ML19316A081
| ML19316A081 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/15/1970 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Thies A DUKE POWER CO. |
| References | |
| NUDOCS 7911210806 | |
| Download: ML19316A081 (2) | |
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. FWR-2 Reading ASchwencer 50-2M JUL 15,1970C K 8**k
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Freduction & Operation DRS/DRL Br. Chiefs Licensing Assistant Gaetlement.
Attorney, OGC
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We have esoplated eer review ef the meterial that you have filed on i
^ the less-of-eamlant occident (LOCA) analysis in connection with your application for. operating 11eennes for the Ocenee Nuclear Units.
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.On the basis of our ev=1 d H en of the information you have provided, and our evaluations of the IACA for other FWR designs, we eenmet establish reasonable assuraees that yoer methode of analyses are esseervative. We are maalasing a list of questions which, if answered satisfactorily, abould permit us to concinde that your ECCS design and analyses are neceptable.
' Your reopense to the'==*1 mamma should'be expedited so that we may complate our review of your ECCS design.
Sincerely, 3.aal Signed )1 Pater 6.Ngdl /
Peter A. Morris, Director Division of Beester Licensing e
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Additiemal Informatiam s
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lt July 15, 1970 ADDITIONAL INFORMATION REQUEST 1.
Provide the results of your evaluation of the LOCA using a multinode analysis (such as your FLASH-2.5 code) for a 28-inch ID, double-ended, cold-leg pipe rupture.
In addition to providing information on clad temperature, system pressure, etc, also provide the core and hot channel flow rate in detail suf ficient to fully characterize the thermal and hydraulic performance during blowdown.
These details should include:
a.
core pressure drop, quality, mass velocity; b.
hot channel pressure drop, quality, mass velocity; c.
heat flux distribution in hot channel;
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flow rates in upper and lower plenums; e.
flow rate in broken and intact cold-leg and hot-leg piping; and f.
flow rate out the break.
Identify the heat transfer correlations used for the various phases of the blowdown and refill period and relate these correlations to the most recent experimental dr.;a available.
2.
With the same degree of detail, provide the results of your evaluation of a 36-inch ID, double-ended hot-leg pipe rupture.
3.
Provide a summary discussion regarding your acceptance criteria for ECCS functional performance. Your discussions should include an identification of any supporting information which has become available as a result of the Commission-sponsored emergency core cooling test programs.
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