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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 ffp2 Buchanan, N.Y. 10511-0249 Tel (914) 734-6710 February 25, 2008 Re: Indian Point Nuclear Generating Unit 2 Docket No. 50-247 NL-08-036 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Supplemental Submittal Regarding 10 CFR 50.55a Inservice Testing Program Relief Request P-2 for Recirculation Pump Testing
References:
- 1. Entergy letter NL-07-028 to NRC, "Inservice Testing Program Summary for the 4 th Interval, Revision 0," dated February 28, 2007.
- 2. Entergy letter NL-07-157 to NRC, "10 CFR 50.55a Inservice Testing Program Relief Request P-1 Regarding Recirculation Pump Testing,"
dated December 18, 2007.
Dear Sir or Madam:
Entergy Nuclear Operations, Inc. (Entergy) submitted the 4th Ten-Year Interval Inservice Testing Program Plan for the period March 1, 2007 through April 3, 2016 for Indian Point Unit 2 (IP2). The 4 th Ten-year interval Inservice Testing Program in Reference 1 commenced March 1, 2007 and incorporated the 1995 Edition with the 2003 Addenda of the OM Code as required by 10 CFR 50.55a(b)(3).
A new requirement for the 4th interval involves testing of certain pumps at a flowrate that is within + 20% of the pump design flowrate. The existing configuration of the IP2 recirculation piping associated with the Containment Recirculation Pumps does not allow for testing at this flowrate. Therefore, Reference 2 was submitted by Entergy requesting relief from ASME OM Code requirements, in accordance with 10 CFR 50.55(a)(3), to use a proposed alternative for testing the Containment Recirculation Pumps. Compliance with the new requirement for the 4 th interval requires a modification of IP2 system piping inside containment.
Entergy is hereby submitting a second proposed alternative to the ASME OM Code requirements, in accordance with 10 CFR 50.55(a)(3), in requesting an extension to the performance of the full flow rate test from the current refueling outage, until the following scheduled refueling outage, 2R1 9. This relief would allow us to delay the installation of the piping modification require for the + 20% of the pump design flowrate testing for two years, from the 2008 scheduled refueling outage 2R1 8 (March 25 - April 2008), until the following scheduled IP2 refueling outage, 2R19 in the spring of 2010.
NL-08-036 Docket No. 50-247 Page 2 of 2 Entergy requests the NRC review this relief request (P-2) in parallel and within the same time frame as the previously submitted relief request (P-i) in Reference 2, and requests a response to this request by March 20, 2008.
There are no new commitments contained in this letter.
If you have any questions or require additional information, please contact Mr. Robert Walpole, Manager, Licensing at 914-734-6710.
Sincerely, Robert Walpole Manager, Licensing Indian Point Energy Center cc: Mr. John P. Boska, Senior Project Manager, NRC NRR DORL Mr. Samuel J. Collins, Regional Administrator, NRC Region I NRC Resident Inspector's Office Indian Point Mr. Paul Eddy, New York State Department of Public Service Mr. Paul D. Tonko, President NYSERDA
ATTACHMENT 1 TO NL-08-036 INDIAN POINT 2 SECOND IST RELIEF REQUEST P-2 REGARDING RECIRCULATION PUMP FLOWRATE TESTING ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT GENERATING UNIT NO. 2 DOCKET NO. 50-247
NL-08-036 Docket No. 50-247 Attachment 1 INDIAN POINT UNIT 2 10 CFR 50.55a ISI RELIEF REQUEST P-2 Proposed Alternative In Accordance with 10 CFR 50.55a(a)(3)(i)
Alternative Provides Acceptable Level of Quality and Safety A. ASME Code Component Affected System: Emergency Core Cooling System Component: Containment Recirculation Pumps; 21 RP and 22RP Group: B Class: 2 Function: The Containment Recirculation Pumps are standby pumps which are credited for mitigating the effects of certain hypothetical accident scenarios. These pumps take suction from the recirculation sump in the containment floor and deliver spilled reactor coolant and borated refueling water backto the core through the residual heat exchangers. The pumps do not have any function for support of normal plant operation.
B. Applicable Code Edition and Addenda The applicable-Code edition and addenda are ASME Code for Operation and Maintenance of Nuclear Power Plants (OM), 2001 Edition through 2003 Addenda, which is being invoked for the 4 th Ten-year interval; March 1, 2007 through April 3, 2016.
C. Applicable Code Requirement ISTB-3300(e)(1), "Reference Values", requires that reference values shall be established within +/-20% of pump design flow rate for comprehensive tests.
D. Reason for Request The new requirement of ISTB-3300(e)(1) applicable for the 4 th Ten-year interval cannot be met with the existing configuration of the recirculation piping associated with the Containment Recirculation Pumps. Compliance with the new requirement will require a modification of the system piping.
The design flowrate of the Containment Recirculation Pumps is 3000 gpm so that a test reference value of +/- 20% of the design flowrate per ISTB-3300(e)(1) would require testing at 2400-3600 gpm. The existing recirculation piping for these pumps is a 2-inch diameter which supports a nominal test flowrate of 300 gpm, or 10% of the design flowrate. Testing at 80-120% of the design flowrate will require a plant modification to replace the existing 2-inch diameter recirculation piping with 6-inch diameter piping.
The pumps and the recirculation piping are located in the sump which has limited accessibility and open space as a result of the installation of enhanced suction strainers which provide for improved performance under the new debris blocking assumptions.
The modification to meet the new requirement for the 4th interval involves flowrate that is 1
NL-08-036 Docket No. 50-247 Attachment 1 within + 20% of the pump design flowrate will conflict with the modification to the IP2 sump being completed to meet the requirements of GSI-1 91.
The work in Containment during IP2 2R18 refueling outage for the completion of the sump modification in support of GSI-191 would be performed just below the modification work required for the new full flowrate pump testing. Both of these modifications will require workers to be working in the same area of Containment at the same time with very limited space. This leads to issues and problems with industrial safety and increase dose.
Therefore, Entergy is requesting an extension to the timing of the installation of the modification. Entergy is requesting delaying the modification two years, from the 2008 scheduled refueling outage 2R1 8 (March 25 - April 2008), until the following scheduled IP2 refueling outage, 2R19 in the spring of 2010.
E. Proposed Alternative and Basis for Use The proposed alternative consists of a pump test flowrate of 300 gpm which is 10% of the 3000 gpm design flow. The pump curve for these Ingersoll-Dresser pumps is shown in Figure Two for information. This flowrate is an increase over the 160 gpm test flowrate which was applicable for the previous IST 10-year intervals. Engineering analysis confirms that 300 gpm is achievable with the existing system configuration and does not introduce a risk of localized cavitation at the pump suction. Pump vibration will be measured and recorded in accordance with the criteria specified in the Code.
Vibration spectral analysis will also be performed which is a more accurate method of detecting mechanical degradation or changes than that of the traditional inservice test vibration requirements.
In addition, motor current analysis will be used for each pump motor in the 2R1 8 refueling outage to ensure the motor meets test specifications. The analysis examines the motor for: winding resistance, insulation resistance, polarization index, and motor circuit evaluation. This methodology is used to detect degraded insulation, high resistance shorts and grounds, and the integrity of all motor connections. The predictive maintenance tasks for spectral bearing vibration analysis and motor current analysis will provide additional assurance of operational readiness. With a lack of any significant wear degradation mechanisms, the most likely cause for these pumps to be unavailable would be an electrical fault. The motors are environmentally qualified and the motor current analysis tasks ensure that possible problems are detected and remedied in a timely manner.
The Recirculation Pumps were replaced in 2000 and testing has consistently demonstrated satisfactory performance within the narrow acceptance band established by Engineering for these pumps. A major modification to the pump suction strainer capability for these pumps was completed in 2006. The test arrangement permits testing of the Recirculation Pumps without wetting of the suction strainer mesh filtration system.
The analysis values for minimum and maximum head result in an acceptable operation band which is more conservative than the reduced band allowed in table ISTB-5200-1 used for comprehensive testing. Therefore, degradation will be monitored and action taken conservatively with respect to the Code.
2
NL-08-036 Docket No. 50-247 Attachment 1 In addition, the pump is located in a dry sump section (separated by a weir from the strainer assembly). The pump is only operated at refueling frequency for Code test purposes. The pump does not contain any liquid when not in use. When the test is conducted, the sump section is filled with non-borated water which is removed after the test. Therefore, there is no degradation mechanism which could result in reducing pump effectiveness over time.
The proposed alternative provides a means of assuring the performance capability of these pumps in 2R18, and provides an acceptable level of quality and safety.
F. Duration of Proposed Alternative The proposed alternate testing, consisting of a flow test of at least 10% of design flow, special vibration monitoring and motor current analysis will be preformed on the pumps during the 2008 refueling outage.
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NL-08-036 Docket No. 50-247 Attachment 1 IP2 Relief Request P-1 Figure One - Test Loop Sketch From IP2 Plant Drawing 235296 t II1 4
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