ML20040A000
| ML20040A000 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 01/03/1977 |
| From: | Cox T Office of Nuclear Reactor Regulation |
| To: | Happell J BABCOCK & WILCOX CO. |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201200149 | |
| Download: ML20040A000 (3) | |
Text
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U.S. NOCLEAR REGULATCRY COMMISSION WASlilNSTON, D. C. 20555 301-492-7000 Tel e cop i e r---------------------492-7617 ( Aut'emati c)
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AGENDA FOR DISCUSSION WITH B&W ON BSAR-205 Q-2 RESPONSES TO 221.0 SERIES REQUESTS 1.
(221.54) The applicant must (a) show the 0.99 flow distribution to 95/95, or (b) provide assa.ibly exit flow distribution test results, or (c) eliminate those interior assemblies abutting the peripheral assemblies from " consideration" by showing that boundary conditions for those assemblies, never create a DNB problem before one occurs in a more interior assembly.
Topical Report BAW-10025P discusses assembly flow distribution. In order to evaluate the validity of the stated distributions for BSAR-205 we need a list of pressure sensors, probes, meters, tranducers, etc.,
and indicate their locations. Provide error bands for measurements
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and indicate truncation or calculational errors inherent in the codes a
used to interpret data. Discuss the adequacy o'f your calibration technique since the pumps wereenot running during ' calibration and only static head preovided pressure. Detail your application of statis tical tolerances.
Indicate statistical level of signific ance, detail assumptions, state where using parametric or non-parametric statistics and defend assumptions. Describe the number of flow tests performed and how the test results were combined. Were any tests discarded? If so, why? For four-pump operation, what was the smallest flow distribution value of an interior assembly?
- 2. A* 2 2.
(221.51) Provide a DNBR plot showing the minimum for the locked rotor accident and revise reference errors in (4.).
3.
(221.57) You did not' address the problem of demonstrating that you have satisfied the three criteria you list in Section 4.4.1 (Design Bases), specifically for anticipated transients.
Is Steam Line Break the worst case (centerline fuel temperature) analyzed? For this corro bornhg or any other claimed worst case you should provide mammahabamateng information, giving at least the maximum temperatures of fuel centerline for other transients.
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