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Revised QUALITY DATE ASSURANCE APPENDIX B 12/31/93 MANUAL R.E. GINNA NUCLEAR POWER PLANT GINNA STATION INSERVICE INSPECTION PROGRAM PAGE FOR THE 1990-1999 INTERVAL 1 of 5 TABLE OF CONTENTS Section 1.0 Inservice Inspection Program: 1.0 Introduction 1 ~ 1 General 1.2 Applicable Documents 1 ~ 3 Inspection Intervals 1.4 Classification of Components 1.5 Responsibility 1.6 Records 1.7 Examination Methods and Requirements 1.8 Repair Requirements 1.9 Replacement Requirements 1. 10 System Pressure Testing 2.0 Class 1 Program Plan 2.1 Basis for Preparation 2.2 Components Subject to Examination 2.3 Extent and Frequency of Examinations 2.4 Exemption Criteria 2.5 Examination of Reactor Coolant Pump Flywheels 2.6 Inservice Inspection Program Plan 3.0 Class 2 Program Plan 3.1 Basis for Preparation 3.2 Components Subject to Examination 3.3 Extent and Frequency of Examinations 3.4 Exemption Criteria 3.5 Inservice Inspection Program Plan 4.0 Class 3 Program Plan 4.1 Basis for Preparation 4.2 Components Subject to Examination 4.3 Extent and Frequency of Examinations 4 4 Exemption Criteria 4.5 Inservice Inspection Program Plan 5.0 Class 1, 2 & 3 Component Supports 5.1 Basis for Preparation 5.2 Components Subject to Examination 5.3 Extent and Frequency of Examinations 5.4 Exemption Criteria 5.5 Inservice Inspection Program Plan 9401250044 940111. PDR ADOCK 05000244. 8 'DR QUALITY TITLE: DATE ASSURANCE APPENDIX B 12/31/93 MANUAL R.E. GINNA NUCLEAR POWER PLANT GINNA STATION INSERVICE INSPECTION PROGRAM PAGE FOR THE 1990-1999 INTERVAL 2 of 5 Section 2.0 Relief Requests: 1.0 Introduction 1.1 General Section 3.0 P&ID Boundary Drawings: 1.0 General P&ID Boundary Drawings Section 4.0 Code Tables: 1.0 General Table 1, Class 1 Table 2, Class 2 Table 3, Class 3 Table 4, Class 1, 2, & 3 IWF Component Supports Section 5.0 Line List: 1.0 General Line List Section 6.0 Allocation Tables: 1.0 General ASME Code Requirements Class 1 Class 2 Class 3 Class 1,2, & 3 Supports Augmented Reactor Coolant Pump Flywheel Program Reactor Vessel Augmented Program, Category B-A High Energy Program Snubber Program Seismic Support Program QUALITY DATE ASSURANCE APPENDIX B 12/31/93 MANUAL R.E. GINNA NUCLEAR POWER PLANT GINNA STATION INSERVICE INSPECTION PROGRAM PAGE FOR THE 1990-1999 INTERVAL 3 of 5 Section 7.0 UT Calibration Blocks: 1.0 General UT Calibration Blocks Section 8.0 High Energy Program: 1.0 General 2.0 Examination Requirements 3.0 Examination Methods 4.0 Frequency of Examination 5.0 Examination Evaluation 6.0 Repair & Testing Requirements 7.0 Replacement & Testing Requirements 8.0 Scheduling 9.0 Reports & Records Table 1 — High Energy Welds & Component Support Identification. Section 9.0 Snubber Program: 1.0 General 2.0 Examination, Testing & Monitoring Requirements 3.0 Examination & Testing Methods 4.0 Examination & Testing Frequency 5.0 Examination, Testing & Monitoring Evaluation 6.0 Repair, Replacement & Modification Requirements 7.0 Scheduling 8.0 Reports & Records Section 10.0 Seismic Support Program: 1.0 General 2.0 Examination Requirements 3.0 Examination Methods 4.0 Frequency of Examination 5.0 Examination Evaluation 6.0 Repair & Testing Requirements 7.0 Replacement & Testing Requirements 7.0 Scheduling 8.0 Reports & Records QUALITY DATE ASSURANCE APPENDIX B 12/31/93 MANUAL R.E. GINNA NUCLEAR POWER PLANT GINNA STATION INSERVICE INSPECTION PROGRAM PAGE FOR THE 1990-1999 INTERVAL 4 ot 5 Section 11.0 Additional Programs: 1.0 General 2.0 Steam Generator Tube Inspection Program 2.1 General 2.2 Examination Requirements 2.3 Examination Methods 2.4 Frequency of Examination 2.5 Examination Evaluation 2.6 Repair, Replacement & Testing Requirements 2.7 Scheduling 2.8 Reports & Records 3.0 Reactor Coolant Pump Flywheel Program 3.1 General 3.2 Examination Requirements 3.3 Examination Methods 3.4 Frequency of Examination 3.5 Examination Evaluation 3.6 Repair, Replacement & Testing Requirements 3.7 Scheduling 3.8 Reports & Records 4.0 Class 1 Bolting Program (IEB 82-02) 4.1 General 4.2 Examination Requirements 4.3 Examination Methods 4.4 Frequency of Examination 4.5 Examination Evaluation 4.6 Repair, Replacement & Testing Requirements 4.7 Scheduling 4.8 Reports & Records 5.0 Reactor Vessel Augmented Program, Category B-A 5.1 General'.2 Examination Requirements 5.3 Examination Methods 5.4 Frequency of Examination 5.5 Examination Evaluation 5.6 Repair, Replacement & Testing Requirements 5.7 Scheduling 5.8 Reports & Records QUALITY TITLE: DATE ASSURANCE APPENDIX B 12/31/93 MANUAL R.E. GINNA NUCLEAR POWER PLANT GINNA STATION INSERVICE INSPECTION PROGRAM PAGE FOR THE 1990-1999 INTERVAL 5 of 5 SUPPLEMENT 1 TO APPENDIX B "Inservice Inspection Program Plan" (Separate Document controlled by Materials Engineering 6 Inspection Services.) SUPPLEMENT 2 TO APPENDIX B "The Repair, Replacement and Modification Program" QUALITY ASSURANCE MANUAL PAGE GINNA STATION Section 1 1 of 34 EFFECTIVE DATE: December 31, 1993 ROCHESTER GAS 8E ELECTRIC CORPORATION SIGNATURE DATE TITLE PREPARED BY: +Dt ( q3 APPENDIX B p g ~ QUALITY R. E. GINNA NUCLEAR POWER PLANT ASSURANCE INSERVICE INSPECTION PROGRAM REVIEW: FOR THE 1990-1999 INTERVAL APPROVE BY: 1.0 INTRODUCTION General This Appendix "B" to the Quality Assurance Manual outlines the third interval inservice inspection examination (ISI) requirements for Class 1, Class 2, and Class 3 systems, and components for Rochester Gas & Electric Corporation's (RG&E) R. E. Ginna Nuclear Power Plant (Ginna Station). The third inspection interval begins on January 1, 1990, as permitted by Paragraph IWA-2400 of ASME Code Section XI, the second interval concluded December 31,1989. 1.1.1 This program is based on the requirements of the 1986 Edition of the American Society for Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, "Inservice Inspection of Nuclear Power Plant Components" as adopted by the Code of the Federal Regulations, 10 CFR Part 50, (Federal Register 53FR16051) May 5, 1988. 1. 1.2 This program excludes'he controls of the Enforcement Authority, and N-Stamp, in addition to IWE of ASME Section XI, since it is not endorsed by'the Regulation. 1 ~ 1 ~ 3 Inservice Testing of pumps (IWP) and valves (IWV) is performed in accordance with Appendix C of the Ginna Station Quality Assurance Manual. TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVXCE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 XNTERVAL 2 of 34 1.2 Applicable Documents RG&E has adopted the following documents as the basis for the third inspection interval and is committed to satisfying their requirements. Specific exceptions to the requirements of ASME Section XI are identified and located in the "Relief Requests", Section 2.0 of this document. This program was developed in accordance with these documents: 1 ~ 2.1 ASME Boiler and Pressure Vessel Code Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 1986 Edition, no Addenda. 1.2. 1. 1 ASME Boiler & Pressure Vessel Code, Section XI, 1986 Edition, no Addenda, Appendix IV. 1 '.2 U.S. Nuclear Regulatory Commission (USNRC) Regulatory Guides: a ~ 1.14, Rev. 1, "Reactor Coolant Pump Flywheel Integrity" b. 1.147, Latest Revision, "Xnservice Inspection Code Case Acceptability — ASME Section XI, Division l" c ~ 1.150, Rev. 1, "Ultrasonic Testing of Reactor Vessel Welds During Preservice and Xnservice Examinations" d. 1.83, Rev. 1, "Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes" e. 1.26, Rev. 3 "Quality Group Classifications and Standards for Water, Steam, and Radioactive Waste Containing Components of Nuclear Power Plants. 1.29, Rev. 3, "Seismic Design Classification". g 1.121, Rev. 0, "Bases for Plugging Degrated PWR Steam Generator Tubes". TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GXNNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 3 of 34 h. 1.65, Rev..0, "Materials and Inspections for Reactor Vessel Closure Studs". 1.2.3 ASME Code Cases In accordance with 10CFR50.55a, Footnote 6, ASME Section XI Code Cases referenced in Regulatory Guide 1.147, "Xnservice Inspection Code Case Acceptability- ASME Section XX, Division 1," may be incorporated into the Ginna Station ISI Program. Those Code Cases included in Regulatory Guide 1.147 that will be implemented at Ginna Station are identified in this section. Each Code Case is preceded by information on the applicable component/area, ASME requirements, and how the Code Case will be implemented. Paragraph 1.2.3.1 lists those code cases that have been technically reviewed and endorsed, with or without conditions by the NRC in Regulatory Guide 1.147 and will be implemented during the 3rd ten year Inspection Interval. Use of any subsequent NRC endorsed code cases that are identified in revisions to the Regulatory'uide 1.147 may be incorporated in the program and used during the 3rd ten year Inspection Interval. 1.2.3.1 USNRC Regulatory Guide 1.147 — Approved ASME Section XI Code Cases Code Case No. Sect. XI References Com onent Area N 307-1 IWB-2500-1 Studs and Bolts with Heater Holes N-416 IWA-4400 Any repaired or replaced Class 2 piping component that cannot be isolated by valves or requires securing safety/ relief valves. N-401 IWA-2233 Eddy Current Examinations TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 4 of 34 N-402 IWA-2233 Eddy Current Calibration Standard Material N-427* Code Cases Code Cases in Inspection Plans N-437 IWA-5260 Use of digital readout and digital measurement devices for performing Pressure Tests.
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