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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20207L0451999-01-0808 January 1999 Cost-Benefit Risk Analyses:Radwaste Sys for Light Water Reactors ML20248B7341998-05-27027 May 1998 Rev 1 to ES199800777, Engineering Evaluation ML20217P3191998-01-28028 January 1998 Rev 7 to Ccnpp Emergency Action Levels Technical Basis Document ML20135F4741997-03-0606 March 1997 Emergency Action Levels Technical Basis Document, Rev 5 ML20116L9871996-07-25025 July 1996 Portions of Diesel Fuel Oil Sys License Renewal Technical Rept, Written for License Renewal Technical Rept Template Phase 2 Development ML20116L9701996-07-25025 July 1996 Portions of Structures License Renewal Technical Rept, Written for License Renewal Technical Rept Template Phase 2 Development ML20116L9651996-07-25025 July 1996 Entire Feedwater Sys License Renewal Technical Rept, for License Renewal Technical Rept Template Phase 2 Development ML20116L9481996-07-25025 July 1996 Draft Template of License Renewal Technical Rept ML20116L9761996-07-25025 July 1996 Portions of Component Supports License Renewal Technical Rept, Written for License Renewal Technical Rept Template Phase 2 Development ML20117K9691996-06-30030 June 1996 Fitness for Duty Program Performance Data Personnel Subj to 10CFR26, for Period Ending 960630 ML20113E3491996-05-31031 May 1996 USI A-46 Seismic Evaluation ML20112B9701996-05-21021 May 1996 Rev 1 to Aging Mgt Review Rept for Rms (077/079) ML20112C0421996-05-21021 May 1996 Rev 2 to Aging Mgt Review Rept for Component Supports ML20112C0201996-05-21021 May 1996 Rev 2 to Aging Mgt Review Rept for Auxiliary Bldg, Final Rept ML20112C0031996-05-20020 May 1996 Rev 2 to Aging Mgt Review Rept for Turbine Bldg, Final Rept ML20112C0241996-05-20020 May 1996 Rev 3 to Aging Mgt Review Rept for Containment Structure (Sys 059), Final Rept ML20112B9791996-05-20020 May 1996 Rev 2 to Aging Mgt Review Rept for Condensate Storage Tank 12 Enclosure, Final Rept ML20112B9951996-05-20020 May 1996 Rev 2 to Aging Mgt Review Rept for Fuel Oil Storage Tank 21 Enclosure, Final Rept ML20112C0111996-05-20020 May 1996 Rev 2 Aging Mgt Review Rept for Intake Structure, Final Rept ML20112C0361996-05-0909 May 1996 Rev 1 to Aging Mgt Review Rept for Containment Sys (059) ML20112B9741996-05-0101 May 1996 Rev 1 to Aging Mgt Review Rept for MFW Sys ML20112B9641996-05-0101 May 1996 Rev 1 to Aging Mgt Review Rept for Diesel Fuel Oil Sys (023) ML20101J6721996-03-24024 March 1996 Travelers Under Owners Group Vs TSTF Consideration by Needed Date ML20100G1131996-01-31031 January 1996 Rev 3 to Ccnpp EALs Technical Basis Document ML20096D7321996-01-11011 January 1996 Integrated Plant Assessment Methodology, Rev 1 ML20117K9871995-12-31031 December 1995 Rev 2 to Fitness for Duty Program Performance Data Personnel Subj to 10CFR26, for Period Ending 951231 ML20100Q4831995-12-15015 December 1995 1995 Unit II RFO SG 22 All Call Listing ML20113E3551995-11-30030 November 1995 USI A-46 Relay Evaluation ML20087K7921995-08-18018 August 1995 Rev 0 to Calvert Cliffs Nuclear Power Plant Integrated Plant Assessment Methodology ML20086S9221995-07-17017 July 1995 Best Estimate Chemistries for Calvert Cliffs Reactor Vessel Beltline Welds, Rev 1 ML20100Q3291995-05-12012 May 1995 1995 Unit II RFO Steam Generator 21 All Call Listing ML20077M8271995-01-10010 January 1995 Simulator Four-Yr Certification Rept ML20076F8851994-10-13013 October 1994 Probabilistic Risk Assessment Evaluation of Tornado- Generated Missile Impact on Ccnpp EDG Engine Air Intake & Exhaust ML20058G1751993-11-30030 November 1993 Application of Reactor Vessel Surveillance Data to Calvert Cliffs Unit 1 ML20059F8901993-10-15015 October 1993 Nonproprietary Version of Calvert Cliffs Nuclear Power Plant,Unit 1 & 2 Pressurizer Inconel 600 Sleeve Nozzle SAR for Alternative Roll/Plug Repairs ML20056F9881993-08-25025 August 1993 Instrumentation & Control Sys Design Rept, for Emergency Diesel Generator Project ML20046B1541993-07-26026 July 1993 Rev 0 to Electrical Engineeing Design Rept,Edg Project. ML20046A4781993-06-15015 June 1993 Rev 0 to Emergency Action Levels Technical Basis Document. W/Two Oversize Encls ML20056C2521993-05-0101 May 1993 Integrated Plant Assessment Methodology,Vol 2:Component Evaluation ML20064D4081993-03-31031 March 1993 SGs 21 & 22 Eddy Current Testing Final Rept Mar 1993 ML20044C2061993-03-0808 March 1993 Component Level Itlr Screening Results for Reactor Coolant Sys. ML20044C2401993-02-23023 February 1993 Component Level Itlr Screening Results for Containment Sys. ML20126D7051992-12-18018 December 1992 Rev 0 to Civil Engineering Design Rept EDG Project ML20044C2411992-09-30030 September 1992 Component Level Itlr Screening Results for Compressed Air Sys. ML20044C2451992-09-23023 September 1992 Component Level Itlr Screening Results for Salt Water Cooling Sys. ML20066D7871991-01-0707 January 1991 Simulator Certification NRC Submittal Document for Plant Ref Simulator at Calvert Cliffs Nuclear Power Plant ML20058A4781990-06-30030 June 1990 Final Rept on Reactor Vessel Pressure-Temp Limits for Calvert Cliffs Unit 2 for 12 Efpys ML19332B6061989-10-31031 October 1989 Final Rept Low Temp Overpressure Protection Pressure Temp Limits for Calvert Cliffs Unit 1. ML20247R0881989-09-18018 September 1989 Basis for Determination:Unit 1 Safe Operation Re Unit 2 Pressurizer Heater Sleeve Leakage ML19332B6081988-12-31031 December 1988 Final Rept Pressure Temp Limits for Calvert Cliffs Nuclear Power Plant Unit 2. 1999-01-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G6971999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Calvert Cliffs Npp,Units 1 & 2.With ML20216J8731999-09-10010 September 1999 Rev 52 to QA Policy for Calvert Cliffs Nuclear Power Plant ML20212A4441999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ccnpp,Units 1 & 2. with ML17326A2011999-08-23023 August 1999 LER 99-004-00:on 990724,reactor Tripped Due to Main Transformer Bushing Flashover.Plant Was Brought to SS & Components Were Tested & Performed Satisfactorily.With 990823 Ltr ML20210S6091999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ccnpp,Units 1 & 2. with ML20210N6001999-07-27027 July 1999 ISI Summary Rept for Calvert Cliffs Unit 2. Page 2 of 3 in Encl 1 of Incoming Submittal Not Included ML20210B7941999-07-15015 July 1999 SER Denying Licensee Request for Changes to Current Ts,Re Deletion of Tendon Surveillance Requirements for Calvert Cliffs LD-99-039, Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified1999-06-30030 June 1999 Part 21 Rept Re Defect of Abb 1200A 4kV Vacuum Breakers. Initially Reported on 990625.Defect Results in Breaker Failing to Remain in Closed Position.Root Cause Evaluation & Corrective Action Plan Being Developed.Licensee Notified ML20209F1721999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Calvert Cliffs Npp.With LD-99-035, Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed1999-06-25025 June 1999 Part 21 Rept Re Abb 1200A 4KV Vacuum Breakers Performing Trip Free Operation When Close Signal Received by Breaker. Defect Results in Breaker Failing to Remain in Closed Position.Root Cause & CAP Being Developed ML20196C6981999-06-21021 June 1999 Safety Evaluation Concluding That Use of ASME Section XI Code Including Summer 1983 Addenda as Interim Code for Third 10-year Insp Interval at Calvert Cliffs Units 1 & 2 Until Review of 1998 Code Completed,Would Be Acceptable ML20195K2811999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Ccnpp,Units 1 & 2. with ML20206R5871999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ccnpp,Units 1 & 2. with ML20195B3891999-04-30030 April 1999 0 to CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models ML20205N2951999-04-13013 April 1999 Special Rept:On 990314,fire Detection Sys Was Removed from Svc to Support Mod to Replace SRW Heat Exchangers in Unit 2 SRW Room During Unit 2 Refueling Outage.Contingency Measure 15.3.5.A.1 Will Continue Until Fire Detection Sys Restored ML20210T5211999-04-0101 April 1999 Rev 0 to Ccnpp COLR for Unit 2,Cycle 13 ML20205P5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20204H6471999-03-21021 March 1999 SER Re License Renewal of Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20207M8321999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Calvert Cliffs Nuclear Power Plant.With ML20203D4311999-02-0505 February 1999 Safety Evaluation Accepting Procedure Established for long-term Corrective Action Plan Related to Containment Vertical Tendons ML20199G4671999-01-20020 January 1999 SER Accepting USI A-46 Implementation for Plant ML20206Q3221999-01-11011 January 1999 Special Rept:On 981226,wide Range Noble Gas Effluent RM Was Removed from Operable Status.Caused by Failure of mid-range Checksource to Properly Reseat.Completed Maint & post-maint Testing & RM Was Returned to Operable Status on 990104 ML20207L0451999-01-0808 January 1999 Cost-Benefit Risk Analyses:Radwaste Sys for Light Water Reactors ML20199F4781999-01-0808 January 1999 Safety Evaluation Concluding That Bg&E Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking.Concludes GL 95-07 Actions Were Addressed ML20198S7591999-01-0707 January 1999 SER Accepting Quality Assurance Program Description Change for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20207M2281998-12-31031 December 1998 1998 Annual Rept for Bg&E. with ML20199E2931998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Calvert Cliffs Npp. with ML20206R9911998-12-0808 December 1998 Rept of Changes,Tests & Experiments (10CFR50.59(b)(2)). with ML20198B2631998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2.With ML20195H1001998-11-16016 November 1998 Safety Evaluation of First Containment Insp Interval Iwe/Iwl Program Alternative ML20196E2211998-10-31031 October 1998 Non-proprietary Rev 03-NP to CEN-633-NP, SG Tube Repair for Combustion Engineering Designed Plant with 3/4 - .048 Wall Inconel 600 Tubes Using Leak Limiting Alloy 800 Sleeves ML20195E5281998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Calvert Cliffs Nuclear Power Station,Units 1 & 2.With ML20154Q7191998-10-21021 October 1998 Special Rept:On 980923,unit 1 Wrngm Was Removed from Operable Status.Caused by Failure of Process Flow Transducer.Completed Maint to Remove Process Flow Transducer Input to Wrngm Microprocessor & Completed Formal Evaluation ML20154G3931998-10-0505 October 1998 Safety Evaluation Concluding That Flaw Tolerance Evaluation for Assumed Flaw in Inboard Instrument Weld of Pressurizer Meets Rules of ASME Code ML20154M5841998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Calvert Cliffs Nuclear Plant,Units 1 & 2.With ML20153C2571998-09-18018 September 1998 Special Rept:On 980830,wide Range Noble Gas Monitor (Wrngm) Channel Was Removed from Operable Status.Caused by Need to Support Performance of Required 18-month Channel Calibr.Will Return Wrngm to Operable Status by 980925 ML20153C1091998-09-18018 September 1998 Part 21 Rept Re Defective Capacity Control Valves.Trentec Personnel Have Been in Contact with Bg&E Personnel Re Condition & Have Requested Potentially Defective Valves ML20151U5441998-09-0404 September 1998 Bg&E ISI Summary Rept for Calvert Cliffs ML20151T5281998-09-0101 September 1998 Special Rept:On 980819,declared Rv Water Level Monitor Channel a Inoperable.Caused by Failure of Three Heated Junction Thermocouples (Sensors) in Lower Five Sensors. Channel a & B Rv Water Level Probes Will Be Replaced ML20151Y1191998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Calvert Cliffs Nuclear Power Plant Units 1 & 2.With ML20237D4981998-08-19019 August 1998 Safety Evaluation Accepting Licensee Request for Extension of Second ten-year Inservice Insp Interval 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 ML20237B9371998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Calvert Cliffs Nuclear Power Plant ML20237D5941998-07-22022 July 1998 Rev 2 to Ccnpp COLR for Unit 2,Cycle 12 ML20236L7521998-07-0606 July 1998 Safety Evaluation Granting Bg&E 980527 Request for Relief from Requirement of Section IWA-5250 of ASME Code for Calvert Cliffs Unit 2.Alternatives Provide Reasonable Assurance of Operational Readiness ML20236F7791998-06-30030 June 1998 Safety Evaluation Authorizing Request for Temporary Relief from Requirement of Subsection IWA-5250 of ASME Code,Section XI for Plant,Unit 1 ML20236R0881998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Calvert Cliffs Nuclear Power Plant,Units 1 & 2 ML20236X3101998-06-19019 June 1998 Rev 1 to Calvert Cliffs Nuclear Power Plant COLR for Unit 2,Cycle 12 ML20249A9571998-06-15015 June 1998 Special Rept:On 980430,fire Detection Sys Was Removed from Svc to Support Mod to Purge Air Sys 27-foot Elevation & 5-foot Elevation East Piping Penetration Rooms.Installed Temporary Alteration & Returned Fire Detection Sys to Svc ML20249A7711998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Ccnpp,Units 1 & 2 1999-09-30
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A Review of the Evaluations Performed For a Non-Conformance in the Main Steam Line For the Number 12 Steam Generator by John P. Houstrup Combustion Engineering, Inc.
for Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant Lusby, MD September, 1987 O g79,30 Dt g P 05000317 PDR
Table of Contents
- 1. Discussion'of the Problem
- 2. Probable.Cause-
- 3. ' Conclusions
- 4. Discussion of Technical Reviews
- 5. . References l
- 1. Discussion of the Problem .
During a voluntary inspection of piping components in Unit 1 of the Calvert Cliffs Nuclear Power Plant, an area of a pipe wall was discovered to be less than the minimum thickness required for general design by the Piping Design Code, USAS B31.1, (1967). The area is in the main steam line for steam generator 12 and is located in the base metal of the horizontal run just downstream from the second elbow af ter the flow restrictor. The area of non-conformance is approximately 1/2 inch in axial length along the pipe and 24 inches in circumferential length, located immediately adjacent to the weld of the pipe run to the second elbow. A graphical representation of this area is shown in Figure 1 of Reference 3. The pipe is 34 inches in diameter with a i design pressure of 1000 psi and design temperature of 580*F, i and fabricated of ASTM A-155 KCF70 grade 1 (welded A-515 grade 70 plate) material. The required minimum wall is 0.950 inches, the average as measured wall is 1.08 inches and the smallest measured wall thickness is 0.86 inches.
- 2. Probable Cause It is this reviewers opinion that this area of reduced wall thickness is a result of the initial fabrication and was not operationally induced. The area is adjacent to a field weld. It is probable that this thin-walled pipe was slightly bent or dented in handling and was ground locally on the I.D. in the field for weld fit up. A pictorial of this is shown in Figure 1. This kind of fabrication action would result in the shape of the thin area observed and would result in a fabrication non-conformance rather than a flaw. This opinion is substantiated by the original weld 1
radiographs that show a slightly darker band in this region, and by the OD contours as plotted on Sheet 8 of Reference 1.
I i
t 781^J Weso 20'!!
Fust THicwess 3
1 -
I A
EL 00 60 JgpJ y ?!PY NALL gy ,g g, f,dALL
_b L lbATPKIAL fROVAJD AwAv foe fir-Up Figure 1 Probable Configuration
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- 3. Conclusions A review of the evaluations performed to demonstrate the adequacy of this pipe and the results of the NDE used to establish the existing as-built geometry leads to the conclusion that this pipe in its present configuration meets the requirements of the original Construction Code, USAS B31.1 (1967), with the additional analysis provided in Reference 3. The NDE showed no evidence of cracks or flaws, only the local thin area. Thus, considering this area as an original fabrication non-conformance, Reference 3, if accepted by the ANI and the Regulatory authorities, provides full justification and the problem is solved. If it is
~
mandated that this area be considered as a flaw, Reference 2 (modified to show compliance with IWB-3612 rather than IWB-3611) and Reference 3 demonstrate full compliance with IWB-3610 (a) and (b) of ASME B&PV Code Section XI, 1983 with S-83 Addenda. This again completes the problem except for additional future examinations as required by Section XI.
- 4. Discussion of Technical Reviews (a) BG&E Calculation M-86-10 dated 12-9-86 (Reference 1).
This calculation established the basic requirements for the pipe and uses a novel reinforcement approach to justify the reduced thickness. The concept of local reinforcing would be valid for some shapes of reduced wall thickness, but does not apply to this long narrow area and has been rejected by the NRC.
(b) SWRI Report 17-4772-861, " Thin Walled Pipe Integrity Assessment - A Fracture Evaluation" dated March, 1987 (Reference 2)
i This is a fracture mechanics evaluation of the reduced wall area assuming it as a circumferential crack. The methods used are those of Appendix A, IWB-3610(a) and IWB-3611 of the ASME B&PV Code Section XI, 1983 with S-83 Addenda. A lower bound material toughness of K73 = KIc = 100 ksi 7b bI was assumed and crack growth over the life of the plant was determined to be small (0.045 inches in the remaining 30 years). The critical crack depth was determined to be 4.29 l inches, or through wall. A pressure of 1693 psi was used.
l A simplified limit load evaluation considering a 360*
l l circumferential crack showed that a remaining ligament of 0.405 inch or less (0.675 crack depth) is necessary for plastic collapse, using the methods of IBW-3640 for austenitic piping. (Note: this is not completely l applicable and IWB-3640 is not included in the 83 Edition, S-83 Addenda of Section XI).
This evaluation used only membrane loadings (pipe bending was not included, nor can Appendix A methods accommodate them), used a very high pressure of 1693 psi, a high membrane correction factor, M , f 1.65 (should be 1.1), and m
applied Appendix A to a thin-walled pipe. Appendix A was developed for ferritic vessels 4 inch and greater in thickness. It's use in this case (Class 2 thin-walled pipe) would be permitted - IWC-3000 (Class 2) refers back to IWB-3000; IWB-3620 (ferritic components less than 4 inches thick) refers back to IWB-3610, the paragraph used.
However, the potential for ductile flaw growth in ferritic piping is not included, nor are the effects of gross pipe bending. The results should be conservative.
An application of the currently being developed IWB-3650 criteria for ferritic piping, shown in Addendum 1, using LEFM techniques and including pipe bending, yields a K7 =
35.6 ksi tIin that is compared with an allowable of 135.9
i l
ksiyinasrequiredforthismaterialusingminimum properties. Thus, even if this thin area is considered as a crack, both flaw evaluations conservatively justify continued operation for the remaining life of the plant.
(c) SWRI Report 17-4772-861, " Stress Analysis of Thin Pipe i Region in No. 12 Steam Generator Main Steam Line",
dated February, 1987 (Reference 3)
This is a finite element stress analysis of a section of straight pipe and a full elbow with a reduced thickness area at the joint simulating the actual area. The results demonstrate that the primary local membrane stresses for pressure and dead weight loadings meet the stress allowables of USAS B31.1 (1967), even in the reduced thickness areas.
The sophisticated approach used (as opposed to the simple thickness formula) is permitted by 331tl as stated in the Forward:
... a designer who is capable of a more rigorous analysis than is specified in the Code may justify a
'less conservative design, and still satisfy the basic intent of the Code."
and in the
Introduction:
I 1
"It is intended that a designer capable of applying more complete and rigorous analysis to special or unusual problems shall have the latitude in the i development of such designs and the evaluation of complex or combined stresses." !
This reviewer agrees with the conclusion stated in the summary that the reduced section of the pipe meets the original design requirements of the Construction Code 1.
l
[(USAS B31.1(1967)] for primary loadings. Although not evaluated in the referenced report, the expansion bending and membrane stresses (axial in the pipe and normal to the reduced section) are low (see P e in Addendum 1) at this location and the total combined axial stress should be less than S, a conservative approach to B31.1.
- 5. References
- 1. BG&E Calculation M-86-10 dated 12-9-86 by W. C. Holston.
I
- 2. SWRI Report 17-4772-861, " Thin Walled Pipe Integrity i Assessment - A Fracture Evaluation" dated March, 1987.
- 3. SWRI Report 17-4772-861, " Stress Analysis of Thin Pipe Region in No. 12 Steam Generator Main Steam Line", dated February, 1987.
- 4. USAS B31.1 Code for Pressure Piping (1967)
- 5. ASME B&PV Code Section XI, " Inservice Inspection of Nuclear Power Plant Components", 1983 Edition, Summer 83 Addenda.
s a
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Addendum 1 Application of Currently Being Developed IWB-3650 and Appendix "Z" for Flaw Evaluation of Ferritic Piping.
The most conservative approach (LEFM) will be used. This will demonstrate the validity of the Reference 2 results.
Pipe -
A-155 KCF70 Class 1 (A-515 Grade 70 plate) 34" O.D. 1.08 wall Flaw -
24" long, 0.276 deep circumferential on I.D.
l in base metal Loadings P = 1000 psi P
m = 7.57 ksi P3 = 1.70 ksi E' = 30,800 ksi T>500'F P
e = 3.85 ksi (on upper shelf)
/, Material Category 1 2
Use J IC = 600 in#/in 6' = 27.1 ksi Y
L-IWB-3650 Criteria for acceptance
'K ,5.(J 7 IC E'/1000)0.5 Appendix "Z" Z-7300 l
K7 = (SF) 17 a (P,F,+(Pb+ )F3 b l
F, = .1.10 + ( [ .15 2 41 + 16. 77 2 ( X 6 /fr) . 8 5 5 - 14.944 (X9/;r)]
I F
b=1.10+((.09967+5.0057(Xe/W).565 - 2.8329 (XG/#)]
x=(= 5 g = .2546 A= 24 100.028
= *2399
?f F,= 1.30' Fb = 1.29 Ky = 35.60 ksi y in (SF)'= 2.77 (J 1c E'/1000)0.5 135.94 ksi %
=
35.60 < 135.94 , /, flaw acceptable i
JP068
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