ML17352A230
| ML17352A230 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 09/01/1993 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17352A229 | List: |
| References | |
| JPN-ESI-PTN-3-4, JPN-ESI-PTN-3-4-R, JPN-ESI-PTN-3-4-R00, NUDOCS 9309140077 | |
| Download: ML17352A230 (369) | |
Text
Juno Nuclear Engineering Equipment Support and Inspections Group 700 Universe Blvd.
Juno Beach, Florida 33408 Third Ten-Year Inservice Inspection Program for Turkey Point Nuclear Power Plants Units 3 and 4 Florida Power and Light Company P.O. Box 3088 Florida City, Florida 33034 Commercial Service Date: September 7, 1973 USNRC Docket Numbers: 50-250: Unit 3 50-251: Unit 4 Document Number: JPN-ESI-PTN-3/4 Rev. 0 Date:
ISI Specialist
./7 Date: gpss o/'P3 Reviewed by:
Supervisor CPS Approved by: Date: 9 < R ag r ESI 9309i40077 9309'Oi PDR ADOCK 05000250 PDR
~ f',
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Table of Contents Table of Contents Record of Revlslon
~ ~
Vl List of Figures ~ Vll List of Tables vlii Abbrevlatlons 1X Xl Ab stract ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
1.0 Introduction ~ ~ ~ ~ ~ ~ 2 1.2 Applicable Editions and Addenda to Section XI 4 1.3 System Classification 1.4 Inspection Program 4 1.5 Regulatory Guides 5 1.6 ASME Section XI Code Cases 6 2.0 Development of the Inspection Plans 7 2.1 Class 1 7 2.1.1 ASME Code Exemptions Employed ~ ~ ~ 7 2.1.2 Component/Piping Examination Basis 8 Category B-A 8 Category B-B 9 Category B-D 10 Category B-E 11 Category B-F 12 Category B-G-1 13 Category B-G-2 14 Category B-H 14 Category B-J 15 Category B-K . ~ ~ 15 Category B-L-1 ~ ~ 15 Category B-L-2 15 Category B-M-1 16 Category B-M-2 16 Category B-N-1 16 Category B-N-2 16 Category B-N-3 16 Category B-0 17 Category B-P 17 Category B-Q 18 Augmented Examinations 18 2.2 Class 2 ~ ~ ~ ~ 18 2.2.1 Components Exempt from Examin ation 19 2.2.2 Component/Piping Examination Basis 20 Category C-A . 20 Category C-B . 21
F' Turkey Point ISI Program Revision 0 Date: August 27, 1993 Category C-C 23 Category C-D 23 Category C-F-1 24 Category C-F-2 25 Category C-F 26 Category C-G 26 Category C-H 26 Augmented Examinations ~ ~ 27 2.3 Class 3 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 27 2.3.1 ASME Code Exemptions employed ~ ~ 27 2.3.2 Component/Piping Examination Ba sls 28 Category D-A 28 Category D-B 28 Category D-C 29 2.3.3 System Pressure Tests 29 2.4 Component Supports 30 2.5 Reexamination of Flaw Indications 30 2.5.1 Class 1 30 2.5.2 Class 2 31 2.5.3 Class 3 31 2.6 Substitute Examinations 31 2.7 Class MC Components 31 3.0 Relief Requests 33 4.0 Evaluation Criteria 34 4.1 Acceptance by Engineering Evaluation 34 4.2 Acceptance by Repair 34 4.3 Acceptance by Replacement 34 4.4 Acceptance by Analytical Evaluation 35 4.5 Component Support Indications 35 4.6 Supplemental Examinations 35 4.7 Additional Examinations 35 4.8 Minimum Thread Engagement Requirements 35 5.0 Program Boundary Drawings 39 6.0 Records 40 6.1 General 40 6.2 Nondestructive Examinations 40 6.3 Final Reports 40 6.4 Final Report Format 40 6.5 Inservice Inspection Summary Reports 40 7.0 Repairs, Replacements and Modifications 46 7.1 Repairs 46 7.2 Replacements 46 7.3 Modifications 47 7.4 Evaluation 47 7.5 Access 48 7.6 Determination of Design and Construction Cod es 48 7.7 Authorized Nuclear Inservice Inspector 48 7.8 Implementation 48 8.0 Inservice Inspection Plan and Schedules 49
0 0
Turkey Point ISI Program Revision 0 Date: August 27, 1993 8.1 Inspection Plan Tables ~ ~ 49 8.2 Ten Year Inspection Plan ~ ~ 49 8.3 Weld Identification ~ ~ 50 9.0 Nondestructive Examination Procedures 52 10.0 Calibration Block Table 54 Appendix A ~ ~ 58 Table A-1 ~ ~ 58 Table A-2 ~ ~ 59 Appendix B ~ ~ 60 Table B-1 ~ (
~ ~ ~ 60 Table B-2 ~ ~ 62 Table B-3 ~ ~ 63 Table B-4 ~ ~ 65 Appendix C ~ ~ ~ ~ ~ 66 Table C-1 ~ ~ 66 Table C-2 ~ ~ 68 Table C-3 ~ ~ 69 Table C-4 ~ ~ 76 Table C-5 ~ ~ 78 Table C-6 79 Appendix D ~ ~ 87 Table D-1 87 Table D-2 88 Table D-3 89 Table D-4 90 Table D-5 94 Table D-6 95 Table D-7 96 Table D-8 97 Appendix E ~ ~ ~ 100 Table E-1 100 Table E-2 101 Table E-3 102 Table E-4 104 Table E-5 106 Table E-6 107 Table E-7 108 Table E-8 110 Appendix F ~ ~ 112 Table F-1 112 Table F-2 114 Table F-3 117 Table F-4 121 Table F-5 123 Table F-6 126 Appendix G 129 iv
a v '
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Relief Requests ~ ~ ~ ~ 129 Relief Request No. 1 130 Relief Request No. 2 140 Relief Request No. 3 143 Relief Request No. 4 155 Relief Request No. 5 157 Relief Request No. 6 159 Relief Request No. 7 169 Relief Request No. 8 172 Relief Request No. 9 175 Relief Request No. 10 177 Appendix H 179 Piping and Instrumentation Drawings 179
I( ~
4
(
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Record of Revision Revision Date Affected Reason for Revision No. Pages August 27, 1993 Entire Original Issue Third Ten Document Year Inspection Program
Turkey Point ISI Program Revision 0 Date: August 27, 1993 List of Figures Inservice Inspection Summary Record 42 NIS-BB Owners'eport of Steam Generator Examinations 43 Upper Shell to Flange Limitations 134 Head to Lower Head Ring Limitations 135 Lower Head Ring to Lower Shell Limitations 136 Inlet Nozzle to Shell Limitations 137 Outlet Nozzle to Shell Limitations Parallel 138 Outlet Nozzle to Shell Limitations Transverse 139 Examination Area Coverage 150 Unit 3 Regenerative Heat Exchanger 151 Unit 3 Regenerative Heat Exchanger Terminal End Welds 152 Unit 4 Regenerative Heat Exchanger 153 Unit 4 Regenerative Heat Exchanger Terminal End Welds 154
Turkey Point ISX Program Revision 0 Date: August 27, 1993 List of Tables USNRC Regulatory Guides 5 Applicable Code Cases 6 Table 4.1 Class 1 Acceptance Standards 36 Table 4.2 Class 2 Acceptance Standards 37 Table 4.3 Class 3 Acceptance Standards 37 Table 4.4 Component Support Acceptance Standards 38 V3.3.3.
0 Turkey Point ISI Program Revision 0 Date: August 27, 1993 Abbreviations Listed below are the abbreviations utilized in this document:
ANII Authorized Nuclear Inservice Inspector ASME American Society of Mechanical Engineers B&PV Boiler and Pressure Vessel Code CCW Component Cooling Water CRDM Control Rod Drive Mechanism CH Charging System CPS Code Programs Section CTMT Containment CV Control Valve CVCS Chemical and Volume Control System ECCS Emergency Core Cooling System ECT Eddy Current Testing (Examination)
ESI Equipment Support and Inspections FPL Florida Power and Light Company FPS Fuel Pool System FSAR Final Safety Analysis Report FW Feedwater System HPSI High Pressure Safety Injection JPN Juno Nuclear Engineering LPSI Low Pressure Safety Injection MOV Motor Operated Valve MSIV Main Steam Isolation Valve MS Main Steam System MT Magnetic Particle Testing (Examination)
N/A Not Applicable NDE Nondestructive Examination NPS Nominal Pipe Size PS(ID Piping and Instrumentation Diagram POV Pneumatic Operated Valve PT Liquid Penetrant Testing (Examination)
PTN Turkey Point Nuclear Power Plant
P I~
Turkey Point ISI Program Revision 0 Date: August 27, 1993 QA Quality Assurance QC Quality Control Pressurized Water Reactor PZR Pressurizer RCS Reactor Coolant System RCP Reactor Coolant Pump RGX Regenerative Heat Exchanger RPV Reactor Pressure Vessel SD Structural Discontinuity SG Steam Generator SGBD Steam Generator Blowdown SI Safety Injection Thickness of Component, Pipe, etc.
TE Terminal End USNRC United States Nuclear Regulatory Commission UT Ultrasonic Testing (Examination)
Visual Testing (Examination)
II I ~, (
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Glossary of Terms ASSESS to determine by evaluation of data compared with previously obtained data such as operating data or design specifications.
AUTHORIZED INSPECTION AGENCY an organization that is empowered by the 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 are performed in accordance with the 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 III.
CODE, the as used in this document, the 1989 Edition of the American Society of Mechanical Engineers,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components 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 referred 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 manufacture 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 t to be rejectable.
DISCONTINUITY a lack of continuity or cohesion; an interruption in the normal physical structure of material or a product.
- t. s
~,
~,
Turkey Point ISI Program Revision 0 Date: August 27, 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 of indications that exceed allowable acceptance standards to determine margins required by the Design Specification if and the the Construction Code are maintained.
EVALUATION the process of determining the significance of examination or of test 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 tested.
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 Examples include junctions between shells of different thickness, cylinder shell-to-conical shell junctions.
IMPERFECTION a condition of being imperfect; a departure of a quality characteristic from its intended condition.
INDICATION the 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.
INSPECTION PROGRAM the plan and schedule for performing examinations or tests.
INSPECTION verification of the performance of examinations and tests by an Inspector.
I D Turkey Point ISI Program Revision 0 Date: August 27, 1993 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, determined by inspection program B.
ITEM a material, part, appurtenance, piping sub-assembly, component or component support.
MAINTENANCE replacement of parts, adjustments, and similar actions that do not change the design of an item, taken to correct deficiencies in the function of the item.
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.
OWNER the organization legally responsible for the operation, maintenance, safety and power generation of the nuclear power plant.
REGULATORY 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 ORGANIZATION the organization that replaces or repairs components or systems under the provisions of the Owners's Quality Assurance Program. The Owner may be the repair organization.
ROUTINE SERVICING the performance of planned, preventive maintenance that does not require disassembly or replacement of parts.
STRUCTURAL DISCONTINUITY As used in this program: includes pipe weld joints to vessel nozzles, valve bodies, pump casings, pipe fittings (such as tees, elbows, reducers, flanges, etc. conforming to ANSI B16.9) and pipe branch connections and fittings.
kJ II 4 h s I~ II
Turkey Point ISI Program Revision 0 Date: August 27, 1993 TERMINAL ENDS the extremities of piping runs that connect to structures, components, or pipe anchors, each of which acts as a rigid restraint or provides at 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.
VERIFY to determine that a particular action has been performed in accordance with the rules and requirements of Section XI either by witnessing the action or by reviewing records.
xlv
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Abstract This document describes the bases for the Third Ten-Year Inservice Inspection Program for Turkey Point Nuclear Power Plant, Units 3 and 4.
This program was developed and prepared to meet the requirements of the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code,Section XI, 1989 edition, and is subject to the limitations and modifications of 10 CFR 50.55a (b)(2), except the design and access provisions and preservice examination requirements.
their supports It identifies which are those subject to components examination and/or and systems testing.
and Additional requirements for augmented examinations are addressed.
This program contains requests for relief from certain code requirements. The basis for the relief and proposed alternative examinations are included.
Tables have been developed showing the bases for selection of components.
l k Turkey Point ISI Program Revision 0 Date: August 27, 1993 1.0 Introduction 1.1 This document details the Long-Term Inservice Inspection Program for the Third Ten-Year Inspection Interval for Turkey Point Nuclear Plants (PTN), Units 3 and 4.
1.1.1 The Inservice Inspection Program for Class 1, Class 2, and Class 3 (or Quality Groups A, B, and C respectively) systems and components (and their supports) was developed after giving due consideration to the following documents to the extent practical within the limitations of design, geometry, and materials of construction.
10 CFR 50.55a Code of Federal Regulations Sections V and XI of the American Society of Mechanical Engineers (ASME) Code, 1989 Edition United States Nuclear Regulatory Commission (USNRC)
Regulatory Guides 1.14 Reactor Coolant Pump Flywheel Integrity Revision 1, August 1975 1.26 Quality Group Classifications and standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants, Rev. 2, June 1975 1.65 Materials and Inspections for Reactor Vessel Closure Studs 1.68 Initial Test Program for Water Cooled Nuclear Power Plants, Rev. 2, Aug. 1978 1.83 Inservice Examination of Pressurized Water Reactor Steam Generator Tubes, Revision 1, july 1975 1.147 Inservice Inspection Code Case Acceptability ASME Section XI Latest Revision 1.150 Ultrasonic Testing of Reactor Vessel Welds during Preservice and Inservice Examinations, Rev. 1, February 1983 Turkey Point 3 Final Safety Analysis Report Turkey Point 4 Final Safety Analysis Report Turkey Point Technical Specifications, sections 4.0.5, 3/4 ~ 4 ~ 5g 3/4 ~ 4 11 g 3/4 ~ 7~9 USNRC Standard Review Plan 6.6,Section I.8, (for Class 2 Augmented Inspections)
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Branch Technical Position APCSB 3.1, paragraph B.2.c(4)
First and Second Ten year Interval Inspection Plans 1.1.2 Programs outside the scope of this document:
The program for Inservice testing of Class 1, 2, an'd 3 Pumps and Valves is covered by the Turkey Point IST program which is submitted and approved separately.
The Steam Generator ECT Program is controlled by Plant Technical Specifications.
1.1.3 The first two periods of the first Inservice Inspection Interval were conducted in accordance with the 1970 Edition with Addenda through Winter 1970 Addenda of the ASME Boiler and Pressure Vessel (B&PV) Code,Section XI.
The last period was conducted in accordance with the 1974 Edition with Addenda through Summer 1975 of ASME BGPV Code,Section XI.
The first Interval for Turkey Point Unit 3 began on December 13, 1972 and ended on February 22, 1984. The first Interval for Turkey Point Unit 4 began on September 7, 1973 and ended on April 14, 1984. An extension of the First Intervals was granted by the USNRC on March 1, 1984.
- 1. 1.4 The Second Ten Year Inservice Inspection Interval for both Units was conducted in accordance with the 1980 Edition thru Winter 1981 Addenda of Section XI. Turkey Point Unit 3 second interval ran from February 22, 1984 to February 21, 1994. Turkey Point Unit 4 second interval ran from April 15, 1984 to April 14, 1994.
1.1.5 The Construction permit for Turkey Point, was issued on April 27, 1967, Florida Power and Light Company (FPL) is the Owner of Record.
1.1.6 The operating licenses for Turkey Point Unit 3 and 4 were issued on July 19, 1972 and April 10, 1973, respectively.
1.1.7 The dates of the Third Interval and Periods are as follows:
Unit 3 Unit 4 Interval 2/22/1994 2/21/2004 4/15/1994 4/14/2004 1st Period 2/22/1994 2/21/1997 4/15/1994 4/14/1997 2nd Period 2/22/1997 2/21/2001 4/15/1997 4/14/2001 3rd Period 2/22/2001 2/2 1/2 0 04 4/15/2001 4/14/2004
I d Jl u I
I
Turkey Point ISI Program Revision 0 Date: August 27, 1993 1.2 Applicable Editions and Addenda to Section XI Pursuant to Title 10 of the Code of Federal Regulations, paragraph 50.55a(b)(2), the Inservice Inspection Requirements applicable to nondestructive examination and system pressure testing at Turkey Point Units 3 and 4 are based on the 1989 Edition of ASME Section XI. This Edition of ASME Section XI was endorsed by the USNRC twelve months prior to the start of the Third Ten Year Interval (February 22, 1993 for Unit 3 and April 15, 1993 for Unit 4).
1.3 System Classification The system classification used as a basis for the Inservice Inspection Program are based on the requirements of 10 CFR 50 and Regulatory Guide 1.26.
Class 1 system boundaries are developed based on 10 CFR 50.2(v), and the Turkey Point Plant Units 3 and 4 FSAR's.
Class 2 and 3 system boundaries are developed based on Regulatory Guide 1.26 and the Turkey Point Plant Units 3 and 4 FSAR's.
Optional construction of a component within a system boundary to a classification higher than the minimum class established in the component Design Specification shall not affect the overall system classification by which the applicable rules of Section XI are determined.
The portions of piping that penetrates the containment vessel which is required to be constructed to Class 1 or 2 rules for piping and which may differ from the classification of the balance of the piping system, shall not affect the overall system classification that determines the applicable rules of Section XI.
Piping and Instrumentation Diagrams are provided to show the specific boundaries for the Class 1, 2, and 3 systems (see Section 5.0).
1.4 Inspection Program Examinations are scheduled in accordance with Inservice Inspection Program B for all Class 1, 2, and 3 systems and components, as described in sub-article IWA-2400 of the Code. Examinations are scheduled based upon the Second Ten Year Interval Program, to the extent practical. Appendix G lists those areas where schedules were changed and reasons for the changes.
.P V
g *t l
~-
,I 0
8 l ~ ~
Turkey Point. ISI Program Revision 0 Date: August 27, 1993 1.5 Regulatory Guides The Regulatory Guides which have been determined to be applicable to Turkey Point for purposes of this Program are listed below:
USNRC Regulatory Guides R. G. Description of Applicable to Applicable to Number Regulatory Guide Program Plan Implementation
- 1. 14 Reactor Coolant Pump Yes Yes Flywheel Integrity, Rev. 1
- 1. 26 Quality Group Yes No Classifications, Rev. 2 1.65 Materials and Yes Yes Inspections for Reactor Vessel Closure Studs 1.147 Section XI Code Case Yes Yes Acceptability, latest revision
Turkey Point. ISI Program Revision 0 Date: August 27, 1993 1.6 ASME Section XI Code CasesSection XI Code Cases applicable to ISI are shown below.
Each of the code cases have been approved by the USNRC, and are listed in Regulatory Guide 1.147.
Applicable Code Cases Number Description Applicable Applicable to to Plans Implementation N-307-1 Revised UT Exams for No Yes B-G-1 N-355 Calibration Block for No Yes Angle Beam UT of Large Fittings N-416 Alternative Rules for No No Hydrostatic Testing of Repair or Replacement of Class 2 Piping,Section XI, Division 1 N-460 Alternate Examination No Yes Coverage for Class 1 and Class 2 Welds,Section XI, Division 1 N-461 Alternate Rules for Yes Yes Piping Calibration Block Thickness,Section XI, Division 1 N-481 Alternate Examination Yes Yes Coverage for Cast Austenitic Pump Casings,Section XI, Division 1 N-489 Alternative Rules for No Yes Level III NDE Qualification Examinations N-498 Alternate Rules for 10 Yes Yes Year Hydrostatic Pressure Testing for Class 1 6 2 Systems,Section XI Division 1 Note: Code Case N-481 requirements wall be mod>,fred by Florida Power and Light from Hydrostatic to System Pressure Test to conform with Code Case N-498.
The Guidelines of Code Case N-509 will be used for scheduling Integral Attachments (see Relief Request No. 8).
Turkey Point ISI Program Revision 0 Date: August 27, 1993 2.0 Development of the Inspection Plans The following is the detailed description of the Inspection Program Basis for components and/or systems subject to examination.
Each Code Class has the requirement to repeat the schedule of examinations established during the First Interval. The First Interval examinations performed at Turkey Point were largely examined under Codes that did not require Class 2 or Class 3 components to be examined. In order to reduce radiation exposure and use the Second Interval as the guideline for performing examinations, Relief Request No. 9 has been written to address this issue.
2.1 Class 1 The Class 1 system boundaries are developed based upon the requirements of 10 CFR 50.2(v) and the Turkey Point Units 3 and 4 FSAR's. The components/systems to be examined in the Class 1 systems are described in detail below:
- 2. 1. 1 ASME Code Exemptions Employed IWB-1220 The following components (or parts of components) are exempted from the volumetric and surface examination requirements of IWB-2500:
(a) Components that are connected to the reactor coolant system and- part of the reactor coolant pressure boundary and that are of such a size and shape so that upon postulated rupture the resulting flow of coolant from the reactor coolant system under normal plant operating conditions is within the capacity of makeup systems which are operable from on-site emergency power.
(b) 1. Piping of 1" nominal pipe size and smaller, except for steam generator tubing; and
- 2. Components and their connections in piping of 1" nominal pipe size and smaller.
(c) Reactor Vessel head connections and associated piping, 2" nominal pipe size and smaller, made inaccessible by control rod drive penetrations.
5 \I r I' I
Turkey Point ISI Program Revision 0 Date: August 27, 1993 2.1.2 Component/Piping Examination Basis 2.1.2.1 Category B-A, Pressure Retaining Welds in the Reactor Pressure Vessel Bl.ll CircumferentialShell Shell Welds Bl.12 Lon itudinal Welds Scope of Examination 100% of all longitudinal and circumferential shell welds (does not include shell to flange weld).
PTN-3 PTN-4 longitudinal shell welds circumferential shell welds B1.21 Circumferential Bottom Head Welds B1.22 Meridional Bottom Head Welds Scope of Examination 1004 of accessible length of circumferential and meridional head welds.
PTN-3 PTN-4 meridional head welds circumferential head weld B1.21 Circumferential To Head Welds B1.22 Meridional To Head Welds Scope of Examination 1004 of accessible length of circumferential and meridional head welds.
PTN-3 PTN-4 meridional head welds circumferential head welds B1.30 Shell-to-Flan e Weld Scope of Examination 100~ of the shell to flange weld.
PTN-3 PTN-4 Circumferential shell to flange weld 1 Note: If partial examinations are conducted from the flange face, the remaining volumetric examinations required to be conducted from the vessel wall may be performed at or near the end of each inspection interval. The examination may be performed during the first and third inspection periods in conjunction with the
~
It, ~ ~,K <s4'k 8 y T N
Turkey Point ISI Program Revision 0 Date: August 27, 1993 nozzle examinations of Category B-D (Program B). At least 504 of the weld shall be examined by the end of the first inspection period, and the remainder by the end of the third inspection period.
B1.40 Head to Flan e Weld Scope. of Examination 100% of the head to flange weld.
PTN-3 PTN-4 circumferential head to flange weld B1.51 Re air Welds Beltline Re ion Not applicable to Turkey Point Units 3 or 4 284 of the Category B-A welds will be examined by the end of the first period, with the remaining welds examined during the third period for both units.
See Paragraph 2.1.2.17(b) for additional requirements.
2.1.2.2 Category B-B, Pressure Retaining welds in vessels other than Reactor Vessels Pressurizer:
B2.11 Circumferential Shell to Head Welds B2.12 Lon itudinal Shell to Head Welds Scope of Examination 100% of both shell to head welds and 1 ft. on one intersecting longitudinal weld at each circumferential weld.
PTN-3 PTN-4 circumferential welds longitudinal welds Pressurizer:
B2.21 Circumferential Head Welds B2.22 Meridional Head Welds Scope of Examination 1004 of 1 circumferential and 1 meridional weld per head.
Not applicable to Turkey Point Units 3 or 4 Steam Generators:
B2.31 - Circumferential Head Welds B2.32 Meridional Head Welds
I Pr J, P,
N
't a
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Scope of Examination 1004 of one circumferential and one meridional weld per head (the exams may be limited to one vessel among the group of vessels performing a similar function).
Not applicable to Turkey Point Units 3 or 4 Steam Generators:
B2.40 Tubesheet to Head Welds Scope of Examination 1004 of one weld on one Steam Generator PTN-3 PTN-4 3 Tubesheet. to head welds per SG-B SG-A unit Heat, Exchan ers:
B2.51 Circumferential Head Welds B2.52 Meridional Head Welds B2.60 Tubesheet to Head Welds B2.70 Lon itudinal Welds B2.80 Tubesheet to Shell Welds PTN-3 PTN-4 B2.51 B2.52 B2.60 B2.70 B2.80 No welds scheduled, see Relief Request No. 3 Due to scheduling, the relief request on the Regenerative Heat Exchanger, and in order to minimize radiation exposure, 604 of the required B-B examinations on Turkey Point Unit 3 will be completed during the first period.
2.1.2.3 Category B-D, Full Penetration Welds of Nozzle in Vessels (Program B)
Reactor Vessel:
B3.90 Nozzle to Vessel Welds B3.100 Nozzle Inside Radius Section Scope of Examination 100% of all nozzles PTN-3 PTN-4 RPV Nozzle Welds RPV Nozzle Inner Radius 10
li ') '
s j + A m
H I A'I ,l',8 v 4 'I I a Ik
%I
Turkey Point ISI Program Revision 0 Date: August 27, 1993 All examinations have been deferred to near the end of the Interval. See Relief Request No. 8.
Pressurizer:
B3.110 Nozzle to Vessel Welds B3.120 Nozzle Inside Radius Sections Scope of Examination 100% of all nozzles PTN-3 PTN-4 Nozzle to Vessel Welds Nozzle Inner Radius Steam Generators:
B3.130 Nozzle to Vessel Welds B3.140 Nozzle Inside Radius Sections Scope of Examination 100% of all nozzles PTN-3 PTN-4 Nozzle to Vessel Welds 0 Nozzle Inner Radius (2 per vessel) 6 Heat Exchan ers:
B3.150 Nozzle to Vessel Welds B3.160 Nozzle Inside Radius Section Scope of Examination 100~ of all nozzles PTN-3 PTN-4 B3. 150 12 12 B3. 160 12 12 No examinations scheduled. See Relief Request No. 3.
Due to scheduling, the relief request on the Regenerative Heat Exchanger, and in order to minimize radiation exposure, 84 of the required B-D examinations on Turkey Point Unit 4 will be completed during the First Period. 41% of the required examinations for Unit 3 and 4 will be complete by the end of the Second Period.
2.1.2 ' Category B-E, Pressure Retaining Partial Penetration Welds in Vessels Partial Penetration Welds B4.11 Vessel Nozzles B4.12 Control Rod Drive Nozzles B4.13 Instrumentation Nozzles 11
f If Turkey Point ISI Program Revision 0 Date: August 27, 1993 Scope of Examination VT-2 on 254 of the nozzles each interval.
Pressurizer:
Item B4.20 Heater Penetration Welds Scope of Examination VT-2 on all heater penetration welds each interval.
2.1.2.5 Category B-F, Pressure Retaining Dissimilar Metal Welds Reactor Vessel:
B5.10 NPS 4 or Lar er Nozzle to Safe End Butt Welds B5.20 Less Than NPS 4 Nozzle to Safe End Butt Welds B5.30 Nozzle to Safe End Socket Welds Scope of Examination 1004 of all dissimilar welds each interval PTN-3 PTN-4 B5.10 > 4" Safe-End Butt, Welds 6 6 B5.20 < 4" Safe-End Butt Welds 0 0 B5. 30 Socket Welds 0 0 Pressurizer:
B5.40 NPS 4 or Lar er Nozzle-to-safe End Butt Welds B5.50 Less Than NPS 4 Nozzle-to Safe End Butt Welds B5.60 Nozzle-to-Safe End Socket Welds Scope of Examination 100~ of all dissimilar welds each interval.
PTN-3 PTN-4 B5.40 > 4" Safe End Butt Welds B5.50 < 4" Safe-End Butt Welds B5.60 Socket Welds Steam Generator:
B5.70 NPS 4 or Lar er Nozzle to Safe End Butt Welds B5.80 Less Than NPS 4 Nozzle to Safe End Butt Welds B5.90 Nozzle to Safe End Socket Welds Scope of Examination 1004 of all dissimilar welds each interval 12
Turkey Point ISI Program Revision 0 Date: August 27, 1993 PTN-3 PTN-4 B5.70 > 4" Safe-End Butt Welds B5.80 < 4" Safe-End Butt Welds B5.90 Socket Welds Heat Exchan ers:
B5.100 NPS 4 or Lar er Nozzle to Safe End Butt Welds B5.110 Less Than NPS 4 Nozzle to Safe End Butt Welds B5.120 Nozzle to Safe End Socket Welds Not Applicable to Turkey Point Units 3 or 4
~Pi in B5.130 NPS 4 or Lar er Dissimilar Metal Butt Welds B5.140 Less Than 4 NPS Dissimilar Metal Butt Welds B5.150 Dissimilar Metal Socket Weld Not Applicable to Turkey Point Units 3 or 4 See Table A-1 for Listing of B-F Welds.
Due to scheduling and to reduce radiation exposure, 55% of the required B-F examinations in PTN-3 will be completed during the First Period and 77% by the end of the Second Period.
2.1.2.6 Category B-G-1, Pressure Retaining Bolting, Greater 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.
PTN-3 PTN-4 B6.10 Closure Nuts 58 58 B6.30 Closure Studs 58 58 B6.40 Threads in Flange 58 58 B6.50 Closure Washers 116 116 Pressurizer: Items B6.60 B6.70 B6.80 Steam Generators: Items B6.90 B6.100 B6.110 Heat Exchan ers: Items B6.120 B6.130 B6.140 Pi in Items B6.150 B6.160 B6.170 Valves: Items B6.210 B6.220 B6.230 Not Applicable to Turkey Point Units 3 or 4 Pum s: Items B6.180 B6.190 B6.200 Scope of Examination 1004 of the above items in one Reactor Coolant Pump in the interval. See Tables B-1 and B-3 for summary listing by Unit.
13
I l~t g
< . 4 >~ P~vll I ~
j
Turkey Point ISI Program Revision 0 Date: August 27, 1993 PTN-3 PTN-4 (72) B6.180 Studs per Unit 24 24 (3) B6.190 Flange Surfaces per Unit 1 1 (72) B6.200 Nuts, Washers per Unit 24 24 There are no bushings in the Reactor Coolant Pumps.
Due to scheduling and to reduce radiation exposure, 68% of the required B-G-1 examinations in PTN-3 will be completed by the end of the Second Period. 414 of PTN-4 will be completed by the end of the First period and 70% by the end of the Second Period.
2.1.2.7 Category B-G-2, Pressure Retaining Bolting, 2 in. and Less in Diameter Items: B7.10 B7.20 B7.30 B7.40 B7.50 B7.60 B7.70 B7.80 Scope of Examination Visual examinations each interval are limited to components selected for examination under B-B, B-J, B-L-2, and B-M-2. See Table B-2 for summary listing of valve bolting for Unit 3 and Table B-4 for Unit 4.
Due to scheduling and to reduce radiation exposure, 45% of the required B-G-2 examinations in PTN-3 will be completed by the end of the First Period, 70~ by the end of the Second Period.
414 of the required examinations for PTN-4 will be completed by the end of the First period and 70% by the end of the Second Period.
2.1.2.8 Category B-H, Integral Attachments for Vessels Reactor Vessel:
B8.10 Inte rail Welded Attachment Not applicable to Turkey Point Unit 3 or 4 Pressurizer:
B8.20 Inte rail Welded Attachment Scope of Examination 1004 surface exam of support skirt to vessel weld.
Support Skirts on both Units have welds outside the inspection envelope defined in Fig IWB-2500-14. No examinations are required.
Steam Generator:
B8.30 Inte rail Welded Attachment Not Applicable to Turkey Point Unit 3 or 4 Heat Exchan ers:
B8.40 Inte rail Welded Attachment 14
W Turkey Point ISI Program Revision 0 Date: August 27, 1993 Scope of Examination- 1004 of each integral attachment PTN-3 PTN-4 B8.40 Heat Exchanger (RGX)
No exams to be performed See Relief Request No. 3 2.1.2.9 Category B-Z, Pressure Retaining Welds in Piping Items: B9.11 B9.12 B9.21 B9.22 B9.31 B9.32 B9.40 Scope of Examination All dissimilar metal pipe welds, high stress welds, terminal ends, plus an additional number of piping welds so that 25% of all nonexempt circumferential and branch connection pipe welds are examined. All longitudinal pipe welds intersecting any of the selected circumferential welds will also be examined.
Refer to Tables C-1,2,3 (Unit 3) and Tables C-4,5,6 (Unit 4) for a complete listing, by zone, of welds subject to examination for this category.
2.1.2.10 Category B-K, Integral Attachments to Piping, Pumps, and Valves The guidelines of Code Case N-509 will be used in the performance and scheduling of examinations in lieu of the B-K-1 requirements of the 1989 Edition of Section XI which do not require examinations for the third and fourth intervals.
Scope of examination -10% of the Integral Attachments will receive a Surface examination, 100% of required areas of each welded attachment. In the case of multiple components within a system of similar design, function, and service, only one of the integral attachments of only one of the multiple components shall be examined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).
B10.10 Pi in Inte rail Welded Attachments B10.20 Pum Inte rail Welded Attachments Scope of examination: 10> of the Integral Attachments will receive a surface examination.
See Relief Request No. 8.
B10.30 Valve Inte rail Welded Attachments Not applicable to Turkey Point Units 3 or 4.
2.1.2.11 Category B-L-1, Pressure Retaining Welds in Pump Casings; and Category B-L-2, Pump Casings 15
I l ll I p ~ II 'P ik L ~
Turkey Point ISI Program Revision 0 Date: August 27, 1993 B12.10 Pum Casin Welds Scope of Examination: 100o volumetric exam of weld in one of the three Reactor Coolant Pumps per Unit. Code Case N-481 will be utilized as an alternate examination.
See Appendix B for details of requirements for both Units 3 and 4.
In order to reduce radiation exposure, 100>o of the required B12.10 examinations in PTN-3 and PTN-4 will be completed during the 3rd period.
B12.20 Pum Casin Scope of Examination: Visual examination of interior surfaces of one of the three Reactor Coolant Pumps when disassembled for maintenance.
See Appendix B for Pump and Valve Groupings.
2.1.2.12 Category B-M-1, Pressure Retaining Welds in Valve Bodies; and Category B-M-2, Valve Bodies B12.30 Valve Bod Welds < NPS 4 B12.40 Valve Bod Welds > NPS 4 Not applicable to Turkey Point Units 3 or 4.
B12.50 Valve Bod > NPS 4 Scope of Examination Visual examination of at least one valve of a group of valves once per interval when disassembled for maintenance or repair. See Appendix B, Table B-2 for details on Unit 3 and, and Table B-4 for Unit 4 ~
2.1.2.13 Category B-N-1, Interior of Reactor Vessel; Category B-N-2, Integrally Welded Core Support Structures and Interior Attachments to Reactor Vessels; and Category B-N-3, Removable Core Support Structures B13.10 Reactor Vessel Interior Scope of Examination Visual examination of accessible areas (areas above and below the reactor core made accessible for exam by removal of components during normal refueling), once each inspection period.
Item: B13.20 B13.30 B13.40 Not applicable to Turkey Point Units 3 or 4.
16
0 4 ~ l Turkey Point ISI Program Revision 0 Date: August 27, 1993 Item: B13.50 Scope of Examination Interior attachments within the beltline region (once per interval) for both Units 3 and 4.
Item: B13.60 Scope of Examination Interior attachments beyond the beltline region (once per interval) for both Units 3 and 4.
Item: B13.70 Scope of Examination Visual examination of accessible surfaces of core support structures when removed from the vessel (once per interval) For both Units 3 and 4.
Due to scheduling and in order to reduce radiation exposure, these Categories are scheduled together to meet the requirements of Program B.
2.1.2.14 Category B-O, Pressure Retaining Welds in Control Rod Housings Item: B14.10 Scope of Examination 10> of peripheral housings.
PTN-3 PTN-4 B14.10 Control Rod Housings 65 65 In order to reduce radiation exposure, all required examinations for PTN-3 will be performed during the second period and during the first period for PTN-4.
2.1.2.15 Category B-P, All Pressure Retaining 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 Examination System pressure tests are conducted on Class 1 systems and components as follows:
(a) A S stem Leaka e Test, IWA-5211(a) is conducted prior to plant startup following each occurrence where the Class 1 pressure boundary is breached, such as during a refueling outage.
The pressure retaining boundary subject to the leakage test corresponds to 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 17
Turkey Point ISI Program Revision 0 Date: August 27, 1993 examination boundary extends to include the second closed valve at the boundary extremity, which may be a check valve opposing Reactor Coolant system pressure. The test is conducted at system operating temperature and pressure.
(b) A S stem Leaka e Test will be performed in accordance with alternate exam techniques of Code Case N-498 "Alternative Rules for 10-Year Hydrostatic Pressure Testing for Class 1 and 2 SystemsSection XI, Division I".
All ASME Section XI Pressure Testing requirements are controlled by site procedures.
2.1.2.16 Category B-Q, Steam Generator Tubing B16.20 Steam Generator Tubin in U-Tube Desi n Scope of Examination The extent and frequency of examination shall be governed by the plant Technical Specifications. The Steam Generator tubing surveillance requirements are contained in Plant Technical Specification 3/4.4.5.
2.1.2.17 Augmented Examinations (a) Reactor Coolant Pump Flywheels As required by Regulatory Guide 1.14, the bore and keyway areas of each RCP flywheel are examined ultrasonically once each period. Additionally, the flywheels receive a 100%
volumetric examination and a surface examination near the end of each Inspection Interval. Reference PTN 3/4 Technical Specifications, Paragraph 4.4.10.
(b) The Reactor Vessel examinations (including the Closure Head) are performed to Regulatory Guide 1.150, Rev. 1 as augmented by Appendix VII of the 1989 Edition of Section XI.
2.2 Class 2 The Class 2 System Boundaries are developed based upon the requirements of Regulatory Guide 1.26 and the Turkey Point Units 3 and 4 FSAR'S.
Specific examination requirements for components and systems are based upon the 1989 Edition of ASME Section XI.
Augmented examinations required by SRP 6.6,Section I.8 and APCSB 3.1 para. B.2.c(4) are incorporated as described in para. 2.2.2.9.
18
II I $ ~ << I > II 1 x I lt II Turkey Point ISI Program Revision 0 Date: August 27, 1993 2.2.1 Components Exempt from Examination IWC-1220 The following components (or parts of components) are exempted from the volumetric and surface examination requirements of IWC-2500.
2.2.1.1 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 lq 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'. 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, valves, other components, and component connections of any size in statically pressurized, passive (i.e., no pumps) safety injection systems of pressurized water reactor plants.
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.
2.2.1.2 IWC-1222 Components within systems (or portions of systems) other than RHR, ECC and CHR systems (a) Vessels, piping, pumps, valves, and other components NPS 4 and 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.
19
I I
Turkey Point ISI Program Revision 0 Date: August 27, 1993 (c) Vessels, piping, pumps, valves, other components, and component connections of any size in systems or portions of systems that operate (when the system function is required) at a pressure equal to or less than 275 psig and 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.
2.2.1.3 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.
2.2.2 Component/Piping Examination Basis 2.2.2.1 Category C-A, Pressure Retaining Welds in Pressure Vessels C1.10 Shell Circumferential Welds Scope of Examination 1004 of all welds at gross structural discontinuities only. The examination may be limited to one vessel or distributed among the vessels.
Components applicable to:
Steam Generators (3)
PTN-3 PTN-4 Ext. Ring to Lower Shell SG-A SG-A Lower Shell to transition SG-B SG-B Transition to Upper Shell SG-B SG-A RHR Heat Exchan ers (2)
No C1.10 welds on RHR Heat Exchanger Cl.20 Head Circumferential Welds Scope of examination: 100~~ of head-to-shell welds, (limited to one of multiple vessels). Components applicable to:
Steam Generators (3) PTN-3 PTN-4 Upper Shell to Head SG-B SG-C RHR-Heat Exchan ers (2)
Head to Shell RHR-HX-A RHR-HX-A 20
'N c ~ =
'E I
Turkey Point ISI Program Revision 0 Date: August 27, 1993 C1.30 Tubesheet, to Shell Welds Scope of examination: 100% of tubesheet to shell welds (limited to one of multiple vessels).
Components applicable to:
Steam Generators(3) PTN-3 PTN-4 Ext. Ring to Tubesheet. SG-A SG-A RHR Heat Exchan er (2)
Shell to Tubesheet RHR-HX-A RHR-HX-A Excess Letdown Heat Exchan er (1)
Cap to Shell LDHX LDHX Shell to Flange LDHX LDHX 2.2.2.2 Category C-B, Pressure Retaining Nozzle Welds in Vessels C2.10 Nozzles in Vessels < ' Nominal Thickness C2.11 Nozzle to Shell or Head Weld Not applicable to Turkey Point Units 3 or 4 Item: C2.20 C2.21 C2.22 Nozzles without Reinforcing Plate in Vessels > 1/2" Nominal Thickness.
C2.21 Nozzle to Shell or Head Welds Scope of Examination All nozzles at terminal ends of piping runs (limited to one of multiple vessels)
Steam Generators 3 PTN-3 PTN-4 Main Steam Nozzles SG-A SG-A Main Feedwater Nozzles SG-A SG-A Note: Third Interval Nozzle to Shell examinations will be performed on Steam Generator A only based on C-F-2 weld selection changes from the Second Interval (decrease from 25> to 7.5%). Performing C-B examinations only on Steam Generator A is in compliance with the Code and provides consistency with the C-F-2 selections.
21
0 Turkey Point ISI Program Revision 0 Date: August 27, 1993 C2.22 Nozzle Inside Radius Section Scope of Examination All nozzles at terminal ends of piping runs (limited to one of multiple vessels).
Steam Generators 3 PTN-3 PTN-4 Main Steam Nozzles SG-A SG-A Main Feedwater Nozzles SG-A SG-A Note: Third Interval Inner Radius examinations will be performed on Steam Generator A only based on C-F-2 weld selection changes from the Second Interval (decrease from 254 to 7.54). Performing C-B examinations only on Steam Generator A is in compliance with the Code and provides consistency with the C-F-2 selections.
C2.30 C2.31 C2.32 & C2.33 Nozzles with Reinforcing Plate in Vessels > 1/2" Nominal Thickness.
C2.31 Reinforcin Plate Welds to Nozzle and Vessel Scope of Examination All nozzles at terminal ends of piping runs (limited to one of multiple vessels).
RHR-Heat Exchan ers(2) PTN-3 PTN-4 Reinforcing Plate Welds RHR-HX-A RHR-HX-A C2.32 Nozzle to Shell or Head Welds When Inside of Vessel is Accessible Not applicable to Turkey Point Units 3 and 4 C2.33 Nozzle to Shell or Head Welds When Inside of Vessel is Inaccessible Scope of Examination VT-2 of telltale hole in reinforcing plates (limited to one of multiple vessels).
RHR Heat Exchan ers (2) PTN-3 PTN-4 VT-2 of Heat Exchangers RHR-HX-A RHR-HX-A Due to scheduling and in order to reduce radiation exposure, the Category C-B required examinations are scheduled as follows:
22
0 s ~ ~
Turkey Point ISI Program Revision 0 Date: August 27, 1993 1st 2nd 3rd Per Per Per PTN-3 0>o 50>o 504 PTN-4 50>o 50>o 09.
2.2.2.3 Category C-C, Integral Attachments for Vessels, Piping, Pumps and Valves The guidelines of Code Case N-509 will be used in the performance and scheduling of examinations in lieu of the C-C requirements of the 1989 Edition of Section XI.
Scope of examination -10% of the Integral Attachments will receive a Surface examination, 100~ of required areas of each welded attachment. In the case of multiple components within a system of similar design, function, and service, only one of the integral attachments of only one of the multiple components shall be examined. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).
See Relief Request No. 8.
C3.10 Pressure Vessels Inte rail Welded Attachments No integrally welded attachment on Turkey Point Steam Generators RHR Heat Exchan ers (2)
PTN-3 PTN-4 One per Heat Exchanger RHR-HX-A RHR-HX-A C3.20 Pi in Inte rail Welded Attachments Scope of Examination 100% of required areas of welded attachments (limited to attachments of components examined per C-F-1 and C-F-2). Multiple component concept is not applicable.
C3.30 Pum s Inte rail Welded Attachments There are no Class 2 Pumps with integrally welded attachments at Turkey Point Units 3 or 4.
2.2.2.4 Category C-D, Pressure Retaining Bolting > 2" in Diameter C4.10 C4.20 C4.30 and C4.40 Not applicable to Turkey Point Units 3 and 4 23
) lt V
f+
p gl
Turkey Point ISI Program Revision 0 Date: August 27, 1993
. 2.2.2.5..-,Category C-F-1, Pressure Retaining Welds in Austenitic
-.-'.Stainless Steel or High Alloy Piping.
C5-' C5.11 C5.12 C5.20 C5.21 C5.22 C5.30 C5.40 C5.4 and C5 42~
=Welds are selected as noted below. Refer to Tables D-1 through D-11 for a complete listing by zone and unit of welds selected for examination.
(a) Requirements for examination of welds in piping NPS 4 apply to PWR high pressure safety injection systems in accordance with the exemption criteria of IWC-1220.
(b) The welds selected for examination shall include
'.7.54, but not less than 28 welds, of all austenitic stainless steel of high alloy 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-1. These welds, however,
.shall be included in the total weld count to which the 7.54 sampling rate is applied, listed as Category C-F). The examinations shall be distributed as follows:
(1) the examinations shall be distributed among the Class 2 systems prorated, to the degree practicable, on the number of nonexempt austenitic stainless steel or high alloy welds in each system (i.e.,
the nonexempt if welds, a system contains 304 of then 30% of the nondestructive examinations required by Examination Category C-F-1 should be performed on that system);
I (2). within a system, the examinations shall be distributed among terminal ends and structural discontinuities prorated, to the degree
--'.-.. practicable, on the number of nonexempt terminal ends and structural discontinuities in that system; and I
. - ."--=(3) .within each system, examinations shall be distributed between line sizes prorated to the
,degree practicable.
(c)-- 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.
(d) The . welds selected for examination shall be reexamined during subsequent inspections over the 24
Turkey Point ISI Program Revision 0 Date: August 27, 1993 service lifetime of the piping component to the extent practical.
2.2.2.6 Category C-F-2, Pressure Retaining Welds in Carbon or Low Alloy Steel Piping Items C5.60 C5.61 and C5.62 Not applicable to Turkey Point Units 3 and 4 Items C5.50 C5.51 C5.52 C5.70 C5.80 C5.81 and C5.82 Welds are selected as noted below. Refer to Tables E-1 through E-8 for a complete listing by zone and unit of welds selected for examination.
(a) Requirements for examination of welds in piping NPS 4" apply to PWR high pressure safety injection systems in accordance with the exemption criteria of IWC-1220.
(b) The welds selected for examination shall include 7.5S, 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, listed as Category C-F). The examinations shall be distributed as follows:
(1) the examinations 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);
(2) within a system, the examination shall be distributed among terminal ends and structural discontinuities prorated, to the degree practicable, on the number of nonexempt terminal ends and structural discontinuities in that system; and (3) within each system, examinations shall be distributed between line sizes prorated to the degree practicable.
(c) Structural discontinuities include pipe weld joints to vessel nozzles, valve bodies, pump casings, pipe fittings (such as elbows, tees, reducers, flanges, 25
Turkey Point ISI Program Revision 0 Date: August 27, 1993 etc., conforming to ANSI B16.9), and pipe branch connections and fittings.
I (d) The welds selected for examination shall be reexamined during subsequent inspection intervals over the service lifetime of the piping component to the extent practical.
(e) Only those welds showing reportable preservice transverse indications need to be examined for transverse reflectors.
2.2.2.7 Category C-F, Piping Exempt from Examination Under Categories C-F-1 and C-F-2 Welds that are exempt from examination under Categories C-F-1 and C-F-2 do not require examination.
They are included within, the Summary Tables for counting purposes only.
2.2.2.8 Category C-G, Pressure Retaining Welds in Pumps and Valves Items C6.10 & C6.20 Not applicable to Turkey Point Units 3 and 4 2.2.2.9 Category C-H, All Pressure Retaining Components Items C7. 10 C7.20 C7.30 C7.40 C7.50 C7.60 C7.70 &
C7.80 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 performed as required by the Plant Technical Specifications 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 the performance of the periodic system (or component) functional test.
Nominal operating pressure of the system functional test is acceptable as the system test pressure.
26
0' Turkey Point ISI Program Revision 0 Date: August 27, 1993 (b) A S stem Leaka e Test, will be performed in accordance with alternate exam techniques of Code Case N-498, "Alternative Rules for 10 Year Hydrostatic Pressure Testing for Class 1 and 2 SystemsSection XI, Division 1", except for Steam Generators out to the first isolation valve where Code Case N-416 will be utilized.
- 2. 2. 2. 10 Augmented Examinations (a) Welds in those portions of systems addressed in USNRC Branch Technical Position APCSB 3.1 para.
B.2.c(4);
(b) Welds in those portions of systems addressed in SRP 6.6 paragraph I.8.
(c) Steam Generator Feedwater Nozzle Piping Augmented Examination FPL will perform an augmented examination each refuel outage on the Steam Generator Feedwater Nozzle piping from the nozzle taper to a point one pipe diameter down on the first elbow. These examinations will continue until an engineering evaluation concludes these examinations are no longer required.
2.3 Class 3 The Class 3 system boundary examination is based upon the requirements of Regulatory Guide 1.26, and ASME Section XI, Table IWD-2500-1.
2.3.1 ASME Code Exemptions employed 2.3.1.1 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 for the Auxiliary Feedwater System.
2.3.1.2 Integral attachments of supports and restraints to components exceeding 4" Nominal 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.
27
I 5 a a ll(
0 0
t
Turkey Point ISI Program Revision 0 Date: August 27, 1993 2.3.2 Component/Piping Examination Basis The guidelines of Code Case N-509 will be used in the performance and scheduling of examinations in lieu of the D-A, D-B, and D-C requirements of the 1989 Edition of Section XI.
See Relief Request No. 8.
2.3.2.1 Category D-A, Systems in Support of Reactor Shutdown Function D1.20 Inte ral Attachments Com onent Su orts and Restraints Dl.30 Inte ral Attachments Mechanical and H draulic Snubbers D1.40 Inte ral Attachments S rin T e Su orts Dl.50 Inte ral Attachments Constant Load T e
~Su orts D1.60 Inte ral Attachments Shock Absorbers Scope of Examination 10< of the Integral Attachments will receive a Visual (VT-1) examination, 100% of required areas of each welded attachment. 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. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).
2.3.2.2 Category D-B, Systems in Support of Emergency Core Cooling, Containment Heat Removal, Atmosphere Cleanup, and Reactor Residual Heat Removal D2.20 Inte ral Attachments Com onent Su orts and Restraints D2.30 Inte ral Attachments Mechanical and H draulic Snubbers D2.40 Inte ral Attachments S rin T e Su orts D2.50 Inte ral Attachments Constant Load T e
~Su orts D2.60 Inte ral Attachments Shock Absorbers Scope of examination -10% of the Integral Attachments will receive a Visual (VT-1) examination, 100% of required areas of each welded attachment. 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. The integral attachments selected for examination shall correspond to those component supports selected by IWF-2510(b).
28
s 4
C
Turkey Point ISI Program Revision 0 Date: August 27, 1993 2.3.2.3 Category D-C, Systems in Support of Residual Heat Removal from Spent Fuel Storage Pool D3.20 Inte ral Attachments Com onent Su orts and Restraints D3.30 Inte ral Attachments Mechanical and H draulic Snubbers D3.40 Inte ral Attachments S rin T e Su orts D3.50 Inte ral Attachments Constant Load T e
~Su orts D3.60 Inte ral Attachments Shock Absorbers Scope of examination -10% of the Integral Attachments will receive a Visual (VT-1) examination, 1004 of required areas of each welded attachment. 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. The integral attachments selected for examination shall correspond to those component, supports selected by IWF-2510(b).
2.3.3 System Pressure Tests 2.3.3.1 The pressure retaining components within the 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, IWA-5211(c) For 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 to test pressurization during a System Inservice Test extends to those pressure retaining components under operating pressures during normal system operation; or (b) 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 performed as required by the Plant Technical Specifications 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 the performance of the 29
> C" I* ~
Turkey Point ISI Program Revision 0 Date: August 27, 1993 periodic system (or component) functional test.
Nominal operating pressure of the system functional test is acceptable as the system test pressure.
(c) System Hydrostatic Test, IWA-5211(d) is performed on Class 3 systems once in 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 function.
The system pressure requirements are defined in sub-article IWD-5223 of the Code. The VT-2 examination performed during a system hydrostatic test is used to satisfy the system pressure test requirements of (a) and (b) above for that period in which it is conducted.
2.3.3.2 All ASME Section XI Pressure Testing requirements are controlled by site procedures. The boundaries subject to system Pressure tests, Functional tests, Inservice tests, and Hydrostatic tests are shown in the Piping and Instrumentation Diagrams (see Section 5.0) .
2.4 Component Supports Scope of Examination Component supports subject to examination are selected in accordance with sub-article IWF-2510. A minimum sample of 25% will be examined.
Those supports selected receive a visual examination (VT-3) to determine their general mechanical and structural condition. Spring type supports and mechanical and hydraulic snubbers receive a visual examination to determine conditions relating to their operability. All Code item numbers will be examined as applicable. See Appendix F for details of selections for both Units 3 and 4. Credit will be taken for 25> of the Snubber examinations.
Several supports hold more than one classified line.
These supports are counted only once and if scheduled for examination, will cover all of the applicable lines. The support will be counted once for credit.
2.5 Reexamination of Flaw Indications 2.5.1 Class 1 Pursuant to the Section XI Code, sub-article IWB-2420, in the case of Class 1 components, where examinations reveal the presence of flaw indications that exceed the acceptance standards and the component is analyzed as acceptable for service (see section 4.4), the areas containing the flaw indications will be scheduled for 30
Jt
}
l
Turkey Point ISI Program Revision 0 Date: August. 27, 1993 reexamination during the next three (3) inspection periods of Inspection Plan B (IWB-2410). Provided the flaw indications remain essentially unchanged over that period, the component examination schedule will revert to the original schedule of successive inspections.
2.5.2 Class 2 Pursuant to the Section XI Code, sub-article IWC-2420, in the case of Class 2 components, where examinations reveal the presence of flaw indications that exceed the acceptance standards and the component is analyzed as acceptable for service (see section 4.4), the areas containing the flaw indications will be scheduled for reexamination during the next inspection period of Inspection Plan B (IWC-2412). Provided the flaw indications remain essentially unchanged over that period, the component examination schedule will revert to the original schedule of successive inspections.
2.5.3 Class 3 Class 3 components with flaw indications that exceed the acceptance standards and are analyzed as acceptable for continued service (see section 4.4) need not be scheduled for reexamination except as required by Inspection Plan B (IWD-, 2412).
2.5.4 Component Supports Component supports with flaw indications that render them non-functional but are accepted for continued service by evaluation shall be reexamined during the next inspection period.
2.6 Substitute Examinations FPL may substitute unscheduled components for scheduled components when the original selection was part of a sample. This substitution may be performed when conditions such as limited physical access, high radiation levels, or other situations which may necessitate a substitute examination. Specific exams required by the Code that can not be completed will be the subject of a relief request.
2.7 Class MC Components 10 CFR 50.55A presently incorporates only those portions of Section XI that address the ISI requirements for Class 1, 2, and 3 components and their supports. The regulations do not currently address the ISI of containments. Since this proposed amendment is only 31
L w
P ~
Turkey Point ISI Program Revision 0 Date: August 27, 1993 intended to include the latest ASME Code edition and addenda, the requirements of Subsection IWE is not imposed upon Commission licensees by this amendment.
Per the above statement, Subsection IWE of Section XI is not applicable, and is not addressed in this Program.
The incorporation by reference Subsection of IWE into 50.55a is presently the subject of a separate rulemaking action.
Reference:
Federal Register, Vol. 57, No. 152, Dated August 6, 1992 32
Turkey Point ISI Program Revision 0 Date: August 27, 1993 3.0 Relief Requests 3.1 During the First and Second Ten Year Inspection Intervals, there were cases where component configuration and/or interference prevented the code required volume or surface area from being examined. In each case where limitations were encountered, the details were documented in a Relief Request. Those items which are scheduled for examination during the third inspection interval are included in this section. As allowed by Code Case N-460, only those examinations where less than 90~O coverage was attained will be part of a Relief Request.
3.2 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 evaluating the development of new or improved examination techniques with the intent of applying these techniques where a practical improvement in the examination can be achieved.
3.3 Each Relief Request contains the following information:
A. Component Identification describes the Code Class and a brief description of the component; B. Examination Requirement describes the Code Category and Item Numbers, and the examination requirements; C. Relief Requested description of the Code requirements that are being requested for relief; D. Basis for Relief describes examinations conducted and/or evaluated to support the reason relief is being requested; E. Alternative Examinations describes examinations conducted and/or evaluated to support the basis for relief; and F. Implementation Schedule when the relief request is expected to be implemented; G. Attachments to the Relief identify all Figures, Tables, Sketches, Photographs, etc., attached to the Request for Relief.
3.4 Relief Requests are found in Appendix G.
33
Turkey Point ISI Program Revision 0 Date: August 27, 1993 4.0 Evaluation Criteria Florida Power and Light will perform non-destructive examinations using Visual, Surface (Penetrant and Magnetic Particle), and volumetric (Ultrasonic, Radiography, and Eddy Current) techniques.
Other NDE techniques may be utilized when required.
During Inservice Inspections, NDE indications are evaluated against the acceptance standards of ASME Section XI (see tables 4.1 through 4.4). Components with indications that do not exceed the acceptance criteria will be considered acceptable for continued service. Additional examinations are not required.
Examinations that reveal indications exceeding the acceptance standards identified in tables 4.1 through 4.4 will be made acceptable by an engineering evaluation, repair, replacement, or an analytical evaluation.
4.1 Acceptance by Engineering Evaluation Examinations that reveal indications exceeding the acceptance standards identified in Tables 4.1 through 4.4 may be submitted to Nuclear Engineering for evaluation and disposition as follows:
A. Indications determined to be acceptable by the FPL Design and/or Manufacturer's Specifications shall be acceptable for continued service provided they meet the minimum requirements of the Construction Code.
B. Indications determined to be surface anomalies (e.g fabrication marks, scratches, surface abrasion, material roughness, or other conditions) are acceptable for continued service provided the indication is removed by light flapping and/or grinding (surface preparation) without violating the design minimum wall thickness.
4.2 Acceptance by Repair Components whose volumetric or surface examination reveals indications exceeding the acceptance criteria of Tables 4.1 through 4.4 shall be unacceptable for continued service until repaired. Repairs are further covered by section 7.0.
4.3 Acceptance by Replacement As an alternative to repairing the component, the portion of the component containing the indication may be replaced.
Replacements are further covered by section 7.0.
34
l K~
k Y (
C i <<t 4
p I k ~
S p'
Revision 0 Date: August 27, 1993 4.4 Acceptance by Analytical Evaluation Components whose volumetric or surface examination reveals indications exceeding the acceptance criteria of Tables 4.1 through 4.4 are acceptable for continued service without the repair or replacement if an analytical evaluation meets the acceptance criteria of IWB-3600.
4.5 Component Support Indications If the evaluations conducted on a component support demonstrates that the support was performing its intended safety function, additional exams are not required.
Corrective action may still be performed.
4.6 Supplemental Examinations Volumetric, visual, or surface examinations that. detect indications requiring evaluation may be supplemented by other examination methods and techniques to determine the character of the indication.
4.7 Additional Examinations Additional examinations that are required in accordance with IWB-2430, IWC-2430, and IWF-2430 will be performed before the end of the outage.
4.8 Minimum Thread Engagement Requirements Turkey Point Nuclear Engineering has reviewed the Code requirements applicable to thread engagement for safety related bolted connections. When studs or bolts are threaded into nuts, the end of the stud or bolt, excluding any points, shall extend through the nut at, least until it is flush with the face of the nut and until there is no evidence of unengaged threads in the nut.
Bolting that does not meet this criteria shall be unacceptable for further service until a JPN Engineering evaluation has been completed and approval for continued use is obtained or the bolting has been repaired or replaced.
Reference:
Letter from S.T. Hale to L.N. Motley, dated February 12, 1991, document no. JPNS-PTN-91-0684.
35
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Table 4.1 Class 1 Acceptance Standards Examination Component or Part Examined Acceptance Category Standard B-A Welds in Reactor Vessels IWB-3510 B-B Welds in Other Vessels IWB-3510 B-D Vessel Nozzle Welds IWB-3512 B-E Partial Penetration welds in IWB-3522 Vessels B-F, B-J Dissimilar and Similar Metal IWB-3514 Welds in Piping B-G-1 Bolting > 2" diameter IWB-3515/3517 B-G-2 Bolting < 2" diameter IWB-3517 B-H Integral Attachments for Vessels IWB-3516 B-L-1, B-M-1 Welds in Pumps and Valves IWB-3518 B-L-2, B-M-2 Pump Casings and Valve Bodies IWB-3519 B-N-1, B-N-2 Interior Surfaces and Internal IWB-3520 B-N-3 Components of Reactor Vessels B-0 Control Rod Drive Housing Welds IWB-3523 B-P Pressure Retaining Boundary IWB-3522 B-Q Steam Generator Tubing IWB-3521 36
i I1
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Table 4.2 Class 2 Acceptance Standards Examination Component or Part Examined Acceptance Category Standard C-A Welds in Pressure Vessels IWC-3510 C-B Nozzle Welds in Vessels IWC-3511 C-C Integral Attachments for IWC-3512 Vessels, Piping, Pumps and Valves C-D Bolting IWC-3513 C-F-1, C-F-2 Welds in Piping IWC-3514 C-G Welds in Pumps and Valves IWC-3515 C-H Pressure Retaining Components IWC-3516 Table 4.3 Class 3 Acceptance Standards Examination Component or Part Examined Acceptance Category Standard D-A Pressure Boundary (VT-2) IWD-3000 Integral Attachments (VT-3)
D-B Pressure Boundary (VT-2) IWD-3000 Integral Attachments (VT-3)
D-C Pressure Boundary (VT-2) IWD-3000 Integral Attachments (VT-3) 37
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Table 4.4 Component Support Acceptance Standards Examination Component or Part Examined Acceptance Category Standard F-A Supports IWF-3410 FPL will consider as acceptable paint spatter found on close tolerance machined or sliding surfaces as long as an engineering evaluation has determined that its presence does not interfere with the function of the support.
38
sj ~kg r I 7 'c' I<' -'-p'I j '~in e'
II J4 Ib 0
Turkey Point ZSI Program Revision 0 Date: August 27, 1993 5.0 Program Boundary Drawings The code required boundaries for all Class 1, 2, and 3 systems are denoted by a boxed-in letter (A, B, and C respectively) on Piping and Xnstrument Diagrams (P&IDs).
39
Turkey Point ISI Program Revision 0 Date: August 27, 1993 6.0 Records 6.1 General Records of Inservice Inspection Program, Plans, outage schedules, calibration standards, examination and test procedures, results of activities, final reports, certifications, and corrective actions taken or recommended will be developed and maintained in accordance with IWA-6000 of the ASME Boiler and Pressure Vessel Code,Section XI, and Relief Request No. 6.
6.2 Nondestructive Examinations Completed data packages shall be submitted to the ISI Specialist following completion of the Inservice examination activity.
6.3 Final Reports Final reports shall be generated for the following activities:
(a) Nondestructive Examination Activities performed on Class 1, 2, or 3 systems, components and their supports.
(b) Snubber examinations and tests (c) System Pressure Tests (d) Eddy Current examinations (e) Repairs and Replacements 6.4 Final Report Format Final reports shall contain, as a minimum, the information required on the NIS-1A or NIS-2B form or similar format, as applicable.
6.5 Inservice Inspection Summary Reports One Hundred Twenty days (120) following the end of the period, FPL shall forward a Summary Report of the ISI activity to the Nuclear Regulatory Commission in accordance with IWA-6220.
Included within the Summary Report, the following Owners'ata Reports shall be included:
(a) NIS-1A, Owners'ata Report for Inservice Inspections.
40
4 A ff
Turkey Point ISI Program Revision 0 Date: August 27, 1993 (b) NIS-1B, Abstract of Examinations and Tests (c) NIS-1C, Examinations not Performed as Identified in the Inspection Plan (d) NIS-lD, Identification of Items with Flaws which Require Analytical Evaluation for Continued Acceptability (e) ISI Summary Records (or similar form)
(f) NIS-2A, Repair/Replacement Plan Certification Record (g) NIS-2B, Abstract of Repairs and Replacements (h) NIS-BB Owners'ata Report for Eddy Current Examinations The reports submitted shall include information since the last submittal.
These reports are designed to include the information required by the Code and the additional requirements of the Plant Technical Specifications.
41
Turkey Point ISI Program Revision 0 Date: August 27, 1993 DATE: 08/27/93 (A) TURKEY POINT NUCLEAR PLANT UNIT 3 (0) PAGE: 1 REVISION : 1 (B) IHSERVICE INSPECTION
SUMMARY
REPORT SECOHD INTERVAL, THIRD PERIOD, FIRST OUTAGE (1991)
CLASS 1 ALL STATUS COMPOHEHTS REACTOR PRESSURE VESSEL (E) (C)
N I 0 ZONE NUMBER : 001 (F) ASME S ON 0T SEC. XI T RSEH
SUMMARY
EXAMINATION AREA CATGY EXAM A E I 0 E REMARKS NUMBER IDENTIFICATION ITEM NO METHOD PROCEDURE T C G M R **CALIBRATIONBLOCK**
3PSRV1 REF. DNG. HO. 3-V01 (G) 0100 3.NR-18 (I) (L) 8-A UT 0 NDE 5.4 C X- 12/90 - DATE AND REMARKS ON COMPLETED FLANGE TO UPPER SHELL (J) (M) B1.30 UT 45 NDE 5.4 (P) X- EXAM CTMT, 58'EVEL (K) UT 45T NDE 5.4 X- (S)
UT 60 NDE 5.4 X-UT 60T NDE 5.4 X- *AU[ 1**
(N) (0) (o) (R)
(A) Date the inspection plan table was printed
(~) Current revision number of the inspection plan (C) Specific outage and classification of system (D) Page number of the table (E) System designation (F) Zone number (G) Isometric drawing (H) Summary number of the record (I) Component or weld identification number
(~) Component or weld description (K) Elevation and/or location of component (L) ASME Code category (M) ASME Code item number (N) NDE methods (o) Procedure number (p) Shows status of examination X Scheduled C Completed A Augmented P Partial E Expanded Scope (Q) Types of indications found (R) Ultrasonic calibration block (S) Remarks on examinations performed during this outage. Date is optional.
Inservice Inspection Summary Record 42
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Eddy Current, Summary of Results Plant:
Examination Dates: Through Total Tubes Steam Total Total Ind. Total Ind. Plugged as Total Generator Tubes 204 40< Preventive Tubes Number Inspected to 39~o to 1004 Maintenance Plugged Location of Indications Drilled Support Top of Tube Sheet Steam AVB 1 through 6 to 1 Drilled Support Generator Bars Cold Leg Hot Leg Cold Leg Hot Leg Certification of Record 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: By:
NDE Supervisor NIS-BB Owners'eport of Steam Generator Examinations
il I
a
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Steam Generator Tubes Plugged Plant:
Steam Generator Steam Generator Steam Generator 3E210A 3E210B 3E210C Row Column Remarks Row Column Remarks Row Column Remarks NIS-BB Owners'eport of Steam Generator Examinations 44
1'j Revision 0 Date: August 27, 1993 Steam Generator Eddy Current Examination Results Plant:
Examination Dates: through Row Column % Tube Wall Origin Location Penetration NIS-BB Owners'eport of Steam Generator Examinations 45
I" k N 7
II
Turkey Point ISI Program Revision 0 Date: August 27, 1993 7.0 Repairs, Replacements and Modifications A Repair/Replacement Plan shall be prepared in accordance with the requirements of the 1992 Edition of Section XI, IWA-4140.
All other applicable requirements of the 1989 Edition of Section XI, IWA-4000, shall be met.
7.1 Repairs 7.1.1 Code repairs are performed in accordance with approved procedures or instructions in accordance with IWA-4000.
7.1.2 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 a description of the flaw.
(b) The flaw 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 nondestructive examination methods to be used after the repair.
(d) Evaluation as described in 7.4.
(e) The repair programs shall be subject to review by the enforcement and regulatory authorities having jurisdiction at the plant site.
7.1.3 After repairs by welding on the pressure retaining boundary, a system pressure test shall be performed in accordance with IWA-5000 (when required by IWA-4700).
7.1.4 The repaired area shall be reexamined to establish a new preservice record. The examination shall include the method that detected the flaw.
7.2 Replacements 7.2.1 Replacements are performed using approved procedures or instructions in accordance with IWA-7000. 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 46
a a
~ a
Turkey Point ISI Program Revision 0 Date: August 27, 1993 (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-7500.
(h) The application of the ASME Code Symbol Stamp in accordance with IWA-7300.
7.2.2 Replacements that involve substitution of materials, dimensional changes, process changes, deviations to specifications or changes to design codes require engineering approval.
7.2.3 All procedures for the installation of renewal, spare, and replacement parts shall be in accordance with IWA-4100.
7.2.4 Prior to the systems return to service, a preservice examination shall be made in accordance with IWB-2200, IWC-2200, IWD-2200, or IWF-2200, as applicable, for the component and part replaced.
7.3 Modifications The performance of modifications is controlled in accordance with Quality Procedure QP 3.4.
7.4 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 and/or 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.
47
). v' 0
Revision 0 Date: August 27, 1993 7.5 Access 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.
7.6 Determination of Design and Construction Codes 7.6.1 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.
7.6.2 The design and analysis of piping, components and supports shall meet the design code of record as identified in the FSAR or design specification.
7.6.3 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 50.55a(g).
7.7 Authorized Nuclear Inservice Inspector The services of an Authorized Inspection Agency (ANII) shall be used when making 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 necessary inspections may be performed.
7.8 Implementation All ASME Section XI Class 1, 2, and 3 Repairs and Replacements are controlled by Engineering procedures.
II k
ll
Turkey Point ISI Program Revision 0 Date: August 27, 1993 8.0 Inservice Inspection Plan and Schedules 8.1 Inspection Plan Tables 8.1.1 The Inservice Inspection Plan Tables for the Inservice examinations of the major components of Florida Power and Light, Turkey Point Units 3 and 4 will be in a format similar to the Table found on page 51.
8.1.2 The Inspection Plan has been divided into zones. Each zone is defined by a drawing which identifies and locates welds and other examination areas for each system.
8.1.3 For the sake of continuity and clarity, all items to which a Code category and Code item number can be applied are identified.
8.2 Ten Year Inspection Plan The Ten Year Inspection Plan provides the following information:
8.2.1 Program Summary Number Each weld or component is assigned a unique summary number. These are for administrative control and are subject to change. This provides a format for accessing multiple data bases relating to each weld or component.
8.2.2 ASME Section XI Item Number The Code item number from table IWB-2500-1, IWC-2500-1, IWD-2500-1, or IWF-2500-1, as applicable, of the ASME Boiler and Pressure Vessel Code,Section XI.
8.2.3 Component Identification The unique component or weld identification number. This number appears on the applicable ISI isometric drawing.
8.2.4 Component Description A brief description of the component or, in the case of a weld, the parts being joined.
8.2.5 Code Category The Code category from table IWB-2500-1, IWC-2500-1, IWD-2500-1, or IWF-2500-1, as applicable, of the ASME Boiler and Pressure Vessel Code,Section XI.
8.2.6 Code Exam Methods The examination method(s) to be used for each item number, if applicable.
8.2.7 ISI Interval The numbers 1, 2, 3, or 4 signify a ten-year interval. The current inspection interval 49
Turkey Point ISI Program Revision 0 Date: August 27, 1993 relating to this table is number 3 (see Figure 8-1).
Each outage within a period will have an "X" placed in the applicable period and outage in which it will be examined or an A g B g C g E ( or "P" to show when the examination took place and the type of exam performed.
8.2.8 Instructions Identifies specific examination notes.
8.3 Weld Identification Welds and other components that are subject to examination and have not been identified by plant drawings have been assigned identification numbers for tracking purposes.
When new longitudinal seam welds are identified, they reference the intersecting circumferential weld.
50
Turkey Point ISI Program Revision 0 Date: August 27, 1993 TE: 08/27/93 (A) TURKEY POINT HUCLEAR PLANT UNIT 3 (D) PAGE: 146 REVISION: 1 (B) TEN-YEAR IHSERVICE INSPECTION PLAN CLASS 1 COMPONENTS (C)
INSPECTION INTERVAL PLAN STATUS RPV CLOSURE HEAD (E) FIRST SECOHD THIRD ZONE NUHBER: 051 (F) ASME PERIOD PERIOD PERIOD SUHMARY EXAMINATION AREA SEC. XI CATGY HDE - - - - - 0 U T A G E - - - -- INSTRUCT IOHS NUMBER I IDENT IF CATION ITEM HO METH 1 2 3 4 1 2 3 4 1 2 3 4 **CALIBRATIONBLOCK**
SYSTEM NO. 41 5613-P-570-S SH. 1 OF 3 REF. DWG. NO. 3-A24 (G) 091000 2"-RC-1305-28 (I) (L) 8-J PT 1 2-C (P)
QH) ELBSI TO PIPE (J) (M) B9.40 (N) X CTMT, 24'0" (K) 3-4 ** (Q) **
(O) 7/4/93 - THIS IS MHERE REMARKS FROM PREVIOUS OUTAGES ARE LOCATED (R)
(A) Date the inspection plan table was printed (B) Current revision number of the inspection plan (C) Classification of system (D) Page number of the table (E) System designation (F) Zone number (G) Isometric drawing (H) Summary number of the record (I) Component or weld identification number
(~) Component or weld description (K) Elevation and/or location of component (L) ASME Code category (M) ASME Code item number (N) NDE methods (o) Shows when an item was examined or is scheduled to be examined. Any interval can be shown separately.
A Augmented B Baseline C Completed E Expanded Scope P Partial X Scheduled Other Codes may be used as needed.
(P) Specific instructions for this component (Q) Ultrasonic calibration block (R) Remarks from previous outages. Date is optional.
Inspection Plan Table Format Figure 8-1, Summary Tables in the Ten-Year Plan 51
Turkey Point ISI Program Revision 0 Date: August 27, 1993 9.0 Nondestructive Examination Procedures The following is a list of the standard NDE procedures used for ISI activities. The specific revision used during an activity will be listed in the examination plan for that activity. Other NDE procedures may be used as required.
Procedure Title No.
NDE 1. 3 Eddy Current Examinations of Non Ferro-magnetic Tubing with Multi Frequency Techniques MIZ-12 NDE 2.2 Magnetic Particle Examination NDE 3.3 Liquid Penetrant Examination Solvent Removable Visible Dye Technique NDE 4. 1 Visual Examination VT-1 for Welds/Bolting/Bushings/Washers NDE 4. 2 Visual Examination VT-2 Conducted During System Pressure Tests NDE 4.3 Visual Examination VT-3 NDE 4.4 Steam Generator Secondary Side Visual Examination NDE 5. 1 Ultrasonic Examination of Pressure Vessel Welds Except Reactor Vessels NDE 5. 2 Ultrasonic Examination of Ferritic Piping Welds NDE 5. 4 Ultrasonic Examination of Austenitic Piping Welds NDE 5. 5 Ultrasonic Examination of Main Coolant Piping Welds, Turkey Point 3 and 4 NDE 5. 6 Ultrasonic Examination of Integrally Welded Attachments to Piping NDE 5. 7 Ultrasonic Examination of Reactor Pressure Vessel Studs and Reactor Coolant Pump Studs NDE 5.8 Ultrasonic Examination of Bolting Material for Cracking NDE 5.9 Ultrasonic Examination of Bolting Material for Corrosion NDE 5. 10 Ultrasonic Examination of Nuts Two Inches in Diameter or Greater 52
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Procedure Title No.
NDE 5.11 Ultrasonic Examination of Dissimilar Metal Welds NDE 5.12 Manual Ultrasonic Examination of Reactor Vessel Flange to Shell Welds and Stud Hole Threads NDE 5.13 Ultrasonic Examination of Nozzle Inner Radius Areas NDE 5. 14 Manual Ultrasonic Examination of Reactor Pressure Vessel Shell and Closure Head Welds NDE 5. 15 Ultrasonic Examination of Reactor Coolant Pump Flywheels NDE 5. 16 Ultrasonic Examination Technique for the Evaluation of Cracking in Steam Generator Feedwater Piping NDE 5.18 Ultrasonic Thickness Measurement NDE 5. 19 Ultrasonic Examination of Socket welds in the Pressurizer Auxiliary Spray Line PTN-3/4 53
Turkey Point ISI Program Revision 0 Date: August 27, 1993 10.0 Calibration Block Table Block Thickness Diameter Material Drawing Heat Number Number Number UT-1 9.000" FLAT SA 508 CL 2 D-4352-038 218993 UT-2 6.988" FLAT SA 508 CL 2 D-4352-022 216817 UT-3 4.812" FLAT SA 508 D-ISI-005 UT-4 IR N/A SA 508 CL 2 D-4352-028 216817 UT-5 IR N/A SA 533 GR B D-4352-016 C5312-1 UT-6 5.000" Flat SA 533 GR B D-4352-023 C5312-1 UT-7 3.620" N/A SA 302 GR B C-ISI-008 UT-8 5.750" N/A SA 216 GR WCC C-ISI-007 17436/27256 UT-9 5.500" N/A SA 216 GR WCC C-ISI-009 17436/27256 UT-10 3.000" Flat SA 508 C-ISI-010
.UT-11 N/A 6 00" RPV STUD D-4352-024 UT-12 2.635" 27.5 SA 376 TP 316 C-ISI-20 D8770 UT-13 3.000" Flat SA 533 GR B C-ISI-006 C5312-1 UT-14 7.000" N/A SA 508 CL 2 D-4352-041 218993 UT-15 6.937" N/A SA 508 CL 2 D-4352-039 218993 UT-16 No longer used UT-17 1.500" 26" SA 155 KC 70 D-4352-030 202575 54
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Block Thickness Diameter Material Drawing Heat Number Number Number UT-18 N/A 3.500n RCP STUD C-ISI-013 UT-19 N/A 5.375 RCP NUT D-4352-021 UT-20 .594n 14n SA 106 GR B C-ISI-002 UT-21 .875n 2 6n SA 155 KC 70 CL1 E-ISI-003 UT-22 .750n 6n E-ISI-004 R81221 UT-23 437 6n SA 106 Gr B C-ISI-002 23242 UT-24 No longer used UT-25 N/A 7.875n RPV NUT D-4352-025 UT-26 3.016 27.5n Sa 351 CF8M C-4352-040 FB117-01 UT-27 pn 10n SA 376 TP 316 C-ISI-023 J2009 UT-28 8 II 8. 750 MANWAY BOLT B-ISI-017 T05989 UT-29 .750n 18n SA 106 GR B LMT-106 L84404 UT-30 1.250n 14 fl SA 376 TP 316 C-4174-023 E1473 UT-31 1.250n 14n SA 132 TP 304 C-ISI-001 UT-32 No longer used UT-33 375 14n SA 312 TP 304 LMT-101 V71515 UT-34 1. 125 SA 376 TP 316 C-4174-025 51420 UT-35 375 12n SA 312 TP 304 LMT-102 F81528 55
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Block Thickness Diameter Material Drawing Heat Number Number Number UT-36 330 12" SA 358 TP 304 D-4352-034 17493 UT-37 280 6" SA 312 TP 304 D-4352-033 M2444 UT-38 593 1P II SA 106 GR B LMT-107 N35898 UT-39 .365" 1P 11 SA 312 TP 304 D-4352-032 A29600 UT-40 1.160" 9 II SA 105 D-4352-036 225026 UT-41 .718" 8 II SA 376 TP 316 C-4174-024 J1424 UT-42 718 ,811 SA 376 TP 304 LMT-104 M0194 UT-43 32211 8 II SA 312 TP 304 LMT-103 8052226 UT-44 438 3 II SA 312 TP 316 C-4174-019 2P3278 UT-45 438n 4 II SA 312 TP 316 C-4174-020 2P1941 UT-46 2.437" 29" SA 376 TP 316 C-4174-026 D8770 UT-47 30011 3 11 SA 312 TP 304 LMT-105 05032 UT-48 N/A 4 II 2P6396 UT-49 875 8 SA 182 TP 304 C-ISI-002 0890-18-1-2 UT-50 1.000" 1 2 ll SA 312 TP 304 C-ISI-001 UT-51 1.406" 14" SA 106 GR B UT-52 511 Flat SA 336 UT-53 0.438 4.00" SA 182 TP 316 1G4865 56
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Block Thickness Diameter Material Drawing Heat Number Number Number UT-54 .344" 2 II SS FSK-M-3077 UT-55 1. 018 Flat SS RHR Heat Exchanger N/A N/A N/A CSCL N/A Steam Generator Mockup 57
Revision 0 Date: August 27, 1993 Appendix A Table A-1 Turkey Point Unit 3 Category B-F Weld Listing Zone Number Weld Summary Code Item Size Identification Number Number 007 31"-RCS-1301-5 043800 B5. 70 31" 008 29"-RCS-1304-1 044700 B5. 10 29 II 008 29 n-RCS-1304-4 045100 B5. 70 29 It 009 27 5tr-RCS-1307-14 046000 B5.10 27.5" 010 31"-RCS-1302-5 046200 B5. 70 31ll 011 29"-RCS-1305-1 047100 B5.10 29 II 011 29"-RCS-1305-4 047700 B5.70 2 9 II 012 27.5"-RCS-1306-14 048600 B5.10 27.5 013 31"-RCS-1303-5 048800 B5.70 31" 014 29"-RCS-1308-1 049700 B5. 10 2 9 lI 014 29"-RCS-1308-4 050200 B5. 70 29 ll 015 27.5"-RCS-1309-14 051000 B5. 10 27.5 016 14"-RC-1302-8A 052500 B5.40 14" 017 4>>-RC-1301-lA 052700 B5. 40 4 II 018 4"-RC-1302-lA 054100 B5.40 4 II 019 4"-RC-1303-lA 055500 B5.40 4fl 020 4"-RC-1304-1A 062100 B5. 40 4fl 022 4't-RC-1306-lA 068700 B5.40 4 1I 58
Revision 0 Date: August 27, 1993 Appendix A Table A-2 Turkey Point Unit 4 Category B-F Weld Listing Zone Weld Summary Code Item Size Number Identification Number Number 007 31>>-RCS-1401-5 055800 B5.70 31>>
008 29>>-RCS-1404-1 056600 B5.10 2 9 II 008 29>>-RCS-1404-4 056900 B5.70 29>>
009 27.5>>-RCS-1407-14 057500 B5.10 27.5>>
010 31>>-RCS-1402-5 057900 B5.70 3 1>>
011 29>>-RCS-1405-1 058700 B5. 10 2 9 ll 011 29>>-RCS-1405-4 059000 B5. 70 29 012 27.5>>-RCS-1406-14 059600 B5. 10 27.5>>
013 31>>-RCS-1403-5 060100 B5.70 31>>
014 29>>-RCS-1408-1 060900 B5.10 29>>
014 29>>-RCS-1408-4 061200 B5.70 29>>
015 27.5>>-RCS-1409-14 061700 B5.10 27.5 016 14>>-RC-1401-8A 063200 B5. 40 14>>
017 4>>-RC-1401-lA 063300 B5.40 4 II 018 4>>-RC-1402-1A 064400 B5.40 4>>
019 4>>-RC-1403-lA 065500 B5.40 4>>
020 4 I'-RC-1404-3 1 069600 B5.40 4 II 022 4>>-RC-1406-1A 076600 B5.40 4>>
59
a Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix B Table B-1 Turkey Point Unit 3 Class 1 Pump Grouping Table Zone Pump B-L-1 B-L-2 B-G-1 Selected Number Number Weld ID ID Identification for Exams 056 RCP-A 3-RCP-A-A 3-RCP-A 3-RCP-FSA-1 24 See 3-RCP-A-B 3-RCP-FNA-1 24 Notes 3-RCP-A-C 3-RCP-FLA-1 24 Below 057 RCP-B 3-RCP-B-A 3-RCP-B 3-RCP-FSB-1 24 See 3-RCP-B-B 3-RCP-FNB-1 24 Notes 3-RCP-B-C 3-RCP-FLB-1 24 Below 058 RCP-C 3-RCP-C-A 3-RCP-C 3-RCP-FSC-1 24 See 3-RCP-C-B 3-RCP-FNC-1 24 Notes 3-RCP-C-C 3-RCP-FLC-1 24 Below Notes: B-L-1 Exams limited to one pump per group per interval.
B-L-2 Exam required only when pump is disassembled for repair, maintenance or volumetric examination.
B-G-1 Examinations are limited to components selected for exam under B-L-2.
Code Case N-481 Alternative Examination Requirements for Cast Austenitic Pump CasingsSection XI, Division I Inquiry: When conducting examination of cast austenitic pump casings in accordance with Section XI, Division I, what examinations may be performed in lieu of the volumetric examinations specified in Table IWB-2500-1, Examination Category B-L-l, Item B12.10?
Reply: It is the opinion of the Committee that the following requirements shall be met in lieu of performing the volumetric examination specified in Table IWB-2500-1, Examination Category B-L-1, Item B12.10:
1 Turkey Point ISI Program Revision 0 Date: August 27, 1993 (a) Perform a VT-2 visual examination of the exterior of all pumps during the System Leakage test required by Table IWB-2500-1, Category B-P, and Code Case N-498.
(b) Perform a VT-1 visual examination of the external surfaces of the welds of one pump casing.
(c) Perform a VT-1 visual examination of the internal surfaces whenever a= pump is disassembled for maintenance.
(d) Perform an evaluation to demonstrate the safety and service-ability of the pump casing. The evaluation shall include the following:
(1) evaluating material properties, including fracture toughness values; (2) performing a stress analysis of the pump casing; (3) reviewing the operating history of the pump; (4) selecting locations for postulating flaws; (5) postulating one-quarter thickness reference flaw with a length six times its depth; (6) establishing the stability of the selected flaw under the governing stress conditions; (7) considering thermal aging embrittlement and any other processes that may degrade the properties of the pump casing during service.
(e) A report of this evaluation shall be submitted to the regulatory and enforcement authorities having jurisdiction at the plant site for review.
61
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix B Table B-2 Turkey Point Unit 3 Class 1 Valve Grouping Table B-M-2 B-G-2 Group Zone Valve Type Size Summary Summary Selected Number Number Number Number Number for Exam 036 MOV-3-750 Gate Isol 14 II 121900 122000 See Notes 036 MOV-3-751 Gate Isol 14 II 122900 123000 Below 037 3-875A Check 1PII 124900 125000 See 038 3-875B Check 1Plf 126900 127000 Notes 039 3-875C Check 1PIf 134000 134100 Below 037 3-875D Check 10II 123200 123300 038 3-875E Check 1P If 128600 128700 039 3-875F Check 10" 131700 131800 037 3-876A Check 8 II 126300 126400 See 038 3-876B Check 8" 128800 128900 Notes 039 3-876C Check 8 II 130600 130700 Below 038 3-876D Check 8" 129500 129600 039 3-876E Check 8 II 130000 130100 Notes:
B-M-2 Examination is required only when a valve is disassembled for maintenance or repair (one valve per group per interval).
B-G-2 For bolting, examinations are limited to valves selected for examination under Category B-M-2.
62
r' Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix B Table B-3 Turkey Point 4 Class 1 Pump Grouping Table Zone Pump B-L-1 B-L-2 B-G-1 Selected Number Number Weld ID ID Identification for Exams 056 RCP-A 4-RCP-A-A 4-RCP-A 4-RCP-FSA-1-24 See 4-RCP-A-B 4-RCP-FNA-1-24 Notes 4-RCP-A-C 4-RCP-FLA-1-24 Below 057 RCP-B 4-RCP-B-A 4-RCP-B 4-RCP-FSB-1-24 See 4-RCP-B-B 4-RCP-FNB-1-24 Notes 4-RCP-B-C 4-RCP-FLB-1-24 Below 058 RCP-C 4-RCP-C-A 4-RCP-C 4-RCP-FSC-1-24 See 4-RCP-C-B 4-RCP-FNC-1-24 Notes 4-RCP-C-C 4-RCP-FLC-1-24 Below Notes: B-L-1 Exams limited to 1 pump per group per interval.
B-L-2 Exams required only when pump is disassembled for repair, maintenance or volumetric examination.
B-G-1 Examinations are limited to components selected for exams under B-L-2.
Code Case N-481 Alternative Examination Requirements for Cast Austenitic Pump CasingsSection XI, Division I Inquiry: When conducting examination of cast austenitic pump casings in accordance with Section XI, Division I, what examinations may be performed in lieu of the volumetric examinations specified in Table IWB-2500-1, Examination Category B-L-1, Item B12.10?
Reply: It is the opinion of the Committee that the following requirements shall be met in lieu of performing the volumetric examinations specified in Table IWB-2500-1, Examination Category B-L-1, Item B12.10:
63
Revision 0 Date: August 27, 1993 (a) Perform a VT-2 visual examination of the exterior of all pumps during the System Leakage test required by Table IWB-2500-1, Category B-P and Code Case N-498.
(b) Perform a VT-1 visual examination of the external surfaces of the weld on one casing.
(c) Perform a VT-1 visual examination of the internal surfaces whenever a pump is disassembled for maintenance.
~ ((1) Perform an evaluation to demonstrate the safety and service-ability of the pump casing. The evaluation shall include the following:
(1) evaluating material properties, including fracture toughness values; (2) performing a stress analysis of the pump casing; (3) reviewing the operating history of the pump; (4) selecting locations for postulating flaws; (5) postulating one-quarter thickness reference flaw with a length six times its depth; (6) establishing the stability of the selected flaw under the governing stress conditions; (7) considering thermal aging embrittlement and any other processes that may degrade the properties of the pump casing during service.
(e) A report of this evaluation shall be submitted to the regulatory and enforcement authorities having jurisdiction at the plant site for review.
64
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix B Table B-4 Turkey Point 4 Valve Grouping Table B-M-2 B-G-2 Group Zone Valve Type Size Summary Summary Selected Number Number Number Number Number for Exam 036 MOV-4-750 Gate 1 41l 115300 115400 See Notes 036 MOV-4-751 Gate 14 ll 116600 116700 Below 037 4-875A Check 10it 120100 120200 See Notes 038 4-875B Check 10" 122800 122900 Below 039 4-875C Check 10it 126800 126900 037 4-875D Check 10it 118600 118700 038 4-875E Check 10it 121300 121400 039 4-875F Check 10ii 125300 125400 037 4-876A Check 8" 117100 117200 See Notes 038 4-876B Check 123400 123500 Below 039 4-876C Check 8 II 124700 124800 038 4-876D Check 8" 124000 124100 037 4-876E Check 8" 117800 117900 Notes:
B-M-2 Examination is required only when a valve is disassembled for maintenance or repair (one valve per group per interval).
B-G-2 For valves, examinations are limited to valves selected for examination under B-M-2.
65
Revision 0 Date: August 27, 1993 Appendix C Table C-1 Turkey Point Unit 3 B-J Piping Welds Summary Zone Sys. B9.11 B9. 12 B9. 21 B9. 31 B9.32 B9.40 007 RCS 008 RCS 009 RCS 010 RCS 011 RCS 012 RCS 013 RCS 014 RCS 015 RCS 016 RCS 017 RCS 10 018 RCS 10 019 RCS 10 020 RCS 29 021 RCS 022 RCS 026 RCS 027 RCS 028 RCS 035 RCS 40 036 RHR 037 21 038 24 039 28 66
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix C Table C-1 Turkey Point Unit 3 B-J Piping Welds Summary Zone Sys. B9.11 B9.12 B9.21 B9.31 B9.32 B9.40 040 HPSI 34 041 HPSI 29 042 HPSI 29 043 HPSI 36 044 HPSI 37 045 CVCS 45 046 CVCS 29 047 CVCS 22 048 CVCS 18 049 CVCS 050 CVCS 30 051 CVCS 37 052 CVCS 29 059 CVCS Totals 210 121 18 390 67
h i "s Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix C Table C-2 Turkey Point Unit 3 Class 1 Non-Exempt B-J Piping Welds by Code Item Number and Size Size B9. 11 B9. 12 B9. 21 B9. 31 B9. 32 B9. 40 Tot Sch Tot, Sch Tot Sch Tot. Sch Tot Sch Tot Sch 3 1 II 15 5 29 II 27.5 14" 12 4 12 II 1 0 ll 52 17 8 II 21 7 4ft 92 26 0 0 3 tl 0 121 21 2 fI 13 8 380 84 1.5" 10 Total 210 69 4 121 21 18 9 390 88 Totals (not including B9.12, longitudinal seams)
B-J welds 746 Scheduled 190 4 scheduled 190/746 = 25.5C 68
e N
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix C Table C-3 Turkey Point Unit 3 Category B-J Welds Selected for Examination Examined Third Zone Weld Identification Code Size During Interval Number Item Second Selection Interval Criteria 007 31>>-RCS-1301-BC-1 B9.32 2 II Yes 25~o 31>>-RCS-1301-10 B9.11 3 1>> Yes TE 008 29>>-RCS-1304-2 B9. 11 29>> Yes 25%
29>>-RCS-1304-BC-2 B9.32 2 II Yes 254 009 27.5>>-RCS-1307-11 B9.11 27.5>> Yes TE 27.5>>-RCS-1307-BC-1 B9.32 2>> Yes 254 27.5>>-RCS-1307-12 B9.11 27.5>> Yes 25>o 27 5'I-RCS-1307-BC-2 B9.31 10>> Yes 25~a 27 5>>-RCS-1307-BC-3 B9.32 3 II Yes 25~a 010 31>>-RCS-1302-8 B9. 11 3 1>> Yes 254 31>>-RCS-1302-BC-1 B9.32 2 II Yes 25a 31>>-RCS-1302-10 B9.11 31>> Yes TE 011 29>>-RCS-1305-2 B9. 11 29>> Yes 25>
29>>-RCS-1305-BC-3 B9. 31 14>> Yes 25~o 29'I-RCS-1305-3 B9. 11 29>> Yes 254 012 27 5>>-RCS-1306-11 B9. 11 27.5 Yes TE 27.5>>-RCS-1306-BC-1 B9. 32 2 II Yes HS 27.5>>-RCS-1306-BC-3 B9. 32 2>> Yes 254 27.5>>-RCS-1306-12 B9. 11 27.5 Yes 25>
27.5'I-RCS-1306-BC-4 B9. 31 10>> Yes 25%
013 31>>-RCS-1303-7 B9. 11 31>> Yes 25~o 31>>-RCS-1303-10 B9. 11 3 ill No TE 015 27.5>>-RCS-1309-11 B9. 11 27.5>> No TE 016 14>>-RC-1302-lA B9. 11 14>> No TE 12>>-RC-1301-1 B9. 11 Yes 25>
12>>-RC-1301-8 B9. 11 12>> Yes 25>o 017 4>>-RC-1301-1 B9. 11 4>> Yes TE 4'I-RC-1301-7 B9. 11 4>> Yes 25~o TE Terminal End 25 254 Additional Welds HS High Stress LS Longitudinal Weld 69
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix C Table C-3 Turkey Point Unit 3 Category B-J Welds Selected for Examination Examined Third Zone Weld Identification Code Size During Interval Number Item Second Selection Interval Criteria 018 4>>-RC-1302-1 B9. 11 4>> Yes TE 4>>-RC-1302-4 B9. 11 4 II Yes 25~o 019 4>>-RC-1303-1 B9.11 4>> Yes TE 4>>-RC-1303-5 B9.11 4>> Yes 25%
4>>-RC-1303-7 B9.11 4>> Yes 25~o 020 4>>-RC-1304-1 B9.11 4>> Yes TE 4>>-RC-1304-2 B9.11 4 ll Yes 25'5~o 4>>-RC-1304-9 B9.11 4 II Yes 4>>-RC-1304-FW10 B9.11 4 Il Yes 25~o 4>>-RC-1304-FW18 B9.11 4 If Yes 25>
4'I RC 1304 FW20 B9.11 4>> Yes 25%
4>>-RC-1304-21 B9.32 2 fl No HS 4-RC-1304-22 B9.11 4 II Yes 25~o 4>>-RC-1304-23 B9.11 4>> Yes 25~a 4>>-RC-1304-26 B9.11 4 If Yes TE 021 4>>-RC-1305-1 B9.11 4>> Yes TE 4>>-RC-1305-2 B9.11 4>> Yes 25%
41'-RC-1305-7 B9.11 4 II Yes 25<
4'I-RC-1305-8 B9.11 4 II Yes 25'5~o 4>>-RC-1305-13 B9.11 4>> Yes 4>>-RC-1305-19 B9.11 4 Il Yes HS 022 4>>-RC-1306-1 B9. 11 4 II Yes TE 4>>-RC-1306-3 B9.11 4 Il Yes 25~
4>>-RC-1306-4 B9.11 4 II Yes 25%
4>>-RC-1306-7 B9.11 4 II Yes 25~o 3>>-RC-1304-1 B9.21 3>> Yes 25~o 3>>-RC-1305-3 B9.21 3>> Yes 25~o 026 2>>-RC-1301-1 B9. 40 21f Yes TE 2>>-RC-1301-2 B9. 40 2 II Yes 25~o TE Terminal End 25 25% Additional Welds HS High Stress LS Longitudinal Weld
'70
'd k '
~ > li '
h
'I 'I A
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix C Table C-3 Turkey Point Unit 3 Category B-J Welds Selected for Examination Examined Third Zone Weld Identification Code Size During Interval Number Item Second Selection Interval Criteria 027 2>>-RC-1302-1 B9.40 2 II Yes TE 2>> -RC-13 02-5 B9.40 2>> Yes 25>
028 2>>-RC-1303-1 B9. 40 2 II Yes TE 2'I RC 1303 5 B9. 40 2>> Yes TE 035 2>>-RC-1310-1 B9. 40 2>> Yes HS & TE 2>>-RC-1310-2 B9. 40 2>> Yes HS 2>>-RC-1310-3 B9. 40 2>> Yes HS 2>>-RC-1310-4 B9. 40 2 II Yes 254 2>>-RC-1310-11 B9. 40 2 II Yes 25<o 2>>-RC-1310-16 B9. 40 2 II Yes 25>o 2>>-RC-1310-31 B9.40 2 II Yes 25%
036 14>>-RHR-1301-1 B9. 11 14>> No TE 14>>-RHR-1301-6 B9. 11 14>> Yes 254 14>>-RHR-1301-9 B9. 11 14>> Yes 2 5~o 037 10>>-SI-1301-1 B9. 11 1P>> No TE 10>>-SI-1301-2 B9. 11 1P>> Yes 25>o 10>>-SI-1301-22-BC B9. 32 2>> Yes 254 10>>-SI-1301-17 B9. 11 10>> Yes 25>o 10>>-SI-1301-18 B9.11 10>> Yes 25~o 10>>-SI-1301-20 B9.11 1Q>> Yes 254 10>>-SI-1301-21 B9.11 10>> Yes 25~o 8>>-RHR-1301-1 B9.11 8>> Yes TE 8>>-RHR-1301-3 B9.11 8>> Yes TE 038 10>>-SI-1302-1 B9. 11 10>> Yes TE 10>>-SI-1302-4 B9. 11 1P>> Yes 25<
10>> SI 1302 5 B9.11 1 Q II Yes 25~o 10'I-SI-1302-14 B9.11 1P>> Yes 25>o 8>>-RHR-1302-1 B9.11 8>> Yes TE 8>>-RHR-1302-2 B9.11 8>> Yes 25%
TE Terminal End 25 254 Additional Welds HS High Stress LS Longitudinal Weld 71
,r
'i d
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix C Table C-3 Turkey Point, Unit 3 Category B-J Welds Selected for Examination Examined Third Zone Weld Identification Code Size During Interval Number Item Second Selection Interval Criteria 039 8>>-RHR-1305-2A B9. 11 8 Yes 25%
8>>-RHR-1305-3 B9. 11 8 II Yes 25~o 8>>-RHR-1304-8 B9. 11 8 II Yes 25~o 10>>-RHR-1303-16 B9.11 1P>> Yes 2 5~o 10>>-RHR-1303-5 B9.11 1 P 'll Yes 25<o 10>>-RHR-1303-8 B9.11 1P>> Yes 25<o 10>>-RHR-1303-8-LS1 B9.12 10>> Yes LS 10>>-RHR-1303-8-LS2 B9.12 10>> Yes LS 10"-RHR-1303-10-LS1 B9.12 1P>> Yes LS 10>>-RHR-1303-10-LS2 B9.12 10 Yes LS 10>>-RHR-1303-FW-ll B9.11 1 P ll Yes TE 10>>-RHR-1303-FW13 B9.11 1P>> Yes 25>
10>>-RHR-1303-FW14 B9.11 1P>> Yes 254 10>>-RHR-1303-FW15 B9.11 1P>> Yes TE 040 2>>-SI-1301-1 B9. 40 2 II Yes TE 2>>-SI-1301-2 B9.40 2>> Yes 25>o 2>>-SI-1301-3 B9.40 2 II Yes 25~o 2>>-SI-1301-4 B9.40 2 II Yes 25<
2>>-SI-1301-5 B9.40 2>> Yes 254 2>>-SI-1301-16 B9.40 2>> Yes 25~o 2>>-SI-1301-25 B9.40 2 II Yes 25~o 2>>-SI-1301-26 B9.40 2>> Yes 25~o 041 2>>-SI-1302-2 B9.40 2!l Yes 25>o 2>>-SI-1302-6 B9.40 2>> Yes 254 2>>-SI-1302-7 B9.40 2>> Yes 2 5~o 2>>-SI-1302-14 B9.40 2 II Yes 25>
2>>-SI-1302-22 B9.40 2 II Yes 25>o 2>>-SI-1302-26 B9.40 2>> Yes 25~o 2>>-SI-1302-28 B9.40 2>> Yes 25<
TE Terminal End 25 254 Additional Welds HS High Stress LS Longitudinal Weld 72
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix C Table C-3 Turkey Point Unit 3 Category B-J Welds Selected for Examination Examined Third Zone Weld Identification Code Size During Interval Number Item Second Selection Interval Criteria 042 2>>-SI-1303-1 B9. 40 2>> Yes 25~a 2>>-SI-1303-2 B9. 40 2lt Yes 25>
2>>-SI-1303-6 B9. 40 2 II Yes 25~o 2>>-SI-1303-7 B9. 40 2 It Yes 25~o 2>>-SI-1303-8 B9. 40 2>> Yes 25~o 2>>-SI-1303-10 B9. 40 2>> Yes 25>o 2>>-SI-1303-21 B9. 40 2 It Yes 25<o 2>>-SI-1303-26 B9. 40 2>> Yes 254 043 2>>-SI-1305-4 B9. 40 2>> Yes 25>
2>>-SI-1305-5 B9. 40 2>> Yes 25%
2>>-SI-1305-6 B9. 40 2>> Yes 25>o 2>>-SI-1305-7 B9. 40 2>> Yes 25%
2>>-SI-1305-8 B9. 40 2 II Yes 25<a 2t'-SI-1305-9 B9. 40 2>> Yes 25%
2>>-SI-1305-21 B9. 40 2>> Yes 25~o 2>>-SI-1305-22 B9. 40 2 lt Yes 25~a 2>>-SI-1305-23 B9. 40 2 Il Yes 25<
2>>-SI-1305-24 B9. 40 2 II Yes 25%'5%
2>>-SI-1305-25 B9. 40 2 II Yes 2>>-SI-1305-27 B9. 40 2>> Yes 25~o 2>>-SI-1305-28 B9. 40 2 II Yes 25~a 2>>-SI-1305-29 B9. 40 2>> Yes 25~o 044 2>>-SI-1306-6 B9. 40 2 II Yes 25~o 2>>-SI-1306-26 B9. 40 2>> Yes 25~o 2>>-SI-1306-31 B9. 40 2 II Yes 25%
2>>-SI-1306-34 B9. 40 2>> Yes 25'o TE Terminal End 25 25: Additional Welds HS High Stress LS Longitudinal Weld 73
P lt K P l
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix C Table C-3 Turkey Point Unit 3 Category B-J Welds Selected for Examination Examined Third Zone Weld Identification Code Size During Interval Number Item Second Selection Interval Criteria 045 3'I-CH-1301-9 B9. 21 3>> Yes 254 3>>-CH-1301-15 B9. 21 3>> Yes HS 3>>-CH-1301-16 B9. 21 3 II Yes HS 3>>-CH-1301-18 B9. 21 3>> Yes HS 3>>-CH-1301-28 B9.21 3 II Yes HS 3>>-CH-1301-41 B9.21 3 II Yes TE 3>>-CH-1301-42 B9.21 3 II Yes 254 3>>-CH-1301-43 B9.21 3 II Yes 25>
3>>-CH-1301-44 B9.21 3 II Yes 254 3>>-CH-1301-45 B9.21 3>> Yes TE 046 3>>-CH-1302-2 B9. 21 3>> Yes HS 3>>-CH-1302-23 B9. 21 3 II Yes 25~o 3>>-CH-1302-24 B9. 21 3>> Yes 25~a 3>>-CH-1302-29 B9. 21 3>> Yes 25>o 047 3>>-CH-1303-1 B9. 21 3 II Yes TE 3>>-CH-1303-4 B9. 21 3 II Yes 254 3'I-CH-1303-9 B9. 21 3 II Yes 25<
3'I-CH-1303-10 B9. 21 3>> Yes 25~o 3'I-CH-1303-23 B9. 21 3>> Yes TE 048 2>>-CH-1301-1 B9.40 2 Yes TE 2>>-CH-1301-2 B9.40 2 II Yes 25%
2>>-CH-1301-3 B9.40 2>> Yes 2 5~o 2>>-CH-1301-4 B9.40 2 II Yes 25~o 2>>-CH-1301-5 B9.40 2>> Yes 25<
2>>-CH-1301-6 B9.40 2>> Yes TE 2>>-CH-1301-7 B9.40 2 II Yes TE 2>>-CH-1301-18 B9.40 2>> Yes TE TE Terminal End 25 25% Additional Welds HS High Stress LS Longitudinal Weld
so 0
4
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix C Table C-3 Turkey Point Unit 3 Category B-J Welds Selected for Examination Examined Third Zone Weld Identification Code Size During Interval Number Item Second Selection Interval Criteria 049 2>>-CH-1302-1 B9. 40 2>> Yes TE 2>>-CH-1302-10 B9. 40 2>> Yes 25~o 2>>-CH-1302-11 B9. 40 2>> Yes 254 2>>-CH-1302-14 B9. 40 2 ll Yes 25~o 2>>-CH-1302-28 B9. 40 2 II Yes 25<o 2>>-CH-1302-29 B9. 40 21I Yes 25>o 2>>-CH-1302-34 B9. 40 2 II Yes 25<
2>>-CH-1302-35 B9.40 2 II Yes 25%
050 l. 5>>-CH-1301-1 B9.40 1.5>>
1.5>>
No TE 1 5>>-CH-1301-2 B9.40 Yes 25%
2>>-CH-1303-1 B9.40 2 II Yes 25%
2>>-CH-1303-2 B9.40 2>> Yes 25%
2>>-CH-1303-3 B9.40 2>> Yes 25%
2>>-CH-1303-5 B9.40 2>> Yes 25%
2>>-CH-13 03-6 B9.40 2>> Yes 254 051 1 5>>-CH-1302-4 B9.40 5>> No TE 2>>-CH-1304-2 B9.40 2 lI Yes 25~o 2>>-CH-1304-3 B9.40 2>> Yes 254 2>>-CH-1304-4 B9.40 2 Il Yes 25%
2>>-CH-1304-5 B9.40 2>> Yes 25<a 2>>-CH-1304-6 B9.40 2>> Yes 254 052 1 5>>-CH-1303-4 B9.40 1.5>> No TE 2>>-CH-1305-1 B9.40 2>> Yes 25>o 2>>-CH-1305-2 B9.40 2>> Yes 25~o 2>>-CH-1305-3 B9.40 2>> Yes 25~o 2>>-CH-1305-4 B9.40 2 Il Yes 25%
TE Terminal End 25 25% Additional Welds HS High Stress LS Longitudinal Weld 75
g~ ~ I ( t Turkey Point XSX Program Revision 0 Date: August 27, 1993 Appendix C Table C-4 Turkey Point Unit 4 B-Z Piping Weld Summary Zone Sys. B9.11 B9.12 B9.21 B9.31 B9.32 B9.40 007 RCS 008 RCS 009 RCS 010 RCS 011 RCS 012 RCS 013 RCS 014 RCS 015 RCS 016 RCS 017 RCS 018 RCS 019 RCS 020 RCS 30 0 021 RCS 27 022 RCS 026 RCS 027 RCS 028 RCS 035 RCS 30 036 16 037 30 038 24 039 RHR 19 76
- 9) a,) 4> 4 "*- ~
~ gd
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix C Table C-4 Turkey Point Unit 4 B-J Piping Weld Summary Zone Sys. B9.11 B9.12 B9.21 B9. 31 B9.32 B9.40 040 HPSI 34 041 HPSI 38 042 HPSI 25 043 HPSI 38 044 HPSI 45, 045 CVCS 38 046 CVCS 45 047 CVCS 24 048 CVCS 16 049 CVCS 29 050 CVCS 35 051 CVCS 39 052 CVCS 43 059 CVCS Totals 221 138 16 399 77
I s g g~ f I 4 l b b t U ~ 'Jk
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix C Table C-5 Turkey Point Unit 4 Class 1 Non-Exempt B-J Piping Welds by Code Item Number and Size Size B9. 11 B9. 12 B9. 21 B9. 31 B9. 32 B9. 40 Tot Sch Tot Sch Tot Sch Tot Sch Tot Sch Tot Sch 3 1 II 15 6 0 0 0 29" 0 0 0 27.5 0 0 0 14 II 17 8 0 0 0 12" 0 0 0 10II 55 17 3 0 0 8 II 21 6 0 0 0 4 II 93 25 1 0 0 3 II 0 157 35 0 7 0 2 II ll 3 0 21 8 391 98 5 II 0 0 0 Total 224 72 0 168 38 4 28 8 399 101 Totals (not including B9.12, longitudinal seams)
B-J welds 782 Scheduled 222
% scheduled 222/782 = 28.44 78
~ % . ~ pp P
0
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix C Table C-6 Turkey Point Unit 4 Category B-Z Welds Selected for Examination Examined Third Zone Weld Code Size During Interval Number Item Second Selection Interval Criteria 007 31>>-RCS-1401-8 B9. 11 31>> Yes 25%
31>>-RCS-1401-10 B9. 11 31>> No TE 31>>-RCS-1401-16 B9.32 2 II Yes TE 31>>-RCS-1401-23 B9.21 3 II Yes 25>o 008 29>> -RCS-14 04-2 B9.11 29>> Yes 254 29>>-RCS-1404-17 B9.32 2>> No HS 009 27. 5>>-RCS-1407-11 B9. 11 27.5>> No TE 27 5 I'CS 14 07 12 B9.11 27.5 Yes 2S<o 27.5>>-RCS-1407-20 B9.31 10>> Yes 2 5<o 27.5>>-RCS-1407-25 B9.40 2 II Yes 25~o 010 31>>-RCS-1402-6 B9.11 31>> Yes 25<
31>>-RCS-1402-10 B9.11 31>> Yes TE 31>>-RCS-1402-19 B9.32 2 II Yes 25~o 31>>-RCS-1402-23 B9.21 3 II Yes 25~o 31>>-RCS-1402-24 B9.21 3>> Yes 25>o 012 27.5>>-RCS-1406-11 B9.11 27.5>> No TE 27.5>>-RCS-1406-BC-17 B9.32 2>> Yes 25<
27 5>>-RCS-1406-18 B9.31 1 0 lf Yes 25>
27.5>>-RCS-1406-26 B9.40 2 II Yes 25%
013 3 1>>-RCS-14 03-8 B9. 11 3 llf Yes 254 31>>-RCS-1403-10 B9.11 31>> No TE 31>>-RCS-1403-24 B9.21 3>> Yes 25>o 015 27 5>>-RCS-1409-11 B9.11 27.5 Yes TE 27.5>>-RCS-1409-12 B9.11 27.5 Yes 25>o 27.5>>-RCS-1409-15 B9.32 2>> Yes 25%
27 5>>-RCS-1409-BC-16 B9.31 4>> Yes 25~o 27.5>>-RCS-1409-BC-17 B9.31 10>> Yes 25~o 27.5>>-RCS-1409-22 B9.40 21f Yes 25~o HS High Stress Weld TE Terminal End Weld 25 25% Additional Welds SD Structural Discontinuity 79
I 4
~ J
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix C Table C-6 Turkey Point Unit 4 Category B-J Welds Selected for Examination Examined Third Zone Weld Code Size During Interval Number Item Second Selection Interval Criteria 016 14<<-RC-1401-1A B9. 11 14<< No TE 12<<-RC-1401-1 B9. 11 12<< Yes 25%
12<<-RC-1401-2 B9. 11 12<< Yes 25<o 12<<-RC-1401-3 B9. 11 12<< Yes 254 12<<-RC-1401-4 B9. 11 1 2 II Yes 25l; 017 41'-RC-14 01-5 B9. 11 4 II Yes 254 4<<-RC-1401-9 B9. 11 4<< Yes 25~o 018 4<<-RC-1402-2 B9. 11 4 Il Yes 4<<-RC-1402-5 B9. 11 4<< Yes 019 4 <<-RC-1403-2 B9.11 4<< Yes 4<<-RC-1403-5 B9.11 4<< Yes 020 4<<-RC-1404-1 B9. 11 4 II Yes 25>
4<<-RC-1404-4 B9.11 4 II Yes 25<
4<<-RC-1404-10 B9.11 4<< Yes 25>o 4<<-RC-1404-FW-12 B9.11 4 II Yes 25%
4<<-RC-1404-FW-14 B9.11 4 II Yes 25>o 4<<-RC-1404-19 B9.11 4 11 Yes 25~o 4<<-RC-1404-22 B9.11 4<< Yes 25%
4 il -RC- 14 04-28 B9.11 4 II Yes 25~o 021 4<<-RC-1405-1 B9.11 4 II Yes 254 4<<-RC-1404-3 B9.11 4 II Yes 25<
4<<-RC-1404-4 B9.11 4 II Yes 25~o 4i'-RC-1404-FW-11 B9.11 4 II Yes 25~o 4<<-RC-1404-FW-15 B9.11 4 II Yes 25>
4<<-RC-1404-17 B9.11 4 11 Yes 25~o 4<<-Rc-1404-21 B9.11 4<< Yes 25~o 4<<-RC-1404-27 B9.11 4 II Yes 25>o HS High Stress Weld TE Terminal End Weld 25 25~ Additional Welds SD Structural Discontinuity 80
ll 1 I ~w. hei '
6 ~ I
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix C Table C-6 Turkey Point Unit 4 Category B-J Welds Selected for Examination Examined Third Zone Weld Code Size During Interval Number Item Second Selection Interval Criteria 022 4>>-RC-1406-1 B9. 11 4>> Yes 25'5%
4>>-RC-1406-8 B9. 11 4>> Yes 4>>-RC-1406-9 B9. 11 4>> Yes HS 3>>-RC-1404-1 B9. 21 3>> Yes HS 3>>-RC-1405-4 B9. 21 3 II Yes 25~o 3>>-RC-1405-5 B9. 21 3 fl Yes 254 026 2>>-RC-1401-3 B9.40 2>> Yes 25~o 2>>-RC-1401-5 B9.40 2>> Yes 254 027 2>>-RC-1402-1 B9.40 2>> Yes 25%
028 2>>-RC-14 03-1 B9.40 2>> Yes 25 2>>-RC-14 03-3 B9.40 2 II Yes 254 2>>-RC-1403-4 B9.40 2 II Yes 25%
2>>-RC-1403-5 B9.40 2>> Yes 254 035 2>>-RC-1410-7 B9.40 2>> Yes 25~o 2>>-RC-1410-24 B9.40 2>> Yes 25%
2>>-RC-1410-25 B9.40 2 II Yes 254 2>>-RC-1410-33 B9.40 2 fl Yes 254 2>>-RC-1410-34 B9.40 2>> Yes 254 036 14>>-RHR-1401-1 B9. 11 14>> Yes TE 14>>-RHR-1401-5 B9. 11 14>> Yes 25<
14>>-RHR-1401-6 B9. 11 14>> Yes 25~o 14>>-RHR-1401-7 B9. 11 14>> Yes 2 5~o 14>>-RHR-1401-9 B9. 11 14>> Yes 25%
14>>-RHR-1401-13 B9. 11 14>> Yes 254 14>>-RHR-1401-16 B9. 11 14>> Yes 25>o HS High Stress Weld TE Terminal End Weld 25 25% Additional Welds SD Structural Discontinuity 81
II 0
t 'll I
ll
Revision 0 Date: August 27, 1993 Appendix C Table C-6 Turkey Point Unit 4 Category B-J Welds Selected for Examination Examined Third Zone Weld Code Size During Interval Number Item Second Selection Interval Criteria 037 8>> -RHR-14 0 1-3 B9. 11 8 II Yes 25~o 8>> -RHR-14 0 1-6 B9. 11 8>> Yes 25~o 8'I-RHR-14 01-10 B9. 11 8 II Yes 25<
10>>-RHR-1401-5 B9. 11 10>> Yes 25~o 10>>-RHR-1401-11 B9. 11 10>> Yes 25%
10>>-RHR-1401-12-BC B9.32 2>> Yes HS 10>>-RHR-'1401-14 B9.11 1P>> Yes 25~o 10>>-RHR-1401-17A B9.11 1P>> Yes 25~o 10>>-RHR-1401-18 B9.11 1P>> Yes TE 038 10>>-SI-1402-1 B9. 11 10>> Yes 25~o 10>>-SI-1402-4 B9.11 1Q>> Yes 25~o 10>>-SI-1402-8 B9.11 1P>> Yes 25~o 10'I-SI-1402-BC-12 B9.32 2 II Yes 25~o 10>>-SI-1402-13 B9.11 1P>> Yes 25%
10>>-SI-1402-17 B9.11 1P>> Yes TE 8>>-RHR-1402-4 B9.11 8>> Yes 254 8>>-RHR-1402-7 B9.11 8>> Yes 25~o 039 8>> -RHR-14 04-2 B9. 11 8 Yes 25~o 10'I-SI-1403-1 B9. 11 1P>> Yes 25~o 10>>-SI-1403-4 B9. 11 1P>> Yes 25~o 10>>-SI-1403-6 B9. 11 10>> Yes 25~o 10>>-SI-1403-8 B9. 11 1 P II Yes 25~o 10>>-SI-1403-12-BC B9.32 2>> No HS 10>>-SI-1403-14 B9.11 1 p II Yes 25>o 10>>-SI-1403-15 B9.11 1P>> Yes 25~o 10>>-SI-1403-17 B9.11 1Q>> Yes TE HS High Stress Weld TE Terminal End Weld 25 25% Additional Welds SD Structural Discontinuity 82
k4' %kilt'h s8 lf l N I
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix C Table C-6 Turkey Point Unit 4 Category B-J Welds Selected for Examination Examined Third Zone Weld Code Size During Interval Number Item Second Selection Interval Criteria 040 2'I-SI-1401-3 B9. 40 2 II Yes 25<
2'I-SI-1401-6 B9. 40 2 II Yes 254 2'I-SI-1401-14 B9.40 2 II Yes 25~o 2"-SI-1401-22 B9.40 2 II Yes 25%
2'I-SI-1401-25 B9.40 2 II Yes 25>
2II SI 1401 26 B9.40 2 II Yes 254 2"-SI-1401-30 B9.40 2 II Yes 254 2'I-SI-1401-31 B9.40 2 II No HS & TE 041 2"-SI-1402-8 B9. 40 2 II Yes 25~o 2"-SI-1402-11 B9. 40 2 II Yes 254 2"-SI-1402-20 B9. 40 2 II Yes 254 2"-SI-1402-29 B9.40 2 II Yes 254 2"-SI-1402-32 B9.40 2 II Yes 254 2"-SI-1402-35 B9.40 2 II Yes 254 2"-SI-1402-37 B9.40 2 II Yes TE 042 2"-SI-1403-2 B9.40 2 II Yes 25%
2"-SI-1403-8 B9.40 2 II Yes 25<
2"-SI-1403-9 B9.40 2 II Yes 25~o 2"-SI-1403-12 B9.40 2 II Yes 25>o 2"-SI-1403-16 B9.40 2 II Yes 254 2"-SI-1403-17 B9.40 2 II Yes 25~o 2"-SI-1403-23 B9.40 2 II Yes 2 5~o 2'I-SI-1403-25 B9.40 2 II No HS 043 2"-SI-1405-4 B9. 40 2 II Yes 25<
2"-SI-1405-6 B9. 40 2 II Yes 25~o 2"-SI-1405-20 B9.40 2 II Yes 25<
2I'-SI-1404-2 B9.40 2 It Yes 25>o 2"-SI-1404-6 B9.40 2 II Yes 25%
2"-SI-1404-10 B9.40 2 II Yes HS & TE HS High Stress Weld TE Terminal End Weld 25 25% Additional Welds SD Structural Discontinuity 83
a ~ I4 I I
'I
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix C Table C-6 Turkey Point Unit 4 Category B-J Welds Selected for Examination Examined Third Zone Weld Code Size During Interval Number Item Second Selection Interval Criteria 044 2>>-SI-1406-3 b9.40 2 fl Yes 25>o 2>>-SI-1406-9 B9.40 211 Yes 25~o 2>>-SI-1406-10 B9.40 2 II Yes 25~o 2>>-SI-1406-16 B9.40 2 lf Yes 25>o 2>>-SI-1406-17 B9.40 2 II Yes 25>o 2>>-SI-1406-21 B9.40 2 II Yes 254 211 SI 1406 25 B9.40 2 II Yes 25'5~o 2>>-SI-1406-33 B9.40 2 II Yes 2>>-SI-1406-39 B9.40 2 II Yes 25>o 2>>-SI-1406-40 B9.40 2 11 Yes 25>o 2>>-SI-1406-48 B9.40 2 II Yes TE 045 3>>-CH-1401-4 B9. 21 3 II Yes 25>o 3>>-CH-1401-14 B9. 21 3 II Yes 25>
3>>-CH-1401-15 B9. 21 3>> Yes 254 31'-CH-1401-31 B9. 21 3 II Yes 254'5>o 3>>-CH-1401-32 B9. 21 3>> Yes 3>>-CH-1401-33 B9. 21 3 II Yes 254 3>>-CH-1401-34 B9. 21 3 II Yes 25>o 3>>-CH-1401-35 B9. 21 3>> Yes 25~o 3>>-CH-1401-36 B9. 21 3 ll Yes 25%
3>>-CH-1401-37 B9. 21 3 II Yes TE 046 3 I'-CH-1402-11 B9. 21 3 ll Yes 2 5~o 3>>-CH-1402-15 B9. 21 3 It Yes 25<
31'-CH-1402-16 B9. 21 3 II Yes 25%
3>>-CH-1402-34 B9.21 3 ll Yes 25>o 3 -CH-1402-35 11 B9.21 3 fl Yes 25<o 3'I-CH-1402-38 B9.21 3>> Yes 25~o 3>>-CH-1402-39 B9.21 3 11 Yes 25>o 3>>-CH-1402-40 B9.21 3 Il Yes 25<
3>>-CH-1402-41 B9.21 3 Il Yes 254 3>>-CH-1402-42 B9.21 3 II Yes 25~o 3>>-CH-1402-4 B9.21 3 11 Yes TE HS High Stress Weld TE Terminal End Weld 25 25% Additional Welds SD Structural Discontinuity 84
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix C Table C-6 Turkey Point Unit 4 Category B-J Welds Selected for Examination Examined Third Zone Weld Code Size During Interval Number Item Second Selection Interval Criteria 047 3"-CH-1403-1 B9. 21 3 II Yes 25l; 3"-CH-1403-5 B9. 21 3 II Yes 254 3"-CH-1403-7 B9. 21 3 II Yes 25~0 3"-CH-1403-9 B9. 21 3 II Yes 254 3"-CH-1403-10 B9. 21 3 II Yes 254 3II-CH-1403-11 B9. 21 3 II Yes 254 3"-CH-1403-12 B9. 21 3 II Yes 254 048 2"-CH-1401-1 B9. 21 2 ll Yes TE 2"-CH-1401-4 B9.40 2 II Yes 25>
2"-CH-1401-5 B9.40 2 II Yes 254 049 2"-CH-1402-15 B9. 40 2 II Yes 254 2"-CH-1402-20 B9. 40 2 II Yes 25%
2"-CH-1402-21 B9. 40 2 II Yes 25>
2"-CH-1402-22 B9. 40 2 ll Yes 25<0 2"-CH-1402-25 B9. 40 2 II Yes 25>o 2"-CH-1402-26 B9. 40 2 II Yes 25~o 2"-CH-1402-27 B9. 40 2 II Yes 25>o 2"-CH-1402-28 B9. 40 2 II Yes 25~
050 2"-CH-1403-4 B9. 40 2 II Yes 254 2'I-CH-1403-5 B9. 40 2 II Yes 25%'5~0 2"-CH-1403-6 B9. 40 2 II Yes 2"-CH-1403-14 B9. 40 2 II Yes 25~o 2"-CH-1403-26 B9. 40 2 II Yes 25~0 2"-CH-1403-27 B9. 40 2 II Yes 25~o 2"-CH-1403-28 B9. 40 2 II Yes 25<
2"-CH-1403-29 B9. 40 2 II Yes 25~0 1.5"-CH-1401-4 B9. 40 5 II Yes 25~o HS High Stress Weld TE Terminal End Weld 25 25% Additional Welds SD Structural Discontinuity 85
I ~ ~ J ~ II If 1,/ l '$,. 1, 0
h ,
~ gl
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix C Table C-6 Turkey Point Unit 4 Category B-J Welds Selected for Examination Examined Third Zone Weld Code Size During Interval Number Item Second Selection Interval Criteria 051 2>>-CH-1404-18 B9. 40 2>> Yes 25>
2>>-CH-1404-28 B9. 40 2>> Yes 254 2>>-CH-1404-30 B9. 40 2 II Yes 25>o 2>>-CH-1404-31 B9. 40 2>> Yes 25~0 2>>-CH-1404-32 B9. 40 2>> Yes 254 2>>-CH-1404-33 B9. 40 2>> Yes 254 2>>-CH-1404-34 B9. 40 2>> Yes 254 2>>-CH-1404-35 B9. 40 2>> Yes 25~0 2>>-CH-1404-36 B9. 40 2 II Yes 25>o 2>>-CH-1404-37 B9. 40 2>> Yes 25>o 2>>-CH-1404-37A B9.40 2 II Yes 25<
1 5>>-CH-1402-1 B9.40 5>> Yes 25%'5>o 052 2>>-CH-1405-9 B9.40 2>> Yes 2>>-CH-1405-28 B9.40 2>> Yes 25<
2>>-CH-1405-30 B9.40 2>> Yes 25%
2>>-CH-1405-31 B9.40 2>> Yes 254 2>>-CH-1405-32 B9.40 2>> Yes 254 2>>-CH-1405-34 B9.40 2>> Yes 25<
2>>-CH-1405-36 B9.40 2 II Yes 25%
2>>-CH-1405-40 B9.40 2>> Yes 25~o 1.5>>-CH-1403-2 B9.40 1. 5>> Yes 25%
HS High Stress Weld TE Terminal End Weld 25 25< Additional Welds SD Structural Discontinuity 86
'h I ll~ il lt, ~
~~sT k <
u 1 g $ @~fan I
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix D Table D-1 Turkey Point Unit 3 C-F-1 Non-exempt Piping Welds Summary by Zone, System, and Code Item Number Zone Syst: em C5. 11 C5. 12 C5. 21 C5. 30 C5. 41 063 24 18 064 RHR 12 065 17 066 13 067 18 068 15 069 RHR 37 081 18 084 085 13 086 089 21 090 SI 095 HPSI 70 49 096 HPSI 70 48 Totals 210 28 140 97 87
a c
~ 'I 'I" ~ " i h
~ I>>"
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix D Table D-2 Turkey Point Unit 3 C-F-1 Non-exempt Piping Welds by Code Item Number and Size NPS C5. 11 C5. 12 C5. 21 C5. 30 C5.41 Tot Sch Tot Sch Tot Sch Tot Sch Tot Sch 14 II 84 25 22 18 12 II 52 10" 18 8" 52 6II 4 It 86 10 3tt 2 It 97 Totals 210 42 28 21 140 18 97 Note: Total Welds selected for Examination is based on adding non-exempt circumferential welds in this table to the exempt circumferential welds and multiplying by 7.54.
Non-Ex 454 (Not counting C5.12)
Exempt + 231 Total = 685 x 7.5% = 52 welds minimum 88
~ P Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix D Table D-3 Turkey Point Unit 3 C-F-1 Non-Exempt Piping Examination Distribution
% Non-Number Non- Number Zone Term Struct Exempt to be Branch Exempt to be End Dis. fields in Exam'd Conn. in Exam'd Zone Zone 63 1-14" 23-14 5. 5~o 3-14 64 1-14 10-14 2.54 14 ((
65 17-14 3.9w 0-14" 66 11-14" 2.5> 3-14" 67 18-14 4.1% 2-14 68 14-12 3.24 2-12 69 6(l 8.3C 4-12" 34-12" 81 18-10" 4. 1% 2-10" 84 6-8" 1. 4~o 8 II 85 10-8 2 ~ 3~o 8(l 86 3 8(I 0.7% 0-8" 89 21-8" 4.84 4 8 90 4-8 0. 9~o 8 ll 95 6(l 6 II 28. 3~o 6(l 2 ll 25%
2(l 64-4" 8-4 52-2 5 2(l 96 3 3(l 16-4" 27 F 14 4 II 3 2(l 75<
47-3 8 3(l 52-2 (( 6-2" Tot 10 425 54 Note: Totals do not include pipe to pipe welds or those selected under SRP 6.6.
89
~ f '
'I W
N
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix D Table D-4 Turkey Point Unit 3 C-F-1 Non-Exempt Welds Selected for Examination Selected Third Zone Weld Code Size During Interval Identification Item Second Selection Interval Criteria 63 14>>-RHR-2301-1 C5.11 14>> Yes SRP 6. 6 14>>-RHR-2301-1LS1 C5.12 14>> Yes SRP 6. 6 14'I-RHR-2301-lLS2 C5.12 14>> Yes SRP 6. 6 14'I-RHR-2301-2 C5.11 14>> Yes SRP 6. 6 14>>-RHR-2301-2LS1 C5.12 14>> Yes SRP 6. 6 14>> RHR 2301 2LS2 C5.12 14>> Yes SRP 6. 6 14>> RHR 2301 3 C5.11 14>> Yes SRP 6. 6 14>>-2301-RHR-3LS1 C5.12 14>> Yes SRP 6. 6 14>>-RHR-2301-3LS2 C5.12 14>> Yes SRP 6. 6 14>> RHR 2301 4 C5.11 14>> Yes SRP 6. 6 14>>-RHR-2301-4LS1 C5.12 14>> Yes SRP 6. 6 14>>-RHR-2301-4LS2 C5.12 14>> Yes SRP 6. 6 14>>-RHR-2301-4LS1 C5.12 14>> Yes SRP 6. 6 14"-RHR-2301-4LS2 C5.12 14>> Yes SRP 6. 6 14>> RHR 2301 5 C5.11 14>> Yes SRP 6. 6 14>>-RHR-2301-5LS1 C5.12 14>> Yes SRP 6. 6 14>>-RHR-2301-5LS2 C5.12 14>> Yes SRP 6. 6 14>>-RHR-2301-6 C5.11 14>> Yes SRP 6. 6 14>>-RHR-2301-6LS1 C5.12 14>> Yes SRP 6. 6 14>>-RHR-2301-6LS2 C5.12 14>> Yes SRP 6.6 14>> RHR 2301 7 C5.11 14>> Yes SRP 6. 6 14>>-RHR-2301-8 C5.11 14 Yes SRP 6. 6 14>> RHR 2301 9 C5.11 14>> Yes SRP 6. 6 14'I-RHR-2301-9LS C5.12 14>> Yes SRP 6. 6 14'I-RHR-2301-10 C5.11 14>> Yes SRP 6. 6 14>>-RHR-2301-11 C5.11 14>> Yes SRP 6. 6 14>>-RHR-2301-11LS C5.12 14>> Yes SRP 6.6 14>>-RHR-2301-12 C5.11 14>> Yes SRP 6. 6 & HS 14>>-RHR-2302-18 C5.11 14>> Yes SD 14'I-RHR-2302-19 C5.11 14>> Yes SD 14>> RHR 2302 24 C5.11 14>> Yes SD TE Terminal End 25 25% Additional Welds HS High Stress Weld SD Structural Discontinuity LS Longitudinal Seam 90
I
w.g$ gg,p~gh
~ as w ~ ~ ~ II H
'J t
R, ll 4
P k
cy e
,r A
J I
E'I
,j ~ ~ 6-y
't II l
'P r p N I g~t, A+XX'y'
\'.
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix D Table D-4 Turkey Point Unit 3 C-F-1 Non-Exempt Welds Selected for Examination Selected Third Zone Weld Code Size During Interval Identification Item Second Selection Interval Criteria 64 14>>-RHR-2303-1 C5. 11 14>> Yes SRP 6. 6 14>>-RHR-2303-1LS C5. 12 14>> Yes SRP 6. 6 14>>-RHR-2303-2 C5. 11 14>> Yes SRP 6. 6 14>>-RHR-2302-2A C5. 11 14>> Yes SRP 6. 6 14>>-RHR-2303-3LS C5. 12 14>> Yes SRP 6. 6 14>>-RHR-2303-4 C5. 11 14>> Yes SRP 6. 6 14>>-RHR-2303-11 C5. 11 14>> Yes SD 66 14>>-RHR-2305-3 C5.11 14>> Yes SD 14>>-RHR-2305-10 C5.11 14>> Yes SD 14>>-RHR-2305-11 C5.11 14>> Yes SD 67 14>>-RHR-2306-1 C5. 11 14>> Yes TE 14>>-RHR-2306-4 C5.11 14>> Yes SD 68 12>>-RHR-2301-1 C5.11 12 fl Yes SD 12>>-RHR-2301-10 C5.11 12>> Yes SD 69 12>>-RHR-2302-1 C5. 11 12>> Yes SD 12>>-RHR-2302-4 C5. 11 12>> Yes SD 12>>-RHR-2302-8 C5. 11 12>> Yes SD 12"-RHR-2302-23LS C5. 12 12 II Yes LS 12>>-RHR-2302-24 C5. 11 12>> Yes SD 12>>-RHR-2302-24LS C5. 12 12>> Yes LS 81 10>>-SI-2304-1LS C5. 12 10>> Yes LS 10>>-SI-2304-2 C5. 11 10>> Yes SD 10>>-SI-2304-3 C5. 11 10>> Yes SD 84 8>>-SI-2302-6 C5. 11 8>> Yes SD 8>> SI 2303 1 C5.11 8>> Yes SD TE Terminal End 25 25% Additional Welds HS High Stress Weld SD Structural Discontinuity LS Longitudinal Seam 91
~ y ~, ~
~ p
'h 3 ~ Al ~8, II W
pr g
Turkey Point XSI Program Revision 0 Date: August 27, 1993 Appendix D Table D-4 Turkey Point Unit 3 C-F-1 Non-Exempt Welds Selected for Examination Selected Third Zone Weld Code Size During Interval Xdentification Item Second Selection Xnterval Criteria 89 8>>-SI-2309-20 C5. 11 8 II Yes SD 8I'-SI-2309-21 C5.11 8>> Yes SD 8>>-SI-2309-22 C5.11 8 Yes SD 8>>-SI-2309-24 C5.11 8 Yes SD 90 8>>-SI-2308-19 C5.11 8 Yes TE 95 6>>-SI-2307-1 C5.11 6>> Yes TE 6>>-SX-2307-2 C5.11 6>> Yes SD 4>>-SI-2303-27 C5.21 4>> No SD 4>>-SI-2303-32 C5.21 4 II No SD 4>>-SI-2303-38 C5.21 4 II No SD 4>>-SI-2303-48 C5.21 ~4 II No SD 4>>-SI-2305-1 C5.21 4 II No SD 4>>-SI-2305-3 C5.21 4 II No SD 4>> SX 2305 6 C5.21 4 II No SD 4>>-SI-2305-24 C5.21 4 II No SD 2>>-SI-2306-12 C5.30 2>> No TE 2>>-SI-2307-1 C5.30 2 II No SD 2>> SX 2309 1 C5.30 2 II No TE 2>>-SI-2309-5 C5.30 2 II No SD TE Terminal End 25 25% Additional Welds HS High Stress Weld SD Structural Discontinuity LS Longitudinal Seam 92
t I i
Turkey Point ISI Program Revision 0 Date: August, 27, 1993 Appendix D Table D-4 Turkey Point Unit 3 C-F-1 Non-Exempt Welds Selected for Examination Selected Third Zone Weld Code Size During Interval Identification Item Second Selection
'Interval Criteria 96 4>>-SI-2302-13 C5. 21 4 II No SD 4>>-SI-2302-14 C5.21 4>> No SD 4>>-SI-2302-10 C5.41 2 II No TE 3>>-SI-2301-1 C5.21 3 II No TE 3>>-SI-2301-4 C5.21 3 II No SD 3>>-SI-2301-13 C5.21 3 II No SD 3>>-SI-2303-21 C5.21 3 II No SD 3 I'-SI-2303-23 C5.21 3>> No SD 3>>-SI-2303-24 C5.21 3 II No SD 3>>-SI-2303-28 C5.21 3 II No TE 3>>-SI-2304-3 C5.21 3 II No SD 2>>-SI-2302-1 C5.41 2 II No TE 2>>-SI-2302-2 C5.30 2 II No SD 2>>-SI-2304-1 C5.30 2>> No SD 2>>-SI-2304-3 C5.30 2>> No SD 2>>-SI-2304-10 C5.30 2 II No SD TE Terminal End 25 25% Additional Welds HS High Stress Weld SD Structural Discontinuity LS Longitudinal Seam 93
~ ~
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix D Table D-5 Turkey Point Unit 4 C-F-1 Non Exempt Piping Weld Summary by Zone, System, and Code Item Number Zone System C5.11 C5. 12 C5.21 C5.30 C5. 41 063 RHR 25 10 064 13 065 16 066 RHR 067 17 068 15 069 RHR 39 081 17 084 RHR 19 085 17 086 087 SIS 089 23 090 097 HPSI 139 34 098 HPSI 54 Totals 225 15 139 88 94
P II ss c l
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix D Table D-6 Turkey Point Unit 4 C-F-1 Non Exempt Piping Welds by Code Item Number and Size NPS C5. 11 C5. 12 C5. 21 C5.30 C5. 41 Tot Sch Tot Sch Tot Sch Tot Sch Tot Sch 14 II 82 27 10 10 1 2 II 54 10<t 17 8i 68 10 6"
4 II 80 3 II 59 2 II 88 Total 225 47 14 139 88 Note: Total Welds Selected for Examination is based on adding non-exempt circumferential welds in Table D-6 to the number of exempt circumferential welds and multiplying by 7.5%.
Non Ex.= 458 (Does not include C5.12 welds)
Ex. = 235 Total = 693 x 7.5% = 52 welds minimum 95
imigrd 1 ~ a e I 4 ~
5, 4 5 awd)
P I'
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix D Table D-7 Turkey Point Unit 4 C-F-1 Non-Exempt Piping Exam Distribution
% Non-Term Struct Exempt Number Branch o Non Number Zone End Dis. in to be Conn. Exempt to be Zone Exam'd in Zone Exam'd 063 1-14" 21-14" 5. 3~o 18-14" 064 1-14" 12-14" 2.84 3-14 065 16-14" 3. 9~o 3-14 066 10-14" 2.4%
067 16-14 3. 9>o 068 15-12 3.6%
069 37-12" 8. 9~o 5-12 081 17-10" 4 ~ 1~o 2-10" 084 11-8 2 ~ 7~o 2-8" 085 14-8 3. 4~o 8 II 086 8 II 8 ll 087 3 8 II <14 0-8" 089 19-8 4. 6~o 4 8 II 090 4 8 II 1 ~ 0~o 8 II 097 2 6 II 2-6" 43. 6~o 6 II 2 II 100~o 2 II 4-3" 84-4 2-4" 3-2" 55-3" 3 II 3 1-2 II 2-2" 098 2 II 48-2" 13.0% 4-2" Tot 17 417 56 Note: Pipe to Pipe welds are not counted.
96
h
~ A T 4 g a Ja
~ 1
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix D Table D-8 Turkey Point Unit 4 C-F-1 Non-Exempt Welds Selected for Examination Selected Third Zone Weld Code Size During Interval Identification Item Second Selection Interval Criteria 063 14<<-RHR-2401-1 C5. 11 14<< Yes 6.6 14<<-RHR-2401-1LS C5. 12 14 Yes 6.6 14<<-RHR-2401-2 C5. 11 14<< Yes 6.6 14<<-RHR-2401-3 C5. 11 14<< Yes 6.6 14<<-RHR-2401-3LS1 C5.12 14 << Yes 6.6 14<<-RHR-2401-3LS2 C5.12 14 << Yes 6.6 14<<-RHR-2401-4 C5.11 14<< Yes 6.6 14"-RHR-2401-4LS C5.12 14<< Yes 6.6 14<<-RHR-2401-5 C5.11 14<< Yes 6.6 14<<-RHR-2401-5LS C5.12 14 << Yes 6.6 14<<-RHR-2401-5A C5.11 14 << Yes 6.6 14<<-RHR-2401-5B C5.11 14>> Yes 6.6 14<<-RHR-2401-5BLS C5.12 14 << Yes 6.6 14<<-RHR-2401-6 C5.11 14<< Yes 6.6 14<<-RHR-2401-6LS C5.12 14<< Yes 6.6 14<<-RHR-2401-7 C5.11 14<< Yes 6.6 14<<-RHR-2401-8 C5.11 14>> Yes 6.6 14<<-RHR-2401-8LS C5.12 14>> Yes 6.6 14<<-RHR-2401-9 C5.11 14 << Yes 6.6 14<<-RHR-2401-9LS C5.12 14<< Yes 6.6 14<<-RHR-2401-10 C5.11 14<< Yes 6.6 14<<-RHR-2401-10LS C5.12 14>> Yes 6.6 14<<-RHR-2401-11 C5.11 14 << Yes 6.6 14<<-RHR-2401-12 C5.11 14<< Yes 6.6 14<<-RHR-2401-13 C5.11 14 Yes 6.6 14<<-RHR-2401-14 C5.11 14 << Yes 6.6 14>>-RHR-2401-15 C5.11 14 << Yes 6.6 063 14<<-RHR-2402-8 C5. 11 14<< Yes SD 064 14 <<-RHR-24 03-1 C5.11 14<< Yes SD/6. 6 14<<-RHR-2403-2 C5.11 14 II Yes SD/6. 6 14<<-RHR-2403-4 C5.11 14 << Yes SD/6. 6 TE Terminal End 25 25+o Additional Welds HS High Stress SD Structural Discontinuity LS Longitudinal Seam 6.6 Standard Review Plan 6.6 97
s
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix D Table D-8 Turkey Point Unit 4 C-F-1 Non-Exempt Welds Selected for Examination Selected Third Zone Weld
- Code Size During Interval Identification Item Second Selection Interval Criteria 065 14>>-RHR-24 04-15 C5. 11 14>> Yes 6.6 14'I RHR 2404 16 C5. 11 14 n Yes 6.6 14>>-RHR-2404-17 C5. 11 14 n Yes 6.6 066 14 n-RHR-24 05-10LS C5. 12 14>> Yes LS 14>> RHR 2405 11 C5. 11 14>> Yes SD 067 14>>-RHR-2406-4 C5. 11 14>> Yes SD 068 12>>-RHR-2401-2 C5.11 12>> Yes SD 069 12>>-RHR-2402-1 C5. 11 12>> Yes SD 12>>-RHR-2402-15 C5. 11 12>> Yes SD 12>>-RHR-2402-FW26 C5. 11 1 2 II Yes SD 12>>-RHR-2402-26LS C5. 12 Yes LS 12'I-RHR-2402-34 C5. 11 12>> Yes SD 10>>-RHR-2402-35 C5.11 Yes SD 081 10'I-SI-2407-4 C5. 11 10>> Yes SD 10'I-SI-2407-5 C5. 11 1 0 II Yes SD 084 8>>-SI-2402-14 C5. 11 8 II Yes SD 8>>-SI-2402-17 C5. 11 8 II Yes SD 8>>-SI-2403-16 8 II Yes 085 8I'I 2403-17 C5. 11 C5. 11 8 II Yes SD SD 086 8>>-SI-2404-2 C5. 11 8 Yes SD 089 8 n-SI-2407-1 C5. 11 8>> Yes SD 8>>-SI-2407-lA C5. 11 Sn Yes SD 8>>-SI-2407-2 C5.11 8 II Yes SD 8>>-SI-2407-8 C5.11 8'I Yes SD 090 8 n SI 2408 17 C5. 11 8>> Yes SD TE Terminal End 25 25% Additional Welds HS High Stress SD Structural Discontinuity LS Longitudinal Seam 6.6 Standard Review Plan 6.6 98
II 1 J 4 ~ % lj T h 6I h
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix D Table D-8 Turkey Point Unit 4 C-F-1 Non-Exempt Welds Selected for Examination Selected Third Zone Weld Code Size During Interval Identification Item Second Selection Interval Criteria 097 3"-SI-2401-1 C5. 21 3 II No TE 3"-SI-2401-3 C5. 41 2 II No BC 4"-SI-2401-4 C5.21 4 II No SD 4'I-SI-2401-5 C5.21 4 II No SD 2"-SI-2401-1 C5.30 2 II No TE 4 II-SI-2401-52 C5.21 4 II No SD 4"-SI-2401-53 C5.21 4 II No SD 6"-SI-2403-2 C5.11 6" Yes TE 6"-SI-2404-1 C5.11 6 II Yes TE 3"-SI-2404-3 C5.21 3 II No SD 098 2"-SI-2406-1 C5. 30 2 II No TE 2II SI 2406 2 C5.30 2 II No SD 2"-SI-2406-11 C5.30 2 II No SD 2"-SI-2406-13 C5.30 2 II No TE TE Terminal End 25 25% Additional Welds HS High Stress SD Structural Discontinuity LS Longitudinal Seam 6.6 Standard Review Plan 6.6 99
n
~ ~
1 I
i
Revision 0 Date: August 27, 1993 Appendix E Table E-1 Turkey Point Unit 3 C-F-2 Non-Exempt Piping Weld Summary Zone System C5.51 C5.52 C5.81 C5.82 Number 097 MS 12 21 098 MS 19 099 MS 15 28 100 MS 17 101 MS 18 102 MS 18 103 SGBD 22 104 SGBD 105 SGBD 29 106 SGBD 107 SGBD 108 SGBD 109 FW 29 110 FW 27 FW 30 112 FW 113 FW 114 FW Totals 285 81 12 Note: There are 9 exempt 6" welds (t(.375") included in this summary, three each in Zones 101, 102, and 103.
100
E A a li,4, g '",'pp ~
I
Revision 0 Date: August 27, 1993 Appendix E Table E-2 Turkey Point Unit 3 C-F-2 Non Exempt Piping Weld Summary by Code Item Number and Size Nominal C5.51 C5.52 C5.81 Pipe Size Total Sch Total Sch Total Sch 3 1 II 2611 46 81 10 14 II 112 13 12 II 8 II 6" 117 15 Totals 285 37 81 10 12 Totals (not including C5.52, longitudinal seams)
Non-Ex 298 Exempt + 9 Total + 307 x 7.54 = 23 Category C-F-2 requires a minimum of 28 welds. The total welds scheduled is greater than the minimum required due to augmented exams as well as size distribution criteria.
101
ft 4 ~ k
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix E Table E-3 Turkey Point Unit 3 C-F-2 Non-Exempt Piping Examination Distribution
% Non- % Non-Struct Number Branch Exempt Number Zone Term Exempt to be to be End Dis. Welds in Exam'd Conn. in Exam'd Zone Zone 097 1-31" 0 3. 9~0 1 31II 1-26 7-26" 098 1-31" 0 3.44 0 1-26" 1-26" 099 1-3 1 fl 0 5. 2~o 0 1-26" 10-26" 1-26 100 1-26" 1-26 6. 9~0 2-26 2-12" 25>o 7-14" 1-14" 6 II 4 8 II 81f 3 6 lf 0-6" 101 1-26" 2-26" 7 ~ 3~o 2 12 254 1 7-14 1-6" 1-6" 4 8 3-6 102 1-26" 2-26 7. 3>o 0 2-12" 254 7-14" 2-14" 1-6 4 8 8 ll 3 6 II 0 103 22-6 9.44 4 6 ll 104 18-6" 7 7~o 3 6 II 105 16-6" 6.94 3-6" 106 4 6 ll 1 ~ 7~o 107 8- 3. 4~o 1-6" 108 4 6 lf 1 7~o 6 II 109 11 ~ 2~o 6 II 8.3% 6 II 2-14" 21-14 2-14 110 18 1-18 10. 7>o 4-14 6 II 8. 3>o 2-14 21-14" 102
',p II N
I lj
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix E Table E-3 Turkey Point Unit 3 C-F-2 Non-Exempt Piping Examination Distribution 4 Non- 4 Non- Number Term Struct Exempt Number Branch Exempt Zone End Dis. Welds in to be Conn. in to be Exam'd Exam'd Zone Zone 1-18" 1-18 11.64 6 II 8.3%
2-14" 24-14 2-14" 112 7 6 II 3.0< 6 II 113 7 6 II 3.04 1-6 114 8-6" 3. 0<o 6 II Tot 18 233 36 12 Note: Pipe to pipe welds are not counted.
103
4 f A ~ 't I
l 0
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix E Table E-4 Turkey Point Unit 3 C-F-2 Non-Exempt Piping Welds Selected for Exam Selected Third Zone Weld Code Size During Interval Number Identification Item Second Select Interval Criteria 097 31>>-MSA-2301-1A C5.51 31>> Yes TE 26>>-MSA-2301-FW1 C5.51 26>> Yes SD 26>>-MSA-2301-1LSD C5.52 26>> Yes LS 098 26>>-MSB-2302-10 C5.51 26>> Yes SD 26>>-MSB-2302-10LSU C5.52 26>> Yes LS 26>>-MSB-2302-10LSD C5.52 26 Yes LS 26>>-MSB-2302-11 C5.51 26 Yes SD 26>>-MSB-2302-11LSU C5.52 26>> Yes LS 26>>-MSB-2302-11LSD C5.52 26>> Yes LS 099 26>>-MSC-2303-9LSU C5.52 26>> Yes LS 26>>-MSC-2303-9 C5.51 26>> Yes SD 26>>-MSC-2303-9LSD C5.52 26>> Yes LS 100 26>>-MSA-2304-13 C5.51 26>> Yes TE 26>>-MSA-2304-13LSU C5.52 26>> Yes LS 26>>-MSA-2304-13LSD C5.52 26>> Yes LS 26>>-MSA-2304-17 C5.51 26>> Yes SD 26>>-MSA-2304-17LSU C5.52 26>> Yes LS 14>>-MSA-2301-1 C5.51 14>> Yes SD 14>>-MSA-2302-2 C5.51 8>> Yes SD 101 26>>-MSB-2305-12 C5.81 6>> Yes SD 26>>-MSB-2305-13 C5.81 12>> Yes SD 26>>-MSB-2305-14 C5.81 12>> Yes SD 102 14>>-MSC-23 05-1 C5.51 14>> Yes SD 14>>-MSC-2305-5 C5.51 8>> No SD 14>>-MSC-2306-1 C5.51 14>> Yes SD 103 6>>-BDA-2301-FW1 C5.51 6>> Yes SD 6>>-BDA-2301-FW6 C5.51 6>> Yes SD 6>>-BDA-2301-FW8 C5.51 6>> Yes SD 6>>-BDA-2301-FW18 C5.51 6>> Yes SD TE Terminal End 25 25% Additional Welds HS High Stress SD- Structural Discontinuity LS Longitudinal seam 104
l 4
J'
~
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix E Table E-4 Turkey Point Unit 3 C-F-2 Non-Exempt Piping Welds Selected for Exam Selected Third Zone Weld Code Size During Interval Number Identification Item Second Select Interval Criteria 104 6>>-BDB-2302-FW1 C5.51 6>> Yes SD 6>>-BDB-2302-FW12 C5.51 6fl Yes SD 6>>-BDB-2302-FW18 C5.51 6>> Yes SD 105 6>>-BDC-2303-FW6 C5.51 6>> Yes SD 6>>-BDC-2303-FW24 C5.51 6 If Yes SD 6>>-BDC-2303-FW29 C5.51 6>> Yes SD 107 6>>-BDB-2305-FW24 C5.51 6>> Yes SD 108 6>>-BDC-2306-FW30 C5.51 6fl Yes SD 109 14>>-FWA-2301-2A C5. 81 6 II Yes SD 14>>-FWA-2301-20 C5.51 14>> Yes SD 14>>-FWA-2301-21A C5.51 18>> Yes SD 18>>-FWA-2301-FW2 C5.51 14>> Yes SD 110 14>>-FWB-2304-1 C5.51 14>> Yes SD 14>>-FWB-2304-3 C5.51 14>> Yes SD 14'I-FWB-2303-9 C5.51 14>> Yes SD 14>>-FWB-2303-17 C5.51 14>> Yes HS 14>>-FWC-2306-1 C5. 51 14>> Yes SD 14>>-FWC-2305-6 C5.51 14>> Yes SD 18>>-FWC-2305-24 C5.51 18>> Yes SD 112 6 I'-FWA-23 0 1-2 C5. 51 6 II Yes SD 113 6>>-FWB-2302-2 C5.51 6>> Yes SD 114 6>>-FWC-2303-7 C5.51 6 II Yes SD TE Terminal End 25 25% Additional Welds HS High Stress SD- Structural Discontinuity LS Longitudinal seam 105
II E
~ '
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix E Table E-5 Turkey Point Unit 4 C-F-2 Non-Exempt Piping Welds Summary Zone System C5.51 C5.52 C5.81 C5.82 Number 099 MS 10 100 MS 8 101 MS 102 MS 103 MS 14 104 MS 14 105 MS 28 106 MS 19 107 MS 21 108 MS 109 MS 110 MS FW 27 112 FW 20 113 FW 18 114 FW 0 115 116 FW FW Totals 238 34
,Exempt items ((.375") in these Zones total 18. Owing to this limited number, these items have been included in the C-F-2 selection. Since 7.54 of the welds is not greater than 28, the
- minimum number has been selected.
106
Revision 0 Date: August, 27, 1993 Appendix E Table E-6 Turkey Point Unit 4 C-F-2 Non-Exempt Piping Welds Summary by Code Item and Size Nominal Pipe C5.51 C5.52 C5. 81 Size Total Select Total Select Total Select 3 1 tl 2 6 II 35 34 18 II 14 ll 80 12 II 12 6" 98 10 12 Totals 234 23 34 18 107
'I 4 J I s Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix E Table E-7 Turkey Point Unit 4 C-F-2 Non-Exempt Piping Exam Distribution 4 Non- Number 4 Non- Number Zone Term Struct Exempt, to be Branch Exempt, to be End Dis. Welds in Exam'd Conn. in Exam'd Zone Zone 099 1-31}1 0 3.5l; 1-31" 1-26" 6-26 1-26" 100 1-31" 0 3 ~ l~o 0-31 1 2 5-26 1-26 101 1-3 1" 0 3 ~ 1~o 0-31" 1-26 5-26 1-26" 102 1-26" 2-26 8. O~o 1-26 2-12" 27.83% 2-12" 6-14" 1-14') 3 6 II 6 II 4 8 0-8" 5 6 lI 0-6" 103 1-26 2-26 8.34 1-26 2-12 27.834 1-12" 7-14" 0-14 3 61I 611 4 81I 0-8 5 61I 0-6" 104 1-26" 2-26" 8. 3% 0-26 2-12" 27.83>o 0-12" 7-14" 0-14" 3-6" 0 6ii 4-8" 0 8ii 5 6 II p 105 6 fl 25-6 11 ~ 3~o 4-6" 106 1-6" 18-6" 8.34 6 II 107 1-6" 15-6" 7. 0>o 2-6 108 5 6 II 2. 1>o 6 fl 109 4 6ll 1.74 6 II 110 4 6 If 1 '4 6 II 1-18 1-18" 10. O~o 0-18" 6 II 5. 5~o 1-6" 22-14 2-14" 112 1-18" 1-18 7.44 0-18" 1-6" 5. 5>o p 16-14 1-14 108
I Revision 0 Date: August 27, 1993 Appendix E Table E-7 Turkey Point Unit 4 C-F-2 Non-Exempt Piping Exam Distribution
> Non- Number
> Non- Number Zone Term Struct Exempt to be Branch Exempt to be End Dis. Welds in Exam'd Conn. in Exam'd Zone Zone 113 1-18 1-18" 7. 4>o 0-18 6 II 5. 5~o p 6 II 16-14 1-14" 114 6 II 2. 6~o 0-6" 115 6 II 2. 6~a p 116 7 6ll 3 14 6 II Tot 15 217 22 18 Note: Pipe to Pipe welds are not counted.
109
Ik 4
i
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix E Table E-8 Turkey Point Unit 4 C-F-2 Non Exempt Piping Welds Selected for Exam Selected Third Zone Weld Code Size During Interval Number Identification Item Second Selection Interval Criteria 099 31>>-MSA-2401-1A C5.51 31>> Yes TE 26>>-MSA-2401-8LS C5.52 26>> Yes LS 26>>-MSA-2401-9 C5.51 26>> Yes TE 26>>-MSA-2401-9LS C5.52 26>> Yes LS 100 2 6>> -MSB-24 02-7 C5.51 26>> Yes TE 26>>-MSB-2402-7LS C5.52 26>> Yes LS 101 26>>-MSC-2403-9LS C5.52 26>> Yes LS 26>>-MSC-2403-10 C5.51 26>> Yes TE 102 26>>-MSA-2404-1LU C5.52 26>> No LS 26>>-MSA-2404-1 C5.51 26>> Yes SD 26>>-MSA-2404-1LD C5.52 26>> Yes LS 26>>-MSA-2404-2 C5.81 6>> Yes BC 26>>-MSA-2404-3 C5.81 12>> Yes SD 26>>-MSA-2404-4 C5.81 12>> Yes SD 26>>-MSA-2404-5LU C5.52 26>> Yes LS 26>>-MSA-2404-5 C5.51 26>> Yes SD 14>>-MSA-2402-1 C5.51 14>> Yes BC 103 26>>-MSB-2405-1LU C5.52 26>> No LS 26>>-MSB-2405-1 C5.51 26>> Yes TE 26>>-MSB-2405-1LD C5.52 26>> Yes LS 26>>-MSB-2405-2 C5.81 Yes BC 26>>-MSB-2405-3 C5.81 12>> Yes BC 105 6>>-BDA-2401-2 C5.51 6>> Yes SD 6>>-BDA-2401-6 C5.51 6>> Yes LS 6>>-BDA-2401-9 C5.51 6>> Yes SD 6>> BDA 2401 15 C5.51 6>> Yes LS 106 6>>-BDB-2402-19 C5.51 Yes TE 107 6>> BDC 2403 2 C5.51 6 Yes SD 6>>-BDC-2403-6 C5.51 6>> Yes SD 108 6>>-BDA-2404-FW45 C5.51 6>> Yes SD t HS 25 High Stress Weld 25~o Additional Welds 110 TE Terminal End Weld SD Structural Discontinuity
4C 8
' ~0 a p,
I
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix E Table E-8 Turkey Point Unit 4 C-F-2 Non Exempt Piping Welds Selected for Exam Selected Third Zone Weld Code Size During Interval Number Identification Item Second Selection Interval Criteria 109 6"-BDB-2405-FW42B C5.51 61I Yes SD 110 6"-BDC-2406-FW35C C5.51 6" Yes SD 14"-FWA-2401-8 C5. 81 6 Yes BC 14 n-FWA-2401-21 C5. 51 1 4 II Yes SD 14"-FWA-2401-FW3A C5.51 1 4 ll Yes SD 14"-FWA-2401-28 C5.51 1 4 II Yes SD 14"-FWA-2401-29 C5.51 18" Yes TE 112 14"-FWB-2402-3 C5.51 14 lt Yes SD 113 14't-FWC-2403-3 C5.51 14" Yes SD 116 6"-FW-2303-1A C5.51 4 II Yes SD t HS High Stress Weld 25 25% Additional Welds 111 TE Terminal End Weld SD Structural Discontinuity
~ '
Revision 0 Date: August 27, 1993 Appendix F Table F-1 Turkey Point Unit 3 Class 1 Supports Number Selected Zone Total Supports Per 1 Per 2 Per 3 003 004 005 006 016 020 021 17 022 027 035 14 036 037 038 039 040 15 041 10 042 043 13 044 045 046 12 047 048 112
r ~ ~
I
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix F Table F-1 Turkey Point Unit 3 Class 1 Supports Number Selected Zone Total Supports Per 1 Per 2 Per 3 049 050 051 052 056 057 058 059 Totals 183 17 17 12 Piping 176 Components 7 Total 183 Piping Schd 43 Component Schd 3 Percentage Scheduled 46/183 = 25%
Note: Supports that contain more than one classified line are counted only once.
Only one of multiple components within a system are examined.
This has the effect of lowering the percentage examined.
Over 25< of the piping supports are examined.
113
J I O'II M ~ %.~ i > ll I
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix F Table F-2 Turkey Point Unit. 3 Class 2 Supports Number Selected Zone Number Total Supports Per 1 Per 2 Per 3 063 064 065 066 067 068 069 10 070 071 072 073 074 075 076 077 078 079 080 081 082 083 0 084 085 114
It I't~
ianna>k I tt>r t
t 0
Revision 0 Date: August 27, 1993 Appendix F Table F-2 Turkey Point Unit 3 Class 2 Supports Number Selected Zone Number Total Supports Per 1 Per 2 Per 3 086 087 088 089 090 091 092 093 094 095 38 096 32 097 098 099 100 101 102 103 10 104 105 10 106 107 115
t ~ ~ tl ~ \~ ~ " Il ail Revision 0 Date: August 27, 1993 Appendix F Table F-2 Turkey Point Unit 3 Class 2 Supports Number Selected Zone Number Total Supports Per 1 Per 2 Per 3 108 109 110 112 113 114 115 116 120 121 0 122 Totals 195 15 13 22 Piping 189 Components 6 Total 195 Piping Schd 47 Component Schd 3 Percentage scheduled 47/189 = 25~o Note: Supports that contain more than one classified line are counted only once.
Only one of multiple components within a system are examined.
116
g y g IL eye (
II'
Revision 0 Date: August 27, 1993 Appendix F Table F-3 Turkey Point Unit 3 Class 3 Supports and Integral Attachments Number Number Total Selected by Total Selected by Zone Supports Period Integral Period Attachments 118 3(D-A) 119 4 (D-A) 120 3 (D-B) 121 2 (D-B) 122 1 (D-B) 123 12 2 (D-B) 124 125 1 (D-B) 126 1(D-B) 127 2 (D-B) 128 2 (D-B) 129 14 2 (D-B) 130 2 (D-B) 131 1 (D-B) 132 2 (D-B) 133 3 (D-B) 134 2 (D-B) 135 1(D-B) 136 3 (D-A) 137 2 (D-B) 138 3 (D-B) 139 3 (D-B) 117
dy b
0 J 0
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix F Table F-3 Turkey Point Unit 3 Class 3 Supports and Integral Attachments Number Number Total Selected by Total Selected by Zone Supports Period Integral Period Attachments 140 141 142 (D-B) 143 3 (D-B) 144 1 (D-B) 145 3 (D-B) 146 4 (D-B) 147 2 (D-B) 148 3 149 4 (D-B) 150 3 (D-B) 151 7 (D-B) 152 1 (D-B) 153 6 (D-B) 154 2 (D-B) 155 2 (D-B) 156 1 (D-B) 157 2 (D-B) 158 4 (D-B) 159 1(D-B) 160 118
1 I I ~ a 4 'I h I" I'+
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix F Table F-3 Turkey Point Unit 3 Class 3 Supports and Integral Attachments Number Number Total Selected by Total Selected by Zone Supports Period Integral Period Attachments 161 1 (D-B) 162 15 7 (D-A) 163 13 5 (D-A) 164 12 5 (D-B) 165 166 167 168 2 (D-A) 169 12 170 12 171 Total 329 29 21 41 112 Supports:
Piping 176 Components 7 Total 183 Piping Schd 43 Component Schd 3 Scheduled 91 Total 329 Percentage 91/329 = 27.7%
119
l II 'l L "'I $ g i
w 4 ~ If Jl 1 )
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix F Table F-3 Turkey Point Unit 3 Class 3 Supports and Integral Attachments Note: Supports that contain more than one classified line are counted only once.
Integral Attachments:
Scheduled 14 Total 112 Percentage 14/112 = 12.5>
120
1 ll
.i
Turkey Point ISX Program Revision 0 Date: August 27, 1993 Appendix F Table F-4 Turkey Point Unit 4 Class 1 Support Summary Supports Examined Zone Total Supports Per 1 Per 2 Per 3 016 017 018 019 020 14 021 21 022 035 17 036 037 038 039 040 12 041 12 042 043 044 045 046 047 14 048 049 121
~ I Revision 0 Date: August 27, 1993 Appendix F Table F-4 Turkey Point Unit 4 Class 1 Support Summary Supports Examined Zone Total Supports Per 1 Per 2 Per 3 050 051 12 052 Totals 175 10 21 15 Scheduled 46 Total 175 t Percentage 46/175 = 26.3%
Note: Supports that contain more than one counted only once.
classified line are 122
>>'i' 4 Revision 0 Date: August 27, 1993 Appendix F Table F-5 Turkey Point Unit 4 Class 2 Supports Supports Examined Zone Total Supports Per 1 Per 2 Per 3 063 064 065 066 067 068 069 070 071 072 073 074 075 076 077 081 082 083 084 13 085 086 087 088 123
~ r 'I
'1
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix F Table F-5 Turkey Point Unit 4 Class 2 Supports Supports Examined Zone Total Supports Per 1 Per 2 Per 3 089 090 091 092 093 094 095 096 097 48 098 21 099 100 101 102 103 104 105 106 107 108 109 110 124
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix F Table F-5 Turkey Point Unit 4 Class 2 Supports Supports Examined Zone Total Supports Per 1 Per 2 Per 3 112 113 114 115 116 Totals 199 14 18 18 Scheduled 50 Total 199 Percentage 50/199 = 25.1%
Note: Supports that contain more than one classified line are counted only once.
125
l g
0 0
J 0
Revision 0 Date: August 27, 1993 Appendix F Table F-6 Turkey Point Unit; 4 Class 3 Supports and Integral Attachments Number Number Total Examined by Total Examined by Zone Supports Period Integral Period Attachments 120 0 0 3(D-A) 121 3 (D-A) 122 2 (D-B) 123 1 0 3 (D-B) 124 0 1 125 3 (D-A) 126 5 (D-B) 127 0 1 3 (D-B) 128 0 0 129 2 (D-B) 130 3 (D-B) 0 0 131 2 (D-B) 0 0 132 0 2 2 (D-B) 133 10 1 3 7 (D-B) 0 0 134 0 1 2 (D-B) 0 1 135 1 0 2(D-B) 136 1 (D-B) 137 1 1 2 (D-B) 0 0 138 0 0 139 10 1 0 4(D-A) 140 0 1(D-B) 0 0 126
l 4 w" 'I ~ 4>>+' "" ~
~
~ '
Revision 0 Date: August 27, 1993 Appendix F Table F-6 Turkey Point Unit 4 Class 3 Supports and Integral Attachments Number Number Total Examined by Total Examined by Zone Supports Period Integral Period Attachments 141 10 1 2 2 (D-B) 142 3 (D-B) 143 2 (D-B) 144 2 (D-B) 0 0 145 2 (D-B) 0 0 146 147 1 (D-B) 148 0 0 3 (D-B) 0 0 149 2 (D-B) 150 1 (D-B) 151 0 1 4 (D-B) 0 0 152 1 0 4 (D-B) 153 1 0 4 (D-B) 154 2 (D-B) 155 1 0 4 (D-B) 156 1 0 4 (D-B) 157 158 16 1 (D-B) 159 0 0 160 0 1 3 (D-B) 0 0 161 0 0 2 (D-B) 127
il II ~ - li" Q f," "'
P 0
s 4 ~
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix F Table F-6 Turkey Point Unit 4 Class 3 Supports and Integral Attachments Number Number Total Examined by Total Examined by Zone Supports Period Integral Period Attachments 162 1 (D-B) 163 25 6(D-A) 164 165 166 167 Total 329 37 27 26 103 Supports:
Scheduled 90 Total 329 Percentage 90/329 = 27.6%
Note: Supports that contain more than one classified line are counted only once.
Integral Attachments:
Scheduled 11 Total 103 Percentage ll/103 = 10.7%
128
4 hing ' kg (II" J g
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix G Relief Requests Relief Description Request Incomplete Coverage Reactor Pressure Vessel Welds Incomplete Coverage RPV Safe End Welds Relief from Exams Regenerative Heat Exchanger Inservice Test Requirements for Snubbers Relief from Exams Reactor Pressure Vessel Alternate NIS-1 and NIS-2 forms Alternate Examinations of Longitudinal Seam welds on Piping Alternative Rules for the Selection and Examination of Class 1, 2, and 3 Integrally Welded Attachments Alternative Scheduling of Examinations 10 Alternative Examination of Class 1 and 2 Borated Bolted Connections Subject to VT-2 Examination 129
II 1 ~
4 k I I ~ 1 5 h' ' 4 ~ ~~ t
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Relief Request No. 1 A. Component Identification:
Turkey Point Units 3 and 4 Class 1 Reactor Pressure Vessel B. Examination Requirements:
Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition Exam Item Description Category No.
B-A B1.30 Volumetric examination of shell to flange weld, includes essentially 100% of weld length.
B-D B3.90 Volumetric examination of full penetration welds in vessels (includes nozzle to vessel weld and adjacent areas of nozzle and vessel).
C. Relief Requested:
Relief is requested from examining the Code required volume during the performance of ultrasonic examinations of the following vessel outlet nozzle and flange to shell weld.
Item No. Turkey Pt. 3 Turkey Pt. 4 B1. 30 3-WR-18 4-WR-18 B3. 90 3-DO-A 4-DO-A 3-DO-B 4-DO-B 3-DO-C 4-DO-C 130
i II Turkey Point ZSI Program Revision 0 Date: August 27, 1993 D. Basis for Relief:
Configuration of the outlet nozzles and flange to shell welds prohibit 100% ultrasonic examination coverage of the required code examination volume.
- 1. Nozzle to Shell Weld Limitations When performing computerized Ultrasonic examinations of the Nozzle to Shell Welds from the vessel wall, several areas were described as having limited examination scans. These limitations were restricted to the last several scans of the nozzle to shell examination and were due to the physical limitations imposed by the adjacent nozzles. The limitations all occurred in the vicinity of the 90'nd 180'ozzle azimuth relative to nozzle orientation.
- 2. Reactor Pressure Vessel Shell to Flange Weld There are areas that did not receive 0 degree, 45 degree transverse, or 60 degree transverse weld coverage due to the geometric configuration of the flange radius located just above the weld.
Examinations performed from the shell side of the weld provided essentially 100 percent coverage of the weld and 1/2t of the base material on the shell side.
RPV Nozzle to Shell Weld Limitations Examination Type Percentage Remarks of Coverage Achieved Parallel Scans 100~a None Transverse Scans 88.79~o Exams from the shell were limited due to interference from the integral attachment 131
M J ~ ll, q L ~ A
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Reactor Pressure Vessel Shell to Flange Weld Percentage Examination Type of Remarks Coverage Achieved Parallel Scans 77.224 Exams from the shell surface were limited due to the flange inside taper Transverse Scans 54.87>o Exams from the shell surface were limited due to the flange inside taper Total Weld Length = 488.51" Reactor Pressure Vessel Bottom Head to Lower Head Ring Percentage Examination Type of Remarks Coverage Achieved Parallel Scans UP 90 ~ 00~o Exams were limited DN 98 ~ 00~o due to the close proximity of the instrumentation tubes Transverse Scans CW 91. 734 Exams were limited CCW 88.00% due to the close proximity of the instrumentation tubes Total Weld Length = 488.51" E. Alternative Examinations:
Periodic System Leakage Tests per Category B-P and the achievable ultrasonic testing. The extent of examination volume achieved ultrasonically and the alternative system pressure tests provide assurance of an acceptable level of quality and safety.
132
II '1 ~ .
y 04 gl $e k) *~I
Revision 0 Date: August 27, 1993 F. Implementation Schedule:
Third Period of the Third Interval.
G. Attachments Upper Shell to Flange limitation drawing Head to Lower Head Ring limitation drawing Lower Head Ring 'to Lower Shell limitation drawing Inlet Nozzle to Shell Limitations Outlet. Nozzle to Shell Limitations 133
1 >, y 1~
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Upper Shell to Flange Limitations I I I Porallel 45'ull vee Tr onsverse exon exon 360'ron the 360' on the shell surface shell surface Veld Q Notei LIPllted Exanlnatlon due to Inside surface Upper Shell to Flange taper, 134
t A 1 g i 1l~'t' ">Ill<
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Head to Lower Head Ring Limitations Cor e stabllzlng lug Veld Q L eer Lower Head Head Rno Rho Four Istrumentatton tube locations Llnlted transverse exans due to proxlnlty Instrurlentatlon Lower oF nlstrunent tubenlgs Head tube Head Llnlted bean Looking up due to Prox'nlty oF lnstrunent tubing Llnlted bean looking down due to Proxtnlty Head to Low Head Ring oF Instrunent tubing 135
l
'H
,g
' ~
<g> ~' '," ~ t s>(",'
II
Turkey Point XSX Program Revision 0 Date: August 27, 1993 Lower Head Ring to Lower Shell Limitations Lower Lower Shell Shell Cor e stabUzlng lug Veld 0 'N ca Lower He acl H eacl Rln g Rilg Instr urlentatlon tubing Llnlted transverse exans due to proxlnlty oF lugs Llnlted parallel exans Low Head Ring to Lower Shell due to proxlnlty of lugs 136
h II lb 0,
Revision 0 Date: August 27, 1993 Inlet Nozzle to Shell Limitations 5'r90' on 270'5'rom bor e 6 O' bore areas due to 180'lmlted geometric shadowing Inlet Nozzle to Shell (with 1 angle only) 137
0 Turkey Point ISI Program Revision 0 Date: August 27, 1993 Outlet Nozzle to Shell Limitations Parallel 90' 270 0' 180rom 8 90 and 270'S'rom bor e 60' bore 180 Par allel From bore Llmlted areas due to geometric shadowing (one angle only) 138
E 1 el iL 1 1 <<. ~II
Turkey Point XSI Program Revision 0 Date: August 27, 1993 Outlet Nozzle to Shell Limitations Transverse 90' 270 180'r ansver se From shell Limited exanlnatlon due to proximity oF Integra( Ext.
139
4 A =
e
~ 1 4
4 ~ 4 t, f
~ II ig ~
4 J ~ i 0
Revision 0 Date: August 27, 1993 Relief Request No. 2 A. Component Identification:
Turkey =Point Units 3 and 4 Class 1 Reactor Pressure Vessel Safe-End Pressure Retaining Dissimilar Metal Welds, Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition Code Category: B-F Code Item Number: B5.10 Volumetric and surface examinations shall be performed during each inspection interval.
t C. Relief Requested:
Relief is requested from the required code examination area during ultrasonic and liquid penetrant examinations.
D. Basis for Relief:
- 1. Portions of the required volumetric and surface area are inaccessible due to permanent physical obstructions in the Reactor Pressure Vessel.
- 2. In order to conduct these examinations at Turkey Point, access is from the refuel pool, which requires seal ring and sand plug cover removal.
- 3. Non-removable vessel and piping insulation and limited space in the sand plug area restricts access to the exterior surface. 100% of the surface area can not be effectively examined.
140
gt
~ >> < v
Revision 0 Date: August 27, 1993 Surface Examination Coverage CW CCW Weld No. Coverage Coverage Weld Percentage from TDC from TDC Length Covered 27 '"-RCS-1306-14 10" 17" 86. 4') 31. 34 27.5"-RCS-1307-14 2 1 Il 23" 86.4" 50.9%
27.5"-RCS-1309-14 2 1 II 2 1 II 86 4 48.64 27 5't RCS 1406 14 3 11 4 fl 86.4" 8.1>
27-5't-RCS-1407-14 3 II 4 II 86.4" 8.
1%'.9%
27 5"-RCS-1409-14 3 II 3 II 86.4"
- 4. Performance of these examinations on the nozzles involves excessive cost, manhours, and radiation exposure with little and or no compensating increase in the level of quality safety.
- 5. The examinations conducted provide assurance of an acceptable level of quality and safety.
E. Alternative Examinations:
- 1. Conduct volumetric and surface examinations to the extent possible on the Inlet Reactor Pressure Vessel Nozzle Safe-End Welds. r PTN-3 PTN-4 27.5"-RCS-1307-14 27.5"-RCS-1407-14 27 5>>-RCS-1306-14 27.5"-RCS-1406-14 27.5"-RCS-1309-14 27.5"-RCS-1409-14
- 2. Conduct a full volume ultrasonic examination including the outside surface of the Reactor Pressure Vessel outlet nozzle safe end welds in lieu of the surface examinations.
141
a t
g ' ~
,I
'i<a ~ I i;4 f~lk II ~
Y) ~
e I
e J
Turkey Point ISI Program Revision 0 0 Date: August 27, 1993 PTN-3 FTN-4 29"-RCS-1304-1 29"-RCS-1404-1 29"-RCS-1305-1 29"-RCS-1405-1 29"-RCS-1308-1 291'-RCS-1408-1
- 3. The volumetric'xamination technique utilized will cover the entire volume of the weld and 1/2" of the base metal from the edge of the weld. This examination will interrogate the outside surface of the weld from two different directions circumferentially and axially. This technique was used for previous examinations on these welds with satisfactory results in accordance with the previous Relief Request.
- 4. Conduct system pressure tests as required by the Turkey Point Inservice Pressure Test Program.
- 5. The examination volume achieved by surface and/or ultrasonic examination, combined with the system pressure tests, provide an acceptable level of quality and safety.
F. Implementation Schedule:
Third Inservice Inspection Interval The nozzle safe-ends will be examined in conjunction with the Reactor Pressure Vessel examinations at or near the end of the inspection interval.
G. Attachments None 142
N s i'i' <~ h i i <5<
I II k P I t 0
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Relief Request No. 3 A. Component Identification:
Turkey Point Units 3 and 4 Class 1 Regenerative Heat Exchangers and connecting piping at Turkey Point, Nuclear Plants, Units 3 and 4.
B. Examination Requirements:
Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition IWB-2500 Examination and Pressure Test Requirements Exam Item No. Examination requirements Catgy B-B B2. 51 Volumetric examination, to include 100%
B2. 80 of the length of circumferential tube sheet to shell welds and head to shell welds B-D B3. 150 Volumetric examination, to include 100%
B3. 160 of each nozzle to vessel weld and nozzle inside radius area.
B-H B8.40 Volumetric or surface examination to include 100~ of each integrally welded support of one exchanger.
B-J B9.21 Surface examination to include 1004 of weld surface on approximately 254 of the total interconnecting piping joints.
B9.40 Surface examination of essentially 1004 of the weld length of selected welds during each interval.
B-J Footnote 1 Examinations shall include the following:
(a)All terminal ends in each pipe or branch run connected to vessels.
F-A All Code Item Examine welds, mechanical connections, Numbers as clearances, alignment, sliding surfaces, Applicable and assembly of the supports.
143
~ ~
I
Revision 0 Date: August 27, 1993 Exam Item No. Examination requirements Catgy N/A Terminal Ends The extremities of piping runs that.
connect to structures, components, or pipe anchors, each of which acts as a rigid restraint or provides at least 2 degrees of restraint to piping thermal movement C. Relief Requested:
Relief is requested from the Code required examinations on the Regenerative Heat Exchanger shell welds, interconnecting piping welds, support welds, connecting terminal end piping welds, and the component supports.
Item No. Examination Areas Turkey Turkey
.Point Point Unit 3 Unit 4 B2. 51 Head to Shell Circ Welds 6 welds 6 welds B2.80 Shell to Tubesheet welds 6 welds 6 welds B3.150 Nozzle to Shell welds 12 welds 12 welds B3.160 Nozzle Inside Radius 12 areas 12 areas Section B8.40 Welded Support 3 welds 3 welds B9. 21 Interstage Piping 10 welds 10 welds B9. 40 Socket Welds 2 welds 2 welds All Code Item Supports 1 support 1 support Numbers as Applicable See Tables 1 and 2 for detailed listings of welds.
D. Basis for Relief:
The Regenerative Heat Exchanger is located in a locked high radiation area. This area has a general field of 2 Rem/hr with contact dose rates of up to 10 Rem/hr, is highly contaminated, 144
l ' fk~t i "'LAkl'<
Revision 0 Date: August 27, 1993 and requires the use of a full face respirator. Turkey Point Health Physics (HP) rules require the constant presence of an HP technician during entry to this area. Other conditions include limited accessibility to the examination areas due to the close proximity of the adjacent wall and floor, limited work area due to cubicle walls built to shield personnel in adjacent areas, and interference from other lines and supports in the immediate area.
During construction of Turkey Points Units 3 and 4, asbestos insulation was used extensively. Asbestos insulation is present in the area of the Regenerative Heat Exchanger.
Additional protection is required for personnel entering this area to avoid possible spreading and ingestion of this hazardous material (i.e. an extra layer of protective clothing, tenting, HEPA filters.)
Performing Code required examinations would require large expenditures of man-hours and accumulated Man-Rem dose. The welds must be de-insulated for examination and temporary shielding and scaffold installed. Effective shielding reduces accessibility to the examination areas. Proper surface conditioning will add to the time and exposure required to perform valid surface and volumetric examinations. The area must be tented to avoid spreading of asbestos fibers found in the insulation. The design and arrangement of the Regenerative Heat Exchanger are not conducive to meaningful examinations.
FPL has performed examinations on the Regenerative Heat Exchangers for both Turkey Point Units 3 and 4 during the first inspection interval (approximately early 1972 through late 1983) before the original relief request was approved. This experience showed that the design arrangement and accessibility are not conducive to meaningful examinations. The configuration, limited accessibility, high radiation levels, and interference from supports, walls, and the floor do not allow the Code required 100~ volumetric and/or surface examinations.
Terminal ends in Category B-J, welds are to receive surface and/or volumetric examinations. FPL has performed examinations on terminal end welds on other components in the Chemical and Volume Control system. Since 1985, VT-2 and VT-3 examinations have been performed on the terminal end welds listed in this relief. These were performed in accordance with the previous approved relief request, which required FPL to look for evidence of leakage around the Regenerative Heat Exchanger just 145
C!i>i
~
Turkey Point ISI Program Revision 0 Date: August, 27, 1993 after shutdown for a refueling outage, and a second time during the system pressure test at plant startup.
During the 1991 outages of both units, the system hydrostatic tests were performed on the affected systems. No leakage was detected. No evidence of leakage from the Regenerative Heat Exchanger or its attached piping has been noted in either unit during any of the previous examinations.
Performing the alternative examinations will not increase the health and safety risk to the public.
146
<<a <>-CH-1301-1 3"-CH-1402-1 3"-CH-1303-23 3"-CH-1403-24 2"-CH-1301-18 2"-CH-1401-18 2"-CH-1302-1 2"-CH-1402-1 148
lf
'v ~ i < fill v
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Table 2 Regenerative Heat Exchanger Weld Identification Weld Description Weld Numbers
- Head to Shell RGX-I-1 RGX-II-1 RGX-III-1 Shell to Tube Sheet Primary RGX-I-2 RGX-II-2 RGX-III-2 Tube Sheet to Shell Secondary RGX-I-3 RGX-II-3 RGX-III-3 Channel Head Weld Secondary RGX-I-4 RGX-II-4 RGX-III-4 Shell I Nozzle Welds RGX-I-9 RGX-I-10 RGX-I-11 RGX-I-12 Shell II Nozzle Welds RGX-II-9 RGX-II-10 RGX-II-11 RGX-II-12 Shell III Nozzle Welds RGX-III-9 RGX-III-10 RGX-III-11 RGX-III-12 Shell I Nozzle to Pipe Interstage RGX-I-7 Piping RGX-I-8 Shell II Nozzle to Pipe Interstage RGX-II-5 Piping RGX-II-6 RGX-II-7 RGX-II-8 Shell III Nozzle to Pipe Interstage RGX-III-5 Piping RGX-III-6 Integrally Welded Supports RGX-I-LUG RGX-II-LUG RGX-III-LUG
- The weld numbers are the same for both units.
149
0 Turkey Point ISI Program Revision 0 Date: August 11, 1993 Examination Area Coverage UMITED EXAMINATION FROM SHELL DVE TO NOZZLE, 76%
NO EXAM ON WElD OR NOZZLE 9DE DVE COVERAGE; UMITED EXAM ON CAP 9OE DUE TO CONFIGURAllOH, TO ITS CONFIGURATIOII. OX COVERACE LESS THAN 50% COVERAGE. 76Ã CF WElD LENGlH EXAMIIIED UMIIED EXAM ON SHELL DUE (TYPICAL 12 AREAS)
ON CAP SIDE DVE TO LVG (TIPICAL THREE WELDS) TO CLAMP. 87K COVERAGE UMITED EXAM ON SHElL DUE (TYPICAL 4 AREAS) TO CLAMP, 87K COVERAGE (TROPICAL 4 AREAS)
LIMITED EXAM ON CAP SIDE OVE TO IlS CONFIGURATION, LESS THAN 50X COVERAGE (TYPICAL 3 WELDS)L 53X COVERAGE FROM SHELL SDE SHEU. OVE TO NOZZLES (TYPICAL 3 WELDS)
HO EXAM ON BOTTOM OF LVG OUE TO ANGlE IRON BRACKET COLERING WELD, 55 COVERAGE UMITED EXAM ON SHEU. DVE
'TO CLAMP. 87X COVERAGE (TYPICAL 4 AREAS) 76K OF SHEU. 9DE EXAMINED DUE TO NOZZLE UMITATION; NO EXAM ON lVBE SHEET 9OE OUE TO CLAMP (V'OVERACE) 53X COVERAGE FROM SHELL SIDE DVE TO NOZZLES (TYPICAL 3 WELDS)
NO EXAM FROM IVBESHEET SIDE DVE TO CLAMP (OX COVERAGE) 150
Turkey Point ISI Program Revision 0 Date: August 11, 1993 Unit 3 Regenerative Heat Exchanger 2"-CH-1302 3"-CH-1303 SEE DWG. 3-A48 SEE DWG. 3-A46 ZONE 049 ZONE 047 RGX-I- I RGX-l-9 ~ RGX-I-10 RGX-I-4 SHELL
~
I RGX-I-LUG LUG RESllNG ON ANGLE IRON BRACKET RGX-I-11
<<RGX-1-7 RGX-l-2 RGX-I-CR RGX-II-5 CLAMP
~
RGX-I-3
~ RGX-I-12 RGX-I-8 RGX-II-6 RGX-II-I RGX-ll-9 ~ RGX-II-I 0 RGX-II-4 SHELL II
~~
RGX-II-LUG ~~ RGX-II-11 RGX-II-7 RGX-II-2 RGX-II-CR CLAMP
~ RGX j ~ RGX-II-I 2 RGX-II-8
~ RGX-III-I RGX-III-8 RGX-III-9
~
~RGX-III-6 RGX-III-10 RGX-III-4 SHELL III
~ RGX-III-11 RGX-III-2 RGX-III-CR
~~ ~ R GX-III-12 RGX-III-LUG CLAMP 2"- CH-1301 RGX-III-3 3 -CH-1301 SEE DWG. 3-A47 SEE DWG. 3-A44 ZONE 048 ZONE 045 151
Turkey Point ISI Program Revision 0 Date: August 11, 1993 Unit 3 Regenerative Heat Exchanger Terminal End Welds 20 21 3 CH 1 303 2 CH 1 302 22 3 CH 1 301 18 2 CH 301 1
17 18 152
C~l 4)
Turkey Point ISI Program Revision 0 Date: August 11, 1993 Unit 4 Regenerative Heat Exchanger 2"-CH-1402 3"-CH-1403 SEE DWG. 4-A43 SEE DWG. 4-A41 ZONE 049 ZONE 047 RGX-1-1 RGX-1-9 ~ RGX-1-10 RGX-1-4 SHELL I RGX- I-LUG LUG RESTING ON ANGLE IRON BRACKET RGX-1-11
~RGX-1-7 RGX-1-2 RGX-I-CR CLAMP
~
~
RGX-1-3
~ RGX-1-12 RGX-1-8 RGX-11-6 RGX-11-6 RGX-!1-1 RGX-11-9
~ RGX-11-10 RGX-11-4 RGX-11-LUG ~~
SHELL ll RGX-11-11 RGX-II-7 RGX-11-2 RGX-II-CR CLAMP
~~
J
~
~ RGX-11-12 RGX-II-G
~ RGX-III-I RGX-III-6 RGX-111-9
~
~
RGX RGX-III-6
~RGX-lll-lG RGX-111-4 SHELL Ill
~ RGX-111-1 1 RGX-111-2 RGX-III-CR
~~ ~RGX-111-12 RGX-III-LUG CLAMP RGX-111-3 2"-CH-1401 3 -CH-1402 SEE DWG. 4-A42 SEE DWG. 4-A40 ZONE 048 ZONE 046 153
Turkey Point ISI Program Revision 0 Date: August 11, 1993 Unit 4 Regenerative Heat Exchanger Terminal End Welds 21 23 3 CH 1403 2 CH 1402 3 CH 1 402 2 CH 1 401 154
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Relief Request No. 4 A. Component Identification:
Turkey Point Units 3 and 4 ASME Section XI, 1989 Edition IWF-5000 Inservice Test Requirements ASME Class 1, 2, and 3 Snubbers B. Examination Requirements:
Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition IWF-5300 Inservice Examination and Tests (a) Inservice examination shall be performed in accordance with the first Addenda to ASME/ANSI OM-1987, Part 4 (published in 1988), using the VT-3 visual examination method described in IWA-2213.
(b) Inservice tests shall be performed in accordance with the first Addenda to ASME/ANSI OM-1987, Part 4 (published in 1988) .
C. Relief Requested:
Relief is requested from the requirements of ASME/ANSI OM-1987, Part 4 (OM Part 4).
D. Basis for Relief:
- 1. Table 6.5.2-1 of OM Part 4 has been incorporated into the Turkey Point plant technical specifications and is currently implemented.
- 2. The functional test plan and sample expansion plans identified in OM Part 4 are engineering manpower intensive.
It results in hardships for Turkey Point with its relatively small snubber population. There would be additional time, expense, and an accompanying increase in radiation exposure without a compensating increase in the level of quality or safety.
155
la i ~, Q/I
~
k
Turkey Point ISI Program Revision 0 Date: August 27, 1993
- 3. FPL has very successful snubber functional and visual testing programs at Turkey Point. Both programs follow the plant technical specifications which is more stringent than OM Part 4. The functional test program utilizes the 10%
sample plan and a 10% expansion criteria based on design type. The visual examination program includes a "limited operability test" by hand stroking all snubbers each refueling outage during the VT-3 examination.
E. Alternative Examinations:
FPL will utilize the Snubber Functional and Visual Testing Program currently in place as described in the Basis this Relief Request. These examinations and tests exceed the requirements of OM Part 4 and provide an acceptable level of quality and safety.
F. Implementation Schedule:
Third Inspection Interval G. Attachments:
none 156
I 0
If I' V V 8 ' >4
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Relief Request No. 5 A. Component Identification:
ASME Class 1 Reactor Pressure Vessel Examination Category B-D Full Penetration Welds of Nozzles in Vessels Inspection Program B B. Testing Requirements:
Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition Category Item No. Description B-D B3. 90 Nozzle to Vessel Welds B-D B3.100 Nozzle Inside Radius Sections ote (2) At least 25% but not more than 504 (credited) of the nozzles 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 examining at least 254 of the Category B-D welds and inside radius sections in the Reactor Pressure Vessels of Turkey Point Units 3 and 4 by the end of the first inspection period.
D. Basis for Relief During the 1990-1991 Outages for both Turkey Point Units 3 and 4, 100% of the Reactor Pressure Vessel welds were examined (categories B-A, B-D, and B-F). The examinations consisted of using the Enhanced Data Acquisition System from Southwest Research Institute (SwRI), which captures essentially 100% of the Ultrasonic signal for processing. Several of the SwRI personnel had qualified for certification with this equipment, through an internal program. The Electric Power Research Institute Nondestructive Examination Center had qualified several of these SwRI personnel in IGSCC detection. Every 157
'I r '~ l,iS'g Turkey Point ISI Program Revision 0 Date: August 27, 1993 recorded indication was evaluated to determine its nature. No reportable indications were found. This was the third Inservice Inspection of these nozzles and inside radius sections.
These examinations met the requirements of 10 CFR 50.55a (g)(6)(ii)(A), Augmented Examination of Reactor Vessels.
E. Alternative Examinations Florida Power and Light will perform 100% of the Category B-D nozzle welds and inside radius sections in the Reactor Pressure Vessels approximately 10 years after the previous examination.
F. Implementation Schedule Third Period of the Third Ten-Year Interval G. Attachments none 158
7w'4' '4h Turkey Point ISI Program Revision 0 Date: August 27, 1993 Relief Request No. 6 A. Article Identification:
Article IWA-4000 Repair Procedures Article IWA-6000 Records and Reports Article IWA-7000 Replacement B. Article Requirements:
IWA-4800 The records required by IWA-6000 shall be completed for all repairs.
IWA-7520 (a)(8) Completed Owner's Report for Repairs or Replacements, Form NIS-2 IWA-6210 (c) The Owner shall prepare inservice inspection summary report for Class 1 and 2 pressure retaining components and their supports.
IWA-6220 (c) Inservice inspection summary reports shall be required at the completion of each inspection conducted during a refueling outage.
Examinations, tests, replacements, and repairs conducted since the preceding summary report shall be concluded.
IWA-6220 (d) Each summary report shall contain the following:
(2) Owner's Report for Inservice 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, the Owner shall .file inservice inspection summary reports with the enforcement and regulatory authorities having jurisdiction at the plant site.
C. Relief Requested:
Relief is requested from the following:
- 1. Preparation of the Owner's Report for Inservice Inspection, Form NIS-1.
159
t 'L 11 l
~ ll 1
l
Revision 0 Date: August 27, 1993
- 2. Preparation of the Owner's Report for Repair or Replacement, Form NIS-2.
- 3. Submittal of the summary report within 90 days following completion of the inservice inspection conducted during each refueling outage.
D. Basis for Relief:
Florida Power and Light Company considers 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 Turkey Point.
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 not required to be included in the summary report submittal.
Both a Final Report and Summary Report must be prepared, reviewed, and approved in order to comply with IWA-6220 and IWA-6310.
The preparation, review, approval, and certification of each record and report within the time frame of 90 days following completion of each refueling outage substantially increases the costs associated with inservice inspection activities. This puts an unreasonable time constraint on FPL without increasing assurance of Code compliance.
t E. Alternative Examinations or Tests:
As an alternate to the requirements of IWA-6000, Florida and Light Company proposes the following:
Power
- 1) Repair/Replacement Plan Repair/Replacement plans shall meet the requirements of IWA-4140 (1992 Edition), to the extent required, for all Code Classes.
160
a 1 L r <r i" 1
Turkey Point ISI Program Revision 0 Date: August 27, 1993 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., CR, CNR, P/CM, MEP, CWO, PWO, etc.).
All other applicable requirements of IWA-4000, 1989 Edition, shall be met.
- 2) Repair/Replacement Certification Record As an alternate to the NIS-2 Report, FPL shall prepare and certify the Repair/Replacement Plan Certification Records, form NIS-2A (or similar), following completion of repairs or replacements.
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 an index of 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.
It will be made available upon request for review by the enforcement and regulatory authorities having jurisdiction at the plant site.
- 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 (or similar) .
- b. Abstract of examination and tests information, Form NIS-1B (or similar).
161
~ ~ z a ~ z I y" < ~'Lit Turkey Point ISI Program Revision 0 Date: August 27, 1993
- c. Listing of examinations, Form NIS-1C (or similar), that were not performed and were identified in the inspection plan for the inspection period, and when or planned for a later date.
if they are Any alternate examinations (IWA-2240) that were performed.
- d. A listing of flaws that required analytical evaluation, Form NIS-1D (or similar).
- e. A Repair/Replacement Plan Certification Record, form NIS-2A (or similar) .
- e. Abstract of repairs and replacements, Form NIS-2B (or similar), which were required due to an item having exceeded the acceptance criteria.
F. Implementation Schedule:
The Third Inservice Inspection Interval.
G. Attachments to the Relief:
Form NIS-lA Owner's ASME Section XI Summary Report Form NIS-1B Abstract of Examination and Tests Form NIS-1C Examinations Not Performed as Identified in the Inspection Plan Form NIS-1D Identification of Items with Flaws Which Required Analytical Evaluation for Continued Acceptability Form NIS-2A Repair/Replacement Plan Certification Record Form NIS-2B Abstract of Repairs and Replacements 162
e s" a '" .4 i~k II L
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Form NIS-1A OWNER'S ASME SECTION XI
SUMMARY
REPORT Page of Report Identification Number Rev. Date Owner (Name and Address of Owner)
Plant (Name and Address of Plant)
Plant Unit Refueling Outage Humber Conmercial Service Date Current Inspection Interval:
Inspection Interval Date: From to Inspection Period: I] First [I Second [I Third Inspection Period Date: From to Applicable Edition of Section XI: Addenda Date/Revision of Inspection Plan Edition and Addenda of ASHE Section XI applicable to Repairs and Replacements, if different than the Inspection Plan:
CERTIFICATE OF COHPLIAHCE We certify that thc statements made in this Swnery Report are correct, and that the examinations, tests, repairs, replacements, and corrective measures represented by this report conform to the rules of the ASHE Code,Section XI.
Certificate of Authorization Ho. Expiration Date Date Signed Owner's Representative and Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid conmission 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 O~ner has performed all activities represented by this report in accordance with the rules of ASHE 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.
Connissions Inspector's Signature National Board, State, Province, and Endorsements Date 163
t Turkey Point ISI Program Revision 0 Date: August 27, 1993 FORM NIS-18 ABSTRACT OF EXAMINATION AND TESTS Page of Code Total Items Total Examinations Total Examinations Total X Exams Exclusions Examination Subject to Required for Required for this Credited for or Category Examination Interval Period Interval Deferrals 8-A B-B 8-D 8-F 8-G-1 8-G-2 8-H 8-J 8-K-1 8-L-1 8-L-2 8-M-2 B-N-1 B-N-2 B-N-3 C-A C 8 C.C C-F.1 C-F-2 D-A D.B F-A 164
V t
~ '
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Form NIS-1C Examinations not Performed as Identified in the Inspection Plan Page of Examination Item Item Date of Method of Category Number Description Rescheduled Alternate Examination Exam Performed 165
h I Turkey Point ISI Program Revision 0 Date: August 27, 1993 Form NIS-1D Identification of Items with Flaws Which Reguired Analytical Evaluation for Continued Acceptability Page of Examination Item Item Flaw Flaw Category Number Description Characterization Found (IWA-3300) During Scheduled XI Exam/
Test (Yes or No) 166
t 4 Ea" k Revision 0 Date: August 27, 1993 Form NIS-2A Repair/Replacement Plan Certification Record Page of Repair/Replacement Plan Number Owner's Certificate of Compliance lie certify that the represented by Repair/replacement Plan Number conforms to the rules of the ASHE Code, Section XI.
Type Code Symbol Stamp Certificate of Authorization No. Expiration Date Signed Date Owner or Owner's Designee, Title Certificate of Inservice Inspection I, the undersigned, holding a valid conmission 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 ASHE 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.
Comnissions Inspector's Signature National Board, State, Province, and Endorsements Date 167
0 ha 'A I 1
~ '
II 0'
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Form NIS-2B Abstract of Repairs and Replacements Page of ASHE Repair or Item Description Description Flau Found Date Repair/
Class Replacement of Work During Scheduled Complete Replace Section Xi Plan Number Exam/Test (Yes/No) 168
t
~ I,,1 q ~ 8 il 8 A I II ~ ~
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Relief Request No. 7 A. Component Identification:
ASME Class 1 Examination Category B-J Pressure Retaining Welds in Piping ASME Class 2 Examination Category C-F-1 Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping Examination Category C-F-2 Pressure Retaining Welds in Carbon Steel or Low Alloy Piping B. Testing Requirements:
Exam Item Description Category No.
B-J B9.12 Longitudinal welds NPS 4 or larger B9.22 Longitudinal welds less than NPS 4 C-F-1 C5. 12 Longitudinal Welds in Piping >3/8" Nominal Wall for Piping > NPS 4 C5.22 Longitudinal Welds in Piping >1/5" Nominal Wall Thickness for Piping > NPS 2 and < NPS 4 C5.42 Longitudinal welds in Pipe Branch Connections of Branch Piping > NPS 2 C-F-2 C5.52 Longitudinal Welds in Piping >3/8" Nominal Wall for Piping > NPS 4 C5. 62 Longitudinal Welds in Piping >1/5" Nominal Wall Thickness for Piping > NPS 2 and < NPS 4 C5.82 Longitudinal welds in Pipe Branch Connections of Branch Piping > NPS 2 169
Revision 0 Date: August 27, 1993 C. Relief Requested Relief is requested from the Required Surface and/or Volumetric examination requirements for the following:
1 ~ Class 1 at least a pipe diameter length but no more than 12" of each longitudinal weld intersecting a circumferential weld required to be examined by Categories B-F and B-J.
2 ~ Class 2 2.5t at the intersecting circumferential weld
'equired to be examined under Categories C-F-1 and C-F-2.
D. Basis for Relief Longitudinal welds are fabricated under controlled shop conditions, which produce higher quality and more uniform residual stress patterns. They undergo heat treatment in the shop, which enhances the material properties of the weld and reduces the residual stresses created by welding.
Intergranular stress corrosion cracking (IGSCC) or other corrosion problems have not occurred in PWR austenitic stainless steel or carbon steel piping longitudinal welds to any significant extent due to the non-oxygenated environment.
Results of previous weld inspections throughout the industry indicate 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.
Longitudinal welds have not been shown to be susceptible to any particular degradation mechanism. The only area 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.
The man-rem exposure and cost, associated with the inspection of longitudinal welds is dependent on the time it would take to remove/reinstall insulation and interferences, locate the weld, prepare the weld for examination, and perform the examination.
Based on the above arguments, there is little technical benefit to performing inservice inspections on longitudinal piping welds. Radiation exposure and costs associated with these inspections would be reduced.
170
Turkey Point ISI Program Revision 0 Date: August 27, 1993 E. Alternative Examinations Florida Power and Light will perform the required examinations on the length of longitudinal weld that is normally examined with the intersecting circumferential weld.
The volumetric examinations at the intersection of circumferential and longitudinal welds will include both transverse and parallel scans within the length of longitudinal weld which falls within the circumferential weld examination volume. The examination of intersecting longitudinal welds will be noted to documented as to the extent of the examination.
F. Implementation Schedule Third Inspection Interval G. Attachments None 171
1 f w
~,
~ '
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Relief Request No. 8 A. Component Identification:
Turkey Point Units 3 and 4 Class 1, 2, and 3 Integrally Welded Attachments B. Examination Requirements:
Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition Code Category Code Item Description Number B-K-1 B10.10 Piping B10.20 Pumps B10.30 Valves C-C C3.10 Pressure Vessels C3.20 Piping C3.30 Pumps C3.40 Valves D-A Dl.20 thru Systems in Support of Reactor D1.60 Shutdown Function D-B D2.20 thru Systems in Support of Emergency D2.60 Core Cooling, Containment Heat Removal, Atmosphere Cleanup, and Reactor Residual Heat Removal D-C D3.20 thru Systems in Support of Residual D3.60 Heat Removal from Spent Fuel Storage Pool C. Relic f Requested:
Relief is requested from performing examinations on Class 2, Code Category C-C Integral Attachments, and 'Class 3, Code 172
I Nl >> k A s ' e I d ~ ~ 4 5 hfP g
W
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Categories D-A, D-B, and D-C Integral Attachments in accordance with the 1989 Edition of Section XI requirements.
D. Basis for Relief:
Florida Power and Light has not experienced any significant problems with Integral Attachments in Class 1, 2, and 3 systems in over 40 years of operating experience at Turkey Point.
Turkey Point insulation.
still has numerous areas These areas must be tented and that have asbestos special precautions must be observed during the insulation removal.
Many of the integral attachments are within radiation areas.
The additional exposure required to prepare the areas for examination is significant. If the examination area is covered with asbestos insulation, the additional time required for its removal increase radiation exposure.
Based on the above arguments, there is little technical benefit to performing inservice inspections on the number of integral attachments required by the Code. Reducing the number of integral attachments examined would lower the radiation exposure and costs associated with these examinations.
Code Case N-509 was approved on November 25, 1992. This Code Case reflects the direction Section XI is taking with regard to examinations of Integral Attachments.
E. Alternative Examinations:
Florida Power and Light will perform Surface examinations on 104 of the Integral Attachments of Class 1 and Class 2 vessels, piping, pumps, and valves in accordance with the guidelines of Code Case N-509.
VT-1 examinations will be performed on 104 of the Integral Attachments of Class 3 piping, pumps, and valves.
In the case of multiple vessels of similar design, function, and service, only one integral attachment of only one of the multiple vessels will be examined.
Examinations will be performed on integral attachments when a component, support member deformation (e.g., broken, bent, or 173
4 ill k
Turkey Point ISI Program Revision 0 Date: August 27, 1993 pulled out parts) is identified during operation, refueling, maintenance, examination, inservice inspection, or testing.
F. Implementation Schedule:
Third Inservice Inspection Interval G. Attachments None.
174
L Turkey Point ISI Program Revision 0 Date: August 27, 1993 Relief Request No. 9 Alternative Scheduling of Examinations A. Component Identification:
Turkey Point Units 3 and 4 Class 1, 2, and 3 Components and Supports B. Examination Requirements:
Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition IWB-2420 Successive Inspections IWC-2420 Successive Inspections IWF-2420 Successive Inspections (a) The sequence of component examinations established during the first inspection interval shall be repeated during each successive inspection interval, to the extent practical.
C. Relief Requested:
Florida Power and Light requests relief from repeating the sequence of examinations established during the first interval.
D. Basis for Relief:
Florida Power and Light performed examinations on only Class 1 systems during the first two Periods of the First Interval (1970 Edition of Section XI). During the Third Period, the examinations performed on Class 2 and 3 components and supports were pro-rated for the Interval (1974 Edition with Addenda through Summer 1975).
The sequence of examinations for the majority of the Class 2 and 3 components and supports was established during the Second Interval. The Second Interval examinations covered all Code Classes, unlike the First. Interval.
Optimizing the sequence of examinations reduces the need for personnel to prepare and examine components in essentially the same area several times. The reduction in time and manpower 175
a ae t
E
Turkey Point ISI Program Revision 0 Date: August 27, 1993 required to perform these tasks can be significantly reduced by changing the sequence of examinations.
The problem areas that FPL has identified at Turkey Point receive augmented examinations that exceed Code requirements.
These areas will continue to be monitored on a more frequent basis. The majority of the examination areas at Turkey Point have not demonstrated any flaws.
Changing the sequence of examinations will not affect the safety of the Plants. Reduced activity due to changing the sequence of examinations will lower the number of problems created by the examination activities, preparation, and recovery.
E. Alternative Examination Schedule Florida Power and Light will schedule the same areas for examination that were performed during the Second Interval to the extent practical. The sequence of examinations will be altered to reduce radiation exposure and cost, and allow the examinations, preparation of areas, and the recovery process to be minimized.
F. Implementation Schedule Third Inservice Inspection Interval G. Attachments None 176
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Relief Request No. 10 A. Component Identification:
Turkey Point Units 3 and 4 Class 1 and 2 Borated Bolted Connections Subject to VT-2 Examination Rules for Inservice Inspection of Nuclear Power Plant Components, 1989 Edition IWA-5242 Insulated Components (a) For systems borated for the purpose of controlling reactivity, insulation shall be removed from pressure retaining bolted connections for visual examination VT-2.
t C. Relief Requested:
Florida Power and Light requests relief from removing the insulation from pressure retaining borated bolted connections during VT-2 examinations.
D. Basis for Relief:
Removing the insulation on bolted borated connections will required significant manpower (insulation removal, scaffold, and recovery) and radiation exposure. The System Engineers and others who perform routine surveillance examinations check the entire lines for leakage, movement, or other conditions that, would indicate a problem has occured. These surveillance checks are performed, to a large extent, when the system is in service.
This means the lines are checked on a more frequent basis than required by Code and during a period when system pressure has typically been present for a longer period of time. The ability to detect a leak is greatly enhanced as water, insulation discoloration, or Boron crystals would be evident, since no drying of the area would have occured. This is the same condition being sought-during VT-2 examinations that, would only take place on a scheduled and less frequent basis.
177
'r li
~
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Looking for system leakage during routine system examinations is more cost effective, performs the desired Code examinations, and requires far less radiation dose.
E. Alternative Examinations Florida Power and Light will check bolted connections for leakage when performing routine system examinations:
During the monthly flow path verification by the System Engineer When the unit is offline, a leak inspection is performed inside the containment. per the plant surveillance program (required by Technical Specifications)
These routine surveillances will include looking for the following conditions:
Pooling of water directly under the bolted connections Water leaking from the lowest elevation section of vertical lines containing bolted connections Examining insulation around bolted connections for discoloration or boric acid residue Examination of leakage collection systems to insure their operability When repairs or replacements are made, the examination will be limited to that area of the system Florida Power and Light will perform required and scheduled VT-2 examinations on systems per Code requirements without removal of insulation.
F. Implementation Schedule Third Inservice Inspection Interval G. Attachments None 178
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Appendix H Piping and Instrumentation Drawings Drawing Sheet Drawing Title Number Numbers 5613-M-3018 Condensate Storage System 5614-M-3018 Condensate Storage System 5613-M-3019 1 thru 4 Intake Cooling Water System 5614-M-3019 1 thru 3 Intake Cooling Water System 5613-M-3030 1 thru 5 Component Cooling Water System 5614-M-3030 1 thru 4 Component Cooling Water System 5613-M-3033 Spent Fuel Pool Cooling System 5613-M-3041 1 thru 4 Reactor Coolant System 5614-M-3041 1 thru 4 Reactor Coolant System 5610-M-3046 Chemical and Volume Control System 5613-M-3047 1 thru 3 CVCS Charging, Letdown & RCP seal 5614-M-3047 1 thru 3 CVCS Charging, Letdown & RCP Seal 5613-M-3050 Residual Heat Removal System 5614-M-3050 Residual Heat Removal System 5613-M-3056 Containment Emergency Filter System 5614-M-3056 Containment Emergency Filter System 5613-M-3057 CTMT Normal & Emergency Coolers 5614-M-3057 CTMT Normal & Emergency Coolers 5613-M-3062 1/2 Safety Injection System 5614-M-3062 1/2 Safety Injection System 5613-M-3064 Safety Injection Acc. Sys (CTMT) 5614-M-3064 Safety Injection Acc. Sys (CTMT) 5613-M-3068 Containment Spray System 5614-M-3068 Containment Spray System 5613-M-3072 1/ 3 Main Steam System 5614-M-3072 1/ 3 Main Steam System 5613-M-3074 3, 4 Feedwater System 5614-M-3074 3, 4 Feedwater System 5613-M-3075 1/2 Auxiliary Feedwater System 5614-M-3075 1/2 Auxiliary Feedwater System 179
Turkey Point ISI Program Revision 0 Date: August 27, 1993 Drawing Sheet Drawing Title Number Numbers 5610-M-3075 Auxiliary Feedwater System Turbine Drive for Auxiliary Feedwater Pumps 5610-M-3075 Auxiliary Feedwater System Turbine Drive for Auxiliary Feedwater Pumps t Note: 5610 5613 5614 series denotes both Unit series denotes Unit 3 series denotes Unit 4 3 and 4 180