ML16280A153
Text
Inc. Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel 914 254 6700 Anthony J. Vitale Site Vice President
Subject:
Indian Point Unit No. 2 Amendment Update to the Updated Final Safety Analysis Report (UFSAR), Revision 26 Indian Point Nuclear Generating Unit No. 2 Docket No. 50-247 License No. DPR-26
References:
- 1. NEI 98-03, "Guidelines for Updating Final Safety Analysis Reports," Revision 1, June 1999 2. 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 2014, through the. information available, at a minimum, as of March 17; 2016, which is six months prior to the date of this Note that the last IP2 refueling outage was completed on June 16, 2016. This submittal constitutes the twenty-sixth (26) revision to the IP2 UFSAR. 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 the guidance contained in NRC, "General (Non-Adjudicatory)
Electronic Submission Instructional Guide," June 11, 2009, Revision 4.
NL-16-109 Docket Nos. 50-247 Page 2 of 3 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. 26" 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 26 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 DVD. As specified in NEI 98-03 (Reference 1), 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. A "Summary of Revisions to the IP2 Technical Requirements Manual (TRM)" is provided in Attachment 3, and the entire document is provided on the enclosed DVD. NEI 99-04 (Reference
- 2) provides guidance on the commitments which may be changed without prior NRC approval, but which require periodic NRC staff notification either annually or along with the .FSAR updates as required by 10 CFR 50. 71 (e). This periodic update is not required if individual notifications of commitment changes have previously been filed with the NRC. In this reporting period, all commitment changes have previously been individually communicated to the NRC. Therefore, this letter does not contain a commitment change summary report as an attachment.
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 DVD. 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-16-109 Docket Nos. 50-247 Page 3 of 3 I declare under penalty of perjury that the foregoing is true and correct. Executed on S3epte¥nb.e.r IC/,
Date Sincerely, AJV/gd Attachments:
- 1. Summary Report of IP2 UFSAR Revision 26 Changes 2. Summary of Revisions to the IP2 Technical Specification Bases 3. Summary of Revisions to the IP2 Technical Requirements Manual (TRM)
Enclosure:
DVD containing the IP2 UFSAR (Rev. 26) files, entire documents of the IP2 Technical Specification 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. Daniel H. Dorman, 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-16-109 Summary Report of IP2 UFSAR Revision 26 Changes ENTERGY NUCLEAR OPERATIONS, INC. Indian Point Nuclear Generating Unit No. 2 Docket No. 50-247 License No. DPR-26 UFSAR SECTION CHAPTER 1 1.3.7 1.9.2 CHAPTER2 2.2.3 CHAPTER3 3.0 3.1.1 3.2.1.1.1.
7 3.2.3.2.1.1 3.2.6 3.2 3.2 Figures 3.2 3.2.2.1 3.2.2.4 3.2.2.6 3.2.3 3.2.3.2.1 3.2.6 3.2 References 3.2 CHAPTER4 None NL-16-109 Docket No. 50-247 Attachment 1 Page 1of6 Summary Report of IP2 UFSAR Revision 26 Changes AFFECTED SOURCE(S) of PAGES, CHANGE, EC, INFORMATION I DESCRIPTION OF CHANGES TABLE, 50.59, PAD, FIGURE SCREEN NOs 21 EC-36416 Changes associated with crediting four fan cooler units in TS Amendment 276 the containment integrity analysis for the limiting single (RA-14-110) failure (EDG 23) (reanalysis by Westinghouse to address long-term mass and energy release errors identified in NSALs 11-05 and 14-2) 35 Editorial Addition of Revision 26 to the list of revisions 3 PAD Add a description of the addition of a 42 inch pipeline for gas routed through the southeast corner of the site 1 EC-52275 Cycle 23 fuel and core design 1 13 43,45,46 59,60 T3.2-1A I 70 T3.2-7 I 77-79 82 F3.2-68A F3.2-68B 25,27-29 Editorial I 33 Typographical 36 36 43,51 60 61,65 F3.2-61C UFSAR SECTION CHAPTERS 5.1.1.1.6 5.1.4.2.3 CHAPTER 6 6.2.2.1.2 6.3.1.1 6.3.2.1.2 6.3.3.1 6.3 6.4.1.1 6.4.3.1 6.4 6.2.2.1.4 CHAPTER 7 7.1.4 7.2.4.3.2 NL-16-109 Docket No. 50-247 Attachment 1 Page 2 of 6 Summary Report of IP2 UFSAR Revision 26 Changes AFFECTED SOURCE(S) of PAGES, CHANGE, EC, INFORMATION I DESCRIPTION OF CHANGES TABLE, 50.59, PAD, FIGURE SCREEN NOs 4 EC-36416 Changes associated with crediting four fan cooler units in TS Amendment 276 the containment integrity analysis for the limiting single (RA-14-110) failure (EOG 23) (reanalysis by Westinghouse to address long-term mass and energy release errors identified in NSALs 11-05 and 14-2) 42 EC-17512 Replace "temporary closure plate" with Containment Reference CR-I P3-Equipment Hatch Closure Plug" in last paragraph per EC-2016-03653 17512-this was inadvertently not included in LBDCR U2-2010-05-01-002.
Delete reference to an outstanding license amendment request (LAR) regarding the roll-up door as an editorial change as there is not a pending LAR. 14 EC-36416 Changes associated with crediting four fan cooler units in 62 TS Amendment 276 the containment integrity analysis for the limiting single 66 (RA-14-110) failure (EOG 23) (reanalysis by Westinghouse to address 70 long-term mass and energy release errors identified in T6.3-4 /74 NSALs 11-05 and 14-2) 79 89-90 T6.4-1I93 16 EC-57962 Revision to 2-ES-1.3 switchover sequence CR-IP2-2015-00531 7 EC-36416 Changes associated with crediting four fan cooler units in TS Amendment 276 the containment integrity analysis for the limiting single (RA-14-110) failure (EOG 23) (reanalysis by Westinghouse to address long-term mass and energy release errors identified in NSALs 11-05 and 14-2) 39,40 DRN-06-00911 Correction of the reference to Figure 7.2-26 per DRN-06-00911 NL-16-109 Docket No. 50-24 7 Attachment 1 Page 3 of6 Summary Report of IP2 UFSAR Revision 26 Changes AFFECTED ' SOURCE(S) of UFSAR PAGES, CHANGE, EC, INFORMATION I DESCRIPTION OF CHANGES SECTION TABLE, 50.59, PAD, FIGURE SCREEN NOs 7.7.4 104 Con Edison Mod Revise locations of CCR radio/telephone equipment per 7.7.4.2 105 CCP-200204937-1 modification CCP-2002049371 and Applicability Applicability Determination 02-0336-MD-OO-AD.
This was initially Determination 02-submitted by UFSAR Change Request #1160 but the 0336-M D-00-AD changes were not incorporated into the UFSAR. See CR-UFSAR Change IP2-2014-04234.
An editorial change is also being made to the original UFSAR Change Request #1160 -bullet 2 in Request #1160, per Section 7.7.4 is revised to read, "Indian Point area radios SA0-139 provide the central control room with radio communication Editorial to the emergency response facilities and offsite monitoring teams." CHAPTERS ' , 8.2 26 EC-45752 Revision of reference document due to revision of EOG References Loading Calculation FEX-00039 8.2.2.6 15 Editorial Addition of footnote:
- Note that the "Amptector" may be Evaluation PE replaced by the equivalent Westinghouse device, 125387 "Westector" CHAPTER9 '* 9.2 T9.2-6 Editorial Change 4.238 to 4,238 (Total Tritium in Coolant for Equilibrium Cycle) 9.5.6 EC-55258 Addition of the auxiliary bridge to the list of allowed heavy load lifts over the reactor cavity area while the reactor head is removed and irradiated fuel is in the vessel 9.9.2 113 EC-57018 Alternate Control Room portable breathable air supply configuration ,CHAPTER 10 10.2.6.3 20 Editorial Addition of footnote:
- Note that the Amptector
may be Evaluation PE replaced by the equivalent Westinghouse device, 125387 'Westector' CHAPTER 11 11.2.5.1 32 Approved NRG Change terminology from thermoluminescent dosimeters Change (TLDs) to Dosimeters of Legal Record (DLR), and Editorial associated changes NL-16-109 Docket No. 50-247 Attachment 1 Page 4 of6 Summary Report of IP2 UFSAR Revision 26 Changes AFFECTED SOURCE(S) of UFSAR PAGES, CHANGE, EC, INFORMATION I DESCRIPTION OF CHANGES SECTION TABLE, 50.59, PAD, FIGURE SCREEN NOs CHAPTER12
." 12.7.1 6 IPEC-EP Rev.15-02 Revise discussion of Emergency Plan using wording from UFSAR-only the document IPEC-EP (Indian Point Energy Center Emergency Plan); correct names of ERFs and Hudson Change (Obsolete Valley Transportation Management Center; delete Information) obsolete reference CHAPTER 13 None CHAPTER 14.
- See next page UFSAR SECTION 14.2.1.3 14.3.5.1.1 14.3.5.1.3 14.3.5.3.1 14.3.5.3.2 14.3.5.3.5 14.3.5.3.7 14.3.5.3.9 14.3 References 14.3 Tables 14.3 Figures NL-16-109 Docket No. 50-247 Attachment 1 Page 5 of 6 Summary Report of IP2 UFSAR Revision 26 Changes AFFECTED SOURCE(S) of PAGES, CHANGE, EC, INFORMATION I DESCRIPTION OF CHANGES TABLE, 50.59, PAD, FIGURE SCREEN NOs 60 EC-50141 (PAD R1) Removal of word "blind" from description of the temporary CR-I P2-2016-03652 cooling of the Spent Fuel Pit as a result of the installation of a removable connection for cooling for FLEX purposes 119-120 EC-36416 Changes associated with crediting four fan cooler units in 120 TS Amendment 276 the containment integrity analysis for the limiting single 130 (RA-14-110) failure (EOG 23) (reanalysis by Westinghouse to address 130 long-term mass and energy release errors identified in 132 NSALs 11-05 and 14-2) 133 133 149 T14.3-15/163 T14.3-16/164-167 T14.3-17/169-173 T14.3-i 18/174-175 T14.3-19/176 T14.3-20/177 T14.3-21/178-179 T14.3-22/180-184 T14.3-27/186-187 T14.3-28/188-192 T14.3-29/193 T14.3-30/194 T14.3-31/195
T14.3-32/196 14.3-33/197 T14.3-34/197 T14.3-37/201-202 T14.3-38/203 T14.3-39/204 14.3 Figures/218 F14.3-105 thru F14.3-114 UFSAR SECTION NL-16-109 Docket No. 50-247 Attachment 1 Page 6 of 6 Summary Report of IP2 UFSAR Revision 26 Changes AFFECTED SOURCE(S) of PAGES, CHANGE, EC, INFORMATION I DESCRIPTION OF CHANGES TABLE, 50.59, PAD, FIGURE SCREEN NOs Appendix A -License Renewal A.2.1.5 4 A.2.1.20 -NRC SER The descriptions for the Buried Piping and Tanks A.2.1.20 14 dated October 2009 Inspection Program, the Nickel Alloy Inspection Program, A.2.1.28 21 (NUREG-1930), and the Periodic Surveillance and Preventive Maintenance A.2.3 33 Section 3.0.3.3.5 Program are revised per NRC SER dated October 2009 A.2.1.5, A.2.1.28 -(NUREG-1930), and NRC SER dated November 2014 (NUREG-1930 Supplement 2). NRC SER Supplement 2 is NRC SER dated added as a Reference (Section A.2.3) November 2014 (NUREG-1930 Supplement 2), Sections 3.0.3.1.2
& 3.4.2.A.3.5 A.2.3 -Editorial Drawings 5.1, 6.2, 7.2, 30 drawings Inclusion of latest Replacement of drawings with their current revisions 8.2, 9.2, 9.3, -see revision of Controlled 9.4, 9.6, LBDCR for documents 10.2 list Attachment 2 to NL-16-109 Summary of Revisions to the IP2 Technical Specification Bases ENTERGY NUCLEAR OPERATIONS, INC. Indian Point Nuclear Generating Unit No. 2 Docket No. 50-24 7 License No. DPR-26 NL-16-109 Docket Nos. 50-24 7 Attachment 2 Page 1 of 1 Summary of Revisions to the IP2 Technical Specification Bases (Since last reported September 17, 2014) AFFECTED REV EFFECTIVE DESCRIPTION SECTION DATE BASES UPDATE PACKAGE 49-10032014 B 3.4.13 5 10/3/2014 TS Amendment 177 SG allowable leakage reduced to 85 gallons per day per SG BASES UPDATE PACKAGE 50-8272015 B 3.4.17 1 8/27/2015 TS Amendment 281 SG Inspection frequencies and tube sample selection Attachment 3 to NL-16-109 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-16-109 Docket Nos. 50-24 7 .Attachment 3 Page 1 of 1 Summary of Revisions to the IP2 Technical Requirements Manual (TRM) (since last reported September 17, 2014) AFFECTED NEW EFFECTIVE DESCRIPTION SECTIONS REV# DATE 3.2.A 3 11/17/2014 Corrected the TRM and Bases to note that SR 3.2.4.2 B3.2.A provides an accurate means of tilt monitoring since calculations are not practical with an NIS power range channel inoperable 3.3.B 3 11/17/2014 Editorial change to correct the page not properly incorporated 5.5.B 13 11/17/2014 Revised to procedural reference to the program controlling primary coolant sources outside containment 3.7.A 4 5/7/2015 Deleted the TRM which was superseded by TS LCO 3.0.8 3.7.D 4 3/18/2016 Revise the TRM surveillance frequencies to reconcile 3.7.H 1 the current TRM frequencies and the testing 3.7.1 1 frequencies currently in place 3.7.D / 3.7.D 4 3/18/2016 Revise the action statements from "Present a report to 3.7.G 13.7.G 2 OSRC on corrective action" to Issue a CR and, in 3.7.1 / B3.7.I 1 response to a CA, prepare a corrective action report outlining the cause of the inoperability, the extent of 3.7.J I B3.7.J 1 condition, and the plans and schedule for restoring the 3.8.C / 3.8.C 3 equipment to FUNCTIONAL status" 3.10.A/ 0 6/11/2016 Revised the TRM and associated Bases to reflect B3.10.A FLEX equipment, FLEX connections and the Spent 3.10.B/ 0 Fuel Pool Level Instruments B3.10.B 3.10.C I 0 B3.10.C INDIAN POINT ENERGY CENTER (IPEC) UNIT 2. Docket No. 50-247 Entergy Letter NL-16-109 September
- 19. 2016 File Naming Table Document Title File Name I Multiple File Document -I Indian Point 2 UFSAR, Rev. 26 I ! 001 1.1 Introduction and ! Chapter 1, Introduction and Summary -f Summary.pdf I Chapter 1, Figures 001_ 1.2 Ch 1 Figures.pdf
! Chapter 2, Site and Environment 002_2.1 and Environment.pdf i Chapter 2, Figures 002_2.2 CIJ 2 Figures.pdf I Chapter 3, Reactor Reactor.pdf j Chapter 3, Figures *'
Ch 3 Figures.pdf Chapter 4, Reactor Coolant System 004_ 4.1 Reactor Coolant Sys.pdf Chapter 4, Figures 004_ 4.2 .Ch 4 Figures.pdf
! Chapter 4, Plant Drawings 004_ 4.3 Ch 4 Drawings.pdf I I 005_5:1 Containment Sys.pdf ! Chapter 5, Containment Systems ! Chapter 5, Figures 005_5,2 Ch 5 Figures.pdf Chapter 5, Plant Drawings 005_5.3 Ch 5 Drawings.pdf Chapter 6, Engineered Safety Features 006_6.1 Engineered Safety Features.
pdf Chapter 6, Figures 006_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 I 008..:._8.3 Ch 8 Drawings.pdf Chapter 9, Auxiliary and Emergency Systems 009_9.1 Auxiliary and Emergency Sys.pdf Chapter 9, Figures 009:._9.2 Ch 9 Figures.pdf Chapter 9, Plant Drawings 009_9.3 Ch 9 Drawings.pdf 1
I i ! i I I I i I INDIAN POINT ENERGY CENTER (IPEC) UNIT 2, Docket No. 50-247 Entergy Letter NL-16-109 September 19, 2016 File Naming Table (continued)
Document Title File Name Multiple File Document -Indian Point 2 UFSAR, Rev. 25 j Chapter 10, Steam and Power Conversion 010_ 10.1 Steam and Power !System Conversion Sys.pdf I Chapter 10, Figures 010_ 10.2 Ch 10 Figures.pdf J Chapter 10, Plant Drawings 010_ 10.3 Ch 10 Drawings.pdf 1 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 1 Chapter 11, Plant Drawings 011 _ 11.3 Ch 11 Drawings.pdf Chapter 12, Conduct of Operations I 012_ 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 Appendix A, License Renewal 015_15.1 App A, Lie Renewal.pdf Instructions and Key 016 _ 16 .. 1 Instructions and Key. pdf Table of Contents 017_17 .. 1 TOC.pdf Single File Documents Indian Point 2 Technical Requirements Manual 001_1P2 TRM.pdf (TRM) Indian Point 2 Technical Specification Bases 002_1P2 Tech Spec Bases.pdf Holtec Licensing Report on the lnter-Uni.t 003_Holtec Licensing Report.pdf Transfer of Spent Nuclear Fuel 2