ML20045C509

Forwards Request for Relief 93-01 from ISI Requirement. Basis for Request Explained in Section III

ML20045C509
Person / Time
Site:	Catawba
Issue date:	06/17/1993
From:	Rehn D DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9306230209
Download: ML20045C509 (23)

Text

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. Duke Itwer Company . (803)&11-3000 Calairba Nuclear Station

, 480;rConcordRoad York, SC29745 t

DUKEPOWER June 17,1993 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Catawba Nuclear Station, Unit 2 Docket No. 50-414 Relief Request 2EOC5 Inservice Inspection Report Please find attached, Catawba's Request for Relief 93-01. The basis for this request is explained in Section III.

Any questions concerning this request should .be directed to L. J. Rudy at (803) 831-3084.

Very truly yours, ,

.u

- D. L. Rehn )

KEN /EOC51SI .RLF 1

Attachment xc: S. D. Ebneter ,

Regional Administrator, Region II R. J. Freudenberger .l NRC Senior Resident inspector i

R. E. Martin,' ONRR .!

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i 21002i; 9306230209 930617 PDR  %

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. . Serial No. 93-01 Page1of2 DUKE POWER COMPANY Request for Relief From Inservice Inspection Requirement

f. Station: Catawba Unit: 2 Requesting Department: Nuclear Generation Department Reference Code: ASME Boiler and Pressure Vessel Code,Section XI 1980 Edition l- through Winter 1981 Addenda l

I. Component for which exemption is requested:

a. Name and Identification Number: See Attachment 1

b. Function: See Attachment 1 l

l

c. ASME Section XI Code Class: Class 1

d. Construction Code and Class (If Applicable): ASME Section III Class 1 d

e. Valve Category (If Applicable): NA i

II. Reference Code Requirement that has been determined to be impractical:

See Attachment 1 III. Basis for Requesting Relief:

During the ultrasonic examination of the welds shown in Attachment 1, the minimum 90% coverage requirement of ASME.Section XI,1980 Edition, clarified by Code Case N-460, could not be obtained. Examination coverage was limited due -

to part geometry.

A surface examination was performed on the Item Numbers shown in Attachment 1, as required by ASME Section XI. Examination coverage was not limited.

Serial No. 93-01 Page 2 of 2 Although the coverage requirements of ASME Section XI could not be met while performing the volumetric examinations, this will in no way endanger the health and safety of the general public.-

No additional examinations are required.

IV. Alternate Examination:

Due to the impracticality of a different volumetric examination method, no alternate examination will be performed. We will continue to use the most current ultrasonic techniques available for future examinations of the Item Numbers shown in Attachment 1.

V. Implei tentation Schedule:

These examinations will continue to be scheduled in accordance with the requirements of ASME Section XI for future Inspection Intervals at Catawba Nuclear Station, Unit 2.

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ASME Class 1 NDE Inservice Inspection Request For blief Serial No. 93-01 For Catawba Unit 2 Based On ASME Section XI - 1980 Code Through Winter 1981 Addenda Attachment 1

• Page 1 of 2 ,

Licensee Item No. Exam Category System Or Function Area To Be Reason For Request 1 NPosed Alternate

/ Figure No. Component Examined Examination B03.140.001 B-D Steam Generator Provide steam to the turbine Pnmary Inlet Limited scan due to pa t geometry. None IWB-2500-7 2A Nozzle Inside Actual coverage obtained =55.25%

Radius Section B03.140.002 B-D Steaan Generator Nvide steam to the turbine Pnmary Limited scan due to part geometry. None IWB-2500-7 2A Outlet Nozzle Actual coverage obtained =71.60%

Inside Radius Section B03.140.007 B-D Steam Generator Nvide steam to the turbine Primary Inlet Limited scan due to part geometry. None IWB-2500-7 2D Nozzle Inside Actual coverage obtained =55.25%

Radius Section B03.140.008 B-D Steam Generator Nvide steam to the turbine Primary Limited sean due to part geometry. None IWB-2500-7 2D Outlet Nozzle Actual coverage obtained =71.60%

Inside Radius Section B05.070.001 B-F Steam Generator Provide steam to the turbine Pnmary Inlet Limited scan due to part geometry. None IWB-2500-8 2A Nozzle Actual coverage obtained =73.90%

Safe End B05.070.002 B-F Steam Generator Provide steam to the turbine Pnmary Limited scan due to part geometry. None IWB-2500-8 2A Outlet Nozzle Actual coverage obtained =74.30%

Safe End B05.070.007 B-F Steam Generator Provide steam to the turbine Pnmary Inlet Limited scan due to part geometry. None IWB-2500-8 2D Nozzle Actual coverage obtained =75.00%

Safe End B05.070.008 B-F Steam Generator Provide steam to the turbine Primary Limited scan due to part geometry. None IWB-2500-8 2D Outlet Nozzle Actual coverage obtained =75.00%

Safe End B05.130.002 B-F & actor Coolant Transport heat energy from Pipe Limited scan due to part geometry. None IWB-2500-8 System ( NC ) Reactor Core to Steam To Actual coverage obtained =73.90%

Generator Safe End B05.130.003 B-F bector Coolant Transport heat energy from Pipe Limited scan due to part geometry. None IWB-2600-8 System ( NC ) Reactor Core to Steam To Actual coverage obtained =74.30%

Generator Safe End B05.130.014 B-F hactor C:olant Transport heat energy from Pipe Limited scan due to part geometry. - None IWB-2500-8 Systeri( NC ) Reactor Core to Steam To Actual coverage obtained =75.00%

Generator Safe End B05.130.015 B-F Reactor Coolant Transport heat energy from Pipe Limited scan due to part geometry. None IWB-2500-8 System (NC ) Reactor Core to Steam To Actual coverage obtained =75.00%  ;

Generator Safe End

~

ASME Cicas 1 Components NDE Innervice Intpection hquest For Relief . Serial No. 93-01 ~

For Cctawha Unit 2 Based On ASME Section XI- 1980 Ccde Through Winter 1981 Addenda Attachment 1 -

Page 2 of 2 9

Item No. Exam Category System Or Function Area To Be Reason For Request 1 Licensee

/Mgure No. Component Examined Proposed Alternate Examination B09.03 LOO 5 B-J Reactor Coolant Transport he::.t energy from Branch Limited scan due to part geometry. None IWB-250011 System ( NC ) Reactor Core to Steam Connection Actual coverage obtained =42.60%

Generator To Main Loop B01031.006 B-J Reactor Coolant Transport heat energy from Branch Limited scan due to part geometry. None IWB-2500-11 System ( NC )- Reactor Core to Steam Connection Actual coverage obtained =48.10%

Generator To Main Loop i

ISee Attachment 2 for specific information concerning examination coverage for each individual Item Number.

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