ML19323B497
| ML19323B497 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 05/05/1980 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0667, RTR-NUREG-667 NUDOCS 8005120448 | |
| Download: ML19323B497 (1) | |
Text
8005120YYY
$ S klU D SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 s street, Box 15830. sacomento. California 95813; (916) 452-3211 May 5, 1980 Dr. Harold Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station, Unit No.1
Dear Dr. Denton:
The Sacramento Municipal Utility District has reviewed the draf t version of NUREG-0667, " Transient Response of Babcock & Wilcox - Designed Reactors" dated April 2,1980 and would like to offer the following comments.
Since the Thrte Mile Island accident, the Districu has undertaken many efforts to determine areas for improvement in the Rancho Seco plant design.
We are commited to many improvements as a result of the failure modes and effects analysis of the integrated control system, the auxiliary feedwater system reliability analysis in response to NUREG-0578, and in response to our cooldown transient of March 20, 1978 and the Crystal River transient this past February.
We feel that these analyses and commitments have not been reviewed adequately by the Staff to determine their impact on the recommendations listed in NUREG-0667.
In addition, we feel that plant specific design details have not been properly considered in arriving at the generic recon:rendations in this report.
We are concerned that an arbitrary schedule may be established for the implementation of the items recommended in this document and encourage the completion of Items 10 and 19 (Sensitivity Studies and Criteria Establish-ment) as necessary predecessors to the implementation or consideration of the remaining items.
We also feel it to be highly desirable to consider these recomrrendations along with. the other items contained in the NRC's Draft Action Plan 50 that a coordina.ted and realistic schedule can be developed for imple-mentation of these items.
If you have any questions on our positicn or desire further discussion, please feel free to contact us.
Sincerely yours,
huhhWn Y
f 3
' chn J. Mattimoe Assistant General Manager
//O and Chief Engineer