Text

Rev 0 to [[::JAF-ISI-0003|JAF-ISI-0003]], Third ISI Interval,Ten-Yr ISI Plan
	ML20199G592
Person / Time
Site:	FitzPatrick
Issue date:	01/07/1998
From:	Anderson E, Penny R, Alexandra Smith; POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	;
Shared Package
ML20199G519	List: JPN-98-002, Forwards Third ISI Interval Insp Program Plan for JAFNPP & Requests for Relief from Snubber Insp Requirements of ASME Section Xi,Article IWF-5000; ML20199G566; ML20199G592; ML20266E914; ML20266E918; ML20266E924; ML20266E929; ML20266E934; ML20266E937; ML20266E943; ML20266E948; ML20266E953; ML20266E958; ML20266E963; ML20266E966; ML20266E971; ML20266E976; ML20266E981; ML20266E984; ML20266E990; ML20266E995; ML20266F000; ML20266F006; ML20266F011; ML20266F016; ML20266F021; ML20266F026; ML20266F031; ML20266F037; ML20266F044; ML20266F048;
References
	[[::JAF-ISI-0003\|JAF-ISI-0003]], JAF-ISI-3, NUDOCS 9802040302
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l JAMES A. FITZPATRICK NUCLEAR POWER PLANT, I

i THIRD INSERVICE INSPECTION INTERVAL i

I

{ TEN-YEAll INFEltVICE -

INSPECTION l! PLAN l

i

'l COMMERCIAL SERVICE DATE: JULY 28,1975

DOCUMENT NO. [[: :JAF-ISI-0003|JAF-ISI-0003]] I

NewYorkPbwer 4 Authority l

l NFE YORK POWER AUTHORITY 123 MAIN STREET WHITE PLAINS, NEW YOlth 19601 pgg20$D00k000333 0 PDR

NewWrkPower 4 Authority O v a mr

,uk u m~n0LLED New York Power Authority 123 Main Street White Plains, New York 10601 James A. Fitzpactrick Nuclear Power Plant THIRD INSERVICE INSPECTION INTERVAL TEN-YEAR INSERVICE INSPECTION PLAN Prapared For James A. Fitzpatrick Nuclear Power Plant P.O. Box 41

] Lycoming, New York 13093 Commercial Service Date: July 28,1975 NRC Docket Number: 50-333 Document Number: JAF lSI-0003 l Revision Number: 0 Date: January 7,1998 Prepared b : MsazM u Edwap . An 'on , Consultant Reviewed by: L :d/b

~

Aturo D. Snfilh -lSI ochnical Specialist i

Approved by: /

R ector Engineering Programs l

Reviewed by: _

Authorized Nuclear Inservice inspector l

JAMES A. FITZPATRICK JAF4SI-0003 NUCLEAR POWER PLANT

> lilew%rkPower tv Authortty G THIRD INSERVICE INSPECTION INTERVAL Rev. O TEN. YEAR INSERVICE INnPECTION Date: January 7,1998 PLAN Page 2 of 35 1

TABLE OF CONTENTS Table of Contents . . . 2 l i

Record of Revision . . . ~. 5 Abs *ract . . .. . .. . . .. . .. .. 6 1.0 I n t ro d u c tio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 1.1 Inspection interval 7 1.2 Inspection Periods . . . . . 7 1.3 Applicable Documents . . . . . .. .7 1.4 Applicable Code Edition and Addenda 10 1.5 Subsequent Code Editions and Addenda . 11 4

b 2.0 Development of Inspection Plan . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 2.1 Class 1 Systems / Components 12 2.2 Class 2 Systems / Components .. 12 2.3 Class 3 Systems / Components 12 2.4 Class 1,2,3 Component Sepoorts 12 2.5 Substitute Examinations . . 12 2.6 Nondestructive Examinations . . . 13 f 2.7 Weld / Support Location Maps 13 2.8 Ultrasonic Calibration Blocks . . . 13 2.9 Weld identification . . . . . . 13 3.0 R e c o rd s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 3.1 Genera! . . . . . . 16 3.1.1 Scheduled Examination Tables . . 16 3.1.1 Inspection Zones . . . . 16 3.1.3 Code item Classification . . . . ... . 16 3.1.4 InspecSon/ Examination Table Contents . 16 3.2 Final Reports . . . .. .. . . 17 3.3 ISI Summary Report . 17 l

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1 JAMES A.FITZPATRICK JAF ISI-0003 NUCLEAR POWER PLANT h THIRD INSERVICE INSPECTION INTERVAL Rev. O TEN. YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 3 of 35 4.0 C l a s s 1 T a bl e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 01 Reactor Pressure Vessel 01 1 thru 01 'i3 02 2 Reactor Recirculation System . . . . 02-1 thru 02 29

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3 Jet Pump System . .. 02.3-1 thru 02.3-1 03 Control Rod Drive Systern . . . 03-1 thru 03-1 10 Residual Heat Removal System .. . 10-1 thru 10-12 12 Reactor Water Cleanup System . .. 121 thru 12-5 13 Reactor Core Injection Cooling System . 131 thru 13 9 14 Core Spray System . 141 thru 14-11 23 High Pressure Coolant Injection System . 23-1 thru 23-5 29 Main Steam Systern .. .. 291 tr.ru 29-24 34 Feedwater System . . 341 thru 3412 5.0 C l a s s 2 T a ble s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 0

(,,T 03 Control Rod Drive System . . . . 031 thru 03-11 10 Residual Heat Removal Jystem 10-1 thru 10-92 13 Reactor Core Injection Cooling System . 13-1 thru 13-3 14 Core Spray System .. . 141 thru 1419 23 High Pressure Coolant injection System . 23-1 thru 23-19 27 Containment Purge / CAD Pass System . 27-1 thru 2713 29 Main Steam System . 29-1 thru 29-2 j 6.0 C la s s 3 Ta ble s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 21 10 Residual Heat Removal System . . . 10-1 thru 10-10 13 Reactor Core Injection Cooling System 13-1 thru 13-2 15 Rea;; tor Building Closed Loop Cooling System . . 15-1 thru 15-9 19 Fuel Pool Cooling System . , , . . 19-1 thru 19-5 46 Service Water System . .. 46-1 thru 46-11 66 Reactor Building Vent and Cooling System . 66-1 thru 66-3 70 Control Room and Relay Room Vent and Cooling System . 701 thru 70-6 7.0 Augmented Examination Tables . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 01 . Reactor Pressure Vessel Examinations .. . , 7-1 tnru 7-1 Augmented IGSCC Examinations , , 7-2 thru 7-16 l

Main Steam and Feedwater Augmented Examinations . 7-17 thru 719 NUREG 0619 Feedwater and Control Rod Drive Examinations 7-20 thru 7 20 O 01 In-Vessel Visual Augmented Examinations . 7-21 thru 7 22 V 14 Core Spray Augmated Examinations . . 7 23 thru 7-24 i

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pr _

ll JAMES A. FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] NUCLEAR POWEP. PLANT

D filowWrkPower ev Authority O THIRD INSERVICE INSPECTION INTERVAL Rev. O TEN YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 4 of 35 APPENDICES A Acceptance Cnteria . 23 B Ultrasonic Cahbration Blocks . . . 26 C Class 1,2, and 3 Weld / Support Location Maps . 30 D - ASME Code Cases ~

. 33 LIST OF FIGURES 2-1 Tee Weld ID . . .. .. . 14 22 Elbow weld ID . . .. .. . . . . 14 23 Reducer weld ID . . . . . .. .. .. . .. 14 3-1 Inservice inspection Schedule . .. 18 LIST OF TABLES A1 Class 1 Acceptance Standards . 24 O\ A-2 Class 2 Acceptance Standards . 25 A3 Class 3 Acceptance Standards . . . 25 A-4 Component Support Acceptance Standards 25 r ;

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I JAMES A. FITZPATRICK JAF ISI-0003 NUCLEAR POWER PLANT THIRD INSERVICE INSPECTION INTERVAL Rev. O TEN YEAR INSERVICE INSPECTION Cate: January 7,1998 ,

PLAN Page 5 of 35 RECORD OF REVISION

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REVISION- g$Q1] DATES'y lAFFECTED 1 ; "- REASON FOR REVISIONj*!., " ^ , Q :y

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% !Non 2 . ~? ?PAGE8? si -

0 January 7,1998 Entire Ten-Year Inservice Inspection Plan and Document Schedule for the 3* Ten Year Inservice inspection Interval O

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f JAMES A.FITZPATRICK JAF ISI-0003 NUCLEAR POWER "t. ANT e 4#

THIRD INSERVICE INSPECTbON INTERVAL Rev. O Date: January 7,1998 TEN YEAR INSERVICE INSPECTION PLAN Page 6 of 35

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ABSTRACT This document provides the Inservice Inspection Long-Term Third Ten-Year Inservice inspection Interval Plan and Schedule for James A. Fitzpatrick Nuclear Power Plant.

This Schedule identifies those components and/or systems (including supports) which are classified Quality Group A, B and C (ASME Code Class 1, 2, and 3, selected for nondestructive examination, as set forth in the ASME Boiler and Pressure Vessel Code,Section XI,1989 Edition no Addenda, to the extent practical within toe limitations of design, geometry and materials of construction of the components as stated in 10 CFR 50.55a (b)(2).

Where an examinatua required by Section XI is determined to be impractical, the basis for this determination is included in the James A. Fitzpatrick Inservice inspection Program, in the form of a Request for Relief, t

Tables for each system subject to examination are included within this document, which provides Code classification, Code examination category, Code itein number, component identification and description, examination method, and where within the Third Ten-Year inspection interval and period the component is scheduled to be performed.

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JAMES A. FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] i NUCLEAR POWER PLANT )

> liew%wkPower W Authority G THIRD INSERVICE INSPECTION INTERVAL Rev. O TEN YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 7 of 35

1.0 INTRODUCTION

This document details the Long Term inservice inspection Plan and Schedule for the Third Ten-Year Inservice Inspection Interval at the James A. Fitzpatrick Nuclear Power Plant.

The Construction permit for James A. Fitzpatrick Nuclear Power Plant wasissued in May 1970. New York Power Authonty, hereafter referred to as the Authority, is the Owner of Record.

The Operatirq License for James A. Fitzpatrick Nuclear Power Plant was issued on October 17, 1974.

The Commercial Service Date for James A. Fitzpatrick Nuclear Power Plant is July 28,1975.

1.1 INSPECTION INTERVAL The Third inservice inspection interval becomes effective on September 28,1997 and is scheduled to end on September 27,2006.

Note: The third inspection interval is nine (9) years in duration, due to N YPA's extension C of the second inspection interval by one (1) year.

1.2 INSPECTION PERIODS The Third inservice inspection Interval is divided into three successive inspection period as determined by calendar years of plant service within the inspection interval. Identified below j cre the period dates for the third inspection interval as defined by inspection Program "B".

TABLE 12 JAF INSERVICE INSPECTION PERIODS j INSPECTION PERIOD START DATE's PER!OD END DATE's )

PERIOD's :

1 September 28,1997 September 27,2000 2 September 27,2000 September 28,2004 3 September 28,2004 September 27, 2006 l

l 1.3 APPLICABLE DOCUMENTS I pj The Third Ten Year Inservice Inspection Program for Quality Group A, B, and C (ASME Code Class 1,2 and 3), systems and components (including their supports) was developed i after giving due consideration to the following dccument!. and subject to the limitations and l

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JAMES A. FITZPATRICK JAF.ISI-0003 NUCLEAR POWER PLANT THIRD INSF8tVICE INSPECTION INTERVAL Rev. O TEN YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 8 of 35 modifications listed in 10 CFR 50.55a(b), and to the extent practical within the limitations of design, geometry and materials of construction.

APPLICABLE DOCUMENTS - Continued

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- Code of Federal Reguiations 10 CFR 50.55(a) Code of Federal Regulations; Federal Register, Volume 61, Number 154, dated August 8,1996, amendment to the regulation to incorporate by reference the 1992 Fdition with the 1992 Addenda of Subsection lWE and lWL of Section XI, Division 1, of the ASME Code.

ASME Code Editions and Addenda ASME Boiler and Pressure Vessel Code, Sections V,1989 Edition, " Nondestructive Examination" A

i i ASME Boiler and Pressure Vessel Code,Section XI,1989 Edition, " Rules for Inservice Inspection of Nuclear Power Plant Components" ASME Boiler and Pressure Vessel Code,Section XI,1992 Edition through the 1992 Addenda, ' Rules for Inservice Inspection of Nuclea* Power Plant Components",

Subsections IWE and IWL.

USNRC Regulatory Guides The following list of Regulatory Gu'. des are applicable to the James A. Fitzpatrick Nuclear Power Plant Third ?nservice inspection Program:

1.26 Quality Group Classificatioris and Standards for Water-Steam, and Radioactive-Waste-Containing Components of Nuclear Power Plants, Revision 2, June 1975.

1.84 Design and Fabrication Code Case AcceptabHity ASME Section Ill, Division 1, Latest Revision.

1.85 Material Code Case Acceptability ASME Section lil, Division 1, Latest Revislan.

1,147 Inservice Inspection Code Case Acceptability ASME Section XI, Division 1, Revision 11 and Draft Revision 12.

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JAMES A.FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] NUCLEAR POWER PLANT

> liewVorkPower

& Authonty G THIRD INSERVICE INSPECTION INTERVAL Rev, 0 TEN YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 9 of 35 APPLICABLE DOCU.'AENTS - Continued

- JAFNPP Specific Documents James A. Fitzpatrick Updated Final Safety Analysis Report, Sections 1,5,7,9,12,

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16, James A. Fitzpatrick Technical Specifications, USNRC Docket number 50-333, Sections 3.6 and 4.6.

- USNRC NUREGSISRP's USNRC NUREG 0313, Technical Report on Material Selection and Processing Guidelines for BWR Ccolant Pressure Boundary Piping, Revision 2.

USNRC NUREG 0619, BWR Feedwater Nozzle and CRD Return Lines

- USNRC Bulletins

'- 82-03 Stress Corrosion Cracking in Thick-Wall, Large-Diameter, Stainless Steel, Recirculation System Piping at BWR Plants, Revision 1, October 28,1982.

- USNtiC Generic Letters 88-01 USNRC Position on IGSCC in BWR Austenitic Stainless Steel Piping, January 25,1988.

88-01 NRC Position on Intergranular Stress Corrosion Cracking (lGSCC) in BWR Austenitic Stainless Steel Piping, Supplement 1, February 4,1992.

90-05 Guidance for Performing Temporary Non-Code Repairs to ASME (ISI) Code Class 1,2 and 3 Piping and Components, June 15,1990.

90-09 Alternative Requirements for Snubber Visual inspection Intervals and Corrective Actions, December 11 1990.

- USNRC Informational Notices 89-79 Degraded Coatings and Cor, ?sion of Steel Containment Vessels, December 1,1989.

- ASME Code Cases

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N-355 Calibration Block for Angle Beam Ultrasonic Examination of Large Fittings in accordance with Appendix lll-3410,Section XI, Division 1 File: jafisipl.wpd

JAMES A. FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] NUCLEAR POWER PLANT

> NewYorkPower qv Authortty G THIRD INSERVICE INSPECTION INTERVAL Rev. O TEN YEAR ?NSERVICE INSPECTION Date: January 7,1998 PLAN Page 10 of 35 ASME Code Cases continued N-416-1 Alternative Pressure Test Requirement for Welded Repairs or Installation of Replacement items by Welding, Class 1,2 and 3,Section XI, Division 1.

N-460 Altemative Examination Coverage for Class 1 and Class 2 Welds,Section XI Division 1.

N-491-1 Alternative Rules for Examination of Class 1, 2, 3 and MC Component Supports of Light Water Cooled Power Plants,Section XI, Division 1.

N-498-1 Altemative Rules for 10-Year Hydrostatic Pressure Testing for Class 1 and Class 2 Systems,Section XI, Division 1.

n N 509 Attemative Rules for the Selection and Examination of Class 1,2 and 3 integral < Welded Attachments,Section XI, Division 1.

N-522 Pressure testing of Containment Penetration Piping,Section XI, Division 1.

N-524 Alternative Examination Requirements for Longitudinal Welds in Class 1 and 2 Pip;ng,Section XI, Division 1 N-532 Attemative Requirements to Repair and Replacement Documentation Requirements and inservice Surnmary Report Preparation and Submission As Required by IWA-4000 and IWA-6000,Section XI, Division 1.

1.4 APPLICABLE CODE EDITIONS AND ADDENDA 1.4.1 Third inspection Interval Pursuant to Title 10, Part 50, Section 55a(g)(4), of the Code of Federal Regulations, the inservice Inspection requirements applicable to nondestructive examination and system pressure testing for the Thirri inservice inspection Interval is based on the rules set forth in the 1989 Edition of Section XI, that was endorsed twelve months prior to the start of the Third inspectid,n intervs!.

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f JAMES A. FITZPATL rJK ! [[::JAF-ISI-0003|JAF-ISI-0003]] NUCLEAR POWER PLANT 49 THIRD INSERVICE INSPECTION INTERVAL Rev. O TEN YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 11 of 35 1.5 Subsequent Code Editions and Adoenda As permitted by 10 CFR 50.55a(g)(4)(iv), New York Power Authority may elect to meet the requirements set forth in subsequent Editions and Addenda of Section XI that are "

incorporated by reft..;nce into '.0 CFR 50.55a(b)(2), subject to the applicable limitations and

- modification and subject to USNRC approval.

Portions of Editions av Addenda may also be used provided that all related requirements to the respective Edition and Addenda are met. NYPA intends to continually evaluate and epply, as appropriate, changes in adopted Code Editions and Addenda which provides the continuing assurance of the quality and safety of pressure containing components and systems.

O O

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JAMES A.FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] NUCl. EAR POWER PLANT

> Power THIRD INSERVICE INSPECTION INTERVAL Rev. O TEN YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 12 of 35 2.0 DEVELOPMENT OF INSPECTION PLAN This document provides the component schedule for inservice nondestructive examinations to be performed over the Third Ten-Year inservice inspection Interval on Class 1,2 and 3 components and their supports of the New York Power Authority (NYPA), James A. Fitzpatrid Aclear Power Plant (JAF): Component and/or system selected for nondestructive examination are scheduled in accordance with the requirements of Section XI, to the extent practical.

2.1 CLASS 1 SYSTEMS / COMPONENTS The Class 1 system boundaries subject to examination were developed based upon the requirements of 10 CFR 50.2(v) and NYPA JAF-FSAR. The Class 1 components and systems (including supports) selected for examination are identified in Section 4.0 of this document.

2.2 CLASS 2 SYSTEMS / COMPONENTS The Class 2 system boundaries subject to examination were develeped based upon the o$

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requirements of Regulatory Guide 1.26 and the NYPA JAF-FSAR. The Class 2 components and systems (including supports) seleaed for examinaSon are identified in Section 5.0 of this document.

2.3 CLASS 3 SYSTEMS / COMPONENTS The Class 3 system boundaries subject to examination were developed based upon the requi.ements of Regulatory Guide 126, and the NYPA JAF-FSAR. The Class 3 components and systems (including supports) selected for examination are identified in Section 6.0 of this document.

2.4 CLAv i 1, CLASS 2 AND CLASS 3 COMPONENT SUPPORTS -lWF Component supports selected for examination shall be the supports of those components that are required to be examined under IWB, IWC and IWD, and are included within Sections 4.0,5.0 and 6.0 as applicable.

2.5 SUBSTITUTE EXAMINATIONS NYPA may substitute component = scheduled in this Document for others not previously scheduled when the original selection was part of the additional piping weld selection. This substitution may be done due to such conditions as limited physical access, high radiation levels, inaccessibility etc. Such changes will be noted in the Summary Report Submittal.

Specific examinations that are required, and can not be cornpleted within the period / interval

,, will be identified within the Summary Report Submittal, and may be the subject of a request l ) for relief.

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JAMES A.FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] NUCLEAR POWER PLANT

> NewYorkPower 4# Authority G THIRD INSERVICE INSPECTION INTERVAL Rev. 0 TEN YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 13 of 35 1

2.6 NONDESTRUCTIVE EXAMINATIONS Nondestructive examinations will be performed in accordance with established James A.

Fitzpatrick (JAF) nondestru:tive examination procedures and/or NYPA approved vendor

- procedures which conform to the requirements of the NYPA Quality Assurance Program and the applicable sections of the ASME Boiler and Pressure Vessel Code. NYPA app oved vendor NDE Procedures will be identified as required,(example, Automated UT of RPV).

2.7 WELDISUPPORT LOCATION MAPS Weld / Support location maps indicating components, areas, weld locations, and other information pertinent to the performance of the inservice Nondestructive examinations are contained in Appendix C.

2.8 ULTRASONIC CAllBRATION BLOCKS

~s Ultrasonic calibration blocks for each component subject to volumetric examination is maintained at the plant site. A listing of applicable ul?asonic calibration blocks is included in Appendix B.

2.9 WELD IDENTIFICATION Longitudinal welds in Class 2 piping and pipe fittings do not receive unique identification numbers from the spool fabricators Since Class 2 longitudinal welds are required to be examined for a distance of 2.5 times the wall thickness from the intersecting circumferential weld; they will be given unique identification numbers as denoted below.

Fittings: Longitud:nal welds in fittings are identified by adding letter A, B, or C, (1,2, or 3), as applicable, to the I.D. for the reference weld The reference weld is definad as the first circumferential weld encountered when entering the fitting on the direction of the flow.

()

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JAMES A. FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] NUCLEAR POWER PLANT e tv THIRD INSERVICE INSPECTION INTERVAL TEN YEAR INSERVICE INSPECTION Rev. O Date: January 7,1998 PLAN Page 14 of 35 The following figure shows the convention for identifying which weld in a welded fitting FG receives a particular letter designation.

1 i

Tee Case 1: Three welds located as shown in a i ' *

' ~'

~ Figure 2-1. ) ,

j ! 4 -

Tee Case 2: If only one weld Figure 2-1 TEE '

weld ID exists it is identified by the letter A or 1.

Figure 2-1 Tee Weld ID Elbow Case 1: Two welds located as shown in !

O!*

\

Figure 2-2, one located on the inside radius and ,,.

the other on the outside radius. l

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Elbow Case 2: If only one weld exists it is . -

identified by the letter A or 1.

Figure 2-2 Elbow wold ID Elbow Case 3: If two welds exist in locations other than Case 1. Weld A or 1 is the first weld encountered when moving clockwise from the reference weld datum while looking in the direction of flow. The other weld is identified by B or 2.

~

Reducer Case 1: If only one weld exists it is identified by the letter A or 1.

Reducer Case 2: If two welds exist, weld A or 1 is the first weld encountered when moving y ,[*<

clockwise from the reference weld datum while / !.

" ?, ~

looking in the direction of flow. The other weld is identified by B or 2. See Figure 2-3.

Figure 2-3 Reducer weld ID File: jafisipl.wpd

I JAMES A. FITZPATRICK JAF ISI-0003 )

NUCLEAR POWER PLANT

> NewYorkPower i W Authority G THIRD INSEitVICE INSPECTION INTERVAL Rev. O TEN YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 15 of 35 Piping: Longitudinal piping welds are not assigned a specific weld identification number. They are identified by reference to the intersecting circumferential weld first encountered when entering the seamed pipe in the direction of flow.

4 A

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JAMES A. FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] NUCLEAR PCWER PLANT THIRD IN3ERVICE INSPECTION INTERVAL Rev. O TEN YEAR INSERVICE INSPECTION Date: Janut.ry 7,1998 PLAN Page 16 of 35 3.0 RECORDS 3.1 General Records and Reports of Inservice Inspection activities (such as Programs, Plans, Schedules,

' calibration, examination procedures, examination results, finaT reports, equipment and personnel certifications, corrective actions taken or recommended will be developed and maintained in accordance with IWA-6000 cf the ASME Boiler and Pressure Vessel Code,Section XI.

3.1.1 SCHEDULED EXAMINATION TABLES The Scheduled Examination Tables for Inservice examinations of major components of New York Power Authonty, James A. Fitzpatrick Nuclear Power Station will be in a format similar to Figure 3-1.

3.1.2 INSPECTION ZONES

( Areas subject to examination have been divided into systems. Each system is

% defined by a weld / support location map which identifies and locates all welds, supports, and other examination areas subject to and/or seiccted 'or e) amination within each system.

3.1.3 CODE ITEM CLASSIFICATION For the sake of continuity and clarity, all items to which a Code category and Code item number can be apphed are identified.

3.1.4 INSPECTION / EXAMINATION TABLE CONTENTS The Inservice inspection / Examination Tablec provide the following information:

ASME SECTION XI ITEfu NUMBER - Listed in this column is the appropriate item number from Table IWB-2500-1, IWC-2500-1, IWD-2500-1 or IWF-2500-1, as applicable, of the ASME Boiler & Pressure Vessel Code,Section XI.

COMPONENT IDENTIFICATION - The examination area identification is the unique component or weld identification number. This number also appears on the applicabic ISI Weld / Support Location Map.

COMPONENT DESCRIPTION - The examination area description is a brief ,

description of the component or, in the case of a weld, the parts being joined.

i CODE EXAMINATION CATEGORY - Listed in this column are the appropriate

\ examination categories from Tables IWB-2500-1, IWC-2500-1, IWD-2500-1 or IWF-2500-1, as applicable, of the ASME Boiler & Pressure Vessel Code,Section XI.

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JAMES A.FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] NUCLEAR POWER PLANT THIRD INSERVICE INSPECTIOk' *TERVAL Rev. O TEN-YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 17 of 35 CODE EXAMINATION METHODS - Listed in this column are the appropriate nondestructive examination method (s) to be used for each component or item subject to exa Tiination, if applicable.

ISI INTERVAL - Identified in this column are numbers 1,2, and 3. Each number

ion interval relating to this Table signifying an inspection period. The current .

is number 3. Within each column a s/ stem of cus are entered to define the status of each component or item. For the purpose of providing Tables of components or areas selected for examination during the interval an (X) will be placed on the applicable row. Each row is defined by period, depending on where the (X) is placed, will determine when that item is scheduled to be examined within the interval, and period. Additional codes are used to provide a status of examination conducted during a given period in time. Additional codes such as those identified in Figure 3-1 may also be used.

REMARKS - This column identifies examination note (s) and/or instruction applicable to a particular item.

f)

O 3.2 FINAL tlEPORTS FollowMg the completion of the inservice inspection Activity, NYPA shall prepare a inservice inspection Final Report. The Final Report will be filed at the James A. Ftpatrick site Document Control Center. Final Examination Report Tables are included as part of the Final Report along with any additional records and reports in order to provide a documentation of the complete examination activity.

This report shall be made available for review by the Enforcement and Regulatory Authority having jurisdiction at the plant side.

3.3 INSERVICE INSPECTION

SUMMARY

REPORT Following the units retum to service, NYPA shall forward a Summary Report of Ue ISI activity to the Nuclear Regulatory Commission as required by Section XI.

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JAMES A.FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] NUCLEAR POWER PLANT

> NewWrkPower

& Authortty G THIRD INSERVICE INSPECTIDN INTERVAL Rev. O TEN-YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN

,Page 18 of 35 1

James A. Fittpatrick Nuclear Power Plant DATE: (A)

Third inservice inspection Interval Rev. (B)

Ten . Year inspection Plan Page (C)

Component ASME ASME Description ASME Rel Weld Remarks identliication Code Code cme Req Inspection Intsrval Lth. Or Cat item Es am Peri Per2 Per3 . Thick SYSTEM (D)

DRAWING NUMBER:(E)

LINE NO. (F)

(G) (1) (J) (H) (K; (L)---- - - - - - . -

(K)

(A) Denotes the date of the inspection plan table (B) Denotes the current revision number of the plan (C) Identifies the page number of the table (D) Identifies the System applicable to this table (E) Denotes the applicable Drawing number for this table (F) Identifies the applicable Line number for this table p (G) Denotes the component or weld identification number V(H) Identifies the component or weld description Denotes the ASME Code Category (l)

(J) Denotes the ASME Code item Number (K) Denotes the NDE Method to be used for the examination (L) Shows when an item was examined or is scheduled to be examined. Any interva: can be shown separately.

X - Scheduled P - Partial C - Completed E Axpanded Scope A- Augmented B - Baseline (M) Denotes specific instruction applicable to the item FIGURE 31 Inservice inspection Long Term Plan O)

'J File: jafisipt.wpd

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JAMES A.FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] NUCLEAR POWER PLANT

> NewWrkPower tv Authority G THIRD INSERVICE INSPECTION INTERVAL Rev. O TEN YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 19 of 35 4.0 CLASS 1 INSERVICE INSPECTION PLAN TABLES This section contains the Long Term Ten-Year Inservice inspection Examination Tables for nondestructive examinations of selected systems and components for the Th;cd inservice inspection Interval.

01 Reactor Pressure Vessel 01-1 thru 01 *3 02-2 Reactor Recirculation System , 02-1 thru 02-29 02-3 Jet Pump System 02.3-1 thru 02.3-1 03 Control Rod Drive System 03-1 thru 03-1 10 Residual Heat Removal System . . 10-1 thru 10-12 12 Reactor Water Cleanup System . , ,, , 12-1 thru 12-5 13 Reactor Core injection Cooling System 13-1 thru 13-9 v' 14 Core Spray System 141 thru 14-11 23 High Pressure Coolant injection System 23-1 thru 23-5 29 Main Steam System , 29-1 thru 29-24 34 Feedwater System , 34-1 thru 34-12

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File: jafisipl.wpd

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..J YJ James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] g gjVor Power Third Inservice inspection Interval Date: January 7,1998 Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCR!PTION EXAM REO PER1 PER2 PER3 THICK REMARKS 01 - Reactor Pressura Vcesel Drawing Number: MSK-3036 Une No. 02V-1 ShellWelds VC-F-1 B-A B1.30 Snell-to-Flange Weld Vol X -

X 730" 50% in 1". Period, remainder end of interval VC-1-2 B-A B1.11 Shell Circumferential Weld Vol X - -

730" Augmented Examinations per 10 FR 0.55a (g)(ii)( A)

(3) (ii) to t e examined 1 st. Outage 1st. Period,3rd.

Interval VC-2-3 B-A B1.11 Shell Circumferential Weld Vol X - -

730" Augmented Examinations per 10 FR 0.55a (g){ ii)( A)

(3) (ii) to be examined 1 st. Outage,1st. Period. 3rd.

Interval VC-3-4 B-A B1.11 Shell Circumferential Weld Vol X 730" Augmented Examinations per 10 FR 0.55a (g)(ii)( A)

(3) (ii) to be examined 1 st. Outage,1st Period. 3rd.

Interval VC-A-BH-1 B-A B1.11 Shell Circumfe~ential Weld Vol X - -

714" Augmented Examinations per 10 FR 0.55a (g)(ii)( A)

(3) (ii) to be examined 1 st. Outage.1st. Period. 3rd.

Interval VV-1A B-A B1.12 Shell Longitudiinal Weld Vol X 150" Augmented Examinatons per 10 FR 0.55a (g)(ii)( A)

(3) (ii) to be examined 1 st. Outage,1st. Period 3rd.

Interval W-18 B-A B1.12 Shell Longitudinal Weld Vol X - -

150" Augmented Examinations per 10 FR 0.55a (g)(ii)( A)

(3) (ii) to be examined 1 st. Outage,1st. Period 3rd.

Interval VV-1C B-A B1.12 Shell Lor gitudinal Wekt Vol X 150" Augmented Examinations per 10 FR 0 55a (g)(ii)( A)

(3) (ii) to be examined 1 st. Outage.1st. Period. 3rd.

Interval W-2A B-A B1.12 Shell Longitudinal Weld Vol X - -

150" Augmented Examinations per 10 FR 0.55a (g)(ii)( A)

(3) (ii) to be exa nined 1 st. Outage,1st. Period. 3rd.

Interval FILE: RPVPLAN 01 Page 01 - 1 of 01 - 13

(/ 'O 'd James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] A NenMW Third inservice inspecCon Interval Date: Januar,7,1998 Ten - Year inspection Plan ReGsion 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 01 - Reactor Prenure Vessel Drawing Number: MSK-3036 Line No. 02V-1 Shell Welds - continued W -2B B-A B1.12 Shell Longitudinal Weld Vol X 150" Augmented Examinations per 10 FR 0 55a (g);ii)( A)

(3) (ii) to be examined 1 st. Outage,1st. Period. 3rd.

Interval W-2C B-A B1.12 Shell Longitudinal Weld Vol X - -

150" Augmented Examinahons per 10 FR 0.55a (g){ E)( A)

(3) (ii) to be examined 1 st. Outage 1st Period. 3rd.

Interval W-3A B-A B1.12 Shell Longitudinal Weld Vol X - -

150" AugmentM Examinations per 10 FR 0.55a (g)( H){ A)

(3) (ii) to be examined 1 s'. Outage,1st. Penod,3rd.

Interval W -3B B-A B1.12 Shell Longitudinal Weld Vol X 150" Augmented Examinations per 10 FR 0.55a (g){ ii)( A)

(3) (ii) to be examined 1 st Outage 1st. Period 3.d.

Interval W-3C B-A B1.12 Shell Longitudinal Weld Vol X 150" Augmented Examinations per 10 FR 0.55a (g)(ii)( A)

(3) (ii) to be examined 1 st. Outage,1st. Period. 3rd.

Interval W-4A B-A B1.12 Shell Longitudinal Weld Vol X 150" Augmented Examinations per 10 FR 0.55a (g)( E)( A)

(3) (ii) to be examined 1 st Outage.1st. Periou. 3rd.

Interv,al W-48 B-A B1.12 Shell Longitudinal Weld Vol X 150" Augmented Examinations per 10 FR 0.55a (g)( E){ A)

(3) (ii) to be examined 1 st Outage.1st Period,3rd.

Interval W-4C B-A B1.12 Shell Longitudinal Weld Vol X 150" Augmented Examinations per 10 FR 0.55a (g)( E)( A)

(3) (ii) to be examined 1 st. Outage.1st. Period,3rd.

Interval FILE: RPVPLAN 01 Page 01 - 2 of 01 -13

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h James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] gNew Third inservice Inspection interval Date: January 7,1998 Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME IDENTPFICATION CODE WELD CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THfCK REMARKS 01 -Reactor Vessel Drawing No. TASK-3036 Line No. 02V-1 Closure (Top) Head VC-TH-2-F B-A B1.40 Head-to-Flange Weld Vol/ Surf -

X -

670" VC-TH-1-2 B-A B1.21 Top Head Cire Weld Vol -

X -

343" W-TH-1A B-A B1.22 Top Head Meridional Weld Vol -

X -

83" W-TH-1B B-A B1.22 Top Head Meridional Weld Vol -

X -

83" W-TH-1C B-A B1.22 Top Head Meridional Weld Vol -

X -

83-W-TH-1D B-A B1.22 Top Head Meridional Weld Vol -

X -

83*

W-TH-1E B-A B1.22 Top Head Meridional Weld Vol -

X -

83*

W-TH-1F B-A B1.22 Top Head Meridional Weld Vol -

X -

83" W-TH-1G B-A B1.22 Top Head Meridional Weld Vol -

X -

83*

W-TH-1 H B-A B1.22 Top Head Meridional Weld Vol -

X -

83" RPV Studs B-G-1 B6.20 Studs 1 through 52 Vol X X X >2- 1/3 Each Period RPV Studs B-G-1 B6.30 Studs when removed Surf - -

X >2* (4) Studs

?

RPV Nuts B-G-1 B6.10 Nuts 1 through 52 Surf X X X -

1/3 Each Period RPV Flange Thread B-G-1 B6.40 Flange Threads 1 through 52 Vol X X X -

1/3 Each Period. (22) additional to be performed in 1st Period RPV Washers B-G-1 B6.50 Washers 1 through 52 VT-1 X X X -

1/3 Each Period RPV Bushings B-G-1 B6.50 Bushings 1 through 52 VT-1 X X X -

1/3 Each Period FILE: RPVPLAN.01 Page 01 - 3 of 01-13

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James . Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Af'> NewMPter Third Inservice inspection Interval Date: January 7,1998

1. Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE COD 2 REL ISIINTERVAL LTH OR car ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 01 - Reactor Pressure Vessel Drawing Number: MSK-3036 tJne No. 02V-1 Bottom Head - continued VC-BH-1-2 B-A B1.21 Bottom Head Circ Weld Vol - -

X 566" VC-BH-2-3 B-A B1.21 Bottom Head Cire Weld Vol -

X -

317" W-BH-2A 9-A B1.22 Bottom Head Meridional WrId Vol - -

X 54" W-BH-28 B-A B1.22 Bottom Head Meridional Weld Vol - -

X 54" W-BH-2C B-A B1.22 Bottom Head Meridional Weld Vol - -

X 54" W-BH-2D B-A B1.22 Bottom Head Meridional Weld Vol - - X 54" t

W-BH-2E B-A B1.22 Bottom Head Meridional Weld Vol - -

X 54" W-BH-2F B- A B1.22 Bottom Head Meridional Weld Vol - -

X 54" W-BH-1A B-A B1.22 Sottom Head MeridionalWeld Vol - -

X 69" W-BH-1 B B-A R1.22 Bottom Head Meridional Weld Vol - -

X 69" W-BH-1C B-A B1.22 Bottom Head Meridional Weld Vol - -

X 69" W-BH-1D B-A B1.22 Bottom Head MeridionalWeld Vol - -

X 69" ,

W-BH-1 E B-A B122 Bottom Head Meridional Weld Vol - -

X 69" W-BH-1F B-A B1.22 Bottom Head MeridionalWeld Vol -

X -

69*

W-BH-1G B-A B1.22 Bottom Head MeridionalWeld Vol - X -

69" W-BH-1H B-A B1.22 Bottom Head Meridional Weld Vol -

X -

69" FILE: RPVPLAN 01 Page 01 - 4 of 01 -13 2

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4 bMM James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third Inservice inspection Interval Date: January 7,1998 Ten -Year inspectinn Plan Revision 0 COMPONENT ASME ASME ASME IDENTIFICATION W7_LD CODE CODE CODE REL ISIINTERVAL CAT ITEM LTH OR DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARMS 01 - Reactor Pressure Vessel Drawing Number: MSK-3038 Une No. 02V-1 Reactor Pressure Vessel Nozzfes N1A B-D B3.90 28 0" RC Outlet Nozzle Vol -

X -

At least 25% but not more than 50% (credited) of the nozzles by End of 1". Period, remainder by end of the interval.

N-1B B-D B2.90 28.0" RC Outlet Nozzle Vol X - -

At least 25% but not more than 50% (credited) of the nozz!es by End of 1". Period, remainder by end of the interval.

N-2A B-D B3.90 12.0" RC Intet Nozzle Vol X - -

At least 25% but not more than 50% (credited) c'the nozzles by End of 1". Period, remainder by end of the interval.

N-28 B-D B3.90 12.0" RC Inlet Nozzle Vol X - -

At least 25% but not more than 50% (credited) of the nozzles by End of 1". Period, remainder by end of tfe interval.

N-2C B-D B3.90 12.0" RC Inlet Nozzle Vol -

X -

At least 25% but not more than 50% (credded) of the nozzles by End of 1". Period, remainder by end of the interval.

N-2D B-D B3.90 12.0" RC Inlet Nozzle Vol - -

X At least 25% but not more than 50% (credited) of the nozzles by End of 1". Period, remainder by end of the interval.

N-2E B-D B3.90 12.0" RC Inlet Nozzle Vol X - -

At least 25% but not more than 50% (credited) of the nozzles by End of 1". Period, remainder by end of the interval.

N-2F B-D B3.90 12.0" RC Intet Nozzle Vol - -

X At least 25% but not more than 50% (credited) of the nozzles by End of 1". Period remainder by end of the interval.

FILE: RPVPLAN 01 Page 01 - 5 of 01 -13

LJ \.J' Q James A. Fitzpatrick Nuclear Power Plant [[::JAF-tSI-0003|JAF-tSI-0003]] gh Paw Third hiservice Inspection Interval Date: January 7,1998 Ten -Year inspection Plan Rev'sion 0 COMPONENT ASME ASME ASME VELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAis REO PER1 PER2 PER3 THICK REMARKS 01 - Reactor Pressure Vessel Drawing Number: MSK-3036 Line No. 02V-1 Reactor Pressure Vessel Nozzles - continued N-2G B-D B3.90 12.0" RC Inlet Nozzle Vol - -

X At least 25% but not more than 50% (credited) of the nozzles by End of 1". Period. remainder by end of the irnerval.

N-2H 3-D B3.90 12.0" RC Inlet Nozzle Vol X - -

At least 25% but not more than 50% (credrted) of the nozzles by End of 1". Period, remainder by end of the interval.

N-2) B-D B3.90 12.0" RC Intet Nozzle Vol - -

X At least 25% but not more than 50% (credrted) of the nozzles by End of 1". Period remainder by end of the interval.

N-2K B-D B3.90 12.0" RC Inlet Nozzle Vol X - -

At least 25% but not more than 50% (cred4ed) of the nozzies by End of 1". Feriod, remainder by end of the interval.

N-3A B-D Bo 90 24.0" MS Nozzle Vol X - -

At least 25% but not more than 50% (credited) of the nozzles by End of 1". Period, remainder by end of the interval.

N-38 B-D B3.90 24 0" MS Nozzle Vol X - -

At least 25% but not more than 50% (credited) of the nozzles by End of 1". Period remnnder by end of the interval.

N-3C B-D B3.90 24 0" MS 'Jozzle Vol -

X -

At least 25% but not more than 50% tc; edited) of the nozzles by End of 1". Perio<'. remairx.7r by end of the interval.

N-3D B-D B3.90 24.0* MS Nozzle Vol - -

X At least 25% but not more than 50% (credited) of the nozzles by End of 1". Period remainder by end of the interval.

FILE: RPVPLAN 01 Page 01 - 6 of 01 -13

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U, V .

V James A. Fitzpatrick Nucle:r Power PITnt [[::JAF-ISI-0003|JAF-ISI-0003]] g Pbur Third Inservice inspection Interval Ten - Year inspection Plan Date: January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR ;

CAT ITEM , DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 01 - Reactor Pressure Vessel Drawing Number: MSK-3036 Line No. 02V-1 Reactor Pressure VesselI .zles - continued N-4A B-D B3.90 12.0" FW Nozzle Vol RR-7 - - X At least 25% but not more than 50% (credited) of the nozzles by End 41". Period remainder by end of the interval.

N-4B B-D B3.90 12.0" FW Norzle Vol RR-7 - -

X At least 25% but not more than 50% (credited) of the nozzles by End of 1". Period, remainder by c.1d of the interval, N-4C B-D B3.90 12.0" FW Nozzle Vol RR-7 - -

X At least 25% but not more than 50% (credited) of the nozzles by End of 1". Period, remainder by end of the l intervat.

N4D B-D B3.90 12.0" FW Nozzle Vol RR-7 - -

X At least 25% but not more than 50% (credited) of the nozzles by End of 1". Period, remainder by end of the interval.

N-5A B-D B3.90 .0.0" CS Nozzle Vol -

X -

At least 25% but not more than 50% (credited) of the nozzles by End of 1". Period, remainder by end of the interval.

N-5B B-D B3.90 10.0" CS Nozz!e Vol - - X At least 25% but not more than 50% (credited) of the nozzles by End of 1". Period, remainder by end of the

' interva!.

N-8A B-D B3.90 4.0" JP Nozzle Vol - -

X At least 25% but not more than 50% (credited) of the nozzles by End of 1". Period, remainder by end of the interval.

N-8B B-D B3 90 4.0" JP Nozzle Vol X - -

At least 25% but not more than 50% (credited) of the nozzles by End of 1". Period, remainder by end of the interval.

File: RPVPLAN 01 Pasa 01 - 7 of 01 -13

N/

James A Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] N]

4 bMM Third Inservice inspection Interval Date: January 7,199R Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION COCE CODE CODE REL ISilNTERVAL LTH OR CAT ITf*** D 3CRtPTION

. EXAM REQ PER1 PER2 PER3 THICK REMARKS 01 - Reactor Pressure Vessel Drawing Number: MSK-3036 Line No 02V-1 Reactor Pressure Vessel Nozzles N-9 B-D B3.90 3.0" CRD Nozzle Vol - - - Exempt IWB-1220(a)

Various B-O B14.10 CRD Housing Welds Vol/ Surf - -

X various B-G-2 B7.80 CRD Fenetration Botting VT-1 - - -

<2" Only when disassembled. 8 bolts per assembly, limited to components setected under B-J.

Various B-G-2 87.80 in-Core Monitoring Bolting VT-1 - - - <2* Only when disassembled,8 bolts per assembly, Limited to components selected under B-J N-TH-A B-D B3.90 5.75"CH Inst. Nozzle Vol X - -

N-TH-A-C1 B-J B9.11 5.75" Nozzle-6.0" Flange Vot/ Surf X - -

N-TH-A B-G-2 87.10 inst. Nozzle Flange Bolting VT-1 X - -

<2" Limited to components selected under B-J,8 bolts per assembly N-TH-B B-D B3.90 3.812" CH Vent Nozzle Vol -

X -

N-TH-B-C1 B-J 89.11 3.812" Nozzle-4.0" Flenge Vol/ Surf - - -

N-TH-B B-G-2 B7.10 Hd. Vent Nozzle Flange Boiting VT-1 - X -

<2" Limited to components selected under B-J. 8 bc4ts per asserpbly N-TH-C B-D B3.90 5.75" CH Inst. Nozzle Vol - -

X t ~ TH-C-C1 B-J 89.11 5.75" Nozzle-6.0" Flange Vol/ Surf - - -

N-TH-C B-G-2 87.10 inst. Nozzle Flange Botting VT-1 - -

X <2" Limited to components selected under B-J. 8 bolts per assembly N-10 N/A N/A 2.0" Instrument Nozzle - - - - Exempt IWB-1220(c)

FILE: RPVPLAN.01 Page 01 - 8 of 01 - 13

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b James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] N.J g Po m r Third Inservice inspection Interval Ten -Year inspection Plan Date: January 7,1998 -

Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DEACRIPTION EXAM REQ PER1 PER2 PER3 THICK + REMARKS 01 - Reactor Pressure Vessel Drawing Number: MSK 3036 Line No. 02V-1 Reactor Pressure Vessel Nozzle inner Radius N-11 A N/A N/A 2.0" instrument Nozzle - - - - Exerrpt IWB-1220(c)

N-11B N/A N/A 2.0" instrument Nozzle - - - -

Exerr pt IWB-1220(c)

N-12A N/A N/A 2.0" instrument Nozzle - - - -

Exempt IVG-1220(c)

N-128 N/A N/A 2.0" instrument Nozzle - - - -

Exempt IVS-1220(c)

N-16A N/A N/A 2.0" instrument Nozzle - - - -

Exempt IWB-1220(c)

N-16B N/A N/A 2.0" instrument Nozzle - - - - Exempt IWB-1220(c)

N-1A-IR B-D B3.100 28.0" RC Outlet Nozzle IRS Vol -

X -

N-18-IR B-D B3.100 28.0" RC Outlet Nozzle IRS Vol X - -

N-2A-IR B-D B3.10012.0* RC Inlet Nozzle IRS Vol X - -

N-2B-IR B-D B3.10012.0" RC Inlet Nozzle IRS Vol X - -

N-2C-IR B-D B3.10012.0" RC Inlet Nozzle IRS Vol -

X -

N-2D-IR B-D B3.10012.0* RC Inlet Nozzle IRS Vol - - X

?

N-2E-IR B-D B3.10012.0" RC Inlet Nozzle IRS Vol X - -

N-2F-iR B-D B3.10012.0" RC Intet Nozzle IR"- Vor - -

X N-2G-IR B-D B3.10012.0" RC Inlet Nozzle IRS Vol - -

X N-2H-IR B-D B3.10012.0" RC Inlet Nozzle IRS Vol X - -

N-2J-IR B-D B3.10012.0" RC Inlet Nozzle IRS Vol - -

X FILE: RPVPt.AN 01 Page 01 - 9 of 01 -13

( (. 3 k.. d James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] b

$b Third Inservice Inspection Interval Ten - Year inspection Plan Date: January 7,1998 Revision 0 COMPONENT ASME ~ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRfPTION EXAM REQ PER1 PER2 PER3 THfCK REMARKS 01 - Reactor Pressure Vessel I Dravnng Number: MSK-3036 Line No 02V-1 Reactor Pressure Vessel Nozzle Inner Radius N-2K-lR B-D B3.10012.0" RC Inlet Nov.zle IRS Vol X - -

N-3A-IR B-D B3.100 24.0" MS Nozzle IRS Vol X - -

N-38-lR B-D B3.100 24.0" MS Nozzle IRS Vol X - -

N-3C-IR B-D B3.100 24.0" MS Nozzle IRS Vol -

X -

N-3D-Id B-D B3.100 24.0" MS Nozzle IRS Vol - -

X N-4A-IR B-D B3.10012.0" FW Nozzle IRS Vol RR-7 - -

X NUREG 0619 h 4? IR B-D B3.10012.0" FW Nozzle IRS Vol RR-7 - -

X NUREG 0619 N-4C-IR B-D B3.10012.0" FW Nozzle IRS Vol RR-7 - -

X NUREG 0619 N-4D-IR B-D B3.10012.0" FW Nozzle IRS Vol RR-7 - -

X NUREG 0019 N-5A-IR B-D B3.10010.0" CS Nozzle IRS Vol -

X -

N-5B-IR B-D B3.10010.0" CS Nozzle IRS Vol - -

X N-8A-IR B-D B3.100 4.0" JP Nozzle IRS Vol - -

X ,

N-8B-lR B-D D3.100 4.0" JP Nozzle IRS Vol X - -

N-9-IR B-D 93.100 3.0" CRD Nozzle IRS Vol RR-7 - - -

Exempt IWB-1220(a)

N-TH-A-IR B-D B3.100 5.75- CH inst. Noz ;RS Vol X - -

N-TH-B-IR B-D B3.100 3.812" CH Vent Noz. IRS \ 01 -

X -

N-TH-C-!R B-D B3.100 5.75"CH Inst. Noz. IRS Vol - -

X FILE: RPVPLAN 01 Page 01 -10 of 01 - 13

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] g b Third Inservice lospection Interval Ten -Year inspection Plan Date: January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATIC M CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRfPTION EXAM REQ PER1 PER2 PER3 THfCK REMARKS t

01 - Reactor Pressure Vessel Drawing Number: MSK-3036 Line No. 02V-1 Reactor Pressure Vessel Support Skirt N-10-IR N/A N/A 2.0" IRS - - - -

Exempt IWB-1220(c)

N-11 A-IR N/A N/A 2.0" Inst. Nozzle IRS - - - -

Exempt IWB-1220(c)

N-118-IR N/A N/A 2.0" Inst. Nozzle IRS - - - -

Exempt IWB-1220(c)

N-12A-IR N/A N/A 2.0" Inst. Nozzle IRS - - - -

Exempt IWB-1220(c)

N-128-IR N/A N/A 2.0* Inst Nozzle IRS - - - -

Exempt IWB-1220(c) b N-16A-IR N/A N/A 2.0" Inst. Nozzle IRS - - - -

Exempt IWB-1220(c)

N-168-IR N/A N/A 2.0" inst.Nnzzle IRS - - - -

Exempt IWB-1220(c)

VC-SKC B-H 88.10 RPV Support Skirt Weld Surf RR-4 X X -

522" CC N-509. % of weld each period VC-SKC F-A F1.40 RPV Support Skirt VT-3 RR-2 X - -

CC N-491-1 VC-SKC-1 N/A N/A RPV Intermediate Skirt Weld N/A - - -

552" No Exan- Required VC-SKC-2 N/A N/A RPV Intermediate Skirt Weld N/A - - -

552" No Exam Required VH-SKV-1 N/A N/A RPV intermediate Skirt Weld N/A - - -

27" No Exgm Required VH-SKV-2 PIA N/A RPV Intermediate Skirt Weld N/A - - - 27' No Exam Required VH-SKR-1 N/A N/A RPV Intermediate Skirt Weld N/A - - -

39" No Exam Required VH-SKR-2 N/A N/A RPV Intermediate Skirt Weld N/A - - -

39" No Exam Required VH-SKR-3 N/A N/A RPV Intermediate Skirt Weld N/A - - -

39" No Exam Required FILE: RPVPLAN 01 Page 01 -11 of 01 -13

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James . Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h

$ Third Inservice Inspection Interval Ten - Year inspection Plan Date: January 7,1998 Revision 0

' COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTHLn CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS t

C1 - Reactor Pressure Vessel Drawing Number: MSK-3036 VH-SKR-4 N/A N/A RPV Intermediate Skirt Weld N/A - - -

39" No Exam Required Stabilizer-1 B-H 88.10 Vessel Stabilizer Surf RR-4 -

X -

CC N-509 Stabilizer-2 B-H 88.10 Vessel Stabilizer Surf RR-4 -

X -

CC N-509 Stabilizer-3 B-H 88.10 Vessel Stabilizer Surf RR-4 - -

X CC N-509 Stabilizer-4 B-H B8.10 Vessel Stabilizer Surf RR-4 - -

X CC N-509 Line No. 02V-1 RPV Interior Jet Pump B-N-2 B13.20 Riser Brace Attachment Weld VT-1 - -

'. Accessible weids Feedwater Sparger B-N-2 B13.30 Bracket We!ds VT-3 - -

X Accessible welds Core Spray B-N-2 B13.30 Bracket Vessel Weldi VT-3 - -

X Accessible welds Top Guide B-N-2 B13.40 Assembly VT-3 - -

X Accessible surfaces Shroud Support B-N-2 813.40 Access Cover VT-3 - -

X Accessible surfaces Vessel B-N-2 B13.30 Guide Rod Support VT-3 - -

X Accessible welds Vessel B-N-2 B13.30 Steam Dryer Support Bracket VT-3 - -

X Accessible welds Vessel B-N-2 B13.30 Steam Dryer Hold Down Bracket VT-3 - -

X Accessible welds Vzssel B-N-2 B13.20 Surv. Capsule Holder Bracket VT-1 - -

X Accessible welds Vessel B-N-2 B13.30 Shroud Support Plate Weld 3 - -

X Accessible welds Vcssel B-N-2 B13.30 Gusset Plate VT-3 - -

X Accessible welds FILE: RPVPLAN 01 Page 01 - 12 of 01 -13

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] b

$ Third Inservice inspection Interval Ten - Year Inspection Plan Date: January 7,1998 Revision 0 COMPONENT ASME ASME ASME WILD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCSUPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS i

01 - Reactor Pressure Vessel -

Drawing Number: MSK-3036 Line No. 02V-1 RPV Interior Shroud Support B-N-2 B13.40 Gusset & Weld to SuW Plate VT-3 - -

X Accessible welds CRD B-N-2 . B13.40 Guide Tube VT-3 - -

X AccessiNe surfaces Core Plate B-N-2 B13.40 Assembly VT-3 - - X Accessible serriaces !

t Core Plate B-N-2. B13.40 Hold Down Botting VT-3 - -

X Accessible surfaces Fuel Supt. Casting B-N-2 B13.40 Assembly VT-3 - -

X Accessible surfaces Bottom Head B-N-1 B13.10 General Area VT-3 X X X Accessible areas Shroud B-N-2 B13.40 Vertical Shroud Welds VT-3 - -

X Accessible surfaces Groud B-N-2 B13.40 Horizontal Shroud Welds VT-3 - -

X Accessible surfaces t

FILE: RPVPtAN 01 Page 01 - 13 of 01 -13

v' LJ James A Fitzpatrick im*-- Dower Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

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gb Third Inservice Inspection Iderval Ten -Yearinspection FHn Date: January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH CR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 TH!CK TE2' ARKS e

C2 Reactor Recirculation System Drawing Number: MSK-3001 Line No.12*-WH GE-4A from nozzle N2A N-2A-SE B,- B5.10 Nozzle-Safe End Vol/ Surf X - -

.54T IGSCC D every 2 refuereg outages 12-02-2-1 B-J 89.11 Safe End-Pipe Vot/ Surf X - -

54T iGSCC E every 2 refueing outages Terr, mal End 12-02-2-1-LS1 B-J 89.12 Pipe long Seam Vol/ Surf RR-5 X - -

.54T IGSCC A-1.CC N-524 12-02-2-2-LS2 B-J 89.12 Pipe Long Stam Vot/ Surf RR-5 - - - .54T IGSCC A-1. CC N-524 12-02-2-2 B4 B9.11 Pipe-Elbow Vo!/ Surf - - -

.54T IGSCC C-2, once every 10 years 12-02-2-2-LS1 B-J 89.12 Elbow Long seam VW RR-5 - - -

.54T IGSCC A-1, CC N-524 12- 02-2-3-LSI B-J 89.12 Elbow Long seam Va/ Surf RR-5 - - -

.54 7 IGSCC A-1, CC N-524 12-02-2-3 B-J 89.11 E! bow-Pipe Vot/ Surf - - -

.54T IGSCC C-2, once every 10 years 12-02-2-3-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf RR-5 - - -

.54T IGSCC A-1, CC N-524 12-02-2-4-LS1 B-J B9.12 Pipe Long seam Vol/Surt RR-5 - - -

.54T IGSCC A-1, CC N-524 02-2-4A-NN-1 A N/A N/A Whip Restraint N/A - - - - No Exam required 12-02-2-3A B-J B9.32 1.0" Branch Connection N/A - - -

54T Exempt IWB-1220(a) 12-02-2-4 B-J 89.21 12.0" Branch Connection VoLSur? X - -

.54T IGSCb C-2. cnce every 10 years FILE:RCPLAN 02 Page C2 - 1 Of 02 - 29

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Jrnes A. Fitzpatrick Nuclear Powr Plant JAF-ISl4003 (V )

A hMPewer Third Inservice Inspection interval Date: January 7,1998 Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL tSIINTERVAL LTH OR CAT (TEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS T

02 Reactor Recirculation System Drawing Numter: MSK-3001 Line No.12*'-WH-GE-5A from nozzle N2B N-28-SE B-F B5.10 Nozzle-Safe End Vol/ Surf X - -

.54T IGSCC D svery 2 refueling outages 12-02-2-7 B-J Bt . Safe End-Pipe Vol/ Surf X - -

.54T IGSCC C-2, once every to years. Terminal End 12-02-2-7-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf X - -

.54T IGSCC A-1. CC N-524 12-02-2-8-LS2 N B9.12 Pipe Long Seam Vol/ Surf RR-5 - - -

.54T IGSCC A-1, CC N-524 1242-2-8 B-J 89.11 Pepe-Elbow Vol/ Surf - - -

54T IGSCC E, every 2 refueling outages 12-01-2-8-LS1 B-J 89.12 Elbow Long Seam Vol/ Surf RR-5 - - -

54T IGSCC A-1 CC N-524 12-02-2-9-LS2 B-J 89.12 Elbow Long Seam Vol/ Surf RR-5 - - -

.54T IGSCC A-1 CC N-524 12-02-2-9 B-J 89.11 Elbow-Pipe Vol/ Surf - - -

.54T IGSCC C-2, cnce every 10 years 12-02-2-9-LS1 B-J B9.12 Pipe Long Seam Vol/ Surf RR-5 - -

_54T IGSCC A-1 CC N-524 12-02 2-9A B-J 09.32 1.0" Branch connection N/A - - - -

Exempt IWB-1220(a) 02-2-5A-NN-1C N/A N/A Yhip restraint N/A - - - -

No Exam required 12-02-2-10-LS1 B-J 89.12 Pipe Long seam Vol/ Surf RR-5 -

X- -

54T IGSCC A-1. CC N-524 12-02-2-10 B-J 89.31 12.0 Branch Con.m Vol/ Surf -

X -

.54T IGSCC C-2. once every 10 years 4

FILE: RCPl.AN_02 Page 02 - 2 Of 02-29

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.!ames A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] M llowMh Third inservice inspection Interval Date: January 7.1998 Ten -Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL !SIINTERVAL LTH OR CAT ITEM D5SC"flPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS _

02 Reactor Recirculation System Drawing Number: IC K-3001 Line No.12*-WH-GE-6A from nozzle N2C N-2C-SE B-F B5.10 Nozzk-Safe End Voi/Sud -

X -

.54 7 IGSCC D every 2 refuefog outages 12-02-2-23 B-J 89.11 Safe End-Pipe VouSurf -

X - .54T IGSCC E every 2 refuermg outages. Temvial End 12-02-2-23-LS1 B-J 89.12 Pipe Long Seam VoVSurf RR-5 -

X - .54T IGSCC A-1.CC N-524 12-02-2-24-LS2 B-J 09.12 Pipe Long Seam VoVSurf RR-5 - - -

.54T IGSCC A 1.CC N-524 12-02-2-24 B-J 89.11 Pipe-Elbow Vot/ Surf - - - .54 7 IGSCC C-2, once every 10 years 12-02-2-24-LS1 B-J 89.12 Elbow Long Seam VouSurf RR-5 - - -

.54T IGSCC A-1.CC N-524 12-02-2-25-LS2 B-J 89.12 Elbow Long Seam Vol/ Surf RR-5 - - -

.54T IGSCC A-1,CC N-524 12-02-2-25 B-J B9.11 Elbow-Pipe Vol/ Surf - - -

.54T IGSOC C-2. once every 10 years 12-02-2-25-LS1 B-J 89.12 Pipe Long Seam VoVSurf RR-5 - - -

.54T IGSCC A-1. CC N-524 02-2-6A-NN-1 E N/A N/A Whio Restraint N/A - - - -

No Exam Required 12-02-2-25A B-J 89.32 1.0" Branch Connection N/A - - -

.54T Es empt IWB-1220(a) 12-02-2-26 B4 89.11 Pipe-Reducer Vol/ Surf - - -

.54T IGSCC C-2. Once every 10 years t

4 FILE: RCPLAN 02 Page 02 - 3 Of 02 -29 i

W. s James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h

gh Third Inservice inspection Interval Ten -Year inspection Plan Date: January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THtCK REMARKS 9

02 Reactor Recirculation System Drawing Number: MSK-3001 Une No 28"-WH-GE-2A 28-02-2-27 B-J 89.11 Reducer-Cross Vol/ Surf - - -

1.36" 'GSCC C2. once every 10 years 28-02-2-30 B-J 89.11 Cross-Tee VoVSurf - - -

1.36" IGSCC C-2. ence every to years 28-02-2-31 B-J 89.11 Tee-Pipe Vo!! Surf - - -

1.36" IGSCC C-2. once every 10 years 28-02-2-31-LS1 B-J 69.12 Pipe Long Seam VoVSurf .~to-5 - - -

1.36* IGSCC A-1. CC N-524 02-2-2A-H3-3 N/A N/A Hydraulic Snubber VT-3 RR4* - - - .750" TS Section 3.6.1 28-02-2-31A B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

0.750 CC N-509 23-02-2-318 B-K-1 B10.10 Integraf Attachment Surf RR-4 - - - -

CC N-509 02-2-2A-HS-4 N/A t#A Hydraulic Snubber VT-3 RR-11 - - - -

TS Section 3.6.1 02-2-3A-NN-2C t#A PFA Whip Restraint N/A - - - -

No Exam Required 28-02-2-31C B-K-1 B10.10 Integral Attachment Surf RR-4 -

X - -

CC N-509 02-2-2A-AN-5 F-A F1.10b Constraint VT-3 RR-2 -

X -

1.5" CC N-491-1. need drawing 28-02-2-31D - - - - - - - -

This s ppyt was removed 02-2-2A-NN-5A N/A t#A Whip Restraint N/A - - - -

No Exam Required 28-02-2-32 B-J 89.31 4.0" Branch Connection VoVSurf - -

.337" IGSCC A 4-02-2-47C B-J 89.31 4.5" Branch Connection VoVSurf X - -

.337" IGSCC A. Capped 23-02-2-31E - -

Insu!ation Lugs - - - - -

No Exam Required FILE RCPLAN 02 Page 02- 4 Of 02-29

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

$ .b8 Third inservice inspect **.n Interval Ten - Year inspection Plan Date: January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISliNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS

- .msmw 02 Reactor Recirculation System Drawing Number: MSK-3001 Line No. 28*-WH-GE-2A 28-02-2-33 B-J P9.11 Pipe-Elbow Vot/ Surf - - -

1.36" IGSCC E every 2 refueling ouWes 28-02-2-33-LS1 B4 89.12 Elbow Long Seam VouSurf RR-5 - - -

1.36" IGSCC A-1. CC N-524 28-02-2-33-LS2 B4 B9.12 Fabw Long Seam Vol/ Surf RR-5 - - -

1.36" !GSCC A-1. CC N-524 28-02-2-33-LS3 BJ B9.12 Pipe Long Seam Vol/ Surf RR-5 - - -

1.36" IGSCC A-1 CC N-524 02-2-2A-HS-8 N/A N/A Hydraulic Snubber VT-3 RR-11 - - - -

TS Sectron 3.6.1 23-02-2-34 B4 B9.11 Va!ve MOV-53A-Elbow Vol/ Surf - - -

1.36" IGSCC C-2 every 10 years 28-02-2-34-LS1 8-J 89.12 Elbow Long Seam Vol/ Surf RR-5 - - -

1.36" IGSCC A *, CC R5"4 28-02-2-34-LS2 B-J B912 Efbow Long Seam Vol/ Surf R9-5 - - -

1.36" IGSCC A-1 CC N-524 MOV-53A B-M-2 B12.50 28" Gate Valve VT-3 - - - -

When Disassembled, one valve in a group of valves MOV-53A B-G-2 37.70 Valve Bolting VT-1 - - -

<2" Limited to valve selected under B-M-2 28-02-2-35 B4 89.11 Valve MOV-53A-Pipe Vol/ Surf - X -

1.3S" IGSCC C-2. every 10 years 28-02-2-35-LS1 B-J B9.12 Pipe Long Seam Vot/ Surf RR-5 -

X -

1.36" IGSCp A-1. CC N-524 28-02-2-35A B-J 89.32 3/4" Branch Connection Surf - - - -

Exempt IWB-1220(a) 28-02-2-36 B4 R9.31 4.0" 3 ranch Connection Vol/ Surf - - - -

IGSCC A 4-02-2-38C B-J 89.31 4.5" Branch Connection Vol/ Surf -

X -

.337" IGSCC A Capped 28-02 2-37 B-J 89.11 Pipe-Pumo 02-2-P-1 A Vol/ Surf X - -

1.36" IGSCC 2 every 10 years 28-02-2-37-LS1 B4 89.12 Pipe Long Seam Vol/ Surf RR-5 X - -

1.36" IGJCC A-1.CC N-524 FILE- RCPT.AN.02 Page 02 - 5 Of 02 - 29

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h h Third inservice Inspection Interval Date: January 7,1998 Ten - Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODfi REL IS8 INTERVAL LTH OR CAT DESCRfPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS

- . ITEM - -

02 Reactor Recirculation System Drawing Number: FJ 5K-3001 Line No.12"-WH-GE-7A from nozzle N2D N-2D-SE B-F B5.10 Nozzle-Safe End Vol/ Surf - - X .54T IGSCC D. every 2 refueting outages 12-02-2-12 B4 B9.11 Safe End-Pipe Vol/ Surf - -

X .54T IGSCC E. every 2 refueling outages Terminal End 02-02-2-12-LS1 B4 B9.12 Pipe Long Seam Vol/ Surf RR-5 - -

X .54T IGSCC A-1 CC N-524 12-02-2-13 B4 8911 Pipe-Elbow VotiSurf - - -

.54T IGSCC C-2, every 10 years 12-02-2-13-LS1 B-J 89.12 Elbow Long Seam Vol/ Surf RR-5 - - -

.54T IGSCC A-1, CC N-524 12-02-2-13-LS2 B-J B9.12 Pipe Long Seam Vol/ Surf RR-5 - - -

.54T IGSCC A-1, CC N-524 12-02-2-14 B4 89.11 Elbow-Pipe Vol/ Surf - - -

.54T IGSCC C-2 every 10 years 12-02-2-14-LS1 B4 B9.12 Pipe Long Seam Vol/ Surf RR-5 - - -

.54T IGSCC A-1 CC N-524 12-02-2-14-LS2 B-J 89.12 Elbowlong Seam Vol/ Surf RR-5 - - -

.54T IGSCC A-1.CC N-524 02-2-7A-NN-2C N/A N/A Whip Restraint N/A - - - -

No Exam Required 12-02-2-14A B4 89.32 1.0" Branch Connection Surf - - - - Exempt IWB-1220(a) 12-02-2-15 B-J 89.31 12.0" Branch Conr% ion Vol/ Surf - - -

.54T IGSCC E. every 2 refuelmg outages 12-02-2-15-LS1 B-J B9.12 Pipe Long Seam Vol/ Surf RR-5 - - -

.54T IGSCC A-1, CC N-524 FILE: RCPLAN 02 Page 02 - 6 Of 02 - 29

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James A. Fitzpatrick Nuclear Power Plant Q)

[[::JAF-ISI-0003|JAF-ISI-0003]] 4 3588Mb Third inservice inspection Interval Date: January 7,1998

Ten -Yearinspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENflFICATION CODE CODE CODE REL 108 INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARMS 9

02 Reactor Recirculation System Drawing Number: MSK-3001 Line No.12"-WH-GE-6A from nozzle N2E N-2E-SE B-F B5.10 Nozzh-Safe End Vot/ Surf X - -

.54T IGSCC D every 2 refueling outage 12-02-2-17 B.J 89.11 Safe End-Pipe Vo:/ Surf X - -

.54T IGSCC C-2. ev=ry 30 years. Temwnal End 12-02-2-17-LS1 B-J B9.12 Pipe Long Seam VoUSurf RR-5 X - -

.54T IGSCC A-1. CC N-524 12-02-2-18 B-J 89.11 Pipe-Elbow Vol/ Surf - - -

54T IGSCC E. every 2 refueling outages 12-02-2-18-LS1 BJ B9.12 Elbow Long Seam Vol/ Surf RR-5 - - -

.54T IG."-CC A-1. CC N-524 12-02-2-18-LS2 B-J 89.12 Pipe Long Seam Vot/ Surf RR-5 - - -

.54T IGSCC A-1. CC N-524 12-02-2-19 B-J 89.11 Elbow-Pipe Vot/ Surf - - -

.54T IGSCC E em 2 refuereng outages 12-02-2-19A B-J 89.32 1.0 Branch Connection N/A - - - -

Exempt IWB-1220(a) 12-02-2-19-LS1 B-J B9.12 Pipe Long Seam Vol/ Surf RR-5 - - -

.54T IGSCC A-1.CC N-524 12-02-2-19-LS2 B-J B9.12 Elbow Long Seam Vol/ Surf RR-5 - - -

.54T IGSCC A-1. CC N-524 i

02-2-8A-NN-2A N/A N/A Whip Restraint N/A - - - -

No Exam Required 12-02-2-20 B-J 89.31 12.0 Branch Connection VeUSurf - - -

.54T IGSCC C-2. every 10 years 12-02-2-20-LS1 B-J 89.12 Pipe Long Seam Vot/ Surf RR-5 - - -

.54T IGSCC A-1. CC N-524 i

Fil.E: RCPtAN 02 Page 02 - 7 Of 02-29

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-tSI-0003|JAF-tSI-0003]] b

$ Third Insmice inspection Interval Ten -Year inspection Plan Date: Janu,*.ry 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD fDENTIF1 CATION CODE CODE CCDE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 TECM REMARKS 02 Reactor Recirculation System Drawing Number: MSK-30C0 Line No. 22 -WH-GE-3A 22-02-2-22 B-J E9.11 Pipe-Cap VoVSurf - - -

.993- IGSCC E. every 2 refuehng outages 22-02-2-22-LS1 B-J 89.12 Pp Long Seam Vo Surf RR-5 - - -

.993- IGSCC A-1. CC t4-524 22-02-2-21 B-J 89.31 12.0" Branch Correcten Vot/ Surf - - - -

iGSCC A*

22-02-2-21-LS1 B-J 89.12 Pipe Long Seam VoUSurf RR-5 - - -

.993' IGSCC A-1. CC N-52 22-02-2-22A B-K-1 810.10 Integral Atta2. ment Surf RR-4 - - X .750- CC N-509 02-2-3A-AN-2 F-A F1.10b Constraint VT-3 RR-2 - -

X .750" CC N-491-1 need draveng 02-2-3A-NN-28 N/A N/A VMp Restraint N/A - - - - No Exam Regtnred 22-02-2-22B B-K-1 B10.10 Integraf Attachment Surf RR-4 - - -

.750 CC N-509 22-02-2-16 B-J 89.31 12.0" Branch Cory ection VoVSurf -

X - -

IGSCC A*

22-02-2 *6-LS1 B-J B9.12 Pipe Long Sesm VoVSurf RR-5 - - -

.993- IGSCC A-1. CC N-524 22-02-2-16-LS2 B-J 89.12 Pipe Long Seam VoVSurf RR-5 - - -

.993- IGSOC A-1. CC N-524 22-02-2-28 B-J 89.11 Cross-Pipe Vol/ Surf X - -

.933' IGSCC C-2. every 10 years 22-02-2-28-LS1 B-J B9.12 Pipe Long Seam Vol/ Surf RR-5 X - -

933' IGSC'C A-1. CC N-524 22-02-2-29 B-J 8911 Cross-Pipe VoVSurt - - -

.933* IGSCC C-2. every 10 years 22-02-2-29-LS1 B-J 89.12 Pipe Long Seam VoVSurf RR-5 - - -

.933" IGSCC A-1. CC N-524 02-2-3A-NN-1D N.'A N/A Whip Restraint N/A - - - - No Exam Requrred 22-02-2-11 B-J 89.31 12.0" Branch Connection Vo!/ Surf - - - -

IGSCC A*

FILE- RCPLAN 02 Page 02 - 8 Of C2-29

v , . . O James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] M hMh Third Inservice Inspection Interval Date: January 7,1998 Ten -Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISi tNTERVAL LTF 3R CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 TH3CK REMARKS 02-2 -l'eactor Recirculation System Drawing Number: IWtSK-3001 Line No. 22"-WH-GE-3A 22-02-2-11-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf RR-5 - - -

.933" IGSCC A-1.CC N-524 22-02-2-11-LS2 B-J B9.12 Pipe Long Seam Vol/ Surf RR-5 - - -

.933* IGSCC A-1, CC N-524 22-02-2-6B B-K-1 810.10 integral Attachment Surf RR-4 - - -

0.750 CC N-509 22-02-2-6A J-K-1 B10.1G Integral Attachment burf PR-4 - - -

0.750 CC N-509 02-2-3A-NN-1B N/A N/A Whip Restraint N/A - - - - No Exam Required 02-2-3A-AN-1 F-A F1.10b Constraint VT-3 RR-2 - - -

0.750" CC N-491-1, neej dramng 22-02-2-5 B-J 89.31 12.0" Branch Connection VoVSurf - - - .553* IGSCC A*

22-02-2-6-LS1 B-J B9.12 Pipe Long Seain Vol/ Surf RR-5 - - -

.993* IGSCC A-1, CC N-524 22-02-2-6 B-J B9.11 Pipe-Cap Vot/ Surf - - -

.993" IGSCC C-2, every 10 years 22-02-2-6-LS1 B-J B9.12 Pipe Long Seam Vol/ Surf RR-5 - - -

.993- IGSCC A-1, CC N-524 i

Fit.E. RCPLAN 02 Page C2 - 9 Of 02 - 29

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] g h Third inservice inspection Interval Ten - Year Inspection Plan Date: Janc.ary 7,1998 Rev!sion 0 COMPONENT ASME ASME ASME WELD IDENTIFICATl0N CODE CODE CODE REL ISi!NTERVAL LTH OR CAT ITEM DESCR!PTION EXAM REQ PERT PER2 PER3 THICK REMARKS 02 Reactor Recirculation System Drawing Number: MSK-3001 Line No. 28"-WH-GE-1 A from nozzle N1B N-1B-SE B-F B5.10 Nozzle-Safe End Vo'JSurf X - -

123" IGSCC D, every 2 refueling outage 28-02-2-48 B-J 89.11 Safe End-Pipe Vol/ Surf X - -

123" IGSCC E, every 2 refueling ou' age. Temwnal End 28-02-2-48-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf RR-5 X - -

1.23* IGSCC A-1 CC N-524 28-02-2-49 B-J 89.11 Pipe-Elbow Vol/ Surf X -

123" IGSCC C-2, once every 10 years 28-02-2-49-LS1 B-J 89.12 Pipe Long Seam VouSurf RR-5 -

X -

123" IGSCC A-1. CC N-524 28-02-2-49-LS2 B-J 89.12 Elbow Long Seam VoVSurf RR-5 - X -

123" IGSCC A-1, CC N-524 28-02-2-49-LS3 B-J B9.12 Elbow Long Sesm Vol/ Surf RR-5 -

X -

1.23" IGSCC A-1, CC N-524 02-2-1A-NN-27 N/A N/A Whip Restraint N/A - - - -

No Exam Required 28-02-2-50 B-J 89.1" Elbow-Pipe VoVSurf - -

X 123" IGSCC C', orre every 10 years 28-02-2-50-LS1 B-J B9.12 Elbow Long Seam Vot/ Surf RR-5 - - X 123" IGSCC A-1, CC N-524 28-02-2-50-LS2 B-J 89.12 Elbow Long Seam Vol/ Surf RR-5 - -

X 1.23* IGSCC A-1.CC N-524 28-02-2-50-LS3 B-J 89.12 Pipe Long Seam VoVSusf RR-5 - - X 123" 1GSCC A-1. CC N-524 28-02-2-51 B-J B9.11 Pipe-Pipe VoVSurf - - -

1.23" IGSCC C-2, once every 10 years 28-02-2-51-LS1 B-J 89.12 Pipe Long Seam VoVSurf RR-5 - - -

123" IGSCC A-1. CC N-524 28-02-2-51-LS2 B-J 89.12 Pipe Long Seam VoltSurf RR-5 - - -

123" IGSCC A-1. CC N-524 02-2-1A-NN-24 N/A N/A Whip Restraint N/A - - - - No Exam Required 02-2-1 A-HS-12 N/A N/A Hydrautic Snubber VT-3 RR-11 - - - -

TS Sedion 3.6.1 FILE RCPLAN 02 Page 02 - 10 Of G2 - 29

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] 4 bV8'*h 'ihird Inservice inspection Interval Date: January 7,1998 Ten - Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL t58 INTERVAL LTH OR CAT ITEM DESCRfPTION EXAM REQ PER1 PER2 PER3 THTCM REMARKS P

02 Reactor Recirculation System Drawing Number: MSK-3001 Line No. 28*-WH-GE-1 A from nozzta N1B 28-02-2-50A B-J 89 11 Pipe-Pipe VoVSurf - - -

123' IGSCC C-2. once every 10 years 28-02-2-50A-LS1 B-J 09.12 Pipe Long Seam VoVSurf RR-5 - - -

123* IGSCC A-1. CC N-524 28-02-2-50A-LS2 B-J 89.12 Pipe Long Seam VoVSurf RR-5 - - -

123* tGSCC A-1. CC N-524 02-2-1 A-HS-t, N/A N/A Hydraulic Snubber VT-3 RR-11 - - - -

TS Secbon 3.G 1 02-2-1 A-AN-14 F-A F1.106 Constraint VT-3 RR-2 - - -

1.5" CC N-491-1. need dravnng 28-02-2-51A B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

1.5" CC N-509 02-2-1A-NN-25 N/A N/A Whip Restraint N/A - - - - No Exam Required 28-02-2-51B B-J 89.32 1.0" Branch Connection N/A - - - -

Exempt IWB '220(a) 28-02-2-51C N/A N/A Insulation Lugs N/A - - - - No Exam Required 28-02-2-52 B-J 89.11 Pipe-Eibow VoVSurf - - -

123- IGSCC E every 2 refuehng outages 28-02-2-52-LS1 B-J B9.12 Pipe Long Seam VoVSorf RR-! - - -

123' IGSCC A-1. CC N-524 28-02-2-52-LS2 B-J 89.12 Elbow Long Seam Vol/ Surf RR-5 - - -

1.23* IGSCC A-1. CC N-524 28-02-2-52-LS3 B-J B9.12 E! bow Long Seam Vol/ Surf RR-5 - - -

1.23" IGSCC A-1.CC N-524 28-02-2-53 B-J 89.11 Eibow-V3fve MOV-43A Vol/ Surf - - -

1.23' IGSCC E. every 2 ref.,efing outages 28-02-2-53-LS1 B-J B9.12 Elbow Long Seam VoVSurf RR-5 - - -

1 23" IGSCC A-1. CC N-524 28-02-2-53-LS2 B-J 89.12 Elbow Long Seam VouSurf RR-5 - - -

123' IGSCC A-1. CC N-524 FILE- RCPLAN 02 Page 02 - 11 Of 02-29

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] g h Third Inservice inspection Interval Ten -Year inspection Plan Date: January 7,1998 Rev;sion 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT UEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICK REMARKS 02 Reactor Recirculation System Drawing Number: MSK-3001 Line No. 28"-WH-GE-1 A from nozzle N1B MOV-43A B-M-2 B12.50 28* Gate Valve VT-3 - - - - When disassembled, one vafve M a group of vatees MOV-43A B-G-2 B7.70 Valve Botting VT-1 - - - -

Limited to vaFee selected under B-M-2 28-02-2-54 B-J 89.11 Vafve MOV-43A -Pipe VouSurf - - -

123* IGSCC C-2, once everf 10 years 28-02-2-54-LS1 B-J 89.12 Pipe Long Seam VoUSurf RR-5 - - -

123' IGSCC A-1, CC N-524 28-02-2-55 B-J 89.31 6.0" Branch Confiaction VoUSurf - - -

123* IGSCC C-2, once e.ery 10 years 6-02-2-1 B-J 89.11 Pipe-Flange VouSurf - - - -

Flange B-G-2 B7.50 Flange Botting VT-1 X - -

<2* Limrted to wwet selected under B-J 28-02-2-55A B-J B9.32 2.0" Branch Connection Surf - - - -

Exemot IWB-1220(a) 28-02-2-558 B-J B9.32 1.25" Branch Connection Surf - - - -

Exempt TWB-1220(a) 28-02-2-55C R-J 89.32 1.0" Branch Connection Surf - - - - Exempt IW3-1220(a) 28-02-2-56 B-J 89.11 Pipe-Elbow VoVSurf - - -

123' IGSCC C-2, once every 10 years 02-2-1A-AN-22 F-A F1.10b Constraint VT-3 RR-2 - - - -

CC-491-1, need drawing 28-02-2-56-L S1 B-J 89.12 Elbow Long Seam VoVSurf RR-5 - - -

1.23* IGSCC A-1 CC N-524 28-02-2-56-LS2 B-J B9.12 Dbow Long Seam VoVSurf RR-5 - - -

1.23' IGSCC A-1 CC N-524 28-02-2-56-LS3 B-J 89.12 Elbow Long Seam VoVSurf RR-5 - - -

1.23' IGSCC A-1 CC N-524 28-02-2-57 B-J 89.11 Elbow-Pipe Pump 02-2P-1 A Vol/ Surf - - -

123' IGSCC C-2, once e y 10 years Fit.E- RCPLAri 02 Page 02 - 12 Of 02-29

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O James A. Fitzpatrick Nuclear Power Plant JAF4SI-0003 O

! O bMM %ird Inservice inspection Interval Date: January 7,1998 Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDF'ITIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRfPTrON EXAM REQ PER1 PER2 PER3 TH:CM REMARKS O .

02 Reactor Recirculation System Drawing Number: MSK-3001 Line No. 28" WH-GE-1 A from nozzle N1B 28-02-2-57-LS1 B-J B9.12 Elbow Long Seam VoVSurf RR-5 - - -

123" IGSCC A-1. CC N-524 28-02-2-57-LS2 B-J B9.12 Elbow Long Seam VoVSurf RR-5 - - -

123- IGSOC A-1. CC N-524 28-02-2-40 B-J 89.11 Pipe-Safe End VoVSuri - -

X 123" IGSCC E. every 2 re- 7 ou' ages Te mrr.at End i

FILE RCPLAN 02 Page 02 - 13 Of 02 - 29

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C d James A Fitzpatrick Nuclear Power Plant KF-tSI-0003 V

g Piswer Third inservice Inspection Interval Ten WsrInspection Plan Date: January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCR1PT10N EXAM REQ PER1 PER2 PER3 THICK REMARKS 02 Reactor Recirculation System Drawing Number: MSK-3002 Line No.12"-WH-GE-8B from nozzle N2K N-2K-SE 8-F B5.10 Nozzle-Safe End Vol/ Surf X - -

.54 7 IGSCC D.every 2 refueling outages 12-02-2-75 B-J 89.11 Safs End-Pipe Vol/ Surf X - -

.54T IGSCC C-2. once every 10 years terminal End 12-02-2-75-LS1 B-J 89.12 Pipe long Seam Vol/ Surf RR-5 X - -

.54T IGSCC A-1. CC N-524 12-02-2-76 B-J B9.11 P'pe-Elbow Vol/ Surf - - -

.54P IGSr.r f., every 2 refueling outages 12-02-2-76-LS1 B-J B9.12 Elbow Long seam Vol/ Surf RR-5 - - -

.54T IGSC'. A-1. CC N-524 12-02-2-76-LS2 B-J B9.12 Pipe Long Seara Vol/Scrf RR-5 - - - .54T IGSCC A-1.CC N-524 12-02-2-77 B-J B9.11 Elbow-Pipe Vol/ Surf - - -

.54T IGSCC C-2 once every 10 years 12-02-2-77-LS1 t3-J B9.12 Elbow Long Seam Vol/Suri RR-5 - - -

.54T IGSCC A-1. CC N-524 12-02-2-77-LS2 ES .I 89.12 Pipe Long seam Vol/ Surf RR-5 - - -

.54T IGSCC A-1. CC N-524 02-2-88-NN-2C N/A N/A Whip Restraint N/A - - - - No Exam required 12-02-2-77A B-J 89.32 1.0" Branch Connection N/A - - -

.54T Exempt IWB-1220(a) 12-02-2-78 B-J 89.31 12.0" Branch Connection Vol/ Surf - - -

.54T IGSCC C-2. once every 10 years 12-02-2 78-LS1 B-J . B9.12 Pipe Long seam Vol/ Surf RR-t - - -

.54 7 IGSC'CA-1. CC N-524 r!LE. RCPLAN.02 Page 02 - 14 Of 02-29

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Jame /G;upatric:I Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third inservice Inspection Interval Date: January 7,1998

$ 88** Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PERT PER2 PER3 TMCM REMARKS 02 Reactor Recirculation System Drawing Number: MSK-3002 Line No.12"-WH-GE-78 from nozzle Pf2J N-2J-SE B-F B5.10 Nozzle-Safe End Vol/ Surf - -

X .54T IGSCC D every 2 refuel:ng outages 12-02-249 B-J B9.11 Safe End-Pipe Vol/ Surf - -

X .54T IGSCC E. every 2 refueling outages. Terminal End ,

12-02-2-69-LS1 B-J B9.12 Pipe Long Seam Vot/ Surf RR-5 - -

X .54T los. ; A-1. CC N-524 12-02-2-70 R-J 89.11 Pipe-Elbow VoVSurf - - - .54 7 IGSCC E. every 2 refueing r outages 12-02-2-70-LS1 B-J 89.12 Elbow Long Seam Vol/ Surf RR-5 - - -

.54T IGSCC A-1. CC N-524 12-02-2-70-LS2 B-J B9.12 Pipe Long Seam Vol/ Surf RR-5 - - -

_54T IGSCC A-1. CC N-524 12-02-2-71 B-J B9.11 E! bow-Pipe Vol/ Surf - - -

.54T IGSCC C-2. once every 10 years 12-02-2-71-LS1 B-J B9.12 Pipe Long Seam Vol/ Surf RR-5 - - - .54T IGSCC A-1. CC N-524 12-02-2-71-LS2 B-J 89.12 Elbow Long Seam Vol/ Surf RR-5 - - -

.54T IGSCC A-1. CC N-524 12-02-2-71A B-J 89.32 1.0" Branch connection N/A - - - -

Exempt IWB-1220(a) 02-2-73-NN-2A N/A N/A Whip restraint N/A - - - -

No Exam requwed 12-02-2-72 B-J 89.31 12.0" Branch Connection VodSerf - - -

.54T IGSCC C-2. oner. every 10 years 12-02-2-72-LS1 B-J 89.12 Pipe Long seam Vol/ Surf RR-5 - - -

.54 7 IGSCh A-1. CC N-524 FILE: RCPLAN 02 Page 02 - 15 Of 02-29

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] m

g Ptmer Third Inservice inspection Interval Ten -Yearinspection Plan Date: January 7,1398 Revision 0 COMPONENT ASME ASME ASME WELD

!DENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH GR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICK REMARKS m

t 02 Reactor Recirculation System Drawing Number: MSK-3002 Line No.12"-WH-GE-6B f~m nozzle N2H N-2H-SE B-F B5.10 Nozzle-Safe End Vol/ Surf X - -

.54T IGSCC D. every 2 refueling outages 12 02-2-81 B4 99.11 Safe End-Pipe Vol/ Surf X - - .54T IGSCC C-2. once every 10 years. Terminal End 12-02-2-81-LS1 B4 89.12 Pipe Long Seam Vol/ Surf RR-5 X - -

.54T IGSCC A-1.CC N-524 12-02-2-82 B4 B9.11 Pipe-Elbow VolSurf - - -

.54T IGSCC C-2, once every 10 years 12-02-2-82-1 S1 B4 09.12 Elbow Long Seam Vol/ Surf RR-5 - - -

.54 7 IGSCC A-1. CC N-524 11-02-2 82-LS2 B4 B9.12 l'ipe Long Seam VoliSurf RR-5 - - -

.54T IGSCC A-1. CC N-524 12-02-2-83 B4 89.11 Esbow-Pipe Vol/ Surf - - -

.54T IGSCC C-2. once every 10 years 02-2-68-NN-1E N/A N/A VAlip Restraint N/A - - - -

No Exam Required 12-02-2-83A B4 B9.32 1.0" Branch Connection N/A - - -

.54T Exempt IWB-1220(a) 12-02-2-83-LS1 B4 89.12 Pipe Long Seam VoJSurf RR-5 - - -

.54T IGSCC A-1. CC N-524 12-02-2-83-LS2 B4 B9.12 Elbow Long Seam Vol/ Surf RR-5 - -

.54T IGSCC A-1. CC N-524 12-02-2-84 B4 B9.11 Pipe-Redt:cer Vol/ Surf - - -

.54T IGSCC C-2. Once every 10 years t

FILE RCPLAN 02 Page 02 - 16 Of 02-29

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James A. Fitzpatrick Nuclear Pov er Plant

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[[::JAF-ISI-0003|JAF-ISI-0003]] M bMM Third inservice inspection Interval Date: January 7,1998

Ten -YearInspection Plan Revision 0 COMPONENT ASME ASME ASME VVELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DE~fCR!PTION EXAM REQ PER1 PER2 PER3 THICK RF02 ARKS 02 2 - Reactor Recirculation System Drawing Number: MSK-2002 Line No. 28"-WM-GE-28 28-02-2-85 B-J B911 Reducer <ross VouSurf - -

X 1.36" IGSCC C-2. coce every 10 years 2842-2-88 B-J 89.11 Cross-Tee Vol/ Surf - - -

1.36" IGSCC C-2. once every 10 years 28-02-2-89 B-J B9.11 Tee-Prpe Vot/ Surf - - -

1.36" IGSCC C-2. once every 10 years 28-02-2-89-LS1 B-J B9.12 Poe Long Sesm VoVSurf RR-5 - - -

1.36" IGSCC A-1. CC N-524 28-02-2-89A B-K-1 810.10 l' tegral Attachment Surf RR-4 - - -

0.750 CC N-509 02-2-28-HS-3 N/A N/A Hydraurc Snubber VT-3 RR-11 - - -

0.750" TS Secten 3.6.1 28-02-2-899 B-K-1 B10.10 Integrat Attachment Surf RR-4 - - - -

CC N-509 02-2-2B-HS-4 N/A N/A Hydraute Snubber VT-3 Ril-11 - - - -

TS Secton 3.6.1 28-02-2-89E B-J 89.32 1.0" Branch Connechon Surf - - - -

Esempt IV B-1220(a) 28-02 2-f,9F B-J 89.32 1.0" Branch Cor nection Surf - - - -

Exempt IV.B-1220(a) 28-02-249E D-K-1 810.10 Integral Attachment Surf RR-4 - - - -

CC N-509 t

02-2-2B-AN-5 F-A F1.10b Constraint VT-2 RR-2 - - -

1.5" CC N-491-1, need drawing 28-02-2-89D - - - - - - - -

Support removed 02-2-28-NN-5A N/A N/A Whip Restraint N/A - - - -

No Exam Required 28-02-2-90 B-J 89.31 4.0" Branch Connection VoUSurf - - -

.337" IGSCC A 4-02-2-93C B-J 89.31 (.C" Branch Connection Vol/ Surf - -

X 337" IGSCC A. Capped 28-02-2-90A N/A N/A Insulation Lugs - - - - -

No Exam Required FILE- RCPLAN 02 Page 02 - 17 Of C2 - 29

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J James A. Fitzpetrick Nuclear Power Plant JAF 2SI-0003 g Pseer Third Inservice inspection Interval Ten - Year Inspecticn Plan Date: January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 TH1CK REMARKS t

02 Reactor Recirculation System Drawing Number: MSK-3002 Line No. 28 -WH-GE-2B 23-02-2-91 B-J 89.11 Pipe-Elbow Vol/ Surf - - -

1.36* IGSCC C-2. once every 10 years 02-2-28-HS-8 N/A N/A Hydrautic Snubber VT-3 RR-11 - - - -

TS Section 3.6.1 28-02-2-92 B-J 89.11 Pipe-Safe-End Vol/ Surf - - -

1.3G IGSCC E.every 2 refueling outages 90-02-2-92-LS1 B-J 89.12 Elbow Long Seam Vot/ Surf RR-5 - - -

1.36" IGSCC A-1.CC N-524 28-02-2-92-LS2 B-J 89.12 Elbow Long Seam Vol/ Surf RR-5 - - -

1.36" IGSCC A-1. CC N-524 -

MOV-538 B-M-2 B12.50 28* Gate Valve VT-3 - - - -

When disassembled, one valve in a group of valves MOV-530 B-G-2 87.70 Vafve Botting VT-1 - - - -

Limited to valve selected urder B-M-2 28-02-2-104 B-J 89.11 Valve MOV-53A-Pipe Vol/ Surf - - -

1.30" 'GSCC C-2,every 2 refueling outages 28-02-2-104-LS1 P-J 89.12 Pipe Long Seam Vol/ Surf RR-5 - - -

1.36" IGSCC A-1. CC N-524 28-02-2-103 B-J 89.31 4.0~ Branch Connection Vol/ Surf - - - -

IGSCC A 28-02-2-104A B-J 89.32 1.0" Branch Connection Surf - - - -

Exempt IWB-1220(a) 4-02-2-102C B-J 89.31 4.0" Branch Connection Vel / Surf - -

.337" IGSCC A Capped 28-02-2-105 B-J 89.11 Pipe-Pump 02-2-P-1 A Vot/ Surf - -

X 1.36* IGSCC C-2. every 2 refueling outages. Termina! End 28-02-2-105-LS1 B4 89.12 Pipe Long Seam Vol/ Surf RR-5 - -

X 1.36' IGSCC A-1. CC N-524 FILE: RCPLAN 02 Page02-18 Of 02 - 29

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l gj James A. Fitzpatrick Nuclea- Power Plant [[::JAF-ISI-C903|JAF-ISI-C903]] (v/

g Pimer Third Inservice Inspection Interval Ten -Year Inspection Plan Date: January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE F<EL ISIINTERVAL LTH OR CAT ITEM DESCRfPTION EXAM REO PER1 PER2 PER3 TFsCK REMARKS 02 Reactor Recirculation System Drawing Number: MSK-3002 Line No.12"-WH-GE-SB from nozzle N2G N-2G-SE B-F B5.10 Nozzle-Safe End VouSurf - -

X .547" IGSCC D, every 2 re;uehog outages 12-02-2-64 B-J B9.11 Safe End-Pipe VoUSurf - -

X .54T IGSCC E. every 2 refuehng outagas, Terminal End 12-02-2-64-LS1 B-J 89.12 Pipe Long Seam VoUSurf RR-5 - -

X .54T IGSCC A-1.CC N-524 12-02-2-65 B-J 89.11 Pipe-Elbow VouSurf - - -

.54T IGSCC E, every 2 refueling outages 12-02-2-65-LS1 B-J B9.12 Elbow Long Seam VouSurt RR-5 - - -

.547" IGSCC A-1. CC N-524 12-02-2-65-LS2 B-J 89.12 Pipe Long Seam VouSurf RR-5 - - -

.54T IGSCC A-1.CC N-524 12-02-2-06 B-J 89.11 Elbow-Pipe VouSurf - - -

.547" IGSCC C-2, every 10 years 12-02-2-66-LS1 B-J 89.12 Pipe Long Seam VouSurf RR-5 - - -

.54T IGSCC A-1. CC N-524 12-02-2-66-LS2 B-J 89.12 Elbow long Seam VoUSurf RR-5 - - -

.54T IGSCC A-1 CC N-524 02-2-58-NN-1C N/A N/A VWp Restraint N/A - - - -

No Exam Required 12-02-2-06A B-J 89.32 1.0" Branch Cont ection Surf - - - -

Exempt Ive-1220(a) 12-02-2-67 B-J 89.31 12.0" Branch Connecten VoVSurf - - -

.547" IGE': O 3, every 10 years 12-02-2-67-LS1 B-J 89.12 Pipe Long Seam Vo!/ Surf RR-5 - - -

.547" IGSC'C A-1 N N-524 Fit.E: RCPLAN 02 Page 02 - 19 Of 02 -29

V (O James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

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gb h Third Inservice inspection Interval Date: January 7,1998 Ten - Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRtPTION EXAM REO PER1 PER2 PER3 THICK REMAR8tS 02 Reactor Recirculation System Dratring Numinr: MSK-3002 Line No.12"-WH-GE-4B from nozzle N2F N-2F-SE B-F B5.10 Nozzle-Safe End VouSurf - -

X .54T IGSCC D, every 2 refueling outage 12-02-2-58 B-J B9.11 Safe End-Pipe VoVSurf - -

X .54T IGSCC C-3 ence every 10 years, Termmal End 12-02-2-58-LS1 B-J 89.12 Pipe Long Seam Vot/ Surf RF 5 - -

X .54T IGSCC A-1. CC N-524 12-02-2-59 B-J B9.11 Pipe-Elbow Vot/ Surf - - -

.54T IGSCC C-2, once every 10 years 12-02-2-59-LS1 BJ B9.12 Elbow Long Seam Vol/ Surf RR-5 - - -

.54T IGSCC A-1 CC N-524 12-02-2-59-LS2 B-J 89.12 Pipe Long Seam VoVSurf RR-5 - - -

.54T IGSCC A-1 CC N-524 12-02-2-60 B-J 09.11 Elbow Dipe Vol/ Surf - - -

.54T IGSCC 12-02-2-60A B-J B9.32 1.0 Branch Connection N/A - - - - Exempt IWB-1220(a) 12-02-2-60-LS1 B-J 89.12 Pipe Long Seam VoVSurf RR-5 - - -

.54T IGSCC A-1, CC N-524 12-02-2-60-LS2 B-J 89.12 Elbow Long Seam VouSurf RR-5 - - -

.54T IGSCC A-1. CC N-524 02-248-NN-1A N/A N/A Whip Restraint N/A - - - - No Exam Required 12-02-2-61 B-J 89 31 12.0 Branch Connection Vol/ Surf - - -

.54T IGSCC C-3. once every 10 years

2-02-2-61-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf RR-5 - - -

.54T IGSC'C A-1. CC N-524 FILE: RCPLAN 02 Page 02 - 20 Of 02 - 29

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James A'Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] t

\j) 4 MW8kh Third Inservice Inspection Interval Date: January 7,1998 Ten - Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION ' CODE CODE CODE REL IS!!NTERVAL LTH OR CAT ITEM DESCRIPTION EXA1 REQ PER1 PE t2 PER3 T}cCM REMARKS 02 Reactor Recirculation System Drawing Number: MSK-3002 ,

Une No. 22 -WH-GE-3B 22-02-2-63 B-J 89.11 Pipe-Cap VoUSurf - - -

993* IGSCC E. every 2 refuelt.g outages 22-02-2-63-LS1 BJ B9.12 Pipe Long Seam VoVSurf RR-5 - - -

.993* IGSCC A-1. CC N-524 22-02-2-62 B-J 89.31 12.0" Branch Cw -Gi VouSurf - - - -

IGSCC A*

22-02-2-62-LS1 B-J 89.12 Pipe Long Seam VouSurf RR-5 - - -

.903* IGSCC A-1. CC N-524 22-02-2 868 B-K-1 810.10 Integral Attachment Surf HR-4 - - -

150* CC N-509 02-2-38-AN-1 F-A F 1.t Constraint VT-3 RR-2 X - -

.750* CC N-491-1. need dramng 02-2-38-NN-1B N/A N/A VMp Restraint N/A - - - -

No Dam Pequired 22-02-2-86A B-K-1 B10.10 Integral A.W Surf RR-4 - - -

.750 CC N-509 22-02-2-68 B-J 89.31 12 0* Branch Conneo.on VoUSurf - - - - IG~~;C A*

22-02-2-68-LS1 tk J B9.12 Pipe Long Seam Vot/ Surf RR-5 - - -

.993* IGSCC A-1.CC N-524 22-02-2-68-LS2 B-J 89.12 Pipe Long Seam VoVSurf RR-5 -

X -

.993* IGSCC A-1. CC N-524 22-02-2-86 B-J 89.11 Cross-Pipe VoUSurf -

X -

.933* IGSCC C-2. once every 10 years 22-02-2-86-LS1 B-J 89.12 Prpe Long Seam Vot/ Surf RR-5 -

X -

933* IGSC'C A-1. CC N-524 22-02-2-87 B-J 89.11 Cross-Pipe VoVSurf - - -

.933' IGSCC C-2. once every 10 years 22-02-2-87-LS1 B-J 89.12 Pipe Long Seam Vot/ Surf RR-5 - - -

.933' IGSCC A-1. CC N.524 02-2-38-NN-20 N/A N/A VWp Restraint N/A - - - -

No Exam Required 22-02-2-73 B-J 89.31 12.0" Branch Corw:3cton VoVStaf -

X - -

IGSCC A*

\

FILE RCPLAN 02 Page 02 - 21 Of 02-29

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James A. Fitzpatrick Huclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] t

v) g h Third inservice inspection Interval Ten - Year inspection Pla, Date: January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS t

02 Reactor Recirculation System Drawing Number: MSK-3002 Line No 22"-WH-GE-3B 22-02-2-73-LS1 B-J 89.12 Pipe Long Seam Vot/ Surf RR-5 - - -

.933* IGSCC A-1. CC N-524 22-02-2-73-LS2 B-J B9.12 Pipe Long Seam VoVSurf RR-5 - - -

.933' IGSCC A-1. CC N-524 22-02-2-87A B-K.1 B10.10 Integral Attachment Surf RR-4 - - -

0.750 CC N-509 22-02-2-878 B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

0.750 CC N-509 0<2-2-38-MN-28 N/A N/A Whip Restraint N/A - - - -

No Exam Required 02-2-38-AN-2 F-A F1.105 Constraint VT-3 RR-2 - - -

.750" CC N-491-1, need drawing 22-02-2-79 B-J 89.31 12.0" Branch Connection Vol/S arf - - -

.553- IGSCC A*

22-02-2-79-LS1 B-J B3.12 Pipe Long Seam VouSurf RR-5 - - -

.993" IGSCC A-1, CC N-524 22-02-2-80 B-J 89.11 Pipe-Cap VoVSurf - - -

.993- IGSCC C-2. once every 10 years 22-02-2-80-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf RR-5 - - -

.993" IGSCC A-1.CC N-524 1

FILE: RCPLAN.02 Page02 "'2 Of 02 -29

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James Fitzpatrick Nuclear Power Plant [[::JAF-1St-0003|JAF-1St-0003]] 4 hMh Third Inservice inspection laterval Date: January 7,1998 Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATEN CODE CODE' CODE REL ISIINTERVAL LTH OR CAT ITEM DESCR1PTION EXAM REO PER1 PER2 PER3 THfCK , REMARKS ,. .. -

02 Reactor Recirculation System Drawing Number- MSK-3002 tlne No. 28"-WH-GE-1B from nozzle N1 A N-1 A-SE B-F B5.10 Nozzle-Safe Ergi Vol/ Surf -

X -

123* IGSCC D, every 2 refueling outage 28-02-2-1M B-J 8911 Safe End-Pipe Vol/ Surf -

X -

1.23" IGSCC C-2, once every 10 years. Terminal End 28-02-2-106-LS1 B-J 89.12 Pipe Long Searq Vo'/ Surf RR-S -

X -

123* IGSCC A-1.CC N-524 28-02-2-107 B-J 89.11 Pipe-E! bow Vot/ Surf X - -

123' IGSCC C-2, once every 10 years 28-02-2-107-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf RR-5 X - -

123' IGSCC A-1, CC N-524 28-02-2-107-LS2 B-J B9.12 Elbow Long Seam Vol/Suri RR-5 X - -

123" IGSCC A-1.CC N-524 2842-2-108 B-J B9.11 Elbow -Pipe Vol/ Surf - - -

123" IGSCC C* Under Whip, once every 10 years 28-02-2-108-LS ? B-J B9.12 Elbow Long Seam Vo!/ Surf RR-5 - - -

1.23" IGSCC A-1 CC N-524 28-02-2-108-LG2 B-J B9.12 Elbow Long Seam Vol/ Surf RR-5 - - -

1.23" IGSCC A-1. CC N-524 28-02-2-108-LS1 B-J 89.12 Pipe Long Seam Vot/ Surf RR-5 - - -

1.23" IGSCC A-1. CC N-524 02-2-1B-NN-24 N/A N/A Yvhip Restraint N/A - - - -

No Exam Required 28-02-2-109 B-J 89.11 Pipe-Tee Vol/ Surf - -

X 1.23" IGSCC C-2. once every to years 28-02-2-109-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf RR-5 - -

X 123* IGSCC A-1. CC N-524 28-02-2-110 B-J 89.11 Tee-Pipe Vol/ Surf - - -

123' IGSCC C-2, once every 10 years 28-02-2-110-LS1 B-J B9.12 Pipe Long Seam Vol/ Surf RR-5 - - -

1.23" IGSCC A-1. CC N-524 28-02-2-110G B-K-1 010.10 Integral Attachment Surf RR-4 - - -

.750" CC N-509 02-2-1 B-HS-12 N/A N/A Hydraulic Snubber VT-3 RR-11 - - - -

TS Section 3.G.?

FILE RCPLAN.02 Page 02 -23 Of 02-29

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Om Third Inservice Inspection Interval Date: January 7,1998 g b Ten -Year Inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME LTH OR CODE CODE REL ISIINTERVAL IDENTIFICATION CODE REQ PER1 PER2 PER3 TH1CK REMARKS l

' CAT ITEM DESCRTFTION EXAM 02-2 -. setor Recirculation System f

I Drawing Number: MSK-3002 Line No. 28"-WH-GE-1B from nozzle N1 A l

B10.10 Integral A11odowat Surf RR-4 - - - .750" CC N-509 28-02-2-110F B-K-1 Hydraulic Snubber VT-3 RR-11 - - - -

TS Sectet 3.6.1 02-2-18-HS-13 t#A N/A Surf RR-4 - - -

1.5* CC N-609 28-02-2-110E B-K-1 B10.10 Integra' Attachment VT-3 RR-2 - - - - CC N 491-1 need drawing 02-2-18-AN-14 F-A F1.10b Constraint N/A - - - No Exam Required 02-2-18-NN-25 N/A N/A Whip Res'raint -

1 N/A - - - Exempt IWB-1220(a) 89.32 1.0" Branch Cuiw stive 28-02-2-1100 B-J N/A - - - - Exempt sWB-1220(a) 28-02-2-110C 9-J 69.32 1.0" Branch Connection 89.11 Pipe-Pipe Vol/ Surf - - - -

IGSCC 28-02-2-110H B-J N/A - - - - Exempt IWB-1220(a) 28-02-2-1108 B-J 89.32 1.0" Branch Connectron Vol/ Surf 123" IGSCC C-2 ence every 10 years 28-02-2-110A B-J 89.11 Pipe-Pipe - - -

B-J BP Fipe Long Seam VM/ Surf RR-5 - - - 123' IGSCC A 1. CC N-524 28-02-2-110A-LS1

2 Pipe Long Seam Vol/ Surf RR-5 - - - 1.23* IGSCC A-1. CC N-524 28-02-2-110A-LS2 B-J P Insulation Lugs N/A - - - No Eram Required 28-02-2-111 A N/A .4A -

Vol/ Surf 123* IGSCC C-2. once every 10 years 28-02-2-1)1 B-J 89.11 Pipe-Elbow - - -

Vot/ Surf - - - 1.23" IGSCC C-2 ence every 10 years 28-02-2-112 B-J 89.11 Elbow-Valve MOV-439 89.12 Elbow Long Seam Vol/So. RR-5 - - -

123' IGSCC A-1.CC N-524 28-02-2-112-LS1 B-J B9.12 EToow Long Seam Vol/ Surf RR-5 - - - 123' IGSCC A-1. CC N-524 28-02-2-112-LS2 B-J FILE: RCPLAN 02 Page C2 - 24 Of 02 - 29

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o Pimer James eitzpatrick Nuclear Power Plant Third Inservice inspection Interval [[::JAF-ISI-ObO3|JAF-ISI-ObO3]] Date: January 7,1998 Revision 0 Ten -Year inspection Plan ASME WELD COMPONENT ASME ASME ISIINTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE REQ PER1 PER2 PER3 THICK REMARKS CAT ITEM DESCRIPTION EXAM t

02 Reactor Recirculation System Drawing Number: MSK-3002 Line No. 28 -WH-GE-1B from nozzle N1 A Yvhen Drsassembled. one valve in a group of valves B-M-2 B12.50 28' Gate Valve VT-3 - - - -

MOV-438 87.70 Valve Botting VT-1 - - - <2" Limited to valve selected under B-M-2 MOV-438 ~ B-G-2 Vol/ Surf - 123- IGSCC E every 2 refuelir g outages 28-02-2-113 B-J 89.11 Valve MOV-438 -Pipe - -

89.12 Pipe Long Seam VouSurf RR-5 - - - 123" IGSCC A-1. CC N-524 28-02-2-113-LS1 B-J VouSurf 123" IGSCC C-2.once every 10 years 89.31 4.0" Branch Cumac,%06 28-02-2-114 B-J B-J 89.11 Pipe-Flange VouSurf - - - -

l 6-02-2-2 VT-1 X - <2" Limited to component selected under B-J Flange B-G-2 87.50 Flange Bo!!ing -

Surf - - - - Exempt IWB-1220(3) 28-02-2-114A B-J B9.32 1.0" Branch Connection Surt - - - - Exempt IWB-1220(a)

! 28-02-2-1148 B-J 89.32 1.25' Branch Connection Surf - - - - Exempt iWB-1220(a) 28-02-2-114C B-J 89.32 1.0" Branch Connection VoUSurf 123* IGSCC C-2. once every 10 years 2G-02-2-115 B-J 89.11 Pipe-Elbow - - -

B9.12 Pipe Long Seam VoVSurf RR-5 - - - 1.23" IGSCC A-1. CC N-524 28-02-2-115-LS1 B-J r 89.12 Elbow Long Seam VouSurf RR-5 - -

X 123" IGSCC A-1. CC N-524 28-02-2-115-LS2 B-J B9.12 Elbow Long Seam Vo*1 Surf RR-5 - -

X 1.23- IGSCC A-1. CC N-524 28-02-2-115-LS3 B-J Vot/ Surf X 123" IGSCC E every 2 refueling outages. Terminal End 28-02-2-116 B-J 89.11 Elbow-Pipe Pump 02-2P-1B - -

B9.12 ElbowLong Seam VoUSurf RR-5 - -

X 123* IGSCC A-1. CC N-524 28-02-2-116-LS1 B-J 8912 Elbow Long Seam VouSurf RR-5 - - - 123" IGSCC A-1. CC N-524 28-02-2-116-LS2 B-J FILE: RCPLAN 02 Page 02 - 25 Or 07 -29

James A Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] )

Date: January 7,1998 W Third Ir: service Inspection interval

$ Ten -Year inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME LTH OR CODE CODE REL ISt INTERVAL IDENTIFICATION CODE REO PER1 PER2 PER3 THICK FEMARKS CAT ITEM DESCRIPTION EXAM C2 Reactor Recirculation System Drawing Number: MSK-3001 Line No. 02-2-P-1A Recirculation Pump Exam requeed only when disassembled for l B-L-2 B12.20 Pump intemal VT-3 - - - - -

I 02-2-P-1 A maintenance, repair, Onfy one pump in a group of pumps Vol - - - Exam Emited to pump selected under B-t-2 02-2-P-1 A B-G-1 B6.180 Pump Bolting - -

VT-1 - - - - Bushings and Threads to be examined when 02-2-P-1A B-G-1 B6.190 Flanga Surface -

disassembled. Exam limited to pump selected under B-t-2 VT-1 - - Limited to pump selected under B-L-2 02-2-P-1 A B-G-1 B6.200 Nuts, and washers - - -

VT-1 - - Limited to pump selected under B-L-2 B7.60 Cap Screws - - -

02-2 P-1A B-G-2 B10.20 Integral Attachment Surf RR-4 - - - 1.5" CC N-509 28-02-2-153 B-K-1 Hydraulic Snubber VT-3 RR-11 - - - 1.5" TS Section 3.6.1 02-2-1 A-HS-18 N/A N/A VT-3 RR-2 X - CC N-491-1, need drawing 02-2-1A-AN-22 F-A F1.40 Support - -

B10.20 lntegral Attachme#. Surf RR-4 - - X 1.5" CC N-509 28-02-2-155 B-K-1 Hydraulic Snubber VT-3 RR-11 - - - 1.5" TS Section 3.6.1 02-2-1 A-HS-20 N/A N/A r

(

VT-3 .:R-2 X - CC N-491 1. need drawing F1.40 Support - -

02-2-1 A-AN-21 F-A N/A No E".am Required 02-2-1A-NN-28 N/A N/A ' Whip Restraint - - - -

810.20 Integral Attachment Surf RR-4 - - - 1.5" CC N-509 28-02-2-155A B-K-1 Hydraulic Snubber VT-3 RR-11 - - - 1.5* TS Section 3.6.1 02-2-1 A-HS-17 N/A N/A 810.20 Integral Attachment Surf RR-4 - - -

1.5" CC N-509 23-02-2-156 B-K-1 FILE RCPLAN 02 Page 02 - 26 Of 02 - 29 i

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O O James A. Fitzpatrick Nuclear Power Plant JAF4SI-0003 O

Third inservice inspection interval Date: January 7,1998 g b Ten -Yearinspection Plan Revision 0 ASME WELD CCMPONENT ASME ASME CODE REL IS11NTERVAL t.TH OR fDENTIFICATION CODE CODE REQ pct 1 PER2 PER3 THN",X REMARKS CAT ITEM DESCRrPTON EXAM 4

02 Reacter Recirculation System Drawing Number: MSK-3001 Une No. 02-2-P-1 A Recirculation Pump B1020 Integra! Attachment Surf RR-4 - - -

1.5* CC N-509 28-02-2-150 B-K-1 VT-3 RR-11 - - - 1.5" TS Seebon 3.6.1 02-2-1 A-HS-13 N/A N/A Hydraulic Snubber B1020 Integraf Attachment Surf RR-4 - - -

1.5* CC N-509 28-02-2-151 B-K-1 Hydraulic Snubber VT-3 RR-11 - - - 1.5" TS Sectron 3.G 1 M-2-1 A-HS-16 N/A N/A B1020 Integral Attachment Surf RR-4 - - -

1.5" CC N-505 28-02-2-156A B-K-1 B1020 Integral Attachment Surf RR-4 - - - 1.5* CC N-509 28-02-2-158 B-K-1 F1.40 Support VT-3 RR-2 - X - - CC N 491-1 02-2-1A-AN-23 F-A 810.20 Integral Attactment Surf RR-4 - - - 1.5* CC N-509 28-02-2-154 B-K-1 Hydraulk, Snubber VT-3 RR-11 - - - 1.5* TS Section 3 6.1 02-2-14HS-19 NeA N/A 7

i

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Page 02 - 27 Of G2-29 FILE: RCPLAN 02 i

O O O James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third Inservice Inspection Interval Date: January 7,1998 b

$ Ten -YearInspection Plan Revision 0 i

i ASME WELD l COMPONENT ASME ASME LTH OR CODE CODE REL ISIINTERVAL fDENTIFk.ATION CODE REQ PER1 PER2 PER3 THICM REMARKS f

i CAT ITEM DESCRfPN EXAM 02 Reactor Recirculation System Drawing Number: MSK-3002 Line No 02-2-P-1B VT-3 - - - Exam required only when disassembled for 02-2-P-1B B-L-2 812.20 Pump intemat -

maintenance, repair. Only one pump in a group of pumps Vol - - - Exam limited to pump selected under B-L-2 02-2 P-1B B-G-1 B6.180 Pu np Bolting -

l VT-1 - - - - Bushings and Threads to be examined when 02-2-P-1 B B-G-1 B6.190 Flange Surface disassembled. Exam limited to pump selected under

' B-L-2 l

VT-1 - - - Limrted to pump selected under B-t-2 02-2-P-1B B-G-1 B6200 Nuts, and washers -

f VT-1 - - Limited to pump selected under B-L-2 87.60 Cap Screws - -

02-2-P-18 B-G-2 Surf RR-4 - - -

1.5" CC N-509 28-02-2-144 B-K-1 B10.20 Integral Attachnent Hydrau!ic Snubber VT-3 RR-11 - - - 1.S* TS Secton 34.1 02-2-1B-HS-19 t#A N/A VT-3 RR-2 - - CC N-491-1 02-2-1B-AN-23 F-A F1.40 Support - -

B1020 Integral Attachment Surf RR-4 - - - 1.5" CC N-509 28-02-2-143 8-K-1 Surf RR-4 - -

1.5" CC N-509. Non load bearing 28-02-2-1468 B-K-1 B10.20 Integral Attachment -

t#A Hydraulic Snuboer VT-3 RR-11 - - - 1.S* TS Sbion 3.6.1 02-2-1 A-HS-17 N/A B10.20 Integral Attachment Surf RR-4 - - - 1.5" CC N-509 28-02-2-140 B-K-1 B10.20 Integral Attachment Surf RR-4 - - - 1.5" CC N-509 j 28-02-2-1470 B-K-1 VT-3 RR-11 - - -

1.5" TS Secten 3.6.1 02-2-1 B-HS-15 N/A t#A Hydraulic Snubber 1

FILE: RCPLAN.07 Page 02 - 28 Of 02 -29

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,new mp m O James A. Fitzpatrick Nuclear Power Pla .t Third inservice 1%pection Interyv [[::JAF-ISI-0003|JAF-ISI-0003]] Data: January 7,1998 h

$ Ten -Year inspection Plan Revision 0 ASME ASME VELD COMPJNENT ASME LTH OR CODE CODE CODE REL lAltNTERVAL IDENTIFICATION PER1 PER2 PER3 TH!CK REll4 ARKS CAT ITEIP DESCR!PTION EMM REQ I

02 Reactor Recirculation System l Dr wing Number: MSK-3001 Line No 02-2-P-1B Recirculation Pump B10.2C Integral Attachment Surf RR-4 - - - 1.5" CC N-509 28-02-2-146A b-K-1 Hydraulic Snubber VT-3 RR-11 - - - 1.5" TS Section 3.6.1 02-2-10-HS-16 N/A N/A B10.20 Integral Attac'iment Surf RR-4 - - - 1.5" CC N-509 28-02-2 145 B-K-1' B10.20 Integral Attachment Surf RR-4 - - -

1.5" CC N-509 28-02-2-147A B-K-1 N/A Hydraulic Snubber VT-3 RR-11 - - - -

TS Section 3.6.1 02-2-18-HS-20 N/A F1.40 Support VT-3 RR-2 - - - - CC N-491-1 02-2-18-AN-21 F-A 810.20 Integral Attachment Surf RR-4 - - - 1.5" CC N-509 28-02-2-148 B-K-1 N/A Hydrautic Snubber VT-3 RR-11 - - - 1.5" TS Sectioa 3.6.1 02-2-? B-HS-20 N/A F1.40 Suppc '; VT-3 RR-2 - - - 1.5" CC N-491-1 02-2-10-AN-22 F-A l

l TS Section 3.6.1 ti'A N/A Hydraulic Snubber VT-3 PR-11 - - -

1.5" 02-2-1C-HS 18 Whip Restraint N/A - - - No Exam required N/A C2-2-1B-NN 28 N/A

?

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FILE: RCPLAN.02 Page 02 - 2+ U 29 L --

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A_ __ q % %. o- 2: -

" James . itzpatrick Nuclerr Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third inservice inspection Interval Date: January 7,1998 g Peer Ten -Yearinspection Plan Revision: 0 t .

ASME ASME WELD COMPONENT ASME ISI INTERVAL LTH OR CODE- CODE CODE REL (DENTIFICATION REQ PER1 PER2 PER3 THICK PcMARKS CAT ITEM DESCRIPTION EXAfA w amummunammmes 02.3 - Nuclear Boiler Vessel Instrumentation Drawing Number- MSK-Later Line No. Jet Pump VoVSurf - -

X - IGSCC D. Every 2 refueling outages l N8A-SE B-F B5.10 Nozzle-Reducer Safe End 1

VoVSurf - -

X - IGSCC D. Every 2 re'ueling outages, Tern el End 4-022-118 B-J 89 11 Reducer Safe End-Reducer VoVSurf - - - - IGSCC D. Every 2 refueling outages N8A-SE-1 B-J 89.11 Reducer-Reducer !

Vof! Surf - - - - IGSCC D. Every 2 refueling outages N8A-SE-2 B-J 89.11 Reducer-Reducer Vol/ Surf - - - - IGSCC D. Every 2 refueling outages N8A-SE-3 BI B911 Reducer-Reducer VoVSurt X - - - IGSCC D. Every 2 refueling outages N88-SE B-F B5.10 Nozzle-Reducer Safe End VoVSurf X - - - IGSCC D. Every 2 rr'ueling outages. Terrrnnal End 4 022-117 B-J 89.11 Reducer Safe End-Reducer VoUSud - - - IGSCC D. Every 2 refueling outages 89.11 Reducer-Reducer N8B-SE-1 B-J Vof/ Surf - - - - IGSCC D. Every 2 refueling outages N83-SE-2 B-J B9.11 Reducer-Reducer VoVSurf - - - - IGSCC D. Every 2 refueling outages N88-SE-3 B-J B9.11 Reducer-Reducer t

1 Fil.E: NBV102.3.WPD Page 02.3 - 1 02.3-1

( + - x o 1 James A.Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third Inservice Inspection Interval Date: January 7,1998 M b y Ten -Year inspection Plan Revision 0

[

ASME w~dLD COMPONENT 'ASME ASME P.* '- JR CODE CODE REL ISIINTERVAL IDENTIFICATION CODE REQ PER1 PER2 PER's THICK REMARK 3

' CAT ITEM DEs CP.!PTION EXAM unsumuuuuuuuuuuum l

03 -Centrol Rod Drive System i 1

Drawing Number: MSK-3003 I Une No. From RPV Surf X IGSCC D, Dissimilar Metal Weld 89.21 Nozzle-Cap - - -

N-9-C1 8-J No;e: This line was cut ar1 capped, therefcre, Examination Category B-J was used in lieu of B-F.

l l

FILE CRD: AN.03%PD Page 03 - 1 of 03-1

V V v James A. Fitzpatrick Nuc; ear Power Plant JAF-ISIC003 g h Third Inservice inspection Interval Ten - Year inspection Plan Date: January 7,1998 Revisloa O COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL iS11NTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THfCK REMARKS i

10 - RESIDUA 1. HEAT REMOVAL SYSTEM Drawfng Number: MSK-3011 -

IJne No. 20*-W20-1504-42 from 28*-WH-GE-1B 20-id-1W B-F B5.130 28x28x20 Reducing Tee-Elbow Vol/ Surf - -

X 1.03" IGSCC A 10-42-AN-212 F-A F1.10c Variable Spring VT-3 RR-2 - - - - ANN H10-350, CC N-491-1

?' C-?19 B-J 8911 Elbow-Tee Voi/Sud - - -

1.03*

. i-19120 B-J 89.11 Tee-Valve RHR-88 Voi/ Surf X - -

1.03" RHR-88 B-M-2 B12.50 20" Globe Valve VT-3 - - -

20" Exam only when d;sassembled, limited to one valve in a group of ve'ves RHR-88 B-G-2 B7.70 20" Globe Valve Botting VT-1 - - -

<2" Limr.ed to valve selected under B-M-2 20-10-120A B-J 89.11 Valve RHR Eibow Vol/ Surf - - -

1.03*

20-10-1200 B-J B9.11 Elbow-Pipe Vol/ Surf - - -

1.03" 20-10-121A B-J 89.32 3/4" Branch Connection Surf - - -

.750" Exempt IWB-1220(a) 10-1-AS-211 F-A F1.10c Variable Spring VT-3 HR-2 X - - - ANY PFSK-4644, CC N-491-1 20-10-976 B-K-1 B10.10 Integral Attachment Surf RR-4 X - -

.500" CC N-509 20-10-976A b-K-1 B10.10 Integral Attachment Surf RR-4 - - -

.500" CC'N-509 10-1-AS-210 F-A F1.10c Variable Spring VT-3 RR-2 -

X -

.500* CC N-491-1 PFSK-4644 20-10-120HJG B-J 89.11 "ipe-Pipe Vol/ Surf - - -

1.03" 20-10-121 B-J 89.11 Pipe-Elbow Vet / Surf X - -

1.03" 20-10-122 B-J 89.11 Elbow-Pipe Vol/ Surf - - -

1.03" 10-1-HS-207 N/A N/A Hydraulic Snubber VT-3 RR - -

.625" TS Section 3.6.1 FILE RHRPLAN.10 Page 10 - 1 of 10-12

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James A. Fitzpatrick N.tclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] gp h Third Inservice inspect ~on intarval Ten - Year Inspection Plan Date: January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL IS!!NTERVAL LTH OR CAT ITEM DESCRIPTION EXAM .

REQ .

PER1 PER2 PER3 TH:CK , REMARKS 10 - RESIDUAL HEAT REMOVAL SYSTEM Drawing Number: MSK-3011 Line No. 20"-W20-1504-42 20-10-975 B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

.625" CC N-509 10-1-HS-209 N/A N/A Hyt.raulic Snubber VT-3 RR - -

.625" TS Section 3.6.1 20-10-975A B-K-1 B10.10 Inte9.al AMachment Surf RR-4 - - -

1.0" CC N-509 10-1-HS-208A N/A N/A Hydraulic Snubber VT-3 RR - -

1.0" TS Section 3.6.1 20-10-975B B-K-1 B10.10 Integral Attachraent Surf RR-4 - - -

1.0" CC N-509 10-1-HS-208 N/A N/A Hydraulic Snubber VT-3 RR - -

1.0" TS Section 3.6.1 20-10-123 B-J 89.11 Pipe-Valve MOV-18 Vol/ Surf - -

X 1.03*

MOV-18 B-M-2 E12.50 20"'3fobe Valve VT-3 - - -

20" Exam only when disassembled, limited to one valve in a group of valves MOV-18 B-G-2 B7.70 20" Globe Valve Botting VT-1 - - -

<2" Limited to valve selected under B-M-2 20-10-124 B-J 89.11 Valve MOV Pipe Vod/ Surf - - -

20" 20-10-124A B-J 89.32 3/4" Branch Connection : - - -

.750" Exempt IWB-1220(a) 10-1-AN-206 F-A F1.10c Variable Spring VT-3 RR-2 - - - -

ANN PF6K-4643 CC N-491-1 20-10-125 B-J 89.11 Pipe-Elbow Vol/ Surf - - -

1.03" 20-10-126 B-J 89.11 Eibow-Elbow Vol/ Surf - - -

1.03" 20-10-127 B-J Bd.11 Elbow-P ,e Vol/ Surf -

X -

1.03" 20-10-128P - -

Insulaticn Lug N/A - - - -

Inaccessible,inside pen No exam required FILE: RHRPLAN.10 Page 10 - 2 of to-12

~ J:mes A. stzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third inservice inspection Intervsl Date: January 7,1998

D 1)s9 V o@ h

'-"~'"' Ten -Year inspect'on Plan Rev sion 0 1

ASME WELD COMPONENT ASME ASME .

LTH OR CODE CODE REL ISIINTERVA" IDENTIFICATION - CODE REQ PER1 PER2 PER3 THtCK REMARMS CAT ITEM DESCRIPTION EXAM 10 -RESIDUAL HEAT REMOVAL SYSTEM Drawing Number: MSK-3011 l Line No. 20"-W261504-42 N/A - - - Inaccessible,inside pen, No exam required 20-10-128N - - Insulation Lug -

N/A - Inaccessible, inside pen, No exam required 20-10-128M - - Insulation I.ug - - -

l NiA - Inaccessible, inside pen, No exam required 20-10-128L - - Insulation Lug - -

N/A - - taaccessible, inside pen, No exam required 2fMO-128K - - Insulation Lug - -

N/A - Inaccessible, inside pen, No exam required 2^r10-128J - - insulation Lug - - -

N/A - - Inaccessible, inside pen, No exam required l 20-10-128H - - Insulation Lug - -

N/A - - - Inaccessible,inside pen, No exam required 20-10-128G - - insulation Lug -

N/A - - Inaccessible,inside pen, No exam required insulation Lug - -

20-10-128F - -

N/A - - - - Inaccessible, inside pen, No exam required 20-10-128E - - Insula

ion Lug N/A - - Inaccessible, inside pen, No exam required Insulation Lug - -

20-10-128D - -

N/A - - Inaccessible, inside pen, No exam required 20-10-128C - - insulation Lug - -

Pipe-integral Fitting Vol/ Surf - - - 1.03* Inaccessible inside Pen 1 20-10-1288 B-J 89.11 i

FILE RHRPLAN.10 Page 10 - 3 of 10-12

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James A. Fitzpatrick Nucle' r Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] l Date: January 7,1998 gg W Third Inservice inspection interval Revision 0 Ten - Year Inspection Plan ASME EJ COMPONENT ASME ASME LTH")R CODE CODE REL ISf PfTERVAL IDENTIFICATION CODE PER1 PER2 PER3 THICK REMARKS ITEM DESCRIPTION EXAM REO CAT

\

10 - RESIDUAL fiEAT REMOVAL SYSTEM Drawing Number: MSK-3011 Line No. 20*-W20-1504-42 B-J 89.11 Integral Fi' ting- Liner Vol/ Surf - - - -

l 33-10-128A Pipe-Integal Fitting Vot/ Surf - - - 1.03" 20-10-128 B-J B9.11 1.0" Exempt IWB-1220(a) 1.0" Branch Connection Surf - - -

20-10-129A B-J 89.32 Pipe-Valve MOV-17 Vol/ Surf - - - 1.03" 20-10-129 B-J 89.11 VT-3 - - 20" Exam only when disassembled. limited to one valve MOV-17 B-M-2 B12.50 20" Globe Valve -

in a group of valves 26 Globe Valve Botting VT-1 - - - <2* Limited to valve selected under B-M-2 MOV-17 B-G-2 87.70

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FILE: RHRPLAN.10 Page 10 -4 of 10-12

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L.J James /.. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third inservice inspection Interval Date: January 7,1998 g llowMW Ten - Ytar laspection Plan Revision 0 1

ASME WELD COMPONENT ASME ASME LTH OR l

1 CODE REL ISIINTERVAL IDENTIFICATION COCE CODE REMARKS l

ITEM DESCRIPTION EX e.M REQ PER1 PER2 PER3 THfCK CAT '

l l 10 - RESIDUAL HEAT REMOVAL SYSTEM Drawing Number: MSK-3013 Line No. 24"-W20-902-14A from 28"-WH-GE-2A B-F B5.130 28x28x24 Reducing 24-10-130 X 1 219 IGSCC D, every 2 refueling outages l Tee-Valve RHR-81A Vo!/ Surf - -

VT-3 - -

24.0" Exem only when disassembled timited to one valve 24" Globe Valve RHR-81A B-M-2 B12.50 in a group of valves 24" Globe Valve lo!Ung VT-1 - - -

<2" Limited to valve selected under B-M-2 RHR-81A B-G-2 B7.70 24-10-131 B-F B5.130 Valve RHR-81 A-Vol/ Surf - X - 1.219 IGSCC D, every 3 refuemg outages Valve AOV-68A RR-2 ANN H10-347, CC N-491-1 F-A F1.10b Vertical Constraint VT-3 - - - -

10-14A-AN-240 VT-3 - - -

24.0" Exam only when disassembled, limited to one valve AOV-68A B-M-2 812.50 24" Check Valve in a group of valves

'4" Check Valve Bolting VT-1 - - - <2" Limited to valve selected under B-M-2 AOV-68A B-G-2 87.70 Vo!! Surf - -

X 1.219 IGSCC 0, every 2 refueling outages

. 24-10-132 B-F B5.130 Valve AOV-68A-E! bow l

Integral Attachment Surf RR-4 - - -

1.0" CC N-509 24-10-132A B-K-1 810.10 Hydraulic Snubber V1-3 RR - - - FFSK-763. TS Section 3.6.1 10-14A-HS-240A N/A N/A Elbow-Pipe Vol/ Surf X - - 1.21 -

24-10-133 B-J 89.11 t

1 Pipe-Pipe Vot/ Surf - - - 1.21 -

24-10-133A B-J 89.11 VT-3 RR - - - H10-348, TS Section 3.6.1 10-14A-AN-241 A N/A N/A Hydraulic Snubber Hydraulic Snubber VT-3 RR - - -

PFSK-761.TS Section 3.6.1 10-14A-HS-240B N/A N/A Surf RR-4 - - - 1.0" CC N-509 24-10-132B B-K-1 B10.10 WeHed Attachment FILE: RHRPLAN.10 Page 10 - 5 of 10 -12

O O James A. Fitzpatrick Nuclear Power Plant JAF-IS14003 C ;

Third Inservice Inspection interval Date: January 7,1998 g Psimer Ten -YearInspection Plan Revision 0 ASME WELD COMPONENT ASME ASME ISINTERVAL LTH OR CODE CODE REL

- IDENTIFICATION CODE REO PER1 PER2 PER3 THICK "iMARKS CAT ITEM DESCRfPTON EXAM ,

10 - RESIDUAL HEAT REMOVAL SYSTEM Drawing Number: MSK-3013 Line No. 24"-W20-902-14A Pipe-Elbow Vot/Suf X - - 1.21 24-10-134 B4 89.11 Elbow-Pipe Vol/ Surf - X - 121 24-10-135 B-J B9.11

- - .375" Exempt per iWB-1220(a) 24-10-985 B-J B9.32 3/4" Branch Connection Surf -

810.10 Integral Attachment Surf RR-4 - - - .375' CC N-509 24-10-985A B-K-1 B9.11 Pipe-Elbow Vol/ Surf - - X 1.21 24-10-136 B-J Pipe-Pipe Vol/ Surf - - - 1.21 24-10-137 B-J B9.11 Pipe Dipe Vol/ Surf - - -

1.21 24-10-138 B-J B9.11 N/A - - Inaccessible, inside pen. No exam required 24-10-139P - - Insulation Lug - -

N/A - Inaccessible, inside pen, No exam required 24-10-139N - - Insulation Lug - - -

N/A - - Inaccessible, inside pen, No exam required 24-10-139M - - Insulation Lug - -

N/A - Inaccessible, inside pen, No exam required losulation Lug - - -

24 .0-139L - -

N/A - - Inaccessible,inside pen No exam required 24-10-139K - - Insulation Lug - -

N/A Inabssible,inside pen No exam required 24-10-139J - - Insulation Lug - - - -

N/A - Inaccessible, :nside pen, No exam required 24-10-139H - - Insulation Lug - - -

FILE: RHRPLAN.10 Page 10 - 6 of 10-12

yj <J v James A Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] A NewWrkPimer Third Inservice Inspection Interval Date: January 7,1998

Ten - Year inspection Plan Revision 0 l

COMPONENT ASME ASME ASME V' ELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICK REMARKS 12 - RESIDUAL HEAT REMOVAL SYSTEM Drawing Number: MSK-3013 '

Line No. 24"-W20-902-14A i

24-10-139G - - Insulation Lug N/A - - - -

Inaccessible, inside pen. No exam reqatired 24-10-139F - -

Insulation Lug N/A - - - - Inaccessible, inside pen, No exam raquired 24-10-139E - -

Insulation Lea N/A - - - -

Inaccessible, inside pen. No exam required 24-10-139D - -

insulation Lug N/A - - - -

Inaccessible, inside pen. No exam required 24-10-139C - - insulation Lug N/A - - - -

Inaccessible,inside pen. No exam required 37-10-1398 B-J BD.11 Integral Fitting-Pipe Vol/Sud - - - -

Inaccessible inside Pen X-13A 37-10-139A B-J 89.11 Integral Fitting-Liner Vot/ Surf - - - -

24-10-139 B-J B9.11 Pipe-Integral Fitting Vot/ Surf - - -

1.21 FW 24-10-140 B-J 89.11 Pipe-Valve AOV-25A Vol/T' sri - - -

1.21 FW 24-10-140D B-J 39.32 3/4" Branch Connection Surf - -

.750" Socket. Exempt per IWB-1220(a)

AOV-25A B-M-2 B12.50 24* Globe Valve VT-3 - - -

24" Exam only when disassembled. limited to one valve in a group of valves AOV-25A B-G-2 87.70 24" Globe Valve Botting VT-1 - - -

<2" Limited to valve selected under B-M-2 24-10-987 B-J B9.11 Valve-Pipe Vol/ Surf - - -

1.21 FW 24-10-988 B-J 89.32 3/4" Branch Connecten Surf - - -

.750" Exempt per IWB1220(a)

FILE: RHRPLAN.10 Pa,,e 10 - 7 of 10-12

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V James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] pp Pamr Thirri inservice Inspecticn Interval Date: January 7,1998

en -Year inspection Plan Revision 0 COMPONENT AS'AE ASME ASME WCLD IDENTIFICATIOt* CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 10 - RESIDUAL HEAT REMOVAL SYSTEM Drawing Number: MSK-3013 Line No. 24"-W20-902-14A 24-10-989 B-K-1 810.10 Integral Attachment Vul/ Surf RR-4 - - -

.719 CC N-509 10-14A-AS-244 F-A F1.10c Vertical Spring VT-3 RR-2 - -

X -

ANSY PFSK-1902. CO N-491-1 24-10-990 B-J B9.11 Pipe-Valve MOV-27A Vol/ Surf -

X -

1.21 FW MOV-27A B-M-2 B12.50 24" Globe Valve VT-3 - - -

24" Exam.maly when disass wnbled limited to one valve in a group of valves MOV-27A B-G-2 87.70 24" Globe Va!ve Botting VT-1 - - -

<2" Limited to valve selected under B-M-2 24-10-991 B-J B9.11 Valve-Pipe Vol/ Surf - - -

1.21 Line No. 24"-W20-902-148 from 28"-WH-GE-2B 24-10-142 B-F B5.130 28x28x24 Reducing Teehalve RHR-818 Vol/ Surf X - -

1.219 iGSCC D. every 2 refueling outages RHR-818 B-M-2 812.50 24" Globe Valve VT-3 - - -

24" Exam only when dismsembled, limited to one valve in a group of valves RHR-818 B-G-2 B7.70 24" Globe Valve Bolt;ng VT-1 - - -

<2" Limited to valve selectud under B-M-2 10-14B-AN-245 N/A N/A Hydraulic Snubber VT-3 - - -

PFGK-769/JAF#813, TS Section 3.6.1 24-10-143 B-F B5.130 Viv RHR-01B-Viv AOV-68B Vul/ Surf - X -

1.219 IGSCC D, every 2 refueling outages AOV-688 b-M-2 812.50 24" Chek Valve VT-3 - - -

24" Exam only when disassembled, limited to one valve in a group of valves AOV-688 B-G-2 B7.70 24" Check Valve Bo!'ing VT-1 - - -

<2" Limited to valve selected under B-M-2 24-10-144 B-F E,5.130 ValveAOV-688-Elbow Vol/ Surf - -

X 1.219 IGSCC D. every 2 refueling outages FILE: RHRPLAN.10 Page 10 - 8 of 10-12

O O Jisnes A'fitzpatr'ck Nucle:r Power Pl nt [[::JAF-ISI-0003|JAF-ISI-0003]] O .

Third inservice inspection Interval Date: January 7,1998 M NeMrYorkh Revision 0 M Ten - Year inspection plan

! 4 l

ASME WELD COMPONENT ASME ASME IS11NTERVAL LTH OR CODE CODE COJE RE1 IDENTIFICATION EXAM REO PER1 F ER2 PER3 THICK REMARKS CAT ITEM DESCRfPTION 10 - RESIDUAL HEAT REMOVAL SYSTEM Drawing Number: MSK-3013 Line No. 24"-W20-902-148 Hydraulic Snubber VT-3 RR - - - TS Section 3.6.1. ANY H10-345 l 10-148-HS-245A N/A N/A l

Integral Attachment Surf RR-4 - - - 1.0* CC N-509

! 24-10-144A B-K-1 810.10 89.11 Eltwrv-Elbow Vol/ Surf X - - 121 24-10 145 B-J Elbow-Pipe Vof/ Surf - - - 1.21 24-10-146 B-J B9.11 Vertical Support VT-3 RR-2 - X - -

ANY H10-345. CC N-491-1 10-148-AN-246 F-A F1.10b Integral Attachment Suif RR-4 - X .500" CC N-509 24-10-992 B-K-1 B10.10

- 1.0" Exempt per IWB-1220(a) 1.0" Branch Connection Surf - -

24-10-146A B-J 89.32 Pipe-Pipe "* Surf - - - 121 24-10-1468 B-J 89.11 Hydraufic Snubber VT-3 RR - - - T3 Section 3.C.1 HSY PCSK-768/JAF#237 10-148-HS-247 N/A N/A Integral Attachment Surf RR-4 - - - 1.0 CC N-509 24-10-993 B-K-1 B10.10 Pipe-Pipe Vof/ Surf - -

1.21 24-10-147 B-J 89.11 Pipe-Elbow Vot/ Surf - - - 1.21 24-10-148 B-J B9.11 VT-3 RR-2 AN r410-346, CC N-491-1 Vertical Support - - - -

10-148-AN-248 F-A F1.10b Integral Attachment Surf RR-4 - - - .719" CC N-509 24-10-147A B-K-1 810.10 f X 1.21

! B-J B9.11 Elbow-Pipo Vo!/ Surf - -

24-10-149 B9.11 Pipe-Elbow Vol/ Surf - - - 1.21 r 24-10-150 B-J Fipe-Pipe Vol/ Surf - - - 1.21 FW 2'-10-151 B-J 89.11 FILE: RHRPLAN.10 Page 10 - 9 of 10-12

Os O~ Jemes A. Fitzpatrick IJucle:r Power Plant JAF-ISI-0 I

Third Inservice Inspection Interval Date: January 7,1998 -

M 18ewMW Ten -Year Inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME LTH OR l CODE REL ISi tNTERVAL

! IDENTiric4 TION CODE CODE PER1 PER2 PER3 THICK REMARKS CAT ITEM DESCf!!PTION EXAM REO uma ammmmmusrr i 10 - RESIDfjAL HCA's' REMCVAL SYSTEM Drawing Number: MSK-3013 Line No. 24'-W20-902-14D N/A - - - Inaccessible,insde pen, No exam required

- - Insulation Lug -

g 24-10-152P Inaccessible, inside pen, No exam required Insulation Lug N/A - - -

24-10-152N - -

Inaccessible, inside pen, No exam required Insulation Lug N/A - - - -

24-10-152M - -

Inaccessible, inside pen, No exam required Insulation Lug N/A - - - -

' 24-10-152L - -

Inaccessible, inside pen, No exam required insulation lug N/A - - - -

24-10-152K - -

- Inaccessib'e, inside pen, No exam required Insulation Lug N/A - - -

24-10-152J - -

Inaccessible, inside pen, No exam required

,24-10-152H - - Insulation Lug N/A - - - -

- Inaccessible, inside pen, No exam .equired insulation Lug N/A - - -

. 24-10-152G - -

Inaccessible, insMe pen, No exam required Insu!ation Lug N/A - - - -

24-10-152F - -

N/A - - Inaccessible, inside pen, No exam required Insulation Lug - -

24-10-152E - -

Inaccessible, inside pen, f !O axam required insulation Lug N/A - - - -

24-10-152D - -

?

FILE: RHRPLAN.10 Page 10 - to of 10-12

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] O(.

M Third inservice inspection Interval Date: January 7,1998 gIBees Ten - Year Ir.spection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK PEMARKS 13 - RESIDUAL VdAT REMOVAL SYSTEM Drawing Number: MSK-3013 Line No. 24"-W20-902-14B 24-10-152C - - Insulation Lug N/A - - - -

Inaccessib!e inside pen. No exam required 24-10-1528 PJ 89 11 Integral Fitting-Pipe VoI1 Surf - - - - Inaccessible, inside pen X-138

} 24-10-152A B-J . 89.11 Ir.tegral Fi"ing-Lar:er Vol/ Surf - - - -

24-10-152 B-J 89.11 Pipe-int egral Fitting Vol/ Surf - - -

1.21 FW 24-10-1500 B-J B9.32 3/4" Branch ConnecNor4 Surf - - -

.750" FW Socket Weld. Exempt IVE-1220(a) 24-10-153 B-J 89.11 Pipe-Valve MOV-258 Vol/ Surf -

X -

1.21 FW MOV-258 B-M-2 P12.50 24" Giobe Valve VT-3 - - - ?.4* Exam only when disassembled, limited to one valve in a group of valves MOV-25B B-G-2 B7.70 24" Globe Vafve Bolting VT-1 - - -

<2" Limited to valve selected under B-M-2 24-10-995A B-J 09.32 3/4" Branch Connection Serf - - -

.750" Exempt IWB-1220(a) 24-10-995 B-J 09.11 Valve f/OV-25B-Reducer Vol/ Surf -

X -

1.21 FW 24-10-997A B- B9.32 3/4" Branch Connection Surf - - -

.750' Exempt IWB-11220(a) 10-148-A-249 F-A F1.10c Variab!e Spring VT-3 RR-2 - - - -

ASV PFSK-1903. CC N-491-1 24-10-997 B-J 89.11 Reducer-Valve MOV-270 Vol/ Surf - - -

1 ?1 FW 24-10-996 B-K-1 B10.10 Integral Attachment Surf P,R-4 - - -

.719" CC N-509 MOV-27B B-M-2 012.50 24" Globe Valve VT-3 - - -

24' Exam only when disassembled, limited to one valve in a group of valves FILE: RHRPLAN.10 Page 10 - 11 of 10-12 1

f3 ')J QV.

& JImes A. Fitzpatrick Nucleir Power Pl nt [[::JAF-ISI-0003|JAF-ISI-0003]] Date: January 7,1998 g b Third inservice inspection Interval

' Ten - Year inspection Plan Revision 0 l

l WELD I COMPONENT ASME ASME ASME CODE REL ISIINTERVAL LTH OR IDENTIFICATION CODE CODE REMARKS CAT ITEM DESCRIPTION EYAM REQ PER1 PER2 PER3 THICK 10 - RESIDUAL HEAT REMOVAL SYSTEM Drawing Number: MSK-3013 Line No. 24"-W20-902-14B l

24" Globe Valve Botting VT-1 - - -

<2* Limited to valve selected under B-M-2

! MOV-278 B42 B7.70 Valve-Prpe VoVSurf - - - 1.21 l 24 10-998 B-J 89.11 l

i t

FILE: RHFtPLAN.10 Page 10 - 12 of 10-12

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l [[::JAF-ISI-0003|JAF-ISI-0003]] J mes A. Itzpatrick Nuclear Powar Plant Third Inservice inspection Interval Date: January 7,1998 AfD NewywkPower Ten - Year inspection Plan Revision 0 1

ASME WELD COMPONENT ASME ASME LTH OR CODE REL ISi fNTERVAL IDENTIFICATION CODE CODE RfMARKS j CAT ITEM DESCRMON EXAM REQ PER1 PER2 PER3 THICK l

12 - Reactor Water Cleanup Drawing Number: MSK-3018 Lme flo. 6"-WR-1504-73 Pipe-Valve RWC-46 Vol/ Surf - - -

.432" 6-12-141 B B-J 89.11 7

Line No. 6"-WR-902A-1 VT-3 - - - Only wnen disassembled, Larruted to orse valve Valve Interior RWC-46 B-M-2 812.50 among a group of vafves Valve Botting VT-1 - - - - Limited to valve selected under B-M-2 RWC-46 B-G-2 87.70 Valve RWC-46-Pipe VouSurf X - -

.432*

6-12-901 B-J 89.11 Surf - - -

.432" Exempted per IWB-1220(a) 6-12-901 A B-J 89.32 3/4" Branch Connection Surf - -

.432" Exempted per (WB-1220(a) 6-12-901 B B-J 09.32 2' Branch Connection -

i Pipe-Et,ow VoVSurf X - -

.432" l 6-12-902 B-J 89.11 89.11 Elbow-Valve MOV-15 VouSurf - - -

432" 6-12-903 B-J 1" Branch Connection Surf - - -

432" Bypass Line Exempt RAS-1220(a) 6-1. -903A B-J 89.32 VT-3 - - - Only when disassembled Limited to one valve in a MOV-15 B-M-2 B12.50 Vafve interiors -

group of valves Vatve Bolting VT-1 - - - <2" Limited to valve selected under B-M-2 MOV- 15 B-G-2 B7.70 89.11 Valve MOV-15-Pipe VoVSurf - - -

.432" 6-12-904 B-J VT-3 RR-2 H12-90, CC N-491-1 Variable Spring - - -

12-1-AN-16 F-A F1.10c I

Pipe-Pipe VoVSurf - - - .432" 6-12-904A B-J 89.11 FILE: RWCPL AN.12 Page 12 - 1 of 12-5

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James A. Fitzpatrick Nuclear Power PI:nt [[::JAF-ISI-0003|JAF-ISI-0003]] O

Third Inservice Inspection Interval Daw: January 7,1998 h

$ Ten -Yearinspection Plan Revision 0 ASME WELD COMPONENT ASME ASME ISIINTERVAL LTH OR CODE CODE REL IDEN'Ir7 CATION CODE REQ PER1 PER2 PER3 THICK REMARKS CAT ITEM DESCRIPTION EXAM 12 - Reactor Water Cleanup Drawing Numoer: MSK-3018 Line No, t"-WR-902A-1 Vol/ Surf - X -

.432" 6-12-905 B-J 89.11 Pipe-Elbow Elbow-Pipe Vol/ Surf - - - .432" 6-12-906 B-J 89.11 VT-3 RR-2 X -

.203* H12-91, CC N-491-1 12-1-AN-17 F-A F1.10c Variable Spring -

Surf RR-4 - X - .203" CC N-509 6-12-906A B-K 1 B10.10 Integral Attachrnent Vol/ Surf - - - 432" 6-12-913 B-J 89.11 Pipe-Pipe Vol/3urf - - - .432" 6-12-906TM B-J B9.11 Pipe-Pipe VT-3 RR - - H12-96. TS Section 3.6.1 12-1-HS-18 N/A N/A Hydraulic Snubber VT-3 RR - - H12-95 TS Section 3.6.1 12-1-HS-19 N/A d/A Hydraulic Snub 6er Pipe-Elbow VouSurf - - - .432" 6-12-907 B.J 89.11 Elbow-Pipe Vol/ Surf - - - .432*

6-12-908 B-J 89.11 VT-3 RR'1 - - - H12-94, TS Section 3.6.1 12-1-HS-20 N/A N/A H)draulic Snubber 7 Pipe-Pipe Vot/ Surf - - - 432*

6-12-908-JF B-J 89.11 VT-3 RR - - H12-93. TS Section 3.6.1 12-1-HS-20A N/A N/A Hydraurtc Snubber F' pe-Elbow Vol/ Surf - X - .432" 6-12-909 B-J B9.11 l VT-3 RR-2 - - - .375" H12-92, CC N-491-1 12-1-AN-21 F-A F1.10b Rigid Support Surf RR-4 - - - 375* CC N-509 6-12-909A B-K-1 B10.10 Integral Attachment Page 12 - 2 of 12-5 FILE: RWCPLAN.12

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\s' J mes A. Fitzpatrick Nuclect Power Plant [[::JAF-ISI-0000|JAF-ISI-0000]] est 18ewWrkFoner Third Inservice inscection Interval Date: January 7,1998

Ten - Year Inspection Plan Revision 0 i

COM?ONENT' ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM .

DESCRIPTION EXAM REQ PER1 PERT PER3 fHICK R2 MARKS 12 - Reactor Water C!eanup i Drawing Number: MSK-3018 Line No. 6"-WR-902A-1 6-12-910 B-J 89.11 Elbow-Pipe Vol/ Surf - -

X .432" 6-12-910A B-J 89.32 3/4" Branch Connection Surf - - - -

E.:empt IVG-1220(a s 6-12-911 B-J 89.11 Pipe-Pipe Vol/ Surf - - -

.432" 6-12-911-Q - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen. X-14. No exam required 6-12-911-P - - Insulation Lug N/A - - - -

Maccessible, insk1e Pen. X-14. No exam required 6-12-911-N - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen. X-14. No exam required 6-12-911-M - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen. X-14. No exam required 6-12-911-L - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen. X-14. No exam required 6-12-911-K - -

insulation Lug N/A - - - -

Inaccessible, inside Pen. X-14. No exam required 6-12-911-J - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen. X-14. No exam required 6-12-911-H - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen. X-14, No exam required 7

6-12-911-G - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen. X-14, No exam required FILE: RWCPLAN.12 Page 12 - 3 of 12-5

C ,/ V v' James A. Fitzpatrick Noclear Power Piant [[::JAF-ISI-0003|JAF-ISI-0003]] M NewYorkPower Third Inservice inspection interval Date: January 't,1998 Ten - Year Inspection Plan Revision 0 COMPONENT ASME ISME ASME WELD IDENTIFICATION CODE CODE COuE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 12 - Reactor Water Cleanup Dratring Number: MSK-30iB Line No. 6"-WR-902A-1 6-12-911-F - - -

Insulation Lug N/A - - - - Inaccessible, inside Pen. X-14. No exam required 6-12-911-E - -

Insulation Lug N/A - - - -

Inaccesdble, inside Pen. X-14. No exam required 6-12-911-D - -

Insulation Lug N/A - - - -

inaccessible, insida Pen. X-14, No exam required 18-12-911C B-J 89.11 Integral Fitting-Liner Vol/ Surf - - - -

6-12-911 B B-J 89.11 Pipe-tr tegral Fitting Vol/ Surf - - -

.432" Inaccessible inside pen. X-14 6-12-911 A B-J 89.11 Integral Fitting-F ipe Vol/ Surf - - -

.432" 6-12-912 B-J B9.11 Pipe-Valve MOV-18 Vot/ Surf - -

X .432" MOV-18 B-M--2 812.50 Valve interior VT-3 - - - -

Only when disassembled MOV-18 B-G-2 B7.70 Valve BoMing VT-1 - - - -

Limited to valves selected under B-M-2 1.lae No. 4"-WD-902A-14 From hent Exchanger E-2A MOV-69 B'A-2 B12.50 Valve interior VT-3 - - - -

Only when disassembled, Limited to one valve in a g.obp of valves MOV-69 B-G-2 87.70 Vafve Botting VT-1 - - - -

Limited to valve selected under B-M-2 4-12-470 B-J 89.11 Pipe-Valve MOV-69 Vot/ Surf - -

X .337" 4-12-900 B-K-1 B10.10 Integral Attachment Lug Surf RR-4 - - - -

CC N-509 FILE: RWCPLAN.12 Page 12 - 4 of 12-5

O -

O James A. Fitzpatrick Nuchar Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] O

I Thl.d Inservice inspection Interval Date: Janut*y 7,1998 g Pbuser Ten - Year inspectior. Plan Revision 0 f

l ASME WELD COMPONENT. ASME ASME LTH OR i

CODE CODE REL ISIINTERVAL

! IDENT!FICATION CODE PER1 PER2 PER3 THICK REMArWS CAT ITEM DESCRIPTION EXAM REO j

i j 12 - Reactor Water Cleanup Drawing Number: MSK-3018

Line No. 4*-WD-902A-14 From Heat Exchanger E-2A VT-3 RR-2 X - - - PFSK-2312, CC N-491-1 12-14-NS-4 F-A ' F1.10b Box Constraint Elbov>-Pipe Vol/ Surf - X -

.337" 4-12-469 'B-J 89.11 B-J B3.11 Pipe-Elbow Vol/ Surf X -

.337"

. 4-12-469A VT-3 RR-2 - - - PFSK-1896, CC N-401-1

! 12-14-NS-3 F-A F1.10b Box Constraint -

B10,10 Integral Attachment Lug Surf RR-4 - - - -

CC N-509 4-1 .-899 B-K-1 VT-3 RR-2 - - - - PFSK-1897. CC N-491-1 12-14-NS-2 F-A F1.1'.t Box Constraint 89.11 Elbow-Pipe Vot/ Surf - - - .337" 4-12-467 B-J 89.11 Pipe-Elbow Vol/ Surf - - -

.337" 4-12-466 B-J Integral Attachment Surf RR-4 - - - - CC N-509 4-12-898 B-K-1 810.10 VT-3 RR-2 - - - PFSK-1892, CC N-491-1 12-14-NS-1 F-A F1.10b Constraint -

89.11 Elbow-Pipe Vo!/ Surf - - - .337" 4-12-915 B-J P

B-J 89.11 Pipe-Elbow Vol/ Surf - - - .337" 4-12-916 B-J 89.11 Elbow-Pioe Vol/ Surf - - - .327" 4-12-917 B-J 89.11 Pipe-Elbow Vol/ Surf - - - .337" 4-12-918 B10.10 Integral Attachment Surf RR-4 - - - - CC N-509 4-12-896 B-K-1 89.11 Reducer-Pipe Vol/ Surf - - - .337*

4-12-463 B-J l

l FILE: RWCPt.AN.12 Page 12 - 5 of 12-S 4.

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James A. F;tzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

,1p> MWykPamr Tnird Inservice Inspection Interval Date: January 7,1998 Ten -Year Inspection Plan Revisior. O COMPONENT ASME ASME ASME WELD IDENTIFICN00N CODE CODE CODE REL IS!!NTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS t

13 - Reactor Core injection Cooling

, Drawing Number: MSK-3019 Line No. 4"-W22-9024 from Valve MOV-21 MOV-2i B-M-2 B12.50 Valve interior VT-3 - - - -

Onfy when disassemoled, Emited to one valve in a group of vafves MOV-21 842 B7.70 Vafve Botting VT-1 - - - -

Limited to valve selected under B-M-2 4-13-1001 B-J 89.11 Pipe-Valve MOV-21 Vol/ Surf X - -

37T 4-13-1000A B-J 89.32 3/4" Branch Connection Surf - - - -

Exempt MB-1220(a) -

4-13-1000 B-J 89.11 Pipe-Pipe Vol/ Surf - - - 3 77" 4-13-458 B-J 89 11

+a RCIC-22 -Pipe Vol/ Surf -

X -

377" RCIC-22 B-M-2 B12.50 Valve interior VT-3 - - - -

Only when disassembled. Limited to one valve in a group of va!ves.

RCIC-22 B-G-2 B7.70 Valve Botting VT-1 - - - -

Limited to valve selected under B-M-2 4-13-457 B-J 89.11 Pipe-Valve Vol/ Surf - -

X .377" 13-4A-NS-11 F-A F1.10b Pipe Support VT-3 RR-2 - - - -

PFSK-919 CC N-491-1 4-13-456A B-J 89.11 Pipe-Pipe Vol/ Surf - - -

.37T ,

4-13-456 B-J 89.11 Elbow-Pipe Vol/ Surf X - -

.377" 4-13-455 B-J 89.11 Pipe-Elbev Vol/Sur' -

X -

.377" 13-4A-NS-10 F-A F1.10b Constraint VT-3 RR-2 - - -

.375" PFSK-2255, CC N491-1 4-13-454A B-J 89.11 Pipe-Pipe Vol/ Surf - - -

.377" Fil.E: RCIC.13 Page 13 - 1 of 13-9 m

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James . Itzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

'g %YN h Third Inservice inspection Interval Ten -Yearinspection Plan Date: January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS

~ ~

i 13 - Reactor Core Injection Coollag Drawing Number: MSK-3019 Une No. 4"-W22-902-4 from Valve MOV-21 4-13-895 B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

375" CC N-509, Located inside wa.1 s:eeve 4-13-454B B-J 89.32 3/4" Branch Connection Suif - - - -

Exempt IWB-1220(a) 4-13-454- B-J 89.11 Elbow-Pipe Vol/ Surf - - -

.337' 4-13-453 B-J 89.11 Pipe-Sibow Vol/ Surf - -

.337" 4-13-453A B-K-1 810.10 Integral Attachment Surf RR-4 - -

X .250" H13-10 CC N-509 13-4A-NS-9 F-A F1.10b Corntraint VT-3 RR-2 - -

X .250" H13-10. CC N-491-1 4-13-894 B-K-1 B10.10 Integral Attachment Lug Surf RR-4 - - - -

CC N-509 4-13-893 B-K-1 810.10 Integral Attachment Lug Surf RR-4 - - - -

CC N-509 4-13-452A B-K-1 B10.10 Integral Attachment Surf RR-4 -

X -

.250" H13-11. CC N-509 13-4A-NS-8 F-A F1.10b Constraint VT-3 RR-2 -

X -

.250" H13-11, CC N-491-1 4-13-452 B-J 89.11 Pipe-Pipe Vot/ Surf - - -

.337" 4-13-892 B-K-1 B10.10 Integraf Attachment Lug Surf RR-4 - - - -

CC Ne509 4-13-451B B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

.250" CC N-509 13-4A-NS-7 F-A F1.10b Constraint VT-3 RR-2 - - -

.250" H13-12. CC N-491

4-13-891 B-K-1 B10.13 Integral Attachment Lug Surf RR-4 - - - -

CC N-509 13-tA-NS-6 F-A F1.10b Constraint VT-3 RR-2 X - -

.375" H13-13 CC N-491-1 h

FILE: RCIC.13 Page 13 - 4 of 13-9

O O James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] O

Third inservice Inspection Interval Date: January 7,1998 gg h Ten -Year inspection Plan Revision 0 ASME WELD

' COMPONENT ASME ASME LTH OR CODE CODE REL ISIINTERVAL IDENTIFICATION CODE ~ REMARKS ITEM DESCRtPTION EXAM REQ PER1 PER2 PER3 THICK CAT m- .

13 - Reactor Core injection Cooling Drawing Number: MSK-3019 l Line No.1"-W22-902-4 from Valve MOV-21 B10.10 Integral Attachment Surf RR-4 - - - .375" CC N-509 4-13-451 A B-K 89.11 Pipe-Pipe Vol/ Surf - - - .337*

4-13-451 B-J B13.10 Integral Attachment Lug Surf RR-4 - - - - CC N-509 4-13-890 B-K-1 810.10 Integral Attachment Surf RR-4 - - - .250" CC N-509 4-13-4500 B-K-1 VT-3 RR-2 - - - .250" H13-14, CC N-491-1 13-4A-NS-5 F-A F1.10b Constraint 810.10 Integral Attachment Lug Surf RR-4 - - - - CC N-509 4-13-889 B-K-1 VT-3 RR-2 - - -

.250* H13-15, CC N-491-1 13-4A-NS-4 F-A F1.10b Constraint B10.10 Integral Attachment Surf RR-4 - - -

.250" CC N-509 4-13-450A B-K-1 89.11 Pipe-Pipe Vol/ Surf - - - .337" 4-13-450 B-J B10.10 Integral Attachment Lug Surf RR-4 - - - - CC N-509 4-13-888 B-K-1 B9.11 Elbow-Pipe Vol/ Surf - - - .337" 4-13-449 B-J VT-3 RR-2 - - -

.254" H13-16, CC N-491-1 13-4A-NS-3 F-A F1.10b Constraint B10.10 integral Attachment Surf RR-4 - - - .154* H13-16. CC N-509 4-13-448A B-K-1 B9.11 Pipe-Elbow Vof/ Surf - - -

.337" 4-13-448 B-J Surf - - - - Exempt IWB-1220(a) 4-13-887A B-J B9.32 3/4" Branch Connection 89.1- Elbow-Pipe Vol/ Surf - - .- .337" 4-13-447 B-J FILE: RCIC 13 Page 13 - 3 of 13-9

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! WEBSTER NE YORK 14580 (716) 265-1600

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James . Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Date: Jarpsary 7,1998 g W Third inservice Inspection interval Ten -Yearinspection Plan Revision 0 ASME WELD COtIPONENT ASaIE ASME ISilNTERVAL

TH OR -

CODE CODE REL IDENTIFICATK)N CODE EXAM REQ PER1 PER2 PER'.; THICK REMARKS CAT ITEM DESCRtPTION 13 - Reactor Core injection Cooling Drawmg Number: MSK-3019 -

$ Line No. 4"-W22-902-4 from Valve MOV-21 89.11 Pipe-Elbow Vol/ Surf - - - .337" b 4-13-446 B-J

- r CC N-509 810.10 Integral Attachmimt Lug Surf RR-4 - - - -

4-13-887 B-K-1 VT-3 RR-2 - - - - PFSK-1030 CC N-491-1 13-4A-NS-2 F-A F1.10b Box Constraint VT-3 RR-2 - - - - PFSK-2214. CC N-491-1 13-4A-NS-1 A F-A F1.10e Rigid Sway Strut

{

89.11 Elbow-Pipe Vol/ Surf - - -

.337" 4-13-445 PJ Vol/ Surf - - - .337"

~

4-13-444 B-J 59.11 Pipe-Elbow

+

Surf RR-4 - - - - CC N-509

= 4-13-886 B-K-1 810.10 Integral Attachment Lug E .500* CC N-509 B-K-1 B10.10 integral Attachment Surf RR-4 - - -

4-13-443A VT-3 RR-2 - - .500" H13-19. CC N-491-1 13-4A-NN-1 F-A F1.10b Constraint 5 89.11 Reducer-Pipe Vol/ Surf - - - .337"

= 4-13-443 B-J I

Vol/ Surf - - - 442" 6-13-442 B-J 89.11 Tee-Reducer Vol/ Surf RR-5 - - .432" Thenpal Sleeve, CC M-524 6-13-965-LS1 B-J 89.12 Tee-Long Seam -

h Thermal Sleeve, CC N-524 89.12 Tee-Long Seam Vot/ Surf RR-5 - - - .432"

- 6-13-965-LS2 B-J

. Thermal Sleeve, CC N-524 89.12 Tee-Long Seam Vol/ Surf RR-5 - - - .432"

[ 6-13-966-LS1 B-J

=

F B9.12 Tee-Long Seam Vol/ Surf RR-5 - - - .432" Thermal Sleeve. CC N-524 i 6-13-966-LS2 B-J h Vol/ Surf - - - .432"

- 6-13-462 B-J 89.11 Tee-Reducer E

E t

a c Page 13 - 4 of 13 - 9 FILE: RCIO.13 g

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U<~ James A. Fitzp'. trick Nucle r Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third inservice inspection Interval Date: January 7,1938 4 h Revision 0 Ten - Year Inspection Plan ASME WELD COMPONENT ASME ASME ISilNTERVAL LTH OR CODE CODE REL tDENTIFICATION CODE REO PER1 PER2 PER3 THICK REMARKS CAT ITEM DESCRIP"ON EXAM 13 - Reactor Core injection Cooling Drrwing Number: MSK-3019 Liste No. 4"-W22-902-4 from Valve MOV-21 Vol/ Surf - - X 432" 6-13-441 B-J 89.11 Pipe-Tee B9.11 Reducer-Pipe Vol/ Serf - - - .432" 6-13-440 B-J Line :*o. 4"-W22-902A 4A 89.11 Pipe-Reducer Vol/ Surf - - -

.337" 4-13-439 B-J 89.11 Tee-Pipe Vol/ Surf - - - .337" 4-13-438 B-J r

Page 13 - 5 of 13-9 FILE: RCIC.13

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! James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] l

4 II8WMM Third Inservice inspection Interval Date: January 7,1998 Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITENI DESC t!PTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 1

13 - Reactor Core injection Cooling Drawing No. MSK-3020 Line No. 3"-SHP-902-17A from MSK-3031 3-13-1017 B-J 89.21 Reducer-Pipe Surf - - -

.300" Exempt IWB-1220(a) 3-13-1018 B-J 89.21 Pipe-Elbow Surf - - -

.300" Exempt IW8-1220(a) 3-13-1019 B-J B9.32 1* Branch Connection Surf - - - -

Exempt IWB-1220(a) 3-13-1020 B-J B9.32 1" Branch vonnection Surf - - - -

Exempt IVB-1220(a) 3-13-1021 B-J 89.21 Elbow-Pipe Surf - - -

.300" Exempt MB-1220(a) 3-13-1022 B-J 89.21 Pipe-Elbow Surf - - -

.300* Exempt IWB-122-(a) 3-13-1023 B-J 89.32 1" Branch Connection Surf - - -

300" Exempt IWB-122C(a) 3-13-1024 B-J 89.32 1" Branch Connection Surf - - -

.300* Exempt !WP-122C(a) 3-13-1025 B-J 89.21 Elbow-Pipe Surf - - -

.300" Exempt IWB-1220(a) 3-13-1026 B-J 89.32 1" Branch Connection Surf - - - -

Exempt IWB-1220(a) 3-13-1027 B-J 89.21 Pipe-Pipe Surf - - -

.300* Exempt IVB-1220(a) 3-13-1028 B-J B9.21 Pipe-Elbow Surf - - -

.300* Exenypt IWB-1220(a) 13-17A-AN-15 F-A F1.10b Constraint VT-3 - - - -

H13-37A 3-13-1029 B-J B9.32 3/4" Branch Connection Surf - - - -

Exempt IWB-1220(a) 13-17A-AN-16 F-A F1.10b Constraint VT-3 - - - -

H13-38 3-13-1030 B-J B9.21 Pipe-Elbow Surf - - -

.300" Exempt IWB-1220(a)

FILE: RCIC.13 Page 13 - 6 of 13-9

, 3 James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] A New M M Third inservice inspection Interval Date: January 7,1998

Ten -Yearinspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 13 - Reactor Core injection Cooling Drawing No, MSK-3020 line No. 3"-SHP-902-17A from MSK-3031 3-13-1031 B-J 89.21 Elbow-Pipe Surf - - -

.300" Exempt IWB-1220(a) 3-13-1032 B-J B9.32 3/4" Branch Connection Surf - - -

.300" Exempt IWB-1220(a) 3-13-1032A B-J 89.32 1" Branch Connection Surf - - - - Exempt IWB-1220(a) 3-13-10328 B-J 89.21 Pipe-Valve MOV-15 Surf - - -

.300" Exempt IWB-1220(a)

MOV-15 N/A N/A Valve Interior VT-3 - - - <4' Exempt IWB-1220(a)

MOV-15 B-G-2 B7.70 Valve Bolting VT-1 - - -

<2* ljmited to valve selected under B-M-2 3-13-1032GL B-J B9.21 Valve-Pipe Surf - - -

.300* Exempt IWB-1220(a) 3-13-1032C B-J B9.32 1" Branch Coiinection Surf - - - - Exempt IWB-1220(a) 3-13-1033 B-t 89.21 Pipe-Elbow Surf - - -

.300" Exempt IWB-1220(a) 3-13-1034 3-J 89.21 Elbow-Pipe Surf - - -

.300* Exempt IWB-1220(a) 13-17A-NN-17 F-A F1.10b Constraint VT-3 - - -

.375' H13-39 3-13-1034A B-K-1 B10.10 Integral Attachment Surf - - -

.375* ,

3-13-1035 B-J 89.21 Pipe-Elbow Surf - - -

.300" Exempt IWB-1220(a) 3-13-1036 B-J 89.21 Elbow-Pipe Surf - - -

.300" Exempt lWB-1220(a) 3-13 1037 B-J 89.21 Pipe-Elbow Surf - - -

.300* Exempt IWB-1220(a) 3-13-1038 B-J B9.21 Elbow-Pipe Surf - - -

.300* Exempt IWB-1220(a)

FILE: RCIC.13 Page 13 - 7 of 13-9

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4 s ;V James A'.'. /Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] A bMM Third inservice inspection interval Date: January 7,1998 Ten - Year Inspection Plan Revision 0

. COMPONENT ASME ASME ASME WELD l IDENTIFICATION CODE COJE CODE REL ISIINTERVAL LTH OR l CAT ITEM OESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 13 - Reactor Core injection Cooling Drawing No. MSK-3020 Line No. 3"-SHP-902-17A from MSK-3031 i

13-17A-AN-18 F-A F1.10b Constraint VT-3 - - -

.145" H13-40 3-13-1038A B-K-1 810.10 Integral Attachment Surf - - -

.145* H13-40 3-13-1039 B-J 89.21 Pipe-Pipe Surf - - -

.300" Exempt IVB-1220(a) 3-13-10400 - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen X-10. No exam required 3-13-1040P - -

Insulation Lug N/A - - - - Inaccessible, inside Pen X-10, No exam required l 3-13-1040N - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen X-10. No exa.n required 3-13-1040M - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen X-10, No exam required l

l 3-13-1040L - -

Insulation Lug N/A - - - -

Inaccessib*e, inside Pen X-10, No exarr. required 3-13-1040K - -

Insufation Lug N/A - - - -

Inaccessible, inside Pen X-10, No exam required 3-13-1040J - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen X-10. No exam required 3-13-1040H - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen X-10, No exam required 3-13-1040G - -

Insutation lug N/A - - - -

Inaccessible, inside Pen X-10, No exam required l

l l

FILE: RCIC.13 l' age 13 - 8 of 13-9

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James A. Fitzpatrick Nuclear Po wer Plant JAF-ISl4003 4 hMh Third Inservice Inspection Interval Date: January 7,1998

Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICM REMARKS 13 - Reactor Core injection Cooling

' Drawing No. MSK-3020 Line No. 3"-SHP-902-17A from MSK-3031 3-13-1040F - - Insulation Lug N/A - - - - Inaccessible, inside Pen X-10, No exam required 3-13-1040E - - Insulation Lug N/A - - - -

Inaccessible, inside Pen X-10. No exam required 3-13-1040D - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen X-10. No exam required 3-13-1040C B-J 8921 Pipe-Integral Fitting Surf - - -

.300" Inaccessible, inside pen X-10 14-13-10408 B-J 89.21 Liner-Integral Fitting Surf - - - -

Exempt IWB-1220(a) 3-13-1040A B-J 89.21 Integral F.tting-Pipe Surf - - -

.300* Exempt IWB-1220(a) 3-13-1041 B-J B9.21 Pipe-Valve MOV-16 Surf - - -

.300" Exempt IWB-1220(a)

MOV-16 N/A N/A Valve interior VT-3 - - - <4" Exempt fWB-1220(a)

MOV-16 B-G-2 B7.70 Valve Botting VT-1 - - -

2" Limited to valve ser ected under B-M-2 r

flLE: RCIC.13 Page 13 - 9 of 13-9

'Gs %-

Jarnes Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] gb b Third Inservice laspection Interval Date January 7,1998 Ten -Yearinspection Fian Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PERS PER2 PER3 TH*OK REMARKS 14 - Core Spray System Drawing Number: MSK-3022 Line No.10"-W23-902-5A MOV-11 A B-G-2 ') ni Valve Bolting VT-1 - - -

<2" Limited to Valve r lected under B-M-2 MOV-11 A B-M-2 .12.50 Valve Interior VT-3 - - - Only when disassembled, limited to one valve in a group of valves.

10-14-771 B-J 89.11 Pipe-Valve MOV-11 A Vol/ Surf - -

X .594-10-14-772 B-J 89.32 3/4" Dianch Connection Surf - - - -. Exempt 1WB-1220(a) 10-14-773 B-J 89.32 3/4* Branch Connection Surf - - - -

Exerr,x IWB-1220(a) 10-14-774 B-J 89.11 Elbow-Pipe Vot/ Surf - - -

.594" 10-14-775 B-K-1 B10.10 Integral A'tachment Surf RR-4 X - -

.257" CC N-509 14-5A-AS-22 F-A F1.10c Variable Spring VT-3 RR-2 X - -

.237" PFSK-2139. CC N-491-1 10-14-776 B-J 89.11 Pipe-Elbow Vol/ Surf - - -

.594" 10-14-777 B-J 89.11 Valve MOV-12A-Pipe Vol/ Surf - - -

.594*

MOV-12A B-G-2 B7.70 Valve Bolting VT-1 - - -

<2" Limited to Valve selected under B-M-2 MOV-12A B-M-2 B12.50 Valve interior VT-3 - - - -

Only when disassembled, limited to one valve in a group of valves.

10-14-491 B-J 89.11 Pipe-Valve MOV-12A Vol/ Surf - - -

.594" 10-14-491 A B-J 89.11 Integral Fitting-Pipe Vol/ Surf - - -

.594*

20-14-4918 B-J 09.11 Liner-Integral Fitting Vol/ Surf - -

.8" FILE: CSPLAN.14 6 age 14 - 1 of 14-11

o V James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] V

$ %M Third Inservice inspection Interval Ten - Year Irispection Plan Date January 7,1998 Revision 0 COMPONENT ASME AEME ASME WELD IDENTIFICATION CODC CODE CODE REL ILilHTERVAL LTH OR CAT ITEM DESCRIPTION EXACA REC PER1 PER2 PER3 THICK r;EMARKS 14 - Core Spray System Drawing Number: MSK-3022 Line No.10"-W23-902-5A 10-14-491C B-J B9.11 Pipe-integral Fitting Vol/ Surf - - -

.594* Inaccessi51e inside Pen. X-16A 10-14-491D - - Insulation Lug N/A - - - - Inaccessible, inside Pen. X-16A, No exam required 10-14-491E - -

insulation Lug N/A - - - - Inaccessible, inside Pen. X-16A, No exam required 10-14-491F - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen. X-16A, No exam required 10-14-491G - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen. X-16A, No exam required 10-14-491H - -

Insulation Lug N/A - - - -

loaccessible, inside Pen. X-16A, No exam required 10-14-491J - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen. X-16A, No exam required 10-14-491 K - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen. X-16A, No exam required 10-14-491L - - insulation Lug N/A - - - - Inaccessible, inside Pen. X-16A, No exam required 10-14-491M - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen. X-16A, No exam required 10-14-491 N - -

Insulation Lug N/A - - - -

laaccessible, inside Pen. X-16A No exam required 7

FILE: CSPLAN.14 Page 14 - 2 of 14 - 11

('^'/ James A. itzpatrick Nuclear Power Plant JAF-ISl4003 V

Ptmer Third Inservice inspection Interval g g3 Ten -Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PEA 1 PER2 PER3 TH!CK REMARKS l 14 -Core Spray System l D awing Number- MSK-3022 l Line No.10"-W23-902-5A 10-14-491P - -

Insulation Lug N/A - - - - Inaccessible, inside Fen. X-16A, No exar1 required 10-14-491Q .

- Insulation Lug N/A - - - -

Inaccessible, inside Pen. X-16A, No exam required 10-14-490 B-J 89.11 Pipe-Pipe Vot/ Surf - - -

.594" j 10-14-489A B-J B9.32 3/4" Branch Connection Surf - - - -

Exempt IWB-1220(a) l 10-14-489 B-J 89.11 Elbow-Pipe Vol/ Surf - - -

.594" 10-14-488 B-J 89.11 Valve AOV-13A-Elbow Vol/ Surf - - -

.594" AOV-13A B-G-2 B7.70 Valve Bolting VT-1 - - -

<2" Limited to valve selected under B-M-2 AOV-13A B-M-2 B12.50 Valve interior VT-3 - - - -

Only when disassembled, !imited to one valve in a group of valves.

10-14-487 B-J B9.11 Pipe-Valve AOV-13A Vol/ Surf - - -

.594" 10-14-486 B-J 89.11 Elbow-Pipe Vol/ Surf - - -

.594" 10-14-485 B-J 89.11 Pipe-Elbow Vol/ Surf - - -

.594" 14-5A-HS-25 N/A N/A Hydraulic Snubber VT-3 RR - - - PFSK-794, TS Section 3.6.1 14-5A-HS-24 N/A N/A Hydraulic Snubber VT-3 RR - - - PFSK-793, TS Section 3.6.1 10-14-483 B-J B9.32 3/4" Branch Connection Surf - - - -

Exempt IWB-1220(a) 10-14-482 B-J B9.11 Pipe-Pipe Vot/ Surf - - -

.594" N

Y FILE: CSPLAN.14 Page 14 - 3 of 14 -11

Q] O James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

\J' 4 bMb Third Inservice inspection Interval Date January 7,1998 Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICAT!ON CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 TH!CK REMARKS 14 -Core Spray System Drawir.g Number: MSK 0022 Line No.10**-W23 902-5A 10-14-482A B-J 89.11 Valve CSP-14A-Pipe Vol/ Surf - - -

.594* Valve stub piece CSP-14A B-G-2 B7.70 Valve Bolting VT-1 - - -

<2" Limited to Jafve selected under B-M-2 CSP-14A B-M-2 B12.50 Valve Interior VT-3 - - - - Only when disassembled. Limited to one valve in a group of vafves 10-14-481 A B-J 8911 Pipe-Valve CSP-14A Vot/ Surf - - -

.594* Valve stub pioce 10-14-481 B-F B5.130 Pipe-Pipe Vol/ Surf -

X -

.594" IGSCC A, Dissimilar metal weld 10-14-480 B-J 89.11 Pipe-Elbow Vol/ Surf X - -

.594* IGSCC A 10-14-480-LS1 B-J 89.12 Pipe-Long Seam Vol/ Surf RR-5 X - -

.594" IGSCC A-1, CC N-524 10-14-480-LS2 B-J 89.12 Elbow-Long Seam Vol/ Surf RR-5 X - -

.594* IGSCC A-1 CC IJ-524 10-14-480-LS3 B-J 89.12 Elbow-Long Seam Vol/ Surf RR-5 X - -

.594* IGSCC A-1. CC N-524 10-14-479 B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

.237" CC N-509 14-5A-HS-23 N/A N/A Hydraulic Snubber VT-3 RR-11 - - -

237" PFSK-2139. TS Section 3.6.1 t

14-5A-AN-26 F-A F1.10b Vertical Restraint VT-3 RR-2 - - -

.375" H i4-56, CC N-491-1 10-14-478A B-K-1 B10.10 Integtal Attachment Surf RR-4 - - -

.375" CC N-509 10-14-478 B-K-1 010.10 Integral Attachment Surf RR-4 - - - -

CC N-509 10-14-477 B-J 89.11 Elbow-Pipe Vol/ Surf -

X -

.594* IGSCC A FILE: CSPLAN.14 Page 14 - 4 of 14 -11

g3 N, %

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] g b Third Inservice inspection interval Ten - Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL .dIINTERVAL LTH OR CAT ITEM DESCR!PTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 14 - Core Spray System Drawing Number: MSK-3022 Line No 10"-W23-902-5A 10-14-477-LS1 B4 89.12 Elbow-Long Seam VoVSurf RR-5 -

X -

.594* IGSCC A-1 CC N-524 10-14-477-LS2 B-J 89.12 Elbow-Long Seam VoVSurf RR-5 -

X -

.594* IGSCC A-1 CC N-524 10-14-477-LS3 B4 B9.12 Pipe-Long Seam VouSurf RR-5 -

X -

.594* IGSCC A-1.CC N-524 10-14-476 B4 B9.11 Pipe-Elbow VoVSurf -

X -

.594* IGSCC A 10-14-476-LS1 B-J E,9.12 Pipe-Long Seam VoUSurf RR-5 -

X -

.594* . ' SCC A-1, CC N-524 10-14-476-LS2 B-J 89.12 Elbow-Long Seam VoVSurf RR-5 -

X -

.594* IGSCC I,-1, CC N-524 10-14-476-LS3 B4 89.12 Elbow-Long Seam VoVSurf RR-5 -

X -

.594* IGSCC A-1, CC N-524 10-14-475 B-J 89.11 Elbow-Elbow VoVSurf - -

X .594* IGSCC A 10-14475-LS1 B4 B9.12 Elbow-Long Saam VoVSurf RR-5 - -

X .594* IGSCC A-1 CC N-524 10-14-475-LS2 B-J 89.12 Eibow-Long Seam VoUSurf RR-5 - -

X .594* IGSCC A-1, CC N-524 10-14-475-LS3 B-J 89.12 Elbow-Long Seam VoVSurf RR-5 - -

X .594* IGSCC A-1, CC N-524 10-14-475-LS4 B-J 89.12 Elbow-Long Seam VoUSurf RR-5 - -

X .594* IGSCC A-1, CC N-524 10-14-474 -B-J B9.11 Elbow-Pipe Vol/ Surf - - -

.594* IGSCC A 10-14-474-LS1 B-J 89.12 Elbow-Long Seam VoVSurf RR-5 - - -

.594* IGSCC A, CC N-524 10-14-474-LS2 B-J B9.12 Elbow-Long Searn VoUSurf RR-5 - - -

.594* IGSCC A-1, CC N-524 10-14-474-LS3 B-J 89.12 Pipe-Long Seam VoWurf RR-5 - - -

.594* IGSCC A-1 CC N-524 Fit.E: CSPLAN.14 Page 14 - 5 of 14 -11

v) 5 x._ /

I James A. Fitzpatrick Nuclear Power Plant [[::JAF-lSI-0003|JAF-lSI-0003]] t

N l g b Third Inservice Inspection Interval Ten -YearInspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS _

l 14 -Core Spray System Drawing Number: MSK-3022 Line No.10"-W23-902-5A 10-14-473 B-J 89.11 Pipe-Eibow Vol/ Surf - - -

594" IGSCC A 10-14-473-LS1 B-J 89.12 Pipe-Long deam Vol/ Surf RR-5 - - -

.594* IGSCC A-1, CC N-524 10-14-473-LS2 B-J 89.12 Elbow-Long Seam Vol/ Surf RR-5 - - -

.594" IGSCC A-1. CC N-524 l

10-14-473-LS3 B-J 89.12 Elbow-Long Seam Vol/ Surf RR-5 - - -

.594" IGSCC A-1, CC N-524 10-14-473A B-J 89.32 1" Branch Connection Surf - - - -

Exempt IWB-1220(a) i 10-14-472 B-J 89.11 Elbow-Pipe Vol/ Surf - - -

.594" IGSCC A 10-14-472-LS1 B-J B9.12 Elbow-Long Seam VoVSurf RR-5 - - -

.594* IGSCC A-1, CC N-524

. 10-14-472-LS2 B-J 89.12 Elbow-Long Seam Vol/ Surf RR-5 - - -

.594" IGSCC A-1. CC N-524 l

i 10-14-472-LS3 B-J 89.12 Pipe-Long Seam Vol/ Surf RR-5 X - -

.594* IGSCC A-1, CC N-524 10-14-471 B-J B9.11 Pipe-Safe End Vol/ Surf X - -

.594* IGSCC A. Terminal End 10-14-471-LS1 B-J 89.12 Pipe-Long Seam Vol/ Surf RR-5 X - -

.594* IGSCC A-1, CC N-524 NSA-SE B-F B5.10 Safe End-Nozzle VouSurf -

X -

.594" NUREG 0313 FILE: CSPLAN.14 Page 14 - 6 of 14 -11

s p

) \ j i James . itzpatrick Nuclear Powe6 Plant [[::JAF-ISI-0003|JAF-ISI-0003]] 4NewM M Third Inservice inspection Interval Date January 7,1998 Ten - Year inspection Plan Revision 0 l

! COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 14 - Core Spray System Drawing Number: MSK-3023 Line No.10"-W23-902-58 MOV-11B B-G-2 B7.70 Valve Botting VT-1 - - -

<2" Limited to valve selected under B-M-2 MOV-11B B-M-2 B12.50 Valve interior VT-3 - - - -

Only when disassembled limited to one valve in a group of valves.

10-14-870 B-J 89.11 Pipe-Va!ve MOV-11B Vo81 Surf - - -

.594*

10-14-871 B4 B9.32 3/C 83 ranch Connection Surf - - -

.594* Exempt IVB-1220(a) 10-14-872 B-J 89.32 3/4" B anch Connection Surf - - - - Exempt IWB-1220(a) 10-14-873 B-J 89.11 Elbow-Pipe Vot/ Surf - - -

.594*

14-58-AS-42 F-A F1.10c Variable Spring VT-3 RR-2 - - X .237" PFSK-1895. CC N-491-1 12-14-874 B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

.237" CC N-509 10-14-875 B-J 89.11 Pipe-Elbow Vol/ Surf - - -

.594*

10-14-876 B-J 89.11 Valve MOV-12B-Pipe Vol/ Surf - - -

.594" MOV-12B B-G-2 B7.70 Valve Botting VT-1 - - -

<2* Limited to valve selected under B-M-2 MOV-128 B-M-2 B12.50 Valve interior VT-3 - - - -

Only ywhen disassembled. limited to one valve in a group of valves.

10-14-512 B-J 89.11 Pipe-Velve MOV-128 Vol/ Surf - - -

.594*

10-14-512A B-J 89.11 Integral Fitting-Pipe Vot/ Surf - - -

.594*

20-14-512B B-J 89.11 Liner-Integral Fitting Vol/ Surf - - -

.8' FILE: CSPN 14 Page 14 - 7 of 14 -11

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

> New M h Third Inservice Inspection Interval Date January 7,1998

Ten - Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 TH1CK REMARKS

_... .s . -

14 -Core Spray System Drawing Number: MSK-3023 Line No.10"-W23-902-5B 10 '.4-512C B-J B9.11 Pipe-integral FitW Vol/ Surf - - -

.594* Inaccessible inside pen. X-168 10-14-5120 - -

Insulation Lt g N/A - -

.- - Inaccessible, inside Pen. X-168. No exam required 10-14-612E - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen. X-168, No exam required 10-14-512F - - insu!ation Lug N/A - - - -

fr sccessible,inside Pen X-168. No exam requied 10-14-512G - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen. X-16B, No exam required 10-14-512H - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen. X-168, No exam req:Ared 10-14-512J - -

Insulation Lug rd/A - - - -

Inaccessible, inside Pen. X-168. No exam required 10-14-512K - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen. X-168. No exam required 10-14-512L - -

Insulation Lug N/A - - - -

Inaccessibie, inside Pen. X-168, No exam rerguired 10-14-512M - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen. X-168, No exam required 10-14-512N - -

Insulation 1 ug N/A - - - -

Inaccessible. inside Per X-168. No exam required t

i FILE: C3 PLAN.14 Page 14 - 8 of 14 -11

,* ,m ,

(

i L) '.]'

James 'A.Fitzpatrick Nuclear Power Plant [[::JAF-lH-0003|JAF-lH-0003]] (G l g h Third Inservice inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISl!NTERVAL LTH OR CAT ITEM DESCR!PTION EXAM REQ PER1 PER2 PER3 THICK REMARKS aut 14 -Core Spray System Drawiag Number: MSK-3023 lane No.10"-W23-902-5B 10-14-512P - -

Insulation Lug N/A - - - -

Inaccessible, inside Pen. X-168, No exam required 10-14-5120 - -

Insulation Lug N/A - - - -

Inesible, insW Pen. X-168, No exam required 10-14-511A B-J 89.11 Pipe-Pipe Vol/ Surf - - -

.594*

10-14-511 B-J 89.11 Pipe-Pipe Vol/ Surf - - -

.594" 10-14-510A B-J B9.32 3/4" Branch Connection Surf - - - -

Exempt IWB-1220(a) 10-14-510 B-J 89.11 Elbow-Pipe Vol/ Surf - - -

.594*

10-14-509 B-J 89.11 Valves AOV-13B-Elbow Vol/ Surf - - -

.594*

AOV-138 B-G-2 87.70 Valve Botting VT-1 - - -

<2" Limited to va!ve selected unde; B-M-2 AOV-13B B-M-2 B12.50 Valve Interior VT-3 - - - -

Only when disassembled, limite i to one valve in a group of valves.

10-14-508 B-J B9.11 Pipe-Velve AOV-138 Vol/ Surf -

X -

.594*

10-14-507 B-J 89.11 Elbow-Pipe Vol/ Surf - - -

.594*

r 10-14-506 B-J 89.11 Pipe-Elbow Vot/ Surf X - -

594" 10-14-504 B-J 89.32 3/4" Branch Connection Surf - - - -

Exempt IWB-1220(a) 14-5B-HS-43 N/A N/A Hydraulic Snubber VT-3 RR-11 - - - -

PFSK-1133. TS Section 3.6.1 14-58-HS-44 N/A N/A Hydraulic Snutber VT-3 RR-11 - - - -

PFSX-1132. TS Section 3.6.1 FILE: CSPLAN.14 Page 14 - 9 of 14 -11

Am.,/ L/ s/

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] A (le 9York W

'~"""'

Third inservice inspection Interval Date January 7,1998 Ten - Year inspection Plan Revision 0 COMPONEMT ASME ASME ASME WELD IDENTIFICATlON CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRtPTION EXAM REO PER1 PER2 PER3 THfCK REMARKS 14 -Core Spray Syster,i Drawing Number: MSK-3023 Line No.10"-W23-902-5B 10-14-F03A B-J 89.11 Valve CSP-148-Pipe Vot/ Surf -

X -

.594* Valve stuo piece 10-14-503 B-J B9.11 Pipe-Pipe Vol/ Surf - - -

.594*

CSP-148 B-G-2 B7.70 Valve Bolting VT-1 - - -

<2" Limited to valve selec.ed under B-M-2.

CSP-148 B-M-2 312.50 Valve Interior VT-3 - - - -

Only when disassembled, limited to one va!ve in a group of valves.

10-14-502A B-J 89.i i Ptpe-Vaive C5P-14B Vol/ Surf - - -

.594* IGSCC .NUREG 0313 10-14-500 B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

.237" CC N-509 10-14-499 N/A N/A Insulation Lug N/A - - - -

No exam required 10-14-498A B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

"*75" CC N-509 10-14-494 B-F B5.130 Elbow-Pipe Vol/ Surf -

X -

.594* IGSCC A. Dimimilar Metal Weld 10-14-769 B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

.594" CC N-509 14-58-HS-45 N/A N/A Hydraulic Snubber VT-3 RR-11 - - -

.237" PFSK-5827. TS Section 3.6.1 7

10-14-768 B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

.571* CC N-509 14-58-AN-46 N/A N/A Hydraulic Snubber VT-3 RR-11 - - -

.375" PFSK-5826, TS Section 3.6.1 10-14-493A B-J 89.32 1" Branch Connection Surf - - -

Exempt IWB-1220(a) 10-14 493 8-J 89.11 Pipe-Elbow Vol/ Surf -

X .594* IGSCC A FILE: CSPLAN.14 Page 14 - 10 of 14 -11

a James hNitzpatrict. Nuclear Power PI nt [[::JAF-ISI-0003|JAF-ISI-0003]] v

M 15ew h Third Inservice inspection in4. val Date January 7,1998 Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION COCE CODE CODE REL A .NTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMAPWS 14 - Core ' ny System Drawir* .htmber: MSK-3023 -

Line No'.10**-W23-902-5B 10-14-492 B-J B9.11 Pipe-Pipe Vo'JSurf - -

X .594* IGSCC A. Terminal End N-58-SE B-F B5.10 Nozzle-Pipe Vol/ Surf - -

X .594* IGSCC A 1

t l

FILE: CSPLAN.14 Page 14 - 11 of 14-11 ,

O J mes A.9Itzpitrick Nucletr Power Ptsnt [[::JAF-ISI-0003|JAF-ISI-0003]] O

Third inservice inspection interval Date January 7,1998 g b Ten -Year inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME REL ISIINTERVAL LTH OR CODE CODE CODE REMARKS fDENTIFICATION DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK CAT ITEM f

23 - High Pressure Coolant injection Drawing Number: MSK-3024 Line No.10"-SHP-902-19A continued from MSK-3032 89.11 Reducer-Pipe Vol/ Surf - - -

.59C 10-23-658 B-J Vol/Sef - - - .594*

10-23-659 B-J 89.11 Pipe-E! bow Vol/ Surf - - .594" 89.11 Elbow-Pipe 10-23-660 B-J Surf RR-4 X - - .237" CC N-509 10-23-660A B-K-1 810.10 Integral Attachment !

RR-2 X .237" H23-76, CC N-491-1 VT-3 - -

23-19A-AN-1 F-A F1.10b Constraint Vol/ Surf - - - .594*

10-23-661 B-J 89.11 Pipe-Elbow 1 Surf RR-4 - - - .237" CC N-509 10-23-661C B-K-1 B10.10 Irdegral Attachment

.237" TS Section 3 S.1 l N/A Hydraulic Snubber VT-3 RR - -

23-19A-HS-2 N/A Surf - - - - Exempt IWB-1220(a) 10-2'*-661 A B-J 8922 1" Branch Connection Exempt IWB-1220(a)

Surf - - -

10-23-6618 B-J 89.32 1" Branch Connection Vol/ Surf - -

.594~

89.11 Elbow-Pipe 10-23-662 B-J Vol/ Surf - - - .594" 10-23-663 B-J 89.11 Pipe-Elbow Vol/ Surf X - -

.594" 10-23-664 B-J B9.11 Elbow-Pipe Sur' - - - - Exempt IWB-1220(a) 10-23-664A B-J 89.32 1.5" Branch Connection Vol/ Surf - X -

.594"

0-23-665 B-J B3.11 Pipe-Valve MOV-15 VT-3 - - - - Only when disassembled. Limited to one valve in a MOV-15 B-M-2 812.50 Vafve interior group of valvas VT-1 - - - <2* Limited to valve selected under B-M-2 MOV-15 B-G-2 B7.70 Vafve Bolting Page 23 - 1 of 23 - 5 P 1E HPCIPLAN.23.WPD

,- , ~ .

l ) ( )

James tzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] 4NewM h Thl:J Inservice Inspection Interval Date January 7,1998 Ten - Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMAltKS I

23 - High Pressure Coolant injection Drawing Number: MSK-3024 Line No.10"-SHP-902-19A, continued from MSK-3032 23-19A-HS-3 N/A N./A Hydrau!ic Snubber VT-3 RR - - -

H23-87. TS Section 3.6.1 l 23-19A-HS-4 N/A N/A Hydraulic Snubber VT-3 RR - - -

H23-88. TS Section 3.6.1 10-23-666 B4 B9.11 Valve MOV-15 Pipe Vol/ Surf - - -

.594*

10-23-667 B4 B9.11 Pipe-Elbow Vol/ Surf - - -

.594" 10-23-6G8 B4 B9.11 Elbow-Pipe Vol/ Surf - -

X .594" 10-23-668A B-K-1 B10.10 integral Attachment Surf RR 4 - - - -

CC N-509 23-19A-AN-5 F-A F1.10b Constraint VT-3 RR-2 - - -

.750" H23-77, CC N-491-1 10-23-669 B4 89.11 Pipe-Elbow Vol/ Surf - -

X .594*

10-23-670 B-J 89.11 Elbow-Pipe Vol/ Surf - - -

.594" 10-23-670P - -

Insulation Lug N/A - - - -

Inaccessible inside Pen. X-11, No exam required 10-23-670N - -

Insulation Lug N.'A - - - -

Inaccessible inside Pen. X-11, No excm required 10-23470M - -

Insulation Lug N/A - - - -

Inaccessible inside Pen. X-11, No exam required 10-23-670L - - insulation Lug N/A - - - -

Inaccessible inside Pen. X-11 No exam required 10-23-670K - -

Insulation Lug N/A - - - -

Inaccessible inside Pen. X-11 No exam required FILE: HPCIPLAN 23.WPD Page 23 - 2 of 23-S

k.~. V(. .

James A.'F;;2 patrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] O

d8> g%d'Pimer Third Inservice inspection Interval Date January 7,1998 4 Ten - Year Inspection Plan Revision 0 COMPONENT ASME ASME ASMC WELD IDEN18FICATION CODE CODE CODE REL IS! INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICK REMARKS 23 - High Pressure Coolant injechon Drawir J Number: MSK-3024 Line No.10"-SHP-902-19A, continued from MSK-3032 10-23-670J - - Insulation Lug N/A - - - - Inaccessible inside Pen. X-11. No exam required 10-23470H - - Insulation Lug N/A - - - - InaccessiNe insMe Pen. X-11, No exam required 10-23470G - -

Insulation Lug N/A - - - - Inaccessible inside Pen. X-i t No exam required 10-23-670F - -

Insulation Lug N/A - - - - Inaccessible inside Pen. X-11 No exam required 10-23-670E - -

Insulation Lug N/A - - - -

Inaccessible inside Pen. X-11. No exam reped 10-23-670D - -

Insulation Lug N/A - - - - Inaccessible insiae P~ v ii. No . m required 10-23-670C - -

Insulation Lug N/A - - - - Inaccessible inside Pen. X-11 No exc:n required 10-23-6708 B-J 89.11 Integral Fitting-Pipe Vol/ Surf - - - -

Inaccessible ina.ide Pen X-11 23-23-671 A B-J 89.11 Integral Fitting-Liner Vol/ Surf - - - -

10-23-671 B-J 89.11 Pipe-Integral Fitting Vol/ Surf - - - -

10-23472 B-J B9.11 Pipe-Valve MOV-16 Vol/ Surf - - -

.594*

MOV-16 B-M-2 B12.50 Valve Interior VT-3 - - - -

Only when disassembled, Limited to one valve in a gropp of valves MOV-16 B-G-2 B7.70 Valve Botting VT-1 - - -

<2" Limited to valve selected under B-M-2 Fit.E: HPCIPLAN 23 WPD Page 23 - 3 of 23-5

( ,)

I i Janes . Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] g R** Third Inservice Inspection Interval Ten - Year Inspection Plan -

Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT' ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS P

23 - High Pressure Coolant injection Drawing Number: MSK-3026 Line No.14".W25-902A-3A ,

MOV-19 B-M-2 B12.50 Vatve Interior VT-3 - - - -

Only v0en disassembled, Lirr.ited to one valve in a group of valves MOV-19 B-G-2 87.70 Valve Bolting VT-1 - - -

<2" Limited to vafve seladed under B-M-2 14-23-435 B-J 89.11 Valve MOV-19 -Pipe Vot/ Surf - - -

.933" 14-23-434A B-J B9.32 3/4" Branch Connection Surf - - - -

Exempt IWB-1220(a) 14-23-434 B-J B9.11 Valve HPI-18-Pipe Vol/ Surf - - - -

HPl.18 B-M-2 B12.50 Valve Interior VT-3 - - - -

Only when dessc-rrided. Limited to one valve in a group of valves HPI-18 B-G-2 B7.70 Valve Bolting VT-1 - - -

<2" Limited to valve selected under B-M-2 14-23-433 B-J B9.11 Pipe-Valve HPI-18 Vol/ Surf - - - .938" 14-23-433A B-J 89.32 3/4" Branch Connection Surf - - - -

Exempt IWB-1220(a) 14-23-432 B-J 89.11 Elbow-Pipe Vol/ Surf - - -

.938*

14-23-431 B-J 89.11 Pipe-Elbow Yot/ Surf - - -

.938' 23-3A-AN-21 F-A F1.10b Constraint VT-3 RR-2 - -

X - H2b50A, CC N-491-1 14-23-430 B-J B9.11 Elbow-Pipe Vol/ Surf X - -

.938*

14-23-429 B-J 89.11 Pipe-Elbow Val / Surf -

X -

.938" 14-23-428A B-K-1 B10.10 Integral Attachment Surf RR-4 - -

X .750" CC N-509 FILE: HPCIPLAN.23.WPD Page 23 - 4 of 23 - 5

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,-~

( l

%)

James A. Itzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] A New% kPomr Third Inservice inspection Interva: Date January 7,1998

Ten - Year inspection Plan Revision 0 COMPONt.NT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL IS' INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 TH!CM REMARKS 23 - High Pressure Coolant injection Drawing Number: MSK-3026 Une No.14"-W25-902A-3A 23-3A-Nti-20A F-A F1.40 Turbine Support Surf RR-2 - -

X - HP 23TU-2, CC N491-1 14-23-428 B-J 89 11 Tee-Pipe Vol/ Surf - -

X .938" i

i i

?

FILE- HPCIPLAN.23?PD Page 23 - S of 23 - 5

James . Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] 4 l) T M W Third Inserfice Inspection interval Date January 7,1598 Ten - Year Inspection Plan Revision 0 COMPONEN1 ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL IS14NTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 29 - Main Steam Drawing Number: MSK-3031 Line No. 24"-SHP-902-1 A from Reactor Vessel N-3A-SE B-J B9.11 Nozzle-Safe End Vol/ Surf X - -

1.21" 24-29-513 B-J B9.11 Safe End-Pipe Vo'fSurf X - - 1.21" Terminat End 24-29-513A B-J 89.32 2" Branch Connection Surf - - - -

Exempt IWB-1220(a) 24-29-514 B-J 89.11 Pipe-Elbow Vol/ Surf - - -

1.21" 24-29-515 B-J 89.11 Elbow-Pipe Vol/ Surf - - -

1.21*

24-29-516 8-J 89.11 Pipe-Pipe Vol/ Surf - - -

1.21" 24-29-518 N/A N/A Insulation Lug N/A - - - -

No exam required 24-29-519 B-J B9.11 Pipe-Pipe Vol/ Surf - - - 1.21" 29-1 A-AN-1B F-A F1.10b Vertical Support VT-3 RR-2 X - -

1.5" H29-1 CC N-491-1 24-29-519A B-K-1 B10.10 Integral Attac.hment Surf RR-4 - - -

1.5" CC N-509 24-29-520 N/A N/A Insulation Lug N/A - - - -

No exam required 29-1A-HS-2 N/A N/A Hydraulic Snubber VT-3 RR-11 - - -

.500" H29-128. TS Section 3.6.1 29-1A-HS-3 N/A N/A Hydraulic Snubber VT-3 RR-11 - - -

.500" H29'129 TS Secon 3.6.1 24-29-521 A L-K-1 B10.10 Integral Attachment Surf RR-4 - - - .500" CC N-509 24-29-521 B-J 89.11 Pipe-Elbow Vol/ Surf - - -

1.21" 24-29-522A B-K-1 010.10 Integral Attachment Surf RR-4 - - -

.750" CC N-509 29-1A-HS-4 N/A N/A Hydraulic Snubber VT-3 RR-11 - - -

.750" PFSK-1875. TS Section 3.6.1 e ILE: MSPLAN.29.WPD Page 29 -1 of 29 - 24

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l \. I James . Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] g" lye 9M M Third Inservice Inspection interval Date January 7,1998 Tea - Year inspection Plan Revision 0 l

-COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 29 - Main Steam Drav 9g Number: MSK-3031 Lip do. 24"-SHP-902-1 A from Reactor Vessel s

24-29-522 B-J 89.11 Elbow-Pipe Vol/ Surf - - -

1.21" 24-29-527A B-K-1 B10.10 Integ al Attachment Surf RR-4 - - -

.750" CC N-509 29-1A-AN-5 FA F1.10b Constraint VT-3 RR-2 X - -

.750" H29-2 CC N-491-1 24-29-523- B-J 89.31 6" Branch Connection Vol/ Surf X - - -

l l 24-29-527 B-J 89.11 Pipe-Pipe Vot/ Surf - - -

1.21" l 24-29-528 B-J 89.31 6" Branch Connection Vol/ Surf - - -

24-29-531 B-J 89.31 6" Branch Connection Vol/ Surf - - - -

i 24-29-5348 B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

.500* CC N-509 29-1 A-NS-6A N/A N/A Hydraulic Snubter VT-3 RR-11 - - -

.500" H29-136. TS Section 3.6.1 29-1A-NS-6B N/A N/A Hydr afic Snubber VT-3 RR-11 - - -

.500" H29-137. TS Section 3.6.1 24-29-534A B-K-1 B10.10 Integral Attachment Vol/ Surf RR-4 - - -

.750" CC N-509 29-1 A-AN-6 F-A F1.10b Vertical Support VT-3 RR-2 - - -

.750" H29-3 CC N-491-1 24-29-534 B-J B9.11 Pipe-Elbow Vol/ Surf 1.21" 24-29-536 B-J 89.11 Elbow-Pipe Vol/ Surf - - -

1.21 24-29-536A B-J 89.32 1" Branch Connection Surf - - - -

Exempt IWB-1220(a) 24-29-5368 B-J 89.32 1" Branch Connection Surf - - - -

Exempt IWB-1220(a) 24-29-536C B-J 89.32 1" Branch Connection Surf - - - -

Exempt IWB-1220(a)

FILE: MSPt.AN.29.WPD Page 29 - 2 of 29-24

U/ James . Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] V

M NewMPawer Third Inservic" Inspection Interval Date January 7,1998 l Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ P *R1 PER2 PER3 THICK REMARKS

29 - Main Steam i- Drawing Number: MSK-3031 l

Line No. 24"-SHP-902-1A from Reactor Vessel 24-29-5360 B-J 89.32 1" Branch Coanection Surf - - - -

Exempt IWB-1220(a) 24-29-538 B-J 89.11 Pipe-Elbow Vol/ Surf - - -

1.21" 24-29-538A - B-K-1 B10.10 Integra! Attachment Surf RR-4 - - -

.500" CC N-509 29-1A-AN-8 N/A N/A Hydraulic Snubber VT-3 RR-11 - - -

.500* PFSK-217. TS Section 3E.1

! 29-1A-HS-8A N/A N/A Hydraulic Snubber VT-3 RR-11 - - -

.500" PFSK-217. TS Section 34.1 24-29-539 B-J B9.11 Elbow-Pipe Vol/ Surf X - -

1.21" 29-1A-NS-9 F-A F1.10b Constraint VT-3 RR-2 - - -

1.0" PFSK-904. CC N-491-1 i

24-29-539A B-J 89.32 2" Branch Connection Surf - - - -

Exempt IWB-1220(a) l 24-29-539B B-K-1 B10.10 integral Attachment Surf RR-4 - - -

1.0" CC N-509 l

24-29-540 B-J 89.11 Pipe-Valve AOV-80A Vot/ Surf X - -

1.21"

?4-29-540A B-J 89.32 3/4" Branc.: Connection Surf - - -

Exempt IWB-1220(a)

AJ'-80A B-M-2 B12.50 Valve interior VT-3 - - - -

Only v%n disassembled, Limited to one va've in a group o. valves

( AOV-80A B-G-2 B7.70 Valve Botting VT-1 - - -

<2" Limited to valve selected under B-M-2 24-29-541 B-J 89.11 Valve AOV-80A-Pipe Vol/ Surf X - -

1.21" High Stress Weld 24-29-542-0 - -

Insulation Lug N/A - - - -

Inaccessible inside Pen X-7A, Mo exam required 24-29-542-P - -

Insulation Lug N/A - - - -

Inaccessible inside Pen X-7A, No exam required FILE: MSP1.AN 29.WPD Page 29 - 3 of 29 - 24

s

("/ James . Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] V

A flowMPower Third Inservice inspection Interval Date Jamsary 7,1998

Ten - Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTETNAL LTH OR CAT ITEC DESCRfPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS I

29 - Maia Steam Drawing Number- MSK-3031 Line No. 24"-SHP-9021 A from Reactor Vessel 24-29-542-N - -

Insulation Lug N/A - - - -

Inaccessible inside Pen X 'A, No exam required 24-29-542-M - -

Insulation Lug N/A - - - -

Inaccessible inside Pen X-7A, No exam required 24-29-5d2-L - -

Insulation Lug N/A - - - -

Inaccessible inside Pen X-7A, No exam required 24-29-542-K - -

Insulation Lug N/A - - - -

Inaccessible inside Pen X-7A. No exam required 24-29-542-J - -

Insulation Lug N/A - - - -

Inaccessible inside Pen X-7A, No exam required 24-29-542-H - -

Insulation Lug N/A - - - -

Inaccessible inside Pen X-7A, No exam required 24-29-542-G - -

Insulation Lug N/A - - - -

Inaccessible inside Pen X-7A. No exam required 24-29-542-F - -

Insulation Lug N/A - - - -

Inacceswbie inside Pen X-7A, No exam required 24-29-542-E - -

Insulation Lug N/A - - - -

Inaccessible inside Pen X-7A, No exam required 24-29-542-D - -

Insulation Lug N/A - - - -

Inacces.we inside Pen X-7A, No exam required 24-29-542-B B-J 89.11 Integral Fitting-Pipe Vol/ Surf - - - -

Inaccessible inside Pen X-7A 24-29-542C B-J B9.11 Liner-integral Fitting Vol/ Surf - - - -

24-29-542 B-J B9.11 Integral Fitting-Pipe Vol/ Surf - - -

1.21" 24-29-542A B-J 39.11 Pipe-Pipe Vol/ Surf - - -

1.21" 24-29-543 B-J 89.11 Pipe-Valve AOV-86A Vol/ Surf - - -

1.21" 24-29-543B B-J B9.32 1" Branch Connection Surf - - - -

Exempt IWB-1220(a)

AOV-86A B-M-2 B12.50 Valve interior VT-3 - - - -

Only when disassembled. Limited to one valve in a group of valves FILE MSPLAN 29.WPD Page 29 - 4 of 29 - 24

-- s U, James tzpatrick Nuclear Power Plant [[::JAF-ISI-0C03|JAF-ISI-0C03]] Os My b Third Inservico inspection Intery;.1 Date January 7,1393 Ten -YearInspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE- CODE REL ISIINTERVAL LTH CR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICK REMARKS f

29 - Main Steam Drawing Number: MSK-3031 i Line No. 24"-SHP-902-1 A from Reactor Vessel AOV-86A B-G-2 B7.70 Valve Bolting VT-1 - - -

<2" Limited to valve selected under B-M-2 I

I i

l l

l 7

FILE: MSPLAN 29.WPD Page ?4 - S of 29-24

__ ________m ___

D (

\

U Jrmes A. Fitzpatrick Nucle:r Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Date January 7,1598

.g b Third Inservice inspection Interval Ten -Year inspection Plan Revision 0 t

A ?'" WELD COMPONENT ASME ASME ISIINTERVAL LTH OR SDc REL (DENTIFICATlON CODE CODE REQ PER1 PER2 PER3 THfCK REMARKS CAT ITEM DESCRIPTION EXAM 29 - Main Steam Drawing Number: MSK-3031 Line No. 24"-SHP-902-1B from Reactor Vessel Vol/ Surf - X - 1.21" N-3B-SE B-J 89.11 Nozzle-Safe End Vol/ Surf - X - 1.21" Terminal End 24-29-544 B-J 89.11 Safe End-Pipe Vol/ Surf - - - 1.21*

24-29-545 B-J 89.11 Pipe-Elbow Vol/ Surf - 121' 24-29-546 B-J 89.11 Elbow-Pipe

-t- - 1.21" B-J 89.11 Pipe-Pipe Vol/ Surf - -

24-29-547 Vol/ Surf - - - 1.21" 24-29-547A B-J 89.11 Pipe-Pipe

- No exam required N/A - - -

24-29-548 N/A N/A Insulation Lug N/A - - - - No exam required 24-29-549 N/A N/A Insufation Lug RR-2 X 1.50" H29-4, CC N-491-1 F-A F1.10b Vertical Support VT-3 - -

29-18-AN-200 Surf RR-4 - - - 1.50" CC N-509 24-29-550A B-K-1 B10.10 Integra! Attachment Vof/ Surf - .- - 1.21" 24-29-550 B-J 89.11 Pipe-Pipe N/A - - - No exam required 24-29-551 N/A N/A Insulation Lug -

X 1.21" High' Stress We.!d Vol/ Surf - -

k 4-23-552 B-J 89.11 Pipe-Tee Vo# Surf X - 1.21" High Stress Weld 24-29-553 B-J B9.11 Tee-Pipe -

Vol/ Surf -

X - .625" 24-29-554 B-J 89.21 6" Branch Connection Surf RR-4 - - - .625" CC N-509 24-29-557A B-K-1 B1010 Integral Attachment VT-3 RR-2 X - .625* PFSK-4858. CC N-491-1 F1.10c vdable Spring 29-18-AN-13 F-A Page 29 - 6 cf 29-24 FILE: MSPLAN.29.WPD

O. O James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] O

Third Inservice Inspection Interva' Dde January 7,1998 A New M M Revisk r O Ten -YearI spection Plan ASME ASME WELD COMPONENT ASME LTH OR CODE CODE CODE REL ISIINTERVAL IDENTIFICATION REQ PER1 Pf'R2 PER3 TdW REu RMS CAT ITEM DE3CRfPTION EXAM t

29 - Main Steam i Drawing Number: MSK-3031 IJne ha. 24 -SHP-902-1B from ReactorVessel N/A Hydraulic Snubber VT-3 RR-11 - . - - .625' PFSK 4859. TS Secten 3.6.1 29-18-HS-13A N/A B9.11 Pipe-Pipe VoUSurf - X -

121* Hegh Stress WM 24-29-557 BJ B10.10 Integral Attachr9ent Surf RR-4 - - - .500" CC N-509 24-29-5578 B K-?

Hydraulic Snubber VT-3 RR-11 - - .500* H29-130 TS Secbon 3.6.1 24-1B-HS-11 N/A v4/A N/A N/A Hydraulic Snubber VT-3 RR-11 - - - .500" H29-131. TS Section 3.6.1 29-1B-HS-12 B-J B9.11 Pipe-Cap Vol/ Surf - - - 121" 24-29-558 Surf - - - - Exempt IWB-1220(a) 3-29-558A B-J 89.32 3" Branch Connection B9.11 Tee-Pipe VoVSurf - X - 1.21" High Stress WWd 24-29-559 B-J 24-29-560 B-J 89.31 6' Branch Cor nection VoUSurf - - - -

89.11 Pipe-Pipe VoVSurf - - - 121*

24-29-563 B-J B10.10 Integral A3achment SM RR-4 - - -

.750" CC N-509 24-29-563A B-K-1 VT-3 R42 .750" PFGK-138, CC N 491-1 29#1 AN-14 F-A F1.10c Variable Spring - - -

B-K-1 B10.10 Integral Attachment Surf RR-4 - - - 1.0" CC N-509 74 2'- '79 9 N/A N/A Hydraulic Snubber VT-3 RR-11 - - - 1.0" H29-139 TS Section 3.6.1 N/A N/A Hydraulic Snubber VT-3 RR-11 - - - 1.0" H29-138. TS Section 3.6.1 29-1B-hi 89.11 Pipe-Eitw VoVSurf - - - 1.21*

24-29-564 B-J 89.11 E'e-Pipe Vol/ Surf - - - 1.21" 24-29-566 B-J FILE MSPtAN 29 WPD Page 29 - 7 of 29 - 24

James Fitzpstrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third Inservice inspection interval Date January 7,1998 4 bMb Ten -Yearinspection Plan Revision 0 ASME ASME WELD COMPONENT ASME LTH OR CODE CODE REL IS! INTERVAL IDENTIFICATION CODE REMARKS CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 TH5CK m 29 - Main Steam Dr= wing Number: MSli-3031 Line No. 24"-SHP-902-1B from Reactor Vessel Surf - - - -

Exemot IWB-1220(a) 24-29-560A B-J B9.32 1" Branch Connection Surf - - - Exempt IWB-1220(a) 89.32 1 BranchConnection 24-29-5600 J Surf - - - Exempt 1%S f 220(a) 89.32 1" Branch Cor'nection 24-29-566C B-J Surf - - - - Exempt IVvB1220(a) 24-29-566D B-J 89.32 1* Branch Connection B-J B9.11 Pipe-Elbow Vol/ Surf - - -

121*

24-29-568 Surf RR-4 - - - .500* CC N-509 24-29-568A B-K-1 B10.10 Integral Attachment Hydraulic Gnubber r1 RR-11 - - - .500" PFSK-1876. TS Sechon 3.6.1 24-1B-HS-17 t#A N/A B-J 89.11 Elbow-Elbow Vot/ Surf - - -

121" 24-29-569 810.10 Integral Attachment Surf RR 4 - - -

.75* CC N-509 24-29-569A B-K-1 F1.10b Vertical Support VT-3 RR-2 - - - .75* H29-244. CC N491-1 29-18-AN-18A F-A 89.11 Eibow-Pipe Vol/Vol/ Serf - - -

121" 24-29-570 B-J 810.10 Integral Attachment Surf RR-4 - - -

1.0" CC N-509 l 24-29-5698 B-K-1 N/A Hydraulic Snubber VT-3 RR-11 - - -

1.0" PFSK-900. TS Section 3.6.1 29-1B-NS-18 N/A B-J 09.11 Pipe-Vatve AOV-800 Vol/ Surf - - -

121" 24-29-571 Vol/ Surf - - - - Exemp' IWB-1220(a) 24-29-571A B-J B9.32 3/4" Branch Connection VT-3 - - - - Only when disassembled. Limted to one valve in a AOV-808 B-M-2 B12.50 Valve Interior group of valves 87.70 Valve Bolting VT-1 - - -

<2" t.iri d to valve selected under B-M-2 AOV-808 B-G-2 FILE: MSPLAN 29%PD Page 29 - 3 of 29 -24

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James Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third Inservice inspection Interval Date January 7,1998 M 15ewYorkh Revision 0

Ten - Year inspection Plan ASME WELD COMPONENT ASME ASME LTH OR CODE CODE REL ISt rNTERVAL IDENTIFICATION CODE REMARKS CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 TNICK 29 - Main Steam Drawing Number: MSK-3031 Line No. 24'*-SHP-902-1B from Reactor Vessel B9.11 Pipe-Pipe Vot/ Surf -

X -

1.21" Ffgh Stress Weld 24-25-572 B-J 810.10 integral Attachment Surf RR-4 - - - 1.75" CC N-509 24-29-572A B-K-1 F1.10b Lateral Support VT-3 RR-2 - - - 1.75" PFSK-1868. CC N-491-1 29-18-NS-188 F-A N/A - - Inaccessible inside Pen X-78. No Suam requared 24-29-573-R - - Insulation Lug - -

Insulation Lug N/A - - - - Inaccessible inside Pen X-7B. No exam reW 24-29-573-P - -

Irnccessible inside Pen X-78. No exam required Insulation Lug N/A - - - -

24-29-573-N - -

Inaccessible inside Pen X-78. No exam required insulation Lug N/A - - - -

24-29-573-M - -

N/A - - Inaccessible inside Pen X-78. No exam requ: red 24-29-573-L - - inwfat.on Lug - -

N/A - - Inaccessible inside Pen X-78. No exam required Insufation Lug - -

24-29-573-K - -

N/A - Inaccessible inside Pen X-7B. No exam required Insulation Lug -

24-29-573-J - -

N/A - - - Inaccessible inside Pen X-78. No exam required 24-29-573-H - - Insulation Lug -

N/A - - Inaccessible inside Pen X-78. No exam required 24-29-573-G - - Insulation Lug - -

N/A - - I sible inside Pen X-78. No exam required 24-22-573-F - - Insulation Lug - -

l N/A - Inaccessible inside Pen X-78. No exam required Insulation Lug - - -

24-29-5,3-E - -

N/A Inaccessible inside Pen X-78. No exam required Insulation Lug - - -

24-29-573-D - -

89.11 Pipe-Integrat Fitting Vol/ Surf - - - - Inaccessible inside Pen. X-78 24-29-5738 B-J 24-29-573C B-J 89.11 Liner-Integral Fitting Vol/ Surf - - - -

FILE:MSPLAN 29 WPD Page 29 - 9 of 29 - 24

O 4 158*Mh e

James A. Fitzpatrick Nuclear Power Plant Third inservice Inspection Interval [[::JAF-ISI-0003|JAF-ISI-0003]] O

Date January 7,1998 Ten - Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THtCK REMARMS 29 - Main Steam Drawing Number: MSK-3031 Line No. 24"-SHP-902-1B from ReactorVessel 24-29-573 B-J 89.11 Integral Fitting-Pipe Vol/ Surf - - -

1.21*

24-29-57 % B-J 89.11 PipePipe Vol/ Surf -- - -

1.21*

24-29-574 B-J 89.11 Pipe-Valve AOV-868 Vol/ Surf - - -

1.21*

24-29-5748 B-J B9.32 1* Branch Connection Surf - - - -

Exempt IWB-1220(a)

AOV-868 B4,1-2 B12.50 Valve interior VT-3 - -- - -

Only when disassembled Limited to one valve in a group of vatves AOV-868 B-G-2 B7.70 Valve Boltog VT-1 - - -

<2" Limited to vatve selected under B-M-2 7

i FILE. MSPLAN.29.WPD Page 29 - 10 of 29 - 24

sj d James . Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] g MMW - - " - ' '

Third inservice inspection Interval Ten - Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PERT PER2 PER3 TH9CK REMARKS 9

29 - Main Steam Drawing Number: MSK-3032 Line No. 24*-SHP-902-1C from Reactor Vessel N-3C-SE B-J 89.11 Nozzle-Safe End Vol/ Surf -- -

X 1.21*

24-29-575 B-J B9.11 Safe End-PW Vol/ Surf - -

X 1.21* Terminal End 24-29-576 B-J 89.11 Pipe-Elbow Vol/ Surf - - -

121*

24-29-577 B-J B9.11 Elbow-Pipe Vol/ Surf - - -

121*

24-29-5858 B-K-1 810.10 Integral Attachment Surf RR-4 - - -

.625" CC N-509 29-1C-AN 23A F-A F1.10b Vertical Support VT-3 RR-2 - - -

.750* CC N-491-1 24-29-578 B-J 89.11 Pipe-Pipe Vol/ Surf - - -

1.21-24-29-581 B-J B9.11 Pipe-Pipe Vol/ Surf - - -

1.21*

24-29-581A B-J 89.11 Pipe-Pipe Vol/ Surf - - -

121-24-29-579 N/A N/A Insulation Lug N/A - - - -

No exam required i 24-29-530 N/A N/A Insulation Lug N/A - - - -

No exam required 24-29-582 N/A N/A fnsulation Lug N/A - - - -

No exam required 24-29-583 B-J B9.11 Pipe-Tee Vol/ Surf - - X 1.21" Hh Stress Weld 24-29-584 B-J 89.11 Tee-Pipe Vol/ Surf - - X 121" High Stress Weld 24-29-585 B-J 89.31 6* Branch Connection Vol/ Surf - -

X .625*

24-29-585A B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

.750" CC N-509 24-29-58G8 B-J 89.31 6 Branch Connection Vol/ Surf - - - -

FILE:MSPLAN 29.WPD Page 29 - 11 of 29 - 24

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%J James A. Fitzpatrick Nuclear Power Plant JAFMJ N 3 Third inservice inspection Interval

$ '98FMW--~~"'

Ten -Year inspection Plan DG A .

7,1998 W, 'A E COMPONENT ASME ASME ASME WELD IDENTIFICATION ' CODE CODE CODE REL IS!8NTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICd REMARKS

. sms%wy mv en e

29 - Main Steam Drawing Number: MSK-3032 Line No. 24"-SHP-902-1C from Reador Vessel 291C-HS-238 t#A f#A Hydraufe Snutber VT-3 RR-11 - - -

.625" PFSK-4859. TS Secbon 3.6.1 29-1C-AN-23 F-A F1.10e Variable Spring Hanger VT-3 RR-2 - - -

.625" PFSK-4858, CC N-491-1 2 "e29-588A B-K-1 810.10 Integral Attachment Surf RR-4 - - -

.500* CC N-509 29-1C-HS-21 N/A N/A Hydraulic Snubber VT-3 RR-11 - - - .500" H29-134. TS Sechon 3.6.1 29-1C-HS-22 N/A N/A Hydrauric Snubber VT-3 RR-11 - - -

.500* H29-135.TS Section 3.6.1 24-29-588 B-J 89.11 Pipe-Reducer Vol/ Surf - -

X 1.21" High Stress Weld 24-29-589 B-J 89.11 Tee-Pipe Vot/ Surf - - X 1.21" High Stress Weid 2* 29-590 B-J 89.31 6" Branch Connecan.

Vol/ Surf - - - -

24-29-593 B-J 89.11 Pipe-Pipe Vol/ Surf - - -

121*

24-29-593A B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

1.0" CC N-509 24-29-594 B-J 89.31 6" Branch Connection Vot/ Surf - - - -

24-29-597 B-J 89.11 Pipe-Elbow Vol/ Serf - - -

1.21" 2429-598 B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

.750" CC 5-509 29-1C-AN-25A F-A F1.10c Variable Spring Hanger VT-3 RR-2 - - -

.750" PFSK-139, CC N-491-1 24-29-599 B-J B9.11 Elbow-Pipe Vol/Sarf - - -

1.21" 24-29-599A B-J 89.32 1" Branch Connection Surf - - - -

Exempt rWB-1220(a) 24-29-5998 9J 89.32 1" Branch Connection Surf - - - -

Exempt rAB-1220(a)

FitE MSPLAN 29 WPD Page 29 -) of 29 - 24

s

/

James . Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] v

M bMb Third Inservice inspection Interval Date January 7,1998 Ten - Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICK REMARKS 29 - Main Steam Drawing Number: MSK-3032 I.ine No. 24"-SHP-902-1C frorn Reactor Vessel 24-29-599C B-J 89.32 1" Branch Connection Surf - - - -

Exempt IWB-1220(a) 2$29-599D B-J 89.32 1" Branch Connection Surf - - - -

Exempt IWB-1220(a) 2 >29-601 B-J 89.11 Pipe-Elbow Val / Surf i- - -

121-2429-601A B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

.500* CC N-509 2?1C-HS-26 N/A N/A Hydraulic Snubber VT-3 RR-11 - - -

.500* H29-249. TS Section 3.6.1 24-29-602 B-J 89.11 Elbow-Eltm Vol/ Surf - - -

1.21-24-29-603 8-J E9.11 tElbow-Pipe Vol/ Surf - - -

1.21-24-29402A B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

.75* CC N-509 29-1C-AN-28 F-A F1.10b Vertical Support VT-3 RR-2 - - -

.75- H29-245. CC N-491-1 24-29-603B B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

1.0" CC N-509 29-1C-AS-29 F-A F1.10b Lateral Support VT-3 RR-2 - - -

1.0" PFSK-898, CC N-491-1 r 24-29-604 B-J 89.11 Pipe-Valve AOV-80C Vol/ Surf - - -

1.21' 24-29-605A B-J 89.32. 2" Branch Connection Surf - - - - Exer'npt IWB-1220(a)

AOV-80C B-M-2 B12.50 Valve Interior VT-3 - - - -

Only when disassembled. Limited to one valve in a group of valves AOV-80C B-G-2 87.70 Vafve Botting VT-1 - - -

<2- Limited to vatve selected under B-M-2 24-29-605 B-J 89.11 Valve AOV-80C-Pipe Vol/ Surf - -

X 121- Heh Stress Weld 24-29-605B B-K-1 810.10 Integral Attachment Surf RR-4 - - -

1.75' CC N-509 FILE- MSPLAN 29.WPD Page 29 -13 of 29 - 24

( ) (, -)

v v James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] 4 bMb Third Inservice inspection Inte vah Isate January 7.1998 Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD EDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRtPTION EXA M REO PER1 PER2 PER3 TH3CK REMARKS 29 - Main Steam Drawing NumSer- MSK-3032 Line No. 24"-SHP-902-1C from Reacter Vessel 29-1C-NS-30 F-A F1.10b Lateral Support VT-3 RR-2 - -

X 1.75" PFSK-1868, CC N-491-1 24-29406-Q - -

Insulaton Lug N/A - - - -

Inaccessib8e inside Pen X-7C, No ?xam required 24-29-606-P - -

Insulation Lug N/A - - - -

Inaccessible inside Pen X-7C, No exam regured 24-29-606-N - -

Insulation Lug N/A - - - -

Inaccessible inside Pen X-7C, No exam requred 24-29-606-M - -

Insulation lug N/A - - - -

Inaccessible inside Pen X-7C, No exam requred 2429-606-L - -

insulation Lug N/A - - - -

Inaccessible inside Pen X-7C. No exam requred 24-29-606-K - -

Insulation Lug N/A - - - -

Inaccessible inside Pen X-7C. No exam required 24-29-606-J - -

Insulation Lug N/A - - - -

Inaccessible inside Pen X-7C, No exam required 24-29-606-H - -

Insulation Lug N/A - - - -

Inaccessible inside Pen X-7C. No exam required 24-29406-G - - Insulatton Lug N/A - - - -

Inaccessible inside Pm X-7C, No exam regured 24-29-60G-F - -

Insulation Lug N/A - - - -

Inaccessible inside Pen X-7C, No exam required 24-29406-E - -

Insulation Lug N/A - - - -

Inaccessible inside Pen X-7C, No exam required 24-29-606-D - -

Insulation Lug N/A - - - - Inacbess,ble inside Pen X-7C. No exam required 24-29-606B B-J B9.11 Pipe-In'?gral Fitting Vol/ Surf - - - - Inaccessible, inside Pen. X-7C 2429-606C B-J 89.11 Liner-Integral Fitting Vol/ Surf - - - -

24-29-606 B-J 89.11 Integral Fitting-Pipe Vol/ Surf . - -

121" 24-29 407 B-J 89.11 Pipe-Valve AOV-86C Vol/ Surf - - -

121" FILE- MSPLAN 29 WPD Page 29 - 14 of 29 - 24

(mv)

James Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] b

$ Third Inservice Inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTER'JAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THtCK REMARMS S

29 - Main Steam Drawing Number: M3K-3032 Line No. 24"-SHP-902-1C from Reactor Vessel 24-29-607D B-J 89 32 1* Branch Ceinechon Surf - - - - Exempt IWB-1220(a)

AOV-86C B-M-2 B12.50 Vafve Interior VT-3 - - - -

Only when disassembled, Limited to one valve in a group of valves AOV-86C B-G-2 B7.70 Valve Bolting VT-1 - - -

<2- t imited to valve selected under B-M-2 29-1C-HS-24 N/A N/A Hydraulic Snubber VT-3 RR-11 - - -

1.0" H29-140. TS Sechon 3.6.1 29-1C-HS-25 N/A N/A Hydraurc Snubber VT-3 RR-11 - - -

1.0* H29-141. TS Section 3.6.1 I

i t

FILE: MSPLAN 29.WPD Page 29 -15 of 29 -24

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James A. Fitzpatrick Nuclear Power Plant

\d [[::JAF-ISI-0003|JAF-ISI-0003]] g Idow h Third Inservice inspection Interval Date January 7,1998 Ten - Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 TMCK REMARKS 29 - Main Steam Drawing Number- MSK-3032 Line No. 24*-SHP-902-1D from Reactor Vessel N-3D-SE B-J 89.11 Nozzle-Safe End Vol/ Surf X - -

1.21*

24-29-608 B-J B9.11 Safe End-Pipe Vol/ Surf X - -

121" Termmal End 24-29-609 B-J B9.11 Pir.e-Elbow Vol/ Surf - - -

121" 24-29-610 B-J 89.11 Elbow-Pipe Vol/ Surf - - -

121*

24-29-610A B-K-1 810.10 Integral Attachment Surf RR-4 X - -

1.50" CC N-509 29-1D-AN-33 F-A F1.10b Vertical Support VT-3 RR-2 X - -

.750" H29-23, CC N-491-1 24-29-611 B-J B9.11 Pipe-Pipe Vol/ Surf - - -

1.21*

24-29-612 N/A N/A Insulation Lug N/A - - - -

No exam required 24-29-613 B-J B9.11 Pipe-Pipe Vol/ Surf - - -

1.21" 24-29-614 N/A N/A Insulation Lug N/A - - - - No exam required 24-29-615 N/A N/A Insu!ation Lug N/A - - - -

No exam regurred 24-29416 B-J 89 11 Pipe-Elbow Vol/ Surf - - -

121" 24-29-616A B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

.500" CC f4-509 29-1D-HS-34 N/A N/A Hydraulic Snubber VT-3 RR-11 - - -

.500" H29-132. TS Section 3.6.1 29-1D-HS-35 N/A N/A Hydraulic Snubber VT-3 RR-11 - - -

.500" H29-133. TS Section 3.6.1 24-29-617 B-J B9.11 Elbow-Pipe Vol/ Surf - - -

121*

24-29-617A B-K-1 810.10 Integral Attachment Surf RR-4 - - -

.750" CC N-509 FILE MSPLAN29V/PD Page 29 - 16 of 29 -24

, (.

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(_ / \ /

James Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

h

$ Third Inservice inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICAT10N CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 29 - Main Steam Drawing Number: MSK-3032 Line No. 24*-SHP-902-1D from ReacPs Vessel 241D-HS-36 N/A N/A Hydraulic Srubber VT-3 RR-11 - - -

.750" FFSK-1880. TS Secten 3.6.1 24-29418 B-J 89.31 6" Branch Connection VcuSurf X - - -

4-29-618A B-K-1 810.10 Integral Attachment Surf RR-4 -

X -

.750* CC N-509 29-1D-AN-338 F-A F1.10b Vertical Support VT-3 RR-2 -

X -

.750" H29-8. CC N-491-1 24-29422 B-J 89.31 6" Branch Connection Vol/ Surf - - - -

24-29-625 B-J 89.11 Pipe-Pipe Vol/ Surf - - -

1.21" 24-29-626 B-J B9.31 6" Branch Connection Vol/ Surf - - - -

24-29-625C B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

.500* CC N-509 29-1D-HS-39 N/A N/A Hydraulic Snubber VT-3 RR-11 - - -

.500* H29-143. TS Sectron 3.6.1 29-1D-HS-40 N/A N/A Hydrau?ic Snubber VT-3 RR-11 - - -

.500" PFSK-234. TS Secten 3.61 24-29-625A B-K-1 B10.10 Integral Attachment Surf RR-4 - - X .75" CC N-509 29-1D-AN-40A F-A F1.10b Vertical Support VT-3 RR-2 - -

X .75" CC N-491-1 24-29429 B-J 89.11 Pipe-Elbow Vol/ Surf - - -

1.21" 24-29-631 B-J B9.11 Elbow-Pipe Vol/ Surf - - -

1.21" 24-29-631A B-J 89.32 1" Branch Connection Surf - - - -

Exempt IVB-1220(a) 24-29-6318 B-J 89.32 1" Branch Connection Surf - - - -

Exempt IWB-1220(a) '

24-29-631C BJ B9.32 1" Branch Connection Surf - - - - Exempt IWB-1220(a)

FILE: MSPLAN.29 WPD Page 29 - 17 of 29 - 24 f

. ._. [

O Q ,/ Q ,J James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] g h Third inservice inspection Interval Ten-Yearinspectior P!an Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL IS: INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PERT PER2 PER3 THICK REMARKS 29 - Main Steam Drawing Number- MSK-3032 Line No. 24*-SHP-902-1D from Reactor Vessel 24-29-631D B4 B9.32 1* Branch Connechon Surf - - - - Exempt RAS-1220(a) 24-29-633 B-J B9.11 Prpe-Elbow VctSurf - - -

121*

24 29-633A B-K-1 B10.10 Integral A tachment Surf RR-4 - - -

.750" CC N-509 24-1D-HS-41 N/A N/A Hydraulic Snubber VT-3 RR-11 - - -

.750" H29-250. TS SecSon 3.6.1 29-1D-AN-42 F-A F1.10b Vertical Support VT-3 RR-2 - - -

750* H29-246 CC N491-1 24-29-634 B-J B9.11 Elbow-Pipe Vol/ Surf - X - 121*

24-29-634A B-J 89.32 2* Branch Connection Surf - - - - Exempt IWB-1220(a) 24-29-634C B-K-1 B10.10 Integra Attachment Surf RR-4 - - -

1.0" CC N-509 29-1D-NS-44 F-A F1.10b Lateral Support VT-3 RR-2 - - -

1.0" PFSK-902. CC N-491-1 24-29-635 B-J 89.11 Pipe-Valve AOV-80D Vol/ Surf - X. -

1.21" 24-29-635A B-J B9.32 2 Branch Co mechon Surf - - - -

Sempt IWB-1220(a)

AOV-800 B-M-2 B12.50 Valve Interior VT-3 - - - -

Only when disassembled, Limited to one valve in a group of valves AOV-800 B-G-2 B7.70 Valve Bottrng VT-1 - - -

<2" Limited to valve selected under B-M-2 2#,-29-636 B-J B9.11 Valve AOV-800-Pipe Vol/ Surf - -

X 121* H;gh Stress Weld 24-29437-O - - Insulation Lug N/A - - - - Inaccessible inside Pen X-7D, No exam required 24-29-637-P - - Insulation Lug N/A - - - - Inaccessible inside Pen X-7D. No exam required 2429-637-N - -

Insulation Lug N/A - - - - Inaccessible inside Pen X-7D, No exam required FILE- MSPLAN29%VD Page 29 - 18 of 29 -24

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] A NouvYork h Third Inservico Inspection Interval Date January 7,1998 Ten - Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL IS! INTERVAL LTH OR CAT ITEM DESCR!PTION EXAM REQ PER1 PER2 PER3 THtCK REMARKS 29 - Main Steam Drawing Number: MSK-3032 Line No. 24 -SHP-902-1D from Reactor Vessel 24-29-637-M - -

Insulation Lug N/A - - - - Inaccessable inside Pen X-7D. No exam required 2%29437-L - -

Insulation Lug N/A - - - - k cewssible inside Pen X-7D. No exam requked 24-29-637-K - -

Insulation Lug N/A - - - - 3 mssible inside Pen X-70. No exam required 2 %29-637-J - - Insulation Lug N/A - - - -

Inacmssible inside Pen X-7D. No exam required 24-29-637-H - -

Insulation L sg N/A - -- - - Inaccessible inside Pen X-7D. No exam requwed 24-29-637-G - -

Insulation Lug N/A - - - -

Inaccessible inside Pen X-7D. No exam requwed 2429-637-F - - Insulation Lug N/A - - - -

Inaccessible inside Pen X-70. No exam required 24-29-637-E - -

Insulation Lug N/A - - - - Inaccessib!e inside Pen X-7D. No exam required 24-29-637-D - -

Insulation Lug N/A - - - -

Inaccessibb inside Pen X-7D. No exam required 24-29-6378 B-J 89.11 Pipe-integral Fitting Vol/ Surf - - - -

Inaccessible inside Pen. X-7D 37-29-637C B-J 89.11 Liner-integral Fitting Vol/ Surf - - - -

24-29-637 B-J 89.11 Integral Fitting-Pipe Vol/ Surf - - -

1.21" r

24-29-638 B-J 89.11 Pipe-Valve AOV-86D Vol/ Surf - - -

1.21*

24-29-638D B-J B9.32 1* Branch Connedion Surf - - - -

Exempt IW3-1220(a)

AOV-86D B-M-2 812.50 Vafve Interior VT-3 - - - -

Only when disassembled. Limited to one valve in a group of valves AOV-86D B-G-2 B7.70 Vafve Bo!!ing VT-1 - - -

<2" Limited to valve selected under B-M-2 FILE: MSPLAN.29 WPD Page 29 - 19 of 29 - 24

s James A. Fitzpatric' Nuclear Power Plant [[::JAF-ISt-0003|JAF-ISt-0003]] b

$ Third Inservice inspection Interval Ten -Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME k WELD IDENTIFICATION CODE CODE CODE REL ISIINTCtVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PERT PEM2 PER3 THfCK REMARMS 29 - Main Steam I Drawing Number: MSK-3032 Une No. 24"-SHP-902-1D from Reactor Vessel 29-1D-AN-33A F-A F1.10b Vertical Support VT-3 RR-2 - - -

1.50" H29-7, CC N-491-1 l

I r

1 FILE- MSPLAN.29.WPD Page 29 - 20 of 29 -24

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'LJ Jarnes A. Fitzpatrick Nuclear Power Plant [[::JAF-4SI-0003|JAF-4SI-0003]] M IU888Mb Third Inservice inspection interni Date January 7,1998

& AsphorW Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRfPTION EXAM REQ PER1 PER2 PER3 THtCK REMARKS t

29 - Main Steam Drawing Number- MSK-3011 Line No. 6"-SHP-902-5N 6-29-532 B-J 89.11 Pipe-Pipe Vot/ Surf y - -

.432*

6-29-533 B-J 89.11 Pipe-Flange Vot/ Surf X - -

432" Flange N B-G-2 B7.50 Flange Botting VT-1 X - -

<2" Limited to wivcna as selected under B-J 02RV-718 B-M-2 B12.50 Safety Relief Valve VT-3 - - - -

On!y when disassembled Line No. 6"-SHP-902-5P 6-29-529 B-J 89.11 Pipe-Pipe Vol/ Surf - - -

432" 6-29-530 B-J 89.11 Pipe-Flange Vol/ Surf - - - .432" Flange P B-G-2 B7.50 Flange Bottrng VT-1 - - -

<2" Limited to wiW =4s selected under B-J 02RV-71A B-M-2 B12.50 Safety Relief Valve VT-3 - - - - Only when disassembled Line No. 6"-SHP-902-5X 6-29-524 B-J 89.11 Pipe-Pipe Vol/ Surf - - -

.432" 6-29-525 B-J 89.11 Pipe-Flange Vol/ Surf - - -

.432*

Flange X B-G-2 B7.50 Flange Botting VT-1 - - -

<2" LimrIed to wivvients selected under B-J 02RV-71K B-M-2 B12.50 Safety Relief Valve VT-3 - - - - On8y when disassembled Line No. 6"-SHP-902-SV 6-29-561 B-J B9.11 Pipe-Pipe Vol/ Surf - X -

.432" 6-29-562 B-J 89.11 Pipe-Flange Vot/ Surf -

X -

.432" Flange V B-G-2 B7.50 Flange Botting VT-1 - X -

<2* Lirruted to wivv *-its selected uW B-J FILE: FASPLAN 29 WPD Page 29 - 21 of 29 -24

, n James A. Fitzpatrick Nuclear Power P!snt [[::JAF-ISI-0003|JAF-ISI-0003]] gb h Third Inservice inspection Interval Date January 7,1998 Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISi tMTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THtCK REMARKS 29 - Main Steam Drawing Number: MSK-3031 Une No. 6"-SHP-902-SV 02RV-71D B-M-2 B12.50 Safety Retief Valve VT-3 - - - -

Only when disassembled Une No. 6"-SHP.902-5U 6-29-555 B-J 89.11 Pipe-F:pe Vol/ Surf - - -

.432" 6-29-556 B-J 89.11 Pipe-Flange Vol/ Surf - - -

432" Flange U B-G-2 B7.50 Flange Botting VT-1 - - -

<2* Umited to wr4+ e as selected under B-J 02RV-71C B-M-2 812.50 Safety Relief Vafve VT-3 - - - -

Only when disassembled Une No. 6"-SHP-902-5 6-29-586 8-J 89.11 P:pe-Pipe Vol/Surt - - X 432" 6-29-587 B-J 89.11 Pipe-Flange VoVSurf - -

X .432" Flange 5 B-G-2 B7.50 Flange Botting VT-1 - -

X <2" Limited to wam ds selected under B-J 02RV-71E B-M-2 B12.50 Safety Relief Valve VT-3 - - - -

Only when disassembled Une No. 6"-SHP-902-SS 6-29-591 B-J 89.11 Pipe-Pipe Vol/ Surf - - -

.432" 6-29-592 B-J 89 11 Pipe-Flange Vol/ Surf - -

432" Flange S B-G-2 B7.50 Flange Botting VT-1 - - - <2- Umsted to components selected under E-J 02RV-71G B-M-2 812.50 Safety Relief Valve VT-3 - - - -

Only when disassembled FILE MSPLAN.29.WPO Page 29 - 22 of 29 - 24 i

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%J \ .J QJ James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] 4 MMM Third Inservice Inspection interval Date January 7,1998 Ten - Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME wm IDENTIFICATION CODE CODE CODE REL ISilNTERVAL t.TH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 29 - Main Steam Drawing Number- MSK-3032 Line No. 6"-SHP-902-ST 6-29-595 B-J 89.11 Pipe-Pipe VoVSurf - - -

.432" 6-29-596 B-J 89.11 Prpe-Flange VouSurf - - -

432*

Flange T B-G-2 B7.50 Flange Botting VT-1 - - -

<2* Limrted to w.w e 45 selected under B-J 02RV-71F B-M-2 B12.50 Safety Reitef Valve VT-3 - - - -

Only when disassembled Line No. 6"-SHP-902-5R 6-29-623 B-J 89.11 Pipe-Pipe VoVSurf - - -

432*

6-29-624 B-J 89 11 Pipe-Flange VoVSurf - - -

432" Flange R B-G-2 B7.50 Flange Boning VT-1 - - - <2* Limded to w @ e 45 selected under B-J G2RV-71J B-M-2 512.50 Safety Relief Vafve VT-3 - - - -

Only wher' disassembled Line No. 6"-SHP-902-5W 6-29-627 B-J 89.11 Pipe-Pipe VouSurf - - -

.432" 6-29-628 B-J B9.11 Pipe-Flange VouSurf - - -

432" Flange W B-G-2 87.50 Flange Bolting VT-1 - - -

<2" Lirrded to w% m 4. seleded unde B-J 02RV-71L B-M-2 B12.50 Safety Relief Valve VT-3 - - - -

Only when disassembled FILE:MSPLAN.29 WPD Page 29 - 23 of 29 - 24

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] M bMM Third Inservice Inspection Interval Date January 7,1998 Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME VVELL IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICM REMARKS 4

29 - Main Steam Drawing Number: MSK-3032 Line No. 6"-SHP-902-5Q 6-29-619 B-J 89.11 Pipe-Pipe VoVSurf - - -

.432-6-29-620 B-J 89.11 Pipe-F:ange Vo:/ Surf - - -

432-Flange Q B-G-2 87.50 Flange Botting VT-1 - - -

<2" Limited to wiw eas selected under B-J ,

02RV-71H B-M-2 B12.50 Safety Renef Valve VT-3 - - - - Only when disassembled l

I t

FILE MSPLAN 29 WPD Page 29 - 24 of 29 -24

7 i < i i G \

James Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] ')

b

$ Third inservice Inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 34 - Feedwater System Drawing Number: MSK-3033 Line No.12"-WFP-902A-5C to Reactor Vessef N-4A-SE B-J B9.11 Nozzie-Safe End Vol/ Surf - - - .844*

12-34-363 B-J B9.11 Safe End-Pipe Vol/ Surf - - X .844' Tenmnal End 12-34-364 B-J 89.11 Pipe-Elbow Vol/ Surf - - -

.844' 12-34-365 B-J 89.11 Elbow-Pipe Vo!/ Surf - - -

.844*

12-34-939 B-K-1 810.10 Integral Attachment Surf RR-4 X - -

1.5" CC N-509 34-5C-AN-3 F-A F1.10c Variable Spring Hanger VT-3 RR-2 X - - 1.5" PFSK-1025. CC N-491-1 12-34-36S B-J 89.11 Pipe-Elbow VoLSurf - - -

.844*

12-34-367 B-J 89.11 Elbow-Pipe Vol/ Surf - - -

.844*

12-34-368 B-J 89.11 Pipe-Elbow Vol/ Surf X - - .844* High Stress Weld 12-34-369 B-J 89.11 Elbow-Elbow Vot/ Surf X - -

.844* High Stress Weld 12-34-940 B-K-1 810.10 Integrat Attachment Surf RR-4 - - -

.500* CC N-509 34-SC-HS-6 N/A N/A Hydraulic Snubber VT-3 RR-11 - - -

.500* H34-117. TS Sechon 3.6.1 34-SC-HS-7 N/A N/A Hydraulic Snubber VT-3 RR-11 - - -

.500* H34 I18. TS Section 3 6.1 12-34-370 B-J 89.11 Elbow-Pipe Vol/ Surf - X -

.844* High Stress Weld 12-34-371 B-J 89.11 Pipe-Pipe Vol/ Surf -

X -

.844* High Stress Weld 12-34-933 B-K-1 810.10 Integral Attachment Surf RR-4 - - -

.500*

34-5C-AN-8 F-A F1.10b Constraint VT-3 RR-2 - - -

.500* H34-106. CC N- 491-1 FILE: FWPLAN.34WPD Page 34 - 1 of 34 -12

r~h rm m James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] b Date January 7,1998

$ Third Inservice Inspection Interval Ten -Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CCDE CODE REL IS1 INTERVAL LTH OR CAT ITEM DESCRWTIO** EXAM REQ PER1 PER2 PER1 THICK REMARM') .

34 - Feedwater System Drawing Number: MSK-3033 Line No.12"-WFP-902A-SC to Reactor Vessel 12-34-934 B-K-1 B10.10 Integral Attachment Surl RR-4 - - - .500- CO N-509 34-5C-AN-9 F-A F1.10b Constraint VT 3 RR-2 - - - .500" H34-107. CC N-491-1 12-34-935 B-K-1 B10.10 Integral Attachment Surf RR-4 - - - .500- CC N-509 J4-5C-AN-10 7-A F1.10b Constraint VT-3 RR-2 - - - .500* H34-103, CC N-491-1 12-34-372 B-J 39.11 Pipe-Pipe Vol/ Surf - Y - 644- High Stress Weld 12-34-373 B-J 89.11 Pipe-Reducer Vot/ Surf -

- 844- High Stress Weld i

FILE: FWPLAN.34 WPD Page 34 - 2 of 34 -12 j

,m ,

N James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h

$ Third Inservice inspection interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICK REMARKS Feedwater System Drawing Number: MSK-3033 Une No.12-WFP-902A-5A to heactor Vessel N-4B-SE B-J B9.11 Nozzle-Safe End Vol/ Surf RR-7 - - X .844' 12-34-375 B-J 89.11 Safe End-Pipe Vol/ Surf - -

X .844* High Stress Weld, Termina! End 12-34-376 B-J 89.11 Pipe-Elbow VouSurf - - - .844' 12-34-377 B-J 89.11 Elbow-Pipe Vot/ Surf - - -

.844*

12-34-377A B-K-1 B10.10 Integra! Attachment Surf RR-4 - - -

1.50" CC N-509 34-54-AN-12 F-A F1.10c Variable Spring Hanger V7-3 RR-2 - - - 1.50* PFSK-1023. CC N-491-1 12-34-378 B-J 89.11 Pipe-Elbow VouSurf - - - .844" 12-34-379 B-J 89.11 Elbow-Pipe VoVSurf - - -

.844*

12-34-380 B-J 89.11 Pipe-Elbow VouSurf - - -

.844-12-34-381 6-J B9.11 Elbow-Tee VoVSurf - - -

.844-

?

FitE f WPt.AN.34.WPD Page 34 - 3 of 34 - 12

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r James A. Fitzpatrick Nuclear Pcwer Plant [[::JAF-ISI-0003|JAF-ISI-0003]] (J

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O IU8WMM Third Inservice Inspection interval Date January 7,1998 Ten -Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCR.'PTION EXAM REO PER1 PER2 PER3 THICM REMARKS I

34 - Feedwater System Drawing Number: MSK-3033 Line No.18"-WFP-902A-4A 18-34-374 B-J 89.11 Reducer-Tee Vol/ Surf - - X 1.15- High Stress Weld 18-34-382 B-J 89.11 Tee-Pipe Vot/ Surf - -

X 1.15" High Stress Weld 18-34-383 B-J 83.11 Pipe-Elbow Vol/ Surf - - -

1.15-18-34-384 B-J 89.11 Eltmw-Pipe Vol/ Surf - - -

1.15" 18-34-385 B-J 89.11 Pipe-Elbow Vo!/ Surf - - -

1.15*

18-34-937 B-K-1 B10.10 Integral Attachment Surf RR4 - - -

.500" CC N-509 34 4A-HS-16 N/A N/A Hydraulic Snubber VT-3 RR-11 - - - .500- H34-119. TS Sectron 3.6.1 34-4A-HS-17 N/A N/A H/ drau!ic Snubber VT-3 RR-11 - - -

.500" H34-119. TS Section 3.6.1 18-34-386 B-J B9.11 Elbow-Valve FWS-29A Vol/ Surf - - -

1.15' FWS-29A B-M-2 B12.50 Valve Interior VT-3 - - - -

Only when disassembled Lirwed to one vatre in a group of valves FWS-29A B-G-2 B7.70 Vafve Botting VT-1 - - - <2" Limited to valve selected under B-M-2 18-34-387 B-J 89.11 Valve FWS-29A-Pipe Vol/ Surf - - -

1.15" ,

18-34-937A B-K-1 B10.10 Integral Attachme.it Surf RR-4 - -

X 1.50* CC N-509 34-4A-AN-18 F-A F1.10b Constraint VT-3 RR-2 - -

X 1.50" H34-109. CC N-491-1 18-34-387A B-J 89.32 3/4' Branch Connection Surf - - - - Exempt IV 0-1220(a) 18-34-388 B-J 89.11 Pipe-Elbow Vol/ Surf - - - 1.15*

18-34-388A B-J B9.32 3/4" Branch Connection Surf - - - - Exempt IV.B-1220(a) l Fl* ED FV/Pt.AN.34 WPD Page 34 - 4 of 34 -12

James Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] M NewMM Third Inservice Inspection Interval Date January 7,itM Ten -Yearinspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISa lMTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THtCK REMARKS 34 - Feedwater System Drawing Number: MSK-3033 Line No.18"-WFP-902A-4A 18-34-389 B-J B9.11 Elbow-Valve FVG28A Vol/ Surf - - X 1.15" High Stress Weld FVG28A B-M-2 B12.50 Valve Intenor VT-3 - - - - Only when disassembled. Limited to one vahre in a group of valves FWS-28A B-G-2 B7.70 Valve Botting VT-1 - - -

<2- Lirrsted to valve selected under B-M-2 18-34-391 B-J 89.11 Valve FWS-28A-Pipe Vol/ Surf - -

X 1.15' Hegh Stress Weld 18-34-3910 - -

Insulation Lug N/A - - - - Inaccessible inside Pen. X-9A, No exam requeed 18-34-391N - - Insulation Lug N/A - - - - Inaccessible inside Pen. X-9A. No exam requ: red 18-34-391M - - Insulation Lug N/A - - - - Inaccessible inside Pen. X-9A, No exam requred 18-34-391L - -

Insulation Lug N/A - - - Inaccessible inside Pen. X-9A. No exam required 18-34-391K - -

Insulation Lug N/A - - - - Inaccessible inside Pen. X-9A No exam required 18-34-391J - -

Insulation Lug N/A - - - -

Inaccessible inside Pen. X-9A, No exam required 18-34-391H - -

.asulation Lug N/A - - - -

Inaccessible inside Pen. X-9A. No exam requred 18-34-391G - - Insulation Lug N/A - - - -

Inaccyssible mside Pen. X-9A, No exam required 18-34-391F - - Insulation Lug N/A - - - -

Inaccessible inside Pen. X-9A. No exan, requred 18-34-391E - -

Insutaton Lug N/A - - -. -

Inaccessible inside Pen _ X-9A No exam requred 18-34-391D - -

Insulation Lug N/A - - - - Inaccesste inside Pen. X-9A, No exam required 18-34-391C - - Insulation Lug N/A - - - -

Inaccessible inside Pen. X-9A. No exam requeed 18-34-3918 B.J 89.11 Pipe-Integral Fstting Vol/ Surf - - -

1.15" Inaccessible inside Pen. X-9A F!LE- FWPLAN 34 WPD Page 34 - 5 of 34 -12

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] M 15mMPomr Third Inservice inspection Interval Date January 7,1998 Ten -Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME VWELD IDENTIFICATION CODE CODE COTE REL ISi tNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICM REMARKS 34 - Feedwater System Drawing Number- MSK-3G33 Line No.18"-WFP-902A-4A 31-34-391A BJ 89.11 Liner-Integral Fitting Vol/ Surf - - -

1_50" 18-34-392 B-J 89.11 Pipe-Pipe VoVSurf - - - 1.15*

18-34-393 B-J 89.11 Pipe-Reducer Vol/ Surf - -

X 1.15" 20-34-394 B-J 89.11 Reducer-Tee Vol/ Surf - - -

128' 8-13-436 B-J 89.11 Tee-Pipe Vol/ Surf - - -

.500" 8-13-437 B-J 89.11 Pipe-reducer Vol/ Surf - - - .500*

20-4-395 B-J B9.11 Tee-Reducer Vol/ Surf - - -

1.28~

18-34-394A B-J 89.32 3/4' Branch Connection Surf - - - Exempt IWB-1220(a) 20-34-395 B-J 09.11 Tee-Reducer Vot/ Surf - - -

153" I 10-34-39G B-J B9.11 Reducer-Valve NRV *11A Vot/ Surf - - -

1.15' NRV-111 A B-M-2 B12.50 Valve Interior VT-3 - - - - Only when disassembled, Umited to one valve in a grougof vahres NRV-111 A B-G-2 B7.70 Va!ve Botting VT-1 - - -

<2" Umited to valve selected under B-M-2 l

i 18-34-396A N/A N/A Vafve NRV-111 A-Pipe N/A - - -

1.15' Non-nuclear safety-related i

34-3A-AN-19 F-A F1.10e Rigid Sway Strut VT-3 RR-2 - -

X -

H34-15. CC N-491-1 l

l 34-3A-AN-20 F-A F1.10e Rigid Sway i VT-3 RR-2 - - - - H34-16, CC N-491-1 l

i 34-3A-NS-21 F-A F1.10e Rigid Sway St VT-3 PR-2 - - - - PFSK-1874, CC N491-1 l

FILE: FWPLAN 34 WPD Page 34 -6 of 34 -12

O O James A. Fitzpatrick Nuclear Power Plant [[::JAF-4SI-0003|JAF-4SI-0003]] Date January 7,1998 Third Inservice Inspection Interval g h Ten -Year inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME REL ISilNTERVAL LTH OR CODE CODE REMARKS IDENTIFICATION CODE EXAM REQ PER1 PER2 PER3 TH!CK CAT ITEM DESCRfPTION 34 - Feedwater System Drawing Number: MSK-3034 Line No.12"-WFP-902A-5D to Reactor Vessel VoVSurf RR-7 - - - .844*

N-4D-SE B-J 89.11 Nozzle-Safe End Vol/ Surf - - X .844* Terminal End 12-34-397 B4 89.11 Safe End-Pipe Vol/ Surf . - - .844- i 12-34-398 B-J 39.11 Pipe-Elbow l VouSurf - - - .844" 12-34-399 B4 89.11 Elbow-Pipe Surf RR-4 - - - 1.5" CC N-509 12-34-401 A B-K-1 B10.10 Integral Attachment VT-3 RR-2 - - X 1.5" PFSK-1025. CC N-491-1 F-A F1.10c Variable Spring Hanger 34-5D-AN-25 VoVSurf - - - .844*

12-34-400 B-J B9.11 Pipe-Elbow VoVSurf - - - .844-12-34-401 B-J 89.11 Elbow-Pipe VoVSurf - X - .844' High Stress Weld 12-34-402 B-J 89.11 Pipe-Elbow X - .844" Kegh Stress Weld 89.11 Elbow-Pipe Vol/ Surf -

12-34-403 B-J Surf RR-4 - - - .500* CC N-509 12-34-940A B-K-1 810.10 Integral Attachment VT-3 RR-11 - - - .500* H34-122.TS Section 3 6.1 34-5D-HS-26 N/A N/A Hydraulic Snubber VT-3 RR-11 - - - .500" H34-121. TS Sectior' 3.6.1 34-SD-HS-27 N/A N/A Hydraulic Snubber VoUSurf - - X .844- Kgh Stress Weld 12-34-404 B-J 89.11 Pipe-Elbow VoVSurf - - X .844* High Stress Weld 12-3A405 B-J B9.11 Pipe-Pipe Surf RR-4 - - - .500*

12-34-941 B-K-1 B10.10 Integral Attachment VT-3 RR-2 - - - .500* H34-111. CC N-491-1 34-SD-AN-28 F-A F1.10b Vertical Support Page 34 - 7 of 34 -12 FILE FWPtAN.34WPD

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] O bMM Third Inservice inspection Interval Date January 7,1998

Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THtCK REMARKS 34 - Feedwater System Drawing Number: MSK-3034 Line No.12"-WFP-902A-5D to Reactor Vesse!

12-34-942 B-K-1 810.10 Integral Attachment Surf RR-4 - - -

.500" CC N-509 34-5D-AN-29 F-A F1.10b Constraint VT-3 RR-2 - - -

.500" H34-112. CC N-491-1 34-5D-AJ4-30 F-A F1.10b Constraint VT-3 RR-2 - - -

.500" H34-113 CC N-491-1 12-34-943 B-K-1 B10.10 Integral Attachment Surf RR-4 - - -

.500* CC N-509 12-34-406 B-J B9.11 Pipe-Pipe Vol/ Surf - -

X .844* High Stress Weld 12-34-407 B-J B9.11 Pipe-Reducer Vol/ Surf - - X .844" High Stress Weld i

P FILE FWPLAN 34 WPD Page 34 - 8 of 34 -12

James A.Fitzpatrick Nuclear Power Plant JAF-tS14063 Third Inservice Inspect!on Interval Date January 7,1998 M

$ Ten -Year inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME REL ISIINTERVAL LTH OR CODE CODE CODE REMARKS IDENTIFICATION DESCRIPTION EXAM REQ PER1 PER2 PER3 TittCM CAT ITEM 34 - Feedwater System Drawing Number: MSK-3034 Line No 12"-WFP-902A-5B to Reactor Vessel VoVSurf RR-7 - - X 844" N-4C-SE B-J B9.11 Nozzle-Safe End VoUSurf - - X .844* High Stress Welt,Termmal End 12-34-409 B-J 89.11 Safe End-Pipe VoVSurf - - - .844*

12-34-410 B-J G9.11 Pipe-Elbow VoVSurf - - - .844*

12-34-411 B-J 89.11 Elbow-Pig a Surf RR-4 - - - 1.50" CC N-509 11-34-944 B-K-1 B10.10 Integrat Attachment VT-3 RR-2 - - - 1.50* PFSK-1022. CC N-491-1 34-58-NN-32 F-A F1.10b Constraint VoUSurf - - - .844*

12-34-412 B-J B9.11 Pipe-Elbow VoVSurf - - - .844" 12-34-413 B-J B9.11 Elbow-Pipe Vot/ Surf - - - .844*

12-34-414 B-J 89.11 Pipe-Elbow Vol/ Surf - - - .844*

12-34-415 B-J 89.11 Elbow-Tee I

l ,

l Page 34 -9 of 34 -12 FILE- FWPLAN 34.WPD

O James A. Fitzpatrick Nuclear Power Plant Third inservice inspection interval [[::JAF-431-0003|JAF-431-0003]] dam January 7,1998 h

$h Ten -YearInspection Plan Revision 0 ASME WELD COMPONENT ASME ASME REL ISilNTERVAL LTh 0R CODE CODE IDENTIFICATION CODE EXA%I REO PER1 PER2 PER3 THICK REMARKS DESCRIPTION CAT ITEM 34 - Feedwa'er System Drawing N ber: MSK-3034 Line No. W-WFP-902A-4B Vol/ Surf X - - 1.15' High Stress Weld 18-34-408 B-J 89.11 Reducer-Tee Vol/ Surf X - - 1.15" High Stress Weld 18-34-416 B-J 89.11 Tee-Pipe Vol/ Surf - - - 1.15*

18-34-417 B-J 89.11 Pipe-Elbow Vol/ Surf - - 1.15" 89.11 Elbow-Pipe 10-34 418 B-J Vol/ Surf - - - 1.15" 18-34-419 B-J 89.11 Pipe-Elbow Surf RR-4 - - - .500- CC N-509 18-34-945 B-K-1 010.10 Integral Attachtnent RR-11 .500" H34-123, TS Section 3.6.1 N/A N/A Hydraulic Snubber VT-3 - - -

34-48-HS-35 VT-3 RR-11 - - - .500" H34-124. TS Secte 3.6.1 34-48-HS-36 N/A N/A Hydraulic Snubber Vot/ Surf - - - 1.15' 18-34-420 B-J 89.11 Elbow-Valve FWS-298 VT-3 - - - - Only when disassembled, Limited to one va!ve in a FWS-298 B-M-2 B12.50 Valve interior group of valves j VT-1 - - <2* Limited to valve selected under B-M-2 FWS-298 B-G-2 B7.70 Vatve Botting -

1.15* j B-J 89.11 Valve FWS-29A-Pipe Vol/ Surf - - -

18-34-421 Surf RR-4 - - - 1.50" CC N-509 18-34-421 A B-K-1 B10.10 Integral Attachment VT-3 RR-2 - X - 1.50" H34-114. CC N-491-1 34-48-AN-37 F-A F1.10b Const aint Surf - - - - Exempt IWB-1220(a) l 18-34-421B P-J B9.32 3/4' Branch Connection VouSurf - - - 1.15*

18-34-422 B-J 89.11 Pipe-Elbow Surf - - - - Exempt IWL-1220(a) 18-34-422A B-J 89.32 3/4* Branch Connection Page 34 - 10 of 34 -12 FILE FWPLAN 34.WPD

Jam:s A Fitzpttrick Nuclesr Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third Inservice inspection Interval Date January 7,1998 b

$ Ten - Yea-Inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME REL IS1 INTERVAL LTH OR CODE CODE REMARKS IDENTIFICATION CODE EXAM REQ PER1 PER2 PER3 THICK CAT ITEM DESCRtPTION t

34 - Feedwater System Drawing Number: MSK-3034 Line No.18'*-WFP-902A-4B Ve!/Sud - X - 1.15" High Stress Weld 18-34-423 B4 B9.11 Elbow-Valve FWS-28B

- Only when disassembled. Limited to one vafve in a B12_50 Vatve Interior VT-3 - - -

FWS-28B B-M-2 group of valves VT-1 - - -

<2" Limited to valve selected under B-M-2 FWS-28B B-G-2 B7.70 Valve Botting Vot/ Surf - X - 1.15" High Stress Weld 18-34-425 B-J 89.11 Valve FWS-288-Pipe

- - Inaccessible inside Pen. X-98. No exam required

- Insulation 8 ug N/A - -

18-34-4250 - -

- Inaccessible inside Pen. X-98. No exam required

- Insulation Lug N/A - - -

18-34-425N -

- Inaccessible inside Pen X-98. No exam required N/A - - -

- Insuhtion Lug 18-34-425M -

- Inaccessible inside Pen. X-98. No exam required

- Insulation Lug N/A - - -

18-34-425L -

- Inaccessible inside Pen. X-98 No exam required

- Insulation Lug N/A - - -

18-34-425K -

Im.ccessitne inside Pen. X-98. No exam reqisired N/A - - -

- Insulation Lug 18-34-425J -

- Inaccess31e inside Po:. X-98. No exam required

- Insulation Lug N/A - - -

18-34-425H -

N/A - - - -

Inacepssible inside Pen. X-9B. No exam required

- Insulation Lug 18-34-425G -

- Inaccessible inside Pen. X-953 No exam required

- Insulation Lug N/A - - -

18-34-425F -

- Inaccessible inside Pen. X-9B. No exam required

- Insulation Lug N/A - - -

18-34-425E -

- Inaccessible inside Pen. X-98. No exam required

- Insulation Lug N/A - - -

18-34-42.5D -

- Inaccessible insid? Pen. X-98, No exam required

- Insulation Lug N/A - - -

18-34-425C -

- 1.50" Inaccessible inside Pen. X-98 No exam required 89.11 Pipe-Integral Fitting Vot/ Surf - -

18-34-425B B-J Page 34 - 11 of 34 -12 FILE: FWPLAN.34.WPD

O O James A. Fitzp: trick Nuctsar Power Plznt [[::JAF-ISI-0063|JAF-ISI-0063]] O

Third inservice inspection Interval Date January 7,1998 h

$ Ten - Year Inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME ISIINTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE ETAM REQ PER1 PER2 PER3 THICK REMARKS CAT ITEM DESCRIPTION 34 - Feedwater System Drawing Number: MSK-3034 Line No.18"-WFP-902A-4B Vol/ Surf - - - 1.15" 31-34-425A B-J 89.11 Liner-Integral Fitting Vot/ Surf - - 1.15" 89.11 Pipe-Tee 18-34426 B-J Vol/ Surf - - 1.15" 89.11 Tee-Pipe 18-34-427 B-J Surf - - - - Exempt IWB-1220(a) 18-34-427B B-J B9.32 3/4" Branch Connection Vol/ Surf - - - 1.15' 18-34-427A B-J B9.11 Reducer Vafve NRV-111B VT-3 - - - - Only when disassembled, Limited to one valve in a NRV-1118 B-M-2 B12.50 Vaive Interior group of valves VT-1 - -

<2" Umited to valve selected under B-M-2 B7.70 Valve Botting NRV-1118 B-G-2 N/A - 1.15" Non-nuclear safety-related Valve NRV-111B-Pipe - -

18-34-428 N/A N/A VF-3 RR-2 - - - - H34-13, CC N-491-1 34-38-AN-38 F-A F1.10b Constraint VT-3 RR-2 - - - - H34-14A, CC N-491-1 34-38-HS-39 F-A F1.10b Constraint VT-3 RR-2 - - - - H34-14, CC r4-491-1

! 34-38-AN-40 F-A F1.10b Constraint l t Page 34 - 12 of 34 -12 FILE: FWPLAN 34.WPD

3 JAF ISI-0003 JAMES A. FITZPATRICK NUCLEAR POWER PLANT

b NewYorkPower

& Authortty G THIRD INSERVICE INSPECTION INTERVAL Rev. O TEN YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 20 of 35 5.0 CLASS 2 INSERVICE INSPECTION PLAN TABLES This section contains the Long Term Ten-Year Inservice inspection Examination Tables for nondestructive examinations of selected systems and components for the Third Inservice inspection Interval.

03 Control Rod Drive System . . 03-1 thru 03-11 10 Residual Heat Removat System . 10-1 thru 10-92 13 Reactor Core injection Cooling System .

13-1 thru 13-3 14 Core Spray System ,, , 14-1 thru 14-19 23 High Pressure Coolant Injection System 23-1 thru 23-19 27 Containment Purge / CAD Pass System 27-1 thru 27-13 29 Main Steam System . 29-1 thre 29-2 O

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Third inservice Inspection Interval Ten -Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WEl.D IDENTIFICATION CODE CODE COtsE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THfCK REMARKS 4

03 - Control Rod Drive System Drawing Number: MSK-3038 Line No. Scram Tank 03TK-1 A N4-A - -

1.0" Nozzle to Shell welds - - - - -

Exempt IWC-1222(a)

TH1-A C-A C1.20 Head to Shell Weld Vol X - -

75'-4* Limited to one vessel in a group of vessels N2A-A - -

1.0" Nozzle to Shell welds - - - - - Exempt IWC-1222(a)

N28-A - - 1.0" Nozzle to Shell welds - - - - - Exempt IWC-1222(a)

N2C-A - -

1.0" Nozzle to Shell welds - - - - - Exempt IWC-1222(a)

N2D-A - - 1.0" Nozzle to Shell welds - - - - - Exempt IWC-1222(a)

N1A C-B C2.21 10.0" Nozzle to Shell welds Vol/ Surf X - - -

Nozzle Inner Radius does not exist N1 A-lR C-B C2.22 Nozzle Inner radius Vol X - -

10.0" LL1-A C-C C3.10 Lifting Lug Surf RR - - 14" CC N-509, Excluded IWC-2500-1(1)(b)

LL2-A C-C C3.10 Lifting Lug Surf RR - - 14" CC N-509, Excluded IWC-2500-1(1)(b)

CC1-A C-C C3.10 Integral Attachment Surf RR -

X .50" CC N-509, Limited to one vessel in a group of vessels CC1-A F-A F1.40 Pedestal Support VT-3 RR - X -

CC y-491-1 CC2-A C-C C3.10 Integral Attachment Surf RR - -

.50" CC N-509, Limited to one vessel in a group of vessels "

CC1-A F-A F1.40 Pedestal Support VT-3 RR-2 X - - -

CC N-491-1 CC3-A C-C C3.10 Integral Attachment Surf RR - -

50" CC N-509, Limited to one vesselin a group of vessels FILE: CRD02.03.WPD Page 03 - 1 of 03-11

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Q) h Date January 7,1998

$ Third Inservice Inspection Interval Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICAT10N CODE CODE CCDE REL ISI INTERVAL LTH OR CAT ITEM DESCRfPTION EXAM REQ PER1 PER2 PER3 THICM, REMARKS i

03 - Control Rod Drive System Drawing Number: MSK-3038 Line No. Scram Tank 03TK-1A CC1-A F-A F1.40 Pedestal Support VT-3 RR-2 X - - - CC N-491-1, CC4-A C-C C3.10 Integral Attachment Surf RR - -

.50" CC N-509, Limited to one vesselin a group of vessets CC1-A F-A F140 Pedestal Support VT-3 RR-2 X - - -

CC N-491-1 N3A-A - - 1.0" Nozzle to Shell welds - - - - - Exempt IWC-1222(a)

N3B-A - -

1.0" Nozzle to Shell welds - - - - -

Exempt IWC-1222(a)

N3C-A - -

1.0" Nozzle to Shell welds - - - - - Exempt IWC-1222(a)

N3D-A - -

1.0" Nozzle to Shell welds - - - - -

Exempt IYC-1222(a)

BH1-A C-A C120 Head to Shell Weld Vol -

X -

75'-4* Limited to one vesselin a group of vessels NS-A - - 2.0" Nozzle to Shell welds - - - - - Exempt IWC-1222(a) f FILE: CRD02.03.WPD Page os -1 03-11

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James . Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] g Nm Pam Third Inservice Inspection interval Date January 7,1998 Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 03 - Control Rod Drive System Drawing Number: MSK-3038 Line No. Scram Tank 03TK-18 N4-B - -

1.0" Nozzle to Shell welds - - - - - Exempt IWC-1222(a)

TH1-B C-A C1.20 Head to She!! Weld Vol - - -

75'-4" Limited to one vesselin a group of vessels N2A-B - -

1.0" Nozzle to Shell welds - - - - - Exempt IWC-1222(a)

N28-8 - -

1.0" Nozzle to Shell welds - - - - - Exempt IWC-1222(a)

N2C-B - - 1.0" Nozzle to Shell welds - - - - - Exempt IWC-1222(a) l N2D-B - -

1.0" Nozzle to Shell welds - - - - - Exempt IYC,-1222(a)

N1B C-B C2.21 10.0" Nozzle to Shell welds Vol/ Surf - - - -

Nozzle inner Radius Section does not exist N18-IR C-B C2.22 Nozzle Inner radius Vol - - -

10.0" LL1-B C-C C3.10 Lifting Lug Surf RR - - 14* CC N-509. Excluded IWC-2500-1(1)(b)

LL2-B C-C C3.10 Lifting Lug Surf RR - - 14" CC N-509. Excluded IWC-2500-1(1)(b)

CC1-B C-C C3.10 Integral Attachment Surf RR - -

.50" CC N-509. Limited to one vessel in a group of vessels CC1-B F-A F1.40 Pedestal Support VT-3 RR - - -

CC f/-491-1 CC2-8 C-C C3.10 Integral Attachment Surf RR - -

.50" CC N-509. Limited to one vessel in a group of vessels CC1-B F-A F1.40 Pedestal Support VT-3 RR - - -

CC N-491-1 CC3-8 C-C C3.10 Integra! Attachment Surf RR - -

.50" CC N-509, limited to one vessel in a group of vessels FILE: CRD02.03 WPO Page 03 - 3 of 03-11

J V James A. Fitzpatrick Nuclear Potver Plant [[::JAF-ISI-0003|JAF-ISI-0003]] U

h Third Inservice Inspection laterval Date January 7,1998 gNew Ten - Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 03 -Control Rod Drive System Drawing Number: MSK-3038 Line No. Scram Tank 03TK-1B CC1-B F-A F1.40 Pedestal Support VT-3 RR - - - CC N-491-1, CC4-B C-C C3.10 Integral Attachment Surf RR - -

.50" CC N-509 Limited to one vessel in a group of vessels CC1-B F-A F1.40 Pedestal Support VT-3 RR - - -

CC N-491-1 N3A-B - -

1.0* Nozzle to Shell welds - - - - - Exempt IWC-1222(a)

N38-B - -

1.0" Node to Shell welds - - - - - Exempt IWC-1222(a)

N3C-B - -

1.0' Nozzic to Sheit welds - - - - - Exempt IWC-1222(a)

N3D-B - - 1.0" Nozzle to Shell welds - - - - - Exempt IWC-1222(a)

BH1-B C-A C1.20 Head to Shell Weld Vol X - -

75'-4" Limited to one vessel in a group of vessels NS-B - -

2.0" Nozzle to Shell welds - - - - -

Exempt IWC-1222(a) t FILE: CRD02.03.WPD Page 03 - 4 of 03 -11

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] hwer Third inservice Inspection interval Date January 7,1998 g New Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRfPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 03 -Control Rod Drive System Drawing Number: MSK-3039 Line No. 8.C-WR-901 8-03-1 C-F-2 C5.51 Pipe to Cap Vol/ Surf X - -

.500" 3-NS-1 F-A F1.20a Rod Hanger VT-3 RR -

X - CC N-491-1, PFSK-3005 3-NS-2 F-A F1.20e Sway Strut VT-3 RR -

X -

CC N-491-1 PFSK-3004 3-NS-3 F-A F1.20a Rod Hanger VT-3 RR - - -

CC N-491-1 8-03-2 C-F-2 C5.51 Pipe to Pipe - - - -

.500" Excluded from Exam 3-N S-4 F-A F1.20b Lateral Restraint VT-3 RR - - - CC N-491-1, PFSK-3002 3-NS-5 F-A F1.20b Adjustable Restraint VT-3 RR - - - CC N-491-1, PFSK-3060 3-NS-6 F-A F1.20b Box Restraint VT-3 RR - - - CC N-491-1, PFSK-3001 3-NS-7 F-A F1.20b Box Restraint VT-3 RR - - - CC N-491-1, PFSK-3001 8-03-3 C-F-2 C5.51 Pipe to Elbow Vol/ Surf X - -

.500" 8-03-4 C-F-2 C5.51 Elbow to Pipe Vol/ Surf - - -

.500" 8-03-5 C-F-2 C5.51 Pipe to Reducer Vo'! Surf - - -

.500" 8-03-21 C-F-2 C5.51 Reducer-Pipe Vol/ Surf - - -

.500" 8-03-22 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.500" 8-03-23 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.500" 3-NS-12 F-A F1.20a Rod Hanger VT-3 RR - - - CC N-491-1, PFSK-3009 3-NS-13 F-A F1.20a Rod Hanger VT-3 RR - - -

CC N-491-1 PFSK-3008 FILE: CRD02.03.WPD Page 03 - 5 of 03-11

N_] %) O James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] g b Third inservice inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD

' IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR g CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICI( REMARKS 03 -Control Rod Drive System Drawing Number: MSK-3039 I ine No. 8.0"-WR-901 8-03-24 C-F 2 C5.51 Pipe-Pipe - - - -

.500" Excluded from Exam 3-NS-14 F-A F120a Rod Hanger VT-3 RR - - - CC N-491-1, PFSK-3007 3-NS-15 F-A F1.20e Sway Strut VT-3 RR - - - CC N-491-1, PFSK-3006 3-NS-16 F-A F1.20e Sway Strut VT-3 RR - - -

CC N-491-1 PFSK-3006 8-03-25 C-F-2 C5.51 Pipe-Cap Vol/ Surf - - -

.500" Drawing Number: MSK-3040 8-03-26 ' C-F-2 C5.51 Pipe-Cap Vol/ Surf - - -

.500" 3-NS-17 F-A F120b Adjustable Restraint VT-3 RR -

X - CC N-491-1, PFSK-3063 3-NS-18 F-A F1.20a Rod Hanger VT-3 RR -

X - CC N-491-1, PFSK-3019 3-NS-19 F-A F1.20e Sway Strut VT-3 RR - - - CC N-491-1, PFSK-3020 8-03-27 C-F-2 C5.51 Pipe-Pipe - - - -

.500" Exc.aded from Exam 3-NS-20 F-A F1.20e Sway Strut VT-3 RR - - -

CC N-491-1 PFSK-3022 8-03-28 C-F-2 C5.51 Pipe-Pipe - - - -

.500" Excluded from Exam 3-NS-21 F-A F1.20a Rod Hanger VT-3 RR - - - CC N-491-1, PFSK-3021 3-NS-22 F-A F1.20e Sway Strut VT-3 RR - - - CC N-491-1, PFSK-3023 3-NS-23 F-A F1.20e Sway Strut VT-3 RR - - - CC N-491-1, PFSK-3023 0-03-29 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.500" FILE: CRD02.03 WPD Page 03 - 6 of 03-11

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

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w) g Ptmer Third Inservice inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL t.TH OR CAT ITEM DESCRfPTION EXAM REQ PER1 PER2 PER3 THtCK REMARKS t

03 -Control Rod Drive System Drawing Number: MSK-3040 Line No. 8.0"-WR-901 8-03-30 C-F-2 C5.51 Reducer-Elbow Vol/ Surf - - -

.500" 8-03-44 C-F-2 C5.51 Reducer-Elbow Vol/ Surf - - -

.500" 8-03-45 C-F-2 C5.51 Elbow-Pipe Vot/ Surf - - -

.500" 3-NS-27 F-A F1.20a Rod Hanger VT-3 RR - - - CC N-491-1, PFSK-3026 3-NS-28 F-A F1.20e Sway Strut VT-3 RR - - -

CC N-491-1. PFSK-3027 3-NS-29 F-A F1.20a Rod Hanger VT-3 RR - - -

CC N-491-1. PFSK-3028 3-NS-30 F-A F1.20b Lateral Restraint VT-3 RR - - - CC N-491-1, PFSK-3029 8-03-46 C-F-2 C5.51 Pipe-Pipe - - - -

.500" Excluded from Exam 3-NS-31 F-A F1.20a Rod Hanger VT-3 RR - - -

CC N-491-1. PFSK-3030 8-03 17 C-F-2 C5.51 Pipe-Pipe - - - -

.500" Excluded from Exam 3-NS-32 F-A F1.20b Box Restraint VT-3 RR - - -

CC N-491-1. PFSK-3031 3-NS-33 FA F1.20e Sway Strut VT-3 RR - - - CC N-491-1, PFSK-3032 3-NS-34 F-A F1.20e Sway Strut VT-3 RR - - -

CC N-491-1. PFSK-3032 8-03-48 C-F-2 C5.51 Pipe-Cap Vot/ Surf - - -

.500" FILE: CRD02.03.WPD Page 03 - 7 of 03 -11

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James A. Fitzpa' rick Nuclear Power Plant JAF-ISl4)003 h

$b Third Inservice inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTDtVAL LTH OR CAT ITEM DESCR1FTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 03 - Control Rod Drive System Drawing Number: MSK-3039 Line No.10"-WR-901 10-034 C-F-2 C5.51 Reducer to Pipe Vo/ Surf - - -

.594~

3-NS-8 F-A F1.20e Sway St^ VT-3 RR-2 X - - -

CC N-491-1. PFSK-3010 3-NS-9 F-A F1.20e Sway Strut VT-3 RR - - -

CC N-491-1. PFSK-3010 10 03-7 C-F-2 C5.51 Pipe to Tee Vo/ Surf - - -

.594~

10-03-8 C-F-2 C5.51 Tee to Pipe Vol/ Surf - - -

.594~

10-03-9 C-F-2 C5.51 Pipe to Pipe - - - -

.594* Exduded from Exam 10-03-10 C-F-2 C5.51 Pipe to Pipe - - - -

.594~ Exduded from Exam 10-03-11 C-F-2 C5.51 Pipe to Elbow Vol/ Surf - - -

.594" 10-03-12 C-F-2 C5.51 Elbow to Pipe Vol/ Surf - - -

.594" 3-N"-10 F-A F1.20b Adjustable Restraint VT-3 RR - - -

CC N-491-1. PFSK-3061 3-NS-11 F-A F1.20b Adjustable Restraint VT-3 RR - - -

CC N-491-1. PFSK-3061 10-03-13 C-F-2 C5.51 Pipe to Elbow Vol/ Surf - - -

.594" 10-03-14 C-F-2 C5.51 Elbow to Pipe Vol/ Surf - - -

.594*

10-03-15 C-F-2 C5 51 Pipe to Elbow Vol/ Surf - - -

594" 10-03-16 C-F-2 C5.51 Elbow to Pipe Vol/ Surf - - -

.594*

10-03-17 C-F-2 C5.51 Pipe to Pipe - - - -

.594~ Exduded from Exam 10-03-18 C-F-2 C5.51 Pipe to Pipe - - - -

.594~ Exduded from Exam FILE: CRD02.03V/PD Page 03 - 8 of 03-11

' (3 r s

James A. Fitzpatrick Nucle r Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h

$ Third Inservice Inspection Interval Ten -Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI f*(TERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS t

03 - Control Rod Drive System Drawing Number: MSK-3039 Line No.10"-WR-901 10-03-19 C-F-2 C5.51 Pipe to Nozzle VoUSurf X - -

.594~ Tenninal End 10-03-20 C F-2 C5.51 Tee to Reducer VoVSurf X - -

.594*

th FILE: CRD02.03.V/PD Page 03 - 9 of 03-11

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

> New%rkW Third Inservice inspection Interval Date January 7,1998

Ten -Yearinspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THtCK REMARKS S

03 -Control Rod Drive System Drawing Number: MSK-3040 Line No.10"-WR-901 10-03-31 C-F-2 C5.51 Pipe-Reducer VoVSurf - - - .594" 3-NS-24 F-A F1.20e Sway Strut VT-3 RR-2 X - - - CC N-491-1, PFSK-3024 10-03-32 C-F-2 C5.51 Tee-Pipe VoUSurf - - -

.594" 10-03-33 C-F-2 C5.51 Pipe-Tee VoVSuri - - -

.594" 10-03-34 C-F-2 C5.51 Pipe-Pipe - - - -

.594* Exduded from Exam 10-03-35 C-F-2 C5.51 Pipe-Pipe - - - -

.594" Exduded from Exam 10-03-36 C-F-2 C5.51 Pipe-Pipe - - - -

.594" Exduded from Exam l

10-03-37 C-F-2 C5.51 Pipe-Pipe - - - -

.594" Exduded from Exam l

10-03-38 C-F-2 C5.51 Elbow-Pipe VoUSurf - - -

.594*

10-03-39 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

.594" 10-03-40 C-F-2 C5.51 Pipe-Pipe - - - -

.594" Exduded from Exam 10-03-41 C-F-2 C5.51 Nozzle-pipe VoUSurf X - -

.594" Terminal End 10-03-42 C-F-2 C5.51 Tee-Pipe VoVSurf - - -

.594" 3-NS-25 F-A F1.20e Sway Strut VT-3 RR - - -

CC N-491-1. PFSK-3025 l

3-NS-26 F-A F1.20e Sway Strut VT-3 RR - - -

CC N-491-1 PFSK-3025 10-03-43 C-F-2 C5.51 Pipe-Reducer VoUSurf - - -

.594" l

FILE: CRD02.03.WPD Page 03 - 10 of 03 -11

O<~ J.

James A. Fitzpatrick Nucle:r Power PI:nt [[::JAF-ISI-0003|JAF-ISI-0003]] Third inservice inspection Interval Date January 7,1998 gp h Ten - Year inspection Plan Revision 0 ASME VVEt.D COMPONENT ASME ASME REL ISI INTERVAL LTH OP.

CODE CODE CODE REMARKS IDENTIFICATION DESCRIPTION EXAM REQ PER1 PER2 PER3 THtCK CAT ITEM 03 - Control Rod Drive System Dr.. wing Number: MSK-3003 Line No. Line through Penetration X-36 was cut out and capped

- - Excluded from examination per IWC-2500-1(1)

C5.61 Cap-Pipe Vot/ Surf - -

3-03-963 C-F 2

- No exam required

- losulation Lug N/A - - -

3-03-963A -

- No exam required

- Insulation Lug N/A - - -

3-03-963B -

- No exam required insulation Lug N/A - - -

343-963C - -

- No exam required Insu!ation Lug N/A - - -

3-03-963D - -

- No exam required Insulation Lug N/A - - -

3 C3-9632 - -

- - No exam required Insutation Lug N/A - -

3-03-963F - -

- No exam required Insuhtion Lug N/A - - -

3-03-963G - -

- No exam required insulation Lug N/A - - -

3-03-963H - -

No exam required N/A - - -

Insulation Lug -

3-03-963J - -

- No exam required

- Insulation Lug N/A - - -

3-03-963K -

N/A - - - No exam required Insulation Lug -

3-03-963L - -

- no e'xam required

- insufation Lug N/A - - -

3-03-963M -

i

- - Excluded from examination per IWC-2500-1(1)

C-F-2 C5.61 Pipe-!ntegral Fitting Vol/ Surf - -

3-03-963N

- - Excluded from examination per IWC-2500-1(1)

C-F-2 C5.61 Liner-Integral Fitting Vol/ Surf - -

7-03-963P

- - Excluded from examination per IWC-2500-1(1)

C-F-2 C5.61 Integral Fitting-Pipe Vot/ Surf - -

3-03-9630

- - Excluded from examination per IWC-2500-1(1)

C5.61 Pipe-Cap Vol/ Surf - -

3-03-9G4 C-F-2 Page 03 - 11 of 03 -11 FILET CRD02.03.WPD

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James A Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] V

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$b Third Inservice Inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENT!F! CATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 10 - Residual Heat Exchanger System Drawing Number MSK-3037 Line Number: RHR Heat Exchanger 10E-2A N3-A C-B C2.21 20.0" Nozzle-Head Vol/ Surf -

X - 875" N7-A - -

1.0" Nozzle-Head Surf - - -

.375" Exempt 1\W-1221(c)

N8-A - -

3/4" Nozzle-Head Surf - - -

.375' Exempt IWC-1221(c)

C5-A C-A C1.20 Head-Shell Weld Vol - -

X .875' L3-A - -

LongitudinalWeld - - - - -

Excluded liW-2500-1 Sup-1A C-C C3.10 Integral Attachment Surf RR-4 X - -

1.0" CC N-509 Sup-1A F-A F1.40 Support VT-3 RR-2 X - - -

CC N-491-1 Sup-2A C-C C3.10 Integral Attachment Surf RR-4 - - -

1.0" CC N-509 Sup-2A F-A F1.40 Support VT-3 RR-2 X - - -

CC N-491-1 Sup-3A C-C C3.10 Integral Attachment Surf RR-4 - - -

1.0" CC N-509 Sup-3A F-A F1.40 Support VT-3 RR-2 -

X - -

CC N-491-1 Sup-4A ' C-C C3.10 Integral Attachment Surf RR-4 - - -

1.0" CC N-509 Sup-4A F-A F1.40 Support VT-3 RR-2 -

X - -

CC [J-491-1 N 10-A - -

3/4" Nozzle-Head Surf - - - -

Exempt IWC-1221(c)

C-4-A C-A C1.10 Shell Circumferential Weld Vol -

X - -

Sup-5A C-C C3.10 integra! Attachment Surf RR-4 - - - - 12.0", CC N-509 FILE: RHR02.10.WPD Page 10 - 1 of 10-92

Q/ James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Q

4 b VNk h Third inservice inspection Interval Date January 7,1998

Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS I

10 - Residual Heat Exchangar System Drawing Number: MSK-3037 Line Number: RHR Heat Exchanger 10E-2A Sup-SA F-A F1.40 Support VT-3 RR-2 - -

X -

CC N-491-1 81-A - - 2.0" Support Bolts (12) N/A - - - 2.0" Excluded IWC-2500-1 Sup-6A C-C C3.10 Integral Attachment Surf RR-4 - - -

1.0" CC N-509 Sup-GA F-A F1.40 Support VT-3 RR-2 - -

X -

CC N-491-1 L2-A - - Longitudinal Weld - - - - -

Excluded IWC-2500-1 N9-A - -

3/4" Nozzle-Head Surf - - - - Exempt IWC-1221(c)

N4-A C-8 C2.21 20.0* Nozzle-Head Vol/ Surf - - X 1.12" C-3-A C-A C1.10 Shell-Flange Weld Vol - - X -

NG-A - -- 1 1/2" Nozzle-Head Surf - - - - Exempt IYC-1221(c)

B2-A - - 1.0" Flange Bolts (72) N/A - - - - Excluded IWC-2500-1, No exam required r

FILE: RHR02.10.WPD Page 10 - 2 of 10-92

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James . Fitzpatrick Nuclear Pner Plant [[::JAF-ISI-0003|JAF-ISI-0003]] b Date January 7,1998

$ Third Inservice Inspection interval Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENT FICATION CODE CODE CODE REL ISilNTERVAL t TH OR CAT ITFM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS I

10 - Residual Heat Exchanger System Drawing Number: MSK-3037 Line Number- Heat Exchanger 10E-2B N3-8 C-B C2.21 20.0" Nozzle-Head Vol/ Surf - - -

.875" N7-B - -

1.0" Nozzie-Head Surf - - -

.375" Exermt FAC-1221(c)

NS-B - -

3/4* Nozzle-Head Surf - - -

.375" Exempt IVC-1221(c)

C5-B C-A C1.20 Head-Shell Weld Vol - - -

.875" L3-8 - -

Longitudinal Weld - - - - -

Excluded PWC-2500-1 Sup-1B C-C C3.10 Integral Attachment Surf RR-4 - - - 1.0" CC N-509 Sup-1B F-A F1.40 Support VT-3 RR-2 - - - -

CC N-491-1 Sup-28 C-C C3.10 Ir egral Attachment Surf RR-4 - - -

1.0" CC N-509 Sup-28 F-A F1.40 Support VT-3 RR-2 - - - -

CC N-491-1 Sup-38 C-C C3.10 Integral Attachment Surf RR-4 - - -

1.0" CC N-509 l

Sup-38 F-A F1.40 Support VT-3 RR-2 - - - - CC N-491-1 Sup-4B C-C C3.10 Integral Attachment Surf RR-4 - - - 1.0" CC N-509 Sup-4B FA F1.40 Support VT-3 RR-2 - - - - CC f4-491-1 N10-B - -

3/4" Nozzle-Head Surf - - - - Exempt IWC-121(c) i C-4-B C-A C1.10 Shell Circumferential Weld Vol - - - -

1 Sup-58 C-C C3.10 Integral Attachment Surf RR-4 - - -

12.0" CC N-509 l

FILE: RHR02.10.WPD Page 10 - 3 of 10-92

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James E Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] ^

s h Date January 7,1998

$h Third inse,vice inspection Interval Ten -Yearinspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCR!PTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 10 - Residual Heat Exchanger System Drawing Number- MSK-3037 Line Number: Heat Exchanger 10E-2B Sup-58 F-A F1.40 Support VT-3 RR-2 - - - -

CC N-491-1 81-B - - 2.0" Support Bolts (12) N/A - - -

2.0" Excluded IWC-2500-1 Sup-68 C-C C3.10 Integral Attachment Surf RR-4 - - -

1.0" CC N-509 Sup-6B F-A F1.40 Support VT-3 RR-2 - - - -

CC N-491-1 L2-B - -

Longitudinal Weld - - - - -

Excluded IWC-2500-1 N9-8 - -

3/4" Nozzle-Head Surf - - - -

Exempt IWC-1221(c)

N4 B C-B C2.21 20.0" Nozzle-Head Vol/ Surf - - -

1.12*

C-3-B C-A C1.10 Shell-Flange Weld Vol - - - -

NG-B - -

1 1/2" Nozzle-Head Surf - - - - Exempt IWC-1221(c)

B2-B - - 1.0" Flange Bolts (72) N/A - - - -

Excluded IWC-2500-1, No exam required

?

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l FILE: RHR02.10.WPD Page 10 - 4 of 10-92 i

! James A. Fitzpatrick Nuclear Power Plant JAF-ISl#003 h

l

$ Third inservice inspection Interval Ten -Yearinspection Plan Date January 7,1998 Revision 0 t

! COMPONENT ASME ASME ASME WELD l

IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR l CAT' ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICK REMARKS 1

10 - Residual Heat Removal System Drawing Number: MSK-3004 Line Number: 16"-W20-302-78 from RHR Pump P-3B

( 10-78-NS-1 A F-A F1.40 P3-B Pump Suppert VT-3 RR-2 -

X -

2.25" CC N-491-1 16-10-200 C-F-2 C5.51 Pump-Pipe Vot/ Surf -

X -

.500" Terminal End 16-10-201 C-F-2 C5.51 Pipe-Elbow Vol/ Surf -

X -

.500" 16-10-202 C-F-2 C5.51 Elbow-Elbow Vol/ Surf - - -

.500" 16-10-202A C-C C3.20 Integral Attachment Surf RR-4 - - -

.237" CC N-509 10-78-AS-1 F-A F1.20c Variable Spring VT-3 RR-2 - - - 237" PFSK-2039, CC N-491-1 16-10-203 C-F-2 C5.51 Elbow-Flange Vol/ Surf - - - .500*

Flange - - Flange Botting - - - -

<2" No exam required 16-10-203A C-F-2 C5.51 Flange-Pipe Vof/ Surf - - -

.500" 16-10-204 - - 3.0" Branch Connection Surf - - - -

Exempt IWC-1221(c) 16-10-205 - -

3/4" Branch Connection Surf - - - -

Exempt IWC-1221(c) 16-10-206 - -

3/4" Branch Connection Surf - - - -

Exempt IWC-1221(c) 16-10-207 C-F-2 C5.51 Pipe-Valve RHR-42B Vol/ Surf - - -

500" RHR-428 - -

16.0" Check Valve - - - - -

16-10-208 C-F-2 C5.51 Valve RHR-428-Pipe .Vol/ Surf - - -

.500" 16-10-209 - - 4.0" Branch Connection Surf - - - -

Exempt IWC-1221(c) 16-10-210 C-F-2 C5.51 Pipe-Valve RHR-458 Vol/ Surf - - -

500" FILE: RHR02.10.WPD Page10-5 of 10-92

James itzpatrick Nuclear Power Plant JAF-IS'-0003 Date January 7,1998

$g h Third inservice Inspection Interval Ten - Year inspection Plan Revision 0 4

COMPONENT ASME' ASME ASME WELD IDENTWICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM L2SCR PTION EXAM REO PER1 PER2 PER3 THICK REMARKS t

10 - Residual Heat Removal System Drawing Number: MSK-3004 Une Number- 16"-W20-302-7B from RHR Pump P-38 10-78-MS-3 t#A N/A Mechanical Snubber VT-3 RR - - -

PFSK-2089/JAF#8422. TS Section 3.6.1 RHR-45B - - 16.0" Valve Botting VT-1 - - - <2" No exam required 16-10-211 C-F-2 C5 51 Valve RHR-45B-Elbow VoVSurf - - -

.500" 16-10-211 A - -

11/2" Branch Connection Surf - - - - Exempt l'T 1221(c) 16-10-212 C-F-2 C5.51 Elbow-Reducer Vol/ Surf - - -

500" Une Number: 20"-W20-302-8B 20-10-213 C-F-2 C5.51 Reducer-Pipe VoVSurf - - -

.594" t

20-10-213A - -

2.(T' Branch Connection Surf - - - - Exempt IWC-1221(c)

Une Number: 16*-W20-302-7D from RHR Pump P-3D l 10-7D-NS-2A F-A F1.40 Pump P3-D Support VT-3 RR-2 - - -

2.2C' CC N-491-1 16-10-214 C-F-2 C5.51 Pump P-3D-Pipe VoVSurf X - -

.500" Terminal End 16 *0-215 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

.500" 16-10-216 C-F-2 C.S.51 Elbow-Elbow VoVSurf - - -

.500" 16-10-216A C-C C3.20 Integral Attachment Surf RR-4 - - -

.237" CC N-509 10-7D-AS-2 F-A F1.20e Variable Spring VT-3 RR-2 - - - .237" CC N431-1 16-10-217 C-F-2 C5.51 Elbow-Flange VoVSutf - - -

.500" Flange - - Flange Botting VT-1 - - - <2" No exam required FILE RHR02.10.WPD Page 10 - 6 of 10-92 l

hm em -

O O James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Date January 7,1998 Third Inservice inspection Interval g b Ten -Year inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME REL ISIINTERVAL LTH OR CODE CODE REMARKS IDENTIFICATION CODE EXAM REQ PER1 PER2 PER3 THfCK CAT ITEM DESCRIPTION 1'l- Residual Heat Removal System Dr:: wing Number: MSK-3004 Line !Jumber- 16"-W20-302-7D from RHR Pump P-3D VoVSurf - - - .500*

16-10-217A C-F-2 C5.51 Flange-Pipe

- - Exempt IWC-1221(c)

- 3.0" Branch Connection Surf - -

16-10-218 -

- Exempt IWC-1221(c)

- 3/4" Branch Connection Surf - - -

16-10-219 -

- Exempt IVE-1221(c)

- 3/4* Branch Connection Surf - - -

16-10-220 -

VoVSurf - - - .500" 16-10-221 C-F-2 C5.51 Pipe-Valve RHR-42D

- <2" No exam required

- 16.0" Check Valve Dotting VT-1 - -

RHR-42D -

VoVSurf - - - .500*

16-10-222 C-F-2 C5.51 Valve RHR-42D-Pipe

- Exempt IWC-1221(c)

- 4.0" Branch Connection Sud - - -

16-10-223 -

VoUSurf - - - .500" 16-10-224 C-F-2 C5.51 Pipe-Valve RHR-45C

- - No exam required

- 16.0" Valve botting VT-1 - -

RHR-45C -

VoUSurf - - - .500" 16-10-225 C-F-2 C5.51 Valve RHR-45C-Pipe Surf PR-4 - - -

.500" CC N-509 16-10-226A C-C C3.20 Integral Attachment r

Line Number: 20"-W20-302-88 Surf X - - .500" Inaccessible 20-10-226 C-F-2 C5.81 20.0" Branch Connection X SAD Saddle Weld, CC N-509 C3.20 Integral Attachment Surf RR-4 - -

20-10-2268 C-C I VoUSurf - - - .594" 20-10-227 C-F-2 C5.51 Pipe-Elbow

~

VoVSurf - - - .594*

20-10-228 C-F-2 C5.51 Elbow-Pipe Page 10 -7 of 10-92 FlLE: RHR02.10AVPD

V k)

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] V

g Power Third inservice inspection Interval Ten -Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilMTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THfCK REMARKS 10 - Residual Heat Removal Systern Drawing Number: MSK-3004 Line Number: 20"-W20-302-8B 20-10-229 C-F-2 C5.81 20.0" Branch Connection Surf -

X - -

Line Number:16"-W20 302-9B 16-10-230 C-F-2 C5.51 Pipe-Valve MOV-65B VoL' Surf - - -

.500" MOV-658 - - 16.0" Valve botting VT-1 - - -

<2" No exam required 10-98-HS-4 N/A N/A Hydraulic Snubber - RR - - TS Section 3.6.1 10-9B-HS-5 N/A N/A Hydrau!ic Snubber - RR - - - TS Section 3.6.1 16-10-231 C-F-2 C5.51 Vafve MOV-65B-Pipe Vol/ Surf - - -

.500" 10 98-HS-6 N/A N/A Hydraulic Snubber - RR - - -

TS Section 3.6.1 10-9B-HS-8 N/A N/A Hydraulic Snubber -

RR - - -

TS Section 3.6.1 10-99-HS-7 N/A N/A Hydraulic Snubber -

RR - - -

TS Section 3.6.1 16-10-231 A C-C C3.20 Integral Attachment Surf RR-4 - - -

.500" CC N-509 l ine Number: 20"-W20-302-8B 20-10-232 - - 1 1/2* Branch Connection Surf - - - -

Exht IWC-1221(c) 20-10-233 C-F-2 C5.51 Pipe-Va!ve MOV-66B Vol/ Surf - - -

.594*

10-88-HS-9 N/A t#A Hydraulic Snubber -

RR - - -

TS Section 3.6.1 10-8B-HS-10 N/A N/A Hydraulic Snubber -

RR - - -

TS Secbon 3.6.1 MOV-668 - - 20.0" Valve Bolting VT-1 - - -

<2" No exam required FILE: RHR02.10.WPD Page 10 - 8 of 10-92

[ (y .,,

l James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISt-0003|JAF-ISt-0003]] b

$b Third inservice inspection interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATtON CODE CODE CODE REL tSt INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS i

10 - Residual Heat Removat System Drawing Number: MSK-3004 Line Number" 20"-W20-302-8B 20-10-234A C-C C320 Integral Attachment Surf RR-4 - - -

.750" CC N-509 20-10-234 C-F-2 C5.51 Valve MOV-668-Pipe Vol/ Surf - -

X .594" 10-88-HS-12 N/A N/A Hydraulic Snubber -

RR - - -

TS Sectron 3.6.1 10-88-NS-14 F-A F120b Vertical Constraint VT-3 RR-2 - - X .500" PFSK-1935. CC N-491-1 20-10-2348 C-C C3.20 integral Attachment Surf RR-4 - -

X .500" CC N-509 20-10-235 C-F-2 C5.81 16 0" Branch Connection Surf - - - -

20-10-255 - -

1 1/2" Branch Connecbon Surf - - - - Exempt 8WC-1221(c) 20-10-256 - -

1 1/4" Branch Connecdw>

Surf - - - - Exempt tWC-1221(c) 20-10-257 C-F-2 C5.81 20.0* Branch Connection Surf - - - -

Inaccessible 20-10-259A C-C C320 Integra! Attachment Surf RR-4 - - -

.500" CC N-509 10-88-NS-15 F-A F1205 Vertical Support VT-3 RR-2 - - - .500" CC N-491-1 20-10-260 C-F-2 C5.51 Pipe-Reducer Vol/ Surf - - -

.594" l Line Number: 16"-W20-320-10B 16-10-236 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - - .500* Excluded 1%C-2500-1 16-10-237 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

.500" 16-10-238 C-F-2 C5.51 Elbow-Pipe Vot' Surf - - -

.500*

16-10-239 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.500" FILE: RHR02.10.VFD Page 10 - 9 of 10-92

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James A. Fitzpatrick Nuclear Po w Plant [[::JAF-ISI-0003|JAF-ISI-0003]] VD'k h

$ Third Inservice Inspection interval Ten - Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRfPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 1

10 - Residual Heat Removal System Drawing Number: MSK-3004 Line Number: 16"-W20-302-10B 16-10-240 C-F-2 C5.51 Elbow-Pipe Vot/ Surf - - -

.500" 16-10-241 C-F-2 C5.51 Pipe-Pipe Vot/ Surf - - -

.500" Excluded IWC-2500-1 16-10-242 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.500" 16-10-2428 C-C C3.20 Integral Attachment Surf RR-4 -

X -

.875" CC N-509 10-10-B-AS-16 F-A F1.20c Variable Spring VT-3 RR-2 -

X - - PFSK-261, CC N-491-1 16-10-242A C-C C3.20 Integral Attachment Sc:f RR-4 - - -

.875" CC N-509 16 10-243 C-F-2 C5.51 Elbow-Valve MOV-128 Vol/ Surf - - -

.500" MOV-12B - - 16" Valve Botting VT-1 - - -

<2" No exam required 10-10B0HS-17 N/A N/A Hydraulic Snubber -

RR - - -

PFSK-249. TS Section 3.6.1 10-108-HS-id N/A N/A Hydraulic Snubber -

RR - - -

PFSK-2250. TS Section 3.6.1 10-108-HS-19 N/A N/A Hydraulic Snubber -

RR - - - PFSK-2373, TS Section 3.6.1 10-108-HS-20 N/A N/A Hydraulic Snubber -

RR - - - PFSK-2448, TS Section 3.6.1 16-10-244 G F-2 C5.51 Valve MOV-128 - Pipe Vol/ Surf - - -

.500" 16-10-244A C-C C3.20 Integral Attachment Surf RR-4 - - -

.500" CC N-509 16-10-245 - -

1 1/2" Branch Connection Surf - - - -

Exempt IWC-1221(c) 16-10-246 - -

4.0" Branch Connection Surf - - - -

Exempt IWC-1221(c) 16-10-247 - -

1 1/2" Branch Connection Surf - - - -

Exempt IWC-1221(c)

FILE: RHR02.10.WPD Page 10 - 10 of 10-92

(v) James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

.x g h Third Inservice Inspection Interval Ten -YearInspection Plan Date January 7,1998 Revision 0

' COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRtPTION EXAM REQ PER1 PER2 PER3 THICK REWARKS 10 - Residual Heat Removal System Drawing Number: MSK-3004 Line Number: 16"-W20-302-10B 16-10-247A - -

3/4" Branch Connection Surf - - - - Exempt IWC-1221(c) 16-100t8 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.500" 16-10-249 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.500" 10-108-AN-21 F-A F1.20b Vertical Restraint VT-3 RR-2 - - -

H10-89A. CC N-491-1 16-10-250 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.500"

! 16-10-251 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.500"

( 16-10-252 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.500" 16-10-253 C-F-2 C5 51 Elbow-Elbow Vol/ Surf - - -

.500" 20-10-254 C-F-2 C5.51 Elbow-Hx Nozzle Vol/ Surf - -

X .500" Terminal End Line Number: 16"-WS-302-56B 16-10-258 C-F-2 C5.51 Pipe-Valve RHR-1778 Vol/ Surf X - -

.500" RHR-1778 - - 16.0" Check Valve Botting VT-1 - - -

<2" No exam required 16-10-259 C-F-2 C5.51 Valve RHR-177B - Elbow Vol/ Surf - - -

.500" 16-10-761 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.500" 16-10-765 - -

11/2" Branch Connection Surf - - - - Exempt IWC-1221(c) 16-56B-NS-22 F-A F1.20e Rigid Sway Strut VT-3 RR-2 - - - -

PFSK-2199 CC N-401-1 16-10-766 C-F-2 C5.51 Pipe-Elbers Vol/ Surf - - - .500" 1

FILE: RHR02.10 WPD Page 10 - 11 of 10 -92 l

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James A'.~_Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

-$ h Third Inservice Inspection Interval Ten -YearInspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISi tNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS

. 10 - Residual Heat Removal System Drawing Wmber:MSK-3004 1.fr:e Number.16"-WS-302-56B 16-10-767 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.500" 16-10-769 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

.500"10-770 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - - .500*

16-10-771 C-F-2 CE.51 Pipe-Elbow Vot/ Surf - - -

.500" 16-10-772 C-F-2 C5.51 Elbow-Pipe Vcl/ Surf - - -

.500" 16-10-773 C-F-2 05.51 Pipe-Pipe Vot/ Surf - - - .500" Excluded IWC-2500-1 16-10-774 C-C C3.20 Irtegral Attachment Surf RR-4 - -

.500" CC N-509 16-56B-NS-95 F-A F1.20b Anchor VT-3 RR-2 - - - - CC N-491-1 16-10-775 C-F-2 C5.51 Pipe-Valve MOV-1498 16.0' Valve - - -

<2" Class break from 2 to 3 1

FILE: RHR02.10.WPD Page 10 - 12 of 10-92

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James h. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] M Date January 7,1998

$ Third Inservice inspection Interval Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISi tNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICK REMARKS i

10 - Residual Heat Removal System Drawing Number: MSK-3005 Line Number: 16"-W20-302-7C from RHR Pump P-3C 10-7C-NS-30A F-A F1.40 Pump Support VT-3 7-2 - - -

2.25" CC N-491-1 16-10-600 C-F-2 C5.51 Pump-Pipe Vol/ Surf - -

X .500* Terminal End 16-10-601 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

JA 0" 16-10-602 C-F-2 C5.51 Elbow-Elbow Vol/ Surf - - -

.500*

16-10-602A C-C C3.20 Integral Attachment Surf RR-4 - -

.237* CC N-509 10-7C-AN-30 F-A F1.20c Variable Spring VT-3 RR-2 - - - - CC N-491-1 16-10-603 C-F-2 C5.51 Elbow-Flange Vol/ Surf - - -

E00*

Flange - - Flange Botting - - - -

<2" No exam requicJ 16-10-603A C-F-2 C5.51 Flange-Pipe Vol/ Surf - - -

.500" 16-10-604 - -

10" Branch Connection Surf - - - -

Exempt IWC-1221(c) 16-10-605 - - 3/4" Branch Connection Surf - - - - Exempt IWC-1221(c) 16-10-606 - -

3/4" Branch Connection Surf - - - - Exempt IWC-1221(c) 16-10-607 C-F-2 C5.51 Pipe-Valve RHR-42C Vol/ Surf - - -

.500" RHR-4?C - - 16.0" Check Valve Bolting VT-1 - - -

<2" No exams required if J"-608 C-F-2 C5.51 Valve RHR-42C-Pipe Vol/ Surf - - -

.500" 16-10-609 - - 4.0" Branch Connectio; Surf - - - - Exempt IVC,-1221(c) 16-10-610 C-F-2 C5.51 Pipe-Valve RHR-45C Vol/ Surf - - -

.500" FILE: R;IR02.10.WPD Page 10 - 13 of 10-92

O O James A. Fitzpr'-ick Nucle r Power Lat [[::JAF-ISI-0003|JAF-ISI-0003]] O

Third Inservice inspection Interval Date January 7,1998 g Pour Ten -Year inspection Plan Revision 0 ASME WELD COttPONENT ASME ASME REL ISIINTERVAL LTH OR CODE CODE CODE REMARKS IDENTIFICATION EXAM REQ PER1 PER2 PER3 TH!CK CAT ITEM DESCRIPTION 10 - Residual Heat Removal System Drawing Number: MSK-3005 Une Number: 16"-W20-30? 7C from RHR Pump P-3C

<2" No exams required

- 16.0" Vafve Botting VT-1 - - -

RHR-45C -

C5.51 Valve RHR-4SC-Pipe Vol/ Surf - - - .500" 16-10411 C-F-2 Surf - - - - Exempt IWC-1221(c) 16-10-611 A - - 1.0" Branch Connection Vol/ Surf - - - .500" 16-10-612 C-F-2 C5.51 El'uow-Reducer .

Line Number: 16"-W20-302-7A from RHR Pump P-3A VT-3 RR-2 - - - 2.25" CC N-491-1 10-7A-NS-31 A F-A F1.40 Pump Support Vol/ Surf - - X .500* Terminal End 16-10-614 C-F-2 C5.51 Pump-Pipe

.500"

~

C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

16-10-615 Vot/ Surf - - - .500" 16-10-616 C-F-2 C5.51 Elbow-Elbow Surf RR-4 - - -

.237" CC N-509 16-10-616A C-C C3.20 Integ al Attachment RR-2 PFSK-2048, CC N-491-1 F-A F1.20c Variable Spring VT-3 - - - -

10-7A-AN-31 C5.51 Elbow-Flange Vot/ Surf - - -

.500" C-F-2 1

16-10u17 VT-1 - - - <2" ho exam required Flange - - Flange Botting Vol/ Surf - - - .500" 16-10-617A C-F-2 C5.51 Flange-Pipe Surf - - - - Exempt IWC-M1(c) 16-10-618 - - 3/4" Branch Connection Surf - - - - Exempt IWC-1221(c) 16-10420 - - 3.0" Branch Connection

- Exempt IWC-1221(c) 3/4" Branch Connection Surf - - -

16-10-619 - -

+

Page 10 - 14 of 10-92 FILE: RHR02.10.WPD

. _ - - bd

G' James A. Fitzpatrick Nuclear Power PI:nt [[::JAF-ISI-0003|JAF-ISI-0003]] hird Inservice Inspection Interval Date January 7,1998 g Pour Ten -Yearinspection Plan Revision 0 ASM8E WELD COMPONENT ASME A*ME ISIINTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE PER1 PER2 PER3 THICK R* MARKS DEST 71PTION EXAM REO CAT ITEM ummmmmmms ,

10 -Residual Heat Removal System Dr= wing Number: MSK-3005 Uno Number:16"-W20-302-7A from RHR Pump P-3A VoVSurf - - -

.500*

16-iN21 C-F-2 C5.51 Pipe-Valve RHR-42A

- <2" No eram required

- 16.0" Check Valve Bo8 ting VT-1 - -

RHR-42A -

Vol/ Surf - - - .500*

16-10-622 C-F-2 C5.51 Valve RHR-42A -Pipe

- - Enempt IV.0-1221(c)

- 4.0" Branch Connection Surf - -

16-10-623 -

Vol/ Surf - - - .500" 16-10-624 C-F-2 C5 51 Pipe-Vafve RHR-45A

- - <2" No exam requeed 16 0" Valve Boltrng VT-1 -

RHR-45A - -

Vol/ Surf - - - .500" 16-10-625 C-F-2 C5.51 Valve RHR-45A -Pipe RR-4 X - Reenforemg Pad, CC N-509 C-C C320 Integral Attachment Surf - -

16-10-626A Line Number: 20"-W20-302-8A from 16' x 20" Reducer l

Surf - - - - Inaccessible 20-10-626 C-F-2 C5.81 20 0 Branch Connection Inaccessible Reenforceg Pad, CC N-509 C320 htegral Attachment Surf RR-4 - - - -

20-10-6268 C-C VoVSurf - - - .594*

20-10-613 C-F-2 CSS 1 Reducer-Prpe

- ExEnpt IWC-1221(c)

- 2.0" Branch Connection Surf - - -

20-10-613A -

VoVSurf - X - .594' 20-10-627 C-F-2 C5.51 Pipe-Elbow VoVSurf - - .594-C5 51 Elbow-Pipe 20-10-628 C-F-2 Exempt IWC-1221(c) durf - - - -

20-10429 * - - 3/4" Branch Connect .n

- - Exempt fWC-1221(c)

- 3/4' O. ranch Connection Surf - -

20-10-630 -

Page 10 - 15 of 10-92 FILE RHR02.10.WPD

Jarr.es A. Fitzp: trick Nuclear Power PI:nt [[::JAF-ISI-0003|JAF-ISI-0003]] Third inservice Inspection Interval Date January 7,1998 M AlserMPomer Ten - Year Inspection Plan Revision 0 ASME WELD COMPONENT ASti." ASME IS3 !NTERVAL LTH OR CODE CODE REL IDENTFICATION CODE EXAM REQ PER1 PER2 PER3 TMrCK REMARMS CAT ITEM DESCRwisON 10 - Residual Heat Removal System Drawing N' uber: MSK-3005 Line Numle 20"-W20-302-8A from 16" x 20' Reducer Surf - - X -

20-10-631 C-F-2 C5.81 20.0* Branch Connectior.

C5.51 Pipe-Va!ve MOV-6SA Vot/ Surf - - - .594*

20-10434 C-F-2 VT-1 - <2" No exam requirad MOV-66A - - 20.0" Valve Botting - -

RR - - - PCSK-2243. TS Section 3 61 10-8A-HS-32 N/A N/A Hydraurec Snubber -

RR - - - H10 464. TS Section 3.6.1 104A-HS-33 N/A N/A Hydraulic Sr'ubber -

RR - - - PFSK-2075, TS Section 3 6.1 10-8A-HS-35 N/A N/A Hydraulic Snubber -

C5.51 Vafve MOV-66A-Pipe VouSurf - - - .594*

20-10435 C-F-2 C-F-2 C5.81 20.0" Branch Conr.ection Surf - - - -

2'J-1043G VT-3 RR-2 - - X - PFSK-1991. CC N-491-1 10-8A-NS-36 F-A F120b Vertical Catraint Surf RR-4 - - - CC N-509 C320 Integral Attachment 20-10-636A C-C Surf - - - - Exempt IVC 1221(c) 20-10-655 - - 1 1/2" Branch Connection 11/4" Branch Cwi,c Uw. Surf - - - - Exempt IVC 1221(c) 20-10-654 - -

VT-3 RR-2 - - -- - H1d.32. CC N491-1 10 8A-NS 37 F-A F120b Vertical Constraint C320 integral Attachment Surf RR-4 - - - 28" CC N-509 20-10-656 C-C l Surf - - - - maccessible 20-14657 C-F-2 C5.81 20.0" Branch Connection C5.51 Pipe-Reducer Vol/ Surf - - -

.594-20-10460 C-F-2 FILE RHR02.10.WPD Page 10 - 16 of 10-92 i

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third Inservice Inspection Interval Date January 7, %98 g b Ten -Year inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME REL ISliNTERVAL LTH OR CODE CODE CODE REMARKS R)ENTIFICATION DESCRIPTIt'N EXAM REQ PER1 PER2 PER3 THICK CAT ITEM 4

10 - Residual Heat Removal System Drawing Number: MSK-3005 Une Number: 16"-W20-302-9A To valve MOV-65A RR - - - PFSK-2082. TS Section 3.6.1 t#A Mechanical Snubber -

10-9A-NS-40A N/A C5.51 Pipe-Vahre MOV-65A Vol/ Surf - -

16-10-632 C-F-2

<2* No exam required

- 1(i.0" Vaive Botting VT-1 - - -

MOV-65A -

RR - - - PFSK-2073. TS Seebon 3.6.1 t#A 10-9A-HS-38 t#A H rdraulic Snubbc4 RR - - - PFSK-2086. TS Sectron 3 6.1 10-9A-HS-39 t#A N/A Hydraulic Snuocer -

- RR - - - PFSK-2444. TS Secbon 3 6.1 10-9A-MS 40 N/A N/A Hydraufic Snubber Uns Number: 16"-W20-307-10A le Valve MOV-12A

- .500" Exduded IVC,-2500-1 C5 51 Pipe-Pipe Vol/ Surf - -

16-10-637 C-F-2 Vot/ Surf - - - .500" ,

16-10-633 C-F-2 C5.51 Pipe-Elbow 1 Vol/ Surf - - - .500" l 16-10-639 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - - .500~

16-10-640 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - - .500~

16-10-641 C-F-2 C5.51 ElbowPipe Vo!/ Surf - - - .500" 16-10-642 C-F-2 C551 Pipe-Elbow VT-3 RR-2 - - - - PFSK-2440. CC N-491-1 F-A F120e Variable Spring 10-10A-AS-41 Surf RR-4 - - - .875' CC N-509 16-10-641A C-C C320 Integral Attachment Surf RR-4 - - - .500" CC N-509 16-10-642A C-C C320 Integral Attachment RR - - - TS Seebon 3E1 10-10A-HS-45 N/A N/A Hydraulic Snubbcr -

Page 10 - 17 of 10-92 FILE RHR02.10.WPD

(_j Fitzpatrick Nuclear Power Plant [[::JAF-4SI-0003|JAF-4SI-0003]]

(

James h

$ Third inservice Inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPCNENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPT10a4 EXAM REQ PER1 PER2 PER3 THICK REMARMS 10 - Residual Heat Removal System Drawing Number: MSK-3005 1.Ine Number: 16"-W20-302-10A to MOV-12A 10-10A-HS-42 N/A N/A Hydraulic Snubber - RR - - -

PFSK-2201. TS Sc-Jion 3.6.1 16-10-643 C-F-2 C5.51 Pipe-Valve MOV-12A VouSurf - - -

.500" MOV-12A - - 16.0* Valve Bolting VT-1 - - -

<2" No exam required 10-10A-HS-43 N/A N/A Hydraulic Snubber - RR - - -

PFSK-2069. TS Section 3 6.1 16-10-644 C-F-2 C5.51 Valve MOV-12A -Pipe Vot/ Surf - - -

.500" 16-10-642B C-C C320 Integral Attachment Surf RR-4 - - -

.500* CC N-509 16-10-645 - -

4.0" Branch Connection Surf - - - Exempt IWC-1221(c) 16-10 446 - -

1 1/4' t$ ranch Cceneden Surf - - - - Exempt IWC-1221(c) 16-10-647A - -

11/2" Branch Connecten Surf - - - - Exempt IWC-1221(c) 16-10-647 - -

1.0" Branch Connecton Surf - - - -

Exempt IWC-1221(c) 16-10-648 C-F-2 C5.51 Pipe 4fbow Vol/ Surf - - -

.500" 16-10-649 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.500" 16-10-649A C-C C320 Integral Attachment Surf RR-4 - - -

.750" Hid-868. CC N-509 10-10A-AN-46 F-A F120c Variable Spring VT-3 RR-2 - - - -

H10-868. CC N491-1 16-10-650 C-F-2 C5.51 Pipe-Elbow Voi/ Surf - - -

.500" 16-10-651 C-F-2 CSS 1 Elbow-Pipe Vot/ Surf - - - .500" 16-10-652 C-F-2 C5.51 Elbow-Pipe VouSurf - - -

.500" FILE RHR02.10.WPD Page 10 - 18 of 10-92

/m

\J James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] M h M P m er Third Inservice inspection Interval Date January 7,1998 Ten -Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 10 - Residual Heat Removal System Drawing Number: MSK-3005 Line Number: 16"-W20-302-10A TO Vafve MOV-12A 16-10-653 C-F-2 C5.51 Elbow-Elbow Vol/ Surf - - -

.500" 20-10-653A C-F-2 C5.51 Reducer-Hx Vol/ Surf -

X -

.500" Terminal End Line Number- 16"-WS-302-56A to valve MOV-149A 16-10-658 C-F-2 C5.31 Pipe-Valve RHR-177A Vol/ Surf - - -

.500" RHR-177A - -

16.0" Check Va've Bolting VT-1 - - -

<2" No exams regurred 16-10-659 C-F-2 C5.51 Vatve RHR-177A -Elbow Vol/ Surf - - - .500" i 16-10-750 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.500-10-56A-NS-60 F-A F1.20b t ateral Constraint VT-3 RR-2 - - - -

CC N-491-1 16-10-751 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

.500" 16-10-752 C-F-2 C5.51 Elbow-Pipe Vot/ Surf - - -

.500" 16-10-753 C-C C3 20 Integral Attachment Surf RR-4 - - -

.500" CC N-509 10-56A-AS-90 F-A F1.20c Variable Spring VT-3 RR-2 - - - -

H10-142. CC N-491-1 16-10-754 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

500" 16-10-755 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.500" 1G-10-756 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.500" 1

FILE: RHR02.10.WPD Page 10 - 19 of 10-92

- ~

(C) (- )

f

\/

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] b

$ Third inservice inspection Interval Ten - Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WM IDENTIFICATION CODE CODE CODE REL ISilMTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 T R3 THICK REMARKS 10 - Residual Heat Removal System Drawing Number: MSK-3005 Line Number: 16"-WS-302-53A to valve MOV-149A 16-10-757 C-F-2 C5.51 Elbow-Pepe Vol/ Surf - - - .500" 16-10-758 C-C C320 Integral Attachmer:t Surf RR-4 - - -

.500* CC N-509 10-56A-NS-92 F-A F120b Vertical Constraint VT-3 RR-2 - - - -

H10-141. CC N-491-1 16-10-759 C-F-2 C5.51 Pipe-Valve MOV-149A Vot/ Surf -

X -

.500*

MOV-149A - -

16.0" Valve Botting VT-1 - - -

<2" Class tweak from 2 to 3 i

t i

i FILE: RHR02.10.WPD Page 10 - 20 of 10-92

v V James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] V

b

$ Third inservice Inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATSON CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRtPTION EXAM REQ PER1 PER2 PER3 THICM REMARMS f

10 - Residual Heat Removal System Drawing Number: MSK-3006 Une Number: 24"-W20-302-11 A 24-10485A - -

3/4" Branch Connection Surf - - - - Exempt n%1221(c) 2410485 - -

2.0* Branch Connection Surf - - - - Exempt IWC-1221(c) 24-10484 C-F-2 C5.51 Pipe-Reducer Vol/ Surf - - -

.688" 24-10-683 - - 4.0* Branch Connection Surf - - - - Exempt n&1221(c) 24-10-682 C-F-2 C5.51 Elbow-Pipe Vol/ Surf -

X -

.688*

24-10481 C-F-2 C5.51 Pipe-Elbow VoL"Jurf - X -

.688*

24-10-680 C-F-2 C5.51 Pipe-Pipe Vot/ Surf - - -

.688" Exc!uded IWC-2500-1 10-11 A-HS-85 N/A N/A Hydraulic Snubber - RR - - -

PFSK-878. TS Seebon 3.6.1 2410-678A C-C C3.20 Integral Attachment Surf RR-4 - - -

.625" CC N-509 ,

24-10-678 C-C C3.20 Integral Attachment Surf RR-4 - - -

.28" CC N-509 10-11 A-NS-85A F-A F1.20b Vertical Constraint VT-3 RR-2 -

X - -

CC N-491-1 24-10-679 C-C C3.20 Integral Attodonent Surf RR-4 - - -

SAD Reenforemg Pad. CC N-509 i 21-10-677A - -

11/2" Branch Connection Surf - - - - Exe'mpt IWC-1221(c) l 24-10-6778 C-F-2 C5.81 16.0" Branch Connection Surf -

X - -

Inaccessible 24-10-677 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.688* i 24-10-676 C-F-2 C5.51 Pipe-Elbow Vo!/ Surf - -

X .688*

FILE RHR02.10.WPD Page 10 - 21 of 10-92

,c ,

James A. Fitzpatrick Nucivar Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] b

$ Third Inservice Inspection Interval Ten -Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME VVELD IDENTIFICATION CODE CODE CCDE REl. ISIINTERVAL LTH OR CAT ITEM DESCRfPTION EXA4 REQ PER1 PER2 PER3 THtCK REMARKS 10 -Residual Heat Removal System Drawing Number: IWISK-3006 1.ine Number: 24 -W20-302-11 A 10-11A-NS-83 F-A F120b Vedcal Constraint VT-3 RR-2 - - - -

PFSK-864. CC N-491-1 2510-675A C-C C320 integml A".achment Surf RR-4 -

X -

.322* CC N-509 24-10-675 C-F-2 C5.51 Elbow-Pipe VoVSurf - - - .688-24-10-674 C-F-2 C5.51 Pipe-Elbow VouSurf - - -

.688-24-10-673 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.688" 24-10-672 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

E88-2410-671 - -

3/4" Branch Csinn. Surf - - - -

Exempt IWC-1221(c) 2510-670 - -

1.0" Branch Connection Surf - - - - Exempt IYE-1221(c) 2 &10-669 C-F-2 C5.51 Flange-Pipe Vol/ Surf - - -

.688" Flange - - Flange Bolting - - - - <2- No exam required 24-10-668 C-F-2 C5.51 Pipe-Flange VoVSurf - - -

.688" 10-11 A-AN-82 F-A F 120e Variable Spring VT-3 RR-2 - - X -

H10 47. CC N-491-1 24-10-6G7 C-F-2 C5.51 Elbow-Pipe VoVSurf - - - .688*

24-10-666 C-F-2 C5.51 Pipe-Elbow VoVSurf - - - .688-24-10-665 - -

1 1/2" Branch Connection Surf - - - -

Exempt IWC-1221(c) 2410-664 C-F-2 C5.51 Elbow-Pipe Vot/ Surf - - -

.688-2 510-663 C-F-2 C5.51 Tee-Elbow Vobsurf - - -

.688" FILE RHR02.10.WPD Page 10 - 22 of 10-92

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third inservice Inspection intervat Date January 7,1998 A NasMPmer Ten -Year inspection Flan Revision 0 ASME WELD COMPONENT ASME ASME LTH OR CODE REL IS!!NTERVAL IDENTIFICATION CODE CODE REMARKS DESCR# TRON EXAM REO PER1 PER2 PER3 THfCK CAT ITEM i 10 - Residual Heat Removal System Drawing Number: MSK-3006 Une Number. 24*-W20-302-11 A Vol/ Surf - - - .688" 24-10-662 C-F-2 C5.51 Tee-Reducer VT-3 RR-2 - - - - PFSK-2080. CC N 491-1 10-17-NS-60 F-A F120b Anchor Vol/ Surf - - - .588~

24-10-661 C-F-2 C5.51 Reducer-Tee Une Number: 24" W20-302-17 VoVSurf X - - .688*

24-10-265 C-F-2 C5.51 Pipe-Reducer VT-3 RR-2 - - - - PFSK-1990. CC N 491-1 10-17-NN-51 F-A F1.20b Anchor Surf RR-4 - - - 1.0* CC N-509 24-10-263A C-C C3.20 Integral Attachment Vol/ Surf - - - .608" beluded IVC 2500-1 44-10-264 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - .688" Excluded IV&2500-1 C5.51 Pipe-Pipe 24-10-263 C-F-2 Vol/ Surf - - - .688*

24-10-262 C-F-2 C5.51 Tee-Pipe VT-3 RR-2 - - - - PFSK-2378. CC N 491 1 10-17-NS-50 F-A F120b Anchor Vol/ Surf - - - .688*

24-10-261 C-F-2 C5 51 Reducer-Tee r

Line Number: 20"-W20-302-17 C5.51 Reducer-Pipe Vot/ Surf - - X .594*

20-10-283 C-F-2 Surf - - - - bempt IVE,-1221(c) 4.0" Branch Cui -Mn,a 20-10-282 - -

VoUSurf - - - .594*

20-10-281 C-F-2 C5 51 Pipe-Vafve MOV-20

<2" No exams requered

- 20 0* Valve Bothng VT-1 - - -

MOV-20 -

I 4

l Page 10 - 23 of 10-92 FILE RHR02.10.WPD

O &

C W James A. Fitzpatrick Nuclea Power Plant [[::JAF-IS1-0003|JAF-IS1-0003]]

{V'}

4 bMM Third Inservice Inspection Interval Date January 7,1998 Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL IS1 tNTERVAL LTH OR CAT ITEM DESCR'PTION EXAM REQ PER1 PER2 PER3 THICK REMARF, 10 - Residual Heat Removal System Drawing Number: MSK-3006 Line Number: 20"-W20-302-17 20-10-280 C-F-2 C5.51 Valve MOV-20-Pipe VoVSurf - - -

.594-20-10-278 - -

4.0" Branch Connection Surf - - - - Exempt 1%C-1221(c) 10-17-NS-59 F-A F120a Rod Hanger VT-3 RR-2 - - - - PFSK-2363, CC N 491-1 10-17-NS-58 F-A F120a Rod Hanger VT-3 RR-2 - - - -

PFSK-2361. CC N-491 1 20-10-277 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

.594*

20-10-276 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.594*

20-10-275 C-F-2 C5.51 Elbow-Pipe VoESurf - - - .594-20-10-274 C-F-2 C5.51 Pipe-E! bow VoVSurf - - -

.594*

10-17-HS-53 fvA N/A Hydraulic Snubber - RR - - -

PFSK-2059. TS Sechon 3.6.1 10-1/-HS-57 N/A N/A Hydraulic Snubber -

RR - - - PFSK-2482, TS Section 3.6.1 10-17-HS-56 N!A PUA Hydraulic Snubber -

RR - - -

H10-35. TS Section 3.6.1 20-10-273 C-F-2 C5.51 Elbow-Pipe VoUSurf - - -

.594' 20-10-272 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

.594' FILE RHR02.10.WPD Page 10 - 24 of 10-92

i

%) (

%j

) b1 N. J James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] 4 hMb Third inservice inspection Interval Date January 7,1998 I Ten -Year inspection Plan Revision O COMPONENT ASME ASME ASME VVELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 5

13 - Residual Heat Removal System Drawing Number: MSK4006 Une Number: 20*-W20-302-17 20-10-271 C-F-2 C551 Elbow-Pipe Vol/ Surf - - -

.594*

20-10-270 C-F-2 C5.51 Pipe-ETI:ow Vol/ Surf - - - .594*

10-17-HS-54 N/A N/A Hydrautec Snubber -

RR - - -

PFSK-2388. TS Secton 3.6.1 10-17-HS-53 N/A N/A Hydraurc Snubber - RR - - -

PFSK-2059. TS Seebon 3 6.1 20-10-268A C-C C320 Integral Attachment Surf RR-4 -- - -

.28' CC N-509 20-10-269 - -

1 1/2" Branch Cw .-Mw.

Surf - - - - Exempt IWC-1221(c) 10-17-NS-52 F-A F120d Sliding Base Constraint VT-3 RR-2 - - - -

PFSK-2213. CC N-491-1 20-10-268 C-F-2 C5 81 8.0" Branch Connection Surf - - - -

Inaccessib:e

, 20-10-267 C-F-2 C5.51 Valve RHR-9 -Pipe VoVSurf - - -

.594~

RHR-9 - - 20.0" Valve Bolting VT-1 - - -

<2" No exam requeed 20-10-206 C-F-2 C5.51 Valve RHR-9 -Reducer Vol/ Surf - - -

.594*

t FILE RHR02.10.WPD Page 10 - 25 of 10-92

3 (.

i, ) I )

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] b

$b Third Inservice Inspection Interval Ten -Year Inspecbon Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICAT3ON CODE CODE CODE REL ISIINTERVAL LTH CR CAT .lTEM DESCRIPTION EXAM REO PER1 ~8ER2 PER3 THICM REMARKS 10 - Residual Heat Removal Sys'am Drawing Number MSK-3006 Une Number: 8~-W20-302-38 8-10-284 C-F-2 C5.51 Pipe-Flange Vol/ Surf - - -

.322- Enduded W/C-2500-1 Flange - -- Flange Botteng VT-1 - - -

<2" No exam required 8-10-285 C-F-2 C5.51 Flange-Pipe VoVSurf - - -

.322~ Exduded iWC-2500-1 8-10-2B6 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.322" Exduded WC2500-1 8-10-287 C-F-2 C5.51 Pipe-Elbow VoUSurf - - -

.322" Excfuded WC2500-1 8-10-288 - - 3/4" Branch CwG. Surf - - - - Exempt WC1221(c) 10-38-NS-61 F-A F120s Rod Hanger VT-3 RR-2 - - - -

PFSK-1976. Excluded IWC-2500-1 8-10-289 C-F-2 C5.51 Pipe-pipe VoVSurf - - -

.322" Exduded IWC-2500-1 10-38-NS-62 F-A F120e Rigd Sway Strut VT-3 RR-2 - - - -

PFSK-1871. Excluded WC2500-1 10-38-NS-63 F-A F1.20a Rod Hanger VT-3 RR-2 - - - -

PFSK-1872. Excluded IWC-2500-1 8-10-290 C-F-2 C5.51 Pipe-Elbow VoUSurf - - -

.322" Exduded WC2500-1 6-10-291 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.322' Exdeded fWC-2500-1 8-10-292 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

.322" Excluded IWC-2500-1 8-10-293 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.322" Exduded IWC-2500-1 10-38-NS-64 F-A F120e RigM Sway Strut VT-3 RR-2 - - - -

PFSK-2224. Exduded N/C-2500-1 8-10-294A C-C C320 Integral Attachment Surf RR-4 - - -

.750" Exduded IVC 2500-1(4) 10-38-AS-65 F-A F120b 1.ateral Constrahnt VT-3 RR-2 - - - -

PFSK-2460. Exduded IWC-2500-1 FILE RHR02.10.WPD Page 10 - 26 of 10-92

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~J %J James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h

$ Third inservice inspection Interval Ten -Year Inspection Plan Date January 7,1998 Revision O COMOONENT ASME ASME ASME WELD IDENTIFICATION CODE CCDE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRfPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS S

10 - Residual Heat Removal System Drawing Number: MSK-3006 1ine Number: 8'*-W20-302-38 8-10-295 C-F-2 C5.51 Pioe-Eibow VoVSurf - - -

.322" Excluded IWC-2500-1 8-10-296 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.322- Exclud-d IVC 2500-1 8-10-297 C-F-2 C5_51 Pipe-Elbow VoVSurf - - -

.322" Excluded UC2500-1 8-10-298 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.322* Exduded NC2500-1 10-J8-NS-66 F-A F120b Vertical Constraint VT-3 RR-2 - - - -

PFSK-2503. Excluded IWC-2500-1 8-10-293 C-C C320 Integral Attachment Surf RR-4 - - -

.625" Excluded IVC 2500-1(4) 8-10-300 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

322" Excluded IV&2500-1 10-38-NS-67 F-A F12Cb Bcx Constraint VT-3 RR-2 - - - -

PFSK-2486. Excluded IWC-2500-1 8-10-301 C-C C320 Integral Attachment Surf RR-4 - - -

.375' Excluded IYC2500-1(4) 8-10-301 A C-C C320 Integral Attachment Surf RR-4 - - -

.750" Excluded !WC-2500-1(4) 10-38-AS-68 F-A F120c Variable Spring VT-3 RR-2 - - - -

PFSK-2355. Excluded im"00-1 8-10-302 C-F-2 C5.51 Prpe-Elbow Vol/ Surf - - -

.322" Exduded IWC-2500-1 8-10-303 C-F-2 C5.51 Elbow-Elbow VoVSurf - - -

22" ExI:!uded IVC 2500-1 8-10-304 C-F-2 C5.5 7 E! bow-Pipe Vol/ Surf - - -

.322" Exduded IWC-2500-1 8-10-304A C-C C320 Integral Attachment Surf RR-4 - - -

.375* Exduded IWC-2500-1(4) 10-38-NS49 F-A F120b Box Constraint VT-3 RR-2 - - - -

PFSK-2029. Exduded IVC 2500-1 8-10-305A - -

1 1/2" Branch Connection Surf - - - -

Exempt 1%C-1221(c)

FILE: RHR02.10.WPD Page 10 - 27 of 10-92

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James A Fitzpatrick Nuclear Power Plant [[::JAF-IS1-0003|JAF-IS1-0003]] b

$b Third Inservice Inspection interval Ten -Yearinspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTis'ICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRtPTION EXAM REQ FER1 PER2 PER3 THICM REMARKS 10 - Residual Heat Removal System Drawing Number: MSK-3006 Line Number: 8~-W20-302-38 8-10-305 C-F-? C5.81 8.0 ' Branch Cv. negus SURF - - - -

Excluded IWC-2500-1 8-10-306 C-F-2 C5.51 Elbow-Pipe VoVSuil - - -

.322" Exduded IWC-2500-1 10-38-AN-70 F-A F120c Variable Spring VT-3 RR-2 - - - -

H10-211. Exduded IWC-2500-1 8-10-307 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.322" Exduded IVC 2500-1 8-10-308 C-F-2 C5.51 ElbowPipe VoVSurf - - - .322* Exduded PAG 2500-1 10-38-NS-71 F-A F120a Rod Hanger VT-3 RR-2 - - - -

PFSK-377. Exduded IWC-2500-1 10-38-NS-71 A F-A F120b Box Constraint VT-3 RR-2 - - -

.250" PFSK-1993. Exdudad MC2500-1 6-10-308A C-C C320 Integral Attachment Surf RR-4 - - -

.250" Exduded IVC 2500-1(4) 8-10-310 C-F-2 C5.51 Pipe-Elbow Voi/ Surf - - -

.322" Exduded (WC-2500-1 8-10-311 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.322" Erduded IWC-2500-1 10-38-NS-72 F-A F120b Constraint VT-3 RR-2 - - - -

PFSK-1980. ExcluhiIWC-2500-1 8-10-312 C-C C320 Integral Attachment Surf RR-4 - - -

.250" Exduded IVC 2500-1(4) 10-38-NS-73 F-A F120b Anchor VT-3 RR-2 - - - -

PFbKs302. Exduded IWC-2500-1 i 8-10-313 C-F-2 C5.51 Prpe-Elbow Vot/ Surf - - -

.322" Excluded fWC-2500-1 8-10-314 C-F-2 C5.51 Elbow-Pipe VouSurf - - - .322" Exduded IYC2500-1 i 8-10-315 - -

1 1/2" Branch Connection Surf - - - -

Exempt IWC-1221(c) l 8-10-316 C-C C320 Integral Attachment Surf RR-4 - - - .187" Exduded IWC-2500-1(4) i i

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l FILE: RHR02.10.WPD Page 10 - 28 of 10-92

LJ %.J G James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-OOO3|JAF-ISI-OOO3]] b Date January 7,1998

$b Third Inservice inspection Interval Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PERT PER2 PER3 THk*H REMARMS 10 - Residual Heat Removat System Drawing Number. MSK-3006 Line Number. 8*-W20-302-38 10-38-NS-74 F-A F1206 Box Constraint VT-3 RR-2 - - - -

PFSK-2259. Enduded rt&2500-1 8-10-316A C-C C3.20 Integel Attachment Surf RR-4 - - -

.500" Enduded WC-2500-1(4) 8-10-317 C-F-2 C5.51 Pipe-Pipe Vot/ Surf - - -

.322- Erduded r/&2500-1 8-10-318 C-C C3.20 Integral Attachment Surf RR-4 - - -

150- Exduded rt&2500-1(4) 10-33-NS-75 F-A F1.20b Anchor VT-3 RR-2 - - - -

PFSK-2433. Excluded IV&2500-1 10-38-NS-76 F-A F1.20b Vertical Constraint VT-3 RR-2 - - -

250- PFSK-2602 Exduded INO2500-1 8-10-319 C-C C3.20 Integral Attachment Surf RR-4 - - -

250" ExduJed IWC-2500-1(4) 10-38-NS-77 F-A F1.20b Box Constraint VT-3 RR-2 - - -

250" PFSK-2294. Excluded rWC-2500-1 8-10-320 C-F-2 C5 51 Pipe-E! bow VoVSurf - - -

.322" Emduded P/&2500-1 8-10-321 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - - .322- Exduded IWC-2500-1 10-38-AN-78 F-A F120c Variable Spring VT-3 RR-2 - - - -

H10-221. Excluded fWC-29X)-1 10-38-NS-79 F-A F1.206 Vertcal Constraint VT-3 RR-2 - - - -

PFSK-2497. Excluded IVC 2500-1 8-10-322 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.322" Exduded IWC-2500-1 8-10-323 C-C C3.20 Integral Attachment Surf RR-4 - - -

.500* Excluded TVC2500-1(4) 10-38-NS-80 F-A F120b Anchor VT-3 RR-2 - - - -

PFSK-2019 Exduded PWC-2500-1 8-10-324 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.322" Exduded IVC-2500-1 8-10-325 C-F-2 C5.51 E! bow-Pipe Vol/ Surf - - -

.322" Exduded r/C2500-1 FILE RHR02.10.WPD Page 10 - 29 of 10-92

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

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h gh Third Inservice Inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASIWE WELD IDENTIFICATION CODE CODE CODE REL IS!!NTERVA1. LTH CR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 TWCK RE1 WARKS 10 - Residual Heat Removal System Drawing Number: MSK-3006 _

Une Number: 8"-W20-302-38 10-38-NS-P1 F-A F1.20e Sway Strut VT-3 RR-2 - - - -

PFSK-2298. Exduded IWC-2500-1 8-13-325A - - 3/4" Branch Cw-G. Surf - - - - Exempt IV.C-1221(c) 8-10-326 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.322" Enduded IV.C-2500-1 8-10-327 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.322" Exduded IV.C-2500-1 8-10-328 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.322" Excluded XYC,-2500-1 8-10-329 C-F-2 C5.51 Pipe-Valve FPC-51 Vo03urf - - -

.322" Exduded IWC-2500-1 FPC-51 - - 8.U* Valve Botting VT-1 - - -

<2* No exam requred FILE: RHR02.10.WPD Page 10 - 30 of 10 -92

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h

$ Third Inservice Inspection Interval Ten -Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION ( ~h>E CODE CODE REL ISliNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 Pf'R3 THfCK REMARKS 10 - Residual Heat Removal System Drawing Number: MSK-3006 Line Number: 24"-W20-302-11B 24-10-331 C-F-2 C5.51 Tee-Elbow Vol/ Surf - - - .688*

2L10-332 C-F-2 C5.51 Elbow-Pipe VoVSurf -

X -

.688-2*,-10-333 C-F-2 C5.51 Pipe-Elbow VoVSurf - -

X .688" 24-10-334 C-F-2 C5.51 Elbow-Pipe VoUSurf - - - .688* Lw.wete Ex.o a.ition 2a10-335 C-F-2 C5.51 Pipe-Pipe VouSurf - - -

.688- Excluded IWC-2500-1 10-11B-AN-86A F-A F120b AdjustableConstraint VT-3 RR-2 - -

X -

H10-44. CC N-491-1 2110-336 - -

1 1/2" Branch Connection Surf - - - - Exempt IWC-1221(c) 10-11B-NS-87 F-A F120b Non-adjustable Constraint VT-3 RR-2 - - - -

H10-45. CC N-491-1 2a10-337 C-F-2 C5.51 Pipe-Flange VoUSurf - - -

.688" Flange - - Flange Botting VT-1 - - - <2" No exam rer.p.rired 24-10-318 C-F-2 C5.51 Flange-Ptpe Vol/ Surf - - -

.688" 24-10-319 - -

1.0" Branch Connection Surf - - - - Exempt IYC,-1221(c) 24-10-320 - -

3/4* Branch Connection Surf - - - - Exempt IWC-1221(c) 24-10-0,41 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.688- .

2 %10-342 C-F-2 C5 51 Elbow-Pipe VoGurf - - -

.688*

2*,-10-343 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.688*

2 110-344 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.688-FILE RHR02.10.WPD Page 10 - 31 of 10-92

(v) Jarues Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] V

h

$b Third Inservice Inspection Interval Ten -Year Inspection Plan Date January 7,1998 Revision O COMPCPvENT ASWE ASME ASWE VVELD IDENTIFICATION CODE CODE CODE REL ISitNTERVAL LTH OR CAT TTEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THfCK REMARKS 10 - Residual Heat Removm System Drawing Number: MSK-3006 Une humber. 24"-W20-302-11B 24-10-3458 C-F-2 C5.61 16.0" Branch Connect:on Surf - - - -

Re-enforong Pad 21-10-345 C-F-2 C5.81 16 0" Branch Ce u Ms.

Surf - - - -

inacces2 A Une Nu nber.16"-W20-302-158 16-10-345A C-C C320 Integral Attacfwnent Surf RR-4 - - -

1.50" CC N-509 10-158-NS-88 F-A F120b Non adjustable Constraint VT-3 RR-2 - - - -

PFSK-2310. CC N491-1 Une Number. 24 -W20-302-118 10-118-HS-69 N/A N/A Hydraufic Snubber VT-3 RR - -

.500" PFSK-1870/JAF222. TS Sechon 3 6.1 24-10-346 C-C C320 Integral Attachment Surf RR-4 - - -

.500" CC N-509 24-10-347 C-F-2 C5.51 Pipe-Pipe Vei/ Surf - - -

.688" Excluded IWC-2500-1 24-10-347A C-C C320 Integral Attachment Surf RR-4 - - -

.750" CC N-509 10-11B-NS-89A F-A F1.20b Non Adjustable Constraint VT-3 RR-2 X - -

.750" PFSK-980/JAF#421. CC N491-1 24-10-348 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

~688" 24-10-349 C-F-2 C5.51 Ebow-Pipe Vol/ Surf - - -

.688" 23-10-350 - -

4.0" Branch Connection Surf - - - -

Exempt IE,-1221(c) 24-10-351 C-F-2 C5.51 Pipe-Reducer Vol/ Surf X - -

.688*

23-10-352 - -

2E Branch Connection Surf - - - -

Exempt P.'VC-1221(c)

FILE: RHR02.10.WPD Page 10 -32 of 10-92

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-tSI-0003|JAF-tSI-0003]] V

h gh Third Inservice Inspection Interval Ten -Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 TH:CM REMARKS 1

10 - Residual Heat Removal System Drawing Number- MSK-3007 Une Number: 16"-W20-302-15A 10-15A-HS-84 N/A N/A Hydraulic Snubber -

RR - - - TS Section 3 6.1 16-10-686A C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

.50(T 16-10486 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - - .500*

16-10487 C-F-2 C5.51 Pipe-Elbow VouSurf - - - .500" 16-10-688 C-F-2 C5.51 Elbow-Pipe Vol/ Surf X - -

.500" 10-15A-NS-100 F-A F120b Box Constraint VT-3 RR-2 - - - - PFSK-1947 CC N-491 1 16-10-688A C-C C3.20 Integral Attachment Surf RR-4 - - - .500" CC N-509 16-10-689 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.500" Excluded IWC-2500-1 10-15A-NS-101 F-A F120b Non Adjustab;e Constraint VT-3 HR-2 - - - - H10-45A, CC N-491-1 10-15A-HS-102 N/A N/A Hydraulic Snubber -

RR - - -

PFSK-2079. 7 Seebon 3 6.1 16-10490 C-C C320 Inteyal Attachment Surf RR-4 - - -

.750" CC N-509 16-10-691 - -

11/2* Branch Ccnnection Surf - - - - Exempt fWC-1221(c) 10-15A-AS-104 F-A F120c Variable Spnng VT-3 RR-2 -

X - -

PFbK-2034. CC N-491-1 16-10-691 A C-C C320 Integral Attachment Surf RR-4 - - -

.237" CC N-509 16-10-692 C-F-2 C5.81 16.0" Branch Connection Surf - - - -

16-10-748 C-F-2 C5.51 Pipe-Valve MOV-39A Vol/ Surf - - - .500" MOV-39A - - 16.0~ Vahe Bo! ting VT-1 - - -

<2" No exam required 10-15A-HS-103 N/A N/A Hydraunc Snubber -

RR - - -

PFSK-2502 TS Section 3.6.1 l

l File RHR02.10.WPD Page 10 -33 of 10-92

g N.) ,Y James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-00C3|JAF-ISI-00C3]] b

$ Third Inservice Inspection interval Ten -Year Inspection Plan Date Jaruary 7,1998 Revision 0 COMPONENT ASME ASME ASME VVELD IDENTFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRtPTION EXAM REQ PER1 PER2 PER3 Tm REMARKS 10 - Residual Heat Removal System Drawing Number- MSK-3007 Line Number: 12"-W20-302-13A 12-10-693 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

3 75* Exduded Ivr,-2500-1 12-10-694 C-F-2 C5.51 Pipe-Elbow VoL/ Surf X - -

3 75*

1-10495 C-F-2 CSS 1 Elbow-Pipe Vol/ Surf - X -

3 75" 12-10-696 C-F-2 CiS1 Pipe-Pipe Vol/ Surf - - -

375" Exduded !YC,-2500-1 10-13A-HS-105 N/A N/A Hydraulic Snubber -

RR - - -

H10-388. TS Sedion 3.6.1 12-10-697 C-F-2 C5.51 Pipe-Elbow Vo lSurf - - -

3 75-12-10-697A C-C C320 Integral Attachmerit Surf RR-4 X - -

1.0" CC N-509 10-13A-NS-105A F-A F1.20b Vertical Support VT-3 RR-2 X - - -

PFSK-2398.CC N 491-1 12-10-698 C-F-2 C5.51 Elbow Pipe Vol/ Surf - - -

3 75" 12-10-699 C-F-2 C5.51 Pipe-Elbow VoL/ Surf - - - .375' 12-10-700 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - - .375*

10-13A-NS-106 F-A F120b Oonstraint VT-3 RR-2 - - - -

PFSK-2449. CC N-491-1 12-10-701 C-C C320 Integral Attachment Surf RR-4 - - - .500" CC N-509 12-10-702 - -

11/2" Branch Connedion Surf - - - - Exempt MC-1221(c) 12-10-703 C-F-2 C5.51 Pipe-Pipe Vot/ Surf - - -

375' Exduded IWC-2500-1 12-10-704 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

375-12-10-705 C-F-2 C5 51 Elbow-Pipe Vo8' Surf - - - .375" Fit.E: RHR02.10.WPD Page 10 - 34 of 10-22

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] b

$b Third Inservice Inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCR!PTION EXAM REQ PER1 PER2 PER3 TH3CK REMARKS 10 -Residual Heat Removat System Drawing Number: MSK-3007 Une Numbe-- 12"-W20-302-13A 10-13A-AS-107 F-A F120e Variable Spring VT-3 RR-2 - - - -

PFSK-2315. CC NJ91-1 12-10-706 C-F-2 C5.51 Pipe-Pipe VoVSurf - - -

.375- Excluded !\*.C-2500-1 10-13A-NN-108 F-A F120b Non Adjustable Support VT-3 RR-2 - - - -

PFSK-1641. CC N-491-1 12-10-706A C-C C320 Integral Attachment Surf RR-4 - - -

.500* CC N-509 10-13A-HS-109A N/A N/A Hydrauhc Snubber - RR - -

PFSK-2518. TS Sechon 3.6.1 12-10-707 C-F-2 C5.51 PpElbow VoySurf - - -

.375*

10-13A-NS-109C F-A F120a Rod Hanger VT-3 RR-2 - - - -

PFSK-2310. CC N 491-1 12-10-708 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.S75*

10-13A-HS-109B N/A N/A Hydraulic Snubber -

RR - - -

PFSK-1518. TS Section 3.6.1 12-10-708A - -

4.0" Branch Connection Surf - - - -

Exempt IWC-1221(c) 10-13A-NS-110 F-A F1 Ob Non Adjustable Support VT-3 RR-2 - - - -

H10-392. CC N-491 1 10-13A-NS-111 F-A F120b Box Constramt VT-3 RR-2 - - - -

PFSK-2194. CC N-491-1 10 . . -NS-112

. F-A F120b Box Constraint V7-3 RR-2 - - - -

CC'N-491-1 12-10-708B C-C C320 Ictegral Attachment Surf RR-4 - - -

.500" CC N-509 12-10-709 O-F-2 C5.51 Pipe-Pipe Vot/ Surf - - -

.375" Excluded IN%C-2500-1 10-13A-NS-113 F-A F1.20e Rigid Sway Str it VT-3 RR-2 - - - -

PFSK-2057. CC N-491-1 12-10-710 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

.375-FILE RHR02.10.WPD Page 10 - 35 of 10-92

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James A. Fikp.tiick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] b

$ Third inservice inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision O COMPONENT ASME ASME ASME WELD EDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRrPTION EXAM REQ PER1 PER2 PER3 W REMARKS 13 - Rat kfr* 4 eat Removal System Drwving K 4@ tr: MSK-3007 Line Ram2#.n s2"-W20-302-13A 12-10-711 C-F-2 C5.51 Elbow-Pepe VoVSurf - - - .375' 12-10-712 C-F-2 C5.51 Pipe-Elbow VoLSuri - - -

.375' 12-10-713 C-F-2 C5.51 Elbow-Fipe VoVSurf - - -

.375" 10-13A-NS-114 F-A F120b Box Ccetstrair t VT-3 RR-2 - - - - PFSK-1916, CC N-491-1

'2-10-714 - - 3/4" Branch Connection Surf - - - - Exempt IWC-1221(c) 12-10-715 C-F-2 C5.51 Pipe-Pipe VoVSurf - - -

.375" Erduded IWC-2500-1 12-10-716 - -

3/4" Branch Connectron Surf - - - -

Exempt ivc 1221(c) 12-10-717 C-F-2 C5.51 Pipe-Pipe VoVSurf - - -

.375" Excluded IVC 2500-1 1-10-718 C-F-2 C5.51 Pipe-Reducee Vol/ Surf - - - .375" t ine Number: 10-W20-302-12A 10-10-719 C-F-2 C5.51 Reducer-Vatve MOV-26A VoVSurf - - -

.365- Excluded IYC2500-1 MOV-26A - -

10.0" Valve Botting VT-1 - - -

<2" No exam required 10-10-720 C-F-2 C5.51 Vafve MOV-26A-Pipe VoVSurf - - -

.365- Exc'fuded IWC-2S00-1 10-10-721 - -

2.0" Branch Connection Su:1 - - - -

Exempt h*C,-1221(c) 10-10-722 - -

1 1/2" Branch Cuiu m'uun Surf - - - -

Exempt IYC,-1221(c) 10-12A-AN-115 F-A F120b Adjustable Support VT-3 RR-2 - - - -

H10-397. Excluded fWC-2500-1 10-12A-NS-116 F-A F120b Non Adjustable Support VT-3 RP 2 - - - -

PFSK-1917. Excluded IWC-2500-1 FILE RHR02.10.WPD Page 10 -36 of 10-92

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James A Fitzpatrick Nuclear Power Plant JAF4SI-0003 g h Third Inservice Inspection Interval Ten -Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISa lNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 TH3CK REMARKS 10 - Residual Heat Removal System Orawing Number- MSK-3007 Une Number: 10"-W20-302-12A 10-10-723 C-C C3.20 Integral Attachment Surf RR-4 - - -

.216" Excluded IVC,-2500-1(4) 10-10-724 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.365* Exduded IV&2500-1 10-10-725 C-C C320 Integral Attachment Surf RR-4 - - -

.500" Exduded IYC2500-1(4) 10-12A-HS-117 N'A N/A Hydraulic Snubber -

RR - - -

PFSK-1928. TS Section 3.6.1 10-10-726 C-C C320 Integral Attachment Surf RR-4 - - -

.500" Excluded IVC 2500-1(4s 10-10-727 C-F-2 C5.51 Elbow-Valve MOV-31 A Vol/ Surf - - - .365~ Exc!uded IWC-2500-1 MOV-31A - -

10.0" Valve Boltmg VT-1 - - -

<2" No exam required 10-10-728 C-F-2 C5.51 Valve MOV-31 A-Pipe Vol/ Surf - - -

.365* Exduded IVC 2500-1 10-10-729 C-C C320 Pen. X-39A integral Attachment Surf RR-4 - - - -

Exduded IWC-2500-1(4) 10-10-730 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.365* Exduded IWC-2500-1 10-10-731 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.365- Exduded IWC-2500-1 10-10-732 C-F-2 C5.51 Pipe-Pipe Vot/ Surf - - -

.365' Exduded IWC-2500-1 10-10-732A C-F-2. C5.51 Pipe-Flange Vol/ Surf - - - .3G5" Exduded IWC-2500-1 Flange - - Flange Botting VT-1 - - -

<2- No exam required 10-10-733A C-F-2 C5.51 Flange-Pipe Vol/ Surf - - -

.365' Excluded IVC 2500-1 10-10-738 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

_365' Excluded IWC-2500-1 10-10-734 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.365" Exchaded IWC-2500-1 FILE- RHR02.10.WPD Page 10 - 37 of 10-92

N) James A. Fitzpatrick Nuclear Power Plant JAF 8SI-0003 b

$b Third inservice inspection Interval Ten -Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASWE ASME ASWE WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICM REMARKS 10 - Residual Heat Removal System Drawing Number. MSK-3007 Une Number.10"-W20-302-12A 10-10-735 C-F-2 C5.51 Elbow-Pipe VouSurf - - -

.365* Exduded I E2500-1 10-10-736 C-F-2 C5.51 Pipe-Elbow VoLSurf - - -

.365* Exduded IWC-2500-1 10-10-737 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

365* Exduded liC2500-1 10-12A-NN-118 F-A F1.20b Non Adjustable Support VT-3 RR-2 - - - -

H10-354. Exduded r.%2500-1 10-10-738 C-F-2 C5.51 Pipe-Pge VoVSurf - - - .365* Exduded FAC-2500-1 10-10-738A C-F-2 C5.51 Pipe-Flange VouSurf - - -

.365* Exduded liC2500-1 Flange - - Flange Bo!!ing VT-1 - - -

<2* No exam reqwred 1G.10-739A C-F-2 C5 51 Flange-Pipe VoVSurf - - -

.365* Exduded nC2500-1 10-10-739 C-F-2 C5.51 Pipe-Pipe VoVSurf - - -

.365* Exduded IWC-2500-1 10-10-740 C-F-2 C5.51 Pipe-Elbow VoVSaf - - -

.365* Exduded r.%2500-1 10-10-741 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.365* Exduded IWC-2500-1 10-10-741 A C-F-2 C5.51 Pipe-Pipe VouSurf - - -

.365* Exduded IVC-2500-1 10-10-742 C-F-2 C5.51 Pipe-Eibow VouSurf - - -

.365* ExE.fuded 1%C2500-1 10-10-743 C-F-2 C5.51 Elbew-Pipe VoUSurf - - -

.365* Exduded IWC-2500-1 10-10-744 C-F-2 C5.51 Pipe-Pipe VoUSurf - - -

.365* Exduded IWC-2500-1 10-10 745 C-F-2 C5.51 Pipe-Pipe VoVSurf - - -

.365* Exduded INC2500-1 Fil.E: RHR02.10.W?D Page 10 - 38 of 10-92

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James A. Fitzpatrick I'uclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

(

g b Third Inservice Inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision O COEIAPONEffT AS*8E ASME ASME WELD IDENTFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICM REMARKS 10 - Residual Hes'.Memoval System Drawing Number: MSK-3007 Une Number- 10'-W20-302-12A 10-10-746 .C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.365* Exduded r.T,-2500-1 10-10-747 C-F-2 C5.51 Pipe-Ring Vol/ Surf - - -

.365* Exduded IWC-2500-1 i

t t

l FILE RHR02.10.WPD Page 10 - 39 of 10-92 i

(y (-

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] V

O bMM Third Inservice inspection Interval Date January 7,1998 Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCR!PT;ON EXAM REO PER1 PER2 PER3 THICK REMARKS 10 - Residual Heat Removal System Drawing Number: MSK-3008

. ne Number:10 -W20-302-128 10-10-423 C-F-2 CJ 81 10.0" Brarch Connection Surf - - - -

Exduded IWC-2500-1 10-10-422 C-F-2 C5 51 Pipe-Pipe VoVSurf - - -

.365* Exduded rWC-2500-1 10-10421 C-F-2 C5.51 Pipe-Pipe VoVSurf - - -

.365* Excluded IWC-2500-1 10-10-420 C-F-2 C5.51 Pipe-Pipe VoVSurf - - -

.365' Exduded IWG2500-1 10-10-419 C-F-2 C5.51 Pipe-Pipe VoVSurf - - -

.365" Exduded IWC-2500-1 10-10-418 C-F-2 C5.51 Pipe-Elbow Vousurf - - -

.365- Exduded IWC-2500-1 10-10-417 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.365" Exduded IWC-2500-1 10-10-416 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

.365" Excluded IWC-2500-1 10-10-415 C-F-2 C5 51 Elbow-Pipe VoVSurf - - -

.365* Exduded IWC-2500-1 10-10-414 C-F-2 C5.51 Pipe-Pipe VoVSurf - - -

.365' Exduded IWC-2500-1 10-10-413 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

.365' Exduded IWC.,-2500-1 10-10-412 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.365" Exduded IWC-2500-1 10-10-411 C-F-2 C5.51 Pipe-Pipe VoVSurf - - -

365' Excluded IWC-2500-1 10-10-411 A C-F-2 C5.51 Pipe-Flange VoVSurf - - -

.365" Exduded IWC-2500-1 Flange - - Flange Botting VT-1 - - -

<2" Exc!rded IWG2500-1 10-10-410A C-F-2 C5.51 Flange-Pipe VouSurf - - -

.365* Exduded IWG2500-1 10-10-410 C-F-2 C5.51 Pipe-Pipe VoVSurf - - -

.365' Exduded IWC-2500-1 FILE RHR02.10.WPD Page 10 - 40 of 10-92

d h James A. Fitzpatrick Nuclear Power Plant Third Inservice inspection Interval [[::JAF-ISI-0003|JAF-ISI-0003]] Date January 7,1998

$ Ten -Yearinspection Plan Revision 0 ASME WELD COMPONENT ASME ASME ISIINTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE REO PER1 PER2 PER3 THICK REMARKS CAT ITEM DESCRIPTION EXAM 10 - Residual Heat Removal System Drawing Number: MSK-3003 Line Number: 10~-W20-302-12B VT-3 RR-2 - - - - H10-353. Exduded IWC-2500-1 10-128-NN-144 F-A F120b Non Adjustable Support C5.51 P:pe-Elbow VouSurf - - - 165* Exduded IWC-2500-1 10-10409 C-F-2 C5.51 Elbow-Pipe VoFSurf - - - 365- Exduded IWC-2500-1 10-10-408 C-F-2 VouSurf - - - .365* Exduded IWC-2500-1 10-10-407 C-F-2 C5.51 Pipe-Elbow C5.51 Eibow-Pipe VoVSurf - - - .365* Exduded IWC-2500-1 10-10406 C-F-2 VouSurf - - -

.365~ Exduded I%%2500-1 10-10-405 C-F-2 C5.51 Pipe-Pepe VoC3urf - - .365* Exduded IWC-25001 C5.51 Pipe-Flange 10-10-405A C-F-2 VT-1 - - -

<2" No exams required Flange - - Flange Bolting VoVSurf - - .3G5" Exduded IWC-2500-1 C5.51 F4nge-Pipe 10-10-404A C-F-2 VouSurf - - .365* Erduded IWC-2500-1 10-10-404 C-F-2 C5.51 Pipe-Pipe -

vouSurf - .365' Exduded IWC-2500-1 C5.51 Pipe-Elbow - -

10-10-403 C-F-2 l C5.51 Elbow-Pipe VoVSurf - - - .365~ Exduded IWC-2500-1 l 10-10402 C-F-2 l

C3 20 Pen.X-398 Integral Attachment Surf RR4 - - - .305" Exduded IVC 2500-1(4) 10-10-401 C-C C3 20 Integral Attachment Surf RR-4 - - -

.500" Exduded IWC-2500-1(4) 10-10-400A C-C C5.51 Pipe-Valve MOV-31B VoVSurf - - - .365* Exduded IWC-2500-1 10-10-400 C-F-2 VT-3 RR-2 - - - H10-521. Excruded IWC-2500-1 F120b Adjustable Support 10-128-AN-143 F-A )

VT-1 - - <2" No exams required i MOV-318 - 10.0" Vafve Bolting -

f 1

l FILE- RHR02.10.WPD Page 10 -41 of 10-92 l

/y James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISt-0003|JAF-ISt-0003]] Third inservice inspection Interval Date Jaruary 7,1998 4bMW Ten -Year inspection Plan Revision 0 ASME WELD COMPONE14T ASME ASME IS! INTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE EXAM REQ PER1 PER2 PER3 THtCM REMARKS CAT ITEM DESCRIPTION 10 - Residual Heat Removal System Drawing Number: MSK-3008 Une Number: 10"-W20-302-128 VoVSurf - - - .365* Excided IWC-2500-1 10-10-399 C-F-2 C5.51 Vatve MOV-31B-Elbow Surf RR-4 - - - .500* Excluded IWC-2500-1(4) 10-10-398 C-C C3.20 Integral Attacf* ment PFSK-2393. TS Sectgm 3.6.1 I N/A Hydraulic Snubber RR - - -

MA 10-128-HS-142 RR - - - H 10 496. TS Sedion 3.6.1 10-128-HS-141 N/A N/A Hydraulic Snubber -

VouSurf - - .365~ Exduded IVC-2500-1 10-10-396 C-F-2 C5.51 Elbow-Pipe -

- Exempt rAC-1221(c) 1 1/2" Branch CuWiw.

Surf . - -

10-10-395 - -

Exempt IWC-1221(c) 2.0" Branch Connection Surf - - - -

10-10-394 - -

VouSurf - - - .365* Exduded IWC-2500-1 10-10-393 C-F-2 C5.51 Pipe-Valve MOV-268

<2* No exams requwed 10.0" Valve Botting VT-1 - - -

MOV-268 - -

.365* Excluded IWC,-2500-1 C-F-2 C5.51 Vafve MOV-268-Reducer VovSurf - - -

j 10-10-392 Une Number: 12*-W20-302-138 VoVSurf - - X .S75*

12-10-391 C-F-2 C5.51 Pipe-Reducer l

VT-3 RR-2 - - X - PF5K-2520. CC N-491-1 10-138-NS-140 F-A F1.20e Rigid Sway Strut VT-3 RR-2 - - - - Pf-oK-2334. CC N-491-1 10-13B-NS-139 FA F1.20e Rigid Sway Strut C5.51 Elbow-Pipe VoVSurf - - - .375*

12-10-390 C-F-2 VouSurf - - - .375" 12-10-389 C-F-2 C5.51 Pipe-Elbow VT-3 RR-2 - - - - PFSK-2386. CC N-491 1 10-138-NS-138 F-A F1.20b Vertical Constraint 7

FILE- RHR02.10.WPD Page .0 -42 of 10-92

b,,f O O [[::JAF-ISI-6063|JAF-ISI-6063]] O

James A. Fitzpatrick Nuclear Power Plant Date January M98 Third Inservice inspection Intervat g b Ten -Yearinspection Plan Revision 0 ASME WELD COMPONENT ASME ASME REL ISIINTERVAL LTH OR CODE CODE CODE REMAMi(5 IDENTIFICATION EXAM REQ PER1 PER2 PER3 THICK CAT ITEM .. _ DESCRIPTION _

10 - Residual Huat Removal System Drawing Number: MSK-3008 Line Number: 12"-W20-302-138 Vol/ Surf - - - .375" 12-10-388 C-F-2 C5.51 Elbuw-Pipe PFSK-2386, TS Section 3.6.1 N/A N/A Hydraulic Snubber - RR - - -

10-1138-HS-137 Surf RR-4 - - - 1.0" CC N-509 12-10-387 C-C C3.20 'ntegral Attachment Vot/ Surf - - -

.375*

12-10-386 C-F-2 C5.51 Pipe-Elbow

- Exempt IWC-1221(c) 1 1/2* Branch Oc' mction Surf - - -

12-10-385 - -

Vol/ Surf - - - .375*

12-10-384 C-F-2 35.51 Elbow-Pipt.

Vol/ Surf - - - .375*

12-10-383 C-F-2 C5.51 Pipe-Elbow

/" 3 RR-2 - - X - CC N-491-1 10-13B-NS-135 F-A F1.20b Box Constraint Surf RR-4 - - X .500" CC N-509 12-10-382 G-C C3.20 Integral Attachment VT-3 RR-2 - - - - PFSK-2523 CC N-491-1 10-13B-NS-134 F-A F1.20a Rod Hanger Vol/ Surf - - - .375" Excluded IWC-2500-1 12-10-381 C-F-2 C5.51 Pipe-Pipe RR-2 PFSK-1962, CC N-491-1 F-A F1.20b Lateral Constraint VT-3 - - - -

10-13B-NS-133 '

Vot/ Surf - -

.375*

12-10-380 C-F-2 C5.51 Elbow-Pipe -

RR-2 PFSK-1966, CC N-491-1 F-A F1.20e Rigid Sway Strut VT-3 - - - -

10-138-NS-132 Surf RR-4 - - - .216* CC N-509 12-10-379 C-C C3.20 Integrat Attachment Vol/ Surf - - - .375*

12-10-378 C-F-2 C5.51 Pipe-Elbow Surf - - - - E.empt IWC-1221(c) 12-10-377 - - 4.0" Branch Connection Page 10 - 43 of 10-92 FILE: RHR02.10.WPD

i James A. Fitzp trick Nuclear Power PI:nt [[::JAF-4SI-0003|JAF-4SI-0003]] Third Inservice inspection Interval Date January 7,1998 A M M P m er

""""' Ten - Year inspection Plan Revision D ASME WELD COMPONENT ASME ASME ISilNTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE REQ PER1 PER2 PER3 THICK REMARKS ITEM DESCRIPTION EXW.A CAT -

10 - Residual Heat Removal System ,

Drawing Number: MSK-3008 LI:- Number: 12" W20-302-138 C5.51 Elbow-Pipe vouSurf - - - .375" 12-10-376 C-F-2 Vot/ Surf - - - .375*

12-10-375 C-F-2 C5.51 Pipe-Elbow Surf - - - - Exempt IWC-1221(c) 12-10-374A - - 1 1/2" Branch Connection VT-3 RR-2 - - - - PFSK-2220. CC N-491-1 10-13B-NS-131 F-A F1.20b Box Constraint Surf RR-4 - X - 1.0" CC N-509 12-10 374 C-C C3.20 Integral Attachment VT-3 RR-2 - X - - PFSK-2225. CC N-491-1 10-138-NS-130 F-A F1,20a Rod Hanger Surf - - - - Exempt IWC-1221(c) 12-10-373 - - 1 1/2" Branch Connection C5.51 Elbow-Pipe Vol/ Surf - - - .375" 12-10-372 C-F-2 Vol/ Surf - - - .375" 12-10-371 C-F-2 C5.51 Pipe-Elbow VT-3 RR-2 - - - - PFSK-2457. CC N-491-1 10-13B-NS-129 F-A F1.20b Box Constraint Surf RR-4 - - -

.500" CC N-509 12-10-370 C-C C3.20 Integral Attachment C5.51 Elbow-Pipe Vol/ Surf - - - .375" 12-10-369 C-F-2 Vol/ Surf - - - .375" 12-10-3G8 C-F-2 C5.51 Pipe-Elbow VT-3 RR-2 - - - - PFSK-2487. CC N-491-1 10-138-NS-127 F-A F1.20e Rigid Sway Strut RR-4 .375" un finished support. Gr iM09 C-C C3.20 Integral Attachmant Surf - - -

12-10-3678 RR-2 PFSK-1956. Ct, W.81-1 F-A F1.20b Vertical Support VT-3 - - - -

10-138-NS-126 RR-4 .500" unfinished support. CO N-SCG C-C C3.20 Integral Attachment Surf - - -

12-10-367A Page 10 - 44 of 10-92 FILE: RHR02.10.WPD

O O James A. Fitzpatrick Nucle:r Power Picnt [[::JAF-ISI-0003|JAF-ISI-0003]] O

Third Inservice inspection interval Date January 7,1998 g M Ten -YearInspection Plan Revision 0 ASME WELD COMPONENT ASME ASME REL ISIINTERVAL LTH OR COD 8E IDENTIFICATlON CODE CODE REQ PER1 PER2 PER3 THICK REMARKS ITEM DESCR!PTION EXAM CAT 10 - Residual Heat Rernoval System Dr wing Number: MSK 3008 Line Number: 12"-W20-302-13B Vot/ Surf - - - .375" 12-10-367 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - .375" C5.51 Elbow-Pipe 12-10-366 C-F-2 Vol/ Surf - - - .375" Excluded IWC-2500-1 12-10-365 C-F-2 C5.51 Pipe-Pipe Une Number: 16"-W20-302-158 RR-4 - Reenforcing Pad CC N-509 C-C C3.20 Integral Attachment Surf - - -

16-10-362A Surf - - - - Inaccestible 16-10-362 C-F-2 C5.81 12.0" Branch Connection

- <2" No exam required 12.0* Valve Botting VT-1 - -

MOV-398 - -

Vol/ Surf - - - .500" 16-10-364 C-F-2 C5.51 Pipe-Va!ve MOV-39B l

Surf RR4 - - - .500" CC N-509 16-10-364B C-C C3.20 Integra! Attachment l PFSK-2570, CC N-491-1 F1.20b Vertical Constraint VT-3 RR-2 - - - -

10-158-NS-125A F-A RR - - - PFSK-1949, TS Section 3.6.1 10-158-NS-125 N/A N/A Mechanical Snubber -

RR - - - PFSK-1949. TS Section 3.6.1 10-158-MS-1258 N/A N/A Mechanical Snubber -

1 Surf - - - - Exempt IWC-1221(c) 16-10-363 - - 1 1/2" Branch Connection RR-4 reenforcing Pad. CC N-509 C-C C3.20 Integral Attachment Surf - - - -

16-10-362C RR-2 X .500" PFSK-2573, CC N-491-1 F-A F1.20b Vertical Constraint VT-3 - -

10-15B-NS-124A RR - - - PFSK-1953. TS Section 3.6.1 10-158-rJS-124 N/A N/A Mechanical Snubber -

RR - - - PFSK-1953. TS Section 3.6.1 10-158-NS-124B N/A N/A Mechanical Snubber -

Page 10 - 45 of 10-92 FILE: RHR02.10.WPD

O O J mes A. Fitzpatrick Nucle:r Power Picnt [[::JAF-ISI-0003|JAF-ISI-0003]] O

Third Inservice inspection Interval Date January 7,1998 g Per Ten -Yearinspection Plan Revision 0 ASME WELD COMPONENT ASME ASME REL ISilNTERVAL LTH OR CODE CODE CODE REMARKS IDENTIFICATION DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK CAT ITEM 10 - Residual Heat Removal System Drawing Number: MSK-3008 Line Number: 16"-W20-302-158 Surf RR-4 - - - .500" CC N-509 16-10-362B C-C C" 0 Integral Attachment

.500" PFSK-5678, CC N 491-1 F1.20b Vertical Suppart VT-3 RR-2 - - -

10-158-NS-123 F-A Vol/ Surf - - - .500" Excluded IWC-2500-1 16-10-361 C-F-2 C5.51 Pipe-Pipe Surf RR4 - - -

1.0" CC N-509 16-10-360A C-C C3.20 Integrat Attachment RR - - - PFSK-2107. TS Sectran 3.6.1 10-15B-NS-122 N/A N/A Hydraufic Snubber -

Surf RR-4 - - - .750" CC N-509 16-10-3608 C-C C3.20 Integral Attachment RR - - - PFSK-2558.TS Section 3.6.1 10-158-HS-121 N/A N/A Hydraulic Snubber -

Vol/ Surf - -

.500" C5.51 Elbow-Pipe 16-10-360 C-F-2 Vol/ Surf - - - .500" 16-10-359 C-F-2 C5.51 Pipe-Elbow Surf RR-4 - - -

.500* CC N-509 16-10-358A C-C C3.20 Integral Attachment RR-2 .500* PFSK-2434, CC N-491-1 F-A F1.20b Vertical Support VT-3 - .- -

10-158-NS-120 C5.51 Elbow-Pipe Vot/ Surf - - - .500" 16-10-358 C-F-2 Surf RR-4 - - .750" CC'N-509 16-10-356 C-C C3.20 Integral Attachment RR - - - PFSK-2535. TS Section 3.6.1 10-15B-NS-1198 N/A N/A Hydraulic Snubber -

RR - -

.750" PFSK-2534. TS Section 3.6.1 10-158-NS-119A N/A N/A Mechanical Snubber -

Vol/ Surf - - - .500" 16-10-357 C-F-2 C5.51 Pipe-Elbow C5.51 Elbow-Pipe Vol/ Surf - - - .500" 16-10-355 C-F-2 Page 10 - 46 of 10-92 FILE: RHR02.10.WPD

T James A. Fitzpatrick Nucle:r Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third Inservice inspection Interval Date January 7,1998 h Revision 0

$h Ten - Year inspecLon Plan ASME WELD COMPONENT ASME ASME REL ISalNTERVAL LTH OR CODE CODE REMARKS IDENTIFICATION CODE EXAM REQ PER1 PER2 PER3 THICK CAT ITEM DESCRIPTION 10 - Residual Heat Removat System Dr: wing Number- MSK-3008 Line Number: 16" W20-302-15B Vol/ Surf - - -

.500*

16-10-354 C-F-2 C5.51 Elbow-Elbow Vol/SLvf - - - .500" 18-10-353 C-F-2 C5.51 Pipe-Elbow

?

l l

I Page 10 - 47 of 10-92 FILE: RHR02.10.WPD

< ,e V' v V James A. Fitzpatrick Nuclear Pov er Plant [[::JAF-ISI-0003|JAF-ISI-0003]] b

$ Third Inservice Inspection interval Ten - Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ~ ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THtCK REMARKS i

10 - Residual Heat Removal System Drawing Number: MSK-3009 Line Number: 20"-W20-152-2B 20-10-892 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.375" Excluded IVC-2500-1 20-10-891 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.375" Excluded FWC-2500-1 20-10-890A C-C C3.20 integral Attachment Surf RR-4 - - -

.500" CC N.509 10-2B-NS-163 F-A F1.20e Rigid Sway Strut VT-3 RR-2 - - -

.500" H10-16. CC N-491-1 20-10-890 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.375" Excluded IVE-2500-1 20-10-8898 C-F-2 C5.51 Pipe-Pipe Vot/Surt - - -

.375" Exc!uded IWC-2500-1 10-2B-HS-161 N/A N/A Hydraulic Snubber -

RR - - -

PFSK-2567/JAF#261. TS Section 3.6.1 20-10-889A C-C C3.20 Integra! Attachment Surf RR-4 - - - .750" CC N-509 10-28-HS-162 N/A N/A Hydraulic Snubber -

RR - -

.750" PFSK-2112/JAF#219. TS Section 3.6.1 20-10-889 C-C C3.20 Integral Attachment Surf RR-4 - - -

.28" CC N-509 10-2B-AS-160 F-A F1.20c Variable Spring VT-3 RR-2 - - -

.28" PFSK-2077. C N-491-1 20-10-888 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.375" Excluded IWC-2500-1 20-10-857 C-F-2 C5.81 8.0" Branch Connection Surf - - - -

20-10-856 - -

1.5" Branch connection Surf - - - - Exempt IWC-1221(c) 20-10-8558 C-C C3.20 Integral Attachment Surf RR-4 - - -

.28" CC N-509 10-28-HS-159A N/A N/A Hydraulic Snubber - RR - - - TS Section 3.61 20-10-855A C-C C3.20 Integral Attachment Surf RR-4 - - -

.28" CC N-509 FILE: RHR02.10.WPD Page 10 - 48 of 10-92

a James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Date January 7,1998 Third Inservice Inspection Interval g Pimer Ten -Yearinspection Plan Revision 0 ASME WELD COMPONENT ASME ASME ISilNTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE REQ PER1 PER2 PER3 THICK REMARKS CAT ITEM DESCRIPTION EXAM 10 -Residual Heat Removal System Drawing Number: MSK-3009 Une Number: 20"-W20-152-2B RR-2 .28" PFSK-2020, CC N-491-1 F.A F1.20c Variable Spring VT-3 - - -

10-2B-AS-159 Vol/ Surf - - X 375*

20-10-855 C-F-2 C5.51 Tee-Pipe Vol/ Surf - - X .375" 20-10-854 C-F-2 C5.51 Pipe-Tee i C5.51 Elbow-Pipe Vo8/ Surf - - -

.375*

20-10-853 C-F-2 RR-2 - H10-21 A, CC N-491-1 F-A F1.20b Adjustabfe VT-3 - - -

10-28-AN-158 Vot/ Surf - - - .375" 20-10-852 C-F-2 C5.51 Pipe-Elbow C5.51 Valve MOV-158 -Pipe Vot/ Surf - - -

.375*

20-10-851 C-F-2

<2* No welds in valve, botting <2.0*

- 20.0" Valve Bolting VT-1 - - -

MOV-158 -

C5.51 Pipe-Valve MOV-15B Vol/ Surf - - -

.375*

20-10-849B C-F-2 VT-3 RR-2 X - - .75* H10-22 CC N-491-1 10-28-AN-157 F-A F1.20b Adjustable Vot/ Surf - - - .375*

20-10-849 C-F-2 C5.51 Pipe-Elbow Surf RR-4 X - - .750* CC N-509 20-10-849A C-C C3.20 Integral Attachment Surf - - - - Exempt IWC-1221(c) 20-10-848 - - 1.0" Branch Connection i Surf - - - - Exempt IWC-1221(c) 20-10-847 - - 3/4" Branch Connection l C-F-2 C5.51 Tee-Pipe Vol/ Surf - - -

20-10-846 Surf - - - - Exempt IWC-1221(c) 20-10-845 - - 3/4* Branch Connection FILE: RHR02.10.WPD Page 10 - 49 of 10-92

O.~. J mes A. Fitzpatrick Nuclect Power PI:nt [[::JAF-ISI-0003|JAF-ISI-0003]] Third inservice inspection Interval Date January 7,1998 h

$ Ten -Year Inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME ISilNTERVAL LTH OR CODE REL IDEN7IFICATION CODE CODE PER1 PER2 PER3 TH!CK REMARKS ITEM DESCRIPTION EXAM REQ CAT 10 - Residual Heat Removal Systent Drawing Number: MSK-3009 Line Number: 24"-W20-152-38 From Suppression Chamber to RHR Pump 10P-3B Surf - - - .375" 24-10-800 C-C C320 Pipe-Pen. X-225B Weld Vol/ Surf X - -

.375" 24-10-801 C-F-2 C5.51 Pipe-Vafve MOV-151B

<2* No welds in valve, botting <2.0*

24.0" Vafve Bolting VT-1 - - -

MOV-151B - -

Vol/ Surf - - - .375" 24-10-802 C-F-2 C5.51 Valve MOV-1518 -Elbow Vot/ Surf - - - .375" 24-10-803 C-F-2 C5.51 Elbow-Pipe

- Exempt IWC-1221(c) 1.5" Branch Connection Surf - - -

24-10-804 - -

RR-2 PFSK-z270, CC N 491-1 F-A F1.20d Sliding Base Support VT-3 - - - -

10-3B-NS-150 Vol/ Surf - - - .375" Excluded IWC-2500-1 24-10-805 C-F-2 C5.51 Fipe-Pipe Vol/ Surf - - - .375*

24-10-806 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - .375" C5.51 Erbow-Pipe 24-10-807 C-F-2 RR-2 PSFK-1854, CC N-491-1 F-A F1.20c Variable Spring VT-3 - - - -

10-38-AS-151 Vol/ Surf - - - 375* Exq!uded IWC-2500-1 24-10-808 C-F-2 C5.51 Pipe-Pipe Surf - - - - Exempt IVC-1221(c) 24-10-809 - - 1.5" Branch Connection RR-2 .625" PFSK-2009, CC N-491-F-A F1.20b Rigid Support VT-3 - - -

10-3B-NS-152 Surf RR-4 - - - .625" CC N-509 24-10-810 C-C C3.20 Integral Attachment PSFK-1936/JAF#268, TS Section 3.6.1 N/A Hydraulic Snubber - RR - - -

10-3B-HS-153 N/A FILE: RHR02.10.YPD Page 10 - 50 of 10-92

, s f3

\. N James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] N3w M Pomr Thirrl inservice inspection Interval Date January 7,1998 Ten - Year inspection Plan Revision 0 COMPONCNT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRtPTION EXAM REO PER1 PER2 PER3 THICK REMARKS 10 - Residual Heat Removal System Drawing Number: MSK-3009 Line Number: 24"-W20-152-3B 10-38-NS-154 N/A N/A Hydraulic Snubber -

RR - - -

PFSK-2072/JAF#328. TS Section 3 6.1 24-10-811 C-F-2 C5.51 Pipe-Tee VoVSurf - - -

.375" 24-10-812 - -

2.0" Branch Connection Surf - - - - Exempt IWC-1221(c) 24-10-835 C-F-2 C5.51 Tee-Pipe VoVSurf - - -

.37" 24-10-836 C-F-2 C5,51 Pipe-Reducer VoVSurf - - -

.375" Line Number: 20*-W20-152-6B 20-10-837 C-F-2 C5.51 Recucer-Elbow VoUSurf - - -

.375" 10-68-AS-156 F- A F1.20e Variable Spring VT-3 RR-2 - - - -

PFSK-2065 CC N-491-1 20-10-838 C-F-2 C5.51 Elbow-Valve MOV-13B Vol/ Surf - - -

.375" MOV-138 - - 20.0" Valve Botting VT-1 - - - - No weids in valve, botting <2.0" 20-10-839 C-F-2 C5.51 Valve MOV-138-Tee VoUSurf - - -

.375" l

20-10-840 - -

4.0" Branch Connection Surf - - - -

Exempt IWC-1221(c) 20-10-841 C-F-2 C5.51 Tee-Flange Vol/ Surf - - -

.375" l FLANGE - -

Flange Bolting - - - -

< 2.0" Excluded IWC-2500-1 20-10-842 C-F-2 C5.51 Pipe-Pipe VoUSurf - - -

.375" Excluded IWC-2500-1 20-10-842A C-F-2 C5.51 Flanga-Pipe VoVSurf - - -

.375" l

l 20-10-843 C-F-2 C5.51 Pipe-Pipe VoUSurf - - -

.375" Excluded IWC-2500-1 FILE: RHR02.10.WPD Page 10 - 51 of 10-92 i

O James A. Fitzpatrick Nuclecr Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] O '

Third inservice Inspection interval Date January 7,1998 g PDMI Ten -YearInspection Plan Revision D ASME WELD COMPONENT ASME ASME ISilNTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE REO PER1 PER2 PER3 THICK REMARKS CAT ITEM DESCRIPTION EXAM 9

10 - Residual Heat Removal System Dr wing Number: MSK-3009 Une Number: 20"-W20-152-6B VouSurf - - - .375" 20-10-843A C-F-2 C5.51 Pipe-Flange

- - - < 2.0* Excluded ?WC-2500-1 Flange Botting FLANGE - -

Vol/ Surf - X .375* Terminal End 20-10-844 C-F-2 C5.51 Flange-Pipe -

I ir.e No. 20"-W20-152-6D to RHR Pump 10P-3D C5.51 Tee-Pipe VoVSurf - - - .375*

20-10-814 C-F-2 C5_51 Pipe-Valve MOV-13D VoVSurf - - - .375" 20-10-815 C-F-2 VT-1 - - - No welds in valve, botting <2.0" MOV-13D - - 20 0" Valve Bolting -

C-F-2 C5.51 Valve MOV-13D - Tee Vol/ Surf - - -

20-10-81G Surf - - - - Exempt IWC-1221(c) 20-10-817 - - 4.0* Branch Connection C5.51 Tee-Flange VoVSurf - - - .375*

20-10-818 C-F-2

- - - < 2.0" No Exam Required FLANGE - - Flange Bolting -

C5.51 Pipe-Flange VoUSurf - - -

.375* ,

20-10-819A C-F;2 Vot/ Surf - -

.375" Excluded FAC-2500-1 C5.51 Pipe-Pipe 20-10-819 C-F-2 VoVSurf - - .375" Excluded IWC-2500-1 C5.51 Pipe-Pipe 20-10-820 C-F-2 VoUSurf - - -

.375*

20-10-820A C-F-2 C5.51 Pipe-Flange

- - - <2.0" No Exam Required FLANGE - - Flange Botting -

VoVSurf - X - .375" Terminal End 20-10-821 C-F-2 C5.51 Flange-RHR Ht. Ex.

FILE: RHR02.10.WPD Page 10 - 52 of 10-92

? I i )

'% / % Q James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Pomr gh Third Inservice inspection Interval Ten - Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISi tNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 10 - Residual Heat Removal System Drawing Number- MSK-3009 Une Number: 20"-W20-152-2D 20-10-822 - -

3/4" Branch Connection Surf - - - - Exempt IWC-1221(c) 10-2D-AN-155 F-A F1.20b Adjustable VT-3 RR-2 - - -

.625" H10-23 CC N-491-1 20-10-823 C-F-2 C5.51 Tee-Elbow Vol/ Surf - - -

375*

20-10-823A C-C C3.20 Integral Attachfrent Surf RR-4 - - -

.625" CC N-509 20-10-824 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.375*

20-10-825 C-F-2 C5.51 Pipe-Elbow Vol/ Surf -

X - 375" 20-10-826 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.375' 20-10-827 - -

3/4' Branch Connection Surf - - - - Exempt IVE,-1221(c) 20-10-828 - - 1.0" Branch Connection Surf - - - - Exempt IWC-1221(c) 20-10-829 C-F-2 C5.51 Pipe-Valve MOV-15D Vol/ Surf - - - -

375" MOV-15D - -

20.0" Valve Bciting VT-1 - - - - -

No welds in valve, bolting <2.0" 20-10-830 C-F-2 C5.51 Vafve MOV-15D-Pipe Vol/ Surf - - - -

375" 20-10-831 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - - -

.375' Exduded IWC-2500-1 20-10-832 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - - -

375" 20-10-833 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - - -

375" 20-10-834 C-F-2 C5.G1 Pipe-Tee Vol/ Surf - - - -

.375*

FILE: RHR02.10.VFD Page 10 - 53 of 10-92

i James A. Fitzpatrick Nucle:r Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third Inservice Inspection interval Date January 7,1998 h

$ Ten - Year Inspection Plan Revision 0 ASME WELD C W ONENT ASME ASME ISIINTERVAL LTH OR CODE CODE REL

t . FICATION CODE EXAM REQ PER1 PER2 PER3 THfCM REMARKS CAT ITEM DESCRIPTION

m. ,

10 - Residual Heat Removat System Drawing Number: MSK-3009 t ine No. 8"-W20-152-39 VoVSurf - - -

.322* Excluded IWC-2500-1 8-10-858 C-F-2 C5.51 Pipe-Flange

<2.0" No Exam Required FLANGE - - Flange Botting -

Vot/ Surf - - -

.322" Excluded IWC-2500-1 8-10-859 C-F-2 C5.51 Flange-Elbow Suri - - - - Exempt IWC-1221(c) 0-10-86C - - 3/4" Branch Connection VoUSurf - - .322" Excluded IWC-2500-1 C5.51 Elbow-Pipe 8-10-861 C-F-2 VoUSurf - - - .322" Excluded IWC-2500-1 8-10-862 C-F-2 C5 51 Pipe-Pipe RR-2 PFSK-2187, CC N-491-1 F-A F1.20e Rigid Sway Strut VT-3 - - - -

10-39-NS-164 Surf RR-4 - - - .750" CC N-509 8-10-862B C-C C3.20 Integra! Attachment VT-3 RR-2 - - -

.750" PFSK-1005. CC N-491-1 10-39-AN-165 F-A F1.20c Variable Spring Vol/ Surf - - .322* Excluded IVE-2500-1 C5.51 Pipe-Elbow 8-10-863 C-F-2 VoUSurf - -

.322" Excluded IWC-25do-1 8-10-864 C-F-2 C5.51 E! boa-Pipe -

Vot/ Surf - -

.322" Exduded MC-2500-1 8-10-865 C-F-2 C5.51 Pipe-Elbow -

VouSurf - - -

.322" Excluded IWC-2500-1 8-10-866 C-F-2 C5.51 Elbow-Pioe Surf RR-4 - - - .500* Excluded MC-2500-1(1)(c) 8-10-868 C-C C3.20 Integra! Attachment VT-3 RR-2 - - - .500* PFSK-770 10-39-NN-167 F-A F1.20b Box Constraint VoUSurf - - - .322" Excluded IWC-2500-1 8-10-867 C-F-2 C5.51 Pipe-Pipe Surf RR-4 - - - .216* Excluded IWC-2500-1(1)(c) 8-10-868B C-C C3.20 Integral Attachment FILE: RHR02.10.WPD Page 10 - 54 of 10-92

0 Y, %..Y James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] g Pour Third inservice inspection Interval Ten - Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITE31 DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARMS 10 - Residual Heat Removal Syste n Drawing Number: MSK-3009 t.ine Number: 8" W20-152-39 10-39-HS-166A N/A N/A Hydraufic Snubber VT-3 RR - - .216" PFSK-2456. TS Section 3.6.1 8-10-868A C-C C3.20 Integral Attachment Surf RR-4 - - -

.216" Exduded iWC-2500-1(1)(c) 10-39-HS-166 N/A N/A Hydraulic Snubber -

RR - -

216" PFSK-2456/154. TS Sechon 3.6.1 8-10-869 C-C C3.20 Integral Attachment Surf RR-4 - - - 237" Exduded IWC-2500-1(1)(c) 10-39-NS-168 F-A F1.20b Lateral Support VT-3 RR-2 - - -

.237" PFSK-2468 8-10-870 C-C C3.20 Integral Attachment Surf RR-4 - - -

.750" No Exam Raquired 10-39-AS-169 F-C F1.20c Variable Spring VT-3 RR-2 - - -

.750" PFSK-2149 8-10-871 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.322" Exduded IWC-2500-1 8-10-872 C-F-2 C5.51 Elbow-Elbow Vol/ Surf - - - .322" Exduded IWC-2500-1 8-10-873 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.322* Exduded IWC-2500-1 10-39-HS-170 F-A F1.20b Lateral Support VT-3 RR-2 - - - -

PFSK-1923 8-10-874 - -

1.5" Branch Connection Surf - - - - Exempt IWC-1221(c) 8-10-875 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.322" Exc'fuded IWC-2500-1 8-10-876 C-F-2 C5.51 Elbow-Pipe Vot/ Surf - - - .322" Exduded IWC-2500-1 8-10-877 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.322" Exduded IWC-2500-1 8-10-878 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.322" Exduded IWC-2500-1 10-39-AN-171 F-A F1.20c Variable Spring VT-3 RR-2 - - - -

PFSK-1003 FILE: RHR02.10.WPD Page 10 - 55 of 10-92

James itzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

$bM Third inservice Inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ~ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI LNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THtCK REMARKS I

10 - Residual Heat Removal System Drawing Number: MSK-3009 Une Number: 8"-W20-152-39 B-10-879 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.322" Exduded IWC-2500-1 8-10-880 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.322" Exduded IWC-2500-1 10-39-NS-172 F-A F120b Vertical Support VT-3 RR-2 - - - -

PFSK-1934 10-39-NS-173 F-A F1.20e Rigid Sway Strut VT-3 RR-2 - - - - PFSK-2489 10-39-NS-174 F-A F1.20a Rod Hanger VT-3 RR-2 - - - - PFSK-2281 8-10-881 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.322" Exduded IV&2500-1 10-39-NS-175 F-A F120b Lateral support VT-3 RR-2 - - - -

PFSK-1982 8-10-882 C-F-2 C551 Elbow-Pipe Vol/ Surf - - -

.322* Exduded lVC2500-1 8-10-8828 C-C C3 20 Integral Attachment Surf RR-4 - - -

.322" Exduded IWC-2500-1(1)(c) 10-39-NS-176 F-A F1.20b t.nchor VT-3 RR-2 - - -

.250" PFSK-2302 8-10-083 C-C C3.20 Integral Attachment Surf RR-4 - - -

.250" Excluded IWC-2500-1(1)(c) 8-10-884 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - - .322" Exduded IWC-2500-1 8-10-885 - - 1.0" Branch Connechon Surf - - - - Exempt IYC1221(b) 8-10-866 C-F-2 C5.51 Pipe-Valve FPC-34 Vol/ Surf - - -

.322" Exduded IWC-2500-1 FPC-34 - - 8.0" Valve Botting VT-1 - - -

<2* Class 3 Break FILE: RHR02.10.WPD Page 10 - E6 of 10-92

( ( )

NJ J

%,)' Qt James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h

$ Third Inservice Inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD tDENT1FICATION CODE CODE CODE REL ISIINTERVAL 1 TH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 10 - Residual Heat Removal System Drawing Number: MSK-3010 t.ine Number. 20"-W20-152-2B 20-10-893 - -

1.5" Branch Connection Surf - - -

1.5" Exempt IWC-1221(c) 20-10-893A C-C C3.20 Integral Attachment Surf RR-4 - - -

.28" CC N-509 10-28-AS-180 F-A F1.20c Variable Spring VT-3 RR-2 - - -

.28- PFSK-214. CC N-491-1 20-10-8958 C-C C320 Integra! Attachment Surf RR-4 - - -

.28* CC N-509 10-28-NS-181 F-A F1.20b Vertical Constraint VT-3 RR-2 X - -

.2S" H10-15. CC N-491 1 20-10-894 C-F-2 C5.51 Pipe-Fipe Vol/ Surf - - -

.375 Excluded IWC-2500-1 10-2844S-182 F-A F120b Vertical Constraint VT-3 RR-2 - X -

.28" PFSK-2078. CC N-491-1 20-10-894A C-C C3.20 Integra! Atta+ ment Surf RR-4 - - -

.28* CC N-509 20-10-895 C-F-2 C531 Pipe-Pipe Vot/ Surf - - -

.375' Excluded IWC-2500-1 10-28-NS-182A F-A F1.20b Box Constraint VT-3 RR-2 - - - -

CC N-491-1 20-10 896 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.375" Excluded IWC-2500-1 Line Number: 20"-W20-152-2C 20-10-897 - -

2.0" Dranch Connectkm Surf - - -

2.0" Exempt IWC-1221(c) 10 NS-183 F-A F1.20b Vertical Constraint VT-3 RR-2 -

X -

.500" PFSK-2387. CC N-491-1 20-10-897A C-C C3.20 Integral Attachment Surf RR-4 - - -

.500" CC N-509 20-10-898 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.375" Excluded IWC-25CD-1 20-10-899 - -

1.0" Branch Connection Surf - - -

1.0" Exempt IE1221(c) 20-10-900 - -

3/4" Branch Connection Surf - - -

.750" Exempt IWC-1221(c)

FILE: RHR02.10.WPD Page 10 - 57 of 10-92

Y]

James d.~ Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h Third inservice Inspection Interval Date January 7,1998 g Nem Ten - Year inspection Plan Revision 0 COMPONENT A3ME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 TH1CK REMARKS I 10 - Residual Heat Removal System Drawing Nuruber: MSK-3010 Line Number: 20"-W20-152-2C 10-2C-NS-183A F-A F120b Box Constraiat VT-3 RR-2 - -

X - PFSK-2053, CC N-491-1 20-10-901 C-C C320 Integrai Attachment Surf RR-4 - - -

.500" CC N-509 10-2C-AN-184 F-A F1.20b Vertical Constraint VT-3 RR-2 X - -

.500* H10-13A, CC N-491 1 20-10-902 C-F-2 C5 51 Pipe-Pipe Vot/ Surf - - -

.375' Excluded iWC-2500-1 20-10-902C C-C C3.20 Integral Attachment Surf RR-4 - - -

28" CC N-509 10-2C-NS-184A F-A F1.20b Vertical Ccnstraint VT-3 RR-2 - - -

.28- PFSK-2084, CC N-491-1 20-10-002A C-C C3.20 Integral Attachment Surf RR-4 - - -

28* CC N-509 10-2C-NS-185 F-A F1.20bBox Constraint VT-3 RR-2 - - - -

CC N-491 1 20-10-902B C-C C3.20 Integral Attachment Surf RR-4 - - -

1.0" CC N-509 10-2C-HS-186A N/A N/A Hydraulic Snubber VT-3 RR - -

1.0" PFSK-1971/JAF#826. TS Section 3.6.1 10-2C-HS-1868 N/A N/A Hydraulic Snubber VT-3 RR - -

1.0" PFSK-1971/JAF#831. TS Section 3.6.1 10-2C-HS-187 N/A N/A Hydraulic Snubber VT-3 RR - -

1.0" PFSK-2129/JAF#280, TS Section 3.6.1 10-2C-HS-188 F-A F1.20e Rigid Sway Strut VT-3 RR-2 - - - -

PFSK-2110, CC N-491-1 20-10-903 C-F-2 C5.51 Pipe Pipe Vot/ Surf - - -

.375" Excluded IWC-2500-1 20-10-903A C-C C320 Integra! Attachment Surf RR-4 - - -

.500" Excluded IWC-2500-1(1)(c) 10-2C-AS-189 F-A F1.20c Variable Spring VT-3 RR-2 - - -

.500" PFSK-2513, CC N-491-1 10-2C-NS-190 F-A F1.20e Rigid Sway Strut VT-3 RR-2 - - - -

PFSK-2560 CC N-491-1 FILE: RHR02.10.WPD Page 10 - 58 of 10-92

c. ,.

James A. Fitzpatrick Nuclear Power Plant [[::JAF-131-0003|JAF-131-0003]] g P e er Third Inservice Inspection Interval Ten - Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME A',ME WELD IDENTIFICATION CODE CODE CODE REL ISi tNTERVAL LTH OR CAT IMM DESCRIPTION EXAM REQ PER1 PER2 PER3 THtCK REMARK 3 1

10 - Residual Heat Removal System Drawing Number: MSK-3010 Line Number: 20"-W20-152-20 20-10-904 - -

3/4" Branch Connection Surf - - -

.750" Exempt IWC-1221(c) 20-10-905 C-F-2 C5.51 Pipe-Tee Vol/ Surf - - -

.375" 20-10-926 C-C C3.20 Integral Attachment Surf RR-4 - - - .500" CC N-509 10-2C-AN-191 F-A F1.20b Vertical Support VT-3 RR-2 - - -

.500 PFSK-624. CC N-491-1 20-10-927 C-F-2 C5.51 Tee-Pipe Vot/ Surf - - -

.375*

20-10-928 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.375*

10-20-AN-192 F-A F1.20b Vertical Support VT-3 RR-2 - - -

.500" CC N-491-1 20-10-929 C-F-2 C5.51 Elbc y-Pipe Vol/ Surf - - -

.375" 20-10-931 C-F-2 C5.51 Pipe-Valve MOV-15C Vol/ Surf - - -

.375" MOV-15C - - 20" Valve Botting VT-1 - - - No exam required i

l 20-10-932 C-F-2 C5.51 Va!ve MOV15C-Elbcw Vol/ Surf - - -

.375" l 20-10-932A C-C C3.20 Integral Attachment Surf RR-4 - - -

.250" CC N-509 10-2C-AN-193 F-A F1.20b Adjustable ':-0 RR-2 - - -

.250" H1d-7. CC N-491-1 l 20-10-933 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.375" 20-10-934 - -

1.0" Branch Connection Surf - - -

1.0" Exempt IWC-1221(c) 20-10-935 - -

3/4" Branch Connedion Surf - - -

.750" Exempt IWC-1221(c) 20-10-936 C-F-2 C5.51 Pipe-Tee Vol/ Surf - - -

.375" 20-10-937 - -

3/4" Branch Connection Surf - - -

.750" Exempt IWC-1221(c) l l

FILE: RHR02.10.WPD Page 10 - 59 of 10-92

V x)

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] V

A New M W Third Inservice inspection Interval Cate January 7,1998 4 Ten -Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISitNTERVAL LTH OR CAT ITEM DESCR!PTION EXAM REQ PER1 PER2 PER3 THfCK REMARMS E

10 - Residual Heat Removal System ;

Drawing Number: MSK-3010 Une Number: 20"-W20-152-2C 20-10-937A - -

4.0" Branch Connechon Surf - - - 4.0" Exempt IWC-1221(c)

Une Number: 20*-W20-152-6C 20-10-942 C-F-2 C5.51 Flange-RHR Pump 10P-3C Vol/ Surf X - - .375" Terminal End. From RHR Pump 10P-3C Flange N/A N/A Flange Botting VT-1 - - -

<2" Exduded IWC-2500-1 20-10-941 A C-F-2 C5.51 Flange-Pipe Vol/ Surf - - -

375*

20-10-941 C-F-2 C5.51 Pipe-Pipe Vot/ Surf - - -

.375" Exduded IWC-2500-1 20-10-940 - -

3/4" Branch Connedion Surf - - - .750" Exduded IWC-2500-1 20-10-939 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.375" Exduded IWC-2500-1 20-10-938A C-F-2 C5.51 Pipe-Flange VotiSurf - - -

.375" Flange N/A N/A Flange Bolting N/A - - -

<2" Exduded IWC-2500-1 20-10-938 C-F-2 C5.51 Tee-Flange Vol/ Surf - - - .375" 20-10-944A C-F-2 C5.51 Tee-Valve MOV-13C Vol/ Surf - - -

.375" MOV-13C - -

20" Valve Botting VT-1 - - -

20" No' exam require <1 20-10-944 C-F-2 C5.51 Valve MOV-13C - Pipe Vot/ Surf - - -

.375" 20-10 945 C-F-2 C5.51 Pipe-Tee Vot/ Surf - - -

.375" FILE: RHR02.10NVPD Page 10 - 60 of 10-92

p ,. m 0 N.

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h

$ Third inservice inspection Interval Ten - Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL IS!!NTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THfCK REMARKS 10 - Residual Heat Removal System Drawing Number: MSK-3010 Line Number- 20"-W20-152-2A 20-10-906 C-F-2 C5.51 Tee-Pipe VoVSurf X - -

.375" 20-10-907 C-F-2 C5.51 Pipe-Tee Vol/ Surf - - -

.375" 20-10-908 C-F-2 C5.51 Elbow-Valve MOV-15A VoVSurf - - - .375*

MOV-15A - - 20" Valve Botting VT-1 - - -

20" No exam required 20-10-909 C-F-2 C5.51 Valve MOV-15A - Pipe VoVSurf - - -

.375" 20-10-910 - -

1.0" Branch Connection Surf - - -

1.0" Exempt IWC-1221(c) 20-10-911 - - 3/4" Branch Connection Surf - - - .750" Exempt rWC-1221(c) 20-10-912 C-F-2 C5.51 Reducer-Elbow VoVSurf - - -

.375" 20-10-913 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

.375" 20-10-914 C-F-2 C5.51 Eibow-Pipe VoVSurf - - -

.375*

l 10-2A-AN-194 F-A F1.20c Variable Spring VT-3 RR-2 - - -

.625" H10-8. CC N-491-1 20-10-914A C-C C3.20 Integral Attachment Surf RR-4 - - -

.635" CC N-509 20-10-915 C-F-2 C5.51 Elbow-Tee Vol/ Surf - - -

.375" 20-10-916A - - 4.0" Branch Connection Surf - - -

4.0" Exempt IWC-1221(c) l 10-10-921 C-F-2 C5.51 Flange-Pump 10P-3A VoVSurf - - -

.375" Flange - - Flange Bolting VT-1 - - -

<2" Excluded IVC 2500-1 i 20-10-920A C-F-2 C5.51 Pipe-Flange Vol/ Surf - - -

.375" FILE: RHR02.10.WPD Page 10 - 61 of 10-92

y --.

v s .- g James A. Fitzpatrick Nuclerr Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h Thirt! inservice inspection Inte: val Date January 7,1998

$New Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 8TR2 PER3 THICK REMARKS 10 - Residual Heat Removal System Drawing Number: MSK-3010 Line Number: 20" W20-152-2A 20-10-920 C-F-2 C5.51 Pipe-Pipe Vot/ Surf - - -

.375" Excluded iWC-2500-1 20-10-919 - - 3/4" Branch Constection Surf -- - -

.750" Exempt IVC-1221(c) 20-10-918 C-F-2 C5.51 Pipe-Pipe Vof/ Surf - - -

.375" Exc!uded IWC-2500-1 20-10-917A C-F-2 C5.51 Flange-Pipe Vol/ Surf - - - .375" Flange - -

Flange Bolting VT-1 - - - <2" Excluded !WC-2500-1 20-10-917 C-F-2 C5.51 Tee-Pipe Vot/ Surf - - -

.375" 20-10-922 C-F-2 C5.51 Tee-Valve MOV-13A Vol/ Surf - - - .375" MOV-13A - - 20" Valve Botting VT-1 - - - 20" No exams required 20-10-923 C-F-2 C5.51 Valve MOV-13A -Elbow Vol/ Surf - - -

.375" Line Number: 20"-W20-152-6A 10-6A-AS-195 F-A F1.20c Variable Spring VT-3 RR-2 - - - .375" PFSK-2402. CC N-491-1 20-10-924 - -

1.5" Branch Connection Surf - - - 1.5" Exgmpt IWC-1221(c) 20-10-925 C-F-2 C5.51 Elbow-Reducer Vol/ Surf - - - .375" Line Number: 24" W20-152-3A 24-10-946 C-F-2 C5.51 Reducer-Pipe Vol/ Surf - -

X .375" 24-10-947 C-F-2 C5.51 Pipe-Tee Vol/ Surf - - - .375" FILE: RHR02.10.WPD Page 10 - 62 of 10-92

O \ .]

James A. Fitzpa' rick Nuclear Power Plant [[::JAF-131-0003|JAF-131-0003]] O

b

$b Third Inservice Inspection Interval Ten - Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL IS11NTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THtCM REMARKS 10 - Residual Heat Removal System Drawing Number: MSK-3010 Line Number: 24"-W20-152-3A 24-10-948 - -

2.0" Branch Connection Surf - - -

2.0" Exempt IVC 1221(c) 24-10-949 C-F-2 C5.51 Tee-Pipe Vot/ Surf - - -

.375" 10-3A-NS-196 F-A F1.20d Sliding Base Support VT-3 RR-2 X - -

.250" PFSK-2470. CC N-491-1 10-3A-HS-197 - -

Hydraulic Snubber VT-3 RR-11 - - -

.750" PFSK-2471/JAF#332, CC N-491-1 24-10-949B C-C C3.20 Integral Attachroent Surf RR-4 - - -

.750" CC N-509 10-3A-HS-198 - - Hydraulic Snubber VT-3 RR-11 - - -

.750" PSFK-237. TS Section 3.6.1 24-10-949A C-C C3.20 Integral Attachment Surf RR-4 - - -

.750" CC N-509 24-10-950 - -

1.5" Branch Connection Surf - - -

1.5" Exempt rWC-1221(c) 10-3A-AS-199 F-A F1.20c Variable Spring VT-3 RR-2 - - - -

PFSK-1855. CC N-491-1 24-10-951 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.37T 24-10-952 C-F-2 C5.51 Elbow-Pipe Vot/Su.f - - -

.375" 10-3A-NS-200 - - Hydraulic Snubber VT-3 RR-11 - - - -

PFSK-2238. TS Section 3.6.1 24-10-953 - -

1.5" Branch Connection Surf - - -

1.5" Exe'mpt IVC 1221(c) 24-10-954 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.375" 24-10-955 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.375" 24-10-956 C-F-2 C5.51 Pipe-Valve MOV-151 A Vol/ Surf - - -

.375" MOV-151 A - - 24" Valve Bolting VT-1 - - -

24* No exam required FILE: RHR02.10.WPD Page 10 - 63 of 10-C2

p r n Y .,

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] b

$ Third Inservice inspection interval Ten - Year:nspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARMS 10 - Residual Heat Removal System Drawing Number: MSK-3010 Line Number: 24"-W20-152-3A 24-10-957 C-F-2 C5.51 Valve MOV-151A -Pipe Vol/Staf - - - -

.375" 24-10-958 C-C C320 Pipe-PenX-225A Surf RR-4 - - -

.375* CC N-509 FILE: RHR02.10.WPD Page 10 - 64 of 10-92 ,

7~

N) Y James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] A hMW Third Inservice inspection Interval Date January 7,1998 Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICM REMARKS 10 - Residstal Heat Removal System Drawing Number: MSK-3011 Line Number- 20"-W20-152-2C 20-10-959 C-F-2 C5.51 Pipe - Elbow Vol/ Surf - - -

.375" 20-10-960 C-F-2 C5.51 Elbow-Pipe Vof/ Surf - - - .375" 20-10-961 - -

1.5" Branch Connection Surf - - - 1.50" Exempt IVE-1221(c) 10-2C-NN-201 F-A F1.20e Rigid Sway Strut VT-3 RR-2 - - -

PFSK1809. CC N-491-1 10-2C-AN-203 F-A F1.20b Vertical Support VT-3 RR-2 - - -

.500" H10-50A, CC N-491-1 20-10-962 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.375" 20-10-963 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.375" 20-10-963A C-C C3.20 Integral Attachment Surf RR-4 - - -

.500" CC N-509 20-10-964 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.375" Excluded IWC-2500-1 20-10-964A C-C C3.20 Integral Attachment Surf RR-4 -

X -

.750" CC N-509 10-2C-NS-204 F-A F1.20b Box Constraint VT-3 RR-2 - X -

.750" PFSK-9330. CC N-491-1 20-10-965 C-F-2 C5.51 Pipe-Elbow Vol/ Surf X - -

.375" 20-10-966 C-F-2 C5.51 Elbow-Pipe Vol/ Surf -

X -

.375" 20-10-967 - -

4.0" Branch Connection Surf - - -

4.0" Exempt IWC-1221(c) 20-10-968 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.375" 20-10-969 C-C C3.20 Integral Attachment Surf RR-4 - - -

.250" Excluded IWC-2500-1(1)(c) 10-2C-AN-205 F-A F1.20c Variable Spring VT-3 RR-2 - - -

.250" PFSK-065. CC N-491-1 FILE: RHR02.10.WPU Page 10 - 65 of 10-92

s __

James . Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

g Ppwer Third Inservice inspection Interval Ten - Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRfPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS t

10 - Residual Heat Removal System Drawing Number: MSK-3011 Line Number: 20"-W20-152-2C 20-10-970 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.375" 20-10-971 - -

3/4" Branch Connection Surf - - -

.750" Exempt IVE.-1221(c) 20-10-972 - -

1.5" Branch Connection Surf - - -

1.50" Exempt IWC-1221(c) 20-10-973 C-F-2 C5.51 Pipe-Pipe VoUSurf - - - .375" Excluded IWC-2500-1 l 20-10-974 C-F-2 C5.51 Pipe-Valve MOV-17 Vol/ Surf - - -

.375" l

MOV-17 - - 20.0" Valve Botting VT-1 - - -

<2* No exam reqtired r

i t

l

! FILE: PHR02.10.WPD Page 10 - 66 of 10-92 l_ _ _ _ _ _ _ _ _

0 l

( [[::JAF-ISI-0003|JAF-ISI-0003]] James A. Fitzpatrick Nucles Power Plant Third inservice inspection interval Date January 7,1998 h

$ Ten -Year inspection Pfar- Revision 0 ASME WELD COMPONENT ASME ASME IS!!NTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE PER1 PER2 PER3 TH1CK REMARKS ITEM DESCRIPTION EXAM REQ CAT 6

10 - RESIDUAL HEAT REMOVAL SYSTEM Drawing Number: MSK-3012 Line No. 4"-W20-902v6 through Penetration X-17

.337" Exempt IWC-1221(a)

C5 61 Pipe-Cap VoVSurf - - -

4-10-182 C-F-2

- Inaccessible inside pen. X-17 No exam requeed Insulation Lug N/A - - -

4-10-183P - -

- Inaccessible, inside pen. X-17. No exam requwed Insulation Lug N/A - - -

4-10-183M - -

- Inaccessible. L side pen. X-17. No exam required Insulation Lug N/A - - -

4-10-183K - -

- Inaccessible. inside pen. X-17. No exam required Insulation Lug N/A - - -

4-10-183H - -

- - Inaccessible, inside pen. X-17. No exam required Insulation Lug N/A - -

4-10-183F - -

- inaccessible, inside pen. X 17, No exam required Insulation Lug N/A - - -

4-10-183D - -

- Inaccessible. inside pen. X-17. No exam required Insulation Lug N/A - - -

4-10-183N - -

Inaccessible, inside pen. X-17. No exam required N/A - - -

4-10-183L - - Insulation Lug

- Inaccessible, inside pen. X-17. No exam required Insulation Lug N/A - - -

4-10-183J - -

- Inaccessible, inside pen. X-17. No exam requi;ed Insulation Lug N/A - - -

4-10-183G - -

1 J

Inaccessible, inside pen. X-17. No exam iequired Insulation Lug N/A - - -

4-10-183 - -

Ina'ccessible, inside pen. X-17, No exam required Insufation Lug N/A - - - -

4-10-183C - -

.337" Inaccessible, inside pen. X-17 Exempt IWC-C-F-2 C5.61 Integral Fitting-Pipe Vol/ Surf - - --

4-10-183B 1221(a)

Vol/",urf - - - - Exempt IWC-1221(a) 4-10-183A C-F-2 C5 61 Integral Fitting-Liner VoVSurf - - - .337" Exempt IWC-1221(a) 4-10-183 C-F-2 C5.61 Pipe-integraf Fitting Exempt IWC-1221(c) 3/4" Branch Connection Sorf - - - -

4-10-983 - -

Page 10 - 67 of 10-92 FILE: RHR02.10.WPD

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] 4MMM Third Inservice inspection Interval Date Janualy 7,1998 Ten - Year lospection Pir.n Revision 0 COMPCNENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EAAM REQ PER1 PER2 PER3 THICK REMARKS 10 - Residual Heat Removal System Drawing No. MSK-3012 Line Number: 4"-W20-902-36 4-10-iO24 N/A N/A Pipe-Cap N/A - - -

.3'7" Weld removed Line Number: 4"-W20-902-35 from Fuel Pool Cooling Heat Exchanger Room 4-10-220A C-F-2 C5.61 Cap-Pipe Vol/ turf - - -

237 Exempt IWC-1221(a) 10-35-NS-221 A N/A N/A Mechar.ical Snubber - RR-11 - - -

.154" TS Section 3.6.1 4-10-904 C-C C3.20 Integral Attachment Surf - - - -

Exempt IWC-1221(a) 10-35-AN-221 F-A F1.20c Variable Spring VT-3 RR-2 - - - -

Excluded IWC-2500-1 4-10-2208 C-F-2 C5.61 Pipe-Elbow Vol/ Surf - - -

.237" Exempt IWC-1221(a) 4-10-220C C-F-2 C5.61 Elbow-Pipe Vol/ Surf - - -

.237" Exempt IWC-1221(a) ,

4-10-220D C-F-2 C5.61 Pipe-Elbow VotiSurf - -

.23T Exempt IVC,-1221(a) 4-10-220E C-F-2 C5.61 Elbow-Pipe Vol/ Surf . - -

.23T Exempt IVC,-1221(a) 10-35-NS-220 N/A N/A Mechanical Snubber -

RR-11 - - - -

TS Section 3.6.1 4-10-220F C-F-2 C5.61 Pipe-Valve FCV-43 Vol/ Surf - - -

.237" Exempt IWC-1221(a)

FCV-43 - -

Valve Botting VT-1 - - -

<2" No' exam required 4-10-220G C-F-2 C5.61 Valve FCV-43 -Pipe Vol/Surt - - -

.237" Exempt IWC-1221(a) 4-10-220H C-F-2 C5.61 Pipe-Elbow Vol/ Surf - - -

.237" Exempt IWC-1221(a) 4-10-220J C-F-2 C5.61 Elbow-Pipe Vol/ Surf - - -

.23T Exempt IWC-1221(a)

FILE: RHR02.10.WPD Page 10 - 68 of 10-92

p ,r s U' \

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h

h

$ Third inservice inspection Interval Ten - Year inspection Plan Date Januaiy 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTIOrd EXAM REQ PER1 PER2 PER3 THtCK REMARMS 4

10 - Residual Heat Removal System Drawing Number: MSK-3014 Line Number: 16"-W20-302-34 16-10-453 C-F-2 C5.51 Reducer-Pipe Vot/ Surf - -

X .500" 16-10-454 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - -

.500" 16-10-455 C-F-2 C5.51 Elbow-Pipe Vof/ Surf - - -

.500" 16-10-456 - -

11/2" Branch Connection Surf - - - -

Exempt IWC-1221(c) 16-10-457 - -

1 1/2" Branch Connection Surf - - - -

Exempt IWC-1221:c) 16-10-458A C-C C3.20 Integral Attachment Surf RR-4 - - -

1.0" CC N-509 10-9A-MS-254 N/A N/A Mechanical Snubber - RR-11 - - - -

PFSK-2071. TS Section 3.6.1 16-10-458B C-C C3.20 Integra! Attachment Surf RR-4 X - -

1.0" CC N-509 10 9A-ANY-253A F-A F1.20c Variable Spring VT-3 RR-2 X - - - H10-86C, CC N-491 1 16-10-459 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

.500" 16-10-400 C-F-2 C5.51 Elbow-Pipe Vcl/ Surf - - -

.500" 10-9A-AN-253 F-A F1.20c Variable Spring VT-3 RR-2 - - - - H10-85A, CC N-491-1 16-10-461 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.500" 16-10-462 C-C C3.20 Integral Attachment Surf RR-4 - - -

.500" CC N-509 10-9A-HS-252 N/A N/A Hydraulic Snubber - RR-11 - - - -

PFSK-1857. TS Section 3.6.1 16-iO-463 C-F-2 C5.51 Elbow-Elbow Vol/ Surf - - -

.500" 16-10-464 C-C C3.20 Integral Attachment Surf RR-4 - - -

.500" CC N-509 FILE: RHR02.10.WPD Page 10 - 69 of 10-92

1 k [[::JAF-ISI-0003|JAF-ISI-0003]]

. emes n. Fitzpatrick Nucle r Power Plant Third Inservice Inst,ection interval Date January 7,1998 W

$ Ten - Year inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME ISI!NTERVAL LTH OR CODE REL

' IDENTIFICATION CODE CODE PER1 PER2 PER3 THICK REMARKS ITEM DESCRIPTION EXAM REQ CAT 10 - Residual Heat Removal System Drawing Number: MSK-3014 Une Number: 16"-W20-392-34 RR-11 - - - - PFSK-2282. TS Section 2.6.1 10 9A-HS-251 N/A N/A Hydraufic Snubber -

Vol/ Surf - - - .500" s 16-10-465 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - - .500" 16-10-466 C-F-2 C5.51 Pipe-Elbow CC N-491-1, PFSK-1109 F1.20c Dual Spring Hanger VT-3 RR-2 - - - -

10-9A-AN-250 F-A Vol/ Surf - - - .500" 16-10-467 C-F

C5.51 E! bow-Pipe Vol/ Surf - - - .500" 16-10-468 C-F-2 C5.51 Pipe-Efoow Vol/Sur' - - - .500*

16-10433 C-F-2 C5.51 Elbow-Valve MOV-65A

- <2" No exam required 16.0" Va!ve Botting VT-1 -

MOV-65A - -

I t

Page 10 - 70 of 10-92 FILE: RHR02.10.WPD

a

< *ee . g s

i James A. Fitzpatrick Nuclear Power Plant [[::JAF-tSI-0003|JAF-tSI-0003]] Third inr,ervice inspection Interval Date January 7,1998 j- g b Ten -YearInspection Plan Revision 0 ASMt WELD COMPONENT ASME ASME LTH OR CODE CCX)E M 154INTENVAL IDENTIFICATION . CODE EXAM ret. PER1 PER2 PER3 TM8CK REMARKS CAT GEM _. DESCRTFTION 10 - Residual Heat Removal System Drawing Number: MSK-3014 Line Number: 8*-SHP-902-32A Redocer-Pipe Vol/S# X - -

.500*

8-10-503 C-F-2 C5.51 VT 3 RR-2 X - - - PFSK-1893. CC N491-1 10-32A-NS-258A F-A F1.20b Box C-'stratnt

- Exempt tv.C-1221(c) 11/2" Branch Connection Surf - - -

0-10-502 - -

VT-3 RR-2 - - - - PFSK-1898.CC N491 t 10-32A-NS-2588 F-A F120b Box Constraint VovSurf X -

.500*

Pipe-Elbx 8-10-501 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - - .50C" 0-10-500 C-F-2 C5.51 Surf RR4 - - - .500~ CC N-509 G-10499A C-C C320 integra! Attachment VT-3 RR-2 - - - .500" PFSK-1911. CC N491-1 10-32A-NS-259 F-A F120b Box Constraint Pipe-Elbow Vel / Surf - - - ST-8-10499 C-F-2 C5.51 Elbow-Pipe VouSurf - - -

.500" 8-10498 C-F-2 C5.51 VT-3 RR-2 - - - - PFSK-2620. CC N491-1 10-32A-NN-260 F-A r* 20b Box Constraint VT-3 RR-2 - - PFSK-2002. CC FM91-1 F120a Rod Hanger - -

10-32A-NS-261 F-A Pipe-Elbow VouSurf - - - .500" 0-1CM97 C-F-2 C5.51 Elbow-Pipe Vot/ Surf - - - .500" 8-;049GA C-F-2 C5.51 Pipe-E! bow Vol/ Surf - -

X 500" 8-10496 C-F-2 C5.51 Surf RR4 - - X- .75(T CC N-509 8-10495 C-C C320 Integraf Attachment VT-3 RR-2 - X - PFSK-2033. CC PM91-1 F120e Rigid Sway Strut 10-3A-NS-2G2 F-A FILE RHR02.10.WPD Page 10 -71 of 10-92

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O, [[::JAF-ISI-0003|JAF-ISI-0003]] James A. Fitzpatrick Nuclear Power Plant Third inservice Inspectiori interval Date January 7,1998 O bMb Ten -Year inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME tSflNTERVAL LTH OR CODE CODE REL IDENTFICATION CODE REO PERT PER2 PER3 THICK REMARKS CAT ITEM DESCRfDTION EXAM 10 - Residual Heat Removat System Drawing Number: MSK-3014 Line Number: 8"-SHP-902-32A Elbow-Pipe VoVStrf - - .500" 8-10-494 C-F-2 C5.51 VovSurf - - - .500~ Excluded IWC-2500-1 8-10 493 C-F-2 C5.51 Pipe-Pipe VoVSurf - - - .500-8-10492 C-F-2 C5.51 Pipe-Elbow Elbow-Pipe VoVSurf - - - .500*

8-10490 C-F-2 C5.51 Integraf Attachment Surf RR4 - X - .625' CC N-509 8-10-491 C-C C320 VT-3 RR-2 - X - - PFSK-1922. CC N-491-1 10-32A-NS-263 F-A F120b Lateral Restraint VT-3 RR-2 - - - - PFSK-1909. CC N-491-1 10-32A-NS-2b4 F-A F120b Anchor Surf RR-4 - - - .250" CC N-509 8-10-489A C-C C320 Integraf Attachment VouSurf - - - .500*

8-10-489 C-F-2 C5.51 Pipe-Elbow VouSur" - - - .500~

8-10-488 C-F-2 C551 Elbow-Pipe VT-3 RR-2 - - - - PFSK-1865. CC N 491-1 10-32A-NS-205 F-A F120a Rod Hanger Vol/ Surf - - - .500" 8-10-487 C-F-2 C5 51 Pipe-Elbow Elbow-Pipe Vo&S wf - - - .500" 8-1(M86 C-F-2 C5.51 Pipe-Elbow VoVSurf - - - .500*

8-10485 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.500*

i 8-10-484 C-F-2 C5.51 VoVSurf - - - .500" 8-10-483 C-F-2 C5.51 Pipe-Elbow Elbow-Pipe VoUSurf - - - .7XF 8-40-482 C-F-2 C5.51 FILE: RHR02.10.WPD Page 10 -72 of 10-92

'V V James A Fitzpatrick Nuclear Power Piant [[::JAF-ISl-0003|JAF-ISl-0003]] V

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$ Third 1.1 service Inspection laterval Ten - Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME W6LD IDENTIFICATlON CODE CODE CODE REL 854 INTERVAL LTH OR CAT ITEM DESCRfPTION EXAM REO PER1 PER2 PER3 THICK RCMARKS 10 - Residual Heat Removal System Drawing Number: MSK-3014 t.ine Number- 8~-SHP-902-32A 8-10-481 - - 3/4" Branch Cw o.cc,e.

Surf - - - - Exempt IV.C1221(c) 10-32A-NS-2SS F-A F120b Box Constract VT-3 RR-2 - - - - PI-SK-2443, CC N 491-1 10-32A-NS-257 F-A F120e Rigid Sway Strut VT-3 RR-2 - - - -

PFSK-2275. CC N-491-1 10-32A-NS-268 F-A F120b Box Constract VT-3 RR-2 - - - -

PFSK-2322. CC N 491-1 8-10-480 C-F-2 C5.51 Pipe-Valve MOV-70A VouSu f - - -

.500*

MOV-70A - - 8.0" Valve Boling VT-1 - - -

<2*

B-10-480A C-F-2 C5.51 Vdve MOV-70A-Pipe VoVSurf - - -

.500*

8-10-479 - - 3/4" Branch Cswedni Surf - - - - Exempt Int-1221(c) 8-10-478 C-F-2 C5.51 Ppe-Elbow VoVSurf - - -

500*

8-10-477 C-F-2 C5.51 Elbow-Pipe VoLSurf - - -

.500*

8-10-477A C-C C3 20 Integral Aitod.ea Surf RR-4 - - -

.250" CC N-509 10-32A-NS-269 F-A F120b Rigid Constraint VT-3 RR-2 - - - -

PFSK-2540. CC N.491-1 8-10-476 C-F-2 C5.51 Pipe-Elbow VoLSurf - - -

.500*

8-10-475 C-F-2 C5.51 Elbow-Pipe VoLSurf - - -

500*

8-10-474 C-F-2 C5.51 Pipe-Vahre PCV-69A VoVSurf - - - .500*

PCV-69A - -

8 D* Vahre Bolting VT-1 - - -

<2*

8-10-473 C-F-2 C5.51 Vahre PCV-69A-Pipe VoVSurf - -

.500*

FILE: RHR02.10.WPD Page 10 - 73 of 10-92

v' J James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] O

h

$ Third Inservice inspection Interval Tan -Year Inspection Plan Date January 7,1998 Revision 0 COMPCNENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ESitNTERVAL t.TH OR CAT ITE8A DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 13- Residual Heat Removal System Drawing Number: MSK-3014 Lk +, Number: 8"-SHP-902-32A ,

8-10-472 - -

3/4* Branch Cw wGi Surf - - - - Exempt IWC,-1221(c) 8-10-471 C-F-2 C5.51 Pspe-Elbow Vol/ Surf - - -

.500*

8-10-470 C-F-2 C5.51 Elbow-E! bow Vol/ Surf - - -

.500*

8-10-469 C-F-2 C5.51 Elbow-Reducer Vot/ Surf - - -

.500*

Line Number: 20~-SLP-302-33A 20-10-450 C-F-2 C5 51 Reducer-Pipe Vol/ Surf - - - _500*

16-10-449 - -

3/4 Branch Cw <&. Surf - - - - Exempt MC-1221(c) 20-1t)-448 - -

4.0" Branch Connection Surf - - - -

Exempt IWC-1221(c) 20-10-451 C-F-2 C5.51 Tee-Nozzle Vol/ Surf - - -

.594*

20-10-452 C-F-2 C5.51 Recucer-Pipe Vol/ Surf - - -

.594-Une Nuraber:4"-SLP-302-86A 4-10-447 C f-2 C5.51 Pipe-Valve SV-74A Vol/ Surf - - -

.237* Exempt IWC-1221(a)

SV-74A - -

4.0" Valve Botting VT-1 - - -

<2" No' exam reg; ired FILE: RHR02.10.WPD Page 10 -74 of 10-92

m -

) ; 4

%J x) %.J James A. Fitzpatrick Nuclear Power Plant JAF-ISIM3 M IU8WMM Third Inservice inspection Interval Date Anuary 7,1998

& Aetherity Ten -Year inspection Plan Revision O COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 TNICK REMARKS I

10 - Residual Heat Removal System Drawing Number: MSK-3014 Line Number- 6"-SLP-302-34A 6-10 446 C-F-2 C5.51 Vahre SV-74A-Pipe VoLSurf - - -

.280* Exduded rNC-2500-1 6-10 445 C-F-2 C5.51 Pme-Elbow VoLSurf - - -

287 Emduded IWC-2500-1 6-10-444 C-F-2 C5.51 Elbow-Pipe VoLSurf - - -

.230' Exdudad rir,-2500-1 6-10-443 C-F-2 C5.51 Pne-Elbow Vol/ Surf - - - .280" Erduded r/C2500-1 6-10-442 C-F-2 C5.51 Elbow Pipe VoLSurf - - -

280" Exch*d PAC-2500-1 6-10441 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

287 Exduded IWC-2500-1 6-10 440 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

280" Enduded FAC-2500 -

6-10-439 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

.280* Erduded IWC-2500-1 6-10-438 C-F-2 C5.51 Elbow-Pipe Vol/ Surf + - - -

.280* Exduded rWC-2500-1 6-10-437 - -

2.0" Banch Connection Surf - - -

.280* Exempt IVC 1221(c) 6-10-436 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

280* Exduded rt&2500-1 6-10-435 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - - 280" Exduded rt&2500-1 v

10-34A-NS-254A F-A F120b Non Adjustable V7-3 RR-2 - - - -

Exduded IVC 2500-1 6-10-434A C-C C320 Integral Attachment Surf RR-4 - - - .500* Exduded !WC-2500-1 6-10434 C-F-2 C5.51 Pipe-Pipe Vot/ Surf - - -

.280" Exduded IVC 2500-1 6-10-433 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

280" Enduded !WC-2500-1 6-10-432 C-F-2 C5.51 Elbow-Elbow Vot/ Surf - - -

280* Exduded IVC.~". 500-1 FILE: RHR02.10.WPD Page 10 - 75 of 10-92

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I \ h LJ ~ _J James A. Fitzpatrick Nuclear Power Plant JAF4SI-0003

[G 4 k WmMor Third inservice Inspection interval Date January 7,1998 Ten -Year inspection Plan Revision 1 COMPONENT ASME ASME ASME WELO IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCR:PTION EXAM REQ PER1 PER2 PER3 THrCK REMARKS 10 - Residual Heat Removal System Drawing Number: MSK-3014 Une Number 6"-SLP-302-34 A 6-10-431 C-F-2 C5.51 Elbow-Pipe Vot/ Surf - - -

280" Exduded IVC 2500-1 S-10-430 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - - 280" Exduded IVC 2500-1 6-10-429 C-C C320 Integra! Attachment Surf RR-4 - - -

.750" Exduded IWC ~2500-1 10 34A-NS-253 F-A F120b Constraint V'-3 RR-2 - - - -

FFSK-4167. Exduded n&2500-1 10-34A-NS-255A F-A F120b Anchor VT-3 RR-2 - - - -

PFSK-2354. Exduded nh*AO-1 6-10-428 C-C C3.20 Integral Attachment Surf RR-4 - - -

1.0" Exduded rVC2500-1 10-4A-NS-256 F-A F120b Verical Constraint VT-3 RR-2 - - -

.375" PFSK-2317. Exduded IV&2500-1 6-10427 C-F-2 C5.51 Elbow-Pipe VoVSurf - -

280" Erduded IYC2500-1 10-34A-NS-257 F-A F120a Rod hanger VT-3 RR-2 - - - -

PFSK-2331. Exduded n%2500-1 10-34A-NN-258 FA F120b Connaint VT-3 RR-2 - -

PFSK-2327. Exduded IVC 2500-1 6-10-426 C-F-2 C5.51 Pipe-Elbow Vo!/ Surf - - -

280" Exduded IWC-2500-1 6-10-425 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

280" Excluded IWC-2500-1 6-10-424 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.280" Exbaded IWC-2500-1 FILE RHR02.10.WPD Page 10 - 76 of 10-92

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James A. Fitzpatrick Nuclear Power Piritt [[::JAF-ISI-0003|JAF-ISI-0003]] U

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$ Third Inservice Inspection interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COtPPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THCK REMARKS 10 - Residual Heat Removal System Drawing Number: MSK-3015 Une Number: 8"-SHP-902-328 8-10-507 C-F-2 C5 51 Reducer-Pipe VoVSTf - - X .500" 10-328-NS-275A F-A F1206 Box Constraint VT-3 RR-2 - - - -

PFSK-1894. CC N-491-1 10-328-NS-2758 F-A F120e RW Sway Strut VT-3 RR-2 - - - -

PFSM-1891. CC N-491 1 8-10-508 C-F-2 C5.51 Pipe-Pipe VoLSurf - - -

.500" Ezcluded IVC,-2500-1 8-10-509 C-F-2 C5.51 PW VouSurf -

X -

.500" 8-10-510 C-F-2 C5.51 Elbow-Pepe VoLSurf - - X .500" 8-10-510A C-C C320 Integra! Attachment Surf RR-4 X - -

2 50" CC N-509 10-328-NS-275 F-A F1206 Vertcal Constraint VT-3 RR-2 X - - -

PFSK-2221. CC N-491-1 8-10-511 C-F-2 C5 51 PMIbow VoVSurf -

X -

.500" 8-10-512 C-F-2 C5.51 Elbow-Pipe VoVSu-f - X -

.500" 8-10-513 C-F-2 C5.51 Pipe-Elbow VoLSurf -

X -

.500" 8-10-514 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.500" r

8-10-515 C-F-2 C5.51 Pipe-E! bow VouSurf - - -

.500" 8-10-516 C-F-2 C5.51 Elbow-Pipe VoLSurf - - -

.500" 8-10-517 C-C C320 Integral Attachment Surf RR-4 - - -

.28" CC N-509 10-32B-HS-277 N/A N/A Hydraute Snubber -

RR-11 - - -

PFSK-2366. TS Sc bon 3.6.1 10-328-NS-278 N/A N/A Hydratic Snubber -

RR-11 - - - -

PFSK-2366. TS Secbon 3.6.1 F!LE RHED2.10.WPD Page 10 -77 of 10-92

p p V, 3 V James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] V

4 bMM Third inservice inspection Interval Date January 7,1998 Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WTafa IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THrCK REMARKS 10 - Residual Heat Removal System Drawing Number: MSK-3015 Line Number: 8 -SHP-902-328 8-10-518 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

.500" 8-10-519 C-F-2 C5.51 Elbow-Elbow VoVSurf - - -

.500" 8-10-520 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.500" 8-10-521 C-F-2 C5.51 Pipe-Tee VoVSurf - - -

.500" 8-10-522 C-F-2 C5.51 Tee-Cap VoVSurf - - -

.500" d-10-523 C-F-2 C5.51 Tee-Pipe VoUSurf - - -

.500" 0-10-524 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

.500" 8-10-525 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.500" 8-10-526 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

.500" t

8-10-527 C-F-2 C5.51 Elbow-Pipe VoLSurf - - -

.500" 10-328-NS-279 F-A F1.20b Box Constraint VT-3 RR-2 - - - -

PFSK-2566. CC N-491-1 8-10-527A C-C C3.20 Integral Attachment Surf RR-4 - - -

.500" CC N-509 10-328-NS-281 F-A F1.20b Anchor VT-3 RR-2 - - - -

PFSK-2342 CC N-491-1 8-10-528A C-C C3.20 Integral Attachment Surf RR-4 - - -

.250" CC N-509 8-10-528 C-F-2 C5.51 Pipe-Elbow VouSurf - - -

.500" 8-10-529 C-F-2 C5.51 Elbow-Pipe VoUSurf - - -

.500" 8-10-530 C-F-2 C5.51 Pipe-Elbow VouSurf - - -

.50Cr FILE- RHR02.10.WPD Pam 10 -78 of 10-92

-s 7

% ./ L/ O James A. Fitzpatrick Nuclear Power Plant [[::JAF-tSI-0003|JAF-tSI-0003]] 4 bMW Third inservice Inspection Interval Date January 7,1998

Ten -Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THfCM REMARKS 10 - Residual Heat Removal System Drawing Number: MSK-3015 Une Number 8"-SHP-902-32B 8-10-531 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.500" 8-10-532 C-F-2 C5.51 Pipe-Pipe VoVSurf - - -

.500" Exduded n%2500-1 8-10-533 - -

1.0" Bnanch Connection Surf - - - - Exempt nT-1221(c) 8-10-534 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

.500*

10-328-NS-282 F-A 7120b Vertical Constraint VT-3 RR-2 - - - -

PFSK-2362. CC N-491-1 8-10-535 C-F-2 C5.51 Elbow-Velve MOV-709 VouSurf - - -

.500" MOV-708 - - 8.0" Valve Botting VT-1 - - -

<2" No exam required 8-10-536 C-F-2 C5.51 Vatve MOV-708-Pipe VoVSurf - - - .500*

8-10-53/ - -

3/4" Branch Connection Surf - - - -

Exempt IVE,-1221(c) 10-32B-NS-283 F-A F120b Rigid Constraint VT-3 RR-2 - - - -

PFSK-2502 CC N-491-1 8-10-53J C-F-2 C5.51 Pipe-Elbow VoUSurf - - -

.500*

8-10-539 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.500" l 10-328-NS-284 F-A F120b Non Adjustable VT-3 RR-2 - - - -

CC'N491-1 8-10-539A C-C C320 fr'tegral Attachment Surf RR-4 - - -

25" CC N-509 8-10-540 C-F-2 C5.51 Pipe-Elbow VouSurf - - -

.500" 8-10-541 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.500" 8-10-542 C-F-2 C5.51 Pipe-Valve PCV-69B VoVSurf - - -

500" FILE RHR02.10.WPD Page 10 - 79 of 10-92

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-4003|JAF-ISI-4003]] h

$b Third inservice Inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 i COMPONENT ASME ASME ASME WELD l IDENTIFICATION CODE CODE CODE REL IS4 INTERVAL LTH OR CAT ITEM DESCR:PTION EXAM REO PER1 PER2 PER3 THICM REMARKS 1')- Residual Heat Removal System Drawing Numbec MSK-3015 Une Numbec 8*-SHP-902-328 PCV-698 - -

8.0" Valve Bolting VT-1 - - -

<2" No exam requeed Line Numben 8"-SLP-302-378 8-10-543 C-F-2 C5.51 Valve PCV-698-Pipe Vol/Su f - - -

.500" B-10-544 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

.500" 8-10-545 C-F-2 C5.51 Elbow-Elbow Vol/ Surf - - -

.500" 8-10-E 46 - -

1 1/4" Branch Cv. G. Surf - - - - Exempt IYC1221(c) 6-10-547 ,

C-F-2 C5.51 Elbow-Reducer Vol/ Surf - - -

_500" Line Numbec 20"-SLP-302-33B 20-10-548A - -

3/4" Branch Connection Surf - - - - Exempt IVC 1221(c) 20-10-548 C-F-2 C5.51 Reducer-tee Vol/ Surf - - -

.500" 20-10-549 - -

4.0* Branch Connection Surf - - - - Exempt IWC-1221(c) 20-10-550 C-F-2 C5.51 Tee-Nozzle Vol/ Surf X - -

500" Terminal End, Hx B 20-10-551 - -

11/4" Branch Connection Surf - - - -

Exht MC-1221(c) ,

20-10-553 C-F-2 C5.51 Tee-Reducer Vol/ Surf - - -

_500" I

i FILE- RHR02.10.WPD Page 10 - 80 of 10-92

t,/ V James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Q

4 bMb Third Inservice Inspection Interval Date January 7,1998 Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME A*ME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRTPT10M EXAM REO PER1 FER2 PER3 THICK REMARKS 10 Residual Heat Removal System Deawing Number: MSK-3015 Line Number: 16~-W20-302-9B 16-10-554 C-F-2 C5.51 Reducer-Pipe Vol/ Surf X - -

.500" 16-10-555 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - -

X .500" 10-10-556 C-F-2 C5.51 Elbow-Pipe Vol/Sur! - - -

.500*

16-10-557 - -

1.0" Branch Connection Surf - - - - Exempt rWC-1221(c) 16-10-558 - -

1 1/2" Branch Connection Surf - - - -

Exempt IWC-1221(c) 10-10-559 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.500* Excluded IWC-2500-1 16-10-560 C-C C320 Integral Attachment Surf RR-4 - - -

.375* CC N-509 10-98-AN-285 F-A F120c Variable Spring VT-3 RR-2 - - - -

H10-898. CC N491-1 16-10-561 C-F-2 C5.51 Pipe-Pipe Vol/Su f - - -

.500" Excluded IYC-2500-1 16-10-562 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.500-16-10-563 C-F-2 C5.51 Elbow-Pipe Vot/ Surf - - - .500" 10-98-AN-286A F-A F120b Adjustable VT-3 RR-2 - - - -

H10-58. CC N-491-1 16-10-564 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.500*

10-9B-MS-284 F-A F120b Rigid Constraint VT-3 RR-2 - - - -

PFSK-2553. CC N-491-1 16-10-564A C-C C320 Integral Attachment Surf RR-4 - - -

.500* CC N-509 10-9B-HS-287 N/A N/A Hydrauf c Snubber -

RR-11 - - - -

PFSK-2543. TS Sechon 3 6.1 16-10-565 C-F-2 C5.51 Elbow-Elbow Vol/ Surf - - -

.500*

FILE: RHR02.10.WPD Page 10 - 81 of 10-92

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James Fitzpatrick Nuclear Power Plant JK -tSI-0003 h Third inservice inspection Interval Date January 7,1998

$ Ten -Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME ' WELD fDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRts' TION EXAM REO PER1 PER2 PER3 THrCM REMARMS 1]- Residual Heat Removal System Drawing Number: MSK-3015 Une Number: 16"-W20-302-9B 10-9B-HS-288 N/A N/A Hydraulic Snubber - RR-11 - - - -

PFSK-2068 TS Sechen 3.6.1 16-10-565A C-C C320 Integral AMachment Sur' RR-4 - - -

.500" CC N-509 16-10-506 C F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.500" 10-96-AN-289 F-A F120b Adjustable VT-3 RR-2 -

X - -

PFSK-1108. CC N-491-1 16-10-567 C-F-2 C5.51 Pme-E! bow Vol/ Surf - - -

.500*

16-10-568 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.500*

16-10-569 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

_500" 16-10-570 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.500" MOV-658 - - 16" valve - - - - -

Cortnued on LTSK-3004 Line Number: 4"-SLP-302-868 4-10-552 C-F-2 C5.51 Pipe-Va ve SV-748 i

Vol/Curf - - -

.237' Exempt IVWC-1221(a)

SV-748 - -

4.0" Valve Bolunr: VT-1 - - -

<2' No exam requ: red s

Line Number: 6"-SLP-302-348 6-10-571 C-F-2 C5.51 Valve SV-748-Pipe Vol/ Surf - - -

280" Excluded WC2500-1 6-10-572 C-F-2 C5.51 Pipe-Elbo.y Vol/ Surf - - -

280" Excluded WC2500-1 6-10-573 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

280" Excluded rAC-2500-1 6-10-574 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

280" Excluded NC2500-1 FILE RHR02.10.WPD Page 10 - 82 of 10-92

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i f l O' G James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] (J

h

$ Third Inservice Irnpection Interval Ten -Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME W EL.D IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCR!PTION EXAM REQ PER1 PER2 PER3 TH3CK REMARKS 10 - Residual Heat Removal System Drawing Number: MSK-3015 Line Number. 6"-SHP-302-34B 6-10-575 C-F-2 C5.51 Elbow-Pg>e VouSurf - - -

.280* Exduded IV&2500-1 6-10-576 C-F-2 C5.51 Pipe-Elbow VouSurf - - -

.280" Exduded IWC-2500-1 6-10-577 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

280" Exduded IV.C-2500-1 10-348-NS-270 F-A F1.20b Non Adjustable VT-3 RR-2 - - - -

PFSK-2380. Exduded WC2'i10 6-10-578 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

280" Exduded WC2500-1 6-10-579 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

2 80" Exduded IV&2500-1 6-10-580 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.280" Exduded WJC-2500-1 6-10-581 - -

3.0" Branch Connection Surf - - - - Exempt IWC-1221(c) 6-10-582A C-C C3.20 Integral Attachment Surf RR-4 - - -

250" Exduded IVC 2500-1 10-348-NS-271 F-A F1206 Rigid Corv 'raint VT-3 RR-2 - - - -

PFSK-2397. Excluded IWC-2510 6-10-583 C-F-2 C5.51 Pipe-Elbow VouSurf - - -

2 80" Exduded IYC2500-1 6-10-584 C-F-2 C5.51 Elbow-Pipe VouSurf - - -

280" Exduded IVC 2500-1 6-10-585 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

280" Erduded IWC-2500-1 6-10-586 C-F-2 C5.51 Elbow-Prpe Vot/Stef - - -

280" Exduded IWC-2500-1 6-10-586A C-C C320 Integrat Attachment Surf RR-4 - - -

.375" Exduded 6-10-582 C-F-2 C5.51 Pipe-Pipe Vol/Stuf - - -

.280" Excluded IWC-2500-1 10-348-NS-272 F-A F120b Rigid Co .straint VT-3 RR-2 - - - -

PFSK-2548. Exduded FILE RHR02.10.WPD Page 10 - 83 of 10-92

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\. _, j James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h

$ Third Inservice inspection interval Ten - Year Inspection Plan Date January 7.1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICA'.lON CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM ,

DESCRfPTION EXAM REO PER1 PER2 PER3 TH3CM REMARMS 10 - Residual Heat Removal System Drawing Number- MSK-3015 Une Number: 6*-SHP-302-348 6-10-587 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

280* Exduded n&2500-1 6-10-588 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

2 80" Exduded IV&2500-1 6-10-589 C-C C320 Integral Attachment Surf RR-4 - - -

.250" Exduded 10-348-NS-273 F-A F120b Lateral Constraint VT-3 RR-2 - - - -

PFSK-2582. Excluded IWC-2510 10-348-NS-273A F-A F120e Rigid Sway Strut VT-3 RR-2 - - - -

PFSK-2597 Excluded IV&2510 6-10-590 C-F-2 C5.51 Pipe-Elbow Vcd/ Surf - - - .280* Exduded IVC 2500-1 10-348-NS-274 F-A F120b Vertical Restraint VT-3 RR-2 - - - -

PFSK-2161. Exduded IVC 2510 6-10-590A C-C C320 Integral Attachment Surf - - -

.375- Exdudad 6-10-591 C-F-2 C5.51 Elbow-Pipe 1/ Surf - - -

.280" Exduded IAC-2500-1 6-10-592 - -

3/4" Branch Connectxm Surf - - - -

Exempt IWC-1221(c) 6-10-593 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

280* Excluded IV&2500-1 1

FILE- RHR02.10.WPD Page 10 - 84 of 10-92

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V J James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] b

4 bMM Third Inservice Inspection Interval Date January 7,1998 Ten -Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME M1 ELD IDENTIFICATION CODE CODE CCDE REL ISilNTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICM REMARKS 13- Residual Heat Removal System Drawing Number: MSK-3016 Une Ntimber- 16"-W20-302-15B 16-10-1027 C-F~ C5.51 Vahre MOV-39B-Prpe VoVSurf - - -

.500* Contmued on MSK-3008 16-10-1027A C-C C3 20 Integra! Attachment Surf RR-4 - - -

.322" CC N-509 10-158-NS-291 t#A N/A Hydratic Soubber -

RR-11 - - - - PFSK-2477, TS Secbon 3.6.1 16-10-1026 C-C C320 Integral Attachment Surf RR-4 - -

X .750" CC N-509 10-158-NS-292 N/A N/A Hydraulic Snubber -

RR-11 - - - -

PFSK-2042 TS Secton 3 6.1 16-10-1025 C-F-2 C5.81 6.0" Branch Connecron Surf - - - -

Inaccessible 16-10-123 C-F-2 C5.51 Pipe-Reducer VoVSurf - - -

.500" Line No.14"-W23-152-98 14-10-1022 C-F-2 C5.51 Reducer-Valve MOV-348 VoVSurf - -

X .375*

MOV-343 - - 14.0" Valve Botting VT-1 - - -

<2" No eram required 10-158-HS-293 N/A PFA Hydraulic Snubber - RR-11 - - - -

PFSK-2074. TS Secten 3.6.1 10-158-HS-294 PUA t#A Hydraulic Snubber -

RR-11 - - - -

PFSK-2074. TS Sechon 3.6.1 10-15B-HS-295 N/A t#A Hydraulic Snubber - RR-11 - - - -

PFbK-2047. TS Seckon 3.6.1 10-158-HS-29G N/A N/A Hydraunc Snubber - RR-11 - - - -

PFSK-2047. TS Secten 3.6.1 14-10-1021 C-F-2 C5.51 Valve MOV-34B-Reducer VoVSurf - - -

.375*

FILE: RHR02.10.WPD Page 10 - 85 of 10-92

m. -

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James A. Fitzpatrick Nuclear Power Plant C/

JAF-tS14)003 A hMM Third Inservice Inspection Interval Date January 7,1998 Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASarc- WELD IDENTIRCATION CODE CODE CODE REL ESIINTERVAL LTH OR CAT ITEM DESCR'PTION EXAM REO PERT PER2 PER3 THtCM REMARMS 10 - Residual Heat Removal System Drawing Number: MSK-3016 Line Number: 16"-W20-152-58 13-10-1020 C-F-7 C5-.51 ReducerPipe VoL* Surf X - - .375' 16-10-1019 - -

4 (T Branch Cw w@i Surf - - - - Exempt WC1221(c) 10-58-HS-297 F-A F120b Non Adjustable VT-3 RR-2 - - - -

PFSK-2437. CC N-491-1 16-10-1018 C-r-2 C5 81 6.0" Branch Cw a Mb . Surf - - - -

Inaccessible 16-10 1017 - -

3/4" Branch CercMei Surf - - - -

Exempt IVC 1221(c) 16-10-1016 C-F-2 C5 51 Elbow-Pepe Vc@ Surf - - -

.375" 16-10-1015 C-F-2 C5.51 Ptpe-Ebew Vc4 Surf - - -

375' 16-10-1012 C-F-2 C5.81 14.0" Branch Cw <66.

Surf - - - -

Inaccessible 16-10-1011 - -

1 1/2" Branch Connechon surf - - - - Exempt IVC 1221(c) 16-10-1013 C-C C320 Integral Attachment Surf RR4 - -

X -

Rsf#69 Pad, CC N-509 10-58-NS-278 F-A F1.20tr Non Adi ustable V7-3 RR-2 - - - -

CC N491-1 16-10-1010 - -

4 0 Branch Connection Surf - - - -

Exempt IVC 1221(c) 16-10-1009 C-F-2 C5.51 Etbow-Pipe Vol/ Surf - - -

_375' 16-10-1008 C-F-2 C5.51 Pipe-Elbow Voi/ Surf - - -

.375" 16-10-1007 C-F-2 C5.51 Pipe-Pipe VoLSurf - - -

.375" Exduded IYC2500-1 16-10-1006 - -

4 0* Branch Connection Surf - - - -

Exempt IVC 1221(c) 4-10-1005 - - Pipe-Pipe N/A - - - -

Exempt IVC 1221(c)

FILE: RHR02.10.WPD Page 10 - 86 of 10-92

,r\ (

j N)

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h Third Inservice laspection Interval Date January 7,1998

$b Ten -Year Inspection Pian Revision 0 COMPONENT ASME ASME ASME vvELD IDENTIFICATION CODE CODE CODE REL ISitNTERVAL LTH OR CAT ITEM DESCRfPTION EXAM REQ PER1 PER2 PER3 TH8CK REMARKS 10 - Residual Heat Removal System Drawing Number: MSK-3016 Une Number: 16"-W20-152-5B 16-10-1004 C-F-2 C5.51 Pipe-Pipe VouSurf - - -

3 75* Exduded IWC-2500-1 16-10-1003 C-F-2 C5.51 Pipe-Pipe VoVSurf - - -

.375' Exduded IWC-2500-1 16-10-1002 C-C C320 Pipe-Penetrabon Surf RR-4 - - -

3 75- CO N-509 Pen. X-2108 16-10-1001 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.375- Exduded IWC-2500-1 16-10-1000 C-F-2 C5.51 Pipe-Pipe VoVSurf - - -

.375" Exduded !WC-2500-1 Line Number: 6"-W20-152-168 6-10-1028A - -

3/4' Branch Connedian f,urf - - - - Exempt IWC-1221(c) 6-10-1028 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

180" Exduded TWC4"00-1 6-10-1029 C-F-2 C5.51 Elbow-Reducer VoVSu f - - - 280" Exduded IWC-2500-1 Line Number: 4"-W20-152-408 4-10-1030 C-F-2 C5.~1 Reducer-Valve MOV-388 Vol/ Surf - - -

180" Exempt IWC-1221(a)

MOV-388 - - 4.0" Valve Botting VT-1 - - -

<2* No exam regaired 4-10-1031 C-F-2 C5.51 Valve MOV-38B-Reducer Vol/ Surf - - -

1 80" Exempt IWC-1221(a)

FILE: RHR02.10.WPD Page 10 - 07 cf 10-92

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( ) [,l James Fitzpatrick Nuclear Power Plant JAF-ISI-C"M13 h

$ Third Inservice Inspection Interval Ten - Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME VVELD IDENTIFICAT10N CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRtPTION EXAM REO PER1 PER2 PER3 THICK REMARKS t

10 - Residual Heat Removal System thawing Number: MSK-3016 Une Number- 6'-W20-152-448 6-10-1032 C-F-2 C5.51 Reducer-Pire VoLSurf - - -

.280- Exduded NC2500-1 6-10-1033 C-F-2 C5.51 Pipe-Elbow VoLSurf - - -

280" Exduded iWC2500-1 6-10-1034 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

1 80* Exduded NC2500-1 6-10-1035 C-F-2 C5.51 Pipe-Elbow VoVSurf - - - 280~ Exduded nC2500-?

6-10-1036 C-F-2 C5.51 E! bow-Elbow VoVSurf - - -

280" Exduded WC2500-1 6-10-1037 C-F-2 C5.51 Elbow-Pipe VoLSurf - - -

280- Exduded WC2500-1 6-10-1038 - -

3/4" Branch Connection Surf - - - - Exempt ht1221(c) 6-10-1039 C-F-2 C5.51 Pipe-Elbow VoLSurf - - -

280" Exduded I\%2500-1 6-10-1040 C-F-2 C5.51 Elbow-Pipe VoL3urf - - -

.280- Exduded WC2500-1 6-10-1041 C-F-2 C5.51 Pipe-Pipe VoLSurf - - -

.280" Exduded 1\C2500-1. Pen X-2118 6-10-1042 C-C C320 Pipe-Penetration Surf - - -

2 80- Exduded IWG2500-1. In accessible 6-10-1043 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

280" Exduded IWC-2500-1, inaccesstle in Torus 6-10-1044 C-F-2 C5.51 Elbow-Pipe VouSurf - - -

280" Excluded WC2500-1. Inaccessbie in Torus 6-10-1045 C-F-2 C5.51 Pipe-Tee VoVSurf - - -

280" Exciuded WC2500-1, inaccessible in Torus FILE- RHR02.10.WPD Page 10 - 88 of 10-92

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James A. Fitzpatrick Nuclear Power Plant JAF4SI-0003 b

$ Third Inservice inspection Interval Ten -Year Inspection Plan Date Jan jary 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD SDENTIFICATION CODE CODE CODE REL ISilNTERVAL LTH OR CAT ITEM DESCRfPTION EXAM REO PER1 PER2 PER3 T.CCM REMARKS 13- Residual Heat Removal System Drawing Number- MSK 3017 Une Number: 6"-W20-302-16A to suppression chamber 6-10-1078 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - - 280* Exduded IVC 2500-1 6-10-1079 C-F-2 C5.51 Elbow-Reducer Vol/ Surf - - -

280" Endudad n%2500-1 C-10-1080 C-F-2 C5.51 Reducer-Valve MOV-33A Vol/ Surf - - -

280* Exduded n%2500-1 MOV-38A - -

4.0" Vafve Botting VT-1 - - -

<2" No exam requred 4-10-1081 C-F-2 C5.51 Valve MOV-38A-Reducer Vol/ Surf - - -

_280~ Exduded IV&2500-1 Una No. 6"-W20-152-44A 6-10-1082 C-F-2 C5.51 Reducer-Pipe Vol/ Surf - - -

280* Exduded IWC-2500-1 6-10-1083 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

280" Exduded FAC-2500-1 6-10-1084 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

280* Exduded n%2500-1 6-10-1085 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.280" Exduded IV&2500-1 6-10-1086 C-F-2 C5.51 Ppe-Elbow Vol/ Surf - - -

280* Exduded IWC-2500-1 6-10-1087 C-F-2 C5.51 Elbow-Elbow Vot/ Surf - - -

280- Excluded IWC-2500-1 6-10-1088 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

2 80" Exduded IVC 2500-1 6-10-1089 3/4' Branch Cwn+ L, Surf Exempt IWC-1221(c) 6-10-1090 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

280" Exduded IWC-2500-1 6-10-1092 C-F-2 C5.51 Elbow-Pipe Vot/ Surf - - -

.280" Exduded IV&2500-1 FILE: RHR02.10.WPD Page 10 - 89 of 10-92

~J %j w James A. Fitzpatrick Nuclers Power Plant [[::JAF-8S8-0003|JAF-8S8-0003]] 4 SETMb Third inservice inspection Interval Date January 7,1998 Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISitNTERVAL LTH OR CAT TTEM DESCRIPTION EXAM REQ PER1 PER2 PER3 TWCM REMARMS 10 - Residual Heat Removal System Drawing Number: MSK-3017 Line Number: 6"-W20-152-44A 6-10-1093 C-C C320 Pipe-Penetration Surf - - -

.280" Exdudad IWC-2500-1. Pen. X-211 A 6-10-1094 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

230" Excuded IWC-2500-1. Inaccessible h Torus 6-10-1095 C-F-2 C5.51 Elbow-PW Vol/ Surf - - -

2 80" Exduded IWC-2500-1, maccessible in Torus 6-10-1096 C-F-2 C5.51 Pipe-Tee Vol/ Surf - - - 280- Excluded IV&2500-1. inaccess2Ae in Torus Une Number- 16"-W20-320-15A To valve MOV-39A 16-10-1069 C-C C320 Integral Attach <nent Surf RR-4 - X -

1.0" CC N-509 16-10-1070 C-C C320 Integral Attachment Surf RR-4 - - -

1.0" CC N-509 10-15A-NS-303 N/A N/A Mechanical Snubber -

RR-11 - - - -

PFSK-1944. TS Section 3.6.1 10-15A-NS-304 N/A N/A Mechanical Snubber - RR-11 - - - -

PFSK-1940. TS Section 3.6.1 16-10-1071 C-F-2 C5.51 Reducer-Pipe Vol/ Surf X - -

.500*

16-10-1072 - -

3/4" Branch Connection Surf - - - -

Exempt IVC 1221(c) 16-10-1073 C-F-2 CS S1 6.0" Branch Connection Surf X - - -

16-10-1074 C-F-2 C5.51 Pipe-Pipe Vot/ Surf - - -

.500" Exduded FAC-2500-1 16-10-1075 C-F-2 C5.51 Pipe-Pipe Vot/ Surf - - -

.500" Exduded FAC-2500-1 16-10-1076 - -

3/4" Bra.x:h Connection Surf - - - -

Exempt !WC-1221(c) 16-10-1077 C-F-2 C5.51 Pipe-Valve MOV-39A Vol/ Surf - - -

.500" 16-10-107A C-C C3.20 Integral Attachment Surf RR-4 - - -

.500" CC N-509 FILE- RHR02.10.WPD Page 10 - 90 of 10-92

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$b Third Inservice inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL IS4 INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PERT PER2 PER3 TH?CK REMARKS 10 - Residual Heat Removal System Drawing Number. MSK-3017 Une Number: 16"-W20-320-15A to valve MOV-39A 10-15A-MS-307 N/A N/A Mechanical Snubber - RR-11 - - - -

PFSK-1952. TS Secbon 3.6.1 10-15A-MS-308 N/A N/A M&tw.R Snubber -

RR-11 - - - -

PFSK-1952.TS Sechon 3_6.1 16-10-1077B C-C C320 Integral Attachment Surf RR-4 - - - .500" CC N-509 10-15A-NS-306 N/A N/A Hydraufsc Snubber - RR-11 - - - -

PFSK-1984 TS Sechon 3.6.1 1#,-10-1068 C-F-2 C5.51 Vatve MOV-34A-Reducer Vol/ Surf - - -

.375*

MOV-34A - - 14.0" Valve Botting VT-1 - - - <2* No exam recurred 14-10-1067 C-F-2 C5.51 Valve MOV-34A-Reducer Vol/ Surf - - -

.375*

Une Number: 16"-W20-152-5A 16-10-1066 C-F-2 C5.51 Reducer-Pipe Vol/ Surf - - -

.375" 16-10-1065 - -

1 1/2" Branch Connecdon Surf - - - - ExemptIVC1221(c) 16-10-1064 - -

4.0" Branch Ceis. Surf - - - Exempt 1%C122"(c) 10-5A-NS-302 F-A F120b Non Adjustable VT-3 RR-2 - - - -

PFSK-2126. CC N491-1 16-10-1063 - - n~ Branch Connection Surf - - - -

Exempt W&t221(c) 16-10-1062 - -

3.0* Branch Connection Surf - - - - Exempt IWC1221(c) 16-10-1061 C-F-2 C5.81 6.0"" Branch Connection Surf - X - -

16-10-1060A - -

3/4" Branch Connection Surf - - - - Exempt 1%C1221(c) 16-10-1060 C-C C320 Integral Attachment Surf RR-4 - - - -

CC N-509 FILED RHR02.10.WPD Page 10 - 91 of 10-92

O Jarnes 9Fitzpatrick Nuclerr Power Plant Third Insesvice inspection Interval [[::JAF-tSI-0003|JAF-tSI-0003]] Date January 7,1998 b

$ Ten -Year Inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME ISIINTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE EXAt3 REQ PER1 PER2 PER3 TWCK REMARKS CAT ITEM DESumrTION 10 - Residual Heat Removat System Drawing Number: MSK-3017 Line Number: 16*-W20-152-5A

- Bempt IWC-1221(c) 1 1/2" Branch Connection Surf - - -

16-10-1059 - -

RR-2 PFSK-2085, CC N491-1 F-A F1.206 Non Adjustable VT-3 - - - -

10-5A-NS-300 Surf - - - - Inaccessible 16-10-1054 C-F-2 C5 81 10.0" Branch Connectron X - Reenforong Pad VMd selected for nv 42 9 C-F-2 C5.81 Reenforcing Pad Surf - -

14-10-1055 potential pump discha.ge vibration da nage Surf - - - - bempt IWC-1221(c) 16-10-1053 - - 4.0" Branch Connectron Vot/ Surf - - - .375" 16-10-1052 C-F-2 C5.51 Elbow-Pepe VouSurf - - - .375' Pipe-Elbow 16-10-1051 C-F-2 C5.51 VouSurf - - - .375' &c!uded IWC-2500-1 16-10-1050 C-F-2 C5.51 Pipe-Pipe Vot@ arf - - - 37F Scluded !%C-2500-1 16-10-1049 C-F-2 C5.51 Pipe-Pipe

.3 75- Sciuded IWr,-2500-1 C5.51 Pipe-Pipe Vot/ Surf - - -

16-10-1048 C-F-2 RR-4 .375" Pen. X-210A, CC N-509 C-C C3.20 Integral Attachment Surf - - -

16-10-1047 C-F-2 C5.51 Pipe-Pipe VoUSurf - - -

.375" 6p IWC-2500-1 16-10-1046 i

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1 Ffte: MHPN.10.WPD Page 10 - 92 of 10-92

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third inservice inspectiori interval Date January 7,1998 O N8"Mb Ten -Yearinspection Plan Revision 0 ASME WELD COMPONENT ASME ASME ISIINTERVAL LTH OR CODE REL IDENTIFICAT10N CODE CODE REO PER1 PER2 PER3 THtCK REMARKS ITEM DESCRmisN EXAM CAT f

13 - Reactor Core injection Coofing Drawing Number: MSK-3019 Une No. U"-SLP-152-22 To Suppression Chamber

<2" No exams required. Class Break from 2 to 3 8.0" Va!ve Botting VT-1 - - -

RCl-5 - -

VotiSurf - - .322" Exduded IVC 2500-1 8-13-1003 C-F-2 C5.51 Vafve RCl-5-Pipe -

Surf - - - - Exempt IV&i222(b) 8-13-1004 - - 3/4" Branch Connedian Exempt IWC-1222(b) 3/4" Branch Connechon Surf - - - -

8-13-1005 - -

Vol/ Surf - - .322" Exchded PWC-2500-1 8-1-1000 C-F-2 C5.51 Pipe-Vane RCiC-4 -

- <2* No exams required 8.0" Valve Botting VT-1 - -

RCIC-4 - -

Vol/ Surf - - .322" Exduded rWC-2500-1 8-13-1007 C-F-2 C5.51 Vane RCfC-4-Pipe -

Surf - - - - Exempt IWC-1222(b) 3/4" Branch Cw 6;c0 8-13-1008 - -

Vol/ Surf - - - .322" Excluded hvC-2500-1 0-13-1009 C-F-2 C5.51 Pipe-Valve RCIC-3

- <2" No exams required

- 8.0" Valve Botting VT-1 - -

RCIC-3 -

C5.51 Valve RCIC-3 -Pipe Voi/ Surf - - - .322" Exduded PA"M1 8-13-1010 C-F-2 Vol/ Surf - - .322" Exo!uded hNC-25001 i C5.51 Pips-Elbow l

8-13-1G11 C-F-2 Exduded IWC-2500-1 l C5.51 Eibow-Pipe Vol/ Surf - - - .322" l 8-13-1012 C-F-2 Vol/ Surf - - .322" Exduded IVC 2500-1 8-13-1012A C-F-2 C5.51 Pipe-Pipe -

Surf RR-4 - - .500" Excluded IVC 2500-1.CC N-509. Pen. X-212 C320 Pipe-Penetration 8-13-1013 C-C Vof/ Surf - - .322" Exduded IV&2500-1. Inaccessible in Torus C5.51 Pipe-Eibow 6-13-1014 C-F-2 Page 13 - 1 of 13-3 FILE: RCIC02.13 WPD

James A'FCzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third inservice Inspection Interval Date January 7,1998 g W Ten -Year inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME REL ISilNTERVAL LTH OR CODE CODE IDENTIFICATION CODE REQ PER1 PER2 PER3 THtCK REMARKS ITEM DESCRIPTION EXAM CAT 13 - Reactor Core injection Cooling Drawing Number: MSK-3019 Une No. 8"-SLP-152-22 To Suppression Chamber VT-3 - - - - Inaccessible. Exduded 13-22-NN-14 F-A F120b **on Adgustable

.322" Exduded lYC,-2500-1. Inaccessible in Torus C5.51 Pipe-Pipe Vol/ Surf - - -

0-13-1015 C-F-2

.322" Exduded IWC-2500-1, inaccessible in Torus C-F-2 C5_51 Prpe-Pipe VoVSurf - - -

8-13-1016

.322" Exduded IWC-2500-1, Inaccessible in Toru-C-F-2 C5.51 Efbow-Pipe VouSurf - - -

8-13-1017

.322" Erduded nVC-2500-1, Inaccessible in Torus C-F-2 C5.51 Pipe-Elbow VouSurf - - -

8-13-1018

.322" Exduded IWC-2500-1, inaccessible in Torus C-F-2 C5.51 Elbow-Pipe VouSurf - - -

8-13-1019 VT-3 - - - - Excluded IWC-2500-1. Inaccessible in Torus Support A F-A F1.20b Constraint VoVSurf - - .322" Excluded IWC-2500-1. Inaccessible in Torus C5.51 Pipe-Elbow 8-13-1020 C-F-2 VoVSurf -

.322* Excluded IWC-2500-1. Inaccessible in Torus C5.51 Elbow-Pipe - -

8-13-1921 C-F-2 Exduded IWC-2500-1, inaccessible in Torus F-A F120b Constraint VT-3 - - - -

Support B VT-3 - - - - Exduded IWC-2500-1. Inaccessible in Torus Support C F-A F1.20b Constraint t

l l

I l

Page 13 - 2 of 13-3 FILE- RCIC02.13YtPD

n w s

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h Date January 7,1998

$ Third Inservice inspection Interval Ten -Year Inspection Plar Revision 0 COMPONENT ASME ASME ASME WELD IDENTFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT DEM DESCRIPTION EXAM REO PER1 PER2 PER3 TH1CK REMARKS 13 - Reactor Core injection Cooling Drawing Number: MSK-3020 Une No. 6"-W22-152-16 From Suppressen Chamber 6-13-1045 C-C C.20 Integral Attachment Surf RR-4 - - -

432* Pen. X-224. CC N-509 6-13-1044 C-F-2 C5.51 Pipe-Valve MOV-41 VoVSurf X - -

.732" MOV-41 - - 6.0" Valve Borting VT-1 - - -

<2" No exam requred. Class txeak im 2 to 3 t

F!LE: RCICO2.13 WPD Page 13 - 3 of 13-3

,m i \

James Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] (n \

g h Third Inservice inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL iSI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PERT ,PER2 PER3 THICK REMARMS 10- Core Spray System Drawing Number: MSK-3021 Line Number 16" W23-152-1 A From Pen. X-227A Suppression Chamber l

16-14-700 C-C C320 Integral Attachment Surf RR-4 - - -

.500" Pen. X-227A. CC N-509 16-14-701 C-F-2 C531 Pipe-Valve MOV-7A Vol/ Surf - - X .375" MOV-7A - - 16.0" Valve Botting VT-1 - - -

<2" No exams requwed 16-14-702 C-F-2 C5.51 Valve MOV-7A -Pipe VouSurf - - -

.375" 16-14-702A - --

3/4* Branch Connection Surf - - - -

Exernst IWC-1222(b) 16-14-703 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.375" 16-14-704 C-F-2 C5.51 Elbow-Pipe VouSurf - - -

.375" 16-14-705 - -

1.0" Branch Certnection Surf - - - - Exempt IWC-1222(b) 14-1 A-NS-1 F-A F120b Box restraint VT-3 RR-2 X - - -

PFSK-2511. CC N-491-1 16-14-706 C-F-2 C5.51 Pipe-Pipe Voi/ Surf - - -

.375" Excluded IWC-2500-1 14-1 A-NA-2 F-A F120b Adjustable-Constraint VT-3 RR-2 - - - -

H14-40. CC N-491-1 16-14-706A C-C C320 Integra! Attachment Surf RR-4 - - -

.237" CC N)5O9 16-14-707 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

.375" 16-14-708 C-F-2 C5.51 Elbow-Pipe Vot/ Surf - - -

.375" 16-14-708A C-C C320 Integraf Attachment Surf RR-4 - - - -

Bellows. CC N-509 14-1 A-NS-3 F-A F120b Box Constraint VT-3 RR-2 - - - -

PFSK-2418. CC N-491-1 FILE CS02.14 WPD Page 14 - 1 of 14-19

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James A Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] V)

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4 bMb Third inservice inspection Interval Date January 7,1998 Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ FER1 PER2 PER3 THICK REMARKS

. 14 - Cere Spray System Drawing Number: MSK-3021 U.ie Number 16*-W23-152-1 A From Pen. X-227A S"poression Chamber 16-14-709 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.375*

16-14-710 C-F-2 C5.51 Eibow-Pipe VoVSurf - - -

.375" 16-14-711 - -

3/4" Branch Connection Surf - - - - Exempt MC-1222(b) 16-14-712 - - 2.0" Branch Connection Surf - - - - Exempt IWC-1222(b) i 16-14-712A C-C C320 Integral Attachment Surf RR-4 - - -

.237* CC N-509 l

16-14-713 C-F-2 C5.81 12.0" Branch Connection Surf - - - -

l l 14-1 A-AS-4 F-A F1.20e Variable Spring VT-3 RR-2 - - - -

PFSK-2028. CC N-491-1 l

! Line Number 16"-W23-152-3A i

16-14-716 - -

3/4' Branch Connection Surf - - - - Exempt IWC-1222(b) i 16-14-717 C-F-2 C5.51 Pipe-Flange VoUSurf - - - .375' Flange - -

Flange Bolting VT-1 - - -

<2" No exam required 16-14-718 C-F-2 C5.51 Flange-Reducer Vot/ Surf - - -

.375" ,

16-14-720 - -

1 1/2" Branch Connection Surf f - - -

Exempt IYC,-1222(b) 14-14-721 - - 3/4" Branch Connection Surf - - - - Exempt rWC-1222(b) l 14-14-722 C-F-2 C5.51 Reducer-Flange Vo!/ Surf -f - -

.375' Flange - - Flange Bolting VT-1 - - - <2* No exam required l

l FILE: CS02.14.WPD Page 14 - 2 of 14-19 l

J mes A. Fitzpatrick Nuclerr Power Picnt [[::JAF-tSI-0003|JAF-tSI-0003]] Third inservice Inspection Interval Date January 7,1998 4 bMM Ten -Year inspection Plan Revision 0 ASW WELD COMPONENT ASME ASME REL ISI INTERVAL LTH OR CODE CODE CODC REMARKS IDENTIFICATION DESCRIPTION EXAM REQ PER1 WR2 PER3 THICK CtT ITEM 14 - Core Spray System Drawing Number: MSK-3021 Une Number 16"-W23-152-3A Vol/ Surf - X - .375* Temimal End 14-14-723 C-F-2 C5.51 Flange- CS Pump 14P-1 A uno Number 12"-W23-152-2A To valve CSP-8A Vol/ Surf - - - .375*

12-14-714 C-F-2 C5.51 Pipe-Valve CSP-8A

<2" No exams required. Class break from 2 to NNS 12.0* Vafve Bo!!ing VT-1 - - -

CSP-8A - -

l l

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Page 14 - 3 cf 14 -19 FILE: CS02.14%'PD

%/ (

'v James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third Inservice inspection Interval Date January 7,1998 A lleur M M Ten -Year Inspection Plan Revision 0

D ASME MELD COMPONENT ASME ASME ISI INTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE REQ PER1 PER2 PER3 THICK REMARKS CAT ITEM DE3CRIPTIOf! EXAM 14-Core Spray System Drawing Number: MSK-3021 t_ine Number 16"-W23-152-1B From Pen. X-2278 Suppression Cha nber RR-4 X .375* Pen. X-2278, CC N-509 C-C C3.20 Integral Attachment Serf - -

16-14-800 Vol/ Surf - - - .375" 16-14-801 C-F-2 C5.51 Pipe-Vafve MOV-7B

- - <2" No exams required 16.0" Valve Bolting V T-1 -

MOV-78 - -

C5.51 Valve MOV-78-Pipe Vol/ Surf - - - .375" 16-14-802 C-F-2 Surf - - - - Exempt IWC-1222(b) 16-14-802A - - 3/4" Branch Connection Vol/ Surf - - - 375" 16-t4-803 C-F-2 C5.51 Pipe-Eibow Vol/ Surf - - .375" C5.51 Elbow-Pipe 16-14-803A C-F-2

- Exempt IWC-1222(b) 1.0" Branch Connection Surf - - -

16-14-804 - -

VT-3 RR-2 - - - -

PFSK-2512. CC N-491-1 14-18-NS-5 F-A F1.20b Box Restraint Vol/ Surf - - - 375" Excluded IWC-25'X)-1 1 414-805 C-F 2 C5.51 Pipe-Pipe Surf RR-4 - - - .237" CC N-509 16-14-805A C-C C3.20 Integral Attachment VT-3 RR-2 - - - -

H14-44, CC N-491-1 14-1 B-AN-6 F-A F1.20e Vnriable Spring Vol/ Surf - - - .375" 16-14-806 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - -

.375" 16-14-807 C-F-2 C5.51 Elbow-Pipe -

l Surf RR-4 - - - .375" C.r!!ows, CC N-509 l 16-14-8078 C-C C3.20 Integral Attachment RR-2 PFSK-2454, CC N-491-1 F-A F1.20e Rigid Sway Strut VT-3 - - - -

14-1 B-NS-7 TS Section 3.6.1 And Shock Arrester - RR - - -

Page 14 -4 of 14 -19 FILE: CS02.14.WPD l

1 - - - - - .

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\.b [[::JAF-ISI-0003|JAF-ISI-0003]] 0(.-

James ATFitzpatrick Nuclear Power Plant Third inservice Inspection Interval Date January 7,1998 b

$ Ten -Year inspection Plan Revision O W1 ELD ASME ASME ASME COMPONENT CODE REL ISI INTERVAL LTH OR IDENTIFICATION CODE CODE REMARKS CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK 14 - Core Spray System Drawing Number: MSK-3021 Line Number 16"-W23-152-1B Frorr ' A X-227B Suppression Chamber Surf RR-4 - - -

.237" CC N-509 16-14-807A C-C C320 Integral Attachment Vol/ Surf - - -

_375" 16-14-808 C-F-2 C5.51 Pipe-Elbow C5.51 E! bow-Pipe Vol/ Surf - - -

.375" 16-14-809 C-F-2

- Exempt PAG 1222(b) 3/4" Branch Connection Surf - - -

16-14-810 - -

Surf - - - - Exempt IWC-1222(b)

I 16-14-811 - - 2.0" Branch Comection Surf RR-4 - - .237" CC N-509 C329 integral Attachment 16-14-811 A C-C C-F-2 C5.81 12.0" Branch Connection Surf - - - -

16-14-812 VT-3 RR-2 - - - - H14 21, CC N-491-1 14-1B-AN-8 F-A F1.20c Variable Spring l Surf - - - - Exempt nNC-1222(b) l 16-14-815 - - 3/4" Branch Connection Line Number 16"-W'23-152-38 l

C5.51 Pipe-Flange V "3urf - - - .375" l 16-14-816 C-F-2 VT-1 - - - <2" No exam requ' red Flange - - Flange Botting VouSurf - - .375" 05.51 Flange-Reducer 16-14-817 C-F-2 Surf - - - - Exempt nNC-1222(b) 16-14-819 - - 1 1/2" Branch Connection Surf - - - - Exempt IVE-1222(b) 16-14-820 - - 3/4" Branch Connection C5.51 Reducer-Flange VoVSurf - - - .375" 14-14-821 C-F-2 Page 14 - 5 of 14 -19 FILE: CS02.14 WPD ,

O O J:mes A. Fitzpatrick Nuclear Pnwer Plant [[::JAF-ISI-0003|JAF-ISI-0003]] O

Third Inservice Inspection Interval Date January 7,1998 b

$ Ten - Year inspection Plan Revision 0 ASME WELD t;OMPONENT . ASME ASME ISI INTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE REQ PER1 PER2 PER3 THICK REMARKS CAT ITEM DESCRIPTION EXAM 14 -Core Spray System Drawing Number. MSK4021 Line Number 16"-W23-152-38 VT-1 - - - <2* No exam required Flange - - Flange Botting C5.51 Flange-CS Pump 14P-1B Vol/ Surf X - - .375" Terminal End 14-14-822 C-F-2 Line Number 12"-W23152-28 Vol/ Surf - - - .375*

12-14-813 C-F-2 C5.51 Pipe-Valve CSP-8B

<2" No exam requhed. Class break from 2 to NNS 12.0" Valve Botti. . , VT-1 - - -

CSP-8B - -

T Page 14 - 6 of 14-19 FILE: CS02.14.WPD

9"" AM" y

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James Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h

$ Thhd Inservice inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL 1.TH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 14 - Core Spray Sys*em Drawing Number: MSK-3022 Line Number 12"-W23-3024A From CS Pump 1 A CSP 14P-1A - - CSPump - - - - -

id 'A !!S-10A F-A F1.40 Pump Support VT-3 RR -

X -

CC N-491-1 12-14-724 C-F-2 C5.51 Pump-Elbow VoUSurf -

X -

.406" Terminal End, weld selected for monitoring potential pump discharge vibration damage 14-4A-AS-10 F-A F1.20e Variable Spring VT-3 RR X - -

PFSK-2000. CC N-491-1 12-14-725 C-C C3.20 Integral Attachment Surf RR - -

.216" CC N-509 12-14-726 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.406" 12-14-727 - -

2.0" Branch Connection Surf - - - -

Exempt IWC-1222(b) 12-14-727A - -

3/4" Branch Connection Surf - - - -

Exempt IWC-1222(b) 12-14-7278 - -

3/4" Branch Connection Surf - - - -

Exempt IWC-1222(b) 12-14-728 - -

3.0" Branch Connection Surf - - - -

Exempt IWC-1222(b) l 12-14-729 C-F-2 C5.51 Pipe-Valve CSP-10A VoVSurf - - -

406" I r CSP-10A - -

12.0" Check Valve Botting VT-1 - - -

<2" No exam required l

I 12-14-730 C-F-2 C5.51 Valve CSP-10A-Pipe VoVSurf - - -

.406" 12-14-731 - -

1.0" Branch Connection Surf - - - -

Exempt IWC-1222(b) 12-14-732 - -

2.0" Branch Connection Surf - - - -

Exempt IWC-1222(b) 12-14-733 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

.406" l

t FILE: CS02.14 WPD Page 14 - T of 14-19 l

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Power Third Inservice Inspection Interval Date January 7,1998

$ New Ten - Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REl. ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 4

14 -Core Spray System Drawing Number: MSK-3022 Line Number 12"-W23-302-4A From CS Pump 1 A 12-14-734 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - -

X 406" Weld selected for monitoring potential pump discharge vibration damage 12-14-735 C-F-2 C5.51 Pipe-Elbow Vol/ Surf X - -

.40G" 12-14-736 C72 - C5.51 Elbow-Pipe Vol/ Surf - - -

.406" 12-14-737A - - 2.0" Branch Connection Surf - - - - Exempt IVE-1222(b) l l

l 14-4A-NS-11 F-A F1.20b Vertical Constraint VT-3 RR - - - H14-2, CC N-491-1 12-14-737 - -

3/4" Branch Connechon Surf - - - - Exempt IWC-1222(b) 12-14-738 - -

3/4" Jranch Connection Surf - - - - Exempt IWC-1222(b) l 12-14-739 - -

1 1/2" Branch Connection Surf - - - - Exempt IWC-1222(b) 1

\

12-14-740 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.406" 12-14-741 C-F-2 C5.51 Eibow-Pipe Vol/ Surf - - -

.406" 12-14-742 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.406" r

12-14-743 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

406" l 14-4A-HS-12 N/A N/A Hydraulic Snubber -

RR - - -

PFSK-2209. TS Section 3 6.1 l

12-14-744 C-C C3.20 Integral Attachment Surf RR - -

.750" CC N-509 12-14-745 C-F-2 C5.51 Pipe-Pipe Vo!/ Surf - - -

.406" Excluded IWC-2500-1 12-14-746 - -

3/4" Branch Connection Surf - - - - Exempt IWC-1722(b)

FILE CS02.14.WPD Page 14 - 8 of 14-19

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t/ s James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] v

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$ Third Inservice inspection Interval Ten - Yearinspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CotX CODE REL ISI INTERVAL LTH OR CAT ITEP1 DESCRIPTION gram REQ PER1 PER2 PER3 TH!CK REMARKS 1

14 -Core Spray System Drawing Number: MSK-3022 1.ine Number 12"-W23-302-4A From CS Pump 1A 12-14-747A - -

3/4" Branch Connection Surf - - - - Exempt IWC-1222(b) 12-14-747 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.406" Excluded fWC-2500-1 12-14-748 C-C C3.20 Integral Attachment Surf RR - -

1.0" CC N-509 14-4A-HS-13 N/A N/A Hydraulic Snubber -

RR - - - PFSK-2006, TS Section 3.6.1 12-14-749 - -

2.0" Branch Connection Surf - - - - Exempt IWC-1222(b) 12-14-751 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

.406" 12-14-752 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.406" 12-14-753 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

406" 12-14-754 C-F-2 C5.51 Elbow-Pipe Vot/ Surf - - -

.406" 12-14-755 C-C C3.20 Integral Attachment Surf RR - -

.375" CC N-509 14-4A-NS-16 F-A F1.20e Rigid Sway Strut VT-3 RR - - -

PFSK-2210 CC N-491-1 12-14-756 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.406" Excluded IWC-2500-1 12-14-757 C-C C3.20 Integral Attachment Surf RR -

.500" CC N-509 14-4A-HS-17 . N/A N/A Hydraulic Snubber -

RR - - -

PFSK-2005. TS Section 3.6.1 12-14-758 - -

2.0" Branch Connection Surf - - - - Exempt IWC-1222(b) 12-14-758A C-C C2.20 Integral Attachment Surf RR - -

.750" CC N-509 FILE: CS02.14.WPD Page 14 - 9 of 14 -19

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h Third inservice Inspection interval Date January 7,1998

$ Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 TH!CK REMARKS 14 - Core Spray System Drming Number: MSK-3022 1.ine Number 12"-W23-302-4A From CS Pump 1 A 12-14-759 C-F-2 C5 51 Pipe-Elbow VoVSurf - - - .406"

' 14-4A-NS- 18 F-A F120b Vertical Constraint VT-3 RR -

X - PFSK-1920, CC N-491-1 12-14-760 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.406" 12-14-761 C-F-2 C5.51 Pipe-Elbow Vouf- c - - -

.406" 12-14-762 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.406" 14-4 A-NN-18A F-A F1.20b Non Adjustable VT-3 RR - - - H14-43, CC N-491-1 12-14-763 C-F-2 C5.51 Pipe-Pipe VoVSurf - - -

.406" Excluded IWC-2500-1 14-4A-NS-19 F-A F1.20a Rod Hanger VT-3 RR - - - PFSK-2060, CC N-491-1 12-14-7G3A C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.406" 12-14 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.406" 14-4A-NS-20 F-A F1.20b Vertical Restraint VT-3 RR - - -

PFSK-1915. CC N-491-1 12-14-765 - -

3/4" Branch Connection Surf - - -

Exempt IWC-1222(b) 12-14-766 C-F-2 C5.51 Pipe-Flange VoVSurf - - -

.406" Flange - - Flange Bolting VT-1 - - -

<2" No exam required 12-14 767 C-F-2 C5.51 Flange-Pipe Vo!! Surf - - -

.406" 12-14-768 - -

2.0" Branch Connection Surf - - - - Exempt IWC-1222(b)

FILE: CSU2.14 WPD Page 14 - 10 of 14-19

gx S O J mes . Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

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$g h Third inservice inspection Interval Date January 7,1Pa8 Ten -Yearinspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICK REMARKS 14 -Core Spray System Drawing Number: MSK-3022 Une Number 12"-W23-302-4A From CS Pump 1 A 12-14-769 C-F-2 C5.51 Pipe-Reducer Vo!/ Surf - - -

.406" 10-14-770 C-F-2 C5.51 Reducer-Valve MOV-11 A Vol/ Surf - - -

.594*

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FILE: CS02.14.WPD Page 14 - 11 of 14 -19

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h Date January 7,1998

$b Third Inservice inspection Interval Ten -YearInspection Plan Revision C COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS e.

t 14 - Core Spray System Drawing Number- MSK-3022 Line Number 10"-W23-302-8A 12-14-750A C-C C3.20 Integral Attachment Surf RR - -

.625" Saddle Weid. CC N-509 12-14-750 C-F-2 C5.81 10.0" Branch Connection Surf X - - - Weld selected for monitoring potential pump discharge vibration damage, inaccessible 12-14-750B C-C C3.20 Integral Attachment Surf RR - -

.625" Saddle Weld, CC N-509 10-14-778 C-F-2 C5.51 Pipe-Reducer Vol/ Surf - - -

.365" Exduded IWC-2500-1 14-9A-HS-15 N/A N/A Hydraulic Snubber -

RR - - -

PFSK-2509. TS Section 3.6.1 8-14-780A C-C C3.20 Integral Attachment Surf RR - -

.437' CC N-509 8-14-779 C-F-2 C5.51 Reducer-Valve MOV-26A Vol/ Surf X - -

.322" Weld selected for monitoring potential pump discharge vibration damage Exduded IWC-2500-1 l MOV-26A - - 8.0" Valve Bolting VT-1 - - -

<2" No exam required Line Number: 10"-W23-163-9A 8-14-780 C-F-1 C5.11 Valve MOV-26A-Reducer Vol/ Surf X - -

.365" Weld selected for monitoring potential pump discharge vibration damage, Excluded IVC,-2500-1 8-14-780B C-C C3.20 Integra! Attachment Surf RR - -

CC N-509 14-9A-HS-14 N/A N/A Hydraulic Snubber -

RR - - -

PFSK-2343. TS Section 3.6.1 10-14-781 C-F-1 C5.11 Reducer pipe Vol/ Surf - - -

.365* Excluded IWC-2500-1 10-14-782 - - 3.0" Branch Connection Surf - - - - Exempt IWC-1222(b) 10-14-783 C-F-1 C5.11 Pipe-Elbow Vot/ Surf - - -

.365" Excluded IWC-2500-1 10-14-784 C-F-1 C5.11 Elbow-Elbow Vol/ Surf - - - .365" Excluded IWC-2500-1 PLE: CS02.14 WPD Page 14 - 12 of 14-19

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James . Itzpatrick Nuclect Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Q

h

$ Third Inservice Inspection Interval Ten - Year inspection Plan Date January 7.1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ 'PER1 PER2 PER3 THfCK REMARKS 14 -Core Spray System Drawing Number: MSK-3022 Line Number 10"-W23-163-9A 10-14-785 C-F-1 Co.11 Pipe-Elbow Vot/ Surf - - -

.365" Exduded IWC-2500-1 10-14-785A C-F-1 C5.11 Pipe-Elbow Vol/ Surf - - - .365" Exduded IWC-2500-1 10-14-7858 - - 1 1/2" Branch Connection Surf - - - -

Exempt IWC-1222(b), Continued on MSK-3017 i

?

FILE: CS02.14 WPD Page 14 - 13 of 14-19

V \ _ ./

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] A hMPier Third Inservice inspection Interval Date January 7,1998 Ten - Year Inspection Plat F:evision 0 COMPONENT ASME ASME ASME WELD i IDi: INT 1FICATION CODE CODE CODE REL ISI INTERVAL t.TH OR CAT ITEM DESCRIPTION EXAnt' s

. ') PER1 PER2 PER3 THtCK REMARKS w-8 14 - Core Spray System Drawing Number: MSK-3023 Line Number 12"-W23-302-48 14-48-NS-30A F-A F1.40 CS Pump Support 14P-1B VT-3 RR - -

1.75" CC N-491-1 12-14-823 C-F-2 C5.51 Pump-Elbow Vol/ Surf - X - 406" Weld selected for monitoring potential pump discharge vibration damage. Termtnal End 12-14-823A C-C C3.20 Integral Attachment Surf RR - -

.216" CC N-509 12-14-824 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.406" 14-4B-AN-30 F-A F1.20b Adjustable Constraint VT-3 RR - - H14-24, CC N491-1 12-14-825 - -

3.0" Branch Connection Surf - - - -

Enmpt IWC-1222(b) 12-14-826 - - 2.0" Branch Connection Surf - - - -

Enmpt fWC-1222(b) 12-14-827 - -

3/4" Branch Connection Surf - - - - Exempt (WC-1222(b) 12-14-828 - -

3/4" Branch Connection Surf - - -

Exempt (WC-1222(b) 1

! 12-14-829 C-F-2 C5.51 Pipe-Valve CSP-108 Vol/ Surf - - -

.406" i

CSP-108 - - 12.0" Check Valve Botting VT-1 - - -

<2" No e5am required 12-14-830 C-F-2 C5.51 Valve CSP-108 -Pipe Vol/ Surf - - -

.406" 12-14-831 - -

2.0" Branch Connection Surf - - - - Exempt (WC-1222(b) 12-14-832 - -

1.0" Branch Connection Surf - - - - Exempt '.'WC-1222(b) 12-14-833 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

406" FILE: CS02.14 WPD Page 14 - 14 of 14-19

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] b

$ Third Inservice Irispection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 CCMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL t.TH OR CAT ITEM O'".SCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 14 -Core Spray System Drawing Number: MSK-3023 1.ine Number 12*-W23-3J2-4B 12-14-834 C-F-2 C5.51 Elbow-Pipe VoUSurf - -

X .406" Weld selected for monitoring potentia' pump discharge vibration dama je 12-14-835 - -

1.0" Branch Connection Surf - - - - Exempt IWC-1222(b) 12-14-836 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

.406" 12-14-837 C-F-2 C5.51 Elbow-Pipe Vot/ Surf - - -

406" 12-14-838 - -

3/4" Branch Connection Surf - - - - Exempt IWC-1222(b) 14-4 B-NS-31 F-A F1.2ft Non Adjustable VT-3 RR - - -

H14-25. CC N491-1 12-14-839 - -

3/4* Branch Connection Surf - - - -

Exempt IWC-1222(b) 12-14-840 - -

3/4" Branch Connection Surf - - - - Exempt IWC-1222(b) 12-14-841 C- F-2 C5.51 Pipe-Elbow VoVSurf - - -

.406" 12-14-842 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.40G" 12-14-843 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

406"

?

12-14-844 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

406*

12-14-845 C-C C3.20 Integral Attachment Surf RR - -

.375" CC N-509 14-48-NS-32 F-A F1.20b Box Restraint VT-3 RR - -

.375" PFSK-2358. CC N-491-1 12-14-846A - -

1.0" Branch Connection Surf - - - - Exempt IWC-1222(b) 12-14-846 C-F-2 ;5.51 Pipe-Pipe Vol/ Surf - - -

.406" Excluded TNC-2500-1 Fit.E: CS02.14.WPD Page 14 - 15 of 14-19

Jrmes A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

$g M Third Inservice inspection Interval Date January 7,1998 Ten - Year Inspection Plzn Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 14 - Core Spray System Drawing Number: MSK-3023 Line Number 12"-W23-302-4B 12-14-847 - -

3/4" Branch Connection Surf - - - - Exempt IWC-1222(b) 12-14-848 - -

3/4" Branch Connection Surf - - - - Exempt IWC-1222(b) 12-14-849 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.406" Excluded IWC-2500-1 14-48-NS-33 F-A F1.20b Vertical Support VT-3 RR X - -

PFSK-2007. CC N 491-1 12-14-850 C-C C3.20 Integral Attachment Surf RR X -

1.0" CC N-509 12-14-851 C-F-2 C5.81 10.0" Branch Connection Surf - - -

.625" Weld selected for monitoring potential pump discharge vibration damage, inaccessible Line No.10"-W23-302-88 10-14-851B C-C C3.20 Integral Attachment Surf RR - -

.625" CC N-509 10-14-877 C-F-2 C5 51 Pipe-Reduccr Vol/ Surf - - -

.365" 3-14-8808 C-C C3.20 Integral Attachment Surf R R-4 - - -

.500" CC N-509 8-14-878 C-F-2 C5.51 Reducer-Valve MOV-268 Vol/ Surf - - X .322" Weld selected for monitoring potential pump <!ischarge vibration damage

?

Line Number- 10"-W23-163-9B

MOV-268 - - 8.0" Valve Botting VT-1 - - -

<2" No exam required l

8-14-879 C-F-1 C5.11 Valve MOV-26B-Reducer Vol/ Surf - -

X .322" Weld selected for monitoring potential pump discharge vibration damage 14-98-HS-34 N/A N/A Hydraulic Snubber - RR - - -

PFSK-2392. TS Section 3.6.1 8-14-880A C-C C3.20 Integral Attachment Surf RR - -

.500" CC N-509 FILE: CS02.14 WPD Page 14 - 18 of 14-19 l

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James . Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] b

$ Third loservice inspection Interval Ten -Yearinspection Plan Date January 7.1998 Revision 0 COMPONENT ASME- ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRfPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 14 - Lore Spray System Drawing Number: MSK-3023 Une Number 10"-W23-163-98 14-98-HS-35 N/A N/A Hydraulic Snubber - RR - - -

PFSK-2265. TS Sechon 3.6.1 10-14-880 C-F-1 C5.11 Reducer-Pipe VoVSurf - - -

.365" Excluded IWC-2500-1 10-14-881 - -

3.0" Branch Connection Surf - - - - Exempt (WC-1222(b) 10-14-882 C-F-1 C5.11 Pipe-Elbow Vol/ Surf - - -

.365" Excluded IWC-2500-1 10-14-883 C-F-1 C5.11 Elbow-Pipe VoVSurf - - -

.365" Excluded IWC-2500-1 10-14-884 C-F-1 C5.11 Pipe-Pipe Vol/ Surf - - -

.365* Excluded IWC-2500-1 10-14-884A C-F-1 C5.11 Pipe-Tee VoVSurf - X -

.365" Weld selected for monitoring potential pump discharge vibration damage Excluded IWC-2500-1 Line No.12"-W23-302-4B l

l 12-14-851 A C-C C3.20 Integral Attachment Surf RR - -

.625" Saddie Weld, CC N-SC9 i

j 12-14-852 C-F-2 C5.11 Elbow-Pipe Vot/ Surf - - - .406" 12-14-853 C-F-2 C5.11 Pipe-Elbow Vol/ Surf - - -

.406" r

12-14-854 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

406" l

l 12-14-855 C-F-2 C5.51 Pipe-Elbow VoUSurf - - -

.406" 14-4B-NS-36 F-A F1.20b Vertical Constraint VT-3 RR - - -

PFSK-2524 CC N-491-1 i

12-14-856 C-C C3.20 Integral Attachment Surf RR - -

.375" CC N-509 l

12-14-857 C-F-2 C5.51 Pipe-Pipe VoVSurf - - -

.406" Excluded IWC-2500-1 14-4B-NS-37 F-A F120b Ar.chor VT-3 RR - - - PFSK-1864, CC N-491-1 FILE: CS02.14 WPD Page 14 - 17 of 14-19

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] 4 bMh Third Inservice inspection Interval Date January 7,1998 Ten - Year inspection Plan Revision 0 COMPONENT AFUE ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 14 - Core Spray System Drawing Number: MSK-3023 Line Number 12"-W23-302-4B 12-14-858 C-C C3.20 Integral Attachment Surf RR - -

.500" CC N-509 12-14-859 - -

2.0" Branch Connection Surf - - - - Exempt IWC-1222(b) 14-4B-NS-38 F-A F1.20b Constraint VT-3 RR - -

.500" PFSK-251, CC N-491-1 12-14-869 C-C C3.20 Integral Attachment Surf RR - -

.500" CC N-509 i2-14-861 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

406" 12-14-862 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.406" 14-48-AS-39 F-A F1.20c Variable Spring VT-3 RR -

X - PFSK-2557, CC N-491-1 12-14-863 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.406" Excluded IWC-2500-1 14-48-NS-40 F-A F1.20b Constraint VT-3 RR - - - PFSK-201, CC N-491-1 12-14-864 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.406" 14-48-AS-41 F-A F1.20b Constraint VT-3 RR - - - PFE,K-1678, CC N-491-1 i

12-14-865 C-F-2 C5.51 Flange-Pte Vol/ Surf - - -

.406" 12-14-865A - -

3/4" Branch Connection Surf - - - -

Exempt IWC-1222(b)

Flinge - - Flange Bolting VT-1 - - -

<2* No exam required 12-14-8658 - -

3/4" Branch Connection Surf - - - -

Exempt IWC-1222(b) 12-14-866 C-F-2 C5.51 Pipe-Flange Vol/ Surf - - - 406" i

FILE: CS02.14.WPD Page 14 - 18 of 14-19

f James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

$MMM --""""'

Third Inservice inspection interval Ten - Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 FER3 TH3CK REMARKS 14 - Core Spray System Drawing Number: MSK-3023 Line Number 12".W23-302 4B 12-14-867- - -

2.0" Branch Connection Surf - - - - Exempt IWC-1222@)

12-14-868 C-F-2 C5.51 Reducer-Pipe Vol/ Surf - - -

406*

10-14-869 C-F-2 C5.51 Reducer-Valve MOV-118 Vol/ Surf - - -

.594-t FILE CS02.14.WPD Page 14 - 19 of 14-19

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] MNewM W Third Inservice Inspection Interval Date January 7,1998 Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 TMcK REMARKS t

23 - High Pressure Cooling injection Drawing Number: MSK-3024 Line No.10"-SHP-902-19 From MOV-16 10-23-673 C-F-2 C5.51 Valve MOV-16 -Pipe Vot/ Surf X - -

.594* Class break from 1 to 2 10-23-674 - - 2.0" Branch Connection Surf - - - - Exempt IYC.1222(a) 10-23-C75 C-F-2 C5.81 10.0" Branch Connection Surf -

X - -

10-23-682 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - X -

.594*

10-23-683 C-F-2 C5.51 Elbow-Ppe Vol/ Surf - -

X .594*

10-23-684 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

.594*

10-23-685 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.594*

10-23-686 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.594" 10-23-687 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.594*

I 10-23-688 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.594" 10-23-689 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - -

.594*

23-19-AS-9 t-A F1.20c Variable Spring VT-3 RR-2 - - - -

PFSK-2173. CC N-491-1 l

10-23-690 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.594*

10-23-690A C-C C3.20 Integral Attachment Surf RR-4 - - -

.280" CC N-509 l

23-19-HS-10 N/A N/A Hydraulic Snubber - RR.11 - - -

PFSK-2036 TS Secbon 3.6.1

( 1(;-23491 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.594" l

FILE: HPCl02.23.WPD Page 23 - 1 of 23-19

(-y ,

YY James A Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] g Po u r Third Inservice inspection Interval Ten -Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR l CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICK REMARKS l ,

23 - High Pressure Cooling injection Drawing Number: MSK-3024 Line No.10"-SHP-902-19 From MOV-16 23-19-AN-11 F-A F120e Variable Spring VT-3 RR-2 - - - -

PFSK-1453. CC N-491-1 23-19-NN-12 F-A F120b Rigid Support VT-3 RR-2 - - - - PFSK-4349. CC N491-1 10-23-692 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.594* Excluded r/C,-2500-1 23-19-HS-13 N/A N/A Hydraulic Snubber -

RR - - -

PFSK1452. TS Section 3.6.1 10-23-693 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.594*

23-19-AN-14 F-A F1.20e Variable Spring VT-3 RR-2 - - - -

H23-97/PFSK-5655. CC N-491-1 10-23-693A C-C C320 Integral Attachment Surf RR-4 - - -

.500" CC N-509 10-23-694 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.594*

10-23-694A C-C C320 Integral Attachment Surf RR-4 - - -

280- CC N-509 23-19-HS-15 N/A N/A Hydraulic Snubber -

RR - - -

PFSK-2041. TS Section 3.6.1 23-19-NN-16 F-A~ F1.20b Non Adjustable VT-3 RR-2 - - - - CC N-491-1 10-23-695 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

.594* t 10-2-695A C-C C3.20 Integral Attachment Surf RR-4 - - -

.375" CC N-509 23-19-HS-17 N/A N/A Hydraulic Snubber - RR - - -

PFSK-2293. TS Section 3.6.1 23-19-AS-18 F-A F1.20c Variable Spring Support VT-3 RR-2 - -

X -

PFSK-2301. CC N-491-1 10-23-6958 C-C C3.20 Integral Attachment Surf RR-4 - -

X .625" CC N-509 FILE: HPC102.23.WPD Page 23 - 2 of 23 - 19

O 9 James A. Fitzpatrick Nuclear Power PIant [[::JAF-TI-0003|JAF-TI-0003]] O

A New M W Third Inservice Inspection Interval Date ranuary 7,1998 Ten - Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD tDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 TH1CK REMARKS 23 - High Pressure Cooling injection Drawing Number: MSK-3024 Line No.10"-SHP-902-19 From MOV-16 10-23-696 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.594*

23-19-NS-18A F-A F1.20b Rigid Support VT-3 RR-2 - - - -

CC N-491-1 10-23-696A C-C C3.20 Integral Attachment Surf RR-4 - - - 375' CC N-509 10-23-697 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

.594" 10-23-698 C-F-2 C5.51 Elbow-Pipe VoUSurf - - -

.594*

10-23-699 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

.594" 10-23-699A C-C C3.20 Integral Attachment Surf RR-4 - - - .500* CC N-509 23-19-AS-19 F-A F120c Variable Spring VT-3 RR-2 - - - -

PFSK-2304. CC N-491-1 10-23-700 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.594" 10-23-701 - -

3/4" Branch Connection Surf - - - - Exempt IWC-1222(b) 23-19-NS-20 F-A F1.20e Rigid Sway Strut VT-3 RR-2 - - X -

PFSK-2207. CC N-491-1 10-23-702 - - 1.0" Branch Connection Surf - - - -

Ex9mpt (WC-1222(b) 10-23-703 - -

3/4' Branch Connection Surf - - - - Exempt IWC-1222(b) 10-23-704 C-F-2 C5.51 Pipe-Tee VoVSurf - - -

.594" 10-23-705 C-F-2 C5.51 Tee-Pipe Vol/ Surf - - -

.594" 10-23-706 - -

1.0" Branch Connection Surf - - - - Exempt IWC-1222(b)

FILE: HPC102.23.WPD Page 23 - 3 of 23 -19

y- -

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h

$ Third Inservice Inspection Interval Ten - Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL 138 INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 23 - High Pressure Cooling in}ection Drawing Number: MSK-3024 Une No.10"-SHP-902-19 From MOV-16 10-23-707 C-F-2 C5.51 Pipe-Cap VollSurf - - - .594*

10-23-708 - - 3/4* Branch Connection Surf - - - -

Exempt IWC-1222(b) 10-23-709 C-F-2 C5.51 Tee-Pipe VoUSurf - - -

.594*

10-22 .10 C-F-2 C5.51 Pipe-Valve MOV-14 Vol/ Surf - - - .594*

MOV-14 - -

10.0" Valve Bolting VT-1 - - -

<2* No exam required 10-23-711 C-F-2 C5 51 Valve MOV-14 -Pipe Vol/ Surf - - -

.594*

23-19-AS-19A F-A F1.20c Variable Spring VT-3 RR-2 - - - - PFSK-5631, CC N-491-1 10-23-711 A C-C C3.20 Integral Attachment Surf RR-4 - - -

.500* CC N-509 10-23-712 C-F-2 C5.51 Pipe-Flange Vct/ Surf - - -

.594* Turbine 23-TU-2 23-19-NS-20A F-A F1.40 Turbine Support VT-3 - -

X -

CC N-491-1 Une No.10"-SHP-902-34 From Pen. X-11 10-23-677 C-F-2 C5.51 Pipe-Elbow Vol/ Surf X - -

.594* r 10-23-678 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.594*

23-34-AS-6 F-A F1.20c Variable Spring VT-3 RR-2 - - - -

PFSK-1889 CC N-491-1 23-34-HS-7 N/A N/A Hydrau!ic Snubber -

RR - - -

PFSK-1890. TS Section 3.6.1

( 10-23-679 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.594*

I l

l l

FILE HPC102.23.WPD Page 23 -4 of 23 -19

v t s James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h Third inservice Inspection interval Date January 7,1998 Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 23 - High Pressuro Cooling !njection Drawing Number: MSK-3024 Line No.10"-SHP-902-34 From Pen X-11 10-23-680 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.594*

10-23-681 C-F-2 C5.5 t Pipe-Elbow Vol/ Surf - - - .594" 10-23-681 A C-F-2 C5.51 Elbow-Tee Vot/ Surf - - -

.594*

10-23-6818 - -

2.0" Branch Connection Surf - - - - Exempt IWC-1222(b) 10-23-681C C-F-2 C5.51 Tee-reducer Vot/ Surf - - -

.594* Cont On MSK-3015 10-23-681D C-F-2 C5.51 Tee. Reducer Vot/ Surf - - -

594* Cont On MSK-3014

?

FILE- HPC102.23.WPD Page 23 - 5 of 23 -19

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] M NewMhser Third Inservice inspection Interval Date January 7,1998 Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS t

' 23 - High Pressure Cooling injection Drawing Number- MSK-3025 Line No.14"-W25-902-3 From HPCI Pump 23P-1M 23-3-NS-43A F-A F1.40 Pump Support VT-3 - - -

X CC N-491-1 14-23-476 C-F-2 C5.51 Reducer-Pump 23P-1M Vol/ Surf X - -

.750" Terminal End 14-23-475 C-F-2 C5.51 Pipe-Reducer Vol/ Surf -

X -

.750" 14-23-474 - -

2.0" Branch Connection Surf - - - - Exempt PNC-1222(b) 14-23-473A C-C C3 20 Intsgral Attachment Surf RR-4 - - -

.237" CC N-509 23-3-AN-43 F-A F1.20c Variable Spring VT-3 RR-2 - - - -

H23-22. CC N-491-1 I 14-23-473 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - X .750" 14-23-472 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.750" 14-23-471 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - - .750" 14-23-470 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - - .750" 23-3-NS-42A F-A F1.20b VertK:alConstraint VT-3 RR-2 - - - - H23-23, CC N-491-1 23-3-NS-42 F-A F1.20b LateralRestraint VT-3 RR-2 - - - -

PFSK-1939. CC N-491-1 14-23-4698 C-C C3.20 Integral Attachment Surf RR-4 - - -

.322" CC N-509 23-3-NS-41 F-A F1.20a Rod Hanger VT-3 RR-2 - - - -

PFSK-1986. CC N-491-1 23-3-NS-40 F-A F1.20e Rigid Sway Strut VT-3 RR-2 - - - - PFSK-1985, CC N-491-1 14-23-469A C-C C3.20 Integral Attachment Surf RR-4 - - -

.375* CC N-509 FILE: HPCl02.23.WPD Page 23 - 6 of 23-19

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] M NewMPimer Third Inservice inspection Interval Date January 7,1998 Ten -Year hsDection Plan Revision 0 COMPONENT ASME ASME ASME WEl.D IDENTIFICATION CODE CODE CODE REL ISI INTERVAL - LTH OR CAT ITEM DESCRIPTIO,N EXAM REQ PER1 PER2 PER3 THICK REMARKS 23 - High Pressure Cooling injection Drewing Number: MSK-3025 Une No.14"-W25-902-3 From HPCI Pump 23P-1M 14-23-469 C-F-2 C5.31 Elbow-Pipe

. Vol/ Surf - - -

.750" 14-23-468 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.750" 14-23-467 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.750" 14-23-466 C-F-2 C5.51 Pipe-Elbow VouSuii - - -

.750" 23-3-NS-39 F-A F120b VerticalConstraint VT-3 RR-2 - - - - H23-26, CC N-491-1 14-23-465 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.750" Excluded IWC-2500-1 14-23-464 C-F-2 C5.51 Pipe-Elbow VoVSurf - - -

.750" 14-23-463 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.750" 14-23-462 - -

2.0" Branch Connection Surf - - - - Exempt IWC-1222(b) 14-23-461 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

.750" 14-23-460A C-C C3.20 Integral Attachment Surf RR-4 -' X -

.750" CC N-509 23-3-NS-38 F-A F1.20b Vertical Constraint VT-3 RR-2 -

X - -

H2}-27 CC N-491-1 14-23-460 C-F-2 C5.51 Elbow-Pipe VoUSurf - - -

.750" 14-23-459 - -

3/4" Branch Connection Surf - - - - Exempt IWC-1222(b) 14-23-458A C-C C3.20 Integral Attachment Surf RR-4 - - -

.750" CC N-509 23-3-NS-37 F-A F1.20b LateralRestraint VT-3 RR-2 - -

X -

PFSK-1939. CC N-491-1 FILE: HPC102.23.WPD Page 23 -7 of 23 -19

'w] \j 8am A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Q)

I g h Third inservice Inspection Interval Ten - Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD

[ IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR i CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMAR.KS 9

23 - High Press.are Cooling injection Drawing Number: MSK-3025 Line No.14"-W25-902-3 From HPCI Pump 23P-1M 14-23-458 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.750"14-234 57 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.750" 23-3-NN-3G F-A F1.20b Constraint VT-3 RR-2 - - - - H23-43, CC N-491-1 23-3-NS-35 F-A F1.20a Rod Hanger VT-3 RR-2 - - - -

PFSK-2274. CC N-491 1

, 14-23-456 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.750" Excluded IWC-2500-1 1

23-3-NS-34 F-A F1.20a Rod Hanger VT-3 RR-2 - - - - PFSK-2217, CC N-491-1 14-23-455 - - 3/4" Branch Connection Surf - - - - Exempt IWC-1222(b) 14-23-454 - -

4.0" Branch Connection Surf - - - -

Exempt IYC1222(b) l 23-3-NS-33 F-A F1.20b Anchor VT-3 RR-2 - - - -

PFSK-1960. CC N-491-1 14-23-453A C-C C3.20 Integral Attachment Surf RR-4 - - -

.500" CC N-509 14-23-453 C-F-2 C5.51 Pipe-Flange Vol/ Surf - - -

.750" Flange - -

Flange Botting VT-1 - - -

<2" Nopxam required 14-23-452 C-F-2 C5.51 Flange-Pipe Vol/ Surf - - -

.750" l

23-3-NS-32 F-A F1.20b Anchor VT-3 RR-2 - - - -

PFSK-2530. CC N-491-1 14-23-451 - -

1.0" Branch Connection Surf - - - -

Exempt IWC-1222(b) 14-23-450 C-F-2 C5.51 P:pe-Pipe Vol/ Surf - - -

.750" Excluded IVC 2500-1 l

FILE: HPC102.23.WPD Page 23 - 8 of 23 -19

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] A leewVorkPtmer Third inservice Inspection Interval Date January 7,1998

&kW Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS

23. High Pr?ssure Cooling injection Drawing Number: MSK-3026 Line Number: 14"-W25-902-3 From HPCI Pump 23P-1M 23-3-NS-31 F-A F1.20b Constraint VT-3 RR-2 - - - - H23-48, CC N-491-1 14-23-449 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.750" Excluded M2500-1 23-3-NS-30 F-A F1.20b Constraint VT-3 RR-2 - - - -

H23-49. CC N-491-1 14-23-448 - -

3/4" Branch Connection Sud - - - - Exempt PNC-1222(b) 14-23-447 C-F-2 C5.51 Pipe-Valve MOV-20 Vol/ Surf - - - .750" MOV-20 - - 14.0" Valve Bolting VT-1 - - - <2" No exam required i 14-23-446 C-F-2 C5.51 Va!ve MOV-20 -Tee Vol/ Surf - - - .750" 23-3A-NS-22 F-A F1.20b Constraint VT-3 RR-2 X - - - H23-50, CC N-491-1 14-23-438A C-C C3.20 Integrat Attachment D;rf RR-4 - - -

1.0" CC N-509 l

14-23-436 C-F-2 C5.51 Tee-Valve MOV-19 Vol/ Surf - - - .750" MOV-19 - - 14.0" Valve Bolting VT-1 - - -

<2" No exam required, Class break from 2 to 1 l

Line No.10"-W25-902-4 to Valve MOV-21 ,

10-23-437 C-F-2 C5.51 Reducing Tee-pine Voi/ Surf -

X -

.594" 10-23-438 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

.594*

10-23-439 C-F-2 C5.51 Elbow-Pipe Vot/ Surf - - -

.594" 23-4-NS-23 F-A F1.20a Red Hanger VT-3 RR-2 X - - -

PFSK-2262. CC N-491-1 I

FILE HPC102.23.WPD Page 23 - 9 of 23-19 l

(!

g ) { i w/ J Gi James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] g lysgrMPimer Third inservice inspection Interval Date January 7,1998

- """"' s Ten -Yearinspection Plan Revision 0 COMPONENT ASME ASME ASME WELD 1DENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 23 - High Pressure Cooling in}ection Drawing Number: MSK-3026 Line Number: 10"-W25 902-4 10-23-439A - -

1.0" Branch Connection Surf - - - - Exempt IWC-1222(b) 10-23-440 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - - .594* ExcludM IWC-2500-1 23-4-NS-24 F-A F1.20e Rigid Sway Strut VT-3 RR-2 - - - - PFSK-2182, CC N-491-1 23-4-NS-25 F-A F1.20b Anchor VT-3 RR-2 - - - -

PFSK-1945 CC N-491-1 10-23-440A C-C C3.20 Integral Attachment Surf RR-4 - - -

.500" CC N-509 10-23-441 C-F-2 C5.51 Pipe-Flange Vol/ Surf - - -

.594" Ft:nge - -

Flange Bolting VT-1 - - -

<2" No exam required 10-23-442 C-F-2 C5.51 Flange-Pipe Vol/ Surf - - -

.594*

23-4-NN-26 F-A F1.20b Anchor

T-3 RR-2 - - - -

H23-53. CC N-491-1 10-23-443 C-F-2 C5.51 Pipe-Reducer Vol/ Surf - - -

.594*

8-23-444 C-F-2 C5.51 Reducer-Valve MOV-21 Vol/ Surf - - -

.594" MOV-21 - - 8.0" Valve Bolting VT-1 - - -

<2* No exam required t

FILE- HPC102.23.WPD Page 23 - 10 of 23 -19 .

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] 4 bMM Third Inservice Insnection Interval Date January 7,1998

Ten -Yearinspection Plan Rev$sion 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICM REMARKS 23 - High Pressure Cooling injection Drawing Number: FCKM027 Line No. 20"-SLP 1.52-28 3 HPCI Turbine 23TU-2 20-23-521 - -

3/4" Branch Connection Surt - - - - Exempt IWC-1222(b) 20-23-520 C-F-2 C5.51 Pipe-Cap Vol/ Surf - - -

.375" 20-23-519 - -

2.0" Branch Connection Surf - - - - Exempt IWC-1222(b) 20-23-518 - -

1.0" Branch Connection Surf - - - - Exempt IWC-1222(b) 20-23-517 - -

1.0" Branch Connection Surf - - - - Exempt IWC-1222(b) 20-23-515 - - 3/4" Branch Connection Surf - - - - Exempt IWC-1222(b) 18-23-514 C-F-2 C5.51 Pipe-Flange Vol/ Surf - -

X .375" 20-23-513 C-F-2 C5.81 18.0" Branch Connection Surf - -

X -

20-23-512 - - 3/4" Branch Connection Surf - - - - Exempt IWC-1222(b) 20-23-512A - - 1.0" Branch Connection Surf - - - - Exempt IWC-1222(b) 20-23-511 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.375" Excluded IWC-2500-1 20-23-510 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.375* ,

^

23-25-AN-85 F-A F1.20c Variable Spring VT-3 RR-2 X - - - H23-1, CC N-491-1 20-23-5098 C-C C3.20 Integral Attachment Surf RR-4 X - -

1.0" CC N-509 20-23-509 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.375" 23-25-NS-86 F-A F1.20e Rigid Sway Strut VT-3 RR-2 - - - -

PFSK-1955. CC N-491-1 FILE: HPCl02.23.WPD Page 23 - 11 of 23 -19

O h James

9. Fitzpatrick Nucle:r Power Plant Third Inservice inspection Interval [[::JAF-ISI-0003|JAF-ISI-0003]] Date January 7,1998

$ Ten -Year Inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME ISI INTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE EXAM REO PER1 PER2 PER3 THICK REMARKS CAT ITEM DESCRIPTION 23 - High Pressure Cooling injec'lon Dr.. wing Number- MSK-3027 Line No. 20"-SLP-1f,2-25 from HPCI Turbine 23TU-2 Surf RR-4 - - - .250" CC N-509 20-23-508A C-C C320 Integra! Attachment PFSK-2223, CC N-491-1 F1.20e Rigid Sway Strut VT-3 RR-2 - - - -

23-25-NS-87 F-A Surf RR-4 - - - .25' CC N-509 20-23-508AA C-C C3.20 Integral Attachment Surf - - - - Exempt IWC-1222(b) 20-23-508 - - 3/4" Branch Connection Surf - - - - Exempt IVE,-1222(b) 20-23-507 - - 3/4" Branch Connection

- Exempt IWC-1222(b) 3/4* Branch Connection Surf - - -

20-23-506 - -

PFSK-1958. CC N-491-1, inaccessible in Torus F1.20e Rigid Sway Strut VT-3 RR-2 - - - -

23-25-NS-84 F-A Vol/ Surf - - - .375*

20-23-505 C-F-2 C5.51 Pipe-Tee C5.51 Reducer-Flange Vol/ Surf - - - .375" 16-23-503 C-F-2 Vol/ Surf - - - .375" 20-23-502 C-F-2 C5.51 Tee-Reducer Vol/ Surf - - .375*

C5.51 Pipe-Tee 20-23-501 C-F-2 l Surf RR-4 X -

1.25' CC,N-509 C3.20 Integral Attachment 20-23-500A C-C VT-3 RR-2 - X - 1.25 PFSK-1987. CC N-491-1 23-25 NS-82 F-A F1.20b VerticalConstraint C5.51 Elbow-Pipe Vol/ Surf - - - .375" 20-23-500 C-F-2 Vol/ Surf - - .375" 20-23-499 C-F-2 C5.51 Pipe-Elbow -

Surf - - - - Exempt IWC-1222(b) 20-23-498 - - 3/4" Branch Connection Page 23 - 12 of 23 -19 FILE: HPCl02.23.WPD

~

O James N. Fitzpatrick Nuclear Power Plant Third Inservice Inspection I.tterval JAF-IS'-0003 Date January 7,1998 h

$ Ten -Year Inspection Plan Revision 0 ASME IMELD COMPONENT ASME ASME LTH OR CODE REL ISI INTERVAL IDENTIFICATION N CCDE EXAM REO PERT FER2 PER3 THrCK REMARKS CAT ITEM DESQurirvN 23 - High Pressure Cooling injection Drawing Number: MSK-3027 Line No. 20~-SLP-152-25 from HPCI Tutme 23TU-2 C5.51 Elbow-Pipe Vot/ Surf - - - .375*

20-23-497 C-F-2 RR-4 - - a.T CC N-509 20-23-490A C-C C320 Integral Attachment -

RR - - - PFSK-2247 TS Sectoi 3.6.1 23-25-HS-81 N/A N/A Hydraulic Snubber -

Surf - - - - Exemet IVC 1222(b) 20-23-496 - - 2.0" Branch Connechon VouSurf - - - 375*

20-23-495 C-F-2 C5.51 Valve HPI-65 -Elbow VT-1 - - <2" No exam required HPI-65 - - 20.0" Vahre Bolting -

Surf - - - - Exempt IVC 12z2(t) 20-23-4948 - -

3/4" Branch Connection Surf - - - - Exempt IVC 1222(b) 20-23-494A - - 3/4" Branch Connection VouSurf - - - .375' 20-23-494 C-F-2 CSI1 Reducer-Vafve HPI-65 Surf - - - - E:empt IYC1222(b) 20-23-493 C-F-2 - 1.0" Branch Comection durf RR-4 - - - CC N-509 20-23-493A C-C C320 integra! Attachment -

Vol/Sorf . - - .375* r 16223-492 C-F-2 C5.51 Valve HPI-12 -Reducer VT-1 -

<2* No exam requwed HT'l-12 - - 16.0" Valve Botting - -

Surf - - - - Exempt rWC-1222(b) 16-23-4908 - - 3/4" Branch Connection Surf - - - - Exerrpt IWC-1222(b) 1C 23-490A - - 1.0" Branch Connection VouSurf - - -

.375" 16-23-490 C-F-2 C5.51 Valve HP12-HPI-11 Page 23 - 13 of 23 - 19 FILE: HPC10223.WPD

O C James A. Fitzpatrick Nuclear Power Plant [[::JAF-tSI-0003|JAF-tSI-0003]] O

Third Inservice inspection it.terval Date January 7,1998 b

$ Ten -Yearinspection Plan Revis3 ort 0 ASME WELD COlnPONENT ASME ASME ISI INTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE REO PERT PER2 PER3 Tl#CK REMARKS CAT ITEM DESCRIPTION EXAM 23 -High Pressure Cooling injection Drawing Number: MSK-3027 Line No. 20"-SLP-152-25 from HPCI Turtnne 23TU-2 VT-1 - - <2* No exam regured HPI-11 - - 16.0" Valve Bolting -

V6-3 RR-2 - - - PFSK-2494. CC N 491-1 23-25-NS-80 F-A F120a Rod Hanger -

VoUSurf - - - .375*

16-23-489 C-F-2 C5.51 Reducer-Valve HPI-11 Une No. 24"-SLP-152-26 From Pen. X-214 C5.51 Pipe-Reducer VouSurf - - X .375*

l 24-23-488 C-F-2 l

- - - Exempt fWC.-1222(b) 2.0" Branch Connection Sewf -

24-23-487 - -

VoVSurf - - - 375* Excluded IWC-2500-1 24-23-486 C-F-2 C5.51 PipePipe Surf RR-4 - - .375* CC N-509 24-23-485 C-C C3.20 Integraf Attachment -

VoVSurf - .375" Excluded IWC-2300-1 C5.51 Pipe-Pipe - -

24-23-484 C-F-2 C5.51 Elbow-Pipe VoVSurf - - - .375* Inaccessible in Torus I 2?c23483 C-F-2 VoVSurf - - - .3) ' inaccessib.e in Terus 24-23-482 C-F-2 CSS 1 Elbow-Elbow VoVSurf - .375* Inaccessibse in Torus C5.51 Pipe-Erbow - -

24-23-481 C-F-2 Pipe-Pipe VouSurf - - - 375" Excluded IM-2500-1 24-23-480 C-F-2 C5.5*

FILE: HPCIO2.23.WPD Page 23 - 14 of 23 - 19

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James A. Fitzpatrick Nuclear Power Plant JA F-ISI-0003 I

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A NowVukPemer Third Inservice inspection Interval Date January 7,1998 Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTKM4 EXAM REO PER1 PER2 PER3 THICK REMARKS 23 -High Pressure Coofing Injection Drawing Number: MSK-3028 Line No.16"-W25-152-7 From Pen. X-226 16-23-525 C-C C320 Integra! Attachment Surf Rf<-4 - - -

.375" CC N-509 16-23-526 C-F-2 C5.51 Pipe-Valve MOV-98 Vol/ Surf -

X - .375*

MOV-98 - - 16.0" Valve Bolting VT-1 - - -

<2" No exam requ red 16-23-527 C-F-2 C5.51 Valve MOV-98 -Eibow VoVSurf - - -

275' 16-23-528 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - - .375' 16-23-529 - -

3/4* Branch Connection Surf - - - - Exempt IWC-1222(b) 23-17-NS-86 F-A F120e Rigid Strut VT-3 RR-2 - - - - PFSK-2305, CC N-491-1 16-23-530 C-F-2 C5.51 Pip > Elbow Vol/ Surf - - -

.375^

16-23-531 C-F-2 C5.51 Elbow-Pipe vouSurf - - -

.375' 16-23-532 C-F-2 C5.51 Ptpe-Elbnw Vol/ Surf - - -

.375" 16-23-533 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.375' 23-17-NS-86A F-A F1205 Box Constraint VT-3 RR-2 - X - -

PFSK-983. CC N-491-1 16-23-532A C-C C320 Integral Attachment Surf RR-4 - X -

.750" CC N-509

S-23-534 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.375' Excluded MIC-2500-1 23-17-HS-88 N/A N/A Hydraulic Snubber - RR - - -

H23-89. TS Section 3.6.1 23 17-HS-87 N/A N/A Hydraulic Snubber - RR - - -

PFSK-2248. TS Section 3.6.1 FILE- HPC102.23.WPD Page 23 - 15 of 23 -19

V x ./

James A"Fitzpatrick Nuclear Power Plant [[::JAF-tSI-C003|JAF-tSI-C003]] V

A 15ewMh Third Inservice inspection Interval Date January 7,1998 Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI IP8TERVAL LTT OR CAT ITEM DESCRfPTION EXAM REQ PER1 PER2 PER3 TMrCM REMARKS 8

23 - High Pressure Cooling injection Drawing Number: MSK-3028 Une No.16*-W25-152-7 From Pen. X-226 16-23-535 C-C C320 Integral Attachme it Surf RR-4 - -

X .750" CC N-509 16-23-536 C-F-2 C5.51 Pipe-E bow Vol/ Surf - X -

.375" 16-23-539 C-F-2 C5.51 Elbow-Pipe VouSurf - -

X .375" 16-23-538 - -

3/4" Branch Connection Surf - - - - Exempt IWC *~'N 16-23-537 - - 3/4" Branch Connection Sud - - - - Exempt rvNC-1222(b) 16-23-540 C-F-2 C5.51 Pipe-Valve HPI-61 Vol/ Surf - - -

.375" HPI-61 - - 16.0" Valve t3otting VT-1 - - -

<2" No exam requrred 16-2-541 C-F-2 C5.51 Vafve HPI-61 -Valve MOV-57 VouSurf - - -

375*

MOV-57 - - 16.0* Valve Botting VT-1 - - -

<2" No exam required Une No.16"-WCP-152-1 to Pump 23P-18 Suction 16-23-542 C-F-2 C5.51 Valve MOV-57 -Tee Vot' Surf - - -

.375" 16-23-543 C-F-2 C5.51 Tee-Pipe VoVSurf - - -

.375* r 16-23-544 C-C C320 Integr8 Attachment Surf RR-4 - - -

2 37" CC N-509 23-1-AN-89 F-A F120e Variable Spring VT-3 RR-2 - - - -

H23-30. CC N-491 1 16-23-545 - -

3/4 Branch Connection Surf - - - - Exempt IWC-1222(b) 16-23-546 - -

3/4" Branch Connet.fion Surf - - - - Exempt IWC-1222(b)

FILE: HPC102.23.WPD Page 23 - 16 of 23 -19

(' :

Jamer. . tzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] b

$ Third Inservice Inspection Interval Ten -Yearinspection Phn Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCR1pTION EXAM REQ PER1 FER2 PER3 TieCK REMARMS P

23 - High Pressure Cooling injection Drawing Number: MSK-3028 Line No.16"-WCP-152-1 To Pump 23P-18 Suction 16-23-547 - - 3/4" Branch Connection Surf - - - - Exempt LC1222(b) 13-23-548 C-F-2 C5.51 riye-Elbow Vo!/ Surf - - -

.375*

16-23-549 - - 3/4" Branch Connedion Surf - - - - Exempt IWC-1222(b) 16-23-550 - -

3/4* Branch Connection Surf - - - - Exempt IWC-1222(b) l 16-23-552 C-F-2 C5.51 Elbow-Flange VoLSurf - - -

.375*

l

[ Flange - - Flange Bolting VT-1 - - -

<2" No exam required 16-23-553 C-F-2 C5.51 Flange-Pipe Vol/Su f - - -

.375*

l 16-23-554 C-F-2 C5.51 Pine-Flange Vot/ Surf -

X -

.375*

, Flange - - Flange Botting VT-1 - - - <2* No exam requwed j 16-23-555 C-F-2 C' 51 Flange-Reducer (16"x147 Vol/ Surf - - -

.375*

l 14-23-557 C-F-2 C5.51 Reducer- HPCI Pump Suction Vol/ Surf - -

X .375" Pump 20P-18 16-23-556 - -

3/4" Branch Connection Surf - - - - Exempt IWC-1222(b)

I I

i FILE: HPCl02.23.WPD Page 23 - 17 of 23 -19

Jarnes Fitzpatrick Nuclear Power Plant JA:-ISI-0003 g b Third inservice Inspection Interval Ten -Year inspection Plan Data January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DidSCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 23 - High Pressure Cooling injection Drawing Number: MSK-3028 Une No.16 -WCP-152-1 from Condensate Storage Tank 16-23-577 C-F-2 C5.51 Valve MOV-17-Tank Vol/ Surf - - -

.375-MOV-17 - - 16.0" Valve Bottrng VT-1 - - - <2" No exam required

~

16-23-576 C-F-2 C5.51 Valve MOV valve HPI-32 Vol/ Surf - - -

.375*

16-23-574 - -

3!4* Branch Connechon Surf - - - - Exempt IWC-1222(b) 23-1-NN-98 F-A F120a Rod Hanger VT-3 RR-2 - - - -

PFSK-2118. CC N-491-1 16-23-573 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

.375* Excluded IWC-2500-1 2' 1-NS-97 F-A F120b Rigid Support VT-3 RR-2 - - - -

H23-36. CC N-491-1 23-1-NS-96 F-A F120b Rigid Support VT-3 RR-2 - - - -

H23-35. CC N-491-1 16-23-572 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.375*

16-23-571 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.375*

23-1-NS-95 F-A F120b Lateral Support VT-3 RR-2 - - - -

H23-34. CC N-491-1 16-23-570 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

.375' ,

16-23-569 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.375" 23-1-NS-94 F-A F120b wertical Support VT-3 RR-2 - - - -

H23-33. CC N-491-1 23-1-NS-93 F-A F1.20a RM Hanger VT-3 RR-2 - - - -

PFSK-1950. CC N-491 1 16-23-567 C-C C3.20 Int,gral Attachment Surf RR-4 X - -

.875" CC N-509 FILE: HPC102.23.WPD Page 23 -18 of 23 -19

rN q m James A Fitzpatrick Nuclear Power Plant JAF-ISl4003 4 bMW Third Inservice inspection Interval Date January 7,1998 Ten - Year inspection Plan Revision 0

' COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 T10CK REMAWS 23 -High Pressure Cooling Injection Drawing Number: MSK-3028 Une No 16"-WCP-152-1 from Condensate Storage Tank 23-1-HS-92 N/A N/A Hydraure Snubber -

RR - - -

PFSK-2242.TS Sechon 3.6.1 23-1-HS41 N/A N/A Hydraulic Snubber - RR - - - PFSK-2500, TS Sectior. 3.6.1 i

16-23-566 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

.375' 16-23-565 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.375*

16-23-564 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - - .375*

16-23-563 C-F-2 C5.51 Pipe-Elbow Vot! Surf - - -

.375" 16-25 562 - - 3/4' Branch Cormaction Surf - - - - Exempt IWC-1222(b) 23-1-AN-90 F-A F1.20c Variable Spring VT-3 RR-2 - - - - H23-31 CC N-491-1 16-23-561 C-F-2 C5.51 E! bow-Pipe Vol/ Surf - - -

.375*

16-23-560 C-F-2 C5.51 E! bow-Elbow Vo'JSurf - - -

.375" 16-23-559 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

.375" 16-23-558 C-F-2 C5.51 Tee-Pipe Vol/ Surf - - -

.375* ,

Fit _E: HPC102.23.WPD Page 23 - 19 of 23 -19

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] '

Mb Third Inservice Inspection interval Ten -Year Inspection Plan Date January 7,1998 Reevision 0 COMPONENT ASIG ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 27 - Containment Purge System Drawing Number: f#.SK-3029

. Une Number: 18*-N-152A4 13-27-108 C-F-2 C5.51_ Ppe-Pipe Vol/ Surf - - -

0.250" Exduded nVC-2500-1. Pen. X-25 18-27-109 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

0.250" Exduded IWC-2500-1 18-27-110 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

0 250" Exduded IWC-2500-1 18-27-111 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

0.250* Exduded IWC-2500-1 27-6-NS-4 F-A F120b Non Adjustable Constraint VT-3 RR - - -

Exduded IWC-2510. CC N-491-1 18-27-112 C-C C320 Integral Attachmcr:t Surf RR - - -

Exduded IWC-2500-1. CC N-509 18-27-113 C-F-2 C5.51 Pipe-Reducer Vol/ Surf - - -

0250" Exduded IWC-2500-1 Line Number: 24"-N-152A-8 24-27-114 - - .,2* Branch Connection Surf - - - - Exempt fWC-1222(b) 24-27-115 - -

1 1/2" Branch Connection Surf - - - - Exempt IWC-1222(b) 2?27-116 C-F-2 C5.51 Reducer-Tee Vol/ Surf - - -

0.250" Exduded 'WC-k%1 24-27-117 C-F-2 C5.51 Tee-valve AOV-112 Vol/ Surf - - -

0.250" Exq!uded IWC-2500-1 AOV-112 - - 24.0" Valve Botting VT-1 - - -

<2" No exam required 2 *c27-119 C-F-2 C5.51 T(e-Reducer Vol/ Surf - - - 0.250" Exduded IWC-25001 FILE: CPS 02.27AVPD Pcge 27 - 1 of 27 -13

O (/

James A Fitzpatrick Nuclear Power Pfar:t [[::JAF-tSI-0003|JAF-tSI-0003]] V

4MMM Third inservice Inspection Interval Date January 7,1998 Revision 0 Ten - Year Inspection Plan COMPONENT ASME ASME ASME WELD IDENTIFICATf0N CODE CODE CODE REL tSI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 27 - Containment Purge System Drawing Number: MSK-3029 Line Number: 14-N-152A-9 14-27-120 C-F-2 C5.51 Reducer-Pipe Vol/ Surf - - -

0 250" Exduded IWC-2500-1 14-27-121 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

0250" Exduded lYC2500-1 1f 27-122 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

0250" Exduded MC-25001 27-9-AS-7 F-A F120b Adjustable Constraint VT-3 RR - - -

Exduded hvC-2510. CC N-491-1 27-9-NS-8 F-A F120b Non Adjustable Constraint VT-3 RR - - -

Exduded hYC-2510. CC-N-491-1 1?27-123 C-F-2 C5.51 Pipe-Pipe Vo!/ Surf - - -

0250" Exduded IVC 2500-1 14-27-124 C-F-2 C5.51 Pipe-Pse Vo!/ Surf - - - 0.250" Exduded IYC2500-1 27-9-NS-9 F-A F120b Non Adjustable Constraint VT-3 RR - - -

Exduded hE2510. CC N-491-1 14-27124A C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

0 250" Exduded IVC 2500-1 14-27-125 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

0250" Exduded IWC-2500-1 14-27-126 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - --

0 250" Exduded IWC-2500-1 14-27-127 C-F-2 C5.51 Eibow-pipe Vol/ Surf - - -

0 250" Exduded IWC-2500-1 14-27-128 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

C250" Exduded IWC-2500-1 14-27 129 C-F-2 C5.51 Elbow-Pipe Vot' Surf - - -

0 250" Exduded IWC-2500-1 14-27-130 C-F-2 C5.51 Prpe-Elbow Vol/ Surf - - -

0.250" Exduded IWC-2500-1 14-27-131 C-C C320 Integral Attachment Surf R R-4 - - - -

Exduded IWC-25CO-1. CC N-509 FILE- CPS 02.27.WPD Page 27 -2 of 27 -13

James A. Fl*zpatrick Nuclear Power Plant .[[::JAF-ISI-0003|JAF-ISI-0003]] g h Third Inservice Inspection interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICK REMARKS 27 - Containment Purge System Drawing Number: MSK-3029 Line Number: 14-N-152A-9 27-9-AS-11 F-A F120b Adjustable Constraint VT-3 RR - - -

Exduded IWC-2510. CC N-491-1 14-27-132 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

0.250* Exduded IWC-2500-1 14-27-133 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

J 250" Exduded IVC,-2500-1. Pen X-71 i

I t

i I

r FILE CPS 02.27.WPD Page 27 - 3 of 27 -13

S

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V. ()

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] d

h

$ Thi;d Inservice Inspection Interval Ten -Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THfCK REMARKS 27 -Containment Purge System Drawing Number: MSK-3029 Line Number: 20-N-152A-7 20-27-154 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

0.250* Exclud$.1 tVE,-2500-1 Pen X-220 20-27-155 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

0.250" Excluded IVC-2500-1 20-27-156 - -

2.0" Branch Cunnecoun Surf - - - - Exempt IVC,-1222(b) 20-27-157 - -

2.0" Branch Connection Surf - - - -

Exempt IWC-1222(b) ,

20-27-158 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - - 0250" Excluded IWC-2500-1 20-27-159 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - - 0.250" Excluded IVC 2500-1 20-27-160 C-F-2 C5.51 Pipe-Vafve Vol/ Surf - - -

0.250" Excluded IVC 2500-1 AOV-116 - - 20.0" Valve Boiting VT-1 - - -

<2" No exam required r

FILE: CPS 02.27.WPD Page 27 -4 of 27-13

g

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N. A. _ ]

James / Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] gb b Third Inservice Inspection Interval Date January 7.1998 Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRfPTION EXAM REQ PER1 PER2 PER3 THtCK REMARKS f

27 - Containment Purge System Drawing Number: MS'a-3029 Line Number: 20~-N-152A-20 20-27-134 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

0250- Exdeced IWC-2500-1. Pen X-205 20-27-135 C-F-2 C5.51 Pipe-Elbow Vol! Surf - - -

0250" Exduded rWC-2500-1 20-27-136 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

0.250" Exduded 1WC-2500-1 20-27-137 - -

2.0" Branch Connection Surf - - - - Exempt IWC-1222(b) 20-27-138 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

0.250" Exduded PNC-2500-1 20-27-139 C-F-2 C5.51 Elbow-Elbow Vol/ Surf - - -

0.250" Exduded WC2500-1 20-27-140 CP C320 Integral AII&ent Surf RR - - -

Exduded IWC-2500-1. CC N-509 27-20-AN-12 F-A F1.20b Adjustable Constraint VT-3 RR - - -

Exdoded IWC-2510. CC N491-1 20-27-141 C-F-2 C5.51 Elbow-Elbow Vol/ Surf - - -

0250" Exduded WC2500-1 20-27-142 C-F-2 C5.51 Elbow-Prpe Vol/ Surf - - -

0.250" Exduded IVC 2500-1 20-27-143 - -

2.0" Branch Connection Surf - - - - Exempt IWC-1222(b) 20-27-144 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

0250" Exduded PNC-2500-1 20-27-145 C-F-2 C5 51 Elbow-Pipe Vot/ Surf - - -

0250" Erduded IVC 2500-1 20-27-145A C-F-2 C5 51 Pipe-Pipe Vot/ Surf - - -

0.250" Exduded tV&2500-1 20-27-146 C-F-2 C5.51 Pipe-Pipe Vot/Su-f - - -

0250" Exduded TNC-2500-1 27-20-NS-13 F-A F120b Non Adjustable Constraint VT-3 RR - - -

Excluded IV&2510 CC N-491-1 FILE: CPS 02.27.WPD Page 27 - 5 of 27-13

! O O James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] O

W

$ Third inservice inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 l

i l COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR l

l CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 T5ffCK REMARKS 27 -Containment Purge System Drawing Number: MSK-3029 Line Number: 20"-N-152A-20 20-27-147 C-C C3.20 Integral Attachment Surf RR - - -

Exduded IWC-2500-1. CC N-509 20-27-148 - -

2 0" Branch Connedion Surf - - - - Exempt IWC-1222(b) 20-27-149 - - 2.0" Branch Connechen Surf - - - - Exempt IWC-1222(b) 20-27-150 C-F-2 C5.51 Pipe-Valve AOV-117 Vot/ Surf - - -

0.250" Excluded IWC-2500-1 AOV-117 - - 20" Valve Botting VT-1 - - -

<2" No exam regtfred i

i FILE CPS 02.27.WPD Page 27 - 6 of 27 -13

( ) IQj)

</

James Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] A IlowMh Third Inservice inspection Interval Date January 7,1998

Ten - Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRfPTION EXAM REQ PER1 PER2 PER3 THfCK REMARKb 27 -Containment Purge System Drawing Number: MSK-3029 Line Number: 18"-N-152A-26B 18-27-100 - -

3/4" Branch Connection Surf - - - - Exempt IVC 1222(b) 18-27-101 - 3/4" Branch Connection Surf - - - - Exempt IWC-1222(b) 18-27-102 - -

3/4" Branch Connection Surf - - - - Exempt IWC-1222(b) 18-27-103 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

0.250" Exduded IWC-2500-1, Pen X-268 18-27-104 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

0.250" Exduded IWC-2500-1 18-27-1C SA C-F-2 C5.51 Elbow-Pipe Vol/Suri - - -

0.250" Exduded fWC-2500-1 18-27-104B C-F-2 C5.51 Pipe-Reducer Vol/ Surf - - - 0250" Exduded IWC-2500-1 Line Number: 24"-N-152-188 24-27-104C C-F-2 C5.51 Reducer-Elbow Vol/ Surf - - -

0250" Exduded IWC-250CL1 24-27-104D C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

0250* Excluded IWC-2500-1 24-27-105A C-F-2 C5.51 Pipe-Tee Vol/ Surf - - -

0250" Excluded IWC-2500-1 Line Number- 24"-N-152-18A r 24-27-105B C-F-2 C5.51 Pipe-Tee Vol/ Surf - - -

0.250" Exduded IWC-2500-1 24-27-105C C-F-2 C5.51 Pipe-Valve f.OV-113 Vol/ Surf - - -

0250" Exduded IWC-2500-1 AOV-113 - - 24.0" Valve Botting VT-1 - - -

<2" No exam required 24-27-105 C-C C320 Integraf Attachment Surf RR - - -

Exduded IWC-2500-1. CC N-509 FILE: CPS 0227.WPO Page 27 - 7 of 27-13

James A Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h Third Inservice inspection Interval Date January 7,1998 Ten - Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICK REMARKS 27 -Containment Purge System Drawing Number: MSK-3029 Une Number: 24"-N-it:2-18A 2427-1071 - -

1.0* Branch Connection Surf - .- - - Exempt IWC-1222(b) i 24-27-107H - -

1.0" Branch Connection Surf - - - - Exempt IWC-1222(b) 24-27-107F C-F-2 C5.51 Pipe-Tee Vol/ Surf - - -

0250* Excluded IVE-2500-1 27-18A-NS-1 F-A F1.20b Non Adjustable Constraint VT-3 RR - - -

Excludsf IWC-2510. CC N-491-1 27-18A-AN-1 B F-A F1.20b Adjustable Constraint VT-3 RR - - -

Excluded IWC-2510. CC N-491-1 24-27-107G - -

1.0" Branch Connection Surf - - - - Exempt IWC-1222(b) 27-18A-AN-1 A F-A F1.20b Adjustable Constraint VT-3 - - - - Exempt IWC-1222(b). CC N-491-1 24-27-107E C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

0250" Excluded IWC-2500-1 24-27-107D C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

0250" Excluded IWC-2500-1 24-27-107C C-F-2 C5.51 Reducer-Pipe Vol/ Surf - - -

0.250* Excluded MC-2500-1 Line Number: 18"-N-152A-26A 18-27-1078 C-F-2 C5.51 Pipe-Reducer Vol/ Surf - - -

0.250" Exqluded IWC-2500-1 18-27-107A C-F-2 C5.51 Eltx)w-Pipe Vo!/ Surf - - -

0.250" Excluded IWC-2500-1 18-27-107 C-F-2 C5.51 Pipe-Elbow Vo;/ Surf - - -

0.250" Excluded IWC-2500-1 18-27-10G C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

0.250* E"-ksded MC-2500-1 FILE CPS 0227.WPD Page 27 - 8 of 27-13

b \

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h

M

$ Third Inservice Inspection interval Ten -Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAt. LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THtCK REMARKS 27 - Containment Purge System Drawing Number: MSK-3030 Line Number: 20"-N-152-16 AOV-1018 - - 20.0" Vaive Bottmg VT-1 - - -

<2" No exam requeed 20-27-182A C-F-2 C5.51 Valve AOV-1018-Tee Vol/ Surf - - -

0250" Exduded IWC-2500-1 20-27-182 C-F-2 C5.51 Tee-Valve ACV-101A Vot/ Surf - - -

0.250" Exduded IWC-M1 AOV-101 A - -

20.0" Vafve Bolting VT-1 - - -

<2" No exam required i 27-16-NS-21 F-A F120b Non Adjustable Constraint VT-3 RR - - -

Exduded fWC-2510. CC N-491-1 20-27-181 C-F-2 C5.51 Tee-Pipe Vol/ Surf - - -

0250' Excluded IWC-2500-1 20-27-180 C-C C320 Integral Attachment Surf RR - - -

Excluded IWC-2500-1. CC N-509 20-27-179 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

0.250' Exduded IWC-2500-1 20-27-178 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

0250* Exduded n%2500-1 27-16-NS-19 F-A F1.20b Non Adjustable Constraint VT-3 RR - - -

Exduded IWC-2510. CC N-491-1 20-27-177 C-C C3.20 Integral Attachment Surf RR - - - Excluded IWC-2500-1, CC N-509 20-27-176 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

0250" Exduded IWC-2500-1 20-27-175 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

0250" Exduded IWC-2500-1 20-27-174 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

0250' Excluded IWC-2500-1 20-27-173 C-F-2 C5.51 Pipe-Tee Vot/ Surf - - -

0.250" Excluded IWC-2500-1 FILE: CPS 02.27.WPD Page 27 - 9 of 27 -13

O James A Fitzpatrick Nucle:rPowerPlant Third inservice inspeJon Interval [[::JAF-tSI-0003|JAF-tSI-0003]] Date January 7,1998 h

$ Ten -Year Inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME ISI INTERVAL LTH OR CODE REL IDEhWJTION CODE CODE REO PER1 PER2 F*ER3 THtCM REMARKS (TEM DESCRIPTION EXAM CAT 27 - Containment Purge System Drawing Number: MSK-3030 L*ne Number: 30~-N-152-13E VoUSurf - - - 0.312" Exduded !WC-2500-1. Pen X-202B C-F-2 C5.51 Pipe-Pipe 30-27-163 VoVSurf - - 0.312" Exduded PAG 2500-1 C5.51 Pipe-Pepe 30-27-164 C-F-2 VouSurf - - 0.312" Exduded IWC-2500-1 30-27-165 C-F-2 C5 51 Pipe-Elbow -

VouSurf - - - 0 312" Exduded PWC-2500-1 C-F-2 C5.51 Elbow-Pipe 30-27-166 VT-3 RR - - - Excluded FAG 2510.CC N-491-1 27-13E-NS-18 F-A F1.20b Non Adjustable Constraint VouSurf - - 0.312" Exduded IVC 2500-1 30-27-167 C-F-2 C5.51 Pre-Elbow VouSurf - - - 0.312" Exduded n%2500-1 30-27-168 C-F-2 C5.51 Elbow-Tee VouSurf - - - 0.312" Exduded IWC-2500-1 30-27-172 C-F-2 C5.51 Tee-Va?ve VB-2

<2" No exam reqtared 30 0" Vafve Bo! ting VT-1 - - -

VB-2 - -

VoVSurf - - - 0.312" Excluded IWC-2500-1 30-27-171 C-F-2 C5.51 Vafve VB-2 -Ebow VoVSurf - 0.312" Exduded IWC-2500-1 30-27-170 C-F-2 C5.51 Elbow-Pipe - -

VoVSurf - 0.312* Exduded IWC-2500-1. Pen X-202G C5.51 Pipe-Pipe - -

l 30-27-169 C-F-2 i

Line Number: 30"-N-152-13D VoVSurf -

0.312" Excluded WC2500-1. Pen X-202C C5.51 Pipe-Pipe - -

30-27-2C8 C-F-2 VoVSurf -

0.312" Exduded IWC-2500-1 C5.51 Pipe-Pipe - -

30-27 207 C-F-2 Vol/ Surf - -

0.312" Exduded IWC-2500-1 C5.51 Pipe-Elbow 30-27-200 C-F 2 Page 27 - 10 of 27-13 FILE: CPS 02.27.WPD

O U . mes A. Fitzpatrick Nuclear Power Plant Third Inservice Inspection Interval [[::JAF-ISI-0003|JAF-ISI-0003]] Date January 7,1998 b

$ Ten -YearInspection Plan Revision 0 ASME WELD COMPONENT ASME ASUE LTH OR CODE CODE REL IStINTERVAL IDENTIFICATION CODE REO PER1 PER2 PER3 THtCK REMARMS CAT ITEM DESCRwirON EXAM 27-Containment Purge System Drawing Number: '4fSK-3030 Line Number: 30"-N-152-13D VouSurf - - -

0.312" Exduded IV&2500-1 33-27-205 C-F-2 C5.51 Elbow-Pipe Exduded IVC 2510, CC N-491-1 F-A F1.20b Adjustable Constraint VT-3 RR - - -

27-13D-AN-23 Vol/ Surf - - 0.312" Exduded IWC-2500-1 30-27-204 C-F-2 C5.51 Pipe-Eh -

VoVSurf - - - 0.312" Exduded IWC-2500-1 33-27-203 C-F-2 C5.51 Elbow-Pipe VouSurf - 0.312" Exduded IWC-2500-1 C5.51 Pipe-vaive VB-3 - -

30-27-202 C-F-2 VT-1 -

<2" No exam required VB-3 - - 30.0" Ve've botting - -

VouSurf - - -

0.312" Exduded IWC-2500-1 30-27-201 C-F-2 C5.51 Vafve VB-3-Elbow VoVSurf - - -

0.312" Exduded IWC-2500-1 30-27-200 C-F-2 C5 51 Elbow-Pipe VouSurf -

0.312" Exduded IV&2500-1. Pen X-202H C5_51 Pipe-Prpe - -

30-27-199 C-F-2 Line Number: 30*-N-152-13C Vol/ Surf 0.312" Exduded IWC-2500-1. Pen X-202D C5.51 Pipe-Pipe - - -

30-27-218 C-F-2 Vol/ Surf - 0.312" Exduded IVC 2500-1 30-27-217 C-F-2 C5.51 Pipe-Pipe - -

Vol/ Surf 0.312* Exduded IVC 2500-1 C5.51 Pipe-Elbow - - -

30-27-21G C-F-2 C5.51 Elbow-Pipe VoVSurf - - - 0.312" Exduded IWC-2500-1 30-27-215 C-F-2 VT-3 RR - - - Exduded IWC-2510. CC N491-1 27-13C-AN-24 F-A F1.20b Adjustable Constraint VouSurf 0.312" Enduded IVC 2500-1 C5.51 Pipe-Elbow - - -

30-27-214 C-F-2 C5.51 Elbow-Pipe VoVSurf - - -

0.312" Exduded !YC2500-1 30-27-213 C-F-2 FILE- CPS 02.27.WPD Page 27 - 11 of 27-13

O %) v James A Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] b

$b Third Inservice Inspection Interval Ten - Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 *ER3 THICK REMARKS 27 -Containment Purge System Drawing Number: MSK-3030 l ine Number: 30"-N-152-13C 30-27-212 C-F-2 C5.51 Pipe-valve VB-4 Vot/ Surf - - -

0.312" Exduded IWC-2500-1 VB-4 - - 30 0* Valve bottog VT-1 - - -

<2* No exam requrred 30-27-211 C-F-2 C5.51 Valve VB-4-Elcow Vot/ Surf - - -

0.312" Exciuded IWC-2500-1 30-27-210 C-F-2 C5.51 Elbow-Pipe Vot1 Surf - - -

0.312" Exduded WC2500-1 30-27-209 C-F-2 C5.51 Pipe-Pipe VoVSurf - - -

0.312" Exduded WC2500-1. Pen X-2021 Line Number: 30"-N-152-138 30-27-228 C-F-2 C5.51 Pipe-Pipe Vol/ Surf - - -

0.312" Exduded WC2500-1. Pen X-202E 30-27-227 C-F-2 C5.51 Pipe-Pipe Vot/ Surf - - -

0.312" Exduded IVC 2500-1 30-27-226 C-F-2 C5.51 Pipe-Elbow Vot/ Surf - - -

0.312" Exduded IWC-2500-1 30-27-225 C-F-2 C5.51 Elbow-Pipe Vol/ Surf - - -

0.312" Exduded r*NC-2500-1 27-138-AN-25 F-A F1.20b Adjustable Constraint VT-3 RR - - -

Exduded IWC-2510. CC N 191-1 30-27-224 C-F-2 C5.51 Pipe-Elbow Vol/ Surf - - -

0.312" Exduded IVC 2500-1 30-27-223 C-F-2 C5.51 Elbow-Pipe Vot/ Surf - - -

0.312" Enduded IWC-2500-1 30-27-222 C-F-2 C5.51 Prpe-vatve VB-5 VoVSurf - - -

0.312" Exduded IWC-2500-1 VB-5 - -

30.0" Valve bottmg VT-1 - - -

<2" No exam requeed 30-27-221 C-F-2 C5.51 Valve VB-5-Elbow Vol/ Surf - - -

0.312" Exduded IYC2500-1 FILE: CPS 02.27.WPD Page 27 - 12 of 27-13

James A. Fitzpatrick Nucle:r Power PL:nt [[::JAF-ISI-0003|JAF-ISI-0003]] Third inservice inspection interval Date January 7,1998 b Revision 0

$ Ten -Year Inspection Plan ASME WELD COMPONENT ASME ASME REL ISI INTERVAL LTH OR CODE CODE CODE REMARKS IDENTFICATION DESCR!PTION EXAM REQ PER1 PER2 PER3 THICK CAT ITEM 27- Containment Purge System Drawing Number: MSK-3030 Line Number: 30"-N-152-138 Vot/ Surf - - 0 312* Exduded hvC-2500-1 30-27-220 C-F-2 C5.51 E! bow-Pipe -

Vol/ Surf - -

0.312" Exduded IWC-2500-1. Pe i X-202J ,

C5.51 Pipe-Pipe 30-27-219 C-F-2 Line Number- 30"-N-152-13A Vol/ Surf - - 0.312" Exduded IWC-2500-1. Pen X-202A C5.51 Pipe-Pipe 30-27-189 C-F-2 VoVSurf - - - 0.312" Exduded nNC-2500-1 30-27-190 C-F-2 C5.51 Fy Pipe Vot/ Surf - - - 0.312" Exduded IWC-2500-1 30-27-191 C-F-2 C5.51 Pipe-Etow VoFSurf . - - 0 312" Excluded nVC-2500-1 30-27-192 C-F-2 C5.51 Elbow-Pipe VT-3 RR - - - Exduded IWC-2510. CC N 491-1 27-13A-AN-22 F-A F120b Adjustable Constraint Vet / Surf - - 0.312" Exduded IWC-2500-1 30-27-193 C-F-2 C5.51 Pipe-Elbow -

1 Vol/ Surf - - 0.312" Exduded IWC-2500-1 C5.51 Efbow-Pipe i -

30-27-194 C-F-2 VouSurf - -

0.312* Exduded IWC-2500-1 30-27-195 C-F-2 C5.51 Pipe-valve VB-1 -

<2* No exam required

- 30 0" Vafve bolting VT-1 - - -

VB-1 -

Vol/ Surf - - - 0.312" Exduded IWC-2500-1 30-27-196 C-F-2 C5.51 Vaive VB-1-Elbow VoUSurf - 0.312" Exduded IWC-2500-1 C5.51 Elbow-Pipe - -

30-27-197 C-F-2 VoVSurf - - 0.312" Exduded IWC-2500-1. Pen X-202F 30-27-198 C-F-2 C5.51 Pipe-Pipe -

Page 27 - 13 of 27 -13 FILE: CPS 02.27.WPD

_ - _ - _ _ M

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] V

h

$ Third Inservice inspection interval Ten -YearInspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME A$ME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ P REMARKS

_ -31 PER2 PER3 THICK 29 - Main Steam System Drawing Number: MSK-3031 Line No. 24"-SHP-902-101A 24-29-543A C-F-2 C5.51 Vafve AOV-86A-Pipe Vot/ Surf - - -

121*

29-101 A-AN-10 F-A F120d Sliding Support VT-3 RR-2 - - - -

H29-26. CC N-491-1 29-101 A-NS-10A F-A F120b Constra'nt VT-3 RR-2 - - - -

H29-351 CC N-491-1 29-101 A-NS-10B F-A F120b Constraint VT-3 RR-2 X - - -

H29-27. CC N-491-1 24-29-543C C-C C3.20 Integral Attachment Surf RR-4 X - -

.750" CC N-509 24-29-543D C-C C3.20 Integral Attachment Surf RR-4 - - -

.750' CC N-509 Line No. 24"-SHP-902-1018 From Valve 868 24-29-574A C-F-21 C5.51 Valve AOV-868 -Pipe Vol/ Surf - - -

121" Y

29-1018-AN-19 F-A F120d Stkling Support VT-3 RR-2 - - - - H29-24, CC N-491-1 29-101 B-NS-20 F-A F1.20b Constraint VT-3 RR-2 - - - -

CC N-491-1 29-1018-NS-e : F-A F1.20b Constraint VT-3 RR ~' - - - -

CC NA91-1 24-29-574C C-C C320 Integral Attachment Surf RR-4 - - -

.750" CC N-509 24-29-574D C-C C320 Integral Attachment Surf RR-4 - - -

.750- CC N-509 i

FILE:MS02.29.WPD Page 29 - 1 of 29 - 2

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]]

'd P e er

$h Third inservice 1: spection interval Ten - Year inspection Plan Date January 7,1998 Revision 0 t

i COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 29 - Main Steam System Drawing Number: MSK-3032 Line No. 24"-SHP-902101C From Valve 86C 24-29-607A C-F-2 C5.51 Valve AOV-86C-Pipe Vol/ Surf - - -

1.21*

29-101C-AN-31 F-A F120d Sliding Support VT-3 RR-2 - -

X -

H29-22. CC N491-1 29-101C-NS-32 F-A F1.20b Constraint VT-3 RR-2 - - - -

PFSK-4169. CC N-491-1 29-101C-NS-33 F-A F1.20b Constraint VT-3 RR-2 - - - -

H29-23. CC N-491-1 24-29-607B C-C C320 Integral Attachment Surf RR-4 - - -

.750" CC N-509 24-29-607C C-C C320 Integral Attachment Surf RR-4 - - -

.750* CC N-509 Line No. 24"-SHP-902-101D From Valve 86D 24-29-638A C-F-2 C5.51 Valve AOV-86D-Pipe Vol/ Surf - - -

1.21*

29-1010-AN-45 F-A F1.20d Sliding Support VT-3 RR-2 - - - -

H29-20. CC N-491-1 29101D-NS-4G F-A F1.20b Constraint VT-3 RR-2 - - - -

H29-348. CC N-491-1 29-101D-NS-47 F-A F1.20b Constraint VT-3 RR-2 - - - -

H29-21. CC N-491 1 24-29-6388 C-C C3.20 Integral Attachment Surf RR-4 - - - .750" CC N,509 24-29-638C C-C C3.20 Integral Attachment Surf RR-4 - - -

.750* CC N-509 FILE MS02.29.WPD Page 29 - 2 of 29 - 2

JAMES A. FITZPATRICK JAF ISI-0003 NUCLEAR POWER PLANT

> NewYorkPower tv Authority G THIRD INSERVICE INSPECTION INTERVAL Rev. O TEN. YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 21 of 35 6.0 CLASS 3 INSERVICE INSPECTION PLAN TABLES This section contains the Long Term Ten Year Inservice inspection Examination Tables for nondestructive examinations of selected systems and components for the Third Inservice inspection interval.

~

10 Residual Heat Removal System . 10-1 thru 10-10 13 Reactor Core Injection Cooling System . . . 13-1 thru 13-2 15 Reactor Building Closed Loop Cooling System 15-1 thru 15-9 19 Fuel Pool Cooling System . . . 19-1 thru 19-5 46 Service Water System . . 46-1 thru 4611 66 Reactor Building Vent and Cooling System . 66-1 thru 66-3 70 Control Room and Relay Room Vent and Cooling System 70-1 thru 70-6 O

O b

File: jafisipl.wpd

O G James A. Fitzpatrick Nuclear Pcwer Plant [[::JAF-ISI-0003|JAF-ISI-0003]] O

h

$ Third Inservice inspection Interval Ten - Year Inspection Plan Date January 7,1996 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICA'lON CODE CODE ,

CODE REL ISI INTERVAt- t TH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS t

10 - Residual Heat Removal System Drawing Number: MSK-166A1 Line Number: 16*-WS-151-29B PFSK-1997 F-A F1.30b Anchor A3 VT-3 RR-2 - - -

CC N-491-1 PFSK-1997 D-B D2.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 PFSK-2402 F-A F1.30e Rigid Sway Stnf VT-3 RR-2 - - -

CC N-491-1 PFSK-2402 D-B D220 Integra! Attachment VT-3 RR-4 - - -

CC N-509 H10-248 F-A F1.30b Pipe Constraint VT-3 RR-2 - - -

CC N-509 PFSK-2121 F-A F1.30e Rigid Sway Strut VT-3 RR-2 X - -

CC N-491-1 PFSK-2121 D-B D2.20 Integra! Attachment VT-3 RR-4 X - - CC N-509 PFSK-2453 F-A F1.30b Pipe Support VT-3 RR-2 - - -

CC N-491 1 PFJK-2453 D-B D2.20 Inteoral Attachment VT-3 RR-4 - - -

CC N-509 PFSK-2140 F-A F1.30b Pipt: oupport VT-3 RR-2 - - -

CC N-491-1 PFSK-2140 D-B D2.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 PFSK-2171 F-A F1.30b Pipe Support VT-3 RR-2 - - -

CC Nf91-1 PFSK-2171 D-B D220 Integral Attachment VT4 RR-4 - - -

CC N-509 PFSK-2148 F-A F1.30b Pipe Support VT-3 RR-2 - - -

CC N-491-1 PFSK-2148 D-B D220 Integral Attachment VT-3 RR-4 - - -

CC N-509 PFSK-2403 F-A F1.30b Pipe Suprort VT-3 RR-2 - - - CC N-491-1 PFSK-2403 D-B D2.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 FILE: RHR03.10.WPD Page 10 - 1 of 10-10

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James A. Fitzpatrick Nuclear Power Plant C/

[[::JAF-ISI-0003|JAF-ISI-0003]] g b Third inselvice Inspection interval Ten -Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRlPTION EXAM REQ PER1 PER2 PER3 THICK REMARMS 10 - Residual Heat Removal System Drawing Numbec MSK-166A1 Line Numbec 16"-WS-151-29B PFSK-2167 F-A F1.30b Pipe Support VT "3 RR-2 X - - GC N-491-1 PFSK-2167 D-B D220 Integral Attrohment VT-3 RR-4 X - -

CC N-509 PFSK-2401 F-A F1.3Gb Pipe Support VT-3 RR-2 - - -

CC N491-1 PFSK-2401 D-B D220 integral Attachment VT-3 RR-4 - - -

CC N-509 PFSK-2412 F-A F1.30e Rigid Sway Strut VT-3 RR-2 X - -

CC N-491-1 PFSK-2412 D-B D220 Integral Attachment VT-3 RR-4 - - - CC N-509 PFSK-2267 F-A F1.30b Anchor A4 VT-3 RR-2 - - -

CC N-491-1 PFSK-2267 D-B D220 Integrai Attachment VT-3 RR-4 - - -

CC N-509 Drawing Numbec MSK-166B1 Line Numbec 16"-WS-151-29B PFSK-2474 F-A F1.30b Pipe Support VT-3 RR-2 - - -

CC N-491-1 f-fr T5it-2474 D-B D220 Inkegm! Attachment VT-3 RR-4 - - -

CC N-509 t

H10 264 F-A F1.30b Constraint VT-3 RR-2 -

X -

CC N491-1 H10 264 D-B D2.20 Integral Abac5 ment VT-3 RR-4 - - - CC N-509 H10 ~65 F-A F1.30b Constraint VT-3 RR-2 - - -

CC N-491-1 H10-265 D-B D220 Integral Attachment VT-3 RR-4 - - -

CC N-509 FILE: RHR03.10.WPD Page 10 - 2 of to-10

, .3 James Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h

$ Third inservice Inspection interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONEh_ ASME ASME ASME VYELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCPIPTION EXAM REQ PERT PER2 PER3 THICK REMARKS 10 - Residual Heat Removal System Drawing Number: MSK-16681 Une Number: 16*-WS-151-298 s

PFSK-2227 F-A F1.30e Rioid Sway Strut VT-3 RR-2 - X -

CC N491-1 PFSK-2227 D-B D220 Integral Attodwiw.1 VT-3 RR-4 -

X -

CC N-509

[ PFGK-2156 F-A F1.30e Rigid Sway Strut VT-3 RR-2 - - -

CC N-491-1 PFSK-2483 F-A F130b Anchor VT-3 RR-2 - - -

CC N-491-1 l PFSK-2483 D-B D2.20 Integra' Atta-hment VT-3 RR-4 - - -

CC N-509

! Drawing Number: MSK-166C1 l Line Number: 16"-WS-151-21A l

! H10-110 F-A F1.30a Rod Hanger VT-3 RR-2 - - -

CC "e-491-1 PFSK-2104 F-A F1.30b Lateral Support VT-3 RR-2 - - -

CC N-491-1 H10-112 F-A F1.30a Rod Hanger VT-3 RR-2 CC N-491-1 l

l l PFSK-1967 F-A F1.30b Axial Pipe Support VT-3 RR-2 - -

X CC N-491-1 t

l l PFSK-1967 D-B D2.20 Integral Attachment VT-3 RR 4 - -

X CC N-509 ,

l t PFSK-1989 F-A F1.30b Pipe Support VT-3 RR-2 - - -

CC N-491-1 H10-115 F-A F1.30a Rod Hanger VT-3 RR-2 - - -

CC N491-1

! H10-116 F-A F1.30a Red Hanger VT-3 RR-2 - - X CC N-491-1 l

l FILE RHR03.10.WPD Page 10 - 3 of 10-10

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-4St-0003|JAF-4St-0003]] W Date January 7,1998

$ Third Inservice Inspection Interval Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INT;'RVAL LTA OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 10 -Residual Heat Removal System Drawing Number: MSK-166C1 Line Number.16"-WS-151-29A PFSK-2025 F-A F1.30b Lated Pipe Support VT-3 RR-2 - - -

CC N491-1 H10-118 F-A F1.30a Rod Hanger VT-3 RR-2 - - -

CC N-491-1 PFSK-2536 F-A F1.30b lam 5al Support VT-3 RR-2 - - -

CC N491-1 H10-120 F-A F1.30a Rod Hanger VT-3 RR-2 - - -

CC N-401-1 PFSK-2379 F-A F1.30a Rod Hanger VT-3 RR-2 - - -

CC N491-1 PFSK-2356 F-A F1.30b Pipe Support VT-3 RR-2 - - - CC N-491-1 PFSK-2109 F-A F1.30a Rnd Hanger VT-3 RR-2 - - -

CC N491-1 PFSK-2119 F-A F1.30a Rod Hanger VT-3 RR-2 - - -

CC N491-1 PFSK-2226 F-A F1.30b Vertical Pipe Sopport VT-3 RR-2 - - - CC N-491-1 PFSK-2391 F-A F1.30a Rod Hanger VT-3 RR-2 - - -

CC N491-1 PFSK-1924 c-A F1.30b Anchor A12 VT-3 RR-2 - - -

CC N-491-1 PFSK-1924 D-B D2.20 Integral Attodonent VT-3 RR-4 - - -

CC Nr509 FILE: RHR03.10.WPD Page 10 - 4 of 10-10

James A Fitzpatrick NuclearPowerPlant [[::JAF-ISI-0003|JAF-ISI-0003]] Third Inservice inspection Interval Date January 7,1998 4 II8*MP88'r Ten -Yearlaspection Plan Revision 0 ASME WELD COMPONENT ASME ASME ISI I!!TERVAL LTH OR CODE CODE REL IDENTIFICATION CODE EXAM REQ PER1 PER2 PER3 TH1CK REMARKS CAT ITEM DESCRIPTION 10 - Residual Heat Removal System Drawing Number: MSK437A1 Une Nur.iber: 12"-WS-151-27D VT-3 RR-2 X - - CC N491-1 PFSK-2159 F-A F1.30d Sliding Support Une Number: 12"-WS-151-278 VT-3 RR-2 - - - CC N491-1 PFSK-2160 F-A F1.30d Sliding Support l

Une Number: 16"-WS-151-28D VT-3 RR-2 - - - CC N-491-1 H10-99D F-A F1.30b Constraint VT-3 RR4 - - - CC N-509 H10-99D D-B D2.20 Integraf Attachment Une Number- 16"-WS-151-288 VT-3 RR-2 - - - CC N491-1 H10-998 F-A F1.30b Constraint Une Number; 16*-WS-151-298 VT-3 RR-2 - - - CC N491-1 Anchor At F-A F1.30b Anchor VT-3 RRA - - - CC N-509 Anchor At D-B D2.20 Integret Attachment VT-3 RR-2 - - - CC N 7491-1 H10-101 F-A F1.30b Constraint VT-3 RR-2 - - - CC N491-1 PFSK-2013 F-A F1.30b Pipe 3upport F1.30b Pipe Support VT-3 RP 2 - - - F N491-1 PFSK-2515 F-A VT-3 RR-2 - - - .?.C N491-1 FFSK-2003 F-A F1.30b Pipe Support l

l FILE: RHR03.10.WPD Page 10 - 5 of 10-10 l

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third Inservice Impection Interval Date January 7.1998 g h Ten -Year inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME ISI INTERVAL LTH OR CODE CODE CODE R.Cs REMARKS IDENTIFICATION EXAM 'tEQ PER1 PER2 PER3 THICK 1mummmmuummmmme CAT ITEM DESCRIPTION 10 - Rer/ lual Heat Removal Systen.

Drawir < lumber: MSK-137B1 Line P ~1ber: 16"-WS-151-298 i VT-3 RR-2 - - X CC N-491-1 PF!,6-2145 F-A F1.30e Rigid Sway Stru.

VT-3 RR-2 - - - CC N>91-1 PFSK-2131 F-A' F1.30b Box Castraint VT-3 RR-2 - - - CC N 491-1 PFSK-2438 F-A F1.30a Rod Hanger VT-3 RR-2 - - - CC N-491-1 PFSK-2211 F-A F1.30a Rod Hanger VT-3 RR-2 - - - CC N-491-1 PFSK-2521 F-A F1.30e Rigid Sway Stre:

VT-3 RR-2 - - - CC N-491-1 PFSK-2426 F-A F1.3Ob Anchor A6 VT-3 RR-4 - - - CC N-509 PFSK-2426 D-B D2.20 Integral Attachment Dr; wing Number: MSK-137C1 Line Number: 16"-WS-151-258 VT-3 RR-2 - - - CC N-491-1 H10-151 F-A F1.30b Rigid Ret'raint V F-3 RR4 - - - CC N-509 l H10-151 D-B D2.20 Integral Attachment F1.30c Vailable Spring Support VT-3 RR-2 - - - CC N-491-1 H10-150 FA VT-3 RR-4 - - - CC N-509 H10-150 D-B D2.40 Pipe Stanchion Line Number: 16"-WS-151-56B VT-3 RR-2 - - - CC N-491-1 PFSK-2215 F-A F1.30b Rigid Restraint VT-3 RR-4 - - - CC N-509 PFSK-2215 D-B D2.20 Integral Attachment FILE: RHR03.10.WPD Page 10 - 6 of 10-10

s i [[::JAF-ISI-0003|JAF-ISI-0003]] J mea Fitzpatrick Nucle r Power Plant Date January 7,1998 M Third inservice inspection Interval gAj Ten -Year Inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME ISI INTERVAL LTH OR CODS CODE REL IDENTIFICATION CODE REQ PER1 PER2 PER3 THICK REMARKS C/.T ITEM DEJCRfPTION EXAM 10 Residual Heat Removal System Drawing Number: MSK-137C1 Une Number: 16"-WS-151-568 VT-3 RR-2 - - X CC N491-1 PFSK-2507 F-A F1.30d Sliding Support VT-3 RR-4 - - - CC N-509 PFSK-2507 D-B D2.20 Integral Attachment Drawing Number: MSK-137D1 Une Number: 12"-WS-151-27A VT-3 RR-2 - - - CC N-491-1 PFSK-2152 F-A F1.30d Sliding Support

- Une Number: 12"-WS-15f 27C VT-5 RR-2 - - - CC f1491-1 PFSK-2153 F-A F1.30d Sliding Support Une Number: 16"-WS-151-28A VT-3 RR-2 - - - CC N-491-1 H10-99C F-A F1.30d Sliding Support i

VT-3 RR-4 - - - CC N-509 H13-99C D-B D2.20 Integraf Attachment Une Number: 16"-WS-151-28C VT-3 RR-2 - X - CC N-491-1 H10-99A F-A F1.30d Sliding Support VT-3 RR-4 - X - CC N-509 H10-99A D-B D2.20 Integral Attachment Line Number: 16"-WS-151-29A VT-3 RR-2 - - - CC N-491-1 AnchoiA10 F-A F1.30b Anchor VT-3 RR-4 - - - CC N-509 Anchor ATO D-B D2.20 Integral Attachment FILE: RHR03.10.VFD Page 10 - 7 of 10-10

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISt-0003|JAF-ISt-0003]] Third Inservice inspection Interval Date January 7,1998 h

$ Ten -YearInspection Plan Revision 0 ASME WELD COMPONENT ASME ASME REL ISI INTERVAL LTH OR CODE CODE CODE REMARKS IDENTIFICATION DESCRIPTION EXAM REQ PER1 PER2 PER3 THtCK CAT ITEM 10 - Residual Heat Removal System Drawing Number: MSK-137D1 Line Number: 16"-WS-151-29A VT-3 RR-2 - - - CC N-491-1 PFSK-2138 F-A F1.30b Pipe Support VT-3 RR-4 - - - CC N-509 PFSK-2138 D-B D2.20 Integral Attachment VT-3 RR-2 - - - CC N-491-1 PFSK-1969 F-A F1.30b Pipe Support VT-3 RR-2 - - - CC N-491-1 H10-105 F-A F1.30b Pipe Support VT-3 RR-2 - - - CC N491-1 PFSK-2158 F-A F1.30b Constraint VT-3 RR-2 - - - CC N-491-1 H10-107 F-A F1.306 Constraint VT-3 RR-2 - - - CC N491-1 PFSK-2428 FA F1.306 Pipe Support VT-3 RR-2 - - - CC N-491-1 PFSK-1925 F-A F1.30b Anchor /11 VT-3 RR-4 - - - CC N-509 PFSK-1925 D-B D2.20 Integral Attachment Drrwing Number: MSK-137E1 Line Number: 16"-WS-151-29A VT-3 RR-? - X - CC N-491-1 PFSK-2308 F-A F1.30 % Hanger VT-3 RR-2 - - - CC N'-491-1 PFSK-2233 F-A F1.30e Rigid Tie Bar VT-3 RR-2 - - - CC N-491-1 F-A F1.30c Variable Spring Can Support PFSK-2198 l

RR-4 - - CC N-509 D2.40 Integral Attachment, Stanchion VT-3 l

PFSK-2198 0 -B VT-3 RR-2 - - - CC N-491-1 PFSK-2461 F-A F1.30b Vertical Constrak VT-3 RR-4 - - - CC N-509 PFSK-2461 D-B D2.20 Integra! Attachmeitt Page 10 - 8 of 10-10 FILE: RHR03.10.WPD

o James

y. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] o

Date January 7,1998 Third Inservice Inspection intervat g h Ten -YearInspection Plan Revision 0 ASME WELD COMPONENT ASME ASME REL ISI INTERVAL LTH OR CODE CODE CODE REMARKS IDENTIFICATION DESCRfkTION EXAM REQ PEr:1 PER2 PER3 THICK CAT ITEM 10 - Residual Heat Removal System Dr: wing Number: MSK-137E1 Une Number: 16"-WS-151-29A VT-3 RR-2 - - - CC N-401-1 PFSK-2529 F-A F1.30b Ver*.ical Constraint VT-3 RR-4 - - - CC N-509 PFSK-2529 D-B D2.20 Integral Attachment VT-3 RR-2 - - - CC N-491-1 PFSK-2076 F-A F1.30b Anchor A13 VT-3 RR-4 - - - CC N-509 PFSK-2076 D-B D2.20 Integral Attachment Dr: wing Number: MSK-137F1 Une Number: 16"-WS 151-29A VT-3 RR-2 - - X CC N-491-1 H10-136 F-A F1.30b Pipe Constraint VT-3 RR-4 - -

X CC N-509 H10-136 G-B D2.20 Integral Attachment.(2) Lugs Une Number: 16"-WS-151-53A VT-3 RR-2 - - - CC N-491-1 H10-139 F-A F1.30b Pipe Constraint VT-3 RR-4 - - - CC N-509 H10-139 D-B D2.20 Integra! Attachment. (2) Lugs Une Number: 16"-WS-151-29A VT-3 RR-2 - - - CC N-491-1 F-A F1.30c Variable Spring Support H10-138 RR-4 - - - CC N-509

'410-138 D-B D2.20 Integral Attachment.StarecHon VT-3 CC N-491-1 j F1.30d S!iding Support VT-3 RR-2 - - -

SK-2095 F-A i VT-3 RR-4 - - - CC N-509 PFSK-2095 D-B D2.20 Integral Attachment Page 10 - 9 of 10-13 FILE: RHR03.10.WPD

O O J:mes A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] O

Third Inservice inspection Interval Date January 7,1998 A Ptmer Ten -Yearinspection Plan Revision 0 ASME WELD COMPONENT ASME ASME ISI INTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE REQ PER1 PER2 PER3 THION REMARKS CAT ITEM DESCRf? TION EXAM 10 - Residual Heat Removal System Drawing Number: MSK-137H1 Une Number: 16"-WS-151-30A VT-3 RR-11 - - - TS Section 3.6.1 PFSK-2240 N/A N/A Hydraulic Snubber VT-3 RR-4 - - - CC N-509 PFSK-2240 D-B D2.30 ft%,,4al Attachment VT-3 RR-11 - - - TS Section 3.6.1 PFSK-2241 N/A N/A Hydraufic Snubber Une Number: 16"-WS-151-308 VT-3 RR-11 - - - TS Section 3.6.1 PFSK-2232 N/A N/A Hydraulic Snubber VT-3 RR-11 - - - TS Sechon 3.6.1 PFSK-2485 N/A N/A Hydraulic Snubber t

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j FILE: RHR03.10.WPD Page 10 - 10 of 10-to

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O, O(~ James A. Fitzpatri:k Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third inservice inspection Interval Date January 7,1998 g h Ten -Yearinspection Plan Revision 0 ASME WELD COMPONENT ASME ASME REL ISI INTERVAL LTH OR CODE CODE CODE REMARKS IDENTIFICATION EXAM REQ PER1 PER2 PER3 THICK CAT ITEM DESCRIPTION 13 - Reactor Core injection Cooling System Drawing Number: MSK-167C1 Line Number: Turbine 13TU-2 VT-3 RR-2 X - - CC N-491-1 13TU-2 F-A F1.40 Turbine Support Drawing Number: MSK-102A1 from Valve MOV-41 to RCIC Pump 13P-1 Line Number: 6"-WCP-152-2 VT-3 RR-2 - X - CC N-491-1 13P1 F-A F1.40 Pump Support VT-3 RR-2 - X - CC N-491-1 F-A F1.30b Horizontal Support H-13-19A VT-3 RR-2 - X - CC N-509 H-13-19A D-A D120 Integraf Attachmer't.(2) lugs Line Number: 6"-WCD-152-2 VT-3 RR-2 - - - CC N-491-1 H-13-4 F-A F1.30c Variable Spring Support RR-4 - - CC N-509 H-13-4 D-A D1.20 Integral AttacFmnt, Stanchion VT-3 -

Line Number: 6*-W22-152-16 l CC N-491-1 F1.30e Rigid Sway Strut VT-3 RR-2 - - -

PFSK-2101 F-A VT-3 RR-4 - - - CC N-509 PFSK-2101 D-A D1.20 Trunnion VT-3 RR-2 - - - CC N-491-1 H-13-3 F-A F1.3Oo Pipe Support RR-4 - - CC N-509 H-13-3 D-A D1.20 Integral Attachment. Stanchion VT-3 -

VT-3 RR-2 - - CC N-491-1 F-A F1.30b Horizontal Pipe Support -

H-13-48 VT-3 RR-4 - - - CC N-509 H-13-48 D-A D120 Integra! Attachment j

FILE- RCIC03.13.WPD Page 13 - 1 of 13-2 l

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] A h M P m er Third Inservice Inspection interval Date January 7,1998 Ten -Yearinspection Plan Revision 0 COMPONENT ASME ASME ASME _

Y.' ELD IDENTIFICATION CODE CODE CODE REL ISi INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PE*43 THfCK REMARKS P

43 - Reactor Core injection Coo!!ng System Drawing Number: MSK-102A1 Line Number: 6"-W22-152-16 PFSK-2467 F-A F1.30b Vertical Constrair ! VT-3 RR-2 - - -

CC N-491-1 PFSK-2467 D-A D1.20 Pipe Support VT-3 RR-2 - - -

CC N-509 PFSK-2473 F-A F1.30b Vertical Constraint VT-3 RR-2 - - -

CC N-491-1 PFSK-2473 D-A D1.20 Pipe Support VT-3 RR-4 - - -

CC N-509 Drawing Number: MSK-167C1 Une Number- 8"-SLP-152-22 PFSK-1049 F-A F1.30c Variable Spring Support VT-3 RR-2 - - -

CC N-491-1 PFSK-1049 D-A D1.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 PFSK-1919 N/A N/A Hydraulic Snubber VT-3 RR-11 - - -

TS Section 3.6.1 PFSK-1921 N/A N/A Hydraulic Snubber VT-3 PR-11 - - -

TS Section 3.6.1

! PFSK-1963 F-A F1.30b Pipe Support VT-3 RR-2 - - -

CC N-491-1 PFSK-1903 D-A D1.20 Welded Pad VT-3 RR-4 - - - CC N-Sn9 t

Drawing Number: MSK-102B1 H-13AsA F-A F1.30a Rod Hanger VT-3 RR-2 - - -

CC N-491-1 l

i FILE: RCIC03.13.WPD Page 13 - 2 of 13-2 1

O James

9. Fitzpatrick Nuctorr Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] O

Third Insepice Inspection Interval Date January 7,1998

> Pmer Revision 0 Ten -YearInspection Plan ASME WELD COMPONENT ASME ASME REL ISIINTERVAL LTH OR CODE CODE CODE REMARKS IDENTIFICATION DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK CAT ITEM 15 - Reactor Building Closed Loop Cooling System Drawing Number: MSK-103A1 Line Number: 8"-WES-151-100 VT-3 RR-2 - - - CC N-491-1 PFSK-2051 F-A Fi.30b Anchor A5 VT-3 RR-2 - - - CC N-491-1 PFSK-2413 F-A F1.30b Box Restraint VT-3 RR-4 - - - CC N-509 PFSK-2413 D-B D2.20 Integral Attachment (4) Lugs VT-3 RR-2 - - - CC N-491-1 PFSK-2526 F-A F1.30c Variable Spring Hanger VT-3 RR-2 - - X CC N-491-1 PFSK-2016 F-A F1.30b Vertical Constraint VT-3 RR-4 - -

X CC N-509 PFSK-2016 D-B D2.20 integral Attachment Stanchion VT-3 RR-2 - - CC N-491-1 PFSK-2395 F-A F1.30b Anchor A10 VT-3 RR-4 - - CC N-509 PFSK-2395 D-B D2 20 Integral Attachment Drtwing Number: MSK-103B1 from MSK-166F1 Line Number: 8"-WES-151-99 VT-3 RR-2 - - - CC N-491-1 PFSK-2288 F-A F1.30b Box Constraint VT-3 RR-4 - - - CC N-509 PFSK-2288 D-B D2.20 Integral Attachment (4) Lugs VT-3 RR-2 - X - CC t[-451-1 PFSK-2229 F-A F1.30c Spring Can Hanger RR-2 CC N-491-1, No drawing F-A F1.30a Rod Har'ger VT-3 - - -

H15-10 VT-3 RR-2 - - - CC N491-1 PFSK-894 F-A F1.30b Anchor CC N-509 l D2.20 Integral Attachment VT-3 RR-4 - - -

PFSK-894 D-B Page 15 - 1 of 15 -9 FILE: RBCLO3.15.WPD

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\ s' % G' James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h

$ Third Inservice Inspection Interval Ten - Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME- ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCR!PTION EXAM REQ PER1 PER2 "YR3 THICM REMARKS 15 - Reactor Building Closed Loop Cooling System Drewing Number: MSK-103B1 Line Number: 6"-WES-151-104 PFSK-2395 F-A F1.30b Anchor A9 VT-3 RR-2 - - -

CC N-491-1 PFSK-2395 D-B D2.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 Drawing Number: MSK-103C1 Line Number: 6"-WCL-151-103 PFSK-2555 F-A F1.30b Vertical Constraint VT-3 RR-2 - - -

CC N-491-1 PFSK-2612 F-A F1.30b Pipe Constraint VT-3 RR-2 - - -

CC N-491-1 PFSK-2556 F-A F1.30e Rigid Sway Strut VT-3 RR-2 - - -

CC N-491-1 Line Number: 6"-WCL-151-29 PFSK-2614 F-A F1.30b Pipe Constraint VT-3 RR-2 - - -

CC N-491-1 PFSK-2613 F-A F1.30b Pipe Constraint VT-3 RR-2 - - -

CC N-491-1 PFSK-2571 F-A F1.30b Anchor VT-3 RR-2 - - -

CC N-491-1 PFSK-2571 0-B D2.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 r

Drcwing Number: MSK-103C2 Line Number: 6"-WCL-151-61 PFSK-2287 F-A F1.30b Anchor VT-3 RR-2 - - -

CC N-491-1 PFSK-2287 D-B D2.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 H15-139 F-A F1.30b Pipe Constraint VT-3 RR-2 - - -

CC N-491-1 FILE: RBCLO3.15.WPO Page 15 - 2 of 15 -9

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James AIFitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] V'

h Date January 7,1998

$ Third Inservice inspection Interval Ten -Yearinspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION COD'? CCDE CODE REL ISI INTERVAL LTH OR CAi ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 2.

15 - Reactor Building Closed Loop Coolin,, System Drawing Number: MSK-103C2 Line Number: 8"-WCL-151-29 PFSK-2287 F-A F1.30b Anchor VT-3 RR-2 - - -

CC N-491-1 PFSK-2287 D-B D2.20 Integral Attachment VT-3 RR-4 - - - CC N-509 PFSK-729 F-A F1.30b Pipe Constraint VT-3 RR-2 - - -

CC N-491-1 H15-160 F-A F1.30b Pipe Constraint VT-3 RR-2 - - -

CC N-491-1 Line Number: 6"-WES-151-103 PFSK-2287 F-A F1.30b Anchor VT-3 RR-2 - - -

CC N-491-1 PFSK-2287 D-B D2.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 H15-94 F-A F1.30b P;pe Support VT-3 RR-2 - - -

CC N-491-1 H15-94 D-B D2.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 PFSK-2336 F-A F1.30b Rigid Constraint VT-3 RR-2 - - -

CC N-491-1 PFSK-2336 D-B D2.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 PFSK-2278 F-A F1.30b Pipe Constraint VT-3 RR-2 - - -

CC Np91-1 PFSK-2278 DB D2.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 PFSK-2517 F-A F1.30c V riable Spring Hanger VT-3 RR-2 - -

X CC N-401-1 PFSK-2517 D-B D2.40 Integral Attachment VT-3 RR-4 - -

X CC N-509 FILE: RBCLO3.15.WPD Page 15 - 3 of 15 -9

3 O O Jrmes A. Fitzpatrick Nuclect Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Date January 7,1998 Third inservice Inspection Interval g P m er Ten -Year Inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME REL ISIINTERVAL LTH OR CODE CODE CODE REMARKS IDENTIFICATION DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK CAT ITEM 15 - Reactor Dullding Closed Loop Cooling System Drt: wing Number: MSK-103C2 Line Number: 6"-WES-151-103 VT-3 RR-2 X - - CC N-491-1 H15-90 F-A F1.30b Pipe Constraint VT-3 RR-4 X - - CC N-509 H15-90 D-B D2.20 Integral Attachment VT-3 RR-2 - - - CC N-491-1 PFSK-2335 F-A F1.30b Frunnfon VT-3 RR-4 - - - CC N-509 PFSK-2335 D-B D2.20 Integral Attachnent VT-3 RR-2 - - - CC N-491-1 PFSK-2496 F-A F1.30b Rigid Constraint VT-3 RR-4 - - - CC N-509 PFSK-2496 D-B D2.20 Integrat Attachment VT-3 RR-2 - - - CC N-491-1 Anchor F-A F1.30b Pump Anchor VT-3 RR-4 - - - CC N-509 Anchor D-B D2.20 Integral Attachment Drawing Number: MSK-103C3 Line Number: 6"-WES-151-104 VT-3 RR-2 - - - CC N-491-1 PFSK-2154 F-A F1.30b Anchor VT-3 RR-4 - - - CC N-509 PFSK-2154 D-B D2.20 Integral Attacament Pad r

Dr: wing Number: MSK-103F Line Number: 6"-WCL-151-29A ,

CC N-491-1 j F1.30b Anchor VT-3 RR-2 - - -

PFSK-2442 F-A VT-3 RR-4 - - - CC N-509 PFSK-2442 D-B D2.20 Integral Attachment )

l FILE: RBCLO3.15.WPD Page 15 4 of 15 -9 :

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Jameslhitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Date January 7,1998

$% h Third Inservice Inspection Interval Ten -Yearinspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 15 - Reactor Building Clo-ed Leop Cooling System Drawing Number: MSK-103F Line Number: 6"-WES-151-103 l PFSK-2424 F-A F1.30b Anchor VT-3 RR-2 - - -

CC N-491-1 PFSK-2424 D-B D2.20 Integml Attachment Pad VT-3 RR-4 - - -

CC N-509 H15-312 N/A N/Ab Lateral Support VT-3 N/A - - - NNS H15-313 F-A N/Ac Variable Spring Can Support VT-3 N/A - -

X NNS 1". Support after valve H15-313 N/A N/A Integral Attachment VT-3 N/A - -

X 1". Support after va!ve Drawing Number: MSK-103P Line Number: 6"-WES-151-104 I PFSK-2154 F-A F1.30b Anchor VT-3 RR-2 - - -

CC N-491-1 j PFSK-2154 D-8 D2.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 l

PFSK-2185 F-A F1.30e Rigid Sway Strut VT-3 RR-2 - - - CC N-491-1 PFSK-2188 F-A F1.30b Lateral Support VT-3 RR-2 - - -

CC N-491-1 PFSK-6552 F-A F1.30b Support VT-3 RR-2 - - -

CC N-491-1 t

l l

FILE: RBCLO3.15.WPD Page 15 - 5 of 15 -9

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James A. Fitzpatrick Nucle:r Power Plant Third inservice inspection Interval [[::JAF-ISI-0003|JAF-ISI-0003]] Date January 7,1998 P N 8' R wis'an 0

$ Ten - Year inspection Plan ASME WELD COMPONENT ASME ASME REL ISIINTERVAL LTH OR CODE CODE CODE REMARKS IDENTIFICATION DESCRIPTION EXAM REQ PER1 PER2 PER3 THtCK CAT ITEM 15 - Reactor Building Closed Loop Cooling System Drawing Number: MSK-103C8 Line Number: 8"-WES-151-99 VT-3 RR-2 - - - CC N491-1 Anchor F-A F1.30b Anchor VT-3 RR-4 - - - CC N-509 Anchor D-B D2.20 Anchor Line Number: 8"-WES-151-100 VT-3 RR-3 - - - CC N-491-1 H15-3 F-A F1.30a Rigid Rod Hanger i

VT-3 RR-4 - - - CC N-509 H15-3 D-R D2.20 Integral Attachment i

Line Number: 6"-WCL-151-61 I 1

VT-3 RR-2 - - - CC N-491-1 Anchor F-A F1.30b Anchor VT-3 RR-4 - - - CC N-509 Anchor D-B D2.20 Integral Attachment

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Line Number: 6"-WCL-151-24 VT-3 RR-2 - - - CC N491-1 Anchor F-A F1.30b Anchor VT-3 RR-4 - - - CC N-509 Anchor D-8 D2.20 Integral Attachment Line Number: 6"-WCL-151-96 VT-3 RR-2 - - - CC N-491-1 Anchor F-A F1.30b Anchor VT-3 RR-4 - - - CC N-509 Anchor D-8 D2.20 Integral Attachment Page 15 - 6 of 15 -9 FILE RBCLO3.15.WPD

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James A Fitzpatrick Nuclear Power Flant [[::JAF-ISI-0003|JAF-ISI-0003]] v

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$ Third Inservice inspection Interval Ten -Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 15 - Reactor Building Closed Loop Cooling System Drawing Number: MSK-103C8 Line Number: 6"-WES-151-104 PFSK-2154 F-A F1.30b Ancf or VT-3 RR-2 - - -

CC N-491-1 PFSK-2154 D-B D2.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 PFSK-943 F-A F1.30a RigW Rod Hanger VT-3 RR-2 - - -

CC N-491-1 H15-244 F-A F1.30b Constraint VT-3 RR-2 X - -

CC N-491-1 PFSK-939 F-A F1.30a Rigid Rod Hanger VT-3 RR-2 - - -

CC N-491-1 PFSK-939 D-8 D2 20 Weided Saddle VT-3 RR-4 - - -

CC N-509 PFSK-2371 F-A F1.30e Rigid Sway Strut VT-3 RR-2 - -

X CC N-491-1 PFSK-2371 D-B D2.20 Integral Attachment Pad VT-3 RR-4 - - X CC N-509 PFSK-925 F-A F1.30a Rigid Rod Hanger VT-3 RR-2 - - -

CC N491-1 PFSK-925 D-B D2.20 integral Attachment Pad VT-3 RR-4 - - -

CC N-509 PFSK-929 F-A F1.30a Rigid Rod Hanger VT-3 RR-2 -

X -

CC N-491-1 l PFSK-329 D-B D2.20 Integral Attachment VT-3 RR-4 -

X -

CC N@09 PFSK-2181 F-A F130e Rigid Sway Strut VT-3 RR-2 - - -

CC N-491-1 PFSK-928 F-A F1.30a Rigid Rod Hanger VT-3 RR-2 - - -

CC N-491-1 l PFSK-920 FA F1.30a Rigid Rod Hanger VT-3 RR-2 - - -

CC N-491-1 PFSK-2191 .* F1.30e Rigid Sway Strut VT-3 RR-2 - - -

CC N-491-1 l

l FILE RBCLO3.15.WPD Page 15 - 7 of 15 -9 &

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O O J:mes A. Fitzpstrick Nucle r Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] O

Third Inservice inspection Interval Date January 7.1998 4 bMW Ten -Yearinspection Pfar: Revision 0 ASME WELD COMPONENT ASME ASME LTH OR CODE REL ISIINTERVAL

' IDENTIFICATION CODE CODE REMARKS DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK CAT ITEM 15 - Reactor Bellding Closed Loop Cooling System Drawing Number: MSK-103C8 Line Number: 6*-WES-151-104 VT-3 RR-2 - - - CC N-491-1 PFSK-915 F-A F1.30a Rigid Rod Hanger Line Number: 6"-WES-151-103 VT-3 RR-2 - - - CC N-491-1 PFSK-2163 F-A F1.30b Anchor VT-3 RR-4 - - - CC N-509 PFSK-2168 D-B D2.20 Integraf Attachment Pad VT-3 RR-2 - X - CC N-491-1 PFSK-2389 F-A F1.30e Rigid Sway Strut VT-3 RR-4 - X - CC N-509 PFSK-2389 D-B D2.20 Pipe Supposi VT-3 RR-2 - - - CC N491-1 PFSK-2170 F-A F1.30e Rigid Sway Strut VT-3 RR-4 - - - CC N-509 PFSK-2170 D-B D2.20 Pipe Support VT-3 RR-2 - - - CC N-491-1 PFSK-922 F-A F1.30a Rigid Rod Hanger VT-3 RR-4 - - - CC N-509 PFSK-922 D-B D2.20 Integral AttachmentPad VT-3 RR-2 - - - CC N-491-1 PFSK-2254 F-A F1.30e Rigid Sway Strut i CC NA09 l D-B D2.20 Pipe Support VT-3 RR4 - - -

PFSK-2254 VT-3 RR-2 - - - CC N-491-1 PFSK-923 F-A F1.30a Rigid Rod Hanger VT-3 RR-4 - - - CC N-509 PFSK-923 D-B D2.20 Welded Lug FILE: RBClu3.15.WPD Page 15 - 8 of 15 -9

/s a James . Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] O

M ItewMM Third inservice Inspection Interval Date January 7,1998 Ten -Yearinspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION em CODE CODE REL ISI INTLRVAL LTH OR CAT ITEM DESCRIPTION EXAM.

REQ PER1 PER2 PER3 THICK REMARMs 15 - Reactor Buliding Closed Loop Cooling System Drawing Number: MSK-103CS Une Number: 6"-WCL-151-72 PFSK-2219 F-A F1.30b Anchor VT-3 RP-2 - - -

CC N-491-1 PFSK-2219 D-B D2.20 Integrat Attachment Pad VT-3 RR-4 - - -

CC N-509 PFSK-2228 F-A F1.30b Lateral Constraint VT-3 RR-2 - - -

CC N-491-1 PFSK-2333 F-A F1.30b Anchor VT-3 RR-2 - - -

CC N-491-1 PFSK-2333 D-B D2.20 Integra! Attachment Pad VT-3 RR-4 - - -

CC N-509 Line N:Jmber: 6"-WCL-151-61 Ancher F-A F1.30b Anchor @316*-0" VT-3 RR-2 - - - CC N-491-1

~

Anchor D-B D2.20 Anchor @316'-0" VT-3 RR-4 - - -

CC N-509 PFSK-2407 F-A F1.30b Anchor VT-3 RR-2 - -

X CC N-491-1 PFSK-2407 D-B D2.20 Welded Saddie VT-3 RR-4 - -

X CC N-509 PFSK-2516 F-A F1.30b Pipe Constraint VT-3 RR-2 - - -

CC N-491-1 PFSK-2565 F-A F1.3Ob Anchor VT-3 RR-2 - - -

CC Np91-1 PFSK-2565 D-B D2.20 Integral Attachment Pad F' RR-4 - - -

CC N-509 PFSK-2185 F-A F1.30e Rigid Sway Strut . RR-2 - - -

CC N-491 1 PFSK-2188 F-A F1.30b Lateral Support VT ^, RR-2 - - -

CC N-491-1 FILE: RBCLO3.15.WPD Page 15 - 9 of 15 -9

,em_ ,

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James A. Fitzpatrick Nuclear Power Pist:t [[::JAF-ISI-0003|JAF-ISI-0003]] g V'wkh Third Inservice Inspection interva!

Ten - Year Ins,rection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME W Ef.D IDENTIFK:ATION CODE CODE CODE REn- ISI!NTERVAL LTH OR CAT ITEM DESCPJPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 19 - F uel Pool Cooling System Drawing Number: MSK-11381 Une Number: 6"-WD-153-14A PFSH-2533 F-A F1.30b Anchor A3 VT-3 RR-2 - - -

CC N-491-1 PFSK-2533 D-C D3.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 PFSK-2316 F-A F1.30a Rod Hanger VT-3 RR-2 - - - CC N-491-1 PFSK-2231 F-A F1.30b Box Constrai'1 VT-3 RR-2 - X -

CC N-491-1 PFSK-2231 D-C D3.20 Integral Attachment VT-3 RC-4 -

X -

CC N-509 PFSK-2479 F-A F1.30b Vertical Constraint VT-3 RR-2 - - -

CC N-491-1 PFSK-2479 D-C D3.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 PFSK-645 FA F1.30b U-bolt Restrain VT-3 RR-2 - - -

CC N-491-1 PFSK-311 F-A F1.30b Lateral Constraint VT-3 RR-2 - - -

CC N-491-1 H19-234 F-A F1.30b Pipe Constraint VT-3 RF -2 - - -

CC N-491-1 PFSK-4945 F-A F1.30b Lateral Restraint VT-3 AR-2 - - -

CC N-491-1 PFSK-4943 F-A F1.30b Anchor (Pipe Stanchion) A4 VT-3 RR-2 - - -

CC 4 91-1 PFSK-4943 D-C D3.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 PFSK-4914 F-A F1.30b Lateral Restraint VT-3 RR-2 - - -

CC N-491-1 FILE: FPC03.19.WPD Page 19 - 1 of 19-5

.V James . Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] V

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$b Third Inservice inspection Inter.at Ten - Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS is - Fuel Pool Cooling System Drawing Number: MSK-113E1 Line Number: 8"-WD-153-66 PFSK-2480 F-A F1.30b Anchor A-4 VT-3 RR-2 - - -

CC N-491-1 PFSK-2480 D-C D320 Integral Pipe Support VT-3 RR-4 - - -

CC N-509 Line Number: 8"-WD-151-67 PFSK-2491 F-A F1.30b Vertical Restraint VT-3 RR-2 - - -

CC N-491-1 PFSK-2491 D-C D3.20 (4) Welded Lugs VT-3 RR-4 - - -

CC N-509 PFSK-2309 F-A F1.30b Box Constraint VT-3 RR-2 - - - CC N-491-1 PFSK-2330 F-A F1.30b Constraint VT-3 RR-2 - - -

CC N-491-1 PFSK-2067 F-A F1.30b Pipe Restraint VT-3 RR-2 - - -

CC N-491-1 PFSK-2332 F-A F1.30c Spring Hanger VT-3 RR-2 - -

X CC N-491-1 PFSK-2332 D-C D3.40 IntegralWelded Lugs VT-3 RR-4 - -

X CC N-509 PFSK-1867 F-A F1.30b Box Restraint VT-3 RR-2 - - -

CC N-491-1 i

PFSK-2302 F-A F1.30b Anchor A2 VT-3 RR-2 - - -

CC N-491-1 PFSK-2302 D-C D3.20 Welded Pad VT-3 RR-4 - - -

CC N-509 Line Number: 8"-W19-151-17 PFSK-1929 F-A F1.30b Pipe Restraint VT-3 RR-2 - - -

CC N-491-1 FILE: FPC03.19.WPD Page 19 - 2 of 19-5

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$b Third Inservice inspection interval Ten -Year inspection Plan Date January 7,1998 Revision 0

COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 TH:CM REMARKS 19 - Fuel Pool Cooling System Drawing Number: MSK-113D1 Lira Number.10"-W19-151-1B PFSK-2551 F-A F1.30c Variable Spring Hanger VT-3 RR-2 - - -

CC N-491-1 H19-123 F-A F1.30b Pipe Constraint VT-3 RR-2 - - -

CC N-491-1 H19-123 D-C D3.20 Integral Attachment (4) Lugs VT-3 RR-4 - - -

CC N-509 PFSK-2552 F-A F1.30c Variable Spring Hanger VT-3 RR-2 - - -

CC N-491-1 PFSK-2425 F-A F1.30e Vertical Sway Strut VT-3 RR-2 - - -

CC N-491-1 PFSK-1933 F-A F1.30b Pipe Conuraint VT-3 RR-2 - - -

CC N-491-1 PFSK-2368 F-A F1.30a Rod Hangen VT-3 RR-2 - - -

CC N-491-1 PFSK-2493 F-A F1.30b Anchor A6 VT-3 RR-2 - - -

CC N-491-i PFSK-2493 D-C D3.20 Welded Pad VT-3 RR-4 - - -

CC N-491-1 oFSK-2103 F-A F1.30b Box Constraint VT-3 RR-2 - - -

CC N-491-1 Drawing Number. MSK-113F1 Line Numter: 8"-WD-153-13A ,

PFSK-2096 F-A F1.30b Lateral Constraint VT-3 RR-2 - - -

CC N-491-1 PFSK-2096 D-C D3.20 Integrally Welded Lug VT-3 RR-2 - - -

CC N-509 FILE: FPCO3.19.WPD Page 19 - 3 of 19-5

%J James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] A liie w M W Third Inservice Inspection Interval Date January 7,1998

Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT TTEM DESCRtPTION EXAM REQ PERT PER2 PER3 THfCK REMARKS 19 - Fuel Pool Cooiing System Drawing Number: MSK-113F1 Line N' m1ber: 6"-WD-153-14A PFSK-1979 F-A F1.30b Anchor A1 VT-3 RR-2 - - -

CC N-491-1 PFSK-1979 D-C D3.20 Welded Trunnion VT-3 RR-4 - - -

CC N-509 FFSK-2411 F-A F1.30b Vertical L mirarnt VT-3 RR-2 X - -

CC N-491-1 PFSK-2411 D-C D3.20 Weldr

Pipe Stanchion VT-3 RR-4 X - -

CC N-509 PFSK-2021 F-A F1.30b Anchor A8 VT-3 RR-2 - -

CC N-491-1 PFSK-2021 D-C D3.20 Wetdsd Pad VT-3 RR-4 - - -

CC N-509 H19-216 F-A F1.30a Rod Hanger VT-3 RR-2 - - -

CC N-491-1 PFSK-1000 F-A F1.30a Rod Hanger VT-3 RR-2 - -

X CC N-491-1 PFSK-1948 F-A F1.30a Rod Hanger VT-3 RR-2 - - - CC N-491-1 PFSK-2533 F-A F1.30b Anchor A3 VT-3 RR-2 - - -

CC N-491-1 PFSK-2533 D-C D3.20 Welded Pad VT-3 RR-4 - - -

C 1 N-509 t

Line Number: 6"-WD-153-14B PFSK-2569 F-A F1.30b Anchor VT-3 RR-2 - - -

CC N-491-1

- PFSK-2569 D-C D3.20 Welded Pad VT-3 RR-4 - -

CC N-509 H19-215 F-A F1.30a Rod Hanger VT-3 RR-2 - - -

CC N-491-1 PFSK-1927 F-A F1.30b Lateral Constraint VT-3 RR-2 - - -

CC N-491-1 FILE: FPC03.19.WPD Page 19 - 4 of 19-5

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Ten - Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 TH!CK REMARKS 19 - Fuel Pool Cooling System Drawing Number: MSK-113F1 Line Number. T'-WD-153-14B H19-214 F-A F1.30a Rod Hanger VT-3 RR-2 - - -

CC N-491-1 PFSK-2022 F-A F1.30b Anchor VT-3 RR-2 - - -

CC N-491-1 PFSK-2022 D-C D3.20 Wolded Pad VT-3 RR-4 - - -

CC N-509 H19-236 F-A F1.30b Constraint VT-3 RR-2 - - - CC N-491-1, inaccessible H19-237 F-A F1.30b Cons *raint VT-3 RR-2 - - - CC N-491-1, inaccessible Drawing Number: MSK-113C1 Line Number: 6"-WD-153-14B PFSK-1012 F-A F1.30c Variable Spring Hanger VT-3 RR-2 - - -

CC N-491-1 PFSK-2276 F-A F1.30b Restraint VT-3 RR-2 - - -

CC N-49' -1 PFSK-2297 F-A F1.30b Box Restraint VT-3 RR-2 X - -

CC N-491-1 FILE: FPC03.19.WPD Page 19 - 5 of 19-5

James aA. Nitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] '

g h Third Inservice inspection interval Ten - Year inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 31CK REMARKS 49 - Service Water System Dra.ving Number: MSK-137K1 Line Number: 12"-WES-151-2A from Pump 46-P-2A Anchor A12 F-A F1.30b Anchor VT-3 RR-2 X - -

CC N-491-1 Anchor A12 D-B D2.20 Integral Attachment VT-3 RR-4 X - -

CC N-509 Anchor A9 F-A F1.30b Anchor VT-3 RR-2 - - - CC N-491-1 Anchor A9 D-B D2.20 Integral Attachment VT-3 RR-4 - -

CC N-509 PFSK-4004 F-A F1.30b Vertical Pipe Support VT-3 RR-2 -

X -

CC N-491-1 Line Number: 10"-WES-151-37 PFSK-2410 F-A F1.30b Vertical Pipe Support VT-3 RR-2 - - -

CC N491-1 PFSK-2012 F-A F1.30b Pipe Support VT-3 RR-2 - - -

CC N-491-1 PFSK-2010 F-A F1.30b Vertical Pipe Support VT-3 RR-2 - - -

CC N-491-1 ri46-40 F-A F1.30b Constraint VT-3 RR-2 - - - CC N-49;-1 PFSK-2008 F-A F1.30b Constraint VT-3 RR-2 - - -

CC N-491-1 H46-38 F-A F1.30b Pipe Support VT-3 RR-2 - - -

CC N,-491-1 PFSK-2015 F-A F1.30b Pipe Support VT-3 RR-2 - - -

CC N-491-1 FILE: SWS03A6.WPD Page 46 - 1 of 46-11

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46 -Service Water System Drawing Number: MSK-137K1 Line Number: 12"-WES-151-28 from Pump 46-P-2B AnchorA11 F-A F1.30b Anchor VT-3 RR-2 - - -

CC N-491-1 Anchor A11 D-B D2.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 Anchor A8 F-A F1.30b Anchor VT-3 RR-2 - - -

CC N-491-1 Anchor A8 D-B D2.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 PFSK-4005 F-A F1.30b Vertical Pipe Support VT-3 RR-2 - - -

CC N-491-1 PFSK-2093 F-A F1.30b Vertical Pipe Support VT-3 RR-2 - - -

CC N-491-1 Line Number: 10"-WES-151-38 i

PFSK-1992 F-A F1.30b Vertical Constraint VT-3 RR-2 - - -

CC N-491-1 PFSK-1123 F-A F1.30b Pipe Constraint VT-3 R.R-2 - - -

CC N-491-1 PFSK-2014 F-A F1.30b Vertical Pipe Constraint VT-3 RR-2 - - -

CC N-491-1

, PFSK-1124 F-A F1.30b Pipe Constraint VT-3 RR-2 - - -

CC N-491-1 P

FILE: SWS03.46.WPD Page 46 -2 of 4G - 11

O James

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Third Inservice Inspection Interval Date January 7,1998

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- Ten -Year Inspection Plan Revision D ASME WELD COMPONENT ASME ASME ISI INTERVAL LTH OR CODE REL IDFJITIFICATION CODE OODE REQ PER1 PER2 PER3 THICK REMARKS CAT ITEM DESCRIPTION EXAM 46 -Service Water System Drawing Number: MSK-137N1 t ine Number: 12"-WES-151-9 VT-3 RR-2 - - - CC N491-1 PFSK-1996 F-A F1.3Lo Anchor A1 D2.20 Welded Pipe Stanchion VT-3 RR-4 - - - CC N-509 l PFSK-1996 D-B VT-3 RR-2 - - - CC N-491-1 PFSK-2108 F-A F1.30b Pipe Support Box VT-3 RR-2 - - - CC N-491-1 PFSK-1998 F-A F1.30b Box Restraint Line Number: 8*-WES-151-10 VT-3 RR-2 - - - CC N-491-1 PFSK-1352 F-A F1.30b Guide Support VT-3 RR-4 - - - CC N-509 PFSK-1352 D-B D2.20 (4)Integraffy Weided Lugs VT-3 RR-2 - X - CC N-491-1 H46-158 F-A F1.30b Pipe Constraict VT-3 RR-4 - X -

.25" CC N-509 H46-158 'D-B D2.20 (4)Integratly Welded Lugs VT-3 RR-2 - - - CC N-491-1 PFSK-2115 F-A F1.30b Vertical Pipe Support RR-4 - - CC N-509 PFSK-2115 D-B D2.20 Integral Attachment Stanchion VT-3 -

F1.30b Lateral Pipe Support VT-3 RR-2 - - -

CC Nr491-1 PFSK-1973 F-A VT-3 RR-2 - - - CC N-491-1 ;

PFSK-2117 F-A F1.30c Vertical Pipe Support 1 VT-3 RR-2 - - - CC N-491-1 PFSK-2026 F-A F1.30b Anchor A3 VT-3 RR-4 - - CC N-509 PFSK-2026 D-B D2.20 Welded Pipe Support -

Page 4G - 3 of 46 -11 FILE: SWS03.46.WPD

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g h Third Inservice Inspection Interval Ten -Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL 151 INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 46 - Service Water System Drawing Number: MSK-137P1 Line Number: 8"-WES-151-4B HPCI Turbine Heat Exchanger Line 23TU-2 H46-182 F-A - F1.30b Anchor A2-380 VT-3 RR-2 - - - CC N-491-1,6.21-46-182 H46-182 D-8 D2.20 Integral Attachment VT-3 RR-4 - - - CC N-509 H46-181 F-A F1.30s Rod Hanger VT-3 RR-2 - X -

CC N-491-i. 6.21-46-181 -

PFSK-1983 F-A F1.30a Vertical Rod Hanger VT-3 RR-2 - - -

CC N-491-1 H46-165 F-A F1.30a Rod Hanger VT-3 RR-2 - - - CC N-491-1 H46-165 D-B D2.20 Integral Attachment (1) Lug VT-3 RR-4 - - - CC N-509 H46-164 F-A F1.30e Rod Hanger VT-3 RR-2 - - -

CC N-491-1 H46-164 D-B D2.20 Integral Attachment (1) Lug VT-3 RR-4 - - - CC N-509 Line Number: 8"-WES-151-4A PFSK-706 F-A F1.30a Rod Hanger VT-3 RR-2 X - - CC N-491-1 H46-180 F-A F1.30b Constraint VT-3 RR-2 - - -

CC N-491-1 H46-179 F-A F1.30b Anchor A1-1 VT-3 RR-2 - - -

CC Np91-1 H46-179 D-B D2.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 FILE: SWS03.46.WPD Page 46 -4 of 46 -11

O O James A Fitzpatrick Nucle r Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] O

Third inservice Inspection interval Date January 7,1998

-M M Revision 0 Ten -Year Inspection Plan ASME WELD COMPONENT ASME ASME REL ISIINTERVAL LTH OR CODE CODE CODE REMARKS IDENTIFICATION DEscrtlPTION EXAM REQ PER1 PER2 PER3 THICK CAT ITEM 46 -Service Water System Drawing Number: MSK-137P1 Lino Number: 8"-WES-151-38 VT-3 RR-2 - - - CC N-491-1 F-A F1.30b Lateral Pipe Support PFSK-2458 -

VT-3 RR-2 - - - CC N-491-1 F-A F1.30b Vertical Pipe Support PFSK-2204 VT-3 RR-4 - - - CC N-509 PFSK-2204 D-B D2.20 Integral Attachment VT-3 RR-2 - - - CC N-491-1 H46-340 F-A F1.30b Pipe Constraint VT-3 RR-2 - - - CC N-491 1 H46-162 F-A F1.30b Pipe Support RR-4 - - - CC N-509 H46-162 D-B D2.20 Integral Attachment Stanchion VT-3 CC N-491-1, No drawing F1.30b Pipe Constraint VT-3 RR-2 - - -

PFS:'-4946 F-A Line Number: 8"-WES-15f-3A VT-3 RR-2 - - - CC N-491-1 PFSK-1853 i F-A F1.30b l_ateral Support VT-3 RR-2 - - - CC N-491-1 H46-161 F-A F1.30b Pipe Support RR-4 - - - CC N-509 H46-161 D-B D2.20 Integra! Attachment, Stanchion VT-3 VT-3 RR-2 - - - CC N y491-1 H46-338 F-A F1.30b Horizontal Constraint VT-3 RR-2 - - - CC N-491-1 H46-160 F-A F1.30b Pipe Support i

RR-4 - - - CC N-509 H46-160 D-B D2.20 Integral Attachment Stanchion VT-3 l

Page 46 -S of 46 - 11 FILE: SWS03.46.WPD

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$b Ten -Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERYAL LTH OR i CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICK REMARKS 46 - Service Water System Drawing Numbec MSK-137Q1 Une Number: 8*-WES-151-4A H43-179 F-A F1.30b Anchor A1-1 VT-3 RR-2 - - -

CC N-491-1 H46-179 D-B D2.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 H46-178 F-A F1.30b Constraint VT-3 RR-2 - - CC N-491-1 Une Number: 6"-WES-151-5A H46-177 F-A F1.30b Constraint VT-3 RR-2 - - - CC N-491-1 PFSK-2011 F-A F1.30b Vertical Pipe Support VT-3 RR-2 - - - CC N-491-1 l

Une Number: 6*-WES-151-5B H46-176 F-A F1.30b Constraint VT-3 RR-2 - - -

CC N-491-1 PFSK-1981 F-A F1.30b Vertical Pipe Support VT-3 RR-2 - -

X CC N-491-1 Une Number: 8"WES-151-48 A2-380 F-A F1.30b Anchor VT-3 RR-2 - - -

CC N-491-1 A2-380 D-B D2.20 Integral Attachment VT-3 RR-4 - - -

CC N9509 H46-168 F-A F1.30b Constraint VT-3 RR-2 - - -

CC N-491-1 Une Number: 6"-WES-151-6A H46-175 F-A F1.30b Constraint VT-3 RR-2 - - -

CC N-491-1 PFSK-2066 F-A F1.30b Vertical Constraint VT-3 RR-2 - - - CC N-491-1 FILE: SWS03.46.WPD Page 46-6 of 46-11

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f 46 -Service Water System Drawing Number: MSK-166E1 Line Number: 1G" WES-151-38 from MSK-137K1 VT-3 RR-2 X - - CC N 491-1 PFSK-2004 F-A F1.30b Pipe Support VT-3 RR-2 - - - CC N-491-1 H46-125 F-A F1.30d Sliding Support VT-3 RR-4 - - CC N-509 H46-125 D-B D220 Integral Attachment VT-3 RR-2 - - - CC N-491-1 PFSK-2372 F-A F1.30b Vertical Dipe Suppe:t VT-3 RR-2 - - - CC N 491-1 PFSK-2113 F-A F1.30b Pipe S,Jpport VT-3 RR-2 - - - CC N-491-1 H46-126 F-A F1.30b Pipe Constraint VT-3 RR 4 - - - CC N-509 H46-128 D-8 D2.20 8ntegraf Attacewnent VT-3 RR-2 - - CC N-491-1 PFSK-2114 F-A F1.30b Vertical Pipe Support -

VT-3 RR-2 - - - CC N-491-1 H46-130 F-A F1.30b Pipe Support VT-3 RR-2 - - - CC F 491-1 PFSK-2146 F-A F1.30b Anchor A4 VT-3 RP4 - - - CC N-509 PFSK-2146 D-B D2.20 Integral Attachment VT-3 RR-2 - - X CC N 7491-1 H46-132 F-A F1.30b Pipe Constraint D220 Welded Pipe Stanchion VT-3 RR-4 - -

X CC N-509

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VT-3 RR-2 - - - CC N-491-1 PFSK-2144 F-A F1.30b Pipe Support VT-3 RR-2 - - - CC N-491-1 H4G-134 F-A F1.30b Pipe Constraint VT-3 RR-2 - - - CC N-490-1 PFSK-2382 F-A F1.30b Pipe Support Page 46 - 8 of 46 -11 FILE: SWS03.46.WPD

O James CFitzpatrick Nuclear Power Plant [[::JAF-ISI-0023|JAF-ISI-0023]] Date January 7,1998 Third Inservice Inspection Interval p h Ten -Year Inspect 8en Plan Revision 0 ASME WELD COMPONENT ASME ASME ISIINTERVAL LTH J',d CODE REL IDENTIPCATION CODE CODE REO PERS PER2 PER3 THCK REMARKS CAT ITEM DESCmri Ged EXAM 46 - Service Water System Drawing Number: MSK-166E1 Line Number: 10"-WES-if t-38 from MSK-137K1 VT-3 RR-2 - - - CC N-491-1 H46-136 F-A F1.30b Pipe Constraint VT-3 RR-2 - - - CC N-491-1 PFSK-243.9 F-A F'_30b Pm Support D220 Welded Pipe Stanc^ won VT-3 RR-4 - - - CC N-509 PFSK-2432 D-B VT-3 RR-2 - - - CC N-491-1 H46-138 F-A F1.30b Pipe Support VT-3 RR-4 - - - CC N-509 H46-138 D-B D220 Integraf Attachment VT-3 RR-2 - - - CC N-491-1 PFSK-2472 F-A F1.30b Pipe Support Une Number: 8"-WES-151-100 VT-3 RR-2 - - - CC N-491-1 H46-140 F-A F1.30b Pipe Support VI-3 RR-4 - - CC N-509 H46-140 D-B D2.20 Welded Pipe Stancivon -

VT-3 RR-2 - - - CC N-491-1 PFSK-2051 F-A F1.30b Anchor A5 VT-3 RR-4 - - - CC N-509 PFSK-2051 0-B D2.20 Integral Attachment

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FILE: SWS03.46.WPD Page 46 - 9 of 46 -11

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] nird Inservice inspection Interval Date January 7,1996 g h Ten -Year Inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME ISI INTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE REQ PER1 PER2 PER3 THICK REEARKS CAT ITEM DESCRIPTION EXAM ._

l 46 -Service Water System Drawing Number: MSK-166F1 Une Number: 10"-WES-151-37 VT-3 RR-2 - - - CC N-491-1 PFSK-1912 F-A F130b Anchor F-3 RR-4 - - - CC N-509 PFSK-1912 D-B D2.20 Integraf Attachment VT-3 RR-2 - - X CC N 491-1 PFSK-2017 F-A F1.30b Pipe Support VT-3 RR-2 - - - OC N 491-1 PFSK-2464 F-A F1.30b Pipe support VT-3 RR-2 - - - CC N-491-1 PFSK-2475 F-A F130b Pipe Support VT-3 RR-2 - X - CC N-491-1 PFSK-2169 F-A F130b Pipe Support VT-3 RR-2 - - - CC N-491-1 PFSK-2037 F-A F1.3% Pipe Support VT-3 RR-2 - - - CC N-491-1 PFSK-2131 F-A F130b Pipe Support VT-3 RR-2 - - - CC N-491-1

'FSK-2399 F-A F1.30b Pipe Support VT-3 RR-2 - - - CC N-491-1 PFSK-2200 F-A F130b Pipe Support VT-3 RR-2 - - - CC N-491-1 PFSK-1970 F-A F1.30b Pipe Support F1.30b Pipe Support VT-3 RR-2 - - - CC NA91-1 PFSK-2445 F-A VT-3 RR-2 - - - CC N-491-1 PFSK-2441 F-A F1.30b Pipe Support VT-3 RR-2 - - - CC N-491-1 PFSK-2459 F-A F130b Pipe Support FitE SWS03.46.WPD Page 46-10 of 46 -11

o h Jarnes9. Fitzpatrick Nuclear Power JAF-tS14003 Third Inservice inspection Interval Plant Date January 7,1098 o

$ Ten -Year Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THfCK REMARKS t

46 - Service Water System Drawing Number: MSK-166F1 Line Neber. 8"-WES-151-99 PFSK-1999 F-A F1.30b Pipe Support VT-3 RR-2 - - -

CC N-491-1 PFSK-1974 F-A F1.3Ob Pipe Suppod VT-3 RR-2 - - -

CC N-491-1 PFSK-2348 F-A F1.30b Anchor AS VT-3 RR-2 - - -

CC N-491-1 PFSK-2348 D-8 D2.20 Integral Attachment VT-3 R~l-4 - - -

CC N<09 i

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i James Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] b Third Inservice Inspection Interval Date Janualy 7,1998

$ Ten -Yeal Inspection Plan Revision 0 COMPONENT ASME ASEE ASME WELD IDE"TFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PERg PER2 PER3 THICK. REMARKS 66 - Reactor Building Vent and Cooling System Drawing Number: MSK-1359 Line Number: 6'-WES-151-69 BFSK421 F-A F130b Anchor VT-3 RR-2 - - -

CC N-491-1 BFSK-421 D-B D2.20 (4)IntegraHy Welded Lugs VT-3 RR-4 - - -

CC N-509 Drawing Number: MSK-1361 Line Number: 6"-WES-151-69 BFSK-871 F-A F130b Pipe Constraint VT-3 RR-2 X - -

CC PM91-1 BFSK-1010 F-A F130b Pipe Constraint VT-3 RR-2 - - -

CC PM91 1 BFSK-970 F-A F130b Pipe Constraint VT-3 RR-2 - - -

CC fM91-1 BFSK-872 F-A F130b Pipe Constraint VT-3 RR-2 - - - CC N-491-1 l

3FSK-875 F-A F130b Pipe Constraint VT-3 RR-2 - - -

CC N-491-1 BFSK-862 F-A F1.30b Pipe Constraint VT-3 RR-2 - - -

CC N-491-1 BFSK-1014 F-A F130b Pipe Constraint VT-3 RR-2 - - -

CC N-491-1 BFSK-955 F-A F130b Pipe Constraint VT-3 RR-2 - - -

CC N-491-1 BFSK-1029E F-A F130a Rod Hanger VT-3 RR-2 - X -

CC N-491-1 BFSK-1013 F-A F1.30b Pipe Constraint VT-3 RR-2 - - - CC N-491-1 BFSK-866 F-A F130b Dipe Constraint VT-3 RR-2 - - -

CC N-491-1 BFSK-819 F-A F130b Anchor VT-3 RR-2 - - - CC N-491-1 BFSK-819 D-B D220 Welded StanctCw VT-3 RR-4 - - -

CC N-509 FILE- RBVCO3.66.WPD Page 6C - 1 of 66 -3

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'm N, James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] g h Third Inservice inspection Interval Ten -Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTUtVAL LTH OR CAT ITEM DESCRIPTON EXAM REQ PER1 PER2 PER3 THICK REMARKS 9

66 - Reactor Building Vent and Cooling System Drawing Number: MSK-1361 Line Nuinber: 6"-WES-151-69 BFSK-1032 F-A F1.30b Pipe Constraint VT-3 RR-2 - - X CC N491-1 BFSK-82G F-A F1.30b Pipe Constraint VT-3 RR-2 - - - CC N-491-1 BFSK-10290 F-A F130a Rod Hanger VT-3 RR-2 - - -

CC N-491-1 BFSK-1002 F-A F1.30b Pipe Constraint VT-3 RR-2 - - -

CC N491-1 BFSK-1029C F-A F1.30a Rod Hanger VT-3 RR-2 - - -

CC N-491-1 BFSK-10298 F-A F1.30a Red Hanger VT-3 RR-2 - - -

CC N-491-1 BFSK-820 F-A F1.30b Pipe ConstraW VT-3 RR-2 - - -

CC N-491-1 BCSK-1031 F-A F1.30b Pipe Constraint VT-3 RR-2 - - -

CC N-491-1 BFSK-1029A F-A F1.30a Rod Hanger VT-3 PR-2 - - -

CC tt-491-1 BFSK-81G F-A F1.30e Unistrut VT-3 RR-2 - - -

CC N-491-1 BFSK-874 F-A F1.30b Pipe Constrairi VT-3 RR-2 - - -

CC N491-1 BFSK-1030 F-A F130b Pipe Cordraint VT-3 RR-2 - - -

CC NT491-1 BFSK-889 F-A F1.30b Pipe Constraint VT-3 RR-2 - - -

CC N-491-1 FILE RBVCO3.66?WPD Page 66 - 2 of 66-3

O O James A. Fitzpatrick Nuclear Power Plant J#.F-IS14003 Date January 7,1998 W Third inservice Inspection Interval

$ Ten -Yearinspection Plan Revision O ASME WELD COMPONENT ASME ASME LTH OR CODE REL ISI INTERVAL IDENTIFICATION CODE CODE REMARKS CAT ITEM DESCRIPTION EXAM REQ PERS PER2 PERs THICK 66 - Reactor Building Vent and Cooling System Drawing Number: MSK-1363 Une Number: 6"-WS-151-7 VT-3 RR-2 - - - CC N-491-1 BFSK 446G F-A F1.30b Box Constraint VT-3 RR-2 - - - CC N491-1 BFSK-852 f-A F1.30b Verical Constraint VT-3 RR-2 - - - CC N-491-1 BFSK-447C F-A F1.30b Box Constraint VT-3 RR-2 - - - CC N-491 1 BFSK-922 F-A F1.30b Box Constraint r

FILE RBVCO3.66.WPD Page 66 - 3 of 66 -3

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$ Third Inservice inspection Interval Ten - Year Inspection Plan Date January 7,1998 Revision 0 i

COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 70 - Control Room Vent and Cooling System Drawing Numbec MSK-1474 Une Numbec 6"-WS-151-2 BFSK-632 F-A F1.30b Restraint VT-3 RR-2 - - -

CC N-491-1 BFSK-785 F-A F1.30b Constraint VT-3 RR-2 - - -

CC N-491-1 BFSK-779 F-A F1.30b Anchor VT-3 RR-2 - - -

CC N-491-1 BFSK-779 D-B D2.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 BFSK-967 F-A F1.30b constraint VT-3 RI.-2 - - -

CC N-491-1 Drawing Number: MSK-1475 ;

BFSK-731 F-A F1.30b Trunnion / Anchor VT-3 RR-2 X - -

CC N-491-1 BFSK-731 D-B D2.20 Welded Pipe Support VT-3 RR-4 X - -

CC N-509 BFSK-743 F-A F1.30b Vertical Constraint VT-3 RR-2 - - - "C N-491-1 BFSK-932 F-A F1.30b Vertical Constraint VT-3 RR-2 - - -

CC N-491-1 BFSK-784 F-A F1.30b Trunnion / Anchor VT-3 RR2 - - -

CC N-491-1 BFSK-784 D-B D2.20 Integral Attachment VT-3 RR-4 - - - CC N 509 Line Number: 6*-WS-151-35 BFSK-864 F-A F1.30b Constraint VT-3 RR-2 - - -

CC N-491-1 BFSK-864 D-B D2.20 Integral Attachrnent VT-3 RR-4 - - -

CC N-509 FILE CRVCO3.70.WPD Page 70 - 1 of 70 - 6

V James A Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h Third inservice Inspection Interval Date January 7,1996

$ Ten - Year Inspection Plan Revision O COMPONENT ASME ASME ASME VVELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS m.

70 - Control Room Vent and Cooling System Drawing Numbec MSK-1475 Line Numbec 6"-WS-151-1 BFSK-809 F-A F1.3Ob Anchor VT-3 RR-2 - - -

CC N491-1 BFSK-809 D-B D220 Welded Pipe Suppor. VT-3 RR-4 - - - CC N-509 BFSK-865 F-A F1.30b Vertice' Constraint VT-3 RR-2 - - -

CC N491-1 BFSK-936 F-A F1.30b Anchor VT-3 RR-2 - - -

CC N491-1 BFSV-93G D-B D2.20 Welded Pipe Support VT-3 RR-4 - - -

CC N-509 Drawing Numbec MSK-1476 BFSK-777 F-A F1_30b Vertical Constraint VT-3 RR-2 - - -

CC N-491-1 BFSK-737 F-A F1.30b Anchor VT-3 RR-2 - - -

CC NJ91-t BFSK-737 D-B D220 Welded Pad VT-3 RR-4 - - -

CC N-509 Drawing Numbec MSK-1456 Une Numbec 6"-WES-151-41 NoID F-A F1.30b Constraint VT-3 RR-2 - - -

CC Np91-1, inaccess.ble BFSK-10G4 F-A F130s Rod Hanger VT-3 RR-2 - X -

CC N-491-1 BFSK-1063 F-A F1.30a Rod Hanger VT-3 RR-2 - - -

CC N-491-1 BFSK-387 F-A F1.30b Anchor VT-3 RR-2 - - -

CC N491-1 ,

t BFSK-387 D-B D220 Integral Attachment VT-3 RR-4 - - -

CC N-509 BFSK-386 F-A F1.30b Constraint VT-3 RR-2 - - - CC N-491-1 FILE: CRVCO3.70.WPD Page 70 - 2 of 70-6

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-4SI-0003|JAF-4SI-0003]] v

h Third inse*vice inspection Interval Date Januzry 7,1998

$ Ten -Year inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE t CODE REL ISIINTERVAL LTH OR CAT ITEM CCSCRIPTION EXAW REQ PER1 PER2 PER3 THICK REMARKS 70 - Control Room Vent and Cooling System Drawing Number: MSK-1456 Une Number: 6~-WES-151-41 BFSK-385 F-A F130b Restraint VT-3 RR-2 - - - CC N491-1 BFSK-384 F-A F1.30b Restraint VT-3 RR-2 - - -

CC N491-1 Une t4 umber: 6"-WES-151-40 No10 F-A F130b Constraint VT-3 RR-2 - - - CC N-491-1, Inaccessible BFSK-1064 F-A F1.30a Rod Hanger VT-3 RR-2 - X -

CC N-491-1 BFSK-1063 F-A F1.30a Rod Hanger VT-3 RR-2 - - -

CC N491-1 BFSK-387 F-A F1.30b Anchor VT-3 RR-2 - - -

CC N-491-1 BFSK-337 D-B D220 ntegral Attachment VT-3 RR-4 - - -

CG N-509 BFSK-386 F-A F1.30b Constraint VT-3 RR-2 - - -

CC N-491-1 BFSK-385 F-A F1.30b Restraint VT-3 RR-2 - - -

CC N-491-1 BFSK-384 F-A F1.30t$ Restraint VT-3 RR-2 - - -

CC N-491-1

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Drawing Number: MSK-1457 Une Number: G"-WES-151-41 BFSK-1077 F-A F1.30a Rod Hanger VT-3 RR-2 - - - CC N-491-1 BFSK-392 F-A F1.30e Rigid Sway Strut VT-3 RR-2 X - - CC N-491-1 BFSK-1076 F-A F1.33a Rod Hanger VT-3 RR-2 - - - CC N-491-1 FILE: CRVC03.70.WPD Page 70 - 3 of 70 -6

James A Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] h Date January 7,1998

$ Sird Inservice Inspection Interval Ten -YearInspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL IS3 INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICK REMARKS 70 - Control Room Vent and Cooling System Drawing Number: MSK-1457 Une Number: 6"-WES-151-40 BFSK-1077 F-A F130a Rod Hanger VT-3 RR-2 - - -

CC N 491-1 i

BFSK-392 F-A F130e Rigid Sway Strut VT-3 RR-2 - -

X CC N-491-1 BFSK-1076 F-A F1.30a Rod Hanger VT-3 RR-2 - - -

CC N-491 1 Drawing Number: MSK-1458 Line Number: 6"-WES-151-41 BFSK-937 F-A F130b Constraint VT-3 RR-2 - - X CC N-491-1 BFSK-921 F-A F130b Constraint VT-3 RR-2 - - -

CC N-491-1 i BFSK-883 F-A F130b Constraint VT-3 RR-2 - - -

CC N-491-1 f

BFSK-896 F-A F1.30b Constraint VT-3 RR-2 - - -

CC N-491-1 BFSK-894 F-A F1.30b Anchor VT-3 RR-2 - - -

CC N-491-1 l BFSK-894 D-B D2 20 Integral A tachment VT-3 RR-4 - - -

CC N-509 Line Number: 6"-WES-151-40 t

! BFSK-987 F-A F130b Constrarnt VT-3 RR-2 - -

X CC N-491-1 l

BFSK-921 F-A F130b Constraint VT-3 RR-2 - - -

CC N-491-1 BFSK-883 F-A F1.30b Constraint VT-3 RR-2 - - -

CC N-491-1 BFSK-896 F-A F130b Constraint VT-3 Rrt-2 - - -

CC N-491-1 l

FILE: CRVC03.70.WPD Page 70 - 4 of 70-6

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] g b Third Inservice Inspection Interval Ten -Year Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIPCATION CODE CODE CODE REL ISI NTERVAL LTH OR CAT ITEM DESCRioTION EXAM REQ PER1 PER2 PER3 TRCK REVARKS 70 - Control Room Vent and Cooling System Drawing Number: MSK-1458 Line Number: 6"-WES-15140 BFSK-940 F-A F1.306 Anchor VT-3 RR-2 - - -

CC N-40 s-1 BFSK-940 0-8 D2.20 Integral Attachment VT-3 RR-4 - - -

CC N-509 Drawing Number: MSK-1492 Line Number: 6"-WES-151-41 BFF'(-1050 N/A N/A Rod Hanger Temporary Support N/A N/A - - -

No exam required,left in place BFSK-1049 F-A F1.30a Rod Hanger VT-3 RR-2 - - -

CC N-491-1 BFSK-844 F-A F1.30b Box Restraint VT-3 RR-2 - - - CC N-491-1 BFSK-1048 F-A F1.30a Rod Hanger VT-3 RR-2 - - -

CC N-491 1 BFSK-1047 F-A F1.30a Rod Hanger VT-3 RR-2 - - -

CC N-491-1 BFSK-830 F-A F1.30b Box Restraint VT-3 RR-2 - - -

CC N-491-1 BFSK-1046 F-A F1.30a Rod Hanger VT-3 RR-2 - - -

CC N-491-1 BFSK-861 F-A F1.30b Box Restraint VT-3 RR-2 - - -

CC N T491-1 BFSK-846 F-A F1.30k Box Restraint VT-3 RR-2 - - -

CC N-491-1 FILE: CRVC03.70.WPD Page 70 - 5 of 70 -6

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James rAtzpatrick Nuclear Power Plant JAF4SI-0003 g Power Third inservice Inspection; Interval Ten - Year inspection P!:et Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD !

IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRfPTION EXAM REQ PER1 PER2 PEF; THICK REMARKS 70 - Control Room Vent and Cooling System Drawing Number: MSK-1492 Une Number: 6*-WES-151-40 BFSK-1044 N/A t#A Rod Hanger Temporary Support t#A PUA - - - No exam required,left in place BFSK-834 F-A F1.30b Vertical Pipe Support VT-3 RR-2 - - -

CC N-491-1 BFSK-1045 F-A F1.30a Rod Hanger VT-3 RR-2 - - - CC N-491-1 BFSK-854 F-A F1.30b Box Restraint VT-3 RR-2 - - - CC N-491-1 i

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FILE: CRVC03.70.WPD Page 70 - 6 of 70-6

JAMES A. FITZPATRICK JAF lSI-0003 i NUCLEAR POWER PLANT

> NewVorkPower 4er Authority G THIRD INSERVICE INSPECTION INTERVAL Rev.

Date: January 7,1998 O

TEN. YEAR INSERVICE INSPECTION PLAN Page 22 of 35 ;

7.0 AUGMENTED INSERVICE INSPECTION PLAN TABLES This section contains the Long Term Ten-Year Inservice Inspection Examination Tables for nondestructi/e ex9minations of Augmented Examinations of selected systems and components for the Third inservice Inspection Interval Note: NYPA Lans on utilizing, where applicable, Augmented Examination results to satisfy the requirements of the ASME Code,Section XI.

01 Reactor Pressure Vessel Examinations . . . . 7-1 thru 7-1 Augmented IGSCC Examinations . 7-2 thru 716 IGSCC Category A Wolos 7 2 thru 7 3 IGSCC Category A-1 Welds . . 7 3 thru 7-8 IGSCC Category A" Welds 7-9 thru 7-9 O IGSCC Category B Welds . 7 9 thru 7-9 IGSCC Category C Welds 7 9 thru 7 9 IGSCC Category C-2 Welds . 7-9 thru 712 IGSCC Category C" Welds 7-12 thru 7-12 IGSCC Category C-3 Welds . . . 7-12 thru 712 IGSCC Category D Welds . 712 thru 7-14 IGSCC Category E Welds . 7-14 thru 716 IGSCC Category F Welds . . 7-16 thru 7-16 IGSCC Category G Welds 7-16 thru 7-16 29/34 Main Steam and Feedwater Augmented Examinations 7-17_thru 7-19 01 NUREG 0619 Feedwater and Control Rod Drive Examinations 7-20 thru 7 20 01 in-Vessel Visual Augmented Examinations . . . 7 21 thru 7-22 14 Core Spray Augmented Examinations 7-23 thru 7-24 File: jafisipt.wpd

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Jamesh itzpatrick Nuclear Power Plant JAC-ISI-0003 4 IE88'MM Third Inservice inspection Interval Date January 7,1998 Augmented Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICM REMARMS Augmented Reactor Pressure Vessel Examinations Examinations are performed in accordance with the ASME Code.Section XI and the additional regurements of Regulatory Guide 1.150. Rev.1.

The change in the regulation effected the Second Ten-Year Inservice inspechon Interval. NYPA recente appromi from the USNRC to defer the esse %aDy 100% volumetnc examnation till the first refueling outage, of the first inspection period. of the third inspection interval. As required by 1v CFR 50.55a(a)(g)(6)(ii)(A). NYPA shall augn'-mt the reactor vessel examination by 6.pim na aa g once, as part of the inservice inspection interval in effect on September 8.1992, the examinat> requirements for reactor vessel sher welds specified in Examination item 81.10 of Examination Category B-A," Pressure Retaining weldt h Reactor Vessel."in Table IWB-2500-1 of Subsection IWB of the 1989 Edtbon of Sechon XL Drawing Number: MSK-3036, Line No. 02V-1 Shell Welds VC-1-2 B-A B1.11 ShellCircumferentialWold Vol X- - -

- 730" 100% of weld leng h VC-2-3 B-A B1.11 ShellCirrumferentialWeld Vol X- - - - 7" 0" 100% of weld length VC-3-4 B-A B1.11 ShellCircumferentialWeld Vol X- - - - 730" 100% of we'd lengt*:

VC-A-BH-l B-A B1.11 Shell Cwcur iferential Weld Vd X- - - - 714* 100% of weld leng'h W-1A B-A B1.12 SheG Longdudinal Weld Vol X- - - - 150" 100% of weld length W -1B B-A B1.12 Sher Longrtudinal Weld Vol X- - -

- 150" 100% of weld length W-1C B-A U1.12 Shell Longitudinal Weld Vol X- - -

- 150" 100% of weld length W-2A B-A 81.12 Shell Longitudinal Weld Vol X- - -

- 150" 100% of weld Ierxf.

W-28 B-A B1.12 Shen LongitudinalWeld Vol X- - -

- 150" 100% r% eld length W-2C B-A B1.12 Shen Longitudinal Weld Vol X- - -

- 150" 100% of we!11er=;::.

W-3A B-A B1.12 Sher Long4udinal Weld Vol X- - -

- 150" 100% of weld sength W-3B B-A B1.12 Shell Longitudinal Weld Vol X- - -

- 150" 100% of weldlength W-3C B-A B1.12 Sher Longitudinal Weld Vol X- - - - 150" 100% of weld length W-4A B-A B1.12 Sher Longitudinal Weld Vol X- - - - 150" 100% of weld length W -4B B-A B1.12 Shell Longitudinal Weld Vol X- - -

- 150* 100% of weld length W-4C B-A C1.12 Shell Longdudstal Weld Vol X- - -

- 150* 100% of weld length All augmented examinations wiu be performed dunng the First outage, of the First penod, of the Third inspection interval. Cred t will te taki i for these examinations to satisfy the Section XI 1989 Edition .equirementa for the Third Inspection Interval.

FILE JAFAUG.TXT.WPD Page 7 - 1 of 7 -24

James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] g f Power Third Inservice Inspection Interval Augmented Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCPIPTION EXAtr REO PER1 PER2 PER3 THfCK REMARKS i

Augmented IGSCC Examinations The James A. Fitzpatrick Tectnca' Speoficatons, Sect:en 4.65.3, requires the NYPA to implement an augmented inspechon program for those welds desegnated as IGSCC susceptible. The requirements for an augmented IGSCC inspecton program are mandated by Genene Letter GL 88-01. GL 88-01 SWe ced 1. *1ntergranular Stress Cerrosen Crackirg in BWR Austenitic Stainless Steel' 7 and NUREG-0313, Reymon 2, *Tectncal Report on Matenal Selechen and Prvc.cs> g Gudennes for BWR Cookrit Pressure Bourdary Piping."

IGSCC "A - A 25% sample of welds shall be examined during this inspection interval T 02-2 Reactor Reorcu!ation System Drawing Number. MSK-3001. Line No. 28 -WRGE-2A 28-02-2-32 B4 B9.314.0" Branch Connection VoUSurf -- - -

- .33T IGSCC A 4-02-2-47C B4 B9 314.5" Branch Connecten VoUSurf X- - -

- .33T IGSCC A, Capped 23-02-2-36 B-J B9.314.0" Branch Connect on vouSurf -- - - -

IGSCC A C-07-2-38C B-J 89.314.5" Branch Conr ecbon VoVSurf -- X - - .33T IGSCC A Capped Drawing Number MSK-3002, Line No. 28~-VM-GE-2B 28-02-2-90 B4 B9.314.0" Branch Connechon VouSurf -- - -

- .33T IGSCC A 4-02-2-93C B-J 89.314.0" Branch Connection VoVSurf -- - X - .337" IGSCC A, Capped 28-02-2-103 B4 B9.314.0" Branch Cw +.Insi VoVSurf IGSCC A C-02-2-102C B-J B9 31 4.0" Branch Connection VoVSurf -- - -

- .33T IGSCC A Capped 10 Residual He.4 Removal System, Drawing Number MSK-3011. Line No. 20"-W20-1504-42 20-10-117 B-F B5.130 Pipe-Eloow VouSurf -- -

X - 1.03- IGSCC A 14 Core Spray System. Drawmg Numtw. MSK-3022, Line No.10~-W23-902-5A 10-14-481 B-F B5.130 Pipe-?ipe VoUSurf X- - - -

.594' IGSCC A,Dissmiarmetalweld 10-14-480 B-J 89.11 Elbow-Pipe VoVSurf X- - - -

.594* IGSGC A 10-14-477 B-J 89.11 Pipe-Elbow VoVSurf --

X - -

.594* IGSCC A 10-14-476 B-J 89.11 ElbowPq:e VoVSurf -- X - -

.594* IGSCC A 10-14-475 B-J B9.1: Erbow-Elbow YouSu.1 -- - X - .594* 'GSCC A 10-14-474 B-J 89.11 Pipe-Elbow VoVSurf -- - - -

.594* IGSCC A 10-14-473 B4 89.11 Elbow-Prpe VoVSurf -- - - -

.594* IGSCC A 10-14-472 B-J 89.11 Pipe-Elbow VoLSaf -- - A - .594* IGSCC A 10-14-471 B4 B9.11 Pipe-Safe End VoVSurf X- - - -

.594' IGSCC A TerminalEnd FILE JAFAUG.TXT.WPD Page 7 - 2 of 7 -24

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James A. Fi%atrk.k Nuclear Power Plant

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J.4r s.53-0003 A New%rkPemr Third inservice inspection Interval Date January 7,1998 Augmented Inspection Plan Revision O COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS Drawing Numbec MS53023. Line No.10*-W23-902-5B 12-14-502A B-J 89.11 Pipe-Va!ve CSP-14B Vol/ Surf -- - - -

.594* IGSCC A 10-14-494 B-F B5.130 Elbow-Pipe Vol/ Surf X- - - - .594* 13 SCC A. Dissm!ar Metal We:d 10-144 93 B-J 89.11 Pne-Elbow Vol/5urf -- -

X - .594* IGSCC A 10-14-492 B-J 89.11 Pipe-Pipe Vol/ Surf -- -

X - .594* VGSCC A. Terminal End N-58-SE B-F B5.10 Nozzle-Pipe VoVSurf -- -

X - .594* IGSCC A IGSCC *A-1"-Identifies longitudinal seam welds, (41) required. This sample includes only those longitudinal seam wc'ds that intersect a circumferential weld.

02-2 Reactor Recrculation System. Drawing Numbet MSK-3001. Line No.12*-WH-GE-4A from nozzle N2A 12-02-2-1-LS1 B-J 89.12 Pipe long Seam Vol/ Surf X- - -

- .54T IGSCC A-1.CC N5;24 12-02-2-2-LS2 B-J 89.12 Pipe Long Seam Vot/ Surf -- - -

- .54T IGSCC A-1. CC N-524 12-02-2-2-LS1 B-J 89.12 Elbow Long seam Vol/ Surf -- - -

- .54T IGSCC A-1. CC N-524 12-02-2-3-LS2 B-J 89.12 Elbow Long seam Vol/ Surf -- - - - .54T IGSCC A-1.CC N-524 12-02-2-3-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf -- - - -

.547* IGSCC A-1. CC N-E24 12-02-2-4-LS1 B-J B9.12 Pipe Long seam Vol/ Surf -- - -

- .54T IGSCC A-1. CC N-524 Drawing Numbec MSK-3001. Line No.12*-VkH-GE-SA from nozzle N2t' 12-02-2-7-LS1 B.J 89.12 Pipe Long Seam WISurf -X - -

- .54T IGSCC A-1.CC N-524 12-02-2-8-LS2 B-J 89.12 Pipe Long Seam VC%f -- - - -

.547* IGSCC A-1. CC N-524 12-02-2-8-LS1 B-J 89.12 Elbow Long Seam Vol/Sud -- - -

- .54T IGSCC A-1. CC N-524 12-02-2-9-LS2 B-J B9.12 Elbow Long Seam Vol/ Surf -- - -

- .54T IGSCC A-1. CC N-524 12-02-2-9-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf -- - -

- .54T IGSCC A-1. CC N-524 12-02-2-10-LS1 B-J 89.12 Pipe Long seam Vol/ Surf -- - -

- .54T IGSCC A-1. CC N-524 Drawing Numbec MSK-3001. Line No.12*-VtH-GE-6A from nozzle N2C 12-02-2-23-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf --

X - -

.547* IGSCC A-1. CC N-524 12-02-2-24-LS2 B-J 89.12 Pipe Long Seam Vol/ Surf -- - -

- .54T IGSCC A-1. CC N-524 12-02-2-24-LS1 BJ 89.12 Elbow Lorv Seam Vol/ Surf -- - - - .54T IGSCC A-1. CC N-524 12-02-2-25-LS2 B-J 89.12 E! bow Long Seam Vol/ Surf -- - - - .54T IGSCC A-1. CC N-524 12-02-2-25-LS1 B,J 89.12 Pipe Long Seam Vol/ Surf -- - -

- .54T IGSCC A-1.CC N-524 12 ?-2-26-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf -- - - -

.547" IGSCC A-1. CC N-524 Drawirs Numbec MSK-3001. Line No. 28*-VkH-GE-2A 28-02-2 '-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf -- - - - 1.36" IGSCC A-1. CC N-524 28-02-2-33-LS1 B-J 89.12 Elbow Long Seam Vol/ Surf -- - - -

1.36" IGSCC A-1. CC N-524 28-02-2-33-LS2 B-J 89.12 Elbow Long Seam VoGurf -- - - -

1.36" IGSCC A-1. CC N-524 28-02-2-33-LS3 B-J 89.12 Pipe Long Seam Vol/ Surf -- - -

1.36" 3GSCC A-1. CC N-524 28-02-2-34-LS1 B-J B9.12 Elbow Long Seam Vol/ Surf -- - - -

1.36* IGSCC A-1. CC N-524 FILE: JAFAUG.TXT.WPD Page 7 - 3 of 7 -24 L

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James A. Fitzpatrick Nuclear Power Plant h

$ Third Inservice Inspection Interval Augmented Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE - CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK REMARKS 28-02-2-34-LS2 B-J 89.12 Elbow Long Seam Vol/ Surf -- - - -

1.36* IGSbC A-1. CC N-524 28-02-2-35-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf -- X - - 1.36* IGSCC A-1.CC N-524 28-02-2-37-LS1 B-J 89.12 Pipe Long Seam Vol/Su f X- - -

1.36* IGSCC A-1. CC N-524 Drawing Number- MSK-3001, Line No 12*-WH-GE-7A from nozzle N2D 12-02-2-12-LS1 B-J 89.12 Pipe Long Seam VeiSurf --

- .54T IGSCC A-1, CC N-524 12-02-2-13-LS1 B-J 89.12 Elbow Long Seam VA/ Surf --

- .54T IGSCC A-1, CC N-524 12-02-2-13-LS2 B-J 89.12 Pipe Long Seam '/ol/ Surf -- - - - 54T IGSCC A-1, CC N-524 12-02-2-14-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf -- - -

- .54T IGSCC A-1. CC N-524 12-02-2-14-LS2 B-J 89.12 Elbow long Seam Vol/ Surf -- - -

- .54T IGSCC A-1 CC N-524 12-02-2-15-LS1 B-J B9.12 Pipe Long Seam Vol/Suri -- - -

- .54T IGSCC A-1 CC N-524 Drawing Number: MSK-3001, Line No.12* "VH-GE-8A from nozzle N2E 12-02-2-17-LS1 B-J B9.12 Pipe Long Seam Vol/ Surf X- - -

- .54T IGSCC A-1, CC N-52<

12-02-2-18-LS1 BJ 89.12 Elbow Long Seam Vol/ Surf -- - - -

.54" IGSCC A-1 CC N-524 12-02-2-18-LS2 B-J 89.12 Pipe Long Seam Vol/ Surf -- - -

- .54T IGSCC A-1, CC N-524 12-02-2-19-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf -- - -

- .54T IGSCC A-1 CC M24 12-02-2-19-LS2 B-J 89.12 Elbow Long Seam Vol/ Surf -- - -

- .54T IGSCC A-1. CC N-524 12-02-2-20-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf -- - -

- .54T IGSCC A-1 CC N-524 Drawing Number- MSK-3001. Line No. 22*-WH-GE-3A 22-02-2-22-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf -- - -

- .993* IGSCC A-1, CC N-524 22-02-2-21-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf -- - - -

.993* IGSCC A-1, CC N-524 22-02-2-16-LS1 0-J 89.12 Pipe Long Seam Vol/ Surf -- - -

- .993* IGSCC A-1, CC N-524 22-02-2-16-LS2 B-J 89.12 Pipe Long Seam Vol/ Surf -- - - -

.993* IGSCC A-1, CC N-524 22-02-2-28-LS1 B-J 89.12 Pipe Loreg Seem Vol/ Surf X- - - -

.933' IGSCC A-1.CC N-524 22-02-2-29-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf -- - - -

.933" IGSCC A-1, CC N-524 22-02-2-11-LS1 B-J B9.12 Pipe Long Seam Vot/ Surf -- - - - .933* IGSCC A-1 CC N-524 22-02-2-11-LS2 B-J B9.12 Pipe Long Seam Vol/ Surf -- - - -

.933* IGSCC A-1, CC N-524 l

' 22-02-2-6-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf -- - - -

.993* tGSCC A-1 CC N-524 22-02-2-6-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf -- - - - .993* IGSCC A-1,CC N-524 22-02-2-5-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf -- - - -

.993* IGSCC A-1,CC N-524 l

l l

FILE: JAFAUG.TXT.WPD Page 7 - 4 of 7 - 24

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$ Augmented inspection Plan Revision 0 COMPONENT ASME ASME At.2E WELD IDENTIFICATION CODE CODE COD 2 REL ISI INTERVAL LTH OR CAT ITEM DESCRfPTION EXAM REQ PER1 PER2 PER3 THtCK REMARMS Drawing Number MSK-3001, the No. 28*-WH-GE-1A from nozzle N1B 28-02-2-48-LS1 B4 159.12 Pipe Long Seam Vol/ Surf X- - - - 1.23* IGSCC A-1 CC N-524 28-02-2-49-LS1 B4 B9.12 Pipe Long Seam Vol/ Surf -- X - - 1.23" IGSCC A-1, CC r4-52#

28-02-2-49-LS2 84 89.12 Elbow Long Seam Vol/ Surf -- X - - 1.23' IGSCC A-1, CC N-524 28-02-2-49-LS3 B-J 89.12 Elbow Lung Seam Vol/ Surf --

X - - 123* IGSCC A-1.CC N-524 28-02-2-50-LS1 B4 89.12 Elbow Long Seam Vol/ Surf -- - -

X 1.23' IGSCC A-1. CC N-524 28-02-2-50-LS2 B-J 89.12 Elbow Long Seam Vol/ Surf -- - - X 123" IGSCC A-1, CC N-524 28-02-2-50-LS3 B-J 89.12 Pipe Long Seam Vol/ Surf -- - -

X 1.23* IGSCC A-1. CC N-524 28-02-2-51-LS1 B4 89.12 Pipe Long S am Vol/ Surf -- - - -

1.23* IGSCC A-1 CC N-524 28-02-2-51-LS2 B-J 89.12 Pipe Long Seam Vot/Sur' -- - - - 123" IGSCC A-1 CC N-524 28-02-2-50A-LS1 B-J 89.12 Pipo Long Seam Vol/ Surf -- - - -

1.23" IGSCC A-1,CC N-524 28-02-2-50A-LS2 B4 B9.12 Pipe Long Seam Vol/ Surf -- - - -

1.23* IGSCC A-1 CC N-524 28-02-2-52-LS1 B4 89.12 Pipe Long Seam Vol/ Surf -- - - - 1.23" IGSCC A-1 CC N-524 28-02-2-52-LS2 B4 89.12 Elbow Long Seam Vol/ Surf -- - -

- 123" IGSCC A-1 CC N-524 28-02-2-52-LS3 B-J 89.12 Elbow Long Seam Vol/ Surf -- - -

- 123* IGSCC A-1.CC N-524 28-02-2-53-LS1 B4 B9.12 Elbow Long Seam Vol/ Surf -- - -

- 123' IGSCC A-1, CC N-524 28-02-2-53-LS2 B-J 89.12 Elbow Long Seam Vol/ Surf -- - - - 1.23* IGSCC A-1, CC N-524 28-02-2-54-LS1 B4 B9.12 Pipe Long Seam Vot/ Surf -- - - -

1.23' IGSCC A-1,CC N-524 28-O"'-2-56-LS1 B4 89.12 Elbow Long Seam Vol/ Surf - - - - - - 1.23* IGSCC A-1 CC N-524 28-02-2-56-LS2 B-J 89.12 Elbow Long Seam Vot/ Surf -- - -

- 123* IGSCC A-1 CC N-524 28-02-2-56-LS3 B-J 89.12 Elbow Long Seam Vot/ Surf -- - -

- 123* IGSCC A-1 CC N-524 28-02-2-57-LS1 B-J 89.12 Elbow Long Seam Vol/ Surf -- - - - t 23" IGSCC A-1, CC N-514 28-02-2-57-LS2 B4 B9.12 Elbaw Long Seam Vol/ Surf -- - - -

1.23* IGSCC A-1.CC N-524 Drawing Number- MSK-3002 Line No.12*-W*+GE-8B from nozzle N2K 12-02-2-75-LS1 B-J 89.12 Pipe long Seam Vol/ Surf X- - -

- .54T IGSCC A-1, Go N-524 12-02-2-76-LS1 B4 89.12 Elbow Long seam Vol/ Surf -- - -

- .54T IGSCC A-1, CC N-524 12-02-2-76-LS2 B-J g 89.12 Pipe Long Seam Vol/ Surf -- - -

- .54T IGSCC A-1, CC N-524 12-02-2-77-LS1 B4 89.12 Elbow Long Seam Vol/ Surf -- - -

- .54T IGSCC A-1. CC N-524 12-02-2-77-LS2 B-J 89.12 Pipe Long seam Vol/ Surf -- - -

- .54T IGSCC A-1. CC N-524 12-02-2-78-LS1 B-J 89.12 Pipe Long seam Vol/ Surf -- - - -

.547* IGSCC A-1. CC N-524 FILE JAFAUG.TXT.WPD Page 7 - 5 of 7-24

James Fitzpatrict Nuclear Power Plant [[::JAF-4SI-0003|JAF-4SI-0003]] ^

h

$ Third Inservice inspection Interval Augmented Inspection Plan Date January 7,1998 Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL t TH OR CAT ITEM DESCRIFFION EXAM REQ PER1 PER2 PER3 THICK REMARKS t

Drawing Number- MSK-3002, Line No.12"-VM-GE-7B from nozzle N2J 12-02-2-69-LS1 B-J E9.12 Pipe Long Seam Vol/ Surf -- -

X - 54T IGSCC A-1. CC N-524 12-02-2-70-LS1 B-J B9.12 Elbow Long Seam VoVSurf -- - -

54T IGSf'C A-1, CC N-524 12-02-2-70-LS2 BJ 69.12 Pipe Long Seam Vot/ Surf -- - -

- .54T IGSCC A-1. CC N-524 12-02-2-71-LS1 B-J B9.12 Pipe Long Seam Vot/ Surf -- - -

- .54T IGSCC A-1.CC N-524 12-02-2-71-LS2 B-J 89.12 Elbow Long Seam Vol/ Surf -- - -

- .54T IGSCC A 1, CC N-524 12-02-2-72-LS1 B-J 89.12 Pipe Long seam Vol/ Surf -- - - - 54 7 IGSCC A-1, CC N-524 Drawing Number- MSK ";302, Line No.12"-WH-GE-6B from r.czzle N2H 12-02-2-81-LS1 B-J B9.12 Pipe Long Seam Vol/ Surf X- - -

- .54T IGSCC A-1, CC N-524

'2-02-2-82-LS1 B-J 89.12 Elbow Long Seam Vol/ Surf -- - -

- .54T IGSCC A-1.CC N-524 12-02-N-LS2 B-J 89.12 Pipe Long Seam Vol/ Surf -- - - - 54T IGSCC A-1 CC N-524 12-02-2-oJ-LS1 8-J 89.12 Pipe Long Seam Vot/ Surf -- - -

- 54T IGSCC A-1.CC N-524 12-02-2-83-LS2 B-J B9.12 Elbow Long Seam Vol/Snr1 -- - -

- .54T IGSCC A-1, CC N-524 12-02-2-84-LS1 B4 89.12 Pipe Long Seam Vol/Eurf -- - -

- .54 7 IGSCC A-1, CC N-524 Drawir > rMr- MSK-3002, Line No. 28~-VM-GE-2B 28-02 31 B-J 89.12 Pipe Long Seam Vot/ Surf -- - - -

1.36" IGSCC A-1.CC N-524 28-02-2-9.-cS t B-J 89.12 Pipe Long Seam Vol/ Surf -- - - -

1.36- IGSCC A-1, CC N-524 28-02-2-91-LS2 B-J 89.12 Elbow Long Seam Vol/ Surf -- - - - 1.36- IGSCC A-1, CC N-524 28-02-2-91-LS3 B-J 89.12 Elbow Long Seam Vol/ Surf -- - - -

1.36* IGSCC A-1. CC N-524 28-02-2-92-LS1 B-J 89.12 Elbow Long Seam Vol/ Surf -- - - -

1.36" IGSCC A-1, CC N-524 28-02-2-92-LS2 B-J 89.12 Elbow Long Seam Vol/ Surf -- - - -

1.36" IGSCC A-1, CC N-524 28-02-2-104-LS1 B-J 89.12 Pipe Long Seam Vot/ Surf -- - - -

1.36' IGSCC A-1, CC N-524 28-02-2-105-LS1 B-J B9.12 Pipe Long Seam Vol/ Surf X- - - - 1.36" IGSCC A-1, CC N-524 Drawing Number: MSK-3002 Line No.12*-WH-GE-58 from nozzle N2G ,

12-02-2-64-LS1 B-J 89.12 Pipe Long Seam Vol/ Surf -- - -

X .54T IGSCC A-1 CC N-524 12-02-2-65-LS1 B-J 89.12 Elbow Long Seam Vol/ Surf -- - -

- .54T IGSCC A-1 CC N-524 12-02-2-65-LS2 B-J B9.12 Pipe Long Seam Vol/ Surf -- - -

- .54T IGSCC A-1, CC N-524 12-02-2-66-LS1 B-J B9.12 Pipe Long Seam Vol/ Surf -- - -

- .54T IGSCC A-1, CC N-524 12-02-2-66-LS2 B-J B9.12 E! bow long Seam Vot/ Surf -- - -

- .54T IGSCC A-1,CC N-524 12-02-2-67-LS1 B-J B9.12 Pipe Long Seam Vol/Surt -- - -

- .54T IGSCC A-1. CC N-524 FILE: JAFAUG.TXT.WPD Page 7 - 6 of 7 -24

O; V

b'O James Fitzpatrick Nuclear Power Plant [[::JAF-IS3-0003|JAF-IS3-0003]] Date January 7,1998 h Third Inservice inspection Interval

$ Augmented Inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME IS: INTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE REO PER1 PER2 PER3 THfCK REMARKS CAT ITEM DESCRfPTION EXAM B Drawing Number MSK-3002, Line No.12*-WH-GE-4B from nozzle N2F IGSCC A-1, CC N-524 89.12 Pipe Long Seam VouSurf -- - X - .54T 12-02-2-58-LS1 B-J - .54T IGSCC A-1. CC N-524 BJ 89.12 Elbow Long Seam VouSurf - - -

12-02-2-59-LS1 - .54T IGSCC A-1, CC N-624 B-J 89.12 Pipe Long Seam VoVSurf -- - -

12-02-2-59-LS2 - .54T IGSCC A-1 CC N-524 B-J 89.12 Pipe Long Seam VoVSurf -- - -

12-02-2-60-LS1 - .54T IGSCC A-1, CC N-524 B-J 89,12 Elbow Long Seam Vol/ Surf -- - -

12-02-2-60-LS2 - .54T IGSCC A-1. CC N 524 B-J 89.12 Pipe Long Seam VoFSurf -- - -

12-02-2-61-LS1 Drawing Number MSK-3002, Line No. 22*-Vai-GE-38 - - .993* IGSCC A-1, CC N-524 B-J 89.12 Pipe Long Seam VoVSurf -- -

22-02-2-63-LS1 - 993* IGSCC A-1 CC N-524 B-J B9.12 Pipe Long Seam VoUSurf -- - -

22-02-2-62-LS1 .993* IGSCC A-1. CC N-524 B-J B9.12 Pipe Long Seam VoVSurf -- - - -

22-02-2-68-LS1 X - - .993* IGSCC A-1, CC N-524 B-J 89.12 Pipe Long Seam Vol/ Surf --

22-02-2-68-LS2 X - .933" IGSCC A-1 CC N-524 VoVSurf 22-02-2-86-LS1 B-J 89.12 Pipe Long Seam IGSCC A-1, CC N-52A B9.12 Pipe Long Seam VoVSurf -- - - - .933' 22-02-2-87-LS1 B-J - .933* IGSCC A-1, CC N-524 B-J 89.12 Pipe Long Seam VoVSurf -- - -

22-02-2-73-LS1 .933" IGSCC A-1, CC N-524 B-J B9.12 Pipe Long Seam VouSurf -- - - -

22-02-2-73-LS2 .993* IGSCC A-1. CC N-524 B-J B9.12 Pipe Long Seam VouSurf -- - - -

22-02-2-79-LS1 - .993* IGSCC A-1, CC N-524 B-J 09.12 Pipe Long Seam VoVSurf -- - -

22-02-2-80-LS1 Drawing Number: MSK-3002, Line No. 28*-VA4-GE-18 from nozzle N1 A 1.23* IGSCC A-1 CC N-524 89.12 Pipe Long Seam VoVSurf -- X - -

28-02-2-106-LS1 B-J 1.23* IGOOC A-1, CC N-524 B-J 89.12 Pipe Long Seam VoUSurf X- - - -

28-02-2-107-LS1 X- - 123" IGSCC A-1, CC N-524 B-J 89.12 Elbow Long Seam VouSurf - -

28-02-2-107-LS2 - 1.37 GSCC A-1 CC N-524 1 B-J 89.12 Elbow Long Seam VoVSurf -- - -

28-02-2-107-LS3 - 127 IGSCC A-1, CC N-524 B-J 89.12 Elbow Long Seam VouSurf -- - -

28-02-2-108-LS1 1' IGSGC A-1 CC N-524 B-J O.12 Elbow Long Seam VoVSurf -- - - -

28-02-2-108-LS2 .S ISCC A-1, CC N-524 B-J 89.12 Pipe Long Seam Vot/ Surf -- - -

28-02-2-108-LS3 X - 1.23" eGSCC A-1, CC N-524 Vof/ Surf l 28-02 109-LS1 B-J 89.12 Pipe Long Seam IGSCC A-1, CC N-524 VoVSurf -- - - -

1.23*

28-02-2-110-LS1 B-J B9.12 Pipe Long Seam IGSCC A-1, CC N-524 89.12 Pipe Long Seam Vol/ Surf -- - - -

1.23" 28-02-2-110A-LS1 B-J - 123* IGSCC A-1, CC N-524 89.12 Pipe Long Seam VoVSurf -- - -

28-02-2-110A-LS2 B-J 1.36* IGSCC A-1, CC N-524 ;

B-J 89.12 Pipe Long Seam VoUSurf - - - -

28-02-2-111-LS1 -

1.36' IGSCC A-1, CC N-524 )

B-J B9.12 Elbow Long Seam Vol/ Surf -- - -

28-02-2-111-LS2 1.36" IGSCC A-1, CC N-524 B-J 89.12 Elbow Long Seam VoVSurf -- - - -

28-02-2-111-LS3 - 123" IGSCC A-1, CC N-524 i B-J 89.12 Elbow Long Seam Vousurf -- - -

28-02-2-112-LS' - 1 23* IGSCC A-1, CC N-524 ,

B-J B9.12 Elbow Long Seam VoVSurf -- - -

28-02-2-112-LS2 1.23* IGSCC A-1, CC N-524 l l B-J 89.12 Pipe Long Seam Vol/ Surf -- - - -

28-02-2-113-LS1 Page 7 - 7 of 7 - 24 )

FILE: JArAUG TXT.WPD

O O James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] O

Third inservice Inspection Interval Date January 7,1998 h

$ Augmented Inspection Plan Revision O ASME WELD COMPONENT ASME ASME REL ISIINTERVAL LTH OR CODE CODE CODE REMARKS IDENTIFICATION DESCRIPTION EXAM REQ PER1 PER2 PER3 THICK CAT ITEM Vol/ Surf -- - - - 1.23* IGSCC A-1. CC N-524 28-02-2-115-LS1 B-J 89.12 Pipe Long Seam IGSCC A-1.CC N-524 89.12 Elbow Long Seam VouSurf -- - X - 1 23" 28-02-2-115-LS2 B-J - X - 1.23" IGSCC A-1. CC N-524 B9.12 Elbow Long Seam Vol/ Surf --

28-02-2-115-LS3 B4 X - 1.23* IGSCC A-1. CC N-524 89.12 Elbow Long Seam Vol/ Surf -- -

28-02-2-116-LS1 84 X - 1 23" IGSCC A-1. CC N-524 89.12 Elbow Long Seam Vol/ Surf -- -

28-02-2-116-LS2 B-J 14 Core Spray Syster L Drawing Number MSK-3022. Line No.10*-W23-902-5A .594* IGSCC A-1.CC N-524 E9.12 Pipe-Long Seam Vo!/ Surf X- - - -

10-14-480-LS1 B-J .594* IGSCC A-1. CC N-524 89.12 Elbow-Long Seam Vol/ Surf X- - - -

10-14-480-LS2 B4 X- - -

.594* IGSCC A-1. CC N-524 B4 89.12 Elbow-Lorig Seam VouSurf -

10-14-480-LS3 X - -

.594* IGSCC A-1. CC N-524 B4 89.12 Elbow-Long Seam Vol/ Surf --

10-14 477-LS1 X - -

.594* IGSCC A-1.CC N-524 84 B9.12 Elbow-Long Seam Vol/ Surf -

10-14-477-LS2 X - - r 4" IGSCC A-1. CC N-524 B4 B9.12 Pipe-Long Seam Vol/ Surf --

10-14-477-LS3 X - -

.594* IGSCC A-1. CC N-524 89.12 Pipe-Long Seam Vol/ Surf -

10-14-476-LS1 B4 X - -

.594* IGSCC A-1. CC N-524 B-J 89.12 Elbow-Long Seam Vol/ Surf -

10-14-476-LS2 X - -

.594* IGSCC A-1. CC N-524 89.12 Elbow-Long Seam Vol/ Surf -

10-14-476-LS3 B-J X - .594* IGSCC A-1. CC N-524 B-J 89.12 Elbow-Long Seam VouSurf - -

10-14-475-LS1 X - .594* IGSCC A-1. CC N-524 B4 89.12 Elbow-Long Seam VoVSurf - -

10-14-475-LS2 X - .594* IGSCC A-1. CC N-524 B-J B9.12 Elbow-Long Seam VouSurf - -

10-14-475-LS3 X - .594* IGSCC A-1.CC N-524 89.12 Elbow-tong Seam Vol/ Surf - -

10-14-475-LS4 B-J .594* iGSCC A-1, CC N-524 B-J 89.11 Elbcw-Long Seam VouSurf - - - -

10-14-474-1.S1 - .594* IGSCC A-1. CC N-524 B-J 89.11 E! bow-Long Seam Vol/ Surf - - -

10-14 474-LS2 VoVSurf - - - -

.594* IGSCC A-1. CC N-524 10-14 474-LS3 B-J B9.11 Pipe-Long Seam Vol/ Surf - - - - .594* IGSCC A-1. CC N-524 10-1/-473-LS1 B4 89.12 Pipe-Long Seam VoUSurf -- - - -

.594* IGSCC A-1. CC N-524 10-14-473-LS2 B4 89.12 Elbow-Long Seam VoVSurf - - - -

.594* IGSCC A-1.CC N-524 10-14-473-LS3 B-J 89.12 Elbow-tong Seam Voi/ Surf -- - - - .594* IGSQC A-1.CC N-524 10-14-472-LS1 B-J 89.12 Elbow-Long Seam Vol/ Surf - - - - .59r GSCC A-1. CC N-524 10-14-472-LS2 B-J B9.12 Elbow-Long Seam VouSurf X- - - - J n- IG'EC A-1. CC N-524 10-14-472-LS3 B-J 89.12 Pipe-Long Seam IGSOC A *, CC N-524 VouSurf X- - - - J 94*

10-14-471-LS1 B-J 89.12 Pipe-Long Seam Page 7 - 8 of 7 -24 FILE: JAFAUG.TXT.WPD

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] 4 MM_h Third inservice Inspection Interval Date January 7,1998 Augmented Inspection Plan Revision 0 COMPONENT ASME ASME ASME VELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PERT PER2 PER3 THICK REMARKS 9

IGSCC *A"-Identifies sweep-o-let welds that have been solution annealed.

02-2 Reactor Recirculation System. Drawing Numbec MSK-3001. Line No. 22*-WH-GE-3A 22-02-2-21 B-J 89.31 12.0" Branch Connection Vol/ Surf -- - - -

IGSCC A-22-02-2-16 B-J B9.31 12.0" Branch Connection VoVSurf --

X - - IGSCC A*

22-02-2-11 B-J B9.31 12.0" Branch Cw u im%w. Vol/ Surf IGSCC A*

22-02-2-5 B-J 89.31 12.0" Branch Connection VoVSurf -- - - -

.553* IGSCC A*

Drawing Numbec MSK-3002 Line No. 22*-WH-GE-38 2'.-02-2-62 B-J 89.31 12.0" Branch Conrection Vol/ Surf -- - - -

IGSCC A*

22-02-2-68 B-J 89.31 12.0" Branch Connechon Vol/ Surf -- - - -

IGSCC A*

22-02-2-73 B-J 89.31 12.0" Branch Connecison Vol/ Surf --

X - -

IGSCC A*

22-02-2-79 B-J 89.31 12.0" Branch Connection VoVSurf -- - - -

.553* IGSCC A*

IGSCC *B* - There are no welds in this category IGSCC 'C"- All welds shall be inspected once during this inspection interval.

IGSCC *C-2* -

02-2 Reactor Recirculation System. Drawing Numbec MSK-3001, Line No. 12*-WH-GE-4A from nozzle N2A 12-02-2-2 B-J 89.11 Pipe-Elbow Vol/ Surf -- - -

- .54T IGSCC C-2, once every 10 years 17 2-3 B-J 89.11 Elbow-Pipe Vol/ Surf -- - - -

.547- IGSCC C-2, once every 10 years 12-0. 2-4 B-J 89.31 12.0" Branch Connection VoVSurf X- - - -

.547' IGSCC C-2, once every 10 years Drawing Numbec MSK-3001, Line No.12*-WH-GE-5A from nozzle N2B 12-02-2-7 B-J 89.11 Safe End-Pipe Vol/ Surf -X - - -

.547* IGSGC C-2 once every .0 year t. Terminal End 12-02-2-9 B-J 89.11 Elbow-Pipe Vol/ Surf -- - -

- .54T IGSCC C-2, once every 10 yea 3 12-02-2-10 B-J 89.31 12.0" Branch Connection Vol/ Surf -- - -

- .54T IGSCC C-2, once every 10 yea.s Drawing Numbec MSK-3001. Line No.12*-WH-GE-6A from nozzle N2C 12-02-2-24 B-J 89.11 Pipe-Elbow Vol/ Surf -- - - -

.547- IGSCC C-2.once every 10 years 12-02-2-25 B-J 89.11 Elbow-Pipe Vol/ Surf -- - - -

.547" IGSCC C-2 once every 10 years 12-02-2-26 B-J 89.11 Pipe-Reducer VollSurf -- - -

- .54T IGSCC C-2. Once every 10 years FILE JAFAUG.TXT.WPD Page 7 - 9 of 7 -24

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James A Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] A g@mer Third Inservice inspection Interval Date January 7,1998

-"""' Augmented inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REQ PER1 PER2 PER3 THtCK REMARKS Drawing Nuraber MSK-3001. Line No. 28*-WH-GE-2A 28-02-2-27 B-J 89.11 Reducer-Cross VoVSurf -- - - -

1.36' IGSCC C-2. once every 10 years 28-02-2-30 B-J 89.11 Cross-Tee VoUSurf -- - - -

1.36' IGSCC C-2 once every 10 years 28-02-2-31 B-J 89.11 Tee-Pipe VoUSurf -- - - -

1.36* IGSCC C-2. once every 10 years 28-02-2-34 B-J 89.11 Valve MOV-53A-Elbow VoVSurf -- - - -

1.36' IGSCC C-2. every 10 years 28-02-2-35 B-J 89.11 Valve MOV-53A-Pipe VoVSurf --

X - -

1.36' IGSCC C-2. every 10 years 28-02-2-37 B-J 89.11 Pipe-Pump 02-2-P-1 A VoVSurf X- - - -

1.36" IGSCC C-2, every 10 years Drawing Number MSK-3001. Line No.12"-WH-GE-7A from nozzle N2D 12-02-2-13 B-J B9.11 Pipe-Elbow VoVSurf -- - -

.54T IGSCC C-2. every to years 12-02-2-14 B-J B9.11 Elbow-Pipe VouSurf -- - -

- .54T IGSCC C-2. every 10 years Drawing Number : MSK-3001. Line No.12*-WH-GE-8A from nozzle N2E 12-02-2-17 B-J 89.11 Safe End-Pipe VoUSurf X- - -

- .54T IGSCC C-2. every 10 years. Terminal End 12-02-2-20 B-J 89.31 12.0 Branch Connection VoVSurf -- - -

- .54T IGSCC C-2. every 10 years Drawing Number MSK-3001. Line No. 22*-WH-GE-3A 22-02-2-28 B-J 89.11 Cross-Prpe VovSurf X- - - -

.933" IGSOC C-2. every 10 years 22-02-2-29 B-J 89.11 Cross-Pipe VoVSurf -- - - -

.933" IGSCC C-2. evey 10 years 22-02-2-6 B4 89.11 Pipe-Cap VoVSurf -- - - -

.993* IGSCC C-2. every 10 years Drawing Number MSK-3001. Line No. 28*-WH-GE-1 A from nozzle N1B 28-02-2-49 B4 89.11 Hpe-E! bow VoUSurf --

X - -

1.23* IGSCC C-2 once every 10 years 28-02-2-51 B-J 89.11 Pipe-Pipe VoUSurf -- - - - 1.23" IGSCC C-2 once every "O yeare 28-02-2-50A B-J B9.11 Pipe-Pipe VoUSurf -- - - -

1.23' IGSCC C-2. once every 1Cy een 28-02-2-54 B-J 89.11 Vafve MOV-43A -Pipe VoVSurf -- - - -

1.23* IGSCC C-2. once every 10 ye.*.

28-02-2-55 B-J B9.316.0" Branch Connection VoVSurf -- - - -

1.23' 3GSQC C-2 once every 10 years 28-02-2-56 B-J 89.11 Pipe-Elbow VoUSurf -- - - -

1.23* IGSCC C-2 once every 10 years 28-02-2-57 B-J 89.11 Elbow-Pipe Pump 02-2P-1A Vol/ Surf -- - - -

1.23* IGSCC C-2. once every 10 years Drawing Number. MSK-3002. Line No.12*-WH-GE-8B from nozzle N2K 12-02-2-75 B-J 89.11 Safe End-Pipe Vol/ Surf X- - -

- .54T IGSCC C-2. once every 10 years, terminal End 12-02-2-77 B-J 89.11 Elbow-Pipe VoUSurf -- - -

- .54T IGSCC C-2 once every 10 years 12-02-2-78 B-J E9.31 12.0" Branch Connection VoVSurf -- - -

- .54T IGSCC C-2 once every 10 years FILE: JAFAUG.TXT.WPD Page 7 - 10 of 7 -24

w James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] g New h Third Inservice inspection Interval Date January 7,1998 Augmented Inspection Plan Revision 0 i

COMPONENT ASME ASME ASME W1 ELD IDENTIFICATION CODE CODE COD'd REL ISIINTERVAL LTH OR CAT ITEM DESCRIPTION EXAM REO PER1 PER2 PER3 THICK REMARMS Drawing Number MSK-3002. Line No.12*-WH-GE-78 frorn nozzle N2J 12-02-2 71 B-J 89.11 Elbow-Pipe Vol/ Surf -- - -

- .54T IGSCC C-2. once every 10 years 12-02-2-72 B-J 89.31 12.0" Branch Connection Vot/ Surf -- - - - .547" IGSCC C-2 once every 10 years

! Drawing Numbec MSK-3002. Line No.12" WH-GE-68 from nozzle N2H 12-02-2-81 B-J B9.11 Safe End-Pipe Vol/ Surf X- - -

- .54T IGSCC C-2. onca every 10 years. Term:nal End 12-02-2-82 B-J 89.11 Pipe-Elbow Vol/ Surf -- - -

- .54T IGSCC C-2 once every 10 years 12-02-2-83 B-J 89.11 Elbow-Pipe Vol/ Surf -- - -

- .54T IGSCC C-2. once every 10 years 12-02-2-84 B-J B9.11 Pipe-Reducer Vol/ Surf -- - -

- .54T IGSCC C-2. Once every 10 years Drawing Numbec MSK-3002. Line No. 28*-VM-GE-2B 28-02-2-85 B-J 89.11 Reducer-Crcss Vol/ Surf -- -

X - 1.36* IGSCC C-2. once every 10 years 28-02-2-88 B-J 89.11 Cross-Tee Vc'/ Surf -- - - -

1.36' IGSCC C-2. once every to years 28-02-2-89 B-J 89.11 Tee-Pipe Vol/ Surf -- - - -

1.36" IGSCC C-2. once every 10 years 23-02-2-91 B-J 89.11 Pipe-Elbow Vol/ Surf -- - - -

1.36' IGSCC C-2. once every 10 years 28-02-2-104 B-J 89.11 Valve MOV-53A-Pipe Vol/ Surf -- - - -

1.36' IGSCC C-2. once every 10 years 28-02-2-105 B-J 89.11 Pipe-Pump 02-2-P-1 A Vol/ Surf -- - -

X 1.36' IGSCC C-2 Once every 10 years. Tenrnna! End Drawing Numbec MSK-3002. Line No.12*-VM-GE-50 from nozzle N2G 12-02-2-66 B-J 89.11 Elbow-Pipe Vot/ Surf -- - - -

.547" IGSCC C-2. every 10 years Drawing Numbec MSK-3002. Line No.12" VM-GE-4B from nozzle N2F 12-02-2-59 B-J 89.11 Pipe-Elbow Vol/ Surf -- - - -

.547" IGSCC C-2. ence every 10 yea-1242-2-60 B-J 89.11 Elbow-Pipe Vol/ Surf -- - - -

.547" IGSCC C-2. once every 10 years Drawing Number MSK-3002, Line No. 22*-WH-GE-38 22-02-2-86 B-J B9.11 Cross-Pipe Vo!/ Surf --

X - -

.933' IGSGC C-2. once every 10 years 22-02-2-87 B-J 89.11 Cross-Pipe Vot/ Surf -- - - -

.933" IGSCC C-2. once every 10 years 22-02-2-80 B-J 89.11 Pipe-Cap Vot/ Surf -- - - -

.993* IGSCC C-2. mee every 10 years Drawing Numbec MSK-3002. Line No. 28*-WH-GE-1B from nozzle N1 A 28-02-2-106 B-J 89.11 Safe End-Pipe Vot/ Surf -- X - -

1.23" IGSCC C-2. once every 10 years. Terminal End 28-02-2-107 B-J B9.11 Pipe-Elbow Vot/ Surf X- - - -

1.23* IGSCC C-2. once every 10 years 20-02-2-109 B-J 89.11 Pipe-Tee Vol/ Surf -- -

X - 123* IGSCC C-2. once every to years 28-02-2-110 B-J 89.11 Tee-Pipe Vol/ Surf -- - -

- 1 23" IGSCC C-2. once every 10 years 28-02-2-110A B-J 89.11 Pipe-Pipe Vot/ Surf -- - -

- 123* IGSCC C-2. once every 10 years 28-02-2-111 B-J 89.11 Pipe-Elbow Vol/ Surf -- - -

- 123* IGSCC C-2 once every 10 years 28-02-2-112 B-J 89.11 Elbow-Valve MOV-438 Vol/ Surf -- - -

- 123' IGSCC C-2. once every 10 years FILE: JAFAUG.TXT.WPD Page 7 - 11 of 7-24

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G James A.'.Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] A NwvWower Third Inservice Inspection Interval Date January 7,10**

D Augmented Inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION CODE CODE CODE REL ISI INTERVAL LTH OR CAT TTEM DESCRIPTIOtt EXAM REO PER1 PER2 PER3 THtCK REMARKS 28-02-2-114 B-J 89.314.0" Branch Connedion Vol/ Surf -- - - -

1.23* IGSdC C-2 once every 10 years 28-02-2-115 B-J 89.11 PIPE-Etbew VouSurf -- - - -

1.23* IGSCC C-2. once every 10 years IGSCC t** -

Drawing Numbec MSK-3001. Line No. 28*-%%GE-1 A from nozzle N1B 28-02-2-50 B-J B9.11 Elbow-Pipe VoVSurf -- -

X - 1.23* IGSCC C*. once e,ery 10 years Drawing Numbec MSK-3002. Line No. 28*-%%GE-1B from nozzle N1 A 28-02-2-108 B-J B9.11 Elbow-Pipe VoVSurf -- - - -

1.23" IGSCC C* Under Whip. once every 10 years IGSCC *C-3"- 3 required, During Refueling Outages 1988 and 1990 Drawing Numbec MSK-3002, Line No.12*-WH-GE-5B from nozzle N2G 12-02-2-67 B-J 89.31 12.0" Branch Connechon VoUSurf -- - -

- .54T IGSCC C-3. every 10 years

! Drawing Nur,bec MSK-3002. Line f4 s 12*-VM-GE-48 from nozzle N2F 12-02-2-58 B-J B9.11 Safe End-Pipe VoVSurf -- - -

X .54T IGSCC C-3. once every 10 years. Terrmnal End 12-02-2-61 B-J 89.31 12.0 Branch Conaedion VoVSurf -- - -

- .54T IGSCC C-3, once every 10 years i

100% of all NUREG 0313, Category C welds were inspected. Based on clanfication by the USNRC regarding Extent and Frequency requirements, this category faits under w l

Augmented 1G-Year Inspection Interval, which began in 1992 and is complete in 2002.

IGSCC *D*- All welds shall be examined at least every two refueling outages. Approximately 50% of all Category D welds shall be examined each refueling outage.

Drawing Numbec MSK-3001 Line No.12*-WH-GE-4A from nozzle N2A j N-2A-SE B-F B5.10 Nozzle-Safe End VouSurf X- A - A .54T IGSQC D every 2 refueling outages l

i Drawing Numbec MSK-3001, Line No.12*-VM-GE-5A from nozzle N2B N-28-SE B-F B5.10 Nozzle-Safe End vouSurf X- A - A .54T IGSCC D every 2 refueling outages Drawing Numbec MSK-3001, Line No.12*-VM-GE-GA from nozzle N2C N-2C-SE B-F B5.10 Nozzle-Safe End VoVSurf A- X - A .54T IGSCC D every 2 refueting outages i Drawing Numbec MSK-3001. Line No.12*-WH-GE-7A from nozzle N2D I N-20-SE B-F B5.10 Nozzle-Safe End VoVSurf -A -

X - .54T IGSCC D, eve:y 2 refueling outages FILE: JAFAUG.TXT.WPD Page 7 - 12 of 7-24

I m James . itzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third Inservice inspection Interval Date January 7,1998 g Piim Augmented inspection Plan Revision 0 ASME WELC COMPONENT ASME ASME REL ISI INTERVAL LTH OR CODE CODE REMARKS IDENTIFICATION CODE EXAM REQ PER1 PER2 PER3 THICK CAT ITEM DESCRIPTION Drawing Number- MSK-3001. Line No.12"-WH-GE-8A from nozzie N2E A - A .547" IGSCC D, every 2 refuelmg outage Vol/ Surf X-N-2E-SE Bf B5.10 Nozzle-Safe End Drawing Numbec MSK-3001. Line No. 28"-WH-GE-1 A from nozzle N1B A - A 123" IGSCC D. every 2 refueling outage Vol/ Surf X-N-18-SE B-F B5.10 Nozzle-Safe End Drawing Numbec MSK-3002. Line No.12"-WH-GE-8B from nozzle N2K A - A .54T IGSCC D. every 2 refueting outages VoL' Surf X-N-2K-SE B-F B5.10 Nozzle-Safe End Drawing Numbec MSK-3002. Line No.12"-WH-GE-78 from nozzle N2J -A - X - .54T IGSCC D every 2 refue:mg cutages B5.10 Nozzle-Safe End Vot/ Surf N-2J-SE B-F Drawing Numbec MSK-3002. Line No.12"-WH-GE-6B from nozzle N2H X- A - A .54T IGSCC D every 2 refueling outages B5.10 Nozzle-Safe End VoLGurf N-2H-SE D-F Drawing Number: MSK-3002. Line No.12*-WH-GE-5B from nozzle N2G A- A - X .54T IGSCC D.every 2 refueEng outages B5.10 Nozzle-Safe End Vol/ Surf N-2G-SE B-F Drawing Numbec MSK 3002. Line No.12"-WH-GE-4B from nozzle N2F A- A - X .54T IGSCC D every 2 refueling outage B5.10 Noz-le-Safe End Vot/ Surf N-2F-SE B-F Drawing Numbec MSK-3002. Line No. 28"-WH-GE 18 from nozzle N1A A- X - A 123" IGSCC D. every 2 refuefing outage B5.10 Nozzle-Safe End Vol/ Surf N-1A-SE B-F 03 Control Rod Driva System. Drawmg Numbec MSK-3003. Line No. From RPV A - A IGSCC D. Dissimilar Metal Weld B9.21 Nozzle-Cap Surf X-N-9-C1 B-J ,

Note: This line was cut and capped.

Drawing Numbec MSK-3013. Line No. 24"-W20-902-14A Vol/ Surf X- A - A 1.219 IGSCC D, every 2 refue8mg outages B-F B5.130 Pipe-Valve RHR-81 A - A 1.219 IGSCC D. every 2 refuermg cutages 24-10-130 Vot/ Surf A- X B-F B5.130 Viv RHR-81 A-Viv AOV-68A 24-10-131 Vot/ Surf - A - X- 1.219 IGSCC D. every 2 refueling outages 24-10-132 B-F B5.130 Valve AOV-68A-Elbow Drawing Numbec MSK-3013. Line No. 24~-W20-902-148 X- A - A 1219 IGSCC D. every 2 refueling outages u.s.130 Pipe-Va se RHR-818 Vol/ Surf 24-10-142 BF A- X - A 1.219 IGSCC D. every 2 refueling outages 24-10-143 B-F B5.130 Viv RHR-818-Viv AOV-688 Vol/Se' - A X- 1.219 IGSCC D. every 2 refuehng outages B5.130 Valve AOV-688-Elbow Vol/ Surf -

24-10-144 B-F Page 7 - 13 of 7 -24 FILE- JAFAUG.TXT.WPD i

k gJ3 gJ James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third inservice Inspection Interi Date January 7,1998 Pimer

$ Augmented !~.,pection Plan Revision 0 ASME WELD COMPONENT ASME ASME REL ISIINTERVAL LTH OR CODE CODE CODE REMARKS IDENTIFICATION EXAM REQ PER1 PER2 PER3 THfCK CAT ITEM DESCRfPTION 1

Drawing Numben later . Line No. Jet Pump - A X- IGSCC D. every 2 refueling outage B-F B5.10 Nozzle-Reducer Safe End VouSurf -

NBA-SE - A X- IGSCC D, every 2 refuetog outages 89.11 Reducer Safe End-Reducer VoVSurf -

4-022-118 B-J X- IGSCC D. every 2 refue!mg ou' ages VoFSurf - A -

N8A e"~

B-J 89.11 Reducer-Reducer X- IGSCC D. every 2 refueling outages VouSurf - A -

NoA B-J B911 Reducer-Reducer X- IGSCC D every 2 refuetog outages VoFSurf - A -

NBA-St:. , B-J 89.11 Reducer-reducer A - A IGSCC D. every 2 refuehng outages VouSurf X-red-SE B-F B5.10 Nozzle-reducer Safe End - A IGSCC O. every ~ efuehng outages

<ouSurf X- A 4-022-117 B-J 89.11 Reducer Safe End-Reducer A - A 'GSCC D. every 2 refuelmg outages VoVSurf X-N88-SE-1 B-J 89.11 Reducer-Reducer A - A IGSCC D.every 2 refuehng outages VovSurf X-N88-SE-2 B-J 83.11 Reducer-reducer A - A IGSCC D. every 2 refueling outages VoVSurf X-N88-SE-3 B-J 89.11 Reducer-Reducer 14 Core Spray System. Drawing Number MbK-3022. Line No.10"4V23-902-5A IGSCC D. every 2 refuehng outages B5.10 Nozzfe-Pipe VoVSurf X- A - A .594-N5OSE B-F IGSCC *E*-inspected once every two refueling outages after repair. Approximately 50% shall be inspected during the first refueling outage. All welds incl category are weld overfays.

Drawing Numbec MSK-3001. Line No. 12"-WH-GE-4A from nozzle N2A A - A .54T IGSCC E every 2 refueling outagas. Termmal End E9.11 Safe End-Pipe VoVSurf C-12-02-2-1 B-J Drawing Numbec MSK-3001. Line No.12*-WH-GE-5A from nozzic N2B A - A .54T IGSCC E. every 2 refteling outages 89.11 Pipe-Elbow VoUSurf A-12-02-2-8 B-J l

Drawmg Numbec MSK-3001. Line No.12" WH-GE-6A from nozzle N2C - A .54T IGSCC E. every 2 refuelmg outages. Termmal End 89.11 Safe End-Pipe VoVSurf A- X !

12-02-2-23 B-J !

r Drawing Number MSK-3001. Line No. 28*-WH-GE-2A - A A- 1.36- IGSCC E. c<ery 2 refueling outages B-J B9.11 Pipe-Elixr- VovSurf -

28-02-2-33 Drawing Number MSK-3001. Line No.12"-WH-GE-7A from nozzle N2D X- .547" IGSCC E. every 2 refueling outages. Termmal End 85.11 Safe End-Pipe VoVSurf - A -

12-02-2-12 B-J - A .54T !GSCC E. every 2 refuermg outages VoVSurf A- A 12-02-2-15 B-J B9.31 12.0" Branch Connecten Drawing Numbec MSK-3001. Line No.12"-WH-GE-8A from nozzle N2E - A A- .54T IGSCC E. every 2 refueling outages B-J 89.11 Pipe-Elbow VouSurf -

12-02-2-18 VoFSurf - A - A- .54T IGSCC E. every 2 refueling outages 12-02-2-19 B-J 89.11 Elbow-Pipe Page 7 - 14 of 7-24 FILE JAFAUG.TXT.WPD

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James . Fitzoatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third Inse'rvice Inspection Int trval Date January 7,1998

> ljiewYorkIhm Revision 0

" ~ "' Augrnented Inspection Plan ASME WELD COMPONENT ASME ASME ISI INTERV?.L LTH OR CODE CODE REL IDENTIFICATION CODE EXAM REQ ITR1 PER2 PER3 THICK REMARKS CAT ITEM DESCRIPTION Drawing Number MSK-3001, Une No. 22"-Wh-GE-3A 'GSCC E. every 2 refueling ouiages B9.11 Pipe-Cap Vol/ Surf A- A - A .993" 22-02-2-22 B4 Drawing Numbec MSX-3001, Line No. 28" WH-GE-1 A from nonle N1B IGSCC E. every 2 refueling outage. Terrinal End 89.11 Safe End-Pipe VoVSurf X- A - A 123" 28-02-2-48 B-J IGSCC E. every 2 refueling outages 89.11 Pipe-Elbow VoVSurf A- A - A 1.23*

28-02-2-52 B4 A- 1.23* IGSCC E, every 2 refueline outage .

B9.11 Elbow-Valve MOV-43A VoVSurf - A -

28-02-2-53 B-J iGSCC E. every 2 refueling outages, Termina. End B9.11 Pipe-Safe End VoUSurf - A - X- 's .23" 2D-02-2-40 3-J Drawing Number- MSK-3002, Une No.12"-WH-GE-8B from nonle N2K IGSCC E, every 2 refueling outages 89.11 Pipe-Elbow VoVSur' A- A - A .547" 12-02-2-76 B-J Drawing Nuntes. wtSK-3002, une No.12"-WH-GE-78 from nonle N2) X- .547" 13 SCC E. every 2 refueling outages. Terminal End B9.11 Safe End-Pipe Vol/ Surf - A -

12-02-2-69 B4 A IGSCC E, every 2 refueling outages B4 B9.11 Pipe-Elbow VoVSurf A- - A .547" 12-02-2-70 Drawing Numbec MSK-3002, Line No. 28"-WH-GE-2B A- 1.36 IGSCC E, every 2 refueling outages 89.11 Pipe-Safe-End VoVSurf - A -

28-0?-2-92 B-J Drawing Numbec MSK-3002, Line No.12"-WH-GE-5B from nonle N2G IGSCC E, every 2 refueting outages, Tenninal End 84 89.11 Se's End-Pipe VoVSurf A- A - X .547*

12-02-2-64 A- A - A .547* IGSCC E, every 2 refueling outages B4 89.11 Pipe-Elbow VoVSurf 12-02-2-65 Drawing Numbec MSK-3002, Line No. 22"-WH-GE-3B A- .993* IGSCC E. every 2 refueling outages 89.11 Pipe-Cap VoVSurf - A -

22-02-2-63 8-J Drawing Number: MSK 3002, Line No. 28"-WH-GE-1B from nonle N1 A 1.23" IG - b E, eveiy 2 refwiMc outages l

89.11 Valve MOV-438 -Pipe VoVSurf - A - A-28-02-2-113 B4 X- 1.23" IGSUC E. every 2 refuehng outages, Terminal End 89.11 Elbow-Pipe Pump 02-2P-18 VoVSurf - A -

28-02-2-110 B-J IGSCC E. every 2 refueling outages VoUSurf - A -

X-N8A-SE-2 B-J 89.11 Reducer-Reducer IGSCC E. every 2 refueling outages 89.11 Reducer Safe End-Reducer VoVSurf - A -

X-4-02-2-118 B-J FILE: JAFAUG.TXT.WPD Page 7 - 15 of 7 - 24

James ^$ Fitzpatrick Nucle:r Power PI:nt [[::JAF-ISI-0003|JAF-ISI-0003]] Third Inservice inspection interval Date January 7,1998 g Power Avgmented Inspection Plan Revision 0 i

ASME WELD COMPONENT ASME ASME ISI INTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE REO PER1 PER2 PER3 TH'CK REMARKS CAT ITEM DESCRIPTION EXAM IGSCC *E"-each outage 02-2 Reactor Recirculation System. Drawing Numbec MSK-3001, Line No.12"-WH-GE-7A IGSCC E* every 10 years Vol/ Surf A- - - - .547" 12-02-2-13 B-J 89.11 Pipe-Elbow

.. awing Numbec MSK-3002. Line No.12"-WH4E-58 .547* IGSCC E*. Every 10 years B-J 89.11 Elt ow-Pipe Vol/ Surf A- - - -

12-02-2-6S IGSCC *F*- no welds in this Category IGSCC *G '- no welds in this Category

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l FILE: JAFAUG.TXT.WPD Page 7 - 16 of 7 -24

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James A Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Date January 7,1998 M Third Inservice Inspection Interval

$ Augmented inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME ISI INTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE EXAM REQ PER1 PER2 PER3 THICK REMARKS CAT ITEM DESCRIPTION Main Steam and Feedwater Augmented Examinations An Augmented Inservice Examination program is required for those high stressed circumferential pipe joints located in the Main Steam and F 4.0 in in diameter, where no restraint against pipe whip is provided. Scope of Examination - 100% inspection of these welds each inspection interval.

29 - Main Steam, Drawing Number: MSK-3031, Line No. 24"-SHP-902-1 A from Reactor % assel Vol/ Surf X- - - - 1.21" High Stress Weld 24-29-541 B-J 89.11 Valve AOV-80A-Pipe Surf - - X - - 1.21" High Stress Weld 24-29-552 B-J B9.11 Pipe-Tee 29 - Main Steam, Drawing Number MSK-3031, Line No. 24"-SHP-9C2-18 from Reactor Vessel Vol/ Surf - - X - - 1.21" Ngh Stress Weld 24-29-557 B-J B9.11 Pipe-Pipe Vol/ Surf - - X - - 1.21" High Stress Weld 24-29-559 B-J 89.11 Tee-Pipe Vol/ Surf - - X - - 1.21" High Stress Weld 24-29-572 B-J 89.11 Pipe-Pipe 29 - Main Steam, Drawing Number: MSK-3032, Line No. 24"-SHP-902-1C from Reactor Vessel Vol/ Surf - - -

X- 1.21* High Stress Weld 24-29-583 B-J 89.T 1 Pipe-Tee Vol/ Surf -

X- 1.21" High Stress Weld 24-29-584 B-J 89.11 Tee-Pipe - -

Vol/ Surf - - -

X- 121" High Stress Weld 24-29-588 B-J 89.11 Pipe-Reducer Vol/ Surf - - - X- 1.21" High Stress Weld 24-29-589 B-J 89.11 Tee-Pipe Vol/ Surf X- 1.21" High Stress WeH 89.11 Valve AOV-80C-Pipe - - -

24-29-605 B-J 29 - Main Steam, D6 awing Number: MSK-3032, Line No. 24"-SHP-902-1D from Reactor Vessel Vol/ Surf X- 121" High Stress Weld 89.11 Valve AOV-80D-Pipe - - -

24-29-636 B-J Page 7 - 17 of 7 -24 FILE: JAFAUG.TXT.WPD

O O James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-CN13|JAF-ISI-CN13]] O

Third Inservice Inspection Interval Date s nuary 7,1998 g Power Augme . sed Inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME LTH OR CODE REL ISI INTERVAL IDENTIFICATION CODE CODE REMARKS ITEM DESCR!PTION EXAM REO PER1 PER2 PER3 THfCK CAT t

34 - Feedwater System, Drawing Number: MSK-3033, une No 12"-WFP-902A-5C to Reactor Vessel VoVSurf X- - - - .844" High Stress Weld 12-34-368 B-J 89.11 Pipe-Elbow Vol/ Surf X- - - - .844" High Stress Weld 12-34-369 B-J 89.11 Elbow-Elbow Vol/ Surf X - - .844* High Stress Weld 12-34-370- B-J 89.11 Elbow-Pipe -

Vol/ Surf X - - .844* High Stress Weld 89.11 Pipe-Pipe 12-34-371 B-J VoVSurf - - X - - .844' High Stress Weld 12-34-372 B-J 89.11 Pipe-Pipe Vol/ Surf - - X - - .844" High Stress Weld 12-34-373 B-J 89.11 Pipe-Reducer Vol/ Surf - - X - - .844* High Stress Weld, Terminal End 12-34-375 B-J 89.11 Pipe-Safe End 34 - Feedwater System, Drawing Number: f1SK-3033, Une No.18"-WFP-902A4A VoVSurf - - - X- 1.15" High Stress Weld 18-34-374 B-J 89.11 Reducer-Tee Vol/ Surf X- 1.15" High Stress Wefd -

89.11 Tee-Pipe - - -

18-34-382 B-J Vol/ Surf - - - X- 1.15" High Stress Weld 18-34-389 B-J 89.11 Elbow-Valve FWS-28A Vol/ Surf X- 1.15" High Stress Weld 89.11 Valve FWS-28A-Pipe - - -

10-34-391 B-J 34 - Feedwater System, Drawing Number: MSK-3034, Line so.12"-WFP-902A-5D to Reac*or Vessel Vol/ Surf - -

X - - .844" High Stress Weld 12-34-402 B-J 89.11 Pipe-Elbow Vol/ Surf X - - .844* High Stress Weld 12-34-403 B-J 89.11 Elbow-Pipe - -

VoVSurf - - - X- .844* High Strest Weld 12-34-404 B-J 89.11 Pipe-Elbow Vol/ Surf - - - X- .844" Hioh Stress Weld 12-34-405 B-J 89.11 Pipe-Pipe Page 7 - 18 of 7 -24 f FILE: JAFAUG.TXT.WPD

James A. Fitzpatrick Nuclear Power Pl;nt [[::JAF-ISI-0003|JAF-ISI-0003]] Third Inservice Inspection Interval Date January 7,1998 g Pour Augmented inspection Plan Revision 0 AsME WELD COMPONENT ASME ASME REL ISI INTiERVAL LTH OR CODE CODE CODE REMARKS IDENTIFICATION EXAM REQ PER1 PER2 PER3 THICK CAT ITEM DESCRIPTION Vol/Strf - - - - X .844" High Stress Weld 12-34-406 B-J 89.11 Pipe-Pipe Vol/ Surf - - - - X .844* High Stress Weld 12-344 07 B-J 89.11 Pipe-Reducer 34 - Feedwater System, Drawing Number: MSK-3034, Line No.12"-WFP-902A-5B to Reactor Vessel Vol/ Surf - - X - - .844" High Stress W:Id. Terminal End 12-34-409 B-J 89.11 Pipe-Safe End 34 - Feedwater System, Drawing Number: MSK-3034, Line No.18*-WFP-902A4B -

Vot/ Surf X- - - - 1.15" High Stress Weld 18-34-408 B-J 89.11 Reducer-Tee Vol/ Surf X- - - - 1.15" High Stress Weld 18-34-416 B-J 89.11 Tee-Pipe Vol/ Surf - - X - - 1.15' High Stress Weld 18-34-423 B-J 89.11 Elbow-Vafve FWS-28B Vof/ Surf - - X - - 1.15" High Stress Weld 10-34-425 B-J 89.11 Vafve FWS-288-Pipe Note: In addressing the augmented examination requirements of those portions of systems, pipe-to-pipe welds and longitudinal seams are requi Additionalty, the Code boundary is extended past the code citss boundary (MSIV) to the first restraint. The welds and supports thus affected a identified through Examination Notes in the Main Steam and Feedwater examination Tables.

r Page 7 - 19 of 7 - 24 FILE: JAFAUG.TXT.WPD

s James A. Fitzpstrick Nucle:r Power Plant [[::JAF-ISI-000|JAF-ISI-000]]" Third Inservice Inspection Interval - Date Janua.y 7,1998 gMMh "~'"' Augmented Inspection Plan Revision 0 ASME WELD COMPONENT ASME ASME ISIINTERVAL 1.TH OR CODE CODE REL IDENTIFICATION CODE REQ PER1 PER2 PER3 THICK REMARKS CAT ITEM DESCRIPTION EXAM __

f NUREG (,619 BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking NYPA committed to a program of periodic examinations of the (4) Feedwater nozzles /Feedwater Sparger Assemblies in accordance with the requirement Feedwater Nozzle and Control Rod Drive Retum Line Nozzle Cracking . In compliance with this NUREG, NYPA has removed the cladding from the Feedwa capped the CRD Rctum Line. In additions NYPA has submitted a Request for Relief 7 from performing Liquid Penetrant (PT) examination of the blend radius. Scope of Examination - The zones to be examinad by the Ultrasonic techniques shall be the regions as shown for identifcation purposes in Figure 6-5.

01 - Reactor Pressure Vessel , Drawing Number: MSK-3036, Line No. 02V-1 Reactor Pressure Vessel Nozzles R-Vol - - - A- 12.0" At or near end ofinterval N-4A B-D B3.10012.0" FW Nozzle R-Vol - - - A 12.0" At or near eno ofinterval N-48 B-D B3.10012.0" FW Nozzio R-Vol - - - A- 12.0* At or near end ofinterval N-4C B-O B3.10012.0* FW Nozzle R-Vol - - A- 12.0" At or near end ofinterval N-4D B-D B3.10012.0" FW Nozzle VT-3 - - - A- 12.0" Every 4 . Refueling Outage Feedwater Sparger Assemblies and Feedwater Nozzles VT-1 AA A A A 3.0" Examine each outage until final PT is performed N-9 B-D B3.90 3.0" CRD Nozzle f

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FILE: JAFAUG.TXT.WPD Page 7 - 20 of 7 - 24

) J J;mes A. Fitzp . trick Nuclerr Power Pl:nt [[::JAF-ISI-0003|JAF-ISI-0003]] O

Third inservice inspection Interval Date January 7,1998 A NewWrkPower Revision 0 U Augmented litspection Plan ASME WELD COMPONENT ASME ASME ISI INTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE EXAM REQ PER1 PER2 PER3 THICK REMARKS CAT ITEM DESCRIPTION In-VesselVisual Augmented Examinations in addition to the ASME Code requirements. this Section identifes those additional examination activites, that JAF has evaluated and determined t interval. Augmented examinations may be recommended by Regulatory documents. NSSS recommendations, industry experience, and/or good engi Nota: Selections will be assigned as required.

Top Guide - - Alignment wedges and Hold GE RICStL 071. Surfaces of 4. sampling of the high Down Botts VT-3 - - -

VT-1 - - - - - fluence cells

- - Top Guide rim we!d

- - GE SIL 462. Verify no cracking in crevice weld region

- - Crevice Weld Region (1) UT - - -

- - GEJAF 86. BWROG 91. GE SIL 474. Periodically Assembly VT - - -

Steam Dryer - -

inspect to assess component condition; UT inspr<:t as necessary to characterize cracking; (10)

Shroud Tie Assembly VT-3 - - - - - BWRVIP-07. (EPRI TR-105747. Examine Shroud tie Shroud Assembly - -

rod assembly, Examine Nut mgagement Nut Engagement VT-1 - - - - -

VT - - - - - NUREG/CR 3052. USNRC Bulletin 80-07. GE SIL 330.

Jet Purae Beams (2) - -

Inspect eas .e Inspection Interval NUKG/CR 4523. Examine CS Sparger Assembly and Sparger (3) VT - - - - -

Core Spray - -

piping, ecch refueling outage GEJAF 83. BWROG 91. GE S!L 433. Good Engineering Shroud Heads Assembly VT - - - - -

Moisture Separator - -

Practice. Periodically inspect to assess component condition (10)

VT - - - - - Replacement Bolts. Periodically as required (10)

Shroud Head - -

Bolfs (4)

GE SIL 420. GE SIL 465. GE SIL 574. Examine jet Assembly VT - - - - -

Jet Pump - -

Pump assembFes, diffuser to shelf welds, sensing lines and brackets on a periodic basis to assess component condition. (10) f Page 7 - 21 of 7 -24 FILE: JAFAUG.TXT.WPD

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JAF4SI-0003

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James A. Fitzpatrick Nuclear Power Plant h Third Inservice inspection interval Date January 7,1998

'$ Augmented inspection Plan Revision 0 COMPONENT ASME ASME ASME WELD IDENTIFICATION . CODE CODE CODE P.EL ISIINTERVAL LTH CR CAT ITEM DESCRIPTION EXAid REQ PER1 PER2 PER3 THICK REMARKS Feedwater Sparger - -

Nozzle (5) VT - - - - - Good Engincesing Practice. VisuaDy insped each fourth reftaling outage. Examine the nozzles on the replacement FW 3parger on a penodic basis (10)

IRM/SRM - -

Dry Tt.bes (6) VT - - - - - Industry Recommendations. Exemine on a penodicaly basis to assess the cond~tions of the tubes. (10)

Control Rod Drive - - Stub Tube / Housing Penetrations VT - - - - - Good Engineering Practice Yvhen Accessible (10) t in-Core - - Instrumentation / Housing Pens VT - - - - - Good Engineering Practice, When Accessible (10)

Core Delta Pressure / Standby Liquid Control VT - - - - - Good Engineering Practice, When Accessible (10)

N-9 - - 3.0" CRD Nozzla VT-1 - - - - - Examine each outage until final PT is penormed Note: (1) NYPA has not determined whether a reexamination of this areas is warranted during the third interval.

(2) The Jet Pump beams were replaced per Modification Dl-92-077.

(3) Core Spray Sparger "B" clamp was repaired per Modification F1-88-199.

(4) Bolts were replaced. Type 347, per Modification F1-86-122.

(5) Feedwater Sparger assemblies replaced per Modification F!-78-036.

(6) IRM/SRM Dry Tubes have all been replaced with Tyoe 348 material per Modification F1-85-090.

t (10) These inspections are not commitments and are subject to change as necessary to support good engineering practices FILE: JAFAUG.TXT.WPD Page 7 - 22 of 7 -24

O O J mes A. Fitzpatrick Nucle:r Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] O

Third Inservice inspection Interval Date January 7,1998 PN Revision 0 g New Augmented Inspection Plan ASME WELD COMPONENT ASME ASME REL ISI INTERVAL LTH OR CODE CODE CODE REMARKS IDENTIFICATION EXAM REQ PER1 PER2 PER3 TH1CK CAT ITEM DESCRtPTION Core Spray Augmented Examinations Augmented Examinations identified below are welds that are dedicated to monitoring the pump discharge piping for vibration dam and surface examination of selected welds as defined below:

14 - Core Spray System, Drawing Number: MSK-3022, Line Number 12"-W23-302-4A From CS Pump 1 A X - .- 406" Terminal End, weld selected for monitoring potential C5.51 Pump-Elbow Vol/ Surf - -

12-14-724 C-F-2 pump discharge vibration damage X- .40G" Weld selected for monitoring potential pump c'ischarge C5.51 Elbow-Pipe Vol/ Surf - - -

12-14-734 C-F-2 vibrt. tion damage 14 - Core Spray System, Drawing Number: fnSK-3022 Line Number 10"-W23-302-8A X- - - Weld selected for monitoring potential pump discharge C-F-2 C5.81 10.0" Branch Contrection Surf -

12-14-750 vibration damage, inaccessible X - - - .322" Weld selected for monitoring potential pump discharge C5.51 Reducer-Valve MOV-26A Vol/ Surf -

8-14-779 C-F-2 vibration damage, Excluded IWC-2500-1 X- - - .365" Weld selected for monitoring potential pump discharge C5.11 Valve MOV-20A-Reducer Vo!/ Surf -

8-14-780 C-F-1 vibration damage Excluded IWC-2500-1 14 - Core Spray System, Drawing Number: MSK-3023, Line Number 12"-W23-302-48 X - - .406" Weld selected for monitoring potential pump discharge C-F-2 C5.51 Pump-Elbow Vol/ Surf - -

12-14-823 vibration damage, Terminal End X- .406" Weld selected for monitoring potential pump discharge C-F-2 C5.51 Elbow-Pipe VoJSurf - - -

12-14-834 vibration uamage i

X .625" Weld selected for monitoring potential pump discharge C-F-2 C5.81 10.0" Branch Connection Surf - - - -

12-14-851 vibration damage, inaccessible Page 7 - 23 of 7 - 24 FILE: JAFAUG.TXT.WPD

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James A. Fitzpatrick Nuclear Power Plant [[::JAF-ISI-0003|JAF-ISI-0003]] Third Inservice inspection Interval Date January 7,1998 Ml# "je9M Psever

- " " " ' Augmented Inspection Plan Revision 0 ASi, FLD

. COMPONENT ASME ASME ISI INTERVAL LTH OR CODE CODE REL IDENTIFICATION CODE IEQ PER1 PER2 PER3 THICK REMARKS CAT ITEM DESCRIPTION EXAM 5

14-Core Spray System Drawing No. MSK-3023, une No.10"-W23-302-8B X- .322" Weld selected for monitoring potential pump discharge C-F-2 C5.51 Reducer-Valve MOV-268 Vol/ Surf - - -

8-14-878 vibration damage Vot/ Surf - - - X- .322* Excluded IWC-2500-1 8-14-879 C-F-1 C5.11 Valve MOV-268-Reducer 14 - Core Spray Syst m. Drawing Number- MSK-3023, Line Number 10"-%23-163-98 X - - .365" Weld selected for monitoring potential pump discharge C-F-1 C5.11 Pipe-Tee Vol/ Surf - -

10-14-884A vibration damage Exc uded IWC-2500-1 1

l FILE: JAFAUG.TXT.WPD Page 7 - 24 of 7 - 24 t --___ _

l JAMES A.FITZPATRICK JAF lSI-0003 NUCLEAR POWER PLANT !

4# --

THIRD INSERVICE INSPECTION INTERVAL Rev. O Date: Januarv 7,1998 !

TEN YEAR INSERVICE INSPECTION PLAN Page 23 of 35 APPENDIX A ACCEPTANCE CRITERIA Indicatians detected by inservice examinations, shall be compared against the acceptance criteria of Section XI as defined in Tables A-1 through A-4.).

O V

File; jafisipl.wpd

JAMES A. FITZPATRICK JAF ISI-0003 NUCLEAR POWER PLANT All> NewWrkPower tv Authority 9 THIRD INSERVICE INSPECTION INTERVAL Rev. O Date: January 7,1998 TEN YEAR INSERVICE INSPECTION PLAN Pag: 24 of 35 TABLE A 1 - CLASS 1 ACCEPTANCE STANDARDS EKAMINATION ' LGOf*PONENT OR PART EXAMINED - ' ACCEPTANCE:

CATEGORY- -STANDARD-B-A Welds in Reactor Vessels ;NB 3510 B-B Welds in Other Vessels IWB-3510 B-D Vessel Nozzle Welds IWB-3512 B-E Partial Penetration welds in Vessels IWB-3522 B F. B-J Dissimilar and Similar Metal Welds in Piping ,

IWB-3514 BG1 Bolting > 2" dia. lWB-3515/3517 B G-2 Botting 5 2" dia. lWB-3517 B-H, B K-1 Integral Attachments for Piping. Valves, Pumpc & Vessels IWB-3516

/%

( B L 1, B-M-1 Welds in Pumps & Valves IWB-3518 b

B L-2, B-M-2 Pump Casings & Valve Bodies IWB-3519 B-N-1 B-N-2 Interior Surfaces & Internal Components of Reactor Vessels IWB-3520 B-N 3 BO Control Rod Drive Housing Welds IWB-3523 B-P Pressure Retaining Boundary IWB 3522 B-Q Steam Generator Tubing IWB-3521 7

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JAMES A. FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] NUCLEAR POWER PLANT

b NewWrkPower tv Authority G THIRD INSERVICE INSPECTION INTERVAL Rev.

Date: January 7,1998 TEN YEAR INSERVICE INSPECTION

+ Page 25 of 35 TABLE A 2 -CLASS 2 ACCEPTANCE STANDARDS

"^ N ^

COMPONENT OR PART EXAMINED STAN RD C GO Y C-A Welds in Pressure Vessels IWC-3510 C-B Nozzle Welds in Vessels IWC-3511 C-C integral Atcachments for Vessels, Piping. Pumps and Valves IWC-3512 C-D Botting (WC-3513 C-F-1,C-F-2 Welds in Piping IWC-3514 C-G Welds in Pumps and Valves IWC-3515 C.H Pressure Retaining Components IWC-3516

% TABLE A CLASS 3 ACCEPTANCE STANDARDS L EXAMINATION CATEGCRY ~ . COMPONENT OR PART EXAMINEDi ACCEPTANCE'

STANDARD D-A Pressure Boundary (VT 2) ^No Leakage

Mfg. Code Integral Attachments (VT 3) & Applicable Standards D-B Pressure Boundary (VT-2) ^No Leakage

Mfg. Code integral Attachments (VT-3) & Applicable Standards D-C Pressure Boundary (VT 2) IWA 5250

Mfg. Code &

Integral Attachments (VT-3) Appl'aabte Standards ASME Section XI Acceptance Standard in course of preparation. !

^ Defhed as no leakage from the pressure boundary,in excess of that which is expected and determined to be w. thin acceptable limits, i.e., at valve packing, bolted connections, pump seats, etc.

TABLE A-4 -COMPONENT SUPPORT ACCEPTANCE STANDARDS

- EXAMINAT'ON CATEGORY . COMPONENT OR PART EXAMINED) ;ACCEPTANCEb y : STANDARD-F-A Supports IWF-3410 sq l

File: jafisipl.wpd

JAMES A. FITZ?ATRICK [[::JAF-ISl-0003|JAF-ISl-0003]] NUCLEAR POWER PLANT

D NewYorkPower 4W Authority 9 THIRD INSERVICE INSPECTION INTERVAL Rev. O TEN YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 26 of 35 APPENDIX B ULTRASONIC CALIBRATION BLOCKS

[Fli.E NUMBERj NDENTIFICATIONli KDIAMETER $ s MATERIAL

~

001 3-A376 .300 3.50' A376SS 002 4-A376 .337 4.50" A376SS 003 6-A376. 432 6 625* A376SS 004 10-A376 60 10.75* 476SS 005 12 A376-.660 12.75* A376SS 006 12 A376.760 12.75* A376SS 007 20-A376-1.14 20 00* A376SS 008 22-A376-1.16 22.00* A376SS 009 24-A376-1.25 24.00* A376SS 9 010 28-A376-1.53 28.00* A376SS 011 3 4106-438 3.50" A106CS 012 4-A106 .350 4.50* A106CS 013 6-A106- 460 6.625' A106CS 014 6-A106- 864 6.625' A106CS 015 8-A106.500 8.625* A106CS 016 10-A106. 365 10.75* A106CS 017 10-A106 .594 10.75* A106CS 018 12.A106 .844 12.75* A106CS 019 14-A106 .940 14.00* A106CS 020 18-A106-1,156 18.00* A106CS 021 20-A106 .594 20.00* A106CS 022 20-A106-1.05 20.00* A106CS 023 20-A106-1.281 20.00* A106CS 024 24-A106-1.32 24.00* A106CS 025 PN1 14 38' A508CS

,rx 026 PN2 5.25* A508CS 027 PN3 13 44' A508CS File: jafisipl.wpd

JAMES A. FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] NUCLEAR POWER PLANT

> NewWrkPower tv Autho:My G THIRD INSERVICE INSPECTION INTERVAL Rev. O TEN YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 27 of 35

? FILE NUMBER : ODENT5tCAI1ONj tnAMETER LMATERIALd-028 PN 4 29.06* A508CS 029 PT NO S 5 44' A508CS 030 PN 6 14.38" A182SS 031 PN 7 5.25" A182SS 032 PN 8 13 44* A182SS 033 PT NO 9 29.% A182SS

~

034 PT NO 10 5 44' A182SS 035 FITZ-1 R-4.03 PLATE A508CS 036 FITZ 1R 5.25 PLATE A508CS 037 FITZ-1 R-7.76 PLATE A508CS

- 038 PT NO 1 PLATE A533CS

- 039 PT NO 2 PLATE A533CS 040 PT N? 3 PLATE A533CS 041 PT NO 4 PLATE A508CS 042 OVERLAY 1 12.00* INCONEL.0L 043 SS 304.750 PLATE A304 SS 044 SS-304 .800A PLATE A304 SS 045 SS-304 .8008 PLATE A304 SS 046 SS-304-12* 12 75" A304SS W/308SS OL 047 SS 304 22* 22.00* 304SS W/318SS OL 048 FITZ-RC-INLET-14*NOZ-1 14* A304SS & A016 CS 049 FITZ-RC-OUTLET 28'NOZ-1 28' A304SS & A106 CS 050 02-2-1S 2.750" AS40 CS 051 02-2-2S 2.750* A540CS 052 0223S 2.750" AS40CS 053 02-2-4S 2.750" AS40 CS 054 02-IS 6.000 A540 CS n ~

( 055 02-2S 6 000 A540 CS v

056 02-3S 6.000 AS40 CS File: jafiSipl.wpd

JAMES A FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] NUCLEAR POWER PLANT

> lilewYorkPower

& Authority G THIRD INSERVICE INSPECTION INTERVAL Rev. O TEN-YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 28 of 35

FILE NilMPER: iIDENTIFICATION . JDtAMETERj [ MATERIAL 057 02-4S 6 000 A540 CS 058 NOT ASSIGNED 21.55" A403WP 304 SS

~ ~

059 CRD-CB-NPS-d' 4.50 A508 INCONEL 060 3-A106 .300 3.50 A106 CS 061 CS SE 1 13.625 A182 F304 SS 062 CS-TS-1 11.255 A182 F304 SS 063 NOT ASSIGNED 13 632 SA182 F347 SS 064 NOT ASSIGNED 29 63* SA187 F347 SS 065 NOT ASSIGNED 14 874* SA182 F347 SS 066 NOT ASSIGNED 13 94* SA508 CL2 ALLOY STL 067 JPI-SE-1 4.50" SB166CS/INCONEL 600

'v 068 1.25-A304-CTD PLATE A304 SS 069 .75-A304-CTD PLATE A304 SS 070 1.25 304 CWB PLATE A304 SS 071 .75-A304-CWB PLATE A304 "S 072 100-A304 45MP PLA A304 SS 073 1.00-A304-60MP PLATE A304 SS 074 NMP128-1.050-SS 28 00* A358 SS 075 NMPI-3-80-CS 3 50" A353 CS C6 10-A376 .69 10.75* A376 SS/F304 077 JPI-SE-2 8.75' A182/F304 078 M2410144 24* F304 079 M2410143 24' F304 080 M2410142 24' F304 081 M2302230 28' F304 082 M2802285 28' F304 083 SK [[::JAF-88-006|JAF-88-006]] 4 F304 084 DECON 1 4" F304 v

085 JAF-85 4' F304 File: jafs;pl.wpd

JAMES A. FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] NUCLEAR FOWER PLANT

> NewYorkPower

& Authority G l THIRD INSERVICE INSPECTION INTERVAL Rev, O TEN YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 29 of 35 FILE NUMBER lIDENT!FICATIOtd < i DIAMETERf !q; llj i; MATERIAL-i!

086 JAF-86 12' F304 087 MSK-3093 PLATE A516-70

~ ^

088 MSK-3092 PLATE A516-70 089 MSK 3095 14* A106 GRB 090 MSK 3094 24' A106 GRD 091 OL8-10-SS .550 10" F304 092 C3-1 S. WEDGE A516GR70 033 CS-2 S. WEDGE A516GR70 094 SS-2 S WEDGE SA240TP304 095 SS-1 S WEDGE SA240TP304

,m 0% RL-1 PLATE SA240TP304

{ .i C- 097 RL-2 PLATE SA240TP304 098 RL-3 PLATE SA240TP304 099 RL-4 PLATE SA240TP304 100 RL-5 PLATE SA240TP304 101 RL-6 PLATE SA240TP304 102 87008 28' / 4' F304 103 10-A403 .600 10' A347/403 104 FITZ-1344-SE-NOZ 13.44" SA508/A347/403

( \

'wJ' File:. jafisipl.wpd

JAMES A. FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] NUCLEAR POWER PLANT

b ljewYorkPtwer e' Authority G THIRD INSERVICE INSPECTION INTERVAL Rev. O TEN YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 30 of 35 APPENDIX C CLASS 1,2 and 3 WELD / SUPPORT LOCATION MAPS IDrawinghuintsii th 34 /RhisioENumbe$

STitieffS4 MSK-3001 -

Reactor Water Recirculation System - 11 MSK-3002 Reactor Water Recirculation System 10 MSK 3003 Control Rod Dnve 7 MSK-3004 Residual Heat Removal System 11 MSK 3005 Residual Heat Removal Oystem 11 MSK-3006 Residual Heat Removal System 8 MSK 3007 Residual Heat Rermoval System 8 MSK-3008 Residual Heat Rem tal System 9

- MSK 3009 Residual Heat Removal System 9

_ MSK 3010 Residual Heat Removal System 8 MSK 3011 Residual Heat Removal System 8 MSK-3012 Residual Heat Removal System 9 MSK 3013 Residual Heat Removal System 7 MSK 3014 Residual Heat Removal System 7 MSK 3015 Residual Heat Removal System 7 MSK-3016 Residual Heat Removal System 7 MSK-3017 Resuiual Heat Removal System 7 MSK-3018 Reactor Water Cleanup System 8 MSK 3019 Reactor Core injection Cooling System 10 MSK-3020 Reactor Core injection Cooling System 9 MSK-3021 Core Spray System 6 MSK-3022 Core Spray System 11 MS!'-3023 Core Spray System 11 MSK-3024 High Pressure Cooling injection 10 MSK-3025 High Pressure Cooling injection 8 MSK-3026 High Pressure Cooling injection 7 MSK-3027 High Pressure Cooling injection 7 File: jafiaipl.wpd

JAME3 A. FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] N'JCLEAR POWER PLANT

> NewYorkPower ev Authority S THIRD INSERVICE INSPECTION INTERVAL Rev. O TEN YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 31 of 35 g Drawing Nismber " >

] Title ; Rwiston Numtsr MSK 3028 Hgh Pressure Coohng injection 8 MSK 3029 DrywellInerting. C.A D., and Purge System 6

~

MSK-3030 Drywell inerting, CAD., and Purge System 5 MSK-3031 Main Steam System 7 MSK 3032 Main Steam System 7 MSK-3033 Feedwater System 6 MSK 3034 Feedwater System 7 MSK-3036 ISI Reactor Vessel Stretch Out for Weld Desgnation 2 MSK-3037 ISI Resid Jai Heat Removal Heat Exchanger Weld identification 2 MSK-3038 ISI Scram Tank Weld Identification 2 MSK-3039 ISI CRD-West S:de Piping 4 O MSK-3040 ISI CRD-East Sdc Piping 3 MSK 166A1 Resdual Heat Removal Systern 5 MSK-166B1 Residual Heat Removal system 4 MSK 166C1 Residual Heat Removal System 5 MSK 137A1 Residual Heat P,emovat System 6 MSK 137B1 Resdual Heat Removal System 6 MSK-137C1 Resdua! Heat Removal System 7 MSK 137D1 Residual Heat Removal System 7 MSK-137E1 Residual Heat Removal System 5 MSK-137F1 Residual Heat Removal System 6 MSK 137H1 Res4ual Heat Removal System Latest revision MSK-167C1 Reactor Core Injection Coohng System B MSK 102A1 Reactor Core lajection Cooling System 8 MSK-167C1 Reactor Core injection Coohng System 8 MSK 10201 Reactor Core injection Cooling System 8 MSK 103A1 Reactor Building Closed Loop Coohng System 6 MSK-10381 Reactor Building Closed Loop Cookng System 6 MSK-103C1 Reactor Building Closed Loop Coohng System 7 File: jafisipl.wpd

JAMES A. FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] NUCLEAR POWER PLANT

> NewYorkPower

& Authority G THIRD INSERVICE INSPECTION INTERVAL Rev. O TEN YEAR INSERVICE INSPECTION Date: January 7,1998 PLAN Page 32 of 35

! DrawlikNnr!; ETitleS N.RedsloE Numtierl MSK-103C2 Reactor Building Closed Loop Coohng System 7 MSK 103C3 Reactor Building Closed Loop Coohng System 9 MSK-103F Reactor Building Closed Loop Cochng System 1 MSK-103P Reactor Building Closed Loop Cookng System 3 MSK-103C8 Reactor Building Closed Loop Cookng System 7 MSK 113B1 Fuel Pool Coohng System 8 MSK-113E1 Fuel Pool Cool;ng System 4 MSK-113D1 Fuel Pool Coohng System 5 MSK 113Fi Fuel Pool Coohng System 7 MSK-113C1 Fuel Pool Cooling System 8 MSK 137K1 Service Water System 8 W MSK-137N1 Service Water System 8 MSK-137P1 Service Water System 9 MSK 137Q1 Service Water System 10 MSK 166Et Service Water System 4 MSK 166F1 Service Water System 5 MSK-1359 Reactor Building Vent and Coohng System 3 MSK 1361 Reactor Building Vent and Coohng System 5 MSK-1363 Reactor Building Vent and Ceohng System 3 MSK 1474 Control Room Vent and Cochng System 2 MSK 1475 Control Room Vent and Coohng System 3 MSK-1476 Control Room Vent and Coohng System 3 MSK 1456 Control Room Vent and Cookng System 2 MSK-1457 Control Room Vent and Coohng System 8 MSK-1458 Control Room Vent and Cooling System 7 MSK 1492 Control Room Vent and Coohng System 3 f

_)

E.3 File: jahipl.wpd

JAMES A. FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] NUCLEAR POWER PLANT THIRD INSERVICE INSPECTION INTERVAL Rev. O TEN YEAR INSERVICE INSF ECTION Date: January 7,1998 PLAN Page 33 of 35 APPENDIX D ASME CODE CASES The following ASME Code Cases have been reviewed for possible use during the Third Inservice inspection Interval.

Code Cases used during the inspection interval shall be identified with the specific component within the Inspection /

Examination Tables. - -

CODE CASE EUMBER TITLE N-236-1 Repair and Replacement of Class MC Vessels,Section XI, Division 1.

N-355 Calibration Block for Angle Beam Ultrasonic Examination of Large Fittings in accordance with Appendix 111-3410,Section XI Division 1.

N-389-1 Alternative Rules for Repairs, Replacements, or Modifications,Section XI, Division 1,

[ 1-416-1 Altemative Pressure Test Requirement for Welded Repairs or installation of Replacement items by

'u Welding, C! ass 1,2 and 3,Section XI, Division 1.

N-432 Repair Wek'ing Using Automatic or Machine Gas Tungsten-Arc Welding (GTAW) Temper Bead Technique Section XI, Division 1.

N-457 Qualification Specimen Notch Location for Ultrasonic Examinatio i of Bolts and Studs,Section XI, Division 1.

N-458-1 Magnetic Particle Examination of Coated Materials,Section XI, Division 1.

N-460 Alternative Examination Coverage for Class 1 and Class 2 Welds,Section XI, Division 1 N-472 Use of Digital Readout and Digital Measurement Devises for performing Pump Vibration Testing,Section XI, Division 1.

N-485-1 Eddy Current Examination of Coated Ferritic Surfaces as an attemative to Surface Examination,Section XI, Division 1.

N-490-1 Alternative Vision Test Requirements for Nondestructive Examiners,Section XI, Div9 an 1.

N-491-1 Altemative Rules for Examit.a! ion of Class 1,2,3, and MC Component Supports,Section XI, Division 1

N-498-1 Altemative Rules for 10-Year System Hydrostatic Testing for Class 1,2 and 3 Systems,Section XI, Division 1 m.J File:jafisipl.wpd

JAMES A. FITZPATRICK [[::JAF-ISI-0003|JAF-ISI-0003]] NUCLEAR POWER PLANT

> NewYorkPower tv Authority 9

THIRD INSERVICE INSPECTION INTERVAL Rev. 0 Date: January 7,1998 TEN-YEAR INSERVICE INSPECTION PLAN Page 34 of 35 CODE CASE NUMBER TITLE N-504-1 Alternative Rules for Repair of Class 1,2 and 3 Austenitic Stainless Steel Piping,Section XI, Division 1.

N-509 Alternative Rules for the Selection and Damination of Class 1, 2 and 3 Integrally Welded Attachments,Section XI, Div'sion 1 N-516 Underwater Welding,Section XI, Division 1 N-522 Pressure Testing of Containment Penetration Piping,Section XI, Division 1.

N-523 Mechanical Clamping Devices for Class 2 and 3 piping.Section XI, Division 1.

N-524 Alternative Examination Requirements for Longitudinal Welds in Class 1 and Class 2 Piping,Section XI, Division 1

N-532 Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice b/ Summary Report Preparation and Submission as required by IWA-4000 and IWA-6000,Section XI, Division 1.

N-534 Alternative Requirements for Pneumatic Pressure Testing,Section XI, Division 1.

N-537 Location of Ultrasonic Depth Sizing Flaws,Section XI, Division 1.

N-554 Altemative Requirements for Re:onciliation of Replacement items,Section XI, Division 1.

N 573 Transfer of Procedure Qualification ~ = cords Between Owners,Section XI, Division 1.

[

w; File: jafisipl.wpd

CASE-N-236-1 g , _ CASES OF ASME BOILER AND PRESSURE VESSEL CODE

_I ,

Approval Date: September 5,1985 See Numerie Index for expiration and any restfirmation dates.

3 Case N 236 1 Repair and Replacement of Class MC VesselsSection XI, Division 1 Inquiry: What are the requirements of Section XI, Division 1, regarding repair and installation of replace ~

ments of Class MC vessels?

Replyt it is the opinion of the Committee that re-pairs and installation of replacements of Class MC vessels may be conducted using the rules of Section XI, Division 1, and the following.

TABLE OF CONTENTS 1000 Repair Procedures 2210 General 1100 General 2220 Tests Following Repair, Modifica-1110 Scope tion, or Replacement 1120 Procedure 2221 Leakage Test 1200 Removal of Defects including Prep. 2222 Deferral of Leakage Tests arations for Welding 2240 Visual Examination 1210 Thermal Removal Processes 2250 Corrective Measures 1211 Requirements for P-No. I Materials 1220 3000 Installation of Replacements Mechanical Rerr wal Processes 3100 Scope 1230 Preparation for tepair Welding 1300 3300 Installation Not Requiring Welding Repair %elding 1310 3310 Mechanical Joints Applicable ReqC _aents 1320 . 3320 Bolted Connections Butterbead Temperbead Repair 1321 3400 Installation Requiring Welding General Requirements 1322 We: ding Qualifications 3600 Materials 1322.1 Procedure Qualification 1322.2 1322.3-Performance Qualification Production Test 3[ Temperbead Technique

. 1323 Welding Techmque 1323-2 Illustration of the Temperbead

- """" " Technique for Reinforcement of

-1323. Repair Techm. ques Existing Fillet Welds p)%/

,1330 2000 lialf Bead Repair System Pressure Tests .

1325-1 1325-2 Repair Techniques for Improper Temperbead Spacing Example of Weld Undercut Repair 2200 System Test Requirements Technique 503

i CASE (continued) l N-236-1 l i

/N CASES OF ASME BOILER AND PRESStJRE VESSEL CODE .

(

1000 REPAIR PROCEDURES (3) The depth of mechanically removed material 1100 GENERAL shall be determined by actual measurements.

1110 ECOPE 1220 MECHANICAL REMOVAL PROCESSES This Case provides the rules and requirements for the welding and repair of components covered under (a) When a mechanical removal process is used m.

the scope of IWE-1100. an area where repair weldmg is not required, the area shall be faired into the surrounding area. After fmal grinding, the affected surfaces shall be examined by 1120 PROCEDURE the magnetic particle or liquid penetrant method to assure that the defect-has been removed.

Defects shall be removed or reduced in size in accor-dance with 1200. When the cavity created by remeral (b) When repair w 'ds are to be made, the require-of this defect exceeds the acceptance criteria ofIWA- ments of 1230 shall apply.

3000 and repair by welding is necessary, the rep.r welds shall be made in accordance with IWA 4000 and 1230 PREPARATION FOR REPAIR WELDING this Case.

When repair weldmg is required, the following shall apply, s ma ne r gr un smood 1200 REMOVAL OF DEFECTS INCLUDING * #'.

8n C can 5 Cle proe smtae ao PREPARATIONS FOR WELDING cessibilit y for welding.

Defects may be removed or reduced in size by ther. (b) After final preparation, the affected surfaces, in.

mal or mechanical removal processes, provided the cluding surfaces of cavities prepared for welding, shall (S requirements of this Case are satisfied, be examined by the magnetic particle or liquid pene-( trant method to assure that the defect has been re-moved.

1210 THERM E REMOVAL PROCESSES (c) Indic1tions, detected as a result of the excava-1211 Requiren,ents for P-No. I Materials tion, which are not associated with the defect.being removed shall be evaluated for acceptability in accor-(a) Preheating, when used, shall be specified in the dance with IWA 3000.

repair procedure.

(b) When carbon air are gouging or plasma are cut-ting is used, any scale on the gouged or cut surface 1300 REPAIK WELDING shall be mechanically removed in accordance with the following. 1310 APPLICABLE REQUIREMESTS (1) When repair welds are to be made, the re- Repair welds shall be performed and examined in quirements of 1230 shall apply, accordance with IWA-4120, except repair welding may (2) When repair welds are not required, approx- be performed in accordance with the requirements of imately S in. of material shall be removed and the 1320 or 1330 when the original construction require-area shall be faired into the surrounding area. ments are impractical.

(c) When oxyfuel cutting or other thermal removal processes are used, material shall be removed by a mechanical method from thermaily processed areas m, 1320 BUTTERBEAD TEMPERDEAD REPAIR accordance with the following.

(a) These requirements are for welding when the (1) When repair welds are to be made, a minimum size or configuration of the .gair leads to highly re-of b in. of material shall be removed from the cavity strained weld joints and when factors such as water to be repaired. In addition, the requirements of 1230 shall apply. backing make preheat and postweld heat treatments impractical.

(2) When reprir weids are not required, a mini.

. n) (b) This repair technique is limited to P-No.1 Gr.

mum of b in. material shall be removed and the area - No. I and P-No. I Gr. No. 2 pressure boundary ma-shall be faired into the surrounding area. terial.

504

CASE (c;ntinued)

O CASES OF ASME BOILER AND PRESSL1RE N-236-1 VESSE 1321 General Requirements (a) The shielded metal are welding process if peening (SMA W) is used, it shall be considered as a sariable in the welding procedure.

using low hydrogen electrodes shall be used.

(b) The following rules sh:11 apply for lowminimize (g) Fabrication and welding shall be sequence hydrogen electrodes used for the repair welding. the effects of restraint.

(1) After receipt from the electrode manufacturer and before use, all covered electrodes shall be1322 baked Welding Qualifications. The welding proc dure and welders shall be qualified in accordan at the electrode manufacturer's recommended Section baking IX and the additional requirements of S temperature. In no case shall the baking temperature be less than 6507 or greater than 3507. The tem. III, except through as modified or supplemented by 132 1322.3.

perature of the oven shall not exceed 300T when the _

electrodes are inserted for the baking cycle. The tem- Procedure Qualification. Welding pro 1322.1 perature shall not be raised more than 300T/hr. The dure qualification tests shall be performed in ac total time above 500T, including the holding time, dance with Section IX for groose welds and the shall not exceed 5 hr. After baking and before ditionalcooling requirements of NE-4000. Impact test below 2257, the electrodes shall be transferred to the requirements and acceptance criteria shall be as r holding or drying ovens and maintained at 2257-350T. quired by the Design Specification for the comp base material (2) During repair welding, electrodes shall be maintained in heated ovens or heated portable con- 1322.2 Performance Qualification.The welders tainers in the repair area until used. The oven tem shall be qualified on a radiographically examine perature shall be maintained between 2257 and 350T.- groove weld test in accordance with Section IX and Electrodes shall be used within 2 hr by the holding or drying ovens or heated portable con-after removal from performance of the production test requir A 1322.3. The welder shall use the production V tainers. Electrodes removed from heated more than 2 hr, but less than 4 hr, shall be returned ovensSpecification Procedure obstructions.

for and simulate typical p to a holding oven and held at a temperature between 2257 and 3507 for at least 8 hr before use. 1322.3 Electrodes Production Test. In addition to the pro removed from heated ovens or heated portable con. cedure qualification test equirements of 1322.1, on tainers for a period in excess of 4 hr shall be rebaked production test is required prior to any repair w in accordance with (b)(1) above beforeproduction shall not be rebaked more than once.

A use. Electrodestest simulates repair welding using variables listed in (a) and (b) below. A produc1 n t (c) Welding materials used in the repair shall be assembly may consist of one or more production test controlled during repair so that thef are identified as acceptable material until consumed. The variables listed in (a) and (b) below uated by performing a production test. The productio (d) Welding material contaminated with oil grease

, test assembly shall be evaluated by performing the water, or other foreign material shall not be used examinations required by (d) below, (e) All welding material shall conform to the ma(a) The production test base material that represe terial testing requirements of NE 2000. For each thelot-pressure boundary shall be of the sa:ne mater of covered electrodes, weld metal tests shallspecification, be made type, class, group number, or grade a in accordance with test requirements of NE-243i.

1 and boundary material to be repaired by the pressure the coupons shall be tested in the as-welded ing. condition All other material shall be of the same P-Numb Impact test requirements and acceptance criteria shall.

as those to be used in the repair. When the origina be as required by the Design Specification formaterial the com- is no longer manufactured, material similar ponent base metal to be repaired.

to the original material specification may be substi

(/) Controlled peening of welds may be performed tuted. Electrodes used for the production test shall be to minimize distortion, provided it is also used the on the same specification and classification as those us welds made to qualify the repair procedure and the for the weld repair and shall be treated as requ p$ production test assembly. Peening shall not be1321(b). used on Q,) the initial layer of the weld metal or on the final .

layer (b) The production test shall simulate the repair.

The following parameters shall be recorded:

505

I CASE (continued)

N-236-1 O

/

CASES OF ASME BOILER AND PRESSURE VESSEL CODE V (1) all essential and supplementary essential var.

er deleterious cond'itions shall be cause for rejection of iables listed for the process in Section IX; the prcxiuction test.

(2) nominal pressure boundary base metal thick-ness: (#) e minimum of two microhardness traverses shall be taken from one cross section for each pro-(3) maximum nominal attachment base metal duction test. The traverses shall be taken from areas thickness; of maximum anticipated hardness including the toe of (4) weld joint geometry (including joint design the butterbead layer as shown in Fig.1323-1. The and fit up tolerances) and the maximum nominal weld indentation spacing of the heat affected zone (HAZ) thickness. For fillet welds, the nommal thickness is the throat thickness, and for groove welds, the nominal microhardness traverse shall consist of not less than thickness is the depth of the weld groove. ten indentations. Hardness values for the traverse shall be recorded. The maximum hardness for the pressure (J) restraint on the weld joint; the restraint shall boundary HAZ shall not exceed 400 KHN (500 gram be maintained on the product on test assembly for a load).

minimum of 48 hr after the completed weld has reached ambient temperature; (6) weld sequencing (both fabrication steps and 1323 Welding Technique. Welding shall be in accor-order of bead sequence);

dance with the following.

(7) weld position (see Section IX);

(a) Prior to welding, the area to be welded shall be (S) water backing and water temperature within spectfied tolerances, as applicable; examined by rngnetic particle or liquid penetrant methods in accordance with Subsection NE.

(9) actual weld electrode sizes to be used for the (b) All surfaces to Sc welded and the surrounding butterbead layer and the temperbead or temperbead layer; areas shall be clean and free of scale, rust, moisture, or other surface contaminants.

(10) range of electrode si.es to be used to complete O the weld joint; (c) The minimum preheat temperature specified in d (111 preheat and preheat maintenance within tol-the Welding Procedure Specification and the produc.

tion test 1322.3 shall be maintained during tack weld-erances specified in the WelJing Procedure Specifica- ing and until completion of the weld.

tion; (d) The maximum interpass temperature shall be (121 peening, as applicable; $00*F.

(13) guides, templates, and fixtures used for weld placement, as applicable; (e) Welding shall consist of the application of a butterbead layer, followed by temperbeads or a tem-(141 maximum temperbead edge clearance (dimen-sion 5) as shown in Figs.13231 and 1323 2 and the perbead layer. Butterbead and alternate temperbead placement is shown in Fig.13231, detail (a). Similar minimum temperbead e9e clearances shall be re-corded; application of the temperbead technique for the rein-forcement of fillet welds is shown in Fig.1323-2. The (15) maximum weave width for the butterbead technique described in this paragraph shall be per-layer.

formed in the production test and actual work.

(c) The production test shall be of rufficient size to

(/) No postweld heat treatment is required.

permit removal of the test specimens required in (d) below.

(d) The production test shall be evaluated as follows:

(1) visual examination in accordance with IWA-2000 (VT-3) for compliance with the Welding Proce-dure Specification; 1324 Examination (2) surface examination and acceptance of the (a) The completed weld shall be visually examined welds in the completed test assembly in accordance with Subsection NE; (VT 1) in accordance with IWA 2200.

(b) The completed weld and a band 1 in. on either (J) examination of two cross sections for each side of the weld shall be examined by the magnetic production test is required. The cross sections shall be particle method not less than 48 hr after the completed polished and suitably etched and examir.ed at X 10 (Q) magnification. Cross sections containing cracks or oth- repair has reached ambient temperature. The accept-ance criteria of Subsection NE shall be met.

506

l CASE (Entinued)

N-236-1 CASES OF ASME BOILER AND PRESSURE VESSEL CODE O

Temperbead Attachment (optional but same as productson

, test)

Weld out to site and profile f Detail (a) of (b)

(mandatory for f g pressure

\ boundary)

Pressure ~~ - - ~ - - - -- ----

arv

/

r Typical microhardness traverse locath (see detav '*)'

Typical microhardness Bunerbead Typical mecrohardness entse location Temperbead '8Y" traverse location Temperbead Isee deta i ic))

layer (see detail (c)]

Butterbead

~ ".'. %'," "

S

-k S i

.J Detail f a)

Detail (b) 0 -- A -

"*d V-0.010 in. - -

0.020 in. - . -

0.030 in. - - -

y HAZ 0.040 in. - -

0.050 in. - - .-

0.0G0in. ~ . - , .

Detail le) (Typecall 0.070 in. - - -~

_-___ A Base metal GENERAL NOTES:

(a) Butter layer may also be deposited as weave bead between buttertrad or temperbead.

(b) H weave bead la used, initial and final weave passes must be accompanied by temcerbead.

{c) If stnnger technique is used, ends of stringer passes must be accompanied by temperbead.

(d)minimum In electrode selection, tensile strength preference specified for the baseshould metal, be Oiven to electrode types with as-welded yield strengths e which do n o )- FIG.1323-1 TEMPERBEAD TECHN!QUE 507

CASE (continued) l N-236-1 l

CASES OF ASME BOILER AND PRESSURE VESSEL CODE O SY (See detail (a) or (b), '

Fig.132311

,' d s #' / i et

/ 1

. F '

s ~

I i , ! A x

N Attachment \ Pres:ure N, retaineng N boundarv

\

N N

N O '

FIG.1323-2 ILLUSTRATION OF THE TEMPERGEAD TECHNIQUE FOR REINFORCEMENT OF EXISTING FILLET WELDS 1325 Repair Techniques 2000 SYSTEM PRESSURE TESTS (a) Defects contained wholly in the weld metal shall 2200 SYSTEM TEST REQUIREMENTS be repaired in accordance with NE-4400, except as noted in (b) below. 2210 GENERAL (b) Improper application of the temperbead or de- Except as noted in 2240, the requirements of IWA-fects in the butterbead or temperbead shall be repaired 5000 are not applicable to Class MC components, by application of a new butterbead and temperbead as shown in Fig.1325-1.

(c) The repair technique fet undercut greater than 2220 TESTS FOLLOWING REPAIR, d2 m. is shown m, Fig.1325 2. MODIFICATION, OR REPLACEMENT 2221 Leakage Test. Except as noted in 2222, repairs or modifications to the pressure retaining boundary or 1330 HALF BEAD REPAIR replacement of Class MC components shall be sub-jected to a pneumatic leakage test m accordance with As an alternative to 1310 and 1320, the half bead the provisions of Title 10, Part 50, of the Code of p welding process shall be used for weld repairs and the Federal Regulations, Appendix J, Paragraph IV.A, V requirements of IWB-4320 shall be met. which states:

j l

l 508

CASE (continued) oQ CASES OF ATME BOILER AN'D PR'S'N-236-1 SURE VESSEL CODE

~ * = ;r --

- '==:

T/N7/A /

Step

L/////Z St*01

' / New butterbead New butterbead o

.s W_HA _

$tep 7 M /XA Step 2

%w temperbead

\)f New temperbead G/MJ Step 3 (O?l/A

-> 7f tel Spacing Too Large Step 3 (bl Spacing Too Smett F1G.13251 REPAIR TECHNIQUES FOR IM PROPER TEMPERGEAD SPACING O 1 se

CASE (continued) ,

(

N 236-1 CASES OF Mf E BOMR AND MESSURE YESSEL CODE Undercut greater than 1/,12 in. deep

^ ~

T/////////

L.......

St.. ,

,.t..n, boundary New butterbead O T///////J (Properationcem2..

with 1200.)

Step 2

'> nperbead V///~/' ///1 Step 3 FIG.1325-2 EXAMPLE OF WELD UNDERCUT REPAIR TECHNIQUE O

$10

_ _ _ - _ - _ - - - - - - - _ - - - - - - - - - - - - - - - - - - - ~ - '

CASE (corttinued)

CASES OF ASME Bolt 1R AND PRESSURE N-236-1 YESSEL C "Any major modification, replacement of a component which is part of the primary reactor containment 1000 and leakage testing shall be reperformed as boundary, or resa:aling a seal welded door, quiredperformed by 2220, prior to returning the component to after the preoperational leakage rate test shall be fol- service.

lowed by either a Type A Type B, or Type C test, as applicable for the area affected by the modification. 3000 The measured leakage from this test shall be INSTALLATION included OF REPLACEMENTS in the report to the Commission, required3100 by SCOPE V.A The acceptance criteria of Ill.A.S.(b), Ill.B.3., or lil.C.3, as appropriate, shall be met. Minor modifications, Thisre-Section installation provides the rules and requirements of replacements.

formed directly prior to the 3300 conduct of a scheduledplaceme Type A test do not require a separate test." INSTALLATION NOT REQUIRING 2222 WELDING Deferral of Leakage Tests. Leakage tests for 3310 the following minor repairs or modifications to the MECHANICAL JOINTS pressure retaining boundary may be deferred until the Mechanicaljoint: 3 hall meet the requirements of the next scheduled leakage examination is performe test, provided nondestructive original Design Specification. Alternatively, the re-pro /ed repair program: d in accordance with thequirements ap- of Section III, NE-4700, may be used, p vided the requirements of IWA 7210 are met, (a) welds of attachments to the surface of the pres-sure retammg boundary; 3320

, (b) repair cavities, the depth of whi:h does not.

BOLTED pen CONNECTIONS etrate the required design wall by more than 10%; Boltedandconnections shall meet the requirements of (e) welds smaller, attaching penetrations that are NPS 1 or the original Design Specification. Alternatively the ,

methods of Section III, Appendix E, may be used, 2240 provided the requirements o'IWA 7210 are met.

VISUAL EXAMINATION 3400 The requirements of IWA $246 for visual examl- INSTALLATION REQUIRING WELDING nations are applicable, Welds joining replacements to the existing system 2250 shall be made in accordance with IWA 4000 CORRECTIVE MEASURES 3600 MATERIALS If the leakage test requirements of 2221 cannot be satisfied, the source ofleakage shall be located and the shall comply with the requirements to Materials area shall be examined to the extent necessary to es-which the original component or part was constructed.

tablish the requirements for corrective action. Repairs naterials may comply with the require-AIMrnatively, shall be performeu in accordance with the rules mentsof of Section III, NE 2000, provided the require-ments ofIWA 7210 are met.

n v .

511

CASE N-355 f-e . , CASES OF ASME BOILER AND PRESSL'RE VESSEL CODE l 1 Approval Cate: July 16,1982 See Numer'c Index fo. espiration l nnd any restfirmation dates. )

l l

, Case N 355 practical, deposition of the cladding shall be by the !

Calibration Block for Angle Beam Ultrasonic manual method.

Examination of Large Fittings in Accordance With (/) The fmish on the examination surfaces of the Appendix III 3410 block shall be representative of the surface fmish of Section XI, Division 1 the applicable fitting or component examination sur-faces. -

Inquiry: When ur,ing Appendix Ilt of Section XI, (3) Search Unit and Couplant Selection Division 1, may flat calibration blocks be used for Section V, Article 5, Appendix A shall be applied ultrasonic examination of elbows or other 6ttings with for determining the critical radias for arigle beam ex-compound curvatures if the elbow or fittings has an aminations. The minimum radius of the fitting to W outside diameter greater than 20 in? examined shall be determined. The search unit wede size, couplant, and frequency shall be selected so that Reply: It is the opinion of the Committee ' hat flat the minimum radius is greater than the critical radius calibration blocks may be used for ultrasonic czami- as determined by Appendix A. If rectangular search nation of cibows or other fittings with compound cur- units are used, the dimension of the search unit face vatures if the elbow or fitting has an outside diameter tangent to the minimum radius shall be used instead greater than 20 in., provided the following require- of the transdt er diameter in Table A 10 of Appendix ments are met. A.

{} (1) Scope (4) Re niing and Reporting V A flat calibration block may be used for ultrasonic (a) /.11 indications 50% of DAC or greater shall examination of any weld within the fitting, fitting to be recorded.

6tting weld, or component to fitting weld. For pipe to (b) All indications 100% of DAC or greater shall tit:ing or pipe to component welds, the examination be investigated by a Level II or Level Ill examiner to shall be performed from the pipe side using Appendix the extent necessary to determine the shape, identity, III calibration blocks, and location of the reflectors.

(1) Block Material (c) All indications 20% of DAC or greater orig-(a) The basic calibration blocks shall be made inating in the heat affected aone or base metal shall from material of the same nominal thickness or pipe be investigated by a level II or Level III examiner to schedule as the fitting to be examined. the extent necessary to determine the shape, identity, (b) Where the examination is to be performed and incation of the reflector, from only one side of the joint, the caEbration block (d) The following shall be recorded on an ex-material shall be of the same specification as the ma- amination data sheet:

terial on that side of the joint. (1) Data sheet identification, date, and time pe-(c) If material of the same spxificatio is net riod of examination; available, material of similar chemical analysis, tensile (2) Names and SNT-TC-1A levels of exami-properties, and metallurgical structure may be used. nation personnel; (d) For calibration blocks for disrimilar metal (3) Examination procedure and revision; welds, the material selection shall be based on the side (() Applicable calibration sheet identification; of the weld from which the examination will be con- (S) Identification and location of weld or vol-ducted. If the examination will be conducted from buh ume scanned (for example, marked-up drawings or tides, calibration reflectors shall be provided in cali- sketches);

bration blocks of both materials. (6) Surface from which exammation is con.

(e) Where the component material is clad, blocks ducted; and q shall be clad by the same welding procedure as the (7) Record of indications or of volume free of

(% ) production part. Where the automatic method is im- indications:

$99

_ _ _. _ ___ _ . _ ___. _ . . ._._ _ . . _ _ . _ ~ . _ _ . . _ _ . . . . . _ _ . . _ _.._._.-_ _ .- . .__ .__ .___.

CASE r Atlk DF ASME MHLER AND PRf3SL'RE VL$$tt CODE .

N-389 4

(

ApproveI Dete: December 9.1993 See knenc inon for espiration endany restformation dates.

R Case N4891 1

Ahernatne Rules for Repairs Replacements, t e ModllicationsSection XI. IHvision !

Inquiry! When making a repair, replacement, or mod-ification in accordance with the requirements of Section XI Division 1, which Editions and Addenda of Sectl<m XI may be used as an alternative lo those specified in the Owner's inse vice Inspection Program?

Reply!It is the opinion of the Committee that Editions those specified in the Owner's Inservice Ins 4

gram may be used for repair, replacement, or m(xlifi.

cation. Specific provisions within an Edition or Ad-denda later than those specified in the Owner's inservice Inspection Program may be used, provided all related requirernents are met. The later Edition and Addenda 1 story authorities having jurisdiction at the .

This Case number shall be shown on the NIS 2 Form 4

T 9

721 h '-

$ i. -p E ',

_ ,-~w- _ ~ . --

CASE N-416-1 O CASES OF ASME DOILER AND PRESSURE VESSEL CODE Approval Dete: Fotmwy 16,1994 l See niumeric indea for espiretson end any reaffirmation detes.

Case N 4161 placement items by welding, a system leakage test may Alternstlie Pressure Test Requirement for Welded be med provided the following requirements are met.

Repairs or Installation of Replacement items by (a) NDE shall be performed in accordance with the l Welding. Class I,2 and 3 methods and acceptance crite*ia of the applicable Sub-Section XI. Division I section of the 1992 Edition of Section !!!.

(b) Prior to or immediately upon retum to service, a visual examination (VT 2) shall be performed in con-

/nquiry: What attemative pressure test may be per- junction with a system leakage test, using the 1992 Edi-formed in lieu of the hydrostatic pressure test required tion of Section XI, in accordance with para. IWA 5000, by paru. IWA 4000 for welded repairs or installation of at nominal operating pressure and temperature, replacement items by welding? (c) Use of this Case shall be documented on an NIS-2 Fonn.

Replyt it is the opinion of the Comrmitee that in lieu If the previous version of this case were used to defer of performing the hydrostatic pressure test required by a Class 2 hydrostatic test, the deferred test may be clim-para, lWA 4000 for welded repairs or installation of re- insted when the requirements of this revision are met.

..l ,

N 4

e 7

d 769

CASE N-432 CASE /, OF ASME BOIt.ER AND PRESSURE VESSE1. CODE V

Approval Date: February 20,1986 See Numeric Index for expiration and any restfirmation dates.

Case N 432 2.1 Prvcedure Qualifications Repair Welding Using Automatie or Machine Gas (a) The test assembly materials for the welding Tungsten Arc Welding (GTAW) Temper Bead procedure qualifi ation shah be of the same sPecifi-Technique cat. ion type, grade, and class as the materials be,mg Section XI, Division 1 repaired. The test assembly shall receive a postweld heat treatment that is at teast equivalent to the timc Inquiry: May the automatic or machine GTAW and temperature applied to the materials being re-process be used as an alternative to the SMAW proc- paired. The procedure and performance qualifica.

ess for performing the temper bead technique on ti n tests may be combm, ed, provided Section IX re-Class 1 components? quirements are met. The test assembly dimensions, including joint details, shall be documented on the Reply: It is the opinion of the Committee that re. PQR.

(b) The test assembly thickness shall be at least pair to P Nos.1,3,12A,12B, and 12C' base material and associated welds may be made by the automatic five times the depth of repair, but need not exceed or machine GTAW temper bead techriique without the thickness of the material to be repaired provided the specified postweld heat treatment requirements the required test specimens can be removed. When of Section III, provided the requirements of 1.0 the thickness of the base metal to be repaired is greater than 2 in., the depth of the cavity in the test p)

("

through 5.0 below are met. The depth of repair is not limited provided the test assembly meets the re.

assembly shall be the greater of 1 in. or the depth of the cavity to be repaired. However, in no case shall quirements of 2.1.

the procedure qualification test assembly be less than 2 i't thick, nor shall the depth of the cavi'j in the 1.0 GENERAL REQUIREMENTS *'h)" st 5 i nsions surrounding the (a) The requirements of IWA-4000, as applicable, cavity shall be at least the thickness of the component shall be met. at the location of the repair or 6 in., whichever is (b) Only the automatic or machine GTAW process greater. If the repair weld is to be performed ee-using cold wire feed shall be used. No are ncillation motely, the procedure qualification test assembly shall be taed, stu.Il be completed with the same or duplicate sen-(c) Welding materials shall be controlled during sing and control equipment to be used for the repair, repair so that they are identified as acceptable ma- The test assembly shall simulate the position and ob-terial until consumed. structions of the actual repair.

(d) The neutron fluence in the repair areas shall (i) The root width and the included angle of the be taken into account wher, establishing the weld cavity in the test assembly shall be no greater than rnetal composition limits, the minimum specified to be used in the repair.

(c) Peening shall not be permitted. (c) This test assembly may be used to qualify pro-cedures for weld buildup of pressure retaining ma-terials. For this application, the depth of the cavity "9 WE1. DING QUALIFICATIONS shall not be less than the thickness of the weld build-up or 1 in., whichever is greater. In addition, the stea The Welding Procedure Specification and the of the cavity shall not be less than the area of he welding operators shall be qualified in armrdance weld buildup to be applied or !1 sq in., whichever is with Section IX and additional requirements of Sec- less.

tion Ill, as modified by 2.1,2.2, and 3.0(c) and (d). (f) For all applications, the test assembly and cav-14 ity shall be of sufficient size to obtain the required test specimens.

P-Nos. t2A. t2B, and 12C designations refer to specific resterial ,

ci ssincation. orisinally identified in section III. and oubsequently (g) Welding matenal shall meet the requirements reclassified in a ta:er edition of Section IX. of Sections IX and III, and the Edition and Addenda

, 777

CASE (c:ntinu:d)

N-432 CASES OF ASME BOlli.R AND PRESSURE \T.SSEL CODE f

I step 1: Dormit I l i yer one wnh I tir i i.yer weid f parameters used in ouslefications.

lI l

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$tep 2: Depolst l leyer two with i .econd itver weid f parameters used 66 l QuelsfacetaOnt O ,

l, ,t.p m.

_f_

t

,.y.r.

I wnh I.ver ihree

.j l. through sin weld I peremetera used in qualif cations l l i \

I lIj lk Step 4: Sutmquent w f leyers to be I depoined 8.

oustified.

FIG,1 AUTOMATIC OR MACHINE (GTAW) TEMPER BEAD TECHNIQUE O

779

CASE N-457

%, CASES OF ASME BOILER AND PRESSURE VESSEL CODE

).

Approval Date: December 7,1987 See Nun'eric Indes for expiration and any restfirmation dates.

Case N 457 Qualification Specimen Notch location for Ultrasonic Examination of Bolts and StudsSection XI, Division 1 Inquiry When qualifying ultrasenic techmques for -

.' bolt or stud examination in accordance with Section XI, Division 1 Yl 2430, may the qualification notch for manmum metal path qualification be located with-in one bolt or stud diameter from the end opposite the search unit?

Reply: It is the opinion of the Committee that for Section XI, Division 1, VI 2430, the qualification notch may oc located within one diameter from the end op-posite the search unit to demonstrate the ultrasonic technique qualification for the entire length or maxi-mum metal path of the bolt or stud.

we Q 4 813

CASE

! N-458-1 CASES OF ASME BOILER AND PRESSL'RE VESSEL CODE u

Approval Date: March 14,1995 See Numeriest index for expiration ant' any restfirmaticn dates.

Case N 4581 held by surface irregularities)

Magnetic Particle Examination of Coated Materials (f) lastructions for identification and confirmation Section XI, Dirision 1 of suspected flaw indications (k) recording criteria Inquiry When ccraducting magnetic particle ex- (I) personnel qualification requirements amination (MT) in accordance with Section XI, Dl. (m) reference to the procedure qualification rec-vision 1 IWA 2221, which references Article 7 of ordsSection V, what supplementary rules may be used for (n) method of verifying that the yoke lifting power examining coated ferritic materials by the AC yoke and the illumination source used in the production technique without removing the coating? examination are at least as great as specified.

Reply: It is the opinion of the Committee that mag-2.0 EQUIPMENT netic particle examination may be conducted in ac-cordance with IWA 2221 using the AC yoke tech- (a) A powered powder blower which provides for nique on coatt.d ferritic materials without removing controlled, continuous powder application shall be the coatirig, when the applicable requirements of utilized for application of dry powder. Hand v Section XI, Division 1, and the following require- squeezed particle applicators shall not be used.

ments are met. (b) Magnetic particles shall contrast with the com-ponent background.

(c) Nonconductive materials such as plastic shim 1.0 PROCEDURE stock may be used to s*mulate nonconductive coat-ins 5 f r Procedure and personnel qualification.

Magnetic particle examination shall be performed in accordance with a written procedure. The proce-dure shall include the following: 3.0 COATING TIIICKNESS (a) identification of surface configurations to be MEASUREMENT examined, meluding coating materials, maximum qualified coating thickness, and product forms (e.g., Procedure demonstration and periormance of ex.

base material or welded surface) aminations shall be preceded by measurement of the (b) surface condition requirements and prepara- coating thickness in the areas to be examined. If the tion methods coating is nonconductive, an eddy current technique (c) manufacturer and model of AC yoke may be used to measure the coating thickness. If the (d) manufacturer and type of magnetic particles coating is conductive, a magnetic coating thickness (c) minimtr.n and maximum yoke leg separation technique shall be used in accordance with ASTM (f) method of measuring coating thickness D1186. Coating measurement equipment shall be (g) identification of the steps in performing the used in accordance with the equipment manufactur-examination er's instructions. Coating thickness measurements (h) minhnum lighting and AC yoke lifting power shall be taken at the intersections of a 2 in. maximum requirercents (as measured in accordance with 4.0 grio pattern over the area of examination and at least below) % the maximum yoke leg separation beyond the ex-(i) methods of identifying flaw indications and dis- amination area. The thickness shall be the mean of criminafmg between flaw indications and nonrele- three separate readings withm % in. of each inter.

(%y vant indications (e.g., magnetic writing or particle section.

815

CASE (continued)

N-458-1 CASES OF ASME BOHE.R AND PRESSURE ST.SSEL CODE

9.0 REFERENCES

TO TECIINICAL REPORTS The following Electric Power Research Institute reports are relevant to this Case. Requests for copies should be directed to EPRI Research Reports Cen-ter, Box 50490, Palo Alto, CA 94303.

NP 5834 - Nondestructive Exarninati on of Welds Through Painted Surfaces, May 1988.

~

NP 5951 - Reliability of Magnetic Particle Inspec-tion Performed Through Coatings, July *

~,

4988.

O Q

_ _ - - - - - - - - - - - - - - - - - - - ~ - ~

CASE i

i CASES OF ASME BOILER AND PRES $tJRE VESSELN-460 CODE Approval Date: July 27,1988 See Numeric Iresen for espiration and any restformation dates.

Case N 460 Alternative Examination Coretage for Cass 1 and Cass 2 Welds Section XI, Division 1

- Inquiry: What titernative rules may be used- for Section XI, Division 1, examination of Class I welds (IWB-2$00) or Cass 2 welds (IWC 2500) when the entire examination volume or area cannot be examined due to interference by another component or part ge-ometty?

Reply: It is the opinion of the Committee that when the entire examination volume or area cannot be ex-amined due to interference by another component or part geometry, a reduction in examination coverage on any Class 1 or Cass 2 weld may be accepted provided the reduction in coverage for that weld is less than O 10% The applicable examination records shall identify both the cause and percentage of reduced examination coverage.

0 819

CASE N-472

^

CASES Di' ASME BOILER AND I'R1351)AE VESSEL CODE Approval Date: March 8,1989 See Numeric It' des for expiration and any restformation dates.

Case N-472 Use of Digital Readout and Digital Measurement Derices for Performing Pump Vibration Testing Section XI, Division 1

~

Inquiry: Under what conditioas may digital vibra ~

~

tion measuring instruments be used for pump vibration testing under IWP 40007 Reply: It is the opinion of the Committee that digital vibration measuring instruments may be used for pump vibration testing under IWP-4000 provided the follow-ing are met:

(a) calibration requirements of IWP-4140; (b) instrument system accuracy within 5% over the calibrated range; (c) position requirements of IWP 4160; and (d) vibration amplitude requirements of IWP-4500.

O. The instrument range requirerr.ents of IWP-4000 shall not apply.

O Q

871

CASE i N-485-1 l CASES OL' AsME DOJJJL AND PRESStlRE VESSEL CODE

%J Approval Dete: August 14,1991 See Numericalindex for expiration and any reemrmation detes.

Case N 4851 vant indications (e.g., indications from probe lift-off, Eddy Carroat Eaam' ation of Coated Ferritic coating thickness variations, or permeability changes Surfaces as an Alternative to Surface Examination in the ferromagnetic materials);

Section XI, Dielslon 1 (m) instrueon for identification and confirmation of suspected & .idications;

, Inquiry: May an eddy current test method (ET) (n) recording criteria;

. technique be used to examine coated ferritic surfaces (o) personnel qualification requirements; as an alternative to the surface examination of Sub- (p) reference to the procedure qualification re-section IWA, IWA 22207 cords.

Reply: It is the opinion of the Committee that an ET technique may be used to examine coated ferritic 2.0 EQUIPMENT surfaces as an alternative to the surface examination of IWA 2220, when the applicable requirements of The ET system shall include phase and amplitude display.

l Section XI, Division 1 and th . lowing require-ments are met:

3.0 COATING THICKNESS MEASUREMENT 1.0 PROCEDURE Procedure demonstration and performance of ex-aminati ns shall be preceded by measurement of the Eddy current examination shall be performed in coating thicknesses in the areas to be examined. If accordance with a nrkten procedure. The procedure the coating is nonconductive, an eddy current tech-shallinclude the foisowing:

, . nique may be used to measure the coating thickness.

(a) identification of surface configurations to be If the coating is conductive, a taagnetic coating thick-examined, including coating materials, maximum ness technique shall be used in accordance with qualified coating thickness, and product forms (e.g.,

base metal or welded surface); ASTM D1186. Coating measurement equipment shall be used in accordance with the equipment ma (b) surface condition requirements and prepara-uf er's instructions. Coating thickness measure-ments shall be taken at the intersections of a 2 in.

c) 4 d type of probes, description, part or

' maximum grid pattern over the area to be examined.

drawing number, and length of probe cable;

~~

(d) manufacturer and model of eddy current The thickness shall be the mean of three separate readings within /, in. of each intersection.

equipment; (c) data recording equipment and method; (m um n s e and scan index; 4A EM WMCAN (h) scan pattern; (a) A qualification specimen is required.%e ma-(i) method of metauring coating thickness; terial used for the specimen shall be the same as the (f) identification of calibration procedure and ca- coated ferromagnetic material to be examined. If a libration stardards; conductive primer was used on the material to be (k) examination technique (e.g., scanning instrue. examined, the primer thickness on the procedure tions, hand probe or mechanized probe device); qualificatica specimen shall be the maximum allowed (l) method of identifying flaw indications and dis-(y} criminating between flaw indications and nonrele-on the examination surfaces by the coating specifi-cation. Plastic shim stock may be used to simulate 903

~ , , , - ,, .-

CASE N-490-1 ;

CASES OF ASbfE SOILER AND PRESSt/RE W.6SEL CODE r t

Apptevel Date: May 13,1tti See NumericalIndex for expiration '

and any reaffirmation dotes.

Case N 4901 TABLE 1 NEAR-DISTANCE ACUITY TEST Alternative Vision Test R:;iants for DISTANCES AND CHARACTER HEIGHTS 2 Nondestructive Examiiners Maniene Low can Section XI, Divisions 1,2, nad 3 Test Distance (in.) Character Height (in.)

~

Inquiry: What alternatives to the near-distance vi- 12 o.on sion test requirernents of Section XI, Divisions 1,2, 13 o.024 and 3 may be applied for nondestructive examiners? 14 0.025

, is o.o n l

. Reply: It is the opinion of the Committee that the following alternative requiremeats may be applied in GENERAL NOTE: The test distances (eye te charo and correspond lieu of Section XI, Divisions 1,2, and 3 near distance ing character heipas prwide a visual ancie of 6.25 minutes, which Inpaienne a snenen framon of ms.

vision test requirements for nondestructive exam.

i iners:

(a) Personnel shall demonstrate natural or cor-rected near distance acuity of 20/25 or greater Snel-len fraction, with u least one eye, by reading words or identifying characters on a near distance test chart such as a Jaeger chart that meet the requirements of use, with an optical comparator (10X or greater) or

! (b) below Equivalent measures of near distance acu- other suitable instrument, to verify that the height of ity may be used. a representative lower case character without an as-(b) A measurement of one of the near distance cender or descender, for the selected type size, meets test chan .haractea shall be made once before initial the requirements of Table 1.

O 911

CASE N-491-1 CASES Or ASME It0lLEk AND PRESSURE VLSSEL CODE

}

s Approval Date: April 30,1993 See N smeticalIndex for expiration and arty restfirmatiots c'aus.

Case N-491 1 1000 SCOPE AND RESPONSIBILITY Alternative Rules for Examination of Class 1. 2,3, and htC Co nponent Supports of Light Water 1100 SCOPE Cooled Pos+er Plants This Case provides alternative rules for inservice Section XI, Disision 1 inspectica of Class 1.,2,3. and hic component sup.

ports.

1200 CON 1PONENT SUPPORTS SUBJECT Inquiry. What alternative exammation require- 'I'O EXAh11 NATION AND TEST ments to those stated in Section XI, Division 1, Sub-scetion !WF may be used when determining the com- 1210 Examination Requirements ponent supports subject to examination and g ,, ;

establishing requirements for component supports. following:

(a) piping supports; (h) supports otner than piping supports.

Repk It is the opinion of the Committee that the 1220 Snubber Inspection Requirements

. following alternative rules may be used for determin-ing component supports subject to examination and The insenice inspection requirements for snub-for establishing examination requirements for Class bers sha!! be in accordance with the Section XI Edi-1,2,3, and htC component supports under Subsec- tion and Addenda specif;ed in the Owner's Insenice tion IWF,Section XI, Division 1. Inspection Program.

TABLE OF CONTENTS 1000 SCOPE AND RESPONSIBILITY -3000 STANDARDS FOR EXAhilNATION 1100 Scope EVALUATIONS 1200 Component Supports Subject to Exam- -3100 Evaluation of Examination Results ination and Test 3110 Presenice Examination 1210 Examination Requirements 3111 General

-1220 Snubber inspection Requirements 3112 Acceptance 1230 Supports Exe.npt from Examination 3120 Insenice Examinations

-1300 Support Examinatiori Boundaries 3121 General

-3122 Acceptance 2000 EXAhilNATION AND INSPECTION

-3200 Supplemental Examinations 2100 dcope 3400 Acceptance Standards 2200 Presenice Examination 3410 Acceptance Standards - Component -

2210 Initial Examination Adjustment. Repair, and Replacement Support Structural Integrity 2220

-2400 Inspection Schedule 2410 Inspection Program (q

g 2420 2430 Successive Inspections Additional Examinations TABLES

~

-2500 Examination Requirements -2410-1 Inspection Program A 2510 Supports Selected for Examination 2410-2 Inspection Program B 2520 hiethod of Examination -2500-1 Exardnation Categories 913

CASE (continued)

N-491-1 CASE.S OF AshtE BOILER AND l'R135t'RE VLSSEL CODE J,

1230 Supports Exempt from Earnination adjusted in accordance with 3000, repaired, or re-laced, Component supporis exempt from the examination requirements of -2000 are those cc'inected to com-(O m p rns at operate af a temperature ponents and items exempted from examination under greatu than M ( um, g nmmat Want opnam, se Owner shall perform an additional preservice ex-IWD 1220. IWC-1220. IWD 1220, and IWE 1220. In amination on the affected componen supports dur-addition, portions of supports that are inaccessible ing m f Howing the subsequent system heatup and by being encased in concrete, buried undergiound, e idown cycle unless determined unnecessary by or encapsulated by guard pipe are also exempt from evaluation. T his examination shall be performed dur-the examination requirements of -2000.

ing operation or at t,he next refueling outage.

1300 SUPPORT EXAMINATION llOUNDARIES Support examination boundaries shall be in ac. 2400 INSPECTION SCIIEDULE cordance with IWF 1300.

2410 Inspection Prognm (a) Insenice examinations shall be performed 2000 EXAMINATION AND either during normal system operation or plant out-INSPECTION ages.

(b) The required examinations shall be completed 2100 'SCO PF' in accordance with the inspection schedule provided The requirements of this Case apply to the ex- in Table 24101 or Table 2410-2.

(c) The inspection period specified in (b) above Os amination and inspection of component supports, but not to the inservice test requirements of IWF 5000. may be decreased or extended by as much as one year to enable a.1 inspection to coincide with a plant outage, within the limitations of IWA 2400 2200 PRESERVICE EXAMINATION (d) Following completion of Program A afier 40 years, successive inspecti n intervals shall fePow the 2210 Initial Esamination 10 year inspection interval of Program B.

(a) All examinations listed in Table 25001 shall be performed completely, once, as a preservice ex-2420 Successive inspections amination. These preservice examinations shall be extended to include ItXFe of all supports not ex- (a) The sequence of component support extmi-empted by -1230. nations established during the fir:t irupection inter-(b) Examinations for systems thu operate at a val shall be repeated during each successive inspec-temperature greater than 200"F durmg normal plant tion interval, to the extent practical.

operation shall be performed during or following in. (b) When a component support must be subjected itial system heatup and cooldown. Other examina- to corrective measores in accordance with 3000, that tions ma.' be performed prior to initial system heatup support shall be reexamined during the next inspec.

and cooldown. tion period listed in the inspection schedules of the inspection programs of -2410.

2220 en a na c trec e measmes are n t Adpistment, Repair, and Replacement required during the next inspection period as a result (a) Prior to return of the system to senice, the of .:.e examinations requir d by (b) above, the in-upplicable examinations listed in Table 2500-1 shall spection schedule m y revert to the requirements of be performed on component supports that have been (a) above.

/N t

v) i 914

CASE (continued)

N-491-1 O

v CASES OF ASME BOILER AND PRESSURE VESSEL CODE 2430 Additional Examinations (a) When component supports must be subjected to corrective measures in accordance with 3000, the cc nponent supports in idiately adjacent to those TABLE 2410-1 for which corrective action is required shall be ex-INSPECTION PROGRAM A amined. Also, the examinations shall be extended to include additional supports within the system, equal in number and of the same type and function as those Inspection a Ya f Esa na ns Enam n ns Credited, %

scheduled for examination during the inspection pe-Interval Plant Service Completed, %

. .. nod.

1:t 3 too 100 (b) When corrective measures ir. accordance with 3000 are required as a resuh of the additional ex-rnd 7 33 67 aminations, the remaining component supports with-

200 30' in the system of the same typ3 and function as in (a) 3rd is is 34 above shall be examined.

17 ao so (c)(1) When corrective measures in accordance 20 66 75 with 3000 are required as a result of the additional 23 too too examinations in (b) above, examinations shall be ex-tended to include all nonexempt supports potentially

.tn ,, , 3, 30 ts 34 subject to the same failure modes that required cor-33 so 67 rective measures in accordance with (a) and (b)

H 75 100 above.

'O 100 (2) These additional examinations shall include nonexempt component supports m other systems when support faih'"s requiring corrective measures indicate non system-related support failure modes.

(d) When corrective sneasures are, required by (c) above, the Owner shall examine those exempt com-TABLE 2410-2 Ponent supports that could be affected by the same INSPECTION PROGRAM B observed failure modes and could affect nonexcmpt inspection Period, Components.

Calendar Years of Plant Service Minimum Maximum inspection Within the Examinations Examinations 2500 EXAMINATION REQUIREMENTS Interval Interval Completed, % Credited, %

The following shall be examined in accordance 1st 3 16 3a with Table 2500-1.

7 50 67 (a) mechanical cormections to pressure retaining 10 100 100 components and building stnicture; sucensin 3 16 3 (b) weld connections to building structure; 7 so 67 (c) weld and mechanical connections at interme-10 100 100 diate joints in multiconnected integral ano noninte-gral supports; (d) clearances of guides and stop:, ag ment of supports, and assembly of support items; (c) hot or cold settings of spring rupports and con-stant load supports;

/G (f) accessible slidit.~ surfaces.

b 1

915

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TA8LE -2500-1 EXAMINATION CATEGORIES EXAMINATION CATEGORY F-A, SUPPORTS Itema support Type Emannnacon Requirements /

gO No. Esamined Fig. No.

Examinahen blethod Acceptance Standard Estentof Emandnation s

& rn h

Gee -2500) Fn-y of Emaminatien*

(O g F1.13 Class 1 Piping Sapports IWF-1300-1 vhual, VT-3 4 O i

-3410 25% of Oass l' s 3 E ach inspct.cn interwal F1.20 Class 2 P, ping Samports IWF-13001 Visuaf, VT-3 -3410 15% of Class 2' af Each aspecten irtervat F1.30 Class 3 Pip ng Supports I IWF-1300-1 Visual, VT-3 A -3410 10% of Class 3' Each anspection inte,wat F1.40 Supports Other than !

twF-1300-1 Visuet, VT-3 -3410

Piping Supports 100% of the supports

Each % tion inteeval 1

(Class 1, 2, 3, and MC) i

[

NOTES:

(1) Item numbers shall be categerbed to idr%Fy support types tv component supsIert bnction , Ate = 3supports such as one-directenal red hann 8 = sieports such as muttedirectional restraints; and C = supports that allow therrnal movement, such as springst (2)-- Themtotal percentageiesanapie

,,eper.n.i .,e shall be congrised of asprerts from each system (e.3, Mah $ team Feedweler

, , , n mndual or WHR) w4ere the i d pl a n.er.e, .f no e.e,t s pe,ts of e.a. t.pe and f.nnien wi in o.a. s,,te,r.. l (3)conveneats For enultiple components other than piping, within a system of sirniter design, funct% and service are required M be enamined. , me supports of only one of the enuatete p

[-- E (4)-.eTo the entent

.nter practical, the same sioports selected for esamination during the first inspection,interwas shall ve be eneWned during each successi I

t I

, 1 L

i

.- __ _ - _ _ _ __ _ _ _ _ __ . _ ~_ .__ .__ __ . _ _ _ _ _ .

CASE (continued)

N-491-1 CASES OF ASME 80!LER AND PRESSURE YESSEL CODE 1

2510 Supports Selected for Examination (2) improper hot or cold settings of spring sup-Ports and constant load supports; Component and piping supports shall be examined f3) ml581isnment f Supports; or in accordance with Table 2500-1. Component sup-H) ImPropur displacement settings of guides ports to be examine hall be the supports of tuse 58 components that are required to be examined under 8nfg ,0P5

, pair in accordance with IWA 4000 and reex-IWB 2500, IWC 2500, IWD 2500, and IWE 2500 by aminst: n m accordance with 2200; volumetric, surface, or visual (VT 1 or VT 3) exam-(c) replaurnent in accordance with IWA 7000 and ination methods. Piping supports Io be examined reexaminati n m, accordance with 2200.

shall be the supports of piping not exempted under IWB 1220, IWC 1220, IWD 1220, and IWE 1220. 3112.3 Acceptance by Evaluation or Test. As an alternative to the requirement of 3112.2, a compo-nent support that is unacceptable for senice may be i 2520 Method of Examination analyzed or tested to the extent 'iecessary to sub-The methods of exsmination shall comply with stantiate its integrity for its intended service. Records ,

those in Table 25001. Alternative methods of ex- and reports shall meet the requirements of IWA-amination meeting the requirements of IWA 2240 6000.

may be used.

3000 STANDARDS FOR 3120 Insenice Examinations EX.WINATION EVALUATIONS 3121 General. Inservice nondestructive examina-

, 3100 EVALUATION OF EXAMINATION tions performed during or at the end of successive RESULTS insper.' ion intervals to meet the requirements of Ta-ble 2.iOO-1 ;nd conducted in accordance with the 3110 Preservice Examinations procedures of IWA 2200 shall be evaluated by com-3111 General. The presenice examinations pet. Paring the results of examinations with the accept-formed to meet the requirements of 2200 shall be ance standards specified in 3400.

i i evaluated by comparing the examination results with 3122 Acceptance acceptance standards specified in 3400.

3122.1 Acceptance by Examination. Component 3112 Acceptance supports whose examinations do not reveal condi-3112.1 Acceptance by Examination. Component tions described in -3410(a) shall be acceptable for supports whose examinations do not reveal condi- continued service. Verified changes or conditions tions described in 3410(a) shall be acceptable for from prior examinations shall be recorded in accord.

service, ance with IWA-6220.

3112.2 Acceptance by Correction. Component 3122.2 Acceptance by Correction. Component supports whose examinations reveal conditions de- supports whose examinations reveal conditions de-scribed in 3410(a) shall be unacceptable for senice scribed in 3410(a) shall be unacceptable for conti-until such conditions are corrected by one or more nued Penice umil such conditions are corrected by of the following: one or more of the following:

(a) adjustment and reexamination in accordance (a) adjustment and reeraminatior, in accordance with 2200 for conditions such as with 2200 for conditions such as (1) detached or looseaed meenar.. cal connec. (1) detached or loosened mechanical connec-tions; tions;

(

917

l CASE (c ntinu:d) l N-491-1 Q CASES OF AkME BOILER AND PRESSt'RE VESSEL CODE U

(2) improper hot or cold settings of spring sup- 3400 ACCEFTANCE STANDARDS ports and constant load supports 3410 Acceptance Stas. .irds - Cotaponent (3) misalignment cf supports; or Support Structural Integrity (4) improper displacemerit tettings of guides and stops. (a) Component support conditions which are un-(b) repair in accordance with IWA-4000 and reex- acceptable for continued service shallinclude the fol-amination in accordance'with 2200; lowing:

(c) replacement in accordance with IWA 7000 arid (1) deformations or structural degradations of reexamination in accordance with 2200. fasteners, springs, clamps, or other support items; 3122.3 Acceptance by Evaluation or Test. As an (?) missing, detached, or loosened support alternative to the requirement of 3122.2, a compo- "'h) are strikes, weld spl. <:er, paint, scoring, 7

nent support or portion of a component support roughness, or general corrosion on close tolerance which is unacceptable for continued service may be analyzed and/or tested to the extent necessary to sub- machined or sliding surfaces; stantiate its integrity for its intended servic:. Records (4) improper hot or cold settings of spring sup-reports shall meet the reouirements of IWA- ports anu eunstant load supports; (5) misalignment of supports; (6) im-roper clearances of guides and stops.

(b) Except as defined in (a) above, the following are examples of non. relevant conditions:

3200 SUPPLEMENTAL EXAMINATIONS (1) fabrication marks (e.g., from punching, lay-out, berding, rolling, and machm, ing);

Examinations that detect conditions that require (2) chipped or discolored paint; Os evaluation in accordance with the requirements of 3100 may be supplemented by other examination (3) weld spla:!ct on other than close tolerance machined or sliding surfaces; methods and techniques (IWA 200G) to determine (4) scra ches and surface abrasion marks; the character cf the flaw (i.e., sin, shape, and ori- (5) roughness or Eeneral corrosion which does entation). Visual examinations that detect surface not reduce the load bearing capacity of the support; flaws that exceed 3400 criteria shall be supplement- (6) general conditions acceptable by the mate-ed by either surface or volumetric examinations. rial, Design, or Construction Specifications.

O 918

i CASE N-498-1 CASES OF ASME BOILER AND PRES $t'RE VESSEL CODE Approval Date: May 11,1994 See NurnericalIndex for expiration and any restfirmstron dates.

Case N 4981 (2) The boundary subject to test pressurization Alternathe Rules for 10 Year System Ilydrostatic during the system pressure tes' hat: extend to all Testing for Class 1,2, and 3 Systems Class 2 components included in those portions of sys-Section XI, Dhision I tems required to operate or support the safety system function up to and including the first nortnally closed Inquiry: What alternative rules may be used in lieu valve, including a safety or relief valve, or valve ca-of those required by Section XI, Division 1. Table pable of automatic closure when the safety function lWB 2500-1,. Category B P, Table IWC-250v-1, Cat- is required. _

egory C H, and Table IWD 2500-1, Categories D A, (3) Prior to performing the VT 2 visual exami-D B, and D C, as applicable, for the 10-year system nation, the system shall be pressurized to nominal hydrostatic test? operating pressure for a minimum of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for in-sulated systems and 10 mir'utes for aoninsulated sys-tems. The system shall be maintained at nominal op-erating pressure during performance of the VT 2 Reply: visual examination.

(a) It is the oninion of the Committee that as an (4) The VT 2 visual examination shall include alternative to the 10-year system hyarostatic test re- all components within the boondary identified in quired by Table IWB 25001, Category B-P, the fol. (b)(2) above.

lowing rules shall be used. (5) Test instrumentation requirements of IWA-(1) A system leakage test (IWB 5221) shall be 5260 are not applicable, p conducted at or near the end of each inspection in- (c) It is the opinion of the Committee that, as an V terval, prior to reactor startup, alternative to the 10-year system hydrostatic test re-quired by Table IWD 2500-1, Categories D-A, D-D, (2) The boundary subject to test pressurization during the system leakage test shall extend to all or D-C (D B for the 1989 Edition with the 1991 and Class 1 pressure retaining components within the sys. subsequent Addenda), as applicable, the following tem boundary, rules shall be used.

(3) Prior to performing the VT-2 vist'al exami. (1) A system pressure test shall be conducted at nation, the system saall be pressurized to nominal or near the end of each inspection interval or during operating pressure for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for insulated the same inspecti on period of each inspection inter-systems and 10 minutes for noninsulated systems. val of Inspection Program B.

The system shall be maintained at nominal operating (2) The boundary subject to test pressurization pressure during performance of the VT-2 visual ex- during the system pressure test shall extend to all amination. Class 3 components included in those portions of sys-(4) Test temperatures and pressures shall not tems required to operate or support the safety system exceed limiting conditions for the hydrostatic test function up to and including the first normally closed curve as contained in the plant Technical Specifica- valve, including a safety or relief valve, or valve ca-tions. pable of automatic closure when the safety function (5) The VT-2 visual examination shall include is required.

all components within the boundary identified in (3) Prior to performing the VT 2 visual exami-(a)(2) above. nation, the system shall be pressurized to nominal (6) Test ;nstramentation requirements of IWA. operating pressure for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for insulated 5260 are not applicable. systems and 10 minutes for noninsulated systems.

(b) It is the opinion of the Committee that, as an The system sball be maintained at nominal operating alternative to the 10-year system hydrostatic test re- pressure during perfurmance of the VT 2 visual ex-quired by Table IWC 2500-1 Category C H, the fol- amination.

( lowing rules shall be used. (4) The VT-2 visual examination shall include (3) (1) A system pressure test shall be conducted at or near the end of each inspection interval or during all components within the boundary identified in (c)(2) above.

the same inspection period of each inspection inter- (5) Test instrumentation requirements of IWA-val of Inspection Program B. 5260 are not applicable.

943

CASE N-504-1 CASES OF ASME BOILER AND PRESSL'RE VESSEL CODE O

Approval Date: August 9,1993 See Numericalindes for exporation and any reathtmatoon deres.

Case N 5%1 penetrant method. Indications greater thani6 / in,are 8

Alternative Rules for Repair of Class 1, 2, and 3 unacceptable and shall be prepared for weld reinforce-Austenitic Stainless Steel Piping Section XI. Division 1 ment in accordance with (1) or (2) below:

(1) Unacceptable indication shall be excavated to the extent necessary to create a cavity that can be re-Inquiry: Under the rules of IWB-4120, IWC-4120, or paired using qualified welding procedures.

IWD-4120, in Editions up to and including the 1986 (2) One or more layers of weld overlay thall be Edition with the 1987 Addenda and in IWA-4300 in later applied to seal unacceptable indications in the area to be Editions and Addenda, a defect may be reduced to a flaw of acceptable size by either mechanical or thermal repaired without excavation. The thickness of these lay-ers shall not be included in meeting weld reinforcement means. As an alternadve, is it permissible to establish design thickness requirements.

ti.e seceptability of a defect in accordance with IWB-(d) If the preparation of (c)(1) or (2) above is re-3640 by increasing the pipe wall thickness by deposition quired, the area where the weld reinforcement is to be of weld reinforcement material on the outside surface of deposited, including any local repairs or initial weld the pipe?

overlay layers, shall be examined by the liquid penetrant Reply: It is the opinion of the Committee that, in lieu method, and shall contain no indications greater than

'/,6 n.i prior to application of the structurallayers of the of the requirements of IWB-4120, IWC-4120, or IWD-w ld overlay.

4120 in Editions up to and including the 1986 Edition (c) The weld reinforcement shall consist of a mini-(v with the 1987 Addenda, and L IWA 4300 in later Edi-mum of two weld layers having as-deposited delta fer-tions and Addenda, the accepta >ility of a def ct in aus-rite content of at least 7.5 FN. The first layer of weld tenitic stainless steel piping rmy be established in ac-cordance with IWB 3640 by deposition of weld metal with delta ferrite content of at least 7.5 FN shall constitute the first layer of the weld reinforcement de-reinforcement (weld overlay) or. the outside surface of sign thnkness. Altematively, first layers of at leas' 5 FN the pipe, provided the following acquirements are met:

may 5e acceptable based on evaluation.

(a) The repair shall be perfonned in accordance with (f) Design of the weld reinforcement shall provide a Repair Prog.am' satisfying the requirements of IWA-for access for the examinations required by (i) and (j) 4000 in the Edition and Addenda of Section XI appli-below, avi shall be in accordance with (1), (2), or (3) cable to the plant in-service inspection pmgram, or late r behw.

Edition and Addenda.

(b) Reinfon:cment weld metal r, hall be low carbon (1) For circuraferentially oriented t a greater than 10% of the pipe circumference, axial flaws (0.035% max.) austenitie stainless steel applied 360 deg, greater thar.1.5 in, in length, or more than 5 axial around the circumference of the pipe, and shall be de-flaws of any length, the weld reinforcement shall pro-posited in accordance with a qualified welding pc>ce-vide the necessary wall thickness to satisfy the flaw dure specification identified in the Repair Program.

evaluation procedures of IWB 3640 from the 1983 (c) Prior to deposition of the weld reinforcement, the Edition with the Winter 1985 Addenda, or later Edi-surface to be repaired shall be examined by the liquid tions and Addenda. The flaw shall be assumed to be 100% through the original pipe wall thickness for the entire circumference of the pipe. The axial length and end slope of the reinforcement shall be sufficient to provide for load redi>tribution from the pipe into the deposited weld metal and back into the pipe with-

'When applying ttus Case to E&tions and AMenda later than the 1989 out violating applicable stress limits of Section III for

,w E& tion. reference to Repair Program shall be read as 8tepair Plan.

\ Primary local and bending stanses and secondary (G

975 I

CA SE (continued)

N 504-1 CASES OF ASME BOILER AND PRIsst'RE \T.SSEL CODE

/^g

' peak stresses. (These requirements will usually be denda, are satisfied for the design life of the repair, satisfied if the overlay full thickness length extends considering potential flaw growth due to fatigue and axially at least 0.75Vit beyond each end of the ob-the mechanism believed to have caused the flaw. The served flaws, where R and r are the outer radius and flaw growth evaluation shall be performed in accord.

nominal wall thickness of the p;pe, prior to deposit- ance with Appendix C. When structural credit is tak-ing the weld overlay, and the end slope is no steeper en for SAW or SMAW weld metal in the original than 45 deg.)

pipe weldment or the weld overlay, the evaluation (2) When there are fewer than five axia! flaws, requirements of Tables IWB 36415 and IWB-3641-each less than 1.5 in. in length, and short circumfer. 6 shall be applied.

ential flaws, the combined length of which does not (3) The evaluation of other welds and compo.

exceed 10% of the pipe circumference, an alternative nents in the system shall consider potential increases weld reinforcement thickness may be used. In deter- in loading, including shrinkage effects, due to all mining the combined length of circumferential flaws weld overlays in the system, and shall identify and for comparison with this limit, multiple flaws shall be record the magnitude and location of the maximum treated as one flaw oflength equal to the sum of the shrinkage stress developed. These welds and com-lengths of the individual flaws characterized in ac- ponents shall meet the applicable stress limits of the cordance with IWA 3300. The flaw shall be assumed Construction Code. Shrinkage stresses sinall be in-to be 100% through the original pipe wall thickness cluded with other applied loads on the system in any with circumferential length equal to the combined IWB-3640 flaw evaluation required for the system.

circumferentiallength of the flaws. Following appli- In addition, the effect of shrinkage from weld over-cation of weld reinforcement, the assumed flaw shall lays on the affected portion of the system restraints, meet the flaw acceptance criteria of IWB 3640 from supports, and snubbers shall be evaluated to deter-the 1983 Edition with the Winter 1985 Addenda or mine whether design tolerances are exceeded.

later Editions and Addenda. The axial length and (h) The completed repair shall be pressure tested end slope requirements shall meet the criteria of (1) in accordance with IWA 5000 if the flaw penetrated

[,) above.

U (3) For weldments with four or fewer axial flaws, the original pressure boundary prior to welding, or if any evidence of the flaw penetrating the pressure each less than 1.5 in. in length, and no circumfer- boundary is observed during the weldmg operation, ential flaws, the weld reinforcement shall have suf-a system hydrostatic test shall be performed in ac-ficient thickness to satisfy the requirements of (c) cordance with IWA 5000. If the system pressure above. No additional structural reinforcement is re- boundary has not been penetrated, a systerr leakage, quired. The axial length of the weld overlay shall insenice, or functional test shall be performed in cover the we.ldment and the heat affected zone on accordance with IWA 5000, each side of tre weldment, with a minimum overlap (i) Presenice examination of the completed re-of % in. on each end of the observed flaws. The end pair shall be performed in accordance with IWB-slope shall meet the criteria of (1) above.

2200. For all classes of components, liquid penetrant (g) An evaluation of the repaired weldment, as and ultrasonic examination of the completed weld well as other welds and components in the system repair shall be performed. Examination procedures affected by the weld reinforcement, shall be per- shall be specified in the Repair Program. The ac-formed in accordance with (1) through (3) below.

ceptance standards of Table IWB-3514-2 shall apply. ,

(1) The Owner shall comply with IWA 1400(p) Ultrasonic examinations shall verify the integrity of from the 1989 Edition with the 1990 Addenda. the newly applied weld reinforcement. Examinations (2) For repaired welds the evaluation shall con-sha!! also be performed to identify the cricinal flaws sider residual stresses produced by the weld overlay with other applied loads on th: system. The effects in the outer 25% of the underlying pips ' sa beachmark for subsequent examinations ot &

of water backing on the repair weld shall be consid- erlay. Grinding and machining of the as-welded ov-cred. The evaluation shall demonstrate that the re- erlay surface may be used to improve the surface quirements of IWB-3640 from the 1983 Edition with finish for such examinations, wiwn the overlay thick-the Winter 1985 Addenda, or later Editions and Ad-ness is not reduced below n'esign requirements.

p O

976 I

i i CASE (continued)

I N-504-1 CASES OF ASME BOILER AND PRESSURE VESSEL CODE

(/) Nondestructive exam. nations shall include the weld and volume identified in (i) abcve.

(k) After completion of all repair activities, the af-fected restraints, supports, and snubbers shall be VT-3 visustly examined to determine if design tolerances are met.

(l) All other applicable requirements of IWA-4000 and IWB-4000, IWC 4000, or IWD-4000 shall be met.

(m) Use of this Case shall be documented on an

.415-2 form.

O O

977

CASE N-509 i

CASES OF ASME B0!LER AND PRE 55tJRE VESSEL CODE Approval Date: November 25,1992 See Numenc Index for expiration and any reaffirmation dates.

Case N 509 1.1 Exemption Criteria Alternathe Rules for the Selection and Examinalon (a) The exemption crit:ria provided in IWB 1220, cf Class 1,2, and 3 Integrally Welded Attachments IWC 1220, and IWD 1220 may be applied to ClassSection XI, Division 1 1,2, and 3 components respectively, with integrally welded attachments, required to be examined in ac-1riquiry: What alternative requiretrents to those of cordance with Table *2500-1.

IWB IWC, and IWD may be used to select and (b) Class 1,2, and 3 integrally welded attachment examine integrally welded attachments? examinations performed as a result of component support deformation cannot be credited under the requirements of IWB 2411 or IWB 2412, IWC 2411 Reply: It is the opinion of the Commi: tee that the or IWC 2412, and IWD-2411 or IWD 2412, respec-following rules may be used to select and examine tively.

integrally welded attachments:

(a/ This Case is limited to Examination Categories B ll B K 1, C-C, D A, D B, and D C. 1.2 Inspection Schedule (b) Class 1,2, and 3 component supports shall be Class 1,2, or 3 integrally welded attachments se-selected for examination in accordance with 1% F of lected for examination by sample selection criteria in the 1989 Edition with the 1990 Addenda. accordance with Table 2500-1, Examination Cate.

(c) Except for the selection of component supports O for examination, all references to Section XI within this Case shall be from the edition and addenda spec-gories B K, C C, and D A, shall meet the require-ments of IWB 2411 or IWB 2412, IWC-2411 or IWC 2412, or IWD 2411 or IWD-2412, repectively.

ified in the Owner's Inservice Inspection Program.

1.3 Additional and Successive Examinations (a) Class 1,2, and 3 additional and successive ex-1.0 SCOPE amination requirements of IWB 2430 and IWB-2420 These requirements apply to examination and for Class 1, IWC 2430 and IWC-2420 for Class 2 and sample selection of Class 1,2, and 3 integrally welded 3 as applicable, shall be applied to integrally welded attachments of vessels, piping, pumps, and valves attachments whose examinations reveal flaws or rel-listed in Table 2500-1 as follows: evant onditions that exceed the acceptance stan-(a) Table 25001, Examination Category B-K shall dards of IWB-3000, IWC-3000, and IWD 3000, re-be used for Class 1 integrally welded attachments in spectively.

Examination Categories B H and B K 1 of IWB. (b) When integrally welded attachments are ex-(b) Table 2500-1, Examination Category C-C shall amined as a result of identified ccimponent support be used for Class 2 integrally welded attachments in deformation and the results of these examinations Examination Category C-C of IWC. exceed the applicable acceptance standards listed (c) Table 25001, Examination Category D A shall above, additional or successive examinations shall be be used for Class 3 integrally welded attachments in performed when determined necessary based on an Examination Categories D-A, D B, and D-C of IWD. evaluation by the Owner.

O 985

ov zg a gy TABLE 2500-1 Ut m EXAMINATIOrt CATEGORIES O ~8 EXAMINATION CATEGORY B-K, INTEGRAL ATTACHMENTS FOR CLASS 1 VESSELS, PIPING, PUUPS, AND VALVES 1 3

Examination C Item Reqmren.entsf Exafmnation Acceptance e

No. Parts Enarruned Fig. N6. Method St.andard Extent of Erwrunation" Frequency W 3:

Enaminatw B10.10 Pressure Yessets IWB-2500-13, Swface' IWB-3516 100% of requered areas of each Integralty Wetded -14, and -15 Each ident hed occwrence and welded attactwvent each i% Won interwar*

Attachr9eests h

810.20 Piping IW 8-2500-13, Surface IW8-3516 100% of regmred areas of exh Each identified occurre ice and l 1 a Integraily Weided -14, and -15 welded attachment O

each inspection intervat' 9 Attachments N

K=

810.30 Purnos IW8-2500-13, Swface IET3516 100% of requered areas of each Integra!1y Weided -14, and -15 Ead identefied ecturvexe and es welded attactrnent each inspection interwar 2 Attachments e 810.40 Valves IWB 250013, Surface IW8-3516 E Integrally Welded -14, ana -15 100% of requered areas of each Each id- mf>=d occurrence and h d

welded attachme t each lenpectico intervaP Attachments E

NOTES: $

(1) Ema nination is timited to these integral'y welded attachments that meet the followeg cord <tions-(a) the attachment is on the outside surface of the pr-ssure retaining component, E" (b) the attachment provides cornpenent support as defined in NF-1110; and ]

(c) the atta2 ment weld joins the attactrnent either directY to the surface of the cornponent er to an integrafty cast or ferged attachment to the corrponent g v,

(2) The entent of the esansiation includes essentially 100% of the length of the attachment weld at each attachment subsect to examination.

(3) Selected sanyles of integrally welded attac!vnents shall be enammed each inspettion interval. p n

(4) In the case of multiple vessels of sirnitar design, function and service, only one htegraffy weided attachment of only one of the multiple vessets shall be selected for esaminat'on s . O (5) be Foe piping, pwres, and valves, a sanvie of 10% of the welded attachrents associated with the component supports selected for exammation uIdr the 1990 Addecida, IWF-2510 shall examined. h 4

(6) inservice Examination is required inspect whenever corW supprart enember deformation (e.e, broken, bent, er pulled out parts) is identified during operation, refoe# rig, rnaintenance esaminatiori

% or testing. , ,

(7) For the configuration shown in Fig. IW8-2500-14, a volumetric examination of volume A-B-C-D from side (8-C) of the c'-wa examination of surfaces A-D and 8-C.

aW welds may be perforyned in lieu of the surface i

e 1-) v .

(

N. y .-

TABLE 2500-1 (CONT'D) ,

EXAMINATION CATEGORIES EXAMINATION CATEGORY C-C, INTEGRAL ATTACHMENTS FOR CLASS 2 VESSELS, PIPING, PUMPS, AND VALVES Esarrination Item Requirements / Examination Acceptance Extent of Frequency of N o. Parts Examined' Fig. No. Methed Standard Examination" Ex amination

C3.10 Pressere Vessels IWC-2500-5 S wface IWC-3512 100% of regtwed areas of each Each ident;f ed occurrence and Intevatty Welded welded attarhment each inspection intmat' f

Attahments O

m

, C3.20 Piping IWC-2500 5 Surface IWC-3512 100% of retrmed areas of each Each identified occurrence and g Integrally Welded welded attachment each inspection intervat* K Attachments O

C3.30 Pamps :WC-2500-5 Surface IWC-3512 100% of required areas of each Each identifed occurrence and 5 Int-gralty Welded welded attachment each inspection intervat* bd 2

~.a At'achments C3.40 Valves IWC-2500-5 Swface IWC-3512 100% of required areas of each Each ida-*lfied orterrence and %

integrilly We.Jed welded attachrent each inspetticn interval

Q Attactrnera m NOTES:

(1) Esamination is limited to those integralty welded attachments that meet the following conditions:

(a) the attactwnent is on the outside surface of the pressure retaining compor.ent ,

itJ the attachment provides componert support as defined in NF-1110; and p (c) she .itachment weld joins the attachment either directly to the surface of the cormorient or to an integrally cast or forged attactwnent to the component. n (21 The exMnt of the examination includes essentlaffy 100% of the it with of the attachment we81 at each attachment subiett to examination. O (3) Oefected samples of is:tegrally welded attachments shall be examined each impection interval. , E f

(4) In the case of roultiple vessels of similar desitA unction and service, only one integrally welded attachment of only one of the muittple vessels shall be selected for examination.

(5) For p6ing, pays, and valves, a sample of 10% of the welded attachments associated wi*h the component supports selected for examsnation under the 1990 Addenda, IWF-2510 shall be exam:-ned.

(6) Examinatio is required whenever component support rnernber deformation (e.g, broken, bent, or pulled out parts) is identified during operation, refueling, maintenance, cuamination, I tr ervice impettion, or testing. g

-. U3 ITI

=

Z. 0 e (O C o

c;; _8.

(* ,h'

'e '. <

j q ,

R -

s

- 4 g. -

e O W i

z. g.

TABLE 2500-1 (CONT'D) U1 m EXAMINATION CATEGORIES gm

~

g$

EXAMINATION CATEGORY D-A,INTEGkAL ATTAt,l'MENTS FOR CLASS 3 VESSELS, ?!PINR, PUPPS, A D %YES b-

=

Examination C l Erar;*stion Item No. Parts Er, mined

Requireme.its/

Fig. No. Method Acceptance Standard Exten* of Examination '

Frequency of

~

k Examination" DL10 Pressure Vessels IWD-25001 Visual, VT-I IWD-3000 100% of required areas of each [ach oder'i!iev' onurrence and I.,tegra!!y Welded welded attachment each inst c' son interval Attachments DI.2e Piping IWD-2500-1 Visual. VT-1 IV'D 3000 100% of required a eas of each Each ihntifed occurre .e p.ad U intec alty Welded Attadrnents welded a:tactwnent each inspection interval k g

DI.30 Pumps IWD-2500-1 Visual, VT-1 K

IWD-3000 100% of reonired areas of each Each identified occurrence and M

Integrally Welded welded attachtrent each inspectic1 interval Attachrents y

o lc D1.40 Valves IWD 25001 Visual, VT.1 IW9 3000 100% of required a.cas of each co Integrally Weided Each identir.ed octerrence and D Attachments wel<ted attachmrnt each inspect'on interval b

~

y NOTES: $

vi (1) Examination is limited to those integrally welded attachments that meet the fallowing condiOons; ta) the attactwnent is on the outside surface of the pressure retaining (ornponent; j

m (b) the attaciwnent provides cceponent s<4 port as defined in NF-1110; and y

(c) the attachment weld joites the attachment either direi tly to the surface of the cornponent or to an integrally cast or forged attachment to the component. id (2) lie extent of the examination includes essentia!!y 100% of the length af the attachment we8d at each attachment subject to examination.

(3) Selected sartmles of integrally welde I attactets shat! be examined each inspection intewa A!! integralty welded attact:rr mts selected for examination Wall be subject to corrosion, ai q determie,ed by the Owner, such as sie ;. tegrally welded attachments of the Service Water or Energency Service Water systerns. In the case of multiple vessais of timilar d .tp, o function and service, the integrally welded attachments of only one of the mv%ple vessels shal1 be selected for exar.tination. F *'iegrally wel attachments of piping, pur.M and valves a 10% sample shall be selected for examinatien. This percentage sample

hall be proportennat to the total .unber ci noneampt integra.ly welded J-lactuae

connected to the %

plaing, pumps, and vafwes, !Nated within each system subject to these examinaticM.

(4) Examination is req.eired whenever e.omponent support member detorrr.ation (e g., beden, bent, er pulled out parts) is identified during cperation, refueling, saintenance, examination, inserv.ce inspection, or t* sting.

____ _o h

CASE N-516 .

CASE 3 OF ASME BOILER AMs PRESSUkE VESSEL CODE Approval Date: August 9,1993 See Numeric Index for expiration and any reaffirmation dates.

Case N 516 2.0 ADDITIONAL VARIABLES FOR DRY Underwater Welding UNDERWATER WELDING Section XI, Division 1 L Procedure Qualification Inquiry. What alternative weldirg mettods to Welding Procedure Specifications for dry under-those required by IWA-4000 may be used when re- water welding shall be qualified to the requirements pair or replacement of P-No. 8 and P-No. 4X mate-

_ of Section IX for groove _ welds. The followir.a vari-rials are to be performed underwater? ables also app'y.

(a) Additional essential variables.

Reply: It is the opinion of the Committee that the (1) a change in the method for underwater following alternative welding methods may be used transport and storage of filler material (e.g., from in lieu of those required by IWA 4000 when repair sealed packages to exposed);

or replacement of P-No,8 and P No. 4X materials (2) addition or deleun of waterproof or sup- i are to be performed underwater. All other applicable plementary coatings for the filler metal or a change egairements of Section XI shall be met, in the type of any waterproof or supplementary coat-ngs;

' (3) a change in depth beyond that qualified in

, 1.0 SCOPE AND GENERAL REQUIREMENTS accordance with Table 2.1-1; i (4) a changv in the nominal background gas t

(a) Thae requirements 5 are for dry or wet under-composition2 ;

f,'N water welding.

(5) for 3 MAW and FCAW, use of a larger di-d (b) The terrrs and definitions of ANSI /AWS D3.6-ameter electrode than that used in qualification.

89, " Specification for Underwater Welding" shall be used.

(b) Additional nonessential variables:

(1) for SMAW and FCAW, an increase in time (c) Repair cr replacement of P-No.8 and P-No. 4X of electrode exposure to the t;nderwater environ-materials and associated welds may be performed un' ment;

derwater provided the welding procedures and weld'

/2) a change in the method of protecting, re-ers or welding operators are qualified in accordanc' moviag moisture from, or otherwise conditioning with Sectica IX and the additional essential variables bare filler metal and bare electrodes in the under-of para. 2.0 or 3.0, as applicable. water environment.

(d) Dry underwater welding may be performed with GMAW, GTAW, PAW, SMAW, or a combi-nation of these processes.

", (c) Wet underwater. welding may be performed 2.2 Performance Quallilcation with GMAW (FCAW-type only), SMAW, or a com-bination cf tbse processes. Welders and welding operators for dry underwater welding shall be qualified in accordance with Section IX and the variables listed below. When a welder or welding operator has not welded with a process in a dry underwater environment for at least six months,

=

the qualifications for that underwater proceis shall

ANSI /t ?"., D3.6 89. " Specification for Underwater Welding" expire, contains additional technical infonnation that the Owner or uct .

nuy fir.d useful Additicnal variables or controls may be consi- (a) A change m. weldm.g mode (i.e., dry chamber, dered for specific applications. dry Spot or habitat).

' Background ga is gas that displaces water and is not necessarily (b) A chang *. In the SFA specification AWS filler intended to shield t..t arc.The gas may or may not be breathable-f Metal classification i

\

1011

1 l CASE (continued)

N-516 CASES OF ASME BOILER AND PRESSURE VESSEL CODE

'J Q) determine as-deposited chemical composition Q) the confirmation weld shall be made in one of in accordance with the applicable SI A specification. the positions to be used in production; (c) Acceptance criteria: (4) the confirmation weld shall be at least 6 in long (1) the ferrite number shall meet the requirements or shall simulate the production weld length.

of the Constraction Code; (b) Procedure quali6eation at the underwaterlocation (2) the 'altimate tensile strength shall meet the min- may be substituted for the confirmation weld, imum tensile strength specified for either of the base metals to be joined; Q) the chemical composition shall meet the appli-6.0 EXAMINATION

~'

cable SFA specification requirements for the as-depos-i'ed chemical composition. When it is impractical to perform the exaniination re-

- quired by this Division or the Construction Code be-cause of the underwater environment, the following al-temative requirements shall bc met. Acceptance criteria 5.0 CONFIRMATION WELD shall be m, accordance with the requirements of this Di-(a) A conarmation weld shall be produced at the un- vision or the Construction Code. The remote visual ex-derwater location before production welding. This weld eminations in (a) and (b) below shall t>e demonstrated shall be used by the repair organization to confirm that to have sufficient sensitivity to detect indications reject-the we: ding system is functioning properly, if it is not able by the surface exaruination acceptance criteria.

practicable to perform the confirmation weld at the ac- (a) The cavity, after defect removal, shall be visually

, tual location (e.g., because of ALARA concems), it examined remotely at a minimum of 5X, in lieu of any shall be performed at another location under similar un- requird surface examination and evaluated using sur-derwater conditions. The qualified welding procedure, fa te examination acceptance criteria.

O as amended below, shall be used for the confirmation (b) The weld shall be visually examined remotely at weld. a minimum of 5X, in lieu of any required surface ex-(1) a confirmation weld shall be made with each amination and evaluated using surface examination ac-welding system used in production; ceptance criteria.

(2) for material less than '/4 in, thick, the confir- (c) The weld may be ultrasonically examined using a mation weld shall simulate the production weld joint procedure qualified for the underw. ster environment in pressure differential and wet or dry backside conditions; lieu of any other required volumetric examination.

%q6 v'

t (J

i 1

1013

CASE N-522 CASES OF ASME BOILER AND PRESSURE VESSEL CODE Appmval Date: December 9,1993 See NumericalIndex for ext ' '-

and any resthemation oste.,

Case N 522 Pressure Testing of Containment Penetratinn Piping Section XI. Division 1 Inquiry: What alternative to the rules of Table IWC-2500-1, Category C-H may be used for pressure testing piping that penetrates a contais. ment vessel, when the piping and isolation valves that are part of the contain-ment system are Class 2 but the balance of the piping system is outside the scope of Section XI?

Reply: It is the opinica of the Committee that 10 CFR 50 Appendix J, may be used as an alternative to the rules in Table IWC-2500-1, Category C-H, for pressure testing pping that penetrates a containment vessel, when the piping and isolation valves that are part of the con-tainment system are Class 2 but the balance of the pip-ing system is outside the scope of Section XI?

p 1029

CASE N-523 CASES OF ASME BOILER AND PRESS 11RE ViSSEL CODE

'w/

Approval Date: August 5,1994 See Numeric Index for expiration and any reaffirmation dates.

Case N 523 defect characterization method, design require-Mechanical Clamping Devices for Gass 2 and 3 ments, and monitoring requirements.

Piping

_s Section XI, Division 1

" 34 AUTHORIZED INSPECTION AGENCY Ingwy What requirements may be used for me-chanical clamping device? to controlleakage through The services of an Authorized Inspection Agency the pressure boundary and to maintain the structural shall be used. The Owner shall notify the Authorized integrity of Class 2 and 3 piping? Inspection Agency prior to welded fabrication or in-stauntion of the clampmg device and shall keep the Reply: It is the opinion of the Committee that the Inspector informeo of the progress so that necessary following requi--ments may be used for mechanical inspections may be performed, clamping devices to control leakage through the pres-sure boundary and to maintain the strectural integ-rity of Class 2 and 3 piping, NPS 6 and smaller.

4.0 DEFECT CIIARACTERIZATION n The size, location, and apparent cause of the de-( 1.0 SCOPE feet shall be determined. The defect size shall be suitab!y bounded to account for nondestructive ex-(a) The provisions of this Case apply to piping and amination limitations. If the defect size cannot be tubing, and their associated fittings and flanges, and directly determined, a conservative bound o' '

sc-the welding ends of pumps, valves, and pressure ves- tual defect size shall be determined and docum; aed, sels, except for those that form the containment boundary. The provisions of this Case do not apply to oth,:r locations in pumps, valves, and pressure ves.

sels. 5.0 DESIGN REQUIREMENTS (b) This Case shall not be used for piping larger 5.1 General Design Requirements than NPS 2 when the nominal operating temperature .

or pressure exceeds 200'F or 275 psig. The following general design requirements shall be (c) Mechanical clamping devices constructed in inclucc.d in the Repair / Replacement Plan and shall accordance with this Case may remain in service only be considered in the analyses of the c:amping device until the r. ext refueling outage, at which time the (para. 5.2) and piping (para. 5.3):

defect shall be repaired or replaced in accordance (a) Requirements to address environmental and with IWA 4000.' corrosive effects of sea; composition, seal installa-tion, and system fhild on piping. clamping device, and bolting.

2.0 REPAIR / REPLACEMENT PLAN (b) The defect size used in the design of the clamp-ing device shall include any projected growth, A Repair / Replacement Plan shall be developed in (c) If additanal supports are required to satisfy accordance with IWA-4140(b), and shall identify the para. 5.2 or para. 5.3, they shall be considered non-pressure retainmg items and shall be designed in ac-cordance with the requirements of the Construction

References to Sect > XI are to the 1992 Edition with the 190 Code for the system or as permitted by IWA-4170(c)

'w/ Addenda. Or (d).

1031 l

CASE (continued)

N-523 CASES OF ASMP BOILER AND PRESSURE VESSEL CODE k

(b) Monitoring of defect size shall not be required for a circumferential crack. '

(c) In addition to the requirements for monitoring defect size, the clamping device shall be monitored ,

for leakage at least weekly. Any leakage at any time shall be dispositioned.

10.0 DOCUMENTATION REQUIREMENTS Use of this Ca:e shall be documented on an NIS- ~

_ 2 Form. The records required by IWA-4900 and the _

_1

, Repair / Replacement Plan shall be maintained by the Owner until the cl.tmping device is removed. ,

O 1033

. , _ _ _ . ~ . . . _ _ . _ . . - .... .. . . , . . . - . .

I CASE N-524 CASES OF ASME B0lllR AND PRESSURE VESSEL CODE Approval Date: August 9,1993 See Numericallodex for expiration and any reaffirmation dates.

Case N 524 Alternative Examination Requirements for bngitudinal Welds in Class 1 and 2 Piping Section XI, D' vision 1

. ~

Inquhy: What alternative requirements may be ap-pli<

tc the surface and volumetrie examinauon of longitudinal piping welds specifkd in Table IWB.

2500-1 Examination Category B-J, Table IWC-2500-

1. Examination Categories C F 1 and C-F 2 (Exam-ination Categon C F prior to Winter 1983 Adden-da), and Table IWC 2520, Examination Cat.: gory C-G (1974 Edition, Summer 1975 Addenda)?

Rrp&: It is the opinion of the Committee that the following shall apply:

(a) When only a surface examination is required, f

\

examination of longitudinal piping welds is not re-

~ quired beyond those portions of the welds within the examination boundaries of intersecting circumfer-ential welds.

(b) When both surface and volumetric examina-tions are required, examinatica oflongitudinal piping welds is not required beyond those portions of the welds within the examination boundaries of inter-secting circumferential welds provided the following -

requirements are met.

(1) Where longitudinal welds are specified and locations are known, examination requirements shall

' met for both transverse and parallel flaws at the

.ntersection of the welds and for that length of lon-gitudinal weld s ithin the circumferential weld ex-amination volume; (2) Where longitudinal welds are specified but locations are unknown, or the existence of longitu-dinal welds is uncenain, the examination require-ments shall be met for both transverse and parallel flaws within the entire examination volume of inter-secting circumferential welds.

O V -

i 1035

CASE

(

N-532

[T CASES OF ASME BOILER AND PRESSURE VESSEL CODE h

Approval Date: December 12,1994 See Numeric tradex for expiration and any reaffirmation dates.

Case N 532 (c) The completed Form NIS-2A shall be main-Alternative Requirements to Repair and tained by the Owner.

Replacement Documentation Requirements and (f) The Owner shall maintain an index of Repair /

Inservice Summary Report Preparation and Replacement Plans in accordance with IWA-6340.

Submission as Required by fWA 4000 and IWA. The index shall identify the ioentification nt.mber 60005 required by (b) above and the inspection interval and Section XI, Division 1 period during which each repair or rep'acement was completed.

Inquiry: What alternatives may be used to the re-2.0 OWNER'S ACTIVITY REPORT quirements of IWA 491C(d) and IWA-6210(e) for PREPARATION AND SUBMITTAL completion of Form NIS 2 following repair or re.

placement, and IWA-6210(c) and (d), IWA-6220, An OWNER'S ACTIVITY REPORT FORM p IWA 6230(b), (c), m.d (d), and IWA-6240(b) for OAR 1 shall be prepared and certified upon com-d preparation and submittal of the inservice summary report and Form NIS-1?

pletion of each refueling outabe. Each Form OAR.

1 prepared during an inspection period shall be sub-mitted following the end of the inspection period.

Reply: It is the opinion of the Comtr. tee that as Each Form OAR-1 shall contain the following:

an alternative to the requirements of IWA-4910(d), (a) Abstract of applicable examinations and tests IWA-6210(c), (d), and (c), IWA-6220, IWA-6230(b), with the information and format of Table 1.

(c), and (d), and IWA 6240(b), the following provi- (b) A listing of item (s) with flaws or relevant con-sions may be used. This Case shall be utilized at least ditions that required evaluation to determine ac-until the end of the inspection period in which it was ceptability for continued service, whether or not the invoked. flaw or relevant condition was discovered during a scheduled examination or test. The listing shall pro-1.0 CERTIFICATION OF THE REPAIR OR vide the information in the format of Table 2.

REPLACEMENT (c) Abstract for repairs, replacements and correc-(a) The Owner's Repair / Replacement Program tive measures performed which nre required due shall identify use of this Case. to an item containing a flaw or selevant condition (b) A Repair / Replacement Plan shall be prepared that exceeded IWB-3000, IWC-3000, IWD-3000, in accordance with IWA-4140', and shall be given a IWE-3000, IWF-3000, or IWL-3000 acceptance cri-unique identification number. teria; even though the discovery of the flaw or rele-(c) Upon completion of all required activities as- vant condition that necessitated the repair, replace-sociated with de Repair /Replacemet Plan, the meat or corrective measure, may not t e resulted Owner shall prepare a REPAIR /REPMCEMENT from an examination or test required by this Division.

CERTIFICATION RECORD, FORM NIS-2A. If acceptance criteria for a pas.:cular i tem is not (d) Form NIS-2A shall be presented to the specified in this Division,- the provisions of IWA-Inspector for certification. 3100(b) shall be taed to determine which repairs,

') replacements, and corrective measures are required d- 'All references to IWA 4000 and IWA 6000 used in this Case refer to be included in the abstract. The abstract chall pro-to the 1992 Edition. vide the information in the format of Table 3.

1061

l CASE (continued)

N-532 CASES OF ASME BOILER AND PRESSURE VESSEL CODE FORM NIS 2A REPAIR /REPU. CEMENT CERTIFICATION RECORD vWNER'S CEhTIFICATE OF CONFORMANCE i certify that the represent by Repair / Replacement

- repe,, or repiecement -

Plan number conforms to the reautrements of Section XI.

Type Coce Symbol stamp Certificate of Author 6tation No. Empiration Date --

Sigaed Date Owner or Owner's Desse.ee. Title CERTIFICATE OF INSERVICE INSPECTION f, the undersigneu, holdmg a valid commission issued by the National Board of Boiler and Pressure VesselInspectors and the State or Province of ar.d employed by of have inspected the items described in Repair / Replacement Plan number durmg the period to and state IMt to the best of my knowledge and belief, the Owner has performed all the activities desenbed in the Repair / Replacement Plan in accordance with the requirements a f Section XI.

By signmg this certificate eeither the Inspector nor his employer makes any warranty. expressed or implied, concermng the activities described in the Repair / Replacement Plan. Furthermore, neither the irispector nor his employer shall be liable in any manner for any personalinjury or property damage or loss of any kind ansing from or connected with this inspection.

Commissions inspector's Segnature National Board. Sate. Province, and Endorsements Date This form (E00126) may be obtained from the Order Dept., ASME. 22 Law Drive, Box 2300. Fairfield. NJ 07007 2300.

(m f

l 1062 l

i CASE (continued) l I

N-532

% CASES OF ASME BOILER AND PRESSL'RE VLSSEL CODE

,e FORM OAR 1 OWNER'S ACTIVITY REPORT Recon humDe' _ . .

Owr.e*

iheme one aseess er owne<:

P ta nt

ML20199G592

Text

1.0 INTRODUCTION

SUMMARY

9.0 REFERENCES

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