ML15223A270

NRC000182 - Letter from James Trapp, NRC, to John Ventosa, Entergy, Indian Point Nuclear Generating Unit 2 - NRC License Renewal Team Inspection Report 05000247/2013010 (Sept. 19, 2013)

ML15223A270
Person / Time
Site:	Indian Point
Issue date:	09/19/2013
From:	NRC/OGC
To:	Atomic Safety and Licensing Board Panel
SECY RAS
References
RAS 28147, ASLBP 07-858-03-LR-BD01, 50-247-LR, 50-286-LR
Download: ML15223A270 (18)

See also: IR 05000247/2013010

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BOULEVARD, SUITE 100 KING OF PRUSSIA, PENNSYLVANIA 19406-2713 September 19, 2013 Mr. John Ventosa

Site Vice President

Entergy Nuclear Operations, Inc.

Indian Point Energy Center

450 Broadway, GSB Buchanan, NY 10511-0249

SUBJECT: INDIAN POINT NUCLEAR GENERATING UNIT 2 - NRC LICENSE RENEWAL

TEAM INSPECTION REPORT 05000247/2013010

Dear Mr. Ventosa:

On September 12, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an

inspection at your Indian Point Nuclear Generating Unit 2. The enclosed inspection report

documents the results of our review of your completed actions for the remaining

10 commitments, which were discussed on September 12, 2013, with you and members of your staff.

The inspectors examined activities conducted by your staff to complete commitments Entergy made as part of your application for a renewed facility operating license. The inspectors also

reviewed selected procedures and records, observed activities, and interviewed personnel. This inspection was conducted to follow-up on several commitments that were determined to merit additional inspection during a previous NRC License Renewal Team Inspection.

No findings were identified during this inspection. The NRC determined that the commitments reviewed associated with the license renewal application had been appropriately implemented.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the

NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's Agencywide Document Access and Management System (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/ James M. Trapp, Chief

Engineering Branch 1

Division of Reactor Safety

Docket No. 50-247 License No. DPR-26

ML13263A020 SUNSI Review Non-Sensitive Sensitive Publicly Available Non-Publicly Available OFFICE RI/DRS RI/DRP RI/DRS NAME GMeyer/MM ABurrit JTrapp DATE 9/18/13 9/19/13 9/19/13

J. Ventosa 2 Enclosure: Inspection Report 05000247/2013010 w/Attachment: Supplementary Information

cc w/encl: Distribution via ListServ

J. Ventosa 3 Distribution w/encl: (via E-mail) W. Dean, RA (R1ORAMAIL RESOURCE) D. Lew, DRA (R1ORAMAIL RESOURCE) D. Roberts, DRP (R1DRPMAIL RESOURCE) M. Scott, DRP (R1DRPMAIL RESOURCE) R. Lorson, DRS (R1DRSMAIL RESOURCE) J. Rogge, DRS (R1DRSMAIL RESOURCE) A. Burritt, DRP T. Setzer, DRP

S. McCarver, DRP

L. McKown, DRP

S. Stewart, DRP, SRI K. Dunham, DRP, RI Ami Patel, DRP, RI

D. Hochmuth, DRP, AA

D. Rich, RI OEDO

RidsNrrPMIndianPoint Resource RidsNrrDorlLpl1-1 Resource ROPReports Resources

i Enclosure U.S. NUCLEAR REGULATORY COMMISSION REGION I Docket No.: 50-247

License No.: DPR-26

Report No.: 05000247/2013010

Applicant: Entergy Nuclear Northeast (Entergy)

Facility: Indian Point Energy Center Unit 2

Location: 450 Broadway

Buchanan, NY 10511-0249

Dates: September 9-12, 2013

Inspectors: G. Meyer, Senior Reactor Inspector

M. Modes, Senior Reactor Inspector

Approved By: James M. Trapp, Chief

Engineering Branch 1

Division of Reactor Safety

ii Enclosure SUMMARY OF FINDINGS

IR 05000247/2013010; 09/09/2013 - 09/12/2013; Indian Point Nuclear Generating Unit 2; License Renewal Inspection.

This report covers an announced one week inspection, using the guidance provided in NRC inspection procedure Temporary Instruction 2516/001, "Review of License Renewal Activities,"

of activities conducted by Entergy to complete commitments made to the NRC as a part of the Indian Point Energy Center, Unit 2, application for a renewed operating license. The commitments reviewed during this inspection are recorded in Supplement 1 to NUREG-1930,

"Safety Evaluation Report Related to the License Renewal of Indian Point Generating Units

Numbers 2 and 3," Attachment 1, dated August 2011, and in other related correspondence.

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity No findings were identified. The inspectors concluded Entergy had made sufficient progress to

complete our review of 44 commitments.

Enclosure REPORT DETAILS 4. OTHER ACTIVITIES 4OA5 Review of License Renewal Activities (TI 2516/001)

.1 Background The expiration date of the operating license for Indian Point Unit 2 is midnight on September 28, 2013. Indian Point Unit 2 meets the criteria in Title 10 of the Code of Federal Regulations (10 CFR) 2.109(b), "Effect of timely renewal application," and will likely operate beyond the current operating license expiration date. Due to the

Commission's decision to revise the Waste Confidence Decision and Rule and because of the ongoing Atomic Safety and Licensing Board hearings, the Commission is not expected to issue a renewed license for Indian Point Unit 2 before the expiration date of

the original license. Therefore, Indian Point would continue operations under the timely

renewal provisions of 10 CFR 2.109(b). The team used NRC Inspection Manual Temporary Instruction 2516/001 to conduct this inspection. The Temporary Instruction was written specifically for plants like Indian Point

Unit 2, where the holders of an operating license meet the criteria of 10 CFR 2.109, for

timely renewal, but a final decision by the NRC on the license renewal application is not

expected prior to the period of extended operation. The inspection objectives and

requirements of the Temporary Instruction are to report the status of license renewal commitment implementation, the status of aging management program implementation, and to verify the description of programs and activities for managing the effects of aging

are consistent with the Updated Final Safety Analysis Report.

The NRC has conducted three separate license renewal inspections that have reviewed a total of 44 license renewal commitments. Our first license renewal inspection conducted during a refueling outage, reviewed four commitments as documented in

NRC Inspection Report 05000247/2012008 (ML12110A315). On May 23, 2013, the

NRC completed a License Renewal Commitment Team Inspection, as documented in

NRC Inspection Report 05000247/2013009 (ML13186A179). The team inspection

concluded that Entergy had made sufficient progress to complete review of 30 commitments and identified 11 commitments that merited further assessment during a planned follow-up inspection. During the current planned follow-up inspection, the

inspectors completed our review of ten of the 11 commitments identified by the team as

requiring additional review. Commitment 47, one of the 11 commitments previously identified for additional review, was not assessed during this inspection because Entergy revised the completion date for this commitment to March 1, 2015, in a letter to the NRC (ML13142A202).

2 Enclosure .2 Commitment Reviews .2.1 Commitment 6: Enhance the Fatigue Monitoring Program to monitor steady state cycles and feedwater cycles or perform an evaluation to determine monitoring is not required. Review the number of allowed events and resolve discrepancies between reference

documents and monitoring procedures. a. Inspection Scope In the prior inspection, the inspectors noted that Entergy had awarded contracts to

perform calculations to determine whether monitoring of steady state cycles and

feedwater cycles was required. The inspectors also noted that Entergy planned to revise procedure 2-PT-2Y015, Thermal Cycle Monitoring Program, if the calculations demonstrated that a change in the number of allowable steady state cycles and

feedwater cycles was identified.

During this inspection, the inspectors reviewed Westinghouse calculation IPP-13-20, Revision 1, dated August 14, 2013, reporting the "Steady State Fluctuations and Feedwater Cycling Transient Disposition," presenting LTR-PAFM-13-87, Revision 2.

This result determined that both transients do not significantly affect the fatigue of the

primary system and can be removed from the transient cycle counting program. It was determined the feedwater cycle transient must still be tracked for the secondary side of

the steam generator and feedwater piping, with a 25,000 cycle limit. The inspectors verified that procedure 2-PT-2Y015, "Thermal Cycle Monitoring Program," Revision 4, tracked the feedwater cycle transients.

Findings and Observations No findings were identified. .2.2 Commitment 13: Enhance the Metal-Enclosed Bus (MEB) Inspection Program to add a 480 volt bus, visually inspect the external surface of MEB enclosure assemblies, include

acceptance criteria, inspect bolted connections, and remove reference to "re-torquing"

connections from the applicable site procedure. a. Inspection Scope

In the prior inspection, the inspectors identified that Entergy had not included all

accessible portions of the MEB within the scope of the maintenance inspection program. The inspectors noted that sections of the emergency diesel generator 480 volt MEB in the electrical tunnel had not been visually inspected and were not included in the scope

of the maintenance procedure which performed the MEB inspections and tests. As a

result of the NRC's observations, Entergy initiated a Condition Report

(CR-IP2-2013-01786) to revise site procedures and conduct visual inspections of those

additional sections of the bus ducts prior to the period of extended operations. During this inspection the inspectors reviewed the revised inspection and test

procedures for the portions of the MEB previously considered to be inaccessible. The

3 Enclosure inspectors reviewed the work orders under which the inspections and tests were completed for the three MEB sections and corrective action documents which resolved any identified conditions.

Findings and Observations

No findings were identified. .2.3 Commitment 19: Implement the One-Time Inspection Program as described in License Renewal Application, Section B.1.27. This new program will be implemented consistent

with the corresponding program described in NUREG-1801, Section XIM32, One-Time

Inspection. a. Inspection Scope

In the prior inspection, the inspectors noted the One-Time Inspection Program involved

over 400 inspections. Because Entergy had only completed approximately half of the planned inspections, the inspectors determined that additional NRC review was merited to assess the remaining inspection results; any further actions needed, and program

conclusions.

During this inspection the inspectors reviewed the One-Time Inspection Summary

Report, the completed inspection tracking matrix, and 20 additional inspection reports. The inspectors determined that all inspection results were acceptable and there was no need for additional action. Further, Entergy concluded that the inspection results

demonstrated that the existing aging management programs for water chemistry and the diesel fuel monitoring and oil analysis had been effective in managing aging. The test

program results also indicated that additional inspections on components specified in the License Renewal Application had not identified any unacceptable degradation.

Findings and Observations

No findings were identified. .2.4 Commitment 23: Implement the Selective Leaching Program as described in License Renewal Application, Section B.1.33. This new program will be implemented consistent with the corresponding program described in NUREG-1801, Section XIM33 Selective

Leaching of Materials.

a. Inspection Scope In the prior inspection, the inspectors noted Entergy was in the progress of completing

selective leaching inspections. The inspectors determined that additional NRC

inspection was merited to review the results of the remaining inspections, any further

actions needed, and program conclusions. During this inspection, the inspectors reviewed Selective Leaching Summary Report,

including the final sampling plan, the destructive evaluation results of seven

4 Enclosure components, and associated corrective action documents. Entergy determined that the visual inspections of 22 gray cast iron components and 17 copper alloy components showed an absence of selective leaching. However, destructive evaluations

demonstrated that significant selective leaching (i.e., graphitization, had occurred in gray

cast iron components) was occurring. While the commitment actions were complete,

Entergy concluded that they would refine the process and documented a corrective

action to perform engineering evaluations to develop a continuing monitoring program to manage and evaluate selective leaching.

Findings and Observations

No findings were identified .2.5 Commitment 26: Implement the Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) Program as described in License Renewal Application, Section B.1.37. This new program will be implemented consistent with the

corresponding program described in NUREG 1801,Section XI.M12, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel Program. a. Inspection Scope

In the prior inspection, the inspectors noted that Entergy was planning to screen all cast

austenitic stainless steel components to determine which were potentially susceptible to a loss of fracture toughness. These components were to be further evaluated, using a refined analytical technique, to determine the components susceptibility to reduction in

fracture toughness. Entergy chose to perform a unique fracture mechanics analysis of

these components, which was in progress at the time of the prior inspection. The

inspector noted that there may be a question regarding the submittal of the analysis under ASME requirements, as stipulated in 10 CFR 50.55a.

Subsequently the inspector, in consultation with the Division of License Renewal,

determined submittal of the analysis was not required. During this inspection the

inspectors reviewed the completed evaluation of the screened components'

susceptibility to reduction in fracture toughness: Report 1300066.403, Revision 0, "Aging Management of CASS Piping at Indian Point 2, Flaw Tolerance Evaluation of CASS Piping at Indian Point," dated August 2013. The methodology of probabilistic

fracture mechanics determined a postulated starting reference flaw of one-quarter

thickness would remain below the maximum allowable flaw size during a 60 year life for

all components. Findings and Observations

No findings were identified.

.2.6 Commitment 27: Implement the Thermal Aging and Neutron Irradiation Embrittlement of Cast Austenitic Stainless Steel (CASS) Program as described in License Renewal

Application, Section B.1.38. This new program will be implemented consistent with the

5 Enclosure corresponding program described in NUREG-1801,Section XI.M13, Thermal Aging and Neutron Embrittlement of Cast Austenitic Stainless Steel program.

a. Inspection Scope

In the prior inspection, the inspectors noted a site document had not been developed

that defined and implemented the screening criteria of Electric Power Research Institute (EPRI) Technical Report 1013234, "Materials Reliability Program: Screening Categorization, and Ranking of Reactor Internals Components for Westinghouse and

Combustion Engineering PWR Design," (MRP-191), listed in Table 3-5, as applied to the

Indian Point components listed in Table 5-1 of EPRI Report 1022863, "Materials

Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines," (MRP-227-A).

During this inspection the inspectors reviewed Entergy Nuclear Engineering Report:

"Indian Point Energy Center: Thermal Aging and Neutron Irradiation Embrittlement of

Cast Austenitic Stainless Steel Aging Management Program," IP-RPT-13-00049, Revision 0, dated August 14, 2013. This report implemented the above screening criteria and ranking methodology for Indian Point.

Findings and Observations

No findings were identified. .2.7 Commitment 33: For the locations identified in License Renewal Application, Table 4.3-13 (IP2), update the fatigue usage calculations using refined fatigue analyses

to determine if Cumulative Usage Factors (CUF) remain less than 1.0 when accounting

for the effects of reactor water environment, using valid Fen factors. a. Inspection Scope

In the prior inspection, the inspectors noted that calculations documented in calculation

WCAP 17149-P, "Evaluation of Pressurizer Insurge/Outsurge Transients for Indian Point

Unit 2," and WCAP 17199-P, "Environmental Fatigue Evaluation for Indian Point Unit 2," concluded that cumulative fatigue usage factors, including reactor water environment effects, were below the American Society of Mechanical Engineers (ASME) Code

allowable value of 1.0 for transients postulated for 60 years of operation. The inspectors

noted Entergy's action plan included revising the Thermal Cycle Monitoring Program

procedure to reflect changes in the number of projected cycles used in WCAP 17199-P. During this inspection the inspectors reviewed Indian Point Programs and Components

Engineering Procedure 2-PT-2Y015, Revision 4, "Thermal Cycle Monitoring Program."

The inspectors noted the procedure was updated to reflect the number of allowable

cycles derived from the above analysis. The procedure referenced WCAP 17199-P and included a Table (Attachment 1) that included actual plant cycles rather than the number of cycles used in the original design calculations. The procedure also was revised to better reflect operational assumptions used and the bases for the revised calculations of

the WCAP.

6 Enclosure Findings and Observations No findings were identified.

.2.8 Commitment 40: Evaluate plant specific and appropriate industry operating experience and incorporate lessons learned in establishing appropriate monitoring and inspection

frequencies to assess aging effects for the new aging management programs. Documentation of the operating experience evaluated for each new program will be available on site for NRC review prior to the period of extended operation.

a. Inspection Scope During the prior inspection, there was insufficient material to review this commitment. Subsequently, Entergy completed an operational review for the following new aging

management programs embodied in separate commitments:

1. 3, Buried Piping and Tanks Inspection Program #14, Non-EQ Bolted Cable Connections Program #15, Non-EQ Inaccessible Medium-Voltage

1. 16, Non-EQ Instrumentation circuits Test Review Program

1. 17, Non-EQ Insulated Cables and Connections Program

1. 19, One-Time Inspection Program

1. 20, One-Time Small Bore Piping Program #23, Selective Leaching Program #26, Thermal Aging Embrittlement of Cast Austenitic Stainless Steel (CASS) Program # 27, Thermal Aging and Neutron Irradiation Embrittlement of Cast Austenitic Stainless Steel (CASS) Program. During this inspection the inspectors reviewed a selected sample of the reviews and

noted each of the programs was subject to an operational review which included Indian

Point specific experience. For example, the Buried Piping Program for Unit 2 was

assessed for a period of six years, 2007 through 2013. This period of time enveloped

the operational experience included in the guidance documents, such as Generic Aging Lessons Learn (NUREG-1801), Revision 2. External operational experience considered included license event reports, NRC generic letters, NRC information notices, and

Institute of Nuclear Power Operations (INPO) documents.

Findings and Observations

No findings were identified.

.2.9 Commitment 43: Indian Point Energy Center will review design basis ASME Code Class 1 fatigue evaluations to determine whether the NUREG/CR-6260 locations that

have been evaluated for the effects of the reactor coolant environment on fatigue usage are the limiting locations for the Unit 2 and Unit 3 configurations. If more limiting locations are identified, the most limiting location will be evaluated for the effects of the

7 Enclosure reactor coolant environment on fatigue usage. Indian Point Energy Center will use the NUREG/CR-6909 methodology in the evaluation of the limiting locations consisting of nickel alloy, if any.

a. Inspection Scope

In the prior inspection, the inspectors noted that Entergy had awarded contracts to perform calculations to support closure of this commitment. Because the results of the calculations were not available at the time, the inspectors deferred inspection of this

commitment.

During this inspection the inspectors reviewed calculation CN-PAFM-13-32, Revision 0, "Indian Point Unit 2 (IP2) and Unit 3 (IP3) Refined EAF Analyses and EAF Screening Evaluations." This calculation was the evaluation of locations previously screened by calculation CN-PAFM-12-35, Revision 1, "Indian Point Unit 2 and Unit 3 EAF Screening

Evaluations," that could be more limiting than the locations identified in

NUREG/CR-6260, "Application of NUREG/CR-5999 Interim Fatigue Curves to Selected Nuclear Power Plants Components." The inspectors noted the CUFen result for the pressurizer nozzle was 0.999 at 60 years. Entergy was aware that accumulation of

cycles at a rate greater than assumed in the calculation would require a more refined

analysis, application of a non-destructive monitoring technique, or replacement of the

pressurizer nozzle.

Findings and Observations No findings were identified.

.2.10 Commitment 48: Entergy will visually inspect in-scope underground piping prior to the period of extended operation and then on a frequency of at least once every 2 years

during the period of extended operation. Visual inspections will be supplemented with

surface or volumetric non-destructive testing if indications of significant loss of material

are observed. Adverse indications will be entered into the plant corrective action

program for evaluation of extent of condition and for determination of appropriate

corrective actions (e.g., increased inspection frequency, repair, or replacement). a. Inspection Scope

In the prior inspection the inspectors noted that work orders had been issued to perform

the inspections prior to the period of extended operation. The inspectors determined that additional inspection was merited regarding review of the results of the underground piping inspections.

The inspectors reviewed the results of selected inspections performed subsequent to the

May 23, 2013, NRC inspection. EN-EP-S-002-MULTI, Attachment 7.2 "Pipe/Tank

Coating Visual Inspection Checklist" was reviewed for the following lines:

8 Enclosure 21-EDGE-2/EDG FOST 3-inch equalizing line 21-EDGE-2/EDG FOST 4-inch fill line 21-EDGE-2/EDG FOST 4-inch vent line

22-EDGE-2/EDG FOST 3-inch equalizing line

22-EDGE-2/EDG FOST 4-inch fill line

22-EDGE-2/EDG FOST 4-inch vent line

23-EDGE-2/EDG FOST 3-inch equalizing line 23-EDGE-2/EDG FOST 4-inch fill line 23-EDGE-2/EDG FOST 4-inch vent line

The check list included the inspection of the piping for aging affects such as mechanical

damage, coating breaks (referred to as a holiday), and blistering. Findings and Observations

No findings were identified. 4OA6 Meetings, Including Exit On September 12, 2013, the inspectors presented the inspection results to Mr. John

Ventosa, Site Vice President, and other members of the Entergy staff. The inspectors

verified that no proprietary information was retained by the inspectors or documented in

this report.

ATTACHMENT: SUPPLEMENTARY INFORMATION

A-1 Attachment SUPPLEMENTARY INFORMATION KEY POINTS OF CONTACT Entergy Personnel J. Ventosa, Site Vice President N. Azevedo, Code Programs Supervisor C. Caputo, License Renewal Team

J. Curry, Senior Project Manager

G. Dahl, Licensing Engineer

P. Guglielmino, Implementation Team Manager L. Lubrano, Component Electrical Engineer R. Sporbert, One-Time Inspection Coordinator LIST OF ITEMS OPENED, CLOSED, DISCUSSED, AND UPDATED Closed

The inspectors determined that the following 10 commitments had been appropriately

implemented:

6 Fatigue cycles analysis 13 Metal enclosed bus inspection

19 One-time inspection

23 Selective leaching inspection

26 Embrittlement of CASS analysis 27 Embrittlement of CASS analysis 33 Fatigue monitoring

40 Operating experience for new programs

43 Fatigue monitoring analysis

48 Underground piping inspection

LIST OF ACRONYMS ADAMS Agencywide Documents Access Management System ASME American Society of Mechanical Engineers CASS Cast Austenitic Stainless Steel CFR Code of Federal Regulations

CUF Cumulative Usage Factor ENTERGY Entergy Nuclear Northeast

EPRI Electric Power Research Institute

INPO Institute of Nuclear Power Operations IPEC Indian Point Energy Center LRA License Renewal Application

MEB Metal-Enclosed Bus

A-2 Attachment MRP Materials Reliability Project NRC Nuclear Regulatory Commission UFSAR Updated Final Safety Evaluation Report

LIST OF DOCUMENTS REVIEWED

Commitment 6, 33, and 43 2-PT-2Y015, Revision 3, Thermal Cycle Monitoring Program

IP-RPT-11-LRD13, Revision 0, Review of the Fatigue Monitoring Aging Management Program for License Renewal Implementation EN-LI-100, Revision 13, Process Applicability Determination EN-AD-101, Revision 16, Procedure Process

WCAP-17199-P, July 2010, Environmental Fatigue Evaluation for Indian Point Unit 2

WCAP-17149-P, July 2010, Evaluation of Pressurizer Insurge/Outsurge Transients for Indian

Point Unit 2 Entergy Letter dated August 9, 2010 (NL-10-82), License Renewal Application - Completion of Commitment #33 Regarding the Fatigue Monitoring Program Indian Point Nuclear

Generating Unit Nos. 2 and 3 [ML102300504]

Commitment 13 2-ELC-016-BUS, Inspection, Cleaning and Testing of 480V Buses, Revision 2 CR-IP2-2009-03029, Water dripping at the bend in the electric tunnel

CR-IP2-2012-01903, Bus 5A surface rust noted on the interior divider panel

Work Order 52293872, Inspection of Bus 5A Switchgear and Station Service Transformer

Work Order 52294517, Inspection of Bus 5A (480 V Switchgear to EDG) 2-ELC-016-BUS, Revision 4, Inspection, Cleaning and Testing of 480V Buses 2-ELC-403-BUS, Revision 7, Inspection and Cleaning of 480 Volt Bus Duct

Work Order 351381, 21 EDG Bus Visual, Cleaning, Bolted Checks in Electrical Tunnel,

completed on July 18, 2013

Work Order 351382, 22 EDG Bus Visual, Cleaning, Bolted Checks in Electrical Tunnel,

completed on June 12, 2013 Work Order 351448, 23 EDG Bus Visual, Cleaning, Bolted Checks in Electrical Tunnel, completed on August 12, 2013

CR-IP2-2013-01738, MEB acceptance criteria

CR-IP2-2013-01748, Leaks in Unit 2 electrical tunnel

CR-IP2-2013-02375, 22 EDG bus inspection CR-IP2-2013-02923, 21 EDG bus inspection CR-IP2-2013-03330, 23 EDG bus inspection

CR-IP2-2013-02912, Thermography procedures

CR-IP2-2013-02913, Water intrusion into Unit 2 electrical tunnel

A-3 Attachment Commitment 19 IP-RPT-11-LRD28, Revision 0, Review of the One-Time Inspection Program

EN-FAP-LR-024, Revision 1, One-Time Inspection

NL-13-046, Amendment 13 to LRA for One-Time Inspection and Selective Leaching Programs,

March 18, 2013

IPEC Unit 2 One-Time Inspection Tracking Matrix, May 3, 2013 and May 21, 2013 20 Inspection reports for one-time inspections IP-RPT-13-LRD03, Revision 0, Unit 2 License Renewal One-Time Inspection Summary Report IPEC Unit 2 One-Time Inspection Tracking Matrix, August 28, 2013

20 Additional inspection reports for one-time inspections

Commitment 23 IP-RPT-11-LRD34, Revision 0, Review of the Selective Leaching Program

EN-FAP-LR-02, Revision 3, Selective Leaching Inspection

NL-13-046, Amendment 13 to LRA for One-Time Inspection and Selective Leaching Programs, March 18, 2013 IPEC Unit 2 Selective Leaching Inspection Tracking Matrix, May 20, 2013

10 Inspection reports for copper-alloy selective leaching inspections

12 Inspection reports for gray cast iron selective leaching inspections

WO 00326036-01

WO 00326216-01 IP-RPT-13-LRD07, Revision 0, License Renewal Selective Leaching Inspection Summary Report Altran 13-0313-TR-001, Laboratory Analysis of Several Valves for Selective Leaching, Revision 0 Altran 13-0313-TR-001, Laboratory Analysis of Several Valves for Selective Leaching, Revision 1 CR-IP2-2013-03037, Selective leaching of gray cast iron components

CR-IP2-2013-03360, Selective leaching of copper alloy components

Commitment 26 Entergy Letter, NL-09-018, "Reply to Request for Additional Information - Miscellaneous Items," January 27, 2009

Entergy Letter NL-11-101, "Clarification for Additional Information (RAI) Aging Management Programs," August 22, 2011

LR# 173, LR Request, Confirm each AMP will be implemented with ten elements IP-RPT-11-LRD38, "Review the Thermal Aging Embrittlement of CASS Aging Management Program for License Renewal Implementation," 1/2/2013

NRC Letter, "License Renewal Issue No. 98-0030, "Thermal Aging Embrittlement of Cast

Austenitic Stainless Steel Components," May 19, 2000

WCAP-10977, Supplement 1, "Additional Information in Support of the Technical Justification for

Eliminating Large Primary LOOP Pipe Rupture as the Structural Design Basis for Indian Point Unit 2," January 1989

A-4 Attachment Commitment 27 IP-RPT-11-LRD39, Revision), "Review of the Thermal Aging & Neutron Embrittlement of CASS

Aging Management Program for License Renewal Implementation," ED41109,

1/23/2013

EPRI 1013234 "Materials Reliability Program: Screening, Categorization, and Ranking of Reactor Internals Components for Westinghouse and Combustion Engineering PWR Design (MRP-191)," November 2006 EPRI 1022863 "Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A)," December 2011

NRC Letter "Request for Additional Information for the Review of the Indian Point Nuclear

Generating Unit Nos. 2 and 3, License Renewal Application," May 15, 2012 Entergy Letter, NL-11-101, "Clarification for Request for Additional Information (RAI) Aging Management Programs," 8/22/2011

Entergy Letter NL-13-052, "Reply to Request for Additional Information Regarding the License

Renewal Application," 5/7/2011

LR Request #173 Confirm new programs will be implemented consistent with 10 elements of NUREG-1801. IP-RPT-11-LRD39 "Review of the Thermal Aging and Neutron Irradiation Embrittlement of

CASS Aging Management Program for License Renewal Implementation," EC41109, 1/2/13

Commitment 48 Work Order PMRQ 00349816-01, 23 Fuel Oil Storage Tank Underground Piping Inspections Work Order PMRQ 00349802-01, 21 Fuel Oil Storage Tank Underground Piping Inspections

Work Order PMRQ 00349814-01, 22 Fuel Oil Storage Tank Underground Piping Inspections

Work Order 00342492-01, Inspect Underground Piping by the IP2 EDG Building DF-2 Area

Work Order 00342493-01, Inspect Underground Piping by the IP2 EDG Building DF-2-1 Area Work Order 00342494-01, Inspect Underground Piping by the IP2 EDG Building DF-2-2 Area