ML17299A164: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
(7 intermediate revisions by the same user not shown)
Line 1: Line 1:
{{Adams
#REDIRECT [[NL-17-121, Submittal of Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 07]]
| number = ML17299A164
| issue date = 10/02/2017
| title = Indian Point Unit No. 3 - Submittal of Amendment Update to the Updated Final Safety Analysis Report (Ufsar), Revision 07
| author name = Vitale A J
| author affiliation = Entergy Nuclear Operations, Inc
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000286
| license number = DPR-064
| contact person =
| case reference number = NL-17-121
| package number = ML17299A163
| document type = Letter
| page count = 21
}}
 
=Text=
{{#Wiki_filter:A Entergy Nuclear Operations. Inc. Indian Point Energy Center Entergx NL-17-121 October 2, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-27.38 450 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. 3 Amendment Update to the Updated Final Safety Analysis Report (UFSAR), Revision 07 Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286 License No. DPR-64
 
==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 3 (IP3). This submittal incorporates applicable changes made to the IP3 facility since the UFSAR update in October 2015, through the information available, at a minimum, as of March 13, 2017. Note that the last IP3 refueling outage was completed on May 18, 2017. This submittal constitutes the seventh (7) revision to the IP3 UFSAR. Entergy is submitting two copies of the entire IP3 UFSAR, IP3 Technical Specification Bases, IP3 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 DVDs in accordance with the guidance contained in NRC, "General (Non-Adjudicatory) Electronic Submission Instructional Guide," June 11, 2009, Revision 4. Two DVDs are enclosed, Enclosure 1 containing a Redacted version of the ,UFSAR and Enclosure 2 a Non-Redacted version of the UFSAR. A Redacted version of the UFSAR h9s had certain sensitive information removed which was identified due to meeting the NRC's criteria on sensitive information, as specified in SECY-04-0191, "Withholding Sensitive Unclassified Information Concerning Nuclear Power Reactors from Public /
NL-17-121 Docket Nos. 50-286 Page 2 of 3 Disclosure." Entergy is requesting that the version be withheld from the public in accordance with 10 CFR 2.390(d)(1) as material included within is classified as non-publicly available information. The Non-Redacted version of the UFSAR is for use by the NRC staff. 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. 07" 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 IP3 UFSAR Revision 07 Changes," contains a summary with a brief description of the information changed in this revision to the IP3 UFSAR. IP3 Technical Specification 5.5.13.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 IP3 Technical Specification Bases" and the entire document is provided on the enclosed DVDs. 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 IP3 Technical Requirements Manual (TRM)" is provided in Attachment 3, and the entire document is provided on the enclosed DVDs. 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 a commitment change summary report as an attachment. I 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 DVDs.
NL-17-121 Docket Nos. 50-286 Page 3 of 3 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. I declare under penalty of perjury that the foregoing is. true and correct. Executed on Ociob*er-;;J, J0/7 " Date Sincerely, AJV/gd Attachments: 1. Summary Report of IP3 UFSAR Revision 07 Changes 2. Summary of Revisions to the IP3 Technical Specification Bases 3. Summary of Revisions to the IP3 Technical Requirements Manual (TRM)
 
==Enclosures:==
1. DVD containing the IP3 Redacted UFSAR (Rev. 07) files, entire documents of the IP3 Technical Specification Bases, IP3 TRM, and Rev. 6 of the Holtec International Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at IPEC 2. DVD containing the IP3 Non-Redacted UFSAR (Rev. 07) files -Withhold from Public Disclosure per 10 CFR 2.390(d)(1) cc w/o enclosure: Mr. Daniel H. Dorman, Regional Administrator, NRC Region I Mr. Richard Guzman, Senior Project Manager, NRC NRR DORL Ms. Bridget Frymire, New York State Department of Public Service Ms. Alicia Barton, President and CEO, NYSERDA NRC Resident Inspectors    to NL-17-121 Summary Report of IP3 UFSAR Revision 07 Changes ENTERGY NUCLEAR OPERATIONS, INC. Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286 License No. DPR-64 UFSAR SECTION CHAPTER 1 1.1 1.3.2 1.3.5 1.3.3 CHAPTER2 2.2.2 2.2.3 References 2.7 NL-17-121 Docket No. 50-286 Attachment 1 Page 1 of 8 Summary Report of IP3 UFSAR Revision 07 Changes AFFECTED SOURCE(S) of PAGES, TABLE, CHANGE, EC, INFORMATION I DESCRIPTION OF CHANGES DWG, 50.59, PAD, FIGURE SCREEN NOs 2* Editorial Reformatting, editorial changes, removal of obsolete information, and revision of effective date to May 18, 2017 30 EC-16185 & PAD Deletion of the Outage Equipment Hatch and 92 addition of the Containment Equipment Hatch Closure Plug (EC-16185). Changes were originally in LBDCR U3 2011 I 01-01-002 but were not incorporated. New LBDCR required due to differences in changes from LBDCR U3 2011 / 01-01-002. Reference CR-IP2-2016-03653. 43 NRC SER Revise references to IEEE Standard 279 for the Editorial Reactor Protection System (RPS) to be consistent with the 9/21/73 IP3 SER which evaluated the RPS CR-IP3-2016-design against the 1968 edition. Reference CR-IP3-01118 2016-01118 3 PAD Inclusion of new 42 inch gas pipeline; correction of 4 Editorial "exiting" to "existing" 7 F2.7-1 Editorial Reformatting, editorial changes, and revision of F2.7-2 effective date to May 18, 2017 F2.7-3 F2.7-4 UFSAR SECTION CHAPTER3 3.2.1.1 3.2.2 3.2.2.4 References 3.2 3.2.1.1 CHAPTER4 4.2.3 4.2.5 4.3.4 4.4.1 CHAPTER 5 5.1.4.2 5.1.4.3 5.1.7.3 5.2.2.7 NL-17-121 Docket No. 50-286 Attachment 1 Page 2 of 8 Summary Report of IP3 UFSAR Revision 07 Changes AFFECTED SOURCE(S) of PAGES, TABLE, CHANGE, EC, INFORMATION I DESCRIPTION OF CHANGES DWG, 50.59, PAD, FIGURE SCREEN NOs 22 EC-63102 Changes as a result of Cycle 20 fuel and core design 25 PAD 30 71,72 T3.2-1,T3.2-2,T3.2-3,T3.2-4,T3.2-5 14 -16 Editorial Reformatting, editorial changes, removal of obsolete information, and revision of effective date to May 18, 2017 33 EC-59472 Revision of PT curves for L TOP 37 61,62 74,75,77 22 EC-16185 & PAD Deletion of the Outage Equipment Hatch and 28 addition of the Containment Equipment Hatch 39 Closure Plug (EC-16185). Changes were originally in LBDCR U3 2011 I 01-01-002 but were not 50 incorporated. New LBDCR required due to differences in changes from LBDCR U3 2011 I 01-01-002. Reference CR-IP2-2016-03653.
UFSAR SECTION 5.1.4.2 5.1.4.3 5.2.2.1 5.2 CHAPTERS 6.2 6.2 App. 60 App.6F 6.2.2 6.2 NL-17-121 -Docket No. 50-286 Attachment 1 Page 3 of 8 Summary Report of IP3 UFSAR Revision 07 Changes AFFECTED SOURCE(S) of PAGES, TABLE, CHANGE, EC, INFORMATION I DESCRIPTION OF CHANGES 50.59, PAD, DWG, SCREEN NOs FIGURE 21 EC-60109 Increase of the temperature limit of concrete CR-IP3-2015-adjacent to the Containment hot pipe penetrations 04036 from 150 F to 250 F 25 Editorial, Editorial changes involving figures and drawings 48 typographical 20253 Other Approval Replacement of drawings with their current revisions 27293 Sh 2c 27353 27513 Sh1 T6.2-13 EC-73244 Revision of the Net Positive Suction Head (NPSH) Calculation 98-049 Required, the NPSH Available, and the Fluid markup Operating Temperature for the Auxiliary Feedwater pumps WT-WTIPC-2017-00099 CA-7 i \ T6.2-12 Editorial Reformatting, editorial changes, removal of obsolete T6D-1 information, and revision of effective date to May 18, 203 2017 28 Editorial, Editorial changes involving figures and drawings typographical 27353 Other Approval Replacement of drawings with their current revisions \
UFSAR SECTION Appendix 6E 6.4.2 6.4.3 6.7.1.2 CHAPTER 7 7.2 7.2.1 7.2.2 7.3.1 NL-17-121 Docket No. 50-286 Attachment 1 Page 4 of 8 Summary Report of IP3 UFSAR Revision 07 Changes AFFECTED SOURCE(S) of PAGES, TABLE, CHANGE, EC, INFORMATION I DESCRIPTION OF CHANGES DWG, 50.59, PAD, FIGURE SCREEN NOs 198 Editorial, Editorial changes involving figures and drawings typographical 104 EC-65920 Revision of the VC coating options SPEC-16-00002-1 RO 107 Editorial Reconciliation of the containment fan coolers delay time specified in Section 6.4.3 with the time specified in Table 14.3-55 136 Typographical Correct "tom" to "to" in first sentence of first paragraph 27-29,39 DCP 97-3-357 Incorporate changes associated with the deletion of NSE 93-3-223 RPC references to turbine runback DCP 99-3-063 EVAL 99-3-063 N IS 8 NRC SER Revise references to IEEE Standard 279 for the Editorial Reactor Protection System (RPS) to be consistent with the 9/21/73 IP3 SER which evaluated the RPS CR-IP3-2016-design against the 1968 edition. Reference CR-IP3-01118 2016-01118 15 Typographical Capitalized "boiler'' in 5th sentence of 3rd paragraph 54 EC-59472 Revision of PT curves for L TOP UFSAR SECTION 7.5 CHAPTERS 8.2 8.2.3 8.2 CHAPTER9 9.3 NL-17-121 Docket No. 50-286 Attachment 1 Page 5 of 8 Summary Report of IP3 UFSAR Revision 07 Changes AFFECTED SOURCE(S) of I PAGES, \ TABLE, CHANGE, EC, INFORMATION I DESCRIPTION OF CHANGES DWG, 50.59, PAD, FIGURE SCREEN NOs T7.5-1 EC-72087 CE-T-34 (A 11) has been restored and is replacing CE-T-05 (C8). These CETs are in the sar;ne core quadrant and will maintain the Technical Specifications requirement of 2 qualified CETs per train per quadrant. Also, the cable from CE-T-28 (M-13) has been used to restore CE-T-53 (K11) as a qualified core exit thermocouple. Therefore, CE-T-28 (M 13) is no longer in service. 617F645 EC-52527, -60930, Revision of drawing to add the Open Phase -60931 Detection System trip logic to the Unit 3 Station PAD Auxiliary Transformer and Gas Turbine Autotransformer protection logic diagram -not enabled at this time 14 UFSAR Only Resolution of issues identified in the 2010 CDBI (Removing regarding fuel consumption of the EDGs under Excessive Detail) minimum safeguards loading for all design basis Editorial (EC-accident scenarios 65951) 33853 Other Approval Replacement of drawings with their current revisions 617F643 617F644 617F645 30063 Sh1 30083 39893 27513 Sh1 Other Approval Replacement of drawings with their current revisions NL-17-121 -Docket No. 50-286 Attachment 1 Page 6 of 8 Summary Report of IP3 UFSAR Revision 07 Changes AFFECTED SOURCE(S) of PAGES, UFSAR TABLE, CHANGE, EC, INFORMATION I DESCRIPTION OF CHANGES SECTION DWG, 50.59, PAD, FIGURE SCREEN NOs 9.6 T9.6-1 EC-66581 Reduction of required flows for Service Water T9.6-2A Strainer backwash from 180 gpm to 100 gpm 9.6.1 111 EC-71892 To identify that postulated passive failures of service References 151 water system piping will not cause flooding in the PAB 9.3.1 40 Editorial Reformatting, editorial changes, removal of obsolete 9.6.5 151 information, and revision of effective date to May 18, 2017 9.6 '20333 Sh1 Other Approval Replacement of drawings with their current revisions 20333 Sh2 27223 40903 CHAPTER 10 10.2 28,29 Editorial Revise Section 10.2 to achieve consistency with the rest of the UFSAR, other Licensing Basis Documents, and design basis calculations regarding auxiliary feedwater flow 10.2 20093* Other Approval Replacement of drawings with their current revisions 20183 Sh1 20203 Sh1 20253 20263 20403 27273 27293 Sh2 10.2.1 13 EC-71363 Interim abandonment of Independent Electrical 10.3.1 41 PAD Overspeed Protection System (IEOPS)
NL-17-121 Docket No. 50-286 Attachment 1 Page 7 of 8 Summary Report of IP3 UFSAR Revision 07 Changes AFFECTED SOURCE(S) of PAGES, UFSAR TABLE, CHANGE, EC, INFORMATION I DESCRIPTION OF CHANGES SECTION DWG, 50.59, PAD, FIGURE SCREEN NOs CHAPTER 11 11.2.3.1 34 EC-56698 Replacement of the Bantam 11 computer with a 11.2.3.2 40-42 PAD Radiation Monitoring System using the PICS F11.2-7 computer and a flat screen with a touchscreen keyboard CHAPTER12 12.1 1-3, 7-10 QAPM R33 Revision of organizational structure; editorial 12.4 13 7 /1 /17 Organization changes; referral to QAPM for qualification of nuclear 12.5 13 Charts plant personnel; removal of obsolete information 12.6 14 12.7 14 Editorial F12.1-1 Remove obsolete info " CHAPTER 13 ' None CHAPTER14 14.1 8 NRC SER Revise references to IEEE Standard 279 for the Editorial Reactor Protection System (RPS) to be consistent with the 9/21/73 IP3 SER which evaluated the RPS CR-IP3-2016-design against the 1968 edition. Reference CR-IP3-01118 2016-01118 14.3.3.1 120 Editorial, Editorial changes involving figures and drawings 14.3.4.2 131 typographical 14.3.4.3 132 14.3.5.1 140 T14.3-13 NL-17-121 Docket No. 50-286 Attachment 1 Page 8 of 8 Summary Report of IP3 UFSAR Revision 07 Changes AFFECTED SO!-JRCE(S) of PAGES, UFSAR TABLE, CHANGE, EC, INFORMATION I DESCRIPTION OF CHANGES SECTION 50.59, PAD, DWG, SCREEN NOs FIGURE CHAPTER15 None CHAPTER 16 16.1.8 25 PAO" Revise the discussion that allows for the use of the Generic Implementation Procedure (GIP) methodology as an alternate method to existing methods for the seismic design and verification of equipment classified as Seismic Class I to exclude:
* Regulatory Guide 1.97 Category I items
* Residual Heat Removal System motor operators for MOV-730 and MOV-731 Appendix A -License Renewal \ None    to NL-17-121 Summary of Revisions to the IP3 Technical Specification Bases ENTERGY NUCLEAR OPERATIONS, INC. Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286 License No. DPR-64 NL-17-121 Docket Nos. 50-286 Attachment 2 Page 1 of 1 Summary of Revisions to the IP3 Technical Specification Bases (Since last reported October 1, 2015) / AFFECTED EFFECTIVE DESCRIPTION SECTIONS REV DATE I BASES UPDATE PACKAGE 50-10012015 B3.4.3 5 10/01/2015 RCS Pressure and Temperature Curves -B3.4.12 7 10/01/2015 Low Temperature Overpressure Protection BASES.UPDATE PACKAGE 51-02232016 B3.4.1 2 02/23/2016 Changes consistent with COLR BASES UPDATE PACKAGE 52-08032016 B3.4.3 6 08/03/2016 Correct heading error on first page B3.4.12 7 08/03/2016 Correct heading error on first page BASES UPDATE PACKAGE 53-09302016 83.8.1 8 09/30/2016 Added beginning material regarding non-conservative BASES UPDATE PACKAGE 54-12062016 B3.1.3 2 12/06/2016 TS Amendment 261 exemption from near EOL MTC measurement    to NL-17-121 Summary of Revisions to the IP3 Technical Requirements Manual (TRM) ENTERGY NUCLEAR OPERATIONS, INC. Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286 License No. DPR-64 NL-17-121 Docket Nos. 50-286 Attachment 3 Page 1of2 Summary of Revisions to the IP3 Technical Requirements Manual (TRMl (since last reported October 1, 2015) AFFECTED NEW EFFECTIVE DESCRIPTION SECTIONS REV# DATE TRM Section 3.4.A revised to change the region of applicability from 330-380 deg. F to 330-370 deg. F based 3.4.A 4 10/1/2015 upon new heatup curves. (Note: Associated with IP3 TS Amendment 258 allowing operation to 37 EFPY for Appendix G limitations.) 3.3.B 5 Revised TRM and Bases sections 3.3.B (Met Inst), 3.7.A.1 3.7.A.1 3 (HP Fire Water), 3.7.A.2 (Spray & Sprinkler Sys), 3.7.A.3 3.7.A.2 4 (Fire Sep. Devices), 3.7.A.4 (Fire Det. Sys), 3.7.A.5 (Hose 3.7.A.3 9 Stations), 3.7.A.6 (Hydrants & Hose House), 3.7.A.7 (C02), 3.7.A.4 4 3.7.A.8 (RCP Oil Collection) and 3.7.B (App R ASSS Equip.) 3.7.A.5 2 to remove requirements for OSRC reports and replace with the issuance of a Condition Report and the preparation of a 3.7.A.6 2 3/18/2016 corrective action report. 3.7.A.7 3 3.7.A.8 1 Revised Frequency of TRS 3.7.H.1 (EOG Ventilation Sys), 3.7.B 13 3.7.1.1 (Swgr. Room Ventilation Sys), and 3.7.J.1 (Elec. Tunnel Ventilating) from 12 months to 24 months; revised 3.7.H 1 Frequency of TRS 3.7.H.2 from 18 months to 72 months; 3.7.1 1 revised Frequency of 3.7.1.2 and 3.7.J.2 from 18 months to 3.7.J 1 24 months 3.10.A 1 TRM Section 3.10 was implemented in Rev 0 to address FLEX and SFPI requirements. Changes were made to clarify 3.10.B 1 5/26/2016 1) when a component is out an OSRC report is required; and 3.10.C 1 2) to reflect IP2 implementation of FLEX since the two plants share components in order to meet N+1. 3.7.A.1 4 Utilize unused time in the non-permanent 1-month extension 3.7.A.6 2 6/13/2016 to TRM surveillance frequency of 184 days for TRS 3.8.A.2, "DEMONSTRATE Closure of Turbine Steam Stop and 3.8.A 3 Control Valves." Remove the TRS 3.8.B.5 requirement to demonstrate that the 3.8.B 6 12/20/2016 IP3 App. R/SBO diesel has the ability to lineup and provide power to the IP2 App. R/SBO loads. ------_ J NL-17-121 Docket Nos. 50-286 Attachment 3 Page 2 of 2 Summary of Revisions to the IP3 Technical Requirements Manual CTRM) (since last reported October 1, 2015) AFFECTED NEW EFFECTIVE DESCRIPTION SECTIONS REV# DATE Revised TRM 3.1.A, Anticipated Transient Without Scram (A TWS) Mitigating Systems Actuation Circuitry (AMSAC), 3.1.A 3 1/26/2017 Bases for Action A.1 to clarify that there is no need to reevaluate the Conditional Core Damage Probability (CCDP) value for the 30 day AOT whenever the PRA model is updated. (1) Revised TRS 3.7.A.4.2 to change the Frequency for the three dedicated heat detectors associated with the Turbine Building Steam Bridge Water Spray System from 12 months to 24 months for consistency with the Frequency for the 3.7.A.4 5 dedicated heat detectors that operate the Steam Bridge 3/1/2017 Water Curtain System 3.7.A.7 6 (2) Revised TRS 3.7.A.7.3 to eliminate the requirement to "exercise" fire dampers associated with the rooms provided with total-flooding C02 suppression (480V Swgr. Room, Cable Sprd. Room, EDG Rooms) on a 12-month frequency for consistency with the Frequency for testing the associated C02 suppression systems I I I I I I I l I I ! ENCLOSURE 1 TO NL-17-121 INDIAN POINT ENERGY CENTER (IPEC) UNIT 3, Docket No. 50-286 File Naming Table Document Title Multiple File Document -Indian Point 3 UFSAR, 2017 Rev. 07 c File Name I Chapter 1, Introduction and Summary 001_ 1.1 Introduction & Summary.pdf j Chapter 1, Figures 001_ 1.2 Ch 1 Figures.pdf ! I Chapter 1, Drawings -REDACTED 001_ 1.3 Ch 1 Drawings.pdf I Chapter 2, Site and Environment 002_2.1 Site & Environment.pdf I Chapter 2, Figures 002_2.2 Ch 2 Figures.pdf j Chapter 2, Drawings 002_2.3 Ch 2 Drawings.pdf 1 I Chapter, 3, Reactor 003_3.1 Reactor.pdf \Chapter 3, Figures 003_3.2 Ch 3 Figures.pdf i Chapter 4, Reactor Coolant System 004_ 4.1 Reactor Coolant Sys.pdf J Chapter 4, Figures 004_ 4.2 Ch 4 Figures.pdf J Chapter 4, Drawings 004_ 4.3 Ch 4 Drawings.pdf ' \Chapter 5, Containment I 005_5.1 Containment.pdf I Chapter 5, Figures 005_5.2 Ch 5 Figures.pdf I Chapter 5, Drawings -REDACTED 005_5.3 Ch 5 Drawings.pdf ' I Chapter 6, Engineered Safety Features I 006_6.1 Engineered Safety Features.pdf I Chapter 6, Figures 006_6.2 Ch 6 Figures.pdf J Chapter 6, Drawings -REDACTED 006_6.3 Ch 6 Drawings.pdf I Chapter 7, Instrumentation and Control I 007 _7.1 Instrumentation & Control.pdf J Chapter 7, Figures Joo7 _7.2 Ch 7 Figures.pdf !Chapter 7, Drawings -REDACTED I 007 _7.3 Ch 7 Drawings.pdf ) Chapter 8, Electrical Systems 008_8.1 Electrical Systems.pdf ' 'i ' , J Chapter 8, Drawings 008_8.2 Ch 8 J Chapter 9, Auxiliary and Emergency Systems 009_9.1 Auxiliary & Emerg Sys.pdf I Chapter 9, Figures 009_9.2 Ch 9 Figures.pdf 1 1 Chapter 9 Drawings -REDACTED f 009_9.3 Ch 9 Drawings.pdf Page 1 of 2 I I ENCLOSURE 1 TO NL-17-121 INDIAN POINT ENERGY CENTER (IPEC) UNIT 3, Docket No. 50-286 Document Title File Name Multiple File Document -Indian Point 3 UFSAR, 2017 Rev. 07 I Chapter 10, Steam and Power Conversion Jsystem J Chapter 10, Figures J Chapter 10, Drawings -REDACTED I Chapter 11, Waste Disposal and Radiation I Protection System Chapter 11, Figures ] Chapter 11, Drawings -REDACTED I I Chapter 12, Conduct of Operations I I Chapter 12, Figures ! Chapter 13, Initial Tests and Operations J Chapter 13, Figures j Chapter 14, Safety Analysis \Chapter 14, Figures Chapter 15, Technical Specifications I Chapter 16, Design Criteria for Structures and I Equipment
* I Chapter 16, Figures /Chapter 17, Quality Assurance Program J Appendix A, License Renewal IT able of Contents ' j 1nstructions 010_ 10.1 Steam & Power Conv Sys.pdf 010_ 10.2 Ch 10 Figures.pdf 010_ 10.3 Ch 10 Drawings.pdf 011_ 11.1 Waste Dis & Rad Prat Sys.pdf 011_ 11.2 Ch 11 Figures.pdf 011_ 11.3 Ch 11 Drawings.pdf 012_ 12.1 Conduct of Operations.pdf 012_ 12.2 Ch 12 Figures.pdf 013_ 13.1 Initial Tests & Oper.pdf .013_ 13.2 Ch 13 Figures.pdf 014_ 14.1 Safety Analysis.pdf 014_ 14.2 Ch 14 Figures.pdf 015_ 15.1 TS.pdf 016_ 16.1 Design Criteria Struct & Equip.pdf 016_ 16.2 Ch 16 Figures.pdf 017_17.1 QA Program.pdf 018_ 18.1 App A, Lie Renewal.pdf 019_19.1 TOC.pdf 020_20.1 lnstructions.pdf Single File Documents i Indian Point 3 Technical Requirements Manual j(TRM) I . [Indian point 3 Technical Specification Bases HOL TEC International, "License Report on the Inter-Unit Transfer of Spent Nuclear Fuel at Indian Point Energy Center" [Rev. 6] 001_1P3 TRM.pdf 002_1P3 Technical Specification Bases.pdf 003_1P3 HOL TEC Report.pdf Page 2 of 2 ENCLOSURE 2 TO NL-17-121 INDIAN POINT ENERGY CENTER (IPEC) UNIT 3, Docket No. 50-286 File Naming Table i Document Title File Name I Multiple File Document -Indian Point 3 UFSAR, 2017 Rev. 07 I Chapter 1, Introduction and Summary 001_ 1.1 Introduction & Summary.pdf \Chapter 1, Figures 001_ 1.2 Ch 1 Figures.pdf i Chapter 1, Drawings -NON-REDACTED ! . 001_ 1.3 Ch 1 Drawings_NON-REDACTED.pdf I Chapter 2, Site and Environment I 002_2.1 Site & Environment. pdf i Chapter 2, Figures I 002_2.2 Ch 2 Figures.pdf I Chapter 2, Drawings 1002_2.3 Ch 2 Drawings.pdf J Chapter 3, Reactor 003_3.1 Reactor.pdf I Chapter 3, Figures 003_3.2 Ch 3 Figures.pdf J Chapter 4, Reactor Coolant System 004_ 4.1 Reactor Coolant Sys.pdf I
* I Chapter 4, Figures 004_ 4.2 Ch 4 Figures.pdf I Chapter 4, Drawings \ 004_ 4.3 Ch 4 Drawings.pdf ! . I
* 005_5.1 Containment.pdf I Chapter 5, Containment I J Chapter 5, Figures loo5_5.2 Ch 5 Figures.pdf I Chapter 5, Drawings -NON-REDACTED 005_5.3 Ch 5 Drawings_NON-REDACTED.pdf /Chapter 6, Engineered Safety Features 006_6.1 Engineered Safety Features.pdf J Chapter 6, Figures joo6_6.2 Ch 6 Figures.pdf /Chapter 6, Drawings -NON-REDACTED I 006_6.3 Ch 6 Drawings_NON-REDACTED.pdf I Chapter 7, Instrumentation and Control 007 _7.1 Instrumentation & Control.pdf Jchapter 7, Figures 007 _7.2 Ch 7 Figures.pdf ! \Chapter 7, Drawings -NON-REDACTED 007 _7.3 Ch 7 Drawings_NON-REDACTED.pdf I J 008_8.1 Electrical Systems.pdf l Chapter 8, Electrical Systems I J Chapter 8, Drawings 008_8.2 Ch 8 Drawings.pdf I Chapter 9, Auxiliary and Emergency /systems 009_9.1 Auxiliary & Emerg Sys.pdf I I Chapter 9, Figures 009_9.2 Ch 9 Figures.pdf ) Chapter 9 Drawings -NON-REDACTED 009_;;9.3 Ch 9 Drawings_NON-REDACTED.pdf Page 1 of 2 I I _J I I I I I ENCLOSURE 2 TO NL-17-121 INDIAN POINT ENERGY CENTER UPEC) UNIT 3, Docket No. 50-286 Document Title File Name __ -10-.2-C_h_1_o_F_ig_u_re_s ___ I Chapter 10, Drawings -NON-REDACTED 010_ 10.3 Ch 10 Drawings_NON-REDACTED.pdf I Chapter 11, Waste Disposal and Radiation 011 11 1 W t D" & R d p ts df Protection System -* as e is a ro ys.p Chapter 11, Figures 011_11.2 Ch 11 Figures.pdf Chapter 11, Drawings -NON-REDACTED io11_ 1_1 ___ 3_C_h_1_1 _D-ra_w_i-ng_s ___ N_O_N ___ R_E_D_A_C_T_E_D_.p_d_f_--; Chapter 12, Conduct of Operations 012_ 12.1 Conduct of Operations.pdf Chapter 12, Figures 012_ 12.2 Ch 12 Figures.pdf Chapter 13, Initial Tests and Operations 013_ 13.1 Initial Tests & Oper.pdf j Chapter 13, Figures 013_13.2 Ch 13 Figures.pdf I Chapter 14, Safety Analysis jo14_14.1 Safety Analysis.pdf Chapter 14, Figures 014_ 14.2 Ch 14 Figures.pdf I Chapter 15, Technical Specifications 015_15.1 TS.(:{df I Chapter 16, Design Criteria for Structures 016_16.1. Design Criteria Struct & Equip.pdf \ and Equipment Chapter 16, Figures 016_ 16.2 Ch 16 Figures.pdf I Chapter 17, Quality Assurance Program 017_17.1 QA Program.pdf I Appendix A, License Renewal [ 018_ 18.1 App A, Lie Renewal.pdf Table of Contents 019_19.1 TOC.pdf Instructions J 020_20.1 lnstructions.pdf Page 2 of 2 
}}

Latest revision as of 01:53, 6 April 2019

Redirect to:

Retrieved from "https://kanterella.com/w/index.php?title=ML17299A164&oldid=1405537"