Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 24,Unit 2,3,Turbine Bldg El 116 Ft Common Equipment Area (Beneath Switchgear Rooms),Fire Area 78BML20126J825 |
Person / Time |
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Site: |
Peach Bottom |
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Issue date: |
05/20/1985 |
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From: |
Dewey J, Melly B PROFESSIONAL LOSS CONTROL, INC. |
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To: |
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Shared Package |
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ML20126J788 |
List: |
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References |
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NUDOCS 8506100706 |
Download: ML20126J825 (12) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217B9061999-10-0101 October 1999 Proposed Tech Specs Re Control Rod Block Instrumentation ML20212H5261999-09-27027 September 1999 Proposed Tech Specs Pages,Revising TS Re Loss of Power Setpoints for 4 Kv Emergency Buses ML20210N0801999-08-0606 August 1999 Proposed Tech Specs Incorporating Note Which Will Permit one-time Exemption Until 990930,from 90 F Limit Stated in SR 3.7.2.2 ML20210E6001999-07-21021 July 1999 Proposed Tech Specs,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20209F7751999-07-12012 July 1999 Proposed Tech Specs Sections 2.1.1.2 & 5.6.5,incorporating Revised SLMCPR Due to Use of Cycle Specific Analysis & Deleting Previously Added Footnotes Which Are No Longer Necessary ML20209D9861999-07-0808 July 1999 Proposed Final Tech Spec Pages Correcting Minor Administrative Errors in Figure Showing Site & Exclusion Boundaries & Two SRs ML20209B9211999-07-0101 July 1999 Proposed Tech Specs,Reflecting Change in Corporate Structure ML20196A5441999-06-14014 June 1999 Proposed Final Tech Spec Pages for License Change Request ECR 98-01802 Re Installation of Digital Power Range Neutron Monitoring (Prnm) Sys & Incorporation of long-term thermal- Hydraulic Stability Solution Hardware ML20195B8271999-05-25025 May 1999 Proposed Final Tech Specs Pages for License Change Application ECR 96-01511 Re Rev to Loss of Power Setpoints for 4 Kv Emergency Buses ML20206C5821999-04-20020 April 1999 Rev 4 to RW-C-100, Solid Radwaste Sys Process Control Program (Pcp) ML20205F6391999-03-29029 March 1999 Proposed Tech Specs Pages,Deleting Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20207E2551999-03-0101 March 1999 Proposed Tech Specs Supporting PBAPS Mod P00507 Which Will Install Power Range Neutron Monitoring Sys Incorporate long-term T/H Stability Solution Hardware ML20202E6251998-12-31031 December 1998 PBAPS Unit 2 Cycle 13 Startup Rept. with ML20198N2531998-12-24024 December 1998 Proposed Tech Specs Revising Setpoints & Limits of Allowable Values for LOP Instrumentation for 4kV Emergency Buses Contained in TS Table 3.3.8.1-1, LOP Instrumentation ML20195J1651998-11-16016 November 1998 Rev D to LGS Emergency Preparedness NUMARC Eals ML20195J1541998-11-16016 November 1998 Rev D to PBAPS Emergency Preparedness NUMARC Eals ML20154C8271998-09-29029 September 1998 Proposed Tech Specs SR 3.6.4.1.2,revising Wording to Maintain Requirement That Secondary Containment Is Not Breached at Any Time When Secondary Containment Is Required ML20151Y3841998-09-14014 September 1998 Revised Proposed Final TS Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Units 2 & 3 ML20151Y3711998-09-11011 September 1998 Proposed Final TS Pages for License Change Application ECR 98-01403,revising SLMCPRs for Unit 2 ML20151Y3651998-09-11011 September 1998 Proposed Final TS Pages for License Change Applications ECR 96-02324 & 98-00499,revising MSIV Leakage & Safety Relief Valve Surveillance Testing ML20151T0421998-08-31031 August 1998 Proposed Final Tech Specs Pages for License Change Application ECR 97-02809,incorporating end-of-cycle Recirculation Pump Trip Sys at Plant ML20236W2201998-07-29029 July 1998 Proposed Tech Specs,Supporting Installation of Mod P00271 for Unit 2 Re Replacement of Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20236R3121998-07-10010 July 1998 Proposed Tech Specs Pages for License Change Application ECR 98-01403,revising TS Section 2.0.W/non-proprietary Addl Info Re 1.10 Cycle Specific SLMCPR Cycle 13 ML20236P7531998-07-0909 July 1998 Proposed Tech Specs Supporting Installation of Mod P00271, for Unit 2 Re Facility Operating License Change Request 93-18 ML20247C2611998-05-0101 May 1998 Proposed Tech Specs Deleting Requirements for Functional Testing of SRVs During Each Unit Startup ML20217K3651998-04-28028 April 1998 Proposed Tech Specs Bases Through Unit 2 Bases Rev 17 & Unit 3 Bases Rev 19 ML20206C5711998-04-16016 April 1998 Rev 11 to ODCM for Pbaps,Units 1 & 2 ML20217G7531998-03-20020 March 1998 Proposed Tech Specs Re end-of-cycle Recirculation Pump Trip Sys at Plant ML20217Q4711998-03-0202 March 1998 Proposed Tech Specs Adding Requirements to Achieve Compliance w/10CFR50.36a, TS on Effluents from Nuclear Power Reactors ML20202F4201998-02-0404 February 1998 Proposed Tech Specs Revising SR 3.6.4.1.2 & Associated Bases to Reflect Changes in Requirements for Secondary Containment Doors ML20202H4141998-01-31031 January 1998 Cycle 12 Startup Rept Unit 3 ML20211H9281997-09-26026 September 1997 Proposed Tech Specs,Replacing Page 2.0-1 & Adding Page 5.0-21 for Unit 3 ML20211F4001997-09-22022 September 1997 Proposed Tech Specs Replacing Source Range & Intermediate Range Monitors W/New Wide Range Neutron Monitoring Sys ML20141G4871997-06-30030 June 1997 Proposed Tech Specs,Revising TS Section 2.0, Safety Limits to Incorporate Revised SLMCPRs Due to Use of GE13 Fuel Product Line & cycle-specific Analysis Performed by GE ML20140D8601997-06-0404 June 1997 Proposed Tech Specs,Revising Section 3.8.2.1 to Eliminate Inconsistency Between Requirements for ECCS Operability & auto-start & Trip Bypass of of EDGs on ECCS Initiation Signal During Listed Events in Application ML20141L0111997-05-23023 May 1997 Proposed Tech Specs Revising Section 5.5.12 to Exclude Measured Main Steam Isolation Valves Leakage from Total Type B & C Local Leak Rate Test Results ML20141E0801997-05-0909 May 1997 Proposed Tech Specs 3.6.1.3.16,replacing Frequency of Primary Containment Purge & Exhaust Valve Inflatable Seals ML20141J0311997-05-0808 May 1997 Rev 7 to Pump & Valve IST Program Third Ten Yr Interval ML20137P7561997-03-31031 March 1997 Proposed Tech Specs,Extending Surveillance Interval for Calibr of Average Power Range Monitor Flow Bias Instrumentation from 18 Months to 24 Months ML20217M8301997-01-30030 January 1997 Rev 10 to ODCM, for Peach Bottom Atomic Power Station Units 1 & 2 ML20134A6751997-01-24024 January 1997 Cycle 12 Startup Rept Unit 2 ML20134F6121996-10-30030 October 1996 Proposed Tech Specs,Section 2.0,revising Slmcprs Due to GE Determination That Previous Calculation Is Nonconservative ML20138B0081996-09-27027 September 1996 Rev 3 to Solid Radwaste Sys Process Control Program (Pcp) ML20117L2891996-09-0606 September 1996 Proposed Tech Specs 3.3.5.1, ECCS Instrumentation, & 3.8.1, AC Sources-Operating ML20117F9471996-08-27027 August 1996 Proposed Tech Specs Re CRD Charging Water Header Pressure for Shutdown Margin Test ML20117H6761996-08-23023 August 1996 Proposed Tech Specs 2.0 Re Safety Limits ML20117M7041996-06-13013 June 1996 Proposed Tech Specs,Sr 3.3.1.1.12,for APRM Flow Biased High Scram Function,Allowing SR to Be Performed W/O Entering Associated Conditions & Required Actions for Up to Six H Provided Core Flow at or Above 82% ML20101K8131996-03-25025 March 1996 Proposed Tech Specs Section 2.0 Re Safety Limits ML20100J7591996-02-15015 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20096F1481996-01-16016 January 1996 Proposed Tech Specs Base Changes Re Implementation of Main Stack & Vent Stack Radiation Monitoring Sytems 1999-09-27
[Table view] Category:TEST REPORT
MONTHYEARML20202E6251998-12-31031 December 1998 PBAPS Unit 2 Cycle 13 Startup Rept. with ML20202H4141998-01-31031 January 1998 Cycle 12 Startup Rept Unit 3 ML20134A6751997-01-24024 January 1997 Cycle 12 Startup Rept Unit 2 ML20096B4311995-12-31031 December 1995 Cycle 11 Startup Rept ML20078S9501994-12-16016 December 1994 PBAPS Cycle 11 Startup Rept for Unit 2 ML20063J9191994-02-10010 February 1994 Cycle 10 Startup Rept ML20101S9401991-12-31031 December 1991 PBAPS Unit 2 Vessel Surveillance Matls Testing & Fracture Toughness Analysis ML20090L8131991-12-24024 December 1991 Reactor Containment Bldg Integrated Leak Rate Test Rept ML20082B9391991-07-17017 July 1991 Rept of Plant Start-Up Following Eighth Refueling Outage on 910112-0412.W/undated Ltr ML20079C9511991-03-29029 March 1991 Reactor Containment Bldg Integrated Leak Rate Test Rept ML20067E5111991-01-0303 January 1991 Rev 1 to TP-161, Peach Bottom Atomic Power Station Simulator Performance Test Examples ML20033G7331990-04-0202 April 1990 Rept of Plant Startup Following Seventh Refueling Outage, 870331-900202 ML19332C8201989-11-17017 November 1989 Rept of Plant Startup Following Seventh Refueling Outage, 870315-891010. W/891117 Ltr ML20244C2571989-01-31031 January 1989 Reactor Containment Bldg Integrated Leak Rate Test ML20155G1931988-10-31031 October 1988 Rept on Restart Review Panel Assessment of Readiness for Restart ML20155J8451988-05-27027 May 1988 App R Multiple High Impedance Cable Fault Flame Test Rept ML20154C7101988-05-0606 May 1988 Vessel Surveillance Matls Testing & Fracture Toughness Analysis ML20138Q9771985-10-28028 October 1985 Rept of Plant Startup Following Sixth Refueling Outage, 840428-850713 ML20135D5431985-06-11011 June 1985 Reactor Containment Bldg Integrated Leakage Rate Test Rept ML20126J8401985-05-30030 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 51,Unit 2,3,Turbine Bldg El 135 Ft Corridor to Switchgear Rooms,Fire Area 78A ML20126J9761985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 96,Unit 2,3,Turbine Bldg El 116 Ft Toilet Area,Fire Area 115 ML20126J9901985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 97,Unit 2,3,Turbine Bldg El 116 Ft Janitor Room,Fire Area 116 ML20126J9521985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 95,Unit 2,3,Turbine Bldg El 116 Ft Clean Clothes Room,Fire Area 114 ML20126J9261985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 94,Unit 2,3,Turbine Bldg El 116 Ft Counting Room,Fire Area 78E ML20126J9091985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 93,Unit 2,3,Turbine Bldg El 116 Ft Health Physics Util Room,Fire Area 82 ML20126J8861985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 92,Unit 2,3,Turbine Bldg El 116 Ft Conventional Chemistry Lab,Fire Area 78D ML20126J8581985-05-24024 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 91,Unit 2,3,Turbine Bldg El 118 Ft Radiation Chemistry Lab,Fire Area 78C ML20126J8251985-05-20020 May 1985 Rev 0 to Structural Steel Analysis for Peach Bottom Generating Station:Calculation 24,Unit 2,3,Turbine Bldg El 116 Ft Common Equipment Area (Beneath Switchgear Rooms),Fire Area 78B ML20238D8651985-02-28028 February 1985 Hydrogen Water Chemistry Mini Test Final Rept. W/Two Oversize Drawings.Related Info Encl ML20092D7071984-06-20020 June 1984 Ultrasonic Indications in Jet Pump Instrumentation Penetrations of Peach Bottom Atomic Power Station,Unit 3 ML20084R3001984-03-14014 March 1984 Fire Endurance & Hose Stream Tests on Floor Penetration Fire Stops Design Fc 350 ML20084R2921984-02-16016 February 1984 Fire Endurance & Hose Stream Tests on Wall Penetration Fire Stops Design Wp 713 ML20082N3381983-12-31031 December 1983 HVAC Damper Program Penetration Seal Test Results & Exemption Requests ML20084R2881983-11-0404 November 1983 Fire Endurance & Hose Stream Tests on Wall Penetration Fire Stops Design WP694 ML20082G1231983-08-23023 August 1983 Reactor Containment Bldg Integrated Leakage Rate Test Rept, Conducted During Aug 1983 ML20080F9801983-02-14014 February 1983 Rept of Plant Startup Following Fifth Refueling Outage, Feb 1983 ML20027C3241982-02-28028 February 1982 Rept of Plant Startup Following Fifth Refueling Outage, 820219 ML20032A8161981-10-21021 October 1981 Revised Pages 90 & 91 of Reactor Containment Bldg Integrated Leak Rate Test Rept ML20039B6801981-09-0606 September 1981 Primary Reactor Containment Integrated Leakage Rate Test Rept ML20041C8071981-03-0707 March 1981 Rept of Plant Startup Following Fourth Refueling Outage, 810307 ML20062K2481980-07-28028 July 1980 Primary Reactor Containment Integrated Leak Rate Test ML19345A8241980-03-31031 March 1980 Rept of Plant Startup Following Fourth Refueling Outage, Mar 1980 ML19344D2631980-03-0505 March 1980 Rept of Startup Following Third Refueling Outage,Sept 1979 ML19274D3301978-10-31031 October 1978 Rept of Plant Start-up Following Third Refueling Outage Sept-Oct 1978. Assures That Unit 2 Refueling Outage Caused No Conditions or Sys Characteristics to Diminish Safe Operation ML20081B9871977-04-0404 April 1977 Reactor Containment Bldg:Integrated Leakage Rate Test Rept ML20072N7491975-07-22022 July 1975 Noise Level Measurements Surveillance Test Results ML20072N7551975-04-30030 April 1975 Noise Level Measurements Surveillance Test Results ML20072N7781974-10-29029 October 1974 Noise Level Measurements Surveillance Test Results ML20072N7611974-07-25025 July 1974 Noise Level Instruments Surveillance Test Results ML20072N7701974-02-24024 February 1974 Noise Level Measurements Surveillance Test Results 1998-12-31
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' STRUCTURAL STEEL ANALYSIS
- for PEACH BOTTOM GENERATING STATION Calculation-No.24 Unit 2,3 Turbine Building El. 116" Common Equipment Area (Beneath Switchgear Roome)
Fire Area 78B 77 PDR Prepared by:
Date:_[_2d_((
7 Reviewed by:
h O
Revision: O 7922 West Chester Pike e Upper Darby, Pa. 19082 * (215) 853-1700
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PEACH BOTTOM GENERATING STATION 1.
ARgA_QgggRIPTIgN The area under conalderation la the Common Equipment Area on the 116' elevation of the Turbine Building (Fire Area 78B).
The bounding walls are constructed of reinforced concrete with an average: thickness of 3 ft.
The total surface area for. heat transfer is 9,552 ft2 (see Attachment A for a sketch of the area under consideration).
2.
"ggnBygIIBLg_LgAgINg This area contains cable trays.
The avarage loading in the-cable trays is 8.93'1bs/ft2 of cable tray surface area.
The total surface area of cable trays in this area is 1,964 ft2, There are no combustible liquida in this area.
Enclosed combustibles.auch as cabling in conduit have not been considered in this analysia.
3.
VENTILATIgN_ PARAMETER @
There are 3 doors which enter this area.
999E_Numbgg
______gigg________
Locgtign 73 6"-4 1/2 x 3'-O" West wall 134 6'-4 1/2 x 3'-O" West wall 149 6'-4 1/2 x 3'-O" West wall 1
There is an opening on the east side of this area which measures 117'-O" wide by 18'-O 1/2".
In addition, there is a 6'-O" wide i
Eby 18'-O 1/2" opening in the north and south wall.
l 4.
CAggg_EXAMNED
.A spreading cable fire was assumed to originate in the area of heaviest cable concentration 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 ft.-per hour and instantaneously up any vertical trays encountered.
The fire will spread a distance of 15 feet in each direction along the cable trays before the original point
(-
source dies out after 89 minutes.
A maximum surface area of 184 ft2 of cable trays (see Attachment B for a list of trays)
.will be involved at any one time, which corresponds to a heat output'of 3,235 kW.
This heat output is assumed constent throughout the fire duration.
The actual heat output as the fire spreads-out of the area originally involved would'be less since the quantity of cabling involved at any one time would be less.
5.
RggULT@
The only case examined was that of a spreading cable fire occurring when one personnel door was open.
The fire duration was taken to be 180 minutes.
The maximum temperature reached was 717 OF, which is below the critical temperature for the 1
structural steel (see Attachment for results of analysis.)
Since L
the resulting fire was fuel controlled with one door open, it
~
will also be fuel controlled if any additional doors are open.
2
~ _
The positions of cable trays relative to structural steel members were examined throughout the area in order to anaeas the potential for localized heating.
Attachment D contains the results of calculations performed to determine the response of the affected structural members to localized heating.
These calculations are conservative because they assume that the entire length of the member la sub ected to the exposure temperature, J
whereas, in reality only a short section would be.
The duration of each cable tray fire is taken to be 90 minutes which is the time required for a, cable tray to burn to completion.
The cable tray exposures and beam responses are tabulated as follows:
Final Beam Caae Member Exposure
(
C 0
_Ngz_
_Irgg_
Iggez1 El Iggez_1 El 1
W16x36 15000F 1500 2
W12x27 15000F 1500 3
W1'2x27 13OOOF 1300 4
W16x36 13OOOF 1300 5
Same as Case 1 6
Same as Case 2 7
Same as Case 2 8
Same as Case 1 9
Same as Case 3 10 Same as Case 4 11 Same as Case 3 12 Same as Case 3
\\
3
1
.(
i 6.-
gggggIg_gg_IgaggIggI_ggggggIIgggg i
The worst case fire examined was fuel controlled with a duration of 180 minutes.
The maximum additional heat release rate due to transient materials in the area which will result in en area 0
temperature.less than 1100 F is listed below.
2 Eigg_Durgtign 946__1hWfm y ggggy 180 6.5 2,533 The distance between the floor and the deepeat beams supporting the ceiling in 16'-8 1/2".
The heat release rates required of floor level transient combustible fires to produce plume temperatures of 11000F, 13OOOF and 15000F at the bottom
-(
flange of the beam have been determined and tabulated below.
For 0
..the temperatures greater than 1100 F the time requirsd to heat the sizes;of the beams supporting the ceiling have also been determined.
Time =te_1199 F1migl II 1 IBW1 W12_E_2Z W19_E_2s W19_E_99 1100 7,257 1300 9,549 13 14 38 1500 12,042 9
10 26 4
c.
'k e
A C
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A U
U' i
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Unit 2,3 Turbin Building, Elevation 116'-0" Common Equipment Area
> Surface Area Calculation,
Walls 2
North wall (57' x 18')
l',026 ft South wall (57' x 18')
1,026 ft2 West wall (128' x 18')
2,304 ft i
2 4,356 ft 2
Ceiling (128' x 57') - (50' x 42')
5,196 ft 2
Total Surface Area for Heat Transfer 9,552 ft
'(-
ATTACHMENT A
SPREADING CABLE FIRE TRAYS
,y
(.
Tray Section
-Width Length
.. Surf. Area (Inches)
(Feet)
(Sq. Ft.)
2CH 010 12
?4 24 2RH 040 6
24 12 2CK 010 14 24 28 2CH 030 18 12 18 2CF 057 & 058~
30 6
15 2CJ 050~
13 24 26 2RF 050 18 24 36
'2CH 058 18 6
9 2CK-010
^
4 24 8
^
2CJ 050 4
24 8
o 184 sq. ft.
r -
k ATTACHMENT B
- u..SE NO. :
1.
BUILDING: PEACH BOTTOM TURBINE BUILDING ELEVATION AND AREA DESCRIPTION: 116' COMMON EQ. AREA (BENEATH SWGR. RM)
CASE DESCRIPTION: SPREADING CABLE FIRE
++o++++++++++++++++++++++++++++++++++++++4:*+++++++++4:*++++++++++++++++++++++++++
i CEILING / WALL CEILING / WALL Ao Ho Aw Q
THICKNESS.
MATERIAL
- (FT. )
SQ. FT.
FT.
SQ. FT.
KW
-++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++++
- 3. 0 CONCRETE 19.1
- 6. 4 9552 3235 FIRE IS FUEL CONTROLLED FIRE DURATION GAS TEMPERATURE (MIN.)
(DEG. F) 10 522 20 538 30 552 40 565 50 578 50 590
- (-
70
'601 80 613 90 624 100 535 110 545 120 G56 130 667 140 677 150 G87 150 E97 170 707 180 717
'(
ATTACHMENT C
l 9.
"f' 7E NO. :. :1 L_ALDING: PEACH BOTTOM TURBINL' C'JILDING
~ ELEVATION AND AREA DESCRIPTION: 11L' COMMON EQ. AREA (BENEATH SWGR. RM)
CASF DESCRIPTION:.W12X27 EFFECTS OF LOCAL HEATING ON STRUCTURAL STEEL FIRE TEMPERATURE.(DEG. F):
1300
. EIGHT OF STEEL' MEMBER (LBS./FT.):
27 W
SURFACE OF. STEEL MEMBER HEATED (SQ. FT./FT):
4.12
. TIME STEEL TEMPERATURE (MIN.)
(DEG. F) 5 811 10 1106 15 1223 20 1269 25 1288 30 1295 35 1298 40
,1299 445
'1300-50 1300 55 1300
-(
60 1300 65 1300 70 1300 75 1300
~
80 1300 85 1300 90 1300 f
e ATTACHMENT D v
e i
CASE NO.:
2.
BUILDING: PEACH BOTTOM TURBINE BUILDING ELEVATION AND AREA DESCRIPTION: 116' COMMON EG. AREA CASE DESCRIPTION: W12X27 EFFECTS OF LOCAL HEATING ON STRUCTURAL STEEL FIRE TEMPERATURE (DEG. F):
1500 WEIGHT OF STEEL MEMBER (LBS./FT.):
27 SURFACE OF STEEL MEMBER HEATED (SQ. FT./FT):
4.12 TIME STEEL TEMPERATURE (MIN.)
(DEG. F) 5 932 10 1275 15 1411 20 1465 25 1486 30 1494 35 1498 40 1499 I
45 1500 50 1500 55 1500 60 1500 65 1500 70 1500 75 1500 80 1500 85 1500 i
90 1500
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ATTACHf1ENT D L
J.
[
CASE NO.':
'3 BUILDING:- PEACH -BOTTOM TURBINE BUILDING ELEVATION AND AREA DESCRIPTION: 116' COMMON EQ. AREA CASE DESCRIPTION: W16X36 EFFECTS OF LOCAL HEATING ON STRUCTURAL STEEL FIRE TEMP'ERATURE (DEG. F):
1300 WEIGHT OF STEEL MEMBER (LBS./FT.):
36 SURFACE OF STEEL MEMBER HEATED (SQ. FT./FT):
4.28 TIME STEEL TEMPERATURE (MIN.)
(DEG. F) 5 647 10 954 15 1117 20 1203 25 1248 30 1273 35 1286 40 1292
(.
45 1296 50 1298
.55 1299 60 1299 65 1300 70 1300 75 1300 80 1300 85 1300 90 1300
's ATTACHMENT D L_
r t
ll r-I
-CASE NO.:
4 BUILDING: PEACH: BOTTOM TURBINE BUILDING
- ELEVATION AND AREA DESCRIPTION: 11G' COMMON EQ. AREA CASE DESCRIPTION: W16X3G EFFECTS OF LOCAL HEATING ON STRUCTURAL STEEL FIRE TEMPERATURE (DEG. F):
1500
' WEIGHT OF STEEL MEMBER (LBS./FT.):
3G SURFACE OF STEEL MEMBER HEATED (SQ. FT./FT):
4.28 TIME STEEL TEMPERATURE
-(MIN.)
(DEG. F) 5
-741 10 1098 15 1287 l
20 1387 25 1440 30-14G8 35 1483
-(-'
40 1491
- 45 1495 50 1497 55 1499 50 1499 65 1500 70 1500 75 1500 80 1500 85 1500 90 1500 1
ATTACHMENT D G