ML17158A594
| ML17158A594 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/30/1995 |
| From: | Poslusny C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9504050263 | |
| Download: ML17158A594 (49) | |
Text
R500 Wp0 Cy C00 IVl
++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 Harch 30, 1995 LICENSEE:
Pennsylvania Power and Light Company FACILITY:
Susquehanna Steam Electric Station, Units 1 and 2
SUBJECT:
SUMMARY
OF FEBRUARY 21, 1995 MEETING On February 21,
- 1995, NRC and Pennsylvania Power
& Light Company (PP&L) staff met in Rockville, Maryland, to discuss the status of the licensee's evaluation of the cause and effects of the vibration/noise event that occurred in June 1994 during startup testing of Susquehanna Steam Electric Station (SSES) Unit 2.
Enclosure 1 is a list of those who attended the meeting.
Enclosure 2 is the set of slides addressed by PP&L during the presentation.
The meeting included a review of the June 1994 event which occurred after the reactor recirculation (RR) pumps'peeds had been increased to 1571 rpm and 1582 rpm (core flow at approximately 108 Mlb/hr).
The normal core flow is usually maintained at about 100 Mlb/hr.
The normal operating noise level had increased and some vibration was identified in the containment instrument gas line outside containment and in the suppression pool hatch covers.
The vibration and noise was attributed to vane passing phenomenon induced by the RR pumps'peeds.
PP&L then discussed followup actions.
Specifically, after the event, an administrative control was implemented to limit the RR pumps'peed to, 1515 rpm (103 Mlb/hr core flow).
Then tests on Unit 2 were conducted in December 1994 to gather additional data to support further analysis of the root cause and effects of the event.
The tests involved incremental increases in RR pump
- speed, matched and mismatched with speed held at each level for data collection and observation of effects.
PP&L, with support from GE Nuclear, completed analysis of the data collected during the June and December tests and determined that the RR system piping and attached residual heat removal (RHR) system piping have resonant modes in the 120 to 140 Hz range.
Further conditions exist for a hydraulic resonance at the junction of the RHR and RR systems.
Also, the containment has potential resonant modes in the 120 to 140 Hz range.
The test results revealed that (1) the RHR/LPCI (low pressure core injection) injection line is the primary source of the noise, (2) the suppression pool hatches are the secondary source of the noise, (3) the noise is present at low core flows but is not normally easily noticeable by the ear, (4) a containment resonant mode exists at 129 Hz, (5) accelerations and displacements are very
- small, and (6) the resulting pipe and containment stresses are negligible.
Most importantly, the root cause was attributed to vane passing pulses being amplified by hydraulic and mechanical mechanisms in the RHR/LPCI injection line and by mechanical vibration in the suppression pool hatches.
9504050263 950330 't POR ADOCK 0500038>'OR
(
O5oog Jc nIIe HI.L C~ER CIIPV~f I
\\'I
~
gL J
t
Although PPKL concluded that this vane passing phenomenon-induced noise and vibration was benign in its overall effect in the identified systems, the licensee indicated that it still plans to collect data on the RHR piping inside containment in Unit 1.
Specifically, accelerometers will be installed inside containment(Enclosure
- 3) in April during the refueling outage of the unit.
A test similar to that conducted in December 1994 on Unit 2 will be conducted on Unit 1 in May 1995 and additional data will be collected.
Subsequently, PP&L will analyze the data and correlate it with that gathered during the Unit 2 test.
Then based on the results of the data, the plant operating restrictions will be revised or eliminated.
The results of this analysis is expected to be provided to the NRC in July.
The staff reacted favorably to the information provided during the meeting and indicated that it had no immediate safety concerns regarding the cause and effects of the vibration and noise phenomenon.
The staff indicated that it would like to visit the site while the tests are being conducted on Unit 1.
/s/
Chester
- Poslusny, Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-387/388
Enclosures:
As stated cc w/encls:
See next page DISTRIBUTION w/encl 1
RZimmer man CWu SVarga PChen JZwolinski JStolz HO'Brien OGC EJordan HAshar RFrahm HRubin KManoly ACRS(4)
WDean U~IS RIBUTIUN T
11 Docket File PUBLIC PDI-2 Reading
- JWhite, RGN-I CPoslusny OFFICE NAME DATE PDI-2 LA O'Br>en ~"
95 PDI-2 PH CPoslusny 95 P
2 D
JStolz 95 OFFICIAL RECORD COPY DOCUMENT NAME:
SU2-21.MTS
y c4.
~
E~
Although PPLL concluded that this vane passing phenomenon-induced noise and vibration was benign in its overall effect in the identified systems, the licensee indicated that it still plans to collect data on the RHR piping inside containment in Unit 1.
Specifically, accelerometers will be installed inside containment(Enclosure
- 3) in April during the refueling outage of the unit.
A test similar to that conducted in December 1994 on Unit 2 will be conducted on Unit 1 in May 1995 and additional data will be collected.
Subsequently, PP8L will analyze the data and correlate it with that gathered during the Unit 2 test.
Then based on the results of the data, the plant operating restrictions will be revised or eliminated.
The results of this analysis is expected to be provided to the NRC in July.
The staff reacted favorably to the information provided during the meeting and indicated that it had no immediate safety concerns regarding the cause and effects of the vibration and noise phenomenon.
The staff indicated that it would like to visit the site while the tests are being conducted on Unit 1.
Docket Nos.
50-387/388
Enclosures:
As stated cc w/encls:
See next page Chester
- Poslusny, roject Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Pennsylvania Power
& Light Company Susquehanna Steam Electric Station, Units 1
8 2
cc:
Jay Silberg, Esq.
- Shaw, Pittman, Potts L Trowbridge 2300 N Street N.W.
Washington, D.C.
20037 Bryan A. Snapp, Esq.
Assistant Corporate Counsel Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Hr. J.
H. Kenny Licensing Group Supervisor Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Hrs. Maitri Banerjee Senior Resident Inspector U. S. Nuclear Regulatory Commission P.O.
Box 35 Berwick, Pennsylvania 18603-0035 Hr. William P. Dornsife, Director Bureau of Radiation Protection Pennsylvania Department of Environmental Resources P. 0.
Box 8469 Harrisburg, Pennsylvania 17105-8469 Hr. Jesse C. Tilton, III Allegheny Elec. Cooperative, Inc.
212 Locust Street P.O.
Box 1266 Harrisburg, Pennsylvania 17108-1266 Chairman Board of Supervisors 738 East Third Street
- Berwick, PA 18603 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. Harold G. Stanley Superintendent of Plant Susquehanna Steam Electric Station Pennsylvania Power and Light Company Box 467 Berwick, Pennsylvania 18603 Hr. Herbert D. Woodeshick Special Office of the President Pennsylvania Power and Light Company Rural Route 1,
Box 1797 Berwick, Pennsylvania 18603 George T. Jones Manager-Engineering Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Hr. Robert-G.
Byram Senior Vice President-Nuclear Pennsylvania Power 8 Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803
LIST OF ATTENDEES NRC MEETING WITH PP&L FEBRU Y 21 1995 C. Poslusny H. Ashar R.
Frahm M. Rubin K. Manoly C.
Wu P.
Chen J. Refling C. Dvorscak J. Vernarr R. Sgarro J. Bartos W.
Wang T. Madden P. Tutton ORGANIZATION NRC/NRR NRC/NRR NRC/NRR NRC/NRR NRC/NRR NRC/NRR NRC/NRR PP&L PP&L PP&L PP&L PP&L S&W SWEC PECO Energy ENCLOSURE I
usque anna nit 2 ontainment oise Investigation nit 2 Test Resu ts John A Bartos February 21, 1995
Presentation ut ine
+ Review June 1994 Noise Event
+ Investigation Status
+Unit 2 Test Results
+ Conclusions
+ Revised Action Plan
+Schedule
ant on itions Durin ontainlnent Noise Event
+Reactor at 920/o ofuprated power.
+Recirc. pump A at 1571 rpm.
+Recirc. pump B at 1582 rpm.
+Core flow at 108 Mlb/Hr.
+Increased core flowtests complete.
servations ant uringt e ontainment Noise Event
+Allinstalled plant instrumentation indicated
~
normal readings.
+ Recirculation pump vibration readings showed no unusual increases.
+ Hatch cover to the wetwell air space, was observed to be vibrating.
+Reports ofsome small pipes vibrating more than normal.
ctions to E iminate Noise
+ Recirculation pump speeds individually reduced to 1515 rpm.
+ Pump A reduced first.
Magnitude ofnoise reduced.
Beat frequency increased to 6 Hz.
+ Pump B speed reduction eliminated noise.
+ Core flow at 103 Mlb/Hr.
ontainment oise
+ Loud audible sound in reactor building.
+ Noise appears to originate in containment.
+ Noise Characteristics Steady rhythmic noise.
131 Hz base frequency.
1 Hz beat frequency.
+ Coincident with recirculation pump vane passing frequency.
Investigation tatus
+ Analysis Results Recirculation system piping and attached RHR piping have resonant modes in the 120 to 140 Hz. range.
Conditions exist for a hydraulic resonance at the junction ofthe RHR and Recirculation Systems.
The containment has potential resonant modes in the 120 to 140 Hz range.
+ Test Results Provided confirmation of analysis findings, confirmed analytical root cause, and established that the resulting stresses are benign..
k8
Monitore Parameters
+ Reactor Building Noise General ambient Adjacent to RHR injection line
+ Containment Vibration
+ Wetwell Hatch Vibration
+ RHR Injection Line Vibration
+ Recirculation Pump Vibration
+ Loose Parts Monitoring System
Test on itions
+ Reactor at 100% ofuprated power.
+ Recirculation pump speeds from 1442 rpm to 1592 rpm.
+ Core flows from 100 Mlb/hrto 107.7 Mlb/hr.
+ 240 days of continuous power operation.
+ Test performed on December 5 to 12.
Unit 2 Test Resu ts
+ RHR/LPCI injection line is the primary source of noise.
+ Wetwell hatches are secondary source.
+ The noise is present at low core flows but can not be distinguished by the ear.
+ A containment resonant mode exists at 129 Hz.
+ Accelerations and displacements are very small.
+ Pump speed mismatch has no noticeable effect.
+ The resulting pipe and containment stresses are negligible.
Reactor Bui ing Noise Elevation 646'0 70 60 50 40 Cl 30-20 10-0 101 102 103 104 105 106 107 108 Core Flow - Mlb/hr
Reactor Bui ing Noise Elevation 670'00 90 80-70-60 Kl 50 40 30-20-10-g <<<<<<<<ge <<<<<<H <<<<<<<<<>>>>>g 101 102 103 104 105 Core Flow - Mlb/hr 106 107 108
Reactor Bui
'ing Noise Elevation 683'0 a a a e
a g a
a 70 60--
50
[Xi Q
40-30-20-10-0 101 102 103 104 105 Core Flow - Mlb/hr 106 107 108
Reactor Bui ing Noise Elevation 719'0 80 70 60-50 40 30 20 10 101 102 103 104 105 106 107 108 Core Flow - Mlb/hr
Reactor Bui
'111g oise Elevation 749'0 80
- -'--- - - - - -"- -- m- --
70 60-50 40 30 20 10 0
101 102 103 104 105 Care Flow - Mlb/hr 106 107 108
Reactor Bui ing Noise Noise Adjacent to RHR Injection Lines 100-90-80
~
70-60-50-E 40-30-20-10-100 102 Line B I
104 106 108 Core Flaw - Mlb/hr
RB12 'B'OOP NOISE DATA tKAR 15B 188 MIC-15B ~
MICROPHONE tKSR %% 15B VA VE jp:
SPECTRLN DISPLFK 85-DEC~
17: 43 DB
~
B7.62 LOAD ~ 1%.8 RPM ~
1465'PS
~
24.42 888 1288 1688 2888 FREQLENCY IN HZ Machine:
Meas. Point:
Date/Time:
Data Label:
LABEL: BASELINE DATA FOR TP-264~1 LIST OF SPECTRAL PEAKS (RB12) 'B'OOP NOISE DATA NEAR 15B MIC-15B
-P05 MICROPHONE NEAR RHR 15B VALVE 05-DEC-94 17:43:23 Amplitude Units:
PASCALS BASELINE DATA FOR TP-264-021 dB PEAK NO.
1 2
3 4
5 6
7
- W8 9
10 FREQUENCY (Hz)
- 16. 10 24.33 35.51 41.72 60.01 82.51 105.38 122.81 138.95 148.73 PEAK VALUE
- 76. 94 76.32 67 F 81 68.46 71.71 62.45 64.55 84.66 69.64 64 '2 ORDER VALUE
.66 1.00 1.45 1.71 2.46 3.38 4.32
- 5. 03
- 5. 69
- 6. 09 PEAK NO.
11 12 13 14 15 16 17 18 19 20 FREQUENCY (Hz) 164. 02 220.35 245.16 270.44 310.74 367 '8 426.60 447.93 507.37 639.25 PEAK VALUE 65'5 66.58 75'6 67.63 66.09 66.96 62.03 62.05 62.02 63.07 ORDER VALUE 6'2 9.02 10.04 11 08 12.73 15.05 17.47 18.35 20.78 26 18 TOTAL MAG 87.62 SUBSYNCHRONOUS 71.93
/
34 SYNCHRONOUS 86.21
/ 724 NONSYNCHRONOUS 81.61
/
25%
RB12 'B'OOP NOISE DATA NJ% 15B 118 VIC-15B
-P85 VICROPHOm~ an 15B Va VC SPECTRlN DISPLAY 13-DEC~
16: 58 DB
~
97.84 LOAD ~ 188.8 RPN
~
1598~a RPS
~
26.58 888 1288 1688 2888 FREQUENCY IN HZ LABEL: TP-264~1 STEP 7. 1. 117 LIST OF SPECTRAL PEAKS Machine:
(RB12) 'B'OOP NOISE DATA NEAR 15B Meas.
Point,:
MIC-15B
-P05 )
MICROPHONE NEAR RHR 15B VALVE Date/Time:
13-DEC-94 16:58:20 Amplitude Units:
PASCALS dB Data Label:
TP-264-021 STEP 7.1.11 PEAK NO 1
2 3
4 5
6 7
8 9
FREQUENCY (Hz) 16.72 23.68
'38.94 42.61 59.86 105.50 114 '4 132.48 160.78 PEAK VALUE ORDER VALUE
.63
.89 1'7 1.61 2.26 3.98 4'1 5.00 77.66 68.44 69.69 70.36 73 '1 73.64 66.36 97.56 69'8 6.07 PEAK NO.
10 11 12 13 14 15 16 17 FREQUENCY (Hz) 219 '1 264.63 273 92 279.77 291.47 310.47 397.72 423.71 PEAK VALUE
- 66. 17 74.51 67.72 66.68 69.11 67.61 72.30 66.14 ORDER VALUE 8'9 9'9 10.34 10.56 11.00 11.72 15.01 15.99 TOTAL MAG 97.84 SUBSYNCHRONOUS 76 96
/
14 SYNCHRONOUS 97.64
/
96%
NONSYNCHRONOUS 83.40
/
44
I n'ection ine Vi ration Vibration at 15A Valve 0.7 0.6 0.5--
Horizontal 0.4-
+ 03-Axial 0.2 0.1 100 101 102 103 104 105 106 107 108 Core Flow - Mlb/hr
ontainment Vi ration Elevation 670'.025
~
0.02--
/
0.015 --
/
./
0.01
/=
0.008 W
g-101 102 103 104 105 106
- 107, 108 Core Flow - Mlb/hr
ontainment Vi ration Elevation 683'.04-0.03-tO 0.02-0.015 P--
/ Q-.
/
e
/ r Q.
l gg x-~
0.01.~-~ ~
~~
X 0.005 101 102 103 104 105 106 Core Flow - INlb/hr I
107 108
ontainment '
ration Elevation 719'.1 0.09 0.08 0.07 0.06 0.05 V) 0.04 0.03 0.02 0.01 0
101 102 103 104 105 106 107 Core Flow - Mlblhr 108
ontainment ration Elevation 749'.035 0.03--
0.025 --
g 0.02-0.015--
Q g
Q, Q
0.01--
0.005--
101 102 103 104 105 106 107 108 Core Flow - Mlblhr
- 8. 883 I
C9 X
M
- 8. 882 RB12 LNIT 2 CONTAIttKNT VIB/f%ISE CONT U2 -V13 VIB 13 678'EHIND 2C246 SPECTRA DISPLAY 8S-DEC~
15: 19 PK
~
. 8876 LOAD ~ 1N.8 RR1 1462.~
~
24.37
- 8. 881 288 388 FREQUENCY IN HZ Machine:
Meas. Point:
Date/Time:
Data Label:
LABEL: BASELINE DATA FOR TP-264~1 LEST OF SPECTRAL PEAKS (RB12)
UNIT 2 CONTAINMENT VZB/NOISE CONT U2 -V13 )
VZB 13 670'EHIND 2C246
'5-DEC-94 15:19:24 Amplitude Units:
G-S PK BASELINE DATA FOR TP-264-02 PEAK NO.
1 2
m&3 4
5 6
7 8
9 10 FREQUENCY (Hz) 97.34 120 '4 122.44 124.83 170.54 183.59 184.52 185.13 186.40 188.28 PEAK VALUE 2.61E-04 3 '5E-04
.0023 2 '3E-04 3.38E-04 2.79E-04
- 3. 04E-04 3.21E-04
.0005
.0008 ORDER VALUE 3.99 4.93 5.02 5.12 7.00 7.53 7.57 7.60 7.65 7.73 PEAK NO.
11 12 13 14 15 16 17 18 19 20 FREQUENCY (Hz) 189 '1 189 '0 191.40 193.30 194.52 197.63 198.58 348.59 365.53 367 '4 PEAK VALUE
.0016
.0020
.0011
~ 0017
.0034
.0006
.0005 2.65E-04
.0009 3.34E-04 ORDER VALUE F 77 7.79 7.86 7.93 7.98 8'1 8 15 14 31
- 15. 00
- 15. 08 TOTAL MAG
. 0076 SUBSYNCHRONOUS
.0018
/
54'YNCHRONOUS
.0035
/ 214 NONSYNCHRONOUS
.0065
/ 744
- 8. 812 I
CD Z
M RB12 LNIT 2 CONTAI~ VIB/NOISE CONT U2 -V13 VIB 13 678'EHIND 2C246 SPECTRLN DISPLAY 13-DEC-94 17: 34 PK
~
.8142 LOAD ~ 188.8 RPf1
~
1598. ~
~
26.58 8.888
- 8. 884 LABEL: TP-264~1 STEP: 7. 1. 117 LIST OF SPECTRAL PEAKS Machine:
(RB12)
UNIT 2 CONTAINMENT VZB/NOISE Meas. Point:
CONT U2 -V13 )
VIB 13 670'EHIND 2C246"=
Date/Time:
13-DEC-94 17:34:33 Amplitude Units:
G-S PK Data Label:
TP-264-021 STEP:
7.1.117 PEAK NO.
1 2
4 5
6 7
8 9
10 FREQUENCY (Hz) 130. 13 131.06 132.31 133.59 134.22 158.58 185.11 186.40 189.51 191.40 PEAK VALUE 4.16E-04 4.20E-04
.0113
. 0006
.0006
.0006
.0009
.0009
.0022
.0006 ORDER VALUE 4'1 4.95 4.99
- 5. 04
- 5. 06 5.98 6.99 7.03 7.15 7'2 PEAK NO.
11 12 13 14 15 16 17 18 19 20 FREQUENCY (Hz) 191. 73 193.58 195.19 196.67 198 28 345 49 348.31 349.50 396.53 397.43 PEAK VALUE
.0006
.0010
.0036
~ 0013
.0006 4.01E-04 4.73E-04 4.17E-04
.0005
.0005 ORDER VALUE 7.24 7'0 7.37 7.42 7 48
- 13. 04
- 13. 14
- 13. 19
- 14. 96 15 00 TOTAL MAG SUB SYNCHRONOUS
. 0142
.0006
/
0%
SYNCHRONOUS
.0115
/
65%
NONSYNCHRONOUS
.0084
/
35%
etwe Hate Res onse Wetwell Hatch "A" 0.5-0.45 0.4 0.35 0.3-
~ 0.25 0.2-0.15 0.1 0.05 Hatch Center Hatch Edge a
w w &
w a
a
% a a
e a
e w e a Q.
a ag 101 102 103 104 105 Core Flow-Mlb/hr 106 107 108
etwe Hate Res onse Wetwell Hatch "B" 0.6 0.5 0.4-Hatch Center 0.2 0.1 Hatch Edge e
e 0
a e
a e
a a
a Cl e
e 101 102 103 104 105 106 107 108 Core Flow - INlb/hr
RB12 LAIT 2 CONTAIRKNT VIB8%ISE 8 CONT U2 -V89 VIB 9 683'ET INLY $%TCH iB'PECTRlN DISPLAY 13-DEC~
17: 26 8.7 8.6 M
K 2:
8.5
. 6363 LOAD ~ 188.8 RPN
~ 1598.~
~
26.58 8.4 8.3 4
f}.
- 8. 2
~
~
8.1 8
~
188 LABEL: TP-264~1 STEP: 7. 1. 117 LIST OF SPECTRAL PEAKS Machine:
(RB12)
UNIT 2 CONTAINMENT VIB/NOISE Meas. Point:
CONT - U2 -V09 )
VIB 9 683'ET WELL HATCH -
'B'ate/Time:
13-DEC-94 17:26:26 Amplitude Units:
MILS P-P Data Label:
TP-264-021 STEP: 7.1.117 PEAK NO.
1 2
3 4
~~ 5 6
7 8
9 10 FREQUENCY (Hz) 103.95 127.35 129.53 130'6 132.25 133.92 135.12 136.09 138 '1 140 18 PEAK VALUE
. 0045
.0056
.0180
.0262
.6062
.0397
.0264
.0168
.0058
.0048 ORDER VALUE 3.92 4'1 4.89 4'2 4.99 5.05 5'0 5.14 5.23 5'9 TOTAL MAG SUBSYNCHRONOUS
.6363
.0128
/
04 SYNCHRONOUS
.5841
/ 844 NONSYNCHRONOUS
.2521
/ 164
RB12 i%IT 2 CONTAIRKNT VIE4%ISE CONT 02~
VIB 9R 6B3'KT I'LL f&TCH EDGE SPECTRAL DISPLAY 13-DEC~
17: 27
- 8. 816 V)
MKz
- 8. 812 6)
N Ih
. 8378 LOAD ~ iM.8 RR1
~ 1598~
~
26.58 A
- 8. 884 LABEL: TP-264~1 STEP: 7. 1. 117 Machine:
(RB12)
UNIT 2 CONTAINMENT VIB/NOISE Meas. Point:
CONT - U2 -09A VIB 9A 683'ET WELL HATCH EDGE Date/Time:
13-DEC-94 17:27:46 Amplitude Units:
MILS P-P Data Label:
TP-264-021 STEP: 7.1.117 PEAK NO.
1 2
3 5
6 7
8 9
10 FREQUENCY (Hz)
- 10. 21 11.14 12.38 14.83 15.16 17.71 18'1 19.55 21.39 22.96 PEAK VALUE
.0070
.0056
.0053
.0160
.0150
.0048
.0050
.0036
.0030
.0032 ORDER VALUE
.39
.42
.47
.56
.57
.67
.71
.74
.81
.87 PEAK NO 11 12 13 14 15 16 17 18 19
'~20 FREQUENCY (Hz) 24 22 25 21 26.42 28.00 29.92
- 31. 40 49.86 51.41 53.26 132.45 PEAK VALUE
.0026
.0065
.0068
.0027
.0064
.0020
.0020
.0027
.0029
.0142 ORDER VALUE
.91
.95 1.00 1.06 1.13 1.18 1.88 1.94 2.01 5.00 TOTAL MAG
.0378 SUBSYNCHRONOUS
.0307
/ 664 SYNCHRONOUS
.0168
/ 204 NONSYNCHRONOUS 0142
/ 144
easure cce erations an Dis acements
+ Containment structural measurements are very small Accelerations <.1 g Displacements < 1 mil
+ Resulting stresses are negligible.
+ Wetwell hatch motion is greater but results in small stress increases.
ecirc. Pum ee ismatc E
ects
+No effect on perceived sound magnitude.
+No noticeable change in recorded d t trends.
+Change in beat frequency.
eoirc.
um ee ismato E
ects Containment Vibration - Elevation 683'est Point V08 0.0140 0.0120 0.0100 --
0.0080-0 0.0060 0.0040 0.0020 0.0000 r
rf p
< 2%
99 100 101 102 103 104 105 106 107 108 Core Flow - Nllblhr
Recirc.
um ee ismatc E
ects Noise Adjacent to RHR Injection Line A 100 98 -.
96.-
2%
0%
m 92-90-88 86 84 82 101 102 103 104 105 1%
106 107 108 Core Flow - Illb/hr
easure E
ects Insi e ontainment
+No noticeable changes in measured. process variables.
+ Small but acceptable increase in pump vibration.
+ Small increases in Loose Parts Monitoring System sensor readings.
Recircu ation Pump i ration RRP A, Pump Bawl Acceleration 0.34 0.32 0.3.-
0.28 0.26 a
~
~ ~
ga X~<<0/
0 g
""X 4-.--
.e-1'P 2']o 0.24 0.22 0.2 99 100 101 102 103 104 105 106 107 108 Core Flow - Mlb/hr
ecircu ation um uction Line' Loose Parts Accelerometer Readings 0.014 0.012-0.01-0.008
+
0.006 Loop Loop A 0.004 0.002 101 102 103 104 105 106 107 108 Core Flow - Nllb/hr
Root ause Base on Unit 2 Test
+Vane passing pulses are being amplified by hydraulic and mechanical mechanisms in the RHR/LPCI injection line and by mechanical vibration in the wetwell hatches.
t er oncusions romt e Unit 2 Test
+Allmeasured parameters are in acceptable ranges.
+ Calculated stresses based on test data range from negligible to small.
+ Data indicates that the noise is benign.
+ Additional information willbe collected on the RHR/LPCI injection line inside of containment to verify calculated stresses.
ontainment oise ction an Revise
+ Install additional accelerometers in containment on Unit 1.
+ Perform a test on Unit 1 similar to the Unit 2 test and take data.
+ Analyze the Unit 1 data and correlate findings to the Unit 2 test.
+ Revise or eliminate plant operating restrictions.
+ Keep NRC informed.
Action P an Target Dates Date
+ NRC Status Meeting
+ Complete Test Unit 1 Instrument Installation
+ Perform Unit 1 Noise Test
+ Complete Analysis ofTest Results 02/21/95 04/30/95 05/17/95 06/30/95
+ Inform NRC ofAnalysis 07/10/95 Results
Enclosure 3