ML20207S538
| ML20207S538 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/17/1987 |
| From: | Kelly G Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8703190647 | |
| Download: ML20207S538 (1) | |
Text
s March 17, 1987 Docket No.: 50-245-NOTE T0:
File FROM:
Glenn Kelly
SUBJECT:
MILLSTONE 1 VALVES 1-RR-2A and 1-RR-2B TeleconbetweenGlennKe'lly(NRC),JimShea(NRC),MitchLederman(NNECO),
Mike Chi (NNECO)..Nurmal Jain(NNECO), Paul Blasioli(NNECO), Jan Rader(NNECO),
JohnBickel(NNECO),andDickMassiani(NNECO).
Telecon date:
February 25, 1987 For small breaks less than 0.lft, worst SF is gas turbine generator failure.
Cannot be assured LPSI lo~op selection will choose right loop for this range of breaks. So only have DG, I core spray, and some LPCI flow (which makes it worse). Do not exceed 2200 F for Appendix K.
For old calculation of large breaks greater than 0.lft, LPSI valve failure (10A or 108) was worst single failure. Then if fail 1-RR-2A or -2B, it makes no difference since have already failed injection.
If, however, assume 1-RR-2A and -2B fail due to their harsh environment, then gas turbine generator failure is the worst single failure and PCT exceeds 2200 F for Appendix K calc.
and B.E. calculations.
cc:
Docket File ISAPD File PDR J.Shea LPDR m
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