ML13333A687
| ML13333A687 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/24/1988 |
| From: | Medford M SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8803020049 | |
| Download: ML13333A687 (2) | |
Text
Southern California Edison Company P. 0 BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 M.O.MEDFORD TELEPHONE MANAGER OF NUCLEAR ENGINEERING (818) 302-1749 AND LICENSING February 24, 1988 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
Docket No. 50-206 Augmented ISI Program San Onofre Nuclear Generating Station Unit 1
References:
- 1. Letter, J. H. Drake, SCE, to E. G. Case, NRC, Amendment No. 69, December 30, 1977
- 2. Letter, Dennis L. Ziemann, NRC, to James H. Drake, SCE, NRC Amendment No. 46, September 26, 1979 Technical Specification 4.10, "Augmented Inservice Inspection of High Energy Lines Outside Containment," describes the scope of examination of high energy lines outside containment at San Onofre Unit 1. Reference 1 provided, as Proposed Change No. 67, a request to revise Specification 4.10 such that exemptions were defined for three feedwater piping welds 201, 205 and 209. By Reference 2 the NRC responded by indicating that Specification 4.10 did not require a revision in order to grant such a relief request and Item A.10 of Reference 2 granted the relief request. Accordingly, it is understood that any necessary relief from the inspection requirements of Specification 4.10 should be handled as a normal relief request under the provisions of 10 CFR 50.55a(g)(6)(i).
As a result of past inspection difficulties, additional relief from the inspection requirements of Specification 4.10 is requested for feedwater piping weld 604 and main steam piping welds 253, 254, 263 and 264. Detailed justification of the relief request is provided as an enclosure to this letter.
If you have any questions, please let me know.
Very truly yours, Enclosure cc:
J. B. Martin, Regional Administrator, NRC Region V F. R. Huey, NRC Senior Resident Inspector, San Onofre Units 1, 2 and 3 8803020049 880224 PDR ADOCK 05000206 IDCD
February 24, 1988 Enclosure
- 1. Request relief from volumetric examination for feedwater weld 604 which is inspected in accordance with the Augmented ISI program for high energy lines outside containment.
Code Requirement San Onofre Unit 1 Technical Specification 4.10 requires volumetric examination of 100% of the weld in accordance with the Edition and Addenda of the ASME Boiler and Pressure Vessel Code,Section XI, "Inservice Inspection of Nuclear Power Plant Components," referenced for the IST program in Technical Specification 4.7.
Licensee Basis for Relief Request The weld joins a nozzle (elbow) to the shell of the first point heater in a fillet-type configuration. The geometric configuration of this type of weld produces uninterpretable signals when examined ultrasonically and therefore does not yield meaningful results. Surface examination is proposed as an alternative examination.
- 2. Request relief from volumetric examination of main steam welds 253, 254, 263 and 264. (Item C2.1, Examination Category C-G; Note: These welds are also inspected per the Augmented ISI program for high energy lines outside containment.)
Code Requirement Per the same reference as in Item 1 above, the requirement is for volumetric examination of 100% of the weld.
Licensee Basis for Relief Request Welds 253, 254, 263 and 264 are welds joining main steam relief valves to reducers. The weld configuration provides insufficient access for scanning of the weld with the ultrasonic probe. Surface examination is proposed as an alternative.