ML19312E141
| ML19312E141 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 05/22/1980 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8006030342 | |
| Download: ML19312E141 (1) | |
Text
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esuun SACRAMENTO MUNICIPAL UTILITY DISTRICT C 6201 S Street, Box 15a30, sacramento, California 93813, (916) 452-3211 May 22, 1980 Mr. Robert W. Reid Operating Reactor Branch No. 4 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear cir. Reid:
In our letter of April 11, 1980, we committed to quantify any leakage from the Seal Injection and Mue-up System, the Letdown System and the High Pressure injection System while performing SP 207.04 at Hot Shut-down prior to returning to power operation.
This was done on May 7, 1980, and was documented on Rancho Seco Work Reques t No. 46503.
No leakage was found in any of the systems above.
The calculated water loss rate from the Reactor Coolant System, as calculated by SP 207.04, was 0.745 gpm.
This includes reactor coolant pump seal leakage as well as other known losses. There was no Reactor Coolant System unidentified leakage.
As reported in our letter of April 11, 1980, the leakage rate fromtheReactorCoolantChemicalAdditionandSagplingSystemoriginally installed at Rancho was measured to be 2.05 x 10-gpm by SP 205.02 (Local Leak Rate Testing). The leakage rate from the High Source Level Reactor Coolant Sampling System will be measured at the completion of installation, which will not be for several months.
Sincerely, C.- -
/
J. J. Ma t t i moe /i~-
Assistant General Manager and Chief Engineer JJM:RW: bks 8006030 3 a
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