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Category:Inspection Report
MONTHYEARIR 05000003/20230032023-11-21021 November 2023 NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003 IR 05000003/20230022023-08-22022 August 2023 NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002 IR 05000003/20230012023-05-22022 May 2023 Unions 1, 2 and 3 - NRC Inspection Report Nos. 05000003/2023001, 05000247/2023001, 05000286/2023001, and 07200051/2023001 IR 05000003/20234012023-05-10010 May 2023 NRC Security Decommissioning Inspection Report Nos. 05000003/2023401, 05000247/2023401, and 05000286/2023401 IR 05000003/20220042023-03-13013 March 2023 NRC Inspection Report Nos. 05000003/2022004, 05000247/2022004, 05000286/2022004, and 07200051/2022002 IR 05000003/20220022022-11-17017 November 2022 NRC Inspection Report Nos. 05000003/2022002, 05000003/2022003, 05000247/2022002, 05000247/2022003, 05000286/2022002, 05000286/2022003, and 07200051/2022001 IR 05000003/20224022022-10-28028 October 2022 Reissued NRC Security Decommissioning Inspection Report Nos. 05000003/2022402, 05000247/2022402, and 05000286/2022402 (Letter Only) IR 05000003/20224012022-05-25025 May 2022 NRC Security Decommissioning Inspection Report Nos. 05000003/2022401, 05000247/2022401, and 05000286/2022401 IR 05000003/20220012022-05-25025 May 2022 NRC Inspection Report Nos. 05000003/2022001, 05000247/2022001, and 05000286/2022001 IR 05000003/20210042022-03-0404 March 2022 NRC Inspection Report Nos. 05000003/2021004, 05000247/2021004, 05000286/2021004, and 07200051/2021001 IR 05000003/20210032021-11-0909 November 2021 NRC Inspection Report Nos. 05000003/2021003, 05000247/2021003, and 05000286/2021003 IR 05000003/20210022021-08-0404 August 2021 NRC Inspection Report Nos. 05000003/2021002, 05000247/2021002, and 05000286/2021002 IR 05000286/20210022021-06-0707 June 2021 Integrated Inspection Report 05000286/2021002 IR 05000286/20214022021-05-0505 May 2021 Security Baseline Inspection Report 05000286/2021402 IR 05000003/20210012021-04-21021 April 2021 Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Units 1 and 2 - NRC Inspection Report No. 05000003/2021001 and 05000247/2020001 IR 05000286/20210012021-04-15015 April 2021 Integrated Inspection Report 05000286/2021001 IR 05000286/20200062021-03-0303 March 2021 Annual Assessment Letter for Indian Point Energy Center, Unit 3 (Report 05000286/2020006) IR 05000247/20200142021-02-0101 February 2021 Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Unit 2 NRC Inspection Report No. 05000247/2020014 IR 05000286/20200042021-01-28028 January 2021 Integrated Inspection Report 05000286/2020004 IR 05000003/20200012020-12-0808 December 2020 Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Units 1 and 2, NRC Inspection Report No. 05000003/2020001 and 05000247/2020013 IR 05000286/20200032020-10-28028 October 2020 Integrated Inspection Report 05000286/2020003 IR 05000286/20200102020-09-16016 September 2020 Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000286/2020010 IR 05000286/20200052020-08-31031 August 2020 Updated Inspection Plan for Indian Point Energy Center, Unit 3 (Inspection Report 05000286/2020005) IR 05000247/20200022020-08-10010 August 2020 Integrated Inspection Report 05000247/2020002 and 05000286/2020002 IR 05000286/20200122020-07-27027 July 2020 Design Basis Assurance Inspection (Programs) Inspection Report 05000286/2020012 IR 05000247/20020102020-05-12012 May 2020 Final ASP Analysis - Indian Point 2 (IR 050002472002010) IR 05000247/20200012020-04-29029 April 2020 Integrated Inspection Report 05000247/2020001 and 05000286/2020001 IR 05000247/20190062020-03-0303 March 2020 Annual Assessment Letter for Indian Point Energy Center, Units 2 and 3 (Report 05000247/2019006 and 05000286/2019006) IR 05000247/20190042020-02-10010 February 2020 Integrated Inspection Report 05000247/2019004 and 05000286/2019004 IR 05000003/20190012020-01-16016 January 2020 Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Unit 1 - NRC Inspection Report No. 05000003/2019001 IR 05000247/20190122020-01-0909 January 2020 Temporary Instruction 2515/194 Inspection Report 05000247/2019012 and 05000286/2019012 IR 05000247/20194112020-01-0909 January 2020 Material Control and Accounting Program Inspection Report 05000247/2019411 and 05000286/2019411 (Cover Letter Only) IR 05000247/20194032019-11-0505 November 2019 Cyber Security Inspection Report 05000247/2019403 and 05000286/2019403 (Cover Letter Only) IR 05000247/20190032019-11-0404 November 2019 Integrated Inspection Report 05000247/2019003 and 05000286/2019003 IR 05000247/20194102019-10-0202 October 2019 Security Inspection Report 05000247/2019410 and 05000286/2019410 (Cover Letter Only) IR 05000247/20190102019-09-26026 September 2019 Biennial Problem Identification and Resolution Inspection Report 05000247/2019010 and 05000286/2019010 IR 05000247/20190052019-08-28028 August 2019 Updated Inspection Plan (Inspection Report 05000247/2019005 and 05000286/2019005) IR 05000247/20190022019-08-13013 August 2019 Integrated Inspection Report 05000247/2019002 and 05000286/2019002 IR 05000247/20190112019-07-0909 July 2019 Design Basis Assurance Inspection (Programs) Inspection Report 05000247/2019011 and 05000286/2019011 IR 05000247/20190012019-05-13013 May 2019 Integrated Inspection Report 05000247/2019001 and 05000286/2019001 ML19130A0422019-05-0808 May 2019 Information Request for the Cyber-Security Inspection, Notification to Perform Inspection 05000247/2019403 and 05000286/2019403 IR 05000247/20193012019-04-18018 April 2019 Initial Operator Licensing Examination Report 05000247/2019301 IR 05000247/20180062019-03-0404 March 2019 Annual Assessment Letter for Indian Point Energy Center, Units 2 and 3 (Reports 05000247/2018006 and 05000286/2018006) IR 05000247/20180042019-02-0707 February 2019 Integrated Inspection Report 05000247/2018004 and 05000286/2018004 IR 05000247/20180102019-01-15015 January 2019 Design Bases Assurance Inspection (Teams) Report 05000247/2018010 and 05000286/2018010 IR 05000247/20180022019-01-0909 January 2019 Errata for Indian Point Nuclear Generating - Integrated Inspection Report 05000247/2018002 and 05000286/2018002 IR 05000247/20184102018-12-0606 December 2018 Security Inspection Report 05000247/2018410 and 05000286/2018410 (Cover Letter Only) IR 05000247/20182012018-11-27027 November 2018 NRC Inspection Report 05000247/2018201 and 05000286/2018201 IR 05000247/20180032018-11-0808 November 2018 Integrated Inspection Report 05000247/2018003 and 05000286/2018003 IR 05000003/20180012018-10-25025 October 2018 Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Station Unit 1 - NRC Inspection Report No. 05000003/2018001 Dated October 25, 2018 2023-08-22
[Table view] 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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Text
'" Entergy Entergy Nuclear Northeast Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan.
NY 10511-0249 T. R. Jones Licensing Manager Tel 914 734 6670 July 19, 2007 Re: Indian Point Unit 3 Docket No. 50-286 NL-07-083 Document Control Desk U. S. Nuclear Regulatory Commission Mail Stop O-Pl-17 Washington, DC 20555-0001
Subject:
Steam Generator Tube Inspection Report for Spring 2007 Refueling Outage
Reference:
- 1. NRC letter to Entergy dated August 18, 2004 regarding Evaluation of Steam Generator Tube Inspection Results for 2003. [ML042300253]
Dear Sir or Madam:
Entergy Nuclear Operations, Inc (Entergy) is providing in Attachment I the Steam Generator Tube Inspection Report required by Indian Point 3 Technical Specification 5.6.8. The subject inspection was performed from March 1 5 th through March 1 9 th, 2007 during the Spring 2007 Refueling Outage (3R14).The scope of the inspection included all four steam generators, which are Westinghouse Model 44F with thermally treated Alloy 690 tubes. At the time of the inspection, the steam generators had approximately 137 effective full power months of operation since the first inservice inspection performed in 1990. All four steam generators were found to be in compliance with condition monitoring requirements.
The previous inspection (Reference
- 1) was performed during the Spring 2003 Refueling Outage (3R12).There are no new commitments identified in this submittal.
If you have and questions or require additional information, please contact me at 914-734-6670.
Licensing Manager Indian Point Energy Center cc: next page AYo (
NL-07-083 Docket 50-286 Page 2 of 2 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 3 Mr. Paul Eddy, NYS Department of Public Service ATTACHMENT I TO NL-07-083 STEAM GENERATOR TUBE INSPECTION REPORT FOR INDIAN POINT 3 SPRING 2007 REFUELING OUTAGE (3R14)ENTERGY NUCLEAR OPERATIONS, INC INDIAN POINT NUCLEAR GENERATING UNIT 3 DOCKET 50-286 NL-07-083 Attachment I Docket 50-286 Page 1 of 7 Steam Generator Tube Inspection Report for Indian Point 3 Spring 2007 Refueling Outage (3R14)1.0 Examination Program Description At the time of the Spring 2007 refueling outage (3R14) at Indian Point 3, the steam generators (SGs) had accumulated approximateiy 137 effective full power months (EFPM) of operation since the first in-service inspection performed in 1990. The steam generators were replaced in 1989 and each have 3214 tubes made from thermally treated Alloy 690. The reactor coolant system operates with a hot leg temperature of 599 0 F. Refueling outage 3R14 was the refueling outage nearest the endpoint of the first inspection period of 144 EFPM as defined in section 5.5.8.d.2 of the Technical Specifications.
The steam generator inspections were performed from March 1 5 th through 1 9 th 2007.The following information is provided as required in section 5.6.8 of the Technical Specifications.
- a. The scope of inspections performed on each SG, b. Active degradation mechanisms found, c. Nondestructive examination techniques utilized for each degradation mechanism, d. Location, orientation (if linear), and measured sizes (if available) of service induced indications, e. Number of tubes plugged during the inspection outage for each active degradation mechanism, f. Total number and percentage of tubes plugged to date, g. The results of condition monitoring, including the results of tube pulls and in-situ testing, and h. The effective plugging percentage for all plugging in each SG.The tubesheet map and location landmarks are provided in Figure One and Figure Two, respectively.
2.0 Scope of Inspections Performed on each SG The following SG inspection scope was performed on all 4 SGs except as noted: 2.1 Bobbin inspection over the full length of 50% of the tubes in rows 3-45 (about 1515 tubes/SG) in a patterned inspection of every other pair of columns.2.1.1 In addition, those tubes not inspected since the first ISI in 1990 and not captured in this pattern were added to the inspection plan. This added 324 and 117 tubes in 33 and 34 SGs respectively.
2.2 Bobbin inspection of the hot and cold straight leg sections of 50% of the tubes in rows 1 and 2 aligning with the same columns as the patterned inspection for full length bobbin (about 92 tubes/SG).
2.2.1 In addition, those tubes in row one on both hot and cold legs not inspected in 2003 and not captured in this pattern were added to the inspection plan.
NL-07-083 Attachment I Docket 50-286 Page 2 of 7 2.3 Plus-point inspection of the U-bend sections of those row 1 and 2 tubes inspected in 2.2 above but not 2.2.1 (about 92 tubes/SG) plus any row 3 tubes that could not pass a nominal size bobbin probe. Plus-point probes were used in rows 1 and 2 because the tight radius of the bend does not permit quality data to be collected with the bobbin probe.2.3.1 In addition, those tubes whose row 1 and 2 U-bend sections were not inspected since the first ISI in 1990 were added to the inspection plan.This added 19 and 21 tubes to 31 and 32 SG respectively.
2.4 Plus-point inspection of the HOT leg expansion transitions from TTS+3 to TTS-3 inches of 20% of the tubes in a patterned inspection (about 643 tubes/SG) that captured tubes not previously inspected in prior patterns to the extent practical.
The purpose of this inspection was to collect baseline information of the tube expansion transition region for comparison should this region be considered for potential degradation mechanisms.
2.5 Plus-point inspection of the HOT leg expansion transitions from TTS+3 to TTS-3 inches of all HOT leg peripheral tubes (defined as 3 tubes in from the annulus in column, row and diagonal directions and all row 1 and 2 tubes) (about 550 tubes/SG not covered by 20% patterned inspection).
The purpose for this inspection was to identify possible loose parts and loose part wear in what are considered the most susceptible regions of the SG.2.6 Plus-point inspection of the COLD leg expansion transitions from TTS+3 to TTS-3 inches of all COLD leg peripheral tubes (defined as 3 tubes in from the annulus in column, row and diagonal directions and all row 1 and 2 tubes) (about 700 tubes/SG).
The purpose for this inspection was to identify possible loose parts and loose part wear in what are considered the most susceptible regions of the SG.2.7 Special interest inspections as necessary to disposition possible degradation signals from the routine inspections including all dents/dings
> 5 volts and a 20%sample of dents/dings 2.00 -4.99 volts in the HOT leg straight sections.I Summary of 3R14 SG Inspections (Number of Tests)Inspection 31 SG 32 SG 33 SG 34 SG Total Bobbin -Full length bobbin (rw 4)1518 1517 1841 1634 6510 (rows 3-45)Bobbin -Hot leg straight 107 107 134 108 456 section (rows 1 & 2)Bobbin -Cold leg straight 107 107 134 108 456 section (row 1 & 2)Plus Pt. -U-Bends (rows 1 111 113 91 90 405& 2)Plus Pt. -Hot leg TTS 1226 1216 1235 1248 4925 Plus Pt. -Cold leg TTS 699 694 697 696 2786 Plus Pt. -Special interest 45 4 1 28 78 NL-07-083 Attachment I Docket 50-286 Page 3 of 7 3.0 Active Degradation Mechanisms Found The only tube degradation mechanism found during the SG inspection in 3R14 was freespan wear in two tubes. The wear was due to contact with sludge lancing equipment used in 2001 that has not been used since. Although these tubes were inspected in 2003, the indications were not called at that time because they were at or below the threshold for detection based on the data at the time. The degradation was conservatively sized less than the repair limit and the tubes were left in service. Since the wear was the result of contact with maintenance equipment, the existing wear will not change in the future.4.0 Nondestructive Examination Techniques Utilized NDE Techniques used for Potential Degradation Mechanisms Detection Detection Sizing Sizing Degradation Probe ETSS Probe ETSS Wear at AVB supports, support Bobbin 96004.1 Bobbin 96004.1 plates & FDB Wear at tube support plates and Bobbin 96004.1 +Point 96910.1 flow distribution baffle plate Wear due to loose parts; Bobbin 96001.1 +Point 21998.1 volumetric indications
+Point 21998.1 Axial ODSCC in dents/ding
+Point 21409.1 +Point (1)(>5 volts) +PointI21409.1
_+Point I1)NDE Techniques used for Information Purposes Only Detection Detection Sizing Sizing Degradation Probe ETSS Probe ETSS Pitting Bobbin 96005.2 +Point 21998.1 U-bend axial ODSCC +Point 21409.1 +Point (1)U-bend circumferential ODSCC +Point 21410.1 +Point (2)Axial ODSCC at expansion
+Point 21409.1 +Point (1)transitions Circumferential ODSCC at +Point 21410.1 +Point (2)-expansion transitions Note (1) The Vp-p method from CEOG Task 1151 Note (2) EPRI TR-1 07197 Location, Orientation and Measured Sizes of Service Induced Indications SGID Row Col Orien Ind %TW Loc Inch Comment Wear due contact with 31 1 8 Axial VOL 26 TSC 16.34 sludge lance equipment in 2001 Wear due contact with 31 1 27 Axial VOL 29 TSC 16.16 sludge lance equipment in 1_ 1 2001 5.0 NL-07-083 Attachment I Docket 50-286 Page 4 of 7 6.0 Number of Tubes Plugged During 3R1 4 for each Active Degradation Mechanism No tubes were plugged for degradation during 3R14, however, two adjacent tubes in 31 SG were administratively plugged due to a metallic object wedged between the two tubes that could not be retrieved despite several attempts.
The object was detected during secondary side visual inspections and confirmed with eddy current. The tubes were evaluated for stabilization which was determined unnecessary given the location and extent of circumferential contact. The tube plugging list from 3R14 is below.Indication Degradation SG Tube Location Depth %TW Reason for Plugging 31 R29 C79 TSH +0.57 <Detectable Irretrievable Object 31 R29 C80 TSH +0.26 <Detectable Irretrievable Object Total Number and Percentage of Tubes Plugged to Date SG 31 SG 32 SG 33 SG 34 Total Total Number of Tubes 3214 3214 3214 3214 12856 Number of Plugged Tubes 3 6 3 4 16% of Tubes Plugged to Date 0.09% 0.19% 0.09% 0.12% 0.12%7.0 8.0 Results of Condition Monitoring The 3R14 refueling outage represented the end of the eighth fuel cycle after steam generator replacement and the end of the first inspection period following the first in-service inspection in 1990. Consequently, all four steam generators were inspected.
A Condition Monitoring assessment was performed, on a defect-specific basis, to demonstrate compliance with integrity criteria by the comparison of 3R14 NDE measurements with calculated burst and leakage integrity limits. Calculated integrity limits, including consideration for appropriate uncertainties, burst and leak analytical correlations, material properties, NDE technique, and analyst uncertainties were provided in the degradation assessment report. All indications in this inspection were below the calculated integrity limits and, therefore, met integrity requirements without further testing. Based upon the inspection results, all four steam generators were found to be in compliance with Condition Monitoring requirements.
All measured tube degradation was less than the condition monitoring limit. No in-situ pressure testing was required nor were any tubes pulled for examination.
NL-07-083 Attachment I Docket 50-286 Page 5 of 7 9.0 Effective Plugging Percentage for all Plugging in each SG SG 31 SG 32 SG 33 SG 34 Total Total Number of Tubes 3214 3214 3214 3214 12856 Number of Sleeved Tubes 0 0 0 0 0 Number of Plugged Tubes 3 6 3 4 16 Effective Tube Plugging % 0.09% 0.19% 0.09% 0.12% 0.12%Note: Since there are no sleeves installed and the safety analyses credit plugged tubes with the same value regardless of location, the effective tube plugging is equivalent to the percentage of tubes plugged.
NL-07-083 Attachment I Docket 50-286 Page 6 of 7 FIGURE ONE Indian Point 3 Steam Generator Tubesheet Map Coll No.4-10 -1 1--X 13- 1 -X 16--"1 18-'19-23 -I30- 1 11 1-325- 1X 34 2- 1IY 32-' 1 33- x II III I-N53-" 0, 37-'Z 6 38---11 4083 41c A0 4263 --64 65ilt-675 -51^^.
NL-07-083 Attachment I Docket 50-286 Page 7 of 7 FIGURE TWO Indian Point 3 Steam Generator Location Landmarks AV3 AV4 AV2 V5 AVI, 1 , AV6o 6H 6C 5H 5C 4H 4C 3H 3C 2H 2C 1H -C BPH BPC TSH TSC TEH TEC Westinghouse Model 44F Steam Generator Legend AV = Anti-Vibration Bar (AVB C = cold leg support plate (TSP)H = hot leg support plate (TSP)# = number of support structure BP = baffle plate (FDB)TS = tubesheet (Hot or Cold)TE = tube end (Hot or Cold