ML18108A607
| ML18108A607 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/31/1973 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Anthony Giambusso US Atomic Energy Commission (AEC) |
| References | |
| Download: ML18108A607 (3) | |
Text
AEC D~ TRIBUTIOH FOR. PART 50 DOCKET MA~RIAL (TEMPORARY FORM)
CONTROL NO:
FILE:
FROM:
Florida Power 6 Light Company Miami, Fla.
33101 R. E.,Uhrig 12-31-73 1-3-74 DATE OF DOC DATE REC'D LTR 1fEMO OTHER
.TO:
A. Giambusso ORIG 3 signed CC OTHER SENT AEC PDR SENT LOCAL PDR CLASS UNCLASS XXX PROP INFO INPUT NO C S REC'D DOCKET NO:
50-389 DESCRIPTXOH:
Ltr re our 10-10-73 ltr, furnishing information regarding Anticipated Transients Without Scram for St. Lucie Unit 52 ENCLOSURES:
DO NOT REMOVE PLANT NAtfE: St. Lucie Unit 8'2
. ACKNOWLEDGED FOR ACTION/11YYFO":~~fATXON 1-12-74 GC BUTLER(L)
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Mr. Angelo Giambusso, Deputy for Reactor Projects Directorate of Iicensing Office of Regulation U. S. Atomic Energy Commission Washington, D. C.
20545
Dear Mr. Giambusso:
Re:
St. Lucie Plant Unit No.
2 Docket No. 50-389
.yp 4
'.d'n response to your October 10, 1973 letter concerning the subject of Anticipated Transients Without Scram (ATWS), the approach that we intend to follow for St. Lucie Plant Unit. No.
2 (Docket No. 50-389) is AEC Staff Position IB specified in Appendix A. Wash 1270, UC-78 of September 1973 titled "Technic~e@rt on Anticipated Transients Without Scram for Water-Cooled Power Reactors."
Implementation to make ATWS consequences acceptable will be i+accordance with the guidelines and schedule of Section IIB of Appendix A.
In support of meeting these requirements the reactor vendor, Combustion Engineering, has advised that they plan'". to complete the development of the ATWS evaluation model, applicable to all CE reactor plants, on a timely basis with frequent meetings with the AEC staff to generate a model acceptable to the AEC.
Once the ATWS analysis model is approved by the AEC, it will be applied to the Unit No.
2 plant to determine if specific "design changes are needed to make the consequences of ATWS acceptable.
In addition, a review of the reactor protective system will be conducted with the aim of identifying and correcting areas that might be particularly vulnerable to common mode failures.
A schedule for the accomplishing of these objectives is being developed.
Very truly yours, Robert E. Uhrig Director of Nuclear Affairs REU:nch cc:
Mr. Jack R.
Newman HELPING BUILD FLORIDA
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