Text

End of Cycle 24 In-service and Steam Generator In-service Inspection Summary Reports
	ML17207A102
Person / Time
Site:	Mcguire
Issue date:	07/20/2017
From:	Capps S; Duke Energy Carolinas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	MNS-17-032
	Download: ML17207A102 (22)
	v • d • e

ef_~DUKE

~ ENERGYrn Serial No: MNS-17-032 July 20, 2017 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Duke Energy Carolinas, LLC (Duke Energy)

McGuire Nuclear Station, Unit 2 Docket Number 50-370 Renewed Facility License Number NPF-17 Steven D. Capps Vire President McGuire Nuclear Station Duke Energy MG!l1VP 112700 Hager.s Ferry Road Huntersville, NC 28078 o: 980.875.4805 f: 980.875.4809 Steven.Capps@duke-energy.com End of Cycle 24 In-service and Steam Generator In-service Inspection Summary Reports Pursuant to American Society of Mechanical Engineers (ASME)Section XI, as amended by ASME Code Case N-532-5, Duke Energy hereby submits the In-service Inspection Summary Report for McGuire Unit 2 End of Cycle (EOC) 24.

Additionally, pursuant to ASME Section XI and McGuire Technical Specification 5.6.8, Duke Energy submits the Steam Generator In-service Inspection Summary Report for McGuire Unit 2 EOC 24.

This submittal document contains no regulatory commitments.

If there are any questions or if additional information is needed, please contact Brian Richards of Regulatory Affairs at (980) 875-5171.

Sincerely, : :

McGuire Unit 2 End of Cycle 24 In-service Inspection Summary Report McGuire Unit 2 End of Cycle 24 Steam Generator In-service Inspection Summary Report

U.S. Nuclear Regulatory Commission July 20, 2017 Page 2 xc:

C. Haney, Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave. NE, Suite 1200 Atlanta, GA 30303-1257 Electronic:

A. Hutto, NRC Senior Resident Inspector Andy.Hutto@nrc.gov M. Mahoney, Project Manager Michael.Mahoney@nrc.gov P. Hooper, Standards and Inspections (NC DOL) phil.hooper@labor.nc.gov McGuire Unit 2 End of Cycle 24 In-service Inspection Summary Report

CASE N-532-5 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number ~-------O:::...::w~n~e:..:.r'-=s~A~c:..:t~iv~it~y~R~e~p~o:..:rt-'--'.:fo~r~R:..:.:::.e.:.:fu~e~li~n~g~O::..::.u~ta~g~e~2=-=E~O~C:..:2~4.:..._ ______ _

Plant f\\/tGuire Nuclear Station, 12700 Hagers Feny Rd, Huntersville, NC 20078-9340 Unit No.

2 Commercial service date --------

Refueling outage no.

2EOC24 03/0111984 t1f applicable)

Current inspection interva I -:...:1 S:..:1_-4.:..:t::..:hL, C=o~nl:::a::..:in""m.:..:..::.en:..:.t=--3:..:r-=d'-----..,-c-=-~"7"7,,..-~,--------------

11st 2nd. 3rd, ~I~. olher)

Current inspection period ISl-1 st, Containment-1st (1sl. 2nd. ~rd)

Edition and Addenda of Section XI applicable to the inspection plans 2007 with 2008 addenda Date and revision of inspection plans See attachment

~---------------------------

Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Same Code Cases used:

The follo.Mng Cede Cases are penritted by the ISi Plans: N-513-3, N-526, N-532-5, N-500-1, N-613-1, N-639, N-643-2, N-648-1, N.ffi3, N-7C6-1, N-716, N-722-1, N-729-1. N-731, N-735. N-770-1 (1f app!lcab!e)

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of 2ECC24 o:xiform to the requirem:nts;if Sectio~I.

(rauair.;iau<qerl.lltgi

~

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Signed Date 7/11/2017 CERTIFICATE OF INSERVICE INSPECTION I. the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of North Carolina and employed by The Hartford Sieam Boiler lnsoection and Insurance Co.

of Hartford, CT have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evalL1ation described in this report. Furthermore, neither the Inspector nor his layer shall be liable in any nner for any personal injury or property damage or a loss of any kind arising from or nected with this inspection NB 11473 N, I NC 1524

_,,1'1:::;~':1..<'ZJ!..~~::::::..L;,4(&!..L~::=z~~===------ Commissions -------------

July 12, 2017 Page 1of3

CASE N-532~5 Attachment McGuire Unit 2 End of Cycle 24 lnservice Inspection Report The McGuire Nuclear Station Unit 2 Fourth Ten Year lnservice Inspection (ISi) Plan complies with 10CFR50.55a(g), which implements, by reference, the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 2007 Edition with 2008 Addenda.

This summary report is being submitted pursuant to the reporting requirements of ASME Section XI as amended by ASME Code Case N-532-5, "Repair/Replacement Activity Documentation Requirements and lnservice Inspection Summary Report Preparation and Submission Section XI, Division 1".

Contained within this summary report are the form OAR-1 (Owner's Activity Report) and Tables 1 and 2 of Code Case N-532-5 for McGuire Nuclear Station during cycle 24 and Refueling Outage 24 (2EOC24).

2EOC24 is the second outage of the first ISi period in the fourth inspection interval. 2EOC24 is the second outage of the first Containment period in the third inspection interval. This report includes all Repair/Replacement activities from October 10, 2015 through April 22, 2017, cycle 24.

Date and Revision of lnservice Inspection Plans:

Fourth Interval lnservice Inspection Plans The following document comprises the McGuire Nuclear Station 4th Interval lnservice Inspection Plan for Unit 2 (Class 1, 2, and 3 Components):

"Fourth Interval lnservice Inspection Plan, McGuire Nuclear Station Unit 1 and Unit 2, General Requirements" - Document "MISl-1462.10-0040-GEN REQ UNIT 1 SECOND AND THIRD PERIODS AND UNIT 2", Rev 1, dated 05/28/2015.

The following document comprises the McGuire Nuclear Station 4th Interval lnservice Inspection Pressure Test Plan for Unit 2:

"McGuire Nuclear Station - Fourth Interval lnservice Inspection Plan - Pressure Test Plan",

Document MISl-1462.20-0040-PTPLAN, Rev 1, dated 06/18/2015.

Containment lnservice Inspection Plan The following document comprises the McGuire Nuclear Station 3'd Interval Containment lnservice Inspection Plan for Unit 2 (Class MC):

"McGuire Nuclear Station - Third Interval Containment lnservice Inspection Plan -

Containment - Units 1 & 2", Document #MC-ISIC3-1042-0001, Rev. 4, dated 11/28/2016.

Page 2 of 3

CASE N-532-5 McGuire Nuclear Unit 2 Form OAR-1 Owner's Activity Report Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service Examination Category and Item Description Evaluation Description Item Number Inactive boron leak found on Reactor Coolant Pump 2C.

Item was evaluated under IWA-5251 by B-P I 615.10 Dry boron powder identified on seal #1 and #2 pressure Engineering in NCR 02118551 and found to be relaininr:i bol!inr:i durinq 2EOC24.

acceptable.

Inactive boron leak found on Unit 2 Boric Acid Tank weld Item was evaluated by Engineering in NCR D-8 I 02.10 at base of tank prior to 2EOC24.

02053369 and found to be acceptable. This item was repaired durinq 2EOC24. see table 2.

F-A/F'l.20 Relevant condition found on hanger 2MCA-Nl-5104 prior Item was evaluated by Engineering in NCR to 2EOC24.

02110953 and found lo be acceptable.

F-A/F1.30 Relevant condition found on hanger 2MCA-CA-5602 prior Item was evaluated by Engineering in NCR to 2EOC24.

02107853 and found to be acceptable.

F-A/F1.40 Relevant condition found on hanger 2FWTK-SUPPORT Item was evaluated by Engineering in NCR prior to 2EOC24.

02063327 and found to be acceptable.

Thickness readings below 87.5% of nominal wall were Items were evaluated by Service Water R-A I R.17 observed during inspection of nuclear service water pipe Corrosion program manager in NCR 02116426 wall thickness grid at welds 1 RN218-9, 1 RN218-3.

and found to be acceptable.

RN2F2150. RN2F2149 and RN2F2292 dunno 2EOC24.

Table 2 Abstract of Repair/Replacement Activities Required For Continued Service Code Item Description Description of Work Date Completed Repair I Replacement Class Plan Number Reactor coolant system 20 Cold Temporary Weld overlay used Leg 1.5" boron injection piping; 1

thru wall leak at 50 bend just to repair leakage during forced 3/812017 20053461-16, 19,39 upstream of nozzle.

outage prior to 2EOC24 1

Reactor Coolant System 2D Cold Replaced section of pipe from 4/21/2017 20151614-1,7 Leg 1.5" boron injection pipinq.

nozzle past the 5D bend 2

Valve 2NC-30, pinhole leak in Replaced valve 3/8/2017 20025608-10,11.03 valve bodv 3

Boric Acid Tank, leak al weld and Code repair of tank base metal 4/15/2017 02205701-7,10 base metal Haw.

and weld.

Page 3 of 3 McGuire Unit 2 End of Cycle 24 Steam Generator In-service Inspection Summary Report

Steam GeTl!J,erator J!JllJ,"'serrvice l'nspectiOJllJ, §YAmmary JReprDHrl M<<:G'Plf,irte NucleOlr Siati(}n Unit 2 JEOC 2~

Sprirru,g Outage 2017 Location: McGuire Nuclear Station, 12700 Hagers Ferry Road Huntersville. N.C.

28078-9340 NRC Docket No. 50-370 National Board No. 84 Commercial Service Date: March l, 1984 Owner: Duke Energy Carolinas, LLC 526 South Church St.

Charlotte, N.C. 28202 Revision 0 Prepared By: Mitch Hatley ~-<$z~

Checked By: Dan Mayes b)G l(Y)~

Approved By: Etienne Fonteneau c:

"'~~.................... <6..b*---,../

Date: t.. /F/ 1 7 Date: 4$017 Date: b/lq/Wl7 Controlled Distribution

~

Original Uncontrolled Diltribution 2

J Document Completion Date: --------

Assigned To McGuire Nucl= St:1tion Document Conll'tll M:ister File MC 120 I.JS NRC Document Conuol H3!1fonl Steam Boiler lnspcctron and Insurance Corporation (A I Al Suuc of Nonh Carolina Department of Labor

NC-SUPP. 5 CASE (continued)

CASES OF ASME BOILER AND PRESSURE VESSEL CODE FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number Owner's Activity Report for SG lns~on Outage 2EOC24 Plant McGuire Nuclear Station. 12700 Hagers Ferry Rd, Huntersville. NC 28078-9340 N-532-5 Unit No~ __

2 _________ Commercial serviced ate: March 1st 1984 Refueling outage no. 2EO~C=2~4 __

(if applicable)

Current inspection interval _~4=th~---------

(1st, 2nd, 3rd, 4th, other)

Current inspection period ___ Js1 _

(1st, 2nd, 3rd)

Edition and Addenda of Section XI applicable to the inspection plans 20Ql_Edition through 2008 Addenda Date and revision of inspection plans 4/7/17 Revision 1 (MISISG-0269.030.0040)

Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans ________ _

Same as Plan

~- ---- ----------------

Code Cases used for inspection and evaluation: N-532-5 ____ _

(if applicable, includin cases modified b Case N-532 and later revisions)

CERTIFICATE OF CONFORMANCE I certifyttrnt (a} t11estaten'nts rmde in tt1isreportarecorrect: (b) tl1eexarrinalions and tests rreet the Inspection Plan as required by the ASME Code, Section XL and(c}tl1erepair/replacerrenl acti*Jitiesand evaluations supportingthecorrpletion or ~2=EO~C=2~4 ___________ _

conforrrlo the requiren-enls of Section XI.

Siqned I,,...

I J

=---*---:::z(,.J;__Date __

_,"0'-+/_,J'--l..___,__~;_*7~---

CERTlFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by Hartford Steam Boiler Inspection & Insurance Company of Hartford, Connecticut have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector *nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any annerforany personal injury property damage or a loss of any kind arising from or connected with this inspection.

(06/11)

TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Item Description Evaluation Description Category and Item Number Category B-Q Steam Generator Tubing in U-No ASME Section XI B16.020.001 Tube Design Acceptance Requirement B16.020.002 Exceeded (Reference Attached B16.020.003 Inspection Report)

B16.020.004 TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Class Item Description Description of Work Date Repair/Replacement Completed Plan Number 1

2NC SG0005 Plugged 6 tubes via 4/14/2017 Work Order#

2A Steam rolled plug and top of 02177729-15 Generator tubesheet wire rope stabilizer 1

2NC SG0007 Plugged 5 tubes via 4/14/2017 Work Order#

2C Steam rolled plug and top of 02177731-15 Generator tubesheet wire rope stabilizer 1

2NC SG0008 Plugged 5 tubes via 4/13/2017 Work Order#

2D Steam rolled plug and top of 02177732-15 Generator tubesheet wire rope stabilizer

McGuire 2 EOC24 Steam Generator Tube Inspection Report Pursuant to McGuire technical specification 5.6.8 the following information is provided:

a. The scope of inspections performed on each SG Bobbiu lllspectio11 Full length bobbin probe inspection of 50% tubes. The 50% sample mentioned above contained:

All tubes not inspected in 2EOC21.

All tubes with previous indications, e.g., wear, DNT, PLP, PRX, etc.

All tubes surrounding plugged tubes one tube deep.

Periphe1y tubes flvo rows deep in the hot leg and cold leg full length.

50% of rows 1-6 full length.

Array Inspection 100% ofperiphe1y tubes (5 tubes in from periphery) with array probe from top oftubesheet to the first support in both hot leg (TSH to 01 H) and cold leg (TSC to OJ C).

Special interest inspections were also pe1fonned on selected indications.

Visual Inspection Previously installed plugs Bowl cladding inspection Foreign object search and retrieval ( FOSAR) of the tubeslieet in all 4 steam generators.

b.

Degradation mechanisms found Degradation found included wear at support structures and wear from foreign objects.

c.

Non-destructive examination techniques utilized for each degradation mechanism The bobbin probe was utilized for the detection of wear at support structures and freespan locations and to size wear at support structures. The array probe was used to size the foreign object wear.

d. Location, orientation (if linear), and measured sizes (if available) of service induced indications.

There were 325 indications offanbar ( FB) wear reported. Ten of these indication were newly reported.

The deepest of fan/Jar wear indication was 26% TW The growth rate was 0. 7 o/oTW/EFPY. There were nvelve ( 12) indication of lattice grid (LG) wear reported. One of these indications was 1ze-wly reported. The deepest of lattice grid wear indication was 13% TW. The growth rate for lattice grid wear was near zero.

There were two (2) indication of foreign object were reported. Both were historical and showed no growth.

The complete listing for service induced indications is attached.

e.

Number of tubes plugged during the inspection outage for each degradation mechanism There were no tubes plugged in the 28 SG. There were six (6) tubes plugged in the 2A SG and there *were five (5) tube plugged in the 2C SG. All were plugged for visually identified foreign objects that could not be removed. There were five (5) tubes plugged in the 2D SG. Two of them were plugged due to eddy current identified possible loose parts. Three others in the region were preventively plugged.

2A SG 2CSG 2DSG Count Row Col Row Col Row Col Reason 1

80 27 109 68 103 108 Possible Loose Par/

2 81 26 108 69 102 109 Possible Loose Part 3

80 25 109 70 102 107 Pre1*enlive 4

79 26 JJO 69 101 108 Preventive 5

78 27 1 JJ 70 JOO 109 Prevenlive 6

79 28

f.

Total number and percentage of tubes plugged to date, and the effective plugging percentage in each steam generator.

Steam Generator1 2A 2B 2C 2D Total Prior to EOC24 20 8

13 5

46 EOC24 6

0 5

5 16 Total 26 8

18 JO 62

% Plugged/Effective Plugging % 0.39% 0.12%

0.27% 0.15% 0.23%

1= There are 6633 tubes per steam generator

g. The results of condition monitoring, including the results of tube pulls and in-situ testing.

The cumulative SG EFPY for EOC-22 was 14.84, EOC-23 was 16.21 and EOC-24 was 17.63.

As of EOC-24, the McGuire steam generators had operated 16.42 EFPY since the first in-service inspection after replacement. In total, the McGuire steam generators had operated 17.63 EFPY since replacement. At the time of the EOC24 outage, the McGuire Unit 2 steam generators were 4.42 EFPY into the second inspection period which has a duration of 120 EFPM. The EOC24 steam generator inspection was the second of three planned inspections in the second inspection period.

Condition monitoring structural and leakage integrity were met for fanbar, lattice grid mzd foreign object wear.

An NDE maximum depth call of 48. 7 o/oTW or lessforfanbar wear is sufficient to demonstrate a minimum degraded tube burst pressure of 3L1P, 4050 psi, at 0. 95 probability with 50% confidence. The worst case depth call forfanbar wear observed during the inspection was an NDE depth of 26%TW.

An NDE maximum depth call of 50.5 o/oTW or less for lattice grid wear is sufficient to demonstrate a minimum degraded tube burst pressure of 3L1P, 4050 psi, at 0.95 probability with 50% confidence. The worst case depth call for lattice grid wear observed during the inspection was an NDE depth of 12%TW.

An NDE maximum depth call of 51.2%TW or less for FO wear is St(fficient to demonstrate a minimum degraded tube burst pressure of 3L1P, 4050 psi, at 0.95 probability with 50% confidence. The worst case depth call for FO wear observed during the inspection was an NDE depth of l 5%TW.

During FOSAR, a total of 24 111etal objects were found with 11 removed. All foreign objects that were not removed have a technical evaluation demonstrating that tube integrity will be 111et through the next scheduled inspection at EOC27 or tubes surrounding the object were plugged. There was no wear was associated with any foreign object.

No degradation was detected in the plug visual or bowl cladding inspections.

No in-situ tests or tube pulls were pe1fonned.

List of Service Induced Indications McGuire 2, EOC-24 _

SG -

A Service Induced Degradation McGu.,i re 2EOC24 MNS 20170401 0s10212011 09,s0,ss

+--- -+- -- -+-- - - - - - - -+-- - -+- - --+- - - -+- -- --+- - --+- -- - - - - --+- -- - - -- - -+-- - - - - - - -+- -- -- -- --+- - -----+------ -+- -- -+- - - -+- - - - --+------+- -----+--+- ----+

[ ROW COL VOLTS DEG IND PER CHN LOCN INCHl INCH2 UT!Ll UTIL2 CRLEN CRWID BEGT ENDT PDIA PTYPE CAL IDX[

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PS 06H

. 47 WAR TEC TEH

. S60 ZBAHS 26 H

99 [

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.12 289 PCT

.13 117 PCT

.16 281 PCT

.10 261 PCT

.22 46 PCT

.10 116 PCT

.18 117 PCT

.26 106 PCT

.28 291 PCT

.20 111 PCT

.19 98 PCT

.12 91 PCT

.16 244 PCT

.14 62 PCT

.18 68 PCT

.19 271 PCT

.20 29S PCT

.13 72 PCT

.lS 97 PCT

.08 268 PCT

.19 2S7 PCT

. 20 246 PCT

.19 70 PCT

. 22 90 PCT

.18 2S2 PCT

.14 278 PCT

.17

. 22

.16

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.28

.22 113 261 PCT PCT 274 PCT BB PCT 93 PCT 83 PCT

. 24 267 PCT

.24 76 PCT

.20

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.67 47 PCT S9 PCT 83 PCT 264 PCT 273 PCT 88 PCT 283 PCT 2S0 PCT

.28 269 PCT

.23

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.24 92 PCT 79 PCT 260 PCT 100 PCT 262 PCT 7S PCT 286 PCT 6

8 10 13 13 11 11 6

10 10 10 6

4 10 10 11 10 6

8 10 16 13 11 10 10 8

12 9

2S 19 4

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. 60

-1.69

.69

-1.32

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1. 41

1. 03 1.38

.44

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. 31

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.82 37

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1. 20 1.02

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-.S9 1.68

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-.83

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-. 67

-. 96 1.10 WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH

. S60 ZBAHS

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SG -

A Service Induced Degradation McGuire 2 2EOC24 MNS 20170401 05/02/2017 09,50,ss

+- ---+- -- -+- --- --- - -+- - - -+- - --+- - - -+- - - - -+- - --+- -- - - - -- -+-- -- - --- -+-- - -- - - --+--- --- -- -+- -- -- - -+-- - - -- -+- - - -+--- -+- - -- - -+-- -- --+-- ----+--+- ----+

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+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+-------+----+----+------+------+------+--+-----+

101 76

.19 5S PCT 8

PS FB6

. 66 WAR TEC TEH

. S60 ZBAHS 19 771 107 117 117 117 117 70 86 100 106 110 110 110 114 9S 101 107 107 115 115 115 72 69 80 75 83 115 115 115 115 48 86 96 108 99 115 115 102 110 110 110 83 95 47 8S 56 17 17 76 76 76 76 76 77 77 77 77 77 77 77 77 78 78 78 78 78 78 78 79 80 81 82 82 82 82 82 82 83 83 83 83 84 84 84 85 8S 8S 8S 86 86 90 90 97 108 116 140

.11 118 PCT

. S4 101 PCT

.19 89 PCT

. 78 93 PCT

. 25 90 PCT

.19

.31

.13

.26

.4S

.31

.24

.19

.21

.32 S6 PCT 81 PCT 99 PCT 81 PCT 27S PCT 82 PCT 57 PCT 271 PCT 46 PCT 103 PCT

.30 86 PCT

.20 26S PCT

.42 84 PCT

. S4 93 PCT

. 24 247 PCT

.16 118 PCT

.19 92 PCT

. 20 247 PCT

. 20 286 PCT

.20 2S2 PCT

.27 96 PCT

. 40 275 PCT

. 39 89 PCT

.19 49 PCT

.16 97 PCT

.27 87 PCT

.2S 94 PCT

. 47 267 PCT

.41

.11

.42

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26 11 10 15 13 20 lS 11 10 10 13 14 10 19 22 12 10 10 10 12 17 17 8

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Tubes: 81 Records: 100 ST Max

SG -

8 Service Induced Degradation McGuire 2EOC24 MNS 20170401

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SG -

8 McGuire.

Service Induced Degradation 2EOC24 MNS 20170401

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Tubes: 52 Records: 62 ST Max

SG -

C Service Induced Degradation McGuire 2 2EOC24 MNS 20170401 05/02/2017 09,50,55

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CAL IDXI

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151 I

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2421 I

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90 61

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. 560 ZBAHS 23 471 I

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P5 FB4

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PS FB4

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1071 I

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87 76

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PS FB4

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PS FB3

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PS FBS

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+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+-------+----+----+------+------+------+--+-----+

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ST Max

SG -

C Service Induced Degradation McGuire 2EDC24 MNS 20170401 05/02/2017 09,50,55

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82 79

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P5 FB7 61 80

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P5 FB4 111 80

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P5 FB3 107 82

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1. 41

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. 560 ZBAHS TEC TEH

.560 ZBAHS TEC TEH

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. S60 ZBAHS TEC TEH

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. 560 ZBAHS TEC TEH

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. 560 ZBAHS TEC TEH

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.560 ZBAHS TEC TEH

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.560 ZBAHS TEC TEH

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. 560 Z8AHS TEC TEH

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. 560 ZBAHS TEC TEH

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.S60 Z8AHS TEC TEH

. S60 ZBAHS TEC TEH

. S60 ZBAHS I

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Tubes: 85 Records: 90 ST Max

SG - D Service Induced Degradation Mc Gu_! re 2EOC24 MNS 20170401

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.11 S3 PCT

.18 318 PCT

.11 109 PCT

.14 2S9 PCT

.3S 270 PCT

. 26 277 PCT

.19 82 PCT

.19 83 PCT

.17 9S PCT

.13 27S PCT

.lS 70 PCT

.21 9S PCT

.14 89 PCT

. 23 8S PCT

. 29 281 PCT

.26 8S PCT

.16 273 PCT

.14 84 PCT

.31 77 PCT

.24 91 PCT

.30 276 PCT

. 21 273 PCT

.28 9S PCT

.20 270 PCT

.21 256 PCT

.19 270 PCT

.20 98 PCT

.27

.S9

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.43 4S PCT 74 PCT 81 91 PCT PCT

. 23 267 PCT

.24

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.16

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. 16

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.28 90 PCT 100 PCT 250 PCT 89 PCT 51 PCT 67 PCT 286 PCT 289 PCT 273 PCT 7S PCT 269 PCT 282 PCT 104 PCT 94 PCT 86 PCT 87 PCT 98 PCT 117 PCT 293 PCT 94 PCT

. 46 268 PCT

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11 10 11 11 20 10 19 12 13 8

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. 62

. 70

-. 52

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.S60 ZBAHS

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. 560 ZBAHS

.560 ZBAHS

. 560 ZBAHS

.560 ZBAHS

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.560 ZBAHS

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. S60 ZBAHS

.S60 ZBAHS

. S60 ZBAHS

.S60 ZBAHS

. 560 ZBAHS

.S60 ZBAHS

. S60 ZBAHS

.S60 ZBAHS

. S60 ZBAHS

.S60 ZBAHS

. S60 ZBAHS

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.560 ZBAHS 10 11 11 12 12 12 11 12 12 11 12 12 11 12 H

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84 73

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.17 79 PCT 11 97 74

.12 280 PCT 6

107 74

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.10 265 PCT 90 75

.18 66 PCT 11 90 75

.21 89 PCT 13 90 75

.23 96 PCT 14 73 76

.05 230 PCT 4

101 76

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90 77

.15 245 PCT 10 73 78

.21 72 PCT 81 78

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97 80

.11 276 PCT 66 81

. 11 230 PCT 69 82

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.23 275 PCT 10 80 83

.15 107 PCT 82 83

.18 284 PCT 11 61 84

.25 267 PCT 11 7S 84

.10 264 PCT 72 87

.17 83 PCT 10 90 87

.19 96 PCT 8

55 88

.20 72 PCT 12 67 88

.13 62 PCT 8

71 88

.15 80 PCT 8

4S 90

.13 92 PCT 6

71 90

.22 87 PCT 73 90

.13 57 PCT 8

57 92

.16 266 PCT 50 99

. 07 275 PCT P5 F85 P5 F85 P5 FB4 P5 FB5 P5 FB4 P5 FB3 P5 FB4 PS FB5 P5 FB6 P5 FB4 P5 FB2 P5 FB4 P5 FB5 PS F84 P5 F84 P5 FB4 P5 FBS P5 F83 P5 F84 P5 FB4 P5 FB4 P5 FB5 P5 FB5 P5 F84 P5 FB4 PS FB5 P5 FB5 P5 FB5 P5 FB5 P5 FB5 P5 FB5 P5 FB4

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-1.19 1.47 WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR WAR TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH TEC TEH

.560 ZBAHS

. 560 ZBAHS

.560 ZBAHS

. 560 ZBAHS

.560 ZBAHS

. 560 ZBAHS

.560 ZBAHS

. 560 ZBAHS

.560 ZBAHS

. 560 ZBAHS

.560 ZBAHS

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.560 ZBAHS

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. 560 ZBAHS

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.560 ZBAHS 18 17 18 17 17 18 18 H 18 H

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Tubes: 72 Records: 87 ST Max

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EPID:L-2017-LRO-0022, End of Cycle 24 In-service and Steam Generator In-service Inspection Summary Reports (Approved, Closed)
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