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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20205L0541999-04-0101 April 1999
Nonproprietary Replacement Pages to HI-91738,consisting of Section 5.0, Thermal-Hydraulic Analysis
ML17059C5501999-01-31031 January 1999
Rev 0 to MPR-1966(NP), NMP Unit 1 Core Shroud Vertical Weld Repair Design Rept.
ML20151P1751998-06-16016 June 1998
Rev 0 to SIR-98-067, Evaluation of NMP Unit 2 Feedwater Nozzle-to-Safe End Weld Butter Indication (Weld 2RPV-KB20, N4D)
ML20198B4991998-05-15015 May 1998
Non-proprietary Replacement Pages for Attachment F to Which Proposed to Change TS 5.5, Storage of Unirradiated & Sf
ML17059C1681998-03-19019 March 1998
Revised Niagara Mohawk Powerchoice Settlement Document for NMPC PSC Case Numbers 94-E-0098 & 94-E-0099, Vols 1 & 2
ML18040A3301998-02-28028 February 1998
Rev 0 to Technical Rept 97181-TR-03, EPR Testing of Boat Samples from Core Shroud Vertical Welds V-9 & V-10 at NMP Unit 1.
ML17059B9051998-02-28028 February 1998
NMP Unit 1 Boat Samples Analyses Part Iii:Tension Tests, RDD:98:55863-004-000:01
ML17059B9061998-02-28028 February 1998
Non-proprietary Rev 0 to GE-NE-523-B13-01869-113NP, Assessment of Crack Growth Rates Applicable to NMP Unit 1 Vertical Weld Indications.
ML17059B9071998-02-28028 February 1998
Rev 0 to Technical Rept 97181-TR-02,Vol 1 to Interpretive Metallurgical Rept on Core Shroud Vertical Weld Boat Samples from NMP Unit 1.
ML20217F1201997-09-30030 September 1997
Rev 1 to Boat Sample Analyses at NMP Unit 1
ML17059B6771997-08-11011 August 1997
Rev 0 to Evaluation of Overlay for RWCU Weld 33-FW-22.
ML17059B5901997-06-30030 June 1997
Rev 0 to Metallurgical Evaluation of Failed Shroud Tie Rod Lower Spring Contact Wedge Latches, for June 1997
ML17059B4861997-04-30030 April 1997
Non-proprietary Rev 0 to GE-NE-523-B13-01869-043, Assessment of Vertical Weld Cracking on NMP1 Shroud.
ML17059B4881997-04-30030 April 1997
Non-proprietary Rev 0 to Gene B13-01739-40, Shroud Repair Anomalies NMP1,RF014.
ML17059B5111997-04-30030 April 1997
Non-proprietary Version of Rev 1 to GE-NE-523-B13-01869-043, Assessment of Vertical Weld Cracking on NMP1 Shroud.
ML17059B4891997-04-30030 April 1997
Non-proprietary Rev 0 to Gene B13-01739-22, Design Rept for Improved Shroud Repair Lower Support Latches.
ML17059B5071997-04-30030 April 1997
Final Rept, Analysis of Nine Mile Point Unit 1 Shroud Weld V9 & Weld V10 Cracking.
ML17059B4931997-04-0303 April 1997
Core Shroud Cracking Evaluation.
ML17059B2411996-08-13013 August 1996
NMP-1 Core Shroud Repair Mod Summary Rept.
ML17059B2441996-08-13013 August 1996
Non Proprietary Version of Suppl 1 NMP-1 Seismic Analysis, Core Shroud Repair Mod.
ML17059B2421996-08-13013 August 1996
Suppl 4 NMP-1 Shroud Repair Hardware Stress Analysis.
ML17059B2431996-08-0909 August 1996
Rev 4 to Stabilizer Installation.
ML18040A1801996-08-0101 August 1996
Rev 5 to Reactor. Drawings Encl
ML17059B1221996-04-29029 April 1996
Nonproprietary Core Shroud Repair 270 Degree Tie Rod Assembly Assessment.
ML17059B0091995-11-29029 November 1995
NMP Unit 2 Safety Evaluation Summary Rept.
ML18040A1671995-09-29029 September 1995
NMP Nine Mile Point Unit 1 Nuclear Power Station Rept of RPV FW & CRD Return Line Nozzle Exams Performed for NUREG-0619...at Culmination of Refueling Outage 13 Which Ended on 950404.
ML17059B0181995-01-20020 January 1995
Feedwater Nozzle Analysis.
ML18040A1621995-01-16016 January 1995
Rev 2 to 25A5583, Shroud Repair Hardware.
ML17059A5781994-12-31031 December 1994
Non-proprietary Version of Final Rept Plant-Specific Charpy Shift Model for Nine Mile Point Unit 1.
ML17059A5041994-12-31031 December 1994
Unit 2 Safety Evaluation Summary Rept 1994.
ML18040A2971994-10-31031 October 1994
Final Rept Entitled Fracture Mechanics Assessment of Nine Mile Point Unit 1 Shroud H4 Weld.
ML18040A2271994-08-19019 August 1994
Nuclear Engineering Rept, Nine Mile Point Unit 1 Shroud Cracking Safety Assessment for GL 94-03.
ML17059A3611994-07-0606 July 1994
Emergency Action Level Verification & Validation Rept.
ML17059A3531994-06-10010 June 1994
Ny State EAL Upgrade Project Nine Mile Point Unit 1 EAL Generation Package.
ML17059A3551994-06-10010 June 1994
Eals.
ML17311A0181994-05-13013 May 1994
New York State EAL Upgrade Project Verification & Validation Rept.
ML17059A3401994-04-30030 April 1994
Rev 0 to Nine Mile Point Unit 1 Feedwater Nozzle Fatigue Evaluation.
ML17059A3411994-04-30030 April 1994
Rev 0 to Nine Mile Point Unit 1 CRD Return Nozzle Fatigue Evaluation.
ML17059A0881993-12-31031 December 1993
Safety Evaluation Summary Rept 1993.
ML17059A0311993-08-31031 August 1993
Elastic Plastic Fracture Mechanics Assessment...Nine Mile Point,Unit 1:Response to NRC RAI Re GL 92-01
ML18038A7381993-03-17017 March 1993
Upper Shelf Energy Uncertainty Analysis for Nine Mile Point Unit 1 Beltline Welds Final Rept
ML18038A7351993-02-22022 February 1993
Final Rept, Elastic-Plastic Fracture Mechanics Assessment of Nine Mile Point Unit 1 Beltline Plates for Service Level C & D Loadings.
ML18038A7361993-02-19019 February 1993
Beltline Plate Orientation Determination, Final Rept
ML18037A0831992-12-16016 December 1992
Elastic-Plastic Fracture Mechanics Assessment of Nine Mile Point Unit 1 Beltline Plates for Svc Level a & B Loadings.
ML18038A7261992-11-19019 November 1992
Technical Response to SE by NRR Related to Proposed Deferment of Torus Mods, Nmp,Nmpns,Unit 1 Docket 50-220
ML17056C1091992-10-29029 October 1992
NMP Unit 2 Safety Evaluation Summary Rept.
ML18038A7141992-10-16016 October 1992
Final Rept Entitled, Elastic-Plastic Fracture Mechanics Assessment of Nine Mile Point Unit 1 Beltline Plates for Service Level a & B Loadings.
ML18038A5181992-06-12012 June 1992
Response to GL 92-01 for Nine Mile Point Unit 1.
ML17056B4781991-12-31031 December 1991
Unit 2 Safety Evaluation Rept 1991.
ML18038A3741991-09-0909 September 1991
Rev 1 to Root Cause Rept for Exide UPS 1A,B,C,D & G Trip Event of 910813. Electrical Fault on B Phase Main step-up Transformer Occurred Due to Improper Design.Logic Power Supply for Subj UPS Units to Be Modified
1999-04-01
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217G2161999-10-15015 October 1999
Errata Pages 2 & 3 for Safety Evaluation Supporting Amend 168 Issued to FOL DPR-63 Issued on 990921.New Pages Change Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend
ML20217K4631999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Nine Mile Point, Unit 1.With
ML20216J9251999-09-30030 September 1999
Suppl to Special Rept:On 990621,11 Containment Hydrogen Monitoring Sys Chart Recorder Was Indicating Below Normal Operating Range.Caused by Excessive Wear on Valve Body & Discs of Bypass Pump.Sample Pump Replaced
ML20212F7301999-09-21021 September 1999
Special Rept:On 990907,CR Operators Declared 12 Containment Hydrogen Monitoring Sys Inoperable for Planned Maint.Cause of Low Flow Condition Was Determined to Be Foreign Matl. Replaced Sample Pump Valve Discs
ML20212B9081999-09-14014 September 1999
Special Rept:On 990901, 12 Containment Hydrogen Monitoring Sys Was Declared Inoperable for Planned Maint.Caused by Planned Maint Being Performed as Corrective Action.Check Valves with O Rings Were Replaced
ML20212C4601999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Nine Mile Point Nuclear Station,Unit 1.With
ML20216F5141999-08-31031 August 1999
Rept on Status of Public Petitions Under 10CFR2.206
ML20210U4591999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Nine Mile Point, Unit 1.With
ML20209D0291999-07-0202 July 1999
Special Rept:On 990621,operator Identified That Number 11 Hydrogen Monitoring Sys (Hms) Chart Recorder Was Indicating Below Normal Operating Range.Cause Indeterminate.Licensee Will Complete Troubleshooting of Subject Hms by 990709
ML20210B9081999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Nine Mile Point Unit 1.With
ML20209F8811999-06-0808 June 1999
Rev 1 to NMP Unit 1 COLR for Cycle 14
ML20207G2261999-06-0707 June 1999
SER Accepting Proposed Mod to Each of Four Core Shroud Stabilizers for Implementation During Current 1999 Refueling Outage at Plant,Unit 1
ML20196E2111999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Nmp,Unit 1.With
ML20207B0241999-05-18018 May 1999
Safety Evaluation of Topical Rept TR-107285, BWR Vessel & Intervals Project,Bwr Top Guide Insp & Flaw Evaluation Guidelines (BWRVIP-26), Dtd December 1996.Rept Acceptable
ML20206U5351999-05-17017 May 1999
SER Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant, Units 1 & 2
ML20196L2301999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Nmp,Unit 1.With
ML20205L0541999-04-0101 April 1999
Nonproprietary Replacement Pages to HI-91738,consisting of Section 5.0, Thermal-Hydraulic Analysis
ML20205S5701999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for NMP Unit 1.With
ML20207M9231999-03-12012 March 1999
Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results
ML20207G2671999-03-0101 March 1999
Special Rept:On 990315,Nine Mile Point,Unit 1 Declared Number 12 Containment Hydrogen Monitoring Sys Inoperable. Caused by Degraded Encapsulated Reed Switch within Flow Switch FS-201.2-1495.Technicians Replaced Flow Switch
ML20204C9971999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Nine Mile Point,Unit 1.With
ML20207E9311999-02-26026 February 1999
Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced
ML17059C5501999-01-31031 January 1999
Rev 0 to MPR-1966(NP), NMP Unit 1 Core Shroud Vertical Weld Repair Design Rept.
ML20199M0891999-01-22022 January 1999
Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc
ML20199K9331998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Nine Mile Point Nuclear Station,Unit 1.With
ML20210R8441998-12-31031 December 1998
1998 Annual Rept for Energy East
ML20206P2391998-12-31031 December 1998
Special Rept:On 981222,operators Removed non-TS Channel 12 Drywell Pressure Recorder & Associated TS Pressure Indicator from Svc.Caused by Intermittent Measuring Cable Connection in non-TS Recorder Circuitry.Replaced Cable
ML20206P2421998-12-30030 December 1998
Special Rept:On 981219,number 12 Hydrogen Monitoring Sys (Hms) Was Declared Inoperable When Operators Closed Valve 201.2-601.Caused by Indeterminate Failure of Valve 201.2-71. Supplemental Rept Will Be Submitted After Valve Is Repaired
ML20198M3571998-12-23023 December 1998
Special Rept:On 981210,operators Declared Number 11 Inoperable,Due to Failure of CR Chart Recorder.Caused by Inverter Board in Power Supply Circuitry of Recorder Due to Component Aging.Maint Personnel Replaced Failed Inverter
ML20198D9361998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Nine Mile Point,Unit 1.With
ML20155E2001998-11-0202 November 1998
Safety Evaluation Approving NMP 980227 Request for Extension of Reinspection Interval for Core Shroud Vertical Welds at NMP1 from 10,600 Hours to 14,500 Hours of Hot Operation
ML20195J4141998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Nine Mile Point Nuclear Station,Unit 1.With
ML20154D8401998-10-0505 October 1998
Safety Evaluation Accepting Proposed Changes Related to PT Limits in Plant,Unit 1 TSs
ML20154P1821998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Nine Mile Point Nuclear Station,Unit 1.With
ML20153B2001998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Nmpns,Unit 1.With
ML20237C6351998-07-31031 July 1998
Monthly Operating Rept for July 1998 for Nine Mile Point Nuclear Station,Unit 1
ML20236T5911998-07-20020 July 1998
LER 98-S01-00:on 980618,security Force Member Left Nine Mile Point,Unit 2 Vehicle Gate Unattended Without Ensuring,Gate Alarm Had Been Reactivated.Caused by Inadequate Work Practice.Vehicle Gate Alarm Was Activated
ML18040A3491998-07-0202 July 1998
LER 98-017-00:on 980602,control Room Ventilation Sys Was Declared Inoperable.Caused by Original Design Deficiency. Mod Designed,Tested & Implemented Prior to Startup from RF06 to Correct Design deficiency.W/980702 Ltr
ML20236Q1701998-06-30030 June 1998
Monthly Operating Rept for June 1998 for Nine Mile Point Nuclear Station,Unit 1
ML17059C1011998-06-24024 June 1998
LER 98-014-00:on 980525,noted Differences Between Actual Valve Weights & Weights Shown on Engineering Drawings.Caused by Vendor Failing to Provide Accurate Valve Weights.Revised Valve Drawings & Associated Calculation,Per 10CFR21
ML20151P1751998-06-16016 June 1998
Rev 0 to SIR-98-067, Evaluation of NMP Unit 2 Feedwater Nozzle-to-Safe End Weld Butter Indication (Weld 2RPV-KB20, N4D)
ML18040A3451998-06-0404 June 1998
LER 98-004-01:on 980302,TS Required LSFT of Level 8 Trip of Main Turbine Was Missed.Caused by Knowledge Deficiency of EHC Sys.Revised Applicable LSFT Procedures Prior to Refueling Outage 6.W/980604 Ltr
ML20249B4971998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Nine Mile Point Nuclear Station,Unit 1
ML20248F3531998-05-21021 May 1998
Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted
ML20198B4991998-05-15015 May 1998
Non-proprietary Replacement Pages for Attachment F to Which Proposed to Change TS 5.5, Storage of Unirradiated & Sf
ML20247R1141998-04-30030 April 1998
Monthly Operating Rept for Apr 1998 for Nine Mile Point Nuclear Station,Unit 1
ML20217B0621998-03-31031 March 1998
Monthly Operating Rept for Mar 1998 for Nine Mile Point Nuclear Station,Unit 1
ML17059C1681998-03-19019 March 1998
Revised Niagara Mohawk Powerchoice Settlement Document for NMPC PSC Case Numbers 94-E-0098 & 94-E-0099, Vols 1 & 2
ML20217F4341998-03-19019 March 1998
SER Related to Proposed Restructuring New York State Electric & Gas Corp,Nine Mile Point Nuclear Station,Unit 2
ML17059B9051998-02-28028 February 1998
NMP Unit 1 Boat Samples Analyses Part Iii:Tension Tests, RDD:98:55863-004-000:01
1999-09-30
[Table view] |
Text
tel P~ Vl 0 ~ Vv I s CI I Va DV4.> IC,~ldll VV ~
GE Nuclear Energy GENE B l3-07739-22 Revision 0 Class III Apm 1997 Design Report for Improved Shroud Repair Lower $upport Latches B.H. Koepke, Senior Engineer Reactor ModNcafion Services Reviewecf Oy:
6.A. cleaver, Engineering leader Reactor MocKcation Services Approved by:
.F. odabaugh, Missi n Manager In Vessel Repairs 97oqgoo248 9704 PDR *DOCK 050 P
0 GENE B13-01739-22 Revision 0 April 1997 REVISION STATUS SHEET Revision Approval Date Description 0 G.A. Deaver 4/6/97 Initial Issue
e GENE B53-05739-22 Revision 0 April 1997 IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT Please read carefully The only undertakings of the General Electric Company (GE) respecting information in this document are contained in the contract between Niagara Mohawk Power Corporation and GE, as identified in PO 15247, and nothing contained in this document shall be construed as changing the contract. The use of this information by anyone other than the Niagara Mohawk Power Corporation, or for any purpose other than that for which it is intended is not authorized; and with respect to any unauthorized use, GE makes no representation or warranty, express or implied, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document, or that its use may not in&inge upon privately owned rights.
GENE B13<<01739-22 Revision 0 April 1997 LIST OF FIGURES Figure Subject Page No.
Shroud Repair Lower Support Configuration 13 4.1 Latch FEA Model 14 4.2 Stress Results From a 0.100" Displacement 15 4.3 Original Latch FEA Model 16 4"4 Original Latch Stress (Maximum Stress Location) 17 LIST OF TABLES Table Subject Page No.
4-1 Subsection NG Stress Analysis
'4-2 Stress Corrosion Evaluation 10
GENE B13-01739-22 Revision 0 April 1997
1.0 INTRODUCTION
The purpose of this report is to provide the results of an evaluation performed by GE regarding the redesign of the spring latch which holds the lower wedge in place and is part of the shroud repair assembly. The original function of the latch was to provide a locking feature for the lower wedge which is held onto the lower spring assembly. In the course of installing the lower wedge, the latch only experiences dead weight loads. During plant operation, the original latch was not designed to accommodate sliding of the lower wedge with respect to the lower spring assembly, since it was postulated that the lower wedge would slide on the vessel wall. Since slidirig will occur at the wedge to lower spring interface when the lower wedge does not slide on the vessel wall, the redesign of the latch includes a flexible member which can accommodate vertical displacements which occur during plant operation. See Figure 4.1 for the configuration of the new latch.
2.0 SUM1VGMY This report demonstrates that the new latch design is a significant improvement over the previous design, and that even under very conservative assumptions regarding the loading and displacement of the latch that no failure of the latch will occur in the next operating cycle. It is fully expected that the new latch will last for a significantly longer time based on a 8 to 12 factor of improvement which has been determined based on its ability to accommodate vertical movements. For the expected sliding case where the movement is always along the lower wedge/lower spring interface, the latch will last the remaining life of the plant. Therefore, based on the new latch improvements in combination with the installation change to remove looseness in the lower attachment to the shroud support, satisfactory shroud tie rod repair hardware performance is expected in the future.
3.0 EVALUATION The following evaluations were performed using nominal conditions. In reviewing the issues associated with the latch failure phenomena, there are numerous variables such as &iction factors, material properties, dimensional tolerances, reactor operating conditions, hardware installation details, equipment measurement accuracy, etc. Therefore, the use of nominal conditions is the most realistic approach to assess the redesign of the lower spring latch.
GENE B13-01739-22 Revision 0 Ap)7I 1997 3.1 Plant Operating Conditions The following paragraphs identify the plant operating conditions which cause loads to occur on the latch. The geometry of the hardware at the lower spring support of the shroud repair is shown in figure 1.1. Relative vertical movements between the tie rod components that could affect the loading on the new latch are described in sections 3.1.1 through 3.1.5. Section 3.3 will utilize the displacements defined in sections 3.1.1 through 3.1.5 to establish the maximum latch vertical deflections for the wedge sliding scenarios defined in section 3.2. The adequacy of the new latch to meet the required stress criteria is then demonstrated in section 4.0.
3.1.1 Hydrotest
0 f'ENE B13-01739-22 Revision 0 April 1997
e GENE B13-01739-22 Revision 0 April 1997
GENE B13-01739-22 Revision 0 April 1997
GENE B13-01739-22 Revision 0 April 1997
GENE B13-Of 739-22 Revision 0 April 1997
0 GENE B13-01739-22 Revision 0-April 1997
GENE B13-01 739-22 Revision 0 April 1997
0 GENE B13-01739-22 Revision 0 April 1997
GENE B13-01739-22 Revision 0 Ap17I 1997 4.3 Finite Element Model A 2D plain stress finite element model was prepared for the latch and the Algor linear static analysis sofbvare (Algor Linear Stress Analysis - SSAPOH Rel. 15-FEB-95 Ver. 11.08-3H) was used to determine the latch stresses. Figure 4-1 contains a sketch of the model. Figure 4-2 contains stress contour plot of the Z-direction component stress. The plots show that at the maximum stress location, the stress is almost exclusively bending.
11
GENE B13-01739-22 Revision 0 April 1997 4.4 Comparison of Latch Designs A 2D plain stress finite element analysis was also performed for the original latch. Figure 4-3 contains a sketch of the model for the original latch. Figure 4-4 contains a stress contour plot of the maximum stress location for the original latch for a 0.100" applied displacement. The calculated membrane + bending + peak stress was 772 ksi and the membrane + bending was approximately 400 ksi (using a linear elastic analysis). The original latch was much more highly stressed (by a factor of 8 to 12 times) than the new latch.
5.0 CONCLUSION
S The new latch has been designed to accommodate larger vertical displacements while still maintaining its original function of locking the wedge to the lower spring structure. The stresses are within ASME code limits and the latch has been analyzed to be resistant to stress corrosion for a minimum of 2 years assuming conservative worst case displacements in the latch. It is fully expected that the latch will last for a significantly longer time based on the factor of improvement which has been demonstrated &om the original design. For the expected sliding case where the movement is always along the lower wedge/lower spring interface, the latch will last the remaining life of the plant. Consistent with the inspection recommendations made for the original shroud repair hardware installation, it is recommended that the latches should be visually inspected after the next operating cycle. The condition of the latches and the position of the lower wedge should be evaluated based on a criteria which utilizes reactor temperature and pressure information &om the operating cycle. As discussed in this report, some amount of displacement of the lower wedges can be expected which would be considered normal.
12
GENE B13-01739-22 Revision 0 April 1997 OWER SPRING VESSEL W L lATCH FIGURE 1.1 SHROUD REPAIR LOWER SUPPORT CONFIGURATION 13
GENE B13-01739-22 Revision 0 April 1997 FIGURE 4-1 LATCH FEA MODEL 14
GENE B13-01739-22 Revision 0 April 1997 FIGURE 4-2 STRESS RESULTING FROM A 0.100" DISPLACEMENT 15
GENE B13-01739-22 Revision 0 April 1997 FIGURE 4-3 ORIGINALLATCH FEA MODEL 16
GENE B13-01739-22 Revision 0 Ap)7/ 1997 FIGURE 4-4 ORIGINAL LATCH STRESSES (MAXIMUMSTRESS LOCATION) 17
