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 Plants Plant Name: Prairie Island Unit 2 Utility: Xcel Energy Date of Exams: 27NOV13 thru 03DEC13 Plant Age: 39 (years)/ 34 EFPY Primary Components 109 Prairie Island Unit 2 110 Prairie Island Unit 2 111 Prairie Island Unit 2 Not Inspected this outage 728 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 indications in the large, low-fluence platesThe extent of the bolt failures was bounded by minimum pattern analysis plus margin term per WCAP-1 7096 tommenis: 112 Prairie Island Unit 2 Not Inspected this outage 113 aPrairie Island Unit 2 Notes 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 be examined 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 be examined 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 2 Expansion Components Upper Internals Assembly Upper core plate Enhanced visual examination (EVT-1)100% of accessible surfaces (Note 2).Not Inspected this outage Comments: Lower Internals Enhanced visual 100% of accessible Assembly examination (EVT-1) surfaces (Note 2). Not Inspected this outage Lower support forging or castings See Figure 4-33 of MRP-227-A.Comments: 115 Prairie Island Unit 2 Ite E Required Examination Coverage Examination Coverage Achieved Findings (Note 1)Core Barrel Volumetric 100% of accessible bolts.Assembly examination (UT) Accessibility may be Not Inspected this outage Barrel-former bolts limited by presence of thermal shields or neutron pads (Note 2).See Figure 4-23 of MRP-227-A.Comments: Lower Support Volumetric 100% of accessible bolts Assembly examination (UT) or as supported by plant- Not Inspected this outage Lower support specific justification (Note column bolts 2).See Figures 4-32 and 4-33 of MRP-227-A.

Comments: 116 Prairie Island Unit 2 Core Barrel Assembly Core barrel outlet nozzle welds Enhanced visual examination (EVT-1)100% ot one side ot the accessible surfaces of the selected weld and adjacent base metal (Note 2).See Figure 4-22 of MRP-227-A.Not Inspected this outage Comments: Core Barrel Enhanced visual 100% of one side of the Assembly examination (EVT-1) accessible surfaces of the Not Inspected this outage Upper and lower core selected weld and barrel cylinder axial adjacent base metal (Note welds 2).See Figure 4-22 of MRP-227-A.Comments: 117 W-Prairie Island Unit 2 Item Examination Method Required Examination Cover-g Examination

...._ _Coverage Achieved Findings (Note 1)Lower Support Enhanced visual 100% of accessible Assembly examination (EVT-1) surfaces (Note 2). Not Inspected this outage Lower support column bodies See Figure 4-34 of MRP-(non cast) 227-A.Comments: Lower Support Enhanced visual 100% of accessible Assembly examination (EVT-1) support columns (Note 2). Not Inspected this outage Lower support column bodies See Figure 4-34 of MRP-(cast) 227-A.Comments: 118 Prairie Island Unit 2 Bottom Mounted Instrumentation System Bottom-mounted instrumentation (BMI)column bodies Visual examination (VT-3)100% of BMI column bodies for which difficulty is detected during flux thimble insertion/withdrawal.

Not Inspected this outage See 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 is required (including both the accessible and inaccessible portions).

119 Prairie Island Unit 2 Existing Programs Components 120 Prairie Island Unit 2 121 Prairie Island Unit 2 35 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 loss DONE IN CONJUNCTION WITH MRP-227-A RELATED EXAMS. *Not Inspected this outage 122 Prairie Island Unit 2 Notes 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 Plants Plant Name: Oconee Unit 2 Date of Exams: 10/12/2013 to 12/5/2013 Utility: Duke Energy Plant Age: 40 (years) / 31.82 EFPY Primary Components Comments:

The one-time physical measurement was performed in Fall 2008 with no evidence of wear occurring during service period 124 Oconee Unit 2 Comments: 100% No relevant Indications were There are 8 vent valves, noted on retaining rings.See Comment Section for relevant indications noted on other 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 parts of 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 of the 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 no evidence of movement.

Additionally, deformation was present on the center guide block of the right jack screw. The indications on Vent Valve XW were 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 no evidence of movement.

The indication on Vent Valve ZW was evaluated and left in place.125 Oconee Unit 2 Comments:

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 support assembly (CSA) stand. The bolts and locking devices are in place with no evidence of movement.

No Relevant Indications Noted.126 Oconee Unit 2 Comments:

Examination limitation was noted on Hex Head Baffle-to-Former Bolt (Quadrant

-Plate -Column -Elevation)

1. 3-3-2-3.

Probe did not seat correctly.

Due to the absence of UT information in two of four channels this bolt is classified as un-inspectable.

100% No relevant Indications were noted.Comments: 127 0 Comments: Oconee Unit 2 100% No relevant Indications were 864 baffle-to-former and 272 noted.internal baffle-to-baffle bolts.UT -- 100% UT -2 flow distributor bolts (#4 96 bolts inspected, and #48) with crack like indications.

VT -100% VT -No relevant Indications 96 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 2 Comments: 100% No relevant Indications were 52 spider castings, each noted.casting with 8 welds.Comments: 129 2 Oconee Unit 2 Notes to B&W Primary Component Table 1. 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 and that no abnormal degradation has occurred.

Examine the valves for evidence of scratches, pitting, embedded particles, leakage of the seating surfaces, cracking of lock welds 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 test programs (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 inspection credit.130 Oconee Unit 2 Expansion Components Upper Grid Assembly Alloy X-750 dowel-to-upper grid fuel assembly support pad welds Visual examination (V'-3)Accessible surfaces of 100% of the dowel locking welds.See Figure 4-6 of MRP-227-A (i.e., these are similar to the lower grid fuel assembly support pads).N/A Comments: Core Barrel Assembly Bolts: Volumetric 100% of accessible N/A Upper thermal shield (UTS) examination (UT). bolts or studs/nuts and bolts and their locking devices Locking Devices: their locking devices Visual examination (Note 2).(VT-3)See Figure 4-7 of MRP-227-A.Comments: 131 Oconee Unit 2 1!Examination Required Coverage Examination Exam intion Examination Achieved Findings (Note 1)....C ov er gCore Barrel Assembly Bolt or Stud/Nut:

100% of accessible N/A Surveillance specimen holder Volumetric bolts or studs/nuts and tube (SSHT) studs/nuts (CR- examination (UT). their locking devices 3) 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/A Lower grid fuel assembly (VT-3) the pads, dowels, and support pad items: pad, pad- cap screws, and to-rib section welds, Alloy X- associated welds in 750 dowel, cap screw, and 100% of the lower grid their locking welds fuel assembly support pads.See Figure 4-6 of MRP-227-A.Comments: 132 Oconee Unit 2 Lower Grid Assembly Alloy X-750 dowel-to-lower grid fuel assembly support pad welds Visual examination (VT-3)Accessible surfaces of 100% of the support pad dowel locking welds.N/A See Figure 4-6 of MRP-227-A.Comments: Lower Grid Assembly Bolts: Volumetric 100% of accessible N/A Lower grid shock pad bolts examination (UT). bolts and their locking and their locking devices Locking Devices: devices. (Note 2)Visual examination (VT-3) See Figure 4-4 of MRP-227-A.Comments: 133 Oconee Unit 2 V.n Required Coverage Examination eIemieation Examination Achieved Findings (Note 1)Lower Grid Assembly Bolts: Volumetric 100% of accessible N/A Lower thermal shield (LTS) examination (UT). bolts and their locking bolts (ANO-1, DB and TMI-1) Locking Devices: devices. (Note 2)or studs/nuts (ONS, CR-3) Visual examination and 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 2 Expansion Components Requiring Evaluation or Replacement In Lieu of Inspection ItemExaminationMethod Disposition3 Core Barrel Assembly No examination requirements.

Core barrel cylinder (including Justify by evaluation or by replacement.

vertical and circumferential seam welds)Former plates Comments: 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 external baffle-to-baffle bolts and core barrel-to-former bolts Comments: 135 4 I Tables for Reporting MRP-227-A Inspection Results for Westinghouse Plants Plant Name: Point Beach Nuclear Plant Unit 2 Date of Exams: March, 2014 (U2R33)Utility: NextEra Energy

-Plant Age: 41 (years) / 34 EFPY 1 I I Primary Components L;omments:

A VT-3 inspection and Guide Card Wear Measurements (GCWM) were completed on thirty-three (33) guide tubes, this being 100% of the rodded locations in the upper internals.

In total, fifty-one (51) recordable indications were identified during the guide card inspection, and all indications were analyzed by Westinghouse Engineering.

136 Point Beach Nuclear Plant Unit 2 Comments: An EVT-1 inspection of the upper and lower GT flange welds was completed on twenty-four (24) guide tubes around the periphery of the upper internals.

One-hundred eleven (111) welds were inspected to EVT-1 quality, and an additional fifty-two (52) welds were inspected, but EVT-1 quality was not demonstrated.

No recordable indications were identified during the GT flange weld inspection.

Not examined Comments: To be examined during U2R34 137 t Point Beach Nuclear Plant Unit 2 Comments: To be examined during U2R34 Not examined%.,OmIIfetFI5-To be examined during U2R34 138 Point Beach Nuclear Plant Unit 2 s.omments:

To be examined during U2R34 100% (727 -see below) 15 (< 3%) original bolts exhibited reportable ultrasonic indications.

All of the reported indications in the bolts were in the head to shank interface region (DHS).No reported indications in the replacement bolts Comments: 552 -original bolts. 175 -replacement bolts Total of 727 bolts. One bolt location does not contain a bolt 139 Point Beach Nuclear Plant Unit 2 I I%.I LA III I ICI I MO.To be examined during U2R34 V/A NUI I I I BII:1 n Ld.N/A -Point Beach Internals hold down spring is Type 403 SS 140 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 be examined 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 be examined 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 2 Expansion Components Exminon Mh Required Examination Coverage Examination,t E o Cov ge Achieved Findings (Note 1)Upper Internals Enhanced visual 100% of accessible Assembly examination (EVT-1) surfaces (Note 2). N/A Upper core plate Comments: Not required to be examined -CRGT lower flange welds -No recordable indications U2R33 Lower Internals Enhanced visual 100% of accessible N/A Assembly examination (EVT-1) surfaces (Note 2).Lower support forging or castings See Figure 4-33 of MRP-227-A.Comments: Not required to be examined -CRGT lower flange welds -

No recordable indications U2R33 142 Point Beach Nuclear Plant Unit 2 Core Barrel Assembly Barrel-former bolts Volumetric examination (UT)100% of +++accessible bolts. Accessibility may be limited by presence of thermal shields or neutron pads (Note 2).N/A See Figure 4-23 of MRP-227-A.Comments: Not required to be examined -baffle-former bolts -results do not require expansion

-U2R33 Lower Support Volumetric 100% of accessible bolts N/A Assembly examination (UT) or as supported by plant-Lower support specific justification (Note column bolts 2).See Figures 4-32 and 4-33 of MRP-227-A.

Comments: Not required to be examined -baffle-former bolts -results do not require expansion

-U2R33 4 143 Point Beach Nuclear Plant Unit 2 It Item. Exmination Method Required Examination Coverage Examination Coverage Achieved Findings (Note 1)Core Barrel Enhanced visual 100% of one side of the N/A Assembly examination (EVT-1) accessible surfaces of the Core barrel outlet selected weld and nozzle welds adjacent base metal (Note 2).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/A Assembly examination (EVT-1) accessible surfaces of the Upper and lower core selected weld and barrel cylinder axial adjacent base metal (Note welds 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 2 Lower Support Assembly Lower support column bodies Lnhanced visual examination (EVT-1)100u/% ot accessible surfaces (Note 2).N/A See 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/A Assembly examination (EVT-1) support columns (Note 2).Lower support column bodies See Figure 4-34 of MRP-(cast) 227-A.Comments: Not required to be examined -CRGT lower flange welds -No recordable indications U2R33 145 4 Point Beach Nuclear Plant Unit 2 Item ini Method Required Examination Coverage Examination C gExam e Achieved Findings (Note 1)Bottom Mounted Visual examination 100% of BMI column N/A Instrumentation (VT-3) bodies for which difficulty System is detected during flux Bottom-mounted thimble instrumentation (BMI) insertion/withdrawal.

column bodies See Figure 4-35 of MRP-227-A.Comments: Not required to be examined -CRGT lower flange welds -No recordable indications U2R33 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 is required (including both the accessible and inaccessible portions).

146 Point Beach Nuclear Plant Unit 2 Existing Programs Components L;omments:

ASME Section XI ISI Exam not performed during U2R33 N/A%,VIIIII~ltPII5.

ASME Section XA ISI Exam not performed during U2R33 147 14 Point Beach Nuclear Plant Unit 2 A e,U IIISeI XI I L.peu ASME Section Xl ISI Exam not performed during U2R33 N/A.;omments:

ASME Section XI ISI Exam not performed during U2R33 148 Point Beach Nuclear Plant Unit 2 ASME Section Xl ISI Exam not performed during U2R33*1*N/A Comments: ASME Section Xl ISI Exam not performed during U2R33 149 4 Point Beach Nuclear Plant Unit 2 N Notes to Westinghouse Existing Programs Components Table: 1. XL = "Extra Long" referring to Westinghouse plants with 14-foot cores.150