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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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S=Entergy Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel 914 734 6700 Joseph Pollock Site Vice President Administration March 8, 2010 NL-10-030 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Revised Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule Per 10 CFR 50, Appendix H Indian Point Unit Number 2 Docket No. 50-247 License No. DPR-26
REFERENCE:
1 Entergy Letter to NRC, NL-1 0-025, "Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal,'
dated March 4, 2010.
Dear Sir or Madam:
Entergy Nuclear Operations, Inc. (Entergy) requested, Reference 1, NRC approval of a revision to the reactor vessel surveillance specimen withdrawal schedule in accordance with the provisions of 10 CFR 50, Appendix H, Section III.B.3. Entergy discussed that request with the NRC in a telecom on March 5, 2010. A revision to the proposed surveillance capsule revision in reference 1 reflects that telecom. The acceptance criteria used for the surveillance capsule schedule revision remains the same. Approval is requested by March 18, 2010.
Docket No. 50-247 NL-10-030 Page 2 of 2 There are no new commitments identified in this submittal.
If you have any questions or require additional information, please contact Mr. Robert Walpole, Manager, Licensing at (914)734-6710.Sincerely, JEP/sp Attachment
- 1. REVISED PROPOSED REVISION TO REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE PER 10 CFR 50, APPENDIX H cc: Mr. John P. Boska, Senior Project Manager, NRC NRR DORL Mr. Samuel J. Collins, Regional Administrator, NRC Region 1 NRC Resident Inspectors Mr. Francis J. Murray, Jr., President and CEO, NYSERDA Mr. Paul Eddy, New York State Dept. of Public Service ATTACHMENT I TO NL-10-030 REVISED PROPOSED REVISION TO REACTOR VESSEL SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULE PER 10 CFR 50, APPENDIX H ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247 Docket No. 50-247 NL-10-030 Attachment 1 Page 1 of 4 1.0 REQUIREMENTS Appendix H of 10 CFR 50 (Reference
- 1) describes reactor vessel material surveillance program requirements.
Paragraph (111)(B)(3) requires "A proposed withdrawal schedule must be submitted with a technical justification as specified in Section 50.4. The schedule must be approved prior to implementation." Reference 2 allows NRC approval of the proposed changes to the withdrawal schedule without a license amendment if the changes conform with the American Society for Testing and Materials (ASTM) Standard E 185 (Reference 3).2.0 PROPOSED CHANGES The proposed change revises the withdrawal schedule for two of the surveillance capsules which remain in the reactor vessel by adding the flexibility to withdraw capsule S and designating capsule U as a spare. The current schedule and proposed changes are identified in Tables 1 and 2, respectively.
Table 1 -Current Withdrawal Schedule The following is a list of the surveillance program capsules along with the actual (past)and anticipated (future) withdrawal schedule based on the latest fluence and embrittlement calculations performed in accordance with the requirements of Regulatory Guide 1.99, Revision 2 (WCAP-15629).
Capsule Location Lead Factor Withdrawal Date T 3200 3.42 End of Cycle 1 Y 2200 3.48 End of Cycle 2 Z 400 3.53 End of Cycle5 V 40 1.18 End of Cycle 8 S 1400 3.5 Retired in Place U* 1760 1.2 End of Cycle 19 W* 1840 1.2 End of Life X* 3560 1.2 Spare*The withdrawal schedule of these capsules is interchangeable due to common materials and lead factors.
Docket No. 50-247 NL-10-030 Attachment 1 Page 2 of 4 Table 2 -Proposed Withdrawal Schedule Capsule Location Lead Factor Withdrawal Date T 3200 3.42 End of Cycle 1 Y 2200 3.48 End of Cycle 2 Z 400 3.53 End of Cycle5 V 40 1.18 End of Cycle 8 S 1400 3.5 Retired in Place" U* A1760 1.2 Spare W* 1840 1.2 End of Life***X* 3560 1.2 Spare*The withdrawal schedule of these capsules is interchangeable due to common materials and lead factors.Capsule S may be withdrawn during the RFO19 if modified tooling capable of removing the capsule is available.
If not withdrawn no capsule is required.
If withdrawn testing will be coordinated with the industry to optimize the usefulness of the test data.***At end of life as currently licensed, Capsule W (or U or X) will be withdrawn.
The following table provides detailed fluence levels for each of the capsules.Table 3 -Capsule Fluence levels Capsule Capsule Lead Withdrawal Withdrawal Capsule Location Factor Outage EFPY (vessel) Fluence (n/cm 2)T 3200 3.42 RFO1 1.42 2.53 x 10"'Y 2200 3.48 RFO2 2.34 4.55 x 101s Z 4 0 0 3.53 RFO5 5.17 1.02 x 1019 V 40 1 .18 RFO8 8.6 4.92 x 101" S 1400 3.5 *RFO19 or 26.0 (approx) 3.8 x 10'9 retired in place (approx) ***U** 1760 1.2 *RFO19 or Spare 26.0 (approx) 1.3 x 10'9 (approx) ***W** 1840 1.2 End of Life EOL (32 EFPY) 1.5x10" X** 3560 1.2 N/A Spare N/A Notes: *Capsule S will be withdrawn if possible and if not then retired in place**The withdrawal schedule for these three capsules is interchangeable due to the common lead factor and the common materials in the capsules.
Docket No. 50-247 NL-10-030 Attachment 1 Page 3 of 4 Fluence values obtained from Westinghouse letter IPP-01-079, dated April 26, 2001.3.0 TECHNICAL ANALYSIS This request proposes to revise the surveillance capsule withdrawal schedule to allow the attempted removal of Capsule S which is currently retired in place, and to allow capsule U to be declared a spare. If capsule S cannot be successfully removed then it will be maintained as retired in place. It is desired to remove Capsule S at this time since its fluence exceeds 2 times the currently licensed life and exceeds the peak vessel fluence of 1.90 x 1019 at the end of the 48 EFPY projected if License renewal is granted. Westinghouse recently advised that they had increased the load capability of the capsule removal tool and believe that Capsule S could now be removed. Capsule S was retired in RFO16 when the maximum tool removal load was reached and the capsule could not be withdrawn.
The attempt to remove Capsule S at this time is desirable since it is the last remaining capsule with weld material.
Because of the high lead factor of 3.5, Capsule S will have been exposed to a fluence level of approximately 90 EFPY by RFO19. Additional fluence beyond these levels could result in exceeding the fluence limits provided in ASTM E 185 decreasing the usefulness of the data to assess future condition of the belt line materials.
The current withdrawal schedule was approved in 2004 when capsule S was stuck (Reference 4). The surveillance capsules are used to monitor the beltline materials.
The surveillance capsules are located closer to the core than the reactor vessel beltline materials so that fracture toughness testing can be used to determine the nil-ductility transition temperature of the vessel at a later time in life.1 OCFR50, Appendix H requires that the surveillance capsule program "... must meet the requirements of the edition of ASTM E 185 that is current on the issue date of the ASME Code to which the reactor vessel was purchased".
For IP2, this is the 1966 Edition of ASTM E 185. Appendix H also requires that "...For each capsule withdrawal, the test procedures and reporting requirements must meet the requirements of ASTM E 185-82 to the extent practicable for the configuration of the specimens in the capsule".Therefore, for IP2 the surveillance capsule withdrawal schedule is based on the 1966 Edition of ASTM E 185, although the IP2 schedule has been upgraded to meet the requirements of the 1982 Edition of ASTM E 185 to the extent practicable.
Since the peak ARTPTS increase due to fluence exceeds 2000 F, ASTM E 185 requires that five capsules be withdrawn.
To date, four capsules have been withdrawn (capsules T, Y, Z and V) with four capsules (i.e. capsules S, U, W and X) remaining in the vessel.Capsule W is currently scheduled to be the fifth (i.e. the EOL) capsule to satisfy the withdrawal requirements of ASTM E 185.
Docket No. 50-247 NL-10-030 Attachment 1 Page 4 of 4 In addition to the requirements of ASTM E 185, capsule U is also scheduled to be withdrawn during the upcoming end of cycle 19 refueling outage. Since capsule U is not required to meet the requirements of ASTM E 185 (i.e. capsule U is the sixth capsule), designating Capsule U as a spare, even if Capsule S cannot be withdrawn, will have no adverse impact on compliance with the requirements of ASTM E 185.
4.0 REFERENCES
- 1. 10 CFR 50, Appendix H, "Reactor Vessel Material Surveillance Program Requirements." 2. NRC Administrative Letter 97-04, "NRC Staff Approval For Changes to 10 CFR 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules," dated September 30, 1997.3. ASTM Standard E185, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels".4. NRC letter dated November 16, 2004, Indian Point Nuclear Generating Unit No.2 regarding the Reactor Vessel Capsule Withdrawal Schedule Changes (TAC No.MC5059)
