ML19270G400
| ML19270G400 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 05/30/1979 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7906060279 | |
| Download: ML19270G400 (2) | |
Text
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'v-SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S street
. Bcx 15830, sacramento, Califernia 95813; (916) 452-3211 May 30, 1979 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Cormission Washington D.C.
20555 Docket No. 50-312, Rancho Seco Nuclear Generating Station, Unit No. 1
Dear Mr. Denton:
Item (d) of Commission Order 7590-01 dated May 7,1979 requires an analysis of potential small breaks applicable to Rancho Seco Unit No. 1.
The Babcock & Wilcox Company has provided a report, " Evaluation of Transient Behavior and Small Reactor Coolant System Breaks in the 177-Fuel Assembly Plant," May 7, 1979.
Your staff has requested confirmation that this report was based on parameters which bound actual conditions at Rancho Seco Unit No.1.
The following table provides a comparison af parameters used in the analysis and existing at Rancho Seco Unit 1.
Analysis SMUD Power level, MWt 2827 2772 Reactor trip pressure, psig 1885 1900 ESFAS trip pressure, psig 1350 1600 HPI pump information No. of pumps 1(a) 2 Flow @ 600 psig RCS pressure, gpm/ pump 500 500 Shutoff head, psig 2800
> 2900 Delay time, s 35 25 Auxiliary feedwater pump information No. of pumps 1
2 Flow @ 1050 SG pressure, gpm/ pump 550 780 790C066}7ej 2.26 8.38 Rod worth, Mk/k (a) In section 6.2.1 and 6.2.2, two HPI pumps were utilized in the analysis.
Acci j S
//0 o
u.m.
.s m:
.m
.. 4 m
2274 351
Mr. Harold R. Denton May 30, 1979 This data shows that the small break analysis performed by B&W is indeed applicable to Rancho Seco Unit 1.
Please advise if we can provide any further information.
Sincerely yours, ft.tMNK
.J. Mattimoe Assistant General Manager and Chief Engineer 2274
.552
.