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| document type = Inservice/Preservice Inspection and Test Report, Letter
| document type = Inservice/Preservice Inspection and Test Report, Letter
| page count = 71
| page count = 71
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=Text=
{{#Wiki_filter:* NL-16-097 September 6, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box249 Buchanan, NY 10511-0249 Tel 914 254 6700 Anthony J. Vitale Site Vice President
==SUBJECT:==
Indian Point Fifth Ten Year Interval lnservice Inspection Program Plan Indian Point Unit Number 2 Docket No. 50-247 License No. DPR-26
==Reference:==
Entergy Letter to NRC (NL-16-091 ), "Indian Point Fifth Ten Year Interval lnservice Inspection Program Plan," dated August 17, 2016
==Dear Sir or Madam:==
Entergy is submitting this letter to supplement the submittal of the fifth ten year interval lnservice Inspection Program plan for Indian Point 2 (IP2) in the referenced letter. That submittal was to consist of two sections but only one section was enclosed. The second section is enclosed with this letter to fully comply with the requirements of 10 CFR 50.55a(g)(4)(ii). If you have any questions or require additional information, please contact Mr. Robert Walpole, Manager, Regulatory Assurance at (914) 254-6710. Sincerely,
==Enclosure:==
Fifth Ten Year lnterva) lnservice Inspection Program Plan cc: Mr. Douglas Pickett, Senior Project Manager, NRC NRR DORL Mr. Daniel H. Dorman, Regional Administrator, NRC Region 1 NRC Resident Inspectors Office Mr. John B. Rhodes, President and CEO, NYSERDA Ms. Bridget Frymire, New York State Dept. of Public Service ENCLOSURE TO NL-16-097 FIFTH TEN YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN ENTERGY NUCLEAR OPERATIONS, INC. INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247 
-PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 1 of69 IP2 FIFTH TEN-YEAR INTERVAL INSERVICE INSPECTION (ISl)J CONTAINMENT INSERVJCE INSPECTION (Cll) PROGRAM PLAN ENTERGY NUCLEAR ENGINEERING PROGRAMS APPLICABLE SITES All Sites: 0 Specific Sites: ANO 0 GGNS 0 IPEC 181 JAF 0 PLP 0 PNPS 0 RBS 0 VY 0 W3 0 HON 0 Current Revision Safety Related: Program Section Revision Summary Description of Change Yes 0 No ------*--i-------------------------------l I II Revision 4 Incorporated the following changes: 4 1_. e:,_m_on_wnh 20-os I_ 1<7' PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No.4 Page 2 of69 REVIEW AND CONCURRENCE SHEET Program Section Title: IP2 Fifth Ten-Vear Interval lnservice Inspection (ISl)/Containment lnservice Inspection (Cll) Program Pian Reviewed __ Programs Erl Reviewed For I EJIWL Only ANll: Allan Schiaffino Authorized Nuclear Jn-Service Inspector {ANll) Concurred: Nelson Azevedo Responsible S Date Date Date Date .s/c)s-J h */x/0 f-sk/tl:;; vj2c,f 16 
-SECTION All REVISION STATUS SHEET PROGRAM SECTION NO. SEP-151-IP2&deg;001 Revision No.4 Page 3 of69 SEP-iSl-IP2-<J01 R4. PAGE REVISION STATUS PAGE NO. As Applicable REV. Incorporate Data for*Fifth Ten-Year Interval 
* --::--Entergy Section TABLE OF CONTENTS PROGRAM SECTION No. SEP-ISl*IP2*001 Revision No.4 Page4 of69
==1.0 INTRODUCTION==
AND PLAN DESCRiPTION ............................ ,. ........................................... 6 1.1 Introduction .......................... ,. ................................................................................... 6 1.2 IS! Inspection Interval.. ............................................................... ., ............................... 7 1.3 IP2 Original Construction Codes of Record ............................................................. 11 1.4 IP2 Fifth Inspection Interval ASME Code of Record ................................................. 13 1.5 lnservice Inspection Program Plan Development.. .................................................. 16 1.6 lnservice Inspection Boundary Development .......................................................... 17 1.7 Inspection, Examination, and Testing Activities Not Controlled By thrs Plan ............ 20 1.8 Augmented Inspection Programs ................................................................. ., ......... 20 1.9 Administrative Controls ............................................................................................ 28 1.1 O ID DEAL Data-Management Program .................................................................... 28 1.11 Adoption and Use of ASME Section XI Code Cases ............................................... 29 1.12 Technical Positions .......................................................................... ,. ..................... 31 1.13 Relief Requests ....................................................................................................... 32 1.14 Calibration Blocks ......................................................................... ,, ........................ 35 1.15 Limited Examinations .......................................... , .................................................... 35 2.0 APPLICATION CRITERIA AND CODE COMPUANCE ......................................................... 37 2.1 ASME Section XI .................................................................................................... 37 3.0 ATIACHMENTS .......................................................................................................... " ........ 52 Attachment 3.1 Table 2.1 IP2 Code Category Summary ............................................... 53 
----Entergy SECTION 1.0 PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No.4 Page 5 of69 INTRODUCTION AND PLAN DESCRIPTION 
-PROGRM'i SECTION No. SEP*ISl*IP2*001 Revision No.4 Page 6 of 69
==1.0 INTRODUCTION==
AND PLAN DESCRIPTION 1.1 Introduction This document establishes the Fifth Ten-Year Interval lnservlce Inspection (ISi) Program Plan and the Containment lnservice Inspection (Cll) Program Plan for Indian Point Nuclear Generating Station Unit 2 (lP2), in accordance with the Code of Federal Regulations (CFR), Title 10, Part 50, Section 55a, "Codes and Standards" (10 CFR 50.55a). The IP2 Fifth Ten-Year Interval ISi Program Plan is compliant with ASME Section XI, Division 1, uRules for lnservice Inspection of Nuclear Power Plant Components 2007 Edition through 2008 Addenda, as conditioned by 10 CFR 50,55a; and altered as allowed by 1 O CFR 50.55a(g)(6) or 1 O CFR 50.55a(z) and documented in the included requests for relief." The inspection and non-destructive examination of systems, structures, and components (SSCs) will be performed to the extent practical1 and possible as permitted by existing designs, equipment arrangements, available access, and radiological conditions. Relief request reference documentation, is also provided for those component$ where meeting the code requirement is impractical or unnecessarily burdensome. Throughout the Fifth Ten-Year Interval ISi Program Plan, reference is made to SEP-ISl-IP2-002, "IP2 Fifth Ten-Year Interval lnservice Inspection (181)/Containment lnservice Inspection (Cll) Schedule and Bases Document". The IP2 Fifth Ten-Year Interval ISi Program is also used for implementation of the license renE!Wal commitments described in LO-LAR-2011-0174 CA 35, CA 37, CA 38, CA 40, and CA 65. This Program Plan outlines the requirements for inspection of: 1.1.1 ISi -Pressu.re Retaining Components/Supports e ISi Class 1, 2, and 3 (Quaflly 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 exceptions: c The RI-ISi Program shall be re-employed at IP2* during the 5th Ten-Year JSI Interval; however. the RI-ISi Program shall be implemented utilizing ASME Code Case N-716-1 approved for use per USNRC Regulatory Guide 1.147. This alternative Inspection Program is used in lieu of the requirements of IWS-2420, IWB-2430, Table IWB-2500-1, Examination Categories B-F and B-J, IWC-2420, IWC-2430 and Table IWC-2500-1 (excluding Examination Categories C-C and C-H), for inservice inspection of Class 1 piping welds or Class 2 components, IWB-2200 and IWC-2200 for preservice inspection of Class 1 piping welds or Class 2 components, or as additional requirements for Class 3 or Non-Class components. The Inspection Program provides alternative criteria for selection, examination method, and examination coverage based on ASME Code 'Case N-716-1. 1 The construction pe1T11il for Indian Point Unit 2 was issued on October 14, 1956. Per 10 CFR 50.55a(g)(1) Jnservice inspection requiroments far older plants (pre-1971 CPs). "For a boiling or pressurized water-cooled nuclear power facility whose construction pemiit was issued before January 1, 1971, components (including supports) must meet lhe requirements of paragraphs (g}(4} and (g)(5)
* to the extent practical." * 
-----Entergy PROGRAM SECTION No. &sect;J;P*ISl*IP2*Q01 Revision No.4 Page 7 of69 e As defined by IWF-1300, snubber support hardware such as tugs, bolting, pins, clamps, and structural steel between the snubber pin and the pressure retaining item and between the snubber pin and 1he building steel are included in the support population and examined in accordance with Subsection IWF per this Program Section.
* Class 1 pressure retaining welds containing Alloy 600/821182 in accordance with Code Case N-722-1, "Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/821182 Materials", Section XI Division 1 with conditions specified in 10 CFR 50.55a(g)(6)0i)(E)(2) through (4). (Reference Augmented Program 1.8.4). If? 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 10 CFR 50.55a(g)(6)(ii)(D)(2} through (6). (Reference Augmented Program 1.8.5). e Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigatiqn Activities in accordance with Code Case N-770-1, "Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities", Section XI, Division 1, in accordance with the requirements in 10 CFR 50.55a(g)(6)(1i)(F)(2) through (10). Note: License Renewal commitment LO-LAR-2011-0174 CA37 is tracked and monitored in accordance with the Code Case N-770-1 examination requirements, and augmented existing ISi inspections as appropriate. (Reference Augmented Program 1.8.6). 1.1.2 CH -Containment ISi Pressure Boundary Liner/Concrete e 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 a Augmented inspection programs are detailed Jn Section 1.8. 1.2 JSR Inspection Interval 1.2.1 ISi -IWA, IWB, IWC, IWO, & IWF Interval History The commercial service date for IP2 was August 1, 197 4. The table below summarizes the IP2 Interval dates.
PROGRAM SECTION No. SEP*ISl*IP2*001 Revision No.4 Page 6 of69 IP2 Interval Dates Summary 10-Year Interval Interval Inspection Start Date End Date length of Interval Interval 1 Julv 1, 1974 June 30, 1984 1 O vears. O months 2 Julv 1. 1984 June 30. 1994 1 O vears, O months 3c July 1. 1994 Februarv 28 2007 012 vears. 8 months 4 March 1. 2007 Mav 31. 2016 bg vears. 3 months 5" June 1, 2016 Mav 31, 2026 1 O vears. O months *The Third Ten-Year Inspection lnleNal ISi program plan was orlginally approved ror the effedive dates from July 1, 1994 truough June 30, 2004. ASME Boiler & Pressure Vessel Code, Section XI (1989 EdilionJ Paragraph IWA-2430 (e), allows inspection inleNals 10 be extended whenever there is an outage greater than six months. An interval extension equivalent to the lime Iha! the unit has been out of service ls allowed. The first period was rrom July 1, 1994 lo September 1 B. 1998 having been extended 326 days for the 0850 Breaker Outage. The second period was from September 19, 1998 la December 5, 2002 having been extended 321 days for steam generator replacement outage and olller plan! equipment emergencies. Thus, Ille third period was re.scheduled from June 30. 2004 lo February 28, 2007. These dales can be extended or decreased 1 year to coincide with a refueling outage. b IP2 Fourth Ten-Year lnspedlon Interval and lhls lSl/Cll Planwm be effective from Maren 1. 2007, through and lnc.'Llding May 31, 2016. II should be noted that !he. plant's cutrenl {original} operating license will expire on September 28. 2013. Entergy is in the process qf a license renewal application. The end date of the 4th lnteival will be controlled by the ISl/Cll Program Plan. commensurate with !he Operating License Renewal Application. c During the Third Period al the Third ISi ln!eival. Illa Rlsk-lnfonned Program (Rl*ISI} was approved for use via NRC Safely Evaluation Report {TAC No. MC0303). During !h!s lime period the requited percentage for !he period was compleled. The Rl*ISI Program Is re-employed at IP2 during* lhe 41" Ten-Year !SI lnleival via Relief Request RR*OS. This program is comprised of Class 1 (ASME categories B*F and B*JJ piping segments/elements. As an alternative lnspecllon Program the criteria far selection. examination method, examination coverage, and extent is based on EPRI repor1 TR-112657. *As part of tile Fifth Inspection lnteNal update. IP2 implemented Code case N*716* 1. This aflemauve lnspeciioo Program is used In lieu of !he requirements of IWB-2420. IWB-2430. Table IWS...2500*1. Examination Categories B*F and B*J. IWC.2420. IWC*2430 and Table IWC-2500-1 (excluding Examination Categories C-C and C*H). for inservlce inspection of Class 1 piping welds or Class 2 components. IWB-2200 and IWC-2200 for pieservlce inspection of Class 1 piping welds or Class 2 components. or as additional requirements for Class 3 or Non-Class comjl-Onents. 1.2.2 Cll -IWEJIWL Interval History On September 9, '1996, 10 CFR 50.55a 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 water cooled nuclear power plants and IWL contains the requirements for ISl 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 _I 
-Entergy' ------------PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No.4 Page 9 of69 inspection interval. Therefore the First Period Examinations were completed by September 9, _2001 to meet 10 CFR 50.55a requirements. The IWE inspection periods were therefore: 10-Year Inspection inspeci:lon Period IWE Period Dates Interval 1 1 Sep. 9, 1996 -Sep. 9, 2001 i 2 Seo. 10, 2001 -Jan. 9, 2005 1 3 Jan. 10. 2005 -aFeb. 28. 2007 2 1 March 1, 2007 -Mav 31 2010 2 2 June 1 2010-Mav 31. 2014 2 3 June 1 2013-Mav 31. 2016 :i' 1 June 1. 2016-Mav 31, 2019 3t> 2 June 1, 2019-Mav 31. 2023 3b 3 June 1, 2023 -Mav 31 2026 a Based upon this extended First Period that ended on September 9, 2001, the First 10-Yr Interval for IP2 Containment ISi was originally scheduled to end on May 9, 2010, but was shortened lo align with the Third.ISi Interval. b Although it is only the IWE Inspection Interval at IP2, the ISi Plan is combined and labeled in the Tille as the 5m Ten-Year lnlerval as well as in the Database. 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 June, 2000; the second inspection was completed in June 2005; the third inspection was completed during 2010; and the fourth inspection completed during 2015. Subsection IWL-2421 does not apply to lP2. 1.2.3 Fifth Ten-Year Bnterval Schedule The IP2 Fifth Ten-Year Interval ISi Program Plan and CH Plan will be effective from June 1, 2016 through May 31, 2026. 1.2.3.1 IWB, !WC, IWD, IWE, and IWF Inspection Schedules: The inspection schedule for the fifth inspection 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 
* ------Entergy PROGRAM SECTION No *. SEP-ISJ-IP2-001 Revision No.4 Page 10 of 69 Inspection Period 1 2 3 table summarizes the period dates for the fifth inspection interval as defined by IWB-2411, IWC-2411, IWD-2411, IWE-2411 and IWF-2410. The inspection schedule for each ISi Period is provided in the lddeal software. Changes to the stated Inspection Interval or Inspection Period dates, if deemed necessary, will be documented. IP2 Fifth Interval lnsoectlon Periods Summarv Dates Period Start Period End Years of Plant PDant Refueling Out.ages Operation Within Date Date Period within Period June 1. 2016 Mav 31, 2019 3 years RF0-23 (Serina 2018) June 1. 2019 May 31, 2023 4years RFD-24 (Spring 2020) RF0-25 (SprinQ 2022) June 1. 2023 May 31, 2026 3 years RF0-26 (Spring 2024) RF0-27 (Spring 2026) 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). Any concrete surface areas that become affected by a repair/replacement activity shall be examined in accordance with the requirements of IWL-2510 at I year(+/- 3 months) following completion of repair/replacement activity. If plant operating conditions are such that examination of portions of the concrete cannot be completed within this time interval, examination of those portions may be deferred until the next scheduled plant outage. 1.2.3.2.1 Notification to New York State In compliance with Atomic Safety and licensing Board Order (Approving Settlement of Contention NYS-24), Docket Nos. 50-247-LR and 50-286-LR, ASLBP No. 07-S58-03"LR-BD01(January26, 2012), and the Settlement Agreement Regarding New York State Contention 24 (December 21, 201 i) approved therein: 1.2.3.2.1.1 When an inspection is completed, reviewed and approved by the Unit ISi Engineer. a copy of the completed inspection report shall be foiwarded to Licensing. 1.2.3.2.1.2 The Unit ISi Engineer shall issue a Work Tracking CR to Licensing to assure that copies of the report(s) are forwarded to:
AE -=-----== ntergy PROGRAM SECTION No. SEP01Sl*IP2*001 Revision No.4 Page 11of69 State of New York Office of the Attorney General and Power Systems Operations, New York State Department of Public Service Notes: The names and mailing addresses of the State-designated recipients of the reports are retained and updated (as necessary) by Licensing. Copies of the above-referenced Order and Settlement Agreement also are retained by Licensing. The Settlement Agreement provides that Entergy (or its successor in interest) shall provide New York State with copies of the results of future ASME Section XI IWL visual inspections and/or the results of inspections or tests that might replace, augment, or update these visual Inspections of the exterior concrete surfaces of the IP2 containment. 1.2.4 Alignment of ISi and Containment ISi Intervals An integral part of this Fourth Ten-Year Interval Program Plan was the merging of the Cll Program Plan with the ISi Program Plan. The Fifth Inspection Interval will continue the merger of these two program plans. This will facilitate one set of ASME Code requirements for both program plans. The First Interval Cll Program Plan was originally effective from September 9, 1996, through and including May 9, 2010. This time period was shortened to end on February 28, 2007. !WE Containment inservice examinations scheduled for the first 40-month period were completed during the Third Period of the Third ISi Inspection Interval. These examinations now serve the same purpose as service baseline examinations. The required IWL inservice examinations were also completed and re-inspections are scheduled at 5 year frequency. The next scheduled IWL inservice examination will be performed in 2020 and documented in the IS! 5th Interval Program Plan. (Tracked under W0-438424). Henceforth, the Second Ten-Year Interval for IWE/IWL Containment ISi inspections at IP2 commenced on March 1, 2007 coincident with the start of the Fourth 10-Year ISi Program Interval. Therefore, both the ISi and the Cll IWEIJWL Program Plans were aligned with the Fourth Interval ISi Program schedule and ASME Code requirements and thus will be aligned with the Fifth Interval ISi Program Schedule and ASME Code requirements. 1.3 IP2 Original Construction Codes of Record The construction permit for Indian Point Unit 2 was issued on October 14, 1966. At that time, the ASME Boiler and Pressure Vessel Code covered fabrication of only nuclear vessels. Piping was built to the rules of USAS 831.1.0-1955, Power Piping. There were no Codes identified for pumps and valves, In the record documents. 1.3.1 ISi-Systems, Structures, and Components The primary IP2 original Construction Codes for major equipment are listed below.
AE ntergy PROGRAM SECTION No. SEP-iSl-IP2-001 Revision No.4 Page 12 of69 Component System Pressure Vessels, non-RCS Reactor Vessel, Pressurizer, & RCP Bowl Steam Generators Piping Design -General Design Criteria Construction Code ASME Boiler & Pressure Vessel Code, Section VIII, 1968 ASME Code, Section 111, Class A, 1965 Edition thru the 1966 Addenda ------------------------! ASME Code, Section Ill, 1980 Edition, plus winter 1981 addenda (stress report to the 1965 ASME B&PV Code, Section Ill, plus Addenda thru summer 1966) ASA Section 831. 1 Pressure Piping Code 1955 1.3.1.1 ISi Pre-service Inspections Westinghouse performed the preservice inspection of Indian Point Unit 2 in 1971 (Ref. Westinghouse letter No. LEE-1043, dated Nov. 12, 1971). 1.3.2 Cll -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 0.25-in. thick liner located on top. The 0.25-in. liner plate is covered with 3 ft. of concrete, which forms the floor of the containment and serves to carry internal equipment loads. The basemat ts supported directly on rock. 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 fl 6 in. thick. A steel liner is attached to the inside face of the concrete shell to form a leak tight membrane. The steel liner is 0.50 in. thick in the first three courses, thickened to 0.75 in. at penetrations, and 0.375 in. thick for the remaining portion of the cylindrical wall. The hemispherical dome is a 135 ft. diameter 3 ft. 6 in. thick shell that is lined with a 0.50 in liner plate. The inside radius of the dome is equal to the inside radius of 
---=Entergy PROGRAM SECTION NO. SEf*ISJ.IP2*0C>1 Revision No.4 Page 13 of 69 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 Ill, 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. The liner, penetration sleeves and airlocks were constructed and tested to the requirements of Specification 9321-01-225-3. 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 IP2 commencing operations. However, in accordance with the regulatory requirements of 1 O CFR 50.55a, 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 five years for the implementation of the First Period Examinations, which were completed by September 9, 2001. 1.4 IP2 Fifth Inspection Interval ASME of Record 1.4.1 The regulations in 1 O CFR 50.55a(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 10 CFR 50.55a(b), one year prior to the beginning of each 120-month ISi inspection interval. This is considered the Code of Record. The Code of Federal Regulation in effect one year prior to the beginning of the fifth inspection interval was published in June 2011 as CFR76FR36232. This CFR incorporated, by reference, the ASME Section XI, 2007 Edition through 2008 Addenda in paragraph (b)(2) with limits and conditions. Subsequently, CFR73FR52749 was published in September 2008 requiring expedited implementation of Code Cases and N-722. In October 2008 CFR73FR57235 was published correcting errors in CFR73FR52749. In June 2011 CFR76FR36269 was published requiring implementation of Code Cases N-722-1 and N-770-1 . 1.4.2 Based on the referenced CFRs in 1.4.1, the IP2 Fifth Ten-Year Interval ISi Program Plan is based on the requirements of the 2007 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI through 2008 Addenda with the limits and conditions contained in 1 O CFR 50.55a(b)(2} and fisted in SEP-ISl-IP2-002. Additionally, based on specific limits, earlier editions and addenda are also being used as described below. 
----Entergy 10 CFR. 50.65a Reference 10 CFR 50.55a(b}(2)(ii} 10 CFR 50.55a(b}(2)(xiv) 10CFR 50.55a(b)(2){XViii}(A) 10 CFR 50.55a(b)(2)(xxi)(A} PROGRAM SECTION No. SEP-ISl*lf2-001 Revision No.4 Page 14 of69 Mandated Additional Requirements/Conditions/Exemptions Section XI Condition: Pressure-retaining welds in ASME Code Class 1 piping (applies to Table IWB-2500 and IWB-2500-1 and Category B-J}. If the facility's application for a construction permit was docketed prior to July 1, 1978, the extent of examination for Code Class 1 pipe welds may be determined by the requirements of Table IWB-2500 and Table IWB-2600 Category B*J of Section XI of the ASME BPV Code in the 197 4 Edition and Addenda through the Summer 1975 Addenda or other requirements the NRC may adopt (Note: This reference Is provided for Information/completeness only, Category B-J welds will be examined in accordance with Code Case N-Section XI condition: Appendix VIII personnel qualification. All personnel quanfied for performing ultrasonic examinations in accordance with Appendix VIII must receive 8 hours of annual hands-on training on specimens that contain cracks. Licensees applying the 1999 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1)(1i} of this section may use the annual practice requirements in Vll-4240 of Appendix VII of Section XI in place of the 8 hours of annual hands-on training provided that the supplemental practice is performed on material or welds that contain cracks. or by analyzing prerecorded data from material or welds that contain cracks. In either case, training must be completed no earlier than 6 months prior to performing ultrasonic examinations at a licensee's facility, Section XI Condition: NDE personnel certification: First provision. Level I and II nondestructive examination personnel must be recertified on a 3-year interval in lieu of the 5-year interval specified in the 1997 Addenda and 1998 Edition of IWA-2314, and IWA-2314(a) and IWA-2314(b) of the 1999 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1)(ii) of this section. Section XI Condition: Table IWB-2500-1 examination requirements: Table IWB-2500-1 examination requirements: First provision. The provisions of Table IWB 2500-1, Examination Category B-D, Full Penetration Welded Nozzles in Vessels, Items 83.120 and 83.140 (Inspection Program B) of the 1998 Edition must be applied when using the 1999 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1)(ii) of this section. A visual examination with magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the allowable flaw length criteria in Table IWB-3512-1, 1997 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1 )(ii) of this section, with a limiting assumption on the flaw aspect ratio (i.e., a/I= 0.5), may be performed instead of an ultrasonic examination. 
* -::::::-Entergy 10 CFR 50.55a Reference 1 O CFR 50.55a(b)(2)(xxii) 10 CFR 50.55a(b)(2}(xxix) 10CFR 50.55a(g}(6)(1i){D)(1) 10CFR 50.55a{g}(6)(ii){E)( 1) 10CFR 50.55a(g){6}(ii)(F)(1) PROGRAM SECTION No. SEP-1Sf-IP2-001 Revision No.4 Page 15 of 69 Mandated Additional Requirements/Conditions/Exemptions Section XI condition: Surface examination. The use of the provision in IWA-2220, "Surface Examination," of Section XI, 2001 Edition through the latest edition and addenda incorporated by reference in paragraph (a)(1)(ii) of this section, that allows use of an ultrasonic examination method ls prohibited. Section XI condition: Nonmandatory Appendix R. Nonmandatory Appendix R. "Risk-Informed Inspection Requirements for Piping," of Section XI, 2005 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1)(ii) of this section, may not be implemented without prior NRC authorization of the proposed alternative in accordance with oaraaraoh {z) of this section. Augmented ISi requirements: Reactor vessel head Inspections. All licensees of pressurized water reactors must augment their inservice inspection r:>rogram with ASME Code Case N-729-1, subject to the conditions specified in paragraphs (g)(6)(ii)(0)(2) through {6) of this section. (Program Note: (g)(G)(ii)(D)(4) By September 1, 2009, ultrasonic examinations must be performed using personnel, procedures, and equipment that have been qualified by blind demonstration on representative mockups using a methodology that meets the conditions specified in paragraphs (g)(6)(ii)(D)( 4)(1) through (iv), instead of the qualification requirements of Paragraph -2500 of ASME Code Case N""." 729-1. References herein to Section XI, Appendix VIII, must be to the 2004 Edition with no addenda of the ASME BPV Code.} Augmented ISi requirements: Reactor coolant pressure boundary visual inspectfons. All licensees of pressurized water reactors must augment their inservice inspection program by implementing ASME .Code Case N-722-1, subject to the conditions specified in paragraphs (g)(6)(ii}(E)(2) through (4) of this section. The inspection requirements of ASME Code Case N-722-1 do not apply to components with pressure retaining welds fabricated with Alloy 600/821182 materials that have been mitigated by weld overlay or stress improvement. Augmented ISi requirements: Examination requirements for Class 1 piping and nozzle dissimilar0metal butt welds. Licensees of existing, operating pressurized-water reactors as of July 21, 2011 must implement the requirements of ASME Code Case N-770-1, subject to the condttions specified in paragraphs (g)(6)(ii)(F)(2) through (10) of this section, by the first refueling outage after August 22, 2011. 
----Entergy 1.5 lnservice lns@;!ectlon Program Plan Development PROGRAM SECTION No. SEP-1SHP2-001 Revision No.4 Page 16 of69 1.5.1 ISllCU n Class 1, 2, and 3 (Quality Group At 81 and C), and Class MC and CC The Fifth Ten-Year lnteival 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 1 O CFR 50.55a e ASME Boiler & Pressure Vessel Code Section V -2001 Edition through 2003 Addenda (Currently in use for Nondestructive Examinations, Repair and Replacement Activities, Pressure Testing and Flaw Evaluation Programs) 0 ASME Boiler & Pressure Vessel Code Section XI -2001 Edition through 2003 Addenda as modified by 10 CFR 50.55a(b)(2) (Currently in use for Nondestructive Examinations, Repair and Replacement Activities, Pressure Testing and Flaw Evaluations Programs) o ASME Boiler & Pressure Vessel Code Section V -2007 Edition through 2008 Addenda e ASME Boiler & Pressure Vesset Code Section XI -2007 Edition through 2008 Addenda as modified by 10 CFR 50.55a(b)(2) and (g)(6)(ii) lfll United States Nuclear Regulatory Commission Regulatory Guides m Regulatory Guide 1.16, Rev. 4 ill Regulatory Guide 1.26, Rev. 2 11 Regulatory Gulde 1.26, Rev. 4 a Regulatory Guide 1.83, Rev. 1 " Regulatory Guide 1.147, Latest Revision "' IP2 UFSAR
* IP2 Improved Technical Specifications {2 IP2 First Interval Ten-Year lnservice Inspection Program Plan "' IP2 Second Interval Ten-Year lnservice Inspection Program Plan 111 JP2 Third Interval Ten-Year lnservice Inspection Program Plan <II IP2 Fourth Interval Ten-Year lnservice Inspection Program Plan "' I P2 First Ten-Year Containment lnservice Inspection Program Plan 
, ......... -:-::::::-Entergy PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No.4 Page 17 of69
* IP2 Second Ten-Year Containment lnservice 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-ISl-IP2-002. 1.6 lnservice Inspection Boundary Development 10 CFR 50.55(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 inservice inspection {ISi) requirements of 1 O CFR 50.55a to the systems and components installed at IP2, ISi class designations and boundaries have been defined and established. Taking into consideration the fact that the Code of Federal Regulations (CFR) does not define components identified for Class 2 or 3 designations, the NRG issued Regulatory Guide 1.26. Revision 2 of Regulato!Y Guide 1.26, dated June 1975, provided the Initial guidance for determining component2 classification. Revision 4 of Regulatory Guide 1.26, dated March 2007, provides the current guidance for classification of components. The guidance presented in these regulatory guides, as appropriate, was/is used In establishing component classification and boundaries. In those instances where the guidance conflicted with IP2 design or licensing basis, the IP2 design or licensing basis was/is used. ISi Class boundaries designating Quality Group A, B, C, (Class 1, 2, 3), MC, & CC piping, components, and structures are controlled and depicted on the ISi drawings listed in ISl-IP2-002. Welds, components and their supports that are subject to inservice inspection are shown on lnservice Inspection Isometric Drawings that can be obtained from Entergy's Configuration Control Management system. Pursuant to 10 CFR 50.55a, the inservice inspection requirements of ASME Section XI have been assigned to these components within the constraints of existing plant design and the guidance of Regulatory Guide 1.26. 1.6.1 ISi Boundaries and Classification For ISi Class 1 component(s) (Quality Group A), the requirements of Subsection IWB, Code Case N-722-1, Code Case N-729-1 and Code Case N-770-1 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). The P&IDs are marked up with triangular shaped "flags" which include alpha characters designating Quality Group A, B, C, MC. CC, or blank for non-nuclear safety class. The blank flag has no letter symbol and is designated with a completely filled-in triangular shape in black. -Component a vessel, concrete containment. pump, valve, storage tank. piping system, or core support slruciure (IWA-9000). 
--::==-Entergy PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No.4 Page 18 of69 Classification boundary breaks (Quality Group A, B, C, or MC) at a component within the system or between systems shall include the component at the higher classification. A weld adjoining a higher class component to a component of lower classification shall be designated at the lower classification. SEP-ISl-IP2-002 provides a list of applicable ISi and Cll drawings for this program. Copies of these drawings are available through Entergy's Configuration Control Management System.
* 1.6.2 IWEllWL 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 (fWE) 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 boundaiy are: e Dome finer 4' Wallllner e Basemat liner o Penetration sleeves o Personnel air lock o Equipment access hatch/personnel lock a 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 10 CFR 50.55a, 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
* Concrete basemat 
---Entergy PROGRAM SECTION No. SEP..fSl-f P2-001 Revision No.4 Page 19 of69 ISi Class CC containment components shall be inspected per the requirements of ASME Section XI, Subsection lWL Table IWL-2500-1 as modified by 10 CFR 50.55a, Code Cases, Technical Positions. and Relief Requests approved by the NRC. The IP2 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 (CH} Drawings The Cll 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 Cll Drawings is contained in SEP-ISl-IP2-002. 1.6.4 Piping Penetrating Containment Boundaries 1.6.4.1 Quatity Group A, B, and C Piping and Components Piping and components that penetrate containment, including their welded attachments, that are Quality Group A, 8, 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. 4 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 are part of the MC designation for !WE components.
* 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. e Repair/Replacement shall be in accordance with the requirements of IWA-4000 and the Indian Point design specification and ihe construction code.
* Pressure test shall be in accordance with and 10 CFR 50 Appendix J. 
--=-Entergy PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No.4 Page 20 of69 "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 Bv 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 f P2 Improved Technical Specifications (JTS), 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. 816.20 will be examined in accordance with the requirements of ITS Section 5.5. 7. 1.7.2 System Pressure Tests for Class 1, 2, and 3 components will be scheduled and controlled in accordance with IP2 site procedures. 1.7.3 Inspection and Testing of Snubbers will be scheduled and controlled in accordance with IP2 site procedures. 1.7.4 [nservice Testing of Pumps and Valves will be performed and controlled in accordance with IP2 site procedures. 1. 7 .5 The ASME Section XI Repair/Replacement Program will be implemented and maintained in accordance with site procedures. 1.8 Augmented lnsggction Programs Augmented examinations are those that are outside the scope of 10 CFR 50.55a(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 10 CFR 50.55a, 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. The process of implementing changes to augmented examination. requirements and schedules, resulting from commitments to the NRC, may not utilize the provisions of 1 O CFR 50.55a(a)(z), or (g)(S)(iii) or {iv); rather, changes are required to be evaluated using the 10 CFR 50.59 screening/review processes. 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 5.5.5 of the ITS and Section 5.1.2.5.2 of 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 IP2; however, the regulatory guide is used for guidance in establishing a basis for the examination. 
---=-Entergy PROGRAM SECTION No. SEP-lS8-IP2-001 Revision NoA Page 21 of69 Source Document: Technical Specification 5.5.5 and UFSAR Section 5.1.2.5.2. Commitment No.: None. Associated Documents:
* FSAR paragraphs 4.2.2.5 and 5.5.E. " NRC Regulatory Guide 1.14, Reactor Coolant Pump Flywheel Integrity.
* NUREG-1431, "Standard Technical Specifications -Westinghouse Plants". I? Westinghouse WCAP-15666, "Extension of Reactor Coolant Pump Motor Flywheel Examination". Purpose: Reactor coolant pump (RCP} motor flywheels are examined due to a concern about high-energy missiles inside containment that could potentially damage* and cause the simultaneous failure of multiple trains of multiple re!ated systems. Scope: The scope includes the examination of all four RCP upper flywheels. Method: Surveillance of the primary coolant pump flywheels shall consist of an ultrasonic examination of the upper flywheels. Industry Code or Standards: ASME Section XI, 2007 Edition through 2008 Addenda. Frequency: Survemance of the primary coolant pump flywheels shall consist of a 100% volumetric inspection of each upper flywheel each 20 years. Acceptance Criteria or Standard: Any flaws detected during examination shall be forwarded to Entergy Engineering for resolution. Regulatory Basis: Technical Specification 5.5.5 defines the scope and frequency of the required examinations. Even though there is no longer a commitment to Regulatory Guide 1.14, the basis for augmented examination of each reactor coolant pump flywheel is Regulatory Guide 1.14. Revision 1, August 1975. Reporting Requirements: Any flaws detected during examination shall be forwarded to Entergy Engineering for resolution. 1.8.2 NEI Initiatives -Materials Reliabillty Program (MRP-146 Revision 1) for Management of Thermal Fatigue in Normally Stagnant Non*lsoJable Reactor Coolant System Branch Lines EPRI has developed a program titled "Management of Thermal Fatigue in Normally Stagnant NonQlsolable Reactor Coolant System Branch Lines"(MRP-146) guideline dated June 2005 with NEI 03-08 "needed" elements. The objective --' 
--==-Entergy PROGRAM SECTION No. SEP-ISl*IP2-00::1 Revision No.4 Page22 of69 of this guideline is to provide a common industry approach for assessing the potential for thermal fatigue cracking in normally stagnant non-isolable RCS branch piping. Supplemental guidance (MRP-146S, 1018330) was released as a nuclear QA product in January 2009. MRP-146 Rev. 1 supersedes MRP-146 Rev. O in its entirety and supersedes most elements of MRP-146S including the "needed" actions as described In that document. Implementation of MRP-146 Rev. 1 was completed during 2012 refueling outage. Source Document: "' NRC Bulletin 86-08, <<Thermal Stresses in Piping Connected to Reactor Coolant Systems". o Management of Thermal Fatigue in Normally Stagnant Non*lsolable Reactor Coolant System Branch Lines"(MRP-146} guideline dated June 2005. o Management of Thermal Fatigue in Normally Stagnant Non-lsolable Reactor Coolant System Branch Lines -Supplemental Guidance" (MRP-1468). Commitment No.: Industry Commitment Associated Documents: IP2 calculation IP-CALC-07-00088. _ Purpose: Plan and implement a program to provide continuing assurance that unisolable sections of all piping connected to the RCS will not be subjected to combined cyclic and static thermal and other stresses that could cause fatigue failure during the remaining life of the unit. Scope: In accordance with MRP-146 Rev. 1, guidance has been provided to inspect Reactor Coolant System Branch Lines. The following have been identified for examination: MRP-146 Rev 1 {and 1465) H Configuration line line 96, 3 inches Normal Charging line into cold leg 21, has a MRP-146 Rev 1 {and 1468) requirement of 100% volumetric and visual examinations. IP2 has one weld, 96-2 that is classified as an H charging configuration line and is selected for examination under the MRP-146 Rev 1 (and 1468) every refueling outage. The selection of this weld for examination meets the requirements of Augmented Program MRP 146 Rev 1(and 1468) H model configuration Examination Requirements. 146 Rev 1 (and 1465) DH Configuration Une Line 82, 22 intermediate leg 2 inches drain line, Line 83, 23 intermediate leg 2 inches drain line and 84, 24 leg 2 inches drain line have a MRP-146 Rev 1 (and 146S) requirement of 100% volumetric and visual examinations. IP2 has three welds, 824, 834 and 84-4 that are classified as 
-----Entergy PROGRAM SECTION No. SEP-ISHP2-001 Revision No.4 Page 23 of69 DH drain configuration lines, and are selected for examination under the MRP-146 Rev 1 (and 146S) every other refueling outage. The selection of these welds for examination meets the requirements of Augmented Program MRP 146 Rev 1{and 1468) DH model configuration Examination Requirements. Method: Subject piping segments shall be visual and ultrasonically examined, as required. Industry Code or Standards: MRP-146, Rev. 1, and MRP-1468. Frequency: Reference Attachment 3, Table 2.1-3. Acceptance Criteria or Standard: Flaws detected during examination shall be evaluated by comparing the examination results to the acceptance standards established in ASME Section XI, Subsection IWC. Regulatory Basis: NRC Bulletin 88-08. Reporting Requirements: Any flaws detected during examination shall be forwarded to Entergy Engineering for resolution. 1.8.3 Examination of Socket Welds license Renewal Commitment#46 (LO-LAR-2011-0174 CA 65) requires five volumetric weld metal inspections of socket welds be performed periodically during each 10-year ISi interval scheduled as specified by IWB-2412 of the ASME Section XI Code during the period of extended operation. In lieu of volumetric examinations, destructive examinations may be performed, where one destructive examination may be substituted for two volumetric examinations. The small-bore piping socket weld sample is selected from the RI-ISi small bore socket welds population. However it is in addition to ASME B&PV Code Case N-716-1, the only examination that is required on a socket weld by the RI-ISi Program is a VT-2 visual examination each refueling outage with the exception for Item No. R1 .11 which volumetrically examines the base material at the toe of the weld. Source Document: License Renewal Commitment #46. Commitment No.: LO-LAR-2011-0174 CA 65. Associated Documents: LER 10-004-00, SER Related to License Renewal, Dated 08/30/2011 (ML 11201A033). Purpose: As part of License Renewal for effective aging management, the NRC requires a robust inspection program for socket welds. This action is to address concerns based on the operating experience at IP2. The inspection sampling should be statistically significant so that cracking, if present. will be detected prior 
.... ---Entergy PROGRAM SECTION No. SEP*ISl-IP2-001 Revision No.4 Page 24 of69 to leakage of the component. A sample of 25 welds was determined to be an adequate sample size. Scope: Twenty-five (25) socket welds selected from the most susceptible and risk-significant welds scheduled as specified by IWB-2412 of the ASME Section XI Code. The small-bore piping socket weld sample is selected from the RI-ISi small bore socket welds population. The current RI-ISi program is based upon Code Case N-716-1. The population selected will include all high safety significant socket welds with a postulated damage mechanism. Additionally, high safety significant socket welds without a postulated damage mechanism will be selected to meet the 25 total requirement, that are located on the reactor coolant pressure boundary inside containment before the first isolation valve. Pipe breaks in these locations are not isolable and were assigned the highest conditional core damage probability in the Code Case N-716-1 analysis. Method: Volumetric weld metal inspections of socket welds shall be performed. In lieu of volumetric examinations, destructive examinations may be performed, where one destructive examination may be substituted for two volumetric examinations.
* Industry Codes or Standards: MRP-350-Nondestructive Evaluation: Examination of Small Bore Socket Welds for Vibration and Thermal Fatigue Frequency: The inspection sample shall be examined during each of the ISi 10-year intervals of extended operation. Acceptance Criteria or Standard: The sample welds shall be free of cracking. If cracking is detected during the examinations, there will be an extent of condition review 1o evaluate the inspection sampling size to ensure that it is adequate to identify cracking that could occur at other locations. Regulatory Basis: SER Related to License Renewal, Dated 08/30/2011 ML 11201A033). Reporting Requirements: Any flaws detected during examination shall be foiwarded to Entergy Engineering for resolution. 1.8.4 Class 1 pressure retaining welds containing Alloy 600/82/182 in accordance with Code Case N" 722-1, "Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/821182 Materials", Section XI Division 1 with conditions specified in 10 CFR 50.55a(g}(6)(ii)(E)(1} through (4). Source Document: ASME Code Case N-722-1, "Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials". Commitment No.: None Associated Documents: 10 CFR 50.55a(g)(6)(ii)(E)(1) through ( 4 ). Purpose: Identification of the presence of pressure boundary leakage. 
------.-Entergy* PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No.4 Page25 of69 Scope: Code Case N-722-1, Items 815.90 and 815.95, IP2 has four reactor vessel hot leg connections that will be visually inspected each refueling outage and four reactor vessel cold leg connections that will be visually examined each inspection interval. Method: o Direct VE of the bare metal surface, or alternatively, I) VE performed with the insulation In place using remote visual examination equipment that provides resolution of the component metal surface equivalent to a bare metal direct VE. Industry Code or Standards: ASME Section Xl 2007 Edition through 2008 Addenda. Frequency; Every other refueling outage in accordance with Code Case N-722-1. Acceptance Criteria or Standard: IWB-3522, absence of evidence of pressure leakage. Regulatory !Basis: 10 CFR 50.55a(g)(6)(ii}(E). Reporting Requirements: Evidence of pressure leakage shall be reported immediately to Entergy Engineering. The results of the examination shall be reported in the outage inspection summary report. 1.8.5 Reactor vessel upper head penetrations in accordance with Code Case "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 10 CFR 50.55a(g)(6)(ii)(D)(1) through {6). Source Document: ASME CC N-729-1, "Alternative Examination Requirements for PWR Reactor Vessel Upper Heads With Nozzles Havlng Pressure-Retaining Partial-Penetration Welds, Section XI, Division 1" (Approval Date: March 282006), with the conditions in 10 CFR 50.55a(g){6)(ii)(D). Commitment No.: None Associated Documents: 10 CFR 50.55a{g}(6){ii)(0)(1) through (6). Purpose: Assess the present of PWSCC in reactor vessel upper heads with nozzles install with pressure-retaining partial-penetration welds. Scope: Visual Examination -Outer surface of the Upper Reactor Vessel Head defined by Figure 1 of Code Case N-729-1.Volumetric/Surface Examinations -Partial penetration welds of the Nozzles and the Upper Reactor Vessel Head.
PROGRAM SECTION No. SEP*ISHP2-001 Revision No.4 Page26 of69 Note: Appendix I, Analysis Procedure for Alternative Examination Area or Volume Definition, of ASME CC N-729-1 must not be implemented without prior NRC approval. [10 CFR 50.55a(g)(6)(ii)(D)(6)}. Method: Visual examination areas defined by Figure 1 on CC N-729-1 of the outer surface of the Reactor Vessel Head. Volumetric and/or surface examinations of essenUally 100 percent of the required volume or equivalent surface examination of essentially 100 percent of the subject J-groove welds. A demonstrated volumetric or surface leak path assessment through all J-groove welds must be performed. If a surface examination is being substituted for a volumetric examination on a portion of a penetration nozzle that is below the toe of the J-groove weld, the surface examination must be of the inside and outside wetted surface of the penetration nozzle not examined volumetrically. [10 CFR 50.55a(g)(6)(ii)(D}(3)]. Industry Code or Standards: ASME Section XI, 2007 Edition through 2008 Addenda as supplemented by 10 CFR 50.55a(g)(6)(ii)(D)(4) restricts the use of Section XI, Appendix VIII requirements to ASME Section XI, 2004 Edition with no Addenda for Code Case N-729-1. [10 CFR 50.55a(g)(6)(ii)(D)(4)]. Frequency: The examinations listed in Table 1 of CC N-729-1 shall be performed completely, once, as a baseline examination. These examinations shall include all nozzles. lnservice examination frequencies are based on calculated RIY (Reinspection Years calculation compliant with paragraph -2410 of CC N-729-1) and the result of previous examinations. Per 10 CFR 50.55a(g)(6)(ii)(D}(5), ifflaws attributed to PWSCC have been identified, whether acceptable or not for continued service under Paragraphs -3130 or-3140 of ASME CC N-729-1, the re-inspection interval must be each refueling outage instead of the re-inspection intervals required by Table 1, Note (8), of ASME Code Case N-729-1. Note 9 of the CC shall not be implemented. [1 o CFR 0.55a(g)(6){il)(D)(2)]. Acceptance Criteria or Standard: Acceptance shall be as specified by code case paragraph-3130 and-3140. Additionally, if flaws attributed to PWSCC have been identified, whether acceptable or not for continued seivice under Paragraphs -3130 or-'3140 of ASME Code Case N-729-1, the re-inspection interval must be each refueling outage instead of the re-inspection intervals required by Table 1, Note (8), of ASME Code Case N-729-1. [50.55a(g)(6)(ii)(D)(5)]. Regulatory Basis: 1 O CFR 50.55a{g)(6)(ll)(D) "Augmented ISi requirements: Reactor vessel head inspections". Reporting Requirements: Report of any indication of PWSCC flaws to Entergy Engineering immediately. The results of these examinations shall be included in the outage inservice Inspection summary report. 
-=---Entergy PROGRAM SECTION No. SEP-ISl-IP2*001 Revision No.4 Page27 of69 1.8.S Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS N060B2 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities in accordance with Code Case N-770-1, "Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities", Section XI, Division 1," in accordance with the requirements in 10 CFR 50.55a{g)(6}(ii}(F)( 1) through (10). Note: License Renewal commitment LQ-LAR-2011-0174 CA37 is tracked and monitored in accordance with the Coda Case 770-1 examination requirements, and augmented existing tSl inspections as appropriate. Source Document: ASME Code Case N;,.770-1, "Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of listed Mitigation Activities Section XI, Division 1. 10 CFR 50.55a(g)(6)(ii)(F) "Augmented ISi requirements: Examination Requirements for Class 1 Piping and Nozzle Oissimilar*Metal Butt Welds". Commitment No.: None Associated Documents: 1 O CFR 50.55a(g}(6)(ii)(F}. Purpose: Detection or unacceptable growth of known PWSCC Cracking. Scope: IP2 has four reactor vessel hot leg connections that will be inspected volumetrically every 5 years and visually each refueling outage, and four reactor vessel cold leg connections that will be inspected volumetrically every inspection period not to exceed seven years and visually once per inspection interval. Method: Ultrasonic Examination procedures and personnel qualification in accordance with Appendix VIII of ASME Section XI. Industry Code or Standards: ASME Section XI, 2007 Edition through 2008 Addenda. Frequency: IP2 has four reactor vessel hot leg connections that wilf be inspected volumetrically every 5 years and visually each refueling outage, and four reactor vessel cold leg connections that will be inspected volumetrically every second inspection period not to exceed seven years and visualty once per inspection interval. Acceptance Criteria or Standard: Code Case paragraphs -3130 and -3140. IWB-3514 of the ASME Section XI, 2007 Edition through 2008 Addenda as supplemented by Nonmandatory Appendix Q, if applicable weld overlays are applied. Regulatory Basis: 10 CFR 50.55a{g)(6)(ii)(F) "Augmented ISi requirements: Examination requirements for Class 1 piping and nozzle dissimilar-metal butt welds". 
-----Entergy PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No.4 Page28of69 Reporting Requirements: Report of any indication of PWSCC flaws to Entergy Engineering immediately. The results of these examinations shall be Included in the inservfce inspection summary report. For any mitigated weld whose volumetric examination detects growth of existing flaws in the required examination volume that exceed the previous IWB-3600 flaw evaluations or new flaws, a report summarizing the evaluation, along with inputs, methodologies. assumptions, and causes of the new flaw or flaw growth is to be provided to the NRC prior to the weld being placed in service other than modes 5 or 6. [10 CFR 50.55a(g)(6)(1i)(F)(6)]. 1.9 Administrative Controls 1.9.1 This program ls 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 .iiems 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-2411 and IWF-2410. 1.9.4 Organizational and of responsibilities for the management and implementation of the 1$i 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 0lnformation Only''. PCNs are not required to be provided to the NRC. 1.9.6 The initial lSI Program Plan, revisions, anc;t PCNs are subject to review by the Authorized Nuclear lnservice Inspector (ANll). 1.10 IODEAL Data-Management Program IP2 ISi Components and their examination schedules are developed with the aid of the IODEAL 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 controlllng entity for managing and implementing the ISi program. The lnservice Inspection Data Management software is comprised of a series of program modules assembled in a comprehensive software package entitled the !ddeal Software Suite. This software suite is NETWORK based within the Entergy system and is accessible by any computer within Entergy. The lddeal Software Suite is a quality level 8 software. It is the Controlled copy of the ISi Schedule. The software has limited access to protect the contents of the databases. Access to the software is limited through the use of a user defined password controlled via Central Engineering Procedure CEP-COS-100. The ScheduleWorks 
-----E11tergy PROGRAM SECTION NO. SEP-ISl-IP2-001 Revision No.4 Page29 of69 Module contains the IPEC information necessary to perform ISl/Cll and Augmented Program. Maintenance of the Module is controlled via Central Engineering Procedure CEP-COS-110. All changes to data in the IPEC ISl/Cll Database must be made in accordance with CEP-COS-110. 1.11 Adoption and Use of ASME Section XI Code Cases In accordance with ASME Section XI, IWA-2441(a}, Code Cases to be used during a preservice or inservice inspection shall be identified in the lnservice Inspection Plan. ASME Section XI Code Cases adopted for ISi and NOE activities are listed in Tables 1.11-1 and 1.11-2. In addition, other Code Cases as approved in USNRC Regulatoiy Guide 1.147, latest revision, may be used as required. Code Cases applicable to Nondestructive Examination (NOE), Repair/Replacement (R/R) Activities, Pressure Testing and Flaw Evaluation are addressed in their respective program documents and are not inciuded in this Program. The use of Code Cases Is in accordance with ASME Section XI, IWA-2440, 10 CFR 50.55a, and USNRC Regulatory Guide 1.147. As permitted by ASME Section XI, USNRC Regulatory Guide 1.147, and 10 CFR 50.55a, 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 Gulde 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 Regulatoiy Guide are also incorporated. Table 1.11-1 identifies the Code Cases that have been approved for use in USNRC Regulatory Guide 1.147 and are incorporated into the ISi program. 1.11.2 Adoption of Code Cases Not Approved in USNRC 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 Regulatoiy Guide 1.147. Use of such Code Cases may be requested in the form of a "Request for Alternative" in accordance . with 10 CFR 50.55a(a)(z). Code Cases that have been requested in accordance with 10 CFR 50.55a{a)(z) may not be used until NRC approval has been obtained. Section 1.13 Identifies the Code Cases that have been requested in accordance with 10 CFR 50.55a(a)(z). 1.11.3 Adoption of Code Cases Mandated by 10 CFR 50.55a Code Cases required by rule in 1 O CFR 50.55a are incorporated into the ISi Program and implemented at the specified schedule. Code Cases currently required by 10 CFR 50.55a 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 inspection lntel'Val that are subsequently annulled by ASME may be used for the remainder of the inspection interval. 
-----Entergy PROGRAM SECTION No. SEP-ISl-IP2.001 Revision No-4 Page 30 of69 N-526 N-532-5 N-586*1 N-686-1 N-716-1 N-731 N-735 N-747 N-765 1.11.5 Code Case Revisions ao1:::iot1on of a Code requires use of revision of Code in Regulatory Guide 1.147. However, if an adopted Case is .. "'"""""wi and approved by the NRC, then the earlier or later revision may used. An exception to provision would the inclusion a limitation or condition on the use the Code Case which is necessary to enhance 1.11-1 from Regulatory 1.147 Alternative Requirements for Successive Inspections of Class 1 and 2 Vessels Section XI, Division 1 Repair/Replacement Activity Documentation Requirements and lnservice Inspection Summary Report Preparation and Submission Section XI, Division 1 Alternative Additional Examination Requirements for Classes 1, 2, and 3 Piping, Components, and Supports Section XI, Division 1 Alternative Requirements for Inner Radius Examination of Class 1 Reactor Vessel Nozzles Section XI, DMslon 1 Conditions Use: In lieu of a UT licensees may perform a VT-1 examination in accordance with the code of record for the lnservice Inspection Program utilizing the allowable flaw length criteria ofTable IWB-3512-1 with limiting assumptions on the flaw aspect ratio. 2010 Edition 2011 Addenda 2010 Edttion 2007 Edition 2008 Addenda 2013 Edition Alternative Requirements for Visual Examinations VT-1. VT-2, and VT-3 2004 Edition Section XI. Division 1 Alternative Piping Classification and Examination Requirements Section XI, 2013 Edition Division 1 Alternative Class 1 System Leakage Test Pressure Requirements Section 2013 Edition XI, Division 1 Alternative to Inspection Interval Scheduling Requirements of IWA-2430 Section XI, Division 1 Edition Edition 2008 Addenda 
----Entergy PROGRAM SECTION No. &sect;EP-jSl*IP2-Q01 Revision No.4 Page 31 of 69
* Table 1.11-2. Code Cases Roouired bv 1o:cfR 50.55a* Code Case " Number: Title Notes .. Additional Examinations for PWR Pressure Retaining Welds Conditions specified if! paragraphs N-722-1 in Class 1 Components Fabricated With Alloy 600/821182 (g)(6}(ii}(E)(2) through (4) of 10 CFR Materials, Sedfon XI, Division 1 50. 55a. Implemented in the Pressure Test Program Altemative Examination Requirements for PWR Reactor Conditions specified In paragraphs N-729-1 Vessel Upper Heads With Nozzles Having Pressure-(g}(6){ii)(D)(2) through (6) of 10 CFR Retaining Partial-Penetration Welds, Section XI, Division 1 50.55a Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS N06082 or UNS W86182 Weld Conditions specified in paragraphs N-770-1 Filler Material With or Without Application of listed Mitigation (g}(6)(ii}{F)(2) through (10) of 10 Activities, Section XI, Division 1 CFR 50.55a 1.12 Technical Positions Technical Positions are created for areas where the Code does not provide dear direction or areas where regulation requires more attention to a specific area. Technical Position papers used as bases for the ISi program are listed in Table 1.12*1. Table Technical Position Pa ers Document Number Title Notes None at this time Entergy 1.13 Relief Beguests PROGRAM SECTIONJ No. &sect;EP-iSl-IP2*001 Revision No.4 Page 32 of69 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 10 CFR 50.55a rule, or to use provisions from Editions or Addenda of Section Xf not approved by the NRC as referenced in 10 CFR 50.55a(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 1 O CFR 50.55a. 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 1 O CFR 50.55a(a)(z) and (g)(5). The applicable Entergy submittal and NRC Safety Evaluation Report (SER) correspondence numbers are also included for each request. Note: Requests associated with the ISi program only are listed in Table 1.13-1. Requests applicable to Nondestructive Examination (NDE), Repair/Replacement (RJR) Activities, Pressure Testing and Flaw Evaluation are identified in their respective program documents. 11.13.1 Request for Alternatives When seeking an alternative to the rules contained in 10 CFR 50.55a(b) through (h), the request is submitted under the provision of 10 CFR 50.55a(z). Once approved by the Director, Office of Nuclear Reactor Regulation, the alternative may be incorporated into the ISi program. These types of requests are typically used to request use of Code Cases, Code Edition, or Addenda not yet approved by 1he NRC. Request for Alternatives must be approved by the NRC prior to their Implementation or use. Within the provisions of 10 CFR 50.55a(z) there are two specific methods of submittal: 1.13.1.1 10 CFR 50.55a(a)(.z)(1): Acceptable level of quality and safety. The proposed alternative would provide an acceptable level of quality and safety. 1.13.1.2 10 CFR 50.55a(a)(z)(2): Hardship without a compensating increase < in quality and safety. Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase ln the level of quality and safety. 1.13.2 Relief Request Required Due to Impracticality 1 O CFR 50.55{a)(g)(5)(iii) allows relief to be requested in instances when IP2 has determined conformance with a Code requirement is impractical, e.g. limited examination coverage. Under 10 CFR 50.55(a){g}(5)0v), relief requests for examination impracticalities must be submitted for NRC review and approval not later than 12 months after the expiration of the initial or subsequent 120-month inspection interval for which relief is sought rn cases where the ASME Section XI requirements for inservice inspection are considered impractical, IP2 will notify the NRC and submit information to support the determination, as required by 1 O CFR 50.55a(g}(5). The submittal of this information will be referred to as a Request for Relief. 
----Entergy PROGRAM SECTION No. SEP*lS!-IP2*001 Revision No.4 Page 33 of 69 1.13.3 Requests to use Later Edition and Addenda of ASME Section XI On July 28, 2004, the NRC published Regulator1' Issue Summary (RlS) 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 10 CFR 50.55a(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. 
-----Entergy Table 1.13-1 Fifth Interval Relief Requests Relief Request Relief Request Description Entergy Correspondence IP2*1Sl-RR-01 Pressurizer shell to head, circumferential and longitudinal NL-15-138 welds. ASME Cat B-B, Ref. IWB-2500. IP2-ISl-RR*02 Proposed Alternative Examination Area for Code Case N-72B-NL-15-139 1. IP2*1Sl*RR*03 Proposed Alternative to Use of Weld Reference System NL-15-140 PROGRAM SECTION No. SEP-JSl-IP2-001 Revision No. 4 Page 34 of69 NRC SER Correspondence Modified ( NIA NIA NIA 1.14 Calibration Blocks PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 35 of69 A detailed list of all ISi calibration blocks to be employed during the fifth inspection interval is provided in SEP-ISl-IP2-002. 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 ASME Code Section XI 2007 Edition through 2008 Addenda, IWA-2200(c), 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 shall be submitted per paragraph 1.13.2. ASME Section XI examinations should meet the examination coverage criteria established in ASME Code Section XI, 2007 Edition through 2008 Addenda, IWA-2200(c). Therefore, the guidance Included in ASME Code Section XI 2007 Edition through 2008 Addenda IWA*2200{c) shall be followed by Entergy IP2 when determining whether to prepare a relief request or apply the criteria of ASME Code Section XI, 2007 Edition through 2008 Addenda, IWA-220{c) 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.
SECTION 2.0 PROGRAM SECTION No. SEP-1Sl-IP2-001 Revision No. 4 Page 36 of69 APPLICATION CRITERIA AND CODE COMPLIANCE PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 37 of69 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, 2007 Edition through 2008 Addenda for the IP2, Fifth Ten-Year Interval ISi Program Plan. The application and distribution of examinations for this inspection interval is based upon utilizing Inspection program defined by paragraphs IWB-2411, IWC-2411, IWD-2411, IWE-2411 IWF-2410 and IWL-2400 of Section XI. The results of this application are summarized by ASME Category and Item Number and are contained within the IP2 Code Category Summary Table contained in this document. This table only contains those ASME Item Numbers that are relevant to IP2. 2.1.1 Examination Category B-A -Pressure Retaining Welds in Reactor Vessel Reactor vessel examinations were scheduled to meet the 2007 Edition through 2008 Addenda of the ASME Code, Section XI as required by 10 CFR 50.55a. Article IWB-2420 in the 2007 Edition through 2008 Addenda of ASME Code, Section Xl 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 (3) specifies at least 50% of the Shell to Flange Welds will be examined by the end of the firsl inspection period of the first inspection interval. In successive inspection intervals, Note 5 allows deferral of the Shell to Flanges provided conditions in Note (5) are satisfied. The conditions of Note (5) are satisfied. The selection of these welds for examination meets the requirements of Examination Category B-A Examination Requirements in the 2007 Edition through 2008 Addenda of Section XI. 2.1.2 Examination Category B-B
* Pressure Retaining Welds in Vessels other Than Reactor Vessels The 2007 Edition through 2008 Addenda of Section XI, Examination Category 8-8 requires the pressurizer and primary side of steam generators (S/G) and regenerative heat exchangers 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. Relief Request IP2-ISl-RR-01 was requested for approval which would allow Welds PZRC5 {82.11) & PZRL4 (82.12) to be visually examined cvr-2) after each refueling outage in lieu of the Code required volumetric examination. This will be tracked via Pressure Testing Procedure PT-R75. Therefore, only one of the two Shell to Head Welds and Longitudinal Welds are selected for 50%. STEAM GENERATORS PROGRAM SECTION No. SEP*ISl-IP2-001 Revision No. 4 Page 38 of69 IP2 has four steam generators. Table JWB-2500-1, Category B-8, Note (1) allows the examination to be limited to one vessel among a group of vessels performing a similar function or 25% for IP2. 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. REGENERATIVE HEAT EXCHANGERS Section XI requires volumetric examination of all Regenerative Heat Exchanger Head to Shell and Tubesheet to Shell Welds. ASME Code Case N-706-1 approved through USNRC Regulatory Guide* 1.147, will be implemented, and therefore all B2.60 and 92.80 welds will be visually examined {VT-2) after each refueling outage in lieu of the Code required volumetric examination. This will be tracked via Pressure Testing Procedure PT-R75. Implementation of ASME Code Case N-706-1 requires the Owner to evaluate industry experience to determine which heat exchanger designs or configurations have leaked. If any leakage is detected, it shall be corrected in accordance with IWA-4000. Use of Code Case N-706-1 shall be discontinued for the Regenerative Heat Exchangers and others of the same design . or configuration. The affected Regenerative Heat Exchangers and others of the same design or configuraUon shall be examined in accordance with IWB-2500 or IWC-2500, as applicable. Therefore, the selection of these welds for examination meets the requirements of Examination Category 8-B Examination Requirements in the 2007 Edition through 2008 Addenda of Section XI and ASME Code Case N-706-1. 2.1.3 Examination Category B-0 -Full Penetration Welded Nozzles In Vessels This category applies to the reactor vessel, pressurizer, steam generators and regenerative heat exchangers. 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, Categoiy B-D. Note (3) allows partial deferral if the examinations are conducted from Inside the nozzle bore 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 inspection interval. PRESSURIZER The 2007 Edition through 2008 Addenda no longer has a requirement to examine Pressurizer Nozzle Inside Radius Section. However, 10 CFR 50.55a(b)(2)(xxi)(A) requires utilities to either apply the Volumetric Examination of the 1998 Edition when using the 1999 Addenda through the latest edition and addenda incorporated by reference in paragraph (a}(1)(ii) of this section or allows a visual examination with magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 39 of69 allowable flaw length criteria In Table IWB-3512-1, 1997 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)( 1 )(ii) of this section, with :a limiting assumption on the flaw aspect ratio {i.e., a/1=0.5), may be performed instead of an ultrasonic examination. Pressurizer Nozzle Inside Radius Sections will be examined volumetrically or with an enhanced visual as required by 10 CFR 50.55a{b)(2)(xxi}(A) depending on which method is determined to be prudent to IP2. These*examinations are identified in the ISi Program as Examination Category B-0, Item Number 83.120 in accordance with the 1998 Edition of ASME Section XL IP2 Pressurizer nozzles are integrally cast and therefore, contain no Item Number 83.110, nozzle to vessel welds. STEAM GENERA TOR The 2007 Edition through 2008 Addenda no longer has a requirement to examine Stearn Generator Nozzle Inside Radius Section. However, 1 O CFR 50.55a(b)(2)(xx:i)(A} requires utilities to either apply the Volumetric Examination of 1998 Edition when using the 1999 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1)(ii)of his section or allows .a visual examination with magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the allowable flaw length criteria in Table lWB-3512-1, 1997 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1 )(ii) of this section, with a limiting assumption on the flaw aspect ratio (i.e., a/1=0.5). may be performed instead of an ultrasonic examination. Steam Generator Nozzle Inside Radius Sections will be examined volumetrically or with an enhanced visual as required by 10 CFR 50.55a(b)(2)(xxi)(A) depending on which method is determined to be prudent to IP2. These examinations are identified in the ISi Program as Examination Category B-0, Item Number 83.140 in accordance with the 1998 Edition of ASME Section. IP2 Steam Generator nozzles are integrally cast and therefore, contain no Item Number B3.130, nozzle to vessel welds. REGENERA TlVE HEAT EXCHANGERS Section XI requires volumetric examination of all Regenerative Heat Exchanger Nozzle to Vessel Welds and Nozzle Inside Radius Sections. ASME Code Case N-706-1 approved through USNRC Regulatory Guide 1.147, will be implemented, therefore all 83.150 nozzle to vessel welds and B3.160 nozzle inside radius sections will be visually examined (VT*2) after each refueling outage in lieu of the Code required volumetric examination. This will be tracked via Pressure Testing Procedure PT-R75. Implementation of ASME Code Case N-706-1 requires the Owner to evaluate industry experience to determine which heat exchanger designs or configurations have leaked. If any leakage is detected, it shall be corrected in accordance with IWA-4000. Use of Code Case N-706-1 shall be discontinued for the Regenerative Heat Exchangers and others of the same design or configuration. The affected Regenerative Heat Exchangers and others of the same design or configuration shall be examined in accordance with IWB-2500 or IWC-2500, as applicable.
PROGRAM SECTION No. $EP-ISl-!P2-001 Revision No. 4 Page40 of69 The selection of these welds and inner radius sections for examination meets the requirements of Examination Category 8-D Examination Requirements in the 2007 Edition through 2008 Addenda of Section XI as modified by ASME Code Case N-706-1 and 10 CFR 50.55a(b){2)(xxl)(A). 2.1 Examination Category B-F -Pressure Retaining Dissimilar Metal Welds in Vessel Nozzles This category addresses Nozzle to Safe End Welds. Risk Informed Jnservice Inspection utilizing ASME Code Case N-716-1 (approved through USN RC Regulatory Guide 1.14 7) will be implemented for Examination Category B"F requirements. Examination. of these dissimilar metal welds will not be covered under Examination Category B-F, but under Examinatibn Category A Table 2.1-3, with the exception of eight (8) Reactor Vessel Nozzle to Safe End Butt Welds fabricated with UNS N060802 or UNS W86182 Weld Filler Material. The eight (8) Reactor Vessel Nozzle to Safe End Butt Welds Will be examined utilizing ASME Code Case N-770-1. 2.1.5 Examination Category B-0&deg;1 *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 2007 Edition through 2008 Addenda of Section XI. Examination of the Reactor Vessel Bolting will be performed in the first and third periods. For volumetric of reactor coolant pump studs, one of four sets of reactor coolant pump studs is selected for volumetric examination. For the visual examination of pump bolting, one of the reactor coolant pumps will be examined only if disassembled. This is the same requirement as for Examination Category B-L-2 and will be met during the maintenance or repair/replacement process. During the first, second and third inspection intervals pump bolting examinations were scheduled by bolt. For the fourth and fifth inspection intervals 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 2007 Edition through 2008 Addenda of Section XI. 2.1.6 Examination Category B-Gm2 "Pressure Retaining Bolting, 2" and Less in Diameter This category includes oonoseal bolting, manway bolting, valve bolting, flange bolting in piping, and reactor coolant pump seal bolting. Examinations will be conducted as required in Table IWS..2500-1 in the 2007 Edition through 2008 Addenda of Section XI. This bolting will only be examined if associated connections are disassembled or bolting is removed.
* PROGRAM SECTION NO. SEP*ISl-IP2-001 Revision No. 4 Page 41 of69 For components other than piping, bolting examinations will be required only when the component is examined under Examination Category 8-B, B-L-2, or M-2. IP2 has grouped B-G-2 boning in accordance with components examined under Examination Category 8-8, B-L-2, or B-M-2. This grouping is identified in Tables 2.1-1 for piping and Table 4.1-2 for valves. IP2 has 7 sets of conoseal bolting on the Reactor Vessel Closure Head. Examination of bolting is only required if disassembled or bolting is removed. IP2 has four Steam Generators (Vessel Group 1 ), each with a cold leg and a hot leg manway. Examination of bolting is only required if disassembled or bolting is removed. IP2 has sixteen Class 1 piping flanges. These flanges are grouped into five piping flange groups identified in Table 2.1-1. Each group of piping flanges contains bolted connections of similar design, size, function and service. Only one bolted connection from each flange group is required to be examined each Inspection interval, and this examination is only required when a bolted connection is dissembled or bolting is removed. No piping flanges have been selected. For bolting removal involving the repair/replacement process, this requirement will be met during the repair/replacement process.
DWGNo 200684 206685 200713 206714 DWGNo 200687 200689 206691 206693 OWGNo 206687 206689 206691 206693 DWGNo 206731 206732 206733 OWGNo 206711 PROGRAM SECTION No. SEP..JSl-IP2..001 Revision No. 4 Page 42 of69 Table 2.1-1 B-G*2 PIPING FLANGE GROUPINGS Gmuo 1. COMP ID DESCRIPTION 19 F 2 3" Blind Flanqe Boltin!.l {8) 27F 4 3" Blind Flamie Boltint:i {Si 79f 1 3" Blind Flanae Bol!lnc:i !Ell 80F1 3" Blind Flanqe Soltinq (8) Grouo 2 COMP ID DESCRIPTION 41F1 1.5" 21 RCP Flanoe Bo!! {4l 42F1 1.5" 22 RCP FlanQe Bolt (4} 43F 1 1.5" 23 RCP Flanoe Bolt (4} 44F 1 i.5" 24 RCP Flanoe Bolt (4} .. Gm1.11>3 COMP ID DESCRIPTION 41F2 2" Pipe Flanoa Boltint1 (8) 42 F2 2" Pioo Flancie Boliinc.i (8) 43 F2 2" Pioe Flanc:te Boltlna ( 8) 44 F2 2" PiM Flanae Bollino 18) I Group4 .. I COMP ID DESCRIPTION 342 F 1 PZR PCV464 Flanae &lit (8) . 343F1 PZR PCV466 Flanoe Bolt {8} 344F1 PZR PCV4S6 Flanae Bolt {8) Gro1.1p6 COMP ID DESCRIPTION 64F1 2" Blind Flanaa Boltina CS) IP2 has four Reactor Coolant Pumps (Pump Group 1), each pump contains seal housing bolting. Examination of pump bolting is only required if disassembled. Examination of the bolting is only required on one RCP pump seal housing bolted . connection when disassembled or bolting is removed. IP2 has seventeen valves with bolting. The valves have grouped, as required by Examination Category B-M-2, into four Valve Groups identified in Table 2. 1-2. Examination of valve bolting is only required on one valve in each group if or bolting ls removed. third intervals During the first, second and third inspection intervals Steam Generator and Pressurizer manway bolting examinations were also scheduled by bolt For the fourth and fifth inspection intervals these examinations combined to PROGRAM SECTION NO. SEP-JSl-IP2*001 Revision No. 4 Page 43 of69 one summary number for each manway that requires examination of all the bolting of the manway. The selection of these components for examination meets the requirements of Examination Category B-G-2 Examination Requirements in the 2007 Edition through 2008 Addenda of Section XL 2.1.7 Examination Category B-J -Pressure Retaining Welds in Piping Examination Category B-J of the ASME Code Section XI, 2007 Edition through 2008 Addenda requires examination of Class 1 piping welds. Risk Informed lnseivice Inspection utilizing ASME Code Case N-716-1 (approved through USNRC Regulatory Guide 1.147) will be implemented for Examination Category B-J requirements. Examination of these welds will not be covered under Examination Category B-J, but under Examination Category R-A Table 2.1-3. 2.1.8 Examination Category B-K -Welded Attachments For Vessels, Piping, Pumps, And Valves Examination Category B-K of the ASME Code Section XI, 2007 Edition 2006 Addenda requires examination of welded 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. IP2 has one Pressurizer Welded Attachment that is selected for examination. For piping. pumps, and valves, inspection of 10% of the total population of welded attachments is required. Ten Percent (10%) of all piping welded attachments and 10% of all pump welded attachments are selected for examination. IP2 does not have any Class 1 valve welded attachments. The population of welded attachments contained In the ISi program has been evaluated and seven have been identified to be associated with whip restraints. These seven do not meet the criteria of Examination Category 8-K, Note 1 and have been removed from the program. The selection of these welded attachments for examination meets the requirements of Examination Category B-K Examination Requirements in the 2007 Edition through 2008 Addenda of Section XI. 2.1.9 Examination Category B-L-2 -Pump Casings This category involves reactor coolant pumps and requires visual examination of pump casing internal surfaces when disassembled. The reactor coolant pumps are the only Code Class 1 pumps. B-L-2 requires examination of the pump casing Internal surfaces of one pump in each group of pumps pertorming similar functions in the system. However, this examination is only required when a pump is dissembled for maintenance or repair. For pump disassembly involving repair/replacement activities, this requirement will be met during the repair/replacement process.
PROGRAl\fl SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page44 of69 The selection of these components for examination meets the requirements of Examination Category B-L-2 Examination Requirements in the 2007 Edition through 2008 Addenda of Section XI. 2.1.10 Examination Category B0M02 -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. IP2 has grouped these valves based on size, design, manufacturing method, and function into four groups of valves identified in Table 2.1-2. B-M-2 requires examination of the valve body internal surfaces of one valve in each group of valves that are of the same size, constructural design, man&#xb5;facturing method, and that performs similar functions in the system. However, this examination is only required when a valve is dissembled for maintenance or repair. No valve body internal surfaces have been selected. For valve disassembly involving repair/replacement activities, this requirement will be met during the repair/replacement process. Table below lists all valves grouped by system, size, and type and subject to examination under B-M-2. Table21-2 B*M*2 VALVE GROUPINGS -Group.1 Drawing Component Size Type Valve System Number Number 206903 351 695A 206904 352 8958 206905 353 89SC 206901 350 8950 206903 351 897A HI Darling Check SIS 206904 352 8978 206905 350 897C 206901 353 8970 Group2 Drawing Component Size Type Valve system Number Numbef 206906 355 838A 206907 206908 358 838C 6 VelanCheck SIS 206910 367 8380 Group3 Drawing Component Size Type Valve System Number Number 206731 PCV464 206732 PCV466 4X6 Crosby Relief RCS 206733 PCV468 I PROGRAM SECTION No. Table2.1-2 VALVE GROUPINGS Group4 Drawing Component Size Type Valve Number Number 206669 10730 '.14 Copes Vulcan Gate ;mesas 10731 Revision No. 4 Page 45 of 69 System RHR The selection or these components for examination meets the requirements of Examination Category 8-M-2 Examination Requirements in the 2007 Edition through 2008 Addenda of Section XL 2.1.11 Examination Category B-N-1
* Interior of Reactor Vessel These examinations will be conducted each inspection period. This meets the Examination Category S.N-1 Examination Requirements in the 2007 Edition through 2008 Addenda of Section XL 2.1.12 Examination Category B-N-2-Welded Core Support Structures and Attachments to Reactor Vessel These examinations will be scheduled to coincide with the inspection of the reactor vessel. The selection of these welds for examination meets the requirements of Examination Category 8-N-2 Examination Requirements in the 2007 Edition through 2008 Addenda of Section XL 2.1.13 Examination Category BwN--3-Removable Core Support Structures These examinations will be conducted to coincide with the inspection of the reactor vessel. The selection of these welds for examination meets the requirements of Examination Category B-N-3 in the 2007 Edition through 2008 Addenda of Section XI. 2.1.14 Examination Category B-0 *Pressure Retaining Welds in Control Rod Drive and Nozzle Housings The ASME Code, Section XI, 2007 Edition through 2008 Addenda requires volumetric or surface examination of 10% of peripheral Control Rod Drive Housings Welds during the inspection inten1aL There are 28 peripheral Control Rod Drive Mechanisms (CRDMs} on the reactor vessel head. To meet the Code requirements, three CRDMs have been selected. The selection of these components for examination meets the requirements of Examination Category B-0 Examination Requirements in the 2007 Edition through 2008 Addenda of Section XL 2.1.15 Examination Category B-P Pressure Retaining Components PROGRAM SECTION No. SEP-ISl..JP2-llfJ1 Revision No. 4 Page46 of69 The pressure testing program at IP2 meets the requirements of ASME Code, Section XI, 2007 Edition through 2008 Addenda for Class 1 Systems. Details are contained In the pressure test program. 2.1.16 Examination Category B-Q -Steam Generator Tubing The Steam Generator Tube inspection program at IP2 is governed by IP2 Technical Specifications. 2.1.17 Examination Category C-A -Pressure Retaining Welds In Pressure Vessels Risk Informed lnservice Inspection utilizing ASME Code Case N-716-1 (approved through USNRC Regulatory Guide 1.147} will be implemented for Examination Category C-A requirements of the Steam Generators (HSS per N-716-1) and Residual Heat Exchangers. Examination schedule of the Steam Generators {HSS per N-716-1), utilizing ASME Code Case N-716-1, will be under Examination Category C-A and not under Examination Category R-A Table 2.1-3. Examination schedule of the Residual Heat Exchangers, utilizing ASME Code Case N-716-1, will not be under Examination Category C-A, but under Examination. Category R-A Table 2.1-3. 2.1.18 Examination Category C-B
* Pressure Retaining Nozzle Welds In Vessels Risk Informed lnseivice Inspection utilizing ASME Code Case N-716-1 (approved through USNRC Regulatory Guide 1.147) will be implemented for Examination Category C-B requirements of the Steam Generators (HS8 per N-716-1) and Residual Heat Exchangers. Examination schedule of the Steam Generators (HSS per N-716-1), utilizing ASME Code Case N-716-1, will be under Examination Category C-8 and not under Examination Category R-A Table 2. i-3.
* Examination schedule of the Residual Heat Exchangers, utilizing ASME Code Case N-716-1, will not be under Examination Category C-B, but under Examination Category R-A Tabfe 2.1-3. 2.1.19 Examination Category C..C -Welded Attachments for Vessels, Piping, Pumps and Valves Examination Category C..C of the ASME Code Section XI, 2007 Edition through 2008 Addenda requires examination of welded 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. IP2 has two welded attachments on each Residual Heat Exchanger. One of the four Residual Heat Exchanger welded attachments is selected for examination or 25% of all vessel welded attachments, PROGRAM SECTION No. SEP-ISl-IP2-0ll1 Revision No. 4 Page47 of69 For piping, pumps, and valves, inspection of 10% of the total population of welded attachments is required. Ten percent (10%) of all Piping Welded Attachments are selected for examination. IP2 does not have any Class 2 pump or valve welded attachments. The population of welded attachments contained in the ISi program has been evaluated and fifty-one have been identified to be associated with whip restraints or exempt piping. These fifty-one do not meet the criteria of Examination Category C-C, Note 1 or are located on pipe and have been removed from the program. The total population of welded attachments contained in the ISi program is 190 components. however in accordance with Table IWC-2500-1, Note 5, the welded attachments that are required to be examined are the welded attachments associated with the supports selected for examination under class 2 supports; at !P2 28 welded attachments are associated with the class 2 supports. The population of welded attachments contained in the ISi program has been evaluated under Table IWC-2500-1, Note 5 criteria, therefore 3 welded need to be examined. The selection of these welded .attachments for examination meets the requirements of Examination Category C-C Examination Requirements in the 2007 Edition through 2008 Addenda of Section XI. 2.1.20 Examination Category C-F-1 -Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping Risk Informed lnservice Inspection utilizing ASME Code Case N-716-1 (approved through USNRC Regulatory Guide 1.147) will be implemented for Examination Category. C-F-1 requirements. Examination of-fuese welds will not be covered under Examination Category C-F-1, but under Examination Category R-A Table 2.1-3. 2.1.21 Examination Category C-F-2 -Pressure Retaining Welds in Carbon or Low Alloy Steel Piping Risk Informed lnservice Inspection utilizing ASME Code Case N-716-1 {approved through USNRC Regulatory Guide 1.147) will be implemented for Examination Category C-F-2 requirements. Examination of these welds will not be covered under Examination Category G-F-2, but under Examination Category R-A Table 2.1-3. 2.1.22 Examination .Category C-H -All Pressure Retaining CompoS1ents The pressure testing program at IP2 meets the requirements of ASME Code, Section XI, 2007 Edition through 2008 Addenda for Cfass 2 systems. Details are contained in the pressure test program.
PROGRAM SECTION No. SEP-ISl-JP:Z-001 Revision No. 4 Page 48 of69 2.1.23 Examination Category D-A -Welded .Attachments for Vessels, Piping, Pumps, and Valves Examination Category D-A of the ASME Code Section XI, 2007 Edition through 2008 Addenda requires examination of welded attachments. For vessel attachments, Note (3) allows for multiple vessels of similar design, function, and service, the welded attachments of only one of the multiple vessels shall be selected for examination. Note 3 also requires that "'All welded attachments selected for examination shall be those most subject to corrosion. as determined by the Owner, such as the welded attachments of the Service Water or Emergency Service Water systems." For single vessels, only one welded attachment shall be selected for examination. IP2 has two groups of multiple vessels and a single vessel with one welded attachment. One welded attachment is selected on one of the vessels for each group of vessels. In addition, one welded attachment on the single vessel is selected for examination. Three of the 9 vessel welded attachments are selected for examination or 33% of all vessel welded attachments. For piping, pumps and valves, inspection of 10% of the total population of Welded Attachments is required. Ten percent (10&deg;/o) of all Piping and Pump Welded Attachments are selected for examination. IP2 does not have any Class 3 valve welded attachments. The population of welded attachments contained in the JSI program has been evaluated and twenty-eight have been identified to be associated with whip restraints or exempt piping. These twenty-eight do not meet the criteria of Examination Category D-A. Note i or are located on exempt pipe and have been removed from the program. The selection of these welded attachments for examination meets the requirements of Examination Category D-A Examination Requirements in the 2007 Edition through 2008 Addenda of Section XI. 2.1.24 Examination Category D-8 -Ali Pressure Retaining Components The pressure testing program at IP2 meets the requirements of ASME Code, Section XI, 2007 Edition through 2008 .Addenda for Class 3 systems. Details are contained in the pressure test program. 2.1.25 Examination Category E-A -Containment Surfaces Examination Category E-A of the ASME Code Section XI, 2007 Edition through 2008 Addenda requires examination of Class MC "Metallic Containment" pressure-retaining components and their integral attachments, as we.II as, the metallic shell and penetration liners of Class CC "Concrete Containment" pressure-retaining components and their integral attachments. IP2 will examine 100% of the accessible inside surface area (192 examinations) of the containment each period and 100% of the moisture barriers (6 examlnations) each inspection period. Any identified Containment Surfaces Requiring Augmented Examinations will be examined in accordance with the requirements of Examination Category E-C, Item No. E4.11 and E4.12.
PROGRAM SECTION No. Revision No. 4 Page49 of69 This meets the Examination Category E-A Examination Requirements in the 2007 Edition through 2008 Addenda of Section XI. 2.1.26 Examination Category E..C -Containment Surfaces Requiring Augmented Examination Indian Point Unit 2 currently has no Code required Augmented examinations identified. 2.1.27 Examination Category E-G -Pressure Retaining Bolting Examination Category E-G of the ASME Code Section XI, 2007 Edition through Addenda requires examination of Class MC pressure retaining bolting. IP2 has 18 bolted connections scheduled for examination during the interval (6 bolled connections each period). This meets the Examination Category E-G Examination Requirements in the 2007 Edition through 2008 Addenda of Section XI. 2.1.28 Examination Category F-A -Supports Examination Category of the ASME Code Section XI, 2007 Edition through the 2008 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. 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 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. It was discovered that whip restraints, and supports on exempt piping had been included in the original fourth interval program. Whip restraints do not provide component support. Therefore the whip restraints and exempt supports have been removed. 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 scheduled for inspection. IP2 scheduled the following supports: "' one Pressurizer Support; .. one of four Reactor Coolant Pump Supports; .. two of six Regenerative Heat Exchanger Supports;
* one of four Steam Generator Supports;
* one of two Containment Spray Pumps Supports;
* one of two RHR Pump Supports;
* two of four RHR Heat Exchanger Supports; 2.1.29 2.1.30 PROGRAM SECTION No. SEP-ISMP2-0Q1 Revision No. 4 Page 50 of69 " one of three Safety Injection Pump Supports; 0 one of two Auxiliary Feedwater Pump Supports (Electric); a. one Auxiliary Feedwater Pump Support (Turbine}; 0 one of two Component Cooling Water Heat Exchanger Supports: e one of three Component Cooling Water Pump Supports; " one Non Regenerative Heat Exchanger Support; &deg;' one of six Service Water Pump Plate Supports; e one of six Service Water Pump Motor Supports; o one of six Service Water Pump Strainer Supports; Eighteen of the fifty-three non-piping supports are selected for examination or 33% 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, 2007 Edition through 2008 Addenda. Examination Category L-A -Concrete Examination Category l-A of the ASME Code Section XI, 2007 Edition through 2008 Addenda requires examination of the reinforced concrete portions of Class CC "Concrete Containment" components. This inspection divides the containment into three areas. Inspections are conducted on the dome and the upper and lower sections of the cylinder.
* IP2 last examined these areas in 2015 and will examine all accessible surface area every 5 years with exams scheduled in lhe second and third periods. Any identifietl "Suspect areas" will be examined in accordance with the requirements of Item L1.12. The selection of these components for examination !Tleets the requirements Examination Category L-A Examination Requirements in .the ASME Code Section XI, 2007 Edition through 2008 Addenda of Section XI. Examination Category R*A *Risk Informed Piping The RI-ISi Program was approved for use during the Third 10-Year Interval via NRC Safety Evaluation Report (TAC No. MC0303). The RI-ISi Program was employed at IP2 during the 4th Ten;. Year ISi Interval via Relief Request RR-05. This program was comprised of Class 1 (ASME Categories B-F and B-J) piping segmentslelements with the exception of 8 (eight) reactor vessel nozzle-to-safe end welds required to be examined per ASME Code Case N-722-1 and N-770-1. The criteria for selection, examination method, examination coverage, and extent were based on EPRI report TR-112657. The Risk Informed Program for lhe Fifth 10-Year Interval is based on ASME Code Case N-716-1 {approved for use per USNRC Regulatory Guide 1.147) Alternate Classification and Examination Requirements, Section XI, Division 1. This program will be utilized in lieu of the requirements of IWB-2420, IWB-2430, Table IWB-2500-1, Examination Categories B-F and IWC-2420, IWC-2430, and PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 51 of69 Table IWC-2500-1 (excluding Examination Categories C-C and C-H), for inservice inspection of Class 1 piping welds or Class 2 components, IWB-2200 and IWC-2200 for preservice inspection of Class 1 piping welds or Class 2 components, or as additional requirements for Class 3 or Non-Class components. Periodic updates of the program are required on an ASME period basis. The update evaluates new information such as design changes, examination history, industry and plant events, PRA changes and operational changes for program impact. Changes to program selections must be evaluated against the N-716-1 selection criteria and potential impact on the program change-in-risk calculation.
SECTION 3 .. 0 ATTACHMENTS PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 52 of69 
---Entergy Attachment 3.1 Table 2.1-3 IP2 Code CaletiOl'V Summarv Required to Numberot be Examined category llem Number Descrlpllon Exam Method Compommlll In During Item No. Interval B*A Prossure Retaining Welds In Reactor Vessel B-A B l.11 Reactor Vessel Circumferential Volumetric 3 3 Shell Welds B-A D1.12 Reactor Vessel Longiludinal Shell Volumetric a 8 Welds B-A Bl.21 Reactor Vessel Circumferenlial Volumetric 2 2 Head Welds B-A 81.22 Ke actor Vessel Meridional Head Volumetric 12 12 Welds 8-A 81.30 Reactor Vessel Shell to Flange Volumetric 1 1 Weld B*A 81.40 Reactor Vessel Head to Flange Volumetric and 1 1 Weld Surface Category Total 27 27 Examination Number to be Percentage Examined In Required Interval 100% All Welds 100% All Welds 100% Length or AU Welds 100% Accessible Length cl All Welds 100% Weld 100% Weld PROGRAM SECTION No. SEP*ISl-IP2..001 Revision No. 4 Page 53 of69 Number to Number to Number to be be be Examined Examined Examined in Third In First In Second Period Period Period 0 Q 31*1 0 0 alll 0 1 1<*1 0 6 6(0 0 0 1<*1 0 1 0 0 9 191'1 Noles for Cst. B*A Note 1: Examinations required ror perloonanca unless PfOposed Request Im Relief tor a1denslon from 10 years lo 20 year.; is approved by Nuclear Regulalory Commission. B-B Prossuro Rotalnlog Wolds In Vessels Other Than Reactor \Iossa ls B*B 82.11 Pressurizer SheU*to*Head Welds Volumetric 2 1 50%111 1 weld 0 0 1 Circumleren!lal B-B B2.12 Pressurizer SheU-to-Head Welds Volumetric 2 1 503121 l ft. (300 mm) of 1 0 0 Lonqitudinal one weld oer tiead B-B 82.40 Sleam Generators (Primary Slcle) Volumetric 4 1 25%111 1 Weld 0 1 0 Tubesheet to Head Weld Heal Excnangen; (Primary Side)
* 0%{3} B*B 82.60 Shell TubeslleeMo-Head Volumelric 6 0 0 0 0 0 Welds!3x*i Heat Exchangers (Primary Side)
* O"A>m B*B 82.BO Shall TubesheeMo-Snell Volumetric 6 0 0 0 0 0 Welds'3"'1 Category Total 20 3 1 1 1 
-----Entergy PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 54 of 69 Attachment 3.1 Table 2.1*3 IP2 Code Category Summary Required to Number to Numborto Number of be examined Examination Number to ba be be be Examined Category ltom Number Oeacrlptlon ExamMothod Components In During Percentage Examined In Examined Examined In Third Item No. Required lnterv;;il In First ln Second Interval Period Period Period Note 1: The examination may be limited 10 one vessel among the group of vessels performing a simijar function (Rer. Table IWB-2500-1, Examinallo11 category 8-B. Nole 1 ). Note 2: Relief Request IP2-ISl-RR*01 was requesled for approval which permits Welds PZRC5 (62.11) & PZRL4 (82.12) lo be visually examined (\ff-2) after each refueling outage in lieu of the Code required volumetric examinaticm. This will be !racked via Pressure Testing Procedure PT-R75. Nole 3: lmplementalion of ASME Code Caso N*706* 1, permits an 62.60 and 02.80 welds 10 be visually examined (\ff*2) after each refueling outage In lieu ol lhe Code required Noles for Cat. B*B volumelric examination. This will be Ira eked via Pressure Testing Procedure PT*R75. No:e4: lmp!emenlalion of ASME Code Case N-706-1 requires U1e Owner to evaluate industry experience 10 determine which heat exchanger designs or configurations have leaked. rr any leakage is detected, it shall be com1Cled in accordance with IWA-4000. Use of this Case shall be discontinued Car lllat heal exchanger (Regenera!ive Heat Exchangers) and others of the same design or configuratltm. The .affected heat exchanger (Regenerative Heat Exchangers) and others of the same design or conllouralioo shall be examined in accordance with IWB-2500 or JWC-2500 as applicable. S-0 Full Ponolratlon Wo!dod Noz:zlos lo Vessels B*D!11 83.90 Reactor Vessel Nozzle-to-Vessel Volumetric 8 8 100% All Nozzles 0 0 5fll Wefds a-0<11 B3.100t*l Reactor Vessel Nonie Inside Volometricl51 8 8 100% All Nozzles 0 0 a<*> Radius Section B*D BJ.12of:i Pressurizer Nonie Inside Radius Valumelric or 6 6 100% All nozzles 3 0 3 Sec lion Visual B*D Sleam Generators (Primary Side) Volumetric or 8 8 100% All noules 0 4 4 Nozzle inside Radius Section Vlsual B-D 83.150 Heal Exchangers (Prima;];' Side} Nozzle-lo-Vessel Welds<3 ''1 Volumetric 12 0 0%(3) All Nozzles 0 0 0 B-0 63.160 Heat Exchangers (Primal)' Side(. Nozzle Inside Radius Seclion'31 Volumelric 12 0 0%''' All Nozzles 0 0 0 Category Total 54 30 3 4 23 Note 1: Examinations required for performance unless proposed Request for Relier for extension from 10 years lo 20 years is approved by Nuclear Regulatory Commission. No!e2: These llem Numbers are from the 1998 Edilion of Sedion XI as required by 10 CFR 50.55a(b)(xxi)(A). If visual examinelion is performed, Iha examination shall be in accordance with 10 CFR 50.55a(b){xxi)(A) as defined in Section 1.4.2 of this program plan. Note 3: lmplemenlalion of ASME Code Case N-706-1. pennils all 83.150 and BJ.160 welds lo be vlsua!lyelffirnined (\ff*2} alter each refueling outage in lieu or lhe Code required volumetric examinalion. This will be tracked via Pressure Tesling Procedure PT*R75. Note4: Implementation of ASME Code Case N-706-1 requires Ille Owner to evaluate industry experience to determine which heal exchanger designs or conliguratlons have leaked. If any leakage is detected, ii shaU be c:orreded in acoordanoo with IWA-4000. Use ol lhis Case shall be dlsconlinued for that heat exchanger (Regenerallve Heal Notes for Cat. B*D Exchangers) and others of lhe same design or configuration. The affected heal exchanger (Regenerative Heal Exchangern) and others of the same design er configuration shall be examined in accordance wilh MfB-2500 or IWC-2500 as applicable. Noto 5: IP2 has adopted ASME Code Case N-648*1, which permils visual examination in place or a UT examlnation. 
---Ent erg;; Attachment 3.1 Table 2.1*3 IP2 Code CateQOl"J Summary Required to Number of be Examined Category Item Numbar Description Exam Method Compommls In During item No. lnteroal B-F Pressurn Retaining Dlsslmllar Metal Welds In Vassel Nozzlos 111 Reactor Vessel NPS (ON 100) or Volumelric and B*F 85.10 larger Nozzle-To-Safe End Bult Visual 4 0 Welds Ho! lea Reader Vessel NPS (ON 100) or Volumelric and B*F 85.10 Larger End Bull Visual 4 0 Welds Colt! Leq Catogory Tomi 8 0 Examination Number to be Percentage Examined In Required Interval Same as for 1" 100% interval Same as for 1" 100% inleival PROGRAM SECTION No. SEP-ISl*IP2-001 Revision No. 4 Page 55 of 69 Number to Numbarto Number to be be be Examined Examined Examined In Third in First In Second Period Period Period 0 0 a 0 0 0 0 0 0 Notes for Cal. B-F Nole 1: These examinations are exempt from Code Case N-716*1 and ore in aceordance with Code Case N-722-1 and Code Case N-770-1 as required by 10 CFR 50.55alnll6ltillCElt2l lhrouah 14\ and 10 CFR 50.55alaU6Wil<F1<21throuoh11m. Tables am provided below ror 111eso Code Cases. B-0*1 Pressure Retainlno Boltlno, Gr&alor Than 2 In. 50 mml In Dfamatllr B-G-1 66.10 Reactor Vessel Closure Head Visual, VT-1 54 54 100% Same as for 1st 18 0 36 Nuis Interval 8-G-1 86.20 Reactor Vessel Closure Studs Volumetric 54 54 100% Same as for 1st 13 0 36 in1erval B-G-1 86.40 Reactor Vessel Threads in Volumetric 54 54 100% Samo as for 1st 0 0 54 F!anae inte!Val B*G-1 86.50 Reactor Vessel Closure Washers. Visual, VT-1 54 54 100% Samo as for 1sl 1ll 0 36 Bushinos Interval B-G-1 86.180 Pumps Bolls and Studs Volumetric 4 1 25%m Same as for 1sl 0 0 1 interval B-&1 86.190 Pumps Flange Surface. when Visual. VT-1 4 ot*x,, 0%1!){J) Same as for 1st 0 0 0 connection disassembled interval B*G-1 86.200 Pumps Nuls. Bushings. and Visual, VT-1 4 0(1)(3/ 0%(!)(lJ Same as for 1st 0 D 0 Washers inlerval Category Tola! 228 217 54 0 163 Nole 1: Nol Required unless disassembled. Nole2: Volumetric examination or bolting for heat exchangers, pumps, or valves may be conducted on one heat exchanger, one pump, or one valve among a group of heat Notes for Cal. B-G-1 exchangers, pumps, or valves that are similar in design, lype, and function. (Ref. Table IWB-2500-1, Examinallon Ca!egory B-G* 1. Note 3). Note3: For heal exchaogelS. piping, pumps. and valves, examinations are limited lo oomponenls selected for examinalion under Examination Category B-B. B-L-2 or B-M-2. /Ref. Tab!e lWB-2500*1, Examination Cateqorv B-G-1, Note 4). B*G*2 Prassuro Retaining Bolling, 21n. (50 mm} and Loss In Dlamotor 8-G-2 87.10 Reacior Vessel Bolls, Studs. ond Visual, VT-1 1 0 0% Same as for 1st 0 0 0 Nuls iCRD Houslnol interva1!IJ(h(JJ B-G*2 97.20 Pressurizer Botts, Studs, and V1Sual, VT-1 1 0 0% Same as for 1 sl 0 0 0 Nuts interva111x1HJ1 
---Entergy Attachment 3.1 Table:U-3 IP2 Code Cate!'.lorv Summarv Required to Numoorof Examination Category ltemNumbm' t:mscrip&.in Elliam Method Com!X!flents In be Examined Percentage Dming Item No. lnteMlll Required B*G*2 87.3!l Steam Generator Botts. Studs, Visual. VT-1 & (} O",f, and Nuts EH3*2 137.50 Piping Bolts. Studs. and Nuls \/lsual. VT-1 16 0 0% B*G-2 87.60 Pumps Batts. Studs. and Nuts Visual. VT-1 4 0 0% B*G-2 87.70 Va!11es Balls, Studs, and N!Jls Visual, VT-1 17 0 0% GatGgoiy Total 53 Cl Nole 1: Bolling is required to ha eiu1mined only when a connection Is disass1:lmbllld or bolling is re1m:ived. Number to be Examined In Interval Sama as for 1s! Pl Same !IS fm 1st Same as for 1s1 lnleiva! rnm;;1J;si Same as for 1st inleiva! rnm1>He1 PROGRAM SECTION No. SJ;P-ISl-tP2-001 Revision No. 4 Page 56 of69 Number to Nmnberto Number to be Ell:amim1d Examined be Examined In Third In First In Second Period Pisrioo Period 0 0 0 0 0 0 0 0 0 0 0 0 (l 0 0 Nole 2: For vessels. pumps,. aml valves. examina!ions aJe to compnrn:m!s selected for examinallon under Examination C'.alegories B*B. B*L*2, and B*M*2 (Ref. Table IWB-2500-1, Examina!lcn Calegory B*G-2. No.le 2). Nola 3; E.:caminallon is only required once per interval. Note4: E.:caminali<>n is !imlled to at least one piping fiange In each group of piping flanges Iha! are of !he similar design, slze. runcUon. and service in Iha syslem. lP2 piping Notes lo.r Cat. B*G*2 flanges are grouped Into five groups in Table 2.1-1. Nole 5: Only one pump ot each group of pumps is required as outlined in B-L-2. Nole6: Only one valve of ea1:;h group orvaives is requited as outlined In B*M*2. B-K Woldod Att.llehmi;nts for Vessels, Plplng, Pumps, and Vah1es B*K 610.IO essels Welded Surface l 1 100% Same as for 1ii>I 0 0 1 inteNal B*K 810.20 Piping Welded Allaciimemls Surfac:& 22 3 10% Sarne el! for 1st 1 2 0 interval El-I< 1310.30 Pumps Welded A!laclimenls Suiface 12 2 10% Same as for 1st 0 0 2 inleNal Calegory Total 6 1 2 3 B*l-2 Pump Casings 8*L*2 812.20 PumpCesiog Visual. VT*:! 4 0 ()",!, Same as for firsl 0 l.J 0 inlerval01m Category Total 4 0 0 0 0 Category llom Number Notes far Cat. B-L-2 B*M*2 Valve Bodles B*M*2 812.SO Notes ror Cat. 8*M*2 Noto 1: Note 2: Attachment 3.1 Table 2.1-3 IP2 Code Cateaorv Summarv Required to Number of Examination Number to be Description Exam Method Comporuints in *
* be Examined Percentage Examined In ltamNo. During Required Interval lnterv1d Examination ls limlled lo at least one pump in each group or pumps performing similar runc!ions ln Ina system. PROGRAM SECTION No. SEP*ISl-IP2*001 Revision No. 4 Page 57 of69 Number to Number to Number to be be Examined examined be Examined in First in Second In Third Period Period Period Examlnalion is required only when a pump or valve is disassembled for maintenance, or repair. Examination of the internal pressure boundary shall Include the internal pressure retaining surfaces made accessible rorexamlnalion by disassembly. If a partial examination is performed and a subsequent disassembly or U1a1 pump or valve allows a more extensive examinalion, an examination shaU be performed during lhe subsequent disassembly. A camplele examination is required only once durino the inleival. Valve Body, Exceeding NPS 4 Same as for first Visual. VT-3 17 0 0% inle1Val 0 0 Q (DN 100) fl)r;!J Category Total 17 0 0 0 0 Note 1: Examination is limiled to at least one valve within each group of valves that are of !he same size, constructural design (such as globe, gale. or check valves), manufaciuring method. and Iha! perform similar functions in lhe system. IP2 valves are grouped iota four groups in Table 2.1-2. Note2: Examination ls required only when a pomp or valve is disassembled for maln!enance, or repair. Examination of Ille internal pressure boundary shall indude the inlemal pressure retaining surfaces made aCCl.!s.sibfe for examination by disassembly. Ir a partial examination is performed and a subsequent disassembly of that pump or valve allows a lll()re el<tensive examination. an examination shall be perfonned during !he subsequent diSassembly. A complete examinallon is required only once durina the Interval. B-N-"I Roaclor Vessol lntorlor B-N-1 813.10 Reactor Vessel, Vessel Interior Visual. vr -3 1 3tt) 100% Each inspection 1 1 1 llB*N*1\ oeri<>d Category Total 1 3lll 1 1 1 Notes for Cat. B-N-1 Note 1: Examination or this Item number is required each period. Therefore the number required during lhe interval is three times the total number or components. This is reOec:ted in lhe category tolal. B*N*2 Welded Coro Support Structures and Interior Attachments to Reactor Vessels Reactor Vessel (PWR) Interior Same as for 1st B-N*2 813.60 Attachments Beyond Bellline Visual. VT-3 1 1 100% 0 0 1{1) Reoion IB-N-21 interval Catagoiy Tot.al 1 1 0 0 1lll Noles for Cat. B*N-2 Note t: Examinations required for performance unless proposed Request ror Reller for extension from 10 years to 20 yearn is approved by Nudear Regulatory Commission. B*N-l Romovablo Coro Support Structuros B*N*3 B13.70 Reactor Vessel (PWR) Core Visuat, Vf-3 2 2. 100% Same as for 1st 0 0 Tl) Support Structure (B-N-3\ inlorvat Entergy Attachment 3.1 Table 2.1-3 IP2 Code Category Summarv Required to Number of ooexamined CategOl'l( Item Ntlmber De.icrlptlon Exam Method Components ln During Percentage ll<1mNr>. Required rnterval Category Total 2 2 Numoorto be Exiamlned in Interval PROGMM SECTION No. SEP*ISl*IP2*00j Revision No. 4 Page 58 of69 Number to Number to Number to be be he Examined Examined Examined In Third in First In Second Period Period Period a () 21*1 Noles for Cat. 8*N*3 Note 1: Examinations required for performance unless proposed Request for Relief fOI' exlension from 10 years to 20 years is appro111!d by Nudear Regufatoiy Commission. 13*0 Pmlil.ium Rotalning Welds in Control Rod Drive and lmr1trumont Nonie Housings Reac1or Vessel (PWR) Welds lrl Volumelric or 10% peripheral 6-0 814.20 21l 3 10% CRD housings () 0 3 Con!rol Rod Drive (CRD) Housing Surface Ol Categoiy Total 28 3 I) 0 3 Noles for Cat. B-0 Note 1: There are 28 Peripheral Ccm!ml Roo Olive (CROJ Housings C-A f'f(IHUnl Retaining Welds in Pl'0ssura Vessels (Steam Ge11&#xa3;irators HSS per N*111M) C*A cuo Pressure Vessels Shell Vo!ume!rlc 14 4 28.5% Eacn 1nsnooion 1 1 2 Circumrerential Welr;ls lnleNalllt2I C-A Cl.20 Pressure Vessels Head Volumelflc 6 2 33.3% Each insneaion 1 0 1 Circumferential Welds interva1&deg; (31 C-A C1.30 Pressure Vessels TubesheeMo* Volumetric 4 1 25% Each {) 1 0 snenWeld ln!erval11 141 Category Total 24 7 2 2 3 Nole 1: The e>1aminalion may be limited lo one vessel among tile group of vessels of similar design. size, and sel\lioo (Ref. Table IWC-2500-1. r.xamimilioo Calegmy C*A. Nole 3). ' Nola2: There are three vessel Sile!! welds on lour SIG lherafore based on Nole 1, 3 of 12 SfG vessel shell circumferenliaf welds are required to be examined. and there is one Notes for Cat. C-A vessel sMU weld on each RHR HX or 1 of 2 lor a lolal of 4 of 14 Ot %. Nole3: There Is one circumfemnliai head weld on four S!Gs thereroro based i:m Nole 1, 1 ol 100 4 SIG vessel head circ11mferanlial welds are required lo be examined, and thera is one circumferential head weld on each RHR HX er 1 of 2 required for e total of 2 of 6 or 33.3%. No!e4: There is one tubesheet-t!Nlheli Mild on four SJGs, ltmmfore based on Nole 1. 1 of lhe 4 lubesheeMo-shell welds am reauirad lo be examined for 25%. C*B Pressure Retaining Nozzle Welds In VesG111ls (Steam GaruarntO!l'I HSS par M*nti-1) 
-----Entergy Attachment 3.1 Table 2.1-3 IP2 Code Catei:iorv Summarv Required to NumbGrof Catsgory ltmnNumoor Description E.nam illleth!'Jd Compom:mts In be Examined Item No. During Interval Nozzles Wilhoul Reinforcing Plate in Vessels > 112 in. (13mmj Surface and 0-B 02.21 Nominal Tllicimess Noule-lo-Volumelrtc B 2 Shen (Nozzle to Head or Noulo to Nozzlel Weld Nozzles Without Reinforcing C-B C222 Pl<!le in Vessels ,. 1/2 in. (13mm) Volumetric 4 1 Nominal Thiclmess Nozzle Inside Radius 51.1ction Nozzles Wilh Reillrorcing Plate in Vessels > 1f2 in. (13mm) C*B C2.31 Nominal Thickness Reinforcing Surlaca 8 4 Plate Welds 10 Nozzle and Vessel Nozzle-to-Shell (Nozzle lo Head C-B C2.33 or Nozzle lo Noure)We!ds When VT*2 4 2 Inside of Vessel Is lnacces!Sible Category Total 24 9 Examfnatlcm Number to be Percenbge Examined In Required Interval 25%'21 Each in!er.ta!11 25%'31 Each inspection Each irneival1' 50%'51 Each inspection period10 PROGRAM SECTION No. SEP-ISl-IP2-Q01 Revision No. 4 Page 59 of 69 Number to Number to Number to be be !lLamlMd Examined be Examined in first Jn Second in Third Period Period Period 0 0 2 0 0 1 2 2 0 (6) (61 IS) 2 2 3 Note1: The examination may be limited to one vessel among the grollfl of vessels ol slmilar design, size, and selllioa (Rel Table IWC-2500*1, Exam!natioo Category C-B. Nole 4). Note2: There are two nozzles on 4 S/Gs; therefore based on Nole 1. 2 of the 8 nozzles are required lo be examined or 25%. Noles for Cal. C-B Note3: There is nozzle inside radius sect!on on 4 S!Gs; therefore based.on Note 1, 1 of lhe 4.noule inside radius section is required to be examined or 25%. Nole4: There am 2 nozzles with 2 reinforcing plates on each of lhe lwo RHR HX, or 4 or a or 50% required. Note5: Tl'lero aro 2 inaccessible nou.le-to-shell welds on each of tile two RHR HX or 2 of 4 or 50% required. Note6: The VT-2 examination is mnu!red each nerloo as roou!ted 1>11 Catenorv C*H. C-C Welded Attachm!:lnts for vessels, Piping, Pumps, 111nd Val111>s Each idenlilied c.c C3.10 Pressure Vessels \Nelded Surfacr; 4 1 25%1tl:2Hl) oe<:urrence and 0 0 1 Atlachments each irn;pecilon In larval Each identified C*C C3.20 Piping Welded Altactimonls Surface 1901'1 3 1.5%,0ll*! occurrem:e and 1 1 1 each inspection interval Category Total 32 4 1 1 2 
--.....r-.. ---Entergy PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 60 of 69 Attachment 3.1 Table 2.1-3 IP2 Code Cateqorv Summaiv Required to Number to Number to Number to Number of be Examined Examination Number to be be be ba Examined Category ltom Numhar Oascrlpllon Exam Motltod Components In During Percentage Examined In Examined Examined In Third ltsmNo. Required Interval In First In Second Interval Period Period Period Nole 1: For multiple vessels of similar design, function. and service, only one welded a!lachment or only one of the multiple vessels shall be selected for examination_ For single vessels. only one welded allachmenl sha11 be selecied for examination (Ref. Table IWC*2500*1, Examination Calegory C-C, Note 4). Nole2: There are lwo welded attachments on each Residual Heat Exchanger; therefore 1 of lhe 4 welded aUachments is required to be examined for 25%. Noles for Cat. C*C Nole3: Examination is required whenever component support member deformation is identified (Ref. Table IWC-2500-1, Examination Calegory C*C, Nole 6). Nole4: IP2 has a total of 85 class 2 supports scheduled for examination In the fifth interval. 28 are welded attachments supports therefore in accordance wilh Table lWC-2500-1 Nole (5). 10% of the Category F*A supports with welded altachments are required lo be examined. The lolal populallon for Code Category C-C. C3.20 is 190 as such 1.Mt mnuires examination. D*A Wolded Attachments for Vessols, Piping, Pumps, and Valves Each identified D-A Dl.10 Pressure Vessels Welded Visual. VT-1 9 3 33% oi:currnnce and 0 0 3 Allachments each inspecllon lnlerval111!2l13l Each identilied D-A 01.20 Piping Welded A!laehments Visual. VT-1 156 21ttl 13% occurrence and at*> 5t*l 8c11 each Inspection lnteiva1<t><3> Each Identified D*A 01.3(} Pumps Welded Allathments Visual. VT-1 g 1 10% occurrence and 0 0 1 each inspeclion interva1C3lHl Calogory Toi.al 174 25 8 5 1.2 Nole 1: For mullipl-0 vessels of similar design, function, and service, the welded aUocnmenls of only one of Iha multiple vessels shall be selected for examination. For single vessels. only one welded allachmen! shall be selected for examination. All welded auachmenls selecled for examinallons shall be lhose most subject lo corrosion. as determined by the Owner, such as welded allachmanls of the Service Weter or Emergency Service water Systems. For welded attachments of piping. pumps, and valves, a 10% sample shall be selected for examination. This percentage sample shall be proportional lo the Iola! number or nonexempt welded auachments cannecled to the piping, pumps, and valves in each system subject lo lhese examinations. Therefore additional piping welded allachments are schedt.t!ed. (Rel. Table IWD-2500* 1, Examination Category D*A, Nol-e 3). Note2: There are two groups of mufliple vessels (one with lwo vessels and one wilh sfx vessels) and one single vessel; therefore, 3 of the 9 are required to be examined for 33%. Noles ror Cat. 0-A Nole3: Examination is required whenever component support member deformation is idenlllled (Ref. Table IWD-2500*1, Examination Calegof)' D*A, Note 4). NGle4: Thero are !Wo sels or pumps (6 SeNice Water Pumps and 3 Component Cooling Waler Pumps}. For welded auachments or piping. pumps, and valves, a 10% sample shall be selected for ei<aminallon. This percentage sample shall be proportional lo the total number of nonexempt welded attachments connected !o the piping. pumps. and values in each syslem r.ubjecl to these examimllions. Thus 1 Service Water Pump ls required lo be examined for 10%. 
---------Entergy Attachment 3.1 Table 2.1-3 IP2 Code Catenorv Summarv Required to Number of be Examined Category ltom Number Doscrlpllon Exam Method Components In During UomNo. lntel'Val e*A Contalnmon! Surfaces E-A E1.11 Conlainment Vessel Accessible General Visual 192 5761'1 Surface Areas E-A E1.12 Containment Vessel Welled VT-3 0 0% Surfaces of Submerged Areas E*A E1.30 Conlainment Vessel Moisture General Visual 6 16''1 Barriers Category Total 198 5941'1 Examination Number to be Exam Jned In Required lnlerval 100% 100% During each Inspection Period 0% 100% 100% 100% During each lnspeclion Period PROGRAM SECTION No. SEP*ISl*IP2-001 Revision No. 4 Page 61 of69 Number to Number to Number to be be be Examined Examined Examinod In TI1lrtl in Flrst In Second Period Period Period 192 192 192 0 0 0 6 6 6 198 198 198 Noles for Cat. E*A Note I: Examination of this ilem number is required eaell period. Therefore. the number required during the interval is three limes the lotal number or components. This is renected in the cate11orv total. E*C Containment Surfaces Requiring Augmented Examlna!Ion Containment Surface Areas 100% of surface E-C E4.11 Visible Surfaces vr.1 0 0% 0% areas identified by 0 0 0 IWE-1242('> 100% of minimum wan thickness localions during Containment Surface A<eas Ultrasonic eachinspeclion E*C E4.12 Surface Area Grid Minimum Wall -Thiclmess 0 0% 0% period. established 0 0 0 Thickness Localion in accordance wilh IWE-2500(b)(3}m andlWE-\ 2500(b}(4\m Category Total 0 0 0 0 0 
--------Cata gory E-G E*G F*A F-A F*A F-A l"*A F-A Entergy PROGRAM SECTION No. SEP-ISl*IP2-001 Revision No. 4 Page 62 of 69 Attachment 3.1 Table 2.1-3 IP2 Code Cateflorv Summaf1/ Required to Number to Number to Number to Numbarof Examination Number to be be be Item Number Oescrlpllon Exam Method Components In be Examined Percentage Examined In examined E1Camlned be Examined ltamNo. Ou ring Required fn(erval In First In Second in Tbird Interval Period Period Period Note 1: Containment surface areas requiring augmented examination are those iclen!ilied in IWE-1240. Notes for E*C N11te2: Tue extent of examination shall be 100% for each inspection period until the areas examined remain essenllalll' unchanged for the next inspecilon period. Such areas no lonaer reouire aucimenled e>Camination in acrordance wllh IWE-2420(c). Prossuro Retaining 8olllng 100% of"1ach E8.10 Bolled Conriections(IJ VT-1 18 16 100% bolted connection 6 6 6 (2) Category Total 16 6 6 6 .. Note1: Examinalion shall include bolls, s1uds. nuts, bushings, washers. and lhreads In base material and flange ligaments belWeen fastener holes. Noles for E*G Note2: Examination may be perlonned wi!h !he conneciion assembled and bolling In place under tension, provided the conneciion Is nol disassembled during the interval. II lhe bolled conneciion is disassembled for anv reason du1inq lhe interval, ihe examination shall be performed with ihe connection disassembled. Supports F1.10A Class 1 Piping Supports -One Visual. Vf.J 113 30 26.5% Each inspection 6 13 11 Directional lnlerval Svsrem eve 57 15 ... 2 1 6 RCS 37 10 ... 2 5 3 RHR 4 1 Ill 0 0 1 SIS 15 4 .. 2 1 1 F1.10B Class 1 Piping Supports -Multi-Visual, VT-3 89 24 26.9% Each !n:;;pecilon 6 10 8 direclional interval Syslem eve 62 16 \II 1 7 6 RCS 14 4 -"' 4 0 0 SIS 13 4 Ill 1 3 0 Fl .10C Class 1 Piping Supports -Visual, VT-3 81 23 28.3% EaCh inspection 6 7 10 Thennal Movement Interval Svslem eve 33 9 "' 2 4 3 RCS 22 6 Ill 2 1 3 RHR 5 2 "' 0 1 1 SIS 21 6 ,., 2 1 3 f1.10 Total Class 1 Piping Supports Visual, 263 n 25%1'1 Each Inspection 18 30 29 VT-3 Interval Fl.20A Class 2 PlplJlg Supports -One Visual, VT-3 245 40 16.3*,(, Each inspection 11 14 15 Olrecliona I Interval  .1 Table 2.1*3 IP.2 Code Categorv Summary Required to Number of be Examined Category Item Number Description ExC1mMathod Components In During ltamNo. Interval Svslem AFW 3 1 BFD 11 2 eve 1 1 HIS 45 7 MS 31 5 RHR 20 3 SIS 134 21 F-A F1.20B Class 2 Piptng Supports -Multi* Visual. Vf-3 117 21 d!ractional Svstem BFD 13 2 eve 1 1 HIS 46 7 MS . 18 3 RHR 6 3 SIS 33 5 F-A F1.20C Class 2 Piping Supports -Visual. Vf-3 133 24 Thermal Movement System AFW 4 1 BFD 8 2 eve 1 1 HIS 19 3 MS 35 6 RHR 19 3 SIS 47 8 F*A F1.20 Tot.al Class 2 Piping Supports Visual, 495 65 VT-3 F-A F1.30A Class 3 Piping Supports -One Visui'.11, Vf.J 235 27 Difactii:mal Svslem ACS 1 1 AFW 33 4 ccw 114 12 eve 1 1 SW 86 9 F-A F1 .308 Class 3 Piping Supports -Mulli-Visual. VT-3 189 21 directional Svstem AFW 7 1 ccw 51 6 Examination Number to be Percentage Examined In Required Interval '" ,,, '" "' '" '" "' 17.9% Each rnspeclion interval lll "' "' ,,, ,,, "' 18% Eaeh inspection inlerval "' w "' ,,, Ill lll ,,, 15%11) Eachlnspocllon Interval 11.4% Each inspection inlerval '" \I) ,,, l'I \\) 11.1% Each inspeciiM interval lll ,,, PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 63 of69 Numoorto Number to Number to be be be Examined Examined Examined In Third in First In Second Period Period Period 0 0 1 0 1 1 0 0 1 0 3 4 2 3 0 1 0 2 B 7 6 a 3 10 1 0 1 0 0 1 3 3 1 1 0 2 3 0 0 0 0 5 s 7 12 0 0 1 1 1 Q 0 1 0 0 0 3 1 3 2 2 1 0 1 1 6 24 24 37 9 4 14 0 0 1 0 1 3 5 3 4 0 0 1 4 0 5 3 8 10 0 0 1 2 2 2 
---:::--' Entergy Attachment 3.1 Table 2.1-3 IP2 Code Category Summary Required to Numoorof be Examined Catogary ltom Number Dascrlption Exam Method Components in During llem No. Interval SW 131 14 F-A F1.30C Class 3 Piping SuppMs -Visual, VT-3 51 6 Thermal Movement Svslem ACS 7 1 AFW 8 1 ccw 17 2 SW 19 2 F-A F1.30 Total Class 3 Piping Supports Visual, 475 54 VT-3 F-A F1.40B Supports olhcr lhan Piping Visual, VT*3 15 5 Suooorls Svstem eve 6 2 RCS 9 3 F-A F1 .40C Supports other lhan Piping Visual, VT *3 11 6 Supports Svslem RHR 6 3 SIS 5 2 f-A F1.400 Supports other lhan Piping Visual. VT-3 31 14 Suooorts Svslem AFW 3 2 ccw 6 2 SW 18 6 NIA 4 4 F*A F1.40 Supports otbor than Piping Visual. 'Sf 24 Supports ICla!>S 1.2.3, nnd MC) VT-3 Ca&O(lory Total 1310 240 Examination Number to be Percentage Examined In Required Interval '" 11.7% Each inspection inlerval ,,, ,,, "' \11 10%'" EaehlnspecUon Interval 33.3% 46.4%. 46.1% 42.1% Each Inspection lnterva112H1l PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 64 of 69 Number to Number to Numbarto be bo be Examined Examined Examined in Third In Fir.st In Second Period Period Period 1 6 7 0 5 1 0 1 0 0 1 0 0 1 1 0 2 0 12 17 25 0 0 5 0 0 2 0 0 3 1 0 4 1 0 2 0 0 2 0 1 13 0 1 1 0 0 2 0 0 6 0 0 4 1 1 22 65 72 113 
-= --Entergy PROGRAM SECTION No. SEP-1$1-IP2-001 Revision No. 4 Page 65 of69 Attachment 3.1 Table 2.1-3 IP2 Code Cateaorv Summarv Required to Number to Number to Number to Number of Examination Number to be be be Cat&gory !tom Number DoscripUon Exam Mothod Components In be Examined Percentage Examined In Examined Examined bo Examined Item No. During Required Interval In First In Second in Third Interval Period Period Period Note 1: The tolal percentage sample shall he comprised of supports from each system. where lhe indivldual sample sizes are proportional to the lotal number or non-exempt supports or each type and lunciion within each system (Ref. Table IWF-2500*1, Exeminalion Category F*A, Nole 2}. Total may exceed percentage requirements to alf<1w seleclion of al least one support of every type anti system. Nole2: For mu!Ople components other tll<m piping, within a system or similar design. function. and se!Vice. lhe supports of only one or the multiple components are required to be examined (Ref. Tabla IWF-2500-1, Examination Category F-A. Note 3). Noles For Cat. F-A Note3: 1 Pressurizer Support, 1 of 4 Reactor Coolant Pump Supports, 2 of 6 Regenerative Heal Exchanger Supports, 1 of 4 Sleam Generator Supports. 1 of 2 Containment Spray Pump Supports. 1 of 2 Residual Heat Removal Pump Supports. 2 of 4 Residual Heal Removal Heal Exctianger Supports. 1 of 3 Safety lnjeclion Pump Suppons, 1 of 2 Auxiliary Feedwater Pump Supports (Electric), 1 of 2 Component Cooling Water Heat Exchangers Supports, 1 of 5 Recirculation Fan Coorer Supports. 1 ol 6 Seivlce Water Pump Supports. 1 al 3 Compomml Cooling Waler Pump Supports. 1 Audiary Feedwater Purnp Supports (Turbine), 1 of 2 Spent Fuel Pump Supports and 1 of 6 Sewice Water Pump Strainer Supports. Additionally !here are 4 CROM supports. with 4 of 4 required. 24 of the 57 non piping supports are selected for examination or 42.1 % or all non* piping supports. L-A Concrete l*A l1.11 All accessible surface areas General Visual 48 9510 100% IWL*2410 0 48 48 l-A ll.12 Suspect areas Detailed Visual 0 0 100% IWL-2410 0 0 0 Ca1egory Total 48 96111 0 48 48 Notes for Cat. L*A Note 1: IWL-2410 requires 100% exam!nalion every 5 years. Therolore the number required during Illa interval is twloo lhe lolal number of components. This is reflected in the category total. R*A Risk Informed Piping and Component Welds High Safely Significant Pip>.ng R*A R1 .10 S!ruciural Elemenls (1) Elements Subject to Thennal Each inspection R-A R1.11 Fatigue Volumetric 122 31 (1) interval 11 8 12 Elements Subject to Thermal Visual VT *2 of Fatigue (socket welds of any size Otting and Each inspection R*A R1 .11s and branch conneelions NPS 2 or Volumetnc of 3 3 (1) lnlef\ial0i 0 3 0 smaller) base metal ln lninino R-A RU2 Nol Used 
--="'Entergy Attachment 3.1 Table 2.1-3 IP2 Code Categorv Summarv Required to Numbarof Cata gory Item Number Dascrlpllon Exam Method Components In be Examined Item No. During Interval Elements Subject lo Erosion-R-A R'l.'l3 Cavil a lion Volume Irie NIA NIA Elements Subject to Crevice R-A R1.14 Corrosion Cracking Volume Irie NIA NIA Elements Subject to Primary R*A R1.15 Waler Stress Corrosion Cracking Volumetric NIA NIA IPWSCCl Wefds Subject to lnlergranu!ar or R-A R1.16 Transgranular Slress Corrosion Volumetric 12 5 Crackin11 CIGSCC or TGSCCJ Welds Subject lo lntergranu!ar or Transgranular Stress Corrosion R*A R1.16s Cracking (IGSCC or TGSCC) Visual, VT*l 5 z (soclmt welds of any size and branch connections NPS 2 or smaller) Elaments Subjeci to Localizecl Visual, VT-3 R-A R1.17 Corrosion (Microbiologically* Internal NIA NIA Influenced Corrosion {MIC) 01 Surfaces or Pitting] Volumetric Elements Subject to Flow Owner's R-A R1.1B Acceleraled Corrosion (FAC) Existing NIA NIA Promam ElemenJs Subject to External R*A R1.19 Chloride Stress Corrosion Surface NIA NIA Cracldng (ECSCC) Elements not Subject to a R-A R1.20 Oegradalion Mechanism Volumelric 460 37 Elements nol Subject to a R-A R1.20s D11gradation Mechanism (sockel Visual. VT*2 434 28 welds of any size and branch connections NPS 2 or smaller) Category Total 1036 10& Examination Number to be Percentage Examined In Required Interval Each inspection (1) interval Each ins.pedion (1J inteival Ea Ch inspection (1)(2) Interval Eaeh Inspection (1) Interval {1} (4) (1] Each Inspection inteival Each inspection (1) interval Each inspection (1) interval Each inspection (1) interval {1) (4) PROGRAM SECTION No. SEP-1Sl-IP2*001 Revision No. 4 Page 66 of69 Number to Number to Number lo be be Examined Eicamlned bo Examined In First in Second in Third Period Period Period NIA NIA NIA NIA NIA NIA NIA NIA NIA 3 2 0 N/A NIA NIA NIA NJA NIA NIA NIA WA NIA NIA NIA 3 115 19 NIA N/A NIA 17151 28151 311*l 
--------Entergy PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 67 of 69 Attachmer;t 3.1 Table 2.1-3 IP2 Code Cateaorv Summarv Required to Number to Number to Number to Number of be examined Examination Number to be be be be Examined Cato gory Item Number Oescriptlon Exam Molhod Components In During Percentage Examined In Examined examined in Third Item No. Required Interval In first In Second rnteirval Period Period Period Nole 1; The selections are based on lhe requirements of Code Case lil-716-1 and not by Code Item Number. Note 2: llem R1.15 is only used when multiple damage mechanisms including PWSCC is al a lacallon. PWSCC is addressed by NRC requlred Ct1de Cases N-722-1. N-729*1 and N-770-1 and not Code Case N*716*1. Noles for Cal. R*A \lole J; Volumetric of base metal is once an fnlerval, lhe Visual. VT*2 of lhe lilting is condueled in accordance wilh Calegories a-P. C-H or D*B, as applicable lo lhe component ASME classification. "Joie 4: The Visual. VT-2 is conducted in acc.ordance wilh Categories B*P, C*H or 0-8, as appficable lo the component ASME cfassillcation. Nole 5: Period totals do not include Visual. VT-2 onlv exams. Code Caiso N-722-1 Additional Examinations for PWR Pros11uro Retaining Wolds In Class 1 Components Fabricated With Alloy 600/821182 Materials 111 N-722-1 815.80 RPV Bottom-Mounted Instrument Visual, VE"1 1 3!ll 100% E: very other 1 1 1 Penelrations rerueling outage N-722*1 815.90 Reactor Vessel Hol Leg Nozzle-Visual, VE12l 4 201*1 100% Each refueling 4 a 8 lo-Pipe Connoclions oulage N-722*1 815.95 Reactor Vessel Cold Leg Nozzle-Visual, VEm 4 100% Once per interval 0 4 0 lo-Pipe Connections Category Total 9 27'lM*l s 13 9 Nole 1: These examinations are in accordance wilh Code Case N-722-1 as required by 10 CFR 50.55a(g)(6){li)(E)(2) through (4). No!e2; An u!lrasonic exarninalion fron1 either !he ID or the OD in accordance wilh Ifie requirements of Appendix Viti shall be acceptable in lieu of Iha Visual, VE. Note 3: Examination of this llem number Is required every other outage. Therefore, the number required during !he interval is two limes !he Iota! number of components. This is reOecied in lhe category total. Notes for Cat. N* 722-1 Noto4: Examination or this ilem nt1mber is required each outage. Therefore. !he number required during Iha Interval is live limes the lolal number of components. This is reflected in the category Iola!. Visual. VE examinations requited for Code Case N-722-1oflha4 Reaclor Vessel Hol Leg Nozzle-to-Pipe Connections consisl!ng of Alloy 6001621182 Material are performed under ASME Code Case N-770-1 Category Table 1 Item No. A*2. Note 5: Examination of lhis ilem is required once per inlerval. VE e)(aminations required for Code Case N*722-1 of the 4 Reactor Vessel Cold Leg Nozzle-lo*Pipe Connections consisting of Alloy 600/821182 Malarial are oerformed under ASME Cade Case N-77G-1 Cateaorv Table 1 Uem B. Coda Case N-729*1 Allernatlvo cKamlnatlon Requirements ror PWR Reactor Vassel Uppar Hoads With Nozzlos Having Prassure*Ret.alnlng Partlal*Penetratlon Welds 1'l Reactor Vessel Upper Head wilh N-729-1 84.10 UNS N06600 nozzles 1!11d UNS Visual. VE 1 5!1l 100% Each refueling 1 2 2 N06082 or UNS W86182 Partial outage Penetration Welas Reactor Vessel Upper Head UNS N-729*1 84.20 N06600 nozzles and UNS Vo!umetr!c/ 1 5PJ 100% Each refueling 1 2 2 N06082 or UNS W86162 partial-Surface outage , oenetralion welds lo head Category Tot.al 2 10""1' 2 4 4 
.. ---Entergy PROGRAM SECTION No. SEP-ISl-IP2--001 Revision No. 4 Page 68 of 69 Attachment 3.1 Table 2.1*3 IP2 Code Cateciorv Summarv Required to Number to Number to Number to Numb&ror ExamlnaUon Number to be be be Cate9oiy Item Number Dase rl ptlon Exam PAeihod Components ln be Examined Percentage Examinedln Examined Examined be Examined Item No. During Required Interval In First In Second In Third Interval Period Period Period Nole 1: These examinations are in* acwrdance with Code Case N-729-1 as required by 10 CFR 50.55a(g}(6}(ii)(D)l2) through (6). Nole2: Examination of this item number is required each oulage. Therefore, the number required during lhe interval is five times the Iota I number of components. This is Notes for Cat. N-729-1 rellected in the category total. Nola3: Examination of lhls ilem ls required each outage. Therefore, lhe number required during lhe interval is five limes the total number of components. This Is also reflecled in lhe calegorv total. Code Case Alternatl11e Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Norzle Butt Welds Fabricated With UNS N06082 or UNS W66182 N-170*1 Wold Fiiier Material With or Without Applleation of Listed Actlvlllesl'I N-770*1 A*2 (85.10) Reactor Vessel Unmitigated Volume Ilic 4 12m 100% Every five years 4 4 4 <B*Fl Hot Log Wolds A*2 N-770-1 A-2 (BS.10) ReactorVessol Unmltfgated Visual, VE121 4 100% Each refueling 4 6 B CB-Fi Hot Loq Wolds A-2 oulaae Evesy second N-770-1 B (85.10) ReactorVcl.lSel Unmitigated Volumetric 4 415) 100% inspection period 0 4 0 (B-F) Cold Leg Welds B not to exceed seven voars N-7701 (B*F) B (BS.10) Reactor Vessel Unmitigated Visual, VE121 4 4l2> 100% Once per intel\tal 0 4 0 Colc:l Leq Wolds B Category Total 16 40 8 20 12. Note 1: These examinations are in accordance wilh Code Case N-770-1 as required by 10 CFR 50.55a(g)(6){il)(F)(2) through (10}. Nole2: An ultrasonic examlnallon from either lhe ID or the OD in accordance wHh the requirements of Appendix VIII shell be acceplable in lieu of the Visual, VE. Code Case N* 722*1 and Code Case visual el<aminations should be scheduled al lhe same time. Note3: Examination of this !lem number Is required every five years. Therefore, IM number required during Iha inleival is 3 limes the Iota I number of components based on 24 Noles force N*770-t month refueling cyde. This Is reflected In the category total. Note 4: Examination of this item number is required each refueling outage. Therefore, !he number requ!red during the interval is 5 times the total number or components. ihis is reflected in lhe category total. Vcsual, VE examinations performed under N-770-1 Item No. A-2 additionally credjled for ASME Code Case N-722-1 Item No. 815.90. Nole 5: Examination or this item number is required every seven years. Therefore, lhe number required during the interval ls 1 lime the total number of components. This ls reflecie<I in lhe cate<:sorv Iola!. Visual, VE examinations uerformed under N-770-1 !fem No. B addilionally credited for ASME Code Case N*722-1 Item No. 815.95. MRP-146Rev1 Management of Tharmal Fatigue In Normally Stagnant Non-lsolable Reactor Coolant System Branch Llnast11 NIA Una 95 MRP 146 conliguralion H Volume Irie: 1 5!2J!*t 100% Each refueling 1 2 2 oula11e NIA Line 96 MRP 146 configur<Jtion H VisualVT-2 1 5l211*i 100% Each rerueting 1 2 2 oulage Category Total 2 10cz1m 2 4 4 NIA line 82 tv1RP 146 configuration OH Volumetric 1 2J)(41 100% Every other 0 1 1 refueling oulage 
---Entergy PROGRAM SECTION No. SEP*ISl*IP2*001 Revision No. 4 Page 69 of 69 Attachment 3.1 Table 2.1*3 IP2 Code Categorv Summarv Required to Number to Number to Numborto Number of Examination Number to be be be Category Oescrl pllon ExamMothod ComJ)-0110111.s In be Examined Percentage Examined in Examined Examined Ila Examined Item No. During Required Interval In First In Second in Thlrd Interval Period Period Period NIA Line 62 MRP 145configuration DH Visual VT-2 1 2(3)(*) 100% Everyolhar 0 1 1 refueling oulage NIA Line 83 MRP 146 configuration DH Volumetric 1 -2(3)(4) 100% Every olher 0 1 1 refueling oulage NIA Line 63 MRP 146 configuration DH Visual VT-2 1 2(l)(*) 100% Every other 0 1 1 refueling outage NIA Linc 64 MRP 146 configuration DH Volumetric t 2(l)l4) 100% Eveiy other 0 1 1 refueling outage NIA Unell4 MRP 146 conllguration DH VisualVT-2 1 2mNJ 100% Every o!har 0 1 1 refueling outage Category Total I) 1zCl1!*1 0 6 6 Nole 1: These examinations are in accordance with MRP* 146 Rev 1 Guideline. Note2: Examlnalion of lhis ilem number iS required each refueling outage. Thetefore, lhe number required during lhe interval is 5 !imes lhe lolal number of componenlS. This is Notes for MRP-146 reflected in the calegory total. Nore3: Examinatfon of lhis item number Is required every other outage. Therefore, Iha number required doling the Interval Is two limes the Iola I number of components. This is reRected in tile category total. Note4: The ISi orooram wm track and monllor the MRP-146 Rev 1 lnspecllons. Socilot Wolds llcons& Renewal Commiuoont #46 (LO-LAR-2011..0174 CA 65) Socket Wold Examination Elemenls Subject ta Thermal R-A R1 .11s Faligue (socket welds or any size Volumetric<11 3 3 100% Each Interval 0 3 0 and branch connections NPS 2 or smaller) Welds Subject to lntergranular or Trnnsgranular Stress Corrosion R-A R1.16s Cracking (lGSCC or TGSCC) Vo!umelriclO 5 5 100% Each Interval 2 0 3 (socket welds ol any size and branch cnnnections NPS 2 or smaller) Elemenls no! Subject to a R-A R1.20s Degradation Mechanism (socket Volumetric<11 17 17 100% Each Interval 5 6 6 welds of any size and branch NPS 2 orsmaflerl Caleaory Total 25 25 7 9 9 Notes for Socket Welds Nole 1: Volumetric weld meral !nspeclions al socket welds shall be performed. In lieu of volume!rlc examinalions. destructive examinations may be performed, where one deslructive examination mav be subslilutw for lwo volumetric examina!ions. 
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Revision as of 22:53, 5 May 2018

Indian Point, Unit 2, Fifth Ten Year Interval Inservice Inspection Program Plan
ML16256A782
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 09/06/2016
From: Vitale A J
Entergy Nuclear Northeast
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-16-097
Download: ML16256A782 (71)
v • d • e


Text

  • NL-16-097 September 6, 2016 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box249 Buchanan, NY 10511-0249 Tel 914 254 6700 Anthony J. Vitale Site Vice President

SUBJECT:

Indian Point Fifth Ten Year Interval lnservice Inspection Program Plan Indian Point Unit Number 2 Docket No. 50-247 License No. DPR-26

Reference:

Entergy Letter to NRC (NL-16-091 ), "Indian Point Fifth Ten Year Interval lnservice Inspection Program Plan," dated August 17, 2016

Dear Sir or Madam:

Entergy is submitting this letter to supplement the submittal of the fifth ten year interval lnservice Inspection Program plan for Indian Point 2 (IP2) in the referenced letter. That submittal was to consist of two sections but only one section was enclosed. The second section is enclosed with this letter to fully comply with the requirements of 10 CFR 50.55a(g)(4)(ii). If you have any questions or require additional information, please contact Mr. Robert Walpole, Manager, Regulatory Assurance at (914) 254-6710. Sincerely,

Enclosure:

Fifth Ten Year lnterva) lnservice Inspection Program Plan cc: Mr. Douglas Pickett, Senior Project Manager, NRC NRR DORL Mr. Daniel H. Dorman, Regional Administrator, NRC Region 1 NRC Resident Inspectors Office Mr. John B. Rhodes, President and CEO, NYSERDA Ms. Bridget Frymire, New York State Dept. of Public Service ENCLOSURE TO NL-16-097 FIFTH TEN YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN ENTERGY NUCLEAR OPERATIONS, INC. INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247

-PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 1 of69 IP2 FIFTH TEN-YEAR INTERVAL INSERVICE INSPECTION (ISl)J CONTAINMENT INSERVJCE INSPECTION (Cll) PROGRAM PLAN ENTERGY NUCLEAR ENGINEERING PROGRAMS APPLICABLE SITES All Sites: 0 Specific Sites: ANO 0 GGNS 0 IPEC 181 JAF 0 PLP 0 PNPS 0 RBS 0 VY 0 W3 0 HON 0 Current Revision Safety Related: Program Section Revision Summary Description of Change Yes 0 No ------*--i-------------------------------l I II Revision 4 Incorporated the following changes: 4 1_. e:,_m_on_wnh 20-os I_ 1<7' PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No.4 Page 2 of69 REVIEW AND CONCURRENCE SHEET Program Section Title: IP2 Fifth Ten-Vear Interval lnservice Inspection (ISl)/Containment lnservice Inspection (Cll) Program Pian Reviewed __ Programs Erl Reviewed For I EJIWL Only ANll: Allan Schiaffino Authorized Nuclear Jn-Service Inspector {ANll) Concurred: Nelson Azevedo Responsible S Date Date Date Date .s/c)s-J h */x/0 f-sk/tl:;; vj2c,f 16

-SECTION All REVISION STATUS SHEET PROGRAM SECTION NO. SEP-151-IP2°001 Revision No.4 Page 3 of69 SEP-iSl-IP2-<J01 R4. PAGE REVISION STATUS PAGE NO. As Applicable REV. Incorporate Data for*Fifth Ten-Year Interval

  • --::--Entergy Section TABLE OF CONTENTS PROGRAM SECTION No. SEP-ISl*IP2*001 Revision No.4 Page4 of69

1.0 INTRODUCTION

AND PLAN DESCRiPTION ............................ ,. ........................................... 6 1.1 Introduction .......................... ,. ................................................................................... 6 1.2 IS! Inspection Interval.. ............................................................... ., ............................... 7 1.3 IP2 Original Construction Codes of Record ............................................................. 11 1.4 IP2 Fifth Inspection Interval ASME Code of Record ................................................. 13 1.5 lnservice Inspection Program Plan Development.. .................................................. 16 1.6 lnservice Inspection Boundary Development .......................................................... 17 1.7 Inspection, Examination, and Testing Activities Not Controlled By thrs Plan ............ 20 1.8 Augmented Inspection Programs ................................................................. ., ......... 20 1.9 Administrative Controls ............................................................................................ 28 1.1 O ID DEAL Data-Management Program .................................................................... 28 1.11 Adoption and Use of ASME Section XI Code Cases ............................................... 29 1.12 Technical Positions .......................................................................... ,. ..................... 31 1.13 Relief Requests ....................................................................................................... 32 1.14 Calibration Blocks ......................................................................... ,, ........................ 35 1.15 Limited Examinations .......................................... , .................................................... 35 2.0 APPLICATION CRITERIA AND CODE COMPUANCE ......................................................... 37 2.1 ASME Section XI .................................................................................................... 37 3.0 ATIACHMENTS .......................................................................................................... " ........ 52 Attachment 3.1 Table 2.1 IP2 Code Category Summary ............................................... 53

Entergy SECTION 1.0 PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No.4 Page 5 of69 INTRODUCTION AND PLAN DESCRIPTION

-PROGRM'i SECTION No. SEP*ISl*IP2*001 Revision No.4 Page 6 of 69

1.0 INTRODUCTION

AND PLAN DESCRIPTION 1.1 Introduction This document establishes the Fifth Ten-Year Interval lnservlce Inspection (ISi) Program Plan and the Containment lnservice Inspection (Cll) Program Plan for Indian Point Nuclear Generating Station Unit 2 (lP2), in accordance with the Code of Federal Regulations (CFR), Title 10, Part 50, Section 55a, "Codes and Standards" (10 CFR 50.55a). The IP2 Fifth Ten-Year Interval ISi Program Plan is compliant with ASME Section XI, Division 1, uRules for lnservice Inspection of Nuclear Power Plant Components 2007 Edition through 2008 Addenda, as conditioned by 10 CFR 50,55a; and altered as allowed by 1 O CFR 50.55a(g)(6) or 1 O CFR 50.55a(z) and documented in the included requests for relief." The inspection and non-destructive examination of systems, structures, and components (SSCs) will be performed to the extent practical1 and possible as permitted by existing designs, equipment arrangements, available access, and radiological conditions. Relief request reference documentation, is also provided for those component$ where meeting the code requirement is impractical or unnecessarily burdensome. Throughout the Fifth Ten-Year Interval ISi Program Plan, reference is made to SEP-ISl-IP2-002, "IP2 Fifth Ten-Year Interval lnservice Inspection (181)/Containment lnservice Inspection (Cll) Schedule and Bases Document". The IP2 Fifth Ten-Year Interval ISi Program is also used for implementation of the license renE!Wal commitments described in LO-LAR-2011-0174 CA 35, CA 37, CA 38, CA 40, and CA 65. This Program Plan outlines the requirements for inspection of: 1.1.1 ISi -Pressu.re Retaining Components/Supports e ISi Class 1, 2, and 3 (Quaflly 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 exceptions: c The RI-ISi Program shall be re-employed at IP2* during the 5th Ten-Year JSI Interval; however. the RI-ISi Program shall be implemented utilizing ASME Code Case N-716-1 approved for use per USNRC Regulatory Guide 1.147. This alternative Inspection Program is used in lieu of the requirements of IWS-2420, IWB-2430, Table IWB-2500-1, Examination Categories B-F and B-J, IWC-2420, IWC-2430 and Table IWC-2500-1 (excluding Examination Categories C-C and C-H), for inservice inspection of Class 1 piping welds or Class 2 components, IWB-2200 and IWC-2200 for preservice inspection of Class 1 piping welds or Class 2 components, or as additional requirements for Class 3 or Non-Class components. The Inspection Program provides alternative criteria for selection, examination method, and examination coverage based on ASME Code 'Case N-716-1. 1 The construction pe1T11il for Indian Point Unit 2 was issued on October 14, 1956. Per 10 CFR 50.55a(g)(1) Jnservice inspection requiroments far older plants (pre-1971 CPs). "For a boiling or pressurized water-cooled nuclear power facility whose construction pemiit was issued before January 1, 1971, components (including supports) must meet lhe requirements of paragraphs (g}(4} and (g)(5)

  • to the extent practical." *

Entergy PROGRAM SECTION No. §J;P*ISl*IP2*Q01 Revision No.4 Page 7 of69 e As defined by IWF-1300, snubber support hardware such as tugs, bolting, pins, clamps, and structural steel between the snubber pin and the pressure retaining item and between the snubber pin and 1he building steel are included in the support population and examined in accordance with Subsection IWF per this Program Section.

  • Class 1 pressure retaining welds containing Alloy 600/821182 in accordance with Code Case N-722-1, "Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/821182 Materials",Section XI Division 1 with conditions specified in 10 CFR 50.55a(g)(6)0i)(E)(2) through (4). (Reference Augmented Program 1.8.4). If? 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 10 CFR 50.55a(g)(6)(ii)(D)(2} through (6). (Reference Augmented Program 1.8.5). e Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigatiqn Activities in accordance with Code Case N-770-1, "Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities",Section XI, Division 1, in accordance with the requirements in 10 CFR 50.55a(g)(6)(1i)(F)(2) through (10). Note: License Renewal commitment LO-LAR-2011-0174 CA37 is tracked and monitored in accordance with the Code Case N-770-1 examination requirements, and augmented existing ISi inspections as appropriate. (Reference Augmented Program 1.8.6). 1.1.2 CH -Containment ISi Pressure Boundary Liner/Concrete e 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 a Augmented inspection programs are detailed Jn Section 1.8. 1.2 JSR Inspection Interval 1.2.1 ISi -IWA, IWB, IWC, IWO, & IWF Interval History The commercial service date for IP2 was August 1, 197 4. The table below summarizes the IP2 Interval dates.

PROGRAM SECTION No. SEP*ISl*IP2*001 Revision No.4 Page 6 of69 IP2 Interval Dates Summary 10-Year Interval Interval Inspection Start Date End Date length of Interval Interval 1 Julv 1, 1974 June 30, 1984 1 O vears. O months 2 Julv 1. 1984 June 30. 1994 1 O vears, O months 3c July 1. 1994 Februarv 28 2007 012 vears. 8 months 4 March 1. 2007 Mav 31. 2016 bg vears. 3 months 5" June 1, 2016 Mav 31, 2026 1 O vears. O months *The Third Ten-Year Inspection lnleNal ISi program plan was orlginally approved ror the effedive dates from July 1, 1994 truough June 30, 2004. ASME Boiler & Pressure Vessel Code,Section XI (1989 EdilionJ Paragraph IWA-2430 (e), allows inspection inleNals 10 be extended whenever there is an outage greater than six months. An interval extension equivalent to the lime Iha! the unit has been out of service ls allowed. The first period was rrom July 1, 1994 lo September 1 B. 1998 having been extended 326 days for the 0850 Breaker Outage. The second period was from September 19, 1998 la December 5, 2002 having been extended 321 days for steam generator replacement outage and olller plan! equipment emergencies. Thus, Ille third period was re.scheduled from June 30. 2004 lo February 28, 2007. These dales can be extended or decreased 1 year to coincide with a refueling outage. b IP2 Fourth Ten-Year lnspedlon Interval and lhls lSl/Cll Planwm be effective from Maren 1. 2007, through and lnc.'Llding May 31, 2016. II should be noted that !he. plant's cutrenl {original} operating license will expire on September 28. 2013. Entergy is in the process qf a license renewal application. The end date of the 4th lnteival will be controlled by the ISl/Cll Program Plan. commensurate with !he Operating License Renewal Application. c During the Third Period al the Third ISi ln!eival. Illa Rlsk-lnfonned Program (Rl*ISI} was approved for use via NRC Safely Evaluation Report {TAC No. MC0303). During !h!s lime period the requited percentage for !he period was compleled. The Rl*ISI Program Is re-employed at IP2 during* lhe 41" Ten-Year !SI lnleival via Relief Request RR*OS. This program is comprised of Class 1 (ASME categories B*F and B*JJ piping segments/elements. As an alternative lnspecllon Program the criteria far selection. examination method, examination coverage, and extent is based on EPRI repor1 TR-112657. *As part of tile Fifth Inspection lnteNal update. IP2 implemented Code case N*716* 1. This aflemauve lnspeciioo Program is used In lieu of !he requirements of IWB-2420. IWB-2430. Table IWS...2500*1. Examination Categories B*F and B*J. IWC.2420. IWC*2430 and Table IWC-2500-1 (excluding Examination Categories C-C and C*H). for inservlce inspection of Class 1 piping welds or Class 2 components. IWB-2200 and IWC-2200 for pieservlce inspection of Class 1 piping welds or Class 2 components. or as additional requirements for Class 3 or Non-Class comjl-Onents. 1.2.2 Cll -IWEJIWL Interval History On September 9, '1996, 10 CFR 50.55a 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 water cooled nuclear power plants and IWL contains the requirements for ISl 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 _I

-Entergy' ------------PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No.4 Page 9 of69 inspection interval. Therefore the First Period Examinations were completed by September 9, _2001 to meet 10 CFR 50.55a requirements. The IWE inspection periods were therefore: 10-Year Inspection inspeci:lon Period IWE Period Dates Interval 1 1 Sep. 9, 1996 -Sep. 9, 2001 i 2 Seo. 10, 2001 -Jan. 9, 2005 1 3 Jan. 10. 2005 -aFeb. 28. 2007 2 1 March 1, 2007 -Mav 31 2010 2 2 June 1 2010-Mav 31. 2014 2 3 June 1 2013-Mav 31. 2016 :i' 1 June 1. 2016-Mav 31, 2019 3t> 2 June 1, 2019-Mav 31. 2023 3b 3 June 1, 2023 -Mav 31 2026 a Based upon this extended First Period that ended on September 9, 2001, the First 10-Yr Interval for IP2 Containment ISi was originally scheduled to end on May 9, 2010, but was shortened lo align with the Third.ISi Interval. b Although it is only the IWE Inspection Interval at IP2, the ISi Plan is combined and labeled in the Tille as the 5m Ten-Year lnlerval as well as in the Database. 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 June, 2000; the second inspection was completed in June 2005; the third inspection was completed during 2010; and the fourth inspection completed during 2015. Subsection IWL-2421 does not apply to lP2. 1.2.3 Fifth Ten-Year Bnterval Schedule The IP2 Fifth Ten-Year Interval ISi Program Plan and CH Plan will be effective from June 1, 2016 through May 31, 2026. 1.2.3.1 IWB, !WC, IWD, IWE, and IWF Inspection Schedules: The inspection schedule for the fifth inspection 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

  • ------Entergy PROGRAM SECTION No *. SEP-ISJ-IP2-001 Revision No.4 Page 10 of 69 Inspection Period 1 2 3 table summarizes the period dates for the fifth inspection interval as defined by IWB-2411, IWC-2411, IWD-2411, IWE-2411 and IWF-2410. The inspection schedule for each ISi Period is provided in the lddeal software. Changes to the stated Inspection Interval or Inspection Period dates, if deemed necessary, will be documented. IP2 Fifth Interval lnsoectlon Periods Summarv Dates Period Start Period End Years of Plant PDant Refueling Out.ages Operation Within Date Date Period within Period June 1. 2016 Mav 31, 2019 3 years RF0-23 (Serina 2018) June 1. 2019 May 31, 2023 4years RFD-24 (Spring 2020) RF0-25 (SprinQ 2022) June 1. 2023 May 31, 2026 3 years RF0-26 (Spring 2024) RF0-27 (Spring 2026) 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). Any concrete surface areas that become affected by a repair/replacement activity shall be examined in accordance with the requirements of IWL-2510 at I year(+/- 3 months) following completion of repair/replacement activity. If plant operating conditions are such that examination of portions of the concrete cannot be completed within this time interval, examination of those portions may be deferred until the next scheduled plant outage. 1.2.3.2.1 Notification to New York State In compliance with Atomic Safety and licensing Board Order (Approving Settlement of Contention NYS-24), Docket Nos. 50-247-LR and 50-286-LR, ASLBP No. 07-S58-03"LR-BD01(January26, 2012), and the Settlement Agreement Regarding New York State Contention 24 (December 21, 201 i) approved therein: 1.2.3.2.1.1 When an inspection is completed, reviewed and approved by the Unit ISi Engineer. a copy of the completed inspection report shall be foiwarded to Licensing. 1.2.3.2.1.2 The Unit ISi Engineer shall issue a Work Tracking CR to Licensing to assure that copies of the report(s) are forwarded to:

AE -=-----== ntergy PROGRAM SECTION No. SEP01Sl*IP2*001 Revision No.4 Page 11of69 State of New York Office of the Attorney General and Power Systems Operations, New York State Department of Public Service Notes: The names and mailing addresses of the State-designated recipients of the reports are retained and updated (as necessary) by Licensing. Copies of the above-referenced Order and Settlement Agreement also are retained by Licensing. The Settlement Agreement provides that Entergy (or its successor in interest) shall provide New York State with copies of the results of future ASME Section XI IWL visual inspections and/or the results of inspections or tests that might replace, augment, or update these visual Inspections of the exterior concrete surfaces of the IP2 containment. 1.2.4 Alignment of ISi and Containment ISi Intervals An integral part of this Fourth Ten-Year Interval Program Plan was the merging of the Cll Program Plan with the ISi Program Plan. The Fifth Inspection Interval will continue the merger of these two program plans. This will facilitate one set of ASME Code requirements for both program plans. The First Interval Cll Program Plan was originally effective from September 9, 1996, through and including May 9, 2010. This time period was shortened to end on February 28, 2007. !WE Containment inservice examinations scheduled for the first 40-month period were completed during the Third Period of the Third ISi Inspection Interval. These examinations now serve the same purpose as service baseline examinations. The required IWL inservice examinations were also completed and re-inspections are scheduled at 5 year frequency. The next scheduled IWL inservice examination will be performed in 2020 and documented in the IS! 5th Interval Program Plan. (Tracked under W0-438424). Henceforth, the Second Ten-Year Interval for IWE/IWL Containment ISi inspections at IP2 commenced on March 1, 2007 coincident with the start of the Fourth 10-Year ISi Program Interval. Therefore, both the ISi and the Cll IWEIJWL Program Plans were aligned with the Fourth Interval ISi Program schedule and ASME Code requirements and thus will be aligned with the Fifth Interval ISi Program Schedule and ASME Code requirements. 1.3 IP2 Original Construction Codes of Record The construction permit for Indian Point Unit 2 was issued on October 14, 1966. At that time, the ASME Boiler and Pressure Vessel Code covered fabrication of only nuclear vessels. Piping was built to the rules of USAS 831.1.0-1955, Power Piping. There were no Codes identified for pumps and valves, In the record documents. 1.3.1 ISi-Systems, Structures, and Components The primary IP2 original Construction Codes for major equipment are listed below.

AE ntergy PROGRAM SECTION No. SEP-iSl-IP2-001 Revision No.4 Page 12 of69 Component System Pressure Vessels, non-RCS Reactor Vessel, Pressurizer, & RCP Bowl Steam Generators Piping Design -General Design Criteria Construction Code ASME Boiler & Pressure Vessel Code,Section VIII, 1968 ASME Code, Section 111, Class A, 1965 Edition thru the 1966 Addenda ------------------------! ASME Code, Section Ill, 1980 Edition, plus winter 1981 addenda (stress report to the 1965 ASME B&PV Code, Section Ill, plus Addenda thru summer 1966) ASA Section 831. 1 Pressure Piping Code 1955 1.3.1.1 ISi Pre-service Inspections Westinghouse performed the preservice inspection of Indian Point Unit 2 in 1971 (Ref. Westinghouse letter No. LEE-1043, dated Nov. 12, 1971). 1.3.2 Cll -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 0.25-in. thick liner located on top. The 0.25-in. liner plate is covered with 3 ft. of concrete, which forms the floor of the containment and serves to carry internal equipment loads. The basemat ts supported directly on rock. 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 fl 6 in. thick. A steel liner is attached to the inside face of the concrete shell to form a leak tight membrane. The steel liner is 0.50 in. thick in the first three courses, thickened to 0.75 in. at penetrations, and 0.375 in. thick for the remaining portion of the cylindrical wall. The hemispherical dome is a 135 ft. diameter 3 ft. 6 in. thick shell that is lined with a 0.50 in liner plate. The inside radius of the dome is equal to the inside radius of

---=Entergy PROGRAM SECTION NO. SEf*ISJ.IP2*0C>1 Revision No.4 Page 13 of 69 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 Ill, 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. The liner, penetration sleeves and airlocks were constructed and tested to the requirements of Specification 9321-01-225-3. 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 IP2 commencing operations. However, in accordance with the regulatory requirements of 1 O CFR 50.55a, 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 five years for the implementation of the First Period Examinations, which were completed by September 9, 2001. 1.4 IP2 Fifth Inspection Interval ASME of Record 1.4.1 The regulations in 1 O CFR 50.55a(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 10 CFR 50.55a(b), one year prior to the beginning of each 120-month ISi inspection interval. This is considered the Code of Record. The Code of Federal Regulation in effect one year prior to the beginning of the fifth inspection interval was published in June 2011 as CFR76FR36232. This CFR incorporated, by reference, the ASME Section XI, 2007 Edition through 2008 Addenda in paragraph (b)(2) with limits and conditions. Subsequently, CFR73FR52749 was published in September 2008 requiring expedited implementation of Code Cases and N-722. In October 2008 CFR73FR57235 was published correcting errors in CFR73FR52749. In June 2011 CFR76FR36269 was published requiring implementation of Code Cases N-722-1 and N-770-1 . 1.4.2 Based on the referenced CFRs in 1.4.1, the IP2 Fifth Ten-Year Interval ISi Program Plan is based on the requirements of the 2007 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI through 2008 Addenda with the limits and conditions contained in 1 O CFR 50.55a(b)(2} and fisted in SEP-ISl-IP2-002. Additionally, based on specific limits, earlier editions and addenda are also being used as described below.

Entergy 10 CFR. 50.65a Reference 10 CFR 50.55a(b}(2)(ii} 10 CFR 50.55a(b}(2)(xiv) 10CFR 50.55a(b)(2){XViii}(A) 10 CFR 50.55a(b)(2)(xxi)(A} PROGRAM SECTION No. SEP-ISl*lf2-001 Revision No.4 Page 14 of69 Mandated Additional Requirements/Conditions/ExemptionsSection XI Condition: Pressure-retaining welds in ASME Code Class 1 piping (applies to Table IWB-2500 and IWB-2500-1 and Category B-J}. If the facility's application for a construction permit was docketed prior to July 1, 1978, the extent of examination for Code Class 1 pipe welds may be determined by the requirements of Table IWB-2500 and Table IWB-2600 Category B*J of Section XI of the ASME BPV Code in the 197 4 Edition and Addenda through the Summer 1975 Addenda or other requirements the NRC may adopt (Note: This reference Is provided for Information/completeness only, Category B-J welds will be examined in accordance with Code Case N-Section XI condition: Appendix VIII personnel qualification. All personnel quanfied for performing ultrasonic examinations in accordance with Appendix VIII must receive 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of annual hands-on training on specimens that contain cracks. Licensees applying the 1999 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1)(1i} of this section may use the annual practice requirements in Vll-4240 of Appendix VII of Section XI in place of the 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of annual hands-on training provided that the supplemental practice is performed on material or welds that contain cracks. or by analyzing prerecorded data from material or welds that contain cracks. In either case, training must be completed no earlier than 6 months prior to performing ultrasonic examinations at a licensee's facility,Section XI Condition: NDE personnel certification: First provision. Level I and II nondestructive examination personnel must be recertified on a 3-year interval in lieu of the 5-year interval specified in the 1997 Addenda and 1998 Edition of IWA-2314, and IWA-2314(a) and IWA-2314(b) of the 1999 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1)(ii) of this section.Section XI Condition: Table IWB-2500-1 examination requirements: Table IWB-2500-1 examination requirements: First provision. The provisions of Table IWB 2500-1, Examination Category B-D, Full Penetration Welded Nozzles in Vessels, Items 83.120 and 83.140 (Inspection Program B) of the 1998 Edition must be applied when using the 1999 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1)(ii) of this section. A visual examination with magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the allowable flaw length criteria in Table IWB-3512-1, 1997 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1 )(ii) of this section, with a limiting assumption on the flaw aspect ratio (i.e., a/I= 0.5), may be performed instead of an ultrasonic examination.

  • -::::::-Entergy 10 CFR 50.55a Reference 1 O CFR 50.55a(b)(2)(xxii) 10 CFR 50.55a(b)(2}(xxix) 10CFR 50.55a(g}(6)(1i){D)(1) 10CFR 50.55a{g}(6)(ii){E)( 1) 10CFR 50.55a(g){6}(ii)(F)(1) PROGRAM SECTION No. SEP-1Sf-IP2-001 Revision No.4 Page 15 of 69 Mandated Additional Requirements/Conditions/ExemptionsSection XI condition: Surface examination. The use of the provision in IWA-2220, "Surface Examination," of Section XI, 2001 Edition through the latest edition and addenda incorporated by reference in paragraph (a)(1)(ii) of this section, that allows use of an ultrasonic examination method ls prohibited.Section XI condition: Nonmandatory Appendix R. Nonmandatory Appendix R. "Risk-Informed Inspection Requirements for Piping," of Section XI, 2005 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1)(ii) of this section, may not be implemented without prior NRC authorization of the proposed alternative in accordance with oaraaraoh {z) of this section. Augmented ISi requirements: Reactor vessel head Inspections. All licensees of pressurized water reactors must augment their inservice inspection r:>rogram with ASME Code Case N-729-1, subject to the conditions specified in paragraphs (g)(6)(ii)(0)(2) through {6) of this section. (Program Note: (g)(G)(ii)(D)(4) By September 1, 2009, ultrasonic examinations must be performed using personnel, procedures, and equipment that have been qualified by blind demonstration on representative mockups using a methodology that meets the conditions specified in paragraphs (g)(6)(ii)(D)( 4)(1) through (iv), instead of the qualification requirements of Paragraph -2500 of ASME Code Case N""." 729-1. References herein to Section XI, Appendix VIII, must be to the 2004 Edition with no addenda of the ASME BPV Code.} Augmented ISi requirements: Reactor coolant pressure boundary visual inspectfons. All licensees of pressurized water reactors must augment their inservice inspection program by implementing ASME .Code Case N-722-1, subject to the conditions specified in paragraphs (g)(6)(ii}(E)(2) through (4) of this section. The inspection requirements of ASME Code Case N-722-1 do not apply to components with pressure retaining welds fabricated with Alloy 600/821182 materials that have been mitigated by weld overlay or stress improvement. Augmented ISi requirements: Examination requirements for Class 1 piping and nozzle dissimilar0metal butt welds. Licensees of existing, operating pressurized-water reactors as of July 21, 2011 must implement the requirements of ASME Code Case N-770-1, subject to the condttions specified in paragraphs (g)(6)(ii)(F)(2) through (10) of this section, by the first refueling outage after August 22, 2011.

Entergy 1.5 lnservice lns@;!ectlon Program Plan Development PROGRAM SECTION No. SEP-1SHP2-001 Revision No.4 Page 16 of69 1.5.1 ISllCU n Class 1, 2, and 3 (Quality Group At 81 and C), and Class MC and CC The Fifth Ten-Year lnteival 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 1 O CFR 50.55a e ASME Boiler & Pressure Vessel Code Section V -2001 Edition through 2003 Addenda (Currently in use for Nondestructive Examinations, Repair and Replacement Activities, Pressure Testing and Flaw Evaluation Programs) 0 ASME Boiler & Pressure Vessel Code Section XI -2001 Edition through 2003 Addenda as modified by 10 CFR 50.55a(b)(2) (Currently in use for Nondestructive Examinations, Repair and Replacement Activities, Pressure Testing and Flaw Evaluations Programs) o ASME Boiler & Pressure Vessel Code Section V -2007 Edition through 2008 Addenda e ASME Boiler & Pressure Vesset Code Section XI -2007 Edition through 2008 Addenda as modified by 10 CFR 50.55a(b)(2) and (g)(6)(ii) lfll United States Nuclear Regulatory Commission Regulatory Guides m Regulatory Guide 1.16, Rev. 4 ill Regulatory Guide 1.26, Rev. 2 11 Regulatory Gulde 1.26, Rev. 4 a Regulatory Guide 1.83, Rev. 1 " Regulatory Guide 1.147, Latest Revision "' IP2 UFSAR

  • IP2 Improved Technical Specifications {2 IP2 First Interval Ten-Year lnservice Inspection Program Plan "' IP2 Second Interval Ten-Year lnservice Inspection Program Plan 111 JP2 Third Interval Ten-Year lnservice Inspection Program Plan <II IP2 Fourth Interval Ten-Year lnservice Inspection Program Plan "' I P2 First Ten-Year Containment lnservice Inspection Program Plan

, ......... -:-::::::-Entergy PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No.4 Page 17 of69

  • IP2 Second Ten-Year Containment lnservice 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-ISl-IP2-002. 1.6 lnservice Inspection Boundary Development 10 CFR 50.55(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 inservice inspection {ISi) requirements of 1 O CFR 50.55a to the systems and components installed at IP2, ISi class designations and boundaries have been defined and established. Taking into consideration the fact that the Code of Federal Regulations (CFR) does not define components identified for Class 2 or 3 designations, the NRG issued Regulatory Guide 1.26. Revision 2 of Regulato!Y Guide 1.26, dated June 1975, provided the Initial guidance for determining component2 classification. Revision 4 of Regulatory Guide 1.26, dated March 2007, provides the current guidance for classification of components. The guidance presented in these regulatory guides, as appropriate, was/is used In establishing component classification and boundaries. In those instances where the guidance conflicted with IP2 design or licensing basis, the IP2 design or licensing basis was/is used. ISi Class boundaries designating Quality Group A, B, C, (Class 1, 2, 3), MC, & CC piping, components, and structures are controlled and depicted on the ISi drawings listed in ISl-IP2-002. Welds, components and their supports that are subject to inservice inspection are shown on lnservice Inspection Isometric Drawings that can be obtained from Entergy's Configuration Control Management system. Pursuant to 10 CFR 50.55a, the inservice inspection requirements of ASME Section XI have been assigned to these components within the constraints of existing plant design and the guidance of Regulatory Guide 1.26. 1.6.1 ISi Boundaries and Classification For ISi Class 1 component(s) (Quality Group A), the requirements of Subsection IWB, Code Case N-722-1, Code Case N-729-1 and Code Case N-770-1 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). The P&IDs are marked up with triangular shaped "flags" which include alpha characters designating Quality Group A, B, C, MC. CC, or blank for non-nuclear safety class. The blank flag has no letter symbol and is designated with a completely filled-in triangular shape in black. -Component a vessel, concrete containment. pump, valve, storage tank. piping system, or core support slruciure (IWA-9000).

--::==-Entergy PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No.4 Page 18 of69 Classification boundary breaks (Quality Group A, B, C, or MC) at a component within the system or between systems shall include the component at the higher classification. A weld adjoining a higher class component to a component of lower classification shall be designated at the lower classification. SEP-ISl-IP2-002 provides a list of applicable ISi and Cll drawings for this program. Copies of these drawings are available through Entergy's Configuration Control Management System.

  • 1.6.2 IWEllWL 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 (fWE) 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 boundaiy are: e Dome finer 4' Wallllner e Basemat liner o Penetration sleeves o Personnel air lock o Equipment access hatch/personnel lock a 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 10 CFR 50.55a, 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
  • Concrete basemat

---Entergy PROGRAM SECTION No. SEP..fSl-f P2-001 Revision No.4 Page 19 of69 ISi Class CC containment components shall be inspected per the requirements of ASME Section XI, Subsection lWL Table IWL-2500-1 as modified by 10 CFR 50.55a, Code Cases, Technical Positions. and Relief Requests approved by the NRC. The IP2 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 (CH} Drawings The Cll 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 Cll Drawings is contained in SEP-ISl-IP2-002. 1.6.4 Piping Penetrating Containment Boundaries 1.6.4.1 Quatity Group A, B, and C Piping and Components Piping and components that penetrate containment, including their welded attachments, that are Quality Group A, 8, 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. 4 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 are part of the MC designation for !WE components.

  • 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. e Repair/Replacement shall be in accordance with the requirements of IWA-4000 and the Indian Point design specification and ihe construction code.

--=-Entergy PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No.4 Page 20 of69 "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 Bv 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 f P2 Improved Technical Specifications (JTS), 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. 816.20 will be examined in accordance with the requirements of ITS Section 5.5. 7. 1.7.2 System Pressure Tests for Class 1, 2, and 3 components will be scheduled and controlled in accordance with IP2 site procedures. 1.7.3 Inspection and Testing of Snubbers will be scheduled and controlled in accordance with IP2 site procedures. 1.7.4 [nservice Testing of Pumps and Valves will be performed and controlled in accordance with IP2 site procedures. 1. 7 .5 The ASME Section XI Repair/Replacement Program will be implemented and maintained in accordance with site procedures. 1.8 Augmented lnsggction Programs Augmented examinations are those that are outside the scope of 10 CFR 50.55a(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 10 CFR 50.55a, 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. The process of implementing changes to augmented examination. requirements and schedules, resulting from commitments to the NRC, may not utilize the provisions of 1 O CFR 50.55a(a)(z), or (g)(S)(iii) or {iv); rather, changes are required to be evaluated using the 10 CFR 50.59 screening/review processes. 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 5.5.5 of the ITS and Section 5.1.2.5.2 of 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 IP2; however, the regulatory guide is used for guidance in establishing a basis for the examination.

---=-Entergy PROGRAM SECTION No. SEP-lS8-IP2-001 Revision NoA Page 21 of69 Source Document: Technical Specification 5.5.5 and UFSAR Section 5.1.2.5.2. Commitment No.: None. Associated Documents:

  • NUREG-1431, "Standard Technical Specifications -Westinghouse Plants". I? Westinghouse WCAP-15666, "Extension of Reactor Coolant Pump Motor Flywheel Examination". Purpose: Reactor coolant pump (RCP} motor flywheels are examined due to a concern about high-energy missiles inside containment that could potentially damage* and cause the simultaneous failure of multiple trains of multiple re!ated systems. Scope: The scope includes the examination of all four RCP upper flywheels. Method: Surveillance of the primary coolant pump flywheels shall consist of an ultrasonic examination of the upper flywheels. Industry Code or Standards: ASME Section XI, 2007 Edition through 2008 Addenda. Frequency: Survemance of the primary coolant pump flywheels shall consist of a 100% volumetric inspection of each upper flywheel each 20 years. Acceptance Criteria or Standard: Any flaws detected during examination shall be forwarded to Entergy Engineering for resolution. Regulatory Basis: Technical Specification 5.5.5 defines the scope and frequency of the required examinations. Even though there is no longer a commitment to Regulatory Guide 1.14, the basis for augmented examination of each reactor coolant pump flywheel is Regulatory Guide 1.14. Revision 1, August 1975. Reporting Requirements: Any flaws detected during examination shall be forwarded to Entergy Engineering for resolution. 1.8.2 NEI Initiatives -Materials Reliabillty Program (MRP-146 Revision 1) for Management of Thermal Fatigue in Normally Stagnant Non*lsoJable Reactor Coolant System Branch Lines EPRI has developed a program titled "Management of Thermal Fatigue in Normally Stagnant NonQlsolable Reactor Coolant System Branch Lines"(MRP-146) guideline dated June 2005 with NEI 03-08 "needed" elements. The objective --'

--==-Entergy PROGRAM SECTION No. SEP-ISl*IP2-00::1 Revision No.4 Page22 of69 of this guideline is to provide a common industry approach for assessing the potential for thermal fatigue cracking in normally stagnant non-isolable RCS branch piping. Supplemental guidance (MRP-146S, 1018330) was released as a nuclear QA product in January 2009. MRP-146 Rev. 1 supersedes MRP-146 Rev. O in its entirety and supersedes most elements of MRP-146S including the "needed" actions as described In that document. Implementation of MRP-146 Rev. 1 was completed during 2012 refueling outage. Source Document: "' NRC Bulletin 86-08, <<Thermal Stresses in Piping Connected to Reactor Coolant Systems". o Management of Thermal Fatigue in Normally Stagnant Non*lsolable Reactor Coolant System Branch Lines"(MRP-146} guideline dated June 2005. o Management of Thermal Fatigue in Normally Stagnant Non-lsolable Reactor Coolant System Branch Lines -Supplemental Guidance" (MRP-1468). Commitment No.: Industry Commitment Associated Documents: IP2 calculation IP-CALC-07-00088. _ Purpose: Plan and implement a program to provide continuing assurance that unisolable sections of all piping connected to the RCS will not be subjected to combined cyclic and static thermal and other stresses that could cause fatigue failure during the remaining life of the unit. Scope: In accordance with MRP-146 Rev. 1, guidance has been provided to inspect Reactor Coolant System Branch Lines. The following have been identified for examination: MRP-146 Rev 1 {and 1465) H Configuration line line 96, 3 inches Normal Charging line into cold leg 21, has a MRP-146 Rev 1 {and 1468) requirement of 100% volumetric and visual examinations. IP2 has one weld, 96-2 that is classified as an H charging configuration line and is selected for examination under the MRP-146 Rev 1 (and 1468) every refueling outage. The selection of this weld for examination meets the requirements of Augmented Program MRP 146 Rev 1(and 1468) H model configuration Examination Requirements. 146 Rev 1 (and 1465) DH Configuration Une Line 82, 22 intermediate leg 2 inches drain line, Line 83, 23 intermediate leg 2 inches drain line and 84, 24 leg 2 inches drain line have a MRP-146 Rev 1 (and 146S) requirement of 100% volumetric and visual examinations. IP2 has three welds, 824, 834 and 84-4 that are classified as

Entergy PROGRAM SECTION No. SEP-ISHP2-001 Revision No.4 Page 23 of69 DH drain configuration lines, and are selected for examination under the MRP-146 Rev 1 (and 146S) every other refueling outage. The selection of these welds for examination meets the requirements of Augmented Program MRP 146 Rev 1{and 1468) DH model configuration Examination Requirements. Method: Subject piping segments shall be visual and ultrasonically examined, as required. Industry Code or Standards: MRP-146, Rev. 1, and MRP-1468. Frequency: Reference Attachment 3, Table 2.1-3. Acceptance Criteria or Standard: Flaws detected during examination shall be evaluated by comparing the examination results to the acceptance standards established in ASME Section XI, Subsection IWC. Regulatory Basis: NRC Bulletin 88-08. Reporting Requirements: Any flaws detected during examination shall be forwarded to Entergy Engineering for resolution. 1.8.3 Examination of Socket Welds license Renewal Commitment#46 (LO-LAR-2011-0174 CA 65) requires five volumetric weld metal inspections of socket welds be performed periodically during each 10-year ISi interval scheduled as specified by IWB-2412 of the ASME Section XI Code during the period of extended operation. In lieu of volumetric examinations, destructive examinations may be performed, where one destructive examination may be substituted for two volumetric examinations. The small-bore piping socket weld sample is selected from the RI-ISi small bore socket welds population. However it is in addition to ASME B&PV Code Case N-716-1, the only examination that is required on a socket weld by the RI-ISi Program is a VT-2 visual examination each refueling outage with the exception for Item No. R1 .11 which volumetrically examines the base material at the toe of the weld. Source Document: License Renewal Commitment #46. Commitment No.: LO-LAR-2011-0174 CA 65. Associated Documents: LER 10-004-00, SER Related to License Renewal, Dated 08/30/2011 (ML 11201A033). Purpose: As part of License Renewal for effective aging management, the NRC requires a robust inspection program for socket welds. This action is to address concerns based on the operating experience at IP2. The inspection sampling should be statistically significant so that cracking, if present. will be detected prior

.... ---Entergy PROGRAM SECTION No. SEP*ISl-IP2-001 Revision No.4 Page 24 of69 to leakage of the component. A sample of 25 welds was determined to be an adequate sample size. Scope: Twenty-five (25) socket welds selected from the most susceptible and risk-significant welds scheduled as specified by IWB-2412 of the ASME Section XI Code. The small-bore piping socket weld sample is selected from the RI-ISi small bore socket welds population. The current RI-ISi program is based upon Code Case N-716-1. The population selected will include all high safety significant socket welds with a postulated damage mechanism. Additionally, high safety significant socket welds without a postulated damage mechanism will be selected to meet the 25 total requirement, that are located on the reactor coolant pressure boundary inside containment before the first isolation valve. Pipe breaks in these locations are not isolable and were assigned the highest conditional core damage probability in the Code Case N-716-1 analysis. Method: Volumetric weld metal inspections of socket welds shall be performed. In lieu of volumetric examinations, destructive examinations may be performed, where one destructive examination may be substituted for two volumetric examinations.

  • Industry Codes or Standards: MRP-350-Nondestructive Evaluation: Examination of Small Bore Socket Welds for Vibration and Thermal Fatigue Frequency: The inspection sample shall be examined during each of the ISi 10-year intervals of extended operation. Acceptance Criteria or Standard: The sample welds shall be free of cracking. If cracking is detected during the examinations, there will be an extent of condition review 1o evaluate the inspection sampling size to ensure that it is adequate to identify cracking that could occur at other locations. Regulatory Basis: SER Related to License Renewal, Dated 08/30/2011 ML 11201A033). Reporting Requirements: Any flaws detected during examination shall be foiwarded to Entergy Engineering for resolution. 1.8.4 Class 1 pressure retaining welds containing Alloy 600/82/182 in accordance with Code Case N" 722-1, "Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/821182 Materials",Section XI Division 1 with conditions specified in 10 CFR 50.55a(g}(6)(ii)(E)(1} through (4). Source Document: ASME Code Case N-722-1, "Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials". Commitment No.: None Associated Documents: 10 CFR 50.55a(g)(6)(ii)(E)(1) through ( 4 ). Purpose: Identification of the presence of pressure boundary leakage.

.-Entergy* PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No.4 Page25 of69 Scope: Code Case N-722-1, Items 815.90 and 815.95, IP2 has four reactor vessel hot leg connections that will be visually inspected each refueling outage and four reactor vessel cold leg connections that will be visually examined each inspection interval. Method: o Direct VE of the bare metal surface, or alternatively, I) VE performed with the insulation In place using remote visual examination equipment that provides resolution of the component metal surface equivalent to a bare metal direct VE. Industry Code or Standards: ASME Section Xl 2007 Edition through 2008 Addenda. Frequency; Every other refueling outage in accordance with Code Case N-722-1. Acceptance Criteria or Standard: IWB-3522, absence of evidence of pressure leakage. Regulatory !Basis: 10 CFR 50.55a(g)(6)(ii}(E). Reporting Requirements: Evidence of pressure leakage shall be reported immediately to Entergy Engineering. The results of the examination shall be reported in the outage inspection summary report. 1.8.5 Reactor vessel upper head penetrations in accordance with Code Case "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 10 CFR 50.55a(g)(6)(ii)(D)(1) through {6). Source Document: ASME CC N-729-1, "Alternative Examination Requirements for PWR Reactor Vessel Upper Heads With Nozzles Havlng Pressure-Retaining Partial-Penetration Welds,Section XI, Division 1" (Approval Date: March 282006), with the conditions in 10 CFR 50.55a(g){6)(ii)(D). Commitment No.: None Associated Documents: 10 CFR 50.55a{g}(6){ii)(0)(1) through (6). Purpose: Assess the present of PWSCC in reactor vessel upper heads with nozzles install with pressure-retaining partial-penetration welds. Scope: Visual Examination -Outer surface of the Upper Reactor Vessel Head defined by Figure 1 of Code Case N-729-1.Volumetric/Surface Examinations -Partial penetration welds of the Nozzles and the Upper Reactor Vessel Head.

PROGRAM SECTION No. SEP*ISHP2-001 Revision No.4 Page26 of69 Note: Appendix I, Analysis Procedure for Alternative Examination Area or Volume Definition, of ASME CC N-729-1 must not be implemented without prior NRC approval. [10 CFR 50.55a(g)(6)(ii)(D)(6)}. Method: Visual examination areas defined by Figure 1 on CC N-729-1 of the outer surface of the Reactor Vessel Head. Volumetric and/or surface examinations of essenUally 100 percent of the required volume or equivalent surface examination of essentially 100 percent of the subject J-groove welds. A demonstrated volumetric or surface leak path assessment through all J-groove welds must be performed. If a surface examination is being substituted for a volumetric examination on a portion of a penetration nozzle that is below the toe of the J-groove weld, the surface examination must be of the inside and outside wetted surface of the penetration nozzle not examined volumetrically. [10 CFR 50.55a(g)(6)(ii)(D}(3)]. Industry Code or Standards: ASME Section XI, 2007 Edition through 2008 Addenda as supplemented by 10 CFR 50.55a(g)(6)(ii)(D)(4) restricts the use of Section XI, Appendix VIII requirements to ASME Section XI, 2004 Edition with no Addenda for Code Case N-729-1. [10 CFR 50.55a(g)(6)(ii)(D)(4)]. Frequency: The examinations listed in Table 1 of CC N-729-1 shall be performed completely, once, as a baseline examination. These examinations shall include all nozzles. lnservice examination frequencies are based on calculated RIY (Reinspection Years calculation compliant with paragraph -2410 of CC N-729-1) and the result of previous examinations. Per 10 CFR 50.55a(g)(6)(ii)(D}(5), ifflaws attributed to PWSCC have been identified, whether acceptable or not for continued service under Paragraphs -3130 or-3140 of ASME CC N-729-1, the re-inspection interval must be each refueling outage instead of the re-inspection intervals required by Table 1, Note (8), of ASME Code Case N-729-1. Note 9 of the CC shall not be implemented. [1 o CFR 0.55a(g)(6){il)(D)(2)]. Acceptance Criteria or Standard: Acceptance shall be as specified by code case paragraph-3130 and-3140. Additionally, if flaws attributed to PWSCC have been identified, whether acceptable or not for continued seivice under Paragraphs -3130 or-'3140 of ASME Code Case N-729-1, the re-inspection interval must be each refueling outage instead of the re-inspection intervals required by Table 1, Note (8), of ASME Code Case N-729-1. [50.55a(g)(6)(ii)(D)(5)]. Regulatory Basis: 1 O CFR 50.55a{g)(6)(ll)(D) "Augmented ISi requirements: Reactor vessel head inspections". Reporting Requirements: Report of any indication of PWSCC flaws to Entergy Engineering immediately. The results of these examinations shall be included in the outage inservice Inspection summary report.

-=---Entergy PROGRAM SECTION No. SEP-ISl-IP2*001 Revision No.4 Page27 of69 1.8.S Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS N060B2 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities in accordance with Code Case N-770-1, "Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities",Section XI, Division 1," in accordance with the requirements in 10 CFR 50.55a{g)(6}(ii}(F)( 1) through (10). Note: License Renewal commitment LQ-LAR-2011-0174 CA37 is tracked and monitored in accordance with the Coda Case 770-1 examination requirements, and augmented existing tSl inspections as appropriate. Source Document: ASME Code Case N;,.770-1, "Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of listed Mitigation ActivitiesSection XI, Division 1. 10 CFR 50.55a(g)(6)(ii)(F) "Augmented ISi requirements: Examination Requirements for Class 1 Piping and Nozzle Oissimilar*Metal Butt Welds". Commitment No.: None Associated Documents: 1 O CFR 50.55a(g}(6)(ii)(F}. Purpose: Detection or unacceptable growth of known PWSCC Cracking. Scope: IP2 has four reactor vessel hot leg connections that will be inspected volumetrically every 5 years and visually each refueling outage, and four reactor vessel cold leg connections that will be inspected volumetrically every inspection period not to exceed seven years and visually once per inspection interval. Method: Ultrasonic Examination procedures and personnel qualification in accordance with Appendix VIII of ASME Section XI. Industry Code or Standards: ASME Section XI, 2007 Edition through 2008 Addenda. Frequency: IP2 has four reactor vessel hot leg connections that wilf be inspected volumetrically every 5 years and visually each refueling outage, and four reactor vessel cold leg connections that will be inspected volumetrically every second inspection period not to exceed seven years and visualty once per inspection interval. Acceptance Criteria or Standard: Code Case paragraphs -3130 and -3140. IWB-3514 of the ASME Section XI, 2007 Edition through 2008 Addenda as supplemented by Nonmandatory Appendix Q, if applicable weld overlays are applied. Regulatory Basis: 10 CFR 50.55a{g)(6)(ii)(F) "Augmented ISi requirements: Examination requirements for Class 1 piping and nozzle dissimilar-metal butt welds".

Entergy PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No.4 Page28of69 Reporting Requirements: Report of any indication of PWSCC flaws to Entergy Engineering immediately. The results of these examinations shall be Included in the inservfce inspection summary report. For any mitigated weld whose volumetric examination detects growth of existing flaws in the required examination volume that exceed the previous IWB-3600 flaw evaluations or new flaws, a report summarizing the evaluation, along with inputs, methodologies. assumptions, and causes of the new flaw or flaw growth is to be provided to the NRC prior to the weld being placed in service other than modes 5 or 6. [10 CFR 50.55a(g)(6)(1i)(F)(6)]. 1.9 Administrative Controls 1.9.1 This program ls 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 .iiems 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-2411 and IWF-2410. 1.9.4 Organizational and of responsibilities for the management and implementation of the 1$i 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 0lnformation Only. PCNs are not required to be provided to the NRC. 1.9.6 The initial lSI Program Plan, revisions, anc;t PCNs are subject to review by the Authorized Nuclear lnservice Inspector (ANll). 1.10 IODEAL Data-Management Program IP2 ISi Components and their examination schedules are developed with the aid of the IODEAL 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 controlllng entity for managing and implementing the ISi program. The lnservice Inspection Data Management software is comprised of a series of program modules assembled in a comprehensive software package entitled the !ddeal Software Suite. This software suite is NETWORK based within the Entergy system and is accessible by any computer within Entergy. The lddeal Software Suite is a quality level 8 software. It is the Controlled copy of the ISi Schedule. The software has limited access to protect the contents of the databases. Access to the software is limited through the use of a user defined password controlled via Central Engineering Procedure CEP-COS-100. The ScheduleWorks

E11tergy PROGRAM SECTION NO. SEP-ISl-IP2-001 Revision No.4 Page29 of69 Module contains the IPEC information necessary to perform ISl/Cll and Augmented Program. Maintenance of the Module is controlled via Central Engineering Procedure CEP-COS-110. All changes to data in the IPEC ISl/Cll Database must be made in accordance with CEP-COS-110. 1.11 Adoption and Use of ASME Section XI Code Cases In accordance with ASME Section XI, IWA-2441(a}, Code Cases to be used during a preservice or inservice inspection shall be identified in the lnservice Inspection Plan. ASME Section XI Code Cases adopted for ISi and NOE activities are listed in Tables 1.11-1 and 1.11-2. In addition, other Code Cases as approved in USNRC Regulatoiy Guide 1.147, latest revision, may be used as required. Code Cases applicable to Nondestructive Examination (NOE), Repair/Replacement (R/R) Activities, Pressure Testing and Flaw Evaluation are addressed in their respective program documents and are not inciuded in this Program. The use of Code Cases Is in accordance with ASME Section XI, IWA-2440, 10 CFR 50.55a, and USNRC Regulatory Guide 1.147. As permitted by ASME Section XI, USNRC Regulatory Guide 1.147, and 10 CFR 50.55a, 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 Gulde 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 Regulatoiy Guide are also incorporated. Table 1.11-1 identifies the Code Cases that have been approved for use in USNRC Regulatory Guide 1.147 and are incorporated into the ISi program. 1.11.2 Adoption of Code Cases Not Approved in USNRC 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 Regulatoiy Guide 1.147. Use of such Code Cases may be requested in the form of a "Request for Alternative" in accordance . with 10 CFR 50.55a(a)(z). Code Cases that have been requested in accordance with 10 CFR 50.55a{a)(z) may not be used until NRC approval has been obtained. Section 1.13 Identifies the Code Cases that have been requested in accordance with 10 CFR 50.55a(a)(z). 1.11.3 Adoption of Code Cases Mandated by 10 CFR 50.55a Code Cases required by rule in 1 O CFR 50.55a are incorporated into the ISi Program and implemented at the specified schedule. Code Cases currently required by 10 CFR 50.55a 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 inspection lntel'Val that are subsequently annulled by ASME may be used for the remainder of the inspection interval.

Entergy PROGRAM SECTION No. SEP-ISl-IP2.001 Revision No-4 Page 30 of69 N-526 N-532-5 N-586*1 N-686-1 N-716-1 N-731 N-735 N-747 N-765 1.11.5 Code Case Revisions ao1:::iot1on of a Code requires use of revision of Code in Regulatory Guide 1.147. However, if an adopted Case is .. "'"""""wi and approved by the NRC, then the earlier or later revision may used. An exception to provision would the inclusion a limitation or condition on the use the Code Case which is necessary to enhance 1.11-1 from Regulatory 1.147 Alternative Requirements for Successive Inspections of Class 1 and 2 VesselsSection XI, Division 1 Repair/Replacement Activity Documentation Requirements and lnservice Inspection Summary Report Preparation and Submission Section XI, Division 1 Alternative Additional Examination Requirements for Classes 1, 2, and 3 Piping, Components, and SupportsSection XI, Division 1 Alternative Requirements for Inner Radius Examination of Class 1 Reactor Vessel NozzlesSection XI, DMslon 1 Conditions Use: In lieu of a UT licensees may perform a VT-1 examination in accordance with the code of record for the lnservice Inspection Program utilizing the allowable flaw length criteria ofTable IWB-3512-1 with limiting assumptions on the flaw aspect ratio. 2010 Edition 2011 Addenda 2010 Edttion 2007 Edition 2008 Addenda 2013 Edition Alternative Requirements for Visual Examinations VT-1. VT-2, and VT-3 2004 Edition Section XI. Division 1 Alternative Piping Classification and Examination RequirementsSection XI, 2013 Edition Division 1 Alternative Class 1 System Leakage Test Pressure Requirements Section 2013 Edition XI, Division 1 Alternative to Inspection Interval Scheduling Requirements of IWA-2430 Section XI, Division 1 Edition Edition 2008 Addenda

Entergy PROGRAM SECTION No. §EP-jSl*IP2-Q01 Revision No.4 Page 31 of 69

  • Table 1.11-2. Code Cases Roouired bv 1o:cfR 50.55a* Code Case " Number: Title Notes .. Additional Examinations for PWR Pressure Retaining Welds Conditions specified if! paragraphs N-722-1 in Class 1 Components Fabricated With Alloy 600/821182 (g)(6}(ii}(E)(2) through (4) of 10 CFR Materials, Sedfon XI, Division 1 50. 55a. Implemented in the Pressure Test Program Altemative Examination Requirements for PWR Reactor Conditions specified In paragraphs N-729-1 Vessel Upper Heads With Nozzles Having Pressure-(g}(6){ii)(D)(2) through (6) of 10 CFR Retaining Partial-Penetration Welds,Section XI, Division 1 50.55a Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated with UNS N06082 or UNS W86182 Weld Conditions specified in paragraphs N-770-1 Filler Material With or Without Application of listed Mitigation (g}(6)(ii}{F)(2) through (10) of 10 Activities,Section XI, Division 1 CFR 50.55a 1.12 Technical Positions Technical Positions are created for areas where the Code does not provide dear direction or areas where regulation requires more attention to a specific area. Technical Position papers used as bases for the ISi program are listed in Table 1.12*1. Table Technical Position Pa ers Document Number Title Notes None at this time Entergy 1.13 Relief Beguests PROGRAM SECTIONJ No. §EP-iSl-IP2*001 Revision No.4 Page 32 of69 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 10 CFR 50.55a rule, or to use provisions from Editions or Addenda of Section Xf not approved by the NRC as referenced in 10 CFR 50.55a(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 1 O CFR 50.55a. 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 1 O CFR 50.55a(a)(z) and (g)(5). The applicable Entergy submittal and NRC Safety Evaluation Report (SER) correspondence numbers are also included for each request. Note: Requests associated with the ISi program only are listed in Table 1.13-1. Requests applicable to Nondestructive Examination (NDE), Repair/Replacement (RJR) Activities, Pressure Testing and Flaw Evaluation are identified in their respective program documents. 11.13.1 Request for Alternatives When seeking an alternative to the rules contained in 10 CFR 50.55a(b) through (h), the request is submitted under the provision of 10 CFR 50.55a(z). Once approved by the Director, Office of Nuclear Reactor Regulation, the alternative may be incorporated into the ISi program. These types of requests are typically used to request use of Code Cases, Code Edition, or Addenda not yet approved by 1he NRC. Request for Alternatives must be approved by the NRC prior to their Implementation or use. Within the provisions of 10 CFR 50.55a(z) there are two specific methods of submittal: 1.13.1.1 10 CFR 50.55a(a)(.z)(1): Acceptable level of quality and safety. The proposed alternative would provide an acceptable level of quality and safety. 1.13.1.2 10 CFR 50.55a(a)(z)(2): Hardship without a compensating increase < in quality and safety. Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase ln the level of quality and safety. 1.13.2 Relief Request Required Due to Impracticality 1 O CFR 50.55{a)(g)(5)(iii) allows relief to be requested in instances when IP2 has determined conformance with a Code requirement is impractical, e.g. limited examination coverage. Under 10 CFR 50.55(a){g}(5)0v), relief requests for examination impracticalities must be submitted for NRC review and approval not later than 12 months after the expiration of the initial or subsequent 120-month inspection interval for which relief is sought rn cases where the ASME Section XI requirements for inservice inspection are considered impractical, IP2 will notify the NRC and submit information to support the determination, as required by 1 O CFR 50.55a(g}(5). The submittal of this information will be referred to as a Request for Relief.

Entergy PROGRAM SECTION No. SEP*lS!-IP2*001 Revision No.4 Page 33 of 69 1.13.3 Requests to use Later Edition and Addenda of ASME Section XI On July 28, 2004, the NRC published Regulator1' Issue Summary (RlS) 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 10 CFR 50.55a(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.

Entergy Table 1.13-1 Fifth Interval Relief Requests Relief Request Relief Request Description Entergy Correspondence IP2*1Sl-RR-01 Pressurizer shell to head, circumferential and longitudinal NL-15-138 welds. ASME Cat B-B, Ref. IWB-2500. IP2-ISl-RR*02 Proposed Alternative Examination Area for Code Case N-72B-NL-15-139 1. IP2*1Sl*RR*03 Proposed Alternative to Use of Weld Reference System NL-15-140 PROGRAM SECTION No. SEP-JSl-IP2-001 Revision No. 4 Page 34 of69 NRC SER Correspondence Modified ( NIA NIA NIA 1.14 Calibration Blocks PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 35 of69 A detailed list of all ISi calibration blocks to be employed during the fifth inspection interval is provided in SEP-ISl-IP2-002. 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 ASME Code Section XI 2007 Edition through 2008 Addenda, IWA-2200(c), 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 shall be submitted per paragraph 1.13.2. ASME Section XI examinations should meet the examination coverage criteria established in ASME Code Section XI, 2007 Edition through 2008 Addenda, IWA-2200(c). Therefore, the guidance Included in ASME Code Section XI 2007 Edition through 2008 Addenda IWA*2200{c) shall be followed by Entergy IP2 when determining whether to prepare a relief request or apply the criteria of ASME Code Section XI, 2007 Edition through 2008 Addenda, IWA-220{c) 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.

SECTION 2.0 PROGRAM SECTION No. SEP-1Sl-IP2-001 Revision No. 4 Page 36 of69 APPLICATION CRITERIA AND CODE COMPLIANCE PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 37 of69 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, 2007 Edition through 2008 Addenda for the IP2, Fifth Ten-Year Interval ISi Program Plan. The application and distribution of examinations for this inspection interval is based upon utilizing Inspection program defined by paragraphs IWB-2411, IWC-2411, IWD-2411, IWE-2411 IWF-2410 and IWL-2400 of Section XI. The results of this application are summarized by ASME Category and Item Number and are contained within the IP2 Code Category Summary Table contained in this document. This table only contains those ASME Item Numbers that are relevant to IP2. 2.1.1 Examination Category B-A -Pressure Retaining Welds in Reactor Vessel Reactor vessel examinations were scheduled to meet the 2007 Edition through 2008 Addenda of the ASME Code,Section XI as required by 10 CFR 50.55a. Article IWB-2420 in the 2007 Edition through 2008 Addenda of ASME Code, Section Xl 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 (3) specifies at least 50% of the Shell to Flange Welds will be examined by the end of the firsl inspection period of the first inspection interval. In successive inspection intervals, Note 5 allows deferral of the Shell to Flanges provided conditions in Note (5) are satisfied. The conditions of Note (5) are satisfied. The selection of these welds for examination meets the requirements of Examination Category B-A Examination Requirements in the 2007 Edition through 2008 Addenda of Section XI. 2.1.2 Examination Category B-B

  • Pressure Retaining Welds in Vessels other Than Reactor Vessels The 2007 Edition through 2008 Addenda of Section XI, Examination Category 8-8 requires the pressurizer and primary side of steam generators (S/G) and regenerative heat exchangers 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. Relief Request IP2-ISl-RR-01 was requested for approval which would allow Welds PZRC5 {82.11) & PZRL4 (82.12) to be visually examined cvr-2) after each refueling outage in lieu of the Code required volumetric examination. This will be tracked via Pressure Testing Procedure PT-R75. Therefore, only one of the two Shell to Head Welds and Longitudinal Welds are selected for 50%. STEAM GENERATORS PROGRAM SECTION No. SEP*ISl-IP2-001 Revision No. 4 Page 38 of69 IP2 has four steam generators. Table JWB-2500-1, Category B-8, Note (1) allows the examination to be limited to one vessel among a group of vessels performing a similar function or 25% for IP2. 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. REGENERATIVE HEAT EXCHANGERS Section XI requires volumetric examination of all Regenerative Heat Exchanger Head to Shell and Tubesheet to Shell Welds. ASME Code Case N-706-1 approved through USNRC Regulatory Guide* 1.147, will be implemented, and therefore all B2.60 and 92.80 welds will be visually examined {VT-2) after each refueling outage in lieu of the Code required volumetric examination. This will be tracked via Pressure Testing Procedure PT-R75. Implementation of ASME Code Case N-706-1 requires the Owner to evaluate industry experience to determine which heat exchanger designs or configurations have leaked. If any leakage is detected, it shall be corrected in accordance with IWA-4000. Use of Code Case N-706-1 shall be discontinued for the Regenerative Heat Exchangers and others of the same design . or configuration. The affected Regenerative Heat Exchangers and others of the same design or configuraUon shall be examined in accordance with IWB-2500 or IWC-2500, as applicable. Therefore, the selection of these welds for examination meets the requirements of Examination Category 8-B Examination Requirements in the 2007 Edition through 2008 Addenda of Section XI and ASME Code Case N-706-1. 2.1.3 Examination Category B-0 -Full Penetration Welded Nozzles In Vessels This category applies to the reactor vessel, pressurizer, steam generators and regenerative heat exchangers. 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, Categoiy B-D. Note (3) allows partial deferral if the examinations are conducted from Inside the nozzle bore 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 inspection interval. PRESSURIZER The 2007 Edition through 2008 Addenda no longer has a requirement to examine Pressurizer Nozzle Inside Radius Section. However, 10 CFR 50.55a(b)(2)(xxi)(A) requires utilities to either apply the Volumetric Examination of the 1998 Edition when using the 1999 Addenda through the latest edition and addenda incorporated by reference in paragraph (a}(1)(ii) of this section or allows a visual examination with magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 39 of69 allowable flaw length criteria In Table IWB-3512-1, 1997 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)( 1 )(ii) of this section, with :a limiting assumption on the flaw aspect ratio {i.e., a/1=0.5), may be performed instead of an ultrasonic examination. Pressurizer Nozzle Inside Radius Sections will be examined volumetrically or with an enhanced visual as required by 10 CFR 50.55a{b)(2)(xxi}(A) depending on which method is determined to be prudent to IP2. These*examinations are identified in the ISi Program as Examination Category B-0, Item Number 83.120 in accordance with the 1998 Edition of ASME Section XL IP2 Pressurizer nozzles are integrally cast and therefore, contain no Item Number 83.110, nozzle to vessel welds. STEAM GENERA TOR The 2007 Edition through 2008 Addenda no longer has a requirement to examine Stearn Generator Nozzle Inside Radius Section. However, 1 O CFR 50.55a(b)(2)(xx:i)(A} requires utilities to either apply the Volumetric Examination of 1998 Edition when using the 1999 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1)(ii)of his section or allows .a visual examination with magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the allowable flaw length criteria in Table lWB-3512-1, 1997 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1 )(ii) of this section, with a limiting assumption on the flaw aspect ratio (i.e., a/1=0.5). may be performed instead of an ultrasonic examination. Steam Generator Nozzle Inside Radius Sections will be examined volumetrically or with an enhanced visual as required by 10 CFR 50.55a(b)(2)(xxi)(A) depending on which method is determined to be prudent to IP2. These examinations are identified in the ISi Program as Examination Category B-0, Item Number 83.140 in accordance with the 1998 Edition of ASME Section. IP2 Steam Generator nozzles are integrally cast and therefore, contain no Item Number B3.130, nozzle to vessel welds. REGENERA TlVE HEAT EXCHANGERS Section XI requires volumetric examination of all Regenerative Heat Exchanger Nozzle to Vessel Welds and Nozzle Inside Radius Sections. ASME Code Case N-706-1 approved through USNRC Regulatory Guide 1.147, will be implemented, therefore all 83.150 nozzle to vessel welds and B3.160 nozzle inside radius sections will be visually examined (VT*2) after each refueling outage in lieu of the Code required volumetric examination. This will be tracked via Pressure Testing Procedure PT-R75. Implementation of ASME Code Case N-706-1 requires the Owner to evaluate industry experience to determine which heat exchanger designs or configurations have leaked. If any leakage is detected, it shall be corrected in accordance with IWA-4000. Use of Code Case N-706-1 shall be discontinued for the Regenerative Heat Exchangers and others of the same design or configuration. The affected Regenerative Heat Exchangers and others of the same design or configuration shall be examined in accordance with IWB-2500 or IWC-2500, as applicable.

PROGRAM SECTION No. $EP-ISl-!P2-001 Revision No. 4 Page40 of69 The selection of these welds and inner radius sections for examination meets the requirements of Examination Category 8-D Examination Requirements in the 2007 Edition through 2008 Addenda of Section XI as modified by ASME Code Case N-706-1 and 10 CFR 50.55a(b){2)(xxl)(A). 2.1 Examination Category B-F -Pressure Retaining Dissimilar Metal Welds in Vessel Nozzles This category addresses Nozzle to Safe End Welds. Risk Informed Jnservice Inspection utilizing ASME Code Case N-716-1 (approved through USN RC Regulatory Guide 1.14 7) will be implemented for Examination Category B"F requirements. Examination. of these dissimilar metal welds will not be covered under Examination Category B-F, but under Examinatibn Category A Table 2.1-3, with the exception of eight (8) Reactor Vessel Nozzle to Safe End Butt Welds fabricated with UNS N060802 or UNS W86182 Weld Filler Material. The eight (8) Reactor Vessel Nozzle to Safe End Butt Welds Will be examined utilizing ASME Code Case N-770-1. 2.1.5 Examination Category B-0°1 *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 2007 Edition through 2008 Addenda of Section XI. Examination of the Reactor Vessel Bolting will be performed in the first and third periods. For volumetric of reactor coolant pump studs, one of four sets of reactor coolant pump studs is selected for volumetric examination. For the visual examination of pump bolting, one of the reactor coolant pumps will be examined only if disassembled. This is the same requirement as for Examination Category B-L-2 and will be met during the maintenance or repair/replacement process. During the first, second and third inspection intervals pump bolting examinations were scheduled by bolt. For the fourth and fifth inspection intervals 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 2007 Edition through 2008 Addenda of Section XI. 2.1.6 Examination Category B-Gm2 "Pressure Retaining Bolting, 2" and Less in Diameter This category includes oonoseal bolting, manway bolting, valve bolting, flange bolting in piping, and reactor coolant pump seal bolting. Examinations will be conducted as required in Table IWS..2500-1 in the 2007 Edition through 2008 Addenda of Section XI. This bolting will only be examined if associated connections are disassembled or bolting is removed.

  • PROGRAM SECTION NO. SEP*ISl-IP2-001 Revision No. 4 Page 41 of69 For components other than piping, bolting examinations will be required only when the component is examined under Examination Category 8-B, B-L-2, or M-2. IP2 has grouped B-G-2 boning in accordance with components examined under Examination Category 8-8, B-L-2, or B-M-2. This grouping is identified in Tables 2.1-1 for piping and Table 4.1-2 for valves. IP2 has 7 sets of conoseal bolting on the Reactor Vessel Closure Head. Examination of bolting is only required if disassembled or bolting is removed. IP2 has four Steam Generators (Vessel Group 1 ), each with a cold leg and a hot leg manway. Examination of bolting is only required if disassembled or bolting is removed. IP2 has sixteen Class 1 piping flanges. These flanges are grouped into five piping flange groups identified in Table 2.1-1. Each group of piping flanges contains bolted connections of similar design, size, function and service. Only one bolted connection from each flange group is required to be examined each Inspection interval, and this examination is only required when a bolted connection is dissembled or bolting is removed. No piping flanges have been selected. For bolting removal involving the repair/replacement process, this requirement will be met during the repair/replacement process.

DWGNo 200684 206685 200713 206714 DWGNo 200687 200689 206691 206693 OWGNo 206687 206689 206691 206693 DWGNo 206731 206732 206733 OWGNo 206711 PROGRAM SECTION No. SEP..JSl-IP2..001 Revision No. 4 Page 42 of69 Table 2.1-1 B-G*2 PIPING FLANGE GROUPINGS Gmuo 1. COMP ID DESCRIPTION 19 F 2 3" Blind Flanqe Boltin!.l {8) 27F 4 3" Blind Flamie Boltint:i {Si 79f 1 3" Blind Flanae Bol!lnc:i !Ell 80F1 3" Blind Flanqe Soltinq (8) Grouo 2 COMP ID DESCRIPTION 41F1 1.5" 21 RCP Flanoe Bo!! {4l 42F1 1.5" 22 RCP FlanQe Bolt (4} 43F 1 1.5" 23 RCP Flanoe Bolt (4} 44F 1 i.5" 24 RCP Flanoe Bolt (4} .. Gm1.11>3 COMP ID DESCRIPTION 41F2 2" Pipe Flanoa Boltint1 (8) 42 F2 2" Pioo Flancie Boliinc.i (8) 43 F2 2" Pioe Flanc:te Boltlna ( 8) 44 F2 2" PiM Flanae Bollino 18) I Group4 .. I COMP ID DESCRIPTION 342 F 1 PZR PCV464 Flanae &lit (8) . 343F1 PZR PCV466 Flanoe Bolt {8} 344F1 PZR PCV4S6 Flanae Bolt {8) Gro1.1p6 COMP ID DESCRIPTION 64F1 2" Blind Flanaa Boltina CS) IP2 has four Reactor Coolant Pumps (Pump Group 1), each pump contains seal housing bolting. Examination of pump bolting is only required if disassembled. Examination of the bolting is only required on one RCP pump seal housing bolted . connection when disassembled or bolting is removed. IP2 has seventeen valves with bolting. The valves have grouped, as required by Examination Category B-M-2, into four Valve Groups identified in Table 2. 1-2. Examination of valve bolting is only required on one valve in each group if or bolting ls removed. third intervals During the first, second and third inspection intervals Steam Generator and Pressurizer manway bolting examinations were also scheduled by bolt For the fourth and fifth inspection intervals these examinations combined to PROGRAM SECTION NO. SEP-JSl-IP2*001 Revision No. 4 Page 43 of69 one summary number for each manway that requires examination of all the bolting of the manway. The selection of these components for examination meets the requirements of Examination Category B-G-2 Examination Requirements in the 2007 Edition through 2008 Addenda of Section XL 2.1.7 Examination Category B-J -Pressure Retaining Welds in Piping Examination Category B-J of the ASME Code Section XI, 2007 Edition through 2008 Addenda requires examination of Class 1 piping welds. Risk Informed lnseivice Inspection utilizing ASME Code Case N-716-1 (approved through USNRC Regulatory Guide 1.147) will be implemented for Examination Category B-J requirements. Examination of these welds will not be covered under Examination Category B-J, but under Examination Category R-A Table 2.1-3. 2.1.8 Examination Category B-K -Welded Attachments For Vessels, Piping, Pumps, And Valves Examination Category B-K of the ASME Code Section XI, 2007 Edition 2006 Addenda requires examination of welded 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. IP2 has one Pressurizer Welded Attachment that is selected for examination. For piping. pumps, and valves, inspection of 10% of the total population of welded attachments is required. Ten Percent (10%) of all piping welded attachments and 10% of all pump welded attachments are selected for examination. IP2 does not have any Class 1 valve welded attachments. The population of welded attachments contained In the ISi program has been evaluated and seven have been identified to be associated with whip restraints. These seven do not meet the criteria of Examination Category 8-K, Note 1 and have been removed from the program. The selection of these welded attachments for examination meets the requirements of Examination Category B-K Examination Requirements in the 2007 Edition through 2008 Addenda of Section XI. 2.1.9 Examination Category B-L-2 -Pump Casings This category involves reactor coolant pumps and requires visual examination of pump casing internal surfaces when disassembled. The reactor coolant pumps are the only Code Class 1 pumps. B-L-2 requires examination of the pump casing Internal surfaces of one pump in each group of pumps pertorming similar functions in the system. However, this examination is only required when a pump is dissembled for maintenance or repair. For pump disassembly involving repair/replacement activities, this requirement will be met during the repair/replacement process.

PROGRAl\fl SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page44 of69 The selection of these components for examination meets the requirements of Examination Category B-L-2 Examination Requirements in the 2007 Edition through 2008 Addenda of Section XI. 2.1.10 Examination Category B0M02 -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. IP2 has grouped these valves based on size, design, manufacturing method, and function into four groups of valves identified in Table 2.1-2. B-M-2 requires examination of the valve body internal surfaces of one valve in each group of valves that are of the same size, constructural design, manµfacturing method, and that performs similar functions in the system. However, this examination is only required when a valve is dissembled for maintenance or repair. No valve body internal surfaces have been selected. For valve disassembly involving repair/replacement activities, this requirement will be met during the repair/replacement process. Table below lists all valves grouped by system, size, and type and subject to examination under B-M-2. Table21-2 B*M*2 VALVE GROUPINGS -Group.1 Drawing Component Size Type Valve System Number Number 206903 351 695A 206904 352 8958 206905 353 89SC 206901 350 8950 206903 351 897A HI Darling Check SIS 206904 352 8978 206905 350 897C 206901 353 8970 Group2 Drawing Component Size Type Valve system Number Numbef 206906 355 838A 206907 206908 358 838C 6 VelanCheck SIS 206910 367 8380 Group3 Drawing Component Size Type Valve System Number Number 206731 PCV464 206732 PCV466 4X6 Crosby Relief RCS 206733 PCV468 I PROGRAM SECTION No. Table2.1-2 VALVE GROUPINGS Group4 Drawing Component Size Type Valve Number Number 206669 10730 '.14 Copes Vulcan Gate ;mesas 10731 Revision No. 4 Page 45 of 69 System RHR The selection or these components for examination meets the requirements of Examination Category 8-M-2 Examination Requirements in the 2007 Edition through 2008 Addenda of Section XL 2.1.11 Examination Category B-N-1

  • Interior of Reactor Vessel These examinations will be conducted each inspection period. This meets the Examination Category S.N-1 Examination Requirements in the 2007 Edition through 2008 Addenda of Section XL 2.1.12 Examination Category B-N-2-Welded Core Support Structures and Attachments to Reactor Vessel These examinations will be scheduled to coincide with the inspection of the reactor vessel. The selection of these welds for examination meets the requirements of Examination Category 8-N-2 Examination Requirements in the 2007 Edition through 2008 Addenda of Section XL 2.1.13 Examination Category BwN--3-Removable Core Support Structures These examinations will be conducted to coincide with the inspection of the reactor vessel. The selection of these welds for examination meets the requirements of Examination Category B-N-3 in the 2007 Edition through 2008 Addenda of Section XI. 2.1.14 Examination Category B-0 *Pressure Retaining Welds in Control Rod Drive and Nozzle Housings The ASME Code,Section XI, 2007 Edition through 2008 Addenda requires volumetric or surface examination of 10% of peripheral Control Rod Drive Housings Welds during the inspection inten1aL There are 28 peripheral Control Rod Drive Mechanisms (CRDMs} on the reactor vessel head. To meet the Code requirements, three CRDMs have been selected. The selection of these components for examination meets the requirements of Examination Category B-0 Examination Requirements in the 2007 Edition through 2008 Addenda of Section XL 2.1.15 Examination Category B-P Pressure Retaining Components PROGRAM SECTION No. SEP-ISl..JP2-llfJ1 Revision No. 4 Page46 of69 The pressure testing program at IP2 meets the requirements of ASME Code,Section XI, 2007 Edition through 2008 Addenda for Class 1 Systems. Details are contained In the pressure test program. 2.1.16 Examination Category B-Q -Steam Generator Tubing The Steam Generator Tube inspection program at IP2 is governed by IP2 Technical Specifications. 2.1.17 Examination Category C-A -Pressure Retaining Welds In Pressure Vessels Risk Informed lnservice Inspection utilizing ASME Code Case N-716-1 (approved through USNRC Regulatory Guide 1.147} will be implemented for Examination Category C-A requirements of the Steam Generators (HSS per N-716-1) and Residual Heat Exchangers. Examination schedule of the Steam Generators {HSS per N-716-1), utilizing ASME Code Case N-716-1, will be under Examination Category C-A and not under Examination Category R-A Table 2.1-3. Examination schedule of the Residual Heat Exchangers, utilizing ASME Code Case N-716-1, will not be under Examination Category C-A, but under Examination. Category R-A Table 2.1-3. 2.1.18 Examination Category C-B
  • Examination schedule of the Residual Heat Exchangers, utilizing ASME Code Case N-716-1, will not be under Examination Category C-B, but under Examination Category R-A Tabfe 2.1-3. 2.1.19 Examination Category C..C -Welded Attachments for Vessels, Piping, Pumps and Valves Examination Category C..C of the ASME Code Section XI, 2007 Edition through 2008 Addenda requires examination of welded 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. IP2 has two welded attachments on each Residual Heat Exchanger. One of the four Residual Heat Exchanger welded attachments is selected for examination or 25% of all vessel welded attachments, PROGRAM SECTION No. SEP-ISl-IP2-0ll1 Revision No. 4 Page47 of69 For piping, pumps, and valves, inspection of 10% of the total population of welded attachments is required. Ten percent (10%) of all Piping Welded Attachments are selected for examination. IP2 does not have any Class 2 pump or valve welded attachments. The population of welded attachments contained in the ISi program has been evaluated and fifty-one have been identified to be associated with whip restraints or exempt piping. These fifty-one do not meet the criteria of Examination Category C-C, Note 1 or are located on pipe and have been removed from the program. The total population of welded attachments contained in the ISi program is 190 components. however in accordance with Table IWC-2500-1, Note 5, the welded attachments that are required to be examined are the welded attachments associated with the supports selected for examination under class 2 supports; at !P2 28 welded attachments are associated with the class 2 supports. The population of welded attachments contained in the ISi program has been evaluated under Table IWC-2500-1, Note 5 criteria, therefore 3 welded need to be examined. The selection of these welded .attachments for examination meets the requirements of Examination Category C-C Examination Requirements in the 2007 Edition through 2008 Addenda of Section XI. 2.1.20 Examination Category C-F-1 -Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping Risk Informed lnservice Inspection utilizing ASME Code Case N-716-1 (approved through USNRC Regulatory Guide 1.147) will be implemented for Examination Category. C-F-1 requirements. Examination of-fuese welds will not be covered under Examination Category C-F-1, but under Examination Category R-A Table 2.1-3. 2.1.21 Examination Category C-F-2 -Pressure Retaining Welds in Carbon or Low Alloy Steel Piping Risk Informed lnservice Inspection utilizing ASME Code Case N-716-1 {approved through USNRC Regulatory Guide 1.147) will be implemented for Examination Category C-F-2 requirements. Examination of these welds will not be covered under Examination Category G-F-2, but under Examination Category R-A Table 2.1-3. 2.1.22 Examination .Category C-H -All Pressure Retaining CompoS1ents The pressure testing program at IP2 meets the requirements of ASME Code,Section XI, 2007 Edition through 2008 Addenda for Cfass 2 systems. Details are contained in the pressure test program.

PROGRAM SECTION No. SEP-ISl-JP:Z-001 Revision No. 4 Page 48 of69 2.1.23 Examination Category D-A -Welded .Attachments for Vessels, Piping, Pumps, and Valves Examination Category D-A of the ASME Code Section XI, 2007 Edition through 2008 Addenda requires examination of welded attachments. For vessel attachments, Note (3) allows for multiple vessels of similar design, function, and service, the welded attachments of only one of the multiple vessels shall be selected for examination. Note 3 also requires that "'All welded attachments selected for examination shall be those most subject to corrosion. as determined by the Owner, such as the welded attachments of the Service Water or Emergency Service Water systems." For single vessels, only one welded attachment shall be selected for examination. IP2 has two groups of multiple vessels and a single vessel with one welded attachment. One welded attachment is selected on one of the vessels for each group of vessels. In addition, one welded attachment on the single vessel is selected for examination. Three of the 9 vessel welded attachments are selected for examination or 33% of all vessel welded attachments. For piping, pumps and valves, inspection of 10% of the total population of Welded Attachments is required. Ten percent (10°/o) of all Piping and Pump Welded Attachments are selected for examination. IP2 does not have any Class 3 valve welded attachments. The population of welded attachments contained in the JSI program has been evaluated and twenty-eight have been identified to be associated with whip restraints or exempt piping. These twenty-eight do not meet the criteria of Examination Category D-A. Note i or are located on exempt pipe and have been removed from the program. The selection of these welded attachments for examination meets the requirements of Examination Category D-A Examination Requirements in the 2007 Edition through 2008 Addenda of Section XI. 2.1.24 Examination Category D-8 -Ali Pressure Retaining Components The pressure testing program at IP2 meets the requirements of ASME Code,Section XI, 2007 Edition through 2008 .Addenda for Class 3 systems. Details are contained in the pressure test program. 2.1.25 Examination Category E-A -Containment Surfaces Examination Category E-A of the ASME Code Section XI, 2007 Edition through 2008 Addenda requires examination of Class MC "Metallic Containment" pressure-retaining components and their integral attachments, as we.II as, the metallic shell and penetration liners of Class CC "Concrete Containment" pressure-retaining components and their integral attachments. IP2 will examine 100% of the accessible inside surface area (192 examinations) of the containment each period and 100% of the moisture barriers (6 examlnations) each inspection period. Any identified Containment Surfaces Requiring Augmented Examinations will be examined in accordance with the requirements of Examination Category E-C, Item No. E4.11 and E4.12.

PROGRAM SECTION No. Revision No. 4 Page49 of69 This meets the Examination Category E-A Examination Requirements in the 2007 Edition through 2008 Addenda of Section XI. 2.1.26 Examination Category E..C -Containment Surfaces Requiring Augmented Examination Indian Point Unit 2 currently has no Code required Augmented examinations identified. 2.1.27 Examination Category E-G -Pressure Retaining Bolting Examination Category E-G of the ASME Code Section XI, 2007 Edition through Addenda requires examination of Class MC pressure retaining bolting. IP2 has 18 bolted connections scheduled for examination during the interval (6 bolled connections each period). This meets the Examination Category E-G Examination Requirements in the 2007 Edition through 2008 Addenda of Section XI. 2.1.28 Examination Category F-A -Supports Examination Category of the ASME Code Section XI, 2007 Edition through the 2008 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. 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 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. It was discovered that whip restraints, and supports on exempt piping had been included in the original fourth interval program. Whip restraints do not provide component support. Therefore the whip restraints and exempt supports have been removed. 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 scheduled for inspection. IP2 scheduled the following supports: "' one Pressurizer Support; .. one of four Reactor Coolant Pump Supports; .. two of six Regenerative Heat Exchanger Supports;

  • one of two RHR Pump Supports;
  • two of four RHR Heat Exchanger Supports; 2.1.29 2.1.30 PROGRAM SECTION No. SEP-ISMP2-0Q1 Revision No. 4 Page 50 of69 " one of three Safety Injection Pump Supports; 0 one of two Auxiliary Feedwater Pump Supports (Electric); a. one Auxiliary Feedwater Pump Support (Turbine}; 0 one of two Component Cooling Water Heat Exchanger Supports: e one of three Component Cooling Water Pump Supports; " one Non Regenerative Heat Exchanger Support; °' one of six Service Water Pump Plate Supports; e one of six Service Water Pump Motor Supports; o one of six Service Water Pump Strainer Supports; Eighteen of the fifty-three non-piping supports are selected for examination or 33% 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, 2007 Edition through 2008 Addenda. Examination Category L-A -Concrete Examination Category l-A of the ASME Code Section XI, 2007 Edition through 2008 Addenda requires examination of the reinforced concrete portions of Class CC "Concrete Containment" components. This inspection divides the containment into three areas. Inspections are conducted on the dome and the upper and lower sections of the cylinder.
  • IP2 last examined these areas in 2015 and will examine all accessible surface area every 5 years with exams scheduled in lhe second and third periods. Any identifietl "Suspect areas" will be examined in accordance with the requirements of Item L1.12. The selection of these components for examination !Tleets the requirements Examination Category L-A Examination Requirements in .the ASME Code Section XI, 2007 Edition through 2008 Addenda of Section XI. Examination Category R*A *Risk Informed Piping The RI-ISi Program was approved for use during the Third 10-Year Interval via NRC Safety Evaluation Report (TAC No. MC0303). The RI-ISi Program was employed at IP2 during the 4th Ten;. Year ISi Interval via Relief Request RR-05. This program was comprised of Class 1 (ASME Categories B-F and B-J) piping segmentslelements with the exception of 8 (eight) reactor vessel nozzle-to-safe end welds required to be examined per ASME Code Case N-722-1 and N-770-1. The criteria for selection, examination method, examination coverage, and extent were based on EPRI report TR-112657. The Risk Informed Program for lhe Fifth 10-Year Interval is based on ASME Code Case N-716-1 {approved for use per USNRC Regulatory Guide 1.147) Alternate Classification and Examination Requirements,Section XI, Division 1. This program will be utilized in lieu of the requirements of IWB-2420, IWB-2430, Table IWB-2500-1, Examination Categories B-F and IWC-2420, IWC-2430, and PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 51 of69 Table IWC-2500-1 (excluding Examination Categories C-C and C-H), for inservice inspection of Class 1 piping welds or Class 2 components, IWB-2200 and IWC-2200 for preservice inspection of Class 1 piping welds or Class 2 components, or as additional requirements for Class 3 or Non-Class components. Periodic updates of the program are required on an ASME period basis. The update evaluates new information such as design changes, examination history, industry and plant events, PRA changes and operational changes for program impact. Changes to program selections must be evaluated against the N-716-1 selection criteria and potential impact on the program change-in-risk calculation.

SECTION 3 .. 0 ATTACHMENTS PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 52 of69

---Entergy Attachment 3.1 Table 2.1-3 IP2 Code CaletiOl'V Summarv Required to Numberot be Examined category llem Number Descrlpllon Exam Method Compommlll In During Item No. Interval B*A Prossure Retaining Welds In Reactor Vessel B-A B l.11 Reactor Vessel Circumferential Volumetric 3 3 Shell Welds B-A D1.12 Reactor Vessel Longiludinal Shell Volumetric a 8 Welds B-A Bl.21 Reactor Vessel Circumferenlial Volumetric 2 2 Head Welds B-A 81.22 Ke actor Vessel Meridional Head Volumetric 12 12 Welds 8-A 81.30 Reactor Vessel Shell to Flange Volumetric 1 1 Weld B*A 81.40 Reactor Vessel Head to Flange Volumetric and 1 1 Weld Surface Category Total 27 27 Examination Number to be Percentage Examined In Required Interval 100% All Welds 100% All Welds 100% Length or AU Welds 100% Accessible Length cl All Welds 100% Weld 100% Weld PROGRAM SECTION No. SEP*ISl-IP2..001 Revision No. 4 Page 53 of69 Number to Number to Number to be be be Examined Examined Examined in Third In First In Second Period Period Period 0 Q 31*1 0 0 alll 0 1 1<*1 0 6 6(0 0 0 1<*1 0 1 0 0 9 191'1 Noles for Cst. B*A Note 1: Examinations required ror perloonanca unless PfOposed Request Im Relief tor a1denslon from 10 years lo 20 year.; is approved by Nuclear Regulalory Commission. B-B Prossuro Rotalnlog Wolds In Vessels Other Than Reactor \Iossa ls B*B 82.11 Pressurizer SheU*to*Head Welds Volumetric 2 1 50%111 1 weld 0 0 1 Circumleren!lal B-B B2.12 Pressurizer SheU-to-Head Welds Volumetric 2 1 503121 l ft. (300 mm) of 1 0 0 Lonqitudinal one weld oer tiead B-B 82.40 Sleam Generators (Primary Slcle) Volumetric 4 1 25%111 1 Weld 0 1 0 Tubesheet to Head Weld Heal Excnangen; (Primary Side)

  • 0%{3} B*B 82.60 Shell TubeslleeMo-Head Volumelric 6 0 0 0 0 0 Welds!3x*i Heat Exchangers (Primary Side)
  • O"A>m B*B 82.BO Shall TubesheeMo-Snell Volumetric 6 0 0 0 0 0 Welds'3"'1 Category Total 20 3 1 1 1

Entergy PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 54 of 69 Attachment 3.1 Table 2.1*3 IP2 Code Category Summary Required to Number to Numborto Number of be examined Examination Number to ba be be be Examined Category ltom Number Oeacrlptlon ExamMothod Components In During Percentage Examined In Examined Examined In Third Item No. Required lnterv;;il In First ln Second Interval Period Period Period Note 1: The examination may be limited 10 one vessel among the group of vessels performing a simijar function (Rer. Table IWB-2500-1, Examinallo11 category 8-B. Nole 1 ). Note 2: Relief Request IP2-ISl-RR*01 was requesled for approval which permits Welds PZRC5 (62.11) & PZRL4 (82.12) lo be visually examined (\ff-2) after each refueling outage in lieu of the Code required volumetric examinaticm. This will be !racked via Pressure Testing Procedure PT-R75. Nole 3: lmplementalion of ASME Code Caso N*706* 1, permits an 62.60 and 02.80 welds 10 be visually examined (\ff*2) after each refueling outage In lieu ol lhe Code required Noles for Cat. B*B volumelric examination. This will be Ira eked via Pressure Testing Procedure PT*R75. No:e4: lmp!emenlalion of ASME Code Case N-706-1 requires U1e Owner to evaluate industry experience 10 determine which heat exchanger designs or configurations have leaked. rr any leakage is detected, it shall be com1Cled in accordance with IWA-4000. Use of this Case shall be discontinued Car lllat heal exchanger (Regenera!ive Heat Exchangers) and others of the same design or configuratltm. The .affected heat exchanger (Regenerative Heat Exchangers) and others of the same design or conllouralioo shall be examined in accordance with IWB-2500 or JWC-2500 as applicable. S-0 Full Ponolratlon Wo!dod Noz:zlos lo Vessels B*D!11 83.90 Reactor Vessel Nozzle-to-Vessel Volumetric 8 8 100% All Nozzles 0 0 5fll Wefds a-0<11 B3.100t*l Reactor Vessel Nonie Inside Volometricl51 8 8 100% All Nozzles 0 0 a<*> Radius Section B*D BJ.12of:i Pressurizer Nonie Inside Radius Valumelric or 6 6 100% All nozzles 3 0 3 Sec lion Visual B*D Sleam Generators (Primary Side) Volumetric or 8 8 100% All noules 0 4 4 Nozzle inside Radius Section Vlsual B-D 83.150 Heal Exchangers (Prima;];' Side} Nozzle-lo-Vessel Welds<3 1 Volumetric 12 0 0%(3) All Nozzles 0 0 0 B-0 63.160 Heat Exchangers (Primal)' Side(. Nozzle Inside Radius Seclion'31 Volumelric 12 0 0%' All Nozzles 0 0 0 Category Total 54 30 3 4 23 Note 1: Examinations required for performance unless proposed Request for Relier for extension from 10 years lo 20 years is approved by Nuclear Regulatory Commission. No!e2: These llem Numbers are from the 1998 Edilion of Sedion XI as required by 10 CFR 50.55a(b)(xxi)(A). If visual examinelion is performed, Iha examination shall be in accordance with 10 CFR 50.55a(b){xxi)(A) as defined in Section 1.4.2 of this program plan. Note 3: lmplemenlalion of ASME Code Case N-706-1. pennils all 83.150 and BJ.160 welds lo be vlsua!lyelffirnined (\ff*2} alter each refueling outage in lieu or lhe Code required volumetric examinalion. This will be tracked via Pressure Tesling Procedure PT*R75. Note4: Implementation of ASME Code Case N-706-1 requires Ille Owner to evaluate industry experience to determine which heal exchanger designs or conliguratlons have leaked. If any leakage is detected, ii shaU be c:orreded in acoordanoo with IWA-4000. Use ol lhis Case shall be dlsconlinued for that heat exchanger (Regenerallve Heal Notes for Cat. B*D Exchangers) and others of lhe same design or configuration. The affected heal exchanger (Regenerative Heal Exchangern) and others of the same design er configuration shall be examined in accordance wilh MfB-2500 or IWC-2500 as applicable. Noto 5: IP2 has adopted ASME Code Case N-648*1, which permils visual examination in place or a UT examlnation.

---Ent erg;; Attachment 3.1 Table 2.1*3 IP2 Code CateQOl"J Summary Required to Number of be Examined Category Item Numbar Description Exam Method Compommls In During item No. lnteroal B-F Pressurn Retaining Dlsslmllar Metal Welds In Vassel Nozzlos 111 Reactor Vessel NPS (ON 100) or Volumelric and B*F 85.10 larger Nozzle-To-Safe End Bult Visual 4 0 Welds Ho! lea Reader Vessel NPS (ON 100) or Volumelric and B*F 85.10 Larger End Bull Visual 4 0 Welds Colt! Leq Catogory Tomi 8 0 Examination Number to be Percentage Examined In Required Interval Same as for 1" 100% interval Same as for 1" 100% inleival PROGRAM SECTION No. SEP-ISl*IP2-001 Revision No. 4 Page 55 of 69 Number to Numbarto Number to be be be Examined Examined Examined In Third in First In Second Period Period Period 0 0 a 0 0 0 0 0 0 Notes for Cal. B-F Nole 1: These examinations are exempt from Code Case N-716*1 and ore in aceordance with Code Case N-722-1 and Code Case N-770-1 as required by 10 CFR 50.55alnll6ltillCElt2l lhrouah 14\ and 10 CFR 50.55alaU6Wil<F1<21throuoh11m. Tables am provided below ror 111eso Code Cases. B-0*1 Pressure Retainlno Boltlno, Gr&alor Than 2 In. 50 mml In Dfamatllr B-G-1 66.10 Reactor Vessel Closure Head Visual, VT-1 54 54 100% Same as for 1st 18 0 36 Nuis Interval 8-G-1 86.20 Reactor Vessel Closure Studs Volumetric 54 54 100% Same as for 1st 13 0 36 in1erval B-G-1 86.40 Reactor Vessel Threads in Volumetric 54 54 100% Samo as for 1st 0 0 54 F!anae inte!Val B*G-1 86.50 Reactor Vessel Closure Washers. Visual, VT-1 54 54 100% Samo as for 1sl 1ll 0 36 Bushinos Interval B-G-1 86.180 Pumps Bolls and Studs Volumetric 4 1 25%m Same as for 1sl 0 0 1 interval B-&1 86.190 Pumps Flange Surface. when Visual. VT-1 4 ot*x,, 0%1!){J) Same as for 1st 0 0 0 connection disassembled interval B*G-1 86.200 Pumps Nuls. Bushings. and Visual, VT-1 4 0(1)(3/ 0%(!)(lJ Same as for 1st 0 D 0 Washers inlerval Category Tola! 228 217 54 0 163 Nole 1: Nol Required unless disassembled. Nole2: Volumetric examination or bolting for heat exchangers, pumps, or valves may be conducted on one heat exchanger, one pump, or one valve among a group of heat Notes for Cal. B-G-1 exchangers, pumps, or valves that are similar in design, lype, and function. (Ref. Table IWB-2500-1, Examinallon Ca!egory B-G* 1. Note 3). Note3: For heal exchaogelS. piping, pumps. and valves, examinations are limited lo oomponenls selected for examinalion under Examination Category B-B. B-L-2 or B-M-2. /Ref. Tab!e lWB-2500*1, Examination Cateqorv B-G-1, Note 4). B*G*2 Prassuro Retaining Bolling, 21n. (50 mm} and Loss In Dlamotor 8-G-2 87.10 Reacior Vessel Bolls, Studs. ond Visual, VT-1 1 0 0% Same as for 1st 0 0 0 Nuls iCRD Houslnol interva1!IJ(h(JJ B-G*2 97.20 Pressurizer Botts, Studs, and V1Sual, VT-1 1 0 0% Same as for 1 sl 0 0 0 Nuts interva111x1HJ1

---Entergy Attachment 3.1 Table:U-3 IP2 Code Cate!'.lorv Summarv Required to Numoorof Examination Category ltemNumbm' t:mscrip&.in Elliam Method Com!X!flents In be Examined Percentage Dming Item No. lnteMlll Required B*G*2 87.3!l Steam Generator Botts. Studs, Visual. VT-1 & (} O",f, and Nuts EH3*2 137.50 Piping Bolts. Studs. and Nuls \/lsual. VT-1 16 0 0% B*G-2 87.60 Pumps Batts. Studs. and Nuts Visual. VT-1 4 0 0% B*G-2 87.70 Va!11es Balls, Studs, and N!Jls Visual, VT-1 17 0 0% GatGgoiy Total 53 Cl Nole 1: Bolling is required to ha eiu1mined only when a connection Is disass1:lmbllld or bolling is re1m:ived. Number to be Examined In Interval Sama as for 1s! Pl Same !IS fm 1st Same as for 1s1 lnleiva! rnm;;1J;si Same as for 1st inleiva! rnm1>He1 PROGRAM SECTION No. SJ;P-ISl-tP2-001 Revision No. 4 Page 56 of69 Number to Nmnberto Number to be Ell:amim1d Examined be Examined In Third In First In Second Period Pisrioo Period 0 0 0 0 0 0 0 0 0 0 0 0 (l 0 0 Nole 2: For vessels. pumps,. aml valves. examina!ions aJe to compnrn:m!s selected for examinallon under Examination C'.alegories B*B. B*L*2, and B*M*2 (Ref. Table IWB-2500-1, Examina!lcn Calegory B*G-2. No.le 2). Nola 3; E.:caminallon is only required once per interval. Note4: E.:caminali<>n is !imlled to at least one piping fiange In each group of piping flanges Iha! are of !he similar design, slze. runcUon. and service in Iha syslem. lP2 piping Notes lo.r Cat. B*G*2 flanges are grouped Into five groups in Table 2.1-1. Nole 5: Only one pump ot each group of pumps is required as outlined in B-L-2. Nole6: Only one valve of ea1:;h group orvaives is requited as outlined In B*M*2. B-K Woldod Att.llehmi;nts for Vessels, Plplng, Pumps, and Vah1es B*K 610.IO essels Welded Surface l 1 100% Same as for 1ii>I 0 0 1 inteNal B*K 810.20 Piping Welded Allaciimemls Surfac:& 22 3 10% Sarne el! for 1st 1 2 0 interval El-I< 1310.30 Pumps Welded A!laclimenls Suiface 12 2 10% Same as for 1st 0 0 2 inleNal Calegory Total 6 1 2 3 B*l-2 Pump Casings 8*L*2 812.20 PumpCesiog Visual. VT*:! 4 0 ()",!, Same as for firsl 0 l.J 0 inlerval01m Category Total 4 0 0 0 0 Category llom Number Notes far Cat. B-L-2 B*M*2 Valve Bodles B*M*2 812.SO Notes ror Cat. 8*M*2 Noto 1: Note 2: Attachment 3.1 Table 2.1-3 IP2 Code Cateaorv Summarv Required to Number of Examination Number to be Description Exam Method Comporuints in *

  • be Examined Percentage Examined In ltamNo. During Required Interval lnterv1d Examination ls limlled lo at least one pump in each group or pumps performing similar runc!ions ln Ina system. PROGRAM SECTION No. SEP*ISl-IP2*001 Revision No. 4 Page 57 of69 Number to Number to Number to be be Examined examined be Examined in First in Second In Third Period Period Period Examlnalion is required only when a pump or valve is disassembled for maintenance, or repair. Examination of the internal pressure boundary shall Include the internal pressure retaining surfaces made accessible rorexamlnalion by disassembly. If a partial examination is performed and a subsequent disassembly or U1a1 pump or valve allows a more extensive examinalion, an examination shaU be performed during lhe subsequent disassembly. A camplele examination is required only once durino the inleival. Valve Body, Exceeding NPS 4 Same as for first Visual. VT-3 17 0 0% inle1Val 0 0 Q (DN 100) fl)r;!J Category Total 17 0 0 0 0 Note 1: Examination is limiled to at least one valve within each group of valves that are of !he same size, constructural design (such as globe, gale. or check valves), manufaciuring method. and Iha! perform similar functions in lhe system. IP2 valves are grouped iota four groups in Table 2.1-2. Note2: Examination ls required only when a pomp or valve is disassembled for maln!enance, or repair. Examination of Ille internal pressure boundary shall indude the inlemal pressure retaining surfaces made aCCl.!s.sibfe for examination by disassembly. Ir a partial examination is performed and a subsequent disassembly of that pump or valve allows a lll()re el<tensive examination. an examination shall be perfonned during !he subsequent diSassembly. A complete examinallon is required only once durina the Interval. B-N-"I Roaclor Vessol lntorlor B-N-1 813.10 Reactor Vessel, Vessel Interior Visual. vr -3 1 3tt) 100% Each inspection 1 1 1 llB*N*1\ oeri<>d Category Total 1 3lll 1 1 1 Notes for Cat. B-N-1 Note 1: Examination or this Item number is required each period. Therefore the number required during lhe interval is three times the total number or components. This is reOec:ted in lhe category tolal. B*N*2 Welded Coro Support Structures and Interior Attachments to Reactor Vessels Reactor Vessel (PWR) Interior Same as for 1st B-N*2 813.60 Attachments Beyond Bellline Visual. VT-3 1 1 100% 0 0 1{1) Reoion IB-N-21 interval Catagoiy Tot.al 1 1 0 0 1lll Noles for Cat. B*N-2 Note t: Examinations required for performance unless proposed Request ror Reller for extension from 10 years to 20 yearn is approved by Nudear Regulatory Commission. B*N-l Romovablo Coro Support Structuros B*N*3 B13.70 Reactor Vessel (PWR) Core Visuat, Vf-3 2 2. 100% Same as for 1st 0 0 Tl) Support Structure (B-N-3\ inlorvat Entergy Attachment 3.1 Table 2.1-3 IP2 Code Category Summarv Required to Number of ooexamined CategOl'l( Item Ntlmber De.icrlptlon Exam Method Components ln During Percentage ll<1mNr>. Required rnterval Category Total 2 2 Numoorto be Exiamlned in Interval PROGMM SECTION No. SEP*ISl*IP2*00j Revision No. 4 Page 58 of69 Number to Number to Number to be be he Examined Examined Examined In Third in First In Second Period Period Period a () 21*1 Noles for Cat. 8*N*3 Note 1: Examinations required for performance unless proposed Request for Relief fOI' exlension from 10 years to 20 years is appro111!d by Nudear Regufatoiy Commission. 13*0 Pmlil.ium Rotalning Welds in Control Rod Drive and lmr1trumont Nonie Housings Reac1or Vessel (PWR) Welds lrl Volumelric or 10% peripheral 6-0 814.20 21l 3 10% CRD housings () 0 3 Con!rol Rod Drive (CRD) Housing Surface Ol Categoiy Total 28 3 I) 0 3 Noles for Cat. B-0 Note 1: There are 28 Peripheral Ccm!ml Roo Olive (CROJ Housings C-A f'f(IHUnl Retaining Welds in Pl'0ssura Vessels (Steam Ge11£irators HSS per N*111M) C*A cuo Pressure Vessels Shell Vo!ume!rlc 14 4 28.5% Eacn 1nsnooion 1 1 2 Circumrerential Welr;ls lnleNalllt2I C-A Cl.20 Pressure Vessels Head Volumelflc 6 2 33.3% Each insneaion 1 0 1 Circumferential Welds interva1° (31 C-A C1.30 Pressure Vessels TubesheeMo* Volumetric 4 1 25% Each {) 1 0 snenWeld ln!erval11 141 Category Total 24 7 2 2 3 Nole 1: The e>1aminalion may be limited lo one vessel among tile group of vessels of similar design. size, and sel\lioo (Ref. Table IWC-2500-1. r.xamimilioo Calegmy C*A. Nole 3). ' Nola2: There are three vessel Sile!! welds on lour SIG lherafore based on Nole 1, 3 of 12 SfG vessel shell circumferenliaf welds are required to be examined. and there is one Notes for Cat. C-A vessel sMU weld on each RHR HX or 1 of 2 lor a lolal of 4 of 14 Ot %. Nole3: There Is one circumfemnliai head weld on four S!Gs thereroro based i:m Nole 1, 1 ol 100 4 SIG vessel head circ11mferanlial welds are required lo be examined, and thera is one circumferential head weld on each RHR HX er 1 of 2 required for e total of 2 of 6 or 33.3%. No!e4: There is one tubesheet-t!Nlheli Mild on four SJGs, ltmmfore based on Nole 1. 1 of lhe 4 lubesheeMo-shell welds am reauirad lo be examined for 25%. C*B Pressure Retaining Nozzle Welds In VesG111ls (Steam GaruarntO!l'I HSS par M*nti-1)

Entergy Attachment 3.1 Table 2.1-3 IP2 Code Catei:iorv Summarv Required to NumbGrof Catsgory ltmnNumoor Description E.nam illleth!'Jd Compom:mts In be Examined Item No. During Interval Nozzles Wilhoul Reinforcing Plate in Vessels > 112 in. (13mmj Surface and 0-B 02.21 Nominal Tllicimess Noule-lo-Volumelrtc B 2 Shen (Nozzle to Head or Noulo to Nozzlel Weld Nozzles Without Reinforcing C-B C222 Pl<!le in Vessels ,. 1/2 in. (13mm) Volumetric 4 1 Nominal Thiclmess Nozzle Inside Radius 51.1ction Nozzles Wilh Reillrorcing Plate in Vessels > 1f2 in. (13mm) C*B C2.31 Nominal Thickness Reinforcing Surlaca 8 4 Plate Welds 10 Nozzle and Vessel Nozzle-to-Shell (Nozzle lo Head C-B C2.33 or Nozzle lo Noure)We!ds When VT*2 4 2 Inside of Vessel Is lnacces!Sible Category Total 24 9 Examfnatlcm Number to be Percenbge Examined In Required Interval 25%'21 Each in!er.ta!11 25%'31 Each inspection Each irneival1' 50%'51 Each inspection period10 PROGRAM SECTION No. SEP-ISl-IP2-Q01 Revision No. 4 Page 59 of 69 Number to Number to Number to be be !lLamlMd Examined be Examined in first Jn Second in Third Period Period Period 0 0 2 0 0 1 2 2 0 (6) (61 IS) 2 2 3 Note1: The examination may be limited to one vessel among the grollfl of vessels ol slmilar design, size, and selllioa (Rel Table IWC-2500*1, Exam!natioo Category C-B. Nole 4). Note2: There are two nozzles on 4 S/Gs; therefore based on Nole 1. 2 of the 8 nozzles are required lo be examined or 25%. Noles for Cal. C-B Note3: There is nozzle inside radius sect!on on 4 S!Gs; therefore based.on Note 1, 1 of lhe 4.noule inside radius section is required to be examined or 25%. Nole4: There am 2 nozzles with 2 reinforcing plates on each of lhe lwo RHR HX, or 4 or a or 50% required. Note5: Tl'lero aro 2 inaccessible nou.le-to-shell welds on each of tile two RHR HX or 2 of 4 or 50% required. Note6: The VT-2 examination is mnu!red each nerloo as roou!ted 1>11 Catenorv C*H. C-C Welded Attachm!:lnts for vessels, Piping, Pumps, 111nd Val111>s Each idenlilied c.c C3.10 Pressure Vessels \Nelded Surfacr; 4 1 25%1tl:2Hl) oe<:urrence and 0 0 1 Atlachments each irn;pecilon In larval Each identified C*C C3.20 Piping Welded Altactimonls Surface 1901'1 3 1.5%,0ll*! occurrem:e and 1 1 1 each inspection interval Category Total 32 4 1 1 2

--.....r-.. ---Entergy PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 60 of 69 Attachment 3.1 Table 2.1-3 IP2 Code Cateqorv Summaiv Required to Number to Number to Number to Number of be Examined Examination Number to be be be ba Examined Category ltom Numhar Oascrlpllon Exam Motltod Components In During Percentage Examined In Examined Examined In Third ltsmNo. Required Interval In First In Second Interval Period Period Period Nole 1: For multiple vessels of similar design, function. and service, only one welded a!lachment or only one of the multiple vessels shall be selected for examination_ For single vessels. only one welded allachmenl sha11 be selecied for examination (Ref. Table IWC*2500*1, Examination Calegory C-C, Note 4). Nole2: There are lwo welded attachments on each Residual Heat Exchanger; therefore 1 of lhe 4 welded aUachments is required to be examined for 25%. Noles for Cat. C*C Nole3: Examination is required whenever component support member deformation is identified (Ref. Table IWC-2500-1, Examination Calegory C*C, Nole 6). Nole4: IP2 has a total of 85 class 2 supports scheduled for examination In the fifth interval. 28 are welded attachments supports therefore in accordance wilh Table lWC-2500-1 Nole (5). 10% of the Category F*A supports with welded altachments are required lo be examined. The lolal populallon for Code Category C-C. C3.20 is 190 as such 1.Mt mnuires examination. D*A Wolded Attachments for Vessols, Piping, Pumps, and Valves Each identified D-A Dl.10 Pressure Vessels Welded Visual. VT-1 9 3 33% oi:currnnce and 0 0 3 Allachments each inspecllon lnlerval111!2l13l Each identilied D-A 01.20 Piping Welded A!laehments Visual. VT-1 156 21ttl 13% occurrence and at*> 5t*l 8c11 each Inspection lnteiva1<t><3> Each Identified D*A 01.3(} Pumps Welded Allathments Visual. VT-1 g 1 10% occurrence and 0 0 1 each inspeclion interva1C3lHl Calogory Toi.al 174 25 8 5 1.2 Nole 1: For mullipl-0 vessels of similar design, function, and service, the welded aUocnmenls of only one of Iha multiple vessels shall be selected for examination. For single vessels. only one welded allachmen! shall be selected for examination. All welded auachmenls selecled for examinallons shall be lhose most subject lo corrosion. as determined by the Owner, such as welded allachmanls of the Service Weter or Emergency Service water Systems. For welded attachments of piping. pumps, and valves, a 10% sample shall be selected for examination. This percentage sample shall be proportional lo the Iola! number or nonexempt welded auachments cannecled to the piping, pumps, and valves in each system subject lo lhese examinations. Therefore additional piping welded allachments are schedt.t!ed. (Rel. Table IWD-2500* 1, Examination Category D*A, Nol-e 3). Note2: There are two groups of mufliple vessels (one with lwo vessels and one wilh sfx vessels) and one single vessel; therefore, 3 of the 9 are required to be examined for 33%. Noles ror Cat. 0-A Nole3: Examination is required whenever component support member deformation is idenlllled (Ref. Table IWD-2500*1, Examination Calegof)' D*A, Note 4). NGle4: Thero are !Wo sels or pumps (6 SeNice Water Pumps and 3 Component Cooling Waler Pumps}. For welded auachments or piping. pumps, and valves, a 10% sample shall be selected for ei<aminallon. This percentage sample shall be proportional lo the total number of nonexempt welded attachments connected !o the piping. pumps. and values in each syslem r.ubjecl to these examimllions. Thus 1 Service Water Pump ls required lo be examined for 10%.

Entergy Attachment 3.1 Table 2.1-3 IP2 Code Catenorv Summarv Required to Number of be Examined Category ltom Number Doscrlpllon Exam Method Components In During UomNo. lntel'Val e*A Contalnmon! Surfaces E-A E1.11 Conlainment Vessel Accessible General Visual 192 5761'1 Surface Areas E-A E1.12 Containment Vessel Welled VT-3 0 0% Surfaces of Submerged Areas E*A E1.30 Conlainment Vessel Moisture General Visual 6 161 Barriers Category Total 198 5941'1 Examination Number to be Exam Jned In Required lnlerval 100% 100% During each Inspection Period 0% 100% 100% 100% During each lnspeclion Period PROGRAM SECTION No. SEP*ISl*IP2-001 Revision No. 4 Page 61 of69 Number to Number to Number to be be be Examined Examined Examinod In TI1lrtl in Flrst In Second Period Period Period 192 192 192 0 0 0 6 6 6 198 198 198 Noles for Cat. E*A Note I: Examination of this ilem number is required eaell period. Therefore. the number required during the interval is three limes the lotal number or components. This is renected in the cate11orv total. E*C Containment Surfaces Requiring Augmented Examlna!Ion Containment Surface Areas 100% of surface E-C E4.11 Visible Surfaces vr.1 0 0% 0% areas identified by 0 0 0 IWE-1242('> 100% of minimum wan thickness localions during Containment Surface A<eas Ultrasonic eachinspeclion E*C E4.12 Surface Area Grid Minimum Wall -Thiclmess 0 0% 0% period. established 0 0 0 Thickness Localion in accordance wilh IWE-2500(b)(3}m andlWE-\ 2500(b}(4\m Category Total 0 0 0 0 0

Cata gory E-G E*G F*A F-A F*A F-A l"*A F-A Entergy PROGRAM SECTION No. SEP-ISl*IP2-001 Revision No. 4 Page 62 of 69 Attachment 3.1 Table 2.1-3 IP2 Code Cateflorv Summaf1/ Required to Number to Number to Number to Numbarof Examination Number to be be be Item Number Oescrlpllon Exam Method Components In be Examined Percentage Examined In examined E1Camlned be Examined ltamNo. Ou ring Required fn(erval In First In Second in Tbird Interval Period Period Period Note 1: Containment surface areas requiring augmented examination are those iclen!ilied in IWE-1240. Notes for E*C N11te2: Tue extent of examination shall be 100% for each inspection period until the areas examined remain essenllalll' unchanged for the next inspecilon period. Such areas no lonaer reouire aucimenled e>Camination in acrordance wllh IWE-2420(c). Prossuro Retaining 8olllng 100% of"1ach E8.10 Bolled Conriections(IJ VT-1 18 16 100% bolted connection 6 6 6 (2) Category Total 16 6 6 6 .. Note1: Examinalion shall include bolls, s1uds. nuts, bushings, washers. and lhreads In base material and flange ligaments belWeen fastener holes. Noles for E*G Note2: Examination may be perlonned wi!h !he conneciion assembled and bolling In place under tension, provided the conneciion Is nol disassembled during the interval. II lhe bolled conneciion is disassembled for anv reason du1inq lhe interval, ihe examination shall be performed with ihe connection disassembled. Supports F1.10A Class 1 Piping Supports -One Visual. Vf.J 113 30 26.5% Each inspection 6 13 11 Directional lnlerval Svsrem eve 57 15 ... 2 1 6 RCS 37 10 ... 2 5 3 RHR 4 1 Ill 0 0 1 SIS 15 4 .. 2 1 1 F1.10B Class 1 Piping Supports -Multi-Visual, VT-3 89 24 26.9% Each !n:;;pecilon 6 10 8 direclional interval Syslem eve 62 16 \II 1 7 6 RCS 14 4 -"' 4 0 0 SIS 13 4 Ill 1 3 0 Fl .10C Class 1 Piping Supports -Visual, VT-3 81 23 28.3% EaCh inspection 6 7 10 Thennal Movement Interval Svslem eve 33 9 "' 2 4 3 RCS 22 6 Ill 2 1 3 RHR 5 2 "' 0 1 1 SIS 21 6 ,., 2 1 3 f1.10 Total Class 1 Piping Supports Visual, 263 n 25%1'1 Each Inspection 18 30 29 VT-3 Interval Fl.20A Class 2 PlplJlg Supports -One Visual, VT-3 245 40 16.3*,(, Each inspection 11 14 15 Olrecliona I Interval .1 Table 2.1*3 IP.2 Code Categorv Summary Required to Number of be Examined Category Item Number Description ExC1mMathod Components In During ltamNo. Interval Svslem AFW 3 1 BFD 11 2 eve 1 1 HIS 45 7 MS 31 5 RHR 20 3 SIS 134 21 F-A F1.20B Class 2 Piptng Supports -Multi* Visual. Vf-3 117 21 d!ractional Svstem BFD 13 2 eve 1 1 HIS 46 7 MS . 18 3 RHR 6 3 SIS 33 5 F-A F1.20C Class 2 Piping Supports -Visual. Vf-3 133 24 Thermal Movement System AFW 4 1 BFD 8 2 eve 1 1 HIS 19 3 MS 35 6 RHR 19 3 SIS 47 8 F*A F1.20 Tot.al Class 2 Piping Supports Visual, 495 65 VT-3 F-A F1.30A Class 3 Piping Supports -One Visui'.11, Vf.J 235 27 Difactii:mal Svslem ACS 1 1 AFW 33 4 ccw 114 12 eve 1 1 SW 86 9 F-A F1 .308 Class 3 Piping Supports -Mulli-Visual. VT-3 189 21 directional Svstem AFW 7 1 ccw 51 6 Examination Number to be Percentage Examined In Required Interval '" ,,, '" "' '" '" "' 17.9% Each rnspeclion interval lll "' "' ,,, ,,, "' 18% Eaeh inspection inlerval "' w "' ,,, Ill lll ,,, 15%11) Eachlnspocllon Interval 11.4% Each inspection inlerval '" \I) ,,, l'I \\) 11.1% Each inspeciiM interval lll ,,, PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 63 of69 Numoorto Number to Number to be be be Examined Examined Examined In Third in First In Second Period Period Period 0 0 1 0 1 1 0 0 1 0 3 4 2 3 0 1 0 2 B 7 6 a 3 10 1 0 1 0 0 1 3 3 1 1 0 2 3 0 0 0 0 5 s 7 12 0 0 1 1 1 Q 0 1 0 0 0 3 1 3 2 2 1 0 1 1 6 24 24 37 9 4 14 0 0 1 0 1 3 5 3 4 0 0 1 4 0 5 3 8 10 0 0 1 2 2 2

---:::--' Entergy Attachment 3.1 Table 2.1-3 IP2 Code Category Summary Required to Numoorof be Examined Catogary ltom Number Dascrlption Exam Method Components in During llem No. Interval SW 131 14 F-A F1.30C Class 3 Piping SuppMs -Visual, VT-3 51 6 Thermal Movement Svslem ACS 7 1 AFW 8 1 ccw 17 2 SW 19 2 F-A F1.30 Total Class 3 Piping Supports Visual, 475 54 VT-3 F-A F1.40B Supports olhcr lhan Piping Visual, VT*3 15 5 Suooorls Svstem eve 6 2 RCS 9 3 F-A F1 .40C Supports other lhan Piping Visual, VT *3 11 6 Supports Svslem RHR 6 3 SIS 5 2 f-A F1.400 Supports other lhan Piping Visual. VT-3 31 14 Suooorts Svslem AFW 3 2 ccw 6 2 SW 18 6 NIA 4 4 F*A F1.40 Supports otbor than Piping Visual. 'Sf 24 Supports ICla!>S 1.2.3, nnd MC) VT-3 Ca&O(lory Total 1310 240 Examination Number to be Percentage Examined In Required Interval '" 11.7% Each inspection inlerval ,,, ,,, "' \11 10%'" EaehlnspecUon Interval 33.3% 46.4%. 46.1% 42.1% Each Inspection lnterva112H1l PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 64 of 69 Number to Number to Numbarto be bo be Examined Examined Examined in Third In Fir.st In Second Period Period Period 1 6 7 0 5 1 0 1 0 0 1 0 0 1 1 0 2 0 12 17 25 0 0 5 0 0 2 0 0 3 1 0 4 1 0 2 0 0 2 0 1 13 0 1 1 0 0 2 0 0 6 0 0 4 1 1 22 65 72 113

-= --Entergy PROGRAM SECTION No. SEP-1$1-IP2-001 Revision No. 4 Page 65 of69 Attachment 3.1 Table 2.1-3 IP2 Code Cateaorv Summarv Required to Number to Number to Number to Number of Examination Number to be be be Cat&gory !tom Number DoscripUon Exam Mothod Components In be Examined Percentage Examined In Examined Examined bo Examined Item No. During Required Interval In First In Second in Third Interval Period Period Period Note 1: The tolal percentage sample shall he comprised of supports from each system. where lhe indivldual sample sizes are proportional to the lotal number or non-exempt supports or each type and lunciion within each system (Ref. Table IWF-2500*1, Exeminalion Category F*A, Nole 2}. Total may exceed percentage requirements to alf<1w seleclion of al least one support of every type anti system. Nole2: For mu!Ople components other tll<m piping, within a system or similar design. function. and se!Vice. lhe supports of only one or the multiple components are required to be examined (Ref. Tabla IWF-2500-1, Examination Category F-A. Note 3). Noles For Cat. F-A Note3: 1 Pressurizer Support, 1 of 4 Reactor Coolant Pump Supports, 2 of 6 Regenerative Heal Exchanger Supports, 1 of 4 Sleam Generator Supports. 1 of 2 Containment Spray Pump Supports. 1 of 2 Residual Heat Removal Pump Supports. 2 of 4 Residual Heal Removal Heal Exctianger Supports. 1 of 3 Safety lnjeclion Pump Suppons, 1 of 2 Auxiliary Feedwater Pump Supports (Electric), 1 of 2 Component Cooling Water Heat Exchangers Supports, 1 of 5 Recirculation Fan Coorer Supports. 1 ol 6 Seivlce Water Pump Supports. 1 al 3 Compomml Cooling Waler Pump Supports. 1 Audiary Feedwater Purnp Supports (Turbine), 1 of 2 Spent Fuel Pump Supports and 1 of 6 Sewice Water Pump Strainer Supports. Additionally !here are 4 CROM supports. with 4 of 4 required. 24 of the 57 non piping supports are selected for examination or 42.1 % or all non* piping supports. L-A Concrete l*A l1.11 All accessible surface areas General Visual 48 9510 100% IWL*2410 0 48 48 l-A ll.12 Suspect areas Detailed Visual 0 0 100% IWL-2410 0 0 0 Ca1egory Total 48 96111 0 48 48 Notes for Cat. L*A Note 1: IWL-2410 requires 100% exam!nalion every 5 years. Therolore the number required during Illa interval is twloo lhe lolal number of components. This is reflected in the category total. R*A Risk Informed Piping and Component Welds High Safely Significant Pip>.ng R*A R1 .10 S!ruciural Elemenls (1) Elements Subject to Thennal Each inspection R-A R1.11 Fatigue Volumetric 122 31 (1) interval 11 8 12 Elements Subject to Thermal Visual VT *2 of Fatigue (socket welds of any size Otting and Each inspection R*A R1 .11s and branch conneelions NPS 2 or Volumetnc of 3 3 (1) lnlef\ial0i 0 3 0 smaller) base metal ln lninino R-A RU2 Nol Used

--="'Entergy Attachment 3.1 Table 2.1-3 IP2 Code Categorv Summarv Required to Numbarof Cata gory Item Number Dascrlpllon Exam Method Components In be Examined Item No. During Interval Elements Subject lo Erosion-R-A R'l.'l3 Cavil a lion Volume Irie NIA NIA Elements Subject to Crevice R-A R1.14 Corrosion Cracking Volume Irie NIA NIA Elements Subject to Primary R*A R1.15 Waler Stress Corrosion Cracking Volumetric NIA NIA IPWSCCl Wefds Subject to lnlergranu!ar or R-A R1.16 Transgranular Slress Corrosion Volumetric 12 5 Crackin11 CIGSCC or TGSCCJ Welds Subject lo lntergranu!ar or Transgranular Stress Corrosion R*A R1.16s Cracking (IGSCC or TGSCC) Visual, VT*l 5 z (soclmt welds of any size and branch connections NPS 2 or smaller) Elaments Subjeci to Localizecl Visual, VT-3 R-A R1.17 Corrosion (Microbiologically* Internal NIA NIA Influenced Corrosion {MIC) 01 Surfaces or Pitting] Volumetric Elements Subject to Flow Owner's R-A R1.1B Acceleraled Corrosion (FAC) Existing NIA NIA Promam ElemenJs Subject to External R*A R1.19 Chloride Stress Corrosion Surface NIA NIA Cracldng (ECSCC) Elements not Subject to a R-A R1.20 Oegradalion Mechanism Volumelric 460 37 Elements nol Subject to a R-A R1.20s D11gradation Mechanism (sockel Visual. VT*2 434 28 welds of any size and branch connections NPS 2 or smaller) Category Total 1036 10& Examination Number to be Percentage Examined In Required Interval Each inspection (1) interval Each ins.pedion (1J inteival Ea Ch inspection (1)(2) Interval Eaeh Inspection (1) Interval {1} (4) (1] Each Inspection inteival Each inspection (1) interval Each inspection (1) interval Each inspection (1) interval {1) (4) PROGRAM SECTION No. SEP-1Sl-IP2*001 Revision No. 4 Page 66 of69 Number to Number to Number lo be be Examined Eicamlned bo Examined In First in Second in Third Period Period Period NIA NIA NIA NIA NIA NIA NIA NIA NIA 3 2 0 N/A NIA NIA NIA NJA NIA NIA NIA WA NIA NIA NIA 3 115 19 NIA N/A NIA 17151 28151 311*l

Entergy PROGRAM SECTION No. SEP-ISl-IP2-001 Revision No. 4 Page 67 of 69 Attachmer;t 3.1 Table 2.1-3 IP2 Code Cateaorv Summarv Required to Number to Number to Number to Number of be examined Examination Number to be be be be Examined Cato gory Item Number Oescriptlon Exam Molhod Components In During Percentage Examined In Examined examined in Third Item No. Required Interval In first In Second rnteirval Period Period Period Nole 1; The selections are based on lhe requirements of Code Case lil-716-1 and not by Code Item Number. Note 2: llem R1.15 is only used when multiple damage mechanisms including PWSCC is al a lacallon. PWSCC is addressed by NRC requlred Ct1de Cases N-722-1. N-729*1 and N-770-1 and not Code Case N*716*1. Noles for Cal. R*A \lole J; Volumetric of base metal is once an fnlerval, lhe Visual. VT*2 of lhe lilting is condueled in accordance wilh Calegories a-P. C-H or D*B, as applicable lo lhe component ASME classification. "Joie 4: The Visual. VT-2 is conducted in acc.ordance wilh Categories B*P, C*H or 0-8, as appficable lo the component ASME cfassillcation. Nole 5: Period totals do not include Visual. VT-2 onlv exams. Code Caiso N-722-1 Additional Examinations for PWR Pros11uro Retaining Wolds In Class 1 Components Fabricated With Alloy 600/821182 Materials 111 N-722-1 815.80 RPV Bottom-Mounted Instrument Visual, VE"1 1 3!ll 100% E: very other 1 1 1 Penelrations rerueling outage N-722*1 815.90 Reactor Vessel Hol Leg Nozzle-Visual, VE12l 4 201*1 100% Each refueling 4 a 8 lo-Pipe Connoclions oulage N-722*1 815.95 Reactor Vessel Cold Leg Nozzle-Visual, VEm 4 100% Once per interval 0 4 0 lo-Pipe Connections Category Total 9 27'lM*l s 13 9 Nole 1: These examinations are in accordance wilh Code Case N-722-1 as required by 10 CFR 50.55a(g)(6){li)(E)(2) through (4). No!e2; An u!lrasonic exarninalion fron1 either !he ID or the OD in accordance wilh Ifie requirements of Appendix Viti shall be acceptable in lieu of Iha Visual, VE. Note 3: Examination of this llem number Is required every other outage. Therefore, the number required during !he interval is two limes !he Iota! number of components. This is reOecied in lhe category total. Notes for Cat. N* 722-1 Noto4: Examination or this ilem nt1mber is required each outage. Therefore. !he number required during Iha Interval is live limes the lolal number of components. This is reflected in the category Iola!. Visual. VE examinations requited for Code Case N-722-1oflha4 Reaclor Vessel Hol Leg Nozzle-to-Pipe Connections consisl!ng of Alloy 6001621182 Material are performed under ASME Code Case N-770-1 Category Table 1 Item No. A*2. Note 5: Examination of lhis ilem is required once per inlerval. VE e)(aminations required for Code Case N*722-1 of the 4 Reactor Vessel Cold Leg Nozzle-lo*Pipe Connections consisting of Alloy 600/821182 Malarial are oerformed under ASME Cade Case N-77G-1 Cateaorv Table 1 Uem B. Coda Case N-729*1 Allernatlvo cKamlnatlon Requirements ror PWR Reactor Vassel Uppar Hoads With Nozzlos Having Prassure*Ret.alnlng Partlal*Penetratlon Welds 1'l Reactor Vessel Upper Head wilh N-729-1 84.10 UNS N06600 nozzles 1!11d UNS Visual. VE 1 5!1l 100% Each refueling 1 2 2 N06082 or UNS W86182 Partial outage Penetration Welas Reactor Vessel Upper Head UNS N-729*1 84.20 N06600 nozzles and UNS Vo!umetr!c/ 1 5PJ 100% Each refueling 1 2 2 N06082 or UNS W86162 partial-Surface outage , oenetralion welds lo head Category Tot.al 2 10""1' 2 4 4

.. ---Entergy PROGRAM SECTION No. SEP-ISl-IP2--001 Revision No. 4 Page 68 of 69 Attachment 3.1 Table 2.1*3 IP2 Code Cateciorv Summarv Required to Number to Number to Number to Numb&ror ExamlnaUon Number to be be be Cate9oiy Item Number Dase rl ptlon Exam PAeihod Components ln be Examined Percentage Examinedln Examined Examined be Examined Item No. During Required Interval In First In Second In Third Interval Period Period Period Nole 1: These examinations are in* acwrdance with Code Case N-729-1 as required by 10 CFR 50.55a(g}(6}(ii)(D)l2) through (6). Nole2: Examination of this item number is required each oulage. Therefore, the number required during lhe interval is five times the Iota I number of components. This is Notes for Cat. N-729-1 rellected in the category total. Nola3: Examination of lhls ilem ls required each outage. Therefore, lhe number required during lhe interval is five limes the total number of components. This Is also reflecled in lhe calegorv total. Code Case Alternatl11e Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Norzle Butt Welds Fabricated With UNS N06082 or UNS W66182 N-170*1 Wold Fiiier Material With or Without Applleation of Listed Actlvlllesl'I N-770*1 A*2 (85.10) Reactor Vessel Unmitigated Volume Ilic 4 12m 100% Every five years 4 4 4 <B*Fl Hot Log Wolds A*2 N-770-1 A-2 (BS.10) ReactorVessol Unmltfgated Visual, VE121 4 100% Each refueling 4 6 B CB-Fi Hot Loq Wolds A-2 oulaae Evesy second N-770-1 B (85.10) ReactorVcl.lSel Unmitigated Volumetric 4 415) 100% inspection period 0 4 0 (B-F) Cold Leg Welds B not to exceed seven voars N-7701 (B*F) B (BS.10) Reactor Vessel Unmitigated Visual, VE121 4 4l2> 100% Once per intel\tal 0 4 0 Colc:l Leq Wolds B Category Total 16 40 8 20 12. Note 1: These examinations are in accordance wilh Code Case N-770-1 as required by 10 CFR 50.55a(g)(6){il)(F)(2) through (10}. Nole2: An ultrasonic examlnallon from either lhe ID or the OD in accordance wHh the requirements of Appendix VIII shell be acceplable in lieu of the Visual, VE. Code Case N* 722*1 and Code Case visual el<aminations should be scheduled al lhe same time. Note3: Examination of this !lem number Is required every five years. Therefore, IM number required during Iha inleival is 3 limes the Iota I number of components based on 24 Noles force N*770-t month refueling cyde. This Is reflected In the category total. Note 4: Examination of this item number is required each refueling outage. Therefore, !he number requ!red during the interval is 5 times the total number or components. ihis is reflected in lhe category total. Vcsual, VE examinations performed under N-770-1 Item No. A-2 additionally credjled for ASME Code Case N-722-1 Item No. 815.90. Nole 5: Examination or this item number is required every seven years. Therefore, lhe number required during the interval ls 1 lime the total number of components. This ls reflecie<I in lhe cate<:sorv Iola!. Visual, VE examinations uerformed under N-770-1 !fem No. B addilionally credited for ASME Code Case N*722-1 Item No. 815.95. MRP-146Rev1 Management of Tharmal Fatigue In Normally Stagnant Non-lsolable Reactor Coolant System Branch Llnast11 NIA Una 95 MRP 146 conliguralion H Volume Irie: 1 5!2J!*t 100% Each refueling 1 2 2 oula11e NIA Line 96 MRP 146 configur<Jtion H VisualVT-2 1 5l211*i 100% Each rerueting 1 2 2 oulage Category Total 2 10cz1m 2 4 4 NIA line 82 tv1RP 146 configuration OH Volumetric 1 2J)(41 100% Every other 0 1 1 refueling oulage

---Entergy PROGRAM SECTION No. SEP*ISl*IP2*001 Revision No. 4 Page 69 of 69 Attachment 3.1 Table 2.1*3 IP2 Code Categorv Summarv Required to Number to Number to Numborto Number of Examination Number to be be be Category Oescrl pllon ExamMothod ComJ)-0110111.s In be Examined Percentage Examined in Examined Examined Ila Examined Item No. During Required Interval In First In Second in Thlrd Interval Period Period Period NIA Line 62 MRP 145configuration DH Visual VT-2 1 2(3)(*) 100% Everyolhar 0 1 1 refueling oulage NIA Line 83 MRP 146 configuration DH Volumetric 1 -2(3)(4) 100% Every olher 0 1 1 refueling oulage NIA Line 63 MRP 146 configuration DH Visual VT-2 1 2(l)(*) 100% Every other 0 1 1 refueling outage NIA Linc 64 MRP 146 configuration DH Volumetric t 2(l)l4) 100% Eveiy other 0 1 1 refueling outage NIA Unell4 MRP 146 conllguration DH VisualVT-2 1 2mNJ 100% Every o!har 0 1 1 refueling outage Category Total I) 1zCl1!*1 0 6 6 Nole 1: These examinations are in accordance with MRP* 146 Rev 1 Guideline. Note2: Examlnalion of lhis ilem number iS required each refueling outage. Thetefore, lhe number required during lhe interval is 5 !imes lhe lolal number of componenlS. This is Notes for MRP-146 reflected in the calegory total. Nore3: Examinatfon of lhis item number Is required every other outage. Therefore, Iha number required doling the Interval Is two limes the Iola I number of components. This is reRected in tile category total. Note4: The ISi orooram wm track and monllor the MRP-146 Rev 1 lnspecllons. Socilot Wolds llcons& Renewal Commiuoont #46 (LO-LAR-2011..0174 CA 65) Socket Wold Examination Elemenls Subject ta Thermal R-A R1 .11s Faligue (socket welds or any size Volumetric<11 3 3 100% Each Interval 0 3 0 and branch connections NPS 2 or smaller) Welds Subject to lntergranular or Trnnsgranular Stress Corrosion R-A R1.16s Cracking (lGSCC or TGSCC) Vo!umelriclO 5 5 100% Each Interval 2 0 3 (socket welds ol any size and branch cnnnections NPS 2 or smaller) Elemenls no! Subject to a R-A R1.20s Degradation Mechanism (socket Volumetric<11 17 17 100% Each Interval 5 6 6 welds of any size and branch NPS 2 orsmaflerl Caleaory Total 25 25 7 9 9 Notes for Socket Welds Nole 1: Volumetric weld meral !nspeclions al socket welds shall be performed. In lieu of volume!rlc examinalions. destructive examinations may be performed, where one deslructive examination mav be subslilutw for lwo volumetric examina!ions.

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