|
|
(2 intermediate revisions by the same user not shown) |
Line 17: |
Line 17: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:BBC BROWN BOVERI Welded%otors for Steam Turbines Publication No.CK-T 060 072 E*1 I J*J*J ,t I'I I'hi",.I"'I J h h h t J I'I 4 J~<<L Jh Jg>>'P I A>>&>>4>>A h JJ Jh W Ua,ihi Jhw>>th4ththh+ | | {{#Wiki_filter:BBC Welded%otors BROWN BOVERI for Steam Turbines Publication No. CK-T 060 072 E |
| hhhhhhht IOVthhh h'Wt Ji.IJ.hk>>0"-, J h'004000 6hg-3 0 Rotors for large steam turbines The rotor weld and the welding procedure The rotors for all large BBC turbines consist of a number of disks welded together to form a single solid unit.The high-pressure rotor of a large turbine as shown in Fig.4 contributes 440 MW to the total turbin~enerator output of 1350 MW.When building saturated steam turbines for nuclear power plants with an output of about 1000 MWe, the large component weights of 1800 or 1500 rev/min units be-come very Important.
| | * ,t J |
| In the low-pressure section for example, rotor weights between 150 and 200 tons and even higher are not unusual.With these large rotors the Brown Boverl welded disk design has a very important advantage. | | 1 I'I I |
| The individual rotor components still have moderate weights and the relatively small cross-sections allow the material to be thoroughly forged.Thus a high quality steel is guaranteed with a reduced risk of rejection. | | J* |
| Fig.5 shows the welding of the low-pressure rotor of a 1000 MWe turbine for a nuclear power plant, and Fig.6 shows the same rotor after wefdfng and annealing. | | J I'hi",. |
| Fig.7 shows the various stages of development of the weld preparation during the last 40 years.The deep weld technique adopted for today's rotors has been used since about 1958 (Fig.ld).Using this procedure and BBC's advanced welding methods a rotor is produced where the stress values in the welded areas are similar to those in the base material of the forged disks.Regular tests on rotor welds provide a solid statistical back-ground to the welded rotor design.Microsectlons through rotor welds (Fig.8)are carried out to determine the quality of the weld, the extent of the base material affected by the welding procedure and the mechanical properties of the weld material.Fts.4: Hlsh~ressuro rotor of a 135G Mw aac steam tvelne 4 f sea s introduction
| | h I "' |
| ~~Rotors of medium-sized steam turbines During the first two decades of this century, Brown Boveri used solid torged rotors tor small turbines, and built-up rotors, consisting of a number ot disks shrunk on to a central shaft, for larger units.For small machines the solid forged rotor is still standard, but for the large machines BBC subsequently discarded the shrunk disk design because of Its higher stress levels.Articles from a number ot Independent sources deal with the stress levels and quality of this type of rotor (1, 2, 3J.After 1930 a design was adopted using a number ot disks welded together to form a solid rotor.Thus all the risks inherent in large one-piece torgings were avoided and a high standard of fault detection was achieved.since the individual disks delivered by the steelworks are relatively small and can thus be very thoroughly tested.Fig.1 depicts the cross-section through the rotor of a 60 MW condensing turbine and clearly shows the forgings from which the rotor has been built up.The individual forgings are rough machined and ultrasonically tested at the steelworks, and in addition mechanical tests are carried out on pieces from each disk before delivery is made, to ensure that the mechanical characteristics are achieved.These tests determine the tensile strength, impact strength and yield point of the material.All the disks are subJected to further standard inspection procedures in the workshops, including chemical analy-sis, tensile and impact tests, before machining com-mences.In addition the disks are ultrasonically examined for any internal flaws, such as cracks or inclusions.
| | h h |
| Only when confirmation has been received that all tests have been passed does premachining commence.This con-sists of turning the inner contour ot the disk and the weld preparation contour.The condition of the rotor during this stage of manufacture can be seen in Fig.2.After welding and machining, the rotor has the shape shown in Fig.3.Rg.t: Section through the rotor of a 60 MW condensing turbine.II r ,.~~'1~e It I l r, w4~,~a~Fig.tu Stacking the individual rotor disks in readiness for welding.I Fig.tht Medium<ized condensing tulhine rotor alter machining.
| | t J |
| Brown Boverl's rotor welding technology has been the subject of a number of articles in the technical press j4, 5].The following is a short summary of the manu-facturing procedure.
| | I I J J |
| Argon arc welding is used for the root weld.Fig.5 shows the assembled rotor in the vertical position.The required preheat temperature is obtained using in-duction heating.After welding the root, filling is carried out on a hori-zontal lathe using submerged arc welding.Fig.9 gives an impression of this stage of the welding process and shows the equipment for preheating and maintaining the temperature of the rotor.Automatic methods have been used for the two welding processes-the argon arc root weld and the submerged arc filler weld-for many years and thus the same quality is achieved In all the welds of each rotor.After welding, the complete rotor is subjected to heat treatment ln an oven (Fig.6).The surfaces close to the welds are then machined to permit ultrasonic exami-nation of the welded zone.Fltf.S: Contptetlntf the llllar weld of a rotor on the weldlntf lathe.l.
| | 'I 4 |
| ~i@gl j i'~'lOvl1I lSQOEI Fig.5: Making the root weld on the 200 t fo~ressure rotor of an 1t00 MW nuclear turbine..@RE'l WOwN KlvCAI>4M Fig.6: Lo~ressure rotor ol an 1 t00 MW nuclear turbfne alter welding and stress relieving.
| | J h |
| Fig.8: Mlcrosectlon ol a rotor weld.(-" S t Fig.7: BBC weld preparation shapes: development during the last 40 years.'n!IN.l The use of modern calculation methods for the design of rotors Summary To design a rotor making use of the latest technologies,'
| | ~ <<L Jh Jg>>' P I A>>&>> 4>>A h JJ Jh W Ua,ihi Jhw>>th4ththh+ h'Wt Ji. IJ.hk>> 0"-, |
| large computer is used.Finite element analysis allows the operating stresses in all parts of the rotor to be accurately calculated. | | hhhhhhht IOVthhh 6hg-3 |
| Fig.10 shows the mesh used for the intermediate-pressure rotor of a 500 MW turbine to determine Its Isothermal field and operating stresses.For the same rotor the combined stresses due to the rotor speed and temperature (comparative stress)are shown under full load conditions In Fig.11.All points on any line in the figure have the same comparative stress level.Extensive information Is available on the stresses in steam turbine rotors during start up.A summary of this information is given in reference[7).Brown Boveri steam turbine rotors are designed, manu-factured and inspected in such a way that a maximum of safety during operation can be guaranteed. | | '004000 |
| The welded rotor has the following positive characteristics: | | |
| -exceptionally large flexural rigidity, favourable for a smooth running characteristic,-low stress levels since the solid disks have no central bore[3],-good quality of all highly stressed sections since the small disks can be more thoroughly forged,;simple inspection of the individual pieces before welding and thus a high degree of safety against material defects,-favourable heat flow during transient operation with no appreciable axial stresses at the centre of the rotor since only a tw~imenslonal stress pattern exists.Flp.t0: The linite element mesh for the determination ol the isothermal field and the operatln0 stresses of a Bao rotor.I I,~r I I I Flp.11: Stresses ln the intermediate pressure rotor ol a aBC 000 MW turtrfne durtn0 steady-state operation.
| | 0 Rotors for large steam turbines The rotor weld and the welding procedure The rotors for all large BBC turbines consist of a number Fig. 7 shows the various stages of development of the of disks welded together to form a single solid unit. The weld preparation during the last 40 years. The deep weld high-pressure rotor of a large turbine as shown in Fig. 4 technique adopted for today's rotors has been used since contributes 440 MW to the total turbin~enerator output about 1958 (Fig. ld). Using this procedure and BBC's of 1350 MW. advanced welding methods a rotor is produced where When building saturated steam turbines for nuclear the stress values in the welded areas are similar to power plants with an output of about 1000 MWe, the large those in the base material of the forged disks. Regular component weights of 1800 or 1500 rev/min units be- tests on rotor welds provide a solid statistical back-come very Important. In the low-pressure section for ground to the welded rotor design. Microsectlons through example, rotor weights between 150 and 200 tons and rotor welds (Fig.8) are carried out to determine the even higher are not unusual. With these large rotors the quality of the weld, the extent of the base material Brown Boverl welded disk design has a very important affected by the welding procedure and the mechanical advantage. The individual rotor components still have properties of the weld material. |
| | moderate weights and the relatively small cross-sections allow the material to be thoroughly forged. Thus a high quality steel is guaranteed with a reduced risk of rejection. |
| | Fig. 5 shows the welding of the low-pressure rotor of a 1000 MWe turbine for a nuclear power plant, and Fig. 6 shows the same rotor after wefdfng and annealing. |
| | Fts. 4: Hlsh~ressuro rotor of a 135G Mw aac steam tvelne 4 |
| | f sea s |
| | |
| | ~ ~ |
| | introduction Rotors of medium-sized steam turbines During the first two decades of this century, Brown Boveri Fig.1 depicts the cross-section through the rotor of a used solid torged rotors tor small turbines, and built-up 60 MW condensing turbine and clearly shows the forgings rotors, consisting of a number ot disks shrunk on to a from which the rotor has been built up. The individual central shaft, for larger units. For small machines the forgings are rough machined and ultrasonically tested at solid forged rotor is still standard, but for the large the steelworks, and in addition mechanical tests are machines BBC subsequently discarded the shrunk disk carried out on pieces from each disk before delivery is design because of Its higher stress levels. Articles from made, to ensure that the mechanical characteristics are a number ot Independent sources deal with the stress achieved. These tests determine the tensile strength, levels and quality of this type of rotor (1, 2, 3J. impact strength and yield point of the material. |
| | After 1930 a design was adopted using a number ot disks All the disks are subJected to further standard inspection welded together to form a solid rotor. Thus all the risks procedures in the workshops, including chemical analy-inherent in large one-piece torgings were avoided and a sis, tensile and impact tests, before machining com-high standard of fault detection was achieved. since the mences. In addition the disks are ultrasonically examined individual disks delivered by the steelworks are relatively for any internal flaws, such as cracks or inclusions. Only small and can thus be very thoroughly tested. when confirmation has been received that all tests have been passed does premachining commence. This con-sists of turning the inner contour ot the disk and the weld preparation contour. The condition of the rotor during this stage of manufacture can be seen in Fig.2. After welding and machining, the rotor has the shape shown in Fig.3. |
| | Rg. t: Section through the rotor of a 60 MW condensing turbine. |
| | 1 ~ e ItI r |
| | II |
| | ,.~~' l r, w4 ~,~a~ |
| | Fig. tu Stacking the individual rotor disks in readiness for welding. |
| | I Fig.tht Medium<ized condensing tulhine rotor alter machining. |
| | |
| | Brown Boverl's rotor welding technology has been the After welding the root, filling is carried out on a hori-subject of a number of articles in the technical press zontal lathe using submerged arc welding. Fig. 9 gives j4, 5]. The following is a short summary of the manu- an impression of this stage of the welding process facturing procedure. and shows the equipment for preheating and maintaining Argon arc welding is used for the root weld. Fig.5 the temperature of the rotor. |
| | shows the assembled rotor in the vertical position. The Automatic methods have been used for the two welding required preheat temperature is obtained using in- processes the argon arc root weld and the submerged duction heating. arc filler weld for many years and thus the same quality is achieved In all the welds of each rotor. |
| | After welding, the complete rotor is subjected to heat treatment ln an oven (Fig. 6). The surfaces close to the welds are then machined to permit ultrasonic exami-nation of the welded zone. |
| | Fltf. S: Contptetlntf the llllar weld of a rotor on the weldlntf lathe. |
| | l. |
| | |
| | ~i@ |
| | gl j |
| | i' |
| | ~ |
| | 'l .@RE lOvl1I lSQOEI WOwN KlvCAI >4M Fig. 5: Making the root weld on the 200 t fo~ressure rotor of an Fig. 6: Lo~ressure rotor ol an 1 t00 MW nuclear turbfne alter 1t00 MW nuclear turbine. welding and stress relieving. |
| | Fig. 8: Mlcrosectlon ol a rotor weld. |
| | (-" |
| | S t |
| | Fig. 7: BBC weld preparation shapes: development during the last n! IN.l 40 years. |
| | |
| | The use of modern calculation Summary methods for the design of rotors To design a rotor making use of the latest technologies,' Brown Boveri steam turbine rotors are designed, manu-large computer is used. Finite element analysis allows factured and inspected in such a way that a maximum of the operating stresses in all parts of the rotor to be safety during operation can be guaranteed. The welded accurately calculated. Fig.10 shows the mesh used for rotor has the following positive characteristics: |
| | the intermediate-pressure rotor of a 500 MW turbine exceptionally large flexural rigidity, favourable for a to determine Its Isothermal field and operating stresses. smooth running characteristic, For the same rotor the combined stresses due to the low stress levels since the solid disks have no central rotor speed and temperature (comparative stress) are bore [3], |
| | shown under full load conditions In Fig.11. All points good quality of all highly stressed sections since the on any line in the figure have the same comparative small disks can be more thoroughly forged, stress level. |
| | Extensive information Is available on the stresses in |
| | ; simple inspection of the individual pieces before welding and thus a high degree of safety against steam turbine rotors during start up. A summary of this material defects, information is given in reference [7). favourable heat flow during transient operation with no appreciable axial stresses at the centre of the rotor since only a tw~imenslonal stress pattern exists. |
| | Flp. t0: The linite element mesh for the determination ol the isothermal field and the operatln0 stresses of a Bao rotor. |
| | I I, |
| | ~ r I I I |
| | Flp. 11: Stresses ln the intermediate pressure rotor ol a aBC 000 MW turtrfne durtn0 steady-state operation. |
| BBC BROWN BOVERI BBC Brown, Boverl 8 Company, Ltd., CH-5401 Baden/Switzerland printed In switzerland rrrtrt-20004) | | BBC BROWN BOVERI BBC Brown, Boverl 8 Company, Ltd., CH-5401 Baden/Switzerland printed In switzerland rrrtrt-20004) |
| Classification rto.01st/ot02}} | | Classification rto. 01st/ot02}} |
Similar Documents at Cook |
---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML17335A5451999-09-28028 September 1999 Rev 1 to Containment Sump Level Design Condition & Failure Effects Analysis for Potential Draindown Scenarios. ML17326A1481999-09-17017 September 1999 Independent Review of Control Rod Insertion Following Cold Leg Lbloca,Dc Cook,Units 1 & 2. ML17335A5461999-08-0202 August 1999 Rev 0 to Evaluation of Cook Recirculation Sump Level for Reduced Pump Flow Rates. ML17325B5671999-03-0202 March 1999 Summary of Unit 1 Steam Generator Layup Chemistry from 980101 to 990218. ML17325B5661999-01-27027 January 1999 Unit 1 Steam Generator Layup Chemistry Out of Specification During 970924 Through 971231. ML17325B4511998-12-15015 December 1998 Rev 1 to ER-98-009, Preliminary Waste Characterization of DC Cook SG Lower Assemblies. ML17335A2741998-09-0101 September 1998 Rev 0 to ER-98-009, Preliminary Waste Characterization of DC Cook SG Lower Assemblies. ML17335A1921998-07-10010 July 1998 Non-proprietary Cook Unit 1 SG Operability Re-Review. ML17334A6151998-01-0606 January 1998 Containment Sump Operability Determination. ML17333B0921997-10-0909 October 1997 MAAP4 Analyses of DC Cook Containment Response to Small Break Loca. ML17333B0041997-08-14014 August 1997 Responses to RAI on Holtec Rept HI-951389 DC Cook Spent Fuel Pool. ML17333A9561997-07-21021 July 1997 Generator U1R97 Condition Monitoring & Operational Assessment. ML17333A9571997-07-21021 July 1997 Generators U1R97 2 Volt Interim Plugging Criteria Rept. ML17333A5641996-08-31031 August 1996 Final Rept, Reactor Vessel Nozzle Bore Data Evaluation. ML17333A2821995-12-31031 December 1995 DC Cook Nuclear Plant USI A-46 Seismic Evaluation Rept. ML17333A2801995-12-31031 December 1995 DC Cook Nuclear Plant USI A-46 Safe Shutdown Equipment List Rept. ML17333A2761995-12-31031 December 1995 DC Cook Unit 1 1995 Interim Plugging Criteria 90 Day Rept. ML17333A2891995-12-22022 December 1995 Updated Thermal-Hydraulic Analysis of Spent Nuclear Fuel Pool DC Cook Nuclear Plant Indiana Michigan Power Co. ML17333A3251995-11-30030 November 1995 Criticality Analysis of DC Cook Nuclear Plant New Fuel Storage Vault W/Credit for Integral Fuel Burnable Absorbers, for Nov 1995 ML17333A2831995-11-0606 November 1995 DC Cook Nuclear Plant USI A-46 Relay Evaluation Rept. ML17333A3321995-07-31031 July 1995 DC Cook Nuclear Plant Boric Acid Concentration Reduction. ML17333A9051995-07-25025 July 1995 Rev 0 to NRC GL 86-10 Technical Evaluation App R Section III.G.2(b) Twenty Foot Separation Between Redundant Components W/No Intervening Combustibles,Fire Zone 6M & Fire Zone 6S. ML17332A8021995-06-15015 June 1995 EDG Load-Run Performance & Reliability During Short & Long Duration Test Periods TER ML17333A9061995-06-0505 June 1995 Rev 0 to NRC GL 86-10 Technical Evaluation,App R Section III.G.2(b) Twenty Foot Separation Between Redundant Components W/No Intervening Combustibles Fire Zone 44N & Fire Zone 44S. W/Two Oversize Drawings ML17332A7611995-05-0505 May 1995 Svc Water Sys Operational Performance Insp (Swsopi) Self- Assessment Rept. ML17332A5841995-02-28028 February 1995 DC Cook Nuclear Plant IPE for External Events Revised Fire Pra. ML17332A5851995-02-28028 February 1995 DC Cook Nuclear Plant Units 1 & 2 Addendum to Seismic PRA Notebook. ML17332A7121994-12-0505 December 1994 Evaluation of Cook Ipe/Hra Matls. ML17332A3731994-10-24024 October 1994 Assessment of Indications in DC Cook Unit 2 Head Penetration 75. ML17332A4141994-08-25025 August 1994 Rev 0 to HI-941183, Spent Nuclear Fuel Pool Thermal- Hydraulic Analysis Rept for DC Cook Nuclear Plant. ML17331B4301994-06-13013 June 1994 Rev 0 to DC Cook Nuclear Plant E-Plan Classification Vs NUMARC/NESP-007 Deviation Basis Document. ML17331B4391994-06-0909 June 1994 1 Cycle 13 IPC Assessment. ML17331B1331993-12-31031 December 1993 DC Cook Units 1 & 2 Main Steam Safety Valve Lift Setpoint Tolerance Relaxation. ML17331B1411993-12-0909 December 1993 Suppl Info for DC Cook Unit 1 Ipc. ML17331B1691993-12-0707 December 1993 Reactor Protection & Control Process Instrumentation Replacement Project at Donald C Cook Nuclear Plant Units 1 & 2,Reactor Protection Sys Functional Diversity Assessment. ML17331B1961993-09-30030 September 1993 Control Rod Misalignment Analysis. ML17331A0631993-02-28028 February 1993 DC Cook Nuclear Plant Hydrogen Control Evaluation Summary Rept. ML17329A7141992-12-16016 December 1992 DC Cook Nuclear Plant Units 1 & 2 Reliability & Mtbf Analysis Reactor Protection & Control Sys Replacement Project. ML17329A7161992-12-16016 December 1992 DC Cook Nuclear Plant Units 1 & 2 Summary Rept for Response Time Evaluations Reactor Protection & Control Sys Replacement Project. ML17329A7071992-12-16016 December 1992 Engineering Analysis of Temperature & Humidity Effects on Foxboro Spec 200 Instrumentation Reactor Protection & Control Sys Replacement Project. ML17329A7091992-12-16016 December 1992 Preliminary Emi/Rfi Evaluation Aepsc Reactor Protection & Control Sys Replacement Project. ML17329A7131992-12-16016 December 1992 DC Cook Nuclear Plant Units 1 & 2 Failure Modes & Effect Analysis (FMEA) Protection Set 1 Foxboro Spec 200 Reactor Protection & Control Sys Replacement Project. ML17329A7111992-12-16016 December 1992 Engineering Analysis of Grounding Issues Reactor Protection Process Control Group Replacement Project DC Cook Nuclear Plants Units 1 & 2. ML17329A7101992-12-16016 December 1992 DC Cook Nuclear Plant Units 1 & 2 Summary Rept for Sys Power Quality Evaluation Reactor Protection & Control Sys Replacement Project. ML17329A7171992-12-15015 December 1992 Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plant Units 1 & 2 TS Compliance Assessment. ML17329A7121992-12-15015 December 1992 Regulatory Requirements & Industry Standards Associated W/Reactor Protection Portion of Reactor Protection & Control Process Instrumentation Replacement Project. ML17329A7201992-12-14014 December 1992 Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plant Units 1 & 2 Reactor Protection Sys Functional Diversity Assessment. ML17329A7181992-12-14014 December 1992 Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plants Units 1 & 2 Qualification Compliance. ML17329A7151992-12-10010 December 1992 Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plant Units 1 & 2 Functional Requirement Summary. ML17329A7191992-12-10010 December 1992 Reactor Protection & Control Process Instrumentation Replacement Project at DC Cook Nuclear Plant Units 1 & 2 Test Program Summary. 1999-09-28
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17335A5641999-10-18018 October 1999 LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr ML17335A5531999-10-0707 October 1999 LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented ML17335A5631999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 1.With 991012 Ltr ML17335A5621999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 2.With 991012 Ltr ML17335A5481999-09-30030 September 1999 Non-proprietary DC Cook Nuclear Plant Units 1 & 2 Mods to Containment Sys W SE (Secl 99-076,Rev 3). ML17335A5451999-09-28028 September 1999 Rev 1 to Containment Sump Level Design Condition & Failure Effects Analysis for Potential Draindown Scenarios. ML17326A1291999-09-17017 September 1999 LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary ML17326A1481999-09-17017 September 1999 Independent Review of Control Rod Insertion Following Cold Leg Lbloca,Dc Cook,Units 1 & 2. ML17326A1211999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 2.With 990915 Ltr ML17326A1201999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 1.With 990915 Ltr ML17326A1121999-08-27027 August 1999 LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed ML17326A1011999-08-26026 August 1999 LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs ML17326A0911999-08-16016 August 1999 LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4 ML17326A0771999-08-0404 August 1999 LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830 ML17335A5461999-08-0202 August 1999 Rev 0 to Evaluation of Cook Recirculation Sump Level for Reduced Pump Flow Rates. ML17326A0871999-07-31031 July 1999 Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Unit 1.With 990812 Ltr ML17326A0861999-07-31031 July 1999 Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Units 2.With 990812 Ltr ML17326A0741999-07-29029 July 1999 LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves ML17326A0661999-07-26026 July 1999 LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr ML17326A0651999-07-22022 July 1999 LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis ML17326A0491999-07-13013 July 1999 LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr ML17326A0331999-07-0101 July 1999 LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written ML17326A0511999-06-30030 June 1999 Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 2.With 990709 Ltr ML17326A0501999-06-30030 June 1999 Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 1.With 990709 Ltr ML17326A0151999-06-18018 June 1999 LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified ML17325B6421999-06-0101 June 1999 LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed ML17325B6311999-06-0101 June 1999 LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions ML17326A0061999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Dcp.With 990609 Ltr ML17326A0071999-05-31031 May 1999 Monthly Operating Rept for May 1999 for DC Cook Nuclear Plant,Unit 2.With 990609 Ltr ML17325B6351999-05-28028 May 1999 LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions ML17265A8231999-05-24024 May 1999 LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made ML17325B6001999-05-20020 May 1999 LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed ML17325B5861999-05-10010 May 1999 LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised ML17325B5811999-05-0404 May 1999 LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared ML17325B5771999-05-0303 May 1999 LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design ML17335A5301999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 1.With 990508 Ltr ML17335A5291999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 2.With 990508 Ltr ML17325B5581999-04-16016 April 1999 LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold ML17325B5471999-04-12012 April 1999 LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation ML17325B5321999-04-0707 April 1999 LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate ML17325B5161999-04-0101 April 1999 LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures ML17325B5491999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant Unit 2.With 990408 Ltr ML17325B5441999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant,Unit 1.With 990408 Ltr ML17325B5221999-03-29029 March 1999 LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing ML17325B4801999-03-18018 March 1999 LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling ML17325B4741999-03-18018 March 1999 LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed ML17325B5671999-03-0202 March 1999 Summary of Unit 1 Steam Generator Layup Chemistry from 980101 to 990218. ML17325B4631999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Power Station,Unit 2.With 990308 Ltr ML17325B4621999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Plant,Unit 1.With 990308 Ltr ML17325B4571999-02-24024 February 1999 LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors 1999-09-30
[Table view] |
Text
BBC Welded%otors BROWN BOVERI for Steam Turbines Publication No. CK-T 060 072 E
1 I'I I
J*
J I'hi",.
h I "'
h h
t J
I I J J
'I 4
J h
~ <<L Jh Jg>>' P I A>>&>> 4>>A h JJ Jh W Ua,ihi Jhw>>th4ththh+ h'Wt Ji. IJ.hk>> 0"-,
hhhhhhht IOVthhh 6hg-3
'004000
0 Rotors for large steam turbines The rotor weld and the welding procedure The rotors for all large BBC turbines consist of a number Fig. 7 shows the various stages of development of the of disks welded together to form a single solid unit. The weld preparation during the last 40 years. The deep weld high-pressure rotor of a large turbine as shown in Fig. 4 technique adopted for today's rotors has been used since contributes 440 MW to the total turbin~enerator output about 1958 (Fig. ld). Using this procedure and BBC's of 1350 MW. advanced welding methods a rotor is produced where When building saturated steam turbines for nuclear the stress values in the welded areas are similar to power plants with an output of about 1000 MWe, the large those in the base material of the forged disks. Regular component weights of 1800 or 1500 rev/min units be- tests on rotor welds provide a solid statistical back-come very Important. In the low-pressure section for ground to the welded rotor design. Microsectlons through example, rotor weights between 150 and 200 tons and rotor welds (Fig.8) are carried out to determine the even higher are not unusual. With these large rotors the quality of the weld, the extent of the base material Brown Boverl welded disk design has a very important affected by the welding procedure and the mechanical advantage. The individual rotor components still have properties of the weld material.
moderate weights and the relatively small cross-sections allow the material to be thoroughly forged. Thus a high quality steel is guaranteed with a reduced risk of rejection.
Fig. 5 shows the welding of the low-pressure rotor of a 1000 MWe turbine for a nuclear power plant, and Fig. 6 shows the same rotor after wefdfng and annealing.
Fts. 4: Hlsh~ressuro rotor of a 135G Mw aac steam tvelne 4
f sea s
~ ~
introduction Rotors of medium-sized steam turbines During the first two decades of this century, Brown Boveri Fig.1 depicts the cross-section through the rotor of a used solid torged rotors tor small turbines, and built-up 60 MW condensing turbine and clearly shows the forgings rotors, consisting of a number ot disks shrunk on to a from which the rotor has been built up. The individual central shaft, for larger units. For small machines the forgings are rough machined and ultrasonically tested at solid forged rotor is still standard, but for the large the steelworks, and in addition mechanical tests are machines BBC subsequently discarded the shrunk disk carried out on pieces from each disk before delivery is design because of Its higher stress levels. Articles from made, to ensure that the mechanical characteristics are a number ot Independent sources deal with the stress achieved. These tests determine the tensile strength, levels and quality of this type of rotor (1, 2, 3J. impact strength and yield point of the material.
After 1930 a design was adopted using a number ot disks All the disks are subJected to further standard inspection welded together to form a solid rotor. Thus all the risks procedures in the workshops, including chemical analy-inherent in large one-piece torgings were avoided and a sis, tensile and impact tests, before machining com-high standard of fault detection was achieved. since the mences. In addition the disks are ultrasonically examined individual disks delivered by the steelworks are relatively for any internal flaws, such as cracks or inclusions. Only small and can thus be very thoroughly tested. when confirmation has been received that all tests have been passed does premachining commence. This con-sists of turning the inner contour ot the disk and the weld preparation contour. The condition of the rotor during this stage of manufacture can be seen in Fig.2. After welding and machining, the rotor has the shape shown in Fig.3.
Rg. t: Section through the rotor of a 60 MW condensing turbine.
1 ~ e ItI r
II
,.~~' l r, w4 ~,~a~
Fig. tu Stacking the individual rotor disks in readiness for welding.
I Fig.tht Medium<ized condensing tulhine rotor alter machining.
Brown Boverl's rotor welding technology has been the After welding the root, filling is carried out on a hori-subject of a number of articles in the technical press zontal lathe using submerged arc welding. Fig. 9 gives j4, 5]. The following is a short summary of the manu- an impression of this stage of the welding process facturing procedure. and shows the equipment for preheating and maintaining Argon arc welding is used for the root weld. Fig.5 the temperature of the rotor.
shows the assembled rotor in the vertical position. The Automatic methods have been used for the two welding required preheat temperature is obtained using in- processes the argon arc root weld and the submerged duction heating. arc filler weld for many years and thus the same quality is achieved In all the welds of each rotor.
After welding, the complete rotor is subjected to heat treatment ln an oven (Fig. 6). The surfaces close to the welds are then machined to permit ultrasonic exami-nation of the welded zone.
Fltf. S: Contptetlntf the llllar weld of a rotor on the weldlntf lathe.
l.
~i@
gl j
i'
~
'l .@RE lOvl1I lSQOEI WOwN KlvCAI >4M Fig. 5: Making the root weld on the 200 t fo~ressure rotor of an Fig. 6: Lo~ressure rotor ol an 1 t00 MW nuclear turbfne alter 1t00 MW nuclear turbine. welding and stress relieving.
Fig. 8: Mlcrosectlon ol a rotor weld.
(-"
S t
Fig. 7: BBC weld preparation shapes: development during the last n! IN.l 40 years.
The use of modern calculation Summary methods for the design of rotors To design a rotor making use of the latest technologies,' Brown Boveri steam turbine rotors are designed, manu-large computer is used. Finite element analysis allows factured and inspected in such a way that a maximum of the operating stresses in all parts of the rotor to be safety during operation can be guaranteed. The welded accurately calculated. Fig.10 shows the mesh used for rotor has the following positive characteristics:
the intermediate-pressure rotor of a 500 MW turbine exceptionally large flexural rigidity, favourable for a to determine Its Isothermal field and operating stresses. smooth running characteristic, For the same rotor the combined stresses due to the low stress levels since the solid disks have no central rotor speed and temperature (comparative stress) are bore [3],
shown under full load conditions In Fig.11. All points good quality of all highly stressed sections since the on any line in the figure have the same comparative small disks can be more thoroughly forged, stress level.
Extensive information Is available on the stresses in
- simple inspection of the individual pieces before welding and thus a high degree of safety against steam turbine rotors during start up. A summary of this material defects, information is given in reference [7). favourable heat flow during transient operation with no appreciable axial stresses at the centre of the rotor since only a tw~imenslonal stress pattern exists.
Flp. t0: The linite element mesh for the determination ol the isothermal field and the operatln0 stresses of a Bao rotor.
I I,
~ r I I I
Flp. 11: Stresses ln the intermediate pressure rotor ol a aBC 000 MW turtrfne durtn0 steady-state operation.
BBC BROWN BOVERI BBC Brown, Boverl 8 Company, Ltd., CH-5401 Baden/Switzerland printed In switzerland rrrtrt-20004)
Classification rto. 01st/ot02