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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20209G0211999-06-30030 June 1999 GE-NE-B13-02010-33NP, Evaluation of Limerick Unit 2 Shroud Cracking for at Least One Fuel Cycle of Operation ML20207H8331999-05-31031 May 1999 Non-proprietary Rev 0 to 1H61R, LGS - Unit 2 Core Shroud Ultrasonic Exam B110078, Rev 1 to GE-NE-B1100786-01, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 11998-12-31031 December 1998 Rev 1 to GE-NE-B1100786-01, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 1 ML20236X7641998-07-31031 July 1998 Rev 0 to SIR-98-079, Response to NRC RAI Re RPV Structural Integrity at Lgs,Units 1 & 2 ML20151Z4881998-06-30030 June 1998 GE-NE-B1100786-02, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 2 ML20202B6231998-01-23023 January 1998 Non-proprietary Version of Rev 1 to ER-9605NP, Missile Probability Analysis Methodology for Limerick Generating Station,Units 1 & 2,w/Siemens Retrofit Turbines ML20198B3351997-06-30030 June 1997 Annual 10CFR50.59 & Commitment Rev Rept for 960701-970630, for Limerick Generating Station,Units 1 & 2 ML20135D7721996-04-30030 April 1996 Non-proprietary, Evaluation of Limerick Initial Core Channels for Re-Use on Ex-Shoreham Fuels Bundles ML20101F1901996-02-29029 February 1996 Evaluation of Limerick Unit-1 Core Shroud Insps (Refuel Outage 6) ML20099L6331995-06-30030 June 1995 Annual 10CFR50.59 & Commitment Rev Rept 940701 - 950630 ML20094H0521995-06-30030 June 1995 Pyrolysis Gas Chromatography Analysis of 21 Thermo-Lag Fire Barrier Samples ML20086B1681995-06-26026 June 1995 Ipeee ML20083K6611995-04-26026 April 1995 Rev a to Upgraded Eals ML20078S3351994-02-10010 February 1994 Evaluation of Abnormal Wear at Limerick ML20059K6261993-10-26026 October 1993 SAR Licensing Rept for Spent Fuel Storage Capacity Expansion,Lgs Units 1 & 2 ML20046B5011993-06-27027 June 1993 Evaluation of Potential Internal Radiation Exposures Associated W/Contamination Events in Handling Traversing In-Core Probe (TIP) Tubing at Limerick Nuclear Generating Station & Recommendations for Evaluation & Control of ... ML20127N8811992-12-31031 December 1992 LLRW Shipment Insp Repts 50-352/PA-92-02 & 50-353/PA-92-02 on 921116-18.No Violations or Deviations Noted.Major Areas Inspected:Licensee LLRW Shipment to Burial Site Including Shipping Documentation,Package Insp & Contamination Surveys ML20113D9801991-11-30030 November 1991 Industry Approach to Seismic Severe Accident Policy Implementation, for Nov 1991 ML20082N0471991-08-28028 August 1991 Annual Plan Mod Rept,Jul 1990 Through June 1991 ML20072R0121991-03-15015 March 1991 Common Plant Summary of ASME Section XI Repairs & Repalcements Completed from 890520-901217,Rept 3 ML20072R0071991-03-14014 March 1991 Common Plant Summary Rept for 890520-901217,Periodic Insp Rept 3 ML20066K7201991-01-31031 January 1991 Simulator Certification Submittal, Providing Supporting Info to Form NRC-474 ML20055J3291990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML20042E0901990-03-31031 March 1990 Description of Limerick Inadvertent Spray Actuation Analysis. ML20246A8511989-08-15015 August 1989 Common Plant Summary of ASME Section XI Repairs or Replacements from 870901-890519,Rept 2 ML20248A0261989-06-30030 June 1989 Rev 1 to Response to NRC Bulletin 88-05 for Limerick Generating Station,Unit 2 ML20247J0521989-05-31031 May 1989 Vol Ii,Book 1 to Limerick Generating Station,Unit 2 Independent Design & Const Assessment, Hazards Program Evaluation Suppl ML20245A0801989-04-30030 April 1989 Vol II of Book 1 to Independent Design & Const Assessment, Design Assessment ML20245A0951989-04-30030 April 1989 Vol I of Book 1 to Independent Design & Const Assessment, Assessment Summary ML20245A1031989-04-30030 April 1989 Vol II to Books 2,3 & 4 to Independent Design & Const Assessment,Design Observation Repts,DOR-001 to DOR-118 ML20246P5671989-03-22022 March 1989 Safety Evaluation of Limerick 1,Cycle 3 Revised Core Loading Pattern ML20235Z5981989-02-28028 February 1989 Extension of Equipment Qualification Programs to Limerick Generating Station Unit 2 ML20235Y3811989-02-28028 February 1989 Rev 11 to Design Assessment Rept ML20206K3101988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Limerick Generating Station Unit 1 ML20148R7511988-03-0808 March 1988 Readiness Program Assessment for Limerick 2 ML20236V6631987-08-31031 August 1987 Summary of ASME Section XI Repairs & Replacements Completed from 840928-870831,Rept 1 ML20153G3091986-02-24024 February 1986 Summary of Validation Program for Spds ML20129C3861985-06-30030 June 1985 Control Room Design Review Supplemental Rept 2 to Final Rept of June 1984 ML20112E4491985-02-11011 February 1985 BNL Technical Review Rept & Handwritten Notes of 850121-25 Insp ML20083L7691984-12-31031 December 1984 Descriptive Rept of Archeological Investigation for 220-60 Transmission Line Right-of-Way in Association W/Limerick Nuclear Generating Station,Montgomery & Chester Counties, Pa ML20083L7901984-12-31031 December 1984 Descriptive Rept of Archeological Investigation for 220-61 Transmission Line Right-of-Way in Association W/Limerick Nuclear Generating Station,Montgomery & Chester Counties, Pa ML20107G6421984-10-31031 October 1984 Control Room Design Review, Final Rept,Suppl 1 ML20129D7351984-09-30030 September 1984 Evaluation of Feedwater Containment Isolation Check Valves for Hypothetical Pipe Rupture Condition for Limerick Generating Station ML20098E9061984-09-30030 September 1984 Rev 10 to Design Assessment Rept ML20093C9921984-09-17017 September 1984 Independent Design Review of Limerick Generating Station 1, Core Spray Sys, Bimonthly Status Rept 8 for Period Ending 840915.Related Correspondence ML20096C7651984-08-31031 August 1984 Environ Qualification Rept ML20095A6021984-08-0909 August 1984 Rev 0 to Raceway Separation Criteria. Raceway Separation Test Program Discussion Encl ML20093N6651984-07-31031 July 1984 Nonproprietary Rev 9 to Vol 1 of Design Assessment Rept ML20095D3101984-06-30030 June 1984 Rev 3 to Final Rept Overhead Handling Sys Review ML20092K9461984-06-30030 June 1984 Control Room Design Review,Final Rept 1999-06-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D1211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Lgs,Units 1 & 2. with ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A8861999-09-13013 September 1999 Safety Evaluation Authorizing First & Second 10 Yr Interval Inservice Insp Plan Requestss for Relief RR-01 ML20212A4481999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Limerick Generating Station,Units 1 & 2.With ML20211E9891999-08-20020 August 1999 LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5 ML20210L7051999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Limerick Generating Station,Units 1 & 2.With ML20209G0211999-06-30030 June 1999 GE-NE-B13-02010-33NP, Evaluation of Limerick Unit 2 Shroud Cracking for at Least One Fuel Cycle of Operation ML20209D7741999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2 ML20207H8331999-05-31031 May 1999 Non-proprietary Rev 0 to 1H61R, LGS - Unit 2 Core Shroud Ultrasonic Exam ML20195G4651999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Lgs,Units 1 & 2 ML20209D7791999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Limerick Generating Station,Units 1 & 2 ML20195B3021999-05-0606 May 1999 Rev 0 to PECO-COLR-L2R5, COLR for Lgs,Unit 2 Reload 5 Cycle 6 ML20206N2901999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Limerick Generating Station,Units 1 & 2.With ML20195G4761999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Lgs,Units 1 & 2 ML20206D8971999-04-22022 April 1999 Rev 2 to PECO-COLR-L1R7, COLR for Lgs,Unit 2 Reload 7, Cycle 8 ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML20205N9311999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Limerick Generating Station,Units 1 & 2.With ML20204G9851999-03-11011 March 1999 Safety Evaluation Re Revised Emergency Action Levels for Limerick Generating Station,Units 1 & 2 ML20207J7461999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Limerick,Units 1 & 2.With ML20199G2371999-01-31031 January 1999 Rev 0 to NEDO-32645, Limerick Generating Station,Units 1 & 2 SRV Setpoint Tolerance Relaxation Licensing Rept ML20199L5301999-01-19019 January 1999 Special Rept:On 981214,seismic Monitor Was Declared Inoperable.Caused by Spectral Analyzer Not Running.Attempted to Reboot Sys & Then Sent Spectral Analyzer to Vendor for Analysis & Rework.Upgraded Sys Will Be Operable by 990331 B110078, Rev 1 to GE-NE-B1100786-01, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 11998-12-31031 December 1998 Rev 1 to GE-NE-B1100786-01, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 1 ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20199F9611998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Limerick Generating Station.With ML20198C7151998-12-10010 December 1998 Rev 1 to COLR for LGS Unit 1,Reload 7,Cycle 8 ML20198A3871998-12-10010 December 1998 Safety Evaluation Supporting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power- Operated Gate Valves ML20206N4061998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Limerick Generating Station,Units 1 & 2.With ML20199E3281998-11-23023 November 1998 Rev 2 to PECO-COLR-L2R4, COLR for Lgs,Unit 2,Reload 4,Cycle 5 ML20195C9771998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Limerick Generating Station,Units 1 & 2.With ML20154H5691998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Limerick Generating Station,Units 1 & 2.With ML20151X3511998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Limerick Generating Station Units 1 & 2.With ML20237F0291998-08-27027 August 1998 Special Suppl Rept:On 960425,one Loose Part Detection Sys (Lpds) Was Identified to Be Inoperable.Initially Reported on 960531.Caused by Loose Parts Detector Module.Repairs Performed & Intermittent Ground No Longer Present ML20237D1041998-08-17017 August 1998 Books 1 & 2 of LGS Unit 1 Summary Rept for 960301-980521 Periodic ISI Rept 7 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20236X7641998-07-31031 July 1998 Rev 0 to SIR-98-079, Response to NRC RAI Re RPV Structural Integrity at Lgs,Units 1 & 2 ML20237B4711998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Limerick Generating Station,Units 1 & 2 ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps ML20151Z4881998-06-30030 June 1998 GE-NE-B1100786-02, Surveillance Specimen Program Evaluation for Limerick Generating Station,Unit 2 ML20236P9781998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Limerick Generating Station,Units 1 & 2 ML20196K1801998-06-30030 June 1998 Annual 10CFR50.59 & Commitment Rev Rept for 970701-980630 for Lgs,Units 1 & 2. with ML20249B3501998-06-11011 June 1998 Rev 1 to PECO-COLR-L2R4, COLR for LGS Unit 2 Reload 4,Cycle 5 ML20249A5331998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Limerick Units 1 & 2 ML20247M7071998-05-14014 May 1998 Safety Evaluation Supporting Amend 128 to License NPF-39 ML20217Q5101998-05-0404 May 1998 Safety Evaluation Supporting Amend 127 to License NPF-39 ML20247H5071998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Limerick Generating Station ML20216F3601998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Limerick Generating Station,Units 1 & 2 ML20217M0791998-03-31031 March 1998 Safety Evaluation Supporting Amends 125 & 89 to Licenses NPF-39 & NPF-85,respectively ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20216F9471998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Limerick Generating Station,Units 1 & 2 ML20216F3471998-02-28028 February 1998 Revised Monthly Operating Rept for Feb 1998 for Limerick Genrating Station,Unit 1 1999-09-30
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}(( IVofessional Loss Control, Inc.
STRUCTURAL STEEL ANALYSIS for LIMERICK GENERATING STATION Unit 1
. Reactor Building El . 283' General Floor Area
. Fire Area 47A i
November 1, 1983 l
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E 7922 West Chester Pike e Upper Darby, Pa. 19082 * (215) 853 1700
LIMERICK GENERATING STATION
- 1. AREA DESCRIPTION The area under consideration is the general floor area on the 283' eleva-tion of the Unit 1 Reactor Building (Fire Area 47A). The heaviest combusti-ble loading encountered on this elevation is found in the northeast corner.
The area of heaviest combustible loading is bounded by column lines 20 & 23 and J & H (see Attachment A for sketch of area). Bounding walls are of reinforced concrete construction with an average thickness of 3 ft. Total surface, area for heat transfer is 6947 ft (645 2 m2) (see Attachment A for calculation of areas).
- 2. COMBUSTIBLE LOADING The heaviest concentration of cabling found within this area is located five feet to the west of column line 21.5. The average combustible loading of the cable trays in th*! .rea is 4 lbs/ft2 of tray surface area. There l are no combustible liquids in this area. Enclosed combustibles are not included in the combustible loading.
- 3. VENTILATION PARAMETERS The area under consideration is open to the remainder of this elevation on its south side, however, there are several rooms at floor level that extend ;
a height of 12 ft from the floor. This leaves a ventilation opening above these rooms approximately 54' wide by 17' high.
- 4. CASES EXAMINED A spreading cable fire was assumed to originate in the area of heaviest cable conccntration in order to present the worst case. The fire is assumed to start at a point source and spread horizontally along the cable trays in each direction at a rate of 10 feet per hour. The fire is assumed to extend alcng the north wall and southwest, a distance of 7 feet before the original point source dies 'out after 40 minutes. A maximum surface area of 172 ft2 of cable trays (see Attachment B for list of' cable trays initially burning) will be involved at any one time, which corresponds to a heat output of approximately 3050 kW. This heat output' is assumed constant )
throughout the fire duration. The actual heat output as the fire spreads I out of the area originally involved would be less because concentrations of cabling that would be involved at any one time would be less. '
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- 5. RESULTS The fire was assumed to last 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> with no action taken by plant per-sonnel to extinguish the fire. The peak gas temperature reached was 731*F- (see Attachment C) which is below the critical temperature for 1
the structural steel. Since the fire was assumed to occur in the area j of heaviest combustible loading, the results are considered to be l
representative for the entire general floor area on the 283' elevation j of the Reactor Building.
The position of cable trays relative to structural steel members were examined throughout the 283' elevation of the Reactor Building in order to assess the potential for localized heating. Cable trays were encoun-tered within 1 foot of type 36WF230 beams in numerous locations. Cable
! trays ICCRA, ICCTA, IMIAB, and 1ACYA were positioned 12 inches below a 18WF45 beam located northeast of the drywell near column line 20.
Attachment D contains the results of calculations performed to deter-mine the response of the structural members. The exposure time for the localized heating was taken to be 40 minutes which is the time required for a tray to burn to completion. As can be seen from the results, the member types 36WF230 will not reach their critical temperature during the 40 minute exposure period. The member type 18WF45 will exceed its critical temperature well within the exposure period. Appendix D includes a sketch showing the location of the structural member which will fail due to localized heating effects.
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Unit 1 Reactor Building El. 283' Surface Area Calculation Walls North wall (61' x 29') 1769 ft2 South wall (48' x 12') 576 ft2 East wall (44' x 29') 1276 ft2 West wall (46' x 29') 1334 ft2 4955 ft2 Ceiling Area 1 (30' x 60') - (18' x8' stairwell) 1655 ft2 Area 2- (24' x 14') 336 ft2 1992 ft2 Total Surface Area for Heat Tiansfer 6947 ft2(645m2)
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4 ATTACHMENT A ,
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Cable Trays
' The following cable trays are present in the area defined for the source fire and all of the trays are assumed to burn simultaneously.
Surface Cable Tray No. Tray Width (in) Tray Length (ft) Area (ft 2)_
1M1AC01-02 24 15 30 1M1AD01-02 24 15 30 1M1AE01-02 24 15 30 10CVA18 24 15 30 >
101SA73 24 2 4 1BCWA91 24 7 14 1BCWA92 24 5 10 IBCWA80 24 7 14 1BCWA75 24 5 10 172 172 ft_2 _ x 190 kW/m2 = 3050 kW 10.76 ft'/m' Average Combustible Loading per Tray Surface Area = 4.0 lb/ft2 Fire Duration for Free Burning Tray Fires =
4.0 lb/ft2 + 0.1 lb = 40 minutes ft'/ min t
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CASE NUMBER: .1 BUILDING: UNIT'1 REACTOR BUILDING ELEVATION AND AREA DESCRIPTION: 2" NORTHEAST CORNER CASE DESCRIPTION: ONE OPENING SPREADING CADLE FIRE u a *u * *
- x x * * * * * * * * * * * * * * * * * * *
- CEILING / WALL CEILING / WALL Ao' Ho Aw Q THICKNESS hATERIAL (ft) (ft2) (ft) (ft2) (kW) x nun
'3. 0 CONCRETE 910 17 6947 3050 FIRE IS FUEL CONTROLLED FIRE DURATION GAS TEMPER ATURE (min) (deg.F) 10 220 20 292 30 341 40 383 50 419 60 452
. 70 483 80 511 90 538
-100 563 a 110 507 120 610 130 632 140 ,
653 150 672 160~ 693 170 712 180 731 a
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ATTACHMENT C
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CASE NUMBER: 1 BUILDING:' . UNIT 1 REACTOR DUILDING
-ELEVATION AND. AREA DESCRIPTION: 283' GENERAL FLOOR AREA CASE DESCRIPTION: LOCALIZED HEATING OF MEMBER TYPE 10WF45 EFFECTS OF LOCAL HEATING ON STRUCTURAL GTEEL FIRE TEMPERATURE (deg. F): 1500 WEIGHT OF STEEL MEMBER (lbs./ft): 45 SURFACE OF STEEL MEMBER HEATED (sq.ft./ft): 4.41 TIME STEEL TEMPERATURE
'(min) (deg.F) 5.00 622 10.00 962 15.00 1170 20.00- 1298 25.00 1376 .
30.00 1424 35.00 1453 40.00- 1471 O
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ATTACHMENT D
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CASE NUMBER: 2 BUILDING: UNIT 1 REACTOR BUILDING ELEVATION AND AREA DESCRIPTION: 283' GENERAL FLOOR AREA CASE DESCRIPTION: LOCALIZED HEATING OF MEMBER TYPE 36WF230 EFFECTS OF LOCAL HEATING ON STRUCTURAL STEEL
~
FIRE: TEMPERATURE (deg. F): 1500 WEIGHT OF STEEL MEMBER (lbs./ft): 230 SURFACE OF STEEL MEMBER HEATED (sq.ft./ft): 9.84 TIME STEEL TEMPER ATURE (nin) (deg.F) 5.00 310 10.00 511 15.00 678 20.00 817 25.00 932 30.00 1028 35.00 1108 40.00 1174 9
4 ATTACHMENT D