NL-14-121, Indian Point, Unit 2, Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 25

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Indian Point, Unit 2, Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 25
ML14287A278
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Site: Indian Point Entergy icon.png
Issue date: 09/17/2014
From: Ventosa J A
Entergy Nuclear Operations
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Document Control Desk, Office of Nuclear Reactor Regulation
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NL-14-121
Download: ML14287A278 (24)


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Enter-qy Nuclear Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel 914 254 6700 John A. Ventosa Site Vice President NL-14-121 September 17, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-2738

Subject:

Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (UFSAR). Revision 25 Indian Point Nuclear Generating Unit No. 2 Docket No. 50-247 License No. DPR-26

References:

1. Entergy Letter NL-13-130, dated September 26, 2013, "Indian Point 2 Nuclear Power Plant Amendment Update to the Updated Final Safety Analysis Report (UFSAR), Revision 24 for License Renewal and Period of Extended Operation" 2. NEI 98-03, "Guidelines for Updating Final Safety Analysis Reports," Revision 1, June 1999 3. NEI 99-04, "Guidelines for Managing NRC Commitments," Revision 2, December 1995

Dear Sir or Madam:

Entergy Nuclear Operations, Inc. (Entergy), in accordance with 10 CFR 50.71(e), hereby transmits the most recent update to the Updated Final Safety Analysis Report (UFSAR)for Indian Point Unit 2 (IP2). This submittal incorporates applicable changes made to the IP2 facility since the UFSAR update in September 2012, through the information available, at a minimum, as of March 19, 2014, the completion of the last IP2 refueling outage. This submittal constitutes the twenty-fifth (25) revision to the IP2 UFSAR. Note that revision twenty-four to the IP2 UFSAR was submitted in September 2013 to only incorporate changes due to License Renewal (Reference 1).Entergy is submitting one copy of the entire IP2 UFSAR, IP2 Technical Specification Bases, IP2 Technical Requirements Manual (TRM), and the Holtec International,"Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center" in the electronic medium of Adobe PDF on CD-ROM in accordance with 1kos-NL-14-121 Docket Nos. 50-247 Page 2 of 3 the guidance contained in NRC, "General (Non-Adjudicatory)

Electronic Submission Instructional Guide," June 11, 2009, Revision 4.UFSAR changes to the text and tables since the last revision are indicated by gray highlighted background rather than a revision bar next to the line containing the change.Any UFSAR figures that have been revised since the last revision contain "Rev. 25" in the figure title block.This update to the FSAR also contains information that has been classified as"Historical" information according to the NEI 98-03 definition (Reference 2), and is no longer subject to updating.

Material designated as "Historical" information in the UFSAR is indicated by a green highlighted background.

Attachment 1 to this letter, "Summary Report of IP2 UFSAR Revision 25 Changes," contains a summary with a brief description of the information changed in this revision to the IP2 UFSAR.IP2 Technical Specification 5.5.12.d, "Technical Specification Bases Control Program," requires that changes to the Bases implemented without prior NRC approval be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

The required information is provided in Attachment 2, "Summary of Revisions to the IP2 Technical Specification Bases" and the entire document is provided on the enclosed CD-ROM.As specified in NEI 98-03 (Reference 2), the Technical Requirements Manual (TRM) is controlled in a manner consistent with procedures fully or partially described in the UFSAR. Under this approach, the TRM document is subject to the change control requirements of 10 CFR 50.59 and the update/reporting requirements of 10 CFR 50.71(e).

The required information is provided in Attachment 3, "Summary of Revisions to the IP2 Technical Requirements Manual (TRM)," and the entire document is provided on the enclosed CD-ROM.Attachment 4, "Revisions to IP2 Docketed Commitments," submits a summary update of all changes made to the Unit 2 docketed commitments using the NEI 99-04 guidance (Reference

3) for determination of commitments which do not have either a safety or regulatory significance, which may be changed without prior interaction with the NRC staff and which require periodic NRC staff notification either annually or along with the FSAR updates as required by 10 CFR 50.71(e).As specified in NEI 98-03 (Reference 2), the Holtec International, "Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center" is a licensee controlled document that is explicitly "incorporated by reference" into the IPEC IP2 and IP3 UFSARs. Under this approach, the referenced document is subject to the change control requirements of 10 CFR 50.59 and the update/reporting requirements of 10 CFR 50.71(e).

The entire document is provided on the enclosed CD-ROM.There are no new commitments contained in this letter. In the event of any questions, please contact Mr. Robert W. Walpole, Manager, Regulatory Assurance at 914-254-6710.

NL-14-121 Docket Nos. 50-247 Page 3 of 3 I declare under penalty of perjury that the foregoing is true and correct.9/ 7//l/Executed on Date Sincerely, JAV/gd Attachments:

1. Summary Report of IP2 UFSAR Revision 25 Changes 2. Summary of Revisions to the IP2 Technical Specification Bases 3. Summary of Revisions to the IP2 Technical Requirements Manual (TRM)4. IP2 Commitment Change Summary Report

Enclosure:

CD-ROM containing the IP2 UFSAR (Rev. 25) files, entire documents of the IP2 T.S. Bases, IP2 TRM, and Rev. 6 of the Holtec International Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at IPEC cc w/o enclosure:

Mr. William M. Dean, Regional Administrator, NRC Region I Mr. Douglas V. Pickett, Senior Project Manager, NRC NRR DORL Ms. Bridget Frymire, New York State Department of Public Service Mr. John B. Rhodes, President and CEO, NYSERDA NRC Resident Inspectors Attachment 1 to NL-14-121 Summary Report of IP2 UFSAR Revision 25 Changes ENTERGY NUCLEAR OPERATIONS, INC.Indian Point Nuclear Generating Unit No. 2 Docket No. 50-247 License No. DPR-26 NL-14-121 Docket No. 50-247 Attachment 1 Page 1 of 11 Summary Report of IP2 UFSAR Revision 25 Changes UFSAR AFFECTED PAGES, SOURCE(S) of CHANGE, SECTION TABLE, FIGURE EC, 50.59, PAD, SCREEN INFORMATION

/ DESCRIPTION OF CHANGES NOs Instructions 1,2 CR-IP3-2014-00425 Correction of errors from 2013 update (see CR-IP3-2014-00425 CA-2 4.1 T4.1-8 LBDCR U2-2013-License attachment titled "IP2 R24 & IP3 R5 FSAR EOC Review Results")4.2 T4.2-5 Renewal 4.5.2 64 Changes originally made in 2013 per Commitment via A.2.0, 2 RA-1 3-132 A.2.1.8, 7 A.2.1.16, 12 A.2.1.28, 21 A.2.1.39 26 Typographical in 2014 A.1 1 A.2.1.5 4 A.2.1.17 12 A.2.1.19 13 A.2.1.23 15 A.2.1.26 17,18,19 A.2.1.28 21 A.2.1.35 24 A.2.1.41 28 A.2.2.1.3 30 A.2.2.2.1 30 A.2.2.6 32"Ta-ble -. .dtral -.. .Correc-tion oeftitJesf hp ters 5 ; l and 1 3a-nd,: additi6ornofo

{r aQfp .,, -..a l: ,5 ..

NL-14-121 Docket No. 50-247 Attachment 1 Page 2 of 11 Summary Report of IP2 UFSAR Revision 25 Changes UFSAR AFFECTED PAGES, SOURCE(S) of CHANGE, SECTION TABLE, FIGURE EC, 50.59, PAD, SCREEN INFORMATION

/ DESCRIPTION OF CHANGES NOs Chapter-1 1.1 1 Amendment 241 Changes due to stretch power uprate -previously incorporated in R20 CR-lP2-2005-05192

-now correcting a prior typo 1.9.2 35 Editorial Add Revisions 24 and 25 to list of revisions 1.10.3 36 QAPM Revise Organization and Responsibilities section to replace obsolete information with information from QAPM Section A.2 1.11.6.3 63 EC-32468 EC reduced the Unit 1 vent stack height to approximately El. 202'.This reduction will make the stress analysis summary discussed in Unit 2 UFSAR conservative and the section is being revised to represent the correct information.

1.11.4.8 46 Typographical Change "Ofy" to "(fy" Chapter 2: 2.5 30 CCR log of River Water Include 9 feet 8 inches water level recorded onsite during November Level 2012 extra-tropical Superstorm Sandy in Section 2.5 2.8 37 TS Amend. #90 RETS Removal of obsolete and excessive information PAD NL-14-121 Docket No. 50-247 Attachment 1 Page 3 of 11 Summary Report of IP2 UFSAR Revision 25 Changes UFSAR AFFECTED PAGES, SOURCE(S) of CHANGE, SECTION TABLE, FIGURE EC, 50.59, PAD, SCREEN INFORMATION I DESCRIPTION OF CHANGES NOs Chapter 3 3.2.1.1.1.5 11 ER-05-2-090 Updates for Cycle 18 core design -previously incorporated in R20 -now correcting a prior typo ("analyses")

3.0 1 EC-39344 Changes due to new core design for Cycle 22 3.1.1 1 3.2.1.3 23 3.2.3.2.1.1 43,44,47 3.2.3.2.1.3 50 3.2.3.2.1.4 50 3.2.6 59,60 3.2 65,66 References 3.2 T3.2-1A, T3.2-7, F3.2-68A, F3.2-68B, 82 3.2.1.2.1 15 WCAP-7308-L-P-A, Clarify the measurement uncertainty from the flux map based on the Section L, Addendum 1, number of available thimbles, where 75% of available thimbles is 3.2.1.2.5 19 Revision 1 to UPDATE to required WCAP-7308-L, "Evaluation of Nuclear Hot Channel Factors Uncertainties" NL-14-121 Docket No. 50-247 Attachment 1 Page 4 of 11 Summary Report of IP2 UFSAR Revision 25 Changes UFSAR AFFECTED PAGES, SOURCE(S) of CHANGE, SECTION TABLE, FIGURE EC, 50.59, PAD, SCREEN INFORMATION I DESCRIPTION OF CHANGES NOs 3.2.1.2.7.1 22 Editorial Change "moderate" to "moderator" in Section 3.2.1.2.7.1; change 3.2.2.1.2 26 "Departure from nucleate boiling" to "Departure from Nucleate Boiling)and "predicted" to "predicated" in Section 3.2.2.1.2; identification of T3.2-7 historical information on Table 3.2-7 Chapter 4 4.2.2.8 27 ER-05-2-114 Pressurizer spray valves were modified to delete the leakoff lines to the RCDT. Now correcting prior typo -changed "of' to "or" in last sentence 4.3.4.1 56 EC-39129 RCS heatup and cooldown curves and LTOPs Technical Specification 4.3 60 PAD for 48EFPY operation and LTOPs setting requirements References Tech Spec Amend #274 A.2.2.1.2 29 LR-LAR-2014-00124 CA-2 (to include in License Renewal Application)

Amendment 16 4.5.2 64 NRC Letter dated 1/14/14 Revision of the reactor vessel surveillance specimen withdrawal (RA-14-009) schedule to cover the additional twenty year period of extended operation 38 Removal of excessive Modified 3 rd sentence in 5 th paragraph

-added comma, deleted detail "expected" and "licensed life" NL-14-121 Docket No. 50-247 Attachment 1 Page 5 of 11 Summary Report of IP2 UFSAR Revision 25 Changes AFFECTED PAGES, TABLE, FIGURE SOURCE(S) of CHANGE, EC, 50.59, PAD, SCREEN NOs INFORMATION

/ DESCRIPTION OF CHANGES 5.1.5 50 Typographical 1 st paragraph, next-to last sentence -corrected spelling of re-analyzed in "component supports were re-analzed" 5.2 T5.2-1 (Item 70) EC-42090 Provide indication in CCR for Source Range and RCS Thot & RCS F5.2-28 Tcold for selected SG WR level loops. Add a radiant energy heat shield to ASSS instrument racks 19A and 21A.Chapter 6 6.2 T6.2-2 Formatting and Formatting and typographical corrections of the tables T6.2-3 typographical T6.2-3 -singularized "supplier' in several places T6.2-4 T6.2-8 App 6C -added periods to References 21 through 43 T6.2-9 T6.2-1 0 T6.2-11 T6.2-12 T6.2-13 T6.2-14 App 6B 140 App 6C 145, T6C-6 6.2.2.1.2 12 PAD & Screen for Sump Changes to Chapters 6, 7, and 14 to incorporate sump modification modification previously incorporated in R20 -now correcting 2 prior typos NL-14-121 Docket No. 50-247 Attachment 1 Page 6 of 11 Summary Report of IP2 UFSAR Revision 25 Changes UFSAR AFFECTED PAGES, SOURCE(S) of CHANGE, SECTION TABLE, FIGURE EC, 50.59, PAD, SCREEN INFORMATION

/ DESCRIPTION OF CHANGES NOs 6.4.3.6 91 ER-IP2-04-30350 Removal of excessive detail regarding the electrical insulation rating 6.4 92 PAD and construction characteristics of the Containment recirculation fan 6.4e92nPAD motors and regarding fan motor testing -previously incorporated in References R20 -now correcting 3 prior typos in 6.4.3.6, correcting 1 typo and 7.1.3.3 4 adding 1 omitted item in 6.4 References ,and adding 2 items mistakenly deleted in 7.1.3.3 Chapter :7.7.2.3.2.3.5 29 Tech Spec Amendment Delete references to Cases C and D which were eliminated following 241 Editorial (mistakenly re-analysis for Stretch Power Uprate, and delete a redundant sentence not included in previous LBDCR 2005-14-00-001) 7.2.4.1.3 32 Typographical Corrected "thichness" in 3 rd paragraph 5 th sentence Chapter 9 9.5.2.2.9 82 PAD Change to allow N5000 and vacuum grease on areas of the STC lid where the coating on the carbon steel surfaces was found to be Holtec Licensing Report damaged as a result of the wet fuel storage operation WO 325861 Task 4 9.5.2.2.5 81 Editorial and typographical Correction of "tolls" to "tools", adding "of' to "safety factor of 11.49:1", deletion of 5 commas (typographical)

NL-14-121 Docket No. 50-247 Attachment 1 Page 7 of 11 Summary Report of IP2 UFSAR Revision 25 Changes UFSAR AFFECTED PAGES, SOURCE(S) of CHANGE, SECTION TABLE, FIGURE EC, 50.59, PAD, SCREEN INFORMATION

/ DESCRIPTION OF CHANGES NOs 9.6.1.2 T9.6-1 EC-40622 Reanalysis of CCW system to gain analytical operating margin for the pumps 9.8.2 110 PAD Changes resulting from the Engineering evaluation of the acceptability of the modified field configuration regarding the fresh air supply louver T9.8-1 EC37660 210 for the Waste Storage Tank Pit area of the PAB Chapter 10 10.2 20 PAD Change to reflect that instrument air is not credited post accident and the need for a nitrogen supply for operability until locally manned Chapter 12 12.1.2 1 NRC TS Amend. #271 Approved change to the Entergy QAPM and associated plant Tech Specs regarding staff qualifications 12.1.1 1 Editorial Title changes: "Plant Manager" to "General Manager, Plant 12.2 2 Operations;". "watch engineers" to "Shift Technical Advisors" Chapter 13 13.6.1 40 Reformatting Minor changes to core loading verification and "Determination of Zero Power Flux Level" that were not previously incorporated NL-14-121 Docket No. 50-247 Attachment 1 Page 8 of 11 Summary Report of IP2 UFSAR Revision 25 Changes UFSAR AFFECTED PAGES, SOURCE(S) of CHANGE, SECTION TABLE, FIGURE EC, 50.59, PAD, SCREEN INFORMATION I DESCRIPTION OF CHANGES NOs Chapter 14 14.1.5.2.1 15 EC-44828 Defining "neutron source" as secondary source assemblies, primary source assemblies, or irradiated fuel assemblies T14.2-8 91 Typographical and format Correcting misspelling and formatting table T14.2-9 14.2.1 54, 55 PAD Revise due date for Spent Fuel Pool BADGER testing from 2012 to 2013 based on the most recent analysis from vendor report on the References 85 NETCO letter 12/12/12 prediction of Boraflex in the pool. Also, allow credit for Boraflex Monitoring Program as described in the License Renewal Application.

14.3.3.2.1 102 Typographical and editorial Typographical:

correction of 2 misspellings and deletion of apostrophe 14.3.3.3.1 105,106 in 14.3.3.3.1 14.3.3.3.3 107 Editorial:

14.3.3.2.1 2.2b -changed "to" to "with"; 14.3.3.3.3

-added"in" to "is presented in Section 5.3; deleted "Indian Point Unit 2" from 14.3.3.3.4 107,108 14.3.3.3.3, 14.3.3.3.4, 14.3.3.3.5, 14.3.3.3.6; 14.3.3.3.5

-changed"Table 14.3-5-A" to "Table 14.3-5A" 14.3.3.3.5 108 14.3.3.3.6 108,109 NL-14-121 Docket No. 50-247 Attachment 1 Page 9 of 11 Summary Report of IP2 UFSAR Revision 25 Changes UFSAR AFFECTED PAGES, SOURCE(S) of CHANGE, SECTION TABLE, FIGURE EC, 50.59, PAD, SCREEN INFORMATION

/ DESCRIPTION OF CHANGES NOs 14.3 T14.3-5A Typographical and Corrected typographical error in T14.3-5A footnote "*" ("esulted");

T14.3-19 formatting reformatted T14.3-19, T14.3-20, T14.3-29, T14.3-30, T14.3-34, T14.3-20 T14.3-35, T14.3-36, T14.3-37, T14.3-43, T14.3-45, T14.3-46, T14.3-T14.3-29 49, T14.3-50, T14.3-51, T14.3-52 T14.3-30 T14.3-34 T14.3-35 T14.3-36 T14.3-37 T14.3-43 T14.3-45 T14.3-46 T14.3-49 T14.3-50 T14.3-51 T14.3-52 NL-14-121 Docket No. 50-247 Attachment 1 Page 10 of 11 Summary Report of IP2 UFSAR Revision 25 Changes UFSAR AFFECTED PAGES, SOURCE(S) of CHANGE, SECTION TABLE, FIGURE EC, 50.59, PAD, SCREEN INFORMATION

/ DESCRIPTION OF CHANGES NOs 14.3.1 93 Amendment 248 Changes as a result of the use of Westinghouse Best Estimate Large Break Loss-of-Coolant Accident (BE-LBLOCA) analysis methodology

-14.3.3.1.1 98,100 WCAP-16009-P-A previously incorporated in R20 -now correcting following errors 14.3.3.2.1 101-104 (number in parentheses indicates number of errors in the section): 14.3.3.3.1 105, 106 Omissions:

14.3.1 (1), 14.3.3.1.1 (2), 14.3.3.2.1 (6), 14.3.3.3.1 (3), 14.3.3.3.3 107 14.3.3.3.3 (1)Prior typos- 14.3.3.1.1 (1), 14.3.3.2.1 (7), 14.3.3.3.1 (8)14.3.3.3.5 108 Appendix A A.2.1.28 21 PAD Delete GT3 black start diesel from Periodic Surveillance and Preventive Maintenance Program, and the Closed Cooling Water A.2.1.39 26, 27 CR-IP2-2013-04379 Program Amendment 15 to License Renewal Application (NL-13-152)A.2.1.11 8 Revisions to the License A.2.1.41 -added commitment to replace split pins in 2R22;A.2.1.41, 28 Renewal Application by A.2.2.21 -Deleted "reactor vessel internals" from the list of Class 1 A.2.2.21, 30 letters NL-13-122 and NL- metal fatigue components A.2.2.2.3, 31 14-067 A.2.2.2.3

-new section to discuss reactor vessel internals A.2.2.2.4 31 A.2.2.2.4

-renumbered previous A.2.2.2.3 (Environmental Effects on Fatigue)

NL-14-121 Docket No. 50-247 Attachment 1 Page 11 of 11 Summary Report of IP2 UFSAR Revision 25 Changes UFSAR AFFECTED PAGES, SOURCE(S) of CHANGE, SECTION TABLE, FIGURE EC, 50.59, PAD, SCREEN INFORMATION I DESCRIPTION OF CHANGES NOs A.2.2.1.4 30 Editorial Editorial correction FROM "All remaining plate and weld beltline materials meet the requirement of exceed 50 ft-lb at 48 EFPY" TO "All remaining plate and weld beltline materials meet or exceed the requirement of 50 ft-lb at 48 EFPY."

Attachment 2 to NL-14-121 Summary of Revisions to the IP2 Technical Specification Bases ENTERGY NUCLEAR OPERATIONS, INC.Indian Point Nuclear Generating Unit No. 2 Docket No. 50-247 License No. DPR-26 NL-14-121 Docket Nos. 50-247 Attachment 2 Page 1 of 2 Summary of Revisions to the IP2 Technical Specification Bases (Since last reported October 1, 2012)BASES UPDATE PACKAGE 43-12202012 B 3.3.3 4 12/20/2012 Bases change to reflect Amendment 270 sump level indication changes B 3.7.5 5 12/20/2012 Bases changes to clarify AFW pump requirements for less than 100% capacity B 3.7.13 3 12/20/2012 Bases change to clarify Badger testing requirements BASES UPDATE PACKAGE 44- 12202013 B 3.5.4 2 12/20/2013 Bases change to allow RWST valves that isolate non-seismic piping to be opened under administrative control for filtration until the end of RFO 22 (Amendment 273)BASES UPDATE PACKAGE 45- 01152014 B 3.2.1 1 01/15/2014 Bases change to clarify that the FQ(Z) measurement uncertainty of 5% is based on 75% available thimbles B 3.2.2 2 01/15/2014 Bases change to clarify that the FA measurement uncertainty of 4% is based on 75% available thimbles BASES UPDATE PACKAGE 46 -03052014 B 3.4.3 2 03/05/2014 Bases change to reflect Amendment 274 for 48 EFPY P-T and LTOP limits B 3.4.12 2 03/05/2014 Bases change to reflect Amendment 274 for 48 EFPY P-T and LTOP limits NL-14-121 Docket Nos. 50-247 Attachment 2 Page 2 of 2 Summary of Revisions to the IP2 Technical Specification Bases (Since last reported October 1, 2012)BASES UPDATE PACKAGE 47- 07312014 B 3.3.2 B 3.3.7 B 3.4.12 B 3.4.13 B 3.4.14 B 3.4.15 B 3.5.3 B 3.5.4 B 3.6.6 B 3.6.7 B 3.7.7 B 3.7.8 B 3.7.9 B 3.7.10 B 3.7.12 B 3.7.13 B 3.8.1 B 3.8.4 B 3.8.7 B 3.8.9 7/31/2014 7/31/2014 7/31/2014 7/31/2014 7/31/2014 7/31/2014 7/31/2014 7/31/2014 7/31/2014 7/31/2014 7/31/2014 7/31/2014 7/31/2014 7/31/2014 7/31/2014 7/31/2014 7/31/2014 7/31/2014 7/31/2014 7/31/2014 Change End State from Mode 5 to Mode 4 Change End State from Mode 5 to Mode 4 Clarify single failure for SR 3.4.12.1,2,3 Change End State from Mode 5 to Mode 4 Change End State from Mode 5 to Mode 4 Change End State from Mode 5 to Mode 4 Change End State from Mode 5 to Mode 4 Change End State from Mode 5 to Mode 4 Change End State from Mode 5 to Mode 4 Change End State from Mode 5 to Mode 4 Change End State from Mode 5 to Mode 4 Change End State from Mode 5 to Mode 4 Change End State from Mode 5 to Mode 4 Change End State from Mode 5 to Mode 4 Credit for Boraflex Monitoring Program Credit for Boraflex Monitoring Program Change End State from Mode 5 to Mode 4 Change End State from Mode 5 to Mode 4 Change End State from Mode 5 to Mode 4 Change End State from Mode 5 to Mode 4 BASES UPDATE PACKAGE 48 -08212014 B 3.6.4 2 7/21/2014 TS Amend 276 to use 4 Fan Cooler Units B 3.6.5 3 7/21/2014 TS Amend 276 to use 4 Fan Cooler Units B 3.6.6 5 7/21/2014 TS Amend 276 to use 4 Fan Cooler Units Attachment 3 to NL-14-121 Summary of Revisions to the IP2 Technical Requirements Manual (TRM)ENTERGY NUCLEAR OPERATIONS, INC.Indian Point Nuclear Generating Unit No. 2 Docket No. 50-247 License No. DPR-26 NL-14-121 Docket Nos. 50-247 Attachment 3 Page 1 of 1 Summary of Revisions to the IP2 Technical Requirements Manual (TRM)(since last reported October 1, 2012)AFFECTED NEW EFFECTIVE DESCRIPTION SECTIONS REV# DATE B3.3.B 3 11/28/2012 Corrected the Bases reference from FT-956 to FT-946 3.7.D / 2 11/28/2012 Revised the TRM and Bases for the electrical tunnel B3.7.D fans and louvers to adopt a standard TRM format for HVAC systems. This added a required action for when a single fan was not restored in the required time and an action statement for 2 Fans out of service. Also added specific surveillances for the fans and dampers.3.7.G / 0 11/28/2012 Created a TRM with Bases for Plant Aux Building, B3.7.G Diesel Generator Building, Switchgear Room, and 3.7.H / Control Room Ventilating systems using a consistent B3.7.H format and content requirement for all 3.7.1/B3.7.1 3.7.J /B3.7.J 5.0 12 11/28/2012 Revised TRM 5.2.A and 5.5.L to reference procedure EN-LI-1 13 for making TRM changes rather than site procedure IP-SMM-LI-1 13 3.8.B / 2 8/13/2013 Revised TRM and Bases to clarify the use of the IP3 B3.8.B SBO / App R diesel as an independent diesel when the IP2 SBO / App R diesel was out of service. Added a SR to assess the electrical path.3.7.G / 7/10/2013 Revised the TRM and associated Basis to reflect a B3.7.G condition where one PAB exhaust fan is inoperable or both fans are inoperable and the plenum needs to be accessed for maintenance or testing 3.4.E / 2 3/21/2014 Revised the TRM and associated Bases to reflect B3.7.E License Amendment 274 changing the EFPY and required pressurizer safety arming temperature changes 3.7.A / 2 3/21/2014 Revised the TRM and associated Bases to reflect the B3.7.A use of the ASME OM Code requirements for the examination and testing of snubbers 3.7.D / 3 3/21/2014 Revised the TRM and associated Bases to reflect the B3.7.D removal of the gravity dampers from the electrical tunnel exhaust fans Attachment 4 to NL-14-121 IP2 Commitment Change Summary Report ENTERGY NUCLEAR OPERATIONS, INC.Indian Point Nuclear Generating Unit No. 2 Docket No. 50-247 License No. DPR-26 NL-14-121 Docket Nos. 50-247 Attachment 4 Page 1 of 1 IP2 COMMITMENT CHANGE

SUMMARY

REPORT (Since last reported October 1, 2012)COMMITMENT CURRENT CHANGED DESCRIPTION NUMBER STATUS DATE A-10450 Closed 3/7/14 Original Commitment

==

Description:==

Entergy will incorporate instructions into applicable fleet/site guidance for IPEC to activate the expanded response capability and to integrate this capability into the existing augmented emergency response organization structure based upon the following conditions as described in Nuclear Energy Institute 12-01, Revision ), dated May 2012.Revised Commitment

==

Description:==

Commitment Description remains the same -commitment date has been revised per NL-14-034 to June 25, 2014 Note: NRC was notified of this change in Entergy letter NL-14-034 dated February 27, 2014. The commitment has subsequently been Closed.

INDIAN POINT ENERGY CENTER (IPEC)UNIT 2. Docket No. 50-247 Entergy Letter NL-14-121 September 17, 2014 File Naming Table Document Title File Name Multiple File Document -Indian Point 2 UFSAR, Rev. 25 001_1.1 Introduction and Chapter 1, Introduction and Summary Summary.pdf Chapter 1, Figures 001_1.2 Ch 1 Figures.pdf 1 Chapter 2, Site and Environment 1002_2.1 Site and Environment.pdf Chapter 2, Figures 002_2.2 Ch 2 Figures.pdf Chapter 3, Reactor 003_3.1 Reactor.pdf Chapter 3, Figures 003_3.2 Ch 3 Figures.pdf Chapter 4, Reactor Coolant System 004_4.1 Reactor Coolant Sys.pdf IChapter 4, Figures 004_4.2 Ch 4 Figures.pdf Chapter 4, Plant Drawings 004_4.3 Ch 4 Drawings.pdf Chapter 5, Containment Systems 005_5.1 Containment Sys.pdf Chapter 5, Figures 005_5.2 Ch 5 Figures.pdf Chapter 5, Plant Drawings 005_5.3 Ch 5 Drawings.pdf 006_6.1 Engineered Safety Chapter 6, Engineered Safety Features Features.pdf Chapter 6, Figures 1006_6.2 Ch 6 Figures.pdf Chapter 6, Plant Drawings 006_6.3 Ch 6 Drawings.pdf Chapter 7, Instrumentation and Control 007_7.1 Instrumentation

& Control.pdf Chapter 7, Figures 007_7.2 Ch 7 Figures.pdf Chapter 7, Plant Drawings 007_7.3 Ch 7 Drawings.pdf Chapter 8, Electrical Systems 008_8.1 Electrical Systems.pdf Chapter 8, Figures 008_8.2 Ch 8 Figures.pdf Chapter 8, Plant Drawings 1008_8.3 Ch 8 Drawings.pdf Chapter 9, Auxiliary and Emergency Systems 0099.1 Auxiliary and Emergency Chapter 9, Figures 1009_9.2 Ch 9 Figures.pdf Chapter 9, Plant Drawings 1009_9.3 Ch 9 Drawings.pdf 1

INDIAN POINT ENERGY CENTER (IPEC)UNIT 2. Docket No. 50-247 Entergy Letter NL-14-121 September 17, 2014 File Naming Table (continued)

Document Title File Name Multiple File Document -Indian Point 2 UFSAR, Rev. 25 Chapter 10, Steam and Power Conversion 010_10.1 Steam and Power System Conversion Sys.pdf Chapter 10, Figures [010 10.2 Ch 10 Figures.pdf Chapter 10, Plant Drawings [010_10.3 Ch 10 Drawings.pdf Chapter 11, Waste Disposal and Radiation 011 11.1 Waste Disposal and Rad Protection System Protection Sys.pdf Chapter 11, Figures 011_11.2 Ch 11 Figures.pdf Chapter 11, Plant Drawings 011_11.3 Ch 11 Drawings.pdf Chapter 12, Conduct of Operations 1012_12.1 Conduct of Operations.pdf Chapter 13, Tests and Operations 013_13.1 Tests and Operations.pdf Chapter 14, Safety Analysis 014_14.1 Safety Analysis.pdf

'Chapter 14, Section 14.1 Figures 014_14.2 Ch 14.1 Figures.pdf Chapter 14, Section 14.2 Figures 014 14.3 Ch 14.2 Figures.pdf ,Chapter 14, Section 14.3 Figures 014_14.4 Ch 14.3 Figures.pdf IA dA, License Renewal 015_15.1 App A, Lic Renewal.pdf Instructions and Key 016_16.1 Instructions and Key.pdf ITable of Contents 1017_17.1 TOC.pdf Single File Documents Indian Point 2 Technical Requirements Manual 001_IP2 TRM.pdf (TRM)Indian Point 2 Technical Specification Bases 002_1P2 Tech Spec Bases.pdf IrHoltec Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel 003_Holtec Lic Report.pdf 2