ML20040B408
| ML20040B408 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 01/21/1982 |
| From: | Sargent C COMMONWEALTH EDISON CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20040B409 | List: |
| References | |
| RTR-NUREG-0803, RTR-NUREG-803 NUDOCS 8201260021 | |
| Download: ML20040B408 (2) | |
Text
.
Ctmm:nw sith Edison d,
one First National Plata, Chicago. !!I nois,
U Address Reply to-Post Othce Box 767 Chicago, lihnois 60690 Janua ry 21, 1982
['
[
b RECBlVED
-9 Mr. A. Schwencer, Chief 2
JAff 2 51982=- 1 Licensing Branch //2 E-m, Division of Licensing Ear avaa n U.
S.
Nuclear Regulatory Commission MS s
Washington, DC 20555 V>
4
~
Subject:
LaSalle County Station Units 1 and 2 Response to NUREG-0803 NRC Docket Nos. 50-373 and 50-374 Reference (a):
Darrell G.
Eisenhut letter to G.E. BWR Licensees dated August 31, 1981.
l
Dear Mr. Schwencer:
l The purpose of this letter is to transmit otr response to NUREG-0803 as required by the LaSalle County Station Draf t Operating License and Reference (a).
Accordingly, the enclosed report "LaSalle Evaluation Report Regarding Integrity o f Scram System Piping" is provided to satisfy these requirements.
j The evaluation per NUREG-0803 for LaSalle is centered i
around the probabilistic fracture mechanics evaluation o f the scram system piping which demonstrates that the mean probability of a rupture in the system is conservative 1v established at 7x10-6 per reactor year for the scram discharge volume (SDV) and associated piping sized 2-inches or greater and 4x10-4 per reactor year for 3/4-inch piping connected with the hydraulic control units (HCU's).
This result is a magnitude and a half lower than the generic results because the bene ficial influence o f pod'.-erection hydro testing and the relatively benign stress time history are acknowledged.
The evalu'ation establishes tnat even with the postulated break in the scram system piping, the LaSalle leak detection equipment and the station operating procedures will guide the reactor operators to a prompt and successful mitigation of the event with equipment that is qualified for safe shutdown, adequate core cooling, and capable o f maintaining secondary containment integrity.
8201260021 820121
/ fl PDR ADOCK 05000373 D
A PDR
'L be g
i
A. Schwencer Ja nua r y 21, 1982 If there are any further questions in this regard, please contact this of fice.
Ve ry t ruly yours,
d <%
i C. E.
Sa rge n t Nuclea r Licensing Administrato r CE5/1m Enclosure ec:
NRC Resident Inspector - L5CS w/o Attachment 3294N l
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