ML20247A503

From kanterella
Jump to navigation Jump to search
Inservice Insp Rept Unit 1 Catawba 1987 Refueling Outage 2
ML20247A503
Person / Time
Site: Catawba 
Issue date: 04/07/1989
From: Hogge A
DUKE POWER CO.
To:
Shared Package
ML20247A459 List:
References
NUDOCS 8909120134
Download: ML20247A503 (6)


Text

. _ _ _ _ -

.Q. ' W' :

  • 4.:

INSERVICE INSPECTION REPORT UNIT 1 CATAWBA 1987 REFUELING OUTAGE 2-Location:

Hyw. 274, Newport, South Carolina NATIONAL BOARD NO. 130 COMMERCIAL SERVICE DATE:

JUNE 29, 1985 Owner: -Duke Power Company

~

422 S. Church St.

Charlotte, N. C.

28242 Revision 1 t

-1 1

l Prepared By:

Date

-d-((

  1. '[- 89 Revsewed By:

3 Date Y-7 ~N Approved By:

m i

Date D

l Copy No.

5 Assigned To NRC Document Control Controlled,

X Uncontrolled C/6550049 6909120134 890E:31 E -- {DR ADOCK 05000413 1

n

.'ph ' 4,,-

]N 4[',

l bi,

.t

.t

. TABLE OF CONTENTS-Section

' Title Revision 1.

Summary of-Inservice Inspection 0

2.

. Status of Require'd Inspections _

l'

- 3.

Final Inservice Inspection Plan for Outage 2-0 4.

Results of' Inspections Performed During Outage 2 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.

Classes 1 and 2 Repairs _and Replacements 0

f C/6550049 t __ __

y',,,..

1 ne 2.0 Status of-Required Inspect' ions L.

- The completion - status - of inspections ' required by the 1980 ASME ' Code Section.XI, 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 InspectionsSection XI Inspections Inspections Percentage Deferral' Category.

Description.

Required Completed Completed Allowed B-A Pressure Retaining 14 Welds 2.5 Welds 17.86%

Yes Welds in Reactor Vessel B-B Pressure Retaining 8 Welds 2 Welds 25%

No Welds in Vessels Other than Reactor Vessels

.B-D Full Penetration Welds.

36 Inspections 10 Inspections 27.78%

Partial

. of Nozzles in Vessels B-E Pressure Retainfag 55 Welds 55 Welds 34%

No Partial Penetration Credited' Welds in Vessels

'B-F.

Pressure Retaining-46 Welds 14 Welds 30.43%

No Dissimilar Metal Welds B-G-1 Pressure Retaining 466 Items 123 Items 26.39%

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

  • 79 Connections 21 Connections 26.58%

No Bolting 2 Inches and Less in Diameter B-H

- Integral Attachments 9 Attachments 2 Attachments 22.22%

No For Vessels B-J Pressure Retaining 285 Welds 65 Welds 22.81%

No Welds in Piping

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

  • Totai connections include CRDMS that are disassembled.

Page 1 Revision 1 C/6550049 April 6, 1989

'. 4.,..,... -

3.,

e Class'1 Inspections'(Continued)

-Section

.XI Inspections Inspections:. Percentage.

Deferral--

'_ Category Description Required

_ Completed Completed Allowed.-

. B-L-1--

~ Pressure Retaining Welds None N/A.

N/A N/A-in Pump. Casings-B-L Pump Casings:

None N/A.

N/A

.N/A B-M-1 Pressure Retaining Welds 2 Welds None 0%

Yes in Valve Bodies I -M-2 Valve Bodies > 4 In.

7 Valves None 0%

Yes B

Nominal Pipe Size.

B-N-1

. Interior of-Reactor 3 Items 1 Item 33.33%

No

. Vessel-JB-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 Ret.aining 3 Welds None 0%

Yes Welds in Control Ro'd Housings B-P All Pressure Retaining 189 Components 43 Components 22.75%

Yes

' Components B-Q

Steam-Generator Tubing 100%'of Technical Specifications met N/A F1. 01, Class 1 Component 367 Supports 119 Supports 32.43%

~No Supports l

l Page 2 Revision 1 LC/6550049 April 6, 1989 b

' ' > +, is.

^ '

.,e y

4 Class 2 Examinations

-Section XI:

' Inspections Inspections Percentage, Deferral

~

Category Description

' Required Completed Completed Allowed C-A Pressure Retaining 13 Welds 3 Welds 23.08%-

No-Welds In Pressure

. Vessels C-8)

Pressure Retaining 10 Welds 3 Welds 30%

No Nozzle Welds in

. Vessels-C-C Integral Attachments 38 Items 10 Items 26.32%

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 Retaining 323 Welds 106 Welds 32.82%

No.

Welds in Piping C-G-Pressure Retaining 25 Welds 7 Welds 28%

No r

Welds-in Pumps and Valves C-H All Pressure Retaining 108 Components 14 Components 12.96%'

No-Components F1.02

.. Class 2 Component 591 Supports 155 Supports 26.23%

No Supports Page 3 Revision 1 C/6550049 April 6, 1989 L____-_L_,

I

l

=

p l.

L r

Augmented Inspections l

Description Percentage Complete Reactor Coolant Pump Flywheels Exams 25%

Steam Generator Tube Exams on 100% of requirements for Outages 1 & 2 Preheater Section Main Steam Pipe Rupture Protection 100% of requirements for Outages 1 & 2 Containment Spray System 100% of requirements fue Outages 1 & 2 Page 4 Revision 1 C/6550049 April 6, 1989

_ _ _ _ _ _ _ _ - _ _ _ _ _ _