Text

Rev 0 to ISI Rept - Unit 1,McGuire 1991 Refueling Outage 7
	ML20090G169
Person / Time
Site:	McGuire
Issue date:	02/26/1992
From:	Barbour J, Hogge A, Underwood G; DUKE POWER CO.
To:	;
Shared Package
ML20090G162	List: ML20090G159; ML20090G169;
References
	NUDOCS 9203120118
	Download: ML20090G169 (201)
	v • d • e

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INSERVICE INSPECTION REPORT UNIT 1 MCGUIRE 1991 REFUELING OUTAGE 7 Location: Hwy 73, COWANS FORD, NORTH CAROLINA 28216 NATIONAL BOARD NO. 44 C0FNERCI AL SERVICE DATE: DECEMBER 1, 1981 Owner: Duke Power Company

422 S. Church St.

Charlotte, N.C. 2fl201 4

Revision 0

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Prepared By: '

'. I Date /'8/~ fL m Oi Reviewed By: .(/ sat 3nved( Date 2 25-92 Approved By: }inf.L6MU Date 2b!d Q / '

Copy No. 5 Assigned To NRC Documnt Control

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Controlled X Uncontrolled 920312011e 920306

{DR ADOCK 05000369 PDR i EQA388 i

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I i 199 Pages

} FORM NIS 1 OWNER $' DATA REPORT FOR INSERYlCE INSPECTIONS As requhod by the Provisions of the ASME Code Rules

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3. Own,tDuke Power Co., 422 S. Church St., Charlotte, NC 28201 (Nune and Address of Owooel f

l 2 eta : McGuire Nuclear Station Hwy. 73 Cowans Ford, NC 28216 j- (Norne and Addmes of Plasti .

3. Plant Unit 3 4. Owtwr Ceraticast of Ausbonsamos (if roquad) N/A i 3. Conumercial Service Date 3 2/I/81 6. Nonocal Sonni Nusaber for Unit 44

$ 7. Componesa iaspected Manufactergr

Component or Manufacturer at installet saw or - Nanonal 3

. Appurueance of lastallef Senal No. Pnmace No. Board No, j .

_SEE SECTION 1 PARAGRAPH 1.5 IN THE ATTACHED REPORT t

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.i Note Supplemental sheets in form of lists. sketenes, or drawings may be used provided (1) sue is 5% in. m 11 in..

(2) information m items 1 through 6 on this dass report u included os each sheet, sad (3) each sheet is cumbered -

i and the number of sheets is recorded at the top of this form,'

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O FORM NIS 1 (back)

s. Eummanon D. 05/17/90 to 12/07/9_1 p. in pecuo. i.imas rewn 12/01/81.12 'n1/o1 ,

10. Abstract of Examinacons. Include a tiet of examinacons and a statement concerning status of work required tor cumat inwmi. SEE ATTACHED REPORT

11. Abaract of condinons Nowd. SEE ATTACHED REPORT -

it. Ab.ci.ct of cometm Me-r= necommended and Taue. SEE ATTACHED REPORT we cerofy that the staternents inade in this report am comet and the exam and com rrve rnee-sures taken conform to etw rulee of the ASME Code, Sectios XI, Qat 2b 19 Signed nokn Dnune en By- - v

M/

Cetufksee of Authomation No.(if applicable) N/A Empiranon Date H /a J, CERTIFICATE OF INSERVICE INSFECTION I, the underngned, holding a valid . --a_ _ 7 issued by the National Board of Boiler and Pressure Venert taspectors and/or the State ce Pvtmace or N . C . and employed by *The HS R I & I l'n . of Ha rt ford Conn bave insevered the componente desenbad in this Owners' Data Report dunng the period I.L~1 d 0 to 11'7~9I - and state that to the best of my knowledet and behef, the Owner hee perfonned exarninacone and takes correctm measures desenbed in this Owtiers' Data Report is accordance i with the requirements of the ASME Code, Secuos XI, l By signing this comficate neither the loopectoe not his employer makes any warranty, expressed or implied, concerntag the examinanoes and cometm rueesures desenbed in this Owners' Data Report. Furthennon, neither the laspectoe noe his enaployer shall be liable in any manner for any personalinjury or property darnage or a loss of any kind anang from oe e M with the toepeenoa, Date _. 19 k l '#MM f ~ poe's Signanare

_ co,nm e.one rJL 853 National Board, State Ptovmee and No.

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The Hartford Steam Boiler Inspection & Insurance Company 200 Ashford Center North Suite 300 Atlanta, Georgid 30338 l

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t CONTROLLED DISTRIBUTION P

Copy No. Assigned To 1 l Original J. O. Barbour 1

1 G. J. Underwood ,

2 L. C. Keith (McGuire) l l__

3 W. D. Minton i

(BWNS - Lynchburg) 4 R. L. Gi_ll, Jr.

(To Licensing File) 5 NRC Document Control ~.

4 UNCONTROLLED DISTRIBUTION 6 C. A. Ireland (AIA, Atlanta,GA) l O

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O EQA388.

TABt.E'0F CONTENTS Section Title Revision '

1. Summary of Inservice inspection 0

2. Status of Required Inspections 0

3. Final Inservice Inspection Plan for Outage 7 0

4. Results of Inspections Performed During Outage.7 0

5. Class 1 Inspection Results 0

6. Class 2 Inspection Results 0 ,

7. Augmented Inspection Results- 0

8. Personnel. Equipment, and Material Certifications 'O

9. Problem .(nvestigation Reports -0

10. Reference Documents 0

11. Class 1 and 2 Repairs and Replacements 0 O

O EQA388

1,0 Summary of inservice In_spect_1on

O 'his renert descr18es 18e inservice insnectien ef o"'e re er cemn nv s McGuire Nuclear Station Unit I during the 1991 Refueling Outage (also referred to as Outage 7), which is the last refueling outage in the Third Inspection Period of tt.e First Ten Year interval.

Included in this report are the final Inservice Inspection Plan, the inspection results for each item, a summary for each category of examination, and corrective action taken when unacceptable conditions were found, in addition, there is a section included for repairs and replacements required since May 17, 1990, 1.1 Class 1__ Inspection The Class 1 Inservice Inspection included examinations on the Reactor Vessel Circumferential and Longitudinal Shell Welds, Circumferential and Meridonal Head Welds, and the Shell to Flange Weld, Also, examinations 4

were performed on the Norzle to Vessel Welds and Inside Radius Sections, Nozzle to Safe-End Butt Welds, Threads in Vessel Flange, Reactor Vessel Interior Surfaces and the Core Support Structure.

Examinations were performed on Steam Generators IA, 18 and 10 Manway Bolting, and on Valves INI-157 and INI-160 Bolting.

Dissimilar Metal Butt Welds in the Safety Injection System and Piping

} Welds in the Reactor Coolant and Safety Injection Systems received

, t examinations, In addition, the inter nal surfaces of Valves IND-2A.C.

1NI-125, and 1NI-157 received examinations, Visual examinations were performed on the Class 1 Pressure Boundary during Hydrostatic Tests. Also, visual examinations were performed on the Class 1 Component Supports of the Reactor Coolant, Safety Injection, Chemical and Volume Control Systems and on Steam Generator IC Support.

The Inconel 600 tubing in Steam Generators IA, IB, IC 'nd ID wi,s

, inspected by eddy current during Outage 7. The results of the inspec-tions are shown in Section 5 of this report, A detailed description of the McGuire 1 Refueling Outage 7 eddy current inspection is provided in the October / November 1991 Eddy Current Examination Report on file in the Corporate Office in Charlotte, North Carolina, Reportable indications were found on the Class 1 Inspections snown in this section, Inspection and evaluation data for each reportable indication found on Class 1 Inspections.is included in Section 5 of thts report.

A detailed description of each inspection is found in the final Inservice Inspection Plan in Section 3 of this report, Resetts of each examination are found in Section d, t

O EQA388 Page 1 Revision 0 January 31, 1992 I

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1.2 Class 2 Inspecticn The Class 2 Inr.pections included examinations on Steam Generator 1C l

O Lower Shell to Transition Cone Weld, Residual Heat Removal Heat Excnanger IA Nozzle Belt to Flange, Nozzle Belt to Head Weld, and Inlet Nozzle A and Outlet Nozzle B to Vessel Welds. Vessel integrally-welded '

attachments on Residual Heat Removal- Heat Exchanger IA and piping integrally-welded attachments on the Main Feedwater and Main Steam Systems were examined. Examinations were performed on circumferential butt welds of the Main Feedwater and Main Steam Systems.

Visual examinations were performed on the Class 2 Pressure Boundary durin0 System Hydrostatic Tests. Also, visual examinations were performed on Class 2 Component Surr,rts of the Auxiliary Feedwater (CA),

Refueling Water (FW), Residual Heat Removal (ND), Safety Injection (NI),

Containment Spray (NS), Nuclear Service Water (RN), Containment Ventilation Cooling Water (RV), Main Steam Supply to Auxiliary Equipment (SA), Main Steam (SM), and Main Steam Vent to Atmosphere (SV) Systems.

( Also, the Safety Injection Accumulator Tank B Support Skirt received a visual examination.

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

1.3 Augmented Inspection I

Augmented inspections were performed on Reactor Coolant Pumps IA and 10 t Gwheels, Steam Generator Tubing, Pipe Rupture Protection, Steam

, Generator Feedwater Modification, Thermal Stress Piping and on Safety Injection Accumulator Nozzles. A detailed description of each examination is found in the final Inservice Inspection Plan in Section 3 of this report. .Results of eacn examination are found in Section 4.

l l 1.4 Alternate Examination No alternate examinations were performed during Outage 7.

1.5 Identification Numbers l Owner: Duke Power Company, 422 S. Church St., Charlotte, NC 28201

l. Plant: McGuire Nuclear Station, Highway 73, Cowans Ford, NC 28216 l Plant Unit: 1 Owner Certificate of Authorization: N/A Connercial Service Date: 12-1-81 EQA388 Page 2 Revision 0 January 31, 1992

Manufacturer State or National Manufacturer or Installer Province Board item or Installer Serial No_. No. No.

Reactor Vessel Combustion CE67102 NC-178379 20766 Engineering Pressurizer Westinghouse 1471 NC-178395 68-123 steam Generator 1A Westinghouse 1461 NC-178375 68-107 Steam Generator 1B Westinghouse 1462 NC-178376 68-108 Steam Generator IC Westinghouse 1463 NC-178377 68-109 Steam Generator ID Westinghouse 1464 NC-178378 68-110 Main Steam Supply Duke Power SA N/A 4 to Auxiliary Co.

Equipment System Containment Air Duke Power VQ N/A 12 Release and Co.

Addition System Main Steam System Duke Power SM N/A 17 g Co.

Main Steam Vent to Duke Power SV N/A 18 Atmosphere System Co.

Reactor Coolant Duke Power NC N/A 28 System Co.

Liquid Waste Duke Power WL N/A 29 Recycle System Co.

Refueling Water Duke Power FW N/A 31 System Co.

Auxiliary Feed- Duke Power CA N/A 32 water System Co.

Residual Heat Duke Power ND N/A 35 Removal System Co.

Nuclear Service Duke Power RN N/A 36 Water System Co.

Chemical & Volume Duke Power NV N/A -37 Control System Co.

O EQA388 Page 3 Revision 0 January 31, 1992 l

q Manufacturer State or National I,j Manufacturer or Installer Province Board item or Installer Serial No. _ No. No.

Component Cooling Duke Power KC N/A 38 System Co.

Main Feedwater Duke Power CF N/A 39 System Co.

Containment Spray Duke Power NS N/A 40 System Co.

Containment Venti- Duke Power RV N/A 41 lation Cooling Co.

Water System

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Safety Injection Duke Power NI N/A 42 System Co.

Safety Injection Delta 41617-72-1 NC-178396 3038 Accumulator Tank Southern Co.

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tfaty Injection Delta 41617-72-2 NC-178397 3039

_ Accumulator Tank Southern Co.

r"~s 1B

%)

Safety Injection Delta 4'.617-72-3 NC-178398 3040 Accumulator Tank Southern Co.

1C Safety Injection Delta 41617-72-4 NC-178399 3041 Accumulator Tank Southern Co.

1D Unit 1 Duke Power N/A N/A 44 Co.

1.6 Authorized Nuclear Inservice Inspector (s)

Name(s): R. D. Klein MM Employer: The Hartford Steam Boi er Inspection and Insurance Company 200 Ashford Center North Suite 300 Atlanta, Ga. 30338 O

EQA388 Page 4 Revision 0 January 31, 1992

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PROGRAM: NI., -GAISIC2 DUKE PtME2 CMANf PAGE S FILE: C007133 .

GUALITV f,SSURANCE DEPARTMENT DaTE 82/13/92 PLANTS. MCGUIRE t.MIT 1 PRE-SERVICE APG IN-SERVICE INSPECTitM SYSTEM KEY: ;- ITEM MDBER 507 MCGUIRE 1 CLASS 1 REPORTA8LE ITEMS tFAGE 7 INSP PROC. MATERIAL DIAM./ CALIS l ITEM ft#BER 10. MRSER - DRAMING >RSWERS ^ LOCS. REG. IO SERS TYPE / GRADE THICK BLOCK COPMENTS -

. seassss==sss ==sssssssse==isusssa

==============s===s3 meses mass sess==== 33ss====== ====== sessa mzs==================ss e m s 827.620.000 ********* PRESSURIZER BOLTS. STUDS Afe MJTS m **::::::::::::::: ******* e m ****** _._ ** m

m m

m m ** m e m ** . ,

837.C30.000 ********rSTEAM GENERATOR *********** *** ******* ***** _._ ame HApetAY BOLTING (16 BOLTS) i BOLTS, STUDS.AND MJTS _._ *********** *

m ** m ******* '

S37.C30.001 ISGA-tet-MK' MCM1201.01-3 Vil GAL-13 CS 01.88 SGIA MAPMAY BOLTING E 16 BOLTS)

_._ - PRIMARY MAretAY IN X-Y QUADRANT

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FIR l-M92-00ZZ

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, - 807.030.002- ISGA-fM-2M MCM1201.01-3 .VT1 4AL-13 CS 01.88 SGI A M4petAY BOLTING (16 90LTSI

, , , , _ . _ PRIMARY MADMAY IN Z-Y QUADRANT 3 PIR l-M9Z-00ZZ 3

807.C30.003 ISG8-198-XY MCM1201.01-3 VT1 QAL-13 CS 01.88 SGIS PWMAY BOLTING (16 90LTS)

_..,,,,,,,,,, PRIMARY fWMAY III X-M GUADRANT -[

PIR l-M9Z-002Z ,

037.030.004 "'ISGB-996-YZ MCM1201.01-3 YT1 GAL-13 CS 01.88 SG1B Mafet4Y BOLTING t16 BOLTSI

_,,,._,,,,,,, PRIMARY MApotAY IN Z-M GUADRANT PIR l-M92-00ZZ B07.C50.000 CLASS 1 PIPING *** ** m ** ***** _._ ***** rrrrrrrrrrrr rrrr rrr---- :rrr 9,0,LTS,.S,TU,,DS,,AM,,D,M,,J,TS,

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I- B07.060.000

CLASS 1 PLMPS ' 90LTS. STUDS Afe MJTS ' *** * * *** ***** _._ ***** rrrrrrr rr ---- rrrrrrr r- rr ,

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'b M ' ' % l PROGRAM: NISwure-QAISIO2 - Dt%E POMEQ COMPAM( PAGE 18 FILER COO 7133 GUALITY ASSURANCE DEPARTNENT DATE 02/13/92 PLANT: MCGUIRE' UNIT 1 PRE-SERVICE AND IN-SERVICE INSPECTI N SYSTEM KEY: ITEM NUPBER 816 NCCUIRE 1 CLA*eS 1 REPORTABLE ITEMS OUTAGE 7 !

INSP PROC. MATERIAL 01AM./ CALIB i ITEM ft#9ER 10 NtkBER .... ORAMING,NUPSERS LOCS,3. REG. MJPBERS TYPE / PLOCK COPH

.=een,ENTS !

=======ss == . === es .,z 33=,.== 3=======esus === s=== ==e===== 3==s.GDADE Tli1CK or

====== n==m m 3=e m e m

D16.620.000 ********* STEAM GENERATOR TUBING **** * * * * * * * * * * ***** _._ ***** ** m ********** m *******----"

e m ********* m m e _._ ********** - ** w * **********

C16.021.000 *****SGA STEAM GENERATOR TUBING **** *** ******* ***** _._ ***** *******we****we*** m ******* r

- n o m ****we***** _._ *n u m u** m new u e** m es ,

I G16.021.001 . ISGA-TLBES HCM-1201.01-187 ET ISI-424 IN 00.75 SELECT CALIBRATICH STANDARD I 00.043 PER YOLUME 1 SECTI0tt 10.2 i Bl&.C22.000 *n**SGB STEAM GENERATOR RIBING**** *** ******* ***** _._ ***** ************* m **************

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i 016.022.001 ISCB-TUBES HCM-1201.01-187 ET ISI-424 IN 00.75 SELECT CALIBRATION STANDARD [

00.043 PER VUltR1E 1 SECTIN 10.2 i i

C15.C23.000 *****SGC STEAM GENERATOR Tt2ING**** .*** ******* ***** _._ ***** ::::::::==********************

- - - - w ******** _._ ***** m we** m e m ****** m e B16.C23.001 ISGC-TUBES HCM-1201.01-187 EE 151-424 IN 00.75 SELECT CALISPATION STANDARD 00.043 PER YOLUME 1 SECTI N 10.2 3

316.C24.000 *****SGO STEAM GENERATOR TUBING **** *** ******* ***** _._ ***** ******************************

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M DUKE Pt9Cl C M ANY 17 PROGRAM: NI -4AISI!2 .

PAGE -

t FILES . COO 7153 GUALITY ASSURANCE DEPARifENT DATE C2/13/92 ?

- PLANT *- MCGUIRE UNIT 1 PRE-SERVICE AND IN-SERVICE INSPECTION SYSTEM !

KEY: - ITEM paASER 816 .=- PCGUIRE 1 C p 1 REPORTAS ITEfts cuTAGE 7

. INSP PINE. MATERIAL ' DIAM./ CALIB ITEM 14ASER,ssss===s=============

ID. MASER DRAMING >R HBERS LOCS. RE9. MASERS TYPE / GRADE THICK SLOCK CDPMENTS sammessmus ess==wsnes====sesser. s==== ==== ======== =====se=== ====== s==== === 3=========================

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, -216.624.001 ' ISGO-TUBES . .'MCH-1201.01-167 ET 131-424 IN 00.75 SELECT CALIBRATION STANDARD 00.043 PER VOLUME 1 SECTION 10.2 t

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1 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

. 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

, Table IWC-2500-1 for Class 2 Inspections. Augmented inspections are

also included.

Class 1 Inspections i

Section

XI Inspections Inspections Percentage Deferral Rategory Description Required Completed Completed, Allowed l

B-A Pressure Retaining 27 Welds 27 Welds 100% Yes

Welds in Reactor ;

Vessel

8-B Pressure Retaining 8 Welds 8 Welds 100% No l Welds in Vessels Other than Reactor Vessel B-D Full Penetration 36 Inspections 36 Inspections 100% Partial Welds of Nozzles -

O ie vesseis l- B-E Pressure potaining 55 Welds 55 Welds 100% No Partial Penetration Welds in Vessels B-f Pressure Retaining 38 Welds 38 Welds 100% No Dissimilar Metal

Welds B-G-1 Pressure Retaining 366 Items- 366 Items 100% No Bolting Greater than 2 Inch Diameter

B-G-2 Pressure Retaining *55 55 Connections 100% No-

}_ Bolting 2 Inches Connections and Less-in Diameter B-H Integral Attachment 12 Attachments 12 Attachments 100% No for Vessels B-J Pressure Retaining 180 Welds 180 Welds 100% No Welds in Piping

Total connections include CROMs that are disassembled.

EQA388 Page 1 Revision 0 January 31, 1992:

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, - Class 1 Inspections (Continued)

Section XI Inspections Inspections Percentage Deferral Category Description Required Completed Completed Allowed _

B-K-1 Integral Attachments None N/A N/A N/A for Piping, Pumps and Valves B-L-1 Presse-e Retaining None N/A N/A N/A Welds in Pump Casings B-L-2 Pump Casings None N/A N/A N/A B-M-1 Pressure Retaining None N/A N/A N/A_

-Welds in Valve Bodies .

B-M-2 Valve Body > 4 in. 6 Valves 6 Valves 100% Yes Nominal Pipe Size B-N-1 Interior of Reactor 3 Items 3 Items -

100% No Vessel B-N-2 Integrally Welded None N/A N/A N/A Core Support l O. Structures and Interior Attachments to Reactor Vessels B-N-3 Removable Core 1 Item 1 Item 100% Yes Support Structures B-0 Pressure Retaining 3 Housings 3 Housings 100% -Yes

! Welds in Control Rod Housings l

1-B-P All Pressure Retaining No Components System Leakage Test 133 Components 133 Components' 100%

System Hydrostatic 22 Components 21 Components 95.45%

Test--

, B-Q Steam Generator 100% of Technical Specifications Met L Tubing F1.01 Class 1 Component 507 Supports 507 Supports 100T No i Supports O-l EQA388 Page 2 Revision 0 January 31, 1992

Class 2 Inspections XI .

Inspections Inspections Percentage Deferral Category Descriptien Required Completed Completed Allowed C-A Pressure Retaining 9 Welds 9 Welds 100% No Welds in Pressure Vessels i C-B Pressure Retaining 6 Welds 6 Welds 100% No l Nozzle Welds in

! Vessels C-C Integral Attachments 17 17 100% No fnr Vessels Piping, Attachments Attachments Pumps and Valves '

1 C-D Pressure Retaining None N/A N/A N/A Bolting Exceeding 2 Inches in Diameter C-F Pressure Retaining 321 Welds 321 Welds 100% No Welds in Piping ,

C-G Pressure Retaining 8 Welds 8 Welds 100% No Welds in Pumps and Valves C-H All Pressure P.etaining No Components System or Component 43 Components 43 Components 100%

Functional Test System Hydrostatic 79 Components 18 Components 22.78% ,

Test F1.02 Class 2 Component 491 Supports 491 Supports 100% No Supports O

EQA388 Page 3 Revision 0 January 31, 1992

l Augmented Inspectlons

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Description Percentage Complete Reactor Coolant Pump Flywheels 100% of Technical Specifications Met Steam Generator Tubes on i , heater Section 100% of requirements Pipe Rupture Protection 100% of requirements Steam Generator Feedwater Modification 100% of requirements Thermal Stress Piping 100% of requirements safety injection Accumulator Nozzles 100% of requirements ~.

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O EQA38P Page 4 Revision 0 January 31, 1992

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3.0 Final inservice Inspection Plan For Outage 7 The final ISI plan presented in this section lists all examinations O credited for Outage 7 at McGuire Unit 1. This includes ASME Section XI, Class 1 and 2 and augmented inspections required by the plant technical specifications, NRC Bulletins and Problem Investigation Reports.

The inf ormation 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),

1WC-2500-1 (Class 2), IWD-2500-1 (Class 3),

1WF-2500-1 (Class 1, Class 2, and Class 3) and Augmented Requirements ID Number = Unique Identification Number Drawing Number : Location and/or Detail Drawing Locs, = Location Insp. Req. = Examination Technique - Magnetic Particle, Dye Penetrant, etc.

Proc. Numbers = Examination Procedures Material Type / Grade : General Description of Material Diam./ Thick = Diameter / Thickness

)

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

() EQA388 Page 1 Revision 0 January 31, 1992 1

PROGRAM NISIRUPS-CAISIC2 DC E POE2 COWANY PsEE 1 ;

FILE: C007133 -

QUALITY ASSURANCE DEPARTMENT DATE O2/20/*2 i PLANT: MCGUIRE UNIT 1 PRE-SERVICE AND If4-SERVICE INSPECTION SYSTEM !

KEY: ITEM PAASER . 801 MCGUIRE 1 INSERVICE INSPECTIW4. LISTING OUTAGE 7 o, i INSP PROC. MATERIAL DIAM./ CALIB ITEM M.RBER DRANING BLOCK

=====m...C0. RENTS,,3m,===.

es========== ID. NLPBER==================== ======= N.UPeERS========== LES. REQ.

===== ==== feeERS. TYPE / GRADE

======= ========== THICK

===== .

001.000.000 REACTOR YESSEL MELDS *************** *** ******* ***** _._ ***** --------------""- --"-" ""'"-'-

r r ** m en w n e ww**** _._ ** m ** - ** m m m m *** m 801.010.000 REACTOR VESSEL SHELL MELDS ********* *** ******* ***** _. ***** *****

m ** m ************** !

u*** m e m u n *** _._ m w - m ** m m m e m e m 831.011.000 REACTOR VESSEL CIRCUMFERENTIAL***** *** ****we *m* . *m* u m m **n m u m m e m ***

SHELL MELDS ********* [.1 e.****w*****mr r r :::: r r me .

801.011.001 1RPV 8-442 MCM1201-01-223 UT ISI-138 CS . 50377 PC. 4%-01 TO 4%-02 MCM1201-01-146 M.20 UPPER SHELL TO MIDDLE SHELL s

i 301.011.P02 " 1RPV 9-442 MCM1201-01-223 t/T 15I-138 CS . 50377 PC. 4%-02 TU 4%-03 MCM1201-01-146 M.MO MIDDLE SHELL TO LOMA SHELL l 801.011.003 1RPV10-442 MCM1201-01-223 11T ISI-138 CS 5037S PC. 4%-03 TS 46*-01 MCM1201-01-146 E.150 LtMER SHELL TO LOMER HEAD ,

C01.012.000 REACTOR VESSEL LONGITUDINAL ******** *** ******* ***** ***** ***** w**ee uwm*m- - - - - - -

SHELL E LDS********* [.~._ ** m e m m n** m m e wo m e 501.012.001 1RPV 1-442A MCM1201-01-223 UT 151-138 CS . 50378 APP 0X. 60 DEC.

MCM1201-01-146 15.700 UPPER SHELL LONG SEAM i i 1-4 w **

S

PROGRAMr NIS1 RUNS-SAISIi2 Ot.EE PtDE2 CtMPANY PAGE 2 FILE: COO 7133 GUALITY K.SSURAPCE OEPARTMENT DATE C2/20/92

. PLANT: MCGUIRE tMIT 1 PRE-SERVICE AM) Ite-SERVICE INSPECTItDC SYSTEM ;

KEY: . ITEM te.2SER B01 MCGUIRE 1 IM3ERVICE INSPECTItDt, LISTING OUTAGE 7

. v , ,w INSP PROC. MATERIAL DIApf./ CALIB ITEM MASER ID. MASER -

ss=wasssemer m33====s.=====z33,w= DRANING

====== == M,PSER$

ms===ezzes LOCS. =====REG.sss=MASERS.

==TYPE / GRADE

========== BLOCK ==========,CtDMENTS THICK.===== ========= w3 3.

{' .. . .

B01.012.002 1RPV 1-4428- .MCM1201-01-223 UT 151-138 CS . 50378 APROX.180 DEG.

tLM1201-01-146 _ _ _

T5.750 UPPER SHELL LCDC SEAM B01.012.003 1RPV 1-442C McM1201-01-E23 UT ISI-138 CS . 50378 APROX. 300 DEG.

MCM1201-01-146 E.750 UPPER SHELL LONG SEAPt 801.C12.004 1RPV 2-442A MCM1201-01-223 UT 151-138 CS . 50377 APROX. O DEG.

MCM1201-01-146 M.E50 MIDDLE SHELL LONG SEAM

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~ B01.812.005 1RPV 2-4425 NCM1201-01-223 UT 151-138 CS . 50377 APROX.120 DEG.

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==========re====,UPBER,,,w3e================,s==========3 LOCS. REW. MRSERS TYPEARADE TMICK BLOCK CIP9ENTS [
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FILE: C097233 EPJALITy aMEANCE DEPARTNENT CATE C*M*2 Pt.JWT s MCGJIRE LHIT 1 PPE-SERVICE AND IN-SERVICE INSPECTItM SYSTEM REY: ITEH MASER F1. MCGUIRE I IK,ERVICE IPCPECTItN LI.*. TING CUTAGE 7 INSP PE. FlTTWIAL DIAM./ CA<!8 DRAMING NJSERS LCCS. RES. P7BERS TYPEr,RADE TMICK BLOCK CcPTENTS ITEM NLFEER ID. PR79ER __;_____e seene swee seenween wee . . . , _ _ _ ._ e eezens ===== _________;_____;________.__ -
=====*=====e neerzwezemezzeeerece we======:m T1.C3.047 I-NCA-CA-264 NCSRD CAB VT GAL-14 04.00 RIGID SLFPCRT CUT.3 ALDED FER IN24 Meal F1.C3.068 1-NCA-C A-247 NCSRD CAS VT GAL-14 04.00 RIGID N
~~~
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CUI.3 ALUED FLid Ins 24MtAl 1-NCA-CA-293 NCSRD CAD VT GAL-14 04.00 RIGID SUPPCRT FI.C3.084
~ ~ ~
OUI .3 AOUED FER IM2*M4Ah I-NCA-CA-294 PrSRD CAD VT GAL-14 04.00 RIGID SUPPCRT R.C3.085 DJi.3 AeDie FER 1*ef z4 Min t 1-fCA-CA-t*8 71CSRD CAE VT CAL-14 04.00 RICID SUPPORT F1.03.089
~-
WI.3 Aacts PER laFiwwt A 6 1-HCA-CA-299 NCSRD CAE VT GAL-14 04.00 RIGID SUPPcRT T1.C3.090
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F1.03.Ot3 1-NCA-CA-102 PCSPD CAE YT GAL-14 _ _
04.00 RIGID SUFFCett
=_ l F1.C3.094 1-tCA-CA-358 MCSRD CAA YT GAL-14 06.00 . RIGID SUPFCRT
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cur.3 Aada FU N Z4N4A6 F1.C3.C*5 1-MCA-CA-4*1 NCSpo CAD VT GAL-34 04 c0 RIcts 3.PecKT
~~ ~~~
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. . . . . - . - - . . __ - - . . . . . - . - = - _ . . .. . ..
4.0 Results Of inspections Performed During Outage 7 The .'esults of each inspection shown in the final ISI Plan (Section 3 of O this report) are included in this. section.
status for each inspection are shown.
The completion date and All inspections revealing reportable indications are describad in further detail in Section 5, 6, or 7 as cpplicab h 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),
IWF-2500-1 (Class 1, Class 2 and Class 3), and Augmented Requirements ,
10 Number = Unique Identificaticr ' umber Intpection Date = Date of Examination Inspection Status CLR = Clear REC. = Recordable
REP = Reportable Inspection Limited L = Limited
- = No k
deo. Ref. = Geometric Reflector N = No Y = Yes Comments : General and/or Detail Description i
i I
O coa 388 eeee 1 Revision 0 January 31, 1992 j
y
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(
PROGRANs NISIR W -QAIS104 OlRE PCHE2 COMPANY PAGE 1 FILE: C007133 QUALITY ASSURANCE DEPARTMENT DATE C2/25/t2 PLANT: HCGUIPE tMIT 1 PRE-SERVICE AND IN-SERVICE INSFECTIM4 SYSTEM
-KEY: ITEN NUtBER S01 MCGUIRE 1 ItGERVICE IN5FECTime RESULTS CUTAGE 7 IPCPECTIG4 ItCPECTIG4 INSPECTIG4 GES.
ITEM MJtBER ID NtJBER 0 ATE STATts LIMITED REF. C3ttENTS
=s=========s ====ws=======e====ss szzz====es ====ssue== ========== ==== ===========================r3.
B01.011.001 1RPV 8-442 10/23/91 REC L Y B01.011.002 1RPY 9-442 10/30/?1 CLR _
Y 4
B01.011.003 1RPV10-442 10/27/91 CLR L Y B01.012.001 1RPV 1-44tA 10/23/91 CLR _
Y B01.012.002 IKPV 1-4428 10/23/91 REC _
94 B01.012.003 1RPV 1-442C 10/23/91 REC _
N B01.012.004 1RPV 2442A 10/21/91 CLR ,,
N B01.012.005 1RpV 2-442B 10/21/91 REC _
N B01.012.CC6 1RPV 2-442C 10/21/91 CLR ,
N B01.012.007 1RPV 3-442A 10/21/91 REC _
Y B01.012.008 1RPV 3442B 10/21/91 REC _
N B01.012.009 1RPV 3-442C 10/21/91 REC _
Y B01.021.002 1RPV 4-469 10/26/91 REC L Y BSN 1991 RPV.REPCRT SECT.3-18A B01.022.006 1RPV 1-202A 10/27/91 CLR _
Y B01.022.007 1RPV 1-202B 10/27/71 REC _
Y
DIRE PtBE2 Ct99AMf PAGE 2 PROGRAft: NITIRthe-GAISIO4 DATE 02/25/92 FILET - C007133 . . QUALITY ASSURAfEE DEPARTNENT PLAffT: NCGUIRE UNIT 1 PRE-SERVICE AND IN-SERVICE IMSPECTION SYSTEM KEY: ITEM MABER 801 MCGUIRE 1 IW,ERVICE INSPECTIt24 RESULTS OUTAGE 7
-INSPECTION INSPECTIt96 INSPECTIt94 GES.
' ITEM MesfiR - 10 MDeER DATE- - STATUS LIMITTD REF. CDP 91ENTS sessssssssss 'assssssssssses==ssse mass ===ses - seass=sess essnes==== sses esses ==sssssssssssssssssssssss 801.022.008 1RPV 1-202C 10/27/91 CLR _
N
'1RPY 1-202D 10/27/91, CLR Y
.801.022.009- _
s B01.022.010 1RPV 2-20ZE 10/27/91 CLR _.
Y 801.022.011 1RPY 1-202F 10/27/91 CLR _
N B01.030.001 ' 1RPV 7-442 10/02/91 CLR L M OUT. 7 180-360 DEG. fee-650 B01.030.002 1RPV 7-442 10/23/91 REC L Y
-..w.-- ,.,.:___ms_
--w-,- u_s,t . _ . - _
Pt.CE 3 OUVE /CMER CCMPANY OATE 02/25/t2 FRCCRAM: NISIRLHD-QAISIO4 GUALITY ASSURANCE DEPARTMENT FILE: C007153 PLINT: NCGUIRE LHIT 1 PRE-SERVICE AND IN-SERVICE IEPECTION SYSTEM KEY: 11EM NUPBER 803 NCCUIRE 1 IEERV'CE ItGPECTION RESULTS OJTAGE 7 I
ItGPECT124 ItGPECTicN IEPECTIcti GEU.
STATUS LIMITED REF, COP 1NENTS ITEN PU BER 10 PARSER DATE ==se=======s=====e===wrecerse.
eses ===rs= ors ======= ====
s======= ================s=== ======
10/25/91 REC L Y B03.090.001 1RPV5-445A L Y B03.090.001A 1RPVS-445A 10/17/91 CLR 10/25/91 CLR L Y m B03.090.002 1RPVS-4458 10/17/91 CLR L Y 803.090.002A 1RPYS-445D 10/25/91 REC L N B05.090.003 1RPV5-445C L Y B03.090.003A 1RPVS-445C 10/18/91 CLR L N
! B03.090.004 1RPVS-445D 10/25/91 REC 10/17/91 REC L Y B03.090.004A 1RPVS-445D 10/24/91 REC L M B03.090.005 1RPV5-44bE 10/15/91 CLR L N B03.090.005A 1RPV5-445E 10/24/91 REC L N B03.090.006 1RPY5-445F 10/15/91 REC L Y B03.090.006A 1RPV5-445F 10/30/91 CLR L N B03.090.007 1RPV5-445G 10/16/91 REC L Y B03.090.007A 1RPV5-445G 10/30/91 CLR L N B03.090.008 1RPVS-445H i
l 1
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DIKE PtBED CtlPFMff PAGE 4 PPUCRAM: NISIRLARHDA13IO4 DATE 02/25/92
. FILER CD07233 . GUALITY ASSUR4fCE DEFARTMENT PLANT: MCSUIRE -UNIT 1 PRE-SERVICE AND IN-SERVICE INSPECTIt94 $YSTEM KEY: --ITEM PAASER - 803 NCGUIRE 1 INSERVICE INSPECTICD4 RESULTS (IUTAGE 7 INSPECTItW4 INSPECTItpd INSPECTIt!N GE S.
',.ID NtDSER DATE . STATUS LIMITED REF. CEDMENTS ITEM PERSER 3:3======= e=ss===ess ========== ==== =========we3=====rzwe===ser
===s:s====== sesss===esssss===3sw 10/16/91 CLR L Y 803.090.008A 1RPY5-445M 10/28/91 REC L N 803.100.001 1RPVS-445AR 10/28/91 REC L M 803.100.002 '1RPV5-44584
'10/28/91 .CLR L N B03.100.003 1RPVS-445CR 10/28/91 CLR' L N 803.100.004 1RPVS-4450R 10/29/91 REC L Y
-803.100.005 1RPY5-445ER 1RPYS-445FR 10/29/91 REC L Y B03.100.006 10/28/91 CLR L M B03.100.007 1RPV5-445GR !
10/29/91 CLR- L M B03.100.006 1RPVS-445HR l
l 1
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PAGE 5 PROGRAM: NISIROND-C.*.1SIO4 DL*E PCHE'l CSFANY QUALITY AS M ANCE DEPARTMENT DOTE CZ/25/92 FILE: C007133 PLANT: ft .211RE UNIT 1 PRE-SERVICE AND IN-SERVICE INSPECTIS4 SYSTEM KEY: ITEM PU BER BOS PCCUIRE 1 IfGERVICE INSPECTItN RESULTS CUTAGE 7 INSPECTIG4 INSPECTIM4 INSPECTINI GES.
DATE STATUS LIMITED REF. CO HENTS ITEM tAlreER IDtOSER ===sss==ce ===3s===== ==== n=======s========ses=======er=
============ sss===rsssensssssssa sszz===ees 1RPY 3-4458-SE 10/28/91 CLR N B&M 1991 RPV. REPORT SECT.3-18A B05.010.001 _
10/28/91 CLR N 88N 1991 RPV. REPORT SECT.3-184 B05.010.001A 1RPV 3-4458-SE _
1RPV 3-445A-SE 10/37/91 REC N BRM 1991 RPY REPCRT SECT.3-ISA 805.010.003 _
10/17/91 REC N B&M 1991 RPV. REPORT SECT.3-18A B05.010.003A 1RPV 3-445A-SE _
10/17/91 REC Y B&M 1991 RPY REPCRT SECT.3-184 B05.010.005 3RPV 3-445D-SE _
1RPV 3-4450-SE 10/17/91 REC Y BEM 1991 RPV REPCRT SECT.3-18A B05.010.005A _
10/25/91 CLR N B2M 1991 RPV REPORT SECT.3-18A B05.010.007 1RPV 3-445C-SE _
10/25/91 CLR N BRM 1991 RPY REPORT SECT.3-18A B05.010.007A 1RPV 3-445C-SE _
1RPV 3-445F-SE 10/14/91 REC L Y REF. 824 1991 RPV REPORT B05.010.009 1RPV 3-445F-SE 10/14/91 REC L Y REF. BAN 1991 RPY REPCRT B05.010.009A 10/28/91 CLR N REF. BAM 1991 RPV REPORT B05.010.011 1RPV 3-445E-SE _
10/28/91 CLR N REF. B&M 1991 RPV REPORT B05.010.011A 1RPV 3-445E-SE _
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PROGRAHt NISIRUND-GAISIO4 DL%E POW D COMPANY PAGE 6
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CJALITY (SSURANCE DEPART)(NT DATE 62/25/92
PLANT: MCGUIRE LMIT 1 . PRE-SERVICE AND IN-SERVICE INSPECTitM SYSTEM i KEY: ITEM NikeER ELOS - MCGUIRE 1 INGERVICE INSPECTIEN JtESULTS OUTAGE 7 .
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' ITEM te eER . Ib MJMBER DATE STATUS LIMITED REF. CtR9ENTS
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805.010.0154 . IRPY '3 445G-SE 10/29/91 CLR _ Y- RET. ban 1991 RPV REPORT B05.050.016' 1NI1rM-38 3 10/16/91 CLR L' N
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DATE STATUS LIMITED REF. CN4 ITEN NLPBER IDfueER ========== ========33 ==== =3s=============3sa ==========
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10/02/91 CLR N 806.040.025 1RPV-THREAD-25 _
10/02/91 CLR N B06.040.026 1RPV-THREAD-26 _
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10/02/91 CLR N B06.040.028 1RPV-THREAD-28 _
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ITEM PU SER IDt&BER CATE STATLS LIMITED REF. COf1ENTS
====== ==================== =======s== =====s==ss ========r= ==== ========================
l B09.011.010 1PC1F-107 10/22/91 CLR L Y l
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N ItJC-3087-H1 CLR L N B09.011.027 09/26/91 INCP-226-1 10/29/91 CLR N B09. 011. 071 _
B09. 011.071 A IPCP-226-1 10/24/91 CLR _
N B09. 011.072 ItCIF-540 10/29/91 CLR _
N 10/24/91 CLR H B09. 011. 072A ItE1F-540 _
B09.011.075A ItC1F-1-1 10/29/91 CLR _
N REF. BSN 1991 RPV REPORT 10/29/91 CLR N B09.011.0758 itE1F-1-1 _
B09.011.075A IPE1F-2-1 10/28/91 CLR _
N REF. BEH 1991 RPV RFPORT 1NC1F-2-1 10/28/91 CLR N B09.011.0768 _
B09.011.07?A INC1F-3-1 10/19/91 CLR _
N REF. BSN 1991 RPV REPORT B09.011.077B INC1F-3-1 10/19/91 CLR _
N B09.011.078A IPC1F-4-1 10/28/91 CLR _
N REF. BEN 1991 RPV REPORT l
10/28/91 CLR N B09.011.078B ltC1F-4-1 _
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EPJALITY ASSURANCE DEPARTNENT PLANTJ MCGUIRE Utf17 1 PRE-SERVICE AND IN-SERVICE IPCPECTIO4 SYSTEM KEY: ITCH tAREER B09 MCGUIRE 1 It0ERVICE ItCPECTIO4 RESULTS SJTAGE 7 IPEPECTIO4 ItGPECTION INSPECTIO4 GES.
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10/28/91 CLR N BEN 1991 RPV REPORT SECT.3-18A B09.011.080A INCIF-2-8 _
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CLR N BSN 1991 RPV REPORT SECT.3-18A B09.011.081A IPC1F-3-8 10/28/91 ,
10/2.2/91 CLR N B09.011.0818 INC1F-3-8 _
10/28/91 CLR N 88N 1991 RPV REPORT SECT.5-18A B09.011.082A ItCIF-4-8 _,
10/28/9?. CLR N 609.011.0828 INC1F-4-8 _
10/21/91 CLR L Y B09.011.434 INI1F-643 INI1F-643 10/16/91 CLR N B09.011.434A _
INI462-1 10/23/91 CLR Y B09.011.435 _
INI462-1 10/16'91 CLR N l ,
809.011.435A _
10/21/91 CLR L Y B09.011.444 INI1F-645 10/16/91 CLR N B09.011.444A INIIF-645 _
10/16/91 CLR N B09.021.007 itCIF2-13A _
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ID Nt#SER DATE STATUS LIMITED REF. Ct9MENTS ITEM MDSER ========== ========== ==== ==============================
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10/16/91 CLR N B09.021.008 INCIF4-9A ,,
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F1.01.144 1-MCR-MC-9790 10/18/91 CLR _
N 1-NCR-9C-Oo 91 10/17/*1 CLR M F1.01.145 _ _. _
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1-MCR-NC-0792 10/17/91 CLN N F1.01.146 _
1-MCR-NC-C793 10/17/91 CLR. M F1.SI.147 _
F1.01.148 1-MCR-MC-9794 10/17/91 CR _
N F1.91.149 1-MCR-NC-0802 10/08/91 CLR _
N 1-!ER-4C-0803 CLR N F1.01.150 10/98/91' _
10/08/91 CLR M F1.01.151 .I M -MC-0804 _
1-MCR-tic-0885 10/08/91 . CLR M F1.91.152 _
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F1.01.155- 1-9ER-9C-08e8 10/98/91 CLR _
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N F1.01.449 1-t1CR-MI-0717 99/2 U91 CLR _
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N F1.01.453 1-t1CR-HI-0721 09/26/91 CLR _
N F1.01.454 1-MCR-NI-0722 09/2U91 CLR _
N F1.01.4!5 1-tCR-MI-0 /30 10/08/91 CLR _
N F1.01.456 1-fCR-NI-0 731 10/08/91 CLR _
N F1.01.457 1-tCR-NI-0732 10/08/91 CLR _
N F1.01.458 1-NCR-NI-0733 10/08/91 CLR _
N F1.01.459 1-NCR-HI-0 734 09/26/91 CLR _
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N 1-NCR-NI-0822 09/26/91 *LR N F1.01.499 _
1-f1CR-PG-0823 09/26/51 CLR N F1.01.500 _
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N 1-NCR-MI-0851 10/08/91 C1R N F1.01.515 _
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10/08/91 CLR- M F1.01.526 1-MCR W -Oe62 _
1-MCR-MI-Oe63- 10/08/91 CLR M F1.01.527 _
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1-9CR-MI-9901 09/Z u91 CLR M F1.01.560' ._
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F1.01.706 1-MCR-tN-1094 09/26/91 CLR _
N F1.01.707 1-MCR-fN-1095 3/26/91 CLR _
N 1-71CR-tN-1096 09/26/91 REC N F1.01.708 _
1-NCR-NV-1201 0*/26/91 REC N F1.01.709 _
ISGC-SUPPORT 10/13/91 REC N F1.01.806 _
IMA-CA-468 10/12/91 CLR N F1.02.036 _
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&#CGRAM: MISIRUND-QAISIo* DUKE FOMC2 CtyrANY PArt c1 FILE: COQ 7133 GtJALITY ASSURANCE DEPARTNENT DATE C 25/92 PLANT: MCGUIRE ONIT 1 PRE-SERVICE AND IN-SERVICE INSPECTIS4 SYSTEM KEY: ITEN PUBER F1. NCGUIRE 1 INSERVICE INSPECTI54 RERTS DJTAGE 7 INSPECTIJi DCPECTIS4 IN5PECTIO4 CE C.
ID PUBER DATE STATLG REF CtFffMTS ITEM SU BER.
=======sess 33 3=====,3 . e,3=====ws ======= .L..IMI.TE D er, 22_______________;____________
F1.02.076 1-NCR-CA-450 10/10/91 CLR _
N F1.02.077 1-McR-CA-451 10/11/91 CLR _
M a
F1.02.078 1-NCR-CA-479 0*/26/91 CLR _
N 3
F1.02.079 1-NCR-CA-480 10/11/91 CLR ,,
N F1.02.080 1-fCR-CA-481 10/10/91 CLR _
N F1.02.083 1-MCR-CA-485 10/11/91 CLR _
N F1.02.087 1-NCR-CA-4*O 10/10/91 CLR _,
M F1.02 088 . 1-NCR-CA-499 10/10/91 CLR _
N F1.02.089 1-NCR-CA-500 10/10/91 CLR _
N F1.02.091 1-NCR-CA-502 10/10/91 CLR _
N F1.02.092 1-NCR-CA-503 10/10/91 CLR _
N F1.02.093 1-NCR-CA-504 10/10/91 CLR ,
N F1.02.094 1-NCR-CA-505 10/10/91 CLR _
M F1.02.322 1-NCA-FN-121 09/10/91 CLR _
N F1.02.323 1-NCA-FM-122 09/10/91 CLR _
N
P-PROGRAMt MISINLSS-4AISIO4 SL5LE PtBE2 CtpFANY PAGE 42 FILE: CSD7133 . SJALITY ASSNtafEE BEPARTMENT DATE S2/25/92
. P*JNT:
. MCSUIRE 15ET 1 - PWE-SERVICE ASW IN-SERVICE INSPECT 1tpf SYSTEM KEY: ITEM PRDWER F1. MCGUIRE 1 IfRIERY1CE INSPECT 1tSt RESULTS SJTAGE 7 gm . .-
INSPECT 198 196PECTIM 196PECTISE GES.
ITEM ft#9ER- 10 98JPOER DATE STATUS REF. CtW9ENTS mes===eeres, m ========s==s.33== m ======= es======== .L.IM.I.TE0
.. m ==-3 ======m =,e== s-e===.
F1.02.324 1-4CA-FM-123 09/11/$2 CLR _
M F1.02.325 1-MCA-FM-124 09/10/91 CLR _
N 4 -
F1.02.326 1-MCA-FM-125 09/10/91 CLR _
N s ..
F1.02.429 1-MCA-pe-031 09/18/91 NEC _
N F1.02.467 1-MCA-98-072 09/18/91 REC _
N F1.02.473 1-NCA-95-078 09/17/91 NEC _
M F1.02.474 1-MCA-fe-079 09/17/91 CtX _
N F1.02.478 1-MCA-95-083 S9/17/91 CLR _
M F1.02.482 1-NCA-96-067 39/17/91 CLR _
N F1.02.483 . .1-MCA-96-008 09/18/91 REC _
M F1.02.487 1-MCA-fe-095 10/16/91 CLR _
M F1.02.488 1-MCA-96-694 09/17/91 CLR _
N F1.02.489" 1-MCA-95-995 09/18/91 NEC _
N
~F1.02.491" 1-MCA-SS-997 99/17/91 CLR _
M F1.02.493 " 1-9CA-95-099 99/10/91 'CLR _
M
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PROGRAM: NICIfRSS-441SIg4 SLKE PtBE) CN PAE 43 FILET COO 7133 smans YTY ammassrr gEPART7ENT DATE C2/25/92 PLANFt MCEUIRE 1881T 1 . PSE-scRVICE Afe IN-SERVICE INSPECTIED8 SYSTEM REYs ITEM 949eER F1. MCSUIRE 1 INGERVICE IM5PECTIt96 NESULTS OUTAGE 7 INSPECTItBE INSPECTItBf - INSPECT 1tst GES.
ITEM 3RSWER 19paseER DATE . STAT 7M LIMITED REF. CIWWENT3
==== -==_______e_________________;
mmme==emesse ==================== ========== mereest a __-_______
F1.02.494 ' 1-4CA-fe-100 99/10/91 CLR _
M F1.02.495 1-MCA-ND-101- 99/10/91 CLR _
N-
. e F1.02.496 1-MCA-fe-102 09/10/91 CLR _
N
. i
'F1.02.504 1-MCA-te-129 09/27/91 CLR ,
N F1.02.507 ' 1-tE'A-te-151 09/17/91 CLR _
N
.F1.02.509 1-MCA-fe-153 .09/17/91 CLR _
N F1.02.510 1-fCA-te-156 .,99/17/91 CLR _
M F1.02.529 '1-MCA-ter-264' 99/19/91 CLR _
N F1.02 531 1-MCA + 264 99/11/91 NEC ,
N 1-fECA-te-268 09/19/91 CLR **
F1.92.533 _
F1.02.541 1-fCA-le-276 ,09/19/91 CLR _
M F1.02.549 - 1-K A-te-294' 09/10/91 CLR _
N F1.02.550 1-MCA-88-285 09/10/91' CLR - _
-N F1.02.500 1-MCA-te-338 10/24/91 ~ CLR _
M 1-MCR-ge-510 16/10/91 . CLR _- M
-F1.02.5e4 t-
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' PRERMtAM: NES -4415I94 SERE PtBE3 CtppaNr PACE 44 FILET- COB 7135 est.ITY ausmasCE SEPARTPENT DATE C2/23/92 PLANTt- MCSUIRE 1881T 1 PRE-SEWVICE ape IM-SERVICE INSPECTItSt SYSTEPt KEYt. ITEM 3RaeER . F1. MCGUIRE 1 IBGEstVICE INSPECTitBS IIESULTS tRJTAGE T 4
IMSPECT*tpt INSPECT 1tpl INSPECTItpt GEff.
ITEM IRSSER 19 9479FR - SA STATUS LIMITED REF. CtpeqENTS
===== - ==== ========= = ====== e ==== TE.33s ==________ ====s===== ==== ======________________________
'F1.02.586 1-MCR M -512 09/26/91 CLR _
M F1.02.657 1-fCR-M1-561 09/26/91 CLR _
M-F1.GZ.658 1-PER-MI-542 99/26/91 CLR _
N F1.02.659 1-NCR-MI-563 C9/26/91 CLR _
M _
F1.02.661 1-MCR-MI-578 09/26/91 -LCLR _
M F1.02.663' 1-MCR-MI-656. 09/26/91 CLR _
M F1.02.664 1-MCR-MI-661 '0/13/91 1 CLR _
M ,
F1.02.665. 1-MCR-ME-663 89/26/91 CLR _
M F1.02.802 1-MCA-tes-015 89/19/91 CLR _
M F1.02.824 : 1-MCA-896-317 09/19/91 CLR _
M F1.02.825 1-NCA-156-1195 09/19/91 CLR _
k F1.02.826 1-MCA-fee-1165 09/19/91. CLR. _
M F1.02.829 1-fCA-IWS-2968 99/19/91 CLR _
M
'F1.02.8SS 1-MCA-858-2966 09/17/91 CLR ._ M F1.02.858 1-fCA-frV-233 99/17/91 CLR _
M _
PUNWRAM NIS -9413I04 OLRE PtBE2 CopaNT PAGE 45 FILER- . CSD7133 .- SUALITY LSSURd8CE DEPARTIENT EATO C2/25/92 PLAMit MCGUIRE UNIT 1 PRE-SERVICE A86 IM-SERVICE INSPECTION SYSTEM F.EY: ITEM MUPSER F1. MCEUIRE 1 IN2EVICE INSPECTION RESULTS SUTAGE 7 IMSPECTItWe IMSPECTItSt INSPECTitpt CES.
ITEM 9479ER 10ft#SER DATE STATUS LIMITED REF. Ct90ENTS e eess======msewe== _ -____e= ========== ========== em e m eesse m e -___________e-
e=
F1.02.876 1-MCA-SA-017- 09/2u91 IIEC _
M F1.02.MO . 1-MCA-SM-011 '10/10/91 CLR _
M NEC M F1.02.903 1-MCA-SM-015 10/16/91 _
F1.02.904 1-MCA-SM-023 10/16/91 IIEC _
N F1.02.907. 1-MCA-SM-068 09/26/91 REC _
M F1.02.906 1-MCA-SM-069 09/26M1 CLR _
M F1.02.910 1-MCA-SM-109 10/16/91 REC ,
N F1.02.911 1-MCA-SM-140 09/26/91 SEC _
M F1.02.956 1-MCA-SV-008 10/16/91 CLir ' _
M F1.02.999A 1ACCB-SKIRT 11/19/91 CLR L M 1-ftCA-CA-017 CLR M F1.03.011 86/25/91 _
F1.03.012' 1-MCA-CA-018 07/09/91 CLR _
M F1.03.013 1-MCA-CA-019- 07/09/91 CLR L M
-F1.03.045 1-MCA-CA-096 ' . 09/04/91 CLR _
M F1.03.066 1-#CA-CA-239 , 09/DU91 CLR _
M i .. .. .. . . . . . . - . .. . .. ..
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O P80GRAF: NISIRUPC-43AISIO4 DUKE PCHE"? C&1PANY CUALITY AS3JRAPCE DEPARTMENT PAGE 46 CSTE C2/25,"M FILE: CC07I53 PLANT: MCOUIRE e wTr ; PRE-SERVICE AND IN-SERVICE INCTI&4 SYSTEM KEY: ITEM PRJPSER F1. MCOUIRE I INSERVICE IPGPECTIT4 RISULT5 CL*TAGE 7 INSPECTICH 17CPECT1&f ItGPECTION GES.
ITEM FU BER ID MJPSER DATE STAT 1JS LIMITED REF. COPf1ENTS nezesse messes ==== ======= = =======e3= ==== ===w=3eewme=== m eeerewew===
==er======== ezee======s3 F1.03.067 1-NCA-CA-246 09/04/91 CLR _
N F1.03.068 1-NCA-CA-247 09/04/91 CLR ,
N F1.03.082 1-NCA-CA-284 09/04/91 CLR _
N 1-91CA-CA-293 09/17/91 CLR N F1.03.084 _
F1.03.085 1-NCA-CA-294 09/04/91 CLR _
N I
1-fCA-CA-298 06/25/91 CLR H i F1.03.089 F1.03.090 1-MCA-CA-299 06/25/91 CLR _
N F1.03.092 1-NCA-CA-301 07/09/91 CLR _
N 1-NCA-CA-302 07/09/91 CLR N F1.03.093 ,
1-f1CA-CA-358 09/04/91 CLR N F1.03.094 _
CLR N j F1.03.095 1-?CA-C8-491 09/04/91 _
1 F1.03.203 1-NCA-SA-023 07/26/91 CLR _
N F1.03.205 1-NCA-SA-027 09/10/91 CLR _
M 1-NCA-SA-029 09/10/91 CLR N F1.03.207 _
F1.03.21G 1-NCA-SA-106 09/26/91 CLR _
N
1 O s.o ci 1 te a ctie" a it-Examination were perf ormed during Outage 7 on the Reactor Vessel, Steam Generators 1A, IB, 1C and 10, Class 1 Piping of the Safety Injection (NI) and Reactor Coolant (NC) Systems, Valve Internal Surfaces and Class 1 Component Supports.
5.1 Reactor Vessel Three (3) Reactor Vessel Circumferential Shell Welds, nine (9)
Longitudinal Shell Welds, one (1) Circumferential Head Weld, six (6)
Meridonal Head Welds and Shell to Flange Weld (from Vessel ID O'-360',
Item No. B01.030.002) were volumetrically examined by remote ultrasonics during Outage 7. No reportable indications were found.
Four (4) Inlet Nozzle to Vessel Welds (Vessel and Nozzle ID examinations; Item Numbers B03.09.001, B03.090.001A : B03.090.002, B03.090.002A ; B03.090.003, 803.090.003A ; 803.090.004 and B30.090.004A) ,
with respective Nozzle Inside Radius Section (Item Numbers B03.100.001, '
B03.100.002, 803.100.003 and B03.100.004) and with respective Nozzle to Safe-End Butt Welds from Nozzle Side and Safe-End side), item Numbers B05.010.001, B05.010.001A ; B05.010.003, 805.010.003A ; B05.010.005, B05.010.005A, B05.010.007 and B05.010.007A) and with respective Safe-End to Pipe Welds (UT from Safe-End and UT from Pipe side) B09.011.079A, 809.011.0798 ; B09.011.0 BOA, B09.011.080B ; B09.011.081A, 809.011.081B ;
B09.011.082A and B09.011.0828 were examined by remote ultrasonic techniques during Outage 7. No reportable indications were found.
Four (4) Outlet Nozzle to Safe-End Butt Welds (UT from Pipe Side, item Numbers B09.011.075B, B09.011.076B B09.011.0778 and B09.011.0788) were examined by remote ultrasonic techniques during Outage 7. No reportable indications were found.
The Shell to Flange Weld (from flanga surface 180'-360') was manually examined by ultrasonics during Outage 7. No reportable indications were found.
Four (4) Outlet Nozzle to Vessel Welds (including respective Inside Radius Sections, Nozzle to Safe-End Butt Welds and Safe-End to pipe circumferential butt welds, as shown below) were re-examined by remote ultrasonics per Duke Power Company's Request for Relief MNS-004, item No. 10 No. Description Nozzle to 803.090.005A 1RPV5-445E Outlet Noz. E to Shell (Noz 10)
Vessel Weld B03.090.006A 1RPV5-445F Outlet Noz. F to Shell (Noz, 10) 803.090.007A 1RPV5-445G Outlet Noz. G to Shell (Noz 10)
B03.090.00BA 1RPV5-445H Outlet Noz. H to Shell (Noz,10)
Nozzle B03.100.005- 1RPV5-445ER Inside Outlot Noz. E to Shell (Vessel 10)
B03.100.006 1RPV5-445FR Outlet Noz F to Shell (Vessel 10)
Radius B03.100.007 1RPV5-445GR Section B03.100.008 Outlet Noz G to Shell (Vessel 10)'
1RPV5-445HR Outlet Noz. H to Shell (Vessel ID)
EQA388 Page 1 Revision 0 January. 31, 1992
i O 11em ue. 10 Ne. Descriatien Nozzle to B05.010.011 1RPV3-445E-SE Outlet Noz. E to Safe-End (Noz. Side)
Safe-End 805.010.011A 1RPV3-445E-SE Outlet Noz. E to Safe-End (S.E. Side)
Butt Wolds B05.010.009 1RPV3-445F-SE Outlet Noz. F to Safe-End (Noz. Side)
B05.010.009A 1RPV3-445F-SE Outlet Noz. F to Safe-End (S.E. Sido)
B05.010.015 1RPV3-4450 SE Outlet Noz. G to Safe-End (Noz. Side)
B05.010.015A 1RPV3-445G-SE Outlet Noz. G to Safe-End (S.E. Side)
B05.01d.013 1RPV3-445H-SE Outlet Noz. H to Safe-End (Noz. Side)
B05.010.013A 1RPV3-445H-SE Outlet Noz. H to Safe-End (S.E. Side)
Nozzle B09.011.075A INC1F-1-1 Outlet Noz. E (S.E. Side)
Safe-End to 809.011.076A INC1F-2-1 Outlet Noz. F (S.E. Side)
Pipe _ Weld B09.011.077A INC1F-3-1 Outlet Noz. G (S.E. Side)
B09.011.078A INC1F-4-1 Outlet Noz. H (S.E. Side)
These examinations met the requirements of 1989 ASME Section XI Code.
Credit will be applied to the Second Inspection Interval, First inspection Period requirements for the Outlet Nozzle-to-Vessel Welds.
Table IWB-2500-1 Category B-0. No reportable indications were found. A copy of the Request for Relief MNS-004 is included in Section 10 of this report. The examinations are described in more detail in the Babcock and Wilcox "1991 Reactor Vessel Examination Report" summary included in Section 10 of this report.
O Seventeen (17) Stud Hole Threads in the Reactor Vessel Flange received an ultrasonic examination. No reportable indications were found.
The accessible internal surfaces of the Reactor Vessel were inspected by remote visual methods. No reportable conditicns were found.
The Reactor Vessel Core Support structure was visually inspected after removal from the vessel. No reportable conditions were found.
5.2 Steam Gererators Steam Generator 1A and IB Primary Manway Bolting received a visual examination. Reportable conditions were found.
Steam Generators 1A, 18 and 10 Primary Manway Bolting located at "WX, ZW"; "XY, YZ"; and "XY, "YZ" respectively received a visual examination.
Reportable conditions were detected (Item Numbers B07.030.001, B07.030.002, B07.030.003 and B07.030.004). Refer to Problem Investigation Report 1-M92-0022 included in Section 9 of this report.
The scope of the inspection was extended per ASME Section XI, Paragraph IWB-2430(a) to include the bolting in Steam Generator 10. The inspection data sheets are included in this section of the report. No other reportable conditions were found.
5.3 Piping Dissimilar Metal Butt Welds:
Four (4) dissimilar metal butt welds, nominal pipe size four inches and greater received an ultrasonic and a dye penetrant examination. No reportable indications were found.
EQA388 Page 2-Revision 0
. January .31, 1992- _
j
i Similar Metal Welds:
Nominal pipe size four inches and greater:
Six (6) circumferential butt welds received an ultrasonic and a dye penetrant examinatien. One (1) circumferential butt weld received an ultrasonic examination. No reportable indications were found.
Nominal pipe size four inches and smaller:
Three (3) circumferential butt welds, three (3) branch pipe connection welds and five (5) socket welds received a dye penetrant examination.
No reportable indications were found.
Piping Supports:
Eighty-five (85) Class 1 Component Supports received a visual '
examination as required by ASME Section XI. Article IWF-2000. No reportable conditions were found.
5.4 Valv_ej -
The internal surfaces of valves IND-2A.C, IN!-125, and 1N1-157 received a visual examination. No reportable conditions were found.
The pressure retaining bolting in valves 1N!-157 and INI-160 received a O visual examination. No reportable conditions were found.
5.5 Steam Ger:erator Tubing 1he inconel 600 tubing in the four Westinghouse Model D2 recirculating steam generators (RSG's) - A, D C and D at Duke power Company's McGuire UnitIwereexaminedbyeddycurrenttechniquesduringOctober/
1991. The tubing in the generators measure $ 0.750 nominal November outside diameter X 0.043" nominal wall thickness. The examinattuns were performed by personnel from Duke Power Company, B&W Nuclear Services (BWNS) Company and Zetec, Inc. during the 7th Refueling Outage.
The following is a summary of the results of the bobbin coil and rotating eddy-current examinations for each generator. A detailed description of the McGuire 1 Refueling Outage 7 eddy current inspection is provided in the October / November 1991 Eddy Current Examination Report on file in the Corporate Office in Charlotte, North Caiolina.
RSG A Eddy Current Examinations began in RSG A on 10/1/91 and were completed on 10/11/9).
6,472 tubes were examined full length by bobbin coil, 2 tubes
\ colitained indications 40% thru-wall (TV) or greater; L6 tubes contained indications 20-39% TW.
EQA388 Page 3 Revision 0 January 31, 1992
__ _ _ _ _ _ . - _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ _ _ - - ~ _ _ _ .
t ,
i O -
4 aoa "oties tebe>8eets "# 4.472 ceidi 9 t#6 sheet with SM-15; 247 hotleg tubes,14 coldleg tubes and 112 U-Bends were ere 4"ed ,
examined using MRPC.
- 166 hotleg (HL) and 172 coldleg (CL) rolled plugs were examined using MRPC,
- 163 previously installed sleeves were inspected with a .510" bobbin coil and also with BWNS Eddy-360 rotating crosswound probe, i
26 tubes were removed from service by plugging. 145 tubes were
~
repaired by sleeving. Of the 145 tubes repaired by sleeving, 137 of these were 17.5" sleeves while the remaining 8 were 11" sleeves. .
RSG B Eddy Current Examinations began in RSG B on 9/31/91 and were * .
completed on 10/14/91.
4.398 tubes were examined full length by bobbin coil; L6 tubes contained indications 40% TW or greater; 20 tubes contained indications 20-39% TW.
4,314 hotleg tubesheets and 4.398 coldleg tubesheets were examined by SM-15; 239 hotleg tubes,1 coldleg tube and 107 U-Bends were ;
examined using MRPC. .
255 hotleg and 251 coldleg rolled plugs were examined using MRPC.
84 previously installed sleeves were inspected with a .510" bobbin coil and also with BWNS' Eddy-360 rotating crosswound probe.
22 tubes were removed from service by plugging. 95 tubes were repaired by sleeving. Of the 95 tubes repaired by sleeving, 85 of these were 17.5" sleeves while the remaining 10 were 11" sleeves.
RSG C Eddy Current Examinations began in RSG C on 9/30/91 and were
. completed on 10/12/91,.
4,393 tubes were examined full length by bobbin coil; il tubes contained -indications 40% TW or- greater; 27 tubes contained indications 20-39% TW.
4.393 hotleg tubesheets and 4,394 coldleg tubesheets were examined l
by SM-15; 248 hotleg tubes,19.coldleg tubes, and 106 U-Bends were
examined using MRPC.
260 hotleg and 259 coldleg rolled plugs were exc. mined using MRPC.
O -
there were mo orev4eusiv iestailed sleeves in RSa C.
EQA388 Page 4 Revision 0 "
January 31, 1992
_ _. _ _ . _ __ _ _u _ _ 1 _. .- _. _
13 tubes were removed from tervice by plugging. 97 tubes were O repaired by sleeving. Of the 97 tubes repaired by sleeving, 86 of these were 17.5" sleeves while the remaining 11 were 11" sleevas.
R$G D Eddy Current Examinations began in R5G D on 9/29/91 and were completed on 10/14/91.
4,399 tubes ' w examined full length by bobbin c oil , 5_6 tubes contained ins ions 40% TW or greater; 5 tubes contained indications 20-N TW.
4.249 hotleg tubetheats and 4,399 coldleg tubesheets were examined by SM-15; 221 hotleg tubes, 8 coldleg tubes, and 101 U-Bends were examined using MRPC.
249 hotleg and 255 coldleg rolled plugs were examined using MRPC.
150 previously installed sleeves were inspected with a .510" boobin coil and also with BWNS Eddy-360 rotating crosswound probe.
19 tubes were removed from service by plugging. 122 tubes were repaired by sleeving. Of the 122 tubes repaired by sleeving, 115 of these were 17.5" sleeves while the remaining 7 were 11" sleeves.
O 5.6 System Hydrostatic Test The Class 1 Pressure Boundary was sobjected to a system hydrostatic test as required by ASME Section X1, Table IWB-2500-1. No reportable conditions were found.
The Cla.ss 1 Inservice Hydrostatic Tests required by ASME Section XI.
Table IWB-2500-1, Category B-P, were not completed before the end of the inspection interval. The increased on-line time of Unit I reduced the number of scheduled refueling outages needed to perform the required tests scheduled in the McGuire 1 Inservice Inspection Plan, Refer to Duke Power Company Request for Relief 90-02 included in Section 10 of-this report.
5.7 Class 1 Repairs and Replacements IIeTairs and replacements for work performed from May 18, 1990 to December 7, 1991 are itemized in Section 11 of.this report, s
O EQA388 -Dage 5 Revision 0 January 31, 1992
FORM OCL+13A REV.2 OUKE PpWCR COMPANY STATION N(O4In _ UNIT __OSC 151 VISUAL EXAMIN ATION, VT.1 693/7C PT Pn. I e 1 INSPECTOR LEVEL DATE: PROCEDURE: REV:
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ANil REVIEW v DATE fbN
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QA REVIEW
DATE / 8 7" N/'_. ;
j. FORM OCL 13A REV. ?
DUKE WER COMPANY STATION R/ '0f UN.T-ISI VISUAL EXAMINATION, VT.1 dI/J //g Page - > of- -
INSPECTOR LEVEL DATE: PROCEDURE: REV:
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IN INDCA ON LENGTH WID H N vp REMARKS Alon '
O RESULTS: [ ACCEPTABLE "" UNACCEPTABLE, REQUI AES NDE/ EVALUATION OR REPAIR COMMENTS / DISPOSITION:
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~
, DATE QA REVIEW l \- 0 TE / I / '
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SW EC flELO SYSTEM (TN) (vet. 3.0) "" Wednesday Novenber 20, 1991 2:40 PM "" BABCOCK & WILCOX Co. "** Page '1 O
Steam Generator A
{) ett McGuire age LhltRF0 09/91 1, CJERY: 80881N C0ll INDICAfl0NS 44100% TWD 3
.......... ROW TEST
... ...COL INO ITW VOLI$ CNN DEC LOCAfl0N
... ... ...'.. ... ... ........................ ........ ....... 1....
EXTENT LEG APE ANLST PRB CoetENTS ROBBIN 2 71 101 40 3.'36 17 0 TTS HL + 0.00 71H TSP TE HL 1 C90% 610 E0talN 3 55 IDI 40 17.61 1 16 TE ML + 1.57 71N TSP TE ML 2 P2204 610 9068tN 9 92 101 40 f 81 17 0 T15 ML + 0,00 FL 1E CL 29 C9055 610 BOBBIN 10 68 101 40 ?).04 17 0 TTE HL
0.00 FL TE CL 28 C90% 610 BOUSIN 18 86 IDI 58 9.99 1 23 TE HL + 17.17 FL TE CL 23 K1443 610 80 Balk 24 61 101 40 2.73 17 0 TTS HL + 0.00 FL TE CL 20 N1603 610 806 BIN 26 67 WAt 40 2.36 20 0 3AVB + 0.00 FL TE CL 75 L5914 610 80 GRIN 33 42 001 77 1.30 1 70 BTH TSP + 1.44 FL TE CL 77 L5914 590 BG181N 39 72 101 40 2.42 17 0 TTS HL + 0.00 TL TE CL 8 R6878 610 TOTAL TUBES FOUND a 9 TOTAL INDICATIONS FNND = 9-TOTAL TUDES IN INPtri FILE a 4674 2
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t&W EC FIELO $Y$1EM (TM) (VER. 3.0) *"* Wethesday Novedwr 20, 1991 3:44 PM *"* BABCOCK & WILCOX Co. "** Page 1 (O>/-oseints 09/91 McGuire RF0 Unit 1 Steam Generetor 8 outRT: Bost!N C0ll trDicAfl0ms 40 100% ine TEST EXTENT TAPE ANLST PR5 COMMENTS RCW ...COL
... IND Fi' VOLTS CHN DEG LOCAfl0N.. ..,. ~. ........................ ........ LEG 30881N 2 94 10' eA E:1 1 26 TE ML + 11.70 7T4 TSP TE ML 1 03858 610 0000lN 3 1 Ir. f5 21 1 26 TE ML + 9.17 71H TSP TE HL 1 W2218 610 80841N 3 47 1 ' , 2.81 1 18 TE ML *' 8.01 .TTH TSP T&*HL 2-.H3464 610 00Li 4 ?
2 lb. M 9.21 1 27 TE*HL + 9.14- FL .TE CL 30 P2204 610-00Bitu e' 23 101 48 6.55 1 19 TE ML + 17.18 FL TE*CL . 69 P6444 610-BoestN 1 29 IDI 80 9.60 - 1 32 TE=NL + 10.57 FL' T( CL L 69 K1443 610 90881N 7 42 IDI 40 4.93 1 %6 TE l:L + 17.22 FL TE CL 69 P6444 610 00881N 7 78 IDI 40 3.72 17 O TTS ML + 0.00 FL TE CL 67 LO211 610 Boselu 8 46 IDI 55 6.45- 1 22 TE ML + 16.18 FL TE.CL- 34 $6961 610 00Batu 8 56 IDI 43 7.48 1 1.E*HL + 14.18 FL TE CL 34 -$6961 610 toesth 8 58 101 40 4.59 1 16 TE HL - + 15.35 FL - TE CL 67 -LO211 610 0000lN 8 68 IDI '40 5.76 17 0 TTS ML + 0.00- FL TE CL 67 LO211 610 loseIN 8 69 001 63 0.72 17 70 2ND TSP + 0.05 FL - TE*CL (? LO211 610 4 B0041N 12 29 101 74 8.48 1 29 TE.HL + 3.07 FL- TE CL 3i LO211610 - '
30ealN ; -15 15 IDI 56 2.03 1- 91 TE ML + 15.73 FL . TE CL 28 64260 610 ;
BotetN 22 18 101 83 10.31 '1- 33 TE ML + 5. 73 FL -TE CL 23- 31603 610 ...
ente!N 24 23 001 71 0.86 17 57 1st TSP + 0.08 IST TSP TE CL- T?756 610 +-
BOBBIN 24- 28 101 58 8.59 1 23 TE ML- +--9.32 FL TE CL 22.. K1(43 610 SOB 81N 28- 85 IDI 88 7.56 1 -35 TE ML + 11.45 FL TE CL 51 N16L3 610 80881N . -
IDI 85 8.21- 1 34 TE*HL + 18.22 FL TE CL 51 .N1603 610 00selu 33 19 101- 44 4.82 1 17 TE ML + 15.30 FL TE CL 14 M0155 (10 80881N 101' 72 4.63 1 28 TE HL + 18.20 - FL TE CL 14 M0155 6s'0 B0881N 35 99 IDI- 80 16.92 1 32 TE ML +-5.37 JFL TE CL - 47 11756 61G 8088tM - 39 . 76 mt 50-4.17 20 0 2AVB--- + 0.00 FL 'TE CL 77:P6444 590 -
BOBBIN -40 54 001 61 0.46 17 77 2ND TSP + 0.15 1ST TSP TE CL 72 P6444 610 80selu 42 73 WR 45 5.15 20 - 0 3Avs . + 0.00 FL TE CL- - 77 K1443 590 BOSSIN 44 82 101 75 23.16 1 30 TE*HL + 3.54 FL TE CL '42 N1603 610 SOBSIN 66 36 ODI 73 1.56 17 50 1st Tsp + 0.05 FL TE CL - 6. P2204 610 0 TOTAL TUSES FOLM TOTAL INDICAT10W5 FOUND TOTAL TUSES IN INPLT FILE e 4674
=
e 26 28 1
i
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" C&W EC FIELD SitTEM (TM) 6Ek. 3.0) "** Thursday Novaber 21, 1991 10:09 AM "** BARC0CK & WILC0x CO. "** Pese 1-amt McGuire Unit 1 Stems Generators C p - ise 09/91 RF0 QUERT: tottlW Coll INDICATIONS 40 1003 T W TEST RCW COL IND ETW VOLTS CHN DEG LOCATION EXTENT LEO TAPE ANLST PRS C0petENTS
.......... ... ... ... ... ..... ... ... ........................ ........ ....... .... ..... ... w........
90stlN 5 63 101 40 9.75 17168 iTS-kt- + 0.00 FL TE CL- 22 'N3921 610 8000ls. - 14 61 101 - 63 7.09 1 25 'iE ML + .6.31 FL - TE CL -26 $6961 610
90881N 14 69 101 55 6.63 1' 22 TE ML + 7.38 FL TE CL 26 46961 610 DOBSIN 14 97Cel 50 1.25 1 101 17TN TSP + 13.75 FL TE CL 27 s6961 610 80581N i4 98 IDI 75 4.40 1 30 TE ML + 14.14 FL TE*CL- 27 S6961 610
.DottlN 15 105 101 64 6.22 1 25 TE NL + 9.48 FL TE CL 25. N1603 610 poselu 15 112 IDI 99 17.70 1 40 '* CL + 1,77 FL TE CL 25 N1603 610 00PSIN 18 58 101 s.O 3.73 17 C HA ML + 0.00 FL TE CL 23 89540 610 BOA 81N 19 78 101 44 6.52 17 15 YE ML + 4.47 FL TE CL 23 .39540 610 BOB 81N 27 66 101 43 3.43 1 17 TE*NL + 11.47 FL TE CL 16 P9540 610 80881N 27 104 1DI 40 3.49 17 0 TTS NL + 0,00- FL 1E CL .16 N3921 610 BOSSIN 36 70 101- 50 2.37 1 20 TE NL + 7.25 FL TE CL 10 D3162 610 tottlu 38 39 Walt 51 5.88 20 0 3 Avg
0.00 TTH TSP : TE CL 71 P2204 610 00881N 38 40 WAR 47 4.36 20 0 3Avs + .0.00 TTN TSP TE CL . 71 W6871 610 80581N 39 36 WAR 45 4.13 20 0 2AVS -+ 0.00 TTN TSP TE CL' . 71 P2204 610 _
39 44 WIA 42 3.54 20 0 2AVs TTN TSP TE CL - 71 P2204 610
~
80881N t-0.00 -.
BOSSIN - 42 79 101. 48 4.59 1 19 TE ftt' + 11.62 fL 1E CL 6 B5534 610 '
TOTAL TUDES FOUND = 17 TOTAL INDICATIONS FOUND a 17 TOTAL TUBES IN INPUT FILE = 4674 * ,
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B&W EC FIELD SY$1EM (TM) (VER. 3.0) **** Thursday Novemoer 21, 1991 10:59 AM **** BABCOCK & WILCOX Co. **** P*De 1 gnt McGuire Unit 1 $ team Generator: D ige: 09/91 RF0 QUERYs bO681N INDICATIONS 40-100% TWD TE$T ROW Cot IND %7W YOLTS CHN CTG LOCAY10N EXTENT LEG T APE ANLST PR6 CO% HEN 13 BOBBIN 2 29 IDI 48 5.64 1 19 TE HL + 5.52 TTN TEP TE-ML 1 B3720 610 BOBBlW 4 41 101 65 15.42 1 26 TE... + 1.77 FL TE-CL 35 K1445 610 BOBBIN 5 69 101 60 4.09 1 24 TE HL + 10.68 Ft. TE-CL 70 R6878 610 B008tN 8 23 101 70 19.35 1 28 TE-ML + 2.62 FL TE CL IP L6878 610 BOC8th 8 74 IDI 65 7.04 1 26 TE HL + 6.79 FL TE CL 66 N1603 610 BOBBIN 8 76 IDI 85 11.94 1 34 TE Ht + 10.56 FL TE-CL 68 N1603 410 BOCSIN 9 15 IDI 78 3.57 1 31 TE CL + 15.60 FL TE CL 35 K1443 610 8088tN 10 85 IDI 63 9.09 1 25 TE-HL + 11.66 FL TE-CL 67 P22D4 (10 BOBSIN 11 16 101 45 11.32 1 18 TE HL + 3.76 FL TE CL 75 K1443 610 BOS8IN IDI 40 1.23 17 0 TTS HL + 0.00 FL TE-CL 75 K1443 610 B06 BIN 11 85 IDI EB 9.26 1 35 YE HL
9.72 fi TE-CL 66 W1603 610
- B0081W 13 11 IDI 48 9. 08 1 19 TE ML + 12.69 FL TE CL 31 56961 610 BosBIN 13 65 101 63 7.51 1 25 TE ML + 8.59 FL TE CL 65 M0155 610 BOBBIN 14 80 101 59 6.27 1 23 TE-HL + 9.55 FL TE-CL 64 M0155 610 B0081N 16 16 IDI 41 8.78 1 18 TE CL + 12.29 IST TbP TE CL 4 h3021 610 BOBRlW 16 21 IDI b8 6.65 1 35 TE ML + 17.05 FL TE CL 75 N1603 610
B0081N 17 24 IDI 78 4.09 1 31 TE HL + 13.44 FL T[ CL 28 85534 610 '
BOB 81N 19 62 IDI 55 14.98 1 22 TE-ML + 13.51 FL TE CL 61 R6878 610 6008tN 20 24 IDI T3 2.93 1 29 TE HL + 8.58 FL TE CL 26 P2204 610 B0881N 20 55 101 40 3.15 17 0 TTS ML + 0.00 FL TE-CL 26 L5914 610 Boa 8IN 22 78 IDI 85 10.77 1 33 TE HL + 17.88 F1 TE CL 58 N1603 610 BOCBIN 23 56 101 48 4.52 1 19 TE HL + 10.03 FL ?E CL 24 L5914 610 B008tt 23 92 IDI 48 7.07 1 19 TE HL + 7.13 FL TE CL 57 M0155 610 BOBalN 24 12 101 TO 3.58 1 28 Tt CL + 16,93 FL TE-CL 23 T1756 610 BOBBIN 25 54 IDI 56 10.76 1 23 TE ML + 11.36 FL TE CL 22 K1443 oio B0881u 26 17 101 40 12.12 1 16 TE HL + 11.91 FL TE CL 21 D8021 610 B0BBIN 26 66 IDI 68 4.51 1 27 IE ML 4 10.57 FL TE-CL 55 $6961 610 bOSSIN 27 30 IDI 40 7.50 1 16 TE ML + 10.27 FL TE CL 20 M0155 610 B 27 69 IDI 75 14.16 1 30 TE ML + 3.71 FL TE-CL 55 S4961 610 0081N 29 44 101 55 6.92 1 21 TE-HL + 1.63 9'OBBIN18tN 29 46 101 53 4. T8 1 20 TE HL + '. . 72 FL FL TE CL TE-CL 18 K1443 610 18 K1443 610 BIN 29 66 IDI 75 4,54 1 30 TE HL + 13.52 FL TE CL 53 H3921 610
.vdetN 30 44 101 63 4.31 1 25 TE HL + 16.72 FL TE CL 17 $6961 610 BosalN 30 61 IDI 48 4.04 1 19 TE-HL + 5 81 FL TE CL 52 R6878 610 80081N 30 77 101 45 12.01 1 18 TE-HL - 13.22 FL TE-CL 52 R6878 610 BOBBIN 31 70 IDI 50 10.58 1 20 TE-HL + 4.31 FL TE CL 52 R6878 610 BOBBlW 32 43 101 $8 3.19 1 23 TE ML + 6.01 FL TE CL 15 56961 610 B0681N 32 52 001 80 1.11 17 59 1ST TSP + 0.03 1ST TSP TE-CL 3 L5914 610 BOBBIN 33 23 101 55 2.92 1 22 TE HL + 11.22 FL TE CL 15 56961 610 Bos0lN 33 33 101 70 2.71 1 28 TE HL + 17.24 FL TE CL 15 56961 610 80081N 33 83 101 55 14.53 1 22 TE ML + 9.67 FL TE CL 50 S6961 610 B0881N 35 53 101 40 1.69 17 0 TTS Ht + 0.00 FL T CL 15 85534 610 BOBBIN 35 65 IDI 68 5.37 1 27 TE HL
14.30 FL TE CL 49 56961 610 B0081N 37 26 101 58 8.40 1 23 TE ML + 11.31 FL TE-CL 12 T1756 610 BOBBlW 37 63 IDI 70 7.35 1 20 TE-ML + 12.77 FL TE CL 47 56961 610 BOCBIN 37 86 IDI 53 4.94 1 21 TE HL + 12.69 FL TE CL 47 Sav61 610 BOBBIN 38 24 IDI $8 5.35 1 23 TE HL + 16.59 FL TE-CL 11 85534 610 B0081N 38 46 IDI 88 2.87 1 35 TE HL + 15.61 (L TE CL 81 H3921 610 BOB 8IN 39 45 IDI 65 4.38 1 26 TE-HL + 9.63 FL TE CL 11 B5554 610 B0081N 39 75 101 95 6.00 1 33 TE-HL + 11.29 FL TE-CL 77 M0155 610 SOGBIN 39 54 101 68 3.62 1 2T TE HL + 12.55 FL TE CL 45 N1603 410 R0081R 40 41 IDI 65 6.86 1 26 TE HL + 18.13 FL TE CL 10 R6878 610 B00BlW 40 62 IDI 48 5.05 1 19 TE HL + 12.44 FL TE-CL 45 N1603 610 BOBSIN 42 25 101 40 5.99 1 16 TE HL + 16.25 FL TE CL 9 P2204 610 B08 BIN 45 26 101 65 1.51 1 26 TE HL + 11.26 FL TE CL 7 R6878 610 BOBBIN 47 42 IDI 93 20.69 1 37 TE HL + 1.50 FL TE-CL 6 P2204 610 80881N 49 62 101 55 7.24 1 22 TE-HL + 14.28 FL TE CL 19 H3921 610 TOTAL TUSES FOUND = 56 TOTAL INDICATIONS FOUNO = 57 TOTAL TUBES IN INPUT FILE = 4674 9
i n
6.0 Class 2 Inspection Results inspections were performed during Outage 7 on Steam Generator IC, Residual Heat Removal Heat Exchanger lA, Safety Injection Accumulator Tank 1A, piping integrally welded attachments, piping welds in Auxiliary Feedwater (CA), Main Feedwater (CF) and- Main Steam (SM) Systems and on Class 2 Component Supports.
6.1 Steam Generators and Residual Heat Removal Heat Exchan_qers Steam Generator IC Lower Shell to Transition Cone Weld received an ultrasonic examination. No reportable indications were found, Residual Heat Removal Heat Exchanger 1A Nozzle Belt to Flange, and Head Welds received a radiographic examination. No reportable indications were found Residual Heat Removal Heat Exchanger IA Inlet Nozzle "A" and Outlet * ,
Nozzle "B" and reinforcing pads received a dye penetrant examination.
No reportable indications were found.
One (1) Residual Heat Removal Heat Exchanger IA support received a dye penetrant examination. No reportable indications sere found.
6.2 p i_pi ng Welds one-half inch and less nominal wall thickness:
Four (4) circumferential welds and one (1) longitudinal weld received a magnetic particle examination. No reportable indications were found.
Welds greater than one-half inch nominal wall thickness:
Seven (7) circumferential welds received an ultrasonic and a magnetic particle examination. No reportable indications were found.
Piping integrally-welded attachments:
Five (5) attachments received a magnetic particle examination, No reportable indications were found.
6.3 Component Supports Seventy-five (75) Class 2 Component Supports received a visual examination as required by ASME Section XI, Article IWF-2000. No reportable conditions were found.
6.4 System st or Component Functional / Hydrostatic Tests Class 2 Hydrosh tic Tests were performed as required by ASME Section XI, Table IWC-2500 1. No reportable conditions were found.
O)
(_
.EQA388 Page 1 Revision 0 January 31, 1992
l The Class 2 Inservice Hydrostatic Tests required by ASME Section XI.
Table IWC-2500-1 Category C-H, were not completed before the end of the inspection interval. The increased on-line time of Unit I reduced the number of scheduled refueling outages needed to perform the required tests scheduled in the McGuire 1 Inservice Inspection Plan. Refer to Duke Power Company Request for Relief 90-02 included in Section 10 of this rt. port.
6.5 Class 2 Repairs and Replacements Repairs and replacements for work performed from May 18, 1990 to December 7, 1991 are itemized in Section 11 of this report.
'd
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o EQA388~ Page 2 Revision 0 January 31, 1992 j
_ _ _ _ _ _ _ _ _ _ _ _ - . . - - - i
i 7.0 Augmented Inspection Results l Augmented inspections were performed on Reactor Coolant Pumps IA and .
ID Flywheels, Steam Generator Tube Preheater Sections, Reactor Coolant System for Pipe Rupture Protection. Steam Generator 1B Feedwater Modification, Thermal Stress Piping (NRC Bulletin 88-08) and on Safety Injection Accumulator Nozzles (NRC IE Notice 91-05, Attachment 1).
l 7.1 Reactor Coolant Pump Flywheels I
t Reactor Coclant Pump 1A and ID Flywheels received an ultrasonic examination. No reportable indications were found.
7.2 Steam G,anerator Tube Preheater Section All four Steam Generators were examined by Eddy Current methods. _
Results are shown in Section 5 of this report. No reportable - ,
indications were found.
7.3 Pipe Rupture protection Three (3) welds in the Reactor Coolant (NC)- System recaived an ultrasonic and a dye penetrant examination. No reportable indications were found.
7.4 Steam Generator Feedwater Modification A visual examination was performed on Steam Generator 1B Feedwater Modification. No reportable conditions were found, l 7.5 Thermal Stress Piping Examinations Twelve (12) welds: and three (3) bends were examined by ultrasonic
! volumetric examination on Reactor Coolant System (NC), as required by l USNRC Bulletin 88-08. - No reportable inoications were found. -
7.6 Safety Injection Accumulator Nozzles l Safety Injection Accumulator 1A,18,1C and ID Nozzles received a dye l
penetrant examination in accordance with NRC- Information Notice No.
l 91-05, Integrandular Stress- Currosion Cracking in Pressurized Water l Reactor Safety Injection Accumulator Nozzles. No re' portable indications l were found.
l l
EQA388 Page 1 Revision 0 January 31,-1992
1 8.0 Personnel t Equipment and Material Certifications All personnel who performed or evaluated the results of inservice inspections from May 17, 1990 to December 7, 1991 at McGuire 1 were certified in accordance with the requirements of the 1980 ASME Section XI with Addenda through Winter 1980. The appropriate certification record for each Duke Power Company inspector is on file at McGuire Nuclear Station or in the Corporate Office in Charlotte, North Carolina, 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 & Wilcox offices in Lynchburg, Virginia.
Records of periodic calibration of Duke Power Company inspection equip-ment are on file at McGuire Nuclear Station or in the Corporate Office in Charlotte, North Carolina. '.
8.1 Personnel,_E_quipment and Mat erial Certifications - Eddy Current Testing See Duke Power Company Eddy Current Examination Report, McGuire Nuclear Station. October / November 1991, on file at the Corporate Office in-Charlotte, North Carolina.
O O
E0A388 Page-1 Revision 0 January 31, 1992
6 9.0 Problem Investigation Reports A copy of each Problem Investigation Report resulting from reportable items, originated against scheduled inservico_ . inspections performed during Outage 7, is included in this section. _All were- resolved and found acceptable before returning Unit 1 to service. The following Problem Investigation Report was issued:
P.I.R. NO. DESCRIPTION DATE ISSUED 0-M91-0174 - Class 2 Nozzles - 10-04-91 Acceptance Ci-iteria 1-M92-0022 Steam Generator 1A and IB 01-23-92 Manway Bolting
^
O Lo EQA388 Page.1 Revision 0 January.-31, 1992 l
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POWER CopWANY NUCLEAR STATION 08t08LEM INVEST!GATION RPPORT. SERJAl. No. O./>19/w a7v STATION M rla u'w t, l.ER N0.
1. Problem Occurred Time /Date: kw kw ou?" Discovsred" Time /Date: 9ffI(/ ty! 30 Unit (s): /f2. Unit Status At Time =Progles.0ccurred/Discoveret:' net ocoe(
Cescription ane cause of Problem: Arabladba s dis e oveved at & upe h d ofric cov aaetisnenMaGuM / recevm. h wee PiR t4 - o t i _ co t 3_.
. Du v%1 ea u'. . a a A .c t z., Dea i+ wu cr.1 uu.vei _. u i n m o 6+i ewr h a,,. et henw onc b = M &r u _
he u.w o not a cc ec-hs ca. s-w nde rd s -b / nen t e +c im sn. I pe \dLs; . MLThe & NDE d a c u w k 4 h .,- & Mer.u;n is, & & Q t.ocation of Procles: A Ce u' ce .
Metnod-Used To Discover Problem: ee ero* *. _I s n a o '. ew o coceis.
Imediate Corrective Actions Taken/To Be Taken: h.)aw e Information Sources / References Work Recuests, Occuments Violated, etc. ):
A NDE-Originatec By:( \(Lei a W u A> - Dept./ Group /5ection s A Otner Units Affi$teQ)Yeif )No Sy/Dato Date:l6 cdwe a tWC AeI 9l4ax wa .lov a Tt tA 10l'1 l' l COMPLIANCE EVAL,UAT10N Iten/5ystem Operable "T. C . A(T[
a ~Yes ad-( O sa ne.it.
( )) Not No Apelicable MF O 11.
Evaluated By/DateyM 1- /c/f/f /
v Comment:
Reportaole( )Yes (v7ho Reportable Per:( )50.73 Sect._,,7( )50.72 5ect.
.( 173.71 Sect. ( )T. 5./Lic. Cond. Sect. _( ) Par. f1( )0ther ( )Part 50.9 Evaluated ly/Datet-asfG d 4 is /8/Q / Coments:
III. Telecon/ ENS Rooort to NRC Time /Date: #4 .
NRC Contactee(s): -DPC Contactor(s):
Telegrech/Mailgram/Facste11e Transmission to NRC-Date:-*
Date Notified: NRC Res. Inseector Station Manager , General ___
Office Coments:
IV. Investigation Assigned To: A&M NRC Report Due Date:-
Date.Due to Camp 11ance.after Evaluation ~
PIR Review (Casaliance):- Date:
PIR Station Manager Approval Date:
V. Further Action /tvaluation Required (v1 Yes-( ) No (Explain Below):
Page 2 Assigned To: Q A - % 5.I / G. O.
Comment:
Comp 1tance Reviesec-#VIZ4 Date /s/P/9 / QA Review- N /4 Date Distribution initia1 0eieinator /2D(. JAIP n1 121k Alfc. TM CAff7 2.fS 0
.v Kinal VCm Oriainator
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Other ADOroved Approved (O
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SCAE Requesc C Yes C No
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Determined By/Date 04 cm.
SCAE Assgned To: Send No.
Remarks G
Assqned To Cat.
vm. Cormtm Acton conceted Aporoved
=.
IX. QA Venficatx/1Results Completed By QA Approve Remarks Fine QA Reven ca.
1 COMPLETE FORM BY PRINTING WITH SLACK IRALL PolNT PEN OR TYPE
(] DUKE POWER COMPANY NUCLEAR STATION Problem Investigation Report Serial No. _ CC 9/-Oo93 gDR$Ng station />=
Q%d Ucensee Event Report No.
1. Problem 0 MEW 37)e/Date: ow.Trne/Datea ###// /f"3F/)
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Other Duie S2:icris Affected Eries O No Determr.ec 9y. Ore 74f/4/4er,*c f-F#/
CuTJ A "
I a Ari4 Of PrDblem: [">M//A-Method Used to Discr5er Problem: fei'//N Af/J/SS Immediate Ccr7sethe AcDons Taken/To Be 7a' ken: MMd.
Weric Stoppage Nottflmrion (Form QCK.2A) Serial No.: A//f inkrmanen Sources / References (Work Requests. Docum(rtts Violated, ettp #hf- #A
> A/ - _ .. .,
WuBf ,h# [f@ Date: f'fM ._ Dept./ Group /Seenon: @ M5p it. Compliane.a E Evaluated By/Date- Mtem /Sy,stemOperable Yes C L"//0/4/ No O Not AWu t Commenrr Reportatie C % iiH9o Reportable Par. O 50.73 Section D 50.72Secnon O 73.71 W O T4/UcCond O Part 2' O Other- O Part50.9 Ev=h awt By/ Data: A d' A ' T//o 4/ Comme &
111. Telecon/ ENS Report to NRC Time /Date:
NRC Cu.Ws): ,
DPC Contactony):
Telegraph /Mailgram/Tr eai TiswTusskii to NRC-Date:
Date Nottfied: NAC Res. Inspecton _ Star Manager Genent Office. Ccmmernr IV. Imesaganon Assagned To: NRC Repc: SueDate:
Date Due to Cei@w after Evaluaton-PIR Review (CuiG i.ce): Date:
PIR Station ManagerApproval.
Date:
V. Furtner Action /Evaluanon Recp.ed -
des C No(ExplainEkicw)-
Page 2 Assagned To: h4 - 5 d e Comments:
s >-
CompLance Revww: Date: OA Revie a: M O sts: /8-25-f _
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_ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ . _ _ _ . _ _ _ a
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.O Proposed Resolution to PIR 4-0 91 0093 AU of the nozzle-to-shell welds (ASME Secdon XI C B Wejds) for the second interval at Oconen Units 1, 2, and 3 have been reviewed to desarmine the extent of this situadon, nis review revealed that this was not:an isolated case and the incorrect aceptance criteria was used for au noale-to-shell .>
welds.
l The following corrective aedons will be taken:
Procedure NDE-25 will be revised to clarify when to use A ppendix A vs the other ISI acceptance Append!ces. As a resnJt. of this revision, training will be conducted for all Level II MT/PT '
Inspectors at Oconee. (During the process of investigating this situation, it was identified that procedme NDE-35 is worded similar to NDE-25 and also will be revised for clarW= dan).
The training program will be reviewed by the NDE Level III~ ,
handner to ensure that the lessoa plan adequately addresses how to go about selecting the acceptance critaria in different situadons.
lO .
An iddenda wm se w,inen to tse rS1 gan to ,e.ecsednie the
[ nozzle-to-shell welds for . re-examinadon.
i l He following is a list of the ASME Section XIItem Numbers =3 dam M to '
the nozzle-to-shell welds- which were reviewed _ for this disposidon:.
, UNrr 1 UNTP 2 ggIl
! 1 C02.010.001 C02.010.001- CO2 J10.001 -
CO2.010.002 CO2.010.002 CO2--]lO.002 CO2.010.003 CO2.010.003. CO2.]10.003 CO2.010.004 CO2.010.004 CO2 'J10.004 CO2.021.001 A . CO2.021.001 A COM21.001A t
CO2.021.002A CO2.021.002A. -CO2 J21.002A L
. CO2.021.003 A CO2.021.003A 'CO2 ')21.003A i CO2.021.004A CO2.021.004A - CO2- 021.004A -
L CO2.021.005A CO2.021.005A C02.021.005A
( CO2.021.00tus CO2.021.006A CO2.021.006A L -
u
.. , -..a.-.. .- : --
STAi! Oft DIRECTIVE 2.8.1 ATTADeUT 2 PAGE 1 of 2 APPROVAL $ 2 th3 G REY. 10 QATE l __ */m lu EFFECTIVE DATE _ y/N/4r COMPLETE FORM BY PRINTING WITH BLACK BAL.L POINT PEN OR TYPE OUKE POWER COMPANY NUCLEAR STATION PROBLEM INVEST!GATION REPORT SERIAL NO. 1 M1 007L STATION TYN W ie<
LER NO.
I. Problem Occurred-Time /Date: uN KnowN Oi scovered-Time /Date : 27NoV 91 Unit (s): 1 Unit Status At Time Problem Occurred / Discovered:wtmi m .;,,o,.m Description and Cause of Problem: 'n>
Eg )Wudr S4eem 6enchne*s IM IR were C onA owu ht, duWuo .2 sr in we4A e is an4 in%er4eA heenase 4ke nu+ ux2s 34 vex ew 42J s44 and wal hwe,A to 14k tseta h Al4ian . %e__ eld M14ino rnn4enai tet discarded i
WAL 60% 4've ht esclua+iw bMkem dna , 4c) e b b + % h e A be ouer co+ab k. emai4&r As wa, ed b u QCL- t A o nA AB E %ek'nu F - -
Locs. tion Of Pr'oblem: 5/G /A 9 la .
Metted Used To Discover Proelem: COL l3- A I sr v,3b.i Mspeck M Irmediate Corrective Actions, Taken/Tc Be Taken: Ali bel 4.tha lteiec+edI wm troberJ ANc3 At.t c ra w r h h (P " 8 m o w s AA we<_ vesmilm infoA-+M < u4k eme.
S/6's f t'. . M c T9
~ ~
t / L infmfon Sources / References (Work Requests, Documents Violated, etc.): Gt t-BA's MN 5-91-Co l WO fS43 tic PT 4 WRC93t8tPT . SeeWc' W'1T thtminoktwM220 MrosMM/
Originated By:.id u).TA 1>0 %&
~
Date:333 pt./ Group /Section
M
Othu Units Affk%)d ( )Yes (SolBy/Date ia. Wqa. WOD u a RTwo? ~'
!!. COMPLIANCE EVALUATION-Item / System Operabie (/) Ye
'Q4 bnba>w.M 61bM L
) No ( ) Not Applicable Evaluated By/Date b< 'd ch.wo e .?s-92 Coment:
1 Reportable ( )Yes (V)No Reportable Per:( )50.73 Sect. ( )50.72 Sect.
( )73.71 Sect. ( )T. S./Lic. Cond. Sect. ( )Part 21( )0ther ( )Part 50.9 Evalua.ed By/Date: A w ? Jo . .,m. Coments:
O e 13 */ t III. Telecon/ ENS Report to NRC Time /Date: Af/4 NRC Contactee(s): OPC Contactor(s):
Telegrach/Mailgram/ Facsimile Transmission to NRC-Date:
Ohte No-;ified: NRC Res. Inspector Station Manager General Office , Coments:
IV. Investir;ation Assigned To: N/4 NRC Report Due Date:
Date Ous to Compliance after Evaluation PIR Rsview (Compliance): Date:
PIR Stat?on Manager Approval Date:
V. Further Action / Evaluation Required (v1 Yes ( ) No ('welain Below):
Page 2 Assigned Tc: Ma / rvmA Comentu Compliance Review @7hm Date / 23 42. QA Review Date Distribution initial Originator ra w t% p cec tytM% L.. FE2w,-+ E8 m a h ee d Final
/ ui M u e+1 Oric1nator
7) t$Jmewneaca P user M B
Rev. 6
i d^'lon DIccrirt 2.a.1 ATTA000rt 2 PA3 2 of g PRC8LEM !NVEST!GAf!?N R[pcRT 8tge 2 VI. Root Cause of Proelem
lR No.&!l?$ ~fnn
.P Procosed Resolution of Proelem s
Groum(s) Involved _
Sy Oate 3/C CATE Concurrence Cate
~
Accroved '
Acoroved (Other Groups Af fected) Cate ADDroved Other Approvals Date ADDroved (Other Groups Af fected) Cate QA Ea'te __
Significant Corrective Action
( Assigned To/ Comments A:uation Requesteo Y e s_,,,,, Na VII. Corrective Action (s) Required Assigned To performed By Cate BY:
Orte:
Action / Inspection Remarts Final Como)1ance Review Cate O
l 10.0 Reference Documents The following reference documents apply. to the inservice inspection performed during Outase 7 at McGuire 1:
Babcock & Wilcox "1991 Reactor Vessel Examination Report" (3.0 Examination Summary), dated January 23, D92.
- Duke Power Company Request for Relief MNS-004
- Duke Power Company McGuire Nuclear Station Unit 1 Request for Relief No. 90-02 Duke Power Company, McGuire Nuclear Station Design Engineering Evaluation MC 1201.01 dated January 21, 1992 Code Case N-461 O
l l
.EQA388 339, 1 Fevision 0-January 31, 1992
l-N Copy No.:
4 :lled:-YES 1991 REACTOR VESSEL EXAMINATION REPORT FOR-DUKE POWER COMPANY
~.
-9 MC GUIRE NUCLEAR STATION UNIT 1 ,
Revision: 0 Outage: #7 Owner: Duke Power Company P.O Box 33189 Charlotte, NC 28242 BWNS Reference Number: ContraJt 583-0661 Task 406 MANUFACTURER: Westinghouse Electric Corporation- ._
NRC DOCKET NUMBER: 50-369 GROSS GENERATING CAPABILITY: 3411 MWT COMMERCIAL SERVICE DATE: December 1,.1981 Prepared by: Date: /"23 Y.D. Minton - (NDE Projects = -SPIS - BWNS Reviewed by; af ,
Date: /-23 92 K.S -Hacker - NDE Technology - SPIS - BWNS '
Approved by: h .Date: M $ -f2- -
, D.B. Fairbrother - Mgr. NDE Services - SPIS.--BWNS.
B&W NUCLEAR SERVICE COMPANY O-
- Engineering & Plant Services 3313 Old Forest Road Lynchburg, Virginia 24506
_ _ _____ _ - - l
i L
() 3.0 EXAMINATION
SUMMARY
Revision 0 During the period of October 1991, the B&W Nuclear Service Company performed the first ten-year interval examination of the McGuire Unit i reactor vessel. The examination also included the examination of the inner third of the volume of the adjacent piping welds 1
terminating at the vessel. Attachment #1 is an Examination Summary Table which identifies by Item Number the applicable weld number, the ,
date the examination was performed, the inspection status, whethe'r '
the examination was limited or not, and if geometric indications were recorded.
Attachment #2 is a sketch which illustrates the location of the' welds examined.
O Attachment #3 is a table summarizing the results of the examinations including the disk number containing the examination data,Levaluation report number and results of the evaluation, angles used and.the personnel identification for those who performed-the analysis.
The examination was unique in that the examination exceeded the ASME Code requirements for scanning sensitivity and recording levels.
These enhancements were used to establish the condition of the vessel weldments to the extent that_ state-of-the-art ultrasonic examination technology can provide and were directed specifically at-detecting the presence of planar reflectors. The results of the examination indicatet that no planar flaws were detected. Several low amplitude volumetric reflectors were detected and are all dimensioned less than the maximum allowable flaw sizes permitted by ASME-Code Section XI, C
IWB-3500 acceptance standards.
3-1
[D
%- Duke Power~-le McGui C[ #1 any.
Examination 6. ary Table Attachment s Item Number Weld Number Insp Insp Insp Insp Geometric Cal I. Date Time Status Limited Reflector Block B01.030.002 1RPV 7-442 10-23-91 05:08 REC L Y 50378 B01.011.001 1RPV 8-442 10-23-91 .14:32 REC L Y 50377 B01.011.002 1RPV 9-442 10-30-91 12:05 CLR -
Y 50377 B01.011.003 1RPV 10-442 10-27-91 00:18 CLR L Y 50375 B01.012.001 1RPV 1-442A 10-23-91 05:45 CLR. -
Y 50378 B01.012.002 1RPV 1-442B 10-23-91 04:14 REC -
N 50378 B01.012.003 1RPV 1-442C 10-23-91 03:50 REC -
N 50378 B01.012.004 1RPV 2-442A 10-21-91 14:41 CLR -
N 50377 B01.012.005 1RPV 2-442B 10-21-91 15:29 REC -
N 50377 B01.012.006 1RPV 2-442C 10-21-91 13:55 CLR -
N 50377 B01.012.007 1RPV 3-442A 10-21-91 11:25 REC -
Y 50377 B01.012.008 1RPV 3-442B 10-21-91 10:30 REC -
N 50377 B01.012.009 1RPV 3-442C 10-21-91 09:42 REC -
Y 50377 B01.021.002 1RPV 4-469 10-26-91 10:48 REC L Y 50375 B01.022.006 1RPV 1-202A 10-27-91 20:39 CLR -
Y 50375 B01.022.007 1RPV 1-202B 10-27-91 20:26 REC -
Y 50375 B01.022.008 1RPV 1-202C 10-27-91 20:08 CLR -
N 50375 B01.022.009- 1RPV 1-202D 10-27-91 19:55 CLR -
Y 50375 B01.022.010' 1RPV 1-202E 10-27-91 19:43 CLR -
Y 50375 B01.022.011: 1RPV 1-202F 10-27-91 19:30 CLR -
N 50375 B03.090.005 1RPV 5-445E 10-24-91 06:30 REC L N 50378 B03.090.005A 1RPV 5-445E 10-35-91 14:25 CLR L N 50104 B03.100.005 1RPV-5-445ER 10-29-91 04:54 ' REC L Y 50304 ,
B03.090.006. 1RPV'5-445F 10-24-91 05:55 REC L N 50378 B03.090.006A 1RPV 5-445F- 10-15-91 03:12 REC L Y 50304 B03.100.006 1RPV 5-445FR 10-29-91 16:25 REC L Y 50304 B03.090.007 1RPV 5-445G 10-30-91 07:39 CLR L N 50378 B03.090.007A 1RPV 5-445G 10-16-91 06:16 REC L Y 50304 B03.100.007- 1RPV 5-445GR 10-28-91 17:00 CLR L N 50304 __
-B03.090.008 1RPV 5-445H 10-30-91 07:02 CLR L N 50378 B03'090.008A
. 1RPV 5-445H 10-16-91 02:15 CLR L Y 50304 B03.100.008 1RPV 5-445HR 10-29-91 00:49 CLR L N 50304 B05.010.009&9A. 1RPV 3-445F-SE 10-14-91 12:40 REC' L Y 40397 B09.011.076A INC1 F-2-1 10-28-91 -06:20 CLR -
N 40397 Legend: CLR = Clear, REC = Recordable L = Limited Exam, . - = Not Limited Exam Geometric Reflectors: Y = Yes N = No .
a O Duke Power C ny f]
(V McGui ~ ~ ,1 1 Attachment V
Examination b- ary Table Item Number Weld Number Insp Insp Insp Insp Geometric Cal Date Time Status Limited Reflector Block B09.011.076B INC1F-2-1 10-28-91 06:20 CLR -
N 50214 ,
B05.010.011&11A 1RPV 3-445E-SE 10-28-91 03:55 CLR -
N 40397 {'
B09.011.075A INC1F-1-1 10-29-91 02:20 CLR -
N 40397 DO9.011.075B INC1F-1-1 10-29-91 02:20 CLR -
N 50214 B05.010.013&l3A 1RPV 3-445H-SE 10-28-91 23:58 CLR -
N 40397 B09.011.078A INC1F-4-1 10-28-91 22:30 CLR -
N 40397 P09.011.078B INC1F-4-1 10-28-91 22:30 CLR -
N 50214 B05.010.015&l5A 1RPV 3-445G-SE 10-29-91 18:49 CLR -
Y 40397 B09.011.077A INC1F-3-1 10-19-91 16:00 CLR -
N 40397 B09.011.077B INC1F-3-1 10-19-91 16:00 CLR -
N 50214 B03.090.001 1RPV 5-445A 10-25-91 09:38 REC L 'Y 50378 B03.090.001A 1RPV 5-445A 10-17-91 08:05 CLR L Y 50304 CO3.100.001 1RPV 5-445AR 10-28-91 11:00 REC L N 50304 B03.090.002 1RPV 5-445B 10-25-91 04:15 CLR L Y 50378 B03.090.002A 1RPV 5-445B 10-17-91 05:00 CLR L Y 50304 3 B03.100.002 1RPV 5-445BR 10-28-91 08:55 REC L N 50304 B03.090.003 1RPV 5-445C 10-25-91 05:30 REC L N 50378 h 1RPV 5-445C 10-18-91 05:15 CLR L Y 50304 B03.090.003A B03.100.003 1RPV 5-445CR 10-28-91 13:51 CLR L N 50304 B03.090.004 1RPV 5-445D 10-25-91 06:22 REC L N 50378 B03.090.004A 1RPV 5-445D 10-17-91 23:29 REC L Y 50304 B03.100.004 1RPV 5-445DR 10-28-91 12:58 CLR L N 50304 B05.010.001&lA 1RPV 3-445B-SE 10-28-91 16:12 CLR -
N 40397 B09.011.080A INC1F-2-8 10-28-91 08:02 CLR -
N 40397 B09.011.080B INC1F-2-8 10-28-91 08:02 CLR -
N 50214 B05.010.003&3A 1RPV 3-445A-SE 10-17-91 12:42 REC -
N 40397 B09.011.079A INC1F-1-8 10-28-91 10:27 CLR -
N 40397 B09.011.079B INC1F-1-8 10-28-91 10:27 CLR -
N 50214 B05.010.005&5A 1RPV 3-445D-SE 10-17-91 22:04 REC -
Y 40397 _.
B09.011.082A INC1F-4-8 10-28-91 12:18 CLR -
N 40397 B09.011.082B 1NC1F-4-8 10-28-91 12:18 CLR -
N 50214 B05.010.007&7A 1RPV 3-445C-SE 10-25-91 07:52 CLR -
N 40397 B09.011.081A INC1F-3-8 10-28-91 14:40 CLR -
N 40397 B09.011.081B 1NC1F-3-8 10-28-91 14:40 CLR -
N 50214 Legend: CLR = Clear, REC = Recordable L = Limited Exam, - = Not Limited Exam Geometric Reflectors: Y = Yes N = No
I O .
^ " """* " '
DUKE POWER COMPANY MC GUIRE UNIT 1 REACTOR VESSEL EXAMINATION s
3 445E SE (22 degrees) 3 3 445F-SE'(158 degrees)l 3 4450-SE (202 degrees), [ 3 442 (> I 5-445AR-(67 degrees) 3-445H-SE (338 degrees) 1-442A (60 degrees q-1 442B (180 degrees *
'. llfr
,- 5 445DR (293 degrees) s IN 17 1 1 (22 degrees) == 1-442C (300 de1rees<
1N;17 2-1 (158 degree s ))t.---:r N [3*445A-SE(67 degrees)
INCir-3-l'(202 degrees)
INC1T*4-1 (338 degrees) p ,9 OUTLET N0ZZLE
/ 3-4458 SE (113 degrees)-
3-445C-SE.(241 degrees)
' l s
5-445ER f22 degrees) _ ]m /
f -UPPER SHELL 454 0 INL 6 N0lELE g" / [* 3-445D-SE (293 degrees)
(1HC1F-1-8 (67 degrees 5-445TR 1158 degrees N 1NCIT-2-8 (113 degrees) 5-445GR (202 (tgrees)( _ 8-442 % J 5445HR(338degreesy ; \ ,
l,1NC1F-3-8 (247 degrees) 1NCIT-4-8 (293 degrees)
~ f 5-445A (67 degrees) 5-445E 2-442A (0 degrees j5-4455,(113 degrees)
$~445F (22 (158degrees)*(
degrees) " ,
2-442B (120 degrees 5-445C (247 degrees)
O- 5-945G (202 degrees) 5-445H (338 degrees)
',2-442C (240 degrees 5 445D (293 degrees)
MIDDLE SHELL 454-02 9-442 -
442A (60 degrees 3-442B-(180 degrees 3-442C-(300 degrees)
LOWER SHELL 454-03
] 10-442
_{
1-202A (30 degrees) ' '
TRANSITION RING 1-202B (90 degrees) l
~
469 -
1-202C (150 degrees) W 1-202D (210 degrees) .4-469 3 1-202E (270 degrees) - -
1-202F-(300 degrees) LOWER HEAD LO u1
~ ~~
_-j
. 1 i
O Serial No, MNS-004
NPD Licensing Serial No.
i Page 1 of 3 4
DUKE POWER COMPANY Request For Relief From Inservice Inspection Requirement Station: McGuire .
Units: 1&2 i
Requesting Department: Quality Assurance-ISI Reference Code:
, 1980 1980 ASME Section XI. including addenda through Winterj 1.
Component for which exemption is requested:
O a.
Na e and Identification Nu 6er:
Unit 1:
Reactor Pressure Yessel outlet nozzle-to-vessel welds, outlet nozzle to safe end,_ outlet nozzle safe end to reactor coolant system piping welds.
Unit 2:
Reactor Pressure vessel outlet nozzle-to-vessel welds and outlet nozzle-to-pipe welds-on Reactor Coolant System. .
, b. Function:
Welded connection between the Reactor Pressure Vessel and
respective Reactor Coolant piping providing a flow path to the steam generator, v
c. : ASME Section XI Class 1 O
1
^
O Serial--No, MNS-004 NPD Licensing Serial No.
Page 2 of 3-II. Reference Code Requirement that has been detemined to be impractical:
ASME Section XI,- Table IWB-2500-1, Category 8-D- _ item number 3 B3.90 and 83.100, note (2); at least 255 but= not more than- 50%
(credited) of the nozzles shall be ' examined by : thrend of the '
e first inspection inspection period and the triainder by the- end of -the -
-interval.
ASME Section- X1, IW8-2420(a): The sequence of component examinations - established during the : first _ ins >ection interval shall be repeated during each successive inspect < on. .
III. Basis for Requesting Relief:
0 (A) During the first period of the firstiinspection interval at_
McGuire Nuclear Station Unit -1, the -29" outlet nozzle-to-vessel ,
welds, outlet- nozzle to safe end. outlet nozzle safe end = to-Reactor Coolant System piping welds (nozzle side), were examined using Babcock & W11cox's Automated Reactor Inspection Tool-(ARIS)
(B)- During the first period 'of the first inspection interval at '
McGuire Nuclear Station Unit 2, the~29" outlet nozzle-to-vessel welds, outlet nozzle-to-safe end welds, outlet nozzle-safe end to Reactor Coolant System piping welds were examined using Babcock &
Wilcox's' Automated Reactor Inspection Tool (ARIS).
The four - nozzle welds examined -- for each unit- met the 50%
requirement' of Table. IWB-2500-1 Category B-D (Note 2).
No recordable indications were detected.
During the third period of-.the first ten year inspection interval all reactor vessel nozzle-to-vessel-- and . all respective nozzle-to-pipe welds will be examined- using automated inspection equipment.; Included in this examination willibe the 29"- outlet .
nozzle-to-vessel first period. and nozzle-to-pipe welds examined duringj the; ,
The re-examination 1 of these 129" outlet ' nozzles
- will be performed meeting the 1989 ASME:Section XI. Code. Credit:
will be. applied to the second; interval, first: period 1 requirement
O
'for the 29" outlet nozzle-to-vessel welds:under Table-IWB-2500-1, Category 8-D, . items 83.90 and B3.100.
These examinations will not be intenal. performed during the first period of the second-inspection i
J.
O: ,
Serial lo. MNS-004 NPD Licensing Serial No. -
Page 3 of 3 IV. Alternate Examination:
Automated .re-examination of .all- the reactor vessel nozzle-to-vessel welds, including respective nozzle-to-pipe welds will be- deferred to:- the 'last period of L the- second - ten year, -
+
~
inspection interval.-
V. Implementati 9 Schedule:
Examinations are currently scheduled to be perf'orined during the third inspection period for each of the.McGuire _ Units _ as follows.:
McGuire Unit 1 : RF0 #7 1991 "
.O "c5 $r ua'* z : aro 'a t
^
O: .
-j
.________.__:___ _.1_____.-____ .-
i O November 19, 1990 U.S. Nuclear Regulatory Commission Page No. 1 Duke Power Company McGuire Nuclear Station, Unit 1 Request For Relief From ASME Code Section XI Requirements Relief Reques.t No. 90-02
1. Component For Which Relief Is Requested:
The systems and components for which relief is requested are those portions of items identified in our inservice inspection program that _
have not been hydrostatically tested as required. Please reference the McGuire Inservice Program and post outage inservice reports for McGuire ,
Unit 1.
II.
ASME Code Section XI Requirement That Has Been Determined To Be Impractical:
ASME Boiler and Pressure Vessel Section XI, B and PV, and IWA 2400, Section C.
III. Alternate Examination Proposed:
No alternate examinations are being proposed. The required examinatiocs will be performed. The only change will be the time the examinations will be performed.
IV. Basis For Requesting Relief:
The McGuire inservice plan consists of ten planned refueling outages within the ten year inservice interval. Our present plans are to change our fuel from a Westinghouse design to a Babcock and Wilcox fuel design.
This change will be over mora than one core load and will increase the on-line time of the plant during the first ten years of operation [1*,
4 thereby, reducing the number of scheduled refueling outages from ten to ceven-outages. As a result of this change, the actual inservice inspection time has been reduced by three refueling outages. If the required inservice hydrostatic tests are imposed in the existing ten year interval to include the additional 12 months allowed by 10 CFR 55a, McGuire Unit I would be required to remain in an outage in 1991 for an additional three months.
V.
Why The Alternate Proposed Testing Will Provide An Acceptable Level Of Quality And Safety:
At McGuire to date, all inservice and functional inspections have p revealed no evidence of failed welds in pressure retaining pipirig v systems.
[1, The proposed license amendment for this change is currently being prepared.
i l
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November 19, 1990 U.S. Nuclear Regulatory Commission Relief Request No. 90-02 Page No. 2 The McGuire Unit 1 inservice inspection interval began en December 1, 1981. Our evalcation of the results of our inservice program thus far indicate that extending the McGuire Unit 1 inservice inspection interval for the purpose of completing these hydrostatic tests would not endanger the quality of operations nor affect the health ant, safety of the public. Therefore, we believe the burden of extending a normal refueling outage by three months outweighs the benefit of imposing the requirement during the normally scheduled inservice interval.
VI. Implementation:
Our request would change the required completion date for the hydrostatic tests from December 1, 1992 to December 1, 1993. By this latter date, we will have completed the required inservice hydrostatic tests.
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O January 21, 1992 i
MD10 TO FILE i
Subject:
McGuire Nuclear Station [
Design Engineering Evaluation of Unit 1 10 Year Inservice Inspection. .
Reactor Vessel and Internals
File: MC 1201.01 s
The attached is a review of the indications identified by QA inspectors on the Unit 1_ Reactor Vessel and Internals._ These indications were identified during the-visual ASME required-10 year In Service Inspection performed durir.g . U1EOC7. Each indication p listed was reviewed by Design Engineering personnel. No problems
.g were identified that would affect the integrity of the reviewed All indications were minor -in nature. No corrective parts.
actions are required.
/ , .. . ,
h t ,*,. ..S. 'j:. o ne .
, John B. Beckman
/ D esign Engineer DE-0ED Jbb/jbb
'(ISIMEMO.LP) cc: R. Branch J.-J. Nolin .
A. J. Hogge Central Records
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l 0 HCOUIRE NUCLEAR STATION DESIGN ENGINEERING EVALUATION UNIT 1 EOC7 ISI VISUAL EXAMINATION (VT-3) or REACTOR VESSEL AND INTERNALS The following is a review of the indications identified by QA inspectors on the Uriit 1 Reactor Vessol and Internals. These indications were identified during the visual ASME required 10 year 8
In Serv co Inn -cetion performed during U1E)C7. The inspoetion was made using Wir water black and white video equipment. E3ch indicat M 16 ..stod in QA's QAL-14 procedure by numerical number as well as by video tape number and time. A description of the indication is also given. Each indication listed was reviewed by Design Engineering personnel. No problerns were identified that would affect the integrity of the reviewed parts. All '..tdications ,
were r!.ino,' in nature. No corrective actions are required. .
Many indications noted oy OA were ininor dente, dings, pits and scratches. The tapes of these indications were saview and no evidence of deterioration were noted. These indications will not be specifically reviewed in this evaluation.
The following is the disposition of the indications that received further review or explanation.
Reactor Vessel Inspection facts 1 Thru 6 Hammer Marks and Deteriorations Indications: 4,5,6 These indications were the result of the installation method used on 'Ae Key Clovis Inserts. The Clovis Inserts were frosen 1. Dry Ice and then beaten into place resulting in the hammer marks seen. The pirs were also frocen using Dry Ice and then inserted in the the pin holes. If the Pins f ailed to fully insert, then they were ground down using a pencil grinder and then tack welded in place.
. Damage to Vessel flange Indications: 7, 8 l These were the result of the impact of the Core Barrel on the l vessel flange area during the Core Barrel removal. These were evaluated in PIR 1-H91-0177 Arc Strike Indication: 12 An ultrasonic examir4ation was made of the arc strike area by Babcock and Wilcox Nuclear Service. The results of the examination are attached. No evidence of cracking in the base metal was evident.
I Interngle InspectlpA,%gp,ma 1 Thru 48 weld Splatter ar.d Arc strikes Indications: 1,2,8,10,14,19,20,26,27,43,107
~~] These indications were reviewed and in most cases they appeared to be either small pits with discoloration around the pit or small weld splatter usually located near the weld on a baffle plate bolt locking -- tab. No signs of cracking were eviderit.
i ;
l l
l O cvges Indications 3),35,38,40,44,46,47,48,50,52,54,56,61,62,63,64,65, These indications were the result of knife edge peaning of baff1s plate joints in in effort to reduce the bypass flow impingement on the fuel bundles. This work was performed by Westinghouse.
Chipped sections Indications: 30,32,36,39,49, These indications appeared to be chipped corners but on closer .
review of the tapes and other Baffle Plate bolt locations it !
is concluded that what is seen is the heat effected zone of l the tack weld for the bolt locking strap. Sonne welds were made close to the edge and the edge showed what appeared to be a chip.
couge Indication 55 This indication on first review appeared to be a crack running
from baffle plate edge bolting to edge bolting. Additional ;
video inspections were made by Design personnel showed that, i with different camera angles and different lighting, - the indication was actually a deep scratch or grovw.
Holes At Top of Baffle Plate Indications: 70,72,77,78,79,80,01,82 These indications typear to be holes drilled through the top '
of the baffle plates for lifting purposes during assemble.
l Hai:' Line Crack on Core Barrel Girth Weld Indication: 92 This indication en first review appeared to be small crack in the Core Barrsl Upper Part to Lower Part Girth Weld.
Additional video inspection performed by Design was made of the indication. Using a steel brush on the end of a long handled- tool, the indication was brushed. The indication virtually dteappeared following the light brushing. Therefor it was concluded that this indication was only a mark.
Indication on Neutroa shield Indication: 112 This indication on first review appeared to be a crack on the Neutron Shield. - Additional video inspection was made by Design using different camera angles and different lighting.
l Upon closer examination these indications were determined to be marks or stains.
These indications were reviewed by Jeff Nolin and John Beckman of the McGuire Engineering bivision. No problems were identified that
, would affect the integrity of the raviewed parts. All indications l were minor in nature. No currective actions are required. ,
r d / Co s. 3
/ ohn B. Beckman ;
Design Engineer
DE-MED -
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3;esagro.,n s a%'a T& Bo* W rewoor son.sas3663 November 8, 1991 sett Holin Design Enginoering Hechanical Duke Power company McQuire Nuclear Station 12700 Magers Ferry Road Huntersville, NC 28078 Dear sitt ~. Attached the McGuire are Unit the resultsvcanal I reactor et ancontaining ultrasonioanexamination are strike. of an ar The added scope to the lo year In-Service Inspection. examina In summary trom propagating no evidence of cracking was detected initiating m' or the are atrike. l O [ i . C. ~ M.C. Drop 1y, 'C)0 Mask Leader i
$Uh ==
H.M. Sto'ppelmann, UT Level III
} T5 klbV D.B. Fairbrother, Manager NDE Services -2 0.
(/..K.Wanding,/ProjdetManager Egineering and Field Services cc C.2. Beardon A.M. McClanny O ao-t
.. . . I ! \ . . .* /
. Ano STRIII v //l// ~
VI.TRA80Nic EXAMINATION JO I ' of an area of the reactor vessel not covered un service an are strike. Inspection (Is!) was' conducted to evaluate the effects of The are ntrike was discovered during the visual j examination of the interior of the reactor '/aseiel. Both the visual i Manipulater (CNN) during October of 1991. exam s6d th! - An are strika was detected in the McGuir6 Unit i reac
typroximately 334 degrees below the flange. Based on(reactor vesset ooordinate), 157. 5 'in
and the video image o these coordinates from the-vigeo scan to be at 335 degrees.f extendin strike, the actual location appears tho arc 152 inches belev the flange. g approximately 3 inches from 159 tio :
To insure adequate coverage of the area surrounding the arc strika, an area of: interest was defined ' i flange. from 334 to 337 degrees and from 15s to 163 inches below the - Four four directions. ultrasonic scans were performed to cerver this area from ~a reactor vessel, so The that arcaxial strike was oriented vertically in the i scans would look for cracks . propagating out to the aides, and circ scans would look top and bottom. !
O Data was ao uired usin, a 7 de The traneducer used the same ca ree 1ongitudinai wave transducer.
reactor vessel velds. The libration 1/16 inchas had been used for the side-drilled holes in calibration inspection area was about 2 inches. block examined50304 frontwere used to determine The the-M
twNs AccusoWEX Data All four Analysis scan directions System. were analysed using theth 4 cladding or the base metal beneath it. Analysis n the of the scaI
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t q CA5I U N 461 CASF.S OF ASME Bolt.ER AND PRESSURE VLSSEL CODE Approval Deto: Novembw 30,1988 See twimeroc Inces for espirevon and any roor tormation dom. Case N 461 Alternative Rules for Piping Calibration Block Thickness Section XI, Division 1 Inquiry: When eclecting calibration blocks in acco,J. . ante with Section XI, Division 1,1113410, what alterna-tive wall thickneues or pipe schedules may be uwd? Reply: It is the opinion of the Committee that any calibration block thicknew may be used that is wP.'ine 225% of the pipe wall thicknew to be examined. O i 1 i v 803 1 SUPP.11 - NC
11.0 [lais_1__and2RepairsandReplacements As required by ASME Section XI,1980 Edition, a record s1 of the Clas and 2 Repairs December 7, 1991and Replacements is provided and for work performed from May
,1990 to 18 report.
The individual work request is included documentsinare this section of the McGuire Nuclear Station. on file at the O I EQA388 Page 1 Revision 0 January 31,-1992
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IVP100 STUD 8 NUT REPLACEMENT 207 8 1 8 89156 8 2436 _Jt9L8 IVX30 REPA!R H l'l 209 8 1 8 09164 8 2365 t 3541 t O. INM003 ft I'l 209 8 1 8 89179 I 5436 1 2307 4 IRV))9 RINLR191d[MJNT 210 t 1

89263 8 2379

133L1 211 8 1 8 89548

2661 8 0915 4 0 ATE PERIOD: 5-11-90 TRAr5MITTED ID 151 $UPERVISOR 01-27-92
y 7 Pact 5 0111pfg 1NO1QjyNJQ96 .)f,y L Q y P(PLAC[k[NT 212 4 1 3 95093 3 p31g g 319{j MEVW 2097 H 1"I til 1 1 8 97271 8 2365 8 Jt11J Mif G Dl_.lLVlilLlVill_ 214 8 1 8 97331 4 2455 t J0044 MtVW lllWRLPLPA]R C0W14thmENT VE551k till 1 8 97467 4- 2376 6 30 1]
"IVN 2218ELUl>LMIRW1 _2MJ 1 4 97460 4 2377 8 lift 8 11EL41.MJ1Ul]L H l'l 217 4 1 8 97489 8 2167 8 24361 lit 8 1 4 97517 4 2367 4 (Ulj 219 4 1 4 97694 8 2595 8 1293 ULLJ t 97'17 8- 2}9) 4 2459 4 221 8 1 1 97950 t . JS94 tilaj 5l01AIVilb' t - tt 0^/7 r#8 / ^
O k O DATE PE'1100: 5-19-90 TRANSMITTED 10 151 SUPEDVil0A 01-27-9{ i L i}}

ML20090G169

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