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| #REDIRECT [[L-11-148, Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2.4]] | | {{Adams |
| | | number = ML111600250 |
| | | issue date = 06/09/2011 |
| | | title = Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2.4 |
| | | author name = Harden P A |
| | | author affiliation = FirstEnergy Nuclear Operating Co |
| | | addressee name = |
| | | addressee affiliation = NRC/NRR, NRC/Document Control Desk |
| | | docket = 05000412 |
| | | license number = NPF-073 |
| | | contact person = |
| | | case reference number = L-11-148 |
| | | document type = Letter, Report, Miscellaneous |
| | | page count = 8 |
| | }} |
| | |
| | =Text= |
| | {{#Wiki_filter:FENOC ........ FirstEnergy Nuclear Operating Company Paul A. Harden Site Vice President June 9, 2011 L-11-148 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 |
| | |
| | ==SUBJECT:== |
| | Beaver Valley Power Station, Unit No.2 Docket No. 50-412, License No. NPF-73 Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 724-682-5234 Fax: 724-643-8069 Steam Generator Tube Inspection Report -Technical Specification 5.6.6.2.4 In accordance with Technical Specification 5.6.6.2.4, FirstEnergy Nuclear Operating Company hereby submits a report containing tube inspection results for Beaver Valley Power Station, Unit No.2, steam generators. |
| | The enclosed report provides information required by the technical specification that was obtained during inspections conducted during the spring 2011 refueling outage. There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Fleet Licensing, at (330) 761-6071. |
| | Paul A. Harden |
| | |
| | ==Enclosure:== |
| | |
| | Unit #2 -2R15 Steam Generator F* (F Star) Report cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative FIRST ENERGY NUCLEAR OPERATING COMPANY Technical Services Engineering Department Nuclear Engineering Programs Section Issue Date: May 13, 2011 |
| | |
| | ==Subject:== |
| | Unit #2" 2R15 Steam Generator F* (F Star) Report Prepared by: |
| | __ SG Program Owner, Date: 0 s I , 3/ II Reviewed by: Jeff <<3 --' Date: |
| | Approved by: Doug Reeves o<J..--t.- |
| | ==-Date: S-/I?:> / 1/ Manager, Technical Services UNIT #2 -2R15 STEAM GENERATOR F* (F STAR) REPORT Pursuant to Specification 5.6.6.2.4 of the Technical Specifications, the following information is to be transmitted to the NRC within 90 days after entering MODE 4 following an outage in which the F* (F Star) methodology was implemented. |
| | For 2R 15, MODE 4 occurred on April 7th, 2011. Therefore, this information must be submitted to the NRC on or before July 6, 2011. Per Specification 5.6.6.2.4, the following information is to be submitted and is discussed within this document: (a) The total number of indications, the location of each indication, the orientation of each indication, the severity of each indication and whether the indications initiated from the inside or outside surface, (b) The cumulative number of indications detected in the tubesheet region as a function of elevation within the tubesheet, (c) The projected end-of-cycle accident induced leakage from tubesheet indications. |
| | During the 2R 15 outage, the Plus Point probe was utilized to inspect the top of tubesheet region. The 2R 15 inspection scope was 100% of the inservice hot leg tubes in all three steam generators (SG's) plus a 20% random sample of the inservice cold leg tubes in SG "A". The inspection distance in either leg was from 6.0 inches above the top of tubesheet to 3.0 inches below the top of tubesheet and bounds the required F* examination distance (Le. the expanded portion of the tube below the bottom of roll expansion transition) of 2.22 inches below the bottom of the expansion transition. |
| | A small number of tubes (10 total in the hot leg of all 3 SG's and 4 in SG "A" cold leg) have roll expansion transitions at lower than nominal elevations. |
| | These particular tubes were inspected to a depth of 5.0 inches below the top of tubesheet to ensure that the F* distance was adequately examined. |
| | As seen from the information contained within, the morphology for the vast majority of the indications reported from the hot leg tubesheet region is believed to be attributed to circumferentially oriented outside diameter stress corrosion cracking (ODSCC). This is based on signal recognition and location of the reported indications. |
| | All ODSCC indications observed were plugged upon detection. |
| | All top of tubesheet circumferential indications were stabilized prior to installing the hot leg plug. None of the indications that were removed from service during 2R15 represented a (Cycle 15) leakage potential at postulated main steam line break (MSLB) conditions. |
| | The information provided on the following pages summarizes the degradation observed during the 2R15 tubesheet region examinations. |
| | The data has been analyzed utilizing the 300 kHz channel from the Plus Point probe. This provides the most accurate sizing technique and is used for assessing the severity of the indications. |
| | Page 2 of7 SG "A" Hot Leg Tubesheet: |
| | Twenty tubes were plugged for indications reported during the hot leg tubesheet region examination. |
| | Of these tubes; nineteen tubes were reported with either single or multiple circumferential OOSCC indications located at or slightly below the top of tubesheet and one tube was reported with single axial OOSCC indication located above the top of tubesheet. |
| | SG "A" Cold Leg Tubesheet: |
| | No indications were reported during the 20% random sample inspection of the cold leg tubesheet region. 2RCS-SG21A 2R15 Tubesheet Indications Indication Location Orientation** |
| | SG Row Column Elevation* A 6 50 TSH -0.12" A 8 38 TSH -0.03" A 8 57 TSH -0.09" A 9 23 TSH -0.08" A 11 38 TSH -0.14" A 12 37 TSH -0.15" A 12 41 TSH -0.09" A 12 42 TSH +0.00" A 13 44 TSH -0.07" A 19 55 TSH -0.20" A 20 21 TSH -0.13" A 25 33 TSH -0.08" A 27 72 TSH -0.05" A 33 33 TSH -0.06" A 38 49 TSH +0.49" A 40 43 TSH -0.05" A 41 49 TSH -0.10" A 42 42 TSH -0.07" A 42 45 TSH -0.01" A 43 47 TSH -0.01" |
| | * TSH -Top of Tubesheet (Hot Leg) ** MCI -Multiple Circumferential Indications SAl -Single Axial Indication SCI -Single Circumferential Indication |
| | *** Reported Using the 300 kHz Plus Point Coil Volts SCI 0.12 SCI 0.18 SCI 0.16 SCI 0.21 SCI 0.13 SCI 0.20 SCI 0.13 SCI 0.17 SCI 0.19 MCI 0.13 SCI 0.14 SCI 0.24 SCI 0.20 MCI 0.17 SAl 0.12 MCI 0.27 SCI 0.16 SCI 0.17 SCI 0.07 SCI 0.08 Page 3 of7 Severity*** |
| | Axial Length 0.17" Initiation Arc Surfacel Projected Length Degradation Leakage 65 u OOSCC 0 110 u OOSCC 0 123 0 OOSCC 0 132 0 OOSCC 0 33 u OOSCC 0 59 u OOSCC 0 82 u OOSCC 0 69 u OOSCC 0 69 0 OOSCC 0 190 u OOSCC 0 98 u OOSCC 0 91 u OOSCC 0 155 0 OOSCC 0 130 u OOSCC 0 OOSCC 0 229 u OOSCC 0 50 u OOSCC 0 106 u OOSCC 0 107 0 OOSCC 0 34 u OOSCC 0 SG "8" Hot Leg Tubesheet: |
| | Twenty four tubes were plugged for indications reported during the hot leg tubesheet region examination. |
| | Of these tubes; twenty one tubes were reported with either single or multiple circumferential ODSeC indications located at or slightly below the top of tubesheet and three tubes were reported with single axial ODSee indications located above the top of tubesheet. |
| | 2RCS-SG21B 2R15 Tubesheet Indications Indication Location Orientation** |
| | SG Row Column Elevation* |
| | B 7 41 TSH+O.OO" B 8 32 TSH -0.01" B 8 54 TSH -0.04" B 9 54 TSH -0.12" B 11 19 TSH +0.00" B 11 46 TSH -0.08" B 11 47 TSH +0.00" B 12 57 TSH -0.12" B 15 53 TSH -0.06" B 16 32 TSH -0.12" B 17 9 TSH -0.08" B 17 24 TSH -0.08" B 17 38 TSH -0.10" B 18 49 TSH -0.10" B 20 33 TSH -0.09" B 21 24 TSH +0.04" B 21 25 TSH +0.01" B 21 44 TSH -0.11" B 22 14 TSH -0.09" B 25 26 TSH +0.14" B 32 51 TSH -0.09" B 32 56 TSH +0.00" B 37 51 TSH -0.11" B 38 56 TSH -0.09" |
| | * TSH -Top of Tubesheet (Hot Leg) ** MCI -Multiple Circumferential Indications SAl -Single Axial Indication SCI -Single Circumferential Indication |
| | *** Reported Using the 300 kHz Plus Point Coil Volts SCI 0.19 SCI 0.10 MCI 0.29 SCI 0.18 SCI 0.12 SCI 0.19 MCI 0.21 SCI 0.20 SCI 0.19 SCI 0.14 SCI 0.16 SCI 0.11 SCI 0.24 SCI 0.28 SCI 0.15 SAl 0.31 SAl 0.15 SCI 0.13 SCI 0.10 SAl 0.10 MCI 0.10 SCI 0.12 SCI 0.08 SCI 0.13 Page 4 of7 Severity*** |
| | Axial Length 0.28" 0.16" 0.23" Initiation Arc Surfacel Projected Length Degradation Leakage 87 u OOSCC 0 47 u OOSCC 0 219 u OOSCC 0 75 u OOSCC 0 27 0 OOSCC 0 61 u OOSCC 0 161 u OOSCC 0 68 u OOSCC 0 44 u OOSCC 0 124 0 OOSCC 0 80u OOSCC 0 34 u OOSCC 0 75 u OOSCC 0 134 u OOSCC 0 27 u OOSCC 0 OOSCC 0 OOSCC 0 41 u OOSCC 0 59 u OOSCC 0 OOSCC 0 267 u OOSCC 0 58 u OOSCC 0 27 u OOSCC 0 70 u OOSCC 0 SG "C" Hot Leg Tubesheet: |
| | Seven tubes were plugged for indications reported during the hot leg tubesheet region examination. |
| | Of theses tubes; six tubes were reported with either single or multiple circumferential OOSCC indications located at or slightly below the top of tubesheet and one tube was reported with a single axial OOSCC indication located above the top of tubesheet. |
| | 2RCS-SG21C 2R15 Tubesheet Indications Indication Location Orientation** |
| | SG Row Column Elevation1o C 3 46 TSH -0.17" C 8 57 TSH -0.06" C 8 58 TSH +0.12" C 9 92 TSH -0.16" C 11 53 TSH -0.03" C 20 57 TSH -0.07" C 35 61 TSH -0.09" |
| | * TSH -Top of Tubesheet (Hot Leg) 1o1o MCI -Multiple Circumferential Indications SAI-Single Axial Indication SCI -Single Circumferential Indication |
| | **1o Reported Using the 300 kHz Plus Point Coil Volts SCI 0.09 SCI 0.20 SAl 0.20 SCI 0.08 SCI 0.18 SCI 0.06 MCI 0.19 Page 5 of7 Severity101o1o Axial Length 0.16" Initiation Arc Surfacel Projected Length Degradation Leakage 47 u OOSCC 0 155 u OOSCC 0 OOSCC 0 30 u OOSCC 0 36° OOSCC 0 33 u OOSCC 0 67 u OOSCC 0 Non Tubesheet Region Degradation: |
| | The following information lists the tubes that were removed from service for degradation in other areas of the steam generators. |
| | This information is being submitted for completeness of the tube plugging performed 2R15 and is not required to be reported by Technical Specification 5.6.6.2.4. |
| | 2RCS-SG21A Indication Location Severity *** Initiation Orientation** |
| | Axial Arc Surfacel Projected SG Row Column Elevation* |
| | Volts Length Length Degradation Leakage A 7 37 4H -0.10" SAl 0.16 0.26" OOSCC 0 A 8 25 2H -0.26" SAl 0.13 0.31" OOSCC 0 A 16 8 3H -0.04" SAl 0.11 0.23" OOSCC 0 A 16 9 2H +0.14" SAl 0.12 0.41" OOSCC 0 A 16 24 6H -0.05" SAl 0.16 0.31" OOSCC 0 2RCS-SG21B Indication Location Severity *** Initiation Orientation** |
| | Axial Arc Surfacel Projected SG Row Column Elevation* |
| | Volts Length Length Degradation Leakage B 1 33 3H +0.18" SAl 0.10 0.45" OOSCC 0 B 6 31 3H +0.09" SAl 0.10 0.45" OOSCC 0 B 6 35 3H -0.02" SAl 0.16 0.33" OOSCC 0 B 6 42 2H +0.16" MAl 0.16 0.40" OOSCC 0 B 8 35 6H +0.05" SAl 0.11 0.16" OOSCC 0 B 10 32 3H +0.01" SAl 0.10 0.32" OOSCC 0 B 11 55 2H +0.00" SAl 0.09 0.17" OOSCC 0 B 11 59 2H +0.10" SAl 0.09 0.37" OOSCC 0 B 11 60 3H +0.06" SAl 0.08 0.34" OOSCC 0 B 13 72 3H +0.04" SAl 0.08 0.28" OOSCC 0 B 14 55 2H +0.10" SAl 0.18 0.52" OOSCC 0 B 15 66 3H -0.04" SAl 0.07 0.16" OOSCC 0 B 16 12 4H +0.00" SAl 0.16 0.28" OOSCC 0 B 16 14 3H +0.01" SAl 0.34 0.28" OOSCC 0 B 17 34 6H +0.17" SAl 0.10 0.29" OOSCC 0 B 18 31 2H +0.06" SAl 0.12 0.16" OOSCC 0 B 18 67 3H +0.08" SAl 0.11 0.23" OOSCC 0 B 20 34 2H -0.14" SAl 0.13 0.61" OOSCC 0 B 29 57 2H +0.00" SAl 0.07 0.23" OOSCC 0 B 31 17 2H -0.18" SAl 1.15 0.20" PWSCC 0 Page 6 of7 2RCS-SG21C Indication Location Severity *** Initiation Orientation** |
| | Axial Arc Surfacel Projected SG Row Column Elevation* |
| | Volts Length Length Degradation Leakage C 3 55 8C +0.04" SAl 0.21 0.21" OOSCC 0 C 15 29 4H +0.00" SAl 0.31 0.21" OOSCC 0 C 15 29 6H +0.00" SAl 0.13 0.26" OOSCC 0 C 29 12 VARIOUS PVN See Below 0 C 30 74 4H -0.03" SAl 0.17 0.42" OOSCC 0 C 31 59 6H +41.53" SCI 0.37 26 u OOSCC 0 C 31 63 3H +0.12" SAl 0.11 0.17" OOSCC 0 C 31 63 4H +0.07" SAl 0.07 0.16" OOSCC 0 |
| | * 2H, 3H, 4H, 6H -2 nd , 3 m , 4th, 6 th Hot Leg Tube Support Plate (Flow distribution baffle is referred to as 1 H/1 C) 8C -8 th Cold Leg Tube Support Plate ** MAl -Multiple Axial Indications PVN -Permeability Variation SAI-Single Axial Indication SCI -Single Circumferential Indication |
| | *** Reported Using the 300 kHz Plus Point Coil R29 C12 -This tube exhibited permeability variations ranging from 0.16 volts to 11.58 volts between the 7 th hot leg tube support plate and the 4th cold leg tube support plate. The bobbin probe (200 kHz) was used to verify that no axial OOSCC was present at the tube support plate intersections. |
| | The bobbin probe (100 kHz) was used to verify that no axial OOSCC was present in the free span regions. A magnetically biased Plus Point probe was used to verify that no circumferential OOSCC was present at free span dings which may have represented a structural or leakage potential. |
| | A full length in-situ pressure test was subsequently performed on the tube. No leakage or burst was observed at any of the test pressures. |
| | Post in-situ bobbin probe testing showed no detectable degradation at the tube support plate intersections or in the free span regions. The tube was stabilized on the hot leg side prior to removing it from service via plugging. |
| | Page 7 of7}} |
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Category:Letter
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[Table view] Category:Report
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ML21127A1592018-01-22022 January 2018 ODCM: Radiological Environmental Monitoring Program L-17-277, Pressure and Temperature Limits Reports, Revisions 8 and 92017-10-0404 October 2017 Pressure and Temperature Limits Reports, Revisions 8 and 9 L-17-259, Mitigating Strategies Assessment (MSA) for Flooding2017-09-20020 September 2017 Mitigating Strategies Assessment (MSA) for Flooding ML17213A0162017-05-11011 May 2017 Enclosure a: Beaver Valley, Units 1, Seismic Probabilistic Risk Assessment in Response to 50.54(f) Letter with Regard to NTTF 2.1 ML17213A0172017-05-11011 May 2017 Enclosure B: Beaver Valley, Unit 2, Seismic Probabilistic Risk Assessment in Response to 50.54(0 Letter with Regard to NTTF 2.1 ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 ML16312A3112016-11-0707 November 2016 Spent Fuel Pool Evaluation Supplemental Report. Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Ntif) Review... L-16-327, Technical Basis for Optimization or Elimination of Liquid Penetrant Exams for the Embedded Flaw Repair2016-10-31031 October 2016 Technical Basis for Optimization or Elimination of Liquid Penetrant Exams for the Embedded Flaw Repair L-16-093, Report of Facility Changes, Tests and Experiments2016-06-0303 June 2016 Report of Facility Changes, Tests and Experiments L-16-065, Transmittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.22016-04-0606 April 2016 Transmittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2 L-16-006, Submittal of Annual Report Pursuant to 10 CFR 75.11, Location Information2016-01-20020 January 2016 Submittal of Annual Report Pursuant to 10 CFR 75.11, Location Information L-15-386, Post Accident Monitoring Report Regarding Inoperability of One of the Source Range Nuclear Excore Instrumentation Channel for a Period in Excess of the 30-Day Restoration Time2016-01-0505 January 2016 Post Accident Monitoring Report Regarding Inoperability of One of the Source Range Nuclear Excore Instrumentation Channel for a Period in Excess of the 30-Day Restoration Time L-15-337, Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and NRC Order EA-12-051, Reliable Spent Fuel Pool..2015-12-21021 December 2015 Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and NRC Order EA-12-051, Reliable Spent Fuel Pool.. ML16277A1142015-10-28028 October 2015 ERS-MPD-93-007, Rev. 11, BVPS-U1 Gaseous Radioactivity Monitor Emergency Action Levels. ML15274A3072015-10-0505 October 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54 Seismic Hazard Reevaluations for Recommendation 2.1of the Near-Term Task Force Review L-15-187, Submittal of 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2015-09-16016 September 2015 Submittal of 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML15132A4962015-05-22022 May 2015 Review of the 2014 Steam Generator Tube Inspection Report (TAC No. M4620) ML16277A1222015-04-20020 April 2015 ERS-LMR-14-001, Rev. 1, Liquid Monitor Alert Emergency Action Level (EAL) Set Points. ML15119A1042015-03-31031 March 2015 SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 1 of 4 L-15-091, SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 2 of 42015-03-31031 March 2015 SG-CCOE-14-4-NP, Revision 1, Examination of Steam Generator Tubes Removed, Part 2 of 4 ML21127A1582015-02-11011 February 2015 ODCM: Bases for ODCM Controls ML16277A1152015-01-30030 January 2015 ERS-HHM-87-014, Rev. 8, Unit 1 / Unit 2 ODCM Gaseous Effluent Monitor Setpoints. ML15027A2352015-01-28028 January 2015 Regulatory Audit in Support of the License Amendment Request to Implement a Risk-Informed, Performance-Based, Fire Protection Program (Tac Nos. MF3301 & MF3302) L-14-401, First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In2014-12-19019 December 2014 First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In L-14-352, Steam Generator Tube Inspection Report - Technical Specification 5.6.6.22014-11-0505 November 2014 Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2 ML21127A1442014-10-0707 October 2014 ODCM: Information Related to 40 CFR 190 L-14-259, Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014 Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML14224A5772014-07-31031 July 2014 SG-SGMP-14-17, Revision 1, Beaver Valley, Unit 2, End-of-Cycle 17 Analysis and Prediction for End-of-Cycle 18 Voltage-Based Repair Criteria 90-Day Report. ML14224A5762014-07-31031 July 2014 SG-CCOE-14-1, Revision 0, Generic Letter 95-05 Tube Intersection Burst Test, Leakage Test, and Morphology Conclusions. ML14224A5752014-06-25025 June 2014 R17 Steam Generator F* (F Star) Report ML14009A0892014-02-10010 February 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Daiichi Nuclear Power Plant Accident 2023-08-07
[Table view] Category:Miscellaneous
MONTHYEARL-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments IR 05000334/20210052021-09-0101 September 2021 Updated Inspection Plan for the Beaver Valley Power Station, Units 1 and 2 (Report 05000334/2021005 and 05000412/2021005) ML21131A0242021-05-17017 May 2021 Review of Reactor Pressure Vessel Capsule Y Analysis Report ML21055A0582021-03-10010 March 2021 Review of the Refueling Outage 21 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and F* Reports L-21-063, Facility Id 04-13361, Unit 2 Emergency Diesel Generator Day Tanks2021-02-0101 February 2021 Facility Id 04-13361, Unit 2 Emergency Diesel Generator Day Tanks L-20-257, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic2020-09-22022 September 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic L-19-053, Emergency Response Data System Data Point Library Update2019-02-20020 February 2019 Emergency Response Data System Data Point Library Update L-18-037, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2018-06-18018 June 2018 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-18-017, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado.2018-03-15015 March 2018 Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformances Identified in Response to Regulatory Issue Summary 2015-06, Tornado. ML17024A0362016-12-31031 December 2016 Operating Data Report for 2016 ML16312A3112016-11-0707 November 2016 Spent Fuel Pool Evaluation Supplemental Report. Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (Ntif) Review... L-16-093, Report of Facility Changes, Tests and Experiments2016-06-0303 June 2016 Report of Facility Changes, Tests and Experiments L-16-065, Transmittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.22016-04-0606 April 2016 Transmittal of 180-Day Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2 L-16-006, Submittal of Annual Report Pursuant to 10 CFR 75.11, Location Information2016-01-20020 January 2016 Submittal of Annual Report Pursuant to 10 CFR 75.11, Location Information L-15-386, Post Accident Monitoring Report Regarding Inoperability of One of the Source Range Nuclear Excore Instrumentation Channel for a Period in Excess of the 30-Day Restoration Time2016-01-0505 January 2016 Post Accident Monitoring Report Regarding Inoperability of One of the Source Range Nuclear Excore Instrumentation Channel for a Period in Excess of the 30-Day Restoration Time L-15-337, Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and NRC Order EA-12-051, Reliable Spent Fuel Pool..2015-12-21021 December 2015 Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and NRC Order EA-12-051, Reliable Spent Fuel Pool.. ML15274A3072015-10-0505 October 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54 Seismic Hazard Reevaluations for Recommendation 2.1of the Near-Term Task Force Review L-15-187, Submittal of 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2015-09-16016 September 2015 Submittal of 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML15132A4962015-05-22022 May 2015 Review of the 2014 Steam Generator Tube Inspection Report (TAC No. M4620) ML15027A2352015-01-28028 January 2015 Regulatory Audit in Support of the License Amendment Request to Implement a Risk-Informed, Performance-Based, Fire Protection Program (Tac Nos. MF3301 & MF3302) L-14-401, First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In2014-12-19019 December 2014 First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of In L-14-352, Steam Generator Tube Inspection Report - Technical Specification 5.6.6.22014-11-0505 November 2014 Steam Generator Tube Inspection Report - Technical Specification 5.6.6.2 L-14-259, Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014 Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML14009A0892014-02-10010 February 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Daiichi Nuclear Power Plant Accident ML13284A0242013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3, Seismic Walkdown Report Revision 1, Appendix B, Seismic Walkdown Checklists (Swcs), Part 3 of 5 ML13284A0272013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3, Seismic Walkdown Report Revision 1, Appendix B, Seismic Walkdown Checklists (Swcs), Continued, Part 4 of 5 ML13284A0262013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3, Seismic Walkdown Report Revision 1, Appendix a, Resumes and Qualifications, Part 2 of 5 ML13284A0252013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3, Seismic Walkdown Report Revision 1, Part 1 of 5 ML13284A0232013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Revision 1, Appendix a, Resumes and Qualifications, Part 2 of 5 ML13284A0192013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Revision 1, Appendix B Seismic Walkdown Checklists (Swcs), Part 3 of 5 ML13284A0222013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Revision 1, Part 1 of 5 ML13284A0202013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Revision 1, Appendix B Seismic Walkdown Checklists (Swcs) Continued. Part 4 of 5 ML13284A0212013-09-0404 September 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Revision 1, Appendix C Area Walk-by Checklists (Awcs), Part 5 of 5 L-13-036, Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedules2013-05-28028 May 2013 Proposed Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedules L-13-095, Discharge Monitoring Report (NPDES) Permit No. PA00256152013-02-22022 February 2013 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-12-437, Containment Liner Random and Non-Random Examinations Report2012-12-18018 December 2012 Containment Liner Random and Non-Random Examinations Report L-12-347, FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2012-11-27027 November 2012 FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML13008A0422012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B Seismic Walkdown Checklits (Swcs), Battery 2N. Pages 1 - 82 ML13008A0412012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report. Cover Through A-40 ML13135A2382012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 1 of 513 Through Sheet 301 of 513 ML13008A0432012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B Seismic Walkdown Checklists (Swcs), Purge Valve Isolation. Pages 83 - 161 ML13008A0442012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B Seismic Walkdown Checklists (Swcs), Bus F1, Low Voltage Switchgear. Pages 162 - 240 ML13008A0452012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B Seismic Walkdown Checklists (Swcs), SGI Level Switch SP9B6. Pages 241 - 318 ML13008A0462012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B Seismic Walkdown Checklists (Swcs), Relief Valves SW 3963. Pages 319 - End ML13135A2412012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C - Area Walk-by Checklists (Awcs) and Appendix D - Component List for Anchorage Configuration Check ML13135A2402012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 302 of 513 Through Sheet 513 of 513 ML13135A2362012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report ML13135A2372012-10-31031 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix a - Resumes and Qualifications ML13008A0402012-10-23023 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C Area Walk-by Checklists (Awcs), Prim. Aux. Bldg 735'6. Pages 135 - 191 ML13008A0392012-10-23023 October 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C Area Walk-by Checklists (Awcs), Emer. Swgr. Room Train A. Pages 66 - 134 2023-08-07
[Table view] |
Text
FENOC ........ FirstEnergy Nuclear Operating Company Paul A. Harden Site Vice President June 9, 2011 L-11-148 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No.2 Docket No. 50-412, License No. NPF-73 Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 724-682-5234 Fax: 724-643-8069 Steam Generator Tube Inspection Report -Technical Specification 5.6.6.2.4 In accordance with Technical Specification 5.6.6.2.4, FirstEnergy Nuclear Operating Company hereby submits a report containing tube inspection results for Beaver Valley Power Station, Unit No.2, steam generators.
The enclosed report provides information required by the technical specification that was obtained during inspections conducted during the spring 2011 refueling outage. There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Fleet Licensing, at (330) 761-6071.
Paul A. Harden
Enclosure:
Unit #2 -2R15 Steam Generator F* (F Star) Report cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative FIRST ENERGY NUCLEAR OPERATING COMPANY Technical Services Engineering Department Nuclear Engineering ProgramsSection Issue Date: May 13, 2011
Subject:
Unit #2" 2R15 Steam Generator F* (F Star) Report Prepared by:
__ SG Program Owner, Date: 0 s I , 3/ II Reviewed by: Jeff <<3 --' Date:
Approved by: Doug Reeves o<J..--t.-
==-Date: S-/I?:> / 1/ Manager, Technical Services UNIT #2 -2R15 STEAM GENERATOR F* (F STAR) REPORT Pursuant to Specification 5.6.6.2.4 of the Technical Specifications, the following information is to be transmitted to the NRC within 90 days after entering MODE 4 following an outage in which the F* (F Star) methodology was implemented.
For 2R 15, MODE 4 occurred on April 7th, 2011. Therefore, this information must be submitted to the NRC on or before July 6, 2011. Per Specification 5.6.6.2.4, the following information is to be submitted and is discussed within this document: (a) The total number of indications, the location of each indication, the orientation of each indication, the severity of each indication and whether the indications initiated from the inside or outside surface, (b) The cumulative number of indications detected in the tubesheet region as a function of elevation within the tubesheet, (c) The projected end-of-cycle accident induced leakage from tubesheet indications.
During the 2R 15 outage, the Plus Point probe was utilized to inspect the top of tubesheet region. The 2R 15 inspection scope was 100% of the inservice hot leg tubes in all three steam generators (SG's) plus a 20% random sample of the inservice cold leg tubes in SG "A". The inspection distance in either leg was from 6.0 inches above the top of tubesheet to 3.0 inches below the top of tubesheet and bounds the required F* examination distance (Le. the expanded portion of the tube below the bottom of roll expansion transition) of 2.22 inches below the bottom of the expansion transition.
A small number of tubes (10 total in the hot leg of all 3 SG's and 4 in SG "A" cold leg) have roll expansion transitions at lower than nominal elevations.
These particular tubes were inspected to a depth of 5.0 inches below the top of tubesheet to ensure that the F* distance was adequately examined.
As seen from the information contained within, the morphology for the vast majority of the indications reported from the hot leg tubesheet region is believed to be attributed to circumferentially oriented outside diameter stress corrosion cracking (ODSCC). This is based on signal recognition and location of the reported indications.
All ODSCC indications observed were plugged upon detection.
All top of tubesheet circumferential indications were stabilized prior to installing the hot leg plug. None of the indications that were removed from service during 2R15 represented a (Cycle 15) leakage potential at postulated main steam line break (MSLB) conditions.
The information provided on the following pages summarizes the degradation observed during the 2R15 tubesheet region examinations.
The data has been analyzed utilizing the 300 kHz channel from the Plus Point probe. This provides the most accurate sizing technique and is used for assessing the severity of the indications.
Page 2 of7 SG "A" Hot Leg Tubesheet:
Twenty tubes were plugged for indications reported during the hot leg tubesheet region examination.
Of these tubes; nineteen tubes were reported with either single or multiple circumferential OOSCC indications located at or slightly below the top of tubesheet and one tube was reported with single axial OOSCC indication located above the top of tubesheet.
SG "A" Cold Leg Tubesheet:
No indications were reported during the 20% random sample inspection of the cold leg tubesheet region. 2RCS-SG21A 2R15 Tubesheet Indications Indication Location Orientation**
SG Row Column Elevation* A 6 50 TSH -0.12" A 8 38 TSH -0.03" A 8 57 TSH -0.09" A 9 23 TSH -0.08" A 11 38 TSH -0.14" A 12 37 TSH -0.15" A 12 41 TSH -0.09" A 12 42 TSH +0.00" A 13 44 TSH -0.07" A 19 55 TSH -0.20" A 20 21 TSH -0.13" A 25 33 TSH -0.08" A 27 72 TSH -0.05" A 33 33 TSH -0.06" A 38 49 TSH +0.49" A 40 43 TSH -0.05" A 41 49 TSH -0.10" A 42 42 TSH -0.07" A 42 45 TSH -0.01" A 43 47 TSH -0.01"
- TSH -Top of Tubesheet (Hot Leg) ** MCI -Multiple Circumferential Indications SAl -Single Axial Indication SCI -Single Circumferential Indication
- Reported Using the 300 kHz Plus Point Coil Volts SCI 0.12 SCI 0.18 SCI 0.16 SCI 0.21 SCI 0.13 SCI 0.20 SCI 0.13 SCI 0.17 SCI 0.19 MCI 0.13 SCI 0.14 SCI 0.24 SCI 0.20 MCI 0.17 SAl 0.12 MCI 0.27 SCI 0.16 SCI 0.17 SCI 0.07 SCI 0.08 Page 3 of7 Severity***
Axial Length 0.17" Initiation Arc Surfacel Projected Length Degradation Leakage 65 u OOSCC 0 110 u OOSCC 0 123 0 OOSCC 0 132 0 OOSCC 0 33 u OOSCC 0 59 u OOSCC 0 82 u OOSCC 0 69 u OOSCC 0 69 0 OOSCC 0 190 u OOSCC 0 98 u OOSCC 0 91 u OOSCC 0 155 0 OOSCC 0 130 u OOSCC 0 OOSCC 0 229 u OOSCC 0 50 u OOSCC 0 106 u OOSCC 0 107 0 OOSCC 0 34 u OOSCC 0 SG "8" Hot Leg Tubesheet:
Twenty four tubes were plugged for indications reported during the hot leg tubesheet region examination.
Of these tubes; twenty one tubes were reported with either single or multiple circumferential ODSeC indications located at or slightly below the top of tubesheet and three tubes were reported with single axial ODSee indications located above the top of tubesheet.
2RCS-SG21B 2R15 Tubesheet Indications Indication Location Orientation**
SG Row Column Elevation*
B 7 41 TSH+O.OO" B 8 32 TSH -0.01" B 8 54 TSH -0.04" B 9 54 TSH -0.12" B 11 19 TSH +0.00" B 11 46 TSH -0.08" B 11 47 TSH +0.00" B 12 57 TSH -0.12" B 15 53 TSH -0.06" B 16 32 TSH -0.12" B 17 9 TSH -0.08" B 17 24 TSH -0.08" B 17 38 TSH -0.10" B 18 49 TSH -0.10" B 20 33 TSH -0.09" B 21 24 TSH +0.04" B 21 25 TSH +0.01" B 21 44 TSH -0.11" B 22 14 TSH -0.09" B 25 26 TSH +0.14" B 32 51 TSH -0.09" B 32 56 TSH +0.00" B 37 51 TSH -0.11" B 38 56 TSH -0.09"
- TSH -Top of Tubesheet (Hot Leg) ** MCI -Multiple Circumferential Indications SAl -Single Axial Indication SCI -Single Circumferential Indication
- Reported Using the 300 kHz Plus Point Coil Volts SCI 0.19 SCI 0.10 MCI 0.29 SCI 0.18 SCI 0.12 SCI 0.19 MCI 0.21 SCI 0.20 SCI 0.19 SCI 0.14 SCI 0.16 SCI 0.11 SCI 0.24 SCI 0.28 SCI 0.15 SAl 0.31 SAl 0.15 SCI 0.13 SCI 0.10 SAl 0.10 MCI 0.10 SCI 0.12 SCI 0.08 SCI 0.13 Page 4 of7 Severity***
Axial Length 0.28" 0.16" 0.23" Initiation Arc Surfacel Projected Length Degradation Leakage 87 u OOSCC 0 47 u OOSCC 0 219 u OOSCC 0 75 u OOSCC 0 27 0 OOSCC 0 61 u OOSCC 0 161 u OOSCC 0 68 u OOSCC 0 44 u OOSCC 0 124 0 OOSCC 0 80u OOSCC 0 34 u OOSCC 0 75 u OOSCC 0 134 u OOSCC 0 27 u OOSCC 0 OOSCC 0 OOSCC 0 41 u OOSCC 0 59 u OOSCC 0 OOSCC 0 267 u OOSCC 0 58 u OOSCC 0 27 u OOSCC 0 70 u OOSCC 0 SG "C" Hot Leg Tubesheet:
Seven tubes were plugged for indications reported during the hot leg tubesheet region examination.
Of theses tubes; six tubes were reported with either single or multiple circumferential OOSCC indications located at or slightly below the top of tubesheet and one tube was reported with a single axial OOSCC indication located above the top of tubesheet.
2RCS-SG21C 2R15 Tubesheet Indications Indication Location Orientation**
SG Row Column Elevation1o C 3 46 TSH -0.17" C 8 57 TSH -0.06" C 8 58 TSH +0.12" C 9 92 TSH -0.16" C 11 53 TSH -0.03" C 20 57 TSH -0.07" C 35 61 TSH -0.09"
- TSH -Top of Tubesheet (Hot Leg) 1o1o MCI -Multiple Circumferential Indications SAI-Single Axial Indication SCI -Single Circumferential Indication
- 1o Reported Using the 300 kHz Plus Point Coil Volts SCI 0.09 SCI 0.20 SAl 0.20 SCI 0.08 SCI 0.18 SCI 0.06 MCI 0.19 Page 5 of7 Severity101o1o Axial Length 0.16" Initiation Arc Surfacel Projected Length Degradation Leakage 47 u OOSCC 0 155 u OOSCC 0 OOSCC 0 30 u OOSCC 0 36° OOSCC 0 33 u OOSCC 0 67 u OOSCC 0 Non Tubesheet Region Degradation:
The following information lists the tubes that were removed from service for degradation in other areas of the steam generators.
This information is being submitted for completeness of the tube plugging performed 2R15 and is not required to be reported by Technical Specification 5.6.6.2.4.
2RCS-SG21A Indication Location Severity *** Initiation Orientation**
Axial Arc Surfacel Projected SG Row Column Elevation*
Volts Length Length Degradation Leakage A 7 37 4H -0.10" SAl 0.16 0.26" OOSCC 0 A 8 25 2H -0.26" SAl 0.13 0.31" OOSCC 0 A 16 8 3H -0.04" SAl 0.11 0.23" OOSCC 0 A 16 9 2H +0.14" SAl 0.12 0.41" OOSCC 0 A 16 24 6H -0.05" SAl 0.16 0.31" OOSCC 0 2RCS-SG21B Indication Location Severity *** Initiation Orientation**
Axial Arc Surfacel Projected SG Row Column Elevation*
Volts Length Length Degradation Leakage B 1 33 3H +0.18" SAl 0.10 0.45" OOSCC 0 B 6 31 3H +0.09" SAl 0.10 0.45" OOSCC 0 B 6 35 3H -0.02" SAl 0.16 0.33" OOSCC 0 B 6 42 2H +0.16" MAl 0.16 0.40" OOSCC 0 B 8 35 6H +0.05" SAl 0.11 0.16" OOSCC 0 B 10 32 3H +0.01" SAl 0.10 0.32" OOSCC 0 B 11 55 2H +0.00" SAl 0.09 0.17" OOSCC 0 B 11 59 2H +0.10" SAl 0.09 0.37" OOSCC 0 B 11 60 3H +0.06" SAl 0.08 0.34" OOSCC 0 B 13 72 3H +0.04" SAl 0.08 0.28" OOSCC 0 B 14 55 2H +0.10" SAl 0.18 0.52" OOSCC 0 B 15 66 3H -0.04" SAl 0.07 0.16" OOSCC 0 B 16 12 4H +0.00" SAl 0.16 0.28" OOSCC 0 B 16 14 3H +0.01" SAl 0.34 0.28" OOSCC 0 B 17 34 6H +0.17" SAl 0.10 0.29" OOSCC 0 B 18 31 2H +0.06" SAl 0.12 0.16" OOSCC 0 B 18 67 3H +0.08" SAl 0.11 0.23" OOSCC 0 B 20 34 2H -0.14" SAl 0.13 0.61" OOSCC 0 B 29 57 2H +0.00" SAl 0.07 0.23" OOSCC 0 B 31 17 2H -0.18" SAl 1.15 0.20" PWSCC 0 Page 6 of7 2RCS-SG21C Indication Location Severity *** Initiation Orientation**
Axial Arc Surfacel Projected SG Row Column Elevation*
Volts Length Length Degradation Leakage C 3 55 8C +0.04" SAl 0.21 0.21" OOSCC 0 C 15 29 4H +0.00" SAl 0.31 0.21" OOSCC 0 C 15 29 6H +0.00" SAl 0.13 0.26" OOSCC 0 C 29 12 VARIOUS PVN See Below 0 C 30 74 4H -0.03" SAl 0.17 0.42" OOSCC 0 C 31 59 6H +41.53" SCI 0.37 26 u OOSCC 0 C 31 63 3H +0.12" SAl 0.11 0.17" OOSCC 0 C 31 63 4H +0.07" SAl 0.07 0.16" OOSCC 0
- 2H, 3H, 4H, 6H -2 nd , 3 m , 4th, 6 th Hot Leg Tube Support Plate (Flow distribution baffle is referred to as 1 H/1 C) 8C -8 th Cold Leg Tube Support Plate ** MAl -Multiple Axial Indications PVN -Permeability Variation SAI-Single Axial Indication SCI -Single Circumferential Indication
- Reported Using the 300 kHz Plus Point Coil R29 C12 -This tube exhibited permeability variations ranging from 0.16 volts to 11.58 volts between the 7 th hot leg tube support plate and the 4th cold leg tube support plate. The bobbin probe (200 kHz) was used to verify that no axial OOSCC was present at the tube support plate intersections.
The bobbin probe (100 kHz) was used to verify that no axial OOSCC was present in the free span regions. A magnetically biased Plus Point probe was used to verify that no circumferential OOSCC was present at free span dings which may have represented a structural or leakage potential.
A full length in-situ pressure test was subsequently performed on the tube. No leakage or burst was observed at any of the test pressures.
Post in-situ bobbin probe testing showed no detectable degradation at the tube support plate intersections or in the free span regions. The tube was stabilized on the hot leg side prior to removing it from service via plugging.
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