ML20058P058
| ML20058P058 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/06/1993 |
| From: | Rehn D DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9310220044 | |
| Download: ML20058P058 (4) | |
Text
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Dake'$ bur CoInpay D.L Rrns Catawba Mclear Generanon Department Vice Prestdent
. 4%D Concord Road (803)S313205 Oflice York,5C 2.9745 (803)&11-3426 Fax DUKEPOWER October 6,1993 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Catawba Nuclear Station, Units 1 and 2 Docket Numbers 50-413 and 50-414 Request for Relief Number 93-02 Inservice Inspection Requirement Pursuant to 10 CFR 50.55a, please find attached request for relief number 93-02 from the requirements of Section XI of the ASME Boiler and Pressure Vessel Code (with Addenda through Winter 1981). This request is being submitted due to impracticality of the inspection schedule for nozzle welds as required by code in each inspection interval.
Please see section III of the attached request for the basis of requesting this relief.
i The implementation schedule for this request is EOC7 for Unit 1 (beginning October 30,1993) and EOC7 for Unit 2 (beginning October 8,1995). If you have any questions concerning this request, please contact L. B. Jones at (803) 831-3076.
Very truly yours, l
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D. L. Rehn Site Vice President LIU/coc7isi Attachment xc:
S. D. Ebneter, Regional Administrator Region II R. J. Freudenberger NRC Senior Resident Inspector R. E. Martin, ONRR 9310220044 931006 DR ADDCK 0500 3
A047 n,
Serial No. 93-02 i
.Page1of3 j
1 DUKE POWER COMPANY j
Request for Relief From i
Inservice Inspection Requirement
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1 Station:
Catawba Unit:
1&2 Requesting Department:
Nuclear Generation Department Reference Code:
ASME Boiler and Pressure Vessel Code,Section XI 1980 Edition through Winter 1981 Addenda
.1 I.
Component for which exemption is requested:
a.
Name and Identification Number:
Reactor Pressure Vessel Outlet Nozzle -to-Vessel Welds and Outlet Nozzle Inside Radius Sections.
b.
Function:
Welded connection between the Reactor Pressure Vessel and respective Reactor Coolant Piping providing a flow path to the Steam Generator.
c.
ASME Section XI Code Class:
-1 d.
Construction Code and Class (If Applicable):
NA e.
Valve Category (If Applicable):
NA II.
Reference Code Requirement that has been determined to be impractical:
<j ASME Section XI, Table IWB-2500-1; Category B-D, Item Numbers B3.90 and B3.100.
NOTE (3) : At least 25% but not more than 50% (credited) of the nozzles shall be examined by the end of the first inspection period and the remainder by the end of the -
third inspection period of each inspection interval.
ASME Section XI, IWB-2420 (a) : The sequence of component examinations established during the first inspection interval shall be repeated during each successive inspection j
interval to the extent practical.
Serial No. 93-02 Page 2 of 3 III.
Basis for Requesting Relief:
During the first period of the first ten year inspection interval at Catawba Nuclear Station, Units 1 & 2, the Reactor Vessel Outlet Nozzle -to-Vessel Welds, Outlet Nozzle Inside Radius Sections, Outlet Nozzle -to-Safe End Welds, and Outlet Nozzle Safe End
-to-Reactor Coolant System Piping Welds were examined from the Nozzle ID using Babcock and Wilcox's Automated Reactor Vessel Inspection System ( ARIS ).
These examinations for each unit met the first inspection interval reqmtements of ASME Section XI,1980 Edition threg W81 Addenda, Table IWB-2500-1; Category B-D, NOTE (2). No recordable indication.9 wt c detected.
During the third period of the first ten year inspection interval, the Pressure Retaining Welds in the Reactor Vessel, the Reactor Vessel Outlet Nozzle -to-Vessel Welds (from the Vessel ID ), the Reactor Vessel Inlet Nczzle -to-Vessel Welds, Inlet Nozzle Inside Radius Sections, Inlet Nozzle -to-Safe End Welds, and Inlet Nozzle Safe End -to-Reactor Coolant Piping Welds will be examined using ARIS.
This examination will complete the first inspection interval requirements of ASME Section XI,1980 Edition through W81 Addenda, for the inspection categories represented by these examinations. At the same time, with ARIS already installed on the Reactor Vessel, we will also examine from the Nozzle ID, the Reactor Vessel Outlet Nozzle -to-Vessel Welds, Outlet Nozzle Inside Radius Sections, Outlet Nozzle -to-Safe End Welds, and Outlet Nozzle Safe End -to-Reactor Coolant System Piping Welds to the requirements of both the 1989 and 1992 editions of Section XI of the ASME Code, with exception to Appendix VIII. Credit for these examinations will be applied to the second inspection interval first period requirement for the Nozzle -to-Vessel Welds and Nozzle Inside Radius Sections per ASME Section XI, Table IWB-2500-1; Category B-D, Item Numbers B3.90 and B3.100.
i These examinations will also be applied to meet the second inspection interval percentage requirements of ASME Section XI, Table IWB-2412-1; Inspection Program B.
The Reactor Vessel Outlet Nozzle -to-Vessel Welds and Outlet Nozzle Inside Radius Sections will therefore not be examined during the first period of the second inspection interval.
Following this inspection sequence will substantially reduce radiation exposure, critical path time, risks related to contaminated shipments, and generation of radwaste, without effecting the safe operation or reliability of the Reactor Vessel.
IV.
Alternate Examination:
Automated examination of all Reactor Vessel Nozzle -to-Vessel Welds, Nozzle Inside Radius Sections, Nozzle -to-Safe End Welds, and Nozzle Safe End -to-Reactor Coolant System Piping Welds will be deferred to the last period of the second ten year inspection interval.
)
Serial No. 93-02 Page 3 of 3.
V.
Implementation Schedule:
Examinations are currently scheduled to be performed during the third inspection period for each of the Catawba Units as shown below -
Catawba Unit 1 : RFO # 7,1993 Catawba Unit 2 : RFO # 7,1995 i
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