Revised "ISI Program for 1990-1999 Interval."

QUALITY DATE ASSURANCE APPENDIX B 12/31/93 MANUAL R.E. GINNA NUCLEAR POWER PLANT GINNA STATION INSERVICE INSPECTION PROGRAM PAGE FOR THE 1990-1999 INTERVAL 1 of 5

TABLE OF CONTENTS Section 1.0 Inservice Inspection Program: 1.0 Introduction 1 ~ 1 General 1.2 Applicable Documents 1 ~ 3 Inspection Intervals 1.4 Classification of Components 1.5 Responsibility 1.6 Records 1.7 Examination Methods and Requirements 1.8 Repair Requirements 1.9 Replacement Requirements 1. 10 System Pressure Testing

2.0 Class 1 Program Plan 2.1 Basis for Preparation 2.2 Components Subject to Examination 2.3 Extent and Frequency of Examinations 2.4 Exemption Criteria 2.5 Examination of Reactor Coolant Pump Flywheels 2.6 Inservice Inspection Program Plan

3.0 Class 2 Program Plan 3.1 Basis for Preparation 3.2 Components Subject to Examination 3.3 Extent and Frequency of Examinations 3.4 Exemption Criteria 3.5 Inservice Inspection Program Plan

4.0 Class 3 Program Plan 4.1 Basis for Preparation 4.2 Components Subject to Examination 4.3 Extent and Frequency of Examinations 4 4 Exemption Criteria 4.5 Inservice Inspection Program Plan

5.0 Class 1, 2 & 3 Component Supports 5.1 Basis for Preparation 5.2 Components Subject to Examination 5.3 Extent and Frequency of Examinations 5.4 Exemption Criteria 5.5 Inservice Inspection Program Plan

9401250044 940111. PDR ADOCK 05000244. 8 'DR QUALITY TITLE: DATE ASSURANCE APPENDIX B 12/31/93 MANUAL R.E. GINNA NUCLEAR POWER PLANT GINNA STATION INSERVICE INSPECTION PROGRAM PAGE FOR THE 1990-1999 INTERVAL 2 of 5

Section 2.0 Relief Requests: 1.0 Introduction 1.1 General

Section 3.0 P&ID Boundary Drawings: 1.0 General P&ID Boundary Drawings

Section 4.0 Code Tables: 1.0 General Table 1, Class 1 Table 2, Class 2 Table 3, Class 3 Table 4, Class 1, 2, & 3 IWF Component Supports Section 5.0 Line List: 1.0 General Line List

Section 6.0 Allocation Tables: 1.0 General ASME Code Requirements Class 1 Class 2 Class 3 Class 1,2, & 3 Supports Augmented Reactor Coolant Pump Flywheel Program Reactor Vessel Augmented Program, Category B-A High Energy Program Snubber Program Seismic Support Program QUALITY DATE ASSURANCE APPENDIX B 12/31/93 MANUAL R.E. GINNA NUCLEAR POWER PLANT GINNA STATION INSERVICE INSPECTION PROGRAM PAGE FOR THE 1990-1999 INTERVAL 3 of 5

Section 7.0 UT Calibration Blocks: 1.0 General UT Calibration Blocks Section 8.0 High Energy Program: 1.0 General 2.0 Examination Requirements 3.0 Examination Methods 4.0 Frequency of Examination 5.0 Examination Evaluation 6.0 Repair & Testing Requirements 7.0 Replacement & Testing Requirements 8.0 Scheduling 9.0 Reports & Records

Table 1 — High Energy Welds & Component Support Identification. Section 9.0 Snubber Program: 1.0 General 2.0 Examination, Testing & Monitoring Requirements 3.0 Examination & Testing Methods 4.0 Examination & Testing Frequency 5.0 Examination, Testing & Monitoring Evaluation 6.0 Repair, Replacement & Modification Requirements 7.0 Scheduling 8.0 Reports & Records Section 10.0 Seismic Support Program: 1.0 General 2.0 Examination Requirements 3.0 Examination Methods 4.0 Frequency of Examination 5.0 Examination Evaluation 6.0 Repair & Testing Requirements 7.0 Replacement & Testing Requirements 7.0 Scheduling 8.0 Reports & Records QUALITY DATE ASSURANCE APPENDIX B 12/31/93 MANUAL R.E. GINNA NUCLEAR POWER PLANT GINNA STATION INSERVICE INSPECTION PROGRAM PAGE FOR THE 1990-1999 INTERVAL 4 ot 5

Section 11.0 Additional Programs: 1.0 General 2.0 Steam Generator Tube Inspection Program 2.1 General 2.2 Examination Requirements 2.3 Examination Methods 2.4 Frequency of Examination 2.5 Examination Evaluation 2.6 Repair, Replacement & Testing Requirements 2.7 Scheduling 2.8 Reports & Records 3.0 Reactor Coolant Pump Flywheel Program 3.1 General 3.2 Examination Requirements 3.3 Examination Methods 3.4 Frequency of Examination 3.5 Examination Evaluation 3.6 Repair, Replacement & Testing Requirements 3.7 Scheduling 3.8 Reports & Records 4.0 Class 1 Bolting Program (IEB 82-02) 4.1 General 4.2 Examination Requirements 4.3 Examination Methods 4.4 Frequency of Examination 4.5 Examination Evaluation 4.6 Repair, Replacement & Testing Requirements 4.7 Scheduling 4.8 Reports & Records 5.0 Reactor Vessel Augmented Program, Category B-A

5.1 General'.2 Examination Requirements 5.3 Examination Methods 5.4 Frequency of Examination 5.5 Examination Evaluation 5.6 Repair, Replacement & Testing Requirements 5.7 Scheduling 5.8 Reports & Records QUALITY TITLE: DATE ASSURANCE APPENDIX B 12/31/93 MANUAL R.E. GINNA NUCLEAR POWER PLANT GINNA STATION INSERVICE INSPECTION PROGRAM PAGE FOR THE 1990-1999 INTERVAL 5 of 5

SUPPLEMENT 1 TO APPENDIX B "Inservice Inspection Program Plan" (Separate Document controlled by Materials Engineering 6 Inspection Services.)

SUPPLEMENT 2 TO APPENDIX B "The Repair, Replacement and Modification Program" QUALITY ASSURANCE MANUAL PAGE GINNA STATION Section 1 1 of 34 EFFECTIVE DATE: December 31, 1993 ROCHESTER GAS 8E ELECTRIC CORPORATION SIGNATURE DATE

TITLE PREPARED BY: +Dt ( q3 APPENDIX B p g ~ QUALITY R. E. GINNA NUCLEAR POWER PLANT ASSURANCE INSERVICE INSPECTION PROGRAM REVIEW: FOR THE 1990-1999 INTERVAL APPROVE BY:

1.0 INTRODUCTION General This Appendix "B" to the Quality Assurance Manual outlines the third interval inservice inspection examination (ISI) requirements for Class 1, Class 2, and Class 3 systems, and components for Rochester Gas & Electric Corporation's (RG&E) R. E. Ginna Nuclear Power Plant (Ginna Station). The third inspection interval begins on January 1, 1990, as permitted by Paragraph IWA-2400 of ASME Code Section XI, the second interval concluded December 31,1989. 1.1.1 This program is based on the requirements of the 1986 Edition of the American Society for Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, "Inservice Inspection of Nuclear Power Plant Components" as adopted by the Code of the Federal Regulations, 10 CFR Part 50, (Federal Register 53FR16051) May 5, 1988. 1. 1.2 This program excludes'he controls of the Enforcement Authority, and N-Stamp, in addition to IWE of ASME Section XI, since it is not endorsed by'the Regulation.

1 ~ 1 ~ 3 Inservice Testing of pumps (IWP) and valves (IWV) is performed in accordance with Appendix C of the Ginna Station Quality Assurance Manual. TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVXCE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 XNTERVAL 2 of 34

1.2 Applicable Documents RG&E has adopted the following documents as the basis for the third inspection interval and is committed to satisfying their requirements. Specific exceptions to the requirements of ASME Section XI are identified and located in the "Relief Requests", Section 2.0 of this document. This program was developed in accordance with these documents:

1 ~ 2.1 ASME Boiler and Pressure Vessel Code Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 1986 Edition, no Addenda.

1.2. 1. 1 ASME Boiler & Pressure Vessel Code, Section XI, 1986 Edition, no Addenda, Appendix IV. 1 '.2 U.S. Nuclear Regulatory Commission (USNRC) Regulatory Guides:

a ~ 1.14, Rev. 1, "Reactor Coolant Pump Flywheel Integrity" b. 1.147, Latest Revision, "Xnservice Inspection Code Case Acceptability — ASME Section XI, Division l"

c ~ 1.150, Rev. 1, "Ultrasonic Testing of Reactor Vessel Welds During Preservice and Xnservice Examinations" d. 1.83, Rev. 1, "Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes"

e. 1.26, Rev. 3 "Quality Group Classifications and Standards for Water, Steam, and Radioactive Waste Containing Components of Nuclear Power Plants. 1.29, Rev. 3, "Seismic Design Classification". g 1.121, Rev. 0, "Bases for Plugging Degrated PWR Steam Generator Tubes". TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GXNNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 3 of 34

h. 1.65, Rev..0, "Materials and Inspections for Reactor Vessel Closure Studs".

1.2.3 ASME Code Cases

In accordance with 10CFR50.55a, Footnote 6, ASME Section XI Code Cases referenced in Regulatory Guide 1.147, "Xnservice Inspection Code Case Acceptability- ASME Section XX, Division 1," may be incorporated into the Ginna Station ISI Program. Those Code Cases included in Regulatory Guide 1.147 that will be implemented at Ginna Station are identified in this section. Each Code Case is preceded by information on the applicable component/area, ASME requirements, and how the Code Case will be implemented. Paragraph 1.2.3.1 lists those code cases that have been technically reviewed and endorsed, with or without conditions by the NRC in Regulatory Guide 1.147 and will be implemented during the 3rd ten year Inspection Interval. Use of any subsequent NRC endorsed code cases that are identified in revisions to the Regulatory'uide 1.147 may be incorporated in the program and used during the 3rd ten year Inspection Interval. 1.2.3.1 USNRC Regulatory Guide 1.147 — Approved ASME Section XI Code Cases

Code Case No. Sect. XI References Com onent Area

N 307-1 IWB-2500-1 Studs and Bolts with Heater Holes N-416 IWA-4400 Any repaired or replaced Class 2 piping component that cannot be isolated by valves or requires securing safety/ relief valves. N-401 IWA-2233 Eddy Current Examinations TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 4 of 34

N-402 IWA-2233 Eddy Current Calibration Standard Material N-427* Code Cases Code Cases in Inspection Plans N-437 IWA-5260 Use of digital readout and digital measurement devices for performing Pressure Tests. N-446 IWA-2300 Recertification of Visual Examination Personnel. N-460 IWA-2000/3000 Alternative examination coverage for Class 1 and Class 2 welds. N-481 B-L-1, Item B12.10 Alternative examination requirements for Cast Austenitic Pump Casings. N-491 IWF-1000/2000/3000 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. * As amended by USNRC Regulatory Guide 1.147, April, 1992. 1.2.4 R.E. Ginna Updated Final Safety Analysis Report (UFSAR):

Section 5.4 — For Class 1 Section 6.6 — For Class 2 and 3 1

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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 USAS B31.1.0-1967, "Power Piping" for High Energy Systems

1.2.7 R. E.„ Ginna, Technical Specification 4.2. "Inservice Inspection". 1.2.8 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 Rochester Gas and Electric Corporation Mechanical Engineering Specification, ME-256, Titled— "Snubber Inspection and Test Program".

1.2.11 Electric Power Research Institute PWR Steam Generator Inspection Guidelines, Rev. 2. 1.2.12 Code of the Federal Regulations, 10CFR Part 50. 1.2.13 USNRC, NRC Region I Inspection Report 50-244/90- 12, Section 3.4 regarding repair program "Service Induced" and "Code Rejectable" repairs. 1 ' Inspection Intervals

1.3.1 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. TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVXCE XNSPECTION PROGRAM PAGE GXNNA STATION FOR THE 1990-1999 INTERVAL 6 ot 34

1.3.2 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.

1.3 ' 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. TITLE REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 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.

1.7 Examination Methods and Requirements f 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

I lt

1' TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE

GINNA STATION FOR THE 1990-1999 INTERVAL 8 of ~ 34

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. TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 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 Examinations that detect flaws which require evaluation may be supplemented by other examination methods and techniques to determine the character of the flaw. l.7.5 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

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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

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— Evaluation Test to the extent necessary to substantiate'rits 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 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. 1.7.6.4 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. TITLE:, REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 12 of '34

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 I

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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. TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 14 of 34

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 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. 1.9.2.1 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 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 1.9.2.6 Items identified in IWA'-7400 will be exempt from the requirements of the replacement program. P If H TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 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. Snubbers shall be examined and tested in accordance with Section 9 of this program. 1.9.3.2 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. TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 16 of 34

1. 10 System Pressure Testing

1. 10. 1 General Requirements l. 10. 1. 1 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. TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E..GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 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. TITLE: QUALITY APPENDIX B Section 1 ASSURANCE R.E. GXNNA NUCLEAR POWER PLANT MANUAL INSERVXCE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 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 Examination Requirements 1.10.3.1 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 Test Requirements 1.10.4.1 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. TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 19 of 34

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 ~ Atmospheric Storage Tanks b. 0-15 psi Storage Tanks c ~ Class 1 systems where a mixture of steam, water and noncondensible gases are present in a proportion typical of normal startup conditions. d. 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. TITLE REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 20 of 34

l.l0.4.5 HYDROSTATIC PRESSURE TEST REQUIREMENTS 1.10.4.5.1 General

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. 1.10.4.5.2 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. TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 21 of 34

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 1.10 P 200 1.08 P 300 1.06 P 400 1.04 P 500 or greater 1.02 P "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. 1.10.4.6.2 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 TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 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 Test Implementation 1.10.5.1 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. 1.10.5.2 Applicable Required System Pressure Test Boundaries shall be confirmed prior to examination performance. TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 23 of 34

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 CLASS 1 PROGRAM PLAN 2.1 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. TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 24 of 34

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 Extent and Frequency of Examinations 2.3.1 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. 2.4 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. TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 25 of 34

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 CLASS 2 PROGRAM PLAN 3.1 Basis for Preparation

3.1.1 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. TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION -FOR THE 1990-1999 INTERVAL 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. TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 27 of 34

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 and smaller (including nozzles, socket fittings and other connections) in vessels, piping, pumps, valves and other components of any size; (c) vessels, piping, pumps, valves, other 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 (d) piping and other components of any size beyond the last shutoff valve in open ended portions of systems that do not contain water during normal plant operating conditions. 3.4.3 In addition to the exemptions of IWC-1220, nonpiping 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 & TITLE REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 28 of 34

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 CLASS 3 PROGRAM 4.1 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. ~ ~ TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 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. TITLE REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 30 of 34

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: Section XI Exem tion Criteria Reference Integral attachments of IWD-l220.1 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. Integral attachments of IWD-1220.2 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: (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. REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 31 of" 34

4.4.2 In addition to the exemptions of IWD-1220, nonpiping 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'' TITLE: QUALITY APPENDIX B Section 1 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 32 ot 34

5.0 CLASS 1q CLASS 2~ AND CLASS 3 COMPONENT SUPPORTS 5.1 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. TITLE: QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 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 Extent and Frequency of Examination 5.3.1 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 In addition, snubbers shall be functionally tested at the frequency required by Section 9 of this program. 5.3.3 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. TITLE: REV. QUALITY APPENDIX B Section 1 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 34 of 34

5.3.4 High Energy Piping Component Supports shall be examined to IWC-2500 Category C-C and to IWF-2500 in an Augmented Program. 5.4 Exemptions

5.4.1 ASME Section XI, 1986 Edition, no Addenda, does not contain defined exemption criteria for component supports. 5.4.2 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 PAGE GINNA STATION Section 2 1 of 39 EFFECTIVE DATE: December 31, 1993 ROCHESTER GAS & ELECTRIC CORPORATION SIGNATURE DATE

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

TABLE I

SUMMARYOP RHJFP R

Rebel ASME Requiscment Reason for Proposed Request Section XI for Which Relief Relief Akemate Number Refesence Component is Requested Request Examination

IWB.2500.1 RPV ShcU to Bange Volumetric Examination To perform aU examinations Perform aU examinations associated Cat. B.A WeM during two dUferent assoriatcd with the SheU.to with the SheUao Range at or near pcAods Bange during the same the end of the interval. pcskxL

IWB.2500.1 RPV Nozxlc to-Vcsscl Volumetric Examinadon To perform aU examinations Perform aU cxaminatkins associated Cat. B-D WeMs during two different assocktcd with the Nosxk.to. with the Noxxk to.Vessel weMs at or pcAods. Vessel wcMs during the same near the end of the lntervaL pcsloL

IWA.1400 huthorixed Inspection Use of 'huthorixed Agency'cw York State has Use R. E. Cinna Quality Assurance Inspection Agency. not endorsed ASME Codes Pmgram. and does not have an Authorixcd Inspection Agency.

4 (') IWB.2500 I Reactor Coolant Pump Volumetric Examinatkn of Pump materiai and Hydsostatie test, surface and visual Cat. B.L I Case WeMs and ease weMs and visual of conBgumtion. exams of outside surfaces. B-L2 Intervals. intemab.

IWB-2500 I Chss I Valves Visual Examination of Excessive radiation Examine valve Intcmak when Cat. B M.2 Creatcr than NPS 4. valw intemds. ex posuse and historical disassembled for maintcnanee. reliabilityof valves.

IWD 2500-1 Rsdioanive Waste Visual Bueucadon at Tank wUI be rendered Perform visual examination each Cat. D.B HoMup Tank, hydsostade prcssure. inoperatiw during tests. period at noAnal opcradng prcssure.

IWC5222(a) Charging Pumps Visual Examination at Pumps have maximum Perform Hydro Test and visual at 3420 psig Hydrostatic pressure limiton the scab. 2400 psig. Pressure.

IWC 5222(a) Valves PCV 430 Visual Exasninadon at Valve diaphragms cannot Hydrostatic Test to Fkx Connection and PCV 431C. Hydrostatic Pressure. withstand Test Prcssure. operate diaphragm pcr valve test requirements and pcrfonn Insesvice visual examination once per period.

IWC 5222(a) Secondary Side Visual Examination at RCBE adopted pressure Hydrostatk Test at of steam Hydrostatic Pressure. differential limitadon of 800 1.10 times instead of generator and psig to prevent primary 1.25 Psv setting and assoriatcd main side tube sheet chdding perform visual steam piping. scpamtiolL cxammatfoiu

10 (') IWD-5223(a) Standby Auxiliary Visual Examination Pressure Redunkn Bow Perform Inservice Pump RceiscuL at llydsostatie Pressure. OriTice requires removal and Visual Examination Une from AOV biank4sff. System piping docs once per periosL 9710A, AOV 9710B not provMe lsolatkn to and thek assoei. condcmate supply rank. atcd downstream SigniTicant tank reduction Row orifices. wouM bc required for removal and is comidered impractkai.

IWD.5223(a) Boric Acid Filter and Visual Examinatkn at Test Prcssure required will Perform Inservice Visual Examination assoriatcd piping Hydrostatic Pressure. exceed limits for safe working once per period. between Valves 347, pressure on Boric Acid Fil(cr 348A and 349A. Housing Fhnge Cmkets.

(v) ~ WillIDRAWN TITLE REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 3 of 39 ISI RELIEF RE UESTS

TAB!XI

SUMMARYOF RFJJFP R URIS

Relief ASME Requirement Reason lor Proposed Request Sectfon XI for Which Rriief Relief Alternate Number Reference k Requested Request Examination

12.1 IWD-5223(a) hir Stan for Visual Examinatkn at AirStart Pressure Test wouM Perform Inseivke Examination Diesel Generator Hydrostatic Pressure. fcqiilfctclndnatlon pfiofto once per period and once each htciuding fcacMng engine skid to quarter a prcssure decay test Receiver Tanks preclude ak to air stan performed oiiair rcccivcl; and Piping. motors, kavtng portion of pfping untestable.

IWD-5223(a) Fuel Oil Transfer Visual Examinarion at Requires hohtkn of Diesel Perform system Functional Tesring Pumps and assoriated Hydrostatic Pressure. OilStorage and Dry Tank with assockted Visual plpuig to tert(dr(all at where no means of kola(ion Examination once per period. Oil Storage Tank k provided at Transfer pump discharge piping with tanks vented to atmosphere.

IWD.5223(a) Jacket Cooling Visual Examination at Cooling Water Expansion Perform System Functional Testing Water System and Hydrostatic Prcssure. Tank vented to aunosphcre with associated Vkual Examination associated piping requiring isoktkn with vast once pcf pcfiud. to terminals at piping Involved willbe unable Water Expanskn to prcssurixc Tanks.

13 (111) Table IV C2500 Ckss 2 Piping Under Revision. I, Category CH Pen((rath(3 containment vessel with balance of piping system outskle Section XI scope.

Ckss 3 Ponion of the Visual Examination at Ilydrostatic Tesung is Perform Inservice Visual Examination servke water system Hydrostatic Pressure.. impra(tical due to system once per period. design that is openwnded and empkying butterily valves that wcfc not dcsigncd to provide a kaktight boundary.

15 (') IWC.2500 Qass 2 Piping Piping WeMs c At a mhdmum terminal Surface and Volumetric Examinations Cat. C F-I WeMs c wall thickness3/8'ominal do connection weMs of idcntilied on tcmunal connection weMS of

3/8'ondnal & C F-2 wall thkknem no( require surface and exempted weMs pcr Items Men(ipcd exempted weMS shall be l(ems C5.10 for piping > NPSC. volumetric examinanons. C5.10 and C5.50 of Tabk performed to the requirements of and C5.50 resp. IWC2500 shouM be IWC.2500 1. examinetk

IWB-2500 Qass I &2!ntcgral Volumetric or surface Integtul Attachments on Ckss On Ckss I & 2 Integral hnachmcnts, Cat. 8 K.l Item Attachment on piping examination on Qass I I & 2 suppon attachments a surface examination shall be B10.10 and IWC. speciTically support Integral Attachments is shoUM have a sUffacc performed on suppon attachments to 2500, Cat. CC, Attachments. required on Base examination to insure safety IWB and IWC-2500 requirements. l(em C3.20 Attachment > 5/8. Qass and system integrity. 2 requires a sUrfacc examination on Base Attachments > 3/0'.

I9 IVC2500 Pulsation Dampener, Applicable Surface and/or Physical configuration not Perform Surface and/or Volumetric Category C B, Nossk WeM & Inside Volumetric Examinations. conducive for full Examination to Maximum extent Items Col & Radius. Examination coverage. practkaL C2.22 (') " (1 ~ 1) ~ '4

1 TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE, R.E. GINNA NUCLEAR POWER PLANT MANUAL XNSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 4 of 39 ISX RELIEF RE UESTS

TABIX1

SUMMARYOP RHIKF mSlS

Relief ASME Requirement Reason for Proposed Request Section XI for Which Relief Relief Alternate Number Reference Component is Requested Request Examination

23 (~) IWAA400 Chss 3 Valves: llydrostatie Testing of Code Impraetieality ASME Section III NDE with PT of V~ Rephcement Activities. Root Pass. Perform a VT.2 leak Relief VMII Test. This is a one-time'se VMI3 only. V~ VA738 V.4739 VA760

24 (~) IWA-4400 Class 3 Vrdvcst Ifydrostatic Testing of Code Impractkality ASME Section III NDE with PT of VMI3 Re placement Activities. Root Pass. Pcrfonn a VT2 leak V.4027 Test. This Relief is a one-time V~V 4020 usc only.

(~) ~ ONE TIMEUSE ONLY. t

I TITLE: QUALITY APPENDIX B Section 2 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 5 of 39 ISI RELIEF RE UESTS

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 TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 6 of 39 ISI RELIEF RE UESTS

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 TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT 'ANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE'990-1999 INTERVAL 7 of 39 ISI RELIEF RE UESTS

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. TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 8 of 39 ISI RELIEF REQUESTS

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

II t TITLE REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 9 of 39 ISI RELIEF RE UESTS

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. TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 10 of 39 ISI RELIEF RE UESTS

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).

TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 11 of 39 ISI RELIEF RE UESTS

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 ~ Visual examination (VT-2) of the exterior of all pumps during the hydrostatic pressure test required by Table IWB 2500-1 Category B-P. b. 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. TITLE REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 12 of 39 ISI RELIEF RE UESTS

WITHDRAWN

RELIEF REQUEST NO. 4 (Con't) d. 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) Reviewing of the operating history of the structure. (iv) Selection of locations for postulating flaws. (v) Determination of a flaw size resulting in the detectable leak rate (vi) Establishing the stability of the selected flaw. (vii) 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 TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 13 of 39 ISI RELIEF RE UESTS

RELIEF REQUEST NO. 5

VISUAL INTERNAL EXAMINATIONOF CLASS 1 VALVES Components for Which Relief is Requested: Class 1 valves requiring valve body internal VT examination. Size ~Xn. Valve No. MFG T e Line No. 10 842A Darling/Check 10A-SI2-1502-A 10 842B Darling/Check 10A-SI2-2501-B 10 867A Darling/Check 10A-SI2-2501-A 10 867B Darling/Check 10A-SI2-2501-B 10 700 Velan/Gate 10A-RC02501-A 10 701 Velan/Gate 10A-RCO-2501-A 10 720 Velan/Gate 10A-RCO-2501-B 10 721 Velan/Gate 10A-RCO-2501-B 853A Velan/Check 6A-RC-2501-A 853B Velan/Check 6A-RC-2501-B 852A Velan/Gate 6A-RC-2501-A 852B Velan/Gate 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 TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 14 of 39 ISI RELIEF RE UESTS

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. TITLE REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 15 of 39 ISI RELIEF REOUESTS

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 TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 16 of 39 ISI RELIEF RE UESTS

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. '\ TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR, THE 1990-1999 INTERVAL 17 of 39 ISI RELIEF RE UESTS

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. TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GXNNA STATXON FOR THE 1990-1999 INTERVAL 18 of 39 ISI RELIEF RE UESTS

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. TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 19 of 39 ISI RELIEF RE UESTS

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.' TITLE REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GXNNA NUCLEAR POWER PLANT MANUAL XNSERVICE INSPECTION PROGRAM PAGE GXNNA STATION FOR THE 1990-1999 INTERVAL 20 of 39 XSI RELIEF RE UESTS

RELIEF REQUEST NO. 9 (con't) A letter was submitted to Dennis L. Ziemann. Chief Operating Reactor Branch ¹2, 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 Plant ¹1, 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 TITLE REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E- GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 21 of 39 ISI RELIEF RE UESTS

WITHDRAWN

RELIEF REQUEST NO. 10

ALTERNATIVE HYDROSTATIC TESTING OF STANDBY AUXILIARYPUMP 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 TITLE REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 22 of 39 ISI RELIEF RE UESTS

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 TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 23 of 39 ISI RELIEF RE UESTS

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: Starting Air including receiver tanks and associated piping. 2. Fuel Oil Transfer pumps, suction and discharge including miscellaneous lines terminating at oil storage tanks. 3. 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. (

E' TITLE REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 24 of 39 ISI RELIEF RE UESTS

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 TITLE REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA 'NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 25 of 39 ISI RELIEF REOUESTS

RELIEF REQUEST NO. 13

ALTERNATIVE PRESSURE TESTING OF CONTAINMENT PENETRATION PIPING I

Under Revision. I' TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVXCE XNSPECTXON PROGRAM PAGE GINNA STATION FOR THE 1990-1999 XNTERVAL 26 of 39 ISI RELIEF RE UESTS

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.

TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 27 of 39 ISI RELIEF RE UESTS

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. TITLE REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL XNSERVICE XNSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 XNTERVAL 28 of 39 ISI RELIEF RE UESTS

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 TITLE REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GXNNA NUCLEAR POWER PLANT MANUAL INSERVICE XNSPECTXON PROGRAM PAGE GXNNA STATION FOR THE 1990-1999 INTERVAL 29 of 39 ISI RELIEF RE UESTS

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

fl TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 30 of 39 ISI RELIEF REOUESTS

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 1' 'i

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II TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE XNSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 31 of 39 ISI RELIEF RE UESTS

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 664 UT 65% CF-N2'T 664 UT 65~o

CF-N3 PT >90~o UT 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 fulfillingthe 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

~ ' TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 32 of 39 ISI RELIEF RE UESTS

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 ~ V-4611 b. V-4613 C. V-4626 d. V-4669 e. V-4738 f. V-4739 g 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

4 TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTXON PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 33 of 39 ISI RELIEF RE UESTS

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 TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 34 of 39 ISI RELIEF RE UESTS

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. TITLB REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 35 of 39 1l ISI RELIEF RE UESTS

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: Code Required Test Pressure to SWS Valves Test Pressure be Performedf'~ V-4611 165 psig 75 psig (Nom.) V-4613 165 psig 75 psig (Nom.) V-4626 165 psig 75 psig (Nom.) V-4669 165 psig 75 psig (Nom.) V-4738 165 psig 75 psig (Nom.) V-4739 165 psig 75 psig (Nom.) V-4760 165 psig 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

l TITLE REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 36 of 39 ISI RELIEF RE UESTS

ONE-TIME USE ONLY

RELIEF REQUEST NO. 23 (Con't)

Code Required Test Pressure to AFW Valve Test Pressure be Performed V-4023 2304 psig 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 TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVXCE INSPECTXON PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 37 0( 39 ISI RELIEF RE UESTS

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 ~ V-4663 b. V-4013 c ~ V-4027 d. 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.

TITLE: REV. QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 38 of 39 ISI RELIEF RE UESTS

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:

TITLE: QUALITY APPENDIX B Section 2 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 39 ot 39 ISI RELIEF RE UESTS

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: Code Required Test Pressure to SWS Valves Test Pressure be Performed V-4663 165 psig 75 psig (Nom.) V-4013 165 psig 75 psig (Nom.) V-4027 165 psig 75 psig (Nom.) V-4028 165 psig 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 PAGE GINNA STATION Section 3 1 of 3 EFFECTIVE DATE: December 31, 1993 ROCHESTER GAS ELECTRIC CORPORATION 5 SIGNATURE DATE

TITLE PREPARED BY: 1~ "1 f3 B APPENDIX QUALITY R. E. GINNA NUCLEAR POWER PLANT ASSURANCE INSERVICE INSPECTION PROGRAM I 8-z89 FOR THE 1990-1999 INTERVAL P&ID BOUNDARY DRAWINGS APPROVED Y: l~ C aha 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 Blue Class 2 & High Energy Red Class 3 Green TITLE: REV. QUALITY APPENDIX B Section 3 2 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 2 of 3 P&ID BOUNDARY DRAWINGS

The following list identifies the P&ID drawings that contain ASME Class 1, 2, 3, or High Energy pressure boundaries. Drawin Number Revision 33013-1231 Rev. 22 33013-1232 Rev. 9 33013-1236 Sheet Rev. 8 33013-1236 Sheet Rev. 6 33013-1237 Rev. 27 33013-1238 Rev. 9 33013-1239 Sheet, Rev. 11 33013-1239 Sheet Rev. 9 33013-1245 Rev. 18 33013-1246 Sheet Rev. 7 33013-1246 Sheet Rev. 6 33013-1247 Rev. 20 33013-1248 Rev. 17 33013-1250 Sheet 1 Rev. 13 33013-1250 Sheet 2 Rev. 14 33013-1250 Sheet 3 Rev. 9 33013-1258 Rev. 14 33013-1260, Rev. 15 33013-1261 Rev. 21 33013-1262 Sheet Rev. 10 33013-1262 Sheet Rev. 5 (*) 33013-1263 Rev. 7 33013-1264 Rev. 14 33013-1265 Sheet Rev. 6 33013-1265 Sheet Rev. 5 33013-1266 Rev. 16 33013-1270 Sheet 1 Rev. 5 33013-1272 Sheet 1 Rev. 6 33013-1272 Sheet 2 Rev. 5 (*) 33013-1275 Sh eet 1 Rev. 2 33013-1275 Sheet 2 Rev. 2 33013-1277 Sheet 1 Rev. 6 (*) 33013-1278 Sh eet 1 Rev. 8 (*) 33013-1278 Sh eet 2 Rev. 9 33013-1279 Rev. 9 33013-1863 Rev. 11 33013-1865 Rev. 8 33013-1866 Rev. 13 33013-1870 Rev. 8

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

Drawin Number Revision

33013-1882 Rev. 9 33013-1886 Sheet 2 Rev. 5 33013-1887 Rev. 5 (*) 33013-1893 Rev. 10 33013-1908 Sheet 3 Rev. 3 33013-1915 Rev. 9 33013-1991 Rev. 8 (*) 33013-2278 Rev. 0 33013-2279 Sheet 1 Rev. 0

Note: (*) = Identifies P&IDs containing ASME Class piping NPS 1" and below. These identified drawings are not included within this section. 0

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,Ir» IWLINIINN ~ II QUALITY ASSURANCE MANUAL PAGE GINNA STATION Section 4 1 of 27 EFFECTIVE DATE: December 31, 1993 ROCHESTER GAS 8 ELECTRIC CORPORATION SIGNATURE DATE

TITLE: PREPARED BY: a.-) -f3 B APPENDIX QUAUTY R. E. GINNA NUCLEAR POWER PLANT ASSURANCE INSERVICE INSPECTION PROGRAM REVIEW: f84+3 FOR THE 1990-1999 INTERVAL CODE TABLES APPROVED Y:

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 Exanunation Components and Parts Examhation Examination Requirements for Examhation Technique/Exanunation 0 Ntx Category To be Exanuned Methods Third Inspecthn interval Area Comments td

The ASME Secuon XI item No. Each type of examination Thc NDE method This column provides information regarding This column provides &formation s peciTic to examination techniques, and Category of the component area is listed h this required to satisfy thc number and/or percent of examinations examination areas, or comments. 0 are listed h these columrn. column. Code requirements required to be performed for the inspecdon is listed in this htervai column. H 0 to Q H X H WO 'z 0n~~ U tgl H ~oxtfy ~ OXC d I X U WO P H Egf LO Q ~tf)~ H 0 0 R 'd WX g4Q0

M fll 0 0 Qg>10 SCCARCMP PPgH Item 'n Components and Parts Exanunation Exartdnation Rcqudrcments for Exaudnarion Tcchn'quelgxauunation M 4K Ntx Category To be Examined Methods Thhd Inspection Interval Area Commcras O

REACTOR PRESSURE VESSEL H 0 Bl.)0 B-A Cucumferentia) and Voluinetrie )00)b of one cucumfcrcrzia) weM to be Examination of cucumferenria) sheU weMs willbe performed whh UT Bl.l) Longitudinal Shell WeMs exauuncd at tructural discontinuhy h the techniques. There are no )onghudina) weMs at R. E. Ginna. Bl.)2 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 I or near the end of the Inspccrion IntetvaL m 0 M 81.20 B A Circumfcreruial aud There are no meridional or circumferenria) head weMs at IL E. Gutna. B1.2] MerMiona) Head WeMs B).22

8130 B.A Shell.to.Flange WeM Volumctrk )00bb of the weM to be examineL At least The sheU.to.lhnge weM willbe cxanuned from the vessel seal surface WO 509b of the weM shall be examined from the and from the vessel wall inside surface whh UT. NOTE: Relief o~~ Range face by the end of the fust Inspection Request u 1. 0 tg) H period and the remtdnder by the end of the a~> third Inspecuon period.

b S520 B.F Pressure-Rctahung No dissimilar metal welds on RPV at IL E. Gin@a 0 BS30 Dissin8ar Metal )VeMs

B6.10 SZ.) C)osurc Head Nuts >2 Surface )00)b of nuts to be exanuneL Examhtation Nuts willbe examined whh MTwhen renovcd for refueling. inches in Diameter may be perfosncd at or near the end of the inspection intcrvaL Table 1

NSERVVICE INSPECTION PROGRAM C1ASS 1 (Gout'd)

ExamfnatNn Technique/Examfnathn item Examinarion Components and Parts Examination Examination Requirements for No. Category Tobe~ Methods Third Inspection interval Area Comments

REACTOR PRESSURE VESSEL cont'd

Brx20 BG I Qosure Head Studs, In Volumetrk 1009b ol studs to be examined. Xuamfnadon Qosure stud examfnarions may be performed 'in pince.'xaminations Place, >2 Inches ln may be performed at or near the end ol the shouM be schedukd when studs are removed to reduce radiation Diameter inspecrion intervaL exposure and aBow 0» most thomugh examinarion. Code Case NS07-I shall apply.

Xammiai'on 'The studs willbe examined with UT and MT. Code Case NS0r/ I Qosure Head Studs, When Volumetrk and 10016 of studs to be xanunc«L H ~ Removed, >2 Inches in Surface may be performed at or near the end ol the shall apply. Diameter Inspccrion imervaL 0 U) ~

Threads in Fhmge Volumetri 10016 of threakd holes to be cxanun«L NQ >2 Inches In Diameter Exanunation may be performed at or near the end of the inspection intervaL WOW 86.50 BZ.I Pressure. Retaining Qosure Visual (VT.I) AU washcrs and bushings to be examined Washers and Bufhings upon stud rcmovaL Examfnatkn may be tf) H R c(7 >2 Inches in Dhmetcr performed at or near the cnd of the Inspection tf) C ( 'Ef intcnraL >O(f) OW I No pressure-retaining bohing <2'n diameter on RPV at L E. Gfnna. B7.10 BG.2 Prcssure-Retaining Bohing ++I eWa s2 Inches in Diameter tf) O Igrr H + tf) H B7~ B4.2 CRD Housings Bohs, Studs, Visual (VT.I) AB bohs, studs, and nuts to be exanun«L Pressure-retaining CRD housing bohng wBI be exanuncd when O e()7 and Nuts disassembl«L ~Hgo RPV E. Gfnna meet the BRIO B.H Integral Attachments lor N/A No Integrally welded attachments on at IL that RPV req Iremcnts of Category B H.

B 13.10 B-N.I Vessel Imerior Visual (VTS) Accessible areas to be examined during each Inspection periorL

B13.50 B.N 2 interior Attachments Visual (VT.I) Accessl»k attachment welds to be examin«L Within Bemine Region Exandnations may be compktcd at or near the end ol the inspectkn IntesvaL

B13.60 B.N.2 Interior Attachments Visual (VT-3) AcccssRrk attachment weMs to be examln«L (I) Beyond Behline Region Examinations may be completed at or near (D the end of the Inspecrion intervaL 0

B13.70 B NB CweSupport Structure Visual (VTS) With core.support strtture removed, all I" aceessibk surfaces to be examin«L 0 Examfnacions may be compkted at or near the end of the inspection IntetvaL

BIO.10 Conuol Rod Drive Housing Volmnetric or WcMs in IOIb of the peripheral CRD housings The CRD housLng weMs willbe examined with PT. WcMs Surface to be cxamin«L ~ns may be performed at or near the cnd of the Inspection huesvaL INSERVKXINSPKCIION PROGRAM Qgk)0 CIASS 1 COMPONKNIS (Cont'd) ZCCVRC(/)Q Item Examinarion Components and Parts Examine non Examinarion Rolulrements for Examinarion Technictur/Examfnarion WWgH To be Examined Methods Third Inspecth>n Interval Area Comments No. Category (I) O

REACIOR PRESSURE VESSEL «ont'd t3 0H 8 IS.IO B.P AllPressure.Retaining Vhual (VT2) AU components to be examined during system VTtxaminarions willbe performed in accordance with IWA.524k Boundaries for Vessel leakage test. Examfnarions to be performed Components in accordance with IWB.5221 prior to plant startu p after each refueling outage.

B15.11 B-P AB Pressure-Retaining Visual (VT.2) Allcomponents to be exanuned during system VTexanunations willbe periormed In accordance wnh IWA-524L Boundaries for Vessel hydrostatic test or ahernatiwly to Code Case Components NIPS. Examinarions to be performed ln 0 (/) sccordanm whh itVB.5221/5222 at or near d» end of the Inspection IntervaL Q

W O O~~ 0') H ~u)Z C rE) ~ o v) OX I X U tf) O 0 H ()) tf) < + 'Lf) H (/) Hg 0

g04Q r I

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INSERVKXINSPECIION PROGRAM CXASS I COMFONENIS (Gxa'd)

Item Components and Pans Examination Exatnination Rcqmremeats for Examinarion Technique/Examhation Ncx To be Examhed hlethods Third Inspection interval Area Comments (I) R K O

PRESSURIZER H 0 82.10 8 8 Circumferential and Volumetric The upper and bwer head-tosheU weMs to be Examination willbe perfoccacd with UT techniques. 82.11 longitudinal SheU.to-Head examfnccL One foot of one hngitudhal weM 82.12 WeMs intetsccring each head-to-sheU weM to be examhcd.

82.20 8 8 Circumfccearial and Volumetric Ihere me no p essurixer head weMs at L E. 82.21 MeriTioaai Head WeMs Ghna. 8222 0 0)

83.110 8 D Nmzkco.Vessel WeMs N/A No nozxk-to.vessel welds. Nouks are htegraUy cast into the head of Q pressurizer at L E. G irma. H i2" H Er) Eh)20 8-D Nmzk Inside Radius Volumetric AU hsMe radius secrions to be examhed. At Exandnations willbe performed whh UT techniques. O Secrions least 2596 lmc not more than Stylk of the o~~ nozzks shall be examined by the ead of che 0 c() H fust period and the rcmahdcr by the cnd of U C 'I) the inspection iatccvaL O (/) O Er) I d Heater Penetration WeMs Visual (VT.2) AU pressurizer heater penetration wekls shaU VTexamhation willbe performed in accordance with IWA.5240. Ez) U be examined duchg system hydrostatic test or +c() O igic H ahernatively Code Case in secor +c() XI to N~98 Z DL'd dance with IW8.5222 at or near the end of +QH t)3 the inspection imecvaL 0 BS.C0 B.F Nozzle-toSafe End Surface snd AU butt weMs to be examhed. Examinations willbe periormcd with PT and UT techniques. R 'E) Dissimilar Metal Welds Volumetric td X se Inches NPS g 0 4 Q 'Ef 85.50 8-F Noxxk-toSafe Ead N/A No nmzle-to-safe end ~imUar metal weMs on pressurixer at L E. Dissiaular Metal WeMs <4 Inches NPS Gina'5.60

B.F Noule.toSafe End Socket N/A No dissimilar metal socket weMs on pressurixer st iL E. Ginna. WeMs

Bck60 84.1 Pressure Retahiag Bohhg No bohing oa pressurixer >2 iaches h diameter st R. E. Ghna. 86.70 >2 Inches h Diameter Bc%80 V Bohr, Scuds, and Nuts Visual (VT.I) AU bohr, scuds, and nuts to be examhed. Bohing examharioas may be performed h place uader cension or 0 s2 Inches ia Dhmeter when disassembkd or removed.

8820 B-H IntegraUy Welded P essurixcr support sMrt not required for examharioa for3rd and 4th O Attachments hcervak by Code. 4

C' Tabk 1

INSERVICKINSPECIION PROCRAM CIASS I OOMPONENIS (Cont'd) hem Exanunation Components and Pans Examlnarion Examinarion Requirements for Examination Tcehnhlue/Examination Ntx Category To be Examined Methods Thhd Inspeerion Interval Area Comments c M O

PRESSURIZER Cont'd H IWB-5240. 0 BI520 B-P Pressure.Retaining Visual (VI'2) Allpressurixer components to be examined VTexamination willbe performed in accordance with Boundaries for Vessel during system kahage test. Examination to IWB.5221 Components be performed in accordance with prior to phnt stattup after each refueling outage H B1521 B-P Pressure.Retaining Visual (VT-2) Allpressurizer components to be examined VTexaminarion willbe performed in accordance with IWA.5240. Oundaries for Vessel during system hydrostatic test or ahetnativciy OM Components to Code Case NAPL Exanunation to be performed In accordance with IWB-5221/5222 at A or near the end of the Inspecrion huervaL

Er) O OH~ 0 tf) H R 'T) U ( r() O M O td I xa +If) O P H XI X + tO H 0() ()) R 'Ef 'd

M (i) 0 0 NNSERVICK NSPECIION PROGRAM (2ASS I (2)MPONENIS (Co%'d) MCCOY Iran Examination Components and Parts Examinarion Examhation Requirements for Exsfnhation Technique/Exanination Nfx Category To be Examined Methods Ihffd fnspecdon Intavaf Area Comments O SITA%I GENERATORS H 0 8230 8.8 Cireumferenrial snd There arc no steam generator kfwer head circumferenthl or 8231 Meridfonal WeMs in the meridional weMs. 8282 Iffwer Head

82.S0 8 8 Tubesheec to.Head WeM Volumetric Tht tubahccc.tDhcad wcM willbc cfulffuncd. Examination willbe performed with UT techniques. 'The XI exanhation willbe limited to one of the H v two stcam gcfltrators m 0 (I) 83.130 B.D Nmxle.to Vessel WeMs N/A There are no steam generator nmzle-to-vessel weMs. Nozzks aft integrally cast into heads. Q H g H (z) BXICO B.D Nmzk Inside Radius Volumetri Allnmzk inside radius senions wBI be Examinations willbe performed with UT ccehniques. 'Ihere are no O 4 Sections smfninccL At kast 2596 hz noc more than steam generator nmzle.to.vessel webb. O~~ Sty)h of the nozzks shall be txanuncd by the cf) H I) tnd of the first hspection period and che U C 'I) remainder by the end of the ins penion O (I) O W mtaval I Q 2e + (zf U 85.70 B.F NPS 4 or Larger Nmzle.to. Surface and Allnozzle safe~ dissimihr metal weMs Exanunaf ons willbe performed with PT and UT teehniqua at R E. cf) O ~ H Safe End Diafmilar Metal Volumetric shall be examined. Ginns. XI X > cf) H Wchh 'I) 0 (II less than NFL, Nmzk.to. There are no steam generator wehh of this type. Safe End DissimBar Metal WeMs

NmxlecoSafe End There are no steam genemcor wehh of ttus type. Dissimilar Metal WCMs

86.90 lhG. I Prcssure-Rctsuung Bohng No bokhg on stean generators >2 Inches h 86.100 >2 Inches in Dhmecer diameter ac R E. GinnL 86.110

8730 BG 2 Bohr, Studs, and Nuts Visusl (VT I) Allboks, scuds, snd nuts willbe exanined. Examinations msy be performed in phct under tension or when (/) s2 Inches in Diameter Ihe examination willbe limited to one of the rcmovcd. (t) two sttafn gcntfstofs. 0

IntegmBy WeMed N/A Ihert are no stcam generator imegraBy wehkd attachments. Attachments IW8.2500 13. 0

BI530 8-P Pressure.Retahing Visual (VT-2) AB nesm generator components co be VTexsmlnarions willbe performed h accordance with IWA-524th Bomxhries eaunfned during system leakage test. Exanhations co be paformtd in ccordanm whh IWB-5221 prior to phnt stanu p afttr each refuelhg outage. TaMe I

INSERVKXINSPECIION PROGRAM Qg>10 CLASS I CDMPONENIS (Gun'd) ZCC~RR(/)g ' Item Exandnation Components and Pans Examination Requirements for Examination Technique/Examination ~JYgH No. Categon/ To be Examined Methods lMrd inspection Interval Area Comments (I) C K O

STEAM GENERATORS Cont'd H 0 SISS I B-P Pressure. Retaining Visual (VT.2) Allsteam generator components to be VTexaininanons willbe performed in accordance with IWA4240. Boundaries 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 H 'xf 4 BI6.20 B4) Steam Genemtor Tubing Volumetric The tubing in the hoc kg side, U.bend portion, Examination requirements, exandnation method, and the extent and 0 (/) and optionally coM kg side willbe exanuned. frequency of examinarion shall be in accordance with plant Tcchnical X Erf SpeciYications. Q g H a td O o 0 tf) H Ef C Ef > O fJ) OX I tf) O ~ H > tf) Z + tf) H 0 ( Hg 0 R '(f Q 0

(f) 0 0

0 I a TaMe I Qg>10 NSERVVICE INSPECIION PROGRAM aASS I COMPONENTS (Cont'd) RCMP'CC~

Item Examination Components and Pans Examination Examination Requirements for Examination Technique/Examination VPgH No. Category To be Examined Methods Third Inspection Interual Area Comments M C K O

HEAT EXCHANGERS 0 8250 8.8 Head WeMs No tneridional or circumfcrenriai heal weMs in beat exchanger at IL 8251 E. Ginna 8252

82.60 8 8 Tubcshect-to.Head Welds Volumeuie Each tubesheet-to.head weM willbe Examination wiB be performed with UT teclmiques. cxanulRd

82.70 B.B Longhudinal Welds There are no RHE longitudinal weMs at IL E. Ginna. 0 M Q 82JS B-B Tubesheet.to&hell WeMs Vo!umetrie Each tubeshect.to.shell weM willbe Examination willbe performed with UT tecluuquea, H cxanuncd. X H W O 83.150 8-D Nmzle-to-Vessel WcMs and Volumetri All nmzle.to-sheB and nmzle insMe radius Examination willbe performed with UT techmques. 83.160 B.D Nozzk Inside Radius sections willbe cxaminctL At least 2596 but O Section not more than 50% of the nozzles shall be 0~ R 'E) examined by the end of the first inspecuon C 'E) period and the remainder by the end of the O M OX Interrak I V R X O +If) O ~ H ()) tf) < XI X 85 100 B.F Pressure-Retaining No heat exchanger dissimilar weMs at R. E. GfnnL + M) H 85 110 Dissimihr Metal WcMs 'd ()) 85.120 0

86.120 BG. I Prcssure-Retaining Bohing N/A No heat exchanger bolring at R. E. Glnna b7 8&.130 )2 Inches in Diameter 86.1 CO 0 gCQ Bohs, Studs, and Ntxs No heat exchanger bohing at IL E. Ginna. s2 Inches M Diameter

Integrally WeMed Integrally weMed auachments not required for examination for 3rd Anne hments and 4th Intcnrais by code.

815 C0 B.P Pressure.Retaining Visual (VT-2) All RHE components wiilbe examined during VTexaminarions willbe performed in aceordanee with IWA.5240 Boundaries system kakage test. Examinarions to be (D performed in accordance with IW8.5221 prior 0 to phnt startu p after each refueling outage.

815A I B.P Pressure-Retainfng Visual (VT.2) AllRHE components w81 be examined during VTexaminations willbe performed M accordance with IWA524k 0 Oundsries system hyhostatk test or ahernatively to Code Case NA98. Exandnations to be performed in accordance with IW8.5221/5222 at or near the end of the inspection Interrak II Table 1

INSERVKXINSPECllON PROGRAM Qg>I0 CIASS 1 COMPONENIS (Cont'd) RRf/)g MCCOY item Components snd Pans Exarrdnation Exarrdnation Requirements for Examination Technique/Exsndnatbn QQgH No. To be Examined Methods T)drd Inspection interval Area Comments M O PIPING H 85.130 B.F DissimQar Metal Wekh Volumetric and Allbutt welds to be examined. The wekh willbe examined with UT and PT. 0 s4 Inches NPS Surface

85.140 LF Dhsimibr Metal WeMs N/A No dbsimitsr metal weMs <4 inches NPS at L E. Gtnna <4 inches NPS

85 150 B.F Dissinular Metal Soc'ket N/A No dissimilar metal socket wekh at IL E. Ghana. m WeMs 0 f/) 86.150 BG I Pressure.Retsinhrg Boking No pressure. retaining bohing >2 inches ht diameter at L E. Ginna. Q 86.160 >2 Inches in Diameter H 86.) 70 g H XO Pressure-Rettdning Boking No prcssure.retaining bohing «2 h»hes on piping at L E. Girma. O I s2 Inches in Diameter ~)t)0 H R 'd 89.10 W Cucumferential Pipe Wekh Volumetric and 259k of 0» required circumferential butt The wekb willbe examined whh UT and PT. piping O f/) O Erj 89.11 s4 Inches NPS Surface welds to be examined. See Note I at end of I 'Ej Tabk I for sekction criteria. +I ta Erj O tt) Ett O ~ H 89.12 W Longitudinal Pipe Welds Volumetric and Longitudinal weMs that adjoin schedukd The piping wekh willbe exanuned with UT snd PT. tt) L Z s4 Inches NPS Surhce eircumferemisl wekb are to be examined. )t)H One pipe diameter ncx to exceed 12 inches of 'Tj td each bngitudinsl weM kngth rcquireL 0

Circumferential WeMs Surface 25% of the rcquircd circumferential butt 'the piping wekh willbe examined whh PT. 89.21 <4 Inches NPS weMs to be examhteL See Note I at end of g 0 Table I for sekction criteriL

Longitudinal Pipe VVeMs No pressure.retaining bnghudktst pipe welds < 4 h»hes NPS at IL E. <4 Inches NPS Ginna.

8920 W Branch Pipe Connection Volumetric and 2544 of the required branch connection joints lhe branch connection wekb willbe examined with UT and PT. 898) Welds a4 Inches NPS Surface to be examined. See Note ) at end of Table I for sekction criteriL 8932 W Branch Pipe Connection 25% of the required branch connection joints The branch connection weMs willbe examh»d with PT. WeMs <4 Inches NPS to be examineL See Note I at end of Table ) 0 for sekction eriterim

8940 W Socket )VeMs Surface 25)k of 6e required soc'kct webb to be The socket weMs witt be examined whh PT. 0 exandneL See h ore I at end of Tab k I for selenion eritcria.

Bttk)0 B.K I Integrally WeMcd Integrally weMcd attachments rxx required for examination for 3rd Attachments and 4th intervab by code. F ~

~ I

I . ~ —. ~ Table 1

NSERVKX INSPKCIION PROGRAM Qg>10 (XASS 1 COMPONENIS (Cora'd)

Item Gomponents and Parts Examinarion Requirements for Examination Technique/Examination Ntx To be Examined Third Inspecrion interval Area Comments O

PIPINC Cont'd 0H BI%50 B.P AB Pressure Retaining Visual (VT-2) Allcomponents to be examined during system VTexamination wiB be performed in accordance whh IWA.5241 Boundaries for Piping leakage test. Examfnarion to be performed in Components accordance with IWB.5221 prior to plant stanup alter each fefuelfng outage.

B15.5) B-P AllPressure Retaining Visual (VT-2) Allcomponents to be examined during system VTexamination willbe performed in accordance with IWA.5240. Boundaries for Piping hydrostaric test or alternatively to Code Case Components N 498. Examination to be performed in 0 M accordance with IWB.5221/5222 at or near the end of the Inspection Intetvah Q g H WO

0 NOH a~< ( +OM OX I X U ~tOO ~ H >NOHLQ Q '0 MHg 0 (2) R d g 0 CQ 'E) e'

M (t) 0

I 0

Table 1 Qg>10 INSERVICE INSPECllON PROGRAM CIASS 1 COMPONENIS (Cont'd) RR(/) P'c C C Q Item Examina don Components and Parts Examination Examinadon Requirements for Examination Technique/Examination No. Category To be Examined Methods Third Inspection Interval Area Comments O

PUMPS

86.180 BG.I Bohr and Studs, >2 Inches Volumeuk Allbohs and studs to be exanuned for hems The bohing wtlI be examined whh UT. Code Case N.307.1 shall in Diameter associated with one component In a apply. The bolting may be examined In pkce under tension or when muhicomponent group. disassembled or removetL

86.190 B4.1 Flange Surface for Bolting Visual (VT.I) Examination inc!udes I inch anntdar surface VTexamination willbe performed when UsassembletL »2 Inches h Diameter of Iknge around each stud hok surface when When Connection k disassembled. Disassembled 0 (/l

86200 84.1 Nuts, Bushings, and Visual (VT-I) AU nuts, bushings, and washers to be VTexamination willbe performed when dhassembkd. Q Washers >2 Inches in exanuncd when disassembkd on one Diameter component in a muhicom ponent group. XO 87XO BG.2 Prcssure-Retammg Bohmg No pressure. retaining bohfng <2 Inches in diameter on pumps at IL E. o~~ s2 laches in Diameter Gfnna. tf) H 3 C 'Ef 8IIL20 8-K I Integmlly WeMed Integrally welded attachments not required for examination for 3rd 0 (I) O (x) Attachments and 4th intervals by code. I + X U 812.10 B.LI Pump Casing WeMs Visual (VT.I) Reactor coolant pump easing weMs on one Examination performed in accordance with Code Case N.481. tf) O P H pump to be examineL + 'LO H M Cl 812.20 8-L2 Internal Surfaces of Pump Visual (VM) One reactor coolant pump to be exanuned Pump casing Internal surface willbe examined with vkual techniques (/) Casings when disassembfoL when disasscmbktL H~ 0 I-3 'E) 815.60 B.P Pressure.Retaining Visual (VT.2) Allcomponents to be examined during system VTexanunations willbe performed in accordance with IWA.5240. (T) X Boundaries for Pump kahsge test. Examfnatson to bc performed trt g 0 Components accordance with IWB$221 prior to pknt CQ startup after each refueling outage.

81%61 8-P Pressure. Retaining Visual (VT2) AU components to be examined during system VTexaminations willbe performed in accordance with IWA 524th Boundaries for Pump hydrostatk test or ahcmatively to Code Case Components N.498. Examination to be performed In accordance with IW8.5221/5222 at or near the end of the inspection intervaL (/) (D RG1.14 Flywheel Pump FIywheek Surface and Each reactor cooknt pump Ilywheel to be Examinations willbe performed with MTand UT techniques on the 2 0 Volumetric examined per Rcg. Guide 1.14. High mess active components as a minimum on an Augmented Program. areas to be examined each period with fuU I examination at the end of intcrvaL 0

INSHMCE INSPECllON PROGRAM CIASS I COMPONENIS (Cont'd)

Item Examinarion Components and Pans Examination Retiuirements for Examinarion Tcchnhiue/Examfnarion No. Category To be Exanuned Third Inspecrion Interval Area Comments O

VALVES

86.210 BG I Bohing >2 Inches in N/A No valve bohfng >2 inches in dhtmeter at L E. Ginna 8&.220 Diameter 86230

87.70 BG.2 Bohing s2 Inches In Visual (VT-I) Allbohs, studs, and nuts to be examined on I The bohing may be examined in place under tension or when Diameter component per group. dlsassembkd or removeL

81030 8 K I Integrally WeMcd Integrally weMcd attachments not requfml for examination for 3rd 0 (I) Attachments and 4th intcrvah by axle. Q H 81230 8-M I Pressure. Retaining WeMs No pressure retaining weMs In valve bodies <4 inches NPS at IL E. g H in Valve Bodies < 4 Inches Ginns. XO NPS o~~ 812.40 B-hl I Pressure-Retaining Welds Vo!muetric AilweMs on one valve In each group of Valve weMs willbe exanuned with UT. OeH in Valve Bodies a4 Inches valves that ls of the same nsttucrion and > tf) Z NPS sfmBsr function to be cxaminoh + o(f) OX I 8 IL50 8 M.2 Internal Surfaces of Valve Visual (VT4) One valve iu each gmup of valves that is of Internal surfaces of valve bodies to be examined with VT.3. ea Bodies on Valves the some construction and simBsr function to ()7+tOO >4 Inches NPS be cxaminctL tf) Z d (gi 815.70 8 P All Prcssure. Retaining Visual (Vl'-2) Allcomponents to be examined during system VT examinations willbe performed in accordance with IWB-5240. 0 Boundaries for Valve kahsge test. Examination to be performed in Components accordance with IWB 5221 prior to plant R 'E) stsrtup after each refueling outage.

go 'T) 815.71 8 P All Pressure Retaining Visual (VT-2) Allcomponents to be examined during system VTexaminations willbe performed in accordance with IWA.5240. 4A Boundsries for Valve hydroststk t«st or ahctnatfvely to Code Case Components NA98. Examination to be performed in c' accordance whh IW8.5221/5222 at or near the end of the inspection Interval

(I) 9 0 0

O Table I Q )%10 SCCAQRMQ WWgH

As aUowed by IOCFR50.55(a)(b)(2)(ii), ASME 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 M 'gK 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: 0

(a) Allacoessibk Terminal Ends in each pipe or branch run connected to vessek. 0 (b) Allaeeessibk Terminal Ends and joints in each pipe or branch run connected to other components such as pumps, branches and anchors.

(e) Alldissbnilar metal welds.

(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 =I one Mop and shall be sekcted among the Qass I syrtems, prorated, to the degree piactkaL m 0 M Nixer 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 Q (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. g H Ezj 0 (c) Piping connections to rigMlymounted eomponentr, such as vessels, pumps, cet. n~~ Terminal Ends at component or branch connections are considered to be the piping weM connection to the safewn4 nozzk, reducer, weMokL sockolet or fiange. 0 tf) H ~If)U Q C 'Ej 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 O M O Lxj shaB be considered Structural Discontinuities. I 'Tj wa0 R The folkwingweld are identified in Su I to Appendix the Program Plan. +If) O vbs H types pplement B, (EI tf) ~ 'E.A Terminal End at a Piping Anchor +If) H td 'd (EI 'E-B Terminal End at a Branch Connection 'E.P Terminal End at a Pump Connection 0 'E.V Terminal End at a Vessel Connection R (j * SD Structural Discontinuity 'P Pipe to Pipe Burt Weld 'EAM Longitudinal Seam WeM 'Tj

Note: When more than one weM type k a pplicable, the more restrictive (i.c. 'IE) is utilized.

(2) Examination is limited to those integrally welded artachmems that meet the folkrwingconditions:

(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 8J and the weMed attachments to associated pumps and valves integral to such piping. 1 Table 2 Qg>I0 RAM'CCL

Examination Technique/Exanunation Item Exandnatlon Components and parts Examhtation Examination Requirements for O ho. Category To be Exandned Methods Third Itnpection Interval /trea Comments

Information speeiTic to exanunation techniques, H 'Ihe ASME Section XI Item Ãtx Each type of exarrunatfon The NDE method This colunm provides Information regarding This cohunn provides areas, or comments. 0 and Category of the component area is listed In this required to satisfy the number and/or percent of examfrmtions exandnatfon 4 are listed in these columns. column. Code requirements required to be performed for the inspection is listed h this intervaL column.

0 M Q H WO

LO H 'R 'Tf ~ C '0 O M OX I 'd xaDR +tOO ~ H >tOZ XI X + tO H MH~ M0 N

'Ef

TaMe 2 Qg>10 R 2e (/) ~ INSERVICE INSPBCIION PROGRAM R( ( CRASS 2 COMPONENIS

Item Components and Pats Examhethn Examination Rcquiremerrts for Examhetion Techtuque/Examination Ntx To be Examined Methab Tturd inspection interval Area Comments O t3 PRESSURE VESSELS H0 C1.10 G* SheB Circumferenthl Volumetric 100% of each weM to be examhted (applies The wekb willbe examined whh UT. tveMs only to wekh at gross structural discontintuties). For mukiple vesseh of sinular design sILc and setvioe, examinations may be limited to one vesseL H CIM CA Heal Circumferential Volumetric 100% of each head-toaheB weM to be Wekls cxamineL for mukiple vcsseb of simBar 0 (/) design size and service, xaninations may be X Erf limited to one vesseL Q

C)30 GA Tubesheet.toSheB WeM Volumeuie 100% of each weM to be cxaminecL For The welds wiB be exanuncd with UT. g H mukfpk vcsseh of siuuhr design she and XO z servke, eanhations ney be Bmited to one OH~ vesseL U0QH CL10 C B Nouks in Vesseh xl/2- N/A No Code rcquircd Nouks M Vcsseh aI/2.loch O (I) OX Ch1 I Inch Nonunal Thickness Nominal Thickness Nozzk-toSheB (or Head) WeM I Noule toSheB (or Heal) at L E. GinnL X U tO O 'P H Weld (2') Z L kf) H C220 GB Nozzks Withota Surface and AB nouks to be seketed at terndnal ends of lhe weMs willbe examined with UT and MTor PT as appbcabk. 'El N C2.21 Reinforcing PLste in Volumetric piping runs sekcted for examination under 0 Yeech > I/2.loch Categories C F.l and C.F-2. 100% of each Nomirel Thkkness Noule. weM to be exatrdnccL Manways and lend 1-3 'E) to.SheB (or Head) WeM hoks cxcludeL For muhple vesseh of simihr design, she, and servke, examinations g 0 may be limited to one vesseL 4 A 'E)

C2.22 GB Naze Inside Radius Volumetric 100% of each area to be xataunetL Manways The noule inside ralius section willbe examined with UT. e' Section and hand holes are cxduded. For muMple vessels of similar design, she, and service, examinations ney be limited to one vesseL

C230 GB Nouks with Reinforcing See C291, C232, C283 (I) Phtcin Vcsseh > I/2 inch (B Nominal Thkkncss 0

C291 GB Rehtforcing Phte Wekh Surhee AB nonks at terminal ends of piping runs. The reinforcing plate weMs wiB be cxandned whh PT or MTas Surface to Naze tk Vessel For rntdtiple vesseb of simBar design, size, a pplieab'k. 0 and service, cxanhetions may be limed to one vesseL

0 i Tabb 2

INSERVKXINSPECIION PROGRAM CLASS 2 COMPONEÃIS (Conc'd)

Item Examination Components and Pans Examinarion Examination Reciuirements for Examination Technhiue/ExaminatIon Ntx Category To be Examined Metbxh 'third Inspection Intetva) Area Comments

PRESSURE VESSEIS Cont'd

CL32 GB Nozzle.ToSheB (or Head) N/A AB nozzks at terminal ends of piping runs. The Inside of vessel is not accessible, perfornung CL33 Instead. 0 WeMs When Inside of For muhipk vesseb of simBar design, sbe, Vessel is Accessible and savice, xamlnations may be limbed to one vesseL

C233 C B Nozzk-ToShcB (or Head) Visual (Vl'2) AB nozzks at terminal erxis of piphtg fur@. VTexamfnarions willbe performed In accordance whh IWB-524L Wclds IVhen Inside of For muhiple vcsseb of simBar design, size, B» reluhcd component to be examined during system leakage test. H Vessel is Inaeeessibk and servke, examinations cnay be lirnitcd to m one vesseL 0 (/) Q C3.10 GC Integrally Welded At. I0095 ol each weM to be examineL The weMed attachments willbe examined with MTor PT as H tachments Anachmencs whose base materhl is 3/4 Inch applicable. or greater co be sekaeL Where X k multlpk Er) vesseh are provided with a number of similar 0 attachments, the anachments may be discributed among the vesseh. For muhiple cf) (=) K vesseh of sfnular design and savice, M) C d examinations may be Bmhcd to one vesseL < o(/) A X I CC.IO GD Prcssure. Raaining Robing N/A No pressure.rccaining vessel bohing >2 Inches in diameter at IL E. I Erf U ~ cf) H >2 Inches in Diameter Cinna. ~ O ~ ~tDH~ tO Q Cy. IO GH Pressure.Recaining Compo- Visual (VT.2) AB pressure-rccaining boundaries for vesseb VTexaminations wiB be performed in accordance whh IWA5240. 0 co be examined during system pressure test. (" I-I g 0 Examinarions to be performed in aeeordance whh IWG522l for each inspeaion pericxL

Cy20 GH Pressure Retaining Compo Visual (VT2) AB pressure. retaining boundaries for vesseh VTexaminations wiB be performed in accordance with IWA.52C0. 'd nents 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 'h Table 2

NSERVVICE DISPECIION PROGRAM Qg>10 42/ASS 2 COMPONENIS (Cont'd) CCMg ' CCCC iten Components and Pats Requirements for Examination Techruque/Examfnatbn Area Conunents PSYCH No. To be Examined Third Inspection Interval M RK O PIPING H C3.20 CC lntegraBy WeMcd IOOIIof each weM to be examiners 'Ihe wekb wiB be examined with MTor PT as applicable. Auachmeas Attachments whose base materbl b 3/4 bch 0 or greater to be selected. Selection Bmftcd to those componems selected under Exanunatbn Categories GF. I and GF.2.

C4.20 GD Pressure Retaining Boking No prcssure. retaining baking >2 Inches in diameer at R. E. Ginna. >2 Inches in Diameter 0 M C5.10 C F-I Pipbg WeMs M Austenitic Surface and 1009k of each cueumferential wekl requiting The welds willbe examined whh UT and PT. C5.11 Stainless Steel or High- Volumetric emnfnatbn. See Note I at end of Table 2 Q ABoy piphtg a3/B.inch for sebction crftcriL H hommal WaB TIuckness g H for Piping >4 NPS, XO Circumferential OH~ 0u)H No weMs of tlus hen number at R. E. Ging. C5.12 GF. I Piping Wekb in AusteniYie bngkudfnal U C IEf Stainless Steel or High- O M OW Alby Piping a3/8 loch I Nominal WaB Thickness ra a for Piping >4 NPS, Lon. + kf3O Q H gitudinal + tO H d f33 C5.20 GF I Piping WeMs in Austenftie Surface and IBIDof each circumfcrcntbl weM rcquiYing 'Ihe weMs willbe examined with UT and PT. MHg C52I Stainless Steel or High. Volumetric examination. See Note I at end of Table 2 0 Alby Piping al/S.loch for selection criterh. R 'Ef W Nominal Wall Thickness for Piping a2 NPS and N 0 s4 NPS, Circumferential CQ L C522 GF.I Piping WeMs in AusterdYic No bngitudinal weMs of this iten number at R. E. Ging. caaudess Steel or High. Alby Piping al/5-Inch Nominal WaB Thickness for Piping a2 NPS and s4 NPS, Iongkudinal M 8 C520 CF-I Socket WeMs in AusteniYie IOOIk ol each weld requiring examination. 0 Stalnbss Steel or High- See Note I at end ofTable 2 for sebction Alby Piping crucrh. 0 C5.40 OF-I Pipe Branch Connections 100% of each circumferential weM requiYing The welds willbe «xanined with PT. C5.41 h Austenftb Stairdcss examinatbn. See Note I at end of Table 2 Steel or High-Alby Piping for selection criteri. a2 NPS, Circumferential 0 g

N Tsbk 2 Ag>IO CHSERVICE INSPECllON PROCRAM flASS 2 COMPONENIS (Coca'd) item Examhation Com ponents and Pans Examhation Examhation Requirements for Examination Technique/Examination Ntx Category To be Examhed Methods Ttdrd Inspection Interval Area Comments

PIPING cont'd H CS.c2 GF.I Pipe Branch Connections N/A No bnghudhal welds of this item nmnber at iL E. G irma. 0 h AustcniYie Stainless Steel or High-Alby Ptpmg s2 NPS, lnnghudhal

Cx50 GF-2 Piping Wefds h Carbon or Surface and 100% of each ciicumferenrial and 2.5c of lie wews wiBbe examhed whh UT and MT. I CSSI Inw.AlbySteel s3/8. Volumetric each bnghudhaI weM requhing cxanunatbn. H C552 Inch Nominal IVaB Sce Note 2 at end of Tabk 2 for sekccion m Tldckness for Piping criteria. In addition, 10Nli of the mah steam 0 f/) > 4 NPS, Circumferential and main fecdwater wclds bested outside and Longitudhal containmcnc and traveling safety areas shall Q be examined Technhd SpcriTicacions. H per ixi H C5.60 C F.2 Piping Wews in Guten or N/A No carbon or steel nonexempt wews in thh category at IL E. R baby Ex) CSAiI Inw.ABoy Steel > I/5-Inch Ginns. 0 C5.62 Nominal Wall lhickncsu for Piping s2 NPS and cf) H E) irC NPS, Cfrcumfcrenriai Utf) ~ and Longitudinal ~ o v) OX I D R C5.70 GF-2 Socket WelCh h Cmbon or No carbon or bwatby steel nonexempt welds h thk category at R. E. +) w wa cf) H Low&bySteel Cinns. (2')

C5$2 GF.I Pipe Branch Connections No bngitudhal welds of thb item number at IL E. CinnL g 0 IllCsfboii of LDW.ABoy Steel s2 NPS, Inngitudhal

C720 GH Pressure Reuuning Compo Visual (VT.2) Allpressure.retahhg boundaries for piping co VTexamhatbns mll be periormed in aceordancc with IWA.5240. be exandned during system prcssure test. (I) Examination to be performed in accordance (B whh IVc&5221 for each hspcction pcrkxL 0

Pressure.Retaining Compo. Visual (Vl'-2) AB pressure.retching boundaries for piping to VTexmninstions wBI be performed in accordance with RVA.5240. be cxandned during system hydrostatic test or 0 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 0 periods of each htcrvaL Tabk 2

!NSEINICE INSPECIION PROGRAM Qg>10 t2ASS 2 COMPONDPIS (Cosa'd) ECCLR R (I) Q Item Components and Parts Exanutioa Rccluftements for Exination Tcchahlue/Examinarion Q H Third Inspccrion Interval Area Cnuaents ~) No. To be Examined (/) C K O PUMPS

Cga GC integral/ Wehkd At. N/h 10096 of each wehf to be hnachmems whose base materiai is 3/4 inch or greater to be~sekctoh Sekction limited to those cachmcncs components sekctcd under Examination Category GG. No pumps meet this criteria at R. E. Glans.

C430 GD Pressure. Retaining Bohing N/A No prcssure. retaining pump bohing >2 Inches in diameter at L E. >2 Inches In Diameter Ginna.

No pressure-retaining pump weMs at L y Ginna C6.10 CG Pressure. Reta'uung Welds N/A (/) in Pump Casings 0 Q Pressure. Retaining Compo. Visual (Vl'-2) hll pressure-training boundaries for pumps VTexanunations willbe pcriormcd h accordance with IWA.5240. H ncnts to be examined during pressure test. g H Exanunat ion to be pcriormcd in accordance td O with IWC-5221 for each Inspecrioa perioh O~~ accordance IWAS240. 0cf) H CPA'N Pressure Retaining Compo Vimal (VT-2) All pressure retainiag boundaries for pumps VTexaminatkns willbe performed in with U co be exanuned during system hydrosratk test nents O) or to Code Case NAPIL 0 alternatively I Examination to be performed in accordance X U with IVTS221/5222 at or near the end of gtf) O ~ H each Inspccrion huesvaI or during same in. tO Q spccrion periods of each intcrvah ~ cg) H ~ 0 'T) ()) 0

XI d

0 Tabk 2

NSSERVIcX INSPECIION PROGRAM CLASS 2 COMPONENIS (Cont'd) ZC( C'

Item Examinarion Components and Parts Examhation Requirements for Examhation Technique/Examination No. Category To be Examined lhhd inspection htenral Area Comments

VALVES

C3AO GC Integral/ Wchkd At. Surface 100% of each weM to be examh«L The welds wBI be examined with MTor PT as applicable. 0 tat hments Auachments whose base material is 3/i hch of greater to be sekcted. Sckcthn limbed to those components seketed under Exandnatkn Category GG.

CIAO GD Pressure-Rctahing Bolting No pressure-retainhg bohing >2 hches h diameter at L E. Ghna. H >2 Inches in Nuneter 0 0) Pressure.Retahing WcMs No pressure. retaining wcids h valve bodies at L E. Ginna. Q h Vahre Bodies H g H Cy.70 GH Pressure Retaining Compo. Visual (VT.2) Allpressure.retahhg boundaries for valves to VTexaminations willbe performed in accordance with IWA.524L (x) 0 a ncnts be examined during system prcssure test. Examination to be performed h accordance o~~ whh IWG5221 for each ins pectbn pcriocL +QH

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 O distriliuted as foUows:

(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., ifa 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

(c) whhht each system, examhtations shall be distnl>utcd bctwcen hne skcs prorated to the degree practicable. H (2) 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 (f) 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 0 folbwst Q H (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., ifa system conttdns 30% of g H the nonexempt weMs, then 30% of the nondestructive examinations required by Exanunation Category GF-2 shouM be performed on that system); o~~[x[ O (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 cf) ternunal ends and structural discontinuhks in that system; and H a~< I c([ + O [f) O [x) (e) within each system, exandnadons shall be distributed between line sizes prorated to the degree practkabk. 'd [ XU (d) Only those weMs showing reportable preservice transverse indkations need to be examined for transverse rellectois. +cf) O ~ H td tf) ~ Terminal Ends (TE) are defined M Table I Notes, note number l. (3) 'd N Structural DiseontkuiYies (SD) are defined in Table I Noccs, note number 2. 0 R 0 The foBowfng wcM types are identified M Supplement I to Appendix B, the Program PLtn. g 0

'E A Terminal End at a Piping Anchor L 'KB 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. 0 r. 0

0 t v

W I SNSERVICE INSPECTION PROGRAM RCCV CXXK(IJISS ~~gH V) NK Item Components and Pans Examination Requirements for Examination Technique/Examfnadon 0 No. To be Examined Third Inspection Imetvaf Area Commems H The ASVE Section XI Rem No. Each type of examination The NDE method This column provides Information regarding Tlds column provides Information spcciTic to examination techniques, and CateEory of the component area is listed in tide required to satisfy the number andfor percent of examinations examination areas, or couuucnts. 0 are listed in these columns. column. Code requirements required to be performed for the Inspection is listed in this Intervah column.

0 M Q H X H WO o ~tErOH H I O M O W I Erf U tdy O ~ tEs t3 > u) H ~He 0d fXI

0 Ct 0 ~ It Tabk 3 RCC~

item Examlnarion Components and Pans Exanunation Examination Requirements for Examination Tcchrdqaelgxamlnarion Ntx Category To be Examined Methods Third Ins pcctlotl lluelval Area Comments O b3 CLASS 3 COMPONENTS

Dl.10 D A prcssure.Retaining Compo Visual (VT2) Allcomponents to be examined daring system VTexandnations willbe performed in aceordanee with IWA.5240. D2.10 D-8 pressure or system hydrostatic test as defined D3.10 DC 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 H r whh IWD.5223. m 0 (I) D 1 20 IM Integral Attachments of Visual (VTQ) AIIrequired anachments to be examined throagh Q Suppons and Restraints, daring each inspection Interval as defined by H DIM Hydraulic Snubbers, IIVD.2500 I Tabk Deseriptions. For multiple H D2.20 D 3 Spring, Consamt Load, and components in a system of sin8ar design, g though Shock Absorbers fusion, and service, the integral attachment WO D2X4 of only one of the muhpk components shall OH~ D3.20 DC be examined. 1he ktegral anachments 0 H through selected shall correspond to those support Ut() ~ C '0 D3.60 components selected for cxandnarion in actor. > o(f) OX dance with IIVF-2510(b). I 'E) wa0 R +tg) O ~') )-3 L t() H 0 d Q 0 II I ~ I' N ~

h V

«- > ~ ~ ll r

„1

~ ~ Q PN g ECCLRRMQ

A item Examinsuon Components and Parts ~n Repurements for Exandnation Technhiuef Examination Thhd Inspection interval Area Crnmerus Ão. Category To be Examined H The ARVE Section XI Item No. Each type of examination The IIDE method This column provides Information regarding This column provides Information spceiTic to examination tcchnhiues, 0 cxaminauon of commentn and Category of the component area is hstcd in this required to satisfy the number and/or percent of xaminadons ~ are hsted in these colmnns. colmnn. Code rerfufrements roiuired to be performed for the Inspection is listed in tlds Intervah column. H

0 CQ Q g H WO OHo 'LO H R 'd U C M O M O trf I d eU +LOQId' > tg) H MH~ 0Ef %

XI 0 CQ d

M ID 0

I 0 Qg>10 R R (I) 0 BNSERVICE INSPECI)N PROGRAM R( ( C1JISS I, CJASS 2, AND(1ASS 3 COMPONENT SUPPORTS

item Components and Parts Examination Requirements for xamlnadon Tcchrdqtu JXamfnatmn (I) Ntx To be Examined Third Inspection Interval Area Conunents O

CIASS I AND 3 IWF COMPONENIS SUPPORTS FROM 1990 TO 1993 OUTAGE USING IWF 1986 Code 0 PIATE AND SHEIL TYPE SUPPOR UNEAR TYPE SUPPORTS AND COMPONENT STANDARD SUPPORTS

F1.10 F.A Mechanical Connections to Visual (VT4) Component supports to be selected for Funcuonal testing of snubber type support components shaB be though Pressure-Rcaunfng Com po- examlnadon are the supports of the performed in accordance with Teciudcal Specifications and ln FI.40 nents and BuiMing nonexempc (2ass I, 2, and 3 components accordance with requirements of this program. F2.)0 F-B Structure; WeM Conner. schedued to be xaamfnerL Examination H though tions to BuiMing Structure; bou darles established iu secordam wkh F2.40 WeM and Mechanical IWF-130th Examinations may be performed 0 (I) F3.10 F< Connccdons at Interme. during normal system operation or plant out. through rUate Joints ln Muftf- ages Q FATSO connectcd Integral and H Nonintegral Supports; and L H Component Dlspktcement XO Settings of Guides and O~~ Stops, Misalignment of 0tf) H Supports, Assembly ol Su. a ( 'd pport Items; Spring Type O (I) OX Supports; Comtant Load I Type Suppotts; Shock wa tf) O ~ H Absorbers; Hydraulic Type > tf) 5nubbers ~ 0'Ef W CLASS I. 2. AND 3 IWF COMPONENT SUPPORTS FROM 1994 TO 1999, USING CODE CASE N 491 AND IWF 1986 CODE g 0 Item Components 8 Parts Examination Examination Requirement Examination Techniqucrgxamfnation 'd No. to be Examined Method for the Third interval Area Comments

FI.10 F-A Class I piping supports Visual (VT3) 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 (D n F1 20 F-A Class 3 piping supports Visual (VT3) I0% of aass 3 supports V FI 40 FA Chss I, 2, 5 3 supports Visual (VT4) 10ryrtr except for multiple 0 other than piping supports components. REV. 'AGE QUALITY ASSURANCE MANUAL 5 3 1 of 96 GINNA STATION Section I EFFECTIVE DATE: December 31, 1993 CORPORATION ROCHESTER GAS & ELECTRIC SIGNATURE DATE

TITLE PREPARED BY

APPENDIX B QUAUTY R. E. GINNA NUCLEAR POWER 'PLANT ASSURANCE (Z-Z- INSERVICE INSPECTION PROGRAM REVIEW: ) FOR THE 1990-1999 INTERVAL ~ LINE LIST APPROVE BY:

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 nonexempt 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. CINNANUCLEAR POWER PIANT Inservke ~n Boandery LIne Lbt Thhd Iaspecaoa Interval

P&IDNo r 33013-1231 O Chss r 2 System: MAINSIEAM H Comp Typm COMPONENIS 0

RG&E 151 Size Thkns Exemption NDE IIne No. ~Fi . MstrL ~la. ~la. Bssa Method Po ~Tern ln? Lbe deseri rernsrhs Revised

EMSOIA B-l OAN OAXXI SUR/VOL 715 505 - SIErW CENERATOR* R 1 I/91 EMSOI B Bl OAR 0.000 SUR/VOL 715 505 ~ STEM GENERATOR K R II/91 H 0 M

XH WO + V H LI? H gOMLIyg I HeO M tdy Q LI) H0 H 2g t

C L E. GINNANUCLEAR POWER PIANT Inservise Exanrination BsnnnhnY Une Ust Thini I spection Interval

PAID No t 33013 1231 (2ass t 2 S)stern t MAINSTEAM H Comp T)Tres PIPINC 0 RCAE CEbert ISI Size Thhns NDE line No. line No. ~F1 . MrnrI ~in. ~In. Methort Po ~Tern Int line deseri 'ernarhr

30A-M$600-IA MS-100 MS.1000 B3 A115 30AO MSO SUR/VOL 715 505 5/G IA10 VALVE3517. 30B.M$600-1B MS-200 SMS-1001 33 A11$ 30Am l~ SUR/VOL 715 505 5/G IB TO VALVE3516. 6A MSGR'.IA MS.100 MS 1000 B-9A A106 6Am a 432 BUR/VOL 715 505 30'S PIPE TO VALVE3505A. R 11/91 H 6h-M$600 B MS300 SMS-1001 B.IO A106 6AO 0.432 30'S PIPE VALVE I SUR/VOL 715 505 10 3504A. 0 (/) 6B-M$600. IA M$300 MS.1000 B-9h A106 6Am a 432 SVR/VOL 715 505 3(P MS PIPE 10 VALVE3411. R II/91 6B-MSSS.I B MS 120 SM$1001 B-IO h106 6.00 0.432 SUR/VOL 715 505 30'S PIPE 10 VALVE3410. 6GM$600.1A MS300 MS-1000 B.9h h106 MO 0.432 SVR/VOL 715 505 3(7 MS PIPE TO VALVE3509. R II/91 6OM$600-I B MS300 SMS 1001 B 10 hl06 6.00 0 432 SUR/VOL 715 50$ 30'S PIPE TO VALVE3508. XH 6D.M$600-1A MS300 MS 1000 B-9h h106 6Am 0 432 SUR/VOL 715 505 3(7 MS PIPE 10 VALVE3511. R 11/91 td 0 6D.M$600 IB SM$ 1001 B.IO hl06 MO a432 SUR/VOL 715 505 30'S PIPE TO VALVE3510. 6LM$600 IA MS300 MS-1000 B-9h h 106 MO a432 SVR/VOL 715 505 30'S PIPE TO VALVE3513. R II/9I 6LM$600 IB M$300 SMS-1001 B.IO A106 MO 0.432 SVR/VOL 715 505 30'S PIPE 10 VALVE3512. H+QH * IO g 6EM$6N.IA MS300 MS.1000 B.9A A106 6Am 0 432 SUR/VOL 715 505 30'S PIPE TO VALVE3515. R 11/91 O (/l OX 6F.M$600-1B MS300 SMS-1001 B.IO A106 6AO 0.432 SUR/VOL 715 505 30'S PIPE 10 VALVE3514. 6G-~IA MS300 MS.1000 B-9A A106 M0 a 432 BUR/VOL 715 505 30'S PIPE 10 6 X 2 REDUCKL R ll/91 6G.M$600.I B M$300 SKS.1001 B-IO A106 6' 432 SUR/VOI 715 505 30'S PIPE 10 6 X 2 REDUCEII R 11/91 H 'N 0 3A.M$6N.IA M$300 MS-1000 B9A A106 3'300 IWC.1222(A) 715 505 30 MS PIPE 10 VALVE3615 (3517 BYPASS). R 11/91 3A-M$80 IB MS300 SM$ 1001 B 10 A106 3'300 IViZ1222(A) 715 $0$ 30'S PIPE TO VALVE3614 (3516 BYPASS). R 11/91 g 'LO H 2A.M$60alh B.9A 2AXt OANO IWC.1222(A) 6G-M$600.1 A TO VALVE3521. h 11/91 0 2A.MS600-1B B 10 2Am a000 IS&1222(A) 6G-MLS IB TO VALVE3520. A 11/91 H g 0 ISA-M$600.1h MS-1000 B-9 A106 IM 0.145 IWC.1222(A) 715 505 Y 30'S PIPE 10 VALVE3455 1$A-M$600.1B SMS 1001 B.IO A106 IM 0.145 IWC 1222(A) 715 $05 Y 6A.MSCi00 IB TO VALVE3504C. ISB.M$60a lb MS-1000 B-9h A106 1$0 0.147 IWC 1222(A) 715 $05 Y 6A.MS600 Ih 10 VALVE3505C. R 11/91 50 1$B-M$600.1B B3 180 OAXN IWC 1222(A) 30'S PIPE TO VALVE3$0a R 06/93 e" Q ISC M$600-Ih BB 150 0.000 IWC 1222(A) 30'S PIPE TO VALVE3503. R 06/93

(/l (() 0 Ft 0

0 lf

'lI

t I ~ lL E. GINNANUCLEARPOWER PIANT laserioe Examhstha Boundary une urt Tldrd Iaspecdoa Interval

PdrID No: 33013 123 I O Chss: 3 System: MAINSlEAM Comp Type: COMPONENIS H 0 RGRE GBbert ISI Size Twas Rremptioa NDE g N IIne No. . u ~FI Metrl. ~h. ~in. Basis Metlrod Po ~Tern In? une deseri 'ennsrlrs Robed

NIA OAR OAXO NO IWA; VTD TURBINE DMVENAFW PUMP TURBINE. A IUPI H 0 M

XOX H + r H LO H tO g 5% 0 U) ( %0 H ~eHHIDE g o H 2g

M ID 0 Pe 0

0 R. E. GINNANUCLEAR POWER PIANT nsservire Examinadon Boundary Une Ust Third Inspeenon Interval

PSID No t 33013-1231 Chtss .: 3 System. s MAINSTEAM Comp Type: PIPING

ROSE GUbert SWRI ISI Size NDE Une No. Une ho. Une No. ~Fi . MatrL ~in. Method Po T~em In? Une deseri '/remarks

30A.M$600 I B.9A hll5 Ba00 l~ NO IWA, 715 505 Y VALVE3517 'IO REDUCER ATVALVE3519. A 06/93 30B.M$6fO I 8 10 hl15 3aoo 1~ NO IWA 715 505 Y VALVE3516 TO REDUCER ATVALVE351L h 06/93 8A-MV-150 I N/h &00 OAKO NO IWA AFW PUMP TURBINE EXH TO ATMOS. A 11/91 6A-M$600 I MS.120 G32 A106 &00 OA32 1085 508 Y 3505A TO 3505K TUBELIKE 6B.M$6M-I MS.120 G32 A106 &00 OA32 1085 508 Y 35IMATO 3504 IL 0 Vl 6GMS600 I MS.120 G32 h106 6lO F32 1085 508 Y 6A 8: 6B IO 3A. R II/91 4A-MV.150-1 N/A 4AO a000 IWD.1220.1 AUXFW PUMP TURBINE QUENCH TANKTO BA. A II/9I 3A.M$600 I G32 h106 &00 IL216 IWD-1220.1 1085 508 6C TO AUXFW PUMP R 11/91 g H 3B-M$600.1 B.9h Al15 &00 (L216 IWD-1220.1 715 505 VALVE3615 TO 30A.MSCi00.1. A 06/93 WO 3C M$60al 8 10 A115 &00 tL216 IWD 1220.1 715 505 VALVE3614 'IO 30B-M$600.1. A06/93 t0 ISA.M$6N I MS-120 G32 A106 MO ale IWD-1220.1 lOSS 508 3505C TO 6A R II/91 I8B-MS600.1 120 + LD M$ G32 h106 180 0.145 IWD 1220.1 1085 508 350K 'IO 6K R II/91 H H ISGM$600 I B-9A hl I5 150 0.145 IWD 1220.1 715 505 30A.M$600 I TO VALVE8527. A 06/93 ID ~ O V) ISD.MSCi00-1 B.IO A115 MO IL145 IWD.1220.1 715 505 308 M$6M I TO VALVES52L AOdr/93 W vX L u)n H H to gtDHtg g 0 H Q

IL E. GINNANUCLEAR POWER PLANT Iaservke Exautlnathn Boundary Une Ust Third InspecUon Interval

PAID No..: 33013.1231 O I2ass t HE.2 System. t MAINSTEAM H Comp Type: HF PIPINGt APP.B 0 RUBE SWRI ISI N Une u No. ~Fi . MatrL Po ~Tern tn? Une deseri remaAs

30A.M$600.1A MS 100 MS 1000 HE.I h115 3MO 1350 SUR/VOL 715 505 5/G lb TO VALVE3517. R 06/93 30B.M$600 IB MS 200 SMS 1001 HE.2A AIIS BMO 1350 SUR/VOL 715 505 5/G IBTO VALVE3516. R 06/93 H 6A M$600 lh MS 100 MS.1000 HE-IA A106 6.00 OA32 SUR/VOL 715 505 30'S PIPE TO VALVE3505A. R 06/93 6A.M$600 IB M$300 SMS 1001 HE.2 hl06 6.00 OA32 SUR/VOL 715 505 30'S PIPE 'IO VALVE35IMA. R 06/93 0 UI 6B.M$600.I A MS300 MS.1000 HE-IA A106 6.00 OA32 SUR/VOL 715 505 3IP MS PIPE TO VALVE3411. R 06/93 6B-M$600 IB MS.200 SMS 1001 HE.2 hl06 AS OA32 SUB/VOL 715 505 30'S PIPE TO VALVE3410. R 06/93 6C M$600 IA MS300 MS.1000 HF Ih h106 AS 0.432 SUR/VOL 715 505 RP MS PIPE TO VALVE3509. R 06/93 6GM$600 IB M$300 SMS.1001 HE.2 A106 600 OA32 SUR/VOL 7 IS 505 3ty MS PIPE '10 VALVE350IL R 06/93 g H 6D-M$600.IA MS300 MS.1000 HE.IA A106 6AO OA32 SUR/VOL 715 505 30'S PIPE TO VALVE3511. R 06/93 td 0 6D.MS@00 IB MS300 SMS-1001 HE 2 A106 600 sL432 SUR/VOL 715 505 30'S PIPE 10 VALVE351(L R 06/93 6E.M$400-1A M$300 MS-1000 HE.IA A106 6AS OA32 SUR/VOL 715 505 30'S PIPE 10 VALVE3513. R 06/93 + '4 ~ H 6E-M$600-I B M$300 SMS 1001 HE.2 A106 600 OA32 SUR/VOL 715 505 30'S PIPE TO VALVE3512. R 06/93 6F M$600 IA MS300 MS.1000 HE.IA h105 600 tL432 SUR/VOL 715 505 30'S PIPE VALVE 10 3515. R 06/93 O T/I OW 6EM$600 IB MS300 SMS.I OUI HE.2 AI06 6AO OA32 SUR/VOL 715 505 30'S PIPE TO VALVE3514 R 06/93 6G M$600 IA HE-IA A106 6'A32 SUB/VOL 715 505 Ssy MS PIPE 10 VALVE3521. R 06/93 R5 6G-M$600.1 B SMS.1001 HE.2 A106 650 OA32 SUR/VOL 715 505 30'S PIPE TO VALVE3520. R 06/93 H to 0 H IEI g g + u) H () H 4

M 8 0

0 R

t 'I t j Wt IL E. GINNANUCLEAR POWER PIANT Inrertdee Ezamhathn Boundary Lhe Ilrt 'IIdrd hpection Interval

PAID Na.t 33013.1231 O Char t HE3 S7rtem t MALISTEAM H Comp Type: HE-PIPING: APP-B 0 RUTE 0Bbert ISI Size Thlarr Exemption NDE No. Une No. . lhe ~Pi MatrL ~h. ~h. Baria Metlrod Po ~Tern In? Lhe dereri 'ernaritr Rcvbed 30A-MS600 I HE.IA AIIS 3IL00 I~ SUR/VOL 715 505 Y VALVE3517 TO REDUCER ATVALVE3519. A 06/93 30B-MS600.1 HE-2 A115 30.00 I~ SUR/VOL 715 505 Y VALVE3516 TO REDUCER ATVALVE351L A 06/93 H 0 M

g H WO + H tO H H3 g O EII OX xa HIE? O H + tO Q g II) H0 H g

IL E. GINNANUCLEAR POWER PIANT Insetvloe Examination Boaahsy Line List TMnIInspeenon Interval

P&ID No t 33013.1232 O Qass ..: HBO System..: MAINSTEAM Comp Type: HE-PIPINGt APP-B H 0 RG&E 151 Size TMnts Exam pdon NDE Line No. ~FI . Matrl. ~in. ~in. Po T~ern In7 Une desert rernarits

36-MS600.1 ) MS -1000 HE.7 3600 OAXO SUB/VOL 30' 36'EDUCERS TO END CAP. R 06/93 2%A.MS600 lh MS ~ 1002 HE.7A 24AO 0AID BUR/VOL 715 505 Y 36'S PIPE TO VALVE35%i. R II/91 a 2kB.MS600.1h MS -1003 HE 7h 24AO OANO SUR/VOL 715 505 36'S PIPE VALVE H Y TO 3545 R II/91 m 12A MS600-IA HE-7 12AS OAXO SUB/VOL 36'S PIPE VALVE TQ 3532. A 11/91 Q Vl 12A.MS600-13 HE.7 12'X000 SUR/VOL 36'S PIPE TO VALVE3533. A II/91

g H WO + H tO H II3 g + O Ea OX R5 II3 H H~gO g LO H H g

48 0

~, I IL E. GINNANUCLEAR POWER PLANT Inservice Ezarnlnatba Boundary lbe Ust Thhd Inspeeaoa Interval

9&IDNo r 33013 1236-1 O CLast: HFrQ System d FEEDWATER H Comp Type: HE PIPING: APP.B 0 RG&8 GEbert ISI Size Theat Exemptba NDE Lbe No. Lbe Na ~Fi . MatrL ~b. ~b. Basis Method Po T~em In? Lbe deseri 'emarhs

20 FW.900.1 FW-1001 HE6 20.00 MXO SUR/VOL 715 505 Y TEE AT3984 &3985'TO TEE AT3982 &3983 R 06/93 8 FW.900.1 FW.1081 HE@ BAI0 0.000 SUR/VOL 715 505 Y 20-FW.900.1 TO VALVE9507D. R 06/93 H 0 U)

XAg H W H+1OH 113 g E/3 (T( O (

L(3 H H~gA g LL3 H p H 'g 0-

0 CQg

M (D 0 0

0 I

f IL E. GINNANUCLEAR 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 GtTbett ISI Site Tithe Exempdon NDE Une No. Line No. ~F1 . MatrL ~in. ~ln. Basis Method Po ~Tern In? Une desert nlremarls Revised

EMS 0 IA B.l SUR/VOL 715 505 TIIISCOMP ACCOUNTED FOR ON 33013-1231. R 06/93 EMS 01 3 Bl SUR/VOL 715 505 THIS COMP ACCOUNTED FOR ON 33013-1231. R 06/93 H 0 M

L H WO

H+IOH ID'OR

HID~tD O 'Q H t3 p H g 0 p

03 8 0 0 h

\ L F GINNANUCLEAR POWER PIANT Insesskc Examlhntion Bormday Une Ust %hd Issptcthn lntcsvnl

9&IDNo-t 33013 1236-2 Cher: 2 System t FEEDWATKR Comp ~t PIPING 0 Gihtst 151 She Thhns NDE Uhe No. ~Fi . Mhtsl. ~Ih. ~lh. Method Po ~Tern Ih? Uhe dtsefl ftrhhlhs

18A.FW.900 IA 8 12 18.00 0.000 SUB/VOL S/GW TO 18 X 14 REDUCEL R 06/93 ISB-FW-900 18 8-13 IS.00 0.000 SUR/VOL S/G.B TO 18 X 14 REDUCEL R 06/93 0 1%A FW.KO.IA:- FW-1001 B.lI A106 14AO 0.93S SUR/VOL 715 505 Y 18 X H REDUCER TO VALVE3993. R 06/93 4 148 FW-900.18 FW.1005 8-13 A106 1%AS t1938 SUR/VOL 715 MS Y 18 X 14 REDUCER TO VALVE3992. R 06/93 OM

XOg H HIGH gON~ LO Q

I HeO~ H 'LO tj g ~ II) H H g iB

0) 8 0 po 0

0 E R. E.GINNA NUCLEAR POWER PIANT Insesvlee Euuainsdon OoussLssy LIne use Thlnl Iospee6oa Intesval

9&IDNo: 33013.1236.2 CLsss.,: HE-2 ~m..: FEEDWATER Comp TYpe: HE.PIPING: APP-B 0H RG&E ISI SIxe Tldms Exempchn NDE Uoe Na ~Fi . Rsvp Revisesl

1%A-FW-900.1A FW.1001 BB3 A106 1%AS 0938 SUR/VOL 715 505 Y 18 X 14 REDUCER '8) VALVE3993. R 06/93 148-FW-900.1B FW.1005 HE-4 A106 14AO 0.938 SUR/VOL 715 505 Y 18 X 14 REDUCER TO VALVE3992. R 06/93 H 0 U)

s2s H WO

HQH'LO @0M~ Q I H~OO H 'LO F/1 Q g g LO 0H H g

4Qg 0 g '1

I KE GINNANUCLEAR POWER PLANT Inservke Examinadon Bonndary Lbe Urt 'IBIrd nspeenon Interval

PLAID Ntx.s 33013.1236 2 O aass: HFrQ ~em.: FEEDWATER Comp TYPet HE PIPING: APP-B H 0 RGdrE GBbert ISI SIse Thkns Exempthn NDE Une No. Une Na ~Fi . MatrL ~in. ~in. Breds Method Po ~Tern tnt Une deseri 'emarks Robed

IIA.FW.900 1 HE3 A106 14AO 0.933 SUR/VOL 7 IS 505 Y VALVE3993 TO 20-FW.900 1. A 06/93 1kB.FW-900-1 A106 14.00 0.938 SUR/VOL 715 505 Y VALVE3992 IO 20-FW-900.1. A 06/93 0 M

AH WO

I ~ LO H H 'g goV)~ IEI I IO H HIDEO g 'LO H 0 H g 0 a

IL E. GINNANUCLEAR POWER PIANT nssaviee ~n Bonn5sry Une Ust Thni lnrpeerion Intavnl

PAID No t 33013.1237 O CLsss....: 2 .: AUXIUARYFEEDWhmt Systan H Comp TYper PIPING 0 RGAE GBbat SWRI ISI Size Lbe No. Line No. Une No. ~FI . MetrL ~in. Po ~Tern tnt Une rieseri ranerits

BA.FW-900 IA FW-1001 C IA A106 3AN 0200 IW&1222(h) 715 505 Y 4XNC TO e011, Ieh-FW.900 lb. R 06/93 3A.FINO IB FW-1005 CIC A106 3AN 0300 IWC1222(h) 715 505 Y 4NOD To e012, 1eB.FW-900-IIL R 06/93 H 3B-FW-9001 A FW.1001 C.lb A106 3AN 0300 IWC1222(A) 715 505 Y 4N3 10 4$ 5, 1 eh.FW-900 Ih. R 06/93 3B FWAXN.IB FW-1005 CIB h106 3AN (X300 IWC1222(h) 715 505 Y 4XH TO 4N6, 1eB-FW-900-IL R 06/93 0 (/)

X H Ez( 0 W V + t() H H t() g O 0)

t() 0 H H t() g g I() H p H Q 0

h3 X CQ

0 I I 'I I "'Y I

I P

«4

III

I 'I I

I L E. GINNANUCLEAR POWER FIANT Inservioe Exnsrdnadon Boundnry Une Ust TIdrd Inspeenon Interval

P&IDNo,s 33013 1237 O aass. s 3 Systesa.: AUXIUARYFEEDWATER H Comp Type: COMPONENIS 0 RG&E 08bers ISI NDE Une No. Une No. ~Fi . MatrL Method Po ~Tern Inl Lbe deseri 'emnrks

EAMI N/h OAXI 0.000 IWD 122D.I 75 80 TURBIN DRIVEN AFW PUMP LUBE OILCOOLEL A II/PI EAIO2A N/A OAXI OAXO IWD.1220.1 75 80 AFW PUMP A LUBE OILCOOLEIL A 11/91 EAIO28 N/h OAXI OANO IWD.1220.1 75 80 AFW PUMP B UJBE OILCOOLEL A 11/91 PAR) lh N/h SLOG 0.000 NO IWA 1250 100 AIDUUARYFEEDWATER PUMP A. A 11/91 CI Ul PAIDI8 N/A sLOO OAXO NO IWA 1250 100 AIDUUARYFEEDWATKR PUMP L A II/91 PAIO3 N/A SHOO IX000 NO IWA 1250 100 TURBIN DRIVEN AFW PUMP. A 11/91 g H X A

+ IO H H Ml g O Ul OX R5 Io O H Ml g + u) H o H 'g

Ol 8 n

0 C h

I l! II

I II

I IL E. G]NNANUQEAR POWER PIANT Insetvke hm]nadon Bonndaty L]ne Ust IMtd Inspee6on ]ntesva]

PMD No: 33013.]237 O Chss t 3 System: AV)QIJARYFEEDWATER Comp 1?pe: PIPING H 0 OUI>ett ISI S]ae Thkns 4 Line No. ~R. M nL Po T~em In? i)ne desesi '/semarks

SA-RV7-900.] AFW-200 Gl h]06 5.00 0375 1250 100 ? 3].FW7-900-1 TO VALVE3998, 3F-FW7-900-1 R 1]/91 58-FW7-900-1 AFW-200 G]A A]06 SAO L375 NO SUPPORIS 1250 100 ? 3F FW7-900 I IO RDCR BEPORE 4XXL R 11/91 SGFW7-900 I AFW~~ G]8 A]06 SAS IX375 hO SUPPORTS 1250 100 ? 3H-FW7-900-1 TO 3J.FW7-900 l. R 11/91 H SW-1520 4A42hl 50 ]A G33 A53 4AS 0237 hO SUPPORTS 12 80 ? VALVE4017 TQ 4345. R 06/93 F/) 4A42hl50 18 SW-1520 G33 A53 4AO a237 NO SUPPORTS 12 80 ? VALVE4016 IO 4344. R 06/93 0 LCD-)50.]C SW.]520 G]6 A53 4AS (L237 12 80 t 40]4 IO 4098, TURB AUX FW PUMP SVCIION. R 1]/91 4ASW.125-1 C33 A53 4.00 tX237 Q NO SUPPORTS 75 80 ? 20ISWO-I25-1 > 4640 IO 8> INCLIEE R 11/91 4ASW.]25 H IA C33 4AS a237 ? 4ASW-]25-1 IQ VALVES4027> 4345. R )I/9) 4ASW.]2518 N H C33 400 IX237 ? 4ASW-125-1 TO VALVES4028, 4344. R 11/91 WO K 4ASW.]25 IC G16 4.00 0~ t 16ASW0.125.], 4623 IQ 4098. A 1]/9] 3ACD-ISO. IA G33 h53 3.00 OAXS NO SUPPORTS 12 80 ? 4ACD.]50-]hIQ AFW PUMP h SVCIION. A 06/93 3A42h]50.18 G33 A53 3AS OAOO NO SUPPORTS 12 80 ? 4ACD.]50-18 TO AFW PUMP 8 SUCIION. A 06/93 +IOH '0 H M) >2> 3A-RV7~1h AFW.]00~ G]A A]06 3AS 0300 1250 100 ? 2D.FW7-900 ]AIQ VALVE4XSC R II/91 $ 3A.FW7-900 O ]8 AFW-]00,4O C.IF A]06 > 3.00 tXSIS 1250 100 ? 2D.FW7-900-18 TO VALVE4XOD. R 11/91 0 OX 38.FW7-900 I C.]D h106 3AS tL300 NO SUPPORIS 1250 100 ? 3A FW7-900-]A 'IO 4357. A II/91 3GRV7-900.1 G]E h]06 3.00 0300 NO SUPPORIS )250 100 ? 3A.FW7-900.]S IQ 4356. R 11/91 tO FW7-%0-] O 3D C)E 3.00 IL438 1250 100 ? BYPASS FROM 4357 TO 4356 THRU 4XXIA. A I]/91 H M) 3E FW7.900.1 ~ C ID A]06 SAS L438 1250 100 ? 3X-FW7-900-1 IQ 4360, 4359, SA.FW?-KO.]. R II/91 'LO H 3F FW7-900.1 C I A]06 3AO 0300 1250 100 ? SA FW?.900.1 IO 4O]> 58 FW7.900 1. R I]/91 3G.FW7-900 I C. IA A]06 3.00 0300 1250 100 ? 58 FW7-900-1 TO 4XXL R 11/91 H g CI 3H.FW7-900.1 C I h]06 3.00 0300 1250 100 SA FW7-900.1 IO 4XO, 4XI2, SGFW7-900-1. R I]/91 3].FW7-900 I Gl 3.00 tX300 NO SVPPORIS ? TURB ARVPVMP DISCHC TO SA-FW?.XO.I. h 11/91 3J.FW7 AFW-200 900 I C) 8 h]05 3AS OA3S 1250 100 ? SC FW?-900-1 TO 4004. R II/91 3K.FW7-XO I AFW.]00 C IE 3AS 0.438 1250 100 BYPASS FROM 4357 IQ 4356 THRU 4XX)]L R 11/91 2A FW74XO.]h AFW.]00 C IC A]06 2.00 0.145 1250 100 ? 3A.FW7.900-1h TO ]AFW?4XO.]A. R II/91 2A.RV7.900-18 AFW 100 GIN A106 2AO 0.154 1250 100 t 3A.FW7.900.18 IQ 4310. R 1]/91 28-FW7-900 ]A AFW-100 C.]G A]06 2.00 0.145 1250 100 ? 2A.FW7-900-]A 'IO 4482, MA.FW7-900 ]h. R 11/91 28 RV7~18 GIH 2AO 0.145 1250 ]00 ? 2A-FW74s0th]B TO 4484, ISA FW7400.HL R 11/91 2GFW7.%0.1A CIC 2AS 0.145 MA-FW74OthlhIQ 4483, 3A.FW7.900 ]A. A 11/91 2GRV7 %0.18 C IH 2.00 0.145 t ISA-FW7-900-]8 TO 445, 3A.FW7.900 1]L A 1]/91 2DRV7800.]h C IA 2AS 0.145 NO SUPPORTS ]250 100 ? AFW PVMP A D]SCHG TO 3A-FW74XXhlh. A I]/91 2D FW?.900 18 GIF 2AS 0.145 hO SUPPORTS 1250 100 t AFW PUMP 8 DSCHC IO 3A.FW?-KO IL A 1)/91 FII MA.FW7-9001 G] ]M 0.145 NO IWA ? SA-FW7-900-1 TO 4023, 429], LFW30. h 11/9] It) IJll.RV7-900.]h G]C IM 0.145 NO SUPPORIS t 28-FW7-900 ]ATO 440, 2CFW7-900.]* A 1]/91 0 Mh.RV?-900-18 GIH IM a]45 NO SUPPORIS ? 2B.FW7-900.) 8 TO 4481, 2C RV?-900-HL A 1]/91 0 R E. GINNANUCLEAR POWER PIANT Inservice hminrsnon Une List 'lirirdInspecthn~Interval

PAID No..t 33013-1238 O Qnss....: 2 t3 System t STANDBYAUXIUARYFEEDWATER H Comp T)pe: PIPING 0 RUBE GBbert ISI Site iidnrs Exemptke NDE Une No Une No. . ~F1 MntrL ~in. ~in. Basis Metlrod Po ~Tern 1n7 Line descri 'vnrusrirs Revised

3C FW-902S-lb FW.1001 C 20 A106 300 IL300 IWC.1222IA) 715 505 Y 14A.FW4CD. IATO 9706h, 9704A. R 06/93 3CFW-9025.1B FW.1005 C 24 A106 300 a300 IWC.1222(A) 715 505 Y 14B FW.900.1 B 'IQ 9706B, 9704A. R 06/93 H 0 M

g H Ls) O + tI)H H rEr +OMII) OX R5 LD H HU)gO g 'LO H0 H 2g

M tD n po 0

L F GINNANUCLEAR POWER PIANT Inservloe Eaunlnndoa IIne Lht lldrd Inspeedoa~laterral

PMD No..r 33013 1238 O CLsss: 3 Cd System.: STANDBYAUXIIJARYFEEDWATER H Comp lYPe: COMPONENIS 0 RGB E CBbert SWRI ISI She lMtns Exemptioa NDE 4 Une No. Une No. IIne No. ~Fi . MatrL ~is. ~in. Bash Metirod Po ~Tern IInl Une deseri '/remsrlts Revted

PSFO IA N/h OAXO NO IWA VT4 STANDBYAFW PUMP C. A II/91 PSFOIB N/A IXOOO NO IWA VT4 STANDBYAFW PUMP D. A 11/Pl H ~ OM ~ g Q sos H Q Cd O C HLI3<5< + O th O Cd ~HgRa HIOASW IO H HgOowe

4 A'tf

M tD n 0 I E I 'l P

4 l l

t II

El IL E. GINNANUQZAR POWER HANT Inservke Examlnadon Boundary Une Ust Tidtd Inspecdon Interval

9&IDNo: 33013.1238 Qass .: 3 System: STANDBYAUOUARYFEEDWATER Gnnp ~t PIPING 0H RG&E GBbett SWRI 151 NDE line No. Une No. Une No. ~Fi . Marti Method Po ~Tern In7 Line deserl 'emartts

4ACD.152S C2&h A106 4AO 0200 NO SURPORTS 9707h TO 4A.FW8 1525-* R 06/93 4A.FW8.1525-A G28 A106 4AO 0300 9629h TO SIBYAUXFW PUMP C SUCIION. R I I/91 4A.FWB 152S B G28 h106 4AO 0300 9629B TO SIBYAUXFW PUMP D SUCIION. R II/91 H dfKD.I52S C28A SUPPOR'IS A106 4AO 0300 NO 9707B TO eh-FW8 1525.IL R 06/93 0 F/I 3A-FWB 902S-A C.22 A106 3AO 0300 STBY AUXFW PUMP C DISCHARGE TO 970th. R II/9I 3A.FWB 902S.B C 22 A106 3.00 0300 STBY AUXFW PUMP D DISCHARGE 'IO 9704 1L R 11/91 BOFWB-9025 G23 A106 3.00 0200 3A.FW8-902S-A TO 3A.FW8-902$ K R 11/91 MAFW8 902S G22 A106 IM 0200 3A.FW&d02S.A TO LFWOL R 11/91 g H ISB.FW8.9025 G22A A106 150 0200 3A.FW8-9025-B TO LFW07. R 11/91 XO

+ tO H H UI g O M

H tO O H tO g g IO Ho H g R 'd I t'

t II

r F I a I 'I j

K I

I' IL E. CINNANUCLEAR POWER PIANT Isetxtlte Examlnathn Botmdsty Line Ust Ih(n( Inspect&a Interval

P&IDNo t 3301312391 0 aass t 3 System.: DIESEL CENERATORS H Comp IYpm COMPONENIS 0 RC&E SWRI ISI Sise Ihkns NDE Une No. line No. ~FI . MatrL ~In. Methyl Po ~Tern Int Une cieseri nlremarhs

ESWOSA C37 OAS OAXS DIESEL GEN h JACKET WATER HEAT EXCHGL R 06/93 ESW09A Nlh OAO OASO IWD.122ILI DIESEL GEN A LUBE OILCOOLEL R 06/93 FDGOI N/h OAS OAXS IWD.122shl DIESEL CEN h PRMARYBL'KL R 06/93 H FDG02 N/A OAS OAXO IWD 1220.1 DIESEL GEN A PRIMARYFIL'KL R 06/93 F/2 FDG03 N/A OAS OAXO IWD 1220.1 DIESEL GEN A SECONDARY BLTEL R 06/93 0 FOAM Nlh 0.00 OASO IWD 1220.1 DIESEL GEN A SECONDARY FILTEL R 06/93 FDGOS Nlh 0.00 OAXO IWD.1220.1 DIESEL G EN A LUBE OILBLIEL R 06/93 FDC06 Nlh 0.00 OAXS IWD-1220.1 DIESEL CEN A INTAKEFILIEL R 06/93 g H FDC07 Nlh 0.00 OAXO IWD 1220.1 DIESEL GEN A INTAKEBLIEL R 06/98 XO KDGOIA N/A 0.00 OAXS NO IWA DIESEL CENERAIOR * R 06/93 PDCOI A Nlh OAO OASO NO IWA DIESEL GEN JACKET WAIER A PUMP. R 06/93 + t() PDG02A N/A 0.00 OAXS IWD-1220.1 DIESEL GEN A FUEL OU. TRANSFER PUMP. R 06/93 H H t13 PDG04A N/A OAS OAXO IWD-1220.1 DIESEL GEN A FUEL OILPRIMING PUMP. g R 06/93 O 02 PDGOSA N/A OAS OAXO IWD 1220.1 DIESEL CEV A FUEL BOQSIER PUMP. R OIL 06/93 ( PDG06A N/A OAS OAXS IWD1220.1 DIESEL CEN A lllBEOILPUMP. R 06/93 aa PDC07A N/h OAS OAXS IWD.1220.1 DIESEL GEN A PRE.UJBE OILPUMP. R 06/93 t(3 O H PDGOB N/A OAO OAXO IWD.1220.1 DIESEL GEN A AIR STARTINC MOIQL R 06/93 H~~ g SDGOIA N/A OAO OAXS NO IWA DIESEL GEN A EXHAUST MUFBEL R 06/93 II3 H TDGOIA Nlh OAO 0.000 IWD-1220.1 DIESEL DEN A FUEL OILSIQRACE TANK. R 06/93 'go IDC02A N/A 0.00 OAXO IWD.1220.1 DIESEL CEN A COOUNG WATER EXPAhSION TK, R 06/93 H 0 TDG03A N/A OAO 0.000 IWD.1220.1 DIESEL GEN A STARIING AIR RECEIVER Al. R 06/93 IDG03B N/A OAO OASO IWD.1220.1 DIESEL GEN A STARIINC AIR h2. R 06/93 TDGOeh N/A OAS OAXO IWD-122thl DIESEL GEN A FUEL OILDAYTANK~ R 06/93

0) 9 0 r. 0

0 II

'I l N I

1 4,

a IL E. GINNANUCLEAR POWER FIANT Inserrrke Exarnlnarbn Bonndary Une Usr TIrlrdInspecdon lnterral

PMD No-s 33013.1239-1 Qass s 3 Sysrern r DIESEL GENERATORS Comp Type: PIPING 0 RQtE 0Bberr ISI She Une No. line Na ~Fi . Marrl ~b. Po T~em In? Lbe deseri remarlrs

2OA.DG.150%A N/A A53 2aoo a250 No sUPPORTB AIR INTAKEDG I* R 06/93 20B-DG- ISA C39 A53 20.00 IX2M AIR EXHAUSTDG IA. R 06/93 SA.DG-A C35 SAS 0.000 NO SUPPORTS JW.HXATQ JW PUMP A SUCT. R 06/93 SB DGW C35 5AO OAXO NO SUPPORTS JW PUMP A DISCHG TQ DGA, R 06/93 0 Ul SCDG.A C35 SAI OAIO DG-A REIIJRN UNE TQ JW HX * R 06/93 3A.IQ.1506A N/A A53 3AS a216 IWD.1220.1 DIESEL OIL SIQRAG 5 TANKTO 5955, 2'ED. R 06/93 3B-FO 1506A N/h A53 0.216 IWD 1220.1 2D TO OILTRANSFER PUMP. R 06/93 3'AS 2A.FO 1506A N/h A53 0.145 IWD 1220.1 ISA TO DIESEL OILSIORAGE TANK* R 06/93 X H 2ASA.I~A N/h A53 200 0.145 IWD 1220.1 AIR REEENERS Al!th2 TQ 5905A Br B, 5975 R 06/93 Esl O 2B-IO.1506A N/h A53 2AO 0.145 IWD 1220.1 OILllRNSFER PUMP TQ 5965 Br 5976. R 06/93 2CIO.1506A N/A A53 2AO a145 IWD 1220.1 ISA TQ 5967 Sr 5959. R 06/93 2D.IQ-1506A N/A AS3 ale IWD.1220.1 3A TO 3IL R 06/93 2'~ H Ul ~ IM-IQ.1506A N/A A53 0.133 IWD 1220.1 DAYTANKA TO 5960A, 2A. R 06/93 O M OW WASh.ISLY N/A A53 IM 0.133 IWD-1220.1 2A TQ DG-A AIRSTARTING MOTOR. R 06/93 MACAW.125-1h N/A A53 IM 0.133 IWD 122a I 5900A TO COOLLNG WATER EXPANSION TANK. R 06/93 R5 ISB-FO.150&A N/h A53 IM a 133 IWD 122aI MSATO IA. R 06/93 H LO O H ISC FO-1506A N/A A53 150 a133 IWD.1220.1 5913 TO 5909 63h. R 06/93 LO Q g ISD.IO.1506h N/h 150 0.133 IWD.1220.1 5965 TO I* R 06/93 LO H I~.fO 1506A N/h 12S 0.133 IWD.1220.1 ISB TO DAYTANKh. R 06/93 p H 2e

g 0 4 Q

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P&ID No t 33013 1239-2 O Cher t 3 Syrtern t DIESEL GENERATORS Comp IYpe: COMPONEÃIS H CI RG&E CKbert SWRI Une No. Une No. Une No. Po ~Tern In? Une dereri rernartr

ESItIOB C3$ OAO OAOO DIESEL CEN B JACKET WATKRHEAT EXCHGR. R 06/93 ESWISB N/A OAO IWD.1220.1 DIESEL GEN B WBE OILCOOIEIL R 06/93 FDGOB N/h 0.000 IWD 1220.1 DIESEL GEN B PRIMARYBLIEL R 06/93 FDQS N/h OAO OAXO IWD-1220.1 DIESEL CEM B PRIMARYFILIKIL R 05/93 OM FDGI0 N/A 0.00 0.000 IWD 1220.1 DIESEL CEN B SECOiVDARY BL'IKL R 06/93 FDGII N/A 0.00 0.000 IWD 1220.1 DIESEL CEM B SECONDARY BLIKL R 05/93 Q FDG12 N/A 0.00 0.000 IWD 1220.1 DIESEL CEN B LUBE OILBLIKL R 06/93 H FDG13 N/A OAXO IWD.1220.1 DIESEL CEN B STAKE BLIKIL R 05/93 g H FDG I4 N/A OAO OAOO IWD 1220.1 DIESEL GEM B INTAKEBLIKIL R 06/93 W 0 KDCOIB N/h OAO OAOO NO IWA DIESEL GENERAIOR L R 06/93 PDGOI 3 N/h OAO OAOO NO IWA DIESEL GEN B JACKET WATER PUMP. R 06/93 IO H PDC02B N/A OAO OAXO IWD 1220.1 DIESEL GEN B FUEL OILTRANSFER PUMP. R 06/93 H IO 'g PDCOI 3 N/A OAO OAXO IWD-1 220.1 DIESEL GEN B FUEL OILPRIMINC PUMP. R 06/93 + OFJI o F3 PDGOSB N/A OAXO IWD.1220.1 DIESEL GKN 8 FUEL OILBOOSTER PUMP. R 06/93 td PDC06B N/A OAOO IWD.1220.1 DIESEL CEN B WBE OILPUMP. R 06/93 PDCGFB N/A OAXO IWD.1 220.1 DIESEL C EM B PRE-LUBE OILPUMP. R 06/93 H II2 O PDQS N/A (uXO IWD.1220.1 DIESEL CEM B AIRSTARILVGMOTOR. R 06/93 113~ 'LO SDGOI B N/h OAO OAXO NO IWA DIESEL CEN B EXHAUSTMUFFLEL R 06/93 H IIOOI3 N/h ILL OAXO IWD 1220.1 DIESEL GEN B FUEL OILSTORAGE TANK. R 06/93 o IDG02B N/A 0.00 0.000 IWD-1220.1 DIESEL CEN B COOLING WAIKREXPANSION IK. R 06/93 H g 0 IDG03C N/A 0.00 OAOO IWD 1220.1 DIESEL CEN B STARTING AIR RECEIVER Al. R 06/93 IDQBD N/h OAO OAXO IWD 1220.1 DIESEL CEM B STARTING AIR RECEIVER A2. R 05/93 IDG04B N/A 0.00 0.000 IWD-1220.1 DIESEL GEM B FUEL OILDAYTANK. R 06/93

M 8 n 0

R. E. CINNANUCLEAR POWER PIANT Inservlte Examlnathn Bonnrhry Lhe Urt TMnI Inspection Interval

PMD No t 33013 1239-2 O aass ..: 3 System: DIESEL GENERATORS H Comp Type: PIPING 0 ROSE GBbert ISI She NDE Une No. Lhe No. ~Fi . MstrL ~h. Method Po T~em In? Lhe deseri '/remarks

20A.DC ISHB N/h A53 2IL00 0250 NO SUPPORTS VT3 AIR INTAKEDG IL R 06/93 203-DG-150eB G4) A53 20AS 0250 VT3 AIR EXHAUSTDG IIL R 06/93 H SA DG-B G36 SAIC OAXS NO SUPPORTS VT3 JW-HX-BTO JW PUMP SUCT. R 06/93 I 'IO m SB DC-B G36 SAN OAXS NO SUPPORTS VT3 JW PUMP B DISCHG DG-L R 06/93 CI Ul SC.DG-B G36 SAN OAXO VT3 DG-B REIURN UNE TO JW-HX-L R 06/93 3A.FO-1506B N/A A53 0416 IWD.1220.1 DIESEL OILSIORAG E TANKTO 5956, 2'ED. R 06/93 3'.00 3B.FO 1506B N/A A53 OA3S IWD.1220.1 2D TO OILTRANSFER PUMP. R 06/93 2A.FO 1506B N/h A53 2AS 0.145 IWD 1220.1 1$A TO DIESEL OILSTORAGE TANKL R 06/93 X H 2ASA.150' N/h A53 0.145 IWD 1220.1 AIRRECEIVERS Bl R B2 TO 5906A St S, 5975 R 06/93 X O 2'AX? 2S FO.15063 N/A A53 0.145 IWD.1220.1 OILTRANSFER PUMP TO 5966 S 5976. R 06/93 2GFO.1506B N/A A53 2AO 0.145 IWD 1220.1 1$A 'IO 5967 Bt 5960. R 06/93 + 'LO H 2D.FO 15043 N/A A53 2.00 0.145 IWD 1220.1 3A TO 3IL R 06/93 Hex 1$A.FO 1506B N/A A53 0.133 IWD 1220.1 DAYTANKB TO 5960B, 2A, R 06/93 o M 1$ASA.I~B N/A A53 1$0 0.133 IWD 1220.1 2A TO DG B AIRSTARTING MOTOR. R 06/93 1$A3W.125 IB N/A A53 1.50 0.133 IWD-1220.1 5900B TO COOUNC WATER EXPANSION TANK. R 06/93 1$B-IO 1506B N/A A53 1$0 (1133 IWD 1220.1 I~ TO IA. R 06/93 tO O H 1$C FO.1504B N/A A53 1$0 0.133 IWD 1220.1 5914 TO 5910 Ik 3A. R 06/93 HIDE g ISD.FO 1506B N/A 1$0 0.133 IWD 1220.1 5966 TO I* R 06/93 'LJ3 H IWD.1220.1 1$ 3 TODAYTANK R 06/93 p 125A.PO-1506B N/A IM 0.133 L H g

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f 4 K E. GINNA NUCLEAR POWER PLANT Inserviee Examinatbn Bonndaty Une Ust Thitd Sspeetion Imetval

P&IDNo t 33013.1245 O CLsss. t 2 td System t AtMUARYCOOLANTCXW Comp TYpe: COMPONENTS 0 RG&E ISI Size T?dtns Exempdon NDE Une No. ~FI . MatrL ~in. ~in. Basis Method Po ~Tern InI Une deserl n/remarks Revised

PACOIA 1247 410 350 THIS COMP ACCOUNTED FOR ON 33013-1247. h 11/91 PACOIB 1247 410 350 THIS PUMP ACCOUNTED FOR ON 33013.1247. h 11/91 OM

Q H WO H~g+ IO H w,O ~M O W tD HIDEO IO Hp H g 0

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D IL E. GINNANUQZAR POWER PLANT Insessloe Exnmlnnaoa Oanddtty Une Ust lMtdInspeedoa Itnesval

9&IDNo t 33013-1245 Qnss. t 3 System: AUXIUARYCOOIANTZCW COMPONKNIS H Comp Types 0 RGRE GRhett SWRI LSI NDE

Une No. U N ll N ~FI . MsttL Method

EAC01 N/h 080 OAXO IWD.I~I <275 <200 FAIIZDFUEL RAD MOhlit)R HEAT KXCHGIL A 11/91 EACOIA CAI OAO CACAO VTQ COMPONENT COOUNC WATER HEAT KXCHGR * A II/91 EACOIB ~1 OAO OAXO VTD COMPONENT COOUNC WATER HEAT EXCHGR L A 11/91 EAC02A B.109 OAX) 0AXO N/h RHR HXAACCOUNlTDIQR ON 33013-1247. A 11/91 Q M EAC02B $-109 aoo olxo N/A RHR.HX.B ACCOUNTED FOR OV 33013-1247. A 11/91 KAC04A N/A aoo 0Axo IWD 1220.1 <275 <200 S/G BLOWDOWNSAMPIZ HEAT EXCHGR A. A 11/91 EAC04B N/A OAO OANO IWD.1220.1 «275 «200 5/G SLOWDOWN SAMPIZ HEAT EXCHGR L A 11/91 EACOSA N/h OAN OAXO IWD-122a I <275 <200 PRESSURIZER LIQUIDSPACE SAMPLE HE. A II/91 XH KAQ5B N/A OAS OAXO IWD 1220.1 <275 <200 RC IZCP B HOT LEC SAMPLE HEAT EXCHGR. h 11/91 X A EACOSC N/h aoo aooo IWD 1220.1 <275 <200 PRESSURIZER STKALISPACE ShldplE HE. A 11/91 EACOSA N/A OAN OAXO IWD 122al RHR PUMP COOLER A. h 11/91 FAC06B N/h OAO OAXO IWD.1220.1 RHR PUMP COOlER IL h 11/91 H Ml g ESS04A N/A OAO OAXO IWD.1220.1 <275 <200 POST ACQDENT SAMPIZ COOLER* A 11/91 0 M KSS04B N/A aoo aooo IWD.1220.1 <275 <200 POST ACQDENT SAMPIZ COOLER L A 11/91 w, ~ KSS04C N/A 0.00 OAXO IWD 1220.1 <275 <200 POST ACQDENT SAMPLE COOLER C. A 11/91 ESS040 N/A 0.00 OANO IWD.1220.1 <275 <200 POST ACQDENTSAMPLE COOLER D. A 11/91 I-I e I PAC02A 0.00 OAXO NO IWA COMPONENT COOUNC WAlER PUMP h. R Ol/92 LO Q PAC023 0.00 OAmo NO IWA COMPONENT COOUNC WATER PUMP IL R Ol/92 III H TACOI aoo olxo COMPONENT WATER SURC E COOUNC TANK. A 11/91 H g 0

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0 t, IL E. CINNAhVCIEAR POWER PLANT Inserviee Buunlnadon Boundary Une Ust Third Inspeedon Interval

PMD No..: 33013-1245 O CLass: 3 ~em. t AIDGUARYCOOIANTASW b3 Comp I7pet PIPINC 0 ROBE GEbert SWRI NDE Une No. Une No. Une No. Method Inl

I4APCS. 1 52 CC. 100 N/h G2 14AS 0375 VTQ <150 <200 10 X 14 RDCR FROM B CC PUMP TO 10'DCRS. R 11/91 14 BAGS-152 CC 200 N/h G4 14AS 0375 VF4 <150 <200 734B IO 10'EDUCLNG ELLBEPORE 738A. R I I/91 H 14GAC5.152 CG300 N/h G6 14AS 0375 VT3 <150 <200 14'EE ATRHRHE OUILEISIQ CC PUMPS. R I I/91 IOA4CS 152 OC 100 N/A C2 IOAS 0365 VT3 <150 <200 VALVE723A TO 14 IEE, 14A R 11/91 0 V) IOBACS 152 CC 100 N/A G2 IGAS 0365 NO SUPPORIS VT3 <150 <200 VALVE723B IO 14 X 10'EDUCEIL R 11/91 IOGAC5.152 CGIOO N/h G2 IOAS 0365 NO SUPPORTS VT4 <150 <200 N'EDUCER IQ VALVE733A, CCHE * R II/91 IODACS IS2 CC 100 N/h G2 IGAS 0365 VT3 c 150 <200 14'EDUCER TO VALVE7338, OCHE IL R 11/91 IOEACS. I52 CG200 GAS N/A I 0365 VM'T3 <150 <200 CCHE A IO VALVE734A, 14 IL R II/91 X H IOMC$ 152 CG200 N/A IGAS 0365 <150 <200 14B IQ RHRHE IL R IV91 X 0 IOG*CS-IS2 CC 200 N/A G4 IGAS 0365 VT3 c 150 <200 14B IQ RHRHE A R 11/91 IOHACS.152 N/h G6 IOAS 0365 VT3 c150 <200 RHRHE B OUIIETTO 14'EE. R 11/91 +tOH 101*C$.152 N/h G6 l(LOO 0365 VT3 c150 <200 RHRHE h OUIIZTIQ N'EDUCER. R 11/91 H UI IQMCS 152 N/h G6 10.00 0365 NO SUPPORIS VT3 <150 <200 14C TO CC PUMP g A SUCIION. R I I/91 O Vl O Pd IOK.AC5.152 N/A G6 10.00 0365 NO SUPPORIS VT3 c150 <200 14C IQ CC PUMP 8 SUCIION. R IV91 IOLACS 152 CG 200 N/A G4 IGAS 0365 VT4 «150 «200 CCHE B IQ 7348, 14IL R 11/91 8A.AC5-152 CGIOO N/A G2 8AS 0365 VT3 <150 «200 CC PUMP A IO VALVE723A R 11/91 8BAC$ 152 CGIOO N/A G2 8.00 0365 VT4 c150 <200- CC PUMP B IO VALVE723IL R IV91 'Q 6A4CS. 1 52 G6 6AS 0280 NO SUPPORIS VT3 <150 <200 14C 'IQ 4G R 01/92 g H 4AAC5.152 N/A G2 4AS 0237 IWD.I22ILI <150 <200 IOC IO ACAHHX. R IV91 0 4BAC$ 152 N/A G4 4AS 0337 IWD.122sL I <150 <200 IOE IQ ACAPCP. R IV91 H g 0 4GACS.1 52 N/h G6 4AS 0337 IWD-1220.1 <150 <200 CC SURGE TANK'IO 728, 6/L R 11/91 3lWLCS-152 N/A G4 3AS IL216 IWD I22sLI <150 <200 DRAIN FROM 14 8 IO SALIPLE HES. 3BACS-1$ 2 N/A N/h 3AS 0216 IWD.1220.1 <150 <200 SAMPLE HES 'IQ 772D. R 11/91 g 0 3GACS-152 N/h G6 3AS 0216 IWD 1220.1 <150 <200 772D 'IO CC PUMPS SUCIION. R II/91 <" Q 3DAC5.152 N/h N/A 3AS 0316 IWD 1220.1 < 150 <200 CC SURGE TANKIQ 732. 3SACS.152 N/A 3AS 0216 IWD-I22ILI <150 <200 747H TO 3C A IV91 2A4CS.152 CC 240,120 N/h G4 2AS 0.1$ 4 IWD 1220.1 <150 <200 IOC IO 707h, RHR PUMP* R 11/91 2B4C$ 1$2 CG240,120 N/A N/A 2AS 0.154 IWD.1 220.1 <150 <200 2AIQ7078, RHR PUMP IL R IV91 2GAC$ 152 CG14IL180 N/A N/A 2AS 0.154 IWD-122ILI <150 <200 RHR PUMP B IQ 7088, 2D. R IV91 2D AC$ 152 CC 170,180 N/A G6 2.00 0.1$ 4 IWD-1220.1 c 150 <200 RHR PUMP A 1074lh, 769, IOL R 11/91 2E ACS 152 N/A N/A 2AS (L154 IWD.1220.1 c 150 <200 699 IQ CC SURGE TANK. R II/91 (0 2F ACS.I S2 N/A N/A 2.00 0.154 IWD 1220.1 <150 <200 CC SURCE TANK 731A. R IO II/91 ID 204CS-I 52 N/A N/h 2.00 0.154 IWD 1220.1 <150 <200 CC SURGE TANKIO 713. R II/91 n 2H4CS-I 52 N/A N/A 2.00 0.154 IWD 1220.1 <150 <200 4C IQ 823, 729. R II/91 2I.ACS 152 G6 2.00 0.1$ 4 IWD.122Q,I <150 <200 740A IQ IOL A II/91 r. 2J4CS 152 G6 2.00 0.154 IWD 1220.1 <150 <200 740B TO 14G A 11/91 0 2KACS 152 N/h 2.00 0.154 IWD 1220.1 <150 «200 CC SURGE TANKIO RCVO17. A II/91 13h AC5.152 N/A O.NS IWD.1220.1 <150 <200 3A IO VALVE747G A ll/91 LSILACS-152 N/A 130 0.145 IWD.1 220.1 <150 <200 VALVE747K IO IS, PAS COOLEIL A 11/91 I3GACS-I 52 N/A 130 0.145 IWD 1220.1 <150 <200 IS, PAS COOLERS IQ VALVE747F. A II/91 0 C

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k ' ~ ~ ~ ~ t * I At& h' I;f' IL E. GINNANUCILARPOWER FIANT lnrervke Examination Bonndary Une Lbt 'Ihlrd nrpeenon Interval

PKID No t 33013.1246-I O Clear t I Epact AUXIUARYCOOIANT~ Comp TYper COMPONLNIS 0 RGStE GBbert SWRI ISI She %Mt'xemption hDE Une No. Une No. Une No. ~pi . MatrL ~h. ~in. lhsis Method Po ~Tern In? Une desert 'ennarls Revised

PRCOIA A.7 SUB/VOL 'IHIS PUMP ACCOUNIED fOR ON 33013-1260. R 06/93 PRCOIB h-7 5UR/VOL THIS PUMP ACCOUNIED fOR ON 33013 126a R 06/93 H 0 M Q H g H R O

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P&ID No-t 33013-1246.1 O Chss t 2 Systesn t AIOGUARYCOOLANT

ECH03 N/A IWCI222(A) «275 <200 EXCESS LETDOWN HEAT EXCHANCEIL R 06/93 ECHOBA N/A aOO IWC 1222(A) <275 <200 RCP h UPPER BEARING COO(EL R 06/93 ECHOSB N/A 000 IWC 1222(A) <275 <200 RCP B UPPER BEARING OOOLEL R 06/93 H RX SUPT COOL h N/h aoo IWC 1222(A) <275 «200 REACIQR SUPPORT COOLER A. R 06/93 0) RX SUPT COOL B N/h OAO IWC 1222(A) «275 <200 REACIQR SUPPORT COOLER IL R 06/93 0

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lt R. E. GINNAhUCLEAR POWER PIANT Inseeviee Exam)nation Boandeey Une Ikc Th)n) lnspeedon )steeve)

PBID No: 330)3-1246-) (2nss: 2 $)nrem .: AIDGUARYCOOLANT4SW Comp T)pe) PIPING 0H RG&E GUbeet Une No. 1)ne No. In)

6AAG)52 CC 200 CS 6AS 0280 IWC 1222(C) 90 70 VALVE813 TO PEM 131. R OV93 6)LAG)52 CG220 GS 6AO 0280 IWC 1222(C) 90 70 PEN 130 TO VALVE814. R 06/93 6PAC6.152 CG500,$ 25 N/A G9 6AS IWQ 1222(C) <150 <200 PEN 131 TO 4D, 4)L R 06/93 H 6H.AC6 ) 52 CG$75 N/A G9 6AS 0280 Ph'G)222(C) c)50 <200 REACIOR SUPPORT COOLERS, 40 TO PEN 130. R 06/93 (/) 4A4G152 CC450 8.29 4AS (L237 IWC 1222(h) 90 70 VALVE750B IN CONT TO RDCR PEN 12L R 06/93 0 4BAG)52 CC625 MO 4AO L237 PA&1222(A) 90 70 VALVE750A 'IQ RDCR BEFORE PEN 127 IN CON R 06/93 4BAC6-)52 CC625,CC600 N/A N/A 400 0237 IWG)222(A) «150 <200 750A AT PEN 127 )0 3C. R 06/93 4DAC6 152 CC$ 25 N/A C9 4AO 0237 IWC 1222(A) <150 <200 6F IO RX SUPT COOIER B HEADERS 4LI I'e 4V. R 06/93 g H 4EAC6 ) 52 CG700 N/A N/A 4.00 L237 IWG)222(A) c150 <200 3E AT RPC A TO 3F. R 06/93 (T) A 4F AC6 152 CC 700;725 N/A N/A 4.00 0237 IWC 1222(h) c)50 <200 3F '10 PEN 126. R 06/93 4G.AC6-152 CG450 N/A 8.29 4AS 0237 IWG)222(h) c)50 <200 7508 AT PEM 'IO 3'DCR ~ 128 (30) R 06/93 + I() 4HWC6.) 52 CG525 Nfh G9 400 0237 IWG)222(h) '150 <200 6F 'IO RX SUPT COOLER A HEADERS 41 Ie 41. R 06/93 H '0 41 AC6-152 CGS25 H~g $ Nfh N/A 4AS 0237 IWG)222(A) c)50 <200 4H TO RX SUPT COOLER h. R 06/93 O (/l 4).AC6.152 CG525 N/A N/A 400 a237 IWG)222(A) <150 <200 4H TO RX SUPT COOLER R td OX h. 06/93 ( 4K-AC6.152 CG$25 N/A N/h 400 0237 IWC 1222(h) <150 <200 RX SUPT COOLER A 10 4L R OV93 41 AC6.152 CG525 N/A G9 400 0237 IWG)222(A) <)50 <200 RX SUPT COOLER A DSCHG HDRS 4K, 4U )0 6H R OV93 I() 0 4M AC6 152 CG525 N/A N/A 4.00 0237 WG)222(h) <150 <200 ~ 'LO 4D TO RX SUPT COOLER L R 06/93 ( Q 4M4C6.) 52 OG$2S N/h N/A 4AS 0237 IVI&)222(h) <150 <200 RX SUPT COOLER B )0 4(X R 06/93 u) 1-1 4OAC6.152 CG525 N/h G9 4AO 0237 IWG)222(A) c)50 <200 RX SUPT COOLER 8 DSCHG HDRS 4N, 4W TO 6H R 06/93 4PWC6-)52 Nfh N/A 4.00 0237 IW'G)222(A) c)50 <200 7578 TO P)25. R 06/93 H g 0 4RAC6-152 N/A 4AS 0237 P 'G1222(h) <150 <200 3D AT RCP 8 TO 34 75714 R 06/93 4S AC6-152 8-29 4AS 0237 IWG)222(h) c)50 <200 30 TO RCP L R 06/93 4TAC6 152 MO 4.00 0237 IWG)222(h) <150 <200 3C TO 3Q AT RCP * R 06/93 4UWC6.152 N/A 4AS 0237 PA% 1222(A) <150 <200 RX SUPT COOLER A TO 4L R 06/93 4V.AC6.152 N/A 4AS 0237 IWG)222(h) <150 <200 4D TO RX SUP)'OOLER L R 06/93 4W~)52 Nfh 4AO 0.237 IWG)222(h) <)50 <200 RX SUPT COOLER B TO 40. R 06/93 3A.AG)52 CC 220 N/A 3AO a2)6 IVi&1222(h) 90 70 PEN 125 )0 VALVE759)L R 06/93 3BAG)52 CC 220 N/A 3AO 0216 IWG)222(h) 90 70 PEN 126 TO VALVE7$9A. R 06/93 3GAG 152 CG330%CG450 8-29 3AS 0.216 IWG)222(A) 90 70 RDCR BEFORE PEN 128 IN CONT TO VAL74914 R 06/93 3GAC6.152 CC600 N/A MO 3AS 0216 IWC )222(A) <150 <200 48 )0 751h, 4T. R 06/93 3D AG)52 CG629tCG330 MO 3AO 0.216 IWC 1222(h) 90 70 RDCR BEFORE PEN 127 IM CONT )0 VAL749A. R 06/93 (/l 3D-AC6-152 CG600 N/A N/A 3AS 0.216 IWC 1222(h) <150 <200 RCP 8 )0 REDUCER AT 4I4 R 06/93 (() 3E.AC6 152 CG700 N/A G34 3AS 0.216 IWC 1222(h) <150 <200 RCP A TO REDUCER AT4E. R 06/93 () 3F-AC6 152 CC 700 N/A N/A 3.00 L2)6 IVQ )~ c)50 <200 4E )0 757h, 4F. R 06/93 31 AC6.152 CG400 NIA N/A 3.00 L2)6 )WG)222(h) <150 <200 4R TO 7578, 4P. R 06/93 k" 3).AC61S2 CC 525 N/A N/A 3AO IL2)6 IWC 1222(A) <150 <200 4H TO RX SUPT COOLER* R 06/93 0 3KAC6-)52 CG$25 N/h N/A 3.00 0216 IWC 1222(h) <)50 <200 4D TO RX SUPT COOLER L R 06/93 SMAC6 152 CC$25 NIA N/A K2)6 IWG1222(A) <)50 <200 RX SUPT COOLER A TO 4L R 06/93 3M~152 CC$25 N/A N/A 3.00 (4216 IWC 1222(A) c150 <200 RX SUPT COOLER 8 TO 4O. R 06/93 SOAC6 152 CC450 N/A 8-29 3.00 0216 IWC)222(h) <150 <200 4G )0 7518, 4S. R 06/93 0 3QAC6.152 MO BAO 0216 IWC.)222(A) c150 <200 4TTO RCPA. R 06/93 7A~)52 N/A 0.1$ 4 IWC )222(h) 90 70 PEM 124 TO VALVE743. R 06/93 2)LAG)52 N/A 0.1$ 4 IWG1222(A) 90 70 PEN 124 )0 VALVE745. R 06/93 4

lt L R. E. GINNANUCLEARPOWER PIANT Inservhe Erranhstbn Boaaday Lhe Ust 'IMrdInspeethn Intervrd

PM0 No t 33013 124th I (Cont'd) CLsss t 2 System: AIDGUARYCOOIANTCCW Comp T)rpet PIPING 0H RGBE SWRI ISI Size NDE Une No. line No. ~FI . MntrL ~h. Mrtlrod Po ~Tern In? Une deserl 'emarks

AC&-152 N/h N/A A53 2AI0 (L109 IWC.1222(A) <150 c200 4H 10 RX SUPT COOLER A. R 06/93 2JAC6 152 N/h N/h A53 2.00 0.109 ltrr0 1222(h) <150 <200 4D 10 RX SUPT GOOIER IL R 06/93 2MAG6 152 N/A N/A A53 2AXt Q154 IWC.1222(A) <150 <200 3F 10 75&A. R 06/93 H 2PWC6.152 N/A N/h A53 200 0.154 IWC.1222(A) <150 <200 4P 10 75&IL R 06/93 OM 2QAC6-152 N/h N/A A53 200 0.109 IWC 1222(A) c150 c200 RX SUPT COOLER B 10 40. R 06/93 2S-AC6.152 N/A 2'W 0.154 IWC 1222(A) c150 c 200 RX SUPT GOOIER h 10 4L R 06/93 Q ISA~ I52A S30 A53 0.145 IWC 1222(A) <150 <200 3C TO RCP h. R 06/93 H IEA.AC6-1523 N/A IW 0.145 IWC 1222(A) <150 <200 RCP A TO.75H, IM. R 06/93 g H ISAAC&.152C N/A 180 0.145 IWC 1222(A) c150 «200 IA, FIAIII TO 3F. R 06/93 WO IEA-AC6 152D N/h 150 0.145 IWC.1222(A) c 150 <200 IM10 3F. R 06/93 'IO ISBAC6152A B.29 A53 IM 0.145 IWC.1222(h) c 150 <200 30 RCP IL R 06/93 + 'Q ISB.AC6 152& N/A 0.145 IWC 1222(A) <150 <200 RCP B 10.750. R 06/93 H ISB.AC6-I 52C HLOg N/A 0.145 IWC 1222(h) <150 <200 IGWC6 152A 10 IG.AC6.152IL R 06/93 O (/) OX He( 'Q H 0

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II IL E. CINNANUCLEAR POWER PIANT lnsesvke Examlnadon Line IAst Thinl Inspecthn~Intesvai

P&IDNo s 33013.1246-1 O Qass-s 3 System: AUXKIARYCOOLANT~ H Comp Type: PIPLNG 0 RG&E CBbest ISI Sine Thkas Line No. LIne No. ~Fi . Matsl. ~h. ~in. Po T~em In? Une desesi remarhs

BANC&.152 N/A CS A53 SAS IX322 <150 «200 COMPONENT COOUNC HE TO 817> 6'EDUCEIL R 06/93 BSAC6.152 N/A C.S A53 8AO 0322 <150 <200 4Q TO 816, 14 REDUCEIL R 06/93 H 6AAC6 152 Nfh OS A53 &00 (L180 NO SUPPOR'lS «150 <200 BA 'IO 813. R 06/93 6D AC6 152 Nfh OS A53 6'280 <150 <200 814 TO 815A, BIL R 06/93 Q M 4A.AC6.152 NfA CS A53 4'L237 IWD 1220.1 «150 «200 BA TO REDUCER BEPORE 749A R 06/93 4Q4C6 152 N/A OS A53 4AO 0237 IWD.1220.1 <150 <200 CONNECIS 88, 3H, & 2L R 06f93 3AvhC&.152 Nfh N/A A53 3AO 0216 IWD 1220.1 «150 «200 4A 'IO 749A. R 06f93 3BAG&152 N/A N/A A53 3AS0 0216 IWD 1220.1 < 150 <200 4h TO 749IL R 06/93 X H 3G-AC6.152 N/A CS A53 MO 0216 IWD-1220.1 «150 <200 759A TO 762A, 8IL R 06/93 WO 3HAC6.152 N/A N/A A53 3Axs 0216 IWD 1220.1 <150 <200 759B 'IO 7628, 4Q. R 06/93 W 2AWC6.152 N/A N/h A53 2AO IL154 IWD.1220.1 <150 <200 4A TO 742A, &743 TO EXCESS LETDN HE. R 06/93 II) H 2IAC& 152 N/A Nfh A53 2'L154 IWD I22ILI <150 <200 EXCESS IETDN HE TOP 124 &745 TO 7428, 4Q R 06/93 ~ ~ LO Q g o V) OW I R5 H %O H LO ~ g g 0) H0 0

0 CQg

0 I

I R L

I '4

~ " ~ . K E, GINNANUQEAR POWER PIANT Inrerrioe ~n Borrnthrry Une Urc ThM hnapeedom interval

PAID No r 33013-12462 O Qarr r 2 SFrrerm r AUXIUARYCOOIANT~ t3 Comp COMPONENIS H T)pm 0 RGBE GUberr SWRI 51 Sire Thknr NDE No. UUnnee . Une No. Une Nm ~F1 MarrL ~in. ~in. Made Po ~Tern In? line rieaeri '/remarka

FACOBA N/A OAR OAXXJ IWC 1222(h) SAFETY INJECIION PUMP A COOLFR A. R 06/93 EACOSB N/h OAXJ OAXXJ IWC 1222(A) SAFEIY INJECIION PUMP A COOLER K R 06/93 EAGSA N/A 0.00 OAXe IWC.1222(A) SAFETY INJECIION PUMP B COOLER* R 06/93 H EAGSB N/A DAO OAXXJ IWC 1222(A) SAFEIY INJECIION PUMP B COOLER L R 06/93 0) EACIOA N/A GAS OAXXJ IWC 1222(A) SAFEIY INJECIION WMP C COOLER A. R 06/93 0 EACIOB N/A OA0 OAX0 IWC 1222(A) SAFEIY INJECIION PUMP C COOLER K R 06/93 EACIIh N/h OAJ2 OAXO IWC 1222(h) CONTAINMENTSPRAY WMP A COOLEIL R 06/93 FACIIB N/h 0.00 OAXS IWC.1222(h) CONTAINMENTSPRAY PIJMP B COOIEL R 06/93 X H PSIOI A 1262 N/A OAS OANO NO iWA 1550 200 THIS PUMP ACCOUNIED POR ON 33013 1262. R 06/93 Er( A PSIOI B 1262 N/A OAC OANO NO IWA 1550 200 THIS PUMP ACCOUNTED FOR ON 33013.1262. R 06/93 PSIOIC 1262 N/A 050 OAXXJ NO IWA 1550 200 'IHIS PUMP ACCOUNTED FOR ON 33013.1262. R 06/93 PSI02A 1261 N/A OAJO OAXJO NO IWA 205 70 THIS PUMP ACCOUNTED FOR ON 33013-1261. R 06/93 LO H d H LO PSI023 1261 N/h (LOO MOO NO IWA 205 70 1HIS PUMP ACOOUNIED MR ON 33013. 1261. R 06/93 ~ Q @ O(/l O Pd I R5 H LEJ O H U) ~ g LO Ho H Q 4

l f

P '1

A A I IL E. GLVNANUCLEAR POWER PIANT Inservice aarnlnadon Bonndary Une Ust IMrd Inspecdon Inrerval

PMD No r 33013.1246.2 O Qass .: 3 Sysrern. r AUXIUARYCOOIANTCCW H Cosnp TPPe: COMPONENIS 0 ROTE GEbert SWRI LSI Size Thhs

Une No. Une No. Une No. ~F1 . MarrL ~in. ~ln. Po T~ern In? Une descrl 'ernarlrs

EAC08A N/h aoo aooo IWD-1220.1 SAFEIY INJECIION PUMP A COOIKR A. R 06/93 EAQJSB N/h OAO OAXO IWD.1220.1 SAFElY INJECIION PUMP A COOIZR L R 06/93 H EAQSA N/h aoo aooo IWD.1220.1 SAFETY INJECIIOV PUMP B COOLER* R 06/93 EAQSB N/A OAS OANO IWD 122al SAFEIY INJECIIOV PUMP B COOIZR R 06/93 L Q TJI EACIOA N/A OAO OAXO IWD.122a1 SAFEIY INJECIIOV PUMP C COOIZR A. R 06/93 KACIOB N/A GAS aooo IWD 1220.1 SAFETY INJECIION PUMP C COOLER L R 06/93 EACIIA N/A OAO OANO IWD 1220.1 CONTAINMENTSPRAY PUMP A COOLEL R 06/93 FACIIB N/A OAS OAMO IWD.1220.1 CONTAINMENTSPRAY PUMP B COOLKL R 06/93 X H ECHO I N/h aoo 0AR0 IWD 1220.1 <275 <200 BORIC AQD EVAP DISIIIATECOOLKL R 06/93 WO N/A OAO OAXS IWD122al <275 <200 SEAL WA1KR HEAT EXCHANGEL R 06/93 ECHO'CH05 N/A OAO aooo IWD 1220.1 NON.REGENERATIVE HEAT EXCHANGEL R 06/93 +LDH ECH06 N/A aooo IWD «275 <200 BORIC EVAP EJECIOR ols 122al AQD AIR CONDEhSOL R 06/93 H LD sKs ECH07 N/h OAR 0.000 IWD 122a2 <275 <200 BORIC AQD EVAPORATOL R 06/93 +ON OX EWDOIA N/A a00 0.000 IWD.122a2 <275 <200 WASIKCAS COMPRESSOR h SEAL WATER HE. R 06/93 EWDOIB N/A OAO 0.000 IWD 122a2 <275 <200 WASTE CAS COMPRESSOR B SEAL WA1KR HE. R 06/93 RS EWD09 N/A OAS 0.000 IWD.1220.1 <275 «200 WASTE EVAP CONDENSINC HEAT EXCHGR. R 06/93 LD 0 M EWDI0 N/A OAO 0.000 IWD.1220.1 <275 <200 WASTE EVAP AIR EJECTOR HEAT EXCHCL R 06/93 HIDE g KWDI LEs H I N/h OAO 0.000 IWD.1220.1 «275 <200 WASTE EVAPORATOR DISTILATKCOOLUL R 06/93 p H g 0

0 IL E. C INNANUQEAR POWER PIANT Iaservtee ~n Boundary Uae Ust 'Ihbd Iaspee6on Interval

PIIIDNo t 33013.1246-2 O Qass I 3 System: ANOUARYCOOIA.IT~ Comp Type: PIPENC H0 RGAE GUbert ISI Slee Une No. Une No. . MatrL ~Fl ~h. Po ~Tern Inf Lbe deseri remarks

6BAC6.152 OC310 N/h G3 A53 6AN Q280 <150 <200 COMPONENT COOUNG HE 10 4C, 773. R 06/93 6GAC6.152 CC 230 N/A C7 A53 6AN 0280 <150 <200 COMP CLG HE 1O 760A tk BORIC AQD EVAP. R 06/93 6EAC6.152 CG160 H N/h G3 A53 6AN Q2IN <150 <200 4C TO COMPONENT COOLING PUMPS ~ R 06/93 6GWC6.152 CC.190,CG300 N/h G7 A53 6.00 0.280 <150 <200 BORIC AQD EVAP 10 COMP COOLING PUMPS . R 06/93 CI VI 4GAC6-152 CC 160 N/A G3 A53 4AN 0237 IWD.1220.1 <150 «200 6B TO 773, NON REGEN HE, 778, 6E. R 06/93 3PWC6 152 CC 230 N/h G7 A53 3.00 Q216 IWD 1220.1 <150 <200 6C TO 2'EDUCER BEFORE 764A, 2T. R 06/93 2ILAC6.152 CG250 N/A G3 A53 2AXI 0.154 IWD 1220.1 <150 <200 6B 10 7778. 777C R 06/93 2GAC6 152 CC 260 N/A G3 A53 2AN Q154 IWD 1220.1 «150 <200 CS PUMPS h Ik B IO 6E. R 06/93 rEs H 2DAC6152 CG300 N/A G7 A53 2AN 0.154 IWD.1220.1 c 150 <200 DISIILIATECOOLER TO 7488, 6G. R 06/93 fvf O 2EAC6-152 CG230 N/A G/ A53 2AO Q154 fWD.1220.1 <150 <200 6C TO DISIIUATECOOLEIL R 06/93 2GWC6 152 CG270 N/A G3 A53 200 0.154 IWD.122Q <150 I c200 68 IO Sl PUMP COOLERS. R 06/93 + tfy 2HAC6 152 CG230 N/A C7 A53 2AXI IWD.1220.1 H Q154 <150 c200 llIO 6G. R 06/93 H tfy 2KACIL152 CG320 N/h G3 A53 2AN 0.154 IWD 1220.1 <150 c200 PUMP COOIERS g SI TO 7~6K R 06/93 0 ffl o F3 2N~152 CG310 N/h G3 A53 2AXI 0.154 IWD 1220.1 <150 c200 68 1O 763, SEAL WATER HE. R 06/93 2OAC6-IS2 OC 230 N/A Gy A53 2AN 0.154 IWD 1220.1 <150 <200 WASIE EVAP CONDENSING HE 1O 7648,60. R 05/93 2R4C6-152 R5 CG160 N/A G3 A53 2AN 0.154 IWD-1220.1 <150 <200 SEAL WATER HX'IO 6E R 06/93 H ID 0 H 2TWC6 152 N/h 2AN 0.154 fWD.1220.1 <150 <200 3P TO 764A, EWD09. R 06/93 kD g g ISD AC6 152 N/A N/A A53 Q145 fWD.1220.1 <150 <200 3P 1O CAS COMPRESSOR HE IL R 06/93 kO H ISEAC6 152 N/A N/A A53 ISO 0.145 IWD.1220.1 c 150 «200 CAS COMPRESSOR HE B 1O 2H. R 06/93 'go ISP.AC6 152 N/h N/A A53 ISO 0.145 IWD 1220.1 c 150 <200 3P TO GAS COMPRESSOR HE* R 06/93 H ISO AC6-152 N/h ISO 0.145 IWD.1220.1 <150 <200 GAS COMPRESSOR HE ATO 2IL R 06/93

«" 8 g

0 0

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H R. E. CINNANUQZAR POWER PIANT Inservice ExamhaUon Boundary Lhe Ust Tbbd tnspenhn Interval

PddDNo r 33013.1247 O Qass .: I System r AUXIUARYCOOIANT-RHR H Comp Type: PIPLNC 0 RUBE CBbert SWRI ISI She 'Ibkns Exemption NDE Une No. Une No. Une No. ~Fi . Matrl ~In. ~In. Basis Method Po T~em ln7 Une deseri 'emarks Revised

10A-AC/.2501% A.IS A376 1a00 IAXIC SUR/VOL Y RHR FROM VALVE700 TO 701. A 06/93 10A-AC7.2501 B A-14 A376 10AIC 1.000 SUR/VOL Y RHR FROM VALVE720 TO 721. A 06/93 0 M

XH WO

'LO H H tI3+ 0 gOM~ O bf I R5 H~~> U7O tI7 H0 H g

M 8 0 Ft Pe 0

0 ILE. CINNANUCLEAR POWER PIANT Insertdee Euuninatkut Boundary Une Ust 'T?dtd Inspecnon Interval

PMD No t 33013 1247 Qass t 2 Systetn t AIUGUARYCOOLANT RHR Comp 1)tpet OOMPONENIS

RCtkE Gobett &VRI ISI NDE Une No. line No. line No. ~Fi . Matrk Method Po ~Tern In? Une deter( 'emarks

CONTAINSUMP B RHR400 N/A aoo aooo IWC 122 lg) h%. <200 CONCRETE SUMP EXEMPT FROM EXAMINAIIOXL R 11/91 EAC02A 1247 B-109 o.oo a Goo 410 350 RESIDUALHEAT REMOVALHEAT EXCHGR* R 11/91 H FAC02B 1247 B-109 om aooo 410 350 RESIDUALHEAT REMOVALHEAT EXCHGR L R 11/91 FACOSA N/A OAO OAXO IWC 1221(A) RHR PUMP COOIER * h II/91 Q (/) FAC06B N/A aoo aooo Iwc.1221(A) RHR PUMP COOLER L h II/91 PACOIA 1247 B-23 aoo aooo 410 350 RHR PUMP A, MFG PAQFIG R 11/91 PAGO IB 1247 B-28 aoo Oixe 410 350 RHR PUMP B, MFG PAQFIG R 11/91 XOX H + HIOgtO H O (/) HeO H (/) tO Q g LO H g 0 H 'g

0) (D ft0 0 5

I 4

'I Ill

P l

I II IL E. GINNANUCLEAR POWER FIANT Insaviee Esutminsrion nounthsry Une Uss Ilr(nlI spection Intavel

P&ID No: 33013.1247 Chss: 2 System: AUXIUARYCOOIANT.RHR Comp I)rpe: PIPING

RG&E GUbal SWRI In'? Une No. Une No. Une No. Po ~Tern Une desai rernsrte

IO.AC601 IUIR.100 IO.RH.2013 8-17 A312 IOASO (L365 BUR/VOL 350 350 Y V720 TO REDUCER 10 X 6 BEFORE VALVE717. R II/91 10hkC601 RHR~ 10 RH.2001 8.22 A312 IOA)0 L365 BUR/VOL 410 350 Y VALVE701 IHRU PEN PI40 10 IST TEE. R II/91 108kC601 RHR~ IO.RH-2001 8-20 A312 10.00 L365 SUR/VOL 410 350 Y 10"IEE FROM 10hkG601 '10 VALVE856. R 11/91 IOGAG601 BHR~ IO.RH-2004 8.20A A312 IOAN IL36$ SVR/VOL 350 350 Y IEE ON IODkG601 10 RHR PUMP * R 11/91 0 M IUD.AG601 RHR400 IO.RH-2004 8-20 A312 IOAO 0265 SUR/VOL 350 3$0 Y TEE ON IOA-AG601 TO RHR PUMP L R 11/91 IOEkC601 RHR400 IO.RH.2003 8-20 A312 ISAX) (L365 SUR/VOL 350 350 Y IEE ON IODkG601 IQ VALVE850L I0EEkGI 5 I RHROOD 10 RH 20C8 8-20 A312 IOAC 0365 IWG 1221(F) 350 350 Y VALVE850B 10 1 ST REDUQNG EIBOW. R I I/91

IOG*G601 BHR~ 1051.2010 8-20A A312 IOAe 0365 SUR/VOL 350 350 Y VALVE8$0A PAST IKE'IQ IOC AG601 ~ R 11/91 XH IOGGkC.151 RH ROOD 1081-2010 8-20A A312 IDAN 0265 IWC 1221(F) 350 3$0 Y VALVE850k TO 1 ST REDUQNG ELBOW. R II/91 RO ION.AG601 BHR450,BHR.400 IO.RH.2007 8-24 A312 10.00 0965 SUR/VOL 410 3$0 N CONI'. OF SBkC601 RED EIBOW 10 TKE. 8 AG601 BHR~ B.RH-2010 8-26 A312 SASO 0922 BUR/VOL 350 3$0 Y IO.AG601 IEE.RED IEE PAST HVG624 10 + U) H d 8AkG601 BHR~ 8.RH.2010 8-26 A312 LOO 0922 SUR/VOL 350 350 Y 10 X 8 REDUCER IQ RESIDUALHEAT EXCHA. HIA) g 88-AC601 BHR450 8-23 A312 0922 BUR/VOL 410 3$0 N D5CHC RHR PMP A 10 1ST REDUQNC KUSOW. +OM O Pd 8CAC601 RHRO$0 8 RH.2008 A312 SAN L322 SUR/VOL 410 350 N 10'KE ON IOHkG601 TO RH EX IL 8DkG601 RHRO$0 8.RH.2008 8.23 A312 SAN (L322 SUR/VOL 410 350 N D5CHG RHR PMP 8 10 1ST TEE AFIKRV710B 'Q SE.AG601 RHR~ 8.RH.2017 8-24 A312 LOO 0922 SVR/VOL 410 350 Y REDUCER BEPORE VALVE714 10 RH HT KXA. H 0 SpkGISI RHR~ 8$1 2012 8-20A A312 8AS (1500 IWG1221(F) 350 350 Y VALVE851A 10 RED ELBOW BYVALVE&50A. R 11/91 SFFkG151 RHR~ 851.2009 B20 A312 LOO 0500 IWG1221(F) 350 3$0 Y VALVE851B 10 RED ELBOW BYVALVESSOL R 11/91 IO H SEE-151 Sl 151 8-19 A312 SAN 0.14S SUR/VOL Y 6 X 8 REDUCER ON 6GSI.151 10 S X 10 REDUCEL R 06/93 p SXkC601 RHR~ 8 RH-2018 8-26 A312 LOO (L322 SUR/VOL 410 350 RES HEAT EX B 10 8 X 8 X 6 REDVCKR IKE. 0 6kG601 RHR-100 6 RH-2015 817 A312 6Am 0280 BUR/VOL 350 350 Y VALVE852h 10 IO.AC601 IN CONT. 6A.AG601 RHR.100 6 RH4016 818 A312 6Am 0280 SVR/VOL 350 350 Y VALVE8528 TO 10kG601 IN CONT. 68kG601 RHR~ 6-RH.2012 8-25 A312 600 (L280 SUR/VOL 350 350 Y 10kC601 10 IOHkC601. R II/91 6GAG601 RHR~,RHR450 6-RH-2014 B27 A304 6Am 0280 SUR/VOL 410 350 Y 8AkC601 10 VALVE857C. R 11/91 6CSI-151 819 6.00 OAXN BUR/VOL VALVE857C 10 6 X 8 REDUCER . R 06/93 6DkG601 RHRA$0 6 RH.2011 8-26 A312 6Am (L280 SVR/VOL 410 350 Y 8X.AC601 IQ VALVE857L R 11/91 6DSI.151 8.19 MO OAXN BUR/VOL VALVE857B 10 6 X 8 'IKE . R 06/93 6E AC 151 RH ROOD 6$ 1.2011 8.21 A312 SAN 0.134 IWG1221(F) 350 350 N 10'EE ON IDEE.AC 151 TO VALVEIS IBL R 11/91 6XkC 151 BUR~ 6$ I.2014 8-21 A312 6.00 0.134 IWG1221(F) 350 3$0 N 10'EE ON IOGG.AC 151 TO VALVEIS13A. R 06/93 6LACSOI 8 168 6.00 0280 SUR/VOL 4GAG601, IS16B 10 1816k, 4CSMOI R 06/93 4hkC601 8-20 4Am OAXN IWC 1221(A) 108-AC601 10 4 X 3 RDCR ON 3A AC601. A 11/91 M 4C AG601 8.168 4Am OAXN IWG1221(A) 410 350 6CkG601 10 VALVE1816L R 06/93 (D 3A.AG601 8-26 3Am IWC !221(h) SX*G601 TO 4 X 3 RDCR ON 4A.AG601. A 11/91 () 38 AG601 8.27 3Am OAXO IWC 1221(A) 6GAG601 10 4A.AG601. A 11/91 ct 2kG601 8-20A A312 2Am 0.109 IWC 1221(A) 410 350 IOA-AG601 10 VALVE252. R 11/91 2hkC601 BHR~,RHR~ 8-25 A312 2.00 0.154 IWG1221(A) 350 350 Y 10-AG601 10 IOB.AG601. 0 2B.AG601 RHRO50 8-24 A312 KDO 0.154 IWC 1221(A) 410 350 N SC AG601 '10 VALVE1812A. 2GAC4l RHR~ 8.24 A312 2Am 0.154 IWC 1221(A) 410 350 N SKAG601 TO VALVE1812L 2F AG601 CVC.IOO 8 17 A312 2A)0 0.154 IWC 1221(A) 350 350 Y 10-AC601 10 VALVE702, 2FQI401. R I I/9I RHEA.2AkC601 8-109 A312 2DO 0.'I 54 IWG1221(A) 410 350 RESIDUALHEAT EXCH. h 10 VALVE807G R 11/91 0 RHEA-28kGSO I 8 109 A312 2.00 0.154 IWG1221(A) 410 350 RESIDUALHEAT EXQL h 10 VALVE807D. R 11/91 RHEA-2C AG601 8-109 A312 228 0.154 IWC 1221(h) 410 350 RESIDUALHEAT EXCH. A 10 VALVE807F R 11/91 RHEB.2A.AG601 8.109 A312 2AN 0.154 IWC.1221(h) 410 350 RESIDUALHEAT EXCH. B TO VALVE8078. R II/91 IL E. GLWANUCIZARPOWER PLANT lnsetrice Exandnatioa Boundaty LIne ust 'IIdrd Inspection Intetval

PIHD No..: 33013.1247 (Cote'd) (2ass t 2 System: AUXIUARYCOOLANT.RHR H Co PTYPes PIPING 0 ROTE GBbett SWRI ISI Exen ptxnt LIne No, LIne No. IIne No. ~FI ~ MstsL B M~M po ~T~

RHEB-2BAC601 8-109 A312 2'L154 IWC 1221fjg 410 350 RESIDUALHEAT EXCH. B TO VALVE807F. R 11/91 RHEB-2CAC601 8.109 A312 2.00 0.154 IWC 1221(A) 410 350 RESIDUALHEAT EXCH. B TO VALVE8070. R II/91 H 125A-AC601 8-24 125 IL000 IWC 1221(A) 10H

g H (x) A

H+IOH IO g + O(/) (x) 5 % H H~gO g IE) pH 0

M (D n po 0 I

II I L E, GDINANUQEAR POWER PIANT hservke Erosmhsrha Botmdnry Lhe Ust Third speetioa hatererrI

P&IDNo-t 33013 1248 O Qsss.: 3 Systera t AIDOUARYOOOUNGSPENT FUEL H Comp IFPe: COMPONENIS 0 RG&E ISI She NDE Lhe No. ~Ff . MntrL ~h. Method Po ~Tern Inl LIne desert remnrtts

EAC13 N/A 0.00 IL000 IWD 122tL2 <275 <200 SPENT FUEL POOL HEAT EXCHGR IL A 11/91 PAC07B N/A OAN OAXO IWD 122sX2 <275 <200 SPENT FUEL POOL REQRC PUMP L A 11/91 TAC03 N/A OAR 0.000 IWD-122tX2 <275 <200 SPENT FUEL POOL A 11/91 0M Q g H WO + '4 H H +0MM7 g

t17O MIO+H ~ 'LO 0H CN H 'g 0

M 9 0

I 0 II I

'8 t ,'1

1' rI

I IL E. GINNANUQZAR POWER PIANT Insaviee Ensminstba Bonrsbry Uae Ust TMrd Inspection Intavnl

P8tID No t 33013.1248 n Qsss .: 3 Systan t AUXHJARYODOUNGSPENT FUEL Comp PIPING T7pe: Q RGRE 151 Slee Takes Lbe No. ~FI . MetrL ~b. ~b. Po ~Tern In7 Lbe deseri remarks

8AAC&151$FP N/A 8AO OANO IWD.122IL2 <275 <200 SFP PUMP IL A II/91 8&AC&151$FP N/A 800 tX000 IWD 122IL2 <275 <200 6C 1O SPENT FUEL POOL HE IL h II/91 8CAC&ISISFP 8AXI OAXO IWD12202 N/A «275 <200 SPENT FUEL POOL HE B 1O 6D. A II/91 m 6A~I5 1 SFP N/A 6A6 IX000 IWD.12202 <275 <200 8A IO VALVE8662. h II/91 Q Ul ~ 6BAC8 151$ FP N/h 6AO OAXO IWD.I22sX2 <275 <200 8A 1O VALVE865L A II/91 6OAC&151$ FP N/h 6AO 0.000 IWD.122sL2 «275 <200 SPENT FUEL POOL REQRC PUMP B TO 8IL A 11/91 g Q 6DAC&151$IP N/A 6AS OAXS IWD 12202 <275 «200 8C TO VALVE8663, 6E. A 11/91 6EAC8-151 N/A 6.00 OAXS IWD 122IX2 <275 «200 6D 'IO SPENT FUEL POOL A 11/91 gH'g 4h.AC8-151 N/A 400 0AXXI IWD-1220.1 SPENT FUEL POOL TO 4'ALVE782 A 11/91 XO'Z 4BAC8.151 N/A 400 OAXO IWD 1220.1 SPENT FUEL POOL 1O

UI tD 0 0

0 4

II IL E GINNANUCLEAR POWER PIANT Insenrlot ~n Boundary Une Lbt TMtd lnspecfion Interval

P&ID No t 33013.1250 I O Qass t 2 System t SERVICE WATER H Comp ~ COMPONENTS 0 RG&E 0Ebett SWRI Size TMms IAne No. IAne No. Line No. ~tn. ~in. Po ~Tern In? Line dcsefi remarks

PSIOIA 1262 N/h OAO OAXN NO IWA, 1550 200 THIS PUMP ACCOUNTED FOR ON 33013.1262. R 06/93 PSIOI B 1262 N/A OAN OAXN NO IWA 1550 200 THIS PUMP ACCOUNTED FOR ON 33013 1262. R 06/93 H PSIOIC 1262 N/A DAN 0.000 NO IWA 1550 200 'IHIS PUMP ACCOUNIKDFOR ON 33013 1262. R 06/93 0 M Q H g H WO + '4 HMIgH O FAT OW wa L M3n H H LOS g Q 0H H g 0

(0 8 0 Ft 0 k

d'i R E. GINNANUI2KARPOWER PIANT Inserviee Rammed Bonndary Une Ust Third Inspectha Interval

PBID No: 33013.1250.1 0 Class r 3 t3 System: SERVICE WATER H Comp Types COMPONENTS 0 RQkE 0Eber! SWRI ISI Sian TIdms NDE Une No. Une Na ~in. ~In. Metlsod Po T~em In? line deserI 'emarirs

AAAOIA N/h OAO OAXO IWDI2sXLI CHARGING PUMP A AIRCOOLKL R 06/93 AAAOI8 N/A OAO OAXXI IWD 1220.1 CHARGLVG PUMP B AIRCOOLEL R 06/93 H hhh02A N/A OAO OAXS IWD-122LI RHR PUMP A AIRCOOLKL R 06/93 hhh028 N/h OAO OAXO IWD 1220.1 RHR PUMP 8 AIRCOOIKIL R 06/93 0 F/I AAA03A N/h OAXI OAI00 IWD.1220.1 SAFEIY INJECIION PUMP A AIRCOOLEIL R 06/93 AAA038 N/A IGLOO OAXO IWD-1220.1 SAFKIYINJECIION PUMP 8 AIRCOOLEIL R 06/93 Q AAA03C N/A IGLOO OAXO IWD122IXI SAFEIY INJECIION PUMP C AIR COOLEIL R 06/93 AAAOS N/A OAO OAXO IWD 1220.1 PENETRATION AIR(XRLEIL R 06/93 g H ESW08A C37 0.00 0.000 THIS COMP ACCOUNTED FOR ON 33013-1239. R 06/93 X 0 ESW088 C38 0.00 0.000 THIS COMP ACCOUNIKDFOR ON 33013.1239. R 06/93 t0 ESW09h N/A 0.00 0 AXE NO IWA THIS COMP ACCOUNTED MR ON 33013.1239. R 06/93 + II3H ESttT68 N/A DAO OAXS NO IWA THIS COMP ACCOUNTED MR ON 33013-1239. R 06/93 PSWOIA HIDE OAIO OAXO NO IWA SERVICE WATKRPUMP A R 06/93 O F/I PQVOI8 OAO OAXXI NO IWA SERVICE WATER PUMP L R 06/93 PSWOIC OAXI OAXO NO IWA SERVICK WATER PUMP C. R 06/93 R5 PSÃ01D OAO OAXIO NO IWA SERVICE WATER PUMP D. R 06/93 HegII3 0 H 'Q g Ho H g 0 II

'! K

/ 8 IL E. GINNANUCLEAR POWER PLANT Insersioe Exasnination Bonsahuy Une Us! Thinl Inspeesion Isnerval

P&IDNo s 3301312501 Chss —s 3 Syssesn s SERVICE WATER Cosnp Types PIPING H 0 RG&E Une No. Po These In? Une desesi sesnarks

20ASWO.125.9 C17 0375 IWF-123g- 75 80 t 20E TO 20F, 4665 (BURIUED). R 06/93 20SSWO.1289 G17 20Am 0375 IWF-1230 75 80 ? 20C TO 20H (BURR!ED). R 06/93 20ESWO 125 I G17 20AO 0375 ? 14A, 14B IQ 20A. R 06/93 H 20FSWO 125-1 G12 20.00 0375 2 20A TO 4616, 4610. R 06/93 20CSW0.125 I C 17 CI (/) 20.00 0375 ? 14C, 14D IQ 20IL R 06/93 20HSW0-125.1 C.12 X td 20.00 0375 ? 20B TO 4615, 4779. R 06/93 20ISWO.125-1 C.16 20.00 0375 ? 20B TO 4640, 16A. R 06/93 16ASWO.125 I SW.1850 C 16 16.00 0375 75 80 2 16C IO 4623, 20I. R 06/93 16SSWO.1 25-9 SW.1850 G13 XH 16.00 0375 IWF-1230 75 80 ? 20B TO 6A (BURIUED). R 06/93 W A 16GSW0.125-9 SW.1500 C16 IMO 0375 IWF 1230 75 80 ? 20A TO 16A (BURRIED). R 06/93 16DSWO 125.1 SW.1500 C 16 IMO 0375 75 80 2 201 IO 14E. R 06/93 V 14ASW0.125 I C 17 + M) 14Am IL375 75 80 2 SERVICE WATER PUMP A TO 20E. R 06/93 H 14BSWO.125.1 C 17 HIE) 14AO 0375 75 80 SERVICE WATER PUMP B TO 20E. R 06/93 g 14CSWO.125-1 + O(/) C17 14AN 0375 75 80 SERVICE WAIER PUMP C TO 20G. R 06/93 14DSWO-125-1 C17 0375 75 80 t SERVICE WATER PUMP D IO 20C. R 06/93 14ESVt0125.1 SW.1500 Ra G16B 14'4'4Am 0375 75 80 2 16A IO 4627 6IL R 06/93 'N 14KSVQ 125-1 SW.1400 G13 0 H 0375 NO SUPPORTS 75 80 t 4665 TO 4A, IOIL R 06/93 H LDQ I0BSWO.125.1 G13 0) g IOAS 0375 75 80 ? 14K IQ 4613. R 06/93 'LO H 8ISVQ.125-1 SOO g CD (L327 75 80 ? 20E IO 4609. R 06/93 0 6ASVQ 125.1 SW.1850 G13 MO 0280 NO SUPPORTS 75 80 ? 16B TO 4668B, 4l. R 06/93 H g 0 6GSW0.125-1 G13 6AO 0280 75 80 2 4C, 4 E TO 10'EDUCER . R 06/93 4ASWO.125.1 SW.1850 G13 4.00 0337 IWD-IZKLI 75 80 t 14K TO DIESEL C ENERAIQR A COOLERS. R 06/93 4CSW0.125.1 C13 4AS 0.237 IWD.1220.1 75 80 t DIESEL G ENERAIOR A COOLERS 'IQ 4671, 60. R 06/93 4ESVQ 125.1 C-13 4AO 0.237 IWD 1220.1 75 80 ? DIESEL C ENERAIQR B COOLERS 'IQ 4672, 6G. R 06/93 4ISWO 125-1 G13 400 0.237 IWD.1220.1 2 14K IO DIESEL GENERATOR B COOLERS, 46688 R 05/93 4LSWO 125-1 C 17 400 0.237 IWD-IZKLI 2 14B IHRU 4612, 4611 IO 14G R 06/93 3ASWO 125 I N/A 3.00 0.216 IWD 1220.1 75 80 ? 41 IQ 4668F. R 06/93 3CSWO-1 25.1 Nlh 3Am 0316 IWD 1220.1 75 80 ? 4A IO 466?F. R 06/93 3DSViO 125.1 C.12 (F16 IWD-1220.1 75 80 ? 20F TO 4739, 4769. R 06/93 3ESWO.125 I 3'Am G12 (L216 IWD.1220.1 75 80 ? 20H IO 4738, 4754. R 06/93 3FSWQ.125 I GlI 3AN 0.216 IWD.IZKLI 75 80 t 4753 IO 4739A, 47398, DISCHARGE CANAL R 06/93 13ASVQ 125-1 N/h 130 0.145 IWD IZKLI 75 80 3D IQ 51 GOOIER 3, 3F. R 06/93 0) 13GSWIL125-I (D N/h 0.145 IWD 122ILI 75 80 ? 3D IQ Sl COOLER I, 3F. R 06/93 'I 3ESI5Q-125-1 N/h 130 0.145 IWDI220.1 75 80 ? 3D TO 51 COOLER 2, 3F. R 06/93 0 13FSV Q 125.1 N/A 130 0.145 IWD 1220.1 75 80 2 3D TO PEN COOLER, 3F. R 06/93 135ASVQ.152M r. N/h 135 0.000 IWD.1220.1 ? 4789, 4790 TO .75A, 51 PUMPS. R 06/93 135SSWQ 152M 0 N/A 135 OAXN IWD1220.1 ? Sl PUMPS, .75A IO 3f. R 06/93 4 lI

~ ~ 4 ~ ' 4 IL E. CINNANUCLEAR POWER PIANT Inserrrice Exnminntion BoundnrF LIne ust Tldrd InspeetNn Intervni

P&ID No t 33013 1250.2 A Qass t 3 SFstern r SERVICE WATER

Comp Tamper COMPONENIS H 'g0 RG&E CBbert NDE LIne No. Lbe No. Method Po T~em IIn7 IIne deseri 'nrnnrlrs

AFAOIA N/h 0.00 OAXS IWD IX/0.1 STANDBYAFW PUMP ROOM COOLING UNITA. R 06/93 AFAOI3 N/h OAS OAXSO IIVD1220.1 STANDBYAFW PUMP ROOM COOUNC UNITIL R 06/93 ~ EACOIA O41 IGLOO OAXO THIS COMP ACCOUNTED FOR ON 33013-1245. R 06/93 H EAOOIB O41 OAQ OASOO THLS COMP ACCOUNTED FOR ON 33013-1245. R 06/93 F/I ~ FAC12 N/A 0.00 ILOOO IWD 12202 <275 «200 STANDBYSPENT FUEL POOL HEAT EXCHGR. R 06/93 0 EAC13 N/A IGLOO OAXS IWD.12202 <275 <200 THIS COMP ACCOUNTED FOR ON 33013-1243. R 06/93 EACI4 OAXr OAXS IWD-12202 <275 <200 QQ SPENT FUEL POOL HEAT EXCHCR h. R 06/93 't3XHRQ H WAR tC P g LI3 H ) 5 s=s Ul Pa n ta I W td U LO H g Q g LI3 H HQ00 e Cr

0 '

H h I IL E. GINNANUCLEAR 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 0H RUBE Gilbat SWRI ISI Slee Lbe No, Une No. LIne No. Fli). )4sttL ~h. Po T~em lnt

125.12 SW-1120 20CS)t0 N/A A53 20.00 IL375 /5 80 t 12A, 128 10 BURRIED DLSCHG SIRUC R 06/93 4 20DSWO 125 I SW.)100 C 11 A53 20AO IL375 75 80 ? 14F, 14G 10 BURRIED DISCHARGE, R 06/93 18ASSIL)25 I SW.1000 C 12 A53 18.00 75 80 ? 20F 10 141, 6C R 06/93 16ESWO.)25.1 Fi C 12 16.00 0075 NO SUPPOR'IS t 4610 TO 20K R 06/93 14FSWO SW-) Q M 125 ) 100 C.l ) A53 14.00 IL375 75 80 ? CCHE A 10 20D. R 06/93 125.1 14GSWO SW.)100 C 11 A53 14.00 a375 75 80 ? CCHE B TO 20D. R 06/93 14HSWO ) 25 I SW.)000 C 12 A53 14AO 0975 75 80 t 20H TO CCHE IL R 06/93 14)SWO 125.1 SW.)000 C.)2 '? A53 14.00 0975 75 80 18A 10 CCHE* R 06/93 Q H I?TWO 125 12 N/A 12AO 0275 IWD.)22sL2 ? CCHE h 10 20C R 06/93 WO 12SSW0.125.12 N/h 12AO 0975 IWD.)22sL2 ? CCHE B 10 20G R 06/93 12CSVIL)25-I N/h )2AO 0375 IWD.)2202 t )OD TO SFPHE L R 06/93 + 12DSV9.125.1 N/A 12AO 0375 IWD-122')2 t SFPHE B 10 IOE. R 06/93 LE) H 10DSVIL)25-I C 12 )MO L375 IWD 122tL2 ? )4H 10 12C. R 06/93 H~g 5M 10ES)AIL') O F/) 25 I C)1 IMO sL375 IWD 12202 ? 12D 10 14F. R 06/93 6CStt)L)25-I SW.1020 C 12 A53 600 sL280 IWD 12202 75 80 t 18A 10 SFPHE A. R 06/93 6DSWO.) 25.12 SW.)120 11 C A53 6AO IWD)22sL2 75 80 ? 6E 10 20C. R 06/93 )13 6ESV)L125 SW-1120 0 I C 11 A53 6AO IWD-122Q2 75 80 ? SFPHE h TO 20D (DISCHARGE). R 06/93 ~ )Es 6FSWO.)25.12 Q C 11 A53 6AO IL280 IWD.)22IL2 75 80 ? 20D TO 8686. R 06/93 tA) H 6ISVO 125.1 C.)2 6AO IL280 IWD 1221)2 ? 14) 10 8687. R 06/93 o 4 TWO 152S C 27 A53 400 IL237 IWD.1220.1 75 80 ? 14H 10 96268, 96278. IL 9629)L R 06/93 H g 0 4GSWO 152S C 26 A53 4.00 IL237 IWD 1220.1 75 80 ? 20F 10 9626A, 9627A, IL 9629A. R 06/93- 4KSWO 152S G29 A53 400 0.237 IWD 1220.1 75 80 ? 4F 10 9628A, 96288, 4G. R 06/93 3BSWO 125 12 C I) A53 3.00 0.216 IWD-1220.1 75 80 ? 3F 10 6D. R 06/93 XSESWO.)25 I N/A %SO 0~ WD-)220.1 ? 12D TO 8633, 8634, 10E. R 06/93 2ASWO.)52S C.I ) A53 2.00 0.154 IWD.)220.1 75 80 ? 14F TO )SD. R 06/93 2BSW0.1 52S N/A A53 2AO 0.154 IWD.)220.1 75 80 ? 20C IO )AIL R 06/93 ISSSWO 1525 C 29 A53 )M sL)45 IWD 1220.1 75 80 ? 28 10 ROOM COOLING UNITB, 4F. R 06/93 ISDSWsLIS2S C 29 A53 )M 0.145 IWD.)22IE) 75 80 ? 2A 10 ROOM COO)DIG UNITA. 40. R 06/93 'I 1~)52S N/A 50 0.)45 IWD 1220.1 ? 2A TO 9635, 2)L R 06/93

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C' R. E. GINNANUCLEAR 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 SWRI ISI S(re Ihhrs NDE Line No. Une No. ~Fi . MatrL ~h. ~in. Method Po ~Tern In? Une deseri n/remarla

ACADIA N/A OAN OAXN IWC 12/.l(C) CONTAiiVMENTREQRC FAN A COOLER ~ R 06/93 ACAOIB N/A OAN OAXN IWC 1221(C) CONTALIMENTRMRC FAN B COOILR . R 06/93 ACAOIC ~ N/h OAN OAXN IWC.1221(C) CONTAINMENTRMRC FAN C COOLER. R 06/93 H ACAO ID N/A OAN 0.000 IWC1221(CI ~xca I. COiVTAINMENTREQRC FAN D COOLER ~ R 06/93 ~ ACAOIE N/A OAN 0.000 Q (/) IWC 1221(C) CONTAINMENTREQRC FAN h COOLER ~ R 06/93 ACAO IF N/A OAN OAXN IWC 1221(C) CONTAINMENTREQRC FAN A COOLER ~ R 06/93 ACAOLO g Q N/h OAN OAXN IWC.1221(C) CONTAINMENTRMRC FAN B COOLER . R 06/93 t9 H ACAO IN 4 N/h 0AN OANO IWC !22 1(C) CONTAINMENTREQRC FAN B COOLER . R 06/93 XHR ACAOIJ N/A OAN 0.000 IWG I 22 Er( I(C) CONTAINMENTREQRC FAN C COOLER ~ R 06/93 0 Z ACAOIK N/A AN 0 0.000 IWC 1221(C) CONTAINMENTREQRC FAN C COOLER ~ R 06/93 t0 P ACAOIL N/A OAN OAXN IWC 1221(C) CONTAINMENTREQRC FAN D COOLER ~ R 06/93 ACAOIM IEs N/h OAN OAXN IWC 1221(C) CONTAINMENTREQRC FAN D COOIER . R 06/93 H H g ACA02A N/h OAN OAXN IWC 1221(C) REAC TO R COMPARTMENTCOOLER A. R 06/93 f ACA02B o(/JAPa N/A OAN OAXN INC 1221(C) REAC TO R COMPARTMENTCOOLER L R 06/93 Pa ACAOT I N/A OAN OANO IWC 1221(C) CONTAINMENTREQRC PAN B COOLER . R 06/93 ACA08 N/A OAN OANO IWC >I WXa 1221(C) CONTAINMENTRMRC FAN C COOIER ~ R 06/93 ACA09 H N/A OAN OAXN 1th'G 1221(C) CONTAINMENTREQRC FAN D COOLER. R 06/93 L(2 A 5 W ACAI0 N/h OAN OANO IWC 1221(C) CONTADiVENTREQRC FAN A COOLER ~ R 06/93 HQQQ e(TJ

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1 ~ l IL E. GINNANUCLFAR POWER PIANT Insettrke Exaehu&n Boundasy Line I)st Ihin) Intpeedon Intava)

BklD No t 33013 12503 O Qass. t 2 W Syttem t SERVICE WATER Comp Iypet PIPING 0 RUBE CBbett SWRI Une No. LLinnteeNo line No. in)

8SW.125 SW.WO G322 SVR/VOL VALVE4644 TO 8'KE BY PKN 323 OUT CONT R 06/93 8ASW.)25 SW.)CO 8.00 G322 SUR/VOL PEN 323 TO D REQRC FAN COOIKR . R 06/93 8BSW.125 SW.700 BS3 BAO OB22 SUR/VOL D REQRC fhN COOLER 'IO PDI 3)2. R 06/93 m BQSW.125 SW.)500 B-53 8.00 OB22 BUR/VOL RED ElBOW AFIKR PKN 3)2 IO VALVE4642. R 06/93 0 (0 8DSW.)25 SW.)400 8-52B 8.00 (L322 SUR/VOL VALVE4643 TO 8 'IKE BEFORE PEN 315. R 06/93 8ESW.)25 SW 100 8-528 8.00 OB22 SUR/VOL RED EL PAST P315 IO C RKQRC fAN CQOIKR ~ R 06/93 8FSW.125 8.52 8.00 OB22 SUR/VOL RED EL PAST P320 IO C REQRC FAN COOLER . R 06/93 BCSW.125 SW.)500 8.52 BAO G322 SUR/VOL VALVE4641 TO RKD K)BOW PAST PEN 32G R 06/93 X H BHSW 125 SW.1400 8 SIC 8.00 G322 SUB/VOL VALVE4&30 TO )ST 8'KE BY PKN 311. R 06/93 WO BISW.)25 SW.)50 8-5)B OB22 5UR/VOL RED EL BY P311 TO B RKQRC FAN COOLER . R 06/93 BISW 125 SWS00 BS) L00 OB22 BUR/VOL B REQRC fhN COOLER TO PKN 316. R 06/93 BKSW-125 SW.)500 8-51 8.00 0322 BUR/VQL RED K(BOW AFTER PEN 316 TO VALVE4628. R 06/93 H)K) H 8LSW.)25 SW.)4(O 8-50A 8.00 G322 SUR/VOL VALVE4629 TO 8'EE BY PEN 3NL R 06/93 O(/) 8MSW.)25 SW-200 8-SOA ILOO OB22 SUR/VOL RKD EL BYF308 IO A REQRC FAN COOLER . R 06/93 @ I BNSW.)25 8-50 8.00 G322 SVR/VOL A RKQRC FAN COOU) TO RKD EL BEFORE P319 R 06/93 Ra BOSW 125 SW.)500 8-50 8AO G322 SUR/VOL RED FIBOW BY PEN 319 TO VALVE4627. R 06/93 H>M)O H 6SW-125 SW.)400 8.53A 6AO G280 BUR/VOL 8"IKE BY PEN 323 IO )ST RED ELBOW. R 06/93 ~ tK) I-3 g 6ASW.125 SW.TOOL.) 500 8-53 6AO SUR/VOI. RED EIBOW BEFORE 8 AFTER PEN 312. R 06/93 u) H 6BSW.125 SW-1400 8 528 6.00 0280 SUR/VOL 8'KE ON 8DSW 125 TO PEN 315. R 06/93 6QSW 125 SW-200BW.)500 8.52 6.00 0280 SUR/VOL RED ELBOW IN COiNT Bt OUT CONT ATPEN 320. R 06/93 H g 0 6DSW 125 SW.)400BW 150 B-5)C 6AO 0.280 SUR/VOL 8'TEE BY PEN 311 It) RED ELBOW PEN 311. R 06/93 6ESW )25 SWSOOBW 1500 8.51 6.00 0.280 SUR/VOL RKD ELBOW BE)ORE 6 AFIKR PEN 316. R 06/93 6FSW.125 SW WO~.200 B.SOA 6.00 0.280 SUR/VOL 8'EE BY PKN 308 IO 1ST RKD ELBOW 308. R 06/93 6GSW.)25 SW.500BW-) 500 8.50 6.00 0.280 SVR/VOL RED ELBOW PEN 319 IN CONT TO 319 OVTCON R 06/93 4ASW-125 8-50 4AO 0.237 IWC 1221(h) 8 X 4 RDCG ELLTO RDCR ON FCU 1% SUPPLY. R 06/93 4BSW 125 8.50 400 G237 )WC)22)(h) 8 X 8 X 4 'IKZIO RDCR ON FCU I h SUPPLY. R 06/93 4CSW 125 BSO 4AO OB37 IWC 1221(A) 8 X 4 RDCR 'IO KU I-ASUPPLY. R 06/93 4DSW.)25 B.SOA 4AO G237 IWC 122)(h) 8 X 4 RDCR TO RDCG ELLON FCU 1% RETURN. R 06/93 4ESW 125 8-50A 4AO OB37 IWC 1221(A) 8 X 8 X 4 IKKIORDCG KLLONFCU )*REIURN. R 06/93 4FSW.'I 25 BSOA 4.00 0237 IWC)221(A) 8 X 4 RDCR TO RDQG KLLON FCU IA RETURN. R 06/93 4CSW.125 USIA 4.00 G237 )WC)221(h) 8 X 8 X 4 TEE IO RDCG ELLON KU I 8 SUPPLY. R 06/93 (/) 4HSW-125 BSIA 4.00 G237 IVi&)221(h) 8 X 8 X 4 IKEIO RDCG ELLON KV ).B SUPPLY. R 06/93 (D 4ISW.125 USIA 0.237 fA&122)(h) 8X4 RDCRTORDCG FLLON KU I 8 SUPPLY. R 05/93 0 4ISW 125 8-518 4AO IL237 BY&1221(h) 8 X 4 RDCR IO RDCG ELLON FCU I.B RETURN. R 06/93 rt 4KSW 125 B-S) 8 4AO lta&1221(A) 8XBX4TEE IORDCG ELLON KU 1.8 REIURN. R 06/53 OX'237 4LSW. 125 B-S)B 4.00 IWC.)221(A) 8 X 4 RDCR TO RDCG ELLON KU I 8 REIURN. R 06/93 0 4MSW.125 B-52A 4.00 OB37 IWC.)221(A) 8 X 8 X 4 TEE TO RDCC ELLON KU )@SUPPLY. R 06/93 4NSW 125 8-52A 4.00 OB37 !WC)221(A) 8XBX4IKEIORDCGELLON FCV liCSUPPLY. R 06/93 4QSW )25 8-52A 4.00 0.237 IWC 1221(A) 8 X 4 RDCR TO RDQG ELLON FCU 14: SUPPLY. R 06/93 4PSW.)25 8-52B 0.237 IWC 1221(A) 8 X 4 RDCR IO RDQG ELLOiY fCU )C RE)URN. R 06/93 4QSW.)25 8.52B 4.00 0.237 IWC122)(A) 8 X 4 RDCR TO RDCC ELLON FCV )C RETURN. R 06/93 4RSW 125 8.53 4.00 G237 IWG 1221(A) 8 X 8 X 4 'IKE IO RDCR ON FCU I D SUPPLY. R 06/93 4SSW.125 8.53 -4.00 G237 IWC 1221(A) 8 X 8 X 4 IKEIO RDCR ON FCU I D SUPPLY. R 06/93 t

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I ~ 4 IL E. GINNANUCLEAR 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 0dbert SWM ISI Site IM>ns Exemption NDE Une No. Une No. Une No. ~Fi . Met>L ~in. ~h. Method ~Tern fn? Une deseri '/remarLs 4T~.125 8-53 A53 4Ae 0237 IWC 1231(h) S X 4 RDCR TO 4 X 3 RDCR OV FCU I-DSUPPLY. R 06/93 4USW.125 BSSA A53 4>00 IL237 WGI221(h) 8 X 4 RDCR IO RDCG EU ON FCU I-D RETURN. R 06/93 4VSW-125 ~ BSSA A53 4Am IX237 IN&1221(h) 8 X 8 X 4 TEE 'IO RDCG ELLON FCU I-D RETIIRN. R 06/93 H 4WSW-125 S$ 3A A53 4Am IL237 IWG 1221(A) 8 X 4 RDCR IO RDQG ELLON FCU I D RETURN. R 06/93 3ASW-12$ 0 (I) ~ N/A 300 11216 IWG1221(A) CROSS CIXVNECTFOR ACA07, M, 6 IIL R 06/93 3BSW 125 B$28 A53 3Am OAXN Pi% 1221(A) FCU 14: RETURN IO 8"IKE. R 06/93 A XSASW.125 SW 1410 N/A A53 250 (L203 IWC Q 1221(A) VALVE4636 TO 25 X 25 X 2 IKE PAST PEN 201 ~ R 06/93 2$BSW-125 SW400 N/A %SO R4H A53 IX203 IWC 1221(h) 1ST ELBOW PAST PEN 201 IO ACA02!L R 06/93 MHZ 25CSW.125 SW~ A53 X50 Nfh (L203 IWC 1221(A) REAC IO R COOLKR ACA028 TO PEN 209. R 06/93 (x) ON 2$DSW-1 25 SW 1550 N/A A53 IX203 IWG1221(h) LS X hS X 2 TEE BY PEN 209 IO VALVE4635. R 06/93 WP 25ESW-125 SW.1410 N/h A53 %50 IL203 IWC 1221(A) VALVE4758 TO 25 XXS X 2 'IKE BY PEN 209. R 06/93 XSFSW.125 SW~ N/A A53 %50 IX203 IWC 1221(h) IST RED ELBOW BY PEN IN CoiNT TO ACA02A. R 06/93 gtA)H/Q ~SW-125 SW400 N/A A53 LSO IX203 IWC 1221(A) REAC TO R CtmLER ACA02AIO PEN 201. R 06/93 2$HSW. 1 25 SW.1550 O(/)OPS N/h A53 250 0.203 IWC 1221(h) XS X RS X 2 IKE BY PEN 201 I0 VALVE4757. R 06/93 %SIC. 1 25 B40 %50 OANO INC 1221(A) SN THRU ACAIO,TO SML R 06/93 %Sly.125 B.S I %50 OAXO ~&XIV IWC 1221(A) SJ THRU ACA07> TO 81. R 06/93 2.5K'. 1 25 8-52A %SO 0.000 IWC.1221(h) SF THRU ACA08, TO BE. R 06/93 'hSLSW.1 25 8.53 %SO OAXN IWG1221(A) 88 THRU ACAO9> IO SA. R 06/93 2ASW-125 SW.1410~400 Nfh A53 2.00 0.154 IWC1221(h) 25 X 2$ X 2 IKEAT PEN 201 1ST RED ELBOW. R 06/93 2BSW-125 SW ASKEW.1550 N/A A53 2Am 0.154 IWC 1221(A) RED ELBOW BY PEN 209 TO 1 ST 2'KE . R 06/93 HgQ 2CSW-125 SW.1 410~400 N/A A53 2.00 0.154 IWC 1221(A) 25 X 25 X 2 TKE SY PEN 209 1ST RED ELBOW. R 06/93 2DSW.125 SW4XXLSW.I 550 N/h A53 2Am 0.154 IWC 1221(A) 1ST RED ELBOW BY PEN 201 IO 2'EE . R 06/93 2ESW.125 N/A uu aOOO IWC 1221(A) 2$ISW.125 PAST VALVE4794F. R 06/93 2FSW.125 0 N/A 2AXs 0.000 IWG 1221(A) XQSW.125 PAST VALVE4794K. R 06/93 g 2GSW-125 N/A 2Am OAXN IWC 1221(A) VALVE4794 0 IO %SF'-I 25. R 06f93 IdhSW-125 BSOA WO OAXN IWC 1221(A) SM IHRU VALVE4773 TO 2E. R 06/93

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'4 IL E. GINNANUCLEAR POWER HANT Insersloe Exatnlnadon Bonndaty Une Ust TIdtd Inspectbn Intesval

PSID No-: 33013 12508 Chss: 3 Systetn t SERVICE WATER s PIPD 8 H Con PI?P 0 ROSE GBbett SWRI I51 NDE Une No. No. Une No. Method ~T~ In? LI d

14ISWO.I25.I SW.1400 C 14 A53 14AO 0975 75 80 ? ICAIQ 4561, DISCHARGE CANAL R 06/93 14LSSO125 I GH I4AO 0975 NO SUPPORTS ? BYPASS FOR 4561 FROM 141 THRU 45&L R 06/93 SW-1400 I-I ~ IOASIi0125-I GN A53 10.00 0375 75 80 ? BD, 8E IO 14 REDUCER, 14L R 06/93 IOCSV0 125-1 CI6 IGLOO 0375 4 ? 16D IO 4614 R 06/93 ~ BASWO SW-1500 0 TAI 125 I C I6B A53 8.00 OB22 75 80 ? HE IO 4642. R 06/93 BBSWO SW.1500 125 I G16B A53 MO 0922 NO SUPPORTS 75 80 ? HE TO 4628. R 06/93 BCSWO 125 SW.1500 gQ I CI6B A53 8AS IL322 75 80 ? 14 E IO 4i41. R 06/93 BDSWO 125-1 SW-1400 Q4H C N A53 8AO 0322 75 80 ? 4644 TO IOh. R 06/93 MHZ 8ESWO 125.1 C.14 A53 SOO IL327 75 80 ? 4643 IO IOA. R 06/93 %OR BFStiO 125-1 C.14 A53 MS 11327 75 80 ? 4630 IO 14l. R 06/93 BGSW0.125.1 C.14 A53 MO 0327 75 80 ? 4629 IQ 14 X 14 X 8 TEE, 14J. R 06/93 BHSWO 125.1 t53 H C16B A53 BAD tl327 NO SUPPORTS 75 80 ? 14E TO 4i27. R 06/93 ~ Q 6BSWO-125 SW-1410 I C 18 A53 600 (1280 75 80 ? 4H,4l TO 14L R 06/93 $ 4HSWO.I25-1 o pn O ta C 18 A53 4AO 0~ IWD.1 220.1 75 80 ? 4551A IO 6BSW0.125 I. R 06/93 ~ 4ISWO 125 '? I

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"l IL E. PINNANUCLEAR 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 0

RQIE ISI Size %Res Exam pthn NDE Line No. ~PI . MatrL ~h. ~h. Bash Method Po T~em In? Une deseri remarirs Revbal

AA OAO 0.000 VOL PRESSUIUZEL A 11/9I H ~

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l K IL E. GINNANUCLEAR POWER PLANT Inservtee Examinanon Bonnthry LIne Ust Third I spection interval

PMD No t 33013.1258 O Chss t I System t REACTOR COOIANT-PRESSURIZER Comp Imper PIPLNG H0 RGStE GBbert ISI SIte Une No. Une No. . ~F1 MatrL ~in. Po ~Tern IIn7 Une desert '/rernarirs Revised

IO.RC8-2501 RG200 10 PRZ SURGE ABD A376 IUD ISO SUR/VOL PRZ SURGE UNE IO B HOT LEG. R 11/91 I dh-RCS-2501% 4.RG273 A-13 A376 %AS 0.531 SUR/VOL PRZ REUEF PRZ IO PCV 43S. ~ 4A.RC8.2501.B 4 RC 273 A.13 A376 4Am IL531 SUR/VOL PRZ REUEF PRZ IO PCV 435. H 4ORCB-2501 +RC 1005 h-12 A376 %AS OMI SUR/VOL PRZ REUEF PRZ IO RELIEF MANIIOLD. OMe 3A RC8.2501 3 RC 1005 h-12 A376 3AO OA38 SUR PRZ REUEF MANIPOLDIO VALVE5515 5 43 IC 3A.RC8-2501* RC300 3.RC 1000 A.10 A376 3AM OA38 SUR PRZ SPRAY FROM IlOP A IO ASIA. R 11/91 g Q 3A RC8-2501.B RC300 3-RC-1001 A.I0 A376 3.00 OA38 SUR PRZ SPRAY FROM IQOP 8 TO 431 B. R 11/91 3B-RC8.2501 3.RC 1006 A.12 A376 3.00 OA38 SUR PRZ REUEF MANIFOLDIO VALVES516 B 430. CHR 3ORCB-2501 3-RC 1000 A-9 A376 3.00 SUR PRZ SPRAY FROM 431A It B IO PRZ HEAD. %OX 2A RC8.2501 A 11 2AN 0.000 SUR VALVE297 'IO REDUCER AT3C RC8-2501.

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PdtlDNo r 33013.1258 O Class r 2 Sysrera r REACIOR COOlANT.PRESSURIZER Comp TYPe: PIPING 0 RGBtE GBbert SWRI 151 Size %he Exempaoa NDE Une No. N u ~Fi . MntrL ~In. ~b. Bans Method Po ~Tern In? Une deseri 'emnrlrs

2A.RC.151 N/A 2.00 OAXX) IWC 1222(A) 60 10 - VALVE529 BY PEN 121 TO VALVE50L H Q Ul

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PtklD No t 33013 1260 O Class t I System.: REACIQR COOLANT Comp Typm COMPONENIS 0 RGErE GBbert ISI She Tlhns Mne No. Line No. ~F1 . Matrl. ~in. ~h. Po ~Tern tnt Mne ctescri '/remarks

EMS 0)A AG tMO OAXO SUR/VOL SIE/LM GENERAIQR h. A II/91 EMS GIB A-5 0.00 0.000 SUR/VOL SIEAM GENERATOR L h 11/91 H PRCOIA h-7 0.00 OANO SUR/VOL REACIOR COOIANT PUMP * h 11/91 PRCOIB A.7 OAXI 0.000 SUR/VOL REACIOR COOIANT PUMP K A 11/91 0 M RRCOI A.l 0.00 0.000 SUR/VOL REACTOR VESSEL A 11/91

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PAID No t 33013-1260 Qass t I Systan t REACTOR COOIANT H Comp IYpe: PIPING 0 ROBE ISI NDE Une No. ~FI . Mstrh Metlrod ~Tern IInl Une deseri n/remsrlts

31 RC 250M UNE h h3 CCSS 3 IAN 2500 SUR/VOL Y CROSS OVER FROM SGW TO RCP * 31 RC 2501 B LINE B h3B CCSS 31 AN 2500 SIIR/VOL Y CROSS OVER FROM SG-B TO RCP IL H 29.RC250M UNE A A3 CCSS 29Am 2500 SUR/VOL Y HOT LEG FROM RPV'IO SG-A. 29.RG2501.B UNE B A3B CCSS 29.00 2500 SUR/VOL Y HOT LEG FROM RPV IO SOIL 0 M 27.5 RC 2501% UNE A A3 CCSS 27.50 2.4N SUR/VOL Y COID LEG FROM RCP A TO RPV. 27.5.RC.2501 B UNE B h38 CCSS 2780 2.400 5UR/VOL Y COLD LEG FROM RCP B IO RPV. 10A RCO 2501 h RHR3500 IO.AC 1004 h.l5 A376 10Am IAXN SUR/VOL Y RHR FROM HOT LKG A TO VALVE700. R 11/91 10A.RC0.2501.B 51-200 l(PIC 1001 A.14 A376 10.00 IAXN SUR/VOL Y RHR/Sl FROM 721, 867A IO COID LBG L R 06/93 10B.RC0.2501% A-17 A376 10Am IAXN BUR/VOL Y Sl FROM 867B IO hOOP h COLD IKG. h 06/93 XO

6A.RC0.250 M RHR-100 6AC 1003 A.14 A376 6Am 0.718 SUR/VOL Y RHR FROM VALVE852A 'IO 6X4 REDUCER ~ R 11/91 6A-RED.2501.B RHR.100 6'002 A.IB A376 6D0 0.718 BUR/VOL Y RHR FROM VALVE8528 IO 6X4 REDUCER . R 11/91 4A-RCO 250 M RHR.100 4AGI003. h.14 A376 4AN 0531 SUR/VOL RHR FROM Y 6X4 RKDUCKRIO RPV. R II/91 H UI g 4A.RCO 2501.B RHR-100 4'002 A-18 A376 4D0 0531 SUR/VOL Y RHR FROM 6X4 REDUCER TO RPV. R II/91 O N 2A.RC0.2501% A-26 A376 2.00 0344 SUR Y CHARGING VALVE383A 'IO lOOP A COID IKG. h 06/93 2A.RC0.2501 8 2.DR.1002 A-23A A376 2Am 0344 SUR Y IZIDOWNFROM CROSSOVER LEG IQ 427, 54L R 06/93 k 2B.RC0.2501% 2.LD 1001 A.22 A376 2.00 OAXN SUR ~ Y DRAIN FROM CROSS OVER LEG IO 541, 523. R 06/93 H tO O H 28 RC0.2501.B A-27 A376 2.00 0344 SUR Y CHARGING VALVE393 IO hOOP B HOT LEG. h 06/93 + Ul g g 2ORC0.250M A.20 A376 2.00 0000 SUR Y Sl FROM VALVE877B IO LOOP A HOT LEG. h 06/93 tA) H 2ORC0 2501.B A-25 A376 2.00 0344 SUR Y CHARGING VALVE295 IO IQOP B COID LEG. h 06/93 o 2D RC0.2501.8 A-21 A376 2.00 OAXN SUR Y Sl FROM VALVE877A 'IO lOOP B HOT IKG. h 06/93 H g

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0 IL E. GINNANUCLEAR POWER PIANT Inserviee Examination Botmdary Une Ust 'Bdrd inspeedon lntervtd

P&IDNo r 33013.1261 Q CLsss: 2 System. r CONTAINMENTSPRAY Comp T)rper COMPONFNIS 0H RG&E ISI SIxe IMnrs NDE LLoe No. ~FI . MatrL ~in. ~in. Method Fo T~em tnt line desrri '/rernarirs

PSI02A 1261 N/A (LOO IUNO NO IWQ. 205 70 CONTAINMNTSPRAY PMP h, MFG INCERSOL R/UID R Ol/92 PSI02B 1261 N/A OAM IL000 NO IWA 205 70 CONTAINMNTSPRAY PMP 3, MFG ~ INCERSOL RAND R Ol/92 ~ SS101 1261 N/A IGLOO (OOOO IWG 1221(A) CONTAINhL%'PRAYEDUCTQL R 11/91 H SSI02 1261 N/A 0.00 0AXO IWC 1221(A) CONTAINMENTSPRAY EDUCTOR L R II/9I (/) ~ TSIOI 1261 N/A DAO 0.000 NOT SECT XI REFUEUNG WATERSTORAGE TANK. R 11/91 0 TSI02 1261 N/h (LOO 0.000 IWC 1221(h) SPRAY ADDIIIVETANK. R 06/93 R4HQ Q 'g H g X 0%

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9&IDNo t 33013.1261 O Qass. t 2 System. t CONTAINMENTSPRAY Comp Type: PIPING 0H RUBE SWRI Exemption NDE Une No. Une No. Basis Methad In?

10$ 1 151 1.2IO4 )0$ B 19 A312 10.00 0.165 SUR/VOL 30 70 RWST 10 )ST 10 X 8 S 10 X 6 RDCRS, 8258. R 06/93 1088$ ) 151 10AO OASO SUB/VOL 410 350 RWST TO VALVE856. R 11/91 8A$1.151 RHRASO H ~ B.)9 A312 8.00 0.148 SUB/VOL 30 70 6A$1.)51 '10 C5 PVMP L R 11/91 88$ FOSI RHRA50 1051-151 R 8-19 A312 LOO 0.)48 SVR/VOL 30 70 68$ ).151 10 CS PUMP h. R II/91 ~ 6A$1.)51 RH RUSSO 0 (/) 6$).15)R 8 19 A312 6AS O.MI SUR/VOL 30 70 10$ 1.151 10 RDCR PAST VALVE858L R 11/91 68$ )-)51 RHRA50 10$ 1.15)R B 19 A312 6AS 0.148 SUR/VOL 30 70 10$ 1 151 10 RDCR PAST VALVE858h. R 1)/91 1$01 N Q 6C$ CS 500 B46 A48 6.00 0280 SUR/VOL 205 70 4A$)$01 10 1ST 6 X 6 X 6 TEE . R 11/91 6D$)$0) C5$ 00 B46 A48 6AO (F280 SUR/VOL 205 70 6C$ 1$01 '10 VALVE860A. 6DD$)$01 C5.500 XHX L46 A48 6AO (F280 IWC 1221(F) 205 70 VALVE860h IQ IST 6'EE BEFORE V 862A. (X) OX 68$ )$0) CS$ 00 L46 h48 6.00 (L280 SUR/VOL 205 70 )ST IEE ON UNE 6C$)$01 10 VALVE860L 6EE$ )$01 CS$ 00 A48 6AO Ot280 IWC 1221(F) 205 70 VALVE860B TO VALVE862h. 6F$ )$0) CS.500 B46 A48 6AO IV&122)(F) 205 70 VALVE862A 10 PEN 105. R 1)/91 + AH 60$ I$0) CS.)CO,CS.)50 HtOa5< B48 A312 6AO 0281 itaQ 1221(F) 205 70 PEN 105 TO CS SPRAY RING. +o(/)OW 6H$1$01 CS.)50 N/A A312 6AS (L28) %0 1221(F) 205 70 6G$1$01 10 4 B$)$01. 6)$)$01 CS.)50 ~leva N/A A312 6AS Gt28) IWC 1221(F) 205 70 4C$)$01 '10 6G$)$01. 6)$)$0) CS800 8-47 &XhfU A48 6AO 0280 5VR/VOL 205 70 4D$1$01 10 IST 6 X 6 X 6 TEE . 6K$)$0) CS800 B47 A48 6AO 0280 SUR/VOL 205 70 6 X 6 X 6 TEE ON 6)$)$01 TO VALVE860D. g&0)H 6KK$ 01 'Q )$ CS$ 00 L47 A403 6.00 IL280 IMiZ.)221(F) 205 70 VALVE860D TO 6'EE BEFORE VALVE862L H 6L$1$01 CS800 L47 A48 6.00 (L280 SVR/VOL 205 70 6 X 6 X 6 IEE ON 6)$)$0) IO VALVE860C O e(Z) 6LL$)$01 CS8(O B47 A48 6AO 0~ IWC 1221(F) 205 70 VALVE860C 10 6'EE BEFORE VALVE8628. HgQ 6M$ 0) I$ CS800 B47 A48 6.00 0.280 IWC 1221(F) 205 70 6 X 6 X 6 'IEE BEFORE VALVE862B IQ PEN 109. 6Ã$1$0) C5-200,CS 250 N/h A312 6AS 0280 )WC)221(F) 205 70 PEN 109 'IQ 6'EE ON LOWER CS RING. 6P$ )$01 CS-250 N/A A312 6AO 0.281 IWC 1221(F) 205 70 4F$ 1$01 10 6N$1$01. 60$ WOI CS-250 A312 QO N/A 6.00 0.281 IWC )221(F) 205 70 6N$ 1 $01 10 4 E$1$01. 4A$ 0) C5$ )$ 00 L46 A312 4.00 IWC 1221(A) 205 70 h CS PUMP IO REDUCER R 11/91 48$ )$01 CS-150 N/A A312 400 0.237 IWC )221(h) 205 70 6H$)$0) TO 3AS)$01. R )1/9) 4C$ 1 01 C5.150 $ N/h A312 4.00 OXI7 IWC)221(A) 205 70 3A$)$0) IO 61$ 1$01. R 11/91 1$ 40$ 0) C5$ 00 L47 4AO OAKS IWC 1221(h) 205 70 B CS PUMP TO REDUCER . R 11/91 1$01 C5.250 48$ N/A A312 4AO 0237 IWC 1221(A) 205 70 6 X 4 RDCR TO 38$ )$01. R 11/91 1$01 CS 250 4F$ N/A h312 4AO (L237 1th'G)221(A) 205 70 4 X 3 RDCR '10 6 X 4 RDCR ON 6P$ 1$0). R 1)/91 ).15) 3$ N/A 3AO 0.000 IVI'G)221(A) 30 70 RWST 10 NOZZLE WELD. R II/91 3A$1 01 (/) $ N/h A312 3AS 0216 IVtQ 1221(A) 205 70 4 8$1$01 TO 4C$)$01. R )I/91 38$ 1 01 (t) $ N/h A312 3AS 0216 IVI&1221(A) 205 70 4 X 3 RDCR ON 4E$ )$0) 10 4 X 3 RDCR. R Il/91 3C$ 01 0 )$ N/A 3AS IMAGO Bh&1221(h) SPRAY ADDITNETANK10 VALVE627. R II/91 ) 151 2$ N/A 2AO 0.154 IWC.1221(h) 30 70 RWST 10 VALVE893A. R 11/9) 2A$1.15) N/A 2AO 0.154 )Vs'221(h) 30 70 RWST 10 VALVE893 L R II/9) 0 28$ 1 151 N/A 2AO 0.154 IWC 1221(A) 30 70 RWST 'IQ VALVE894 L R 1)/91 2CSI-)5) 8.20 2AO IL154 IWC 122) (A) 30 70 RWST 10 VALVE808. R 1)/91 2D$1.151 C5$20 8.19 A312 0.154 IWC 1221(A) 30 70 10$ 1-151 10 VALVE873C R II/91 28$ )$0) CS-100 N/A A312 2AS 0.154 IWC )221(A) 205 70 60$ 1$01 10 6N$1$01. R )1/91 0 2F$ 1$0) C5.100 N/A A312 2.00 0.154 IWC 122)(A) 205 70 2E$ 1$01 TO VALVE875A. 20$ 1$01 C5.100 N/A A312 2.00 0.154 IWC 122)(h) 205 70 28$)$01 TO VALVE875L 2H$)$01 C5.100 N/A A312 2.00 a)54 IWC 1221(h) 205 70 28$ )$01 TO VALVE876L Jl

s t R. E. GINNANUCLEAR POWER PIANT Inservice hminrrdoa Line LIst 'Ildrd tnspecdoa~Iaterrrrd

PMD No t 33013.1261 (Cont'd) Chss. r 2 Systera t CONTAINMENTSPRAY Comp T)rper PIPING 0 RUTE ISI SIse NDE LLm No. ~PI . Method Po ~Tern ia7 Uae drscri '/reaurts

2ISIS01 CS-100 N/h A312 0.154 IWC.12@ (h) 205 /0 2ESISO I 'IQ VALVE876A. 2ISIS01 CSS10 8-19 A312 IL154 IWC.1221(h) 205 70 8BSI.151 'TO CS EDUCTOR R II/91 2KSIS01 CSS 1 0 B46 A312 0.154 I%&1221(A) 205 70 6CSIS01 TO VALVE859A, R 11/91 H 2KKSISOI CSS10 N/A A312 0.154 IWC 1221(A) 205 70 CS EDUCIQR A TO 2KSIS01. U) 2LSIS01 CSSI 0 N/A A312 0.154 IWC 1221(A) 205 70 CS EDUCIQR I TO CS EDUCIOR 2. R II/91 0 XtISIS01 CS.510 8 19 A312 0.154 IWC 1221(A) 205 70 BASI-151 'IQ CS EDUCiQR 2NSIS01 CS.510 N/h A312 0.154 IWC 1221(A) 205 70 CS EDUCTOR 2 TO 2QSISOI. R II/91 2PSIS01 CS-51 0,CS-520 N/h h312 0.154 IWC 1221(h) 2LSIS01 TO VALVE873A. R II/91 XH 2QSIS01 CSS10 i%7 A312 (L154 IWC.1221(h) 6ISIS01 TO VALVE859h, 859C R 06/93 WO 2QASISOI CS.520 N/A A312 0.154 IWC 1221(A) 2PSIS01 BYVALVE873B TO VALVE8730. R 11/91

2RSIS01 CSS20 N/h A312 0.154 IWC 1221(h) 2"TEE ON PSI.151 PAST VALVE~ R 11/91 2SSIS01 CSS20 N/h A312 0.154 IWC 1221(h) 2PSIS01 PAST VALVE836B 'IO 1 ST 2'EE . R 11/91 NOH H 'LO 'g 2TSISOI CSS20 N/A A312 0.154 IWC 1221(A) VALVE8818 TO SPRAY ADDITIVETANK. R II/91 ~ 20$ 1.151 N/A 0800 IWC.1222(h) VALVE O(/) o Ff RWST TO 895. A 11/91 g I & O H ting ICs pH 0

IL E. GINNANUCLEAR POWER FIANT lnsaviee ~n Bonndery Une Ust Thhd Inspecnon Intaval

PMD No t 33013 1262-1 O Class t 2 Systan t SAFEIY INIECIION Gnnp Type: COMPONENIS 0H ROBE Gihert ISI Site Ties NDE Une No. Une No. . MetrL ~FI ~1m ~in. Method Po ~Tern In? Une deseri n/remerks PSIOI A 1262 N/h OAS OA0 NO IW/L. 1550 200 SAFElY INJECTION PUMP A, MFG ~WORTHINGTON R 06/93 PSIOI B 1262 N/A OAO OAI00 NO IWA 1550 200 SAFEIY INIECIIONPUMP B, MFG ~WORTHINGTON R 06/93 PSIOIC 1262 ~ N/A IGLOO 0.000 NO IWA 1550 200 SAFEIY INIECIIONPUMP C, MFG ~WORTHINGTON R 06/93 H O 02 ~ g Q XHRt3 4 H WOW

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SCS)30) SI~SSI301 SS)-2001 8-15 A312 8AO 0322 5UR/VOL Sh/SBS)301 10 IST 8'TE ~ R 06/93 SDS)30) SI~P)301 8$)-2003 8 16 h312 BUR/VOL SCS)301 TO 'KKPAST VALVE826L R 06/93 H SES)30) SI~,SSI30) SS).2002 8 16 A3)2 8'322 SUR/VOL SCSI301 10 1ST TEE PAST VALVE826D. R 06/93 SFS)301 SI~,RHRA50 SSI-2003 815A A312 SOO 0322 BUR/VOL SD/SES)30) 'IQ 1 ST 8 X 4 BDCL R 05/93 C) (/) SGS)30) RH F50 8-19 A312 LOO 0322 SUR/VOL SFS)301 '10 VALVE825A, R 06/93 SHS)301 RHRA50 8.16 A312 LOO 0322 SUR/VOL SFS)30) 10 VALVE825)L R 05/93 8)SI.)5) 8 19 LOO 0.000 BUR/VOL VALVE8258 10 1081 151 ~ R 06/93 SLSI.)51 8 19 LOO 0.000 SUR/VOL ..VALVE825A 10 )OSI.)51. R 06/93 g H 4$)301 RHR450 8-168 A312 4'337 IWC 1221(A) 200 200 SFS)301 10 Sl PUMP SUCIION A. R 06/93 w o 4ASI301 RH F50 8-)68 A312 4AX) 0337 IWC.)221(A) 200 200 SHS)301 TO Sl PUMP SUCIION L R 06/93 200 200 SGS)30) 10 Sl PUMP SUCIION C R 06/93 4841301 RH F50 8.168 A312 4A)0 0337 IWC 1221(A) + tA) H d 4CS)301 RHR450 8-168 A312 4AS 0337 IWC 1221(A) 200 200 48$)30) 10 1816A. R 06/93 H ti) lg 4DSI.) 501 S)3(XII.210 le@ A312 4AS IL337 SUR/VOL 1550 200 3AS).1501 THRU PEN 113 TO 4 X 4 X 3 TKE. R 06/93 + O(1) OX 4ESI.)501 5)3IXL51 1)0 S42 A312 4'337 BUR/VOL 1550 200 3ESI-1501 1HRU PEN 101 10 4 X 4 X 3 TKL R 06/93 3AS).1501 5)300 837 A312 3AS 0300 SUR/VOL 1550 200 Sl PUMP h 10 4 X 3 RDCR AFKRVALVESSSA. R 06/93 3881.1501 5)300 840 A312 SOO 0300 SUR/VOL 1550 200 Sl PUMP C PAST FLANGE 10 3'TEE. R 06/93 > tOO 3CS).1501 5)300 IL41 A312 3AS 0300 SUR/VOL 1550 200 3'KE FROM 38 TO 87)h, 870A, 84)X R 06/93 (/)HtOg 'LO H 3DSI.) 501 S)300 L4) A312 3AX) 0300 SUB/VOL 1550 200 3'EE FROM 38 TO 8718, 8708, 84E. R 06/93 g '10 AFTKRVALVE R 0 3ESI.)501 5)300 842 A312 3AX) 0300 SUR/VOL 1550 200 Sl PUMP 8 4 X 3 RDCR 888L 06/93 H 2ESI.)501 844 2AX) OAXN SUR Sl PUMPS DSG RDCRS 10 VALVES898 S 897. R 06/93 g 0 )SAS).1501 S)300 837 A312 1.50 OAXO IVt&)221(B) 1550 200 2ESI-1501 TO 3ASI-)50). R 06/93 13CSI.) 501 S)300 8-54 A312 1.50 OAXN IWC 1221(B) 1550 200 3BSI 1501 10 2ESI.)501. R 06/93 )3DS).1501 5)300 S42 A312 )30 (LOGO IWC.1221(8) 1550 200 3ES).1501 10 2ES).1501. R 05/93

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10ASI2.2501.h Sl 100 10$ 1-1005 h.17 A376 IDAO IAXO 5UR/VOL CHECK VALVE8428 T0 867L R 06/93 10ASI2-2501.B 51-200 10$ 1-1004 A-16 A376 10AO IAXO SUB/VOL CHECK VALVE842A T0 867A. R 06/93 2ASI2-2501 51.110 2$ 1-1001 A 19 A376 2.00 IL344 SUR 8781 '10 1(P Sl ACCUM B DUMP. R 06/93 H rn 28$ 12-2MI 51-210 2$1-1002 A.21 A376 2AO (1344 SUR VALVE878F l0 877A. R 06/93 UT 2CSI2-2MI SI. I 10,.111 2$ 1.1001 h-20 A376 2.00 0844 SUR VALVE878 H T0 877 B. R 06/93 0 2DSI2.2501 51.210 2$ 1-1002 h-16 A376 2AO a344 SUR 878G T0 10'l ACCUM A DUMP. R 05/93 X H W A W

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1 IL E. CUINANUCLEAR POWER PIANT nseervice Examinatbn Une Ust IMrd nspecdon~Interval

9&IDNo t 33013-1262-2 O c2ass t 2 System t SAFEIY INJECIION H Comp 1)pe: PIPUtC 0 RC&E GChert ISI Site NDE No. UUnne line eNo. ~Fi . MatrL ~b. Method Po ~Tern Inl Une descri remarks

10ASI-902 SI5-200 N/A A376 ICAN IAXN IWC.122 /(E) 740 80 ACCUMUIAIQRI TO VALVE841. R OV93 10831.902 SIS-200 N/A A376 10.00 IAXN IWO1221(E) 740 80 OASI.902 CAP ON IEE . R 06f93 I IO ~ 10CSI.2501 SIS-200 N/A A376 10.00 IAXN IWO1221(E) 740 80 VALVE841 IO 842A INQD CAP ON 'IEE . R 06/93 H 10DSI-902 Sl 100 N/A A376 ICAN IAXN IWC 1221(E) 740 80 ACCUMUIAIQR2 TO VALVE865. R OV93 Q(/) e I0ESI-902 SI 100 N/A A376 10.00 IAXN IWO122 I(E) 740 80 10DSI.902 IO TEE CAP. R OV93 IOFSI-2501 51.100 N/A A376 10.00 IAND IWO1221(E) 740 80 VALVE865 IQ 8428 INQD CAP ON IEE . R OV93 NQ 2ASI.1501 51.210 B39 A312 Q218 SUR 1550 200 4DSI-1501 IQ VALVE878A. R 06/93 R4H 2831.1501 51 210 B39 A376 200 0218 SUR 1550 200 4DSI-1501 IO VALVE878IL R OV93 XHX 2CSI.1501 51.110 B45 A376 2Am 0343 SUR 1550 200 4'EE ON 4ESI-1501 IQ VALVE878D. R OV93 ROC 2DSI-1501 51-110 B44 A312 2Am Q218 SUR 1550 200 4'EE ON 4531-1501 IO VALVE878C. R 06/93 2C$ 1-902 515.200 N/A A312 2.00 Q343 IWO1221N) 740 80 10ASI-902 TO VALVE844A. R 06f93 2HSI-902 Sl-101 N/A A312 2Am 0.154 IWO1221(E) 740 80 10DSI-902 'IQ VALVE844 IL R OV93 21$1-902 N/A A312 2Am 0.154 IWCI221N) 740 80 ACCUMUIAIQRI PAST V 833A IO LT939. R 06/93 o(/) OPS 2l$1-902 N/A A312 0.154 IVrC 1221(E) 740 80 LT939 PAST V 833B 10 ACCUMUIAIQRl. R 06/93 '10 2KSI.902 N/A A312 (L154 !Vs&1221(E) 740 80 ACCUMUIAIQRI PAST V 832A LT938. R 06f93 & X LT( U 2LSI-902 N/A A312 Q154 Ita0 1221(E) 740 80 LT938 PAST V 8328 'IO ACCUMUIAIQRI. R OV93 g kEs O H 2MSI-902 N/h A312 0.154 IWO1221(E) 740 80 ACCUMUIAIOR2 PASTY 837h TO LT934. R OV93 + g 2ÃSI-902 N/A A312 2Am Q154- IWC 1221(E) 740 80 LT 934 PAST V 837B IO ACCUMUIAIQR2. R OV93 u) I-I 2PSI-902 Nfh A312 2Am 0.154 IWC 1221(E) 740 80 ACCUMULAIOR2 PAST V 83&AIQ LT935. R OV93 O e (Ei 2()$1.902 N/A A312 2Am 0.154 IWC.1221(E) 740 80 LT935 PAST V 838B IQ ACCUMUIATOR2. R OV93 HgQ 2RSI-2501 B45 2Am OAXN SUR VALVE878D IO VALVE87&I. R OV93 25$ 1-2501 B44 2Am 0.000 SUR VALVE878C IQ VALVE878H. R 06/93 2TSI-2501 B39 2Am 0.000 SUR VALVE878B IQ VALVE878G. R 06/93 2USI.2501 B39 0.000 SUR VALVE878A TO VALVE878E. R 06/93 2VSI-902 N/A 2AX) Q000 IWC 1221(E) DRAIN OFP 2CSI.902. R OV93 2WSI4t02 N/A 2Am 0.000 IWO1221(E) DRAIN OFP 2HSIdt02. R 06/93 '

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1 IL E. GLMihNUCLEAR 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 0H ROBE Gihert ISI She NDE Lbe No. Lbe No. ~Fi . MotrL ~h. Method Po ~Tern In? Lbe deseri 'emarks

TRC03A N/A OANO IWD I~I OVERPRESSURE PROTECIlON ACCUMUIATOR* R 06/93 TRCOSB N/A OAXO IWD.122ILI OVERPRESSURE PROTECIlON ACCUMUIATORIL R 06/93 1RC04A N/A OAXO. IWD.122ILI OVERPRESSURE PROIECllON N2 SURGE TANK* R 06/93 H TRCOIB N/h OOOO IWD.1220.1 OVERPRESSURE PROTECTION N2 SURGE TANKL R 06/93 0 Ul

X H X A + HMkgII3 H O Q OX wa He 0 H tA3 t3 g 'LO H H g 0 I l'

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t 4 R E. GUINANUCIEAR POWER PIANT nseevviee Euunlnation Oonnthrry Une Ust Thin! sspeedces interval

Bt!DNo t 33013-1264 O Chss t I System s CVCS LETDOWN t3 Comp Type: COMPONENTS H p RUBE Grlbert SWRI ISI Slee Tlrkns Exemption N DE Une No. Une No. Une No. MarrL ~FI . ~b. ~in. Po ~Tern In? Une desni remar?a

h4 OAS a000 VOL lHIS COMP ACCOUNTED FOR OiI 33013.1265. R 01/92 A4 a00 a0M VOL THIS COMP ACCOUNTED FOR ON 33013 1265. R 01/92 A4 aoo a 000 VOL THIS COMP ACCOUNTED FOR ON 33013.1265 R 01/92 H N/A am 0.000 IWB-1220(B) EXCESS LETTIWNHEAT EXCHANGER A II/91 P F/2

g H rWO + 'LO H Hex+ W O VT H ICI O H IT? ~ g IO Hp H g

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PAID No t 33013-1264 A Class r W I Gilbert SIstem r CVCSLETDOWN H Comp TYpet PIPING 0

RGRE 151 SIre Tides Exempdon NDE une No. lIiinneeNo. ~FI . MatrL ~b. ~in. BaCk Method Po ~Tern Iat Une deseri rernarlts Revised

2A484.2501 2-LD 1002 A.23 A376 2'L344 ~ SUR Y CVCSV LETDOWN FROM 427 TQ 2204, THRU RHES R IV91 2BCN4.2501 2-LD.1003 A.24 A376 200 Q344 SUR Y RBES TO 200A, 2008, 202. R IV9I H ~

Cl M ~ g Q ROCQHQ HLI3Z jg CD M O X g&XRUeg H LI3 O H '4 H g H@Ooem

0 R. E. GINNANUCLEAR POWER PIANT Insertdoe ~a Botmdsty Une Ust IIdrd Inspectga Interval

PMD No..: 33013-1254 Chss.. t 2 System: CVCS.LETDOWN Comp I)rpe: PIPING 0H RGItE GEbert ISI SIte Une No. Une No. ~Fi . MntrL ~h. Po T~em In? Une deserl n/rernnr Its

2ACH601 CVC 105 N/A A312 0.154 IWC 1222(A) VALVE200A 'IQ 1ST 2 X 2 X 2 IEE. 2BCHWI CVC 105 A312 N/h 0.154 IWC 1222(A) VALVE200B IQ 1 ST 2'TE ON 2ACH401. 2CCHAOI CVC 105 B32 A312 0.154 IWC 1222(A) 2'EE ON 2ACHMI IQ2GCHAOI. H 2DCH401 CVC.IOS N/A A312 0.154 IWC 1222(A) VALVE202 IQ UNE 2CCHMI. (/) 2LCH F01 CVC 105 S32 A312 0.154 IWC 1222(A) 2CCH401 TO VALVE20tA 0 2PCHWI CVC 100 N/h A312 sL154 IWC.1 222(h) 2&AG601 IQ 2'EE PAST VALVEHCV-133. R 11/91 2GCH401 CVG100 B32 A312 (L154 IWC.1222(h) 2'EE ON 2CCH401 TO PEN 112, VLV371. R 06/93 g H WO

H 'LO H O(/) g I HegID 0 + u) H () H g

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fi IL E. GINNANUCLEAR POWER PIANT Inservke KaminatNn Bmmdary Une LIst TIdtd Inspecdon interval

PMD No..: 33013.1265 1 O Chas: I System. r CVCSCHARGING Comp COMPONENTS H Type: 0

RGRE GUbert SWIU ISI Sire TItkns Exemption N DE Line No. Une Une No. . No.. ~Fi Matrk ~b. ~in. Basis Method Po ~Tern In? IAne deseri n/remarlts Revised

PRCOIA A7 OARED 0AID SUR/VOL THIS PUMP ACCOUNTED POR ON 33013.1260. R 06/93 PRCOIB A-7 0.00 OA60 SUR/VOL THIS PUMP ACCOUNTED FOR ON 33013 1260. R 06/93 H ~ 0 Ul ~ Q Q gH'gR4H XOQ

gDMOW I g&O)Hw ta x v tI3 H Hg00

M 8 0 r. 0 L E. CINNANUCLEAR POWER PIANT nseervke ~n Beunday Une Lbt Thitd Inspeedon Interval

PMD No,t 33013-1265.1 A Qass t I Systetn .: CVCSCHARG INC Comp Types PIPINC 0H RGAE ISI Size IMtns Exempdon NDE Une No. ~FI . MsttL ~in. ~in. Method

2CH5.2501 RG300CVC 700 ~1001 A.lI h376 2.00 IL344 SUR CVCS AUXSPRAY FROM 9313 T0 297. R 06/93 2ACH5-2501 CVC 700;-701 24CH.1002 h-27 A376 2AXI a344 SUR CVCS ALTCHARGINC FROM 9315 I0 393. R 06/93 2BCH5.2501 A-25 A376 2AN a344 SUR CVCS CHARGING FROM 9314 '10 295. R 06/93 H 2CCH5.2502 CVG4XI;WI 2-ACH.1001 A.26 A376 2Am 0844 SUR CVCS ALTCHARG FROM 3923 TO 383A R 06/93 FJ2 2HCHS-2501 A32 2AO 0344 SUR VALVE302C I0 RCP.L A 06/93 0 2HCHS 2502 A32A 2Am 0344 SUR VALVE304 B T0 VALVE302C. A 06/93 2ICH5-2501 A31 2AN L344 SUR VALVE302D T0 RCPT h 06/93 214215.2502 A31A 2AO 0344 SUR VALVE304A I0 VALVE3020. h 06/93 XOX H HQH gOM~IOQ

H II7 0 + II7 g II) Ho H g

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0 'k IL E. GINNA NUCLEARPOWER PLANT Insaviee Esarnination Bonndary L(ne Ust TIrirdInspeedon lntaral

P&ID No-t 33013-1265-1 (2ass t 2 0 5)stan t CVCSA3IARGING Comp ~t COMPONENIS H 0 RG&E GEbat ISI She Une No. Line No. ~FI . MarrL ~in. Po T~an In7 Line deseri 'ernarls

A4 OAN OAXN IWC 1222(h) 2300 525 REGENERAIIVE HEAT EXCHANGERA. R 06/93 A4 OAO IWC.1222(h) 2300 525 REGENERATIVE HEAT EXCHANGER K R 06/93 A4 OAN 0.000 IWC 1222(A) 2300 S25 REGENERATIVE NEAT EXCHANGER C. R 06/93 H 1265 B.7 OAN OA)00 IWC m 1222(h) 2450 100 SEAL INJECTION FILTER L R 06/93 (/) 1265 B-7 OAO OAXN IWC 1222(A) 2450 1007 SEAL INIECTION FILTER L R 06/93 0

R H X A

HL u)H tO g td O (/) OW HIOgI() 0 40 Hp H 'g 0 I R E. GINNANUCLEAR POWER KANT Insetviee Exam(nation Une Ust TMnI Inspecdon~Interval

9&IDNo t 33013.1265 I O Qass .: 2 System .: CVCSCfIARGING Comp T)pet PIPING H 0 RG&E GEbert SWRI ISI Sine Thine Exemptwn Une No. UUnneeNo. Une No. ~PI . MatrL ~in. ~in. Po ~Tern In? Une desert 'emarts

3()CH 2502 CVC.1100 N/A A312 3AI a 438 IWC l~(A) 2450 100 2'EE ON 3ÃCH.2502 PAST VALVE275. R 06f93 3RCH.151 CVC 200 N/h A312 ZOO 0.120 IVQ 1222(A) 140 40 PEN 108 IO 3 X 2 REDUCER R 06/9$ ~ =I 3RCH.2502 CVC 1100 N/h A312 3A)0 a438 IMiQ 1222(h) 2450 100 2'EE ON 3t)CH 2502 TO 1ST 2'DCR TEE . R 06/93 2hACH.2502 CVG60O,CVG601 A3IA A312 2AI 0344 IViiC1222(h) b5 2450 100 PEN 106 IO VALVE304/L R 06/58 (/) 2ABCH.2502 CVCSOO,CVC501 A42h A312 2Am 0344 IWC1222(h) 2450 100 PEN 110 'IO VALVE304IL R 06/93 0 2AVZH.151 CVC200 N/A A312 2AXI 0.109 IWC 1222(h) 140 40 3RCH.151 TO VALVES362A &385A. R 06/93 2DCH5.2501 A-29 2AO OAK)0 IWC 1222(A) REGEN HEAT EXCHANGER TO VALVE9314. R 06/93 2ECH5.2501 A.ll 2A)0 a000 IWC.1222(A) 2DCHS 2501 TO VALVE9313. R 06/93 C H 2PCH5-2501 A.27 2AO OAX6 IWC 1222(A) 2D43I5-2501 TO VALVE5815. R 06/93 R 0 2GCH5.2502 A30 2A6 OAXO IWC 1222(h) REG EN HES TO VALVE370L R 06/93 2HABI2502 CVC 1100 N/A A312 2AS 0343 (WC 1222(h) 2450 100 3t)CH 2502 PAST VALVE323 TO PEN 102. R 06f93 + tO 2IZH 2502 CVC 1100 N/A A312 2.00 0344 IWC 1222(A) 2450 100 2'DCR TEE ON 3R43(.2502 TO PEN 110. R 06/93 H 2ICH.2502 CVC1100 N/A A312 2.00 0344 IWC 1222(h) 2450 100 2'DCR TEE 3RZH 2502 'iQ PEN 106. R 06/93 O (O 2K'.2502 CVC1100 N/A A312 2A)0 0344 IWC 1222(A) 2450 100 2'EE ON 3NCH 2502 TQ KH09. R 06/58 2LCH.2502 CVC.1100 N/A A312 2AI 0344 IWC 1222(A) 2450 100 2K~-2502 PAST VALVE303 B 'IO SW FIL2. R 06/93 2M'.2502 CVC.1100 N/A A3i2 2Am 0344 IWC 2'EE 1222(h) 2450 100 ON Bt)CH.2502 TO KH09. R 06/93 I-I e 0 2NCH.2502 CVC.1100 N/A A312 2A!0 0344 IWC 1222(A) 2450 100 2MAUI2502 PAST VALVE303A TO KH08. R 06f93 2PZH 2501 B34 2A!0 a000 IWC1222(A) 2AVCH.IS) TO RC PUMP A. R 06f93 gtOH 2TAUI 151 SS I A312 220 0.109 IWCI222(h) 140 40 3RCH.151 TO VALVE314. R 06/93 0 2VCH.151 Nfh A312 2A!0 0.109 Phd 1222(A) 140 40 2AVCH 151 TO 2 X 35 RDCR R 06f93 H g 0 2WCH 151 SS I A312 a109 IWQ 1222(A) 140 3'DCR ON 3RCH.151 'iO VALVE362K R 06/93 '0 2X42I-2501 S3 A376 2AO 0344 IViC1222(h) 140 40 VALVE3628 PAST VALVE270B TO RC PMP IIL R 06/93 0 2ZCHG502 N/A A312 2A!0 0344 IWC.1222(A) 2450 100 PEN 102 TO VALVE392IL R 06/93

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1 R E. GINNAh UQEAR POWER PLANT Insarnte Examhadon Onnalsry Une Ust Ih(nl speetion lntaval

PAID No t 33013 1265.2 A (2am. t 2 Systan. t CVCSCHARGING H Comp ~t COMPONENIS 0 RG&E 151 SIte Thkns NDE Une No. ~Fi . Matrk ~ln. ~ln. Metlrsal Po ~Tern In? Une deseri 'emarks

PCHOI A 1265 N/A OAN OAXN IWC 1222(h) 2450 100 CHARGING PUMP h, MFG AIAX. R 06/93 KHOI3 1265 N/h OAN OAXN IWC.1222(A) 2450 100 CHARGING PUMP B, MFG AJAX. R 06/93 H PCHOIC 1265 N/A (LOO 0.000 IWC 1222(h) 2450 100 CHARGING PUMP Q MFG AIAX. R 06/93 SCHI I 1265 B6 OAN OAXN SUR/VOL 2450 100 24'HARGING PUMP POISE DAMPENEIL R 06/93 CI 0) Q g H W A + HIDEI() H $ '0 O (A) o F3

H IA) 0 (O ~ < g I() H0 H g 0

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PMD No: 33013 1265 2 O Qass t 2 System.: CVCSCHARGING Comp Type: PIPING 0H RG8iE 0Ebert SWRI Else TMtns NDE U R Line No. Une No. MatrL ~in. ~h. Metliod Po ~Tern In? Une deserI '/remarlts CVC851 PULSE DAMPENER B6 A312 MO 0.906 SUR/VOL 2450 100 3'EE ON 3K'-2502 TO PULSE DAMPENEL R 06/93 8BCH.2502 CVC852 POISE DILRIPENER B6 A312 BOO 0.906 SUR/VOL 2450 100 3'EE ON 3LCH4502 TO PULSE DARIPENEL R 06/93 8CCH.2502 CVG853 PULSE DAMPENER B6 A312 ILOO 0.906 SUR/VOL 2450 100 3'EE ON 3M'-2502 TO PULSE DAMPENEL R 06/93 H 4CH.151 CVC.1200 N/h A312 4AO 0.120 IWC.1221(A) 30 100 4BCH. 151 PAST VAlVE357 TO RViST. R 06/93 4DCH.I U) 5l N/A 4'LOIN IWGI222(A) 4CCH.I 5l THRU 358 TO 4CH-151. R 06/93 0 3GCH-151 CVC 1000 N/A A312 380 0.120 IWC 1222(h) 40 140 VALVE313 1O PEN INL R 06/93 3K431-2502 CVC851 B6 A312 3AN 0A37 IWC 1222(A) 2450 100 CHG PUMP I DSCHG PAST VALVE287 TO TEE ~ R 06/93 3!AH-2502 CVG852 B6 A312 300 OA37 IWC.1222(A) 2450 100 CHG PUMP 2 D5CHG PAST VALVE288 TO TEE ~ R 06/93 H 3M'-2502 CVC853 g B6 A312 3AN OA37 IWG1222(h) 2450 100 CHG PUMP 3 D5CHG PAST VALVE291 TO 1EE . R 06/93 XO 3NZH-2502 CVC.1000 N/A A312 3AC OA38 IWC 1222(A) 2450 100 POISE DAMPENER PAST VALVE289 TO 1ST TEE R 06/93 3PCH.2502 N/h A312 3AN 0.438 IWG1222(A) 2450 100 PULSE DAMPENER PAST VALVE290 PUL DAMP. R 06/93 2FCH.2502 N/h A312 2AN IL344 IWG1222(A) 2450 100 PUISE DAMPER TO CHECK VALVE370L R 06/93 +LOH 2GCH.2502 N/A A312 2AN tL344 Ilh'@1222(A) HU)g 2450 100 2FCH.2502 THRU 384C TO DAMPER. R 06/93 O (/)

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t L E. GINNANUCLEAR 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 0H SWRI ISI SIse Ihhrs Exempdon NDE Une No. ~FI . Marrl. ~ln. ~in. Merhod Po ~Tern In? Une deserI 'emarks Revised

ICHOTA 1266 N/A OAN OAXN NOT S~ Xl 5 210 - BORIC ACIDSIQRAGE TANKA R 1 l/91 ICH07B 1266 N/A OAN OAXN NOT SECT XI 5 210 - BORIC ACIDSIQRAGE TANKL R II/91 OM

g H X 0 H~g+ 8) M O 02

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0 IL E. CINNANUCLEAR POWER PIANT Inservice hrnlnatkat Bonndary Une Urt IIrlrdlnsPeenon Interval

P&ID Nca.t 33013-1266 O Chas t 2 Syrtern. t CVCS.BOIUC ACID H Comp Iypet PIPING 0 RG&E CEbert SWRI ISI SIte NDE Une Nca Une Nca Une No. ~FI . MarrL ~in. Method Po ~Tern In? Une dercri '/remarks

SASI0018 SI~ SSI-2001 8 15 A312 0322 SUR/VOL 5 210 Y BORIC AQD TANK8 TO 8 X 8 X 8 IEE . R 11/91 8SSIOOIA SI~ 851-2001 8.15 A312 L322 SUB/VOL 5 210 Y BOAICAQD TANKh '10 S X S X 8 IEE . R 11/91 H ~ 3ACH.I5 1 A SI~ Nlh ILOOO IWC 1221(A) 5 210 Y BORIC AQD TANKh '10 LOOP SEAL FLANGE. R 11/91 3SCH.ISIS Sl~ Nlh A312 0.120 IWC.1221(h) 5 210 Y BORIC AQD TANKB I0 LOOP SEAL FIANCE. R 11/91 Q (I) ~ 2ASI.I5 IB SI~ 8-15 A312 0.154 IWC.1221(h) 5 210 Y 8 X 8 X 2 IEE ON SASMOI8 '10 VALVE345. R 11/91 2SCH.I 5 1 B Sl~ N/A A312 0.154 IWC.1221(A) 5 210 Y BORIC AQD TANKB TO HCV 105. Q Q 2CSI.I 5 IA SI~ 8.15 A312 0.154 IWC 1221(A) 5 210 Y 8 X 8 X 2 IEE ON SSSIQOI A IO VALVE331. R 11/91 QQH 2DCH 15 lb Sl~ N/A A312 0.154 IW01221(A) 5 210 Y BORIC AQDTAIrI(A I0 HCV 104. XHR WOW

LD H + H tO Q $ ~ C) M O td ~ I H X Er( U ~ tO 0 H H g tI) H HgQO e(E)

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It R. F GINNANUCLEAR POWER PIANT Inservke Examlnsthn Boundary LIne IAst TMrd Inspeedon Intessral

F&IDNo t 33013-12701 O Chss. t 3 W System-: WASTE DISPOSAI LIQUIDDRAINS Comp ~s COMPONENIS 0 RG&E GtTbert SWRI 151 Size Tlrfsrs NDE Une No. Une No. Line No. ~fi . MatrL ~In. ~In. Merliod Po T~em Iat Une deseri 'emarks fWD03 N/A 0.00 OAI IWD l~ «275 «200 ULTRAFILTRATIONSYSTEM. R 06/93' FWD09 N/A 0.00 0.000 IWD I22sk2 <275 <200 WASTE BLTEIL 06/93 PWD12 N/A OAKs 0.000 IWD 12202 <275 <200 WASTE HOLDUP TANKPUMP. R 06/93 H m TWDI0 N/A OAO 0.000 IWD 12202 <275 <200 WASTE HOLDUP TANK. R 06/93 0 M

L H td O + H tAI H +ONtEI g

H tI3gII3 O 0 H g

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I R E. 0NNANUQEAR POWER PIANT laservfce Examlnedon Boandtrry Une Ust Thhd lnspecUoa Interval

PAID No t 33013-1270-1 assr r 3 O Systcrn t WASIE DISPOSAI UQUID DRAINS Comp IPpe: PIPING 0 RQkE 0rIbert ISI Slee Ihtns Exemlmoa NDE line No. Une No. ~Fi . MetrL ~h. ~in. his Method Po I~em lInl LIne deseri n/remsrts

2A.WD0-151 N/A 200 0.143 IWD 12/0.1 I WST HOIDUP IXTO )792, WHT PUMP, 5 16 IOA R 06/93 H 0 Ul

0 H WO + H LED H LO g 0 M t." H tO O H tO g g 'LO H0 H g

R 8 0

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'l IL E. GINNANUCLEAR POWER PLANT tnsavke Exsmlnetlon Bonndsty line Ust Thltd Inspeetbn tntavsd

PAID No-: 33013.1272-1 O CInss-.: 3 Systan: WASTE DISPOSAI UQ.RC DRAINTK Comp Type: PIPING H Q RG8 E LSI Sixe Tidtns Exanpaon NDE line No. ~Fi . MatrL ~In. ~b. Resls Method Po T~em le? Une deseri 'ansths Radsed

+Wm iS> 4AQ OAXXt IWD-1220.1 ? FUEL TRANSFER CANALTO VALVE1711. R 06/93 H ~ Q M ~ g Q ROC hl P g'LOHg~ o tn o hj— I CgR

tE? H HRQQem

M 8 n 0 I

K R. E. GINNANUCLEARPOWER PIANT Inserrdee Examination Oomndary Une Ust Third lnspeetkrn Interval

P8>ID No r 33013-12722 O Chss t 2 System: WASIE DISPOSAI UQ-RC DRAINTK H Comp I)per PIPING 0 RG8>E 0Bberc SWRI ISI Size N No. U Une Une No. ~Fi . MarrL ~in. Po ~Tern In? Une deseri 'emarks

4A.WD 151 RHR400 N/A A312 4AS (L120 IWC I~A) 2 80 PEN 143, TO 8431, 4 X 3 RDCR BEIQRE 1721. R 06/93 4OWD-151 RHR~ N/A A312 ILI20 IWG1222(A) 2 80 3A IO 3C. R 06/93 H 3A WD.151 RHR~ N/h A312 3.00 0.120 IWC 1222(h) 2 80 4h IO VALVE 1721> 4C. R 06/93 rn 3B.WD 151 RHR~ N/h A312 3.00 0.120 IWC 1222(h) 2 80 VALVE1722 TO 4C R 06/93 0 (/) BAWD.151 RHR400 N/A A312 3.00 0.120 IWC 1222(h) 2 80 4C IO VALVE1003 IL R 06/93 3F WD 151 N/h 300 0.120 IWC 1222(h) 4 X 4 X 3 TEE ON 4C TO VALVE1003A. R 06/93 2A.WD 152 N/A (k000 IWC 1222(h) PEN 129 TO 1716A, 1ST TEE W/RDCRS. R 06/93 H g H XO

+ LO H O M & LTj HLOO~ kO (O Q g 'LO 0H H g 0 g

M (D 0 0 I f I IL E. GINNANUCLEAR POWER PlANT Insetvke Esuunlnsdon Boondety Une ust Thhd Inspeedon Inten>al

PMD No t 33013-1272-2 O CLsss: 3 t3 Systetn t WASTE DISPOSAI UQ RC DRALITI( H Comp Type: PIPING 0 RUTE 0Rhett SWRI ISI Size Thkns Rmnpdon NDE >> 4 > U N* ~F! . ManL ~in. ~tn. Besls Metho>I Po ~Tern In? LIne deseri 'emeths

3.WD2 151 3.00 th216 IWD.122ILI 7 FUELTRANSFER DRAINTO 17950> 1722. H QM

g H rWO + 'LO M H gONtly >g I

t17 H H tlygO g LO H o H 'g d K E. CINNANUCLEAR POWER PIANT Snsenke Examinatron Boanday Une Ust IMrdInspeedon lntaval

P&IDNo .: 33013.1275.2 A Gast: 2 System .: WASIE DISPOSALCAS H2 RECOMBIN H Comp Type: PIPINC 0 RG&E CBbat SWRI ISI Size Ihkns Exemp6sn Lbe No. Une No. Une Nrx ~FI . MatrL ~in. ~ln. Po T~em In? Une rteseri 'emarlts RRevtsrrI

2A WDG-152N N/h IWC 1222(A) c275 c200 - PEN 202 TO RDCR BEPORE VALVEIOS4IL R 05/P3 2B.WDG 152N N/h IWC 1222(A) PEN P304 TO VALVE1084A. R 06/93 0 M

X H X A

HIOHtO'g gOM~ I HIOO IO Q LO 0H H g

Ul 9 0

I 0

ILE. GINNANUCLEAR POWER PIANT Insavice ExnmInntion Bontxhry LIne Ust Thhd Inrpeetbn Intavnl

PAID No t 33013.1275-2 O Chss t 3 Sprtan t WASTE DLSPOSALGAS H2 RECOMBIN Comp~ PIPING 0H RGBE 0Bbat SWRI ISI SIte IMms Exanpnon NDE Une No. Une No. No. . Une ~PI MstrL ~h. ~b. Bssis MettrrsI Po ~Tern In? Une desert 'fremsrIrs

2CWDG-152N N/A 200 OAN0 IWD.122Q I <275 <200 - PEN202'IQIM25,N25A,3/O'REDCL A QSr93 2DWDG.152N N/h 2'1000 IWD 122sl1 <275 <200 - PEN30iTOIM33,5433A,3/<'REDCL = A06/93 H 0 M

re H R O

+ 'LO He@H O Ul OX >re H LI3 O HEI g H Q 0 g0

M 8 n Pe 0

0 R. E. OINNANUCLEAR POWER PIANT Insersriee hmlnrnkrn Boundary Une Ust Third Sspeetion Interval

PMD No-t 33013.1277.1 Casa .: 2 System: STEAM GENERATOR BIOWDOWN Comp ~: CONPONENIS H0 RCM OtTbert SWRI ISI SIse Thkns Exampdon NDE Une No. Une No. Une No. ~Fi . Matrl ~b. ~h. Basis Method Po ~Tern tnt line deseri '/remarks Revised

Eh!SOIA B-I SUR/VOL 715 505 TIVS COMP ACCOVNTED FOR ON 33013.1231. R 0dr/93 EM501B Bl SVR/VOL 715 505 THIS COMP ACCOUNTED MR ON 33013.1231. R 06/93 H Q M

g H X 0 I H~ tO H gOM~tOQ I H~gIO 0 IO oH H g 0

Ul ID 0 0 It

I' R. E. GINNANUCLEAR 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 CBbert SWRI ISI Site Une No. line No. Une No. . MatrL ~FI ~ln. Po ~Tern In? Une deserl '/remarlts 3A.BD600. IA N/A A106 0.000 IWC1222(A) 1005 547 Y TEE 2A-M5600 lh 6 28 T0 5701. R 06/93 225D.BD600 lh N/A (1000 lÃC1222(A) VALVES701 TO VALVE5738. R 06/93 225DBD600.1B N/h 0.000 IWG1222(h) VALVES702 TO VALVE5737. R 06/93 H 2A.M5600.1A SCB 100 N/A A106 IL218 IV&1222(h) 1005 547 N. NOZZIE T0 FIRST TEE CIRTH WFID. R 06/93 2A-M5600. (/l IB SG8-200 B31 h106 IL218 15%.1222(A) 1005 547 N. NOZZLE T0 FIRST TEE C IRTH WELD. R 06/93 0 28-M$ 600 lb SG8-100 N/A hl06 IL218 IWG 1222(A) 1005 547 S. NOZZIE T0 HRST TEE CIRTH WFID. R 06/93 28 MS600 IB SOB-200 B31 A106 0218 IWO1222(A) 1005 547 S. NOZZLE 10 FIRST TEE GIRTH WELD. R 06/93 2C M5600 I8 SC8-200'400 B31 A106 IL218 WGI222(h) 1005 547 2A M5600-IB It 28 TO VALVE5702. R 06/93 X H W A

H+NOH IO g + O (/) H100~ I Cl Q 'LO H H g 0

NO A

O) (D 0 0 R. E. GINNANUCLEARPOWER PIANT lnservhe Examinathn Boundary Une Lht Third Inspeenon Interval

BkIDNo r 33013-1279 O Class r 2 System r KST ACQDENTSAMPUNG PIPING H Comp Types Q RGB GBbert SWRI ISI Size Tldms Exemption NDE Lbe No. Une No. Une No. ~Fi . MatrL ~in. ~in. Bash Mctbod Po ~Tern In? Une deserf remarits RReehed

3hSS-151 3AO t1000 IWG 1222(A) PEN P107 TO VALVE172L A IVPI H ~ m Q Ul ~ g Q WHYXOZ

IE) H 4 H $

H M7 8 5 VC tE? H HgQQWe IL E. GINNANUCLEAR POWER FIANT Inservtoe Examination Borrndary Une Ust TInnlI spection Interval

P&ID No..: 33013 1863 Qass t 2 System t CONTAINMENTHVACSYSTEMS H Comp T)re PIPING 0 RG&E GBbert SWRI 151 Slee Une No lliinneeNo. line No. ~FI . MatrL ~In. Po ~Tern fat Lme deseri 'eaaarfs

IASUCT N/h Oi)0 Did IWC 1222(B) 60 120 VLV1559 TO 'h'ONT REQRC FAN A SYS. A OI/92 IAB.RET N/h OAO IWC 1222(B) 60 120 VLV 1562 IIIRU PEN 305 'IO CONIINMENT. R 06/93 IBSUCT N/h OAR OAXO IWC 1222(B) 60 120 VLV1556 TO 'IP CONT REQRC FAN B SYS. h Ol/92 hj Q IGRET N/A Oi)0 (LIMO IWG1222(B) 60 120 VLV1574%IRU PEN 124 'IO CONIINMENT. h 01/92 OM IGSUCI' N/A OAS OXNO IWGI222(B) 60 120 VLV 1571 TO "VCONT REQRC FAN C SYS. A 01/92 DRET N/h OAS IMOO IWG1222N) 60 120 VLV 1568%IRU PEN 203 IO CONIINMENT. A 01/92 IDSOCT N/A aoo IMOO IWG1222(B) 60 120 VLV1563 TO 'O'ONT REQRC FAN D SYS. h Ol/92 H g H WO Hu)Z+IDH O M pVX'4 0 HIDE'4 Ho H g 0

U) (t) 0

I 0

0 k I

I R. E. GDINA NUCLEAR POWER PIANT Inseriee Kxamhsthn Boundnry Lhe LIst Third lnspeethn Interval

PAID No: 33013-1865 Chss: 2 System: CONTAINMENTHVACSYSTEMS Comp TPpet PIPING

RGAE 0ihert 151 She Thhrs Exemption NDE une No. IIne No. ~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 I hf Q M

g H WO > tl)H H II3g d +ON OW

IQ t3

H 2e O

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I 0

0 P

V L E. GDINANUCLEAR POWER PIANT Inserviee Xxaminadon Botmdary LIne ust Thhd tnspeedon interval

PBID No-t 33013-1866 Chns: 2 Gilbert System t CONTAINMENTPURGE EXH 5 MONIT Comp~: PIPING

SWRI ISI Size TIdms Exemption NDE Lbe No. IIne No. ~fi . MatrL ~In. ~in. Basis Method Po ~Tern In? une desert nrremsrts

N/A 36AQ ILGOG IWC 1222(B) 36'URGE EXHAUSTIHRU PEN 300.

0 M ~ g Q gH'g %OR

'LI2 H HQQo e co RCW

M 8 n

0 I

II IL E. GINNANUCLEAR POWER PIANT Insavke Exnmlnsfion Oottndery Line Ust 11drd speetion lntavnl

BIFID No t 33013 1870 CIoss t 2 Systems HVACAIDQUARYdc INIEILKBLDG. H Comp TTPet PIPING 0 GBbat SWRI ISI Site Tldms Exanption NDE Une No. Une No. ~Fi . MstrL ~ln. ~in. Bssis Method Po T~em In7 Une desefi '/rernsrks Revised

N/h 6AO (1000 IWC1222(C) 110 VALVE7P70 PAST PEN P132 TO VALVE7971. R 06/93 H QM Q C H X 0 HQH~ I gOUl o F3 pVWI H t17 0 t17 g LI7 pH H g 0

M 8 0 r. 0 t'

I ~ IL E. GINNANUQZAR POWER PIANT Insavice Estnminntion Ronnday Une List 'IIdnI inspection Intavnl

P8 ID No t 33013-1882 O Qass: 2 Systan: CONTAINMENTBREATHINGAIR H Comp Type: PIPING 0 RGB GEbat SWRI ISI Size TIdms Exempdon NDE UUnne Une deseri rerrnrirs Une No. eNo. Une No. ~PI . ~ ~I ~~~ 8 Mctbod Po T~em ln7 6.AT-1504 Nth 6'F000 IWC 1222iC) <275 <200 VALVE7443 TIIRU PEN P317 IO PIANGE. A I UPI 6 LT400 Nlh 600 0.000 IWC.1222(C) <275 <200 VALVE7444 THRV PEN P313 IO PLANGE. R 06/93 H ~ OM ~ g Q HAHgH'g %OR

HÃR5 'Q H H@Oowe

0 lf

1 IL E. GINNANUCLEAR POWER PLANT lamvke Examhucha Boundary LIne Lbt Thinl nspeeaoa interred

P&IDNo t 33013-1886.2 Chess —t 2 System: SERVICE AIR Comp Type: PIPING H 'g0 RG&E GBbert ISI Size NDE LIne line No. No. ~Pi . MntrL ~in. Method Po ~Tern In? Une deseri remarks Revbed

2AS 0AXO IWC.1222(A) VALVE714 I 'IIIRU PEN P310 TO VALVE7226. R 06r93 H 0 M

XH WO V H~g+IOH O M

'LO Q tly H0 0

g 0 Q

M nI 0

0 L E. GINNANUQEAR POWER PIANT Insetvtee ExamInathn Bonndary Une 11st ThIrd lnspeethn Interval

P&ID Nm.: 33013-1887 O Chss.. t 2 Systmn t INSTRUMENTAIR CONINMTBLDG H Comp ~ PIPING 0 RG&E GBbert SWRI 51 SIte 'Ihtns Exempnon NDE Une No. Lbe Nsx Lbe No. ~FI . MatrL ~h. ~in. Method Po T~em In7 Lbe deseri 'emarks Revised

2-IA.1258 2AS DIXIE IWC 1222(A) VALVE5392 THRU PEN P310 TO VALVE5393. A 11/91 H ~ OM ~ N Q

s2s H 2g WOW

H sEs +otOOXII3 $ ~ >I Wma

'LO H HgOowe

U) 8 0 Tt po 0

0 'v IL E. CINNANIIQZARPOWER PIANT Insavite Examhrrrha Une Urt Tldrd Inrpecdon~Intavrd

PEdDNo t 3301319084 Cher t 2 S)rtan t PiUMARYWATER TREATMENT Comp T)per PIPINC H Q f RGB CGbat SWRI ISI Size TIdrno NDE Lhe No. Une No. Line No. . MrrrrL ~Fi ~h. ~h. Method Po ~Tern In? Lhe desai remorirs

3 PW.125 I N/A IVi&1222(A) 3 X 2 RDCR OUTSIDE TO 3 X 2 RDCR INSIDE. R 06/93 2.PW 125-1 N/A IWC 1222(A) VALVE8418 TO 3 X 2 RDCR ONSIDE CONTNMT. R 06/93 e 2A.PW.125'I N/A IWC 1222(A) 3 X 2 RDCR INSIDE CONTNMT H TO VALVEIM19. R Odr/93 m 0 M

g H Ez) 0 hf HQH>r gOM~ tO '2c I tO O ~eHH kg ()

gh9 Q0

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0 R. E. GINNANUCLEAR POWER PIANT Insavke Examfmnion Bonndary Une Ust 'Ihbd lnspeedon Intetval

PMD No t 33013.1915 0 13ass t 2 System t HEATING SIKAId5 CONDENSATK H Comp~ PIPING 0 RGAE GBbett SWRI Size Thhts Exempdon NDE Une No. Une No. Une No. ~h. ~in. Rasls Method Po T~em In? Une deseri 'emasin Revised

PENEIRAIION301 TO VAIVE6165. h I1/91

0 M

XAg H

H>eH +ONtO g

H 'LO O H tO g g g tO 0H H g

R. E. GINNANUQZAR POWER PIANT Insnviee Examinadon Boundary Une Ust TMtd Inspection Interval

P8 ID No..: 33013-1991 0 Qass. t 2 System...: FIRE PROTECllON IN CONTAINMENT Co p'Iype: PipiNG H 'g0 RGAE GEbert SWRI ISI SIse Tides Exampthn NDE

Une No. Line No. Une No. ~F1 . MatrL ~in. ~in. Basis Metissd Po ~Tete In? Une deseti n/retnarka eh-FS-152 N/A ext0 OAXO IWC 12t)2IA) 135 80 - VALVE9227 'IO VALVE9229 IN CONTAINMENT. R 11/91 2A.F5400 N/A 2.00 t1000 IWC.1221(A) VALVE5129 ATPEN P 103 TO 5130. A 11/91 H 0 N

H ROQ

H> u) H 113 g 0 0) Hingtd) O <-oLI) H H Q

F/) 8 n 0

0 It t. t L E. GUINANUCLEAR POWER PIANT Insaeice Exeminstha Bc rrrsLsry LIne Ust Thinl Inspecdon Intavei

PMD No t 33013-2279.1 O CLsss.: 3 System: WASTE EVAPORATOR SKID H Comp Typa COMPONENTS 0 ROTE GBbat SWRI ISI Size Thkns Exempthn NDE Line No. line No. Une No. ~Fi . MstrL ~b. ~b. Methotl Po T~em In? line Cesal remsrhs

N/A IWD 1220.1 WASTE EVAPORATOR CONCENTRATOIL R 06/93 N/A IWD.1220.1 WASTE EVAPORATOR FEED TANKPUMP. R 06/93 H ~ N/A IWD 1220.1 WASTE EVAPORATOR FEED TANK R 06/93 ON ~ gQ QgHXHR %OR WP

~HMT el'C)NOR I taea >ILD H H O g '4 H HQOOe TT2

cs ,1 L E. GINNANUCIEAR POWER PIANT Ineervlee Eaunlnathm Une Iirt Thlnl Inrprethrn~lntereaI

P&lDNo t 33013-2279-1 13 O Cher —:3 System: WASTE EVAPORATOR SKID H Comp T?per PIPING 0 RG&E 0Qbert ISI N N line No. Pirl, Marrl. ~Tern In? line dererl remarks

MA.WD9 N/A IW 0.000 IWD.122a I ? WEFT TWDOB TO 2642D, WEFT PUMP. R 06/93 ISB-WD9 N/h 150 OAXrO IWD 1220.1 ? Ih TO SWDI4, 26427 .7Sh R 06/93 H MSA.WD9 N/h OAXS IWD 1220.1 ? WE CONCENTRATOR EWD07 'TO 2620C, SWD I4 R 06/93 OM

NTN H WO gLOH LI7 Q ~ O U? ~ I H HeO g LI7 Hp H g 0

V? O 0 r- 0

0 QUALITY ASSURANCE MANUAL PAGE 6 GINNA STATXON Section 1 of 6 EFFECTIVE DATE: December 31, 1993 ROCHESTER GAS 8 ELECTRIC CORPORATION SIGNATURE DATE

TITLE PREPARED BY: B APPENDIX QUALITY R. E. GINNA NUCLEAR POWER PLANT ASSURANCE INSERVXCE INSPECTION PROGRAM REVIEW: FOR THE 1990-1999 INTERVAL ALLOCATION TABLES 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. TITLE: FIEV. QUALITY APPENDIX B Section 6 2 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 2 of 6 ALLOCATION TABLES

ASME CODE RE UIRED

Class 1 Third Interval Scheduled/Percent CatecaCor Total Receuired Period 1 Period 2 Period 3 B-A 10 2/28.5% 2/57.1~o 3/1004 B-B 12 4/57.1% 2/1004 1/71.49'/45.8>o B-D 30 24 5/20.8>o 13/100>o B-F 15 15 5/33.3~ 3/53.3% 7/100'7/100% B-G-1 245 195 49/25.1~o 49/50.2>o B-G-2 22 9 3/33.3% 3/66.64 3/100'3/100~o B-J 536 132 28/21.2~o 51/59.8o 1/1004

B-M-1 8 . 2 2/100< 0/1004 0/100>o B-M-2 12 4 (*) 1/ 100+o (3 remaining, only if disassembled, Per RR g5.) if disassembled. B-N-1 1/33.3% 1/66.64 1/100% B-N-2 0/0% 0/0o 1/100~o

I B-0 20 0/04 0/0>o 3/1004 3/27.2~o 4/63.6

k TITLE: REV. QUALITY APPENDIX B Section 6 2 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 3 of 6 ALLOCATION TABLES

Class 2 Third Interval Scheduled/Percent ~Cate or Total RecCuired Period 1 Period 2 Period 3

C-A 22 13 3/23.0% 4/53.8~o 6/100~o C-B 30 18 6/33.3% 6/66.6~o 6/100~o C-C 131 124 29/23.4o C-F-1 677 53 17/32 '~o 19/67.94 17/1004 C-F-2 387 30 10/33.3>o 10/66.64 10/100>o C-H 72 124 39/31.4p 43/66.1% 42/100>o Total 1319 362

Class 3 Third Interval Scheduled/Percent CatecaCor r Total Receuired 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 30 164 53/32 ~ 3+o 51/64 ~ 3~o 60/100< Hydro/Leakage Total 175 305 I TITLE: REV. QUALITY APPENDIX B Section 6 2 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 4 of 6 ALLOCATION TABLES

Class 1 2 & 3 Su orts Ori ional Distribution to 1986 Code Third Interval Class Scheduled/Percent ~Grou Total Receuired Period 1 Period 2 Period 3 Class 1 159 142 19/13.4~o 55/52.1>o 68/100< Class 2 377 368 93/25 3+o 134/61 6+o 14 1/ 100~o Class 3 477 141 38/26.94 54/65.2>o 49/100>o Total 1013 651 150/23.0% 243/59.6< 258/100%

Inco oration of Code Case N-491 with 1986 Code Revised Distribution

Period 2 Period 1 Completed Program Category Total Completed /Credited Period 3 Reference Item Su orts Re uired Credited Scheduled Scheduled 1986 Code 44 Req. for Completed Period 1 F-A,B,C 1013 651 150 199 253 and '93 All Completed Scheduled Scheduled Outage Items (23.0%)

Code Case F-A 114, 32 10 Credit 6 Credit N-491 for F1.10 5 Sched. ll Sched. Period 2 ( Starting F-A 358 58 19 Credit 17 Credit '94 Outage) F1.20 2 Sched. 20 Sched. and Period 3 F-A 467 50 17 Credit 12 Credit F1.30 4 Sched. 17 Sched. F-A 74 44 10 Credit 0 Credit F1.40 3 Sched. 31 Sched. Totals 1013 184 56(30.4%) 49 (57.0%) 79 (100%)

Au ented Re uired RCP Fl heel Pro ram: Third Interval Scheduled/Percent CatecaCor r Total Receuired Period 1 Period 2 Period 3

Flywheel 2 6 2/33 3+o 2/66 ~ 6+o 2/100> TITLE: REV. QUALITY APPENDIX B Section 6 2 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 5 ot 6 ALLOCATION TABLES

Reactor Vessel Au ented Pro ram Cate or B-A: Third Interval Scheduled/Percent CatecaCor r Total RecCuired Period 1 Period 2 Period 3 B-A 0/0> 0/O~o 3/1004

Hi h Ener Pro ram: Third Interval Scheduled/Percent CatecaCor r Total RecCuired Period 1 Period 2 Period 3 HE-CB 97 97 34/354 30/65.9~o 33/100~o HE-CC (*) 17 17 9/52.94 3/70.6~o 5/100% HE-DB 18 54 18/33.34 18/66.64 18/1004 HE-LK 2 2/28.5~o 2/57.l~o 2/ 1 00+o Total 134 174 (*) = 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 N/A 62 62 20 Comp. 6 Comp. Outage. (31.7%) 18 Sched. 19 Sched.

Code Case N/A 62 3 Credit 4 Credit N-491 for (F-A 0 Sched. 4 Sched. Period 2 F1.20) (27.3%) (63.6%) (100%) ( Starting '94 Outage) and Period 3 TITLE: REV. QUALITY APPENDIX B Section 6 2 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 6 of 6 ALLOCATION TABLES

Snubber Pro ram: Third Interval Scheduled/Percent CatecaCor c Total RecCuired Period 1 Period 2 Period 3 SN-VT (*) 149 1039 443/43.04 447/86.4% 149/1004 SN-FT 149 149 48/32 2~o 57/70 4~o 44/ 100~o

( Total 298 1188

(*) = 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 Period 1 Period 2 Program Category Total Completed Credited Period 3 Reference Item Su orts Re ired Credited Scheduled Scheduled Code Case N/A 93 19 0 Comp. N-491 for (F-A 0 Credit: Period 2 F1.20) 9 Sched. 10 Sched. ( Starting (47.3%) (100%) '94 Outage) and Period 3 QUALITY ASSURANCE MANUAL PAGE GINNA STATION Section 7 1 of 3 EFFECTIVE DATE: December 31, 1993 ROCHESTER GAS 8 ELECTRIC CORPORATION SIGNATURE DATE

PREPARED BY: TITLE j~* i2-f i3 APPENDIX B QUALITY R.E. GXNNA NUCLEAR POWER PLANT ASSURANCE ULTRASONXC CALIBRATXON REVIEW: BLOCK LXSTING APPROVE BY

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 DESCRIPTION MATERIAL SPEC.

6-SS-108-.134-1A-REG 6" D-SCHEDULE 10-SS-PIPE SA 312

6-SS-408-.280-2-REG 6" D-SCHEDULE 40-SS-PIPE SA 312

B-SS-108-.148-3-REG 8" D-SCHEDULE 10-SS-PIPE SA 312

8-SS-408-.322-4-REG 8" D-SCHEDULE 40-SS-PIPE SA 312

B-SS-160-.906-5-REG 8" D-SCHEDULE 160-SS-PIPE SA 312

10-SS-108-.165-6-REG 10" D-SCHEDULE 10-SS-PIPE SA 312

10-SS-408-.365-7-REG 10" D-SCHEDULE 40-SS-PIPE SA 312

10-SS-140-1.0-8-REG 10" D-SCHEDULE 140-SS-PIPE SA 376

'12-SS-SS-.156-9-REG 12" D-SCHEDULE 5-SS-PIPE SA 312

14-SS-10-.250-10-REG 14" D-SCHEDULE 10-SS-PIPE SA 312

14-CS-30-.375-11-REG 14" D-SCHEDULE 30-CS-PIPE SA 106

PL-1.187-SS-12-REG 1- 187 THICK-SS-PLATE SA 240

PL-.30-SS-13-REG .30 THICK-SS-PLATE SA 240

PL-3.5-CS-14-REG 3.5 THICK-CS-PLATE SA 533

9-CSCL-15-REG 9" THICK-CS-CLAD-VESSEL BLOCK SA 508

7-CSCL-16-REG 7" THICK-CS-CLAD-VESSEL BLOCK SA 508

5-CSCL-17-REG 5" THICK-CS-CLAD-VESSEL BLOCK SA 508

PL-3.0-SS-18-REG 3" THICK-SS-PLATE SA 479 TITLf: QUALITY APPENDIX B Section 7 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL ULTRASONIC CALIBRATION PAGE GINNA STATION BLOCK LISTING 2 of 3

IDENTIFICATION NUMBER DESCRIPTION MATERIAL SPEC. 6-SS-160-.719-19-REG 6" D-SCHEDULE 160-SS-PIPE SA 312

4-SS-160-.531-20-REG 4" D-SCHEDULE 160-SS-PIPE SA 376

3-SS-160-.438-21-REG 3" D-SCHEDULE 160-SS-PIPE SA 376

8.5-6-8-CS-22-REG REACTOR PRESSURE VESSEL NUT SA 320-L43

6-1-8-CS-23-REG REACTOR PRESSURE VESSEL STUD SA 320-L43

IR-CSCL-24-REG O.D. INNER RADIUS BLOCK SA 533

6-SS-120-.562-25-REG 6" D-SCHEDULE 120-SS-PIPE SA 312

FS/NS-CSCL-26-REG FLANGE AND NOZZLE SHELL BLOCK SA 533

IR-CSCL-27-REG NOZZLE INNER RADIUS BLOCK SA 553

CRD-SS/IN-.656-28-REG SS-CONTROL ROD DRIVE BLOCK SA 182

10-SS-140-1.0-29-REG 10" D-SCHEDULE 140-SS-PIPE SA 312

3.5-.625-8-CS-30-REG REACTOR COOLANT PUMP STUD ACTUAL STUD

5.375-3.5-8-CS-31-REG REACTOR COOLANT PUMP NUT ACTUAL NUT

1.187-8-7-CS-32-REG 1 187" DIA. X 7 THREADS/IN-CS-STUD SA 193

1.187-N-7-CS-33-REG 1.187" DIA. X 7 THREADS/IN-CS-NUT SA 194

1.125-8-12-CS-34-REG 1.125" DIA. X 12 THREADS/IN-CS-STUD SA 193

1.125-N-12-CS-35-REG 1.125" DIA. X 12 THREADS/IN-CS-NUT SA 194

1.250-8-7-CS-36-REG 1.250" DIA., X 7 THREADS/IN-CS-STUD SA 193

1.250-N-7-CS-37-REG 1.250" DIA. X 7 THREADS/IN-CS-NUT SA 194

10-SS-160-1.147-70 10" D-SCHEDULE 160-SS-PIPE SA 312

6-SS-X-1.1-38-REG 6" D-1.1" WALL-SS-PIPE SA 182

29-SS-X-2.5-39-REG 29" ID-SS-PIPE SA 182

SI/N-CSCL-40-REG SAFETY INJECTION NOZZLE BLOCK SA 508

27.5-CSS-X-2.4-41-REG 27.5" ID-CS-PIPE SA 351

29-CSCL-X-2.5-42-REG 29" ID-CLAD-CS-PIPE SA 508

5.437-SS-X-1.0-43-REG 5.437" D-1" WALL-SS-PIPE SA 182

PL-1.5-CS-44-REG 1.5" THICK-CS-PLATE SA 285

14-CS-100-.938-45-REG 14" D-SCHEDULE 100-CS-PIPE SA 106 II TITLE: REV. QUALITY APPENDIX B Section 7 1 ASSURANCE R-E- GXNNA NUCLEAR POWER PLANT MANUAL ULTRASONIC CALIBRATION PAGE GXNNA STATION BLOCK LISTING 3 of 3

IDENTIFICATION NUMBER DESCRIPTION MATERIAL SPEC. 18-CS-100-1.156-46-REG 18" D-SCHEDULE 100-CS-PIPE SA 106

4-SS-80-.337-47-REG 4" D-SCHEDULE 80-SS-PIPE SA 312

3-SS-80-.300-48-REG 3" D-SCHEDULE 80-SS-PIPE SA 312

4.25-R-CS-N/RB-49-REG REACTOR PRESSURE VESSEL SA'516 NUT REFERENCE BLOCK

1.250-B-6-A490-50-REG S/G SECONDARY MANWAY BOLT ASTM A 490

1.375-8-17-A490-51-REG 1.375 DIA. X 17" LONG-STEEL-STUD ASTM A 490

1.375-8-24-A490-52-REG 1.375 DIA. X 24" LONG-STEEL-STUD ASTM A 490

1.375-S-33-A490-53-REG 1.375 DIA. X 33" LONG-STEEL-STUD ASTM A 490

3-SP-14-A514-GRF-54-REG COLUMN PIN ASTM A 514

2-IC600-80-J-NOZ-55-REG S/G "j" NOZZLE INCONEL 600

1.875-9-8N-CS-56-REG S/G AND PRESSURIZER MANWAY BOLT SA 193

1.0-4-8N-CS-57-REG S/G HAND HOLD BOLT SA 193

1.875-S-S-CS-58-REG S/G PRIMARY MANWAY STUD SA 193

2.89-1.87-8-CS-59-REG S/G PRIMARY MANWAY CLOSURE NUT SA 193

2-CS-, 40-.218-60-REG 2" BLOWDOWN SA 335

S-CS-100-.594-63-REG 8" FW BLOCK SAW6-GR B

15.0-SS-X-1.60-61-REG 15" PZR BLOCK SA182-F316

20-CS-X-1.281-64-REG 20" FW BLOCK SA333-GR 6

24-CS-80-1.218-65-REG 24" MS BLOCK SA106-GR B

30-CS-X-,1.250-66-REG 30" MS BLOCK SA517-GR 70

36-CS-X-1.47-67-REG 30" MS BLOCK SA517-GR 70

3.0-CS-80-.218-68-REG 3" BLOWDOWN SA335- QUALITY ASSURANCE MANUAL PAGE GINNA STATION Section 8 1 of 8 EFFECTIVE DATE: December 31 1993 ROCHESTER GAS 6 ELECTRIC CORPORATION SIGNATURE DATE

TITLE: PREPARED BY: B APPENDIX QUALITY R. E. GINNA NUCLEAR POWER PLANT ASSURANCE z-g-)3 INSERVICE INSPECTION PROGRAM R FOR THE 1990-1999 INTERVAL IE I. P-3- HIGH ENERGY PROGRAM APPROVED BY' g,M

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 examined „ utilizing volumetric, surface and visual examination techniques. 4

I TITLE REV. QUALITY APPENDIX B Section 8 3 ASSURANCE R.E- GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION REPORT PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 2 of 8 HIGH ENERGY PROGRAM

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. 2.4 System Pressure Testing and associated visual I examination for leakage, shall be performed on the main run of the High Energy Piping. 2.4.1 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. 2.4.2 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. TITLE: REV. QUALITY APPENDIX B Section 8 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION REPORT PAGE GINNA STATION FOR THE 1990-1999 XNTERVAL 3 of 8 HXGH ENERGY PROGRAM

4.0 Frequency of Examination 4.1 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. Selected Non-Class High Energy Piping component supports shall be examined once per interval. 4.3 Identified High Energy Piping Xntegrally welded attachments shall be examined once per interval.

4 ~ 4 On the main run of High Energy Piping pressure boundary, a Leakage examination shall be performed once per period. 4.5 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. 5.0 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. TITLE: REV. QUALITY APPENDIX B Section 8 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION REPORT PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 4 of '8 HIGH ENERGY PROGRAM

6.0 Repair & Testing Requirements: 6.1 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 Replacement & Testing Requirements: 7.1 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. 8.0 Scheduling: 8.1 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. 8.2 Table 1 identifies welds, component supports and integral attachments that are within the High Energy Program. 9.0 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. TITLE: REV. QUALITY APPENDIX B Section 8 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION REPORT PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 5 of 8 HIGH ENERGY PROGRAM

TABLE 1

HIGH ENERGY PROGRAM

MAIN STEAM LOOP A - WELDS:

— Desi n Basis Break

30A-MS-600-1A D 30A-MS-600-1A D1 30A-MS-600-1A F1 36-MS-600-1 L1 Conse uential Break

30A-MS-600-1A D2 30A-MS-600-1A D3 30A-MS-600-1A E 30A-MS-600-1A E1 30A-MS-600-1A E2 30A-MS-600-1A F 30A-MS-600-1A G 30A-MS-600-1A G1 30A-MS-600-1A G2 30A-MS-600-1A H 30A-MS-600-1 J 30A-MS-600-1 K 30A-MS-600-1 L

MAIN STEAM LOOP B — WELDS: Desi n Basis Break

30B-MS-600-1B D 30B-MS-600-1B H1 30B-MS-600-1B J1 36-MS-600-1 P1 Conse uential Break

30B-MS-600-1B D1 30B-MS-600-1B D2 30B-MS-600-1B E 30B-MS-600-1B J 30B-MS-600-1B K 30B-MS-600-1B L 30B-MS-600-1B L1 30B-MS-600-1B L2 30B-MS-600-1B M 30B-MS-600-1 N 30B-MS-600-1 0 30B-MS-600-1 P TITLE REV. QUALITY APPENDIX B Section 8 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION REPORT PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 6 of 8 HIGH ENERGY PROGRAM

TABLE 1 Cont.

MAIN STEAM — TURBINE BUILDING — WELDS: Desi n Basis Break 36-MS-600-1 L2 Conse uential Break

36-MS-600-1 L4 24A-MS-600-1A A 24A-MS-600-1A B 24A-MS-600-1A Bl 24A-MS-600-1A Cl 24A-MS-600-1A D 24A-MS-600-1A Dl 24B-MS-600-1A A 24B-MS-600-1A B 24B-MS-600-1A Bl 24B-MS-600-1A C 24B-MS-600-1A Cl 24B-MS-600-1A D

FEEDWATER — TURBINE BUILDING - WELDS: Desi n Basis Break

20-FW-900-1 M3 Conse uential Break 20-FW-900-1 J 20-FW-900-1 Kl 20-FW-900-1 L 20-FW-900-1 Ll 20-FW-900-1 M 20-FW-900-1 Ml 20-FW-900-1 M2 8-FW-900-1 A 8-FW-900-1 B 8-FW-900-1 C 8-FW-900-1 D 8-FW-900-1 E 8-FW-900-1 F 8-FW-900-1 G 8-FW-900-1 H H I

I TITLE: QUALITY APPENDIX B Section 8 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION REPORT PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 7 of 8 HIGH ENERGY PROGRAM

TABLE 1 Cont.

FEEDWATER LOOP A - WELDS: Desi n Basis Break

20-FW-900-1 M4 20-FW-900-1 Ul 20-FW-900-1 U2 14A-FW-900-lA AA Conse uential Break

14A-FW-900-1 T2 14A-FW-900-1 T3 14A-FW-900-1 U7 14A-FW-900-1 U5 14A-FW-900-1 U6 14A-FW-900-1 V 14A-FW-900-1 VA 14A-FW-900-1 VB 14A-FW-900-1 Vl 14A-FW-900-1 V2 14A-FW-900-1 V2A 14A-FW-900-1 V2B 14A-FW-900-1 W 14A-FW-900-1A X 14A-FW-900-1A Y 14A-FW-900-1A Z 14A-FW-900-1A Zl 14A-FW-900-1A Z2 14A-FW-900-1A Z3 14A-FW-900-1A Z4

FEEDWATER LOOP B — WELDS: Desi n Basis Break

20-FW-900-1 Al 20-FW-900-1 F4 14B-FW-900-1B N 14B-FW-900-1B V Conse uential Break

14B-FW-900-1 F3 14B-FW-900-1 F5 14B-FW-900-1 Fl 14B-FW-900-1 F2 14B-FW-900-1 G 14B-FW-900-1 G2 14B-FW-900-1 Gl 14B-FW-900-1 G3 14B-FW-900-1 G4 14B-FW-900-1 H 14B-FW-900-1 HA 14B-FW-900-1 HB 14B-FW-900-1 Hl 14B-FW-900-1 H2 14B-FW-900-1 H2A 14B-FW-900-1 H2B 14B-FW-900-1 z 14B-FW-900-1 K 14B-FW-900-1B L 14B-FW-900-1B M 14B-FW-900-1B Nl 14B-FW-900-1B 0 14B-FW-900-1B 01 14B-FW-900-1B P f

E TITLE: REV. QUALITY APPENDIX B Section 8 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION REPORT PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 8 of 8 HIGH ENERGY PROGRAM

TABLE 1 Cont.

MAINSTEAM - COMPONENT SUPPORTS: (*) MSU-35 MS-39 MS-167 (*) MS-34 MS-151 MS-153 (*) MS-35 MS-40 MS-44 (*) MS-47 (*) MS-41 (*) MS-149 MS-59 S13A MS-45 MS-36 S13B (*) MS-46 MS-37 MS-42 S23A (*) MS-150 MS-43 S23B MS-38

FEEDWATER — LOOP A — COMPONENT SUPPORTS FWU-16 (*) FWU-21 FWU-25 FWU-17 FWU-22 (*) FWU-26 (*) FWU-18 FWU-23 (*) FWU-27 FWU-19 FWU-24 (*) FWU-28 FWU-20

FEEDWATER — LOOP B - COMPONENT SUPPORTS FWU-36 FWU-33 FWU-40 FWU-35 FWU-31 (*) FWU-39 FWU-34 FWU-30 FWU-38 FWU-32 (*) FWU-29 FWU-37

FEEDWATER — MAIN — COMPONENT SUPPORTS

FW-37 FW-40 FW-43 FW-38 FW-41 (*) FW-45 FW-39 FW-42

FEEDWATER — RECIRCULATION LINE — COMPONENT SUPPORTS: CD-167 CD-169 CD-168 (*) CD-170 NOTE: * = Integral Attachments QUALITY ASSURANCE MANUAL PAGE 9 1 of 4 GXNNA STATION Section EFFECTIVE DATE: December 31, 1993 ROCHESTER GAS 8, ELECTRIC CORPORATION SIGNATURE DATE

TITLE PREPARED BY B APPENDIX QUALITY R.E. GINNA NUCLEAR POWER PLANT ASSURANCE INSERVICE INSPECTION PROGRAM REVIEW: FOR THE 1990-1999 INTERVAL SNUBBER PROGRAM APPROVED Y:

1.0 General: 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. 1.2 The snubber program, as defined within ME-256, establishes both visual examination and functional testing requirements. 1.2.1 This program pertains to mechanical and hydraulic snubbers. 1.2.2 The snubber program includes:

a ~ Visual Inspection Requirements b. Visual Inspection Failure Evaluation c ~ Visual Inspection Corrective Action and Impact on Examination Frequency d. Functional Testing Requirements e. Functional Test Sample f. Functional Test Failure Analysis g Functional Testing Corrective Action h. 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

Y TITLE: REV. QUALITY APPENDIX B Section 9 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 2 of 4 SNUBBER PROGRAM

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 Visual (VT-3) Examinations and Functional (FT) Testing shall be performed at the frequency specified within ME-256. 4.2 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. 4.3 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.

TITLE REV. QUALITY APPENDIX B Section 9 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 3 of 4 SNUBBER PROGRAM

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 TITLE: REV. QUALITY APPENDIX B Section 9 3 ASSURANCE R.E. GXNNA NUCLEAR POWER PLANT MANUAL INSERVICE XNSPECTION PROGRAM PAGE GINNA STATXON FOR THE 1990-1999 INTERVAL 4 of 4 SNUBBER PROGRAM

6.0 Repair, Replacement and Modification Requirements: 6.1 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 Scheduling: 7.1 The Visual Examinations and Functional Testing schedules shall be established, tracked and maintained within Supplement 1 to this Appendix. 7.2 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 Applicable records and reports, as required by Supplement 2 for Repairs, Replacements or Modifications, shall be maintained for snubbers. 8.3 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 REV. PAGE GINNA STATION Section 10 1 oI 6 EFFECTIVE DATE: December 31, 1993 ROCHESTER GAS 8 ELECTRIC CORPORATION SIGNATURE DATE

TITLE PREPARED BY I2-I-$3 APPENDIX B QUALITY R.E. GINNA NUCLEAR POWER PLANT ASSURANCE INSERVICE INSPECTION PROGRAM REVIEW: FOR THE 1990-1999 INTERVAL SEISMIC SUPPORT PROGRAM APPROVED': fr-4 ->3

1.0 General: 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. 1.2 Seismic Category I supports outside of the ASME Class boundary are identified in Table 1. 2.0 Examination Requirements:

I 2ol 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. 3.0 Examination Methods: 3.1 The visual (VT-3) examination shall be performed in accordance with Section 1. 4.0 Frequency of Examination: 4.1 The selected sample shall be examined at least once during the inspection interval. 5.0 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. TITLE: REV. QUALITY APPENDIX B Section 10 1 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 2 of 6 SEISMIC SUPPORT PROGRAM

5.2 Supports which do not meet the visual (VT-3) examination requirements shall be reported for evaluation and appropriate corrective action.

6.0 Repair & Testing Requirements: 6.1 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.

7.0 Replacement & Modification, and Testing Requirements: 7.1 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. 8.0 Scheduling: 8.1 Scheduling of identified Seismic Category I supports shall be performed and controlled within Supplement 1 to Appendix B, the program plan. 9.0 Reports and Records: 9.1 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.

TITLE: QUALITY APPENDIX B Section 10 ASSURANCE R.E- GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 3 of 6 SEISMIC SUPPORT PROGRAM

Table 1 Seismic Category I Supports

Line Segment: AFW100 Support Support Support Support Number Number Number Number AFU-130 AFU-132 AFU-137 AFU-138 AFU-139 Line Segment: AFW200 Support Number AFU-88

Line Segment: AFW300 Support Support, Support Support Number Number Number Number AFU-4 AFU-5 AFU-6 AFU-7

Line Segment: CfTC100 Support Number CVU-84

Line Segment: CVC200 Support Support Support Support Number Number Number Number CVU-125 CVU-126 CVU-129 CVU-130 Line Segment: CVC700 Support Support Number Number CVC-56 CVC-58 TITLE REV. QUALIT'Z APPENDIX B Section 10 1 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 4 of 6 SEISMIC SUPPORT PROGRAM

Table 1 (Cont.) Seismic Category I Supports

Line Segment: CVC730 Support Support Number Number CVC-39 CVC-40

Line Segment: FW300 „ Support Support Support Support Number Number Number Number FWU-40 FWU-39 FWU-38 FWU-37 FWU-36 FWU-35 FWU-34 FWU-33 FWU-32 FWU-31 FWU-30 FWU-29 FWU-28

Line Segment: FW301 Support Support Support Support Number Number Number Number FWU-16 $'WU-17 FWU-18 FWU-19 FWU-20 FWU-2 1 FWU-22 FWU-23 FWU-24 FWU-25 FWU-26 FWU-27 Line Segment: MS300 Support Support Support Support Number Number Number Number MSU-35 MSU-59 MSU-60 MSU-51 MSU-52 MSU-53 MSU-54 MSU-47 MSU-48 MSU-49 MSU-50 MSU-56 MSU-57

Line Segment: RHR300

Support Support Support Support Number Number Number Number RHU-86 RHR-87 RHU-90 RHR-91 TITLE: REV. QUALITY APPENDIX B Section 10 1 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 5 of 6 SEISMIC SUPPORT PROGRAM

Table 1 (Cont.) Seismic Category I Supports

Line Segment: SAFW450 Support Support Support Support Number Number Number Number AFU-169 AFU-170 AFU-175 AFU-176 AFU-177 Line Segment: SGB-300 Support Support Number Number BDU-21 BDU-23 Line Segment: SGB-400 Support Support Number Number BDU-26 BDU-27 Line Segment: S2100 Support Number SIU-8 Line Segment: SI200 Support Number SIU-55

Line Segment: SW1500 Support Support Support Support Number Number Number Number SWU-363 SWU-364 SWU-365 SWU-366 II

'I TITLE: REV. QUALITY APPENDIX B Section 10 1 ASSURANCE R.E- GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 6 of 6 SEISMIC SUPPORT PROGRAM

Table 1 (Cont.) Seismic Category I Supports

Line Segment: SW2100 Support Support Support Support Number Number Number Number SWU-523 SWU-524 SWU-525 SWU-526 SWU-533 SWU-534

Line Segment: SW2300 Support Support Support Support Number Number Number Number SWU-602 SWU-603 SWU-604 SWU-605 SWU-606 SWU-607

Line Segment: SW2500 Support Support Support Support Number Number Number Number SWU-637 SWU-642 SWU-639 SWU-640 SWU-638 QUALITY ASSURANCE MANUAL PAGE GINNA STATION Section ll 1 of 9 EFFECTIVE DATE: December 31, 1993 ROCHESTER GAS ELECTRIC CORPORATION 8 SIGNATURE DATE

TITLE PREPARED BY: I ~-I-6 APPENDIX B $~+)g QUALITY R. E. GINNA NUCLEAR POWER PLANT ASSURANCE INSERVICE INSPECTION PROGRAM REVIEW: lZ44 FOR THE 1990-1999 INTERVAL ADDITIONAL PROGRAMS APPROVED Y:

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' TITLE: REV. QUALITY APPENDIX B Section ll 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 2 of 9 ADDITIONAL PROGRAMS

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 Other 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. 2 ' ' 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. TITLE: REV. QUALITY APPENDIX B Section 11 ' ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 3 of 9 ADDITIONAL PROGRAMS

2.4 Frequency of Examinations: 2.4.1 Examinations shall be performed every refueling outage to the extent required and specified within 2. 2, as a minimum. 2.5 Examination Evaluation:

2.5. 1 Eddy Current evaluation shall be performed in accordance with R. E. Ginna Station Technical Specifications.

2.6 Repair, Replacement and Testing Requirements 2.6.1 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 Steam generator tubes that have imperfections greater than 40 percent through-wall as indicated by eddy current, shall be repaired by plugging or sleeving. 2.6.1.2 Steam generator sleeves that have imperfections greater than 30 percent through wall as indicated by eddy current shall be repaired by plugging. 2.6.2 Repairs by welded plugs and sleeves shall be performed in accordance with Supplement 2 to this Appendix. 2.7 Scheduling: 2.7.1 Eddy Current examination schedules of Steam Generator Tubes shall be established within Supplement 1 to this Appendix. 2.8 Reports and Records: 2.8.1 Applicable records shall be maintained as specified within Section 1 of this program and as applicable and required within Supplement 2 to this Appendix. TITLE REV. QUALITY APPENDIX B Section 11 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 4 of 9 ADDITIONAL PROGRAMS

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 TITLE: REV. QUALITY APPENDIX B Section 11 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 5 of 9 ADDITIONAL PROGRAMS

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 Reactor Coolant Pump Anti-Rotation Pawls shall be examined using Surface examination techniques. 3.3 ' 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. TITLE: REV. QUALITY APPENDIX B Section 11 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 6 of 9 ADDITIONAL PROGRAMS

3.6 Repair, Replacement and Testing Requirements 3.6.1 Repairs and Replacements shall be performed in accordance with Supplement 2 to this Appendix, as applicable. 3.7 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

I TITLE REV. QUALITY APPENDIX B Section 11 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVXCE INSPECTXON PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 7 of 9 ADDITIONAL PROGRAMS

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 Repairs and Replacements shall be performed in accordance with Supplement 2 to this Appendix, as applicable. 4.7 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.

TITLE: REV. QUALITY APPENDIX B Section 11 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 8 of 9 ADDITIONAL PROGRAMS

5.0 Reactor Vessel Au ented Pro ram Cate or B-A:- 5.1 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". 5.2 Examination Requirements: 5.2. 1 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. 5.3 Examination Method: 5.3.1 Ultrasonic examinations shall conform and be performed in accordance with Section 1 of this program. 5.4 Frequency of Examinations: 5.4.1 Examinations shall be performed once during the Inspection Interval. 5.5 Examination Evaluation: 5.5.1 Examination Evaluations shall be performed in accordance with Section 1 of this program. 5.5.2 Unacceptable examinations shall be reported for evaluation and appropriate corrective action. 5.6 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

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ll TITLE: REV. QUALITY APPENDIX B Section 11 3 ASSURANCE R.E. GINNA NUCLEAR POWER PLANT MANUAL INSERVICE INSPECTION PROGRAM PAGE GINNA STATION FOR THE 1990-1999 INTERVAL 9 of 9 ADDITIONAL PROGRAMS

5.7 Scheduling: 5.7.1 Examination schedules shall be established within Supplement 1 to this Appendix. 1 5.8 Reports and Records: 5.8.1 Applicable records shall be maintained as specified within Section 1 of this program and when required within Supplement 2 to this Appendix.