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| 50 59(d)(2) Summary Report of Changes. Tests and Experiments | | 50 59(d)(2) Summary Report of Changes. Tests and Experiments cc: NRG Region I Regional Administrator NRC Senior Project Manager, NRA DORL NRC Senior Resident Inspector New York State Department of Public Service President and CEO, NYSERDA |
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| cc: NRG Region I Regional Administrator NRC Senior Project Manager, NRA DORL NRC Senior Resident Inspector New York State Department of Public Service President and CEO, NYSERDA | |
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| Attachment to NL-19-079 50.59(d)(2) Summary Report of Changes, Tests and Experiments ENTERGY NUCLEAR OPERATIONS, INC. | | Attachment to NL-19-079 50.59(d)(2) Summary Report of Changes, Tests and Experiments ENTERGY NUCLEAR OPERATIONS, INC. |
| Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286 Renewed License No DPR-64 | | Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286 Renewed License No DPR-64 |
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| NL-19-077 Attachment 1 Page 1 of 2 50.59(d)(2) Summary Report of Changes, Tests and Experiments 50.59 Evaluation No. Rev.No TITLE Operation of Auxiliary Feedwater System with CT-19-3001-00 -EVAL 0 82-7 Throttled Open up to 1O gpm without a Dedicated Operator Brief Description of the Change, Test or Experiment: | | NL-19-077 Attachment 1 Page 1 of 2 50.59(d)(2) Summary Report of Changes, Tests and Experiments 50.59 Evaluation No. Rev.No TITLE Operation of Auxiliary Feedwater System with CT-19-3001-00 -EVAL 0 82-7 Throttled Open up to 1O gpm without a Dedicated Operator Brief Description of the Change, Test or Experiment: |
| Due to sodium incursion into the Condensate Storage Tank (CST) from the city water system from seat leakage past closed valves PCV-1189 (33 AFWP City Water Makeup Valve) and BFD-FCV-1123 (33 AFWP Recirculation Control Valve), efforts have been ongoing to remove the sodium by flushing and sampling 33 AFWP suction piping while overflowing the CST with 200 gpm of makeup and cleaning up the CST by recirculating water through the Suez cleanuptskid. | | Due to sodium incursion into the Condensate Storage Tank (CST) from the city water system from seat leakage past closed valves PCV-1189 (33 AFWP City Water Makeup Valve) and BFD-FCV-1123 (33 AFWP Recirculation Control Valve), efforts have been ongoing to remove the sodium by flushing and sampling 33 AFWP suction piping while overflowing the CST with 200 gpm of makeup and cleaning up the CST by recirculating water through the Suez cleanuptskid. |
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| * Attachment 1 Page 2 of 2 50.59(d)(2) Summary Report of Changes, Tests and Experiments As an alternative to having a dedicated operator present inside the AFWP Building during the period in which CT-82-7 is open to flush 33 AFWP suction piping, the following compensatory controls have been identified and will be implemented: | | * Attachment 1 Page 2 of 2 50.59(d)(2) Summary Report of Changes, Tests and Experiments As an alternative to having a dedicated operator present inside the AFWP Building during the period in which CT-82-7 is open to flush 33 AFWP suction piping, the following compensatory controls have been identified and will be implemented: |
Latest revision as of 04:36, 22 February 2020
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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
[Table view] Category:Operating Report
MONTHYEARNL-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-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 NL-17-095, 2017 Form OAR-1 Owners Activity Report for Lnservice Inspection and Repairs and Replacements at Indian Point Unit No. 32017-07-26026 July 2017 2017 Form OAR-1 Owners Activity Report for Lnservice Inspection and Repairs and Replacements at Indian Point Unit No. 3 NL-15-052, Revised Core Operating Limits Report for Cycle 192015-04-21021 April 2015 Revised Core Operating Limits Report for Cycle 19 NL-13-031, Submittal of 2013 Summary Reports for Inservice Inspection and Repairs or Replacements2013-06-18018 June 2013 Submittal of 2013 Summary Reports for Inservice Inspection and Repairs or Replacements ML1029403622010-11-12012 November 2010 October 2010 10 CFR 2.206 Monthly Status Report: Enclosures NL-07-060, Revised Core Operating Limits Report2007-05-15015 May 2007 Revised Core Operating Limits Report 2020-09-01
[Table view] |
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,.~Entergy; . Entergy Nyclffr Operations, Indian Point Energy Center 450 Broadway, GSB P.O. Box249 Buchanan, NY 10511-0249 Inc.
Tel 914 254 6700 Anthony J. Vitale Srte Vice President 10 CFR 50.59(d)(2)
NL-19-079 September 26, 2019 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-2738
Subject:
50.59(d)(2) Summary Report of Changes, Tests and Experiments Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286 License No. DPR-64
Dear Sir or Madam:
Pursuant to 10 CFR 50.59(d)(2), Entergy Nuclear Operations, Inc. (Entergy) herein submits in the Attachment a 50.59 summary report of the changes, tests and experiments implemented at Indian Point Unit No. 3 between May 19, 2017 and April 9, 2019, and/or utilized in support of the UFSAR update. The 50.59 Evaluations set forth in the report represent the changes in the facilities, changes in procedures, or tests and experiments implemented pursuant to 10 CFR 50.59.,
There are r10 new commitments made by Entergy in this submittal. If you have any questions or require additional information, please contact Ms. Mahvash Mirzai, Acting Regulatory Assurance Manager at (914) 254-7714.
Sincerely, AJV/gd
Attachment:
50 59(d)(2) Summary Report of Changes. Tests and Experiments cc: NRG Region I Regional Administrator NRC Senior Project Manager, NRA DORL NRC Senior Resident Inspector New York State Department of Public Service President and CEO, NYSERDA
Attachment to NL-19-079 50.59(d)(2) Summary Report of Changes, Tests and Experiments ENTERGY NUCLEAR OPERATIONS, INC.
Indian Point Nuclear Generating Unit No. 3 Docket No. 50-286 Renewed License No DPR-64
NL-19-077 Attachment 1 Page 1 of 2 50.59(d)(2) Summary Report of Changes, Tests and Experiments 50.59 Evaluation No. Rev.No TITLE Operation of Auxiliary Feedwater System with CT-19-3001-00 -EVAL 0 82-7 Throttled Open up to 1O gpm without a Dedicated Operator Brief Description of the Change, Test or Experiment:
Due to sodium incursion into the Condensate Storage Tank (CST) from the city water system from seat leakage past closed valves PCV-1189 (33 AFWP City Water Makeup Valve) and BFD-FCV-1123 (33 AFWP Recirculation Control Valve), efforts have been ongoing to remove the sodium by flushing and sampling 33 AFWP suction piping while overflowing the CST with 200 gpm of makeup and cleaning up the CST by recirculating water through the Suez cleanuptskid.
The activity of flushing water from 33 AFWP suction Jeader 1s directed from system operating procedure 3-SOP-AFW-002 Section 4.2, "Flush and Sample ABFP Suction Piping". The system operating procedure requires a dedicated operator to be present inside the AFWP Building during flushing of any AFWP suction header to immediately close the drain valve if it becomes necessary for the AFW system to perform its design basis function.
To allow 33 Auxiliary Feedwater Pump (AFWP) Suction Header Drain Valve CT-82-7 to be throttled open up to 1O gpm for continuous flushing without a dedicated operator to perform mitigating actions as required by 3-SOP-AFW-002 with the plant operating at mode 4 or above.
CT-82-7 is a 1" normally closed manual drain valve. This valve is required to maintain pressure boundary integrity in order to ensure adequate inventory In the CST and adequate flow to 33 AFWP.
Summary of the 10 CFR 50.59 Evaluation The condensate storage tank (CST) provides a passive flow of water by gravity to the AFW System. The minimum Technical Specification required CST inventory during operation is 360,000 gallons, which is sufficient to hold the plant at hot shutdown for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following a trip from full power. The water from the CST is used by the AFW system to remove decay and sensible heat from Reactor Coolant System via the steam generators. CST elevation 1s such that suff1c1ent net positive suction head (NPSH) 1s available for the AFW pumps. In addition, an alternate supply of water to the AFW System pumps is provided by a connection to the 1.5-million-gallon City Water Storage Tank (CWST). The CWST maintains a minimum volume of 360,000 gallons of water available 'to provide an alternate water supply to the AFW system.
EC 84031 was developed to provide the work scope for a Temporary Modification to maintain CT-82-7 1n a throttled open pos1t1on without a dedicated operator present inside the AFWP Building. Having the drain valve continuously throttled open without a dedicated operator present inside the AFVVP Building could potentially challenge the Technical Specif1cat1on required volume of water in the CST and the ability of 33 AFW pump to deliver required flow.
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NL-19-077
- Attachment 1 Page 2 of 2 50.59(d)(2) Summary Report of Changes, Tests and Experiments As an alternative to having a dedicated operator present inside the AFWP Building during the period in which CT-82-7 is open to flush 33 AFWP suction piping, the following compensatory controls have been identified and will be implemented:
- 1. CT-82-7 will be throttled open to no more than 1O gpm. This will limit the rate of CST inventory depletion and provide operating personnel ample time to Isolate CT-82-7 to ensure the 360,000 gallon minimum volume limit is not challenged.
- 2. Normal makeup to the CST will be maintained while CT-82-7 is throttled open to ensure that CST water inventory exceeds the 360,000-gallon minimum volume limlt.
- 1. To further ensure that the 360,000 gallons CST Technical Specification level is protected, the setpoint for the CST Trouble Alarm will be changed from the current setting of 19.77 feet to 20.66 feet and automatic isolation of CT-LCV-1158-1 and CT-LCV-1158-2 will be changed from 18.77 feet to 19.66 feet. This change in setpolnts provides more than 19,000 gallons of additional inventory in the CST. The additional inventory provides enough excess water to not challenge the 360,000 gallons minimum Technical Specification requirement for over 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br /> even If CST makeup was not available and valve CT-82-7 remained throttled open at 10 gpm. The additional volume protects the required mission time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of inventory for the CST.
- 4. Operators will verify CT-82-7 is locked or otherwise secured in its preset throttled position once per shift and verify flow rs no greater than 1O gpm every 7 days.
- 5. Plant operatlons personnel will bl:l briefed on these compensatory controls.