ML19319B029
| ML19319B029 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/01/1972 |
| From: | Maccary R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8001060030 | |
| Download: ML19319B029 (3) | |
Text
_ -_ _ _ _ _ _ _ _
e.
DEC 1 1372 R.
C. DeYoung, Assistant Director for Engineering Directorate of Licensing STATUS REPORT ON OCONEE 1, 2 AND 3 - PLOW INDUCED VIBRATION TO REACTOR IHTERNALS AND ACCEPTANCE OF TOPICAL REPORTS AND BAW-10037 - REVIGION 1 BAV-10050 Plant Name -
Oconee 1, 2,
and 3 Licensing bosge:
OL Docket Nos.:
50-269/270/28T Responsible Branch and Project Manager:
PVR Branch No. h.
I.
A. Peltier Reviev Gtatus:
BAV-10050 & BAW-10037 - Complete DAV-10051 & BAW-10038 - Partial The Mechanical EngineerinC Branch, Directorate of Licensing has reviewed four topical reports (BAW-10037,10038,10050 and 10051) concerning the hot functional vibration failures submitted by Babcock & Wilcox (L&W).
This status report supersedes our status report of November 29, 1972.
comments on these topicals The MEB conclusions and are as follows:
1.
DAV-10050 - B&W conducted an investigation on the cause of the preoperational test failure.
The metallographic examination of the failure surfaces concluded that the g
fatigue due to flov induced vibratory motion was the l ' ',
i major failure node.
Component redesign was based 4/
. f'C ','
(a) further separation of structural frequencies upon from vortex shielding frequencies, and of the stresses to a level below the caterial(b) further reduction l
limit.
We concur with B&W that endurance such dosi6n modifications vill improve the internals.
structural integrity of the reactor 2.
BAW-LOO 37 - Reactor vessel flov testing was conducted on a one-sixth scale model to investigate flow distribution, pressure loss and the pattern of flow mixinC from the various inlets.
The and vent valve testing vereflow characteristics inside the core emphasized.
Both the original OFTICE >
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GT2 and the mo'dified designs vers tested.
The tests results showed that the modified desi5n provides more uniform flow distribution._vith acceptable pressure loss.
However. BLW indicated that since the flow rate was slightly higher at certain portions of the core, further minor modifications in deciEn vill be required.
Ve concur with B&W on the approach used to verify the core flow. distribution.
3 BAV-10051 --B&V has attempted to Justify the reactor internals design nodifications in DAW-10051 by cocputin6 responnes of codified conponents to flov
' induced vibration.
hovtyer, the actual flow forcinF
~
i functions may not be verified until the new preoperational
. vibration test program for Oconee 1 has been completed.
We concur that internals have been redesigned based upon a1 conservative application of the response and failure data from the Oconee 1 preoperational tests.
.However, due to a inck of valid flov forcing functions and complete response determination, we cannot couplete our evaluation of this topical at this tius.
The applicant has stated that further efforts, includin6 cor.ponent testing of instrument Guide tubes and incore nossle assemblies vill be performed to provide a better understanding of the vibration behavior.
The. thermal shield vibration response characteristics vill be further defined by further evaluation of the Oconee 1 response
.and failure data.
4.
BAW-10030 - The prototype preoperrational vibrntion testing progrs= includinc a subsequent inspection progran for reactor internals is described in EAV-10038.
The applicant -cannot provide valid vibration predictions required by. Safety Guide 20 due to inconclusive as dynamic analysis.
Therefore, ve cannot conplete our evaluation of this report at this tir.e.
OFFIM >
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W TE >
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DU 1 1972 3-R.:C. DeYoung Ve concur with B&W that the design modifications on the internals-have been based on a conservative application of However, due to the response and failure data from Oconee 1.
structural a lack of concrete analytical evidence to assure int *Erity of reactor internals under the transient loadings, satisf actory completion of the new preoperational vibration testing thould be considered as a prerequisite for operation at a significant power level.
LAV-10051 and EAV-10038 nay be approved when the additional tests and evaluations indicated above are completed to When the provide the basis for vibration predictions.infornntion is aceived a The information qualified as a valid prototype plant. contained in EAV-loo 50 and BAW va are not preparing in the Oconee 1, 2, and 3 applications, since these topicals Topical Report I: valuations on these topicals are practically unique to the Oconee application.
05simJ t%;E(d by ItIL Eccry R. R. Maccary, Assistant Director for Fngineering Directorate of Licensing i
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H. Hanauer DRTA DISTRIBUTION J. M.
Hendrie, L L Reading File A. Giachusso, L MEB File
?*R File W. G. Mcdonald, L C<T. FcQ. 6'U Od f/d%/N7 FVR Branch Chiefs D. F. Lance L
I. A. Peltier, L U. L. Branmer, L G.
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