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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
PALISADES NUCLEAR PLANT EA-SC-93-087-02 ENGINEERING ANALYSIS COVER SHEET Total Nl.llt>er of Sheets 4 itle i.ilf bead welding for modifications to TE-0101 and TE-0102 INITIATION AND REVIEW Calculation Status Preliminary Pending Final Superseded Initiated D
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-OBJECTIVE This EA is written to allow the use of ABB Combustion Engineering (CE) welding procedure specification (WPS) SMA-3.43-937 for modification of TE-0102. In addition, this EA shall define the manner in which the half bead welding rules of ASME Section XI are applied for the modification of both TE-0101 and TE-0102. Specifically, the use of the ferritic rules for the base metal requirements and the use of the dissimilar metal weld rules for the fi 11 er metal and examination requirements. It should be noted that this EA only applies to
_the half bead welding portion of SMA-3.43-937.
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PALISADES NUCLEAR PLANT EA-SC-93-087-02 M<<"EtWS I IIliDSS ANALYSIS CONTINUATION SHEET Sheet _2_ Rev # _;O=-----
Reference/COllTilent INPUT
- 1. ASME Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components", 1983 edition including the Summer 1983 addenda. *
- 2. ASME Section III, "Rules for Construction of Nuclear Power Plant Components", Subsection NB, 1986 edition.
- 3. ASME Section IX, "Welding and Brazing Qualifications", 1993 edition.
ASSUMPTIONS MAJOR ASSUMPTIONS None MINOR ASSUMPTIONS None LYSIS CKGROUND Two thermowell nozzles on the pressurizer (T-72) require modification to eliminate leak paths due to axial cracks. Because the nozzles are welded only to the inside of the vessel, the leak path is through the nozzle wall at a location beyond this weld. Therefore, the nozzles will be modified by first welding a pad of inconel filler material on the vessel around the nozzle on the outside of the vessel penetration and then welding the nozzle to the pad.
The material used for th~ vessel head and shell course is SA533 Grade B Class 1. Per ASME Section III (SC III) rules, welding on the head or shell course would normally require a postweld heat treatment (PWHT) at 1100°F to 1250°F. Since PWHT at these temperatures is not practical, SC XI provides alternate rules for welding on this material without a full PWHT. This welding technique is called "half bead welding".
CONCERNING THE MODIFICATION TO TE-0102 One of the rules for qualification of a half bead welding procedure is that the procedure test coupon material be of the same specification type, grade, and class. CE WPS SMA-3.43-937 was qualified for half bead welding on SA533 Grade. B Class 1 material. As stated above, this is the same material as used for the pressurizer head and shell course.
- --~ever, a welded boss of E8018-G filler metal (A No. 10 chemistry) sts at the location of TE-0102. In othe~ words, the modification d will be made on the E8018-G boss not on the vessel shell course proper.
PALISADES NUCLEAR PLANT EA-SC-93-087-02 ANALYSIS CONTINUATION SHEET Sheet _3_ Rev # -'o=<----
Reference/COllme t IX IWB-4320 states that "Repair to P-Nos. 1, 3, 12A, 128, 12C base materials and associated welds may be made by welding in accordance with Section III without the specified postweld heat treatment requirements of NB-4622, provided the requirements of IWB-4321 through IWB-4324 are met." The E8018-G boss is an "associated weld". It should be noted that the corresponding SC III paragraph (NB-4622.9) does not use the term "associated welds" but specifically "A-No. 1, 2, 10, 11 weld filler metal".
A No. 10 chemistry would best fit as a P No. 3 Group 3 material. SA533 Grade B Class 1 (SA533) is also a P No. 3 Group 3 material. Although SC XI is very restrictive with regards to qualification coupon material, SC Ill, which has nearly identical rules for half bead welding (called temper bead welding in SC III), only requires that the material used for qualification of half bead (temper bead) welding be of the same P No.
and Group No.
The main difference between the E8018-G boss' and SA533 is nickel content. The E8018-G deposit has a higher nickel content. All else being equal, increases in nickel content correspond to increases in toughness and decreases in hardenability. Welding on the E8018-G boss should be less of a concern from a toughness and hardenability point of
- w than welding on SA533. In other words, qualification on SA533 te is more conservative than the actual application of welding on the
_ 018-G boss.
CONCERNING APPLICATION OF HALF BEAD RULES SC XI rules for half bead welding are broken up into two categories for pressure boundary materials. These categories are for restoring ferritic only base and\or weld metal and for restoring welds between ferritic and austenitic or nickel metals.
Basically both sets of rules are very similar. The only real difference is in the choice of filler metal and the preheat/interpass temperatures.
While the pressurizer base metal is clearly ferritic, the filler metal to be used of the modifications is inconel (non-ferritic, F-43). For this modification portions of both sets of rules apply. However, when combined, these "portions" will address all of the concerns of either set of rules.
Because the filler metal being used is inconel, the general requirements of IWB-4341 are more applicable. This paragraph (and the corresponding ferritic general requirements) concern the control of filler metal.
For welding qualifications, IWB-4342 is more applicable. This paragraph references most of the requirements of the corresponding ferritic paragraph (IWB-4322) but is modified to take into account the non-
&~~ritic filler metal.
ause the vessel base metal is ferritic, paragraph IWB-4323 should apply. The use of this paragraph will allow higher preheat and interpass temperatures which will help prevent underbead cracking and reduce residual stresses .. While paragraph IWB-4343 would have set lower
PALISADES NUCLEAR PLANT EA-SC-93-087-02 ANALYSIS CONTINUATION SHEET Sheet _4_ Rev # _o~--
ere I 011111ent eheat and interpass temperatures (especially outside the 3/16" layer covering the ferritic material), these higher temperatures are not a concern to the inconel filler metal as would be the case for austenitic stainless steel filler metals. (It should be noted that since inconel filler metal is used, the requirement of part (c) concerning removal of a final reinforcement layer to temper the final layer does not apply.)
For examination requirements, IWB-4344 is more applicable. Once a~ain this is due to the use of inconel filler metal.
CONCLUSION The welded boss in place at TE-0102 is an "associated weld" with an analysis comparable to P No. 3 Group 3 material, as described in IWB-4320. Therefore, SMA-3.43-937 is qualified for welding on this boss using the half bead welding technique.
The modifications to TE-0101 and TE-0102 both involve the use of the half bead welding technique. Both modifications use an inconel filler metal on a ferritic base metal. Because of the manner in which SC XI splits the rules for making half bead welds, the requirements for making these modifications do not fit neatly into a single category as provided hv SC XI. In fact strict adherence to either category is impractical.
9, ever, it is also necessary to address all of the code concerns for ing a half bead weld. Therefore, the applicable paragraphs for the f bead welding portion of the modifications to TE-0101 and TE-0102 are IWB-4341, IWB-4342, IWB-4323, and IWB-4344.