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| | {{#Wiki_filter:SEntergyEnteray Nuclear Northeast Indian Point Energy Center450 Broadway, GSBP.O. Box 249Buchanan, N.Y. 10511-0249 Tel (914) 254-6710Robert WalpoleLicensing ManagerNL-13-032 August 15, 2013U.S. Nuclear Regulatory Commission ATTN: Document Control Desk11555 Rockville PikeRockville, MD 20852 |
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| | ==SUBJECT:== |
| | REFERENCE Technical Specification 5.6.8 -IP3 Steam Generator Tube Inspection Report -Spring 2013 Refueling OutageIndian Point Unit No. 3Docket No. 50-286License No. DPR-641. Entergy letter to the NRC, NL-07-083 |
| | 'Steam Generator Tube Inspection Report for Spring 2007 Refueling Outage', |
| | dated July 19, 2007 |
| | |
| | ==Dear Sir or Madam:== |
| | Entergy Nuclear Operations, Inc (Entergy) is providing in Enclosure 1 the Steam Generator (SG) Tube Inspection Report required by Indian Point 3 Technical Specification 5.6.8.Technical Specification 5.6.8 requires that a report be submitted to the NRC 180 days after theinitial entry into Mode 4 following completion of a steam generator program inspection. |
| | Entergyperformed a SG inspection in March 2013 during unit 3 refueling outage 3R17. The unit initially entered MODE 4 following this inspection on March 25, 2013. This inspection was the 7th in-service inspection (ISI) following SG replacement in 1989 and the 1st of 2 scheduled inspections in the 2nd inspection period.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 steamgenerators had approximately 205 effective full power months of operation since the firstinservice inspection performed in 1990. All four steam generators were found to be incompliance with condition monitoring requirements. |
| | The previous inspection was performed during the spring 2007, Refueling Outage 3R14 (reference 1). |
| | NL-13-032 Docket No. 50-286Page 2 of 2There are no new commitments contained in this letter. If you have any questions or requireadditional information, please contact me at 914-254-6710. |
| | Sincerely, RW/mb/rdcc: Mr. William Dean, Regional Administrator, NRC Region 1Mr. Douglas Pickett,, |
| | Senior Project Manager, NRC NRR DORLMr. Peter Habighorst, Material Control and Accounting Branch, NRCIPEC NRC Resident Inspector's OfficeMr. Francis J. Murray, President and CEO, NYSERDAMs. Bridget Frymire, New York State Department of Public Service ENCLOSURE 1 TO NL-13-032 Steam Generator Examination Program Results2013 Refueling Outage (3R17)ENTERGY NUCLEAR OPERATIONS, INCINDIAN POINT NUCLEAR GENERATING UNIT 3DOCKET NO. 50-286 Indian Point Unit 3Steam Generator Examination Program Results2013 Refueling Outage Q3R17)1.0 Introduction Indian Point Unit 3 Technical Specification (TS) 5.6.8 Steam Generator Tube Inspection Report, requires Entergy Nuclear Northeast to submit a report to the NRC within 180days after initial entry into Mode 4 following a steam generator inspection performed inaccordance with Technical Specification 5.5.8, Steam Generator (SG) Program. |
| | Thereport shall include: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 inducedindications, |
| | : 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-situtesting, andh. The effective plugging percentage for all plugging in each SG.Entergy performed a SG inspection in March 2013 during refueling outage 3R17. Thisinspection was the 7th in-service inspection (ISI) following SG replacement in 1989 andthe 1st of 2 scheduled inspections in the 2nd inspection period. The unit initially enteredMODE 4 following this inspection on March 25, 2013.2.0 Steam Generator |
| | |
| | ===Background=== |
| | The original Westinghouse Model 44 SG's at Indian Point 3 were replaced in 1989 withWestinghouse Model 44F SG's. Each SG has 3214 tubes made from thermally treatedAlloy 690. The nominal OD of each tube is .875 in. and the nominal tube wall is .050 in.thick. At the time of the 2013 refueling outage (3R1 7) at Indian Point 3, the steamgenerators had accumulated approximately 205 effective full power months (EFPM) ofoperation since the first in-service inspection performed in 1990. Refueling outage 3R17was the first of two refueling outages in the second inspection period of 108 EFPM asdefined in section 5.5.8.d.2 of Technical Specifications and the first scheduled inspection of the period. The steam generator inspections were performed in March 2013.Indian Point 3 Steam Generator Primary Inspection PlanOutage Year Cycle SG Inspection Sequential NotesEFPM Cumulative Period Inspection EFPM EFPM Period3R07 1990 13 13 N/A n/a First ISI 3R08 1992 13.6 26.6 13.6 First3R09 1997 18.6 45.2 32.23R10 1999 21.5 66.7 53.73R12 2003 39.7 106.4 93.4 Skip I outage3R14 2007 44.7 151.1 138.1 Skip 1 outage3R17 2013 67 218.1 67 Second Skip 2 outages3R19 2017 45 est. 263 est. 112 est. Skip 1 outage3R21 2021 45 est. 308 est. 45 est. Third Skip 1 outage3R22 2023 22.5 est. 330 est. 67.5 est. Skip 1 outage3.0 Required Report Content -The following information is provided as required in Section5.6.8 of IP3 Technical Specifications a) Scope of Inspections The eddy current examination scope consisted of the acquisition of 50% of all tubesin all four steam generators full length with a bobbin probe, 60% of the hot leg 1stspan and 22% cold leg 1St span with an X-probe array coil probe, 50% of rows 1 and2 u-bends with the single coil +Pt rotating probe. In addition, tubes containing indications from previous examinations were examined. |
| | All indications identified during the bobbin coil had a diagnostic examination performed with the +Pt coil. Thedata analysis scope included the bobbin coil data, the array coil data, all +Pt coildata, and AVB position verification. |
| | In addition to the eddy current inspections, visual inspections were performed on alltube plugs and on the primary bowl drain area.Sludge lancing and Foreign Object Search and Retrieval (FOSAR) was performed onthe secondary side of all SG's. Secondary side Steam Drum and Top Tube SupportPlate (TTSP) inspections were performed on 2 SG's.b) Active Degradation Mechanisms No active degradation mechanisms were found during the SG inspection in 3R17.c) Nondestructive Examination Techniques NDE Techniques used for Potential Degradation Mechanisms Technique EPRI ETSS Degradation Mechanism Bobbin 96004.1 (Rev 13) Wear at AVB supports, support plates & FDBBobbin 27091.2 (Rev 0) Loose part volumetric wear, part not presentBobbin 27091.3 (Rev 1) Loose part volumetric wear, part not present+Pt 10908.4 (Rev 1) Wear at AVB locations |
| | +Pt 21998.1 (Rev 4) Freespan Volumetric |
| | +Pt 27901.1 -27907.1 (Rev 1) Freespan Volumetric |
| | +Pt 96910.1 (Rev 10) Wear at supports and PLP wear part presentArray 20200.1 (Rev 5) OD Circ indications (ODSCC) at TTS andExpansion Transitions d) Service Induced Indications There were no service induced indications detected during 3R17e) Number of Tubes Plugged by Mechanism for 3R17No tubes were plugged during 3R17f) Tubes Plugged to DateSG 31 SG 32 SG 33 SG 34 TotalTotal Number of Tubes 3214 3214 3214 3214 12856Tubes Plugged Pre-Service 0 0 0 2 2Tubes Plugged in Prior Outages 3 6 3 2 14Tubes Plugged in 3R17 0 0 0 0 0Total Tubes Plugged to Date 3 6 3 4 16% of Tubes Plugged to Date 0.09% 0.19% 0.09% 0.12% 0.12%g) Condition Monitoring ResultsNo tubes were found with newly-formed degradation. |
| | There are eight smallvolumetric indications, created in 2001 as a result of sludge lance rail wear, that arestill present, unchanged. |
| | The eight indications did not exceed condition monitoring limits. There was no detectable SG primary-to-secondary leakage during theprevious operating period. Therefore, all of the steam generator performance criteriawere met for the three previous operating cycles. Because the tube degradation found was sized less than the condition monitoring limit, in situ pressure testing wasneither required nor performed. |
| | No tube pulls were performed. |
| | Tube plug andprimary bowl drain inspections had no findings. |
| | Secondary side inspections wereperformed with all results nominal.h) Effective Plugging Percentage Since there are no sleeves installed, the effective tube plugging is equivalent to thepercentage of tubes plugged.4.0 Attachments a) SG Tubesheet Mapb) SG Landmark Information Indian Point 3 Steam Generator Tubesheet Map6ZILn M r 0) rN LO M 0) -0) V) 0l N U -t~t c'IT'-NMCO |
| | 'J MNCNCN CNN- ----Col24.(DI-NN0zcucuH Indian Point _..._.Steam Generator Location Landmarks AV2 AV3AV1 AV46H 6C5H 5C4H 4C3H 3C2H 2C1H 1CBPH BPCTSHTEH TECWestinghouse Model 44FSteam Generator LigandAV = Anti-Vibration Bar (AVB)C = cold legH = hot leg# = support plate (TSP)BP = baffle plate (FDB)TS = tubesheet TE = tube end}} |
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MONTHYEARNL-13-032, Technical Specification 5.6.8 - IP3 Steam Generator Tube Inspection Report - Spring 2013 Refueling Outage2013-08-15015 August 2013 Technical Specification 5.6.8 - IP3 Steam Generator Tube Inspection Report - Spring 2013 Refueling Outage Project stage: Request ML13295A1742013-10-24024 October 2013 Request for Additional Information Regarding the Steam Generator Tube in Service Inspection Performed During the Spring 2013 Refueling Outage Project stage: RAI ML13308B9072013-10-29029 October 2013 Response to Request for Additional Information Regarding Steam Generator Tube Inservice Inspection Performed During the Spring 2013 Refueling Outage Project stage: Request ML14015A4172014-01-30030 January 2014 Staff Summary of the Steam Generator Tube Inservice Inspections for the Spring 2013 Refueling Outage Project stage: Other ML15331A2312014-01-30030 January 2014 Official Exhibit - NYS000540-00-BD01 - Indian Point Nuclear Generating Unit No. 3 - Staff Summary of the Steam Generator Tube Inservice Inspections for the Spring 2013 Refueling Outage (TAC No. MF2614) (January 30, 2014) (ML14015A417) Project stage: Other ML15160A4042014-01-30030 January 2014 NYS000540 - Indian Point Nuclear Generating Unit No. 3 - Staff Summary of the Steam Generator Tube Inservice Inspections for the Spring 2013 Refueling Outage (TAC No. MF2614) (January 30, 2014) (ML14015A417) Project stage: Other 2013-10-29
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Category:Letter
MONTHYEARML24011A1982024-01-12012 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 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 ML23326A1322023-12-0505 December 2023 Issuance of Amendment No. 67, 300 & 276 to Implement the Independent Spent Fuel Storage Installation Only Emergency 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 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 ML23338A0482023-11-30030 November 2023 ISFSI, Report of Changes to Physical Security, Training and Qualification, Safeguards Contingency Plan, and ISFSI Security Program, Revision 28 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 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 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 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) 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 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 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 ML23118A0972023-06-0606 June 2023 06-06-23 Letter to the Honorable Michael V. Lawler, Et Al., from Chair Hanson Regarding Holtec'S Announcement to Expedite Plans to Release Over 500,000 Gallons of Radioactive Wastewater from Indian Point Energy Center Into the Hudson River ML23144A3512023-05-25025 May 2023 Clementina Bartolotta of Pearl River, New York Email Against Treated Water Release from Indian Point Site ML23144A3522023-05-25025 May 2023 Loredana Bidmead of New York E-Mail Against Treated Water Release from Indian Point Site ML23144A3412023-05-25025 May 2023 Dianne Schirripa of Rockland County, New York Email Against Treated Water Release from Indian Point Site ML23144A3472023-05-25025 May 2023 David Mart of Blauvelt, New York Email Against Treated Water Release from Indian Point Site ML23144A3402023-05-25025 May 2023 Melvin Israel of New York Email Against Treated Water Release from Indian Point Site ML23144A3542023-05-25025 May 2023 Terri Thal of New City, New York Email Against Treated Water Release from Indian Point Site ML23144A3532023-05-25025 May 2023 John Shaw of New York Email Against Treated Water Release from Indian Point Site 2024-01-09
[Table view] Category:Inservice/Preservice Inspection and Test Report
MONTHYEARNL-18-063, Submission of IP2 Steam Generator Examination Program Results for the 2018 (2R23) Refueling Outage in Accordance with Technical Specification 5.6.72018-08-13013 August 2018 Submission of IP2 Steam Generator Examination Program Results for the 2018 (2R23) Refueling Outage in Accordance with Technical Specification 5.6.7 NL-18-049, 2018 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2018-07-10010 July 2018 2018 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements NL-18-021, Indian Point, Unit 2 - Submittal of Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability2018-04-0606 April 2018 Indian Point, Unit 2 - Submittal of Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-18-021, Submittal of Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability2018-04-0606 April 2018 Submittal of Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability ML18103A0302018-04-0606 April 2018 Attachment 1 to NL-18-021, LTR-SDA-18-035-NP, Revision 0, Fracture Mechanics Assessment of Embedded Flaw Repair Acceptability NL-18-019, Relief Request Number IP2-ISI-RR-06 - Proposed Alternative to Use Reactor Vessel Head Penetration Flaw Weld Repair Method2018-04-0404 April 2018 Relief Request Number IP2-ISI-RR-06 - Proposed Alternative to Use Reactor Vessel Head Penetration Flaw Weld Repair Method NL-17-059, Request IP2-ISI-RR-22 for Relief from Examination of Non-Regenerative Heat Exchanger Base Support Welded Attachments for Fourth Ten-Year Inservice Inspection Interval Closeout2017-05-30030 May 2017 Request IP2-ISI-RR-22 for Relief from Examination of Non-Regenerative Heat Exchanger Base Support Welded Attachments for Fourth Ten-Year Inservice Inspection Interval Closeout NL-17-057, Request IP2-ISI-RR-20 for Relief from Examinations of Code Class 1 Component Welds with Less than Essentially 100% Examination Coverage for Fourth Ten-Year Inservice Inspection Interval Closeout2017-05-30030 May 2017 Request IP2-ISI-RR-20 for Relief from Examinations of Code Class 1 Component Welds with Less than Essentially 100% Examination Coverage for Fourth Ten-Year Inservice Inspection Interval Closeout NL-16-096, 2016 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements2016-09-0909 September 2016 2016 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements NL-16-097, Fifth Ten Year Interval Inservice Inspection Program Plan2016-09-0606 September 2016 Fifth Ten Year Interval Inservice Inspection Program Plan NL-16-091, Submittal of Fifth Ten Year Interval Inservice Inspection Program Plan2016-08-17017 August 2016 Submittal of Fifth Ten Year Interval Inservice Inspection Program Plan NL-16-092, Submittal of Fifth Ten Year Interval Lnservice Testing Program Plan2016-08-17017 August 2016 Submittal of Fifth Ten Year Interval Lnservice Testing Program Plan NL-16-032, Entergy Transmittal of Indian Point 2 ASME Section XI, Iwl Concrete Containment Inspection in Accordance with the Parties Approved Settlement of License Renewal Contention NYS-24 Indian Point Unit 22016-03-16016 March 2016 Entergy Transmittal of Indian Point 2 ASME Section XI, Iwl Concrete Containment Inspection in Accordance with the Parties Approved Settlement of License Renewal Contention NYS-24 Indian Point Unit 2 NL-15-073, Request for Relief Request IP2-ISI-RR-18 Maintaining ISI Related Activities on the 2001 Edition/2003A ASME Section XI Code for Fifth 10-Year Inservice Inspection (ISI) Interval2015-06-0101 June 2015 Request for Relief Request IP2-ISI-RR-18 Maintaining ISI Related Activities on the 2001 Edition/2003A ASME Section XI Code for Fifth 10-Year Inservice Inspection (ISI) Interval NL-14-060, 2014 Summary Reports for In-Service Inspection and Repairs or Replacements2014-05-0909 May 2014 2014 Summary Reports for In-Service Inspection and Repairs or Replacements NL-13-032, Technical Specification 5.6.8 - IP3 Steam Generator Tube Inspection Report - Spring 2013 Refueling Outage2013-08-15015 August 2013 Technical Specification 5.6.8 - IP3 Steam Generator Tube Inspection Report - Spring 2013 Refueling Outage NL-13-031, Submittal of 2013 Summary Reports for Inservice Inspection and Repairs or Replacements2013-06-18018 June 2013 Submittal of 2013 Summary Reports for Inservice Inspection and Repairs or Replacements NL-13-040, Relief Request IP2-ISI-RR-16: Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination2013-02-20020 February 2013 Relief Request IP2-ISI-RR-16: Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination NL-13-002, Proposed Technical Specification Bases Changes to Credit Four Fan Cooler Units in Containment Integrity Analysis2013-01-28028 January 2013 Proposed Technical Specification Bases Changes to Credit Four Fan Cooler Units in Containment Integrity Analysis NL-11-075, Submittal of Request for Relief to Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination2011-06-29029 June 2011 Submittal of Request for Relief to Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination NL-11-050, Submittal of 2011 Summary Reports for In-Service Inspection and Repairs or Replacements2011-06-20020 June 2011 Submittal of 2011 Summary Reports for In-Service Inspection and Repairs or Replacements ML1024400362010-08-24024 August 2010 Submittal of Steam Generator Examination Program Results 2010 Refueling Outage (2R19) NL-10-058, Summary Reports for In-Service Inspection and Repairs or Replacements2010-06-0909 June 2010 Summary Reports for In-Service Inspection and Repairs or Replacements NL-10-059, Relief Request IP2-ISI-RR-11 for Fourth Ten-Year Inservice Inspection Interval2010-06-0303 June 2010 Relief Request IP2-ISI-RR-11 for Fourth Ten-Year Inservice Inspection Interval NL-09-107, Relief Request 2-10 for Fourth Ten-Year Inservice Inspection Interval2009-08-0505 August 2009 Relief Request 2-10 for Fourth Ten-Year Inservice Inspection Interval NL-09-097, Submittal of Fourth Ten-Year Interval Inservice Inspection and Containment Inservice Inspection Program Plan2009-07-21021 July 2009 Submittal of Fourth Ten-Year Interval Inservice Inspection and Containment Inservice Inspection Program Plan NL-09-090, Relief Requests 08 and 09 for Fourth Ten-Year Inservice Inspection Interval2009-07-0101 July 2009 Relief Requests 08 and 09 for Fourth Ten-Year Inservice Inspection Interval NL-09-069, 2009 Summary Reports for In-Service Inspection and Repairs or Replacements2009-07-0101 July 2009 2009 Summary Reports for In-Service Inspection and Repairs or Replacements NL-09-087, Relief Request IP3-ISI-RR-01, IP3-ISI-RR-02, and IP3-ISI-RR-03 for Fourth Ten-Year Inservice Inspection Interval2009-06-24024 June 2009 Relief Request IP3-ISI-RR-01, IP3-ISI-RR-02, and IP3-ISI-RR-03 for Fourth Ten-Year Inservice Inspection Interval NL-09-037, Response to Request for Information Regarding Request for Relief 3-48 Supporting Refuel Outage 15 Inservice Inspection Program2009-03-23023 March 2009 Response to Request for Information Regarding Request for Relief 3-48 Supporting Refuel Outage 15 Inservice Inspection Program NL-09-003, Supplemental Response to Request for Additional Information on Request for Relief to Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination2009-01-20020 January 2009 Supplemental Response to Request for Additional Information on Request for Relief to Extend the Inservice Inspection Interval for the Reactor Vessel Weld Examination NL-08-110, Summary Reports for In-Service Inspection and Repairs for Replacements2008-07-14014 July 2008 Summary Reports for In-Service Inspection and Repairs for Replacements NL-08-053, 10 CFR 50.55a Request RR-CRV-75 - Relief from Examinations of Component Welds with Less than Essentially 100% Examination Coverage for Third-Ten Year Inservice Inspection Interval Closeout2008-03-26026 March 2008 10 CFR 50.55a Request RR-CRV-75 - Relief from Examinations of Component Welds with Less than Essentially 100% Examination Coverage for Third-Ten Year Inservice Inspection Interval Closeout NL-07-069, Inservice Inspection Third Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval2007-06-13013 June 2007 Inservice Inspection Third Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval ML0707100072007-03-19019 March 2007 Summary of the Staff'S Review of the 2006 Steam Generator Tube Inservice Inspection Reports for Refueling Outrage 17 NL-07-028, Inservice Testing Program Summary for 4th Interval, Revision 02007-02-28028 February 2007 Inservice Testing Program Summary for 4th Interval, Revision 0 NL-07-029, 4th Ten-Year Interval Inservice Inspection and Containment Inservice Inspection Program Plan2007-02-28028 February 2007 4th Ten-Year Interval Inservice Inspection and Containment Inservice Inspection Program Plan NL-05-088, Inservice Inspection (ISI) Second Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval2005-07-0606 July 2005 Inservice Inspection (ISI) Second Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval NL-05-0211, Inservice Testing Program Summary for the Interval July 1, 1994 Through April 6.2006. Revision 32005-02-22022 February 2005 Inservice Testing Program Summary for the Interval July 1, 1994 Through April 6.2006. Revision 3 ML0506304052005-02-22022 February 2005 Inservice Inspection (ISI) Third Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval JPN-04-010, Request to Use 1998 Edition, 2000 Addenda of American Society of Mechanical Engineers (ASME) Section Xl Code Requirements for Examination of Reactor Vessel Closure Studs2004-04-14014 April 2004 Request to Use 1998 Edition, 2000 Addenda of American Society of Mechanical Engineers (ASME) Section Xl Code Requirements for Examination of Reactor Vessel Closure Studs NL-03-188, Request for Approval for Alternative to Use Code Case N-613-1 for Reactor Vessel Nozzle to Vessel Weld Inspection2003-12-30030 December 2003 Request for Approval for Alternative to Use Code Case N-613-1 for Reactor Vessel Nozzle to Vessel Weld Inspection NL-03-078, Relief Request RR 63, Risk-Informed Inservice Inspection (RI-ISI) Program2003-05-12012 May 2003 Relief Request RR 63, Risk-Informed Inservice Inspection (RI-ISI) Program NL-03-055, Withdrawal of Relief Request RR3-29 for Inservice Inspection Program2003-03-27027 March 2003 Withdrawal of Relief Request RR3-29 for Inservice Inspection Program NL-03-026, Refueling Outage Inservice Inspection (ISI) Program Summary Report - Third Outage, Second Period, Third Interval2003-02-25025 February 2003 Refueling Outage Inservice Inspection (ISI) Program Summary Report - Third Outage, Second Period, Third Interval NL-04-006, St Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval2003-01-20020 January 2003 St Period Inspection Results and Repair/Replacement Activities for Third 10-Year Inservice Inspection Interval ML0209900922002-04-0303 April 2002 Revised Relief Request Nos. 3-12, 3-14, 3-16 & 3-17, Third 10-Year Inservice Inspection Interval Program Plan ML0205803912002-02-0505 February 2002 Relief Request RR 3-28, Risk-Informed Inservice Inspection (RI-ISI) Program 2018-08-13
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SEntergyEnteray Nuclear Northeast Indian Point Energy Center450 Broadway, GSBP.O. Box 249Buchanan, N.Y. 10511-0249 Tel (914) 254-6710Robert WalpoleLicensing ManagerNL-13-032 August 15, 2013U.S. Nuclear Regulatory Commission ATTN: Document Control Desk11555 Rockville PikeRockville, MD 20852
SUBJECT:
REFERENCE Technical Specification 5.6.8 -IP3 Steam Generator Tube Inspection Report -Spring 2013 Refueling OutageIndian Point Unit No. 3Docket No. 50-286License No. DPR-641. Entergy letter to the NRC, NL-07-083
'Steam Generator Tube Inspection Report for Spring 2007 Refueling Outage',
dated July 19, 2007
Dear Sir or Madam:
Entergy Nuclear Operations, Inc (Entergy) is providing in Enclosure 1 the Steam Generator (SG) Tube Inspection Report required by Indian Point 3 Technical Specification 5.6.8.Technical Specification 5.6.8 requires that a report be submitted to the NRC 180 days after theinitial entry into Mode 4 following completion of a steam generator program inspection.
Entergyperformed a SG inspection in March 2013 during unit 3 refueling outage 3R17. The unit initially entered MODE 4 following this inspection on March 25, 2013. This inspection was the 7th in-service inspection (ISI) following SG replacement in 1989 and the 1st of 2 scheduled inspections in the 2nd inspection period.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 steamgenerators had approximately 205 effective full power months of operation since the firstinservice inspection performed in 1990. All four steam generators were found to be incompliance with condition monitoring requirements.
The previous inspection was performed during the spring 2007, Refueling Outage 3R14 (reference 1).
NL-13-032 Docket No. 50-286Page 2 of 2There are no new commitments contained in this letter. If you have any questions or requireadditional information, please contact me at 914-254-6710.
Sincerely, RW/mb/rdcc: Mr. William Dean, Regional Administrator, NRC Region 1Mr. Douglas Pickett,,
Senior Project Manager, NRC NRR DORLMr. Peter Habighorst, Material Control and Accounting Branch, NRCIPEC NRC Resident Inspector's OfficeMr. Francis J. Murray, President and CEO, NYSERDAMs. Bridget Frymire, New York State Department of Public Service ENCLOSURE 1 TO NL-13-032 Steam Generator Examination Program Results2013 Refueling Outage (3R17)ENTERGY NUCLEAR OPERATIONS, INCINDIAN POINT NUCLEAR GENERATING UNIT 3DOCKET NO. 50-286 Indian Point Unit 3Steam Generator Examination Program Results2013 Refueling Outage Q3R17)1.0 Introduction Indian Point Unit 3 Technical Specification (TS) 5.6.8 Steam Generator Tube Inspection Report, requires Entergy Nuclear Northeast to submit a report to the NRC within 180days after initial entry into Mode 4 following a steam generator inspection performed inaccordance with Technical Specification 5.5.8, Steam Generator (SG) Program.
Thereport shall include: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 inducedindications,
- 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-situtesting, andh. The effective plugging percentage for all plugging in each SG.Entergy performed a SG inspection in March 2013 during refueling outage 3R17. Thisinspection was the 7th in-service inspection (ISI) following SG replacement in 1989 andthe 1st of 2 scheduled inspections in the 2nd inspection period. The unit initially enteredMODE 4 following this inspection on March 25, 2013.2.0 Steam Generator
Background
The original Westinghouse Model 44 SG's at Indian Point 3 were replaced in 1989 withWestinghouse Model 44F SG's. Each SG has 3214 tubes made from thermally treatedAlloy 690. The nominal OD of each tube is .875 in. and the nominal tube wall is .050 in.thick. At the time of the 2013 refueling outage (3R1 7) at Indian Point 3, the steamgenerators had accumulated approximately 205 effective full power months (EFPM) ofoperation since the first in-service inspection performed in 1990. Refueling outage 3R17was the first of two refueling outages in the second inspection period of 108 EFPM asdefined in section 5.5.8.d.2 of Technical Specifications and the first scheduled inspection of the period. The steam generator inspections were performed in March 2013.Indian Point 3 Steam Generator Primary Inspection PlanOutage Year Cycle SG Inspection Sequential NotesEFPM Cumulative Period Inspection EFPM EFPM Period3R07 1990 13 13 N/A n/a First ISI 3R08 1992 13.6 26.6 13.6 First3R09 1997 18.6 45.2 32.23R10 1999 21.5 66.7 53.73R12 2003 39.7 106.4 93.4 Skip I outage3R14 2007 44.7 151.1 138.1 Skip 1 outage3R17 2013 67 218.1 67 Second Skip 2 outages3R19 2017 45 est. 263 est. 112 est. Skip 1 outage3R21 2021 45 est. 308 est. 45 est. Third Skip 1 outage3R22 2023 22.5 est. 330 est. 67.5 est. Skip 1 outage3.0 Required Report Content -The following information is provided as required in Section5.6.8 of IP3 Technical Specifications a) Scope of Inspections The eddy current examination scope consisted of the acquisition of 50% of all tubesin all four steam generators full length with a bobbin probe, 60% of the hot leg 1stspan and 22% cold leg 1St span with an X-probe array coil probe, 50% of rows 1 and2 u-bends with the single coil +Pt rotating probe. In addition, tubes containing indications from previous examinations were examined.
All indications identified during the bobbin coil had a diagnostic examination performed with the +Pt coil. Thedata analysis scope included the bobbin coil data, the array coil data, all +Pt coildata, and AVB position verification.
In addition to the eddy current inspections, visual inspections were performed on alltube plugs and on the primary bowl drain area.Sludge lancing and Foreign Object Search and Retrieval (FOSAR) was performed onthe secondary side of all SG's. Secondary side Steam Drum and Top Tube SupportPlate (TTSP) inspections were performed on 2 SG's.b) Active Degradation Mechanisms No active degradation mechanisms were found during the SG inspection in 3R17.c) Nondestructive Examination Techniques NDE Techniques used for Potential Degradation Mechanisms Technique EPRI ETSS Degradation Mechanism Bobbin 96004.1 (Rev 13) Wear at AVB supports, support plates & FDBBobbin 27091.2 (Rev 0) Loose part volumetric wear, part not presentBobbin 27091.3 (Rev 1) Loose part volumetric wear, part not present+Pt 10908.4 (Rev 1) Wear at AVB locations
+Pt 21998.1 (Rev 4) Freespan Volumetric
+Pt 27901.1 -27907.1 (Rev 1) Freespan Volumetric
+Pt 96910.1 (Rev 10) Wear at supports and PLP wear part presentArray 20200.1 (Rev 5) OD Circ indications (ODSCC) at TTS andExpansion Transitions d) Service Induced Indications There were no service induced indications detected during 3R17e) Number of Tubes Plugged by Mechanism for 3R17No tubes were plugged during 3R17f) Tubes Plugged to DateSG 31 SG 32 SG 33 SG 34 TotalTotal Number of Tubes 3214 3214 3214 3214 12856Tubes Plugged Pre-Service 0 0 0 2 2Tubes Plugged in Prior Outages 3 6 3 2 14Tubes Plugged in 3R17 0 0 0 0 0Total Tubes Plugged to Date 3 6 3 4 16% of Tubes Plugged to Date 0.09% 0.19% 0.09% 0.12% 0.12%g) Condition Monitoring ResultsNo tubes were found with newly-formed degradation.
There are eight smallvolumetric indications, created in 2001 as a result of sludge lance rail wear, that arestill present, unchanged.
The eight indications did not exceed condition monitoring limits. There was no detectable SG primary-to-secondary leakage during theprevious operating period. Therefore, all of the steam generator performance criteriawere met for the three previous operating cycles. Because the tube degradation found was sized less than the condition monitoring limit, in situ pressure testing wasneither required nor performed.
No tube pulls were performed.
Tube plug andprimary bowl drain inspections had no findings.
Secondary side inspections wereperformed with all results nominal.h) Effective Plugging Percentage Since there are no sleeves installed, the effective tube plugging is equivalent to thepercentage of tubes plugged.4.0 Attachments a) SG Tubesheet Mapb) SG Landmark Information Indian Point 3 Steam Generator Tubesheet Map6ZILn M r 0) rN LO M 0) -0) V) 0l N U -t~t c'IT'-NMCO
'J MNCNCN CNN- ----Col24.(DI-NN0zcucuH Indian Point _..._.Steam Generator Location Landmarks AV2 AV3AV1 AV46H 6C5H 5C4H 4C3H 3C2H 2C1H 1CBPH BPCTSHTEH TECWestinghouse Model 44FSteam Generator LigandAV = Anti-Vibration Bar (AVB)C = cold legH = hot leg# = support plate (TSP)BP = baffle plate (FDB)TS = tubesheet TE = tube end