ML20055A304
| ML20055A304 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/13/1982 |
| From: | Maurin L LOUISIANA POWER & LIGHT CO. |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| 820713, Q-3-B41, V3P82-1776, NUDOCS 8207160109 | |
| Download: ML20055A304 (1) | |
Text
I 142 DELARONDE STREET POWE R & L1GHT P O BOX 6008
- NEW ORLEANS LOUISIANA 70174 * (5041 366 2345 MIDDtf SOUTH utiuTit s sysitM t, y, ggggig July 13, 1982 Vice President Nuclear Opetotions W3P82-1776 Q-3-B41 Mr. R. L. Tedesco U.S. Nuclear Regulatory Commission Assistant Director of Licensing Washington, D.C. 20553
SUBJECT:
WATERFORD 3 SES DOCKET No. 50-382 REACTOR COOLANT PUMP SHEARED SHAFT (SSER3 01#5)
Dear Mr. Tedesco:
During a recent telephone conversation with Mr. Jack Rosenthal of your Instrumentation and Control Systems Branch on the subject of the Waterford 3 Reactor Coolant Pump Sheared Shaft Analysis he requested that we provide the following official confirmation.
The Reactor Coolant Pump Sheared Shaft Analysis presented in our response to FSAR Question 211.45 is based on a plant specific analysis using the steam generator pressure differential reactor trip system which we have committed to provide on Waterford 3 and which is described in our response to FSAR Question 211.105. The analysis is not based on the sequential tripping control concent used on CESSAR 80 plants.
We hope this allows ICSB to close out this open SER item.
If you have any further questions, please do not hesitate to call.
Very truly yours, L[i'7 L. V. Maur oO /
LVM/FUM/pco cc:
S. Black J. Rosenthal 8207160109 820713 PDR ADOCK 05000382 E