ML20084T096
| ML20084T096 | |
| Person / Time | |
|---|---|
| Site: | Palisades, 05000000 |
| Issue date: | 08/20/1973 |
| From: | Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Schemel R US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20084T038 | List: |
| References | |
| NUDOCS 8306210225 | |
| Download: ML20084T096 (20) | |
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August 20, 1973 Denufatory Filo Cy.
Mr. Robert J. Schemel, Chief Re: Docket 50-255 Operating Reactors Branch No 1 DPR-20 Directorate of Licensing US Atomic Energy Commission Washington, DC 20545
Dear Mr. Schemel:
The additional information you requested from us on July 27, 1973 in regard to the ex-core flux detector signal oscillations observed at our Palisades Plant is attached.
Yours very truly, d
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Recalved wfLtr C: tad b20*73 A?PACIC4EITP A Additional Information On Ex-Core Flux Detector Signal Oscillations at the Palisades Plant i
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i Question 1: Provide adequate evidence, by means of analysis or signal interpretation, to verify that the first cantilever mode as claimed is indeed the only dominant mode in the internals vibration. The quantitative relationships between amplitudes at specific locations on the core barrel and the specific measurements of neutron detectors should be provided.
Answer:
Lateral motion of the core support barrel, as the primary cause of
.theeex-core detector-noise phenomenon, is consistent with the character and azimuthal relationship of the six detector signal time traces, as illustrated in Figure 1.
Additional characterization of the noise is afforded by the power spectral density (PSD) of the ex-core signal, an exampic of which ap-pears in Figure 2.
The PSD shows that most of the signal noise is a broad band process in the frequency range up to 6 Hz.
(That this is the frequency region of interest is corroborated by the fact that it is in that region -
particularly at the low end - where the various ex-core signals are coherent, with the phase angles so noticeable among the time traces, as demonstrated by Figures 3 and 4.) There cre no sharp peaks in the frequency spectrum above 6 Hz, except for an " aliasing" peak at 7 5 Hz (a product of the data analysis method and not a component of the actual PSD) and the peak at 14.8 Hz, which corresponds to the pump rotational frequency. Thus, there is no noticeable discrete response in the spectrum which could be equated with significant excitation of the barrel at a specific natural frequency of that component.
This character of the noise differs from that experienced in other reactors where detector noise, although displaying a similar animuthal pattern to that at Palisades, appears to occur primarily at a discrete frequency equated with a natural pendulum frequency of the core support barrel (References 1 and 2).
4 With regard to Palisades, it is postulated that the barrel is being driven to move laterally and randomly, within the constraints of the snubber 4
clearances, by random hydraulic forces in a 0 to 6 Hz frequency range, which is too low to cause prominent excit., Ation of any one of the barrel's natural frequences.
In this context, no one particular mode of side-to-side and
- azimuthal deformation can be precisely identified. The most that, can be said is that, in view of the upper end fixity condition, the motion is a randomly varying combination of cantilever and, possibly, some shell shapes - whatever
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is most compatible with the varying hydraulic force and frequency pattern and which, in the aggregate, appears qualitatively most like centilever deformation.
On occasion, it has been so deteribed, without qualification, and the implica-tion may have been drawn that the barrel was being exc! md in the fundamental mode at the corresponding charneteristic frequency. The description could have been misleading in view of the actual character of the Palisades noise and the fact that a simple fundamental pendulum motion does appear to be occurring in the reactors of References 1 and 2.
J An estimate has been made of the magnitude of the deduced motion; it is based upon the hypothesis that core barrel motion relative to the vessel vall accounts for approximately 80% of the ex-core detector noise, while normal back-1' ground noise and motion of the core relative to the core shroud accounts for the remaining 20%. The fractional apportionment is deduced from the PSD and coher-ence plots of the ex-core signals, and the assumption that barrel motion should result in highly coherent ex-core signal oscillations.
Thus, in the coherence Plots, the highest coherence between ex-core signals occurs in the O to 1-1/2 Hz frequency range, which range accounts for 80% of the noise in the PSD. A statistical evaluation of noise magnitude for a detector (NI-005) showing a 1
relatively large noise component indicated that the 80% population coverage level encompassed all noise equal to or less than 1.3% of the detector measured power level. The sensitivity of the detector to motions of the barrel which would affect the thickness of the attenuating downconer water gap is estimated to be about 0.033% change in signal per 1 mil change in thickness. There-fore, the order of magnitude motion of the barrel is equal to or less than 40 mils (= 1 3% + 0.033% per mil). As indicated by the relative noise levels of j
the variots detectors in Figure 1, motion of that magnitude is in an east-vest direction; it is less in the north-south direction.
4 Each ex-core detector sees the core in a slightly different way as the result of the azimuthally variable core peripheral geometry. Also, each detector is as long as the core and is located external to the vessel, so that I
the signal that it sees is one that is averaged over the core length and over a finite azimuthal angle. Because of these considerations and the approximate i
nature of the evaluation itself, it does not appear meaningful to extend the analysis to determining specific barrel displacements at different elevations and azimuthal locations.
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Question 2:
Discuss the accuracy of predicting the core barrel motion by means of interpreting the neutron noise signals which has been limited to a frequency band of 20 Hz.
Due to the truncation of waves having frequencies hi6her than 20 Hz in the data processing, and the remote locations of detectors from core, the sensitivity of si nal representation should be discussed quantitatively.
6 Answer:
The ex-core noise phenomenon was initially investigated with a portable on-line spectrum analyzer.
The time-varying portion of the ex-core signal was processed by the analyzer to produce a frequency spectrum identifying the most significant frequencies of frequency ranges out to 200 Hz.
As the represen-tative plot (Figure 5) shows, nothing significant is present above 20 H:
except for the usual 60 Hz line noise and its hamonics. Accordingly, the later, more detailed teasurements were restricted to the 20 Hz frequency range, with the assurance that the accuracy of the analysis would not be affected by that restriction.
The effect of the remote location of the detector is primarily one of causing it to see a signal frem the core avera6ed over a finite angle.
This is one of the reasons why it was n-believed preductive to attempt any finer resolution of the barrel motion than is described in the answer to Question 1.
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Question 3: Provide the acceptable design limits in the reactor internals vibration in tems of stresses or displacements under operating g
flow transients, such as the displacement or stress limits at l
the lower end of the core barrel toward the anubbers and the
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stress limits near the key connections at the upper core plate j
and at the vessel flan 6e vicinity. The basis and computation procedares used to arrive at such limits and their relation to neutron flux oscillation levels should be described. The stress limits should be compared with allovable stresses for the range of fatigue cycles.
Answer:
The acceptable design limits of reactor internals vibration under operating flow conditions are based on design limits outlined in Section III.
- k ASME Boiler and pressure Vessel Code, including fatigue allovables for infinite y
life.. Displacements of the core support barrel were computed corresponding to
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the maximum stress allowables for three flexural models': The free cantilever mode, the free canti2ever mode with an interaction between the barrel and the upper guide structure guide lugs (four lugs equally spaced circumferentially around the upper guite structure fuel alignment plate, see Drawing 2966-SJ-1752)
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and the proI-ped cantilever mode. The lateral displacement of the core barrel was assumed to result from a uniform pressure differential acting over the lateral projected area of the core support barrel. The contribution of higher modes to the core barrel displacement, although they are undoubtedly present
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due to the random forcing function, was considered negligible since no signif-D icant motion in these modes at their corresponding frequencies appears in the 4
ex-core power spectral densities. The required displacements, required pressure differentials, locations of limiting stress and the corresponding estimated ex-core ras noise are tabulated in Table I for the limiting stress conditions.
l The displacements listed in Table I assume that the indicated high-h pressure differentials are available and that the snubbers are inoperative for Cases I and II.
The estimated ex-core rms noise magnitude is a linear 4
extrapolation of that corresponding to the postulated h0 mils barrel referred to in the answer to Question 1.
E It is emphasized that the stresses deduced from the postulated motion y
presently being experienced by the core support barrel are approximately a factor of 10 less than the allowable fatigue stress associated with the displacements shcun in Table I.
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Question 4: Provide a detailed drawing of reactor core internals. The configurations of snubbers, core upper joints and the major load paths should be clearly identified, including the analysis of I
motions and displacements which these components may undergo, within the clearance limits as calculated from as-built
-i dimensions.
a Answer:
The details of the reactor core internals are shown on the attached drawing, 2966-SJ-1752. An exploded view of a snubber is shown in Figure 6.
The as-built clearances at each snubber under hot operating conditions are shown on Figure 7 The as-built hot operating condition clearances in the alignment key areas are shown on Figure 8.
The upper guide structure align-p ment lug hot operating as-built clearances are shown on Figure 9 The snub-bers, keys and alignment lu6s restrict movement in the lateral direction.
Figure 10 shows the major load paths for the internals. The core support barrel is restrained at the upper flange by the lateral restraint of the alignment keys and the vertical restraint of the upper guide structure, ring shim and vessel flange assembly. The flange assembly provides a large hold-down force on the core barrel and upper guide structure, thereby re-stricting lateral covement.
The lover en '. of the core Support barrel is restrained laterally by six snubber assemblies. The upper guide structure alignment lugs provide lateral restraint between the base of the upper guide structure and the core support barrel.
The fuel assemblies are laterally restrained by pins which project into the fuel alignment plate at the top 1
and the core support plate at the bottom.
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TABL'E I INTERNALS CONDITIONS REQUIRED TO YIELD COMPONENT LIMITING STRESS i
END CONDITION REQUIRED DISPLACEMENT OF REQUIRED PRESSURE LOCATION OF EX-CORE ESTIMATED BA REL AT CORE Mill-PLAN {g DIFFERENTIAL - psi LIMITING STRESS RM3 NOISE *
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.~ASE I:
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6 shell to flange.
l (Snubbers inoperative) l Free Cantilever CASE II:
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CASE III:
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i 78 530 Junction CB 2%
j shell to flange 9
Snubbar j
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- By comparison, the measured ex-core RMS noise corresponding to the hypothesized 40 mils motion of the barrel is 0.6%.
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O l-References i
1)' " Proof of Pendulum Motion of the Core Support Structure in the Neutron Flux Noise", W. Basti, D. Wach, W. H. Dio, W. Haas, Atomwirtshaft, f
May 1972.
"Trino Nuclear Power Station In-Service Monitoring of Reactor Internals",
2)
M. Calcagno, F. Cioli, A. Cradola, G. Possa, G. Vanoli, ENEL, December j
.1970.
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FIGURE 9
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COMBUSTION ENGINEERING. INC.
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CUSTOMER CONT.No.
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