ML20024A518
| ML20024A518 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 06/09/1983 |
| From: | Kay J YANKEE ATOMIC ELECTRIC CO. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| FYR83-60, NUDOCS 8306170398 | |
| Download: ML20024A518 (1) | |
Text
&
Tolephone (617) 872-8100 TWX 710u320uT619 YANKEE ATOMIC ELECTRIC COMPANY FYR83-60 2.C2.1 Y.
1671 Worcester Road, Framingham, Massachusetts 01701
,YAuxes June 9, 1983 United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing
References:
(a) License No. DPR-3 (Docket No. 50-29)
(b) YAEC Letter to USNRC, dated April 12, 1983 (FYR 83-40)
Subject:
Cooldown Capability of Proposed Integrated Shutdown Systems
Dear Sir:
Reference (b) proposed the integration of system designs for the seismic hot shutdown system and the Appendix R, Alternative Safe Shutdown System.
This letter provides additional information on the capability of the integrated system for plant cooldown as required by Appendix R.
Cooldown would be achieved by steaming through the atmospheric dump valves to approximately 3000F and subsequent flooding of the steam generators to achieve cooldown to 2000F, as defined by Technical Specifications for the cold shutdown condition.
The results of our preliminary analysis show that the above cooldown could be accomplished within 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />. Approximately 5 days would be required in the steaming mode to cooldown to 3000F. During the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, the steam generators would be filled solid to cooldown to 2000F, Flow rates required to remove core decay heat and system latent heat were verified to be within the capability of the proposed pump for the hot shutdown system. This analysis also considered, as a conservative assumption, that 50%
of the feedflow bypassed the steam generators to model the effect of incoming feedwater (through the blowdown line connection) flowing directly to the steam generator outlet nozzle.
We trust this information is satisfactory for acceptance of our proposed system integration concept and completion of the staff SER. To avoid equipment procurement delays, we request that this approval be granted prior to July 1, 1983.
If you have any questions, please contact us.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY p@<
0 8306170398 030609 n
PDR ADOCK 05000029 Q,
p PDR Senior Engineer - Licensing JAK/ds r