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Category:Letter type:NL
MONTHYEARNL-21-034, Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals2021-05-26026 May 2021 Notification of Expected Date of Transfer of Ownership of Nuclear Units to Holtec Indian Point 2, LLC and Holtec Indian Point 3, LLC; and Notification of Receipt of All Required Regulatory Approvals NL-21-039, Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary2021-05-20020 May 2021 Response to Request for Additional Information - License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary NL-21-033, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2021-05-11011 May 2021 Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel NL-21-032, Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center2021-05-11011 May 2021 Termination of Emergency Response Data System Feed to the U.S. Nuclear Regulatory Commission at Indian Point Energy Center NL-21-005, Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions2021-05-11011 May 2021 Cancellation of Commitments Related to Beyond-Design-Basis External Events Seismic and Flooding Actions NL-21-030, Submittal of 2020 Annual Radiological Environmental Operating Report2021-05-0606 May 2021 Submittal of 2020 Annual Radiological Environmental Operating Report NL-21-027, Registration of Spent Fuel Cask Use2021-04-20020 April 2021 Registration of Spent Fuel Cask Use NL-21-021, Registration of Spent Fuel Cask Use2021-04-19019 April 2021 Registration of Spent Fuel Cask Use NL-21-017, Pre-Notice of Disbursement from Decommissioning Trusts2021-04-0808 April 2021 Pre-Notice of Disbursement from Decommissioning Trusts NL-21-010, Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report2021-02-17017 February 2021 Submittal of 2020 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report NL-21-006, Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement2021-02-10010 February 2021 Relief Request IP3-ISI-RR-16, Proposed Alternative to American Society of Mechanical Engineers Code Case N-513-4 Inspection Requirement NL-21-014, Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2021-01-26026 January 2021 Response to 2nd Round Request for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-082, Notice of Planned Transfer of Decommissioning Funds2020-12-14014 December 2020 Notice of Planned Transfer of Decommissioning Funds NL-20-081, Pre-Notice of Disbursement from Decommissioning Trusts2020-12-0909 December 2020 Pre-Notice of Disbursement from Decommissioning Trusts NL-20-080, Report in Accordance with 10 CFR 71.95(a) for Failure to Comply with Certificate of Compliance No. 71-93212020-11-19019 November 2020 Report in Accordance with 10 CFR 71.95(a) for Failure to Comply with Certificate of Compliance No. 71-9321 NL-20-079, (IP2 and IP3) - Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-12012 November 2020 (IP2 and IP3) - Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic NL-20-077, Submittal of Quality Assurance Program Manual Revision 22020-11-0909 November 2020 Submittal of Quality Assurance Program Manual Revision 2 NL-20-078, Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-11-0909 November 2020 Response to Requests for Additional Information - License Amendment Request to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-076, Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal2020-11-0202 November 2020 Revision of Commitment Related to Nuclear Reactor Safeguards Interim Compensatory Measure - Section B.5.b Issue Regarding Spent Fuel Dispersal NL-20-069, One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency2020-10-0808 October 2020 One-time Scheduler Exemption Request from 10 CFR 50, Appendix E Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Public Health Emergency NL-20-070, Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-10-0202 October 2020 Response to Requests for Additional Information, License Amendment Request to Revise the Indian Point Nuclear Generating Unit No. 3 Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-067, Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-09-16016 September 2020 Redacted Version of Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-064, 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments2020-09-0101 September 2020 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments NL-20-060, Status of Remaining Actions for Generic Letter 2004-022020-08-11011 August 2020 Status of Remaining Actions for Generic Letter 2004-02 NL-20-057, Cancellation of Commitment Related to Large Break LOCA Reanalysis2020-07-30030 July 2020 Cancellation of Commitment Related to Large Break LOCA Reanalysis NL-20-0851, 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material2020-07-22022 July 2020 30-Day 10 CFR 21 Notification - Continuously Energized Eaton D26 Relays Could Fail to Deenergize Because of an Organic C3 Insulating Material NL-20-051, Submittal of Quality Assurance Program Manual, Revision 1 for the Indian Point Energy Center2020-07-0707 July 2020 Submittal of Quality Assurance Program Manual, Revision 1 for the Indian Point Energy Center NL-20-052, Unsatisfactory 10 CFR 26 Fitness-For-Duty Blind Performance Testing Results2020-07-0707 July 2020 Unsatisfactory 10 CFR 26 Fitness-For-Duty Blind Performance Testing Results NL-20-012, Application to Revise Provisional Operating License and Technical Specifications2020-06-30030 June 2020 Application to Revise Provisional Operating License and Technical Specifications NL-20-050, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-06-24024 June 2020 Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-041, Registration of Unit 3 Spent Fuel Cask Use2020-05-13013 May 2020 Registration of Unit 3 Spent Fuel Cask Use NL-20-042, Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel2020-05-12012 May 2020 Certifications of Permanent Cessation of Power Operations and Permanent Removal of Fuel from the Reactor Vessel NL-20-033, Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2020-04-28028 April 2020 Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-20-038, Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline2020-04-23023 April 2020 Response to U.S. Nuclear Regulatory Commission Region I Letter Regarding Algonquin Incremental Market Project Pipeline NL-20-035, Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-16016 April 2020 Response to Request for Additional Information - Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic NL-20-034, Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-13013 April 2020 Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic NL-20-021, Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device2020-03-24024 March 2020 Proposed License Amendment to Revise the Licensing Basis to Incorporate the Installation and Use of a New Auxiliary Lifting Device NL-20-020, Submittal of 2019 Annual Fitness for Duty Performance Data Report Update2020-02-26026 February 2020 Submittal of 2019 Annual Fitness for Duty Performance Data Report Update NL-20-015, Submittal of 2019 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report2020-02-10010 February 2020 Submittal of 2019 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report NL-20-008, Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane2020-01-0606 January 2020 Transmittal of Presentation Slides for Partially Closed Pre-Submittal Meeting to Discuss a Planned License Amendment Request to Replace the Fuel Handling Building Crane NL-19-094, 2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report2019-12-16016 December 2019 2018 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report NL-19-084, Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments2019-11-21021 November 2019 Application for Order Consenting to Transfers of Control of Licenses and Approving Conforming License Amendments NL-19-093, Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.12019-11-21021 November 2019 Proposed Technical Specifications (TS) Changes - Indian Point Nuclear Generating Unit 3 TS SR 3.7.7.2 and TS 3.7.6, Required Action A.1 NL-19-092, Request for Rescission of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-11-20020 November 2019 Request for Rescission of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) NL-19-043, Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.122019-10-22022 October 2019 Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.12 NL-19-073, Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2019-10-22022 October 2019 Request for Relaxation of Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) NL-19-078, Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications2019-10-22022 October 2019 Supplement to Technical Specifications Proposed Change - Permanently Defueled Technical Specifications NL-19-091, Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Cask Use2019-10-17017 October 2019 Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Cask Use NL-19-090, Registration of Unit 2 Spent Fuel Cask Use2019-10-0909 October 2019 Registration of Unit 2 Spent Fuel Cask Use NL-19-079, 50.59(d)(2) Summary Report of Changes, Tests and Experiments2019-09-26026 September 2019 50.59(d)(2) Summary Report of Changes, Tests and Experiments 2021-05-06
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Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 SwEnterg y Buchanan, N.Y. 10511-0249 Tel (914) 734-6700 J.E. Pollock Site Vice President Administration September 21, 2009 NL-09-128 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Response To Request for Additional Information Regarding Amendment Application for Battery Capacity Surveillance Requirement (TAC. NO. ME0985)
Indian Point Unit No. 2 Docket No. 50-247 License No. DPR-26
REFERENCE:
- 1. NRC letter to Entergy on Indian Point Nuclear Generating Unit No. 2 -
Request for Additional Information Regarding Amendment Application for the Technical Specification on Battery Capacity (TAC. NO. ME0985), dated July 23, 2009
- 2. Entergy Letter to NRC, NL-09-001, Proposed Change to Indian Point 2 Technical Specifications Regarding Battery Capacity Surveillance Requirement, dated March 29, 2009
Dear Sir or Madam:
Entergy Nuclear Operations, Inc (Entergy) is hereby providing a response to the NRC request for additional information, Reference 1, associated with the proposed changes to Indian Point 2 Technical Specification for battery capacity requirements submitted in Reference 2. The response to the question is provided in Attachment 1.
There are no new commitments identified in this submittal. If you have any questions or require additional information, please contact Mr. R. Walpole, Manager, Licensing at (914) 734-6710.
NL-09-128 Docket No. 50-247 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on September l____, 2009.
Sincerely, JEP/sp
Attachment:
- 1. Reply to NRC Request for Additional Information Regarding Proposed Changes Battery Capacity Requirement
Enclosures:
- 1. FEX-00062-01, "Minimum Operating Electrolyte Temperature for 125 V DC Batteries 21, 22, 23, and 24"
- 2. FEX-00204-00, "Station Battery 22 System Calculation" cc: Mr. John P. Boska, Senior Project Manager, NRC NRR Mr. Samuel J. Collins, Regional Administrator, NRC Region I NRC Senior Resident Inspectors Office Mr. Francis J. Murray, Jr., President and CEO, NYSERDA Mr. Paul Eddy, New York State Dept. of Public Service
ATTACHMENT 1 TO NL-09-128 REPLY TO NRC REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED CHANGES BATTERY CAPACITY REQUIREMENT ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET No. 50-247
Attachment 1 NL-09-128 Docket No. 50-247 Page 1 of 1 Response To Request For Additional Information By letter dated March 29, 2009, Accession No. ML090980300, Entergy Nuclear Operations, Inc, (Entergy) requested an amendment to revise the battery capacity acceptance criterion specified in TS Surveillance Requirement (SR) 3.8.6.6. Specifically, the proposed change would modify SR 3.8.6.6 by establishing a more restrictive acceptance criterion regarding periodic verification of battery capacity to ensure the IP2 batteries can perform their intended design functions. The Nuclear Regulatory Commission staff is reviewing the submittal and the following replies to a request for additional information:
Question 1 In the license amendment request, the licensee proposed revising the battery capacity acceptance criterion specified in Technical Specification Surveillance Requirement 3.8.6.6. Please provide the full calculation for the proposed capacity rating, including assumptions and supporting documentation, to show that the 125 Volt direct current batteries will perform their intended design functions.
Response
The change to 85 % battery capacity was originally determined by calculation FEX-00062-01 (Enclosure 1), and provided margin beyond test procedure acceptance criteria of 90 %. The calculation also established a minimum electrolyte temperature of 59 degrees F.
Current DC system calculations use the same 85 % capacity for battery sizing. One of these calculations, FEX-00204, is provided (Enclosure 2) as a sample. This is typical of the calculations performed to ensure intended design functions can be met.
ENCLOSURE 1 TO NL-09-128 FEX-00062-01 "MINIMUM OPERATING ELECTROLYTE TEMPERATURE FOR 125 V DC BATTERIES 21, 22, 23, AND 24" ENTERGY NUCLEAR OPERATIONS, INC INDIAN'POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET No. 50-247
CON EDISON CALCULATION/'ANALYSIS
_- .. COVER SHEET _._
Calculation Number: FEX-00062-01 Type: CAi2 Entry Date: 1/29/98 ELECTRICAL SYSTEM Project Number: NONE- Modification: NONE Document Page: 5 - " Scaunea: N' OldCalculation: EGP-00L021-00 Revision:
Title:
MINIMUM OPERATING ELECTROLYTE TEMPERATURE FOR 125 VD* BATTERIES 2
- 1. 22"2 3 AND 24 7-Drawings Component, .' Component .- Style Type Description Stylel : Description BATT BATTERY BATT BATTERY System Description...
DC BATTERIES AND 125V DC .
Structure Description -
CB CONTROL BUILDING',
.aoe Preparer: R. SULLIVAN / 4 ozo.&t"ýJ1Jp date- Date. Reviewer;:D OHOSH Signter:1~~ 10798 Sigynaifre/Date:
Approval/Date Conifirm. Required?
Required) - "C-oncurrence(If
CON EDISON CALCILATIONI"ANALYSIS SHEET CALCULATION No.- REVISION NO PAGE,.
FEX-00062 :2.
OF .5 PREP ARER/DATE #/$'//f ' . REVIEWER/DATE . CLASS Bruce Horowitz Roger Sullivan Dipti Ghosh
- 1E SUBJECT/TITLE .' I 5 PROJECT No. _
None.
INDIAN POINT - MINIMUM OPERATING ELECTROLYTE TEMPERATURE FOR 125 VDC BATTERIES 21, 22, 23 and 24..
c-D. NO.- _REVN None DESCRIPTION OF CHANGE SIfETET -
Increased minimum electrol1,tc temperature for all Batteries to 59" F Revision Number Description of Change, . Reaso-n for Change (0) Ori-inal Issue. This calculation supersedes " 1997 RF0 Modification Calculation EGE-0002-"00 (OI Increased minimum electrolyle temperature Desinnmargin reduced from 10%to 5%.
to 59 " F. Change in philosophy.on methodology used for.determining minimum temperatures.
CON EDISON CALCULATION/ANALYSIS SHEET - CALCULATION No. PSVISION NO - PAGE FEX-00062 " 1 -
OF s PREPARER/DATE ,, /. - _" REVIEWER/DATE- CLASS Bruce Horowitz Roe r Sullivan .Dipti Ghosh . - " - - 1 E SUBJECT/TITUE K 3 or. - PPOJECT No.
None INDIAN POINT - MINIMUM OPýRATIN4G ELECTROLYTE TEMPERATUIRE FOR 125 VDC BATTERIES 21, 22,23 and 24 MOD. NO. --
" - - None OBJECTIVE '
To develop the minimum operating electrolyte temperature for Batteries 21. 22. 23 and 24. .
METHODOLOGY IEEE 485 Temperature Correction Multiplier.
See Analysis for methodology REFERENCES IEEE 485- 1997 IEEE Recomimnended Practice for Sizine Lead-Acid Batteries for Stationary Applications" Temperature Correction multiplier.
Battery 21 Sizing Calculation FEX-(K)049-01 Battery 22 Sizing Calculation FEX-00050-01I Battery 23 Sizing Calculation FEX-0005 1-01 Battery 24 Sizin-Ca1-lation FEX-00052-01 Batter, 21 Battery Voltage Profile FEX-00053-01 Battery 22 B~attery Voltage Profile FEX-00054-01 Battery 23 Battery Voltage Profile FEX-00055-01 Battery 24 Battery Voltage Profile FEX-00056-01 CONCLUSIONS See Analysis sechion for minknum temperature value.
CON EDISON .CALCULATI;5N/,ANALYSIS SHEET CALCULATION No - . .EVISION R NO. PAGE
. - .. FEX-60062 1 PREPARER/DATE ,//,',r' - REVIEWER/DATE CLASS - -
Bruce Horowitz.- Roger Sullivan Dipti Ghosh - . 1E SUBJECT/TITLE K Mý . .- . PPOJECT No.
None INDIAN POINT - MINIMUM OPERATING ELECTROLYTE TEMPERATURE FOR 125 VDC BATTERIES 21, 22,.23 and 24 MOD. NO. - REV.
None ANALYSIS . * .-. .- : " .I .. . I -
It is Con Edison's design philosoplhy that in calculating the required size of the battery. we use-a 25% ai, factor. 5%design margin and 5qr temperature correction factors. We also require thai when the battery reaches 90% capacily. we are prepared tw replace the battery at the next refueling outage (every 2 years). Ba.ýed on the fact that a lead acid ba-e\ is relatively stable throughout mosI of its life and that the "knee" of the curve for the batters life versus performance is at 80% (per IEEE 485-1907. section 6.2.3), we do not expect the capacity to reach 85% by the time we replace the battery Litthe next refueling outage. This 85% gives us an additional 5%/r maruin that is not accounted for in our sizing and voltage profile calculations. We wil] use this extra 5% in determininr the
- mlinimum electrolyte temperature. The minimum electrolyte temnperature is calculated as jfollows:
Since the 1.25 aging factor is based upon 80% of nameplate capacity. and we will be changing the battery at or prior to 8517r. the aLing factor is I 00/85 = 1.176 To detemine the new temperature correction factor using the revised a.ein, facor, (1.38 = 1,25* 1.05' 1.05') . . .. .. . .. .
T= 1.38/1.176= 1.173 We will add 5% margin (1.05) to the above correction factor to account for any unforeseen conditions.
T= .173i1.05 = 1.117 Bused on Table I ofIEEE-485. thel.nminim1um1 temprirmure is 59" F
'(D,;
6z Std EEE 485-1997
~E~MM~NC~ ~RAc71C~ Fr~~ . -
Note that the~"arpns" rea ired by &31. ajid .o.33ofB ~ 23r,198. are to be applied durin o, ai fication andare not reiatd to design margin.".
Table 1-Cell size correction factors for temperature Electrolyte Eemperatur I 0
(ýF) ý I ý ( C) 35 1.MO_5 40 *.4 4 1.300 15.6 183 18.9 19.4
.*20.0 20.6ý 21.1
-21.7
-'7.
22.8 23.4 23.9 24.5
- 75. II.000J@ 1ý NOTE-This table is based on vented lead-acid nominal 1-215 spcifcgravryr'Ewever; it may be used for vented calls with up to a 1.300 sp--ific gravity. For cells of other dmsigns, refer to the manufacmrer. -
6.2.3 Aging factor As a rule, the performance of a lead-acid bt=t.,"is -relative-lystable troughpout most of its life, but bzgins to decline with increasing rapidity in its latter stages, with the "knee" of its. i.ieversus prfo-rmance c~urve occurring at approxirately 80% of its rated performance.. - - . . ,
MEE Std 450-1995 recommends that a battery be rep~laced when its, actual petfotrmance drops to 90%7 of its rated performance becamse there is little life to b gaed-by.alIowisfi operation beyond this .point. Therefore, to ensure that the battery is capable of medting it* design loads throughout its service life, the batney's rated capacity should be at least 125% (1.25 aging factor) of the load expected at the end of its s#-Vice life..
Ex.cptiohs to this rule exist. For example, some manufacturers recommnd that vented batteries with Plantd, modified.Plantd, and round plate designs be replaced -When: their rieasured capacity'drops below 100% of
,2Y s.2