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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
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ATTACHMENT 7 ;
Consumers Power Company Palisades Plant Docket 50-255 l
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EVALVATION OF EFFECTIVENESS OF CODE CASE N-504-1 REPAIR FOR PROPOSED ROOT CAUSES FOR l CONTAINMENT SUMP SUCTION CHECK VALVES .
March 6, 1994 l
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9403140336 940306 l PDR ADOCK 05000255 '
P PDR u: _,
l Project No. 9400-040 l
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Nuclear Safety-Related i
Evaluation of the Effectiveness of Code l Case N-504-1 Repair for Proposed Root Causes l for Containment Sump Suction Check Valves l
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Prepared for Palisades Nuclear Station l
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l CMED-058617 i Revision 0-March 5,1994 !
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CMED-058617 Sargent & Lundy N ' '#^"
Prepared by: /Il ' A Date 3 'b I lj J. T. Loud'en J
Reviewed by: O_D '\d _1 Date 3-5-%
'J. F1aberty 'N Approved by: u l) I4h h Date 3/6[94
' G. H dDeBoo Page 2
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CMED-058617 Introduction This evaluation will consider the possible root causes for-the leak in CK-ES3166 and the indications identified in CK-ES3181, and the resultant effect of a Code Case N-504-1 overlay.
The possible root causes as postulated by CPCo are:
- 1. Multiple Heat Input and Repairs at Leak Site Causing Highly Sensitized Casting Material
- 2. Intergranular Corrosion (IGC)
- 3. Intergranular Stress Corrosion Cracking (IGSCC)
- 4. Casting Flaw
- 5. Welding Flaw
- 6. Chemically Induced Pitting Corrosion A review of these root causes concluded that possible root cause 1 was a contributing factor of root causes 2 and 3; therefore it is not addressed' individually,.but as part of root causes 2 and 3. Also,. root causes 4 and 5 were addressed together since the resultant effect on a Code Case N-504-1 overlay is considered the same.
Consequently, the possible root causes evaluated are:
- 1. Intergranular Corrosion (IGC)
- 2. Intergranular Stress Corrosion Cracking (IGSCC)'
- 3. Casting Flaw or Weld Flaw
- 4. Chemically Induced Pitting Corrosion The attributes of a Code Case N-504-1 weld overlay as applied to thesh valves J
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CMED-058617 are presented and their ability to mitigate the propagation of the identified indications is discussed for each possible root cause. It is important to-emphasize that cyclic loading and the associated stress driven flaw propagation is not a factor to be considered for this overlay application as stated in CMED-058599.
This evaluation demonstrates that the Code Case N 504-1 overlay is a technically valid corrective action for all the possible root causes stated above.
Code Case N-504-1 Corrective Action Code Case N-504-1 is an acceptable corrective action for the CK-ES3166 and CK- ,
ES3181 check valve repair for all the possible root causes previously. listed. .
The reasons are as follows:
A. The overlay weld metal has improved IGC and IGSCC corrosion resistance over the casting.
B. The overlay will conservatively meet the ASME Section XI Code structural reinforcement requirements.
C. The overlay will be periodically inservice inspected (ultrasonically) to verify that the flaw is not propagating.
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D. The code case does not limit the flaw to any specific characteristic or l nature, i.e., whether its a crack or localized corrosion.
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CMED-058617 E. The overlay application to these valves is not subjected to any cyclic loading which may cause fatigue crack growth.
The use of Code Case N-504-1 for the check valve repair will be an acceptable
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repair for a probable root cause of intergranular corrosion or for any of the other possible root causes as discussed below: ,
- 1. Intergranular Corrosion (IGC) - The leak in the 24" cast stainless steel check valve, CK-ES3166, has been attributed to intergranular corrosion 1 (IGC).
IGC is a selective form of corrosion that attacks the grain boundaries with the majority of the grain unaffected. it can affect certain alloys (e.g., several of the austenitic stainless steels) that are highly resistant to general and localized attack. These alloys are made susceptible to IGC by sensitization. Sensitization of stainless steel is the precipitation of chromium carbides _at the grain boundaries which depletes the chrome content ir. the adjacent grain boundary. For regular grade stainless steels this occurs during the welding operation.
The overlay will be a low carbon, high ferrite stainless steel, and will not be sensitized by the welding / overlaying process. Without sensitization IGC cannot occur in the overlay. However, the casting surface below the overlay (and at the ends) will be sensitized. Thus, .
IGC could eventually progress from the leak area horizontally to the end of the overlay and then go upward through the casting surface as 'a leak.
However, this path would be substantially longer than the original through wall flaw. Based on the corrosion rate for the past 25 years, the overlay will last for the life of the plant.
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CMED-058617
- 2. Intergranular Stress Corrosion Cracking (IGSCC) - As with IGC, this mechanism requires a sensitized material. Howevei, to propagate, it requires significant stress perpendicular to the crack. For reasons discussed above, the overlay is immune to IGSCC because it is not sensitized. It also has a high resistance to IGSCC because of the required minimum ferrite content. The weld deposition of the overlay will be performed with the pipe filled with water. This produces a residual compressive stress in the casting material below the overlay.
The compressive stress will mitigate IGSCC crack propagation. Since the weld metal is a ductile stainless steel any possible crack propagation through the overlay would be minimized. Additionally, propagation through the sensitized casting under the overlay is unlikely since there -
is very little through-thickness stress to cause propagation. The overlay will last for the life of the plant.
- 3. Casting or Weld Metal Flaw - The high quality overlay (deposited using the machine gas tungsten arc welding process) will present a new defect-free material as verified by the code case required preservice ultrasonic examination. The design of the overlay is of ample thickness to keep the stresses low and thus prevent stress driven propagation. As discussed in Item 2, the residual compressive stress below the overlay will mitigate flaw propagation. The overlay will last
- for the life of the plant.
- 4. Chemically Induced Pitting Corrosion - The low carbon non-sensitized stainless steel overlay is as resistant to chemical attack or pitting as the casting. The overlay will add another layer of material that the pitting corrosion would have to penetrate. While the overlay only adds additional time for pitting to penetrate, it should be emphasized that Page 6
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l CMED-058617 i
this is the least likely root cause. Chemical analysis of the water and metallurgical examination of the surface replica (as detailed in CMED-058599) effectively makes pitting corrosion improbable as a root cause.
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Effect of the Overlav on the Valve Since there are recordable indications on the casting a seal layer will be deposited as stipulated by the code case. Depositing this seal layer may expose new indications. The Code Case N-504-1 requires liquid penetrant examination to be performed after the seal layer is deposited. Indications greater than 1/16" will be repaired as necessary.
Additionally, the weld overlay will induce residual stress fields and system shrinkage. The IWB-3640 flaw evaluation will be performed using as built conditions and combine these effects with the applied loads to demonstrate the acceptance of the overlay for the life of the plant.
Conclusion The findings presented in Report CMED-058599 show that pitting corrosion is a highly unlikely root cause, however the additional material would extend the time for pitting corrosion to penetrate the overlay. Since these valves are not subject to cyclic loading or brittle fracture, propagation of the flaw through the overlay would have to be driven by a corrosion mechanism. The low carbon stainless steel overlay weld metal has better IGC and IGSCC resistance than the casting. Periodic inservice inspections will monitor any flaw growth or propagation. Therefore, with the exception of pitting corrosion, the Code Page 7
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i Case N-504-1 overlay provides an effective corrective action for each of the stated possible root causes for the life of the plant, b 'coden504 tmp Final Page i
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