Text

Submittal of Fourth Ten-Year Interval Inservice Inspection and Containment Inservice Inspection Program Plan
	ML092080147
Person / Time
Site:	Indian Point
Issue date:	07/21/2009
From:	Robert Walpole; Entergy Nuclear Northeast
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NL-09-097
	Download: ML092080147 (60)
	v • d • e

Enterciy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB

'="ýEnbe P.O. Box 249 Buchanan, NY 10511-0249 Tel (914)734-6710 Robert Walpole Licensing Manager July 21, 2009 NL-09-097 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Fourth Ten-Year Interval Inservice Inspection and Containment Inservice Inspection Program Plan Indian Point Unit Number 3 Docket No. 50-286 License No. DPR-64

Dear Sir or Madam:

Entergy Nuclear Operations, Inc (Entergy) hereby submits the 4 th Ten-Year Interval Inservice Inspection and Containment Inservice Inspection Program Plan for the period July 21, 2009 through July 20, 2019. This program plan establishes the Fourth Ten-Year Interval Inservice Inspection (ISI) including the Containment Inservice Inspection (CII) Program Plan for IP3, in accordance with the Code of Federal Regulations, Title 10, Part 50, Section 55a, "Codes and Standards" (10CFR50.55a).

As required by 10 CFR 50.55a(a)(2) and (g)(4), this program has been reviewed to conform with the 2001 Edition 2003 Addenda of ASME Section XI, except where relief from certain inspection requirements is sought in accordance with 10 CFR 50.55a(a)(3) and (g)(5).

The attached program plan does not address the piping examination requirements of ASME Section XI Examination Categories B-F, B-J, C-F-I, and C-F-2. Entergy is planning to develop a risk informed program for the examination of piping as an alternate to the piping requirements contained in IWB-2500 and IWC-2500. There are 2 refuel outages contained in the first period of the fourth interval: either the piping inspection scope required by IWB-2500 and IWC-2500 or the risk based scope approved by the NRC will be complete prior to completing the second outage of the first period. The delayed submittal of the risk informed portion of the ASME Section XI program was discussed and agreed to in a June 18, 2009 phone call with Mr. John Boska and other NRC staff.

This submittal is for NRC information and does not contain anything requiring NRC review and approval. There are no new commitments being made in this submittal.

NL-09-097 Docket 50-286 Page 2 of 2 If you have any questions or require additional information, please contact Mr. Robert Walpole, Manager, Licensing at (914) 734-6710.

Sincerely, RW/sp

Enclosure:

1. IP3 Fourth Ten-Year Interval Inservice Inspection (ISI) / Containment Inservice Inspection (CII) Program Plan cc: Mr. John P. Boska, Senior Project Manager, NRC NRR DORL Mr. Samuel J. Collins, Regional Administrator, NRC Region 1 NRC Resident Inspector, IP3 Mr. Francis J. Murray, President and CEO, NYSERDA Mr. Paul Eddy, New York State Dept. of Public Service

Enclosure 1 TO NL-09-097 IP3 FOURTH TEN-YEAR INTERVAL INSERVICE INSPECTION (ISl)

/ CONTAINMENT INSERVICE INSPECTION (CII) PROGRAM PLAN ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286

- Entergy Entergy Nuclear Indian Point Energy Center Unit 3 (IP3) Power Station 450 Broadway, Buchanan, New York 10511 ASME B&PV CODE SECTION XI IP3 FOURTH TEN-YEAR INTERVAL INSERVICE INSPECTION (ISI) /

CONTAINMENT INSERVICE INSPECTION (CII)

PROGRAM PLAN July 21, 2009 - July 20, 2019 Commercial Service Date: August 30, 1976 NRC Docket Number: - 50-286 Facility Operating License: DPR-64 Program Section: SEP-ISI-IP3-001 Revision Number: 0 Document Date: July 21, 2009

Program Section: SEP-ISL-[P3-001 Rev. 0

---En tergy INDIAN POINT UNIT 3 ENTERGY NUCLEAR NORTHEAST Program Section

Title:

IP3 FOURTH TEN-YEAR INTERVAL INSERVICE INSPECTION (IS)/

CONTAINMENT INSERVICE INSPECTION (CII)

PROGRAM PLAN Revision 0 July 21, 2009 Applicable Site(s)

IPI [] IP2[] IP3[X] JAF[] PLP[] PNPS[] VY[]

ANOI[] ANO2[] HQN[j GGNS[] RBS[] WF3[]

Quality-Related: [X] Yes []No Prepared by': Robert J. Dolansky Date:

Responsible Engineer C hecked by: Lina Cossio-G onzalez c t (3 I 174 Date:.

Programs Engine Re w RE/RPE: Richard Drake .44 . Date://

For IWE/1WL *ton 6Or !/

ANII: Alan Schiaffino Date: i~LL2 Authorized Nuclear In-Service Inspector (ANII)

Approved by: Nelson Azevedo Date:

Supervisor or nltger - Programs Engineering

Indian Point Unit 3 SEP-1SI-IP3-001 Entergy ASME SECTION XI FOURTH TEN-YEAR Rev.

INTERVAL ISI/CIT PROGRAM PLAN Page 3 of 57 TABLE OF CONTENTS

ýDESCITO A ES\

1.0 INTRODUCTION

AND PLAN DESCRIPTION ............................................................ 6 1.1 In tro d u ctio n ................................................................................................................... 6 1.2 ISI Inspection Interval .............................................................................................. 7 1.3 IP3 Original Construction Codes of Record .................................. 10 1.4 IP3 Fourth Ten-Year Interval ASME Code of Record ........................................... 12 1.5 Inservice Inspection Program Plan Development ................................................... 13 1.6 Inservice Inspection Boundary Development ......................................................... 14 1.7 Inspection, Examination, and Testing Activities Not Controlled By this Plan ..... 17 1.8 Augmented Inspection Programs .......................................................................... 18 1.9 A dministrative Controls .......................................................................................... 19 1.10 IDDEAL Data-Management Program ................................................................... 19 1.11 Adoption and Use of ASME Section XI Code Cases ............................................ 20 1.12 T echnical Positions ................................................................................................. 24 1.13 R elief R equ ests ............................................................................................................ 25 1.14 C alibration B locks ................................................................................................... 28 1.15 L im ited E xam inations ............................................................................................ 28 2.0 APPLICATION CRITERIA AND CODE COMPLIANCE ...................................... 30 2.1 ASME Section XI ................................................ 30 2.2 Augm ented Program s ............................................................................................ 43 IP3 Code Category Summary Tables ........................................................................ 44

Indian Point Unit 3 SEP-ISI-IP3-001 Entergy ASME SECTION XI FOURTH TEN-YEAR Rev.

INTERVAL ISI/CII PROGRAM PLAN Page 4 of 57 REVISION

SUMMARY

SHEET Wc.01 DA IT 1.0 1 through 27 0 2.0 28 through 57 0

SUMMARY

OF CHANGES

Indian Point Unit 3 SEP-ISI-IP3-001 Entergy ASME SECTION XI FOURTH TEN-YEAR Rev.

INTERVAL ISI/CII PROGRAM PLAN Page 5 of 57 SECTION

1.0 INTRODUCTION

AND DESCRIPTION

Indian Point Unit 3 SEP-ISI-IP3-001 Entergy ASME SECTION XI FOURTH TEN-YEAR Rev.

INTERVAL 1SI/CII PROGRAM PLAN Page 6 of 57

1.0 INTRODUCTION

AND PLAN DESCRIPTION 1.1 Introduction This document establishes the Fourth Ten-Year Interval Inservice Inspection (ISI)

Program Plan and the Containment Inservice Inspection (CII) Program Plan for Indian Point Nuclear Generating Station Unit 3 (IP3), in accordance with the Code of Federal Regulations, Title 10, Part 50, Section 55a, "Codes and Standards" (10CFR50.55a).

The IP3 Fourth Ten-Year Interval ISI Program Plan is compliant with ASME Section XI, Division 1, "Rules for Inspection and Testing of Components of Light Water Cooled Plants." The inspection and non-destructive examination of systems, structures, and components (SSCs) will be performed to the extent practical and possible as permitted by existing designs, equipment arrangements, available access, and radiological conditions. Relief requests, including supporting documentation, are also provided for those components where meeting the code requirement is impractical or unnecessarily burdensome. Throughout the Fourth Ten-Year Interval ISI Program Plan, reference is made to SEP-ISI-IP3-002, "IP3 Fourth Ten-Year Interval Inservice Inspection (ISI)/Containment Inservice Inspection (CII) Schedule and Bases Document". SEP-ISI-IP3-002 is in the course of preparation and will be complete before the examinations described in this Program are performed.

This Program Plan outlines the requirements for inspection of:

1.1.1 ISI - Pressure Retaining Components/Supports ISI Class 1, 2, and 3 (Quality Group A, B, and C) pressure retaining components and their supports in accordance with ASME Section XI, Subsections IWA, IWB, IWC, IWD, and IWF with the following exception:

Examination Categories B-J, B-F, C-F-1, and C-F-2 are excluded from the scope of the initial ISI Program (Revision 0) for the fourth interval.

These items are the subject of a planned relief request to be pursued with the NRC that would allow for a risk based program as an alternate to the requirements contained in IWB-2500 and IWC-2500. There are two refuel outages contained in the first period of the fourth interval; either the inspection scope required by IWB-2500 and IWC-2500 or the risk based scope approved by the NRC will be complete prior to completing the second outage of the first period.

Indian Point Unit 3 SEP-ISI-IP3-001 Entergy ASME SECTION XI FOURTH TEN-YEAR Rev.

INTERVAL 1SI/CII PROGRAM PLAN Page 7 of 57

Snubber support hardware such as lugs, bolting, pins, clamps, and structural steel between the snubber pin and the pressure retaining item and between the snubber pin and the building steel are included in the support population and examined in accordance with Subsection IWF per this Program Section.

" Reactor vessel upper head penetrations in accordance with Code Case N-729-1, "Alternative Examination Requirements for PWR Reactor Vessel Upper Heads with Nozzles Having Pressure-Retaining Partial Penetration Welds",Section XI, Division 1 with conditions specified in 10CFR50.55a(g)(6)(ii)(D)(2) through (6).

Class 1 pressure retaining welds containing Alloy 600/82/182 in accordance with Code Case N-722, "Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials",Section XI Division 1 with conditions specified in 10CFR50.55a(g)(6)(ii)(E)(1) through (4).

1.1.2 CII - Containment ISI Pressure Boundary Liner/Concrete

ISI Class MC pressure-retaining components (Primary Containment) and their integral attachments in accordance with ASME Section XI, Subsections IWA and IWE.

ISI Class CC reinforced concrete containment and attachments in accordance with ASME Section XI, Subsections IWA and IWL.

1.1.3 Augmented Inspection Programs

Augmented inspection programs are detailed in Section 1.8.

1.2 ISI Inspection Interval 1.2.1 ISI - IWA, IWB, IWC, IWD, & IWF Interval History The commercial service date for IP3 was August 30, 1976. The table below summarizes the IP3 Interval dates.

Indian Point Unit 3 SEP-ISI-IP3-001

-- Entergy ASME SECTION XI FOURTH TEN-YEAR Rev.

INTERVAL ISI/CII PROGRAM PLAN Page 8 of 57 InervaI Dattes Summain,1 IP~3 ...

Inpcto Ineva nera ength ofira

_ ~~starfD111C F~uEdi jte;1 Iner 1 August 30, 1976 August 29, 1987 11 years, 0 months 2 August 30, 1986 July 20, 2000 *13 years, 11 months 3 July 21, 2000 July 20, 2009 **9 years, 0 months 4 July 21, 2009 ***July 20, 2019 10 years, 0 months

The Second Ten-Year Inspection Interval ISI program plan was originally approved for the effective dates from August 30, 1986 through August 29, 1996. ASME Boiler & Pressure Vessel Code,Section XI (1983 Edition, Summer 1983 Addenda) Paragraph IWA-2400(c), allows inspection interval extensions equivalent to the time that the unit has been out of service whenever there is an outage greater than six months. Thus, the second interval end date was re-scheduled from August 29, 1996 to July 20, 2000. These dates include the I year extension permitted by Section XI to coincide with a refueling outage.

- The third inspection interval was nine (9) years in duration, due to the extension of the second inspection interval by one (1) year (Reference IPN-99-051, dated 5/4/99).

- - IP3's Fourth Ten-Year Interval ISI Program Plan and CII Plan will be effective from July 21, 2009, through and including July 20, 2019. It should be noted that the plant's current (original) operating license will expire on December 12, 2015. Entergy is in the process of a license renewal application. The end date of the fourth interval will be controlled by the ISI/CII Program Plan, commensurate with the Operating License Renewal Application.

1.2.2 CII - IWE/IWL Interval History On September 9, 1996, 10CFR50.55a was amended to incorporate the requirements of ASME Section XI Code 1992 Edition through the 1992 Addenda of Subsections IWE and IWL, Containment Program Plan.

Subsection IWE contains the requirements for liners and penetrations of light-water cooled nuclear power plants and IWL contains the requirements for ISI of reinforced concrete containments. The rule at the time required licensees to incorporate the new requirements into their ISI programs and to complete examinations equal to the required First Period Inspections within five years (i.e., no later than September 9, 2001).

Subsection IWE requires that examinations be performed at the required inspection periods of 3, 7 and 10 calendar years of plant service within the interval. Therefore the First Period Examinations were completed by September 9, 2001 to meet 10CFR50.55a requirements. The IWE inspection periods were therefore:

Indian Point Unit 3

- r'Entergy ASME SECTION XI FOURTH TEN-YEAR Rev.

INTERVAL ISI/CII PROGRAM PLAN Page 9 of 57 1 Sep. 10, 1999 - July 20, 2003 2 July 21, 2003 - July 20, 2006 3 Jul 21, 2006 - July 20, 2009 Subsection IWL requires that examination of the entire concrete surface of containment be performed every five years. The first of these examinations was completed by July 20, 2001; the second inspection was completed in June 2005; and the third inspection was completed in July 2009. Subsection IWL-2421 does not apply to IP3.

1.2.3 Fourth Ten-Year Interval Schedule The IP3 Fourth Ten-Year Interval ISI Program Plan and CII Plan will be effective from July 21, 2009 through July 20, 2019.

1.2.3.1 IWB, IWC, IWD, IWE, and IWF Inspection Schedules:

The inspection schedule for the fourth interval is divided into three ISI Periods such that approximately one third of the interval's inspections will be completed each period except for items that may be deferred until the end of the interval. The IWE inspection schedule is aligned with the IWB, IWC, IWD and IWF schedules except for IWE items that are required. to be 100% inspected each period. The following table summarizes the period dates for the fourth inspection interval as defined by Inspection Program "B". In accordance with JWA-2430(d)(3), the first period has been extended by one year and the second period reduced by one year to coincide with outages. This does not alter the inspection interval. The inspection schedule for each ISI Period is provided in SEP-ISI-IP3-002.

1113 1 ti.ntevalnspectioni Periods' Summary Dates 111S~e~toll Perioid'siiii1 ~Period I'l( Phlant P,1tRflil i~i~petion nd~-~ . ~ rOant Reuelin

~~Period~ D.Ite ,Date Opea on1Otaes W~ithinl Priod'

- ~ ~ Withinr-I July 21, 2009 July 20, 2013 4 years RFO-16 (Spring 2011)

RFO-17 (Spring 2013) 2 July 2l, 2013 July 20, 2016 3 years RFO-18 (Spring 2015) 3 RFO-19 (Spring 2017)

July 21, 2016 July20 2019 3 years RFO-20 (Spring 2019)

Indian Point Unit 3 SEP-ISI-IP3-001 Entergy ASME SECTION X1 FOURTH TEN-YEAR Rev.

INTERVAL ISI/C1I PROGRAM PLAN Page 10 of 57 Changes to the stated Inspection Interval or Inspection Period dates, if deemed necessary, will be documented.

1.2.3.2 IWL Inspection Schedule In accordance with the requirements of IWL-2410, the inspections required by IWL-2500-1, Examination Category L-A, are to be completed once every 5 years within the limitations specified in IWL-2410(b), (c), and (d).

1.2.4 Alignment of ISI and Containment ISI Intervals An integral part of this Fourth Ten-Year Interval Program Plan is the merging of the IWE/IWL Containment Inservice Inspection (CII) Program Plan with the Inservice Inspection (ISI) Program Plan. This will facilitate one set of ASME Code requirements for both program plans.

The Second Ten-Year Interval for IWE/IWL Containment ISI inspections at IP3 will commence on July 21, 2009 concurrent with the start of the Fourth Ten-Year Interval Program Plan. Therefore, both the ISI and the CII Program Plans will be aligned with the Fourth Interval ISI Program schedule and ASME Code requirements.

1.3 IP3 Original Construction Codes of Record The construction permit for IP3 was issued on August 13, 1969. At that time, the ASME Boiler and Pressure Vessel Code covered fabrication of only nuclear vessels.

Piping, pumps, and valves were built primarily to the rules of USAS B31.1.0-1967, Power Piping.

1.3.1 ISI- Systems, Structures, and Components The primary IP3 original Construction Codes for major equipment are listed below.

Reactor Vessel, ASME Code,Section III, Class A. 1965 Pressurizer, Reactor Coolant Pumps, Boron Injection Tank

Indian Point Unit 3 a ___________________________________ SEP-ISI-1P3-001

-- Entergy ASME SECTION XI FOURTH TEN-YEAR Rev.

INTERVAL ISI/CII PROGRAM PLAN Page 11 of 57 ConstrutctionCode Steam Generators- ASME Code,Section III, 1983 Edition, plus (Replacement, including the Summer 1984 Addenda transition cone, lower shell, --

tubesheet, and channel head)

Other Pressure Vessels ASME Boiler & Pressure Vessel Code,Section VIII, 1965 Piping Design - General Design ASA Section B3 1.1 Pressure Piping Code Criteria 1967 1.3.1.1 ISI Pre-service Inspections Westinghouse performed the pre-service inspection of IP3 in 1974 and 1975.

1.3.2 CII - Primary Containment Design The reactor containment structure is a reinforced concrete vertical right cylinder with a flat base and hemispherical dome. A welded steel liner is attached to the inside face of the concrete shell to ensure a high degree of leak tightness. The design objective of the containment structure is to contain all radioactive material that might be released from the core following a loss-of-coolant accident. The structure serves as both a biological shield and a pressure container.

The flat concrete basemat is 9 ft. thick and has a liner plate located on top. The liner plate is covered with 3 ft. of concrete, which forms the floor of the containment and serves to carry internal equipment loads.

The cylinder consists of side walls measuring 148 ft. from the basemat to the spring line of the dome, and has an inside diameter of 135 ft. The side walls for the cylinder are 4 ft. 6 in. thick. A steel liner is attached to the inside face of the concrete shell to forin a leak tight membrane.

The hemispherical dome is a 135 ft. diameter 3 ft. 6 in. thick shell that is lined with a liner plate. The inside radius of the dome is equal to the inside radius of the cylinder. The discontinuity that occurs at the springline due to the difference in thickness is on the outer surface. The original design of the containment preceded the issuance of ASME Section I1I, Division 2. As a result the reinforced concrete primary containment was designed and constructed to the requirements of the American Concrete Institute, Building Code Requirements for Reinforced Concrete, ACI 318-63.

Indian Point Unit 3 SEP ISIP3-001 Entergy ASME SECTION XI FOURTH TEN-YEAR Rev.

INTERVAL ISI/CuI PROGRAM PLAN Page 12 of 57 1.3.2.1 Containment ISI Initial Interval - Pre-service Inspections There were no regulatory requirements to implement Subsections IWE and IWL of ASME Section XI prior to IP3 commencing operations. However, in accordance with the requirements of I OCFR50.55a, the examinations performed during the First Period of the First Inspection Interval must serve the same purpose for operating plants as the pre-service examination specified for plants not yet in operation. The rule allowed five years for the implementation of the First Period Examinations, which were completed by September 9, 2001.

1.4 IP3 Fourth Ten-Year Interval ASME Code of Record 1.4.1 The regulations in 10CFR50.55a(g)(4) establish the effective ASME Code edition and addenda to be used by licensees for performing inservice inspections of components (including supports). Paragraph 50.55a(g)(4)(ii) requires the use of the latest edition and addenda that has been incorporated by 10CFR50.55a(b), one year prior to the beginning of each 120-month ISI interval. This is considered the Code of Record. The Code of Federal Regulation (CFR) in effect one year prior to the beginning of the fourth interval was published in September, 2005 as CFR70FR188. This CFR incorporated, by reference, the ASME Section XI, 2001 Edition including the 2002 and 2003 Addenda in paragraph (b)(2) with limits and conditions.

Subsequently, CFR73FR52748 was published in September, 2008 requiring expedited implementation of Code Cases N-729-1 and N-722.

1.4.2 Based on the two referenced CFRs in 1.4.1, the IP3 Fourth Ten-Year Interval ISI Program Plan is based on the requirements of the 2001 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI with the 2002 and 2003 Addenda with the limits and conditions contained in IOCFR50.55a(b)(2) and listed in SEP-ISI-IP3-002.

Additionally, based on specific limits, earlier editions and addenda are also being used as described below.

1.4.2.1 The 1995 Edition with the 1997 Addenda of Section XI is being implemented for IWA-2240 (10CFR50.55a(b)(2)(xix)).

1.4.2.2 The 1998 Edition of Section XI is being implemented for Table IWB-2500-1, Examination Category B-D, Items B3.120 and B3.140 (10CFR50.55a(b)(2)(xxi)(A)).

Indian Point Unit 3 SEP-ISI-IP3-001

- tergy ASME SECTION XI FOURTH TEN-YEAR Rev.

INTERVAL ISI/CI1 PROGRAM PLAN Page 13 of 57 1.4.2.3 The 2001 Edition (no addenda) of Section XI is being implemented for Appendix VIII and the supplements to Appendix VIII and Article I-3000 (10CFR50.55a(b)(2)(xxiv)).

1.4.3 ASME Code Cases N-729-1 and N-722 with the applicable limitations and modifications as identified in 10CFR50.55a(b)(2).

1.5 Inservice Inspection Pro2ram Plan Development 1.5.1 IS/CII - Class 1, 2, and 3 (Quality Group A, B, and C), and Class MC and

\ CC The Fourth Ten-Year Interval ISI Program Plan for Quality Group A, B, and C systems and components (including their supports), was developed after giving consideration to the following documents and applicable relief requests!

" Code of Federal Regulations 10CFR50.55a

ASME Boiler & Pressure Vessel Code Section V - 200,1 Edition w/2002 &

2003 Addenda

ASME Boiler & Pressure Vessel Code Section XI - 2001 Edition w/2002

& 2003 Addenda as modified by 10CFR50.55a(b)(2)

United States Nuclear Regulatory Commission Regulatory Guides

" Regulatory Guide 1.16, Rev. 4

" Regulatory Guide 1.26, Rev. 3

" Regulatory Guide 1.83, Rev. 1

" Regulatory Guide 1.147 Latest Revision

" IP3 UFSAR

IP3 Improved Tech. Specs.

IP3 First Interval Ten-Year Inservice Inspection Program Plan

IP3 Second Interval Ten-Year Inservice Inspection Program Plan

IP3 Third Interval Ten-Year Inservice Inspection Program Plan

IP3 First Ten-Year Containment Inservice Inspection Program Plan 1.5.2 Systems/Lines Exempt from Examination Systems/lines within the ASME Section XI boundaries that are exempted from examination based on ASME Section XI are identified in SEP-ISI-IP3-002.

Indian Point Unit 3 SEP-ISI-IP3-001 Entergy ASME SECTION XI FOURTH TEN-YEAR Rev.

INTERVAL ISI/CuI PROGRAM PLAN Page 14 of 57 1.6 In-service Inspection Boundary Development 10CFR50.55(a) requires that systems and components be designed, constructed, fabricated, erected, tested, and inspected to quality standards commensurate with the importance of the safety function to be performed. To this end, the regulation continues to identify requirements related to defined "classes" of systems and components but, except for Class 1, does not specifically define the functional requirements for establishing classes or boundaries of these classes. Thus, in order to apply the in-service inspection (ISI) requirements of 10CFR50.55a to the systems and components installed at IP3, ISI class designations and boundaries have been defined and established.

Taking into consideration the fact that the CFR does not define components identified for Class 2 or 3 designations, the NRC issued Regulatory Guide 1.26 (Revision 2 dated June, 1975 and Revision 3 (unapproved)) that provide guidance for determining component classification. The guidance presented in these regulatory guides, as appropriate, was used in establishing component classification and boundaries. In those instances where the guidance conflicted with IP3 design or licensing basis, the IP3 design or licensing basis was used.

As part of an initiative to be consistent with Indian Point Unit 2 (IP2), the IP3 Section XI boundary drawings (ISI Flow Diagrams) are being revised to change the boundary designations from ISI Class 1, 2, and 3 to Quality Group A (ISI Class 1), B (ISI Class 2), and C (ISI Class 3). Until this effort is complete, some boundary drawings will identify the ASME Section XI boundaries as ISI Class 1, 2 or 3 and other drawings will identify the ASME Section XI boundaries as Quality Group A, B, or C. This is a change in designation only; there are no adjustments in the boundaries.

The drawings which provide details for examination of welds, components, and their supports and an index to the ASME Section XI boundary drawings are contained in SEP-ISI-IP3-002. Pursuant to 10CFR50.55a, the in-service inspection requirements of ASME Section XI have been assigned to these components within the constraints of existing plant design.

1.6.1 ISI Boundaries and Classification For 1SI Class 1 component(s) (Quality Group A), the requirements of Subsection IWB, Code Case N-729-1, and Code Case N-722 apply, for ISI Class 2 components (Quality Group B) the requirements of Subsection IWC apply, and for ISI Class 3 components (Quality Group C) the requirements of Subsection IWD apply. The requirements of IWF for component supports apply to all three ISI Classes (Quality Groups A, B, and C).

Indian Point Unit 3

____________________________________ SEP-IS1-1P3-0O1.

-- Entergy ASME SECTION XI FOURTH TEN-YEAR Rev.

INTERVAL IS[/CII PROGRAM PLAN Page 15 of 57 The ISI Flow Diagrams are marked with triangular shaped "flags" which include alpha characters designating Quality Group A, B, C, MC (IWE), CC (IWL), or black for non-nuclear safety class.

1.6.2 IWE/IWL Containment Boundaries and Classification As stated above, Quality Group A, B and C piping systems shall be inspected in accordance with applicable subsections of Section XI. The interface boundary between the IWB, IWC, and IWD components and the containment systems are identified in the IPEC Repair and Replacement Program.

1.6.2.1 ISI Class MC (IWE)

ISI Class MC containment components consist of the containment structure and connecting penetrations, appurtenances and parts that form the containment leak tight boundary. The components included in the boundary are:

" Dome liner

Wall liner

Basemat liner

" Penetration sleeves

Personnel air lock

" Equipment access hatch/personnel lock

" Fuel transfer tube ISI Class MC containment components shall be inspected per the requirements of ASME Section XI, Subsection IWE Table IWE-2500-1 as modified by 10CFR50.55a, Code Cases, Technical Positions, and Relief Requests approved by the NRC.

1.6.2.2 ISI Class CC (IWL)

The components that make up the ISI Class CC boundary are:

Concrete wall e Concrete dome

Indian Point Unit 3 SEP-ISI-1P3-0O1 Sntergy ASME SECTION XI FOURTH TEN-YEAR Rev.

INTERVAL ISI/C11 PROGRAM PLAN Page 16 of 57

Concrete basemat ISI Class CC containment components shall be inspected per the requirements of ASME Section XI, Subsection IWL Table IWL-2500-1 as modified by 10CFR50.55a, Code Cases, Technical Positions, and Relief Requests approved by the NRC.

The IP3 containment is a reinforced concrete structure and is not designed utilizing a post tensioning system. Therefore, the requirements of ASME Section XI, Subsection IWL that pertain to post tensioning systems do not apply.

1.6.3 Containment ISI (CII) Drawings The CII drawings were created to graphically identify the components and define the boundaries. The drawings are designed to be used as an inspection tool to locate the components and verify the configuration during inspections.

An index of the CII Drawings is contained in SEP-ISI-IP3-002.

1.6.4 Piping Penetrating Containment Boundaries 1.6.4.1 Quality Group A, B, and C Piping and Components Piping and components that penetrate containment, including their welded attachments, that are Quality Group A, B, or C based on their service function are examined and maintained in accordance with IWB, IWC and IWD, respectively.

1.6.4.2 Piping and Components other than Quality Group A, B, and C Piping and components that penetrate containment, including their welded attachments, that are specifically excluded from classification in accordance with Regulatory Guide 1.26, Rev. 3 based on their service function, such as instrument air, station air, service air, etc., are inspected and maintained as 'ISI Class MC' (noted by triangular shape flags denoting quality group 'MC')*.

Also, drawings with triangular shaped flags such as "E" are part of the MC designation for IWE components.

Indian Point Unit 3 SEP-ISI-IP3-001

-- Entergy ASME SECTION XI FOURTH TEN-YEAR Rev.

INTERVAL ISI/CII PROGRAM PLAN Page 17 of 57 The ISI MC boundary will apply to the first weld of the first containment isolation valve outside containment through the penetration to the first weld inside the containment. If there are two containment isolation valves the MC boundary ends after the second isolation valve. The MC boundary, as defined in the IWE section of the Code, will remain the same.

Repair/Replacement shall be in accordance with Indian Point design specification and the construction code.

Pressure test shall be in accordance with IOCFR50 Appendix J.

Note Quality Group 'Class MC' designation is used for piping penetrations that are not classified Quality Group A, B, or C (Class 1, 2, or 3).

1.7 Inspection, Examination, and Testing Activities Not Controlled By this Plan Although the following items may be contained within the ASME Section XI boundaries and may be subject to ASME Section XI requirements, they are not included in this Program Section. The inspection, examination, or testing activities described below are controlled and managed under IP3 Improved Technical Specifications (ITS), Technical Requirements Manual (TRM), or other applicable Entergy procedures as follows:

1.7.1 Steam Generator Tubing IWB-2500-1 Category B-Q Item No. B16.20 will be examined in accordance with the requirements of ITS Section 5.5.8.

1.7.2 System Pressure Tests for Class 1, 2, and 3 components will be scheduled and controlled in accordance with IP3 site procedures.

1.7.3 Inspection and testing of Snubbers will be scheduled and controlled in accordance with IP3 site procedures and TRM 3.7.C.

1.7.4 In-service Testing of Pumps and Valves will be performed and controlled in accordance with IP3 site procedures and ITS 5.5.7.

1.7.5 The ASME Section XI Repair Replacement Program will be implemented and maintained in accordance with site procedures.

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INTERVAL ISI/CII PROGRAM PLAN Page 18 of 57 1.8 Augmented Inspection Pro2rams Augmented examinations are those that are outside the scope of 10CFR50.55a(g), but are contained and managed by the ISI Program Plan for convenience of scheduling and implementation. These examinations may result from activities including, but not limited to, commitments made to the NRC outside the scope of 10CFR50.55a, internal commitments, License Renewal commitments, or industry initiatives. These examinations may use ASME Section XI techniques and procedures as defined in the commitment, however, the requirements of ASME Section XI, including reporting, do not apply. Current augmented examinations include:

1.8.1 Reactor Coolant Pump Flywheel Inspection Program The Reactor Coolant Pump (RCP) Flywheel inspection is not part of ASME Section XI but is required by Section 5.5.6 of the ITS and the UFSAR. The flywheels are scheduled for examination under the Preventive Maintenance Program. The flywheels are inspected when an RCP motor is removed and sent out for refurbishment in order to meet the ITS and the UFSAR requirements. Entergy is not committed to USNRC Regulatory Guide 1.14 at IP3.

1.8.2 NEI Initiatives - Materials Reliability Program (MRP-139) for Reactor Vessel Dissimilar Metal Welds EPRI has developed a program titled "Materials Reliability Program: Primary System Piping Butt Weld Inspection and Evaluation Guideline (MRP-139),"

dated July 14, 2005, that identifies primary system dissimilar metal (DM) butt weld locations susceptible to primary water stress corrosion cracking (PWSCC) and developed approaches for inspection, re-inspection, mitigation, and flaw evaluation. This includes terminal ends, where most of the Alloy 82/182 welds are located. In accordance With MRP-139, guidance has been provided to inspect DM butt welds as in the Reactor Vessel Nozzle to Safe-end Welds. In this guidance, IP3 falls under the classification of "D","E","J", and "K", as defined in MRP-139. Volumetric examination requirements are in accordance with MRP-139, Section 5.1, and are scheduled in accordance with Table 6-1. The visual examinations required by MRP-139 are replaced with the visual examinations contained in Code Case N-722 as required by I OCFR50.55a Entergy will comply with the criteria, with the exception of visual examinations, of MRP-139 for welds that are potentially susceptible to PWSCC. At IP3 this consists of eight (8) welds where piping (safe-ends) attach to the reactor pressure vessel nozzles.

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INTERVAL 1SI/CIT PROGRAM PLAN Page 19 of 57 1.8.3 Regenerative Heat Exchanger Welds The chemical and volume control system at iP3 is not classified as a Class 2 system. However, components that support reactor coolant pump seal cooling, emergency boration, and reactor coolant system make-up, that are not exempt from examination per IWC-1220, will be volumetric and surface examined per code requirements as applicable. Based on these criteria, the regenerative heat exchanger would not be exempt and will be examined. Code Case 706 will be used.

1.9 Administrative Controls 1.9.1 This program is written and implemented as a Program Section meeting the requirements of EN-DC-174, "Program Sections". This Program Section will be maintained through revisions and Program Change Notices (PCN) in accordance with EN-DC- 174.

1.9.2 This program will be maintained current to reflect applicable changes to plant configuration through the review process defined by EN-DC- 115, Engineering Change Process".

1.9.3 Additions of items to the program resulting from changes to the plant configuration will be incorporated and scheduled for inspection or examination in accordance with IWB/IWC/IWD/IWE-2412 and IWF-2410.

1.9.4 Organizational and divisions of responsibilities for the management and implementation of the 1SI Program are defined in EN-DC-120, "Engineering Code Programs".

1.9.5 In accordance with IWA-1400(c), the initial ISI Program Plan shall be provided~to the NRC for "Information Only". PCNs are not required to be provided to the NRC.

1.9.6 The initial ISI Program Plan, revisions, and PCNs are subject to review by the Authorized Nuclear Inservice Inspector (ANII).

1.10 IDDEAL- Data-Management Program IP3 ISI Components and their examination schedules are developed with the aid of the IDDEAL Software Suite. The IDDEAL Software Suite integrates information from the examination programs to facilitate ease and efficiency in organizing, scheduling and tracking of all inspection and examination work. The software is used as a tool in developing the ISI Program. This Program Section shall be used as the controlling entity for managing and implementing the ISI program.

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INTERVAL ISI/C1I PROGRAM PLAN Page 20 of 57 1.11 Adoption and Use of ASME SectionyXI Code Cases In accordance with ASME Section X1, IWA-2441(a), Code Cases to be used during a pre-service or in-service inspection shall be identified in the Inservice Inspection Plan.

ASME Section XI Code Cases adopted for ISI and NDE activities are listed in Tables 1.11-1 and 1.11-2. In addition, other Code Cases as approved in Regulatory'f¶uide 1.147, latest revision, may be used as required. Code Cases applicable to System Pressure Testing and Repair/Replacement Activities are addressed in their respective program documents and are not included in this Program. The use of Code Cases is in accordance with ASME Section XI, IWA-2440, 10CFR50.55a, and Regulatory Guide 1.147. As permitted by ASME Section XI, Regulatory Guide 1.147, and 10CFR50.55a, ASME Section XI Code Cases may be adopted and used as described below:

1.11.1 Adoption of Code Cases Approved for Use in Regulatory Guide 1.147 Code Cases that are approved for use in the latest revision of Regulatory Guide 1.147 may be included in the ISI program provided any identified limitations or modifications specified in the Regulatory Guide are also incorporated. Table 1.11-1 identifies the Code Cases that have been approved for use in Regulatory Guide 1.147 and are incorporated into the ISI program.

1.11.2 Adoption of Code Cases Not Approved in Regulatory Guide 1.147 Certain Code Cases that have been approved by the ASME Board of Nuclear Codes and Standards may not have been reviewed and approved by the NRC Staff for use and are not listed in Regulatory Guide 1.147. Use of such Code Cases may be requested in the form of a "Request for Alternative" in accordance with 10CFR50.55a(a)(3). Code Cases that have been requested in accordance with 10CFR50.55a(a)(3) may not be used until NRC approval has been obtained. Section 1.13 identifies the Code Cases that have been requested in accordance with IOCFR50.55a(a)(3).

1.11.3 Adoption of Code Cases Mandated by 10CFR50.55a Code Cases required by rule in 10CFR50.55a are incorporated into the ISI Program and implemented at the specified schedule. Code Cases currently required by 10CFR50.55a are identified in Table 1. 11-2.

1.11.4 Use of Annulled Code Cases As permitted by Regulatory Guide 1.147, Code Cases that have been adopted for use in the current interval that are subsequently annulled by ASME may be used for the remainder of the interval.

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INTERVAL 1S1/CII PROGRAM PLAN Page 21 of 57 1.11.5 Code Case Revisions Initial adoption of a Code Case requires use of the latest revision of that Code Case listed in Regulatory Guide 1.147. However, if an adopted Code Case is later revised and approved by the NRC, then either the earlier or later revision may be used. An exception to this provision would be the inclusion of a limitation or condition on the use of the Code Case which is necessary to enhance safety.

CoeGse ~~oi tilq 6"di-e'.1r47 ',

Alternative Examination Coverage for None Class 1 and 2 Welds Alternative Requirements for Successive None Inspections of Class 1 and 2 Vessels Repair/Replacement Activity None Documentation Requirements and Inservice Summary Report Preparation and Submission Location of Ultrasonic Depth-Sizing None Flaws I

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INTERVAL 1ST/CIT PROGRAM PLAN Page 22 of 57 Fm ~~ ~ ~ ~~ h If3~,ŽD~dpe iy~~J3mf R2.ýguipt TyGtide 1" 1,47' Alternative Methods - Qualification for To achieve consistency with the Nozzle Inside Radius Section from the IOCFR50.55a rule change Outside Surface published September 22, 1999 (64 FR 51370), incorporating Appendix VIII, "Performance Demonstration for Ultrasonic Examination Systems," to Section XI, add the following to the specimen requirements:

N-552 "At least 50 percent of the flaws in the demonstration test set must be cracks and the maximum misorientation must be-demonstrated with cracks.

Flaws in nozzles with bore diameters equal to or less than 4 inches may be notches."

Add to detection criteria, "The number of false calls must not exceed three."

Alternative Additional Examination None N-586-1 Requirements for Classes 1, 2, and 3 Piping, Components, and Supports Alternative Examination Requirements for Essentially 100 percent (not less Steam Generator Nozzle to Vessel Welds than 90 percent) of the N-593 examination volume A-B-C-D-E-F-G-H must be inspected.

Ultrasonic Examination of Penetration None Nozzles in Vessels, Examination Category N-613-1 B-D, Item Nos. B3.10 and B3.90, Reactor Nozzle to Vessel Welds, Figs. IWB-2500-7(a), (b), and (c)

N-624 Successive Inspections None

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INTERVAL ISI/CII PROGRAM PLAN Page 23 of 57 L9deCc' LdpL4-'-;fon- I

-1 jijl -N ud 114 '1: r

,rlitims Alternative Calibration Block Material Chemical ranges of the calibration block may vary from the materials specification if(l) it is within the chemical range of the component specification N-639 to be inspected, and (2) the phase and grain shape are maintained in the same ranges produced by the thermal process required by the material specification.

Alternative Requirements for Inner In place of a UT examination, Radius Examination of Class 1 Reactor licensees may perforn a visual Vessel Nozzles examination with enhanced magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the allowable flaw length criteria of Table IWB-3512-1 with limiting assumptions on the flaw aspect N-648-1 ratio. The provisions of Table IWB-2500-1, Examination Category B-D, continue to apply except that, in place of examination volumes, the surfaces to be examined are the external surfaces shown in the figures applicable to this table (the external surface is from point M to point N in the figure).

N-685 Lighting Requirements for Surface None Examination N-695 Qualification Requirements for Dissimilar None Metal Piping Welds Qualification Requirements for Appendix None N-696 VIII Piping Examinations Conducted from the Inside Surface

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INTERVAL IS/CII PROGRAM PLAN Page 24 of 57 FA

_'y Alternative Rules for Selection of Classes None N-700 1, 2, and 3 Vessel Welded Attachments for Examination Alternative Examination Requirements of None Table IWB-2500-1 and Table IWC-2500-N-706 1 for PWR Stainless Steel Residual and Regenerative Heat Exchangers A.." c° es_ ed.1-*

Additional Examinations for PWR NPressure Retaining Welds in Class 1 Implemented in the Pressure Test Components Fabricated With Alloy Program 600/82/182 Materials Alternative Examination Requirements for Conditions specified in PWR Reactor Vessel Upper Heads With N-729-1 Nozzles Having Pressure-Retaining paragraphs (g)(6)(ii)(D)(2)

Partial-Penetration Welds through (6) of 10CFR50.55a 1.12 Technical Positions Technical Positions are created for areas where the Code does not provide clear direction or areas where regulation, requires more attention to a specific area.

I ý'I, Technical Position papers used as bases for the ISI program are listed in Table 1.12- 1.

None at this time

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INTERVAL IS/CI PROGRAM PLAN Page 25 of 57 1.13 Relief Requests Throughout this program, the term "relief request" is used interchangeably referring to submittals to the NRC requesting permission to deviate from either an ASME Section XI requirement, a 10CFR50.55a rule, or to use provisions from Editions or Addenda of Section XI not approved by the NRC as referenced in 10CFR50.55a(b). However, when communicating with the NRC and in written requests to deviate, the terms as defined below must be used for clarity and to satisfy 10CFR50.55a. Submittals to the NRC must clearly identify which of the below rules are being used to request the deviation.

Table 1.13-1 contains an index of Relief Requests written in accordance with 10CFR50.55a(a)(3) and (g)(5). The applicable Entergy submittal and NRC Safety Evaluation Report (SER) correspondence numbers are also included for each request.

Only requests associated with the ISI program and the supporting nondestructive examination requirements are listed in Table 1.13-1. Copies of these requests are located in SEP-ISI-IP3-002. Requests applicable to System Pressure Testing and Repair/Replacement Activities are identified in their respective program documents.

1.13.1 Request for Alternatives When seeking an alternative to the rules contained in 10CFR50.55a(c), (d),

(e), (f), (g), or (h) the request is submitted under the provision of 10CFR50.55a(3). Once approved by the Director, Office of Nuclear Reactor Regulation, the alternative may be incorporated into the IS1 program. These types of requests are typically used to request use of Code Cases, Code Edition, or, Addenda not yet approved by the NRC. Request for Alternatives must be approved by the NRC prior to their implementation or use. Within the provisions of 10CFR50.55a(3) there are two specific methods of submittal:

1.13.1.1 10CFRS0.55a(a)(3)(i) allows alternatives when authorized by the NRC, if the proposed alternatives would provide an acceptable level of quality and safety. Requests submitted under these provisions are not required to demonstrate hardship or burden.

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INTERVAL IS/CII PROGRAM PLAN Page 26 of 57 1.13.1.2 10CFR50.55a(a)(3)(ii) also allows alternatives when authorized by the NRC, if compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. When submitted under this provision, there must be evidence of unusual hardship or difficulty. Typically this hardship will be dose or excessive disassembly.

1.13.2 Relief Request Required Due to Impracticality 10CFR50.55(a)(g)(5)(iii) and (iv) allows relief to be requested in instances when a Code requirement is deemed impractical with (iv) being specific to examination requirements that are determined to be impractical. The provisions of these two paragraphs are typically used to address impracticalities like limited examination coverage. Under 10CFR50.55(a)(g)(5)(iv), relief requests for examination impracticalities must be provided to the NRC no later than 12 months after the end of the active 120-month interval.

In cases where the ASME Section XI requirements for inservice inspection are considered impractical, Entergy will notify the NRC and submit information to support the determination, as required by 10CFR50.55a(g)(5).

The submittal of this information will be referred to as a Request for Relief.

1.13.3 Requests to use Later Edition and Addenda of ASME Section XI On July 28, 2004, the NRC published Regulatory Issue Summary (RIS) 2004-12, "Clarification on Use of Later Editions and Addenda to ASME OM Code and Section XI". This RIS clarifies the NRC position on using Editions and Addenda of Section XI, in whole or in part, later than those specified in the ISI program. If the desired Edition or Addenda are referenced in 10CFR50.55a(b)(2), the request is submitted following the guidance of the RIS. These types of request are not required to demonstrate hardship, difficulty, or provide evidence of quality and safety. They do need to ensure that all related requirements are also used.

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]NiRCSERCorrespondenier i

Extend the ISI Interval for Certain RPV Welds from 10 to 20 Years Request to use Code Case N-753 in Lieu of IWA-2321 (a)

Use of Alternative Requirements for Weld Reference Systems (IWA-2600)

Request to use Code Case N-739-1 for Qualification of Personnel Performing IP3-ISI-RR-03 NL-09-087 Waiting NRC SER N/A Visual Inspections of Class CC Items and Post-Tensioning Systems

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Page 28 of 57 1.14 Calibration Blocks A detailed list of all ISI calibration blocks to be employed during the fourth interval is provided in SEP-ISI-IP3-002. Per the Electric Power Research Institute (EPRI)

Perfornance Demonstration Initiative (PDI) procedures, calibration blocks fabricated to an Edition of Section XI earlier than the 2001 Edition with 2003 Addenda may be used in the fourth interval without reconciliation.

1.15 Limited Examinations In the event that the examination volume or surface as defined in the ASME Code or Code Cases cannot be examined due to interference by another component or part geometry, then, in accordance with Code Case N-460, a reduction in examination volume or area is acceptable if the reduction is less than 10%. In the event that the reduction in examination volume or area is 10% or greater, a request for relief will be submitted. NRC Information Notice 98-42 provides additional guidance that all ASME Section XI examinations should meet the examination coverage criteria established in Code Case N-460. Therefore, the guidance included in NRC Information Notice 98-42 will be followed by Entergy when determining whether to prepare a relief request or apply the criteria of Code Case N-460 for examinations where less than 100% coverage is obtained. This does not apply to the bare metal visual examination required by Code Case N-729-1. When performing visual examinations to meet N-729-1, the requirements of N-729-1 shall be used for determining allowance for partial examination of the required surface. "

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INTERVAL ISI/CIT PROGRAM PLAN Page 29 of 57 SECTION 2.0 CODE COMPLIANCE INSERVICE INSPECTION PROGRAM

SUMMARY

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INTERVAL ISI/C1I PROGRAM PLAN Page 30 of 57 2.0 APPLICATION CRITERIA AND CODE COMPLIANCE 2.1 ASME Section XI The following provides a summary of the application of ASME Code,Section XI, 2001 Edition through the 2003 Addenda for the IP3, Fourth Ten-Year Interval ISI Program Plan. The application and distribution of examinations for this interval is based upon utilizing Inspection Program B of Section XI.

The results of this application are summarized by ASME Category and Item Number and are contained within the IP3 Code Category Summary Table contained in this document. This table only contains those ASME Item Numbers that are relevant to IP3.

2.1.1 Examination Category B-A - Pressure Retaining Welds in Reactor Vessel Reactor vessel examinations were scheduled to meet the 2001 Edition through the 2003 Addenda of the ASME Code,Section XI, as required by 10CFR50.55a. Article IWB-2420 in the 2001 Edition through the 2003 Addenda of ASME Code,Section XI requires that the sequence of component examinations be repeated during each successive inspection interval, to the extent practical. Table IWB-2500-1, Examination Category B-A, Note (4) specifies at least 50% of the Shell to Flange Welds will be examined by the end of the first inspection period, however, Request for Alternative RR-3-43(I) was submitted to extend the inspection interval to 20 years for all reactor vessel welds.

Item Number B1.21, Reactor Vessel Circumferential Head Welds require all accessible length of the weld to be examined. Weld Summary No. 1-1300-8 is totally inaccessible due to CRDM penetrations, therefore two of the total three Reactor Vessel Circumferential Head Welds will be examined for 67%.

Request for Alternative RR-3-43(I) requires that all of the required Reactor Vessel Welds to be examined by the year 2015 for the third interval. Since the

-third interval was extended, these examinations are tracked in the fourth interval, but are credited for the third and will be performed in accordance with Appendix VIII of the ASME Section XI Code.

A flaw that required reexamination for three periods in accordance with IWB-2420(b) was discovered in the Reactor Vessel Head to Flange Weld. It was discovered in the first period of the third interval. This examination will complete the successive examinations if the flaw is essentially unchanged and therefore it will not be examined in accordance with Request for Alternative RR-3-43(I).

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INTERVAL ISI/CII PROGRAM PLAN Page 31 of 57 The selection of these welds for examination meets the requirements of Examination Category B-A Examination Requirements in the 2001 Edition through the 2003 Addenda of Section XI as modified by Request for Alternative RR-3-43(1).

2.1.2 Examination Category B-B - Pressure Retaining Welds In Vessels Other Than Reactor Vessels The 2001 Edition through the 2003 Addenda of Section XI, Examination Category B-B requires the pressurizer and primary side of steam generators (S/G) be examined during the inspection interval. The examinations may be limited to one of a group of vessels with similar function.

PRESSURIZER Section XI requires examination of both Shell to Head Welds and one foot of one intersecting Longitudinal Weld per head. Both of the Shell to Head Welds and Longitudinal Welds are selected meeting the 100% requirement.

STEAM GENERATORS IP3 has four steam generators. Table IWB-2500-1, Category B-B, Note (1) allows the examination to be limited to one vessel among a group of vessels performing a similar function or 25% for IP3. There is one Tubesheet to Head Weld on each S/G. One of four Tubesheet to Head Welds is selected for examination, thus meeting the one vessel among a group of vessels performing a similar function or 25% requirement.

The selection of these welds for examination meets the requirements of Examination Category B-B Examination Requirements in the 2001 Edition through the 2003 Addenda of Section XI.

2.1.3 Examination Category B-D - Full Penetration Welds Of Nozzles In Vessels This category applies to the reactor vessel, pressurizer, and steam generators.

REACTOR VESSEL ASME Code,Section XI does not allow the deferral of these examinations, except for Nozzle to Reactor Vessel Welds. Table IWB-2500-1, Category B-D, Note (3) allows partial deferral if the examinations are conducted from inside the component and the Nozzle Weld is examined by straight beam UT from the nozzle bore. The examinations required to be conducted from the shell inside diameter may be performed at or near the end of the interval.

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INTERVAL ISI/CuI PROGRAM PLAN Page 32 of 57 However, Request for Alternative RR-3-43(J) was submitted to extend the inspection interval to 20 years for these welds. All of the Reactor Vessel Shell Welds will be examined by the year 2015.

PRESSURIZER The 2001 Edition through the 2003 Addenda no longer has a requirement to examine Pressurizer Inner Radii. However, 10CFR50.55a(b)(2)(xxi)(A) requires utilities to either apply the Volumetric Examination of the 1998 Edition or allows a visual examination with magnification that has a resolution sensitivity to detect a 1-mil width wire or crack. These will be examined volumetrically or with an enhanced visual as required by 10CFR50.55a(b)(2)(xxi)(A) depending on which method is determined to be prudent to IP3.

IP3 Pressurizer nozzles are integrally cast and therefore, contain no Item Number B3.110, nozzle to vessel welds STEAM GENERATOR The 2001 Edition through the 2003 Addenda no longer has a requirement to examine Steam Generator Inner Radii. However, 10CFR50.55a(b)(2)(xxi)(A) requires utilities to either apply the Volumetric Examination of the 1998 Edition or allows a visual examination with magnification that has a resolution sensitivity to detect a 1-mil width wire or crack. These will be examined volumetrically as required by 10CFR50.55ai(b)(2)(xxi)(A).

IP3 Steam Generator nozzles are integrally cast and therefore, contain no Item Number B3.130, nozzle to vessel welds.

The selection of these welds for examination meets the requirements of Examination Category B-D Examination Requirements in the 2001 Edition through the 2003 Addenda of Section XI as modified by Request for Alternative RR-3-43 (I) and 10CFR50.55a(b)(2)(xxi)(A).

2.1.4 Examination Category B-E - Pressure Retaining Partial Penetration Welds In Vessels Examination Category B-E was removed from the Code in the 1992 Addenda.

However, Code Case N-729-1 uses Examination Category B-E for its examination requirements. Code Case N-729-1 has been mandated by 10CFR50.55a. This Code Case requires examination of Reactor Vessel Upper Heads. Based on the susceptibility of materials, the Reactor Vessel Head will be visually examined every refueling outage and the Nozzles and Partial-Penetration Welds in the head will be volumetrically examined every refueling outage.

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INTERVAL ISI/CII PROGRAM PLAN Page 33 of 57 The selection of these welds for examination meets the requirements of Code Case N-729-1 Examination Category B-E Examination Requirements as mandated in 10CFR50.55a.

2.1.5 Examination Category B-F - Pressure Retaining Dissimilar Metal Welds In Vessel Nozzles This category addresses Nozzle to Safe End Welds and Piping Welds.

Examination Category B-F is' excluded from the scope of the initial ISI Program (Revision 0) for the fourth interval. These items are subject of a relief request to be pursued with the NRC that would allow for a risk based program as an alternate to the requirements contained in IWB-2500. There are two refuel outages contained in the first period of the fourth interval; either the inspection scope required by IWB-2500 or the risk based scope approved by the NRC will be complete prior to completing the second outage of the first period.

2.1.6 Examination Category B-G Pressure Retaining Bolting, Greater Than 2" In Diameter Components with bolting greater than 2" in diameter include the reactor vessel and reactor coolant pumps. Examinations will be conducted as required in Table IWB-2500-1 in the 2001 Edition through the 2003 Addenda of Section XI. The Reactor Coolant Pump Bolting will only be examined if one of the reactor coolant pumps is disassembled. This is the same requirement as for Examination Category B-L-2. All other B-G-1 components are scheduled for examination.

During previous intervals piping, pump, and valve bolting examinations were scheduled by bolt. For the forth interval these examinations have been combined to one summary number that requires examination of all the bolting of a component.

The selection of these components for examination meets the requirements of Examination Category B-G-1 Examination Requirements in the 2001 Edition through the 2003 Addenda of Section XI.

2.1.7 Examination Category B-G Pressure Retaining Bolting, 2" And Less In Diameter This category includes manway bolting, valve bolting, flange bolting in piping, and reactor coolant pump seal bolting. Examinations will be conducted as required in Table IWB-2500-1 in the 2001 Edition through the 2003 Addenda of Section XI. This bolting will only be examined if associated connections are disassembled.

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INTERVAL ISI/CII PROGRAM PLAN Page 34 of 57 For components other than piping, bolting examinations will be required only when the component is examined under Examination Category B-B, B-L-2, or B-M-2. IP3 has grouped B-G-2 bolting in accordance with components examined under Examination Category B-B, B-L-2, or B-M-2. This grouping is contained in the IDDEAL Software Suite, ScheduleWorks module in the "Program Type" field.

During previous intervals piping, pump, and valve bolting examinations were scheduled by bolt. For the fourth interval these examinations have been combined to one summary number that requires examination of all the bolting of a component.

During previous intervals Steam Generator and Pressurizer manway bolting examinations were also scheduled by bolt. For the fourth interval these examinations have been combined to one summary number for each manway that requires examination of all the bolting of the manway.

10CFR50.55a(b)(2)(xxi)(B) has added a limitation to the 2001 Edition through the 2003 Addenda of Section XI. It requires for Item B7.80, to follow the requirements of the 1995 Edition, if CRDM Bolting is reused. The examination requirement of the 1995 Edition of Section XI is a VT-1 visual examination of CRDM bolting each interval. The NRC condition only requires the VT-I on bolting that is disassembled and reused.

The selection of these components for examination meets the requirements of Examination Category B-G-2 Examination Requirements in the 2001 Edition through the 2003 Addenda of Section XI as modified by 10CFR50.55a(b)(2)(xxi)(B).

2.1.8 Examination Category B-J - Pressure Retaining Welds In Piping Examination Category B-J of the ASME Code Section XI, 2001 Edition through the 2003 Addenda requires examination of Class 1 piping welds.

Examination Category B-J is excluded from the scope of the initial ISI Program (Revision 0) for the fourth interval. These items are the subject of a planned relief request to be pursued with the NRC that would allow for a risk based program as an alternate to the requirements contained in IWB-2500.

There are two refuel outages contained in the first period of the fourth interval; either the inspection scope required by IWB-2500 or the risk based scope approved by the NRC will be complete prior to completing the second outage of the first period.

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Page 35 of 57 INTERVAL ISI/CII PROGRAM PLAN 2.1.9 Examination Category B-K - Welded Attachments For Vessels, Piping, Pumps, And Valves Examination Category B-K of the ASME Code Section XI, 2001 Edition through the 2003 Addenda requires examination of integral attachments. For vessel attachments, Note (4) allows only one welded attachment of only one of the multiple vessels to be selected for examination for multiple vessels of similar design, function, and service. For single vessels, only one welded attachment shall be selected for examination. IP3 has one PZR Welded Attachment that is selected for examination.

For piping, pumps, and valves, inspection of 10% of the total population .of Integral Welded Attachments is required. Ten Percent (10%) of all Piping Welded Attachments and 10% of all Pump Welded Attachments are selected for examination. IP3 does not have any Class 1 valve welded attachments.

The selection of these welds for examination meets the requirements of Examinatiofi Category B-K Examination Requirements in the 2001 Edition through the 2003 Addenda of Section XI.

2.1.10 Examination Categories B-L-1 And B-L Pressure Retaining Welds In Pump Casings, And Pump Casings This category involves reactor coolant pumps and requires volumetric examination on Pump Casing Welds and visual examination of Pump Internals when disassembled. The reactor coolant pumps are the only Code Class 1 pumps.

B-L-1 requires examination of one pump in each group of pumps performing similar functions in the system. The three welds on one of the four Reactor Coolant Pumps are selected for examination meeting the 25% requirement.

B-L-2 requires examination of the pump interior of one pump in each group of pumps performing similar functions in the system. However, this examination is only required when a pump is dissembled for maintenance, repair, or volumetric examination. Scheduling ticklers(t) have been placed in the IDDEAL Software Suite, ScheduleWorks for Reactor Coolant Pumps, requiring examination if disassembled.

The selection of these welds for examination meets the requirements of Examination Categories B-L-1 and B-L-2 Examination Requirements in the 2001 Edition through the 2003 Addenda of Section XI.

Indian Point Unit 3 SEP-ISI-IP3-001 ,Entergy ASME SECTION XI FOURTH TEN-YEAR Rev.

INTERVAL ISI/CII PROGRAM PLAN Page 36 of 57 2.1.11 Examination Categories B-M-1 And B-M Pressure Retaining Welds In Valve Bodies, And Valve Bodies This category only involves reactor coolant, residual heat removal, and safety injection valves. Examinations will be conducted as required in Table IWB-2500-1. There are a total of 17 valves that fall into this examination category.

IP3 has grouped these valves based on size, design, manufacturing method, and function into four groups of valves. This grouping is contained in the IDDEAL Software Suite, ScheduleWorks module in the "Program Type" field.

B-M-1 requires examination of one valve in each group of valves that are of the same size, constructural design, and manufacturing method, and that performs similar functions in the system. There are no Class 1 Valve Body Welds at IP3.

B-M-2 requires examination of the valve internals of one valve in each group of valves that are of the same size, constructural design, manufacturing method, and that performs similar functions in the system. However, this examination is only required when a valve is dissembled for maintenance, repair, or volumetric examination. No valve body internal surfaces have been selected. This requirement will be met during the repair replacement process.

The selection of these welds for examination meets the requirements of Examination Categories B-M-1 and B-M-2 Examination Requirements in the 2001 Edition through the 2003 Addenda of Section XI.

2.1.12 Examination Category B-N-i - Interior of Reactor Vessel These examinations will be conducted each inspection period. This meets the Examination Category B-N-i Examination Requirements in the 2001 Edition through the 2003 Addenda of Section XI.

2.1.13 Examination Category B-N Welded Core Support Structures And Interior Attachments To Reactor Vessel These examinations will be scheduled in the second period to coincide with the inspection of the reactor vessel. The selection of these welds for examination meets the requirements of Examination Category B-N-2 Examination Requirements in the 2001 Edition through the 2003 Addenda of Section XI.

Indian Point Unit 3 SEP-IS1-IP3-001 Entergy ASME SECTION XI FOURTH TENIYEAR Rev.

INTERVAL ISI/CII PROGRAM PLAN Page 37 of 57 2.1.14 Examination Category B-N Removable Core Support Structures These examinations will be conducted during the second period to coincide with the inspection of the reactor vessel. The selection of these welds for examination meets the requirements of meets the Examination Category B-N-3 Examination Requirements in the 2001 Edition through the 2003 Addenda of Section XI.

2.1.15 Examination Category B-O - Pressure Retaining Welds In Control Rod Housing And Instrument Nozzle Housings The ASME Code,Section XI, 2001 Edition through the 2003 Addenda requires volumetric or surface examination of 10% of peripheral Control Rod Drive Housings during the inspection interval. There are 34 peripheral Control Rod Drive Mechanisms (CRDMs) on the reactor vessel head. To meet the Code requirements, four CRDMs have been selected.

The selection of these components for examination meets the requirements of Examination Category B-O Examination Requirements in the 2001 Edition through the 2003 Addenda of Section XI.

2.1.16 Examination Category B-P - All Pressure Retaining Components The pressure testing program at IP3 meets the requirements of ASME Code,Section XI, 2001 Edition through the 2003 Addenda for Class 1 systems.

Details are contained in the pressure test program.

Code Case N-722 is being implemented under Examination Category B-P. IP3 has four hot leg connections that will be visually inspected each refueling outage and four cold leg connections that will be visually inspected once this interval.

The selection of these components for examination meets the requirements of Examination Category B-P Examination Requirements in the 2001 Edition through the 2003 Addenda of Section XI and the requirements of Code Case N-722 as mandated in 10CFR50.55a.

2.1.17 Examination Category B-Q - Steam Generator Tubing The Steam Generator Tube inspection program at IP3 is governed by iP3 Technical Specifications.

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- Entergy ASME SECTION XI FOURTH TEN-YEAR Rev.

INTERVAL ISI/CuI PROGRAM PLAN Page 38 of 57 2.1.18 Examination Category C-A - Pressure Retaining Welds In Pressure Vessels This category applies to the steam generators, residual heat removal heat exchangers (RtHR HX), and boron injection tank (BIT). Note 3 states that "In the case of multiple vessels of similar design, size, and service, the required examinations may be limited to one vessel or distributed among the vessels."

All four S/Gs have three shell circumferential welds, one vessel head weld, and one tubesheet to shell weld. The two RHR HX have one shell circumferential weld and one vessel head weld. The BIT has two vessel head welds.

One S/G and one RHR HX willbe examined. The S/G contains three shell circumferential vessel welds and the RHR HX has one. Therefore, four of 14 or 21% will be examined. One S/G, one RHR HX, and two BIT vessel head welds will be examined for four of eight or 50%. One of four S/G tubesheet to shell welds will be examined for one of four or 25%.

The selection of these welds for examination meets the requirements of Examination Category C-A Examination Requirements in the 2001 Edition through the 2003 Addenda of Section XI.

2.1.19 Examination Category C-B - Pressure Retaining Nozzle Welds In Vessels This category applies to steam generators and RHR HX heat exchangers. Note (1) in Table IWC-2500-1, Category C-B, excludes manways and handholes.

Note (3) requires that nozzles selected initially for examination shall be reexamined over the service life of the component. Note (5) allows that in the case of multiple vessels of similar design, size, and service, the required examinations may be limited to one vessel or distributed among the vessels.

Both of the Vessel Nozzle Welds and Inner Radii on one S/G are selected for examination. Each RHR HX has 4 nozzles with reinforcing plates requiring four surface and ultrasonic examinations this interval and two VT-2 examinations each period on the telltale holes in the reinforcing plates.

The selection of these welds for examination meets the requirements of Examination Category C-B Examination Requirements in the 2001 Edition through the 2003 Addenda of Section XI.

Indian Point Unit 3 SEP-ISi-IP3-001 Entergy ASME SECTION Xl FOURTH TEN-YEAR Rev.

INTERVAL ISI/CII PROGRAM PLAN Page 39 of 57 2.1.20 Examination Category C-C - Welded Attachments For Vessels, Piping, Pumps, And Valves Examination Category C-C of the ASME Code Section XI, 2001 Edition through the 2003 Addenda requires examination of integral attachments. For vessel attachments, Note (4) allows for multiple vessels of similar design, function, and service, only one welded attachment of only one of the multiple vessels shall be selected for examination. For single vessels, only one welded attachment shall be selected for examination. IP3 has two Welded Attachments on each RHR HX and four welded attachments on the BIT. One of the four RHR HX Welded Attachments and one of the four BIT Welded Attachments are selected for examination or 25% of all Vessel Welded Attachments.

For piping, pumps, and valves, inspection of 10% of the total population of Integral Welded Attachments, is required. Ten percent (10%) of all Piping Welded Attachments are selected for examination. IP3 does not have any Class 2 pump or valve welded attachments.

The selection of these welds for examination meets the requirements of Examination Category C-C Examination Requirements in the 2001 Edition through the 2003Addenda of Section XI.

2.1.21 Examination Category C-F-i- Pressure Retaining Welds In Austenitic Stainless Steel Or High Alloy Piping Examination Category C-F-1 of the ASME Code Section XI, 2001 Edition through the 2003 Addenda requires examination Austenitic Class 2 piping welds.

Examination Category C-F-1 is excluded from the scope of the initial ISI Program (Revision 0) for the fourth interval. These items are the subject of a relief request to be pursued with the NRC that would allow for a risk based program as an alternate to the requirements contained in IWC-2500. There are two refuel outages contained in the first period of the fourth interval; either the inspection scope required by IWC-2500 or the risk based scope approved by the NRC will be complete prior to completing the second outage of the first period.

2.1.22 Examination Category C-F Pressure Retaining Welds In Carbon Or Low Alloy Steel Piping Examination Category C-F-2 of the ASME Code Section XI, 2001 Edition through the 2003 Addenda requires examination Carbon or Low Alloy Steel Class 2 piping welds.

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INTERVAL ISI/CII PROGRAM PLAN Page 40 of 57 Examination Category C-F-2 is excluded from the scope of the initial IST Program (Revision 0) for the fourth interval. 'These items are the subject of a planned relief request to be pursued with the NRC that would allow for a risk based program as an alternate to the requirements contained in IWC-2500.

There are two refuel outages contained in the'first period of the fourth interval; either the inspection scope required by IWC-2500 or the risk based scope approved by theNRC will be complete prior to completing the second outage of the first period.

2.1.23 Examination Category C-H - All Pressure Retaining Components The pressure testing program at IP3 meets the requirements of ASME Code,Section XI, 2001 Edition through the 2003 Addenda for Class 2 systems.

Details are contained in the pressure test program.

2.1.24 Examination Category D-A - Welded Attachments For Vessels, Piping, Pumps, And Valves Examination Category D-A of the ASME Code Section XI, 2001 Edition through the 2003 Addenda requires examination of integral attachments. For Vessel Attachments, Note (3) allows for multiple vessels of similar design, function, and service only the welded attachment of one of the multiple vessels shall be selected for examination. For single vessels, only one welded attachment shall be selected for examination. IP3 has three multiple vessels and a single vessel with one integral attachment. One integral attachment is selected on one of the vessels for each group of vessels. In addition, one integral attachment on the single vessel is selected for examination. Four of the 11 vessel welded attachments are selected for examination or 36% of all vessel welded attachments.

For piping pumps and valves, inspection of 10% of the total population of Integral Welded Attachments is required. Ten percent (10%) of all Piping and Pump Welded Attachments are selected for examination. IP3 does not have any Class 3 valve welded attachments.

The selection of these welds for examination meets the requirements of Examination Category D-A Examination Requirements in the 2001 Edition through 2003 Addenda of Section XI.

2.1.25 Examination Category D-B - All Pressure Retaining Components The pressure testing program at IP3 meets the requirements of ASME Code,Section XI, 2001 Edition through the 2003 Addenda for Class 3 systems.

Details are contained in the pressure test program.

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--- e*y ASME SECTION XI FOURTH TEN-YEAR Rev.

INTERVAL ISI/CII PROGRAM PLAN Page 41 of 57 2.1.26 Examination Category E-A, Containment Surfaces Examination Category E-A of the ASME Code Section XI, 2001 Edition through the 2003 Addenda requires examination of Class MC "Metallic Containment" pressure-retaining components and their integral attachments, as well as, the metallic shell and penetration liners of Class CC "Concrete Containment" pressure-retaining components and their integral attachments.

IP3 will examine 100% of the accessible inside surface area of the Containment Vessel. The IDDEAL Software Suite, ScheduleWorks module, is used to track 401 inspection areas and one complete containment roll-up inspection for a total of 402 inspections each period. The bolted connections are also scheduled for a VT-3 visual examination under the Item Number El.1lb during the interval to satisfy the requirements of 10CFR50.55a(b)(2)(ix)(G). IP3 does have areas that are considered inaccessible. These are contained in the IDDEAL Software Suite ScheduleWorks module as inactive El .11 components with component notes stating they are inaccessible.

10CFR50.55a(b)(2)(ix)(H) requires VT-3 examinations of containment bolted connections will be conducted whenever containment bolted connections are disassembled for any reason.

One hundred percent (100%) of the Moisture barrier will be visually examined each inspection period. In the IDDEAL Software Suite, ScheduleWorks module is used to track the 13 inspection areas and one complete moisture barrier roll-up inspection for a total of 14 inspections each period.

This meets the Examination Category E-A Examination Requirements in the 2001 Edition through 2003 Addenda of Section XI as modified by l0DFR 50.55a.

2.1.27 Examination Category F-A - Supports Examination Category F-A of the ASME Code Section XI, 2001 Edition through the 2003 Addenda requires 25% of Class. 1 Piping Supports, 15% of Class 2 Piping Supports, and 10% of Class 3 Piping Supports to be examined during the inspection interval. For multiple components other than piping, within a system of similar design, function, and service, the supports of only one of the multiple components are required to be examined. The supports have been separated by type as defined in Note (1) to Examination Category F-A. This type has been added to the Item Number to clearly identify each support by type. IP3 also has split out their snubber supports. Twenty-five percent (25%) of the Class 1 supports have been selected and are prorated by type and system. Fifteen percent (15%) of the Class 2 supports have been

Indian Point Unit 3 SEP-ISI-IP3-001 Entergy ASME SECTION XI FOURTH TEN-YEAR Rev.

INTERVAL ISI/CII PROGRAM PLAN Page 42 of 57 selected and are prorated by type and system. Ten percent (10%) of the Class 3 supports have been selected and are prorated by type and system.

For supports, other than piping supports, the. components have been scheduled as follows:

Note 3 requires only one component of multiple components of similar design, function, and service to be schedules for inspection. IP3 scheduled the following supports:

0 one Pressurizer Support; 0 one of four Reactor Coolant Pump Supports;

one of four Steam Generator Supports; one of two R1R HX Supports;

one Boron Injection Tank Support;

one of two Residual Heat Removal Pump Supports;

one of three Safety Injection Pump Supports;

one of two RHR HX Supports;

one Spent Fuel Pit Heat Exchanger Support;

one of two Component Cooling Water Heat Exchangers Supports;

one of five Recirculation Fan Cooler Supports;

one of six Service Water Pump Supports; 0 one of three Component Cooling Water Pump Supports;

one of two Auxiliary Feedwater Pump Supports (Electric);

one Auxiliary Feedwater Pump Supports (Turbine);

one of two Spent Fuel Pump Supports;

one of six Service Water Pump Strainer Supports Seventeen of the forty-seven non piping supports are selected for examination or 40% of all non piping supports.

The selection of these components for examination meets the requirements of Examination Category F-A Examination Requirements in the ASME Code Section XI, 2001 Edition through the 2003 Addenda 2.1.28 Examination Category L-A, Concrete Examination Category L-A of the ASME Code Section XI, 2001 Edition through the 2003 Addenda requires examination of the reinforced concrete portions of Class CC "Concrete Containment" pressure-retaining components.

This inspection divides the containment into three areas. Inspections are conducted on the dome and the upper and lower sections of the cylinder.

Indian Point Unit 3 SEP-ISI-1P3-O01 Entergy E ASME SECTION XI FOURTH TEN-YEAR Rev.

INTERVAL ISI/CII PROGRAM PLAN Page 43 of 57 IP3 last examined these areas in July 2009 and will examine all accessible surface area every 5 years, with exams scheduled in the second and third periods.

The selection of these components for examination meets the requirements Examination Category E-A Examination Requirements in the ASME Code Section XI, 2001 Edition through the 2003 Addenda of Section XI.

2.2 Au2mented Programs 2.2.1 MRP- 139 Category D Welds Pressurizer and Hot Leg Welds > 4 inches of Non-Resistant Material-that have not been mitigated by stress improvement (SI) have a MRP-139 requirement of 100% examination per period not to exceed 5 years for pressurizer welds and 100% examination every 5 years for hot leg locations (including surge line nozzles near the hot leg). IP3 has four welds that are Category D Hot Leg Welds and are selected for examination under the MRP Category D Augmented Program every 5 years.

The selection of these welds for examination meets the requirements Augmented Program MRP Category D Examination Requirements 2.2.2 MRP- 139 Category E Welds Cold Leg Welds > 4 inches of Non-Resistant Material that have not been mitigated by SI have a MRP-139 requirement of 100% examination each 6 years. 1P3 has four welds that are Category E Welds. These welds are selected for examination under the MRP Category E Augmented Program.

The selection of these welds for examination meets the requirements Augmented Program MRP Category E Examination Requirements.

2.2.3 Regenerative Heat Exchanger Welds The Regenerative Heat Exchanger is scheduled for examination in accordance with Class 2 Requirements. The requirements of Code Case N-706 will be followed for all vessel welds. The Regenerative Heat Exchanger has six Vessel Head Circumferential Welds and six Tubesheet to Shell Welds. Each of these welds will receive a VT-2 visual examination each inspection period.

The selection of these welds for examination meets the requirements Augmented Program Regenerative Heat Exchanger Welds examination requirements.

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-- Entergy ASME SECTION XI FOURTH TEN-YEAR Rev. 0 INTERVAL ISI/CII PROGRAM PLAN Page 44 of 57 II S113 CodelnSumma

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I itriIl Percentage' Ex,11injnci if] I xamineud fnewl*,7Examinetd inist'o io_7 I-filli(ID]iin "Secoind*illnEX:jitined B-A(') Pressure Retaining Welds in Reactor Vessel-Reactor Vessel B-A Bi.ll Circumferential Shell Volumetric 2 2 100% All Welds 0 2(1) 0

_ _ Welds B-A B1.12 Reactor Vessel Volumetric 9 9 100% AllWelds 0 90) 0 Longitudinal Shell Welds Reactor Vessel Accessible B-A B1.21 Circumferential Head Volumetric 3 2 67% Length of2 All 0 2(1) 0 Welds Welds( )

Accessible Reactor Vessel Meridional B-A B1.22 Head Welds Volumetric 12 12 100% Length of All 0 12(l) 0 Welds B-A B1 .30 Reactor Vessel Shell to Volumetric 1 1 .100% Weld 0 1(i) 0

___ 1 Flange Weld B-A B11.40 Reactor Vessel Head to Volumetric 1 1(3) 100% Weld 1 0 0 Flange Weld and Surface Category Total 28 27 1 26(l) 0 Note 1: NRC authorized the extension of the third 10-year interval RPV ISI during the current license period, with the next inspection for IP3 due by 2015 via letter number RA-09-024.

Notes for Cat. B-A Note 2: Summary No. 1-1300-8 inaccessible due to CRDM penetrations.

Note 3: This weld contains a flaw that required reexamination for three periods in accordance with IWB-2420(b). The flaw was discovered in the first period of the third interval. This examination will complete the successive examinations if the flaw is essentially unchanged.

B-B Pressure Retaining Welds in Vessels Other Than Reactor Vessels B-B B2.11 Pressurizer Shell-to-Head Volumetric Welds Circumferential B-B B2.12 Pressurizer Shell to Head Welds Longitudinal

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_-=-_Entergy ASME SECTION XI FOURTH TEN-YEAR Rev. 0 INTERVAL ISI/CII PROGRAM PLAN Page 45 of 57 2

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..... . . . Wtiel No. I r uo Requiredn a s i in [tilT eilaAiRetf. (ide Ill] 1"0)25%WeIdII e -2secon--d I I Third to Steam Generators (Primary B-B B2.40 Side) Tubesheet to Head Volumnetric 4 1 25% Weld'i) 0 1 0

_______ ______Weld_______ ______ _______ _____

Category Total 8 5 2 1 2 Note 1: The examination may be limited to one vessel among the group of vessels performing a similar function (Ref. Table IWB-2500-1 Examination INotes for Cat, Ji1 Category B-B, Note 1).

B-D Full Penetration Welded Nozzles inVessels Reactor Vessel Nozzle to Volumetric 8 8 100% Same as lst B-D B3.0 Vessel Welds Interval 0 8() 0 B-D() B3.100 Reactor Vessel Nozzle Volumetric 8 8 100% Same as Ist _080)0

_Inside Radius Section Interval_0_8_)_0 B-D B3.120 Pressurizer Nozzle Inside Volumetric 6 6 100% All nozzles 0 0 6 Radius Section or visual 6_6 10% Anzze___

Steam Generators (Primary Volumetric B-D B3.140 Side) Nozzle Inside Radius or visual 100% All nozzles 4 0 4 Section Category Total 30 30 4 16 1.0 Notes for Cat. B-D Note 1: NRC authorized the extension of the third 10-year interval RPV IS1during the current license period, with the next inspection for IP3 due by 2015 via letter number RA-09-024.

T -

B-E PWR Reactor Pressure VesselfUpper Head)1

+

Reactor Vessel Head wit UNS N0600 nozzles and B-E B4.10 UNS N06082 or UNS W86182 Nozzle partial Penetration Welds

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--- " ASME SECTION XI FOURTH TEN-YEAR Page 46 of 57 INTERVAL ISI/CII PROGRAM PLAN Rectrese Hired eb Exam-~- -I~ Compoents~ xamnd annto-~Nmetb- b. 3/4 Caeoy~Description Meho~onpnetin 'i ,ecne

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ef.&_LItem-No. - Requir'ed. Itra 'in First ..- '-IilTird "eon A~.>'~- Peid Pnd. > Period, N0600 nozzles and UN S ()E eyrfiln B-E B4.20 N06082 or UNS W86182 Vol &/or Sur 1 5(2) 100% Every refueng 21 2 partial penetration welds in outage head Category Total 2 10(2) 4 2 4 Note 1: These examinations are in accordance with Code Case N-729-1 as required by IOCFR50.55a(g)(6)(B).

Notes for Cat. B-E Note 2: Examination of this item number is required each outage. Therefore the number required during the interval is five times the total number of components. This is also reflected in the category total.

B-G-1 Pressure Retaining Bolting, Greater Than 2 in. (50 mm) in Diameter B-G1 B6.10 Reactor Vessel Closure Visual, VT-I 54 54 100% Same as for 1st 18 18 Head Nuts V0interval1 Reactor Vessel Closure Volumetric 54 54 100% intearva st_181818 Studs 0interval BG-1 B6.40 Reactor Vessel Threads in Volumetric 54 54 100% Same as for 1st 0 54 0 Flange interval B-G-1 B6.50 Reactor Vessel Closure Visual VT-l 54 54 100% Same as for 1st Washers, Bushings V interval 18 18 18 B-G-l B6.180 Pumps Bolts and Studs Volumetric 4 0 0% (1)(2) 0 0 0 Pumps Flange Surface B-G-1 B6.190 when connection Visual, VT-1 4 0 0% (t)(2) 0 0 0 disassembled B-G-1 B6.200 Pumps Nuts, Bushings, and Visual, VT-I 4 0 0% ()(2) 0 0 0 Washers Visual, VT- ___4____%_ _____0_0_0 Category Total 228 216 54 108 54 Note 1: Not Required unless disassembled.

Notes for Cat. B-G-1 Note 2: For heat exchangers, piping, pumps, and valves, examinations are limited to components selection for examination under Examination Categories B-B, B-J, B-L-2, and B-M-2. (Ref. Table IWB-2500-1, Examination Category B-G-1, Note 3)

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Item-mbe II Description -

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B-G-2 Pressure Retaining Bolting, 2in. (50 mm) and Less in Diameter Pressurizer Bolts, Studs, Visual, 1 0 0% Same as for3 1st B-G-2 B7.20 and Nuts Viul interval(')( ) 0 0 0 Steam Generator Bolts, Visual, VT-i 8 0 0% Same as for 1st 3

B-G-2 B7.30 Studs, and Nuts interval')() 0 0 0 B-G-2 B7.50 Piping Bolts, Studs, and Visual, VT-i 7 0 0% Sm rst

______ B7.50 Nuts 0 interval)(2)() 0 Same as for 1st B-G-2 B7.60 Pumpts Bolts Studs, and Visual, VT-I 4 0 0% interval (1)(2)(3)(4) 0 0 0 Valves Bolts Studs, and Same as for 1st B-G-2 B7.70 Nuts Visual, VT-1 17 0 0% interval (1)(2)(3)(5) 0 0 0 CRD Housing Bolts, Studs, Visual, VT-i 5 0 0% Se ost B-G-2 B7.80 and Nuts interval (6)

Category Total 38 0 0 0 0 Note 1: Not required unless disassembled.

Note 2: For heat exchangers, piping, pumps, and valves, examinations are limited to components selection for examination under Examination Categories B-B, B-J, B-L-2, and B-M-2 (Ref. Table IWB-2500-14 Examination Category B-G-2, Note 2).

Notes for Cat. B-G-2 Note 3: Examination is only required once per interval."

Note 4: Only one pump of each group of pumps is required as outlined in B-L-2.

Note 5: Only one valve of each group of valves is required as outlined in B-M-2.

Note 6: Examination is only required if disassembled and bolting is reused.

Welded Attachments for Vessels. Pining. Pumps. and Valves g B1G.10 Pressure Vessels Welded Surface Attachments __Srface 1 B 10.20 Piping Welded Attachments Surface 6 B10.30 Pumps Welded Surface 12 B10.30_ Attachments Surface 12

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Category Totall 12 3 0 Notes for Cat. B-L INote 1: Examination is limited to at least one pump in each group of pumps performing similar functions in the system.

Note 2: There are four Reactor Coolant Pumps. Each pump has one Casing Weld; therefore, 3 of the 12 welds are required for 25' B-L-2 Pump Casings B 12.20 Pumps Pump Casing (B-L-2)

Category TotalI 4 j 0 Note 1: Examination is limited to at least one pump in each group of pumps performing similar funci NNote 2: Not required unless disassembled.

B-M-2 I Valve Bodies B12.50 IValve Body, Exceeding NPS 4 (DN 100) (B-M-2)

Category TotalI 17 f 0 Note 1: Examination is limited to at least one valve in each group of valves that are and that perform similar functions in the system.

Note 2: Not required unless disassembled.

Interior of Reactor Vessel

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-i- Entergy ASME SECTION XI FOURTH TEN-YEAR Rev. 0 INTERVAL ISI/CII PROGRAM PLAN Page 49 of 57 Category Total I 3(1) I I INote 1: Examination of this item number is required each period. Therefore the number required during the interval is three times the total e fnumber of components. This is also reflected in the category total.

B-N-2 Welded Core Support Structures and Interior Attachments to Reactor Vessels Reactor Vessel (PWR)

B13.60 Interior Attachments Beyond Beltline Region (B- Visual, VT-3 N-2)

Category Total B-N-3 Removable Core Support Structures IReactor Vessel (PWR)

B-N-3 I B'13.70 Core Support Structure (B- Visual, VT-3 Category TotalI I1 I Retaining Welds in Control Rod Drive and Instrument Nozzle Housings Reactor Vessel (PWR) Volumetric B14.20 Welds in Control Rod or surface Drive CRD Housina

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- igahber~ y Description to Du jring ý k ,quired .Inteival $ in lF irst Sco dI hrd B-P Class 1 PWR Components Containing Alloy 600/82/182(1)

B-P B 15.90 Hot Leg Nozzle-to-Pipe Visual, VE 4 20(2) 100% Each refueling 8 4 8 Connections outage Cold Leg Nozzle-to-Pipe Visual, VE 4 4 100% Once per Connections interval_1_1_2 Category Total 8 16(2) 9 5 10 Note 1: These examinations are in accordance with Code Case N-722 as required by IOCFR50.55a(g)(6)(B).

Notes for Cat. B-P Note 2: Examination of this item number is required each refueling outage. Therefore the number required during the interval is five times the total number of components. This is also reflected in the category total.

C-A Pressure Retaining Welds in Pressure Vessels Pressure Vessels Shell Each C-A C1.10 Circumferential Welds Volumetric 14 4 21% inspection 1 2 interval(' )12)

Pressure Vessels Head Each C-A C1.20 Circumferential Welds Volumetric 8 4 50% inspection 1 1 2 interval)('3)

Pressure Vessels Ec Each C-A C1.30 Tubesheet-to-ShellWeld Volumetric 4 1 25% inspection 0 01

____________-Shel

_interval"0(4) Weld__

Category Total 26 9 2 3 4

Indian Point Unit 3 SEP-ISI-IP3-001 Entergy ASME SECTION XI FOURTH TEN-YEAR Rev. 0 INTERVAL ISI/CII PROGRAM PLAN Page 51 of 57

£ P3 Code a*1 O'sin~y~

j~temý Examination

~ e Mitoxam- . 41.- aminauon Numeberrto be be) shellweldsare EL rn Components in ' xmn r2Percentg or-deseredtio bnn r % Examined in LamiedE 1examiined Note1:

Te exmintiomybelmie to one vesaong tReuiroud tofb vesl of~siia dein ie Ndumbertion NmfTblero NiWC-2500-o,

-~us ten lnwvl _ý6c-.

____ 1, 1'4tra2Prid (I_______ý ý- ,____________

lfý -7 'i ýPeodd Priod

-P Note 1: The examination may be limited to one vessel among the group of vessels of similar design, size, and function (Ref. Table IWC-2500-1, Examination Category C-A, Note 3).

Note 2: There are three vessel shell welds on four SIGs, and one vessel shell weld on two RHR HXs, therefore based on Note 1, 4 of 14 vessel Notes for Cat. C-A shell welds are required to be examined or 2 1%.

Note 3: There is one circumferential head weld on four S/Gs and two RR HX and two on the BIT therefore based on Note 1, 4 of the 8 head welds are required to be examined or 50%.

Note 4: There is one tubesheet to shell weld on four S/Gs, therefore based on Note 1, 1 of the 4 tubesheet to shell welds are required to be examined for 25%.

C-B Pressure Retaining Nozzle Welds in Vessels Nozzles Without Reinforcing Plate in Each C-B C2.21 Vessels > l/2in. (13mm) Surface and 8 2 25% inspection 0 0 2 Nominal Thickness Nozzle volumetric interval")")

to Shell (Nozzle to Head or Nozzle to Nozzle) Weld Nozzles Without Reinforcing Plate in Each C-B C2.22 Vessels > 1/2 in. (13mm) Volumetric 8 2 25% inspection 1 1 0 Nominal Thickness Nozzle interval"' (3)

Inside Radius Section Nozzles With Reinforcing Plate in Vessels > 1/2in. Each C-B C2.31 (13mm) Nominal Surface 50% inspection Thickness Reinforcing intervalc)(')

Plate Welds to Nozzle and Vessel III _ II

Indian Point Unit 3 SEP-ISI-IP3-001

-- Entergy ASME SECTION XI FOURTH TEN-YEAR Rev. 0 INTERVAL ISI/CII PROGRAM PLAN Page 52 of 57

......... ..... ........ m beroto u e hull) "Eiiaminaedmxmato

-Item Dbscifi.s Exam *ton : ,~ b

b .... be...

CieoyMib~ Conponenlt's in,-- cPrcenltage -tXanined in->IExamlibed" ExaiineU inl Examlined1in pte \U. equtli~red i ntervati First Second i hird

____I t~ rliod.

P,,c__ 'edod__ Period Nozzle to Shell (Nozzle to Each C-B C2.33 Head or Nozzle to Nozzle) VT-2 4 6(6) 50% inspection 2 2 2 Welds When Inside of period")")

]Vessel Is Inaccessible period(')t 5 )

Category Total 28 12(6) 4 3 5 Note 1: The examination may be limited to one vessel among the group of vessels of similar design, size, and function (Ref Table IWC-2500-1, Examination Category C-B, Note 4).

Note 2: There are two nozzles on 4 S/Gs; therefore based on Note 1, 2 of the 8 nozzles are required to be examined or 25%.

Notes for Cat. C-B Note 3: There are two nozzle inner radii on 4 S/Gs; therefore based on Note 1, 2 of the 8 inner radii are required to be examined or 25%.

Note 4: There are two nozzles on 2 RHR HXs; therefore based on Note 1, 2 of the 4 nozzles are required to be examined or 50%.

Note 5: There are two nozzle inner radii on 2 RHR HXs; therefore based on Note 1, 2 of the 4 nozzles are required to be examined or 50%.

Note 6: Examination of this item number is required each period. Therefore the number required during the interval is three times the total number of components. This is also reflected in the category total.

C-C Welded Attachments for Vessels, Piping, Pumps, and Valves Each identified Pressure Vessels Welded Surface 8 25% occurrence and C-C C3.10 Attachments each inspection

_____ ______interval (1)(2) (3)

Each identified C-C C3.20 Piping Welded Attachments Surface 132 14 10% occurrence ands each inspection 275 interval (1)(3)

Category Total 140 16 3 7 6

Indian Point Unit 3 SEP-ISI-IP3-001 Ent-ergy ASME SECTION XI FOURTH TEN-YEAR Rev. 0 INTERVAL ISI/CII PROGRAM PLAN Page 53 of 57

\411wl 4111heIl mhIt 4 \2 Ii1uiie to be IXx;IIi~miaftn '1111 t4ob> N Ilkert Ilbkt&~ubd o egory$*..'-* *.Numiber ;Desd -* *iiotht

' C:ii* t =n.ie* ern .cN Examied&I intE ined Eta mined in Examied i

-' y~-J ~ ~- .. ~ -~ ileiod ~ -RPrio~~ e6j Note 1: For multiple vessels of similar design, function, and service, only one welded attachment of only one of the multiple vessels shall be selected for examination. For single vessels, only one welded attachment shall be selected for examination (Ref Table IWC-2500-1, Examination Category C-C, Note 4).

Notes for Cat. C-C Note 2: There are two welded attachments on each RHR HXs and four welded attachments on the BIT, therefore 2 of the 8 welded attachments are required to be examined for 25%.

Note 3: Examination is required whenever component support member deformation is identified (Ref. Table IWC-2500-1, Examination Category C-C, Note 6).

D-A Welded Attachments for Vessels, Piping, Pumps, and Valves Each identified D-A DI.10 Pressure Vessels Welded Visual, VT-1 11 36% occurrence and 0 2 2 Attachments each inspection interval(1)(1)(3)

Each identified occurrence and D-A D1.20 Piping Welded Attachments Visual, VT-I 133 14 10% 4 4 6 each inspection interval(3)

Each identified Pumps Welded10% occurrence and D-A D1.30 Attachments Visual, VT- 9 1 each inspection 0 0 interval (3)

Category Total 153 19 5 6 8 Note 1: For multiple vessels of similar design, function, and service, the welded attachments of only one of the multiple vessels shall be selected for examination. For single vessels, only one welded attachment shall be selected for examination (Ref. Table IWC-2500-1, Examination Category D-A, Note 3).

Notesfor Cat. D-A Note 2: There are three groups of multiple vessels (two with two vessels and one with six vessels) and one single vessel, therefore, 4 of the It are required to be examined for 36%.

Note 3: Examination is required whenever component support member deformation is identified (Ref. Table IWD-2500-1, Examination Category D-A, Note 4).

Indian Point Unit 3 SEP-LSL-1P3-0O1

-- Entergy ev

--- ASME SECTION XI FOURTH TEN-YEAR Rev. 0 INTERVAL ISI/CII PROGRAM PLAN Page 54 of 57

=

E-A Containment Surfaces E-A E.ll1 Containment Vessel Accessible Surface Areas Category Total 422 418 418 Note 1: Item Number El. I lb is utilized to ensure compliance with the specific requirements of 10CFR50.55a(b)(2)(ix)(G) and (H) for bolting.

Notes for Cat. E-A Note 2: Examination of this item number is required each period. Therefore the number required during the interval is three times the total number of components. This is also reflected in the category total.

F 1.10(S) Class 1 Piping Supports - Visual, VT-3 Snubbers F;1.10A IClass I Piping Supports -

FOne Directional FL .GB Class I Piping Supports -

IMulti-directional FI.10C Class 1 Piping Supports - Visual, VT-3 Thermal Movement

Indian Point Unit 3

-- EntergyRe. a .SEP-ISI-IP3-001

ASME SECTION XI FOURTH TEN-YEAR Rev. 0 INTERVAL ISI/CII PROGRAM PLAN Page 55 of 57 Examined inl E~xamined in SPeriod~

s 2 Piping Supports - Visual, VT-3

)bers Fl.20A Class 2 Piping Supports - Visual, VT-3 1One Directional Class 2 Piping Supports -

FMulti-directional F1.20C Class 2 Piping Supports - Visual, VT-3 IThermal Movement Total Class 2 Piping F1.20 Supports F1.30(S) Class 3 Piping Supports - Visual, VT-3 Snubbers FI.30A Class 3 Piping Supports - Visual, VT-3 IOne Directional F .301B Class 3 Piping Supports -

Multi-directional Class 3 Piping Supports - Visual, VT-3 F1.30C Thermal Movement

Indian Point Unit 3 SEP.ISI.1P3-001 Entergy ASME SECTION XI FOURTH TEN-YEAR Rev. 0 INTERVAL ISI/CII PROGRAM PLAN Page 56 of 57 I P3 CodeCa teg ry tmrary'>,. ~

Numhbero NT, 0 t ~NUmbero

~Catcgo~ Descption- Vitu Mto am Copnnsi67E8 _ -

amisetio P

Lecetg n Examined'In b 1t

- Examnined ,xmie e6 in 'Examined be in

~ F1.30 CMasV 3 3Piping Suppt t~n 0.

Iubr mNo - DYin iterval Se hrd

'~-~

_______ __________, -. -ý:- --

1W1nR

2 F _in l~rdd3/4 67Prrio'djirs- -I

.~ei

-~

Each F-A Fl.30 Class 3 Piping Supports Visual 679 68 10% inspection 18 26 24 VT 3 interval Supports other than Visual, Each F-A F1.40 Piping Supports (Class V47 17 36% inspection 2

4 7 6 1,2,3, and MC) VT3 interval( )(3)

Category Total 1623 234 72 86 76 Note 1: The total percentage sample shall be comprised of supports from each system, where the individual sample sizes are proportional to the total number of non-exempt supports of each type and function within each system (Ref. Table IWF-2500-1, Examination Category F-A, Note 2).

Note 2: For multiple components other than piping, within a system of similar design, function, and service, the supports of only one of the Notes for Cat. F-A multiple components are required to be examined (Ref. Table IWF-2500-1, Examination Category F-A, Note 3).

Note 3: 1 Pressurizer Support, 1 of 4 Reactor Coolant Pump Supports, 1 of 4 Steam Generator Supports, I of 2 RHR HX Supports, I BIT Support, I of 2 RHR Pump Supports, 1 of 3 SI Pump Supports, 1 of 2 RHR HX Supports, 1 Spent Fuel Pit Heat Exchanger Supports, I of 2 CCW Heat Exchangers Supports, 1 of 5 Recirculation Fan Cooler Supports, I of 6 Service Water Pump Supports, I of 3 CCW Pump Supports, I of 2 AFW Pump Supports (Electric), 1 AFW Pump Supports (Turbine), 1 of 2 Spent Fuel Pump Supports, 1 of 6 Service Water Pump Strainer Supports. 17 of the 47 non piping supports are selected for examination or 36% of all non piping supports.

L-A Concrete L-A LI.11 All accessible surface areas General 3 601) 100% IWL-2410 0 3 3 Visual 3 60) 0 3 3 Category Total Note 1: IWL-2410 requires 100% examination every 5 years. Therefore the number required during the interval is twice the total number of components. This is also reflected in the category total.

MRP-139D Non Mitigated Hot Leg Welds of Non-Resistant Material R-A R1.20 MRP 139 Category D Volumetric 4;0)(1) Every five 0 4 I I years

Indian Point Unit 3 SEPASI-0P3-001

-- Entergy ASME SECTION XI FOURTH TEN-YEAR Rev. 0 INTERVAL ISI/CII PROGRAM PLAN Page 57 of 57

_____ _**** ** ': :* **I3Cd*Category *Summia~r, .... ,u** ..... .... Wio*

-fP3Code týdN S x nt Eximeroin ai Category Totaltobe 0 N:

\II 'j lid I(U epie Ir~l~rg nterI I in First I Third jf .per__oi,,_ R'&i- ULIerid Category Total 4 8(l) 47 0 1 4 Note 1: Hot Leg Welds >4 inches of Non-Resistant Material that have not been mitigated by SI have a MRP-139 requirement of 100%

Notes for MRP- 139D examination each 5 years. Therefore the number required during the interval is twice the total number of components. This is also reflected in the category total.

MRP-139E Non Mitigated Cold Leg Welds of Non-Resistant Material Volumetric R-A R1.20 MRP 139 Category E (MRP 139 4 80) (1) Every six years 4 0 4 Cat E)

Category Total 4 8(1) (1) - 4 0 4 Note 1: Cold Leg Welds >4 inches of Non-Resistant Material that have not been mitigated by SI have a MRP-139 requirement of 100%/

Notes for MRP-139E examination each 6 years. Therefore the number required during the interval is twice the total number of components. This is also reflected in the category total.

Regenerative Heat Exchanger Welds Pressure Vessels Head )Each C-A C1.20(A) Circumferential Welds VT-2(') 18(6) 100% inspection 6 6 6 CruernilWlsperiod(')

Each C-A C1.30(A) Pressure Vessels Tubesheet . VT-2) 6 18(2) 100% inspection 6 6 6 to Shell Weld period(')

Category Total 12 36(2) 12 12 12 Notes for Note 1: Code Case N-706.

Regenerative Heat Note 2: Examination of this item number is required each period. Therefore the number required during the interval is three times the total Exchanger Welds number of components. This is also reflected in the category total.

NL-09-097, Submittal of Fourth Ten-Year Interval Inservice Inspection and Containment Inservice Inspection Program Plan

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1.0 INTRODUCTION

SUMMARY

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NL-09-097, Submittal of Fourth Ten-Year Interval Inservice Inspection and Containment Inservice Inspection Program Plan

Text

SUBJECT:

Dear Sir or Madam:

Enclosure:

Title:

1.0 INTRODUCTION

SUMMARY

SUMMARY

1.0 INTRODUCTION

1.0 INTRODUCTION

SUMMARY

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