ML20136F136
| ML20136F136 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Vogtle |
| Issue date: | 08/10/1984 |
| From: | Berlinger C Office of Nuclear Reactor Regulation |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML082840446 | List:
|
| References | |
| FOIA-84-663 NUDOCS 8408170073 | |
| Download: ML20136F136 (2) | |
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i DOCKET FILE: 50-424/425 AUG 10 W h
cBMfR RLOBEL MEMORANDUM FOR:
E. Mensam, Chief DFIENO Licensing Branch #4, DL SLEE FROH:
C. Berlinger, Chief Core Performance Branch, DSI
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR V0GTLE UNITS 1 AhD 2
Reference:
Memorandum for E. Adensam, Chief. Licensing Branch #4, DL from C. Berlinger, Chief. CPB, DSI (Hay 4,1984) l Docket Numbers:
50-424/425 Licensing Stage:
Operating License i
Responsible Branch:
Licensing Branch #4 Project Manager:
H. Miller (X-24259)
DSI Review Branch:
Core Perfonaance Branch Review Status:
Incomplete - Mditional Information Required The Core Performance Branch has prepared the attached question in eddition to the questions addressed in the reference memorandum on Section 4.4 " Thermal-Hydraulic Design", of the Vogtle FSAR. Please transmit the question to the licensee.
Original signad by t
r H. Berlinger, Chief Core Performance Branch, DSI
Enclosure:
As stated cc:
L. Rubenstein R. Capra G. Lainas
- 8. Sheron
Contact:
S. Lee X-29477 HON O 0%
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ENCLOSURE 492.11 Table 4.4-1 of the Vogtle FSAR quotes the thermal and hydraulic data of SNUPPS to demonstrate that the Vogtle thermal and hydraulic data are similar to those of SNUPPS. However, the quoted SNUPPS data are different from the data of Table 4'.4-1
. of the current SNUPPS FSAR (e.g. coolant flow,' coolant tanperatures, and pressure drop are different).
Explain the discrepancies between the two data sets. >
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Should you determine that the quoted SNUPPS data in Table 4.4-1 of the Vogtle FSAR are no lqnger valid, explain the reason (e.g.,
design changes) why the values of the Vogtle thermal and hydraulic data are different from those of SNUPPS.
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