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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
. :. .
CRACK PROPAGATION ANALYSIS -
FOR CIRCUMFERENTIAL CRACKS ,
IN ALLOY 600 N0ZZLE SAFE-ENDS i
TR-MCC-307 i
r OCTOBER 1993 i
ABB COMBUSTION ENGINEERING NUCLEAR SERVICES ,
COMBUSTION ENGINEERING, INC.
~
1000 PROSPECT HILL ROAD WINDSOR, CONNECTICUT t
9310220100 931015 EL
- PDR ADOCK 05000255 h P PDR k;-
+
4
-TABLE OF CONTENTS ,
TITLE PAGE INTRODUCTION 1 ,
CRACK GROWTH RATE MODEL 1
^
CRACK GE0 METRIC AND PROGRESSION ASSUMPTIONS 2-LOADING AND INITIAL CONDITION ASSUMPTIONS .3 INPUT TO COMPUTATIONS 3 RESULTS 3 REFERENCES 4 f
I I
i l
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I
INTRODUCTION 4
This report documents crack propagation studies performed for selected Alloy 600 components in the pressurizer of the Palisades NSSS. The components include:
e Safety Valve Flange e PORV Safe-End e Surge Line Safe-End e Spray Line Safe-End The assumed mechanism (based on recent failure analysis results) for crack propagation in all analyses is primary water stress corrosion cracking (PWSCC). The methodology used in these studies was developed for specific application to the problem of crack propagation in CEDM nozzles (Reference 1).
CRACK GROWTH RATE MODEL The basic crack propagation model used in the analyses is based on a subset of the Alloy 600 data published by Smialowska et.al. (Reference 2). The only data specifically excluded were high (>7 ppm) lithium data not representative of Palisades primary chemistry. All experiments utilized in the final correlation analysis were performed at a temperature of 330*C.
The crack growth rate correlation is given by:
in di - A + B in in (K-C) dt where: dl = crack growth rate (m/s) dt A = -25.942 B = 3.595 K = Applied Stress Intensity (MPa s/ m)
C-Kisce - 0 (for this case)
The crack growth rate versus stress intensity is shown in Figure 1. It should be noted that no explicit threshold stress intensity is required for crack propagation in this correlation form. This feature was incorporated to permit investigation of crack growth for CEDM nozzles in which observed cracks were extremely shallow (<.4 mm).
Two corrections are necessary to the growth rate correlation for application to the Palisades study. The first involves component temperature. The effect t of temperatures unequal to 330*C is accommodated using an Arrhenius rate law with an activation energy of 33 Kcal/ mole. This is consistent with Reference
- 1. The second correction reflects the effect of the prior cold work present in the Smialowska data. Scott (Reference 3) has suggested reduction in growth rate by a factor of between 5 and 10. A factor of 5 is utilized in the present work.
CRACK GE0 METRIC AND PROGRESSION ASSUMPTIONS One-dimensional Linear Elastic Fracture Mechanics (LEFM) models were used in conjunction with the crack rate correlation to compute crack progression. The assumed configuration for the initial crack is an embedded semi-elliptical surface flaw with Mode I opening. The applied stress is computed using the equation given in Figure 2.3.3 of Reference 4.
K, - 1.95g v' a/$
where K, - applied stress intensity rr - section tensile stress a - flaw depth Q - complete elliptic integral of the second kind Evaluation of crack growth is performed by numerical integration using the crack growth rate correlation and the stress intensity equation. The required input includes operating temperature, initial flaw depth and initial stress intensity, which in conjunction with the two governing equations completely I
I
l l
define the mathematical system. l LOADING AND INITIAL CONDITION ASSUMPTIONS ]
l In the absence of detailed finite element computations, an assumption of net section yield was made for all components. No credit was taken for reduction of yield strength with temperature. This assumption is consistent, however, with finite element analysis results documented in Reference 1 for CEDM nozzles in the partial penetration weld region.
Initial flaw depth was assumed to be approximately 3 mils, consistent with )
results of detailed experiments performed by Boursier et.al. (Reference 5) in 1 which various regimes of PWSCC crack growth were studied for Alloy 600. This-assumed depth is deemed appropriate for separating the initiation and propagation parts of the PWSCC phenomenon and probably represents the beginning of the true fracture mechanics regime.
l The final major assumption concerned the initial (and final) aspect ratio of _ ,
the flaw. For the purposes of the Palisades components a range of flaw aspects was used ranging from a semi-circular (2/1) to a long semi-elliptical (6/1) aspect ratio flaw. ,
i INPUT TO COMPUTATIONS j l
The input for each Palisades component is given in Table 1. In the case of j the PORY Fafe-End computations were performed for two levels of applied stress. The first corresponded to the 77 KSI yield strength cited in the CERTS for the material. The second corressponded to a 40 KSI assumed value ,
obtained from material near or in a softened weld heat affected zone. For the
~
other components CERT yield strength values were used in the analysis.
RESULTS The results of the crack growth assessment for the Palisades PORV safe-end are shown in Figure 1 for the 77 KSI applied stress and in Figure 2 for the 40 KSI I
I I
i
appl.ied stress. The safety valve safe-end crack growth assessment is shown in Figure 3 for a 77 KSI applied stress. The surge line and spray line safe-end crack growth assessment, are shown in Figures 4 and 5 respectively.
Table 2 is a derivative of the information contained in Figures 1-5. The ,
crack depths shown in the table represent the largest cracks which would theoretically permit operation for 15 effective full power months prior to throughwall propagation. The Palisades PORV Safe-End case at 77 KSI applied stress is the most limiting with a required crack detection threshold of 40 mils.
REFERENCES
- 1. ABB Combustion Engineering, " Safety Evaluation of the Potential for and ;
Consequences of Reactor Vessel Head Penetration Alloy 600 ID Initiated Nozzle Cracking," CEN-607, May 1993.
- 2. Smialowska, Z. S. et a1. , " Effects of pH and Stress Intensity on Crack Growth Rate in Alloy 600 in Lithiated and Borated Water at High I Tempertures," Proceedings, Fifth International Symposium on ,
Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Monterey, Aguust, 1991.
- 3. Scott, P. M., "An Analysis of Primary Water Stress Corrosion Cracking in '
PWR Steam Generators," Proceedings, Specialists Meeting on Operating Experience with Steam Generators, Brussels Belgium, September 1991.
- 4. R. L. Cloud et al., Brittle Fracture Desian Guide, ASME,1971.
l
- 5. J. Boursier et al., " Stress Corrosion Cracking of Alloy 600 in Water: !
Influence of Strain Rate on the Different Stages of Cracking," EUROCORR
'92, June 1992.
I l
Table 1 INPUT FOR PALISADES CRACK STUDIES I
initial Stress intensity W all Applied Crack Temperature Component Thickness Stress Depth . (*F)' 2/1 4/1 6/1 (in) (KSI) (in) (KSI V in) -
PORV .438 77 0.0032 640 5.36 7.08 7.58 Safe-End PORV .438 40 0.0032 640 2.78 3.68 3.94 Safe-End Safety 1.3 77 0.0032 640 5.36 7.08 7.58 Valve Flange Surge Line .75 51 0.0032 640 3.54 4.69 5.02 Safe-End 4 Spray Line .625 77 0.0032 540 5.36 7.08 7.58 Safe-End Table 2 CRACK DETECTION REQUIREMENTS i Time to Throughwall. . Crack Depth 15 Months i Component Crack Prior to T/W Crack (Months) .' ' (inches):: 1 PORV Safe-End (77 KSI) 20 .039 PORV Safe-End (40 KSI) 42 .175 f
Safety Valve Flange 38 .550 Surge Line Safe End 41 .310 l
Spray Line Safe-End > 350 .600 1
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