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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARJAFP-23-0008, Supplement to Inservice Inspection Summary Report Cycle 252023-02-22022 February 2023 Supplement to Inservice Inspection Summary Report Cycle 25 JAFP-22-0053, Inservice Inspection Summary Report Cycle 252022-12-20020 December 2022 Inservice Inspection Summary Report Cycle 25 JAFP-20-0087, Inservice Inspection Summary Report Cycle 242020-12-28028 December 2020 Inservice Inspection Summary Report Cycle 24 JAFP-19-0004, Inservice Inspection Summary Report Cycle 232019-01-0404 January 2019 Inservice Inspection Summary Report Cycle 23 JAFP-18-0113, Fifth Ten-Year Lnservice Inspection Interval Program Plan2018-12-17017 December 2018 Fifth Ten-Year Lnservice Inspection Interval Program Plan JAFP-18-0078, Fifth Ten-Year Interval Inservice Testing Program Plan2018-08-0606 August 2018 Fifth Ten-Year Interval Inservice Testing Program Plan JAFP-17-0057, Inservice Inspection Summary Report 2017 Refuel Outage 222017-05-25025 May 2017 Inservice Inspection Summary Report 2017 Refuel Outage 22 JAFP-16-0136, Alternative Examination Requirements Nozzle-to-Vessel Welds and Nozzle Inner Radii Using ASME Code Case N-702 and BWRVIP-2412016-08-24024 August 2016 Alternative Examination Requirements Nozzle-to-Vessel Welds and Nozzle Inner Radii Using ASME Code Case N-702 and BWRVIP-241 JAFP-14-0012, Inservice Testing Program 10 CFR 50.55a Request PRR-052014-02-21021 February 2014 Inservice Testing Program 10 CFR 50.55a Request PRR-05 JAFP-13-0004, Inservice Inspection Summary Report 2012 Refuel Outage (Reload 20/Cycle 21)2013-01-14014 January 2013 Inservice Inspection Summary Report 2012 Refuel Outage (Reload 20/Cycle 21) JAFP-11-0009, Inservice Inspection Summary Report 2010 Refuel Outage (Reload 19/Cycle 20)2011-01-18018 January 2011 Inservice Inspection Summary Report 2010 Refuel Outage (Reload 19/Cycle 20) JAFP-09-0088, Proposed Relief Request VRR-06 for the Fourth Interval In-Service Testing Program2009-07-31031 July 2009 Proposed Relief Request VRR-06 for the Fourth Interval In-Service Testing Program JAFP-09-0008, Response to Request for Additional Information Regarding: Request for Additional Information Third Ten-Year Inservice Inspection Interval Program Plan Relief Request RR-CRV-012009-01-20020 January 2009 Response to Request for Additional Information Regarding: Request for Additional Information Third Ten-Year Inservice Inspection Interval Program Plan Relief Request RR-CRV-01 JAFP-09-0004, Inservice Inspection Summary Report 2008 Refuel Outage (Reload 18/Cycle 19)2009-01-10010 January 2009 Inservice Inspection Summary Report 2008 Refuel Outage (Reload 18/Cycle 19) JAFP-08-0109, Submittal of the Final Ultrasonic Test Results on the N2C-SE Weld Overlay2008-10-20020 October 2008 Submittal of the Final Ultrasonic Test Results on the N2C-SE Weld Overlay JAFP-08-0038, Inservice Inspection Program Relief Requests Third Ten-year Interval Closeout2008-04-30030 April 2008 Inservice Inspection Program Relief Requests Third Ten-year Interval Closeout JAFP-07-0116, Fourth Interval Inservice Testing Program for Pumps and Valves2007-09-26026 September 2007 Fourth Interval Inservice Testing Program for Pumps and Valves JAFP-07-0107, Response to Request for Additional Information Regarding Proposed Relief Request PRR-01 for the Fourth Interval In-Service Testing Program2007-08-29029 August 2007 Response to Request for Additional Information Regarding Proposed Relief Request PRR-01 for the Fourth Interval In-Service Testing Program JAFP-07-0050, Proposed Relief Requests for the James A. FitzPatrick Power Plant Fourth Interval In-Service Testing Program2007-04-11011 April 2007 Proposed Relief Requests for the James A. FitzPatrick Power Plant Fourth Interval In-Service Testing Program JAFP-07-0030, Fourth Inservice Inspection Interval Inspection Program Plan2007-02-27027 February 2007 Fourth Inservice Inspection Interval Inspection Program Plan JAFP-07-0020, Submittal of James A. Fitzpatrick - Inservice Inspection Summary Report 2006 Refuel Outage (Reload 17/Cycle 18)2007-02-0202 February 2007 Submittal of James A. Fitzpatrick - Inservice Inspection Summary Report 2006 Refuel Outage (Reload 17/Cycle 18) JAFP-05-0151, Request for Approval of Relief Request No. RR-39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection2005-10-0707 October 2005 Request for Approval of Relief Request No. RR-39, Implementation of BWRVIP Guidelines in Lieu of ASME Section XI Code Requirements on Reactor Vessel Internals and Components Inspection ML0515802032005-05-26026 May 2005 Request for Relief from System Hydrostatic Test Requirements for Small Bore (5 1 Inch), ASME Code Class 1 Reactor Coolant Pressure Boundary (RCPB) Vent, Drain, and Branch (Vtdb) Lines and Connections JAFP-05-0013, Inservice Inspection Summary Report 2004 Refuel Outage (Reload 16/Cycle 17)2005-01-19019 January 2005 Inservice Inspection Summary Report 2004 Refuel Outage (Reload 16/Cycle 17) 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 JAFP-03-0096, James a FitzPatrick Nuclear Power Plant, Proposed Relief Request No. VRR-08 to In-Service Testing Program2003-07-0808 July 2003 James a FitzPatrick Nuclear Power Plant, Proposed Relief Request No. VRR-08 to In-Service Testing Program JAFP-02-0251, In-Vessel Visual Inspection Summary Report 2002 Refuel Outage (Reload 15/Cycle 16)2002-12-26026 December 2002 In-Vessel Visual Inspection Summary Report 2002 Refuel Outage (Reload 15/Cycle 16) JPN-02-026, Relief Request RR-28, Revision 3 for Third 10-Year Inservice Inspection Interval Program Plan2002-09-12012 September 2002 Relief Request RR-28, Revision 3 for Third 10-Year Inservice Inspection Interval Program Plan JPN-02-022, License DPR-59, Relief Request RR-28, Revision 2 for the Third 10-Year Inservice Inspection Interval Program Plan2002-07-10010 July 2002 License DPR-59, Relief Request RR-28, Revision 2 for the Third 10-Year Inservice Inspection Interval Program Plan JPN-02-001, Submittal of James A. FitzPatrick Owner'S Activity Report, JAF-RPT-MULTI-04331, Rev. 0 Which Contains Inservice Inspection Results & Repair/Replacement Activities Performed During 1st Period of Third 10-Year ISI Interval2002-01-28028 January 2002 Submittal of James A. FitzPatrick Owner'S Activity Report, JAF-RPT-MULTI-04331, Rev. 0 Which Contains Inservice Inspection Results & Repair/Replacement Activities Performed During 1st Period of Third 10-Year ISI Interval 2023-02-22
[Table view] Category:Letter type:JAFP
MONTHYEARJAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications JAFP-23-0069, Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation JAFP-23-0064, Emergency Plan Document Revision2023-11-15015 November 2023 Emergency Plan Document Revision JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023 Registration of Spent Fuel Cask Use JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023 Registration of Spent Fuel Cask Use JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-31031 August 2023 Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0050, Physical Security Plan, Revision 242023-08-31031 August 2023 Physical Security Plan, Revision 24 JAFP-23-0047, Correction to the 2022 Annual Radioactive Effluent Release Report2023-08-30030 August 2023 Correction to the 2022 Annual Radioactive Effluent Release Report JAFP-23-0040, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-0303 August 2023 License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0043, 10 CFR 50.46 Annual Report2023-07-31031 July 2023 10 CFR 50.46 Annual Report JAFP-23-0038, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2023-07-28028 July 2023 License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance JAFP-23-0033, License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation2023-06-28028 June 2023 License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation JAFP-23-0025, 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Annual Radiological Environmental Operating Report JAFP-23-0023, 2022 Annual Radioactive Effluent Release Report2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report JAFP-23-0010, 2022 REIRS Transmittal of NRC Form 52023-03-20020 March 2023 2022 REIRS Transmittal of NRC Form 5 JAFP-23-0008, Supplement to Inservice Inspection Summary Report Cycle 252023-02-22022 February 2023 Supplement to Inservice Inspection Summary Report Cycle 25 JAFP-22-0053, Inservice Inspection Summary Report Cycle 252022-12-20020 December 2022 Inservice Inspection Summary Report Cycle 25 JAFP-22-0046, Core Operating Limits Report Cycle 262022-10-17017 October 2022 Core Operating Limits Report Cycle 26 JAFP-22-0040, 10 CFR 50.46 Annual Report2022-07-29029 July 2022 10 CFR 50.46 Annual Report JAFP-22-0033, Core Operating Limits Report Mid-Cycle 252022-06-23023 June 2022 Core Operating Limits Report Mid-Cycle 25 JAFP-22-0032, Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b..2022-06-16016 June 2022 Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.. JAFP-22-0030, Oswego County and New York State Participation in the Emergency Plan2022-05-13013 May 2022 Oswego County and New York State Participation in the Emergency Plan JAFP-22-0029, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022 2021 Annual Radiological Environmental Operating Report JAFP-22-0028, 2021 Annual Radioactive Effluent Release Report2022-04-27027 April 2022 2021 Annual Radioactive Effluent Release Report JAFP-22-0026, 2021 REIRS Transmittal of NRC Form 52022-04-0707 April 2022 2021 REIRS Transmittal of NRC Form 5 JAFP-22-2020, Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Info2022-03-0404 March 2022 Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Informed JAFP-22-0017, Amendments to Indemnity Agreements2022-02-15015 February 2022 Amendments to Indemnity Agreements JAFP-22-0007, Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102022-01-31031 January 2022 Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 JAFP-22-0010, Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments2022-01-24024 January 2022 Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments JAFP-22-0008, Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary2022-01-14014 January 2022 Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary JAFP-21-0093, Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation2021-10-18018 October 2021 Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0083, Notification of Readiness for NRC 95001 Inspection2021-09-0909 September 2021 Notification of Readiness for NRC 95001 Inspection JAFP-21-0081, Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-0303 September 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements JAFP-21-0075, Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2021-08-12012 August 2021 Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs JAFP-21-0073, Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance.2021-08-0909 August 2021 Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance. JAFP-21-0069, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2021-07-30030 July 2021 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors JAFP-21-0070, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b2021-07-30030 July 2021 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b JAFP-21-0071, 10 CFR 50.46 Annual Report2021-07-29029 July 2021 10 CFR 50.46 Annual Report JAFP-21-0064, Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-07-0707 July 2021 Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting JAFP-21-0053, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-14014 June 2021 Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0052, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021 Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0051, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021 Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0050, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-12012 June 2021 Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0042, Reply to a Notice of Violation; EA-20-1382021-06-0303 June 2021 Reply to a Notice of Violation; EA-20-138 JAFP-21-0041, Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2021-05-17017 May 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing JAFP-21-0040, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2021-05-14014 May 2021 Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs 2023-08-31
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Text
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.
James A. Fitzpatrick NPP
Entergy P.O. Box 110 Lycoming, NY 13093 Tel 315-342-3840 JAFP-08-0109 October 20, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59 Submittal of the Final Ultrasonic Test Results on the N2C-SE Weld Overlay
REFERENCES:
- 1) Entergy Letter to NRC, JAFP-08-0102, "James A. FitzPatrick Request for Relief (RR-7 Revision 1) - Proposed Alternative to ASME Code Requirements for Weld Overlay Repairs", dated October 1, 2008
Dear Sir or Madam:
of reference 1 documented commitments to submit to the NRC, within fourteen days of the completion of the final ultrasonic test (UT) on the weld overlay proposed in the subject relief request, the following:
- 1) Weld overlay examination results including a listing of indications detected;
- 2) Disposition of indications using the standards of ASME Section Xl, Subsection IWB-3514-2 and/or IWB-3514-3 criteria and, if possible, the type and nature of the indications; and
- 3) A discussion of any repairs to the weld overlay material and/or base metal and the reason for the repairs.
In summary the weld overlay repair was performed to N-2C-SE per work order 00106631 and Relief Request RR-7. No repairs, to the weld overlay material and/or base material, were required. Ultrasonic Examination of the weld overlay was performed per ASME Appendix VIII requirements (see Enclosure 1). The examination identified no recordable indications and noted the original axial flaw as previously identified in the original examination. No indications required evaluation to ASME Section Xl, Subsection IWB 3514-2 and/or IWB-3514-3 criteria. of this letter contains a copy of the GE Hitachi Examination Summary, Report No.
08UT175.
There are no new commitment made in this letter and the final commitment made in reference 1 will be completed as scheduled.
JAFP-08-0109 Page 2 of 2 If you have any questions or require additional information, please contact Mr. Eugene Dorman, Acting Licensing Manager, at 315-349-6810.
Sincerely, Eugene Dorman Acting Licensing Manager ED/ed cc:
Mr. Samuel J. Collins, Regional Administrator Mr. Bhalchandra Vaidya, Project U.S. Nuclear Regulatory Commission, Region Manager 475 Allendale Road Plant Licensing Branch King of Prussia, PA 19406-1415 U.S. Nuclear Regulatory Commission Mail Stop O-8-C2A Office of NRC Resident Inspector Washington, DC 20555 James A. Fitzpatrick Nuclear Power Plant P.O. Box 136 Mr. Charles Donaldson, Esquire Lycoming, New York 13093 Assistant Attorney General New York Department of Law Mr. Paul Tonko, President 120 Broadway New York State Energy Research and New York, New York 10271 Development Authority 17 Columbia Circle Mr. Paul Eddy Albany, New York 12203-6399 New York State Department of Public Services
- 3. Empire State Plaza Albany, NewYork 12223-1350
Enclosure 1 to [[::JAF-08-0109|JAF-08-0109]] James A. Fitzpatrick Nuclear Power Station Docket No. 50-333 GE HITACHI EXAMINATION
SUMMARY
SHEET REPORT No. 08UT175
Report No.:
HITACHI EXAMINATION
SUMMARY
SHEET 08UT175 Site: Fitzpatrick Component ID: N2C-SE Outage: RFO18 WELD OVERLAY System:
vj .......
02-2 ASME Cot.: B-F ASME Item B5.10 Aug Req N/A
-I
- Exams Data Sheet Cal Sheet i Procedure Calibration Block Exam / Oper, Cert Leve
. i Date Performed Personnel
,i III !10/4/2008 45' RL D-106 N/A ENN-NDE-9.29 Ve./Rev 1 CAL-DPTH-070 Scott Erickson D-105 N/A ENN-NDE-9.29 Ver/Rev 1 CAL-DPTH-070 Scott Erickson 10/4/2008 70' RL D-104 N/A ENN-NDE-9.29 Ver/Rev 1 CAL-DPTH-070 Scott Erickson HIl 10/4/2008
_o0*Long...- D-103 N/A. - ENN-NDE-9.29 Ver/Rev 1 CAL-DPTH-070 Scott Erickson Ill 1o0/4/2008 Examination Results:
During the Manual Ultrasonic Examination of the above referenced componenL no new ISIor PSI recordable indications were detected utilizing a 0*, 700 RL,and ODCR RL for the PSI portion and 450 RLfor the SI portion of the exam.
No change observed to the thru-wall height (0.51') of previously recorded flow prior to weld overlay repair.
100% of the code required volume was examined.
This UT Examination meets the 2001 Edition of ASME Section xi with the 2003 Addenda and is in accordance with Appendix VIII2001 Edition as amended and mandated by 10CFR50 Amended Requirements, Final Rule dated October 1, 2004 Examination results were compared to Data Report N/A from: N/A - Change These examinations were performed under Work Order: 00125346 No Change This Summary and the following data sheets have been reviewed and ac/ed by the following personnel:
)RWRP N/A N7 10 -& Dose: 251 mr.
Prepared By- Level: Date: UtiIit Date:
ANII Review. Date: Page 1 of 6
0 ý HITACHI Ultrasonic Calibration and Examination Record Manual Piping and Components I Report Number. 08UT175
.Site/Unit: Fitzpatrick/i Data Sheet Number: D-106 Outage: RFO18 Linearity Sheet L-007 Prncpdijrp ENN-NDE-9 29
\.UILk iAAU nJt fn.AA 01 6LJW~A.f'A _ I~- Procedur ENN-N--.-9.
Ver/Rev: 1 DRR: N/A ss FLAT 2.0" Calibration Cal Time Material Size Thick Initial Cal: Search Unit Data i105
- Ultra gel /II0 22 iCal Check Couplant Couplar it batch RTD 01-107 2(8x14) mm/Rect.
Cal Check- 1314 Manufacturer- Serial Number Size/Shape:
261732 95 Thermometer S/N Cal Temp. Final Cal: 1400 0.45 45. 45.
Incident Point: Nominal Angle: Measured Angle:
DAC Construction 2.0 MHz TRL2-Aust RL 2 Frequency: Style: Mode: Elements:
Scan Direction Ax Cal Reflector .8"SDH Search Unit Cable Signal Amplitude: 80%
RG-174 1Z 0 Signal Sweep: 5.40 Div Cable Type: Length: Connectors:
Signal dB: 27.1 dB Sweep 0-10= 2.000 in Metal Path Instrument Settings Calibration Verification Panametrics / Epoch 4 031534305 Manufacturer/Model: Serial Number.
Field Simulator Block S/N; CAL-RHOM-117 Reflector NSDH NIA 7.615eus 02318 in./usec. 0.8-3.0 Zero: Velocity: Narrowband Filter:
Amplitude 40% NIA Gain (dB) 27.1 N/A Auto Fullwove 2.000 in Sq. i Max Sweep (SD) I 22 .1A Rep Rate: Rectification: Range: Pulser/Energy:
400 Ohms 0% 2.0 MHz Dual Acceptable Linearity performed : 12 Damping: Reject: Frequency: Mode:
Exam Data for Weld: N2C-SE WELD OVERLAY Exam Comments / Limitations:
Configuration: Exams performed to maintain a 5% to 20% noise level.
00 120* F 261732 ?&9iFWoav'P
~ ~ 4, "
Exam Surface: Exam Temp. Exam Thermometer Axial U-PST Scan-ald I Recordable Exam Circ DNST Indications I Angle UPSr 3 NRI 4?-
ONST 33 .1 NRI 45" Circ UPST 39.1 --* NRI
-- :45 i
- Em StartL "E~am 1252 Exam End: 1314 Circ DNST 39.1 NRI 450 c . Scot EricksonI Initials: Examiner: Level: GE Reviewe By: Level: Date:
N/A N/A Utility Rey . Date:
Initials: Examiner 2: Level:
initial Col/Exam Date: 10/4/2008 ANII Review.-- - Page 2 of6 Dote
Ultrasonic Calibration and Examination Record HITACHI Manual Piping and Components Report Number. 08UT175 I
'Site/Unit: Fit-zptrick/1 Data Sheet Number: D-105 Outage: RF018 Linearity Sheet L-007 Calibration Data for Block: CAL-DPTH-070 Procedure: ENN-NDE-9.29 Ver / Rev: 1 DRR: NIA 55 FLAT 2.0" i Calibration Cal Time Material Size Thick Initial Cal: Search Unit Data Ultrael 06225 Col Check 1237 RTD 04-392 2('1045)mm/Rect.
Couplant Couplant batch Cal Check 1251 Manufacturer: Serial Number Size/Shape:
261732 95*F Thermometer S/N Cal Temp. i Final Cal: 11407 0.5 ODCR 80.
incident Point: Nominal Angle: Measured Angle:
DAC Construction 2.0 MHz 85rRL2-Aust RL 2 Frequency: Style: Mode: Elements:
Scan Direction Ax Cal Reflector .1'501- Search Unit Cable Signal Amplitude: 80%
RG-174 6L 0 Signal Sweep: 3.80 Div Cable Type: Length: Connectors:
Signal dB: 35.7 dB Sweep 0-10= L500 in Metal Path Instrument Settings Calibration Verification Ponametrics/ Epoch 4 031534305 Manufacturer/model: Serial Number:
Field Simulator Block S/N: CAL-RHOM-117
. Reflector i NSDH N/A 9.825 us 02311 in./sec. 0.8- 3.0 Zero: Velocity: Norrowband Filter:
Amplitude 80% N/A
- - "N/A . .
Gain *dB) 31.4 Auto Fullwave L500 in sq. / Max N/A Rep Rote: Rectification: Range:
Sweep (ISD) 6.1 Pulser/Energy:
400 Ohms 0% 2.0 MHz Dual Acceptable Linearity performed: 9118 Damping: Reject Frequency: Mode:
Exam Data for Weld: N2C-SE WELD OVERLAY Exam Comments / Limitations:
Configuration: i Exams performed to maintain a 5% to 20% noise /de/l.
00 120° F 261732
- &&j~4JSW0 A-7 / M.g Exam Surface: Exam Temp. Exam Thermometer Axial SUPST DNST I Scan dB Recordable Indications Exam Angle Circ Ax (UPST 37.7 NRI 80 Ax DNST 37.7 NRI 807 Circ LIPST 37.7 NRI i8
- Exam Start: 1237 Exam End: 1251 Circ DNST 37.7 NRI 80 Scott Erickson III Initials- Examin er. Level: GE eied B y Level: Date:
Date1/./, e" N/A N/A Dote:
Initials: Exomin er 2: Level: utility Rev Initial Col/Exam Dot e: 10/4/2008 ANI Reve. Page 3 of 6 Dote:
Ultrasonic Calibration and Examination Record 0
,a, HITACHI Manual Piping and Components Report Number 08U T175 I
(.. Site/Unit:
Outage: Fitzpatrick/1 RF018 Data Sheet Number:
Linearity Sheet D-104 L-007 Calibration Data for Block. CAL-DPTH-070 i Procedure: ENN-NDE-9.29 Ver/Rev: 1 DRR- N/A SS FLAT 2.0" Calibration Cal Time Material Size Thick n
Cal: ..
- ,1108 . Search Unit Data
- o*s iCal Check- 1218 Couplant Couplant batch RTD 87-296 2f(x844 mm/Rect Cal Check 1236 Manufacturer
- Serial Number Size/Shape:
261732 95° F Thermometer S/N Cal Temp. Final Cal: 1405 0.35 70* 70" Incident Point Nominal Angle: Measured Angle:
DAC Construction 2.0 MHz 70'TRL2-Aust RL 2 Frequency: Style: mode: Elements:
Scan Direction Cal Reflector .5" SDH Search Unit Cable Signal Amplitude 80%
RG-174 12' 0 Signal Sweep: 5.70 Div Cable Type: Length: Connectors:
Signal dB: 47.1 d8 Sweep 0-10 = 2.500 in Metal Path Instrument Settings Calibration Verification f'anametrics / Epoch 4 031534305 Manufacturer/Model: Serial Number.
FlieId Simulator Block S/N: coAL-RHOM-117 9.275 uis 0.231 in.jJsec. 0.8- 3.0 Reflector NSDH NIA Zero: velocity: Norrowband Filter i Amplitude 80% N/A Gain (dB) 47.1 NIA Auto Fullwave 2.500 in sq. / Max Rep Rate: Rectification: Range: Pulser/Energy:
1Sweep (SD) 3.8 N/A 400 Ohms 0% 2.0 MHz Dual Acceptable Linearity performed: Reject Frequency: Mode:
Damping:
Exam Data for Weld: N2c-SE WELD OVERLAY Exam Comments / Limitations:
Configuration: Exams performed to maintain a 5% to 20% noise levo I _OD 120° F 261732 .4~ T' ~
2A (Kfs - IL Exam Surface: Exam Temp. Exam Thermometer Axial UPSTI Scan d Recordable Exam Circ DNST 1 Indications Angle Ax UPST 49. 1 ! NRI 70° Ax NST 49.
NRI 70" Circ UPST 49.
1 NRI 70 Exam Start: 1218 Exam End: 1235 Circ DNST 49. S NR i 70.
Scott Erickson Initials: Examiner. Level: GE RevieGwed By Level: Clate:
N/A N/A Level: Utility Rev . Date:
Initials: Examiner 2: .
Initial Col/Exam Dote: 101412008 Page 4 of 6 ANII Review. Dote:
I ....
HITACHI !
Ultrasonic Calibration and Examination Record Manual Piping and Components Report Number. 08UT175 I
- Site/Unit Fitzpatrick/1 Data Sheet Number 0-103 Outage: RFO18 Linearity Sheet: L-007 Calibration Data for Block: CAL-DPTH-070 Procedure: ENN-NDE-9.29 Ver / Rev: 1 DRR: NIA 55 FLAT 2.0" 'Calibration Cal Time Material Size Thick initial Cal: i Search Unit Data Liltragel 11 06225 Clcek iCoICheck 1/152 15 Couplont Couplant botch - o t -217 KBA 01031 .43N.2ZlRnd.
Manufacturer' Serial Number Size/Shape:
261732 26132 5FCal Cal.Temp..Fin.l.Cal 95/N Check 11217
- 4-2 Thermomete r SIN Cal Temp. 1:Final Col: 1=1402 A NIA 0* 0.s incident Point: Nominal Angle: Measured Angle:
DAC Construction 2.0 MHz MSEB2 Lond. 2 Frequency: Style: Mode: Elements:
Scan Direction AX Col Reflector .5" SDH Search Unit Cable Signal Amplitude: 80%
RG-174 12Z 0 Signal Sweep: 2.40 Div Cable Type: Length: Connectors:
Signal dB: 37.6 dB Sweep 0-10 = 2.000 in Metal Path Instrument Settings Calibration Verification Ponametnics / Epoch 4 031534305 Manufacturer/Model: Serial Number.
Field Simulator Block S/N: CAL-RHOH-117 Reflector NSDH NIA 9.96eus 02283 in./lsec. 0.8-3.0MHz Zero: velocity: Norrowband Filter:
Amplitude 80% i NIA GainldB) 34.4 h-/A Auto Fullwave 2.000 in Sq. / Max Sweep (SD) 1.5 N/A Rep Rate: Rectification: Range: Pulser/Energy:
400 Ohms 0% 2.0 MHz " Dual Acceptable Linearity performed: 91 008 Damping: Reject: Frequency: Mode:
Exam Data for Weld: Nac-SE WELD OVERLAY Exam Comments / Limitations:
Configuration: Exams performed to maintain a 5% to 20% noise level.
OD 120* F 261732 Exam Surface: Exam Temp. Exam Thermometer Axial UIPST Scan cB Recordable I Exam_x Circ DNST Indications Angle Ax UPST 43.6 NRI o" Ax ... NT . 43.6 NRI
. . Exam Stort: 1W58 Exam End: 1216 Scott Erickson Initials: Examiner. Level: GE Revie~ed By Level: Dote:
/o/ A"/,/,
N/A N/A Date:
Initials: Examiner 2: Level: utilyRv Initial Col/Exam Dote: 10/412008 Page 5 of 6 ANII Revie. _,.-.- Date:
Ultrasonic Examination Indication Report .. Data Report Number: 08UT175 SHITACHI Cal Data Sheet Number D-106 Site: Fitzpatrick Procedure: ENN-NDE-9.29 / 1/N/A Weld ID: N2C-SE Drawing: MKS-003 Size: FLAT Thickness: 2.0" Exam Start: 1252 Lo Location: Toa Dead Center Wo Location: Weld Overlay Centerline Weld Width: NI/A Weld Height: NIA Exam End: 1314 Ind Angle % of I_ndication Lenth I W Distance I Metal Path. AxI Circ Upst/ I No. Used DAC I U I L Max I L2 WI WMax I W 2 1P I MP Max 1 MP2 Dnst Comments:
1 45 30 -.4 1 0 +.4 N/A _ _..5_ ý, N/A 1.538 233 . N/A
Circ CenterlineTWS=0.51" no change In thru-woll size from pre-WOR exam 108UTOi ill. Transducer
!location for flow signal tip.
ISketch
~fScott Erickson III 101412 GE Revi Level: Dote: Utility Review: Date: 1 ANII Review: Dote:'
Examiner Level: Date: Pa 6 of_6