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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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Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
Indian Point Energy Center 1 En tergy 295 Broadway, Suite 1 P.O. Box 249 Buchanan, NY 10511-0249 April 03, 2002 Re: Indian Point Unit No. 2 Docket No. 50-247 NL-02-047 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17 Washington, DC 20555-0001
SUBJECT:
Indian Point Nuclear Generating Unit No. 2 - Response to Request for Additional Information Regarding One-time Extension of Containment Integrated Leak Rate Test Frequency (TAC No. MB2414)
References:
- 1. Consolidated Edison letter (NL 01-093) to NRC, "Indian Point 2 License Amendment Request: Containment Integrated Leakage Rate Testing Frequency," dated July 13, 2001
- 2. NRC letter to Entergy Nuclear Operations, Inc., "Indian Point Nuclear Generating Unit No. 2 - Request for Additional Information Regarding One-Time Extension of Containment Integrated Leakage Rate Test Frequency (TAC No. MB2414)," dated October 4, 2001
- 3. Entergy Nuclear Operations, Inc. letter (NL 01 -140) to the NRC, "Indian Point Nuclear Generating Unit No. 2 - Response to Request for Additional Information Regarding One-time Extension of Containment Integrated Leak Rate Test Frequency (TAC MB2414)"
dated November 30, 2001
- 4. NRC letter to Entergy Nuclear Operations, Inc., "Request for Additional Information Regarding One-Time Extension of Containment Integrated Leak Rate Test Frequency, Indian Point Nuclear Generating Unit No. 2 (TAC No. MB2414)," dated February 5, 2002
- 5. Entergy Nuclear Operations, Inc. letter (NL 02-030) to the NRC, "Indian Point Nuclear Generating Unit No. 2 - Response to Request for Additional Information Regarding One-time Extension of Containment Integrated Leak Rate Test Frequency (TAC MB2414)"
dated March 13, 2002 By letter dated July 13, 2001 (Reference 1), Consolidated Edison Company of New York, Inc., (the previous licensee) submitted an application for an amendment to the Technical Specifications (TS) for Indian Point Unit No. 2 (IP2). The proposed amendment would allow a one-time extension of the frequency for the containment integrated leakage rate test from the current interval of one test in 10-years to one test in 15-years.
X\
NL-02-047 Page 2 of 4 The U.S. Nuclear Regulatory Commission (NRC) staff reviewed this submittal, determined that additional information was required to complete its review, and requested the additional information in its letter of October 4, 2001 (Reference 2).
Entergy Nuclear Operations, Inc. (ENO - the current licensee) submitted a response to the NRC's request for additional information in a letter (Reference 3) dated November 30, 2001.
The NRC staff reviewed the additional information provided, determined that additional information was required to complete the review and requested that additional information in its letter of February 5, 2002 (Reference 4). The requested additional information was provided in an ENO letter to the NRC dated March 13, 2002 (Reference 5). After review of this additional information, the NRC staff, in a March 26, 2002 telephone conversation, requested further additional information regarding the cumulative effect on the change in the Large Early Release Frequency (LERF) when going from the original plant baseline case of three tests in 10-years to the proposed one test in 15-years and the basis for the assumed constant liner corrosion failure rate.
Attachment 1 to this letter provides the requested additional information.
The assessment submitted in Reference 1 that concluded that the proposed TS did not involve a significant hazards consideration is not affected by the additional information submitted herein in support of the application.
There are no commitments contained in this letter.
Should you or your staff have any questions regarding this submittal, please contact Mr.
John F. McCann, Manager, Nuclear Safety and Licensing at (914) 734-5074.
Very truly yours, Fred Dacimo Vice President - Operations Indian Point 2 cc: See Page 3 Attachments
NL-02-047 Page 3 of 4 cc:
Mr. Hubert J. Miller Regional Administrator-Region I US Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Patrick D. Milano, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management US Nuclear Regulatory Commission Mail Stop 0-8-2C Washington, DC 20555 NRC Senior Resident Inspector US Nuclear Regulatory Commission PO Box 38 Buchanan, NY 10511 Mayor, Village of Buchanan 236 Tate Avenue Buchanan, NY 10511 Mr. Paul Eddy NYS Department of Public Service 3 Empire Plaza Albany, NY 12223 Mr. William M. Flynn NYS ERDA Corporate Plaza West 286 Washington Ave. Extension Albany, NY 12223-6399
NL-02-047 Page 4 of 4 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )
ENTERGY NUCLEAR OPERATIONS, INC. ) Docket No. 50-247 Indian Point Nuclear Generating Unit No. 2 )
APPLICATION FOR AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the Regulations of the U. S. Nuclear Regulatory Commission (NRC), Entergy Nuclear Operations, Inc., as holder of Facility Operating License No. DPR-26, hereby submits additional information to support the application for amendment of the Technical Specifications, contained in Appendix A of this license, submitted on July 13, 2001.
The specific additional information is set forth in Attachment 1. The assessment submitted on July 13, 2001 demonstrated that the proposed change does not involve a significant hazards consideration as defined in 10CFR50.92(c). That assessment is unchanged by the additional information.
As required by 10CFR50.91 (b)(1), a copy of this submittal has been provided to the appropriate New York State official designated to receive such amendments.
BY:
Fred Dacimc(
Vice President - Operations Indian Point 2 Subscribed and sworn to before me this,3*--- day f) tL ,2002.
Notary Public KAREN L LANCASTER N~otary Public, Sta, Gf New Y-rk No. 04,-C5 QUalified In Wrsthtser con Term E..ir.... q ou.
ATTACHMENT 1 NL-02-047 Response to Request for Additional Information Regarding Proposed One-Time Extension of the Containment Integrated Leakage Rate Test Frequency ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT UNIT NO. 2 DOCKET NO. 50-247
NL-02-047 Attachment 1 Page 1 of 2 The ENO response to the NRC Staff's Request for Additional Information, dated March 13, 2002, provided the results of a sensitivity study that postulated a potential for undetectable containment liner degradation and calculated the effect that this postulated potential might have on the justification for the proposed change in the Integrated Leakage Rate Test (ILRT) Surveillance Interval from one test in 10-years to one test in 15-years. The study accounted for the potential for liner failure based on an assumed constant liner corrosion failure rate and an assumption that the ILRT would detect this corrosion failure.
Request No. 1 In addition to the sensitivity study results provided in the licensee's response to the staff's Request for Additional Information, dated March 13, 2002, the Staff requests that the cumulative effect of the change in the ILRT surveillance interval from the "original baseline" case of three tests in 10-years to the proposed case one test in 15-years be provided.
Response to Request No. 1 The changes in the Large Early Release Frequency (LERF) resulting from extending the ILRT surveillance interval from three tests in 10-years (original baseline case) and one test in 10-years (current license case) to one test in 15-years (proposed amendment) are presented in the following table:
Class 3b Sensitivity Study Contribution from prior Class 7 Total submittal letter Contribution Contribution (NL 01-140) from Class 3b and Class 7 LERF Three tests in 10-years 6.51 E-07/yr. 1.81 E-08/yr. 6.69E-07/yr.
One test in 10-years 7.16E-07/yr. 2.OOE-08/yr. 7.36E-07/yr.
One test in 15-years 7.49E-07/yr. 2.13E-08/yr. 7.70E-07/yr.
Change in LERF From three tests in 10-years 9.8E-08/yr. 3.3E-09/yr. 1.01 E-07/yr.
to one test in 15-years From one test in 10-years to 3.3E-08/yr. 1.3E-09/yr. 3.4E-08/yr.
one test in 15-years
NL-02-047 Attachment 1 Page 2 of 2 Regulatory Guide 1.174 defines very small changes in LERF as less than 1.OE-07/yr.
The change in the LERF resulting from the proposed change in the ILRT frequency, when compared to the "original baseline" case of three tests in 10-years, is 9.8E-08/yr.
The sensitivity study indicates that, even considering the hypothetical case of the postulated potential for undetectable containment liner degradation, the change in LERF due to increasing the ILRT surveillance interval from the "baseline" case of three tests in 10-years to the proposed case of one test in 15-years is comparable to the guidelines in Regulatory Guide 1.174 for defining a very small change. Therefore, the prior conclusion, that the requested extension is considered to be non-risk significant, remains valid even if the postulated potential for undetectable liner degradation is considered and the change is compared to the original licensing basis.
Request No. 2 Provide the basis for the assumed constant liner corrosion failure rate.
Response to Request No. 2 The failure rate (or likelihood) of 100% liner degradation due to the postulated potential for corrosion in uninspectable areas is based on two events among 70 plants in 5 years.
The two events are Brunswick 2 and North Anna 2 (References 1 and 2). The 70 plants is based on the number of plants with a steel-lined concrete containment (Reference 3), and the 5 years is based on the time since changes were made to 10CFR50.55a that require periodic visual inspections of containment surfaces, since September 1996 (Reference 4). The failure rate is then calculated as:
Failure Rate (A)= 2 events / (70 plants
- 5 years) = 0.005714 per year
References:
- 1. BSEP 02-0032, J. S. Keenan (CP&L), "Response to Request for Additional Information Regarding Request for License Amendments - Frequency of Performance-Based Leakage Rate Testing," Feb. 5, 2002
- 2. Virginia Electric and Power Company, North Anna Power Station, Unit 2, LER 99-002, "Containment Liner Through Wall Defect Due to Corrosion," Oct. 21, 1999
- 3. "Commercial Nuclear Power Plants," SCIENTECH-NUS, 20 Edition, January 1998
- 4. NRC Information Notice 97-10, "Liner Plate Corrosion in Concrete Containment,"
March 13, 1997