Text

ISI Rept Unit 2 Catawba 1990 Refueling Outage 3
	ML20062G722
Person / Time
Site:	Catawba
Issue date:	11/12/1990
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20062G720	List: ML20062G718; ML20062G722; ML20062G727;
References
	NUDOCS 9011300162
	Download: ML20062G722 (146)
	v • d • e

_

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V 145 Paces FORM NIS 1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules i, o,,,,

Duke Power Company, 422 S.~ Church St., Charlotte, NC 28201 (Name and Addres of Owner)

2. Plant CJtawba Nuclear Station. Hiahway 274. Newoort. SC 29710 (Name and Address of Plant)

N/A

3. Plant Unit 2

4. Owner Ceruficaer of Authonaation (if requwed) l73

3. Cocunercial Service Date 8/19/8b 6, National Board Number for Unit

7. Componene inspected Manufacturer Component of Manufacturer or lastaller

. State or Nanonal Appurtensace of installer Senal No.

Province No.

Board No.

SEE SECTION 1 PARAGRAPH 1.5 IN THE ATTACHED REPORT Notei Supplemental sheets in form of lists, sketches, of drawings may be used provided (1) size b 8% in x 11 in.,

(2) information in items I through 6 on this data report u included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

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9011300162 901120 (g

hDR ADOCK 05000414 PDC i

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INSERVICE INSPECTION REPORT UNIT 2 CATAWBA 1990 REFUELING OUTAGE 3 Location:

Hyw. 274, Newport, South Carolina 29710 NATIONAL BOARD NO. 173-00tNERCIAL SERVICE DATE: AUGUST 19, 1986 Owner:

Duke Power Company 422 S. Church St.

Charlotte, NC 28201 Revision 0

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J. O. Barbour (Catawba) W. D. Minton-(BWNS-Lynchburg) u

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TABLE OF CONTENTS Section Title Revision 1.

Summary of Inservice Inspection 0

2.

Status of Required Inspections 0

3.

Final inservice Inspection Plan for Outage 3 0

4.

Results of Inspections Performed During Outage 3 0

5.

Class 1 Inspection Results 0

6.

Class 2 Inspection Results 0

7.

Augmented Inspection Results 0

8.

Personnel, Equipment, and Material Certifications 0

9.

Problem Investigation Reports 0

10.

Reference Documents 0

11.

Class 1 and 2 Repairs and Replacements 0

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1.0 Summary of Inservice Inspection This report describes the Inservice Inspection of Duke Power Company's Catawba Nuclear Station Unit 2 during the 1990 Refueling Outage (also referred to as Outage 3).

Included in the report are the final Inservice Inspection Plan, the inspection results for each item, a summary for each category'of exami-nations, and corrective action taken when unacceptable conditions were found.

In addition, there is a section included for repairs and replace-ments required since June 4, 1989.

1. E Class l' Inspection The Class 1 Inservice Inspections included examinations on the Reactor Vessel Interior Surface, Steam Generator 2B Channel Head to Tubesheet Weld, Steam Generator 2B Primary Inlet and Outlet Nozzle Radiused Sec-tions and Inlet and Outlet Nozzle to Safe End Butt welds.

In addition, the Dissimilar Metal Butt Welds in Reactor Coolant (NC) System were examined.

Reactor coolant Pump 28 Main Flange Bolts and Seal Gland and Seal Housing Bolting and Class 1 Valve Bolting and Internal Surfaces received examinations. Circumferential butt welds in piping of Reactor-Coolant (NC), Residual Heat Removal (NO), Safety Injection (NI) and Chemical and Volume Control (NV) Systems were examined.

Socket welds in the Chemical and Volume Control (NV) System also received examinations.

. f ').

4 Visual examinations were performed on the Class 1 Pressure Boundary during System Leakage Tests. Also, visual examinations were performed on Class 1 Component Supports of Reactor Coolant (NC), Safety Injection (NI), and Chemical and Volume Control-(NV) Systems.

The Inconel 600 tubing in Steam Generators 2A, 2B, 2C and 2D was inspected by eddy current during outage 3.

The results are shown in the Catawba 2 Refueling Outage 3 Eddy Current Examination Report, s

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

Inspection and evaluation' data for each reportable indication found-on Class 1 Inspections is included in Section 5 of this-report.

Inspection and evaluation data for each reportable incication found during Class 1. Eddy Current Inspection is found in the Catawba 2 Refueling Outage 3 Eddy Current Examination Report.

A detail description of each inspection is found in the final Inservice Inspect' ion Plan in Section 3 of this report.

Results of each examination are found in Section 4.

1.2 Class 2 Inspection The Class 2 Inspections included examinecions on the Safety Injeccior.

Accumulator Tank 28 Shell to Lower Head Weld, Outlet Nozzle to Lover

/7 Head Weld and on vessel integrally-welJed attachment on Support Siirt to V'

Lower Head.

Also, examinations were performed on piping integraliy-Page 1 Revision 0 EQA298 November 2, 1990

II welded attachments of the Safety Injection (NI) and Main Steam (SM)

Systems.

In addition, examinations were performed on circumferential butt welds in the Auxiliary Feedwater (CA), Residual Heat Removal (ND),

Feedwater-(CF), Safety Injection (NI), and Main Steam (SM) Systems.

Examinations were performed on longitudinal butt welds in Residual Heat Removal (ND) System and on 2CF60 Valve Body Weld.

Visual examinations were performed on the Class 2 Component Supports of Auxiliary Feedwater (CA), Residual Heat Removal (ND), Safety injection (NI), and Main Steani (SM) Systems.

Reportable indications were found on the Class 2 Inspections shown in this section.

Inspection and evaluation data for each reportable indi-cation found on Class 2 Inspections is_ included in Section 6 of this report.

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

Results of each examination are found in Section 4.

1.3 Augmented Inspection Augmented inspections consisted of Reactor Coolant Pump Flywheel exami-nations, Steam Generator Tubing examinations and examinations on the Main-Steam System for Pipe Rupture Protection.

i

Reportable indications were found on the Augmented Inspections shown in

-this section.

Inspection and-evalua. ion data for each reportable indi-cation found on Augmented Inspection is included in Section 7 of this report.

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 3.

-1.5 Identification Numbers i

Owner:

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

Catawba Nuclear Station, Highway 274, Newport, SC 29710 Plant Unit:

2 Owner Ccrtificate of Authorization:

N/A Commercial Service Date:

8/19/86 Page 2 Revision 0 4

EQA298 November 2, 1990

l 1

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Manufacturer State.or National Manufacturer or Installer Province Board Item or Installer Serial No.

No.

Reactor Vessel CE 8871 N/A 21667 Pressurizer-Westinghouse 1931 N/A W26949 Steam Generator 2A Westinghouse 1923 N/A 4

Steam Generator 2B Westinghouse 1922 N/A 3

Steam Generator 2C Westinghouse 1921 N/A 2

Steam Gcnerator 2D Westinghouse 1924 N/A 5

Reactor Coolant System Duke Power Co.

C-2NC N/A 171 Residual Heat Removal System Duke Power Co.

C-2ND N/A 154 Safety Injection System Duke Power Co.

C-2NI N/A 172 Chemical: And Volume Control System Duke Power Co.

C-2NV N/A 170 Auxiliary Feedwater System Duke Power Co.

C-2CA N/A 159 Feedwater System Duke Power Co.

C-2CF N/A 158 Refueling Water System Duke Power Co.

C-2KF N/A 151 Main Steam Supply to Auxiliary Equipment System Duke Power Co.

C-2SA.

N/A-134 Main Steam System Duke Power Co.

C-2SM N/A 162 Main Steam Vent to (V -

Atmosphere System

-Duke. Power Co.

C-2SV N/A 156 t

Safety Injection.

Southwest Accumulator Tank 2A Fabrication &

Welding Co.

0023 N/'t 313 Safety Injection Southwest Accumulator Tank 2B Fabrication &

Welding Co.

0024 N/A

-314 Safety: Injection Southwest Accumulator Tank 2C Fabrication &

Welding Co.

0030 N/A 320

-Safety' injection.

Southwest Accumulator Tank 2D Fabrication &

Welding Co.

0031 N/A 321 Unit 2 Duke Power-Co.

N/A N/A 173 1.6 The Reactor Vessel', Steam Generators, Pressurizer, Reactor Coolant System Piping, Reactor Coolant Pumps, and Safety Injection Accumulator Tanks were manufactured by or for Westinghouse Elect:

Carporation, Pittsburgh, PA.under purchase agreements from Duke Power Company.

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

Page 3 Revision 0 EQA298 November 2, 1990

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1.7 Authorized Nuclear Inservice Inspector (s) r

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Name(s):

R. N. McGill 1

Employer:

The Hartford Steam Boiler Inspection and Insurance Company Business Address: The Hartford Steam Boiler Inspection and Insurance Company 1117 Perimeter Center W., Suite E-301 Atlanta, GA 30338 i

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QUALITY ASSURAfCE DEPARTIENT 04TE 11/01/90

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C007133 PRE-SERVICE Afe IN-SERVICE INSPECTItSt SYSTEM LANT:

CATA>6A UNIT 2 EY ITEM tRJteER 816 CATAPSA 2 CLASS 1 REPORTABLE ITEMS - ERFTAGE 3 l

. INSP PROC..

MATERIAL OIAM./ CALIS IEM tt."eER ID. NU2ER DRAMING IGASERS LOCS. RE9. ft99ERS TYPE / GRADE TNICK BLOCK Ct90ENTS

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11.023.000 ********* STEAM GEDERAftNt TUBINGe**w

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14.023.003 2SGC-TUBES Cta12201.01-102 ET 151-424 IN 00.75 SELECT CALIBIC ION STANDARD i

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ITEM NUPBER Col.

CATUBA 2 CLASS 2 REPENtTABLE ITENS - StJTAGE 3 INSP PRCE. -

MATERIAL DIAN./ CALIS TEM NUPSE2 ID. MJPSER DRANING IOSERS LtES. REG. IRJPBERS TYPE / GRADE THICK SLOCK Ct99EENTS

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2.0 Status of Required Inspections The completion status of inspections required by the 1980 ASME Section XI Code, including Addenda through Winter 1981, 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 IWC-2500-1 for Class 2 Inspections. Augmented inspections are also included.

Class 1 Inspections s

Section XI Inspections Inspections Percentage Deferral Category' Description Required Completed Completed Allowed B-A Pressure Retaining-24 Welds 6 Welds 25%

Yes Welds in Reactor Vessel B-B-Pressure Retaining 8 Welds 3 Welds 37.50%

No Welds in Vessels Other than Reactor Vessels

. B-D Full Penetration Welds 36 Inspections 12 Inspections 33.33%

Partial of Nozzles in Vessels B-E Pressure Retaining 55 Welds 55 Welds 67% Credited No Partial Penetration Welds in Vessels B-F-Pressure Retaining 46 Welds 18 Wolds 39.13%

No Dissimilar. Metal i

Welds B-G-1 Pressure Retaining 466 Items 171 Items 36.69%

Yes Bolting Greater Than 2 Inch =in Diameter B-G-2 Pressure Retaining

68 Connections 28 Connections 41.17%

No Bolting 2 Inches and i

'Less in Diameter B-H Integral Attachments-9 Attachments 3 Attachments-33.33%

No For Vessels

Total Connections include CRDMs that are disassembled.

9

=

Page 1 Revision 0 EQA298 November 2, 1990 i

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Class 1 Inspections (Continued)

Section XI Inspections Inspections Percentacc Deferral Category Description Required Completed Completed Allowed B-J Pressure Retaining 203 Welds 89 Welds 43.84%

No Welds in Piping B-K-1 Integral Attachments for None N/A N/A N/A Piping, Pumps, & Valves B-L-1 Pressure Retaining Welds None N/A N/A N/A in Pump Casings B-L-2 Pump Casings None N/A N/A N/A B-M-1 Pressure Retaining Welds 2 Welds None 0%

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

7 Valves 4 Valves 57.14%

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

No Vessel lh I

B-N-2 Integrally Welded Core None N/A N/A N/A 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 1 Housing 33.33%-

Yes Welds in Control Rod Housings B-P All Pressure No-Retaining Components System Leakage Test 160 Components 60 Components 37.50%

System Hydrostatic 20 Components 0 Components 0%

Test B-Q

-Steam Generator Tubing 100% of Technical Specifications met N/A F1.01 Class 1 Component 218 Supports 78 Supports 35.77%

No Supports t rx l' O s

Page 2 Revision 0 EQA298 November 2, 1990

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Class 2 InspectionsSection XI Inspections Inspections Percentage Deferral

-Category Description Required Completed Completed Allowed C-A Pressure Retaining 9 Welds 4 Welds 44.44%

No Welds In Pressure Vessels e

C-B Pressure Retaining 6 Welds 3 Welds 50%

No Nozzle Welds in Vessels C-C Integral Attachments 50 Attachments 2C attachments 56%

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 347 Welds 117 Welds 33.71%

No Welds in Piping l

O C-G Pressure Retaining 25 Welds 8 Welds 32%

No V

Welds in Pumps and Valves C-H All Pressure Retaining No Components System or Component 68 Components 34 Components 50%

Functional Test System Hydrostatic 92 Components 0 Components 0%

Test F1.02 Class 2 Component 492 Supports 191 Supports 38.82%

No Supports A.

V Page 3 Revision 0 EQA298 November 2, 1990

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Augmented Inspections Description Percentage Complete Reactor Coolant Pump Flywheels 100% of Technical Specifications met Steam Generator Tubes on 100% of requirements for Outages 1, 2, & 3 Preheater Section Main Steam Pipe Rupture Protection 100% of requirements for Outages 1, 2, & 3 Class 2 Piping Systems 100% of requirements for Outages 1, 2, & 3 Thermal Stress Piping 100% of requirements for Outages 2 & 3

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Page 4 Revision 0 EQA298 November 2, 1990

l 3.0 Final inservice Inspection Plan for Outage 3 f"/

The final ISI Plan presented in this section lists all examinations N

L credited for Outage 3 at Catawba Unit 2.

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:

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, & Class-3), and Augmented Requirements ID Number Unique Identification Number

=

Location and/or Detail Drawing Drawing Number

=

Locs.

Location

=

Insp. Req.-

Examination Technique - Magnetic Particle, Dye

=

Penetrant, etc.

Proc. Numbers Examination Procedures

=

Material Type / Grade =

General Description cf Material jh Diam./ Thick Diameter / Thickness

=

Calib Block.

Calibration Block

=

General and/or Detail Description Comments

=

i nkl Page 1 Revision 0 EQA298 November 2, 1990

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PAGE' 1

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PROGRAPf: N1SIMSG-gAISIO4 '
OUKE PtBER CE9eANY PAGE 33 t
FILE:
.C007133-WALITY meAfCE SEPARTVE9ff DATE 10/26/99 KEY: ' CATafeA 1981T 2 PRE-SERVICE Afe IN-SERVICE INSPECTItBd SYSTEM PLANT:
ITEM PGJUSER GO3 CATApeA 2 INSERVICE INSPECTIt90 RESUL(5 - SJTAGE 3 6
I INSPECTIt96-INSPECTIt90 INSPECTItSt GES.
' ITEM 9RDBER ID9tpeER DATE STATUS LIMITE8 REF.
Ct99ENTS
==
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==
==
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i G03.001.0094 2SM38-15 07/26/90' CLR N
903.001.010 2SM-88-A 08/07/90 CLR L'
Y G03.001.010A 2SM-88-A 08/01/90
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5.0 Class 1 Inspection Results Examinations were performed during Outage 3 on the Reactor Vessel, Steam Generators 2A,.2B, 2C and 2D, Piping Welds of Reactor Coolant (NC),
Residual Heat Removal (ND), Safety Injection (NI), and Chemical and Volume Control (NV) Systems, Pump Bolting, Valve Bolting, Valve Internal Surfaces and Supports.
5.1 Reactor Vessel The accessible internal surfaces of the Reactor Vessel were visually inspected.
No reportable conditions were found.
5.2 Steam Generators Steam Generator 2B Channel Head to Tubesheet Weld received an ultrasonic examination.
No reportable indications were found.
Steam Generator 2B Primary Inlet and Outlet Nozzles Radiused Section received an ultraronic examination.
No reportable indications were found.
~
Steam Generator 2B Inlet and Outlet Nozzle Safe-End Welds received n
ultrasonic and dye penetrant examinations.
No reportable indications
()
were found.
5.3 Pumcs Reactor Coolant Pump 28 Main Flange Bolting received ultrasonic and visual: examinations-No reportable indications or condition were found.
~ Reactor Coolant Pump 2B Seal Gland and Seal Housing Bolts received a visual examination. No reportable conditions were found.
'5.4.Pipina Dissimilar Metal Butt Welds-Two (2) Reactor Coolant System (NC)-Safe-End to pipe welds four inches and greater received ultrasonic and dye penetrant examinations. No reportable indications were found, i
Similar Metal Butt Welds:
Eleven (11) circumferential welds four inches and greater received ultrasonic and dye penetrant-examinations. Two (2) circumferential welds less than four inches received a dye penetrant examination.
Fourteen (14) socket welds received a dye penetrant examination.
No reportable indications were found.
Page 1 Revision 0 E0A298 November 2, 1990
l.
.wl i
2 Piping Supports:
Eighteen-(18) Class 1 Component Supports received a visual examination as required by ASME Section XI, Article IWF-2000.
No reportable conditions were found. -
5.5 Valves The internal surface of valves 2NI-82, 2NI-125 and 2NI-175 received a visual examination.
No reportable conditions were found, f'
5.6 Steam Generator Tubing (See Catawba 2 Refueling Outage 3 Eddy Current Examination Report) 5.7 System t.eakage Test The Class-1 Pressure Boundary was subjected to a system leakage test as required by ASME Section XI, Article IWB-5000.
No reportable conditions were found.
-5.8 Class 1 Repairs and Replacements 7-~3 Repairs and replacements for work performed from June 5, 1989 to Septem-(j ber 8, 1990 are itemized in Section 11 of this report.
-ry b
page 2 Revision 0 EQA298 November 2n 1990
t t
u 6.0 Class 2 Inspection Results Inspections were performed during Outage 3 on Safety injection Accumula-tion Tank 2B, piping integrally-welded attachments, Piping Welds of Reactor Coolant (NC), Residual Heat Removal (ND), Safety Injection (NI) and Chemical and Volume Control (NV) Systems, Valve and Supports.
6.1-Safety Injection Accumulator Tanks Safety Injection Accumulator Tank 28 Shell to Lower Head Weld received an ultrasonic examination, and Outlet Nozzle Weld to lower Head received ultrasonic and magnetic particle examinations.
No reportable indications were found.
Safety Injection Accumulator Tank 2B Support Skirt to Lower Head Inte-grally-Welded Attachment received a magnetic particle examination.
No reportable indications were found.
6.2 piping Welds:one-half inch and less nominal vall thickness:
Nine (9) circumferential welds received a magnetic particle examination.
Twelve (12) circumferential welds and eight (8) longitudinal welds jg[
received a dye penetrant examination.
No reportable indications were w
found.
Welds greater than one-half inch nominal wall thickness:
Eight (8) circumferential welds received an ultrasonic and a magnetic particle examination.
Twelve (12) circumferential welds received an ultrasonic and a dye penetrant examination. One'(1) circumferential weld received a radiographic and a magnetic particle examination.
No report-able indications were found.
piping Integrally-Welded Attachments:
Eleven (11) integrally-welded attachments on Main Steam (SM) System received a magnetic particle examination and one (1) integrally-welded attachment on Safety injection (NI) System received a dye penetrant examination. A reportable indication was found on weld 2-R-SM-1555,
^(Item Number _C03.020.064). The weld indication was repaired and.re-ex-amined and found acceptable (refer to, Problem Investigation Report 2-C90-0246 included in Section 9 of this report). The inspection data sheets are included in this section of the report.
The scope of the inspection was extended to include eleven (11) additional attachment welds,.per ASME Section XI, Paragraph IWF-2430(a).
No other reportable indications were found, p-One (1) integrally-welded attachment on the Safety injection (NI) System-(
received a dye penetrant examination.
No reportable indications were found.
Page 1 Revision 0 EQA298-.
November 2, 1990-
I l'
O 6.3 Valves Valve 2CF60 valve-to-bonnet weld received a magnetic particle examina-tion. No reportable indications were found.
6.4 Component Supports Fifty-three (53) Class 2 Component Supports received a visual examination as required by ASME Section XI, Article IWF-2000.
No reportable condi-tions were found.
6.5 Class 2 Repairs and Replacements Repairs and replacements for work performed from June 5, 1989 to Septem-ber 8, 1990 are itemized in Section 11 of this report.
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O Page 2 Revision 0 1
EQA298 November 2, 1990 l
11 O '~~'
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DUKE POWER COMPANY PROJECT CATAWBA MAGDETIC PARTICLE /UQUC PEPETRANT EXAMMATION REPORT 2-R-SM-1555 Unit Na 2
Date 8-28-90 Weid Na Diameter N/A Senedule/TNcknees
.750 Type Material SS O CS E 3045 MES QA CondWon 1
Work Order Na 14 NDE2SB-J / Rev SKETCH OF ITEM EXAMINED Procedure NDE.96 Appmed M/A N/A Radle.cn Lewel Inspector Level lh/AA1)f II LO in - e.co in - e.on -
Number Length / Width / Diameter, etc.
Acceptable Repvrtable Reference Documents NONE
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MT DATA PT DATA MT Method Used FT Batch Number O FluorsecentXINonfluorescent O Wet nDry Cleaner Penetrant Ale /
MT Unit Sertal Na rwn-?4 Deve6oper 7
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Remarks weld number 1 Ryes O No
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f) sm-7.0 Augmented Inspection Results
. Augmented inspections were performed on the Reactor Coolant Pump Fly-wheels, Steam Generator Preheater Sections and on the Main Stream System for Pipe Rupture Protection.
7.1 Reactor Coolant pump Flywheels Reactor Coolant Pump 2A and 2B Flywheels received an ultrasonic examina-tion in place. No reportable indications were found.
7.2 Pipe Rupture Protection Ten (10) welds on the Main Steam System received an ultrasonic and a magnetic particle examination. No reportable indications r-e found.
7.3. Steam Generator preheater Section All four steam generators were examined by eddy current methods.
Results and evaluation data for examinations are shown in the Catawba 2 Refueling Outage 3 Eddy Current Examination Reports.
6 i
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v Page 1 Revision 0
_ EQA298-November 2, 1990
i O
8.0 Personnel. Equipment, and Material Certifications All personnel who performed or evaluated the results of inservice inspections from June 4, 1989 to September 8, 1990 at Catawba 2 were certified in accordance with the requirements of the 1980 ASME Section XI with Addenda through Winter 1981.
The appropriate certification record for each Duke Power Company inspector is on file at Catawba Nuclear Station or in the Corporate Offices in Charlotte, North Carolina. The certification records for the Babcock and Wilcox inspectors are on file at the Babcock and Wilcox offices in Lynchburg, Virginia.
Records of periodic calibration of Babcock and Wilcox inspection equip-ment are on file at the Babcock and Wilcox offices in Lynchburg, Virginia.
Records of periodic calibration of Duke Power Company inspection equip-ment are on file at Catawba Nuclear Station or in the Corporate Offices in Charlotte, North Carolina, e
.i e
Page 1 Revision 0 EQA298 November 2, 1990
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9.0 Problem Investication Reports A copy of each Problem Investigation Report resulting from reportable items, originated against scheduled inservice inspections performed during Outage 3, is included in this section.- All were resolved and found acceptable by Duke Power's Quality Assurance Department before returning Unit 2-to service. The following Problem Investigation Report-was issued:
P.I.R. No.
Description Date Issued 2-C90-0246 Class 2 Integrally-Welded 07-20-90 Attachment - SM System DJ Page 1 Revision 0 EQA298 November 2, 1990
I marim*es consptava ronas sY PRINTING WITH BLACM BALL POINT PEN OR TYPE 1
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PROBLEM INVESTIGATION REPORT VI. Proposed Hoeolution of Probier.1 C,MlN
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Attschment to PIR 2-C90-0246 A
VI. Proposed Resolution of Problem:
The weld identified on this " ~. As shown on drawing 2-R-SM-1555 as being a 5/16 inch by 1 (one) inch fillet weld attaching a saddle plate to the main steam piping. The main steam pipe is 34 inches in diameter and approximately 1-1/2 inches thick. The saddle plate is 3/4 of.an inch thick. Any thermal growth of the SM (main steam) pipe could initiate a crack in this size weld. There have been other failures on saddle welds of this design. These weld failures were in the same location. Design should evaluate the significance and structurai integrity of the weld identified by this PIR to preclude repetitive analysis.
bY YYAAdhl-
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PROBLEM INVESTIGATION REPORT v
Pogo 2 PIR No. 2 - C 9 O - 62 4b VI. Proposed Resoluton of Problem
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DUKE POWER COMPANY 10/11/90 PIR RES01MIION PAGE 1 0F 1 Problem Investigation Report Serial No. 2-C90-0246 The reference PIR identifies a fillet weld 5/16 inch by 1 inch attaching a saddle plate to the main steam piping (2-R-SM-1555). The main steam pipe is 34 inches in diameter and approximately 1-1/2 inches thick. The saddle plate is 3/4 inches thick. Any thermal growth of the SM (main steam) pipe could initiate a crack in the saddle plate weld.
There have been other failures on saddle welds of this design.
These weld failures were in the same location.
Design should evaluate the significance and structural integrity of the weld identified by this PIR to preclude repetitive analysis.
O The Proposed Resolution To PIR 2-C90-0245 l
l The saddle weld on support (2-R-SM-1555) is not a structural load bearing weld.
It's primary function is to prevent misalignment, to hold the saddle in place.
In this case, if both saddle welds were cracked to the point they could no longer carry any load the integrity of the support to perform it's intended function would still not be compromised. Therefore, the we k identified by this PIR has no significant impact on the structural integrity of the
, support.
This resolution does not attempt to classify or qualify all saddle welds as non-structural. Other saddle weld failure's must be evaluated on a case by case basis.
10/11b8:=
By 'BA 4M
. Date V
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^us isties ror 203i DUKE POWER COMPANY DE m. m N Wi-PIR REYlEW OE0 VEST NTE-8'7'T REF. PIR-8 ~ #- f * # E V '
(COPY ATTACHED)
THROUGH PIR COORDINATOR, PR(UECT MAP AGEMENT OROUP T0. - I d
(TO BE FILLED IN BY PMG)
DE$10NTNGINEERING DEPARTMENT 5
DESION ENGINEERING l$ REQUIRED TO PROYlDE AS$1 STANCE AS SPECIFIED SELO I
FOR THE ATTACHED PIR.
REPLY NEEDED BY:
E OPERA 81LITY EVALUAil0N $UPPORT REPORTA61LITY EVALVATION SUPPORT I/ PROPOSED RESOLUTION (ITEM p: ws )
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(* REQUEST ONLY AFTER STATION QA APPROYAL OF RESOLUTION)
STAil0N CONTACT IS:
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10.0 Reference Documentt l
The following reference documents apply to the inservice inspection performed during Outage 3 at Catawba 2:
None.
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' EQA298L November!2,-1990
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11.0 Class 1 and 2 Repairs and Replacements As required by ASME Section XI, 1980 Edition, a record of the Class 1 and 2 Repairs and Replacements for work performed from June 5, 1989 to September 8, 1990 is provided and is included in this section of the report.
The individual work request documents are on file at the Catawba Nuclear Station.
l O
Page 1 Revision 0 EQA298 November 2, 1990
i; n
CATAWBA NUCLEAR STATION UNIT 2 EOC 3 REPAIR / REPLACEMENT LOG ASME SECTION XI-1981
,Lo Examination Dates:
From 06/05/89 To 09/08/90 Prepared By:
QA Technical Support Transhiitted By:
N* J Date:
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Descr ip tion -
,. _ :w ME5: 00193
[B-REPLtd.'E STRAP [ PORTION.. OF FIG ' aim MINI-STIFF CLAMP 2-R-BD-1010,. R-BB-1041x AND 2-R-DB-1043
'ME5100193-
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- REPLACE:51 RAP: PORTION OF f-20 P W MINI-STIFF... CLAMP 2-R-KN-1708, g-22-R-KC-1901,y2-R-KC-1724 AND'2-R-KC-1728 c6ME5 00743 Ai
-STEAMLGCNERA10R 2A,~28.-2C, 2D MANWAYJBOLTS WERE GOUND AND.MACIIINED
~~MES OOG48e 2B!~~
REPLACED REAR IIRACKET PIN-2-R-SM-1540" 1:
MC5 00852 4 Dc
'REPLACEiSNUBBER'2-R-CA-1646
- MES;01965 AJ DISASSEMBLED.VALUE'2NI125 - NO Pn'tT5 REPLACED MCG'Otv46 A1
. DISASSEMBLED VALVE 2NI175 -- NO PARTS REPLACED 1
~~NES-02201~~
'S-
' REPLACED ANCHORS ON SUPPORT 2-R-ND-OO47 NE5 02470' B
RCPLSSTRP PORTION OFfMINI STIFF CLAMP 2-R-NU-264 ME5 02477 LDL
~~REPLACED STRAP ' PORTION ' OF ~ TIE MINI STIFF CLAMP DN~~
~~2-R-ND-474,-2-R-ND-498, 2-R-ND-410, 2-R-ND-415~~
~~.MES ~ 02470.~~
~~B-REPL'5TRPJORTION OF MINI, STIFF CLAMP 2-R-N."-1530 MES O2479 B"~~
~~REPL'STRP PORTION-OF MINI STIFF CLAMP 2-R-NI-1564 MES O2489.~~
8L REPLACED STRAP? PORTION HINI STIFF CLAMP-ON 2-R-HV~0123 2-R--;UJAOM6, 2-R-NU-0251, 2-R-NV-0253
.MES:02G07
~
B REPLACED DONNET/ BODY CASKET AND VALVE DISC 5 ON 2NV338
.MC5~02YOO:
B-C REPLACED PIPE CL(+lP 2-R-5A-0014
,MES O2939-
=B REPLACED SNOBBCR t2-R-5M-1556)
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MES O2739
-D.
~~2-R-SM-1S61-REPLACED WF DCAM & GU55ET-F' HE5 03039 B~~
l CUT DUrfVALVE 2NV325 2
MES 03040 D
~~CUT DUT VALVE'2NV326 i~~
.MES 03501:
D i.:
REPLACC SNUBBER'2-R-ND-0326
.MES 03541
.D REPLACED SNUBBER BODY 2-R NO-0277 HEG'03562
O.
~~REPLACE SNUBBER 2-R-5A-1SO3, REPLACED STUD hES 03567.'~~
B :/
REPLACED $ NAP RING 2-R-NI-1685 MES'03610 0...
REPLACED CAP 15 CREWS ON SNUBBER 2-R-UB-1003 MES'03630 A-
, REPLACED'VALUE5-2NC19 &.2NC2O
-- M E 5 03647:
-D REPLACED SNUBBER! & LOAD ~STUO 2-R -5M-1000 MES 03647' 8-REPt. ACE'SNUeDER 2-R-SM-1oOo MES 03660-Di
- REPLACED 15A PIPING 1150 25A4.
MES 09660-2 D
REILACED COTTER PIN ( 2--R-5 A-1529 )
' 1REPt. ACED PIPEiCLAMP (2-R-5A-1530)
MES 03664 IL - REPLACED ROD END ON' CLAMP END OF STRUT R-CA-1643 REPLACED PLATC MATERIAL U 2-R-CA-1442 7
~~HNI?064 %~~
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REPLACED NOT;ON:UDNNET-VALVE 2NV17
~
? N5M ' 03;M7 ;
D
~~RCPLACED BONfE1 5TU05 AND NUT 5 ON VALVE 25VO13 i.~~
~~' NSf t 0 H2110 LO~~
~~EPLACED #dLfDONNET STUD 5 ON: VALVE 25V019~~
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Class Descrip t.io tt NSM 03609-D REPLACED VALUE 2NI161
~~NSM OD702 D:~~
- REPf_ ACED - VALUE-2NV205.
i' H5M 03714 D
' CUT ACCESS HOLE 5/G "2A" -- W. FLANGE AND-BOLTING MATERI AL
' N5M 11936 0
- REPL.5NUBBER WITH STRUT, REPL LOAD PIN 2-R-ND-0337 N5M 19053
.O CUT-OUT' VALVE 2BOOBA NSM 13462
'O CUT DUT UALVE-2CA30A N5M 13063 0
. CUT.DUT VALVE 2CA42B NSM 1 3 0 6 4..
O
~~CUT GUT' UALUE 2CA468 N5M A3065.~~
O CUT DUT UALVE 2CASOA N5M 13046 U
CUT GUT VALUE,2CAS4D N5M 13067' B
CUT DUT VALVE 2CASDA NSM 13060 7
UCT DUT VALUE 2CA62A l-JSM 13069 O
CUT'OUT VALVE 2CA668 N5M 13093 G
CUT GUT VALVE 2BB19A N5M u 130'74
'O CUT-OUT VALVE 2 GDS 6A NLM-13095
.D
-CUT OUT VALVE 2BD60A~
N5M 13327 D
CUT OUT VALUES'25AOO2 & 25AOOS N5M 1932/
O 2-It-5A-1520 -_ REPLACE ANCHOR 5, TUDE STEEL, PLATE OPS 30033-4 D
CUT DUT-VALUE:25AOO2, WELD 5 25Al-5,4 OPS 304.13
~~O CUT OUT'UALUE 2NU315 - WELDS 2NU626-14,15 OPS 39729 D~~
_ REPLACED BONNET STUD 5.ON VALUE L%eLA12 OPS el1092 D
REPLACED INTERNALS
&' NOZZLE ON RELIEF VALVE 2NI161 Ops 41099 A-
- REPLACEO'SOME-INTERNAL PARTS ON ENI-163 OPS 41357 O
- 25V1 REPLACE DONNET, STUD 5 AND NUTS OPS 43391 O
REPLACED STUD 5/ NUT 5 ON FLANGES - UALUE 2NV172A OPS 45120-2 O
REPLACED LOAD PINS 2-R-NM-1414 OPS 4 *' 3 3 2 '-
18 REPLACED VALUE'2NV14 OPS elS390 0
REPLACE RELIEF VALVE 2NV305 UP5 45452 D
Ct M OUT'UALVE 25M748 ACE TI'E WEDGE AND STEM ON VALUE EMIlO3A OPS elS435 D
RL f
OPS 45YO6 0
REa 4.CED, NUZZLE IN RELIEF. VALVE 2NI119 OPS-464P/:
D REPLACED DONNET ON VALUE 25U204 UPS 46S$P
'A-DISASSEMBLED UALUE ENC 106'- NO PARTS REPLACEL OPS 467341
- UALVC 2NDOO3.WA5: REPAIRED AND REPLACED t IPS 4N/60 A
DIEA55EME2ED UALVE ENC 13 - NO PARTS REPLACED OPS 468741 A
- DISA55EMDLEC VALVE ~UNC94 - NO PARTS REPLACED pl tl 03206 11
' CliT-UUT UALUE 2BDO60A - tJELD5 2BB41-1,2,3,7 AND 20042-3 PLtd (s3M96 A
. RCPLACE SNAP. RINGS ON WASHERS 2-R-NC-1700.' REPLACED PIN & SNAP RING 5 ON 2-R-tvC-167S n
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Description
-_5WR. 04472 A
REPLACED VALUE.2NC2 4
-SWR 04473
' A
- REPLACED UALUE-2NC3 SWR'04499 i A REPLACED VALVE 2NC1
' SWR 05292 A
~ REACTOR'VE5SEL. FLANGE, CHASED THREADS ON STUD HOLE #6 l-SWR OS292 A
DI5A55EMDLED RV teEAD'- NO PARTS REPLACED
-SWR 05312 A
DISA55EMDLEO.RV HEAD THERMOCOUPLE - NO PARTS REPLACED SWR-06204 A-DISA55EMDLED UALVE 2NIO1 -- NO PARTS REPLACED SWR 06200' Az
' DISA5SEMBLED VALVE 2NIGE REPLACED DONNET, STUD 5, NUT 5 SWR.06310 A=
ENTEREI' 5/G "2D"
. NO PARTS: REPLACED SWR 06319.c A
ENTERED 5/G "2C"
'NO'PART5 REPLACED
~
SWR 06320
' A SINTERED. 5/G "2D" -. NO PARTS FMPLACED SWR 06321 A:
ENTERED 5/G:"2A"'- NO PARTS REPLACED j'
SWR 06061 D
' REPLACED HANDHOLE/ INSTRUMENT COVERS - REPLACED DOLT 5 DN COVER
- SWR 06081
~ R.C.-PUMP "D" REPLACEO MECH. SEAL 5 ON PUMP
' SWR 09442-2 D
' REPLACED SPACER WASHER & SNAP RING 2-R-NU-139 Y
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