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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 Buchanan, N.Y. 10511-0249 IEnta Tel (914) 734-6700 Fred Dacimo Site Vice President Administration May 7, 2007 Indian Point Unit Nos. 2, and 3 Docket Nos. 50-247, and 50-286 NL-07-055 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, Maryland 20852
SUBJECT:
Submittal of Indian Point Response to Generic Letter 2007-01
REFERENCES:
- 1. NRC Generic Letter 2007-01, dated February 7, 2007, "Inaccessible or Underground Power Cable Failures that Disable Accident Mitigation Systems or Cause Plant Transients."
- 2. NEI letter from J. H. Riley to Administrative Points of Contact dated March 26, 2007 "Guidance for Response to GL 2007-01."
- 3. NRC Letter from Michael J. Case, to J. H. Riley dated April 13, 2007, "Response to Nuclear Energy Institute (NEI) Letter Dated March 26, 2007 - Re: Interpretation of Generic Letter (GL) 2007-01, Inaccessible or Underground Power Cable Failures that Disable Accident Mitigation Systems or Cause Plant Transients."
Dear Sir or Madam:
Per reference 1, the NRC issued Generic Letter (GL) 2007-01 to request facilities to submit the following information to the NRC within 90 days of the date of the Generic Letter:
(1) Provide a history of inaccessible or underground power cable failures for all cables that are within the scope of 10 CFR 50.65 (the Maintenance Rule) and for all voltage levels. Indicate the type, manufacturer, date of failure, type of service, voltage class, years of service, and the root causes for the failure.
(2) Describe inspection, testing and monitoring programs to detect the degradation of inaccessible or underground power cables that support EDGs, offsite power, ESW, service water, component cooling water and other systems that are within the scope of 10 CFR 50.65 (the Maintenance Rule).
The response to Item 1 is provided in the attachment to this letter. In researching plant records for the requested information, Entergy Nuclear Operations, Inc. (Entergy) used the NEI and NRC guidance provided in References 2 and 3, respectively, to clarify the population of cables of interest for Indian Point. Data bases researched included Plant Condition Reporting
-/Ii2S
Docket Nos. 50-247, and 50-286 NL-07-055 Page 2 of 2 System (PCRS), Electrical Cable Routing Information System (ECRIS), and personnel interviews.
To date, Indian Point 3 has experienced two (2) cable failures within the scope of the GL and Indian Point 2 has experienced none.
In response to Item 2, Indian Point inspection, testing and monitoring practices presently include visual inspection of cable terminations, periodic meggering / motor current analysis of cables and connected equipment associated with preventative maintenance activities, and periodic inspection of manholes for dewatering. Plant condition reporting is used to determine cause and extent of conditions where deemed necessary and would be the mechanism for determining the need for and extent of any increased cable monitoring.
No new commitments are identified in this submittal.
If you have any questions, or require additional information, please contact Mr. T. R. Jones, Manager, Licensing at (914) 734-6670.
The requested information is being provided pursuant the requirements of 10 CFR 50.54(f). I declare under the penalty of perjury that the foregoing information is true and correct. Executed on May 2007.
nhcere Fred R. Dacimo Site Vice President Indian Point Energy Center - Cable Data Provided In Response to Generic Letter 2007-01 cc: Mr. Samuel J Collins, Regional Administrator, NRC Region I Mr. John Boska, Senior Project Manager, NRC, NRR, DORL Resident Inspector's Office Mr. Paul Eddy, NYS Dept. of Public Service Mr. Peter R. Smith, President, NYSERDA
Attachment 1 To NL-07-055 Cable Data Provided In Response to Generic Letter 2007-01 ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT 2 AND 3 NUCLEAR POWER PLANTS DOCKET NOS. 50-247 AND 50-286 DPR-26 AND 64
NL-07-055 Attachment 1 Docket Nos. 50-247, and 50-286 Page 1 of 1 History of Inaccessible or Underground Power Cable Failures within the Scope of 10CFR 50.65 for Indian Point Cable Type Voltage Manufacturer Date of Failure Type of Root Cause Comments Class I I Service (Yrs.) Service Service Lead Jacket 600 VAC 350 MCM, lead 1994/1975- One phase of Mechanically induced damage Cable within scope of Maintenance
/480 sheathed and 1994 (19 years) feed to resulted in arcing as a result of Rule and experienced catastrophic VAC copper 33SWP moisture and accumulation of failure during operation. Replaced conductor (37 (normally corrosion product in the damaged by Mod 94-3-311 with Okonite copper wires, energized) area. Damage possibly due to cable cable with copper bearing, lead Inner PVC installation or installation of a new sheath, and qualified for water Insulation .10 in adjacent duct bank. Moisture due to submergence.
thick, lead rain with subsequent drying. No cable sheath .09 in degradation due to moisture ingress.
thick, Outer Analysis of cable failure performed by PVC jacket .07 Lucius Pitkin (Ref Report No in thick) M94548).
Lead Jacket 600 VAC Same 2005 /1975 - One phase of Probable cause was insulation Cable within scope of Maintenance
/ 480 2005 (30 years) feed to thinning during original installation Rule and degraded condition found VAC 33SWP with subsequent degradation or during motor current analysis (normally damage during the duct bank collapse (MCA) testing prior to failure.
energized) repaired in 1994. Degradation Replaced (different conductor than contributing cause was submergence the one replaced during 1994 ) by of cable for extended period of time. Mod 1P3-05-20151 with General Moisture due to rain with subsequent Cable Dura Sheath drying. Analysis performed CR-IP3-2005-2634.
Text
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, N.Y. 10511-0249 IEnta Tel (914) 734-6700 Fred Dacimo Site Vice President Administration May 7, 2007 Indian Point Unit Nos. 2, and 3 Docket Nos. 50-247, and 50-286 NL-07-055 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, Maryland 20852
SUBJECT:
Submittal of Indian Point Response to Generic Letter 2007-01
REFERENCES:
- 1. NRC Generic Letter 2007-01, dated February 7, 2007, "Inaccessible or Underground Power Cable Failures that Disable Accident Mitigation Systems or Cause Plant Transients."
- 2. NEI letter from J. H. Riley to Administrative Points of Contact dated March 26, 2007 "Guidance for Response to GL 2007-01."
- 3. NRC Letter from Michael J. Case, to J. H. Riley dated April 13, 2007, "Response to Nuclear Energy Institute (NEI) Letter Dated March 26, 2007 - Re: Interpretation of Generic Letter (GL) 2007-01, Inaccessible or Underground Power Cable Failures that Disable Accident Mitigation Systems or Cause Plant Transients."
Dear Sir or Madam:
Per reference 1, the NRC issued Generic Letter (GL) 2007-01 to request facilities to submit the following information to the NRC within 90 days of the date of the Generic Letter:
(1) Provide a history of inaccessible or underground power cable failures for all cables that are within the scope of 10 CFR 50.65 (the Maintenance Rule) and for all voltage levels. Indicate the type, manufacturer, date of failure, type of service, voltage class, years of service, and the root causes for the failure.
(2) Describe inspection, testing and monitoring programs to detect the degradation of inaccessible or underground power cables that support EDGs, offsite power, ESW, service water, component cooling water and other systems that are within the scope of 10 CFR 50.65 (the Maintenance Rule).
The response to Item 1 is provided in the attachment to this letter. In researching plant records for the requested information, Entergy Nuclear Operations, Inc. (Entergy) used the NEI and NRC guidance provided in References 2 and 3, respectively, to clarify the population of cables of interest for Indian Point. Data bases researched included Plant Condition Reporting
-/Ii2S
Docket Nos. 50-247, and 50-286 NL-07-055 Page 2 of 2 System (PCRS), Electrical Cable Routing Information System (ECRIS), and personnel interviews.
To date, Indian Point 3 has experienced two (2) cable failures within the scope of the GL and Indian Point 2 has experienced none.
In response to Item 2, Indian Point inspection, testing and monitoring practices presently include visual inspection of cable terminations, periodic meggering / motor current analysis of cables and connected equipment associated with preventative maintenance activities, and periodic inspection of manholes for dewatering. Plant condition reporting is used to determine cause and extent of conditions where deemed necessary and would be the mechanism for determining the need for and extent of any increased cable monitoring.
No new commitments are identified in this submittal.
If you have any questions, or require additional information, please contact Mr. T. R. Jones, Manager, Licensing at (914) 734-6670.
The requested information is being provided pursuant the requirements of 10 CFR 50.54(f). I declare under the penalty of perjury that the foregoing information is true and correct. Executed on May 2007.
nhcere Fred R. Dacimo Site Vice President Indian Point Energy Center - Cable Data Provided In Response to Generic Letter 2007-01 cc: Mr. Samuel J Collins, Regional Administrator, NRC Region I Mr. John Boska, Senior Project Manager, NRC, NRR, DORL Resident Inspector's Office Mr. Paul Eddy, NYS Dept. of Public Service Mr. Peter R. Smith, President, NYSERDA
Attachment 1 To NL-07-055 Cable Data Provided In Response to Generic Letter 2007-01 ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT 2 AND 3 NUCLEAR POWER PLANTS DOCKET NOS. 50-247 AND 50-286 DPR-26 AND 64
NL-07-055 Attachment 1 Docket Nos. 50-247, and 50-286 Page 1 of 1 History of Inaccessible or Underground Power Cable Failures within the Scope of 10CFR 50.65 for Indian Point Cable Type Voltage Manufacturer Date of Failure Type of Root Cause Comments Class I I Service (Yrs.) Service Service Lead Jacket 600 VAC 350 MCM, lead 1994/1975- One phase of Mechanically induced damage Cable within scope of Maintenance
/480 sheathed and 1994 (19 years) feed to resulted in arcing as a result of Rule and experienced catastrophic VAC copper 33SWP moisture and accumulation of failure during operation. Replaced conductor (37 (normally corrosion product in the damaged by Mod 94-3-311 with Okonite copper wires, energized) area. Damage possibly due to cable cable with copper bearing, lead Inner PVC installation or installation of a new sheath, and qualified for water Insulation .10 in adjacent duct bank. Moisture due to submergence.
thick, lead rain with subsequent drying. No cable sheath .09 in degradation due to moisture ingress.
thick, Outer Analysis of cable failure performed by PVC jacket .07 Lucius Pitkin (Ref Report No in thick) M94548).
Lead Jacket 600 VAC Same 2005 /1975 - One phase of Probable cause was insulation Cable within scope of Maintenance
/ 480 2005 (30 years) feed to thinning during original installation Rule and degraded condition found VAC 33SWP with subsequent degradation or during motor current analysis (normally damage during the duct bank collapse (MCA) testing prior to failure.
energized) repaired in 1994. Degradation Replaced (different conductor than contributing cause was submergence the one replaced during 1994 ) by of cable for extended period of time. Mod 1P3-05-20151 with General Moisture due to rain with subsequent Cable Dura Sheath drying. Analysis performed CR-IP3-2005-2634.
