ML15223A627

NRC000208E - MRP Letter 2014-09, Biennial Report of Recent MRP-227-A Reactor Internals Inspection Results (May 12, 2014)

ML15223A627
Person / Time
Site:	Indian Point
Issue date:	05/12/2014
From:	NRC/OGC
To:	Atomic Safety and Licensing Board Panel
SECY RAS
References
RAS 28143, ASLBP 07-858-03-LR-BD01, 50-247-LR, 50-286-LR
Download: ML15223A627 (42)

Text

Tables for Reporting MRP-227-A Inspection Results for Westinghouse PlantsPlant Name: Prairie Island Unit 2 Utility: Xcel EnergyDate of Exams: 27NOV13 thru 03DEC13 Plant Age: 39 (years)/ 34 EFPYPrimary Components109 Prairie Island Unit 2110 Prairie Island Unit 2111 Prairie Island Unit 2Not Inspected this outage728 out of 728 bolts 75 bolts with indications.21 of these were Head-to-shank.54 of these were in the shank.653 bolts had no indications.There were no bolts with indicationsin the large, low-fluence platesThe extent of the bolt failures wasbounded by minimum pattern analysisplus margin term per WCAP-1 7096tommenis:112 Prairie Island Unit 2Not Inspected this outage113 aPrairie Island Unit 2Notes to Westinghouse Primary Components Table:1. Examination acceptance criteria and expansion criteria for the Westinghouse components are in Table 5-3 of MRP-227-A.2. A minimum of 75% of the total identified sample population must be examined.3. A minimum of 75% of the total population (examined + unexamined), including coverage consistent with the Expansion criteria in Table 5-3 of MRP-227-A, must beexamined for inspection credit.4. A minimum of 75% of the total weld length (examined + unexamined), including coverage consistent with the Expansion criteria in Table 5-3 of MRP-227-A, must beexamined from either the inner or outer diameter for inspection credit.5. The lower core barrel flange weld may be alternatively designated as the core barrel-to-support plate weld in some Westinghouse plant designs.114 Prairie Island Unit 2Expansion ComponentsUpper InternalsAssemblyUpper core plateEnhanced visualexamination (EVT-1)100% of accessiblesurfaces (Note 2).Not Inspected this outageComments:Lower Internals Enhanced visual 100% of accessibleAssembly examination (EVT-1) surfaces (Note 2). Not Inspected this outageLower supportforging or castings See Figure 4-33 of MRP-227-A.Comments:115 Prairie Island Unit 2Ite E Required Examination Coverage ExaminationCoverage Achieved Findings (Note 1)Core Barrel Volumetric 100% of accessible bolts.Assembly examination (UT) Accessibility may be Not Inspected this outageBarrel-former bolts limited by presence ofthermal shields or neutronpads (Note 2).See Figure 4-23 of MRP-227-A.Comments:Lower Support Volumetric 100% of accessible boltsAssembly examination (UT) or as supported by plant- Not Inspected this outageLower support specific justification (Notecolumn bolts 2).See Figures 4-32 and 4-33of MRP-227-A.Comments:116 Prairie Island Unit 2Core BarrelAssemblyCore barrel outletnozzle weldsEnhanced visualexamination (EVT-1)100% ot one side ot theaccessible surfaces of theselected weld andadjacent base metal (Note2).See Figure 4-22 of MRP-227-A.Not Inspected this outageComments:Core Barrel Enhanced visual 100% of one side of theAssembly examination (EVT-1) accessible surfaces of the Not Inspected this outageUpper and lower core selected weld andbarrel cylinder axial adjacent base metal (Notewelds 2).See Figure 4-22 of MRP-227-A.Comments:117W-Prairie Island Unit 2Item Examination Method Required Examination Cover-g Examination...._ _Coverage Achieved Findings (Note 1)Lower Support Enhanced visual 100% of accessibleAssembly examination (EVT-1) surfaces (Note 2). Not Inspected this outageLower supportcolumn bodies See Figure 4-34 of MRP-(non cast) 227-A.Comments:Lower Support Enhanced visual 100% of accessibleAssembly examination (EVT-1) support columns (Note 2). Not Inspected this outageLower supportcolumn bodies See Figure 4-34 of MRP-(cast) 227-A.Comments:118 Prairie Island Unit 2Bottom MountedInstrumentationSystemBottom-mountedinstrumentation (BMI)column bodiesVisual examination(VT-3)100% of BMI columnbodies for which difficultyis detected during fluxthimbleinsertion/withdrawal.Not Inspected this outageSee Figure 4-35 of MRP-227-A.Comments:Notes to Westinghouse Expansion Component Table:1. Examination acceptance criteria and expansion criteria for the Westinghouse components are in Table 5-3 of MRP-227-A.2. A minimum of 75% coverage of the entire examination area or volume, or a minimum sample size of 75% of the total population of like components of the examination isrequired (including both the accessible and inaccessible portions).119 Prairie Island Unit 2Existing Programs Components120 Prairie Island Unit 2121 Prairie Island Unit 235 out of 36 flux thimble tubes 6 tubes with wall loss 40-59%(one has an internal restriction 18 tubes with wall loss 20-39%due to having been bent and is 1 tube with wall loss 1-19%capped off) 10 tubes with no wall lossDONE IN CONJUNCTION WITH MRP-227-A RELATED EXAMS. *Not Inspected this outage122 Prairie Island Unit 2Notes to Westinghouse Existing Programs Components Table:1. XL = "Extra Long" referring to Westinghouse plants with 14-foot cores.123 Tables for Reporting MRP-227-A Inspection Results for B&W PlantsPlant Name: Oconee Unit 2Date of Exams: 10/12/2013 to 12/5/2013Utility: Duke EnergyPlant Age: 40 (years) / 31.82 EFPYPrimary ComponentsComments: The one-time physical measurement was performed in Fall 2008 with no evidence of wear occurring during service period124 Oconee Unit 2Comments:100% No relevant Indications wereThere are 8 vent valves, noted on retaining rings.See Comment Section forrelevant indications noted onother CSS vent valve parts.Comments: The jack screw locking devices are not currently in MRP-227 but were identified as needing to be screened in A/LAI #2. Additional partsof the Vent Valves, including the jack screw locking devices, receive a ASME Section Xl, Category B-N-3 VT-3 examination.Vent Valve XY -The left lower barrel nut was raised out of the normal position, and moderate deformation was present on the left outside corner ofthe center jack screw guide block. Vent Valve XY was replaced during the outage.Vent Valve XW -The left jack screw locking cup has a tear in the upper crimped section; however, the crimped locking device was in place with noevidence of movement. Additionally, deformation was present on the center guide block of the right jack screw. The indications on Vent Valve XWwere evaluated and left in place.Vent Valve ZW -The right jack screw locking cup has a tear in the upper crimped section; however, the crimped locking device was in place with noevidence of movement. The indication on Vent Valve ZW was evaluated and left in place.125 Oconee Unit 2Comments: Recordable UT indication was detected in LCB Bolt #90. The indication is located in the bolt head-to-shank region.The VT-3 Examination coverage for LCB Bolts #1 and #19 and their locking devices is 75% due to the obstruction from the adjacent core supportassembly (CSA) stand. The bolts and locking devices are in place with no evidence of movement. No Relevant Indications Noted.126 Oconee Unit 2Comments: Examination limitation was noted on Hex Head Baffle-to-Former Bolt (Quadrant -Plate -Column -Elevation) #3-3-2-3. Probe did notseat correctly. Due to the absence of UT information in two of four channels this bolt is classified as un-inspectable.100% No relevant Indications werenoted.Comments:127 0Comments:Oconee Unit 2100% No relevant Indications were864 baffle-to-former and 272 noted.internal baffle-to-baffle bolts.UT -- 100% UT -2 flow distributor bolts (#496 bolts inspected, and #48) with crack likeindications.VT -100% VT -No relevant Indications96 bolts and their locking were noted.devices inspected.Comments: Recordable UT indications detected in FD Bolts #4 and #48. Both indications are located in the bolt head-to-shank region.128 Oconee Unit 2Comments:100% No relevant Indications were52 spider castings, each noted.casting with 8 welds.Comments:129 2Oconee Unit 2Notes to B&W Primary Component Table1. A verification of the operation of each vent valve shall also be performed through manual actuation of the valve. Verify that the valves are not stuck in the open position andthat no abnormal degradation has occurred. Examine the valves for evidence of scratches, pitting, embedded particles, leakage of the seating surfaces, cracking of lockwelds and locking cups, jack screws for proper position, and wear. The frequency is defined in each unit's technical specifications or in their pump and valve inservice testprograms (see BAW-2248A, page 4-3 and Table 4-1, reference 18 of MRP-227-A).2. Examination acceptance criteria and expansion criteria for the B&W components are in Table 5-1 of MRP-227-A.3. A minimum of 75% of the total population (examined + unexamined), including coverage consistent with the Expansion criteria in Table 5-1, must be examined for inspectioncredit.130 Oconee Unit 2Expansion ComponentsUpper Grid AssemblyAlloy X-750 dowel-to-uppergrid fuel assembly supportpad weldsVisual examination(V'-3)Accessible surfaces of100% of the dowellocking welds.See Figure 4-6 of MRP-227-A(i.e., these are similar tothe lower grid fuelassembly supportpads).N/AComments:Core Barrel Assembly Bolts: Volumetric 100% of accessible N/AUpper thermal shield (UTS) examination (UT). bolts or studs/nuts andbolts and their locking devices Locking Devices: their locking devicesVisual examination (Note 2).(VT-3)See Figure 4-7 of MRP-227-A.Comments:131 Oconee Unit 21!Examination Required Coverage ExaminationExam intion Examination Achieved Findings (Note 1)....C ov er gCore Barrel Assembly Bolt or Stud/Nut: 100% of accessible N/ASurveillance specimen holder Volumetric bolts or studs/nuts andtube (SSHT) studs/nuts (CR- examination (UT). their locking devices3) or bolts (DB) and their Locking Devices: (Note 2).locking devices Visual examination(VT-3) See Figure 4-7 of MRP-227-A.Comments:Lower Grid Assembly Visual examination Accessible surfaces of N/ALower grid fuel assembly (VT-3) the pads, dowels, andsupport pad items: pad, pad- cap screws, andto-rib section welds, Alloy X- associated welds in750 dowel, cap screw, and 100% of the lower gridtheir locking welds fuel assembly supportpads.See Figure 4-6 of MRP-227-A.Comments:132 Oconee Unit 2Lower Grid AssemblyAlloy X-750 dowel-to-lowergrid fuel assembly supportpad weldsVisual examination(VT-3)Accessible surfaces of100% of the supportpad dowel lockingwelds.N/ASee Figure 4-6 of MRP-227-A.Comments:Lower Grid Assembly Bolts: Volumetric 100% of accessible N/ALower grid shock pad bolts examination (UT). bolts and their lockingand their locking devices Locking Devices: devices. (Note 2)Visual examination(VT-3) See Figure 4-4 of MRP-227-A.Comments:133 Oconee Unit 2V.n Required Coverage ExaminationeIemieation Examination Achieved Findings (Note 1)Lower Grid Assembly Bolts: Volumetric 100% of accessible N/ALower thermal shield (LTS) examination (UT). bolts and their lockingbolts (ANO-1, DB and TMI-1) Locking Devices: devices. (Note 2)or studs/nuts (ONS, CR-3) Visual examinationand their locking devices (VT-3) See Figure 4-8 of MRP-227-A.Comments:Notes to B&W Expansion Components Table:1. Examination acceptance criteria and expansion criteria for the B&W components are in Table 5-1 of MRP-227-A.2. A minimum of 75% of the total population (examined + unexamined) must be examined for inspection credit.134 Oconee Unit 2Expansion Components Requiring Evaluation or Replacement In Lieu of InspectionItemExaminationMethod Disposition3Core Barrel Assembly No examination requirements.Core barrel cylinder (including Justify by evaluation or by replacement.vertical and circumferential seamwelds)Former platesComments:Core Barrel Assembly Internal baffle-to-baffle bolts:Baffle-to-baffle bolts No examination requirements,Core barrel-to-former bolts Justify by evaluation or by replacement.External baffle-to-baffle bolts, core barrel-to-former bolts: No examination requirements.Justify by evaluation or by replacement.Comments:Core Barrel Assembly No examination requirements.Locking devices, including Justify by evaluation or by replacement.locking welds, for the externalbaffle-to-baffle bolts and corebarrel-to-former boltsComments:1354 ITables for Reporting MRP-227-A Inspection Results for Westinghouse PlantsPlant Name: Point Beach Nuclear Plant Unit 2Date of Exams: March, 2014 (U2R33)Utility: NextEra Energy-Plant Age: 41(years) / 34 EFPY1 I IPrimary ComponentsL;omments:A VT-3 inspection and Guide Card Wear Measurements (GCWM) were completed on thirty-three (33) guide tubes, this being 100% of the roddedlocations in the upper internals.In total, fifty-one (51) recordable indications were identified during the guide card inspection, and all indications were analyzed by WestinghouseEngineering.136 Point Beach Nuclear Plant Unit 2Comments:An EVT-1 inspection of the upper and lower GT flange welds was completed on twenty-four (24) guide tubes around the periphery ofthe upper internals.One-hundred eleven (111) welds were inspected to EVT-1 quality, and an additional fifty-two (52) welds were inspected, but EVT-1quality was not demonstrated. No recordable indications were identified during the GT flange weld inspection.Not examinedComments:To be examined during U2R34137t Point Beach Nuclear Plant Unit 2Comments:To be examined during U2R34Not examined%.,OmIIfetFI5-To be examined during U2R34138 Point Beach Nuclear Plant Unit 2s.omments:To be examined during U2R34100% (727 -see below) 15 (< 3%) original bolts exhibitedreportable ultrasonic indications.All of the reported indications in thebolts were in the head to shankinterface region (DHS).No reported indications in thereplacement boltsComments:552 -original bolts. 175 -replacement boltsTotal of 727 bolts. One bolt location does not contain a bolt139 Point Beach Nuclear Plant Unit 2II%.I LA III I ICI I MO.To be examined during U2R34V/ANUI I I I BII:1 n Ld.N/A -Point Beach Internals hold down spring is Type 403 SS140 Point Beach Nuclear Plant Unit 2Notes to Westinghouse Primary Components Table:1. Examination acceptance criteria and expansion criteria for the Westinghouse components are in Table 5-3 of MRP-227-A.2. A minimum of 75% of the total identified sample population must be examined.3. A minimum of 75% of the total population (examined + unexamined), including coverage consistent with the Expansion criteria in Table 5-3 of MRP-227-A, must beexamined for inspection credit.4. A minimum of 75% of the total weld length (examined + unexamined), including coverage consistent with the Expansion criteria in Table 5-3 of MRP-227-A, must beexamined from either the inner or outer diameter for inspection credit.5. The lower core barrel flange weld may be alternatively designated as the core barrel-to-support plate weld in some Westinghouse plant designs.141 Point Beach Nuclear Plant Unit 2Expansion ComponentsExminon Mh Required Examination Coverage Examination,t E o Cov ge Achieved Findings (Note 1)Upper Internals Enhanced visual 100% of accessibleAssembly examination (EVT-1) surfaces (Note 2). N/AUpper core plateComments:Not required to be examined -CRGT lower flange welds -No recordable indications U2R33Lower Internals Enhanced visual 100% of accessible N/AAssembly examination (EVT-1) surfaces (Note 2).Lower supportforging or castings See Figure 4-33 of MRP-227-A.Comments:Not required to be examined -CRGT lower flange welds -No recordable indications U2R33142 Point Beach Nuclear Plant Unit 2Core BarrelAssemblyBarrel-former boltsVolumetricexamination (UT)100% of +++accessiblebolts. Accessibility may belimited by presence ofthermal shields or neutronpads (Note 2).N/ASee Figure 4-23 of MRP-227-A.Comments:Not required to be examined -baffle-former bolts -results do not require expansion -U2R33Lower Support Volumetric 100% of accessible bolts N/AAssembly examination (UT) or as supported by plant-Lower support specific justification (Notecolumn bolts 2).See Figures 4-32 and 4-33of MRP-227-A.Comments:Not required to be examined -baffle-former bolts -results do not require expansion -U2R334143 Point Beach Nuclear Plant Unit 2ItItem. Exmination Method Required Examination Coverage ExaminationCoverage Achieved Findings (Note 1)Core Barrel Enhanced visual 100% of one side of the N/AAssembly examination (EVT-1) accessible surfaces of theCore barrel outlet selected weld andnozzle welds adjacent base metal (Note2).See Figure 4-22 of MRP-227-A.Comments:Upper core barrel flange weld to be examined U2R34 (Fall 2015)Core Barrel Enhanced visual 100% of one side of the N/AAssembly examination (EVT-1) accessible surfaces of theUpper and lower core selected weld andbarrel cylinder axial adjacent base metal (Notewelds 2).See Figure 4-22 of MRP-227-A.Comments:Upper and lower core barrel cylinder girth welds to be examined U2R34 (Fall 2015)144 Point Beach Nuclear Plant Unit 2Lower SupportAssemblyLower supportcolumn bodiesLnhanced visualexamination (EVT-1)100u/% ot accessiblesurfaces (Note 2).N/ASee Figure 4-34 of MRP-227-A.(non cast)Comments:Upper core barrel flange weld to be examined U2R34 (Fall 2015)Lower Support Enhanced visual 100% of accessible N/AAssembly examination (EVT-1) support columns (Note 2).Lower supportcolumn bodies See Figure 4-34 of MRP-(cast) 227-A.Comments:Not required to be examined -CRGT lower flange welds -No recordable indications U2R33145 4Point Beach Nuclear Plant Unit 2Item ini Method Required Examination Coverage ExaminationC gExam e Achieved Findings (Note 1)Bottom Mounted Visual examination 100% of BMI column N/AInstrumentation (VT-3) bodies for which difficultySystem is detected during fluxBottom-mounted thimbleinstrumentation (BMI) insertion/withdrawal.column bodiesSee Figure 4-35 of MRP-227-A.Comments:Not required to be examined -CRGT lower flange welds -No recordable indications U2R33Notes to Westinghouse Expansion Component Table:1. Examination acceptance criteria and expansion criteria for the Westinghouse components are in Table 5-3 of MRP-227-A.2. A minimum of 75% coverage of the entire examination area or volume, or a minimum sample size of 75% of the total population of like components of the examination isrequired (including both the accessible and inaccessible portions).146 Point Beach Nuclear Plant Unit 2Existing Programs ComponentsL;omments:ASME Section XI ISI Exam not performed during U2R33N/A%,VIIIII~ltPII5.ASME Section XA ISI Exam not performed during U2R3314714 Point Beach Nuclear Plant Unit 2A e,U IIISeI XI I L.peuASME Section Xl ISI Exam not performed during U2R33N/A.;omments:ASME Section XI ISI Exam not performed during U2R33148 Point Beach Nuclear Plant Unit 2ASME Section Xl ISI Exam not performed during U2R33*1*N/AComments:ASME Section Xl ISI Exam not performed during U2R331494 Point Beach Nuclear Plant Unit 2NNotes to Westinghouse Existing Programs Components Table:1. XL = "Extra Long" referring to Westinghouse plants with 14-foot cores.150