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

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I ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program. _ _ _ _ _ _ _ _ _ _ _ _M RP 2016-008 Date: May 18, 2016 To: 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 AnneDemma MRP Chairman MRP Program Manager Exelon Generation Electric Power Research Institute 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 3420 Hillview Avenue, Palo Alto, CA 94304-1338 USA

• 650.855.2000

• Customer Service 800.313.3774

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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. 20 14 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 Core Shroud (Bolted)

Core shroud bolts

.... Volumetric examination (UT) c 100% of accessible bolts (see Note 2). Heads are accessible from the core side. UT N/A See Comments 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. 201 4 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 I

- - ~

- examination (EVT-1) shroud re-entrant comers, at the core mid-plane (+/-three feet in Shroud plates 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

r Palisades, Feb. 2014 Core Shroud Assembly Visual examination Core side surfaces as indicated. 100% Slight gap in shroud plate at (Bolted) (VT-3) the shroud anchor bolt location See Figures 4-25 and 4-26 of for seam 4. All other seams Assembly MRP-227-A. acceptable. See Comments 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 Visual examination If a gap exists, make three to five N/A See Comments (Welded) (VT-1) measurements of gap opening Asaembty 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.

Comments:

Not Applicable to Palisades.

Page 5 of 91

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 we ld 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 ach ieved 86.67% .

The lower girth weld sca n was No indications performed from outs ide the core barrel. Coverage achieved 76.67%.

Comments:

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

In the Wesdyne repo rt these welds are incorrectly named . The report calls t he Middle Girth Weld t he Lower Girth Weld and calls t he 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 time-limited aging defined by evaluation to determine the potential location Lower flange weld 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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' N/A Upper Internals If fatigue life cannot Examination coverage to be 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 Appl icable 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 th e upper guide 87 and G5 have slots in the Instrument guide tubes adjacent to the perimeter of the structure. 8 we lds per guide tubes. Also, at location 87 fuel alignment plate). tube. Coverage achieved there is an extra welded 100% attach ment to the tu be 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 Prim ary Components Table:

1. Examinati on accepta nce crite ria and expa nsion criteri a for the CE compone nts are in Table 5-2 of MRP-227-A.

2. A minimum of 75% of the tota l 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 (exa mined + unexamined), including cove rage consistent with the Expansion criteria in Tab le 5-2 of MRP-227-A, must be examined from either the inner or outer dia meter fo r inspection credit.

4. A minimum of 75% of the total population of core support column we lds.

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

Page 9 of 91

Palisades, Feb. 2014 Existi ng Programs Components Required Coverage Examination Item Examination Method Examination Achieved Findings Coverage Core Shroud Assembly Visua l examination Accessib le 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 instal led . 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 : T urkey Point U nit 3 Utility : NextE ra E nergy/FPL Date of Exams: March-April 2014, PTN3 -27RFO Plant A ge: --"'4=2_ ___,_ (y'--"e=a=-=rs:.)L. -'/----=3'-"0'---= E=F~P~Y Prim ary C omponents 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 20 15 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 du ring NIA T ub e Ass e m b ly examination (EVT-1) CRGT lower flange weld PTN 3-27RFO .

Lower flange welds to determine the surfaces and adjacent base Inspection plann ed for presence of crack-like metal on the individual PTN 3-2 8RFO , 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 Ind ications 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

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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 Indication s Lower core barrel flange examination (EVT-1) accessible surfaces of the weld (Note 5) selected weld and adjacent base metal (Note 4).

Comments:

Pag e 15 of 91

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

Baffle-edge bolts components accessible from Inspection plan ned for core side PTN 3-2 8RFO , 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 PTN 3-27RFO.

Baffle-former bolts from the core side. UT Inspection planned for accessibility may be affected PTN 3-2 8RFO , Fall 2015 by complexity of head and locking device designs.

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

Comments:

Pag e 16 of 91

TurkevPoint Unit 3 SPRING 2014 B err1e -F or m er Visual examination Core side surface as 100% No Recordable Indications Asse mb l y (VT-3) indicated.

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 swellino in former plates)

Comments:

A11gnment. e n d Direct measurement Measurements should be 100% SAT Jn~erf'act n g of spring height taken at several points C o mponer.ts around the circumference of Internals hold down the spring, with a statistically spring adequate number of measurements at each point to minimize uncertainty.

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

Commen t s: Measurements taken at eight circumferential positions. All exceeded the minimum height crite ria for 60 years of operation .

Page 17 of 91

Turkev Point Unit 3 SP RING 2014 f " ~1 i

.. 1 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 tota l 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 cred it.

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

Turkey Point Unit 3 SPRING 2014 Existing P rog r ams Components Req u i r ed C overage Exa m i n ati on Examination lte m E xaminstlon Ac h laved Fi ndings Method 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 Req ulred Coverage Exam i n a tion Ex a mination lt e m Ex a m i n a tion Ac h 1oved Method 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 Ind ications 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 Requ lre d Cov e r a ge Exam i n a t i on Ex a m i na ti on lte m E xa m i n a t i on Ac h la v ed Fi nd i ng s Method Cov era g e B o ttom M o u nt ed Surface Eddy current surface Rep laced seven thimble tubes Seven thimb le 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% Abras ive wear noted on bolts and I nterfacing (VT-3) surfaces at specified lock bars at 270° key and clevis.

Compone n ts frequency. Deg radation 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 th e structural integri ty or fun cti onal ity of the radial support stru cture.

Page 21 of 91

Turkey Point Unit 3 SPRING 201 4 Required Coverage Examination Examination lte m Ex a m i nation Achieved Find i ngs Method Cover a ge A1ign m e n t o n d 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 Prog rams Components Table:

1. XL= "Extra Long" referring to Westinghouse plants with 14-foot co res.

Page 22 of 91

Oconee 3 Spring 2014 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 & One-time phys1cat Determiftetioft of Measurement performed in No relevant Indications were Core S.,,.,. ..c: S,. e,io meeaurement (initial diffeMnttal height of top of 2007 noted .

Assembly Inspection) plenum rib pads to reactor Plenum coverwe1dment rib vessel Hating .urt.ce, pads with plenum in reactor Plenum cover eupport flange vellel.

css top flltnOe Visual (VT-3) for subsequent See Figure 4-1 of MRP-VT-3 100% No relevant Indications were inspections 227-A.

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 retaini ng 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 Ve nt 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 rig ht 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% - 108 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) #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 Berr e 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

Oconee 3 Spring 2014 C ore B *rrel A ssem bly Visual examination 100% of accessible baffle- 100% No relevant Indications were Locking devices, including (VT-3) to-former and internal 864 baffle-to-former and 272 noted .

locking welds, of baffle-to- baffle-to-baffle bolt locking internal baffle-to-baffle bolts.

former bob and internal devices. (Note 3) baffle-to..baft bolts See Figure 4-2 of MRP-227-A.

Com m e n ts:

F1ow D 1str 1but o rAsse m bl y Volumetric 100% of accessible bolts UT --100% UT - 1 flow distributor bolts Flow d'rstributor (FD) bolts examination (UT} of and their locking devices. 96 bolts inspected . (#87) with crack like indications .

and their locking devices the bolts (Note 3)

Visual (VT-3) See Figure 4-8 of MRP- VT-100% VT - No relevant Indications examination of bolt 227-A. 96 bolts and their locking were noted .

locking devices devices inspected .

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

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 Visual examination Accessible surfaces of 100% No relevant Indications.

Alloy X-750 dowel-to-guide (VT-3) 100% of the 24 dowel-to- 24 dowel-to-guide blocks block welds guide block welds. welds.

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

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

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I n c or e Mon ito ri ng Visual examination 100% of top surfaces of 52 100% IMI Guide Tube Spider Casting In str um ent at i on (IMI) (VT-3) spider castings and welds 52 spider casti ngs, each Weld 88-YL had a linear Gu i de 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 Gu ide 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 verifi cati on of the operation of each vent valve shall also be performed through manual actu ation of the valve. Verify that the valves are not stuck in the open position and that no abnormal degradation ha s occurred. Exa mine the va lves for evid ence of scratches , pitting, embedded particles, leakage of the seating surfaces, cracking of lock welds and locking cups, jack screws for proper position, and wea r. The frequency is defined in each unit's technical specifications or in the ir pump and va lve inservice test progra ms (see BAW-2248A, page 4-3 and Ta ble 4-1 , refere nce 18 of MRP-227-A) .

2. Exam ination acceptance criteria and expansion criteria for the B&W components are in Ta ble 5-1 of MRP-227-A.

3. A minimum of 75% of the total population (examined+ unexamined), including coverage consistent with the Expa nsion criteria in Ta ble 5-1, must be examined for inspecti on 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_ __.C....._y_ s)~/__3 ea_r~ ~1"'-_ _ E~F~P~Y Pr imary Components Control Rod Gulde Visual examination 20% examination of the Not inspected during N/A Tube Assembly (VT-3) number of CRGT assemblies, PTN4-28RFO .

Guide plates (can:la) with all guide cards within Inspection planned for each selected CRGT PTN4-29RFO ,Spring2016 assembly examined.

See Figure 4-20 of MRP-227-A Comments:

Page 29 of 91

Turkey Point 4, Sept.2014

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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 fo r 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:

Cor e B arrel 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:

Pag e 30 of 91

Turkey Point 4, Sept.2014 Core B*rret As** mloll!' Enhanced visual 100% of one 'Side of the Upper-100% No Recordable Indications Upper ancil IGwef'CGR examination (EVT-1) accessible surfaces of the barret cylinder girth selected weld and adjacent Lower- 89% No Recordable Indications welds base metal (Note 4).

See Figure 4-22 of MRP-227-A Co mment s:

Core Barre* A ** em i.1:v Enhanced visual 100% of one side of the 85% No Recordable Indications Lower core barrel flange examination (EVT-1) accessible surfaces of the weld (Note 5) &elected weld and adjacent bne metal (Note 4).

Co mment s :

Page 31 of 91

Turkey Point 4, Sept. 2014

~*'.

Bolts and locking devices on Barr1a -F or mer Visual examination 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

Turkey Point 4, Sept.2014 B aN'la -Form aT 100% No Recordable Indications A,..e mbty Assembly (Includes: Baffle plates, See Figures 4-24, 4-25, 4-26 baffle edge bolt& and and 4-27 of MRP-227-A.

indirect effects of void swellin in fonner lates Comments:

A11g nm e nt an d Direct measurement Measurements should be 100% SAT lnter,ecf n g of spring height taken at several points Compone'ftt.* around the circumference of Internals hOld down the spring, wlh 8 statistically spring adequete number of meaaurements at each point to minimize uncertainty.

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

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

Turkey Point 4, Sept.2014 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 tota l 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 Re q uired Coverage E x a m i n ati on Ex a m In a ti o n Item Exam i nati on A ch i eved Findi n gs Meth o d Coverage Core B a rrel Ass e m b l y Visual examination All accessible 100% No Recordable Ind ications 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 Req ul red Cov ere g e Ex a m f n etlon Exe m lnatl on Ite m E >e a m l n a tlon Ac h la ved Fin dings M eth o d Co v erage Lo\Ner I nternals Visua l (VT-3) All accessible 100% No Recordab le Ind ications 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 Indication s 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 Req ulred Coverage Examination Examination lte m E xamination Ac h la v ed Fin d i n gs Meth o d 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: ____ l ___ (years) I 4 .... 34 EFPY Primary Components Not Inspected this outage See Figure 4-20 of MRP-227-A Comments:

Page 39 of 91

Prairie Island 1, Oct. 2014 Control Rod Gulde Enhanced visual 100% of outer (accessible)

Tube Assembly examination (EVT-1) CRGT lower flange weld Not Inspected this outage Lower flange welds 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.

Comm ents:

Core Barrel Assembly Enhanced visual 100% of one side of the Upper core barrel ftange 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 40 of 91

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

Prairie Island 1, Oct. 2014 Baffle-Former Visual examination Bolts and locking devices on Assembly (VT-3) high fluence seams. 100% of 100% No Relevant Indications Baffle-edge bolts components accessible from core side (Note 3).

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

Comments:

Baffle-Former Volumetric 100% of accessible bolts Assembly examination (UT) (Note 3). Heads accessible 728 out of 728 bolts 40 bolts with indications.

Baffle-former bob from the core side. UT 688 bolts had no indications.

accessibility may be affected by complexity of head and No expansion was triggered.

locking device designs.

The extent of the bolt failures was See Figures 4-23 and 4-24 of bounded by minimum pattern analysis MRP-227-A. plus margin term per WCAP-17096 Comments:

(See attached map.)

Page 42 of 91

Prairie Island 1, Oct. 2014 Prairie Island BFB Phased Array UT Indication Map status of 10-23-14 09:38 AM 0 @Ii 90° C§J G GJ ~ 180° G *************

F ** ** ****************** * *********** * *****************

E * * * ********

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° G

F

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

E D

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

c

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

B A

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 0 acquisition ok e without indication not testable (UT) e no acquisition 0 retest e with indication Page 43 of 91

Prairie Island 1, Oct. 2014 Baffle..Former V1&ual examination Core side surface as Assembly (VT-3) indicated. 100% No Relevant Indications 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 Direct measurement of~height Measurements should be taken at several points Not Applicable (403SS) around -the circumference of holddt>wn the spring, with a statistically adequate number of measurement$ at each point to minimize uncertainty.

See Figure 4-28 of MRP-227-A Comments:

Page 44 of 91

Prairie Island 1, Oct. 2014 100% of thermal shield flexures. 100% No Relevant Indications See Figures 28 and '4-38 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 tota l 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 during fall 2014.

Page 45 of 91

Prairie Island 1, Oct. 2014 Existing Programs Components Required Coverage Examination Examination Item Examination Achieved Findings Method 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 Required Coverage Examination Examination Item Examination Achieved Findings Method 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 Required Coverage Examination Examination Item Examination Achieved Findings Method Coveraae Bottom Mounted Surface Eddy current surface Instrumentation examination (ET) examination as 35 out of 36 flu x 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 wa ll 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 Required Coverage Examination Examination Examination Item Achieved Findings Method 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

Intention ally 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 Name: _ __.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..... 1s_____._CU.._2_R3_4_.)..___ _ _ _ Plant Age: _ _4_3_ _ _ _ _ _(years) / _:::::_3......S_ _EFPY b.._er.....,_2_...0__

Primary Components Contr ol R oct GulCI* Visual examination 200.4 examination of the 100% of the CRGT See below Guide.,....

Tut>eA*a*mbly (carda)

(VT-3) number of CRGT assemblies, assemblies with all guide cards within each selected CRGT (COMPLETED DUR ING assembly examined. U2R33 - REPORTED APR IL 2014)

See Figure +.20 of MRP-227-A Co m m en't.s:

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 Enhanced visual 100% of outer (accessible) 100% of outer CRGT No recordable indications Tube A ssembl y examination (EVT-1} CRGT lower flange weld lower flange welds and Lower flange welds 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 DUR ING U2R33 - REPORTED SeeFigure4-21 ofMRP-227- APR IL 2014)

A.

Comments'.

An EVT-1 inspection of the upper and lower GT flange welds was completed on twenty-four (24) guide tubes arou nd th e 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 flang e weld inspection .

Cor e Bar re 1 A ss e m b1y Enhanced visual 100% of one side of the 100% of Weld Length No 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:

Exterior surface Page 52 of 91

Point Beach 2, Oct.2015 Cor

• 8 . ,. , Enhanced Yiewal 100% of Upper Core Upper and tower core examination (EVT-1) Barrel Cylinder Girth barrel cylinder girth Weld Length welds 55.6% of Lower Core See Figure 4-22 of MRP-227- Barrel Cylinder Girth A Weld Length Comments:

Exterio r s u rface 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 limit ed 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 n g t h of the Lovver Care Barre l Cy 11 n 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)

Cor e B a r.rel A aaa m bty Enhanced visual 100% of one side of the 100% of Weld Length No indications Lower CCR~-. emnination (EVT-1) accesai>le surfacesofthe weld (Note 6) selected weld 8l'ld adjacent base metal (Note 4).

Com m e nt s'.

Exterior su r face Page 53 of 91

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%) ori ginal bo lts exhibited A *sem bly examination (UT) (Note 3). Heads accessible repo1ta ble ultrason ic indications.

Baffle..fonner bolts from the core side. UT (COMPLETED DUR ING 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 APR IL 2014) locking device designs. interface reg ion (OHS).

See Figures 4-23 and 4-24 of No reported indications in the MRP-227-A. rep lacement bolts Co mment s :

552 - original bolts. 175 - rep lacement bolts Total of 727 bolts . One bolt location does not co ntai n a bolt Page 54 of 91

Point Beach 2, Oct.201 5 A as em bly 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 sweUi in fonner lates A11 g n m

• nt a n d Direct measurement Measurements should be N/A lnterf'acl .. g of spring height taken at several points

.,,....bald Co.,.,...,,..,.ta spring 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.

Comments :

N/A - Point Beach I nternals hold dovvn spring Is Type 403 SS Page 55 of 91

Point Beach 2, Oct.2015 See Figures 4-28 and 4-36 of MRP-227-A.

Comments:

6Therma1 Sh1e1d F1exures 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 tota l identified sample population must be examined.

3. A minimum of 75% of the total population (exam ined+ unexamined), including coverage cons istent with the Expansion criteria in Table 5-3 of MRP-227-A, must be exam ined 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 Req ulred Cover*ge Examination Examinetlon lt:em Exam i nat: l on Ach ie ved Findings Method 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 LJ 2R33 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 IS i Exam not perfo r med d uring LJ2R33 or LJ2R34 Page 57 of 91

Point Beach 2, Oct.2015 Required C ovarege Exeml n etlo n Exami n ation lum Examination Achieved Ftndlngs Method 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 l y (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 Required Cov e rage Examinat i on Ex a m i neition Item Ex a m i nation Achie v ed Findings Method 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 LJ 2R33 or LJ2 R34 A1i 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 Req u i r ed C overage Exemlnatlon Exam 1 nation Item Exam In atlo n Achie v ed Findings Method 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 Prog rams Components Ta ble :

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 Utility: Florida Power and Light Date of Exams: PTN3-28RFO 10/19/15 to 12/2/15 Plant Age: 43.5 (years) I 31.70 EFPY Primary Components CoM:ro1 t*eam1neoo*n~WCNJ-T..... A*** 111 ~ 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 Gu ide 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 recordab le ind ications.

T ube 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 bl y Enhanced visual 100% of one side of the 100% of weld length. No recordable ind ications 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

Turkey Point 3, Nov.2015 Core Barrel Assembly Enhanced visual 100% of one side of the 100% of Upper Core No recordable indications Upper and lower core examination (EVT-1) accessible surfaces of the Barrel Cylinder Girth barrel cylinder girth selected weld and adjacent Weld Length . (Completed du rin g PTN3-27RFO-welds base metal (Note 4). Reported Spring 2014).

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

Com m en t s:

Core Barr** A .... "' bty Enhanced visual 100% of one side of the 90. 5% of Weld Length . No recordable indications.

Lower core barrel flange examination (EVT-1) accessible surfaces of the weld (Note 5) selected weld and adjacent (C ompleted during PTN3-27RFO-base metal (Note 4). Reported Spring 2014).

Co mm e nt. s:

Page 64 of 91

Turkey Point 3, Nov.2015 Berfla- F or mer Visual examination Bolts and locking devices on 100% of Baffle Edge No recordable indications in 936 Assem b l y (VT-3) high fluence seams. 100% of Bolts. baffle edge bolts.

Baffle-edge bolts components accessible from core side (Note 3).

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

Co mment s.

No recordable indications in 936 examined edge bolts.

Baffle-Form er Volumetric 100% of acceuibJe bolts Only 305 of 1088 baffle No recordable indications in 305 Assemb l y examination (UT) (Note 3). Heads accessible former bolts were baffle former bolts.

Baffle-fonner 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.

Commen t s:

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

Page 65 of 91

Turkey Point 3, Nov.2015 Berrte*F or mer Visual examination Core side surface as 100% No recordable indications Assembly (VT-3) indicated.

Assembly (Completed during PTN3-27RFO-(Includes: Baffle plates, See Figures 4-24, 4-25, 4-26 Reported Spring 2014).

baffle edge bolts and and 4-27 of MRP-227-A.

indirect effects of void swellin in former Comment s:

A1 gn men~ and Direct measurement Measurements should be 100% SAT lnce~f'eclng of spring height taken at several points Coni.fl>Ol'lenta around the circumference of (Completed during PTN3-27RFO-lntemata hold down the spring, with a statisticaUy Reported Spring 2014).

spring adequate number of measurements at each point to minimize uncertainty.

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

C o mment: s:

Page 66 of 91

Turkey Point 3, Nov.2015 (Completed during PTN3-27RFO-See Figures 4-29 and 4-36 of Reported Spring 2014).

URP-227-A.

Co mm e nt s:

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 cred it.

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 co re 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 Req ui red Coverage Exam i n a tion Exam i nation lte m Exam i nation Ach ieved Method Find i ng s Coverage Co r e Ba r re t A sse mb l y Visual examination All accessible 100% A sig nificant 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.

(C ompleted 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 funct ionality and bearing area of these surfaces.

U ppe r In t e rn a l s Visual examination All accessible 100% No recordab le 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 RequJred Coverage Exe m inatlon Ex a m In att o n Item Examinat i o n Achieved Fi nd i n g s Method Coverage L owe r I nterna l s V isual (VT-3) All accessible 100% No reco rdable indications Assemb l y examination of the surfaces at specifi ed Lower core plate lower core plates to freq uency. (Completed during PTN 3-27RFO-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 Repo rted Spring 2014).

(Note 1)

Com men-rs'.

Page 69 of 91

Turkey Point 3, Nov.2015 Requi r e d Co v erage Examination Exam i nation lte m Examinatio n Ac hle v e d Method Find i ngs Coverage Bottom Mou nLe d Surface Eddy current surface Replaced seven thimb le tubes Seven th imble 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. Deg radation attributed to foreign Clevis insert bolts materia l, possibly an RCP diffuser adapter cap screw, retrieved during previous RFO .

(Completed during PTN 3-27RFO-Reported Spring 2014).

Co mm e nt s:

Page 70 of 91

Turkey Point 3, Nov.201 5 R e q uire d C o v era ge Exam l n e tlon E xa m l n at.l on I te m M et hod Exa m l n a tlon A c hi e ved Find i ng s Cov er age 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 Existi ng Programs Components Table:

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

Page 71 of 91

I nt e nti onally Blank Page 72 of 91

Prairie Island 2, Nov. 2015 T a b l es F or 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* Visual examination Examination per \'VCAP* Maximum% volume vvear:

Tub* A........ ,>' (VT-3) 17451-Pof CRGT Not Inspected this outage Five (5) vvorsr case CRGTs:

Guide plates {cards) 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 wear measurements to wear volume.

See MRP-2014-006 and Also specify high or low flow WCAP-17451-P operation as defined in Tbl 4-2 of the WCAP Com ments '.

Page 73 of 91

Prairie Island 2, Nov. 201 5

fl

100% of outer (accessible)

Concr o l Roo Gulde Enhanced visual Tube Assembly examination (EVT-1) CRGT lower flange weld 100% of perip heral 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 we ld 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

Prairie Island 2, Nov. 201 5 C ore Barr el A ssembl y Enhanced visual 100% of one side of the Upper and lower core examination (EVT-1) accessible surfaces of the barrel cylinder girth selected weld and adjacent 100% of Upper Girth No relevant indications welds base metal (Note 4). Weld See Figure 4-22 of MRP-227- 76.5% of Lower Girth A Weld Comme n r.s:

'*'81...

Core Barre

• As.* m .. ,Y Lower core weld .(Nole I)

Enhanced visual examin8ltion (EVT-1) 100% of one side of the accessible surfaces of the aelected weld and adjacent 100% No relevant indications base metal (Note 4).

Comments:

Page 75 of 91

Prairie Island 2, Nov. 2015 Visual examination Bolts and locking devices on Assem b ly (VT-3) high fluence seams. 100% of 100% No relevant indications Baffle..edge bolts components accessible from core side (Note 3).

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

Co mm e nt s:

B affl e - F orm e r Volumetric 100% of accessible bolts A ssembly examination (UT) (Note 3). Heads accessible Not examined this Baffle-former bolts 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.

Comments:

Page 76 of 91

Prairie Island 2, Nov. 2015 B erfl a -For ma r Visual examination Core side surface aa A sse mb l y (VT-3) indicated. 100% No relevant indications 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 swellin in fonner lates Commen ts :

A1 gn ment. end Direct measurement Measurements should be lno:erf'ectng of spring height taken at several points Not Required for springs ComponenC* around the circumference of of type-403 material.

tntelMll hoJd the spring, wlh a statisticaly adequate number of measurements at each point to minimize uncertainty.

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

Commen t s:

Page 77 of 91

Prairie Island 2, Nov. 2015 A ase mb l y 100% No relevant indications Thermal shield ttexurea See Figures 29 and 4-36 of MRP-227-A.

Co mment s:

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 tota l 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 cons istent with the Expa nsion 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 Required Coverage Examination Examtnatlon lte m Exam i nation Ach ie ved Findings Method 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 freq uency.

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 indication s Upper support ring or frequency.

skirt Comments'.

Page 79 of 91

Prairie Island 2, Nov. 2015 Req ulred Coverege Ex a m in e ti on Exami n ation Item Examinati on Ac hleved Findings Method 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 Required Coverage Examinet.t o n Exe m !nation Ite m Examination Comments:

M ethod Coverage Ac h Ie ve d Fin d i n gs

• • 'REPORT UPON THESE INSPECTIONS ONLY WHEN DONE IN CONJUNCTION WITH MRP-227-A RELATED EXAMS.

Alignment. and Visual examination All accessible Int erfac 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 Is land Nuclear Station Unit 1 Utility: Exelon Generation Date of Exams: 10/28/2015 to 11/23/2015 Plant Age: _4_1_ _ _ _ _ _ _ _ _ (years) .4_ _ _EFPY

/ ----'3~0_

Primary Components Pte,.um Cow*rA s *emlUy & One~l m e physica l 100% or t h e \Ne l dmentrlb No fi n d i n g s ,

Core S u pport Sl\Jeld measurement (1nttl*l dlffaranti*t height or top of pads, p 1e n um s upport fl a n ge, Ass em 1o1y Inspection) p l enum rib pads to reactor and CSS top r l ange.

P1enum cover watdment rib vessel ***ting surface, pads Visua l (VT-3) for wtth plenum tn reactor vesse l.

P1enum cover support na n ge s u bse qu ent CSS t o p fl ange I n spec tion s S ee F 1g&.1re 4-1 o rMRP-227-A.

Com m e nt s:

No fi n di n g s we re re p o r te d .

Co n tr ol Rod G ulde Tube V is u a l (VT-3} Ac cess i b l e su rfaces at N/A N/A Assemb ly each of the 4 screvv CRGT spacer c a stings focetlons (*t e v ery 90°) of 100% of the CRGT spacer ce s t ings

(.um it e-* 100%

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

One indeterminate volu m etrlc exam of bo l t 24 . Assumed Upp- <:ore l>al' *t (UCB} the boka (Note 3) fai l e d .

boft:a and tftalr l-ocilt,,o 120 bo l ts e x ami n ed .

ld*vtces V1auat (VT-3} See Ftgure 4-7 of MRP-ex* mlnatton of bolt 227-A.

locking devices Comments:

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

TMl-1, FALL 2015 Core Barrel Assembly Volumetric 100% or accessible bolts 100% of a ll bo l ts and t.heir No finding s.

Lower core barrel (LCB) examination (UT) of and their tocking devlces l ocking devices.

bolts and their locking the bolts (Note 3) devices 108 bo l ts examined .

Visual (VT-3) s** F111ur* 4-8 of' MRP-axe mlnetlon of bolt 227-A.

locking devices Comme n ts'.

No fi n dings.

Core Barrel Assembly V01u m etrlc 100% of eccesstbta bolts. N/A N/A Baff'te"'to""torm er boks examination (UT) (Note 3)

See F111ure 4-2 of MRP-227-A.

Comme nt s'.

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

Core Barrel Assembly Vtsual examination 100% of the accessible N/A N/A Bame plates (VT-3) surface within 1 inch around each now end bolt hole.

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

Commen t s:

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 Core Berrel Assembly Visual examination 100% or accessible bame- N/A N/A Locking devices, includlng (VT-3) 'to-former end Internet l ocking welds, or beme~o baffle-to-baffle bolt locking form er bo l ts and tnt.ernal de v ices. (Note 3) b arr1e - to - b effle bolts See Figure 4-2 or MRP-227-A.

Comments:

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

F1ow D1urllH*t* Aa ** m lltty V 01u m atrtc 100% or" cc esslble bolts 100% o f a ll bo l ts a nd th e i r One volumetric i ndica tion on Frow dlsulb"Utor ( 0) bok*

• xem1nat1on (UT) or and thel-r tocking devices. l oc kin g dev ices. bo l t44.

e ntl the r rocking tl*v cee the bolts (Not* 3)

See F gure 4-8 or MRP- 108 bo lt s examrned Visual (VT-3) 227-A.

ex* m1natlon of bolt tocking devices Comments :

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 th reads approximately 4.40" from the top of the bolt head . Ex pa n sion criteria vvere not triggered.

Lower Grid Assemb l y V isua l examination A ccessible surfaces ot 100% of dovv e l -to-gulde No r e l eva nt Indica tion s n oted.

Anoy X-750 dowel-to-guide (VT-3) 100% orthe 24 dowel-to- b l ock vve l ds.

block wetels guide block welda.

See figure 4-4 or MRP- 12 guide b l ock pair s 227-A. e xamin ed.

Com m ents'.

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

TMl-1 , FALL2015 Inca-re Mol'ltt°'rlnfJ Vtsuat examination 100% ort:op aurfacas or 52 N/A N/A lnso;rument*tiol'I (1Mt) (VT-3) sptder c=astlngs *ncf welds G..... Tub* A........ ij,' to the a<ljacant lowar grid IMt guide tub* ap.tden rtb s ectJon.

IMJ 9"1d* tu** *l"k:l ..."'t.0- See Fie .... ** 4-3 and 4-6 or tower grid rib section welds MRP-227-A.

Comme nt s:

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 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 ns oc In Ch" pump

• nd valvo In. ocvlc 0 '""

pcogca ms (soe BAW-2248A, pogo 4-3 and Tab le 4-1 , coroc cncc 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 Required Coverage Examination Examination lte m Examinat i on Achieved Findings (Note 1)

Method 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-t o-upper (VT-3) 100% or the dowe l l ocking vve l ds .

grid fu e I a s s e m b I y s upport 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 100% of a cc e s s 'b I e N/A N/A (LJT). bo lt s or studs/nuts and Upper therm a1 shield (UTS) e xamination their locking devices bo l ts and their l ocking devices Lock in g Devices:

Vis u a l examination (Not e 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 Requir e d Cov e r age E xa m i n ation E x a m In a t io n lte m Exa m i n a t io n A c hi e ved Find ings (Note 1)

Meth o d C o ver age Core B a rr e l Ass e mbly Bo lt or St ud/ 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 (SS HT) stud s / n uts (CR- exam i nation (LJ T). their t ock 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 l y 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 id fu e l a ss c m b ly (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 fuel assemb l y support their l ocking w e l d s pads .

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

Comments :

Expans i on to t h is item vva s not req ui red 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 Required Coverage Examination Examination lte m Examination Achieved Finding s (Note 1)

Method 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 gr id shock pad bo l ts exa m inat i 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 t on 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 a nd 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 MR P- 227 R e v isio n 1 . T he l owe r Grid S h ock P a d 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 s emb ly Bolts: Volumetric 100% of accessible N/A N/A Lower thermal s hield (LTS) o xa m in 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 l e:

1. Examination acceptance criteria and expansion criteria t'orthe B&W compo nent s are In Tab l e 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 lt e m Exa mln a tlon Meth o d Di sposi t io n Core Barre l A ss 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 to t h is i tem vva s not r eq uir ed during F a11 2015.

Core Barrc1A s scmbly Interna l b a ff l e -to - b a ff'I e b a lt 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 by e v a I u at i on or by Ju stify rep l acement.

Externa l b a ff l e -ro-b a ff! e bo l ts , co r e barre l -re- N/A former b a l ts : 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 l t s Co m me n ts'.

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

Page 91 of 91

-=~121

~*-

I ELECTRIC POWER RESEARCH INSTITUTE MRP Materials Reliability Program. _ _ _ _ _ _ _ _ _ _ _ _M RP 2016-008 Date: May 18, 2016 To: 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 AnneDemma MRP Chairman MRP Program Manager Exelon Generation Electric Power Research Institute 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 3420 Hillview Avenue, Palo Alto, CA 94304-1338 USA

• 650.855.2000

• Customer Service 800.313.3774

• 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. 20 14 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 Core Shroud (Bolted)

Core shroud bolts

.... Volumetric examination (UT) c 100% of accessible bolts (see Note 2). Heads are accessible from the core side. UT N/A See Comments 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. 201 4 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 I

- - ~

- examination (EVT-1) shroud re-entrant comers, at the core mid-plane (+/-three feet in Shroud plates 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

r Palisades, Feb. 2014 Core Shroud Assembly Visual examination Core side surfaces as indicated. 100% Slight gap in shroud plate at (Bolted) (VT-3) the shroud anchor bolt location See Figures 4-25 and 4-26 of for seam 4. All other seams Assembly MRP-227-A. acceptable. See Comments 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 Visual examination If a gap exists, make three to five N/A See Comments (Welded) (VT-1) measurements of gap opening Asaembty 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.

Comments:

Not Applicable to Palisades.

Page 5 of 91

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 we ld 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 ach ieved 86.67% .

The lower girth weld sca n was No indications performed from outs ide the core barrel. Coverage achieved 76.67%.

Comments:

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

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

Page 6 of 91

Palisades, Feb. 2014

-~

-* 1-; ~

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 time-limited aging defined by evaluation to determine the potential location Lower flange weld 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

~

' N/A Upper Internals If fatigue life cannot Examination coverage to be 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 Appl icable 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 th e upper guide 87 and G5 have slots in the Instrument guide tubes adjacent to the perimeter of the structure. 8 we lds per guide tubes. Also, at location 87 fuel alignment plate). tube. Coverage achieved there is an extra welded 100% attach ment to the tu be 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 Prim ary Components Table:

1. Examinati on accepta nce crite ria and expa nsion criteri a for the CE compone nts are in Table 5-2 of MRP-227-A.

2. A minimum of 75% of the tota l 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 (exa mined + unexamined), including cove rage consistent with the Expansion criteria in Tab le 5-2 of MRP-227-A, must be examined from either the inner or outer dia meter fo r inspection credit.

4. A minimum of 75% of the total population of core support column we lds.

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

Page 9 of 91

Palisades, Feb. 2014 Existi ng Programs Components Required Coverage Examination Item Examination Method Examination Achieved Findings Coverage Core Shroud Assembly Visua l examination Accessib le 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 instal led . 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 : T urkey Point U nit 3 Utility : NextE ra E nergy/FPL Date of Exams: March-April 2014, PTN3 -27RFO Plant A ge: --"'4=2_ ___,_ (y'--"e=a=-=rs:.)L. -'/----=3'-"0'---= E=F~P~Y Prim ary C omponents 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 20 15 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 du ring NIA T ub e Ass e m b ly examination (EVT-1) CRGT lower flange weld PTN 3-27RFO .

Lower flange welds to determine the surfaces and adjacent base Inspection plann ed for presence of crack-like metal on the individual PTN 3-2 8RFO , 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 Ind ications 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 Indication s Lower core barrel flange examination (EVT-1) accessible surfaces of the weld (Note 5) selected weld and adjacent base metal (Note 4).

Comments:

Pag e 15 of 91

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

Baffle-edge bolts components accessible from Inspection plan ned for core side PTN 3-2 8RFO , 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 PTN 3-27RFO.

Baffle-former bolts from the core side. UT Inspection planned for accessibility may be affected PTN 3-2 8RFO , Fall 2015 by complexity of head and locking device designs.

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

Comments:

Pag e 16 of 91

TurkevPoint Unit 3 SPRING 2014 B err1e -F or m er Visual examination Core side surface as 100% No Recordable Indications Asse mb l y (VT-3) indicated.

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 swellino in former plates)

Comments:

A11gnment. e n d Direct measurement Measurements should be 100% SAT Jn~erf'act n g of spring height taken at several points C o mponer.ts around the circumference of Internals hold down the spring, with a statistically spring adequate number of measurements at each point to minimize uncertainty.

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

Commen t s: Measurements taken at eight circumferential positions. All exceeded the minimum height crite ria for 60 years of operation .

Page 17 of 91

Turkev Point Unit 3 SP RING 2014 f " ~1 i

.. 1 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 tota l 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 cred it.

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

Turkey Point Unit 3 SPRING 2014 Existing P rog r ams Components Req u i r ed C overage Exa m i n ati on Examination lte m E xaminstlon Ac h laved Fi ndings Method 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 Req ulred Coverage Exam i n a tion Ex a mination lt e m Ex a m i n a tion Ac h 1oved Method 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 Ind ications 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 Requ lre d Cov e r a ge Exam i n a t i on Ex a m i na ti on lte m E xa m i n a t i on Ac h la v ed Fi nd i ng s Method Cov era g e B o ttom M o u nt ed Surface Eddy current surface Rep laced seven thimble tubes Seven thimb le 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% Abras ive wear noted on bolts and I nterfacing (VT-3) surfaces at specified lock bars at 270° key and clevis.

Compone n ts frequency. Deg radation 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 th e structural integri ty or fun cti onal ity of the radial support stru cture.

Page 21 of 91

Turkey Point Unit 3 SPRING 201 4 Required Coverage Examination Examination lte m Ex a m i nation Achieved Find i ngs Method Cover a ge A1ign m e n t o n d 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 Prog rams Components Table:

1. XL= "Extra Long" referring to Westinghouse plants with 14-foot co res.

Page 22 of 91

Oconee 3 Spring 2014 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 & One-time phys1cat Determiftetioft of Measurement performed in No relevant Indications were Core S.,,.,. ..c: S,. e,io meeaurement (initial diffeMnttal height of top of 2007 noted .

Assembly Inspection) plenum rib pads to reactor Plenum coverwe1dment rib vessel Hating .urt.ce, pads with plenum in reactor Plenum cover eupport flange vellel.

css top flltnOe Visual (VT-3) for subsequent See Figure 4-1 of MRP-VT-3 100% No relevant Indications were inspections 227-A.

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 retaini ng 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 Ve nt 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 rig ht jacking screws were not shown as engaged.

Page 24 of 91

Oconee 3 Spring 2014

-~

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% - 108 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) #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

• ~

t

~

Core Berr e 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

Oconee 3 Spring 2014 C ore B *rrel A ssem bly Visual examination 100% of accessible baffle- 100% No relevant Indications were Locking devices, including (VT-3) to-former and internal 864 baffle-to-former and 272 noted .

locking welds, of baffle-to- baffle-to-baffle bolt locking internal baffle-to-baffle bolts.

former bob and internal devices. (Note 3) baffle-to..baft bolts See Figure 4-2 of MRP-227-A.

Com m e n ts:

F1ow D 1str 1but o rAsse m bl y Volumetric 100% of accessible bolts UT --100% UT - 1 flow distributor bolts Flow d'rstributor (FD) bolts examination (UT} of and their locking devices. 96 bolts inspected . (#87) with crack like indications .

and their locking devices the bolts (Note 3)

Visual (VT-3) See Figure 4-8 of MRP- VT-100% VT - No relevant Indications examination of bolt 227-A. 96 bolts and their locking were noted .

locking devices devices inspected .

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

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 Visual examination Accessible surfaces of 100% No relevant Indications.

Alloy X-750 dowel-to-guide (VT-3) 100% of the 24 dowel-to- 24 dowel-to-guide blocks block welds guide block welds. welds.

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

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 str um ent at i on (IMI) (VT-3) spider castings and welds 52 spider casti ngs, each Weld 88-YL had a linear Gu i de 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 Gu ide 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 verifi cati on of the operation of each vent valve shall also be performed through manual actu ation of the valve. Verify that the valves are not stuck in the open position and that no abnormal degradation ha s occurred. Exa mine the va lves for evid ence of scratches , pitting, embedded particles, leakage of the seating surfaces, cracking of lock welds and locking cups, jack screws for proper position, and wea r. The frequency is defined in each unit's technical specifications or in the ir pump and va lve inservice test progra ms (see BAW-2248A, page 4-3 and Ta ble 4-1 , refere nce 18 of MRP-227-A) .

2. Exam ination acceptance criteria and expansion criteria for the B&W components are in Ta ble 5-1 of MRP-227-A.

3. A minimum of 75% of the total population (examined+ unexamined), including coverage consistent with the Expa nsion criteria in Ta ble 5-1, must be examined for inspecti on 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_ __.C....._y_ s)~/__3 ea_r~ ~1"'-_ _ E~F~P~Y Pr imary Components Control Rod Gulde Visual examination 20% examination of the Not inspected during N/A Tube Assembly (VT-3) number of CRGT assemblies, PTN4-28RFO .

Guide plates (can:la) with all guide cards within Inspection planned for each selected CRGT PTN4-29RFO ,Spring2016 assembly examined.

See Figure 4-20 of MRP-227-A Comments:

Page 29 of 91

Turkey Point 4, Sept.2014

"-e[

• . 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 fo r 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:

Cor e B arrel 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:

Pag e 30 of 91

Turkey Point 4, Sept.2014 Core B*rret As** mloll!' Enhanced visual 100% of one 'Side of the Upper-100% No Recordable Indications Upper ancil IGwef'CGR examination (EVT-1) accessible surfaces of the barret cylinder girth selected weld and adjacent Lower- 89% No Recordable Indications welds base metal (Note 4).

See Figure 4-22 of MRP-227-A Co mment s:

Core Barre* A ** em i.1:v Enhanced visual 100% of one side of the 85% No Recordable Indications Lower core barrel flange examination (EVT-1) accessible surfaces of the weld (Note 5) &elected weld and adjacent bne metal (Note 4).

Co mment s :

Page 31 of 91

Turkey Point 4, Sept. 2014

~*'.

Bolts and locking devices on Barr1a -F or mer Visual examination 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

Turkey Point 4, Sept.2014 B aN'la -Form aT 100% No Recordable Indications A,..e mbty Assembly (Includes: Baffle plates, See Figures 4-24, 4-25, 4-26 baffle edge bolt& and and 4-27 of MRP-227-A.

indirect effects of void swellin in fonner lates Comments:

A11g nm e nt an d Direct measurement Measurements should be 100% SAT lnter,ecf n g of spring height taken at several points Compone'ftt.* around the circumference of Internals hOld down the spring, wlh 8 statistically spring adequete number of meaaurements at each point to minimize uncertainty.

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

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

Turkey Point 4, Sept.2014 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 tota l 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 Re q uired Coverage E x a m i n ati on Ex a m In a ti o n Item Exam i nati on A ch i eved Findi n gs Meth o d Coverage Core B a rrel Ass e m b l y Visual examination All accessible 100% No Recordable Ind ications 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 Req ul red Cov ere g e Ex a m f n etlon Exe m lnatl on Ite m E >e a m l n a tlon Ac h la ved Fin dings M eth o d Co v erage Lo\Ner I nternals Visua l (VT-3) All accessible 100% No Recordab le Ind ications 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 Indication s 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 Req ulred Coverage Examination Examination lte m E xamination Ac h la v ed Fin d i n gs Meth o d 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: ____ l ___ (years) I 4 .... 34 EFPY Primary Components Not Inspected this outage See Figure 4-20 of MRP-227-A Comments:

Page 39 of 91

Prairie Island 1, Oct. 2014 Control Rod Gulde Enhanced visual 100% of outer (accessible)

Tube Assembly examination (EVT-1) CRGT lower flange weld Not Inspected this outage Lower flange welds 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.

Comm ents:

Core Barrel Assembly Enhanced visual 100% of one side of the Upper core barrel ftange 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 40 of 91

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

Prairie Island 1, Oct. 2014 Baffle-Former Visual examination Bolts and locking devices on Assembly (VT-3) high fluence seams. 100% of 100% No Relevant Indications Baffle-edge bolts components accessible from core side (Note 3).

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

Comments:

Baffle-Former Volumetric 100% of accessible bolts Assembly examination (UT) (Note 3). Heads accessible 728 out of 728 bolts 40 bolts with indications.

Baffle-former bob from the core side. UT 688 bolts had no indications.

accessibility may be affected by complexity of head and No expansion was triggered.

locking device designs.

The extent of the bolt failures was See Figures 4-23 and 4-24 of bounded by minimum pattern analysis MRP-227-A. plus margin term per WCAP-17096 Comments:

(See attached map.)

Page 42 of 91

Prairie Island 1, Oct. 2014 Prairie Island BFB Phased Array UT Indication Map status of 10-23-14 09:38 AM 0 @Ii 90° C§J G GJ ~ 180° G *************

F ** ** ****************** * *********** * *****************

E * * * ********

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° G

F

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

E D

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

c

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

B A

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 0 acquisition ok e without indication not testable (UT) e no acquisition 0 retest e with indication Page 43 of 91

Prairie Island 1, Oct. 2014 Baffle..Former V1&ual examination Core side surface as Assembly (VT-3) indicated. 100% No Relevant Indications 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 Direct measurement of~height Measurements should be taken at several points Not Applicable (403SS) around -the circumference of holddt>wn the spring, with a statistically adequate number of measurement$ at each point to minimize uncertainty.

See Figure 4-28 of MRP-227-A Comments:

Page 44 of 91

Prairie Island 1, Oct. 2014 100% of thermal shield flexures. 100% No Relevant Indications See Figures 28 and '4-38 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 tota l 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 during fall 2014.

Page 45 of 91

Prairie Island 1, Oct. 2014 Existing Programs Components Required Coverage Examination Examination Item Examination Achieved Findings Method 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 Required Coverage Examination Examination Item Examination Achieved Findings Method 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 Required Coverage Examination Examination Item Examination Achieved Findings Method Coveraae Bottom Mounted Surface Eddy current surface Instrumentation examination (ET) examination as 35 out of 36 flu x 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 wa ll 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 Required Coverage Examination Examination Examination Item Achieved Findings Method 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

Intention ally 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 Name: _ __.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..... 1s_____._CU.._2_R3_4_.)..___ _ _ _ Plant Age: _ _4_3_ _ _ _ _ _(years) / _:::::_3......S_ _EFPY b.._er.....,_2_...0__

Primary Components Contr ol R oct GulCI* Visual examination 200.4 examination of the 100% of the CRGT See below Guide.,....

Tut>eA*a*mbly (carda)

(VT-3) number of CRGT assemblies, assemblies with all guide cards within each selected CRGT (COMPLETED DUR ING assembly examined. U2R33 - REPORTED APR IL 2014)

See Figure +.20 of MRP-227-A Co m m en't.s:

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 Enhanced visual 100% of outer (accessible) 100% of outer CRGT No recordable indications Tube A ssembl y examination (EVT-1} CRGT lower flange weld lower flange welds and Lower flange welds 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 DUR ING U2R33 - REPORTED SeeFigure4-21 ofMRP-227- APR IL 2014)

A.

Comments'.

An EVT-1 inspection of the upper and lower GT flange welds was completed on twenty-four (24) guide tubes arou nd th e 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 flang e weld inspection .

Cor e Bar re 1 A ss e m b1y Enhanced visual 100% of one side of the 100% of Weld Length No 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:

Exterior surface Page 52 of 91

Point Beach 2, Oct.2015 Cor

• 8 . ,. , Enhanced Yiewal 100% of Upper Core Upper and tower core examination (EVT-1) Barrel Cylinder Girth barrel cylinder girth Weld Length welds 55.6% of Lower Core See Figure 4-22 of MRP-227- Barrel Cylinder Girth A Weld Length Comments:

Exterio r s u rface 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 limit ed 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 n g t h of the Lovver Care Barre l Cy 11 n 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)

Cor e B a r.rel A aaa m bty Enhanced visual 100% of one side of the 100% of Weld Length No indications Lower CCR~-. emnination (EVT-1) accesai>le surfacesofthe weld (Note 6) selected weld 8l'ld adjacent base metal (Note 4).

Com m e nt s'.

Exterior su r face Page 53 of 91

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%) ori ginal bo lts exhibited A *sem bly examination (UT) (Note 3). Heads accessible repo1ta ble ultrason ic indications.

Baffle..fonner bolts from the core side. UT (COMPLETED DUR ING 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 APR IL 2014) locking device designs. interface reg ion (OHS).

See Figures 4-23 and 4-24 of No reported indications in the MRP-227-A. rep lacement bolts Co mment s :

552 - original bolts. 175 - rep lacement bolts Total of 727 bolts . One bolt location does not co ntai n a bolt Page 54 of 91

Point Beach 2, Oct.201 5 A as em bly 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 sweUi in fonner lates A11 g n m

• nt a n d Direct measurement Measurements should be N/A lnterf'acl .. g of spring height taken at several points

.,,....bald Co.,.,...,,..,.ta spring 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.

Comments :

N/A - Point Beach I nternals hold dovvn spring Is Type 403 SS Page 55 of 91

Point Beach 2, Oct.2015 See Figures 4-28 and 4-36 of MRP-227-A.

Comments:

6Therma1 Sh1e1d F1exures 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 tota l identified sample population must be examined.

3. A minimum of 75% of the total population (exam ined+ unexamined), including coverage cons istent with the Expansion criteria in Table 5-3 of MRP-227-A, must be exam ined 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 Req ulred Cover*ge Examination Examinetlon lt:em Exam i nat: l on Ach ie ved Findings Method 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 LJ 2R33 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 IS i Exam not perfo r med d uring LJ2R33 or LJ2R34 Page 57 of 91

Point Beach 2, Oct.2015 Required C ovarege Exeml n etlo n Exami n ation lum Examination Achieved Ftndlngs Method 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 l y (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 Required Cov e rage Examinat i on Ex a m i neition Item Ex a m i nation Achie v ed Findings Method 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 LJ 2R33 or LJ2 R34 A1i 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 Req u i r ed C overage Exemlnatlon Exam 1 nation Item Exam In atlo n Achie v ed Findings Method 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 Prog rams Components Ta ble :

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 Utility: Florida Power and Light Date of Exams: PTN3-28RFO 10/19/15 to 12/2/15 Plant Age: 43.5 (years) I 31.70 EFPY Primary Components CoM:ro1 t*eam1neoo*n~WCNJ-T..... A*** 111 ~ 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 Gu ide 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 recordab le ind ications.

T ube 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 bl y Enhanced visual 100% of one side of the 100% of weld length. No recordable ind ications 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

Turkey Point 3, Nov.2015 Core Barrel Assembly Enhanced visual 100% of one side of the 100% of Upper Core No recordable indications Upper and lower core examination (EVT-1) accessible surfaces of the Barrel Cylinder Girth barrel cylinder girth selected weld and adjacent Weld Length . (Completed du rin g PTN3-27RFO-welds base metal (Note 4). Reported Spring 2014).

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

Com m en t s:

Core Barr** A .... "' bty Enhanced visual 100% of one side of the 90. 5% of Weld Length . No recordable indications.

Lower core barrel flange examination (EVT-1) accessible surfaces of the weld (Note 5) selected weld and adjacent (C ompleted during PTN3-27RFO-base metal (Note 4). Reported Spring 2014).

Co mm e nt. s:

Page 64 of 91

Turkey Point 3, Nov.2015 Berfla- F or mer Visual examination Bolts and locking devices on 100% of Baffle Edge No recordable indications in 936 Assem b l y (VT-3) high fluence seams. 100% of Bolts. baffle edge bolts.

Baffle-edge bolts components accessible from core side (Note 3).

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

Co mment s.

No recordable indications in 936 examined edge bolts.

Baffle-Form er Volumetric 100% of acceuibJe bolts Only 305 of 1088 baffle No recordable indications in 305 Assemb l y examination (UT) (Note 3). Heads accessible former bolts were baffle former bolts.

Baffle-fonner 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.

Commen t s:

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

Page 65 of 91

Turkey Point 3, Nov.2015 Berrte*F or mer Visual examination Core side surface as 100% No recordable indications Assembly (VT-3) indicated.

Assembly (Completed during PTN3-27RFO-(Includes: Baffle plates, See Figures 4-24, 4-25, 4-26 Reported Spring 2014).

baffle edge bolts and and 4-27 of MRP-227-A.

indirect effects of void swellin in former Comment s:

A1 gn men~ and Direct measurement Measurements should be 100% SAT lnce~f'eclng of spring height taken at several points Coni.fl>Ol'lenta around the circumference of (Completed during PTN3-27RFO-lntemata hold down the spring, with a statisticaUy Reported Spring 2014).

spring adequate number of measurements at each point to minimize uncertainty.

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

C o mment: s:

Page 66 of 91

Turkey Point 3, Nov.2015 (Completed during PTN3-27RFO-See Figures 4-29 and 4-36 of Reported Spring 2014).

URP-227-A.

Co mm e nt s:

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 cred it.

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 co re 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 Req ui red Coverage Exam i n a tion Exam i nation lte m Exam i nation Ach ieved Method Find i ng s Coverage Co r e Ba r re t A sse mb l y Visual examination All accessible 100% A sig nificant 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.

(C ompleted 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 funct ionality and bearing area of these surfaces.

U ppe r In t e rn a l s Visual examination All accessible 100% No recordab le 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 RequJred Coverage Exe m inatlon Ex a m In att o n Item Examinat i o n Achieved Fi nd i n g s Method Coverage L owe r I nterna l s V isual (VT-3) All accessible 100% No reco rdable indications Assemb l y examination of the surfaces at specifi ed Lower core plate lower core plates to freq uency. (Completed during PTN 3-27RFO-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 Repo rted Spring 2014).

(Note 1)

Com men-rs'.

Page 69 of 91

Turkey Point 3, Nov.2015 Requi r e d Co v erage Examination Exam i nation lte m Examinatio n Ac hle v e d Method Find i ngs Coverage Bottom Mou nLe d Surface Eddy current surface Replaced seven thimb le tubes Seven th imble 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. Deg radation attributed to foreign Clevis insert bolts materia l, possibly an RCP diffuser adapter cap screw, retrieved during previous RFO .

(Completed during PTN 3-27RFO-Reported Spring 2014).

Co mm e nt s:

Page 70 of 91

Turkey Point 3, Nov.201 5 R e q uire d C o v era ge Exam l n e tlon E xa m l n at.l on I te m M et hod Exa m l n a tlon A c hi e ved Find i ng s Cov er age 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 Existi ng Programs Components Table:

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

Page 71 of 91

I nt e nti onally Blank Page 72 of 91

Prairie Island 2, Nov. 2015 T a b l es F or 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* Visual examination Examination per \'VCAP* Maximum% volume vvear:

Tub* A........ ,>' (VT-3) 17451-Pof CRGT Not Inspected this outage Five (5) vvorsr case CRGTs:

Guide plates {cards) 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 wear measurements to wear volume.

See MRP-2014-006 and Also specify high or low flow WCAP-17451-P operation as defined in Tbl 4-2 of the WCAP Com ments '.

Page 73 of 91

Prairie Island 2, Nov. 201 5

fl

100% of outer (accessible)

Concr o l Roo Gulde Enhanced visual Tube Assembly examination (EVT-1) CRGT lower flange weld 100% of perip heral 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 we ld 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

Prairie Island 2, Nov. 201 5 C ore Barr el A ssembl y Enhanced visual 100% of one side of the Upper and lower core examination (EVT-1) accessible surfaces of the barrel cylinder girth selected weld and adjacent 100% of Upper Girth No relevant indications welds base metal (Note 4). Weld See Figure 4-22 of MRP-227- 76.5% of Lower Girth A Weld Comme n r.s:

'*'81...

Core Barre

• As.* m .. ,Y Lower core weld .(Nole I)

Enhanced visual examin8ltion (EVT-1) 100% of one side of the accessible surfaces of the aelected weld and adjacent 100% No relevant indications base metal (Note 4).

Comments:

Page 75 of 91

Prairie Island 2, Nov. 2015 Visual examination Bolts and locking devices on Assem b ly (VT-3) high fluence seams. 100% of 100% No relevant indications Baffle..edge bolts components accessible from core side (Note 3).

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

Co mm e nt s:

B affl e - F orm e r Volumetric 100% of accessible bolts A ssembly examination (UT) (Note 3). Heads accessible Not examined this Baffle-former bolts 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.

Comments:

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Prairie Island 2, Nov. 2015 B erfl a -For ma r Visual examination Core side surface aa A sse mb l y (VT-3) indicated. 100% No relevant indications 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 swellin in fonner lates Commen ts :

A1 gn ment. end Direct measurement Measurements should be lno:erf'ectng of spring height taken at several points Not Required for springs ComponenC* around the circumference of of type-403 material.

tntelMll hoJd the spring, wlh a statisticaly adequate number of measurements at each point to minimize uncertainty.

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

Commen t s:

Page 77 of 91

Prairie Island 2, Nov. 2015 A ase mb l y 100% No relevant indications Thermal shield ttexurea See Figures 29 and 4-36 of MRP-227-A.

Co mment s:

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 tota l 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 cons istent with the Expa nsion 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.

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Prairie Island 2, Nov. 201 5 Exis"t i ng Progr a m s Co mpon ents Required Coverage Examination Examtnatlon lte m Exam i nation Ach ie ved Findings Method 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 freq uency.

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 indication s Upper support ring or frequency.

skirt Comments'.

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Prairie Island 2, Nov. 2015 Req ulred Coverege Ex a m in e ti on Exami n ation Item Examinati on Ac hleved Findings Method 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.

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Prairie Island 2, Nov. 201 5 Required Coverage Examinet.t o n Exe m !nation Ite m Examination Comments:

M ethod Coverage Ac h Ie ve d Fin d i n gs

• • 'REPORT UPON THESE INSPECTIONS ONLY WHEN DONE IN CONJUNCTION WITH MRP-227-A RELATED EXAMS.

Alignment. and Visual examination All accessible Int erfac 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:

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

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

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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 Is land Nuclear Station Unit 1 Utility: Exelon Generation Date of Exams: 10/28/2015 to 11/23/2015 Plant Age: _4_1_ _ _ _ _ _ _ _ _ (years) .4_ _ _EFPY

/ ----'3~0_

Primary Components Pte,.um Cow*rA s *emlUy & One~l m e physica l 100% or t h e \Ne l dmentrlb No fi n d i n g s ,

Core S u pport Sl\Jeld measurement (1nttl*l dlffaranti*t height or top of pads, p 1e n um s upport fl a n ge, Ass em 1o1y Inspection) p l enum rib pads to reactor and CSS top r l ange.

P1enum cover watdment rib vessel ***ting surface, pads Visua l (VT-3) for wtth plenum tn reactor vesse l.

P1enum cover support na n ge s u bse qu ent CSS t o p fl ange I n spec tion s S ee F 1g&.1re 4-1 o rMRP-227-A.

Com m e nt s:

No fi n di n g s we re re p o r te d .

Co n tr ol Rod G ulde Tube V is u a l (VT-3} Ac cess i b l e su rfaces at N/A N/A Assemb ly each of the 4 screvv CRGT spacer c a stings focetlons (*t e v ery 90°) of 100% of the CRGT spacer ce s t ings

(.um it e-* 100%

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

One indeterminate volu m etrlc exam of bo l t 24 . Assumed Upp- <:ore l>al' *t (UCB} the boka (Note 3) fai l e d .

boft:a and tftalr l-ocilt,,o 120 bo l ts e x ami n ed .

ld*vtces V1auat (VT-3} See Ftgure 4-7 of MRP-ex* mlnatton of bolt 227-A.

locking devices Comments:

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

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TMl-1, FALL 2015 Core Barrel Assembly Volumetric 100% or accessible bolts 100% of a ll bo l ts and t.heir No finding s.

Lower core barrel (LCB) examination (UT) of and their tocking devlces l ocking devices.

bolts and their locking the bolts (Note 3) devices 108 bo l ts examined .

Visual (VT-3) s** F111ur* 4-8 of' MRP-axe mlnetlon of bolt 227-A.

locking devices Comme n ts'.

No fi n dings.

Core Barrel Assembly V01u m etrlc 100% of eccesstbta bolts. N/A N/A Baff'te"'to""torm er boks examination (UT) (Note 3)

See F111ure 4-2 of MRP-227-A.

Comme nt s'.

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

Core Barrel Assembly Vtsual examination 100% of the accessible N/A N/A Bame plates (VT-3) surface within 1 inch around each now end bolt hole.

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

Commen t s:

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 Core Berrel Assembly Visual examination 100% or accessible bame- N/A N/A Locking devices, includlng (VT-3) 'to-former end Internet l ocking welds, or beme~o baffle-to-baffle bolt locking form er bo l ts and tnt.ernal de v ices. (Note 3) b arr1e - to - b effle bolts See Figure 4-2 or MRP-227-A.

Comments:

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

F1ow D1urllH*t* Aa ** m lltty V 01u m atrtc 100% or" cc esslble bolts 100% o f a ll bo l ts a nd th e i r One volumetric i ndica tion on Frow dlsulb"Utor ( 0) bok*

• xem1nat1on (UT) or and thel-r tocking devices. l oc kin g dev ices. bo l t44.

e ntl the r rocking tl*v cee the bolts (Not* 3)

See F gure 4-8 or MRP- 108 bo lt s examrned Visual (VT-3) 227-A.

ex* m1natlon of bolt tocking devices Comments :

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 th reads approximately 4.40" from the top of the bolt head . Ex pa n sion criteria vvere not triggered.

Lower Grid Assemb l y V isua l examination A ccessible surfaces ot 100% of dovv e l -to-gulde No r e l eva nt Indica tion s n oted.

Anoy X-750 dowel-to-guide (VT-3) 100% orthe 24 dowel-to- b l ock vve l ds.

block wetels guide block welda.

See figure 4-4 or MRP- 12 guide b l ock pair s 227-A. e xamin ed.

Com m ents'.

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

TMl-1 , FALL2015 Inca-re Mol'ltt°'rlnfJ Vtsuat examination 100% ort:op aurfacas or 52 N/A N/A lnso;rument*tiol'I (1Mt) (VT-3) sptder c=astlngs *ncf welds G..... Tub* A........ ij,' to the a<ljacant lowar grid IMt guide tub* ap.tden rtb s ectJon.

IMJ 9"1d* tu** *l"k:l ..."'t.0- See Fie .... ** 4-3 and 4-6 or tower grid rib section welds MRP-227-A.

Comme nt s:

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 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 ns oc In Ch" pump

• nd valvo In. ocvlc 0 '""

pcogca ms (soe BAW-2248A, pogo 4-3 and Tab le 4-1 , coroc cncc 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 Required Coverage Examination Examination lte m Examinat i on Achieved Findings (Note 1)

Method 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-t o-upper (VT-3) 100% or the dowe l l ocking vve l ds .

grid fu e I a s s e m b I y s upport 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 100% of a cc e s s 'b I e N/A N/A (LJT). bo lt s or studs/nuts and Upper therm a1 shield (UTS) e xamination their locking devices bo l ts and their l ocking devices Lock in g Devices:

Vis u a l examination (Not e 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 Requir e d Cov e r age E xa m i n ation E x a m In a t io n lte m Exa m i n a t io n A c hi e ved Find ings (Note 1)

Meth o d C o ver age Core B a rr e l Ass e mbly Bo lt or St ud/ 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 (SS HT) stud s / n uts (CR- exam i nation (LJ T). their t ock 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 l y 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 id fu e l a ss c m b ly (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 fuel assemb l y support their l ocking w e l d s pads .

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

Comments :

Expans i on to t h is item vva s not req ui red 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 Required Coverage Examination Examination lte m Examination Achieved Finding s (Note 1)

Method 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 gr id shock pad bo l ts exa m inat i 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 t on 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 a nd 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 MR P- 227 R e v isio n 1 . T he l owe r Grid S h ock P a d 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 s emb ly Bolts: Volumetric 100% of accessible N/A N/A Lower thermal s hield (LTS) o xa m in 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 l e:

1. Examination acceptance criteria and expansion criteria t'orthe B&W compo nent s are In Tab l e 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 lt e m Exa mln a tlon Meth o d Di sposi t io n Core Barre l A ss 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 to t h is i tem vva s not r eq uir ed during F a11 2015.

Core Barrc1A s scmbly Interna l b a ff l e -to - b a ff'I e b a lt 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 by e v a I u at i on or by Ju stify rep l acement.

Externa l b a ff l e -ro-b a ff! e bo l ts , co r e barre l -re- N/A former b a l ts : 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 l t s Co m me n ts'.

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

Page 91 of 91