Letter Sequence Other |
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MONTHYEARML20215A9291986-09-22022 September 1986 Proposed Tech Specs Making Wording Consistent W/Sts & Extending Waiver on Surveillance of Internal Vent Valves to Cycle 8 Refueling Project stage: Other ML20215A9091986-09-22022 September 1986 Application for Proposed Amend 145 to License DPR-54, Revising Tech Specs to Make Wording Consistent W/Sts & to Extend Waiver on Surveillance of Internal Vent Valves to Cycle 8 Refueling.Fee Paid Project stage: Request ML20212E4931986-12-17017 December 1986 Smud Vent Valve Matl & Hinge Clearances Project stage: Other ML20212E5351987-01-29029 January 1987 Matls-Chemistry Assessment for Internal Vent Valve Project stage: Other ML20212E4761987-02-20020 February 1987 Forwards B&W Documents 51-1167259-00, Smud Vent Valves Matl & Hinge Clearances & 51-1167330-00, Matls-Chemistry Assessment for Internal Vent Valves, in Response to G Kalman Request Re Proposed Amend 145 to License DPR-54 Project stage: Other ML20236V7961987-11-25025 November 1987 Proposed Tech Spec Figures 6.2-1 & 6.2-2,reflecting Util Corporate Support of Nuclear Safety & Nuclear Organization Chart,Respectively Project stage: Other ML20236V5821987-11-25025 November 1987 Application for Amend to License DPR-54,consisting of Suppl 2 to Rev 2 to Proposed Amend 138,changing Tech Spec Figures 6.2-1 & 6.2-2 to Assign Nuclear Security Manager & Staff Directly to Nuclear Power Production Project stage: Request ML20236U3361987-11-25025 November 1987 Proposed Tech Specs Page 1-2b,adding Words to Effect That 3.25 Factor Applicable to Three Consecutive Time Intervals Will Be Reset to Begin After Next Surveillance Project stage: Other ML20236U3241987-11-25025 November 1987 Suppl 1 to 860922 Application for Amend to License DPR-54, Consisting of Proposed Amend 145,adding Wording to Tech Spec Page 1-2b Re Surveillance of Internal Vent Valves to Cycle 8 Refueling Outage Project stage: Request ML20237B3961987-12-0707 December 1987 Forwards Amend 92 to License DPR-54 & Safety Evaluation. Amend Revises Tech Specs to Redefine Refueling Interval to Make Definition Consistent W/Sts & Extends Surveillance Interval of Vent Valves to Cycle 8 Refueling Project stage: Approval ML20246M1741989-05-0808 May 1989 Submits Addendum to Safety Evaluation Supporting Amend 92 to License DPR-54,per Util 881129 Request to Revise Safety Evaluation.Approval to Extend Refueling Interval as Applies to Reactor Vessel Vent Valve Granted Project stage: Approval 1987-11-25
[Table View] |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20155D4801998-10-27027 October 1998 Amend 3 to Rancho Seco DSAR, Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode ML20217D3271997-07-30030 July 1997 Update of 1995 Decommissioning Evaluation for Rancho Seco Nuclear Generating Station ML20137W8151997-03-20020 March 1997 Amend 1 to Post Shutdown Decommissioning Activities Rept ML20217A5711990-08-28028 August 1990 Final Engineering Rept,Assessment of Spent Fuel Pool Liner Leakage ML20058B6521990-05-0404 May 1990 Rev 0 to ERPT-M0216, Property Loss Study for Rancho Seco Nuclear Generating Station in Long Term Defueled Mode ML20246F6301989-02-28028 February 1989 Auxiliary Feedwater Sys Overpressurization Event Engineering Evaluation Rept,Feb 1989 ML20154K8571988-08-24024 August 1988 Evaluation of Double Steam Line Break at Rancho Seco ML20151U4851988-07-31031 July 1988 Power Ascension Mid-Term Assessment of Plant Operations & Maint & Scheduling Activities ML20154M7381988-05-31031 May 1988 Assessment of Control Room Habitability Given Postulated Onsite Release of 20 Weight Percent Aqueous Ammonia ML20147E5361988-03-0707 March 1988 Control Room/Technical Support Ctr Habitability Study, Aqueous Ammonia Concentrations ML20147C3751988-03-0101 March 1988 Procurement Engineering Assessment Plan,Interim Rept ML20147E5201988-02-29029 February 1988 Control Room/Technical Support Ctr Habitability Study, Radiological Dose Assessment ML20147E4991988-02-29029 February 1988 Methodology for Revised Control Room X/Q Determination for Rancho Seco Nuclear Station ML20151U0241988-02-29029 February 1988 Rev 5 to Final Wire & Cable Program Rept for Rancho Seco Nuclear Generating Station ML20148C7641988-02-24024 February 1988 Rev 1 to Future Plant Capacity Factor Engineering Assessment ML20147G4881988-02-11011 February 1988 Preliminary Rept Rancho Seco Piping Vibration Tdi Diesels a & B ML20196E6971988-02-0505 February 1988 Rev 3 to Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75 ML20148G2861988-01-31031 January 1988 Radioactive Liquid Effluent Sys Evaluation Using Program Liquid Effluent Based Operating Guides Rev II ML20149D3981988-01-19019 January 1988 Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings, Final Rept ML20148T1551987-12-31031 December 1987 Rev 4 to Wire & Cable Program Rept ML20147D3401987-12-31031 December 1987 Proposed Alarm Sys Mods NFPA 72D Compliance ML20234D8161987-12-0404 December 1987 Rev 0 to Resolution of Audit Findings Pertaining to Fire Pumps ML20237B2791987-12-0101 December 1987 Rev 2 to Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75 ML20236U1321987-11-17017 November 1987 Review of Smud Emergency Operating Procedures ML20236B0101987-10-12012 October 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Nuclear Svcs Electrical Bldg Essential & Normal HVAC Sys ML20236B0051987-10-0707 October 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Component Cooling Water (CCW) & Turbine Plant Cooling Water (Tcw) Sys ML20236B0021987-10-0707 October 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Auxiliary Feedwater Sys ML20236A9981987-10-0707 October 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of 480-Volt AC Distribution Sys ML20236A9921987-10-0707 October 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Rcs ML20236A9891987-10-0707 October 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Safety Features Actuation Sys ML20235V7951987-09-30030 September 1987 Response to NRC Questions on Geologic & Seismologic Conditions. W/Five Oversize Drawings Encl ML20235Y8891987-09-28028 September 1987 Rev 0 to Rept on Response to NRC IE Circular 79-02, Engineering Rept ML20235Q7301987-09-15015 September 1987 Pressurizer Heater Incident,Task 852 ML20239A0301987-09-0303 September 1987 Twelve Sys Assessment of Expanded Augmented Sys Review & Test Program Rept ML20239A1071987-08-31031 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Radiation Monitoring Sys Sys ML20235Y6651987-08-31031 August 1987 Rereview of Plant Instrumentation & Control for IE Bulletin 79-27 ML20239A1041987-08-27027 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Seal Injection & Makeup Sys ML20239A0891987-08-27027 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Non-Nuclear Instrumentation Sys ML20239A0841987-08-27027 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Nuclear Svc Cooling Water Sys ML20239A0821987-08-27027 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of 120 Volt AC Vital Power Sys Sys ML20239A0751987-08-27027 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Main Feedwater Sys ML20239A0661987-08-18018 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Main Steam Sys ML20239A0531987-08-18018 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Nuclear Raw Water Sys ML20239A0461987-08-18018 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Emergency Diesel Generator Sys ML20239A0431987-08-18018 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Control Room/Technical Support Ctr Essential Hvac ML20239A0381987-08-18018 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of DHR Sys ML20239A0341987-08-18018 August 1987 Expanded Augmented Sys Review & Test Program (Expanded Asrtp) Evaluation of Integrated Control Sys ML20237J4241987-08-0505 August 1987 Evaluation of Integrated Control Sys ML20237J3871987-08-0404 August 1987 Evaluation of DHR Sys ML20237J3841987-08-0404 August 1987 Evaluation of Control Room/Technical Support Ctr Essential HVAC Sys 1998-10-27
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20211H7921999-08-13013 August 1999 Safety Evaluation Supporting Amend 126 to License DPR-54 ML20195D1901999-05-0606 May 1999 Annual Rept ML20195H8571998-12-31031 December 1998 1998 Annual Rept for Smud. with ML20155D4801998-10-27027 October 1998 Amend 3 to Rancho Seco DSAR, Representing Updated Licensing Basis for Operation of Permanently Shutdown & Defueled Rancho Seco Nuclear Facility During Permanently Defueled Mode ML20248C4301998-05-0606 May 1998 Annual Rept, Covering Period 970507-980506 ML20249A7831997-12-31031 December 1997 1997 Smud Annual Rept ML20198G8271997-08-22022 August 1997 Safety Evaluation Supporting Amend 125 to License DPR-54 ML20217D3271997-07-30030 July 1997 Update of 1995 Decommissioning Evaluation for Rancho Seco Nuclear Generating Station ML20140A6371997-05-0606 May 1997 Annual Rept, Covering Period 960507-970506 ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20137W8151997-03-20020 March 1997 Amend 1 to Post Shutdown Decommissioning Activities Rept ML20141J2711996-12-31031 December 1996 Smud 1996 Annual Rept ML20138L1231996-11-13013 November 1996 Smud Rancho Seco Incremental Decommissioning Action Plan, Rev 0,961113 ML20129E7151996-10-14014 October 1996 Defueled SAR for Rancho Seco ML20059H6821994-01-17017 January 1994 Revised Rancho Seco Quality Manual ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20056E5171993-08-31031 August 1993 Technical Review Rept, Tardy Licensee Actions ML20059K1981993-05-0606 May 1993 Annual Rept, Covering Period from 920501- 930506,consisting of Shutdown Statistics,Narrative Summary of Shutdown Experience & Tabulations of Facility Changes, Tests & Experiments,Per 10CFR50.59(b) ML20128C9641993-02-0202 February 1993 Informs Commission of Status of Open Issues & Progress of Specified Facilities Toward Decommissioning ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20126E6771992-08-0303 August 1992 Rev 7 to Rancho Seco Quality Manual NL-90-451, Monthly Operating Rept for Oct 1990 for Rancho Seco Nuclear Generating Station1990-10-31031 October 1990 Monthly Operating Rept for Oct 1990 for Rancho Seco Nuclear Generating Station ML17348B5061990-10-0909 October 1990 Part 21 Rept Re Zener Diode VR2 on Power Supply Board 9 1682 00 106 Possibly Being Installed Backwards ML20059G9621990-09-10010 September 1990 Safety Evaluation Supporting Amend 115 to License DPR-54 NL-90-443, Monthly Operating Rept for Aug 1990 for Rancho Seco1990-08-31031 August 1990 Monthly Operating Rept for Aug 1990 for Rancho Seco ML20217A5711990-08-28028 August 1990 Final Engineering Rept,Assessment of Spent Fuel Pool Liner Leakage NL-90-439, Monthly Operating Rept for Jul 1990 for Rancho Seco Nuclear Generating Station1990-07-31031 July 1990 Monthly Operating Rept for Jul 1990 for Rancho Seco Nuclear Generating Station ML20055F8591990-07-16016 July 1990 Special Rept 90-11:on 900613,06,25,18,21 & 28,fire Barriers Breached More than 7 Days & Not Made Operable in 14 Days. Corrective Actions:Operability of Fire Detectors Verified on One Side of Breached Barriers NL-90-423, Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station1990-06-30030 June 1990 Monthly Operating Rept for June 1990 for Rancho Seco Nuclear Generating Station ML20055C6291990-05-21021 May 1990 Special Rept 90-08:on 900419,fire Pump Batteries Inoperable When Surveillance Procedure SP.206 Not Performed by Due Date.Caused by Test Frequency Incorrectly Changed from Weekly to Monthly.Surveillance Schedule Revised ML20055C6301990-05-21021 May 1990 Special Rept 90-09:on 900424,25,30,31 & 0502,fire Barriers Inoperable for More than 7 Days,Per Tech Spec 3.14.6.2 Requirement.Hourly Fire Watches Established & Penetrations & Doors Returned to Operable Status ML20058B6521990-05-0404 May 1990 Rev 0 to ERPT-M0216, Property Loss Study for Rancho Seco Nuclear Generating Station in Long Term Defueled Mode ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating NL-89-634, Monthly Operating Rept for Aug 1989 for Rancho Seco Nuclear Generating Station1989-08-31031 August 1989 Monthly Operating Rept for Aug 1989 for Rancho Seco Nuclear Generating Station NL-89-598, Monthly Operating Rept for Jul 1989 for Rancho Seco Nuclear Generating Station1989-07-31031 July 1989 Monthly Operating Rept for Jul 1989 for Rancho Seco Nuclear Generating Station ML20247B3611989-07-17017 July 1989 Safety Evaluation Supporting Amend 112 to License DPR-54 NL-89-556, Monthly Operating Rept for June 1989 for Rancho Seco Nuclear Station1989-06-30030 June 1989 Monthly Operating Rept for June 1989 for Rancho Seco Nuclear Station ML20245E1161989-06-20020 June 1989 Safety Evaluation Supporting Amend 111 to License DPR-54 ML20245B6651989-06-15015 June 1989 Part 21 Rept 150 Re Potential Defect in Component of Dsr Standby Diesel Generator.Cause of Failure Determined to Be Combination of Insufficient Lubrication to Bushings.Listed Course of Action Recommended at Next Scheduled Engine Maint ML20245A1991989-06-0909 June 1989 Safety Evaluation Supporting Amend 110 to License DPR-54 ML20248B9361989-06-0505 June 1989 Safety Evaluation Supporting Amend 107 to License DPR-54 ML20248B6321989-06-0505 June 1989 Safety Evaluation Supporting Amend 108 to License DPR-54 ML20248B9621989-06-0505 June 1989 Safety Evaluation Supporting Amend 109 to License DPR-54 NL-89-517, Monthly Operating Rept for May 1989 for Rancho Seco Nuclear Generating Station1989-05-31031 May 1989 Monthly Operating Rept for May 1989 for Rancho Seco Nuclear Generating Station ML20247P1761989-05-30030 May 1989 Safety Evaluation Accepting Generic Ltr 83-28,Item 4.5.2 Re on-line Testing of Reactor Trip Sys ML20247N7491989-05-30030 May 1989 Special Rept 89-13:on 890328-29,specific Activity of Primary Sys Exceeded Limits in Administrative Procedure & Chemistry Control Commitment.Possibly Caused by Power Reduction.Isotopic Analysis Continued ML20247K7261989-05-23023 May 1989 Safety Evaluation Supporting Amend 105 to License DPR-54 1999-08-13
[Table view] |
Text
- - _ _ _
.- ;4 ATTACilMENT 1 B'ANS 20no 3 :s es) -
CCW O MICOX ENGINEERING INFORMATION RECORD a Mcoermott comparty Safety Related:
Document identifier 51 -1167259-00 Yes 00 No O SMUD VENT VALVE MA'rERIAL AND HINGE CLEARANCES Title Prepared by _
Date /2MG/f/
I R.B[ REYNOLDS Revis, ed by A * -- Date /Z//7 !8#
' &~ d. Mhestf f/ l lf 01]f Remarks:
The information contained herein has been prepared to document the material of construction and hinge clearances of the Reactor Vessel Internals Vent Valve.
It should be noted that the values calculated herein differ from those reported in Table 3.2-11 of the USAR. However, it is felt that the calculated results accurately represent the clearances on the reactor vessel vent valve hinge.
l l
l 8703040365 870220 PDR ADOCK 05000312 P PDR Page / of 8
!.>' / 51-1167259-C0 l
I. SCOPE SMUD requested B&W to provide information on the Reactor Vessel Vent Valves. The specific- information is the material for the valve body, valve disc, disc / body shaf t, and shaft bushings; and-the hinge interface clearances.
II. _ INTRODUCTION The Q . 7. . Data Package (B&W ~ Document 23-0745-00) identifies the material and drawings for the .SMUD . Vent Valves.
However, the specific dimensions of interest are not listed for all of the respective parts. The Q.A. Data Package (B&W-Document 23-ll7817-00) for Toledo Edison lists the specific dimensions of interest and the same drawings used . for the design / manufacture of the TED vent valves were the same for the design / manufacture of the SMUD vent valves. Based on this comparison, the vent valve hinge clearances can be determined. The. material specifications will be taken from the SMUD Data Package. The vent valves- were design /
manufactured by Atwood & Morrill Co (A&M), Salem, Mass.
i III. REFERENCES A. B&W Document 23-0745-00 for SMUD Contract 620-0011, Internals Vent Valve Q.A. Data Package.
B. B&W Document 23-1117817-00 for TED. Contract 620-0014, Internals Vent Valve Q.A Data Package.
C. B&W Document 51-1164588-00. TMI and DB-1 Vent Valve Material & Design Comparison.
D. 1983 ASME Code,Section III, Division I Appendices.
'( Value)
E. SMUD USAR, Volume II, Chapter 3.
IV. DISCUSSION The specific materials for the SMUD Vent Valves body, disc, shaft, and bushings are listed in Table 1. The cross reference of the TED and SMUD drawings are listed in Table
- 2. The specific dimensions for the respective parts are listed in Table 3, and the hinge clearances are tabulated in Table 4. Figure A identifies the respective locations where the clearances are tabulated.
2
.. t 51-1167259-00 l
There are eight (e) vent valve assemblies. They were all designed / fabricated to. the same requirements. ~ Atwood &
Morril assigned.each assembly a serial number which is: 50-547,51-547, 52-547,53-547, 54-547,-55-547,56-547, 57-547.
The data for this document will be taken from serial number 56-547 and 50-547.
O 3
_ __ . . . ~ .~. , _ _ _ . - . _ _ _ . _ . _ . _ , ~ . . _ _ _ _
., . ~ . . . .
51-1167259-00 TABLE 1 Internal Vent Valve Materials
'(Ref.'III.A.-& Ref. III.E Table 3.2-10)
Valve Part Name A&M Part No. Material Specification Valve' Body, 1- ASTM'A351 Gr-CF8 Valve Disc 4 ' ASTM-A351 Gr-CF8-Disc Shaft 5 ASTM-A276 Type 431 Cond-T Shaft-Bushings 7 Stellite #6 TABLE 2 TED vs. SMUD Drawings
-TED Drawing SMUD Drawing Valve Part Name (Ref. III-B) (Ref. III~A)
Valve Body 20690D-10 20690D-10 Valve Disc 20691D-4 20691D-4 Disc Shaft 22608B-3 22608B-3 4
Shaft' Bushings 23331A-2 23331A-2 4
51-1167259 .
TABLE 3 Specific. Dimensions
.(Reference-III.C)
Design
. Valve'Part Name A&M Part No. Description Dimension (in.)
Valve Body 1 Body. Lug Gap 5.765-5.780
- Body Lug Hole'I.D _2.000-2.005=
Valve Disc 4 Disc Hub Width 4.740-4.750 Disc Hub Hole I.D. 2.000-2.005 Disc Shaft 5- Shaft O.D. 1.485-1.490 Shaft Bushing 7 Bushing I.D. 1.500-1.505 Bushing O.D. 1.995-1.997
-Bushing Flange .245- . 248 Thk.
5 f
- w - p--, ,
--,p- --- . , - , , , -
7,, . ...
T ,51-116 72 59-C0 '
TABLE 4 l Vent 1 Valve Hinge Clearances (See Figure A for Locations)
A.. Cold Clearance (at 70-F). in.
. Bushing ID 1.500 to 1.505 Shaft OD 1.490 to 1.485 0.010- to 0.020 Diametral clearance (gaps 1,2,7;and 8)
' Lug / Hub ID 2.000 to- 2.'005 Bushing OD- l'997 to 1.995 '
0.003 to 0.010 Diametral clearance
-(gaps 3,4,5,and 6)
Bushing End Clearance Body Lugs 5.765 to 5.780 Disc-Hub 4.750 to- 4.740 1.015 to 1.040 Bushing Flanga .992 to .980
.023 to .060- End clearance
.245x4=.980' (gaps 9 and 10)
.248x4=.992 .
B. Hot Clearance (differential crowth from 70 to 580 F1-Linear coefficient of thermal expansion of the materials for a temperature change from 70 to 580 F.
Shaft -
A276-TP.431 6.7x10-6 in./in.-F Ref. III C Bushing -
Stellite No. 6 8.1x10-6 in./in.-F Ref. III C Bodies -
CF8 Stainless 9.5x10-6 in. fin.-F Ref. III D delta T = 580 - 70 = 510F Shaft D=D T = 1.5(6.7 x 10-6) 510'= 0.0051 Bushing ID D = 1.5(8.1 x 10-6) 510 = 0.0062 0.0011 Typical diametral
> clearance increase Bushing OD D = 2(8.1 x 10-6) 510 = 0.0083 Lug / Hub ID D = 2(9.5 x 10-6) 510 = 0.0097 0.0014 Typical diametral 4
clearance increase 6
-e- -t-- - -
.jy -
.; ,. =
_ _51-1167259-00=
~
. TABLE 4 (Cont'd)
-Bushing Endplay.
. CF8 - Lug / Hub '. L'= 1(9.5.x'10-6)'510 = .O.0048 Stellite.No. 6 bushing L = 1(8.1 x 10-6) 510 = 0.0041 0.0007 Typical end.
clearance increase 7
-
FIGURE A
. -VENT VALVE HINGE CLEARANCE LOCATIONS N
- s T
(
/
l i
~
VALVE DISC BODY LUG GAP 9 GAP 10 GAP l GAP 2 GAP 5
{ GAP 6 h6 bb
- 1 l l lllllllll& ////flll20 h VllllYllll (lllllYllA l MN'" x%%%'NWN' M
.AP , a .AP , i .AP , i L .AP ,
SHAFT
[DISCHUB BUSHING SECTION Z-Z Page a of 8
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