ML20247A503

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: ML20247A455 ML20247A503
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-((

Revsewed By: .

3 Date # '[- 89 Approved By: m i Date Y- 7 ~N l

D Copy No. 5 Assigned To NRC Document Control Controlled , X Uncontrolled C/6550049 6909120134 890E:31 ADOCK 05000413 E_-- {DR -- -

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 Category .

Percentage Deferral' 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.

'_ Category Deferral--

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 B-M-2 Valve Bodies > 4 In. 7 Valves None 0% Yes 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 .

^ '

4

.,e.. y 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

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