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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 C Consumers Power Company Palisades Plant Docket 50-255 MOVATS - SWITCH ADJUSTMENT POLICIES & JUSTIFICATIONS January 15, 1988 aao12boo29 g~gAA~ss PDR ADOCK PDR Pages 5 G
-OC0188-0008-NL04
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ATTACHMENT C Switch Adjustment Policies And Justifications This phase of the program defines the technical basis for establishing torque and limit switch setpoints. A given control switch may be set to a number of possible positions. The most appropriate setting will be selected and switch setting procedures revised after a review of the valve function, operator and valve design and over Plant policies. The following are the setpoint methods and technical justifications that will be considered for implementation during the control circuit review pro.cess. In each case, the method to be used by Palisades on most valves will be identified.
II-A Open Torque Switches The open torque switch acts to alert Plant personnel of mechanical problems with the valve or operator. The torque switch also provides some element of protection if the open limit switch fails to open. Historical data has shown that open limit switch failures are extremely rare.
Typically, the open torque switch is set to actuate at a thrust value above the calculated unseating load (including maximum design differential pressure loads). During valve unseating, the initial load peak (cracking load) may be of a high enough level to cause the torque switch to trip. Because of this peak, the torque switch must be electrically bypassed during this phase of
One acceptable approach (already evaluated by Palisades as a viable approach) is to eliminate the open torque switch from the control circuit. From a maintenance point of view, the "alerting" function of the open torque switch trip is not necessary if valve/operator condition is monitored using some other means to provide adequate indication of developing mechanical degradations (ie, MOVATS MCC System) *.
As an alternative (already evaluated by Palisades), the open torque switch will be wired into the control circuit and set to trip at a value greater than the load calculated for valve unseating. To establish the torque switch setpoint, the opening thrust value for full differential pressure conditions must be established accurately.
II-B Open Limit Switches The open limit switch must be adjusted to prevent inadvertent backseating of the valve. (Conditions and precautions to be observed when intentionally backseating a valve electrically are addressed in the discussion of open torque switch settings.)
Typically, the open limit switch will be set at approximately 90 percent of stroke from the close-to-open position. It is recognized that the amount of
..
2 stem travel after limit switch trip is influenced by the inertia of the MOV assembly, valve design and delay in motor contactor drop out after actuation of
- the open limit switch. Therefore, a specific setpoint for the open limit switch cannot be established. Instead, the following process will be used:
The limit switch will be set initially for 90-92 percent of the full open stroke. The valve will then be cycled open and allowed to trip electrically. Plant personnel will then place the operator in manual and continue to open the valve using the handwheel. If the valve can be opened an additional amount past the coastdown position, it can be assumed that the valve has hit the backseat. In the unlikely event that the valve has inadvertently backseated, a MOVATS signature analysis test will be conducted and the stem loading and subsequent stem stress levels will be evaluated. The limit switch setting will then be reduced in two percent increments and the valve will be cycled and checked until it is verified that the disc is not coasting into the backseat.
II-C Close-To-Open Torque Bypass Limit Switch The close-to~open torque bypass limit switch prevents torque switch actuation during the high loading condition normally experienced when the valve disc is "cracked" from its seat (Tc - see Figure 2). From an operational standpoint, many switch settings are acceptable, depending on utility operating and maintenance policies. Operator loading conditions during the opening cycle must be examined to understand technical justifications for each acceptable setting *
- Figure 1 shows a typical stem thrust and control switch actuation signature for a valve going from the close-to-open position with zero differential pressure across the valve. Figure 2 is the same basic signature modified to show bypass switch actuation at 5-10 percent of valve stroke (based on stem movement).
Historically, it is believed that the 5-10 percent _switch setting would encompass the initial valve unseating. After the valve began to pass fluid, the high loading conditions would decrease rapidly. This theory was generally accepted even though full pressure and flow data were not available to validate such an assumption.
Figure 3 depicts a thrust signature from the same valve shown in Figure 2. The changes in the signature characteristics result from differential pressure across the valve. With the typical bypass switch setting of 5-10 percent of stroke, it is clear that the torque switch may not be bypassed during the full unseating process. However, Figure 3 demonstrates that the "cracking load" (Tc) occurrs early enough in the open cycle that the 5-10 percent bypass encompasses this loading condition.
Data from tests with full and partial differential pressure conditions (Table
- 1) indicates that the cracking.load condition occurs at less than one percent of valve stroke for globe and gate valves, even though the loading condition during unseating does not begin to decrease until as must at 15 percent of stroke.
Based on analysis of test data, the following are acceptable settings for the close-to-open torque bypass limit switch:
IEB85-03 ATT B~LIOl
3
- 1. Three percent of total valve stroke as measured from the point of stem motion. The three percent value ensures that cracking has occurred at
- the time of switch actuation though unseating may not be complete. Tb use the three percent setting, the open torque switch must be set in accordance with recommendations contained in Section II-A.
- 2. Five to ten percent of stroke will provide some additional margin for added stem loads due to buildup of foreign materials on the valve seat, etc. Bypass switch actuation will occur during or at the completion of valve unseating under differential pressure conditions.
- 3. The approach generally to be used by Palisades will be to use 20-25 percent of stroke to ensure that the entire unseating is bypassed. The advantages of this approach are the same as 1 and 2 above. In addition, the valve will most likely perform its intended function even.
if the torque switch is set improperly. If this option is selected, it should be recognized that the closed light will illuminate when the valve is 20-25 percent open on operators equipped with two-rotor limit switches. Operationally, this condition can be justified for many applications. Of course, the 20-25 percent setting will not affect position indicating lights if operators are equipped with four-rotor limit switches and the indicating light limit switches ar~ on different rotors then the close-to-open torque bypass limit switch (which will be the case at Palisades).
- 4. Ninety to 98 percent of stroke will have the same advantages as 1 through 3 above and will preclude stoppage of valve travel i f large mechanical loads are encountered anytime during the opening stroke *
- Ninety to 98 percent of stroke will still provide back up for the open limit switch.
- 5. One hundred percent Bypass - With this option, the open torque switch is wired completely out of the opening circuit, thereby negating the need for the bypass switch (see II-A, Open Torque Switches, for guidance on this condition).
II-D Open Indication Limit Switch See Phase II in body of this enclosure.
II-E Close Torque Switch The closing torque switch ensures that sufficient loads are delivered to the valve stem to provide leak tight closure of the valve. Although certain types of valves and/or unusual closing requirements may dictate use of a limit switch for valve closure, the torque switch is the most common method for control during the closing stroke.
As with the open torque switch, the closed torque switch setting must be calculated accurately. To establish the torque switch setpoint, the closing thrust value for full differential pressure conditions must be established.
accurately.
IEB85-03 ATT B-LIOl
4 The equations were developed by MOVATS and validated using full and partial pressure testing data. When the closing stem thrust has been established, the margins for operator, valve and instrumentation variations (previously described) are applied to determine the target closed torque switch setting.
As will be discussed in Phase III, the equations will not be relied upon if sufficient industry full or partial pressure test data is not available at the time of the Plant test to validate the equation being used for thrust calculations. The present MOVATS database does not include suffi2ient test results to validate MOVATS closing thrust equations for flex and solid wedge gates or globe valves with orifice diameters less than 1.75 inches of greater than 2.0 inches. Therefore, the testing program at Palisades will include differential pressure testing in the closing direction of representative valves. Utilizing this data, specific equations will be developed. The equations will be considered accurate for a particular valve if pressure test data is provided by four valves of the same* type and size or 20 valves of the same type.
When closing a valve, the final loading condition may be significantly higher than the closed torque switch trip setpoint. This difference is due to the inertia effects of the operator and valve assembly as well as variations in the motor contract drop-out time. Closing a valve without flow and pressure will result in the highest closure forces and the final forces must be evaluated against the operator and valve manufacturer's thrust limits.
II-F Closed Limit Switches For valves that are controlled using a limit switch during closure, the final closure forces must be examined closely. These forces can vary widely depending on inertia, contactor drop-out time and valve design.
Signature analysis techniques will be used to verify that the closure forces are acceptable when compared with operator and valve manufacturer's limits. In the long range program, any significant changes in contactor drop-out time will be noted and the impact on final stem loads will be monitored and evaluated.
II-G Closed Indication Limit Switch See Phase II in body of enclosure.
II-H Open-To-Close Torque Bypass Limit Switches Typically, the open-to-close torque bypass limit switch is of no operational concern because large hammerblow loading conditions do not occur during the initial phases of the closing cycle. For this reason, no specific requirements are placed on this switch setting relative to the valve stroke. Unless some other need is identified for positioning of this switch, the position that results from coastdown of the motor after open limit switch actuation will be accepted.
IEB85-03 ATT B-LIOl
5 II-I Control Of Butterfly Valves The guidelines of setting butterfly valve limit switches (and torque switches, where applicable) will be basically the same as previously discussed for other types of valves. There is one notable exception.
Normally, butterfly valves do not _employ torque bypass switches. Bypass switches for the open torque switch will be considered when all of the follow~ng conditions exist:
- 1. Normal operating position of the valve is closed.
- 2. The safety position of the valve is open.
- 3. The valve is in a sea water of water environment such that foreign material build-up effects are negligible.
If all of the above conditions exist, then the open torque switch will be wired out of the control circuit or the close-to-open torque bypass limit switch will be set for-approximately 98 percent of stroke .