ML20209C087
| ML20209C087 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 01/31/1987 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20209C042 | List: |
| References | |
| PROC-870131, NUDOCS 8702040199 | |
| Download: ML20209C087 (159) | |
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O LINERICK GENERATING STATION UNIT 1 l AND CONNON PLANT FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM O
PHILADELPHIA ELECTRIC CONPANY 4
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,_ LIMERICK GENERATING STATION UNIT 1 l AND COMMON PLANT FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM TABLE OF CONTENTS
1.0 INTRODUCTION
1.1 General 1.2 Inspection Programs 1.3 Examination and Testing Plano 1.4 ASME Section XI Code Effective Dates 1.5 Schedule of Inservice Inspections
- 1.6 Responsibility
\l 1.7 Records 1.8 Methods of Examination 1.9 Classification of Components 1.10 Repair Program 1.11 Replacement Program ,
l 1.12 Applicable ASME Code Cases 2.0 ASME CODE CLASS 1 COMPONENT INSPECTION PROGRAM 2.1 Identification of ASME Code Class 1 Systems 2.2 Inspection Program for the ASME Code Class 1 Reactor Pressure Vessel 2.3 Examination Plan for the ASME Code Class 1 Reactor Pressure Vessel Rev. 2, 01/87
' s TABLE OF CONTENTS (Cont'd) 2.4 Requests for Relief from ASME Section XI l Requirements - Class 1 Reactor Pressure Vessel 2.5 Inspection Program for ASME Code Class 1 Piping 2.6 Examination Plan for ASME Code Class 1 Piping 2.7 Requests for Relief from ASME Section XI l Requirements - Class 1 Piping 2.8 Inspection Program for ASME Code Class 1 Pumps 2.9 Examination Plan for ASME Code Class 1 Pumps 2.10 Requests for Relief from ASME Section XI l Requirements - Class 1 Pumps 2.11 Inspection Program for ASME Code Class 1 Valves 2.12 Examination Plan for AdME Code Class 1 O Valves 2.13 Requests for Relief from ASME Section XI l Requirements - Class 1 Valves 3.0 ASME CODE CLASS 2 COMPONENT INSPECTION PROGRAM 3.1 Identification of ASME Code Class 2 Systems 3.2 Inspection Program for ASME Code Class 2 Pressure Vessels 3.3 Examination Plan for ASME Code Class 2 Pressure Vessels 3.4 Requests for Relief from ASME Section XI l Requirements - Class 2 Pressure Vessels 3.5 Inspection Program for ASME Code Class 2 Piping 11 - Rev. 2, 01/87
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TABLE OF CONTENTS (Cont'd) 3.6 Examination Plan for ASME Code Class 2 Piping 3.7 Requests for Relief from ASME Section XI l Requirements - Class 2 Piping 3.8 Inspection Program for ASME Code Class 2 Pumps 3.9 Examination Plan for ASME Code Class 2 Pumps 3.10 Requests for Relief from ASME Section XI l Requirements - Class 2 Pumps 3.11 Inspection Program for ASME Code Class 2 Valves 3.12 Examination Plan for ASME Code Class 2 Valves 3.13 Requests for Relief from ASME Section XI l Requirements - Class 2 Valves
() 4.0 ASME CODE CLASS 3 COMPONENT INSPECTION PROGRAM 4.1 Identification of ASME Code Class 3 Systems 4.2 Inspection Program for ASME Code Class 3 Components 4.3 Examination Plan for ASME Code Class 3 Components ,
4.4 Requests for Relief f rom ASME Section XD l Requirements - Class 3 Components i 1 5.0 ASME CODE CLASS MC COMPONENT INSPECTION PROGRAM f 5.1 Inspection Program for ASME Compenents Included in the Primary Containment Boundary I
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LGS ISI PROGRAM TABLE OF CONTENTS (Cont'd)
O 6.0 ASME CODE CLASS 1, 2, & 3 COMPONENT SUPPORT INSPECTION PROGRAM 6.1 General 6.2 Inspection Program for ASME Code Class 1, 2, & 3 Component Supports 6.3 Examination Plan for ASME Code Class 1, 2, & 3 Component Supports 6.4 Requests for Relief From ASME Section XI l Requirements - Class 1, 2, & 3 Component Supports 7.0 ASME CODE CLASS 1, 2, & 3 SAFETY RELATED PUMP TESTING PROGRAM 7.1 General 7.2 Operability Testing Program 7.3 Repairs and Replacements 8.0 ASME CODE CLASS 1, 2, & 3 SAFETY RELATED VALVE G TESTIt4G PROGRAM V
8.1 General 8.2 Operability Testing Program 8.3 Repairs and Replacements l
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('} TABLE OF CONTENTS (Cont'd)
Table No. Title 2.0-1 Inservice Inspection Program ASME Code Class 1 RPV 2.0-2 Reactor Pressure Vessel Relief Request Summary 2.0-3 Inservice Inspection Program ASME Code Class 1 Piping 2.0-4 ASME Code Class 1 Piping Relief Request Summary 2.0-5 Inservice Inspection Program ASME Code Class 1 Pumps 2.0-6 Inservice Inspection Program ASME Code Class 1 Valves 2.0-7 ASME Code Class 1 Valves Relief Request Summary 3.0-1 Inservice Inspection Program O' ASME Code Class 2 Pressure Vessels 3.0-2 ASME Code Class 2 Pressure Vessels Relief : quest Summary 3.0-3 Inservice Inspection Program ASME Code Class 2 Piping 3.0-4 ASME Code Class 2 Piping Relief Request Summary 3.0-5 Inservice Inspection Program ASME Code Class 2 Pumps i
l 3.0-6 ASME Code Class 2 Pumps l Relief Request Summary 3.0-7 Inservice Inspection Program l
ASME Code Class 2 Valves
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(}- TABLE OF CONTENTS (Cont'd) l Table No. Title 4.0-1 Inservice Inspection Program ASME Code Class 3 Components 6.0-1 Inservice Inspection Program ASME Code Class 1, 2, & 3 Component Supports FIGURES Figure No. Title A Sht. 1 Weld Identification (RPV)
A Sht. 2 Weld Identification (RPV)
A Sht. 3 Weld Identification (RPV)
A Sht. 4 Weld Identification (RPV)
A Sht. 5 Weld Identification (RPV)
A Sht. 6 Weld Identification (RPV) 6.4-1 Snubber Boundaries
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' LGS ISI PROGRAM l TABLE OF CONTENTS (Cont'd)
APPENDIXES Appendix A - ASME Section XI Boundary P&ID's:
- 1. ISI-M-01, Main Steam, Rev. 0
- 2. ISI-M-ll, Sht. 1, Emergency Service Water, Rev. 0
- 3. ISI-M-ll, Sht. 2, Emergency Service Water, Rev. 0
- 4. ISI-M-11, Sht. 3, Emergency Service Water, Rev. 0
- 5. ISI-M-12, RHR Service Water, Rev. O
- 6. ISI-M-13, Reactor Enclosure Cooling Water, Rev. 0
- 7. ISI-M-15, Sht. 6, Compressed Air (Service Rev. 1 Air),
- 8. ISI-M-20, Fuel and Diesel Oil Storage and Rev. O Transfer,
- 9. ISI-M-26, Sht. 1, 2, & 3, Plant Process Radiation Rev. O Monitoring,
- 10. ISI-M-40, MSIV Leakage Control System, Rev. 0
- 11. ISI-M-41, Nuclear Boiler, Rev. 0
- 12. ISI-M-42, Nuclear Boiler Vessel Rev. O Instrumentation, Rev. 0
- 13. ISI-M-43, Reactor Recirculation Pump, Rev. 0
- 14. ISI-M-44, Reactor Water Clean-Up, Rev. 0
- 15. ISI-M-47, Control Rod Drive, Hydraulic - Rev. O Part B,
- 16. ISI-M-48, Standby Liquid Control, Rev. 0
- 17. ISI-M-49, Reactor Core Isolation Cooling, Rev. 1
- 18. ISI-M-50, RCIC Pump Turbine, Rev. 0
- 19. ISI-M-51, Sht. 1, Residual Heat Removal, Rev. 0
- 20. ISI-M-51, Sht. 2, Residual Heat Renoval, Rev. 1
- 21. ISI-M-52, Core Spray, Rev. 0
- 22. ISI-M-53, Fuel Pool Cooling and Clean-Up, Rev. 0
- 23. ISI-M-55, High Pressure Coolant Injection, Rev. 1
- 24. ISI-M-56, HPCI Pump Turbine, Rev. 0
- 25. ISI-M-57, Sht. 1, Containment Atmosphere Rev. O Control,
- 26. ISI-M-57, Sht. 2, Containment Atmosphere Rev. O
- Control,
- 27. ISI-M-59, Primary Containment Instrument Gas, Rev. 0
- 28. ISI-M-60, Primary Containment Leak Testing, Rev. 0
- 29. ISI-M-61, Liquid Radwaste Collection, Rev. 0
- 30. ISI-M-87, Sht. 2, Drywell Chilled Water, Rev. 0
- 31. ISI-M-90, Control Enclosure Chilled Water Rev. 0 l
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LGS ISI PROGRAM O I aca'cx os"ra^21"o s'^o" o"'T 1 ^"o coaao" "'^"'
FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM LIST OF EFFECTIVE PAGES SECTION 1.0 NUMBER REVISION DATE l All Pages 2 01/87 r
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(} 1.0 Introduction 1.1 General The First 10-Year Interval for Philadelphia Electric Company's (PECo) Limerick Generating Station Unit 1 and Common Plant shall begin coincident with the start of commercial operation on February 1, 1986. During the interval, the requirements for inservice inspection, repair, and replacement of ASME Code Class 1, 2, and 3 (or equivalent) components and their supports are defined in the following two types of documents:
l Inspection Programs These documents are used to identify all the applicable ASME Section XI Code and augmented requirements.
Included are the augmented requirements established by PECo and those established by regulatory and licensing commitments. Inspection Programs identify the requirements that are to be detailed in the Examination and Testing Plans (see below). Inspection Programs are submitted to the regulatory and enforcement authorities having jurisdiction at Limerick. These documents are described further in Section 1.2.
l Examination and Testing Plans O These documents are used to identify the specific details as to how the various requirements and commitments made in the Inspection Programs are to be met. Examination and Testing Plans are maintained at Limerick with the examination and testing data. These documents are described further in Section 1.3.
1.1-1 Rev. 2, 01/87
LGS ISI PROGRAM O 12 '"seccT'o" raooa^as l The Inspection Programs for Limerick Unit 1 and Common Plant consist of the following:
Inservice Inspection Program (this document)
Augmented Inservice Inspection Program 1.2.1 INSERVICE INSPECTION PROGRAM The Inservice Inspection Program, titled " Limerick Generating Station Unit 1 and Common Plant First 10-Year Interval Inservice Inspection Program", (this document)* identifies the ASME Boiler
& Pressure Vessel Code,Section XI requirements to be in effect at the start of Limerick Unit 1 commercial operation. It identifies the jurisdictional boundaries, the examination and testing requirements, and the general requirements for repairs and replacements for the following:
ASME Code Class 1 Reactor Pressure Vessel (RPV)
ASME Code Class 1, 2, & 3 Piping Systems and their Supports l
ASME Code Class MC Components O -
ASME Code Class 1, 2, & 3 Safety Related Pumps & Valves 1.2.2 AUGMENTED INSERVICE INSPECTION PROGRAM The Augmented Inservice Inspection Program, titled " Limerick Generating Station Unit 1 and Common Plant Augmented Inservice Inspection Program",** identifies additional regulatory and licensing requirements found in the Safety Evaluation Report and Supplements, Regulatory Guides, NUREG's, IE Bulletins. These requirements are identified separately from the Inservice Inspection Program since they are considered additions to the ASME Section XI Code requirements and are subject to change during the first 10-year interval.
The Augmented Inservice Inspection Program also identifies additional examinations to be performed at PECo's option based on manufacturer's recommendations.
1.2-1 Rev. 2, 01/87
(~ } l 1.2.3 Relief Requests The Inspection Programs identify both the areas for which compliance with the applicable requirements can and cannot be achieved. Relief requests and proposed alternative exa.uination methods which provide assurance of system integrity are included in these Programs. In accordance with 10CFR50.55a(g) the relief l requests may be updated as the inservice and augmented examinations are scheduled and performed. The updated relief requests will be addressed by revisions to the applicable Inspection Program.
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- NOTE: This document was originally prepared as Document No.
8031-P-500, Limerick Generating Station Unit 1 First l 10-Year Interval Inservice Inspection Program.
- NOTE: This document was originally prepared as Document No.
8031-P-501, Limerick Generating Station Unit 1 First 10-Year Interval Augmented Inservice Inspection Program.
1.2-2 Rev. 2, 01/87 I
() 1.3 EXAMINATION AND TESTING PLANS There are two Examination and Testing Plans in use at Limerick Unit 1 and Common Plant covering the following major areas:
Inservice Inspection of the ASME Code Class 1 Reactor Pressure Vessel and ASME Code Class 1, 2, & 3 Piping Systems and their Supports Inservice Testing of ASME Code Class 1, 2, & 3 Safety Related Pumps and Valves (8031-M-246A-257) 1.3.1 EXAMIANTION PLAN FOR THE REACTOR PRESSURE VESSEL, NUCLEAR PIPING SYSTEMS, AND THEIR SUPPORTS The Examiantion Plan for the reactor pressure vessel, nuclear piping systems, and their supports titled, " Limerick Generating Station Unit 1 and Common Plant First 10-Year Interval Inservice Inspection Examination Plan", specifies the details as to how the ASME Section XI Code and augmented requirements are to be met.
Included in this document are the schedules, procedures, calibration blocks, and other details necessary to perform the examinations and pressure testing of the Class 1 Reactor Pressure Vessel and Class 1, 2, and 3 piping components and their supports.
(]) l 1.3.2 TESTING PLAN FOR THE SAFETY RELATED PUMPS AND VALVES The Testing Plan for the safety-related pumps and valves, titled
" Pump and Valve Inservice Inspection Program (Testing) Plan for Limerick Generating Station - Unit 1", document number 8031-M-246A-257 specifies the details for the operability testing of safety related pumps and valves to assure their operational readiness.
1.3-1 Rev. 2, 01/87
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(} 1.4 ASME SECTION XI CODE EFFECTIVE DATES In accordance with 10CFR50, the Inspection Programs are in compliance, to the extent practical, with the applicable requirements of the ASME Section XI Code, " Rules for Inservice Inspection of Nuclear Power Plant Components", 1980 Edition with Addenda through Winter 1981.
It should be noted that 10CFR50.55a (b)(2)(iv) provides mandatory and optional criteria for the selection and inspection schedule for Category C-F pressure-retaining welds in Class 2 piping.
These criteria, as stated below, will be used for the selection and scheduling of Category C-F welds at Limerick Unit 1 and Common Plant.
" Pressure-retaining welds in ASME Code Class 2 piping (applies to Tables IWC-2520 or IWC-2510-1, Category C-F).
(A) Appropriate Code Class 2 pipe welds in Residual Heat Removal Systems, Emergency Core Cooling Systems, and Containment Heat Removal Systems shall be examined. The extent of the examination for these systems shall be determined by the requirements of paragraph IWC-1220, Table
.IWC-2520 Category C-F and C-G, and paragraph IWC-2411 in the
] 1974 Edition and Addenda through the Summer 1975 Addenda of Section XI of the ASME Code."
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() (B) "For a nuclear power plant whose application for a construction permit is docketed prior to July 1, 1978, the extent of examination for Code Class 2 pipe welds may be determined by the requirements of paragraph IWC-1220, Table IWC-2520 Category C-F and C-G, and paragrpah IWC-2411 in the 1974 Edition and Addenda through the Summer of 1975 Addenda of Section XI.of the ASME Code or other requirements the Commission may adopt."
1.4-1 Rev. 2, 01/87 i
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LGS ISI PROGRAM 1.5 SCHEDULE OF INSERVICE INSPECTIONS
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The schedule of inservice inspections during the first 10-year inservice inspection interval will meet the requirements of ASME Section XI Paragraph IWB-2412 for the RPV and ASME Code Class 1 piping systems, ASME Section XI Paragraph IWC-2412 for ASME Code Class 2 piping systems, and ASME Section XI Paragraph IND-2410 for ASME Code Class 3 piping systems. In additon, the inservice testing of pumps and valves will meet the requirements of ASME Section XI Paragraphs IWP-3400 and IWV-3400, 3500, and 3600 respectively.
System pressure tests will be scheduled as required to coincide with the surveillance test performed to meet the requirements of the Limerick Technical Specifications.
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1.6 RESPONSIBILITY As Owner of the plant, PECO has the overall responsibility for the performance of the inservice inspections. Certain non-destructive examinations may be performed by a qualified examination agency. The results and evaluation of these i
examinations will be reported to PECo for final evaluation and disposition.
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1.7 RECORDS Records and documentation of all information and inspection results which provide the basis for evaluation and which facilitate comparison with results from previous and subsequent inspections, will be maintained and available for the active life of the plant in accordance with ASME Section XI, IWA-6000.
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() 1.8 METHODS OF EXAMINATION Examination methods to be used for the inservice inspections are l visual, surface, and volumetric. Personnel performing non-destructive examinations will be certified with a written procedure prepared in accordance with ASME Section XI, IWA-2300 and the following documents as applicable for the techniques and methods used:
(1) The American Society for Nondestructive Testing (ASNT),
Recommended Practice No. SNT-TC-1A, June 1980 Edition with Supplements and Appendices (2) American National Standard (ANS), ANSI /ASME N45.2.6, 1978 Edition as modified by Regulatory Guide 1.58, Rev. 1 (3) Limerick Generating Station FSAR, Section 13.1 (pump & valve operability) 1.8.1 VISUAL EXAMINATION i
Visual examinations (VT) will be performed in accordance with ASME Section XI, IWA-2210 which defines four types of VT examinations summarized as follows:
(1) VT-1 examinations shall be conducted to determine the
(]) condition of the part, component, or surface examined. The examination shall determine conditions such as cracks, wear, corrosion, erosion, or physical damage on the surfaces of the part or component. This type of examination may be performed by direct or remote methods as defined in ASME Section XI, IWA-2211.
(2) VT-2 examinations shall be conducted to detect leakage (or abnormal leakage) from pressure-retaining components during i system pressure tests as defined in ASME Section XI, IWA-l 5200.
(3) VT-3 examinations shall be conducted to determine general mechanical and structural conditions of components and their supports such as the presence of loose parts, debris or abnormal corrosion products, wear, erosion, corrosion, and the loss of integrity at bolted or welded connections. This type of examination may be performed remotely with or without optical aids as defined in ASME Section XI, IWA-2213.
i (4) VT-4 examinations shall be conducted to determine conditions l related to operability of components or devices such as l
1.8-1 Rev. 2, 01/87
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(]} mechanical and hydraulic snubbers, component supports, pumps, valves, and spring loaded and constant weight hangers.
1.8.2 SURFACE EXAMINATION A surface examination will be performed in accordance with ASME Section XI, IWA-2220. It is performed to detect the presence of surface cracks or discontinuities. It may be performed by either magnetic particle (MT) or liquid penetrant (PT) techniques where the surface condition, material, and accessibility permit such an examination.
1.8.3 VOLUMETRIC EXAMINATION A volumetric examination will be performed in accordance with ASME Section XI, IWA-2230. It is performed to detect the presence of discontinuities throughout the required volume of material. Radiography (RT) and ultrasonic (UT) are two such volumetric examination techniques.
For volumetric examinations, the major emphasis in this program is placed on the use of UT methods for the following reasons:
(1) Other work can be conducted in the area where UT examinations are being performed thus potentially reducing outage time.
(]) (2) In some locations, background radiation levels would preclude RT examinations.
(3) Methods have been developed to permit remote examination with minimum occupancy time in certain areas.
(4) Records have been obtained utilizing both RT and UT
- examinations to indicate pre-operational conditions for comparison with subsequent examinations.
1.8-2 Rev. 2, 01/87
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1.9 CLASSIFICATION OF COMPONENTS
( ) Components have been classified for purposes of inservice l inspection in accordance with the requirements of 10CFR50, the guidance contained in Regulatory Guide 1.26, Rev. 3, and commitments made in the Final Safety Analysis Report (FSAR). A series of special drawings titled "ASME Section XI Boundary P&ID" and identified as ISI-M-XX (where XX corresponds to the construction P&ID number) have been color coded to define the boundaries of the ASME Code Class 1, 2, & 3 piping systems. Thece ASME Code Classes are assigned to Quality Group A, B, and C systems or portions of systems as required per ASME Section XI IWA-1320, IWA-1400, and 10CFR50. These boundaries (as explained in ISI Note A on the P&ID's) identify the areas where the requirements of ASME Section XI apply in their entirety (including repairs and replacements) as described in this program. Additional ASME Section XI requirements are defined or clarified by other ISI Notes on the P&ID's. ISI Note B is used to annotate the boundary differences between the examination plan for piping and the testing plan for pump and valve operability. ISI Note C is used to identify those systems and portions of systems that were originally constructed to ASME Section III requirements but will now be maintained as Quality Group D. ISI Notes D, E, F, G, (]) and H classify various instrument and sampling lines from the process pipe or component to the instrument. ISI Note I is used to annotate systems or portions of systems where the line design Code Class differs from the Quality Group established in the Final Safety Analysis Report (FSAR). These lines have been l classified in accordance with their quality group and will be examined and maintained accordingly. The use of color coding and notes on the ASME Section XI Boundary P&ID's is to assure that all interfaces with the Authorized Nuclear Inservice Inspector are identified. These ASME Section XI Boundary P&ID's are included in Appendix A. I 1.9-1 Rev. 2, 01/87
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1.10 REPAIR PROGRAM Repairs of ASME Code Class 1, 2, or 3 components will be performed in accordance with ASME Section XI, IWA-4000 by utilizing PECo approved procedures which comply with the Code applicable to the construction of the component. The repair program will meet the requirements of ASME Section XI, IWA-4130 and will be reviewed by an Authorized Nuclear Inservice Inspector (ANII) prior to its implementation. When required, repairs by welding will be subject to surveillance by the ANII who will be notified prior to starting the repair. These repairs will be documented in accordance with ASME Code Case N-308 which requires the completion of a Form NIS-2. Repairs to Class 2 components may invoke Code Case N-416 for the required pressure tests. O i 1 l I 1.10-1 Rev. 2, 01/87
LGS ISI PROGRAM i 1.11 REPLACEMENT PROGRAM Replacement of ASME Code Class 1, 2, or 3 components will be made in accordance with ASME Section XI, IWA-7000. An evaluation of the suitability of the replacement will be conducted prior to installation. If a replacement is required because of failure of an item, the evaluation will consider probable cause(s) of failure to ensure that the selected replacement is suitable. If the cause of failure appears to be a deficiency in the original specification, the specification will be revised to reflect appropriate corrective actions. When required, the installation of a replacement component will be subject to surveillance by the ANII who will be notified prior to starting the installation. These replacements will be documented in accordance with ASME Code Case N-308 which requires the completion of a Form NIS-2. Replacements to Class 2 components may invoke Code Case N-416 for the required pressure tests. O i l 1.11-1 Rev. 2, 01/87 l ( l I 1
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LGS ISI PROGRAM i (} l 1.12 APPLICABLE ASME CODE CASES Several ASME Code Cases are applicable to the implementation of the Limerick Generating Station Unit One and Common Plant Inservice Inspection Program. These Code Cases are as follows: N307 Revised Ultrasonic Examination Volume for Class 1 Bolting, Table IWB-2500-1, Examination Category B-G-1, When the Examinations are Conducted from the Center-Drilled Hole Section XI, Division 1 N308 Documentation of Reapirsand Replacements Components in Nuclear Power Plants Section XI, Division 1 N322 Examination Requirements for Integrally Welded or Forged Attachments to Class 1 Piping at Containment Penetrations Section XI, Division 1 N356 Certification Period for Level III NDE Personnel Section XI, Divisions 1, 2, and 3 N416 Alternative Rules for Hydrostatic Testing of Repair or Replacement of Class 2 Piping () Section XI, Division 1 N426 Extent of VT-1 Examinations, Cateogry B-G-2 of Table IWB-2500-1 Section XI, Division 1 N435 Alternative Examination Requirements for Vessels with Wall Thicknesses of 2" or Less. I 1.12-1 Rev. 2, 01/87 l
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I LGS ISI PROGRAM i l LIFERICK GENERATING STATION UNIT 1 AND COMMON PLANT
. [ >) FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM i
LIST OF EFFECTIVE PAGES ! SECTION 2.0 NUMBER REVISION DATE l All Pages 2 01/87 O I l l l LEP 2.0-1 Rev. 2, 01/87
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(][- 2.0 ASME CODE CLASS 1 COMPONENT INSPECTION PROGRAM 2.1 IDENTIFICATION OF ASME CODE CLASS 1 SYSTEMS The ASME Section XI ISI boundaries for the ASME Code Class 1 Piping Systems are identified in red (non-exempt) and brown (exempt) color coding on the following drawings (Appendix A): ASME Section XI ASME Code Class 1 Systems Boundary P&ID (1) MSIV-Leakage Control System ISI-M-40 (2) Nuclear Boiler ISI-M-41 (3) Nuclear Boiler Vessel Instrumentation ISI-M-42 (4) Reactor Recirculation Pump ISI-M-43 (5) Reactor Water Clean-up ISI-M-44 (6) Standby Liquid Control ISI-M-48 (7) Reactor Core Isolation Cooling ISI-M-49 (8) Residual Heat Removal ISI-M-51 Shts. 1&2 (9) Core Spray ISI-M-52 = (10) High Pressure Coolant Injection ISI-M-55 In compliance with 10CFR50.2(v) and 10CFR50.55(c)(2)(li), the ASME Code Class boundary for these systems includes: (1) the second of two valves in series for lines inside primary containment, and (2) the outermost containment isolation valve in (]) systems which penetrate primary containment. Each normally open valve is capable of automatic closure. In the event of a component failure during normal reactor operation, each valve i remains operable. The closure times are such that the reactor - can be shut down and cooled down in an orderly manner assuming normal makeup capability. The following components (or parts of components) are exempt from selection for volumetric (RT & UT), surface (MT & PT) and/or visual (VT-1 and VT-3 only) inservice examination requirements in
- accordance with ASME Section XI, IWB-1220:
(1) Components and piping less than 1.39" inside diameter (I.D.) for water service and 2.78" I.D. for steam service based on the premise that the amount of fluid lost in the event of a rupture can be replenished by the normal makeup systems which are operable from onsite emergency power. (2) Component connections, piping, and associated valves one inch nominal pipe size and smaller. 2.1-1 Rev. 2, 01/87 a v
LGS ISI PROGRAM s* , O (3) Reactor vessel head connections and associated piping, 2 inch nominal pipe size and smaller, made inaccessible by control rod drive penetrations. I l
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2.2 INSPECTION PROGRAM FOR THE ASME CODE CLASS 1 REACTOR PRESSURE VESSEL 2.2.1 EXAMINATION SCHEDULE The First 10-Year Interval Inservice Inspection Program for the Reactor Pressure Vessel (RPV) shall commence with commercial operation. RPV examinations are scheduled to coincide with normal plant outages and as required by Section 1.5. A detailed examination schedule is included in the " Limerick Generating Station Unit 1 and Common Plant First 10-Year Interval Inservice Inspection Examination Plan". 2.2.2 EXAMINATION CATEGORIES AND REQUIREMENTS Inservice inspections of the RPV shall, to the extent practical within the limitations of design, geometry, materials of construction and radiation considerations, meet the requirements of the ASME Section XI Edition and Addenda specified in Section 1.4. Table 2.0-1 identifies the RPV components subject to examination during the first 10 year interval. This table provides the corresponding Section XI, Table IWB-2500-1 item number, examination category, the required method of examination, acceptance standard for evaluation, and the extent and frequency of examination. (} 2.2.3 EXAMINATION TECHNIQUES AND PROCEDURES i The techniques and procedures for visual, surface, and volumetric examinations shall meet the requirements of Section XI, IWA-2200 as described below. Examinations, conducted in accordance with ASME Section V shall use the 1980 Edition with Addenda through Winter 1981 or later Editions and Addenda. Nondestructive examinations shall be performed using a written procedure. Requirements for written procedures are determined by the referenced Code Section. Appropriate details and requirements may be included in a number of documents like the Examination and Testing Plans referenced in Section 1.3 and/or specific procedures. (1) Visual examinations of RPV components shall be performed in accordance with Section XI, IWA-2210 and Section V, Article
- 9. (See Footnote 3)
(2) Surface examinations of RPV components shall be performed in accordance with Section XI, IWA-2220 and Section V, Article 6 for liquid penetrant examinations or Section V, Article 7 for magnetic particle examinations. (See Footnote 3) 2.2-1 Rev. 2, 01/87 4
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LGS ISI PROGRAM s (' (3) Volumetric examinations of the RPV welds (excluding safe ends) shall be performed by ultrasonic method in accordance with Section XI, IWA-2230 and Section V, Article 4. Verification of instrument calibration per T-431 shall be performed at the beginning and end of each outage that an RPV weld is examined. (See Footnotes 1 & 3) (4) Volumetric examinations of the RPV safe-end welds shall be performed by ultrasonic methods in accordance with Section XI, IWA-2230 and Section V, Article 5. Weld reflectors producing a response greater than 50% of the reference level shall be recorded. Weld reflectors producing a response greater than 100% reference level shall be recorded and investigated to determine the shape, identity, and location and shall be sized to end points producing a response equal to 100% of reference level. Weld reflectors producing a response greater than 100% reference level shall be characterized in accordance with IWA-3000 and evaluated in terms of the appropriate acceptance standard. The calibration standard shall be fabricated from material of the same material specification, product form and heat treatment as one of the materials being examined. Any indication detected in the weld and required volume not readily attributable to geometrical or metallurgical conditions will be recorded regardless of ultrasonic amplitude response and investigated by a Level II or Level III examiner to the extent necessary to determine the shape, identity, and location of the reflector. PECo will disposition and take the appropriate corrective action for any indication investigated and evaluated to be other than geometrical or metallurgical in nature. For indictions determined to be related and intermitant, i.e. geometrical or metallurgical in nature, the shape, identity, and location of the reflector will only be recorded for the peak amplitude response of the related family of indications. (See Footnote 3) (5) When radiography is used, the examinations shall be performed in accordance with Section V, Article 2. (See Footnotes 3, 4) (6) Alternative examination methods, including combinations of visual, surface and/or volumetric methods, or newly developed techniques may be substituted for the above specified methods, provided that the results are demonstrated to be equivalent or superior to those of the specified method. 2.2-2 Rev. 2, 01/87
LGS ISI PROGRAM r (}^ 2.2.4 EVALUATION OF EXAMINATION RESULTS For Class 1 RPV components, the rules of ASME Section XI IWB-3000 shall be used for the evaluation of examination results and the acceptance criteria for continued service. (1) The acceptance criteria for continued service and preservice examination of repairs shall be in accordance with IWB-3000. Where applicable, references to IWB-4000 shall refer to the repair Articles corresponding with the Code classification of the component being repaired. (2) The acceptance criteria for initial service of replacement components shall be in accordance with IWB-3110. (See Footnote 2) 2.2.4.1 FLAW INDICATION CHARACTERIZATION Flaw indications detected during inservice examinations and preservice examinations of repairs shall be characterized in accordance with IWB-3420 and compared with the acceptance standards specified in IWB-3410. Flaw indications detected during preservice examinations of replacement components need only be characterized in accordance with IWB-3400 provided the nondestructive examinations required (]) by the Design Specification have been performed and the applicable acceptance criteria have been met. l 2.2.4.2 ACCEPTANCE STANDARDS The acceptance standards for Class 1 RPV components are summarized in Table 2.0-1. Where acceptance standards are in the course of preparation, the requirements of IWA-3100 shall apply. For flaw indications detected during inservice examinations and preservice examinations of repairs, acceptance by evaluation per IWB-3120 may be performed. Footnotes:
- 1. Additional recording criteria are required per Regulatory Guide 1.150, Rev. 1, for inservice examinations of Section XI, Category B-A and B-D RPV welds. Refer to the Augmented Inservice Inspection Program referenced in Section 1.2.2 for the specific requirements.
2.2-3 Rev. 2, 01/87 3
LGS ISI PROGRAM
/
- 2. Replacements are defined in Section XI, IWA-7100.
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; l 3. Supplemental examination methods or techniques may be used'in the evaluation of a flaw indication. Surface flaws, detected during visual examinations, shall be supplemented by either surface or volumetric examination. Methods for supplemental surface examinations may include a repetition of the visual examination using improved techniques such'as additional cleaning, improved lighting, the.use of optical aids and/or surface replication.
~
l 4. Evaluation shall be in accordance with IWA-3370. An "a" dimension of " length /2" shall be used until such time as supplemental examinations per Footnote 3 are performed. O i 1 i l l 2.2-4 Rev. 2, 01/87 I 1
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w1 TABLE 2.0-1 INSERVICE INSPECTION PROGRAM P ASME CODE CLASS 1 RAV Item Components & Parts Emamination Examination Requirements Cetenory NO. to De Examined Method For First 10-year Interval Remarks /Retief Reauest
; 8- A 81.11 Circumferential Volumetric 100% of circumferential (1) may be enemined at or near shell welds welds per IWB-2412 the end of each inspection interval Includes Fig. No. IW8-2500-1 for essentially 100% of (2) See Relief Request Sub-weld length section 2.4.1 Acceptance Standard IWB-3510 B-A 81.12 Longitudinal shell Volumetric 100% of longitudinal welds (1) May be examined at or near melds per IW8-2412 the end of each inspection interval Includes Fig. No. IW8-2500-2 #
for essentially 100% of (2) See Relief Request Sub-weld length section 2.4.2
=
Acceptance Standard IW8-3510 8-A 81.21 Circumferential Volumetric 100% of circumferential Bottom head welde may be head welds welds per IWB-2412 examined at or near the , and of each inspection Includes Fig. No. IW8-2500-3 interval for essentially 100% acces-sible weld length Acceptance Standard IW8-3510 8-A 81.22 meridional head Volumetric 100% of meridional welds per Bottom head welds may be welds IW8-2412 examined at or near the end of each inspection Includes Fig. No. IW8-2500-3 interval for essentially 100% of accessible weld length Acceptance Standard IW8-3510 8-A 81.30 Shell-to-flange volumetric Includes Fig. No. IW8-2500-4 (1) Includes examination from mold for essentially 100% of weld the flange face. At least length 50% of the weld will be examined by the er.d of the Acceptance Standard first inspection period. IW8-3510 The remainder may be de-forced until the end of the inspection interval (2) See Relief Request Sub-section 2.4.3 T2.0-1(1) Rev. 2. 01/87
[%t LGS ISI PROGRA! r) 0 G Q ~ f%~j . 7 i TABLE 2.0-1 (cont'd) [
, i INSERV!CE INSPECTION PROGRAM ASME CODE CLASS 1 RPV Item Components & Parts Examination Examination Requirements Category No. to be Examined Method For First 10-v_ ear Interval Remarks / Relief Reavest B-A B1.40 Head-to-flange Volumetric Includes Fig. No. IWB-2500-5 -
weld & surface for essentially 100% of weld
. em.- length ~~
Acceptance Standard IWB-3510 l B-A B1.51 Beltline Regions - - There are no repairs l to the beltline region B-D B3.90 Nozzle-to-vessel Volumetric - 100% of nozzle welds per (1) At least 25% but not more welds IWB-2412 than 50% of nozzles will be examined by the end of
~
Includes Fig. No. the first inspection # IWB-2500-7(b) for 100% of period and the remaln-weld length der by the end of the inspection interval Acceptance Standard IWB-3512 (2) See Relief Request Subsection 2.4.4 B-D B3.100 Nozzle inside Volumetric 100% of nozzle radius At least 25% but not more radius section sections per'!WB-2412 50% of nozzles util be examined by the end of the Includes Fig. No, first inspection period IWB-2500-7(b) and the remainder by the end of the inspection interval i Acceptance Standard IWB-3512 ~ B-E B4.11 Vessel nozzles Visus) (VT-2)e 25% of each group of com- The examinations util be partial penetration parable size and function performed when the RPV is welds to be cumuistively exa- pressuriced prior to mined per IWB-2412 operation includes 100% of external surfaces Acceptance Standard IWA-5250 B-E B4.12 Control Rod Drive Visual (VT-2) 25% of each group of com- The examinations will be housing partial parable size and function performed when the RPV is penetration welds to be cumulatively exa- pressurized prior to mined per IWB-2412 operation Includes 100% of external surfaces ' Acceptance Standard IWA-5250 I T2.0-1(2) Rev. 2 01/87
(J"\ LGS ISI PROG ~Af G* Y (& TABLE 2.0-1 (cont'd) INSERVICE INSPECTION PROGRAM ASME C00'E CLASS 1 RPV r~ Item Components & Parts Examination Examination Requirements Cateoory No, to be Examined Method For First 10-vear Interval Remarks / Relief Reauest B-E B4.13 Instrumentation visual (VT-2) 25% of each group of com- The examinations will be nozzles partial parable size and function performed when the RPV is penetration welds to be cumulatively exa- pressurized prior to mined per IwB-2412 operation Includes 100% of enternal surfaces Acceptance Standard IWA-5250 B-F B5.10 Nozzle-to-safe end Volumetric 100% of nozzle-to-safe end (1) May be examined coincident butt welds greater & Surface butt welds per IwB-2412 with nozzle-to-vessel than or equal to welds (see Category 8-D) # 4" NDS Includes Fig. No. IwB-2500-8 for 100% of weld length (2) Includes dissimilar mets) ' Acceptance Standard IwB-3514 welds B-F B5.20 Nozzle-to-safe end Surface 100% of nozzle-to-safe end (1) May be examined coincident butt welds < 4" NPS butt welds per IWB-2412 with nozzle-to-vessel , welds (see category B-D) Includes Fig. NO. IwB-2500-8 for 100% of weld length (2) Includes dissimilar metal welds Acceptance Standard IwB-3514 B5.30 Nozzle-to-safe end - - There are no nozzle-to-I8-F socket welds safe end socket welds 5-G-1 86.10 Closure head nuts Surface 100% of nuts (1) May be examined in place under tension, when con-Includes 100% of accessible nection is disassembled, surfaces (see remarks) or when the bolting is
, removed Acceptance Standard (2) An augmented volumetric IWA-3100(b) examination may be per-formed in accordance with IWA-2240 in place of the surface examination l (3) See Note (3)
T2.0-1(3) Rev. 2. 01/87
A tO LGS ISI PROGRan Q' (O). TAOLE 2.0-1 (cont'd) INSERVICE INSPECTION PROGRAM ASME CODE' CLASS 1 RPV Item Components & Parts Examination Examination Requirements Category No, to be Examined Method For First 10-year Interval Remarks / Relief Reouest 9-G-1 B6.20 Closure studs, in Volumetric 100% of studs place
.. Includes Fig. No. May be examined in place.
Iws-2500-12 under tension, or when connection is assembled Acceptance Standard IwB-3515 B-G-1 B6.30 Closure studs. when Volumetric 100% of studs - removed & Surface Includes Fig. No. IWB-2500-12 Acceptance Standard IwB-3515 - ' B-G-1 B6.40 Threads in flange Volumetric 100% of threaded holes (1) Includes 1" annular area around threaded hole Includes Fig. No. (2) Required only when Iws-2500-12 connection is . disassembled Acceptance Standard Iws-3515 B-G-1 L6.50 Closure washers Visual (VT-1) 100% of washers upon stud (1) May be examined in place, removal under tension, when con-nection is disassembled, Includes 100% of accessible or when the botting is surfaces removed l Acceptance Standard (2) See Note (3) IWA-3100(b) B-G-2 B7.10 Pressure retaining Visual (VT-1) 100% of bolts, studs, & (1) May be examined in place bolts, studs, & nuts nuts under tension, when con-
?" and less in noction is disassembled, diameter includes 100% of accessible or when the bolting is surfaces removed l Acceptance Standard (2) See Note (3)
IwA-3100(b) l B-G-2 87.80 CRD housing bolts, Visual (VT-1) 100% of bolts, studs, & nuts See Note (3) studs, & nuts 2" in each CRD housing when and less in diameter disassembled Acceptance Standard IwA-3100(b) T2.0-1(4) Rev. 2, 01/87
LGS ISI PROGRAsA j ( {O) TABLE 2.0-1 (cent'd) INSERVICE INSPECTION DROGRAM ASME C00E' CLA55 1 RAV r* Item Components & Parts Enamination Examination Requirements Cateoorv Ne, to be Examined Method For First 10-year Interval Remarks / Relief Request B-H 88.10 Integrally welded Surface 100% of the integral attach- For ASME Section XI Fig, attachments with ment welds to the vessel IWB-2500-14 configurations base material design per IWB-2412 a volumetric examination thickness equal to from one side may be sub-or greater than 5/8" stituted in lieu of surface Includes Fig. No, examination IWB-2500-13 15 for essentially 100% of the weld length Acceptance Standard IWB-3516 8-N-1 B13.10 vessel interior Viscal (VT-3) Includes space above and (1) To be examined during the " below reactor core made first refuel outage and sub-i accessible by removal of sequent refuel outages at components during normal approx. 3 year intervals ' refueling outages l Acceptance Standard (2) See Note (3) IWA-3100(b) . 8-N-2 813.20 Interior attach- Visual (VT-1) 100% of accessible attach- (1) May be examined at or near monts within ment welds per IWB-2412 the end of the inspection beltline region interval l Includes the accessible l length for welds within (2) See Note (3) the effective height of the reactor fuel elements Acceptance Standard IWA-3100(b) S-N-2 813.21 Interior attachments Visual (VT-3) 100% of accessible attach- (1) May be examined at or near beyond bottline ment welds par IWB-2412 the end of the inspection region interval Includes the accessible l I 1ength for welds beyond (2) See Note (3) the effective height of the reactor fuel elements Acceptance Standard IWA-3100(b) B-N-2 B13.22 Core Support Visual (VT-3) Accessible surfaces rer (1) May be examined at or near structures IWB-2412 the end of the inspection interval Acceptance Standard l IWA-3100(b) (2) See Note (3) T2.0-1(5) Rev. 2 01/87 I I
,-s LCS ISI PIOGRAM f TABLE 2.0-1 (cont'd)
INSERVICE INSPECTION PROGRAM
,r ASME CCOE CLASS 1 RPV
]' Item Components & Parts Examination Examination Requirements Category No, to be Examined Method For First 10-veer Interval Remarks / Relief Request i' l 9-0 814.10 welds in control - - Exempt per IWB-1220(a) l rod drive housings 8-P B15.10 Pressure retaining Visual (VT-2) System leakage test See Notes (1) & (2) boundary (IWA-5240. IWB-5221) to be performed prior to start-up following eacn refueling outage Acceptance Standard IWA-5250 8-P B15.11 Pressure retaining Visual (VT-2) System hydrostatic test - # boundary (IFA-5240 IWB-5222) to be performed once at or near the end of inspection interval ' Acceptance Standard IwA-5250 I NOTES: (1) The system leakage test pressure boundary shall correspond to the reactor coolant system boundary . with all valves in the normal position which is required for normal reactor operation startup. The VT-2 enemination shall, however, extend to and include the second closed valve at the boundary extremity. (2) A system hydrostatic test (IWS-5222) and the accompanying VT-2 examination are acceptable in lieu of the system leakage test (Iw8-5221) and VT-2 examination. l (3) Acceptance standard in the course of preparation. Refer to Subsection 2.2.4.2. 4 i I l 1 T2.0-1(6) Rev. 2. 01/87
LGS ISI PROGRAM s 2.3 EXAMINATION PLAN FOR THE ASME CODE CLASS 1 REACTOR (s~y. r PRESSURE VESSEL The schedule of examinations for the reactor pressure vessel are detailed in the " Limerick Generating Station Unit 1 and Common Plant First 10-Year Interval Inservice Inspection Examination Plan". The Examination Plan specifies the details as to how the ASME Section XI Code and augmented requirements are to be met. Included are the details relating to component identification, location, access requirements, schedules, procedures, calibration blocks, special equipment, and other items necessary to perform the examination and pressure testing of the ASME Code Class 1 Reactor Pressure Vessel. The scope of the reactor pressure vessel extends up to and includes the nozzle-to-safe end welds or the safe end-to-safe end extension welds. Components that are cubject to augmented inspection requirements are listed a second time in a seperate section of the Examination Plan specifically for identifying and scheduling the augmented requirements. These components are identified by the addition of a "(+)" symbol to the applicable ASME Code Category. O i i l l 2.3-1 Rev. 2, 01/87 O
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.=. . . . . .
LGS ISI PROGRAM i 2.4 p/
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l REQUESTS FOR RELIEF FROM ASME SECTION XI REQUIREMENTS - CLASS 1 REACTOR PRESSURE VESSEL 2.4.1 RELIEF REQUEST 4 RPV shell circumferential welds. 2.4.1.1 REQUIREMENT FROM WHICH RELIEF IS REQUESTED ASME Section XI, Table IWB-2500-1, Category B-A, Item No. Bl.ll requires volumetric examination of the RPV shell circumferential 4 welds. The examination volume is specified in ASME Section XI, Figure No. IWB-2500-1 and includes essentially 100% of the weld length. Ultrasonic examinations shall include the following: (1) Straight beam scan of the base metal through which the angle beams will travel to detect laminar reflectors that may interfere with the angle beam examination per ASME Section V, T-441.4.3 and T-441.7. (2) Straight beam scan of the weld and required volume to detect planar reflectors per ASME Section V, T-441.6. (3) Nominal 45 and 60 degree angle beam scans of the weld and required volume in two directions perpendicular (transverse) l to the weld axis to detect reflectors oriented parallel to the weld per ASME Section V, T-441.5.1. (~) (4) Nominal 45 and 60 degree angle beam scans of the weld and required volume in two opposite directions parallel to the i ' l weld axis to detect reflectors oriented transverse to the weld per ASME Section V, T-441.5.2. Relief is requested from the requirements to examine 100% of the weld and required volume for those welds identified in Table 2.0-
- 2. This table also identifies the scans that are limited and the examination coverage that is achievable with the~ limited scan.
2.4.1.2 JUSTIFICATION Due to the location of the RPV nozzles and biological shield, 100% compliance with the scanning requirements of ASME Section V, T-441 is not possible for portions of shell circumferential welds l AD and AE. A summary of the Code coverage that is achievable is provided in Table 2.0-2. The percentages listed in this table I l quantify the extent requirements. of do They compliance not represent with ASME a totally Section unexamined XI volume. l l r l 2.4-1 Rev. 2, 01/87 l (:) a. 1
LGS ISI PROGRAM [ The interferences, which affect remote automatic ultrasonic 4 O- examinations, will exist through the service lifetime of Unit 1. Manual ultrasonic examination in the relief request areas (see below) yield no appreciable increase to the volumes examined or percentages of Code compliance. In addition, manual examinations in these areas are contrary to PECo's commitment to ALARA and are not justifiable based on radiation considerations. Radiation exposure rates in each interference area are estimated to be in the range of 100 mrem /hr to 3 rem /hr. Except for the areas adjacent to nozzles NllA and NilB on weld seam AD and nozzles N3B, N3D, N12B, and N12D on weld seam AE, all interference areas are examined from the side of the weld opposite the interference. In these areas, scanning limits are extended to provide for the one-sided examinations. Extending the scanning limits assures, as a minimum, that the inner 1/4 thickness of vessel material is examined with two (2) beaming angles from the transverse direction for the entire weld and required volume. 3 The weld and required volume immediately adjacent to the relief request area (weld seam AD in the area of nozzles N11A and NilB and weld seam AE in the area of nozzles N3B, N3D, N12B, and N12D) i are completely examined in accordance with Section XI
- requirements. These areas are subject to the same service
! conditions as the relief request area. This provides reasonable i p. assurance that service-induced flaws will be detected during v inservice examinations. 1 2.4.1.3 ALTERNATE TO ASME SECTION XI REQUIREMENTS , Inservice examinations will be performed using remote automatic 4 ultrasonic examination techniques. The coverage achieved with these techniques represents essentially 100% of the feasible l ~ examination volume within the limits of design, geometry, ' materials of construction, and radiation considerations. Accordingly,. alternate. testing is not planned. Visual examinations, performed during periodic pressure tests and leak detection capabilities included in the plant design are sufficient to assure plant safety. 2.4.2 RELIEF REQUESTS RPV shell longitudinal welds. 2.4.2.1 REQUIREMENT FROM WHICH RELIEF IS REQUESTED ASME Section XI, Table IWB-2500-1, Category B-A, Item No. Bl.12 requires volumetric examination of the RPV shell longitudinal 2.4-2 Rev. 2, 01/87 O
- u. ,
7
l LGS ISI PROGRAM ' i (x welds. The examination volume is specified in ASME Section XI, I (_) Figure No. IWB-2500-2 and includes essentially 100% of the weld I length. Ultrasonic examinations shall include the following: (1) Straight beam scan of the base metal through which the angle beams will travel to detect laminar reflectors that may interfere with the angle beam examination per ASME Section V, T-441.4.3 and T-441.7. (2) Straight beam scan of the weld and required volume to detect planar reflectors per ASME Section V, T-441.6. (3) Nominal 45 and 60 degree angle beam scans of the weld and required volume in two directions perpendicular (transverse) l to the weld axis to detect reflectors oriented parallel to the weld per ASME Section V, T-441.5.1. (4) Nominal 45 and 60 degree angle beam scans of the weld and required volume in two opposite directions parallel to the l weld axis to detect reflectors oriented transverse to the weld per ASME Section V, T-441.5.2. Relief is requested from the requirements to examine 100% of the weld and required volume for those welds identified in Table l 2.0-2. This table also identifies the scans that are limited and the examination coverage that is achievable with the limited {) scan. 2.4.2.2 JUSTIFICATION Due to the configuration of the RPV nozzles and biological shield, 100% compliance with the scanning requirements of ASME Section V, T-441 is not possible for portions of shell longitudinal welds BC, BF, BK, and BM. A summary of the Code coverage that is achievable is provided in Table 2.0-2. The l percentages compliance with listed ASMEin Section this table quantify the extent XI requirements. ofnot
.They do represent a totally unexamined volume.
The interferences, which affect remote automatic ultrasonic examinations, will exist through the service lifetime of Unit 1. Manual ultrasonic examination in the relief request areas (see below) yield no appreciable increase to the volumes examined or percentages of Code compliance. In addition, manual examinations in these areas are contrary to PECo's commitment to ALARA and are not justifiable based on radiation considerations. Radiation exposure rates in each interference area are estimated to be in l the range of 100 mrem /hr to 3 rem /hr. 2.4-3 Rev. 2, 01/87 O e 4;
LGS ISI PROGRAM p Except for the areas adjacent to nozzles N1B and N2F on weld seam BC, Nozzle N17B cn weld seam BF, and the biological shield bracket on weld seams BK and BM, all interference areas are examined from the side of the weld opposite the interferences. In these areas, scanning limits are extended to provide for the one-sided examinations. Extending the scanning limits assures, as a minimum, that the inner 1/4 thickness of vessel material is examined with two (2) beaming angles from the transverse direction for the entire weld and required volume. The weld and required volume immediately adjacent to the relief request area (weld seam BC in the area of nozzles N1B and N2F, weld seam BF in the area of nozzle N17B and weld seams BK and BM in the area of the biological shield bracket) are completely examined in accordance with Section XI requirements. These areas are subject to the same service conditions as the relief request area. This provides reasonable assurance that service-induced flaws will be detected during inservice examinations. 2.4.2.3 ALTERNATE TO ASME SECTION XI REQUIREMENTS Inservice examinations will be performed using remote automatic ultrasonic examination techniques. The coverage achieved with these techniques represents essentially 100% of the feasible examination volume within the limits of design, geometry, materials of construction, and radiation considerations. Accordingly, alternate testing is not planned. Visual examinations, performed during periodic pressure tests and leak detection capabilities included in the plant design are sufficient to assure plant safety. 2.4.3 RELIEF REQUESTS i RPV shell-to-flange weld. 2.4.3.1 REQUIREMENT FROM WHICH RELIEF IS REQUESTED l ASME Section XI, Table IWB-2500-1, Category B-A, Item No. Bl.30 ! requires volumetric examination of the RPV shell-to-flange weld. The examination volume is specified in ASME Section XI, Figure No. IWB-2500-4 and includes essentially 100% of the weld length. Ultrasonic examinations shall include the following: (1) Straight beam scan of the base metal through which the angle beams will travel to detect laminar reflectors that may interfere with the angle beam examination per ASME Section V, T-441.4.3 and T-441.7. 2.4-4 Rev. 2, 01/87
- 1
! -_ _ . _ _ _ _ _ - . . _ . _ . _ . . . _ _ - - - _ _ _ - - - - - - - - - - _ - - - - - - - - ~
LGS ISI PROGRAM i (~}'
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(2) Straight beam scan of the weld and required volume to detect planar reflectors per ASME Section V, T-441.6. (3) Nominal 45 and 60 degree angle beam scans of the weld and required volume in two directions perpendicular (transverse) i l to the weld axis to detect reflectors oriented parallel to the weld per ASME Section V, T-441.5.1. (4) Nominal 45 and 60 degree angle beam scans of the weld and required volume in two opposite directions parallel to the l weld axis to detect reflectors oriented transverse to the weld per ASME Section V, T-441.5.2. (5) Scanning shall be carried out from one side of the weld axis 4 per ASME Section V, T-441.4.4. Relief is requested from the requirements to examine 100% of the weld and required volume for the weld identified in Table 2.0-2. This table also identifies the scans that are limited and the examination coverage that is achievable with the limited scan, 2.4.3.2 JUSTIFICATION Due to the (3) thermocouples, welded in the scan path, 100% compliance with the scanning requirements of ASME Section V, T-441, is not possible for a portion of shell-to-flange weld AF. A l summary of the Code coverage that is achievable is provided in t O Table 2.0-2. The percentages listed in this table quantify the extent of compliance with ASME Section XI requirements. They do not represent a totally unexamined volume. I 2.4.3.3 ALTERNATE TO ASME SECTION XI REQUIREMENTS Manual examination techniques will be used during inservice inspection. The examination coverage includes essentially 100% i of the required volume. Accordingly, alternate testing is not planned. Visual _ examinations, performed during. periodic pressure tests and leak detection capability included in the plant design, are sufficient to assure plant safety. 2.4.4 RELIEF REQUEST RPV nozzle-to-vessel welds. 2.4.4.1 REQUIREMENT FROM WHICH RELIEF IS REQUESTED ( ASME Section XI, Table IWB-2500-1, Category B-D, Item No. B3.90 requires volumetric examination of all full penetration RPV nozzle-to-vessel welds. The examination volume is specified in 2.4-5 Rev. 2, 01/87
LGS ISI PROGRAM r ASME Section XI, Figure No, IWB-2500-7(b) and includes (w"-}h essentially 100% of the weld length. Ultrasonic examinations shall include the following: (1) Straight beam scan of the base metal through which the angle
- beams will travel to detect laminar reflectors that may interfere with the angle beam examination per ASME Section V, T-441.4.3 and T-441.7.
(2) Straight beam scan of the weld and required volume to detect planar reflectors per ASME Section V, T-441.6. (3) Nominal 45 and 60 degree angle beam scans of the weld and required volume in two directions perpendicular (transverse) l to the weld axis to detect reflectors oriented parallel to the weld per ASME Section V, T-441.5.1. 1 (4) Nominal 45 and 60 degree angle beam scans of the weld and required volume in two opposite directions parallel to the l weld axis to detect reflectors oriented transverse to the j weld per ASME Section V, T-441.5.2. (5) Scanning shall be carried out from one side of the weld axis per ASME Section V, T-441.4.4. Relief is requested from the requirements to examine 100% of the
- O weld and required volume for those welds identified in Table 2.0-
- 2. This table also identifies the scans that are limited and the examination coverage that is achievable with the limited scan.
l 2.4.4.2 JUSTIFICATION , Due to RPV nozzle configuration, 100% compliance with the i scanning requirements of ASME Section V, T-441 is not possible for nozzle-to-vessel welds N2B, N2G, N4B, and N4D. A summary of l the Code coverage that is achievable is provided in Table 2.0-2. i The percentages listed in the table quantify the extent of
- l compliance with ASME Section XI requirements. They do not l represent a totally unexamined volume.
4 The interferences, which affect remote automatic ultrasonic examinations, will exist throughout the service lifetime of Unit
- 1. Manual ultrasonic examinations in the relief request areas i
(see below) yield no appreciable increase to the volumes examined or percentage of Code compliance. In addition, manual examinations in these areas are estimated to be in the range of 100 mrem /hr. to 3 rem /hr. i 2.4-6 Rev. 2, 01/87 i 1
LGS ISI PROGRAM s r Except for a portion of the base material of nozzles N2B, N2G, (_]/ and N4B and the area adjacent to nozzle NilB for nozzle-to-
-vessel weld N4D, the scanning limits are extended to provide for a one-sided examination. Extending the scanning limits assures, as a minimum, that the inner 1/4 thickness of vessel and nozzle material is examined with two (2) beaming angles from the transverse direction for the entire weld and required volume.
The weld and required volume immediately adjacent to the relief request areas (portions of the nozzle base material for nozzles N2B, N2G, and N4B, and nozzle-to-vessel weld N4D in the area of nozzle NllB) are completely examined in accordance with Section XI requirements. These areas are subject to the same service conditions as the relief request areas. This provides reasonable assurance that service-induced flaws will be detected during inservice examinations. 2.4.4.3 ALTERNATE TO ASME SECTION XI REQUIREMENTS l Remote automatic examination techniques will be used during inservice inspections. The coverage achieved represents essentially 100% of the feasible examination volume within the limits of design, geometry, materials of construction, and radiation considerations. Accordingly, alternate testing is not planned. Visual examinations, performed during the pressure tests and leak detection capabilities included in the plant {}} design are sufficient to assure plant safety. i l l 2.4-7 Rev. 2, 01/87 O i I
eg LGS ISI P Q TABLE 2.0-2 REACTOR PRESSURE VESSEL RELIEF REQUEST
SUMMARY
(See Note 2)
~
ASME ASME Percent Percent lSectionXI Section XI Component / Esamination Complete Complete Relief I Category Item No. Weld No, Method (Trans) (Para) Request 8-A B1.11 AD Vol 89.9% 100% 2.4.1 8-A Bl.11 AE Vol 89.0% 100% 2.4.1 8-A B1.12 BC Vol 63.7% 100% 2.4.2 . 8-A Bl.12 BF Vol 75.6% 100% 2.4.2 B-A B1.12 BK Vol 49.0% 100% 2.4.2 8-A 81.12 BM Vol 50.1% 100% 2.4.2 8-A 81.30 AF Vol 98.2% 100% 2.4.3 8-0 83.90 N28 Vol 92.1% 100% 2.4.4 8-D B3.90 N2G Vol 92.1% 100% 2.4.4 5-3 83.90 N48 Vol 92.1% 100% 2.4.4 8-D 83.90 N4D Vol 83.7% 100% 2.4.4 e l Vol - Volumetric Trans - Perpendicular to Weld Para - Parallel to Weld w NOTES: l 1. The installation of Nozzle N178 directly through weld seem BF causes a reduction in the length of the l meld. The actual length of weld seam BF is 101.9". All calculations are based on this actual length. .
- 2. The relief request in this table are based on the information prepared for the Limerick Generating Station Unit 1 and Common Plant First 10-Year Interval inservice Inspection Examination Plan. These relief requests may be updated as the inservice esaminations are scheduled and performed.
T2.0-2(1) Rev. 2, 01/87
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LGS ISI PROGRAM 2.5 INSPECTION PROGRAM FOR ASME CODE CLASS 1 PIPING ( 2.5.1 EXAMINATION SCHEDULE The First 10-Year Interval Inservice Inspection Program for Class 1 piping shall commence with commercial operation. Pipe component examinations are scheduled to coincide with normal A detailed l plant outagesschedule examination and as required is included by inSection the Examination 1.5. Plan referenced in Section 2.6. 2.5.2 EXAMINATION CATEGORIES AND REQUIREMENTS Inservice inspections of Class 1 pipe components shall, to the extent practical within the limitations of design, geometry, materials of construction and radiation considerations, meet the requirements of the ASME Section XI Edition and Addenda specified in Section 1.4. Table 2.0-3 identifies the Class 1 pipe components subject to examination during the first 10-year interval. This table provides the corresponding Section XI, Table IWB-2500-1 item number, examination category, the required method of examination, acceptance standard for evaluation, and the extent and frequency of examination. 2.5.3 EXAMINATION TECHNIQUES AND PROCEDURES (]) The techniques and procedures for visual, surface, and volumetric examinations shall meet the requirements of Section XI, IWA-2200 as described below. Examinations, conducted in accordance with ASME Section V shall use the 1980 Edition with Addenda through Winter 1981 or later Editions and Addenda. Nondestructive examinations shall be performed using a written procedure. Requirements for written procedures are determined by the referenced Code Section. Appropriate details and requirements may be included in a number of documents like the Examination and Testing Plans referenced in Section 1.3 and/or specific procedures. (1) Visual examinations of Class 1 pipe components shall be performed in accordance with Section XI, IWA-2210 and Section V, Article 9. (See Footnote 2) (2) Surface examinations of Class 1 pipe components shall be performed in accordance with Section XI, IWA-2220 and Section V, Article 6 for liquid penetrant examinations or Section V, Article 7 for magnetic particle examinations. (See Footnote
- 2)
, 2.5-1 Rev. 2, 01/87 ( E
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LGS ISI PROGRAM (~) (3) Volumetric examinations of Class 1 pipe components, by \_/ ultrasonic methods, shall be in accordance with Section XI, IWA-2230 and Appendix III including Supplement 7 for welds in austenitic materials. Weld reflectors producing a response greater than 50% of reference level shall be recorded. (See Footnote 2) Any indication detected in the weld and required volume not readily attributable to geometrical or metallurgical conditions will be recorded regardless of ultrasonic amplitude response and investigated by a Level II or Level III examiner to the extent necessary to determine the shape, identity, and location of the reflector. PECo will disposition and take the appropriate corrective action for any indication investigated and evaluated to be other than geometrical or metallurgical in nature. For indictions determined to be related and intermitant, i.e. geometrical or metallurgical in nature, the shape, identity, and location of the reflector will only be recorded for the peak amplitude response of the related family of indications. (See Footnote 2) (4) When radiography is used, the examinations shall be performed in accordance with Section V, Article 2. (See Footnotes 2, 3) (5) Alternative examination methods, including combinations of visual, surface and/or volumetric methods, or newly developed techniques may be substituted for the above specified methods, provided that the results are demonstrated to be equivalent or superior to those of the specified method. 2.5.4 EVALUATION OF EXAMINATION RESULTS For Class 1 piping components, the rules of ASME Section XI IWB-3000 shall be used for the evaluation of examination results and the acceptance criteria for continued service. (1) The acceptance criteria for continued service and preservice examinations of repairs shall be in accordance with IWB-3000. Where applicable, references to IWB-4000 shall refer to the repair articles corresponding with the Code classification of the component being repaired. (2) The acceptance criteria for initial service of replacement components shall be in accordance with IWB-3110. (See Footnote 1) 2.5-2 Rev. 2, 01/87 l
LGS ISI PROGRAM l 2.5.4.1 FLAW INDICATION CHARACTERIZATION Flaw indications detected during inservice examinations and preservice examinations of repairs shall be characterized in accordance with IWB-3420 and compared with the acceptance standards specified in IWB-3410. Flaw indications detected during preservice examinations of replacement components need only be characterized in accordance with IWB-3400 provided the non-destructive examinations required by the Design Specification have been performed and the applicable acceptance criteria have been met. l 2.5.4.2 Acceptance Standards The acceptance standards for Class 1 piping components are summarized in Table 2.0-3. Where acceptance standards are in the course of preparation, the requirements of IWA-3100 shall apply. For flaw indications detected during inservice examinations and preservice examinations of repairs, acceptance by evaluation per IWB-3120 may be performed. Footnotes: O l 1. Replacements are defined in Section IX, IWA-7100.
- 2. Supplemental examination methods or techniques may be used in the evaluation of a flaw indication. Surface flaws, detected during visual examinations, shall be supplemented by either surface or volumetric examination. Methods for supplemental surface examinations may include a repetition of the visual examination using improved techniques such as additional cleaning, improved lighting, the use of optical aids and/or surface replication.
- 3. Evaluation shall be in accordance with IWA-3370. An "a" dimension of " length /2" shall be used until such time as supplemental examinations per Footnote 2 are performed.
2.5-3 Rev. 2, 01/87
LCS ISI PROGRAh (x) TAILE 2.0-3 JNSERVICE INSPECTION PROGRAM A5ME CODE CLASS 1 PIPING l Item Components & Parts Examination Enamination Requirements
! Cateeorv No. to be Examineo detnod Foe First 10-veer Interval Remarks / Relief Reavest 9-F B.5.130 Otssimilar metal voeumetric 100% of the welds per (1) See Relief Request butt welds greater and Surface Iw9-2412 Subsection 2.7.1 than or equal to 4- nominal pipe Includes Fig. No. IwB- (2) RPV safe end-to-pipe size NPS 2500-8 for 100% of weld welds may be enemined length coincident with nozzle-to-vessel welds Acceptance Standard (see Table 2.0-1 Iwe-3514 Category B-D) 8-F 85.140 Olssimilar metal Surface 100% of the welds per RPV safe end-to-pipe j
butt melds < 4- IwS-2412 melds may be esamined 4 NPS coincident with nozzle-Includes Fig. No. IwS- to-vessel welds (see 2500-8 for 100% of weld Table 2.0-1 Tength Category B-D) I Acceptance Standard IwS-3514 ,
! S-F 85.150 Dissimilar metal Surface 100% of the welds per i socket meios IwS-2412 .1 Includes Fig. No. ZwS- -
2500-8 for 100% of weld length Acceptance Standard Iws-3514 s-G-1 86.150 Pressure rotatntng - - There are no bolts or bolts and studs, studs > 2" in 4
> 2- in diameter diameter , B-G-1 86.160 Flange surface - -
Not Applicable when connection i disassembled 1 (where bolts are
> 2- in diameter) 4 ; S-G-1 86.170 Pressure retaining - -
Not applicable nuts, bushings and washers (for bolts > 2* in diameter) t
]
i T2.0-3(1) Rev. 2. 01/87 l 1
d5 ISI PROGRA q TACLE 2.0-3 (cont *c) INSERVICE INSPECTION PROGRAM ASME CODE CLA$$ 1 PIPING Item Components & Parts Examination Examination Requirements Catomary No. to ee E=amined wetnod For First 10-year Interval Romerks/ Relief Reauest S-G-2 87.50 Pressure rotatning Visual (VT-1) 100% of botts, stuos. (1) may be examinec in place bolts, stuos. and and nuts per IwS-2412 under tension. onen nuts less than connection is or equal to 2" Includes 100% of disassembled or when NPS accessible surfaces botting is remoweo l Acceptance Standaro (2) See hotes (3) & (4) IwA-3100(b) 8-J 89.11 Circumferenttet volumetric 25% of the circum- (1) See Rettef Request p9pe welcs greater & Surface forential butt melds Subsection 2.7.2 than or equal to per IWS-2412 a NPS l Includes Fig. No. (2) See Note (5) IWS-2500-8 for 100% of weld length Acceptance Standero IwS-3514 . B-J 89.12 Longituotnal pipe volumetric One pipe diameter length See Note (5) welds greater then & Surface but no more than 12 or equal to 4- inches of each longitudinal NPS meld intersecting a circumferential weld subject to enemination Includes Fig. No. IWS-2500-8 Acceptance Stancero IWS-3514 3-J 89.21 Circumferential Surface 25% of the circumferential - pipe melos < 4- butt welds per IWS-2412 kP5 Includes Fig. No. IWS-2500-8 for 100% of weld length Acceptance Standard IwS-3514 3-J 89.22 Longitudinal - - There are no longitudinal pipe melos pipe welde < 4" NPS
<4- NPS.
T2.0-3(2) Rev. 2 01/87
,a LG5 ISI PROG 4A ( (
ss_/ = TaCLE 2.0-3 (cont *d) INSERVICE INSPECTION PROGRAW ASME COIE CLASS
- P! PING Item Components & Parts Enemination Enamination Recutrements Cetenory ho. to be Esa=9ned method For First 10-year Intervat Remarks /Rettef Recuest i B-J 89.31 Branen pipe connec- Volumetric 25% of the branch See Note (5) tion wolos greater & Surface connection joints than or equal to per IwS-2412 4" NPS Includes Fig. Nos.
Ie8-2500-9 -10. & -11 for 100% of weld length Acceptance Standard IwS-3514 l l B-J 89.32 Branch pipe connec- Surface 25% of the branch - tion melds < 4* NPS connection joints per IwS-2412 Includes Fig. Nos. IwS-2500-9 -10. & -13 for 100% of weld length Acceptance Standard . IW8-3514 B-J 89.40 Socket melds Surface 25% of the socket wetos - per IWS-2412 Includes Fig. No. IwS-2500-8 for 100% of weld length. Acceptance Standard IW8-3514 l B-N-1 810.10 Integrally welded Surface Integrally welded attach- (1) For ASME Section XI Fig, l attachments ments to piping that . 1W8-2500-14 conftpura-requires enemination under tion, a volumetric enemi-Category B-J. whose nation from one side may attachment base motorial be substituted in lieu desten th*ckness is of surface eneminetton 5/8 or greater (2) See Relief Request l Includes Fig. Mos. Subsection 2.7.3 IWS-2500-13. -14 & -15 l for 100% of weld length (3) See Note (6) Acceptance Standard IwS-3516 T2.0-3(3) Rev. 2. 01/07
1 LOS ISI PROGRAW g} (p) TCCLE 2.0-3 (cont d) TNSERv!CE INSPECTION PROGRAW ASME CODE' CLASS 1 PIpikG Item Components & Parts Esaminat,1on Emmetnation Requirements Cetencey No. to ne E=a=9aed method For First to-year interval aemarms/melige neovest S-P B15.50 pressure rotatning Visual (VT-2) System teamage test See Notes (1) & (2) boundary (twA-5240. IwS-5221) to
- e. performed prior to plant startup following each refueling outage Acceptance Standero IwA-5250 l 8-P B15.51 Pressure rotatning visual (VT-2) System hydrostatic -
boundary test (ZwA-5240 IwS-5222) to De performed once at or near the end of the inspection interval Acceptance Standard twA-5250 NOTES: (1) The system lemmage test pressure noundary shall correspond to the reactor coolant system boundary .
=tth all walwes in the normal posttton ehtch is required for normal reactor operation startup. The VT-2 esamination ensII. however, entend to and include the second closed valve at the boundary entremity.
(2) A system hydrostatic test (!we-5222) and the accompanying VT-2 esamination are acceptente in lieu of the system leakage test (IWS-5223) and VT-2 esamination. I (3) Solting examinations are Itmited to piping selected f or esamination under Enemination Category 8-J per Code Case h-426. l (4) Acceptance standard in the course of preparation. Refer to Subsection 2.5.4.2. l (5) For welds in caroon and low alloy steel, esamination for transverse reflectors are enly required foe those = elds with reportocle pre-service transverse indicatices. (6) For tntegral attachments eith Dese material design thickness greater than or equal to 5/8*, 25% of I the integral attachments in each system will be examined during the first 10 year interval. ) t T2.0-3(4) Rev. 2. 01/87
LGS ISI PROGRAM 2.6 EXAMINATION PLAN FOR ASME CODE CLASS 1 PIPING The " Limerick Generating Station Unit 1 and Common Plant First 10-Year Interval Inservice Inspection Examination Plan" specifies the details as to how the ASME Seccion XI and the augmented requirements are to be met. Included in the scope of the document are the details relating to component identification, location, access requirements, schedules, procedures, calibration blocks, special equipment, and other items necessary to perform the examination and pressure testing of ASME Code Class 1 piping. Components that are subject to augmented inspection requirements are listed a second time in a separate section of the Examination Plan specifically for identifying and scheduling the augmented requirements. These components are identified by the addition of a "(+)" symbol to the applicable ASME Code Category. O i .f 2.6-1 Rev. 2, 01/87 4
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LGS ISI PROGRAM 2.7 REQUEST FOR RELIEF FROM ASME SECTION XI REQUIREMENTS - O CLASS 1 PIPING 2.7.1 RELIEF REQUEST Dissimilar metal circumferential welds greater than or equal to 4 in. NPS. 2.7.1.1 REQUIREMENT FROM WHICH RELIEF IS REQUESTED ASME Section XI Table IWB-2500-1, Category B-F, Item B5.130 requires volumetric and surface examination of dissimilar metal butt welds in piping greater than or equal to 4 in nominal pipe size (NPS) per Figure No. IWB-2500-8. These examinations are to be performed once per inspection interval. The affected welds are summarized in Table 2.0-4. > 2.7.1.2 JUSTIFICATION i For volumetric examinations, complete Code coverage may not be achievable due to joint configuration / component design. Code coverage is achievable for 100% of the weld metal. Non-parallel OD and ID surfaces in certain valve and fitting designs may preclude complete Code coverage of the component base material adjacent to the weld when using the same calibration techniques. (]) 2.7.1.3 ALTERNATE TO ASME SECTION XI REQUIREMENTS , Required examinations will be performed to the extent practical. l Ultrasonic base metal scans, limited by joint configuration / component designs, may use full vee path calibrations and/or smaller transducers. Difficult configurations may be divided into examinat, ion " zones" requiring a separate calibration in which case an' average material i thickness over the " zone" will be used. Complete Code surface examinations will be performed as required. Visual examinations will be performed during periodic system pressure tests. 2.7.2 RELIEF REQUEST Circumferential welds greater than or equal to 4 in. NPS. 2.7.2.1 REQUIREMENT FROM WHICH RELIEF IS REQUESTED ASME Section XI, Table IWB-2500-1, Category B-J, Item 9.11 requires volumetric and surface examination of preselected circumferential welds in piping greater than or equal to 4 in. NPS per Figure No. IWB-2500-8. These examinations are to be 1 2.7-1 Rev. 2, 01/87 i l t () e ---.r--,y-- y- . - , - ..----.--n.m ,. ,_,,,,-,,__,,,.,,__,,,,...m, o,-. . - _ .-. - - _ , - _ , _ - - , _ _ - , _ , ..
LGS ISI PROGRAM The affected welds are performed once per inspection interval. O summarized in Table 2.0-4. 2.7.2.2 JUSTIFICATION For volumetric examinations, complete Code coverage may not be achievable due to joint configuration / component design. Code coverage is achievable for 100% of weld metal. Non-parallel OD and ID surfaces in certain valve and fitting designs may preclude complete Code coverage of component base matetial adjacent to the weld when using the same calibration techniques. 2.7.2.3 ALTERNATE TO ASME SECTION XI REQUIREMENTS Required examinations will be performed to the extent practical. l Ultrasonic base metal scans, limited by joint configuration / component designs, may use full vee path calibrations and/or smaller transducers. Difficult configurations may be divided into examination " zones" requiring
, a separate calibration in which case an average material thickness over the " zone" will be used. Complete Code surface i
examinations will be performed as required. Visual examinations will be performed during periodic system pressure tests. l 2.7.3 RELIEF REQUEST () Integrally welded pipe attachments i l 2.7.3.1 REQUIREMENT FROM WHICH RELIEF IS REQUESTED l ASME Section XI, Table IWB-2500-1, Category B-K-1, Item B10.10 requires volumetric or surface examination of integrally welded attachments to piping per Figure Nos. IWB-2500-13, -14, or -15 as applicable. These examinations are to be performed once per inspection interval. The affected welded attachments are summarized in Table 2.0-4. l 2.7.3.2 JUSTIFICATION Integrally welded support members are partially obstructed from examination due to the adjacent pipe clamps. A complete examination of the welds would necessitate removal of the clamp from the pipe. This disassembly would involve performing an engineering analysis to ensure supporting adequacy and, in addition, a temporary support may have to be installed. A job of this scope represents an unnecessary risk of an industrial accident, radiation exposure, and extensive expense solely to perform 10% to 30% of the required examination. In view of the minimal benefits to be obtained, it is concluded that pipe clamp 2.7-2 Rev. 2, 01/87
LGS ISI PROGRAM f- removal to meet this Code requirement is impractical at Limerick Unit 1. l 2.7.3.3 ALTERNATE TO ASME SECTION XI REQUIREMENTS Required examinations will be performed to the extent practical. Inaccessible portions of integrally welded support members will be examined completely if the clamp is removed for maintenance or other reasons. Visual examinations will be performed during periodic system pressure tests. O 2.7-3 Rev. 2, 01/87
. -_ .--, , - - . , , , - _ _ , _ _ _ _ . -r - - . - -
LGS ISI PI M }
%./
TAELE 2.0-4 ASME CODE CLASS 1 PIPING RELIEF REQUEST
SUMMARY
(See Note 3) ASME ASME , Percent Relief Section XI Section XI Component / Examination Complete SIC Request Categorv Item No, weld No, Method (See Note 1) (See Note 2) (See Note 4) B-F B5.130 RHA-013 Vol & Sur 85% vol-100% Sur 2 2.7.1 B-F B5.130 RHB-013 Vol & sur 85% Vol-100% Sur 2 2.7.1 B-F B5.130 RHC-013 Vol & Sur 85% vol-100% Sur 2 2.7.1 B-F B5.130 RHD-013 Vol & Sur 85% vol-100% Sur 2 2.7.1 B-F B5.130 CSA-015 Vol & Sur 85% Vol-100% Sur 2 2.7.1 B-J 89.11 FWA-028 Vol & Sur 95% vol-10C% Sur 4 2.7.2 B-J 89.11 Fws-025 Vol & Sur 95% vol-100% Sur 4 2.7.2 B-K-1 B10.10 DCA-105-H2 Sur 90% Sur 3 2.7.3 B-K-1 B10.10 APE-IMS-HA1 Sur 75% Sur 4 2.7.3 B-K-1 B10.10 APE-IMS-HS1 Sur 75% Sur 4 2.7.3 B-K-1 B10.10 APE-!MS-HC1 Sur 75% Sur 4 2.7.3 B-K-1 B10.10 APE-IMS-HDI Sur 75% Sur 4 2.7.3 B-K-1 B10.10 VRR-IRD-HA2 Sur 75% Sur 4 2.7.3 B-K-1 B10.10 VRR-IRD-HB2 Sur 75% Sur 4 2.7.3 B-K-1 B10.10 VRR-IRS-HAT Sur 75% Sur 4 2.7.3 B-K-1 810.10 VRR-IRS-Het Sur 75% Sur 4 2.7.3 Vol - Volume Sur - Surface NOTES:
- 1. The percent complete values listed are based on (1) results of preservice examinations. (2) differences between preservice and inservice Code edition requirements for examination coverage, and (3) improved inservice examination techniques. Refer to the preservice examination records for component description and details of obstructing condition.
- 2. SIC numbers shown correspond to the Safety Impact Categories per the Preservice Inspection Program and.
for convenience. are re-stated below: SIC s2. Reactor coolant pressure boundary weld (RCPB): Weld is normally pressurized during power operation. Inboard containment isolation (or RCPB) valve performs RCPB isolation function. Significant RCPB 1eakage is detected by leak detection systems. The plant can be safely shut down using unaffected systems. SIC a3. RHR shutdown cooling suction line weld between normally closed valves: During normal plant operation. significant leakage is detected by leak detection systems. The plant can be safely shut down using the main condenser and the alternate shutdown cooling method. SIC #4. RCPB weld between the RPV nozzle and the inboard isolation valves: Weld cannot be isolated. RCPB leak detection systeme detect significant leakage. Plant technical specifications require plant shutdown using the normal shutdown methods. l
- 3. The relief requests in this table are based on the information prepared for the Limerick Generating l Station Unit 1 and Common Plant First 10-Year Interval Inservice Inspection Examination Plan. These relief requests may be updated as the inservice examinations are scheduled and performed.
T2.0-4(1) Rev. 2 01/87
4 LGS ISI PT .tB i " i TABLE 2.0-4 (Cent'd) i ASME CODE CLASS 1 PIPING RELTEF REQUEST
SUMMARY
4 t 4 Table 2.0-4 includes the total population of piping supports with integral attachment welds and removable j pipe clamps that may be included in Relief Request 2.7.3 for Examination Category 8-K-1 Item Number
; B10.10. Refer to the examination plan for the identification of integral attachment welds selected for j examination during the first 10-year interval.
l i
)
i 4 4 I i 1 i l l 1 . I 1 l 1 1 I l 4 I e l i ] T2.0-4(2) Rev. 2. 01/87 i 1 i )
l LGS ISI PROGRAM 2.8 INSPECTION PROGRAM FOR ASME CODE CLASS 1 PUMPS 2.8.1 EXAMINATION SCHEDULE The First 10-Year Interval Inservice Inspection Program for Class 1 pumps shall commence with commercial operation. Pump component examinations are scheduled to coincide with normal plant outages and as required by Section 1.5. A detailed examination schedule l 1s included in the Examination Plan referenced in Section 2.9. 2.8.2 EXAMINATION CATEGORIES AND REQUIREMENTS ; Inservice inspection of Class 1 pump components shall, to the extent practical within the limitations of design, geometry, materials of construction and radiation considerations, meet the requirements of the ASME Section XI Edition and Addenda specified in Section 1.4. Table 2.0-5 identifies the Class 1 pump components subject to examination during the first 10-year interval. This table provides the corresponding ASME Section XI, Table IWB-2500-1 item number, examination category, the required 4 method of examination, acceptance standard for evaluation, and the extent and frequency of examination. 2.8.3 EXAMINATION TECHNIQUES AND PROCEDURES The techniques and procedures for visual, surface, and volumetric examinations shall meet the requirements of Section XI, IWA-2200 as described below. Examinations, conducted in accordance with ASME Section V shall use the 1980 Edition with Addenda through
- Winter 1981 or later Editions and Addenda.
Nondestructive examinations shall be performed using a written procedure. Requirements for written procedures are determined by i the referenced Code Section. Appropriate details and requirements may be included in a number of documents like the Examination and Testing Plans referenced in Section 1.3 and/or specific procedures. , (1) Visual examination of Class 1 pump components shall be performed in accordance with Section XI, IWA-2210 and Section V, Article 9. (See Footnote 2) (2) Surface examinations of Class 1 pump components shall be performed in accordance with Section XI, IWA-2220 and Section V, Article 6 for liquid penetrant examinations or Section V, l Article 7, for magnetic particle examinations. (see Footnote l 2) 2.8-1 Rev. 2, 01/87 O
4 1 LGS ISI PROGRAM { I C)~~' (3) Volumetric examinations of Class 1 pump components, by ultrasonic methods, shall be in accordance with ASME Section XI, IWA-2230 and Section V, Article 5. Weld reflectors producing a response greater than 50% of reference level shall be recorded. Weld reflectors producing a response greater than 100% of reference level shall be recorded and investigated to determine the shape, identity and location and shall be sized to end points producing a response equal to 100% of reference level. Weld reflectors producing a response greater than 100% reference level shall be characterized in accordance with IWA-3000 and evaluated in terms of the appropriate acceptance standard. The calibration standard shall be fabricated from material of the same material specification, product form and heat treatment as one of the materials being examined. Any indication detected in the weld and required volume not readily attributable to geometrical or metallurgical conditions will be recorded regardless of ultrasonic amplitude response and investigated by a Level II or Level III examiner to the extent necessary to determine the shape, identity, and location of the reflector. PECo will disposition and take the appropriate corrective action for any indication investigated and evaluated to be other than geometrical or metallurgical in nature. O For indictions determined to be related and intermitant, i.e. geometrical or metallurgical in nature, the shape, identity, and location of the reflector will only be recorded for the peak amplitude response of the related family of indications. (See Footnote 2) (4) When radiography is used, the examinations shall be performed in accordance with Section V, Article 2. (See Footnotes 2,3) , (5) Alternative examination methods, including combinations of visual, surface and/or volumetric methods, or newly developed techniques may be substituted for the above specified methods, provided that the results are demonstrated to be equivalent or superior to those of the specified method. 2.8.4 EVALUATION OF EXAMINATION RESULTS l l For Class 1 pump components, the rules of ASME Section XI IWB-3000 shall be used for the evaluation of examination results and the acceptance criteria for continued service. 2.8-2 Rev. 2, 01/87
LGS ISI PROGRAM O (1) The acceptance criteria for continued service and preservice examination of repairs shall be in accordance with IWL-3000. . Where applicable, references to IWB-4000 shall refer to the repair Articles corresponding with the Code classification of the component being repaired. (2) The acceptance criteria for initial service of replacement components shall be in accordance with INB-3110. (See Footnote 1) l 2.8.4.1 FLAW INDICATION CHARACTERIZATION Flaw indications detected during inservice examinations and preservice examinations of repairs shall be characterized in accordance with IWB-3420 and compared with the acceptance standards specified in IWB-3410. Flaw indications detected during preservice examinations of replacement components need only be characterized in accordance ; with IWB-3400 provided the nondestructive examinations required by the Design Specification have been performed and the applicable acceptance criteria have been met. l 2.8.4.2 ACCEPTANCE STANDARDS ({) The acceptance standards for Class 1 pump components are summarized in Table 2.0-5. i Where acceptance standards are in the course of preparation, the requirements of IWA-3100 shall apply. For flaw indications detected during inservice examinations and preservice examinations of repairs, acceptance by evaluation per INB-3120 may be performed. l Footnotes: l 1. Replacements are defined in Section XI, IWA-7100.
- 2. Supplemental examination methods or techniques may be used in i the evaluation of a flaw indication. Surface flaws, detected
! during visual examinations, shall be supplemented by either l surface or volumetric examination. Methods for supplemental surface examinations may include a repetition of the visual examination using improved techniques such as additional cleaning, improved lighting, the use of optical aids and/or surface replication. 2.8-3 Rev. 2, 01/87
LGS ISI PROGRAM O- 3. Evaluation shall be in accordance with IWA-3370. An "a" dimension of " length /2" shall be used until such time as supplemental examinations per Footnote 2 are performed. I O 2.8-4 Rev. 2, 01/87
. , ~ _ _ . _ _ _ . _ . . - . _ _
TABLE 2.0-5 INSERVICE INSPECTION PROGRAM ASME CdDE CLASS 1 PUMPS Item Components & Parts Examination Examination Requirements Cateoory No, to be Examined Method For First 10-year Interval Remarks / Relief Request B-G-1 B6.180 Pressure retaining - No examination required (1) See Note (3) bolts and studs,
> 2" in diameter B-G-1 86.190 Flange surface for -
No examination required (1) See Note (3) bolting > 2" in diameter when connection is disassembled B-G-1 B6.200 Pressure retaining No examination required (1) See Note (3) nuts, bushings, and washers less than or equal to 2" in diameter B-G-2 B7.60 Pressure retaining - - There are no pump bolts, bolts, studs, and nuts stude, or nuts less less than or equal than or equal to 2" . to 2" in diameter in diameter l B-K-1 810.20 Integrelly welded Surface Integrally welded attachments (1) For ASME Section XI Fig. attachments in each pump Of similar IW8-2500-14 configurations, design whose attachment a volumetric examination base material design from one side may be thickness is 3/8" or substituted in lieu of greater surface examination l Includes Fig. Nos. IwB- (2) See Note (4) 2500-13. -14, & -15 for 100% of weld length Acceptance Standard IWB-3516 5-L-1 B12.10 Pump casing welds - - There are no pump casing welds B-L-2 812.20 Internal surfaces of - - There are no pump casing pump casing welds welds B-P 815.60 Pressure retaining Visual (VT-2) System leakage test See Notes (1) & (2) boundary (ZwA-5240 IwS-5221) to be performed prior to startup following each refueling outage Acceptance Standard IWA-5250 T2.0-5(1) Rev. 2 01/87
f LGS,ISI P7.0G3( ( TABLE 2.0-5 (Cont'd) INSERVICE INSPECTION PROGRAM ASME CdDE CLASS 1 PUMPS Item Components & Parta Examination Examination Requirements Cotooory No. to be Examined Method For First 10-year interval Romerks/ Relief Reauest l B-P 815.61 Pressure retaining Visual (VT-2) System hydrostatic test - boundary (IWA-5240, IWB-5222) to be performed once at or near the end of the inspection interval Acceptance Standard IWA-5250 NOTES: (1) The system leakage test pressure boundary shall correspond to the reactor coolant system boundary with all valves in the normal position which is required for normal reactor operation startup. The VT-2 examination shall, however, extend to and include the second closed valve at the boundary l extremity. (2) A system hydrostatic test (!wS-5222) and the accompanying VT-2 examination are acceptable in lieu of l the system leakage test (IWS-5221) and VT-2 examination. I (3) In accordance with examinstion category 8-G-1, footnote 3 no pump botting examinations are required. j l (4) For integral attachments with base material desten thickness greater than or equal to 5/8", 25% of . i l the integral attachments of one pump will be examined during the first 10 year interval. I i f I l '1 T2.0-5(2) Rev. 2. 01/87
y-; .,.c k[. e . : . . ., . _ . ,y ~
~ ' '
LGS ISI PROGRAM 2.9 EXAMINATION PLAN FOR ASME CODE CLASS 1 PUMPS The " Limerick Generating Station Unit 1 and Common Plant First, 10 year Interval Inservice Inspection Examination Plan" specifies the details as to how the ASME Section XI and the augme~nted requirements are to be met. ' Included in'the scope of the document are the details relating to component identification, location, access requirements, schedules, procedures, calibration blocks, special equipment, and other items necessary to perform the examination and pressure testing of ASME Code Class 1 pumps. Components that are subject to augmented inspection requirements are listed a second time in a separate section of the Examination Plan specifically for identifying and scheduling the augmented requirements. These components are identified by the addition of a "(+)" symbol to the applicable ASME Code Category. O 2.9-1 Rev. 2, 01/87 ( l l l
S- - -- g- k a- - m 4 6 LGS ISI PROGRAM 2.10 O REQUESTS FOR RELIEF FROM ASME SECTION XI REQUIREMENTS - CLASS 1 PUMPS I None. I O 2.10-1 Rev. 2, 01/87 w
l LGS ISI PROGRAM 1
; 2.11 INSPECTION PROGRAM POR ASME CODE CLASS 1 VALVES 2.11.1 EXAMINATION SCHEDULE The First 10-Year Interval Inservice Inspection Program for Class 1 valves shall commence with commercial operation. Valve component examinations are scheduled to coincide with normal A detailed l plant examination outagesschedule and as required is included by in Section the Examination 1.5. Plan referenced in Section 2.12.
2.11.2 EXAMINATION CATEGORIES AND REQUIREMENTS Inservice inspections of Class 1 valve components shall, to the extent practical within the limitations of design, geometry, materials of construction, and radiation considerations meet the requirements of the ASME Section XI Edition and Addenda specified in Section 1.4. Table 2.0-6 identifies the Class 1 valve components subject to examination during the first 10-year interval. This table provides the corresponding ASME Section XI, Table IWB-2500-1 item number, examination category, the required method of examination, acceptance standard for evaluation, and the extent and frequency of examinations. 2.11.3 EXAMINATION TECHNIQUES AND PROCEDURES f]' The techniques and procedures for visual, surface, and volumetric examinations shall meet the requirements of Section XI, IWA-2200 as described below. Examinations, conducted in accordance with ASME Section V, shall use the 1980 Edition with Addenda through Winter 1981 or later Editions and Addenda. Nondestructive examinations shall be. performed using a written procedure. Requirements for written procedures are determined by the referenced Code Section. Appropriate details and requirements may be included in a number of documents like the Examination and Testing Plans referenced in Section 1.3 and/or specific procedures. (1) Visual examinations of Class 1 valve components shall be
. performed in accordance with Section XI, IWA-2210 and Section l V, Article 9. (See Footnote 2)
(2) When performed as a supplemental examination, surface examinations of Class 1 valve components shall be in accordance with Section XI, IWA-2220 and Section V, Article 6 for liquid penetrant examinations or Section V, Article 7, for magnetic particle examinations. (See Footnote 2) 2.11-1 Rev. 2, 01/87 i
-%---.:, , - - - - - - . , - _ . , -, , , _ . ,,._,.,,,,y _-_.,,,_,---.-.-,.,__,.,_,,,.,yr,_ . _ _ _ _ , _ _7__.,,,.,.m.,., . mr,, _ - ,. . - ,,____,--,y,, - , ,--,,
1 LGS ISI PROGRAM l l 3 (3) When performed as a supplemental examination, volumetric examinations of Class 1 valve components, by ultrasonic methods, shall be in accordance with ASME Section XI, INA-2230, and Section V, Article 5. Weld reflectors producing a i response greater than 50% of the reference level shall be recorded. Weld reflectors producing a response greater than 100% of reference level shall be recorded and investigated to determine the shape, identity, and location and shall be sized to end points producing a response equal to 100% of reference level. Weld reflectors producing a response greater than 100% reference level shall be characterized in accordance with IWA-3000 and evaluated in terms of the appropriate acceptance standard. The calibration standard shall be fabricated from material of the same material specification, product form, and heat treatment as one of the materials being examined. Any indication detected in the weld and required volume not readily attributable to geometrical or metallurgical conditions will be recorded regardless of ultrasonic amplitude response and investigated by a Level II or Level III examiner to the extent necessary to determine the shape, identity, and location of the reflector. PECo will , disposition and take the appropriate corrective action for any indication investigated and evaluated to be other than geometrical or metallurgical in nature. For indictions determined to be related and intermitant, i.e. geometrical or metallurgical in nature, the shape, identity, and location of the reflector will only be recorded for the i peak amplitude response of the related family of indications. (See Footnote 2) (4) When radiography is used as a supplemental examination method, the examinations shall be performed in accordance with Section V, Article 2. (See Footnotes 2, 3) (5) Alternative examination methods, including combinations of visual, surface and/or volumetric methods, or newly developed techniques may be substituted for the'above specified methods, provided that the results are demonstrated to be equivalent or superior to those of the specified method. 2.11.4 EVALUATION OF EXAMINATION RESULTS For Class 1 valve components, the rules of ASME Section XI IWB-3000 shall be used for the evaluation of examination results and the acceptance criteria for continued service. 2.11-2 Rev. 2, 01/87
LGS ISI PROGRAM (1) The acceptance criteria for continued service and preservice
)
~A s examination of repairs shall be in accordance with IWB-3000.
Where applicable, references to IWB-4000 shall refer to the repair articles corresponding with the Code classification of the component being repaired. (2) The acceptance criteria for initial service of replacement components shall be in accordance with IWB-3110. (See Footnote 1) l 2.11.4.1 FLAW INDICATION CHARACTERIZATION Flaw indications detected during inservice examinations and . preservice examinations of repairs shall be characterized in accordance with IWB-3420 and compared with the acceptance standards specified in IWB-3410. Flaw indications detected during.preservice examinations of replacement components need only be characterized in accordance with IWB-3400 provided the non-destructive examinations required by the Design Specification have been performed and the applicable acceptance criteria have been met. l 2.11.4.2 Acceptance Standards The acceptance standards for Class 1 valve components are summarized in Table 2.0-6. {} Where acceptance standards are in the course of preparation, the requirements of IWA-3100 shall apply. For flaw indications detected during inservice examinations and f preservice examinations of repairs, acceptance by evaluation per IWB-3120 may be performed. Footnotes: l 1. Replacements are defined in Section IX, IWA-7100. '
- 2. Supplemental examination methods or techniques may be used in !
the evaluation of a flaw indication. Surface flaws, detected during visual examinations, shall be supplemented by either surface or volumetric examination. Methods for supplemental su-face examinations may include a repetition of the visual examination using improved techniques such as additional cleaning, improved lighting, the use of optical aids and/or surface replication. 2.11-3 Rev. 2, 01/87 O
LGS ISI PROGRAM
^i 3. Evaluation shall be in accordance with IWA-3370. An "a" O dimension of " length /2" shall be used until such time as supplemental examinations per Footnote 2 are performed.
'a 2.11-4 Rev. 2, 01/87 O
LGS ISI PI [ ? TABLE 2.0-6 INSERVICE INSPECTION PROGRAM l ASME CODE CLASS 1 VALVES Item Components & Parts Examination Examination Requirements Category No. to be Examined Method For First 10-year Interval a Remarks / Relief Recuest B-G-1 86.210 Pressure retaining - - There are no valve bolts bolts and studs, and studs > 2" in diamet i > 2" in diameter a B-G-1 B6.220 Flange surface for - - Not applicable bolting > 2" in diameter when connection is
, disassembled \ ; B-G-1 B6.230 Pressure retaining - -
Not applicable nuts, bushings, and washers (for bolts j > 2" in diameter) B-G-2 B7.70 Pressure retaining Visual (VT-1) 100% of bolts, studs (1) May be examined in-bolts, studs, & nuts & nuts place under tension. less than or equal Includes 100% of accessible when connection is to 2" in diameter surface disassembled, or who . Acceptance Standard bolting is removed IwA-3100(b) l (2) See Notes (4) & (5) B-K-1 B10.30 Integrally welded - - There are no integrally j attachments welded attachments on valves B-M-1 812.30 valve body welds - - There are no < 4"
<4" NPS NPS valve body welds B-M-1 812.40 Valve body welds - -
There are no greater greater than or than or equal to 4" equal to 4" NPS NPS valve body welds l B-M-2 B12.50 Internal surfaces Visual (VT-3) One valve in each (1) See notes (1) & (5)
; of valve bodies group of valves that
> 4" NPS are of the same con- (2) See Relief Request struction and similar Subsection 2.13.1 function Acceptance Standard IWA-3100(b)
B-P B15.70 Pressure retaining Visual (VT-2) System leakage test See Notes (2) & (3) boundary (IWA-5240 IwB-5221) to be performed prior to startup following each
- refueling outage i
6 j T2.0-6(1) Rev. 2, 01/87 l, i
LGS ISI P ' TAILE 2.0-6 (Cent d) INSERVICE INSPECTION PROGRAM
~
ASME CODE CLASS 1 VALVES P Item Components & Parts Examination Enamination Requirements Category No. to be Emamined Method For First 10-voor Interval Remarks /Retief Recuest ! l Acceptance Standard IWA-5250 l 8-P B15.71 Pressure retaining Visual (VT-2) System hydrostatic test - boundary (IWA-5240 IWS-5222) to be performed once at or near the end of the inspection interval Acceptance Standard IWA-5250 NOTES: (1) The 14 relief valves in the Reactor Coolant Pressure Soundary will be removed for maintenance, in- 1 spection, and testing during each inspection period according to the Limerick Technical ! Specification, requirements. The visual (VT-3) examinations will be performed concurrently with l the valve maintenance schedule for all these valves, j l (2) The system leakage test pressure boundary shall correspond to the reactor coolant system boundary with all valves in the normal position which is required for normal reactor operation startup. . The VT-2 esamination shall, however, entend to and include the second closed valve at the boundary entremity. (3) A system hydrostatic test (!W8-5222) and the accompanying VT-2 examination are acceptable in lieu of the system leakage test (IWB-5221) and VT-2 examination. l (4) In accordance with Code Case N-426 valve bolting esaminations shall be performed concurrently l with those esaminations conducted under Examination Category 0-M-2. l (5) Acceptance standard in the course of preparation. Refer to Subsection 2.11.4.2. T2.0-6(2) Rev. 2 01/87
LGS ISI PROGRAM
't 2.12 EXAMINATION PLAN FOR ASME CODE CLASS 1 VALVES V(~
l The " Limerick Generating Station Unit 1 and Common Plant First 10-Year Interval Inservice Inspection Examination Plan", l specifies the details as to how the ASME Section XI and the augmented requirements are to be met. Included in the scope of the document are the details relating to component identification, location, access requirements, schedules, procedures, calibration blocks, special equipment, and other items necessary to perform the examination and pressure testing of ASME Code Class 1 valves. Components that are subject to augmented inspection requirements are listed a second time in a separate section of the Examination Plan specifically for identifying and scheduling the augmented requirements. These components are identified by the addition of a "(+)" symbol to the applicable ASME Code Category. O l 2.12-1 Rev. 2, 01/87 l
LGS ISI PROGRAM 2.13 REQUEST FOR RELIEF FROM ASME SECTION XI REQUIREMENTS - CLASS 1 VALVES 2.13.1 RELIEF REQUEST ASME Class 1 valves > 4* NPS. 2.13.1.1 REQUIREMENT FROM WHICH RELIEF IS REQUESTED ASME Section XI, Table IWB-2500-1, Category B-M-2, Item B12.50, requires VT-3 examination of the internal pressure boundary surfaces of one valve in each group of valves of the same design, manufacturing method, manufacturer, and function. The ' examinations are to be performed once per inspection interval. l 2.13.1.2 JUSTIFICATION i Valves on the recirculation loop suction piping would require off-loading the fuel elements and draining the reactor prior to disassembly. Work on recirculation pump discharge valves and RHR injection valves would require installation of plugs in the jet pump risers. Preparatory work of this scope is considered impractical for the sole purpose of conducting a VT-3 examination. Contamination levels in the valves associated with the recirculation loops are particularly high due to the physical location of these valves at the bottom of the system. 1 During routine maintenance, when valves are disassembled, VT-3 examinations are performed on valve body internal surfaces. Disassembly of other Code Class 1 valves solely for internal inspection is impractical in view of the fact that most of these valves, particularly the containment isolation valves, are disassembled frequently for maintenance of leak-tightness. Disassembly of these valves solely for VT-3 inspection, in absence of other required maintenance, would be extremely impractical. The cost of personnel exposure, potential hazards, i time and radioactive waste would be excessively high and in direct violation of the concept of "As Low As Reasonably Achievable". j 2.13.1.3 ALTERNATE TO ASME SECTION XI REQUIREMENTS ASME Code Class 1 valves exceeding four inches nominal pipe size are subjected to VT-3 inspection of the internal surfaces of the valve body when disassembled for maintenance in accordance with
. an established program and documented procedures. External surfaces of Class 1 valves will be visually inspected during periodic system pressure tests.
2.13-1 Rev. 2, 01/87 () l I
LGS ISI P t2 TABLE 2.0-7 ASME CODE CLASS 1 VALVE RELIEF REQUEST
SUMMARY
(See Note 2) , ASME ASME Section XI Section XI Component / Enamination Percent SIC Relief 'l Category Item No. Weld No. Method InsCcessible (See Note 1) Request B-M-2 B12.50 Valves > 4* VT-3 See Relief 2 4 2.13.1 NPS Request (Sub-section 2.13.1.3) q NOTES:
- 1. SIC numbers shown correspond to the Safety Impact Categories per the Preservice Inspection Program and, for convenience, are re-stated below:
SIC s2. Reactor coolant pressure boundary weld (RCPS): Wald is normally pressurized during power operation. Inboard containment isolation (or RCPB) valve performs RCPB isolation function. Significant RCPS leakage is detected by leak detection systems. The plant can be safely shut down using unaffected systems. SIC #4 RCPB weld between the RPV nozzle and the inboard isolation valves Wald cannot be isolated. RCPB leak detection systems detect significant leakage. Plant technical specifications require plant shutdown using the normal shutdown methods.
- 2. The relief request in this table are based on information prepared for the Limerick Generating Station Unit 1 and Common Plant First 10-Year Interval Inservice Inspection Enemination Plan. These relief .
requests may be updated as the inservice examinations are scheduled and performed. 3 s 3 1 l T2.0-7(1) Rev. 2 01/87 i
i LGS ISI PROGRAM ' l LIMERICK GENERATING STATION UNIT 1 AND COMMON PLANT FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM LIST OF EFFECTIVE PAGES SECTION 3.0 NUMBER REVISION DATE l All Pages 2 01/87 t 4 O I i i i LEP 3.0-1 Rev. 2, 01/87 i ; I
LGS ISI PROGRAM
] 3.0 ASME CODE CLASS 2 COMPONENT INSPECTION PROGRAM 3.1 IDENTIFICATION OF ASME CODE CLASS 2 SYSTEMS The ASME Section XI ISI boundaries for the ASME Code Class 2 Systems are identified in blue (non-exempt) and orange (exempt) color coding on the following drawings (Appendix A).
ASME Section XI ASME Code Class 2 Systems Boundary P&ID i ' l (1) Main Steam ISI-M-01 l (2) Reactor Enclosure Cooling Water ISI-M-13 1 (3) Compressed Air (Service Air) ISI-N-15 Sht. 6 (4) Plant Process Radiation Monitoring ISI-M-26 Shts. 1,2, & 3 (5) MSIV Leakage Control System ISI-M-40 (6) Nuclear Boiler ISI-M-41 (7) Reactor Water Clean-up ISI-M-44 (8) Control Rod Drive Hydraulic - Part B ISI-M-47 (9) Standby Liquid Control ISI-M-48 (10) Reactor Core Isolation Cooling ISI-M-49 , (11) RCIC Pump Turbine ISI-M-50 (12) Residual Heat Removal ISI-M-51 Shts. 1&2 l (13) Core Spray ISI-M-52 l (14) Fuel Pool Cooling and Clean-up ISI-M-53 ! (15) High Pressure Coolant Injection ISI-M-55 j () (16) HPCI Pump Turbine (17) Containment Atmospheric Control ISI-M-56 ISI-M-57 Shts. 162 4 (18) Primary Containment Instrument Gas ISI-M-59 (19) Primary Containment Leak Testing ISI-M-60 (20) Liquid Radwaste Collection ISI-M-61 (21) Drywell Chilled Water ISI-M-87 Sht. 2 4 The ASME Code Class 2 boundaries are consistent with the USNRC Regulatory Guide 1.26, Rev. 3, Group B quality standards and/or other licensing commitments. i The following components (or parts of components) are exempt from selection for volumetric (RT & UT), surface (MT & PT), and/or
- visual (VT-1 and VT-3, only) inservice examination requirements.in accordance with paragraph IWC-1220 of the 1974 Edition through the Summer of 1975 Addenda of Section XI. (Reference Paragraph l 1.4)
- ;
(1) Components in systems where both the design pressure ! temperature are equal to or less than 275 psig and 200F, ! respectively. , 3.1-1 Rev. 2, 01/87 5 s, . e w w w w w -- w-w--,s-me,--m. v m-, ,-o,-- m --e--,_s-----e
LGS ISI PROGRAM pg. (2) Components in these systems or portions of these systems
\~J other than ECCS, which do not function during normal reactor operation.
(3) Component connections, piping, and associated valves, and vessels (and their supports), that are 4 in. nominal pipe size and smaller. In addition, paragraph IWC-1230 of the 1980 Edition through the Winter of 1981 Addenda of Section XI applies the following exemption: (1) The inaccessible portion of support members and support components that are encased in concrete. l l 3.1-2 Rev. 2, 01/87 l
- _ . -= - .- . . . -- . - - - . - . -
LGS ISI PROGRAM l 3.2 INSPECTION PROGRAM POR ASME CODE CLASS 2 PRESSURE VESSELS { }' 3.2.1 EXAMINATION SCHEDULE The First 10-Year Interval Inservice Inspection Program for Class 2 pressure vessels shall commence with commercial operation. l Pressure vessel component examinations will be performed during normal operation or scheduled to coincide with plant outages and as required by Section 1.5. A detailed examination schedule is i l included in the Examination Plan referenced in Section 3.3. 3.2.2 EXAMINATION CATEGORIES AND REQUIREMENTS Inservice inspections of Class 2 pressure vessel components j thall, to the extent practical within the limitations of design,
- geometry, materials of construction and radiation considerations, meet the requirements of the ASME Section XI Edition and Addenda specified in Section 1.4. Table 3.0-1 identifies the Class 2 pressure vessel components subject to examination during the first 10-year interval. This table provides the corresponding ASME Section XI, Table IWC-2500-1 item number, exanination category, the required method of examination, acceptance standard l for evaluation, and the extent and frequency of examination.
3.2.3 EXAMINATION TECHNIQUES AND PROCEDURES
- () The techniques and procedures for visual, surface, and volumetric examinations shall meet the requirements of Section XI, IWA-2200 i as described below. Examinations, conducted in accordance with i
ASME Section V shall use the 1980 Edition with Addenda through 1 Winter 1981 or later Editions and Addenda. Nondestructive examinations shall be performed using a written procedure. Requirements for written procedures are determined by the referenced Code Section. Appropriate details and
- requirements may be included in a number of documents like the Examination and Testing Plans referenced in Section 1.3 and/or l specific procedures.
l (1) Visual examinations of Class 2 pressure vessel components shall be performed in accordance with Section XI, IWA-2210 and Section V, Article 9. (See Footnote 2) 4 (2) Surface examinations of Class 2 pressure vessel components shall be performed in accordance with Section XI, IWA-2220 l~ and Section V, Article 6 for liquid penetrant examinations or Section V, Article 7 for magnetic particle examinations.(See Footnote 2) , ! 3.2-1 Rev. 2, 01/87 l ( r, . ! \
- i. - - - - - - . - - - - - - . - - b
LGS ISI PROGRAM w (3) Volumetric examinations of Class 2 pressure vessel
# components, by ultrasonic methods, shall be in accordance with ASME Section XI, IWA-2230 and Section V, Article 5.
Weld reflectors producing a response greater than 50% of reference level shall be recorded. Weld reflectors producing a response greater than 100% reference level shall be recorded and investigated to determine the shape, identity, and location and shall be sized to end points producing a response equal to 100% of reference level. Weld reflectors producing a response greater than 100% reference level shall be characterized in accordance with IWA-3000 and evaluated in terms of the appropriate acceptance standard. The calibration standard shall be fabricated from material of the same material specification, product form, and heat treatment as one of the materials being examined. Any indication detected in the weld and required volume not readily attributable to geometrical or metallurgical conditions will be recorded regardless of ultrasonic amplitude response and investigated by a Level II or Level III examiner to the extent necessary to determine the shape,
; identity, and location of the reflector. PECo will disposition and take the appropriate corrective action for any indication investigated and evaluated to be other than l geometrical or metallurgical in nature.
Q For indictions determined to be related and intermitant, i.e. geometrical or metallurgical in nature, the shape, identity, , and location of the reflector will only be recorded for the ! peak amplitude response of the related family of indications. (See Footnote 2) (4) When radiography is used, the examinations shall be performed in accordance with Section V, Article 2. (See Footnotes 2, 3) (5) Alternative examination methods, including combinations of visual, surface and/or volumetric methods, or newly developed techniques may be substituted for the above specified methods, provided that the results are demonstrated to be equivalent or superior to those of the specified method. 3.2.4 EVALUATION OF EXAMINATION RESULTS For Class 2 pressure vessel components, the rules of ASME Section XI IWB-3000 shall be used for the evaluation of examination results and the acceptance criteria for continued service. 3.2-2 Rev. 2, 01/87 ( 1 j o : I
LGS ISI PROGRAM pi (1) The acceptance criteria for continued service and preservice V examinations of repairs shall be in accordance with IWB-3000. Where applicable, references to IWB-4000 shall refer to the repair Articles corresponding with the Code classification of the component being repaired. (2) The acceptance criteria for initial service of replacement components shall be in accordance with IWB-3110. (See Footnote 1) l 3.2.4.1 FLAW INDICATION CHARACTERIZATION Flaw indications detected during inservice examinations and preservice examinations of repairs shall be characterized in accordance with IWB-3420 and compared with the acceptance standards specified in IWB-3410. Flaw indications detected during preservice examinations of replacement components need only be characterized in accordance with IWB-3400 provided the nondestructive examinations required by the Design Specification have been performed and the applicable acceptance criteria have been met. l 3.2.4.2 ACCEPTANCE STANDARDS l The acceptance standards for Class 2 pressure vessel components i (]} are summarized in Table 3.0-1. Where acceptance standards are in the course of preparation, the requirements of IWA-3100 shall apply. For flaw indications detected during inservice examinations and preservice examinations of repairs, acceptance by evaluation per IWB-3120 may be performed. Footnotes: l 1. Replacements are defined in Section XI, IWA-7100.
- 2. Supplemental examination methods or techniques may be used in the evaluation of a flaw indication. Surface flaws, detected during visual examinations, shall be supplemented by either surface or volumetric examination. Methods for supplemental surface examinations may include a repetition of the visual examination using improved techniques such as additional cleaning, improved lighting, the use of optical aids and/or surface replication.
1 3.2-3 Rev. 2, 01/87 ( 1
LGS ISI PROGRAM ,
- 3. Evaluation shall be in accordance with IWA-3370. An "a" Gs> dimension of " length /2" shall be used until such time as supplemental examinations per Footnote 2 are performed.
0 3.2-4 Rev. 2, 01/87
p~s LGS !$1 PI (vf ) TAELE 3.0-1 INSERVICE INSPECTION PROGRAM 7 ASME CODE CLASS 2 PRESSURE VESSELS Item Components & Parts Examination Examination Requirements Category No. to be Examined Method For First 10-voor Interval Remarks / Relief Recuest l C-A C1.10 Snell circum- Volumetric 100% of weld length (1) Applies to welds forential welds at gross structural
-a.
Includes Fig. No. discontinuities as l IWC-2500-1 defined in ASME Section III NS-Acceptance Standard 3213.2 IWB-3511 (2) See relief request subsection 3.4.1 (3) See Note (1) C-A C1.20 Need circum- Volumetric 100% of weld length See Note (1) forential welds Include Fig. No. IWC-2500-1 l Acceptance Standard l IWS-3511 . C-A C1.30 Tube sheet-to- - - There are no tube sheet-shell weld to-shell welds C-8 C2.11 Nozzle-to-shell (or - - There are no nozzle-head) weld in to-shell weld less than vessels less than or equal to 1/2" or equal to 1/2" nominal thickness nominal thickness C-8 C2.21 Nozzle-to-shell (or Volumetric 100% of each weld (1) Manways and hand head) weld without & Surface holes are excluded reinforcing plate in Includes Fig. No. vessel > 1/2" nominal IWC-2500-4(a) (2) See Relief Request thickness Subsection 3.4.2 Acceptance Standard IWB-3512 (3) See Note (1) C-8 C2.22 Nozzle inside radius Volumetric 100% of each inside (1) Manways and hand section without radius holes are excluded reinforcing plates in vessel > 1/2" Includes Fig. No. (2) See Note (1) nominal thickness IWC-2500-4(a) Acceptance Standard
- IWB-3512 C-B C2.31 Reinforcing plate - -
There are no reinforcing welds to nozzle plate welds. and vessel in vessel i i T3.0-1(1) Rev. 2. 01/87 l l l
(b-- 1 [ ) LGS ISI PF/ (/ Y 1 TAELE 3.0-1 (Cont'd) INSERVICE INSPECTION PROGRAM i . ASME CODE CLASS 2 PRESSURE VESSELS .i j Item Components & Parts Examination Examination Requirements
. Category No, to be Examined Method For First 10-year Interval R ema r k s / R e l i e f Request
> 1/2" nominal thickness
-- C-B C2.32 Nozzle-to-shell - -
There are no reinforcing (or head) welds plate welds inside vessel with ! reinforcing plate in vessel > 1/2" nominal thickness l C-C C3.10 Integrally welded Surface Integrally welded (1) See Relief Request attachments attachments whose Subsection 3.4.3 attachment base material design thickness is (2) See Notes (1) & (4) 3/4" or greater Includes Fig. No. IWC-2500-5 I AcceDiance Standard IWB-3516 . C-D C4.10 Pressure retaining - - There are no bolts bolts and stude or studs > 2" in j > 2" in diameter diameter C-H C7.10 Pressure retaining Visual (VT-2) System pressure test (1) See Notes (2) & (3) boundary during system or component functional (2) A system hydrostatic test (IWA-5240. IWC- test (!wC-5222) and 5221) to be performed accompanying VT-2 during each inspection examination are accepta-period in lieu of system pressure test (IWC-5221) Acceptance Standard and VT-2 examination IWA-5250 1 1 i 1 l T3.0-1(2) Rev. 2 01/87 i
_ _ . _ _. . . . .-. _ _. ... . _ _ m, f LGS ISI PA TABLE 3.0-1 (Cent'd) INSERVICE INSPECTION PROGRAM 2 ASME CODE CLASS 2 PRESSURE VESSELS l
- j Item Components & Parts Examination Examination Requirements Catenory No. to be Examined Method For First 10-year Interval Remarks / Relief Raouest C-H C7.20 Pressure retaining Visual (VT-2) System hydrostatic See Note (2)
, boundary test (IWA-5240 ! IWC-5222) to be performed once at or ! near the end of the 1 inspection interval, or during the same inspec-jl tion period of each j inspection interval of Inspection Program B i Acceptance Standard i IWA-5250 i 1 1 l 4 3 i; J I l i 1 i i
}
jl T3.0-1(3) Rev. 2 01/87 1 i
r LGS ISI PR Q ,2 O %./ (r , jy\ TABLE 3.0-1 INSERVICE INSPECTION PROGRAM { ASME CODE CLASS 2 PRESSURE VESSELS
! NOTES:
(1) In the case of multiple vessels of similar design and service, the required examinations may be performed
, on only one vessel or distributed among the vessels.
j ~' (2) The system pressure test boundary includes only those portions of the system required to operate or
)
support the safety system function up to and including the first normally Closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required, except for i the followings
- a. Open-ended portions of systems.
, b. For repairs or replacements within an isolable portion of a system, the boundary for the required 2
pressure test may be limited to the isolable portion. i (3) Includes only those systems or portions of systems not required to operate during normal reactor l operation. (4) For integral attachments greater than or equal to 3/4" base material design thickness. 25% of the integral I attachments of one RHK heat exchanger will be examined during the first 10-year interval, a e i A l I j i i i 1 T3.0-1(4) Rev. 2 01/87 1
LGS ISI PROGRAM 3.3 EXAMINATION PLAN FOR ASME CODE CLASS 2 PRESSURE VESSELS
)
The " Limerick Generating Station Unit 1 and Common Plant First 10-Year Interval Inservice Inspection Examination Plan", specifies the details as to how the ASME Section XI and the , augmented requirements are to be met. Included in the scope of the document are the details relating to component ; identification, location, access requirements, schedules, l procedures, calibration blocks, special equipment, and other items necessary to perform the examination and pressure testing of ASME Code Class 2 pressure vessels. Components that are subject to augmented inspection requirements are listed a second time in a separate section of the Examination Plan specifically for identifying and scheduling the augmented requirements. These components are identified by the addition of a "(+)" symbol to the applicable ASME Code Category. l l l l O l 1 l 3.3-1 Rev. 2, 01/87 1 l -
LGS ISI PROGRAM 3.4 REQUEST FOR RELIEF FROM ASME SECTION XI REQUIREMENTS - CLASS 2 PRESSURE VESSELS 3.4.1 RELIEF REQUEST RHR heat exchanger lAE-205 shell circumferential weld. 3.4.1.1 REQUIREMENT FROM WHICH RELIEF IS REQUESTED ASME Section XI, Table IWB-2500-1, Category C-A, Item C1.10 requires volumetric examination of shell circumferential welds at gross structural discontinuities of one heat exchanger in each group of heat exchangers of similar design, size, and service per Figure No. IWC-2500-1. These examinations are to be performed once per inspection interval. The affected weld is listed in Table 3.0-2. I 3.4.1.2 JUSTIFICATION i Complete Code coverage of weld RHR-HXA-4 is not achievable. UT
- scans, parallel to the weld axis for transverse reflectors, are limited due to the heat exchanger bolting protruding through the vessel flange.
- 3.4.1.3 ALTERNATE TO ASME SECTION XI REQUIREMENTS
() The weld and adjacent base metal will be completely examined from the shell side by UT scans directed transverse to the weld axis for circumferential reflectors. Parallel UT scans will be completed to the extent practical. Visual examinations will be performed during periodic system pressure tests. 3.4.2 RELIEF REQUEST RHR heat exchanger lAE-205 nozzle weld. I 3.4.2.1 REQUIREMENT FROM WHICH RELIEF IS REQUESTED i ASME Section XI, Table IWC-2500-1, Category C-B, Item 2.21 requires volumetric and surface examinations of nozzle welds of one heat exchanger in each group of heat exchangers of similar design, size, and service per Figure No. IWC-2500-4(a). These examinations are to be performed once per inspection interval. The affected weld is listed in Table 3.0-2. 3.4-1 Rev. 2, 01/87
LGS ISI PROGRAM 3.4.2.2 JUSTIFICATION Complete Code coverage of weld RHR-HXA-N3 is not achievable. Transverse UT scans for circumferential reflectors are limited in i two areas, 180 degrees apart, by sock-o-lets welded in the scan path. r 3.4.2.3 ALTERNATE TO ASME SECTION XI REQUIREMENTS The weld and adjacent base metal will be completely examined by parallel UT scans for transverse reflectors. Transverse UT scans will be completed to the extent practical. Complete surface examinations will be performed. Visual examinations will be performed during periodic system pressure tests. 3.4.2 RELIEF REQUEST RHR heat exchanger lAE-205 integrally welded attachments. 3.4.3.1 REQUIREMENT FROM WHICH RELIEF IS REQUESTED ASME SECTION XI Table IWC-2500-1, Category C-C, Item C3.10 requires surface examination of 3/4 in. thick or greater integrally welded attachments to one heat exchanger in each group or heat exchangers of similar design, size, and service per Figure No. IWC-2500-5. These examinations are to be performed O once per inspection interval. are summarized in Table 3.0-2. The affected welded attachments 3.4.3.2 JUSTIFICATION The attachments are boxed structures designed to support the heat exchanger. The top structures, RHR-HXA-1-A, B, C, & D are plate and shell type supports. The attachment welds inside the box are inaccessible due to the insertion of the tie down anchor plates. The bottom structures are linear type su1 ports. The bottom outside attachment welds are inaccessible due to the proximity of j the supporting I-beam. I ! 3.4.3.3 ALTERNATE TO ASME SECTION XI REQUIREMENTS Required examinations will be performed to the extent practical. For the top support attachment welds, each outside weld and adjacent base metal will be completely examined by surface methods. For the bottom support attachment welds, three sides of 4 each outside weld, each inside weld, and the adjacent base metal will be completely examined by surface methods. Visual examinations will be performed during periodic system pressure tests. , 3.4-2 Rev. 2, 01/87 (
/ LGS ISI P'Rp' J M pi V t'd TABLE 3.0-2 ASME CODE CLASS 2 PRESSURE VESSELS RELIEF REQUEST
SUMMARY
(See Note 3) ASME ASME Percent Section XI Section x1 Component / Examination Complete SIC Relief Category item No. weld No. Method (See Note 1) (See Note SJ Reggggt C-A C1.10 RHA-MMA-4 Vol 87.5% vol 1 3.4.1 C-8 C2.21 RHR-HXA-N3 Vol & Sur 98% vot-100% Sur 1 3.4.2 C-C C3.10 RHR-HXA-1-A Sur 100% Outside-0% Inside Sur 1 3.4.3 C-C C3.10 RHR-HXA-1-8 Sur 100% Outside-0% Inside Sur 1 3.4.3 C-C C3.10 RHR-HxA-1-C Sur 100% Outside-0% Inside sur 1 3.4.3 1 C-C C3.10 RHR-HxA-1-D Sur 100% Outside-0% Inside sur 1 3.4.3 . C-C C3.10 RHR-MMA-2-A Sur 75% Outside-100% Inside Sur 1 3.4.3 ! C-C C3.10 RHR-HXA-2-8 Sur 75% Outside-100% Inside Sur 1 3.4.3 C-C C3.10 RHR-HXA-2-C Sur 75% Outside-100% Inside Sur 1 3.4.3 C-C C3.10 RHR-HXA-2-D Sur- 75". Outside-100% Inside Sur 1 3.4.3 l Vol - Volumetric Sur - Surface NOTES: i 1. The percent complete values listed are based on: (1) results of preservice eneminations. (2) differences between preservice and inservice Code edition requirements for examination coverage, and (3) improved in-g service examination techniques. Refer to the preservice examination records for component description and 4 details of obstructing condition.
- 2. SIC numbers shown correspond to the Safety Impact Categories per the preservice Inspection Program and, for convenience, are re-stated below:
SIC *1. RHR system weld / bolted connection outside containment. downstream of pump discharge check valves: During normal plant power operation, weld is unpressurized or slightly pressurized by keep-full systems. Significant leakage may affect pressure boundary of one RHR loop. Significant leakage is detected by leak detection systems or loss of system function. If leak is within the shutdown cooling loop the plant can be safely shutdown using the main condenser j and the unaffected RHR loop.
- 3. The relief requests in this table are based on the information prepared for the Limerick Generating
, Station Unit 1 and Common Plant First 10-Year Interval Inservice Inspection Examination Plan. These reitef requests may be updated as the inservice examinations are scheduled and performed. J J i T3.0-2(1) Rev. 2 01/87 i 4
LGS ISI PROGRAM (" 3.5 INSPECTION PROGRAM FOR ASME CODE CLASS 2 PIPING (_)Y 3.5.1 EXAMINATION SCHEDULE The First 10-Year Interval Inservice Inspection Program for Class 2 piping shall commence with commercial operation. Pipe l component examinations will be performed during normal operation or scheduled to coincide with plant outages and as required by 4 Section 1.5. A detailed examination schedule is include in the Examination Plan referenced in Section 3.6. 3.5.2 EXAMINATION CATEGORIES AND REQUIREMENTS Inservice inspections of Class 2 pipe components shall, to the extent practical within the limitations of design, geometry, materials of construction and radiation considerations, meet the requirements of the ASME Section XI Edition and Addenda specified in Section 1.4. Table 3.0-3 identifies the Class 2 pipe components subject to examination during the first 10-year interval. This table provides the corresponding ASME Section XI, Table IWC-2500-1 item number, examination category, the required method of examination, acceptance standard for evaluation, and the extent and frequency of examination. 3.5.3 EXAMINATION TECHNIQUES AND PROCEDURES The techniques and procedures for visual, surface, and volumetric examinations shall meet the requirements of Section XI, IWA-2200 as described below. Examinations, conducted in accordance with ASME Section V shall use the 1980 Edition with Addenda through Winter 1981 or later Editions and Addenda. Nondestructive examinations shall be performed using a. written procedure. Requirements for written procedures are determined by the referenced Code Section. Appropriate details and requirements may be included in a number of documents like the Examination and Testing Plans referenced in Section 1.3 and/or specific procedures. (1) Visual examinations of Class 2 pipe components shall be performed in accordance with Section XI, IWA-2210 and Section V, Article 9. (See Footnote 2) (2) Surface examinations of Class 2 pipe components shall be performed in accordance with Section XI, IWA-2220 and Section V, Article 6 for liquid penetrant examinations or Article 7, for magnetic particle examinations. (See Footnote 2) 3.5-1 Rev. 2, 01/87
)
LGS ISI PROGRAM (3) Volumetric examinations of Class 2 pipe components, by 03-ultrasonic methods, shall be in accordance with ASME Setion XI, IWA-2230 and Appendix III including Supplement 7 for welds in austenitic materials. Weld reflectors producing a 1 response greater than 50% of reference level shall be recorded. ) Any indication detected in the weld and required volume not l readily attributable to geometrical or metallurgical conditions will be recorded regardless of ultrasonic amplitude response and investigated by a Level II or Level III examiner to the extent necessary to determine the shape, , identity, and location of the reflector. PECo will disposition and take the appropriate corrective action for any indication investigated and evaluated to be other than geometrical or metallurgical in nature. For indictions determined to be related and intermitant, i.e. geometrical or metallurgical in nature, the shape, identity, and location of the reflector will only be recorded for the l peak amplitude response of the related family of indications. t (See Footnote 2) (4) When radiography is used, the examinations shall be performed in accordance with Section V, Article 2. (See Footnotes 2, 3) (5) Alternative examination methods, including combinations of . visual, surface and/or volumetric methods, or newly developed techniques may be substituted for the above specified j methods, provided that the results are demonstrated to be equivalent or superior to those of the specified method. l 3.5.4 EVALUATION OF EXAMINATIONS RESULTS For Class 2 pipe components, the rules of ASME Section XI IWB-3000 shall be used for the evaluation of examination results and , the acceptance criteria for continued service. ! (1) The acceptance criteria for continued service and preservice examination of repairs shall be in accordance with IWB-3000. Where applicable, references to IWB-4000 shall refer to the repair Articles corresponding with the Code classification of
- the component being repaired.
(2) The acceptance criteria for initial service of replacement components shall be in accordance with IWB-3110. (See Footnote 1) l 3.5-2 Rev. 2, 01/87
LGS ISI PROGRAM
. l 3.5.4.1 FLAW INDICATION CHARACTERIZATION Flaw indications detected during inservice examinations and preservice examinations of repairs shall be characterized in accordance with IWB-3420 and compared with the acceptance standards specified in IWB-3410.
Flaw indications detected during preservice examinations of replacement components need only be characterized in accordance with IWB-3400 provided the nondestructive examinations required by the Design Specification have been performed and the applicable acceptance criteria have been met. l 3.5.4.2 ACCEPTANCE STANDARDS The acceptance standards for Class 2 piping components are summarized in Table 3.0-3. Where acceptance standards are in the course of preparation, the requirements of IWA-3100 shall apply. For flaw indications detected during inservice examinations and preservice examinations of repairs, acceptance by evaluation per IWB-3120 may be performed. Footnotes: l 1. Replacements are defined in Section XI, IWA-7100.
- 2. Supplemental examination methods or techniques may be used in the evaluation of a flaw indication. Surface flaws, detected during visual examinations, shall be supplemented by either surface or volumetric examination. Methods for supplemental surface examinations may include a repetition of the visual examination using improved techniques such as additional cleaning, improved lighting, the use of optical aids i nd/or surface replication.
- 3. Evalution shall be in accordance with IWA-3370. An "a" dimension of " length /2" shall be used until such time as supplemental examinations per Footnote 2 are performed.
3.5-3 Rev. 2, 01/87
TA2LE 3.0-3 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 2 pip!NG P Item Components & Parts Enamination Examination Requirements Category No. to de Esamined wetnod For First 10-year Interval Remarks / Relief Reavest
! C-C C3.20 Integrally welded Surface Integrally welded attach- (1) See Relief Request l attachments ments to piping tnat Subsection 3.7.2 reautres enemination under Category C-F. whose attachment (2) See Note (3) base material design thickness is 3/4" or greater Includes Fig. No. IWC-2500-5 Acceptance Standard IWS-3516 C-D C4.20 Pressure rotatning - -
There are no bolts bolts and stude or studs > 2" in
> 2" in diameter diameter C-F C5.11 Circumferential Surface 100% of each weld requiring See Note (1) l welds less than esamination per IWC-2411 I or equal to 1/2" 1974 Edition .
nominal wall thickness Includes Fig. No. IWC-2500-7 Acceptance Standard IWS-3514 C-F C5.12 Longitudine1 meios Surface 2.ht from the edge of the See Note (1) less than or equal intersecting circumferential to 1/2" nominal weld selected per Item No. wall thickness C5.11 Includes Fig. No. IWC-2500-7 Acceptance Standard IwB-3514 - C-F C5.21 Circumferential volumetric 100% of each weld (1) See Notes (1) & (4) welds > 1/2" & surface requiring examination I nominal wall per IWC-2411 1974 Edition (2) See Relief Request thickness Subsection 3.7.1 Includes Fig. No. IWC-2500-7 Acceptance Standard IwB-3514 T3.0-3(1) Rev. 2 01/87
- __ ~ _
TCOLE 3.0-3 (Cont d) INSERVICE INSPECTION PROGRAM ASME CODE CLASS 2 PIPING Item Components & Parts Examinetton Examination Requirements Category No. to be Enemined metnod For First 10-year Interval Remarks / Relief Reauest C-F C5.22 Longitudinal welds Volumetric 2.5t from the edge of the See Notes (1) & (4)
> 1/2" nominal & surface intersecting circumferential l well thtchness weld selected per Item No, C5.21 Includes Fig. No. IWC-2500-7
.! Acceptance Standard IwS-3514 C-F C5.31 Circumferential Surface 100% of each meld requiring See Note (1) pipe branch connec- examination per IWC-2411 tion welds > 4" 1974 Edition
] nominal pipe stae
. Includes Fig. Nos. IWC-2500-9 to and including IWC-2500-13 as applicable Acceptance Standard IwS-3514 C-F C5.32 Longitudinal pipe Surface 2.St from the edge of the See Note (1) branch connection intersection circumferential l welds > 4" nominal weld selected per item No. pipe size C5.31 2500 2&I b- 50b-Acceptance Standard IW5-3514 j C-H C7.30 Pressure retaining boundary Visual (VT-2) System pressure test (1) See Notes (2) & (5) a during system or component j functional test (IWA-5240 (2) A system hydrostatic IwC-5221) to be perforemd test (IWC-5222) and j during each inspection accompanying VT-2 period examination are ! acceptable in lieu of i Acceptance Standard IWA-5250 the system pressure j I test (IWC-5221) and VT-2 enemination 1 I i T3.0-3(2) Rev. 2 01/87 1 ]
m
)
TABLE 3.0-3 (Cant'd)
, INSERVICE INSPECTION PROGRAM
{ ASME CODE CLASS 2 DIPING Item Components & Parts Examination Examination Requirements Category No. to be Enemined method For First 10-year interval Remarks / Relief Recuest C-H C7.40 Pressure retaining Visual (VT-2) System hydrostatic test See Note (2) boundary (IWA-5240 IWC-5222) to be performed once at or near the end of the inspection [ interval, or during the same inspection period of each inspection interval of Inspection Program B Acceptance Standard IWA-5250 NOTES: , l (1) The selection of ASuE Code Class 2 welds shall be performed in accordance with the limitations imposed by l 10CFR50.55a(O)(2)(iv). Piping melds are selected based upon the criteria contained in Category C-F of Table IWC-2520 and paragraph IWC-2411 of the 1974 Edition of ASME Section XI with Addenda through Summer 1975. (2) The system pressure test boundary includes only those portions of the system required to operate or . support the safety system function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required. except for the followings
- a. Open-ended portions of systems,
- n. For repairs or replacements within en teolable portion of a system, the boundary for the required pressure test may be limited to the isolable portion.
, l (3) For integral attachments greater than or equal to 3/4- base material design thickness, 25% of the integral l attachments in each system will be examined during the first 10 year interval.
,l (4) Circumferential and longitudinal welds at certain main steam elbows will be volumetrically examined by radiographic methods, where deemed necessary, ultrasonic methods will be used for diagnostic purposes.
(5) Includes only those systems or portions of systems not required to operate during normal reactor l operation. I i i 1 l i i T3.0-3(3) Rev. 2. 01/87 i
LGS ISI PROGRAM 3.6 EXAMINATION PLAN FOR ASME CODE CLASS 2 PIPING The " Limerick Generating Station Unit 1 and Common Plant First 10-Year Interval Inservice Inspection Examination Plan" specifies the details as to how the ASME Section XI and the augmented requirements are to be met. Included in the scope of the document are the details relating to component identification, location, access requirements, schedules, procedures, calibration blocks, special equipment, and other items necessary to perform the examination and pressure testing of ASME Code Class 2 piping. Components that are subject to augmented inspection requirements are listed a second time in a separate section of the Examination Plan specifically for identifying and scheduling the augmented requirements. These components are identified by the addition of a "(+)" symbol to the applicable ASME Code Category. O l 3.6-1 Rev. 2, 01/87 l
i . LGS ISI PROGRAM 3.7 REQUEST POR RELIEF FROM ASME SECTION XI REQUIREMENTS - O CLASS 2 PIPING l l 3.7.1 RELIEF REQUEST Piping integrally welded attachments l 3.7.1.1 REQUIREMENT FROM WHICH RELIEF IS REQUESTED ASME Section XI, Table IWB-2500-1, Category C-C, Item C3.20 requires surface examination of preselected 3/4 in, thick or greater integrally welded attachments per Figure No. IWC-2500-5. These examinations are to be performed once per inspection interval. The affected welded attachments are summarized in Table 3.0-4. l 3.7.1.2 JUSTIFICATION Component support integral attachment welds are partially obstructed from examination due to the adjacent pipe clamps and/or building structures. A complete examination of the welds
- would necessitate removal of the clamp from the pipe. This
- disassembly would involve performing an engineering analysis to ensure supporting adequacy and, in addition, a temporary support may have to be installed. A job of this scope represents an i
unnecessary risk of an industrial accident, radiation exposure, and extensive expense solely to perform less than 10% of the O required examination. In view of the minimal benefits to be obtained, it is concluded that pipe clamp removal for this ASME Section XI Code requirement is impractical at Limerick Unit 1. Obstructions other than pipe clamps are permanent structures. 3.7.1.3 ALTERNATE TO ASME SECTION XI REQUIREMENTS Required examinations will be performed to the extent practical. Visual examinations will be performed during periodic system pressure tests. Component support lug welds will be examined completely if the clamp is removed for maintenance or other
; reasons.
i i i 4 3.7-1 Rev. 2, 01/87 ( i
O LG3 ISI PRGw r~N g
%j -
j 7ABLE 3.0-4 ASWE CODE CLASS 2 PTPING RELIEF REQUEST
SUMMARY
(See Note 3) - ASME ASME Percent ReIlef Section x1 Section XI Component / Examination Comolete SIC Request Categorv Item No. meio No. metnod (See Note 1) (See Note 2) (See Mete 4) C-C C3.20 E88-121-H902 Sur 70% Sur 1 3.7.1 I C-C C3.20 EBB-106-H10 Sur 90% Sur 15 3.7.1 C-C C3.20 E88-108-M4 Sur 90% Sur 8 3.7.1 C-C C3.20 E88-108-H8 Sur 90% Sur 8 3.7.1 C-C C3.20 E88-108-H22 Sur 90% Sur 8 3.7.1 C-C C3.20 ESB-108-H38 Sur 90% Sur 8 3.7.1 C-C C3.20 E88-109-H9 Sua 90% Sur 8 3.7.1 I C-C C3.20 ESS-129-H4 Sur 90% Sur 8 3.7.1 l C-C C3.20 EBB-129-H5 Sur 70% Sur 8 3.7.1 i C-C C3.20 ESB-129-H43 Sur 90% Sur 8 3.7.1 C-C C3.20 EB8-131-H8 Sur 90% Sur 8 3.7.1 C-C C3.20 EB8-135-H2 Sur 90% Sur 8 3.7.1 C-C C3.20 ESS-135-H25 Sur 90% Sur 8 3.7.1 C-C C3.20 E88-135-H28 Sur 90% Sur 8 3.7.1 C-C C3.20 E88-142-SH-E13 Sur 90% Sur 19 3.7.1 C-C C3.20 E88-142-SH-E19 Sur 90% Sur 19 3.7.1 C-C C3.20 E88-142-SH-E4 Sur 90% Sur 19 3.7.1 C-C C3.20 E88-142-SH-W12 Sur 90% Sur 19 3.7.1 C-C C3.20 E88-142-SH-W18 Sur 90% Sur 19 3.7.1 C-C C3.20 E88-142-SH-w3 Sur 90% Sur 19 3.7.1 C-C C3.20 EC8-111-H1 Sur 90% Sur 18 3.7.1 . C-C C3.20 G88-101-H4 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-101-H18 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-102-H34 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-107-H19 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-108-H4 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-108-M11 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-111-H4 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-112-H37 Sur 90% Sur 14 3.7.1 C-C C3.20 G88-112-H50 Sur 90% Sur 14 3.7.1 C-C C3.20 G88-113-H8 Sur 90% Sur 14 3.7.1 C-C C3.20 G88-113-H9 Sur 90% Sur 14 3.7.1 C-C C3.20 G88-117-H3 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-117-H4 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-117-H6 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-117-H2O Sur 90% Sur 1 3.7.1 C-C C3.20 G88-118-H1 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-118-H8 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-118-H11 Sur 90% Sur 1 3.7.1 C-C C3.20 Gs8-118-H16 Sur 90% Sur 1 3.7.1 C-C C3.20 GSS-118-H17 Sur 90% Sur 1 3.7.1 C-C C3.20 GS8-118-H49 Sur 90% Sur 1 3.7.1 C-C C3.20 GS8-118-H73 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-118-H80 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-119-H2 Sur 70% Sur 1 3.7.1 C-C C3.20 GSS-119-H11 Sur 90% Sur 1 3.7.1 vol - volumetric Sur - Surface T3.0-4(1) Rev. 2 01/87
([]) 'c5252*a(ll>= (^! s_- TABLE 3.0-4 ASME CODE CLASS 2 Pip!NG RELIEF REQUEST SummaRv (See Note 3) ASME ASME Percent Relief Section x! Section x! Component / Enamination Complete SIC Roguest Category item ho. weld No. wethod (See Note 1) (See Note 2) (See Note 4) l C-C C3.20 G88-119-H12 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-119-H17 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-119-H18 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-119-H27 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-119-H32 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-119-H41 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-119-H44 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-119-H60 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-119-H68 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-119-H95 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-119-H100 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-120-H7 Sur 90% Sur 1 3.7.1 C-C C3.20 G88-120-H8 Sur 90% Sur 1 3.7.1 C-C C3.20 H88-101-H1 Sur 90% Sur 8 3.7.1 C-C C3.20 H88-108-H3A Sur 90% Sur 8 3.7.1 C-C C3.20 H88-108-H4 Sur 90% Sur 8 3.7.1 C-C C3.20 M68-108-H5 Sur 90% Sur 8 3.7.1 l C-C C3.20 M88-117-H1 Sur 90% Sur 11 3.7.1 l C-C C3.20 H88-117-HS Sur 90% Sur 11 3.7.1 C-C C3.20 M88-117-H18 Sur 90s Sur 11 3.7.1 C-C C3.20 Nf8-117-H19 Sur 90% Sur 11 3.7.1 C-C C3.20 M88-117-H21 Sur 90% Sur 11 3.7.1 C-C C3.20 H88-117-H22 Sur 90% Sur 11 3.7.1 C-C C3.20 M88-118-H1 Sur 90% Sur 3 3.7.1 C-C C3.20 M88-118-H3 Sur 90% Sur 3 3.7.1 C-C C3.20 M88-118-H35 Sur 90% Sur 3 3.7.1 C-C C3.20 H88-118-H40 Sur 90% Sur 3 3.7.1 C-C C3.20 H88-118-H42 Sur 90% Sur 3 3.7.1 C-C C3.20 M88-119-H2 Sur 90% Sur 3 3.7.1 C-C C3.20 H88-140-H10 Sur 90% Sur 17 3.7.1 C-C C3.20 H88-154-H2 Sur 90% Sur 16 3.7.1 C-C C3.20 H88-160-H1 Sur 90% Sur 16 3.7.1 C-C C3.20 M88-160-H2 Sur 90% Sur 16 3.7.1 l C-C C3.20 H88-160-H16 Sur 90% Sur 3.7.1 NOTES:
- 1. The percent complete values listed are based on: (1) results of preservice esaminations. (2) differences between preservice and inservice Code edition reoutrements for enemination coverage, and (3) taproved inservice esamination techntoues. Refer to the preservice enemination records for component description and dotatis of obstructing condition.
- 2. SIC numoers shown correspond to the Saf ety Impact Cate9ories per the Preservice Inspection Pro 9 rom and, for convenience, are re-stated below:
Vol - Volumetric Sur - Surface T3.0-4(2) Rev. 2. 01/87
( y TABLE 3.0-4 (Cont *d) ASME CODE CLASS 7 PIPING RELIEF REQUEST
SUMMARY
SIC si. RHR system weld / bolted connection outstae containment. downstream of pump discharge check valves: During normal plant power operation, weld is unpressurized or slightly pressurtzed by keep-full systems. Signif1 Cant leakage may affect pressure boundary of one RHR loop. Stenificant leakage is detected by team detection systems or loss of system function. If leak is within the shutdown cooling loop the plant can be safely shutdown using the main condenser and the unaffected RHR loop. SIC s3. RMR shutdown cooling suction line weld between normally closed valves: During normal plant operation, significant leakage is cetected by leak detection systems. The plant can be safely shut cown using the main condenser and the alternate shutdown cooling method. SIC s8. HPCI. RCIC, and RwCU system wolos outsico containment: During plant power operation. sign 9ficant leakage from lines which are pressurized with steam or hot water is detected and automatically isolated by leak detection systems. None of these systems are required for normal plant shutdown. Plant can be safely shut down using normal shutdown methods. SIC all. RHR. MPCI. RCIC, and Core Spray system welds between the pump suction containment isolation valve and pump discharge check valve: During plant power operation. weld is slightly pressurized by the hydrostatic head of the suppression pool or condensate storage tank. Significant leakage is detected by leak detection system. If the leak is within an RNR shutdown cooling loop. the plant can be safely shut doen using the main condenser and the unaffected RHR loop. I SIC si4 Core spray system weld outside containmenta During plant power operation, weld is slightly pressurized by hydrostatic head or keep-ful1 systems. Leak detection systems detect significant . leakage. The plant can be safely shut down using normal shutdown methods. SIC s15. Main steam system weld inside the turbine enclosures weld is pressurized during plant power operation. If leek is not large enough to be detected and automatically isolated. leakage would be ostected by other methods (e.g. area and stack radiation monitors) and manually isolated. The plant can be safely shut down by depressurtaing via the suppression pool and removing heat via the RHR system. SIC s16. RHR system, vacuum rettef itne weld outsids containment: weld is not pressurtzed during normal plant or RNR system operation. Plant can be safely shut down using normal shutdown methods. SIC s17. RNR system. pressure relief line weld / bolted connection outside containment: weld / bolted connection is not pressurized during normal plant or RMR system operation. The plant can be safely snut down using the normal shutdown methods. SIC s18. AMR system. RPV head spray weld inside containment between normally closed valves: Weld is not pressurized during plant power operation. Significant leakage is detected by leak detection systems. The plant can be safely shut down using the normal shutdown methods. SIC s19. CRD system. scram discharge piping weld outside containment. Weld is not pressurized during normal plant operation. Leakage is detected during system leakage tests. The plant can be safely shut down using normal shutdown methods.
- 3. The rettef requests in this table are based on the information prepared for the Limerick Generating I Station unit i and Common Plant Ftrat 10 year Interval Inservice Inspection Enemination Plan. These relief requests may be updated as the inservice esaminations are scheduled and performed.
- 4. Table 3.0-4 lists the totsi ocoulation of components for which relief request 3.7.1 mgy apply. Refer to the enemination plan for the icentification of specific components selected for examination during the first 10 year interval.
T3.0-4(3) Rev. 2. 01/87
LGS ISI PROGRAM i i i 3.8 INSPECTION PROGRAM FOR ASME CODE CLASS 2 PUMPS 3.8.1 EXAMINATION SCHEDULE i The First 10-Year Interval Inservice Inspection Program for Class 2 pumps shall commence with commercial operation. Pump component l' l examinations will be performed during normal operation or scheduled to coincide with plant outages and as required by Section 1.5. A detailed examination schedule is included in the Examination Plan referenced in Section 3.9. 3.8.2 EXAMINATION CATEGORIES AND REQUIREMENTS i Inservice inspections of Class 2 pump components shall, to the extent practical within the limitations of design, geometry, materials of construction and radiation considerations, meet the requirements of the ASME Section XI Edition and Addenda specified in Section 1.4. Table 3.0-5 identifies the Class 2 pump j components subject to examination during the first 10-year 1 interval. This table provides the corresponding ASME Section XI, Table IWC-2500-1 item number, examination category, the required j method of examination, acceptance standard for evaluation, and
- i the extent and frequency of examination.
j j 3.8.3 EXAMINATION TECHNIQUES AND PROCEDURES 4 The techniques and procedures for visual, surface, and volumetric , examinations shall meet the requirements of Section XI, IWA-2200 j as described below. Examinations, conducted in accordance with j ASME Section V shall use the 1980 Edition with Addenda through l Winter 1981 or later Editions and Addenda. ! Nondestructive examinations shall be performed using a written ! procedure. Requirements for written procedures are determined by l the referenced Code Section. Appropriate details and i requirements may be included in a number of documents like the Examination and Testing Plans referenced in Section 1.3 and/or
- specific procedures.
(1) Visual examinations of Class 2 pump components shall be i performed in accordance with Section XI, IWA-2210 and Section V, Article 9. (See Footnote 2) I l (2) Surface examinations of Class 2 pump components shall be
- performed in accordance with Section XI, IWA-2220 and j Section V, Article 6 for liquid penetrant examinations or Section V, Article 7, for magnetic particle examinations.
] 4 (See Footnote 2) 1 l l 3.8-1 Rev. 2, 01/87 e () 1 l 1 i
LGS ISI PROGRAM 1A, (3) When performed as a supplemental examination, volumetric U examinations of Class 2 pump components by ultrasonic methods shall be in accordance with ASME Section XI, INA-2230 and l Section V, Article 5. Weld reflectors producing a response greater than 50% of the reference level shall be recorded. Weld reflectors producing a response greater than 100% of reference level shall be recorded and investigated to determine the shape, identity and location and shall be sized to end points producing a response equal to 100% of reference level. Weld reflectors producing a response greater than 100% reference level shall be characterized in accordance with IWA-3000 and evaluated in terms of the appropriate acceptance standard. The calibration standard shall be fabricated from material of the same material specification, product form and heat treatment as one of the materials being examined. Any indication detected in the weld and required volume not readily attributable to geometrical or metallurgical conditions will be recorded regardless of ultrasonic amplitude response and investigated by a Level II or Level III examiner to the extent necessary to determine the shape, identity, and location of the reflector. PECo will disposition and take the appropriate corrective action for any indication investigated and evaluated to be other than geometrical or metallurgical in nature. For indictions determined to be related and intermitant, i.e. geometrical or metallurgical in nature, the shape, identity, and location of the reflector will only be recorded for the peak amplitude response of the related family of indications. (See Footnote 2) (4) When radiography is used as a supplemental examination method, the examinations shall be performed in accordance with Section V, Article 2. (See Footnotes 2, 3) l (5) Alternative examination methods, including combinations of ! visual, surface and/or volumetric methods, or newly developed j techniques may be substituted for the above specified { methods, provided that the results are demonstrated to be equivalent or superior to those of the specified method. l 3.8.4 EVALUATION OF EXAMINATIONS RESULTS 1 For Class 2 pump components, the rules of ASME Section XI IWB- ! 3000 shall be used for the evaluation of examination results and , the acceptance criteria for continued service. 3.8-2 Rev. 2, 01/87 r
- - _- _ _ _ . . -. . .- = . - . -
, LGS ISI PROGRAM e e'O (1) The acceptance criteria for continued service and preservice (_-)' examinations of repairs shall be in accordance with IW8-3000. Where applicable, references to IWB-4000 shall refer to the repair Articles corresponding with the Code classification of the component being repaired. (2) The acceptance criteria for initial service of replacement components shall be in accordance with IWB-3110. (See i Footnote 1) 3.8.4.1 FLAW INDICATION CHARACTERIZATION Flaw indications detected during inservice examinations and preservice examinations of repairs shall be characterized in accordance with IWB-3420 and compared with the acceptance ) standards specified in IWB-3410. ] Flaw indications detected during preservice examinations of l replacement components need only be characterized in accordance with IWB-3400 provided the nondestructive examinations required by the Design Specification have been performed and the applicable acceptance criteria have been met. 3.8.4.2 ACCEPTANCE STANDARDS l The acceptance standards for Class 2 pump components are j {} summarized in Table 3.0-5. Where acceptance standards are in the course of preparation, the requirements of IWA-3100 shall apply. ) r f For flaw indications detected during inservice examinations and preservice examinations of repairs, acceptance by evaluation per !l IWB-3120 may be performed. Footnotes l 1. Replacements are defined in Section XI, IWA-7100, i , 2. Supplemental examination methods or techniques may be used in the evaluation of a flaw indication. Surface flaws, detected t
- during visual examinations, shall be supplemented by either surface or volumetric examination. Methods for supplemental i
surface examinations may include a repetition of the visual examination using improved techniques such as additional cleaning, improved lighting, the use of optical aids and/or surface replication. i l 3.8-3 Rev. 2, 01/87 i O i 4
LGS ISI PROGRAM
- 3. Evaluation shall be in accordance with IWA-3370. An "a" O dimension of " length /2" shall be used until such time as supplemental examinations per Footnote 2 are performed.
O
' 8-' av 2, 01/82 O
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I LG5 ISI PRO ht
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TABLE 3.0-5 INSERVTCE INSPECTION PROGRAM ASwE CODE CLASS 2 PUwDS Item Components & Parts Examination Esamination Requirements Category No. to be Enemined wetnoo For First 10-year Interval Renacks/Retief Request l C-C C3.30 Integrally welded Surface Integrally welceo attach- (1) See Relief Request l attachments ments whose attacnment Subsection 3.10.2
~* I base material design thickness is 3/4- (2) See Note (3)
I or greater l Includes Fig. No. l IwC-2500-5 Acceptance Standard l IWS-3516 C-D C4.30 pressure rotatning - - There are no bolts or bolts and stuos stuos > 2* in diameter
> 2 in otameter C-G C6.10 Pump casing elos Surface 100% of all welos in See Relief Request one out of multiple Suosection 3.10.1 pumps of similar coston. .
stas, and service Includes Fig. No. IwC-2500-8 Acceptance Stenoord IwB-3518 C-H C7.50 Pressure-retatning Visual (VT-2) System pressure test during (1) See Notes (1) & (2) bouedary system or component func-tional test (ZwA-5240 (2) A system hydrostatic IwC-5221) to be performed test (IWC-5222) and during each inspection accompanying VT-2 period esamination are acceptable in lieu Acceptance Standard IwC-5250 of the system pres-sure test (!wC-5221) and VT-2 esamination C-N C7.60 pressure-retaining Visual (VT-2) System hydrostatic test See kete (1) boundary (IWA-5240 IWC-5222) to be performed once at or near the end of the inspection in t e rval , or curing the same inspection period of Doch inspection interval of Inspection Program B Acceptance Standard IJA-5250 T3.0-5(1) Rev. 2. 01/87
.-.- - . . - - . . _ _ . . - - . .~. ~ . . -.. -. - ... . ~ . -. ._ - -
LG5 152 3 TABLE 3.0-5 INSERvfCE INSDECTION PeOGaans ASWE CODE CLASS 2 PUt8P5 se0TES: (1) The system pressure test bouncery includes only those portions of the system required to operate or support the safety system function up to and incluoing the first normally closed valve (including a safety 6 or rettef walve) or valve capeole of automatte closure unen the safety function is required. except for tne follo-ings
- a. Open-enced porttons of systems.
D. For repairs or replacements within en isolable portion of a system, the boundary for the required pressure test may be limited to the isolable port ton. (2) Includes only those systems or port tens of systems not required to operate erring normal reactor l operatton. I (3) For integral attachments greater then or equal to 3/4" case material oesign thickness, 2516 of the integral l attachments on Class 2 pumps atti De esamined during the first 10 year interval. 73.0-5(2) Rev. 2. 09/87
LGS ISI PROGRAM O, (_J 3.9 EXAMINATION PLAN FOR ASME CODE CLASS 2 PUMPS The " Limerick Generating Station Unit 1 and Common Plant First 10-Year Interval Inservice Inspection Examination Plan" specifies the details as to how the ASME Section XI and the augmented requirements are to be met. Included in the scope of the document are the details relating to component identification, location, access requirements, schedules, procedures, calibration blocks, special equipment, and other items necessary to perform the examination and pressure testing of ASME Code Class 2 pumps. Components that are subject to augmented inspection requirements are listed a second time in a separate section of the Examination Plan specifically for identifying and scheduling the augmented requirements. These components are identified by the addition of a "(+)" symbol to the applicable ASME Code Category. O 3.9-1 Rev. 2, 01/87
LGS ISI PROGRAM e 3.10 REQUEST FOR RELIEF FROM ASME SECTION XI REQUIREMEN'n k CLASS 2 PUMPS 3.10.1 RELIEF REQUEST RHR Pump 1AP-202 and Core Spray pump 1AP-206 casing welds. 3.10.1.1 REQUIREMENT FROM WHICH RELIEF IS REQUESTED ASME Section XI, Table IWB-2500-1, Category C-G, Item C6.10 requires surface examination of pump casing welds of one pump in each group of pumps of similar design, size, function, and service per Figure No. IWC-2500-8. These examinations are to be performed once per inspection interval. The affected welds are summarized in Table 3.0-6. 3.10.1.2 JUSTIFICATION There are four welds in each RHR and Core Spray pump that are encased in concrete. Access to these welds would necessitate removing the pump internals to perform the examinations from the inside surface. The disassembly of these pumps constitutes a maintenance job of major proportions. This requirement, in the absence of other required maintenance, represents unnecessary exposure to radiation and contamination. Contact exposure rates for the RHR pump are estimated to be in the range of 200 mrem /hr O to 1 rem /hr. Contact exposure rates for the Core Spray pump are estimated to be in the range of 20 mrem /hr to 50 mrem /hr. In addition, a job of this scope represents an unnecessary risk of an industrial accident due to the cramped quarters and limited visibility resulting from the use of full anti-contamination protective equipment 3.10.1.3 ALTERNATE TO ASME SECTION XI REQUIREMENTS The RHR and Core Spray pump casing welds that are encased in concrete will receive a visual or surface examination from the inside surface whenever these welds are accessible as a result of disassembly for other maintenance purposes. The examination method will be consistent with PECo's ALARA program. In the interim, pump performance tests will be performed quarterly to verify pump operability. External inspections will be performed during times of seal maintenance and visual examinations will be performed during periodic system pressure tests. Leakage from the pump casings can be detected at the foundation construction joints. 3.10-1 Rev. 2, 01/87
LGS ISI PROGRAM g l 3.10.2 RELIEF REQUEST l RCIC Pump 10P-203, pump casing integral attachment welds. l 3.10.2.1 REQUIREMENT FROM WHICH RELIEF IS REQUESTED ASME Section XI, Table IWC-2500-1, Category C-C, Item C3.30 requires surface examination be performed on 100% of the weld length and adjacent base material. The examination requirements are shown on Figure IWC-2500-5. These examinations are to be performed once each inspection interval. The affected components are summarized in Table 3.0-6. l 3.10.2.2 JUSTIFICATION The RCIC pump integral attachments are designed to support the pump on the pedestal. The accessible portion of the weld and adjacent base material (85% of the total weld length) can be examined with the pump in place. The inaccessible portion of the weld and adjacent base material (15% of the ' total weld length) is obstructed by the pedestal supporting plates. In order to examine the inaccessible portion of the integral attachments, the pump would have to be lifted off of the pedestal. This activity constitutes a maintenance job of major proportions. This requirement, in the absence of other required maintenance, represents an unnecessary risk of an industrial accident due to the cramped quarters. {} l 3.10.2.3 ALTERNATE TO ASME SECTION XI REQUIREMENTS l The inaccessible portion of the RCIC pump integral attachments will receive a surface examination if the pump isJremoved from the pedestal to perform other maintenance activities. Pump performance tests will be performed quarterly,to verify pump operability. Visual examinations will be performed during l periodic system pressure tests. l l i 3.10-2 Rev. 2, 01/87 0
r D (J I LGS ISI PL
%.)
40 D) (O TABLE 3.0-6 ASME CODE CLASS 2 PUMPS RELTEF REQUEST
SUMMARY
(See Note 4) ASME ASME Percent Section XI Sectien XI component / Examination Complete SIC Relief Category item No. Weld No, Method (See Note 1) ($ee Note 1) ROQuest ] C-G C6.10 RHA-P-A Sur Note 3 11 3.10.1 C-G C6.10 RNA-P-B Sur Note 3 11 3.10.1 C-G C6.10 RHA-P-C Sur Note 3 11 3.10.1 C-G C6.10 RHA-P-D Sur Note 3 11 3.10.1 C-G C6.10 CSA-P-A Sur Note 3 11 3.10.1 C-G C6.10 CSA-P-B Sur Note 3 11 3.10.1 C-G C6.10 CSA-P-C Sur Note 3 11 3.10.1 C-G C6.10 CSA-P-D Sur Note 3 11 3.10.1 C-G C3.30 EC-P-PSI Sur 85% 11 3.10.2 C-G C3.30 RC-P-PS2 Sur 85% 11 3.10.2 C-G C3.30 RC-P-PS3 Sur 85% 11 3.10.2 C-G C3.30 RC-P-PS4 Sur 85% 11 3.10.2 Sur - Surface NOTES: 1 The percent complete values listed are based on: (1) results of preservice examinations. (2) differences . between preservice and inservice Code edition requirements for examination coverage, and (3) improved in-service examination techniques. Refer to the preservice examination records for component description and details of obstructing condition.
- 2. SIC numbers shown correspond to the Safety Impact Categories per the Preservice Inspection Program and.
for convenience, are re-stated below: SIC s11. RHR. HPCI. RCIC, and Core Spray system wolds between the pump suction containment isolation valve and pump discharge check valves During plant power operation, weld is slightly pres-surize* by the hydrostatic head of the suppression pool or condensate storage tank. Significant leakage is detected by leak detection systesm. If the leak is within an RHR shutdown cooling i loop, the plant can be safely shut down using the main condenser and the unaffected RHR loop. l 3. Examinations are to be perf ormed f rom the inside surface. These examinations are deferred untti times of pump disassambly for maintenance purposes. 4 The relief requests in this table are based on information prepared for the Limerick Generating Station Unit 1 and Common Plant First 10-Year Interval Inservice Inspection Examination Plan. These relief request may be updated as the inservice examinations are scheduled and performed, t T3.0-6(1) Rev. 2 01/87
LGS ISI PROGRAM l 3.11 INSPECTION PROGRAM FOR ASME CODE CLASS 2 VALVES 3.11.1 EXAMINATION SCHEDULE The First 10-Year Interval Inservice Inspection Program for Class 2 valves shall commence with commercial operation. Valve l component examinations will be performed during normal operation s or scheduled to coincide with plant outages and as required by Section 1.5. A detailed examination schedule is included in the Examination Plan referenced in Section 3.12. 3.11.2 EXAMINATION CATEGORIES AND REQUIREMENTS Inservice inspections of Class 2 valve components shall, to the extent practical within the limitations of design, geometry, materials of construction and radiation considerations, meet the requirements of the ASME Section XI Edition and Addenda specified in Section 1.4. Table 3.0-7 identifies the Class 2 valve components subject to examination during the first 10-year interval. This table provides the corresponding ASME Section XI, Table IWC-2500-1 item number, examination category, the required method of examination, acceptance standard for evaluation, and the extent and frequency of examination. 3.11.3 EXAMINATION TECHNIQUES AND PROCEDURES i The techniques and procedures for visual, surface, and volumetric examinations shall meet the requirements of Section XI, IWA-2200 as described below. Examinations, conducted in accordance with ASME Section V shall use the 1980 Edition with Addenda through Winter 1981 or later Editions and Addenda. Nondestructive examinations shall be performed using a written procedure. Requirements for written procedures are determined by the referenced Code Section. Appropriate details and requirements may be included in a number of documents like the Examination and Testing Plans referenced in Section 1.3 and/or . specific procedures. (1) Visual examinations of Class 2 valve components shall be performed in accordance with Section XI, IWA-2210 and Section V, Article 9. (See Footnote 2) (2) When performed as a supplemental examination, surface examinations of Class 2 valve components shall be performed in accordance with Section XI, IWA-2220 and Section V, Article 6 for liquid penetrant examinations or Section V, Article 7, for magnetic particle examinations. (See Footnote 2) l ! 3.11-1 Rev. 2, 01/87 e- p - ene-- -- m .e----
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1 LGS ISI PROGRAM l I (3) When performed as a supplemental examination, volumetric ! ()- examinations of Class 2 valve components by ultrasonic ) methods shall be in accordance with ASME Section XI, IWA-2230 l l and Section V, Article 5. Weld reflectors producing a response greater than 50% of the reference level shall be recorded. Weld reflectors producing a response greater than 100% of reference level shall be recorded and investigated to determine the shape, identity and location and shall be sized to end points producing a response equal to 100% of reference level. Weld reflectors producing a response greater than 100% reference level shall be characterized in accordance with IWA-3000 and evaluated in terms of the appropriate acceptance standard. The calibration standard shall be fabricated from material of the same material specification, product form and heat treatment as one of the materials being examined. Any indication detected in the weld and required volume not readily attributable to geometrical or metallurgical conditions will be recorded regardless of ultrasonic amplitude response and investigated by a Level II or Level III examiner to the extent necessary to determine the shape, identity, and location of the reflector. PECo will disposition and take the appropriate corrective action for any indication investigated and evaluated to be other than geometrical or metallurgical in nature. For indictions determined to be related and intermitant, i.e. geometrical or metallurgical in nature, the shape, identity, and location of the reflector will only be recorded for the peak amplitude response of the related family of indications. (See Footnote 2) (4) When radiography is used as a supplemental examination method, the examinations shall be performed in accordance with Section V, Article 2. (See Footnotes 2, 3) 1 (5) Alternative examination methods, including combinations of visual, surface and/or volumetric methods, or newly developed techniques may be substituted for the above specified methods, provided that the results are demonstrated to be l equivalent or superior to those of the specified method. l 3.11.4 EVALUATION OF EXAMINATIONS RESULTS Por Class 2 valve components, the rules of ASME Section XI IWB- ! 3000 shall be used for the evaluation of examination results and the acceptance criteria for continued service. l 3.11-2 Rev. 2, 01/87 l () __ _ . . _ _ _ _ _ . _ , . _ , . _ . . - ~ _ _ _ , . _ . . . _ .
.- = ._ - ._ _ _ .
LGS ISI PROGRAM Om; (1) The acceptance criteria for continued service and preservice examination of repairs shall be in accordance with IWB-3000. Where applicable, references to IWB-4000 shall refer to the repair Articles corresponding with the Code classification of the component being repaired. (2) The acceptance criteria for initial service of replacement components shall be in accordance with IWB-3110. (See Footnote 1) l 3.11.4.1 FLAW INDICATION CHARACTERIZATION Flaw indications detected during inservice examinations and preservice examinations of repairs shall be characterized in accordance with IWB-3420 and compared with the acceptance ; standards specified in IWB-3410. ' Flaw indications detected during preservice examinations of replacement components need only be characterized in accordance , with IWB-3400 provided the nondestructive examinations required l by the Design Specification have been performed and the applicable acceptance criteria have been met. l 3.11.4.2 ACCEPTANCE STANDARDS The acceptance standards for Class 2 valve components are summarized in Table 3.0-7. [}- Where acceptance standards are in the course of preparation, the requirements of IWA-3100 shall apply. For flaw indications detected during inservice examinations and preservice examinations of repairs, acceptance by evaluation per IWB-3120 may be performed. Footnotes: l 1. Replacements are defined in Section XI, IWA-7100.
- 2. Supplemental examination methods or techniques may be used in the evaluation of a flaw indication. Surface flaws, detected during visual examinations, shall be supplemented by either
, surface or volumetric examination. Methods for supplemental l surface examinations may include a repetition of the visual examination using improved techniques such as additional cleaning, improved lighting, the use of optical aids and/or surface replication. I 3.11-3 Rev. 2, 01/87 l
LGS ISI PROGRAM
- 3. Evalution shall be in accordance with IWA-3370. An "a" O' dimension of " length /2" shall be used until such time as supplemental examinations per Footnote 2 are performed.
4 1 O i 3.11-4 Rev. 2, 01/87 i i
LGS ISI PAC fh ( ,f i g_ TABLE 3.0-7 INSERVICE TNSPECTION PROGRAM l ASME CODE CLASS 2 VALVES
; Item Components & Parts Examination Examination Requirements Category No. to be Examined Method For First 10-vear Interval Remarks / Relief Reauest C-C C3.40 Integrally welded - -
There are no integrally attachments welded attachments on valves C-D C4.40 pressure retaining - - There are no bolts or bolts and studs studs > 2" in diameter
> 2" in diameter C-G C6.20 Valve body welds - -
There are no valves with body welds C-H C7.70 Prossure retaining boundary Visual (VT-2) System pressure test (1) See Notes (1) & (2) during system or component functional test (IWA-5240, (2) A system hydrostatic IWC-5221) to be performed test (IWC-5222) and during each inspection accompanying VT-2 period examination are accept i able in lieu of the Acceptance Staadard IWA-5250 system pressure test (IWC-5221) and VT-2 . examination C-H C7.80 Pressure retaining Visual (VT-2) System hydrostatic test See Note (1) components (IWA-5240 IWC-5222) to be performed once at or near the end of the inspection interval, or during the same inspection period of each inspection interval of Inspection Program B j Acceptance Standard IWA-5250 NOTES: (1) The system pressure test boundary includes only those portions of the system required to operate or support the safety system function up to and including the first normally closed valve (including a safety or relief valve) or valve capable of automatic closure when the safety function is required, except for the followings
- a. Open-ended portions of systems.
- b. For repairs or replacements within an isolable portion of a system, the t)oundary f or the required pressure test may be limited to the isolable portion.
(2) Includes only those systems or portions of systems not required to operate during normal reactor operation. T3.0-7(1) Rev. 2 01/87
LGS ISI PROGRAM ( 3.12 EXAMINATION PLAN FOR ASME CODE CLASS 2 VALVES The " Limerick Generating Station Unit 1 and Common Plant First 10 year Interval Inservice Inspection Examiantion Plan" specifies the details as to how the ASME Section XI and the augmented requirements are to be met. Included in the scope of the document are the details relating to component identification, location, access requirements, schedules, procedures, calibration blocks, special equipment, and other items necessary to perform the examination and pressure testing of ASME Code Class 2 valves. Components that are subject to augmented inspection requirements are listed a second time in a separate section of the Examination Plan specifically for identifying and scheduling the augmented requirements. These components are identified by the addition of a "(+)" symbol to the applicable ASME Code Category. 3.12-1 Rev. 2, 01/87 l l l
l i i LGS ISI PROGRAM O. 3.13 REQUEST FOR RELIEF FROM ASME SECTION XI REQUIREMENTS - l CLASS 2 VALVES None. l t O l l 3.13-1 Rev. 2, 01/87
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LGS ISI PROGRAM LIMERICK GENERATING STATION UNIT 1 AND COMMON PLANT l FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM LIST OF EFFECTIVE PAGES SECTION 4.0 NUMBER REVISION DATE l All Pages 2 01/87 i O LEP 4.0-1 Rev. 2, 01/87 l - l l
LGS ISI PROGRAM l 4.0 ASME CODE CLASS 3 COMPONENT INSPECTION PROGRAM 4.1 IDENTIFICATION OF ASME CODE CLASS 3 SYSTEMS The ASME Section XI ISI boundaries for the ASME Code Class 3 Piping Systems are identified in green (non-exempt) and purple (exempt) color coding on the following drawings (Appendix A): ASME Section XI ASME Code Class 3 Systems Boundary P&ID (1) Emergency Service Water ISI-M-ll Shts. 1,2,&3 (2) RHR Service Water ISI-M-12 (3) Reactor Enclosure Cooling Water ISI-M-13 (4) Fuel and Diesel Oil Storage ISI-M-20 and Transfer (5) Nuclear Boiler ISI-M-41 (6) Residual Heat Removal ISI-M-51 Shts. 1&2 (7) Fuel Pool Cooling and Clean-up ISI-M-53 (8) Control Enclosure Chilled Water ISI-M-90 The ASME Code Class 3 boundaries are consistent with the USNRC Regulatory Guide 1.26, Rev. 3 Group C quality standards and/or other licensing commitments. The following components (or parts of components) are exempt from O the selection for visual (VT-1 & VT-3 only) inservice examination requirements in accordance with ASME Section XI, IWD-1220: (1) Integral attachments of supports and restraints to components that are 4" NPS and smaller. (2) Integral attachments of supports and restraints to components exceeding 4" NPS that are: (a) located in systems (or portions of systems) whose function is not required in the support of reactor residual heat removal, containment heat removal, and emergency core cooling, and (b) operate at a pressure of 275 psig or less and at a temperature of 200F or less. 4.1-1 Rev. 2, 01/87
LGS ISI PROGRAM 4.2 INSPECTION PROGRAM FOR ASME CODE CLASS 3 COMPONENTS 4.2.1 EXAMINATION SCHEDULE The First 10-Year Interval Inservice Inspection Program for Class 3 piping shall commence with commercial operation. Class 3 l component examinations will be performed during normal operation or scheduled to coincide with normal plant outages at the frequency stated in Table 4.0-1. A detailed examination schedule is included in the Examination Plan referenced in Section 4.3. 4.2.2 EXAMINATION CATEGORIES AND REQUIREMENTS Inservice inspections of Class 3 pipe components shall, to the extent practical within the limitations of design, geometry, materials of construction and radiation considerations, meet the requirements of the ASME Section XI Edition and Addenda specified in Section 1.4. Table 4.0-1 identifies the Class 3 components subject to examination during the first 10 year interval. This table provides the corresponding Section XI, Table IWB-2500-1 item number, examination category, the required method of examination, acceptance standard for evaluation, and the extent and frequency of examination. 4.2.3 EXAMINATION TECHNIQUES AND PROCEDURES (]) The techniques and procedures for visual, surface, and volumetric examination shall meet the requirements of Section XI, IWA-2200 as described below. Examinations, conducted in accordance with ASME Section V shall use the 1980 Edition with Addenda through Winter 1981 or later Editions and Addenda. ( Nondestructive examinations shall be performed using a written procedure. Requirements for written procedures are determined by the referenced Code Section. Appropriate details and requirements may be included in a number of documents like the Examination and Testing Plans referenced in Section 1.3 and/or specific procedures. (1) Visual examinations of Class 3 components shall be performed in accordance with Section XI, IWA-2210 and Section V, Article 9. (See Footnote 2) (2) When performed as a supplemental examination, surface examinations of Class 3 components shall be performed in accordance with Section XI, IWA-2220 and Section V, Article 6 for liquid penetrant examinations or Section V, Article 7 for magnetic particle examinations. (See Footnote 2) 4.2-1 Rev. 2, 01/87
LGS ISI PROGRAM (3) When performed as a supplemental examination, volumetric O- examinations of Class 3 components by ultrasonic methods, shall be in accordance with Section XI, IWA-2230 and Appendix III including Supplement 7 for welds in austenitic materials. l Weld reflectors producing a response greater than 50% of reference level shall be recorded. Any indication detected in the weld and required volume not readily attributable to geometrical or metallurgical conditions will be recorded regardless of ultrasonic amplitude response and investigated by a Level II or Level III encainer to the extent necessary to determine the shape, identity, and location of the reflector. PECo will disposition and take the appropriate corrective action for i any indication investigated and evaluated to be other than geometrical or metallurgical in nature. , For indictions determined to be related and intermitant, i.e. geometrical or metallurgical in nature, the shape, identity, and location of the reflector will only be recorded for the l peak amplitude response of the related family of indications. (See Footnote 2) (4) When radiography is used as a supplemental examination method, the examinations shall be performed in accordance with Section V, Article 2. (See Footnotes 2, 3)
-O (5) Alternative examination methods, including combinations of visual, surface and/or volumetric methods, or newly developed techniques may be substituted for the above specified methods, provided that the results are demonstrated to be equivalent or superior to those of the specified method.
4.2.4 EVALUATION OF EXAMINATION RESULTS For Class 3 components, the rules of ASME Section XI IWB-3000 shall be used for the evaluation of examination results and the acceptance criteria for continued service. (1) The acceptance criteria for continued service and preservice examination of repairs shall be in accordance with IWB-3000. Where applicable, references to IWB-4000 shall refer to the repair articles corresponding with the Code classification of the component being repaired. (2) The acceptance criteria for initial service of replacement components shall be in accordance with IWB-3110. (See Footnote 1) 4.2-2 Rev. 2, 01/87 O I
LGS ISI PROGRAM {} l 4.2.4.1 FLAW INDICATION CHARACTERIZATION Flaw indications detected during inservice examinations and preservice examinations of repairs shall be characterized in accordance with IWB-3420 and compared with the acceptance standards specified in IWB-3410. Flaw indications detected during preservice examinations of replacement components need only be characterized in accordance with IWB-3400 provided the non-destructive examinations required by the Design Specification have been performed and the applicable acceptance criteria have been met. l 4.2.4.2 Acceptance Standards The acceptance standards for Class 3 components are summarized in Table 4.0-1. Where acceptance standards are in the course of preparation, the requirements of IWA-3100 shall apply. For flaw indications detected during inservice examinations and preservice examinations of repairs, acceptance by evaluation per IWB-3120 may be performed. Footnotes: O l 1. Replacements are defined in Section IX, IWA-7100. ! 2. Supplemental examination methods or techniques may be used in the evaluation of a flaw indication. Surface flaws, detected during visual examinations, shall be supplemented by either surface or volumetric examination. Methods for supplemental surface examinations may include a repetition of the visual examination using improved techniques such as additional cleaning, improved lighting, the use of optical aids and/or surface replication.
- 3. Evaluation shall be in accordance with IWA-3370. An "a" dimension of " length /2" shall be used until such time as supplemental examinations per Footnote 2 are performed.
l l l 4.2-3 Rev. 2, 01/87
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V ). TABLE 4.0-1 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS Item Components & Parts Examination Examination Regairements Cateoory No. to be Examined Method For First 10-year Intervat Remarks / Relief Request D-A D1.10 Pressure retaining Visual (VT-2) (1) System inservice test (1) See Note (1) components in support (IWA-5240/IWD-5221) to of reactor shutdown be performed during (2) A system hydrostatic test a function each inspection period (IWD-5223) and accompany-ing VT-2 examination are , Acceptance Standard acceptable in lieu of 1 IWA-5250 system inservice test l (IWD-5221) (2) System hydrostatic test (IWA-5240/IWD-5223) to be performed once at or near the end of the in-spection interval, or i during the same inspect-1 ion period of each inspec-tion interval of Inspec-tion Program B Acceptance Standard . IWA-5250 l D-A D1.20 Integral attachments- Visual (VT-3) Integral attachments to See Notes (1) & (2) I supports. restraints system boundary of component supports selected per IWF-2500 to be examined once during each inspection interval Includes Fig. No. IWD-2500-1 i Acceptance Standard IWS-3516 i l D-A DI.30 Integral attachments- Visual (VT-3) Integral attachments to See Notes (1) & (2) mechanical snubbers system boundary of component supports selected per IWF-2500 to be examined once ) during each inspection interval Includes Fig. No. IWD-2500-1 Acceptance Standard IWB-3516 I a T4.0-1(1) Rev. 2 01/87
p TABLE 4.0-1 (Cont'd) INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS Item Components & Parts Examination Examination Requirements Category No. to be Examined Method For First 10-year Intervat Rema rk s / R e l i e f Reauest i 3 l D-A D1.40 Integral attachments- Visual (VT-3) Integral attachments to See Notes (1) & (2) spring type supports system boundary of component supports selected per IWF-l 2500 to be examined once during each inspection interval Includes Fig. No. IWD-2500-1 Acceptance Standard IWB-3516 0-A DI.50 Integral attachments- - - There are no constant constant load supports load supports D-A D1.60 Integral attachments- - - There are no shock shock absorbers absorbers (compensating struts) D-B D2.10 Pressure retaining Visual (VT-2) (1) System functional test (1) See Note (1) components in (IWA-5240/IWD-5222) to . support of ECCS, be performed during (2) A system hydrostatic Containment Heat each inspection test (IWD-5223) and Removal (CHR), period accompanying VT-2 Atmosphere Cleanup examination are accept-(AC), and RHR Acceptance Standard able in lieu of system systems IWA-5250 functional test (IWD-5222) l (2) System hydrostatic test (IWA-5240/IWD-5223) to be performed once at or ] near the end of the inspection interval, or during the same inspection period of each inspection interval of Inspection Program 8 A ceptance Standard i IWA-5250 4 T4.0-1(2) Rev. 2, 01/87 i 1
LGS 1( [OGRA3 m,j , TAILE 4.0-1 (Cont'd) INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS Item Components & Parts Examination Examination Requirements Category No, to be Enemined Method For First 10-year Interval Remarks / Relief Request l D-B D2.20 Integral attachments- Visual (VT-3) Integral attachments to supports, restraints system boundary of component See Notes (1) & (2) supports selected per IWF-2500 to be examined once during each inspection interval Includes Fig. No. IWD-2500-1 Acceptance Standard IWB-3516 l D-B D2.30 Integral attachments- Visual (VT-3) Integral attachments to mechanical anubbers system boundary of component See Notes (1) & (2) supports selected per IWF= 2500 to be examined once during each inspection interval Includes Fig. No. !WD-2500-1 Acceptance Standard IWB-3516 l D-B D2.40 Integral attachments- Visual (VT-3) Integral attachments to spring type supports system boundary of component See Notes (1) & (2) supports selected per IWF-2500 to be examined once during each inspection interval Includes Fig. No. IWD-2500-1 Acceptance Standard IW8-3516 D-B D2.50 Integral attachments- - - constant load supports There are no constant load supports D-B D2.60 Integral attachments- - - shock absorbers There are no shock absorbers (compensating struts) T4.0-1(3) Rev. 2, 01/87 4
LGS ISf' ';OGRid2 Q (~ j) - TABLE 4.0-1 (Cent'd) , INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS l Item Components & Parts Examination Examination Requirements Cateoory No. to be Examined Method For First 10-year Interval Remarks / Relief Reauest D-C D3.10 Pressure retaining Visual (VT-2) (1) System inservice test (1) See Note (1) components in (IwA-5240/IWD-5221) to support of RHR be performed during (2) A system hydrostatic from spent fuel each inspection test (IWD-5223) and storage pool period accompanying VT-2 examination are accept-Acceptance Standard able in lieu of system IWA-5250 functional test (IwD-5221) l (2) System hydrostatic test (IWA-5240/IWD-5223) to be performed once at or near the end of the inspection interval. or during the same inspection period of each inspection interval of Inspection Program B Acceptance Standard IWA-5250 I l D-C D3.20 Integral attachments- Visual (VT-3) Integral attachments to See Notes (1) & (2) supports, restraints system boundary of component supports selected per IWF-2500 to be examined once during each inspection interval Includes 0.1g. No. IwD-2500-1 Acceptance Standard IWS-3516 l D-C D3.30 Integral attachments- Visual (VT-3) Integral attachments to See Notes (1) & (2) mechanical snubbers system boundary of component supports selected per IWF-2500 to be examined once during each inspection interval Includes Fig. No. IWD-2500-1 Acceptance Standard IWS-3516 i e T4.0-1(4) Rev. 2 01/87
O LGS ISOOGTA*2
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)
TAOLE 4.0-1 (Cent'd) INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS Item Components & parts Examination Examination Requirements Catonorv No. to be Examined Method For First 10-year Interval Remarks / Relief Reauest l D-C D3.40 Integral attachments- Visual (VT-3) Integral attachments to See Notes (1) & (2) spring type supports system boundary of component supports selected per IwF-2500 to be examined once during each inspection interval Includes Fig. No. IWD-2500-1 Acceptance Standard IWS-3516 D-C D3.50 Integral attachments- - - There are no constant constant load supports load supports D-C D3.60 Integral attachments- - - There are no shock shock absorbers absorbers (compensating struts) NOTES: (1) The system boundary includes only those portions of the system required to perform the safety system function up to and including the first normally closed valve or valves capable of automatic closure. For repairs and replacements within an isolable portion of a system, the boundary for the required pressure test may be limited to the isolable portion. (2) The required examination of integral attachments are to be performed once per inspection interval following a schedule provided in the Limerick Generating Station Unit I and Common Plant First 10-Year Interval Inservice Inspection Examination Plan. System pressurization is not a requirement during these VT-3 examinations. T4.0-1(5) Rev. 2 01/87
LGS ISI PROGRAM 4.3 EXAMINATION PLAN FOR ASME CODE CLASS 3 COMPONENTS The " Limerick Generating Station Unit 1 and Common Plant First 10-Year Interval Inservice Inspection Examination Plan" specifies the details as to how the ASME Section XI requirements are to be met. Included in the scope of the document are the details relating to component identification, location, access requirements, schedules, procedures, calibration blocks, special equipment, and other items necessary to perform the examination and pressure testing of ASME Code Class 3 systems. 4 Components that are subject to augmented inspection requirements are listed a second time in a separate section of the Examination Plan specifically for identifying and scheduling the augmented requirements. These components are identifie3 by the addition of a "(+)" symbol to the applicable ASME Code Category. () 4.3-1 Rev. 2, 01/87
- - - A- e a_ _ m .
O LGS ISI PROGRAM O l 4.4 REQUESTS FOR RELIEF FROM ASME SECTION XI REQUIREMENTS CLASS 3 SYSTEMS COMPONENTS None. O i 4.4-1 Rev. 2, 01/87
LGS ISI PROGRAM l LIMERICK GENERATING STATION UNIT 1 AND COMMON PLANT FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM LIST OF EFFECTIVE PAGES SECTION 5.0 NUMBER REVISION DATE l All Pages 2 01/87 e O s i l i LEP 5.0-1 Rev. 2, 01/87
LGS ISI PROGRAM 5.0 ASME CODE CLASS MC COMPONENT INSPECTION PROGRAM 5.1 INSPECTION PROGRAM FOR ASME COMPONENTS INCLUDED IN THE PRIMARY CONTAINMENT BOUNDARY In accordance with Federal Register 48 FR 5532, effective March 9, 1983 Statements of Consideration, the Inservice Inspection Program need not address Subsection INE of the Code. 48 FR 5532 incorporates, by reference, the Winter 1981 Addenda to the 1980 Edition of Section XI of the ASME Code in 10CFR50.55a. However, one of the changes affected by the Rule in 48 FR 5532 states, in part, "The regulation does not currently address the inservice inspection of containments. Since this amendment is only intended to update current regulatory requirements to include latest Code Addenda, the requirements of Subsection INE are not imposed upon Commission licensees by this amendment." 10CFR50.55a presently only incorporates those portions of Section XI that address the ISI requirements for ASME Code Class 1, 2, and 3 components and their supports. Since the inservice inspection program will be performed in accordance with the 1980 Edition through Winter 1981 Addenda of l Section XI of the ASME Code, the requirements of Subsection IWE for containment-related examinations are not applicable to Limerick Unit 1. () The pressure and structural integrity of the primary containment shall be determined by examination and testing in accordance with l Section 3/4.6 of the Limerick Technical Specifications. Piping l associated with isolation valves at the primary containment l penetrations shall be examined in accordance with the applicable ASME Code Class 1 or 2 Inspection Program as described in this I document. l Class MC component welds between penetrations and liner plate, access hatches and liner plate and pressure retaining welds not backed by concrete (e.g. flued head to penetration sleeve welds) l shall be examined and maintained in accordance with the Codes and Standards referenced in the Final Safety Analysis Report, Section l 3.8.2 and this section. l 5.1.1 TESTS FOLLOWING REPAIR, MODIFICATION, OR REPLACEMENT l 5.1.1.1 LEAKAGE TEST Except as noted in 5.1.1.2, repairs, modifications, and replacements of Class 1, 2, and MC components that are part of l the primary containment pressure retaining boundary shall be subjected to a pneumatic leakage test in accordance with the l 5.1-1 Rev. 2, 01/87 l - ._.- _-. _ _ - __ _ .
LGS ISI PROGRAM i
~~
provisions of Title 10, Part 50, of the Code of Federal Regulations, Appendix J, Paragraph IV.A, which states:
"Any major modification, replacement of a component which is i
part of the primary reactor containment boundary, or resealing a seal-welded door, performed after the l preoperational leakage rate test shall be followed by either i a Type A, Type B, or Type C test as applicable for the area affected by the modification. The measured leakage from this ! test shall be included in the report to the Commission required by the V.A. The acceptance criteria of III.A.S.(b), III.B.3., or III.C.3., as appropriate, shall be met. Minor l modifications, replacements, or resealing of seal-welded
- doors performed directly prior to the conduct of a scheduled Type A test do not require a separate test."
l 5.1.1.2 DEFERRAL OF LEAKAGE TESTS Leakage tests for the following minor repairs or modifications to ! the pressure retaining boundary may be deferred until the next l scheduled leakage test provided the applicable nondestructive examinations are performed. (a) welds of attachments to the surface of the pressure retaining boundary, (]) (b) repair cavities - the depth of which does not penetrate the required design wall by more than 10%, and l (c) Welds attaching penetrations that are NPS 1 or smaller. l 5.1.2 VISUAL EXAMINATION The requirements of IWA-5246 for visual examinations are l applicable. l 5.1.3 CORRECTIVE MEASURES If the leakage test requirements of 5.1.1.1 cannot be satisfied, the source of leakage shall be located and the area shall be examined to the extent necessary to establish the requirements for corrective action. Repairs shall be performed and leakage testing shall be reperformed prior to returning the component to service. 5.1-2 Rev. 2, 01/87 D e<-r-e- -<m e-wonw - m w- =---m e- w w~em w rn s v e wvew- w- +-o-- m---- m- wm s~-em-v.r- --m- - ---- - -
LGS ISI PROGRAM l LIMERICK GENERATING STATION UNIT 1 AND COMMON PLANT O' FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM LIST OF EFFECTIVE PAGES SECTION 6.0 NUMBER REVISION DATE l All Pages 2 01/87 O 4 l LEP 6.0-1 Rev. 2, 01/87
-v m mw .-m -w,--,e- ,m,- an-,n---o--mmw-----w-------ewmn-m, nee--------c- we--,,--w,--- e,---- --ww-- ww-ws v.m,w-a- --eww ,,-
-i LGS ISI PROGRAM p 6.0 ASME CODE CLASS 1, 2, & 3 COMPONENT SUPPORT INSPECTION d PROGRAM 6.1 GENERAL The Inservice Inspection Program for Class 1, 2, & 3 component supports has been developed in accordance with the requirements of Subsection IWF of ASME Section XI Code and Limerick Generating Station Technical Specification 3/4.7.4.
O f f l 6.1-1 Rev. 2, 01/87 i
LGS ISI PROGRAM 6.2 INSPECTION PROGRAM FOR ASME CODE CLASS 1, 2, 6 3 O' COMPONENT SUPPORTS The First 10-Year Interval Inservice Inspection Program for Class 1, 2, & 3 component supports shall commence with. commercial
; operation. Examinations will be performed either during normal system operation or plant outage. Class 1 & 2 support examinations shall be. scheduled as required by Section 1.5.
Class 3 support examinations will be scheduled at the frequency stated in Table 6.0-1. Detailed examination schedules for Class
- 1, 2, & 3 component supports are included in " Limerick Generating l Station Unit 1 and Common Plant First 10-Year Interval Inservice Examination Plan".
I j 6.2.2 EXAMINATION CATEGORIES AND REQUIREMENTS Inservice inspections of Class 1, 2, & 3 component supports shall, to the extent practical within the limitations of design,
! geometry, materials of construction and radiation considerations meet the requirements of the ASME Section XI Edition and Addenda specified in Section 1.4. Table 6.0-1 identifies the component supports subject to examination during the first 10-year interval. ASME Section XI, Table IWF-2500-1 identifies the VT-3 and VT-4 inspection requirements for component supports. The Examination Categories (F-A, F-B, and F-C) all require the same examination frequencies. As an alternative to categorizing component supports in the manner described in Table iWF-2500-1,
({} all component supports will be grouped together in Table 6.0-1 under Examination Category F-A, B, C Item No. FO.00. l 6.2.3 EXAMINATION TECHNIQUES AND PROCEDURES The techniques and procedures for visual, surface, and volumetric examinations shall meet the requirements of Section XI IWA-2200 as described below. Examinations, conducted in accordance with ASME Section V, shall use the 1980 Edition with Addenda through Winter 1981 or later Editions and Addenda. l Nondestructive examinations shall be performed using a written procedure. Requirements for written procedures are determined by l the referenced Code Section. Appropriate details and requirements may be included in a number of documents like the Examination and Testing Plans referenced in Section 1.3 and/or specific procedures. (1) Visual examinations of Class 1, 2, & 3 component supports i shall be performed in accordance with Section XI, IWA-2210 and Section V, Article 9. (See Footnote 2) 6.2-1 Rev. 2, 01/87 i
LGS ISI PROGRAM (2) When performed as a supplemental examination, surface (\ examinations of Class 1, 2, 6 3 component supports shall be in accordance with Section XI, IWA-2220 and Section V, Article 6 for liquid penetrant examinations and/or Section V, Article 7, for magentic particle examinations. (See Footnote 2) (3) When performed as a supplemental examination, volumetric examinations of Class 1, 2, 6 3 component supports by ultrasonic methods shall be in accordance with Section XI, IWA-2230, and Appendix III including Supplement 7 for welds in austenitic materials. Weld reflectors producing a response greater than 50% of reference level shall be recorded. Any indication detected in the weld and required volume not readily attributable to geometrical or metallurgical i conditions will be recorded regardless of ultrasonic amplitude response and investigated by a Level II or Level
- ' III examiner to the extent necessary to determine the shape, identity, and location of the reflector. PECo will disposition and take the appropriate corrective action for
- any indication investigated and evaluated to be other than geometrical or metallurgical in nature.
l For indictions determined to be related and intermitant, i .e. 4 (]) geometrical or metallurgical in nature, the shape, identity, and location of the reflector will only be recorded for the peak amplitude response of the related family of indications. , (See Footnote 2) (4) When radiography is used as a supplemental examination method, the examinations shall be performed in accordance , with Section V, Article 2. (See Footnotes 2, 3) (5) Alternative examination methods, including combinations of j visual, . surface and/or volumetric. methods, or. newl:r . developed techniques may be substituted for the above specifned methods provided that the results are demonstrated to be equivalent j or superior to those of the specified method. 6.2.4 EVALUATION OF EXAMINATION RESULTS For Class 1, 2, 6 3 component supports, evaluation of examination results and the criteria for acceptance for service shall be in accordance with ASME Section XI, IWF-3100. l (1) The acceptance criteria for continued service and preservice
- examination of repairs shall be in accordance with IWF-3120.
i l 6.2-2 Rev. 2, 01/87 5
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LGS ISI PROGRAM ' s (2) The acceptance criteria for replacements shall be in p)i s s accordance with IWF-3110. (See Footnote 1) v. 6.2.4.1 FLAW INDICATION CHARACTERIZATION Flaw indications detected during preservice and inservice examinations shall be characterized and compared with the ' acceptance standards specified in IWF-3400. 6.2.4.2 SUPPLEMENTAL AND ADDITIONAL EXAMINATION Visual examinations that detect surface indications that exceed IWF-3400 criteria shall be supplemented in accordance with IWF-3200. (See Footnote 2) 1 When the results of an examination require corrective measures in accordance with IWF-3000, additional examinations will be performed per IWF-2430. Re-examination of component supports which have received corrective measures shall be in accordance with IWF-2420 (b) and (c). 1 Footnotes ' l 1. Replacements are defined in Section XI, IWA-7100.
- 2. Supplemental examination methods or techniques may be used in
(]) the evaluation of a flaw indication. Surface flaws, detected during visual examinations, shall be supplemented by either surface or volumetric examination. Methods for supplemental surface examinations may include a repetition of the visual examination using improved techniques such as additional cleaning, improved lighting..the use of optical aids and/or surface replication.
- 3. Evaluation shall be in accordance with IWA-3370. An "a" dimension of " length /2" shall be used until such time as supplemental examinations per Footnote 2 are performed.
I i I l l 6.2-3 Rev. 2, 01/87
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J TABLE 6.0-1 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 1 2. & 3 COMPONENT SUPPORTS Item Components & Parts Examination Examination Requirements Category No. to be Enemined Method For First 10-year Interval Remarks / Relief Reauest
, l P-A.B.C FO.00 Mechanical connections Visual (VT-3) So?octed component supports. See Notes (1).(2),(3).
l to pressure retaining each inspection interval (4). & (5)
-' components and build- per IWF-2510 ing structure Includes Fig. No. IWF-1300-1 Acceptance Standard IWF-3410 l F-A.B.C FO.00 Weld connections to Visual (VT-3) Selected component supports. See Notes (1),(2),(3).
l building structure each inspection interval (4). & (5) per IWF-2510 Includes Fig. No. IWF-1300-1 Acceptance Standard IWF-3410 FO.00 Weld and mechanical Visual (VT-3) Selected component supports. See Notes (1),(2).(3) IF-A.B.C connections at each inspection interval (4). & (5) intermediate joints per IWF-25'O . in multiconnected integral and non- Includes Fig. No. IWF-integral supports 1300-1 Acceptance Standard IWF-3410 FO.00 Component displace- Visual (VT-3) Selected component supports. See Notes (1) (2),(3), IF-A.B.L ment settings of each inspection interval (4). & (5) guides and stops, per IWF-2510 misalignment of supports, assembly Includes Fig. No. IWF-1300-1 of support items Acceptance Standard IWF-3410 T6.0-1(1) Rev. 2. 01/87
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TAOLE 6.0-1 (Cont'd) INSERVICE INSPECTION PROGRAM ASME CODE CLASS 1 2. & 3 COMPONENT SUPPORTS Item Components & Parts Examination Examination Requirements Category No, to be Exam 9ned Method For First 10-vear Interval Remarks / Relief Request
, l F-A.8,C FO.00 Spring type supports. Visual (VT-4) Selected component See Notes (1).(2).(3) l constant load type supports each inspection (4). & (5)
- supports, mechanical a
interval per IWF-2510 I snubbers Includes Fig. No. IWF-1300-1 Acceptance Standard IWF-3410 1 F-A.B.C denotes the total population of component supports subject to examination including anchors, meChantCSI anubbers, restraints, and variable supports. NOTES: (1) Component supports selected for examination shall be the supports of those non-exempt systems or portions of systems that are required to be examined by volumetric, surface, or visual (VT-1 or VT-3) examination methods.
, (2) The examination boundaries for component supports are in accordance with IWF-1300. These boundartes are ! shown in detall on each support drawing. The items depicted on the support drawings will be visually examined in accordance with the examination schedule. A file titled "ISI Component Support Boundary Drawings" contains the dotatted drawings for each applicable support. This file will be maintained at Limerick by the Maintenance Department ISI Group.
(3) For multiple component supports within a system of similar design. function, and service, only one of the multiple component supports requires examination. (4) For component standard supports, refer to Relief Request Subsection 6.4.1. (5) The preservice examination requirements of IWF-2200 shall apply only to the supports of those Components that are required to be examined by volumetric, surface, or visual (VT-1 or VT-3) examination requirements. i T6.0-1(2) Rev. 2 01/87
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6.3 EXAMINATION PLAN POR ASME CODE CLASS 1, 2, & 3 COMPONENT ; SUPPORTS l l The " Limerick Generating Station Unit 1 and Common Plant First 10-Year Interval Inservice Inspection Examination Plan" specifies the details as to how the ASME Section XI requirements are to be i met. Included in this document are isometric drawings providing the support location and the details relating to component identification, access requirements, schedules, procedures, calibration block, special equipment, and other items necessary to perform the examination and testing of ASME Code Class 1, 2, and 3 component supports. Components that are subject to augmented inspection requirements are listed a second time in a separate section of the Examination Plan specifically for identifying and scheduling the augmented requirements. These components are identified by the addition of a "(+)" symbol to the applicable ASME Code Category. O 6.3-1 Rev. 2, 01/87 1
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6.4 REQUEST FOR RELIEF FROM ASME SECTION XI REQUIREMENTS - l CLASS 1, 2, & 3 COMPONENT SUPPORTS 6.4.1 RELIEF REQUEST Mechanical snubbers (shock suppressors) for ASME Code Class 1, 2, l & 3 components. 6.4.1.1 REQUIREMENT FROM WHICH RELIEF IS REQUESTED ASME Section XI, Table INF-2500-1, Category F-C, Item numbers F3.10 through F3.50 requires surface examinations (VT-3 and VT-4) of mechanical. type snubbers. These examinations are to be performed once per inspection interval on those snubbers selected in accordance with IWF-2510. 6.4.1.2 JUSTIFICATION l The mechanical snubbers for ASME Code Class 1, 2, & 3 components are currently subjected to an on going inspection and testing program detailed in the Limerick Technical Specification, Surveillance Requirements 3/4.7.4. This program is designed to demonstrate continued operational readiness and structural integrity of the mechanical snubbers. The inspection boundary for Technical Specification Examinations is from the snubber rear bracket attachment weld to the pipe clamp. The remaining portion of the snubber support is subject to examination in accordance O with the Section XI program. See Figure 6.4-1 for the examination boundaries. 6.4.1.3 ALTERNATE TO ASME SECTION XI REQUIREMENTS The IWF boundaries of mechanical snubbers will bo inspected and tested in accordance with a two-part program. The snubber from the rear bracket attachment weld to the pipe clamp will be inspected and tested in accordance with the Limerick Technical Specification, Surveillance Requirements 3/4.7.4. The remaining portion of the snubber structure will be examined in accordance. with the requirements of ASME Section XI. ' The surveillance requirements of Technical Specifications 3/4.7.4 meets or exceeds the requirements of ASME Section XI. The personnel who perform these examinations are certified in accordance with ASME Section XI. I 6.4-1 Rev. 2, 01/87
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SECT. XI TECH. SPEC. BOUNDARY BOUNDARY O _ ELEVATION (SNUBBER) f l P e FIGURE 6.4-1 SNUBBER BOUNDARIES l .
LGS ISI PROGRAM l LIMERICK GENERATING STATION UNIT 1 AND COMMON PLANT Cu FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM LIST OF EFFECTIVE PAGES SECTION 7.0 NUMBER REVISION DATE i l All Pages 2 01/87 O LEP 7.0-1 Rev. 2, 01/87 _..nnn,.---n,.--..,,na-.,.,_,n.w---,.-,,,.-,+-,--
LGS ISI PROGRAM 7.0 ASME CODE CLASS 1, 2, & 3 SAFETY-RELATED PUMP TESTING O. PROGRAM 7.1 GENERAL The inservice operability testing program for safety-related ASME Code Class 2 & 3 pumps provided with an emergency power source has been developed in accordance with the requirements of Subsection IWP of the 1980 Edition of ASME Section XI with Addenda through Winter 1981. The only ASME Code Class 1 pumps are in the recirculation system and they are exempted from the scope of this program. Details of the inservice testing programs for pumps are provided in the inservice Testing Plan for Pumps. Refer to Appendix A of document:
" Pump and Valve Inservice Inspection Program (Testing) Plan for Limerick Generating Station - Unit 1"; NES document No.
80A2972, Rev. 5; Bechtel Vendor Print No. 8031-M-246A-257-2S; or later approved revisions and supplements. Appendix A of 80A2972 above lists the pumps to be tested, the ASME Code Class, the hydraulic circuit to be used, test frequency, location, and parameters to be measured. Reference values required per ASME Section XI, Tables IWP-3100-1 & IWP-3100-2 are filed with the applicable pump test records. O The Inservice Testing Plan for Pumps shall be initiated at the start of Unit 1 commercial operation and shall be in effect for the first 10-year interval. ] 7.1-1 Rev. 2, 01/87 l . i
LGS ISI PROGRAM 7.2 OPERABILITY TESTING PROGRAM 4 Safety-related ASME Code Class 2 and 3 pumps, provided with an emergency power source, shall meet the requirements of ASME Section XI, Subsection INP, as defined in this document and the Inservice Testing Plan for Pumps. The following components are not included in the Pump list in Appendix A of 80A2972 above: (1) Pump drivers where the pump and driver are not an integral unit with common bearings. (2) ASME Code Class 2 and 3 pumps with an emergency power source solely for operating convenience. Components identified in Items 1 & 2 above are exempt from the requirements of ASME Section XI Subsection IWP but may require NDE and pressure tests per ASME Section XI Subsection IWC and IWD 2 depending on the applicable Quality Group classification. Inservice tests on pumps will be performed with the test frequencies specified in Appendix A of 80A2972 above. The pump test frequencies comply with ASME Section XI Subsection INP-3400. Consistent with the treatment of surveillance test in the Technical Specifications, NUREG 1149, these test frequencies may be adjusted plus or minus 25 percent. O interval has exceeded 100 percent of the specified interval, the In casos where the elapsed ! next test interval shall commence at the end of the originally specified interval. l Pump tests may be cancelled at the discretion of the Shift Superintendent or his alternate when in his judgement the test could place the plant in an unsafe condition. Examples of this situation include tests where a failure could negate the safety function of a system and situations where a component is inoperable and testing of the redundant component may cause an
- undesirable transient or if radiation levels higher than those
- consistent with the ALARA concept are encountered. ;
- Cold shutdown inservice testing will be performed under the following conditions. Testing will commence as soon as cold shutdown conditions are achieved, but not later than 48 hours after shutdown, and continue until all tests are complete or the plant is ready to return to power. Completion of all testing is ,
l' not a prerequisite to return to power. Any testing not completed l at one cold shutdown will be performed during subsequent cold l l shutdowns. For planned long duration cold shutdowns where all pump testing will be completed, the above mentioned 48-hour ! i 7.2-1 Rev. 2, 01/87 i () o l
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LGS ISI PRCYo" RAM criteria will not apply. Certain pump tests specified as cold shutdown may be conducted during the mode change approaching cold shutdown conditions. A by-pass loop is provided for those pumps that cannot practically be tested using the regular hydraulic circuit. I O k l ,. 7.2-2 Rev. 2, 01/87
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4 LGS ISI PROGRAM t x- 7.3 REPAIRS AND REPLACEMENTS
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. After a pump has been replaced, a new set or sets of reference > values shall be determined from the results of the first , inservice test run after the pump is put into service. When a , reference value or set of values may have been affected by repair j or routine servicing of the pump, a new reference value or set of values shall be determined or the previous value reconfirmed by an inservice test run prior to or within 96 hours after return of the pump to normal service. Deviations between the previous and new set of reference values shall be identified and verification that the new values represent acceptable pump operation shall be placed in the record of tests ASME Section XI Subsection
; IWP-6000).
If deviations fall within the Alert Range of ASME Section XI Table IWP-2100-2, the frequency of testing specified in ASME ' Section XI IWP-3400 shall be doubled until the cause of the deviation is determined and the condition corrected. 1 If deviations fall within the Required Action Range of ASME Section XI Table IWP-3100-2, the pump shall be declared inoperative and not returned to service until the cause of the deviation has been determined and the condition corrected. I Correction shall be either replacement or repair per ASME Section O XI IWP-3111 or shall be an analysis to demonstrate that the condition does not impair pump operability and that the pump will 4 still fulfill its function. A new set of reference values shall be established after such analysis. When tests show deviations greater than allowed (see ASME Section XI Table IWP-3100-2), the instruments involved may be
- recalibrated and the test rerun.
Repairs shall be made in accordance with ASME Section XI
, IWA-4000, IWA-5000, and this document. . Replacements shall be i
made in accordance with ASME Section XI INA-7000, IWA-5000, and this document. Constraints on Unit 1 start-up (and operation) due to inoperable equipment shall be determined by the Limiting Conditions for Operation given in the Limerick Technical Specifications, NUREG 1149. i 4 l i
, 7.3-1 Rev. 2, 01/87 i,
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LGS ISI PROGRAM l LIMERICK GENERATING STATION UNIT 1 AND COMMON PLANT O. FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM LIST OF EFFECTIVE PAGES SECTION 8.0 NUMBER REVISION DATE l All Pages 2 01/87 O i l l 1 l i l LEP 8.0-1 Rev. 2, 01/87 i O I l l l L
LGS ISI PROGRAM i
# 8.0 ASME CODE CLASS 1, 2, & 3 SAFETY-RELATED VALVE TESTING a
PROGRAM 8.1 GENERAL
, The inservice operability testing program for safety-related ASME 4
Code Class 1, 2, & 3 valves has been developed in accordance with , the requirements of Subsection IWV of the 1980 Edition of ASME Section XI with Addenda through Winter 1981. Details of the inservice testing programs for valves are provided in the inservice Testing Plan for Valves. Refer to Appendix B of i document:
" Pump and Valve Inservice Inspection Program (Testing) Plan for Limerick Generating Station - Unit 1"; NES document No.
80A2972, Rev. 5; Bechtel Vendor Print No. 8031-M-246A-257-2S; or later approved revisions and supplements. Appendix B of 80A2972 above lists the valves to be tested, the ASME Section XI Category, test frequency, type of test, and any relief request from Section XI requirements. The Inservice Testing Plan for Valves shall be initiated at the start of Unit 1 commercial operation and shall be in effect for the first 10-year interval. O i h l i i l 8.1-1 Rev. 2, 01/87 t i e ,.-,.-------ww -.. ,_- - -- ,s- , - - + - - . - , , , , , . - , , - -, -- ,-w,,,----wi, ..w.m-, - . - , . - - -r
LGS ISI PROGRAM i 8.2 OPERABILITY TESTING PROGRAM Safety-related ASME Code Class 1, 2, & 3 valves and their actuating and position-indicating systems shall meet the requirements of ASME Section XI Subsection IWV as defined in this document and the Inservice Testing Plan for Valves. Categories of valves subject to the above requirements are defined as: (1) Category A - Valves for which seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their function. (2) Category B - Valves for which seat leakage in the closed position is inconsequential for fulfillment of their function. (3) Category C - Valves which are self-actuating in response to some system characteristic such as pressure (relief valves) or flow direction (check valves). (4) Category D - Valves which are actuated by an energy source capable of only one operation such as rupture discs or explosive-actuated valves. The following valves are not included in the valve list in s Appendix B of 80A2972 abover (1) Valves used for operating convenience like vent, drain, instrument, and test valves. (2) Valves used for system control like pressure-reducing valves. (3) Valves used in external control and protection systems responsible for sensing plant conditions and providing signals for valve operation. (4) Excess flow check valves which will be leak rate and operability testing in accordance with the Limerick Technical Specifications. (5) Standby Diesel Generator skid-mounted valves (FSAR Figures 9.5-9 through 9.5-11). Their operability will be verified in conjunction with Standby Diesel Generator test performed in accordance with the Limerick Technical Specification. 8.2-1 Rev. 2, 01/87
l 1 LGS ISI PROGRAM I
'>. Valves identified in Items 1, 2, and 3 above are exempt from the requirements of ASME Section XI Subsection IWV but may require NDE and pressure testing per ASME Section XI Subsection INB, IWC, and IWD depending on the applicable Quality Group classification. l Category A valves that perform a containment isolation function will be tested to meet the criteria of Appendix J to 10CFR50.
Category A valves which perform a pressure isolation function will be tested to meet the requirements of ASME Section XI, INV-3420. i Inservice tests on valves will be performed with the test frequencies specified in Appendix B of80A2972 above. The valve 1 test frequencies comply with ASME Section XI, INV-3400, 3500, and , 3600. Consistent with the treatment of surveillance test in the i Limerick Technical Specifications, these test frequencies may be ' adjusted plus or minus 25 percent. In cases where the elapsed interval has exceeded 100 percent of the specified interval, the
, next test interval shall commence at the end of the originally specified interval.
l Valve exercising tests may be cancelled at the discretion of the Shift Superintendent or his alternate when in his judgement the test could place the plant in an unsafe condition. Examples of this situation include certain valves inside containment where a test failure could negate the safety function of a system and l situations where a component is inoperable and testing of the i redundant component may cause an undesirable transient or if radiation levels higher than those consistent with the ALARA concept are encountered. ! Cold shutdown inservice testing will be performed under the following conditions. Testing will commence as soon as cold l shutdown conditions are achieved, but not later than 48 hours l after shutdown, and continue until all tests are complete or the i plant is ready to return to power. Completion of all testing is i not a prerequisite to return to power. Any testing not completed
- at one cold shutdown will be performed during subsequent cold l shutdowns. For planned long duration cold shutdowns where all l pump testing will be completed, the above mentioned 48-hour criteria will not apply. Certain pump tests specified as cold shutdown may be conducted during the mode change approaching cold shutdown conditions.
i 8.2-2 Rev. 2, 01/87 i() ! i 1
LGS ISI PROGRAM 8.3 REPAIRS AND REPLACEMENTS ASME Section XI, IWV-3417 requires corrective action if the measured stroke time for a valve which normally strokes in ten seconds or less varies by fifty percent from the last measured time. ASME Section XI, IWV-3413 allows measurement to the nearest second for stroke times of ten seconds or less. For rapid actuating solenoid and air-operated valves with stroke times of five seconds or less, the application of the above criteria could result in requiring corrective action when the valves are functioning normally. To preclude this, the following criteria will be used for valves with normal stroke times of five seconds or less. If the stroke time is determined to be less than five seconds, the valve will be considered operable without comparing stroke time with previous test results. If the time exceeds five seconds, corrective action will be taken. For valves with stroke times greater than five seconds, the requirements of ASME Section XI, IWV-3417 and IWV-3413 will apply. Repairs shall be made in accordance with ASME Section XI IWA-4000, IWA-5000, and this document. Replacements shall be made in accordance with Section XI IWA-7000, IWA-5000, and this document. O
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Constraints on Unit 1 start-up (and operation) due to inoperable equipment shall be determined by the Limiting Conditions for Operation given in the Limerick Technical Specifications, NUREG 1149. i 8.3-1 Rev. 2, 01/87 _ _ _ - - _ _ _ - . .- . _ ___ _ _ __. _ _ _ _ _ _ _ _}}