Vol 6, Vibration Aging Procedure, to Qualification Plan for Qualification of Edgs 64546 for Application in Comm Ed LaSalle County Station Div 3. Actual Procedure Number: 02-6073-011-QP-(2)-V6-(2)ML20137Z810 |
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ML20137Z802 |
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02-6073-011-QP, 2-6073-11-QP, NUDOCS 8512110412 |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212F9221999-09-23023 September 1999 Rev 2.3 to Chapters 10,11,12 & App F of LaSalle Annex Odcm ML20211L2871999-09-0202 September 1999 Revs to ODCM, for LaSalle Annex Including Rev 2.2 for Chapters 10,11,12 & App F ML20210R3581999-08-13013 August 1999 Proposed Tech Specs Allowing Performance of CRDM & Ni Instrumentation Replacement to Not Be Considered Core Alterations During Operational Condition 5,Refueling,while Fuel Is in Reactor Vessel ML20210Q4101999-08-0606 August 1999 Proposed Tech Specs Section 3/4.6.4, Vacuum Relief, Removing Specific Operability Requirements Related to Position Indication for Suppression chamber-drywell Vacuum Breakers & Revising Action Statements & Srs,Per NUREG-1433 ML20209G3581999-07-14014 July 1999 Proposed Tech Specs Pages Re Amend to Licenses NPF-11 & NPF-18,revising TS Allowing LCS Units 1 & 2 to Operate at Uprated Power Level of 3489 Mwt ML20209D3931999-07-0707 July 1999 Proposed Tech Specs,Changing Proposed Degraded Voltage Low Limit Setpoint & Adding High Limit Setpoint & Allowable Value ML20209D3231999-07-0707 July 1999 Proposed Tech Specs,Revising MCPR Safety Limits & Adding Approved Siemens Power Corp Methodology List of TRs for COLR ML20206T1401999-05-19019 May 1999 Proposed Tech Specs Section 3/4.4.4, Chemistry, Relocating to UFSAR ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20207A9491999-02-23023 February 1999 Rev 4 to LaSalle County Station Restart Plan for Unit 2 ML20195E0101998-11-0909 November 1998 Proposed Tech Specs Re Application for Amends to Licenses NPF-11 & NPF-18,adding Automatic Primary Containment Isolation on Ambient & Differential Temperature to High for RWCU Sys Pump,Pump Valve,Holdup Pipe & Filter/Demineralizer ML20195E0541998-11-0909 November 1998 Proposed Tech Specs Pages Re Application for Amends to Licenses NPF-11 & NPF-18,to Modify Degraded Voltage Second Level Undervoltage Relay Setpoint & Allowable Value to TS 3/4.3.3 & TS Table 3.3.3-2 ML20154M4641998-10-16016 October 1998 Proposed Tech Specs,Lowering Power Level Below Which TCV & TSV Closure Scram Signals & EOC-RPT Signal Are Not in Effect ML20151Y5991998-09-14014 September 1998 Rev 3 to LaSalle County Station Restart Plan, for Unit 2 Only ML20236U5511998-07-24024 July 1998 NRC Manual Chapter 0350 Restart Action Plan,For LaSalle County Station ML20217M6671998-05-0101 May 1998 Proposed Tech Specs Adding Ventilation Filter Testing Program ML20217N9541998-04-30030 April 1998 Rev 1.9 to Chapter 10,rev 2 to Chapter 11 & Rev 1.9 to Chapter 12 of LaSalle Odcm ML20217P2511998-04-28028 April 1998 Rev 2 to LaSalle County Station Unit 1/Unit 2 Restart Plan ML20216E3221998-04-0707 April 1998 Proposed Tech Specs Pages Re Addition of Ventilation Filter Testing Program ML20217J2981998-03-24024 March 1998 Proposed Tech Specs Deleting Unit 1 License Condition 2.C.(30)(a) in Entirety ML20202C8971998-02-0202 February 1998 Proposed Tech Specs Re Changes to Relocate Fire Protection Requirements ML20203G5051997-12-12012 December 1997 Proposed Tech Specs,Modifying Bypass Logic for Msli Valve Isolation Acuation Instrumentation on Condenser Low Vacuum ML20199K5481997-11-24024 November 1997 Proposed Ts,Adding Automatic Primary Containment Isolation on Ambient & Differential Temp High for Rwcs Pump,Pump Valve,Holdup Pipe & F/D Valve Rooms & Eliminating RHR Sys Steam Condensing Mode Isolation Actuation Instrumentation ML20211P9331997-10-15015 October 1997 Proposed Tech Specs Eliminating Unnecessary Detail from Accident Monitoring Instrumentation Surveillance Requirements ML20217C3771997-09-26026 September 1997 Proposed Tech Specs Adding Ventilation Filter Testing Program ML20216H7711997-09-0404 September 1997 Corrected TS Bases Sections B 3/4.2.1 & B 3/4.2.3 Re Thermal Limits ML20216C6381997-08-29029 August 1997 Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates ML20217Q7981997-08-26026 August 1997 Rev 1a to LaSalle County Station Unit 1/Unit 2 Restart Plan ML20141J5671997-08-12012 August 1997 Proposed Tech Specs Surveillance Requirement 4.7.1.3.c Re Ultimate Heat Sink by Deletion of Sediment Deposition Insp in Lake Screen House ML20151K9551997-08-0101 August 1997 Proposed Tech Specs Changing Title of Site Quality Verification Director to Manager of Quality & Safety Assessment ML20148Q4301997-07-0101 July 1997 Proposed Tech Specs Reflecting Improvements Made to Control Room Ventilation Air Intake Radiation Monitoring Sys Logic to Reduce Spurious Actuation of Emergency Filtration Mode of Operation & Unnecessary Challenges to ESF ML20148U2591997-07-0101 July 1997 Proposed Tech Specs to Change Definition of Channel Calibration & Correcting Miscellaneous Errors in TS & Bases. TS Affected Are TS Definition 1.4,TS Tables 3/4.3.2-1 & 3/4.3.6-1 & Bases for TS 3/4.3.1 ML20148N0201997-06-19019 June 1997 Proposed Tech Specs,Relocating Fire Protection Requirements ML20141L0371997-05-27027 May 1997 Proposed Tech Specs,Incorporating Restructured Station Organization,Change to Submittal Frequency of Radiological Effluent Release Rept & Other Administrative Changes ML20148D9561997-05-16016 May 1997 LSCS Unit 1/Unit 2 Restart Plan ML20137W5131997-04-14014 April 1997 Proposed Tech Specs Re Feedwater/Main Turbine Trip Sys Actuation Instrumentation Design Change ML20140C9231997-03-31031 March 1997 Rev 1.9 to Chapter 11, Radiological Environ Monitoring Program & LaSalle Annex Index ML20216H8691997-03-31031 March 1997 Revs to OCDM for LaSalle Station,Including Rev 1.8 to Chapter 10,rev 1.9 to Chapter 11,rev 1.8 to Chapter 12 & Rev 1.7 to App F ML20134A1931997-01-20020 January 1997 Proposed Tech Specs 3/4.1.3.5 Re Control Rod Scram accumulators,3/4.4.4.3.2 Re Reactor Coolant Sys Operational leakage,3/4.5.1 Re ECCS - operating,3/4.5.3 Re ECCS, Suppression Chamber & 3/4.6.2.1 Re Suppression Chamber ML20135E6841996-12-0202 December 1996 Proposed Tech Specs,Requesting Amend to Section 3.4.2 to Revise SRV Configuration to Include Only 13 of Current 18 SRVs ML20134L0221996-11-30030 November 1996 Rev 1.8 to ODCM, Annex,Chapters 10,11 & 12 ML20129J4491996-10-31031 October 1996 Proposed Tech Specs Re Elimination of Seismic Monitoring Instrumentation Requirements ML20129B7981996-10-14014 October 1996 Proposed Tech Specs 2.1.2 Re Thermal Power,High Pressure & High flow,5.3 Re Reactor core,4.0 Re Design features,3/4.1.3 Re Control Rods & 3/4.2.4 Re Linear Heat Generation Rate ML20116A9601996-07-15015 July 1996 Proposed Tech Specs Re Revision of App A,Ts for Licenses NPF-11 & NPF-18,relocating Fire Protection Requirements of Listed TS Sections ML20115D8781996-07-0808 July 1996 Cycle 8 Startup Test Rept ML20113C8641996-06-21021 June 1996 Proposed Tech Specs,Including Extension of 18 Month Surveillance Interval & One Time Change to TS to Extend AOT for Each Subsystem of CR & Auxiliary Electric Equipment Room Emergency Filtration Sys ML20107F0641996-04-16016 April 1996 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements ML20107A8641996-04-0808 April 1996 Proposed Tech Specs for Siemens Power Corp Fuel Transition ML20097C9051996-02-0202 February 1996 Rev 1 to ISI Plan for Comm Ed LaSalle County Station Units 1 & 2 Second Ten-Yr Interval Insp Program ML20096G3411996-01-18018 January 1996 Proposed Tech Specs,Changing Setpoints for Automatic Primary Containment Isolation on MSL Tunnel Differential Temp High & Deleting Automatic Isolation Function on MSL Tunnel Temp High 1999-09-23
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20212F9221999-09-23023 September 1999 Rev 2.3 to Chapters 10,11,12 & App F of LaSalle Annex Odcm ML20211L2871999-09-0202 September 1999 Revs to ODCM, for LaSalle Annex Including Rev 2.2 for Chapters 10,11,12 & App F ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20207A9491999-02-23023 February 1999 Rev 4 to LaSalle County Station Restart Plan for Unit 2 ML20151Y5991998-09-14014 September 1998 Rev 3 to LaSalle County Station Restart Plan, for Unit 2 Only ML20236U5511998-07-24024 July 1998 NRC Manual Chapter 0350 Restart Action Plan,For LaSalle County Station ML20217N9541998-04-30030 April 1998 Rev 1.9 to Chapter 10,rev 2 to Chapter 11 & Rev 1.9 to Chapter 12 of LaSalle Odcm ML20217P2511998-04-28028 April 1998 Rev 2 to LaSalle County Station Unit 1/Unit 2 Restart Plan ML20217Q7981997-08-26026 August 1997 Rev 1a to LaSalle County Station Unit 1/Unit 2 Restart Plan ML20148D9561997-05-16016 May 1997 LSCS Unit 1/Unit 2 Restart Plan ML20140C9231997-03-31031 March 1997 Rev 1.9 to Chapter 11, Radiological Environ Monitoring Program & LaSalle Annex Index ML20216H8691997-03-31031 March 1997 Revs to OCDM for LaSalle Station,Including Rev 1.8 to Chapter 10,rev 1.9 to Chapter 11,rev 1.8 to Chapter 12 & Rev 1.7 to App F ML20134L0221996-11-30030 November 1996 Rev 1.8 to ODCM, Annex,Chapters 10,11 & 12 ML20097C9051996-02-0202 February 1996 Rev 1 to ISI Plan for Comm Ed LaSalle County Station Units 1 & 2 Second Ten-Yr Interval Insp Program ML20095F4041995-12-0202 December 1995 Rev 1 to Procedure LZP-1250-1, A-Model Operation ML20093H1791995-10-10010 October 1995 Rev 1 to Pump & Valve Inservice Testing Program Plan,2nd Ten Year Interval for LaSalle County Station Units 1 & 2 ML20094D9271995-09-30030 September 1995 Rev 1.7 to ODCM Chapters 10,11,12 & App F for LaSalle Station ML20077Q5601994-12-30030 December 1994 Offsite Dose Calculation Manual Revisions to Chapters 10-12 & Appendix F for Lasalle Station ML20149G2551994-10-17017 October 1994 Rev 0 to ISI Plan for LaSalle County Nuclear Station Units 1 & 2 Second Ten-Year ISI Interval ML20149G2591994-10-17017 October 1994 Rev 0 to LaSalle County Station Units 1 & 2 Pump & Valve IST Program Plan 2nd Ten-Yr Interval ML20065G5401994-03-23023 March 1994 Rev 1 to Test Procedure TR-213, One Hour Fire Test of Darmatt KM1 Sys for Protecting Cable Tray,Conduit,Supports & Junction Boxes in LaSalle Nuclear Power Station Units 1 & 2 DG Corridors ML20063F8921994-01-31031 January 1994 Rev 1.0 to Chapters 10,11,12 & App F to Odcm,Lasalle County Station ML20059M9671993-10-27027 October 1993 Rev 1 to LZP-1130-2, Core Damage Assessment ML20045B5921993-05-28028 May 1993 Rev 1 to Procedure LZP-1210-4, Reporting of Transportation Accident. ML20127D0691992-12-30030 December 1992 Corporate Emergency Response Organization Required Reading Package 92-11 ML20114C7321992-08-20020 August 1992 Revised Annex to Chapter 11 to ODCM Re Exposure Pathway &/Or Sample ML20101M3611992-06-25025 June 1992 Offsite Procedures,Including Rev 16 to LZP-1110-01,Rev 2 to LZP-1110-2,Rev 4 to LZP-1120-2,Rev 4 to LZP-1210,Rev 0 to LZP-1210-3 & Rev 0 to LZP-1210-4 ML20079C0351991-05-0303 May 1991 Rev 2 to Procedure LZP-1330-30, Transfer of Wastes from Hrss Waste Tank & Waste Sump ML20043G4791990-05-18018 May 1990 Offsite Procedures,Including Rev 1 to LZP-1330-12,Rev 2 to LPZ-1330-13,Rev 1 to LZP-1330-14 & Rev 6 to LPZ-1330-14 ML20006C0571990-01-18018 January 1990 Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. ML16152A8951990-01-0202 January 1990 Rev 33 to Public Version of Crisis Mgt Plan for Nuclear Stations. ML15264A1571990-01-0202 January 1990 Revised Crisis Mgt Implementing Procedures,Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9,Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML20012A3801990-01-0101 January 1990 Rev 28 to, Offsite Dose Calculation Manual,Oconee,Mcguire & Catawba Nuclear Stations. ML20012A3791990-01-0101 January 1990 Rev 27 to, Offsite Dose Calculation Manual,Oconee Nuclear Station. ML20012A3771990-01-0101 January 1990 Rev 26 to, Offsite Dose Calculation Manual McGuire Nuclear Station. ML20012A3751990-01-0101 January 1990 Rev 25 to, Offsite Dose Calculation Manual,Cawtaba Nuclear Station. ML20012A3691989-12-0505 December 1989 Rev 8 to, Process Control Program,Mcguire Nuclear Station. ML20011D2441989-12-0101 December 1989 Crisis Mgt Implementing Procedures. ML20012A3721989-11-27027 November 1989 Rev 4 to, Process Control Program,Cawtaba Nuclear Station. ML20012A3731989-11-15015 November 1989 Rev 4 to, Process Control Program Oconee Nuclear Station. ML19325F1931989-11-0101 November 1989 Public Version of Rev 32 to, Crisis Mgt Plan for Nuclear Stations. ML19332C8451989-11-0101 November 1989 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 31 to CMIP-1,Rev 28 to CMIP-4,Rev 32 to CMIP-5,Rev 37 to CMIP-6,Rev 36 to CMIP-7,Rev 25 to CMIP-8,Rev 31 to CMIP-9 & Rev 19 to CMIP-13 ML20247H3371989-09-15015 September 1989 Revised Corporate Organization for Nuclear Incidents (Coni) Procedure Manual Including Rev 15 to CONI-1.01, Preparation,Issuance & Control Procedures, Rev 30 to CONI-1.02, Coni & Rev 19 to CONI-1.03, Alerting .. ML19327A7521989-08-16016 August 1989 Rev 2 to Combined Units 1 & 2 Inservice Testing Program for Pumps & Valves. ML20245L7651989-08-0707 August 1989 Rev 0 to Offsite Dose Calculation Manual ML20247M7921989-07-31031 July 1989 Rev 6 to PWR Operations Guideline Number 12 Simulator Testing Program. Simulator Transient Test Review Data Encl ML20247M9151989-07-27027 July 1989 Procedure Generation Package ML20247N0421989-06-19019 June 1989 Rev 5 to SS-1, Braidwood Simulator Steady State Performance Test ML20247M7861989-05-26026 May 1989 Rev 0 to SV-1, Braidwood Simulator Surveillance Testing ML20247M7581989-05-26026 May 1989 Rev 0 to Test NO-1, Braidwood Simulator Normal Operations Testing 1999-09-23
[Table view] |
Text
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02-6073-011-QP-(2)-V6-(2) (
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QUALIFICATION PLAN FOR THE QUALIFICATION OF t
{ EDCS No. 64546 FOR APPLICATION IN THE s
COMMONWEALTH EDISON COMPANY (
LA SALLE COUNTY STATION DIVISION 3 l
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t Volume 6 - Vibration Aging Procedure I
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- SOUTHWEST RESEARCH INSTITUTE 6220 Culebra Road '
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1.0 INTRODUCTION
1.1 Purpose of Vibration Aging
] The purpose of vibration aging of components of the EDGS is to simulate aging conditions and fatigue resulting from significant non-seismic vibration environments which components may see over the 40-year service life of the system. This is in accordance with the requirement " equipment subject to non-seismic vibration during normal and abnormal use shall be subjected to such typical vibration following the aging and seismic procedures" (323, 6.3.5). Accordingly, each mechanical or electromechanical component in the EDCS which could be subject to wear as a result of non-seismic vibrations during the service life of the EDCS will be exposed to an equivalent fatigue environment in the laboratory to simulate this wear.
1.2 Non-Seismic Vibration Environment of the EDCS y
Typically, non-seismic vibration environments for a component in d a nuclear plant are a result of transmission of dynamic loads through the plant piping system, or the proximity of the component to rotating machinery.
The EDCS is not affected by loads transmitted through the plant piping system.
J Furthermore, the major subsystems, the CT/PT, the CC, and AS should not, in general, be exposed to vibration environments caused by rotating machinery, since these subsystems are physically separate from the NC and are floor-mounted. Components of the HC other than the CEX and DE will be exposed to the non-seismic vibration environment created by operation of the DC over its service lifetime for a total of 11,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> maximum. The DE and CEX are designed and maintained to withstand the vibration environment created by their normal operation.
~ Since the major source of non-seismic vibrations is the LE, a preliminary investigation has been nade to obtain data on the power spectral density of the vibratory energy emitted by the DE during operation. These data reveal, as might be expected, that most of the energy is contained in narrow band frequency intervals equal to the rotation frequency of the engine
~ and harmonics of this frequency. For the EDCS considered, these base f requencies are 15 and 30 Hz for the 900 and 1800 rpm engines, respectively.
The data indicate that the maximum ras acceleration value over the range of frequencies emitted by the DE in operation is 0.5 g's or less.
Accordingly, the following vibration environment is postulated.
~
- 1. Over a period of operation of 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> with a major vibration frequency of 30 Hz, couponents seeing the DE vibration
. environnent would receive 1.08 x 108 fatigue cycles.
~ 2. Since the total broadband ras value of acceleration is 0.5 s's, this is a conservative maximum for single frequency sinusoidal excitation sinulating the DE vibration environment.
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- 3. An amplitude exaggeration factor of tw duration for equivalent fatigue by 10~g,will reduceonly requiring the time 1.08 i x 106 fatigue cycles at 1.0 g nss for equivalent fatigue.
i If a 300 Ha sinusoidal excita
! the fatigue cycles,1.08 x 10gion signal cycles is used would be obtained to provide in 1 i
hour. (
i l 4. The maximum number of hours of operttion of the DE is OC member [
j s pecific . One hour of test at 1.0 g and 300 Hz will be run j for each 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> of operation of the DE for the worst case l j .
number of hours of operation for the pertinent OG members '
i involved. The current maximum is 11,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. ,
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2.0 QUALIFICATION, PROCEDURE 2.1 Pr,ercquisite Components to be vibrationally aged will have successfully conpleted thermal radiation and operational aging where required. This will be demonstrated by a functional check (V2) showing that each component to be vibrationally aged meets its EPR.
2.2 Analysis As previously discussed, some of the major subsystem components 3 of the EDGS vill not be exposed to significant non-seismic vibrations during their 40-year service life.
In particular, the components of the CT/PT, the CC and the AS, which are the majority of the electromechanical components, need not be exposed to a non-seismic vibration environment unless information on special cases showing otherwise is provided by the OG. Components of the CEX and DE are part of the design and are maintained such that they
] will be essentially unaffected by the vibration environment produced by the equipment of which they are a part. Other components which may be on the MG skid that are not components of the CEX or DE should not have component resonances at the base frequency or any of the harmonic frequencies of the DE while in operation. If this were so, these components would be particularly susceptible to damage due to the non-seismic vibration environment and would constitute an improper design. Any components of d this type which may be discovered during the resonant search which is part of the process described in Section 2.3 below, should be reviewed for possibio
" elimination fecm the EDCS and replacement with components whose mechanical characteristics are nore suitable to the design. We do not contemplate components of this type will be found.
2.3 Type Test Based on our conservative value for number of fatigue cycles and acceleration level given in Section 1.2, the following type testing will
' be perfor aed on MG skid components other than subcomponents of the DE and GEX in order to produce the appropriate non-seisnic vibration aging.
- 1. The component will be exposed to I hour of uniaxial sinusoidal
' excitation in each of its three principal axes per 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> of DE operation as stated in the CFMA.
- 2. Tests will be performed at 300 Hz in cach axis.
,, 3.
The rms acceleration level of the excitation will be 1.0 g's.
Prior to vibration aging, each component will be exposed to
~ sinusoidal excitation in the frequency range 10 to 200 Itz. Excitation will be at .1 g or less uniaxially in each of the three principal axes of the a
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02-6073-011-QP-(2)-V6-(2)-4 component. The sweep rate will be 2 octaves per minute or less. The
' components will be monitored with an accelerometer in a manner sufficient to determine that no resonances occur at multiples of 15 or 30 Hz. Components !
which have resonances at these frequencies will be reviewed for possible !
, elimination from the EDCS.
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.. , A f tdC bm et1 Y O DATA SUPPLEMENT "I'o Response of an EMD'645' Engine and Selected Accessories to Impulsive and Steady State Loads by '
James F. Unruh The steady-state data, test numbers 19 through 46, of the subject investi-gation were analyzed-for overall RMS acceleration levels in the frequency range from.1-200 Hz. While'the data were considered to be steady state engine ex-citation sample averaging over a 128-second interval (64 sample averages) were used to establish the RMS values listed in Table 1. Typical 1.0 second accel-eration time history and Fourier amplitude spectra in units of g's are given
, on the following data plots. These data were generated using a sample rate of 1,000 samples /second. As can be seen by the overall average RMS amplitudes given in Table 1 and the peak spectrum values that some nonstationarity in the data was present.
Insofar as using these data for evaluating the level of operational loads due to engine vibration it is recommended that an equivalent static load approach be used rather than the specific time history events for the following reasons.
- 1) In a majority of the cases the peak vibratory input is above the seismic region of excitation. Spectra peaks are on the order of 75 Hz and above for the larger excitation levels.
- 2) In those cases where vibration energy is present at the _
engine first two harmonics -(15.or 30 Hz) the base level of vibration is less than 0.2 g's (less than 0.008 inch de-flection).
Based on the RMS summary data given in Table 1 it is suggested that the following (mean + 1 std. dev) peak static gravity loads be used to conserva-tively assess the operational vibratory loads of EDGS.
Direction Level.(g's)
X O.95 Y 0.85 Z 1.00 e
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TABLE 1. RMS mpli tude 'Sumary Measurement -Response
Directions Location (g) -
Name Record No.
Ch. 1 Ch. 2 Ch. 1 Ch. 2 1 X ,Z 0.13 0.078 SSXZ01 1,2 Y t- Z 0.064 0.066 SSYZ01 3,4 2 X Z 0.100 0.087 SSXZO2 5,6 Y Z 0.114 0.162 SSYZO2 7,8 3 X Z 0.450 0.182 SSXZ03 9,10 .
Y Z 0.613 0.560 SSYZO3 11,12 4 X, - Z 0.998' O.748 SSXZO4 13,14 5 X Z 0.769 0.603 SSXZ05 15,16 6 X Z 0.497 0.675 SSXZ06 17,18 Y Z 0.511 0.652 SSYZ06 19,20 7 X Z 0.458 1.020 SSXZ07 21,22 Y
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Z l.00 0.554 SSYZ07 23,24 8 X Z 0.732 0.847 SSXZO8 25,26 Y Z 0.347 0.374 SSYZ08 27,28 9 X Z 0.469 0.477 SSXZ09 29,30 Y Z 0.414 0.469 SSYZO9 31,32 10 X Z 0.378 0.296~ SSXZ10 33,34 Y Z 0.169 0.421 SSYZ10 35,36 11 X Z 0.305 0.281 SSXZ11 37,38 Y Z 0.078 0.267 SSYZll 39,40 12 X Z 0.374 0.198 SSXZ12 41,42 13 X Z 0.349 0.299 SSXZ13 43,44 Y Z 0.344 0.501 SSYZ13 45,46 14 X Z 0.185
,Y 0.211 SSXZ14 47,48 Z OL255 0.601 SSYZ14 49,50 15 X Z 0.'26 1 0.100 SSXZ15 51,52 Y Z 0.142 0.111 SSYZ15 53,54 16 X Z 0.344 0.818 SSXZ16 55,56 Y Z 0.214 0.771 SSYZl6 57,58 RMS
SUMMARY
(g's)
X Y Z Mean 0.416 0.328 0.429' '
Std. Dev. 0.248 0.263 0.268 Variance 0.057 0.064 0.069
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Based on 128 sec of sample averaging, 1-200 Hz window. -
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APPENDIX A 7
TEST PROCEDURES I
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