ML18082A444
| ML18082A444 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/20/1980 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0660, RTR-NUREG-660, TASK-2.K.3.09, TASK-2.K.3.10, TASK-2.K.3.12, TASK-TM NUDOCS 8005220519 | |
| Download: ML18082A444 (2) | |
Text
.0 PS~G e Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 May 20, 1980 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. c.
20555 Attention:
Mr. A. Schwencer, Acting Chief Licensing Projects Branch 3 Division of Licensing Gentlemen:
B&O TASK FORCE RECOMMENDATIONS NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 Public Service Electric and Gas Company hereby transmits its response to your telephone request for confirmation of com-pliance with certain B&O Task Force recommendations concern-ing PORV failures, as identified in Section II.K.3 of NU~EG-0660, "NRC Action Plans Developed as a Result of the TMI-2 Accident."
Recommendation C.3.9 For Westinghouse -
designed reactors, modify the pressure integral derivative controller, if installed on the £ORV, to eliminate spurious openings of the
,j-.*
PORV.
(Reference NUREG-0611, Section 3.2.4.b).
Response
The interlock setpoint has been raised to the same value as the control bistable.
This modification was made in conjunction with the Safety Injection initia-tion logic change to eliminate the coincident require-ment for low pressurizer level with low pressurizer pressure.
Recommendation C.3.10 For Westinghouse -
designed reactors, if the anticipat-ing reactor trip upon turbine trip is to be modified to be bypassed at power levels less than 50 percent, rather than below 10 percent as in current designs, demonstrate that the probability of a small-break LOCA resulting from a stuck-open PORV is not significantly changed by this modification.
(Reference NUREG-0611, Section 3.2.4.c).
The Energy People p
80052205 I/
Boo/
.s
,/o 95-0942
1'"
Director of Nuclear Reactor Regulation 5/20/80
Response
This modification will not be implemented.
Recommendation C.3.11 Demonstrate that the PORV installed in the plant has a failure rate that is not significantly greater than the valves for which there is an operating history.
(Reference NUREG-0611, Section 3.2.4.d).
Response
This recommendation is not applicable, since the PORV's used in the Salem plant are Copes-Vulcan valves.
Recommendation C.3.12 For Westinghouse - designed reactors, confirm that there is an anticipatory reactor trip on turbine trip.
(Reference NUREG-0611, Section 3.2.4.a).
Response
The Salem design incorporates an anticipatory reactor trip on turbine trip.
Should you have any further questions in this regard, do not hesitate to contact us.
CQ23 1/2 Very truly yours,
,R/~~-
R. L. Mittl
~
General Manager -
Licensing and Environment Engineering and Construction