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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:Licensee 30-Day Written Event Report
MONTHYEARNL-17-134, Radiation Monitor R-26 Inoperable2017-10-11011 October 2017
Radiation Monitor R-26 Inoperable
NL-14-089, Unit Number 3, Event Report for Discovery of a Condition That Prevented Immediate Protective Actions to Avoid Exposures to Radiation from Special Nuclear Material2014-07-22022 July 2014
Unit Number 3, Event Report for Discovery of a Condition That Prevented Immediate Protective Actions to Avoid Exposures to Radiation from Special Nuclear Material
NL-14-040, Submittal of 30-Day 10CFR50.46 Report of Change in Emergency Core Cooling System Model2014-03-18018 March 2014
Submittal of 30-Day 10CFR50.46 Report of Change in Emergency Core Cooling System Model
NL-13-148, Report on Inoperable Main Steam Line Radiation Monitor2013-11-25025 November 2013
Report on Inoperable Main Steam Line Radiation Monitor
ML13094A1322013-03-25025 March 2013
Nmfs'S January 30, 2013 Biological Opinion for Continued Operation of Indian Point Nuclear Generating, Unit 2 and 3
NL-11-103, Report on Inoperable Main Steam Line Radiation Monitor2011-08-24024 August 2011
Report on Inoperable Main Steam Line Radiation Monitor
NL-04-010, Report on Inoperable Post Accident Monitoring Instrument LT-33012004-01-22022 January 2004
Report on Inoperable Post Accident Monitoring Instrument LT-3301
2017-10-11
[Table view] |
Text
Indian Point Energy Center 450 Broadway, GSB P.O. Box249 Buchanan, N.Y. 10511-0249 Tel (914) 254-6700 Anthony J. Vitale Site Vice President NL-17-134 October 11, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
Subject:
Radiation Monitor R-26 Inoperable Indian Point Unit No. 3 Docket No. 50-286 License No. DPR-64
Dear Sir or Madam:
The purpose of this letter is to submit a report pursuant to Technical Specification (TS) 5.6.7. Post Accident Monitoring Instrumentation (PAM) Report. When a report is required by LCO 3.3.3, "PAM Instrumentation," a report shall be submitted within the next 14 days. This report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule fo~ restoring the instrumentation channels of the function to operable status.
On August 28, 2017 at 1033 hours0.012 days <br />0.287 hours <br />0.00171 weeks <br />3.930565e-4 months <br />, Operations entered TS 3.3.3. Condition A for Radiation Monitor R-26 being inoperable due to the troubleshooting for R-26 spiking into alarm. On September 28, 2017, at 1033 hours0.012 days <br />0.287 hours <br />0.00171 weeks <br />3.930565e-4 months <br />, R-26 remained in TS 3.3.3 Condition A for one or more functions of Table 3.3.3-1 with one or more required channels inoperable for an inoperable Function 10. Required Action A.1 is to restore required channel to operable in 30 days. 3TS-17-5557 was initiated on August 28, 2017 to track Allowed Outage Time (AOT).
On September 28, 2017, Condition Report (CR) CR-IP3-2017-04541 recorded that the inoperable R-26 associated with Limiting Condition of Operation (LCO) 3.3.3 exceeded the requirement to be returned to operable with 30 days as of 1033 hours0.012 days <br />0.287 hours <br />0.00171 weeks <br />3.930565e-4 months <br />. TS 3.3.3 Condition B (Required Action and associated Completion Time of Condition A not met) required action 8.1 is to initiate action in accordance with TS 5.6. 7. TS 5.6. 7 requires a report to be submitted to NRC within the next 14 days. The report is to outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrument to operable status.
NL-17-134 Docket No. 50-286 Page 2 of 2
- Alternate method of monitoring While R-26 is inoperable, redundant Radiation Monitor R-25. is operable thereby providing the capability to perform the function. Two operable channels ensure no single failure prevent operators from getting the information necessary for them to
. determine the safety status of the unit following an accident. The containment area radiation monitors are passive in nature in that two critical automatic action is assumed to occur and there is a low probability of and event requiring this PAM instrumentation during the interval with one inoperable channel.
- Cause The apparent cause of inoperability of R-26 due to intermittent spiking and alarms from initial troubleshooting has been determined that a faulty detector signal coming from the radiation cable connections between the detector and meter.
- Plans and Schedule for Restoring Instrument to Operable A vendor has been hired and started .work on October 04, 2017 to repair and/or replace R-26 wiring connections. Once this has been completed, any further troubleshooting will be completed as necessary and the radiation monitor will be calibrated. Work to return R-26 to operable is scheduled to be completed by October 31, 2017.
There are no new commitments contained in this letter. Should you or your staff have any questions regarding this matter, please contact Mr. Robert Walpole, Manager, Regulatory Assurance at (914) 254-6710.
AJV/trj cc: Mr. Daniel H. Dorman, Regional Administrator, NRG Region I Mr. Richard V. Guzman, Senior Project Manager, NRG NRR DORL NRG Resident Inspectors Office, Indian Point Energy Center Mr. Timothy Rice, Bureau of Hazardous Waste & Radiation Management, NYSDEC Ms. Bridget Frymire, New York State Public Service Commission Ms. Alicia Barton, President and CEO, NYSERDA
