Text

ISI Rept Unit 1 Catawba 1991 Refueling Outage 5
	ML20077S743
Person / Time
Site:	Catawba
Issue date:	08/29/1991
From:	; DUKE POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20077S742	List: ML20077S740; ML20077S743;
References
	NUDOCS 9109100243
	Download: ML20077S743 (132)
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131 Pages FORM NIS-1 OWNERS' DATA REPORT FOR IN$ERVICE INSFECTIONS As requital by the Provisions of the A$ME Code Rules

1. ow,w, Duke Powe r Co.,,t 4?? S, Chure_h,1, St. Cha rlot te. NC 73101 (Narne and Addren of Ownet)

Catawba Nuclear Station. 4800 Concord Road, York. SC 29745

2. mais (Narne and Address of Phar.)

NA 1

4. Owner Certaficaw of A mornsoon (if requared)

3. Plant Unit

1. Cornmercial Service Det. 6/29/B5 6. Nstoa.i no.,4 swoost for vtut 130

7. Composer.ts lanpected Mam.fseturer Compoovat of Manufacturet or lastainev

$ rats or Natsonal Apputtatance or installet Lenal No.

Prtmt.co No.

Boasd No.

SEE SECTION 1 PARAGRAPH 1.5 IN THE ATTACHED REPORT OG Note: supplemenn) sheets m form of lisrs, sketches, or drawings may be used provided (in saae is 8% in, a 11 in.,

(2)information in nems 1 through 6 on this dass report u itweedd on tech theet, and (3) e6ch sheet is numbered and the nurnber of sheets is recorded at sta top of this form.

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b INSERVICE INSPECTION REPORT UNIT 1 CATAWBA 1991 REFUELING OUTAGE 5 Location: 4800 concord Road, York, SC 29745 NATIONAL BOARD NO, 130 COMMERCIAL SERVICE DATE:

JUNE 29, 1985 Owner: Ouke Power Company 422 S. Church Street Charlotte, NC 28201 Revision 0

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Prepared By:

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Reviewed By:

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U Date Approved sy:

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Dato _ 8 - 2 0 - 9/

Copy No..

5 Assigned To _Nnc__00co m.nt cosq;pl Controlled _,,, X Uncontrolled,

EQA373

CONTROLLED DISTRIBUTION

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,Als oned Tc Copy No C. B. Ctaezem Orir J. E. Cherry 2

J. O. Barbour (Catawba) 3 11, 0, Minton (BWNSLynchburg) 4 P. J. North (To Licensing File) 5 NRC Decument Con +,rol UNCONTROLl.ED DISTRIBUTION 6

C. A. Ireland (AIA, Atlanta,GA)

CQA373-

TABLE Of CONTENTS L-)

Section Title ele vision 1

1.

Summary of Inservice Ins,eec' ion 0

2.

Status of Required Inspecticns 0

3.

Final inservice Inspection Plan for Outa0e 5 0

4.

Results of Inspections Performed During Outage 5 0

5.

Class 1 Insr;ection Resulta 0

6.

Class 2 Inspection Results 0

7.

At gmented Inspection Re.sults 0

8.

Personnel: Coulpmer.t, and Material Certifications 0

9.

Problem Investigation Reports 0

10.

Reference Documents 0

11.

Class 1 and 2 Repairs and Replacements 0

,-b, EQA373

i 1.0

,S,ummary of Inservice Ir.epection This report de:cribes the Inservice Inspection of Duke Power Company's Catawba Nuclear Station Unit 1 during the 1991 Refueling Outage (also referred to as Outage b, which is in the cecond Inspection Period of the First inspection Interval).

Included in this report are the final Inservice Inspection Plan, the inspection results for each item, a summary for each category of exami.

nation and corrective action taken when unacceptable conditions were found.

In addition, there is a section included for repairs and replacements required since April 21, 1990.

1.1 Class 1 lispection The Class 1 Inservice Inspection included examinations on Reactor Vessel Incore Instrument Tube Welds to Lower Head, CRDM Tube Welds to Reactor Vessel Upper Head, Pressurizer Surge Nozzle to Lower Head Weld and Inside Radius Section, Pressurizer Heater Penetration Welds to Lower Head and Safe-End Weld. Examinations were performed on valve bolting-and on circumferential butt welds in the Reactor Coolant (NC), and Residual Heat Removal (ND) Systems. Also, examinations were performed on socket welds in the Safety Injection (N!) and Chemical and Volume Control (NV) Systems and on the internal surfacet of Valve INC-1.

Visual examinations were performed on the Class 1 Pressure Boundary N

during System Leakage Tests.

-The inconel 600 tubing in Steaa Generators IA, 1B, 10 and 10 was inspected by eddy current during Outage 5.

The results are shown in the Catawba 1 Refueling Outage 5 Eddy Currsnt Examination Report.

Reportable. indications were found on the Class 1 Inspections shown in this section.

Inspection and evaluation data for each reportable indi-cation is found in the Catawba 1 Refueling Outage 5 Eddy Current Exami-nation Report.

A detailed description of each inspection is found in the final inservice Inspection Plan in Section 3 of this report.

Results of each examina-tion are found in Section 4.

1.2 Class 2 Inspection The Class 2 Inspections included examinations on circumferential butt wolds of the Residual Heat Removal (ND),_ safety Injection (NI), Main

_ Steam (SM), and Main Steam Vent to Atmosphere (SV) Systems.

Examina-tions were performed on longitudinal butt welds of the Residual Heat Removal (ND) and Safety Injection (NI) Systems.

Examination was performed on Valve IN!-342 body to bolting flange weld, i

Page 1 l

Revision 0 EQA373 August 2, 1991

Visual examinations were performed on the Class 2 Pressure Boundary v'l during System functional Tests. Also, visual examinations were V

performed on Class 2 Component Supports of Residual Heat Removal (ND) and Main Steam (SM) Systems.

A detailed description of each inspection is found in the Final inservice Inspection Plan in Section 3 of this report.

Results of each examination are found in Section 4.

1.3 Augmented Inspection Augmented inspections at Catawba 1 consisted of Reactor Coolant Pump Flywheel examinations, Steam Generator Tubing examinations and Safety injection Accumulator Nozzle examinations.

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.

1.4 Alternate Examination No alternate examinations were performed during Outage 5.

1.5 Identification Numbers Owner:

Duke Power Company, 422 S. Church St., Charlotte, NC 28201 Plant:

Catawba Nuclear Station, 4800 Concord Road, York, SC 29745 A

Plant Unit:

1 W

Owner Certificate of Authorization:

N/A Commercial Service Date:

6/29/85 Manutseturer State or National Manufacturer or Installer Province Board item or installer Serial No.

No.

Reactor Vessel Westinghouse Duke Power Co.

N/A N/A Pressurizer Westinghouse DCPT-1911 N/A W)Cb89 Steam Generator 1A Westinghouse DCPT-1902 N/A W11300 Steam Generator 18 Westinghouse DCPT-1901 N/A W11?.99 Steam Generator 1C Westinghouse DCPT-1904 N/A W11302 Steam Generator ID Westinghouse DCPT-1903 N/A W11301 Reactor Coolant System Duke Power Co.

NC N/A 326 Residual Heat Removal System Duke Power Co.

ND N/A 115 Safety Injectiun System Duke Power Co.

NI N/A 128 Chemical and Volume Control System Duke Power Co.

NV N/A 127 Auxiliary Feedwater System Duke Power Co.

CA N/A 121 Feedwater System Duke Power Co.

CF N/A 120 Refueling Water System Duke Power Co.

FW N/A 91 (3

v Page 2 Revision 9 EQA373 August 2, 1991

Manufacturer State or National l

(

Manufacturer or Installer Province Board

(

Item or installer Serial No. _

No.

Main Steam Supply to Auxiliary Equipment System Duke Power Co.

SA N/A 114 Main Steam System Duke Power Co.

SM N/A 122 Main Steam Vent to Atmosphere System Duke Power Co.

SV N/A 96 Containment Spray System Duke Power Co.

NS N/A 118 SafetyInjection Accumulator Tank 1A Westinghouse 0020 N/A 310 Safety Injection Accumulator Tank 1B Westinghouse 0019 N//

309 Safety injection Accumulator Tank 10 Westinghouse 0018 N/A 308 Safety injection Accumulator Tank 10 Westinghouse 0021 N/A 311 Unit 1 Duke Power Co.

N/A N/A 130 1.6 The Reactor Vessel, Stea.h Generators, Dressurizer, Reactor Coolant System Piping, Reactor Coolant Pumps, and ' safety injection Accumulator Tanks were manufactured by Wostinghouse Electric Corporation Pittsburgh, PA under purchase agreements from Duke Power Company.

All other systems were fabricated and installed by Duka Power Company, 422 S. Church St., Charlotte, NC 28201.

1,7 Authorized Nuclear Inservice Inspector (s) h MNV4 Name(s):

R. N. McGill Employer:

The Hartford Steam Boiler Inspection & Insurance Company Business Address: The Hartford-Steam Boiler Inspection and Insurance Company 200 Ashford Center. North, Suite 300 Atlar.ta, GA 30338 Page 3 Revision 0 EQA373 August 2, 1991

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2.0 S_tatus of Required inspections

.e completion status of inspections required by the 1980 ASME Code Section XI, including i.ddenda through Winter 1981, is sunnarized in this section, lhe requirements are listed by the ASME Section XI examination ca c;ory as defined in Table IWB-2500-1 for Class 1 Inspections and in IWC-2500-1 for Class ? Inspections.

Augmented inspections are also included.

Class 1 InspectionsSection XI Inspections Inspections Percentage Deferral Category Description Required Completed Completed Allowed B-A Pressure Retaining 14 Welds 2.5 Welds 17.85%

Yes Welds in Reactor Vessel B-B Pressure Retaining 8 Welds 5 Welds 62.50%

No Welds in Vessels Other than Reactor Vessels B-D Full Penetration 36 Inspections 18 Inspections 50%

Partial Welds of Nozzles in Vessels l

B-E Pressure Retaining 55 Welds 55 Welds 67%

No Partial Penetration Credited Welds in Vessels B-F Pressure Retaining 46 Welds

?? Welds 58.69%

No Dissimilar Metal Welds B-G-1 Pressure Retaining 466 Items 294 Items 63.09%

Yes Bolting Greater Than 2 Inch Diameter t

l B-G-2 Pressure Retaining

59 Connections 37 Connections 62.71%

No l

Bolting 2 Inches and Less in Diameter B-H ii;ty,al Attachments 9 Attachments 5 Attachments 55.55%

No for Vessels B-J Pressure Retaining 200 Welds 129 Welds 64.50%

No l

Welds in Piping

Total connections include CRDMS that are disassembled.

V,a Page 1 Revision 0 EQA373 August 2, 1991 lT

Class 1 Inspections (Continued) b Section XI Inspections Inspections Percentage Deferral Category Description Required Completed Ccmpleted

_AHaved B-K-1 Integral Attachments None N/A N/A N/A for Piping. Pumps,

& Valves B-L-1 Pressure 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 2 Welds None 0%

Yes Welds in Valve Bodies B-M-2 Valve Body > 4 In.

7 Valves 3 Valves 42.85%

Yes Nominal Pipe Size B-N-1 Interior of Reactor 3 Items 2 Items 66.66%

No Vessel B-N-2 Integrally Welded None N/A N/A N/A Core Support Structures and Interior Attachments to Reactor Vessels B-N-3 Removable Core 1 Item None 0%

Yes Support Structures B-0 Pressure Retaining 3 Housings None Yes Welds in Control Rod Housings B-P All Pressure Retaining No Components System Leakage Test 163 Components 103 Components 63.19%

System Hydrostatic Test 21 Components O Components 0%

B-Q Steam Generator Tubing 100% of Technical Specifications met N/A F1.01 Class 1 Component 280 Supports 184 Supports 65.71%

No Supports tq v

Page 2 Revision 1 EQA373 August 2, 1991

Class 2 Inspections (g'

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Section XI Inspections Inspections Percentage Deferral Category Description Required Completed _

Completed Allowed C-A Pressure Retaining 9 Welds 6 Welds 66.66%

No Welds in Pressure Vessels C-B Pressure Retaining 6 Welds 4 Welds 60.66%

No Nozzle Welds in Vessels C-C Integral Attachments 33 Attachments 22 Attachments 66.66%

No for Vessels, Piping, Pumps and Valves C-D Pressure Retaining None N/A N/A N/A Bolting Exceeding 2 Inches in Diameter C-F Pressure Retaining 343 Welds 217 Welds 63.26%

No Welds in Piping 1

C-G Pressure Retaining 25 Welds 15 Welds 60%

No Welds in Pumps and Valves C-H All Pressure Retaining No Components System or Component" 68 Components 35 Components 51,47%

Functional Test System Hydrostatic Test 64 Components O Components 0%

F1.02 Class 2 Component 574 Supports 376 Supports 65.50%

No Supports Ih Page 3 Revision 0 EQA373 August 2, 1991 9

Augmented Inspections

'( )

Description Percentage Complete Reactor Coolant Pump Flywheels 100% of Technical Specifications roet Steam Generator Tubes on 100% of requirements for Outages 1, 2, Preheater Section 3, 4 & 5.

Main Steam Pipe Rupture Protection 100% of requirements for Outages 1, 2, 3, 4 & 5.

Containment Spray System 100% of requirements for Outages 1, 2, 3, 4 &

5.,

Thermal Stress Piping 100% of requirements for Outage 3, 4

&5 Safety Injection 100% of requirements for outage 5 Accumulator Nozzles l

(3 Page 4 Revision 0 EQA373 August 2, 1991

3.0 Final Inservice inspection Plan for Outage 5

)

The final ISI Plan presented in this section lists all examinations credited for Outage 5 at Catawba Unit 1.

This includes ASME Section XI

~'

Class 1, 2 and augmented inspections required by the plant technical specifications.

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

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

Item Number

=

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

IWF-2500 (Class 1, Class 2 and Class 3),

and Augmented Requirements Unique Identification Number ID Nuttiber

=

location and/or Detail Drawing Drawing Number

=

Location 1.ocs.

=

Examination Technique - Magnetic Particle, Dye Insp. Req.

=

Penetrant. etc.

Examination Procedures Proc. Numbers

=

Material Type / Grade =

General Description of Material Diam./ Thick Diameter / Thickness

=

Calibration Block Calib. Block

=

General and/or Detail Description Comments

=

l l

O Page 1 Revision 0 EQA373 August 2, 1991

m PAGE I

Ot*E P0HE3 CtHPAttf D*.TE 08/0 7J1

,,V PROGRAM: NISIRUNB-QAISI:2 OL'4LITY ASSURANCE DEPARTMEt4T FILE:

Cc07135 PRE-SERVICE AND Iti-SERVICE ItEPECTI0tt SYSTEM PLANT:

CATANSA UNIT 1 CATAtEA I IFEERVICE INSPE*TICl4 LISTItg2 - CUTAGE 5 KEY:

ITEM tAPBER 801 It4SP PROC.

NATERIAL DIAH./ CALIB ITEM PAJMBER ID. NUtBER DR&HING NUMBERS LOCS. REQ. t4 UMBERS TYPE / GRADE THICK BLOCK CCttfENTS

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CATAbeA LMIT l'

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ITEM MJPSER 801-LCATA>BA 1 INSERVICE INSPECTItH LISTING - CUTAGE 5 INSP PROC.

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ITEh NL9BER 802 CATAteA I INSERVICE INSPECTION LISTING - OUTAGE 5 IPCP PROC.

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DATE 08/0t/T1 PROG 3H: NISIntka-QAISIO2 QUALITY ASSURAtCE DEPARTMENT FILE:

C007133 PRE-SERVICE AND IN-SERVICE INSPECTIO4 SYSTEM PLANT:

CATAleA LINIT 1 CATAHBA 1 IPEERVICE IPGPECTIG4 LISTItG - OUTAGE 5 KEY:

ITEM NUtEER B04 ItGP PROC.

MATERIAL DIAM./ CALId DRAHIt4G NUPEERS LOCS. REQ. NUPEERS TYPE / GRADE THICK BLOCK COPNENTS

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C007133 GUALITY ASSURANCE DEPARTMENT-CA1E 08/07/i1~

PLAffT '

CATA>SA UNIT 1-PRE-SERVICE AND IN-LERVICE INSPECTION SYSTEM l

KEY:

ITEM NUISER BOS '

CATAleA 1 INSERVICE INSPECTIt94 LISTING - OUTAGE 5 i

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INSP PROC..

MATERIA' '- DIAM./ CALIB l

ITEM NL9BER ID. ' NLASER -

ORANING PAASERS LOCS. REQ. 7422ERS TYPE /GAADE THISK' BLOCK

. Ct99ENTS 5

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

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l C05.010.000 REACTOR VESSEL N0ZZLE TO SAFE ENOn*

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B09.021.050

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B09.040.116 '

1NI192-08 04/10/91 CLR' N

..i 809.040.161 IPN484-02, 04/10/91'

CLRi N

1-B09.040.162 INV484-04

.04/10/91 CLR N

B09.040.163 1NY48743 04/02/91 CLR N

809.040.164 INY487 04/02/91 CLR N

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PROGRAM: HISTRUND-QAISIO4 DUKE PO4EC COMPANY fAGE

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FILET CCO T135 QUALITY ASSURANCE CEPARTHENT DATE 08/12/01 PLAtUt CATAHBA LMIY I PRE-SERVICE AND IN-SERVICE INSPECTION SYSTEM KEY:

ITEN PAJHGER B09 CATAtBA 1 INSERVICE INSPECTIG4 RESULTS OUTAGE 5 INSPECTION INSPECTIOtt INSPECTION GEU.

ITEH NtitBER ID NUtBER DATE STATUS LIMITED REF.

CCtNENTS

==

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

==

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

B09.040.165 1NV487-11 04/02/91 CLR N

B09.040.166 1NV488-01 04/02/91 CLR H

B0 9. 040.167 IPN488-07 04/02/91 CLR H

B09.040.166 1F~68-10 04/02/91 CLR N

B09.040.169 IPN488-15 04/02/91 CLR H

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