ML16144A789

Biennial Report of MRP-227-A Reactor Internals Inspection Results

ML16144A789
Person / Time
Site:	Palisades
Issue date:	05/18/2016
From:	Demma A, Rudell B Electric Power Research Institute
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
M RP 2016-008, PR030669
Download: ML16144A789 (92)

Text

-=~121 I ELECTRIC POWER

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RESEARCH INSTITUTE M RP Materials Reliability Program. ____________ M RP 2016-008 Date:

To:

May 18, 2016 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-001 From:

Bernie Rudell, Exelon, MRP Integration Chairman Anne Demma, EPRl, MRP Program Manager

Subject:

Biennial Report ofMRP-227-A Reactor Internals Inspection Results The purpose of this letter is to provide NRC staff members with a report of recent pressurized water reactor (PWR) utility inspection results as required by the Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A). Previous results were provided in EPRl letter MRP-2014-006.

Enclosed with this document are individual plant MRP-227-A inspection summary results from 2014-2015 using the report template provided by EPRl. Eight (8) U.S. domestic plants have submitted MRP-227-A reactor internals exam summary results reports in the past two calendar years.

If additional information is required, please contact Kyle Amberge (650-855-2039; kamberge@epri.com) or Anne Demma (650-855-2026; ademma@epri.com)

Sincerely,

/

• 7/C, ;~I//'

B. C. Rudell MRP Chairman Exelon Generation cc:

Joe Holonich, NRC MRP Assessment TAC MRP Integration Committee PMMP Executive Committee

Enclosure:

MRP-227 Inspection Results Together... Shaping the Future of Electricity PALO ALTO OFFICE AnneDemma MRP Program Manager Electric Power Research Institute 3420 Hillview Avenue, Palo Alto, CA 94304-1338 USA

• 650.855.2000

• Customer Service 800.313.377 4

• www.epri.com

ENCLOSURE TO MRP 2016-008 MRP-227 Related Inspections Performed from 2014-2015 Palisades - 2/2014, 26.1 EFPY Turkey Point 3 - 4/2014, 30 EFPY Oconee 3 - 4/2014, 31.7 EFPY Turkey Point 4 - 10/2014, 31 EFPY Prairie Island 1-10/2014, 34 EFPY Point Beach 2 - 10/2015, 35 EFPY Turkey Point 3 - 11/2015, 31.7 EFPY Prairie Island 2 - 11/2015, 35.5 EFPY Three Mile Island 1 - 11/2015, 30.4 EFPY Page 1of91

Intentionally Blank Page 2 of 91

Palisades, Feb. 2014 Tables for Reporting MRP-227-A Inspection Results for CE Plants Plant Name:__.P

........... al_is..... a_d_e....... s ______________ Utility: ___

E_n_t_e_rg..,y....__ ______________ _

Date of Exams: _ _.1..... /3""'""1'"-'-th_r...... u_2..... /2_1 __ /_20

...... 1_4 _______ Plant Age: __

4...... 3 _______ (years) I 26.1 EFPY Primary Components c

Core Shroud.... Volumetric 100% of accessible bolts (see N/A See Comments (Bolted) examination (UT)

Note 2). Heads are accessible Core shroud bolts from the core side. UT accessibility may be affected by complexity of head and locking device designs.

See Figure 4-24 of MRP-227-A of MRP-227-A.

Comments:

In accordance with MRP-227A and the Palisades Aging Management Plan examinations will be performed by 2022. (approximately 34.3 EFPY)

Page 3 of 91

Palisades, Feb. 2014 Core Shroud Assembly Enhanced visual Axial and horizontal weld seams N/A See Comments (Welded) examination (EVT-1) at the core shroud re-entrant Core shroud plate-former comers as visible from the core plate weld side of the shroud, within six inches of central flange and horizontal stiffeners.

See Figures 4-12 and 4-14 of MRP227-A.

Comments:

Not applicable to Palisades.

Cont roudA bly Enhanced visual Axial weld seams at the core N/A See Comments

- ~ -

examination (EVT-1) shroud re-entrant comers, at the I

Shroud plates core mid-plane (+/-three feet in height) as visible from the core side of the shroud.

See Figure 4-13 of MRP-227-A.

Comments:

Not applicable to Palisades.

Page 4 of 91

Core Shroud Assembly (Bolted)

Assembly Comments:

Visual examination (VT-3)

Core side surfaces as indicated.

See Figures 4-25 and 4-26 of MRP-227-A.

100%

Palisades, Feb. 2014 Slight gap in shroud plate at the shroud anchor bolt location for seam 4. All other seams acceptable. See Comments Gap was verified from original fabrication, deviation report DCR 9700101-8 Dated 12/31/68. As-built gap measured at.046". Based on photograph this does not appear to have changed. Examinations included 768 shroud to former bolts and 96 shroud to anchor bolts. One core shroud bolt seated different than all others with the locking bar slightly bent and opening on the right side.

Core Shroud Asurnbly (Welded)

Asaembty Comments:

Visual examination (VT-1)

Not Applicable to Palisades.

If a gap exists, make three to five N/ A measurements of gap opening from the core side at the core shroud re-entrant corners. Then, evaluate the sweHing on a plant-specific basis to determine frequency and method for additional examinations.

See Figures 4-12 and 4-14 of MRP-227-A.

Page 5 of 91 See Comments r

Palisades, Feb. 2014 I

Core Support Barrel Enhanced visual 100% of the accessible surfaces 100% Scan was performed No indications.

Assembly examination (EVT-1) of the upper flange weld (Note 3).

from the inside of the core Upper (core support barrel.

barre~ flange weld See Figure 4-15 of MRP-227-A.

Comments: N/A Core Support Barrel Enhanced visual 100% of the accessible surfaces The upper girth weld scan was No indications Assembly examination (EVT-1) of the lower cylinder welds (Note performed from the inside of Lower cylinder girth 3).

the barrel. Coverage achieved welds 100%.

See Figure 4-15 of MRP-227-A The middle girth weld scan No indications was performed from the outside of the core barrel.

Coverage achieved 86.67%.

The lower girth weld scan was No indications performed from outside the core barrel. Coverage achieved 76.67%.

Comments:

For Palisades the Lower Cylinder Girth Welds consist of three welds: the Upper Girth Weld; the Middle Girth Weld; and the Lower Girth Weld.

In the Wesdyne report these welds are incorrectly named. The report calls the Middle Girth Weld the Lower Girth Weld and calls the Lower Girth Weld the Lower Flange Weld.

Page 6 of 91

Palisades, Feb. 2014

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Lower upport Visual examination 100% of the accessible surfaces 96% See comments.

No indications.

Structure (VT-3) of the core support column welds Core support column (Note 4).

welds See Figures 4-16 and 4-31 of MRP-227-A Comments:

Approximately 4% inaccessible due to baffle plate periphery and no access hole for OD.

Core Support Barrel If fatigue life cannot Examination coverage to be N/A See Comments be demonstrated by defined by evaluation to Lower flange weld time-limited aging determine the potential location analysis (TLAA),

and extent of fatigue cracking.

enhanced visual (EVT-1) examination See Figures 4-15 and 4-16 of MRP-227-A.

Comments:

Not Applicable to Palisades.

Lower Support If fatigue life cannot Examination coverage to be 93% See comments No indications Structure be demonstrated by defined by evaluation to Core support plate time-limited aging determine the potential location analysis (TLAA),

and extent of fatigue cracking.

enhanced visual (EVT-1) examination See Figure 4-16 of MRP-227-A.

Comments:

Approximately 7% inaccessible due to baffle plate construction.

Page 7 of 91

Palisades, Feb. 2014

~ * '

Upper Internals If fatigue life cannot Examination coverage to be N/A See Comments Assembly be demonstrated by defined by evaluation to Fuel alignment plate time-limited aging determine the potential location analysis (TLAA),

and extent of fatigue cracking.

enhanced visual (EVT-1) examination See Figure 4-17 of MRP-227-A.

Comments:

Not Applicable to Palisades.

Control Element Visual examination 100% of tubes in peripheral CEA 15 locations around the Two guide tubes at locations Assembly (VT-3) shroud assemblies (i.e., those periphery of the upper guide 87 and G5 have slots in the Instrument guide tubes adjacent to the perimeter of the structure. 8 welds per guide tubes. Also, at location 87 fuel alignment plate).

tube. Coverage achieved there is an extra welded 100%

attachment to the tube with a See Figure 4-18 of MRP-227-A.

different style bracket.

Comments:

N/A Lower Support Enhanced visual Examine beam-to-beam welds, in N/A See Comments Structure examination (EVT-1) the axial elevation from the beam Deep beams top surface to four inches below.

See Figure 4-19 of MRP-227-A.

Page 8 of 91

Palisades, Feb. 2014 Comments:

Not applicable to Palisades.

Note to CE Primary Components Table:

1.

Examination acceptance criteria and expansion criteria for the CE components are in Table 5-2 of MRP-227-A.

2.

A minimum of 75% of the total population (examined+ unexamined), including coverage consistent with the Expansion criteria in Table 5-2 of MRP-227-A, must be examined for inspection credit.

3.

A minimum of 75% of the total weld length (examined + unexamined), including coverage consistent with the Expansion criteria in Table 5-2 of MRP-227-A, must be examined from either the inner or outer diameter for inspection credit.

4.

A minimum of 75% of the total population of core support column welds.

No EXPANSION components required inspections at Palisades during spring 201 4.

Page 9 of 91

Palisades, Feb. 2014 Existing Programs Components Required Coverage Examination Item Examination Method Examination Coverage Achieved Findings Core Shroud Assembly Visual examination Accessible surfaces at 100% the guide lugs have slight N/A Guide lugs (VT-3), general specified frequency.

wear. Some of the lock pins are condition examination protruding from the insets. One Guide lug inserts and for detection of bolt is loose but secure when the bolts excessive or core barrel is installed. See asymmetrical wear.

Comments.

Comments:

This condition was identified in 1995 and again in 2007. The condition has not changed.

Lower Support Visual examination Accessible surfaces at N/A See comments Structure (VT-3) to detect specified frequency.

Fuel alignment pins severed fuel alignment pins, (plants with core shrouds missing locking tabs, assembled with full-height or excessive wear on shroud plates) the fuel alignment pin nose or flange.

Comments:

The fuel alignment pins at Palisades are in the fuel bundles not in the lower core support plate.

Page 10 of 91

Palisades, Feb. 2014 Required Coverage Examination Item Examination Method Examination Achieved Findings Coverage Lower Support Visual examination Accessible surfaces at N/A N/A Structure (VT-3) specified frequency.

Fuel alignment pins (plants with core shrouds assembled in two vertical sections)

Comments:

Not applicable for Palisades.

Core Barrel Assembly Visual examination Area of the upper 100% coverage.

No signs of abnormal wear.

Upper flange (VT-3) flange potentially susceptible to wear.

Comments:

N/A Page 11 of 91

Intentionally Blank Page 12 of 91

Turkey Point Unit 3 SPRING 2014 Tab l es f'or Reporting MRP-227-A I n s pection Re s ul ts f'or West i ng h ouse P 1a nt s P lant Name: Turkey Point Unit 3 Utility: NextEra Energy/FPL Date of Exams: March-April 2014, PTN3-27RFO Plant Age: --"'4=2 __

__,_(y'--"e=a=-=rs:.L..) -'--/ --=3'-"0'---=E=F~P~Y Primary Components Conuo l R od G ulde Visual examination 20% examination of the Not inspected during N/A Tube Assembly (VT-3) number of CRGT assemblies, PTN3-27RFO.

Guide plates (cards) with all guide cards within Inspection planned for each selected CRGT PTN3-28RFO, Fall 2015 assembly examined.

See Figure 4-20 of MRP-227-A Commen t s:

Page 13 of 91

TurkevPoint Unit 3 SPRING 2014

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C o n tr o l Ro d Gu Ide Enhanced visual 100% of outer (accessible)

Not inspected during NIA T ub e Ass e m b ly examination (EVT-1)

CRGT lower flange weld PTN3-27RFO.

Lower flange welds to determine the surfaces and adjacent base Inspection planned for presence of crack-like metal on the individual PTN3-28RFO, Fall 2015 surface flaws in periphery CRGT assemblies.

flange welds (Note 2)

See Figure 4-21 of MRP-227-A.

Comments:

Co re Ba r r e l A sse mb l y Enhanced visual 100% of one side of the 100%

No Recordable Indications Upper core barrel flange examination (EVT-1) accessible surfaces of the weld selected weld and adjacent base metal (Note 4).

See Figure 4-22 of MRP-227-A.

Comments:

Page 14 of 91

Turkey Point Unit 3 SPRING 2014

~

Core B a r rel A ssembl y Enhanced visual 100% of one side of the Upper-100%

No Recordable Indications Upper and lower core examination (EVT-1) accessible surfaces of the barrel cylinder girth selected weld and adjacent Lower - 90.6%

No Recordable Indications welds base metal (Note 4).

See Figure 4-22 of MRP-227-A Comments:

Core B errel Aase m bly Enhanced visual 100% of one side of the 90.5%

No Recordable Indications Lower core barrel flange examination (EVT-1) accessible surfaces of the weld (Note 5) selected weld and adjacent base metal (Note 4).

Comments:

Page 15 of 91

Turkey Point Unit 3 SPRING 2014 Barfle-Former Visual examination Bolts and locking devices on Not inspected during N/A A ssem bly (VT-3) high fluence seams. 100% of PTN3-27RFO.

Baffle-edge bolts components accessible from Inspection planned for core side PTN3-28RFO, Fall 2015 (Note 3).

See Figure 4-23 of MRP-227-A.

Comment s:

Barrie-Form er Volumetric 100% of accessible bolts Not inspected during N/A Assembly examination (Un (Note 3). Heads accessible PTN3-27RFO.

Baffle-former bolts from the core side. UT Inspection planned for accessibility may be affected PTN3-28RFO, Fall 2015 by complexity of head and locking device designs.

See Figures 4-23 and 4-24 of MRP-227-A.

Comments:

Page 16 of 91

B err1e-F or m e r Asse mb l y Assembly

{Includes: Baffle plates, baffle edge bolts and indirect effects of void swellino in former plates)

Comments:

A11gnment. e n d Jn~erf'act n g C o mponer.ts Internals hold down spring Visual examination (VT-3)

Direct measurement of spring height Core side surface as indicated.

See Figures 4-24, 4-25, 4-26 and 4-27 of MRP-227-A.

100%

Measurements should be 100%

taken at several points around the circumference of the spring, with a statistically adequate number of measurements at each point to minimize uncertainty.

See Figure 4-28 of MRP-227-A.

TurkevPoint Unit 3 SPRING 2014 No Recordable Indications SAT Commen t s: Measurements taken at eight circumferential positions. All exceeded the minimum height criteria for 60 years of operation.

Page 17 of 91

Turkev Point Unit 3 SP RING 2014 f

T her m e 1 Sh1 e 1d Visual examination 100% of thermal shield 100%

No Recordable Indications A ss emb l y (VT-3) flexures.

Thermal shield flexures See Figures 4-29 and 4-36 of MRP-227-A.

Comments:

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.

No EXPANSION components were inspected at Turkey Point 3 during spring 2014.

Page 18 of 91

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Turkey Point Unit 3 SPRING 2014 Existing P rog r ams Components Examination Req u i r ed C overage Exa m i n ati on lte m Method E xaminstlon Ac h laved Fi ndings Coverage Co r e Barre l A sse mbl y Visual examination All accessible 100%

A significant impression and a Core barrel flange (VT-3) to determine surfaces at specified minor arc-shaped impression were general condition frequency.

identified on the underside surface for excessive wear.

of the CBF at the 25-degree location, and a significant impression was identified at the 240-degree location. The impressions appear to have been caused by foreign material (FM) trapped between the underside surface of the CBF and its mating surface, the top side of the CSL.

Comme nt s: The two impression appear to have been caused by (FM) trapped between the two mating surfaces. The impressions are highly localized and not expected to affect the functionality and bearing area of these surfaces Upper I nterna l s Visual examination All accessible 100%

No Recordable Indications Assembly (VT-3) surfaces at specified Upper support ring or frequency.

skirt Com m e n ts :

Page 19 of91

Turkey Point Unit 3 SPRING 2014 Ex a mination Req ulred Coverage Exam i n a tion lt e m Method Ex a m i n a tion Ac h 1oved F1nd l n gs Cov e rag e Lowe r I nt e r nals Visual (VT-3)

All accessible 100%

No Recordable Indications Assemb l y examination of the surfaces at specified Lower core plate lower core plates to frequency.

XL lower core plate detect evidence of (Note 1) distortion and/or loss of bolt integrity.

Comme nt s'.

Lower Internals Visual examination All accessible 100%

No Recordable Indications Assembly (VT-3) surfaces at specified Lower core plate frequency.

XL lower core plate (Note 1)

Com m e nt s:

Page 20 of 91

Turkey Point Unit 3 SPRING 2014 Ex a m i na ti on Req u lre d Cov e r a ge Exam i n a t i on lte m Method E xa m i n a t i on Ac h la v ed Find ing s Cov era g e B o ttom M o u nt ed Surface Eddy current surface Replaced seven thimble tubes Seven thimble tubes successfully I n s t r um e nt. a ti o n examination (ET) examination as during PTN3-27RFO replaced.

Syste m defined in plant Flux thimble tubes response to IEB 88-

09.

Comme n ts:

Alignment and Visual examination All accessible 100%

Abrasive wear noted on bolts and I nterfacing (VT-3) surfaces at specified lock bars at 270° key and clevis.

Compone n ts frequency.

Degradation attributed to foreign Clevis insert bolts material, possibly an RCP diffuser adapter cap screw, retrieved during previous RFO.

Comm e nt:s *The degradation does not affect the structural integrity or functionality of the radial support structure.

Page 21 of 91

Turkey Point Unit 3 SPRING 201 4 Examination Required Coverage Examination lte m Method Ex a m i nation Achieved Find ings Cover a ge A1ign m e n tond Visual examination All accessible 100%

No Recordable Indications I nter f acing (VT-3) surfaces at specified Components frequency.

Upper core plate alignment pins Comments:

Notes to Westinghouse Existing Programs Components Table:

1.

XL= "Extra Long" referring to Westinghouse plants with 14-foot cores.

Page 22 of 91

Tab l es for Reporting MRP-227-A I n s pection Resu lts for B&W P1 a n ts Plant Name:

Oconee Unit 3 _______ Utility:

Duke Energy Date of Exams: 4/14/2014 to 5/14/2014 Plant Age: ___

4_0 __ (years) I --'-3_1.~67-'--- EFPY Primary Components p,.,...,... C."... A..**ml>*y &

Core S.,,.,... c: S,. e,io Assembly Plenum coverwe1dment rib pads Plenum cover eupport flange css top flltnOe One-time phys1cat meeaurement (initial Inspection)

Visual (VT-3) for subsequent inspections Determiftetioft of diffeMnttal height of top of plenum rib pads to reactor vessel Hating.urt.ce, with plenum in reactor vellel.

See Figure 4-1 of MRP-227-A.

Measurement performed in 2007 VT-3 100%

Oconee 3 Spring 2014 No relevant Indications were noted.

No relevant Indications were noted.

Comments: The one-time physical measurement was performed in Fall 2007 with no evidence of wear occurring during service period Page 23 of 91

Oconee 3 Spring 2014 Contro l Rod Guld e Tu be Visual (VT-3)

Accessible surfaces at 100%

No relevant Indications were A sse mbly each of the 4 screw 690 castings with 4 screws noted.

CRGT spacer castings locations (at every 90°) of each.

100% of the CRGT spacer castings (limited accessibility).

See Figure 4-5 of MRP-227-A.

Com m e n ts:

Core S uppor1: Shl eld Visual (VT-3) 100% of accessible 100%

No relevant Indications were A ss embly surfaces There are 8 vent valves.

noted on retaining rings.

CSS vent valve top retaining (see BAW-2248A, page ring 4.3 and Table 4-1).

See Comment Section for css vent valve bottom relevant indications noted on retaining ring See Figure 4-11 of MRP-other CSS vent valve parts.

(Note 1}

227-A.

Com ments: 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 XI, Category B-N-3 VT-3 examination. No vent valve replacements were necessary.

Vent Valve XW - The right side jack screw locking cup crimps indicate that the jack screw has rotated slightly, pushing the locking crimps outward.

The jack screw insert in the in the right side guide block was tilted and there was gouging at both corners of the guide block.

Vent Valve ZW - Relevant indications on the inside crimps of both the right and left side locking cups.

Vent Valve XY - Relevant Indications in the form of gouges were identified on the left and right jacking screw guide blocks.

Vent Valve ZY - Relevant indications on the outside crimp of the right side locking cup.

Vent Valve WZ - The spring loaded locking devices of both the left and right jacking screws were not shown as engaged.

Page 24 of 91

Oconee 3 Spring 2014

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J Core S upport S h1e 1d Volumetric 100% of accessible bolts 100% UT performed in 2007 No recordable indications were Assembly examination (UT) of and their locking devices.

(120 UCB bolts) detected in 118 of the 120 UCB Upper core barrel (UCB) the bolts (Note 3) bolts. Bolts #10 and #85 had bolts and their locking no UT back wall response devices similar to previous inspections.(1984, 1985 and 1987).

Visual (VT-3)

See Figure 4-7 of MRP-VT-3 100% performed this No relevant Indications were examination of bolt 227-A.

outage (120 locking devices) locking devices noted.

Com m ents:

Core B erre l A ssemb l y Volumetric 100% of accessible bolts 100% - 1 08 oolts UT - 3 lower core barrel bolt Lower core barrel (LCB) examination (UT) of and their locking devices with crack like indications (#15, bolts and their locking the bolts (Note 3)

1. 91 and #100). These same devices bolts were identified with indications in 1987.

Visual (VT-3)

See Figure 4-8 of M~P-100% - 108 bolts and locking examination of bolt 227-A.

devices.

VT - No relevant indications locking devices Comme n ts: The indication is located in the bolt head-to-shank region.

Page 25 of 91

Oconee 3 Spring 2014

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Core Berre l Assembly Volumetric 100% of accessible bolts.

863 out of 864 One crack like indication was Baffle-to-former bolts examination (UT)

(Note 3) detected on bolt# 2-1-2-6 See Figure 4-2 of MRP-1 baffle-to-former bolt was 1 un-inspectable, bolt #2-7-1-3 227-A.

un-inspectable due to probe not seating correctly.

Cam m e nt s : Examination limitation was noted on Hex Head Baffle-to-Former Bolt (Quadrant - Plate - Column - Elevation) #2-7-1-3. Probe did not seat correctly.

The indication on bolt #2-1-2-6 is located in the bolt head-to-shank region.

Core Barrel Assembly Visual examination 100% of the accessible 100%

No relevant Indications were Baffle plates (VT-3) surface within 1 inch noted.

around each flow and bolt hole.

See Figure 4-2 of MRP-227-A.

Com m ent: s:

Page 26 of 91

C ore B *rrel A ssem bly Locking devices, including locking welds, of baffle-to-former bob and internal baffle-to..baft bolts Com m e n ts:

F1ow D 1str1but o rAsse m bl y Flow d'rstributor (FD) bolts and their locking devices Visual examination (VT-3)

Volumetric examination (UT} of the bolts Visual (VT-3) examination of bolt locking devices 100% of accessible baffle-to-former and internal baffle-to-baffle bolt locking devices. (Note 3)

See Figure 4-2 of MRP-227-A.

100% of accessible bolts and their locking devices.

(Note 3)

See Figure 4-8 of MRP-227-A.

100%

864 baffle-to-former and 272 internal baffle-to-baffle bolts.

UT --100%

96 bolts inspected.

VT-100%

96 bolts and their locking devices inspected.

Recordable UT indication detected in FD Bolt #87 located in the bolt head-to-shank region.

Oconee 3 Spring 2014 No relevant Indications were noted.

UT - 1 flow distributor bolts

(#87) with crack like indications.

VT - No relevant Indications were noted.

84 Flow distributor bolts were inspected in 1987 and bolt #88 was identified with an indication. There was likely a mix-up in numbering in 1987.

Lower G rid A ssembl y Alloy X-750 dowel-to-guide block welds Visual examination (VT-3)

Accessible surfaces of 100% of the 24 dowel-to-guide block welds.

See Figure 4-4 of MRP-227-A.

100%

24 dowel-to-guide blocks welds.

No relevant Indications.

Cam m e n ts: Guide block W9R is bent outward away from the lower grid shell forging and rotated slightly. Welds to the dowel and bolting are intact.

Marks on the guide block and core barrel stand leg indicate that the damage may have occurred during a previous outage when setting the core barrel in the stand.

Page 27 of 91

Oconee 3 Spring 2014 i

I n c or e Mon ito ri ng Visual examination 100% of top surfaces of 52 100%

IMI Guide Tube Spider Casting In strum entation (IMI)

(VT-3) spider castings and welds 52 spider castings, each Weld 88-YL had a linear Guide Tu be As sem bly to the adjacent lower grid casting with 8 welds.

indication located just below the IMI guide tube spiders rib section.

vertical weld toe in the base IMI guide tube spider-to-material of the lower grid.

lower grid rib section welds See Figures 4-3 and 4-6 of MRP-227-A.

IMI Guide Tube Spider Casting Weld G 11-WR had a linear indication coming from the top of the casting at the weld toe and going downward into the casting material.

Comment s:

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.

No EXPANSION components were inspected during spring 2014.

Page 28 of 91

• =

Turkey Point 4, Sept.2014 Tables ror R e port i n g MRP-227-A I n s pection Re s ult s ror West i n g h o u se P1ants Plant Name: Turkey Point Unit 4 Utility: NextEra Energy/FPL Date of Exams: September-October 2014, PTN4-28RFO Plant Age: __

4_1 __

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E~F~P~Y Primary Components Control Rod Gulde Tube Assembly Guide plates (can:la)

Comments:

Visual examination (VT-3) 20% examination of the number of CRGT assemblies, with all guide cards within each selected CRGT assembly examined.

See Figure 4-20 of MRP-227-A Page 29 of 91 Not inspected during N/A PTN4-28RFO.

Inspection planned for PTN4-29RFO,Spring2016

Turkey Point 4, Sept.2014

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l' Control Rod Guld e Enhanced visual 100% of outer (accessible)

Not inspected during N/A Tub e Assembly examination (EVT-1)

CRGT lower flange weld PTN4-28RFO.

Lower flange welds to determine the surfaces and adjacent base Inspection planned for presence of crack-like metal on the individual PTN4-29RFO. Spring surface flaws in periphery CRGT assemblies.

2016 flange welds (Note 2)

See Figure 4-21 of MRP-227-A.

Comments:

Core Barrel A ssembly Enhanced visual 100% of one side of the 100%

No Recordable Indications Upper core barrel flange examination (EVT-1) accessible surfaces of the weld selected weld and adjacent base metal (Note 4).

See Figure 4-22 of MRP-227-A.

Comments:

Page 30 of 91

Core B*rret As** m loll!'

Upper ancil IGwef'CGR barret cylinder girth welds Co mment s:

Enhanced visual examination (EVT-1)

Core Barre* A ** em i.1:v Enhanced visual Lower core barrel flange examination (EVT-1) weld (Note 5)

Co mment s :

100% of one 'Side of the accessible surfaces of the selected weld and adjacent base metal (Note 4).

See Figure 4-22 of MRP-227-A 100% of one side of the accessible surfaces of the

&elected weld and adjacent bne metal (Note 4).

Page 31 of 91 Upper-100%

Lower-89%

85%

Turkey Point 4, Sept.2014 No Recordable Indications No Recordable Indications No Recordable Indications

Turkey Point 4, Sept.2014

~*

Barr1a-F or mer Visual examination Bolts and locking devices on Not inspected during N/A Assembly (VT-3) high fluence seams. 100% of PTN4-28RFO.

Baffle-edge bolts components accessible from Inspection planned for core side PTN4-30RFO, Fall 2017 (Note 3).

See Figure 4-23 of MRP-227-A.

Comments:

Barrte-F or mer Volumetric 100% of accessible bolts Not inspected during N/A Assembly examination (UT)

(Note 3). Heads accessible PTN4-28RFO.

Baffle..fonner bolts from the core side. UT Inspection planned for accessibility may be affected PTN4-30RFO, Fall 2017 by complexity of head and locking device designs.

See Figures 4-23 and 4-24 of MRP-227-A.

Comments:

Page 32 of 91

B aN'la-Form aT A,..e m bty Assembly (Includes: Baffle plates, baffle edge bolt& and indirect effects of void swellin in fonner lates Comments:

A11g nm e nt an d lnter,ecf n g Compone'ftt.*

Internals hOld down spring Direct measurement of spring height See Figures 4-24, 4-25, 4-26 and 4-27 of MRP-227-A.

100%

Measurements should be 1 00%

taken at several points around the circumference of the spring, wlh 8 statistically adequete number of meaaurements at each point to minimize uncertainty.

See Figure 4-28 of MRP-227-A.

Turkey Point 4, Sept.2014 No Recordable Indications SAT Co m m e nt s

• Measurements taken at eight circumferential positions. All exceeded the minimum height criteria for 60 years of operation.

Page 33 of 91

Comments:

Notes to Westinghouse Primary Components Table:

See Figures 4-29 and 4-36 of MRP-227-A.

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.

Turkey Point 4, Sept.2014

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.

No EXPANSION components were inspected during fall 2014.

Page 34 of 91

Turkey Point 4, Sept.2014 Existin g P rog r ams Co m pone n ts Ex a m In a ti o n Re q uired Coverage E x a m i n ati on Item Meth o d Exam i nati on A ch i eved Findi n gs Coverage Core B a rrel Ass e m b l y Visual examination All accessible 100%

No Recordable Indications Core barrel flange (VT-3) to determine surfaces at specified general condition frequency.

for excessive wear.

Comme nt s:

upper l n 't. er n a l s Visual examination All accessible 100%

No Recordable Indications A ss e m b l y (VT-3) surfaces at specified Upper support ring or frequency.

skirt Comme n ts:

Page 35 of 91

Turkey Point 4, Sept.2014 Exe m lnatl on Req ulred Cov ere g e Ex a m f n etlon Ite m Meth od E

>e a m l n a tlon Ac h la ved Fin dings Co v erage Lo\\Ner I nternals Visual (VT-3)

All accessible 100%

No Recordable Indications Assemb l y examination of the surfaces at specified Lower core plate lower core plates to frequency.

XL lower core plate detect evidence of (Note 1) distortion and/or loss of bolt integrity.

Comments:

Lo\\Ner I nternals Visual examination All accessible 100%

No Recordable Indications Assembly (VT-3) surfaces at specified Lower core plate frequency.

XL lower core plate (Note 1)

Comments:

Bottom Mou nt.e d Surface Eddy current surface N/A N/A lnst.ru mentation examination (ET) examination as System defined in plant Flux thimble tubes response to IEB 88-

09.

Page 36 of 91

Turkey Point 4, Sept.2014 Examination Req ulred Coverage Examination lte m Meth o d E xamination Ac h la v ed Fin d i n gs Coverage Comments:

A1ignmentand Visual examination All accessible 100%

No Recordable Indications I nterfacing (VT-3) surfaces at specified Components frequency.

Clevis insert bolts Com m e nt s:

Alignment and Visual examination All accessible 100%

No Recordable Indications I nterfacing (VT-3) surfaces at specified Compone nts frequency.

Upper core plate alicinment pins Comments:

Page 37 of 91

Turkey Point 4, Sept.2014 Notes to Westinghouse Existing Programs Components Table:

l.

XL= "Extra Long" referring to Westinghouse plants with 14-foot cores.

Page 38 of 91

Prairie Island 1, Oct. 2014 Tables for Reporting MRP-227-A Inspection Results for Westinghouse Plants Plant Name:

Prairie Island Unit 1 Utility: Xcel Energy Date of Exams: October 2014 Plant Age: ____

4.... l ___ (years) I Primary Components Comments:

See Figure 4-20 of MRP-227-A Page 39 of 91 34 EFPY Not Inspected this outage

Control Rod Gulde Tube Assembly Lower flange welds Comments:

Enhanced visual 100% of outer (accessible) examination (EVT-1)

CRGT lower flange weld to determine the surfaces and adjacent base presence of crack-like metal on the individual surface flaws in periphery CRGT assemblies.

flange welds (Note 2)

See Figure 4-21 of MRP-227-A.

Core Barrel Assembly Enhanced visual Upper core barrel ftange examination (EVT-1) weld 100% of one side of the accessible surfaces of the selected weld and adjacent base metal (Note 4).

Comments:

See Figure 4-22 of MRP-227-A.

Page 40 of 91 Prairie Island 1, Oct. 2014 Not Inspected this outage 100%

No Relevant Indications

Prairie Island 1, Oct. 2014 Core Barrel A... mbly Enhanced visual 100% of one side of the Upper and lower core examination (EVT-1) accessible surfaces of the 100% UGW barrel cyHnder girth selected weld and adjacent 76.5% LGW No Relevant Indications welds base metal (Note 4).

See Figure 4-22 of MRP-227-A Comments:

Corf Barret~ Enhanced visual 100% of one side of the La.nr core bl!R"et-lange examination (EVT-1) acceaaible surfaces of the 100%

No Relevant Indications weld (Net* 5) selected weld and adjacent base metal (Note 4).

Comments:

Page 41 of 91

Baffle-Former Assembly Baffle-edge bolts Comments:

Baffle-Former Assembly Baffle-former bob Comments:

Visual examination (VT-3)

Volumetric examination (UT)

(See attached map.)

Bolts and locking devices on high fluence seams. 100% of 1 00%

components accessible from core side (Note 3).

See Figure 4-23 of MRP-227-A.

100% of accessible bolts (Note 3). Heads accessible 728 out of 728 bolts from the core side. UT accessibility may be affected by complexity of head and locking device designs.

See Figures 4-23 and 4-24 of MRP-227-A.

Page 42 of 91 Prairie Island 1, Oct. 2014 No Relevant Indications 40 bolts with indications.

688 bolts had no indications.

No expansion was triggered.

The extent of the bolt failures was bounded by minimum pattern analysis plus margin term per WCAP-17096

Prairie Island BFB Phased Array UT Indication Map G *************

status of 10-23-14 09:38 AM 0

@Ii 90° C§J G

Prairie Island 1, Oct. 2014 GJ

~ 180° F ** ** ****************** * *********** * *****************

E B *********************************** * ***************

A *** * ***** ** *********************** * *****************

G F

E D

c B

A 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 180°~ ~

~

@::1 360°

• • • ** **** ** ** ** * * **** ** 1eee * ** * * **** ** ** ** ** **** ** ***

• • • ** **** ** ** ** ** **** ** I*** * ** ** **** ** ** ** ** **** ** ***

• • • ** **** ** ** ** ** **** ** I*** * ** ** **** ** ** ** ** **** ** ***

53 54 55 56 57 58 59 60 61 62 63 G4 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 0 acquisition to do e no acquisition 0 acquisition ok 0 retest e without indication e with indication Page 43 of 91 not testable (UT)

Baffle..Former V1&ual examination Core side surface as Assembly (VT-3) indicated.

1 00%

Assembly (Includes: Baffle plates, See Figures 4-24, 4-25, 4-26 baffle edge bolts and and 4-27 of MRP-227 -A.

indirect effects of void sweDin in former lates Comments:

AUgnment and holddt>wn Comments:

Direct measurement of~height Measurements should be taken at several points Not Applicable (403SS) around -the circumference of the spring, with a statistically adequate number of measurement$ at each point to minimize uncertainty.

See Figure 4-28 of MRP-227-A Page 44 of 91 Prairie Island 1, Oct. 2014 No Relevant Indications

Comments:

Notes to Westinghouse Primary Components Table:

100% of thermal shield flexures.

See Figures 28 and '4-38 of MRP-227-A.

100%

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.

Prairie Island 1, Oct. 2014 No Relevant Indications

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.

No EXPANSION components were inspected during fall 2014.

Page 45 of 91

Prairie Island 1, Oct. 2014 Existing Programs Components Examination Required Coverage Examination Item Method Examination Achieved Findings Coveraae Core Barrel Assembly Visual examination All accessible Core barrel flange (VT-3) to determine surfaces at specified 100%

No Relevant Indications general condition frequency.

for excessive wear.

Comments:

Upper Internals Visual examination All accessible Assembly (VT-3) surfaces at specified 100%

No Relevant Indications Upper support ring or frequency.

skirt Comments:

Page 46 of 91

Prairie Island 1, Oct. 2014 Examination Required Coverage Examination Item Method Examination Achieved Findings Coverane Lower Internals Visual (VT-3)

All accessible Assembly examination of the surfaces at specified 100% of Accessible Surface No Relevant Indications Lower core plate lower core plates to frequency.

XL lower core plate detect evidence of (Note 1) distortion and/or loss of bolt integrity.

Comments:

Lower Internals Visual examination All accessible Assembly (VT-3) surfaces at specified 100% of Accessible Surface No Relevant Indications Lower core plate frequency.

XL lower core plate (Note 1)

Comments:

Page 47 of 91

Prairie Island 1, Oct. 2014 Examination Required Coverage Examination Item Method Examination Achieved Findings Coveraae Bottom Mounted Surface Eddy current surface Instrumentation examination (ET) examination as 35 out of 36 flux thimble tubes 6 tubes with wall loss 40-59%

System defined in plant (one has an internal restriction 18 tubes with wall loss 20-39%

Flux thimble tubes response to IEB 88-due to having been bent and is 1 tube with wall loss 1-19%

09.

capped off) 10 tubes with no wall loss Comments: ***REPORT UPON THESE INSPECTIONS ONLY WHEN DONE IN CONJUNCTION WITH MRP-227-A RELATED EXAMS. ***

Alignment and Visual examination All accessible Interfacing (VT-3) surfaces at specified 100%

No Relevant Indications Components frequency.

Clevis insert bolts Comments:

Page 48 of 91

Prairie Island 1, Oct. 2014 Examination Required Coverage Examination Item Method Examination Achieved Findings Coveraae Alignment and Visual examination All accessible Interfacing (VT-3) surfaces at specified 100%

No Relevant Indications Components frequency.

Upper core plate alionment pins Comments:

Notes to Westinghouse Existing Programs Components Table:

1.

XL= "Extra Long" referring to Westinghouse plants with 14-foot cores.

Page 49 of 91

Intentionally Blank Page 50 of 91

Point Beach 2, Oct.2015 Tab l es for R e po r ting MRP-227 - A In s p ec t i o n R es u lt s fo r We st i ngho u se P 1a nt s Plant N ame: _ __.P--..o.... in.... t_.B._e.... a.... c_h_N_u_c_le_a_r_P_l_a_n_t_U_n_1_* t_2 __ Utility:

N extEra Energy Date of Exams: __

O"-c"'"'t-..o.....

b.._er.....,_2_...0 __ 1s ___ __._CU.._2_R3_4_.)..__ ____ Plant Age: __

4_3 ______ (years) / _:::::_3...... S __ EFPY Primary Components Contr ol R oct GulCI*

Tut>eA*a*mbly Guide.,.... (carda)

Co m m en't.s:

Visual examination (VT-3) 200.4 examination of the number of CRGT assemblies, with all guide cards within each selected CRGT assembly examined.

See Figure +.20 of MRP-227-A 100% of the CRGT assemblies (COMPLETED DURING U2R33 - REPORTED APRIL 2014)

See below 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.

Page 51 of 91

Point Beach 2, Oct.2015 Con u ol R od G ulde Tube A ssembl y Enhanced visual 100% of outer (accessible) 100% of outer CRGT No recordable indications Lower flange welds Comments'.

examination (EVT-1}

CRGT lower flange weld lower flange welds and to determine the surfaces and adjacent base adjacent base metal presence of crack-like metal on the individual surface flaws in periphery CRGT assemblies.

flange welds (Note 2)

(COMPLETED DURING U2R33 - REPORTED SeeFigure4-21 ofMRP-227-APRIL 2014)

A.

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.

Cor e Barre 1 A ss e m b1y Enhanced visual Upper core barrel flange examination (EVT-1) weld Comments:

Exterior surface 100% of one side of the accessible surfaces of the selected weld and adjacent base metal (Note 4).

See Figure 4-22 of MRP-227-A.

Page 52 of 91 100% of Weld Length No indications

Cor* 8.,.,

Upper and tower core barrel cylinder girth welds Comments:

Exterio r s u rface Enhanced Yiewal examination (EVT-1)

See Figure 4-22 of MRP-227-A 100% of Upper Core Barrel Cylinder Girth Weld Length 55.6% of Lower Core Barrel Cylinder Girth Weld Length Point Beach 2, Oct.2015 Lo\\Ner Core Barre1 Cy 1inder Girth We 1d 1s behind the Therme 1 Shie l d. The 9 ap between in side surface of the therma l sh1e 1d and outside su rf ace of the core barre l limited access to the entire we l d.

100% of th e 1ength of the Upper Care Barr e l Cy1inder Gi rth Wc1d + 55.6% of the 1e ngt h of the Lovver Care Barre l Cy 11n der Girth Weict We re Ex a m; n e d I 2 We I ds :::: 78% of total weld length (Greater than 75% minimum of the total weld length)

Core B a r.rel A aaa m bty Lower CCR~-.

weld (Note 6)

Com m e nt s'.

Exterior su r face Enhanced visual emnination (EVT-1) 100% of one side of the accesai>le surfacesofthe selected weld 8l'ld adjacent base metal (Note 4).

Page 53 of 91 100% of Weld Length No indications

Point Beach 2, Oct.2015 it..

Barr1e-F or mer Visual examination Bolts and locking devices on 100% of Baffle Edge No indications A* **mt>1,,

(VT-3) high fluence seams. 100% of Bolts Baffle..edge bolts components accessible from core side (Note 3).

See Figure 4-23 of MRP-227-A.

Co mment s :

B affle -Form er Volumetric 100% of accessible bolts 100% (727 - see below) 15 (< 3%) original bolts exhibited A *sem bly examination (UT)

(Note 3). Heads accessible repo1table ultrasonic indications.

Baffle..fonner bolts from the core side. UT (COMPLETED DURING All of the reported indications in the accessibility may be affected U2R33 - REPORTED bolts were in the head to shank by complexity of head and APRIL 2014) locking device designs.

interface region (OHS).

See Figures 4-23 and 4-24 of No reported indications in the MRP-227-A.

replacement bolts Co mment s :

552 - original bolts. 175 - replacement bolts Total of 727 bolts. One bolt location does not contain a bolt Page 54 of 91

A as em bly Assembly

{Includes: Baffle plates, baffle edge bolts and indirect effects of void sweUi in fonner lates A11 g n m

• nt a n d lnterf'acl.. g Co.,.,...,,..,.ta

.,,....bald spring Comments :

Direct measurement of spring height See Figures 4-24, 4-25, 4-26 and 4-27 of MRP-227-A.

Measurements should be N/ A taken at several points around 1he circumference of the spring, with a atatisticaHy adequate number of measURMnents at each point to minimize uncertainty.

See Figure 4-28 of MRP-227-A.

N/A -

Point Beach I nternals hold dovvn spring Is Type 403 SS Page 55 of 91 Point Beach 2, Oct.201 5

Comments:

6Therma1 Sh1e1d F1exures Notes to Westinghouse Primary Components Table:

See Figures 4-28 and 4-36 of MRP-227-A.

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.

Point Beach 2, Oct.2015

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.

No EXPANSION components were inspected durfing fall 2015.

Page 56 of 91

Point Beach 2, Oct.2015 Existing Prog r ams Components Examinetlon Req ulred Cover*ge Examination lt:em Method Exam i nat: l on Ach ie ved Findings Coverag e Core B ar r e l A sse mb l y Visual examination All accessible Core barrel flange (VT-3) to determine surfaces at specified N/A general condition frequency.

for excessive wear.

Comments:

ASM E Section XJ \\S J Exam not pe rformed during LJ2R33 or LJ 2R34 Upper I n t e rnal s Visual examination All accessible Ass embly (VT-3) surfaces at specified Upper support ring or frequency.

N/A skirt Comments:

ASM E Section XJ ISi Exam not perfo r med during LJ2R33 or LJ2R34 Page 57 of 91

Point Beach 2, Oct.2015 Exami n ation Required C ovarege Exeml n etlo n lum Method Examination Achieved Ftndlngs Coverage Lovvc r I nter n a l s Visual (VT-3)

All accessible Assembly examination of the surfaces at specified Lower core plate lower core plates to frequency.

N/A XL lower core plate detect evidence of (Note 1) distortion and/or loss of bolt integrity.

Commenr:s:

ASME Section XI ISi Exam not pe rformed during LJ2R33 or LJ2R34 Lovve r Int e rn a l s Visual examination All accessible Assemb ly (VT-3) surfaces at specified Lower core plate frequency.

XL lower core plate N/A (Note 1)

Comments :

ASM E Section XI ISi Exam not performed during LJ2R33 or LJ2 R34 Page 58 of 91

Point Beach 2, Oct.2015 Ex a m i neition Required Cov e rage Examinati on Item Method Ex a m ination Achie v ed Findings Coverage Bott om M o unt e d Surface Eddy current surface I n s t r u men ta t i on examination (ET) examination as Sy s tem defined in plant N/A Flux thimble tubes response to IEB 88-

09.

Comments:

ASME Section XI ISi Exam not performed during LJ2R33 or LJ2R34 A1 i g n m e n t a n d Visual examination All accessible 100%

No recordable indications I nterfacing (VT-3) surfaces at specified Compone nt s frequency.

Clevis insert bolts Comment:.s:

Page 59 of 91

Point Beach 2, Oct.2015 Exam 1 nation Req u ir ed C overage Exemlnatlon Item Method Exam In atlo n Achie v ed Findings Coverage A

11g n mc n t.an d Visual examination All accessible N/A l nt.e r facing (VT-3) surfaces at specified Componenr:s frequency.

Upper core plate alionment pins Comments:

ASME Section XI ISi Exam not pe rformed during LJ2R33 or LJ2R34 Notes to Westinghouse Existing Programs Components Table:

1.

XL = "Extra Long" referring to Westinghouse plants with 14-foot cores.

Page 60 of 91

Turkey Point 3, Nov.2015 T ab l e s ro r R e po r t in g M RP-227-A I n s p e ctio n R e s u lt s ror West in g h o u s e P 1ant s, Rev.2 Plant Name: Turkey Point Nuclear Plant Unit 3 Date of Exams: PTN3-28RFO 10/19/15 to 12/2/15 Utility: Florida Power and Light Plant Age: 43.5 (years) I 31.70 EFPY Primary Components CoM:ro1 T..... A *** 111

~

t*eam1neoo* n ~WCNJ-11.iis1.P of CROT assemblies.

Guide plltel {CMJ8) aasembfies, with al guide cards within each selected CROT assembly examined.

See MRP-201-4..00S and WCAP-17451.P Page 61 of 91

Turkey Point 3, Nov.2015 Comments:

VT-3 inspection and Guide Card Wear Measurements (GCWM) were completed on nine (9) guide tubes (i.e. 20% of the active locations in the upper internals).

Results using the 20% adjusted wear volume are as follows:

Wear Location

(%)

C-7 6

0-8 6

F-4 3

F-12 7

H-8 7

K-14 39 L-5 7

M-8 18 P-10 12 All indications were analyzed using WCAP-17451 and are within the allowable values.

Page 62 of 91

Turkey Point 3, Nov.2015 t-(

C o n t rol Roo G ui d e Enhanced visual 100% of outer (accessible) 100% of weld length.

No recordable indications.

Tube A sse mbly examination (EVT-1)

CRGT lower flange weld Lower ftange welds to detennine the surfaces and adjacent base presence of crack-Uke metal on the individual surface flaws in periphery CRGT assemblies.

flange welds (Note 2)

Sae Figure 4-21 of MRP-227-A.

Com m e nt s:

Two hundred sixteen (216) welds were inspected to EVT-1 quality. No recordable indications were identified during the GT flange weld inspections.

Core Ba r rel As* em bly Enhanced visual 100% of one side of the 100% of weld length.

No recordable indications Upper core barrel flange examination (EVT-1) aoceasible surfllces of the weld selected weld and adjacent (Completed during PTN3-27RFO-base metal (Note 4).

Reported Spring 2014).

See Figure 4-22 ofMRP-227-A.

Comments:

Page 63 of 91

Core Barrel Assembly Upper and lower core barrel cylinder girth welds Com m en t s:

Enhanced visual examination (EVT-1)

Core Barr** A.... "' bty Enhanced visual Lower core barrel flange examination (EVT-1) weld (Note 5)

Co mm e nt. s:

100% of one side of the accessible surfaces of the selected weld and adjacent base metal (Note 4).

100% of Upper Core Barrel Cylinder Girth Weld Length.

90.6% of Lower Core See Figure 4-22 of MRP-227-Barrel Cylinder Girth A

Weld Length.

100% of one side of the accessible surfaces of the selected weld and adjacent base metal (Note 4).

Page 64 of 91 90.5% of Weld Length.

Turkey Point 3, Nov.2015 No recordable indications (Completed during PTN3-27RFO-Reported Spring 2014).

No recordable indications.

(Completed during PTN3-27RFO-Reported Spring 2014).

Berfla-F or mer Assem b l y Baffle-edge bolts Co mment s.

Visual examination (VT-3)

Bolts and locking devices on 100% of Baffle Edge high fluence seams. 100% of Bolts.

components accessible from core side (Note 3).

See Figure 4-23 of MRP-227-A.

Turkey Point 3, Nov.2015 No recordable indications in 936 baffle edge bolts.

No recordable indications in 936 examined edge bolts.

Baffle-Form er Assemb l y Baffle-fonner bolts Commen t s:

Volumetric examination (UT) 100% of acceuibJe bolts Only 305 of 1088 baffle No recordable indications in 305 (Note 3). Heads accessible former bolts were baffle former bolts.

from the core side. UT examined.

accessibifity may be affected by complexity of head and locking device designs.

See Figures 4-23 and 4-24 of MRP-227-A.

Only 305 of 1088 bolts were examined due to equipment issues. Remaining bolts are planned for a future outage.

Page 65 of 91

Berrte*F or mer Assembly Assembly (Includes: Baffle plates, baffle edge bolts and indirect effects of void swellin in former Comment s:

A1 gn men~ and lnce~f'eclng Coni.fl>Ol'lenta lntemata hold down spring C o mment: s:

Visual examination (VT-3)

Direct measurement of spring height Core side surface as indicated.

See Figures 4-24, 4-25, 4-26 and 4-27 of MRP-227-A.

100%

Measurements should be 1 00%

taken at several points around the circumference of the spring, with a statisticaUy adequate number of measurements at each point to minimize uncertainty.

See Figure 4-28 of MRP-227-A.

Page 66 of 91 Turkey Point 3, Nov.2015 No recordable indications (Completed during PTN3-27RFO-Reported Spring 2014).

SAT (Completed during PTN3-27RFO-Reported Spring 2014).

Co mm e nt s:

Notes to Westinghouse Primary Components Table:

See Figures 4-29 and 4-36 of URP-227-A.

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.

Turkey Point 3, Nov.2015 (Completed during PTN3-27RFO-Reported Spring 2014).

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.

No EXPANSION components were inspected during fall 2015.

Page 67 of 91

Turkey Point 3, Nov.2015 Ex i sti n g Prog r am s Com poncnt s Exam i nation Req ui red Coverage Exam i n a tion lte m Method Exam i nation Ach ieved Find i ng s Coverage Co r e Ba r re t A sse mb l y Visual examination All accessible 100%

A significant impression and a Core barrel flange (VT-3) to determine surfaces at specified minor arc-shaped impression were general condition frequency.

identified on the underside surface for excessive wear.

of the CBF at the 25-degree location, and a significant impression was identified at the 240-degree location. The impressions appear to have been caused by foreign material (FM) trapped between the underside surface of the CBF and its mating surface, the top side of the CSL.

(Completed during PTN3-27RFO-Reported SprinQ 2014).

Co mm e nt s:

The two impressions appear to have been caused by (FM) trapped between the two mating surfaces. The impressions are highly localized and not expected to affect the functionality and bearing area of these surfaces.

U ppe r In t e rn a l s Visual examination All accessible 100%

No recordable indications Asse mb l y (VT-3) surfaces at specified Upper support ring or frequency.

(Completed during PTN3-27RFO-skirt Reported Spring 2014).

Comments'.

Page 68 of 91

Turkey Point 3, Nov.2015 Ex a m In att o n RequJred Coverage Exe m inatlon Item Method Examinati o n Achieved Fi nd i n g s Coverage L owe r I nterna l s Visual (VT-3)

All accessible 100%

No recordable indications Assemb l y examination of the surfaces at specified Lower core plate lower core plates to frequency.

(Completed during PTN3-27RFO-XL lower core plate detect evidence of Reported Spring 2014).

(Note 1) distortion and/or loss of bolt integrity.

Comments:

Lovvcr Internal s Visual examination All accessible 100%

No recordable indications A sse mb l y (VT-3) surfaces at specified Lower core plate frequency.

(Completed during PTN3-27RFO-XL lower core plate Reported Spring 2014).

(Note 1)

Com men-rs'.

Page 69 of 91

Turkey Point 3, Nov.2015 Exam i nation Requi r e d Co v erage Examination lte m Method Examinatio n Ac hle v e d Find i ngs Coverage Bottom Mou nLe d Surface Eddy current surface Replaced seven thimble tubes Seven thimble tubes successfully I n strum e ntatio n examination (ET) examination as during PTN3-27RFO.

replaced.

Sy s tem defined in plant Flux thimble tubes response to IEB 88-

09.

Com m e n ts :

A1ig n mentand Visual examination All accessible 100%

Abrasive wear noted on bolts and I nterfacing (VT-3) surfaces at specified lock bars at 270° key and clevis.

Components frequency.

Degradation attributed to foreign Clevis insert bolts material, possibly an RCP diffuser adapter cap screw, retrieved during previous RFO.

(Completed during PTN3-27RFO-Reported Spring 2014).

Co mm e nt s:

Page 70 of 91

Turkey Point 3, Nov.201 5 E xa m l n at.l on R e q uire d C o v era ge E x a m l n e tlon Ite m M ethod Exa m l n a tlon A c hi e ved Find i ng s Coverage A1 ig n me nt a n d Visual examination All accessible 100%

No Recordable Indications I nterfacing (VT-3) surfaces at specified Compone nt s frequency.

(Completed during PTN3-27RFO-Upper core plate Reported Spring 2014).

alignment pins Comments:

Notes to Westinghouse Existing Programs Components Table:

1.

XL= "Extra Long" referring to Westinghouse plants with 14-foot cores.

Page 71 of 91

I ntentionally Blank Page 72 of 91

Prairie Island 2, Nov. 2015 T a b l es For Report i ng MRP-227-A I n spect i o n Resu lts For West i ng h ouse P 1ants, R ev. 2 Plant Name: ___

P~

ra~i~

ri~e~I=s~la~n~d_U

~n_it~2 ____ Utility: ____

X_c_el_E

_n_

e r~g~y ____ _

Date ofExams: _ _ N~

ov_e_m_b~e_r_2_0_1_5 ___ Plant Age: ___

4_2 __ (years) I 35.5 EFPY Primary Components Conuot Rod Gvtd*

Tub* A........,>'

Guide plates {cards)

Com ments '.

Visual examination (VT-3)

Examination per \\'VCAP*

Maximum% volume vvear:

17451-Pof CRGT Not Inspected this outage Five (5) vvorsr case CRGTs:

assemblies, with all guide cards within each selected (ref. Figures 3-5 through 3-7 of CRGT assembly examined.

WCAP-17 451-P for conversion of See MRP-2014-006 and WCAP-17451-P Page 73 of 91 wear measurements to wear volume.

Also specify high or low flow operation as defined in Tbl 4-2 of the WCAP

Prairie Island 2, Nov. 201 5

fl

,,

Concr o l Roo Gulde Enhanced visual 100% of outer (accessible)

Tube Assembly examination (EVT-1)

CRGT lower flange weld 100% of peripheral welds Lower flange welds to determine the surfaces and adjacent base that were accessible No relevant indications presence of crack-like metal on the individual were examined.

surface flaws in periphery CRGT assemblies.

flange welds (Note 2) 42 weld segments were inspected EVT-1.

See Figure 4-21 of MRP-227-A 27 weld segments were inspected as best effort.

51 weld segments on the outer peripheral guide tubes were inaccessible for inspection (back side, obstructed, etc.)

Comments:

Note that the PINGP 14x14 CRGTs have 6 lower flange welds each, due to the fully enclosed guide tube (same as 17x17).

Core B arrel Assembl y Enhanced visual 100% of one side of the Upper core barrel flange examination (EVT-1) accessible surfaces of the 100%

No relevant indications weld selected weld and adjacent base metal (Note 4).

See Figure 4-22 of MRP-227-A.

Comments:

Page 74 of 91

C ore Barrel A ssembl y Upper and lower core barrel cylinder girth welds Comme n r.s:

Enhanced visual examination (EVT-1)

Core Barre

• As.* m..,Y Enhanced visual Lower core '*'81... examin8ltion (EVT-1) weld.(Nole I)

Comments:

100% of one side of the accessible surfaces of the selected weld and adjacent base metal (Note 4).

100% of Upper Girth Weld See Figure 4-22 of MRP-227-76.5% of Lower Girth A

Weld 100% of one side of the accessible surfaces of the aelected weld and adjacent base metal (Note 4).

Page 75 of 91 100%

Prairie Island 2, Nov. 201 5 No relevant indications No relevant indications

Assem b ly Baffle..edge bolts Co mm e nt s:

B affl e - F orm e r A ssembly Baffle-former bolts Comments:

Visual examination (VT-3)

Volumetric examination (UT)

Bolts and locking devices on high fluence seams. 100% of 1 00%

components accessible from core side (Note 3).

See Figure 4-23 of MRP-227-A.

100% of accessible bolts (Note 3). Heads accessible Not examined this from the core side. UT outage.

accessibility may be affected by complexity of head and locking device designs.

See Figures 4-23 and 4-24 of MRP-227-A.

Page 76 of 91 Prairie Island 2, Nov. 2015 No relevant indications

B erfl a -For ma r A sse mb l y Assembly (Includes: Baffle plates, baffle edge bolts and indirect effects of void swellin in fonner lates Commen ts :

A1 gn ment. end lno:erf'ectng ComponenC*

tntelMll hoJd Commen t s:

Visual examination (VT-3)

Direct measurement of spring height Core side surface aa indicated.

See Figures 4-24, 4-25, 4-26 and 4-27 of MRP-227-A.

Measurements should be taken at several points around the circumference of the spring, wlh a statisticaly adequate number of measurements at each point to minimize uncertainty.

See Figure 4-28 of MRP-227-A.

Page 77 of 91 100%

Not Required for springs of type-403 material.

Prairie Island 2, Nov. 2015 No relevant indications

A ase mb l y Thermal shield ttexurea Co mment s:

Notes to Westinghouse Primary Components Table:

See Figures 29 and 4-36 of MRP-227-A.

100%

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.

Prairie Island 2, Nov. 2015 No relevant indications

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.

No EXPANSION components were inspected in Nov.2015.

Page 78 of 91

Prairie Island 2, Nov. 201 5 Exis"t i ng Progr a m s Co mpon ents Examtnatlon Required Coverage Examination lte m Method Exam i nation Ach ie ved Findings Coverege Core Barre l A sse mb l y Visual examination All accessible Core barrel flange (VT-3) to determine surfaces at specified 100%

No relevant indications general condition frequency.

for excessive wear.

Comments:

Upper Inter n a l s Visual examination All accessible Assemb l y (VT-3) surfaces at specified 100%

No relevant indications Upper support ring or frequency.

skirt Comments'.

Page 79 of 91

Prairie Island 2, Nov. 2015 Exami n ation Req ulred Coverege Ex a m in e ti on Item Method Examinati on Ac hleved Findings Coverage Lower Internals Visual (VT-3)

All accessible Assembly examination of the surfaces at specified 100%

No relevant indications Lower core plate lower core plates to frequency.

XL lower core plate detect evidence of (Note 1) distortion and/or loss of bolt integrity.

Com m e n ts:

Lower Internal s Visual examination All accessible Assemb l y (VT-3) surfaces at specified 100%

No relevant indications Lower core plate frequency.

XL lower core plate (Note 1)

C omm e n t s '

Bottom Mounted Surface Eddy current surface I n s trum e nr.atio n examination (ET) examination as Not examined this outage.

System defined in plant Flux thimble tubes response to IEB 88-

09.

Page 80 of 91

Prairie Island 2, Nov. 201 5 Exe m !nation Required Coverage Examinet.t o n Ite m M ethod Examination Ac h I e v e d Fin d i n gs Coverage Comments: **'REPORT UPON THESE INSPECTIONS ONLY WHEN DONE IN CONJUNCTION WITH MRP-227-A RELATED EXAMS....

Alignment. and Visual examination All accessible Interfac ing (VT-3) surfaces at specified 100%

No relevant indications Components frequency.

Clevis insert bolts Comme n ts'.

A 1ignmc n t and Visual examination All accessible I nterfacing (VT-3) surfaces at specified 100%

No relevant indications Components frequency.

Upper core plate alignment pins Comme nt s:

Page 81 of 91

Prairie Island 2, Nov. 2015 Notes to Westinghouse Existing Programs Components Table:

1.

XL= "Extra Long" referring to Westinghouse plants with 14-foot cores.

Page 82 of 91

TMl-1, FALL2015 Tab l es for R eport in g MRP-2 2 7 - A I n spectio n Res u lts f or B&W P1 a n ts Plant Name: Three Mile Island Nuclear Station Unit 1 Utility: Exelon Generation Date of Exams: 10/28/2015 to 11/23/2015 Plant Age: _4_1 _________ (years) / ----'3~0_

.4 ___ EFPY Primary Components Pte,.um Cow*rAs *emlUy &

Core S u pport Sl\\Jeld Ass em 1o1y P1enum cover watdment rib One~l m e physica l measurement (1nttl*l Inspection) pads Visua l (VT-3) for P1enum cover support na n ge s u bse qu ent CSS t o p flange Com m e nt s:

N o fi n di n g s we re re p o r te d.

Co n tr ol Rod G ulde Tube Assembly CRGT spacer c a stings Com m e nt s:

I n spection s V is u a l (VT-3}

Not Examined duri n g Fa ll 2015.

P 1anne d for F a ll 2017.

dlffaranti*t height or top of p l enum rib pads to reactor vessel ***ting surface, wtth plenum tn reactor vesse l.

S ee F 1g&.1re 4-1 o rMRP-227-A.

Ac cess ib le su rfaces at each of the 4 screvv focetlons (*t e v ery 90°) of 100% of the CRGT spacer ce s t ings

(.um ite<i accessf b lllty).

See Figure 4-5 orMRP-227-A.

Page 83 of 91 100% or t h e \\Ne l dmentrlb pads, p 1 e n um s upport fl a n ge, and CSS top r l ange.

N/A N o fi n d i n g s,

N/A

Core Support SMeld Assembly CSS v*nt valve 'top ret.afnlng rtng CSS vent valve bottom retain ng ring (Note 1)

Comments:

Visual (VT-3)

Not Exam;ned dur;ng Fa ll 2015.

P 1anned for Fa ll 2017.

100% of ecca **Ible surfaces (see BAW-2248A, peg*

4.3 end T*ble 4-1).

See Figure 4-11 ofMRP-227-A.

TMl-1, FALL2015 N/A Loc k ing devices vve r e exa m i n ed for a ll Ve n t Va lves.

N/A I mpact damage noted on al l va l ves, with one felled l ocking d ev i ce requ iring va l ve replacement, Ve n t va lv e l ocking dev i ces vve r e e x ami n ed for e l l ve nt v a l ves TS r eq ui reme n ts a n d T M I s p ec ifi c commit m e nt to M RP-227 - A and PWRQG I n terim gu id ance. One vent va l ve (adj acen t to the hot leg) vvas fo u nd vvit h a fai l ed l oc k l n g d e v ice in vvh i ch th e spr i ng retainer had vvorn through t h e l ocking cup. The l ocking c u p end spring r etai n ervvere functiona l as - found, but an assess m ento f o p e r abillty over the next cyc l e cou l d not be made. The dam age mechanism was f l ow induced wear and was be l ieved to or i ginate in 1Rl 8 after impact from the P 1enu m. This vent va l ve was of the origina l design.

Re m a i n in g ve n t valves exhib ite d i m pact damage o n t h e l ock in g devices from t h e Insta ll a t io n of t he Prcnu m.

This I m pac t d a m age did not Im pact th e ability o f th e l ocklng devices to perform their design functio n s.

Co.su...

St......,

A***ai a11r Upp- <:ore l>al' *t (UCB}

boft:a and tftalr l-ocilt,,o ld*vtces Comments:

Votumetr c examU** on (UT) of the boka V1auat (VT-3}

ex* mlnatton of bolt locking devices 100% or aocesstble 1>-*

(Note 3)

See Ftgure 4-7 of MRP-227-A.

100% of a ll bolts and their l oc k ing devices.

120 bo lts e x ami n ed.

One indeterminate volu m etrlc exam of bo l t 24. Assumed fai l e d.

One bo lt(# 24) was Indeter m inate based on vo l umetr ic exa m res u lts.

T he indeterminate response was t he resu l t o f a l ow amp l it u de backwa ll respo n se l ess than t h e 60% m i nim um r equired by proced u re. The backwal l res p o n se was 53%.

N o f l aws were vis i b l e in the reviewed data; however the bo l t was conservatlve l y assu m ed fai l ed. Expansion cri t eria were nottrtggcrcd.

Page 84 of 91

Core Barrel Assembly Lower core barrel (LCB) bolts and their locking devices Comme n ts'.

No fi n dings.

Core Barrel Assembly Baff'te"'to""torm er boks Comme nt s'.

Volumetric examination (UT) of the bolts Visual (VT-3) axe mlnetlon of bolt locking devices V 01u m etrlc examination (UT) 100% or accessible bolts and their tocking devlces (Note 3) s ** F111ur* 4-8 of' MRP-227-A.

100% of eccesstbta bolts.

(Note 3)

See F111ure 4-2 o f MRP-227-A.

Not Examined during Fall 2015. Examination t s p l anned for F a ll 2017.

Core Barrel Assembly Bame plates Commen t s:

Vtsual examination (VT-3) 100% of the accessible surface within 1 inch around each now end bolt hole.

See Figure 4-2 of MRP-227-A.

Not examined during Fall 2015. Examin ation is p l a nn ed for Fa ll 2017.

Page 85 of 91 TMl-1, FALL 2015 100% of a ll bo lts and t.heir No finding s.

l ocking devices.

108 bo lts examined.

N/A N/A N/A N/A

Core Berrel Assembly Locking devices, includlng locking welds, or beme~o form er bo lts and tnt.ernal b arr1e - to - b effle bolts Comments:

Visual examination (VT-3) 100% or accessible bame-

'to-former end Internet baffle-to-baffle bolt locking de v ices. (Note 3)

See Figure 4-2 or MRP-227-A.

Not Examined during Fa ll 2015. Examination is planned for Fa ll 2017.

F1ow D1urllH*t* Aa ** m lltty Frow dlsulb"Utor ( 0) bok*

e ntl the r rocking tl*v cee Comments :

V 01u m atrtc

• xem1nat1on (UT) or the bolts Visual (VT-3) ex* m1natlon of bolt tocking devices 100% or" cc esslble bolts and thel-r tocking devices.

(Not* 3)

See F gure 4-8 or MRP-227-A.

TMl-1, FALL 2015 N/A N/A 100% o f a ll bo lts a nd th e i r One volumetric i ndica tion on l oc kin g dev ices.

bo lt44.

108 bo lt s examrned One v olu m etrlc Ind le etio n noted i n bo lt 44. The indication was reported as a crack in the upper threads approximately 4.40" from the top of the bolt head.

Ex pa n sion criteria vvere not triggered.

Lower Grid Assemb ly Anoy X-750 dowel-to-guide block wetels Com m ents'.

V isua l examination (VT-3)

A ccessible surfaces ot 100% orthe 24 dowel-to-guide block welda.

See figure 4-4 or MRP-227-A.

100% of dovv e l -to-gulde No r e l eva nt Indica tion s n oted.

b l ock vve l ds.

12 guide b l ock pair s e xamin ed.

F ound a l oose parts issue assoc i ated vvith a meta l s live r on the under si de of t h e gui d e b l ock. The l oose part was r e m oved.

Page 86 of 91

Inca-re Mol'ltt°'rlnfJ lnso;rument*tiol'I (1Mt)

G..... Tub* A........ ij,'

IMt guide tub* ap.tden IMJ 9"1d* tu** *l"k:l... "'t.0-tower grid rib section welds Comme nt s:

Vtsuat examination (VT-3) 100% ort:op aurfacas or 52 sptder c=astlngs *ncf welds to the a<ljacant lowar grid rtb s ectJon.

See Fie.... ** 4-3 and 4-6 or MRP-227-A.

Not Examined during Fa ll 2015. Examination is p l anned fo r Fa 11 2017.

Notes to B&W Primary Componont Tab l e TMl-1, FALL2015 N/A N/A l,

A verification of' the operation or each vent. va l ve s ha ll atso be performed through manua l actuation oft. h e va l ve, Verify that the valves are not st uck In the open position and that no abnormal degradation has occurred, Examine the valves for evidence of scratches, pitting, embedded partlc l cs, l ea k age of the scat.Ing surfaces, cracking of l ock welds and locking cups, jack screws for proper position, and wear. The frequency is defined in each unit's technical specifiC a<io n s oc In Ch" pump

• n d v alvo In. ocvlc 0 '""

pcogca ms (soe BAW-2248A, pogo 4-3 and Tab le 4-1, coroccncc 18 orMRP-227-A).

2.

Examination accoptuncc c r it eria and expansion criteria for tho B&W com ponent s arc In Tab l e 5 - 1 of MRP-227 - A.

3.

A minimum or75% of' the total populetlon (examined+ unexemlned). I ncluding coverege consist&ntvvith the Expenslon criteria In Tab l e 5-1, must be exam i ned for Inspection credlL Page 87 of 91

TMl-1, FALL2015 Expansion Components Examination Required Coverage Examination lte m Method Examinat i on Achieved Findings (Note 1)

Cevera ge Upper Grid Assemb ly Visua l ex a m In a t i on Acces s ib l e su r faces or N/A N/A A11oy X-750 dovve l-to-upper (VT-3) 100% or the dowe l grid fu e I a s s e m b I y s upport l ocking vve l ds.

pad vvelds See Figure 4-6 or MRP-227-A (i.e., these are s imil ar to the lower grid fue l assemb l y support pads).

Com m e nt s :

Expans io n to th i s item vvas not required during Fa ll 2015.

Core Barrel Assemb l y Bolts : Vo 1u metric 1 00% of a cc e s s 'b I e N/A N/A Upper therm a1 shield (UTS) e xamination (LJT).

bo lt s or studs/nuts and bo l ts and their l ocking devices Lock in g Devices:

their locking devices Vis u a l examination (Note 2).

(VT-3)

See Figure 4-7 or MRP-227-A.

Comments:

Expansion to this item vvas notrequtred during Fa 11 2015.

Page 88 of 91

TMl-1, FALL2015 E x a m I n a t i o n Requir e d Cov e r age E xa m i n ation lte m Meth od Exa m i n a t io n A

c hi e ved Find ings (Note 1)

C o ver age Core B a rr e l Ass e mbly Bolt or Stud/Nut:

100% o f acces s i b l e N/A N/A Survc ill a nee specimen hold e r Vo lum etri c bolts or st u d s / nu t s and tu be (SSHT) stud s / n uts (CR-exam i nation (LJT).

their tock i ng dev i ces

3) or bo lts (DB) and their Lock ing Dev ice s:

(Note 2).

locking devices Visua l ex a m i n a ti on (VT-3)

See Fig ur e 4-7 of MRP-227-A.

Comme n ts'.

T h is item does no t app ly to TMI.

Lovver Gr i d Assemb l y Visua l ex a m i n a ti on Access i b l e s u rfaces of N/A N/A Lovve r g r i d f u e l a ss c m b l y (VT-3) t h c pad S, dovvc l s, and s upport pad ite m s: pad, p a d-cap s crews, and to-rib section we l ds, A 11 oy X-a ss ociated we l ds in 750 dovve l, cap s cre\\N 1 and 100% of the lovve r grid their l ocking w e l d s fuel assemb l y support pads.

See F ig ur e 4-6 of MRP-227-A.

Comments :

Expans ion to t h is item vva s not req uired d ur in g Fa11 2015.

Lower Grid Assembly Visua l ex a min a t l on Acc es sib l e su r fac es of N/A N/A A11oy X-750 dovve i-to-lovver (VT-3) 100%ofthe suppo r t grid fue l assemb l y S LI pp Ort pad dowe l l oc k ing pad welds vve l ds.

See F igure 4-6 of MRP-227-A.

Commen t s :

Expansion to t h is i t. em "'as not. req u ired d uri ng Fa11 2015.

Page 89 of 91

TMl-1, FALL2015 Examination Required Coverage Examination lte m Method Examination Achieved Finding s (Note 1)

Coverage Lovver Grid Assemb l y Bolts : Vo 1u m etr l c 100% of accessib l e 100% of all bo lts and thei r No fi n di n gs.

Lovvcr grid shock pad bo lts exa m inati on (LJT).

bo l ts and the i r l ocking l oc k ing device s.

and their lock i ng devices Loc king Devices:

device s. (Note 2)

Visua l exa mlnat ton 24 bo lts exa mi ned (VT-3)

See Figure 4-4 of MRP-227-A.

Comments'.

The lovver grid s ho ck pad bo l t s and t hei r l ocki n g dev i ces vvere exam in e d d ur i ng th e Fall 2015 refueling outage du e to the proposed MRP-227 R e v isio n 1. The l owe r Grid S h ock Pad Bo lts are Prim a ry Ite m s

u nd er t he new revisio n. No fin di n gs vve r e repo rt ed.

Lower Grid As semb ly Bolts: Volumetric 100% of accessible N/A N/A Lower thermal s hield (LTS) o x a m i n a ti o n (UT).

b c i ts and their l ocking b O lt S (AN0-1, DB and TMl-1)

Locking Devices:

devices. (Note 2) or studs/nuts (QNS, CR-3)

Visua l ex a min a ti on and their locking devices (VT-3)

See Figure 4-8 of MRP-227-A.

Com m e n ts:

Expansion to this lte m was not req u ired du r l n g Fa 11 2015.

No t es to B&W Expansion Compo n ents T6b le:

1.

Examination acceptance criteria and expansion criteria t'orthe B&W compo nent s are In Tab le 5-1 or MRP-227-A.

2.

A minimum or75% oftho tota l population (oxam1n<.od + unoxam1nod) must bo examined rorlnspCtctlon credit.

Page 90 of 91

TMJ-1, FALL 2015 Expans i on Compo n e n ts R eq u ir i ng E va l uatio n or Rep l ace m ent In L i eu of I nspec t ion lte m Exa mln a tlon Meth o d Di sposi t io n Core Barre l Ass embly No e x a m In a t i o n req uir eme n t s.

N/A Core barrel cy l ind e r (including Ju stify by e v a I u ati on or by rep l acement.

v e rt i ca l and circumferential se am vveld s)

Former p l a t es Co mm e nt s :

E xp ans Io n t o t h is item vva s not r eq uir ed during F a11 2015.

Core Barrc1A s scmbly Interna l b a ffl e -to - b a ff'I e b a l t s :

N/A Baffl e -t o-baffl e bo l t s No e x a m in a ti o n requi r e m e nt s, Core bar r el-to-form e r bolt s Ju stify by e v a I u ati on or by rep l acement.

Externa l b a ffl e -ro-b a ff! e bo lts, co r e barre l -re-N/A former b a lts : No e x a m in a ti o n requirement s.

Ju s tify by e v a I u at.ion or by replacement.

Com m ents:

Expansion to this item vv as not req u i r ed during Fa 11 2015.

Core Barrel A s sembly No ex a min a ti on requirements.

N/A lock i ng devi c es, includ i ng Ju stify by eva l uation or by rep l acement.

lock i n g weld s, for the externa l b a ffle-to-baffle bolts and core barre l-to-form e r bo lt s Co m me n ts'.

Expans i on to t h is itc m vv as not re q uired during Fa11 2015.

Page 91 of 91

-=~121 I ELECTRIC POWER

~*-

RESEARCH INSTITUTE M RP Materials Reliability Program. ____________ M RP 2016-008 Date:

To:

May 18, 2016 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-001 From:

Bernie Rudell, Exelon, MRP Integration Chairman Anne Demma, EPRl, MRP Program Manager

Subject:

Biennial Report ofMRP-227-A Reactor Internals Inspection Results The purpose of this letter is to provide NRC staff members with a report of recent pressurized water reactor (PWR) utility inspection results as required by the Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227-A). Previous results were provided in EPRl letter MRP-2014-006.

Enclosed with this document are individual plant MRP-227-A inspection summary results from 2014-2015 using the report template provided by EPRl. Eight (8) U.S. domestic plants have submitted MRP-227-A reactor internals exam summary results reports in the past two calendar years.

If additional information is required, please contact Kyle Amberge (650-855-2039; kamberge@epri.com) or Anne Demma (650-855-2026; ademma@epri.com)

Sincerely,

/

• 7/C, ;~I//'

B. C. Rudell MRP Chairman Exelon Generation cc:

Joe Holonich, NRC MRP Assessment TAC MRP Integration Committee PMMP Executive Committee

Enclosure:

MRP-227 Inspection Results Together... Shaping the Future of Electricity PALO ALTO OFFICE AnneDemma MRP Program Manager Electric Power Research Institute 3420 Hillview Avenue, Palo Alto, CA 94304-1338 USA

• 650.855.2000

• Customer Service 800.313.377 4

• www.epri.com

ENCLOSURE TO MRP 2016-008 MRP-227 Related Inspections Performed from 2014-2015 Palisades - 2/2014, 26.1 EFPY Turkey Point 3 - 4/2014, 30 EFPY Oconee 3 - 4/2014, 31.7 EFPY Turkey Point 4 - 10/2014, 31 EFPY Prairie Island 1-10/2014, 34 EFPY Point Beach 2 - 10/2015, 35 EFPY Turkey Point 3 - 11/2015, 31.7 EFPY Prairie Island 2 - 11/2015, 35.5 EFPY Three Mile Island 1 - 11/2015, 30.4 EFPY Page 1of91

Intentionally Blank Page 2 of 91

Palisades, Feb. 2014 Tables for Reporting MRP-227-A Inspection Results for CE Plants Plant Name:__.P

........... al_is..... a_d_e....... s ______________ Utility: ___

E_n_t_e_rg..,y....__ ______________ _

Date of Exams: _ _.1..... /3""'""1'"-'-th_r...... u_2..... /2_1 __ /_20

...... 1_4 _______ Plant Age: __

4...... 3 _______ (years) I 26.1 EFPY Primary Components c

Core Shroud.... Volumetric 100% of accessible bolts (see N/A See Comments (Bolted) examination (UT)

Note 2). Heads are accessible Core shroud bolts from the core side. UT accessibility may be affected by complexity of head and locking device designs.

See Figure 4-24 of MRP-227-A of MRP-227-A.

Comments:

In accordance with MRP-227A and the Palisades Aging Management Plan examinations will be performed by 2022. (approximately 34.3 EFPY)

Page 3 of 91

Palisades, Feb. 2014 Core Shroud Assembly Enhanced visual Axial and horizontal weld seams N/A See Comments (Welded) examination (EVT-1) at the core shroud re-entrant Core shroud plate-former comers as visible from the core plate weld side of the shroud, within six inches of central flange and horizontal stiffeners.

See Figures 4-12 and 4-14 of MRP227-A.

Comments:

Not applicable to Palisades.

Cont roudA bly Enhanced visual Axial weld seams at the core N/A See Comments

- ~ -

examination (EVT-1) shroud re-entrant comers, at the I

Shroud plates core mid-plane (+/-three feet in height) as visible from the core side of the shroud.

See Figure 4-13 of MRP-227-A.

Comments:

Not applicable to Palisades.

Page 4 of 91

Core Shroud Assembly (Bolted)

Assembly Comments:

Visual examination (VT-3)

Core side surfaces as indicated.

See Figures 4-25 and 4-26 of MRP-227-A.

100%

Palisades, Feb. 2014 Slight gap in shroud plate at the shroud anchor bolt location for seam 4. All other seams acceptable. See Comments Gap was verified from original fabrication, deviation report DCR 9700101-8 Dated 12/31/68. As-built gap measured at.046". Based on photograph this does not appear to have changed. Examinations included 768 shroud to former bolts and 96 shroud to anchor bolts. One core shroud bolt seated different than all others with the locking bar slightly bent and opening on the right side.

Core Shroud Asurnbly (Welded)

Asaembty Comments:

Visual examination (VT-1)

Not Applicable to Palisades.

If a gap exists, make three to five N/ A measurements of gap opening from the core side at the core shroud re-entrant corners. Then, evaluate the sweHing on a plant-specific basis to determine frequency and method for additional examinations.

See Figures 4-12 and 4-14 of MRP-227-A.

Page 5 of 91 See Comments r

Palisades, Feb. 2014 I

Core Support Barrel Enhanced visual 100% of the accessible surfaces 100% Scan was performed No indications.

Assembly examination (EVT-1) of the upper flange weld (Note 3).

from the inside of the core Upper (core support barrel.

barre~ flange weld See Figure 4-15 of MRP-227-A.

Comments: N/A Core Support Barrel Enhanced visual 100% of the accessible surfaces The upper girth weld scan was No indications Assembly examination (EVT-1) of the lower cylinder welds (Note performed from the inside of Lower cylinder girth 3).

the barrel. Coverage achieved welds 100%.

See Figure 4-15 of MRP-227-A The middle girth weld scan No indications was performed from the outside of the core barrel.

Coverage achieved 86.67%.

The lower girth weld scan was No indications performed from outside the core barrel. Coverage achieved 76.67%.

Comments:

For Palisades the Lower Cylinder Girth Welds consist of three welds: the Upper Girth Weld; the Middle Girth Weld; and the Lower Girth Weld.

In the Wesdyne report these welds are incorrectly named. The report calls the Middle Girth Weld the Lower Girth Weld and calls the Lower Girth Weld the Lower Flange Weld.

Page 6 of 91

Palisades, Feb. 2014

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Lower upport Visual examination 100% of the accessible surfaces 96% See comments.

No indications.

Structure (VT-3) of the core support column welds Core support column (Note 4).

welds See Figures 4-16 and 4-31 of MRP-227-A Comments:

Approximately 4% inaccessible due to baffle plate periphery and no access hole for OD.

Core Support Barrel If fatigue life cannot Examination coverage to be N/A See Comments be demonstrated by defined by evaluation to Lower flange weld time-limited aging determine the potential location analysis (TLAA),

and extent of fatigue cracking.

enhanced visual (EVT-1) examination See Figures 4-15 and 4-16 of MRP-227-A.

Comments:

Not Applicable to Palisades.

Lower Support If fatigue life cannot Examination coverage to be 93% See comments No indications Structure be demonstrated by defined by evaluation to Core support plate time-limited aging determine the potential location analysis (TLAA),

and extent of fatigue cracking.

enhanced visual (EVT-1) examination See Figure 4-16 of MRP-227-A.

Comments:

Approximately 7% inaccessible due to baffle plate construction.

Page 7 of 91

Palisades, Feb. 2014

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Upper Internals If fatigue life cannot Examination coverage to be N/A See Comments Assembly be demonstrated by defined by evaluation to Fuel alignment plate time-limited aging determine the potential location analysis (TLAA),

and extent of fatigue cracking.

enhanced visual (EVT-1) examination See Figure 4-17 of MRP-227-A.

Comments:

Not Applicable to Palisades.

Control Element Visual examination 100% of tubes in peripheral CEA 15 locations around the Two guide tubes at locations Assembly (VT-3) shroud assemblies (i.e., those periphery of the upper guide 87 and G5 have slots in the Instrument guide tubes adjacent to the perimeter of the structure. 8 welds per guide tubes. Also, at location 87 fuel alignment plate).

tube. Coverage achieved there is an extra welded 100%

attachment to the tube with a See Figure 4-18 of MRP-227-A.

different style bracket.

Comments:

N/A Lower Support Enhanced visual Examine beam-to-beam welds, in N/A See Comments Structure examination (EVT-1) the axial elevation from the beam Deep beams top surface to four inches below.

See Figure 4-19 of MRP-227-A.

Page 8 of 91

Palisades, Feb. 2014 Comments:

Not applicable to Palisades.

Note to CE Primary Components Table:

1.

Examination acceptance criteria and expansion criteria for the CE components are in Table 5-2 of MRP-227-A.

2.

A minimum of 75% of the total population (examined+ unexamined), including coverage consistent with the Expansion criteria in Table 5-2 of MRP-227-A, must be examined for inspection credit.

3.

A minimum of 75% of the total weld length (examined + unexamined), including coverage consistent with the Expansion criteria in Table 5-2 of MRP-227-A, must be examined from either the inner or outer diameter for inspection credit.

4.

A minimum of 75% of the total population of core support column welds.

No EXPANSION components required inspections at Palisades during spring 201 4.

Page 9 of 91

Palisades, Feb. 2014 Existing Programs Components Required Coverage Examination Item Examination Method Examination Coverage Achieved Findings Core Shroud Assembly Visual examination Accessible surfaces at 100% the guide lugs have slight N/A Guide lugs (VT-3), general specified frequency.

wear. Some of the lock pins are condition examination protruding from the insets. One Guide lug inserts and for detection of bolt is loose but secure when the bolts excessive or core barrel is installed. See asymmetrical wear.

Comments.

Comments:

This condition was identified in 1995 and again in 2007. The condition has not changed.

Lower Support Visual examination Accessible surfaces at N/A See comments Structure (VT-3) to detect specified frequency.

Fuel alignment pins severed fuel alignment pins, (plants with core shrouds missing locking tabs, assembled with full-height or excessive wear on shroud plates) the fuel alignment pin nose or flange.

Comments:

The fuel alignment pins at Palisades are in the fuel bundles not in the lower core support plate.

Page 10 of 91

Palisades, Feb. 2014 Required Coverage Examination Item Examination Method Examination Achieved Findings Coverage Lower Support Visual examination Accessible surfaces at N/A N/A Structure (VT-3) specified frequency.

Fuel alignment pins (plants with core shrouds assembled in two vertical sections)

Comments:

Not applicable for Palisades.

Core Barrel Assembly Visual examination Area of the upper 100% coverage.

No signs of abnormal wear.

Upper flange (VT-3) flange potentially susceptible to wear.

Comments:

N/A Page 11 of 91

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Turkey Point Unit 3 SPRING 2014 Tab l es f'or Reporting MRP-227-A I n s pection Re s ul ts f'or West i ng h ouse P 1a nt s P lant Name: Turkey Point Unit 3 Utility: NextEra Energy/FPL Date of Exams: March-April 2014, PTN3-27RFO Plant Age: --"'4=2 __

__,_(y'--"e=a=-=rs:.L..) -'--/ --=3'-"0'---=E=F~P~Y Primary Components Conuo l R od G ulde Visual examination 20% examination of the Not inspected during N/A Tube Assembly (VT-3) number of CRGT assemblies, PTN3-27RFO.

Guide plates (cards) with all guide cards within Inspection planned for each selected CRGT PTN3-28RFO, Fall 2015 assembly examined.

See Figure 4-20 of MRP-227-A Commen t s:

Page 13 of 91

TurkevPoint Unit 3 SPRING 2014

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C o n tr o l Ro d Gu Ide Enhanced visual 100% of outer (accessible)

Not inspected during NIA T ub e Ass e m b ly examination (EVT-1)

CRGT lower flange weld PTN3-27RFO.

Lower flange welds to determine the surfaces and adjacent base Inspection planned for presence of crack-like metal on the individual PTN3-28RFO, Fall 2015 surface flaws in periphery CRGT assemblies.

flange welds (Note 2)

See Figure 4-21 of MRP-227-A.

Comments:

Co re Ba r r e l A sse mb l y Enhanced visual 100% of one side of the 100%

No Recordable Indications Upper core barrel flange examination (EVT-1) accessible surfaces of the weld selected weld and adjacent base metal (Note 4).

See Figure 4-22 of MRP-227-A.

Comments:

Page 14 of 91

Turkey Point Unit 3 SPRING 2014

~

Core B a r rel A ssembl y Enhanced visual 100% of one side of the Upper-100%

No Recordable Indications Upper and lower core examination (EVT-1) accessible surfaces of the barrel cylinder girth selected weld and adjacent Lower - 90.6%

No Recordable Indications welds base metal (Note 4).

See Figure 4-22 of MRP-227-A Comments:

Core B errel Aase m bly Enhanced visual 100% of one side of the 90.5%

No Recordable Indications Lower core barrel flange examination (EVT-1) accessible surfaces of the weld (Note 5) selected weld and adjacent base metal (Note 4).

Comments:

Page 15 of 91

Turkey Point Unit 3 SPRING 2014 Barfle-Former Visual examination Bolts and locking devices on Not inspected during N/A A ssem bly (VT-3) high fluence seams. 100% of PTN3-27RFO.

Baffle-edge bolts components accessible from Inspection planned for core side PTN3-28RFO, Fall 2015 (Note 3).

See Figure 4-23 of MRP-227-A.

Comment s:

Barrie-Form er Volumetric 100% of accessible bolts Not inspected during N/A Assembly examination (Un (Note 3). Heads accessible PTN3-27RFO.

Baffle-former bolts from the core side. UT Inspection planned for accessibility may be affected PTN3-28RFO, Fall 2015 by complexity of head and locking device designs.

See Figures 4-23 and 4-24 of MRP-227-A.

Comments:

Page 16 of 91

B err1e-F or m e r Asse mb l y Assembly

{Includes: Baffle plates, baffle edge bolts and indirect effects of void swellino in former plates)

Comments:

A11gnment. e n d Jn~erf'act n g C o mponer.ts Internals hold down spring Visual examination (VT-3)

Direct measurement of spring height Core side surface as indicated.

See Figures 4-24, 4-25, 4-26 and 4-27 of MRP-227-A.

100%

Measurements should be 100%

taken at several points around the circumference of the spring, with a statistically adequate number of measurements at each point to minimize uncertainty.

See Figure 4-28 of MRP-227-A.

TurkevPoint Unit 3 SPRING 2014 No Recordable Indications SAT Commen t s: Measurements taken at eight circumferential positions. All exceeded the minimum height criteria for 60 years of operation.

Page 17 of 91

Turkev Point Unit 3 SP RING 2014 f

T her m e 1 Sh1 e 1d Visual examination 100% of thermal shield 100%

No Recordable Indications A ss emb l y (VT-3) flexures.

Thermal shield flexures See Figures 4-29 and 4-36 of MRP-227-A.

Comments:

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.

No EXPANSION components were inspected at Turkey Point 3 during spring 2014.

Page 18 of 91

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Turkey Point Unit 3 SPRING 2014 Existing P rog r ams Components Examination Req u i r ed C overage Exa m i n ati on lte m Method E xaminstlon Ac h laved Fi ndings Coverage Co r e Barre l A sse mbl y Visual examination All accessible 100%

A significant impression and a Core barrel flange (VT-3) to determine surfaces at specified minor arc-shaped impression were general condition frequency.

identified on the underside surface for excessive wear.

of the CBF at the 25-degree location, and a significant impression was identified at the 240-degree location. The impressions appear to have been caused by foreign material (FM) trapped between the underside surface of the CBF and its mating surface, the top side of the CSL.

Comme nt s: The two impression appear to have been caused by (FM) trapped between the two mating surfaces. The impressions are highly localized and not expected to affect the functionality and bearing area of these surfaces Upper I nterna l s Visual examination All accessible 100%

No Recordable Indications Assembly (VT-3) surfaces at specified Upper support ring or frequency.

skirt Com m e n ts :

Page 19 of91

Turkey Point Unit 3 SPRING 2014 Ex a mination Req ulred Coverage Exam i n a tion lt e m Method Ex a m i n a tion Ac h 1oved F1nd l n gs Cov e rag e Lowe r I nt e r nals Visual (VT-3)

All accessible 100%

No Recordable Indications Assemb l y examination of the surfaces at specified Lower core plate lower core plates to frequency.

XL lower core plate detect evidence of (Note 1) distortion and/or loss of bolt integrity.

Comme nt s'.

Lower Internals Visual examination All accessible 100%

No Recordable Indications Assembly (VT-3) surfaces at specified Lower core plate frequency.

XL lower core plate (Note 1)

Com m e nt s:

Page 20 of 91

Turkey Point Unit 3 SPRING 2014 Ex a m i na ti on Req u lre d Cov e r a ge Exam i n a t i on lte m Method E xa m i n a t i on Ac h la v ed Find ing s Cov era g e B o ttom M o u nt ed Surface Eddy current surface Replaced seven thimble tubes Seven thimble tubes successfully I n s t r um e nt. a ti o n examination (ET) examination as during PTN3-27RFO replaced.

Syste m defined in plant Flux thimble tubes response to IEB 88-

09.

Comme n ts:

Alignment and Visual examination All accessible 100%

Abrasive wear noted on bolts and I nterfacing (VT-3) surfaces at specified lock bars at 270° key and clevis.

Compone n ts frequency.

Degradation attributed to foreign Clevis insert bolts material, possibly an RCP diffuser adapter cap screw, retrieved during previous RFO.

Comm e nt:s *The degradation does not affect the structural integrity or functionality of the radial support structure.

Page 21 of 91

Turkey Point Unit 3 SPRING 201 4 Examination Required Coverage Examination lte m Method Ex a m i nation Achieved Find ings Cover a ge A1ign m e n tond Visual examination All accessible 100%

No Recordable Indications I nter f acing (VT-3) surfaces at specified Components frequency.

Upper core plate alignment pins Comments:

Notes to Westinghouse Existing Programs Components Table:

1.

XL= "Extra Long" referring to Westinghouse plants with 14-foot cores.

Page 22 of 91

Tab l es for Reporting MRP-227-A I n s pection Resu lts for B&W P1 a n ts Plant Name:

Oconee Unit 3 _______ Utility:

Duke Energy Date of Exams: 4/14/2014 to 5/14/2014 Plant Age: ___

4_0 __ (years) I --'-3_1.~67-'--- EFPY Primary Components p,.,...,... C."... A..**ml>*y &

Core S.,,.,... c: S,. e,io Assembly Plenum coverwe1dment rib pads Plenum cover eupport flange css top flltnOe One-time phys1cat meeaurement (initial Inspection)

Visual (VT-3) for subsequent inspections Determiftetioft of diffeMnttal height of top of plenum rib pads to reactor vessel Hating.urt.ce, with plenum in reactor vellel.

See Figure 4-1 of MRP-227-A.

Measurement performed in 2007 VT-3 100%

Oconee 3 Spring 2014 No relevant Indications were noted.

No relevant Indications were noted.

Comments: The one-time physical measurement was performed in Fall 2007 with no evidence of wear occurring during service period Page 23 of 91

Oconee 3 Spring 2014 Contro l Rod Guld e Tu be Visual (VT-3)

Accessible surfaces at 100%

No relevant Indications were A sse mbly each of the 4 screw 690 castings with 4 screws noted.

CRGT spacer castings locations (at every 90°) of each.

100% of the CRGT spacer castings (limited accessibility).

See Figure 4-5 of MRP-227-A.

Com m e n ts:

Core S uppor1: Shl eld Visual (VT-3) 100% of accessible 100%

No relevant Indications were A ss embly surfaces There are 8 vent valves.

noted on retaining rings.

CSS vent valve top retaining (see BAW-2248A, page ring 4.3 and Table 4-1).

See Comment Section for css vent valve bottom relevant indications noted on retaining ring See Figure 4-11 of MRP-other CSS vent valve parts.

(Note 1}

227-A.

Com ments: 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 XI, Category B-N-3 VT-3 examination. No vent valve replacements were necessary.

Vent Valve XW - The right side jack screw locking cup crimps indicate that the jack screw has rotated slightly, pushing the locking crimps outward.

The jack screw insert in the in the right side guide block was tilted and there was gouging at both corners of the guide block.

Vent Valve ZW - Relevant indications on the inside crimps of both the right and left side locking cups.

Vent Valve XY - Relevant Indications in the form of gouges were identified on the left and right jacking screw guide blocks.

Vent Valve ZY - Relevant indications on the outside crimp of the right side locking cup.

Vent Valve WZ - The spring loaded locking devices of both the left and right jacking screws were not shown as engaged.

Page 24 of 91

Oconee 3 Spring 2014

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J Core S upport S h1e 1d Volumetric 100% of accessible bolts 100% UT performed in 2007 No recordable indications were Assembly examination (UT) of and their locking devices.

(120 UCB bolts) detected in 118 of the 120 UCB Upper core barrel (UCB) the bolts (Note 3) bolts. Bolts #10 and #85 had bolts and their locking no UT back wall response devices similar to previous inspections.(1984, 1985 and 1987).

Visual (VT-3)

See Figure 4-7 of MRP-VT-3 100% performed this No relevant Indications were examination of bolt 227-A.

outage (120 locking devices) locking devices noted.

Com m ents:

Core B erre l A ssemb l y Volumetric 100% of accessible bolts 100% - 1 08 oolts UT - 3 lower core barrel bolt Lower core barrel (LCB) examination (UT) of and their locking devices with crack like indications (#15, bolts and their locking the bolts (Note 3)

1. 91 and #100). These same devices bolts were identified with indications in 1987.

Visual (VT-3)

See Figure 4-8 of M~P-100% - 108 bolts and locking examination of bolt 227-A.

devices.

VT - No relevant indications locking devices Comme n ts: The indication is located in the bolt head-to-shank region.

Page 25 of 91

Oconee 3 Spring 2014

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Core Berre l Assembly Volumetric 100% of accessible bolts.

863 out of 864 One crack like indication was Baffle-to-former bolts examination (UT)

(Note 3) detected on bolt# 2-1-2-6 See Figure 4-2 of MRP-1 baffle-to-former bolt was 1 un-inspectable, bolt #2-7-1-3 227-A.

un-inspectable due to probe not seating correctly.

Cam m e nt s : Examination limitation was noted on Hex Head Baffle-to-Former Bolt (Quadrant - Plate - Column - Elevation) #2-7-1-3. Probe did not seat correctly.

The indication on bolt #2-1-2-6 is located in the bolt head-to-shank region.

Core Barrel Assembly Visual examination 100% of the accessible 100%

No relevant Indications were Baffle plates (VT-3) surface within 1 inch noted.

around each flow and bolt hole.

See Figure 4-2 of MRP-227-A.

Com m ent: s:

Page 26 of 91

C ore B *rrel A ssem bly Locking devices, including locking welds, of baffle-to-former bob and internal baffle-to..baft bolts Com m e n ts:

F1ow D 1str1but o rAsse m bl y Flow d'rstributor (FD) bolts and their locking devices Visual examination (VT-3)

Volumetric examination (UT} of the bolts Visual (VT-3) examination of bolt locking devices 100% of accessible baffle-to-former and internal baffle-to-baffle bolt locking devices. (Note 3)

See Figure 4-2 of MRP-227-A.

100% of accessible bolts and their locking devices.

(Note 3)

See Figure 4-8 of MRP-227-A.

100%

864 baffle-to-former and 272 internal baffle-to-baffle bolts.

UT --100%

96 bolts inspected.

VT-100%

96 bolts and their locking devices inspected.

Recordable UT indication detected in FD Bolt #87 located in the bolt head-to-shank region.

Oconee 3 Spring 2014 No relevant Indications were noted.

UT - 1 flow distributor bolts

(#87) with crack like indications.

VT - No relevant Indications were noted.

84 Flow distributor bolts were inspected in 1987 and bolt #88 was identified with an indication. There was likely a mix-up in numbering in 1987.

Lower G rid A ssembl y Alloy X-750 dowel-to-guide block welds Visual examination (VT-3)

Accessible surfaces of 100% of the 24 dowel-to-guide block welds.

See Figure 4-4 of MRP-227-A.

100%

24 dowel-to-guide blocks welds.

No relevant Indications.

Cam m e n ts: Guide block W9R is bent outward away from the lower grid shell forging and rotated slightly. Welds to the dowel and bolting are intact.

Marks on the guide block and core barrel stand leg indicate that the damage may have occurred during a previous outage when setting the core barrel in the stand.

Page 27 of 91

Oconee 3 Spring 2014 i

I n c or e Mon ito ri ng Visual examination 100% of top surfaces of 52 100%

IMI Guide Tube Spider Casting In strum entation (IMI)

(VT-3) spider castings and welds 52 spider castings, each Weld 88-YL had a linear Guide Tu be As sem bly to the adjacent lower grid casting with 8 welds.

indication located just below the IMI guide tube spiders rib section.

vertical weld toe in the base IMI guide tube spider-to-material of the lower grid.

lower grid rib section welds See Figures 4-3 and 4-6 of MRP-227-A.

IMI Guide Tube Spider Casting Weld G 11-WR had a linear indication coming from the top of the casting at the weld toe and going downward into the casting material.

Comment s:

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.

No EXPANSION components were inspected during spring 2014.

Page 28 of 91

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Turkey Point 4, Sept.2014 Tables ror R e port i n g MRP-227-A I n s pection Re s ult s ror West i n g h o u se P1ants Plant Name: Turkey Point Unit 4 Utility: NextEra Energy/FPL Date of Exams: September-October 2014, PTN4-28RFO Plant Age: __

4_1 __

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E~F~P~Y Primary Components Control Rod Gulde Tube Assembly Guide plates (can:la)

Comments:

Visual examination (VT-3) 20% examination of the number of CRGT assemblies, with all guide cards within each selected CRGT assembly examined.

See Figure 4-20 of MRP-227-A Page 29 of 91 Not inspected during N/A PTN4-28RFO.

Inspection planned for PTN4-29RFO,Spring2016

Turkey Point 4, Sept.2014

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l' Control Rod Guld e Enhanced visual 100% of outer (accessible)

Not inspected during N/A Tub e Assembly examination (EVT-1)

CRGT lower flange weld PTN4-28RFO.

Lower flange welds to determine the surfaces and adjacent base Inspection planned for presence of crack-like metal on the individual PTN4-29RFO. Spring surface flaws in periphery CRGT assemblies.

2016 flange welds (Note 2)

See Figure 4-21 of MRP-227-A.

Comments:

Core Barrel A ssembly Enhanced visual 100% of one side of the 100%

No Recordable Indications Upper core barrel flange examination (EVT-1) accessible surfaces of the weld selected weld and adjacent base metal (Note 4).

See Figure 4-22 of MRP-227-A.

Comments:

Page 30 of 91

Core B*rret As** m loll!'

Upper ancil IGwef'CGR barret cylinder girth welds Co mment s:

Enhanced visual examination (EVT-1)

Core Barre* A ** em i.1:v Enhanced visual Lower core barrel flange examination (EVT-1) weld (Note 5)

Co mment s :

100% of one 'Side of the accessible surfaces of the selected weld and adjacent base metal (Note 4).

See Figure 4-22 of MRP-227-A 100% of one side of the accessible surfaces of the

&elected weld and adjacent bne metal (Note 4).

Page 31 of 91 Upper-100%

Lower-89%

85%

Turkey Point 4, Sept.2014 No Recordable Indications No Recordable Indications No Recordable Indications

Turkey Point 4, Sept.2014

~*

Barr1a-F or mer Visual examination Bolts and locking devices on Not inspected during N/A Assembly (VT-3) high fluence seams. 100% of PTN4-28RFO.

Baffle-edge bolts components accessible from Inspection planned for core side PTN4-30RFO, Fall 2017 (Note 3).

See Figure 4-23 of MRP-227-A.

Comments:

Barrte-F or mer Volumetric 100% of accessible bolts Not inspected during N/A Assembly examination (UT)

(Note 3). Heads accessible PTN4-28RFO.

Baffle..fonner bolts from the core side. UT Inspection planned for accessibility may be affected PTN4-30RFO, Fall 2017 by complexity of head and locking device designs.

See Figures 4-23 and 4-24 of MRP-227-A.

Comments:

Page 32 of 91

B aN'la-Form aT A,..e m bty Assembly (Includes: Baffle plates, baffle edge bolt& and indirect effects of void swellin in fonner lates Comments:

A11g nm e nt an d lnter,ecf n g Compone'ftt.*

Internals hOld down spring Direct measurement of spring height See Figures 4-24, 4-25, 4-26 and 4-27 of MRP-227-A.

100%

Measurements should be 1 00%

taken at several points around the circumference of the spring, wlh 8 statistically adequete number of meaaurements at each point to minimize uncertainty.

See Figure 4-28 of MRP-227-A.

Turkey Point 4, Sept.2014 No Recordable Indications SAT Co m m e nt s

• Measurements taken at eight circumferential positions. All exceeded the minimum height criteria for 60 years of operation.

Page 33 of 91

Comments:

Notes to Westinghouse Primary Components Table:

See Figures 4-29 and 4-36 of MRP-227-A.

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.

Turkey Point 4, Sept.2014

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.

No EXPANSION components were inspected during fall 2014.

Page 34 of 91

Turkey Point 4, Sept.2014 Existin g P rog r ams Co m pone n ts Ex a m In a ti o n Re q uired Coverage E x a m i n ati on Item Meth o d Exam i nati on A ch i eved Findi n gs Coverage Core B a rrel Ass e m b l y Visual examination All accessible 100%

No Recordable Indications Core barrel flange (VT-3) to determine surfaces at specified general condition frequency.

for excessive wear.

Comme nt s:

upper l n 't. er n a l s Visual examination All accessible 100%

No Recordable Indications A ss e m b l y (VT-3) surfaces at specified Upper support ring or frequency.

skirt Comme n ts:

Page 35 of 91

Turkey Point 4, Sept.2014 Exe m lnatl on Req ulred Cov ere g e Ex a m f n etlon Ite m Meth od E

>e a m l n a tlon Ac h la ved Fin dings Co v erage Lo\\Ner I nternals Visual (VT-3)

All accessible 100%

No Recordable Indications Assemb l y examination of the surfaces at specified Lower core plate lower core plates to frequency.

XL lower core plate detect evidence of (Note 1) distortion and/or loss of bolt integrity.

Comments:

Lo\\Ner I nternals Visual examination All accessible 100%

No Recordable Indications Assembly (VT-3) surfaces at specified Lower core plate frequency.

XL lower core plate (Note 1)

Comments:

Bottom Mou nt.e d Surface Eddy current surface N/A N/A lnst.ru mentation examination (ET) examination as System defined in plant Flux thimble tubes response to IEB 88-

09.

Page 36 of 91

Turkey Point 4, Sept.2014 Examination Req ulred Coverage Examination lte m Meth o d E xamination Ac h la v ed Fin d i n gs Coverage Comments:

A1ignmentand Visual examination All accessible 100%

No Recordable Indications I nterfacing (VT-3) surfaces at specified Components frequency.

Clevis insert bolts Com m e nt s:

Alignment and Visual examination All accessible 100%

No Recordable Indications I nterfacing (VT-3) surfaces at specified Compone nts frequency.

Upper core plate alicinment pins Comments:

Page 37 of 91

Turkey Point 4, Sept.2014 Notes to Westinghouse Existing Programs Components Table:

l.

XL= "Extra Long" referring to Westinghouse plants with 14-foot cores.

Page 38 of 91

Prairie Island 1, Oct. 2014 Tables for Reporting MRP-227-A Inspection Results for Westinghouse Plants Plant Name:

Prairie Island Unit 1 Utility: Xcel Energy Date of Exams: October 2014 Plant Age: ____

4.... l ___ (years) I Primary Components Comments:

See Figure 4-20 of MRP-227-A Page 39 of 91 34 EFPY Not Inspected this outage

Control Rod Gulde Tube Assembly Lower flange welds Comments:

Enhanced visual 100% of outer (accessible) examination (EVT-1)

CRGT lower flange weld to determine the surfaces and adjacent base presence of crack-like metal on the individual surface flaws in periphery CRGT assemblies.

flange welds (Note 2)

See Figure 4-21 of MRP-227-A.

Core Barrel Assembly Enhanced visual Upper core barrel ftange examination (EVT-1) weld 100% of one side of the accessible surfaces of the selected weld and adjacent base metal (Note 4).

Comments:

See Figure 4-22 of MRP-227-A.

Page 40 of 91 Prairie Island 1, Oct. 2014 Not Inspected this outage 100%

No Relevant Indications

Prairie Island 1, Oct. 2014 Core Barrel A... mbly Enhanced visual 100% of one side of the Upper and lower core examination (EVT-1) accessible surfaces of the 100% UGW barrel cyHnder girth selected weld and adjacent 76.5% LGW No Relevant Indications welds base metal (Note 4).

See Figure 4-22 of MRP-227-A Comments:

Corf Barret~ Enhanced visual 100% of one side of the La.nr core bl!R"et-lange examination (EVT-1) acceaaible surfaces of the 100%

No Relevant Indications weld (Net* 5) selected weld and adjacent base metal (Note 4).

Comments:

Page 41 of 91

Baffle-Former Assembly Baffle-edge bolts Comments:

Baffle-Former Assembly Baffle-former bob Comments:

Visual examination (VT-3)

Volumetric examination (UT)

(See attached map.)

Bolts and locking devices on high fluence seams. 100% of 1 00%

components accessible from core side (Note 3).

See Figure 4-23 of MRP-227-A.

100% of accessible bolts (Note 3). Heads accessible 728 out of 728 bolts from the core side. UT accessibility may be affected by complexity of head and locking device designs.

See Figures 4-23 and 4-24 of MRP-227-A.

Page 42 of 91 Prairie Island 1, Oct. 2014 No Relevant Indications 40 bolts with indications.

688 bolts had no indications.

No expansion was triggered.

The extent of the bolt failures was bounded by minimum pattern analysis plus margin term per WCAP-17096

Prairie Island BFB Phased Array UT Indication Map G *************

status of 10-23-14 09:38 AM 0

@Ii 90° C§J G

Prairie Island 1, Oct. 2014 GJ

~ 180° F ** ** ****************** * *********** * *****************

E B *********************************** * ***************

A *** * ***** ** *********************** * *****************

G F

E D

c B

A 1

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 180°~ ~

~

@::1 360°

• • • ** **** ** ** ** * * **** ** 1eee * ** * * **** ** ** ** ** **** ** ***

• • • ** **** ** ** ** ** **** ** I*** * ** ** **** ** ** ** ** **** ** ***

• • • ** **** ** ** ** ** **** ** I*** * ** ** **** ** ** ** ** **** ** ***

53 54 55 56 57 58 59 60 61 62 63 G4 65 66 67 68 69 70 71 72 73 74 75 76 77 78 79 80 81 82 83 84 85 86 87 88 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 0 acquisition to do e no acquisition 0 acquisition ok 0 retest e without indication e with indication Page 43 of 91 not testable (UT)

Baffle..Former V1&ual examination Core side surface as Assembly (VT-3) indicated.

1 00%

Assembly (Includes: Baffle plates, See Figures 4-24, 4-25, 4-26 baffle edge bolts and and 4-27 of MRP-227 -A.

indirect effects of void sweDin in former lates Comments:

AUgnment and holddt>wn Comments:

Direct measurement of~height Measurements should be taken at several points Not Applicable (403SS) around -the circumference of the spring, with a statistically adequate number of measurement$ at each point to minimize uncertainty.

See Figure 4-28 of MRP-227-A Page 44 of 91 Prairie Island 1, Oct. 2014 No Relevant Indications

Comments:

Notes to Westinghouse Primary Components Table:

100% of thermal shield flexures.

See Figures 28 and '4-38 of MRP-227-A.

100%

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.

Prairie Island 1, Oct. 2014 No Relevant Indications

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.

No EXPANSION components were inspected during fall 2014.

Page 45 of 91

Prairie Island 1, Oct. 2014 Existing Programs Components Examination Required Coverage Examination Item Method Examination Achieved Findings Coveraae Core Barrel Assembly Visual examination All accessible Core barrel flange (VT-3) to determine surfaces at specified 100%

No Relevant Indications general condition frequency.

for excessive wear.

Comments:

Upper Internals Visual examination All accessible Assembly (VT-3) surfaces at specified 100%

No Relevant Indications Upper support ring or frequency.

skirt Comments:

Page 46 of 91

Prairie Island 1, Oct. 2014 Examination Required Coverage Examination Item Method Examination Achieved Findings Coverane Lower Internals Visual (VT-3)

All accessible Assembly examination of the surfaces at specified 100% of Accessible Surface No Relevant Indications Lower core plate lower core plates to frequency.

XL lower core plate detect evidence of (Note 1) distortion and/or loss of bolt integrity.

Comments:

Lower Internals Visual examination All accessible Assembly (VT-3) surfaces at specified 100% of Accessible Surface No Relevant Indications Lower core plate frequency.

XL lower core plate (Note 1)

Comments:

Page 47 of 91

Prairie Island 1, Oct. 2014 Examination Required Coverage Examination Item Method Examination Achieved Findings Coveraae Bottom Mounted Surface Eddy current surface Instrumentation examination (ET) examination as 35 out of 36 flux thimble tubes 6 tubes with wall loss 40-59%

System defined in plant (one has an internal restriction 18 tubes with wall loss 20-39%

Flux thimble tubes response to IEB 88-due to having been bent and is 1 tube with wall loss 1-19%

09.

capped off) 10 tubes with no wall loss Comments: ***REPORT UPON THESE INSPECTIONS ONLY WHEN DONE IN CONJUNCTION WITH MRP-227-A RELATED EXAMS. ***

Alignment and Visual examination All accessible Interfacing (VT-3) surfaces at specified 100%

No Relevant Indications Components frequency.

Clevis insert bolts Comments:

Page 48 of 91

Prairie Island 1, Oct. 2014 Examination Required Coverage Examination Item Method Examination Achieved Findings Coveraae Alignment and Visual examination All accessible Interfacing (VT-3) surfaces at specified 100%

No Relevant Indications Components frequency.

Upper core plate alionment pins Comments:

Notes to Westinghouse Existing Programs Components Table:

1.

XL= "Extra Long" referring to Westinghouse plants with 14-foot cores.

Page 49 of 91

Intentionally Blank Page 50 of 91

Point Beach 2, Oct.2015 Tab l es for R e po r ting MRP-227 - A In s p ec t i o n R es u lt s fo r We st i ngho u se P 1a nt s Plant N ame: _ __.P--..o.... in.... t_.B._e.... a.... c_h_N_u_c_le_a_r_P_l_a_n_t_U_n_1_* t_2 __ Utility:

N extEra Energy Date of Exams: __

O"-c"'"'t-..o.....

b.._er.....,_2_...0 __ 1s ___ __._CU.._2_R3_4_.)..__ ____ Plant Age: __

4_3 ______ (years) / _:::::_3...... S __ EFPY Primary Components Contr ol R oct GulCI*

Tut>eA*a*mbly Guide.,.... (carda)

Co m m en't.s:

Visual examination (VT-3) 200.4 examination of the number of CRGT assemblies, with all guide cards within each selected CRGT assembly examined.

See Figure +.20 of MRP-227-A 100% of the CRGT assemblies (COMPLETED DURING U2R33 - REPORTED APRIL 2014)

See below 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.

Page 51 of 91

Point Beach 2, Oct.2015 Con u ol R od G ulde Tube A ssembl y Enhanced visual 100% of outer (accessible) 100% of outer CRGT No recordable indications Lower flange welds Comments'.

examination (EVT-1}

CRGT lower flange weld lower flange welds and to determine the surfaces and adjacent base adjacent base metal presence of crack-like metal on the individual surface flaws in periphery CRGT assemblies.

flange welds (Note 2)

(COMPLETED DURING U2R33 - REPORTED SeeFigure4-21 ofMRP-227-APRIL 2014)

A.

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.

Cor e Barre 1 A ss e m b1y Enhanced visual Upper core barrel flange examination (EVT-1) weld Comments:

Exterior surface 100% of one side of the accessible surfaces of the selected weld and adjacent base metal (Note 4).

See Figure 4-22 of MRP-227-A.

Page 52 of 91 100% of Weld Length No indications

Cor* 8.,.,

Upper and tower core barrel cylinder girth welds Comments:

Exterio r s u rface Enhanced Yiewal examination (EVT-1)

See Figure 4-22 of MRP-227-A 100% of Upper Core Barrel Cylinder Girth Weld Length 55.6% of Lower Core Barrel Cylinder Girth Weld Length Point Beach 2, Oct.2015 Lo\\Ner Core Barre1 Cy 1inder Girth We 1d 1s behind the Therme 1 Shie l d. The 9 ap between in side surface of the therma l sh1e 1d and outside su rf ace of the core barre l limited access to the entire we l d.

100% of th e 1ength of the Upper Care Barr e l Cy1inder Gi rth Wc1d + 55.6% of the 1e ngt h of the Lovver Care Barre l Cy 11n der Girth Weict We re Ex a m; n e d I 2 We I ds :::: 78% of total weld length (Greater than 75% minimum of the total weld length)

Core B a r.rel A aaa m bty Lower CCR~-.

weld (Note 6)

Com m e nt s'.

Exterior su r face Enhanced visual emnination (EVT-1) 100% of one side of the accesai>le surfacesofthe selected weld 8l'ld adjacent base metal (Note 4).

Page 53 of 91 100% of Weld Length No indications

Point Beach 2, Oct.2015 it..

Barr1e-F or mer Visual examination Bolts and locking devices on 100% of Baffle Edge No indications A* **mt>1,,

(VT-3) high fluence seams. 100% of Bolts Baffle..edge bolts components accessible from core side (Note 3).

See Figure 4-23 of MRP-227-A.

Co mment s :

B affle -Form er Volumetric 100% of accessible bolts 100% (727 - see below) 15 (< 3%) original bolts exhibited A *sem bly examination (UT)

(Note 3). Heads accessible repo1table ultrasonic indications.

Baffle..fonner bolts from the core side. UT (COMPLETED DURING All of the reported indications in the accessibility may be affected U2R33 - REPORTED bolts were in the head to shank by complexity of head and APRIL 2014) locking device designs.

interface region (OHS).

See Figures 4-23 and 4-24 of No reported indications in the MRP-227-A.

replacement bolts Co mment s :

552 - original bolts. 175 - replacement bolts Total of 727 bolts. One bolt location does not contain a bolt Page 54 of 91

A as em bly Assembly

{Includes: Baffle plates, baffle edge bolts and indirect effects of void sweUi in fonner lates A11 g n m

• nt a n d lnterf'acl.. g Co.,.,...,,..,.ta

.,,....bald spring Comments :

Direct measurement of spring height See Figures 4-24, 4-25, 4-26 and 4-27 of MRP-227-A.

Measurements should be N/ A taken at several points around 1he circumference of the spring, with a atatisticaHy adequate number of measURMnents at each point to minimize uncertainty.

See Figure 4-28 of MRP-227-A.

N/A -

Point Beach I nternals hold dovvn spring Is Type 403 SS Page 55 of 91 Point Beach 2, Oct.201 5

Comments:

6Therma1 Sh1e1d F1exures Notes to Westinghouse Primary Components Table:

See Figures 4-28 and 4-36 of MRP-227-A.

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.

Point Beach 2, Oct.2015

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.

No EXPANSION components were inspected durfing fall 2015.

Page 56 of 91

Point Beach 2, Oct.2015 Existing Prog r ams Components Examinetlon Req ulred Cover*ge Examination lt:em Method Exam i nat: l on Ach ie ved Findings Coverag e Core B ar r e l A sse mb l y Visual examination All accessible Core barrel flange (VT-3) to determine surfaces at specified N/A general condition frequency.

for excessive wear.

Comments:

ASM E Section XJ \\S J Exam not pe rformed during LJ2R33 or LJ 2R34 Upper I n t e rnal s Visual examination All accessible Ass embly (VT-3) surfaces at specified Upper support ring or frequency.

N/A skirt Comments:

ASM E Section XJ ISi Exam not perfo r med during LJ2R33 or LJ2R34 Page 57 of 91

Point Beach 2, Oct.2015 Exami n ation Required C ovarege Exeml n etlo n lum Method Examination Achieved Ftndlngs Coverage Lovvc r I nter n a l s Visual (VT-3)

All accessible Assembly examination of the surfaces at specified Lower core plate lower core plates to frequency.

N/A XL lower core plate detect evidence of (Note 1) distortion and/or loss of bolt integrity.

Commenr:s:

ASME Section XI ISi Exam not pe rformed during LJ2R33 or LJ2R34 Lovve r Int e rn a l s Visual examination All accessible Assemb ly (VT-3) surfaces at specified Lower core plate frequency.

XL lower core plate N/A (Note 1)

Comments :

ASM E Section XI ISi Exam not performed during LJ2R33 or LJ2 R34 Page 58 of 91

Point Beach 2, Oct.2015 Ex a m i neition Required Cov e rage Examinati on Item Method Ex a m ination Achie v ed Findings Coverage Bott om M o unt e d Surface Eddy current surface I n s t r u men ta t i on examination (ET) examination as Sy s tem defined in plant N/A Flux thimble tubes response to IEB 88-

09.

Comments:

ASME Section XI ISi Exam not performed during LJ2R33 or LJ2R34 A1 i g n m e n t a n d Visual examination All accessible 100%

No recordable indications I nterfacing (VT-3) surfaces at specified Compone nt s frequency.

Clevis insert bolts Comment:.s:

Page 59 of 91

Point Beach 2, Oct.2015 Exam 1 nation Req u ir ed C overage Exemlnatlon Item Method Exam In atlo n Achie v ed Findings Coverage A

11g n mc n t.an d Visual examination All accessible N/A l nt.e r facing (VT-3) surfaces at specified Componenr:s frequency.

Upper core plate alionment pins Comments:

ASME Section XI ISi Exam not pe rformed during LJ2R33 or LJ2R34 Notes to Westinghouse Existing Programs Components Table:

1.

XL = "Extra Long" referring to Westinghouse plants with 14-foot cores.

Page 60 of 91

Turkey Point 3, Nov.2015 T ab l e s ro r R e po r t in g M RP-227-A I n s p e ctio n R e s u lt s ror West in g h o u s e P 1ant s, Rev.2 Plant Name: Turkey Point Nuclear Plant Unit 3 Date of Exams: PTN3-28RFO 10/19/15 to 12/2/15 Utility: Florida Power and Light Plant Age: 43.5 (years) I 31.70 EFPY Primary Components CoM:ro1 T..... A *** 111

~

t*eam1neoo* n ~WCNJ-11.iis1.P of CROT assemblies.

Guide plltel {CMJ8) aasembfies, with al guide cards within each selected CROT assembly examined.

See MRP-201-4..00S and WCAP-17451.P Page 61 of 91

Turkey Point 3, Nov.2015 Comments:

VT-3 inspection and Guide Card Wear Measurements (GCWM) were completed on nine (9) guide tubes (i.e. 20% of the active locations in the upper internals).

Results using the 20% adjusted wear volume are as follows:

Wear Location

(%)

C-7 6

0-8 6

F-4 3

F-12 7

H-8 7

K-14 39 L-5 7

M-8 18 P-10 12 All indications were analyzed using WCAP-17451 and are within the allowable values.

Page 62 of 91

Turkey Point 3, Nov.2015 t-(

C o n t rol Roo G ui d e Enhanced visual 100% of outer (accessible) 100% of weld length.

No recordable indications.

Tube A sse mbly examination (EVT-1)

CRGT lower flange weld Lower ftange welds to detennine the surfaces and adjacent base presence of crack-Uke metal on the individual surface flaws in periphery CRGT assemblies.

flange welds (Note 2)

Sae Figure 4-21 of MRP-227-A.

Com m e nt s:

Two hundred sixteen (216) welds were inspected to EVT-1 quality. No recordable indications were identified during the GT flange weld inspections.

Core Ba r rel As* em bly Enhanced visual 100% of one side of the 100% of weld length.

No recordable indications Upper core barrel flange examination (EVT-1) aoceasible surfllces of the weld selected weld and adjacent (Completed during PTN3-27RFO-base metal (Note 4).

Reported Spring 2014).

See Figure 4-22 ofMRP-227-A.

Comments:

Page 63 of 91

Core Barrel Assembly Upper and lower core barrel cylinder girth welds Com m en t s:

Enhanced visual examination (EVT-1)

Core Barr** A.... "' bty Enhanced visual Lower core barrel flange examination (EVT-1) weld (Note 5)

Co mm e nt. s:

100% of one side of the accessible surfaces of the selected weld and adjacent base metal (Note 4).

100% of Upper Core Barrel Cylinder Girth Weld Length.

90.6% of Lower Core See Figure 4-22 of MRP-227-Barrel Cylinder Girth A

Weld Length.

100% of one side of the accessible surfaces of the selected weld and adjacent base metal (Note 4).

Page 64 of 91 90.5% of Weld Length.

Turkey Point 3, Nov.2015 No recordable indications (Completed during PTN3-27RFO-Reported Spring 2014).

No recordable indications.

(Completed during PTN3-27RFO-Reported Spring 2014).

Berfla-F or mer Assem b l y Baffle-edge bolts Co mment s.

Visual examination (VT-3)

Bolts and locking devices on 100% of Baffle Edge high fluence seams. 100% of Bolts.

components accessible from core side (Note 3).

See Figure 4-23 of MRP-227-A.

Turkey Point 3, Nov.2015 No recordable indications in 936 baffle edge bolts.

No recordable indications in 936 examined edge bolts.

Baffle-Form er Assemb l y Baffle-fonner bolts Commen t s:

Volumetric examination (UT) 100% of acceuibJe bolts Only 305 of 1088 baffle No recordable indications in 305 (Note 3). Heads accessible former bolts were baffle former bolts.

from the core side. UT examined.

accessibifity may be affected by complexity of head and locking device designs.

See Figures 4-23 and 4-24 of MRP-227-A.

Only 305 of 1088 bolts were examined due to equipment issues. Remaining bolts are planned for a future outage.

Page 65 of 91

Berrte*F or mer Assembly Assembly (Includes: Baffle plates, baffle edge bolts and indirect effects of void swellin in former Comment s:

A1 gn men~ and lnce~f'eclng Coni.fl>Ol'lenta lntemata hold down spring C o mment: s:

Visual examination (VT-3)

Direct measurement of spring height Core side surface as indicated.

See Figures 4-24, 4-25, 4-26 and 4-27 of MRP-227-A.

100%

Measurements should be 1 00%

taken at several points around the circumference of the spring, with a statisticaUy adequate number of measurements at each point to minimize uncertainty.

See Figure 4-28 of MRP-227-A.

Page 66 of 91 Turkey Point 3, Nov.2015 No recordable indications (Completed during PTN3-27RFO-Reported Spring 2014).

SAT (Completed during PTN3-27RFO-Reported Spring 2014).

Co mm e nt s:

Notes to Westinghouse Primary Components Table:

See Figures 4-29 and 4-36 of URP-227-A.

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.

Turkey Point 3, Nov.2015 (Completed during PTN3-27RFO-Reported Spring 2014).

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.

No EXPANSION components were inspected during fall 2015.

Page 67 of 91

Turkey Point 3, Nov.2015 Ex i sti n g Prog r am s Com poncnt s Exam i nation Req ui red Coverage Exam i n a tion lte m Method Exam i nation Ach ieved Find i ng s Coverage Co r e Ba r re t A sse mb l y Visual examination All accessible 100%

A significant impression and a Core barrel flange (VT-3) to determine surfaces at specified minor arc-shaped impression were general condition frequency.

identified on the underside surface for excessive wear.

of the CBF at the 25-degree location, and a significant impression was identified at the 240-degree location. The impressions appear to have been caused by foreign material (FM) trapped between the underside surface of the CBF and its mating surface, the top side of the CSL.

(Completed during PTN3-27RFO-Reported SprinQ 2014).

Co mm e nt s:

The two impressions appear to have been caused by (FM) trapped between the two mating surfaces. The impressions are highly localized and not expected to affect the functionality and bearing area of these surfaces.

U ppe r In t e rn a l s Visual examination All accessible 100%

No recordable indications Asse mb l y (VT-3) surfaces at specified Upper support ring or frequency.

(Completed during PTN3-27RFO-skirt Reported Spring 2014).

Comments'.

Page 68 of 91

Turkey Point 3, Nov.2015 Ex a m In att o n RequJred Coverage Exe m inatlon Item Method Examinati o n Achieved Fi nd i n g s Coverage L owe r I nterna l s Visual (VT-3)

All accessible 100%

No recordable indications Assemb l y examination of the surfaces at specified Lower core plate lower core plates to frequency.

(Completed during PTN3-27RFO-XL lower core plate detect evidence of Reported Spring 2014).

(Note 1) distortion and/or loss of bolt integrity.

Comments:

Lovvcr Internal s Visual examination All accessible 100%

No recordable indications A sse mb l y (VT-3) surfaces at specified Lower core plate frequency.

(Completed during PTN3-27RFO-XL lower core plate Reported Spring 2014).

(Note 1)

Com men-rs'.

Page 69 of 91

Turkey Point 3, Nov.2015 Exam i nation Requi r e d Co v erage Examination lte m Method Examinatio n Ac hle v e d Find i ngs Coverage Bottom Mou nLe d Surface Eddy current surface Replaced seven thimble tubes Seven thimble tubes successfully I n strum e ntatio n examination (ET) examination as during PTN3-27RFO.

replaced.

Sy s tem defined in plant Flux thimble tubes response to IEB 88-

09.

Com m e n ts :

A1ig n mentand Visual examination All accessible 100%

Abrasive wear noted on bolts and I nterfacing (VT-3) surfaces at specified lock bars at 270° key and clevis.

Components frequency.

Degradation attributed to foreign Clevis insert bolts material, possibly an RCP diffuser adapter cap screw, retrieved during previous RFO.

(Completed during PTN3-27RFO-Reported Spring 2014).

Co mm e nt s:

Page 70 of 91

Turkey Point 3, Nov.201 5 E xa m l n at.l on R e q uire d C o v era ge E x a m l n e tlon Ite m M ethod Exa m l n a tlon A c hi e ved Find i ng s Coverage A1 ig n me nt a n d Visual examination All accessible 100%

No Recordable Indications I nterfacing (VT-3) surfaces at specified Compone nt s frequency.

(Completed during PTN3-27RFO-Upper core plate Reported Spring 2014).

alignment pins Comments:

Notes to Westinghouse Existing Programs Components Table:

1.

XL= "Extra Long" referring to Westinghouse plants with 14-foot cores.

Page 71 of 91

I ntentionally Blank Page 72 of 91

Prairie Island 2, Nov. 2015 T a b l es For Report i ng MRP-227-A I n spect i o n Resu lts For West i ng h ouse P 1ants, R ev. 2 Plant Name: ___

P~

ra~i~

ri~e~I=s~la~n~d_U

~n_it~2 ____ Utility: ____

X_c_el_E

_n_

e r~g~y ____ _

Date ofExams: _ _ N~

ov_e_m_b~e_r_2_0_1_5 ___ Plant Age: ___

4_2 __ (years) I 35.5 EFPY Primary Components Conuot Rod Gvtd*

Tub* A........,>'

Guide plates {cards)

Com ments '.

Visual examination (VT-3)

Examination per \\'VCAP*

Maximum% volume vvear:

17451-Pof CRGT Not Inspected this outage Five (5) vvorsr case CRGTs:

assemblies, with all guide cards within each selected (ref. Figures 3-5 through 3-7 of CRGT assembly examined.

WCAP-17 451-P for conversion of See MRP-2014-006 and WCAP-17451-P Page 73 of 91 wear measurements to wear volume.

Also specify high or low flow operation as defined in Tbl 4-2 of the WCAP

Prairie Island 2, Nov. 201 5

fl

,,

Concr o l Roo Gulde Enhanced visual 100% of outer (accessible)

Tube Assembly examination (EVT-1)

CRGT lower flange weld 100% of peripheral welds Lower flange welds to determine the surfaces and adjacent base that were accessible No relevant indications presence of crack-like metal on the individual were examined.

surface flaws in periphery CRGT assemblies.

flange welds (Note 2) 42 weld segments were inspected EVT-1.

See Figure 4-21 of MRP-227-A 27 weld segments were inspected as best effort.

51 weld segments on the outer peripheral guide tubes were inaccessible for inspection (back side, obstructed, etc.)

Comments:

Note that the PINGP 14x14 CRGTs have 6 lower flange welds each, due to the fully enclosed guide tube (same as 17x17).

Core B arrel Assembl y Enhanced visual 100% of one side of the Upper core barrel flange examination (EVT-1) accessible surfaces of the 100%

No relevant indications weld selected weld and adjacent base metal (Note 4).

See Figure 4-22 of MRP-227-A.

Comments:

Page 74 of 91

C ore Barrel A ssembl y Upper and lower core barrel cylinder girth welds Comme n r.s:

Enhanced visual examination (EVT-1)

Core Barre

• As.* m..,Y Enhanced visual Lower core '*'81... examin8ltion (EVT-1) weld.(Nole I)

Comments:

100% of one side of the accessible surfaces of the selected weld and adjacent base metal (Note 4).

100% of Upper Girth Weld See Figure 4-22 of MRP-227-76.5% of Lower Girth A

Weld 100% of one side of the accessible surfaces of the aelected weld and adjacent base metal (Note 4).

Page 75 of 91 100%

Prairie Island 2, Nov. 201 5 No relevant indications No relevant indications

Assem b ly Baffle..edge bolts Co mm e nt s:

B affl e - F orm e r A ssembly Baffle-former bolts Comments:

Visual examination (VT-3)

Volumetric examination (UT)

Bolts and locking devices on high fluence seams. 100% of 1 00%

components accessible from core side (Note 3).

See Figure 4-23 of MRP-227-A.

100% of accessible bolts (Note 3). Heads accessible Not examined this from the core side. UT outage.

accessibility may be affected by complexity of head and locking device designs.

See Figures 4-23 and 4-24 of MRP-227-A.

Page 76 of 91 Prairie Island 2, Nov. 2015 No relevant indications

B erfl a -For ma r A sse mb l y Assembly (Includes: Baffle plates, baffle edge bolts and indirect effects of void swellin in fonner lates Commen ts :

A1 gn ment. end lno:erf'ectng ComponenC*

tntelMll hoJd Commen t s:

Visual examination (VT-3)

Direct measurement of spring height Core side surface aa indicated.

See Figures 4-24, 4-25, 4-26 and 4-27 of MRP-227-A.

Measurements should be taken at several points around the circumference of the spring, wlh a statisticaly adequate number of measurements at each point to minimize uncertainty.

See Figure 4-28 of MRP-227-A.

Page 77 of 91 100%

Not Required for springs of type-403 material.

Prairie Island 2, Nov. 2015 No relevant indications

A ase mb l y Thermal shield ttexurea Co mment s:

Notes to Westinghouse Primary Components Table:

See Figures 29 and 4-36 of MRP-227-A.

100%

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.

Prairie Island 2, Nov. 2015 No relevant indications

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.

No EXPANSION components were inspected in Nov.2015.

Page 78 of 91

Prairie Island 2, Nov. 201 5 Exis"t i ng Progr a m s Co mpon ents Examtnatlon Required Coverage Examination lte m Method Exam i nation Ach ie ved Findings Coverege Core Barre l A sse mb l y Visual examination All accessible Core barrel flange (VT-3) to determine surfaces at specified 100%

No relevant indications general condition frequency.

for excessive wear.

Comments:

Upper Inter n a l s Visual examination All accessible Assemb l y (VT-3) surfaces at specified 100%

No relevant indications Upper support ring or frequency.

skirt Comments'.

Page 79 of 91

Prairie Island 2, Nov. 2015 Exami n ation Req ulred Coverege Ex a m in e ti on Item Method Examinati on Ac hleved Findings Coverage Lower Internals Visual (VT-3)

All accessible Assembly examination of the surfaces at specified 100%

No relevant indications Lower core plate lower core plates to frequency.

XL lower core plate detect evidence of (Note 1) distortion and/or loss of bolt integrity.

Com m e n ts:

Lower Internal s Visual examination All accessible Assemb l y (VT-3) surfaces at specified 100%

No relevant indications Lower core plate frequency.

XL lower core plate (Note 1)

C omm e n t s '

Bottom Mounted Surface Eddy current surface I n s trum e nr.atio n examination (ET) examination as Not examined this outage.

System defined in plant Flux thimble tubes response to IEB 88-

09.

Page 80 of 91

Prairie Island 2, Nov. 201 5 Exe m !nation Required Coverage Examinet.t o n Ite m M ethod Examination Ac h I e v e d Fin d i n gs Coverage Comments: **'REPORT UPON THESE INSPECTIONS ONLY WHEN DONE IN CONJUNCTION WITH MRP-227-A RELATED EXAMS....

Alignment. and Visual examination All accessible Interfac ing (VT-3) surfaces at specified 100%

No relevant indications Components frequency.

Clevis insert bolts Comme n ts'.

A 1ignmc n t and Visual examination All accessible I nterfacing (VT-3) surfaces at specified 100%

No relevant indications Components frequency.

Upper core plate alignment pins Comme nt s:

Page 81 of 91

Prairie Island 2, Nov. 2015 Notes to Westinghouse Existing Programs Components Table:

1.

XL= "Extra Long" referring to Westinghouse plants with 14-foot cores.

Page 82 of 91

TMl-1, FALL2015 Tab l es for R eport in g MRP-2 2 7 - A I n spectio n Res u lts f or B&W P1 a n ts Plant Name: Three Mile Island Nuclear Station Unit 1 Utility: Exelon Generation Date of Exams: 10/28/2015 to 11/23/2015 Plant Age: _4_1 _________ (years) / ----'3~0_

.4 ___ EFPY Primary Components Pte,.um Cow*rAs *emlUy &

Core S u pport Sl\\Jeld Ass em 1o1y P1enum cover watdment rib One~l m e physica l measurement (1nttl*l Inspection) pads Visua l (VT-3) for P1enum cover support na n ge s u bse qu ent CSS t o p flange Com m e nt s:

N o fi n di n g s we re re p o r te d.

Co n tr ol Rod G ulde Tube Assembly CRGT spacer c a stings Com m e nt s:

I n spection s V is u a l (VT-3}

Not Examined duri n g Fa ll 2015.

P 1anne d for F a ll 2017.

dlffaranti*t height or top of p l enum rib pads to reactor vessel ***ting surface, wtth plenum tn reactor vesse l.

S ee F 1g&.1re 4-1 o rMRP-227-A.

Ac cess ib le su rfaces at each of the 4 screvv focetlons (*t e v ery 90°) of 100% of the CRGT spacer ce s t ings

(.um ite<i accessf b lllty).

See Figure 4-5 orMRP-227-A.

Page 83 of 91 100% or t h e \\Ne l dmentrlb pads, p 1 e n um s upport fl a n ge, and CSS top r l ange.

N/A N o fi n d i n g s,

N/A

Core Support SMeld Assembly CSS v*nt valve 'top ret.afnlng rtng CSS vent valve bottom retain ng ring (Note 1)

Comments:

Visual (VT-3)

Not Exam;ned dur;ng Fa ll 2015.

P 1anned for Fa ll 2017.

100% of ecca **Ible surfaces (see BAW-2248A, peg*

4.3 end T*ble 4-1).

See Figure 4-11 ofMRP-227-A.

TMl-1, FALL2015 N/A Loc k ing devices vve r e exa m i n ed for a ll Ve n t Va lves.

N/A I mpact damage noted on al l va l ves, with one felled l ocking d ev i ce requ iring va l ve replacement, Ve n t va lv e l ocking dev i ces vve r e e x ami n ed for e l l ve nt v a l ves TS r eq ui reme n ts a n d T M I s p ec ifi c commit m e nt to M RP-227 - A and PWRQG I n terim gu id ance. One vent va l ve (adj acen t to the hot leg) vvas fo u nd vvit h a fai l ed l oc k l n g d e v ice in vvh i ch th e spr i ng retainer had vvorn through t h e l ocking cup. The l ocking c u p end spring r etai n ervvere functiona l as - found, but an assess m ento f o p e r abillty over the next cyc l e cou l d not be made. The dam age mechanism was f l ow induced wear and was be l ieved to or i ginate in 1Rl 8 after impact from the P 1enu m. This vent va l ve was of the origina l design.

Re m a i n in g ve n t valves exhib ite d i m pact damage o n t h e l ock in g devices from t h e Insta ll a t io n of t he Prcnu m.

This I m pac t d a m age did not Im pact th e ability o f th e l ocklng devices to perform their design functio n s.

Co.su...

St......,

A***ai a11r Upp- <:ore l>al' *t (UCB}

boft:a and tftalr l-ocilt,,o ld*vtces Comments:

Votumetr c examU** on (UT) of the boka V1auat (VT-3}

ex* mlnatton of bolt locking devices 100% or aocesstble 1>-*

(Note 3)

See Ftgure 4-7 of MRP-227-A.

100% of a ll bolts and their l oc k ing devices.

120 bo lts e x ami n ed.

One indeterminate volu m etrlc exam of bo l t 24. Assumed fai l e d.

One bo lt(# 24) was Indeter m inate based on vo l umetr ic exa m res u lts.

T he indeterminate response was t he resu l t o f a l ow amp l it u de backwa ll respo n se l ess than t h e 60% m i nim um r equired by proced u re. The backwal l res p o n se was 53%.

N o f l aws were vis i b l e in the reviewed data; however the bo l t was conservatlve l y assu m ed fai l ed. Expansion cri t eria were nottrtggcrcd.

Page 84 of 91

Core Barrel Assembly Lower core barrel (LCB) bolts and their locking devices Comme n ts'.

No fi n dings.

Core Barrel Assembly Baff'te"'to""torm er boks Comme nt s'.

Volumetric examination (UT) of the bolts Visual (VT-3) axe mlnetlon of bolt locking devices V 01u m etrlc examination (UT) 100% or accessible bolts and their tocking devlces (Note 3) s ** F111ur* 4-8 of' MRP-227-A.

100% of eccesstbta bolts.

(Note 3)

See F111ure 4-2 o f MRP-227-A.

Not Examined during Fall 2015. Examination t s p l anned for F a ll 2017.

Core Barrel Assembly Bame plates Commen t s:

Vtsual examination (VT-3) 100% of the accessible surface within 1 inch around each now end bolt hole.

See Figure 4-2 of MRP-227-A.

Not examined during Fall 2015. Examin ation is p l a nn ed for Fa ll 2017.

Page 85 of 91 TMl-1, FALL 2015 100% of a ll bo lts and t.heir No finding s.

l ocking devices.

108 bo lts examined.

N/A N/A N/A N/A

Core Berrel Assembly Locking devices, includlng locking welds, or beme~o form er bo lts and tnt.ernal b arr1e - to - b effle bolts Comments:

Visual examination (VT-3) 100% or accessible bame-

'to-former end Internet baffle-to-baffle bolt locking de v ices. (Note 3)

See Figure 4-2 or MRP-227-A.

Not Examined during Fa ll 2015. Examination is planned for Fa ll 2017.

F1ow D1urllH*t* Aa ** m lltty Frow dlsulb"Utor ( 0) bok*

e ntl the r rocking tl*v cee Comments :

V 01u m atrtc

• xem1nat1on (UT) or the bolts Visual (VT-3) ex* m1natlon of bolt tocking devices 100% or" cc esslble bolts and thel-r tocking devices.

(Not* 3)

See F gure 4-8 or MRP-227-A.

TMl-1, FALL 2015 N/A N/A 100% o f a ll bo lts a nd th e i r One volumetric i ndica tion on l oc kin g dev ices.

bo lt44.

108 bo lt s examrned One v olu m etrlc Ind le etio n noted i n bo lt 44. The indication was reported as a crack in the upper threads approximately 4.40" from the top of the bolt head.

Ex pa n sion criteria vvere not triggered.

Lower Grid Assemb ly Anoy X-750 dowel-to-guide block wetels Com m ents'.

V isua l examination (VT-3)

A ccessible surfaces ot 100% orthe 24 dowel-to-guide block welda.

See figure 4-4 or MRP-227-A.

100% of dovv e l -to-gulde No r e l eva nt Indica tion s n oted.

b l ock vve l ds.

12 guide b l ock pair s e xamin ed.

F ound a l oose parts issue assoc i ated vvith a meta l s live r on the under si de of t h e gui d e b l ock. The l oose part was r e m oved.

Page 86 of 91

Inca-re Mol'ltt°'rlnfJ lnso;rument*tiol'I (1Mt)

G..... Tub* A........ ij,'

IMt guide tub* ap.tden IMJ 9"1d* tu** *l"k:l... "'t.0-tower grid rib section welds Comme nt s:

Vtsuat examination (VT-3) 100% ort:op aurfacas or 52 sptder c=astlngs *ncf welds to the a<ljacant lowar grid rtb s ectJon.

See Fie.... ** 4-3 and 4-6 or MRP-227-A.

Not Examined during Fa ll 2015. Examination is p l anned fo r Fa 11 2017.

Notes to B&W Primary Componont Tab l e TMl-1, FALL2015 N/A N/A l,

A verification of' the operation or each vent. va l ve s ha ll atso be performed through manua l actuation oft. h e va l ve, Verify that the valves are not st uck In the open position and that no abnormal degradation has occurred, Examine the valves for evidence of scratches, pitting, embedded partlc l cs, l ea k age of the scat.Ing surfaces, cracking of l ock welds and locking cups, jack screws for proper position, and wear. The frequency is defined in each unit's technical specifiC a<io n s oc In Ch" pump

• n d v alvo In. ocvlc 0 '""

pcogca ms (soe BAW-2248A, pogo 4-3 and Tab le 4-1, coroccncc 18 orMRP-227-A).

2.

Examination accoptuncc c r it eria and expansion criteria for tho B&W com ponent s arc In Tab l e 5 - 1 of MRP-227 - A.

3.

A minimum or75% of' the total populetlon (examined+ unexemlned). I ncluding coverege consist&ntvvith the Expenslon criteria In Tab l e 5-1, must be exam i ned for Inspection credlL Page 87 of 91

TMl-1, FALL2015 Expansion Components Examination Required Coverage Examination lte m Method Examinat i on Achieved Findings (Note 1)

Cevera ge Upper Grid Assemb ly Visua l ex a m In a t i on Acces s ib l e su r faces or N/A N/A A11oy X-750 dovve l-to-upper (VT-3) 100% or the dowe l grid fu e I a s s e m b I y s upport l ocking vve l ds.

pad vvelds See Figure 4-6 or MRP-227-A (i.e., these are s imil ar to the lower grid fue l assemb l y support pads).

Com m e nt s :

Expans io n to th i s item vvas not required during Fa ll 2015.

Core Barrel Assemb l y Bolts : Vo 1u metric 1 00% of a cc e s s 'b I e N/A N/A Upper therm a1 shield (UTS) e xamination (LJT).

bo lt s or studs/nuts and bo l ts and their l ocking devices Lock in g Devices:

their locking devices Vis u a l examination (Note 2).

(VT-3)

See Figure 4-7 or MRP-227-A.

Comments:

Expansion to this item vvas notrequtred during Fa 11 2015.

Page 88 of 91

TMl-1, FALL2015 E x a m I n a t i o n Requir e d Cov e r age E xa m i n ation lte m Meth od Exa m i n a t io n A

c hi e ved Find ings (Note 1)

C o ver age Core B a rr e l Ass e mbly Bolt or Stud/Nut:

100% o f acces s i b l e N/A N/A Survc ill a nee specimen hold e r Vo lum etri c bolts or st u d s / nu t s and tu be (SSHT) stud s / n uts (CR-exam i nation (LJT).

their tock i ng dev i ces

3) or bo lts (DB) and their Lock ing Dev ice s:

(Note 2).

locking devices Visua l ex a m i n a ti on (VT-3)

See Fig ur e 4-7 of MRP-227-A.

Comme n ts'.

T h is item does no t app ly to TMI.

Lovver Gr i d Assemb l y Visua l ex a m i n a ti on Access i b l e s u rfaces of N/A N/A Lovve r g r i d f u e l a ss c m b l y (VT-3) t h c pad S, dovvc l s, and s upport pad ite m s: pad, p a d-cap s crews, and to-rib section we l ds, A 11 oy X-a ss ociated we l ds in 750 dovve l, cap s cre\\N 1 and 100% of the lovve r grid their l ocking w e l d s fuel assemb l y support pads.

See F ig ur e 4-6 of MRP-227-A.

Comments :

Expans ion to t h is item vva s not req uired d ur in g Fa11 2015.

Lower Grid Assembly Visua l ex a min a t l on Acc es sib l e su r fac es of N/A N/A A11oy X-750 dovve i-to-lovver (VT-3) 100%ofthe suppo r t grid fue l assemb l y S LI pp Ort pad dowe l l oc k ing pad welds vve l ds.

See F igure 4-6 of MRP-227-A.

Commen t s :

Expansion to t h is i t. em "'as not. req u ired d uri ng Fa11 2015.

Page 89 of 91

TMl-1, FALL2015 Examination Required Coverage Examination lte m Method Examination Achieved Finding s (Note 1)

Coverage Lovver Grid Assemb l y Bolts : Vo 1u m etr l c 100% of accessib l e 100% of all bo lts and thei r No fi n di n gs.

Lovvcr grid shock pad bo lts exa m inati on (LJT).

bo l ts and the i r l ocking l oc k ing device s.

and their lock i ng devices Loc king Devices:

device s. (Note 2)

Visua l exa mlnat ton 24 bo lts exa mi ned (VT-3)

See Figure 4-4 of MRP-227-A.

Comments'.

The lovver grid s ho ck pad bo l t s and t hei r l ocki n g dev i ces vvere exam in e d d ur i ng th e Fall 2015 refueling outage du e to the proposed MRP-227 R e v isio n 1. The l owe r Grid S h ock Pad Bo lts are Prim a ry Ite m s

u nd er t he new revisio n. No fin di n gs vve r e repo rt ed.

Lower Grid As semb ly Bolts: Volumetric 100% of accessible N/A N/A Lower thermal s hield (LTS) o x a m i n a ti o n (UT).

b c i ts and their l ocking b O lt S (AN0-1, DB and TMl-1)

Locking Devices:

devices. (Note 2) or studs/nuts (QNS, CR-3)

Visua l ex a min a ti on and their locking devices (VT-3)

See Figure 4-8 of MRP-227-A.

Com m e n ts:

Expansion to this lte m was not req u ired du r l n g Fa 11 2015.

No t es to B&W Expansion Compo n ents T6b le:

1.

Examination acceptance criteria and expansion criteria t'orthe B&W compo nent s are In Tab le 5-1 or MRP-227-A.

2.

A minimum or75% oftho tota l population (oxam1n<.od + unoxam1nod) must bo examined rorlnspCtctlon credit.

Page 90 of 91

TMJ-1, FALL 2015 Expans i on Compo n e n ts R eq u ir i ng E va l uatio n or Rep l ace m ent In L i eu of I nspec t ion lte m Exa mln a tlon Meth o d Di sposi t io n Core Barre l Ass embly No e x a m In a t i o n req uir eme n t s.

N/A Core barrel cy l ind e r (including Ju stify by e v a I u ati on or by rep l acement.

v e rt i ca l and circumferential se am vveld s)

Former p l a t es Co mm e nt s :

E xp ans Io n t o t h is item vva s not r eq uir ed during F a11 2015.

Core Barrc1A s scmbly Interna l b a ffl e -to - b a ff'I e b a l t s :

N/A Baffl e -t o-baffl e bo l t s No e x a m in a ti o n requi r e m e nt s, Core bar r el-to-form e r bolt s Ju stify by e v a I u ati on or by rep l acement.

Externa l b a ffl e -ro-b a ff! e bo lts, co r e barre l -re-N/A former b a lts : No e x a m in a ti o n requirement s.

Ju s tify by e v a I u at.ion or by replacement.

Com m ents:

Expansion to this item vv as not req u i r ed during Fa 11 2015.

Core Barrel A s sembly No ex a min a ti on requirements.

N/A lock i ng devi c es, includ i ng Ju stify by eva l uation or by rep l acement.

lock i n g weld s, for the externa l b a ffle-to-baffle bolts and core barre l-to-form e r bo lt s Co m me n ts'.

Expans i on to t h is itc m vv as not re q uired during Fa11 2015.

Page 91 of 91