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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML18066A4671999-03-31031 March 1999 Rev 0 to SIR-99-032, Flaw Tolerance & Leakage Evaluation Spent Fuel Pool Heat Exchanger E-53B Nozzle Palisades Nuclear Plant. ML20249C4951998-06-17017 June 1998 Rev 1 to EA-GEJ-98-01, Palisades Cycle 14 Disposition of Events Review ML18066A3411998-04-22022 April 1998 Rev 0 to EMF-98-013, Palisades Cycle 14:Disposition & Analysis of SRP Chapter 15 Events. ML20217C2741998-03-31031 March 1998 Independent Review - Is Consumers Energy Method (W Method) of Determining Palisades Nuclear Plant Best Estimate Fluence by Combining Transport Calculation & Dosimetry Measurements Technically Sound & Does It Meet Intent of Pts ML18065B1641998-02-0505 February 1998 Rev 0 to Regression Analysis for Containment Prestressing Sys at 25th Year Surveillance. ML20197J3891997-12-18018 December 1997 25th Year Physical Surveillance of Palisades Npp ML20217C2571997-12-16016 December 1997 Review of Neutron Fluence Data for Palisades Reactor Pressure Vessel ML18067A6351997-07-0909 July 1997 Excerpt from Ampacity Evaluation for Open Air Cable Trays W/Percent Fill Greater than 30% of Useable Cross Sectional Area. ML18067A6381997-07-0909 July 1997 Excerpt from Ampacity Evaluation for Continuously Energized Power Cables Routed Through Fire Stops, Revision 1 ML18067A6371997-07-0808 July 1997 Excerpt from Ampacity Evaluation for Duct Runs Containing Continuously Energized Power Cables, Revision 1 ML18067A6361997-06-26026 June 1997 Excerpt from Ampacity Evaluation for Continuously Energized Power Cables in Open Air Conduits, Revision 1 ML18066A8581997-01-31031 January 1997 Rev 2 to C-PAL-96-1063-01, Operability Assessment for Transient Conditions at Palisades Nuclear Plant in Response to GL 96-06. ML18065B0471996-07-12012 July 1996 TR on Use of Mcbend Code for Calculation of Neutron Fluences in PVs of Lwrs. ML18065A7571996-05-22022 May 1996 Rev 1 to IPEEE Rept, Per GL 88-20 ML20108C1671996-04-0101 April 1996 Nonproprietary Version of Fluence Calculations for Palisades Plant ML18065A5971996-03-23023 March 1996 Evaluation of Effects of Fire on West Wall of Turbine Lube Oil Room Adjacent to Pipe Tunnel Between TB & FW Purity Bldg. ML18065A6011996-03-22022 March 1996 Evaluation of Effects of Fire on West Wall of CCW Pump Room (Fire Area 16). ML20100D7491996-01-18018 January 1996 Rev 0 to Evaluation of Effects of Fire on West Wall of TB Lube Oil Room Adjacent to Pipe Tunnel Between TB & FW Purity Bldg ML18065A4481995-12-14014 December 1995 Radiological Consequences for Palisades Max Hypothetical Accident & Loss of Coolant Accident. ML18064A8321995-06-30030 June 1995 IPE of External Events (Ipeee). ML20085H2801995-05-23023 May 1995 Security Investigation Rept ML18064A7801995-05-19019 May 1995 Rept of SQUG Assessment at Palisades Nuclear Plant for Resolution of USI A-46. ML20078P7021995-01-27027 January 1995 Investigative Rept ML18064A4121994-08-22022 August 1994 Pressure-Temp Curves & LTOP Setpoint Curve for Max Reactor Vessel Fluence of 2.192 X 10^19 Neutrons/cm^2. ML20070J8001994-07-15015 July 1994 Final Rept Containment Sump Check Valves Weld Overlay Repair Implementation Evaluation Palisades Nuclear Plant ML18059B0041994-04-0505 April 1994 Rev 1 to EDG Fuel Supply Sys Storage Tank Tornado Protection Overview of EDG Fuel Supply Sys, Incorporating CARB Comments of 940318 & 24 ML20064E5301994-03-0606 March 1994 Evaluation of Effectiveness of Code Case N-504-1 Repair for Proposed Root Causes for Containment Sump Suction Check Valves ML20064E4451994-03-0505 March 1994 Check Valve Leak Root Cause,Engineering Analysis & Repair/Replacement Options ML18059A5161993-10-31031 October 1993 Nonproprietary Exam...Sections of Pressurizer PORV Line Safe-End Failure from Palisades Nuclear Generating Station. ML20058P1361993-10-31031 October 1993 Crack Propagation Analysis for Circumferential Cracks in Alloy 600 Nozzle Safe-Ends ML18059A4821993-10-25025 October 1993 Evaluation of Potential Interference Between TE-0102 Nozzle & Thermowell. ML18059A4831993-10-25025 October 1993 Structural Evaluation for Machined Thermawell for TE-0101. ML20059D8811993-10-23023 October 1993 Justification of Weld Mods to Pressurizer Temperature Nozzles for TE-0101 & TE-0102 ML18059A4811993-10-22022 October 1993 Acceptability of Partial Severing of TE-0101 Nozzle. ML18059A4801993-10-19019 October 1993 Structural Analysis of Temperature Nozzle Weld Mods for Consumers Power Palisades Pressurizer. ML18059A4791993-10-15015 October 1993 Half Bead Welding for Mods to TE-0101 & TE-0102. ML18059A4221993-10-0707 October 1993 Pressurizer Safe End Crack Engineering Analysis & Root Cause Evaluation. ML18059A3751993-08-31031 August 1993 Rev 1 to Palisades Cycle 11:Disposition & Analysis of SRP Chapter 15 Events. ML18059B0191993-07-31031 July 1993 Detailed Site Study,Berrien County,Mi, Final Rept ML18064A4271993-06-30030 June 1993 Wind Tunnel Predictions of Control Room Intake Concentrations from Three Sources of Radioactive Materials at Palisades Nuclear Power Plant, (CPP-Project 93-0907) ML18058B8661993-05-13013 May 1993 Resolution of Anchor Bolt Design Issues. ML18058B3911992-12-21021 December 1992 Cycle 11:Disposition & Analysis of Standard Review Plan Chapter 15 Events. ML18058B4281992-11-30030 November 1992 Vols 1,2 & 3 of Palisades Nuclear Plant Ipe. ML18058A5391992-06-16016 June 1992 Twentieth Yr Physical Surveillance of Palisades Nuclear Plant. ML20086P8551991-12-0909 December 1991 Criticality Safety Analysis for Palisades Spent Fuel Storage Pool NUS Racks ML20086P8571991-12-0909 December 1991 Criticality Safety Analysis for Palisades New Fuel Storage Array ML18057B3521991-10-31031 October 1991 Large Break Loca/Eccs Analysis W/Increased Radial Peaking & Reduced ECCS Flow. ML18057A8591991-03-31031 March 1991 Benchmarking & Validation of In-House DOT Calculation Methodology. ML20081K7741990-08-14014 August 1990 Incore Detector Algorithm (Pidal) Analysis of Quadrant Power Tilt Uncertainties ML18057A2611990-06-11011 June 1990 Simulator Certification Submittal. 1999-03-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18066A6901999-11-0101 November 1999 Rev 5 to Palisades Nuclear Plant Colr. ML18066A6761999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Palisades Nuclear Plant ML18066A6271999-09-0202 September 1999 LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr ML18066A6351999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Palisades Nuclear Plant ML18066A6771999-08-31031 August 1999 Operating Data Rept Page of MOR for Aug 1999 for Palisades Nuclear Plant ML18066A6221999-08-20020 August 1999 LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr ML18066A6061999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Palisades Nuclear Plant.With 990803 Ltr ML18066A5201999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Palisades Nuclear Plant.With 990702 Ltr ML18066A4841999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Palisades Nuclear Plant.With 990603 Ltr ML18066A6371999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML18068A5941999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant.With 990503 Ltr ML18066A4161999-04-0101 April 1999 Rev 4 to COLR, for Palisades Nuclear Plant ML18066A4501999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Palisades Nuclear Plant.With 990402 Ltr ML18066A4671999-03-31031 March 1999 Rev 0 to SIR-99-032, Flaw Tolerance & Leakage Evaluation Spent Fuel Pool Heat Exchanger E-53B Nozzle Palisades Nuclear Plant. ML18068A5351999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Palisades Nuclear Plant.With 990302 Ltr ML18066A3931999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Palisades Nuclear Plant.With 990202 Ltr ML18066A3781999-01-20020 January 1999 LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr ML20206F6131998-12-31031 December 1998 1998 Consumers Energy Co Annual Rept. with ML18066A3651998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Palisades Nuclear Plant.With 990105 Ltr ML18066A3421998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Palisades Nuclear Plant.With 981202 Ltr ML18066A3301998-11-11011 November 1998 Part 21 Rept Re Potential Safety Hazard Associated with Wrist Pin Assemblies for FM-Alco 251 Engines at Palisades Nuclear Power Plant.Caused by Insufficient Friction Fit Between Pin & Sleeve.Supplier of Pin Will No Longer Be Used ML18068A4921998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Palisades Nuclear Plant.With 981103 Ltr ML18068A4851998-10-29029 October 1998 LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced ML18066A3181998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Palisades Nuclear Plant ML18066A2901998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Palisades Nuclear Power Plant.With 980903 Ltr ML18066A3191998-08-31031 August 1998 Revised Monthly Operating Rept Data for Aug 1998 for Palisades Nuclear Plant ML18066A2831998-08-18018 August 1998 LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20237E0301998-07-31031 July 1998 ISI Rept 3-3 ML18066A2701998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Palisades Nuclear Plant.W/980803 Ltr ML18066A2311998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Palisades Nuclear Plant ML18066A2261998-06-30030 June 1998 LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired ML18066A3061998-06-18018 June 1998 SG Tube Inservice Insp. ML20249C4951998-06-17017 June 1998 Rev 1 to EA-GEJ-98-01, Palisades Cycle 14 Disposition of Events Review ML18066A1781998-06-0909 June 1998 LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures ML18066A1711998-06-0101 June 1998 Part 21 Rept Re Impact of RELAP4 Excessive Variability on Palisades Large Break LOCA ECCS Results.Change in PCT Between Cycle 13 & Cycle 14 Does Not Constitute Significant Change Per 10CFR50.46 ML18066A1741998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Palisades Nuclear Plant.W/980601 Ltr ML18066A2321998-05-31031 May 1998 Revised MOR for May 1998 for Palisades Nuclear Plant ML18068A4701998-05-31031 May 1998 Annual Rept of Changes in ECCS Models Per 10CFR50.46. ML18065B2451998-05-13013 May 1998 LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge ML18066A2331998-04-30030 April 1998 Revised MOR for Apr 1998 for Palisades Nuclear Plant ML18068A3461998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Palisades Nuclear Plant.W/980501 Ltr ML18066A3411998-04-22022 April 1998 Rev 0 to EMF-98-013, Palisades Cycle 14:Disposition & Analysis of SRP Chapter 15 Events. ML18065B2071998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Palisades Nuclear Plant.W/980403 Ltr ML20217C2741998-03-31031 March 1998 Independent Review - Is Consumers Energy Method (W Method) of Determining Palisades Nuclear Plant Best Estimate Fluence by Combining Transport Calculation & Dosimetry Measurements Technically Sound & Does It Meet Intent of Pts ML18066A2341998-03-31031 March 1998 Revised MOR for Mar 1998 for Palisades Nuclear Plant ML18068A3041998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Palisades Nuclear Plant.W/980302 Ltr ML18066A2351998-02-28028 February 1998 Revised MOR for Feb 1998 for Palisades Nuclear Plant ML18065B1641998-02-0505 February 1998 Rev 0 to Regression Analysis for Containment Prestressing Sys at 25th Year Surveillance. ML18067A8211998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Palisades Nuclear Plant.W/980203 Ltr 1999-09-30
[Table view] |
Text
J G Keppler, Director Palisades Plant September 30, 1980 Attachment l EVALUAT.ION OF PALISADES PLANT WATERHAMMER TEST
- AND POTENTIAL WATERHAMMER EFFECTS Prepared for Consumers power Company By Combustion Engineering, Inc.
Nuclear Power Systems September 30, 1980 80I00706Q9
Attachment 1 ~
J G Keppler, Director Palisades Plant September 30, 1980 EVALUATION OF PALISADES WATERHAMMER TEST DATA 1.0 Introduction This report has been prepared for the Consumers .Power Company by Combustion Engineering, Inc. (C-E). It contains the re-sults of an evaluation of the test data from the waterharnrner test conducted on.May 10, 1980. The test was performed at a steam pressure of 200 psia and at feedwater flowrates of 150 and 300 gpm. This report also includes an evaluation of poten-tial waterhammer effects at hot standby conditi9ns.
2.0 Test Data Prior to the test, special instrumentation was installed on the feedwater pipe and feedwater nozzle of steam generator B.
Six strain gauges were installed on the feedwater pipe next to .the nozzle. Four of the gauges provided bending and tensile strains, while the remaining two gauges recorded hoop strains.
The analysis was performed using the output of one gauge which measured bending and tensile strains in the horizontal plane.
The outputs of the five remaining gauges were lost because of insufficient exposure of the light sensitive paper. The feed-water pipe was also instrumented with an accelerometer, which was located on the first downward sloping elbow of the feegwater pipe. This provided an independent measurement of piping dis-placement and natural frequency.
- 3. O. Analysis
- An elastic model of the feedwater piping was made using the C-E DAGS76 Dynamic Piping Program. This code is the standard C-E computer program for seismic and LOCA dynamic piping analyses for the PWR primary system. In order to simulate the measured response of the strain gauge, various hydraulic forcing functions were assumed for each elbow.
/
The initial compressive strain was postulated to have occurred as the water slug passed through the first elbow. A tensile stress was then assumed as *the pressure on the second elbow increased due to slug retardation downstream of the first elbow.
Figure l contains a diagram of the location of the reactive
~Qi::c.es,_ their directions.and the locations .of.the instrumenta-tion, It was first assumed that classical waterhamrner had occurred during the 300 gpm test. Applying the resultant forcing function, Figure 2, to the piping system model produces piping strains, Figure 3, which are 15 times greater than the corres-ponding field test data. It was, therefore, concluded that classical waterharnrner did not occur.
J G Keppler, Director Palisades Plant September 30, 1980 2 The structural analysis was repeated, with various pressure profiles. The* results were then compared to the test data.
Figure 4 presents the final forcing function and Figure 5 .
shows the corresponding calculated response along with the
. test measurements. As can be seen, this forcing function produces a piping response which compares quite favorably with the test results. This forcing function corresponds to a water slug of approximately 6 feet with an impact velo-city of about .20 ft/sec. The velocity is significantly less than that which would.be calculated using classical rapid condensation rates. Consequent'iy I it appears th'at slow con-densation occurred throughout the process rather than rapid condensation which is usually associated with waterhammer experienced in other nucl~ar units.
A review of the accelerometer data substantiates the con-clusions based on the strain gauge readings. The indicated displacements and frequency of the accelerometer agree reason-ably well with the strain gauge data. Hence, further credence.
is given to the conclusion that a relatively mild waterhammer transient occurred involving only slow film condensation. The
- calculated hydraulically induced stresses are less than the allowable stresses corresponding to.pressure plus Operating Basis Earthquake (OBE) seismic limits.
4.0 Extrapolation of Test Results to Operating Conditions The analysis of the 200 psia test data indicates that pressure spikes on the order of 600 psi occurred during the test. Ex-trapolation of the peak pressure to hot standby conditions using the square root of the pressure ratio produces an over-pressure of 1260 psi. The stress resulting from the test conditions are within theFSAR (OBE) limits as shown in Table 1. (Other examples of faulted limits are also shown in Table 1) .
Although considered highly unlikely, if rapid condensation were postulated to occur at hot standby, the slug could theo-retically achieve a high velocity (approximately 260 ft/sec) and the calculated resultant peak stresses would exceed the allowable stress limits.of the piping.
--- The Palisades -Plant has never experienced -a waterhammer during -
- actual plant operation even though there were a number of*
occasions when the feedwater sparger was drained arid conditions conducive to waterharraner existed. A comparison of the Palisades
y G Keppler, Director Palisades Plant 3
September 30, 1980 piping with other plants indicates that there are two unique design features which may mitigate or eliminate the effects of water hammer. The feedwater ring is two feet below the feedwater nozzle and the horizontal run of feedwater piping
. has a 90° bend in the horizontal plane approximately 8 feet from the feedwater nozzle. The lower feedwater ring reduces.
the number of times the ririg is exposed to a steam environ-ment. If rapid condensation were to occur, the 90° bend in the horizontal plane may eliminate or mitigate the waterhammer by breaking up the slug as it passes through the bend. Figure 6 contains a curve which shows that if rapid condensation occurs, the slug would be in a cavitating condition as it passed through the horizontal elbow. The cavitation in turn would allow steam to bypass the slug, restoring the downstream pressure. This theory is supported through experimental data on cavitating elbows (reference l) . Based on discussions with operators on duty when the 200 psia waterhammer testing was performed, it is extremely unlikely that waterhammer of simil.ar magnitude could have previously occurred undetected. To further postulate that waterhammer of greater magnitude (based on either extrapolation of the 200 psia data, using the square root of the pressure ratio~- or classical waterhammer theory) has gone undetected, is virtually inconceivable.
During the recent feedwater pipe cracking repairs at Palisades, the area of the thermal sleeve in the feedwater nozzle'. was closely inspected on several occasions. No deformation of the thermal sleeve was noted. Deformation (expansion) of the thermal sleeve has been reported during inspection of a steam generator which had been subjeqted to waterhammer at another plant. Lack of such deformation forther corroborates the conclusion that waterhammer has not occurred at Palisades, other than during the test performed at off-normal conditions.
5.0 Conclusions A. Although conditions which are generally conducive to water-hammer existed on a number of occasions there have been no observed occurrences of waterhammer under normal operating conditions at Palisades. This finding is based on:
- l. The operators would have noted a waterhammer even if it were as mild as the one observed during the 200 psia
-test-. -- - - - - - - - - --
- 2. No deformation of the thermal sleeve in the feedwater nozzle was observed druing examinations perforr.ted in conjunction with the repair of the feedwater piping.
J G Keppler, Director Palisades Plant Septeml:>er 30, 1980 4 B. If a waterhammer were to occur at hot standby, with the same condensation rate as inferred from the 200 psia test, the resulting stresses would be within faulted allowables.
C. If one were to postulate a more rapid condensation mechanism at h~t standby (rates consistent with classic waterhammer theory), the increased slug velocities associated with the waterhammer are predicted to result in cavitation as the slug passes through the horizontal elbow. This .would prevent the generation of very large impact forces at the downturning elbow. * *
- IN LIGHT OF THE ABOVE, IT IS CONSIDERED HIGHLY UNLIKELY THAT FEEDING A SINGLE STEAM GENERATOR AT FLOW RATES OF UP TO 300 GPM AT HOT STANDBY CONDITIONS WOULD RESULT IN AN UNACCEPTABLE WATER-HAMMER AT PALISADES PLANT.
6 .0 References (1) D S Miller, "Internal Flow Systems", Volume 5, Published by BHRA Fluid. Engineering, 1978
TABLE 1 STRESS LIMITS
- l. Test Conditions Pressure Stress @ 200 psi = 1150 psi Dead Weight Stress = 95 psi Waterhanuner stress = E x Strain
= 27.0 x 106 psi x (550 - 1150 27.9 x
= 13,977 psi FSAR OBE CRITERIA (18,000 psi) 1150 psi+ 95 psi+ 13,977 psiC::l.2Sh 15 , 2 2 2 < 18 , OOO ps i
- 2.
- Extrapolated Conditions Pressure Stress @ 900 psi = 5175 psi Deadweight Stress = 95 psi Waterhammer Stress = E x Strain x J9/2.
= 27.9 x 106 psi (550 1150 > x io-6 x J9/2 21.9 x io6*
= 29,800 psi FSAR SSE CRITERIA (36,000 psi) 5175 psi + 95 psi + 29, 800 psi< 2. 4Sh 3 5 , O7 O psi < 36 , OO0 psi
. \
Note: Other faulted condition allowables could be 3.0sh = 45,000 psi and .7 s~lt = 42,000 psi
PIPING DIAGRAM FORCE AND INSTRUMENTATION LOCATIONS STEAM GENERA TOR B
x y
~
FB ---"--I-~.
\ p
\
FA X - LOCATION OF STRAIN GAUGE Y - LOCATION OF ACCELEROMETER FIGURE 1
CLASSICAL WA TEA HAMMER FORCING FUNCTION FOR 300 GPM TEST 0
- ~ 3000L----+-~-+--~+--+--.....+-~+-~l---+~-+-~+---t~--;
<(c.< 2000 LI..
1000L---+-~....+:-~+--+--l-ll-+-~+-~l---+~-+-~+---t~--;
.1 .2 .3 .. .4 .5 TIME, SECONDS
- .l .2 .3 . - -- -*'." .5 TIME, SECONDS FIGURE 2
9LCULATED STRAIN GAUGE .PONSE ASSUMING RAPID CONDENSATION STRAIN AT STEAM GENERATOR NOZZLE ANALYSIS RESULT (3000 psi) STRAIN GAUGE DAT A
- 11000 10,000 9000 8000 7000
\0 0 I
~ 3000 '
I
~ 2000
~
E-1 U) 1000 J r\
0 'l r"\. -
u 11 / v
-1000
-2000 u
-3000
-4000 M
-5000
.1 .2 .3 .4 .5 .6 .7 .8 .1 .2 .3 .4 .5 .6 .7 TIME, SECONDS TIME; SECONDS - - - -- -
FREQUENCY ~ 15 hz FREQUENCY = 11.4 MAX. DISPLACEMENT . MAX. DISPLACEMENT AT Y = 2.67 IN AT Y = .18 IN FIGURE 3
SLOW CONDENSATION FORCING FUNCTION FOR*
300 GPM TEST
I --- r----...,._
.02 .04 .06 .08 .10 .12 .14 .16 .18 .20 SECONDS TIME
~ soo1----+-_;_~-4-----1---+1--+----1----+--+--+--+--+----t
~1~4001----+--~---4-----1---M-+----1----+--+--+--+---+----t 3001---+--+--+--+--+-t-+---+--+---t--+--+---t--
200 1001---+---+--+---l---+-+-+---l---+--+--+-'----+--+---t
.02 .04 .06 .08 . 10 . 12 . 14 . 16- . 18 .20 SECONDS TIME FIGURE 4
~ALCULATED STRAIN GAUG-ESPONSE ASSUMING SLOW CONDENSATION STRAIN AT STEAM GENERATOR NOZZLE ANALYSIS RESULTS STRAIN GAUGE DAT A (600Psi) 800 20 700 600 15 500
- 400 10 300 n co 200 , 5 0
.,.. r x 100
~
c(
0 0
~
....a:
"' \\ / l \- "'"'a:w
-100 v u
\J V' ....
-200 -5 "'
~
-300
-400 -10
.1 .2 .3 .4 .5 .6 .1 .2 .3 .4 .5 TIME-SECONDS TIME-SECONDS FREQUENCY FROM ACCELEROMETER FRE:OUENCY ..
11.4 hz ~19 hz MAX~ DISPLACEMENT MAX. DISPLACEMENT AT Y=.18 IN. AT Y=.20 IN.
FIGURE 5
CAVITATION CRITERIA FOR ELBOWS r
I
~p ISADES BEND GE METRY
.Q I
b 3r----~-t-~-+----if--~~-+--+-~--l~~~~~~_;.J I
a:
w CD N~ CAVIT noN
~ I
- > 2i--~~-r-~~--i~~~-+--t--~--l~---~-+----~~--I z
z 0
j:::
<C
.... 1 OPERAT NG
<C
(.)
.5 1.0 1.5 2.0 rid FIGURE 6