ML20215L694
| ML20215L694 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 05/08/1987 |
| From: | Roberts E EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20215L697 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM EWR-122-87, NUDOCS 8706260148 | |
| Download: ML20215L694 (1) | |
Text
_ _ _ _ _ _ _
PorL
\\
/NEA
^
N'o hh fi,#we,p WmW May 8, 1987 Mr. M. Carrington, Program Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 TRANSMITTAL OF TECHNICAL EVALUATION REPORT, "TMI ACTION--NUREG-0737 (II.D.1) RELIEF AND SAFETY VALVE TESTING, RANCHO SECO,"
DOCKET NO. 50-312, EGG-NTA-7700, May 1987 - EWR-122-87 Ref:
INEL Technical Assistance To The Office of Nuclear Reactor Regulation, " Evaluation of OR Licensing Actions - NUREG 0737, II.D.1" (FIN A6492)
Dear Mr. Carrington:
In accordance with the above reference, INEL has been providing technical assistance to the Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation for the evaluation of plant-specific licensing submittals regarding qualification of safety and relief valves.
The enclosed report is an evaluation of the Rancho Seco j
(Docket No. 50-312) submittal. This evaluation found that the licensee, Sacramento Municipal Utility District, has provided I
acceptable submittals and responses to requests for additional I
information, reconfirming that the General Design Criteria 14, 15, and 30 of Appendix A to 10 CFR 50 have been met.
Very truly yours E W.dd 6 mars E. Wayne Roberts, Manager NRC Headquarters Support j
CLN,cin I
Enclosure:
As Stated cc: C. G. Hammer, NRR-EMEB G. L. Jones, DOE-ID l
E. J. Sullivan, Jr., NRR-EMEB J. O. Zane, EG&G Idaho (w/o Encl.)
h EGCB w.o. s,.
titte Rockvme Pike Suite 4M Rockvme, MD 20852 8706260148 870508 PDR ADOCK 05000312 P