ML19329A527
| ML19329A527 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/29/1972 |
| From: | Mccary R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8001060043 | |
| Download: ML19329A527 (3) | |
Text
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R. C. DeYoung, Assistant Director for Pressurized Vater Reactors Directorate of Licensing 2 AND 3 OCONEE NUCLEAR STATION, UNITS 1, Oconee Nuclear Station Plant Name:
Licensing Stage:
OL Docket Numbers:
50-269/2T0/287 i
PVR #h, I. A. Peltier Responsible Branch and Project Manager:
N/A Requested Completion Date:
Applicants Response Date Necessary for Completion of Next N/A Action Planned on Project: Final Evaluation - Mechanical Description of Response:
Engineering Branch Review Status:
Partial Mechanical of the FSAR for the Final Evaluation HEB, Directorate The subject plant, which was prepared by theand dated September 8. 1970 an of Licensing, has been further revised to reflect 25, 1972, submitted September our evaluation of four Babcock & Wilcox Reports occurred during the hot after the recent failure whichIt should be noted that functional test of Oconee-1.
Oconee-1 cannot be qualified as the prototype plant until valid vibration predictions are submitted.
e-gr.?.s5dl e r. Lxp..W R. R. Maccary, Assistant Director for En61ncering
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Directorate of Licensing cc:
S.
H. Hanauer Distribution J.
Hendrie Docket File (50-269/a70/a87)
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FINAL EVALUATION - MECHANICAL OC0 HEE HUCLEAR STATION, UN I'. s 1, 2& 3
-DOCKET NOD. 50-269/270/287 The Final Evaluation from the Mechanical Engineering Branch,
. Directorate of Licensing dated September 8, 1970 and revised September 25, 1972, remains unchanged except for the revision to the specific section below:
VIBRATICU CONTROL The text of this section remains unchanged except for the
. following addition at the'end of the section:
Subsequent to the failure which occurred during the hot functional test of Oconce-1, Babcock and Wilcox submitted the following Topical Reports:
BAW-10037
" Reactor Vessel Model Flov Tests" BAW-10038 "Oconee Internals Vibration Test Program" BAW-10050
" Evaluation of Oconee Reactor Component Failure" BAW-10051 "Decign of Incrnals for Flov Vibration" In the process of reviewing the failure, we have evaluated the above reports.
We concur with the conclusions set forth
.in BAW-10050 that the recommended design modifications on the internals have been based upon a conservative application of the response and failure data from Oconce-1.
We-concur with the conclusions set forth in BAW-10037 that the reactor vessel scale model flow test approach used vill verify the core flow distribution.
However, due to a lack of valid flov forcing functions,.B&W has not yet demonstrated a dynamic analysis to predict the structural behavior of recctor internals when subjected to transient loadings.
The redesigned internals are accepted for Oconee 1 pending satisfactory
. completion of the new hot functional preoperation tests.
The.results obtained from the preoperational test vill be evaluated prior.to licensing to confirm this acceptability.
O a.wetE
I e
2-lack of valid vibration predictions precludes However, the our acceptance of BAW-10038 and BAW 10051 and the designation of Oconee-1 as a prototype plant.
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