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| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Vice President, Operations Entergy Nuclear Operations, Inc. Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 April 28, 2015 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 28, 2015 Vice President, Operations Entergy Nuclear Operations, Inc. |
| | Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 -REVIEW OF THE SPRING 2014 STEAM GENERATOR TUBE INSPECTIONS DURING REFUELING OUTAGE 21 (TAC NO. MF4866) | | INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 - REVIEW OF THE SPRING 2014 STEAM GENERATOR TUBE INSPECTIONS DURING REFUELING OUTAGE 21 (TAC NO. MF4866) |
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| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
| By letter dated September 8, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14262A059), Entergy Nuclear Operations, Inc. (the licensee), submitted information summarizing the results of the spring 2014 steam generator (SG) tube inspections performed at Indian Point Nuclear Generating Unit No. 2. These inspections were performed during refueling outage 21. The licensee submitted additional information regarding the spring 2014 SG tube inspections by letter dated January 15, 2015 (ADAMS Accession No. ML15029A298). | | |
| The U.S. Nuclear Regulatory Commission staff has completed its review of these reports and has concluded that the licensee provided the information required by Indian Point Nuclear Generating Unit No. 2 Technical Specifications and that no additional followup is required. | | By letter dated September 8, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14262A059), Entergy Nuclear Operations, Inc. (the licensee), |
| The staff assessment of the report is enclosed. | | submitted information summarizing the results of the spring 2014 steam generator (SG) tube inspections performed at Indian Point Nuclear Generating Unit No. 2. These inspections were performed during refueling outage 21. The licensee submitted additional information regarding the spring 2014 SG tube inspections by letter dated January 15, 2015 (ADAMS Accession No. ML15029A298). |
| Docket No. 50-247 | | The U.S. Nuclear Regulatory Commission staff has completed its review of these reports and has concluded that the licensee provided the information required by Indian Point Nuclear Generating Unit No. 2 Technical Specifications and that no additional followup is required. The staff assessment of the report is enclosed. |
| | Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-247 |
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| ==Enclosure:== | | ==Enclosure:== |
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| Staff Assessment cc w/enclosure: | | Staff Assessment cc w/enclosure: Distribution via Listserv |
| Distribution via Listserv Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REVIEW OF THE SPRING 2014 STEAM GENERATOR TUBE INSPECTION REPORT ENTERGY NUCLEAR OPERATIONS. | |
| INC. DOCKET NO. 50-247 INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 By letter dated September 8, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14262A059), Entergy Nuclear Operations, Inc. (the licensee), submitted information summarizing the results of the spring 2014 steam generator (SG) tube inspections performed at Indian Point Nuclear Generating Unit No. 2 (IP2). These inspections were performed during refueling outage (RFO) 21. The licensee submitted additional information regarding the spring 2014 SG tube inspections by letter dated January 15, 2015 (ADAMS Accession No. ML15029A298).
| |
| The IP2 replacement SGs, which were installed during RFO 14 in 2000, are Westinghouse model 44F SGs. All four SGs were inspected during RFO 19. Each SG contains approximately 3,214 thermally treated Alloy 600 tubes, which have a nominal outside diameter of 0.875 inches and a nominal wall thickness of 0.050 inches. The tubes are supported by stainless steel tube support plates with quatrefoil-shaped holes and V-shaped anti-vibration bars (AVBs). The licensee provided the scope, extent, methods, and results of the IP2 SG tube inspections in the documents referenced above. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings.
| |
| The U.S. Nuclear Regulatory Commission (NRC) staff has the following notes/observations:
| |
| * An AVB position verification study was performed.
| |
| The purpose was to determine if the AVBs had experienced any inservice movement and to determine whether the AVBs were in their correct positions per the design specifications.
| |
| The findings of this study showed that the insertion depths had not changed since the baseline examination.
| |
| The findings of this study have been entered into the licensee's corrective action program. Based on a review of the information provided, the NRC staff concluded that the licensee provided the information required by its technical specifications.
| |
| In addition, the staff concluded that there are no technical issues that warrant followup action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation, and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units. Enclosure Vice President, Operations Entergy Nuclear Operations, Inc. Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 April 28, 2015
| |
| | |
| ==SUBJECT:==
| |
| INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 -REVIEW OF THE SPRING 2014 STEAM GENERATOR TUBE INSPECTIONS DURING REFUELING OUTAGE 21 (TAC NO. MF4866)
| |
| | |
| ==Dear Sir or Madam:==
| |
| By letter dated September 8, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14262A059), Entergy Nuclear Operations, Inc. (the licensee), submitted information summarizing the results of the spring 2014 steam generator (SG) tube inspections performed at Indian Point Nuclear Generating Unit No. 2. These inspections were performed during refueling outage 21. The licensee submitted additional information regarding the spring 2014 SG tube inspections by letter dated January 15, 2015 (ADAMS Accession No. ML15029A298).
| |
| The U.S. Nuclear Regulatory Commission staff has completed its review of these reports and has concluded that the licensee provided the information required by Indian Point Nuclear Generating Unit No. 2 Technical Specifications and that no additional followup is required.
| |
| The staff assessment of the report is enclosed.
| |
| Docket No. 50-247
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|
| |
|
| ==Enclosure:==
| | REVIEW OF THE SPRING 2014 STEAM GENERATOR TUBE INSPECTION REPORT ENTERGY NUCLEAR OPERATIONS. INC. |
| | DOCKET NO. 50-247 INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 By letter dated September 8, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14262A059), Entergy Nuclear Operations, Inc. (the licensee), |
| | submitted information summarizing the results of the spring 2014 steam generator (SG) tube inspections performed at Indian Point Nuclear Generating Unit No. 2 (IP2). These inspections were performed during refueling outage (RFO) 21. The licensee submitted additional information regarding the spring 2014 SG tube inspections by letter dated January 15, 2015 (ADAMS Accession No. ML15029A298). |
| | The IP2 replacement SGs, which were installed during RFO 14 in 2000, are Westinghouse model 44F SGs. All four SGs were inspected during RFO 19. Each SG contains approximately 3,214 thermally treated Alloy 600 tubes, which have a nominal outside diameter of 0.875 inches and a nominal wall thickness of 0.050 inches. The tubes are supported by stainless steel tube support plates with quatrefoil-shaped holes and V-shaped anti-vibration bars (AVBs). |
| | The licensee provided the scope, extent, methods, and results of the IP2 SG tube inspections in the documents referenced above. In addition, the licensee described corrective actions (i.e., |
| | tube plugging) taken in response to the inspection findings. The U.S. Nuclear Regulatory Commission (NRC) staff has the following notes/observations: |
| | * An AVB position verification study was performed. The purpose was to determine if the AVBs had experienced any inservice movement and to determine whether the AVBs were in their correct positions per the design specifications. The findings of this study showed that the insertion depths had not changed since the baseline examination. The findings of this study have been entered into the licensee's corrective action program. |
| | Based on a review of the information provided, the NRC staff concluded that the licensee provided the information required by its technical specifications. In addition, the staff concluded that there are no technical issues that warrant followup action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation, and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units. |
| | Enclosure |
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|
| Staff Assessment Sincerely, IRA/ Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc w/enclosure:
| | ML15106A012 OFFICE LPL 1-1/PM LPL 1-1/PM LPL2-2/LAiT LPL2-2/LA ESGB/BC LPL 1-1/BC(A) |
| Distribution via Listserv DISTRIBUTION:
| | NAME AGilbertson DPickett LRonewicz BClayton GKulesa by MDudek memo dated DATE 4/21/2015 4/24/2015 4/17/2015 4/17/2015 4/09/2015 4/28/2015}} |
| PUBLIC LPL 1-1 R/F RidsNrrDorl RidsNrrDorlLpl 1-1 RidsNrrLAKGoldstein KKarwoski, DE RidsNrrDorlDpr RidsNrrDeEsgb RidsRgn1 MailCenter RidsNrrPMlndianPoint RidsACRS_MailCTR AJohnson, ESGB ADAMS Accession No.: ML15106A012 OFFICE LPL 1-1/PM LPL 1-1/PM LPL2-2/LAiT LPL2-2/LA NAME AGilbertson DPickett LRonewicz BClayton DATE 4/21/2015 4/24/2015 4/17/2015 4/17/2015 OFFICIAL RECORD COPY ESGB/BC LPL 1-1/BC(A)
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| GKulesa by MDudek memo dated 4/09/2015 4/28/2015}}
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Category:Letter
MONTHYEARIR 05000003/20240022024-08-0606 August 2024 NRC Inspection Report 05000003/2024002, 05000247/2024002, 05000286/2024002 ML24171A0122024-06-18018 June 2024 Reply to a Notice of Violation EA-24-037 ML24156A1162024-06-0404 June 2024 Correction - Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities IR 05000003/20240052024-05-21021 May 2024 and 3 - NRC Inspection Report Nos. 05000003/2024005, 05000247/2024005, 05000286/2024005, 07200051/2024001, and Notice of Violation ML24128A0632024-05-0707 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report L-24-009, HDI Annual Occupational Radiation Exposure Data Reports - 20232024-04-29029 April 2024 HDI Annual Occupational Radiation Exposure Data Reports - 2023 ML24116A2412024-04-25025 April 2024 Annual Environmental Protection Plan Report ML24114A2282024-04-23023 April 2024 Annual Radioactive Effluent Release Report L-24-007, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI)2024-03-29029 March 2024 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations – Holtec Decommissioning International, LLC (HDI) ML24080A1722024-03-20020 March 2024 Reply to a Notice of Violation EA-2024-010 IR 05000003/20240012024-03-20020 March 2024 NRC Inspection Report Nos. 05000003/2024001, 05000247/2024001, and 05000286/2024001 (Cover Letter Only) ML24045A0882024-02-22022 February 2024 Correction to the Technical Specifications to Reflect Appropriate Pages Removed and Retained by Previous License Amendments ML24053A0642024-02-22022 February 2024 2023 Annual Fitness for Duty Program Performance Data Report and Fatigue Management Program Data Report ML24011A1982024-01-12012 January 2024 ISFSI, Notice of Organization Change for Site Vice President ML23342A1082024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan ML23353A1742023-12-19019 December 2023 ISFSI, Emergency Plan, Revision 23-04 L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency Plan ML23339A0442023-12-0505 December 2023 Issuance of Amendment No. 68, 301 and 277 Regarding Changes to Implement the Independent Spent Fuel Storage Installation Physical Security Plan ML23338A2262023-12-0404 December 2023 Signed Amendment No. 27 to Indemnity Agreement No. B-19 ML23356A0212023-12-0101 December 2023 American Nuclear Insurers, Secondary Financial Protection (SFP) Program ML23338A0482023-11-30030 November 2023 ISFSI, Report of Changes to Physical Security, Training and Qualification, Safeguards Contingency Plan, and ISFSI Security Program, Revision 28 ML23242A2772023-11-30030 November 2023 NRC Letter Issuance - IP LAR for Units 2 and 3 Renewed Facility Licenses and PDTS to Reflect Permanent Removal of Spent Fuel from SFPs ML22339A1572023-11-27027 November 2023 Letter - Indian Point - Ea/Fonsi Request for Exemptions from Certain Emergency Planning Requirements for 10 CFR 50.47 and 10 CFR Part 50, Appendix E IR 05000003/20230032023-11-21021 November 2023 NRC Inspection Report Nos. 05000003/2023003, 05000247/2023003, 05000286/2023003, and 07200051/2023003 ML23050A0032023-11-17017 November 2023 Letter - Issuance Indian Point Unit 2 License Amendment Request to Modify Tech Specs for Staffing Requirements Following 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 ML23100A1252023-11-17017 November 2023 Letter and Enclosure 1 - Issuance Indian Point Energy Center Units 1, 2, and 3 Exemption for Offsite Primary and Secondary Liability Insurance Indemnity Agreement ML23100A1432023-11-16016 November 2023 Letter - Issuance Indian Point Energy Center Generating Units 1, 2, and 3 Exemption Concerning Onsite Property Damage Insurance (Docket Nos. 50-003, 50-247, 50-286) L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23064A0002023-11-13013 November 2023 NRC Issuance for Approval-Indian Point EC Units 1, 2 and 3 Emergency Plan and Emergency Action Level Scheme Amendments ML23306A0992023-11-0202 November 2023 and Indian Point Energy Center, Notification of Changes in Schedule in Accordance with 10 CFR 50.82(a)(7) ML23063A1432023-11-0101 November 2023 Letter - Issuance Holtec Request for Indian Point Energy Center Generating Units 1, 2, and 3 Exemptions from Certain Emergency Planning Requirements of 10 CFR 50.47 and Part 50 ML23292A0262023-10-19019 October 2023 LTR-23-0211-RI Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report-RI ML23289A1582023-10-16016 October 2023 Decommissioning International - Registration of Spent Fuel Casks and Notification of Permanent Removal of All Indian Point Unit 3 Spent Fuel Assemblies from the Spent Fuel Pit ML23270A0082023-09-27027 September 2023 Registration of Spent Fuel Casks ML23237A5712023-09-22022 September 2023 09-22-2023 Letter to Dwaine Perry, Chief, Ramapo Munsee Nation, from Chair Hanson, Responds to Letter Regarding Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23242A2182023-09-12012 September 2023 IPEC NRC Response to the Town of New Windsor, Ny Board Certified Motion Letter Regarding Treated Water Release from IP Site (Dockets 50-003, 50-247, 50-286) ML23250A0812023-09-0707 September 2023 Registration of Spent Fuel Casks ML23255A0142023-08-31031 August 2023 LTR-23-0211 Thomas Congdon, Executive Deputy, Department of Public Service, Chair, Indian Point Decommissioning Oversight Board, Letter Independent Spent Fuel Storage Installation Inspection and Office of the Inspector General Report IR 05000003/20230022023-08-22022 August 2023 NRC Inspection Report 05000003/2023002, 05000247/2023002, 05000286/2023002, and 07200051/2023002 ML23227A1852023-08-15015 August 2023 Request for a Revised Approval Date Regarding the Indian Point Energy Center Permanently Defueled Emergency Plan and Emergency Action Level Scheme ML23222A1442023-08-10010 August 2023 Registration of Spent Fuel Casks ML23208A1642023-07-26026 July 2023 Village of Croton-on-Hudson New York Letter Dated 7-26-23 Re Holtec Wastewater ML23200A0422023-07-19019 July 2023 Registration of Spent Fuel Casks ML23235A0602023-07-17017 July 2023 LTR-23-0194 Dwaine Perry, Chief, Ramapo Munsee Nation, Ltr Opposition of the Release and Dumping of Radioactive Waste from Indian Point Nuclear Power Plant Into the Hudson River ML23194A0442023-07-11011 July 2023 Clarification for Indian Point Energy Center License Amendment Request, Independent Spent Fuel Storage Installation Physical Security Plan ML23192A1002023-07-11011 July 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise the Emergency Plan and Emergency Action Level Scheme ML23171B0432023-06-23023 June 2023 Letter - Indian Point Energy Center - Request for Additional Information for Independent Spent Fuel Storage Installation Facility-Only Emergency Plan License Amendment 2024-08-06
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 28, 2015 Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 - REVIEW OF THE SPRING 2014 STEAM GENERATOR TUBE INSPECTIONS DURING REFUELING OUTAGE 21 (TAC NO. MF4866)
Dear Sir or Madam:
By letter dated September 8, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14262A059), Entergy Nuclear Operations, Inc. (the licensee),
submitted information summarizing the results of the spring 2014 steam generator (SG) tube inspections performed at Indian Point Nuclear Generating Unit No. 2. These inspections were performed during refueling outage 21. The licensee submitted additional information regarding the spring 2014 SG tube inspections by letter dated January 15, 2015 (ADAMS Accession No. ML15029A298).
The U.S. Nuclear Regulatory Commission staff has completed its review of these reports and has concluded that the licensee provided the information required by Indian Point Nuclear Generating Unit No. 2 Technical Specifications and that no additional followup is required. The staff assessment of the report is enclosed.
Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-247
Enclosure:
Staff Assessment cc w/enclosure: Distribution via Listserv
REVIEW OF THE SPRING 2014 STEAM GENERATOR TUBE INSPECTION REPORT ENTERGY NUCLEAR OPERATIONS. INC.
DOCKET NO. 50-247 INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 By letter dated September 8, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14262A059), Entergy Nuclear Operations, Inc. (the licensee),
submitted information summarizing the results of the spring 2014 steam generator (SG) tube inspections performed at Indian Point Nuclear Generating Unit No. 2 (IP2). These inspections were performed during refueling outage (RFO) 21. The licensee submitted additional information regarding the spring 2014 SG tube inspections by letter dated January 15, 2015 (ADAMS Accession No. ML15029A298).
The IP2 replacement SGs, which were installed during RFO 14 in 2000, are Westinghouse model 44F SGs. All four SGs were inspected during RFO 19. Each SG contains approximately 3,214 thermally treated Alloy 600 tubes, which have a nominal outside diameter of 0.875 inches and a nominal wall thickness of 0.050 inches. The tubes are supported by stainless steel tube support plates with quatrefoil-shaped holes and V-shaped anti-vibration bars (AVBs).
The licensee provided the scope, extent, methods, and results of the IP2 SG tube inspections in the documents referenced above. In addition, the licensee described corrective actions (i.e.,
tube plugging) taken in response to the inspection findings. The U.S. Nuclear Regulatory Commission (NRC) staff has the following notes/observations:
- An AVB position verification study was performed. The purpose was to determine if the AVBs had experienced any inservice movement and to determine whether the AVBs were in their correct positions per the design specifications. The findings of this study showed that the insertion depths had not changed since the baseline examination. The findings of this study have been entered into the licensee's corrective action program.
Based on a review of the information provided, the NRC staff concluded that the licensee provided the information required by its technical specifications. In addition, the staff concluded that there are no technical issues that warrant followup action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation, and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.
Enclosure
ML15106A012 OFFICE LPL 1-1/PM LPL 1-1/PM LPL2-2/LAiT LPL2-2/LA ESGB/BC LPL 1-1/BC(A)
NAME AGilbertson DPickett LRonewicz BClayton GKulesa by MDudek memo dated DATE 4/21/2015 4/24/2015 4/17/2015 4/17/2015 4/09/2015 4/28/2015