ML20207K848

Rev 0 to Inservice Insp Rept McGuire Unit 2 1988 Refueling Outage 4

ML20207K848
Person / Time
Site:	Mcguire
Issue date:	09/22/1988
From:	Barbour G, Cherry J, Hogge A DUKE POWER CO.
To:
Shared Package
ML20207K840	List: ML20207K836 ML20207K848
References
NUDOCS 8810170059
Download: ML20207K848 (151)

Text

O 147 Pages l

FORM NIS 1 OWNERS' DATA REPORT FOR INSERVICE IN:,PECTIONS As req. dred by the Pronsions of the ASME Code Rules

t. owen Duke Power Comoany. 422 S Church Street. Charlotte NC 28242 (Nesmo and Addreas of Owner)

2. Maec McGuire Nuclear Station. Highway 73, Cowans Ford, NC 28216 (Name and AMeems of Plant)

3. Mast Unic 2

4. Owner Cerunener of Ausherina.on (if requesd) N/A

s. causnarani swewe on. 3-1-84 Ns.o.aa no.d N bn for uni 84

7. C _,

-e taspected Maamh comrer

" - - - t or Manufacturer or lastauer 5enar or Nadoeal Appurtmaames or laemuer Serial No.

Pmyteos No.

Board No.

See Section 1 Paraaraoh 1.5 in the Attached Report.

O i

Note Suppiernestaa shoes in form of lises, sketches, or drawings rosy be uend provWed (1) sise is 8% !a. a 11 la.,

(2) istormance la items 1 through 6 as this data report is lackuded os each sheet, and (3) each sheet is numbered J

and the aussber of sheets is recorded at the top of this forsa.

l O

0010170059 00M370 l

l PDR ADOCK O pg O

i O

' FORM NIS.1 (back) i 7-24-RR

9. Inspecooe laterval fue 3-1-R4 to 3-1-9 4 s, e - - g.coe 7-?-R7 to

10. Abstress of f===aa4a== laciude a time of -=- and a sistannent concermag stame of work requand for comoc taeemt.

11. Abstreet cf f*wh Noemd.

See attached report.

12. Absarece of cormam Messes a-w cahan. See Mtached report.

a we ceruty ser es m-made '.a ele report m comet.ad me --- and cometm me scene talsi etandorns to the naase of the ASME Code. Seedos XI.

N 1 ped Duka Pnwava ennna n yty rh _'

Daes 19 owner M

cernacase of Authoemance No. (if appeleable)

N/A

._ _ tspdecoa osse N/A CERTIFICATE OF INSERVICE INSPECTION I. the e " :Wi holding a veAid en-

-a=

leeued by the Nadonal Board of Boiler and Presente Vesosi Inspectors and/or the $tase or Primoes of MrC-and employed by of i

have inspected the compoesou desanbod la this Owners' Dass Report during the period

~/ 9 7 to ~7,4 N-O

- and stace that to the best of my knowledge and belief, the Owner has performed -uur6<he and takes comstm tooemarse desertbed la this Owners' Data Report in accordance with the requaemeem of the ASME Code, Seedos XI.

By sigmng this certdicsee neither the Inspector not his erapioyer mahme any warranty, erpressed or irapiled, comesenseg the aw-aaaa and cometm rneeseres desenbod la this ownets' Data Report. Furthermore, ommer the laspector not his enspioyer shaAl be liable la any rnaaner for say personal latury or property damage or a lose of say idad aneing trous ce connected with chie inspecuce.

~~ 3 b 19 Dame

[,

AM'77'28 N'

b co====oes

4 in.

6 Valves 1 Valve 16.66%

Yes i

Nominal Pipe Size i

B-N-1 Interior of Reactor 3 Items 2 Item 66.66%

No Vessel B-N-2 Integrally Welded Core None N/A N/A N/A Support Structures and Interior Attachments to O

i aeector ve' e'>

l B-N-3 Removable Core 1 Item None 0%

Yes Support Structures j

B-0 Pressure Retaining 3 Welds 2 Welds 66.66%

Yes Welds in Control Rod a

Housings i

B-P All Pressure Retaining 198 Components 88 Components 44.44%

Yes

(

),

Components i

1 B-Q Steam Generator Tubing 100% Station Technical Specifications Het N/A j

i F1.01 Class 1 Component 255 Supports 118 Supports 46.27%

No i

Supports l

i

}

i l

iO J

i Rev. O Page 2 C/6550053 September 16, 1988 a

)

1_

Class 2 Inspections O Sectiee XI Inspections Inspections Percentage Deferral Category Description

_ Required Completed Completed Allowed C-A Pressure Retaining 9 Welds 5 Welds 55.55%

No Welds in Pressure Vessels C-B Pressure Retaining 6 Welds 3 Welds 50%

No Nozzle Welds in Vessels C-C Integral Attachments 26 Items 15 Items 57.69%

No for Vessels, Piping, Pumps and Valves C-D Pressure Retaining None N/A N/A N/A Bolting Exceeding 2 Inches in Diameter C-F Pressure Retaining 300 Welds 155.5 Welds 51.83%

No Welds in Piping C-H All Pressure Retaining 117 Components 23 Components 19.66%

No Components F1.02 Class 2 Component 500 Supports 243 Supports 48.60%

No v

Supports Rev. O Page 3 j

C/6550053 September 16, 1988

Augmented Inspections Reactor Coolant Pump Flywheels 43.75%

Steam Generator Tubes on Preheater Section 100%

of require-ments for Outages 1, 2, 3 & 4 Pipe Rupture Protection 100%

of require-ments for Outages 3&4 Steam Generator Feedwater Modification 100%

of require-ments for Outages 1, 2, 3 & 4 O

i l

Rev. O C/6550053 Page 4 l

September 16, 1988 l

t i

O 3.o 84# i teservice t# a ctie e" rer oet ae 4 The final ISI plan presented in this section lists all examinations t

credited for Outage 4 at McGuire Unit 2.

This includes ASME Section XI Class 1 and 2 and augmented inspections required by the plant technical specifications, i

The information shown below is a field description for the reporting format included in this section of the report:

i Item Number

=

ASME Section XI Tables IW8-2500-1 (Class 1),

{

IWC-2500-1 (Class 2), IWD-2500-1 (Class 3) and Augmented Requirements Unique Identification Number 10 Number

=

Orawing Number Location and/or Detail Drawing

=

Locs.

Location

=

i i

Insp. Req.

Examination Technique - Magnetic Particle,. Dye

=

Penetral.t etc.

Proc. Numbers Examination Procedures

=

Material Type / Grade =

General Description of Material j

Diam / Thick Diameter / Thickness

=

3 t

Calib. Block Calibration Block

=

Comments General and/or Detail Description

=

I l.

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Rev. O Page 1 I

C/6550053 September 16, 1988

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j PSERMI: MISISUBS-GAISIO2 OtKE PtDeER CENANY PAGE 3

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COST 111 QUALITY S*.*JRANCE DEPARTMNT DATE 09/%2/88

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set lUIRE LMIT 2 PRE-SERVICE Ape IN-SERVICE INSPECTIt24 SYSTEM EEY ITEM lameER 994 MCQJIRE 218CERVICE Z8CPECTItD8 LISTING ERJTAGE 4 4

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( PLANfs KGUIRE tasIT 2 PRE-SERVICE AND IN-SERVICE INTfCTIGd SYSTEM lREYs ITEM BANGER SST MCEUIRE 2 IfCERVICE INSPECTION LISTING CUTAGE 4 ItCP PROC.

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.F1.C2.949 2-MCA-SM-164 MCSRD 29tA VT QCL-14 42.00 MECHANICAL

• M R 9

j F1.02.950 2-MCA-SM-175 MCSRD 2SMA VT QCL-14 42.00 HYDRAULIC SNUBLER

'F1.C2.951 2-MCA-2t-182 MCSRD 20MA VT QCL-14 42.00 MECHANICAL 2ABBER

]

l F1.02.952 2-MCA-29-183 MCSRD 22tA VT QCL-14 42.00 PECHANICAL SNUB 8ER i

'F1.C2.953 2-MCA-29-184 MCSRD 22tA VT QCL-14 42.00 MECHANICAL SNUBBER t

i 1

F1.C3.058 2-MCA-CA-5517 MCSAD 2CA354 VT QCL-14 04.00 RIGID SUPPORT 1

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F1.C3.05?

2-MCA-CA-5518 MCSRD 2CA354 VT QCL-14 04.00 RIGID SUPPORT 01.C3.960 2-MCA-CA-5519 MCSRD 2CA354 VT QCL-14 04.00 RIGID SUPPORT i

1

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pencmasgr MISIRAS-441SIOZ OtKE PCHER CM2'ANY PAGE 42 FILER COO 7133 QUALITY A*.*JIRANCE DEPARTMENT DATE 09/22/88 PLANT:

MCGUIRE LA(IT 2 PRE-SERVICE AtS IN-SERVICE INSPECTIt94 SYSTEM KEY:

ITEM MAGE *.

F1.

MCGUIRE 2 INGERVICE IN0PErTION LISTING GlJTAGE 4 INSP PROC.

MATERIAL DIAM./ CALIS ITEM MASER

10. MAGER ORAMING MASERS LOCS. REQ. MASERS TYPE / GRADE THICK BLOCK CGiENTS saassamassas mammus==

mmeass=====

======asa xm

sans unsamass a====

sassas sanza smazzansasazassamass=mazzaz=as F1.C3.061 2-MCA-CA-5520 MCSRO 2CA3%

VT QCL-14 04.00 RIGID SUPPORT I

F1.C3.062 2-MCA-CA-5521 MCSRD 2CA3%

VT QCL-14 04.00 RIGID SUPPORT F1.C3.063 2-MCA-CA-5522 MCSRD 2CA3%

VT QCL-14 04.00 RIGID SUPPORT F1.C3.064 2-MCA-CA-5525 MCSRO 2CA%%

VT QCL-14 04.00 RIGIO SUPPORT F1.C3.065 2-MCA-CA-5524 MCSRO 2CA3%

VT QCL-14 04.00 RIGID SUPPORT F1.C3.066 2-MCA-CA-5527 MCSRD 2CA3%

VT QCL-14 04.00 RIGID SUPPORT F1.63.067 2-MCA-CA-5529 FC*.RD 2 cal %

VT QCL-14 04.00 RIGID SUPPORT F1.#,3.048 2-MCA-CA-5530 MCSRD 2CA3%

VT QCL-14 04.00 RIGID SUPPORT b

F1.C3.069 2-MCA-CA-5531 MCSRD 2CA3%

VT QCL-14 04.00 RIGID SUPPORT 91.C3.070 2-MCA-CA-5532 MCSRO 2CA3%

VT QCL-14 04.00 RIGID SUPPORT

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A PREERAM: NISIIEAS4b4ISIO2 DEKE POER CmPANY PAGE 43 FILE:

COO 7133 QUALITY ASSURANCE DEPARTMENT DATE 09/22/88 PLANT:

MCGUIRE LA41T 2 PRE-SERVICE AND IN-SERVICE IPCPECTIG4 SYSTEM

' KEY:

ITEM 94ASER F1.

MCGUIRE 2 INCERVICE IPCPECTIG4 LISTING OUTAGE 4 l

INSP FRCE.

MATERIAL DIAN./ CALIB t ITEM 94ASER ID.8AASER DRANIPC #AABERS LOCS. REQ. 94ASERS TYPE / GRADE THICK BLOCK CtD9ENTS assassanssas assammaassamassanssa==sssssssssssssssama===== suas========== massans samass massa mass===sassamassmasassssasssas F1.C3.071 2-MCA-CA-5533 MCSRO 2CA3%

VT QCL-14 04.00 RIGID SUPPORT

)

F1.C3.072 2-MCA-CA-55%

MCSRD 2CAI%

Vr QCL-14 04.00 RIGID SUPPORT 4

' F A.C3.073 2-MCA-CA-5535 MCSRD 2CA3%

VT Q'.L-18 04.00 RIGID SUPPORT

)

'F1.C3.074 2-MCA-CA-5536 NCSRD 2CA3%

VT QCL-14 04.00 RIGID SUPPORT q

1 1

iF1.83.075 2-MCA-CA-5537 MCSRD 2CA3%

VT QCL-14 04.00 RIGID SUPPORT

. F1.C3.C74 2-MCA-CA-5538 MCSRO 2CA3%

VT QCL-14 04.00 RIGID SUPPORT 4

I I

aF1.C3.S77 2-MCA-CA-5539 MCSRD 2CA3%

VT QCL-14 04.00 RIGID SUPPORT 1

1

-F1.C3.C75 2-MCA-CA-5%1 MCSRD 2CA3%

VT QCL-14 04.00 RIGID $UPPORT l

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l lF1.03.C79 2-MCA-CA-5%2 6 2CA3%

VT QCL-14 04.00 RIGID SUPPORT 4

I F1.C3.000 2-NCA-CA-5%3 MCORD 2CA3%

VT QCL-14 04.00 RIGID SUPPORT

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PSEAAft: MISIRLAS-4b4ISIO2 DLKE PCBtER Ct9tPANY PAGE 44 FILE:

C807135 QUALITY meeJeaNCE DEPARTifMT DATE 09/22/88

, PLAfst MCGUIRE LaiIT 2 PRE-SERVICE AfG IN-SERVICE DCPECTICSd SYSTEM KEY:

ITEM 9AAGER FI.

MCGUIRE Z 18CERVICE DGPECTION LISTING GUTAGE 4 INSP PRCE.

MATERIAL DIAN./ CALIS d ITEM 3R3GER 10.DR39ER DRANING 9&ASERS LOCS. REQ. SANBERS TYPE /CRADE THICK SLOCK Ct99ENTS

• SSESRSEEBESS m3333333333333333333 5E33333555555553E355 ESSSE RESS EX3ERSES ESSEE3EEES ESEEES BEEEE RESEEEEEEEEEEEEEEEEEEEEEEESESE t

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I 4.0 Results Of Inspections Performed During Outage 4 O

The results of each inspection shown in the final ISI Plan (Section 3 of this report) are included in this section.

The completion date and status for each inspection are shown.

All inspections revealing report-able indications are described in further detail in Section 5, 6, or 7 as applicable.

The information shown below is a field description for the reporting format included in this section of the report:

Item Number

=

ASME Section XI Tables IWB-2500-1 (Class 1),

IWC-2500-1 (Class 2), IWD-2500-1 (Class 3) and i

Augmented Requirements ID Number Unique Identification Number

=

4 Inspection Date Date of Examination

=

Inspection Status CLR = Clear REC = Recordable REP = Reportable Inspection Limited L = Limited

- = No Geo. Ref.

Geometric Reflector

=

N = No Y = Yes Comments

=

General and/or Detail Description 1

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PREERAM MISImmS-eAISIM DLKE PmER Ct91PANY PAGE 2

FILE:

C007155 GUALITY ASSURANCE PEPARTMENT DATE 09/27/88 PLANTS MCCUIRE I.MIT 2 PSE-SERVICE Ate IN-SERVICE INSPECTIm SYSTEM REY:

ITEM peASER 303 FCGUIRE 2 INSERVICE 18CPECIIN RESULTS (RJTAGE 4 INSPECTI N INSPECTI N INSPECTI M GES.

ITEM DRSSER ID3R99ER DATE STATUS LIMITED REF.

CtR9ENTS susassssssse answsssssssssssssssa==========

massassass masassassa sans aususssssssssssssssssssssssssa 905.110.004 2PZR-13 Ou22/88 CLR L

N B03.110.00$

2PZR-I4 Ou22/88 CLR L

N 903.120.003 2PZR-13R Ou22/88 CLR L

M 903.120.004 2PZR-14R Ou22/88 CLR L

N I

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s 4 PROGRAM: MISIRUpe 4 1SIO4 Duke PCMER CCSFANY PACE 3

FILE:

C007135 QUALITY A"JRANCE DEPARTMENT DATE 09/27/88 s

PLANT:

MCGUIRE LIMIT 2 PRE-SERVICE AND IN-SERVICE ItGPECTION SYSTEM KEY:

ITEM NLfeER 804 MCGUIRE 2 INSERVICE INSPECTI(N RESULTS CUTAGE 4 IPCPECTION INSPECTI(94 INSPECTION GES.

l ITEM 942SER 10DameER DATE STATUS LIMITED REF.

CER9ENTS q

rassassanssa samasssssssssssssssa azzassamas massass=ss smassamass mass amassamassamassazzas=masassass 1

L l

804.012.001 2RPV-CROM 07/24/88 CLR 804.013.001 2RPV-INCORE 07/24/88 CL.R r

804.G.0.001 2PZR-MEAIER 0T/24/88 CLR i

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PeccaAft: MISIMMD-GAISIO4 DWE PmER COMPANY PAGE 4

FILE:

C007155 QUALITY AS*2JRANCE DEPARTPENT DATE 09/27/88 PLANT:

MCGUIRE tmIT 2 PRE-SERVICE AND IN-SERVICE INSPECTI m SYSTEM REY:

ITEM PRNSER 305 PEGUIRE 2 IPCERVICE IPCPECTIN RESULTS tRITAGE 4 INSPECTI m IPCPECTI N INSPECTI m CES.

ITEM 78.99ER 10PSDSER DAIE STATUS LIMITED REF.

Ct99ENTS sass========

mz===ss==ss==== mas:s

==

===azzassa

==

==================

905.020.005 2PZR-M5SE 06/I7/88 CLR L

M 905.020.003A 2PZR-MISE 06/II/88 CLR N

805.020.004 2PZ2-4ASE 06/I7/88 CLR L

N 905.020.004A 2PZR-4ASE 06/15/88 CLR N

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< FILE:

0007155 GUALITY ASTAJRANCE DEPARifENT D1TE 09/27/a8

PLANT:

MCCUIRE 12eIT 2 PRE-SERVICE AND IN-SERVICE INSPECTIt28 SYSTEM KEY:

ITEM 94ASER Su MCCUIRE 2 INGERVICE INSPECTIt28 RESULTS tRITAGE 4

)

i INSPECTION IrGPECTItM INSPECTI N GES.

ITEM 8429ER IO3RamER DATE STATUS LIMITED REF.

Ct99ENTS J

suusss====ss

sassmassamass==ssa massmas=

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==

==

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Parreast NISI ALSS-4MI5IO4 DLEE PGER CGWANY PAGE 6

FILE:

C007133

)

QUALITY AO'XJRANCE DEPARTMENT DATE 09/27/88 PLANT:

MCGtJIRE EMIT 2 PRE-SERVICE AND IN-SERVICE INSPECTImi SYSTEM

,, KEY:

IT*M MAeER 807 PK3UIRE 2 INSERVICE INSPECTIG4 RESULTS MJTAGE 4 i

INSPECTIW4 ItGPECTION INSPECTION GES.

ITF.M MmeER 10 MASER DATE STATUS LIMITED REF.

Ct99ENTS sassanussmus assssammassassansasm assammassa ausssssssa

==

sass samassassassssssssssssssssssas t

907.030.003 2SG8-t96-YY O U12/88 CLR N

907.030.004 2SG8-ft4-YZ 06/12/88 CLR J

N g

507.050.001 2NC53-FL1 07/05/88 CLR N

A00E0 PER IPS-2430f A B il 907.050.002 2NC53-FL2 06/09/88 REP N

PIR 2-M88-OI47 907.050.003 2NC53-FL3 07/05/88 CLR 1

N e

907.060.006 2ACP-28-H 06/17/88 CLR N

]

S07.070.057 2NI-94 06/23/88 CLR N

1 907.070.058 2NI-125 06/17/88 CLR i

N 5

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IP90GRAN: NISIRUDS-44ISIO4 DUKE PONER COMPANY PAGE 7

' FILE COO 7155 GUALITY ASSURAtaCE I1EPARTMENT DATE 09/27/Sa

PLANT

MCGUIRE LMIT 2 PRE-SERVICE Ate IN-SERVICE INSPECTI(M SYSTEN

< KEY:

ITEN 84ASER 809

1. CGUIRE 2 ItCERVICE INSPECTICH RESULTS OUTAGE 4 INSPECTION ItCPECTION INSPECTION GES.

ITEN 94DSER ID94ASER DATE STAILG LIMITED REF.

Ct9MENTS assanassssas sessssssssssssssssas samassmass

==

==

==

s============ss===s:ss=sss====

809.011.009 2NCN-36 73-1 J6/16/88 CLR L

N SO9.s11.009A 2fCN-3673-1 e6/16/88 CLR N

j 1

B09.011.047 2NC2TN24-2 06/28/88 CLR L

Y 809.011.047A 2NC2FN24-2 06/15/88 CLR N

809.011.048 2NC2FN24-3 06/28/88 CLR L

Y 809.011.048A 2NC2FN24-5 06/15/88 CLR N

I i

509.011.049 2NC2FN24-4 06/28/88 CLR L

N l

)

809.011.0494 2NC2FN24-4 06/15/88 CLR N

I 4

809.011.061 2NC2FM51-18 06/14/88 CLR L

N

)

909.011.061A 2NC2FM53-18 06/13/88 CLR N

509.011.062 2NC2FM53-19 06/14/88 CLR L

M l

+

t 809.011.062A 2NC2FN53-19 06/13/88 CLR N

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j 809.011.414 2NI2F-527 06/16/88 CLR L

Y I

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i j

809.011.415 2NI2F-529 06/16/88 CLR Y

SO9.011.415A 2H12F-529 06/11/88 CLR N

809.011.416 2NI2F-531 06/16/88 CLR L

Y I

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809.011.417 2NI2F-532 06/16/88 CLR L

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COO 7133 QUALITY ASSURANCE DEPARTIENT DATE 09/27/88 j PLANFs MCWINE IMIT 2 PRE-SERVICE AND IN-SERVICE INGPECTItM SYSTEN a KEY:

ITENSU SER 509

1. EGUIRE 2 IN;ERVICE INSPECTIN RESULTS OUTAGE 4 1

i INSPECTICH INSPECTICM INOPECTION GES.

ITEN fMSER 10 BMBER DATE STATUS LIMITED REF.

Ct99ENTS i

seassassames aussamasassassamassa suasesamma

==

==

sans massssssssssssamassasssssmussa l

]

SO9.011.417A 2NI2F-532 06/11/88 CLR N

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d SO9.011.418 2NI2F-2747 CV23/88 CLR L

Y i

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i 809.011.419 2NI2F-543 06/16/88 CLR L

Y l

i 909.011.4194 2NI2F-543 06/02/88 CLR N

i SO9.911.420 2NI2F-751 06/20/88 CLR L

Y SO9.011.4204 2NI2F-751 06/15/88 CLR 1

N 909.011.421 2NI2F-550 06/20/88 CLR L

N SG9.411.421A 2MI2F-550 06/15/88 CLR N

i 909.011.422 2NI2F-557 06/17/88 CLR L

N SO9.011.422A 2NIZF-557 06/11/88 CLR N

909.011.423 2NI2F-559 06/17/88 CLR L

Y SO9.011.423A 2NI2F-559 06/11/88 CLR N

k 309.011.424 2NI2F-563 06/17/88 CLR L

M i

809.811.4244 2NI2F-563 06/11/88 CLR N

999.011.425 2 NIP 190-1 06/22/88 CLR Y

SO9.011.4254 2 NIP 190-1 06/15/88 CLR N

3 999.811.426 2NI2F-571 06/21/88 CLR L

Y SO9.011.4264 2NI2F-571 06/15/88 CLR N

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s ymurmang: NISIWUMB-4AISIO6 DUKE PONER CtMPANY PAGE 9

FILE:

C007133 GUALITY ASSURANCE DEPARTMENT DA!E 09/27/88 PLAssT:

MCGUIRE tssIT 2 PflE-SERVICE AND IN-SERVICE INSPECTIt24 SYSTEM REY:

ITEM 9499ER 909 PEGUIRE 2 INSERVICE INSPECTIW4 RE"AJLTS tRJTAGE 4 INSPECTI(24 INSPECTI(24 INSPECTIG4 GE6.

ITEM 9 ESSER 20DRSSER DAIE STATUS LIMITED REF.

C M tTS sassssumessa

==================

==

==

==

=======================e

949.811.427 2NI2F-577 Ou21/88 CLR L

M 309.011.427A 2NI2F-577 06/15/88 CLR N

909.964.162 2NV2FN192-19 06/09/88 CLR N

999.968.163 29W2FN102-20 06/09/88 CLR N

999.060.164 2NV2FN102-21 06/09/86 CLR N

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ITEM DEMSEE S15 PCEUIRE 2 IN" RVICE 18CPECTION RESULTS (RJTAGE 4 4

IPCPECTICDs IPCPECTION ItCPECTItse CE S.

ITEM sastER IoDeseER DATE STAIUS LIMITE D REF.

CE9eENTS

==

samassassenessanss============

sssssssssa samassassa sans massmassassssssssssssssssesass C15.810.001 2nPV 07/24/86 CLR M

C15.029.001 2P2R 07/24/88 CLR N

C15.eSe.Sel 2SG-2A e7/24/88 CLR N

C15.e30.coz 2SG-2S e7/24/88 CLR N

C15.010.003 2SG-2C 87/24/88 CLR N

C15.ese.ee4 2SG-2s e7/24/88 CLR N

C15.eSe. set 2MC-2553.1.e 97/24/86 CLR N

C15.050.002 2PC-2553.7.e e7/24/e8 CLR N

C15.9%.ee3 2MC-2553.5.e eT/24/88 CLR N

C15.450.e04 2MC-25%.1.8 e7/24/86 CLR N

C15.eSe.005 2fE-25%-1.1 e7/24/88 CLR N

C15.ess.se6 2MC-25%-1.2 07/24/se CLR N

C15.054.007 2MC-2%1-1.0 eT/24/88 CLR N

C15.eSe.see 2MC-25 2-1.8 97/24/88 CLR M

C15.e54.099 2MC-2%2-2.8 07/24/88 CLR N

C15.eSe. ele 2MC-2%2-2.1 e7/24/88 CLR N

C15.058.811 2MC-2%2-3.0 e7/24/86 CLR N

C15.eSe.e12 2MC-25+2-3.1 07/24/86 CLR N

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PINERANs BGSIMAG-4AISIh Ot*E PEDGER Ct W ANY PAGE 12 FILE COSTI55 GUAl.ITY ASSullANCE DEPARIPENT DAIE E9/27/88 PLAseT SECEMAE tastT 2 PSE-SERVICE Are IN-SERVICE INSPECTICS8 SYSTEM SEYs ITEM temeER SIS PEGUIRE 2 INSERVICE ItCPECTICD4 RESULTS SUIAGE 4 18CPECTIt96 INSPECTIt24 INSPECTItpf GES.

ITEM 848eER ISDE#eEE SATE STATUS LIftITED REF.

Ct99ENTS usassass====

maasssssssssas==sans==== sass==

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sus=== sass asas

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C087155 GUALITY ASSURANCE DEPARTPENT DATE 09/2T/e8 i PLANTS DEGUIRE LNEIT 2 PSE-SERVICE A86 IN-SERVICE INSPECT 1894 SYSTEM

EETs ITEM faseER C83 MCE;EJIRE 2 IPC;ERVICE Itr#ECTIG4 RESULIS (RJTAGE 4 i

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CtWWENTS j

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============== mass

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I F1.03.069 2-MCA-CA-5531 05/18/88 CLR M

F1.03.0 70 2-MCA-C A-5532 07/07/88 CLR N

i F1.03.071 2-teCA-CA-5533 05/13/88 CLR M

I rx.03.072 2-MCA-CA-5536 05/13/8e CtR M

1 F1.03.073 2-MCA-CA-5535 05/13/88 CLR N

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l 5.0 Class 1 Inspection Results Examinations were performed during Outage 4 on Pressurizer, CROM Tube Welds to Reactor Vessel Up Head, Reactor Vessel Incore Nozzles, Reactor Coolant Pump bolting,perSteam Generator Bolting, piping and valve bolting, and on welds of primary piping.

5.1 Reactor Vessel i

A visual examination was performed on seventy-eight (78) CRDM Tube to Reactor Vessel Upper Head Welds and fifty-eight (58) Incore Instrument Tube to Reactor Vessel Lower Head Welds.

No reportable conditions were found.

The accessible internal surfaces of the Reactor Vessel were visually j

inspected.

No reportable conditions were found.

3.2 Pressurizer Pressurizer Upper Head to Shell Longitudinal Weld and two (2) Safety Nozzles to Upper Head Welds, including inside radiuses, received ultra-i sonic examinations.

No reportable indications were found.

One (1) Pressurizer Relief Nozzle Safe-End Weld and one (1) Pressurizer Safety Nozzle Safe-End Weld received an ultrasonic and a dye penetrant examination.

No reportable indications were found.

Seventy-eight (78) Heater Penetration Welds in Lower Head received a l

visual examination.

No reportable conditions were found.

5.3 Steam Generatort l

Steam Generator 2B Manway Bolting in X-Y Quadrant and Y-Z Quadrant 1

received a visual examination.

No reportable conditions were found.

J 5.4 Piping l'

Two (2) flange connections received a visual examination after dis-assembly.

Reportable conditions were found on flange connection i

2NC53-FL2 (Item Number 807.050.002).

All reportable conditions were i

corrected and declared acceptable.

Refer to Problem Investigation Report i

i Number 2-M88-0147 found in Section 9 of this report.

The inspection data sheets are included in this section of the report.

One (1) additional I

i flange connection was examined per ASME Section XI, Paragraph IWB-l

)

2430(A).

No other reportable conditions were found.

Similar Metal Butt Welds:

Twenty (20) circumferential welds, four inches and greater, received a j

volumetric and surface examination.

No reportable indications were l

t found.

l lO l

{

Rev. 0 Page 1 C/6550053 September 16, 1988

l Three (3) socket welds received a dye penetrant examination.

No report-able indications were found.

Piping Supports:

Twenty-seven (27) hangets were examined by visual methods.

No reportable conditions were found.

[

]

5. 5 Pumps

[

Reactor Coolant Pump 2A Main Flange Bolts received an ultrasonic exami-l nation.

No reportable indications were found.

Reactor Coolant Pump 28 Seal Gland Housing Bolts received a visual examination.

No reportable conditions were found.

5.6 Valves i

Bolting on three (3) valves received a visual examination.

No reportable conditions were found.

l 5.7 Steam Generator Tubing

)

The tubing in all four steam generators were inspected by eday current I

using multi-frequency techniques.

This inspection consisted of fatigue, hot leg tubesheet, code, and row I and 2 inspection.

The following l

table provides a brief summary of the bobbin examinations:

RSG "A" RSG "B" RSG "C" RSG "0" i

Fatigue Tubes Examined 317 294 373 290 f

1

- Run Full Length 2

Hot Leg Tubesheets Examined 3600 3564 3570 3571

- TE-HL to 1st TSP 4

Code Examination 496 549 472 548 j

j

- Run Full Length 4

Row 2 Examined 111 111 113 114 Row 1 Examined 0

0 10 25 The inspection results for Steam Generator "A" are as follows:

There were no tubes found showing degradation equal to or greater than 20%

through-wall (TW).

Forty-one (41) tubes were removed from service based 4

1 on combination of Eddy-360 inspection and use of P* Cciculation.

One (1) i j

additional tube was unplugged then replugged.

The inspection results for Steam Generator "B" are as follows:

There were seven (7) tubes found showing degradation equal to or greater than 20% through-wall (TW).

Thirty-five (35) tubes were removed from service 4

{

based on combination of Eddy-360 inspection and use of P* Calculation, i

Rev. 0 J

Page 2

)

C/6550053 September 16, 1988 i

s

...__,, ~. - - --

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

l l

The inspection results for Steam Generator "C" cre as follows:

There j

were no tubes found. showing degradation equal to or greater than 20%

through-wall (TV).

Fif ty-two (52) tubes were removed from service based on combination of Eddy-360 inspection and use of P* Calculation.

Eleven (11) additional tubes were unplugged then replugged.

1 The inspection results for Steam Generator "0" are as follows:

There 1

were six (6) tubes found showing degradation equal to or greater than 1

20% through-wall (TW).

Twenty-four (24) tubes were removed from service 4

based on combination of Eddy-360 inspection and use of P* Calculation, t

J Thirteen (13) additional tubes were unplugged then replugged, i

9 The following lists include all tubes in Steam Generators 2A, 2B, 2C t

and 2D showing bobbin coil degradation 20% and greater through-wall (TV).

5.8 Inservice Leakage Tests The Class 1 Pressure Boundary was subjected to an inservice leakage test as required by ASME Section XI, Article IWB-5000.

No reportable condi-l tions were found.

1

5. 9 Class 1 Repairs and Replacements Repairs and replacements for work performed from July 3,1987 to July 24, i

1988 are itemized 'n Section 11 of this report.

!O

)

1 I

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Page 3 C/6550053 September 16, 1988

FORM QCL 13A REV.2 26427 f A12 861 O'

i DUKE POWER COMPANY STATION Af f 6o Md UNIT 1

ISI VISUAL EXAMINATION, VT 1 1 (

o72/3/

Page I

of N

INSPECTOR LEVEL DATE:

PROCEDURE:

REV THICKNESS:

VISUAL METHOD:

Of CT R EP, OTE MATERIAL T YPE:

VISUAL AIDS /M & TE SN:

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• Plant McGuire t' nit 2 Steam Generator: B i

Outage:

06/88 RTO QUERY: B&W BOBBIN COIL - DETECTS 29-39% TW i

l TEST ROW COL IND %.TW VOLTS CHN DEG LOCATION EXTENT TAFE i

B&W 46 50 WAR 21 0.99 M 2 123 17TH TSP +

0.00 FL 14 l B&W 48 45 WAR 29 1.97 H2 86 17TH TSP +

8.09 FL 13 i B&W 48 61 WAR 26 1.58 M 2 57 20TH TSP +

0.88 TL L3 i B&W 48 66 WAR 38 2.06 M 2 88 17TH TSP +

0.00 FL L3 l j

B&W 49 51 WAR 23 1.18 M 2 96 !?TH TSP +

0.00 FL L3 ;

B&W 49 58 WAR 21 0.99 M2 e !?TH TSP +

0.08 FL

<3

)

B&W 49 63 WAR 27 1.67 M 2 e 177H TSP +

0.99 FL 33 I

i TOTAL 'A uBES TOUND e

7 f

TOTAL INDICATION TOUND =

7 r

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Planta McGuire Unit 2 Steam Generator: D Outage 06/88 RTO O

Q.UERY: B&W BOBBIN COIL - DEFECTS 20-39% TW TEST ROW COL IND %TW YOLT.S CHN DEG LOCATION EXTENT TAPE i.........

&W 9

32 ODI 28 1.19 M 1 113 22ND TSP-9.70 FL 2

&W 45 59 ODI 21 1.33 M 2 0 167 TSP +

0.00 FL S

36W 47 S1 WAR 21 1.32 M2 8 L7T TSP +

0.00 FL

,4 36W 48 40 WAR 24 1.67 M2 8

87 TSP +

8.00 FL e4 34W 48 62 WAR 24 1.63 M 2 0 a77H TSP +

0.00 FL 14 36W WAR 38 3.11 M 2 8 L77H TSP-0.60 FL 29 36W 48 64 WAR 26 1.81 M2 9 o77H TSP +

0.00 TL 14 TOTAL TUBES FOUND

=

6 TOTAL INDICATION FOUND =

7 t

O O

6. 0 Class 2 Inspection Results Inspections were performed on Safety Injection Accumulator Tank 20 Residual Heat Removal Heat Exchanger 2A Support and piping welds of Auxiliary Feedwater, Main Feedwater, Component Cooling, Residual Heat Removal, Safety Injection, Main Steam, Main Steam Vent to Atmosphere, and Containment Air Release and Addition Systems.

6.1 The Safety Injection Accumulator Tank 20 Shell-to-Lower Head Weld origi-nalJy scheduled for Outage 4 was inaccessible for preparation for the rquired volumetric examination.

Safety injection Accumulator Tank f.0 Shell-to Upper Head Weld was substituted and examined by ultrasonics.

No reportable ir.dications were found.

$se Request for Relief MNS-001 included in Section 10 of this report.

6,2 pjp_ing Ten (10) circumferential welds one half inch and less nominal wall thickness received a magnetic particle examination.

Forty-one (41) circumferential welds one-half inch and less nominal wall thickness received a dye penetrant examination.

A reportable indication was found l

I on weld 2VQ2FW5 2 (Item Number C05.011.811).

The indication was removed by grinding.

The excavated area received a d sonic examination and was found acceptable. ye penetrant and an ultra-See Problem Investigation Report 2-M88-110 included in Section 9 of this report.

A copy of the inspection data sheets is includtd in this section of the report.

The I

scope of the inspection was extended to include six (6) additional welds O

per ASME Section XI, Paragraph IWC-2430(A).

No other reportable indica-tions were found.

Seven (7) longitudinal seam welds one half inch and less nominal wall thickness received a dye penetrant examination.

No reportable indica-tions were found.

One (1) circumferential weld gr ater than one-half inch nominal wall thickness received a radiographic and magnetic particle examination.

Six (5) circumferential welds greater than one-half inch nominal wall thickness received an ultrasonic and a dye penetrant examination.

Two N

l (2) circumferential welds greater than one-half inch nominal wall thick-received an ultrason'c and a magnetic particle examination.

No ness reportable indications were found.

One (1) integrally welded attachment on the Main Feedwater System and four (4) integrally-welded attachments on the Main Steam System received a magnetic particle examination.

No reportable indications were found.

6.3 Class 2 Component Supports Seventy (70) Class 2 Component Supports received a visual examination as required by ASME Section XI, Article IWF-2000.

No reportable conditions were found.

O Rev. O C/6550053 Page 1 September 16, 1988

6.4 Class 2 Repairs and Replacements Rapairs and replacements for work performed from July 3,1987 to July 24, 1988 are itemized in Section 11 of this report.

1 i

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l l0 Rev. 0 Page 2 C/6550053 September 16, 1988 i

26294 (10 85)

FORM NDE.25A QEVISION O DUKE POWER COMPANY PROJECT McGuire MAGNETIC PARTICLE / LIQUID PENETRANT EXAMINATION REPORT FOR PRESERVICE AND INSERVICE INSPECTION Wald No.

2v02W5-2 Item No, c05.011.811 Unit No.

2 Pipe Diameter 6.00 Remarks:

ISI FINAL Wall Section Thickness

. f 34_

Date 13 -Pf.

SKETCH OF ITEM INSPECTED NDE Proc, 3 5 A F Rev.__.10__ _

NDE Inspectors / Level Yof04L 21~

/

/

/

/

/

N m er In i t$on Length /Dlameter Width Acceptable Reportable Reference Documents f

>o A 9 L etc(c.,St e r n) > % Y.' ni v Fr vd ua r/

MT Unit Serial AA Dry Particle Batch No.

kA MT Method OFluorescent ONonfluorescent Serial No. Light Meter VA MT Prepared Bath Batch No.:

NA Serial No. Black Light

/M MT Technique Used:

Black Light intensity Verified CCircular Time UA Date NA ODirect Contact Amp NA Time MA Date

1. d OCentral Conductor Amp uA PT Batch Number OYoke Cleaner 77 To76 M ~J7uco Penetrant 7~7 ~To 11 m e 2 7 CO 5 Remover v4 OLongitudinal Amp Turns OA Developer W n a ~4 't M G. 2 3 4 7 9

AlA CFluorescent ZNonfluorescent 4 I { Vet Particle Batch No.

comments: Fo2 A+AlA ct Y -

b o v.w v v ~ t e. L 1sT

, c.I 7

6vseulj ] d,'c o N esi 1e Movel, PT 0k f.).A % d wn L-tH-V V t

ANI Review De.

^

V. Review Date g g

QA*516A Revision 0 QUALITYA$$URANCEDEPARTMENT EVALUATION REPORT No. NWs en cod PLANT UNIT ITEM NUM8ER 10 NLM8ER McGuire 2

C05.011.811 2VQ2FW5-2 EXANINATION METHOD PROCEDURE INDICATIONS REQUIRING EVALVATICN PT NDE-35 Base metal (linear).3" long.015 vide DESCRIPTION OF ITEM OATE INSPECTED EVALUAT!QH NEEDED SY CATE Wald 2VQ27W5-2 5/31/88 6/3/88 CC*ENTS:

i QRIGINATED BY; d-a /b OATE:

6/1/88 M/

ACCEPTANCE STANDARD U$ED: Jyg-3 $/4 3 N bl e. I W $- 3 D4,3 p,M, j

ComENTS:

!O l

a ACCEPTABLE IN0! CAT!cNs

)L. REJECTABLE IN0! CATIONS I w A,,, t, w n 4

M_ b h J

DATE:

EVALUATED BY:

// / 2.,/ P P 2

1 OlsPO$1TICN:

TNe to indication being rejectable an additional sample of six (6) welds were done.

Weld was ground, indication was removed PT shows weld as being acceptable. (Ps.it 1 Xte-Otto)

A00!TICHAL INSPECTION $ REQUIRED: PLAN At0th0A No. 2MCC-0076 l

1

$URVE!LLANCE INSPECTION $ REQUIRED: Qog i

i i

l P!R SERIAL ho, j

2-M88-0110 c.o.Nu I'

0!$PO$1TICN BY: '4 4bmt.-A DATE:

Ros~ GINk%S

,ua J

26294 (10 85)

FORM NOE 25A GEVISION 0 DUKE POWER COMPANY' n!

PROJECT Mc Guire

(

MAGNETIC PARTICLE / LIQUID PENETRANT EXAMINATlON REPORT FOR PRESERVICE AND INSERVICE INSPECTION Weld No. 2v02 nJ-5-2 Item No, c05.011.811 Unit No.

2 Pipe Diameter 6.00 Remarks:

ISI FINAL Wall Section Thickness 0.134 Date S-J /, g. g SKETCH OF ITEM INSPECTED NDE Proc, 35 A F. Rev, /0 8

NDE inspectors / Level

.4 mm

/

y k

M. h 7 M'E

• N

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Wb _

w vrtw i

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/

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length / Diameter Width Acceptable Reportable Reference Documents '

N m er Indi t n p

.f

"$lviSD

.3"

. 0 /.S

/

rrt c AT-2 VO - C C/

l MT Unit Serial A/A Dry Particle Batch No.

A/ f

/

MT Method DFluorescent C Non fluorescent Serial No. Light Meter A//

MT Prepared Bath Batch No.:

A/bl Serial No. Black Light A' M MT Technique Used:

Black Light intensity Verified CCircular Time A / A Date_.

A/M CDirect Contact Amp NA Time

/VM __ Date

/M CCentral Conductor Amp NA PT Batch Number

gyog, Cleaner f 7 J' o 7 4 me_27&fo F PrM Penetrant 3'17 o 22 we 27f+4 Remover -

NAf CLongitudinal Amp Turns A/M Dueloper 91 # o f f mc 2ooof C Wet Particle Batch No.

NA ZFluorescent Monfluorescent (domments:

ANI Review Date Fmal QA Review Date

wwwmn COMPLETE FORM BY PRINTING WITH BL ACK BALL POINT PEN OR TYPE O

DUKE POWER COMPANY NUCLEAR STATION Problem Investigation Report Serial No. E'M" OI @

Station M'Sa"'

M" e/~ S t u b '" n investigation Report No. @

1. Problem Occurred Tkne/DaIe:#MM Discowred Trne/Date: 8-3/ ~88 Unit Status At Tkne ProbiernOccurned/Disecwed: Es At s />'an Ch Urvts(s):

A of wn/d

• 2 VQ HW-s*-l' hv $ e Descriptnon of Prqbiom' Ar"h1e 2*$Z insnee tNn PT* m tho d. it /4an i-i n k n h 'o n was loanof tAst' exceew/r al-eestance Mede r /s.'

~

Location ut Problem: 1/ef.'f #2 dur 8/de - e /. 7Fo Roern F2P Method Used to kbntfy Pn:biom.

Thr*f ref M 7~

immediate Correcttw Actons Taken/To Be Taken:

Work Stoppage Notfeation(Form OCK 2A)Wntten O Yes iirho; Sortal Na informaton Sources / References (Work Requests, Document Violated, etc.).gt' #OE-K-47 reve /0 Or9nated By: M64 Date: 6*2*8&

Dept./ Group /Section #

'W4A p

'!. Compliance Evaluation-Item / System Operable 94es O No

.V Item Reportable O Yes Gf6 Reportable Pursuant To: O 50.73 Secton O 50.72 Section O T.S Secten O Uc.

Cl Part 21 Evaluated By/Date: pI //p

1. 3e-4A/Xf O Other Comments:.lyk.ML tuidarsd phle A*Q nisip eMha..

til. Te4 con / ENS Report to NRC Time /Date: #/A NRC Contactee(s):

OPC Contactorts):

Telegraph /Madgram/Facssnele Transmssb1 to NRC-Date:

Date Notifed: NRC Res. Inspector Station Manager General Offce Comments:

IV. Innstgation Report Assigned To: N/A NRC Report Due Date:

Date Due to Comphance after Evaluaton

)

PIR Revow(Comphance):

Date PIR Station Manager Approval Date:

V. Further Action /EMRequired Nes O No(Explain Beicw):

Page 2 Assigned To:--(/tUpst 6=yeassag Comments:

Comphance Reyww

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Dane.I[I[8T OA Revew M62tM Date 6/N/M Otstnbuten Irwitsi j Ononator i A)d9 i 6 4, ism ! J Le d = if d /Qr d i

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4 /3 [ff REF. FIR:

2 W f8-O//O

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(COPY ATTACNED)

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[

THROUGN:

C00T i!NATOR, PROJECT MANAGEMENT DIVISION t

I To:

(To BE FILLED IN BY PMD) i W

DESIGN ENGINEERING DEPARTMENT

2. LColl.4

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DESIGN N GINEERING IS REQUESTED TO PROVIDE ASSISTAN I

W BELOW FOR THE ATTACHED PIR.

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g REPLY NEEDED SY:

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t M PERASILITY EVALUATION SUPPORT 4/r/af4wn F ody[nge 10CFR21 EVALUATION SUPPORT y

t i

M ROPOSED RESOLUTION (ITEM VI) 4/2V/Pf N

RESOLUTION COMPLETION VERIFICATION

• i l

5 (CORMCTIVE ACTION, ITEM VIII)

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CRITERION XVI (10CFR 50. APP 5) EVALUATION

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(* REQUEST ONLY AFTER STATION QA APPROVAL 4

o OF RESOLUTION)

STATION CONTACT IS: Movte/h i f EXT. // M h /

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y DATE:

THROUGN C00RDINATOR, PMD I

5 TO:

ATTNi

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(GROUP MANAGER OR PLANT MANAGER)

TNE REQUESTED INFORMATION IS ENCLOSED i

7 FROM:

COORDINATOR, PMD

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26254 (Rf 8h Form NDE408 Revisen 1

DUKE POWER C PANY PROJECT M # _

ULTRASONIC THICKNESS MEASUREMENT REPORT ltem inspected dd2N 5 2 Unity Location /a# - A ##

1 Type Material And Form Plate NominalThk.

- Weld O CS % SS Other ripe Sch. /J V Dia /. d "

Pump / Valve O Cast O Forged i

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SM / 00 Serial No,

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/d MHZ Untrasonic Thickness Scanning Technique Used: Spot 8

Continuous 1

Reference Standard No. 55 -4 Designated Qualification Points

[

Reference Standard Point Thickness Points Serl[N ekness 1

2 3

4 1

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SKETCH OF ITEM INSPECTED Ref Documents A/M +'d*4 Rev 8

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Inspection Results - J4'H#c/ad efer Nf4**e / h

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cept O Reject Acceptance Standard Used A dSI d 3 A' /0 SA 3Q j

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- A SNT-TC-1 A Date 8 '#* 80 Level QA Approve' O. 62 Date S'10'3T

.- N? NU

- - - - - - - - -. - - - W

7. 0 Augmented Inspection Results Augmented inspections were performed on the Reactor Coolant Pump Flywheels, Pipe Rupture Protection and Steam Generator Feedwater Modt-fication.

7.1 Reactor Coolant Pump Flywheels Reactor Coolant Pump 29 Flywheel received an ultrasonic examination in place.

Reactor Coolant Pump 2C Flywheel was removed and examined by ultrasonics and magnetic particle methods.

No reportable indications were found.

7.2 Pipe P.upture Protection Two (2) welds on the Reactor Coolant System Pipe Rupture Protection received an ultrasonic and a dye penetrant examination.

No reportable indications were found.

7. 3 Steam Generator Feedwater Modification A visual examination was performed on Steam Generator 2C Feedwater Modification.

No reportable indications were found, i

O l

o Rev. O C/6550053 Page 1 September 16, 1988

8.0 Personnel, Equipment and Material Certifications All personnel who performed or evaluated the results of inservice inspec-tions from July 3,1987 to July 24, 1988 at McGuire 2 were certified in accordance with the requirements cf the 1980 ASME Section XI with addenda through Winter 1980.

The appropriate certification record for each Duke Power Company inspector is en file at McGuire Nuclear Station.

The certification records for the Babcock & Wilcox inspectors are on file at the Babcock & Wilcox offices in Lynchburg, Virginia, Records of periodic calibration of Babcock & Wilcox inspection equipment are on file at the Babcock and Wilcox offices in Lynchburg, Virginia.

Records of periodic cM11bration of Duke Power Company inspection equip-l ment are on file at McGuire Nuclear Station or in the Corporate Offices in Charlotte, North Carolina, l

4 i

O l

i O

Rev. O C/6550053 Page 1 September 16, 1988

9.0 Problem Investigation Reports A copy of each Problem Investigation Report resulting in reportable items, originated against scheduled inservice inspections performed during Outage 4, is included in this section.

P.I.R. NO.

DESCRIPTION DATE ISSUED l

2-H88-0110 Reportable Indication -

06 02 88 Class 2 Piping Weld

(! tem No. C05.011.811) 2-MS8-0147 Reportable Condition -

06-30-88 Class 1 Flange Connection (Item No. B07.050.002) 2-M88-0155 Steam Generator 24., 28, 07-01-88 2C and 2D Tubes O

O Rev. O C/6550053 Page 1 September 16, 19S8

Form 3S372 ft10 er)

COMPLETE FORM BY PRINTING WITH BLACK BALL PolNT PEN OR TYPE DUKE POWER COMPANY O

NUCLEAR STATION Problem investigation Rep #"</*

1. ^' f"aort Serial No. M N'- OII O Station

1. 1 4""

investigation Repett No. (A

.o I. Problem Occurred. Time /Date:

Discovered Time /Date: 8

/ ~88 UrJts(3):

A Unit Status At Time Probternoccurresf/ Discovered. ## w//de C# 4 3

Description of P tem: DerInn.T5E ins ec to'en of Weld ** a1 Vq 2f W-91' ba fou nof thf_ exec &s' a'eee,0fance t/r n Nsm F lndic<

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%g Location ot Problem:

~

N f reew Method Used to identify Problem:

ImmediatJ CorrectJve Actions Taken/To Be TakeI1:

Work L.ppage Notificat' n(Form OCK 2A) Written O Yes Who: Serial Na e

Inforrnation Sources / References (Work Requests, Document Violated, etc.). p/ #BE-if,M rev. /0 Ong'nated By: WMA Uate: 6'd5e Dept./ Group /Section //W/N h,

11. Compliance Evolustion-Item / System Operable Pfee O No itemReportable O Yes G-f6 Reportab!v Pursuant To: 0 50.73 Section Part 21 e rse. 4 <j gM s

O t.0.72 Section O T.S. Section,

n Uc.

3 O Other Evaluated By/Date:

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lil. Telecon/ ENS Report to NRC Trne/Date: A//d NRC Contactee(s):

OPC Contactor(s):

Telegraph /Mairgram/ Facsimile Transmission to NRC Date:

Date Notified: NRC Res. Inspector Station Manager

)

General Of fice..

Comtrents-IV. Investigation Report Assigned To: N/A NRC Report Due Date:

Date Ov1 to Compilance after Evaluation PIR Review (Compaance):

Date; -

PIR Station Manager Appraal Date:

V. Further Actk a/ Evaluation Roquired GYes O No(Explau)Below):

Page 2 Assigned To: utS'tjit 6pAm3 Comments:

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2M94110-85) MIM/ M 2-#/8/(-6//O /[n Lpfj FORM NDE 25A REVisl0N 0 DUKE POWER COMPANY

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PROJECT McGuire T

MAGNETIC PARTICLE / LIQUID PENETRANT EXAMINATION REPORT I

POR PRESERVICE AND INSERVICE INSPECTION Wald No, 2Vo2 W5-2 Item No, cos.ofi.aii Unit No.

2 Pipe Olameter._ 6.00 -

Remarks:

mym Wall Section Thickness G4 _ __

SKETCH CP ITEM INSPECTED Date 0 -IJ pp NDE Proc.

35 A 7 Rev.

10 NDE Inspectors / Level Y l. % A 1r

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MT Unit Serial 4A Ory Particle Batch No._

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NA Serial No. Block Light ll/A MT Technique Used:

Black Light Intensity Verified CCircular Time u A-Date vA MA ODirect Contact Amp AA Time AlA Date -

CCentral Conductor Amp uA PT Satch Number Clooner 9"?Ta7C A c 1*7 u c o OYoke Penetrant 7 ~7 *ro 1 1 y e n cui Remover oA Z Longitudinal Amo Turns t

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DUKE POWER CO PANY PROJECT N*

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ULTRASONIC THICKNESS MEASUREMENT R EPORT ltam inspected I/dMM S f UnitI Location /a# - A ###

Type Meterial And Form-Plate NominalThk.

Weld O CS % SS Other Plpe Sch.. /J F " Die A d ~ -- Pump / Valve O Cast O Forged Instrument Myh Aire

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/38/2 A Scen Y

Metered or Digl,tel Velocity Type Couplant ' k Transducer Size.Ese "

Type My Serial No. 88F75f' Frequency

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Reference Standard Point Thicknees Points Sert Th i

1 2

3 4

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Fcem M372 aR10 87)

COMPLETE FORM BY PRINTING WITH BL ACK BALL POINT PEN OR TYPE DUKE POWER COMPANY oV NUCLEAR STATION Problem investigation Report Serial No.

1ME-oi4 7 Station McGuire Investigation Report No.

rd/o I. Problem Occurred Time /Date-6-9-8.8 Discovered Time /Date:

6-9-88___

Units (s): _ 2 Unit Status At Time Problem Occurred / Discovered: _.Eefueling_0utage___

Desenption of Problem: _.IS Linspec tian_of _ flange _2SC53-EL2 dBOLO50,002)_af ter_ disassembly _.

.r e.v e a l e d_th a t_3_nu t s _wc r c _ mis s ing.__4_ nu ts_ s erlaLnumb ers JN562._R571._ N555. _S558 ).

_ e r e_ r e f e c t abl e _d ue_ to_ exc e s s ive_ pit ting._2_ s tuds_s erlaL numb ers-_IO 640_ and_0662 )

w

_we r e_rej e c table _due_ to_ exces s ive_ pitting._3_s tuda_s e r i n i numb ers_ (0643._0649.0761)

.weIe_ acceptable _but had_unrcadable._caterlaLcodes etched _on_them._and 10_nuta_scrial_.

.nu=bers_(N562._.N564. N575._S559._07 62._07 62 _0761._0761._D760 _0760)_. Sea _ attachment _1._

Location of Problem:

Iop_of_PZR_Ilevation_S05__90' Method Used to identify Problem: ____Ihis Report immediate Corrective Actions Taken/To Be Taken: _WM6 Work 'toppage Notification (Form OCK 2A)Wntten O Yes lC No; Senal No.

Information Sources / References (Work Requests. Document Violated, etc.):.__QCL-13 Onginated By: M _w__ d2 b M e-Date: _ 6-30 Dept./ Group /Section _]cG.uir.c a_QA.

II. Compliance Evaluation Item / System Operable 7Yes O No p

Item Reportable O Yes ? No Reportable Pursuant To: O 50.73 Section

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b O 50.7? Section _

_. O T.S Section O Lic. Co. Section __.

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_N[A NRC Contactee(s):

DPC Contactor(s):

Te!egraph/Madgram/Facsimde Transmission to NRC Date-Date Not) fred NRC Re3. Insre * >r ____ ___.

Station Manager General Office -___

Comments:

IV. l.1vestigatron Report Assrgned To: _. __

hit

__ NRC Report Due Date: _._

Date Due to Comphance af ter Evaluation PIR Review (Comphance)

Date:

PIR Station Manager Approval Date:._ _

V. Further Action / Evaluation Required /Yes O No(Expta'n Below):

s Page 2 Assigned To: _ _,/>d h e s _ _ _ _ -. _ _. _ _ _ _. _ _

y Comments:

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PROBLEM INVESTIGATION REPORT Pace 2 Plfk No.

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VI. Proposed Resolution of Problem C c i ex lao c.on ve.c 3 a h o as w/ M NPO. th e Mrec l.

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FORM QCL 13A REV.2 26427 IR12 86)

DUKE POWER COMPANY l

k STATION MY.d//F UNIT d

ISI VISUAL EXAMINATION, VT 1

/

W.R.*

/

of Page C72/3/

INSPECTOR LEVEL DATE:

PROCEDURE:

REV:

H f f' DM-13 5

VISUAL M'ETHOD:

REMOTE

s. &. ksor JL THlCKNESS.4 DIRACT

/

a M ATERI AL T YPE:

VISUAL AIDS /M & Ty SN:

D 8454/vylr l

tulttoAf SU RF ACE: io3 JChlo

~

ID NUMBER:

g pg,

,g, r'D/H. /7.).

dgg3 - F/-2 )

ITEM NO. Ao7,4so 88 A ITEUS INSPECTED: Shds 4 Mds * (0163, c4 4l; 014 6~, 06 5'/, 0 740, 0 74,t, 04 st>)(A f r y, f

A's'f t, d121, n'ssn WsG4, N Sa Y, r/s4 s)

IN.

IND CATION LENGTH WIDTH FEMARKS

~~

~

AloJe

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l k

i RESULTS. )(ACCEPTABLE UNACCEPTABLE. REQUIRE $ NDE/ EVALUATION OR REPAIR COYMENTS/ DISPOSITION:

l

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- N i l R E v i E t'.

/

7"I~M QA REVIEW DATE

FOR INFORMATION Obt)

FORM QCL 13A REV.2 2927 m12 *s

<4

,,, g a DUKE POWER COMPANY

[V

)

STATION Md 4vr F UNIT d

ISI VISUAL EXAMINATION, VT 1 W. R. =

/

072[3l Page

/

of INSPECTOR LEVEL DATE:

PROCEDURE:

REV:

7 f' P RA-/3 5

VISUAL METHOD:

01 CT REMOTE

n. msoa THICKNESS: l MATERI AL T YPE:

VISUAL AIDS /M & TE SN:

Y flAsiLE hi*

SU RF ACE: 10 00 Altto R Y

JLA l6 ID NUMBER:

KPSI C ISI

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• ITEM NO. A 07,b50. oO L lTEMS INSPECTED: $h>d 5 + Na+ s. (Ot03 ; D10 5, Of04, 0 70 5'y b Vo (.) (g*t35, d13 4., d 181, Ai r3 p A134, d 140; U 14I; 0 140; W 143, A/1y y, 2145, N1V4, W147, 21gf, p999, g730, gys=j)

I IND CATI N LENGTH WIDTH REMARKS O

ypE Yod 8

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Ll RESULT 3 X^ccE"Taste

- uNacCePT4stE. REOuinES NoE EvatuATioN O= nEmaia CC'."'E N TS DISPOSITION i

I I

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QA QCPM Page 3 Procedure No. QCL-13 Revision 3 4.11 Conditions such as fabrication marks, scratches, surface abrasion, b) material roughness and other indications that are acceptable in accordance with design or manufacturing specifications are con-sidered non relevant and need not be documented.

• • • Note ***

Linear indications are those indications with a length at least 3 times the width.

4.12 Indications as listed below or which may be detrimental to the intended service of the item shall be considered unacceptable for continued service without supplemental NDE or evaluation showing the indication to be acceptable.

4.12.1 Category B-G-1 Nuts and Category B-G-2 Bolts, Studs, and Nuts M

-}-

a)

Cracking b)

Linear nonaxial indications greater than 1/4".

y' c)

Linear axial indications greater than 1".

Q

~i d)

Linear axial indications greater than 50% of nut length g

on nuta 2" and less in diameter, i

e)

Linear axial indications which continue on two or more

faces, f)

More than one deformed or sheared thread in the zone of thread engagement.

N g)

Bending, twisting, or deformation to the extent that assembly or disassembly is impaired.

M%

D h)

Corrosion that reduces bolts or studs cross sectional C4.

area by more than 5%.

l f

i)

Missing, fractured, or loose bolts, studs, and nuts,

... Note...

Evidence of coolant leakage around bolting must be identified and evaluated to assure that tione of the above criteria has been exceedec.

i l

4.12.2 Category B-G-1 bushings, wasners and flanges t 1 m)

Any linear indicstions gre3ter than 1J16 in.

1 0 c f:r Os materials less than 5/3 ir. tnico. greater ins 1 1 t-long for materisis fec-5/c in. tnic, to un er 2 1.

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DUKE POWER COMPANY STATIO:4 A f 6o Md U NIT _2-ISI VISUAL EXAMINATION, VT 1 W"

g 7 2/ 3/

Pap I

of N

INSPECTOR LFVEL DATE:

PROCEDURE:

REV THICKNESS:

^

VISUAL M ETHOD:

01 CT RE{OTE f

I M ATERI AL T YPE:

VISUAL A105/M & TE SN:

f~utJHLZd//7 SURFACE:

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,rEu NO E 0 x e s o. 0 0 2 ITEMS INSPECTED:

k Y

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INDICATION LENGTH WIOTH REMARKS NO.

TYPE se'..

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l lqV $ f p17Trud Ji** W

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O ACCEPTABLE guNACCEPTABLE, REQUIRES NDE/ EVALUATION OR REPAIR g g:,$t(*<f pu?J wlik* M11JZW4 AkJ 19JNFeM Co uLa M t r$6 WJt'e'c %~J (4) f4gygigge g(,cpp,gg,f7)

COMMENT $iol$ POSITION: fy: p y qg pu n y;,,e j,fec ygg, gro 00) fMr w.Mr tueMai s NA 11: Au1 M4a uts_a s tu* Au re e oij er, Af Lffrdd streeiv hfkt YA &n i fN$6 7-ll5 7/-NSSf siJ~n) Acurtsu : h/s4 'ossm'sGr s/fd y

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ANil REVIEW DATE-QA REVIEW DATE 2* 8 '8 8 j

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FORM QCL 13A REV.2 26427 4 A12 96)

DU POWER COMPANY STATION,

86"E#WNIT 1

ISI VISUAL EXAMINATION, VT 1 d 72/3 /

f or. h.ftQ P,,,

INSPECTOR LEVEL DATE:

PROCEDURE:

REV THICKNESS:

VISUAL METHOD:

DI A CT RE{OTE MATERIAL T YPE:

VISUAL AIDS /M & TE SN:

fld) *!L Edd7' SURFACE: io ao O

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$, ff.4CG ID NUMBER:

8d [I ~2 ITEM NO.

d E dId* d@

ITEMS INSPECTEO:

O 0$ (ff6 Jeft ceu ren dn --f )

If40.

IND CATION LENGTH W10TH REMARKS I

p gg fg/

g'(cc'11TYa /Z?*7THC M41 A'</Juc ew u1 'r i 77 7 'ad A rres A And/

,rrirdAr/le r/rerssrst O

r// d4ses' RESULTS:

O ACCEPTABLE Yl)NACCEPTABLE. REQUIRES NDE/ EVALUATION OR REPAIR (7)

COMMENTSiDISPOSITION: gfpf gp y /g f y,jyf g,pg iggynygg,pp,ey u,gg g egg,mf o d A s M a s A rk N 4( J)

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dasman COMPLETE FORM BY PRINTING WITH BLACK BALL POINT PEN OR TYPE DUKE POWER COMPANY n

NUCLEAR STATION v

Problem Investigation Report Serial No.

S- #1M- 0164' Station

"!' Gurre investigation Report No. 4 M-o M-2 7-/- N Discovered. Time /Date:

.54'"9

1. Problem Occurred-Time /Date:

M"e b4 6u f**y+s-Unit Status At Time Problem Occurred / Discovered:

Units (s): _d

<[_g_ru ra Descnptnon of Problem _.D't (* L <ddy f Af_A_c{efe ero nec/_Ls/ en c h.5teo G /i s f cunt W I'1 sp2Cc No*

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el takes n e ec Lo$-ph$$ ng MP2pa &s Location of Problem: _lbf /h 2 - Ateh 5fc.tpr ymer470r Method Used to Identify Problem:

7'#/1 FEREM/M Immediate Corrective Actions Taken/To Be Taken: 354~5 w/ 4 '- Et F44(C6Et?

Work Stoppage Notifcation (Form OCK 2A) Wntten O Yes )d' No; Serial No.

Informaton Sources / References (Work Requests, Document Violated, etc ): 19d2 - f Ong nated By: M5v 1._.Oh7_k+tn_% Date:

7-/ - 8F Dept./ Group /Secton ///Marre@.

II. Compliance Evaluation Item / System Operable GrYes O No Item Reportable Gries O No Reportable Pursuant To: O 50.73 Section pd 24.S. Secton V '/, M $~

n, O Part 21 O Lic. Con. [ec M / M 7/I-!Jr O 50 72 Secton O Other Evaluated By/Date-v7 Comments: _.3 edal _[ep d pepml lptLuJ _JdAMf ding po.LI m t.Artesar.y.

i f

• d4 Ill. Telecon/ ENS Report to NRC Time /Date:

NRC Contactee(s): _._

OPC Contactor(s):

Telegraph /Ma1' gram /Facsimde Transmissen to NRC Date:

Date Notif ed NRC Res inspector Stat:en Manager General of fice Comments:

IV. Investigaton Report Assigned To; A!((- ddLs bn NRC Repo,rt Due Date:l$04[$yd4~tkSEJ"J"

+

Date Due to Comphance af ter Evaluatt di.6A y t_,bh.Ctey /c/a-PIR Review (Comphance).

Ad Date:

PIR Staten Manager Approval A/

bW /dI k.7 //g Date:

V. Further Acton/Evaluatep Required O Yes Yr"flo (Expla n Below):

Page 2 Assigned To:N/A Comments: JdL2SG14.et/__/c'/c-l_Ja6#t0/

/c_.lha.4 sl M_6' 6._/JLnyb 7

y Comphance Rev,ew [k Date

_L M_ _ OA ReviewY Wdhe Date 7/Ull~

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DUKE POWER COMPANY GENERAL OFFICES

'""""h8,,","'

^ * ' " ' "

3 3 432 80Uf M CHURCM Sittti CIIARLOTTE. N. C. 2824P.

June 26, 1988 W. D. Purdue Manager Steam Generator field Services Babcock & Wilcox 3110 Odd Fellows Road Lynchburg, VA. 24501

Subject:

McGuire Nuclear Station Unit 2 "A" Steam Generator Tubes Plugged June 1988 EOC-4 Refueling Outage MC-208.21

Dear Sir,

Attached is a list of fody led mechanical plugs.two (37.)wmtubes to be service by plugging with rol These tubes are being plugged for indications exceeding the plugging limit or at the option of Duke Power Company.

If there are any questions or coments please call me at (704)373-4211.

J l

Sincerely,

0. B. Mayes Nuclear Production Engineer Nuclear Production Department OBM:cee cc:

T. L. McConnell G. W. Hallman S. E. LeRoy W. M. Sample C. W. Hendrix, Jr.

T. M. Hilderbrand R. W. Rider C. F. Robinson C. B. Cheezem j

A. M. McClenny D. R. Xeck J. C. Drive,'

1 L. M. Thompson W. A. Haller G.W.Bryant(B&W) 1 J. W. Boyle R. W. Eaker F

8. Mahaffey (B&W)

M. D. Kimray.

John Pring M. J. Ghallagher (B&W) i t

1 f/( t-A99 "C/ST

• • • • • • DUKE TUBAN(TM) (VER.

3. 0) ****** Tuccday Juno 28, 1988 11:38 PM

• Plant: McGUIRE UNIT 2 Steam Generator: A Order: Sort by ROW, COL

Title:

TUBES TO BE PLUGGED - 06/88 RFO No.

RO.(

CO L g

Cold le.3 ou / mm 1:,-

1; J

,, p ll';J i

U-

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3-i-< l l

.4 t.

\\~

l

(._

lo,

l O

4-4

. s

_p.

.o.

(,

)

h TOTAL TUBES FOUND =

42 j'

i J

4 I

i

.i 4

i i

f;O

\\

J 1

1 1

1

ftk 2?k$"O65 DUKE POWER COMPANY p.o. eon :: ice GENERAL OFFICES s'[s$

O 4

sovin enumen stesst CIIARLOTTE. N. C. 28242 June 26, 1988 W. D. Purdue, Manager Steam Generator Field Services Babcock & Wilcox 3110 Odd Fellows Road Lynchburg, VA. 24501

Subject:

McGuire Nuclear Station Unit 2 "B" Steam Generator Tubes Plugged June 1988 EOC-4 Refueling Outage MC-208.21

Dear Sir,

O Attached is a list of he+y - Foe (.34) s bes to be removed from tu service by plugging with rolled rechanical plugs.

These tubes are being plugged for indications exceeding the plugging licit or at the option of Duke Power Company.

If there are any questions or coments please call me at (704)373-4211.

i Sincerely,

%8 O. 8. Mayes Nuclear Production Engineer Nuclear Production Department i

OBM:cee 1

cc:

T. L. McConnell G. W. Hallman S. E. LeRoy W. M. Sample C. W. Hendrix, Jr.

T. M. Hilderbrand R. W. Rider C. F. Robinson C. B. Cheezem O

A. M. McClenny D. R. Keck J.'9, M MD @

L. M. Thompson W. A. Haller G.W.Bryant(B&W)

J. W. Boyle R. W. Eaker F. B. Mahaffey M. O. Kimray John Pring M. J. Ghallagher(81W)(B&W) 1

fik 2 ~ N ok ~ lSS 000000 DUKE TUBAN(TM) (VER. 3.0)**0000 SundCy Jun3 26, 1988 10:S6 PM

• Plant: McGUIRE UNIT 2 Steam Generator: B O

Order: Sort by ROW, COL

Title:

TUBES PLUGGED - 06/88 RFO NO.

ROW COL 1.

6-35 2.

7-57 3.

9-13 4.

10-5 i

5.

11-5 6.

11-55 7.

13-42 8.

15-25 l

9.

16-21 l

10.

17-43 j

11.

20-63 12, 20-84 13.

24-21 14.

26-19 15.

26-77 16.

28-73 17.31-100 18.

32-92 19.

34-23 0

20.

34-92 21.

34-93 22.

35-50 l

23.

36-15 24.

36-54 25.

37-40 26.

39-32 l

27.

41-37 28.

41-93 29.

42-21 30.

42-81 i

31.

43-25 12.

43-44 33.

48-34 34.

48-70 l

1 TOTAL TUBES FOUND =

34 i

l

h ffk 2'MTh Q(55~

DUKE POWER COMPANY l

P.o. son ss'k' OENERAL OFFICES

" "'s'r's.d!!

432 80 Win CMURCN St At tf CHARLOTTE. N. C. 28242 June 28, 1988 W. D. Purdue, Manager Steam Generator Field Services Babcock & Wilcox 3110 Odd Fellows Road Lynchburg, VA.

24501

Subject:

McGuire Nuclear Station Unit 2 "B" Steam Generator Tubes Plugged June 1988 E00-4 Refueling Outage k.C-208.21 Dear Sir.

O In addition to the thirty-four (34) tubes plugged by letter dated June 26, 1988, tube 25-66 should be removed from service by plugging with rolled mechanical plugs.

These tubes are being plugged for indications exceeding the plugging limit or at the option of Duke Power Comptny.

If there are any questions or coments please call me at (704) 373-4211.

Sincerely, BBm%g D. 8. Mayes Nuclear Production Engineer Nuclear Maintenance i

Nuclear Produs' ion D'n:.rtment DBM:cee cc:

T. L. McConnell G. W. Hallman S. E. LeRoy W. M. Sample C. W. Hendrix, Jr.

T. M. Hilderbrand R. W. Rider C. F. Robinson C. B. Cheezem A. M. McClenny D. R. Keck J. C. Driver L. M. Thompson W. A. Haller i

G.W.Bryant(B&W))

J. W. Boyle R. W. Eaker t

F. 8. Mahaffey (B&W M. D. Kieray John Pring M. J. Ghallagher (B&W) 4 i

ft 2 2 - ALTE-6tSS Ce DUKE POWER COMPANY

p. a s o n a s u s OENERAL OFFICES 8'"l3,j

8" 3

428 Souf M CMURCN Sf ttti CHARLO'ITE. N. C. 28242 June 30, 1988 W. D. Purdue Manager Steam C4nerator Field Services Babcock & Wilcox 3110 Odd Fellows Road Lynchburg, VA. 24501

Subject:

McGuire Nuclear Station Unit 2 "C" Steam Generator Tubes Plugged June 1988 EOC-4 Refueling Outage MC-208.21

Dear Sir,

Attached is a list of sixty Thets h,du s to be removed from service by olugging with rolled mechanical plugs.

These tubes are being plugged for indications exceeding the plugging limit or at the option of Duke Power Company.

If there are any questions or coninents please call me at (704) 373-4211.

Sincerely, b

O. B. Mayes Nuclear Production Engineer i

Nuclear Maintenance Nuclear Production Department DBM:cee

.cc:

T. L. McConnell G. W. Hallman S. E. LeRoy W. M. Sample C. W. Hendrix, Jr.

T. M. Hilderbrand R. W. Rider C. F. Robinson C. 8. Cheezem O

^ a acci ##x o a x ck a c or+

L. M. Thompson W. A. Haller G. W. Bryant (B&W)

J. W. Boyle R. W. Eaker F. B. Mahaffey (B&W) i M. D. Kimray John Pring M. J. Ghallagher (B&W) j l

-m--

--.s-

,--y

-,r--

V(f( 2.-/4$ s ~ O IS S j

i C$*****

DUKE TUBAN(TM) (VER. 3.0)o0000* Thurcday Jun3 30, 1988 05:32 P Plant: McGUIRE UNIT 2 Steam Generator: C Order: Sort by ROW, COL

Title:

6/88 RF0 IUBES PLUGGED NO.

ROW COL No.

ROW COL

~~~~5I

~~5

~65 C 6 fd Le3 o

~~~55 23-507 0

2.

1-66 CefdLe on y 52.

24-91 3.

1-67 Cefd Le og 53.25-107 4.

1-68 c.ta out 54.27-106 5.

1-69 Ceit ont 55.28-105 6.

1-70 C. ( L La ou 56, 29-77 7.

1-71 C.f4 c=y 57.

31-9 t3 8.

1-72 CJli La C ub 58.

34-81 i

73 b6e ld La da 59.

38-92 9.

1-Ld La OdlN 60.

39-53 74 10.

1-11.

1-75 Cs (d La O N y twn 61.

44-70 12.

2-5 62.

44-80 13.

2-89 63.

48-54 14.

4-97 15.

5-34 16.

5-66 17.

5-82 18.

6-38 l

19.

7-59 l

20.

8-5 21, 8-15 22.

8-94 23.

8-99 24.

8-112 25.

9-113 26.

11-43 27.

11-90 t

28.

11-99 29.

12-58 1

O 30.

12-70 31.

12-71 32.

13-69 33.

13-70 34.

13-78 35.13-100 1

36.13-112 37.

14-51 38.

14-98 i

39.

15-99 40.15-111 41.

16-97 42.

17-35 43.

18-83 44.

18-94 45.

18-95 46.18-104 47.

19-34 48.

19-70 49.

20-77 50.

21-78 TOTAL TUBES FOUND =

63 l

\\

lC:)

1

f(('2*N$$~0LS~}~

DUKE POWER COMPANY GENERAL OFFICES

" " ' " * " ' I t 3.'4 '!!

p. o. s o n a s i e e sa: soutn enumen stesst CHARLOTTE. N. C. 28242 June 30, 1988 W. D. Purdue, Manager Steam Generator Field Services Babcock & Wilcox 3110 Odd Fellows Road Lynchburg, VA. 24501

Subject:

McGuire Nuclear Station Unit 2 "0" Steam Generator Tubes Plugged June 1988 EOC-4 Refueling Outage MC-208.21

Dear Sir,

Attached is a list of thirty-seven (37) tubes to be removed from tarvice by plugging with rolled mechanical plugs.

These tubes are being plugged for indications exceeding the plugging limit or at the option of Duke P'wer Company.

If there are any questions or connents please call me at (704) 373-4211.

Sincerely.

D. B. Mayes

)

Nuclear Production Engineer Nuclear Maintenance Nuclear Production Departa nt i

OBM:cet.

l cc:

T. L. McConnell G. W. Hallman S. E. LeRoy W. M. Sample C. W. Hendrix, Jr.

T. M. Hilderbrand O

R. W. Rider C. F. Robinson C. 8. Cheezem

^ a acci a"r o a x c' a c oriv r L. M. Thon9 son W. A. HaIIer G. W. Bryant (B&W)

]

J. W. Boyle R. W. Eaker F. B. MAhaffey (84W)

M. D. Kimray John Pring M.J.Ghallagher(B&W) 1 0

2. 'M $$ ~ O !.'f ocococo DUKE TUBAN(TM) (VER. 3.0)600000 Thursday June 30, 1988 12:22 P Plant McGUIRE UNIT 2 Steam Generator: D Order: Sort by ROW, COL

Title:

TUBES PLUGGED 6/88 RFO NO.

ROW COL

~~~~5~

~~[

~~9 Ho f La Ca ly 2.

1-10 Hei Lt o ulu 3.

1-16 He k 0410 4.

1-20 Ho Ls o 0lr 5.

1-21 He o*>r 6.

1-22 Ho ow b 7.

1-24 de C#84 8.

1-25 No La 04h a:

1:

!? s.+u wr 11.

1-30 64et 6 Oub ge.t La CW /lf

].

1-31 1,:

3; s4 wy a,m.

k3 15.

3-16.

4-41 17.

4-94 18.

5-101 19.

5-111 20.

6-70 21.

8-36 22.

8-64 23.

9-35 24.

9-61 25.

9-63 26.

10-60 27.

10-64 28.

"0-80 O

29.

12-52 30.

12-79 l

31.

13-37 32.

13-84 33.

14

• 82 34.

19-85 35.

20-96 36.

24-92 37.

37-39 TOTAL TUBES FOUND =

37 I

i l

O

,e e

i 10.0 Reference Documents The following referer:ce doucment applies to the inservice inspection performed during Outage 4 at McGui-e 2:

Request for Relief MNS-001 O

i i

f

O I

l Rev. O C/6550053 Page 1 September 16, 1988

Serial No, MNS-001 Page 1 of 2 Duke Power Company Request for Relief from Inservice Inspection Requirement Station: McGuire Unit: 2 Reference Code: 1980 ASME Section XI, including addenda through Win ~er 1980 c

I.

Component for which exemption is requested:

a.

Name and Identification Number:

Safety Injection Accumulator Tanks 2A,28,2C,20.

System: NI Safety Injection System b.

Function: The four accumulator tanks contain dilute boric acid with a pressurized non-reactive cover gas (nitrogen) over it. Contents of the tanks are used to flood the core following Reactor Coolant System depressurization as a result of LOCA.

pg c.

ASME Section III Code Class U/

Equivalent Class 2 d.

Valve Category:

N/A II.

Re ference Code Requirement that has been determined to be l

impractical:

ASME Boiler and Pressure Vessel Code Section XI, 1980 Edition, including 1980 Winter Addenda, article IWC-2500-1, items C01.010.051. The code requires the inspection of one 1**

Shell to Upper Head and ona Shell to Lower Head to complete the equivalent of one vessel.

III. Dasis for Requesting Relief:

The Safety Injection Accumulator Tanks 2A,28,2C,20 are i

manufactured by Westinghouse. The tanks are designed in such a way that the welds (Shell to Lower Head) are inaccessible to prepare for ultrasonic examination, due to support-skirt interferonce.

]

g Page 2 of 2 i

IV.

Alternate Examination The Safety Injection Accumulator Tank Shell to Upper Head has the same geometric design and thickness as the Shell to Lower Head.

Because of the simularties between welds, we will inspect an additional Shell to Upper Head weld. The results of this inspection should be indicative of what conditions exist in the inaccessible areas. See attachment sheet 1 r

Dwg. MCM 1201.04.0036-001.

V.

Implementation Schedule This inspection will be performed during the current (4th) i refueling outage. These inspections will be completed during j

the month of June, 1988.

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11.0 Classes 1 and 2 Repairs and Replacements As required by ASME Section XI,1980 Edition, a record of the Classes 1 and 2 Repairs and Replacements for work performed from July 3, 1987 to July 24, 1988 is provided and is included in this section of the report.

The individual work request documents are on file at the McGuire Nuclear Station.

D v

l l

J l

I Rev. O i

C/6550053 Page 1 i

September 16, 1988

- __=

PAqt1 et _An t1 1-meGyI*E NUCLLAn_UAIKN_ggtul a

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