Text

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)
	v • d • e

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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. ,

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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.

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l 0010170059 PDR ADOCK O 00M370 pg l

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' FORM NIS.1 (back) i s, e - - g .coe 7-?-R7 to 7-24-RR 9. Inspecooe laterval fue 3- 1-R4 to 3- 1-9 4

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 a cahan. See Mtached report.

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.

Daes % 19 N 1 ped

$ Duka Pnwava ennna n yty rh _'

M owner 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 l 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 l has performed -uur6<he and takes comstm tooemarse desertbed la this Owners' Data Report in accordance l 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.

Dame ~~ 3 b 19

[, co====oes AM'77'28 N' b

<i % ysi,saanee risaanes soere(stm, Petmace sad No.

The Hartford Steam Boiler Inspection & Insurance Company 1117 Perimeter Center W.

Suite E-301 Atlanta, GW 30338 9

INSERVICE INSPECTION REPORT r

\ UNIT 2 MCGUIRE 1988 REFUELING OUTAGE 4 Location: Hwy 73, COWANS FORD, NORTH CAROLINA NATIONAL BOARD .

COMMERCIAL SERVICE DATE: MARCH 1, 1984 Owner: Duke Power Company 422 S. Church St.

Charlotte, N. C. 28242 Revision 0 O

Prepared By: Y 27 4 , :b. Date h-- / -((

Reviewed By: . n. m Date k-ff-[

Approved By: h) Date YfN!f[

Copy No.

h 5

7 [ ,

Assigned To NRC DOCUMENT CONTROL ,

Controlled X Uncontrolled O

C/6550053 i

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CONTROLLED DISTRIBUTION O Copy No. Assigned To I

Original J. O. Barbour j 1 i C. B. Cheezem 2 R. P. Ruth (McGuire) f 3 T. E. Smith (B&W I

Lynchburg) !

4 R L Gill (To Licensing ;

File) ,

5 NRC Document Control l

UNCONTROLLED DISTRIBUTION 6, 7 R L Gill

~

(To Licensing)

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O 1 C/6550053 L

4 TABLE OF CONTENTS O Section

, Title Revision i

1. Summary of Inservice Inspection 0

2. Status of Required Inspections 0 t l

3. Final Inservice Inspection Plan for Outage 4 0

4. Results of Inspections Performed During Outage 4 0

5. Class 1 Inspection Results 0

6. Class 2 Inspection Results 0

7. Augmented Inspection Results n 1

8. Personnel, Equipment, and Material Certifications 0

9. Problem Investigation Reports 0

10. Reference Documents 0 i

11. Classes 1 and 2 Repairs and Replacements 0 0

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O C/6550053 I

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1. 0 Summary of Inservice Inspection This report describes the Inservice Inspection of Duke Power Company's McGuire Nuclear Station Unit 2 during the 1988 Refueling Outage (also referred to as Outage 4).

Included in this report are the final inservice inspection pl tn, the inspection results for each item, a summary for each category of exanii-nation and correction action taken when oacceptable conditions were found. In addition, there is a section included for repairs and replace-ments required since July 2, 1987.

1.1 Class 1 Inspection The Class 1 Inspection included examinations on the Pressurizer (Westing-house), Pressurizer Safety Nozzle to Upper Head Welds, CRDM Tubes to Reactor Vessel Upper Head, Incore Instrument Tubes to Reactor Vessel Lower Head and Pressurizer Heater Penetration Welds in Lower Head. In addition, the Class 1 Inspection included examinations on Pressurizer Relief Nozzle Safe-End and Pressurizer Safety Nozzle Safe-End. Also included were examinations on Reactor Coolant Pump 2A Main Flange Bolts, Steam Generator 2B Manway Bolting, Piping Bolting, Reactor Coolant Pump 28 Seal Gland Housing Bolting and valve bolting. Examinations were also performed on circumferential butt welds on Reactor Coolant (NC) and Safety Injection (NI) Systems. Examinations were also performed on socket welds on the Chemical and Volume Control System and the accessi-ble areas of the Reactor Vessel Interior Surface.

Visual examinations were performed on the Class 1 Pressure Boundary during inservice leakage tests. Also, visual examinations were performed on the Class 1 Component Supports of the Reactor Coolant (NC), Safety ;

Injection (HI), and Chemical and Volume Control (NV) Systems.

The Inconel 600 Tubing in Steam Generators 2A, 28, 2C and 20 was in- l spected by eddy current during Outage 4. The results of the inspections !

are shown in Section 5 of this report. ;

Reportable indications were found on the Class 1 Inspections shown on '

the following pages. Inspection and evaluation data for each reportable indication of or condition found on Class 1 Items is included in Section 5 this report.

A detailed description of each inspection is found in the final Inservice Inspection Plan in Section 3 of this report. Results of each examination are found in Section 4.

1. 2 Class 2 Inspection The Class 2 Inspection included examinations on ther Safety Injection Accumulator Tank 20 Shell-to-Upper Head Weld, circumferential butt welds in piping of the Auxiliary Feedwater (CA), Main Feedwater (CF), Component Cooling (KC), Residual Heat Removal (ND), Safety Injection (NI), Main i

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

Steam (SM), Main Steam Vent to Atmosphere (SV), and Containment Air Release and Addition (VQ) Systems. Also included in the Class 2 Inspec-l C- tion were longitudinal butt welds in piping of the Residual Heat Removal (ND) and Containment Air Release and Addition (VQ) Systems.

, Visual examinations were performed on Class 2 Component Supports of Auxiliary Feedwater (CA), Containment Air Palme la.d Addition (VQ), Main Feedwater (CF), Residual Heat Removal (ND), dafety Injection (NI), and Main Steam (SM) Systems.

i Reportable indications were found on the Class 2 Inspections shown on the following pages. Inspection and evaluation data for each reportable indication or condition found on Class 2 Items is included in Section 6 of this report.

A detailed description of each inspection is found in the final Inser-vice Int.pection Plan in Section 3 of this report. Results of each examination are found in Section 4.

1. 3 Augmented Inspections '

l Augmented inspections were performed on Reactor Coolant Pumps 2B and 2C Flywheels, Pipe Rupture Protection and Steam Generator Feedwater Modifi-cation. A detailed description of each examination is found in the final Inservice Inspection Plan in Section 3 of this report. Results are found in Section 4.

O 1. 4 ^1ter"ete exemimetiome No alternate examinations were performed during Outuge 4.

1.5 Identificat.on Numbers Owner: Duke Power Company, 422 S. Church St., Charlotte, NC 28242 Plant: McGuire Nuclear Station, Highway 73, Cowans Ford, NC 28216 Plant Unit: 2

.' Owner Certificate of Authorization: N/A Commercial Service Date: 3-1-84 Manufacturer State or National :

Manufacturer or Installer Province Board I

Item or Installer Serial No. No. No.

Reactor Vessel Rotterdam 30664 NC-201819 --

, Pressurizer Westinghouse 1491 NC-201818 W10285 l

Steam Generator 2A Westinghouse 1481 NC-201307 68-112 4

1 Steam Generator 28 Westinghouse 1482 NC-201308 68-113 l 1

Steam Generator 2C Westinghouse 1483 NC-201309 68-114 O

1 Rev. O Page 2 I C/6550053 September 16, 1988 )

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Manufacturer State or National i O Item Manufacturer or Installer or Installer Serial No.

Province No.

Doard No.

,' Steam Generator 20 Westinghouse 1484 NC-201310 68-115 Auxiliary Steam System Duke Power Co. AS N/A 62 Containment Air Release

, and Addition System Duke Power Co. VQ N/A 56 Main Steam Syr, tem Duke Power Co. SM N/A 70 Main Steam Vent to Atmosphere System Duke Power Co. SV N/A 67 Reactor Coolant System Duke Power Co. NC N/A 82 Liquid Waste Recycle System Duke Power Co. WL N/A 76 Refueling dater System Duke Power Co. FW N/A 54 Auxiliary Feedwater 5 System Duke Power Co. CA N/A 73 Residual Heat Removal O sv tem o#ke eo er co- "o "/^ 83 i

Nuclear Service Water System Duke Power Co. RN N/A 60 ;

Chemical and Volume !

Control System Duke Power Co. NV N/A 80 Component Cooling

System Duke Power Co. KC N/A 78 i Main Feedwater System Duke Power Co. CF N/A 61 !

i Containment Spray System Duke Power Co. NS N/A 69

(

Containment Ventilation Cooling Water System Duke Power Co. RV N/A 72 Safety Injection System Duke Power Co. NI N/A 83 l

! Safety Injection Delta j Accumulator Tank 2A Southern Co. 41618-72-1 NC-201813 3034 l Safety Injection Delta !

t Accumulator Tank 28 Southern Co. 4161872-1 NC-201814 3035

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C/6550053 September 16, 1988 ,.

Manufacturer State or National

(s Manufacturer or Installer Province Board

's I Item or Installer Serial No. No. No.

Safety Injection Delta Accumulator Tank 2C Southern Co. 41618-72-3 NC-201815 3036 Safety Injection Delta Accumulator Tank 20 Southern Co. 41618-72-4 NC-201816 3037 Unit 2 Ouke Power Co. N/A N/A 84 0

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Rev. O Page 4 C/6550053 September 16, 1988

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P90 GRAMS NTOIR176-GAISIO2 DLKE PCHER CD1PANY PAGE 1 FILE: CLS TI55 QUALITY ASSURANCE DEPARTNENT DATE 09/22/83 PLANT: MCGUIRE L2dIT 2 PRE-TARVICE AND I;4-SERVICE IFEPECTIG4 SYSTC".

KEY: ITEM M.fBER B0T PCCUIRE 2 CLASS 1 REPORTABLE ITLIC CUTAGE 4 INSP PROC. MATERIAL DIAM./ CALIS ITEM M.FSER ID. M7SER DRAMING RPEERS LG3. REQ. M.tsERS TYPE / GRADE THICK BLOCK COT 1ENTS samassamassa suusasssssssssssssas assassammassmazzassa masas assa assanssa samassassa maassa massa aussmassammassamassammas=sazza 807.050.002 2NC53-FL2 NCFI-2NC-53 VT1 QCL-13 SS _._

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i Pmaat: MISImme-EMISIO DUKE PCDER COMPA*dY PAGE 2 FILE: COO 7133 QUALITY ASSURANCE DEPARTMENT DATE 09/22/88 PLANT MCEUIRE tsdIT 2 P9E-SERVICE Ape IN ";ERVICE INSPECTIt24 SYSTEM REYs ITEM f*TSER 516 MCEUIRE 2 CLASS 1 REPORTA8tE ITEPC OUTAGE 4 IPCP PST. MATERIAL DIAM./ CALIS

< ITEM DRDSER 10. N!DGER DRANING MASER 3 LOCS. REQ. NUteERS TYPE / GRADE THICK BLOCK CGTENTS 7 messs=====ss ==================== ==================== ===== ==== maamassa assass==== ====== ===== mammassass===ss=======sammassa a

C14.C21.001 2"r.a-TURES MCM-2201.01.187 ET ISI-424 IN 00.75 50285 00.043 3%DINAGE 1 PIR 2-4988-0155 25 m -times MCM-2201.01.187 ET ISI-424 IN 00.75 50285

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00.043 3%t2JTAGE 1 PIR 2-9184-0155 I

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, 2. 0 Status of Required Inspections The completion status of inspections required by the 1980 ASME Code !

' Section XI, including addenda through Winter 1980, is summarized in this l section. The requirements are listed by the ASME Section XI examination

, category as defined in Table IWB-2500-1 for Class 1 inspections and in IWC-2500-1 for Class 2 inspections. Augmented inspections are also ;

included. t Class 1 Inspections '

Section XI Inspections Inspections Percentage l Category Description Deferral Required Completed Complete _d Allowed !

B-A Pressure Retaining 15 Welds 4 Welds 26.67% Yes i,

) Welds in Reactor Vessel t h

B-B Pressure Retaining 8 Welds 3 Welds 37.50% No Welds in Vessels l L

Other than Reactor Vessel l i

B-0 Full Penetration 36 Inspections 18 Inspections 50% Partial l Welds of Nozzles in Vessels l O B-E Pressure Retaining 55 Welds 55 Welds 67% No l

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Partial Penetration Credited !

Welds in Vessels '

B-F Pressure Retaining 46 Welds 25.5 Welds 55.43% No Dissimliar Metal Welds l J

l B-G-1 Pressure Retaining 370 Items 211 Items 57.02% Yes l

, Bolting Greater than 2 Inch

, Diameter !

~

l B-G-2 Pressure Retaining 65 Connections 38 Connections 58.46% No

, Bolting 2 Inches and j Less in Diameter 1

j B-H Integral Attachment 12 Attachments 6.33 Attachments 52.75% No

{ for Vessels B-J Pressure Retaining 258 Welds 127 Welds 49.22% No Welds in Piping

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Page 1 C/6550053 September 16, 1988 l

.I Class 1 Inspections (continued)

Section

XI Inspections Inspections Percentage Deferral !

i* Category Description Required Completed Completed Allowed i I

B-K-1 Integral Attachments None N/A N/A

[

N/A ;

for Piping, Pumps ;

and Valves

{ l

' B- L- 1 Pressure Retaining None N/A N/A N/A Welds in Pump Casings l

B-L-2 Pump Casings None N/A N/A N/A

) B-H-1 Pressure Retaining None N/A N/A N/A l Welds in Valve Bodies v B-H-2 Valve Body > 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 aeector ve' e'>

i 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 ;

a Welds in Control Rod !

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

), Components Yes (

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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

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! C/6550053 September 16, 1988 a

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

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C/6550053 September 16, 1988 l

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

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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 10 Number = Unique Identification Number !

Orawing Number = Location and/or Detail Drawing i

Locs. = Location 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 !

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Calib. Block = Calibration Block Comments = General and/or Detail Description l

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

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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 l

Geo. Ref. = Geometric Reflector

! N = No '

Y = Yes

Comments = General and/or Detail Description 1

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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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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 _ _

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FILE: C007133 QUALITY AO'XJRANCE DEPARTMENT DATE 09/27/88 PLANT: MCGtJIRE EMIT 2 PRE-SERVICE AND IN-SERVICE INSPECTImi SYSTEM

,, KEY:

i IT*M MAeER 807 PK3UIRE 2 INSERVICE INSPECTIG4 RESULTS MJTAGE 4 INSPECTIW4 ItGPECTION INSPECTION GES.

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

< KEY: ITEN 84ASER 809 #CGUIRE 2 ItCERVICE INSPECTICH RESULTS OUTAGE 4 INSPECTION ItCPECTION INSPECTION GES.

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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 _

N 1

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

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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 l

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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 _

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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 C15.064.001 2APC-2A 07/24/86 CLR _ N I

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ITEM 848eER ISDE#eEE SATE STATUS LIftITED REF. Ct99ENTS usassass==== maasssssssssas==sans ==== sass == ========== sus === sass asas ======sassass====sessass===ssa SIS.he 882 2mPC-28 eT/24/88 CLR _ N SI5.he.905 2APC-2C 47/24/88 CLR _ N 815.060.0h 2APC-29 8T/24/88 CLR _ N i

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ITEM MDSER IDI42SER DATE STAIUS LIMITED REF. CGTENTS masssssmasas massomassamassamassa assamassas assassassa massssassa ==== massass===ssassammassamassassa C05.011.004 2CA2FWe4-1 06/04/88 CLR _ N C05.011.005 2CA2T 6*.4 -5 06/04/88 CLR _

N C05.011.006 2CA2f h -18 06/04/88 CLR _ N C05.011.055 2CF29 Wee-1 06/04/88 CLR _ N C05.011.056 2CF2f66,6-8 06/10/88 CLR _ N C05.011.150 2KC2F-2762 06/14/88 CLR _

N C05.011.200 D e2F-24 05/18/88 CLR _ N C05.011.201 2te2F-261 05/18/88 CLR _ N C05.011.207 2te2F-48 05/18/88 CLR _ N C05.011.211 ac2F-50 05/18/88 CLR _ N C05.011.212 2te2F-54 05/24/88 CLR _ N C05.011.213 D e2F-60 05/18/88 CLR _ N C05.011.214 2te2F-61 05/18/86 CLR _ N C05.011.215 DQ2F-65 05/18/88 CLR _

N C05.011.216 D e2F-64 05/18/88 CLR _ N C05.011.217 D e2F-68 05/24/88 CLR _ N C05.011.218 2Pe2F-74 05/24/88 CLR _

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N C05.012.205 2Fe2F-79L 05/24/88 CLR _

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N C05. 021.068 2CF2FN16-12 06/23/88 CLR _

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N F1.01.417 240CR-M1-4745 06/20/88 CLR _ N F1.01.418 2-NCR-N1-4766 96/2fr88 CLR _ N F1.01.606 24tCR-#W-4459 06/18/88 REC _ N _

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1 i F1.01.615 2-MCR-9W-4098 06/18/88 CLR _

N i

F1.01.640 24tCR40V-4401 06/20/88 CJt _ N F1.02.017 2440R-CA-165 06/20/88 CLR _ N F 7.. C.!. 818 2-MCA-CA-046 06/10/88 CLR _ N f

j F1.02.019 2-fCA-CA-055 96/10/se CLR _ M i

F1.02.020 2-ftCA-CA-056 96/10/86 CLR _ N i

! F1.02.021 24eCA-CA-057 06/10/88 CLR _ N 1

I j F1.02.022 2-MCA-CA-058 06/10/06 CLR _ N i

F1.02.023 2-ftCA-CA-059 06/10/88 CLR _ N i

j F1.02.024 24EA-CA-060 06/10/86 CLR _ N F1.02.025 2-MCA-CA-062 06/10/8fs CLR _ N 1

l F1.02.026 2-fEA-CA-061 06/10/88 CLR _ N 1 F1.02.027 24tCA-CA-077 06/10/88 REC _ N d

4 i

i i

i

= .-

PNa80s MISI8485-44tSIM SLFE PtBER CtwaNr PAGE 26 FILE: COOT 155 GUAllyy ae. amANCE MPART9ENT SAIE 99/2T/SS '

PLANf3 MCET.flRE 4381T 2 N *lWVICE AfD IN-SERVICE INSPECTItB6 SYSTEM KEY: ITEM 888S(R F1. 9EERJ1.eE 2 INSERVICE INSPECTIt96 RESULTS (RffAGE 4 INSPECT 1tDi INSPECT 1tDe 19CPECTItB8 GEff.

ITEM 8ASSER 138889ER DATE STATUS LIMITED RE F. CtBWENTS essssssseses ausssssssssssssssssa seassesses ausssssssa aussssssse esas aussssssssssssssssssssssssssa.

F1.92.02S 2-MCR-CA-967 96/29/88 CLR _

N F1.62.829 2-9ER-CA-h 9 96/29/88 CLR _

N F1.02.050 2-MCR-CA-M 9 96/28/88 CLR _ 90 F1.02.951 2-fCR-CA-972 86/28/88 REC _

N F1.02.161 2-MCR-W-4559 96/27/88 CLR _

N F1.02.162 2-MCR-W4551 96/2F/88 CLE _

N F1.02.165 2-MCR-W-4552 96/29/88 CLR _

N F1.82.164 2-#CR-W-4555 96/17/88 CLR _

N F1.92.165 , 2-fER-W-4554 96/1T/98 CLR _

N F1.92.1% 2-MCR-V44555 96/1F/88 REC _ N F1.02.167 2-fECR- W -4994 06/27/88 CLR _ N F1.02.168 2-#ER-V94591 96/29/88 CLR _ N F1.02.169 2-fECR-ve-4592 97/13/88 REC _ N F1.02.170 2-feCR-ve 4 59% e6/27/SS CLR _ N '

F .02.211 2-MCA-CF-112 96/07/88 CLR _ N F1.92.212 2-MCA-CF-173 96/07/88 CLE _ N F1.92.213 2-MCA-CF-185 96/10/88 CLR _ t. ,

F1.02.214 2-MCA-CF-186 96/10/88 CLR _ N F1.92.215 2-MCA-CF-IST 96/19/88 CLR _ N _.

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FILE C007155 GUALITy neeaEIANCE OEFARipKNT PLANFs MCGUIRE (MIT 2 SATE 99/27/88 PmE-Sth1CE Afe IN-SERVICE INSPECTICBI SYSTEM KEY: ITEM 8&setR F1. PCGUIRE 2 IN'4RVICE 28CPECTION RESULTS SUTAGE 4 l

INSPECTIt98 If6PECTItst INSPECTItpf E S.

i ITEM # ANGER 10949eER OATE STATtG LIMITED REF. CfD9ENTS assesses ==== sessassenessassesses asemassess ========== =======s . ==== =====sses=====ssessanss=======

F1.02.487 2-fEA-96-5704 05/13/88 CLR _ N

{ F1.02.488 Z-MCA-te-5706 05/05/88 CLR _ N j F1.02.449 2-NCA-te-5802 95/05/a8 #EC _

N 1

F1.02.490 2-MCA-fe-5801 05/05/88 CLR _ M F1.02.625 2-MCR-MI-4522 06/21/88 CLR _

N i

l F1.02.626 2-MCR-NI-4524 86/21/96 CLR _

N F1.02.627 2-MCR-NI-4555 96/22/88 CLR _

N F1.02.628 2-9ER-N1-4536 06/22/88 CLR _

N l F1.02.629 2-fEA-NI-5201 05/05/58 NEC _

N

{ F1.02.650 2-MCA-MI-5205 95/05/88 REC _ N F1.02.943 2-MCA-29-147 06/07/88 CLR _ N F1.02.944 2-NCA *iM-344 96/10/88 CLR _ N l F1.02.945 2-teCA-29-149 06/07/88 CLR _ N F1.02.946 2-MCA-26-150 06/10/88 CLR _ N j F1.02.947 2-MCA *;M-152 06/10/88 CLF N i

3 F3.02.948 2-MCA-SM-155 06/11/88 CLR _ N F1.02.949 2-MCA-SM-164 06/10/88 CLR _

N F1.02.950 2-MCA-29-175 06/07/88 CLR _ N

F1.02.951 2-MCA-29-182 06/07/88 CLR N

)

I l

____._._.__m_ _ . _ _ _ _ _ _ _ -_ _______m.__________ _ _ _ _ . _ _ . _ _ . _ _ . _ . . _. _ _ _ _ . . - _.__ _ __ m_ ._ __ . _ m___ _

= .

I PetERAM: NISIMAG-4tAISIO6 DLRE PtBER CtWANY PAGE 29 FILE: C507133 GLAALITY a= *3mANCE DEPARTMENT SAIE 09/27/88 PLANT: MCQJIRE 1381T 2 PSE-SERVICE ADS IN-SERVICE INSPECTICD8 SYSTEM REYs ITEM paLSER F1. PEGUIRE 2 INSERVICE IEPECTItD8 RF.SULTS tR1TAGE 4 INSPECTIt98 INSPECTItSt INSPECTION GES.

ITEM tR#et9 IO fa#WER DAIE STAftEl LIMITED REF. Ct90ENTS seassenesses ==================== smasassess ========== samassmans asas ==============================

F1.02.952 2-teCA-SM-183 06/10/88 CLR , N 1 F1.02.953 2-MCA-39-196 06/10/88 CLR _ N e

l F1.03.058 2-teCA-CA-5517 05/17/88 CLR _

N l

j F1.03.059 2-MCA-CA-5518 05/17/88 CLR _

N I

F1.03.060 2-teCA-CA-5519 05/17/8G CLR _ N 4

l F1.03.061 2-teCA-CA-5520 05/17/88 CLR _

N I i~

F1.03.062 2-tetA-CA-5521 05/17/88 CLR _ M F1.03.063 *-MCA-CA-5522 05/17/88 CLR _ M I

! F1.03.064 2-MCA-CA-5523 06/27/88 CLR _

M F1.03.065 2-MCA-CA-5524 08/27/88 CLR _ N F1.03.066 2-MCA-CA-5527 05/13/8e REC _ N i

F1.03.067 2-PCA-CA-5529 05/18/88 CLR _ M 1

F1.03.068 2-teCA 4A-5530 05/18/8e Ctst _ N 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 4

rl.03.07+ 2-nCA-CA-5536- 05e16/88 Cta _ N 1

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I :T MENS OLAY SILE PFPR i lt 1I 1 illl

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.

j The accessible internal surfaces of the Reactor Vessel were visually inspected. No reportable conditions were found.

3.2 Pressurizer Pressurizer Upper Head to Shell Longitudinal Weld and two (2) Safety i

Nozzles to Upper Head Welds, including inside radiuses, received ultra-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.

5.4 Piping J

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 i corrected and declared acceptable. Refer to Problem Investigation Report i Number 2-M88-0147 found in Section 9 of this report. The inspection data ;

I sheets are included in this section of the report. One (1) additional 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

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. ;

i 5.6 Valves 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 1 - Run Full Length f; 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

on combination of Eddy-360 inspection and use of P* Cciculation. One (1) 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 l 4 20% through-wall (TW). Thirty-five (35) tubes were removed from service

{

based on combination of Eddy-360 inspection and use of P* Calculation, i Rev. 0 l 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

J based on combination of Eddy-360 inspection and use of P* Calculation, t Thirteen (13) additional tubes were unplugged then replugged, i 9

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

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 i

Repairs and replacements for work performed from July 3,1987 to July 24, 1988 are itemized 'n Section 11 of this report.

!O

)

1 I

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1

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Rev. O i Page 3 !

C/6550053 September 16, 1988 '

l l

l 26427 f A12 861 FORM QCL 13A REV.2 O' DUKE POWER COMPANY i

STATION Af f 6o Md UNIT 1 ISI VISUAL EXAMINATION, VT 1 1 (

INSPECTOR o72/3/ Page I of N LEVEL DATE: , PROCEDURE: REV THICKNESS:

VISUAL METHOD: Of CT R EP, OTE MATERIAL T YPE: -

VISUAL AIDS /M & TE SN:

SU RF ACE:

ftA)HL50N Y o .

g ID NUMBER:

O PSI

2 AlC 53- R2 $1SI -

treM NO E0xoso 002 ITEMS INSPECTED:

Y k Y (ff 6 /]Cloc.,t'e n cu rf)

IN IND CATl N N ypE LENGTH WIDTH REMARKS Ed M' . Escf1J T v <! PZT'TXHC 441 $C*0M U G l }fU 1 l' f*?~Tfp& 411Y=.W Afscel1, m pgyu .yp p p gjy.

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R ESULTS: O ACCEPTABLE guNACCEPTABLE, REQUIRES NDE/ EVALUATION OR REPAIR '

g g: WtG pttrJ s'fric' nt tilrpC And 198/ifMC Ce sua Me ! d6 MNL r o*J COMMENTS! DISPOSITION: fy r op ryg pa y, (4) /7) :

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ITEMS INSPECTEO:

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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 EXTENT TAFE

, ROW COL IND %.TW

.......... ... ... ... .. ..... VOLTS

... ... CHN DEG LOCATION ........ .

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 !

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... ...COL IND

... ... ...%TW

. ... YOLT.S CHN DEG LOCATION i.........

&W

&W 36W 45 47 9 32 ODI S1 WAR 28 59 ODI 21 1.33 M 2 21 1.19 M 1 113 22ND TSP-1.32 M2 0 167 TSP +

8 L7T TSP +

9.70 0.00 0.00 FL FL FL 2

S

,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 received a dye penetrant inch and less nominal wall thickness examination.

I A reportable indication was found l 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 See penetrant Problemand an ultra-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 N thickness received an ultrasonic and a dye penetrant examination. Two (2) circumferential welds greater than one-half inch nominal wall thick-l ness received an ultrason'c and a magnetic particle examination.

No 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.

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. 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 ua vd 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 NA ODirect Contact Amp Time MA Date #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

wn 6vseulj ] d ,'c o N esi 1e Movel, PT

, 0k f.).A % d

^

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 j N bl e. I W $- 3 D4 ,3 p,M, ComENTS: *

!O l a ACCEPTABLE IN0! CAT!cNs

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

2 EVALUATED BY:

M_ b h _

J DATE: // / 2.,/ P P 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

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l P!R SERIAL ho, j

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

0!$PO$1TICN BY: '4

,ua 4bmt.-A DATE: Ros~ GINk%S 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 *1, e i Me i w w vrtw %

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N m er length / Diameter Width Acceptable Reportable Indi t n Reference Documents '

p .f "$lviSD .3" . 0 /.S / rrt c AT-2 VO - C C/

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. 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 Urvts(s): A Unit Status At Tkne ProbiernOccurned/Disecwed: Es At s />'an Ch 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 '

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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 O Other Evaluated By/Date: pI //p #3e-4A/Xf ' '

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 I Comments:

I 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 //

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 I O Se le e,'a i T: 77. A, i RPf i A o dn es i L Be s t' I i i V Foal ' i Onginator i i ! i i j i l i i i i T

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I DURE POWER COMPANY PIR REVIEW REQUEST DATE: 4 /3 [ff REF. FIR: 2 W f8- O//O {

(COPY ATTACNED)

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THROUGN: C00T i!NATOR, PROJECT MANAGEMENT DIVISION t

I To: (To BE FILLED IN BY PMD) '

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DESIGN ENGINEERING DEPARTMENT

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$ DESIGN N GINEERING IS REQUESTED TO PROVIDE ASSISTAN W BELOW FOR THE ATTACHED PIR.

)

d g REPLY NEEDED SY:

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

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

N RESOLUTION COMPLETION VERIFICATION * '

l 5 (CORMCTIVE ACTION, ITEM VIII)

, ,[

CRITERION XVI (10CFR 50. APP 5) EVALUATION

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(* REQUEST ONLY AFTER STATION QA APPROVAL OF RESOLUTION) ,

! STATION CONTACT IS: Movte/h i f -

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! 5 DETERMINED BY DATE g (DESIGNATED INDIVIDUAL) j

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8 m y DATE:

THROUGN C00RDINATOR, PMD I 5 TO: , ATTNi

) } (GROUP MANAGER OR PLANT MANAGER)

FROM: TNE REQUESTED INFORMATION IS ENCLOSED i

7' COORDINATOR, PMD i

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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 Instrument "Ardo # C d SM / 00 Serial No, /3 Y2 A Scan f Metered or Digital Velocity Type Couplant h fd

~

Transducer Size _ . 246 Type M47 Serial No. AdV75f Frequency /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 .

.l . /o e " . too " . Jo o " .

p" 2 SKETCH OF ITEM INSPECTED Ref Documents A/M +'d*4 Rev 8

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R ev.

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Inspection Results - J4'H#c/ad efer Nf4**e / h $ (492/4/

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inspected Sy l- Level I SNT-TC-1A Date 8_.-/f*88 Disposition: cept O Reject Acceptance Standard Used A dSI d 3 A' /0 SA 3Q j By 2 I ,

M Level - A SNT-TC-1 A Date 8 '#* 80 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 Page 1 C/6550053 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 Page 1 C/6550053 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 Page 1 C/6550053 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 Station # 1 4"" Rep #^'

"</*f"aort Serial No. M N'- OII O investigation Repett No. (A

.o I. Problem Occurred. Time /Date: ._ Discovered Time /Date: 8 / ~88 A

tem: DerInn .T5E ins ec to'en of Weld ** a1 Vq 2f W-91' ba 3 UrJts(3): Unit Status At Time Probternoccurresf/ Discovered. ## w//de C# 4 Description of P t/r n Nsm F lndic< 'on we< fou nof thf_ exec &s' a'eee,0fance e %g Location ot Problem:

Method Used to identify Problem:

L/n.'t *2 NAux. Bldg.k./.

f reew 7to . Ram

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

s O t.0.72 Section O T.S. Section , n Uc. Part 21 O Other Evaluated By/Date:

e rse. 4 <j3 gM Comments:.lyk ML O < itt.lsesel of c M I* erd? 3 no ;y nd is .

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

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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; -

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

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l 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 -

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DUKE POWER CO PANY PROJECT N*

I I 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

e 3M 180 Serial No. /38/2 I A Scen Y Metered or Digl,tel Velocity Type Couplant ' k Transducer Size .Ese " Type My Serial No. 88F75f' Frequency /O MHZ Untresonic Thickness Scanning Technique Used: Soot # Continuous Reference Standard No. _55 -4 -

Designated oustification Points I"

Reference Standard Point Thicknees Points Sert Th i

1 2 3 4 1

. /o e " . 2ac " .300 '

.W" 3 SKETCH OF ITEM INSPECTED Ret Documents A/M Ve A Rw, . 8 Rw.

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COMPLETE FORM BY PRINTING WITH BL ACK BALL POINT PEN OR TYPE o DUKE POWER COMPANY V 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 ) .

_we 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 )

_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 b

. . _ ~

O 50.7? Section _ _. O T.S Section O Lic. Co . Section __. __ O Part 21 O Other. _ _. Evaluated By/Date _ ' ' p_ _Ma __ __7- SM Comments: __CmL d ered _. . Opecc@le.___ p M g I)augAM _

l11. Telecon/ ENS Report to NRC Time /Date: _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: _ _ _ _

l

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

Date Due to Comphance af ter Evaluation hit __ NRC Report Due Date: _._ _ _ _

PIR Review (Comphance) _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ . _ _ _ _ _ Date:

PIR Station Manager Approval _ _ _ . _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ . Date: ._ _

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

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

Comments: _ . . _ . _ _ - . _ _ _ . _ -_ -- .___.

Compiance Rev ew hat NS ate 7- N S T __ _ Q A Reme.v . _ 1 Date Distnbut on n DI'Ob .. . Ong nator _ p,.n G2 C I"i% i m k.O % [ b ,_(b ( (L lf_,5 n _ p{ goy _ /,_ /3 !%ort __.__ __ .

N'O % 4 ,

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_ Finali_,Oryginator _

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l Nrm 35367 @114D i PROBLEM INVESTIGATION REPORT Pace 2 Plfk No. W -- O l M l 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. nu+ s de s ee:be d bv th:s P r"R o .s Miss ;aa had b een ia 'nto c e i doria o o o ; +- onehal:na and were. n'alv r en o v ed o 'ud fo r f- l a n o_ $ r.sr a h i a lh o. ua:+ wos net n m o l< l-:so . Des:o a i i Ers9;a e e eta o eas:e w (MEME A C SPG) D C ' 4 k e. n: Hin s a4 d e s c e ,' b e d i

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Significant Corrective Action Evaluation Assigned To:

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FORM QCL 13A REV.2 26427 IR12 86)

DUKE POWER COMPANY STATION MY.d//F UNIT d l k ISI VISUAL EXAMINATION, VT 1 W.R.* Page / of /

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REV:

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JChlo ID NUMBER: g pg, ,g, r'D/H . /7.) . dgg3 - F/-2 ) ITEM NO. Ao7,4so 88 A f

ITEUS INSPECTED: Shds 4 Mds * (0163, c4 4l; 014 6~, 06 5'/, 0 740, 0 74,t, 04 st>)(A f r y, A's'f t, d121, n'ssn WsG4, N Sa Y, r/s4 s)

IN . IND CATION LENGTH WIDTH FEMARKS

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

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QA REVIEW

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FOR INFORMATION Obt)

FORM QCL 13A REV.2 2927 m12 *s ,

. <4 . .: . ,, , g a DUKE POWER COMPANY STATION Md 4vr F d

[V ) UNIT ISI VISUAL EXAMINATION, VT 1 W. R . =

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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)

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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, e) Linear axial indications which continue on two or more faces, i 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.

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D h) Corrosion that reduces bolts or studs cross sectional C4. area by more than 5%.

l i) Missing, fractured, or loose bolts, studs, and nuts, f

... 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 t1 m) Any linear indicstions gre3ter than 1J16 in. 1 0 c f:r materials less than 5/3 ir. tnico. greater ins 1 1 t-Os long for materisis fec- 5/c in. tnic, to un er 2 1.

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I 26427 4 A12 96) FORM QCL 13A REV.2 DU POWER COMPANY STATION , 86"E#WNIT 1 ISI VISUAL EXAMINATION, VT 1 d 72/3 / P,,, f or . h .ftQ 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 y $ , ff.4CG ID NUMBER:

8d [I ~2 ITEM NO. d E dId* d@

ITEMS INSPECTEO:

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r// d4ses' RESULTS: O ACCEPTABLE Yl)NACCEPTABLE. REQUIRES NDE/ EVALUATION OR REPAIR (7)

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DATE-[~

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dasman COMPLETE FORM BY PRINTING WITH BLACK BALL POINT PEN OR TYPE DUKE POWER COMPANY nv NUCLEAR STATION Problem Investigation Report Serial No. S- #1M- 0164' '

Station "!' Gurre '

investigation Report No. 4 M- o M- 2

1. Problem Occurred-Time /Date:

7-/- N Discovered. Time /Date: .54'"9 Units (s): _d Unit Status At Time Problem Occurred / Discovered: M"e b4 6u f**y+s-cunt W I'1 sp2Cc No* <[_g_ru ra v r.

Descnptnon 24cs Were dofyccye Problem Ad +he._.D't (* L <ddy f Af_A_c{efe ero nec/_Ls/G en /i sc fh .5teo el takes n e ec Lo$-ph$$ i ng MP2pa &s Ws upo n.

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 O 50 72 Secton 24.S. Secton V '/, M $~ n, O Part 21 O Other Evaluated O Lic.

By/Date- Con v7[ec M / M 7/I-!Jr f _.3 edal _[ep d pepml lptLuJ _JdAMf ding po.LI m t.Artesar.y.

i Comments:

Ill. Telecon/ ENS Report to NRC Time /Date: *d4 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 di.6A y t_,bh.Ctey /c/a-NRC Repo,rt Due Date:l$04[$yd4~tkSEJ"J" Date Due to Comphance af ter Evaluatt PIR Review (Comphance). Ad Date:

PIR Staten Manager Approval A/ bW /dI k.7 //g Date: l I

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 sly M_6' 67 ._/JLnyb Comphance Rev,ew [k Date _L M_ _ OA ReviewY Wdhe Date 7/Ull~

D strtbuten

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l DUKE POWER COMPANY I

^ * ' " ' "

GENERAL OFFICES '""""h8,,","'

33 432 80Uf M CHURCM Sittti CIIARLOTTE. N. C. 2824P. !

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

I 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 j R. W. Rider C. F. Robinson C. B. Cheezem A. M. McClenny D. R. Xeck J. C. Drive ,'

G.W.Bryant(B&W) 1 L. M. Thompson W. A. Haller 1 J. W. Boyle R. W. Eaker F 8. Mahaffey (B&W)

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

I 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

--. l

- 1:,-

g Cold le.3 ou / mm

- 1;

. ,, J

. p ,

' - ll';J , i

, . U- ,

..j i j ,

, . ;'- ,.i

i..

i

,4

,, . - Au

,. . , . l4-fe'1 :

, ,f.

- ,J t

,l. - ., 1

,1-

- a, I

). -

lei '

h, . !

,. - i.- Ln N. -

h ,, -

-9 I- id i 4

'. j- In,i 1 i

. ,- 3 i-< l

.;i.

'. 3- -

l

.4'>

t. \~ l

.. - .- . l ;

. : :- ( ._

O : : - lo , l 4

4-

". . s

_p.

.o. - (,

) :_ - h TOTAL TUBES FOUND = 42 j'

i J

4 I

i

.i

, 4 i

1 i

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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 tu bes to be removed from 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.

R. W. Rider T. M. Hilderbrand C. F. Robinson C. B. Cheezem O A. M. McClenny L. M. Thompson D. R. Keck J.'9, M MD @

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.

21.

34-34-92 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

l

h l 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 J. W. Boyle R. W. Eaker G.W.Bryant(B&W))

F. 8. Mahaffey (B&W t

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 ""'"'" 8'"l3,j

8" OENERAL OFFICES 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) l 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 '

l Order: Sort by ROW, COL

Title:

6/88 RF0 IUBES PLUGGED NO. ROW COL No. ROW COL

~~~~5I ~~5 ~65 C 6 fd Le30 o ~~~55 23- 507

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

9. 1- da 59. 38- 92

10. 1- 73 74 b6eLd ld La OdlN 60. 39- 53 ,

11. 1- 75 Cs (d La O N y twn 61. 44- 70 l

12. 2- 5 62. 44- 80 '

13. 2- 89 63. 48- 54

14. 4- 97

15. 5- 34

16. 5- 66 l

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 12- 70 O 30.

31.

32.

12- 71 13- 69

33. 13- 70

34. 13- 78 ,

35. 13- 100 1 1

36. 13- 112

37. 14- 51 l

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

p. o. s o n a s i e e

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

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. '

l 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 R. W. Rider C. F. Robinson C. 8. Cheezem O ^ a acci a"r L. M. Thon9 son o a x c' W. A. HaIIer a c oriv r 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:

11.

1:

1-

!?

30 s.+u wr 64et 6 Oub 1- 31 ge.t s4 La CWwy/lfa,m.

].

1,: ;- 3;

15. 3- k3

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.

30.

31.

12-12-13-52 79 37 l

32. 13- 84

33. 14

82 l

34. 19- 85

35. 20- 96 '

36. 24- 92 ;

37. 37- 39 ,

l TOTAL TUBES FOUND = 37 I i

l O ,

,e e

i 1

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

Request for Relief MNS-001 O :

l i

i l

f

O I

l Rev. O l Page 1 :

C/6550053 September 16, 1988 I

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 c~er 1980 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.

l Re ference Code Requirement that has been determined to be impractical:

ASME Boiler and Pressure Vessel Code Section XI, 1980 Edition, including 1980 Winter Addenda, article IWC-2500-1, items 1**

C01.010.051. The code requires the inspection of one 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 i

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

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