ML20246G125
| ML20246G125 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/28/1989 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8905150193 | |
| Download: ML20246G125 (6) | |
Text
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Duxe POWER GOMPANY
-P.O. BOX 33189 GHARLOTTE, N.O. 28242
!!AL IL TUCKER TELzenoxe N Paest m T (704) 0y3 4531 Ntf()LRAN PRCNM10 TION I
April 28, 1989
. Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.._C.
20555
Subject:
Catawba Nuclear Station,-Units 1 and 2 Docket Nos. 50-413 and 50-414-Relief Request 89-03 Gentlemen:
1 By letter dated April 30, 1987 I submitted Relief Request No. CNS-001 for the Catawba Units 1 and 2 Inservice Testing Program (IST). However, no such request has been placed on Docket Nos. 50-413 or 50-414 at the'NRC Document Control Desk. Please find attached the subject relief request from the requirements of the ASME Boiler and Pressure Vessel Code,Section XI,1980' Edition through Winter 1981 Addenda.'The resubmitted relief request has been assigned No. 89-03.
- This relief request will exempt a section of an integral attachment to a
. vessel weld from the required surface examination. The affected surface area:is inaccessible for examination and is identified in the attachment.
Very truly yours,
- ),tu H. B. Tucker
- JGT/2/RR8903 Attachment 1
i xc: Mr. S. D. Ebneter sy.
Regional Administrator, Region.II U. S. Nuclear Regulatory Commission b
101 Marietta St., NW, Suite 2900 gg Atlanta, Georgia 30323 neo j$
Mr.'W. T. Orders coo NRC. Resident Inspector cov Catawba Nuclear Station
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og Mr. Heyward Shealy, Chief 3
Bureau of Radiological Health i)
South Carolina Department of Health
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and Environmental Control 2600 Bull Street i
Columbia, South Carolina 29201
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Serial No.
Page 1 of 2 DUKE POWER COMPANY Request For Relief From inservice inspection Requirement Station: Catawba I
Unit:
1 and 2 Reference Code: ASME Boiler and Pressure Vessel ~ Code,Section XI 1980 Edition through Winter 1981 Addenda 1.
Component for which exemotion is reauested:
a.
Name and identification Number:
Pressurizer Integrally Welded Attachments g
Pressurizer Support Skirt to Lower Head National Board Number W18589 (Unit 1)
National Board Number W26949 (Unit 2) b',
Function:
Support of Class 1 Vessel c.
ASME Section ill Code Class:
Class 1 d.
Valve Catecory:
N/A II. Reference Code Requirement that has been determined to be impractical:
Section XI Table IWB-2500 Examination Category B-H, requires that 100% of the length of the integral attachment to vessel weld be included in the examination.
The surface exam areas are shown in Figure lWB-2500-13.(See Attachment 1 IWB-2500-13) lli. Basis for Recuesting Relief:
l Relief requested from surface examination required on surface area C-D as shown in Figure IWB-2500-13.
Surface area C-D is inaccessible for examination due to the following reasons:
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Serial No.
CNS 89-03 Page 2 of 2 m-h '
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Basis for Requesting Relief (cont'.)
1.
.The heater cables must be disconnected for access causing some of.the ceramic insulators to fail.
(See~ attachment 2) 1 2.
The maximum clearance between the inside surface of thei support skirt and the outside row of heaters is 14 inches.
(See Attachment 3) 3.
200/250 MR/HR' exposure levles.at this time under.the support skirt.
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W IV.
Alternate Examination,:
The' weld will be examined from surface area A-B (OD surface) by magnetic particle testing.
V.
! implementation Schedule:
Welds will be scheduled in accordance with ASME Section XI requirements.as shown in the 1st Ten Year Interval Catawba Nuclear Station Inservice Inspection Plan, Units 1 and 2.
ATTACHMENT' 1 FOR CNS-89-03
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REQUIREMENTS FOR CLASS 1 COMPONENTS ng, gw g*hu j
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Surf. enom. areas A 8 and C D Ws1 FIG. IWS 2500-13 INTEGRAL ATTACHMENT WELD 79
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ATTACHMENT 2 FOR CNS-89-03 G
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CERAMIC INSULATOR TYPICAL HEATER ASSEMBLY l
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ATTACHMENT 3 FOR CNS 89-03
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