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{{#Wiki_filter:T' e*** ._, CONSUMERS POWER COMPANY PALISADES NUCLEAR PLANT REACTOR INTERNALS NOISE TESTS NOVEMBER 1978 -NOVEMBER 1979
{{#Wiki_filter:._,
,, ' .... v LIST OF FIGURES Figure Title 1 Instrumentation Locations for Noise Tests 2. Schematic of Signal Conditioning Equipment 3 IAPD NI-05 . 4 IAPD NI-06 5 IAPD NI-07 6 IAPD NI-08 7 NPSD NI-05 5/31/78 . 8 NPSD NI-06 5/31/78 9 NPSD NI-05 & NI-06 2/19/79 10 NPSD NI-05 & NI-06 8/16/79 11 NPSD NI-07 5/31/78 12 NPSD NI-08 5/31/78 13 NPSD NI-07 & NI-08 *2/20/79 14 NPSD NI-07 & NI-08 8/17/79 15 Coherence and Phase Diagrams May 1978 16 Coherence and Phase Diagrams February 197.9 17 Coherence and Phase Diagrams August 1979 ii CONTENTS I Introduction II Description of Noise Analysis Method III General Core Arrangement and Signal Conditioning IV Summary of Noise Analysis Results V Conclusion References Reference 5 Memo from DMKennedy to JAMeincke "Palisades Plant Reactor Internals Vibration Monitoring M and N Sigma Limits", May 14, 19?9 f I -1 I Introduction This report entitled Reactor Internals Noise Monitoring-Tests covers the per-iod November 1978 to November 1979. This reporting period encompasses the second half of core three; Palisades was shutdown for a refueling outage during September 1979. Contained in this report is a summary of results ob-tained .from Technical Specification tests, Reference 1, which require data be taken on reactor internals noise on a weekly and monthly basis. The data collected on a weekly basis, Phase One measurements, consists of the integral probability distribution function, standard deviation, and % RMS in selected frequency bands of reactor internals noise. The data collected on a monthly basis, Phase Two measurements, consists of a power spectral density, phase of transfer function, and coherence for each excore_detector combination.
T' e***
The frequency of data collection and the method of data collectibn has changed somewhat since the last reporting period. This change is a result of Ref-erences 2, 3 and 4 which allowed Palisades to monitor reactor internals noise on a more infrequent basis. This change is described in Section
CONSUMERS POWER COMPANY PALISADES NUCLEAR PLANT REACTOR INTERNALS NOISE MONITO~ING  TESTS NOVEMBER 1978 - NOVEMBER 1979 8006110\~7
*''
 
* 2 , II Description of Noise Analysis Method As required by-Reference 1, reactor internals noise monitoring is on a weekly and monthly basis. The weekly surveillance consists of the acquisition of the standard deviation, % RMS, and integral probability distribution (IAPD) of excore detector combinatiOns in the frequency bands (l-3)Hz, (10-16)Hz and (16-20)Hz.
            ~? '
The monthly surveillance consists of the acquisition of the phase of transfer function, normalized power spectral density (NPSD) and coherence of excore detector combinations in the frequency band (0-2S)Hz.
          ~p v                   LIST OF FIGURES Figure                         Title 1 Instrumentation Locations for Noise Tests
below is general discussion of each of the surveillance methods. % RMS Alert and action limits, M sigma and N sigma respectively, have been assigned to the % RMS values per Reference 5 '(attached) which are given below. (l-3)Hz (10-16)Hz (16-20 )Hz M sigma .16% .11% .11% N sigma . 24% .16% .16% These limits were analytically determined based on information in References 6 and 7 and Palisades core geometry.
: 2. Schematic of Signal Conditioning Equipment 3 IAPD NI-05 .
The frequency bands of surveillance are different from those previously monitored since, based on the information in References 6 and 7, information on reactor internals vibration is properly determined from the cross power spectral density rather than the auto power ... spectral density. Furthermore, those frequency bands which show a phase in_ the transfer function between two excore detectors of 180° .are the frequency bands where reactor internals vibration are occurring.
4 IAPD NI-06 5 IAPD NI-07 6 IAPD NI-08 7 NPSD NI-05   5/31/78 .
Phase diagrams from the first 6 months of core three were examined as discussed in Reference 5 and those frequencies with a phase of 180° were noted. Also, frequencies in which core support barrel vibration occurred in 1972, i.e. (12-13)Hz and I'
8 NPSD NI-06   5/31/78 9 NPSD NI-05 & NI-06 2/19/79 10 NPSD NI-05 & NI-06 8/16/79 11 NPSD NI-07   5/31/78 12 NPSD NI-08   5/31/78 13 NPSD NI-07 & NI-08 *2/20/79 14 NPSD NI-07 & NI-08 8/17/79 15 Coherence and Phase Diagrams May 1978 16 Coherence and Phase Diagrams February 197.9 17 Coherence and Phase Diagrams August 1979
* 3 (18.,...19)Hz, were also noted. The above listed frequency bands were determined through a summation of the frequency bartds in* which current phases of detec.,...
 
tor combinations are 180° and.those frequency bands in whic:h core support barrel vibration occurred in the past. A description of the mathematical technique of obtaining sigma and % RMS values from the cross power spectral density is given in Reference  
ii CONTENTS I Introduction II Description of Noise Analysis Method III General Core Arrangement and Signal Conditioning IV Summary of Noise Analysis Results V Conclusion References Reference 5 Memo from DMKennedy to JAMeincke "Palisades Plant Reactor Internals Vibration Monitoring M and N Sigma Limits", May 14, 19?9
: 8. Integral of Amplitude Probability.Distribution (IAPD) The Integral of the Amplitude Probability Distribution  
 
.(IAPD) is determined for each excore detecior in the frequency bands (10.,...16)Hz and (16.,...20)
f I
Hz. The IAPD is formed in the following manner: 1) Data in the time domain is received by the fourier analyzer, 2) The fourier analyzer transforms the data to the frequency domain where *the frequency band of interest is.isola-ted, 3) This frequency band is then transformed to the time domain. Steps 1, 2 and 3 are performed for 500 entries into the fourier:analyzer and the ' ' results are added to form a . The histogram is area normalized and . .  
-                                                                                 1 I   Introduction This report entitled Reactor Internals Noise Monitoring-Tests covers the per-iod November 1978 to November 1979. This reporting period encompasses the second half of core three; Palisades was shutdown for a refueling outage during September 1979. Contained in this report is a summary of results ob-tained .from Technical Specification tests, Reference 1, which require data be taken on reactor internals noise on a weekly and monthly basis. The data collected on a weekly basis, Phase One measurements, consists of the integral probability distribution function, standard deviation, and % RMS in selected frequency bands of reactor internals noise. The data collected on a monthly basis, Phase Two measurements, consists of a power spectral density, phase of transfer function, and coherence for each excore_detector combination.
*to. give the. IAPD. The ordinate scale of. an IAPD ranges between 0 and L Through observation of the location of the
The frequency of data collection and the method of data collectibn has changed somewhat since the last reporting period. This change is a result of Ref-erences 2, 3 and 4 which allowed Palisades to monitor reactor internals noise on a more infrequent basis. This change is described in Section ~I.
* 5 value, a determina-tion can be inade if vibration of the core support barrel or other reactor internal is being impeded in peak to peak swing. Such early termination of peak to peak swing was seen in 1972 and was the result of the core.support' .barrel contacting the snubbers.
 
The IAPD is a backup surveillance to %-RMS. Phase of Transfer Function A transfer function between two excore detectors is formed by taking the fourier transform of the time. domain data from one detector, dividing it by the fourier transform of the time domain data from the second detector and converting the results to polar coordinates.
, II Description of Noise Analysis Method
'l 4 Coherence The co.herence function between two detactors describes the* "common causality" between the two detectors.
* 2 As required by- Reference 1, reactor internals noise monitoring is       t~ke_n on a weekly and monthly basis.       The weekly surveillance consists of the acquisition of the standard deviation, % RMS, and integral probability distribution (IAPD) of excore detector combinatiOns in the frequency bands (l-3)Hz, (10-16)Hz and (16-20)Hz.       The monthly surveillance consists of the acquisition of the phase of transfer function, normalized power spectral density (NPSD) and coherence of excore detector combinations in the frequency band (0-2S)Hz. Present~d  below is   ~ general discussion of each of the surveillance methods.
Its value ranges between 0 and 1 and it is formed through. the following expression:
      % RMS Alert and action limits, M sigma and N sigma respectively, have been assigned to the % RMS values per Reference 5 '(attached) which are given below.
where:
M  sigma      N sigma (l-3)Hz             .16%          . 24%
= (a.-:;: I .x. 6,,
(10-16)Hz           .11%          .16%
* Ga:i'l. I;;-I<<.  
(16-20 )Hz         .11%           .16%
-square of the magnitude of cross spectrum n--_.,.,, -auto of detector 1 C.-<<<--auto spectrum of detector 2 Together with the phase, the coherence forms a.qualitative diagnostic tool in which quantification is achieved through the % RMS. The coherence displays those *frequencies that are common to two excore detectors and-the phase in_. dicates whether the frequency is associated with vibration.
These limits were analytically determined based on information in References 6 and 7 and Palisades core geometry.       The frequency bands of surveillance are different from those previously monitored since, based on the information in References 6 and 7, information on reactor internals vibration is properly determined from the cross... power spectral density rather than the auto power spectral density.     Furthermore, those frequency bands which show a phase in_
Coherence and phase diagrams can be formulated with data from all combinations of excore detectors*and shifts of signature values in phase ot coherence are readily observed.
the transfer function between two excore detectors of 180&deg; .are the frequency bands where reactor internals vibration are occurring.       Phase diagrams from the first 6 months of core three were examined as discussed in Reference 5 and those frequencies with a phase of 180&deg; were noted.       Also, frequencies in which core support barrel vibration occurred in 1972, i.e. (12-13)Hz and
Normalized Power Spectral Density (NPSD) The Normalized Power Spectral Density is formed through the following equation:
 
where: Fi -Fourier of data from a detector F1*-
I' (18.,...19)Hz, were also noted.
conjugate of fourier transfer N -Normalization .constant which includes a power and frequency normalization.
The above listed frequency bands were determined 3
The usefulness of the NPSD is to monitor signature frequencies.
through a summation of the frequency bartds in* which current phases of detec.,...
.. ' *
tor combinations are 180&deg; and.those frequency bands in whic:h core support barrel vibration occurred in the past.         A description of the mathematical technique of obtaining sigma and % RMS values from the cross power spectral density is given in Reference 8.
* 5 III' General Core Arrangement and Signal Conditioning Figure 1 shows the of excore detectors to significant primary system items. The excore detectors NI-05, NI-06, NI-07 and NI-08 are located 0 approximately 45 from the hot legs. The cold legs of the reactor vessel.* are approximately at.the same angular location as the excore detectors.
Integral of Amplitude Probability.Distribution (IAPD)
A rough 9utline of the core is also shown in the figure. Current from the ex-:-core detectors is brought through a current to voltage amplifier and then as shown in Figure 2, through a voltage amplifier, a filter and then to the fourier analyzer.
The Integral of the Amplitude Probability Distribution .(IAPD) is determined for each excore detecior in the frequency bands         (1~3)Hz,  (10.,...16)Hz and (16.,...20)
The voltage amplifier is AC coupled so that only the fluctuating (noise) component.of the signal is amplified.
Hz.     The IAPD is formed in the following manner: 1) Data in the time domain is received by the fourier analyzer, 2) The fourier analyzer transforms the data to the frequency domain where *the frequency band of interest is.isola-ted, 3) This frequency band is then transformed to the time domain.               Steps 1, 2 and 3 are performed for 500 entries into the fourier:analyzer and the results are added to form a histogra~; . The histogram is area normalized and .
The filters are used to bandpass the signal in range .025Hz to 25Hz. The fourier analyzer, HP5451B, is used to. perform all statistical .analysis on the noise component.
. in~egrated    *to. give the. IAPD. The ordinate scale of. an IAPD ranges between 0 and L       Through observation of the location of the
Steam n 11>--------
* 5 value, a determina-tion can be inade if vibration of the core support barrel or other reactor internal is being impeded in peak to peak swing.         Such early termination of peak to peak swing was seen in 1972 and was the result of the core.support'
CORE pressurizer pressure
.barrel contacting the snubbers.         The IAPD is a backup surveillance to %- RMS.
* generator A :i)'*
Phase of Transfer Function A transfer function between two excore detectors is formed by taking the fourier transform of the time. domain data from one detector, dividing it by the fourier transform of the time domain data from the second detector and converting the results to polar coordinates.
___ __, FIGURE 1 Jnsttumentallon locations for noise tests
 
* J! ..... __
'l 4
Input to Fourier Analyzer Low Pass Filter 24db/oct High Pass Filter 24db/oct Operational Amplifier Nominal Gain of 50 FIGURE 2 SCHEMATIC OF SIGNAL CONDITIONING EQUIPMENT  
Coherence The co.herence function between two detactors describes the* "common causality" between the two detectors.         Its value ranges between 0 and 1 and it is formed through. the following expression:
+ Jl Buffered Excore Det.ector Test Signal *
(Cc~{)&deg;"' =   (a.-:;: I .x.
.3/ 4/79 4/1/79 5/25/79 7/1/79 8/26/79
6,,
* 8 IV *. Sunnnary of Noise Analysis Results Presented below is a sunnnary of the surveillance results for the reporting peroid. These results are organized by surveillance technique.  
* Ga:i'l.
% RMS Table 1 lists % RMS values for the frequency bands (l-3)Hz, (10-16)Hz and (16-20)Hz for all detector combinations.
where:
Representative results are listed from tests throughout the reporting period. It is seen that the alert limits of
          ;;- I<<.-
* 16 % RMS for the frequency band of (l-3)Hz and .11 % RMS for the frequency bands (10-16)Hz and (16-20)Hz have not been exceeded.
I~.<il. square of the magnitude of cross spectrum n--
The increase in % RMS for the (l-3)Hz band is an expected increase and is *associated with the de-* creasing concentration as a function of time or burnup as discussed in Reference  
_.,.,, - auto   spec~rum    of detector 1 C.-<<<- - auto spectrum of detector 2 Together with the phase, the coherence forms a.qualitative diagnostic tool in which quantification is achieved through the % RMS.         The coherence displays those *frequencies that are common to two excore detectors and- the phase in_.
: 9. 1 -l-3Hz 2 16Hz 3 20Hz TABLE 1 % RMS FOR DETECTOR COMBINATIONS FOR FREQUENCY BAND (l-3)Hz, (10-16)Hz, (16-20)Hz   
dicates whether the frequency is associated with vibration.         Coherence and phase diagrams can be formulated with data from all combinations of excore detectors*and shifts of signature values in phase ot coherence are readily observed.
. *,
Normalized Power Spectral Density (NPSD)
* 9 IAPD Figures 3, 4, 5 and 6 show the integral of the amplitude probability distri-' bution for the month of August 1979; this is one month before the plant was shut down* for refueTing.
The Normalized Power Spectral Density is formed through the following equation:
As. stated before, the ordinates of the I.APDS are from 0 to 1. The abscissa is expressed in terms of millivolts.
where:
At 100% power the excore detector is 8 volts averaged.
Fi - Fourier     t~ansfer    of data from a detector F1*- Comple~    conjugate of fourier transfer N - Normalization .constant which includes a power and frequency normalization.
On top of the 8 volts exists a millivolt noise component.
The usefulness of the NPSD is to monitor signature frequencies.
This is what is measured by the fourier analyzer and why it.appears in.the IAPD. As can be seen from the figures,.when the IAPD has a .value of .5 on the ordinate scale, the abscissa is at 0 millivoits.
 
III' General Core Arrangement and Signal Conditioning
* 5 Figure 1 shows the r~lationship  of excore detectors to significant primary system items. The excore detectors NI-05, NI-06, NI-07 and NI-08 are located 0
approximately 45   from the hot legs. The cold legs of the reactor vessel.*
are approximately at.the same angular location as the excore detectors. A rough 9utline of the core is also shown in the figure. Current from the ex-:-
core detectors is brought through a current to voltage amplifier and then as shown in Figure 2, through a voltage amplifier, a filter and then to the fourier analyzer. The voltage amplifier is AC coupled so that only the fluctuating (noise) component.of the signal is amplified. The filters are used to bandpass the signal in range .025Hz to 25Hz. The fourier analyzer, HP5451B, is used to. perform all statistical .analysis on the noise component.
 
J!
Steam ~~1-J1C1t"tor n       11>--------
CORE
                            *'----~ pressurizer pressure
                *  ~team  generator A     :i)'*~--....__ _ __ _ ,
FIGURE 1 Jnsttumentallon locations for noise tests
* Jl
                                                            +
Input to Low Pass   High Pass          Operational            Buffered Fourier  Filter    Filter             Amplifier              Excore Det.ector Analyzer 24db/oct   24db/oct           Nominal Gain           Test Signal of 50 FIGURE 2 SCHEMATIC OF SIGNAL CONDITIONING EQUIPMENT
 
IV *. Sunnnary of Noise Analysis Results
* 8 Presented below is a sunnnary of the surveillance results for the reporting peroid. These results are organized by surveillance technique.
                % RMS Table 1 lists % RMS values for the frequency bands (l-3)Hz, (10-16)Hz and (16-20)Hz for all detector combinations. Representative results are listed from tests throughout the reporting period. It is seen that the alert limits of
* 16 % RMS for the frequency band of (l-3)Hz and .11 % RMS for the frequency bands (10-16)Hz and (16-20)Hz have not been exceeded. The increase in % RMS for the (l-3)Hz band is an expected increase and is *associated with the de-
* creasing b~ron concentration as a function of time or burnup as discussed in Reference 9.
TABLE 1
                                  % RMS FOR DETECTOR COMBINATIONS FOR FREQUENCY BAND (l-3)Hz, (10-16)Hz, (16-20)Hz
  .3/ 4/79 4/1/79 5/25/79 7/1/79 8/26/79 1 - l-3Hz 2 16Hz 3 20Hz
 
IAPD
* 9 Figures 3, 4, 5 and 6 show the integral of the amplitude probability distri-bution for the month of August 1979; this is one month before the plant was shut down* for refueTing. As. stated before, the ordinates of the I.APDS are from 0 to 1. The abscissa is expressed in terms of millivolts.      At 100%
power the excore detector is 8 volts averaged.     On top of the 8 volts exists a millivolt noise component. This is what is measured by the fourier analyzer and why it.appears in.the IAPD. As can be seen from the figures,.when the IAPD has a .value of .5 on the ordinate scale, the abscissa is at 0 millivoits.
This. signifies that vibration is of sma11 ''e!lough.magn::f.tude that peak to peak motion is not being hindered.
This. signifies that vibration is of sma11 ''e!lough.magn::f.tude that peak to peak motion is not being hindered.
Normalized Power Spectral Density (NPSD) Figures 7 through 14 show a NPSD for each detector at three different times during core 3, i.e. May 31, 1978, February 19, 1979 and August 16, 1979. These three dates correspond to 6%, 57% and 96% of core life respectively.
Normalized Power Spectral Density (NPSD)
Through an observation of the NPSD (and the coherence discussed in the next section) the following frequencies and their postulated sources display a re.sonance.
Figures 7 through 14 show a NPSD for each detector at three different times during core 3, i.e. May 31, 1978, February 19, 1979 and August 16, 1979.
: 1. 2. 3. 4. 5. 6. 7. .5Hz 2.3Hz ll.25Hz 14.75Hz 15.5Hz 18Hz 23Hz Thermal hydraulic oscillation Fuel bundle vibration Unknown Primary coolant pump blade frequency Shell.mode vibration of reactor vessel Core support barrel vibration Unknown This signature of frequencies has remained relatively constant throughout core 3. A change in this signature over a short period of time would be a strong indication of an anomaly, however this does not exist for core 3. Table II lists the peak amplitude of each of the above frequencies. 
These three dates correspond to 6%, 57% and 96% of core life respectively.
'. * * ' . 10 TABLE II PEAK AMPLITUDE OF NPSD FOR DES.IGNATED FREQUENCIES NI-05 DATE .5Hz 2.3Hz ll.25Hz 14.75Hz 15.5Hz 18Hz 23Hz 5/31/78 75 .,.93 105 2/19/79 69 96 -103 8/16/79 63 83 103 NI-06 DATE . 5Hz 2. 3Hz 11. 25Hz 14. 7 5Hz 15. 5Hz 18Hz 23Hz *5/31/78 75 87 2/ 19/79 69 88 8/16/79 .,...58 90 -84 .,...90 NI-07 DATE .SHz 2.3Hz 11.25Hz 14. 75Hz 15.5Hz 18Hz 23Hz 5/31/78. 74 80 I -103 2/20/79 71 82 8/17/79 65 82 NI-08 DATE .5Hz 2.3Hz ll.25Hz 14.75Hz 15.5Hz 18Hz 23Hz 5/31/78 75 87 2/20/79 70 -85 8/17/79 65 -88
Through an observation of the NPSD (and the coherence discussed in the next section) the following frequencies and their postulated sources display a re.sonance.
-84. -90 NOTE: All value in db blanks signify no resonance
: 1.  .5Hz          Thermal hydraulic oscillation
* 11 Coherence
: 2. 2.3Hz        Fuel bundle vibration
& Phase Figures 15, 16 a.nd 17 present phase and coherence*
: 3. ll.25Hz      Unknown
diagrams for the months -of May 1978, February 1979 and August 1979. The phase at a particular fre-.quency and a given detector combination is given by a straight line for 0&deg; . . 0 0 . phase and a sinusoidal line for a 180 phase. A 90 phase is composed of . half a straight line and half a sinusoidal line. The coherence for the particular frequency and detector combination is written adjacent to the phase line. Significant points from the coherence and phase diagrams are listed below. 1. The .SHz frequency displays for all detector combinations and throughout 0 core life a 0 phase. High coherence is seen. across the hot legs whereas low, coherence is seen diagonally across the core. 2. The 2. 3Hz frequency displays for all detector combina.tions at beginning of core a 0&deg; phase whereas later in core life vibration occurs in the direction of the hot legs. This frequency is believed to be fuel bundle vibration, Reference
: 4. 14.75Hz      Primary coolant pump blade frequency
: 10. 3. The 11. 25Hz frequency displays for all detector combinations and out core life a 0&deg; phase. 4. The 18Hz frequency displays.throughout core life a vibration in the direction of the hot legs. This frequency is believed to be core support barrel vibration. 
: 5. 15.5Hz        Shell.mode vibration of reactor vessel
*
: 6. 18Hz          Core support barrel vibration
* 12 V Conclusion The results from the surveillance methods presented in Section IV show no indication that anomalous or significant reactor internals vibration existed during the reporting period. The magnitude of the %
: 7. 23Hz          Unknown This signature of frequencies has remained relatively constant throughout core 3. A change in this signature over a short period of time would be a strong indication of an anomaly, however this does not exist for core 3.
values in the various frequency bands did not exceed alert or action limits. An inspection of the keys and plungers during the 1979 refueling outage showed no presence of wear which taken in conjunction with the noise analysis data conclusively shows that*the core barrel was tightly clamped during the reporting period and no other anomalous vibrations occurred.
Table II lists the peak amplitude of each of the above frequencies.
FIGURE 3 10 X 10 TO THE INCH* 7 X 10 INCHES KEUFFEL 6 ESSER CO. MADI IN U.S.A. 46 0702 Integral Amplitude Probability Distribution NI-05 fl ;---* 8/16/79 *,. t-t--l-+-1f-+-l-t-l+*t-l-t--t--l-+-l--+-I--l-+--l-1--1-1-..1---,,,_ i'l ' -** ,._ -*----l-IH-1-+-++++-+-l-H-1-1-++++
* TABLE II
* 10 PEAK AMPLITUDE OF NPSD FOR DES.IGNATED FREQUENCIES NI-05 DATE      .5Hz    2.3Hz  ll.25Hz      14.75Hz  15.5Hz  18Hz  23Hz 5/31/78  -62        -75      .,.93      -77                    -105 2/19/79  -58        -69      -93        ~85            -96    -103 8/16/79  -56        -63      -90        -83            -95    -103 NI-06 DATE      . 5Hz    2. 3Hz  11. 25Hz    14. 75Hz 15. 5Hz  18Hz  23Hz
    *5/31/78  -63        -75                  -81    -87 2/ 19/79  -60        -69                  -84    -88 8/16/79  .,...58    -63      -90        -84    .,...90 NI-07 DATE      .SHz    2.3Hz  11.25Hz      14. 75Hz 15.5Hz  18Hz  23Hz 5/31/78. -63        -74      -91        -80                  I -103 2/20/79  -61        -71      -90        -82 8/17/79  -59        -65      -89        -82 NI-08 DATE      .5Hz    2.3Hz  ll.25Hz      14.75Hz  15.5Hz  18Hz  23Hz 5/31/78  -62        -75                  -78    -87 2/20/79  -58        -70                  -85 8/17/79  -55        -65      -88        -84.    -90 NOTE:  All value in db blanks signify no resonance
 
Coherence & Phase
* 11 Figures 15, 16 a.nd 17 present phase and coherence* diagrams for the months -
of May 1978, February 1979 and August 1979.      The phase at a particular fre-
.quency and a given detector combination is given by a straight line for 0&deg;
                .                .      0              0 .
phase and a sinusoidal line for a 180    phase. A 90  phase is composed of .
half a straight line and half a sinusoidal line.      The coherence for the particular frequency and detector combination is written adjacent to the phase line. Significant points from the coherence and phase diagrams are listed below.
: 1. The .SHz frequency displays for all detector combinations and throughout 0
core life a 0  phase. High coherence is seen. across the hot legs whereas low, coherence is seen diagonally across the core.
: 2. The 2. 3Hz frequency displays for all detector combina.tions at beginning of core a 0&deg; phase whereas later in core life vibration occurs in the direction of the hot legs. This frequency is believed to be fuel bundle vibration, Reference 10.
: 3. The 11. 25Hz frequency displays for all detector combinations and through-out core life a 0&deg; phase.
: 4. The 18Hz frequency displays.throughout core life a vibration in the direction of the hot legs. This frequency is believed to be core support barrel vibration.
 
                      *
* 12 V Conclusion The results from the surveillance methods presented in Section IV show no indication that anomalous or significant reactor internals vibration existed during the reporting period. The magnitude of the % R.J.~S values in the various frequency bands did not exceed alert or action


''\' .t; l A A A FIGURE 15 COHERENCE AND PHASE DIAGRAf1S MAY 1978 .SHz li. 25Hz 15.5Hz B A B A B ----A---d
      ~
,...... 18.0&deg; Legen : -Phase 0&deg; Phase 5i6,7,8 Excore Detectors A,B Hot Legs Steam Generator 25 2.3Hz 14.8Hz 5 18Hz 7 
    ,. JAMeiri.cke                                                          Page  2 PALISADES PLANT -
.. l 6 8
  *-   REACTOR INTERNALS VIBRATION c      MONITORING M AND N SIGMA LIMITS May 14; 1979 These limits were obtained using a scale factor of .01%/~il and crest factor of. 3 for the M Sigma limit and a crest factor of 2 for the N Sigma limit.
* FIGURE 16 COHERENCE AND PHASE DIAGRAMS
Derivation of these results can be found on the attached engineering wo~k sheet. Nom{nal clearance of the core barrel from the vessel was taken from a Combustion Engineering Report CEN - 5 (P) March 1, 1974, which states, "Lateral movement of the core support barrel is limited to 20 mils cold (24 mils at reactor operating conditions) in any direction by six stainless steel snubbers welded to the core support barrel reacting against six Inconnel stabilizing lugs attached to the reactor vessel wall".
* FEBRUARY 19 7 9 .SHz 11. 25Hz ]. A B I A 15.SHz Legend: 180&deg; Phase o 0 Phase 5,6,7,8 Detectors.
Typical baseline values for % RMS in the designated frequency bands are:
B A B A B A A,B Hot Legs Steam Generator 26 2.3Hz 14.8Hz J . 5 18Hz A 6 A B I 6 A . ;
1-3   Hz - .057%
* FIGURE 17 COHERENCE AND PHASE DIAGRAMS AUGUST 1979 .5Hz 11. 25Hz I 7 8 15.5Hz 6 Legend:
10-16  Hz - .007%
Phase o 0 Phas.e 5,6,7,8 . Excore Detectors A B A B A A,B Hot Legs Steam Generator 5 \ *j I 7 27 2.3Hz gradually..
16-20  Hz - .002%
broadens over core life 14.8Hz 18Hz * 
These values, as can be seen, are well below their respective-M Sigma limits given above and this indicates.that undue core barrel motion does not exist at i:he present time. This fact .is further supported by Combustion Engineering Report CE 2966-RCE-408, which concludes that based on the results of the January 1978 visual and dimensional inspections no evidence of movement or harmful vibrations of the internals exist.
. \' T ' . REFERENCES
(      In establishing M and N Sigma limits, it is important to have realistic numbers such that core barrel motion is recognized and damage to* the core does not occur, yet, not have numbers which require action when action is not ne~essary. The numbers chosen above are felt to meet both these criteria.
: 1. Palisades Plant Technical Specifications, Section 4.13. 2. Letter, DPHoffman (CPCo) to Director of Nuclear Reactor Regulation (NRC), "Proposed Change to Technical Specifications
* CONSUMERS POWER COMPANY Nuclear Plant ENGINEERING ANALYSIS WORKSHEET
-Reactor Internals Vibration Monitoring", October 25, 1977. 3. Letter, DPHoffman (CPCo) to Director of Nuclear Reactor Regulation (NRC), "Reactor Noise Monitoring Proposed Technical Specifications Change", March 23, 1978. 4. Letter, DLZiemann (NRC) to DABixel (CPCo), January 19, 1979. 5. Letter, DMKennedy to JAMeincke, "Palisades Plant -Reactor Internals Vibration Monitoring M and N Sigma Limits", May 14, 1979. 6. "Calculation of the Scale Factor for Inference of Pressurized Water Reactor Core Barrel Motion from Neutron Noise Spectral Density", Nuclear Technology, Vol. 40, mid August 1978. 7. "Quantification of Core Barrel Motion Using an Analytically Derived Scale. Factor and Statistical Reactor Noise Descriptors", Nuclear Vol. 40, mid August 1978. 8. Reactor Noise by Joseph Thie, Rowman and Littlefield Inc. 1963. 9. Reactor Internals Noise Monitoring Tests, January 1978 (Submitted on April 27, 1978). 10.* XN-74-33, Summary of Mechanical Tests of Palisades Fuel Bundle and Component Parts, September 3, 1974. 
* EA -
.. , :* .. .:* ... * ( f I \. " . To FROM DATE SuB.JECT cc lid)( . Rd' das DMKennedy, Palisades May 14, 1979 PALISADES PLANT -REACTOR INTERNALS VIBRATION MONITORING M AND N SIGMA LIMITS consumers Power company INTERNAL CORRESPONDENCE On October 25, 1977, Consumers Power submitted to the NRC a request for a Technical Specification Change to Reactor Internals Vibration Monitoring which thereafter was*approved by the NRC. The new Technical Specifications allow frequency dependence of the M and N Sigma limits and the purpose of this memo .to s*tate the new limits and .their associated frequency bands. -From a review of Core 3 noise data, it was determined at meeting held at Palisades on February 16, 1979, attended by JAMeincke, KDBrienzo and DMKennedy, that three frequency bands show high coherence and a phase shift of 180&deg;. These bands are: 1-3 Hz 10-16 Hz 16-20 Hz . -. The M and N Sigma limits for these bands were discussed and it was decided to assign different limits to the 1-3 Hz band and the higher frequency bands. The different limits are due to the different manners in which the core support barrel can vibrate. In the 1-3 Hz region, core support barrel movement is believed to consist of a rocking motion in which the core support flange slides back and forth against the vessel support. At the higher frequencies core support barrel movement is believed to be a cantilever beam vibration_-fn' which the core support barrel is secured at the top, .. and oscillates .a,l: the. bottom.* With reference to the attache.d recent publication*"Calculation of the Scale Factor for Inference of Pressurized Water Reactor Core Barrei Motion From Neutron Noise Spectral Density''
Sheet /
Nuclear Technology Vol. 40 mid August 1978, M and N Sigma levels were calculated to be: FREQUENCY BAND M SIGMA N SIGMA Hz .16% .24% 10-16 Hz .11% .16% 16:..20 Hz .11% .16% *Attachment deleted .. '. 
                                                                                                                                                                - - -of- i-_      -
*-c ( " ,. JAMeiri.cke PALISADES PLANT -REACTOR INTERNALS VIBRATION MONITORING M AND N SIGMA LIMITS May 14; 1979 Page 2 These limits were obtained using a scale factor of and crest factor of. 3 for the M Sigma limit and a crest factor of 2 for the N Sigma limit. Derivation of these results can be found on the attached engineering sheet. Nom{nal clearance of the core barrel from the vessel was taken from a Combustion Engineering Report CEN -5 (P) March 1, 1974, which states, "Lateral movement of the core support barrel is limited to 20 mils cold (24 mils at reactor operating conditions) in any direction by six stainless steel snubbers welded to the core support barrel reacting against six Inconnel stabilizing lugs attached to the reactor vessel wall". Typical baseline values for % RMS in the designated frequency bands are: 1-3 10-16 16-20 Hz -.057% Hz -.007% Hz -.002% These values, as can be seen, are well below their respective-M Sigma limits given above and this indicates.that undue core barrel motion does not exist at i:he present time. This fact .is further supported by Combustion Engineering Report CE 2966-RCE-408, which concludes that based on the results of the January 1978 visual and dimensional inspections no evidence of movement or harmful vibrations of the internals exist. In establishing M and N Sigma limits, it is important to have realistic numbers such that core barrel motion is recognized and damage to* the core does not occur, yet, not have numbers which require action when action is not The numbers chosen above are felt to meet both these criteria.
c
c c I \ ,-.. * *
* EA -------Sheet / of i_ CONSUMERS POWER COMPANY Nuclear Plant ENGINEERING ANALYSIS WORKSHEET Alternate Cales c:J


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Latest revision as of 18:04, 23 February 2020

Reactor Internals Noise Monitoring Tests Nov 1978-Nov 1979.
ML18045A222
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Issue date: 11/30/1979
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
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Text

._,

T' e***

CONSUMERS POWER COMPANY PALISADES NUCLEAR PLANT REACTOR INTERNALS NOISE MONITO~ING TESTS NOVEMBER 1978 - NOVEMBER 1979 8006110\~7

~? '

~p v LIST OF FIGURES Figure Title 1 Instrumentation Locations for Noise Tests

2. Schematic of Signal Conditioning Equipment 3 IAPD NI-05 .

4 IAPD NI-06 5 IAPD NI-07 6 IAPD NI-08 7 NPSD NI-05 5/31/78 .

8 NPSD NI-06 5/31/78 9 NPSD NI-05 & NI-06 2/19/79 10 NPSD NI-05 & NI-06 8/16/79 11 NPSD NI-07 5/31/78 12 NPSD NI-08 5/31/78 13 NPSD NI-07 & NI-08 *2/20/79 14 NPSD NI-07 & NI-08 8/17/79 15 Coherence and Phase Diagrams May 1978 16 Coherence and Phase Diagrams February 197.9 17 Coherence and Phase Diagrams August 1979

ii CONTENTS I Introduction II Description of Noise Analysis Method III General Core Arrangement and Signal Conditioning IV Summary of Noise Analysis Results V Conclusion References Reference 5 Memo from DMKennedy to JAMeincke "Palisades Plant Reactor Internals Vibration Monitoring M and N Sigma Limits", May 14, 19?9

f I

- 1 I Introduction This report entitled Reactor Internals Noise Monitoring-Tests covers the per-iod November 1978 to November 1979. This reporting period encompasses the second half of core three; Palisades was shutdown for a refueling outage during September 1979. Contained in this report is a summary of results ob-tained .from Technical Specification tests, Reference 1, which require data be taken on reactor internals noise on a weekly and monthly basis. The data collected on a weekly basis, Phase One measurements, consists of the integral probability distribution function, standard deviation, and % RMS in selected frequency bands of reactor internals noise. The data collected on a monthly basis, Phase Two measurements, consists of a power spectral density, phase of transfer function, and coherence for each excore_detector combination.

The frequency of data collection and the method of data collectibn has changed somewhat since the last reporting period. This change is a result of Ref-erences 2, 3 and 4 which allowed Palisades to monitor reactor internals noise on a more infrequent basis. This change is described in Section ~I.

, II Description of Noise Analysis Method

  • 2 As required by- Reference 1, reactor internals noise monitoring is t~ke_n on a weekly and monthly basis. The weekly surveillance consists of the acquisition of the standard deviation, % RMS, and integral probability distribution (IAPD) of excore detector combinatiOns in the frequency bands (l-3)Hz, (10-16)Hz and (16-20)Hz. The monthly surveillance consists of the acquisition of the phase of transfer function, normalized power spectral density (NPSD) and coherence of excore detector combinations in the frequency band (0-2S)Hz. Present~d below is ~ general discussion of each of the surveillance methods.

% RMS Alert and action limits, M sigma and N sigma respectively, have been assigned to the % RMS values per Reference 5 '(attached) which are given below.

M sigma N sigma (l-3)Hz .16% . 24%

(10-16)Hz .11% .16%

(16-20 )Hz .11% .16%

These limits were analytically determined based on information in References 6 and 7 and Palisades core geometry. The frequency bands of surveillance are different from those previously monitored since, based on the information in References 6 and 7, information on reactor internals vibration is properly determined from the cross... power spectral density rather than the auto power spectral density. Furthermore, those frequency bands which show a phase in_

the transfer function between two excore detectors of 180° .are the frequency bands where reactor internals vibration are occurring. Phase diagrams from the first 6 months of core three were examined as discussed in Reference 5 and those frequencies with a phase of 180° were noted. Also, frequencies in which core support barrel vibration occurred in 1972, i.e. (12-13)Hz and

I' (18.,...19)Hz, were also noted.

The above listed frequency bands were determined 3

through a summation of the frequency bartds in* which current phases of detec.,...

tor combinations are 180° and.those frequency bands in whic:h core support barrel vibration occurred in the past. A description of the mathematical technique of obtaining sigma and % RMS values from the cross power spectral density is given in Reference 8.

Integral of Amplitude Probability.Distribution (IAPD)

The Integral of the Amplitude Probability Distribution .(IAPD) is determined for each excore detecior in the frequency bands (1~3)Hz, (10.,...16)Hz and (16.,...20)

Hz. The IAPD is formed in the following manner: 1) Data in the time domain is received by the fourier analyzer, 2) The fourier analyzer transforms the data to the frequency domain where *the frequency band of interest is.isola-ted, 3) This frequency band is then transformed to the time domain. Steps 1, 2 and 3 are performed for 500 entries into the fourier:analyzer and the results are added to form a histogra~; . The histogram is area normalized and .

. in~egrated *to. give the. IAPD. The ordinate scale of. an IAPD ranges between 0 and L Through observation of the location of the

  • 5 value, a determina-tion can be inade if vibration of the core support barrel or other reactor internal is being impeded in peak to peak swing. Such early termination of peak to peak swing was seen in 1972 and was the result of the core.support'

.barrel contacting the snubbers. The IAPD is a backup surveillance to %- RMS.

Phase of Transfer Function A transfer function between two excore detectors is formed by taking the fourier transform of the time. domain data from one detector, dividing it by the fourier transform of the time domain data from the second detector and converting the results to polar coordinates.

'l 4

Coherence The co.herence function between two detactors describes the* "common causality" between the two detectors. Its value ranges between 0 and 1 and it is formed through. the following expression:

(Cc~{)°"' = (a.-:;: I .x.

6,,

  • Ga:i'l.

where:

- I<<.-

I~.<il. square of the magnitude of cross spectrum n--

_.,.,, - auto spec~rum of detector 1 C.-<<<- - auto spectrum of detector 2 Together with the phase, the coherence forms a.qualitative diagnostic tool in which quantification is achieved through the % RMS. The coherence displays those *frequencies that are common to two excore detectors and- the phase in_.

dicates whether the frequency is associated with vibration. Coherence and phase diagrams can be formulated with data from all combinations of excore detectors*and shifts of signature values in phase ot coherence are readily observed.

Normalized Power Spectral Density (NPSD)

The Normalized Power Spectral Density is formed through the following equation:

where:

Fi - Fourier t~ansfer of data from a detector F1*- Comple~ conjugate of fourier transfer N - Normalization .constant which includes a power and frequency normalization.

The usefulness of the NPSD is to monitor signature frequencies.

III' General Core Arrangement and Signal Conditioning

  • 5 Figure 1 shows the r~lationship of excore detectors to significant primary system items. The excore detectors NI-05, NI-06, NI-07 and NI-08 are located 0

approximately 45 from the hot legs. The cold legs of the reactor vessel.*

are approximately at.the same angular location as the excore detectors. A rough 9utline of the core is also shown in the figure. Current from the ex-:-

core detectors is brought through a current to voltage amplifier and then as shown in Figure 2, through a voltage amplifier, a filter and then to the fourier analyzer. The voltage amplifier is AC coupled so that only the fluctuating (noise) component.of the signal is amplified. The filters are used to bandpass the signal in range .025Hz to 25Hz. The fourier analyzer, HP5451B, is used to. perform all statistical .analysis on the noise component.

J!

Steam ~~1-J1C1t"tor n 11>--------

CORE

  • '----~ pressurizer pressure
  • ~team generator A :i)'*~--....__ _ __ _ ,

FIGURE 1 Jnsttumentallon locations for noise tests

  • Jl

+

Input to Low Pass High Pass Operational Buffered Fourier Filter Filter Amplifier Excore Det.ector Analyzer 24db/oct 24db/oct Nominal Gain Test Signal of 50 FIGURE 2 SCHEMATIC OF SIGNAL CONDITIONING EQUIPMENT

IV *. Sunnnary of Noise Analysis Results

  • 8 Presented below is a sunnnary of the surveillance results for the reporting peroid. These results are organized by surveillance technique.

% RMS Table 1 lists % RMS values for the frequency bands (l-3)Hz, (10-16)Hz and (16-20)Hz for all detector combinations. Representative results are listed from tests throughout the reporting period. It is seen that the alert limits of

  • 16 % RMS for the frequency band of (l-3)Hz and .11 % RMS for the frequency bands (10-16)Hz and (16-20)Hz have not been exceeded. The increase in % RMS for the (l-3)Hz band is an expected increase and is *associated with the de-
  • creasing b~ron concentration as a function of time or burnup as discussed in Reference 9.

TABLE 1

% RMS FOR DETECTOR COMBINATIONS FOR FREQUENCY BAND (l-3)Hz, (10-16)Hz, (16-20)Hz

.3/ 4/79 4/1/79 5/25/79 7/1/79 8/26/79 1 - l-3Hz 2 16Hz 3 20Hz

IAPD

  • 9 Figures 3, 4, 5 and 6 show the integral of the amplitude probability distri-bution for the month of August 1979; this is one month before the plant was shut down* for refueTing. As. stated before, the ordinates of the I.APDS are from 0 to 1. The abscissa is expressed in terms of millivolts. At 100%

power the excore detector is 8 volts averaged. On top of the 8 volts exists a millivolt noise component. This is what is measured by the fourier analyzer and why it.appears in.the IAPD. As can be seen from the figures,.when the IAPD has a .value of .5 on the ordinate scale, the abscissa is at 0 millivoits.

This. signifies that vibration is of sma11 e!lough.magn::f.tude that peak to peak motion is not being hindered.

Normalized Power Spectral Density (NPSD)

Figures 7 through 14 show a NPSD for each detector at three different times during core 3, i.e. May 31, 1978, February 19, 1979 and August 16, 1979.

These three dates correspond to 6%, 57% and 96% of core life respectively.

Through an observation of the NPSD (and the coherence discussed in the next section) the following frequencies and their postulated sources display a re.sonance.

1. .5Hz Thermal hydraulic oscillation
2. 2.3Hz Fuel bundle vibration
3. ll.25Hz Unknown
4. 14.75Hz Primary coolant pump blade frequency
5. 15.5Hz Shell.mode vibration of reactor vessel
6. 18Hz Core support barrel vibration
7. 23Hz Unknown This signature of frequencies has remained relatively constant throughout core 3. A change in this signature over a short period of time would be a strong indication of an anomaly, however this does not exist for core 3.

Table II lists the peak amplitude of each of the above frequencies.

  • TABLE II
  • 10 PEAK AMPLITUDE OF NPSD FOR DES.IGNATED FREQUENCIES NI-05 DATE .5Hz 2.3Hz ll.25Hz 14.75Hz 15.5Hz 18Hz 23Hz 5/31/78 -62 -75 .,.93 -77 -105 2/19/79 -58 -69 -93 ~85 -96 -103 8/16/79 -56 -63 -90 -83 -95 -103 NI-06 DATE . 5Hz 2. 3Hz 11. 25Hz 14. 75Hz 15. 5Hz 18Hz 23Hz
  • 5/31/78 -63 -75 -81 -87 2/ 19/79 -60 -69 -84 -88 8/16/79 .,...58 -63 -90 -84 .,...90 NI-07 DATE .SHz 2.3Hz 11.25Hz 14. 75Hz 15.5Hz 18Hz 23Hz 5/31/78. -63 -74 -91 -80 I -103 2/20/79 -61 -71 -90 -82 8/17/79 -59 -65 -89 -82 NI-08 DATE .5Hz 2.3Hz ll.25Hz 14.75Hz 15.5Hz 18Hz 23Hz 5/31/78 -62 -75 -78 -87 2/20/79 -58 -70 -85 8/17/79 -55 -65 -88 -84. -90 NOTE: All value in db blanks signify no resonance

Coherence & Phase

  • 11 Figures 15, 16 a.nd 17 present phase and coherence* diagrams for the months -

of May 1978, February 1979 and August 1979. The phase at a particular fre-

.quency and a given detector combination is given by a straight line for 0°

. . 0 0 .

phase and a sinusoidal line for a 180 phase. A 90 phase is composed of .

half a straight line and half a sinusoidal line. The coherence for the particular frequency and detector combination is written adjacent to the phase line. Significant points from the coherence and phase diagrams are listed below.

1. The .SHz frequency displays for all detector combinations and throughout 0

core life a 0 phase. High coherence is seen. across the hot legs whereas low, coherence is seen diagonally across the core.

2. The 2. 3Hz frequency displays for all detector combina.tions at beginning of core a 0° phase whereas later in core life vibration occurs in the direction of the hot legs. This frequency is believed to be fuel bundle vibration, Reference 10.
3. The 11. 25Hz frequency displays for all detector combinations and through-out core life a 0° phase.
4. The 18Hz frequency displays.throughout core life a vibration in the direction of the hot legs. This frequency is believed to be core support barrel vibration.
  • 12 V Conclusion The results from the surveillance methods presented in Section IV show no indication that anomalous or significant reactor internals vibration existed during the reporting period. The magnitude of the % R.J.~S values in the various frequency bands did not exceed alert or action limits. An inspection of the keys and plungers during the 1979 refueling outage showed no presence of wear which taken in conjunction with the noise analysis data conclusively shows that*the core barrel was tightly clamped during the reporting period and no other anomalous vibrations occurred.

fl 10 X 10 TO THE INCH* 7 X 10 INCHES KEUFFEL 6 ESSER CO. MADI IN U.S.A. 46 0702  ;---*

FIGURE 3 Integral Amplitude Probability Distribution (I~D) NI-05 8/16/79 *,.

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4

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  • I--*-*-- '--L--1-JH--1-1*-l 1-HH-t-t+++--t-t-l--l--IH-++-t-+-l--I- - ~ -*HH-*-~-+-1-++++--l-t--f-...lf-...l*- .._ L..:.... - l-.. - - - - - - - - - - - ' - _ _ _ _ ' - -* -~-----------1---------i-:---~- ~1---------

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1-1-t-t-t--t-++--t-t-l--IH-t--+++++-l-*I*-*-- -* ._:_f-*-- - - **-1-;-*-* - - - - - - 1---- - --- ------- --*- - __ .__ - - - -- -- - , _......., _ _ , _ , _ , _ _ , _

1--1--1--1-. - - --1-11-+-t-i-t--ll--<-

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-*f--tl-t-l--l--l-1

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- - --1-- -* -- * - -* *- - - - - -- - * -- -* -* -- -- -- l- - -* -* - -- - -*-t-*-+--11--l-i..-- -- -* - -* -- *- - --* **----:1--~ -----*~*-*-*-**-**-**-**-----L-- ---* - - - - - -- - * - - -- -* --* -- -- -- f-* --

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10 X 10 TO THE* INCH* 7 X 10 INCHES KEUFFEL &: ESSER CO. MADE I.. U.S:A. 46 0702 --

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FIGURE 5 INTEGRAL AMPLITUDE PROBABILITY DISTRIBUTION (IAPD) NI-07 8/17/79 1--1---l-lc-1-l--I-- - - '---1-HH-l-++--l

  • 1--f-Hf-l-f--+-f---l--++-*l-.f---f-lf-l-+-l---I- ~ - :.__ -* - .__ ._,_,_,__,__,___,___1-*1-1--1--~-f- __ ...._ _,_ J.- -~ - -f-t- ~ ;_ - t - - I.-- -l--f--1--1-- _...,_*-I-... - - - - ---~ -- --l-- -* - - - -
  • _,_,__,___,__,

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  • i - ~ i--- -* r---1--

+-+-l-HH-l-l-+-l--l-+++--l--l-l-l-ll-l-l-~-+- 1-1-il-l-l- - 1-- i--. 1-1-1.-1.-1.-1--1--1-1-1-ll-l-l--l---1-t- r-- _ --f-- -l--f--f--1---1--1-"- -~ - _ ~ ._ - -

  • _ _ -L-. -*-*t-t--1~t--+--1---1 1-1-+-1---I--'- -t-1---1--1--f---1--l--.f--l-I t-t-ll-t-t-+-+-r-t--t-+-l-l-IH-t-+++-l--l--l-*l-l-HHH-~-++-1--++-1--1-.1-1-1-11---l'---l1-1-1--t-+-1---1--+-1- ,_,_ _,__,___,__,_ ->-1-1-l---1----1- -i:-

1-4-+-1--l--l-~<--t-+-+-l--l--+--I-t-

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l-l-i'--l-f--1--f-.-+--t-+--*'-'-"'-'_._.._.__,__"_*t-i-'t--HH-t-~-+-l-++++-+-+-l-l-IH-l-l--++-l--+-l--l-l-l-l-l-.f-1.--1---+---1 -* ;-...,1-- - - - ,_ >-+--+- ====.

t--t-IH-t-+-++-t--t--l-l-H-t-~-+++++-+-l-HHH-1-l--+-+-l--+-l--1--1-l-l-1-11-1-t---l.+-1---L-L..L-L.l-Ll-1-+-+-f--l---l--l-*l-*I- f - - f-- - ,_._... - - ~ -t-+-+-l--+-+-+--1 __

-l-+-+-++-t-+-+-+-+-l-HH-l--l--+-+-l---l-+-+-+-l-1 1--+-1--1--1---1-1-11-l- - 1_.._ - - - -*->-1---1--1----1-- -l--+--1---t--1----1-.1- - _ _ _ _,____,___,_,_"1- --f-1-l-IH-t-J-.-f--l- _

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~ __ 1- ~L-  :'.'.'.'.:'.. _ ,_ _ r- __ * - 1- -r- _ _ _.._ - - =L-.. - - i -

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rt-HH-t-t-t--t-+-+-t-HHH-t-l-++++--l--t-t-HH-4-4-~+++++-+--+-l-l-l~-l--1-+---1---1--1-1H-t-1-11 ;I..< -t; i.-~ '--- - *- * - 1-<->-1*--+--1---1--t- i-1-1--l--1--1---+-+- -'--'--'---'-'-"t*- 1--t-rt-HH-t-t--t-+-t--t-+-t--'t-1-t-t-++++-+-+-+-l-HH-l-l--+-++++-1--1-.1-.1-1-11--1-1-++-1---L--1-==-ll l.t.i:, k:: . ._ i-- c- - -_*t-1_-1-_-t-._--l._H,-_+-_+,__-.+-t-IH-f-~-++++-+-l-HH-l--~-t-+++--l-l-l

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.5 H-t---rH-t--t-IH--t-t-t-r+-t--~-+--Hl-l----l--l-l-t-+-H-t-+-H-t-+-~-l--l-~-1--1-W-Li.--Uvl:' __ I.I °J- -- -* ... -l-+,.-l-f--l-l-f--l-t--1-1---1-*1-1 l-l-t--+--l--l-+- -~- '--

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1 I.... -- l=~ -**~--1---1--i-i-1H---

-f--+++++++-+-t-1-1-11-1-4-+-+'--1::~~++--+v-,1<q__1--_y_. l-l-t-+-l--1---1--1--1-*1-l-- -*l--l-t-l-!f-l'-l-1-+--l--1--1--1-+--1--1-l--I~- --- ._ _ -*- ---* - - - - - -~ *---

- ~ ,,, -~-++++-I-+-+- -*'-- _ , _ L 1 . . . . - 1-- _ L . . 1 _ -..- -

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-+-*-~--t--1--~-~ -- ----l--~--'-'--1--

. i-.L-.l-l-IH-l*--1---1--1

  • 1-1-11-t-f--l l--1--J- _1-. L - L - - f*- 1--t- 0 f- 1--l--~ -*~~+-f--1--l-*l--l-1-11-1-l--~-l--l---I- - -I-- L...... - - - - * -l--f--t--+--+--1----1--1---<-'-"1--1-*-1*-l-I- - --1-- ~ 1--* - --1 - ' - - -- -*-~-+-+-!- -*- - -- -- - - -- I - -- --- - . l--&-- '-- .._ - - *** l - 1 - k-. *-l-+-+-1----1--1 t-IHH-t-+-1-++++-~----t- -+-1--1--1--- -- --- ---1-l--lf-1-1-.--*- --1-., -* - - * - -* - ._,__ __ - - * - .. - - - - 1-**-1-*-1----1--* ***-1-----

-*-~-+++++-+-+-+-l-Hl-IH-l--~-++--1--1-+-*1-1-l-l-~-l-->-- - - - *-- _..:.. -l- - - l - - . 1- --~- -- - - _ _ _ -"'7' -r--* _ - _ -l- ____ ._. '"--1----.1- -t-1--1'-~-I-- - i - -~*

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1-l-tl--l-+-+-l--f--1-+--l---l-l.-i-+->--1----1--'--'- l-+-lc-+-l--l-l---HHH-t-+-+---l--!--l-.f---t-l-l~*-*-1*-1---+--1--- - - - .___ - -* - - - 1- - --l-l-J.-+-1-- - - - --* - - - -- *- - - -- _ _ 1--. -* -* __ * - _ _ _ - ..... - --1*- ---*f--

_.._ - * - - - -*-1--'---'---1*--l- -i.-. - t-- - -- _:. -l-l--l---l--l--1-+-*l-*t-1-11-1-*-+-1--1~ .1-- - _ . _ _ - * - - - - ~ - - -- - - - - - - - - - - f-- - r-- - - **-* - *-1--* -* - - - - -- - * ... -- - -- - .:.... *-* -* ~ * - * - - - - --i--

,_._ 1-l-l--+-l---f-+--l-*l-l-l-l-l-+-+-l--I- -l-f-~-~-f--l--Hrl-l-f--t-+-+--1-1-- -f---- - - f - - * *--1--~ - * - - * - * - ,-.. *--: - - - *-1---1--t---l-"t--t- --- *-- -- - -* - -*1- - - -- - .. ----~~-----~--------

1-1-+-f--f-.--l--t--I--- _._.___,____,___,_.._, __ - - - -t-~-l--l--l-1--!f-1-l-l--l--f--l---f--l-.-i.-- - - - ....:_ -*-:- - ~. -* -- - - - __ ,_ -  ! - -- - -* - - - --i-- - -f--1--* - 1-11-l---1--I----'----*-~--- -

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  • _I-- _ _ _

- * -- *-**- - - f - - - - - -~-~-f--l--1--1--1-.1-1-.WI-. _...___ -* - - - -+-!*-t--t---l---t---l-*l-'-*f--lf---l-l*-1--1- --..:...:..---: -* - - -*1- - - - -- - -- - -- - --* - - .. ,__. -- -** - -*- *- - --- - - - - -- - .

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-- ---1--- __ .._ -- ...:...1.- -L-. _...___.__ - -'---1-- -'- -r-:1-- *f-t--1-11--1-1-1-- - . _ 1-- I-- l-J.-1-- - - * -*'-* -* -- - - L - .___ - - - L - '-- -L... - t--* - * - - - - -- -- -* - --*I- - - - -- .*. - - *i--* - l-1-1--- ... -* --l-. - -- -* -* --- _ _

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t-*'-- --i--1---1-- --i-- - -- -* -- -- -- - - *-*-;- - L-. - l-1-L... - -r- t-- - *-l--*l- &-- --1 -* -- -- - -* *--l- ---L- - L- l.-. -- - .. -L-* - -- -* - - .*.* * - -* -*-**-**I---* - -- - ~ ..__ **'-- :_ *- L- - - - - * : __ - * -- ***t-- *.

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1--*l- - - t-1--1--* -* -- -- *- -*-1--* -* **- -***- - *--*-**---*-- - : - I - - - -*-'---- *- - - - : * - - * - - - - - - - - -*-*****-- *-* -- - -- -* - - - -* -* --- -- -- :-~- --*t -- - -

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_ -_-.l___.L___LLJ._1:._j__l_J__J__J_*j-_***l-_-J-._-J_,__L_...L_..L__J___l ___J___.J____J___J_L_J__..l._*-L-*L*L*_-L..J_L_J __-1*-_l*-_-L--1*--_1__*--J_**-J_--*L*-*1*_**L-J*L--J_- ,_...__..__...._,'-'--'*-'l-1-....L...L- ~ .._...___ - ..___,_

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10 X. 10 TO THE INCH* 7 x 10 INC:HF.S KEUFFEL 8i ESSER CO. MAr1F IN u S.A 46 0702 FIGURE 6 INTEGRAL AMPLITUDE PROBABILITY DISTRIBUTION (IAPD) NI-08 8/17/79

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HH*-+-+--+-t--1--1--1-1-1--1--1-++-+--I - ,- 1-1-~1--t-+*-l--l--l-+--l-l-+-l---+-l---l--l-+-*l-1--1---t--1-11 - ...-- -* -* -*->-* *- - - -f- 1 - - - - - - - - i-- -- - - -* -* - 1- - - . _ , _ , _ , .... , *......_... 1-- -* - - - i - - **- *- * - -

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10 X 10 TO THE INCH* 7 >< 10 INCHES*

KEUF'F'EL a ESSER CO. MADI IN U.S.A. .46 0702 FIGURE 9 NORMALIZED .POWER SPECTRAL DENSITY (NPSD) NI-05 & NI-06 2/19/79'.

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  • FIGURE 10 NORMALIZED POWER SPECTRAL DENSITY (NPSD) NI-05 & NI-06 8/16/79

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\' .t; 25 FIGURE 15 COHERENCE AND PHASE DIAGRAf1S MAY 1978 B

.SHz 2.3Hz A A B

l li. 25Hz 14.8Hz A A B

5 15.5Hz 18Hz 7

A

A---

~* 18.0° Phase Legend : -~_/'"'..~,......~,

0° Phase 5i6,7,8 Excore Detectors A,B Hot Legs Steam Generator

  • FIGURE 16 COHERENCE AND PHASE DIAGRAMS 26
  • FEBRUARY 19 7 9 B

.SHz 2.3Hz A

B l

11. 25Hz 14.8Hz 6 ].

A A 8

B I

B 5

J 15.SHz 18Hz A A Legend: ~ 180° Phase o0 Phase 5,6,7,8 E~core Detectors.

A,B Hot Legs Steam Generator

  • FIGURE 17 COHERENCE AND PHASE DIAGRAMS 27 AUGUST 1979

.5Hz 2.3Hz A A gradually.. broadens B

over core life

11. 25Hz 14.8Hz I

6 7 A A B B I

8 5

\

15.5Hz *j I

18Hz

  • 6 6 7 A A Legend: ~180° Phase o0 Phas.e 5,6,7,8 . Excore Detectors A,B Hot Legs Steam Generator

T

\'

REFERENCES

1. Palisades Plant Technical Specifications, Section 4.13.
2. Letter, DPHoffman (CPCo) to Director of Nuclear Reactor Regulation (NRC),

"Proposed Change to Technical Specifications - Reactor Internals Vibration Monitoring", October 25, 1977.

3. Letter, DPHoffman (CPCo) to Director of Nuclear Reactor Regulation (NRC),

"Reactor Noise Monitoring Proposed Technical Specifications Change",

March 23, 1978.

4. Letter, DLZiemann (NRC) to DABixel (CPCo), January 19, 1979.
5. Letter, DMKennedy to JAMeincke, "Palisades Plant - Reactor Internals Vibration Monitoring M and N Sigma Limits", May 14, 1979.
6. "Calculation of the Scale Factor for Inference of Pressurized Water Reactor Core Barrel Motion from Neutron Noise Spectral Density", Nuclear Technology, Vol. 40, mid August 1978.
7. "Quantification of Core Barrel Motion Using an Analytically Derived Scale.

Factor and Statistical Reactor Noise Descriptors", Nuclear Technology,-

Vol. 40, mid August 1978.

8. Reactor Noise by Joseph Thie, Rowman and Littlefield Inc. 1963.
9. Reactor Internals Noise Monitoring Tests, January 1978 (Submitted on April 27, 1978).

10.* XN-74-33, Summary of Mechanical Tests of Palisades Fuel Bundle and Component Parts, September 3, 1974.

.,  :* ..~~ .:* ~

To lid)( . Rd' das

( DMKennedy, Palisades FROM consumers DATE May 14, 1979 Power company SuB.JECT PALISADES PLANT -

REACTOR INTERNALS VIBRATION INTERNAL MONITORING M AND N SIGMA LIMITS CORRESPONDENCE cc On October 25, 1977, Consumers Power submitted to the NRC a request for a Technical Specification Change to Reactor Internals Vibration Monitoring which thereafter was*approved by the NRC. The new Technical Specifications allow frequency dependence of the M and N Sigma limits and the purpose of this memo i~ .to s*tate the new limits and .their associated frequency bands. -

From a review of Core 3 noise data, it was determined at meeting held at Palisades on February 16, 1979, attended by JAMeincke, KDBrienzo and DMKennedy, that three frequency bands show high coherence and a phase shift of 180°.

These bands are:

f I

\. 1-3 Hz 10-16 Hz 16-20 Hz . -.

The M and N Sigma limits for these bands were discussed and it was decided to assign different limits to the 1-3 Hz band and the higher frequency bands.

The different limits are due to the different manners in which the core support barrel can vibrate. In the 1-3 Hz region, core support barrel movement is believed to consist of a rocking motion in which the core support b~rrel flange slides back and forth against the vessel support. At the higher frequencies core support barrel movement is believed to be a cantilever beam vibration_-fn' which the core support barrel is secured at the top,..and oscillates .a,l: the.

bottom.* With reference to the attache.d recent publication*"Calculation of the Scale Factor for Inference of Pressurized Water Reactor Core Barrei Motion From Neutron Noise Spectral Density Nuclear Technology Vol. 40 mid August 1978, M and N Sigma levels were calculated to be:

FREQUENCY BAND M SIGMA N SIGMA '.

1~3 Hz .16% .24%

10-16 Hz .11% .16%

16:..20 Hz .11% .16%

  • Attachment deleted

~

,. JAMeiri.cke Page 2 PALISADES PLANT -

  • - REACTOR INTERNALS VIBRATION c MONITORING M AND N SIGMA LIMITS May 14; 1979 These limits were obtained using a scale factor of .01%/~il and crest factor of. 3 for the M Sigma limit and a crest factor of 2 for the N Sigma limit.

Derivation of these results can be found on the attached engineering wo~k sheet. Nom{nal clearance of the core barrel from the vessel was taken from a Combustion Engineering Report CEN - 5 (P) March 1, 1974, which states, "Lateral movement of the core support barrel is limited to 20 mils cold (24 mils at reactor operating conditions) in any direction by six stainless steel snubbers welded to the core support barrel reacting against six Inconnel stabilizing lugs attached to the reactor vessel wall".

Typical baseline values for % RMS in the designated frequency bands are:

1-3 Hz - .057%

10-16 Hz - .007%

16-20 Hz - .002%

These values, as can be seen, are well below their respective-M Sigma limits given above and this indicates.that undue core barrel motion does not exist at i:he present time. This fact .is further supported by Combustion Engineering Report CE 2966-RCE-408, which concludes that based on the results of the January 1978 visual and dimensional inspections no evidence of movement or harmful vibrations of the internals exist.

( In establishing M and N Sigma limits, it is important to have realistic numbers such that core barrel motion is recognized and damage to* the core does not occur, yet, not have numbers which require action when action is not ne~essary. The numbers chosen above are felt to meet both these criteria.

  • CONSUMERS POWER COMPANY Nuclear Plant ENGINEERING ANALYSIS WORKSHEET

Sheet /

- - -of- i-_ -

c

References:

Review Method bY,: Alternate Cales c:J

,J-4 c. ,1. .e. ,..-~--~-t:-C'_N'_"'.,...6-,-"-f'--y-.-.- - Detailed Review is:zJ Qualification test c::J f!~/11 Date

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