ML20115J953
| ML20115J953 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/18/1985 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8504240173 | |
| Download: ML20115J953 (4) | |
Text
DUKE POWER GOMPANY P.O. ISOx 33180 CHARLOTTE, N.O. 28242
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April 18, 1985
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Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Ms. E. G. Adensam, Chief Licensing Branen No. 4 Re: Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 Inservice Inspection Program
Dear Mr. Denton:
Please find attached a request for relief from a requirement of Section XI to the ASME Code for verifying containment integrity per the Code Require-ments.
Very truly yours, JyL.
Hal B. Tucke RWO: sib Attachment cc:
Dr. J. Nelson Grace, Regional Administrator Palmetto Alliance U. S. Nuclear Regulatory Commission 2135 Devine Street Columbia, South Carolina 29205 Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Jesse L. Riley Carolina Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 Robert Guild, Esq.
P. O. Box 12097 Charleston, South Carolina 29412 NRC Resident Inspector Catawba Nuclear Station
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Mr. Harold R. Denton, Dirsctor April 18.-1985 Page Two bec:
K. S. Canady N. A. Rutherford R. O. Sharpe L. T. Parker R. W. Quellette C. L. Hartzell CNS J. E. Cherry G. W. Crier R. C. Futrell J. W. Hampton CNS A. V. Carr J. M. McGarry J. W. Willis CNS SREC NCENC NC MPA-1 PMPA Group File: CN-801.01
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s S3 riel No.
CNS-001 Page 1 of 2 DUKE POWER COMPANY Request For Relief From inservice inspection Requirement Station:
Catawba Unit:
1&2 Reference' Code: ASME Boiler and Pressure Vessel Code,Section XI, 1980 Edition through Winter 1981 Addenda 1.
Component for which exemption is requested:
a.
Name and identification Number: Containment System b.
Function: Maintain Containment Integrity c.
ASME Section lli Code Class:
Class MC d.
Valve Category:
N/A ll. Reference Code Requirement that has been determined to be impractical:
Table IWE-2500-1; Category E-P; Items E9.11, E 9.20, E9.30, and E9.40 Visual Examination, VT-2 Ill. Basis for Requesting Relief:
Duke Power has always performed these tests by using Nuclear Production personnel and performing the tests in accordance with station Technical Specifications. The test personnel and their supervision are qualified in accordance with ANSI N18.1. Having additional personnel qualified in accordance with ASME Section XI or requiring that the existing test per-sonnel be qualified in accordance with ASME Section XI will not improve
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e Serial No.
CNS-001 Page 2 of 2 111.
Basis for Requesting Relief (cont.)
the existing process.
It would however generate additional.administra-tive cost or result in additional radiation exposure.
IV.
Alternate Examination:
The items listed in Section II will be tested in accordance with the station Technical Specification and 10CFR50 Appendix J, using Nuclear Production personnel, qualified in accordance with the station Technical Specification. This will provide assurance that the intent of ASME Section XI is satisfied.
V.
Implementation Schedule:
These tests will be performed at the times specified by the station Technical Specifications and after repair, replacement, or modification to the pressure retaining boundary.
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