ML17263A523

Revised ISI Program for 1990-1999 Interval.

ML17263A523
Person / Time
Site:	Ginna
Issue date:	12/31/1993
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17263A522	List: ML17263A521 ML17263A523
References
PROC-931231, NUDOCS 9401250044
Download: ML17263A523 (519)

Text

QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL DATE PAGE 12/31/93 1 of 5 TABLE OF CONTENTS Section 1.0 Inservice Inspection Program: 1.0 1~1 1.2 1~3 1.4 1.5 1.6 1.7 1.8 1.9 1.10 2.0 2.1 2.2 2.3 2.4 2.5 2.6 3.0 3.1 3.2 3.3 3.4 3.5 4.0 4.1 4.2 4.3 4 4 4.5 5.0 5.1 5.2 5.3 5.4 5.5 Introduction General Applicable Documents Inspection Intervals Classification of Components Responsibility Records Examination Methods and Requirements Repair Requirements Replacement Requirements System Pressure Testing Class 1 Program Plan Basis for Preparation Components Subject to Examination Extent and Frequency of Examinations Exemption Criteria Examination of Reactor Coolant Pump Flywheels Inservice Inspection Program Plan Class 2 Program Plan Basis for Preparation Components Subject to Examination Extent and Frequency of Examinations Exemption Criteria Inservice Inspection Program Plan Class 3 Program Plan Basis for Preparation Components Subject to Examination Extent and Frequency of Examinations Exemption Criteria Inservice Inspection Program Plan Class 1, 2&3 Component Supports Basis for Preparation Components Subject to Examination Extent and Frequency of Examinations Exemption Criteria Inservice Inspection Program Plan 9401250044 940111.PDR ADOCK 05000244.8'DR QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL DATE PAGE 12/31/93 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 Section 5.0 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 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 ASSURANCE MANUAL GINNA STATION APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL DATE PAGE 12/31/93 3 of 5 Section 7.0 UT Calibration Blocks: 1.0 General UT Calibration Blocks Section 8.0 High Energy Program: 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 General Examination Requirements Examination Methods Frequency of Examination Examination Evaluation Repair&Testing Requirements Replacement

&Testing Requirements Scheduling Reports&Records Table 1-High Energy Welds&Component Support Identification.

Section 9.0 Snubber Program: 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 General Examination, Testing&Monitoring Requirements Examination

&Testing Methods Examination

&Testing Frequency Examination, Testing&Monitoring Evaluation Repair, Replacement

&Modification Requirements Scheduling Reports&Records Section 10.0 Seismic Support Program: 1.0 2.0 3.0 4.0 5.0 6.0 7.0 7.0 8.0 General Examination Requirements Examination Methods Frequency of Examination Examination Evaluation Repair&Testing Requirements Replacement

&Testing Requirements Scheduling Reports&Records QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL DATE PAGE 12/31/93 4 ot 5 Section 11.0 Additional Programs: 1.0 2.0 3.0 4.0 5.0 5.7 5.8 General 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 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 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 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 Scheduling Reports&Records QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL DATE PAGE 12/31/93 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 GINNA STATION Section 1 EFFECTIVE DATE: PAGE 1 of 34 December 31, 1993 ROCHESTER GAS 8E ELECTRIC CORPORATION SIGNATURE DATE TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL PREPARED BY: p+Dt g~(q3 QUALITY ASSURANCE REVIEW: APPROVE BY:

1.0 INTRODUCTION

General 1.1.1 1.1.2 1~1~3 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.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.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.

Inservice Testing of pumps (IWP)and valves (IWV)is performed in accordance with Appendix C of the Ginna Station Quality Assurance Manual.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVXCE INSPECTION PROGRAM FOR THE 1990-1999 XNTERVAL REV.3 PAGE 2 of 34 Section 1 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 1.2.1.1 1'.2 ASME Boiler and Pressure Vessel Code Section XI,"Rules for Inservice Inspection of Nuclear Power Plant Components," 1986 Edition, no Addenda.ASME Boiler&Pressure Vessel Code,Section XI, 1986 Edition, no Addenda, Appendix IV.U.S.Nuclear Regulatory Commission (USNRC)Regulatory Guides: a~b.1.14, Rev.1,"Reactor Coolant Pump Flywheel Integrity" 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".

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GXNNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.Section 1 3 PAGE 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 been technically reviewed and without conditions by the NRC 1.147 and will be implemented year Inspection Interval.code cases that have endorsed, with or in Regulatory Guide during the 3rd ten 1.2.3.1 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.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 QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.Section 1 3 PAGE 4 of 34 N-402 IWA-2233 Eddy Current Calibration Standard Material N-427*N-437 N-446 Code Cases IWA-5260 IWA-2300 Code Cases in Inspection Plans Use of digital readout and digital measurement devices for performing Pressure Tests.Recertification of Visual Examination Personnel.

N-460 N-481 N-491 IWA-2000/3000 B-L-1, Item B12.10 IWF-1000/2000/3000 Alternative examination coverage for Class 1 and Class 2 welds.Alternative examination requirements for Cast Austenitic Pump Casings.Alternative rules for examination of Class 1, 2, 3, and MC Component Supports of Light Water Cooled Power Plants.N-498 IWX-5000 Alternative rules for 10-year Hydrostatic Pressure Testing for Class 1 and 2 systems.1.2.4*As amended by USNRC Regulatory Guide 1.147, April, 1992.R.E.Ginna Updated Final Safety Analysis Report (UFSAR): Section 5.4-For Class 1 Section 6.6-For Class 2 and 3 1 A I I'I QUALITY ASSURANCE MANUAL GXNNA STATXON TITLE: APPENDIX B R.E.GXNNA NUCLEAR POWER PLANT INSERVXCE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.Section 1 3 PAGE 5 of 34 1.2.5 Letter dated March 23, 1981, from Darrell G.Eisenhut, Director, Division of Licensing, USNRC, regarding Technical Specification Revisions for Snubber Surveillance 1.2.5.1 First Addenda to ASME/ANSI OM-1987, Part 4 Published in 1988.1.2.6 1.2.7 1.2.8 USAS B31.1.0-1967,"Power Piping" for High Energy Systems R.E.Ginna, Technical Specification 4.2."Inservice Inspection".

R.E.Ginna Technical Specification 3.13 and 4.14"Snubbers".

1.2.9 Letter dated February 16, 1989, to Mr.Carl Stahle, USNRC, PWR Project Directorate No.1, regarding proposed changes to Snubber Technical Specification R.E.Ginna Nuclear Power Plant, Docket No.50-244.1.2.10 1.2.11 1.2.12 1.2.13 1'1.3.1 Rochester Gas and Electric Corporation Mechanical Engineering Specification, ME-256, Titled-"Snubber Inspection and Test Program".Electric Power Research Institute PWR Steam Generator Inspection Guidelines, Rev.2.Code of the Federal Regulations, 10CFR Part 50.USNRC, NRC Region I Inspection Report 50-244/90-12, Section 3.4 regarding repair program"Service Induced" and"Code Rejectable" repairs.Inspection Intervals The inservice inspection intervals for Class 1 components started on January 1, 1970, with the second interval starting on January 1, 1980.The third inspection interval shall start on January 1, 1990.

QUALITY ASSURANCE MANUAL GXNNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVXCE XNSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.3 PAGE 6 ot 34 Section 1 1.3.2 1.3'For Class 2 and Class 3, the first inspection interval started on May 1, 1973;the second on January 1, 1980;and the third on January 1, 1990.The third inspection interval for Class 1, 2 and 3 is scheduled to end December 31, 1999.However, this date is subject to change as allowed by IWA-2400, which states that each inspection interval may be decreased or extended (but not cumulatively) by as much as one year.If R.E.Ginna Nuclear Power Plant is out of service continuously for 6 months or more, the inspection interval and associated period during which the outage occurred may be extended for a period of time equivalent to the outage.1.3.4 A 10-year examination Program Plan (Supplement 1 to Appendix B), will describe the distribution of examinations for Class 1, Class 2, and Class 3 components in accordance with Inspection Program B, the IWB-2400, IWC-2400, IWD-2400 and IWF-2400 of Section XI,"Rules for Inservice Inspection of Nuclear Power Plant Components", 1986 Edition, no Addenda.1.4 Classification of Components The Program Plan components and piping have been classified by RG&E for purposes of inservice inspection based on Section XI, Article IWA-1320, and definitions contained in 10CFR50.2.

l.5 Responsibility As specified in Paragraph IWA-l400 of ASME Section XI, RG&E bears the overall responsibility for implementation of an XSX program.Administrative Procedures, NDE Procedures, ISX Plans and Schedules are'in place to control and implement these Inservice Xnspection requirements.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.Section 1 3 PAGE 7 of 34 1.6 Records Examination records and documentation of results provide the basis for evaluation and facilitate comparison with previous results and subsequent inspections.

In accordance with Section XI, IWA-6000, these records will be maintained for the plant life.1.6.1 An Inservice Inspection Report shall be generated to document applicable Inservice Xnspection and associated Repair, Replacement and Modification activities.

ASME NXS-1 and NIS-2 Forms shall be generated and included within the Xnservice Inspection Report.f 1.7 Examination Methods and Requirements Examination methods which will be used to satisfy Code examination requirements have been listed for nonexempt Class 1, Class 2, and Class 3 components, as applicable.

Provided in the following is a brief explanation of the examination methods which will be performed to satisfy the Code requirements.

Personnel performing nondestructive examinations will be qualified in accordance with written procedures prepared as required by Paragraph IWA'-2300 of Section XI.Methods of examination are also described in the applicable sections of this Inservice Inspection Program.1.7.1 Visual Examination Method Visual examinations (VT)will be performed in accordance with IWA-2210 of ASME Section XI.IWA-2210 defines the three types of VT examinations as follows:

I U)l I lt 1' QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.3 PAGE 8 of~34 Section 1 1.7.1.1 VT-1 examinations are 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 components.

This type of examination may be performed by direct or remote methods as defined in IWA-2211.1.7.1.2 VT-2 examinations're conducted to detect leakage (or abnormal leakage)from pressure-retaining components during system pressure or functional tests as defined in IWA-2212.1.7.1.3 VT-3 examinations are conducted to determine general mechanical and structural conditions of components and their supports such a's the presence of loose parts, debris, or abnormal corrosion products, wear, erosion, corrosion, and the loss of integrity at bolted or welded connections.

VT-3 Examinations are also conducted to determine conditions related to operability of mechanical and hydraulic snubbers, and spring devices.1.7.2 Surface Examination Method 1.7.2.1 A surface examination is performed to detect the presence of discontinuities open to the surface of a material.Techniques for surface examination include either magnetic particle (MT)or liquid penetrant (PT)methods.Surface examinations will be conducted as defined in IWA-2220.1.7.3 Volumetric Examination Method 1.7.3.1 A volumetric examination is performed to detect the presence of discontinuities in the volume of a material.Such volumetric examinations include radiographic (RT), ultrasonic (UT), and eddy current (ET).Volumetric examinations will be conducted as defined in IWA-2230.1.7.3.2 Radiography may be performed by utilizing either x-ray or gamma ray techniques.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.Section 1 3 PAGE 9 of 34 1.7.3.3 The UT examinations may be performed by utilizing either manual or mechanized UT (Mech UT)techniques in accordance with Appendix I of Section XI and Regulatory Guide 1.150,~Rev.1'for the Reactor Vessel Examination only.1.7.3.4 The ET Method will be utilized in the examination of heat exchanger tubing in accordance with Appendix IV of ASME Section XI and USNRC Regulatory Guide 1.83.1.7.4 Alternative Examination Methods 1.7.4.1 Alternative examination methods may be performed to those described in 1.7.1, 1.7.2 and 1.7.3 as allowed in IWA-2240.These may include such things as newly developed techniques, provided that these alternative methods are shown by practical demonstration to be equivalent or superior to those of the specific method to the satisfaction of the Level III NDE Examiner&Authorized Nuclear Inservice Inspector (ANII).1.7.4.2 l.7.5 Examinations that detect flaws which require evaluation may be supplemented by other examination methods and techniques to determine the character of the flaw.Evaluation of Examination Results and Successive Inspections l.7.5.1 The evaluation of nondestructive examination results shall be in accordance with Article IWA-3000 of Section XI.All reportable indications will be subject to comparison with previous data to aid in characterization and determination of origin.Class 1 and Class 3 components containing relevant service induced conditions will be considered acceptable for continued service providing an analytical evaluation performed demonstrates the component's acceptability and is subsequently examined in accordance with the requirements of IWB-3132.4, IWB-3142.4 and IWB-3144(b).

Acceptance by Repair or Replacement can also be performed.

Successive inspections for Class 1 relevant service induced conditions shall comply with the

QUALITY ASSURANCE MANUAL GINNA STATXON TITLE: APPENDIX B R.E.GXNNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.3 PAGE 10 of 34 Section 1 requirements of IWB-2420(b) and (c).For Class 3 relevant, service induced conditions, successive inspections shall comply with the requirements of IWC-2420(b) and (c).Class 2 components containing relevant service induced conditions will be considered acceptable for continued service providing an evaluation performed demonstrates the component's acceptability and is subsequently examined in accordance with the requirements of IWC-3122.4, IWC-3132.3 and XWC-3134(b).

Acceptance by Repair or Replacement can also be performed.

For Class 2 relevant service induced conditions, successive inspections shall comply with the requirements of XWC-2420(b) and (c).Period 1 and u to the'9'4 Outa e'86 Code Class 1, Class 2, and Class 3 Supports containing relevant service induced conditions will be considered acceptable for continued service providing'n evaluation or test is performed that demonstrates the component's acceptability.

Acceptance by Repair or Replacement can also be performed.

Successive inspections on supports containing relevant service induced conditions shall comply with the requirements of IWF-2420(b) and (c).Periods 2 Startin'94 Outa e and 3: Class 1, Class 2, and Class 3 Supports whose visual examination does not reveal conditions as described in the acceptance standards (-3400 of Code Case N-491), shall be acceptable for service.Visual examinations which detect relevant service induced conditions as described in the acceptance standards shall be unacceptable for service unless accepted or corrected by one of the following methods;-Corrective measures (adjustment,'repair, or replacement), and subsequent reexamination including the requirements of-2220(b)(Note: Successive examination requirements of-2420 must be applied to supports containing relevant service induced conditions in which corrective measures were utilized for acceptance.)

'I f fi II I QUALITY ASSURANCE MANUAL GINNA STATION TITLE I APPENDIX B R.E.GXNNA NUCLEAR POWER PLANT XNSERVICE INSPECTION PROGRAM FOR THE 1990-1999 XNTERVAL REV.Section 1 3 PAGE 11 of 34-Evaluation

'r Test to the extent necessary to substantiate its integrity for its intended service (Note: Visual examinations that detect surface flaws that exceed-3400 criteria shall be supplemented by either surface or volumetric examinations)

.Note 1: Flaws or relevant conditions in which analytical evaluations are being performed to determine acceptance, may be considered acceptable for continued service during this evaluation process.1.7.6 Additional Examinations 1.7.6.1 Inservice examinations performe'd that revealed service induced flaws that exceeds the acceptance standards shall have additional examinations performed.

1.7.6.2 Additional examinations shall be performed to the extent required by IWB-2430 whenever a service induced rejectable flaw is identified during the performance of ISI examinations in accordance with the requirements specified within IWB and IWD.1.7.6.3 1.7.6.4 Additional examinations shall be performed to the extent.required by IWC-2430 whenever a service induced rejectable flaw is identified during the performance of ISI examinations in accordance with the requirements specified within IWC.Additional examinations shall be performed, starting the'94 outage, to the extent required by-2430 (Code Case N-491)whenever a service induced rejectable flaw is identified during the performance of ISX examinations in accordance with the requirements specified within Code Case N-491 and XWF.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE:, APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.3 PAGE 12 of'34 Section 1 1.8 Repair Requirements Repairs shall be performed to the requirements specified within Supplement 2 to Appendix B, The Repair, Replacement

&Modification (RR&M)Program.This RR&M Program shall apply to ASME Class 1, 2&3 pressure boundary piping, components

&supports.1.8.1 Performance of Repair Repairs on ASME Class 1, 2 or 3 components shall be performed in accordance with the requirements of IWA/B/C/D/F-4000 of ASME Section XI, 1986 Edition or later Edition/Addenda that is approved via lOCFR50.55a.

Alternatively, repairs'may be performed either to the requirements of the original Construction Code, which th'e component or system was fabricated to, or to later approved editions of the Construction Code, or later approved editions of ASME Section III along with any Code Cases approved via Regulatory Guide 1.147.1.8.2 Examination/Test for Repairs 1.8.2.1 Applicable examination requirements of the Construction Code shall be met.If the repair is performed on an existing weld that requires the complete removal of the original weld metal within that joint before rewelding, the following additional NDE requirements are required: (a)Pressure retaining components greater than 2 inches in diameter shall require both surface , and 1004 volumetric examinations to be performed on the new weld.Or (b)Pressure retaining components 2 inches or less in diameter shall require a surface examination to be performed on the new weld.Examinations and testing of snubbers and supports that have been repaired shall be performed in accordance with 5.0 below and Section 9 of this program.

11 1 1 I II fI I QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.Section 1 3 PAGE 13 of 34 1.8.2.2 The examination shall include the original examination method that detected the flaw, if applicable.

1.8.2.3'pplicable examination requirements of ASME section XI, 1986 Edition shall also be met to serve as a new PSI baseline for future ISI examinations, unless the examination performed under paragraph 1.8.2.1 was conducted under conditions and with equipment and techniques equivalent to those required by Section XI.1.8.2.4 A hydrostatic test shall be performed in accordance with ASME Section XI, 1986 Edition, unless specifically exempted by Section XI Article IWA-4400, or the Alternate Rules of Incorporated Code Cases or Relief Requests, as applicable..

1.8.3 Surface flaws in Class 1, 2, or 3, bolts, studs, nuts and ligaments may be removed by mechanical means provided the removal of that flaw does not alter the basic configuration of the item.Bolts, studs, and nuts that have flaws that cannot be removed by mechanical means shall be replaced or reported for evaluation as indicated by Section XI, Article IWA-3100.1.9 Replacement Requirements Replacement requirements, which includes modifications, are applicable to ASME Class 1, 2 and 3 pressure retaining components and piping systems and their supports, unless specifically exempted by ASME Section XI, 1986 Edition, Article IWA-7400.1.9.1 Replacement Performance Replacements shall meet the requirements of ASME Section XI, 1986 Edition or a later Edition/Addenda approved via 10CFR50.55a.

In addition, replacement items shall meet.the requirements of the original Construction Code to which the original part was constructed.

The R.E.Ginna Nuclear Power Plant Replacement Program is defined within Supplement 2 to Appendix B.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.3 PAGE 14 of 34 Section 1 1.9.1.1 A"Like for Like" replacement is an item that meets the original requirements of the design and procurement documents for the item being replaced and does not require reconciliation, reanalysis or changes to the item's design and technical requirements.

1.9.1.2 An approved equivalent is a replacement that will result in a design or technical change to the original requirements based on reconciliation, re-analysis and/or testing per Paragraph 1.9.2.1.1.9.2 1.9.2.1 Alternatively items used for replacement may meet all or portions of the requirements later additions of the Construction Code or Section III, when the construction code was not Section III.In order to use this alternate approach, the following additional requirements apply.Reconcile the requirements affecting the design, fabrication and examination of the replacement with the Design Analysis or Design Criteria or other methods of analysis that demonstrates the item is satisfactory for the specified design and operating conditions.

1.9.2.2 Mechanical interfaces, fits and tolerances that provide satisfactory performance are compatible with the system and component requirements.

1.9.2.3 Materials used are compatible with installation and system requirements.

1.9.2.4 If a replacement is because of a failure of the item being replaced, a design evaluation or analysis shall consider the cause of the failure and its impact on other similar items, and the necessary actions to'e taken to preclude recurrence.

1.9.2.5 1.9.2.6 When welding is to be performed as part of the replacement, the rules of Section IX shall be followed to satisfy the requirements of IWA-7320 and IWF-7000.C Items identified in IWA'-7400 will be exempt from the requirements of the replacement program.

P If H QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.Section 1 3 PAGE 15 of 34 1.9.3 Examination/Test 1.9.3.1 The replacement item shall be examined and pressure tested in accordance with the Construction Code or later Code provided it meets the requirements of 1.9.1 above.1.9.3.2 Snubbers shall be examined and tested in accordance with Section 9 of this program.Where the attachment of the non-pressure-retaining item is welded to a'ressure boundary, the weld shall be examined in accordance with the requirements of 1.8.2.1.9.3.3 Applicable examination requirements of ASME Section XI, 1986 Edition, shall also be met to serve as a new PSI baseline for future ISI examinations, unless the examination performed under 1.9.3.1 was conducted under conditions and with equipment.and techniques equivalent to those required by ASME Section XI.1.9.3.4 Replacements installed by mechanical methods shall be pressure tested at nominal operating pressure, or for Class 1 systems, the pressure associated with 100%rated reactor power.1.9.4 Reports and Records Reports and records to the extent required by the construction code and IWA-7520, as applicable for the replacement, shall be completed for all replacements.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.Section 1 3 PAGE 16 of 34 1.10 1.10.1 l.10.1.1 System Pressure Testing General Requirements Pressure testing shall be conducted on all Class 1, 2, and 3 pressure retaining components in accordance with the requirements of Section XI Articles IWA-5000, IWB-5000, IWC-5000, IWD-5000;and Section XI Table IWB-2500-1

-Examination Cat.egory B-P, Table IWC-2500-1

-Examination Category C-H, and Table IWD-2500-1

-Examination Category D-A, D-B and D-C.In addition,"High Energy" Main Steam and Feedwater Piping shall also be pressure tested on these non-class systems in accordance with the rules of IWC-5000.1.10.1.2 Pressure tests are conducted from normal operating pressure, to a pressure up to 254 over design pressure.The degree of pressurization and the test boundary depends upon the type of pressure test being performed.

A visual examination (VT-2 method)is performed in concert with the pressure test on pressure retaining components under test pressure.Specific exceptions from achieving Section XI requirements are detailed in the Relief Request Section of this document.1.10.2 Type of Pressure Tests The various types of pressure tests which are required during the inspection int:erval are described in the following:

1.10.2.1 LEAKAGE PRESSURE TEST This test, is performed subsequent to refueling outages.The boundary subject to test pressurization and the associated VT-2 examination during a leakage pressure test will extend to the pressure retaining components within the system boundary containing pressurized reactor coolant under the plant mode of normal reactor st;artup.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E..GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.Section 1 3 PAGE 17 of 34 1.10.2.2 FUNCTIONAL PRESSURE TEST This test is performed once each inspection period.The boundary subject, to test pressurizat'.ion and the associated VT-2 examination during a system functional

-pressure t.est will include only those pressure retaining components within the system boundary pressurized under the test mode required during the performance or a periodic system/component surveillance test.1.10.2.3 INSERVICE PRESSURE TEST This test is performed once each inspection period.The boundary subject to a test.pressurization and the associated VT-'examination during a system inservice pressure test will include only those pressure retaining component'.s under operating pressure during normal system service.1.10.2.4 HYDROSTATIC PRESSURE TEST This test: is performed once each inspection interval.The boundary subject to test pressurization and the associated VT-2 examination during a system hydrostat:ic pressure test includes all Class 1, 2, and 3 components and piping.1.10.2.5 PNEUMATIC PRESSURE TEST This test is limited to Class 2 and 3 systems.The boundary limits subject to test pressurization and the associat;ed VT-2 examination during a system pneumatic pressure test are the same as a hydrostatic pressure test.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GXNNA NUCLEAR POWER PLANT INSERVXCE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL Section 1 PAGE 18 of 34 1.10.2.6 REPAIR/REPLACEMENT PRESSURE TESTS The boundary subject to test pressurization and the associated'VT-2 examination is limited to the portion repaired or replaced, within the Class 1, 2 or 3 boundary.The specific type of pressure test is either a hydrostatic, pneumatic or a test at operating pressure such as the Leakage, Xnservice or Functional.

The specific type of test to be performed and the exemptions which apply to repair/replacement pressure testing are described in Supplement 2 to Appendix B, the Repair, Replacement 6 Modification Program.Code Case N-498 does not apply to Repairs, Replacements or Modifications.

1.10.3 1.10.3.1 Examination Requirements During the conduct of pressure tests, certified VT-2 examination personnel, using RGGE approved NDE VT-2 examination procedure and the associated recording form, will examine the portions of piping under pressurization.

The examination and test boundaries are depicted on controlled color-coded PAID's.In some cases, the test boundary extends beyond the examination boundary due to valve location and/or check valve flow direction.

In general, personnel will examine for evidence of leakage, inoperative leakage collection systems and evidence of corrosion.

1.10.4 1.10.4.1 Test Requirements GENERAL The contained fluid in the system or fluid added to the system shall serve as the pressurizing or test medium.In steam systems either water or air may be used..Where air is used, the test procedures shall permit the detection and location of through wall leakages in components of the system tested.The temperature of the test medium will be that of the available source unless otherwise specified by the implementing test procedure/document.

The test medium will be of a quality which is equal to or better than the system operating medium.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.3 PAGE 19 of 34 Section 1 1.10.4.1.1 During conduct of hydrostatic tests, all entrained air will be vented from the system except in the following cases: a~b.c~d.Atmospheric Storage Tanks 0-15 psi Storage Tanks Class 1 systems where a mixture of steam, water and noncondensible gases are present in a proportion typical of normal startup conditions.

Normal Steam Systems 1.10.4.1.2 For Leakage, Functional, Inservice and Hydrostatic tests, the level of syst: em pressure and temperature indicated or recorded by normal operating system instrumentation, or alternatively by test instrumentation is acceptabl'e.

For hydrostatic tests, the instrument requirements of IWA-5260 and applicable Code Case N-437 must be met.1.10.4.2 LEAKAGE PRESSURE TEST REQUIREMENTS The system leakage pressure test shall be conducted at a pressure not less than nominal operating pressure associated with 100%Rated Reactor Power.The pressure and temperature will be attained at a rate in accordance with the heat-up limitations specified in the Ginna Technical Specifications for the component/piping system being tested.1.10.4.3 FUNCTIONAL PRESSURE TEST REQUIREMENTS The system functional pressure test is normally performed during performance or a Periodic Surveillance Test.The test is used to establish the test conditions associated with normal system operating pressure and temperature for performance of the system functional pressure test.1.10.4.4 INSERVICE PRESSURE TEST REQUIREMENTS The operating pressure and temperature during normal system operation is used during performance of this test.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.Section 1 3 PAGE 20 of 34 l.l0.4.5 1.10.4.5.1 HYDROSTATIC PRESSURE TEST REQUIREMENTS General 1.10.4.5.2 Code Case N-498 stipulations may be employed on Class 1 and 2 Required Systems in lieu of the 10 year Hydrostatic Test.Hydrostatic test pressure requirements vary among each of the classifications.

The minimum test pressure will be maintained for the entire duration of the test, with the exception of tests performed at temperatures greater than 200'F, where the examination phase may be performed at a lower pressure corresponding to 200'F.The test pressure shall not exceed the maximum allowable test pressure of any component.

within the test boundary.The hydrostatic test pressure, including static head, will not exceed 106%of the specified test pressure for the system anywhere within the test boundary.1.10.4.5.2.1 In cases where the highest and lowest elevations"cannot be isolated, and the test pressure including static head, would exceed 106: of the specified test pressure at the lowest point, the test pressure will be reduced.1.10.4.5.2.2 In cases where the high and low elevations result in unreasonably small differences between the test ,pressure including static head, and 106~of the specified test pressure, the test pressure will be reduced to accommodate the precision of the test instrument.

1.10.4.5.2.3 The test pressure, as identified in sections 1.10.4.5.2.1 and 1.10.4.5.2.2, will be adjusted such that, the test pressure, including static head, does not exceed 106%of the specified test pressure at the lowest point.The resulting pressure at the highest point will be considered acceptable.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.3 PAGE 21 of 34 Section 1 1.10.4.5.3 The hydrostatic test boundary will end at the transition between system piping and instrumentation tubing shown on P&ID drawings.When this transition does not occur at an isolation valve, the boundary will be extended to the first isolation valve after the transition.

1.10.4.6 The following sections list the hydrostatic test pressure requirements which will be met for each Code classification:

1.10.4.6.1

, Class 1'he system hydrostatic pressure test is conducted at the pressure calculated from the following table based on the test temperature:

Test Tem erature De.F.Test Pressure 100 or less 200 300 400 500 or greater 1.10 P 1.08 P 1.06 P 1.04 P 1.02 P 1.10.4.6.2"P" is the nominal operating pressure corresponding with l00%rated reactor power.Linear interpolation will be used at intermediate test temperatures.

Technical Specification heat-up/cool-down limits will be observed.Class 2, 3, and High Energy: a~The test pressure will be at least 1.10 times the system pressure for systems with a design temperature of 200'F or less, and at least 1.25 times the system pressure for systems with a design temperature above 200'F.The system pressure will be the lowest pressure setting among'the number of safety or relief valves provided for overpressure protection within the boundary of the system to be tested.For systems (or portions of systems)not provided with safety or relief valves, the system design pressure will be substituted for the syst: em pressure.

II QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.Section 1 3 PAGE 22 of 34 b.In the case of atmospheric storage tanks, the nominal hydrostatic pressure developed with the tank filled to its design capacity will be acceptable as the test pressure.c~For 0 to 15 psi storage tanks, the test pressure will be 1.1 times the design pressure of vapor or gas space above liquid level for which overpressure protection is provided by the relief valves.If relief valves are not installed, the test pressure will be equal to 1.1 times the normal operating pressure.d.For the purpose of the test, open-ended portions of a suction or drain line from a storage tank extending to the f'irst shutoff valve are considered as an extension of the storage tank.e.For open ended portions of discharge lines beyond the last shutoff valve in nonclosed systems, a test that demonstrates unimpaired flow will be performed in lieu of a system hydrostatic pressure test.Unimpaired flow for Class 2 is defined as an"open flow path" and for Class 3 as"adequate flow during system operation".

1.10.5 1.10.5.1 1.10.5.2 Test Implementation All pressure testing is implemented using both.the VT.-2 examination procedure and the specific test procedure for the type of test and portion of system being tested.Applicable Required System Pressure Test Boundaries shall be confirmed prior to examination performance.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.3 PAGE 23 of 34 Section 1 1.10.6 Scheduling When using the inspection plan, it should be noted that during a period or refueling outage in which a hydrostatic test is performed on a system or portion(s) of a system, the leakage test (Functional or Inservice) required for that period on the same system or portion of the system, may be deleted from that period or outage.The hydrostatic test will satisfy the requirements ,for that leakage test.2.0 2.1 CLASS 1 PROGRAM PLAN Basis for Preparation

2.1.1 Preparation

of the Class 1 ISI program plan was based on the requirements of Articles IWB-l000 and IWB-2000 of Section XI.These articles provide rules and guidelines for exemptions,.inspection schedules, and examination requirements for Class 1 pressure retaining components and their integral attachments.

2.1.2 As allowed by 10CFR50.55a (b)(2)(ii), the extent and frequency requirements for Class 1 Category B-J weld examinations may be based on the 1974 Edition of ASME Section XI with Addenda through Summer, 1975.This earlier Code does not.have any criteria established for the selection of specific welds to be examined, and therefore, stress level criteria, and terminal end criteria is not required for the selection process.Instead of utilizing the earlier Code rules for Category B-J welds (which has no selection guidance), the 1986 Code rules will be utilized to the extent, practical.

In lieu of the stress level selection criteria Table IWB-2500-1, Note l(b), all accessible terminal end, welds (including terminal ends to vessel per Note l(a)of Table IWB-2500-1) shall be selected.Refer to Code Table 1 in Section 4 for selection criteria.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.3 PAGE 24 of 34 Section 1 2.2 Components Subject to Examination 2.2.1 Based on the requirements of Section XI, Class 1 nonexempt pressure-retaining components and their integral attachments will be subject to examination during the third inspection interval.2.3 2.3.1 2.4 Extent and Frequency of Examinations Class 1 components, as listed in Section 4, Table 1 shall be examined to the extent and frequency required in Table IWB-2500-1 and Figures IWB 2500 through IWB 2500-20 of Section XI.Exemption Criteria 2.4.1 In accordance with IWB-1220, certain Class 1 components are exempt from examination.

The following criteria were applied to exempt components from surface and volumetric examinations in accordance with Section XI Exem tion Criteria Code Reference Piping of 1 inch nominal pipe IWB-1220(b)

(1)size (NPS)and smaller, except for steam generator tubing Components and their connections IWB-1220(b)

(2)in piping of 1 inch NPS and smaller 2.5 Examination of Reactor Coolant Pump Flywheels The Reactor Coolant Pump Flywheels shall be examined as specified in Section 11 of this program.These examinations shall be scheduled in the Class 1 section of the ISI program plan.2.6 Znservice Inspection Program Plan (Supplement 1 to Appendix B)This plan provides the examination requirements for Class 1 components per the 1986 Edition of Section XI.These requirements shall be satisfied during the third inspection interval.The plan also shows the results of examinations performed in the previous two intervals.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.3 PAGE 25 of 34 Section 1 A detailed description of the contents of the Class 1 Examination Plan can be found in the"Introduction".

This immediately precedes the tables and the isometric and component drawings, in the plan.From this plan, an examination schedule is extracted for implementation of the examinations for each outage of the third interval.3.0 3.1 3.1.1 CLASS 2 PROGRAM PLAN Basis for Preparation Preparation of the Class 2 ISI program plan is based on the requirements of Articles IWC-1000 and IWC-2000 of Section XI.These articles provide rules and guidelines for exemptions, inspection schedule, and examination requirements for Class 2 pressure retaining components and their integral attachments.

3.2 Components

Subject to Examination 3.2.1 Based on the requirements of Section XI, Class 2, nonexempt pressure-retaining components and their integral attachments will be subject to examination during the third inspection interval.3.3 Extent and Frequency of Examinations 3.3.1 Class 2 components, as listed in Section 4, Table 2, shall be examined to the extent and frequency required in Table IWC 2500-1 and Figures IWC 2500-1 through IWC 2500-13 of Section XI.3.4 Exemption Criteria IWC-1220 of Section XI provides the exemption criteria for Class 2 components.

The following criteria were used to exempt Class 2 components from surface and volumetric examinations in accordance with IWC-1220.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM-FOR THE 1990-1999 INTERVAL REV.Section 1 3 PAGE 26 of 34 3.4.1 The following components (or parts of components) of Residual Heat Removal (RHR), Emergency Core Cooling (ECC), and Containment Heat Removal (CHR), systems (or portions of systems)are exempt from the volumetric and surface examination requirements of IWC-2500: (a)vessels, piping, pumps, valves and other components 4 inches NPS and smaller in all systems except in high pressure safety'injection systems of pressurized water reactor plants;(b)vessels, piping, pumps, valves, and other components l-l/2 inches NPS and smaller in high pressure safety injection systems of pressurized water reactor plants;(c)component connections 4 inches NPS and smaller (including nozzles, socket fittings, and other connections) in vessels, piping, pumps, valves, and other components of any size in all systems except in high pressure safety injection systems of pressurized water reactor plants;(d)component connections 1-1/2 inches NPS and smaller (including nozzles, socket fittings and other connections) in vessels, piping, pumps, valves and other components of any size in high pressure safety injection systems of pressurized water reactor plants;(e)vessels, piping, pumps, valves, other components, and component connections of any size in statically pressurized, passive (i.e., no pumps)safety injection systems of pressurized water reactor plants;and (f)piping and other components of any size beyond the last shutoff valve in open-ended portions of systems that do not contain water during normal plant operating conditions.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.3 PAGE 27 of 34 Section 1 3.4.2 The following components (or parts of components) of systems (or portions of systems)other than RHR, ECC and CHR systems are exempt from the volumetric and surface examination requirement's of IWC-2500: (a)vessels, piping, pumps, valves and other components 4 inches NPS and smaller;(b)component connections 4 inches NPS smaller (including nozzles, socket and other connections) in vessels, pumps, valves and other components size;and fittings piping, of any (c)vessels, piping, pumps, valves, other components and component connections of any.size in systems or portions of systems that operate (when the system function is required)at a pressure equal to or less than 275 psig and at a temperature equal to or less than 200'F;and 3.4.3 (d)piping and other components of any size beyond the last shutoff valve in open ended portions of systems that do not contain water during normal plant operating conditions.

In addition to the exemptions of IWC-1220, non-piping component size exemptions shall be as follows: Nonpiping components having a cumulative inlet and a cumulative outlet nominal cross section area, neither of which exceeds the nominal cross section area of the applicable exemption size, shall be exempted from the surface, volumetric, and visual VT-1 and VT-3 examination requirements of IWC-2500.The applicable exemption size shall be 4" NPS for all systems except the Class 2 High Pressure Safety Injection System, which shall be 1 1/2" NPS.This position is based on the interpretation of the clarification made by footnote 1 of IWC-1220 of the 1989 Addenda to ASME Section XI.For the purpose of applying this criteria, it is assumed that the intention of the Code is not to accumulate the cross-section areas of piping from different fluid systems entering a given component (e.g., heat exchanger shell&

QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.3 PAGE 28 of 34 Section 1 tube sides), nor the non-process piping (e.g., vents, drains and instrumentation).

3.5 Inservice Inspection Program Plan (Supplement 1 to Appendix B)This plan provides the examination requirements for Class 2 components per ASME Section XI, 1986 Edition, no Addenda.These requirements shall be satisfied during the third inspection interval.The plan also shows the results of examinations performed during the previous two intervals.

A detailed description of the contents of the Class 2 Examination Plan can be found in the"Introduction".

This immediately precedes the tables and the isometric and components drawings in the plan.From the plan an examination schedule is extracted for implementation of the examinations for each outage of the third interval.4.0 4.1 CLASS 3 PROGRAM Basis for Preparation

4.1.1 Preparation

of the Class 3 ISI program was based on the requirements of Articles IWD-1000 and IWD-2000 of Section XI.These articles provide rules and guidelines for exemptions, inspection schedules, and examination requirements for Class 3 pressure retaining components and their integral attachments.

~~

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.Section 1 3 PAGE 29 of 34 4.2 Components Subject to Examination 4.2.1 Based on the requirements of Section XI, Class 3 nonexempt pressure-ret:aining components integral attachments will be subject to examination during: the third inspection interval:, 4.2.1.1 Other Class 3 systems are not subject to the examination or System Pressure Testing requirements of ASME Section XI because they do not meet the system function requirements of Examination Categories D-A, D-B and D-C, where: D-A Systems in support of Reactor Shutdown Function D-B Systems in support of Emergency'ore Cooling, Containment Heat Removal, Atmosphere Clean-up and Reactor Residual Heat, Removal.D-C Systems in support of Residual Heat Removal From Spent Fuel Storage Pool.4.3 Extent and Frequency of Examinations 4.3.1 Class 3 components, as listed in Table 3 shall be examined to the extent and frequency required in Table IWD 2500-1 and Figure IWD 2500-1 of Section XI.4.3.2 Integrally welded attachments shall be examined, utilizing the VT-3 method, once during the Interval on all Class 3 Component Supports.The associated Class 3 Categories have been grouped since the methods of examination and their Requirements are identical.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.3 PAGE 30 of 34 Section 1 4'Exemption Criteria 4.4.1 In accordance with IWD-l220, certain Class 3 components are exempt from examination.

The following exemption criteria was applied to Class 3 systems as specified in IWD-l220: Exem tion Criteria Section XI Reference Integral attachments of supports and restraints to components that, are 4 inches NPS and smaller within the system boundaries of Examination Categories D-A, D-B, and D-C shall be exempt.from the VT-3 examination, except for Auxiliary Feedwater.

Exemption for the Auxiliary Feedwater System is 1 inch and less.IWD-l220.1 Integral attachments of supports and restraints to components exceeding 4" nominal pipe size may be exempted from the visual examination VT-3 of Table IWD-2500-1 provided: IWD-1220.2 (a)the components are located in systems (or portions of systems)whose function is not rec{uired in support of reactor residual heat removal, containment heat removal, and emergency core cooling;and (b)The components operate at a pressure of 275 psig or less and at, a temperature or 200 degrees F or less.

QUALITY ASSURANCE MANUAL GINNA STATION APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.Section 1 3 PAGE 31 of" 34 4.4.2 In addition to the exemptions of IWD-1220, non-piping component size exemptions shall be as follows: Nonpiping components having a cumulative inlet and a cumulative outlet nominal cross section area, neither of which exceeds the nominal cross section area of the applicable exemption size, shall be exempted from the surface, volumetric, and visual VT-1 and VT-3 examination requirements of IWD-2500.The applicable exemption size shall be 4" NPS for all systems except the Class 3 Auxiliary Feedwater System, which shall be 1" NPS.This position is based on the interpretation of the clarification made by footnote 1 of IWD-1220 of the 1989 Addenda to ASME Section XI.For the purpose of applying this criteria, it is assumed that the intention of the Code is not to accumulate the cross-section areas of piping from different fluid systems entering a given component (e.g., heat exchanger shell&tube sides), nor the non-process piping (e.g., vents, drains and instrumentation).

4.5 Inservice Inspection Program Plan (Supplement 1 to Appendix B)This plan provides the examination requirements for Class 3 IWD components per the 1986 Edition of Section XI.These requirements shall be satisfied during the third inspection interval.The plan also shows the results of examinations performed during the previous two intervals.

A detailed description of the contents of the Class 3 Examination Plan can be found in the"Introduction".

This immediately precedes the tables and the isometric and component drawings in the plan.From the plan an examination schedule is extracted for implementation of the examinations for each outage of the third interval.

t ll

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL Section 1 PAGE 32 ot 34 5.0 5.1 CLASS 1q CLASS 2~AND CLASS 3 COMPONENT SUPPORTS Basis for Preparation The following paragraphs (5.1 through 5.4)describe the Inservice Inspection Program for Class 1, 2, and 3 component supports for the First and Second Periods, up to and including the first outage ('93).The remainder of the Second and Third Periods shall be in accordance with Code Case N-491 (for IWF-1000,-2000 and-3000)and IWF of the'86 Section XI Code.5.1.1 Preparation of the component support ISI Program was based on the requirements of Articles IWF-1000 and IWF-2000 of Section XI.'hese articles provide rules and guidelines for exemptions, inspection schedules, and examination requirements for Class 1, Class 2, and Class 3 component supports.Inservice test requirements and VT-3 inspection requirements for snubbers shall be conducted in accordance with Section 9 of this program which implements the requirements of Article IWF-2000.5.2 Component Supports Subject to Examination 5.2.1 Based on the requirements of Section XI, nonexempt component supports for the Class 1, Class 2 and Class 3 systems identified in paragraphs 2.2, 3.2 and 4.2 of this section shall be subject to examination during the third inspection interval.The component supports requiring examination shall be as follows: 5.2.l.l Plate and Shell-Type Supports Supports which are fabricated from plate and shell elements, such as vessel skirts and saddles, and are normally subjected to a biaxial stress.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL Section 1 3 PAGE 33 of 34 5.2.1.2 Linear-Type Supports Supports acting under essentially a single component or direct stress.Such elements may also be subjected to shear stress.Examples of such structural elements are: tension and compression struts;beams and columns subjected to , bending;trusses;frames;arches;rings;and c'ables.5.2.1.3 Component Standard Supports A support assembly consisting of one or more generally mass-produced units usually referred to as catalog items.Examples of such items are shown in Figure IWF-1210-1 of Section XI.5.3 5.3.1 Extent and Frequency of Examination Component supports selected for examination shall be those components required to be examined under the requirements of 2.3, 3.3 and 4.3, IWF-2500.The inservice test, requirements of Article IWF-5000 shall be satisfied by the requirements of Section 9 of this program.5.3.1.1 Class 3 component supports containing integrally welded attachments shall be examined, utilizing the VT-3 method, once during the Interval.The associated IWF categories have been grouped since the methods of examination and associated Requirements are identical.

5.3.2 5.3.3 In addition, snubbers shall be functionally tested at the frequency required by Section 9 of this program.On piping systems where a piping seismic analysis boundary is beyond the safety class boundary, the component supports within the portion between those two boundaries shall be examined.The extent of these examinations shall be consistent with the examination requirements of that safety class system.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL REV.3 PAGE 34 of 34 Section 1 5.3.4 5.4 5.4.1 5.4.2 High Energy Piping Component Supports shall be examined to IWC-2500 Category C-C and to IWF-2500 in an Augmented Program.Exemptions ASME Section XI, 1986 Edition, no Addenda, does not contain defined exemption criteria for component supports.Exemption criteria specified in IWB, IWC and IWD have been used.5.5 Inservice Inspection Program Plan (Supplement 1 to Appendix B)This plan identifies and incorporates the appropriate component supports into the Class 1, 2, and 3 sections of the examination plan.These requirements shall be satisfied during the third inspection interval.The plan also shows the results of examinations performed in the previous two intervals.

QUALITY ASSURANCE MANUAL GINNA STATION Section 2 EFFECTIVE DATE: PAGE 1 of 39 December 31, 1993 ROCHESTER GAS&ELECTRIC CORPORATION SIGNATURE DATE TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF REQUESTS PREPARED BY QUALITY ASSURANCE APPROVED GY 1.0

Introduction:

General: In accordance with 10CFR50.55a(g)

(5)(iv), Rochester Gas&Electric has requested relief from those ASME Section XI requirements that have been determined impractical for certain areas.This section identifies each active and owner withdrawn Relief Request submitted to the Nuclear Regulatory Commission for their consideration and acceptance.

Table 1 provides information in a summary format for both active and withdrawn relief requests applicable to R.E.Ginna Nuclear Power Plant.Following Table 1, detailed Relief Requests are listed.These provide information on the component for which relief is requested, ASME requirements, proposed alternate method, and other pertinent information, as needed.Existing active relief requests can be withdrawn by the owner at any time.Additional relief requests will be submitted to the Nuclear Regulatory Commission, as appropriate.

c QUALITY ASSURANCE MANUAL GINNA STATION TITLEI APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.3 PAGE 2 of 39 Section 2 TABLE I

SUMMARY

OP RHJFP R Rebel Request Number Section XI Refesence IWB.2500.1 Cat.B.A Component RPV ShcU to Bange WeM ASME Requiscment for Which Relief is Requested Volumetric Examination during two dUferent pcAods Reason for Relief Request To perform aU examinations assoriatcd with the SheU.to Bange during the same pcskxL Proposed Akemate Examination Perform aU examinations associated with the SheUao Range at or near the end of the interval.IWB.2500.1 Cat.B-D RPV Nozxlc to-Vcsscl WeMs Volumetric Examinadon during two different pcAods.To perform aU examinations assocktcd with the Nosxk.to.Vessel wcMs during the same pcsloL Perform aU cxaminatkins associated with the Noxxk to.Vessel weMs at or near the end of the lntervaL IWA.1400 Inspection huthorixed Inspection Agency.Use of'huthorixed Agency'cw York State has not endorsed ASME Codes and does not have an Authorixcd Inspection Agency.Use R.E.Cinna Quality Assurance Pmgram.4 (')IWB.2500 I Cat.B.L I B-L2 Reactor Coolant Pump Case WeMs and Intervals.

Volumetric Examinatkn of ease weMs and visual of intemab.Pump materiai and conBgumtion.

Hydsostatie test, surface and visual exams of outside surfaces.IWB-2500 I Cat.B M.2 Chss I Valves Creatcr than NPS 4.Visual Examination of valw intemds.Excessive radiation ex posuse and historical reliability of valves.Examine valve Intcmak when disassembled for maintcnanee.

IWD 2500-1 Cat.D.B IWC 5222(a)Rsdioanive Waste HoMup Tank, Charging Pumps Visual Bueucadon at hydsostade prcssure.Visual Examination at 3420 psig Hydrostatic Pressure.Tank wUI be rendered inoperatiw during tests.Pumps have maximum pressure limit on the scab.Perform visual examination each period at noAnal opcradng prcssure.Perform Hydro Test and visual at 2400 psig.IWC 5222(a)Valves PCV 430 and PCV 431C.Visual Exasninadon at Hydrostatic Pressure.Valve diaphragms cannot withstand Test Prcssure.Hydrostatic Test to Fkx Connection operate diaphragm pcr valve test requirements and pcrfonn Insesvice visual examination once per period.10 (')IWC 5222(a)IWD-5223(a)

IWD.5223(a)

Secondary Side of steam generator and assoriatcd main steam piping.Standby Auxiliary Pump RceiscuL Une from AOV 9710A, AOV 9710B and thek assoei.atcd downstream Row orifices.Boric Acid Filter and assoriatcd piping between Valves 347, 348A and 349A.Visual Examination at Hydrostatic Pressure.Visual Examination at llydsostatie Pressure.Visual Examinatkn at Hydrostatic Pressure.RCBE adopted pressure differential limitadon of 800 psig to prevent primary side tube sheet chdding scpamtiolL Pressure Redunkn Bow OriTice requires removal and biank4sff.

System piping docs not provMe lsolatkn to condcmate supply rank.SigniTicant tank reduction wouM bc required for removal and is comidered impractkai.

Test Prcssure required will exceed limits for safe working pressure on Boric Acid Fil(cr Housing Fhnge Cmkets.Hydrostatk Test at 1.10 times instead of 1.25 Psv setting and perform visual cxammatfoiu Perform Inservice Visual Examination once per periosL Perform Inservice Visual Examination once per period.(v)~Will IDRAWN QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.3 PAGE 3 of 39 Section 2 TAB!X I

SUMMARY

OF RFJJFP R URIS Relief Request Number Sectfon XI Reference ASME Requirement for Which Rriief k Requested Reason lor Relief Request Proposed Alternate Examination 12.1 IWD-5223(a) hir Stan for Diesel Generator htciuding Receiver Tanks and Piping.Visual Examinatkn at Hydrostatic Pressure.Air Start Pressure Test wouM fcqiilfc tclndnatlon pfiof to fcacMng engine skid to preclude ak to air stan motors, kavtng portion of pfping untestable.

Perform Inseivke Examination once per period and once each quarter a prcssure decay test performed oii air rcccivcl;IWD-5223(a)

IWD.5223(a)

Fuel Oil Transfer Pumps and assoriated plpuig to tert(dr(all at Oil Storage Tank Jacket Cooling Water System and associated piping to terminals at Water Ex panskn Tanks.Visual Examinarion at Hydrostatic Pressure.Visual Examination at Hydrostatic Prcssure.Requires hohtkn of Diesel Oil Storage and Dry Tank where no means of kola(ion k provided at Transfer pump discharge piping with tanks vented to atmosphere.

Cooling Water Expansion Tank vented to aunosphcre requiring isoktkn with vast piping Involved will be unable to prcssurixc Perform system Functional Tesring with assockted Visual Examination once per period.Perform System Functional Testing with associated Vkual Examination once pcf pcf iud.13 (111)Table IV C2500 I, Category CH Ckss 2 Piping Pen((rath(3 containment vessel with balance of piping system outskle Section XI scope.Under Revision.15 (')IWC.2500 Cat.C F-I&C F-2 l(ems C5.10 and C5.50 resp.Ckss 3 Ponion of the servke water system Qass 2 Piping WeMs c 3/8'ondnal wall thkknem for piping>NPSC.Visual Examination at Hydrostatic Pressure..

Piping WeMs c 3/8'ominal wall thickness do no(require surface and volumetric examinanons.

I lydrostatic Tesung is impra(tical due to system design that is openwnded and empkying butterily valves that wcfc not dcsigncd to provide a kaktight boundary.At a mhdmum terminal connection weMs of idcntilied exempted weMs pcr Items C5.10 and C5.50 of Tabk IWC2500 shouM be examinetk Perform Inservice Visual Examination once per period.Surface and Volumetric Examinations on tcmunal connection weMS of Men(ipcd exempted weMS shall be performed to the requirements of IWC.2500 1.IWB-2500 Cat.8 K.l Item B10.10 and IWC.2500, Cat.CC, l(em C3.20 Qass I&2!ntcgral Attachment on piping speciTically support Attachments.

Volumetric or surface examination on Qass I Integral Attachments is required on Base Attachment

>5/8.Qass 2 requires a sUrfacc examination on Base Attachments

>3/0'.I ntegtul Attachments on Ckss I&2 suppon attachments shoUM have a sUffacc examination to insure safety and system integrity.

On Ckss I&2 Integral hnachmcnts, a surface examination shall be performed on suppon attachments to IWB and IWC-2500 requirements.

I9 IVC2500 Category C B, Items Col&C2.22 Pulsation Dampener, Nossk WeM&Inside Radius.Applicable Surface and/or Volumetric Examinations.

Physical configuration not conducive for full Examination coverage.Perform Surface and/or Volumetric Examination to Maximum extent practkaL (')" (1~1)~

'4 N'I 1 QUALITY ASSURANCE, MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT XNSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISX RELIEF RE UESTS REV.Section 2 3 PAGE 4 of 39 Relief Request Number Section XI Reference Component TABIX 1

SUMMARY

OP RHIKF mSlS ASME Requirement for Which Relief is Requested Reason for Relief Request Proposed Alternate Examination 23 (~)IWAA400 Chss 3 Valves: V~VMI I VMI 3 V~V~VA738 V.4739 VA760 llydrostatie Testing of Code Impraetieality Rephcement Activities.

ASME Section III NDE with PT of Root Pass.Perform a VT.2 leak Test.This Relief is a one-time'se only.24 (~)IWA-4400 Class 3 Vrdvcst VMI 3 V.4027 V 4020 V~Ifydrostatic Testing of Code Impractkality Re placement Activities.

ASME Section III NDE with PT of Root Pass.Pcrfonn a VT 2 leak Test.This Relief is a one-time usc only.(~)~ONE TIME USE ONLY.

t A I QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS Section 2 PAGE 5 of 39 RELIEF REQUEST NO.1 DEFER RPV EXAMINATIONS TO END OF INTERVAL Components for Which Relief is Requested:

The component for which relief is requested is the Reactor Pressure Vessel (RPV)Shell-to-Flange Weld.ASME Requirement from Which Relief is Requested:

Table IWB-2500-1, Examination Category B-A, requires that the RPV Shell-to-Flange weld be examined during the first and third periods in conjunction with the nozzle examinations, with at least 50 percent examined during the first period and the remainder by the end of the third period.The required Shell-to-Flange examination is impractical if performed during the periods specified as it can only be accomplished from the flange surface.III.Proposed Alternate Method: During the first two inspection intervals, 100 percent of the accessible length of the RPV welds including the Shell-to-Flange weld were examined at or near the end of the interval when the entire examination could be performed from both the flange surface and the vessel wall.This is a more practical approach in that the required examinations from both surfaces can be performed at the same time.During the third interval, 100 percent of the accessible length of all RPV welds including the shell-to-flange weld will be performed at or near the end of the interval when all the required examinations can be performed at the same time.

I QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.Section 2 3 PAGE 6 of 39 RELIEF REQUEST NO.2 DEFER RPV NOZZLE EXAMINATIONS TO END OF INTERVAL Components for Which Relief is'equested:

The components for which relief is requested are the RPV Nozzle-to-Vessel welds and Nozzle Inside Radius Sections.ASME Requirements for Which Relief is Requested:

Table IWB-2500-1, Examination Category B-D, Item B3.90, Nozzle-to-Vessel welds allows partial deferral."If examinations are conducted from inside the component and the nozzle weld is examined by straight.beam ultrasonic method from the nozzle bore, the remaining examinations required to be conducted from the shell inside diameter may be performed at or near the end of each interval." Examination Category B-D, Item 3.100 Nozzle Inside Radius Sections, does not allow deferral to the end of the interval, and requires (footnote 2)25 percent to 50 percent of the nozzles to be examined during the first period, with the remainder to be examined at the end of the interval.Examinations from the nozzle bore and nozzle inside radius examinations can only be performed on two (outlets)of the six major nozzles without removal of the core barrel.The mechanized examination of the two accessible nozzle and inside radius sections is quite expensive, and the nozzle-to-vessel examination is only a partial examination from the nozzle bore.From a technical position considering the progress which is being made in ultrasonic examination equipment and techniques and for the correlation of data obtained from the bore with that obtained, from the shell, it is highly desirable to perform both examinations at the same time.III.Proposed Alternate Method: Rochester Gas&Electric (RG&E)proposes to perform both nozzle-to-vessel examinations (from the nozzle bore and from the shell inside diameter)at or near the end of the interval.The nozzle inside radius examinations will also be performed at this time.This more practical approach will allow all the required examinations to be performed at the same time on all the nozzles and nozzle inside radii.

It II't I QUALITY ASSURANCE'ANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE'990-1999 INTERVAL ISI RELIEF RE UESTS REV.Section 2 3 PAGE 7 of 39 WITHDRAWN RELIEF REQUEST NO~3 U USE OF AUTHORIZED INSPECTION AGENCY Examination Requirement for Which Relief is Requested:

The ASME Boiler and Pressure Vessel Code,Section XI, 1986 Edition, IWA-1400(f), requires an arrangement with an Authorized Inspection Agency to provide inspection services.In addition, the Code requires that certain administrative functions be performed by the"Enforcement Authority" and"Authorized Nuclear Inservice Inspector".

Proposed Alternative:

Ginna Station is located in the state of New York.This state has not endorsed ASME Codes and therefore does not provide administrative organization and controls such as"Enforcement Authority","Authorized Nuclear Inservice Inspector" and"Reporting Systems".However, Ginna Station's Quality Assurance Program does provide equivalent administrative control.Therefore, RG&E requests that Ginna's Station Quality Assurance Program be used in lieu of Code administrative functions.

Rochester Gas&Electric's program for the inservice inspection, governed by the R.E.Ginna Station Quality Assurance Manual, contains the requirements and responsibilities for implementation of the program and procedures.

The procedures have been prepared and approved by the responsible organizations within Rochester Gas&Electric (e.g., Ginna Station, Engineering, Materials Engineering and Inspection Services, Electric Meter and Laboratory and Purchasing).

Approved procedures will be implemented to control the standards for examination evaluation.

These procedures include the identifications of the organization performing the inspection, description of the method of inspection to be used, acceptance and rejection criteria, and requirements for providing evidence of completion and certification of the inspection activity.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF REQUESTS REV.Section 2 3 PAGE 8 of 39 WITHDRAWN RELIEF REQUEST NO.3 (Con't)In addition, procedures are developed by Ginna Station to prescribe the disposition of nonconformances.

The procedures implemented for the repairs, the retest procedures and the test results will be reviewed by the Plant Operating Review Committee.

The members of this committee include technically qualified staff personnel.

Examination techniques have been established in accordance with written requirements and incorporated into written procedures.

qualifications for nondestructive test personnel are in compliance with Regulatory Guide 1.58,"Qualification of Nuclear Power Plant Inspection, Examination and Testing Personnel." Records and reports of the inservice inspection will be developed and maintained by Rochester Gas and Electric and include such items as examination plans and schedules, examination of results and corrective actions.The functions of the authorized nuclear inservice inspector, namely their review and verification of inservice examinations, personnel qualification and equipment certification during the annual outages at Ginna Station will be performed by personnel of the Hartford Steam Boiler Inspection and Insurance Company.The qualifications of the inspectors, inspections specialists and inspection agency are in compliance with the Code.

I t t II t QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.Section 2 3 PAGE 9 of 39 WITHDRAWN RELIEF REQUEST NO.4 RCP CASING WELDS VOLUMETRIC AND INTERNAL EXAMINATION Components for Which Relief is Requested:

Each of the 27.5 inch diameter recirculation loops at R.E.Ginna has a Class 1 Reactor Coolant Pump.The function of these two pumps is to provide forced circulation through the RPV core during normal reactor operation.

Code Requirement for Which Relief is Requested:

Table IWB-2500-1, Examination Categories B-L-l and B-L-2 require volumetric examination of casing welds and visual examination of internal pressure boundary surfaces of one pump case in each of the pump groups performing similar system functions each inspection interval.These examinations are impractical for the reactor coolant pumps at Ginna Station and relief is, therefore, requested.

A.Supporting Information The two reactor coolant pumps (RCP)for R.E.Ginna are Westinghouse Model 93 pumps.Each pump casing is fabricated by welding four stainless steel (SA351 CF8)castings together.Thus, there are 3 circumferential pressure-retaining welds that are to be volumetrically inspected in accordance with Category B-L-l.2.The unsuitability of ultrasonic examination was demonstrated during the"A" reactor coolant pump examination in 1980.An attempt was made to determine the wall thicknesses using ultrasonic examination,'he casing welds must be inspected using the miniature linear accelerator (MINAC).3.Radiographic examination using the MINAC was performed on the R.E.Ginna"A!'CP during the Spring 1981 refueling outage.In addition, the same type of examination has been performed at several other sites.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.Section 2 3 PAGE 10 of 39 WITHDRAWN RELIEF REQUEST NO.4 (Con't)This examination was performed by placing the MINAC inside the pump casing and placing the film on the outside of the pump.To perform the examination, the pump was completely disassembled.

Disassembly to this extent is far beyond any disassembly expected for this examination.

Also, insulation on the casing exterior was removed for film placement.

Additionally, the pump bowl must be dry for installation of the MINAC.Therefore, all fuel assemblies were removed from the reactor vessel and the vessel water level lowered to below the nozzles.Complete disassembly of the pump was also required to conduct the VT-l examination in accordance with Category B-L-2.4~No problems have been found with the welds at R.E.Ginna or other sites.Additionally, no problems have been found during the Category B-L-2 visual examination.

The visual examination was conducted at, R.E.Ginna by" using the video camera on the MINAC.The whole body exposure to personnel during the Spring 1981 directly attributable to the RCP"A" examinations 93, 067 millirem.This does not include the dose received during the complete core unload to get the plant in condition for the RCP disassembly., 5.The nuclear industry has been successfully applying leak-before-break concepts to primary loop and Class 1 auxiliary piping systems of commercial nuclear power plants.Currently, the analyses supporting such concepts comes under the review of the Nuclear Regulatory Commission by General Design Criteria-4 (GDC-4).

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.3 PAGE 11 of 39 Section 2 RELIEF REQUEST NO.4 (Con't)There are eight different models of RCP's in Westinghouse-type PWRs.Model 93 methodology used in the analyses is consistent with that recommended in NUREG 1061, Vol.3 and GDC-4.A finite element stress analysis model for the Model 93 pump was developed.

The RCP casings are cast stainless steel.The chemistries of each heat of material used in the=pumps were used to determine the fracture toughness.

The phenomenon of thermal aging was addressed.

The program successfully demonstrates that leak-before-break analyses are applicable to all primary pump casings of all Westinghouse design PWRs for which the screening loads are reasonably applicable and the fracture toughness are known.6.We believe that performing a volumetric examination of the Ginna Station Unit 1 RCP casing welds and a visual examination of the interior pressure retaining surface of one pump during the third lO-year inspection period does.not provide an increase in safety and expected radiation exposure.The following items have been considered:

a~b.Visual examination (VT-2)of the exterior of all pumps during the hydrostatic pressure test required by Table IWB 2500-1 Category B-P.Perform a Visual examination (VT-l)of the external surfaces'of the welds of one pump casing.co Perform a visual examination (VT-3)of the internal surfaces each time pump disassembly is required for maintenance.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.Section 2 3 PAGE 12 of 39 WITHDRAWN d.RELIEF REQUEST NO.4 (Con't)Perform an evaluation to demonstrate the safety and serviceability of the pump casing.The evaluation will include: Establishing material properties including fracture toughness values.(ii)Performing a stress analysis of the structure.(iii)(iv)(v)Reviewing of the operating history of the structure.

Selection of locations for postulating flaws.Determination of a flaw size resulting in the detectable leak rate (vi)(vii)Establishing the stability of the selected flaw.Demonstration that a postulated through-wall flaw which yields detectable leakage remains stable for all design loadings, with a margin of 2 on flaw size.NOTE: In making this assessment, thermal aging embrittlement and any other processes which may degrade the properties of the pump casing during service will be considered.

jV P QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.3 PAGE 13 of 39 Section 2 RELIEF REQUEST NO.5 VISUAL INTERNAL EXAMINATION OF CLASS 1 VALVES Components for Which Relief is Requested:

Class 1 valves requiring valve body internal VT examination.

Size~Xn.10 10 10 10 10 10 10 10 Valve No.842A 842B 867A 867B 700 701 720 721 853A 853B 852A 852B MFG T e Darling/Check Darling/Check Darling/Check Darling/Check Velan/Gate Velan/Gate Velan/Gate Velan/Gate Velan/Check Vela n/Check Velan/Gate Velan/Gate Line No.10A-SI2-1502-A 10A-SI2-2501-B 10A-SI2-2501-A 10A-SI2-2501-B 10A-RC02501-A 10A-RCO-2501-A 10A-RCO-2501-B 10A-RCO-2501-B 6A-RC-2501-A 6A-RC-2501-B 6A-RC-2501-A 6A-RC-2501-B II.ASME Requirement, for Which Relief is Requested Table IWB-2500-1, Examination Category B-M-2, requires an internal VT-3 examination on at least one valve within each group of valves that.are of the same size, constructional design (such as globe, gate or check valves)and manufacturing method, that perform similar functions in the system.This relief request is based on the following points: to complete the subject examination, unnecessary expenditures of man-hours and manrem are required with essentially no compensating increase in plant safety, and QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.Section 2 3 PAGE 14 of 39 RELIEF REQUEST NO.5 (Con't)2.the structural integrity afforded by valve casing material utilized will not significantly degrade over the lifetime of the valve.Based on data compiled from a plant similar in age and design to Ginna Station, it is expected that approximately 100 manhours and 5 manrem exposure would be required to disassemble, inspect, and reassemble these vales.Performing this visual examination under such adverse conditions, high doses rate (30-40 R/hr), and poor as-cast surface conditions, realistically provides little additional information as to the valve's casing integrity.

The valves material, a high-strength cast stainless steel (ASTM A35l-CF8), is widely used in the nuclear industry and has performed extremely well.The presence of some delta ferrite (typically 54 or more)substantially increases resistance to intergranular stress corrosion cracking.The delta ferrite also helps the material to resist pitting corrosion in chloride containing environments.

RG&E feels that adequate safety margins are inherent in the basic valve design and that the public's health and safety will not be adversely affected by not performing a visual examination of the valve internal pressure boundary surfaces.Additionally, this visual examination adds little or no value to the overall safety of the plant and subjects plant personnel to unnecessary radiation exposure.Therefore, a request for relief from this requirement is sought.III.Proposed Alternative Method: A's stated above, RG&E does not believe that the visual examination required each ten-year interval is warranted.

However, as standard maintenance practice dictates, when these valves are disassembled for maintenance purposes, a visual examination of the internals and internal pressure boundary surfaces will be performed, to the extent practical.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF REOUESTS REV.Section 2 3 PAGE 15 of 39 WITHDRAWN RELIEF REQUEST NO.6 HYDROSTATIC TESTING OF RADIOACTIVE WASTE HOLDUP TANK Component for Which Relief is Requested:

The radioactive waste hold-up tank in the waste disposal system provides a means of storing contaminated water that has been used in the operation of the nuclear power plant.The waste disposal system and waste hold-up tank may be required to function in all modes of reactor operation including cold shutdown and refueling.

II.ASME Requirement for Which Relief is Requested:

Table IWD 2500-1, Examination Category D-B, Item No.D2.10, requires VT-2 examination of the waste hold-up tank at hydrostatic testing levels (at least 1.10 system pressure)during each interval as well as VT-2 examinations at nominal operating pressure during each period.The design of the waste disposal system is such that contaminated water is stored in the waste holdup tank until such time as the level of contamination is below the limits for discharge.

At this time the holdup tanks may be unavailable for use by emptying the stored liquid.Several important systems within the chemical volume and control system drain into the waste disposal system hold-up tanks.These are the volume and control tank drains, reactor coolant letdown system, reactor coolant drain tank discharge, and the demineralizer system drains.If the tank was to be hydrostatically tested by filling it with water and pressurizing to 1.10 system pressure, the hold-up tank would be rendered useless.The plant would then be potentially put into an unsafe condition for any abnormal plant function and if startup occurred without a holdup tank being available.

f C QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.3 PAGE 16 of 39 Section 2 WITHDRAWN RELIEF REQUEST NO.6 (Con't)Since this hold-up tank constantly stores liquid, any degradation of the tank material would show up prior to it becoming a problem.RGGE believes that hydrostatically testing the rad-waste hold-up tank puts Ginna's plant in an unsafe condition and therefore a request for relief from this requirement is sought.III.Proposed Alternative Method: A Visual VT-2 examination shall be performed once every period with the system at normal operating pressure to verify continued structural integrity.

'\

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR, THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.3 PAGE 17 of 39 Section 2 RELIEF REQUEST N0.7 REDUCED HYDROSTATIC PRESSURE TESTING OF CHARGING PUMPS DISCHARGE PIPING Components for which Relief is Requested:

CVCS, Three Charging Pumps and Discharge Piping to Discharge Isolation Valves.ASME Requirements for which Relief is Requested:

IWC-5222(a)

System Hydrostatic Test;The system hydrostatic test pressure shall be at least 1.10 times the system pressure Psv for systems with Design Temperature of 200 F (93C)or less, and at least 1.25 times the system pressure Psv for systems with Design Temperature above 200 F (93C).The system pressure Psv shall be the lowest pressure setting among the number of safety or relief valves provided for overpressure protection within the boundary of the system to be tested.This corresponds to a test pressure of 3420 psig.The charging pumps have a minimum hydrostatic test pressure limitation on the seals of 2400 psig, as specified by the pump manufacturer.

As a result, the pumps and associated discharge piping to the first isolation valves cannot be tested to the required Code Test Pressure.III.,Proposed Alternate Method: During the hydrostatic test and associated VT-2 examination, the charging pumps and associated discharge piping to the first isolation valves will be tested at a pressure of 2400 psig.

QUALITY ASSURANCE MANUAL GXNNA STATXON TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.Section 2 3 PAGE 18 of 39 RELIEF REQUEST NO.8 ALTERNATIVE TESTING OF RCS OVERPRESSURE PROTECTIONS NITROGEN ACCUMULATOR SYSTEM OF VALVES PCV 430&PCV 431C X.Components for Which Relief is Requested:

RCS Overpressure Protection Nitrogen Accumulator System Valves PCV 430 and PCV 431C IX.ASME Requirements for Which Relief is Requested:

IWC-5222(a)

System Hydrostatic Test;The system hydrostatic test pressure shall be at least 1.10 times the system pressure Psv for systems with Design Temperature of 200'F (93C)or less, and at least 1.25 times the system pressure Psv for systems with Design Temperature above 200 F (93C).The system pressure Psv shall be the lowest pressure setting among the number of safety or relief valves provided for overpressure protection within the boundary of the system to be tested.This corresponds to a test pressure of 137.5 psig.The diaphragms in the operators of the subject valves are only designed to withstand a maximum pressure of 105 psig, and therefore cannot be tested to the required Code test pressure.l XIX.Proposed Alternate Method: The RCS overpressure nitrogen accumulator syst: em will be tested to the Code requirements up to the flex connection to the valve operator.Operability of the diaphragm and operator is verified by valve testing requirements.

In addition, an inservice pressure test at operating pressure will be performed once each inspection period on the piping, including the diaphragm.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.Section 2 3 PAGE 19 of 39 RELIEF REQUEST NO~9 REDUCED HYDROSTATIC TEST OF THE STEAM GENERATOR SECONDARY SIDE Components for Which Relief is Requested:

Main Steam Secondary Side of Steam Generator and Downstream Piping to Class Boundary.ASME Requirement from Which Relief is Requested:

IWC-5222(a)

System Hydrostatic Test;The system hydrostatic test pressure shall be at least 1.10 times the system pressure Psv for systems with Design Temperature of 200'F (93C)or less, and at least 1.25 times the system pressure Psv for systems with Design Temperature above 200oF (93C).The system pressure Psv shall be the lowest pressure setting among the number of safety or relief valves provided for overpressure protection within the boundary of the system to be tested.Since the design temperature of the Main Steam system is greater than 200 F, the test pressure is required to be 1.25 times Psv, or 1356 psig.A pressure differential limitation of 800 psig between the primary and secondary side of the Steam Generator has been adopted.This was established early in plant life due to the experiences of some plants with primary side tube sheet cladding separation.

To maintain this 800 psig differential, and the required pressure on the secondary side, the primary system must be heated up to a minimum of 160'F which would result in a problem with heat balance and a potential operational problem during implementation of the test procedure.

The administrative controls necessary to assure a proper and safe test and the complexity required for the test procedure result in a situation that should be minimized.

In addition to the Section XI volumetric and surfaces examination requirements, the piping is part of the augmented inspection program since it falls within the high energy break criteria.'

QUALITY ASSURANCE MANUAL GXNNA STATION TITLE APPENDIX B R.E.GXNNA NUCLEAR POWER PLANT XNSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL XSI RELIEF RE UESTS REV.Section 2 3 PAGE 20 of 39 RELIEF REQUEST NO.9 (con't)A letter was submitted to Dennis L.Ziemann.Chief Operating Reactor Branch¹2, USNRC, Dated: November 8, 1979, requesting relief.

Subject:

System Pressure Test Restriction for Steam Generator and associated Feedwater and Main Steam piping, R.E.Ginna Nuclear Power Plant¹1, Docket No.50-244.III.Proposed Alternate Method: Test the secondary side of the Steam Generator and associated Main Steam piping at a pressure of 1194 psig, which corresponds to 1.10 times the Psv setting.These components are inside containment and any significant leakage would be detected by various leakage monitoring systems during plant operation.

II II QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E-GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.3 PAGE 21 of 39 Section 2 WITHDRAWN RELIEF REQUEST NO.10 ALTERNATIVE HYDROSTATIC TESTING OF STANDBY AUXILIARY PUMP RECIRCULATION LINE I.Component for Which Relief is Requested:

Feedwater, Standby Auxiliary Pump recirculation line between AOV 9710A, AOV 9710B and their associated downstream flow orifices.I.ASME Requirement from Which Relief is Requested:

IWD-5223(a)

System Hydrostatic Test;The system hydrostatic test pressure shall be at least 1.10 times the system pressure Psv for systems with Design Temperature of 200 F (93C)or less, and at least 1.25 times the syst: em pressure Psv for systems with Design Temperature above 200 F (93C).The system pressure Psv shall be the lowest pressure setting among the number of safety or relief valves provided for overpressure protection within the boundary of the system to be tested.For systems (or portions of systems)not provided with safety or relief valves, the system design pressure Pd shall be substituted"for Psv.In order to hydrotest this piping to Section XI requirements, the pressure reducing flow orifices downstream of AOV 9710A&B would require removal and blank flanges installed.

System piping does not provide an isolation valve between the orifices and the Condensate Supply Tank.A significant reduction in tank level would be required to facilitate orifice removal, which is considered to be impractical.

II.Proposed Alternate Method: The Class 3 portion of this piping shall be VT-2 examined at operational discharge pressure during functional testing which is performed once each period.

v a QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.3 PAGE 22 of 39 Section 2 RELIEF REQUEST NO.11 ALTERNATIVE HYDROSTATIC TESTING OF BORIC ACID FILTER&ASSOCIATED PIPING I.Component for Which Relief is Requested:

CVCS, Boric Acid Filter (CSFLBA)and all piping between valves 347, 348A and 349A.ASME Requirement from Which Relief is Requested:

IWD-5223 (a)System Hydrostatic Test: The system hydrostatic test pressure shall be at least 1.10 times the system pressure Psv for systems with Design Temperature of 200'F (93C)or less, and at least 1.25 times the system pressure Psv for systems with Design Temperature above 200'F (93C).The system pressure Psv shall be the lowest pressure setting among the number of safety or relief valves provided for overpressure protection within the boundary of the system to be tested.For systems (or portions of systems)not provided with safety or relief valves, the system design pressure Pd shall be substituted for Psv.The hydrostatic test pressure necessary to satisfy Section XI requirements will exceed the limits for the safe working pressure on the Boric Acid Filter housing flange gaskets.Proposed Alternate Method: The Boric Acid Filter and associated piping shall be VT-2 examined, at full operational pressure during inservice testing which shall be performed once each period.

1 QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.3 PAGE 23 of 39 Section 2 RELZEF REQUEST NO 12 ALTERNATIVE HYDROSTATIC TESTING OF THE EMERGENCY DIESEL GENERATOR COMPONENTS

&ASSOCIATED PIPING I.Component for Which Relief is Requested; Emergency Diesel Generation:

2.3.Starting Air including receiver tanks and associated piping.Fuel Oil Transfer pumps, suction and discharge including miscellaneous lines terminating at oil storage tanks.Jacket Cooling Water system including miscellaneous line terminating at cooling water expansion tanks.II.ASME Requirement from Which Relief is Requested:

IWD-5223(a)

System Hydrostatic Test;,The system hydrostatic test pressure shall be at least 1.10 times the system pressure Psv for systems with Design Temperature of 200'F (93C)or less, and at least 1.25 times the syst: em pressure Psv for systems with Design Temperature above 200 F (93C).The system pressure Psv shall be the lowest pressure setting among the number of safety or relief valves provided for overpressure protection within the boundary of the system to be tested.For systems (or portions of systems)not.provided with safety or relief valves, the system design pressure Pd shall be substituted for Psv.Only portions of the piping associated with the components

'identified above are capable of being pressure tested.The Air Start System pressure test would require termination prior to reaching the engine skid to preclude administrating air to'the Air Start Motors.This would leave that portion of piping between the Air Start Motors to the first isolation, prior to reaching the engine skid, untestable.

(r I E' QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.Section 2 3 PAGE 24 of 39 RELIEF REQUEST NO.12 (Con't)The Diesel Fuel Oil Transfer system would require flange connection disassembly and the installation of blind flanges to isolate the Diesel Oil Storage Tank, which is vented to atmosphere, and the Day Tank where no means is provided to isolate the transfer pump discharge piping at a point close to the day tank.Additionally, the overflow piping from the day tank to the storage tank, which is identified as Class 3, has no isolation valves installed and is vented to the atmosphere.

The Jacket Cooling Water System would require isolating the Cooling Water Expansion Tank, due to vents to the atmosphere, which would include most of the piping subject to pressure testing.Due to the amount of piping within the class boundary which is unable to be pressurized, testing in accordance with Section XI requirements would not prove system integrity over and above the existing Surveillance Inservice and Functional Testing.Proposed Alternate Method: Inservice Testing shall be performed on the Air Start System at least once each period in accordance with the requirements of Section XI.Additionally, once each quarter a pressure'decay test shall be performed on the air receiver to verify check valve operability in the reverse direction for the air receiver inlet check.System Functional Testing shall be performed at least once each period on the Diesel Fuel Oil Transfer and Jacket Cooling Water Systems in accordance with the requirements of Section XI.In addition to the testing discussed above, Technical Specifications 6.4.1 requires surveillance testing to be performed on a monthly basis.Such as, verifying operability of the fuel oil transfer pumps and verifying that the diesel starts from normal standby conditions.

11 QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E.GINNA'NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF REOUESTS REV.3 PAGE 25 of 39 Section 2 RELIEF REQUEST NO.13 I ALTERNATIVE PRESSURE TESTING OF CONTAINMENT PENETRATION PIPING Under Revision.

I' QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVXCE XNSPECTXON PROGRAM FOR THE 1990-1999 XNTERVAL ISI RELIEF RE UESTS REV.3 PAGE 26 of 39 Section 2 RELIEF REQUEST NO 14 ALTERNATIVE HYDROSTATIC TESTING OF THE CLASS 3 SERVICE WATER SYSTEM Component for Which, Relief is Requested:

Service Water, All pressure retaining components within the Class 3 portion of the Service Water System.ASME Requirement for Which Relief is Requested:

IWD-5223(a)

System Hydrostatic Test;The system hydrostatic test pressure shall be at least 1.10 times the system pressure Psv for systems with Design Temperature of 200 F (93C)or less, and at least 1.25 times the system pressure Psv for systems with Design Temperature above 200 F (93C).The system pressure.Psv shall be the lowest pressure setting among the number of safety or relief valves provided for overpressure protection within the boundary of the system to be tested.For systems (or portions of systems)not provided with safety or relief valves, the system design pressure Pd shall be substituted for Psv.Rochester Gas and Electric believes that the hydrostatic test requirement for the service water system is impractical due to system design which dictates the use of an open-ended test.The portion of the system downstream of the heat exchanger is also open-ended and cannot be hydrostatically tested.The remaining section of the system is only isolatable by means of butterfly valves which were not designed to provide a leak-tight boundary.With the system as such it would be impractical to expect the leakages other than at the valves could be detected.The ample margin in cooling capacity inherently provided by system design does not dictate the need for an essentially leak-tight, boundary.Since the system is in constant operation, its integrity is continually monitored.

Thorough inspection of the system each period at the full operating pressure is adequate to detect any gross failures in the system without degrading system safety or availability.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.3 PAGE 27 of 39 Section 2 RELIEF REQUEST NO.14 (Con't)III.Proposed Alternate Method: Pressure retaining components within the operational boundary will receive an inservice test at operating pressure and an associated VT-2 examination each period during the interval.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT XNSERVICE XNSPECTION PROGRAM FOR THE 1990-1999 XNTERVAL ISI RELIEF RE UESTS REV.3 PAGE 28 of 39 Section 2 WITHDRAWN RELIEF REQUEST NO.15 CLASS 2 PIPING<3/8", AUGMENTED EXAMINATION Component for Which Relief is Requested:

Class 2, IWC 2500-1 Table Examination Category C-F-l and C-F-2, Items C5.l0 and C5.50.ASME Requirements for Which Relief is Requested:

Category C-F-l and C-F-2 (Items C5.10 and C5.50, respectively) for piping welds>3/8 inches nominal wall thickness for piping>NPS4, a surface and volumetric examination is required on 100%of each weld requiring examination at each inspection interval.III.Proposed Alternate Method: Rochester Gas and Electric believes as a minimum that the terminal connection welds of identified exempted welds (<3/8" nominal wall)should be examined to the requirements of,XWC 2500-1 Table, Category C-F-l and C-F-2, Xtems C5.10 and C5.50 respectively.

These examinations are identified in the Class 2 Allocation Tables as Augmented Examinations and also are included under the category C-F-l and C-F-2.In the Program Plan Tables (Supplement 1 to Appendix B).These are identified as C-F-l or C-F-2 followed by"---".These components are also noted in the instruction field.1 4 N QUALITY ASSURANCE MANUAL GXNNA STATION TITLE APPENDIX B R.E.GXNNA NUCLEAR POWER PLANT INSERVICE XNSPECTXON PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.3 PAGE 29 of 39 Section 2 WITHDRAWN RELIEF REQUEST NO 16 CLASS 1&2 INTEGRAL ATTACHMENTS'UGMENTED EXAMINATIONS Components for Which Relief is Requested:

Class 1 and Class 2 Integral Attachments on Piping specifically to Support Attachments.

ASME Requirements for Which Relief is Requested:

For Class 1, Integral Attachments on piping as indicated in IWB-2500-1, Category B-K-l, Item B10.10, requires volumetric or surface examination be performed on Base Attachment Thickness>5/8".For Class 2, Integral Attachments on piping as indicated=in IWC-2500-1, Category C-C, Xtem C3.20, requires a surface examination be performed on Base Attachments

>3/4".It has been felt that support attachments to the pressure boundary such as gussets and stanchions should have a surface examination performed to insure the safety and integrity of the Class 1 and Class 2 Systems.III.Proposed Alternate Method: Surface examinations shall be performed on Integral Attachments on piping specifically support attachments once per interval in accordance with IWB-2500-1 and IWC-2500-1, B-K-l and C-C, respectively.

,g L fl QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF REOUESTS REV.3 PAGE 30 of 39 Section 2 RELIEF REQUEST NO.19 PULSATION DAMPENER'LTERNATIVE EXAMINATIONS FOR NOZZLE WELDS&INSIDE RADIUS'Components for Which Relief is Requested:

Charging System, Class 2 Pulse Dampener nozzle inside radius and nozzle welds examination volumes per Category C-B, Items C2.21 and C2.22.ASME Requirements for Which Relief is Requested:

Within Table IWC-2500-1, Category C-B provides examination requirements for Class 2 pressure retaining nozzle welds in vessels.The Pulse Dampener contains three (3)nozzles, in line, located at.the bottom of the unit.These nozzles require both surface and volumetric examinations as specified by Item C2.21 for nozzle-to-shell welds.The same three (3)nozzles also require volumetric examination as identified by Item C2.22 for the nozzle inside radius sections.ASME Section XI requires"essentially 100>of the weld length" as specified within the Notes within the IWC-2500-1 tables.ASME Section XI Code.Case N-460 states that if the entire examination volume or area cannot be examined due to interference by another component or part geometry, a reduction in coverage is acceptable provided that the coverage is less than 10>.R.E.Ginna Nuclear Power Plant was constructed to B31.1, 1955 edition.This code did not contain requirements to ensure that items be accessible for future examinations.

The Pulse Dampener was constructed and installed in the early 1970's, the construction code utilized did not provide provisions for accessibility for ISI NDE.The Pulse Dampener contains three (3)nozzles that require examination under ASME Section XI, 1986 Edition, no addenda per Category C-B.These nozzles are identified as CF-N1, CF-N2 and CF-N3.The three (3)Nozzle-to-Shell welds require both surface and volumetric examinations as specified by Item C2.21.The same nozzles are also examined volumetrically for the Nozzle Inside Radius Section per Item C2.22.The design of the Pulse Dampener is not conducive for examination of the nozzles as identified within the above item numbers.The outboard 1i g 1 N I~~-H I I I I l 1 II QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE XNSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.3 PAGE 31 of 39 Section 2 RELIEF REQUEST NO.19 (Con't)nozzle is identified as CF-N1.Between this nozzle and the middle nozzle (identified as CF-N2)is a support that covers the edge of one nozzle weld heat affected zone.From the middle nozzle to the third nozzle (identified as CF-N3)is a space of only 7/8" from the edge of one nozzle weld heat affected zone to the edge of the other nozzle heat affected zone.Due to the identified interferences of the nozzles and vessel support, the associated volumetric and surface volume coverage acceptance criteria is below the stated value within Code Case N-460.The following table summarizes the coverage obtained using the indicated examination methods.Nozzle Weld NDE Method of Covera e CF-N1 PT UT 664 65%CF-N2'T UT 664 65~o CF-N3 PT UT>90~o 80<Since ASME Section XI Code requires examination of this component and since it is the only one of its type, style and function;the above identified surface and volume coverage should be acceptable in meeting code requirements.

XI.Proposed Alternate Method: Rochester Gas and Electric (RG&E)proposes that the NDE surface and volume coverage identified within the table above be acceptable in fulfilling the code required examinations.

The actual physical configuration of the component being examined is not conducive in obtaining the requirements specified within Code Case N-460.In addition, RG&E proposes to perform a VT-2 visual examination on the entire Pulse Dampener during a leakage test and hydrostatic pressure test in accordance with IWA-5000 and Table IWC-2500-1, as applicable.

I h ll~'

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.3 PAGE 32 of 39 Section 2 ONE-TIME USE ONLY RELIEF REQUEST NO~23 ALTERNATIVE CLASS 3 HYDROSTATIC TESTING FOR CODE REPLACEMENTS Components for Which Relief is Requested:

A.Service Water System, Rules for Hydrostatic Testing of Repairs, Replacements or Modifications to pressure retaining Class 3 components.

Installation of isolation valves a~b.C.d.e.f.g V-4611 V-4613 V-4626 V-4669 V-4738 V-4739 V-4760 B.Turbine Driven Auxiliary Feedwater System, Rules for Hydrostatic Testing of Repairs, Replacements or Modifications to pressure retaining Class 3 components.

Installation of valve V-4023 II.ASME Requirements for Which Relief is Requested:

Hydrostatic testing of Repairs, Replacements or Modifications on Class 3 systems is required by IWA-4400 which specifies that hydrostatic testing shall be performed to IWD-5223(a).

The system hydrostatic test pressure shall be at least 1.10 times the system pressure P,for systems with Design Temperature of 200'F or less, and at least 1.25 times the system pressure P,for systems with Design Temperature above 200'F.The system pressure P,shall be the lowest pressure setting among the number of safety or relief valves provided for overpressure protection within the boundary of the system to be tested.For systems (or portions of systems)not provided with safety or relief valves, the system design pressure Pd shall be substituted for P,.

L I 4 QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTXON PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.3 PAGE 33 of 39 Section 2 ONE-TIME USE ONLY RELIEF REQUEST NO.23 (Con't)IXI.Basis: The first activity to be performed is the replacement of seven (7)valves in the Class 3 Service Water System.The second activity is the replacement of a check valve in the Class 3 Turbine Driven Auxiliary Feedwater System.Service Water S stem: Seven (7)valves within the service water system are currently being replaced: valve numbers 4611, 4613, 4626, 4669, 4738, 4739, and 4760.The replacement of the valves is being performed to the 1986 edition of ASME B&PV Code,Section III.An evaluation to establish the work area test boundaries for the valve replacements was performed as discussed below (refer to drawings 33013-1250 sheets 1-3): V-4626 The replacement valve is a gate valve.Both the upstream and downstream isolations would require the use of butterfly type isolation valves, thus making an elevated (hydrostatic) pressure test impractical.(see Relief Request g14)V-4611/V-4669/V-4738/V-4739/V-4760/V-4613: The first five replacement valves are gate valves and serve as loop cross-connects.

V-4613 is a butterfly type design and serves as a loop isolation valve.In order to isolate the selected areas for replacement, freeze seals would be required to maintain some systems supplied by the Service Water System operational.

The use of freeze seals as isolation boundaries is not feasible.In order to establish test boundaries, complete service water loops would be required to be isolated, thus creating an operational hardship resulting in a reduction in plant safety due to rendering certain critical operational and safety related equipment unavailable.

't Il 1 QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.3 PAGE 34 of 39 Section 2 ONE-TIME USE ONLY RELIEF REQUEST NO.23 (Con't)Turbine Driven Auxiliar Feedwater S stem: The work activity being performed is the replacement of check valve 4023 in the recirculation test line.The Code used for this work is the 1989 edition of ANSI B31.1.Once the valve is installed, the pipe section cannot be isolated to perform the elevated (hydrostatic) pressure test.Referring to drawing 33013-1237, boundaries for the work area would be the pump suction valves (V-4024&4098), the pump discharge valve (V-3996)and downstream flow control valve V-4291.Both V-3996 and V-4291 are not designed for isolation applications, and would require the installation of test blocks.Installation of these blocks was found to be impractical.

Part of the work area would incorporate piping having a design pressure of 150 psi, with a required test pressure of 2304 psi, therefore, an unacceptable condition would exist.Installation of a test block at the discharge of the pump was reviewed and found to be impractical because disassembly of the pump would be required.IV.Proposed Alternate Method: Alternative Pressure Test Requirements for Welded Repairs or Installation of Replacement Items by Welding: Class 3: Using ANSI B31.1 and ASME B&PV Code Case N-416 as a basis for relief, Rochester Gas&Electric considers the following alternative requirements to be acceptable:

NDE shall be performed in accordance with the methods and acceptance criteria of Subsection ND of the 1986 Edition of Section III.Additional NDE also is performed by dye penetrant testing of the root pass weld for the service water valves.For V-4023, a surface examination will be performed.

QUALITY ASSURANCE MANUAL GINNA STATION 1l TITLB APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.Section 2 3 PAGE 35 of 39 ONE-TIME USE ONLY RELIEF REQUEST NO.23 (Con't)2.Prior to, or immediately upon return to service, a VT-2 visual examination shall be performed in conjunction with an inservice or functional leakage test, using the 1986 Edition of Section XI, in accordance with IWA-5000, at nominal operating pressure and temperature.

This code required test pressure and the nominal system pressure at which a leak test will be performed as proposed are shown in the table below: SWS Valves Code Required Test Pressure Test Pressure to be Performedf'~

V-4611 V-4613 V-4626 V-4669 V-4738 V-4739 V-4760 165 psig 165 psig 165 psig 165 psig 165 psig 165 psig 165 psig 75 psig (Nom.)75 psig (Nom.)75 psig (Nom.)75 psig (Nom.)75 psig (Nom.)75 psig (Nom.)75 psig (Nom.)Test pressure reflects system operating pressure of nominal 75 psig.The test pressure (and nominal operating pressure)is considered adequate to detect potential leakage after performing the replacement.

I I E l QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.Section 2 3 PAGE 36 of 39 ONE-TIME USE ONLY RELIEF REQUEST NO.23 (Con't)AFW Valve V-4023 Code Required Test Pressure 2304 psig Test Pressure to be Performed 1100 psig (Nom.)(2)Test pressure reflects system operating pressure of nominal 1100 psig.3.Use of this Relief Request will be documented on the NIS-2 Form for the Replacement.

N QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVXCE INSPECTXON PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.Section 2 3 PAGE 37 0(39 ONE-TIME USE ONLY RELIEF REQUEST NO 24 ALTERNATIVE CLASS 3 HYDROSTATIC TESTING FOR CODE REPLACEMENTS Components for Which Relief is Requested:

Service Water System, Rules for Hydrostatic Testing of Repairs, Replacements or Modifications to pressure retaining Class 3 components.

Installation of isolation valves a~b.c~d.V-4663 V-4013 V-4027 V-4028 ASME Requirements for Which Relief is Requested:

Hydrostatic testing of Repairs, Replacements or Modifications on Class 3 systems is required by IWA-4400 which specifies that hydrostatic testing shall be performed to XWD-5223(a).

The system hydrostatic test pressure shall be at least 1.10 times the system pressure P,for systems with Design Temperature of 200'F or less, and at least 1.25 times the syst: em pressure P,for systems with Design Temperature above 200'F.The system pressure P,shall be the lowest pressure setting among the number of safety or relief valves provided for overpressure protection within the boundary of the system to be tested.For systems (or portions of systems)not provided with safety or relief valves, the system design pressure Pd shall be substituted for P y.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS REV.3 PAGE 38 of 39 Section 2 ONE-TIME USE ONLY RELIEF REQUEST NO.24 (Con't)III.Basis: This request for relief is for a"one-time" use for the replacement of four (4)Class 3 service water valves.The four valves being replaced are valve numbers 4663, 4013, 4027, and 4028.The replacement represents a previously unscheduled activity attributable to defects encountered during a refurbishment program.The replacement of the valves is being performed to the 1986 edition of ASME B&PV Code,Section III.An evaluation to establish the work area test boundaries for the valve replacements was performed as discussed below (refer to drawings 33013-1250 sheet 3 for V-4663 and 33013-1237 for V-4013, V-4027, and V-4028)All replacement valves are gate valves.Isolation boundaries for the valves would require the use of butterfly valves, making an elevated (hydrostatic) pressure test impractical.(see Relief Request g 14)IV.Proposed Alternate Method: Alternative Pressure Test Requirements for Welded Repairs or Installation of Replacement Items by Welding: Class 3: Using ANSI B31.1 and ASME B&PV Code Case N-416 as a basis for relief, Rochester Gas&Electric considers the following alternative requirements to be acceptable:

NDE shall be performed in accordance with the methods and acceptance criteria of Subsection ND of the 1986 Edition of Section III.Additional NDE also is performed by dye penetrant testing of the root pass weld.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ISI RELIEF RE UESTS Section 2 3 PAGE 39 ot 39 ONE-TIME USE ONLY RELIEF REQUEST NO.24 (Con't)2.Prior to, or immediately upon return to service, a VT-2 visual examination shall be performed in conjunction with an inservice or functional leakage test, using the 1986 Edition of Section XI, in accordance with IWA-5000, at nominal operating pressure and temperature.

This code required test pressure and the nominal system pressure at which a leak test will be performed as proposed are shown in the table below: SWS Valves V-4663 V-4013 V-4027 V-4028 Code Required Test Pressure 165 psig 165 psig 165 psig 165 psig Test Pressure to be Performed 75 psig (Nom.)75 psig (Nom.)75 psig (Nom.)75 psig (Nom.)Test pressure reflects system operating pressure of nominal 75 psig.The test pressure (and nominal operating pressure)is considered adequate to detect potential leakage after performing the replacement.

3.Use of this Relief Request will be documented on the NIS-2 Form for the Replacement.

QUALITY ASSURANCE MANUAL GINNA STATION Section 3 EFFECTIVE DATE: PAGE 1 of 3 December 31, 1993 ROCHESTER GAS 5 ELECTRIC CORPORATION SIGNATURE DATE TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL P&ID BOUNDARY DRAWINGS PREPARED BY: QUALITY ASSURANCE APPROVED Y: l~C aha 1~"1 f3 I 8-z89 g-.y3 1.0 General: The P&ID drawings included within this section identify drawings containing lines classified as ASME Class 1, 2, 3 and High Energy pressure boundary.A unique line identifier has been established for each class-line and high energy pressure boundary line.The line identifier was used in the preparation of the"Line, List" to identify the pressure boundary as well as document the line on the applicable P&ID drawing.The rules of ASME Section XI were applied to both class and high energy pressure boundaries as specified by IWB/C/D/F-1200.

The color coded lines appearing on the applicable drawings identify those lines requiring Inservice Inspection and are not exempt under ASME Section XI for volumetric, surface and/or visual examinations.

Leakage examination boundaries and accompanying visual examinations for leakage is not addressed on these drawings.Pressure boundaries that are not color coded reflect lines that are exempt from volumetric, surface and/or visual examinations.

The following color codes were applied to Class 1, 2, 3, and High Energy pressure boundaries; Class 1 Class 2&High Energy Class 3 Blue Red Green QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL P&ID BOUNDARY DRAWINGS REV.Section 3 2 PAGE 2 of 3 The following list identifies the P&ID drawings that contain ASME Class 1, 2, 3, or High Energy pressure boundaries.

Drawin Number Revision 1 2 3 1 1 2 eet 1 2 1 eet 1 eet 2 33013-1231 33013-1232 33013-1236 Sheet 33013-1236 Sheet 33013-1237 33013-1238 33013-1239 Sheet, 33013-1239 Sheet 33013-1245 33013-1246 Sheet 33013-1246 Sheet 33013-1247 33013-1248 33013-1250 Sheet 33013-1250 Sheet 33013-1250 Sheet 33013-1258 33013-1260, 33013-1261 33013-1262 Sheet 33013-1262 Sheet (*)33013-1263 33013-1264 33013-1265 Sheet 33013-1265 Sheet 33013-1266 33013-1270 Sheet 33013-1272 Sheet 33013-1272 Sheet (*)33013-1275 Sh 33013-1275 Sheet 33013-1277 Sheet (*)33013-1278 Sh (*)33013-1278 Sh 33013-1279 33013-1863 33013-1865 33013-1866 33013-1870 Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.Rev.22 9 8 6 27 9 11 9 18 7 6 20 17 13 14 9 14 15 21 10 5 7 14 6 5 16 5 6 5 2 2 6 8 9 9 11 8 13 8

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL P&ID BOUNDARY DRAWINGS REV.Section 3 2 PAGE 3 of 3 Drawin Number 33013-1882 33013-1886 Sheet 2 33013-1887

(*)33013-1893 33013-1908 Sheet 3 33013-1915 33013-1991

(*)33013-2278 33013-2279 Sheet 1 Revision Rev.9 Rev.5 Rev.5 Rev.10 Rev.3 Rev.9 Rev.8 Rev.0 Rev.0 Note: (*)=Identifies P&IDs containing ASME Class piping NPS 1" and below.These identified drawings are not included within this section.

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L fa Cfkf et W>>tk~NLŽR r~--~~~~II N~WI~~loof~NNII I~l',~~t~I Ilkl I~AO O"I i I<<QJwj I fly~ewe At~w Nt~w~ws~A>0)WN N ION Wkt~I~>w~0 M~)N 0>i~f733!~0 i I I Il LO>~<<",!Ž~l.!'w I CC~ll~ew I~~act I IWIN~N f 0>s INN>>NN lt tl Wt>Nt~OWW~N IIWW iL)30'SO\I~IN kt 9:yg'W 1~0.II~NI~)S C Owt~'>t-l lewo j~l~l, I WMNMt~LOL OO IOOOIODC N>1>O~lu AO CDCNWN~~M I N~I>>L>>t I~~I Ctolwi CVI I I I 2 I IC I J~R~I 8 cl)0 11 I)2 Cell IN I<<N>>W, NH IWO NH~Ne-ew I NW HNt~L Ieln I.let~N HN~N d t~ee eow IH~Ikl~~-I~H H I,4-..~tt te Ill g!Hfonln).I I t I A~I.H 6)e~i>>I~HI~tlHI NH.HNQ~8 L..~&'-)HN I I~I IF>>-~~P<<w y He~k~Y.-" t~e<ekl~CHIC L':~Iekk NH,~Hwtte t HN~I I A HI I I'It Il~IN)I I~~NH Wt.till.~N I~I, Lklh.r A-I,Lklh r 8 L)1 Il".)II I-HI HN~HI Nil Ht HN~.I,, Lkl)r't t t A I Li.'lie~----~2;Ilrr~In kl)-I~en en!g,,A" n<<:l)nr--), II:L)lw~w~III~en I;:)Irk)was Il.ltrr IW<<JA N+H'~1,)N'H We~g--I H~~I I PL'I LL~I~W~tt~we w It~tk~Q~tk Owl~~H~I~W WW-I",, i~I)IN I~N.L)w~IN t H~He Nl Nlt twt KH~~~w INI~I AN~Nt A t I NNI;t!I--.p t H HN~~~~I NHN~H~~1~~~w ten~~~I A Nlk<>N OOI INI Nt lnw CC~~I C~etn CH~~2 5 4 5 o 7 8 II II)2 10 IO 12 N-~I~r.I>>~~I>>~N~~IH WWW~P>>~N W>>N It NI~I~I-N>>.~I IHO t>>t~IN N\~HIH IW~WH>>~NHN~el I~~lo tl~>>I>>.~NM~~N Nt W 11>>>>l~N H~n~>>N Itt>>NIN H j>>IW~NN~H I>>IN IOOI Nt~HN~11~<<>>I>>I NN~W>>tt>>I 1 f+~~IWHII+<< ~I~>>I<<~~NI N>>~t~~H>>WOO~~~~I Sa NIN~NWW W NIN INWW~>>N IHH MII~M ANON lt~HOO 11 I~Hl.C Ti i I~~t-O~1~IIH~llt N~N II~N~W~~HI>>~~~N~I rt<<M~N Wt<<t~I t~NNI~NWM Hl~WWN<<t H NNNM~N OO1 I~I W 1-11>>t~t~IN~11 M~M>>M W HN<<~HIN tl>>~WI HH~I 11 MN~IIO1~H~I>>P ftttttN~IM~II W II N~WtN~H~Hl~~tt III I t>>t O~llHI'N~~1>>l~~1~Ill f OIN irlLM~1>>~HI I<<l~>>I H tlt i fill.'" i~~I H I H NH I I I>>W~H~Itt>>l I IW~N~~HI OHO I>>IW f f Ntl>>HI IH~I Y It Hl~N~Hl~~~NNI~I<<NOW HI~,Ir>>IWLINI INN~I I QUALITY ASSURANCE MANUAL GINNA STATION Section 4 PAGE 1 of 27 EFFECTIVE DATE: December 31, 1993 ROCHESTER GAS 8 ELECTRIC CORPORATION SIGNATURE DATE TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL CODE TABLES PREPARED BY: QUAUTY ASSURANCE REVIEW: APPROVED Y: a.-)-f3 f84+3 1.0 General The following Code Tables were developed to address applicable ASME Section XI Requirements specifically to R.E.Ginna Nuclear Power Plant.The Format of each Table is identical and a definition appears before the start of each text.ASME Section XI Code, 1986 Edition, no Addenda, and 10CFR50 specify that this program conforms to Articles IWB, C, D and F of ASME Section XI, if not altered by a Relief Request and/or Code Case.The following list identified the Code Table applicability. Code Table Com onent Jurisdiction Class 1 Class 2 Class 3 Class 1, 2 and 3 IWF Component Supports Item Ntx Exanunation Category The ASME Secuon XI item No.and Category of the component are listed h these columrn.Components and Parts To be Exanuned Each type of examination area is listed h this column.Examhation Methods Thc NDE method required to satisfy Code requirements is listed in this column.Examination Requirements for Third Inspecthn interval This column provides information regarding thc number and/or percent of examinations required to be performed for the inspecdon htervai Examhation Technique/Exanunation Area Comments This column provides&formation s peciTic to examination techniques, examination areas, or comments.0 td 0 H 0 to X H WO n~~0 tgl H U tfy~~ox I WO~LO Q Egf~tf)H 0 R'd WX g 0 4Q Q H'z C d OX X U P H 0 M fll 0 0 Item Ntx'n Category Bl.)0 B-A Bl.l)Bl.)2 REACTOR PRESSURE VESSEL Components and Parts To be Examined Cucumferentia) and Longitudinal Shell WeMs Exanunation Methods Voluinetrie Exartdnation Rcqudrcments for Thhd Inspection Interval)00)b of one cucumfcrcrzia) weM to be exauuncd at tructural discontinuhy h the bchlh>>region.The duce cuber circumfercntia) wzlds shall be periormed as a Augmented Program as speeiT>>d by 10 CFR Part 50.Examinations may be performed at or near the end of the Inspccrion IntetvaL Exaudnarion Tcchn'quelgxauunation Area Commcras Examination of cucumferenria) sheU weMs will be performed whh UT techniques. There are no)onghudina) weMs at R.E.Ginna.Qg>10 RCMP SCCA PPgH M 4K O H 0 I m 81.20 B A B1.2]B).22 8130 B.A B).CO B.A B).50 B-A BI.S)B3.00 B D B3100 BD SC.)0 B-E BI.)I Bc.)2 Sc.)3 Circumfcreruial aud MerMiona)Head WeMs Shell.to.Flange WeM Volumctrk Head-to-F)ange WeM Volumetric and Surface Repair Welds Nozzk-to.Vessel WeMs and Volumetric hozzk Iruide Radius Section Pania)Penetmtion WcMs: Visual (VT-2)Vessel Nmzks Consol Rod Drive Nmzks Insuumentation Nmzles)00bb of the weM to be examineL At least 509b of the weM shall be examined from the Range face by the end of the fust Inspection period and the remtdnder by the end of the third Inspecuon period.100)b of the weM to be examineL)009bof nmzks.At least 25)b but not more than 50)b of the nmzks shall be examined by the cnd of the fiat period and the remainder by the end of d>>IntctvaL At kast 25)b of each group of weMs of comparabk size and function to be exandneL There are no meridional or circumferenria) head weMs at IL E.Gutna.The sheU.to.lhnge weM will be cxanuned from the vessel seal surface and from the vessel wall inside surface whh UT.NOTE: Relief Request u 1.The head.to.Range weM will be examined with UT and surface examination techniques when the head is removed.No repair welds at R.E.Ginna.'Ihe nmxle-to-vessel weMs and nozzk iiuide radius secrions will be examined with UT.Examination wiB be perfosnef during the system hydrostatic test or ahernariively to Code Ca>>N-49TL VT examinations will be periormcd M accordance with IWA-52Cth 0 M WO o~~0 tg)H a~><OM I bf)O+bf)Z+)f)H 0 MHg R'Ef 0 R wa g H 0'Jy L B5.10 S.F S520 B.F BS30 B6.10 SZ.)IVessure-Retaining Dissimilar Metal bveMs Volumetric 8 Surface Pressure-Rctahung Dissin8ar Metal)VeMs C)osurc Head Nuts>2 Surface inches in Diameter All Nozzle.to safe end butt weMs NPS 4 or larger.)00)b of nuts to be exanuneL Examhtation may be perfosncd at or near the end of the inspection intcrvaL Eauns may be performed cou>>ident whh the vessel nozzle exams require)by Category B.D.No dissimilar metal welds on RPV at IL E.Gin@a Nuts will be examined whh MT when renovcd for refueling. M fD 0 b 0 Table 1 NSERVVICE INSPECTION PROGRAM C1ASS 1 (Gout'd)item No.Examinarion Category Components and Parts Tobe~Examination Methods Examination Requirements for Third Inspection interval ExamfnatNn Technique/Examfnathn Area Comments REACTOR PRESSURE VESSEL cont'd Brx20 BG I Qosure Head Studs, In Place,>2 Inches ln Diameter Volumetrk 1009b ol studs to be examined.Xuamfnadon may be performed at or near the end ol the inspecrion intervaL Qosure stud examfnarions may be performed'in pince.'xaminations shouM be schedukd when studs are removed to reduce radiation exposure and aBow 0>>most thomugh examinarion. Code Case NS07-I shall apply.86.50 BZ.I B7.10 BG.2 B7~B4.2 Qosure Head Studs, When Removed,>2 Inches in Diameter Volumetrk and Surface Threads in Fhmge>2 Inches In Diameter Volumetri Prcssure-Retaining Bohing s2 Inches in Diameter CRD Housings Bohs, Studs, and Nuts Visual (VT.I)Pressure.Retaining Qosure Visual (VT.I)Washers and Bufhings>2 Inches in Dhmetcr 10016 of studs to be xanunc<<L Xammiai'on may be performed at or near the end ol the Inspccrion imervaL 10016 of threakd holes to be cxanun<<L Exanunation may be performed at or near the end of the inspection intervaL AU washcrs and bushings to be examined upon stud rcmovaL Examfnatkn may be performed at or near the cnd of the Inspection intcnraL AB bohs, studs, and nuts to be exanun<<L'The studs will be examined with UT and MT.Code Case NS0r/I shall apply.No pressure-retaining bohing<2'n diameter on RPV at L E.Gfnna.Pressure-retaining CRD housing bohng wBI be exanuncd when disassembl<<L H~0 U)~NQ WOW tf)H R c(7 tf)C ('Ef>O(f)OW I+I eWa+tf)O Igrr H+tf)H O e()7~Hgo BRIO B.H B 13.10 B-N.I Integral Attachments lor RPV Vessel Imerior N/A Visual (VTS)Accessible areas to be examined during each Inspection periorL No Integrally welded attachments on RPV at IL E.Gfnna that meet the req Iremcnts of Category B H.B13.50 B.N 2 interior Attachments Within Bemine Region Visual (VT.I)Accessl>>k attachment welds to be examin<<L Exandnations may be compktcd at or near the end ol the inspectkn IntesvaL B13.60 B.N.2 B13.70 B NB BIO.10 Interior Attachments Beyond Behline Region Visual (VT-3)CweSupport Structure Visual (VTS)Conuol Rod Drive Housing Volmnetric or WcMs Surface AcccssRrk attachment weMs to be examln<<L Examinations may be completed at or near the end of the Inspecrion intervaL With core.support strtture removed, all aceessibk surfaces to be examin<<L Examfnacions may be compkted at or near the end of the inspection IntetvaL WcMs in IOIb of the peripheral CRD housings to be cxamin<<L~ns may be performed at or near the cnd of the Inspection huesvaL The CRD housLng weMs will be examined with PT.(I)(D 0 I" 0 Item No.Examinarion Category 8 IS.IO B.P REACIOR PRESSURE VESSEL<<ont'd Components and Parts To be Examined Examine non Methods All Pressure.Retaining Vhual (VT 2)Boundaries for Vessel Components INSERVKX INSPKCIION PROGRAM CIASS 1 COMPONKNIS (Cont'd)Examinarion Rolulrements for Third Inspecth>n Interval AU components to be examined during system leakage test.Examfnarions to be performed in accordance with IWB.5221 prior to plant startu p after each refueling outage.Examinarion Technictur/Examfnarion Area Comments VT txaminarions will be performed in accordance with IWA.524k Qgk)0 RC(/)Q ZCCV WWgH (I)O t3 H 0 B15.11 B-P AB Pressure-Retaining Boundaries for Vessel Components Visual (VT.2)All components to be exanuned during system hydrostatic test or ahernatiwly to Code Case NIPS.Examinarions to be performed ln sccordanm whh itVB.5221/5222 at or near d>>end of the Inspection IntervaL VT exanunations will be periormed In accordance wnh IWA-524L 0 (/)W O O~~0')H~u)Z~o v)I tf)O ())tf)<+'Lf)H (/)Hg Q C rE)OX X U 0 H 0 g0 4Q r I (/)8 0 r 0 Tsbk I INSERVKX INSPECIION PROGRAM CXASS I COMFONENIS (Gxa'd)Item Ncx PRESSURIZER 82.10 8 8 82.11 82.12 Components and Pans To be Examhed Circumferential and longitudinal SheU.to-Head WeMs Examination hlethods Volumetric Exatnination Rcqmremeats for Third Inspection interval The upper and bwer head-tosheU weMs to be examfnccL One foot of one hngitudhal weM intetsccring each head-to-sheU weM to be examhcd.Examinarion Technique/Examhation Area Comments Examination will be perfoccacd with UT techniques.(I)R K O H 0 82.20 8 8 82.21 8222 83.110 8 D Eh)20 8-D BS.C0 B.F Circumfccearial and MeriTioaai Head WeMs Volumetric Nmzkco.Vessel WeMs N/A Nmzk Inside Radius Secrions Volumetric Nozzle-toSafe End Dissimilar Metal Welds se Inches NPS Surface snd Volumetric Heater Penetration WeMs Visual (VT.2)Ihere me no p essurixer head weMs at L E.Ghna.AU hsMe radius secrions to be examhed.At least 2596 lmc not more than Stylk of the nozzks shall be examined by the ead of che fust period and the rcmahdcr by the cnd of the inspection iatccvaL AU pressurizer heater penetration wekls shaU be examined duchg system hydrostatic test or ahernatively to Code Case N~98 in secor dance with IW8.5222 at or near the end of the inspection imecvaL AU butt weMs to be examhed.No nozxk-to.vessel welds.Nouks are htegraUy cast into the head of pressurizer at L E.G irma.Exandnations will be performed whh UT techniques. VT examhation will be performed in accordance with IWA.5240.Examinations will be periormcd with PT and UT techniques. 0 0)i2" H Er)O o~~U 0 c()H O (/)I d+c()O+c()Z+QH R'E)td X g 0 4 Q Q H C'I)O Er)Ez)U igic H XI DL'd t)3 0'Ef 85.50 8-F Noxxk-toSafe Ead Dissiaular Metal WeMs<4 Inches NPS N/A No nmzle-to-safe end~imUar metal weMs on pressurixer at L E.Gina'5.60 B.F Noule.toSafe End Socket WeMs N/A No dissimilar metal socket weMs on pressurixer st iL E.Ginna.Bck60 84.1 86.70 Bc%80 Pressure Retahiag Bohhg>2 Inches h Diameter Bohr, Scuds, and Nuts Visual (VT.I)s2 Inches ia Dhmeter AU bohr, scuds, and nuts to be examhed.No bohing oa pressurixer >2 iaches h diameter st R.E.Ghna.Bohing examharioas may be performed h place uader cension or when disassembkd or removed.V 0 8820 B-H IntegraUy Welded Attachments P essurixcr support sMrt not required for examharioa for 3rd and 4th hcervak by Code.O 4 C' Tabk 1 INSERVICK INSPECIION PROCRAM CIASS I OOMPONENIS (Cont'd)hem Ntx Exanunation Category PRESSURIZER Cont'd BI520 B-P Components and Pans To be Examined Pressure.Retaining Boundaries for Vessel Components Examlnarion Methods Visual (VI'2)Examinarion Requirements for Thhd Inspeerion Interval All pressurixer components to be examined during system kahage test.Examination to be performed in accordance with IWB.5221 prior to phnt stattup after each refueling outage Examination Tcehnhlue/Examination Area Comments VT examination will be performed in accordance with IWB-5240.c M O H 0 B1521 B-P Pressure.Retaining Oundaries for Vessel Components Visual (VT-2)All pressurizer components to be examined during system hydrostatic test or ahetnativciy to Code Case NAPL Exanunation to be per-formed In accordance with IWB-5221/5222 at or near the end of the Inspecrion huervaL VT examinarion will be performed in accordance with IWA.5240.H OM Er)O OH~U 0 tf)H O M I+If)O+tO H R'Ef A R'T)(r()O td xa P H XI X ()())0'd M (i)0 0 Iran Examination Nfx Category SITA%I GENERATORS 8230 8.8 8231 8282 Components and Parts To be Examined Cireumferenrial snd Meridfonal WeMs in the Iffwer Head Examinarion Methods NNSERVICK NSPECIION PROGRAM (2ASS I (2)MPONENIS (Co%'d)Examhation Requirements for Ihffd fnspecdon Intavaf Exsfnhation Technique/Exanination Area Comments There arc no steam generator kfwer head circumferenthl or meridional weMs.MCCOY O H 0 82.S0 8 8 83.130 B.D BXICO B.D 85.70 B.F Tubesheec to.Head WeM Volumetric Nmzk Inside Radius Sections Volumetri NPS 4 or Larger Nmzle.to.Safe End Diafmilar Metal Wchh Surface and Volumetric less than NFL, Nmzk.to.Safe End DissimBar Metal WeMs Nmxle.to Vessel WeMs N/A Tht tubahccc.tDhcad wcM will bc cfulffuncd. 'The exanhation will be limited to one of the two stcam gcfltrators All nmzk inside radius senions wBI be smfninccL At kast 2596 hz noc more than Sty)h of the nozzks shall be txanuncd by the tnd of the first hspection period and che remainder by the end of the ins penion mtaval All nozzle safe~dissimihr metal weMs shall be examined.Examination will be performed with UT techniques. There are no steam generator nmzle-to-vessel weMs.Nozzks aft integrally cast into heads.Examinations will be performed with UT ccehniques. 'Ihere are no steam generator nmzle.to.vessel webb.Exanunaf ons will be performed with PT and UT teehniqua at R E.Ginns.There are no steam generator wehh of this type.H 0 (I)g H (z)O O~~U cf)H O (I)I+cf)O>cf)H XI v m Q H 4 I)C'I)O W Q 2e (zf U~H XI X'I)(II 0 86.90 lhG.I 86.100 86.110 NmxlecoSafe End Dissimilar Metal WCMs Prcssure-Rctsuung Bohng>2 Inches in Dhmecer No bokhg on stean generators >2 Inches h diameter ac R E.GinnL There are no steam genemcor wehh of ttus type.8730 BG 2 BI530 8-P IntegmBy WeMed Attachments Pressure.Retahing Bomxhries N/A Visual (VT-2)Bohr, Studs, and Nuts Visusl (VT I)s2 Inches in Diameter All boks, scuds, snd nuts will be exanined.Ihe examination will be limited to one of the two sttafn gcntfstofs. AB nesm generator components co be eaunfned during system leakage test.Exanhations co be paformtd in ccordanm whh IWB-5221 prior to phnt stanu p afttr each refuelhg outage.Examinations msy be performed in phct under tension or when rcmovcd.Ihert are no stcam generator imegraBy wehkd attachments. IW8.2500 13.VT exsmlnarions will be performed h accordance with IWA-524th (/)(t)0 0 Item Exandnation No.Categon/STEAM GENERATORS Cont'd SISS I B-P BI 6.20 B4)Components and Pans To be Examined Examination Methods Pressure.Retaining Boundaries Visual (VT.2)Steam Genemtor Tubing Volumetric TaMe I INSERVKX INSPECIION PROGRAM CLASS I CDMPONENIS (Gun'd)'Requirements for lMrd inspection Interval All steam generator components to be examined during system hydrostatic test or ahernatively to Code Case N~PIL Exanunarions to tge performed in accordance whh IWB.5221/5222 at or near the end of the inspection intervaL The tubing in the hoc kg side, U.bend portion, and optionally coM kg side will be exanuned.Examination Technique/Examination Area Comments VT exaininanons will be performed in accordance with IWA4240.Examination requirements, exandnation method, and the extent and frequency of examinarion shall be in accordance with plant Tcchnical SpeciYications. H'xf 4 0 (/)X Erf g H td O o 0 tf)H>O fJ)I tf)O>tf)Z+tf)H 0 (Hg R'(f Q 0 Q a Ef C Ef OX~H 0 Qg>10 RR(/)g ZCC~~JYgH (I)C K O H 0 (f)0 0 0 I a Item No.Examination Category 8250 8.8 8251 8252 HEAT EXCHANGERS Components and Pans To be Examined Head WeMs Examination Methods TaMe I NSERVVICE INSPECIION PROGRAM aASS I COMPONENTS (Cont'd)Examination Requirements for Third Inspection Interual Examination Technique/Examination Area Comments No tneridional or circumfcrenriai heal weMs in beat exchanger at IL E.Ginna Qg>10 RCMP'CC~VPgH M C K O 0 82.60 8 8 Tubcshect-to.Head Welds Volumeuie Each tubesheet-to.head weM will be cxanulRd Examination wiB be performed with UT teclmiques. 82.70 B.B 82JS B-B 83.150 8-D 83.160 B.D 85 100 B.F 85 110 85.120 86.120 BG.I 8&.130 86.1 CO Longhudinal Welds Tubesheet.to&hell WeMs Vo!umetrie Nmzle-to-Vessel WcMs and Nozzk Inside Radius Section Volumetri Pressure-Retaining Dissimihr Metal WcMs Bohs, Studs, and Ntxs s2 Inches M Diameter Prcssure-Retaining Bohing N/A)2 Inches in Diameter Each tubeshect.to.shell weM will be cxanuncd.All nmzle.to-sheB and nmzle insMe radius sections will be cxaminctL At least 2596 but not more than 50%of the nozzles shall be examined by the end of the first inspecuon period and the remainder by the end of the Interrak There are no RHE longitudinal weMs at IL E.Ginna.Examination will be performed with UT tecluuquea, Examination will be performed with UT techmques. No heat exchanger dissimilar weMs at R.E.GfnnL No heat exchanger bolring at R.E.Glnna No heat exchanger bohing at IL E.Ginna.0 M X H W O O 0~O M I+If)O ())tf)<+M)H g 0 CQ Q H R'E)C'E)OX V R X O~H XI X'd ())0 b7 Integrally WeMed Anne hments Integrally weMed auachments not required for examination for 3rd and 4th Intcnrais by code.815 C0 B.P 815A I B.P Pressure.Retaining Boundaries Pressure-Retainfng Oundsries Visual (VT-2)Visual (VT.2)All RHE components wiil be examined during system kakage test.Examinarions to be performed in accordance with IW8.5221 prior to phnt startu p after each refueling outage.All RHE components w81 be examined during system hyhostatk test or ahernatively to Code Case NA98.Exandnations to be per-formed in accordance with IW8.5221/5222 at or near the end of the inspection Interrak VT examinarions will be performed in aceordanee with IWA.5240 VT examinations will be performed M accordance with IWA 524k (D 0 0 II item No.PIPING 85.130 B.F 85.140 LF Components snd Pans To be Examined DissimQar Metal Wekh s4 Inches NPS Dhsimibr Metal WeMs<4 inches NPS Exarrdnation Methods Volumetric and Surface N/A Table 1 INSERVKX INSPECllON PROGRAM CIASS 1 COMPONENIS (Cont'd)Exarrdnation Requirements for T)drd Inspection interval All butt welds to be examined.Examination Technique/Exsndnatbn Area Comments The wekh will be examined with UT and PT.No dbsimitsr metal weMs<4 inches NPS at L E.Gtnna Qg>I0 RRf/)g MCCOY QQgH M O H 0 85 150 B.F 86.150 BG I 86.160 86.)70 89.10 W 89.11 89.12 W Dissinular Metal Soc'ket WeMs Pressure.Retsinhrg Boking>2 Inches in Diameter Pressure-Rettdning Boking s2 Inches in Diameter Cucumferential Pipe Wekh s4 Inches NPS Longitudinal Pipe Welds s4 Inches NPS N/A Volumetric and Surface Volumetric and Surhce 259k of 0>>required circumferential butt welds to be examined.See Note I at end of Tabk I for sekction criteria.Longitudinal weMs that adjoin schedukd eircumferemisl wekb are to be examined.One pipe diameter ncx to exceed 12 inches of each bngitudinsl weM kngth rcquireL No dissimilar metal socket wekh at IL E.Ghana.No pressure.retaining bohing>2 inches ht diameter at L E.Ginna.No prcssure.retaining bohing<<2 h>>hes on piping at L E.Girma.The piping wekb will be examined whh UT and PT.The piping wekh will be exanuned with UT snd PT.0 f/)g H XO O 0 I~)t)H O f/)+I ta I'Ej tt)O Ett tt)Z L)t)H Q H R'd O Erj Erj O~H'Tj td 0 m 89.21 Circumferential WeMs Surface<4 Inches NPS 25%of the rcquircd circumferential butt weMs to be examhteL See Note I at end of Table I for sekction criteriL'the piping wekh will be examined whh PT.g 0 Longitudinal Pipe VVeMs<4 Inches NPS No pressure.retaining bnghudktst pipe welds<4 h>>hes NPS at IL E.Ginna.8920 W 898)8932 W 8940 W Branch Pipe Connection Welds a4 Inches NPS Branch Pipe Connection WeMs<4 Inches NPS Socket)VeMs Volumetric and Surface Surface 2544 of the required branch connection joints to be examined.See Note)at end of Table I for sekction criteriL 25%of the required branch connection joints to be examineL See Note I at end of Table)for sekction eriterim 25)k of 6e required soc'kct webb to be exandneL See h ore I at end of Tab k I for selenion eritcria.lhe branch connection wekb will be examined with UT and PT.The branch connection weMs will be examh>>d with PT.The socket weMs witt be examined whh PT.0 0 Bttk)0 B.K I Integrally WeMcd Attachments Integrally weMcd attachments rxx required for examination for 3rd and 4th intervab by code. F~~I I.~-.~ Item Ntx PIPINC Cont'd BI%50 B.P Gomponents and Parts To be Examined AB Pressure Retaining Visual (VT-2)Boundaries for Piping Components Table 1 NSERVKX INSPKCIION PROGRAM (XASS 1 COMPONENIS (Cora'd)Examinarion Requirements for Third Inspecrion interval All components to be examined during system leakage test.Examfnarion to be performed in accordance with IWB.5221 prior to plant stanup alter each fefuelfng outage.Examination Technique/Examination Area Comments VT examination wiB be performed in accordance whh IWA.5241 Qg>10 O H 0 B15.5)B-P All Pressure Retaining Boundaries for Piping Components Visual (VT-2)All components to be examined during system hydrostaric test or alternatively to Code Case N 498.Examination to be performed in accordance with IWB.5221/5222 at or near the end of the Inspection Intetvah VT examination will be performed in accordance with IWA.5240.0 M g H WO 0 NOH a~<+OM I~tOO LQ Q>NOH MHg R d g 0 CQ e'Q (OX X U~H'0 (2)0'E)M (t)0 I 0 Item No.Examina don Category Components and Parts To be Examined Examination Methods Table 1 INSERVICE INSPECllON PROGRAM CIASS 1 COMPONENIS (Cont'd)Examinadon Requirements for Third Inspection Interval Examination Technique/Examination Area Comments Qg>10 RR(/)P'c C C Q O PUMPS 86.180 BG.I Bohr and Studs,>2 Inches Volumeuk in Diameter All bohs and studs to be exanuned for hems associated with one component In a muhicomponent group.The bohing wtlI be examined whh UT.Code Case N.307.1 shall apply.The bolting may be examined In pkce under tension or when disassembled or removetL 86.190 B4.1 86200 84.1 87XO BG.2 8IIL20 8-K I 812.10 B.LI 812.20 8-L2 815.60 B.P Flange Surface for Bolting>>2 Inches h Diameter When Connection k Disassembled Nuts, Bushings, and Washers>2 Inches in Diameter Prcssure-Retammg Bohmg s2 laches in Diameter Integmlly WeMed Attachments Pump Casing WeMs Internal Surfaces of Pump Casings Pressure.Retaining Boundaries for Pump Components Visual (VT.I)Visual (VT-I)Visual (VT.I)Visual (VM)Visual (VT.2)Examination inc!udes I inch anntdar surface of Iknge around each stud hok surface when disassembled. AU nuts, bushings, and washers to be exanuncd when disassembkd on one component in a muhicom ponent group.Reactor coolant pump easing weMs on one pump to be examineL One reactor coolant pump to be exanuned when disassembfoL All components to be examined during system kahsge test.Examfnatson to bc performed trt accordance with IWB$221 prior to pknt startup after each refueling outage.VT examination will be performed when UsassembletL VT examination will be performed when dhassembkd. No pressure.retaining bohfng<2 Inches in diameter on pumps at IL E.Gfnna.Integrally welded attachments not required for examination for 3rd and 4th intervals by code.Examination performed in accordance with Code Case N.481.Pump casing Internal surface will be examined with vkual techniques when disasscmbktL VT exanunations will be performed in accordance with IWA.5240.0 (/l XO o~~3 tf)H 0 (I)I+tf)O+'LO H (/)H~I-3'E)(T)X g 0 CQ Q C'Ef O (x)X U P H M Cl 0 81%61 8-P RG1.14 Flywheel Pressure.Retaining Boundaries for Pump Components Pump FIywheek Visual (VT 2)Surface and Volumetric AU components to be examined during system hydrostatk test or ahcmatively to Code Case N.498.Examination to be performed In accordance with IW8.5221/5222 at or near the end of the inspection intervaL Each reactor cooknt pump Ilywheel to be examined per Rcg.Guide 1.14.High mess areas to be examined each period with fuU examination at the end of intcrvaL VT examinations will be performed in accordance with IWA 524th Examinations will be performed with MT and UT techniques on the 2 active components as a minimum on an Augmented Program.(/)(D 0 I 0 0 INSHMCE INSPECllON PROGRAM CIASS I COMPONENIS (Cont'd)Item Examinarion No.Category Components and Pans To be Exanuned Examination Retiuirements for Third Inspecrion Interval Examinarion Tcchnhiue/Examfnarion Area Comments O VALVES 86.210 BG I 8&.220 86230 Bohing>2 Inches in N/A Diameter No valve bohfng>2 inches in dhtmeter at L E.Ginna 87.70 BG.2 Bohing s2 Inches In Diameter Visual (VT-I)All bohs, studs, and nuts to be examined on I component per group.The bohing may be examined in place under tension or when dlsassembkd or removeL 81030 8 K I 81230 8-M I 812.40 B-hl I 8 IL50 8 M.2 815.70 8 P 815.71 8 P Integrally WeMcd Attachments Pressure.Retaining WeMs in Valve Bodies<4 Inches NPS Pressure-Retaining Welds in Valve Bodies a4 Inches NPS Internal Surfaces of Valve Bodies on Valves>4 Inches NPS All Prcssure.Retaining Boundaries for Valve Components All Pressure Retaining Boundsries for Valve Components Vo!muetric Visual (VT4)Visual (Vl'-2)Visual (VT-2)Ail weMs on one valve In each group of valves that ls of the same nsttucrion and sfmBsr function to be cxaminoh One valve iu each gmup of valves that is of the some construction and simBsr function to be cxaminctL All components to be examined during system kahsge test.Examination to be performed in accordance with IWB 5221 prior to plant stsrtup after each refueling outage.All components to be examined during system hydroststk t<<st or ahctnatfvely to Code Case NA98.Examination to be performed in accordance whh IW8.5221/5222 at or near the end of the inspection Interval Integrally weMcd attachments not requfml for examination for 3rd and 4th intcrvah by axle.No pressure retaining weMs In valve bodies<4 inches NPS at IL E.Ginns.Valve weMs will be exanuned with UT.Internal surfaces of valve bodies to be examined with VT.3.VT examinations will be performed in accordance with IWB-5240.VT examinations will be performed in accordance with IWA.5240.0 (I)g H XO o~~OeH>tf)Z+o(f)I+tOO ()7 tf)Z R'E)go 4A c'Q H OX ea d (gi 0'T)(I)9 0 0 O Table I As aUowed by IOCFR50.55(a)(b)(2)(ii), ASM E Section XI 1974 Edition with addenda through 1975 k permitted for Category BJ weM sekction and does not utilize stress kvel crfteriiu Category BJ weM sekcdon shall be performed to ASM'ection XI, 1986 Edition, no aMcnda and shall ncc utilize stress level criteria.Exanunations selected shall be distributed in such a mamur to include: (a)All acoessibk Terminal Ends in each pipe or branch run connected to vessek.(b)All aeeessibk Terminal Ends and joints in each pipe or branch run connected to other components such as pumps, branches and anchors.(e)All dissbnilar metal welds.Q)%10 QRMQ SCCA WWgH M'gK 0 0 Nixer (d)AddiYional piping weMs (structural discontinuity weMs)so that the uxal number of circumferential butt weMs (or branch connection or socket weMs)sckctcd I'or exainination equals 25%of the cfrcumferentksI burt weMs (or branch<<onncction or socket weMs)in the Reactor Coolant piping system.This total does mx include weMs excluded by IWB-1220.These addiYional weMs may be kcated In one Mop and shall be sekcted among the Qass I syrtems, prorated, to the degree piactkaL Terminal End (TE)WeMs are defined as the exuemiYies of piping runs that connect to ructures, components, or pipe anchors, each of which acts as a rigid restmint or pmvMes at least two degrees of restraint to piping thermal expansion. Thk definition (ref.IWA.9000)is interpreted to include the folhwingt (a)Chcumferential weMs whfun 3 pipe diameters of the centerUne of rigid pipe anchors or anchors at penetmtions of the prknary reactor conta'uunent.(b)Piping connection weMs in whkh the main process piping is at kast 3 times krger than the Branch Run.(c)Piping connections to rigMly mounted eomponentr, such as vessels, pumps, cet.The folkwing weld types are identified in Su pplement I to Appendix B, the Program Plan.'E.A Terminal End at a Piping Anchor'E-B Terminal End at a Branch Connection 'E.P Terminal End at a Pump Connection 'E.V Terminal End at a Vessel Connection

• SD Structural Discontinuity

'P Pipe to Pipe Burt Weld'EAM Longitudinal Seam WeM Note: When more than one weM type k a pplicable, the more restrictive (i.c.'IE)is utilized.Terminal Ends at component or branch connections are considered to be the piping weM connection to the safewn4 nozzk, reducer, weMokL sockolet or fiange.2.Structural Discontinuity (SD)WeMs includes circumferentksl weM joints at pipe-to.nozzk, pipe-to.valve, pipe.to pump or pipe.to firting.Fitting.to.Firting connections and all socket.wcMcd connections shaB be considered Structural Discontinuities. 0 M g H Ezj 0 n~~U 0 tf)H~If)Q O M I'Tj+If)O (EI tf)~+If)H td R (j Q C'Ej O Lxj 0 R wa vbs H'd (EI 0'Tj=I m (2)Examination is limited to those integrally welded artachmems that meet the folkrwing conditions: (a)the attachment k on the outside surface of the pressure.retaining component;(b)the attaclunent provides component support as defined in NF-1110;(e)the attachment base material design thkkncss k 5/8 inch or greater, and 0 (d)the artaclunent weM joins the artachment either directly to the surface of the component or to an Mtegrally cart or forged attachment to the component. Examinafons include the weMcd attachments of piping required to be exanuned by Exanunation Category 8 J and the weMed attachments to associated pumps and valves integral to such piping. 1 Item ho.Exandnatlon Category'Ihe ASM E Section XI ItemÃtx and Category of the component are listed in these columns.Components and parts To be Exandned Each type of exarrunatfon area is listed In this column.Examhtation Methods The NDE method required to satisfy Code requirements is listed h this column.Table 2 Examination Requirements for Third Itnpection Interval This colunm provides Information regarding the number and/or percent of examfrmtions required to be performed for the inspection intervaL Examination Technique/Exanunation /trea Comments This cohunn provides Information speeiTic to exanunation techniques, exandnatfon areas, or comments.Qg>I0 RAM'CCL O H 0 4 0 M WO~LO H O M I'd+tOO>tOZ+tO H MH~Q H'R'Tf C'0 OX DR xa~H XI X M N 0'Ef Item Ntx PRESSURE VESSELS C1.10 G*Components and Pats To be Examined SheB Circumferenthl tveMs Examhethn Methab Volumetric TaMe 2 INSERVICE INSPBCIION PROGRAM CRASS 2 COMPONENIS Examination Rcquiremerrts for Tturd inspection interval 100%of each weM to be examhted (applies only to wekh at gross structural discontintuties). For mukiple vesseh of sinular design sILc and setvioe, examinations may be limited to one vesseL Examhetion Techtuque/Examination Area Comments The wekb will be examined whh UT.Qg>10 R 2e (/)~R((O t3 H 0 CIM CA C)30 GA CL10 C B Ch1 I C220 GB C2.21 C2.22 GB Heal Circumferential Wekls Volumetric Nouks in Vesseh xl/2-N/A Inch Nonunal Thickness Noule toSheB (or Heal)Weld Nozzks Withota Reinforcing PLste in Yeech>I/2.loch Nomirel Thkkness Noule.to.SheB (or Head)WeM Surface and Volumetric Naze Inside Radius Section Volumetric Tubesheet.toSheB WeM Volumeuie 100%of each head-toaheB weM to be cxamineL for mukiple vcsseb of simBar design size and service, xaninations may be limited to one vesseL 100%of each weM to be cxaminecL For mukfpk vcsseh of siuuhr design she and servke, eanhations ney be Bmited to one vesseL AB nouks to be seketed at terndnal ends of piping runs sekcted for examination under Categories C F.l and C.F-2.100%of each weM to be exatrdnccL Manways and lend hoks cxcludeL For muhple vesseh of simihr design, she, and servke, examinations may be limited to one vesseL 100%of each area to be xataunetL Manways and hand holes are cxduded.For muMple vessels of similar design, she, and service, examinations ney be limited to one vesseL The welds wiB be exanuncd with UT.No Code rcquircd Nouks M Vcsseh aI/2.loch Nominal Thickness Nozzk-toSheB (or Head)WeM at L E.GinnL lhe weMs will be examined with UT and MT or PT as appbcabk.The noule inside ralius section will be examined with UT.H 0 (/)X Erf g H XO OH~U 0QH O (I)I tO O (2')Z L kf)H 1-3'E)g 0 4 A e'Q z OX X U'P H'El N 0'E)C230 GB C291 GB Nouks with Reinforcing Phtcin Vcsseh>I/2 inch Nominal Thkkncss Rehtforcing Phte Wekh Surhee Surface to Naze tk Vessel AB nonks at terminal ends of piping runs.For rntdtiple vesseb of simBar design, size, and service, cxanhetions may be limed to one vesseL See C291, C232, C283 The reinforcing plate weMs wiB be cxandned whh PT or MT as a pplieab'k.(I)(B 0 0 0 i Tabb 2 INSERVKX INSPECIION PROGRAM CLASS 2 COMPONEÃIS (Conc'd)Item Ntx Examination Category Components and Pans To be Examined Examinarion Metbxh Examination Reciuirements for'third Inspection Intetva)Examination Technhiue/ExaminatIon Area Comments PRESSURE VESSEIS Cont'd CL32 GB Nozzle.ToSheB (or Head)N/A WeMs When Inside of Vessel is Accessible AB nozzks at terminal ends of piping runs.For muhipk vesseb of simBar design, sbe, and savice, xamlnations may be limbed to one vesseL The Inside of vessel is not accessible, perfornung CL33 Instead.0 C233 C B C3.10 GC CC.IO GD Cy.IO GH Cy20 GH Nozzk-ToShcB (or Head)Visual (Vl'2)Wclds I Vhen Inside of Vessel is Inaeeessibk Integrally Welded At.tachments Prcssure.Raaining Robing N/A>2 Inches in Diameter Pressure.Recaining Compo-Visual (VT.2)Pressure Retaining Compo Visual (VT 2)nents AB nozzks at terminal erxis of piphtg fur@.For muhiple vcsseb of simBar design, size, and servke, examinations cnay be lirnitcd to one vesseL I 0095 ol each weM to be examineL Anachmencs whose base materhl is 3/4 Inch or greater co be sekaeL Where multlpk vesseh are provided with a number of similar attachments, the anachments may be discributed among the vesseh.For muhiple vesseh of sfnular design and savice, examinations may be Bmhcd to one vesseL AB pressure-rccaining boundaries for vesseb co be examined during system pressure test.Examinarions to be performed in aeeordance whh IWG522l for each inspeaion pericxL AB pressure.retaining boundaries for vesseh to be examined during system hydroscack test or ahernarively to Code Case NAPB.Examinations to be performed in accordance with IWC.522 I/5222 at or near the end ot each inspeaion intaval or during same inspection periods of each htetval VT examfnarions will be performed In accordance whh IWB-524L B>>reluhcd component to be examined during system leakage test.The weMed attachments will be examined with MT or PT as applicable. No pressure.rccaining vessel bohing>2 Inches in diameter at IL E.Cinna.VT examinations wiB be performed in accordance whh IWA 5240.VT examinations wiB be performed in accordance with IWA.52C0.H 0 (/)X k Er)0 cf)K (=)M)<o(/)I~I~cf)O~tO Q~tDH (" I-I g 0 Q H C d A X Erf U~H 0'd m 'h iten No.PIPING C3.20 CC Components and Pats To be Examined lntegraBy WeMcd Auachmeas Table 2 NSERVVICE DISPECIION PROGRAM 42/ASS 2 COMPONENIS (Cont'd)'Requirements for Third Inspection Interval IOOII of each weM to be examiners Attachments whose base materbl b 3/4 bch or greater to be selected.Selection Bmftcd to those componems selected under Exanunatbn Categories GF.I and GF.2.Examination Techruque/Examfnatbn Area Conunents'Ihe wekb wiB be examined with MT or PT as applicable. Qg>10 CCMg CCCC PSYCH M RK O H 0 C4.20 GD C5.10 C F-I C5.11 C5.12 GF.I C5.20 GF I C52I Pressure Retaining Boking>2 Inches in Diameter Pipbg WeMs M Austenitic Stainless Steel or High-ABoy pi phtg a3/B.inch hommal WaB TIuckness for Piping>4 NPS, Circumferential Piping Wekb in AusteniYie Stainless Steel or High-Alby Piping a3/8 loch Nominal WaB Thickness for Piping>4 NPS, Lon.gitudinal Piping WeMs in Austenftie Stainless Steel or High.Alby Piping al/S.loch Nominal Wall Thickness for Piping a2 NPS and s4 NPS, Circumferential Surface and Volumetric Surface and Volumetric No prcssure.retaining baking>2 Inches in diameer at R.E.Ginna.No bngkudfnal weMs of tlus hen number at R.E.Ging.IBID of each circumfcrcntbl weM rcquiYing examination. See Note I at end of Table 2 for selection criterh.'Ihe weMs will be examined with UT and PT.1009k of each cueumferential wekl requiting The welds will be examined whh UT and PT.emnfnatbn. See Note I at end of Table 2 for sebction crftcriL 0 M g H XO OH~U 0u)H O M I+kf3O+tO H MHg R'Ef N 0 CQ Q H C IEf OW ra a Q H d f33 0 W L C522 GF.I C520 CF-I C5.40 OF-I C5.41 Piping WeMs in AusterdYic caaudess Steel or High.Alby Piping al/5-Inch Nominal WaB Thickness for Piping a2 NPS and s4 NPS, Iongkudinal Socket WeMs in AusteniYie Stalnbss Steel or High-Alby Piping Pipe Branch Connections h Austenftb Stairdcss Steel or High-Alby Piping a2 NPS, Circumferential IOOIk ol each weld requiring examination. See Note I at end of Table 2 for sebction crucrh.100%of each circumferential weM requiYing examinatbn. See Note I at end of Table 2 for selection criteri.No bngitudinal weMs of this iten number at R.E.Ging.The welds will be<<xanined with PT.0 M 8 0 0 g'P N item Ntx Examhation Category PIPING cont'd CS.c2 GF.I Com ponents and Pans To be Examhed Pipe Branch Connections h AustcniYie Stainless Steel or High-Alby Ptpmg s2 N PS, lnnghudhal Examhation Methods N/A Tsbk 2 CHSERVICE INSPECllON PROCRAM flASS 2 COMPONENIS (Coca'd)Examhation Requirements for Ttdrd Inspection Interval Examination Technique/Examination Area Comments No bnghudhal welds of this item nmnber at iL E.G irma.Ag>IO H 0 Cx50 GF-2 CSSI C552 C5.60 C F.2 CSAiI C5.62 C5.70 GF-2 Cx80 GF-2 CRSI Piping Wefds h Carbon or Inw.Alby Steel s3/8.Inch Nominal IVaB Tldckness for Piping>4 N PS, Circumferential and Longitudhal Piping Wews in Guten or Inw.ABoy Steel>I/5-Inch Nominal Wall lhickncsu for Piping s2 NPS and irC NPS, Cfrcumfcrenriai and Longitudinal Socket WelCh h Cmbon or Low&by Steel Pipe Branch Connections in Carbon or lnw.Alby Steel s2 NPS, Circumferential Surface and Volumetric N/A Surface 100%of each ciicumferenrial and 2.5c of each bnghudhaI weM requhing cxanunatbn. Sce Note 2 at end of Tabk 2 for sekccion criteria.In addition, 10Nli of the mah steam and main fecdwater wclds bested outside containmcnc and traveling safety areas shall be examined per Technhd SpcriTicacions. 100%of each eireumferential weM requiiriing exsnunation. See Noce 2 at end of Table 2 Ior sekeuon criteria.lie wews wiB be examhed whh UT and MT.No carbon or baby steel nonexempt wews in thh category at IL E.Ginns.No carbon or bwatby steel nonexempt welds h thk category at R.E.Cinns.The welds vriB be examined with MT.H 0 f/)ixi H Ex)0 cf)H Utf)~~o v)I+)w cf)O (2')<(/)~g Q H R E)OX D R wa Q H'E)fy)0 I m C5$2 GF.I Pipe Branch Connections Ill Csfboii of LDW.ABoy Steel s2 NPS, Inngitudhal No bngitudhal welds of thb item number at IL E.CinnL g 0 C720 GH Pressure Reuuning Compo Visual (VT.2)Pressure.Retaining Compo.Visual (Vl'-2)All pressure.retahhg boundaries for piping co be exandned during system prcssure test.Examination to be performed in accordance whh IVc&5221 for each hspcction pcrkxL AB pressure.retching boundaries for piping to be cxandned during system hydrostatic test or akcrnarivcfy co Code Case NA98.Examha.tion to be performed in accordance wkh IN'O522I/5222 at or near the cnd of each hspeetion Interval or during same hspection periods of each htcrvaL VT examhatbns mll be periormed in aceordancc with IWA.5240.VT exmninstions wBI be performed in accordance with RVA.5240.0 (I)(B 0 0 Item No.PUMPS Cga GC Components and Parts To be Examined integral/Wehkd At.N/h cachmcncs Tabk 2!NSEINICE INSPECIION PROGRAM t2ASS 2 COMPONDPIS (Cosa'd)Exanutioa Rccluftements for Third Inspccrion Interval Exination Tcchahlue/Examinarion Area Cnuaents 10096 of each wehf to be~hnachmems whose base materiai is 3/4 inch or greater to be sekctoh Sekction limited to those components sekctcd under Examination Category GG.No pumps meet this criteria at R.E.Glans.Qg>10 R R (I)Q ECCL Q~)H (/)C K O C430 GD Pressure.Retaining Bohing>2 Inches In Diameter N/A No prcssure.retaining pump bohing>2 Inches in diameter at L E.Ginna.C6.10 CG CPA'N Pressure.Reta'uung Welds in Pump Casings N/A Pressure.Retaining Compo.ncnts Visual (Vl'-2)Pressure Retaining Compo Vimal (VT-2)nents hll pressure-training boundaries for pumps to be examined during pressure test.Exanunat ion to be pcriormcd in accordance with IWC-5221 for each Inspecrioa perioh All pressure retainiag boundaries for pumps co be exanuned during system hydrosratk test or alternatively to Code Case NAPIL Examination to be performed in accordance with IVT S221/5222 at or near the end of each Inspccrion huesvaI or during same in.spccrion periods of each intcrvah No pressure-retaining pump weMs at L y Ginna VT exanunations will be pcriormcd h accordance with IWA.5240.VT examinatkns will be performed in accordance with IWAS240.0 (/)g H td O O~~U 0cf)H 0 O)I gtf)O~tO Q~cg)H 0 Q H X U~H'T)())0 XI d n 0 Item No.Examinarion Category VALVES C3AO GC Components and Parts To be Examined Integral/Wchkd At.Surface tat hments Tabk 2 NSSERVIcX INSPECIION PROGRAM CLASS 2 COMPONENIS (Cont'd)Examhation Requirements for lhhd inspection htenral 100%of each weM to be examh<<L Auachments whose base material is 3/i hch of greater to be sekcted.Sckcthn limbed to those components seketed under Exandnatkn Category GG.Examhation Technique/Examination Area Comments The welds wBI be examined with MT or PT as applicable. ZC(C'0 CIAO GD Cy.70 GH CTAO GH Pressure-Rctahing Bolting>2 Inches in Nuneter Pressure.Retahing WcMs h Vahre Bodies Pressure Retaining Compo.ncnts Visual (VT.2)Prcssure-Retaining Compo.Visual (VT.2)All pressure.retahhg boundaries for valves to be examined during system prcssure test.Examination to be performed h accordance whh IWG5221 for each ins pectbn pcriocL AII pressure.retatnmg boundaries for valves to be examined during system hydrostatic test or ahematively to Code Case NA9K Examina.thn to be performed in accordance whh IIVG5221/5222 at or near the end of each ins pection imerval or during same hs pret ion period of each int<<vaL No pressure-retainhg bohing>2 hches h diameter at L E.Ghna.No pressure.retaining wcids h valve bodies at L E.Ginna.VT examinations will be performed in accordance with IWA.524L VT examinations will be perform<<l in accordance with IWA 5240.H 0 0)g H (x)0 o~~+QH Utf)~<o(f)I'd gtf)O LO Q~tO H (/)H~0 Q H a C'E)OX wa~H 0 Z TaMe 2 (I)The weMs sekctcd for examination shall Include 7.5%, but nix kss than 28 weMs, of all austeniuc tainless steel or highutBoy weMs not<<xemptcd by IWG1220.(Some weMs noc exempted by ttus Case are not required to be nondesuuctively examined per Examination Category GF.I.These welds, however, shall be included ln the total weM count to which the 7.5qb sampling rate is applied.)The cxanunatlons shaB be distriliuted as foUows: O (a)the exanunations shall be dhtributed among the Qass 2 systems prorated, to the degree practicable, on the number of nonexempt austeniYie stainkss steel or high.alba weMs in each system (Le., if a system contains 30qb of the nonexempt weMs, then 30%of the nondtcructive examhtations requhed by Examination Category GF.I shouM be performed on that system);(b)within a system, the examinations shall be distributed among tcrtrdnai ends[see hote (3))and structural discontinuiYies [see Noce (4))prorated, to the degree practicable, on the number of nonexempt ternunal ends and structmul disconthtuhies in that system;and (2)(3)(c)whhht each system, examhtations shall be distnl>utcd bctwcen hne skcs prorated to the degree practicable. The weMs sekcted for exambation shall hclude 7.5%, but not less than 28 weMs, of all carbon or bw~weMs not exempccd by IWC 1220.(Some weMs not cxemptcd by tids Case are noc reqtdrcd to be nondestructively examine!per Examhtation Category GF.2.These weMs, however, shall be Included ln the toad weM comu to which the 7.596 sampling rate is applied.)The examinations shall be distributed as folbwst (a)the examinations shaB be dimibutcd among the CLsss 2 systems prorate, to the degree practicable, on the number of nonexempt ear[en or hiwaBoy weMs in each system (Le., if a system conttdns 30%of the nonexempt weMs, then 30%of the nondestructive examinations required by Exanunation Category GF-2 shouM be performed on that system);(b)within a system, the exambtations (hall be distnliuted among terminal ends[see Note (3))and structural discontinuitks (see Ncce (<))prorated, to the degree practicable, on the number of nonexempt ternunal ends and structural discontinuhks in that system;and (e)within each system, exandnadons shall be distributed between line sizes prorated to the degree practkabk.(d)Only those weMs showing reportable preservice transverse indkations need to be examined for transverse rellectois. Terminal Ends (TE)are defined M Table I Notes, note number l.Structural DiseontkuiYies (SD)are defined in Table I Noccs, note number 2.The foBowfng wcM types are identified M Supplement I to Appendix B, the Program PLtn.'E A Terminal End at a Piping Anchor'K B Terminal End at a Branch Connection

• TE.P Temunal End at a Pump Connection

~TE.V Temunal End at a Vessel Connection ~SD Suuctural Discontinuhy PP Pipe to Pipe Butt WeM'EAld Longitudinal Seam WeM Note: When more than one weM rype k app!ieable, the more restrktive (i.e.TE)is utilized.H 0 (f)g H[x[O o~~cf)H a~<+O[f)['d+cf)O td tf)~R 0 g 0 Q H I c([O[x)XU~H'd N 0 L 0 r.0 0 t v g W I Item No.The ASVE Section XI Rem No.and CateEory of the component are listed in these columns.Components and Pans To be Examined Each type of examination area is listed in tide column.The NDE method required to satisfy Code requirements is listed in this column.SNSERVICE INSPECTION PROGRAM CXXK (IJISS Examination Requirements for Third Inspection Imetvaf This column provides Information regarding the number andfor percent of examinations required to be performed for the Inspection Intervah Examination Technique/Examfnadon Area Commems Tlds column provides Information spcciTic to examination techniques, examination areas, or couuucnts. RCCV~~gH V)NK 0 H 0 0 M X H WO o OH~tEr H O M I~tdy O tEs t3>u)H~He Q H I O W Erf U d fXI 0 d 0 Ct 0 ~It Tabk 3 item Ntx Examlnarion Category CLASS 3 COMPONENTS Components and Pans To be Examined Exanunation Methods Examination Requirements for Third Ins pcctlotl lluelval Examination Tcchrdqaelgxamlnarion Area Comments RCC~O b3 Dl.10 D A D2.10 D-8 D3.10 DC D 1 20 IM throagh DIM D2.20 D 3 though D2X4 D3.20 DC through D3.60 Integral Attachments of Suppons and Restraints, Hydraulic Snubbers, Spring, Consamt Load, and Shock Absorbers Visual (VTQ)prcssure.Retaining Compo Visual (VT 2)All components to be examined daring system pressure or system hydrostatic test as defined by IWD-2500 I Table Descriptions. Examfnarion to be performed in aeeordanee INq)-5221 for each inspection period and performed once each interval in accordance whh IWD.5223.AII required anachments to be examined daring each inspection Interval as defined by IIVD.2500 I Tabk Deseriptions. For multiple components in a system of sin8ar design, fusion, and service, the integral attachment of only one of the muhpk components shall be examined.1he ktegral anachments selected shall correspond to those support components selected for cxandnarion in actor.dance with IIVF-2510(b). VT exandnations will be performed in aceordanee with IWA.5240.H 0 (I)g H WO OH~0 H Ut()~>o(f)I'E)+tg)O~'))-3 L t()H d Q H C'0 OX 0 R wa 0 r m Q 0 II I I'~N~h V<<->~~ll r1~~ itemÃo.Examinsuon Category The ARVE Section XI Item No.and Category of the component are hsted in these colmnns.Components and Parts To be Examined Each type of examination area is hstcd in this colmnn.The IIDE method required to satisfy Code rerfufrements is listed in tlds column.~n Repurements for Thhd Inspection interval This column provides Information regarding the number and/or percent of xaminadons roiuired to be performed for the Inspection Intervah Exandnation Technhiuef Examination Area Crnmerus This column provides Information spceiTic to examination tcchnhiues, cxaminauon ~of commentn Q g PN RRMQ ECCL A H 0 H 0 CQ g H WO o OH U'LO H O M I d Id'+LOQ>tg)H MH~XI 0 CQ Q R'd C M O trf eU Ef%0 d M ID 0 I 0 BNSERVICE INSPECI)N PROGRAM C1JISS I, CJASS 2, AND (1ASS 3 COMPONENT SUPPORTS item Ntx Components and Parts To be Examined Examination Requirements for Third Inspection Interval CIASS I AND 3 IWF COMPONENIS SUPPORTS FROM 1990 TO 1993 OUTAGE USING IWF 1986 Code PIATE AND SHEIL TYPE SUPPOR UNEAR TYPE SUPPORTS AND COMPONENT STANDARD SUPPORTS xamlnadon Tcchrdqtu JXamfnatmn Area Conunents Qg>10 R R (I)0 R(((I)O 0 F1.10 F.A though FI.40 F2.)0 F-B though F2.40 F3.10 F<through FATSO Mechanical Connections to Pressure-Rcaunfng Com po-nents and BuiMing Structure; WeM Conner.tions to BuiMing Structure; WeM and Mechanical Connccdons at Interme.rUate Joints ln Muftf-connectcd Integral and Nonintegral Supports;and Component Dlspktcement Settings of Guides and Stops, Misalignment of Supports, Assembly ol Su.pport Items;Spring Type Supports;Comtant Load Type Suppotts;Shock Absorbers; Hydraulic Type 5nubbers Visual (VT4)Component supports to be selected for examlnadon are the supports of the nonexempc (2ass I, 2, and 3 components schedued to be xaamfnerL Examination bou darles established iu secordam wkh IWF-130th Examinations may be performed during normal system operation or plant out.ages Funcuonal testing of snubber type support components shaB be performed in accordance with Teciudcal Specifications and ln accordance with requirements of this program.Item No.Components 8 Parts to be Examined Examination Method Examination Requirement for the Third interval Examination Techniqucrgxamfnation Area Comments CLASS I.2.AND 3 IWF COMPONENT SUPPORTS FROM 1994 TO 1999, USING CODE CASE N 491 AND IWF 1986 CODE H 0 (I)L H XO O~~a 0tf)H O (I)I tf)O>tf)~g 0 Q H ('d OX wa~H'Ef W 0'd FI.10 F-A Class I piping supports Visual (VT 3)25%of Class I suppotts Functional testing of snubber rype support components shall be performed in accordance with Technical S pccilkations and in accordance with requirements of this program.F 1 20 F.A Class 2 piping supports Visual (VTB)1546 of Class 2 supports F1 20 F-A Class 3 piping supports Visual (VT 3)I0%of aass 3 supports FI 40 FA Chss I, 2, 5 3 supports Visual (VT4)10ryrtr except for multiple other than piping supports components.(D n V 0 QUALITY ASSURANCE MANUAL GINNA STATION I Section 5 EFFECTIVE DATE: REV.'AGE 3 1 of 96 December 31, 1993 ROCHESTER GAS&ELECTRIC CORPORATION SIGNATURE DATE TITLE APPENDIX B R.E.GINNA NUCLEAR POWER'PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL~LINE LIST PREPARED BY QUAUTY ASSURANCE REVIEW: APPROVE BY: (Z-Z-)1.0 General The following line list was developed utilizing ASME Section XI Rules and Criteria to identify all Class 1, 2&3 exempt and non-exempt items.This list further identifies non-exempt piping lines and components,,type of nondestructive examination requirements as well as providing a line description. Visual examination for leakage (VT-2)boundaries are not addressed in this Section, but shall be administratively confirmed by the responsible Rochester Gas&Electric organization before implementation. The line list is grouped by P&ID Drawing Number, Class, System, and Component Type.This information appears on each page of the Line List on the upper left hand corner.The Component Type description defines the information as either components or piping.On the individual pages, unique line numbers were identified that correspond to a description of a particular segment.Other relative information listed within each page of the line list includes ISI Figure Numbers, material type, pipe size, wall thickness, applicable code exemption basis, typical examination (NDE)methods, applicable operating pressure and temperature, as well as component insulation information. The revision status of"R" shall indicate that a change has occurred anywhere horizontally for the line number in question.A Revision Status of"A" indicates a new entry was made.A visual representation of the line number can be seen on the corresponding P&ID contained within Section 3.Lines 1" and under are not shown.However, they are identified in the line list data base. R E.CINNA NUCLEAR POWER PIANT Inservke~n Boandery LIne Lbt Thhd Iaspecaoa Interval P&IDNo r 33013-1231 Chss r 2 System: MAIN SIEAM Comp Typm COMPONENIS RG&E IIne No.EMSOIA EMSOI B 151 Size~Fi.MstrL~la.B-l Bl OAN OAXXI OAR 0.000 SUR/VOL 715 505-SIErW CENERATOR* SUR/VOL 715 505~STEM GENERATOR K Thkns Exemption NDE~la.Bssa Method Po~Tern ln?Lbe deseri rernsrhs Revised R 1 I/91 R I I/91 O H 0 H 0 M XH WO+LI?H V H LIyg gOM I HeO M LI)H tdy Q 0 H 2g t C L E.GINNA NUCLEAR POWER PIANT Inservise Exanrination BsnnnhnY Une Ust Thini I spection Interval PAID No t 33013 1231 (2ass t 2 S)stern t MAIN STEAM Comp T)Tres PIPINC H 0 RCAE line No.CEbert line No.ISI Size Thhns~F1.MrnrI~in.~In.NDE Methort Po~Tern Int line deseri'ernarhr 30A-M$600-IA 30B.M$600-1B 6A MSGR'.I A 6h-M$600 I B 6B-M$600.I A 6B-MSSS.I B 6GM$600.1A 6OM$600-I B 6D.M$600-1A 6D.M$600 I B 6LM$600 IA 6LM$600 I B 6EM$6N.IA 6F.M$600-1B 6G-~I A 6G.M$600.I B 3A.M$6N.I A 3A-M$80 I B 2A.M$60alh 2A.MS600-1B ISA-M$600.1h 1$A-M$600.1B I SB.M$60a lb 1$B-M$600.1B ISC M$600-Ih MS-100 MS-200 MS.100 MS300 M$300 MS 120 MS300 MS300 MS300 MS300 M$300 MS300 MS300 MS300 M$300 M$300 MS300 MS.1000 SMS-1001 MS 1000 SMS-1001 MS.1000 SM$1001 MS-1000 SMS 1001 MS 1000 SM$1001 MS-1000 SMS-1001 MS.1000 SMS-1001 MS.1000 SKS.1001 MS-1000 SM$1001 MS-1000 SMS 1001 MS-1000 B3 33 B-9A B.IO B-9h B-IO B.9h B 10 B-9h B.IO B-9h B.IO*B.9A B.IO B-9A B-IO B9A B 10 B.9A B 10 B-9 B.IO B-9h B3 BB A115 A11$A106 A106 A106 h106 h106 hl06 h106 hl06 h 106 A106 A106 A106 A106 A106 A106 A106 A106 A106 A106 30AO MSO 30Am l~6Am a 432 6AO 0.432 6Am a 432 6.00 0.432 MO 0.432 6.00 0 432 6Am 0 432 MO a432 MO a432 MO 0.432 6Am 0 432 6AO 0.432 M0 a 432 6'432 3'300 3'300 2AXt OANO 2Am a000 IM 0.145 IM 0.145 1$0 0.147 180 OAXN 150 0.000 IWC.1222(A) IViZ 1222(A)IWC.1222(A) IS&1222(A) IWC.1222(A) IWC 1222(A)IWC 1222(A)IWC 1222(A)IWC 1222(A)SUR/VOL SUR/VOL BUR/VOL SUR/VOL SVR/VOL SUR/VOL SVR/VOL SUR/VOL SUR/VOL SUR/VOL SVR/VOL SVR/VOL SUR/VOL SUR/VOL BUR/VOL SUR/VOI 715 505 715 505 715 505 715 505 715 505 715 505 715 505 715 50$715 505 715 505 715 505 715 505 715 505 715 505 715 505 715 505 715 505 715$0$715 505 Y 715$05 Y 715$05 Y 5/G IA 10 VALVE 3517.5/G I B TO VALVE 3516.30'S PIPE TO VALVE 3505A.30'S PIPE 10 VALVE 3504A.3(P MS PIPE 10 VALVE 3411.30'S PIPE 10 VALVE 3410.3(7 MS PIPE TO VALVE 3509.30'S PIPE TO VALVE 3508.3(7 MS PIPE 10 VALVE 3511.30'S PIPE TO VALVE 3510.30'S PIPE TO VALVE 3513.30'S PIPE 10 VALVE 3512.30'S PIPE TO VALVE 3515.30'S PIPE 10 VALVE 3514.30'S PIPE 10 6 X 2 REDUCKL 30'S PIPE 10 6 X 2 REDUCEII 30 MS PIPE 10 VALVE 3615 (3517 BYPASS).30'S PIPE TO VALVE 3614 (3516 BYPASS).6G-M$600.1 A TO VALVE 3521.6G-MLS I B TO VALVE 3520.30'S PIPE 10 VALVE 3455 6A.MSCi00 I B TO VALVE 3504C.6A.MS600 Ih 10 VALVE 3505C.30'S PIPE TO VALVE 3$0a 30'S PIPE TO VALVE 3503.R 11/91 R I I/91 R I I/91 R 11/91 R I I/9I R 11/91 R ll/91 R 11/91 R 11/91 R 11/91 h 11/91 A 11/91 R 11/91 R 06/93 R 06/93 H 0 (/)XH td 0+QH H IO g O (/l H'N 0 g'LO H 0 H g 50 e" Q OX 0 (/l (()0 Ft 0 0 lf I I'l I t I~ lL E.GINNA NUCLEAR POWER PIANT laserioe Examhstha Boundary une urt Tldrd Iaspecdoa Interval RGRE u N GBbert IIne No.PdrID No: 33013 123 I Chss: 3 System: MAIN SlEAM Comp Type: COMPONENIS ISI Size~FI.Metrl.~h.Twas Rremptioa NDE~in.Basis Metlrod Po~Tern In?une deseri'ennsrlrs NIA OAR OAXO NO IWA;VTD TURBINE DMVEN AFW PUMP TURBINE.Robed A I UPI O H 0 g H 0 M X H XO+LO H r H tO g 0 U)(HIDE%0~eH o H 2g 5%g H M ID 0 Pe 0 0 R.E.GINNA NUCLEAR POWER PIANT nsservire Examinadon Boundary Une Ust Third Inspeenon Interval PSID No t 33013-1231 Chtss.: 3 System.s MAIN STEAM Comp Type: PIPING ROSE Une No.GUbert Une ho.SWRI Une No.ISI Size~Fi.MatrL~in.NDE Method Po T~em In?Une deseri'/remarks 30A.M$600 I 30B.M$6fO I 8A-MV-150 I 6A-M$600 I 6B.M$6M-I 6GMS600 I 4A-MV.150-1 3A.M$600 I 3B-M$600.1 3C M$60al ISA.M$6N I I 8B-MS600.1 ISGM$600 I I SD.MSCi00-1 MS.120 MS.120 MS.120 MS-120 M$120 B.9A hll5 8 10 hl15 N/h G32 A106 G32 A106 G32 h106 N/A G32 h106 B.9h Al 15 8 10 A115 G32 A106 G32 h106 B-9A hl I 5 B.IO A115 Ba00 3aoo&00&00&00 6lO 4AO&00&00&00 MO 180 150 MO IWD.1220.1 IWD-1220.1 IWD-1220.1 IWD 1220.1 IWD-1220.1 IWD 1220.1 IWD 1220.1 IWD.1220.1 l~NO IWA, 1~NO IWA OAKO NO IWA OA32 OA32 F32 a000 IL216 (L216 tL216 ale 0.145 0.145 IL145 715 505 Y 715 505 Y 1085 508 Y 1085 508 Y 1085 508 Y 1085 508 715 505 715 505 lOSS 508 1085 508 715 505 715 505 VALVE 3517'IO REDUCER AT VALVE 3519.VALVE 3516 TO REDUCER AT VALVE 351L AFW PUMP TURBINE EXH TO ATMOS.3505A TO 3505K 35IMA TO 3504 IL 6A 8: 6B IO 3A.AUX FW PUMP TURBINE QUENCH TANK TO BA.6C TO AUX FW PUMP TUBELIKE VALVE 3615 TO 30A.MSCi00.1.VALVE 3614'IO 30B-M$600.1.3505C TO 6A 350K'IO 6K 30A.M$600 I TO VALVE 8527.308 M$6M I TO VALVE S52L A 06/93 h 06/93 A 11/91 R I I/91 A I I/9I R 11/91 A 06/93 A 06/93 R I I/91 R I I/91 A 06/93 A Odr/93 0 Vl g H WO t0+LD H H ID~O V)W L u)n vX H to tg gtDH 0 H Q QO g H 0 IL E.GINNA NUCLEAR POWER PLANT Iaservke Exautlnathn Boundary Une Ust Third InspecUon Interval PAID No..: 33013.1231 I2ass t HE.2 System.t MAIN STEAM Comp Type: HF PIPINGt APP.B RUBE u N SWRI Une No.ISI~Fi.MatrL Po~Tern tn?Une deseri remaAs O H 0 30A.M$600.1A 30B.M$600 IB 6A M$600 lh 6A.M$600 I B 6B.M$600.I A 6B-M$600 I B 6C M$600 IA 6GM$600 IB 6D-M$600.IA 6D.MS@00 I B 6E.M$400-1A 6E-M$600-I B 6F M$600 IA 6EM$600 I B 6G M$600 IA 6G-M$600.1 B MS 100 MS 200 MS 100 M$300 MS300 MS.200 MS300 M$300 MS300 MS300 M$300 M$300 MS300 MS300 MS 1000 SMS 1001 MS.1000 SMS 1001 MS.1000 SMS 1001 MS.1000 SMS.1001 MS.1000 SMS-1001 MS-1000 SMS 1001~MS.1000 SMS.I OUI SMS.1001 HE.I h115 HE.2A AIIS HE-IA A106 HE.2 hl06 HE-IA A106 HE.2 hl06 HF Ih h106 HE.2 A106 HE.IA A106 HE 2 A106 HE.IA A106 HE.2 A106 HE.IA h105 HE.2 AI06 HE-IA A106 HE.2 A106 3MO 1350 BMO 1350 6.00 OA32 6.00 OA32 6.00 OA32 AS OA32 AS 0.432 600 OA32 6AO OA32 600 sL 432 6AS OA32 600 OA32 600 tL432 6AO OA32 6'A32 650 OA32 SUR/VOL SUR/VOL SUR/VOL SUR/VOL SUR/VOL SUB/VOL SUR/VOL SUR/VOL SUR/VOL SUR/VOL SUR/VOL SUR/VOL SUR/VOL SUR/VOL SUB/VOL SUR/VOL 715 505 715 505 715 505 715 505 715 505 715 505 715 505 7 IS 505 715 505 715 505 715 505 715 505 715 505 715 505 715 505 715 505 5/G lb TO VALVE 3517.5/G IB TO VALVE 3516.30'S PIPE TO VALVE 3505A.30'S PIPE'IO VALVE 35IMA.3IP MS PIPE TO VALVE 3411.30'S PIPE TO VALVE 3410.RP MS PIPE TO VALVE 3509.3ty MS PIPE'10 VALVE 350IL 30'S PIPE TO VALVE 3511.30'S PIPE 10 VALVE 351(L 30'S PIPE 10 VALVE 3513.30'S PIPE TO VALVE 3512.30'S PIPE 10 VALVE 3515.30'S PIPE TO VALVE 3514 Ssy MS PIPE 10 VALVE 3521.30'S PIPE TO VALVE 3520.R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 H 0 UI g H td 0+'4 H O T/I H IEI g to 0+u)H ()H 4 OW R5 g H M 8 0 0 R t'I t j Wt IL E.GINNA NUCLEAR POWER PIANT Inrertdee Ezamhathn Boundary Lhe Ilrt'IIdrd hpection Interval PAID Na.t 33013.1231 Char t HE3 S7rtem t MALI STEAM Comp Type: HE-PIPING: APP-B O H 0 RUTE lhe No.30A-MS600 I 30B-MS600.1 0Bbert Une No.ISI~Pi.MatrL HE.IA AIIS HE-2 A115 3IL00 I~30.00 I~SUR/VOL SUR/VOL 715 505 Y 715 505 Y VALVE 3517 TO REDUCER AT VALVE 3519.VALVE 3516 TO REDUCER AT VALVE 351L Size Thlarr Exemption NDE~h.~h.Baria Metlrod Po~Tern In?Lhe dereri'ernaritr Rcvbed A 06/93 A 06/93 H 0 M g H WO+tO H H H3 g O EII HIE?O+II)H tO Q 0 H g OX xa g H 0 IL E.GINNA NUCLEAR POWER PIANT Insetvloe Examination Boaahsy Line List TMnI Inspeenon Interval P&ID No t 33013.1232 Qass..: HBO System..: MAIN STEAM Comp Type: HE-PIPINGt APP-B RG&E Line No.151~FI.Matrl.Size TMnts Exam pdon NDE~in.~in.Po T~ern In7 Une desert rernarits O H 0)36-MS600.1 2%A.MS600 lh 2kB.MS600.1h 12A MS600-IA 12A.MS600-13 MS-1000 MS~1002 MS-1003 HE.7 HE.7A HE 7h HE-7 HE.7 3600 OAXO 24AO 0 AID 24AO OANO 12AS OAXO 12'X000 SUB/VOL BUR/VOL SUR/VOL SUB/VOL SUR/VOL 715 505 Y 715 505 Y 30'36'EDUCERS TO END CAP.36'S PIPE TO VALVE 35%i.36'S PIPE TO VALVE 3545 36'S PIPE TQ VALVE 3532.36'S PIPE TO VALVE 3533.R 06/93 R I I/91 R I I/91 A 11/91 A I I/91 H Q Vl g H WO+tO H H II3 g+O Ea II3 O H~g LO H H g a m OX R5 g H 48 0'H~, I IL E.GINNA NUCLEAR POWER PLANT Inservice Ezarnlnatba Boundary lbe Ust Thhd Inspeeaoa Interval 9&ID No r 33013 1236-1 CLast: HFrQ System d FEEDWATER Comp Type: HE PIPING: APP.B O H 0 RG&8 Lbe No.GEbert Lbe Na ISI~Fi.MatrL Size Theat Exemptba NDE~b.~b.Basis Method Po T~em In?Lbe deseri'emarhs 20 FW.900.1 8 FW.900.1 FW-1001 FW.1081 HE6 HE@20.00 MXO BAI0 0.000 SUR/VOL SUR/VOL 715 505 715 505 Y TEE AT 3984&3985'TO TEE AT 3982&3983 R 06/93 Y 20-FW.900.1 TO VALVE 9507D.R 06/93 H 0 U)g H XA W+1OH H 113 g O E/3 (T((H~g L(3 A LL3 H p H'g g H 0-g 0 CQ M (D 0 0 0 I If f IL E.GINNA NUCLEAR POWER FIANT Inserriee Kxaminadon Botmdaty Une Ust Tldrd Insposdon Interval P&IDNo t 33013-1236.2 Chss..: 2 System.: FEEDWATER Comp Type: COMPONENTS H 0 RG&E Une No.EMS 0 I A EMS 01 3 GtTbett Line No.ISI Site~F1.MatrL~in.B.l Bl SUR/VOL SUR/VOL 715 505 715 505 TIIIS COMP ACCOUNTED FOR ON 33013-1231. R 06/93 THIS COMP ACCOUNTED FOR ON 33013-1231. R 06/93 Tithe Exempdon NDE~ln.Basis Method Po~Tern In?Une desert nlremarls Revised H 0 M L H WO+IOH H ID'OR HID~tD O'Q H t3 p H g 0 p 03 8 0 0 h V\ L F GINNA NUCLEAR POWER PIANT I nsesskc Examlhntion Bormday Une Ust%hd Issptcthn lntcsvnl 9&ID No-t 33013 1236-2 Cher: 2 System t FEEDWATKR Comp~t PIPING Gihtst Uhe No.151 She Thhns~Fi.Mhtsl.~Ih.~lh.NDE Method Po~Tern Ih?Uhe dtsefl ftrhhlhs 0 18A.FW.900 IA ISB-FW-900 18 1%A FW.KO.IA:- 148 FW-900.18 FW-1001 FW.1005 8 12 18.00 0.000 8-13 IS.00 0.000 B.l I A106 14AO 0.93S 8-13 A106 1%AS t1938 SUB/VOL SUR/VOL SUR/VOL SUR/VOL 715 505 715 MS S/GW TO 18 X 14 REDUCEL S/G.B TO 18 X 14 REDUCEL Y 18 X H REDUCER TO VALVE 3993.Y 18 X 14 REDUCER TO VALVE 3992.R 06/93 R 06/93 R 06/93 R 06/93 OM g H XO HIGH~LO Q gON~I HeO'LO tj~II)H H g 0 4 g H iB 0)8 0 po 0 0 E R.E.GINNA NUCLEAR POWER PIANT Insesvlee Euuainsdon OoussLssy LIne use Thlnl Iospee6oa Intesval 9&ID No: 33013.1236.2 CLsss.,: HE-2~m..: FEEDWATER Comp TYpe: HE.PIPING: APP-B RG&E Uoe Na 1%A-FW-900.1A 148-FW-900.1B FW.1001 FW.1005 ISI~Fi.Rsvp BB3 A106 HE-4 A106 SIxe Tldms Exempchn NDE 1%AS 0938 14AO 0.938 SUR/VOL 715 505 Y 18 X 14 REDUCER'8)VALVE 3993.SUR/VOL 715 505 Y 18 X 14 REDUCER TO VALVE 3992.Revisesl R 06/93 R 06/93 H 0 H 0 U)s2s H WO HQH~'LO Q@0M I H~OO F/1'LO Q g LO H 0 H g g 0 4Q g H g '1 J I K E GINNA NUCLEAR POWER PLANT Inservke Examinadon Bonndary Lbe Urt'IBIrd nspeenon Interval PLAID Ntx.s 33013.1236 2 aass: HFrQ~em.: FEEDWATER Comp TYPet HE PIPING: APP-B H 0 O RGdrE Une No.I IA.FW.900 1 1kB.FW-900-1 GBbert Une Na ISI~Fi.MatrL HE3 A106 A106 14AO 0.933 14.00 0.938 SUR/VOL SUR/VOL 7 IS 505 715 505 Y VALVE 3993 TO 20-FW.900 1.Y VALVE 3992 IO 20-FW-900.1. SIse Thkns Exempthn NDE~in.~in.Breds Method Po~Tern tnt Une deseri'emarks Robed A 06/93 A 06/93 0 M AH WO~I H LO H~IEI'g goV)I HIDE IO O'LO H 0 H g a g H 0 IL E.GINNA NUCLEAR POWER PIANT nssaviee~n Bonn5sry Une Ust Thni lnrpeerion Intavnl PAID No t 33013.1237 CLsss....: 2 Systan.: AUXIUARY FEEDWhmt Comp TYper PIPING O H 0 RGAE Lbe No.GBbat Line No.SWRI Une No.ISI Size~FI.MetrL~in.Po~Tern tnt Une rieseri ranerits BA.FW-900 IA 3A.FINO I B 3B-FW-9001 A 3B FWAXN.I B FW-1001 FW-1005 FW.1001 FW-1005 C I A A106 3AN CI C A106 3AN C.lb A106 3AN CI B h106 3AN 0200 IW&1222(h) 0300 IWC 1222(h)0300 IWC 1222(A)(X300 IWC 1222(h)715 505 Y 715 505 Y 715 505 Y 715 505 Y 4XNC TO e011, I eh-FW.900 lb.4NOD To e012, 1eB.FW-900-IIL 4N3 10 4$5, 1 eh.FW-900 Ih.4XH TO 4N6, 1eB-FW-900-IL R 06/93 R 06/93 R 06/93 R 06/93 H 0 (/)X H Ez(0 W+t()H V H t()g O 0)H t()g t()0 I()H p H Q h3 X CQ g H 0 0 "'Y I I I'I I I P<<4 II'I 4 h II I I!I I'I I 4 IV I L E.GINNA NUCLEAR POWER FIANT Inservioe Exnsrdnadon Boundnry Une Ust TIdrd Inspeenon Interval P&ID No,s 33013 1237 aass.s 3 Systesa.: AUXIUARY FEEDWATER Comp Type: COMPONENIS O H 0 RG&E Une No.08bers Une No.ISI~Fi.MatrL NDE Method Po~Tern Inl Lbe deseri'emnrks EAM I EAIO2A EAIO28 PAR)lh PAID I 8 PAIO3 N/h N/A N/h N/h N/A N/A OAXI 0.000 OAXI OAXO OAXI OANO SLOG 0.000 sLOO OAXO SHOO IX000 IWD 122D.I IWD.1220.1 IWD.1220.1 NO IWA NO IWA NO IWA 75 80 75 80 75 80 1250 100 1250 100 1250 100 TURBIN DRIVEN AFW PUMP LUBE OIL COOLEL AFW PUMP A LUBE OIL COOLEIL AFW PUMP B UJBE OIL COOLEL AIDUUARY FEEDWATER PUMP A.AIDUUARY FEEDWATKR PUMP L TURBIN DRIVEN AFW PUMP.A I I/PI A 11/91 A 11/91 A 11/91 A II/91 A 11/91 CI Ul g H X A+IO H H Ml g O Ul Io O H Ml g+u)H o H'g OX R5 Ol 8 n 0 0 C h N I l!II I II k 1 I IL E.G]NNA NUQEAR POWER PIANT Insetvke hm]nadon Bonndaty L]ne Ust IMtd Inspee6on]ntesva]PMD No: 33013.]237 Chss t 3 System: AV)QIJARY FEEDWATER Comp 1?pe: PIPING OUI>ett Line No.ISI S]ae Thkns~R.M nL Po T~em In?i)ne desesi'/semarks O H 0 4 SA-RV7-900.] 58-FW7-900-1 SGFW7-900 I 4A42hl 50]A 4A42hl50 18 LCD-)50.]C 4ASW.125-1 4ASW.]25 IA 4ASW.]2518 4ASW.]25 IC 3ACD-ISO.I A 3A42h]50.18 3A-RV7~1h 3A.FW7-900 ]8 38.FW7-900 I 3GRV7-900.1 3D FW7-%0-]3E FW7.900.1 3F FW7-900.1 3G.FW7-900 I 3H.FW7-900.1 3].FW7-900 I 3J.FW7 900 I 3K.FW7-XO I 2A FW74XO.]h 2A.RV7.900-18 28-FW7-900 ]A 28 RV7~18 2GFW7.%0.1A 2GRV7%0.18 2DRV7800.]h 2D FW?.900 18 MA.FW7-9001 I Jll.RV7-900.]h Mh.RV?-900-18 AFW-200 AFW-200 AFW~~SW-1520 SW-1520 SW.]520 AFW.]00~AFW-]00,4O AFW-200 AFW.]00 AFW.]00 AFW 100 AFW-100 Gl h]06 5.00 G]A A]06 SAO G]8 A]06 SAS G33 A53 4 AS G33 A53 4AO G]6 A53 4 AS C33 A53 4.00 C33 4AS C33 400 G16 4.00 G33 h53 3.00 G33 A53 3AS G]A A]06 3AS C.IF A]06>3.00 C.]D h106 3 AS G]E h]06 3.00 C)E 3.00 C ID A]06 SAS C I A]06 3AO C.IA A]06 3.00 C I h]06 3.00 Gl 3.00 C)8 h]05 3AS C IE 3AS C I C A]06 2.00 GIN A106 2AO C.]G A]06 2.00 GIH 2AO CIC 2AS C IH 2.00 C IA 2AS GIF 2AS G]]M G]C IM GIH IM 0375 L375 IX375 0237 a237 (L237 tX237 a237 IX237 0~OAXS OAOO 0300 tXSIS tL300 0300 IL438 L438 0300 0300 0300 tX300 OA3S 0.438 0.145 0.154 0.145 0.145 0.145 0.145 0.145 0.145 0.145 0.145 a]45 NO SUPPORIS hO SUPPORTS hO SUPPORTS NO SUPPORTS NO SUPPORTS NO SUPPORTS NO SUPPORTS NO SUPPORIS NO SUPPORIS NO SVPPORIS NO SUPPORTS hO SUPPORTS NO IWA NO SUPPORIS NO SUPPORIS 1250 100 1250 100 1250 100 12 80 12 80 12 80 75 80 12 80 12 80 1250 100 1250 100 1250 100)250 100 1250 100 1250 100 1250 100 1250 100 1250 100 1250 100 1250 100 1250 100 1250 100 1250 100 1250]00?????t???t?????????????t??t]250 100?1250 100 t?t?3].FW7-900-1 TO VALVE 3998, 3F-FW7-900-1 3F FW7-900 I IO RDCR BEPORE 4XXL 3H-FW7-900-1 TO 3J.FW7-900 l.VALVE 4017 TQ 4345.VALVE 4016 IO 4344.40]4 IO 4098, TURB AUX FW PUMP SV CIION.20ISWO-I 25-1>4640 IO 8>INCL IEE 4ASW-]25-1 IQ VALVES 4027>4345.4ASW-125-1 TO VALVES 4028, 4344.16ASW0.125.], 4623 IQ 4098.4ACD.]50-]h IQ AFW PUM P h SVCIION.4ACD.]50-18 TO AFW PUMP 8 SUCIION.2D.FW7-900 ]A IQ VALVE 4XSC 2D.FW7-900-18 TO VALVE 4XOD.3A FW7-900-]A 'IO 4357.3A.FW7-900.]S IQ 4356.BYPASS FROM 4357 TO 4356 THRU 4XXIA.3X-FW7-900-1 IQ 4360, 4359, SA.FW?-KO.]. SA FW?.900.1 IO 4O]>58 FW7.900 1.58 FW7-900-1 TO 4XXL SA FW7-900.1 IO 4XO, 4XI2, SGFW7-900-1. TURB ARV PVMP DISCHC TO SA-FW?.XO.I. SC FW?-900-1 TO 4004.BYPASS FROM 4357 IQ 4356 THRU 4XX)]L 3A.FW7.900-1h TO]A FW?4XO.]A. 3A.FW7.900.18 IQ 4310.2A.FW7-900-]A 'IO 4482, MA.FW7-900 ]h.2A-FW74s0th]B TO 4484, ISA FW7400.HL MA-FW74Othlh IQ 4483, 3A.FW7.900 ]A.ISA-FW7-900-]8 TO 445, 3A.FW7.900 1]L AFW PVMP A D]SCHG TO 3A-FW74XXhlh. AFW PUMP 8 DSCHC IO 3A.FW?-KO IL SA-FW7-900-1 TO 4023, 429], LFW30.28-FW7-900 ]A TO 440, 2CFW7-900.]* 2B.FW7-900.) 8 TO 4481, 2C RV?-900-HL R 1]/91 R 11/91 R 11/91 R 06/93 R 06/93 R 1]/91 R 11/91 R)I/9)R 11/91 A 1]/9]A 06/93 A 06/93 R I I/91 R 11/91 A I I/91 R 11/91 A I]/91 R I I/91 R I]/91 R 11/91 R I]/91 h 11/91 R I I/91 R 11/91 R I I/91 R 1]/91 R 11/91 R 11/91 A 11/91 A 1]/91 A I]/91 A 1)/91 h 11/9]A 1]/91 A 1]/91 H 0 F/)N H WO+IOH H M)>2>O 0 tO O H M)~'LO H H g Q H K$'0 OX CI FII It)0 0 R E.GINNA NUCLEAR POWER PIANT Inservice hminrsnon~Une List'lirird Inspecthn Interval PAID No..t 33013-1238 Qnss....: 2 System t STANDBY AUXIUARY FEEDWATER Comp T)pe: PIPING O t3 H 0 RUBE Une No 3C FW-902S-lb 3CFW-9025.1B GBbert Une No.FW.1001 FW.1005 C 20 A106 300 IL300 C 24 A106 300 a300 IWC.1222IA) IWC.1222(A) 715 505 715 505 Y 14A.FW4CD. IA TO 9706h, 9704A.Y 14B FW.900.1 B'IQ 9706B, 9704A.ISI Site iidnrs Exemptke NDE~F1.MntrL~in.~in.Basis Metlrod Po~Tern 1n7 Line descri'vnrusrirs Revised R 06/93 R 06/93 H 0 M g H Ls)O+tI)H H II)rEr+OM LD O HU)g'LO H 0 H 2g OX R5 g H M tD n po 0 0 L F GINNA NUCLEAR POWER PIANT Inservloe Eaunlnndoa ~IIne Lht lldrd Inspeedoa laterral RGB E Une No.CBbert SWRI Une No.IIne No.PSFO I A PSFOIB PMD No..r 33013 1238 CLsss: 3 System.: STANDBY AUXIIJARY FEEDWATER Comp lYPe: COMPONENIS ISI She~Fi.MatrL~is.N/h N/A lMtns Exemptioa NDE~in.Bash Metirod Po~Tern IInl Une deseri'/remsrlts OAXO NO IWA VT4 STANDBY AFW PUMP C.IXOOO NO IWA VT4 STANDBY AFW PUMP D.Revted A I I/91 A 11/Pl O Cd H 0 4 H~OM~g Q sos H Q Cd O C HLI3<5<+O th O Cd~HgRa HIOASW IO H owe HgO 4 A'tf M tD n 0 I I E'l P lt II'J 4 l l I l I 1 II I II t II El IL E.GINNA NUQZAR POWER HANT Inservke Examlnadon Boundary Une Ust Tidtd Inspecdon Interval 9&ID No: 33013.1238 Qass.: 3 System: STANDBY AUOUARY FEEDWATER Gnnp~t PIPING H 0 RG&E line No.4ACD.152S 4A.FW8.1525-A 4A.FWB 152S B dfKD.I 52S 3A-FWB 902S-A 3A.FWB 902S.B BOFWB-9025 MA FW8 902S ISB.FW8.9025 GBbett SWRI Une No.Une No.151~Fi.Marti C2&h A106 G28 A106 G28 h106 C28A A106 C.22 A106 C 22 A106 G23 A106 G22 A106 G22A A106 4AO 0200 NO SURPORTS 4AO 0300 4AO 0300 4AO 0300 NO SUPPOR'IS 3AO 0300 3.00 0300 3.00 0200 I M 0200 150 0200 NDE Method Po~Tern In7 Line deserl'emartts 9707h TO 4A.FW8 1525-*9629h TO SIBY AUX FW PUMP C SUCIION.9629B TO SIBY AUX FW PUMP D SUCIION.9707B TO eh-FW8 1525.IL STBY AUX FW PUMP C DISCHARGE TO 970th.STBY AUX FW PUMP D DISCHARGE'IO 9704 1L 3A.FW8-902S-A TO 3A.FW8-902$ K 3A.FW&d02S.A TO LFWOL 3A.FW8-9025-B TO LFW07.R 06/93 R I I/91 R I I/91 R 06/93 R I I/9I R 11/91 R 11/91 R 11/91 R 11/91 H 0 F/I g H XO+tO H H UI g O M tO O H tO g IO H o H g R'd g H I t't II t 1 r I I j 1 J l F a'I I,'II II K I I' IL E.CINNA NUCLEAR POWER PIANT Isetxtlte Examlnathn Botmdsty Line Ust Ih(n(Inspect&a Interval P&IDNo t 3301312391 aass t 3 System.: DIESEL CENERATORS Comp IYpm COMPONENIS RC&E Une No.SWRI line No.ISI Sise Ihkns~FI.MatrL~In.NDE Methyl Po~Tern Int Une cieseri nlremarhs 0 H 0 ESWOSA ESW09A FDGOI FDG02 FDG03 FOAM FDGOS FDC06 FDC07 KDGOIA PDCOI A PDG02A PDG04A PDGOSA PDG06A PDC07A PDGOB SDGOIA TDGOI A IDC02A TDG03A IDG03B TDGOeh C37 Nlh N/h N/A N/A Nlh Nlh Nlh Nlh N/A Nlh N/A N/A N/A N/A N/h N/A N/A Nlh N/A N/A N/A N/A OAS OAXS OAO OASO OAS OAXS OAS OAXO OAS OAXO 0.00 OASO 0.00 OAXO 0.00 OAXS 0.00 OAXO 0.00 OAXS OAO OASO 0.00 OAXS OAS OAXO OAS OAXO OAS OAXS OAS OAXS OAO OAXO OAO OAXS OAO 0.000 0.00 OAXO OAO 0.000 OAO OASO OAS OAXO IWD.122IL I IWD.122shl IWD 1220.1 IWD 1220.1 IWD 1220.1 IWD.1220.1 IWD-1220.1 IWD 1220.1 NO IWA NO IWA IWD-1220.1 IWD-1220.1 IWD 1220.1 IWD1220.1 IWD.1220.1 IWD.1220.1 NO IWA IWD-1220.1 IWD.1220.1 IWD.1220.1 IWD.1220.1 IWD-122thl DIESEL GEN h JACKET WATER HEAT EXCHGL DIESEL GEN A LUBE OIL COOLEL DIESEL CEN h PRMARY BL'KL DIESEL GEN A PRIMARY FIL'KL DIESEL GEN A SECONDARY BLTEL DIESEL GEN A SECONDARY FILTEL DIESEL G EN A LUBE OIL BLIEL DIESEL CEN A INTAKE FILIEL DIESEL GEN A INTAKE BLIEL DIESEL CENERAIOR*DIESEL GEN A JACKET WAIER PUMP.DIESEL GEN A FUEL OU.TRANSFER PUMP.DIESEL GEN A FUEL OIL PRIMING PUMP.DIESEL CEV A FUEL OIL BOQSIER PUMP.DIESEL CEN A lllBE OIL PUMP.DIESEL GEN A PRE.UJBE OIL PUMP.DIESEL GEN A AIR STARTINC MOIQL DIESEL GEN A EXHAUST MUFBEL DIESEL DEN A FUEL OIL SIQRACE TANK.DIESEL CEN A COOUNG WATER EXPAhSION TK, DIESEL GEN A STARIING AIR RECEIVER Al.DIESEL GEN A STARIINC AIR~h2.DIESEL GEN A FUEL OIL DAY TANK R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/98 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 H 0 F/2 g H XO+t()H H t13 g O 02 (t(3 O H~~II3 H o H'g aa g H 0 0)9 0 r.0 0 II il'I l I N C 1 4, P N I H V I, a IL E.GINNA NUCLEAR POWER FIANT Inserrrke Exarnlnarbn Bonndary Une Usr TIrlrd Inspecdon lnterral PMD No-s 33013.1239-1 Qass s 3 Sysrern r DIESEL GENERATORS Comp Type: PIPING 0 RQtE Une No.0Bberr line Na ISI She~Fi.Marrl~b.Po T~em In?Lbe deseri remarlrs 2OA.DG.150%A 20B-DG-ISA SA.DG-A SB DGW SCDG.A 3A.IQ.1506A 3B-FO 1506A 2A.FO 1506A 2ASA.I~A 2B-IO.1506A 2CIO.1506A 2D.IQ-1506A I M-IQ.1506A WASh.I SLY MACAW.125-1h I SB-FO.150&A ISC FO-1506A I SD.IO.1506h I~.fO 1506A N/A A53 C39 A53 C35 C35 C35 N/A A53 N/h A53 N/h A53 N/h A53 N/h A53 N/A A53 N/A AS3 N/A A53 N/A A53 N/A A53 N/h A53 N/A A53 N/h N/h 2aoo 20.00 SAS 5AO SAI 3AS 3'AS 200 2AO 2AO 2'~IM IM IM 150 150 12S IWD.1220.1 IWD 1220.1 IWD 1220.1 IWD 1220.1 IWD 1220.1 IWD 1220.1 IWD.1220.1 IWD 1220.1 IWD-1220.1 IWD 122a I IWD 122aI IWD.1220.1 IWD.1220.1 IWD.1220.1 a250 No sUPPORTB IX2M 0.000 NO SUPPORTS OAXO NO SUPPORTS OAIO a216 0.216 0.145 0.145 0.145 a145 ale 0.133 0.133 0.133 a 133 a133 0.133 0.133 AIR INTAKE DG I*AIR EXHAUST DG IA.JW.HXA TQ JW PUMP A SUCT.JW PUMP A DISCHG TQ DGA, DG-A REIIJRN UNE TQ JW HX*DIESEL OIL SIQRAG 5 TANK TO 5955, 2'ED.2D TO OIL TRANSFER PUMP.ISA TO DIESEL OIL SIORAGE TANK*AIR REEENERS Al!t h2 TQ 5905A Br B, 5975 OIL llRNSFER PUMP TQ 5965 Br 5976.ISA TQ 5967 Sr 5959.3A TO 3IL DAY TANK A TO 5960A, 2A.2A TQ DG-A AIR STARTING MOTOR.5900A TO COOLLNG WATER EXPANSION TANK.MSA TO IA.5913 TO 5909 63h.5965 TO I*ISB TO DAY TANK h.R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 0 Ul X H Esl O H Ul~O M H LO O LO Q LO H p H 2e OW R5 g H g 0 4 Q 0 P J k L E.GINNA NUCLEAR POWER PihNT Inrerviee Krrrrrnlnrtdon Boundnry Une Urt Third Inrpeetion Interrrd P&ID No t 33013 1239-2 Cher t 3 Syrtern t DIESEL GENERATORS Comp IYpe: COMPONEÃIS O H CI RG&E Une No.ESItIOB ESWISB FDGOB FDQS FDGI 0 FDGI I FDG12 FDG13 FDG I 4 KDCOIB PDGOI 3 PDC02B PDCOI 3 PDGOSB PDC06B PDCGFB PDQS SDGOI B IIOOI 3 IDG02B IDG03C IDQBD IDG04B CKbert Une No.SWRI Une No.C3$N/A N/h N/h N/A N/A N/A N/A N/A N/h N/h N/A N/A N/A N/A N/A N/A N/h N/h N/A N/A N/h N/A OAO OAO OAO 0.00 0.00 0.00 OAO OAO OAO OAO OAO OAO ILL 0.00 0.00 OAO 0.00 OAOO 0.000 OAXO 0.000 0.000 0.000 OAXO OAOO OAOO OAOO OAXO OAXO OAXO OAOO OAXO (uXO OAXO OAXO 0.000 OAOO OAXO 0.000 IWD.1220.1 IWD 1220.1 IWD-1220.1 IWD 1220.1 IWD 1220.1 IWD 1220.1 IWD.1220.1 IWD 1220.1 NO IWA NO IWA IWD 1220.1 IWD-1 220.1 IWD.1 220.1 IWD.1220.1 IWD.1 220.1 IWD.1220.1 NO IWA IWD 1220.1 IWD-1220.1 IWD 1220.1 IWD 1220.1 IWD-1220.1 Po~Tern In?Une dereri rernartr DIESEL CEN B JACKET WATKR HEAT EXCHGR.DIESEL GEN B WBE OIL COOIEIL DIESEL GEN B PRIMARY BLIEL DIESEL CEM B PRIMARY FILIKIL DIESEL CEN B SECOiVDARY BL'IKL DIESEL CEM B SECONDARY BLIKL DIESEL CEN B LUBE OIL BLIKL DIESEL CEN B STAKE BLIKIL DIESEL GEM B INTAKE BLIKIL DIESEL GENERAIOR L DIESEL GEN B JACKET WATER PUMP.DIESEL GEN B FUEL OIL TRANSFER PUMP.DIESEL GEN B FUEL OIL PRIMINC PUMP.DIESEL GKN 8 FUEL OIL BOOSTER PUMP.DIESEL CEN B WBE OIL PUMP.DIESEL C EM B PRE-LUBE OIL PUMP.DIESEL CEM B AIR STARILVG MOTOR.DIESEL CEN B EXHAUST MUFFLEL DIESEL GEN B FUEL OIL STORAGE TANK.DIESEL CEN B COOLING WAIKR EXPANSION IK.DIESEL CEN B STARTING AIR RECEIVER Al.DIESEL CEM B STARTING AIR RECEIVER A2.DIESEL GEM B FUEL OIL DAY TANK.R 06/93 R 06/93 R 06/93 R 05/93 R 06/93 R 05/93 R 06/93 R 05/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 05/93 R 06/93 OM g H W 0 H IO H+OFJI IO'g td II2 O H 113~'LO H o H g Q H o F3 0 M 8 n 0 0 R.E.CINNA NUCLEAR POWER PIANT Inservlte Examlnathn Bonnrhry Lhe Urt TMnI Inspection Interval PMD No t 33013 1239-2 aass..: 3 System: DIESEL GENERATORS Comp Type: PIPING O H 0 ROSE Une No.GBbert Lhe No.ISI She~Fi.MstrL~h.NDE Method Po T~em In?Lhe deseri'/remarks 20A.DC ISHB 203-DG-150eB SA DG-B SB DC-B SC.DG-B 3A.FO-1506B 3B.FO 1506B 2A.FO 1506B 2ASA.150'2S FO.15063 2GFO.1506B 2D.FO 15043 1$A.FO 1506B 1$ASA.I~B 1$A3W.125 I B 1$B-IO 1506B 1$C FO.1504B I SD.FO 1506B 125A.PO-1506B N/h A53 G4)A53 G36 G36 G36 N/A A53 N/A A53 N/h A53 N/h A53 N/A A53 N/A A53 N/A A53 N/A A53 N/A A53 N/A A53 N/A A53 N/A A53 N/A N/A 2IL00 20AS SAIC SAN SAN 3'.00 2AS 2'AX?2AO 2.00 1$0 1.50 1$0 1$0 1$0 IM 0250 0250 OAXS OAXS OAXO 0416 OA3S 0.145 0.145 0.145 0.145 0.145 0.133 0.133 0.133 (1133 0.133 0.133 0.133 NO SUPPORTS NO SUPPORTS NO SUPPORTS IWD.1220.1 IWD.1220.1 IWD 1220.1 IWD 1220.1 IWD.1220.1 IWD 1220.1 IWD 1220.1 IWD 1220.1 IWD 1220.1 IWD-1220.1 IWD 1220.1 IWD 1220.1 IWD 1220.1 IWD.1220.1 VT3 VT3 VT3 VT3 VT3 AIR INTAKE DG IL AIR EXHAUST DG IIL JW-HX-B TO JW PUMP SUCT.JW PUMP B DISCHG'IO DG-L DG-B REIURN UNE TO JW-HX-L DIESEL OIL SIORAG E TANK TO 5956, 2'ED.2D TO OIL TRANSFER PUMP.1$A TO DIESEL OIL STORAGE TANK L AIR RECEIVERS Bl R B2 TO 5906A St S, 5975 OIL TRANSFER PUMP TO 5966 S 5976.1$A'IO 5967 Bt 5960.3A TO 3IL DAY TANK B TO 5960B, 2A, 2A TO DG B AIR STARTING MOTOR.5900B TO COOUNC WATER EXPANSION TANK.I~TO IA.5914 TO 5910 Ik 3A.5966 TO I*1$3 TODAY TANK L R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 H CI Ul X H X O+'LO H Hex o M tO O HIDE'LJ3 H p H g g H I m Vl 8 0 b4 0 0 P f 4 K E.GINNA NUCLEAR POWER PLANT Inserviee Examinatbn Bonndaty Une Ust Thitd Sspeetion Imetval P&ID No t 33013.1245 CLsss.t 2 System t AtMUARY COOLANTCXW Comp TYpe: COMPONENTS O td 0 RG&E Une No.PACOIA PACOIB 1247 1247 ISI Size~FI.MatrL~in.410 350 410 350 THIS COMP ACCOUNTED FOR ON 33013-1247. h 11/91 THIS PUMP ACCOUNTED FOR ON 33013.1247. h 11/91 T?dtns Exempdon NDE~in.Basis Method Po~Tern InI Une deserl n/remarks Revised OM Q H WO+IO H H~g O M w,~tD O HIDE IO H p H g O W 0 M tD 0 fp r.0 0

• 1 1 ll I I D IL E.GINNA NUQZAR POWER PLANT Insessloe Exnmlnnaoa Oanddtty Une Ust lMtd Inspeedoa Itnesval 9&ID No t 33013-1245 Qnss.t 3 System: AUXIUARY COOIANTZCW Comp Types COMPONKNIS H 0 RGRE Une No.EAC01 EACOIA EACOIB EAC02A EAC02B KAC04A EAC04B EACOSA KAQ5B EACOSC EACOSA FAC06B ESS04A KSS04B KSS04C ESS040 PAC02A PAC023 TACOI G Rhett SWRI U N ll N LSI~FI.MsttL N/h CA I~1 B.109$-109 N/A N/A N/h N/A N/h N/A N/h N/A N/A N/A N/A IWD 1220.1 IWD.1220.1 IWD-122a I IWD 1220.1 IWD 1220.1 IWD 122al IWD.1220.1 IWD.1220.1 IWD.1220.1 IWD 1220.1 IWD.1220.1 NO IWA NO IWA 080 OAXO IWD.I~I OAO CACAO OAO OAXO OAX)0AXO aoo olxo aoo 0Axo OAO OANO OAN OAXO OAS OAXO aoo aooo OAN OAXO OAO OAXO OAO OAXO aoo aooo 0.00 OAXO 0.00 OANO 0.00 OAXO 0.00 OAmo aoo olxo NDE Method VTQ VTD N/h N/A<275<200<275<200<<275<<200<275<200<275<200<275<200<275<200<275<200<275<200<275<200 FAIIZD FUEL RAD MOh lit)R HEAT KXCHG IL COMPONENT COOUNC WATER HEAT KXCHGR*COMPONENT COOUNC WATER HEAT EXCHGR L RHR HXA ACCOUNlTD IQR ON 33013-1247.

RHR.HX.B ACCOUNTED FOR OV 33013-1247. S/G BLOWDOWN SAMPIZ HEAT EXCHGR A.5/G SLOWDOWN SAMPIZ HEAT EXCHGR L PRESSURIZER LIQUID SPACE SAMPLE HE.RC IZCP B HOT LEC SAMPLE HEAT EXCHGR.PRESSURIZER STKALI SPACE ShldplE HE.RHR PUMP COOLER A.RHR PUMP COOlER IL POST ACQDENT SAMPIZ COOLER*POST ACQDENT SAMPIZ COOLER L POST ACQDENT SAMPLE COOLER C.POST ACQDENT SAMPLE COOLER D.COMPONENT COOUNC WAlER PUMP h.COMPONENT COOUNC WATER PUMP IL COMPONENT COOUNC WATER SURC E TANK.A 11/91 A I I/91 A 11/91 A 11/91 A 11/91 A 11/91 A 11/91 A I I/91 h 11/91 A 11/91 h 11/91 h 11/91 A 11/91 A 11/91 A 11/91 A 11/91 R Ol/92 R Ol/92 A 11/91 Q M XH X A H Ml g 0 M w,~I-I e I III H LO Q H g 0 g 0<<" Q M 8 0 rt I 0 0 t, IL E.CINNA hVCIEAR POWER PLANT Inserviee Buunlnadon Boundary Une Ust Third Inspeedon Interval PMD No..: 33013-1245 CLass: 3~em.t AIDGUARYCOOIANTASW Comp I7pet PIPINC O b3 0 ROBE Une No.GEbert Une No.SWRI Une No.NDE Method Inl I 4A PCS.1 52 14 BAGS-152 14GAC5.152 IOA4CS 152 IOBACS 152 IOGAC5.152 IODACS IS2 I OEACS.I 52 IOMC$152 I OG*CS-I S2 IOHACS.152 101*C$.152 IQMCS 152 I OK.AC5.152 I OLACS 152 8A.AC5-152 8BAC$152 6A4CS.1 52 4AAC5.152 4BAC$152 4GACS.1 52 3lWLCS-152 3BACS-1$2 3GACS-152 3DAC5.152 3 SACS.152 2A4CS.152 2B4C$1$2 2GAC$152 2D AC$152 2E ACS 152 2F ACS.I S2 204CS-I 52 2H4CS-I 52 2I.ACS 152 2J4CS 152 2KACS 152 13h AC5.152 LSILACS-152 I 3GACS-I 52 CC.100 CC 200 CG300 OC 100 CC 100 CGIOO CC 100 CG200 CG200 CC 200 CG 200 CGIOO CGIOO CC 240,120 CG240,120 CG14IL180 CC 170,180 N/h N/h N/h N/A N/A N/h N/h N/A N/A N/A N/h N/h N/h N/A N/A N/A N/A N/A N/A N/h N/A N/A N/h N/h N/h N/A N/A N/A N/A N/A N/A N/A G2 G4 G6 C2 G2 G2 G2 G4 G6 G6 G6 G6 G4 G2 G2 G6 G2 G4 G6 G4 N/h G6 N/A N/A G4 N/A N/A G6 N/A N/A N/h N/A G6 G6 N/h N/A N/A N/A 14AS 14AS 14AS IOAS I GAS IOAS I GAS I GAS I GAS I GAS IOAS l(LOO 10.00 10.00 I GAS 8AS 8.00 6AS 4AS 4AS 4AS 3AS 3AS 3AS 3AS 3AS 2AS 2AS 2AS 2.00 2AS 2.00 2.00 2.00 2.00 2.00 2.00 130 130 0375 0375 0375 0365 0365 0365 0365 0365 0365 0365 0365 0365 0365 0365 0365 0365 0365 0280 0237 0337 0337 IL216 0216 0216 0316 0216 0.1$4 0.154 0.154 0.1$4 (L154 0.154 0.154 0.154 0.1$4 0.154 0.154 O.NS 0.145 0.145 NO SUPPORIS NO SUPPORTS NO SUPPORIS NO SUPPORIS NO SUPPORIS IWD.I 22IL I IWD.122sL I IWD-1220.1 IWD I 22sLI IWD.1220.1 IWD 1220.1 IWD 1220.1 IWD-I 22ILI IWD 1220.1 IWD.1 220.1 IWD-122ILI IWD-1220.1 IWD.1220.1 IWD 1220.1 IWD 1220.1 IWD 1220.1 IWD.122Q,I IWD 1220.1 IWD 1220.1 IWD.1220.1 IWD.1 220.1 IWD 1220.1 VTQ VF4 VT3 VT3 VT3 VT4 VT3 VM'T3 VT3 VT3 VT3 VT3 VT3 VT4 VT3 VT4 VT3<150<150<150<150<150<150 c 150<150<150 c 150 c150 c150<150 c150<<150<150 c150<150<150<150<150<150<150<150<150<150<150<150<150 c 150 c 150<150<150<150<150<150<150<150<150<150<200<200<200<200<200<200<200<200<200<200<200<200<200<200<<200<<200<200-<200<200<200<200<200<200<200<200<200<200<200<200<200<200<200<200<200<200<200<<200<200<200<200 10 X 14 RDCR FROM B CC PUMP TO 10'DCRS.734B IO 10'EDUCLNG ELL BEPORE 738A.14'EE AT RHRHE OUILEIS IQ CC PUMPS.VALVE 723A TO 14 IEE, 14A VALVE 723B IO 14 X 10'EDUCEIL N'EDUCER IQ VALVE 733A, CCHE*14'EDUCER TO VALVE 7338, OCHE IL CCHE A IO VALVE 734A, 14 IL 14B IQ RHRHE IL 14B IQ RHRHE A RHRHE B OUIIET TO 14'EE.RHRHE h OUIIZT IQ N'EDUCER.14C TO CC PUMP A SUCIION.14C IQ CC PUMP 8 SUCIION.CCHE B IQ 7348, 14IL CC PUMP A IO VALVE 723A CC PUMP B IO VALVE 723IL 14C'IQ 4G I OC IO ACAHHX.I OE IQ ACAPCP.CC SURGE TANK'IO 728, 6/L DRAIN FROM 14 8 IO SALIPLE HES.SAMPLE HES'IQ 772D.772D'IO CC PUMPS SUCIION.CC SURGE TANK IQ 732.747H TO 3C IOC IO 707h, RHR PUMP*2AIQ7078, RHR PUMP IL RHR PUMP B IQ 7088, 2D.RHR PUMP A 1074lh, 769, IOL 699 IQ CC SURGE TANK.CC SURCE TANK IO 731A.CC SURGE TANK IO 713.4C IQ 823, 729.740A IQ I OL 740B TO 14G CC SURGE TANK IO RCVO17.3A IO VALVE 747G VALVE 747K IO IS, PAS COOLEIL IS, PAS COOLERS IQ VALVE 747F.R 11/91 R I I/91 R I I/91 R 11/91 R 11/91 R I I/91 R 11/91 R I I/91 R IV91 R 11/91 R 11/91 R 11/91 R I I/91 R IV91 R 11/91 R 11/91 R IV91 R 01/92 R IV91 R IV91 R 11/91 R 11/91 R I I/91 A IV91 R 11/91 R IV91 R IV91 R 11/91 R I I/91 R I I/91 R I I/91 R I I/91 A I I/91 A 11/91 A I I/91 A ll/91 A 11/91 A I I/91 H 0 V)X H X 0+tOH H UI g O Vl g'Q H 0 H g g 0<" Q 0 O Pd 0 (0 ID n r.0 C l lt (W 4 4P l N~'I I'i 1'L e'C), I ll 4'(k~~~'~t*I At&h'I;f' IL E.GINNA NUCILAR POWER FIANT lnrervke Examination Bonndary Une Lbt'Ihlrd nrpeenon Interval PKID No t 33013.1246-I Clear t I Epact AUXIUARY COOIANT~Comp TYper COMPONLNIS O 0 RGStE Une No.GBbert SWRI Une No.Une No.ISI She~pi.MatrL~h.%Mt'xemption hDE~in.lhsis Method Po~Tern In?Une desert'ennarls Revised PRCOIA PRCOIB A.7 h-7 SUB/VOL 5UR/VOL'IHIS PUMP ACCOUNIED fOR ON 33013-1260. R 06/93 THIS PUMP ACCOUNIED fOR ON 33013 126a R 06/93 H 0 M g H R O H IE)H~'LO Q gOM I U3 O M H II2 g~'LD H 0 H g Q H OX 0 g 0 CQ M 8 n r.0 0 R E.GINNA NUCLEAR POWER PLANT Insetvke Exatnination Boundary Une Ust'IMsd Isspeetion ltuetval P&ID No-t 33013-1246.1 Chss t 2 Systesn t AIOGUARY COOLANT<XW Cutup Types COMPONENIS O H 0 RG&E Une No.CQbett SWRI Une No.Une No.ISI Size~PI.Po~Tetn-IIn7 Une desesi n/renmrits ECH03 ECHOBA ECHOSB RX SUPT COOL h RX SUPT COOL B N/A N/A N/A N/h N/h aOO 000 aoo OAO IWC I 222(A)IWC 1222(A)IWC 1222(A)IWC 1222(A)IWC 1222(A)<<275<200<275<200<275<200<275<<200<<275<200 EXCESS LETDOWN HEAT EXCHANCEIL RCP h UPPER BEARING COO(EL RCP B UPPER BEARING OOOLEL REACIQR SUPPORT COOLER A.REACIQR SUPPORT COOLER IL R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 H 0 0)g H RO>td)H HLOg O (0 Hu)Z LO O ti)H 0 H g 0 g 0<<,"Q (I)8 n po 0 O II V'I lt R.E.GINNA hUCLEAR POWER PIANT Inseeviee Exam)nation Boandeey Une Ikc Th)n)lnspeedon)steeve)PBID No: 330)3-1246-) (2nss: 2$)nrem.: AIDGUARY COOLANT4SW Comp T)pe)PIPING H 0 RG&E Une No.6AAG)52 6)LAG)52 6PAC6.152 6H.AC6)52 4A4G152 4 BAG)52 4BAC6-)52 4DAC6 152 4EAC6)52 4F AC6 152 4G.AC6-152 4HWC6.)52 41 AC6-152 4).AC6.152 4K-AC6.152 41 AC6.152 4M AC6 152 4M4C6.)52 4OAC6.152 4PWC6-)52 4RAC6-152 4S AC6-152 4TAC6 152 4UWC6.152 4V.AC6.152 4W~)52 3A.AG)52 3BAG)52 3GAG 152 3GAC6.152 3D AG)52 3D-AC6-152 3E.AC6 152 3F-AC6 152 31 AC6.152 3).AC61S2 3KAC6-)52 SMAC6 152 3M~152 SOAC6 152 3QAC6.152 7A~)52 2)LAG)52 GUbeet 1)ne No.CC 200 CG220 CG500,$25 N/A CG$75 N/A CC450 CC625 CC625,CC600 N/A CC$25 N/A CG700 N/A CC 700;725 N/A CG450 N/A CG 525 Nfh CGS25 Nfh CG 525 N/A CG$25 N/A CG525 N/A CG525 N/A OG$2S N/h CG525 N/h Nfh CC 220 CC 220 CG330%CG450 CC600 N/A CG629tCG330 CG600 N/A CG700 N/A CC 700 N/A CG400 NIA CC 525 N/A CG$25 N/h CC$25 NIA CC$25 N/A CC450 N/A CS GS G9 G9 8.29 MO N/A C9 N/A N/A 8.29 G9 N/A N/A N/h G9 N/A N/A G9 N/A N/A 8-29 MO N/A N/A Nfh N/A N/A 8-29 MO MO N/A G34 N/A N/A N/A N/A N/A N/A 8-29 MO N/A N/A 6AS 6AO 6AS 6AS 4AS 4AO 400 4AO 4.00 4.00 4AS 400 4AS 400 400 400 4.00 4AS 4AO 4.00 4AS 4AS 4.00 4AS 4AS 4AO 3AO 3AO 3AS 3AS 3AO 3AS 3AS 3.00 3.00 3AO 3.00 3.00 3.00 BAO 0280 0280 0280 (L237 L237 0237 0237 L237 0237 0237 0237 0237 a237 0237 0237 0237 0237 0237 0237 0237 0237 0237 0237 0237 0.237 a2)6 0216 0.216 0216 0.216 0.216 0.216 L2)6 L2)6 IL2)6 0216 K2)6 (4216 0216 0216 0.1$4 0.1$4 IWC 1222(C)IWC 1222(C)IWQ 1222(C)Ph'G)222(C) IWC 1222(h)PA&1222(A) IWG)222(A) IWC 1222(A)IWG)222(A) IWC 1222(h)IWG)222(h) IWG)222(h) IWG)222(A) IWG)222(A) IWC 1222(h)IWG)222(A) WG)222(h)IVI&)222(h) IWG)222(A) IW'G)222(A)P'G1222(h)IWG)222(h) IWG)222(h) PA%1222(A)IWG)222(h) IWG)222(h) IVi&1222(h) IWG)222(h) IWG)222(A) IWC)222(A)IWC 1222(h)IWC 1222(h)IWC 1222(h)IVQ)~)WG)222(h) IWC 1222(A)IWC 1222(h)IWG 1222(A)IWC 1222(A)IWC)222(h) IWC.)222(A) IWC)222(h)IWG1222(A) 90 90<150 c)50 90 90<<150<150 c150 c)50 c)50'150 c)50<150<150<)50<150<150 c)50 c)50<150 c)50<150<150<150<)50 90 90 90<150 90<150<150 c)50<150<150<)50<)50 c150<150 c150 90 90 70 70<200<200 70 70<200<200<200<200<200<200<200<200<200<200<200<200<200<200<200<200<200<200<200<200 70 70 70<200 70<200<200<200<200<200<200<200<200<200<200 70 70 In)VALVE 813 TO PEM 131.PEN 130 TO VALVE 814.PEN 131 TO 4D, 4)L REACIOR SUPPORT COOLERS, 40 TO PEN 130.VALVE 750B IN CONT TO RDCR PEN 12L VALVE 750A'IQ RDCR BEFORE PEN 127 IN CON 750A AT PEN 127)0 3C.6F IO RX SUPT COOIER B HEADERS 4LI I'e 4V.3E AT RPC A TO 3F.3F'10 PEN 126.7508 AT PEM 128'IO 3'DCR (30)~6F'IO RX SUPT COOLER A HEADERS 41 Ie 41.4H TO RX SUPT COOLER h.4H TO RX SUPT COOLER h.RX SUPT COOLER A 10 4L RX SUPT COOLER A DSCHG HDRS 4K, 4U)0 6H 4D TO RX SUPT COOLER L RX SUPT COOLER B)0 4(X RX SUPT COOLER 8 DSCHG HDRS 4N, 4W TO 6H 7578 TO P)25.3D AT RCP 8 TO 34 75714 30 TO RCP L 3C TO 3Q AT RCP*RX SUPT COOLER A TO 4L 4D TO RX SUP)'OOLER L RX SUPT COOLER B TO 40.PEN 125)0 VALVE 759)L PEN 126 TO VALVE 7$9A.RDCR BEFORE PEN 128 IN CONT TO VAL 74914 48)0 751h, 4T.RDCR BEFORE PEN 127 I M CONT)0 VAL 749A.RCP 8)0 REDUCER AT 4I4 RCP A TO REDUCER AT 4E.4E)0 757h, 4F.4R TO 7578, 4P.4H TO RX SUPT COOLER*4D TO RX SUPT COOLER L RX SUPT COOLER A TO 4L RX SUPT COOLER 8 TO 4O.4G)0 7518, 4S.4TTO RCPA.PEM 124 TO VALVE 743.PEN 124)0 VALVE 745.R OV93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R OV93 R OV93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 H 0 (/)g H (T)A+I()H H~g O (/l td (~I()0 (u)1-1'LO Q H g 0$'0 OX 0 (/l (()()k" 0 4 lt L R.E.GINNA NUCLEAR POWER PIANT Inservhe Erranhstbn Boaaday Lhe Ust'IMrd Inspeethn Intervrd PM 0 No t 33013 124th I (Cont'd)CLsss t 2 System: AIDGUARY COOIANTCCW Comp T)rpet PIPING H 0 RGB E Une No.SWRI line No.ISI Size~FI.MntrL~h.NDE Mrtlrod Po~Tern In?Une deserl'emarks AC&-152 2JAC6 152 2MAG6 152 2PWC6.152 2QAC6-152 2S-AC6.152 ISA~I52A IEA.AC6-1523 ISAAC&.152C IEA-AC6 152D ISBAC6152A ISB.AC6 152&I SB.AC6-I 52C N/h N/h N/A N/A N/h N/A A53 N/h A53 N/A A53 N/h A53 N/A A53 N/A S30 A53 N/A N/A N/h B.29 A53 N/A N/A 2AI0 2.00 2AXt 200 200 2'W IW 180 150 IM (L109 0.109 Q154 0.154 0.109 0.154 0.145 0.145 0.145 0.145 0.145 0.145 0.145 IWC.1 222(A)ltrr0 1222(h)IWC.1222(A) IWC.1222(A) IWC 1222(A)IWC 1222(A)IWC 1222(A)IWC 1222(A)IWC 1222(A)IWC.1222(A) IWC.1222(h) IWC 1222(A)IWC 1222(h)<150 c200<150<200<150<200<150<200 c150 c200 c150 c 200<150<200<150<200 c150<<200 c 150<200 c 150<200<150<200<150<200 4H 10 RX SUPT COOLER A.4D 10 RX SUPT GOOIER IL 3F 10 75&A.4P 10 75&IL RX SUPT COOLER B 10 40.RX SUPT GOOIER h 10 4L 3C TO RCP h.RCP A TO.75H, IM.IA, FIAII I TO 3F.IM 10 3F.30'IO RCP IL RCP B 10.750.I GWC6 152A 10 I G.AC6.152IL R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 H OM g H WO+'Q H HLOg O (/)He('Q H Q H OX 0<"8 0 f 1'\If I I II IL E.CINNA NUCLEAR POWER PIANT lnsesvke Examlnadon ~Line IAst Thinl Inspecthn Intesvai P&ID No s 33013.1246-1 Qass-s 3 System: AUXKIARY COOLANT~Comp Type: PIPLNG O H 0 RG&E Line No.CBbest LIne No.ISI Sine Thkas~Fi.Matsl.~h.~in.Po T~em In?Une desesi remarhs BANC&.152 BSAC6.152 6AAC6 152 6D AC6 152 4A.AC6.152 4Q4C6 152 3AvhC&.152 3 BAG&152 3G-AC6.152 3HAC6.152 2AWC6.152 2IAC&152 N/A N/A Nfh Nfh NfA N/A Nfh N/A N/A N/A N/A N/A CS A53 C.S A53 OS A53 OS A53 CS A53 OS A53 N/A A53 N/A A53 CS A53 N/A A53 N/h A53 Nfh A53 SAS IX322 8AO 0322&00 (L180 6'280 4'L237 4AO 0237 3AO 0216 3AS0 0216 MO 0216 3Axs 0216 2AO IL154 2'L154 NO SUPPOR'lS IWD 1220.1 IWD.1220.1 IWD 1220.1 IWD 1220.1 IWD-1220.1 IWD 1220.1 IWD.1220.1 IWD I22ILI<150<<200<150<200<<150<200<150<200<<150<<200<150<200<<150<<200<150<200<<150<200<150<200<150<200<150<200 COMPONENT COOUNC HE TO 817>6'EDUCEIL 4Q TO 816, 14 REDUCEIL BA'IO 813.814 TO 815A, BIL BA TO REDUCER BEPORE 749A CONNECIS 88, 3H,&2L 4A'IO 749A.4h TO 749IL 759A TO 762A, 8IL 759B'IO 7628, 4Q.4A TO 742A,&743 TO EXCESS LETDN HE.EXCESS IETDN HE TOP 124&745 TO 7428, 4Q R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06f93 R 06f93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 H Q M X H WO W~II)H~LO Q g o V)I H LO~%O g 0)H 0 OW R5 g H 0 g 0 CQ 0 I I R L I'4 l 4 I I j~"~. K E, GINNA NUQEAR POWER PIANT Inrerrioe~n Borrnthrry Une Urc ThM hnapeedom interval PAID No r 33013-12462 Qarr r 2 SFrrerm r AUXIUARY COOIANT~Comp T)pm COMPONENIS O t3 H 0 RGBE Une No.GUberr UUnnee No.SWRI Une Nm 51 Sire Thknr~F1.MarrL~in.~in.NDE Made Po~Tern In?line rieaeri'/remarka FACOBA EACOSB EAGSA EAGSB EACIOA EACIOB EAC I Ih FACI IB PSIOI A PSIOI B PSIOIC PSI02A PSI023 1262 1262 1262 1261 1261 N/A N/h N/A N/A N/A N/A N/h N/h N/A N/A N/A N/A N/h OAR OAXXJ OAXJ OAXXJ 0.00 OAXe DAO OAXXJ GAS OAXXJ OA0 OAX0 OAJ2 OAXO 0.00 OAXS OAS OANO OAC OANO 050 OAXXJ OAJO OAXJO (LOO MOO IWC 1222(h)IWC 1222(A)IWC.1222(A) IWC 1222(A)IWC 1222(A)IWC 1222(A)IWC 1222(h)IWC.1222(h) NO iWA NO IWA NO IWA NO IWA NO IWA 1550 200 1550 200 1550 200 205 70 205 70 SAFETY INJECIION PUMP A COOLFR A.SAFEIY INJECIION PUMP A COOLER K SAFETY INJECIION PUMP B COOLER*SAFEIY INJECIION PUMP B COOLER L SAFEIY INJECIION WMP C COOLER A.SAFEIY INJECIION PUMP C COOLER K CONTAINMENT SPRAY WM P A COOLEIL CONTAINMENT SPRAY PIJMP B COOIEL THIS PUMP ACCOUNIED POR ON 33013 1262.THIS PUMP ACCOUNTED FOR ON 33013.1262. 'IHIS PUMP ACCOUNTED FOR ON 33013.1262. THIS PUMP ACCOUNTED FOR ON 33013-1261. 1HIS PUMP ACOOUNIED MR ON 33013.1261.R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 H 0 0)X H Er(A H LO H~LO Q@O(/l I H U)~LEJ O LO H o H Q d O Pd R5 g H 4 l f P'1 E II A A I IL E.GLVNA NUCLEAR POWER PIANT Inservice aarnlnadon Bonndary Une Ust IMrd Inspecdon Inrerval PMD No r 33013.1246.2 Qass.: 3 Sysrern.r AUXIUARY COOIANTCCW Cosnp TPPe: COMPONENIS O H 0 ROTE Une No.GEbert Une No.SWRI Une No.LSI Size Thhs~F1.MarrL~in.~ln.Po T~ern In?Une descrl'ernarlrs EAC08A EAQJSB EAQSA EAQSB EACIOA KACIOB EACII A FACI I B ECHO I ECHO'CH05 ECH06 ECH07 EWDOIA EWDOI B EWD09 EWDI0 KWDI I N/h N/h N/h N/A N/A N/A N/A N/A N/h N/A N/A N/A N/h N/A N/A N/A N/A N/h aoo aooo OAO OAXO aoo aooo OAS OANO OAO OAXO GAS aooo OAO OANO OAS OAMO aoo 0AR0 OAO OAXS OAO aooo ols aooo OAR 0.000 a00 0.000 OAO 0.000 OAS 0.000 OAO 0.000 OAO 0.000 IWD-1220.1 IWD.1220.1 IWD.1220.1 IWD 122al IWD.122a1 IWD 1220.1 IWD 1220.1 IWD.1220.1 IWD 1220.1 IWD122al IWD 1220.1 IWD 122al IWD 122a2 IWD.122a2 IWD 122a2 IWD.1220.1 IWD.1220.1 IWD.1220.1 <275<200<275<200<<275<200<275<200<275<200<275<200<275<<200<275<200<<275<200 SAFEIY INJ ECIION PUMP A COOIKR A.SAFElY INJECIION PUMP A COOIZR L SAFETY INJECIIOV PUMP B COOLER*SAFEIY INJECIIOV PUMP B COOIZR L SAFEIY INJECIIOV PUMP C COOIZR A.SAFETY INJECIION PUMP C COOLER L CONTAINMENT SPRAY PUMP A COOLEL CONTAINMENT SPRAY PUMP B COOLKL BORIC AQD EVAP DISIIIATE COOLKL SEAL WA1KR HEAT EXCHANGEL NON.REGENERATIVE HEAT EXCHANGEL BORIC AQD EVAP AIR EJECIOR CONDEhSOL BORIC AQD EVAPORATOL WASIK CAS COMPRESSOR h SEAL WATER HE.WASTE CAS COMPRESSOR B SEAL WA1KR HE.WASTE EVAP CONDENSINC HEAT EXCHGR.WASTE EVAP AIR EJECTOR HEAT EXCHCL WASTE EVAPORATOR DISTILATK COOLUL R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 H Q TJI X H WO+LDH H LD sKs+ON HIDE LD 0 LEs H p H g OX RS g M 0 0 IL E.C INNA NUQEAR POWER PIANT Iaservtee~n Boundary Uae Ust'Ihbd Iaspee6on Interval PIIIDNo t 33013.1246-2 Qass I 3 System: ANOUARY COOIA.IT~Comp Type: PIPENC O H 0 RGAE Une No.GUbert Une No.ISI Slee~Fl.MatrL~h.Po~Tern Inf Lbe deseri remarks 6BAC6.152 6GAC6.152 6EAC6.152 6GWC6.152 4GAC6-152 3PWC6 152 2ILAC6.152 2GAC6 152 2DAC6152 2EAC6-152 2GWC6 152 2HAC6 152 2KACIL152 2N~152 2OAC6-I S2 2R4C6-152 2TWC6 152 I SD AC6 152 I SEAC6 152 I SP.AC6 152 ISO AC6-152 OC310 CC 230 CG160 CC.190,CG300 CC 160 CC 230 CG250 CC 260 CG300 CG230 CG270 CG230 CG320 CG310 OC 230 CG160 N/h N/A N/h N/h N/A N/h N/A N/A N/A N/A N/A N/A N/h N/h N/A N/A N/A N/A N/h G3 A53 C7 A53 G3 A53 G7 A53 G3 A53 G7 A53 G3 A53 G3 A53 G7 A53 G/A53 G3 A53 C7 A53 G3 A53 G3 A53 Gy A53 G3 A53 N/h N/A A53 N/A A53 N/A A53 N/h 6AN 6AN 6AN 6.00 4AN 3.00 2AXI 2AN 2AN 2AO 200 2AXI 2AN 2AXI 2AN 2AN 2AN ISO ISO ISO Q280 0280 Q2IN 0.280 0237 Q216 0.154 Q154 0.154 Q154 0.154 Q154 0.154 0.154 0.154 0.154 0.154 Q145 0.145 0.145 0.145 IWD.1220.1 IWD 1220.1 IWD 1220.1 IWD 1220.1 IWD.1220.1 fWD.1220.1 IWD.122Q I IWD.1220.1 IWD 1220.1 IWD 1220.1 IWD 1220.1 IWD-1220.1 fWD.1220.1 fWD.1220.1 IWD.1220.1 IWD 1220.1 IWD.1220.1 <150<200<150<200<150<200<150<200<150<<200<150<200<150<200<<150<200 c 150<200<150<200<150 c200<150 c200<150 c200<150 c 200<150<200<150<200<150<200<150<200 c 150<<200 c 150<200<150<200 COMPONENT COOUNG HE 10 4C, 773.COMP CLG HE 1O 760A tk BORIC AQD EVAP.4C TO COMPONENT COOLING PUMPS~BORIC AQD EVAP 10 COMP COOLING PUMPS.6B TO 773, NON REGEN HE, 778, 6E.6C TO 2'EDUCER BEFORE 764A, 2T.6B 10 7778.777C CS PUMPS h Ik B IO 6E.DISIILIATE COOLER TO 7488, 6G.6C TO DISIIUATE COOLEIL 68 IO Sl PUMP COOLERS.ll IO 6G.SI PUMP COOIERS TO 7~6K 68 1O 763, SEAL WATER HE.WASIE EVAP CONDENSING HE 1O 7648,60.SEAL WATER HX'IO 6E 3P TO 764A, EWD09.3P 1O CAS COMPRESSOR HE IL CAS COMPRESSOR HE B 1O 2H.3P TO GAS COMPRESSOR HE*GAS COMPRESSOR HE A TO 2IL R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 05/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 H CI VI rEs H fvf O+tfy H H tfy g 0 ffl H kD g ID 0 kO H o H'g<<" 8 o F3 R5 g H g 0 0 0 ',f I H R.E.CINNA NUQZAR POWER PIANT Inservice ExamhaUon Boundary Lhe Ust Tbbd tnspenhn Interval PddDNo r 33013.1247 Qass.: I System r AUXIUARY COOIANT-RHR Comp Type: PIPLNC O H 0 RUBE Une No.10A-AC/.2501% 10A-AC7.2501 B CBbert Une No.SWRI Une No.A.IS A376 A-14 A376 1a00 I AXIC 10AIC 1.000 ISI She'Ibkns Exemption~Fi.Matrl~In.~In.Basis NDE Method SUR/VOL SUR/VOL Po T~em ln7 Une deseri'emarks Y RHR FROM VALVE 700 TO 701.Y RHR FROM VALVE 720 TO 721.Revised A 06/93 A 06/93 0 M XH WO H'LO H~tI3+gOM I>U7O H~~tI7 H 0 H g 0 O bf R5 M 8 0 Ft Pe 0 0 IL E.CINNA NUCLEAR POWER PIANT Insertdee Euuninatkut Boundary Une Ust'T?dtd Inspecnon Interval PMD No t 33013 1247 Qass t 2 Systetn t AIUGUARY COOLANT RHR Comp 1)tpet OOMPONENIS RCtkE Une No.Gobett line No.&VRI line No.ISI~Fi.Matrk NDE Method Po~Tern In?Une deter('emarks CONTAIN SUMP B EAC02A FAC02B FACOSA FAC06B PACOI A PAGO IB RHR400 1247 1247 1247 1247 N/A B-109 B-109 N/A N/A B-23 B-28 aoo aooo IWC 122 lg)o.oo a Goo om aooo OAO OAXO IWC 1221(A)aoo aooo Iwc.1221(A) aoo aooo aoo Oixe h%.<200 410 350 410 350 410 350 410 350 CONCRETE SUMP EXEMPT FROM EXAMINAIIOXL RESIDUAL HEAT REMOVAL HEAT EXCHG R*RESIDUAL HEAT REMOVAL HEAT EXCHG R L RHR PUMP COOIER*RHR PUMP COOLER L RHR PUMP A, MFG PAQFIG RHR PUMP B, MFG PAQFIG R 11/91 R 11/91 R 11/91 h I I/91 h I I/91 R 11/91 R 11/91 H Q (/)X H XO+tO H HIOg O (/)HeO (/)tO Q g LO H 0 H'g g H 0)(D 0 ft 0 5 l I 4 II 9 I 1'I Ill 4 l h P t l 4 E I J k II I IL E.GINNA NUCLEAR POWER FIANT Insaviee Esutminsrion nounthsry Une Uss Ilr(nl I spection Intavel P&ID No: 33013.1247 Chss: 2 System: AUXIUARY COOIANT.RHR Comp I)rpe: PIPING RG&E Une No.GUbal Une No.SWRI Une No.Po~Tern In'?Une desai rernsrte IO.AC601 10hkC601 108kC601 IOGAG601 IUD.AG601 IOEkC601 I 0EEkGI 5 I IOG*G601 I OGGkC.151 ION.AG601 8 AG601 8AkG601 88-AC601 8CAC601 8DkG601 SE.AG601 SpkGISI SFFkG151 SEE-151 SXkC601 6kG601 6A.AG601 68kG601 6GAG601 6CSI-151 6DkG601 6DSI.151 6E AC 151 6XkC 151 6LACSOI 4hkC601 4C AG601 3A.AG601 38 AG601 2kG601 2hkC601 2B.AG601 2GAC4l 2F AG601 RHEA.2AkC601 RHEA-28kGSO I RHEA-2C AG601 RHEB.2A.AG601 IUIR.100 RHR~RHR~BHR~RHR400 RHR400 RH ROOD BHR~RH ROOD BHR450,BHR.400 BHR~BHR~BHR450 RHRO$0 RHRO$0 RH R~RHR~RHR~Sl 151 RHR~RHR-100 RHR.100 RHR~RHR~,RHR450 I O.RH.2013 10 RH.2001 IO.RH-2001 I O.RH-2004 IO.RH-2004 I O.RH.2003 10 RH 20C8 1051.2010 1081-2010 I O.RH.2007 B.RH-2010 8.RH.2010 8 RH.2008 8.RH.2008 8.RH.2017 8$1 2012 851.2009 8 RH-2018 6 RH-2015 6 RH4016 6-RH.2012 6-RH-2014 RH ROOD BUR~6$1.2011 6$I.2014 BHR~,RHR~RHRO50 RHR~CVC.IOO RHRA$0 6 RH.2011 8-17 8.22 8-20 8.20A 8-20 8-20 8-20 8-20A 8-20A 8-24 8-26 8-26 8-23 8.23 8-24 8-20A B20 8-19 8-26 817 818 8-25 B27 819 8-26 8.19 8.21 8-21 8 168 8-20 8.168 8-26 8.27 8-20A 8-25 8-24 8.24 8 17 8-109 8 109 8-109 8.109 A312 A312 A312 A312 A312 A312 A312 A312 A312 A312 A312 A312 A312 A312 A312 A312 A312 A312 A312 A312 A312 A312 A312 A304 A312 A312 A312 A312 A312 A312 A312 A312 A312 A312 A312 A312 IOASO IOA)0 10.00 IOAN IOAO I SAX)IOAC IOAe I DAN 10.00 SASO LOO SAN SAN LOO 8AS LOO SAN LOO 6Am 6Am 600 6Am 6.00 6Am MO SAN 6.00 6.00 4Am 4Am 3Am 3Am 2Am 2.00 KDO 2Am 2A)0 2DO 2.00 228 2AN (L365 L365 L365 IL36$0265 (L365 0365 0365 0265 0965 0922 0922 0922 L322 (L322 0922 (1500 0500 0.14S (L322 0280 0280 (L280 0280 OAXN (L280 OAXN 0.134 0.134 0280 OAXN OAXN OAXO 0.109 0.154 0.154 0.154 0.154 0.'I 54 0.154 0.154 0.154 IWG 1221(F)IWC 1221(F)IWG1221(F) IWG1221(F) IWG1221(F) IWG1221(F) IWC 1221(A)IWG1221(A) IWC!221(h)IWC 1221(A)IWC 1221(A)IWG1221(A) IWC 1221(A)IWC 1221(A)IWC 1221(A)IWG1221(A) IWG 1221(A)IWC 1221(h)IWC.1221(h) BUR/VOL BUR/VOL SUR/VOL SVR/VOL SUR/VOL SUR/VOL SUR/VOL SUR/VOL BUR/VOL SUR/VOL BUR/VOL SUR/VOL SUR/VOL SVR/VOL SUR/VOL SUR/VOL BUR/VOL SVR/VOL SUR/VOL SUR/VOL BUR/VOL SVR/VOL BUR/VOL SUR/VOL 350 350 Y 410 350 Y 410 350 Y 350 350 Y 350 3$0 Y 350 350 Y 350 350 Y 350 350 Y 350 3$0 Y 410 3$0 N 350 3$0 Y 350 350 Y 410 3$0 N 410 350 N 410 350 N 410 350 Y 350 350 Y 350 3$0 Y Y 410 350 350 350 Y 350 350 Y 350 350 Y 410 350 Y 410 350 Y 350 350 N 350 3$0 N 410 350 410 350 350 350 Y 410 350 N 410 350 N 350 350 Y 410 350 410 350 410 350 410 350 V720 TO REDUCER 10 X 6 BEFORE VALVE 717.VALVE 701 IHRU PEN PI 40 10 IST TEE.10"IEE FROM 10hkG601'10 VALVE 856.IEE ON I ODkG601 10 RHR PUMP*TEE ON IOA-AG601 TO RHR PUMP L IEE ON I ODkG601 IQ VALVE 850L VALVE 850B 10 1 ST REDUQNG EIBOW.VALVE 8$0A PAST IKE'IQ I OC AG601~VALVE 850k TO 1 ST REDUQNG ELBOW.CONI'.OF SBkC601 RED EIBOW 10 TKE.I O.AG601 IEE.RED 10 IEE PAST HVG624 10 X 8 REDUCER IQ RESIDUAL HEAT EXCHA.D5CHC RHR PMP A 10 1ST REDUQNC KUSOW.10'KE ON IOHkG601 TO RH EX IL D5CHG RHR PMP 8 10 1ST TEE AFIKR V710B REDUCER BEPORE VALVE 714 10 RH HT KXA.VALVE 851A 10 RED ELBOW BY VALVE&50A.VALVE 851B 10 RED ELBOW BY VALVE SSOL 6 X 8 REDUCER ON 6GSI.151 10 S X 10 REDUCEL RES HEAT EX B 10 8 X 8 X 6 REDVCKR IKE.VALVE 852h 10 IO.AC601 IN CONT.VALVE 8528 TO 10kG601 IN CONT.10kC601 10 I OHkC601.8AkC601 10 VALVE 857C.VALVE 857C 10 6 X 8 REDUCER.8X.AC601 IQ VALVE 857L VALVE 857B 10 6 X 8'IKE.10'EE ON IDEE.AC 151 TO VALVE IS IBL 10'EE ON IOGG.AC 151 TO VALVE IS13A.4GAG601, I S16B 10 1816k, 4CSMOI 108-AC601 10 4 X 3 RDCR ON 3A AC601.6CkG601 10 VALVE 1816L SX*G601 TO 4 X 3 RDCR ON 4A.AG601.6GAG601 10 4A.AG601.I OA-AG601 10 VALVE 252.10-AG601 10 IOB.AG601. SC AG601'10 VALVE 1812A.SKAG601 TO VALVE 1812L 10-AC601 10 VALVE 702, 2FQI401.RESIDUAL HEAT EXCH.h 10 VALVE 807G RESIDUAL HEAT EXQL h 10 VALVE 807D.RESIDUAL HEAT EXCH.A 10 VALVE 807F RESIDUAL HEAT EXCH.B TO VALVE 8078.R I I/91 R I I/91 R 11/91 R 11/91 R 11/91 R I I/91 R 11/91 R I I/91 R 11/91 R 11/91 R 06/93 R I I/91 R 11/91 R 06/93 R 11/91 R 06/93 R 11/91 R 06/93 R 06/93 A 11/91 R 06/93 A 11/91 A 11/91 R 11/91 R I I/9I R 11/91 R 11/91 R 11/91 R I I/91 0 M XH RO+U)H HIA)g+OM H'Q 0 IO H p 0 d O Pd 0 M (D ()ct 0 IL E.GLWA NUCIZAR POWER PLANT lnsetrice Exandnatioa Boundaty LIne ust'IIdrd Inspection Intetval PIHD No..: 33013.1247 (Cote'd)(2ass t 2 System: AUXIUARY COOLANT.RHR Co PTYPes PIPING ROTE GBbett LIne No, LIne No.RHEB-2BAC601 RHEB-2CAC601 125A-AC601 SWRI IIne No.ISI~FI~MstsL 8-109 A312 8.109 A312 8-24 2'L154 2.00 0.154 125 IL000 IWC 1221fjg IWC 1221(A)IWC 1221(A)410 350 410 350 Exen ptxnt B M M~po~T~RESIDUAL HEAT EXCH.B TO VALVE 807F.RESIDUAL HEAT EXCH.B TO VALVE 8070.10H<C601'IO CAP.R 11/91 R I I/91 A 11/91 H 0 H 0 U)g H (x)A+IOH H IO g+O(/)%O H~g IE)H p (x)5 g H 0 M (D n po 0 I il i I II I L E, GDINA NUQEAR POWER PIANT hservke Erosmhsrha Botmdnry Lhe Ust Third speetioa hatererrI P&ID No-t 33013 1248 Qsss.: 3 Systera t AIDOUARY OOOUNGSPENT FUEL Comp IFPe: COMPONENIS RG&E Lhe No.ISI She~Ff.MntrL~h.NDE Method Po~Tern Inl LIne desert remnrtts O H 0 EAC13 PAC07B TAC03 N/A N/A N/A 0.00 OAN OAR IL000 IWD 122tL2 OAXO IWD 122sX2 0.000 IWD-122tX2 <275<200<275<200<275<200 SPENT FUEL POOL HEAT EXCHGR IL SPENT FUEL POOL REQRC PUMP L SPENT FUEL POOL A 11/91 A 11/91 A 11/91 0M g H WO+'4 H H M7 g+0M H t17O MIO+~'LO H 0 H'g Q CN 0 M 9 0 I 0 II I I h'8 t ,'1 I r 1'*I IL E.GINNA NUQZAR POWER PIANT Insaviee Ensminstba Bonrsbry Uae Ust TMrd Inspection Intavnl P8tID No t 33013.1248 Qsss.: 3 Systan t AUXHJARY ODOUNGSPENT FUEL Comp T7pe: PIPING RGRE Lbe No.151 Slee Takes~FI.MetrL~b.~b.Po~Tern In7 Lbe deseri remarks n Q 8AAC&151$FP 8&AC&151$FP 8CAC&ISISFP 6A~I 5 1 SFP 6BAC8 151$FP 6OAC&151$FP 6DAC&151$IP 6EAC8-151 4h.AC8-151 4BAC8.151 eohc&I 5 ISFp<D.AC&151$FP 4E.AC&I 5 IS FP 4FWC&151$FP 2AWC&151$1P 2&AC&I 5 I SIP N/A N/A N/A N/A N/h N/h N/A N/A N/A N/A N/A N/h N/h N/h N/h N/A 8AO OANO 800 tX000 8AXI OAXO 6A6 IX000 6AO OAXO 6AO 0.000 6AS OAXS 6.00 OAXS 400 0AXXI 400 OAXO<AO OANO 4AI OAXS 4.00 OAIO 4.00 OAXO 2.00 OAXI 2AO OAXO IWD.122IL2 IWD 122IL2 IWD12202 IWD.12202 IWD.I 22sX2 IWD.122sL2 IWD 12202 IWD 122IX2 IWD-1220.1 IWD 1220.1 IWD 1220.1 IWD.1220.1 IWD.1220.1 IWD.1220.1 IWD 1220.1 IWD-1220.1 <275<200<275<200<<275<200<275<200<275<200<<275<200<275<<200<275<<200<C fk ID TO 6A R 68 It 8657>SFP PUMP IL 6C 1O SPENT FUEL POOL HE IL SPENT FUEL POOL HE B 1O 6D.8A IO VALVE 8662.8A 1O VALVE 865L SPENT FUEL POOL REQRC PUMP B TO 8IL 8C TO VALVE 8663, 6E.6D'IO SPENT FUEL POOL SPENT FUEL POOL TO 4'ALVE 782 SPENT FUEL POOL 1O<D, VALVE 781.VALVE 782 TO 8A.VALVE 781 TO 8'D'IO VALVE 8614.6D 1O VALVE 86&4 6C 10 VALVE 8661.6D TO VALVE 8632.A I I/91 h I I/91 A I I/91 h I I/91 A II/91 A 11/91 A 11/91 A 11/91 A 11/91 A 11/91 A 11/91 A 11/91 h 11/91 A I I/91 h 11/91 h 11/91 m Q Ul~g Q gH'g XO'Z g 117 H$+o p/lope I raw'tl70gH tO H Qee HgQ UI tD 0 0 0 4 l 1 II IL E GINNA NUCLEAR POWER PIANT Insenrlot~n Boundary Une Lbt TMtd lnspecfion Interval P&ID No t 33013.1250 I Qass t 2 System t SERVICE WATER Comp~COMPONENTS O H 0 RG&E IAne No.0Ebett SWRI IAne No.Line No.Size TMms~tn.~in.Po~Tern In?Line dcsefi remarks PSIOIA PSIOI B PSIOIC 1262 1262 1262 N/h N/A N/A OAO OAXN OAN OAXN DAN 0.000 NO IWA, NO IWA NO IWA 1550 200 1550 200 1550 200 THIS PUMP ACCOUNTED FOR ON 33013.1262. THIS PUMP ACCOUNTED FOR ON 33013 1262.'IHIS PUMP ACCOUNIKD FOR ON 33013 1262.R 06/93 R 06/93 R 06/93 H 0 M g H WO+'4 H HMIg O FAT L M3n H LOS Q H 0 H g Q H OW wa g H 0 (0 8 0 Ft 0 k d'i R E.GINNA NUI2KAR POWER PIANT Inserviee Rammed Bonndary Une Ust Third Inspectha Interval PBID No: 33013.1250.1 Class r 3 System: SERVICE WATER Comp Types COMPONENTS 0 t3 H 0 RQkE Une No.AAAOIA AAAOI8 hhh02A hhh028 AAA03A AAA038 AAA03C AAAOS ESW08A ESW088 ESW09h ESttT68 PSWOIA PQVOI 8 PSWOIC PSÃ01D 0Eber!Une Na SWRI ISI N/h N/A N/A N/h N/h N/A N/A N/A C37 C38 N/A N/A Sian TIdms~in.~In.OAO OAXO OAO OAXXI OAO OAXS OAO OAXO OAXI OAI00 IGLOO OAXO IGLOO OAXO OAO OAXO 0.00 0.000 0.00 0.000 0.00 0 AXE DAO OAXS OAIO OAXO OAO OAXXI OAXI OAXO OAO OAXIO IWDI2sXLI IWD 1220.1 IWD-122LI IWD 1220.1 IWD.1220.1 IWD-1220.1 IWD122IX I IWD 1220.1 NO IWA NO IWA NO IWA NO IWA NO IWA NO IWA NDE Metlsod Po T~em In?line deserI'emarirs CHARGING PUMP A AIR COOLKL CHARGLVG PUMP B AIR COOLEL RHR PUMP A AIR COOLKL RHR PUMP 8 AIR COOIKIL SAFEIY INJECIION PUMP A AIR COOLEIL SAFKIY INJECIION PUMP 8 AIR COOLEIL SAFEIY INJECIION PUMP C AIR COOLEIL PENETRATION AIR (XRLEIL THIS COMP ACCOUNTED FOR ON 33013-1239. THIS COMP ACCOUNIKD FOR ON 33013.1239. THIS COMP ACCOUNTED MR ON 33013.1239. THIS COMP ACCOUNTED MR ON 33013-1239. SERVICE WATKR PUMP A SERVICE WATER PUMP L SERVICK WATER PUMP C.SERVICE WATER PUMP D.R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 H 0 F/I g H X 0 t0+II3H HIDE O F/I Heg II3 0'Q H o H g Q R5 g H 0 II L E s 4'!K II/8 IL E.GINNA NUCLEAR POWER PLANT Insersioe Exasnination Bonsahuy Une Us!Thinl Inspeesion Isnerval P&IDNo s 3301312501 Chss-s 3 Syssesn s SERVICE WATER Cosnp Types PIPING RG&E Une No.Po These In?Une desesi sesnarks H 0 20ASWO.125.9 20SSWO.1289 20ESWO 125 I 20FSWO 125-1 20CSW0.125 I 20HSW0-125.1 20ISWO.125-1 16ASWO.125 I 16SSWO.1 25-9 16GSW0.125-9 16DSWO 125.1 14ASW0.125 I 14BSWO.125.1 14CSWO.125-1 14DSWO-125-1 14ESVt0125.1 14KSVQ 125-1 I 0BSWO.125.1 8ISVQ.125-1 6ASVQ 125.1 6GSW0.125-1 4ASWO.125.1 4CSW0.125.1 4ESVQ 125.1 4ISWO 125-1 4LSWO 125-1 3ASWO 125 I 3CSWO-1 25.1 3DSViO 125.1 3ESWO.125 I 3FSWQ.125 I 13ASVQ 125-1 13GSWIL125-I 'I 3ESI5Q-125-1 13FSV Q 125.1 135ASVQ.152M 135SSWQ 152M SW.1850 SW.1850 SW.1500 SW.1500 SW.1500 SW.1400 SW.1850 SW.1850 C17 G17 G17 G12 C 17 C.12 C.16 C 16 G13 C16 C 16 C 17 C 17 C17 C17 G16B G13 G13 CD G13 G13 G13 C13 C-13 G13 C 17 N/A Nlh C.12 G12 Gl I N/h N/h N/h N/A N/h N/A 20Am 20AO 20.00 20.00 20.00 20.00 16.00 16.00 IMO IMO 14Am 14AO 14AN 14'4'4Am IOAS SOO MO 6AO 4.00 4AS 4AO 400 400 3.00 3Am 3'Am 3AN 130 130 130 135 135 0375 0375 0375 0375 0375 0375 0375 0375 0375 0375 0375 IL375 0375 0375 0375 0375 0375 0375 (L327 0280 0280 0337 0.237 0.237 0.237 0.237 0.216 0316 (F16 (L216 0.216 0.145 0.145 0.145 0.145 0.000 OAXN IWF-123g-IWF-1230 IWF-1230 IWF 1230 NO SUPPORTS NO SUPPORTS IWD-I ZKL I IWD.1220.1 IWD 1220.1 IWD.1220.1 IWD-I ZKL I IWD 1220.1 IWD 1220.1 IWD-1220.1 IWD.1220.1 IWD.IZKL I IWD IZKLI IWD 122ILI IWDI 220.1 IWD 1220.1 IWD.1220.1 IWD1220.1 75 80 t 75 80??2???75 80 2 75 80?75 80?75 80 2 75 80 2 75 80 75 80 75 80 t 75 80 2 75 80 t 75 80?75 80?75 80?75 80 2 75 80 t 75 80 t 75 80?2 2 75 80?75 80?75 80?75 80?75 80 t 75 80 75 80?75 80?75 80 2??20E TO 20F, 4665 (BURIUED). 20C TO 20H (BURR!ED). 14A, 14B IQ 20A.20A TO 4616, 4610.14C, 14D IQ 20IL 20B TO 4615, 4779.20B TO 4640, 16A.16C IO 4623, 20I.20B TO 6A (BURIUED). 20A TO 16A (BURRIED). 201 IO 14E.SERVICE WATER PUMP A TO 20E.SERVICE WATER PUMP B TO 20E.SERVICE WAIER PUMP C TO 20G.SERVICE WATER PUMP D IO 20C.16A IO 4627 6IL 4665 TO 4A, I OIL 14K IQ 4613.20E IO 4609.16B TO 4668B, 4l.4C, 4 E TO 10'EDUCER.14K TO DIESEL C ENERAIQR A COOLERS.DIESEL G ENERAIOR A COOLERS'IQ 4671, 60.DIESEL C ENERAIQR B COOLERS'IQ 4672, 6G.14K IO DIESEL GENERATOR B COOLERS, 46688 14B IHRU 4612, 4611 IO 14G 41 IQ 4668F.4A IO 466?F.20F TO 4739, 4769.20H IO 4738, 4754.4753 IO 4739A, 47398, DISCHARGE CANAL 3D IQ 51 GOOIER 3, 3F.3D IQ Sl COOLER I, 3F.3D TO 51 COOLER 2, 3F.3D TO PEN COOLER, 3F.4789, 4790 TO.75A, 51 PUMPS.Sl PUMPS,.75A IO 3f.R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 05/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 H CI (/)X td XH W A+M)H V HIE)g+O(/)H'N 0 0)LDQ g'LO H 0 H g Ra g H 0 0)(D 0 r.0 4 lI~~4~'4 IL E.CINNA NUCLEAR POWER PIANT Inserrrice Exnminntion BoundnrF LIne ust Tldrd InspeetNn Intervni RG&E LIne No.CBbert Lbe No.P&ID No t 33013 1250.2 Qass t 3 SFstern r SERVICE WATER Comp Tamper COMPONENIS NDE Method Po T~em IIn7 IIne deseri'nrnnrlrs A H 0'g AFAOI A AFAOI 3 EACOI A EAOOIB FAC12 EAC13 EACI 4 N/h N/h O41 O41 N/A N/A 0.00 OAXS OAS OAXSO IGLOO OAXO OAQ OASOO 0.00 ILOOO IGLOO OAXS OAXr OAXS IWD IX/0.1 IIVD 1220.1 IWD 12202 IWD.12202 IWD-12202<275<<200<275<200<275<200 STANDBY AFW PUMP ROOM COOLING UNIT A.STANDBY AFW PUMP ROOM COOUNC UNIT IL THIS COMP ACCOUNTED FOR ON 33013-1245. THLS COMP ACCOUNTED FOR ON 33013-1245. STANDBY SPENT FUEL POOL HEAT EXCHGR.THIS COMP ACCOUNTED FOR ON 33013-1243. SPENT FUEL POOL HEAT EXCHC R h.R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 H~0 F/I~QQ't3 Q H XHR WAR tC P g LI3 H)5 Pa s=s Ul n ta I W td U g LO Q g H LI3 H 0 e Cr HQ0 0 'I H h I IL E.GINNA NUCLEAR POWER PIANT Insatriee Buuninnthn Bontshty Lhe I)st I)i)n)Inspecthn Intavn)PAID No-1 330)3-1250.2 Chss t 3 Systan t SERVICE WATER Comp I?pet PIPING H 0 RUBE Lbe No, Gilbat Une No.SWRI LIne No.ISI Slee Fli).)4sttL~h.Po T~em lnt 20CS)t0 125.12 20DSWO 125 I 18ASSIL)25 I 16ESWO.)25.1 14FSWO 125)14GSWO 125.1 14HSWO)25 I 14)SWO 125.1 I?TWO 125 12 12SSW0.125.12 12CSVIL)25-I 12DSV9.125.1 10DSVIL)25-I 10ES)AIL') 25 I 6CStt)L)25-I 6DSWO.)25.12 6ESV)L125 I 6FSWO.)25.12 6ISVO 125.1 4 TWO 152S 4GSWO 152S 4KSWO 152S 3BSWO 125 12 XSESWO.)25 I 2ASWO.)52S 2BSW0.1 52S I SSSWO 1525 I SDSWsLIS2S 1~)52S SW-1120 SW.)100 SW.1000 SW-)100 SW.)100 SW.)000 SW.)000 SW.1020 SW.)120 SW-1120 N/A A53 C 11 A53 C 12 A53 C 12 C.l)A53 C 11 A53 C 12 A53 C.)2 A53 N/A N/h N/h N/A C 12 C)1 C 12 A53 C 11 A53 C 11 A53 C 11 A53 C.)2 C 27 A53 C 26 A53 G29 A53 C I)A53 N/A C.I)A53 N/A A53 C 29 A53 C 29 A53 N/A 20.00 20AO 18.00 16.00 14.00 14.00 14AO 14.00 12AO 12AO)2AO 12AO)MO IMO 600 6AO 6AO 6AO 6AO 400 4.00 400 3.00%SO 2.00 2AO)M)M'I 50 IL375 IL375 0075 IL375 a375 0975 0975 0275 0975 0375 0375 L375 sL375 sL280 IL280 IL280 IL237 IL237 0.237 0.216 0~0.154 0.154 sL)45 0.145 0.)45 NO SUPPOR'IS IWD.)22sL2 IWD.)22sL2 IWD.)2202 IWD-122')2 IWD 122tL2 IWD 12202 IWD 12202 IWD)22sL2 IWD-122Q2 IWD.)22IL2 IWD 1221)2 IWD.1220.1 IWD 1220.1 IWD 1220.1 IWD-1220.1 WD-)220.1 IWD.)220.1 IWD.)220.1 IWD 1220.1 IWD.)22IE) IWD 1220.1/5 80 t 75 80?75 80?t 75 80?75 80?75 80 t 75 80'???t t??75 80 t 75 80?75 80?75 80??75 80?75 80?75 80?75 80??75 80?75 80?75 80?75 80??12A, 128 10 BURRIED DLSCHG SIRUC 14F, 14G 10 BURRIED DISCHARGE, 20F 10 141, 6C 4610 TO 20K CCHE A 10 20D.CCHE B TO 20D.20H TO CCHE IL 18A 10 CCHE*CCHE h 10 20C CCHE B 10 20G)OD TO SFPHE L SFPHE B 10 IOE.)4H 10 12C.12D 10 14F.18A 10 SFPHE A.6E 10 20C.SFPHE h TO 20D (DISCHARGE). 20D TO 8686.14)10 8687.14H 10 96268, 96278.IL 9629)L 20F 10 9626A, 9627A, IL 9629A.4F 10 9628A, 96288, 4G.3F 10 6D.12D TO 8633, 8634, 10E.14F TO)SD.20C IO)AIL 28 10 ROOM COOLING UNIT B, 4F.2A 10 ROOM COO)DIG UNIT A.40.2A TO 9635, 2)L R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93-R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 Q M Q H WO+LE)H H~g O F/)~)13 0 tA)H)Es Q o H g 5M 0 4 Fi Ul 8 0 0 )II h N)I II fl II a 1~t I I!is P C' R.E.GINNA NUCLEAR POWER PIANT Inservice Exam(nadon Bonndary Une Ust TIdrd lnspeedon Interval P&IDNo r 33013-12503 Qass r 2 System r SERVICE WATER Comp TTper COMPONENIS RC&E Line No.SWRI Une No.ISI S(re Ihhrs~Fi.MatrL~h.~in.NDE Method Po~Tern In?Une deseri n/remarla ACADIA ACAOI B ACAOIC ACAO ID ACAOI E ACAO IF ACAOLO ACAO IN ACAOI J ACAOIK ACAOIL ACAOIM ACA02A ACA02B ACAOT ACA08 ACA09 ACAI0 N/A N/A N/h N/A N/A N/A N/h N/h N/A N/A N/A N/h N/h N/A N/A N/A N/A N/h OAN OAXN OAN OAXN OAN OAXN OAN 0.000 OAN 0.000 OAN OAXN OAN OAXN 0 AN OANO OAN 0.000 0 AN 0.000 OAN OAXN OAN OAXN OAN OAXN OAN OAXN OAN OANO OAN OANO OAN OAXN OAN OANO IWC 12/.l(C)IWC 1221(C)IWC.1221(C) IWC 1221(CI IWC 1221(C)IWC 1221(C)IWC.1221(C) IWC!22 1(C)IWG I 22 I(C)IWC 1221(C)IWC 1221(C)IWC 1221(C)IWC 1221(C)INC 1221(C)IWC 1221(C)IWC 1221(C)1th'G 1221(C)IWC 1221(C)CONTAiiVMENT REQRC FAN A COOLER~CONTALIMENT RMRC FAN B COOILR.CONTAINMENT RMRC FAN C COOLER.COiVTAINMENT REQRC FAN D COOLER~CONTAINMENT REQRC FAN h COOLER~CONTAINMENT REQRC FAN A COOLER~CONTAINMENT RMRC FAN B COOLER.CONTAINMENT REQRC FAN B COOLER.CONTAINMENT REQRC FAN C COOLER~CONTAINMENT REQRC FAN C COOLER~CONTAINMENT REQRC FAN D COOLER~CONTAINMENT REQRC FAN D COOIER.REAC TO R COMPARTMENT COOLER A.REAC TO R COMPARTMENT COOLER L CONTAINMENT REQRC PAN B COOLER.CONTAINMENT RMRC FAN C COOIER~CONTAINMENT REQRC FAN D COOLER.CONTADi VENT REQRC FAN A COOLER~R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 H~~xca I.Q (/)~g Q t9 4 H XHR Er(0 Z t0 P H IEs H f g Pa o(/JAPa I>I WXa H L(2 A 5 W Q e(TJ HQQ (/2 I n 0 0 J k ll 1f I'P l~l 1 IL E.GINNA NUCLFAR POWER PIANT Insettrke Exaehu&n Boundasy Line I)st Ihin)Intpeedon Intava)BklD No t 33013 12503 Qass.t 2 Syttem t SERVICE WATER Comp Iypet PIPING O W 0 RUBE Une No.CBbett SWRI LLinnte eNo line No.in)8SW.125 8ASW.)25 8BSW.125 BQSW.125 8DSW.)25 8ESW.)25 8FSW.125 BCSW.125 BHSW 125 BISW.)25 BISW 125 BKSW-125 8LSW.)25 8MSW.)25 BNSW.)25 BOSW 125 6SW-125 6ASW.125 6BSW.125 6QSW 125 6DSW 125 6ESW)25 6FSW.125 6GSW.)25 4ASW-125 4BSW 125 4CSW 125 4DSW.)25 4ESW 125 4FSW.'I 25 4CSW.125 4HSW-125 4ISW.125 4ISW 125 4KSW 125 4LSW.125 4MSW.125 4NSW 125 4QSW)25 4PSW.)25 4QSW.)25 4RSW 125 4SSW.125 SW.WO SW.)CO SW.700 SW.)500 SW.)400 SW 100 SW.)500 SW.1400 SW.)50 SWS00 SW.)500 SW.)4(O SW-200 SW.)500 SW.)400 SW.TOOL.)500 SW-1400 SW-200BW.)500 SW.)400BW 150 SWSOOBW 1500 SW WO~.200 SW.500BW-) 500 BS3 B-53 8-52B 8-528 8.52 8.52 8 SIC 8-5)B BS)8-51 8-50A 8-SOA 8-50 8-50 8.53A 8-53 8 528 8.52 B-5)C 8.51 B.SOA 8.50 8-50 8.50 BSO B.SOA 8-50A BSOA USIA BSIA USIA 8-518 B-S)8 B-S)B B-52A 8-52A 8-52A 8-52B 8.52B 8.53 8.53 8.00 BAO 8.00 8.00 8.00 8.00 BAO 8.00 L00 8.00 8.00 ILOO 8.00 8AO 6AO 6AO 6.00 6.00 6AO 6.00 6.00 6.00 4AO 400 4AO 4AO 4AO 4.00 4.00 4.00 4AO 4AO 4.00 4.00 4.00 4.00 4.00 4.00-4.00 G322 G322 OB22 OB22 (L322 OB22 OB22 G322 G322 OB22 OB22 0322 G322 OB22 G322 G322 G280 0280 0280 0.280 0.280 0.280 0.280 0.237 G237 OB37 G237 OB37 0237 G237 G237 0.237 IL237 OX'237 OB37 OB37 0.237 0.237 0.237 G237 G237 IWC 1221(h))WC)22)(h) IWC 1221(A)IWC 122)(h)IWC 1221(A)IWC)221(A))WC)221(h) IVi&)221(h)fA&122)(h) BY&1221(h) lta&1221(A) IWC.)221(A) IWC.)221(A) !WC)221(A) IWC 1221(A)IWC 1221(A)IWC 122)(A)IWG 1221(A)IWC 1221(A)SVR/VOL SUR/VOL SUR/VOL BUR/VOL SUR/VOL SUR/VOL SUR/VOL SUR/VOL SUB/VOL 5UR/VOL BUR/VOL BUR/VQL SUR/VOL SUR/VOL SVR/VOL SUR/VOL BUR/VOL SUR/VOI.SUR/VOL SUR/VOL SUR/VOL SUR/VOL SUR/VOL SVR/VOL VALVE 4644 TO 8'KE BY PKN 323 OUT CONT PEN 323 TO D REQRC FAN COOIKR.D REQRC fhN COOLER'IO PDI 3)2.RED ElBOW AFIKR PKN 3)2 IO VALVE 4642.VALVE 4643 TO 8'IKE BEFORE PEN 315.RED EL PAST P315 IO C RKQRC f AN CQOIKR~RED EL PAST P320 IO C REQRC FAN COOLER.VALVE 4641 TO RKD K)BOW PAST PEN 32G VALVE 4&30 TO)ST 8'KE BY PKN 311.RED EL BY P311 TO B RKQRC FAN COOLER.B REQRC fhN COOLER TO PKN 316.RED K(BOW AFTER PEN 316 TO VALVE 4628.VALVE 4629 TO 8'EE BY PEN 3NL RKD EL BY F308 IO A REQRC FAN COOLER.A RKQRC FAN COOU)TO RKD EL BEFORE P319 RED FIBOW BY PEN 319 TO VALVE 4627.8" IKE BY PEN 323 IO)ST RED ELBOW.RED EIBOW BEFORE 8 AFTER PEN 312.8'KE ON 8DSW 125 TO PEN 315.RED ELBOW IN COiNT Bt OUT CONT AT PEN 320.8'TEE BY PEN 311 It)RED ELBOW PEN 311.RKD ELBOW BE)ORE 6 AFIKR PEN 316.8'EE BY PKN 308 IO 1ST RKD ELBOW 308.RED ELBOW PEN 319 IN CONT TO 319 OVT CON 8 X 4 RDCG ELL TO RDCR ON FCU 1%SUPPLY.8 X 8 X 4'IKZ IO RDCR ON FCU I h SUPPLY.8 X 4 RDCR'IO KU I-A SUPPLY.8 X 4 RDCR TO RDCG ELL ON FCU 1%RETURN.8 X 8 X 4 IKKIO RDCG KLLON FCU)*REIURN.8 X 4 RDCR TO RDQG KLL ON FCU I A RETURN.8 X 8 X 4 TEE IO RDCG ELL ON KU I 8 SUPPLY.8 X 8 X 4 IKE IO RDCG ELL ON KV).B SUPPLY.8X4 RDCRTORDCG FLLON KU I 8 SUPPLY.8 X 4 RDCR IO RDCG ELL ON FCU I.B RETURN.8XBX4 TEE IORDCG ELLON KU 1.8 REIURN.8 X 4 RDCR TO RDCG ELL ON KU I 8 REIURN.8 X 8 X 4 TEE TO RDCC ELLON KU)@SUPPLY.8XBX4IKEIORDCG ELLON FCV liCSUPPLY. 8 X 4 RDCR TO RDQG ELL ON FCU 14: SUPPLY.8 X 4 RDCR IO RDQG ELL OiY fCU)C RE)URN.8 X 4 RDCR TO RDCC ELL ON FCV)C RETURN.8 X 8 X 4'IKE IO RDCR ON FCU I D SUPPLY.8 X 8 X 4 IKE IO RDCR ON FCU I D SUPPLY.R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 05/93 R 06/93 R 06/53 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 0 (0 X H WO H)K)H@O(/)I>M)O H tK)I-3~u)H H g Ra g H 0 (/)(D 0 rt 0 m t C r 1 1 I't I'I P J I C 4 h 4 I~4 I IL E.GINNA NUCLEAR POWER FIANT Inserviee Xamlnation ~Une Ust IMrd nspeedon Interval PMD No.d 33013.125(L3 (Core'd)Gsss--: 2 System.: SERVICE WAIER Comp Type: PIPING H 0 RGSiE Une No.0dbert Une No.SWM Une No.ISI~Fi.Met>L Site IM>ns Exemption~in.~h.NDE Method~Tern fn?Une deseri'/remarLs 4T~.125 4USW.125 4VSW-125 4WSW-125 3ASW-12$3BSW 125 XSASW.125 2$BSW-125 25CSW.125 2$DSW-1 25 25ESW-125 XSFSW.125~SW-125 2$HSW.1 25%SIC.1 25%Sly.125 2.5K'.1 25'hSLSW.1 25 2ASW-125 2BSW-125 2CSW-125 2DSW.125 2ESW.125 2FSW.125 2GSW-125 I dhSW-125 SW 1410 SW400 SW~SW 1550 SW.1410 SW~SW400 SW.1550 SW.1410~400 SW ASKEW.1550 SW.1 410~400 SW4XXLSW.I 550 8-53 A53 BSSA A53 BSSA A53 S$3A A53 N/A B$28 A53 N/A A53 N/A A53 Nfh A53 N/A A53 N/h A53 N/A A53 N/A A53 N/h A53 B40 B.S I 8-52A 8.53 Nfh A53 N/A A53 N/A A53 N/h A53 N/A N/A N/A BSOA 4Ae 0237 4>00 IL237 4Am IX237 4Am IL237 300 11216 3Am OAXN 250 (L203%SO IX203 X50 (L203 IX203%50 IL203%50 IX203 LSO IX203 250 0.203%50 OANO%50 OAXO%SO 0.000%SO OAXN 2.00 0.154 2Am 0.154 2.00 0.154 2Am 0.154 uu aOOO 2AXs 0.000 2Am OAXN WO OAXN IWC 1231(h)WGI221(h)IN&1221(h) IWG 1221(A)IWG 1221(A)Pi%1221(A)IWC 1221(A)IWC 1221(h)IWC 1221(A)IWG 1221(h)IWC 1221(A)IWC 1221(h)IWC 1221(A)IWC 1221(h)INC 1221(A)IWC 1221(A)IWC.1221(h) IWG 1221(A)IWC 1221(h)IWC 1221(A)IWC 1221(A)IWC 1221(A)IWC 1221(A)IWG 1221(A)IWC 1221(A)IWC 1221(A)S X 4 RDCR TO 4 X 3 RDCR OV FCU I-D SUPPLY.8 X 4 RDCR IO RDCG EU ON FCU I-D RETURN.8 X 8 X 4 TEE'IO RDCG ELL ON FCU I-D RETIIRN.8 X 4 RDCR IO RDQG ELL ON FCU I D RETURN.CROSS CIXVNECT FOR ACA07, M, 6 IIL FCU 14: RETURN IO 8"IKE.VALVE 4636 TO 25 X 25 X 2 IKE PAST PEN 201~1ST ELBOW PAST PEN 201 IO ACA02!L REAC IO R COOLKR ACA028 TO PEN 209.LS X hS X 2 TEE BY PEN 209 IO VALVE 4635.VALVE 4758 TO 25 X XS X 2'IKE BY PEN 209.IST RED ELBOW BY PEN IN CoiNT TO ACA02A.REAC TO R CtmLER ACA02A IO PEN 201.XS X RS X 2 IKE BY PEN 201 I0 VALVE 4757.SN THRU ACAIO, TO SML SJ THRU ACA07>TO 81.SF THRU ACA08, TO BE.88 THRU ACAO9>IO SA.25 X 2$X 2 IKE AT PEN 201 1ST RED ELBOW.RED ELBOW BY PEN 209 TO 1 ST 2'KE.25 X 25 X 2 TKE SY PEN 209 1ST RED ELBOW.1ST RED ELBOW BY PEN 201 IO 2'EE.2$ISW.125 PAST VALVE 4794F.XQSW.125 PAST VALVE 4794K.VALVE 4794 0 IO%SF'-I 25.SM IHRU VALVE 4773 TO 2E.R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06f93 R 06/93 H~0 (I)~Q A R4H MHZ (x)ON WP gtA)H/Q O(/)OPS~&XIV HgQ g 0 M (t)()r.0 0 J a C j'l I il h l t t f I 1 f N'4 IL E.GINNA NUCLEAR POWER HANT Insersloe Exatnlnadon Bonndaty Une Ust TIdtd Inspectbn Intesval PSID No-: 33013 12508 Chss: 3 Systetn t SERVICE WATER Con PI?P s PIPD 8 ROSE Une No.14ISWO.I25.I 14LSSO125 I I OASIi0125-I IOCSV 0 125-1 BASWO 125 I BBSWO 125 I BCSWO 125 I BDSWO 125-1 8ESWO 125.1 BFStiO 125-1 BGSW0.125.1 BHSWO 125.1 6BSWO-125 I 4HSWO.I25-1 4ISWO 125 I 3GStaO125 I 2$ASWO.I25 I LSBSNO 125 I RSCSW0.125-1 XSDSWO 125-1 GBbett No.SW.1400 SW-1400 SW-1500 SW.1500 SW.1500 SW-1400 SW-1410 SWRI Une No.I51 C 14 A53 GH GN A53 CI6 C I6B A53 G16B A53 CI6B A53 C N A53 C.14 A53 C.14 A53 C.14 A53 C16B A53 C 18 A53 C 18 A53 C 18 A53 GN G16 A53 N/A A53 N/A A53 N/A A53 IWD.1 220.1 IWD.1 220.1 IWD-1220.1 IWD 1220.1 IWD 1220.1 IWD 1220.1 IWD.1220.1 14AO 0975 I 4AO 0975 NO SUPPORTS 10.00 0375 IGLOO 0375 8.00 OB22 MO 0922 NO SUPPORTS 8AS IL322 8AO 0322 SOO IL327 MS 11327 MO 0327 BAD tl327 NO SUPPORTS 600 (1280 4AO 0~4'L237 3'L216%SO 11203%50 02C8%50 02C8 2.50 0.203 NDE Method 75 80??75 80??75 80?75 80?75 80?75 80?75 80?75 80?75 80?75 80?75 80?75 80?75 80'??75 80?75 80?75 80?75 80?~T~In?LI d ICA IQ 4561, DISCHARGE CANAL BYPASS FOR 4561 FROM 141 THRU 45&L BD, 8E IO 14 REDUCER, 14L 16D IO 4614 HE IO 4642.HE TO 4628.14 E IO 4i41.4644 TO I Oh.4643 IO IOA.4630 IO 14l.4629 IQ 14 X 14 X 8 TEE, 14J.14E TO 4i27.4H,4l TO 14L 4551A IO 6BSW0.125 I.4652A TO 6BSWM25-1. 4i24C IO 14I.HE IQ 4625, 4i26, 16D.XSA'lO 4i35, 4757.4i36 IO 41.4758 TO XSL R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/58 R 06/93 R 06/93 R 06/93 R 06/93 H 0 I-I~4 0 TAI~gQ Q4H MHZ%OR~t53 H$Q o pn O ta~I<Ca~MXXU tCI H oem HgO 0 I II I I ff ,t(ff H t'I ff H lf ff II It"l IL E.PINNA NUCLEAR POWER PIANT Inserriee Examhathn Bonndary Lhe ust Iidrd Inspeethn nteetva!PAID No r 33013.12SS Chas.t I System r REACIOR COOLANT.PRESSURIZER Comp~: COMPONENIS RQIE Line No.ISI Size~PI.MatrL~h.%Res Exam pthn NDE~h.Bash Method Po T~em In?Une deseri remarirs AA OAO 0.000 VOL PRESSUIUZEL Revbal A 11/9I 0 H~<Mal m 0 N~g Q gH'g WAR+o rn 0 W>I taXa H tOQC VC owe HRO 0 N i l g t~l tt t'l r i lt ll K K 1)S K'K t'I I K l K IL E.GINNA NUCLEAR POWER PLANT Inservtee Examinanon Bonnthry LIne Ust Third I spection interval PMD No t 33013.1258 Chss t I System t REACTOR COOIANT-PRESSURIZER Comp Imper PIPLNG O H 0 RGStE Une No.I O.RC8-2501 dh-RCS-2501% 4A.RC8.2501.B 4ORCB-2501 3A RC8.2501 3A.RC8-2501* 3A RC8-2501.B 3B-RC8.2501 3ORCB-2501 2A RC8.2501 GBbert Une No.RG200 RC300 RC300 10 PRZ SURGE 4.RG273 4 RC 273+RC 1005 3 RC 1005 3.RC 1000 3-RC-1001 3.RC 1006 3-RC 1000 ISI SIte~F1.MatrL~in.ABD A376 IUD A-13 A376%AS A.13 A376 4Am h-12 A376%AS h-12 A376 3AO A.10 A376 3AM A.I 0 A376 3.00 A.12 A376 3.00 A-9 A376 3.00 A 11 2AN ISO 0.531 IL531 OMI OA38 OA38 OA38 OA38 0.000 SUR/VOL SUR/VOL SUR/VOL SUR/VOL SUR SUR SUR SUR SUR SUR Po~Tern IIn7 Une desert'/rernarirs PRZ SURGE UNE IO B HOT LEG.PRZ REUEF PRZ IO PCV 43S.PRZ REUEF PRZ IO PCV 435.PRZ REUEF PRZ IO RELIEF MANIIOLD.PRZ REUEF MANIPOLD IO VALVE 5515 5 43 I C PRZ SPRAY FROM IlOP A IO ASIA.PRZ SPRAY FROM IQOP 8 TO 431 B.PRZ REUEF MANIFOLD IO VALVE S516 B 430.PRZ SPRAY FROM 431A It B IO PRZ HEAD.VALVE 297'IO REDUCER AT 3C RC8-2501.Revised R 11/91 R 11/91 R 11/91 I H~OMe g Q CHR%OX HLOA5W owe HXO gO CQ'0 M 8 0 0 0 \'r I I'I 4 I N)1 Ii'I I I I II I'I tr I 1 I)I r r r r If I k I II li I I I It~~4'I'I I, A.~'I IL F GINNA NUCLEAR POWER PLANT laserviee Examiasrioa BoaadarF Uae Usc IBIrd b specdoa lnrerxnl PdtlDNo r 33013.1258 Class r 2 Sysrera r REACIOR COOlANT.PRESSURIZER Comp TYPe: PIPING O 0 RGBtE Une No.2A.RC.151 GBbert SWRI N u 151 Size~Fi.MntrL~In.N/A 2.00%he Exempaoa NDE~b.Bans Method Po~Tern In?Une deseri'emnrlrs OAXX)IWC 1222(A)60 10-VALVE 529 BY PEN 121 TO VALVE 50L H Q Ul g H XO+'LO H H LI3@o 0 M H~g 113 0 q'LI3 H 0 H g OX R5 0)iD 0 rt r.0 V II I'h II JI IL E.GINNA NUCLEAR POWER PIANT Inservice Examination Botmdary Une Ust Thinl Inspection Interval PtklD No t 33013 1260 Class t I System.: REACIQR COOLANT Comp Typm COMPONENIS O 0 RGErE Mne No.GBbert Line No.ISI She Tlhns~F1.Matrl.~in.~h.Po~Tern tnt Mne ctescri'/remarks EMS 0)A EMS GIB PRCOIA PRCOIB RRCOI AG A-5 h-7 A.7 A.l tMO OAXO 0.00 0.000 0.00 OANO OAXI 0.000 0.00 0.000 SUR/VOL SUR/VOL SUR/VOL SUR/VOL SUR/VOL SIE/LM GENERAIQR h.SIEAM GENERATOR L REACIOR COOIANT PUMP*REACIOR COOIANT PUMP K REACTOR VESSEL A I I/91 h 11/91 h 11/91 A 11/91 A 11/91 H 0 M X H WO H tO H~LOS gOM I HIOO EII~<g 0)H 0 g H M 9 0 0 0 \II I t P I I 1'I 2'I ll I I I II I ,.r~ Ih E.GNNh NUCLEAR POWER PIANT lnservke Exemlnadon Boandsry Une Ust Third Inspecdon Intetvrd PAID No t 33013-1260 Qass t I Systan t REACTOR COOIANT Comp IYpe: PIPING ROBE Une No.ISI~FI.Mstrh NDE Metlrod~Tern IInl Une deseri n/remsrlts H 0 31 RC 250M 31 RC 2501 B 29.RC250M 29.RG2501.B 27.5 RC 2501%27.5.RC.2501 B 10A RCO 2501 h 10A.RC0.2501.B 10B.RC0.2501% 6A.RC0.250 M 6A-RED.2501.B 4A-RCO 250 M 4A.RCO 2501.B 2A.RC0.2501% 2A.RC0.2501 8 2B.RC0.2501% 28 RC0.2501.B 2ORC0.250M 2ORC0 2501.B 2D RC0.2501.8 RHR3500 51-200 RHR-100 RHR.100 RHR.100 RHR-100 UNE h LINE B UNE A UNE B UNE A UNE B IO.AC 1004 l(PIC 1001 6AC 1003 6'002 4AGI003.4'002 2.DR.1002 2.LD 1001 h3 CCSS h3B CCSS A3 CCSS A3B CCSS A3 CCSS h38 CCSS h.l5 A376 A.14 A376 A-17 A376 A.14 A376 A.IB A376 h.14 A376 A-18 A376 A-26 A376 A-23A A376 A.22 A376 A-27 A376 A.20 A376 A-25 A376 A-21 A376 3 I AN 2500 31 AN 2500 29Am 2500 29.00 2500 27.50 2.4N 2780 2.400 10Am I AXN 10.00 I AXN 10Am I AXN 6Am 0.718 6D0 0.718 4 AN 0531 4D0 0531 2.00 0344 2Am 0344 2.00 OAXN 2.00 0344 2.00 0000 2.00 0344 2.00 OAXN SUR/VOL SIIR/VOL SUR/VOL SUR/VOL SUR/VOL 5UR/VOL SUR/VOL SUR/VOL BUR/VOL SUR/VOL BUR/VOL SUR/VOL SUR/VOL SUR SUR SUR SUR SUR SUR SUR Y CROSS OVER FROM SGW TO RCP*Y CROSS OVER FROM SG-B TO RCP IL Y HOT LEG FROM RPV'IO SG-A.Y HOT LEG FROM RPV IO SOIL Y COID LEG FROM RCP A TO RPV.Y COLD LEG FROM RCP B IO RPV.Y RHR FROM HOT LKG A TO VALVE 700.Y RHR/Sl FROM 721, 867A IO COID LBG L Y Sl FROM 867B IO hOOP h COLD IKG.Y RHR FROM VALVE 852A'IO 6X4 REDUCER~Y RHR FROM VALVE 8528 IO 6X4 REDUCER.Y RHR FROM 6X4 RKDUCKR IO RPV.Y RHR FROM 6X4 REDUCER TO RPV.Y CHARGING VALVE 383A'IO lOOP A COID IKG.Y IZIDOWN FROM CROSSOVER LEG IQ 427, 54L Y DRAIN FROM CROSS OVER LEG IO 541, 523.Y CHARGING VALVE 393 IO hOOP B HOT LEG.Y Sl FROM VALVE 877B IO LOOP A HOT LEG.Y CHARGING VALVE 295 IO IQOP B COID LEG.Y Sl FROM VALVE 877A'IO lOOP B HOT IKG.R 11/91 R 06/93 h 06/93 R 11/91 R 11/91 R I I/91 R I I/91 h 06/93 R 06/93 R 06/93 h 06/93 h 06/93 h 06/93 h 06/93 H 0 M XO H UI g O N~k tO O H Ul g+tA)H o H g g H M tD 0 0 0 IL E.GINNA NUCLEAR POWER PIANT Inserviee Examination Botmdary Une Ust'Bdrd inspeedon lntervtd P&ID No r 33013.1261 CLsss: 2 System.r CONTAINMENT SPRAY Comp T)rper COMPONFNIS RG&E LLoe No.ISI SIxe IMnrs~FI.MatrL~in.~in.NDE Method Fo T~em tnt line desrri'/rernarirs Q H 0 PSI02A PSI02B SS101 SSI02 TSIOI TSI02 1261 1261 1261 1261 1261 1261 N/A N/A N/A N/A N/A N/h (LOO IUNO OAM IL000 IGLOO (OOOO 0.00 0AXO DAO 0.000 (LOO 0.000 NO IWQ.NO IWA IWG 1221(A)IWC 1221(A)NOT SECT XI IWC 1221(h)205 70 205 70 CONTAINMNT SPRAY PMP h, MFG INC ERSOL R/UID CONTAINMNT SPRAY PMP 3, MFG~INCERSOL RAND CONTAINhL%'PRAY EDUCTQL CONTAINMENT SPRAY EDUCTOR L REFUEUNG WATER STORAGE TANK.SPRAY ADDIIIVE TANK.R Ol/92 R Ol/92 R 11/91 R I I/9I R 11/91 R 06/93 H~0 (/)~Q Q R4H'g H g X 0%Ht()ZK<~&MAX I IT)gR'Q H o c ca HgQ 0 IL E.GINNA NUCLEAR POWER PIANT Insendoe ExamLnadon Bonndaty Une Ust 1)drd speedon Intesva)9&ID No t 33013.1261 Qass.t 2 System.t CONTAINMENTSPRAY Comp Type: PIPING RUBE Une No.SWRI Une No.Exemption Basis NDE Methad In?O H 0 10$1 151 1088$)151 8A$1.151 88$FOSI 6A$1.)51 68$)-)51 6C$1$01 6D$)$0)6DD$)$01 68$)$0)6EE$)$01 6F$)$0)60$I$0)6H$1$01 6)$)$01 6)$)$0)6K$)$0)6KK$)$01 6L$1$01 6LL$)$01 6M$I$0)6Ã$1$0)6P$)$01 60$WOI 4A$)$0)48$)$01 4C$1$01 40$1$0)48$1$01 4F$1$01 3$).15)3A$1$01 38$1$01 3C$)$01 2$)151 2A$1.15)28$1 151 2CSI-)5)2D$1.151 28$)$0)2F$1$0)20$1$01 2H$)$01 RHRASO RHRA50 RH RUSSO RHRA50 CS 500 C5$00 C5.500 CS$00 CS$00 CS.500 CS.)CO,CS.)50 CS.)50 CS.)50 CS800 CS800 CS$00 CS800 CS8(O CS800 C5-200,CS 250 CS-250 CS-250 C5$00 CS-150 C5.150 C5$00 C5.250 CS 250 C5$20 CS-100 C5.100 C5.100 C5.100)0$1.2IO4 1051-151 R 6$).15)R 10$1.15)R B 19 B.)9 8-19 8 19 B 19 B46 B46 L46 L46 B46 B48 N/A N/A 8-47 B47 L47 L47 B47 B47 N/h N/A N/A L46 N/A N/h L47 N/A N/A N/A N/h N/h N/A N/A N/A N/A 8.20 8.19 N/A N/A N/A N/A A312 A312 A312 A312 A312 A48 A48 A48 h48 A48 A48 A312 A312 A312 A48 A48 A403 A48 A48 A48 A312 A312 A312 A312 A312 A312 A312 h312 A312 A312 A312 A312 A312 A312 A312 10.00 10AO 8.00 LOO 6AS 6AS 6.00 6AO 6AO 6.00 6AO 6AO 6AO 6AS 6AS 6AO 6AO 6.00 6.00 6AO 6.00 6AS 6AO 6.00 4.00 400 4.00 4AO 4AO 4AO 3AO 3AS 3AS 3AS 2AO 2AO 2AO 2AO 2AS 2.00 2.00 2.00 0.165 OASO 0.148 0.)48 O.MI 0.148 0280 (F280 (F280 (L280 Ot280 0281 (L28)Gt28)0280 0280 IL280 (L280 0~0.280 0280 0.281 0.281 0.237 OXI7 OAKS 0237 (L237 0.000 0216 0216 IMAGO 0.154 0.154 0.154 IL154 0.154 0.154 0.154 0.154 a)54 IWC 1221(F)IMiZ.)221(F)IWC 1221(F)IV&122)(F) itaQ 1221(F)%0 1221(F)IWC 1221(F)IWC 1221(F)IWC 1221(F))WC)221(F) IWC 1221(F)IWC)221(F)IWC 1221(A)IWC)221(h)IWC)221(A) IWC 1221(h)IWC 1221(A)1th'G)221(A) IVI'G)221(A) IVtQ 1221(A)IVI&1221(A) Bh&1221(h) IWC.1221(h))Vs'221(h) IWC 1221(A)IWC 122)(A)IWC 1221(A)IWC)221(A)IWC 122)(A)IWC 122)(h)IWC 1221(h)SUR/VOL SUB/VOL SUB/VOL SVR/VOL SUR/VOL SUR/VOL SUR/VOL SUR/VOL SUR/VOL 5VR/VOL SUR/VOL SVR/VOL 30 410 30 30 30 30 205 205 205 205 205 205 205 205 205 205 205 205 205 205 205 205 205 205 205 205 205 205 205 205 30 205 205 30 30 30 30 30 205 205 205 205 70 350 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 RWST 10)ST 10 X 8 S 10 X 6 RDCRS, 8258.RWST TO VALVE 856.6A$1.)51'10 C5 PVMP L 68$).151 10 CS PUMP h.10$1.151 10 RDCR PAST VALVE 858L 10$1 151 10 RDCR PAST VALVE 858h.4A$)$01 10 1ST 6 X 6 X 6 TEE.6C$1$01'10 VALVE 860A.VALVE 860h IQ IST 6'EE BEFORE V 862A.)ST IEE ON UNE 6C$)$01 10 VALVE 860L VALVE 860B TO VALVE 862h.VALVE 862A 10 PEN 105.PEN 105 TO CS SPRAY RING.6G$1$01 10 4 B$)$01.4C$)$01'10 6G$)$01.4D$1$01 10 IST 6 X 6 X 6 TEE.6 X 6 X 6 TEE ON 6)$)$01 TO VALVE 860D.VALVE 860D TO 6'EE BEFORE VALVE 862L 6 X 6 X 6 IEE ON 6)$)$0)IO VALVE 860C VALVE 860C 10 6'EE BEFORE VALVE 8628.6 X 6 X 6'IEE BEFORE VALVE 862B IQ PEN 109.PEN 109'IQ 6'EE ON LOWER CS RING.4F$1$01 10 6N$1$01.6N$1$01 10 4 E$1$01.h CS PUMP IO REDUCER 6H$)$0)TO 3AS)$01.3A$)$0)IO 61$1$01.B CS PUMP TO REDUCER.6 X 4 RDCR TO 38$)$01.4 X 3 RDCR'10 6 X 4 RDCR ON 6P$1$0).RWST 10 NOZZLE WELD.4 8$1$01 TO 4C$)$01.4 X 3 RDCR ON 4E$)$0)10 4 X 3 RDCR.SPRAY ADDITNE TANK 10 VALVE 627.RWST 10 VALVE 893A.RWST 10 VALVE 893 L RWST'IQ VALVE 894 L RWST 10 VALVE 808.10$1-151 10 VALVE 873C 60$1$01 10 6N$1$01.2E$1$01 TO VALVE 875A.28$)$01 TO VALVE 875L 28$)$01 TO VALVE 876L R 06/93 R 11/91 R 11/91 R I I/91 R 11/91 R 1)/91 R 11/91 R 1)/91 R 11/91 R)1/9)R 11/91 R 11/91 R 11/91 R 1)/91 R I I/91 R)I/91 R Il/91 R I I/91 R 11/9)R I I/9)R 1)/91 R 1)/91 R I I/91 R)1/91 H~0 (/)~N Q XHX (X)OX HtOa5<+AH+o(/)OW~leva&XhfU g&0)H'Q H O e(Z)HgQ QO (/)(t)0 0 0 Jl'i s t R.E.GINNA NUCLEAR POWER PIANT Inservice hminrrdoa~Line LIst'Ildrd tnspecdoa Iaterrrrd PMD No t 33013.1261 (Cont'd)Chss.r 2 Systera t CONTAINMENT SPRAY Comp T)rper PIPING RUTE LLm No.ISI SIse~PI.NDE Method Po~Tern ia7 Uae drscri'/reaurts 0 2ISIS01 2ISIS01 2KSIS01 2KKSISOI 2LSIS01 XtISIS01 2NSIS01 2PSIS01 2QSIS01 2QASISOI 2RSIS01 2SSIS01 2TSISOI 20$1.151 CS-100 CSS10 CSS 1 0 CSS10 CSSI 0 CS.510 CS.510 CS-51 0,CS-520 CSS10 CS.520 CSS20 CSS20 CSS20 N/h A312 8-19 A312 B46 A312 N/A A312 N/A A312 8 19 A312 N/h A312 N/h h312 i%7 A312 N/A A312 N/h A312 N/h A312 N/A A312 N/A 0.154 IL154 0.154 0.154 0.154 0.154 0.154 0.154 (L154 0.154 0.154 0.154 0.154 0800 IWC.12@(h)IWC.1221(h) I%&1221(A) IWC 1221(A)IWC 1221(A)IWC 1221(A)IWC 1221(A)IWC 1221(h)IWC.1221(h) IWC 1221(A)IWC 1221(h)IWC 1221(h)IWC 1221(A)IWC.1222(h) 205/0 205 70 205 70 205 70 205 70 205 70 205 70 2ESISO I'IQ VALVE 876A.8BSI.151'TO CS EDUCTOR 6CSIS01 TO VALVE 859A, CS EDUCIQR A TO 2KSIS01.CS EDUCIQR I TO CS EDUCIOR 2.BASI-151'IQ CS EDUCiQR CS EDUCTOR 2 TO 2QSISOI.2LSIS01 TO VALVE 873A.6ISIS01 TO VALVE 859h, 859C 2PSIS01 BY VALVE 873B TO VALVE 8730.2"TEE ON PSI.151 PAST VALVE~2PSIS01 PAST VALVE 836B'IO 1 ST 2'EE.VALVE 8818 TO SPRAY ADDITIVE TANK.RWST TO VALVE 895.R I I/91 R 11/91 R I I/91 R I I/91 R I I/91 R 06/93 R 11/91 R 11/91 R 11/91 R I I/91 A 11/91 H 0 U)XH WO H NOH~'LO'g g O(/)I&O H ting ICs H p o Ff 0 IL E.GINNA NUCLEAR POWER FIANT lnsaviee~n Bonndery Une Ust Thhd Inspecnon Intaval PMD No t 33013 1262-1 Class t 2 Systan t SAFEIY INIECIION Gnnp Type: COMPONENIS O H 0 ROBE Une No.Gihert Une No.ISI~FI.MetrL Site Ties~1m~in.NDE Method Po~Tern In?Une deseri n/remerks PSIOI A PSIOI B PSIOIC 1262 1262 1262 N/h N/A N/A OAS OA0 OAO OAI00 IGLOO 0.000 NO IW/L.NO IWA NO IWA 1550 200 1550 200 1550 200 SAFElY INJECTION PUMP A, MFG~WORTHINGTON R 06/93 SAFEIY INIECIION PUMP B, MFG~WORTHINGTON R 06/93 SAFEIY INIECIION PUMP C, MFG~WORTHINGTON R 06/93 H~O 02~g Q t3 4 H XHR WOW H LO H$Q g o Pn o PJ I'OgR V H owe HQQ RMW R ID 0 ft Pe 0 I"l K PS ID No t 33013.12SL) Chss.: 2 System: SAFE)V INIECIION omP TyPet PIPING ROSE Line No.QVRI line No.R.E.GINNA NUCLEAR POWER PIANT Isetrvtke hminathn Bonnhuy Line list Th)n)I speetion Intetval el I f 0 H 0 SCS)30)SDS)30)SES)30)SFS)301 SGS)30)SHS)301 8)SI.)5)SLSI.)51 4$)301 4ASI301 4841301 4CS)301 4DSI.)501 4ESI.)501 3AS).1501 3881.1501 3CS).1501 3DSI.)501 3ESI.)501 2ESI.)501)SAS).1501 13CSI.)501)3DS).1501 SI~SSI301 SI~P)301 SI~,SSI30) SI~,RHRA50 RH F50 RHRA50 RHR450 RH F50 RH F50 RHR450 S)3(XII.210 5)3IXL51 1)0 5)300 5)300 5)300 S)300 5)300 S)300 S)300 5)300 SS)-2001 8$)-2003 SS).2002 SSI-2003 8-15 A312 8 16 h312 8 16 A3)2 815A A312 8-19 A312 8.16 A312 8 19 8 19 8-168 A312 8-)68 A312 8.168 A312 8-168 A312 le@A312 S42 A312 837 A312 840 A312 IL41 A312 L4)A312 842 A312 844 837 A312 8-54 A312 S42 A312 8AO 0322 8'322 SOO 0322 LOO 0322 LOO 0322 LOO 0.000 LOO 0.000 4'337 IWC 1221(A)4AX)0337 IWC.)221(A) 4A)0 0337 IWC 1221(A)4AS 0337 IWC 1221(A)4 AS IL337 4'337 3AS 0300 SOO 0300 3AS 0300 3AX)0300 3AX)0300 2AX)OAXN 1.50 OAXO IVt&)221(B)1.50 OAXN IWC 1221(B))30 (LOGO IWC.1221(8) 5UR/VOL BUR/VOL SUR/VOL BUR/VOL SUR/VOL SUR/VOL BUR/VOL SUR/VOL SUR/VOL BUR/VOL SUR/VOL SUR/VOL SUR/VOL SUB/VOL SUR/VOL SUR Sh/SBS)301 10 IST 8'TE~SCS)301 TO'KK PAST VALVE 826L SCSI301 10 1ST TEE PAST VALVE 826D.SD/SES)30) 'IQ 1 ST 8 X 4 BDCL SFS)301'10 VALVE 825A, SFS)30)10 VALVE 825)L VALVE 8258 10 1081 151~..VALVE 825A 10)OSI.)51.SFS)301 10 Sl PUMP SUCIION A.SHS)301 TO Sl PUMP SUCIION L SGS)30)10 Sl PUMP SUCIION C 48$)30)10 1816A.3AS).1501 THRU PEN 113 TO 4 X 4 X 3 TKE.3ESI-1501 1HRU PEN 101 10 4 X 4 X 3 TKL Sl PUMP h 10 4 X 3 RDCR AFKR VALVE SSSA.Sl PUMP C PAST FLANGE 10 3'TEE.3'KE FROM 38 TO 87)h, 870A, 84)X 3'EE FROM 38 TO 8718, 8708, 84E.Sl PUMP 8'10 4 X 3 RDCR AFTKR VALVE 888L Sl PUMPS DSG RDCRS 10 VALVE S898 S 897.2ESI-1501 TO 3ASI-)50). 3BSI 1501 10 2ESI.)501. 3ES).1501 10 2ES).1501. P'T~lnt U d 200 200 200 200 200 200 200 200 1550 200 1550 200 1550 200 1550 200 1550 200 1550 200 1550 200 1550 200 1550 200 1550 200 R 06/93 R 06/93 R 06/93 R 05/93 R 06/93 R 05/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 05/93 H C)(/)g H w o+tA)H H ti)lg+O(1)>tOO (/)HtOg g'LO H 0 H g d OX 0 (/)(t)n Ft r.0 0 ft 1 R E.GINNA NUCLEAR POWER PIANT Itsetfvke Ettttmlhtt6oh Boott5eff Llhe Ust Thitd Impettttoh Ihtetval PMD No-: 33013 1262-2 42ass t I 57steto: SAFETY INJECIION Comp T7pet PIPING RG8tE Une No.ISI Site~Fi.MattL~th.TMths Exempcioh~ln.Po T~em ill?Uhe desetl fl/lemtttts O H 0 10ASI2.2501.h 10ASI2-2501.B 2ASI2-2501 28$12-2MI 2CSI2-2MI 2DSI2.2501 Sl 100 51-200 51.110 51-210 SI.I 10,.111 51.210 10$1-1005 10$1-1004 2$1-1001 2$1-1002 2$1.1001 2$1-1002 h.17 A376 A-16 A376 A 19 A376 A.21 A376 h-20 A376 h-16 A376 I DAO 10AO 2.00 2AO 2.00 2AO IAXO I AXO IL344 (1344 0844 a344 5UR/VOL SUB/VOL SUR SUR SUR SUR CHECK VALVE 8428 T0 867L CHECK VALVE 842A T0 867A.8781'10 1(P Sl ACCUM B DUMP.VALVE 878F l0 877A.VALVE 878 H T0 877 B.878G T0 10'l ACCUM A DUMP.R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 05/93 H 0 UT X H W A W+'LO H H~@0 M 113 O H~g H g Ra g H 0 g rn O FAT ID 0 0 0 m lt', W l" R E.GINNA NUCLEAR POWER PLANT nseevvire Esnmirusdoa Bouadtuy Une Ust lhhd Inspecaoa Intervrd P&ID No-r 33013.1262-2 CLsss r 2 System: SAFEIY INJECIION Comp Type: COMPONENIS H 0 RG&E Une No.lS103A ISKGB 0Ebert Une No.1262 1262 ISI~Fi.MstrL N/A N/A Sire Thorns~in.~in.OA)0 OAXO 0.00 OAXO Exemptioa Basis IWG122QE)IWC 1221(E)NDE Method 740 80 740 80 SAFElY L%ECIION ACCUMULATOR A.SAFElY INJ ECIION ACCUMUIA'TOR K Po T~em la?Une deseri'/remerhs Revised R 06/93 R 06/93 H 0 V)g H Lv)0+tO H H LO g O V)pVW tQ 0 H~g~td)H 0 H R g 0 trJ m QH U)8 0 rt r.0 0 r It 1 T II 1 1 IL E.CUINA NUCLEAR POWER PIANT nseervice Examinatbn ~Une Ust IMrd nspecdon Interval 9&ID No t 33013-1262-2 c2ass t 2 System t SAFEIY INJECIION Comp 1)pe: PIPUtC O H 0 RC&E line No.G Chert UUnne eNo.ISI Site~Fi.MatrL~b.NDE Method Po~Tern Inl Une descri remarks 10ASI-902 10831.902 10CSI.2501 10DSI-902 I 0ESI-902 I OFSI-2501 2ASI.1501 2831.1501 2CSI.1501 2DSI-1501 2C$1-902 2HSI-902 21$1-902 2l$1-902 2KSI.902 2LSI-902 2MSI-902 2ÃSI-902 2PSI-902 2()$1.902 2RSI-2501 25$1-2501 2TSI-2501 2USI.2501 2VSI-902 2WSI4t02 SI5-200 SIS-200 SIS-200 Sl 100 SI 100 51.100 51.210 51 210 51.110 51-110 515.200 Sl-101 N/A A376 N/A A376 N/A A376 N/A A376 N/A A376 N/A A376 B39 A312 B39 A376 B45 A376 B44 A312 N/A A312 N/A A312 N/A A312 N/A A312 N/A A312 N/A A312 N/h A312 N/A A312 Nfh A312 N/A A312 B45 B44 B39 B39 N/A N/A I CAN 10.00 10.00 I CAN 10.00 10.00 200 2Am 2Am 2.00 2Am 2Am 2Am 2Am 2Am 2Am 2Am 2Am 2AX)2Am IAXN IAXN I AXN I AXN IAXN I AND Q218 0218 0343 Q218 Q343 0.154 0.154 0.154 (L154 Q154 0.154 Q154-0.154 0.154 OAXN 0.000 0.000 0.000 Q000 0.000 IWC.122/(E)IWO1221(E) IWO1221(E) IWC 1221(E)IWO122 I(E)IWO1221(E) IWO1221N)IWO1221(E) IWCI221N)IVrC 1221(E)!Vs&1221(E) Ita0 1221(E)IWO1221(E) IWC 1221(E)IWC 1221(E)IWC.1221(E) IWC 1221(E)IWO1221(E) 'SUR SUR SUR SUR SUR SUR SUR SUR 740 80 740 80 740 80 740 80 740 80 740 80 1550 200 1550 200 1550 200 1550 200 740 80 740 80 740 80 740 80 740 80 740 80 740 80 740 80 740 80 740 80 ACCUMUIAIQR I TO VALVE 841.I OASI.902 IO CAP ON IEE.VALVE 841 IO 842A INQD CAP ON'IEE.ACCUMUIAIQR 2 TO VALVE 865.10DSI.902 IO TEE CAP.VALVE 865 IQ 8428 INQD CAP ON IEE.4DSI-1501 IQ VALVE 878A.4DSI-1501 IO VALVE 878IL 4'EE ON 4ESI-1501 IQ VALVE 878D.4'EE ON 4531-1501 IO VALVE 878C.10ASI-902 TO VALVE 844A.10DSI-902'IQ VALVE 844 IL ACCUMUIAIQR I PAST V 833A IO LT 939.LT 939 PAST V 833B 10 ACCUMUIAIQR l.ACCUMUIAIQR I PAST V 832A'10 LT 938.LT 938 PAST V 8328'IO ACCUMUIAIQR I.ACCUMUIAIOR 2 PASTY 837h TO LT 934.LT 934 PAST V 837B IO ACCUMUIAIQR 2.ACCUMULAIOR 2 PAST V 83&A IQ LT 935.LT 935 PAST V 838B IQ ACCUMUIATOR 2.VALVE 878D IO VALVE 87&I.VALVE 878C IQ VALVE 878H.VALVE 878B IQ VALVE 878G.VALVE 878A TO VALVE 878E.DRAIN OFP 2CSI.902.DRAIN OFP 2HSIdt02.R OV93 R 06f93 R 06/93 R OV93 R OV93 R OV93 R 06/93 R OV93 R OV93 R 06/93 R 06f93 R OV93 R 06/93 R 06/93 R 06f93 R OV93 R OV93 R OV93 R OV93 R OV93 R OV93 R 06/93 R 06/93 R 06/93 R OV93 R 06/93 H~Q(/)e NQ R4H XHX ROC o(/)OPS&X LT(U g kEs O g H+u)I-I O e (Ei HgQ (/)(D 0 0 0 (W 1 I IJ II i 1 k ll'f H'I)t 1 IL E.GLMih NUCLEAR POWER PIANT Iaserviee~a Oceradery Lbe Ust Thhd Imspeetkra Iatertrel PAID No r 33013.1263 Cbss..: 3 System.: RCS OVERPRESS. PROT.N2 ACCUM.Comp Type: COMPONENIS H 0 ROBE Lbe No.TRC03A TRCOSB 1RC04A TRCOIB Gihert Lbe No.ISI She~Fi.MotrL~h.N/A N/A N/A N/h OANO IWD I~I OAXO IWD.122IL I OAXO.IWD.122IL I OOOO IWD.1220.1 NDE Method Po~Tern In?Lbe deseri'emarks OVERPRESSURE PROTECIlON ACCUMUIATOR* R 06/93 OVERPRESSURE PROTECIlON ACCUMUIATOR IL R 06/93 OVERPRESSURE PROIECllON N2 SURGE TANK*R 06/93 OVERPRESSURE PROTECTION N2 SURGE TANK L R 06/93 H 0 Ul X H X A+II3 H HMkg O Q He 0'LO H tA3 t3 H g OX wa g H 0 I l'I il II I.~lt 1 P.'I l't 4 R E.GUINA NUCIEAR POWER PIANT nseevviee Euunlnation Oonnthrry Une Ust Thin!sspeedces interval Bt!D No t 33013-1264 Chss t I System s CVCS LETDOWN Comp Type: COMPONENTS O t3 H p RUBE Une No.Grlbert Une No.SWRI Une No.ISI~FI.MarrL h4 A4 A4 N/A Slee Tlrkns Exemption N DE~b.~in.OAS a000 VOL a00 a0M VOL aoo a 000 VOL am 0.000 IWB-1220(B) Po~Tern In?Une desni remar?a lHIS COMP ACCOUNTED FOR Oi I 33013.1265. THIS COMP ACCOUNTED FOR ON 33013 1265.THIS COMP ACCOUNTED FOR ON 33013.1265 EXCESS LETTIWN HEAT EXCHANGER R 01/92 R 01/92 R 01/92 A I I/91 H P F/2 g H WO+'LO H r Hex+O VT W ICI O H IT?~IO H p H g g H 5 p OT 9 n r.0 O I II il F C IL E.GINNA NUCLEAR POWER PIANT Inservke Ertamlnation Bonndary Line ust TIdrd Inspeedon Interval PAID No t 33013-1264 Class r I SIstem r CVCSLETDOWN Comp TYpet PIPING A W H 0 RGRE une No.2A48 4.2501 2BCN4.2501 Gilbert lIiinne eNo.2-LD 1002 2-LD.1003 151~FI.MatrL A.23 A376 A.24 A376 SIre Tides Exempdon NDE~b.~in.BaCk Method Po~Tern I at Une deseri rernarlts Revised 2'L344~SUR Y CVCSV LETDOWN FROM 427 TQ 2204, THRU RHES R I V91 200 Q344 SUR Y RBES TO 200A, 2008, 202.R IV9I H~Cl M~g Q QHQ ROC HLI3Z jg CD M O X eg g&XRU H LI3 O g H'4 H oem H@O 0 R.E.GINNA NUCLEAR POWER PIANT Insertdoe~a Botmdsty Une Ust IIdrd Inspectga Interval PMD No..: 33013-1254 Chss..t 2 System: CVCS.LETDOWN Comp I)rpe: PIPING H 0 RGItE Une No.2ACH601 2BCHW I 2CCHAOI 2DCH 401 2LCH F01 2PCHWI 2GCH401 GEbert Une No.CVC 105 CVC 105 CVC 105 CVC.I OS CVC 105 CVC 100 CVG 100 ISI SIte~Fi.MntrL~h.N/A A312 N/h A312 B32 A312 N/A A312 S32 A312 N/h A312 B32 A312 0.154 0.154 0.154 0.154 0.154 sL154 (L154 IWC 1222(A)IWC 1222(A)IWC 1222(A)IWC 1222(A)IWC 1222(A)IWC.1 222(h)IWC.1222(h) Po T~em In?Une deserl n/rernnr Its VALVE 200A'IQ 1ST 2 X 2 X 2 IEE.VALVE 200B IQ 1 ST 2'TE ON 2ACH401.2'EE ON 2ACHM I IQ 2GCHAO I.VALVE 202 IQ UNE 2CCHM I.2CCH401 TO VALVE 20tA 2&AG601 IQ 2'EE PAST VALVE HCV-133.2'EE ON 2CCH401 TO PEN 112, VLV 371.R 11/91 R 06/93 H 0 (/)g H WO H'LO H g O(/)I Heg ID 0+u)H ()H g (/)8 ()po 0 0 K 4 II P w li I I fi IL E.GINNA NUCLEAR POWER PIANT Inservke KaminatNn Bmmdary Une LIst TIdtd Inspecdon interval PMD No..: 33013.1265 1 Chas: I System.r CVCSCHARGING Comp Type: COMPONENTS O H 0 RGRE Line No.GUbert SWIU Une No..Une No.ISI~Fi.Matrk Sire TItkns Exemption N DE~b.~in.Basis Method Po~Tern In?IAne deseri n/remarlts Revised PRCOIA PRCOIB A7 A-7 OARED 0 AID 0.00 OA60 SUR/VOL SUR/VOL THIS PUMP ACCOUNTED POR ON 33013.1260. THIS PUMP ACCOUNTED FOR ON 33013 1260.R 06/93 R 06/93 H~0 Ul~Q Q R4H gH'g XOQ gDMOW I w ta x v g&O)H tI3 H 0<v Hg0 R sEI W M 8 0 r.0 L E.CINNA NUCLEAR POWER PIANT nseervke~n Beunday Une Lbt Thitd Inspeedon Interval PMD No,t 33013-1265.1 Qass t I Systetn.: CVCSCHARG INC Comp Types PIPINC RGAE Une No.ISI~FI.MsttL Size IMtns Exempdon~in.~in.NDE Method A H 0 2CH5.2501 2ACH5-2501 2BCH5.2501 2CCH5.2502 2HCHS-2501 2HCHS 2502 2ICH5-2501 214215.2502 RG300CVC 700~1001 CVC 700;-701 24CH.1002 CVG4XI;W I 2-ACH.1001 A.l I h376 h-27 A376 A-25 A376 A.26 A376 A32 A32A A31 A31A 2.00 IL344 2AXI a344 2AN a344 2Am 0844 2AO 0344 2Am 0344 2AN L344 2AO 0344 SUR SUR SUR SUR SUR SUR SUR SUR CVCS AUX SPRAY FROM 9313 T0 297.CVCS ALT CHARGINC FROM 9315 I0 393.CVCS CHARG ING FROM 9314'10 295.CVCS ALT CHARG FROM 3923 TO 383A VALVE 302C I0 RCP.L VALVE 304 B T0 VALVE 302C.VALVE 302D T0 RCPT VALVE 304A I0 VALVE 3020.R 06/93 R 06/93 R 06/93 R 06/93 A 06/93 A 06/93 h 06/93 h 06/93 H 0 FJ2 X H XO HQH~IOQ gOM H II7 g II7 0+II)H o H g g 0 A M ID n 0 0 'k IL E.GINNA NUCLEAR POWER PLANT Insaviee Esarnination Bonndary L(ne Ust TIrird Inspeedon lntaral P&ID No-t 33013-1265-1 (2ass t 2 5)stan t CVCSA3IARGING Comp~t COMPONENIS 0 H 0 RG&E Une No.GEbat Line No.ISI She~FI.MarrL~in.Po T~an In7 Line deseri'ernarls 1265 1265 A4 A4 A4 B.7 B-7 OAN OAO OAN OAN OAO OAXN 0.000 OA)00 OAXN IWC 1222(h)IWC.1222(h) IWC 1222(A)IWC 1222(h)IWC 1222(A)2300 525 2300 525 2300 S25 2450 100 2450 1007 REGENERAIIVE HEAT EXCHANGER A.REGENERATIVE HEAT EXCHANGER K REGENERATIVE NEAT EXCHANGER C.SEAL INJECTION FILTER L SEAL INIECTION FILTER L R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 H 0 (/)R H X A L u)H H tO g O (/)td HIOg I()0 40 H p H'g OW 0 m I R E.GINNA NUCLEAR POWER KANT Insetviee Exam(nation ~Une Ust TMnI Inspecdon Interval 9&ID No t 33013.1265 I Qass.: 2 System.: CVCSCfIARGING Comp T)pet PIPING O H 0 RG&E Une No.GEbert SWRI UUnne eNo.Une No.ISI~PI.MatrL Sine Thine Exemptwn~in.~in.Po~Tern In?Une desert'emarts 3()CH 2502 3RCH.151 3RCH.2502 2hACH.2502 2ABCH.2502 2AVZH.151 2DCH5.2501 2ECH5.2501 2PCH5-2501 2GCH5.2502 2HABI 2502 2IZH 2502 2ICH.2502 2K'.2502 2LCH.2502 2M'.2502 2NCH.2502 2PZH 2501 2TAUI 151 2VCH.151 2WCH 151 2X42I-2501 2ZCHG502 CVC.1100 CVC 200 CVC 1100 CVG60O,CVG601 CVCSOO,CVC501 CVC200 CVC 1100 CVC 1100 CVC 1100 CVC 1100 CVC.1100 CVC.1100 CVC.1100 N/A A312 N/h A312 N/h A312 A3IA A312 A42h A312 N/A A312 A-29 A.ll A.27 A30 N/A A312 N/A A312 N/A A312 N/A A312 N/A A312 N/A A3i2 N/A A312 B34 SS I A312 Nfh A312 SS I A312 S3 A376 N/A A312 3AI a 438 ZOO 0.120 3A)0 a438 2AI 0344 2Am 0344 2AXI 0.109 2AO OAK)0 2A)0 a000 2AO OAX6 2A6 OAXO 2AS 0343 2.00 0344 2.00 0344 2A)0 0344 2AI 0344 2Am 0344 2A!0 0344 2A!0 a000 220 0.109 2A!0 0.109 a109 2AO 0344 2A!0 0344 IWC l~(A)IVQ 1222(A)IMiQ 1222(h)IViiC1222(h) IWC1222(h) IWC 1222(h)IWC 1222(A)IWC.1222(A) IWC 1222(A)IWC 1222(h)(WC 1222(h)IWC 1222(A)IWC 1222(h)IWC 1222(A)IWC 1222(A)IWC 1222(h)IWC 1222(A)IWC1222(A) IWCI 222(h)Phd 1222(A)IWQ 1222(A)IViC1222(h) IWC.1 222(A)2450 100 140 40 2450 100 2450 100 2450 100 140 40 2450 100 2450 100 2450 100 2450 100 2450 100 2450 100 2450 100 140 40 140 40 140 140 40 2450 100 2'EE ON 3ÃCH.2502 PAST VALVE 275.PEN 108 IO 3 X 2 REDUCER 2'EE ON 3t)CH 2502 TO 1ST 2'DCR TEE.PEN 106 IO VALVE 304/L PEN 110'IO VALVE 304IL 3RCH.151 TO VALVES 362A&385A.REGEN HEAT EXCHANGER TO VALVE 9314.2DCHS 2501 TO VALVE 9313.2D43I5-2501 TO VALVE 5815.REG EN HES TO VALVE 370L 3t)CH 2502 PAST VALVE 323 TO PEN 102.2'DCR TEE ON 3R43(.2502 TO PEN 110.2'DCR TEE 3RZH 2502'iQ PEN 106.2'EE ON 3NCH 2502 TQ KH09.2K~-2502 PAST VALVE 303 B'IO SW FIL 2.2'EE ON Bt)CH.2502 TO KH09.2MAUI 2502 PAST VALVE 303A TO KH08.2AVCH.IS)TO RC PUMP A.3RCH.151 TO VALVE 314.2AVCH 151 TO 2 X 35 RDCR 3'DCR ON 3RCH.151'iO VALVE 362K VALVE 3628 PAST VALVE 270B TO RC PMP I IL PEN 102 TO VALVE 392IL R 06f93 R 06/9$R 06/93 R 06/58 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06f93 R 06/93 R 06/93 R 06/58 R 06/93 R 06/93 R 06f93 R 06f93 R 06/93 R 06f93 R 06/93 R 06/93 R 06/93 0 (/)C H R 0+tO H O (O I-I e 0 gtOH 0 H g 0'0~=I b5 0 (()n 0 0 hl!4 C V 1 I 1 R E.GINNA h UQEAR POWER PLANT Insarnte Examhadon Onnalsry Une Ust Ih(nl speetion lntaval PAID No t 33013 1265.2 (2am.t 2 Systan.t CVCSCHARGING Comp~t COMPONENIS RG&E Une No.151 SIte Thkns~Fi.Matrk~ln.~ln.NDE Metlrsal Po~Tern In?Une deseri'emarks A H 0 PCHOI A KHOI 3 PCHOIC SCHI I 1265 1265 1265 1265 N/A N/h N/A B6 OAN OAXN OAN OAXN (LOO 0.000 OAN OAXN IWC 1222(h)IWC.1222(A) IWC 1222(h)SUR/VOL 2450 100 2450 100 2450 100 2450 100 CHARGING PUMP h, MFG AIAX.CHARGING PUMP B, MFG AJAX.CHARGING PUMP Q MFG AIAX.24'HARGING PUMP POISE DAMPENEIL R 06/93 R 06/93 R 06/93 R 06/93 H CI 0)g H W A+I()H HIDE O (A)H IA)0 (O~<g I()H 0 H g hf X g 0 Q$'0 o F3 0 (/)(D n I 0 0 'M h II IL F GINNA NUCLEAR POWER PI/LNT Inserviee Examlnanon Bonndary Une Ust TIdrd nspeakn Interval PMD No: 33013 1265 2 Qass t 2 System.: CVCSCHARGING Comp Type: PIPING O H 0 RG8iE U R 0Ebert Line No.SWRI Une No.Else TMtns MatrL~in.~h.NDE Metliod Po~Tern In?Une deserI'/remarlts 8BCH.2502 8CCH.2502 4CH.151 4DCH.I 5l 3GCH-151 3K431-2502 3!AH-2502 3M'-2502 3NZH-2502 3PCH.2502 2FCH.2502 2GCH.2502 CVC851 CVC852 CVG853 CVC.1200 CVC 1000 CVC851 CVG852 CVC853 CVC.1000 PULSE DAMPENER B6 POISE DILRIPENER B6 PULSE DAMPENER B6 N/h N/A N/A B6 B6 B6 N/A N/h N/h N/A A312 MO 0.906 A312 BOO 0.906 A312 ILOO 0.906 A312 4AO 0.120 4'LOIN A312 380 0.120 A312 3 AN 0A37 A312 300 OA37 A312 3 AN OA37 A312 3AC OA38 A312 3AN 0.438 A312 2AN IL344 A312 2AN tL344 IWC.1221(A) IWGI 222(A)IWC 1222(h)IWC 1222(A)IWC.1222(A) IWG1222(h) IWC 1222(A)IWG 1222(A)IWG1222(A) Ilh'@1222(A) SUR/VOL SUR/VOL SUR/VOL 2450 100 2450 100 2450 100 30 100 40 140 2450 100 2450 100 2450 100 2450 100 2450 100 2450 100 2450 100 3'EE ON 3K'-2502 TO PULSE DAMPEN EL 3'EE ON 3LCH4502 TO PULSE DARIPENEL 3'EE ON 3M'-2502 TO PULSE DAMPENEL 4BCH.151 PAST VAlVE 357 TO RViST.4CCH.I 5l THRU 358 TO 4CH-151.VALVE 313 1O PEN INL CHG PUMP I DSCHG PAST VALVE 287 TO TEE~CHG PUMP 2 D5CHG PAST VALVE 288 TO TEE~CHG PUMP 3 D5CHG PAST VALVE 291 TO 1EE.POISE DAMPENER PAST VALVE 289 TO 1ST TEE PULSE DAMPENER PAST VALVE 290 PUL DAMP.PUISE DAMPER TO CHECK VALVE 370L 2FCH.2502 THRU 384C TO DAMPER.R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 H 0 U)g H XO+LOH HU)g O (/)~I tE)O H U)g td)H t3 p H g 0 Ul (D ()I 0 H II I w t L E.GINNA NUCLEAR POWER PIANT Inservlee~n Bonndary Lhe Ust Third Inspeedon Inrerval PAID No r 33013.1266 Chss.r 2 Syrrem r CVCS-BORIC ACID Comp Types COMPONENIS H 0 ICHOTA ICH07B 1266 1266 SWRI Une No.ISI SIse~FI.Marrl.~ln.Ihhrs Exempdon NDE~in.Merhod Po~Tern In?Une deserI'emarks N/A N/A OAN OAXN NOT S~Xl 5 210-BORIC ACID SIQRAGE TANK A OAN OAXN NOT SECT XI 5 210-BORIC ACID SIQRAGE TANK L Revised R 1 l/91 R I I/91 OM g H X 0+8)M H~g O 02 I-I NO P/3 LO Q~'LI3 H 0 H g 0 4QM U)ltd 0 Ft I 0 0 IL E.CINNA NUCLEAR POWER PIANT Inservice hrnlnatkat Bonndary Une Urt IIrlrd lnsPeenon Interval P&ID Nca.t 33013-1266 Chas t 2 Syrtern.t CVCS.BOIUC ACID Comp Iypet PIPING O H 0 RG&E Une Nca SASI0018 8SSIOOIA 3ACH.I 5 1 A 3SCH.ISIS 2ASI.I 5 I B 2SCH.I 5 1 B 2CSI.I 5 I A 2DCH 15 lb CEbert Une Nca SI~SI~SI~Sl~SI~Sl~SI~Sl~SWRI Une No.SSI-2001 851-2001 ISI SIte~FI.MarrL~in.8 15 A312 8.15 A312 Nlh Nlh A312 8-15 A312 N/A A312 8.15 A312 N/A A312 0322 L322 ILOOO 0.120 0.154 0.154 0.154 0.154 IWC 1221(A)IWC.1 221(h)IWC.1221(h) IWC.1221(A) IWC 1221(A)IW01221(A) NDE Method SUR/VOL SUB/VOL 5 210 Y 5 210 Y 5 210 Y 5 210 Y 5 210 Y 5 210 Y 5 210 Y 5 210 Y BORIC AQD TANK 8 TO 8 X 8 X 8 IEE.BOAIC AQD TANK h'10 S X S X 8 IEE.BORIC AQD TANK h'10 LOOP SEAL FLANGE.BORIC AQD TANK B I0 LOOP SEAL FIANCE.8 X 8 X 2 IEE ON SASMOI 8'10 VALVE 345.BORIC AQD TANK B TO HCV 105.8 X 8 X 2 IEE ON SSSIQOI A IO VALVE 331.BORIC AQD TAIrI(A I0 HCV 104.Po~Tern In?Une dercri'/remarks R 11/91 R 11/91 R 11/91 R 11/91 R 11/91 R 11/91 H~Q (I)~Q Q QQH XHR WOW H LD H$+~tO Q~C)M O td I~H X Er(U H tO 0 g H tI)H O e(E)HgQ 4 Q rE)(/)(D n 0 0 I nr It R.F GINNA NUCLEAR POWER PIANT Inservke Examlnsthn Boundary LIne IAst TMrd Inspeedon Intessral F&IDNo t 33013-12701 Chss.t 3 System-: WASTE DISPOSAI LIQUID DRAINS Comp~s COMPONENIS RG&E GtTbert SWRI Une No.Une No.Line No.151~fi.MatrL Size Tlrfsrs~In.~In.NDE Merliod Po T~em I at Une deseri'emarks O W 0 fWD03 FWD09 PWD12 TWDI 0 N/A N/A N/A N/A 0.00 OAI 0.00 0.000 OAKs 0.000 OAO 0.000 IWD l~IWD I22sk2 IWD 12202 IWD 12202<<275<<200<275<200<275<200<275<200 ULTRA FILTRATION SYSTEM.WASTE BLTEIL WASTE HOLDUP TANK PUMP.WASTE HOLDUP TANK.R 06/93'06/93 R 06/93 R 06/93 H 0 M L H td O+tAI H H tEI g+ON II3 O H tI3g 0 H g m U)tD 0 po 0 0 'H I I II II k I, N w I R E.0NNA NUQEAR POWER PIANT laservfce Examlnedon Boandtrry Une Ust Thhd lnspecUoa Interval PAID No t 33013-1270-1 assr r 3 Systcrn t WASIE DISPOSAI UQUID DRAINS Comp IPpe: PIPING O 0 RQkE line No.2A.WD0-151 0rIbert Une No.ISI Slee Ihtns Exemlmoa NDE~Fi.MetrL~h.~in.his Method Po I~em lInl LIne deseri n/remsrts N/A 200 0.143 IWD 12/0.1 I WST HOIDUP IX TO)792, WHT PUMP, 5 16 I OA R 06/93 H 0 Ul 0 H WO+LED H H LO g 0 M t." tO O H tO g'LO H 0 H g g H R 8 0 0 0 I W 1 II ll t l I N li'l IL E.GINNA NUCLEAR POWER PLANT tnsavke Exsmlnetlon Bonndsty line Ust Thltd Inspeetbn tntavsd PAID No-: 33013.1272-1 CInss-.: 3 Systan: WASTE DISPOSAI UQ.RC DRAIN TK Comp Type: PIPING RG8 E line No.+Wm iS>LSI~Fi.MatrL 4AQ OAXXt IWD-1220.1 ?FUEL TRANSFER CANAL TO VALVE 1711.Sixe Tidtns Exanpaon NDE~In.~b.Resls Method Po T~em le?Une deseri'ansths Radsed R 06/93 O H Q H~Q M~g Q ROC hl P g'LOHg~o tn o hj-I CgR tE?H Qem HRQ M 8 n 0 I K R.E.GINNA NUCLEAR POWER PIANT Inserrdee Examination Oomndary Une Ust Third lnspeetkrn Interval P8>ID No r 33013-12722 Chss t 2 System: WASIE DISPOSAI UQ-RC DRAIN TK Comp I)per PIPING O H 0 RG8>E U N 0Bberc Une No.SWRI Une No.ISI Size~Fi.MarrL~in.Po~Tern In?Une deseri'emarks 4A.WD 151 4OWD-151 3A WD.151 3B.WD 151 BAWD.1 51 3F WD 151 2A.WD 152 RHR400 RHR~RHR~RHR~RHR400 N/A A312 N/A A312 N/h A312 N/h A312 N/A A312 N/h N/A 4AS 3.00 3.00 3.00 300 (L120 ILI20 0.120 0.120 0.120 0.120 (k000 IWC I~A)IWG 1222(A)IWC 1222(h)IWC 1222(h)IWC 1222(h)IWC 1222(h)IWC 1222(h)2 80 2 80 2 80 2 80 2 80 PEN 143, TO 8431, 4 X 3 RDCR BEIQRE 1721.3A IO 3C.4h IO VALVE 1721>4C.VALVE 1722 TO 4C 4C IO VALVE 1003 IL 4 X 4 X 3 TEE ON 4C TO VALVE 1003A.PEN 129 TO 1716A, 1ST TEE W/RDCRS.R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 H 0 (/)g H XO+LO H O M~&LTj HLOO (O kO Q g'LO H 0 H g H 0 g rn M (D 0 0 I f I IL E.GINNA NUCLEAR POWER PlANT Insetvke Esuunlnsdon Boondety Une ust Thhd Inspeedon Inten>al PMD No t 33013-1272-2 CLsss: 3 Systetn t WASTE DISPOSAI UQ RC DRALI TI(Comp Type: PIPING O t3 H 0 RUTE>>0 Rhett SWRI 4>U N*ISI~F!.ManL Size Thkns Rmnpdon NDE~in.~tn.Besls Metho>I Po~Tern In?LIne deseri'emeths 3.WD2 151 3.00 th216 IWD.122IL I 7 FUEL TRANSFER DRAIN TO 17950>1722.H QM g H WO+'LO H r M tly>g gON I t17 O H tlyg LO H o H'g d g H K E.CINNA NUCLEAR POWER PIANT Snsenke Examinatron Boanday Une Ust IMrd Inspeedon lntaval P&ID No.: 33013.1275.2 Gast: 2 System.: WASIE DISPOSALCAS H2 RECOMBIN Comp Type: PIPINC A H 0 RG&E Lbe No.2A WDG-152N 2B.WDG 152N CBbat SWRI Une No.Une Nrx ISI~FI.MatrL N/h N/h Size Ihkns Exemp6sn~in.~ln.IWC 1222(A)IWC 1222(A)Po T~em In?Une rteseri'emarlts c275 c200-PEN 202 TO RDCR BEPORE VALVE IOS4IL PEN P304 TO VALVE 1084A.RRevtsrrI R 05/P3 R 06/93 0 M X H X A HIOH~tO'g gOM I HIOO LO H IO Q 0 H g Ul 9 0 I 0 O IL E.GINNA NUCLEAR POWER PIANT Insavice ExnmInntion Bontxhry LIne Ust Thhd Inrpeetbn Intavnl PAID No t 33013.1275-2 Chss t 3 Sprtan t WASTE DLSPOSALGAS H2 RECOMBIN Comp~PIPING O H 0 RGBE Une No.0Bbat SWRI Une No.Une No.ISI SIte~PI.MstrL~h.IMms Exanpnon NDE~b.Bssis Met trrsI Po~Tern In?Une desert'fremsrIrs 2CWDG-152N 2DWDG.152N N/A N/h 200 OAN0 IWD.122Q I<275<200-PEN202'IQIM25,N25A,3/O'REDCL A QSr93 2'1000 IWD 122sl1<275<200-PEN30iTOIM33,5433A,3/<'REDCL =A06/93 H 0 M re H R O+'LO H He@O Ul>re H HEI g LI3 O H Q OX 0 g0 M 8 n Pe 0 0 R.E.OINNA NUCLEAR POWER PIANT Insersriee hmlnrnkrn Boundary Une Ust Third Sspeetion Interval PMD No-t 33013.1277.1 Casa.: 2 System: STEAM GENERATOR BIOWDOWN Comp~: CON PONENIS H 0 RCM Une No.OtTbert Une No.SWRI Une No.ISI~Fi.Matrl SIse Thkns Exam pdon NDE~b.~h.Basis Method Po~Tern tnt line deseri'/remarks Revised Eh!SOIA EM501B B-I Bl SUR/VOL SVR/VOL 715 505 715 505 TIVS COMP ACCOVNTED FOR ON 33013.1231. THIS COMP ACCOUNTED MR ON 33013.1231. R 0dr/93 R 06/93 H Q M g H X 0~I H tO H~tOQ gOM I H~g IO 0 IO H o H g 0 Ul ID 0 0 It I' R.E.GINNA NUCLEAR POWER PIANT lnservlee Examlnanon Boundary Une Ust Third Inspeenon Interval PAID No,t 33013 1277.1 Class..: 2 System.t STEAM GENERATOR SLOWDOWN Comp T)pe: PIPING RCAE Une No.CBbert SWRI line No.Une No.ISI Site~FI.MatrL~ln.Po~Tern In?Une deserl'/remarlts 3A.BD600.IA 225D.BD600 lh 225DBD600.1B 2A.M5600.1A 2A-M5600.I B 28-M$600 lb 28 MS600 I B 2C M5600 I 8 SCB 100 SG8-200 SG8-100 SOB-200 SC8-200'400 N/A A106 N/A N/h N/A A106 B31 h106 N/A hl06 B31 A106 B31 A106 0.000 (1000 0.000 IL218 IL218 IL218 0218 IL218 IWC1222(A) lÃC 1222(A)IWG1222(h) IV&1222(h) 15%.1222(A) IWG 1222(A)IWO1222(A) WGI 222(h)1005 547 Y 1005 547 1005 547 1005 547 1005 547 1005 547 TEE 2A-M5600 lh 6 28 T0 5701.VALVE S701 TO VALVE 5738.VALVE S702 TO VALVE 5737.N.NOZZIE T0 FIRST TEE CIRTH WFID.N.NOZZLE T0 FIRST TEE C IRTH WELD.S.NOZZIE T0 HRST TEE CIRTH WFID.S.NOZZLE 10 FIRST TEE GIRTH WELD.2A M5600-IB It 28 TO VALVE 5702.R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 R 06/93 H 0 (/l X H W A+NOH H IO g+O (/)~I H100'LO H Cl Q H g NO A 0 O)(D 0 0 R.E.GINNA NUCLEAR POWER PIANT lnservhe Examinathn Boundary Une Lht Third Inspeenon Interval BkID No r 33013-1279 Class r 2 System r KST ACQDENTSAMPUNG Comp Types PIPING O H Q RGB Lbe No.3hSS-151 GBbert SWRI Une No.Une No.ISI Size~Fi.MatrL~in.3AO t1000 IWG 1222(A)PEN P107 TO VALVE 172L Tldms Exemption NDE~in.Bash Mctbod Po~Tern In?Une deserf remarits RReehed A IVPI H~m Q Ul~g Q WHY XOZ H IE)H$4 H M7 8 5 VC tE?H QWe HgQ IL E.GINNA NUCLEAR POWER FIANT Inservtoe Examination Borrndary Une Ust TInnl I spection Interval P&ID No..: 33013 1863 Qass t 2 System t CONTAINMENT HVAC SYSTEMS Comp T)re PIPING H 0 RG&E Une No GBbert SWRI lliinne eNo.line No.151 Slee~FI.MatrL~In.Po~Tern fat Lme deseri'eaaarfs IASUCT IAB.RET IBSUCT IGRET IGSUCI'DRET IDS OCT N/h N/h N/h N/A N/A N/h N/A Oi)0 OAO OAR Oi)0 OAS OAS aoo Did OAXO (LIMO OXNO IMOO IMOO IWC 1222(B)IWC 1222(B)IWC 1222(B)IWG 1222(B)IWGI 222(B)IWG1222N)IWG 1222(B)60 120 60 120 60 120 60 120 60 120 60 120 60 120 VLV 1559 TO'h'ONT REQRC FAN A SYS.VLV 1562 IIIRU PEN 305'IO CONIINMENT. VLV 1556 TO'IP CONT REQRC FAN B SYS.VLV 1574%IRU PEN 124'IO CONIINMENT. VLV 1571 TO"V CONT REQRC FAN C SYS.VLV 1568%IRU PEN 203 IO CONIINMENT. VLV 1563 TO'O'ONT REQRC FAN D SYS.A OI/92 R 06/93 h Ol/92 h 01/92 A 01/92 A 01/92 h Ol/92 hj Q OM g H WO+IDH Hu)Z O M pVX'4 0 HIDE'4 H o H g H 0 U)(t)0 I 0 0 k I V I R.E.GDINA NUCLEAR POWER PIANT Inseriee Kxamhsthn Boundnry Lhe LIst Third lnspeethn Interval PAID No: 33013-1865 Chss: 2 System: CONTAINMENT HVAC SYSTEMS Comp TPpet PIPING RGAE une No.0ihert IIne No.151 She Thhrs Exemption NDE~pi.MerrL~in.~h.Method Po~Tern In?Lhe desert'enartrs Revised N/A 6AO tL000 INC.1222(Cj 125 80~V 7445 OUT CONT PAST PEN 309 TO V 7478.R 06/93 Q M g H WO>tl)H H II3g+ON IQ t3 H 2e I hf d OW O V)ID 0 I 0 0 P V L E.GDINA NUCLEAR POWER PIANT Inserviee Xxaminadon Botmdary LIne ust Thhd tnspeedon interval PBID No-t 33013-1866 Chns: 2 System t CONTAINMENT PURGE EXH 5 MONIT Comp~: PIPING Gilbert SWRI Lbe No.IIne No.ISI Size~fi.MatrL~In.TIdms Exemption NDE~in.Basis Method Po~Tern In?une desert nrremsrts N/A 36AQ ILGOG IWC 1222(B)36'URGE EXHAUST IHRU PEN 300.0 M~g Q gH'g%OR I'LI2 H o e co HQQ RCW M 8 n 0 0 I II IL E.GINNA NUCLEAR POWER PIANT Insavke Exnmlnsfion Oottndery Line Ust 11drd speetion lntavnl BIFID No t 33013 1870 CIoss t 2 Systems HVACAIDQUARY dc INIEILK BLDG.Comp TTPet PIPING H 0 GBbat Une No.SWRI Une No.ISI Site~Fi.MstrL~ln.Tldms Exanption NDE~in.Bssis Method Po T~em In7 Une desefi'/rernsrks N/h 6AO (1000 IWC1222(C) 110 VALVE 7P70 PAST PEN P132 TO VALVE 7971.Revised R 06/93 H QM C H X 0~I HQH gOUl I pVW t17 0 H t17 g LI7 H p H g Q o F3 0 M 8 0 r.0 t'I ~IL E.GINNA NUQZAR POWER PIANT Insavice Estnminntion Ronnday Une List'IIdnI inspection Intavnl P8 ID No t 33013-1882 Qass: 2 Systan: CONTAINMENT BREATHING AIR Comp Type: PIPING O H 0 RGB Une No.GEbat SWRI UUnne eNo.Une No.ISI Size TIdms Exempdon NDE~PI.~~I~~~8 Mctbod Po T~em ln7 Une deseri rerrnrirs 6.AT-1 504 6 LT400 Nth Nlh 6'F000 IWC 1222iC)<275<200 VALVE 7443 TIIRU PEN P317 IO PIANGE.A I UPI 600 0.000 IWC.1222(C) <275<200 VALVE 7444 THRV PEN P313 IO PLANGE.R 06/93 H~OM~g Q HAH gH'g%OR HÃR5'Q H owe H@O 0 lf 4 1 IL E.GINNA NUCLEAR POWER PLANT lamvke Examhucha Boundary LIne Lbt Thinl nspeeaoa interred RG&E line No.GBbert LIne No.P&ID No t 33013-1886.2 Chess-t 2 System: SERVICE AIR Comp Type: PIPING ISI Size~Pi.MntrL~in.2AS 0AXO IWC.1222(A) NDE Method Po~Tern In?Une deseri remarks Revbed VALVE 714 I'IIIRU PEN P310 TO VALVE 7226.R 06r93 H 0'g H 0 M XH WO+IOH V H~g O M'LO Q tly H 0 g 0 Q 0 M I n 0 0 L E.GINNA NUQEAR POWER PIANT Insetvtee ExamInathn Bonndary Une 11st ThIrd lnspeethn Interval P&ID Nm.: 33013-1887 Chss..t 2 Systmn t INSTRUMENTAIR CONINMTBLDG Comp~PIPING O H 0 RG&E Une No.2-IA.1258 2AS DIXIE IWC 1222(A)VALVE 5392 THRU PEN P310 TO VALVE 5393.GBbert SWRI 51 SIte'Ihtns Ex empnon NDE Lbe Nsx Lbe No.~FI.MatrL~h.~in.Method Po T~em In7 Lbe deseri'emarks Revised A 11/91 H~OM~N Q s2s H 2g WOW H II3 sEs$~+otOOX>I Wma'LO H owe HgO U)8 0 Tt po 0 0 'v IL E.CINNA NIIQZAR POWER PIANT Insavite Examhrrrha ~Une Urt Tldrd Inrpecdon Intavrd PEdDNo t 3301319084 Cher t 2 S)rtan t PiUMARY WATER TREATMENT Comp T)per PIPINC H Q f RGB Lhe No.3 PW.125 I 2.PW 125-1 2A.PW.125'I CGbat SWRI Une No.Line No.ISI Size TIdrno~Fi.MrrrrL~h.~h.N/A N/A N/A IVi&1222(A) IWC 1222(A)IWC 1222(A)NDE Method Po~Tern In?Lhe desai remorirs 3 X 2 RDCR OUTSIDE TO 3 X 2 RDCR INSIDE.R 06/93 VALVE 8418 TO 3 X 2 RDCR ONSIDE CONTNMT.R 06/93 3 X 2 RDCR INSIDE CONTNMT TO VALVE IM19.R Odr/93 H 0 M g H Ez)0 hf>r HQH~tO'2c gOM I tO O H kg~eH ()h9 Q g 0 e m 0)(D ()-Tt 0 0 R.E.GINNA NUCLEAR POWER PIANT Insavke Examfmnion Bonndary Une Ust'Ihbd lnspeedon Intetval PMD No t 33013.1915 13ass t 2 System t HEATING SIKAId 5 CONDENSATK Comp~PIPING 0 H 0 RGAE Une No.GBbett SWRI Une No.Une No.Size Thhts Exempdon NDE~h.~in.Rasls Method Po T~em In?Une deseri'emasin PENEIRAIION 301 TO VAIVE 6165.Revised h I 1/91 0 M g H XA>eH H tO g+ON'LO O H tO g g tO H 0 H g g H 0 R.E.GINNA NUQZAR POWER PIANT Insnviee Examinadon Boundary Une Ust TMtd Inspection Interval RGAE Une No.GEbert SWRI Line No.Une No.P8 ID No..: 33013-1991 Qass.t 2 System...: FIRE PROTECllON IN CONTAINMENT Co p'Iype: PipiNG ISI~F1.MatrL SIse Tides Exam pthn NDE~in.~in.Basis Metissd Po~Tete In?Une deseti n/retnarka 0 H 0'g eh-FS-152 2A.F5400 N/A N/A ext0 OAXO 2.00 t1000 IWC 12t)2IA)IWC.1221(A) 135 80-VALVE 9227'IO VALVE 9229 IN CONTAINMENT. R 11/91 VALVE 5129 AT PEN P 103 TO 5130.A 11/91 H 0 N Q H RO>u)H H 113 g 0 0)td)O Hing LI)H<-o H Q F/)8 n 0 0 It t.t L E.GUINA NUCLEAR POWER PIANT Insaeice Exeminstha Bc rrrsLsry LIne Ust Thinl Inspecdon Intavei PMD No t 33013-2279.1 CLsss.: 3 System: WASTE EVAPORATOR SKID Comp Typa COMPONENTS O H 0 ROTE Line No.GBbat SWRI line No.Une No.ISI Size Thkns~Fi.MstrL~b.~b.N/A N/A N/A Exempthn IWD 1220.1 IWD.1220.1 IWD 1220.1 NDE Methotl Po T~em In?line Cesal remsrhs WASTE EVAPORATOR CONCENTRATOIL WASTE EVAPORATOR FEED TANK PUMP.WASTE EVAPORATOR FEED TANK R 06/93 R 06/93 R 06/93 H~ON~gQ QgH XHR%OR WP~HMT el'C)NOR I>I taea H LD O g H'4 H Oe TT2 HQO 0 0 cs ,1 L E.GINNA NUCIEAR POWER PIANT Ineervlee Eaunlnathm ~Une Iirt Thlnl Inrprethrn lntereaI P&lDNo t 33013-2279-1 Cher-: 3 System: WASTE EVAPORATOR SKID Comp T?per PIPING 13 O H 0 RG&E N N MA.WD9 I SB-WD9 MSA.WD9 0Qbert line No.ISI Pirl, M arrl.N/A N/h N/h I W 0.000 150 OAXrO OAXS IWD.122a I IWD 1220.1 IWD 1220.1~Tern In?line dererl remarks?WEFT TWDOB TO 2642D, WEFT PUMP.R 06/93?Ih TO SWDI 4, 26427.7Sh R 06/93?WE CONCENTRATOR EWD07'TO 2620C, SWD I 4 R 06/93 H OM NTN H WO gLOH~LI7 Q~O U?I HeO LI7 H p H g g H 0 V?O 0 r-0 0 QUALITY ASSURANCE MANUAL GINNA STATXON Section 6 EFFECTIVE DATE: PAGE 1 of 6 December 31, 1993 ROCHESTER GAS 8 ELECTRIC CORPORATION SIGNATURE DATE TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVXCE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ALLOCATION TABLES PREPARED BY: QUALITY ASSURANCE REVIEW: APPROVEO BY: 1.0 General This section identifies program examination.allocations for"ASME Code Required" and"Augmented Required" groups that will be performed during the third interval at R.E.Ginna Nuclear Power Plant.The tables identify the total number of components, the required number and the distribution of the required number within one of the three periods.The"ASME Code Required" group addresses the program requirements with respect to ASME Section XI.This group is divided into the following allocations. Class 1 Class 2 Class 3 Class 1, 2,&3 Supports The"Augmented Required" group addresses Rochester Gas&Electric commitments that were added to the.Inservice Inspection Program to ensure compliance to the commitments and performance. This group is divided into the following allocations. Reactor Coolant Pump Flywheel Program Reactor Vessel Augmented, Program, Category B-A High Energy Program Snubber Program Steam Generator Tubing Program Seismic Support Program Other additional"Owner.Elected" examinations are performed by Rochester Gas&Electric.These additional examinations are not mandatory and are determined by the owner to ensure additional safety and reliability of the plant.These additional"Owner Elected" examinations are not identified within the following allocation tables. QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ALLOCATION TABLES FIEV.Section 6 2 PAGE 2 of 6 ASME CODE RE UIRED Class 1 CatecaCor Total Receuired Third Interval Scheduled/Percent Period 1 Period 2 Period 3 B-A B-B B-D B-F B-G-1 B-G-2 B-J B-L-1 B-L-2 B-M-1 B-M-2 10 12 30 24 15 15 245 195 22 9 536 132 2 1 8.2 12 4 (*)if disassembled. 2/28.5%4/57.1%5/20.8>o 5/33.3~49/25.1~o 3/33.3%28/21.2~o 3/100~o 0/0<o 2/100<1/100+o 2/57.1~o 1/71.49'/45.8>o 3/53.3%49/50.2>o 3/66.64 51/59.8<o 0/1004 0/0>o 0/1004 3/1004 2/1004 13/100>o 7/100'7/100% 3/100'3/100~o 0/1009 1/1004 0/100>o (3 remaining, only if disassembled, Per RR g5.)B-N-1 B-N-2 B-N-3 I B-0 B-Q Total 20 950 479 1/33.3%0/0%0/04 0/04 3/27.2~o 18/304 1/66.64 0/0<o 0/0>o 0/0>o 4/63.6<o 24/70 1/100%2/100~o 1/100~o 3/1004 4/1004 18/1004 '\F 1 k QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ALLOCATION TABLES REV.Section 6 2 PAGE 3 of 6 Class 2~Cate or Total RecCuired Third Interval Scheduled/Percent Period 1 Period 2 Period 3 C-A C-B C-C C-F-1 C-F-2 C-H Total 22 30 131 677 387 72 1319 13 18 124 53 30 124 362 3/23.0%6/33.3%29/23.4<o 17/32'~o 10/33.3>o 39/31.4p 4/53.8~o 6/66.6~o 52/65.3~o 19/67.94 10/66.64 43/66.1%6/100~o 6/100~o 43/100>o 17/1004 10/100>o 42/100>o Class 3 CatecaCor r Total Receuired Third Interval Scheduled/Percent Period 1 Period 2 Period 3 D-A, D-B&D-C 145 141 38/26.9%54/65.2%49/100%D-A, D-B&D-C 30 Hydro/Leakage 164 53/32~3+o 51/64~3~o 60/100<Total 175 305 I QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ALLOCATION TABLES REV.2 PAGE 4 of 6 Section 6 Class 1 2&3 Su orts Ori ional Distribution to 1986 Code Class~Grou Total Receuired Third Interval Scheduled/Percent Period 1 Period 2 Period 3 Class 1 Class 2 Class 3 Total 159 377 477 1013 142 368 141 651 19/13.4~o 55/52.1>o 93/25 3+o 134/61 6+o 38/26.94 54/65.2>o 150/23.0%243/59.6<68/100<14 1/100~o 49/100>o 258/100%Inco oration of Code Case N-491 with 1986 Code Revised Distribution Program Reference Category Total Item Su orts Period 1 Completed Re uired Credited Period 2 Completed/Credited Period 3 Scheduled Scheduled 1986 Code Req.for Period 1 and'93 Outage F-A,B,C All Items 1013 651 150 Completed (23.0%)44 Completed 199 253 Scheduled Scheduled Code Case N-491 for Period 2 (Starting'94 Outage)and Period 3 F-A F1.10 F-A F1.20 F-A F1.30 F-A F1.40 114, 358 467 74 32 58 50 44 10 Credit 19 Credit 17 Credit 10 Credit 6 Credit 5 Sched.17 Credit 2 Sched.12 Credit 4 Sched.0 Credit 3 Sched.ll Sched.20 Sched.17 Sched.31 Sched.Totals 1013 184 56(30.4%)49 (57.0%)79 (100%)Au ented Re uired RCP Fl heel Pro ram: CatecaCor r Total Receuired Flywheel 2 6 Third Interval Scheduled/Percent Period 1 Period 2 Period 3 2/33 3+o 2/66~6+o 2/100> QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ALLOCATION TABLES REV.Section 6 2 PAGE 5 ot 6 Reactor Vessel Au ented Pro ram CatecaCor r Total RecCuired Cate or B-A: Third Interval Scheduled/Percent Period 1 Period 2 Period 3 B-A 0/0>0/O~o 3/1004 Hi h Ener Pro ram: CatecaCor r Total RecCuired Third Interval Scheduled/Percent Period 1 Period 2 Period 3 HE-CB 97 HE-CC (*)17 HE-DB 18 HE-LK 2 Total 134 97 17 54 174 34/354 9/52.94 18/33.34 2/28.5~o 30/65.9~o 3/70.6~o 18/66.64 2/57.l~o 33/100~o 5/100%18/1004 2/1 00+o (*)=Denotes Integral Attachment Code Case N-491 Class 2 Criteria Non-Class Hi h Ener Su ort Distribution Period 2 Period 1 Completed Program Category Total Completed/Credited Period 3 Reference Item Su orts Re uired Credited Scheduled Scheduled Requirement for Period 1 and'93 Outage.N/A 62 62 20 Comp.6 Comp.(31.7%)18 Sched.19 Sched.Code Case N-491 for Period 2 (Starting'94 Outage)and Period 3 N/A (F-A F1.20)62 3 Credit (27.3%)4 Credit 0 Sched.(63.6%)4 Sched.(100%) QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ALLOCATION TABLES REV.2 PAGE 6 of 6 Section 6 Snubber Pro ram: CatecaCor c Total RecCuired SN-VT (*)149 1039 Third Interval Scheduled/Percent Period 1 Period 2 Period 3 443/43.04 447/86.4%149/1004 SN-FT (Total 149 149 298 1188 48/32 2~o 57/70 4~o 44/100~o (*)=Note: Generic Letter 90-09 will be implemented during the'94 Outage of the Second Period.Seismic Su ort Pro ram Outside ASME Class Boundar Code Case N-491 Class 2 Criteria Seismic Su crt Distribution Program Reference Category Item Total Su orts Period 1 Period 2 Completed Credited Period 3 Re ired Credited Scheduled Scheduled Code Case N-491 for Period 2 (Starting'94 Outage)and Period 3 N/A (F-A F1.20)93 19 0 Comp.0 Credit: 9 Sched.(47.3%)10 Sched.(100%) QUALITY ASSURANCE MANUAL GINNA STATION Section 7 PAGE 1 of 3 EFFECTIVE DATE: December 31, 1993 ROCHESTER GAS 8 ELECTRIC CORPORATION TITLE APPENDIX B R.E.GXNNA NUCLEAR POWER PLANT ULTRASONXC CALIBRATXON BLOCK LXSTING SIGNATURE PREPARED BY: j~*QUALITY ASSURANCE REVIEW: APPROVE BY DATE i2-f i3 1.0 General: The list below identifies Ultrasonic Calibration Blocks that are owned by Rochester Gas&Electric and utilized at R.E.Ginna Nuclear Power Plant.Other calibration blocks not owned by Rochester Gas&Electric may be employed only if they meet the applicable requirements specified within ASME Section XI, 1986 Edition, no Addenda.IDENTIFICATION NUMBER 6-SS-108-.134-1A-REG 6-SS-408-.280-2-REG B-SS-108-.148-3-REG 8-SS-408-.322-4-REG B-SS-160-.906-5-REG 10-SS-108-.165-6-REG 10-SS-408-.365-7-REG 10-SS-140-1.0-8-REG '12-SS-SS-.156-9-REG 14-SS-10-.250-10-REG 14-CS-30-.375-11-REG PL-1.187-SS-12-REG PL-.30-SS-13-REG PL-3.5-CS-14-REG 9-CSCL-15-REG 7-CSCL-16-REG 5-CSCL-17-REG PL-3.0-SS-18-REG DESCRIPTION 6" D-SCHEDULE 10-SS-PIPE 6" D-SCHEDULE 40-SS-PIPE 8" D-SCHEDULE 10-SS-PIPE 8" D-SCHEDULE 40-SS-PIPE 8" D-SCHEDULE 160-SS-PIPE 10" D-SCHEDULE 10-SS-PIPE 10" D-SCHEDULE 40-SS-PIPE 10" D-SCHEDULE 140-SS-PIPE 12" D-SCHEDULE 5-SS-PIPE 14" D-SCHEDULE 10-SS-PIPE 14" D-SCHEDULE 30-CS-PIPE 1-187 THICK-SS-PLATE .30 THICK-SS-PLATE 3.5 THICK-CS-PLATE 9" THICK-CS-CLAD-VESSEL BLOCK 7" THICK-CS-CLAD-VESSEL BLOCK 5" THICK-CS-CLAD-VESSEL BLOCK 3" THICK-SS-PLATE MATERIAL SPEC.SA 312 SA 312 SA 312 SA 312 SA 312 SA 312 SA 312 SA 376 SA 312 SA 312 SA 106 SA 240 SA 240 SA 533 SA 508 SA 508 SA 508 SA 479 QUALITY ASSURANCE MANUAL GINNA STATION TITLf: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT ULTRASONIC CALIBRATION BLOCK LISTING Section 7 PAGE 2 of 3 IDENTIFICATION NUMBER 6-SS-160-.719-19-REG 4-SS-160-.531-20-REG 3-SS-160-.438-21-REG 8.5-6-8-CS-22-REG 6-1-8-CS-23-REG IR-CSCL-24-REG 6-SS-120-.562-25-REG FS/NS-CSCL-26-REG IR-CSCL-27-REG CRD-SS/IN-.656-28-REG 10-SS-140-1.0-29-REG 3.5-.625-8-CS-30-REG 5.375-3.5-8-CS-31-REG 1.187-8-7-CS-32-REG 1.187-N-7-CS-33-REG 1.125-8-12-CS-34-REG 1.125-N-12-CS-35-REG 1.250-8-7-CS-36-REG 1.250-N-7-CS-37-REG 10-SS-160-1.147-70 6-SS-X-1.1-38-REG 29-SS-X-2.5-39-REG SI/N-CSCL-40-REG 27.5-CSS-X-2.4-41-REG 29-CSCL-X-2.5-42-REG 5.437-SS-X-1.0-43-REG PL-1.5-CS-44-REG 14-CS-100-.938-45-REG DESCRIPTION 6" D-SCHEDULE 160-SS-PIPE 4" D-SCHEDULE 160-SS-PIPE 3" D-SCHEDULE 160-SS-PIPE REACTOR PRESSURE VESSEL NUT REACTOR PRESSURE VESSEL STUD O.D.INNER RADIUS BLOCK 6" D-SCHEDULE 120-SS-PIPE FLANGE AND NOZZLE SHELL BLOCK NOZZLE INNER RADIUS BLOCK SS-CONTROL ROD DRIVE BLOCK 10" D-SCHEDULE 140-SS-PIPE REACTOR COOLANT PUMP STUD REACTOR COOLANT PUMP NUT MATERIAL SPEC.SA 312 SA 376 SA 376 SA 320-L43 SA 320-L43 SA 533 SA 312 SA 533 SA 553 SA 182 SA 312 ACTUAL STUD ACTUAL NUT 1 187" DIA.X 7 THREADS/IN-CS-STUD SA 193 1.187" DIA.X 7 THREADS/IN-CS-NUT SA 194 1.250" DIA.X 7 THREADS/IN-CS-NUT 10" D-SCHEDULE 160-SS-PIPE 6" D-1.1" WALL-SS-PIPE 29" ID-SS-PIPE SAFETY INJECTION NOZZLE BLOCK 27.5" ID-CS-PIPE 29" ID-CLAD-CS-PIPE 5.437" D-1" WALL-SS-PIPE 1.5" THICK-CS-PLATE 14" D-SCHEDULE 100-CS-PIPE SA 194 SA 312 SA 182 SA 182 SA 508 SA 351 SA 508 SA 182 SA 285 SA 106 1.125" DIA.X 12 THREADS/IN-CS-STUD SA 193 1.125" DIA.X 12 THREADS/IN-CS-NUT SA 194 1.250" DIA., X 7 THREADS/IN-CS-STUD SA 193 II QUALITY ASSURANCE MANUAL GXNNA STATION TITLE: APPENDIX B R-E-GXNNA NUCLEAR POWER PLANT ULTRASONIC CALIBRATION BLOCK LISTING REV.Section 7 1 PAGE 3 of 3 IDENTIFICATION NUMBER 18-CS-100-1.156-46-REG 4-SS-80-.337-47-REG 3-SS-80-.300-48-REG 4.25-R-CS-N/RB-49-REG 1.250-B-6-A490-50-REG 1.375-8-17-A490-51-REG 1.375-8-24-A490-52-REG 1.375-S-33-A490-53-REG 3-SP-14-A514-GRF-54-REG 2-IC600-80-J-NOZ-55-REG 1.875-9-8N-CS-56-REG 1.0-4-8N-CS-57-REG 1.875-S-S-CS-58-REG 2.89-1.87-8-CS-59-REG 2-CS-, 40-.218-60-REG S-CS-100-.594-63-REG 15.0-SS-X-1.60-61-REG 20-CS-X-1.281-64-REG 24-CS-80-1.218-65-REG 30-CS-X-,1.250-66-REG 36-CS-X-1.47-67-REG 3.0-CS-80-.218-68-REG DESCRIPTION 18" D-SCHEDULE 100-CS-PIPE 4" D-SCHEDULE 80-SS-PIPE 3" D-SCHEDULE 80-SS-PIPE REACTOR PRESSURE VESSEL NUT REFERENCE BLOCK S/G SECONDARY MANWAY BOLT 1.375 DIA.X 17" LONG-STEEL-STUD 1.375 DIA.X 24" LONG-STEEL-STUD 1.375 DIA.X 33" LONG-STEEL-STUD COLUMN PIN S/G"j" NOZZLE S/G AND PRESSURIZER MANWAY BOLT S/G HAND HOLD BOLT S/G PRIMARY MANWAY STUD S/G PRIMARY MANWAY CLOSURE NUT 2" BLOWDOWN 8" FW BLOCK 15" PZR BLOCK 20" FW BLOCK 24" MS BLOCK 30" MS BLOCK 30" MS BLOCK 3" BLOWDOWN MATERIAL SPEC.SA 106 SA 312 SA 312 SA'516 ASTM A 490 ASTM A 490 ASTM A 490 ASTM A 490 ASTM A 514 INCONEL 600 SA 193 SA 193 SA 193 SA 193 SA 335 SAW6-GR B SA182-F316 SA333-GR 6 SA106-GR B SA517-GR 70 SA517-GR 70 SA335-QUALITY ASSURANCE MANUAL GINNA STATION Section 8 EFFECTIVE DATE: PAGE 1 of 8 December 31 1993 ROCHESTER GAS 6 ELECTRIC CORPORATION SIGNATURE DATE TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL HIGH ENERGY PROGRAM PREPARED BY: QUALITY ASSURANCE R APPROVED BY'z-g-)3 g,M IE I.P-3-1.0 General: The augmented inservice inspection program for High Energy (Class 6 Non-Class) Piping, outside of containment, as established in Rochester Gas and Electric Corporation's Report"Effect of Postulated Pipe Breaks Outside the Containment Building", dated October 29, 1973, provides for the examination of all identified circumferential butt welds at design break locations and at discontinuity (Consequential) locations where a failure would result in unacceptable consequences. This program also establishes a Non-Class High Energy Piping component support examination requirements. The required examinations are used to detect any change in condition or development of service induced flaws in advance of a potential failure.Surveillance of these components by the inspection program provides assurance that the design basis or consequential Main Steam or Feedwater breaks will not occur.2.0 Examination Requirements:

2.1 Identified

High Energy Piping circumferential butt welds at, design break locations and discontinuity (consequential) locations shall be examinedutilizing volumetric, surface and visual examination techniques. 4 t I QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E-GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION REPORT FOR THE 1990-1999 INTERVAL HIGH ENERGY PROGRAM REV.3 PAGE 2 of 8 Section 8 I 2.2 Identified Non-Class High Energy Piping component supports shall be examined utilizing visual examination techniques. For periods 2 and 3, a reduced selection shall be utilized based on the requirements of Code Case N-491 for Class 2 piping supports.This sampling scheme requires a 15%sample distribution among the systems and support types within each system.All integral attachments associated with High Energy component supports shall receive a surface examination, based on the Code requirements for Class 2 piping integrally welded attachments.

2.3 Examinations

on High Energy Piping circumferential butt welds at design break locations and consequential break locations, as well as component supports and integrally welded attachments, are identified within Table 1 of this section.I 2.4 2.4.1 2.4.2 System Pressure Testing and associated visual examination for leakage, shall be performed on the main run of the High Energy Piping.The 10-year Hydrostatic testing requirements for High Energy Piping was derived from ASME Section XI Code, IWC-5000, as a continuation of the Class 2 boundary.With the implementation of Code Case N-498 within the ISI Program, the code case requirements may be performed in lieu of hydrostatic test requirements for High Energy Piping.Leakage testing requirements for High Energy Piping was derived from ASME Section XI Code, IWC-5000, as a continuation of the Class 2 boundary.3.0 Examination Methods: 3.1 Applicable examinations shall be performed in accordance with 1.7.1, 1.7.2, 1.7.3 and 1.7.4 of Section 1. QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION REPORT FOR THE 1990-1999 XNTERVAL HXGH ENERGY PROGRAM REV.Section 8 3 PAGE 3 of 8 4.0 4.1 Frequency of Examination Xdentified High Energy Piping circumferential butt welds at design break locations shall be examined once each period.Circumferential. butt welds at.discontinuity (consequential) locations shall be examined once per interval.4.3 Selected Non-Class High Energy Piping component supports shall be examined once per interval.Identified High Energy Piping Xntegrally welded attachments shall be examined once per interval.4~4 4.5 5.0 On the main run of High Energy Piping pressure boundary, a Leakage examination shall be performed once per period.In lieu of a Hydrostatic Test once per interval on the main run of High Energy Piping pressure boundary, a Leakage examination may be performed once per interval to Code Case N-498 criteria.Examination Evaluation: 5.1 Thh evaluation of examinations of the High-Energy piping welds outside of containment will be in accordance with Section XI XWC-3130 for visual examinations and IWC-3120 for volumetric and surface examinations. Evaluations of radiographic results shall be in accordance with the acceptance criteria for radiographic examinations referenced in USAS B31.1.0-1967,"Power Piping" and"ASME Section XI." Ultrasonic Examinations performed in accordance with the requirements of Appendix I and III and the acceptance criteria in USAS B31.1.0-1967 (Radiography). Visual examinations of identified High Energy Piping Supports will be evaluated in accordance with IWF-3000 for Period 1, and-3000 of Code Case N-491 for Periods 2 and 3. QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION REPORT FOR THE 1990-1999 INTERVAL HIGH ENERGY PROGRAM REV.Section 8 3 PAGE 4 of'8 6.0 6.1 Repair&Testing Requirements: Repairs and applicable system pressure tests performed on ASME Class 2 and 3 High Energy pressure retaining piping and associated component supports and integral attachments shall conform to the requirements"specified within Supplement 2 to Appendix B, the Repair, Replacement and Modification Program.Code Case N-498 does not apply to Repairs.7.0 7.1 8.0 Replacement &Testing Requirements: Replacements, including Modifications, and applicable system pressure tests performed on ASME Class 2 and 3 High Energy pressure retaining piping and associated component supports and integral attachments shall conform to the requirements specified within Supplement 2 to Appendix B, the Repair, Replacement and Modification Program.Code Case N-498 does not apply to Replacements and Modifications. Scheduling: 8.1 8.2 9.0 Scheduling of the High Energy Program piping welds, component supports and integral attachments shall be performed and controlled within.Supplement 1 to Appendix B, the Program Plan.Table 1 identifies welds, component supports and integral attachments that are within the High Energy Program.Reports and Records: 9.1 Reports and Records generated on High Energy pressure retaining components, integral attachments and component supports shall conform, as applicable, to the requirements of Section 1 and Supplement 2 to Appendix B, the Repair, Replacement and Modification Program. QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION REPORT FOR THE 1990-1999 INTERVAL HIGH ENERGY PROGRAM REV.Section 8 3 PAGE 5 of 8 TABLE 1 HIGH ENERGY PROGRAM MAIN STEAM LOOP A-WELDS:-Desi n Basis Break 30A-MS-600-1A D 30A-MS-600-1A F1 30A-MS-600-1A D1 36-MS-600-1 L1 Conse uential Break 30A-MS-600-1A 30A-MS-600-1A 30A-MS-600-1A 30A-MS-600-1A 30A-MS-600-1A 30A-MS-600-1 30A-MS-600-1 D2 E E2 G G2 J L 30A-MS-600-1A 30A-MS-600-1A 30A-MS-600-1A 30A-MS-600-1A 30A-MS-600-1A 30A-MS-600-1 D3 E1 F G1 H K MAIN STEAM LOOP B-WELDS: Desi n Basis Break 30B-MS-600-1B D 30B-MS-600-1B J1 Conse uential Break 30B-MS-600-1B H1 36-MS-600-1 P1 30B-MS-600-1B 30B-MS-600-1B 30B-MS-600-1B 30B-MS-600-1B 30B-MS-600-1B 30B-MS-600-1 D1 E K L1 M 0 30B-MS-600-1B 30B-MS-600-1B 30B-MS-600-1B 30B-MS-600-1B 30B-MS-600-1 30B-MS-600-1 D2 J L L2 N P QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION REPORT FOR THE 1990-1999 INTERVAL HIGH ENERGY PROGRAM REV.3 PAGE 6 of 8 Section 8 TABLE 1 Cont.MAIN STEAM-TURBINE BUILDING-WELDS: Desi n Basis Break 36-MS-600-1 L2 Conse uential Break 36-MS-600-1 24A-MS-600-1A 24A-MS-600-1A 24A-MS-600-1A 24B-MS-600-1A 24B-MS-600-1A 24B-MS-600-1A L4 B Cl Dl B C D 24A-MS-600-1A 24A-MS-600-1A 24A-MS-600-1A 24B-MS-600-1A 24B-MS-600-1A 24B-MS-600-1A A Bl D A Bl Cl FEEDWATER-TURBINE BUILDING-WELDS: Desi n Basis Break 20-FW-900-1 M3 Conse uential Break 20-FW-900-1 20-FW-900-1 20-FW-900-1 20-FW-900-1 8-FW-900-1 8-FW-900-1 8-FW-900-1 8-FW-900-1 J L M M2 B D F H 20-FW-900-1 20-FW-900-1 20-FW-900-1 8-FW-900-1 8-FW-900-1 8-FW-900-1 8-FW-900-1 Kl Ll Ml A C E G I H I QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION REPORT FOR THE 1990-1999 INTERVAL HIGH ENERGY PROGRAM Section 8 PAGE 7 of 8 TABLE 1 Cont.FEEDWATER LOOP A-WELDS: Desi n Basis Break 20-FW-900-1 M4 20-FW-900-1 U2 Conse uential Break 20-FW-900-1 Ul 14A-FW-900-lA AA 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1A 14A-FW-900-1A 14A-FW-900-1A T2 U7 U6 VA Vl V2A W Y Zl Z3 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1 14A-FW-900-1A 14A-FW-900-1A 14A-FW-900-1A 14A-FW-900-1A T3 U5 V VB V2 V2B X Z Z2 Z4 FEEDWATER LOOP B-WELDS: Desi n Basis Break 20-FW-900-1 Al 14B-FW-900-1B N Conse uential Break 20-FW-900-1 F4 14B-FW-900-1B V 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1B 14B-FW-900-1B 14B-FW-900-1B F3 Fl G Gl G4 HA Hl H2A z L Nl 01 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1 14B-FW-900-1B 14B-FW-900-1B 14B-FW-900-1B F5 F2 G2 G3 H HB H2 H2B K M 0 P f I E QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION REPORT FOR THE 1990-1999 INTERVAL HIGH ENERGY PROGRAM REV.3 PAGE 8 of 8 Section 8 TABLE 1 Cont.MAINSTEAM-COMPONENT SUPPORTS: (*)MSU-35 (*)MS-34 (*)MS-35 (*)MS-47 MS-59 MS-36 MS-37 (*)MS-150 MS-38 MS-39 MS-151 MS-40 (*)MS-41 S13A S13B MS-42 MS-43 MS-167 MS-153 MS-44 (*)MS-149 MS-45 (*)MS-46 S23A S23B FEEDWATER-LOOP A-COMPONENT SUPPORTS FWU-16 FWU-17 (*)FWU-18 FWU-19 FWU-20 (*)FWU-21 FWU-22 FWU-23 FWU-24 FWU-25 (*)FWU-26 (*)FWU-27 (*)FWU-28 FEEDWATER-LOOP B-COMPONENT SUPPORTS FWU-36 FWU-35 FWU-34 FWU-32 FWU-33 FWU-31 FWU-30 (*)FWU-29 FWU-40 (*)FWU-39 FWU-38 FWU-37 FEEDWATER-MAIN-COMPONENT SUPPORTS FW-37 FW-38 FW-39 FW-40 FW-41 FW-42 FW-43 (*)FW-45 FEEDWATER-RECIRCULATION LINE-COMPONENT SUPPORTS: CD-167 CD-168 CD-169 (*)CD-170 NOTE:*=Integral Attachments QUALITY ASSURANCE MANUAL GXNNA STATION Section 9 EFFECTIVE DATE: PAGE 1 of 4 December 31, 1993 ROCHESTER GAS 8, ELECTRIC CORPORATION SIGNATURE DATE TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL SNUBBER PROGRAM PREPARED BY QUALITY ASSURANCE REVIEW: APPROVED Y: 1.0 General: 1.2 1.2.1 The inspection and testing of all safety related snubbers shall be implemented and performed in accordance with Mechanical Engineering Specification ME-256,"Snubber Xnspection 6 Test Program", to ensure the required operability of these snubbers during a seismic or other event, initiating dynamic loads.The snubber program, as defined within ME-256, establishes both visual examination and functional testing requirements. This program pertains to mechanical and hydraulic snubbers.1.2.2 The snubber program includes: a~b.c~d.e.f.g h.Visual Inspection Requirements Visual Inspection Failure Evaluation Visual Inspection Corrective Action and Impact on Examination Frequency Functional Testing Requirements Functional Test Sample Functional Test Failure Analysis Functional Testing Corrective Action Functional Testing Methods Inspection and Testing Documentation 1.3 The Snubber Program adheres to the requirements of ASME Section XI, 1986 Edition Article XWF and includes guidence provided by ASME/ANSI OMc-1990, Part 4.1.4 R.E.Ginna Nuclear Power Plant Technical Specifications establishes a Snubber Seal Service Life Monitoring for Hydraulic Snubbers that is controlled by R.E.Ginna Station Procedures. II II i l Y QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL SNUBBER PROGRAM REV.Section 9 3 PAGE 2 of 4 2.0 Examination, Testing and Monitoring Requirements: 2.1 Visual (VT-3)Examinations and Functional (FT)Testing shall be performed to the extent specified within ME-256.2.2 The seal service life of hydraulic snubbers shall be monitored and seals replaced as required to ensure that the service life is not exceeded between surveillance inspections during a period when the snubber is required to be operable.The seal replacement shall be documented and retained in accordance with Technical Specification.

3.0 Examination

and Testing Methods: 3.1 Visual (VT-3)Examinations and Functional (FT)Testing'shall be performed to'.,verify the requirements specified within ME-256, as a minimum.4.0 Examination and Testing Frequency: 4.1 4.2 4.3 Visual (VT-3)Examinations and Functional (FT)Testing shall be performed at the frequency specified within ME-256.Visual (VT-3)Baseline Examinations shall be performed whenever new snubbers are installed, reinstallation of existing or swapped snubbers that were functionally tested, or after repairs, replacements or modifications. Functional testing requirements for new installations or spares shall be equal to or more stringent than that specified within ME-256.5.0 Examination, Testing and Monitoring Evaluation: I 5.1 Snubbers that do not appear to conform with the Visual (VT-3)Examination requirements of Mechanical Engineering Specification ME-'256, shall be reported for evaluation and appropriate corrective action.Visual examination failure evaluation shall be performed when necessary and required by ME-256.Corrective action may include repair, replacemen't or modification of the snubber.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL SNUBBER PROGRAM REV.Section 9 3 PAGE 3 of 4 5.2 Snubbers that do not appear to conform with the visual examination acceptance requirements and are later confirmed as failures and appears inoperable may be declared operable for the purpose of establishing the next visual inspection interval, providing that: (1)the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2)the affected snubber is functionally tested in the"as found" condition and determined operable.All snubbers found connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable for determining the next inspection interval.Snubbers that, do not appear to conform with the visual examination acceptance requirements and are later confirmed as failures but does not appear inoperable shall not be declared inoperable and the cause of the rejection shall be remedied.5.3 Snubbers that do not meet the operability testing acceptance criteria in ME-256 shall be evaluated to determine the cause of the failure and appropriate corrective action taken.5.4 The service life of a snubber is evaluated via manufacturing input and engineering information through consideration of the snubber service conditions and functional design requirements. The only snubber components with service lives not expected to exceed plant life are seal and o-rings fabricated from certain seal materials. Therefore, a seal replacement program is required to monitor snubber seal and o-ring service life and to assure snubber operability is not degraded due to exceeding component service life. t K QUALITY ASSURANCE MANUAL GINNA STATXON TITLE: APPENDIX B R.E.GXNNA NUCLEAR POWER PLANT INSERVICE XNSPECTION PROGRAM FOR THE 1990-1999 INTERVAL SNUBBER PROGRAM REV.3 PAGE 4 of 4 Section 9 6.0 6.1 Repair, Replacement and Modification Requirements: Repairs, Replacements and Modifications performed on snubbers under this program shall conform, as applicable, to the requirements specified within Supplement 2 to Appendix B, the Repair, Replacement and Modification Program.7.0 7.1 7.2 Scheduling: The Visual Examinations and Functional Testing schedules shall be established, tracked and maintained within Supplement 1 to this Appendix.The Xnservice Inspection Program Plan shall identify and track expanded or additional testing and/or examinations as specified and required by ME-256.8.0 Reports and Records: 8.1 Reports and records for the Visual (VT-3)Examinations and Functional (FT)Testing shall be maintained on all snubbers listed within ME-256.8.2 8.3 Applicable records and reports, as required by Supplement 2 for Repairs, Replacements or Modifications, shall be maintained for snubbers.Records of the service lives of all hydraulic and mechanical snubbers listed in this program, including the date at which the service life commences, and associated installation and maintenance records will be maintained.

QUALITY ASSURANCE MANUAL GINNA STATION Section 10 REV.PAGE 1 oI 6 EFFECTIVE DATE: December 31, 1993 ROCHESTER GAS 8 ELECTRIC CORPORATION SIGNATURE DATE TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL SEISMIC SUPPORT PROGRAM PREPARED BY QUALITY ASSURANCE REVIEW: APPROVED': I2-I-$3 fr-4->3 1.0 General: 1.2 The augmented inservice inspection program for Seismic Category I supports outside of the ASME Class boundary was developed to provide greater assurance that identified component supports will operate when and if needed during a seismic event.Seismic Category I supports outside of the ASME Class boundary are identified in Table 1.2.0 I 2ol 3.0 Examination Requirements: Selected Seismic Category I supports shall be examined utilizing visual (VT-3)examination techniques. Support selection shall be based on Code Case N-491 for Class 2 piping supports.This sampling scheme requires a 15%sample distributed among the systems and support types within-each system.Examination Methods: 3.1 The visual (VT-3)examination shall be performed in accordance with Section 1.4.0 Frequency of Examination: 4.1 5.0 The selected sample shall be examined at least once during the inspection interval.Examination Evaluation: 5.1 The visual (VT-3)examination results shall be evaluated in accordance with IWF-3000 for Period 1, and-3000 of Code Case N-491 for Periods 2 and 3. QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL SEISMIC SUPPORT PROGRAM REV.Section 10 1 PAGE 2 of 6 5.2 6.0 6.1 7.0 7.1 8.0 8.1 9.0 9.1 Supports which do not meet the visual (VT-3)examination requirements shall be reported for evaluation and appropriate corrective action.Repair&Testing Requirements: Applicable repairs and testing shall be performed to the requirements of Supplement 2 to Appendix B, the Repair, Replacement and Modification Program.Code Case N-498 does not apply to Repairs.Replacement &Modification, and Testing Requirements: Replacements and Modifications, and applicable testing shall be performed to the requirements of Supplement 2 to Appendix B, the Repair, Replacement and Modification Program.Code Case N-498 does not apply to Replacements and Modifications. Scheduling: Scheduling of identified Seismic Category I supports shall be performed and controlled within Supplement 1 to Appendix B, the program plan.Reports and Records: Reports and records generated on identified Seismic Category I supports shall conform to applicable requirements specified within Section 1 and Supplement 2 to Appendix B.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E-GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL SEISMIC SUPPORT PROGRAM Section 10 PAGE 3 of 6 Table 1 Seismic Category I Supports Line Segment: AFW100 Support Number AFU-130 AFU-139 Support Number AFU-132 Support Number AFU-137 Support Number AFU-138 Line Segment: AFW200 Support Number AFU-88 Line Segment: AFW300 Support Number AFU-4 Support, Number AFU-5 Support Number AFU-6 Support Number AFU-7 Line Segment: CfTC100 Support Number CVU-84 Line Segment: CVC200 Support Number CVU-125 Support Number CVU-126 Support Number CVU-129 Support Number CVU-130 Line Segment: CVC700 Support Number CVC-56 Support Number CVC-58 QUALIT'Z ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL SEISMIC SUPPORT PROGRAM REV.Section 10 1 PAGE 4 of 6 Table 1 (Cont.)Seismic Category I Supports Line Segment: CVC730 Support Number CVC-39 Support Number CVC-40 Line Segment: FW300Support Number FWU-40 FWU-36 FWU-32 FWU-28 Support Number FWU-39 FWU-35 FWU-31 Support Number FWU-38 FWU-34 FWU-30 Support Number FWU-37 FWU-33 FWU-29 Line Segment: FW301 Support Number FWU-16 FWU-20 FWU-24 Support Number$'WU-17 FWU-2 1 FWU-25 Support Number FWU-18 FWU-22 FWU-26 Support Number FWU-19 FWU-23 FWU-27 Line Segment: MS300 Support Number MSU-35 MSU-52 MSU-48 MSU-57 Support Number MSU-59 MSU-53 MSU-49 Support Number MSU-60 MSU-54 MSU-50 Support Number MSU-51 MSU-47 MSU-56 Line Segment: RHR300 Support Number RHU-86 Support Number RHR-87 Support Number RHU-90 Support Number RHR-91 QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL SEISMIC SUPPORT PROGRAM REV.Section 10 1 PAGE 5 of 6 Table 1 (Cont.)Seismic Category I Supports Line Segment: SAFW450 Support Number AFU-169 AFU-177 Support Number AFU-170 Support Number AFU-175 Support Number AFU-176 Line Segment: SGB-300 Support Number BDU-21 Support Number BDU-23 Line Segment: SGB-400 Support Number BDU-26 Support Number BDU-27 Line Segment: S2100 Support Number SIU-8 Line Segment: SI200 Support Number SIU-55 Line Segment: SW1500 Support Number SWU-363 Support Number SWU-364 Support Number SWU-365 Support Number SWU-366 II'I QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E-GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL SEISMIC SUPPORT PROGRAM REV.1 PAGE 6 of 6 Section 10 Table 1 (Cont.)Seismic Category I Supports Line Segment: SW2100 Support Number SWU-523 SWU-533 Support Number SWU-524 SWU-534 Support Number SWU-525 Support Number SWU-526 Line Segment: SW2300 Support Number SWU-602 SWU-606 Support Number SWU-603 SWU-607 Support Number SWU-604 Support Number SWU-605 Line Segment: SW2500 Support Number SWU-637 SWU-638 Support Number SWU-642 Support Number SWU-639 Support Number SWU-640 QUALITY ASSURANCE MANUAL GINNA STATION Section ll EFFECTIVE DATE: PAGE 1 of 9 December 31, 1993 ROCHESTER GAS 8 ELECTRIC CORPORATION TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ADDITIONAL PROGRAMS SIGNATURE PREPARED BY:$~+)g QUALITY ASSURANCE REVIEW: APPROVED Y: DATE I~-I-6 lZ44 1.0 General: The purpose of this section is to provide information and clarification on additional inspection programs being performed at R.E.Ginna Nuclear Power Plant.These inspection programs may be due in part to ASME Section XI program requirements or to other commitments made by Rochester Gas and Electric.The following list identifies additional inspection programs being performed at R.E.Ginna Nuclear Power Plant: Steam Generator Tube Inspection Program Reactor Coolant Pump Flywheel Program Class 1 Bolting Program (IEB 82-02)., Reactor Vessel Augmented Program, Category B-A 2.0 Steam Generator Tube Ins ection Pro ram: 2.1 General: 2~1.1 The Steam Generator Tube Inspection Program incorporates the requirements of ASME Section XI Code, under Category B-Q, Item Number B16.20.The Code requires that Steam Generator tubing in U-Tube Design be volumetrically (Eddy Current)examined to the extent and frequency governed by the plant Technical Specifications. In accordance with this Code requirement and R.E.Ginna Station Technical Specifications, eddy current examinations shall be performed. Steam Generator Tubing shall be examined their full length, at least once every five years. I' QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ADDITIONAL PROGRAMS REV.Section ll 3 PAGE 2 of 9 2.1.2 The Steam Generator Tube Inspection Program also incorporates the requirements of USNRC Regulatory Guide 1.83, Revision 1, dated July, 1975,"Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes" and the recommendations of the Electric Power Research (EPRI)PWR Steam Generator Inspection Guidelines, Revision 2.2.2 Examination Requirements: 2.2.1 The program for each year of the five years shall include, as a minimum, the following requirements: l.A rotating random sampling of 20%of all operational tubes for their full length.2.A rotating random sample of 20~of each type of sleeved inlet tube for their full length,, including the sleeve from the upper end through the expanded transition of the lower end.3.All operational tubes that had a previously identified degradation of greater than 20%through wall to the extent of previously identified degradation. However, if after two (2)consecutive inspections these tubes have not had greater than 104 further penetration, the inspection frequency on these tubes may be extended to 40 months.2.2.2 2Other tubes may be added to the program each year as necessary to meet other concerns and are classified as"owner elected"."Owner Elected" examinations are not mandatory and may be performed as determined by the owner.The Ginna Steam Generator Reliability Committee may change the aforementioned plan to meet outage schedules, provided that the changes meet the requirement of Regulatory Guide 1.83 and Supplement 1 to this Appendix.2.3 Examination Method: 2.3.1 Eddy Current (Volumetric) Examination techniques shall be employed to perform the required examinations on Steam Generator tubes. QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ADDITIONAL PROGRAMS REV.Section 11'PAGE 3 of 9 2.4 2.4.1 2.5 Frequency of Examinations: Examinations shall be performed every refueling outage to the extent required and specified within 2.2, as a minimum.Examination Evaluation: 2.5.1 Eddy Current evaluation shall be performed in accordance with R.E.Ginna Station Technical Specifications. 2.6 2.6.1 Repair, Replacement and Testing Requirements Repair criteria for steam generator tubes is based on the requirements of Regulatory Guide 1.121,"Bases for Plugging Degraded PWR Steam Generator Tubes".2.6.1.1 2.6.1.2 2.6.2 2.7 2.7.1 2.8 2.8.1 Steam generator tubes that have imperfections greater than 40 percent through-wall as indicated by eddy current, shall be repaired by plugging or sleeving.Steam generator sleeves that have imperfections greater than 30 percent through wall as indicated by eddy current shall be repaired by plugging.Repairs by welded plugs and sleeves shall be performed in accordance with Supplement 2 to this Appendix.Scheduling: Eddy Current examination schedules of Steam Generator Tubes shall be established within Supplement 1 to this Appendix.Reports and Records: Applicable records shall be maintained as specified within Section 1 of this program and as applicable and required within Supplement 2 to this Appendix. QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ADDITIONAL PROGRAMS REV.Section 11 3 PAGE 4 of 9 2.8.2 Within 15 days following the completion of the evaluation of each inservice inspection of steam generator tubes, the number of tubes required by Paragraph 2.6.1 above to be plugged or sleeved in each steam generator shall be reported to the USNCR in,a Special Report.2.8.3 The complete results of the steam generator tube inservice inspection shall be submitted to the USNRC in a Special Report within 12 months following the completion of the inspection. This Special Report shall include: (a)Number of tubes inspected and extent to which inspected.(b)Location and percent of wall-thickness penetration. for each indication of an imperfection, and (c)Identification of tubes plugged or sleeved.2.8.4 If the number of tubes in a generator falling into categories (a)or (b)below exceeds the criteria, then results of the inspection shall be considered a Reportable Event pursuant to 10 CFR 50.73.Oral notification to the NRC Staff shall be accomplished within 48 hours, but no sooner than the next normal working day after the final review of the eddy current results.A written follow-up report shall provide a description of investigations conducted to determine the cause of the tube degradation and corrective measures taken to preclude recurrence. Categories (a)and (b)are: (a)More than 10 percent of the total tubes inspected are degraded (imperfections greater than 20 percent of the nominal wall thickness). However, previously degraded tubes must exhibit at, least 10 percent further wall penetration to be included in this calculation.(b)More than 1 percent of the total tubes inspected are degraded (imperfections greater than the repair limit). ,I QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ADDITIONAL PROGRAMS REV.Section 11 3 PAGE 5 of 9 3.0 Reactor Coolant Pum Fl heel Pro ram: 3.1 General: The augmented inservice inspection program for Reactor Coolant Pump Flywheels incorporates the requirements of the USNRC Regulatory Guide 1.14, Revision 1, dated August 1975, entitled"Reactor Coolant: Pump Flywheel Integrity".

3.2 Examination

Requirements:

3.2.1 Examinations

shall be performed. on all active Reactor Coolant Pump Flywheels and Anti-Rotation Pawls.3'Examination Method: 3.3 1 Reactor Coolant Pump Flywheels shall be examined using Ultrasonic and Surface examination techniques. 3.3.2 3.3'Reactor Coolant Pump Anti-Rotation Pawls shall be examined using Surface examination techniques. Ultrasonic and Surface examinations shall conform to and be performed in accordance with Section 1 of this program.3.4 Frequency of Examinations:

3.4.1 Examinations

shall be performed on all operating Reactor Coolant Pump Flywheel and Anti-Rotation Pawls once each period.3.5 Examination Evaluation:

3.5.1 Examination

evaluations shall be performed in accordance with Section 1 of this program.3.5.2 Unacceptable examinations shall be reported for evaluation and appropriate corrective action. QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ADDITIONAL PROGRAMS REV.3 PAGE 6 of 9 Section 11 3.6 Repair, Replacement and Testing Requirements 3.6.1 3.7 Repairs and Replacements shall be performed in accordance with Supplement 2 to this Appendix, as applicable. Scheduling:

3.7.1 Examination

schedules shall be established within Supplement, 1 to this Appendix.3.8 Reports and Records: 3.8.1 Applicable records shall be maintained as specified in Section 1 of this program and'when required within Supplement 2 to this Appendix.4.0 Class 1 Boltin Pro ram IEB 82-02 4.1 General: This augmented inspection program was established to address IE Bulletin 82-02,"Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of PWR Plants" dated June 2, 1982.4.2 Examination Requirements:

4.2.1 Examinations

shall be performed on threaded fasteners of closure connections when opened for component inspection or maintenance for the following, as applicable: Steam generator and pressurizer manway closures.2.Valve bonnets and pump flange connections installed on lines having a nominal diameter of 6 inches or greater.3.Control rod drive (CDR)flange and pressurizer heater connections that do not have seal welds to provide leak-tight integrity. 4 L HI I QUALITY ASSURANCE MANUAL GINNA STATION TITLE APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVXCE INSPECTXON PROGRAM FOR THE 1990-1999 INTERVAL ADDITIONAL PROGRAMS REV.3 PAGE 7 of 9 Section 11 4.3 Examination Method: 4.3.1 Applicable threaded fasteners of closure connections shall be examined utilizing both Surface and Visual techniques. 4'Frequency of Examinations:

4.4.1 Applicable

components containing threaded fasteners of closure connections shall be examined when opened for component inspection or maintenance.

4.5 Examination

Evaluation:

4.5.1 Examination

evaluations shall be performed in accordance with Section 1 of this program.4.5.2 Unacceptable examinations shall be reported for evaluation and appropriate corrective action.4.6 Repair, Replacement and Testing Requirements 4.6.1 4.7 Repairs and Replacements shall be performed in accordance with Supplement 2 to this Appendix, as applicable. Scheduling:

4.7.1 Examination

schedules shall be established, as applicable and required, within Supplement 1"to this Appendix or the Maintenance Inservice Inspection Program (MISIP).4.8 Reports and Records: 4.8.1 Applicable records shall be maintained as specified within Section 1 of this program and as applicable when required within Supplement 2 to this Appendix.

QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ADDITIONAL PROGRAMS REV.3 PAGE 8 of 9 Section 11 5.0 Reactor Vessel Au ented Pro ram Cate or B-A:-5.1 5.2 General: r As specified within the Federal Register, 10 CFR Part 50, Vol.57, No.152 dated August 6, 1992, a specific augmented examination program is required for ASME Section XI Category B-A, Shell Welds of"Pressure Retaining Welds in Reactor Vessel".Examination Requirements: 5.2.1 5.3 Examinations shall be performed on all ASME Section XI Category B-A, Item B1.0, Shell Welds of"Pressure Retaining Welds in Reactor Vessel" that are not required by the Code.Examination Method: 5.3.1 5.4 Ultrasonic examinations shall conform and be performed in accordance with Section 1 of this program.Frequency of Examinations: 5.4.1 5.5 Examinations shall be performed once during the Inspection Interval.Examination Evaluation: 5.5.1 5.5.2 5.6 Examination Evaluations shall be performed in accordance with Section 1 of this program.Unacceptable examinations shall be reported for evaluation and appropriate corrective action.Repair, Replacement and Testing Requirements 5.6.1 Repairs and Replacements shall be performed in accordance with Supplement 2 to this Appendix, as applicable. i<<i II ll QUALITY ASSURANCE MANUAL GINNA STATION TITLE: APPENDIX B R.E.GINNA NUCLEAR POWER PLANT INSERVICE INSPECTION PROGRAM FOR THE 1990-1999 INTERVAL ADDITIONAL PROGRAMS REV.3 PAGE 9 of 9 Section 11 5.7 5.7.1 5.8 5.8.1 Scheduling: Examination schedules shall be established within Supplement 1 to this Appendix.1 Reports and Records: Applicable records shall be maintained as specified within Section 1 of this program and when required within Supplement 2 to this Appendix.}}