ML20198M076
| ML20198M076 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 01/13/1998 |
| From: | Ewing E ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| W3F1-98-0002, W3F1-98-2, NUDOCS 9801160184 | |
| Download: ML20198M076 (2) | |
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s ea f
y 3f Ente gy perations, Inc.
Kmona LA 70066 Tel 504 739 6242 Early C. Ewing.111 6e fety & Regu!atory AffaWS W3F1-98-0002 A4.05 PR January 13,1998 U.S. NucJear Regulatory Commission ATTN: Document Control Desk War.hington, D.C. 20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Inservice inspection (ISI) Relief Request 1S1-017, Revision 1, Request Autnorization to Substitute Visual (VT-3) Examination for the Code-required Surface or Volumetric Examination of the four Reactor Pressure Vessel Support Integral Attachment Welds (ISI Exam Number 01-074)
Gentlemen:
Letters W3F1-97-0014 and W3F l-97-0040 dated February 13,1997, and March 11, 1997, respectively, were submitted requesting approval to perform an alternative examination to that specified in ASME Section XI for the Reactor Pressute Ves.ccl Supp.. Integral Attachment Welds. The purpose of this letter is to inforrn you that we am withdrawing Relief Request ISI-017, Revision 1, in which the attemative examination was rec,uested.
The Reactor Pressure Vessel Support Integral Attachment Welds were examined during Refueling Outage 8, in accordance with ASME Section XI,1980 Edition, Winter 1981 Addenda, Table IWB-2500-1, Examination Category B-H, item No.
B8.10, to the extent practical. Whare complete examinatian coverage was not attainable due to component design or configuration, the limitation for each examination will be identified and provided to the NRC in accordance with 10 CFR 50.55a(g)(5)(iii). This information will'oe submitted in a future revision to Relief Request 181-001, Limited Examination of Welds / Components.
f C0,. D 9001160184 980113 PDR ADOCK 05000382 Hill.itl.il.H..I ll ll
9 e.
Request to Substitute Visual (VT-3) Examination for Surface or Volumetric
' Examination of the four Reactor Pressure Vessel Support Integral Attachment Welds (Relief Request 1S1-017)
W3F1-98-0002 Page 2 January 13,1998 If there are any questions, please contact Kevin Hall at (504) 739-6423 or n.a at (504)739-6242.
Very truly yours, I
l
,s E.C. Ewing Director Nuclear Safety & Regulatory Affairs ECE/DMU/ssf cc:
E.W. Merschoff, NRC Region IV C.P. Patel. NRC-NRR J. Smith N.S. Reynolds NRC Resident k.spectors Oflice s
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