ML20246N464

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Rev 1 to Inservice Insp Rept,Unit 2 Catawba 1987 Refueling Outage 1
ML20246N464
Person / Time
Site: Catawba Duke Energy icon.png
Issue date: 08/15/1989
From: Cherry J, Hogge A
DUKE POWER CO.
To:
Shared Package
ML20246N444 List:
References
NUDOCS 8909080131
Download: ML20246N464 (7)


Text

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5h INSERVICE INSPECTION REPORT UNIT 2 CATAWBA'1987 REFUELING.

OUTAGE 1 Location:

Hyw. 274, Newport, South Carolina NATIONAL BOARD NO. 173 COMMERCIAL SERVICE DATE: AUGUST 19, 1986 Owner:

Duke Power Company 422 S. Church St.

Charlotte, N. C.

28242 Revision 1

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Date Prepared By:

s.

Reviewed By:

O O

Date b/-

Approved By:

h Date

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Copy No.

5 Assigned To NRC Document Control j

Controlled x

Uncontrolled 8909080131 89o333 m.

EQA175

.gDR ADOCK 0500o414 PDC t

r CONTROLLED DISTRIBUTION Copy No.

Assigned To Original C. B. Cheezem 1

J. E. Cherry 2

J. O. Barbour (Catawba) 3 J. W. Snires (B&W Lynchburg) 4 P. G. Leroy (To Licensing File) 5 NRC Document Control UNCONTROLLED DISTRIBUTION 6, 7 P. G. Leroy (To Licensing)

EQA175

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C TABLE OF CONTENTS y

^ Section-Title.

Revision 1.

sSummary of. Inservice Inspection 0

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2.

Status of Reo' aired Inspections 1

3.

Final: Inservice Inspection-Plan for. Outage 1 0

.~ 4 ;

iResults of Inspections Performed During Outage 1 0

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Class.1-Inspection Results-0 6.

Class'2' Inspection Results 0.

7.-

fAugmentedInspectionResults-0 L8.

Personnel, Equipment, and Material Certifications 0

9.

Problem Investigation Reports-0

- 10.

Reference Documents 0-

. 11.

Classes 1 an'd 2. Repairs and Replacements 0

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' 2. 0. Status'of Reauired Inspections The l-completion' status of inspections required' by the 1980 ASME Code

~

Section XI, including addenda through Winter 1981,.is summarized in this' sect.fon, 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 i

SGction i

tXI Inspections Inspections Percentage Deferral Cateaory Description.

Required _

Completed Completed Allowed B-A.

Pressure Retaining 24 Welds 6 Welds 25%-

.Yes Welds in Reactor Vessel

-B-B Pressure Retaininc 8 Welds None 0%

No Welds in Vessels Other than Reactor 4

Vessels

.9-D Full Penetration Welds 36 Inspections None 0%

Partial' of Nozzles-in Vessels B.'~

Pressure Retaining.

55 Welds None 0%-

No Partial Penetration Welds;in. Vessels B-F Pressure Retaining 46 Welds 4 Welds 8.70%

No Dissimilar Metal Welds' l

B-G-1 Pressure Retaining 466 Items 60 Items 12.90%

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

  • 68 Connections 2 Connections 2.90%

No Bolting 2 Inches and Less'in Diameter

.B-H Integral Attachments

.9 Attachments None 0%

No For~ Vessels B-J Pressure Retaining 203 Welds 19 Welds 9 40%

No Welds in Piping B-K-1

' Integral Attachments for None N/A N/A N/A l

Piping, Pumps, & Valves

  • Total connections include CRDMS that are disassembled.

Page 1 Revision ]

. EQA175 August 14, 1989

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Class-1 Inspections (Continued)

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Section-XI Inspections Inspections Percentage.

Deferral Category-

_ Description-Required Completed Completed Allowed Ei-L-1

. Pressure Retaining Welds None N/A

.N/A N/A.

l' 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 Bodies > 4 In.

7 Valves None 0%

Yes Nominal Pipe Size B-N Interior of Reactor-3 Items 1 Item 33.33%

No-Vessel-B-N-2 Integrally. Welded Core

'None N/A N/A N/A

-Support Structures and Interior Attachments to 1

Reactor 1 Vessels

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'B-N-3

Removable Core 1 Item None 0%'

Yes' Support Structures B-0 LPressure Retaining 3 Welds 1 Weld 33.33%

Yes Welds in Control Rod Housings-B-P.

A1:1-. Pressure Retaining 180 Components 20 Components 11.10%

Yes Components B-Q Steam Generator Tubing 100% of Technical Specifiestions met N/A F1.01 Class 1 Component.

219 Supports 21 Supports 9.60%

No Supports I

i Page 2 Revision 1 EQA175 August 14, 1989

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Jt Class 2 Examinations Soction XI Inspections Inspections Percentage Deferral Category Description

__ Required Completed.

Completed Allowed C-A

'Pressuro Retaining 13 Welds None 0%

No i

Welds In Pressure Vessels C-B-Pressure Retaining 10 Welds None 0%

No Nozzle Welds in.

Vessels C-C' Integral Attachments 51 Items 11 Items 21.56%

No for Vessels, Piping, Pumps and Valves C-D Pressure Retaining 2 Items None 0%

No Bolting Greater than 2 Inches in. Diameter C-F Pressure Retainino 354 Welds 30 Welds 8.50%

No Welds in Piping C-G Pressure Retaining 25 Welds 6 Welds 24%

No Welds in Pumps and Valves C-H All Pressure Retaining 260 Components None 0%

No Components F1.02' Class 2 Component 492 %pports 61 Supports 12.40%

No Supports Page 3 Revision 1 EQA175 August 14, 1989 4

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. Augmented Inspectior,t

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! ercentage Complete.

. D'escri ption P

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Reactor Coolant Pump Flywheels Exams.

0%-

N.'

Steam Generator Tube Exams on.-

100% of_ requirements for Outage 1 Preheater Section-1" Main Steam Pipe Rupture Protection 100% of requirements for Outage 1 1;c ;

100%.of. requirements for Outage 1 r

Class 2 Piping Systems i

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af Page 4 Revision 1 August 14, 1989 EQA175