ML13330B442
| ML13330B442 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/23/1988 |
| From: | Nandy F SOUTHERN CALIFORNIA EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8901030147 | |
| Download: ML13330B442 (3) | |
Text
- ACCELERATED D1S'jJBVT]N D EM NS TP410N SYSWTEMd REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8901030147 DOC.DATE: 88/12/23 NOTARIZED: NO DOCKET #
FACIL:50-206 San Onofre Nuclear Station, Unit 1, Southern Californ 05000206 AUTH.NAME AUTHOR AFFILIATION NANDY,F.R.
Southern California Edison Co.
,RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Provides correction to 1988 steam generator insp rept submitted to NRC on 880325.
DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL
' SIZE:
TITLE: OR Submittal: Inservice Inspection/Testing/Relief from ASME Code NOTES:License Exp date in accordance with 10CFR2,2.109.
05000206 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1
PD5 PD 5
TRAMMELL,C 1
INTERNAL: ACRS 6
AEOD/DSP/TPAB 1
ARM/DAF/LFMB 1
NRR/DEST/MEB 9H 1
NRR/DEST/MTB 9H 1
NUDOGSABSTRACT 1
OGC/HDS2 1
0 R-t 01 1
RES/DSIR/EIB 1
EXTERNAL: EG&G ROCKHOLD,H 1
LPDR 1
NL 007 HEMMING 1
NRC PDR 1
NSIC 1
D S
A NOTE TO ALL "RIDS" RECIPIENTS:
S PLEASE HELP US To REDUCB WSTE!
ONTACT THE DOCMENT ODNTROL DESK, ROOM P1-37 (EXT. 20079) TO ELIMINATE YOUR NAME FRCH DITRIBTION LISTS FOR DOCUMEMPS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 26 ENCL
-26
0 Southem California Edison Company P. 0.
BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 FR NANDY TELEPHONE MANAGER OF NUCLEAR LICENSING December 23, 1988 (818) 302-1896 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
Docket No. 50-206 Steam Generator Inspection San Onofre Nuclear Generating Station Unit 1
References:
- 1. Letter from M. 0. Medford, SCE, to U. S. Nuclear Regulatory Commission, same subject, March 25, 1988
- 2. Letter from Dennis M. Crutchfield, USNRC to K. Baskin, SCE, same subject, February 7, 1984 By Reference 1, a report on the 1988 steam generator inspection results was provided to the NRC. The inspections were performed during February 22, 1988, through March 7, 1988, and completed requirements which were originally planned for the Cycle 10 refueling outage. As part of these inspections, the wrapper support bars were examined and determined to be intact. It was concluded that the wrapper support bars could be left in place without affecting tube integrity.
The purpose of this letter is to correct an error made in the 1988 Steam Generator Inspection Report submitted by Reference 1. In Section VII.B.,
Conclusions, regarding the wrapper support bar inspection it was stated that an inspection of the wrapper support bars would be done during the next refueling outage. In fact, this statement should have stated that the inspection would be done during the Cycle 11 refueling outage. This error was the result of using the.standard boiler plate format and wording for the 1985 steam generator inspection report in preparing the 1988 inspection report.
The inspection of the wrapper support bars is the result of an SCE commitment documented by the NRC in their Safety Evaluation dated February 7, 1984 (Reference 2).
These wrapper support bar inspections have been conducted in conjunction with the steam generator tubing inspections required by the technical specifications.
These inspections are generally scheduled for refueling outages.
The results of the December 1985 (Cycle 9 refueling outage) and the February to March 1988 (second mid-cycle outage) inspections show that the wrapper support bars are intact.
.jiv1c10301.47 '138~
g DoCK 05000206
Document Control Desk December 23, 1988 Due to an extended Cycle 9 refueling outage and the first of two mid-cycle outages from May to July 1987 the Cycle 10 refueling outage steam generator inspection would have been pushed beyond the maximum technical specification steam generator tubing inspection interval of 24 months (+25%). Therefore, the steam generator inspections were conducted during the second mid-cycle outage beginning in February 1988. Accordingly, the next technical specification steam generator tubing inspection is scheduled to be performed during the Cycle 11 refueling outage. The wrapper support bars will also be inspected at the Cycle 11 refueling outage.
If you would like additional information regarding this matter, please let me know.
Very truly yours, cc: 3. B. Martin, Regional Administrator, NRC Region V F. R. Huey, NRC Senior Resident Inspector, San Onofre Units 1, 2 and 3