSURIZER-CIRCUMFERENTIAL VOLUMETRIC 005 PRESSURIZER SHELL-TO-HEAD WELDS 014 2 2 2 0 100 t 0 0 100t 0 0 both welds, 100t essentailly 100t of the weld length 82.12 PRESSURIZER-LONGZTUDINAIi SHELL-TO-HEAD WELDS VOLUMETRIC 005 PRESSURIZER 014 4 2 2 0 100t 0 0 10 0t'0 1 foot of one 100t weld, Per head, that intersects the circ.weld.82.31 STEAM GENERATORS (PRIMARY SIDE)-CIRCUMFERENTIAL HEAD WELDS VOLUiiRZC 003 STEAN GENERATOR 0 2A PRIX)ARY SIDE 014 5 1 0 0 Ot 0 0 Ot 1 0 One weld per 100t head, 100t weld length, limited One Vessel VOLUiiRIC 004 STEAN GENERATOR 0 5 0 0 0 0 0 0 0 28 PRIMNARY SIDE III**1 t 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 SIDE)-MERIDIONAL HEAD WELDS 2A PRZMNARY SIDE 014 9 2 0 0 Ot 0 0 2 0 One weld per 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 SIDB)-TUBBSHEBT-TO-HEAD WELD 2A PRIYNARY SIDE 82.40 STEAM GENERATORS (PRIMARY VOLUMETRIC 003 STEAM GENERATOR 014 1 1 0 0 0 0 1 0100tof weld 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 RBVISZON: 0 ST, LUCZE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN FOR THB SECOND INTERVAL CLASS 1 SECTION XZ S~iY TABLE A PAGE: 4 CODE EDITION: 89 CATEGORY B-B-PRESSURE RETAINING OLDS IN VESSELS OTHER THAN REACTOR VESSELS ASME SEC.XI ITEM¹ITEN DESCRIPTION ZONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION

'EQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS ITEM TOTAL 2 1 0'0%0 0 0%1 0 100%CATEGORY TOTAL 36 8 4 0 0 0 4 0 50%50%100%

DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PIAN'FOR THB SECOND INTERVAL CLASS 1 SECTION XI

SUMMARY

TABLE A PAGB: 5 CODE EDITION: 89 CATEGORY B-D-FULL PENETRATION WELDS OF NOZZLES IN VESSELS INSPECTION PROGRAM B ASME SEC.XI ITEM))ITEM DESCRIPTION ZONE RBL))OP NO I OF COMPONENTS SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS RADIUS SECTION VESSEL B3.100 REACTOR VESSEL-NOZZLE INSIDE VOLUMETRIC 001 REACTOR PRESSURB 014 6 6 0 0 0't 6 0 100t 0 0 100t All Nozzlcs, 25t to 50t 1st period, Remainder end Interval B3.110 PRESSURIZER-NOZZIE-TO-VESSEL VOLUMETRIC 005 PRESSURIZER WELDS 003 6 6 6 0 0 0 014 100t 100t 0 0 All Nozzles, 25t 100t to 50t 1st Period, Remainder end Interval.B3.120 PRESSURIZER-NOZZLE INSIDE VOLUMETRIC 005 PRESSURIZER RADIUS SECTION 0 6 6 6 0 0 0 0 0AllNozzles, 25t 014 100t 100t 100t to 50t 1st Period, Remainder end Interval.B3.130 STEAM GENERATORS (PRIMARY SIDE)-NOZZLE-TO-VESSEL WELDS VOLUMETRIC 003 STEAM GENERATOR 014 3 3 0 0 0 0 2A PRIMMARY SIDE Ot Ot 3 0 All Nozzles, 25t 100't to 50t 1st Period, Remainder end Interval.VOLUMETRIC 004 STEAM GENERATOR 003 2B PRIYNARY SIDE 3 3 0 0 Ot 0 0 Ot 3 0 100t ITEM TOTAL 6 6 0 0 0 0 6 0 Ot Ot 100t B3.140 STEAM GENERATORS (PRIMARY SIDE)NOZZLE INSIDE RADIUS SECTION VOLUMETRIC 003 STEAM GENERATOR 014 2A PRIYMARY SIDB 3 3 0 0 Ot 0 0 Ot 3 0 All Nozzlcs, 25t 100t to 50t 1st Period, Remainder end Interval.VOLUMETRIC 004 STEAM GENERATOR 0 2B PRI~~Y SIDE 3 3 0 0 Ot 0 0 3 0 100t 6 6 0 0 Ot 0 0 Ot 6 0 100t B3.90 REACTOR VOLUMETRIC 001 REACTOR PRESSURE 001 t VESSEL NOZZM-TO-VESSEL WELDS VESSEL 0 6 6 0 0 Ot 6 0 100t 0 0 All Nozzlcs, 25t 100t to 50t 1st Period, Remainder cnd Interval, DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CLASS 1 SECTION XI SUiiRY TABLE A PAGE: CODE EDITION: 89 CATEGORY B D FULL PENETRATION WELDS OF NOZELES IN VESSELS INSPECTION PROGRAM B SEC.XZ ITEM¹ITEM DESCRIPTION

¹OF COMPONENTS ZONE REL¹OF NO.SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS CATEGORY TOTAL 36 36 12 0 33't 12 0 66%12 0 100%

DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CLASS 1 SECTION XI SUNCKY TABLE A PAGE: 7 CODS EDITION: 89 CATEGORY B-F-PRESSURE RETAINING DISSIMILAR METAL WFLDS SEC.XZ ITEM¹ITEM DESCRIPTION

¹OF COMPONENTS ZONE REL¹OF NO.SCHEDULED/COMPLETED 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 WELDS)i 4 INCHES NOMINAL PIPE SURFACE PIPING, LOOP A SG-2A TO RCP-2A2 1 1 1 0 100't 0 0 100t 0 0 All welds.100t VOLUMETRIC 009 REACTOR COOLANT 005 SURFACE PIPING, LOOP A FROM RCP-2A2 TO RPV 1 0 0 Ot 1 0 100t 0 0 100\SURFACE PIPZNG, LOOP B SG-2B TO RCP-2B1 100t VOLUMETRIC 010 REACTOR COOLANT 005 1 1 1 0 0 0 100t 0 0 100t VOLUMETRIC 011 REACTOR COOLANT 005 SURFACE PIPING, LOOP B FROM RCP-2B1 TO RPV 1 1 1 0 100't 0 0 1008 0 0 100t 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 SURFACE PIPING, LOOP A FROM RCP-2A1 TO RPV 0 0 0 0 1 0 Ot Ot 100t SURFACE PIPING, LOOP B SG-2B TO RCP-2B2 0't VOLUiiRZC 014 REACTOR COOLANT 005 1 1 0 0 0 0 Ot 1 0 100't SURfACE PIPING, LOOP B RCP 2B2 TO RPV Ot VOLUMETRIC 015 REACTOR COOLANT 005 1 1 0 0 0 0 Ot 1 0 100t VOLUMETRIC 016 PRESSURIZER SURFACE SURGE LINE 1 1 0 0 Ot 1 0 100t 0 0 100t VOLUMETRIC 021 LOOP 2A1 SAFETY 0 SURFACE INJECTION PIPING, INSIDE CTMT 1 1 0 0 0't 0 0 Ot 1 0 100 t VOLUMETR C 022 LOOP 2A2 SAFETY 0 SURFACE INJECTZON PIPING, INSIDE CTii'1 0 0 Ot 0 0 Ot 1 0 100t DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 1 SECTION XZ SUGARY TABLE A PAGE: 8 CODE EDITION: 89 CATEGORY B-F PRESSURE RETAINING DISSIMILAR METAL WELDS ASME SEC.XI ZONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED ITEM¹ITEM DESCRIPTION EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS WELDS)>>4 ZNCHBS NOMINAL PIPE SURPACE SIZE INJECTION PIPING, INSIDE CRK B5.130 PIPING-DISSIMILAR METAL BUTT VOLRKTRIC 023 LOOP 2B1 SAFETY 0 1 1 0 0 Ot 0 0 Ot 1 0 All welds.100t VOLUMETRIC 024 LOOP 2B2 SAFETY 0 SURFACE INJECTION PIPING, INSIDE CIST 1 1 0 0 Ot 0 0 1 0 Ot 100t VOLUiiRIC 028 LOOP 2B SHUTDOWN 0 SURFACE COOLING LINE 1 1 0 0 0 0 1 0 Ot Ot 100t VOLUMETRIC 029 LOOP 2A SHUTDOWN 0 SURFACE COOLING LINE 1 1 1 0 100t 0 0 0 0 100t 100t ITEM TOTAL 15 15 5 0 33t 2 0 46t 8 0 100t WELDS (4 ZNCHES NOMINAL PIPE SURFACE SIZE PIPZNG, LOOP A FROM RPV TO SG-2A B5.140 PIPING-DISSIMILAR METAL BUTT VOLUMETRIC 006 REACTOR COOLANT 1 1 1 0 100t 0 0 100t 0 0 All welds.100t SURFACE 026 LOOP 2B1 SPRAY 0 LINE 1 1 0 0 Ot 1 0 100 t 0 0 100t SURFACE 027 LOOP 2B2 SPRAY 0 LINE 1 1 0 0 Ot 0 0 Ot 1 0 100t SURFACE 030 PRESSURIZER 0 AUXILIARY SPRAY 1 1 1 0 100t 0 0 100t 0 0 100t SURFACE 031 L7IARGING LINE TO 0 LOOP 2B1 1 1 0 0 Ot 1 0 100t 0 0 100t SURFACE 032 CHARGING LINE TO 0 LOOP 2A2 1 1 0 0, 1 0 0 0 Ot 100t 100t V SURFACE 033 LOOP 2A1 PRIMARY 0 DRAIN 1 1 1 0 100t 0 0 100t 0 0 100t DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CLASS 1 SECI'ION XI SUYNARY TABLE A PAGE: 9 CODE EDITION: 89 CATEGORY B-P-PRESSURE RETAINING DISSIMILAR METAL WELDS SEC.XI ITEM¹ITEM DESCRIPTION ZONE EXAM METHOD SYSTEM DESCRIPTION

¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED REQ COMP,REQ 1ST PER 2ND PER 3RD PER COMMENTS B5.140 PIPING-DISSIMILAR METAL BUTT SURFACE WELDS (4 INCHES NOMINAL PIPE SIZE 034 LOOP 2A2 PRIMARY 0 DRAIN 1 1 0 0 0%'0 0 0 All welds.100t 100t SURFACE 035 LOOP 2B1 PRIMARY 0 DRAIN 1 1 0 0 0't 0 0 Ot 1 0 100 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 30t 4 0 3 0 70t 100t B5.40 PRESSURIZER-NOZZLE-TO SAFE END VOLUMETRIC 005 PRESSURIZER BUTT WELDS)>>4 INCHES NOMINAL SURFACE PIPE SIZE 0 3 3 3 0 0 0 0 0 All welds.014 100t 100t 100't VOLUMETRIC 016 PRESSURIZER SURPACE SURGE LINE 014 1 1 1 0 0 0 0 0 100t 100't 100t VOLUiiRIC 025 COMBINED SURFACE PRESSURIZER SPRAY LINE 0 1 1 1 0 0 0 0 0 100t 100t 100t VOLUMETRIC 038 PRESSURIZER SURFACE RELIEF LINE 014 1 1 1 0 0 0 0 0 100t 100t 100t 6 6 6 0 100t 0 0 100t 0 0 100t CATEGORY TOTAL 31 31 14 0 6 0 11 0 64t 100t DATE: 07/24/93 REVZSIONr 0 ST.LUCIE NUCLEAR PLANT UNIT 2 ZNSERVZCE INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 1 SECTION XI

SUMMARY

TABLE A PAGEr 10 CODE EDITION: 89 CATEGORY B-G 1-PRESSURE RETAINING BOLTING GREATER THAN 2 INCHES IN DIAMETER SEC.XZ ITEM¹ITEM DESCRZPTZON ZONE EXAM METHOD SYSTEM DESCRZPTZON

¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED REQ CNP REQ 1ST PER 2ND PER 3RD PER CO%ANTS VESSEL 0%B6.10 REACTOR VESSEL-CLOSURE HEAD SURFACE 001 REACTOR PRESSURE 0 1 1 0 0 0 0 Ot 1 0 100%All nuts, deferral permissible footnote (6)B6.180 PUMPS-BOLTS AND STUDS PUMP 2Al l I****8 VOLUMETRIC 017 REACTOR COOLANT 0 1 0 0 0 0 0 t***~t't 0 0 Exams limited to tttttti components selected under Cat.B-L-2.VOLUiiRIC 018 REACTOR COOLANT 0 PUMP 2A2 ttttttrr~tttttrrr*lit*~8 1 0 0 0 0 0 0 0 VOLUiiRIC 019 REACTOR COOLANT 0 PUMP 2B1 1 1 1 0 100%0 0 100%0 0 100%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 0 100't 0 0 100%0 0 100%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 PUMP 2A2 1 0 0 0 0 0 ttltttt ttttttg 0 0 I~ttt t%VISUAL 019 REACTOR COOLANT 0 PUMP 2B1 0 0 08 100%100%1, 1 0 0 1 0 VISUAL 020 REACTOR COOLANT 0 PUMP 2B2 0 0 0 0 0 0 0 ll~ttt%Ill*~t'0 lttttt%ITEM TOTAL 4 1 0 0 0%0 100%0 0 100%'B6.200 PUMPS NUTS, BUSHZNGS, AND WASHERS VISUAL 017 REACTOR COOLANT 0 PUMP 2A1 1 0 0 0 t\tttt$0 0 tttttt$0 0 Exams limited to it'll\components selected by Cat.B-L-2~

DATE: 07/24/93 REVZSZON: 0 ST.LUCIE NUCLEAR PLANT UNZT 2 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CLASS 1 SECTION XI

SUMMARY

TABLE A PAGE: 11 CODE EDITION: 89 CATEGORY B-G-1-PRESSURE RETAINING BOLTING GREATER THAN 2 INCHES IN DIAMFTER ASME SEC.XI ITEM¹ITEM DESCRIPTION ZONE REL¹OF NO.¹OF COMPONENTS SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COF34ENTS B6.200 PUMPS NUTS, BUSHINGS, AND WAS HERS PUMP 2A2 II II~*$*1*4*1$I0 l*Ie 8 components selected by Cat.B-L-2.VISUAL 018 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 Exams limited to VISUAL 019 REACTOR COOLANT 0 PUMP 2B1 100%100%100%1 1 1 0 0 0 0 0 VISUAL 020 REACTOR COOLANT 0 PUMP 2B2 1 0 0 0 0 0 4401 11%~110~0'C 0 0 14*1St)ITEM TOTAL 4 1 1 0 100%0 0 100%0 0 100%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 FLANGE VOLUMETRIC 001 REACTOR PRESSURE 014 1 1 0 0 1 0 0 0 All threads in VESSEL 0%100%100%flange, when dissassembled.

B6.50 REACTOR VESSEL-CLOSURE WASHERS, BUSHINGS VISUAL 001 REACTOR PRESSURE 0 1 1 0 0 0 0 1 0 Deferral 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 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN FOR THB SECOND INTERVAL CLASS 1 SECTION XZ

SUMMARY

TABLE A PAGE: 12 CODE EDITION: 89 CATEGORY B-G 2 PRESSURE RETAINING BOLTING 2 INCHES AND LESS IN DIAMETER ASME SEC.XI ITEM 9 ITEM DESCRIPTION ZONE EXAM METHOD SYSTEM DESCRZPTION E OP COMPONENTS REL 8 OF NO.SCHEDULED/COMPLETED REQ COMP REQ 1ST PER 2ND PER 3RD PER COKKNTS B7.10 REACTOR VESSEL-BOLTS STUDS'ND NU1'S VISUAL 002 REACTOR PRESSURE 001 8 8 2 0 4 0 2 0 VESSEL CLOSURE HEAD 25%75%100%All bolts, studs and nuts.B7.20 PRESSURIZER-BOLTS, STUDS, AND VISUAL NUTS 005 PRESSURIZER 014 2 2 2 0 0 0 0 0 100%100%100'll bolts, studs and nuts.B7.30 STEAM GENERATORS-BOLTS, STUDS, VISUAL AND NUTS 003 STEAM GENERATOR 014 4 4 0 0 0 0 4 0 All bolts, studs 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't 0 0 4 0 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 COOLING LINE 2 1 0 0 0%0 1008 0 0 100%VISUAL 029 LOOP 2A SHUTDOWN 0 COOLING LINE 2 1 0 0 0%100%100\1 0 0 0 VZSUAL 033 LOOP 2A1 PRIMARY 0 DRAIN 1 1 1 0 100%0 0 0 0 100%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 ZNJECTION PZPING, INSIDE CTMT 3 3 0 0 0%0 0 3 0 All bolts, studs 0%100%and nuts.Limited to Exam Cat.B-M-2.

DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CLASS 1 SECTION XI SU>WARY TABLE A PAGE: 13 CODE EDITION: 89 CATEGORY B G 2-PRESSURE RETAINING BOITING 2 INCHES AND LESS IN DIAMETER SEC.XZ ITEM¹ITEM DESCRIPTION ZONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED 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 INJECTION PIPING, INSIDE CIÃI'3 0 0 3 0 0 0 0%100%100%All bolts, studs and nuts.Limited to Exam Cat.B-M-2.VZSUAL 023 LOOP 2B1 SAFETY INJECTION PIPING, 0 INSIDE CIA'3 0 0 1 0 2 0 0%33%l.00%VISUAL 024 LOOP 2B2 SAFETY INJECTION PZPZNG, INSIDE CTMT 3 3 3 0 100i'0 0 0 100%100¹VISUAL 028 LOOP 2B SHUTDOWN COOLING LINE 0 5 4 0 0 0%3 0 75%1 0 100'ISUAL 029 LOOP 2A SHUTDOWN COOLING LINE 3 2 2 0 100%0 0 100%0 0 100%VISUAL 037 LETDOWN LINE FROM LOOP 2B1 0 3 1 0 0 1 0 0 0 0%100%100%VISUAL 038 PRESSURIZER RELIEF LINE 0 4 4 0 0 0 0 4 0 0%08 100%ITEM TOTAL 27 23 5 0 21%8 0 10 0 56%100%CATEGORY TOTAL 56 46 16 0 34%14 0 65%16 0 1008 DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 1 SECTION XZ SUaaRY TABLE A PAGB: 14 CODE EDITION: 89 CATEGORY B-H INTEGRAL ATTACHMENTS FOR VESSELS SEC.XZ ITEM¹ITEM DESCRIPTION ZONE REL¹OF NO.¹OF COMPONENTS SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PBR 2ND PER 3RD PER COYAENTS B8.20 PRESSURIZER-INTEGRALLY WELDED SURFACE ATTACHMENTS 005 PRESSURIZER 014 1 1 1 0 100%0 0 100%0 0 100%of 100%attachment weld length 5/8'r greater B8.30 STEAM GENERATORS-INTEGRALLY SURFACE WELDED ATTACHMENTS 003 STEAM GENERATOR 014 2A PRIMARY SIDE 1 1 0 0 08 0 0 1 0 Limited to One 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't 0 0 0%1 0 100%CATEGORY TOTAL 3 2 1 0 50%0 0 50%1 0 100%

DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 1 SECTION XI SUÃ4ARY TABLE A PAGE: 15 CODE EDITION: 89 CATEGORY B-J-PRESSURE RETAINING FIELDS IN PIPING ASME SEC.XI ITEM¹ITEM DESCRIPTION ZONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COi4PLETED 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 4 IN.NOMINAL PIPE SIZE SURFACE VESSEL 0 0%12 0 100%0 0 25%of all Circ 100i butt welds, Essentially 100%of the weld VOLUMETRIC 006 REACTOR COOLANT SURFACE PIPING, LOOP A FROM 014 RPV TO SG-2A 3 1 0 0 0 0 1 0 0%0%100%VOLUMETRIC 007 REACTOR COOLANT 0 SURFACE PIPING, LOOP B FROM RPV TO SG-2B 3 1 1 0 100%0 0 0 0 100%100%VOLUaaRIC 008 REACTOR COOLANT 005 7 5 2 0 1 0 2 0 SURFACE PIPING, LOOP A SG-2A 0 40%60¹100%TO RCP-2A2 006 014'OLUiiRZC 009 REACTOR COOLANT 0 SURFACE PIPING, LOOP A FROM RCP-2A2 TO RPV 2 1 0 0 1 0 0 0 Ot 1008 100%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 RCP 2B1 TO RPV 100%100%100%VOLUMETRIC 012 REACTOR COOLANT 006 7 2 1 0 0 0 1 0 SURFACE PIPING, LOOP A SG-2A 0 TO RCP-2A1 50¹50%100%VOLTAIC 013 REACTOR COOLANT 0 SURFACE PIPING, LOOP A FROM RCP 2AI TO RPV 2 1 0 0 0%0 0 0%1 0 100¹VOLUMETRIC 014 REACTOR COOLANT 006 SURFACE PIPING, LOOP B SG 2B 0 TO RCP-2B2 7 2 0 0 0%1 0 50¹1 0 100'¹ DATE: 07/24/93 REVISION: 0 ST.LUCZE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 1 SECTION XZ SUhmARY TABLE A PAGE: 16 CODE EDITION: 89 CATEGORY B-J PRESSURE RETAINING WELDS ZN PIPING SEC.XI ITEM¹ITEM DESCRIPTION

¹OP COMPONENTS ZONE REL¹OF NO.SCHEDUIED/COMPLETED 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 SURFACE SURGE LINE 0 9 7 1 0 6 0 0 0 14%100%100%VOLUMETRIC 021 LOOP 2A1 SAFETY 0 21 I 0 0 SURFACE INJECTION PIPING, 006 0%ZNSIDE CTMT 0 0 7 0 0%100%VOLUMETRIC 022 LOOP 2A2 SAPETY 0 19 4 0 0 SURFACE INJECTION PIPING, 006 Ot INSIDE CTMT 3 0 1 0 75%100't VOLUiiRIC 023 LOOP 2B1 SAFETY 0 28 6 0 0 SURFACE INJECTION PIPING, 006 0%INSIDE CIMT 0 0 0%6 0 100%VOLUMETRIC 024 LOOP 2B2 SAFETY 0 SURFACE INJECTION PIPING, 006 INSIDE CTMT 19 3 3 0 0 0 0 0 100'C 100%100't VOLUMETRIC 025 COMBINED SURFACE PRESSURIZER SPRAY LINE 0 13 4 4 0 0 0 0 0 100%100%100%VOI UMETRIC 028 LOOP 2B SHUTDOWN 0 34 1 0 0 SURPACE COOLING LINE 006 0%0 0 0%1 0 100%VOLUMETRIC 029 LOOP 2A SHUIDOWN 0 20 0 0 0 0 0 0 0 SURFACE COOLING LINE I~1 I I I V~1***St)*%***I t VOLUMETRIC 038 PRESSURIZER SURFACE RELIEF LINE 0 12 6 0 0 0 0 6 0 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 IN.NOMINAL PIPE SIZE SURFACE VESSEL 0 12 2 0 0'0 0%100%0 0 Each Long weld 100't intersecting circ, weld req'd by B-F&B-J DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 1 SECTION XZ

SUMMARY

TABLE A PAGE: 17 CODE EDITION: 89 CATEGORY B-J-PRESSURE RETAINING WELDS IN PIPING SEC.XI ITEM¹ITEM DESCRIPTION ZONE REL¹OF NO.¹OF COMPONENTS SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COK4ENTS B9w12 LONGITUDINAL PIPE WELDS>~4 VOLUMETRIC 006 REACTOR COOLANT ZN.NOMINAL PIPE SIZE SURFACE PIPING, LOOP A FROM RPV TO SG-2A 2 0 0 0 0 0 F 11'%i~40~0%0 0*14%11)Each Long weld intersecting 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 RPV TO SG-2B 114*11$4+IIPt)%*****8 VOLUMETRIC 008 REACTOR COOLANT 0 10 10 4 0 4 0 2 0 SURFACE PIPING, LOOP A SG-2A 014 TO RCP-2A2 40%80%100%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 SURFACE PIPING, LOOP B SG-2B TO RCP-2B1 10 2 2 0 0 0 0 0 1008 100%100%SURFACE PIPING, LOOP B FROM 0 RCP-2B1 TO RPV 1008 VOL'PiKTRZC 011 REACTOR COOLANT 006 2 2 2 0 0 0 0 0 1008 100%VOLUMETRIC 012 REACTOR COOLANT 0 SURFACE PIPING, LOOP A SG-2A TO RCP-2A1 10 2 2 0 100%0 0 100%0 0 100%VOLUMETRIC 013 REACTOR COOLANT 0 SURFACE PIPING, LOOP A FROM RCP-2A1 TO RPV 2'0 0 0%0 0 0%2 0 100 8 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 SURFACE PIPING, LOOP B RCP-2B2 TO RPV 2 2 0 0 0%0 0 Ot 2 0 100%

DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CLASS 1 SECI'ZON XZ

SUMMARY

TABLE A PAGE: 18 CODE EDITION: 89 CATEGORY B-J-PRESSURE RETAINING WELDS IN PIPING SEC.XI ZTEM¹ITEM DESCRIPTION ZONE¹OP COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER CORKNTS ITEM TOTAL 64 26 10 0 38%8 0 8 0 69%100%B9.21 CIRCUMFERENTIAL PIPE WELDS (4 SURFACE IN.NOMINAL PIPE SIZE 006 REACTOR COOLANT 0 PIPING, LOOP A FROM RPV TO SG 2A 2 0 0 0***I I I t 0 0 111~~IS 0 0 25%of Cix'c.Butt IIIIIIwelds, Essential)y 100%of the weld SURFACE 026 LOOP 2B1 SPRAY 0 LINE 25 6 0 0 6 0 0 0 0%100%100%SURFACE 027 LOOP 2B2 SPRAY 0 LINE 25 6 0 0 5 0 1 0 0%83%100%SURFACE 028 LOOP 2B SHUTDOWN 0 COOLING LINE 13 3 3 0 0 0 0 0 100%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 AUXILIARY SPRAY 33%33%100%0 7 6 2 0 0 0 4 0 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 1 0 0 0 0 0 0 0 DRAIN IIIIII'I~III'IIIIII)SURFACE 034 LOOP 2A2 PRIMARY 0 DRAIN 1 0 0 0 0 0~111~~Q*I~~II4 0 0 IIIIII'URFACE 035 LOOP 2B1 PRIMARY 0 DRAIN 0%0%1 1 0 0 0 0 1 0 100k 0 SURFACE 036 LOOP 2B2 PRZMARY 0 DRAIN 1 0 0 0 0 0 IIII~~$ll~I~I'0 0 I~IIII' DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CLASS 1 SECTION XZ SUYMARY TABLE A PAGE: 19 CODE EDITION: 89 CATEGORY B-J-PRESSURE RETAINING WELDS IN PIPING ASME SEC.XI ITEM¹ITEM DESCRIPTION ZONE¹OF COMPONENTS RBL¹OF NO.SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COKKNTS B9.21 CIRCUMFERENTIAL PIPE WELDS (4 SURFACE IN.NOMINAL PIPE SIZE 037 LETDOWN LINE 0 PROM LOOP 2B1 8 5 2 0 3 0 0 0 40%100%'00%25%of Circ.Butt welds, Essentially 100%of the weld SURFACE 038 PRESSURIZER 0 RELZEF LINE 8 2 0 0 0%0 0 0%2 0 100%ITEM TOTAL 123 32 7 0 17 0 8 0 21%75%1008 B9.31 BRANCH CONNECTION WELDS)~4 VOLUMETRIC 006 REACTOR COOLANT IN.NOMINAL PIPE SIZE SURFACE PIPING'OOP A FROM RPV TO SG-2A 1 0 0 0 0 0 0 0 25%of all Branch<<<<*<<<<1$<<~<<<<<<<<$<<<<<<<<<<<<g Conn weids Essentially 100%of the weld VOLUMETRIC 007 REACTOR COOLANT 0 2 1 0 0 0 0 1 0 SURFACE PIPING, LOOP B FROM 006 RPV TO SG-2B 0%0%100%VOLUMETRIC 009 REACZOR COOLANT 0 1 0 0 0 0 0 0 0 SURFACE PIPING, LOOP A PROM RCP-2A2 TO RPV<<<<~<<<<<<8<<<<<<<<<<<<)**<<<<1*$VOLUMETRIC 011 REACTOR COOLANT 0 1 0 0 0 0 0, 0 0 SURFACE PIPING.LOOP B FROM<<<<<<<<<<<<)<<<<<<<<<<<<8<<<<<<~<<<<)RCP-2B1 TO RPV VOLUMETRIC 013 REACTOR COOLANT 0 SURPACE PIPING, LOOP A PROM RCP-2A1 TO RPV 1 0 0 0 0 0<<<<<<~<<~0<<<<<<<<<<<<\0 0<<<<~<<<<<<)VOLUMETRIC 015 REACTOR COOLANT 0 SURFACE PIPING, LOOP B RCP-2B2 TO RPV 1 0 0 0 0 0<<<<<<<<<<<<$<<<<<<<<**)0 0*<<~<<<<<<%ITEM TOTAL 7 1 0 0 0%0 0 0%1 0 100%t 89~32 BRANCH CONNECTION WELDS (4 SURFACE IN.NOMINAL PIPE SZZE 006 REACTOR COOLANT 0 PIPING, LOOP A FROM RPV TO SG 2A 1 0 0 0<<<<<<<<<<~t 0 0<<<<<<<<<<<<t 0 0 25%of Branch"***<<~%Conn.welds>Essentially 100%of the weld

DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 1 SECTION XZ

SUMMARY

TABLE A PAGE: 20 CODE EDITION: 89 CATEGORY B-J-PRESSURE RETAINING WELDS IN PIPING SEC.XZ ITEM¹ITEM DESCRIPTION ZONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION RE{}COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS IN.NOMINAL PIPE SI2E PIPING, IMP A SG-2A TO RCP-2A2 IIIIII(B9.32 BRANCH CONNECTION WELDS (4 SURPACE 008 REACTOR COOLANT 0 1 0 0 0 0 0 111111$0 0 258 of Branch Conn.welds~Essentially 100%of the weld SURFACE 009 REACZOR COOLANT 0 1 0 0 0 0 0 0 0 PIPING, LOOP A FROM RCP-2A2 TO RPV*~IIII)1*litt)I~IIII'URFACE 010 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 PIPING, LOOP B SG-2B TO RCP-2B1~*~~I~8 IIIIII%I l*l I 1(SURFACE 011 REACTOR COOLANT 0 PIPING, LOOP B FROM RCP-2B1 TO RPV 2 2 0 0 2 0 100%0 0 1008 SURFACE 012 REACTOR COOLANT 0 PIPING, LOOP A SG 2A TO RCP-2A1 1 0 0 0*I~*I~Q 0 0***I I*8 0 0 IIIIII'URFACE 014 REACTOR COOLANT 0 1 0 0 0 0 0 0 0 PIPING, LOOP B SG-2B TO RCP-2B2 llttt~0 IIIIII%11~III%SURFACE 015 REACTOR COOLANT 0 PIPING, LOOP B RCP 2B2 TO RPV 1 0 0 0 0 0 0 0~tt~tt%*111~It 1*1~~IV SURFACE COOLING LINE 100%VOLUMETRIC 028 LOOP 2B SHUTDOWN 006 3 2 2 0 0 0 100%0 0 100%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 COOLING LINE 12 3 0 0 0 0 0%0%3 0 25%of Socket 100%welds, Essentially 100%of the weld DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAI CLASS 1 SECTION XI

SUMMARY

TABLE A PAGB: 21 CODE EDITION: 89 CATEGORY B-J-PRESSURE RETAINING WBLDS IN PIPING ASME SEC.XZ ITEM¹ITEM DESCRIPTION BONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED 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 COOLING LINE PPPPPP%PPPPPP%~PPPPP%welds, Essentially 100%of the weld 0 0 0 0 0 0 0 25%of Socket SURFACE 030 PRESSURIZER AUXILIARY SPRAY 0 23 21 6 0 4 0 11 0 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 DRAIN 5 3 0 0 3 0 0%'00%0 0 100%SURFACE 036 LOOP 2B2 PRIMARY 0 DRAIN 5 0 0 0 0 0*~~***8**1*1*$0 0*~PPPP8 SURFACE 037 LETDONN LINE 0 FROM LOOP 2B1 31 30 17 0 6 0 56\76%7 0 100%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 REVISION: 0 ST.IUCIE NUCLEAR PLANT UNIT 2 INSERVICE ZNSPECTION PLAN FOR THE SECOND INTERVAL CLASS 1 SECTION XZ SI04ARY PAGE: 22 CODE EDITION: 89 CATEGORY B-K-1-INTFGRAL ATTACHMENTS FOR PIPING PUMPS AND VALVES SEC.XI ITEM 8 ITEM DESCRIPTION ZONE REL 5 OP NO.5 OF COMPONENTS SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COiiENTS B10.10 PIPING-INTEGRALLY WELDED ATTACHMENTS SURPACE 023 LOOP 2B1 SAFETY 0 INJECTION PIPING, INSIDE CIIfT 2 2 0 0 0%0 0 0%2 0 100'0 25%of pipe intergral attachments req'd under B-J SURFACE 024 LOOP 2B2 SAFETY 0 INJECTION PIPING, INSIDE CTMT 100%0 0 100't 0 0 100'URFACE 028 LOOP 2B SHUTDOWN 0 COOLING LINE 2 2 1 0 50%1 0 100'C 0 0 100%ITEM TOTAL 8 8 5 0 62%1 0 75%2 0 100'0.20 PUMPS-INTEGRALLY WELDED ATTACHMENTS SURFACE 017 REACTOR COOLANT 0 PUMP 2A1 0 0 0 100%100%0 0 Limited pump 100t integral attach required by B-L-2.SURFACE 018 REACZOR COOLANT 0 PUMP 2A2 4 4 0 0 0%4 0 100%0 0 100%SURFACE 019 REACTOR COOLANT 0 PUMP 2B1 4 4 0 0 0%4 0 200%0 0 100%SURFACE 020 REACTOR COOLANT 0 PUMP 2B2 4 4 0 0 0%0 0 08 4 0 100%ITEM TOTAL 16 16 4 0 25%8 0 75%4 0 100%CATEGORY TOTAL 24 24 9 0 37\9 0 75%6 0 100%

DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVZCE INSPECTION PLAN'FOR THE SECOND ZNTERVAL CLASS 1 SECTION XI SUI4ARY TABLE A PAGE: 23 CODE EDITION: 89 CATEGORY B-L 1-PRESSURE RETAINING WELDS IN PUMP CASING SEC.XI ITEM¹ITEM DESCRIPTION ZONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COKKNTS B12.10 PUMPS-PUMP CASING WELDS PUMP 2A1 1~0 1 lk I t~%I 1 k t t~II 1*%It VISUAL 017 REACTOR COOLANT 0 2 0 0 0 0 0 0 0 Essentially 100t 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 PUMP 2B2 2 2 0 0 0 0 2 0 Ot Ot 100t ITEM TOTAL 8 2 0 0 Ot 0 0 Ot 2 0 100t'ATEGORY TOTAL 8 2 0 0 Ot 0 0 2 0 100't DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 1 SECI'ION XZ SUiiRY TABLE A PAGE: 24 CODE EDITION: 89 CATEGORY B-L-2-PUMP CASINGS ASME SEC.XZ ITEM¹ITEM DESCRIPTION ZONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED 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 PUMP 2A1 1 0 0 0 0 0**it~I%1~1110%0 0 Limited to One"+~~~%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%1 1 1 I 1 1$VISUAL 019 REACTOR COOLANT PUMP 2B1 1 0 0 0 0 0 I~o1~p%*I~II~0 0 0****I 13 VISUAL 020 REACTOR COOLANT PUMP 2B2 1 1 0 0 0 0 1 0 0%0%100%ITEM TOTAL 4 1 0 0 Ot 0 0 1 0 Ot 100%CATEGORY TOTAL 4 1 0 0 0%0 0 1 0" 0%100%

DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CLASS 1 SECTION XI SUKQRY TABLE A PAGE: 25 CODE EDITION: 89 CATEGORY B-M-2-VALVE BODIES SEC.XZ ITEM¹ITEM DESCRZPTION ZONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED EXAM METHOD~SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS B12.50 VALVES-VALVE BODIES EXCEEDING VISUAL 4 INCHES NOMINAL PIPE SZEE 021 LOOP 2A1 SAFETY INJECTION PIPING, INSIDE CTMT IIIIII'l~I~1%IIIIII'group of vlv., when dissem.for maint.3 0 0 0 0 0 0 0Limited1vlv.

in VISUAL 022 LOOP 2A2 SAFETY 3 0 0 0 0 0 0 0 INJECTION PIPING'NSIDE CIMT 1111~IQ IIIIII'IIIII'ISUAL 023 LOOP 2B1 SAFETY INJECTION PIPING, INSIDE CIMT 3 0 0 0 0 0 IIIIII'IIIIIV 0 0**1*11%VISUAL 024 LOOP 2B2 SAPETY INJECTION PIPING, INSIDE CIMT 3 0 0 0'0 IIIIII'111

~1$0 0 IIIIII)VISUAL 028 LOOP 2B SHUTDOWN COOLING LINE 3 0 0 0 0 0 0 0 111111%IIIIIIV IIIIIIV VISUAL 029 LOOP 2A SHUTDOWN 007 COOLING LINE 11~III%**IIIIV llllllg 2 0 0 0 0 0 0 0 ITEM TOTAL 17 0 0 0 I I I I II)0 0 I I***I e 0 0 IIIIII%CATEGORY TOTAL 17 0 0 0'0 0 0 I~~III'*~I~Ie I~IIII' DATEl 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 1 SECTION XI

SUMMARY

TABLE A PAGE: 26 CODE EDITION: 89 CATEGORY B-N-1-INTERIOR OF REACTOR VESSEL ASME SEC.XI ITEM¹ITEM DESCRIPTION ZONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED 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 VESSEL 26 8 0 10 0 30%69%8 0 Once every 100%inspection period CATEGORY TOTAL 10 26 8 0 30%10 0 8 0 69%100%

DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVZCE INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 1 SECI'ZON XI

SUMMARY

TABLE A PAGE: 27 CODE EDITION: 89 CATEGORY B-N-2-INTEGRALLY WELDED CORE SUPPORT STRUCTURES AND INTERIOR ATTACHMENTS TO REACTOR VESSEL ASME SEC.XI ITEM¹ITEM DESCRIPTION ZONE REL¹OP NO.¹OP COMPONENTS SCHEDUIED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS B13.50 REACTOR VESSEL (PWR)-INTERIOR VISUAL ATTACHMENTS WITHIN BELTLINE REGION 001 REACTOR PRESSURE 0 VESSEL 6 6 0 0 6 0 0%100%0 0 Accessible welds, 100%Performed in con)unction with Exam Cat B-A.B13.60 REACIOR VESSEL (PWR)-INTERIOR VISUAL ATTACHMENTS BEYOND BELTLINE REGION 001 REACTOR PRESSURE 0 VESSEL 14 14 0 0 14 0 0 0 Asscesible welds, 0%100%100'C Performed in con)unction with Exam Cat B-A CATEGORY TOTAL 20 20 0 0 0%20 0 100%0 0 100t DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CLASS 1 SECTION XI SUhmARY TABLE A PAGE: 28 CODE EDITION: 89 CATEGORY B-N-3-REMOVABLE CORE SUPPORT STRUCTURES SEC.XI ITEM¹ITEM DESCRIPTION ZONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS B13.70 REACTOR VESSEL (PHR)-CORE SUPPORT STRUCTURE VISUAL 001 REACTOR PRESSURE 0 VESSEL 6 6 0 0 0%6 0 0 0 100%100i'ccessible surfaces.Performed in con).with Exam CATEGORY TOTAL 6 6 0 0 O'C 6 0 100%0 0 100%

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 REVISZON: 0 ST.LUCZE NUCLEAR PLANT UNIT 2 INSERVICE ZNSPECTZON PLAN'FOR THE SECOND INTERVAL CLASS 2 SECTION XZ

SUMMARY

TABLE B PAGE: 29 CODE EDITION 89 CATEGORY C-A-PRESSURE RETAINING WELDS IN PRESSURE VESSELS SEC.XI ITEM¹ITEM DESCRIPTION ZONE¹OF COMPONENTS REL¹OF NO~SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS C1.10 SHELL CIRCUMFERENTIAL WELDS VOLUMETRIC 041 STEAM GENERATOR 2A SECONDARY SIDE 5 4 0 0 0%0 0 0%4 0 Gross structural 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 HEAT EXCHANGER 2A 1 1 0 0 0%0 0 0%1 0 100%VOLUMETRIC 056 SHUTDOWN COOLING 0 HEAT EXCHANGER 2B 1 0 0 0 0 0 0 0*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 2A SECONDARY SIDE 1 1 0 0 0%0 0 0%1 0 Head-to-shell 100%weld, Limited to One vessel among vessels, VOLUMETRZC 042 STEAM GENERATOR 0 2B SECONDARY SIDE 1 0 0 0 0 0 0 0**1***)1esee*f~~p~1~Q 2 1 0 0 0%0 0 0%1 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 HEAT EXCHANGER 2A 1 1 0 0 0%0 0 1 0 100' DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVZCE INSPECTION PLAN FOR THE SECOND ZNTERVAL CLASS 2 SECTION XZ

SUMMARY

TABLE B PAGE: 30 CODE EDITION: p 89 CATEGORY C-A-PRESSURE RETAINING WELDS IN PRESSURE VESSELS SEC.XZ ITEM¹ITEM DESCRIPTION ZONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED 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%0¹100' DATE: 07/24/93 REVISION: 0 ST.LUCZE NUCLEAR PLANT UNIT 2 INSERVICE INSPECI'ZON PLAN'FOR THE SECOND ZNTERVAL CLASS 2 SECTION XI

SUMMARY

TABLE B PAGE: 31 CODE EDITION: 89 CATEGORY C-B-PRESSURE RETAINING NOZZLE WRLDS IN VESSELS ASME SEC.XI ITEM¹ITEM DESCRIPTION ZONE REL¹OF NO.¹OF COMPONENTS SCHEDULED/COMPLETED 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 1/2 IN.NOMINAL THZCKNESS SURFACE 2A SECONDARY SIDE 0%~WITHOUT REINFORCING PLATE 0 0 2 0 0%100\Nozzles at terminal ends of pipe run, Limited One vessel under VOLUMETRIC 042 STEAM GENERATOR 0 SURPACE 2B SECONDARY SIDE 2 0 0 0 0 0 0't0~4~1%I~~P~1%I~0~~4%ITEM TOTAL 4 2 0 0 0%0 0 0%2 0 1008 C2.22 NOZZLE INSIDE RADIUS SECTION>VOLUMETRIC 041 STEAM GENERATOR 0 1/2 IN.NOMINAL THICKNESS 2A SECONDARY SIDE 014 WITHOUT REINFORCING PLATE 0\08 100%terminal ends of pipe run.Limited One vessel under 2 2 0 0 0 0 2 0 Nozzles at 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 0 0%2 0 100%C2.31 REINFORCING PLATE WELDS TO SURFACE NOZZLE AND VESSEL>1/2 IN.NOMINAL THICKNESS 055 SHUTDOWN COOLING HEAT EXCHANGER 2A 0%0%100%terminal ends of pipe run.Limited One Vessel under 4 4 0 0 0 0 4 0 Nozzles at 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 0 0%4 0 100%C2.33 NOZZLE-TO-SHELL (OR HEAD)VISUAL WELDS WHEN INSZDE OF WELD ZS INACCESSIBLE

>1/2 ZN.NOMINAL THZCKNESS 055 SHUTDOWN COOLING HEAT EXCHANGER 2A 2 2 0 0 0 0 2 0 Nozzles at 08 100%terminal ends of pipe run.Limited One Vessel under DATE: 07/24/93 REVISION: 0 ST.LUCIB NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CLASS 2 SECTION XI

SUMMARY

TABLE B PAGE: 32 CODE EDITION: 89 CATEGORY C-B-PRESSURE RETAINING NOZZLE WELDS IN VESSELS SEC.XZ ITEM¹ITEM DESCRIPTION ZONE REL¹OP NO.¹OF COMPONENTS SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS C2.33 NOZZLE-TO-SHELL (OR HEAD)VISUAL WBLDS WHEN INSIDB OF WELD IS INACCESSIBLE

>1/2 IN.NOMINAL THICKNESS HEAT EXCHANGER 2B*I tk*~'t 056 SHUTDOWN COOLING 0 2 0 0 0 0 0 1 1*401(0 0 Nozzles at~++~~+t terminal ends of pipe run.Limited One Vessel under 4 2 0 0 0%0 0 0%2 0 100%CATEGORY TOTAL 20 10 0 0 0%0 0 10 0 0%100%

DATE: 07/24/93 REVISION: 0 ST.LUCIB NUCLEAR PLANT UNIT 2 INSERVZCE INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 2 SECTION XI

SUMMARY

TABLE B PAGE: 33 CODE EDITION: 89 CATEGORY C C-INTEGRAL ATTACHMENTS FOR VESSELS PIPING PUMPS AND VAIVES ASME SEC.XZ ITEM¹ITEM DESCRIPTION BONE EXAM METHOD SYSTEM DESCRIPTION

¹OF COMPONENTS REL¹OF NO~SCHEDULED/COMPLETED REQ COMP REQ 1ST PER 2ND PER 3RD PBR COMMENTS C3.10 PRBSSURE VESSELS-INTEGRALLY SURFACE WELDED ATTACHMENTS 2A SECONDARY SIDE 0 0\041 STEAM GENERATOR 014 8 8 0 0 0 0 8 0 Limit to 1 vessel 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)lf 1111)ITEM TOTAL 16 8 0 0 0 0 8 0 0%O'C 100 8 C3.20 PIPING-INTEGRALLY WELDED ATTAC784BNTS e SURFACE 045 SAFETY INJECTZON 0 PIPING TO SZ TANK 1 1 1 0 100%0 0 0 0 Limited to 100%100%attachments of components required under SURFACE 046 SAPETY INJECTION 0 4 0 0 0 0 0 0 0 PIPING TO SI TANK 2A1*II***)*II**I)t11*'I'll)

SURFACE 061 HPSI PUMP 2A TO 0 HEADER A 2 1 1 0 100%0 0 100%0 0 100%SURPACE 063 MAIN STEAM LINE 0 2A1 INSIDE CONTAINMBNT 3 1 0 0 0%0 100%0 0 100%SURFACE 064 MAIN STEAM LINE 0 2 0 0 0 0 0 0 0 2B1 INSIDE CONTAIhMENT 0~***1)%0~l%~$1*~I'Ii)SURFACE 065 MAIN STEAM LINE 2A1 OUTSIDE CONTAINMENT 0 1 1 0 0 1 0 0 0 0%100%100%SURFACE 066 MAIN STEAM LINE 0 1 0 0 0 0 0 0 0 2B1 OUTSIDE CONTAINMENT 1**441%*4Al**%**1~**0 DATE: 07/24/93 REVISZON: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSBRVICE INSPECTION PLAN FOR THE SECOND INTERVAL CLASS 2 SECTION XZ

SUMMARY

TABLE B PAGE: 34 CODE EDITION: 89 CATEGORY C C-INTEGRAL ATTACHMENTS FOR VESSELS PIPING PUMPS AND VALVES SEC.XZ ITEM¹ITEM DESCRIPTION

¹OF COMPONENTS ZONE REL¹OF NO.SCHEDULED/COMPLETED 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 CONTAINMENT Ot Ot 100t attachments of components required under SURFACE 068 MAIN FEEDWATER 0 TO SG 2B1 INSIDE CONTAINMENT 2 1 0 0 Ot 0 0 1 0 Ot 100t SURFACE 087 COMBINED HPSI DISCHARGE 0 3 1 1 0 0 0 0 0 100t 100t 100t'SURFACE 093 HPSZ 2A 1 0 0 0 0 0 0 0 DISCHARGE TO SDC LOOP 2A 1 1111*t llll**t 11*lilt 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 ATTACHMENTS VZSUAL 097 CONTAINMENT 0 3 3 0 0 0 0 3 0 Limited to 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 Ot 0 0 Ot 3 0 100 t CATEGORY TOTAL 44 18 3 0 16t 2 0 27t 13 0 100t DATE: 07/24/93 REVISION: 0 ST.LUCZB NUCLEAR PLANT UNIT 2 INSERVZCE INSPECTION PLAN FOR THE SECOND INTERVAL CLASS 2 SECTION XZ SUiiRY TABLE B PAGE: 35 CODE EDITION: 89 CATEGORY C F 1 PRESSURE RETAINING WBLDS IN AUSTENZTZC STAINIiESS STEEL OR HIGH ALLOY PIPING SEC.XI ITEM¹ITEM DESCRIPTION ZONE RBL¹OF NO.¹OF COMPONENTS SCHEDULED/COMPLETED 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 OR~to 3/8 IN.NOM.WALL SURFACE DISCHARGE HEADER.THICKNESS FOR PIPING>NPS 4 PIPING 0 68 10 3 0 4 0 3 0 30t 70t 100t 7.5t of non exempt welds, 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 SURFACE PIPING TO SI TANK VOLUiiRIC 045 SAPETY INJECTION 0 14 1 1 0 0 0 0 0 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 SURFACE PIPING TO SI TANK 2B1 VOLUMETRIC 047 SAFETY INJECTION 0 2 1 0 0 Ot 0 0 1 0 Ot 100t VOLUMETRIC 048 SAFETY INJECTION 0 SURFACE PIPING TO SZ TANK 2B2 16 1 0 0 1 0 0 0 Ot 100'00t VOLUMETRIC 051 SHUTDOWN COOLING 0 SURFACE LINE A INSIDE CONTAIhMENT

• • • 1~*t***t**t ii*ae**)2 0 0 0 0 0 0 0 VOLUMETR1C SURFACE 052 SHUTDOWN COOLING 0 LINE B INSIDE CONTAINMENT 2 0 0 0 0 0 4*IIiiIt 11***at 0 0 Aklkllt SURFACE HEADER A VOLUMETRIC 061 HPSI PUMP 2A TO 0 14 2 0 0 0 0 Ot 0't 2 0 100t VOLUMETRIC 062 HPSZ PUMP 2B TO 0 SURFACE 10 2 1 0 1 0 50t 100t 0 0 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 1/5 IN.NOM.THICKNESS FOR SURFACE HEADER A PIPING>OR~TO NPS 2 AND c OR&TONPS 4 20 3 0 0 Ot 0 0 3 0 7.5t of non Ot 100t exempt welds, 7.5t based on total exempt&

DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 2 SECTZON XZ

SUMMARY

TABLE B PAGE: CODE EDITION: 36 89 CATEGORY C-F-1-PRESSURE RETAINING MFLDS IN AUSTENITIC STAINLESS STEEL OR HIGH ALLOY PIPING or e NPS 4 SEC.XI ITEM¹ITEM DESCRIPTION ZONE¹OF COMPONENTS REL¹OP NO.SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION RE{}COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS C5.21 CIRCUMFERENTIAL PIPING HELDS 1/5 IN.NOM.THZCKNESS FOR PZPING>OR~TO NPS 2 AND (OR~TONPS 4>VOLUMETRIC 062 HPSI PUMP 2B TO SURFACE HEADER B 0 10 3 0 0 0%3 0 100%0 0 7.5t of non 100%exempt welds, 7.5%based on total exempt 6 VOLUMETRIC 087 COMBINED HPSI 0 SURFACE DISCHARGE 100\100'C 100%83 14 14 0 0 0 0 0 VOLUMETRIC 088 CHARGING PUMP 2A 0 SURFACE DISCHARGE TO AUX.HPSI 6 0 0 0**II**$0 0 0 0***%*if.**It%*4 VOLUMETRIC 093 HPSI 2A 0 45 5 0 0 0 0 5 0 SURFACE DISCHARGE TO SDC LOOP 2A 0%Ot 100%VOLUMETRIC 094 HPSZ HEADER B TO 0 SURFACE SDC IMP 2B 65 10 0 0 0%0 0 10 0 0%100%VOLUMETRIC 095 HPSZ 2A SURFACE DISCHARGE TO SDC LOOP 2B 0%O'C 100%0 24 4 0 0 0 0 4 0 SURPACE DISCHARGE TO SDC LOOP 2B VOLUiiRZC 096 HPSI 2B 2 0 0 0 0 0 1I1N~*0*01%1~0 0 0 141440$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 DISCHARGE TO AUX.HPSI 46 4 1 0 3 0 0 0~25%100%100't DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVZCE INSPEC1'ZON PLAN'FOR THE SECOND INTERVAL CLASS 2 SECTION XZ

SUMMARY

TABLE B PAGB: 37 CODE EDITION: 89 CATFGORY C-F-1-PRESSURE RETAINING WELDS IN AUSTENITIC STAINLESS STEEL OR HIG'H ALLOY PIPING SEC.XZ ITEM¹ITEM DESCRIPTION ZONE REL¹OF NO.¹OP COMPONENTS SCHEDULED/COMPLETED 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 DISCHARGE TO AUX.HPSZ 0 0 4.0 0%100%0 0 7.5%of non 100%exempt welds, 7.5%based on exempt 6 SURFACE 090 CHARGING PUMP 2C 0 DISCHARGE TO AUX.HPSI 28 4 0 0 4 0 0'O'C 100%100%SURFACE 091 COMBINED CHARGING PIMP DISCHARGE TO HPSZ 0 21 4 0 0 4 0 0 0 08 100%100%SURFACE 092 COMBINED DISCHARGE TO HPSI TZE IN LOOP 2B 0 15 2 0 0 2 0 0 0 0%100%100%SURFACE 096 HPSZ 2B DISCHARGE TO SDC LOOP 2B 0 18 4 0 0 0 0 4 0 0%0%1008 ITEM TOTAL 227 30 9 0 17 0 4 0 308 86%100%C5.41 PIPE BRANCH CONNECTIONS OF SURFACE BRANCH PZPZNG (CIRCIMFERENTAIL WELDS))OR t TO NPS 2 061 HPSI PIMP 2A TO 0 HEADER A 5 2 0 0 0 0 2 0 7.5%of non 08 0%100%exempt welds, 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 DISCHARGE TO AUX.HPSZ 3 1 0 0 0%1 0 1001 0 0 100%SURFACE 089 CHARGING PUMP 2B 0 1 0 0 0 0 0 0 0 DISCHARGE TO AUX.HPSI*tt~tt%tttttt%tttttt%

DATE: 07/24/93 REVISZON: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CLASS 2 SECTION XZ SUYMARY TABLE B PAGE: 38 CODE EDITION: 89 CATEGORY C-F-1-PRESSURE RETAINING WELDS IN AUSTENITIC STAINLESS STEEL OR HIGH ALLOY PIPING SEC.XZ ITEM¹ITEM DESCRIPTION ZONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COUNTS C5.41 PIPE BRANCH CONNECTIONS OF SURFACE BRANCH PIPING (CIRCUMFERENTAIL WELDS)>OR~TO NPS 2 090 CHARGING PUMP 2C 0 DISCHARGE TO AUX.HPSZ 2 1 0 0 0%1 0 0 0 7.5%of non 100%100%exempt welds, 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 30%33 0 62%38 0 100%

DATB: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN'FOR THB SECOND INTERVAL CLASS 2 SECTION XZ SUYBARY TABLE B PAGE: 39 CODE BDZTZON: 89 CATEGORY C-F-2-PRESSURE RETAINING WELDS IN CARBON OR LOW ALLOY STEEL PIPING ASMB SEC.XI ITEM¹ITEM DESCRIPTION ZONE EXAM METHOD SYSTEM DESCRIPTION

¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED 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 OR~TO 3/8 IN.NOM.WALL SURFACE 2A1 INSIDE 66%66't 100%THICKNESS FOR PIPING>NPS 4 CONTAIhMENT 7.5%of non exempt welds, 7.5%based on exempt&non VOLUMETRIC 064 MAIN STEAM LINE 0 SURFACE 2B1 INSIDE CONTAINMENT 17 5 0 0 2 0 3 0 0\'0%100%VOLUMETRIC 065 MAIN STEAM LINE 0 SURFACE 2A1 OUTSIDE CONTAINMENT 30 7 4 0 3 0 0 0 571'00%100%VOLUMETRIC 066 MAIN STEAM LINE 0 SURFACE 2B1 OUTSIDE CONTAINMENT 30 11 0 0 0%0 0 11 0 0't 100%VOLUMETRIC 067 MAIN FEEDWATER SURFACE TO SG 2A1 INSIDE CONTAIhMENT 0 12 4 0 0 4 0 0 0 09'00%100%VOLUMETRIC 068 MAIN FEEDWATER SURFACE'O SG 2B1 INSIDE CONTAINMENT 0 14 4 2 0 0 0 2 0 50%50%100%VOLUMETRIC 071 MAIN FEEDWATER SURFACE TO SG 2A1 OUTSIDE CONTAINMENT 0 5 4 2 0 2 0 0 0 50%100%, 100%VOLUMETRIC 072 MAIN FEEDWATER SURFACE TO SG 2Bl OUTSIDE CONTAINMENT 0 5 4 0 0 0 0 4 0 0%0%100%'TEM TOTAL 128 42 10 0 239 11 0 50%21 0 100%C5.52 LONGITUDINAL PZPING WELDS>OR VOLUMETRIC 063 MAIN STEAM LINE 0~TO 3/8 ZN.NOM.WALL SURFACE 2A1 ZNSZDE THICKNESS FOR PIPING>NPS 4 CONTAINMENT 17 3 2 0 0 0 1 0 2't AT THE 66%66%100%INTERSECTING CIRCUMFERENTIAL WELD.

DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCI EAR PLANT UNIT 2 INSERVZCE INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 2 SECZ'ION XI

SUMMARY

TABLE B PAGE: 40 CODE EDITION: 89 CATEGORY C-F-2-PRESSURE RETAINING WELDS IN CARBON OR LOW ALLOY STEEL PIPING ASME SEC.XZ ITEM 5 ITEM DESCRIPTION ZONE 8 OF COMPONENTS REL 5 OF NO.SCHEDULED/COMPLETED 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~TO 3/8 ZN.NOM.WALL SURFACE 2B1 INSIDE Ot THICKNESS FOR PIPING>NPS 4 CONTAINMENT 5 0 55t 4 0 100t 2.5t AT THE INTERSECTING 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 27t 5 0 8 0 55t 100t CS.81 CIRCUMFERENTIAL BRANCH CONNECTION WELDS OF BRANCH PIPING>OR~to NPS 2 VOLUMETRIC 065 MAIN STEAM LINE 0 10 3 2 0 1 0 0 0 7.5t of non SURFACE 2A1 OUTSIDE 66t 100t 100t exempt welds, CONTAINMENT 7.5t based on exempt a non SURFACE 2Bl OUTSIDE CONTAIhMENT VOLUiiRIC 066 MAIN STEAM LINE 0 10 3 0 0 0 0 3 0 Ot Ot 100t ITEM TOTAL 20 6 2 0 1 0 3 0 33t 50t 100t CATEGORY TOTAL 190 66 17 0 17 0 32'100t 5lt 25t 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 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVZCE INSPECTION PLAN'FOR THE SECOND INTBRVAI CLASS 3 SECTION XI SUiiRY TABLE C PAGE: 4 1 CODE EDITION: 89 CATEGORY D-A-SYSTEMS IN SUPPORT OF REACTOR SHUTDOWN FUNCI'ION SEC.XZ ITEM¹ITEM DESCRIPTION ZONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP RBQ 1ST PER 2ND PER 3RD PER COMMENTS Dl.20 INTEGRAL ATTACHMBNT-COMPONENT SUPPORTS AND RESTRAINTS VISUAL 102 COMPONENT COOLING-SHUTDOWN COOLING HX 2A INLET 3 3 0 0'0 3 0 MULTIPLE STREAMS Ot Ot 100t MAY APPLY.VISUAL 103 COMPONENT COOLING-SHUTDOWN COOLING HX 2B INLET 0 2 2 0 0 0 0 2 0 Ot Ot 100t VISUAL 105 COMPONENT COOLING-SHUTDOWN COOLING HX 2A DISCHARGE 0 4 4 1 0 3 0 0 0 25t 100t 100't e VISUAL VISUAL 106 COMPONENT COOLING-SHUTDOWN COOLING HX 2B DISCHARGE 180 LETDOWN HEAT EXCJ JANG ER 0 3 3 1 0 1 0 1 0 33t 66t 100t 0 2 2 2 0 0 0 0 0 100t 100t 100t ITEM TOTAL 14 14 4 0 28t 4 0 6 0 57t 100t Dl.40 ZNTEGRAL ATTACHMENT

-SPRING VISUAL TYPE SUPPORTS 105 COMPONENT COOLING-SJRJTDOWN COOLING HX 2A DISCHARGE 0 1 1 1 0 0 0 0 0 MULTIPLE STREAMS 100t 100t 100t MAY APPLY.CATEGORY TOTAL 15 15 5 0 4 , 0 6 0 33t 60t 100t DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVZCE INSPECTION PLAN'FOR THE SECOND iNTERVAL CLASS 3 SECTION XI SUYiiRY TABLE C PAGE: 42 CODE EDZTZON: 89 CATEGORY D-B-SYSTEMS IN SUPPORT OF EMER.CORE COOLING CONT.HT REMVL ATMOS CLEANUP AND REACTOR RHR SEC.XI ITEM¹ITEM DESCRIPTION

¹OP COMPONENTS ZONE REL¹OF NO.SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS D2.20 INTEGRAL ATTACHMENT-COMPONENT SUPPORTS AND~RESTRAINTS VISUAL 200 COMPONENT COOLING WATER HX 2A&2B INLET HEADER 100t 100t 100't MAY APPLY.0 2 2 2 0 0 0 0 0 MULTIPLE STREAMS VISUAL 101 COMPONENT COOLING WATER HX 2A&2B DISCHARGE 0 5 5 0 0 5 0 0 0 0't 100t 100t VISUAL 107 COMPONENT COOLING WATER PUMPS 2Ag 2B&2C INLET 0 2 2 1 0 0 0'1 0 50t 50t 100t VISUAL 108 AUXILIARY 0 FEEDWATER PUMP 2C TO MAIN FEEDWATER 2 2 2 0 100t 0 0 100t 0 0 100t VISUAL 110 CONDENSATE-SUCTION TO AUX.FEEDWATER PUMP 2A&2B 0 2 2 2 0 0 0 0 0 100t 100't 100t VISUAL 111 AUX.FEEDWATER PUMPS 2A&2B DISCHARGE 0 10 10 0 0 10 0 0 0 04'00t 100t VISUAL 112 CIRCULATING 0 WATER FROM INTAKE COOLING WATER PUMPS 9 9 0 0 0 0 9 0 Ot Ot 100t VISUAL 113 CIRCULATING WATER TO CCW HEAT EXCHANGER 2A 0 1 1 1 0 0 0 0 0 100t 100t'00t VISUAL 114 CIRCULATING WATER TO CCW HEAT EXCHANGER 2B 0 1 1 1 0 0 0 0 0 lOOt 100t 100t VISUAL 181 COMPONENT COOLING WATER HEAT EXCHANGER 2A 0 4 4 4 0 0 0 0 0 100t 100t 100t DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICB INSPECTION PLAN POR THE SECOND INTERVAL CLASS 3 SECTION XZ S~iY TABLE C PAGE: 43 CODE EDITION: 89 CATEGORY D-B-SYSTEMS IN SUPPORT OF EMER.CORE COOLING CONT.HT REMVL ATMOS CLEANUP AND RFACTOR RHR SEC.XZ ITEM 8 ITEM DESCR1PTION ZONE RBL g OF NO.5 OF COMPONENTS SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COmZENTS D2.20 INTEGRAL ATTACHMENT COMPONENT SUPPORTS AND RESTRAINTS VISUAL 182 COMPONENT COOLING WATER HEAT EXCHANGER 2B 4 0 0 0 0 0 0 0 MULTIPLE STREAMS IIIIII'11111$IIIIII'AY APPLY VISUAL 183 COMPONENT COOLING WATER PUMP 2A 0 4 4 4 0 0 0 0 0 100%1008 100%VISUAL 183 COMPONENT COOLING WATER PUMP 2B 4 0 0 0 0 0 0 0~~IIII)11~11~8~IIIII'ISUAL 183 COMPONENT COOLING WATER PUMP 2C 0 4 0 0 0 0 0 0 0*11~I~Q*~IIII'IIIII'ISUAL 187 SHUTDOWN COOLING 0 HEAT EXCHANGER 2A 2 2 0 0 0%2 0 100'C 0 0 100%VISUAL 187 SHUTDOWN COOI ING 0 HEAT EXCHANGER 2B 2 0 0 0 0 0 0 0 1*11~If~~~111%I~*~I~%VISUAL 188 INTAKE COOLING 0 2 0 0 0 0 0 0 0 WATER PUMP 2A IIIIII'111118 111111$VISUAL 188 1NTAKE COOLING 0 WATER PUMP 2B 2 0 0 0 0 0 0 0 IIIIII(111~Il)IIIIII)VISUAL 188 ZNTAKE COOLING 0 WATER PUMP 2C 2 2 0 0 0%0 0 Ot 2 0 100%VISUAL 189 COMPONENT COOLING WATER SURGE 0 2 2 0 0 0 0 2 0 0%Ot 100\ITEM TOTAL 66 48 17 0 17 0 35%70%14 0 100%D2.40 INTEGRAL ATTACHMENT SPRING VISUAL 100 COMPONENT COOLING WATER HX 2A&2B INLET HEADER 0 2 2 2 0 0 0 0 0 MULTIPLE STREAMS 100'8 100\100%MAY APPLY.

DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN'FOR THB SECOND INTERVAL CLASS 3 SECTZON XI

SUMMARY

TABLE C PAGE: 44 CODB EDITION: 89 CATEGORY D-B-SYSTFMS IN SUPPORT OF EMER.CORE COOLING CONT.HT REMVL ATMOS CLEANUP AND REACTOR RHR SEC.XZ ITEM g ITEM DESCRIPTION g OF COMPONENTS SCHEDULED/COMPLETED ZONE REL 9 OF NO.EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PBR COUNTS TYPE SUPPORTS COOLING WATER PUMPS 2A, 2B Ec 2C INLET D2~40 INTEGRAL ATTACHMENT

-SPRING VISUAL 107 COMPONENT 4 4 0 0 0%2 0 2 0 MULTIPLE STREAMS 50%100%MAY APPLY.ITEM TOTAL 6 6 2 0 2 0 2 0 33%66%100%CATEGORY TOTAL 72 54 19 0 35%19 0 70%16 0 100%

DATE: 07/24/93 REVISION: 0 ST.LUCIB NUCLEAR PLANT UNIT 2 INSERVICB INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 3 SECTION XZ

SUMMARY

TABLE C PAGE: 45 CODE EDITION: 89 CATEGORY D-C-SYSTEMS IN SUPPORT OF RESIDUAL HEAT REMOVAL PROM SPENT FUBI STORAGE POOL SEC.XZ ITEM¹ZTEM DESCRIPTION ZONE REL¹OF NO.¹OF COMPONENTS SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS D3.20 INTEGRAL ATTACHMBNT-COMPONENT SUPPORTS AND RESTRAINTS VISUAL 104 SPENT FUEL POOL COOLING HX 2A DISCHARGE PIPING 0 2 2 2 0 0 0 0 0 MULTIPLE STREAMS 1008 100%100%MAY APPLY.VISUAL 184 FUEL POOL COOLING PUMP 2A 1 0 0 0 0 0 1~0~OO$Oee*14$0 0 1 1441~Q VISUAL 184 FUEL POOL COOLING PUMP 2B 0 1 1 0 0 1 0 0 0 0%100%1008 VISUAL 185 FUEL POOL COOLING HEAT EXCHANGER 2A 2 0 0 0 0 0 t***t 0 Q I*4~I 4 8 0 0 11**1~$VISUAL 185 FUEL POOL COOLING HEAT BXCHANGER 2B 0 2 2 0 0 0 0 2 0 08 Ot 100%ITEM TOTAL 8 5 2 0 408 1 0 60%2 0 100%CATEGORY TOTAL 8 5 2 0 408 1.0 60%2 0 100%

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 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 1 SECTION XZ

SUMMARY

TABLE D PAGE: 46 CODE EDITION: 89 CATEGORY F-A-CLASS 1 SUPPORTS SEC.XI ITEM¹ITEM DESCRIPTiON ZONE REL¹OF NO.¹OF COMPONENTS SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER CO~~S Fl.10 MECHANICAL CONNECTIONS TO PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE INJECI'ION PIPING INSIDE CTMZ eeeeeaQ VISUAL 021 LOOP 2A1 SAFETY 0 1 0 0 0 0 0~144~4%0 0 25%required 4111~1%VISUAL 022 LOOP 2A2 SAFETY INJECTION PIPING, INSIDE CTMT 0 1 1 0 0 0%0 0 0%1 0 100%VISUAL 023 LOOP 2B1 SAFETY 0 INJECTION PIPING, INSIDE CTM1'2 0 0 0%0 0 0%2 0 100%VISUAL 024 LOOP 2B2 SAFETY 0 INJECTION PIPING, INSIDE CIÃF 1 1 0 100%0 0 1008 0 0 1008 VISUAL 025 COMBINED PRESSURIZER SPRAY LINE 0 2 1 1 0 0 0 0 0 100%100%100%VISUAL 026 LOOP 2Bl SPRAY LINE 0 11 3 0 0 3 0 0 0 08 100%100%VISUAL 027 LOOP 252 SPRAY LINE 0 11 3 0 0 3 0 0 0 08 100%100%VISUAL 028 LOOP 2B SHUTDOWN 0 COOLING LINE 1 1 1 0 100%0 0 100%0 0 1008 VISUAL 029 LOOP 2A SHUIDOWN 0 COOLING LINE 2 1 1 0 1008 0 0 100%0 0 100%VISUAL 030 PRESSURZZER AUXILIARY SPRAY 0 13 3 0 0 0 0 3 0 0%0%100%VISUAL 031 CHARGING LINE TO 0 LOOP 2B1 6 2 0 0 0%2 0 100%0 0 100%VISUAL 032 CHARGING LINE TO 0 LOOP 2A2 28 6 2 0 2 0 2 0 33 8 66%100'C

DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVZCE INSPECTION PLAN FOR THE SECOND INTERVAL CLASS 1 SECTION XI SUGARY PAGE: CODE EDITION: 47 89 CATEGORY F-A-CLASS 1 SUPPORTS ASME SEC.XI ITEM¹ITEM DESCRIPTION

¹OF COMPONENTS ZONE REL¹OF NO.SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS Fl.10 MECHANICAL CONNECTIONS TO PRESSURE RETAINING COMPONENTS

.AND BUILDING STRUCTURE VISUAL 033 LOOP 2A1 PRIMARY 0 DRAIN 1 1 I 0 100%0 0 100%0 0 258 required 100%VISUAL 034 LOOP 2A2 PRIMARY 0 DRAIN 1 1 0 0 0%1 0 100'0 100%VISUAL 036 LOOP 2B2 PRIMARY 0 DRAIN 1 1 0 0 0't 0 0 0%1 0 100%VISUAL 037 LETDOWN LINE FROM LOOP 2B1 334 66%100%0 12 3 1 0 1 0 1 0 VISUAL 186 AUXILIARY FEEDWATER PUMP 2A 0 1 0 0 0 0 0 0 0 1*ttttt 11~1114 I~litt(VISUAL 186 AUXILIARY FEEDWATER PUMP 2B 1 0 0 0 0 0 IIIIII)IIIIII't 0 0 I~I~It)VISUAL 186 AUXILIARY FEEDWATER PUMP 2C 0 1 1 1 0 0 0 0 0 100%100%100%ITEM TOTAL 97 31 9 0 12 0 29'7%10 0 100't F1.30 WELD AND MECHANICAL CONNECTIONS AT INTERMEDIATE JOINTS IN MULTZCOa~aCTED INTEGRAL AND NONINTEGRAL VISUAL 003 STEAM GENERATOR 0 2A PRIMARY SIDE 1 1 0 0 0 0 0%0%~1 0 Limited to one 100%component in a group of 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 LINE 1 0 0 0 0 0 ttttttt tttttt)0 0~ttt~It VISUAL 027 LOOP 2B2 SPRAY 0 I INE 1 0 0 0 0 0~ttttt)11*~ttt 0 0 IIIIII' DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CLASS 1 SECTION XI

SUMMARY

TABLE D PAGE: 48 CODE EDITION: 89 CATEGORY F-A-SUPPORTS SEC.XZ ITEM¹ITEM DESCRIPTION ZONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COYMENTS ITEM TOTAL 5 2 1 0 50t 0 0 50t 1 0 100t F1.50 SPRING SUPPORTS AND CONSTANT VISUAL LOAD SUPPORTS 016 PRESSURIZER SURGE LINE 0 3 1 0 0 1 0 0 0 25t required Ot 100t 100t VISUAL 017 REACTOR COOLANT 0 PUMP 2A1 ttkkt*t 11~11*t eeet*at 4 0 0 0 0 0 0 0 VISUAL 018 REACTOR COOLANT 0 PUMP 2A2******t 4%***%t I 0 1%**t 4 0 0 0 0 0 0 0 VISUAL 019 REACTOR COOLANT 0 PUMP 281 0 0 Ot 100t 100t 4 4 0 0 4 0 VISUAL 020 REACTOR COOLANT 0 PUMP 2B2 4 0 0 0 0 0 0 0****1*t'll 11%At l**'lilt VISUAL 021 LOOP 2A1 SAFETY 0 INJECI'ION PIPING INSIDE CTMI'1 0 0 Ot 0 0 Ot 1 0 100t VISUAL 022 LOOP 2A2 SAFETY 0 INJECTION PIPING, INSIDE CTÃP 3 1 0 0 0't 1 0 100't 0 0 100t VISUAL 023 LOOP 2B1 SAPETY 0 INJECTION PIPING, INSIDE CTMT 2 1 0 0 Ot 0 0 Ot 1 0 100t VISUAL 024 LOOP 2B2 SAFETY 0 INJECTION PZPING, INSIDE CTMT 2 1 1 0 100t 0 0 100t 0 0 100t VISUAL 025 COMBINED PRESSURZEER SPRAY LINE 1 0 0 0 0 0 0 0 lit~lit~*0~~*t*%%*1*t V1SUAL 026 LOOP 2B1 SPRAY LINE 0 3 1 0 0 1 0 0 0 Ot 100t 100t DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CLASS 1 SECTION XI

SUMMARY

TABLE D PAGE: 49 CODE EDITION: 89 CATEGORY F-A-SUPPORTS SEC.XI ITEM¹ITEM DESCRIPTION ZONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COKhENTS F1.50 SPRING SUPPORTS AND CONSTANT VISUAL LOAD SUPPORTS 027 LOOP 2B2 SPRAY 0 LINE 3 0 0 0~1@1~4$0 0 0 0 25%required~~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 COOLING LINE 3 1 1 0 0 0 0 0 100%100'0 100%VISUAL 030 PRESSURIZER AUXILIARY SPRAY 2 1 1 0 0 0 0 0 100%100\100%VISUAL 037 LETDOWN LINE FROM LOOP 2B1 0 3 3 2 0 1 0 0 0 66 8 100%100'0 VISUAL 038 PRESSURIZER RELIEF LINE 0 2 2 0 0 0 0 2 0 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 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 ZNSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 2 SECTION XZ

SUMMARY

TABLE E PAGE: 50 CODE EDITION: 89 CATEGORY F-B CLASS 2 SUPPORTS SEC.XZ ITEM 0 ITEM DESCRIPTION ZONE REL g OF NO.8 OF COMPONENTS SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS Fl.10 MECHANICAL CONNECTIONS TO VISUAL PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE DISCHARGE HEADER PIPING 33t 043 LPSZ PUMP 2A 0 15 3 1 0 0 0 33t 2 0 100t VISUAL 044 LPSZ PUMP 2B DISCHARGE HEADER PIPING 0 22 6 0 0 3 0 3 0 Ot 50t 100t VISUAL 045 SAFETY INJECTION 0 PIPING TO SZ TANK 2A2 7 2 1 0 1 0 0 0 50t 100t 100t VISUAL 046 SAFETY INJECTION 0 PIPING TO SZ TANK 2A1 14 3 0 0 Ot 3 0 100t 0 0 100\'ISUAL 047 SAFETY INJECTION 0 PIPING TO SI TANK 2B1 1 1 0 0,0 0 1 0 Ot Ot 100t VISUAL 048 SAFETY INJECTZOiN 0 PIPING TO SZ TANK 2B2 4 1 0 0 0\1 0 100\0 0 100't VISUAL 061 HPSI PUiMP 2A TO 0 HEADER A 7 2 2 0 100t 0 0 100t 0 0 100t VISUAL 062 HPSI PUMP 2B TO 0 HEADER B 5 1 0 0 Ot 1 0 100t 0 0 100't VISUAL 063 MAIN STEAM LINE 2A1 INSIDE CONTAINMENT 0 1 0 0 0 0 0 0 0 I 1*1~0't I~III~t 111000t VISUAL 064 MAIN STEAM LINE 0 3 1 1 0<<0 0 0 0 2B1 INSIDE CONTAINMENT 100t 100t 100t VISUAL 065 MAIN STEAM LINE 0 2A1 OUTSIDE CONTAIN<<<<ENT 4 1 1 0 100t 0 0 100t 0 0 100t DATE: 07/24/93 REVISION: 0 ST.IUCZE NUCLEAR PLANT UNIT 2 INSERVZCE INSPECTION PLAN'FOR TIK SECOND INTERVAIi CLASS 2 SECTION XZ

SUMMARY

TABLE E PAGE: 51 CODE EDITION: 89 CATEGORY F-B-CLASS 2 SUPPORTS SEC.XI ITEM¹ITEM DESCRIPTION ZONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION,REQ COMP REQ 1$T PER 2ND PER 3RD PER COSKNTS F1.10 MECHANICAL CONNECTIONS TO VISUAL PRESSURE RETAINING COMPONENTS AND BUILDING STRUCIURE 066 MAIN STEAM LINE 0 2B1 OUTSIDE CONTAINMENT 4 1 0 0 Ot 0 0 Ot 1 0 100t VISUAL 067 MAIN FEEDNATER TO SG 2A1 INSIDE COiNTAINMENT 0 2 1 1 0 0 0 0 0 100t 100t 100t VISUAL 068 MAIN FEEDWATER 0 3 1 1 0 0 0 0 0 TO SG 2B1 INSIDE CONTAINMENT 100't 100t 100t 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 VISUAL 069 CIQIRGING PUMP 2C 0 071 MAIN FEEDNATER 0 TO SG 2A1 OUTSIDE CONTAINMENT 1 0 0 0 1 1 1 0 100t 0 0 0 0 100 t'0 0 0 100t VISUAL 072 MAIN FEEDWATER TO SG 2B1 OUTSIDE CONTAINMENT 0 1 1 0 0 0 0 1 0 Ot Ot 100t 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 DISCHARGE TO AUX.HPSZ 14 4 0 0 4 0 0 0 Ot 100t 100t VZSUAL 089 CHARGING PUMP 2B 0 DISCHARGE TO AUX.HPSI 5 1 0 0 Ot 1 0 100t 0 0 100t VISUAL 090 CHARGING PUMP 2C 0 2 0 0 0 0 0 0 0 DISCHARGE TO AUX.HPSI**1 1t~t lltOIII*t**%II*t DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVZCE INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 2 SECTION XZ

SUMMARY

TABLE E PAGE: 52 CODE EDITION: 89 CATEGORY F B-CLASS 2 SUPPORTS SEC.XZ ITEM¹iTEN DESCRZPTION ZONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS Fl.10 MECHANZCAL CONNECTIONS TO PRESSURE RETAINING COMPONENTS AND BUILDING STRUCZURE VISUAL 091 COMBINED CHARGING PUMP DISCHARGE TO HPSI 0 7 2 0 0 08 2 0 100%'0 100%VISUAL 092 COMBINED DISCHARGE TO HPSZ TZE IN LOOP 2B 1 0 0 0 0 0 0'111~I~0~I~I~I%I~III~0 VISUAL 093 HPSI 2A DISCHARGE TO SDC LOOP 2A 0 18 5 0 0 0 0 5 0 0%0%100%VZSUAL 094 HPSI HEADER B TO 0 SDC LOOP 2B 15 4 0 0 0 0 4 0 0%0%100%VISUAL 095 HPSI 2A DISCHARGE TO SDC LOOP 2B 0 8 2 0 0 0 0 2 0 0%0%100%VISUAL 096 HPSI 2B DISCHARGE TO SDC LOOP 2B 1 0 0 0 0 0 0 0 IIIIII'IIIIIQ IIIIII'ISUAL 097 CONTAINMENT 0 SPRAY PUMP 2A 1 0 08 0%100%3 1 0 0 0 0 VISUAL 097 CONTAIL7KNT SPRAY PUMP 2B 3 0 0 0 0 0 0 0~IIIII'I~Illa'II~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 LOAD SUPPORTS 044 LPSZ PUMP 2B DISCHARGE HEADER PIPING 0 1 1 0 0 0 0 1 0 At least 25%Ot 100%Ot 0

DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CZASS 2 SECTION XI SUaaRY TABLE E PAGE: 53 CODE EDITION: 89 CATEGORY F B CLASS 2 SUPPORTS SEC.XI ITEM¹ITEM DESCRIPTION ZONE REL¹OF NO.¹OF COMPONENTS SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS F1.50 SPRING SUPPORTS AND CONSTANT VISUAL LOAD SUPPORTS 046 SAFETY INJECI'ZON 0 PIPING TO SI TANK 2A1 1 1 0 0 Ot 1 0 100%0 0 At least 25%100%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 2A1 INSIDE CONTAINMENT 5 1 1 0 100%0 0 100¹0 0 100%VISUAL 064 MAIN STEAM LINE 0 2B1 INSIDE CONTAINMENT 5 1 0 0 0't 0 0 0%1 0 100 t VISUAL 067 MAIN FEEDWATER TO SG 2A1 INSIDE CONTAINMENT 0 2 1 1 0 0 0 0 0 1008 100%100%VISUAL 068 MAIN FEEDNATER 0 TO SG 2B1 INSIDE CONTAZNMENT 5 1 1 0 1008 0 0 100%0 0 100%VISUAL 100 COMPONENT COOLING HATER HX 2A 8 2B INLET HEADER 0 1 1 1 0 0 0 0 0 100%100%100%ITEM TOTAL 22 8 4 0 2 0 2 0 50%75%100%F1.60 SLIDING SURFACES VISUAL 044 LPSZ PUMP 2B 0 DISCHARGE HEADER PIPING 1 0 0 0 0 0 0 0 At least 25%~~1*I~0 11~I~~0 11~I~I%VISUAL 094 HPSZ HEADER B TO 0 SDC LOOP 2B 2 1 1 0 100%'0 100%0 0 100%

DATE: 07/24/93 REVISION: 0 ST.ZUCZE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CLASS 2 SECTION XZ SUYNARY TABLE E PAGE: 54 CODE EDITION: 89 CATEGORY F-B CLASS 2 SUPPORTS SEC.XI ITEM¹ITEM DESCRIPTION ZONE¹OF COMPONENTS RBL¹OF NO.SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COWKTS ITEM TOTAL 3 1 1 0 100%0 0 100%0 0 100%CATEGORY TOTAL 242 66 25 0 18 0 37't 65't 23 0 100%

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 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVZCE INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 3 SECTION XZ

SUMMARY

TABLE F PAGE: 55 CODE EDITION: 89 CATEGORY F-C-CLASS 3 SUPPORTS SEC.XZ ITEM¹ITEM DESCRIPTION

¹OF COMPONENTS ZONE REL¹OF NO.SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRZPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS Pl.10 MECHANICAL CONNECTIONS TO VISUAL PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE 100 COMPONENT COOLING WATER HX 2A&2B INLET HEADER 0 17 3 3 0 0 0 0 0 At least 25'00%100%100'ISUAL 101 COMPONENT COOLING WATER HX 2A&2B DZSCKQtGE 0 15 5 5 0 0 0 0 0 100t 100'00%VISUAL 102 COMPONENT COOLING-SHUTDOWN COOLING HX 2A INLET 0 14 5 3 0 0 0 2 0 60%60%100%VISUAL 103 COMPONENT COOLING-SHUTDOWN COOLING HX 2B INLET 0 13 2 2 0 0 0 0 0 100%100'00%VISUAL 104 SPENT FUEL POOL 0 COOLING HX 2A DZSL7iARGE PIPING 5 2 2 0 100%0 0 100%0 0 100%VISUAL 105 COMPONENT COOLING-SHUTDOWN COOLING HX 2A DISCHARGE 0 18 7 4 0 2 0 1 0 57%85%100%VISUAL 106 COMPONENT COOI ING-SHUTDOWN COOLING HX 2B DISCHARGE 0 24 5 4 0 0 0 1 0 80%80%100%VISUAL 107 COMPONENT COOLING WATER PUMPS 2A, 2B&2C INLET 0 19 4 4 0 0 0 0 0 100%100%100%VISUAL 108 AUXILIARY FEEDWATER PUMP 2C TO MAIN FEEDWATER 0 19 i4 4 0 0 0 0 0 100%1000 100%VISUAL 109 CONDENSATE-SUCTION TO AUX.FEEDWATER PUMP 2C 0 9 2 2 0 0 0 0 0 100%100%100%

DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVZCE INSPECTION PLAN'FOR THB SECOND INTERVAL CLASS 3 SECTION XZ SUGARY TABLE F PAGB: 56 CODE EDITION: 89 CATEGORY F C-CLASS 3 SUPPORTS AS ME SEC.XZ ZTEM¹ITEM DESCRIPTION ZONE REL¹OF NO.¹OF COMPONENTS SCHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COiO4ENTS Fl.lo MECHANICAL CONNECTIONS TO PRESSURE RETAINING COMPONENTS AND BUILD1NG STRUCZURB VISUAL 110 CONDENSATE-SUCTION TO AUX.FEEDWATER PUMP 2A&2B 9 3 2 0 0 0 66%668 1 0 At least 25%100%VISUAL 111 AUX.FEEDWATER PUMPS 2A&2B DISCHARGE 0 21 10 6 0 0 0 4 0 60%608 100'C VISUAL 112 CIRCULATING 0 16 7 6 0 0 0 1 0 WATER FROM INTAKE 85%85%1008 COOLING WATER PUMPS VZSUAL 113 CIRCULATING WATER TO CCW HEAT EXCHANGER 2A 0 14 1 1 0 0 0 0 0 100%1008 100%VISUAL 114 CIRCULATING WATER TO CCW HEAT EXCHANGER 2B 0 11 1 1 0 0 0 0 0 100\100%100%'ISUAL 115 CIRCULATING WATER-CCW HEAT EXCH.2A&B DZSCHARGB 0 11 0 0 0 0 0 0 0 11~~*~\~ttttt%1111~1%VISUAL 180 LETDOWN HEAT EXCHANGER 0 2 2 2 0 0 0 0 0 100%100%100%VISUAL 181 COMPONENT COOLING WATER HEAT EXCHANGER 2A 0 4 4 4 0 0 0 0 0 1008 100%1008 VISUAL 182 COMPONENT COOLING WATER HEAT EXCHANGER 2B o o o o o o o tttttt)~*11*~$ttttttf VISUAL 183 COMPONENT COOLING WATER PUMP 2A o 4 4 4 o o o o 0 loot 1008 100%VISUAL 183 COMPONENT COOLING WATER PUMP 2B 4 0 0 0 0 0 tttttt)tttttt(0 0 tttttt)

DATE: 07/24/93 REVISION: 0 ST.LUCIS NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN'FOR THE SECOND INTERVAL CLASS 3 SECTION XZ SUYMARY TABLE F PAGE: 57 CODE EDITION: 89 CATEGORY F C-CLASS 3 SUPPORTS SEC.XZ ITEM¹ITEM DESCRIPTION ZONE REL¹OF EXAM METHOD SYSTEM DESCRIPTION REQ COMP¹OF COMPONENTS NO.SCHEDULED/COMPLETED REQ 1ST PER 2ND PER 3RD PER COYMENTS Fl.10 MECHANICAL CONNECTIONS TO VISUAL PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE COOLING WATER PUMP 2C I~IIII%183 COMPONENT 0 4 0 0 0 0 0 0 0 At least 25'IIIII%IIIIIIV VISUAL 184 FUEL POOL COOLING PUMP 2A 0 1 0 0 0 0 0 0 0 IIIIII'11~11%IIIIII%VISUAL 184 FUEL POOL COOLING PUMP 2B 0 1 1 1 0 0 0 0 0 100%100%100¹VISUAL 185 FUEL POOL COOLING HEAT EXCHANGER 2A IIIIII'IIIII)

I Ill~I8 0 2 0 0 0 0 0 0 0 VISUAL 185 FUEL POOL COOLING HEAT EXCHANGER 2B 0 2 2 2 0 0 0 0 0 100%100%100%VISUAL 186 AUXILIARY FEEDWATER PUMP 2A 1 0 0 0 0 0 IIIIII'~11'Il)0 0 I IIIIIQ VISUAL 186 AUXILIARY FEEDWATER PUMP 2B IIIII~$IIIIII'IIIII'

'0 0 0 0 0 0 0 VISUAL 186 AUXILIARY FEEDWATER PUMP 2C 0 1 1 1 0 0 0 0 0 100%100%100%VISUAL 187 SHUTDOWN COOLING 0 HEAT EX&iANGER 2A 2 2 2 0 100%0 0 100%0 0 100%'VISUAL 187 SHUTDOWN COOLING 0 2'0 0 0 0 0 0 HEAT EXCHANGER 2B IIIIII'III

~IQ IIIIII'ISUAL 188 INTAKE COOLING 0 WATER PUMP 2A 2 0 0 0 0 0 0 0 II~Ill(111~II)I~II~If VISUAL 188 INTAKE COOLING 0 WATER PUMP 2B 2 0 0 0 0 0 0 0 IIIIII%I~~~II%~~I~lit VISUAL 188 INTAKE COOLING 0 WATER PUMP 2C 2 2 2 0 100'0 100%0 0 100%

DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVICE INSPECTION PLAN FOR THE SECOND INTERVAL CLASS 3 SECTION XI SUaaRY TABLE F PAGE: 58 CODE EDITION: 89 CATEGORY F C CLASS 3 SUPPORTS SEC.XI ITEM 8 ITEM DESCRIPTION OF COMPONENTS ZONE REL 5 OP NO.'CHEDULED/COMPLETED EXAM METHOD SYSTEM DESCRIPTION REQ COMP REQ 1ST PER 2ND PER 3RD PER COMMENTS Fl.10 MECHANICAL CONNECTIONS TO VISUAL PRESSURE RETAINING COMPONENTS AND BUILDING STRUCTURE 189 COMPONENT COOLING WATER SURGE TANK 0 2 2 2 0 0 0 0 0 At least 25%100%2008, 100%ITEM TOTAL 278 81 69 0 2 0 10 0 85%'7%100%F1.30 WELD AND MECHANICAL CONNECTIONS AT INTERMEDIATE JOINTS IN MULTICONNECTED INTEGRAL AND NONINTEGRAL VISUAL 103 COMPONENT COOLING-SHUTDOWN COOLING HX 2B INLET 0 1 1 0 0 0 0 1 0 At least 25%0%08 100%P1.50 SPRING SUPPORTS AND CONSTANT VISUAL LOAD SUPPORTS e 105 COMPONENT COOLING SHUTDOWN COOLING HX 2A DISCZIARGE 0 5 1 1 0 0 0 0 0 At least 25%100%100%'00%VISUAL 106 COMPONENT COOLING-SHUTDOWN COOLZNG HX 2B DISCHARGE 0 2 2 2 0 0 0 0 0 100%100%100%VISUAL 107 COMPONENT COOLING WATER PUMPS 2A, 2B Ea 2C INLET 0 3 3 3 0 0 0 0 0 100%100%100t ITEM TOTAL 10 6 6 0 0 0 0 0 100%100%1008 Fl~60 SLIDING SURFACES VISUAL 101 COMPONENT COOLING WATER HX 2A 6(2B DISCHARGE 0 5 0 0 0 0 0 0 0 At.least 25k 1111~~$~~1111(*~~*11)VISUAL 107 COMPONENT COOLING WATER PUMPS 2A, 2B Ec 2C INLET 0'0 0 0 0 0 0 0 1~~4~1%111111%~1111~0 DATE: 07/24/93 REVISION: 0 ST.LUCIE NUCLEAR PLANT UNIT 2 INSERVZCB INSPECTION PLAN FOR THB SECOND INTERVAL CLASS 3 SECI'ZON XI

SUMMARY

TABLE F PAGE: 59 CODE EDZTZON: 89 CATEGORY F-C-CLASS 3 SUPPORTS SEC.XI ITEM¹ITEM DESCRIPTION BONE¹OF COMPONENTS REL¹OF NO.SCHEDULED/COMPLETED 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 TO AUX.FEEDWATER PUMP 2C tttltt)tttttt)11*111$VISUAL 112 CIRCULATING 0 WATER FROM INTAKE COOLING WATER PUMPS 2 2 1 0 50't 0 0 50%1 0 100%VISUAL 115 CIRCULATING 0 4 0 0 0 0 0 0 0 WATER-CCW HEAT EXCH.2A&B DISCHARGE ttttttf**1111)tttttt)ITEM TOTAL 13 2 1 0 0 0 1 0 50%'0%100'CCATEGORY 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:

CAT.8-A ITEM NO.81.10 81.11 81.12 EXAMINATION REQUIREMENTS Essentially 100%volumetric examination of all longitudinal and circumferential shell welds (does not Include shell to flange weld).8-A 8-A 8-A 81.20 81.21 81.22 81.30 81.40 Essentially 100%volumetric examination of accessible length of circumferential and meridional head welds.Essentially 100%volumetric examination of the shell to flange weld.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 45'ull vee path scans, except for a small area of interference from the 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 45'ull vee path beam.The 0'nd 60'eam limitations are shown on 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 60'eams;however, the 45'ull vee path scans obtain full coverage.The 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 number Examination Area identification Beam Angle Beam Direction Percent Coverage Figure No.Description of Examination Coverage and Limitations 000020 Bottom Head Peel Segment Weld 9 30 Deg.NO.101-154A 0 LAII 45'0'0/70' WRV 45'T 60'T 50/70 T CW/CCW CW/CCW CW/CCW UP/DN UP/DN UP/DN 62%62%62%62%62%69%70%72%1&2 Examination of IWB-2500-3 E-F-G-H volume limited along length of weld near flow skirt-lower head attachment.

000030 Bottom Head Peel Segment Weld 9 90 Oeg.No.101-1548 O'am 45'0'0/70' WRV 45'T 60'T 50/70 T CW/CCW CW/CCW CW/CCW UP/ON UP/DN UP/DN 50%54/62%54/62%54/62%62%69%70%72%1,2,3 Examination of IWB-2500-3 E-F-G-H volume limited along length of weld near flow skirt-lower head attachment and at flow skirt support bracket.Page 102 of 272 ST.LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 1 Stannary nwher Examination Area Identification Beam Angle Beam Direction Percent Coverage Figure Ho.Description of Examination Coverage and Limitations 000040 000050 000060 000070 000080 000110 Bottom Head Peel Segment Weld oI150 Deg.No.101-154C Bottom Head Peel Segment Weld 9210 Deg.No.101-'154D Bottom Head Peel Segment Weld 9270 Deg.No.101-154E Bottom Head Peel Segment Weld 9 330 Deg.No.101-154F Bottom Head-to-Lower shell Circ.Weld No.201-141 Lower Shell Long.Weld 8225 Deg.No.101-142C O'am 45'0'0/70RV 45'T 60 T 50/70'T O'am 45'0'0/70' WRV 45 T 60 T 50/70'T O'am 45'0'0/70' WRV 45'T 60 T O'am 45'0O 50/70RV 45 T 60'T 50/70'T O'am 450 60'0/70'WRV 45 T 60 T 50/70 T O'am 45'0'0/70' WRV 45 T 60'T 50/70'T O'M/CCW CM/CCW CW/CC'M UP/DN UP/DN UP/DN CW/CCW CW/CCW CW/CCW UP/DN UP/DN UP/DN CW/CCW CW/CCW CW/CCW UP/DN UP/DN UP/DN CW/CCW CW/CCW CM/CCW UP/DN UP/DN UP/DN CW/CCM CW/CCW O'M/CCW UP/DN UP/DN UP/DN CW/CCW CW/CCW CW/CCW UP/DN UP/DN UP/DN 62%62/62%62%62/69%70%72%58%54/62%54/62%54/62%62%69%70%72%62%62%62%62/62%69%70%72%58%54%/62%54%/62%54%/62%63/69%70%72%93%100%/86%100%/88%100%/84%93%93%93%93%87%100%/85%>OO//77/100%/87%100%100%100%100%1&2'1.2.3 182 1,2,3 184 1&5 Examination of IWB-2500-3 E-F-G-H volume limited along length of weld near flow skirt-lower head attachment.

Examination of IMB-2500-3 E-F-G-H volune limited along length of weld near flow skirt-lower head attachment and at flow skirt support bracket.Examination of IWB-2500-3 E-F-G-H volwe limited along length of weld near flow skirt-lower head attachment Examination of IMB-2500-3 E-F-G-H volume limited along length of weld near flow skirt-lower head attachment and at flow skirt support bracket.Examination of IWB-2500-3 E-F-G-H volwe limited along length of weld below core barrel anti-rotation lugs.Examination of IWB-2500-2 A-B-C-D volume limited from one side along length of weld near reactor vessel material specimen tubes.Page 103 of 272 ST.LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 1 Sunna ry number Examination Area Identification Beam Angle Beam Direction Percent Coverage Figure No.Description of Examination Coverage and Limitations 000120 000150 000170 000180 000190 000200 Lower Shell-to-Intermediate Shell Circ.Weld Ho.101-171 Intermediate Shell Long.Weld 8255 Deg.No.101-124C Upper Shell Longitudinal Weld ol15 Deg.Ho.101-122A Upper Shell Longitudinal Weld oI 135 Deg.No.101-1228 Upper Shell Longitudinal Weld 8255 Deg.No.'101-122C Upper Shell-to-Flange Circumferential Weld No.101-121 O'am 45'0'0/70RV 45'T 60 T 50/70 T O'am 45'0'0/70' WRV 45 T 60 T 50/70'T O'am 45'0'0/70' WRV 45'T 60 T 50/70'T O'am 45'0'0/70' WRV 45 T 60 T 50/70'T O'am 45'0'0/70' WRV 45 T 60 T 50/70 T O'am 45'0'0/70'0 WRV 45'T 60 T 50/70 T CW/CCW CW/CCW CW/CCW UP/DN UP/DN UP/DN CW/CCW CW/CCW CW/CCW UP/DH UP/DH UP/DN CW/CCW CW/CCW CW/CCW UP/DN UP/DN UP/DH CW/CCW CW/CCW CW/CCW UP/DN UP/DH UP/DN CW/CCW CW/CCW CW/CCW UP/DH UP/DN UP/DH CW/CCW CW/CCW CW/CCW UP/DH UP/DN UP/DN 92/.92%92%92%85%85/85/.83%74%100%/70%100%/55%100%/74%100%100%100%1005 95%100%/96%100/96%100%/99%97%79/74%95%96%100%/98%100%/98%100%98%Br%83%97%96%100%/98%100%/98%100%98%Bri 83%97/70/87%80%707 50%50%50%50%185 186 Examination of IWB-2500-2 A-8-C-D volune limited along length of weld near vessel material specimen tubes.Examination of IWB-2500-2 A-8-C-D voiunc limited along length of weld near vessel material specimen tubes.Examination of IWB-2500-2 A-B-C-D volune limited at intersection with the adjacent outlet nozzle integral extension.

Examination of IWB-2500-2 A-B-C-D voiune limited at intersection with the adjacent inlet nozzle inner blend.Examination of IWB-2500-2 A-8-C-D volune limited at intersection with the adjacent inlet nozzle inner blend.Examination of IWB-2500-2 A-B-C-D volune for Transverse flaws is limited above the weld by the inside surface taper.Page 104 of 272 ST.LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 1 Summry nwber Examination Area Identification Beam Angle Beam Direction Percent Coverage Figure No.Description of Examination Coverage and Limitations 000210 000240 000790 000800 000810 000820 000830 Outlet Nozzle 0I 0 Dcg.Hozzlc-to-Shell Weld.No.105-121a Outlet Nozzle 8 180 Deg.Nozzle-to-Shell Meld No.103-1218 Flange to Torus Weld Ho.101-101 Peel Segment weld 0I 0'01-104-A Peel Segment Weld 0I 90'01-104-8 Peel Segment Weld 9 180'01-104-C Peel Segment Weld 0j 270'01-104-0 0 WRV 45'T 60 T 50/70'T 0 WRV 45 T 60 T 50/70'T O'WRV 45 A 60 A 45 60 0 WRV 45 T 60'T 45 60'WRV 45 T 60'T 45'00 0 WRV 45 T 60 T 45'0'WRV 45'T 60 T 45'0'hell Shell SheLL Shell Sh@L L Shel l SheLL Shell Flange Shroud UP/DOWN UP/DOWN CW/CCW O'M/CCW UP/DOWN UP/DOWN CM/CCW CW/CCW UP/DOWN UP/DOWN CW/CCW CWICCM UP/DOWN UP/DOWN CW/CCM CWICCW UP/DOWN UP/DOWN 28/i 28/28%28%28/i 28/>>28/i 28%80/i 100/70/70/60%100/50%100/100%80%100/80%100/80%100/60/.100/50%80/100/80%100/80%100/60%100/50%80%100/80%100/80%100/60%100/50%80/i 100/80%100/80/i 100/60%100/50%9,10,11 10&13 10&13 10&13 10&13 Examination of IWB-2500-7-A-B-C-0-E-F-G-H-I and M-N-0-P volunes transverse examination from shell is limited by the integral extension.

Examination of IMB-2500-7-A-B-C-D-E-F-G-H-I and N-N-0-P volumes transverse examination from shell is Limited by the integral extension.

Examination of IWB-2500-5 volune limited at intersection of flange flex radius, shroud, shroud hold down lugs, and head lifting lugs.Examination of IMB-2500-3 volume limited by location of shroud and at intersection of adjacent weld 101-101 and shroud.000840 Dome Weld Ho.102-101 0 LAN 45 60'5'0'W/CCW CM/CCW UP/DOWN UP/DOWN 40%35/90%25/80%20/35%10/80%9&13 Examination of IWB-2500-3 volume limited by location of shroud and at intersection of adjacent weld 101-101 and shroud.Page 105 of 272 60'90'I 120 135 180'40'55'70' I 101-121 I C3 300'I 360'AREA OF ID TAPER NOZZLE INTERFERENCE WITH VERTICAL WELD TRANSVERSE SCANS~101-122A~101-122B~106-121~101-122C RPV MATERIAL SPECIMEN TUBES~101-124A~101-1248 101-124C~33'53'3~101-171~101-142A O 60'3 97'04 120~101-14 28 0 180~201-141 277 284'63'101-142C 300'60'LOW SKIRT SUPPORT CORE BARREL ANTI ROTATION LUG 40 85 90'30 150'60'05'10'50'70'80'25'30'LOVI SKIRT UPPER EDGE 101-154A 101-1548 101-154C 101-154 D 101-154E 101-154F FLOW SKIRT 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 79.82 SIDE SECTION VIEV!PEEL SEGMENT WELDS WELDS 101-154A THRU F FIGURE 1.2 PARALLEL EXAM SECTION AT BOTTOM OF WELD TRANSVERSE EXAM r FLOW SKIRT SUPPCRT f EXAM UMITATION SECTION AT SKIRT SUPPORT I I I I II I I III I 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 PARALLEL EXAMINATION UMITATION TRANSVERSE EXAMINATION UM I TATI ON 1/2 t CORE SUPPORT LUGS 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')PARALLEL EXAMINATION LIM I TATlON NO TRANSVERSE EXAMINATION UMI TATI ON 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 II-PARRALLEL SCAN J.-PERPENDICULAR SCAN O'-CAUBRATED LONGITUDINAL ULTRASONIC EXAMINATION OF RPV FLANGE CLOSURE HEAD'AELD 10 23 6" 0 60oJ 45+V, 11 II HEAD I.D.SURFACE 101-104 A-D 45'l 60'3.0 WRV 6" 23" 101-101 6" FLANGE 45 II 60 II 23" CLAD ID PRESSURE RETAINING SURFACE (I.D.SURFACE CLAD O.D.SURFACE PSL RPV CLOSURE HEAD WEl DS FIGURE 1.10 SHROUD LOCATION SCAN DIRECTION 1/2 T WOW 6.2 SCAN DIRECTION 1/2 T FLANGE FLEX AREA 60 60 WELD NO.101-101 FlGVRE 1.11 FLANGE FLEX AREA LIMITATIONS (TYPICAL)SHROUD LUG WELD CROWN 16'I/4" 6 2/10" FLANGE UP 2 5/10 RPV STUD HOLE N LUGS LOCATED AT STUD HOLES;LUG SHROUD LUG III 3O/f 8$12 g 39$17 f 44 III 21 g 48 g 25 III 53 NOTE: LUGS ARE SPACED 38" APART LOCATED BY ADJACENT RPV STUD HOLES.EXAMINED FROM STUD HOLE 0 THROUGH 28 CLOCKNSE LOOKING DOWN.FIGURE 1.12 101-10%-C SAN HA%90 OOO QO~""o'Q72 Q15 52Q Q20Q7 61Q Q2 60 Q19 Q6 51Q Q14<0<Q43 Q oQOo O O 2~O 42 Q O O 56+ooo o 070 0 0 0 oQo 12Q22 Q 0 16Q 23 4O, Oa O"'2O Os7 ,O O-Oss 76 P o o 69 0 0 , oQOo 0 O 270 101-10+-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:

CAT.B-D ITEM NO.83.110 EXAMINATION REQUIREMENTS 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 Identification PZR spray Nozzle-to-Upper head weld No.103-601 PZR Safety Valve Nozzle-to-Upper Head Weld No.108.601-A Beam Angle 60'0o 454 Coverage (cRv)70%One side 80%one side 95%one side Fig.1&2 Description of Limitations Nozzles are mutually interfering, when other nozzle is directly opposite on scan line Nozzles are mutually interfering, when other nozzle is directly opposite on scan line Page 121 of 272

ST.LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 3 Examination coverage Examination Area identification PZR Safety Valve Nozzle-to-Upper Head Weld No.108-601-B PZR Safety Valve Nozzle-to-Upper Head Weld No.108-601 PZR Safety Valve Nozzle-to-Upper Head Weld No.108401-D PZR Surge line Nozzle Weld NO.105-651 Beam Angle 60'5o 60'5o 60o 600 45o Coverage (CRV)70%one, side 85%one side 70%one side 95%one side 80%one side 60%one side 100%one side Fig.1&2 182 Description of Limitations Nozzles are mutually interfering, when other nozzle is directly opposite on scan line Nozzles are mutually interfering, when other nozzle Is directly opposite on scan line Nozzles aro mutually interfering, when other nozzle is directly opposite on scan line Scan obstructed by ten Heater attachments.

Page 122 of 272 NOZZLE NELDS ON THE TOP OF PRESSURIZER, ZONE-5 NOTE: SCAN PATH OF EACH NOZZLE ARE NOTED BY DOTTED LINES.SCAN PATH 8" FROM WELD Q PER NDE 5.1 (FOR 45)AREAS WHERE DOTTED UNES INTERSECT NOZZLES SHOW SCAN LIMITATIONS 180 90'ANWAY LUG 108-601-A//40 I 108-601-B I m4.0".ji 4"~X r 1 X-106 601 C~L.~~~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 AREAS WHERE DOTTED UNES INTERSECT NOZZLES SHOW SCAN UMITATIONS NOTE: SCAN PATH OF EACH NOZZLE IS SHOWN BY DOT1ED UNES, SCAN PATH~12" FROM Q (FOR 0'-60')180'0'ANV/AY LUG~108-601-A/o ri7 3/4"/108-601-C p-Z.'/4'I/7 1/4"~/I 7/~8 1/+" I/'+W/108-601-D~10 3/4" LUG 270 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 C-I A-1 9" 160'-4 11.5" B-I 90'-10-270'-2 10'C-2 11.5 9" 04 WELD NO.105-651 11.5" C-3+A-3 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: Identification of components:

Description of components:

1AND 2 Longitudina/

Welds Intersecting Longitudinal We/ds of Selected Circumfereri tia/Welds B.EXAMINATION REQUIREMENTS:

EXAMINATION CATEGORY B-J C-F-1 C-F-2 EXAMINATION ITEM NUMBER B9.12 B9.22 C5.12 C5.22 C5.42 C5.52 C5.62 C5.82 EXAMINATION DESCRIPTION Nominal Pipe Size 4.0 inch or Greater.Nominal Pipe Size c 4.0 inch.>3/8 inch Nomina/Wall Thickness for Piping>NPS 4.0inch.>1/5 inch Nominal Wall Thickness for piping>NPS 2.0inch and (NPS 4.0 inch.Branch Piping>2.0 inch Longifudinal Welds>3/8 inch Nominal Wall Thickness for Piping>4.0 inch>1/5 inch Nominal Wall Thickness for piping>NPS 2.0 inch and<NPS 4.0 inch.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

2.ST.LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 4 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 will be 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 CAT.BJ B-F ITEM NO.B9.1 1 B5.130 EXAMINATION REQUIREMENTS Essentially 100%volumetric and surface examination of Circumferential welds for>4" nominal pipe size.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 liftoff occurs, 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 Identification Angle Coverage (CRV)Fig.Description of Limitations 2A2 Inlet Field Weld Safe end to Pump weld No.RC-115K 2A2 RCP Inlet shop weld Elbow-to-safe end weld Number RC-115-1501-771-A 2A2 RCP Outlet Field weld, Safe end to Pipe weld Number RC-116-701-771 2B1 RCP Inlet.shop weld elbow-to-safe end weld No.RC-1 16-1 501-771-B 2B1 RCP Outlet Field weld, Safe end to Pipe weld No.RC-121-5 2B1 RCP Outlet Shop weld, Safe end to Pipe weld No.RC-1 21-901-771 45'5'5'5'5'6'0%

from Safe End 0%from Pump side 100%from Elbow 0%from safe end 100%from pipe 30%from safe end 100%from Elbow 0%from safe end 100o from Elbow 0%from safe end l 00'rom Pipe and Safe end 2 Examination limited by configuration.

Examination limited by configuration.

Examination limited by configuration.

Examination limited by configuration.

Examination limited by configuration.

Examination limited by configuration.

Page 132 of 272 ST.LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 5 Examination Coverage Examination Area Identification 2A1 RCP Inlet whop weld Elbow-to-safe end weld no.RC-112-1 501-771-C 2A1 RCP Outlet Shop weld, Safe end to Pipe weld No.RC-112-1 066-771 2B2 RCP Inlet shop weld Elbow-to-safe end weld No.RC-124-1 501-771-D 2B2 RCP Inlet Shop weld safe end to Pipe weld No.RC-124-1 301-771 Beam Angle 45'5'5'5'overage (CRV)100%from elbow 20%from safe end 100%from Pipe and Safe end 100%from Elbow 0%from safe end 100%from pipe 30%from safe end Fig.Description of Limitations Examination limited by configuration.

Examination limited by configuration.

Examination limited by configuration.

Examination limited by configuration.

Page 133 of 272

INCONEL BU TTERING INLET CONFIGURATION RGURE 1~ICAL CONTOURS 8-2 B-1 A-1 (/I ELBOW SA-351 CFBM r I I I I I l l l l l l'l l l l l\'l l\\l\l l\I (SHOP WELD//3OS ss I/I (I (I I (7 SAFE ENO SA-351 CFBM l l l\'l\l 3.FIELD WELD INCONEL I I I (I I I I I I/I ((I (I (I (I I (-1 I I I I Jg I I I I I I I SA-351 I CFBM I I I I I PUMP I SAFE I END I I I I I I I I I I I I CLAD SUBJECT OF REUEF REQUEST NO.5 OUTLET CONF'IGURATION FIGURE 2 PUMP CASING FIELD VELD)//SAFE SHOP VELD PIPE SUBJECT OF'ELIEF REQUEST 5 0 IC FULL SCALE MOCK-UP F'IGURE 3 SA-516 GR 70 INCONEL VELD l~0 0 g SA-351 CFSM 308 VELD i~o o o SA-351 CFSM AXIAL SCAN CALIBRATION CIRCUMFRENTIAL SCAN CALIBRATION IMP INGMENT 40 IMP INGMENT INCIDENT 40 POOR RESPONSE 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 EXAMINATION TECHNIQUE 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: NRC Docket Number: Document Number: Revision Number: August 8, 1983 50-389 RR-5 Date: July 24, 1993 ST.LUCIE UNIT 2 SECOND INSPECTION INTERVAL.RELIEF REQUEST NUMBER 5 1.0 EXAMINATION ITEMS 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 EXAMINATION ACCESS 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 of interest 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 liPoff occurs, 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 weld joints (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 of identical materials with a duplication of as much of the 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 for field 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 of the 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 EX4MINATION PERFORMANCE.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, if any.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 centrr Jr 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 EX4MINATION VOLUME ACHIEVED (PRESERVICE)

SAFE END WE'D A-1 INLET A-2 INLET B-1 INLET SHOP WEM*ELBOW SIDE 10'0.100 100 SHOP WELD*SAFE END.SIDE 20 FIELD WELD**SAFE END SIDE 30 20 10 FIELD PUMP SIDE 30 Page 441 of 272 ST.LUCIE UNIT 2'ECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 6 SAFE END WELD B-2 INLET SHOP TED*PIPE SIDE 100 SHOP WE'D*SAFE END WELD FIELD WELD**SAFE END SIDE 10 FIELD WELD**PUMP SIDE A-1 OUTLET 100 100 100 A-2 OUTLET 100 B-1 OUTLET 100 B-2 OUTLET 100 30 100 30 50 100 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 Identification 2A2 Inlet Field Weld Safe end to Pump weld No.RC-RC-115-4 2A2 RCP Inlet shop weld Elbow-to-safe end weld no.RC-115-1501-771-A 2A2 RCP Outlet Field weld, Safe end to Pipe weld No.RC-1 15-701-771 Beam Angle 45'5'5'overage (CRV)20%from Safe End 0%Pom Pump side 100%from Elbow 0%from safe end 100%Pom pipe 30%Pom safe end Fig.1 3 5 6 7 8 9 10 2 3 4 5 6 7 8 9 10 ll 12 13 14 15 Description of Limitations Examination limited by confi guration.Examination limited by configuration.

Examination limited by configuration.

Page 143 of 272 ST.LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 5 Examination Coverage Examination Area Identification Beam Angle Coverage (CRV)Fig.Description of Limitations 2BI RCP Inlet shop weld Elbow-to-safe end weld No.RC-115-1501-771-B 2B1 RCP Outlet Field weld, Safe end to Pipe weld No.RC-121-5 2B1 RCP Outlet Shop weld, Safe end to Pipe weld No.RC-121-901-771 2Al RCP Inlet shop weld Elbow-to-safe end weld no.RC-1 12-1501-771-C 2AI RCP Outlet Shop weld, Safe end to Pipe weld No.RC-112-1066-771 45'5'5'5'5'00%

from Elbow 0%from safe end 100%Pom Elbow 0%from safe end 100%from Pipe and Safe end 100%from elbow 20%from safe end 100%from Pipe and Safe end 16 17 18 19 20 21 22 23 24 25 26 27 28 29 27 28 29 30 31 32 33 34 35 36 37 38 39 40 Examination limited by confi guration." Examination limited by confi guration.Examination limited by configuration.

Examination limited by configuration.

Examination limited by configuration.

Page 144 of 272 ST.LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 5 Examination Coverage Examination Area Identification 2B2 RCP Inlet shop weld Elbow-to-safe end weld no.RC-124-1501-771-D 2B2 RCP Inlet Shop weld safe end to Pipe weld No.RC-124-1301-771 Beam Angle 45'5'overage (CRV)100%from Elbow 0%from safe end 100%from pipe 30%from safe end Fig.41 42 43 44 45 46 47 48 49 50 51 52 53 54 Description of Limitations Examination limited by configuration.

Examination limited by'onfiguration.

Page 145 of 272 PARTIAL COVERAGE FROM SAFE END SIDE OO 375'5%/////I l I t 1\CODE VOLUME///////r 225'35'ELD NO.RC-115-4 RCP 2A2 INLET FlELD WELD, EXTENT OF EXAMINATION-SECTIONAL VIEW 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-SECTICNAL VIEW FIGURE 5.2 SCAN LlhUT ELBOW\\\\!\l l'!l'!'l l I I I I I I SHOP WELD I I I I I I I I I I~I SAFE ENO I I I I I I\-I I'!I'!I I'!FIELD WELD\I I l I I l I I I~*~~l~~~~~I~l I I I'!I I l I I I/PUMP 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 ELBOW l l l\\\'I\I I I I SHOP WELD I I I I I I I I I I I I I*'AFE ENO I I I I I I l I l I\I\I I'l 1 FIELD WELD\I l I'l I l I I I I'l I I I l I'l I l I I l I/PUMP'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 ELBOW SCAN LIMIT l l l l I I I I I SHOP WELD I I I I I I I I I I I I I EXAMINATION COVERAGE (CUT AWAY VIEW)SAFE END I I I I I I l I l I I'1 I I l FIELD WELD I\I\I\I l I l I'l I I~l~~'I l I I I I l I I\I X P,/PUMP 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 ELBOW SA-351 CFBM 1 0 1 m\\\1'1 I I SHOP'hELD I 308 WELD o SS I I pQ I I I I SAFE END SA-351 CF8M'1 1 1 1 1\'I 1\\\FIELD VELD INCONEL'IELD I I I I I I I I I I I I I I I I I I I PUMP CASING SA-351 CFUM 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 ELBOW l l l l\l l'l I/-I I I SHOP WELD I I I I I/I I I f I I I SAFE END\\'l l l l l\\\\l l flELD VELD/I I I I I I I I I I I I I I I I I I I PUMP 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 ELBOW l l'l l l l l SHOP BELD I I I I I I I I I I I I f I I I I I I I\SAFE ENO l l l l l l I I I I I I f I I I I I I I I-I I I I I I I I PUMP 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 ELBOW\l 1'I\1 I I I SHOP WELD I I I I I I I I I I I I I SAFE END I I I I l I FIELD WELD I l I I\I\/\I\I I I\~I\I I I l I I l I I I)X/PUMP 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 ELBOW l\\l l'l l\l SHOP WELD I I I I I I I I I I I I SAFE END\\l'l'l'l l l\l RELD WELD I I I I I I I I I I I I I I I I I I I I I I I I l I I I I l I I/PUMP 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 CODE VOLUME 270'D 225'35'80'ELD NO.701-771 RCP 2A2 INLET SHOP WELD, EXTENT OF'XAMINATION-SECTIONAL VIEW FIGURE 5.1'I SCAN LIMIT PIPE\l l l l\l'l'l l'l l LILIITEO SCAN AREA I I I SAFE END'l\l l\r 4 OP WELD (I (I I I I I I I-I I I I I I I I I I I I I I FIELD WELD l I/I I I I I I I (I I I I I I I I PUMP 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 PIPE SA-51 6 GR-70 304 SS ROLL BONDED\1\\l I I I SHOP WELD I 308 I WELD I 8 I I I I I I I ga4C4 4 4 4 aa'%e c 4 SCAN UMIT SAFE 0 SA-351 CFBM 0~0~a\\\\'l\l l\FIELD WELD INCONEL WELD I I I I I I I I I I I I I I I I I I I I I I I I I I I I PUMP CASING SA-351 CFSM 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 PIPE'l\\SHOP WELD\'l'l v o , LIMITED SCAN--/~////////l/SAFE END///\././//////(FIELD WELD l l X P./I I I I I I I I I I I I I I I/I'PUMP WELD NO.115-5 AND 701-771 RCP 2A2 OUTLET SAFE END WELDS.PROFILE AND EXTENT OF COVERAGE AT 160 FIGURE 5.14 PIPE 1'1 1\'1 1 1'1\1 1 I I SHOP WELD (I I I/I I I I I I I I I I I I Ps~4p 4 SCAN UMIT SAFE END 4a\1'1 1\\'1 FIELD WELD I I I I I I I I I I I I I I I I I I I I l I I I I I I PUMP 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-SECTIONAL VIEW FIGURE 5.16 SCAN LIMIT\l l I I SHOP WELD I I I I I I I I I I I I I SAFE END SCAN LIMIT\l FIELD WELD'l I I I I I I I I I I I PUMP l\I I\I/WELD NO.1501-771-B AND 121-4 RCP 2B1 INLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT 000 F1GURE 5.17 ELBOW SCAN LILIIT'l l l l\\l\'l l J g I I SHOP WELD/I I I g I g I g.I I I g I I SAFE END I l I I I I\I l I l I I'I I I l FIELD WELD I\I l I l l I'l I I\l i'l I l l l I I I/PUMP 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 ELBOW'l l l 1\l l I I I I I SHOP WELD I I I I I I I I I I AFE END F LD WELD\'I'l l I'l I l I\I I\I/I I I I I I I I I I I I I I I I I I I I I PUMP WELD NO.1501-771-8 AND 121-4 RCP 281 INLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT O90 FIGURE 5.19

ELBOW l\SHOP WELD'l\l I I I I I I I I I I I I-SAFE END'l l 1'l I I I I\I I l I/I I I I I I I I I I I I I I I I PUMP WELD NO.1501-771-8 AND 121-4 RCP 2B1 INLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT 135'IGURE 5.20 ELBOW I l\l l l l\l\SCAN LIMIT I 1 I I I SHOP WELD I I I I I I I I I I I I I I SAFE ENO I I I I I I I I I 1 I\I I l I FIELD WELD l I I'!I\\l I\I I I l i.I.=-l I l I I I'l'i I I I I/PUMP WELD NO.1501-771-8 AND 121-4 RCP 281 INLET SaFE ENO WELDS, PROFILE ANO EXTENT OF COVERAGE AT 180'IGURE 5.21 ELBOW l\'I'l\'l l SHOP WELD l l'l\'I I I I I I I I I I I I I I I I I I I'I I SAFE END'l l l'l 1 FIELD WELD I I I I I I I I I I I I I I I I I I"'I I I I I I I I PUMP WELD NO.1501-771-8 AND 121-4 RCP 281 INLET SAFE ENO WELDS, PROFILE AND EXTENT OF COVERAGE AT 225'IGURE 5.22 EL80W SCAN UMIT 1 1\1 1 SHOP WELD 1 1 1'1'1 1'1 r r I I I I I I I I I I I I I I I I I I!SAFE END FIELD WELD 1 1 1 1 I I 1\I 1 I 1 I/I I I I I l I I I I I I I I I I PUMP WELD NO.1501-771-8 AND 121-4 RCP 281 INLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT 270'IGURE 5.23 ELBOVl SCAN UMIT l\l l'l\l\l'l\l l f I SH0 FIELD I I I I I I l I I I I I I t I AFE END UMISSO SCAN FIELD Vt'ELD l l\\\I I I I I'l I/I I l I l I I I I I I I I I I I I I I PUMP 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-SECTIONAL VIEW FIGURE 5.26 SCAN ARC PIPE l l l 1 I I I I SHOP WELD (I I I I I I I I I I I I I I I SCAN LIMIT END\l l l\l FIELD WELD I I I I I I I I I I I I I I I I I I I PUMP 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 PIPE l l l l SHOP WELD I I I I I I I I I I I I I I I I I I I I I I SCAN LIMIT END l'I l'l\l FIELD WELD I I I I I I I I I I I I I I I I I'I'UMP WELD NO.121-5 AND 901-771 RCP 2B1 OUlLET SAFE ENO WELDS, PROFILE AND EXTENT OF COVERAGE AT 180'IGURE 5.28 PIPE\'l l l\l l\\l l'I l SHOP WELD I I I f I I I I I I I I I I I I I I I SCAN LIMIT END\1\l'l FIELD W'ELD I I I I I I I I I I I I I I I I I I I'I'UMP 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-SECTIONAL VIEW 0 375 45 CODE VOLUME ID 225'35 180 FULL COVERAGE ACHIEVED FROM ELBOW SIDE RGURE 5.30 SCAN UMIT ELBOW l\l\\l\l\\'l\I I I I SHOP WELD I I I I I I I I I I I~-l\l SAFE ENO l l'l l'l l l FIELD WELD SCAN UMIT~g ppl gpss.q5 GE~e<1'I I I I I I I I PUMP I I I I I I I I I'(I 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 SCAII UMIT SCAN UMIT ELBOV/\l l'l l l l l l l l l l l\SHOP WELD I f I f f I f f f f f f I f f f f f f I I I f f f f f I'1 SAFE END l l l\\l SURFACE INSUFFICIENIEY SMCCIN FCR SURFACING RELO LO I I f f I f I PUMP f I I f f f 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 ELBOW l'l\\'I l l'!'l l\r I I I I I i I SHOP%E g I I i I I j FI I I I I I t I SAFE ENO\\'!l l\\l l SURFACE INSUFFICIENILY SMOOIN FOR SURFACING I I I I I I I I I PUMP I I l I I I I I I I//////////WELD NO.1501-771-C AND 112-4 RCP 2AI INLET SAFE DID WELOS, PROFILE AND EXTENT OF'OVERAGE AT 135 BOTTOM NOT ADEQUATELY COVERED DUE TO STEEP IMPINGEMENT ANGLE FIGURE 5.33 SCAN UMIT SCAN LIMIT ELBOW l\\l'I\'l\\l l'l l\\\l l\SHOP Yic i I I I I I I I I I I I l I I I I I I I I I I I SAFE END l i\l'l\\I I I I I I I I PUMP I I I I I I l I I I//////////YiELD NO.1501-771-C ANO 112-4 RCP 2Al INLET SAFE ENO WELOS, PROFILE ANO EXTENT OF COVERAGE AT 180 ROOT NOT COVEREO DUE TO STEEP IMPINGEMENT ANGLE FIGURE 5.34 SCAN UMIT SCAN LIMIT SCAN UMIT ELBOW 1 l 1\1 1 1 1 l'1 l SHOP WELD I I I I I I I I I I I I I I I I I I I I I I SAFE ENO\\\1 FIE WELD I I I I I I I I I PUMP I I I I I I 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 UMIT SCAN UNIT ELBOW 1 1\1\'1 1 1 1 1 1 1 1 1\I I I I I I OP WELD I I I I I I I I I I I I I I I I I I I SAFE END\1'1 1\1 1\I I I I I I I I I PUMP I I I I 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 LIMIT SCAN UMIT EL80V/\l l\'l\\'l l l\\I I I I I I I I I I I I SH W'ELD I I I I I I I I I SAFE END\\\\'l l l\FIELD VELD I I I I I I I I I PUMP I I I I 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-SECTIONAL VIEW 0 CODE VOLUME 270 ID 90 OD 225 135 180 FULL COVERAGE ACHIEVED FROM BOTH SIDES RELIEF 5.38 SCAN UMIT PIPE l'l l\\l'l'l l\\'l l\l l I I I I/I/I/I/I SHOP WELD I I I I I I I I I/I I I/I SAFE END\l l'l'l'l l'l'l FIELD WELD I I I/I I I I I I/I I I I PUMP 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 PIPE 1 1\\\\1 1 1 1\1 I I I I I I I I I I SHOP WELD I I I I I I I I I I I SCAN UMIT SAFE END'1 1\\1 1 1'1'1 FIELD WELD I I I I I I I I I I I I I I PUMP 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-SECTIONAL VIEW 375'5'ODE VOLUME ID 225'35'80'ULL COVERAGE.FROM ELBOW SIDE flGURE 5.41 SCAN UMIT ELBOW\l'l\l l l I I SHOP LD I I I I I I I SAFE END I I I I I I f I\I'l FIELD WELD I I\I I l I'l I l I l I\I\I\I\I I'!I l I I l I X X I PUMP 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 ELBOW l l'I l l\l\\l g I I g SHOP WELD/I g I i i I t I I g i I l-=I I I I SAFE END I I I I II I I I II\FIELD WELD j I l l I I l'l I~\~~'I'I I I l I l I l I/PUMP 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 ELBOW l l l l\\'i I I I I I SHOP WELD I I I I I I I I I I SAFE END I SCAN UMIT'!\FIE WELD I\I l I I\I l I l I I II I I l I l I\I I l I X/PUMP 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 ELBOW l\'I l l\\l l l l l'I l l l I I I I I I SHOP WELD I I.I I I I I I I I I I I I SAFE END I I I I I I I\I\I FIELD WELD 1 I f l I'l l I I\I I l\I I\l I\I I I PUMP 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 ELBOW\l l l l l l'I l l SHOP WELD I I I I I I I I I I I I I I I I I I SAFE END SCAN UMIT l\'l l l I I I I I I I I IELD WELD I I I I I I l I I I~I'l I I l I I'l I I\I/PUMP 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 ELBOW l l\l l\l l l l l I I I I I I I SHOP WELD I I I I I I I I I I I I I I I SAFE END I I I I l I l I l I I l I l FIELD WELD I PUMP l I l I I'l 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 ELBOW SHOP WELD I I I I I I I I I I I I I I I I SAFE END I I I I l I'l I I I l I 1 FIELD WELD I\I I I l I'l I I I I~~~----~~~---~I I l I I l I I'l I I'l I/PUMP WELD NO.1501-771-D AND 124-2 RCP 2B2 INLET SAFE END WELDS, PROFILE AND EXTENT OF COVERAGE AT 225 FlGURE 5.48 ELBOW'l l l l l l\\'l l'l\'l\l l l l 1\'I SCAN LIMIT I I I I I I I I SHOP WELD I I I I I I I I I I I I I I I SAFE END l l\'l l 1\l l FIELD WELD I I I I I I I I I I I I I I I I I I I I I I I I PUMP 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-SECTIONAL VIEW 0 375 45 CODE VOLUME 270 ID 90 225 135 180 100Fe COVERAGE ACHIEVED FROM PIPE SIDE RGURE 5.50 PIPE SCAN UMIT\1 1'1 1 1 1 1 1 1 1 1'1'1'1 SCAN AREA I I I I SHOP WELD I I I I I I I I I I I I II I I I I I I SAFE END'l\'1\1 1\FIELD WELD I I I I I I I I I I I I I I I I I I I I I~I I I PUMP WELD NO.124-5 AND 1301-771 RCP 2B2 OUTLET SAFE END WELDS, PRORLE AND EXTENT OF COVERAGE AT 060 FIGURE 5.51 PIPE l l l l'l l'l l\'I 1 l\l\\SCAN UMIT I I I I SHOP'OELD I I I I t I I I I l I I I SAFE EI'ID l'l l l\'l\l\FIELD YiELD I I I I I j I I l I I i J I I I I I I l C I I i I I I I PUMP WElD NO.124-5 AND 1301-771 RCP 2B2 OUTLET SAFE END YIELDS, PRORLE AND EXTENT OF COVERAGE AT 140 FIGURE 5.52 PIPE\1\\1 1 1\\1 1 I I I I I I SHOP W'ELD I (I I I I I I I I I I I I I I I I SCAN UMIT SAFE END 1'!l 1\1 1 1'1 1 FIELD WELD I I I f I I (II I I f I I I f I I I I PUMP WELD NO.124-5 AND 1301-771 RCP 2B2 OUTLET SAFE END WELDS, PRORLE AND EXTENT OF COVERAGE AT 160 F1GURE 5.53

PIPE\l\l l l l\l\'l l l l l\SCAN UMIT I I I SHOP WELD I I I l I I I I I I I I I I I ENO\l l l\\\\FIELD WELD I I I I I I I!I I I I I I I I I I I I I I I PUMP 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 CAT.BJ ITEM NO.B9.1 1 B9.12 B9.31 EXAMINATION REQUIREMENTS Essentially 100%volumetric and surface examination of Circumferential welds for>4" nominal pipe size.Essentially 100%volumetric and surface examination of Longitudinal weids for>4" nominal pipe size.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 Examination Area Identification Loop 2A Hot Leg, Elbow-to-inlet nozzle Extension piece (field weld)and Nozzle Extension Piece-to-nozzle (shop weld)Weld Nos.RC-1 23-201-258 Beam Angle 450 60'xamination Table Coverage (CRV)100%Both welds from pipe side 30%of shop weld from Nozzle side Supplemental Both sides Fig.Description of Limitations Scan limited from nozzle side due to Nozzle OD transition taper.B Hot Leg to Shutdown Cooling Branch connection Weld No.RC-123-205-771 450 60'00%one side only Supplemental NA One side only due to configuration Page 202 of 272 ST.LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 6 Loop 2A2 Intermediate Cold leg Steam Generator Nozzle-to-extension (shop weld)and Extension-to-Elbow (field weld)Weld Nos.RC-115-1 RC-1 15-401-258-B 45'0'xamination Table 100%both welds from pipe side 98%of field weld from Nozzle side 0%of shop weld from nozzle side Supplemental both sides Scan limited from nozzle side due to nozzle OD transition taper.Loop 2A2 Intermediate Cold leg Longitudinal Seam No.RC-115-1 09-722-LS-A RCS Loop A 2A2 RCP to Reactor Vessel Longitudinal Seam Weld No.RC-115-1 03-722-LS-A RCS Loop B 2B1 RCP to Reactor Vessel Longitudinal Seam Weld No.RC-1 21-1 03-722-A 45'5'A 45'C 45oA 45'C 33%93%90%59%59 Scan limited to a length of 4" due to pipe support.Longitudinal seam obstructed by welded attachment (lugs)on weld centerline.

Longitudinal seam obstructed by welded attachment (lug), on weld and bumper attached to sleeve at biological shield penetration.

Page 203 of 272

ST.LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 6 Loop 2A1 Intermediate Cold leg Steam Generator Nozzle-to-extension (shop weld)and Extension-to-Elbow (field weld)Weld Nos.RC-112-401-258-A 45oA Examination Table 100%both welds from pipe side 30%of shop weld from nozzle side Scan limited from nozzle side due to nozzle OD transition taper.60'A Supplemental both sides Pipe to Valve V-3227 Weld No.RC-151-FW-1 45'A 60oA 45'C 63%from pipe side 0%from valve side Limited by pipe to valve configuration Valve V-3227 to Pipe Weld No.Sl-148-FW-5 Pipe to Valve V-3624 Weld No.SI-148-FW-1 Valve V-3217 to Pipe Weld No.Sl-149-FWC 45oA 60'A 45'C 45'A 45'C 45'A 45'C 60'A 88%from Pipe side 0%from Valve side 100%Pipe side 0%from valve side 81 from pipe side 0%from valve side NA Limited by configuration Limited by configuration Limited by configuration Page 204 of 272 ST.LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 6 Pipe to Valve V-3614 Weld No.Sl-149-FW-1 Valve V-3237 to Pipe Weld No.SI-1 50-FWP Valve V-3247 to Pipe Weld No.SI-1 51-FW-4 Pipe to Valve V-3644 Weld No.SI-1 51-FW-1 45'A 45'C 45oA 45'C 60'A 45'A 45'C 45'A 45'C 60'A Examination Table 100%from pipe side 0%from valve side 100%from pipe side 0%from valve side 45%from pipe side 20%from valve side 63%from pipe side 0%from valve side NA Limited by configuration 9 Limited by configuration 10 limited by configuration 11 Limited by configuration Valve V-3261 to pipe Weld No.SI-518-FW-1 45'A 45'C 63%from pipe side 38%from valve side 12 Limited by pipe to valve configuration Page 205 of 272

~FI D VELD 100%PIPE SIDE 45'ND 60'00%EXT.SIDE 45'0/EXT SIDE 60'SHOP VE D 100/EXT.SIDE 45'ND 60'0%45'AND 60'NOZZLE SIDE 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 VELD SHOP VELD 100/FIELD VELD 45 A, BOTH SIDES 60 A, 100/ELBOV SIDE 1 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 BY BUNPER 53'Y 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)PIPE OD I PIPE ID I-CL HOT Q COLD 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 CAT.C-A ITEM NO.C1.10 EXAMINATION REQUIREMENTS 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 CAT.c-B ITEM NO.C2.21 EXAMINATION REQUIREMENTS 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 F.IMPLEMENTATION SCHEDULE: Second tnservice Inspection Interval.August 8, 1993 to August 08, 2003 G.ATTACHMENTS TO THE RELIEF: Examination Table Examination Area Identification Description of Limitations Fig.Beam Angle Coverage (CRV)Examination limited by configuration to one side.45'00%one side 100%one Side Steam Nozzle to Head Weld No.SG-2A-105-201 60'00%due to full Vee (one sided)98%one sided Examination limited by configuration and welded attachment Feedwater Nozzle to Head Weld NO.SG-2A-111-221 46'0'age 222 of 272 2)Perform to the extent practical the volumetric and surface examinations's required by IWC-2500-1.

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 Area Identification Steam Nozzle to Head Weld No.SG-2A-1 05-201 Beam Angle 45 60 Coverage (CRV)100%one side 100%one side Fig.Description of Limitations Examination limited by configuration to one side.Feedwater Nozzle to Head Weld NO.SG-2A-111-221 60 100%due to full Vee (one sided)98%one sided Examination limited by configuration and welded attachment 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 CAT.C-F-1 C-F-2 ITEM NO.C5.11 C5.81 EXAMINATION REQUIREMENTS Essentially 100%volumetric and surface examination of circumferential welds 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 Area Identification Pipe longitudinal Seam Weld No.MS-1-FW-1-LS MS-33-FW-1-LS Exam Method PT UT 46'A 46'C Coverage 93%86%83%Fig.Description of Limitations Examination limited by welded attachment Page 226 of 272 ST.LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 10 Examination coverage Examination Area Identification Pipe to Valve (V-3144)Sl-146-FW-2 Valve (V-3144)to pipe SI-110-FW-1 Pipe to Elbow SI-110-8-SW-1 Valve (V-3654)to pipe SI-213-FW-2 Exam Method PT UT 45'A 45'C PT UT 45'A 45'C PT UT 45'A 45'C PT UT 45oA 45'C Coverage 37%from Pipe and Valve Sides 65%from Pipe Side 57%from Valve Side 80%CRV Achieved 40%from Pipe side 20%from Valve Side Fig.NIA Description of Limitations Limited due to configuration Limited due to configuration 4" of total circumference missed due to I-Beam of top Limited due to configuration Pipe to Valve (V-3654)SI-213-FW-1 PT UT 45oA 45.C 40%from Pipe side 20%from Valve side Limited due to configuration 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 S z O~Vl Vl I A n I Nr Vl Vl O ZZ 0 C-Vl Vl g I I Vl 9'-10" 27/v wnr CVCC 11'-10" LONGSEAM 4 SDE VIEW OF WELDED SUPPORT ATTACHMENT SADDLE WITH TRUNNIONS nz 27 I I rem r'r'r'r'r'r'IGURE 10.1 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 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 III-3411 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.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 I.D.NUMBER UT-4A COMPONENT DESCRIPTION Hot Leg Primary Coolant Piping DEVIATION FROM CODE Different Material Page 234 of 272 ST.LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 13 CAL.BLOCK I.D.NUMBER UT-45 COMPONENT DESCRIPTION Main Steam Piping Welds DEVIATION FROM CODE Different Diameters 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 B-B B-F B-G-1 8-G-2 B3.90 B3.100 B3.110 B3.120 B3.130 B3.140 B2.11 82.'12 B2.31 B2.32 B2.40 B5.40 B6.50 B7.20 B7.30 B7.50 RPV Nozzle-Vessel Weld RPV Nozzle Inside Radius Pressurizer Nozzle-Vessel Weld Pressurizer Nozzle Inside Radius Steam Generator Nozzle-Vessel Weld Steam Generator Nozzle Inside Radius Pressurizer Shell-Head Welds Pressurizer Long Welds Steam Generator Circ Head Welds Steam Generator Meridional Welds Steam Generator Tubesheet-Head Welds Pressurizer Nozzle-Safe End RPV Threads in Flange Pressurizer Bolts, Studs, Nuts Steam Generator Bolts, Studs, Nuts 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 B-J B8.20 B8.30 B9.11 Pressurizer Integral Attachments Steam Generator Integral Attachments 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 101-121 Shell-Flange 105-1 21-A Nozzle-Shell 105-121-B Nozzle-Shell ON-IR-A Inner Radius ON-IR-B Inner Radius 401-128-A Outlet Noz-Ext 401-128-B Outlet Noz-Ext FL-01-54 Threads in Base Metal 1st and 2nd 1st and 2nd 1st and 2nd 1st Period 1st Period 1st Period 1st Period 1st Period 2nd 2nd 2nd 2nd 2nd 2nd 2nd 2nd REACTOR PRESSURE VESSEL CLOSURE HEAD TABLE ITEM IDENTIFICATION 101-101 Flange to Torus 3rd 1st RESCHEDULED FROM NEW SCHEDULE 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 Meridional Weld SG-2A-202-271 Primary Ext.Ring SG-2A-201-246 Primary Ext.Ring SG-2A-1 04-261 Inlet Noz-Head SG-2A-.1 02-261-A Outlet Noz-Head SG-2A-102-261-B Outlet Noz-Head SG-2A-1 01-244-B Ext.Ring Long.Weld SG-2A-IN-IR Inlet Noz Inner Radius SG-2A-ON-IR-A Outlet Nozzle SG-2A-ON-IR-B Outlet Nozzle SG-2A-PMS-A Manway Studs SG-2A-PMN-A Manway Nuts SG-2A-PMS-B Manway Studs SG-2A-PMN-B Manway Nuts 1st 1st 1st 1st 1st 1st 1st'1st 1st 1st 1st 1st 1st 1st 3rd 3rd 3rd 3!'d 3!'d 3rd 3I'd 3rd 3rd 3rd 3!'d 3rd 3!'d 3!'d 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 Nozzle Extension RC-116-401-258-B SG Nozzle-Nozzle Ext.RC-116-1 Nozzle Ext-Elbow RC-115-103-742-LS-A Long.Seam RC-116-103-742-LS-B Long.Seam RC-112-401-258-A SG Nozzle-Nozzle Ext SG-2A-203-246 2nd Ext.Ring to Tubesheet SG-2A-101-241 2nd Ext.Ring-lower SG-2A-1 02-221 Int.Shell-Cone SG-2A-111-221 FW Nozzle-Cone SG-2A-111-221-IR Long.Seam SG-2A-103-221-A Key Bracket SG-2A-103-221-B Key Bracket 1st 2nd 2nd 2nd 2nd 1st 1st 1st 2nd 2nd 2nd 1st 2nd 3rd 3rd 3rd 3rd 3rd 3rd 3rd 3rd 3rd 3rd 3rd 3rd 3rd Page 242 of 272 ST.LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 14 ITEM IDENTIFICATION SG-2A-1 04-221-A Clevis Bracket SG-2A-105-221-A Support Bracket SG-2A-104-221-8 Clevis Bracket STEAM GENERATOR TABLE RESCHEDULED FROM 1st 2nd 2ncl NEW SCHEDULE 3rd 3rd 3rd Page 243 of 272 ST.LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST, NUMBER 14 ITEM IDENTIFICATION PRESSURIZER TABLE RESCHEDULED FROM NEW SCHEDULE 501-671 Top Head-Upper Shell 503-671-B Safety Valve Nozzle 503-671-C Safety Valve Nozzle 108-601-A Safety Valve Nozzle SVN-IR-A Inner Radius SV-1200 Safety Valve to Flange 108-601-B Relief Valve Nozzle RVN-IR Inner Radius 108-601-C Safety Valve SVN-IR-B Inner Radius SV-1201 Safety Valve to Flange 108-601-D Safety Valve Nozzle SVN-IR-C Inner Radius SV-1202 Safety Valve to Flange 2nd 3!'CI 2ncl 2nd 2ncl 3!'Cl 2ncl 2ncl 2nd 2nd 3!'Cl 2nd 2ncl 3!'d 1st 1st 1st 1st 1st 1st 1st 1st 1st 1st 1st 1st 1st 1st 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 Studs MN-01 Nuts 101-622-A Upper Shell Long.101-642-A Lower Shell Long.304-671 Lower Shell to Lower 103-651 Support Skirt 105-651 Surge Nozzle SRGN-IR Inner Radius RC-514-671 Safe End-Nozzle RC-506-671 Nozzle-Safe End 3rd 3rd 2nd 2nd 2nd 2nd 2nd 2nd 2nd 3rd 1st 1st 1st 1st 1st 1st 1st 1st 1st 1st 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 Nuts 02-0'I 9-S-001-016 Studs 2nd 2nd 1st Page 246 of 272 ST.LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 15 A.COMPONENT IDENTIFICATION:

Class: Identification of Components:

Description of Components:

B.EXAMINATION REQUIREMENTS:

I Inlet and Outlet Nozzle to Pipe Transition Welds Reactor Coolant Piping Examination Category: Examination

==

Description:==

Examination Item Number: B-J Pressure Retaining Welds in Piping B9.11 Item Number B9.11 Exam Method Surface and Volumetric Extent of Examination Nominal Pipe Size 4 inch or Greater, includes 100%of Circumferential Weld C.RELIEF REQUESTED:

Relief is requested from the conduct of the ASME Code Required Surface Examination Method for the following weld configurations.

Summary Number 000330 000340 000350 000360 000370 Weld Identification 401-128-A RC-114-1 201-128-A RC-112-6 201-1 28-B Weld Description Outlet Nozzle to Extension Outlet Nozzle Extension to Pipe Inlet Nozzle to Extension Inlet Nozzle Extension to Elbow , Inlet Nozzle to Extension Size 42 I~42 I I 30 I~3 0 II 3 0 I I Page 247 of 272 ST.LUCIE UNIT 2 SECOND INSPECTION INTERVAL RELIEF REQUEST NUMBER 16 Summary Number 000380 000390 000400 00041 0 000420 000430 000440 Weld Identification RC-121-6 401-1 28-B RC-123-1 201-1 28-C RC-124-6 201-128-D RC-115-6 Weld Description Elbow to Inlet Nozzle Extention Outlet Nozzle to Extension Outlet Nozzle Extension to Pipe Inlet Nozzle to Extension Inlet Nozzle Extension to Elbow Inlet Nozzle to Extension Elbow to Inlet Nozzle Extention Size 30II 42" 42" 30II 30II 3 Q I I 3 0 I~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 VOLUMETRIC EXAMINATION 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: NRC Docket Number: Document Number: Revision Number: Date: July 24, 1993 August 8, 1983 50-389 RR-15

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.b.C.d.the angulation wedge;the coupling material;surface irregularities; and 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.

'CL4lg 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 QUALIFICATION OF 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 EX4MINATION RESULTS 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 IWA-7520 (8)IWA-6210 (c)IWA-6220 (c)IWA-6220 (d)The records required by IWA-6000 shall be completed for all repairs.Completed Owner's Report for Repairs or Replacements, Form NIS-2 The Owner shall prepare inservice inspection summary report for Class 1 and 2 pressure retaining components and their supports.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.

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 Form NIS-1D Form NIS-2A Form NIS-2B Examinations Not Performed as Identified in the Inspection Plan Identification of Items with Flaws Which Required Analytical Evaluation for Continued Acceptability Repair/Replacement Plan Certification Record 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 Date/Revision of Inspection Plan Addenda 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.

inspector's Signature Commissions 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 EXAMINATION CATEGORY B-A B-B B-D B-F B-G-1 B-G-2 B-H B-K-1 B-L-1 B-L-2 B-M-1 B-M-2 B-N-1 B-N-2 B-N-3 C-A C-B C-C C-F-1 C-F-2 D-A D-B D-C F-A F-B F-C TOTAL ITEMS SUBJECT TO EXAMINATION 26 37 36 31 16 56 595 24 17 22 20 20 718 190 15 75 150 242 303 TOTAL EXAMINATIONS REQUIRED FOR INTERVAL 26 36 31 46 202 24 24 22 10 18 102 66 15 57 51 66 90 TOTAL EXAMINATIONS REQUIRED FOR THIS PERIOD 16 59 19 10 31 17 21 16 25 76 TOTAL EXAMS CREDITED%FOR INTERVAL EXCLUSIONS, OR DEFERRALS DEFERRED TO 2ND PERIOD WHEN DISSEMBLED FOR MAINTENANCE 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 CATEGORY ITEM NUMBER ITEM DESCRIPTION DATE OF RESCHEDULED EXAMINATION METHOD OF ALTERNATE EXAM PERFORMED Page 267 of 272 l~/I' 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 CATEGORY ITEM NUMBER ITEM DESCRIPTION FLAW CHARACTERIZATION (IWA-3300)

FLAW FOUND DURING 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 repair or replacement represented by Repair/replacement Plan Number of the ASME Code, Section XI~conforms to the rules Type Code Symbol Stamp Certificate of Authorization No.Expiration Date Signed Owner or Owner's Designee, Title Date 19 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.

Inspector's Signature Commissions National Board, State, Province, and Endorsements Date 19 Page 269 of 272 I p I FORM NIS-28 A8STRACT OF REPAIRS AND REPLACEMENTS As required by the provisions of the ASME Code Rules Page of ASME CLASS REPAIR OR REPLACEMENT ITEM DESCRIPTION DESCRIPTION OF WORK FLAW FOUND DURING SCHEDULED SECTION XI EXAM/TEST (YES/NO)DATE COMPLETE REPAIR REPLACE PLAN NUMBER Page 270 of 272

~>>~f~>~j ,,~~f l I*~q I~I 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 h*I\DI'D S thr EID~w p~~', rhr~<~'D>>ir~3th'">e eS'D'~,~~>"~I I ,~1 r'=~Ot D~~t~>>)II I~Ja 1'Dj f.""$1.j t-"gf I~"I ftr'V)t~;trj t+I'" I-')I ir$1, 1 I I D I t~hr II,)111ht*~~~~'i L~I I~~~~

, 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 1'41