ML20236B758
| ML20236B758 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/20/1987 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20236B760 | List: |
| References | |
| NUDOCS 8707290228 | |
| Download: ML20236B758 (3) | |
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i DUKE POWER GOMPANY:-
. P.O. HOx 33189 j
' CIIARLOTTE, N.C. 28942 l
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'(704) 073-4531:
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'. July'20, 1987
'I U. S. Nuclaar Regulatory Commission Attoution': Document: Control Desk Washington, D. C. 20555
Subject:
-Catawb'a Nuclear Station, Units 1 and 2 Docket Nos;'50-413 and 50-414
Dear Sir:
J Dr. K. N. Jabbour's letter of-June 8, 1987 transmitted a; Request for: Additional Information regarding the Inservice Inspection Program for Catawba l. Units 1:and 2.:
j Responses to these questions are attached.
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=Very truly yours,.
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Hal B. Tucker ROS/51/sbn Attachment i
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Dr. J. Nelson Grace,. Regional Administration U.'S. Nuclear Regulatory Commission i
i Regio. II.
101 Marietta Street,- NW, Suite.2900 Atlanta, Georgia.30323:
1 Mr. P. K. Van : Doorn -
NRC Resident Inspector-f
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i Catawba Nuc1 ear Station Response to NRC RAI J
Inservice Inspection Program I
. (1 )'
Provide the staff with isometric and/or component' drawings showing the welds, components,_and supports which are required to be examined by Section XI of the ASME Code.
Response
The Staff's request for drawings is' impractical.' This request would involve the copying and transmittal.of over 60,000 drawings for a single complete set.
The requested drawings are available for NRC review at Catawba or at Duke's General Office in Charlotte, North Carolina.
(2) With regards to limitations due to metallurgical properties of cast stainless steel (SA351 Grade CF8A), the staff has continued to monitor the development of new or improved' examination techniques. As improvements in these areas are achieved, the staff is requiring that these new techniques be made part of the ISI examination procedures. Discuss the ISI examination procedures for the ultrasonic examination of the Catawba Nuclear Station Units 1 and 2 Primary Coolant System and, in particular, the improved examination techniques and procedures which will be incorporated to increase the level of compliance with the Code examination requirements.
Response
Duke will be using the most current improved examination techniques available for the examination of cast stainless steel piping at Catawba i
Nuclear Station. Attached is a copy of the NES and the B&W Ultrasonic j
Examination Procedures that would be used at the' site.
(3) Code Cases N-356 and N-427 are not referenced in Regulatory Guide 1.147, Revision 5, as NRC-approved code cases.
Therefore, these code cases, as referenced in Section 1.2 of the ISI Program Plans, should not be used.
Regulatory Guide 1.147, Revision 5 Paragraph C.4, states." Code Cases that are not on the approved list of this guide (Paragraph C.1) or other regulatory guides, or for which authorization by the Commission has not.been granted, are not acceptable on a generic basis".
The Licensee should provide justification for the use of these code cases or submit requests for relief, 'along with technical justifications, as to why the Code-required Section XI requirements are impractical.
Response
Although Code Cases N-356 and N-427 do not appear on the approved. list as shown_in Regulatory Guide 1.147 Revision 5, we are requesting.(via the previously submitted ISI program descriptions) that these Code Cases be approved for use at Catawba Nuclear Station. Regulatory Guide 1.147, Revision 5, Paragraph B states " Code Cases that are notLlisted herein are either not endorsed or'will require supplementary provisions on an individual plant basis to attain endorsement status.
IncarviceInspaction(Program Page.Two;'
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'(4) lAs required by'10 CFR 50.55a(g)(5) if the licensee determines-that certain~
code examination requirements are impractical and relief is requested, the licensee shall submit'information to the.NRC to support that determination.
The Licensee should provide a formal submittal-of requests for relief;
. including supporting technical-justifications ~ - Each request for. relief I
should be a " stand-along" document (i.e., all of'the supporting information
'I should'be included as part of the relief request). When' preparing' requests l
for relief, the staff suggests that the Licensee follow the attached 1
Appendix A, " Inservice Inspection:. Guidance for Preparing Requests.for i
Relief from Certain Code Requirements Pursuant to 10 CFR"50.55a(g)(5)".
Response
1 Duke has' complied with Appendix A,'"Inservihe1 Inspection: Guidance for Preparing
' Requests for. Relief from Certain Requirements. Pursuant to 10 CFR 50.55a(g)(5)" in requesting relief:concerning the' surface examination of the Pressurizer Support Skirt.- This.is the only. area.where a need for relief has been identified at Catawba Nuclear Station.
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