ML19316A572
| ML19316A572 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/02/1973 |
| From: | Maccary R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8001100790 | |
| Download: ML19316A572 (3) | |
Text
i i
's p
MAR 2 1373 l
Richard C. DoToung, Assistant Director for Pressurized Water Reactors Directorate of Licensing OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 Plant Name: Oconee Nuclear Station Licensing Stage: OL Docket Numbers: 50-269/270/287 Response Branch and Project Manager: PWRil, I. A. Peltier Requested Completion Date: N/A Applicants Response Date Necessary for Completion of Next Action Planned on Project: N/A Description of Response: Final Evaluation - Mechanical Engineering Branch i
Review Status: Complete The Final Evaluation - Mechanical of the FSAR for the subject plant, which
]
was prepared by the MEB, Directorate of Licensing, dated September 8,1970 and revised September 25, 1972 and November 29, 1972, has been further revised to reflect our evaluation of Oconee-1 hot functional testing results.
[Jb, (
We concur with Babcock & Wilcox concerning the design adequacy of the re-
)
9
! L designed reactor internale of Oconee-1. However, it should be noted that
'( t "
Oconee-1 cannot be qualified as the prototype plant until valid vibration predictions are submitted.
DIgiim1 sid2cd by
' ~
R. R. 31accary R. R. Maccary, Assistant Director for Engineering Directorate of Licensing ec w/ encl S. H. Uanauer, DRTA J. M. Hendrie, L FWR Branch Chiefa J. P. Knight, L
- 1. A. Peltier, L Docket Files 50-269/270/287 B. C. Buckley, L L, Reading File cj M f
H. L. Braumer, L L:MEB File c.
S. 5. Hou, L cc w/o encl:
A C4mmbinen; f.
omg G. Mcdonald, Il L:
B L:
,,,( _
summaut >
NHou:jm JP ight- -. - -.
cary mr>
3/.l.n3..
3/ l.173
. 3/3/7.3.....
foem AIC-HS tRev 9 Sh AICM 0240 W o.
. c o..
- t......,cc,,,c,
,,73...i.33, i
\\
8oo1100790
o FINAL EVALUATION - MECllANICAL OCONEE NUCLEAR STATION, UNITS 1, 2 & 3 DOCKET NOS. 50-269/270/287 i
The Final Evaluation from the Mechanical Engineering Branch, Directorate 25, 1972, of Licensing dated September 8,1970 and revised September remains unchanged except the specific section below which was revisc i on November 29, 1972 should be further revised:
VIBRATION CONTROL The text of this section remains unchanged except the portion added by revision on November 29, 1972 should be replaced by the following:
Subsequent to the failutes which occurred during the initial hot functional test of Oconee-1, Babcock and Wilcox submitted the following Topical Reports:
BAW-10037
" Reactor Vessel Model Flow Tests" BAW-10038 "Oconee Internals Vibration Test Program" BAW-10050
" Evaluation of Oconee Reactor Component Failure" BAW-10051
" Design of Internals for Flow Vibration" In the process of reviewing the m activeprogram, we have evaluated the We concur with the conclusions set forth in BAW-10050 that above reports.
the recommended design modifications on the internals have been based upon a conservative application of the response and failure data from Oconee-l.
We concur with the conclusions set forth in BAW-10037 that the reactor vessel scale model flow test approach used will verify the core flow We have also evaluated BAW-10051, BAW-10038, the results Jistribution.
of the hot functional testing at Oconee-1 conducted af ter re-design (Letter A. C. Thies to A. Giambusso dated February 15, 1973, transmitting the report "Results of Oconee 1 Hot Functional Testing Internals Vibration e
i
Based on o
face inspection.
Monitoring Program"), and the post-test surced submitta the data submitted in the referen t re responses and the internal struc u margins exist between measuredIn addition, no eviden degradation respective allowables.
inspection of the internal structures was observed during the surface ordance with Safety Guide following the test program carried out in acc design adequacy of Based on the above we find that thebeen accepta No. 20 re-designed internals of Oconee-1 has i
e 0
. I-M, +e+%
j