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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
[Table view] Category:Technical Specifications
MONTHYEARML23339A0442023-12-0505 December 2023 Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan ML22307A0452023-11-17017 November 2023 Enclosure 1 - Amendment No. 297 to Rfl No. DPR-26 for Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements with Spent Fuel Transfer to Dry Storage ML23100A1172023-11-17017 November 2023 NRC Response - Indian Point Energy Center Generating Units 1, 2, and 3 Letter with Enclosures Regarding Changes to Remove the Cyber Security Plan License Condition ML20297A3262020-11-23023 November 2020 Enclosure 2, Draft Conforming Amendments for Transfer of Facility Operating Licenses to Holtec International, Owner, and Holtec Decommissioning International, LLC, Operator ML20100H9922020-06-0202 June 2020 Issuance of Amendment No. 269 Proposed Technical Specification Changes to City Water Surveillance Requirement and Condensate Storage Tank Required Action A.1 ML20081J4022020-04-28028 April 2020 Issuance of Amendment No. 294 Permanently Defueled Technical Specifications ML20110A0052020-04-27027 April 2020 Correction to Amendment No. 267 Issued April 10, 2020, Changes to Technical Specifications for a Permanently Defueled Condition ML20071Q7172020-04-10010 April 2020 Issuance of Amendment Nos. 292 and No. 267 Changes to Technical Specification Sections 1.1, 4.0, and 5.0 for a Permanently Defueled Condition ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML19072A1342019-03-15015 March 2019 Amended Provisional Operating License DPR-5, 3-22-2019 ML18212A1902018-09-17017 September 2018 Renewed Facility Operating License DPR-64, Technical Specifications, Appendix a ML18212A1852018-09-17017 September 2018 Renewed Facility Operating License DPR-26, Technical Specifications, Appendix B ML18212A1942018-09-17017 September 2018 Renewed Facility Operating License DPR-64, Technical Specifications, Appendix B ML18212A1952018-09-17017 September 2018 Renewed Facility Operating License DPR-64, Technical Specifications, Appendix C ML16064A2152016-04-12012 April 2016 Issuance of Amendments Cyber Security Plan Implementation Schedule NL-16-027, Response to Request for Additional Information Related to License Amendment Request Regarding Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement2016-03-0202 March 2016 Response to Request for Additional Information Related to License Amendment Request Regarding Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement ML15349A7942016-02-23023 February 2016 Generation, Unit No. 2 - Issuance of Amendment Extension of the Containment Integrated Leak Rate Test to 15 Years NL-15-144, License Amendment Request - Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement2015-12-10010 December 2015 License Amendment Request - Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement NL-15-144, Indian Point, Units 2 and 3 - License Amendment Request - Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement2015-12-10010 December 2015 Indian Point, Units 2 and 3 - License Amendment Request - Conditional Exemption from End-of-Life (Eol) Moderator Temperature Coefficient (Mtc) Measurement NL-15-118, Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 32015-09-0303 September 2015 Post Accident Monitoring (PAM) Report for an Inoperable Reactor Vessel Level Indication System (RVLIS) Train B, Indian Point Unit 3 ML15226A1592015-09-0303 September 2015 Issuance of Amendment Changes to Reactor Vessel Heatup and Cooldown Curves and Low Temperature Overpressure Protection System Requirements ML15110A0092015-05-26026 May 2015 Issuance of Amendment Re Implementation of Technical Specification Task Force Traveler 510, Revision 2, Revision to Steam Generator Program Inspection Frequencies & Tube Sample Selection(Tac Nos. MF3752 & MF3753) ML15083A4902015-04-0202 April 2015 Issuance of Amendment Proposed License Amendment Regarding a Change to Technical Specification 3.1.4 Reactivity Control Systems ML15028A3082015-03-13013 March 2015 Issuance of Amendment Extension of the Type a Containment Integrated Leak Rate Test Frequency from 10 to 15 Years NL-14-128, Proposed License Amendment Regarding Extending the Containment Type a Leak Rate Testing Frequency to 15 Years2014-12-0909 December 2014 Proposed License Amendment Regarding Extending the Containment Type a Leak Rate Testing Frequency to 15 Years ML14265A3292014-09-24024 September 2014 Issuance of Amendment Temporary Change to Technical Specification 3.8.6 Battery 22 Surveillance Requirement (Exigent Circumstances) ML14287A2942014-09-17017 September 2014 Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Requirements Manual NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Requirements Manual2014-09-17017 September 2014 Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Requirements Manual ML14198A1612014-09-0505 September 2014 Issuance of Amendment H* Alternate Repair Criteria for Steam Generator Tube Inspection and Repair (Tac No. MF3369) ML14169A5832014-07-17017 July 2014 Issuance of Amendment Revised Containment Integrity Analysis (Tac No. MF0591) NL-14-053, Response to Request for Additional Information Regarding Emergency Diesel Generator Fuel Oil Storage Supplies2014-04-14014 April 2014 Response to Request for Additional Information Regarding Emergency Diesel Generator Fuel Oil Storage Supplies NL-14-035, Proposed Changes to Technical Specifications Regarding Reactor Vessel Pressure/Temperature Limit Curves2014-04-0101 April 2014 Proposed Changes to Technical Specifications Regarding Reactor Vessel Pressure/Temperature Limit Curves ML14045A2482014-03-0505 March 2014 Issuance of Amendment Pressure-Temperature Limit Curves and Low Temperature Over Pressure Requirements NL-14-032, Supplemental Information to Proposed Changes to Indian Point 2 Technical Specifications Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Over Pressure Requirements Indian Point Unit Number 22014-02-24024 February 2014 Supplemental Information to Proposed Changes to Indian Point 2 Technical Specifications Regarding Reactor Vessel Heatup and Cooldown Curves and Low Temperature Over Pressure Requirements Indian Point Unit Number 2 NL-14-001, Indian Point, Unit 2 - Proposed License Amendment for Alternate Repair Criteria for Steam Generator Tube Inspection and Repair2014-01-16016 January 2014 Indian Point, Unit 2 - Proposed License Amendment for Alternate Repair Criteria for Steam Generator Tube Inspection and Repair NL-14-001, Proposed License Amendment for Alternate Repair Criteria for Steam Generator Tube Inspection and Repair2014-01-16016 January 2014 Proposed License Amendment for Alternate Repair Criteria for Steam Generator Tube Inspection and Repair CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications NL-12-039, Proposed License Amendment Regarding Atmospheric Dump Valves2012-05-23023 May 2012 Proposed License Amendment Regarding Atmospheric Dump Valves NL-12-002, Proposed Change to Containment Purge System and Pressure Relief Line Isolation Instrumentation Technical Specifications2012-01-11011 January 2012 Proposed Change to Containment Purge System and Pressure Relief Line Isolation Instrumentation Technical Specifications NL-11-119, Proposed Change to the Technical Specification Requirement for Containment Sump Level Indication2011-10-18018 October 2011 Proposed Change to the Technical Specification Requirement for Containment Sump Level Indication NL-10-072, Proposed Technical Specification Change Regarding RWST Surveillance Requirement2010-10-0606 October 2010 Proposed Technical Specification Change Regarding RWST Surveillance Requirement NL-09-167, Proposed Exigent License Amendment Re One Time Extension of the Auxiliary Boiler Feedwater Pump Allowed Outage Time2009-12-15015 December 2009 Proposed Exigent License Amendment Re One Time Extension of the Auxiliary Boiler Feedwater Pump Allowed Outage Time NL-09-129, Indian Point, Unit 3, Proposed License Amendment to Change Technical Specifications Regarding Surveillance Requirements for AC and DC Sources2009-11-19019 November 2009 Indian Point, Unit 3, Proposed License Amendment to Change Technical Specifications Regarding Surveillance Requirements for AC and DC Sources NL-09-129, Proposed License Amendment to Change Technical Specifications Regarding Surveillance Requirements for AC and DC Sources2009-11-19019 November 2009 Proposed License Amendment to Change Technical Specifications Regarding Surveillance Requirements for AC and DC Sources NL-09-119, Proposed License Amendment Regarding Diesel Generator Air Start Receiver Pressure, Indian Point Units 2 & 32009-11-17017 November 2009 Proposed License Amendment Regarding Diesel Generator Air Start Receiver Pressure, Indian Point Units 2 & 3 ML0834304242009-05-29029 May 2009 License Amendment, Technical Specifications Regarding Removal of Spent Fuel from Unit 1 and Drain Down of the Spent Fuel Pool NL-08-137, Reply to Request for Additional Information Regarding Amendment Application on Control Room Envelope Habitability2008-09-18018 September 2008 Reply to Request for Additional Information Regarding Amendment Application on Control Room Envelope Habitability ML0811401772008-06-0909 June 2008 Tec Specs to Amedment 236, License No. DPR-64 for Indian Point, Unit 3 ML0727805822007-10-0404 October 2007 Technical Specifications, Change of Pressure-temperature and Low Temperature Protection System Limits ML0722901282007-08-16016 August 2007 Technical Specifications 2023-12-05
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Enterqy Nuclear Northeast Entergy, Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel 914 254 6700 John A. Ventosa Site Vice President Administration January 11, 2012 NL-12-002 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Proposed Change to Containment Purge System and Pressure Relief Line Isolation Instrumentation Technical Specifications Indian Point Nuclear Generating Unit 2 Docket No. 50-247 License No. DPR-26
Dear Sir or Madam:
Pursuant to 10 CFR 50.90, Entergy Nuclear Operations, Inc. (Entergy) hereby requests an amendment to the Facility Operating License Number DPR-26 for Indian Point Nuclear Generating Unit 2 (IP2). The proposed amendment will revise Technical Specification (TS) Table 3.3.6-1 by replacing the "Allowable Value" "< 3 background" with "Trip Setpoint" "(a) As specified in the IP2 Offsite Dose Calculation Manual." provides a description of the proposed changes and an evaluation of the proposed changes in accordance with 10 CFR 50.91 (a)(1) using criteria of 10 CFR 50.92 (c) and has determined that the proposed changes involve no significant hazards considerations. Attachment 2 provides the marked up copy of the proposed changes. No changes to the Bases are planned for this change. A copy of this application and the associated attachments are being submitted to the designated New York State official in accordance with 10CFR 50.91(a)(1).
Entergy requests approval of the proposed amendment within 12 months and an allowance of 30 days for implementation. There are no new commitments identified in this submittal. If you have any questions or require additional information, please contact Mr. Robert Walpole, IPEC Licensing Manager at (914) 254-6710.
NL-1 2-002 Dockets 50-247 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on January ./_
2012.
Sincerely, JV/sp Attachments: 1. Analysis of Proposed Technical Specification Change regarding Containment Purge System and Pressure Relief Line Isolation Instrumentation
- 2. Markup of Technical Specification Page for Proposed Changes regarding Containment Purge System and Pressure Relief Line Isolation Instrumentation cc: Mr. John P. Boska, Senior Project Manager, NRC NRR DORL Mr. William M. Dean, 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 1 TO NL-12-002 ANALYSIS OF PROPOSED TECHNICAL SPECIFICATION CHANGE REGARDING CONTAINMENT PURGE SYSTEM AND PRESSURE RELIEF LINE ISOLATION INSTRUMENTATION ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NO. 50-247
NL-12-002 Dockets 50-247 Attachment 1 Page 1 of 6
1.0 DESCRIPTION
This is a request to amend Operating License DPR-26, Docket 247, for Indian Point Unit 2 (IP2).
The proposed amendment would change the term "ALLOWABLE VALUE" to "TRIP SETPOINT" and revise the current setpoint used for the Containment Purge Systems and Pressure Relief Line isolation. The proposed revision to Table 3.3.6-1 table will change "< 3 background" to allow the allowable value to be as specified in the Offsite Dose Calculation Manual (ODCM) (Reference 1).
2.0 PROPOSED CHANGE
Proposed changes to Section 3.3.6, Table 3.3.6-1 of the Indian Point 2 Technical Specifications are identified below:
Indian Point 2 Technical Specification 3.3.6, Table 3.3.6-1 currently says:
REQUIRED SURVEILLANCE FUNCTION CHANNELS REQUIREMENTS ALLOWABLE VALUE 2.a Gaseous Containment Radiation (R-42) 1 SR 3.3.6.1 < 3 x background SR 3.3.6.4 SR 3.3.6.6 2.b Particulate Containment Radiation (R-41) 1 SR 3.3.6.1 < 3 x background SR 3.3.6.4 SR 3.3.6.6 The proposed amendment will revise Table 3.3.6-1 to say:
REQUIRED SURVEILLANCE FUNCTION CHANNELS REQUIREMENTS TRIP SETPOINT 2.a Gaseous Containment Radiation (R-42) 1 SR 3.3.6.1 (a)
SR 3.3.6.4 SR 3.3.6.6 2.b Particulate Containment Radiation (R-41) 1 SR 3.3.6.1 (a)
SR 3.3.6.4 SR 3.3.6.6 (a) As specified in the Offsite Dose Calculation Manual. -
No changes to the Bases Section associated with the proposed change are needed.
NL-12-002 Dockets 50-247 Attachment 1 Page 2 of 6
3.0 BACKGROUND
Both the containment purge supply and exhaust isolation valves (FCV-1 170, FCV-1 171, FCV-1172, and FCV-1 173) and the containment pressure relief line isolation valves (PCV-1 190, PCV-1191 and PCV-1 192) close when high radiation levels are detected by the Containment Air Particulate Monitor (R-41) or Containment Radioactive Gas Monitor (R-42). The Containment Phase A Isolation ESFAS signal and Containment Spray ESFAS signal also cause closure of the containment purge isolation valves and the containment pressure relief isolation valves.
The use of the allowable value / setpoint of "_<3 x background" is not the best specification for the stated purpose. The value is too low creating the potential for unnecessary isolation and requiring adjustment of the setpoint on a more frequent basis as the background changes during the operational cycle.
The Standard Technical Specification (STS) 3.3.6 have the same stated purpose as IP2 and the Setpoint is "_<2 x background." This change is therefore a deviation from the STS but it has been adopted at a number of plants where the problems have been identified. For example:
- 1. Wolf Creek has the trip setpoint for the containment atmosphere gaseous radioactive monitor set point established such that the actual submersion rate would not exceed 9mR/hr in the Containment.
- 2. Ginna has the trip setpoint for the containment gaseous and particulate radiation monitors set per the Radiological Effluent Controls Program.
- 3. Byron / Braidwood has the trip setpoint for the containment radiation - high established such that the actual submersion rate is < 10 mR/hr but allows the trip setpoint to be increased above this value in accordance with the methodology established in the Offsite Dose Calculation Manual.
- 4. Indian Point 3 has the trip setpoint for the containment gaseous and particulate radiation monitors set per the Offsite Dose Calculation Manual.
- 5. Diablo Canyon has the trip setpoint for the containment gaseous and particulate radiation monitors set per the Offsite Dose Calculation Manual.
The proposed change from "ALLOWABLE VALUE" to "TRIP SETPOINT" is based on an editorial error during the conversion to standard technical specifications (STS). The conversion changed the STS "TRIP SETPOINT" to "ALLOWABLE VALUE" without the intent to do so. This corrects the error.
4.0 TECHNICAL ANALYSIS
The purpose of this proposed amendment is to restore the term "TRIP SETPOINT" as the heading on the last column of Table 3.3.6-1 and to change the value from "< 3 x background" to reference the Offsite Dose Calculation Manual (ODCM) methodology.
NL-12-002 Dockets 50-247 Attachment 1 Page 3 of 6 The Standard Technical Specification (STS) requires radiation monitors with a SETPOINT of "< 2 x background" for Containment Purge System and Pressure Relief Line isolation following an accident. When IP2 converted to the STS no change to the term "TRIP SETPOINT" in the heading of Table 3.3.6-1 was proposed. The final submittal of TS 3.3.6 (Revision 4, Supplement 7) contained the IP2 Improved TS and Bases in part 1 and a markup to show the differences between NUREG-1431 and the IP2 STS in part 3. The final typed version in part 1 had the heading "ALLOWABLE VALUE" while the markup in part 3 had the heading "TRIP SETPOINT." It appears that an editorial error inadvertently changed "TRIP SETPOINT" to "ALLOWABLE VALUE."
Correction of this administrative error has no affect on plant design or operations. Correction of this administrative error has no bearing on accident precursor conditions or events and therefore cannot lead to an increase in the probability of an accident or create the probability of a new or different type of accident than previously evaluated. Correction of this administrative error cannot lead to an increase in the consequences of an accident previously evaluated or affect the margin to safety.
The TS 3.3.6 Bases notes "Containment purge system and pressure relief line isolation instrumentation closes the containment isolation valves in the Containment Purge System (containment purge supply line and containment purge exhaust line) and the Containment Pressure Relief Line. This action isolates the containment atmosphere from the environment to minimize releases of radioactivity in the event of an accident." The Bases further note that the "safety analyses assume that the containment remains intact with penetrations unnecessary for core cooling isolated early in the event, within approximately 60 seconds." The proposed change to reference a setpoint set by the ODCM methodology will result in a higher setpoint than the "< 3 x background" but will still meet the safety function of the instrumentation. The source term from an accident event (Reference 2) is greater than the setpoints the ODCM setpoint will use.
Section 3.2.1 of the ODCM (Reference 1) requires the dose rates for radioactive materials released in gaseous effluents to meet specific limits. When these limits are exceeded the release must be stopped immediately. The release rates are those that would give an annual dose of < 500 mrem whole body or 3 rem skin due to noble gases or that would give an annual dose of 1.5 rem to any organ due to all radionuclide in particulate form with half lives > 8 days. The release rates apply to the site and are conservatively established, as discussed in the ODCM, in order to assure compliance with 10 CFR 20 limits. The current setpoint of "< 3 x background" achieves this purpose but it can also result in unnecessary isolations unless the setpoint is adjusted as the background changes. Changing the setpoint to match the ODCM methodology would eliminate this potential while providing adequate assurance that the results of an accident would not increase because these release rates are below those of the accident analyses.
The use of the ODCM to set the release rate eliminates the need to readjust the trip setpoint as the background levels change inside containment. Further, the risk of spurious trips is eliminated. The margins associated with accident analyses are slightly reduced because a higher level of radioactivity is required to trip the isolation. However, the effect is minimal since the fuel handling accident did not credit isolation, the gas tank ruptures are in the auxiliary building, the SG tube rupture is outside containment, the steam line break is also outside containment and gives the highest dose, and the LOCA source term will go from < 3 x background to the new setpoint in such.
a short time there is no practical difference.
NL-12-002 Dockets 50-247 Attachment 1 Page 4 of 6 Changing the setpoint does not affect the manner in which the plant is operated or controlled so there is no possibility of a different type of accident.
5.0 REGULATORY ANALYSIS
5.1 No Significant Hazards Consideration Entergy Nuclear Operations, Inc. (Entergy) has evaluated the safety significance of the proposed change of Containment Purge and Pressure Relief Line Systems isolation TS. The evaluation was for the change of the term "ALLOWABLE VALUE" to "TRIP SETPOINT" and the proposed revision to the setpoint from "< 3 background" to allow the allowable value to be as specified in the Offsite Dose Calculation Manual (ODCM) according to the criteria of 10 CFR 50.92, "Issuance of Amendment". Entergy has concluded that the subject changes do not involve a Significant Hazards Consideration as discussed below: Containment Purge Systems and Pressure Relief Line
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No. The proposed change will revise the term "ALLOWABLE VALUE" to "TRIP SETPOINT" and change the setpoint requirements from "< 3 background" to allow the allowable value to be as specified in the Offsite Dose Calculation Manual (ODCM). The change to trip setpoint is a correction of an administrative error and will only affect the instrument setting specified. Therefore it does not involve the initiation of an accident or the consequences. The values for the instrument setting are provided for isolating the Containment Purge and Pressure Relief Systems due to increased source terms and are redundant to containment isolation signals. They have no effect on the probability of an accident previously evaluated. The change in the setting will be negligible for purposes of an accident termination. The ODCM limits are based on 10CFR20 limits which are substantially below accident analysis release rates. Therefore the change has a minimum effect on the consequences of such accidents. Therefore, the proposed changes do not involve a significant increase in the probability or consequences of previously evaluated accidents.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No. The proposed change will revise the term "ALLOWABLE VALUE" to "TRIP SETPOINT" and change the setpoint requirements. The changes do not affect the system operations, plant operating procedures or affect how the plant is operated. The change does not create the possibility of any equipment failure or effect on other equipment. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
NL-12-002 Dockets 50-247 Attachment 1 Page 5 of 6 Response: No. The proposed change will revise the term "ALLOWABLE VALUE" to "TRIP SETPOINT" and change the setpoint requirements. The change to trip setpoint is correcting an administrative error and has no significant affect on the margin of safety. The proposed change involves changes to existing setpoints for automatic isolation of the Containment Purge and Pressure Relief Systems.
However, the ability of the systems to isolate remains within current evaluations and therefore does not significantly reduce the safety margin. Therefore, the proposed changes do not involve a significant reduction in a margin of safety.
Based on the above, Entergy Nuclear Operations, Inc. concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92 (c),
and, accordingly, a finding of "no significant hazards consideration" is justified.
5.2 Applicable Regulatory Requirements / Criteria The proposed changes have been evaluated to determine whether applicable requirements continue to be met. The Containment Purge and Pressure Relief Line Systems are isolated by radiation monitors as backup to the ESF system to ensure Containment Isolation. This insures meeting the Containment leakage assumption of accident analyses demonstrating compliance with 10 CFR 100. This instrumentation will continue to perform this function and will satisfy Criterion 3 of 10 CFR 50.36(c)(2)(ii) 5.3 Environmental Considerations The proposed changes to the IP2 Technical Specifications regarding the change of the term "ALLOWABLE VALUE" to "TRIP SETPOINT" and the proposed revision to the setpoint from "< 3 background" to be as specified in the ODCM do not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
6.0 PRECEDENCE The proposed change is consistent with the requirements approved at Wolf Creek (50-482), Ginna (50-244), Byron / Braidwood (50-454, 455, 456, and 457), Indian Point 3 (50-286), and Diablo Canyon (50-275).
7.0 REFERENCES
- 1. Indian Point letter NL-10-045, "2009 Annual Radioactive Effluent Release Report,"
dated April 29, 2010 transmitted Units 1, 2 and 3 Offsite Dose Calculation Manual (ODCM), Revision 2..
NL-12-002 Dockets 50-247 Attachment 1 Page 6 of 6
- 2. Indian Point 2 UFSAR, Chapter 14, Tables 14.2-2 (fuel handling accident), 14.2-4 (MSLB), 14.2-5 (VCT), 14.3-43 (LOCA)
ATTACHMENT 2 TO NL-12-002 MARKUP OF TECHNICAL SPECIFICATION PAGE FOR PROPOSED CHANGES REGARDING CONTAINMENT PURGE SYSTEM AND PRESSURE RELIEF LINE ISOLATION INSTRUMENTATION Changes indicated by lineout for deletion and Bold/Italics for additions Affected Pages:
Page 3.3.6 - 2 ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 DOCKET NOS. 50-247
Containment Purge System and Pressure Relief Line Isolation Instrumentation 3.3.6 Table 3.3.6-1 (page 1 of 1)
Containment Purge System and Pressure Relief Line Isolation Instrumentation SURVEILLANCE TRIP SETPOINT FUNCTION REQUIRED CHANNELS REQUIREMENTS ALLOWABLE VALUE
- 1. Automatic Actuation Logic and 2 trains SR 3.3.6.2 NA Actuation Relays SR 3.3.6.3 SR 3.3.6.5 2.a Gaseous Containment Radiation 1 SR 3.3.6.1 !- 3 x baGkgFetnd (a)
(R-42) SR 3.3.6.4 SR 3.3.6.6 2.b Particulate Containment 1 SR 3.3.6.1 5 3 x baekgFOU*d (a)
Radiation (R-41) SR 3.3.6.4 SR 3.3.6.6
- 3. Containment Isolation - Phase A Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 3.a., for all initiation functions and requirements.
- 4. Containment Spray Refer to LCO 3.3.2, "ESFAS Instrumentation," Function 2, for all initiation functions and requirements.
(a) As specified in the Offsite Dose CalculationManual (ODCM)
INDIAN POINT 2 3.3.6-4 Amendment No. 238