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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
EPRI JUSTIFICATION REPORT REPORT NUMBER 1125*
DATE: _ _/._~_-_1..._7_-_.i".._/_ _ _ __
P .K*. MERRILL REVIEWED BY: /,!l/.~ DATE: / / .- f?-tl .
---m~~~~~
J .N. REED MASONE!LAN DIVISION OF McGRAW EDISON
( 8207160345 820404 \
- PDR ADOCK 05000255
' P . PDR
!NDEX
- PAGc: NO Index. .* .* . * * * * " * * .*
- l Ini:roductioa. . 2 Descrtptiou of Basic Model *
- 0 . ..* 2 Selected Test Valve. 0 ..* * * * * * * *
- 0 0 3 Ocsilt' Variations Betweeu PWB. Plaut Valves and. Seleeted Test Valves.
Couclusiou * ... ec**O&e
- Assembly D~awing A8425 * * * * * * * * * * * ... 4 Parts List A8S29 * * * * * *
- * .. .. .. s Doc 3269A ll-l.3-81
-l-
JUSTIFICATION REPORT
- 1. Introduction
- This report has been prepared for the Electric Power Research Institute, EPR!,
by Masoneilan Division of McGraw Edison at their request. This report will be integrated with EPR!'s Valve Selection/Justification Report.
The information released in this report is not considered proprietary, therefore there is no restriction placed on its use within the confines of the EPRI/PWR Safety and. Relief Valve-Test Program Report.
The valves in the United States subject to this test program were sold only to Westinghouse and were to be installed: at Westinghouse project sites.
Masoneilan has not been provided information to where specific valve serial numbers have been sent. This information should be available through Westinghouse. All valves used on Power Operated Relief Valve, PORV, applications in the United States were Masoneilan Model No. 38-20721 or 38-20771. All valves are 2 ...size.
Identification of the sites in the United States at which Masoneilan PORV's are located are as follows:
UTILITY PLANT MODEL NO.
Duquesne Light - Beaver Valley 1 38-20721 Indiana & Michigan Electric .- Donald Cook 1 & 2 38-20721 Pacific Gas & Electric - Diablo Canyon 1 & 2 38-20771 Tennessee Valley Authority - Sequoyah 1 38-20721 Virginia Electric & Power - North Anna 1 & 2 38-20771 Wisconsin Public Service - Kewaunee 38-20721
- 2. Description of Basic Model The model numbers 38-20771 and 38-20721 valves are top guided single seat ~lobe valves with pneumatic actuators. The valve plug is lifted off the seat by pneumatically loading the actuator. Positive closure is provided by the spring return or failure mode of the actuator. The valve plug is top guided in the valve bonnet. Adequate guiding area has been provided in the bonnet to prevent instability of the plug. The seat ring retainer provides easy and quick access to the seat ring and seat ring gasket for removal and maintenance.
The model numbers 38-20771 and 38-20721 are the only models installed in the U.S. The only difference is the valve plug used in model number 38-20771 uses a linear control contour and in model number 38-20721 has equal percentage contour. Critical dimensions that affect the valves shut-off, flow capacity, stability, and speed remain unchanged. This difference affects only the flow characteristics of modulating valves thus has no significant impact to the EPRI test.
The flow is from under the valve body bridge i.e., the flow forces the valve plug open. The actuator selected has sufficient spring thrust to dVercome these flow and pressure forces. Reference drawing numbers A842S ~nd A8529 *
- 3. Selected Test Valve
!he valve select:ed for test: was secured from. the Tennessee Valley Authorit:y from. the Sequoyah Site* This valve is essentially the same as those at other sites ..
- 4. Oesisp. Var1atious !etveeu PW'&. Plane Valves and Selected Test Valves As seated in the previous paragraphs there are no siguif icane design variations thac would affect the !PR.I tesc results or valve perf ormauce between the test valve and ochers in the field.
S.. Cone lus ion In summary the valve selected by !PRI is r:ept:"esentaeivei eo those cul'?'eutly in use 1J:i. the POB.V applications ia. the United States .
REVISIONS
. .. SYM.
- 1. REWORK 2. SCRAP DESCRIPTION
- 3. USE AS IS 4. RECORD CHANGE C REQ NO. 3731 4 2*3*"71
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Jt j DE.\AIL OF BUTT WE.LD ENO REFERENC-E'.
CERTIFIED DRAWING NO. CPHB-55-C W \THOUT AIR SET CE RllFIED DRAWINCo NO.C.PI 71-C.
WITH Alf\Stl' SIDE VIEW NATIONAL ACME D-2400X LIMIT SWITCH MOUNTING 2." 3 IA58RGP A8529-D
-z!' 3* IA 58 RGP A 8"'1712>-D TA.G NO. PARTS LIST UNLESS OTHERWISE SPECIFIED DRAWN WORTHINGTON CONTROLS COMPANY BACK SEAT CONSTRUCTION DIMENSIONS ARE IN .
OIJ..f.NSIONINli SYSTEM NORWOOD, MASSACHUSETTS MONTEBELLO, CALIFORNIA INCHES AND MILLIMETERS PLUG SHOWN IN UP POSITION A~D ARE AFTER PLATING i.-INCHES (MM)_,
25 INCHES ANGLES
~x, I*'~.1 "~~0 I f +/-
MILLIMETERS
... ;t x
3 :t x.x 0,8 x,xx
- t0.25
~ .IX.\. CO.. 19C. IOHI
PC; NO. REVISIONS **
Ml. PART NO. NAME REQ. MATERIAL SYM. DESCRIPTION DISP. DATE APPROVED SIZE
- 1. REWORK 2. SCRAP 3, USE AS IS 4. RECORD CHANGE B R.t:Q WO. '3'59"1 4 9-11-10 7,.
010224--008-105 SPRING BARREL CAP ASTM A283 GR D
- CONTAINED IN ASSEMBLY 013044-623-999 2 010191--002-117 BALL RACE USS MACH 5 A CONTAINED IN .4SSEMBLY 010309-083-999 010186--058-105 UPPER SPRING BUTTON ASTM A2S3 GR D 8 CONTAINED IN ASSEMBLY 0101'75-142-999 010220--033--002 SPRING BARREL 1 SAE 1020 e RECOM'llENDED SPARE PARTS 971512--020-110 NUT .1 ASTM A307 1" - 14UNS REMACH INE YOKE PER 010405-008-A 010285--012-002 DIAPHRAG\1 PLATE .1 SAE 1020 1*
8 010275--025-686 010217-024-105 DIAPHRAGM STOP. PLATE NEOPRENE & RAYON FABlUC ASTN A283 GR D
~TES:
9 II 010217-004--002 DIAfHRA(;'.I WASHER SAE 1020 1. VALVE STROKE ~ 1 .50 INCHES 10 010700--006-100 YOKE ASTM A216 GR lltB 2. MAXIMUM TEMPERATURE - 650 o F 11 010213-006-317 PACKING BOX WAKEF I ELD ALLOY 41
- 3. AIR PRESSURE IN THE DIAPHRAG.I CHAMBER MUST NOT 12 010209-013-410 PACKING BOX GLAND 1 ASTM B16 EXCEED 5 5 PS I G TO PREVENT COMPONENT D.AMAGE 13 971159--008-110 CAP SCREW 4 ASTM A307 1/2 - 13UNC X 1 ,75 14 971335--002-250 DRIVE SCREW 2 GENERAL AUSTENITIC ST.ST. 4. REQUIRED AIR PRESSURE INPUT TO BEGIN LIFT OF 15 983750-001-153 .SER I AL PLATE ASTM A167 N 304 PLUG FROM MAIN SEAT - 29 PSIG 16* 011156-134-780 PLUG STEM HAYNES ALLOY 25 5. MAXIMUM A IR TO OPERATE VALVE 55 PSIG 17 010102-009-780 PACKING BOX GLAND ASTM A276 TY 316 18 010106--001-026 DRIVE NUT SAE 1117 <D. Vl::.L*vE ":...,; =4<D
- 7. REQUIRED AIR PRESSURE. INPUT FOR SHUT 20 007905-008-066 BODY STUD 8 ASTM A 193 GR B7 7/8 - 9UNC X 3.38 OFF OF BACKSEAT =55 PSIG.
21* 971342-027-780 PIN HAYNES ALLOY 25 22 013902-009-780 SEAT RING RETAINER ASlM A461 GR 630 C0~0\110\...1 H-900 23 013454-658-780 BODY ASTM A351 GR CF 8M 24* 010234-608-780 SEAT RING ASTM A276 TY 316 & N0.6 STELLITE 25* 013434-IOJ-780 PLUG ASTM A276 TY 316 & ~0.6 STELLITE
- 26. 009191-431-801 SEAT RING JASKET 304 ST .ST. WITH ASBESTOS 2.75 o.o. x 2.38 1.0. x .125 27° 010110-237-780 BUSHING NO. 6 STELL ITE BODY GASKET 304 ST .ST. WITH ASBESTOS 3.38 O,D. X 2.94 I .D. X .125 28* 009191-170-801 29* 013044-618-780 BONNET 1 ASlM A351 GR CF 8M 30 971511-068--010 ~T 8 ASTM A194 GR 2H 7/8" - 9UNC PACKING 10 ASBESTOS & GRAPHITE 31
- 005675-503-779 33* 971490-003-177 PACKING BOX STUD 2 ASlM A193 GR 88 1/2 - 13UNC X 2.00 34 010105--001-780 PACK I NG BOX FLANGE 1 ASTM A235 CL C 971520-005-158 PACKING BOX NUT 2 ASTM A194 GR 8 (TUFFTRIDED) 1/2 - 13UNC 35 sa3676--003-SOO INDICATOR PLATE 1 ALUMINUM 971305-015-250 MACHINE SCREW 3 GEN. AUSTENITIC ST.ST.
POINTER A~TM A \(0'7 TY '304 01040&221-lSo SPLIT CLAMP USS MACH 40.
41.
010408-384-117 001904--004-426 971919-007-916 PACKING BOX GASKET STRING PACK ING ASTM B152 TYP ETP ASBESTOS & GRAPH I TE 2.50 O.D. X 2.12 I .D. X .020
.19 DIA X 16.00 010175-143-152 ACTUATOR STEM ASTM A582. TY 303 42* 7 .12 0 .D. X 5 .62 I .D. x .031 001904-628-800 YOKE GASKET 1 ASBESTOS FISER.
430 CAP SCREW 12 ASTM A307 3/8 - 16UNC X .75 44 971161-003-110 45 010310-004-105 LOWER DIAPHRAG\1 CASE ASTM A283 GR D 40 ASThl A307 3/8 - 16UNC 46 971511--012-110 NUT OIAPHRAQ.I CASE CAP SCREW 40 ASTM A307 3/8 - 16UNC X 1.25 47 971004-017-110 010186-059-105 LOWER SPRING BUTTON 1 ASlM A283 GR D 48 49 .. 010309-082-105 UPPER DIAPHRAG\1 CASE ASTM A283 GR 0 000049-001-130 SPRING ASlM A229 50 BALL & RETAINER GEN
51 971700-027-250 010199-019-021 ADJUST ING SCREW I ASTM A108 GR B 1113 52 8 - 32UNC X .56 971264-008-110 MACHINE SCREW 8 ASTM A307 53 UPPER MOUNTING BRACKET I ASlM A293 GR D 54 008149-311-105 4 ASlM A307 5/16 - 18UNC X ,62 55 971002-007-110 CAP SCREW 971961-005-888 SWITCH 2 PURCHASED ASSEMBLY 56 009790-041-207 TAKE OFF BUTTON 2 ASTM Al93 GR 86 57 ADAPTER 1 ASTM Al93 GR 86 58 009790--003-207 1/4 - 28UNF 971514-001-110 LOCK NUT 2 ASlM A307 59 12 - 24UNC X .81 971268--012-110 MACHINE SCREW ASTM A307 60 61 051425--010--026 STEM CONNECTOR SAE 1117 CLAMP ROO ASTM A582 TY 303 62 051332--018-150!. 5/16 - IBUNC LOCK NUT ASlM A307 63 971513--006-110 LOWER t.()UNT ING aRACl<ET ASTM A283 GR D 64 008149-C!.95-105 ASSEMBLY DW:S A842S-D UNLESS OTHERWISE SPECIFIED DRAWN MASONEILAN INTERNATIONAL, INC.
DIMENSIONING SYSTEM CHECKED D1MEN5ll)NS ARE IN NORWOOD, MASSACHUSETIS, U.S.A.
INCH[S ANIJ MILLIMETf.RS j.-rNCHES (MM)_,
AND ARE AFTER PLATING TOLERANCES ON:
!1111llED HOLE TOLERANClS INCHlS ANGLES PER AND10387
.x
+/-.1 !! +/-.03
.xx [ .xxx
+/-.010 I+/-2°30' FILLET RADII _ _ * - - - - MATERIAL FORGING NO.
SIZE CODEIOENT.NO. REV.
MILLIMETERS
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BREAK SHARP EDGES_
fc-'. ,.".,.,o-"'c_"'_ov_*--'.:c""c_"...:"s_~.-1 Fl NISH MACHINED SURFACES REF .. USAS 846.J.1962 J F. N O . f - - - - - + - - - - - - j D ~38683 A 8~ 2. 9
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