Letter Sequence Other |
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Results
Other: ML063100364, NL-07-049, NRC Order EA-05-190; Indian Point Emergency Notification System Relaxation Request Regarding Implementation Date (TAC MD2400/2401), NL-08-134, NRC Order EA-05-190, Emergency Notification System Notification of In-Service Date, NL-08-174, Emergency Notification System, Notification of Compliance with NRC Orders EA-05-190, EA-07-189, and Report of Test Results
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MONTHYEARML0620901182006-07-0505 July 2006
E-mail K. Mcmullin (Entergy) to J. Boska (Nrc/Nrr) Et Al., IPEC Status Report for July 5, 2006
Project stage: Request
ML0626202382006-09-26026 September 2006
Acceptance of Test Plan for Indian Point Emergency Notification System in Accordance with NRC Order EA-05-190 (TAC Nos. MD2400 and MD2401)
Project stage: Acceptance Review
ML0631003642006-11-0909 November 2006
Approval of Emergency Plan Change (TAC Nos. MD2400 and MD2401)
Project stage: Other
NL-07-049, NRC Order EA-05-190; Indian Point Emergency Notification System Relaxation Request Regarding Implementation Date (TAC MD2400/2401)2007-04-13013 April 2007
NRC Order EA-05-190; Indian Point Emergency Notification System Relaxation Request Regarding Implementation Date (TAC MD2400/2401)
Project stage: Other
NL-08-134, NRC Order EA-05-190, Emergency Notification System Notification of In-Service Date2008-08-26026 August 2008
NRC Order EA-05-190, Emergency Notification System Notification of In-Service Date
Project stage: Other
NL-08-174, Emergency Notification System, Notification of Compliance with NRC Orders EA-05-190, EA-07-189, and Report of Test Results2008-12-12012 December 2008
Emergency Notification System, Notification of Compliance with NRC Orders EA-05-190, EA-07-189, and Report of Test Results
Project stage: Other
ML0929501132009-10-21021 October 2009
Request for Additional Information Request for Alternative W3-ISI-015 - Third 10-year Inservice Inspection Interval
Project stage: RAI
2007-04-13
[Table View] |
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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
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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
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NL-21-021, Registration of Spent Fuel Cask Use2021-04-19019 April 2021
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NL-21-017, Pre-Notice of Disbursement from Decommissioning Trusts2021-04-0808 April 2021
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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
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NL-20-081, Pre-Notice of Disbursement from Decommissioning Trusts2020-12-0909 December 2020
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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
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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
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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
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NL-20-034, Temporary Exemption Request from 10 CFR Appendix R, Section Iii.H Due to COVID-19 Pandemic2020-04-13013 April 2020
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NL-19-043, Request for Partial Exemption from Record Retention Requirements in 10 CFR 50.122019-10-22022 October 2019
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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
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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] |
Text
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 fBuchanan, N.Y. 10511-0249 ILLI.-I Tel (914) 734-6700 Fred Dacimo Vice President License Renewal December 12, 2008 Indian Point Nuclear Generating Units 2 and 3 Re: Dockets 50-247 and 50-286 NL-08-174 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Indian Point Emergency Notification System; Notification of Compliance with NRC Orders EA-05-190. EA-07-189, and Report of Test Results
REFERENCES:
- 1. NRC letter to Entergy regarding Confirmatory Order EA-05-190 for the Indian Point Emergency Notification System, dated January 31, 2006
- 2. NRC letter to Entergy regarding Confirmatory Order EA-07-189 for the Indian Point Emergency Notification System, dated July 30, 2007
- 3. Entergy letter NL-08-167 to NRC, "NRC Confirmatory Action Letter 1-08-005; Indian Point Emergency Notification System Tone Alert Radios," dated November 3, 2008
- 4. NRC letter to Entergy regarding Confirmatory Action Letter 1-08-005 for the Indian Point Emergency Notification System, dated August 22, 2008
- 5. DHS letter to NYSEMO regarding FEMA approval for the new Indian Point Energy Center Alert and Notification System to go into Service, dated August 22, 2008.
- 6. Entergy letter NL-08-134 to NRC, "NRC Order EA-05-190; Indian Point Emergency Notification System Notification of In-Service Date (TAC MD2400/2401)," dated August 26, 2008
Dear Sir or Madam:
The purpose of this letter is to inform the U.S. Nuclear Regulatory Commission (NRC) that Entergy Nuclear Operations, Inc. (Entergy) has completed all actions associated with NRC Confirmatory Orders (Order) dated January 31, 2006 (EA-05-190) (Reference
- 1) and July 30, 2007 (EA-07-189) (Reference 2), and has achieved compliance with these Orders. As previously reported (Reference 3), Entergy has also met the requirements of the August 22, 2008, Confirmatory Action Letter (1-08-005) (Reference
- 4) regarding Tone Alert Radios. This letter meets the reporting requirements of Sections IV.IV and IV.II.C.5 of Order EA-05-190.
NL-08-174 Dockets 50-247 and 50-286 Page 2 of 3 Order EA-05-190 required, in part, a backup power system for the Emergency Notification System (ENS) for Indian Point Nuclear Generating Units 2 and 3 and specified the system requirements. Order EA-07-189 supplemented, and confirmed, the requirements of the original Order except as specifically modified.
In response to the NRC Orders, Entergy chose to install a new ENS with the required backup power supply capability, while maintaining the existing ENS capable of providing public alert notification. Prior to placing the new ENS system in service, Entergy satisfied all the pre-operational requirements of the Orders, including obtaining Federal Emergency Management Agency (FEMA) approval (Reference 5), and on August 27, 2008, Entergy placed the new ENS in service (Reference 6). Order EA-05-190 Sections IV.II.C.4 and IV.II.C.5 require that after declaring the system operable, periodic ENS testing be performed, and that three such consecutive tests be performed to demonstrate system reliability and to test the operability of all ENS components used during an actual activation. Entergy conducted these tests on September 24, October 22, and November 20, 2008, meeting the requirements of Section IV.Il.C.4 to conduct periodic testing and Section IV.II.C.5 that these tests be conducted no sooner than 25 days and no more than 45 days from the previous test. Order EA-05-190 Section IV.II.C.5 requires an overall emergency planning zone (EPZ) success rate of 97% or greater with no individual county failure rate greater than 10%. The measured overall EPZ success rates were 99.4%, 98.3% and 99.4% respectively for the periodic tests conducted, exceeding the minimum requirement of 97%. Likewise, the lowest measured success rate for any county was 95.65% exceeding the minimum requirement of 90%.
Table 1 provides a summary of the test results.
No new commitments are being made in this letter. Should you have any questions or require additional information, please contact Mr. R. Walpole, Manager, Licensing at (914) 734-6710.
I declare unler the penalty of perjury that the forgoing is true and correct. Executed on (S' neýrely, Fred R. Dacimo Vice President License Renewal Indian Point Energy Center cc: Mr. Eric Leeds, Director, NRC NRR Mr. Samuel J. Collins, Regional Administrator, NRC Region I Mr. John P. Boska, Senior Project Manager, NRC NRR DORL NRC Resident Inspector's Office, Indian Point 2 NRC Resident Inspector's Office, Indian Point 3 Mr. Robert Callender, Vice President, NYSERDA Mr. Paul Eddy, NYS Department of Public Service Ms. Rebecca Thomson, FEMA
NL-08-174 Dockets 50-247 and 50-286 Page 3 of 3 TABLE 1 Summary of Indian Point Emergency Notification System Consecutive Test Results September 24, 2008 EPZ System Success 171/172xl 00 = 99.4% Acceptance Criterion Rate 97% or greater October 22, 2008 EPZ System Success 169/172x1 00 = 98.3% Acceptance Criterion Rate 97% or greater November 20, 2008 EPZ System Success 171/172x1 00 = 99.4% Acceptance Criterion Rate 97% or greater September 24, 2008 Counties Success Rate Acceptance Criterion Orange County 23/23x100 = 100.0%
Putnam County 16/16xl 00 = 100.0% 90% or greater Rockland County 55/56x100 = 98.2%
Westchester County 77/77x100 = 100.0%
October 22, 2008 Counties Success Rate Acceptance Criterion Orange County 22/23x100 = 95.65%
Putnam County 16/16x100= 100.0% 90% or greater Rockland County 55/56x1 00 = 98.2%
Westchester County 76/77x100 = 98.7%
November 20, 2008 Counties Success Rate Acceptance Criterion Orange County 22/23x100 = 95.65%
Putnam County 16/16xl 00 = 100.0%
Rockland County 56/56x100 = 100.0%
Westchester County 77/77x100 = 100.0%
