Letter Sequence Approval |
---|
|
|
MONTHYEARML0037622752000-10-23023 October 2000 Proposed Amendment Request for a One-Time Change in Appendix J, Type a, Integrated Leakage Rate Test Interval at Indian Point 3 003762275 Project stage: Other ML0109201762001-03-28028 March 2001 Safety Evaluation - One-Time Extension of Appendix J Type a Integrated Leakage Ratetest Interval at Indian Point 3 010920176 Project stage: Approval 2000-10-23
[Table View] |
|
---|
Category:Report
MONTHYEARML22013A7062022-01-13013 January 2022 Investigation Report of LLRW Shipment Pursuant to 10 CFR 20, Appendix G ML21056A0782021-04-0707 April 2021 Final Environmental Assessment and Finding of No Significant Impact for Initial and Updated Decommissioning Funding Plans for Indian Point ISFSI (Docket: 72-51) 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 ML20259A2172020-09-14014 September 2020 Commitment Change Summary Report ML20260H0722020-06-18018 June 2020 IP-RPT-14-00013, Revision 3, Indian Point Nuclear Generating Units 2 and 3, Consequences of a Postulated Fire and Explosion Following the Release of Natural Gas from the New Aim 42 Pipeline Near Ipec ML20122A1052020-05-27027 May 2020 Letter from Margaret M. Doane to John B. Rhodes, Chair and Executive Officer, Ny State Public Service Commission: Response to Ny State Public Service Commission Regarding Natural Gas Transmission Pipelines Near Indian Point Nuclear Power Pl ML20100F6352020-04-0808 April 2020 Expert Team Final Report 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) ML19252A3182019-09-0909 September 2019 Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of Sept 2, 2019 NL-19-061, Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2019-06-13013 June 2019 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements ML19114A0742019-04-22022 April 2019 Entergy to NRC, IPEC Weekly Sturgeon Monitoring Report for Week of April 15, 2019 NL-19-012, Request for Approval of a Certified Fuel Handler Training and Retraining Program2019-04-15015 April 2019 Request for Approval of a Certified Fuel Handler Training and Retraining Program ML18098A0882018-04-0606 April 2018 Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-18-021, Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability2018-04-0606 April 2018 Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-20-066, Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center2017-12-19019 December 2017 Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center ML17349A1562017-12-0808 December 2017 Risk Impact of One-Time Extending the ILRT Interval Associated with the Proposed Technical Specification Changes ML17279A2472017-10-0606 October 2017 2017 Annual Assessment Meeting Written Comments Compilation ML17222A2392017-10-0404 October 2017 NRC Response to Request for Deferral of Actions Related to Beyond-Design-Basis Seismic and Flooding Hazard Reevaluations ML17289A6552017-10-0202 October 2017 Attachment 6 to NL-17-115, Revised HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Energy Center, Revision 9 NL-17-122, Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,20172017-09-28028 September 2017 Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,2017 ML17096A2122017-03-23023 March 2017 Entergy Engineering Report No. IP-RPT-16-00078, Indian Point RAI CLI-16-07 SAMA Cost-Benefit Sensitivities Rev. 1 (March 23, 2017) NL-17-020, License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan2017-02-0606 February 2017 License Renewal Application - Revisions to Reactor Vessel Internals Aging Management Program and Inspection Plan ML17096A2112017-01-0404 January 2017 Entergy Engineering Report No. IP-RPT-16-00077, Indian Point RAI CLI-16-07 MACCS2 Sensitivities, Rev. 0 (Jan 4, 2017) ML16280A2282016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual NL-16-109, Indian Point 2 Technical Requirements Manual2016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual NL-16-109, HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center.2016-09-19019 September 2016 HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center. ML16250A2762016-09-13013 September 2016 Evaluation of Impacts to Proposed Critical Habitat for the Atlantic Sturgeon for Indian Point Nuclear Generating Units 2 and 3 Proposed License Renewal NL-16-083, Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 32016-08-0101 August 2016 Post Accident Monitoring (PAM) Report for an Inoperable Containment Area Radiation Monitor (R-26) High Range, Indian Point Unit Number 3 ML18115A0592016-06-28028 June 2016 After Action Report/Improvement Plan, Drill Date June 28, 2016 ML17052A2662015-10-0202 October 2015 Sturgeon Mobile Tracking for the New Ny Bridge at Tappan Zee NL-15-128, Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update2015-09-28028 September 2015 Submittal of 10 CFR 50.59(d)(2) Summary Report of Changes, Tests and Experiments Implemented Between 04/01/2013 and 03/25/2015, And/Or Utilized in Support of the UFSAR Update 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 NL-15-099, Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report2015-07-30030 July 2015 Submittal of 2014 Annual 10 CFR 50.46 Emergency Core Cooling System Evaluation Changes Report NL-15-072, 2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2015-06-18018 June 2015 2015 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements NL-15-030, Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project2015-04-0808 April 2015 Revised 10 C.F.R. 50.59 Safety Evaluation and Supporting Analyses Prepared in Response to the Algonquin Incremental Market Natural Gas Project NL-15-029, Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 20152015-04-0606 April 2015 Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 2015 ML15062A2002015-02-19019 February 2015 NET-300067-01, Revision 1, Criticality Safety Analysis of the Indian Point, Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels. (Non-Proprietary) NL-15-013, Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval2015-01-28028 January 2015 Re-Submittal of Netco Report NET-300067-01, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels, for NRC Review and Approval ML15061A2772014-12-31031 December 2014 WCAP-17954-NP, Revision 0, Indian Point Unit 3 Heatup and Cooldown Limit Curves for Normal Operation. NL-14-152, Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From...2014-12-22022 December 2014 Entergy'S Expedited Seismic Evaluation Process Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From... ML14329A1952014-11-0404 November 2014 NET-300067-01, Rev. 0, Criticality Safety Analysis of the Indian Point Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels NL-14-115, 10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 20142014-09-18018 September 2014 10 CFR 50.59(d)(2) Summary Report for Indian Point, Units 1 and 2 April 1, 2012 to March 19, 2014 ML14304A7012014-09-16016 September 2014 Reliability Needs Assessment ML15166A0702014-08-31031 August 2014 Algonquin Incremental Market (Aim) Project, Phase 2 Acoustic Survey for Indiana Bats (Myotis Sodalis) and Northern Long-Eared Bats (Myotis Septentrionalis), August 2014 NL-14-110, Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2014-08-27027 August 2014 Third Six-Month Status Report for the Implementation of Order EA-12-049 Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 ML14168A0592014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 5 ML14168A0602014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 ML14168A0612014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 2022-01-13
[Table view] Category:Technical
MONTHYEARNL-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 ML20259A2172020-09-14014 September 2020 Commitment Change Summary Report ML20100F6352020-04-0808 April 2020 Expert Team Final Report ML18098A0882018-04-0606 April 2018 Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-18-021, Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability2018-04-0606 April 2018 Indian Point, Unit 2, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-20-066, Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center2017-12-19019 December 2017 Engineering Report IP-RPT-11-00032, Revision 5, Licensing Report on the Inter-Unit Transfer of Spent Nuclear Fuel at the Indian Point Energy Center ML17349A1562017-12-0808 December 2017 Risk Impact of One-Time Extending the ILRT Interval Associated with the Proposed Technical Specification Changes ML17289A6552017-10-0202 October 2017 Attachment 6 to NL-17-115, Revised HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Energy Center, Revision 9 NL-17-122, Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,20172017-09-28028 September 2017 Transmittal of 10 CFR 50.59(d)(2) Summary Report, March 26, 2015 to May 18,2017 ML17096A2122017-03-23023 March 2017 Entergy Engineering Report No. IP-RPT-16-00078, Indian Point RAI CLI-16-07 SAMA Cost-Benefit Sensitivities Rev. 1 (March 23, 2017) ML17096A2112017-01-0404 January 2017 Entergy Engineering Report No. IP-RPT-16-00077, Indian Point RAI CLI-16-07 MACCS2 Sensitivities, Rev. 0 (Jan 4, 2017) NL-16-109, Indian Point 2 Technical Requirements Manual2016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual ML16280A2282016-09-19019 September 2016 Indian Point 2 Technical Requirements Manual NL-16-109, HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center.2016-09-19019 September 2016 HI-2094289, Licensing Report on the Inter-Unit Transfer of Spent Fuel at the Indian Point Energy Center. ML16250A2762016-09-13013 September 2016 Evaluation of Impacts to Proposed Critical Habitat for the Atlantic Sturgeon for Indian Point Nuclear Generating Units 2 and 3 Proposed License Renewal ML17052A2662015-10-0202 October 2015 Sturgeon Mobile Tracking for the New Ny Bridge at Tappan Zee NL-15-029, Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 20152015-04-0606 April 2015 Summary of Analysis Results Based on Corrected Format 2 Data Files Dated March 2015 ML15062A2002015-02-19019 February 2015 NET-300067-01, Revision 1, Criticality Safety Analysis of the Indian Point, Unit 2 Spent Fuel Pool with Credit for Inserted Neutron Absorber Panels. (Non-Proprietary) ML15061A2772014-12-31031 December 2014 WCAP-17954-NP, Revision 0, Indian Point Unit 3 Heatup and Cooldown Limit Curves for Normal Operation. ML14304A7012014-09-16016 September 2014 Reliability Needs Assessment NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 5 NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 4 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 4 of 5 NL-14-071, Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 52014-06-0505 June 2014 Indian Point, Unit 2 - Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 ML14168A0592014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 1 of 5 ML14168A0602014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 2 of 5 ML14168A0632014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 5 of 5 NL-14-071, Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 4 of 52014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 4 of 5 ML14168A0612014-06-0505 June 2014 Seismic Walkdown Report Update, Enclosure to NL-14-071 - Engineering Report No. IP-RPT-12-00037, Rev 1. Part 3 of 5 ML14107A0432014-03-31031 March 2014 Enclosure 2 to NL-14-045 - Acceptable Value of the Location of the Bottom of the Expansion Transition (Bet) for Implementation of H* at Indian Point Unit 2 ML13337A5942014-01-24024 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14027A5152014-01-16016 January 2014 WCAP-17828-NP, Revision 0, Indian Point Unit 2 H* Alternate Repair Criteria for the Tubesheet Hydraulic Expansion Region (Model 44F - 4-Loop) ML14010A3312014-01-14014 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Indian Point Energy Center, Units 2 and 3, TAC Nos.: MF0744 and MF0745 NL-14-027, LTR-PAFM-13-115-NP, Rev. 0, Technical Justification to Support Extended Volumetric Examination Interval for Indian Point Generating Station Unit 3 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds.2013-11-30030 November 2013 LTR-PAFM-13-115-NP, Rev. 0, Technical Justification to Support Extended Volumetric Examination Interval for Indian Point Generating Station Unit 3 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds. NL-13-089, Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 1 of 62013-05-24024 May 2013 Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 1 of 6 NL-13-089, Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 5 of 62013-05-24024 May 2013 Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 5 of 6 NL-13-089, Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 4 of 62013-05-24024 May 2013 Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 4 of 6 NL-13-089, Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 3 of 62013-05-24024 May 2013 Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 3 of 6 NL-13-089, Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 6 of 62013-05-24024 May 2013 Indian Point, Unit 3, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 6 of 6 ML13176A0082013-05-24024 May 2013 Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 4 of 6 NL-13-089, Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 2 of 62013-05-24024 May 2013 Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 2 of 6 ML13176A0122013-05-24024 May 2013 Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 1 of 6 ML13176A0102013-05-24024 May 2013 Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 6 of 6 ML13176A0092013-05-24024 May 2013 Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 5 of 6 ML13176A0072013-05-24024 May 2013 Enclosure to NL-13-089, Seismic Walkdown Report Update, Part 3 of 6 ML17052A3142013-03-29029 March 2013 Analysis of Potential Sedimentation Effects of Proposed Cylindrical Wedgewire Screens for Intake of Cooling Water at Indian Point Energy Center ML13072A0832013-01-31031 January 2013 12-4116.IPEC.V002, Revision 1, Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation: EA-12-051 ML12353A4662012-11-20020 November 2012 Indian Point Energy Center - Engineering Report No. IP-RPT-12-00039, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 1 of 4 NL-12-168, Indian Point Energy Center - Engineering Report No. IP-RPT-12-00039, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 2 of 42012-11-20020 November 2012 Indian Point Energy Center - Engineering Report No. IP-RPT-12-00039, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 2 of 4 NL-12-168, Indian Point Energy Center - Engineering Report No. IP-RPT-12-00039, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 1 of 42012-11-20020 November 2012 Indian Point Energy Center - Engineering Report No. IP-RPT-12-00039, Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Part 1 of 4 2021-02-10
[Table view] |
Text
March 28, 2001 MEMORANDUM TO: Marsha K. Gamberoni, Chief Section 1 Project Directorate I Division of Licensing Project Management FROM: George T. Hubbard, Chief /RA/
Balance of Plant and Containment Systems Section Plant Systems Branch Division of Systems Safety and Analysis Mark P. Rubin, Chief Safety Program Section Probabilistic Safety Assessment Branch Division of Systems Safety and Analysis
SUBJECT:
SAFETY EVALUATION - ONE-TIME EXTENSION OF APPENDIX J TYPE A INTEGRATED LEAKAGE RATE TEST INTERVAL AT INDIAN POINT 3 (TAC NO. MB0178)
The Plant Systems Branch and the Probabilistic Safety Assessment Branch have completed their review and evaluation of the licensee's letters dated September 6, 2000, and January 18, 2001, proposing a one-time Technical Specification change to extend the test interval for their Appendix J Type A test from the required 10 years to a test interval of 15 years, at the Indian Point Nuclear Power Plant, Unit 3.
Based on our review, we find the licensee's proposal to be acceptable. Our evaluation is attached.
We consider our efforts on TAC No. MB0178 to be complete.
Docket No.: 50-286
Attachment:
As stated CONTACT: J. Pulsipher, SPLB/DSSA 301-415-2811 M. Snodderly, SPSB/DSSA 301-415-2047
March 28, 2001 MEMORANDUM TO: Marsha K. Gamberoni, Chief Section 1 Project Directorate I Division of Licensing Project Management FROM: George T. Hubbard, Chief /RA/
Balance of Plant and Containment Systems Section Plant Systems Branch Division of Systems Safety and Analysis Mark P. Rubin, Chief Safety Program Section Probabilistic Safety Assessment Branch Division of Systems Safety and Analysis
SUBJECT:
SAFETY EVALUATION - ONE-TIME EXTENSION OF APPENDIX J TYPE A INTEGRATED LEAKAGE RATE TEST INTERVAL AT INDIAN POINT 3 (TAC NO. MB0178)
The Plant Systems Branch and the Probabilistic Safety Assessment Branch have completed their review and evaluation of the licensee's letters dated September 6, 2000, and January 18, 2001, proposing a one-time Technical Specification change to extend the test interval for their Appendix J Type A test from the required 10 years to a test interval of 15 years, at the Indian Point Nuclear Power Plant, Unit 3.
Based on our review, we find the licensee's proposal to be acceptable. Our evaluation is attached.
We consider our efforts on TAC No. MB0178 to be complete.
Docket No.: 50-286
Attachment:
As stated CONTACT: J. Pulsipher, SPLB/DSSA 301-415-2811 M. Snodderly, SPSB/DSSA 301-415-2047 DISTRIBUTION: ADAMS SPLB r/f GWunder MGamberoni JHannon JPulsipher GHubbard RLobel MSnodderly MThadani MRubin RBarrett DOCUMENT NAME: IP3TypeA15yrs4rev2.wpd OFFICE SPLB:DSSA:NRR SPSB:DSSA:NRR SC:SPSB:DSSA SC:SPLB:DSSA NAME JPulsipher:bw MSnodderly MRubin GHubbard DATE 3/07/01 3/07/01 3/28/01 3/07/01 / /01 OFFICIAL RECORD COPY
ATTACHMENT SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION PLANT SYSTEMS BRANCH AND PROBABILISTIC SAFETY ASSESSMENT BRANCH ONE-TIME EXTENSION OF APPENDIX J TYPE A INTEGRATED LEAKAGE RATE TEST INTERVAL INDIAN POINT NUCLEAR POWER PLANT, UNIT 3 DOCKET NO. 50-286
1.0 INTRODUCTION
By letters dated September 6, 2000, and January 18, 2001, the New York Power Authority, the licensee for the Indian Point, Unit 3, nuclear power plant, requested a Technical Specification change that would allow a one-time change in their Appendix J Type A test interval from the required 10 years to a test interval of 15 years. Without an extension, the licensee would have to perform a Type A test during their next refueling outage, scheduled to begin in Spring 2001.
2.0 BACKGROUND
10 CFR Part 50, Appendix J, Option B requires that a Type A test (containment integrated leakage rate test) be conducted at a periodic interval based on historical performance of the overall containment system. Indian Point 3 Technical Specification 6.14 requires that a program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.
It further requires that this program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, Performance-Based Containment Leak-Test Program, dated September 1995. This regulatory guide references NEI 94-01, Revision 0, Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J, dated July 26, 1995.
A Type A test is an overall (integrated) leakage rate test of the containment structure.
NEI 94-01 specifies an initial test interval of 48 months, but allows an extended interval of 10 years, based upon two consecutive successful tests. There is also a provision for extending the test interval an additional 15 months under certain circumstances.
The most recent two Type A tests at Indian Point 3 have been successful, so their current interval requirement is 10 years.
The licensee is requesting an addition to Technical Specification 6.14, which would indicate that they are allowed to take an exception to the guidelines of Regulatory Guide 1.163 regarding the Type A test interval. Specifically, the proposed Technical Specification says that the first Type A test performed after the December 2, 1990, Type A test shall be performed no later than December 1, 2005. This would make the interval 15 years since the last test.
2 The licensee states that they expect a rule change to be sought that could eliminate altogether the need for Type A testing, and that the requested extension would allow time for this rule change to be processed. Although the staff has not received a petition for rulemaking, we have initiated preliminary discussions with the industry concerning possible generic changes to the rule, Regulatory Guide 1.163, or NEI 94-01 to permanently extend the test interval or perhaps completely eliminate the test requirement.
3.0 EVALUATION The licensee has performed a risk impact assessment of extending the Type A test interval to 15 years. The assessment was provided to the staff in a January, 18, 2001, letter from the licensee (ADAMS Accession No. ML010300222). In performing the risk assessment, they followed the guidelines of NEI 94-01, the methodology used in EPRI TR-104285, Risk Impact Assessment of Revised Containment Leak Rate Testing, and the guidelines of Regulatory Guide 1.174, An Approach For Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis.
The basis for the current 10-year test interval is provided in Section 11.0 of NEI 94-01, Revision 0, and was established in 1995 during development of the performance-based Option B to Appendix J. Section 11.0 of NEI 94-01 states that NUREG-1493, Performance-Based Containment Leak-Test Program, September 1995, provides the technical basis to support rulemaking to revise leakage rate testing requirements contained in Option B to Appendix J. The basis consisted of qualitative and quantitative assessments of the risk impact (in terms of increased public dose) associated with a range of extended leakage rate test intervals. To supplement the NRCs rulemaking basis, NEI undertook a similar study. The results of that study are documented in EPRI Research Project Report TR-104285.
The EPRI study used an analytical approach similar to that presented in NUREG-1493 for evaluating the incremental risk associated with increasing the interval for Type A tests. The EPRI study estimated that relaxing the test interval from 3 in 10 years to 1 in 10 years, will increase the average time that a leak detectable only by a Type A test goes undetected from 18 to 60 months. Since Type A tests only detect about 3 percent of leaks (the rest are identified during local leak rate tests based on industry leakage rate data gathered from 1987 to 1993), this results in a 10% increase in the overall probability of leakage. The risk contribution of leakage, in percent of person-rem/year, for the PWR representative plant was estimated to increase from .032 percent to .035 percent. This confirmed the NUREG-1493 conclusion that a reduction in the frequency of Type A tests from 3 per 10 years to 1 per 10 years leads to an imperceptible increase in risk.
Building upon the methodology of the EPRI study, the licensee assessed the change in the predicted person-rem/year frequency. The staff considers the licensees assessment an improvement of the EPRI study because the leakage from sequences that have the potential to result in large releases if a pre-existing leak were present were quantified. Since the Option B rulemaking in 1995, the staff has issued RG 1.174 on the use of probabilistic risk assessment (PRA) in risk-informed changes to a plants licensing basis. The licensee has proposed using RG 1.174 to assess the acceptability of extending the Type A test interval beyond that established during the Option B rulemaking. RG 1.174 defines very small changes in the risk-acceptance guidelines as increases in core damage frequency (CDF) less than 10-6 per reactor year and increases in large early release frequency (LERF) less than 10-7 per reactor year.
3 Since the Type A test does not impact CDF the relevant criterion is the change in LERF which the licensee estimated. RG 1.174 also discusses defense-in-depth and encourages the use of risk analysis techniques to help ensure and show that key principles, such as the defense-in-depth philosophy, are met. The licensee estimated the increase in the conditional containment failure probability which helps to ensure that the defense-in-depth philosophy is maintained.
The licensee examined plant specific accident sequences from their Individual Plant Examination. The following sequences were considered in the assessment:
ÿ Core damage sequences in which the containment remains intact initially and in the long term.
ÿ Core damage sequences in which containment integrity is impaired due to random isolation failures of plant components other than those associated with Type B or Type C test components. For example, liner breach, or steam generator manway leakage.
ÿ Core damage sequences in which containment integrity is impaired due to containment isolation failures of pathways left 'opened' following a plant post-maintenance test. For example, valve failing to close following a valve stroke test.
ÿ Accident sequences involving containment failure induced by severe accident phenomena, containment bypassed, large containment isolation failures, and small containment isolation 'failure-to-seal' events were not accounted for in this evaluation.
These sequences are impacted by changes in Type B and C test intervals, not changes in the Type A test interval.
The steps taken by the licensee to perform the risk assessment are as follows:
ÿ Quantified the base-lined risk in terms of frequency per reactor year for each of the eight accident classes evaluated in EPRI TR-104285.
ÿ Developed plant specific person-rem dose (population dose) per reactor year for each of the eight accident classes.
ÿ Evaluated the risk impact of extending the Type A test interval from 10 to 15 years.
ÿ Determined the change in risk in terms of LERF in accordance with RG 1.174.
Determining the change in risk in terms of LERF involves the potential that a core damage event that normally would result in only a small radioactive release from containment could in fact result in a large release due to failure to detect a pre-existing leak during the extension period. The licensee designated these sequences as Class 3B sequences and estimated a frequency of 1.02 x 10-6/year, based on a 10 year test interval. The licensee then used the EPRI methodology to estimate the impact of the Type A test interval on the leakage probability.
Extending the Type A test interval from 10 to 15 years increases the average time that a leak detectable only by a Type A test goes undetected from 60 to 90 months. For a 15-year interval there is a 15% increase in the overall probability of leakage (3
- 90/18) versus 10% for a 10-year interval. Thus, increasing the Type A test interval from 10 years to 15 years results in a 5%
increase in the overall probability of leakage. Multiplying the above LERF frequency (1.02 x
4 10-6/year) by the increase in overall probability of leakage (0.05) gives an increase in LERF of 5.1 x10-8/year. If the risk increase is measured from the original 3 in 10 year interval, the increase in LERF is 1.1 x 10-7/year.
The following conclusions can be drawn from the licensees risk assessment associated with extending the Type A test frequency:
- 1. The risk assessment predicted a slight increase in risk when compared to that estimated from current requirements. Given the change from a 10-year test interval to a 15-year test interval, the increase in the total integrated plant risk (person-rem/year within 50 miles) was found to be 0.048 percent. The increase in the total integrated plant risk, given the change from a 3 in 10-year test interval to a 15-year test interval, was found to be 0.43 percent. This is just slightly greater than the range of risk increase, 0.02 to 0.14 percent, estimated in NUREG-1493 when going from a 3 in 10-year test interval to a 10-year interval. NUREG-1493 concluded that a reduction in the frequency of tests from 3 per 10 years to 1 per 10 years leads to an imperceptible increase in risk. Therefore, the increase in the total integrated plant risk for the proposed change is considered small.
- 2. RG 1.174 provides guidance for determining the risk impact of plant-specific changes to the licensing basis. RG 1.174 defines very small changes in the risk-acceptance guidelines as increases in CDF less than 10-6 per reactor year and increases in LERF less than 10-7 per reactor year. Since the Type A test does not impact CDF, the relevant criterion is LERF. The increase in LERF resulting from a change in the Type A test interval from 1 in 10 years to 1 in 15 years is estimated to be 5.1 x 10-8/year. The increase in LERF resulting from a change in the Type A test interval from the original 3 in 10 years to 1 in 15 years is estimated to be 1.1 x 10-7/year. Increasing the Type A interval to 15 years is considered to be a very small change in LERF.
- 3. RG 1.174 also encourages the use of risk analysis techniques to help ensure and show that the proposed change is consistent with the defense-in-depth philosophy.
Consistency with the defense-in-depth philosophy is maintained if a reasonable balance is preserved among prevention of core damage, prevention of containment failure, and consequence mitigation. The change in the conditional containment failure probability was estimated to be 0.1 percent for the proposed change and 0.4 percent for the cumulative change of going from a test interval of 3 in 10 years to 1 in 15 years. The staff finds that the defense-in-depth philosophy is maintained based on the change in the conditional containment failure probability for the proposed change.
Based on these conclusions, the staff finds that the increase in predicted risk due to the proposed change is within the acceptance criteria while maintaining the defense-in-depth philosophy of RG 1.174 and, therefore, is acceptable.
5
4.0 CONCLUSION
Based on the foregoing evaluation, the staff finds that the interval until the next Type A test at Indian Point 3 may be extended to 15 years, and that the proposed changes to Technical Specification 6.14 are acceptable.