ML13330A289
| ML13330A289 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/10/1981 |
| From: | Baskin K Southern California Edison Co |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML13330A290 | List: |
| References | |
| TAC-47835 NUDOCS 8104150067 | |
| Download: ML13330A289 (2) | |
Text
Southern California Edison Company P. 0. BOX 800 2244 WALNUT GROVE AVENUE ROSEMEAD, CALIFORNIA 91770 K. P. BASKIN April 10, 1981 MANAGER OF NUCLEAR ENGINEERING, SAFETY, AND LICENSING Director, Office of Nuclear Reactor Regulation Attention: D. M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing U. S. Nuclear Regulatory Commission Washington,. D.C. 20555 Gentlemen:
Subject:
Docket No. 50-206 Steam Generator Repair Program San Onofre Nuclear Generating Station Unit 1 Submitted herewith are ten copies of the report entitled, "Steam Generator Repair Program, Return to Power Report, San Onofre Nuclear Generating Station, Unit 1, April, 1981."
The report contains information required to be reviewed and approved by the NRC prior to authorizing return to power following completion of the steam generator repair at San Onofre Unit 1. Specifically, the report discusses:
- 1. the maximum operating interval following return to power prior to a shutdown for inspection,
- 2. the steam generator differential pressure tests to be performed prior to return to power,
- 3. the steam generator water soaks and chemistry control to be performed during heatup for restart, power escalation and steady state operations,
- 4. the close surveillance of primary to secondary leakage during operation, and h 0
- 5. the plans for inservice inspection and preventative tube plugging following the steam generator repair.
As has been discussed with representatives of the Regulatory staff, 1/10 we have determined that the only information contained in the enclosed reportc V
e which requires a change to the License or Technical Specifications prior to return to power involves the preventative plugging limits. Therefore, we
- 5. As 4r indicated that a request to change the Technical Specifications in this area will be submitted by May 1, 1981.
It is our understanding that the Regulatory staff, however, will continue their review of the enclosed report pending receipt of this request.
D. M. Crutchfield
-2 In addition, we discussed our plans with representatives of the Regulatory staff to return to power operation with reduced core outlet temperature. The probable effect of the reduced temperature will be a reduction in the rate of tube degradation.
We are currently reviewing the reanalysis based on nominal core conditions submitted to you by letter dated December 10, 1980, and referenced in the enclosed report, to determine whether any revisions to that reanalysis are required to be consistent with operation at reduced core outlet temperature. Any revisions to the reanalysis which may be required will be submitted by April 17, 1981, and if these revisions result in changes to the Technical Specifications, a request will be submitted by May 1, 1981.
It is our understanding that, with the submittal of the additional information discussed above by April 17, 1981 and May 1, 1981, your approval authorizing return to power can be provided by May 22, 1981, when it is expected that San Onofre Unit 1 will achieve criticality. Accordingly, we are prepared to meet with you to facilitate your review and approval of the enclosed report, as well as the additional information when submitted.
If you have any questions or desire further information concerning the enclosed report or the submittal of the additional information discussed above, please contact me.
Very truly yours, Enclosures (10)