|
---|
Category:Report
MONTHYEAR1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2023-06-29029 June 2023 Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23180A1082023-06-20020 June 2023 ANO Unit 1 SAR Amendment 31, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report 1CAN062302, Enclosure 2: ANO-1 SAR Amendment 31 - Redacted Version2023-06-20020 June 2023 Enclosure 2: ANO-1 SAR Amendment 31 - Redacted Version ML23088A2172022-12-31031 December 2022 Relief Request for Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 - Technical Report, ANP-4023NP, Revision 0, December 2022 2CAN022202, Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods2022-02-24024 February 2022 Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods 0CAN102102, Units 1 and 210 CFR 50.71(e) Report Revision 20 of the ANO Fire Hazards Analysis2021-10-0606 October 2021 Units 1 and 210 CFR 50.71(e) Report Revision 20 of the ANO Fire Hazards Analysis CNRO-2021-00023, Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L2021-10-0606 October 2021 Entergy Operations, Inc. - Supplement to CNRO-2021-00002, Basis for Concluding the Terms of Confirmatory Order EA-17-132/EA-17-153 Are Complete, Element L ML21272A3032021-09-30030 September 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Westinghouse Evinci; Micro-Reactor Tabletop Exercise Report ML21237A0512021-08-25025 August 2021 Follow-on Risk Informed Performance Based Implementation Guidance Needed for Advanced Non-Light Water Reactors ML21081A1922021-06-30030 June 2021 Enclosure - USNRC-CNSC Joint Report Concerning X-Energy's Reactor Pressure Vessel Construction Code Assessment 2CAN062103, Request for Alternative ANO2-PT-003 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping - Fifth Interval2021-06-29029 June 2021 Request for Alternative ANO2-PT-003 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping - Fifth Interval 0CAN052102, Annual 10 CFR 50.46 Report for Calendar Year 2020 Emergency Core Cooling System Evaluation Changes2021-05-10010 May 2021 Annual 10 CFR 50.46 Report for Calendar Year 2020 Emergency Core Cooling System Evaluation Changes ML21272A3382021-04-0101 April 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Versatile Test Reactor Ticap Tabletop Exercise Report ML21090A0332021-03-31031 March 2021 Historical Context and Perspective on Allowable Stresses and Design Parameters in ASME Section III, Division 5, Subsection Hb, Subpart B (ANL/AMD-21/1) ML21083A1362021-03-23023 March 2021 Completed Activities ML21083A1422021-03-22022 March 2021 Strategy 4 ML21083A1402021-03-22022 March 2021 Strategy 2 ML21083A1412021-03-22022 March 2021 Strategy 3 ML21083A1442021-03-22022 March 2021 Strategy 6 ML21083A1382021-03-22022 March 2021 Rulemaking ML21083A1432021-03-22022 March 2021 Strategy 5 ML21083A1372021-03-22022 March 2021 NEIMA Reporting ML21083A1392021-03-22022 March 2021 Strategy 1 ML21014A2672021-01-14014 January 2021 Preapplication Engagement to Optimize Application Reviews January 12 Version - Copy 1CAN032001, Supplemental Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values2020-03-19019 March 2020 Supplemental Information Related to License Amendment Request to Revise Loss of Voltage Relay Allowable Values 0CAN121901, Summary of Lost Specimens Investigation Report2019-12-0303 December 2019 Summary of Lost Specimens Investigation Report ML18215A1782018-06-30030 June 2018 WCAP-18169-NP, Rev 1, Arkansas Nuclear One Unit 2 Heatup and Cooldown Limit Curves for Normal Operation. ML17214A0292018-02-12012 February 2018 Staff Assessment of Flooding Focused Evaluation (CAC Nos. MF9809 and MF9810) ML17291A0092017-10-26026 October 2017 Staff Assessment Regarding Program Plan for Aging Management for Reactor Vessel Internals (CAC No. MF8155; EPID L-2016-LRO-0001) ML17236A1792017-08-22022 August 2017 Arkansas, Units 1 and 2, ANO Emergency Plan On-Shift Staffing Analysis Report, Revision 2 0CAN081703, Document 51-9257562-001, Revision 1, Arkansas Nuclear One Hfe - High Frequency Confirmation Report2017-08-16016 August 2017 Document 51-9257562-001, Revision 1, Arkansas Nuclear One Hfe - High Frequency Confirmation Report ML17167A0832017-06-28028 June 2017 Arkansas Nuclear One, Unit 2 - Review of Commitment Submittal for License Renewal Regarding Nickel-Based Alloy Aging Management Program Plan (CAC No. MF8154) 0CAN061701, Transmittal of 10 CFR 50.71(e) Report, Revision 17 of the ANO Fire Hazards Analysis2017-06-0707 June 2017 Transmittal of 10 CFR 50.71(e) Report, Revision 17 of the ANO Fire Hazards Analysis 0CAN051704, Engineering Report No. CALC-ANOC-CS-14-00017, Rev 0, 2017 Focused Evaluation for External Flooding at Arkansas Nuclear One.2017-03-13013 March 2017 Engineering Report No. CALC-ANOC-CS-14-00017, Rev 0, 2017 Focused Evaluation for External Flooding at Arkansas Nuclear One. 2CAN011703, Submittal of Additional Protocol Report2017-01-26026 January 2017 Submittal of Additional Protocol Report ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 0CAN121602, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information Per Nuclear Energy Institute (NEI) 12-06, Appendix H, Revision 2, H.4.3 Path 32016-12-30030 December 2016 Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information Per Nuclear Energy Institute (NEI) 12-06, Appendix H, Revision 2, H.4.3 Path 3 ML17003A2902016-12-20020 December 2016 Areva, Inc. - Engineering Information Record - Arkansas Nuclear One HFE-High Frequency Confirmation Report ML16365A0272016-10-31031 October 2016 ANP-3486NP, Revision 0, MRP-227-A Applicant/Licensee Action Item 6 Analysis for Arkansas Nuclear One Unit 1 (ANO-1). ML16293A5842016-09-30030 September 2016 WCAP-18166-NP, Revision 0, Analysis of Capsule 284 from the Entergy Operations, Inc. Arkansas Nuclear One, Unit 2 Reactor Vessel Radiation Surveillance Program. 1CAN091601, Submittal of Initial Examination Completion of Post-Examination Analysis2016-09-0101 September 2016 Submittal of Initial Examination Completion of Post-Examination Analysis ML16202A1672016-07-0505 July 2016 Report 1500227.401, PWR Internals Aging Management Program Plan. ML16147A3242016-05-31031 May 2016 ANP-3417NP, Rev. 1, MRP-227-A Applicant/Licensee Action Item #7 Analysis for Arkansas Nuclear One, Unit 1. ML16004A1792015-12-31031 December 2015 Attachment 2, ANP-3418NP, Revision 0, Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2) Licensing Report. (Non-Proprietary) ML15278A0242015-09-28028 September 2015 Attachment 2, Areva Document ANP-3417NP, Revision 0, MRP-227-A Applicant / Licensee Action Item No. 7 Analysis for Arkansas Nuclear One, Unit 1 (Non-Proprietary), Attachment 3, Affidavit, and Attachment 4, List of Commitments ML15099A1522015-04-16016 April 2015 Review of Spring 2014 Steam Generator Tube Inspection Report, Inspection During Refueling Outage 2R23 ML15071A0552015-03-31031 March 2015 ANP-3300Q2NP, Revision 0, Response to Request for Additional Information on Reactor Coolant System Pressure/Temperature and Low Temperature Overpressure Protection System Limits to 54 EFPY for Arkansas Nuclear One, Unit 1. ML15086A0242015-03-25025 March 2015 ANP-3300Q3NP, Revision 0 to Response to Request for Additional Information on Reactor Coolant System Pressure/Temperature and Low Temperature Overpressure Protection System Limits to 54 EFPY for Arkansas Nuclear One, Unit 1 (Non-Proprietary ML15043A1032015-02-10010 February 2015 Areva Document ANP-3383NP, Response to Request for Additional Information for the Reactor Pressure Vessel Internals Aging Management Program Plan for Arkansas Nuclear One Unit 1 ML15041A0742015-02-0606 February 2015 ANP-3300Q1NP, Rev. 0, Response to Request for Additional Information on Reactor Coolant System Pressure/Temperature and Low Temperature Overpressure Protection System Limits to 54 EFPY for Arkansas Nuclear One, Unit 1, Attachment 2 to 1CAN0 2023-06-29
[Table view] Category:Technical
MONTHYEAR1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2023-06-29029 June 2023 Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation ML23180A1082023-06-20020 June 2023 ANO Unit 1 SAR Amendment 31, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report 1CAN062302, Enclosure 2: ANO-1 SAR Amendment 31 - Redacted Version2023-06-20020 June 2023 Enclosure 2: ANO-1 SAR Amendment 31 - Redacted Version ML23088A2172022-12-31031 December 2022 Relief Request for Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 - Technical Report, ANP-4023NP, Revision 0, December 2022 2CAN022202, Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods2022-02-24024 February 2022 Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods 0CAN102102, Units 1 and 210 CFR 50.71(e) Report Revision 20 of the ANO Fire Hazards Analysis2021-10-0606 October 2021 Units 1 and 210 CFR 50.71(e) Report Revision 20 of the ANO Fire Hazards Analysis ML21272A3032021-09-30030 September 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Westinghouse Evinci; Micro-Reactor Tabletop Exercise Report ML21237A0512021-08-25025 August 2021 Follow-on Risk Informed Performance Based Implementation Guidance Needed for Advanced Non-Light Water Reactors ML21081A1922021-06-30030 June 2021 Enclosure - USNRC-CNSC Joint Report Concerning X-Energy's Reactor Pressure Vessel Construction Code Assessment 2CAN062103, Request for Alternative ANO2-PT-003 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping - Fifth Interval2021-06-29029 June 2021 Request for Alternative ANO2-PT-003 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping - Fifth Interval ML21272A3382021-04-0101 April 2021 Technology Inclusive Content of Application Project (Ticap) for Non-Light Water Reactors Versatile Test Reactor Ticap Tabletop Exercise Report ML21090A0332021-03-31031 March 2021 Historical Context and Perspective on Allowable Stresses and Design Parameters in ASME Section III, Division 5, Subsection Hb, Subpart B (ANL/AMD-21/1) ML18215A1782018-06-30030 June 2018 WCAP-18169-NP, Rev 1, Arkansas Nuclear One Unit 2 Heatup and Cooldown Limit Curves for Normal Operation. ML17236A1792017-08-22022 August 2017 Arkansas, Units 1 and 2, ANO Emergency Plan On-Shift Staffing Analysis Report, Revision 2 0CAN081703, Document 51-9257562-001, Revision 1, Arkansas Nuclear One Hfe - High Frequency Confirmation Report2017-08-16016 August 2017 Document 51-9257562-001, Revision 1, Arkansas Nuclear One Hfe - High Frequency Confirmation Report 0CAN061701, Transmittal of 10 CFR 50.71(e) Report, Revision 17 of the ANO Fire Hazards Analysis2017-06-0707 June 2017 Transmittal of 10 CFR 50.71(e) Report, Revision 17 of the ANO Fire Hazards Analysis 0CAN051704, Engineering Report No. CALC-ANOC-CS-14-00017, Rev 0, 2017 Focused Evaluation for External Flooding at Arkansas Nuclear One.2017-03-13013 March 2017 Engineering Report No. CALC-ANOC-CS-14-00017, Rev 0, 2017 Focused Evaluation for External Flooding at Arkansas Nuclear One. ML16365A0272016-10-31031 October 2016 ANP-3486NP, Revision 0, MRP-227-A Applicant/Licensee Action Item 6 Analysis for Arkansas Nuclear One Unit 1 (ANO-1). ML16293A5842016-09-30030 September 2016 WCAP-18166-NP, Revision 0, Analysis of Capsule 284 from the Entergy Operations, Inc. Arkansas Nuclear One, Unit 2 Reactor Vessel Radiation Surveillance Program. ML16202A1672016-07-0505 July 2016 Report 1500227.401, PWR Internals Aging Management Program Plan. ML16004A1792015-12-31031 December 2015 Attachment 2, ANP-3418NP, Revision 0, Arkansas Nuclear One Unit 1 Reactor Vessel Internals License Renewal Scope and MRP-189, Revision 1 Comparison (MRP-227-A Action Item 2) Licensing Report. (Non-Proprietary) ML15278A0242015-09-28028 September 2015 Attachment 2, Areva Document ANP-3417NP, Revision 0, MRP-227-A Applicant / Licensee Action Item No. 7 Analysis for Arkansas Nuclear One, Unit 1 (Non-Proprietary), Attachment 3, Affidavit, and Attachment 4, List of Commitments ML15071A0552015-03-31031 March 2015 ANP-3300Q2NP, Revision 0, Response to Request for Additional Information on Reactor Coolant System Pressure/Temperature and Low Temperature Overpressure Protection System Limits to 54 EFPY for Arkansas Nuclear One, Unit 1. ML15041A0742015-02-0606 February 2015 ANP-3300Q1NP, Rev. 0, Response to Request for Additional Information on Reactor Coolant System Pressure/Temperature and Low Temperature Overpressure Protection System Limits to 54 EFPY for Arkansas Nuclear One, Unit 1, Attachment 2 to 1CAN0 ML14330A2502014-11-30030 November 2014 Attachment 4 to 1CAN111401, ANP-3300, Revision 1, Pressure-Temperature Limits at 54 Efpy. ML14241A2412014-06-30030 June 2014 ANP-3300, Arkansas Nuclear One (ANO) Unit 1 Pressure-Temperature Limits at 54 EFPY, Attachment 4 ML14139A3812014-05-14014 May 2014 CALC-ANO2-CS-12-00002, Revision 1, Flooding Walkdown Report for Resolution of Fukushima Near Term Task Force Recommendation 2.3, Attachment 2 to 0CAN051402 ML14139A3802014-05-14014 May 2014 CALC-ANO1-CS-12-00003, Revision 1, Flooding Walkdown Report for Resolution of Fukushima Near Term Task Force Recommendation 2.3, Attachment 1 to 0CAN051402 1CAN051401, Time-Limited Aging Analysis Regarding Reactor Vessel Internals Loss of Ductility for Arkansas Nuclear One, Unit 1 at 60 Years Arkansas Nuclear One Unit 12014-05-0606 May 2014 Time-Limited Aging Analysis Regarding Reactor Vessel Internals Loss of Ductility for Arkansas Nuclear One, Unit 1 at 60 Years Arkansas Nuclear One Unit 1 ML14141A5552014-05-0101 May 2014 Attachment 1 to 1CAN051403 PWR Internals Aging Management Program Plan ML14007A4592014-02-25025 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14045A1562014-02-20020 February 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Arkansas Nuclear One, Units 1 and 2, TAC Nos.: MF0942 and MF0943 1CAN091301, Updated Seismic Walkdown Report2013-09-30030 September 2013 Updated Seismic Walkdown Report ML13213A2702013-07-22022 July 2013 Stator Drop Root Cause Evaluation Report CR-ANO-C-2013-00888, Rev. 0, Unit 1 Main Turbine Generator Stator. ML13113A2182013-04-23023 April 2013 Technical Letter Report, PNNL Evaluation and Modeling of Licensee'S Alternative for Volumetric Inspection of Dissimilar Metal Butt Welds at Arkansas Nuclear One ML12334A0092012-11-19019 November 2012 CALC-ANO1-CS-12-00003, Flooding Walkdown Submittal Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Flooding, Attachment 1 to 1CAN111202 ML12334A0072012-11-19019 November 2012 CALC-ANO2-CS-12-00002, Rev. 0, Arkansas Nuclear One Unit 2 Flooding Walkdown Submittal Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Flooding. ML12342A0522012-11-16016 November 2012 Arkansas, Unit 2, Attachment 1 - Engineering Report CALC-ANO2-CS-12-00001, Rev. 0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, and Attach. 2, List of Regulatory Commitments, Cover - 1CAN111201, Engineering Report CALC-ANO1-CS-12-00002, Rev. 0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Pages 1 Through 3312012-11-16016 November 2012 Engineering Report CALC-ANO1-CS-12-00002, Rev. 0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Pages 1 Through 331 2CAN111201, Arkansas, Unit 2, Attachment 1 - Engineering Report CALC-ANO2-CS-12-00001, Rev. 0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page 364 of 533 Through End2012-11-16016 November 2012 Arkansas, Unit 2, Attachment 1 - Engineering Report CALC-ANO2-CS-12-00001, Rev. 0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page 364 of 533 Through End ML12342A2202012-11-16016 November 2012 Engineering Report CALC-ANO1-CS-12-00002, Rev. 0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Pages 1 Through 331 1CAN111201, Engineering Report CALC-ANO1-CS-12-00002, Rev. 0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Pages 332 Through 5602012-11-16016 November 2012 Engineering Report CALC-ANO1-CS-12-00002, Rev. 0, Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Pages 332 Through 560 ML1200903102012-01-0909 January 2012 Email Apparent Cause Evaluation Report, Final ACE for Tube to Tube Wear ML0832603222008-11-12012 November 2008 Letter to Elmo E. Collins from FEMA, Region IV, Denton, Texas Dated 11-12-2008 Subj: ANO Radiological EP Final Report for ANO ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 2CAN040801, Summary of Design and Analyses of Weld Overlays for Hot Leg Nozzle Dissimilar Metal Welds for Alloy 600 Mitigation at ANO-22008-04-0202 April 2008 Summary of Design and Analyses of Weld Overlays for Hot Leg Nozzle Dissimilar Metal Welds for Alloy 600 Mitigation at ANO-2 ML0713703522007-05-0808 May 2007 Stress Analysis Summary Report, Pressurizer and Reactor Coolant Hot Leg Weld Overlays ML0710002572007-03-26026 March 2007 Attachment 5 - HI-2063601, Holtec Licensing Report for ANO Unit 2 Partial Rerack, (non-propriety) ML0622204422006-08-10010 August 2006 Holtec Report HI-2022867 Spent Fuel Pool Racks Modifications with Poison Material Inserts in ANO Unit 1 for Entergy. ML0522303712005-08-0808 August 2005 Attachment 2, HI-2043262NP, Rev 0 - Part 50 Criticality Analysis of the MPC-32 for ANO Unit 2, Holtec Project No: 1104, Report Class Safety Related 2023-06-29
[Table view] |
Text
Enclosure 2 2CAN010402 Wesdyne Report WDI-TJ-001-02-NP, Rev 02, Detection of Reactor Head Base Metal Loss from Inside the CRDM (Non-Proprietary)
F WESDyln N
- RN AT I ON AL Trhe: I Detection of Reactor Head Base Metal Loss from Inside the CRDM Penetration Key Words: Date: Document Number:
Technical Justification I 1I3 WDI-TJ-001-02-NP Rev2 1 Westinghouse Non-Propetay Class 3 Page 1 of 20
Fq wEsDynE I1 T P N A*1 10 N AL Document Number. WDT-TJ-O0-02-NP Rev. 2 Page 2 of 20 Detection of Reactor Head Base Metal Loss from Inside the CRDM Penetration Introduction In February of 2002 significant loss of the base metal of the reactor head was discovered at David Besse Nuclear Power Station. The material loss was the result of Boric Acid corrosion of the carbon steel. The particular region of the head where the corrosion had taken place was not identified by visual inspection.
ANO has limited access to the outside surface of the head. As such a program was instituted to develop an inspection that can detect the presence of the carbon steel base metal of the head adjacent to a CRDM penetration The available examination surface is the inside of a CRDM penetration. The technique chosen as having the highest probability of success was a low frequency eddy current technique.
Technique Description The CRDM penetrations are of a non- magnetic NCrFe alloy and the head base metal is a magnetic low alloy carbon steel. The magnetic properties associated with the head base metal offer a means to determine its presence adjacent to the penetration. The simplest inspection to implement for detecting the presence of magnetic is with the use of eddy current techniques.
Eddy current techniques rely on an Electro-magnetic field generated by a coil to interact with a part under test. This applied field generates eddy current flow in the part and this in turn alters the electrical impedance the coil. The Electro-magnetic properties of the part determine the strength and type of interactive response experienced by the coil. For the detection of the base metal of the head adjacent to a CRDM penetration, a coil configuration operates at a low frequency is required to assure that the coil's Electro- magnetic field extends through the CRDM penetration tube. The probe selected for its compatibility with the existing scanner and eddy current instrumentation is a low frequency, driver/pick-up coil probe. In this probe, the driver and pick-up coils have coincident axes that are placed such that they are oriented radially with respect to the penetration.
To perform the inspection, the eddy current probe is mounted into a tool that scans the probe on the ID surface of the penetration over an extent coincident with the head base metal. Figure I shows the probe mounted in a sled on the scanning tool. As the probe is scanned over the area of interest a loss in the base metal is detected as a change in the response of the coil.
Technique Evaluation After a series of bench top tests, the eddy current probe selected for evaluation is a 3 inch diameter driver/pick-up probe (DP-750-SP). The probe was operated at an inspection frequency of 200 Hz. The
MWESDynE I NTEAN NATIQNAL Document Number: WDI-TJ-001-02-NP Rev. 2 Page 3 of 20 probe evaluation was conducted with the probe mounted in a 7010 manipulator. The evaluations were conducted using a head from cancelled reactor located at the Westinghouse Waltz Mills and machined samples. These tests were aimed at understanding the parameters governing the response to the material loss and the "noise" associated with field implementation. The scan increments, reference sensitivities etc. were in accordance with the parameters in the procedure WDI-ET-005.
Figure 2 shows the samples that were machined for this evaluation. They include two material loss morphologies. The first is uniform loss that is simulated by rings cut into the inside of a hollow cylinder. The second is localized loss that is simulated by axially oriented grooves cut into the inside of a half-cylindrical section. Table I lists the nominal dimensions for all of these samples. The samples in Table I were machined to fit the CRDM penetration tube R 6517-2 with an outside diameter of 4.10 inches and a wall thickness of 0.685 inch.
Table I Simulated loss dimensions in machined samples Sample Axial Length (in) Circumferential Radial Depth (in)
_____ _I_ Length (in) l a c..e SK-WB020408- 1/A I SK-WB020408- I/B SK-WB020408-2/A SK-WB020408-2/B SK-WB020408-3/B SK-WB020408-2/A As a further check on inspection sensitivity an additional sample was fabricated from a section of pipe that was bored to fit over a penetration of 4.150 inch diameter. e resulting tube had an a dcie approximately 1/4 inch thick wall into which two through holes oe rwere drilled (Figure 3).
Tests using the machined samples were performed either on a test stand or with the samples surrounding a penetration tube on the head. Figure 4 shows two of the half cylinder samples mounted in the test stand. Figure 5 shows the ring sample (SK-WB020408-3) mounted on a penetration on the head.
Results Machined Samples The first tests performed were designed to determine the sensitivity of the inspection to a loss of carbon steel adjacent to a penetration. In these tests the half cylinder sample sections were clamped together and placed over the penetration in the test stand. Figure 6 shows the results of the test. Arrows in the figure indicate the location where responses from the various groves are anticipated. As can be seen in
q wEsDynE INTERNATIONAL Document Number: WDI-TJ-001-02-NP Rev. 2 Page 4 of 20 the figure only the C c has a poor detection resolution in the C-scan presentation. Additional detection resolution (S/N ratio > 3) is achievable with evaluation of the Lissajous signals the response from the 1/4 inch wide by 1/8-inch deep, 3/16 inch deep, 3/16 inch deep, and 1/44 inch deep groove (SK-WB020408- l/B, 2/A, and 2/B). Only the shallowest
[
- J1produced a weak signal response (S/N ratio < 1) and has remain in practically undetectable signal response range. From these results it was concluded that the total volume of material lost is governing the signal responses.
A supplemental test was conducted to evaluate the sensitivity of the loss response to the area presented to the probe. Two of the half sections were mounted end to end on the test stand. The two sections were then separated at various increments. Measurements of the coil response associated with the gap between the samples were taken. This test duplicates the response of a very long deep loss of various widths. Figure 4 shows the position of the two samples at their maximum separation. The results of these measurements are found in Figure 7. As expected, the ability to detect the presence of the gap falls dramatically, as the width (area) becomes small. As the gap width increases the change in response saturates when ( I.
The final test performed with the machined samples on the test stand determined the dependence of the coil response on the radial depth of material loss. To simulate this type of loss, shims were placed under the upper half section shown in Figure 3. This gives an approximation to the rings machined into Sample SK-WB020408-3 (A and B) but with more flexibility in terms of radial dimension. The measurements consisted of taking the difference in the amplitude of the vertical component of the eddy current response at approximately 1.5 inches within each sample on the same scan line. The measurements from four scan lines were then averaged for the final result. The results of these measurements are found in Figure 8. As a check on the validity of the approach the response of the two grooves in Sample SK-WB020408-3 (A and B) displayed in Figure 9 are shown in Figure 8 as the triangles.
James Port Head Inspections were performed on six penetrations in the James Port reactor head. This head is from a cancelled plant. All of the displays for these inspections can be found in Appendix A. In general the variations seen in the head inspection are smaller than the variations observed in the machined samples.
This fact allows for the counter bore at the top of the head to be observed. The counter bore is a radial opening of the hole in the head though which the penetration is inserted. The counter bore extends over the portion of the hole that is on the "high" side down to the "low" side. Figure 10 shows the results from Penetration 26 with the counter bore obvious in the display.
A further test was conducted where the 1/4 inch thick tube sample with the two holes through the wall was slipped over a penetration that had been cut-off. The results of this inspection are found in Figure
- 11. Again as with the counter bore the presence of the(
I a.c.eI Discussion
N WESDyvnE IN II AT I L AI Document Number: WDI-TJ-001-02-NP Rev. 2 Page 5 of 20 In reviewing the results the variations in response observed in the machined samples figure 9 is significantly (two times) higher than that observed in the head Figure 10. The origin of the variation has not been definitively identified but is believed to originate with a combination of material variability with in the penetration tube being used in the test stand and residual magnetic fields within the samples. These variations limit the detection of low level loss. Without these variations the signal to noise should improve allowing the detection level in the head to also improve over that observed in the samples.
The penetrations on the head are slightly smaller in diameter (4.0 inch diameter) than the penetration used in the test stand so that the pipe sample had a gap between the OD of the penetration and the inside of the pipe. This may have contributed to thel a Bench tests had observed a response for the hole but as expected, at smaller amplitude than the responses of the 1-inch hole.
The results associated with a variation in the gap width (Figure 7) suggest that quantitative measurement of the material loss is indeed possible so long as the area of loss is (
- ) Further these results suggest that even if the area of loss is smaller, quantitative measurement of the loss may be possible by correcting the measurements (Figure 8) with a factor derived from the gap dependence (Figure 7).
The extension of the inspection to a CRDM penetration tube of slightly different dimensions should not present a significant problem. During this evaluation penetration diameters from 4.0 to 4.15 inches in diameter were considered. As the diameter and wall thickness of a penetration decrease the sensitivity of the inspection will improve and the curve in Figure 8 will become conservative.
Summary These tests found that the key parameter determining the response of the inspection is the volume of the loss presented to the probe. Three out of fou{
a-c e 1 Further the tests on the head found that the material noise was lower than that of the machined samples and that the counter bore at the top of the head could be readily detected. At present the technique is capable of estimating the amount of material lost, so long as it extends over a "wide" area. The measurement is based upon a calibration curve developed by displacing a ring section radially from the OD of the CRDM penetration. For assessing small areas of loss additional work will be required.
References
- 1. WDI -ET-005, Rev 0, "RPV Head CRDM Penetration EC Examination for Wastage Detection"
! WESDyvnE IN rso1 N AT I ONAL Document Number: WDI-TJ-001-02-NP Rev. 2 Page 6 of 20 Figure I Eddy current probe mounted in the sled of a 7010 manipulator.
i I
-- EE N i I i I) t
'74.
T i
I' I x i
FM WE$DyflE I N? £ N AT IONA Document Number: WDI-TJ-001-02-NP Rev. 2 Page 7 of 20 CRDM Penetration Tube
'PA"Q m -I . II-.1 Figure 2 Machined samples used in this evaluation. The samples SK-WB08-1 through - 4 are shown clamped together. The penetration tube was used in the test stand.
Figure 3 The tube sample with the through wall holes mounted on the penetration tube. In front is the groove Sample SK-WB08-04.
MWESDynE INT ER NATI 0 NAL L
Document Number: WDI-TJ-001-02-NP Rev. 2 Page 8 of 20 Ies
]Test Stad"' 0 Penetraubon Tube i Figure 4 Half Cylinder Samples mounted on test stand. The samples are shown mounted for the "Gap" dependence study and are at the 2.0-inch separation.
M WESDynE INTI O NAT I0 NAL Document Number: WDI-TJ-001-02-NP Rev. 2 Page 9 of 20 Figure 5 James Port Head with calibration ring and ring sample in position.
I N rER N AT I OiA Document Number: WDI-TJ-001-02-NP Rev. 2 Page 10 of 20 Ljcm
, I I"-A- ,
II/ I 4 I 1) r.j. I-M, S" I, il-.- - A, Ifl,4 H Rat -o , .,fi- I I,-,: ol.3- i III 0. 00 If Fw, "I" Wp, 1.... . . V- I
. I i Aft tiIX i
A.-PO f
~~44'~*"
IL -- t 1 'I'Ut .s tI I
. .... .......... ....... ....... ..= _ _ ...
- _ t !.'~~-
I
_r w_~~~~~~
I ~~~~~~~~~~~~~~~~~~~~~~~~~
I 4- .== I H(
S -n'h i Ai0,00"Wo _ i~~ w ~ ~~~~~
iwii. hQC!
III SI I ~~0 3
_j -
Figure 6 Results from the inspection of the Half Cylinder Samples mounted on the test stand. Arrows indicate location where groove response should be located in the sample identified by the number.
- 1) SK-WB020408-1/A, 2) SK- WB020408-1/B, 3) SK- WB020408-2/A, 4) SK- WB020408-2/B
! WESDyfnE IMNl R PIAT)ONALM Document Number: WDI-TJ-001-02-NP Rev. 2 Page 11 of 20 a.c.e Figure 7 Influence of the width on the reduction in the eddy current response of a long deep simulated loss. Note that the ducton in the response due to the gap saturates when the width is(
Tua!c~~~~~~~~~~~~~~~e
~~~~~~~~~~~~~~ a~c~e I ~ ~ ~ a~~
Figure 8 pdence of the reduction in the eddy current response on the radial loss of the tal. The squares are of placing shims between the OD of the penetration tube and the ins half cylinder.
The triangles are measurements performed on Sample SK-WB08-5 (A and B).
F WESDynE Document Number: WDI-TJ-001-02-NP Rev. 2 Page 12 of 20 a.c.e Figure 9 Eddy current response from Circumferential Rings SK- WB020408-3/A and B.
F WESiwnE IN T E Ft N AT I O N AL A Document Number: WDI-TJ-001-02-NP Rev. 2 Page 13 of 20 Axial Length )f RPVH's Top
,~~~~~
4 A ol - 1 " v Counter-bore Geometry (a I I I W. 3~
i i
'a It',' !.
An..)'I 4;.9 '-
An,"-1.
r I).
.5." '^ '
An,>.
a, i, ,
A:.') -I 7- - - J...- .
-` M .,.s - ,
A_, A=. A, 4.....
Liz, .lli A.....
- \,4 -I; Jo,.,-I
..M w
.. I ha,...
-Frequency 1 Probe 2-
.5 26 1.0 1.0 t 7 7 . . - , 4" Ia- ,1 I I l. I.
Amplitude Scale Cursor Width VH Ratio TimeScale Mag 23.0 ECU 0.00 V Ang 268 deg - Horz + + Vert Figure 10 Eddy current responses from inspection of CRDM Penetration 26 in the James Port head. The arrows identify the counter bore region in both the C-Scan and strip chart displays.
007-
! WESDynE IN T R AT? IC MAL Document Number: WDI-TJ-001-02-NP Rev. 2 Page 14 of 20 axc.e Figures 11 Eddy current responses from %/inch thick pipe sample with through wall holes placed on a cut penetration on the head. The response from the( n P i
F WESDynE INTl6 P MAI0 kAL Document Number WDI-TJ-001-02-NP Rev. 2 Page 15 of 20 Appendix A Graphical displays of data obtained on the James Port Head. Note all presentations are at the same sensitivity level. a.c.e Figure Al Eddy Current Responses from Penetration 2 of the James Port Head.
(Higher ECU represents the presence of carbon steel adjacent to the penetration.)
F WESDynE I NTl NATIN AL Document Number: WDI-TJ-001-02-NP Rev. 2 Page 16 of 20 a.c.e Figure A-2 Eddy Current Responses from Penetration 3 of the James Port Head. (Higher ECU represents the presence of carbon steel adjacent to the penetration.)
% wEsDynE INTlI NAT INAL Document Number: WDI-TJ-001-02-NP Rev. 2 Page 17 of 20
.c.e Figure A-3 Eddy Current Responses from Penetration 4 of the James Port Head. (Higher ECU represents the presence of carbon steel adjacent to the penetration.)
FRIWESPYnE INTER N A? 0AIO Document Number: WDI-TJ-001-02-NP Rev. 2 Pawe 18 of 20 Figure A-4 Eddy Current Responses from Penetration 22 of the James Port Head. (Higher ECU represents the presence of carbon steel adjacent to the penetration.)
! WESDyvnE I NT9 A NATI ONAL Document Number: WDI-TJ-001-02-NP Rev. 2 Page 19 of 20 a:ce Figure A-5 Eddy Current Responses from Penetration 26 of the James Port Head. (Higher ECU represents the presence of carbon steel adjacent to the penetration.)
! WEsDyvnE IMT I AMAT I ONALL Document Number: WDI-TJ-001-02-NP Rev. 2 Page 20 of 20 a.c.e Figure A-6 Eddy Current Responses from Penetration 29 of the James Port Head. (Higher ECU represents the presence of carbon steel adjacent to the penetration.)