ML20215F200

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Vessel Test Instructions,Enrico Fermi Atomic Power Plant Unit 2
ML20215F200
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 02/16/1973
From:
CBI SERVICES, INC. (FORMERLY CHICAGO BRIDGE & IRON
To:
Shared Package
ML20215E634 List:
References
PROC-730216, NUDOCS 8706220278
Download: ML20215F200 (80)


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DESCRIPTION IDENTIFICATION c I^h$k] VESSEL CONTRACT INSTRUCTION VCI 5562 ,,

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VESSEL SOLUTION FILM TEST PROCEDURE VST 5562 '

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VESSEL LEAKAGE RATE VLT 5562 99)pff TEST PROCEDURE WMj4]l y r

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LEAKAGE RATE TEST EQUIPMENT EIP 5562 QiMils INSTALLATION PROCEDURE $ " ?' " l

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VCI 5562 . 1. M TITLE VESSEL CONTRACT INSTRUCTION FOR STRENGTH, NDh- . .5 h LEAK AND LEAKAGE RATE TESTING PAGE NO.1 OF l-PRODUCT NUCLEAR CONTAINMENT VESSEL REv.No. 1 9.. f[g@

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CORP REO REG i' o 08 MEM OEN INSP NU CONST MFG SY DATE .* 2 . ENGR ENOR WELD TEST QA QA QA $ g ' 5 w a GMT RLB CNS GM RS VMY PRERARE CHECKEo CRS 12/28/72 ( WWL 12/28/72 AHB

                                         "                                   AuTwomizEo     WWL      2 /16/.7.B i # ,;hph TYPEo         FC       12/2'8/72 f[4f          ,%7 1.0        SCOPE                                                                               . ,e This vessel contract instruction (VCI) outlines the test                        sequence:Md                :A' and specifies the contract requirements and the instrumentation for field testirg of the containment vessel for this contract, Mk It provides the chronological listing of all preparations, exam-aid                             $f,g${g inations, and tests necessary to perform the overload test as                                                  .

specified by the Code and the leak and/or leakage rate test (s) f;4 as specified by the contract specification. & n, ,,,d; t;,- 2.O REFERENCES _ g, l %g 2.1 Contract Specifications: 3071-9 o,, ;4y 2.2 ASME Boiler and Pressure Vessel Code, Section III, Subsec- ngg tion B, 1968 Edition, with Summer 1969 Addenda, j 2.3 Applicable CBI testing procedures attached and used to -"" perform the required tests: 2.3.1 Vessel Solution Film Test Procedure VST-69-5562 Vessel Overload Test Procedure VOT-695562 2.3.2

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2.3.3 Vessel Leakage Rate Test Procedure VLT-69-5562 a.;., g; r

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4DENTINCATION f;,g} ', VCI 5562 P- .z. - TITLE VESSEL CONTRACT INSTRUCTION FO9 STRENGTH myk LEAK AND LEAKAGE RATE TESTING PRO DUCT NUCLEAR CONTAINMENT VESSEL PAGE NO. REV.NO. 2 1 OF b '4 [. hh  ;. cusTOuE R THE DETROIT EDISON COMPANY ev CRS oATE 2/16/7:3: e p -[;;;g, a

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3.1 The Project Foreman, or his delegate shall be responsibl 7 ' '# for the test (s) performed under this procedure. ,y.7rgs

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3.2 The project welding and quality assurance supervisor, or hisM N delegate shall witness, evaluate, and assist in conducting ;3bsp4 j,g g the tests performed under this procedure.

                                                                                                                          ;I,$ 6-4.0       DESIGN AND TEST CONDITIONS                                                                        . igf         h 4, 1y c 4.1   Design Internal Pressure                                           56 psi           '      WOMj$;            d
                                                                                                                       .s QM 4.2   Overload Pressure                                                  70 psi
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                                                                                                                          ,w;.g 4.3   Leakage Rate Test Pressure                                         56psiNominal}.;*W                           f 4.4   Specified lowest service metal or                                                          .,,y.4 $

test temperature 30'F

                                                                                                                                   .4{K 4.5   Specified Allowable Leakaae Rate                                    0.2% per' day " %

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                                                                                                                                           .e 5.1   Vessel Overload Test and Solution Film Test                                                                   "S' Ufd 5.1.1      Two 6"F dial qaces graduated over a range                                                lw:1 r       -

of about 140 psi. ,3,77 5.1.2 One 12"5 recording cace craduated over a ~ yp~ rance of about 140 psi. g gy ' NOTE: All dial gages shall be calibrated acainst a ' b.*W

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standard dead-weight tester or a calibrated  ; master pace in accordance with the Construction , ;3;. Quality Assurance Program for Nuclear Vessels . . . N @ 1. and parts. w k 5.1.3 Detector Solution: ...

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                                                                                                                                                                                                                        ' O ls j tpi LEAK AND LEAKAGE RATE TESTING                                                                                                                     PAGE NO. 3                  OF PRODUCT NUCLEAR CONTAINMENT VESSEL                                                                                                                                 aEv. NO. g                               -:s a'*]}-f J cusTOuen THE DETROIT EDISON COMPANY                                                                                                                                av CR        DATE 2/16/73 $."

5 .1. '4 Valves, piping, hose in accordance with sketch N;41 rk on page 4 of VOT-69-5562. -g I t oeg 4 ( 5.2 Vessel Leakage Pate Test - . Te'm NOTE: All equipment calibration will be documented.

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i h s. perature Recorder, Dewpoint Recorder, Associated 'g Dewpoint Eculpment, Manometer, Pressure Gaae and Barometer will be mounted in a single enclosure. 1e Afgfg [j@p

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5.2.1 Temperature Measuring System - g 5.2.1.1 Esterline Angus Model All24F Multipoint s'tEikigMk l Temperature Recorder ggg l a) Dual Range, Automatic Switchina ogg Panoe A: 35-75' Dry Bulb ' ,1 < Range B: 70-110*F Dry Bulb @@j with 2 non-selective adjustable "?@ - alarms and one right hand event pen. ,; gy b) Dual Panae linear scale , J,gg ' 35-75 F on top and 70-llo'F on bottom. c) 200 division linear chart "N . l d) Accuracy of recorder is within 0.25% of ' :WJ4 'A j 40*F span (0.1"F) i Smallest chart division 0.2 P '

                                                                                                                                                                                                                                        ^k i Readability O.l'F                                                                                         i,y Q -

5.2.1.2 10 Platinum Pesistance Bulbs dW l Burns Engineering Model (Special) 0- l Accuracy of 0.075*F l 5.2.1.3 Extension cable for resistance bulbs * :,, ~ Three conductor, 18 ca. copper wire. g g; Complete Temperature Measuring System accuracy is . . , within 0.175'F. Xs M_

                                                                                                                                                                                                                                               ,. L 5.2.2     Dew Point Measuring System                                                                                                                                                         ,,

5.2.2.1 Esterline Angus Model fll24F Multi-Point Temperature Recorder Y. a) Range 0-10 DC millivolts linear from ,. Van-Air Dew Point Hygrometer Probes 'E-b) Scale 0-100'F Dew Point i

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IDE.NTIFICATION } ) ;.;f { VCI 5562

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                                                                                                              %               n T' T 'E    VESSEL CONTRACT INSTRUCTION FOR STRENGTH                                          4j                     1 9

LEAK, AND LEAKAGE RATE TESTING PAGE NO. 4 OF .$' Ih PaooucT NUCLEAR CONTAINMENT VESSEL R E v. No. 1 . ' ' :M M cusTouEn THE DETROIT EDISON COMPANY ev CRS OATc 2/16/71e64

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c) 200 division linear chart $i$f  ; I d) Accuracy of recorder within 0.25% of 100*F span (0.25'F) 4 ppg ' l Smallest chart division 0.5'F N 4dhc h. i l Readability 0.25 F. ,,., , 5.2.2.2 Vap-Air PN2684 0822 Model 84A MN Nd;4W Moisture Analyst housed in a JIC enclosure .Ehp Range 0-100'F Dew Point, Output of 0-10 DO l t' *g Millivolts. 'nhIjM ' Vap-Air PN 2694 0896 Automatic Probe NI$fi& 5.2.2.3 Selector Switch for either manual or +spgp .N ;l automatic monitoring.

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5.2.2.4 6 Vap-Air PN 2683 0791 Dew Point Sensors. W4NMs.

        -                                                                                                     WilgQ 5.2.2.5  Extension cable for Dew Point Sensors                              ,eg" Vap-Air EPN 2692 0897.
                                                                                                                 ,qip Complete Dew Point Measuring System                                    Y,,..

accuracy: If instrument is in +60 to +100'F .y ambient temperature rance accuracy is l'F. , If instrument cons down to -20'F or up to

                                            +140 ambient temperature accuracy is 2'F.                             ^$[   , , .

5.2.3 Reference System Equipment , p.,9 5.2.3.1 Wallace and Tiernan Model FA-139 Aneroid Barometer; Range 710 to 785 mm Hg; 0.2 mm Minimum Graduations; Sensitivity 0.02% of y,G8[ full scale (0.0150 mm Hg). Accuracy 0.3% of full scale (0.225 mm Hg). Readability

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0.1 mm Hg. ' 9 Yi iWs*%f a%rgr,,n'"X 5.2.3.2 Wallace and Tiernan Model 62A-2A-0100 j 8 1/2"5 pressure gauge Range 0-100 psig; ,uco t 0.1 psig Graduations; Reccatability 0.03% of aiJ l full scale (0.03 psig) ; Accuracy 0.066% of , . ,e , full scale readability 0.01 psic. Reproducible readability of .02 psig.

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IDENTIFICATION Y i e VCI 5562 k. .. 4 TiTec VESSEL CONTRACT INSTRUCTION FOR STRENGTH A I' LEAK AND LEAKAGE RATE TESTING pAot No. 5 or 9O  % PacoucT NUCLEAR CONTAINMENT VESSEL a cy, uo. 1 47 $$ cusTOuta THE DETROIT EDISON COMPANY ev CRS oATE 2/16/73 , 7 wV. - . M1 5.2.3.3 Meriam Model 207A10 FF 36" Tube Flush MountY Manometerwithprecisionboretubingand'fullh range vernier; scale graduated tenths; Readability 0.01" H20 ~nk@h in inc l 5.2.3.4 Five Nupro B-6BK-SW 3/8"F brass valves N th a replaceable bellows stem seal and KEL-F' d g seat assembly and socket weld connections.~ O D # u -V.cg: 5.2.3.5 2"F manometer reservoir and miscellaneous g;f[1 3/8"F copper tubing.  %

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k5.4 Three Red Spirit Filled Thermometers with Armored Enclosure' %M Range 4*F to 220'F '+%@$ Smallest Graduation 1*F . . n. .f gde g 5.5 4 fans with 3/4 HP motor capable of running under 60 psic .N (use #12 wire, 3 conductor, min. suggested length 100' each)'.S $ ' QAy 5.6 Valves, piping, hose in accordance with sketch on page 9 of w y' , this procedure. f

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5.7 Brooks Hi-Accuracy Full-view Potameter with calibrated M[1 accuracy of la of reading from 100% to 10% of full scale , Q' - and reproducibility of 1/4% of instantaneous readina. Scale ., length is 600 mm with maximum flow rate of 3.38 scfm at 14.7 '? psia and 70'F and with special calibration curve for 56 psig. 5.8 Hoke needle valve with micrometer vernier handle. 9p 6.0 CLEARANCE RULES AND PRFCAUTIONARY MEASURES FOR SAFETY OF $ M. PERSONNEL AND EOUIPMENT .y, ,, ,, % 6.1 All unauthorized persons and all moveable equipment subject 4g - to damage must maintain a minimum clearance in all directions ' f from the drywell of 600 feet while the pressure is being CN l ' increased above 5 psi and until the overload test has been y;g successfully completed.

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6.2 Persons authorized in writina by Chicaao Bridae & Iron Company and The Detroit Edison Company may be admitted with- , in the area defined in 6.1 above. Authorized employees of i

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CBI, Detroit Edison Co. and authorized inspection personnel . [ willbepermittedatthelocationsofthecontrollingvalvesK%.{j i

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IDENTIFICATION

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TITLE VESSEL CONTRACT INSTRUCTION FOR STRENGTH , J% . LEAK AND LEAKAGE PATE TESTING PAGE NO. b OF '9-44 $, PRODUCT NUCLEAR CONTAINMENT VESSEL REv.NO. 1 , g g j. I oAve 2/16/73 cusTouEn THE DETROIT EDISON COMPANY ev CRS l 4:& .Mg h'm 6.2 (Continued) ' 4?$l84%;

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GQW @ l and gages approximately 300 feet from the outside of the drywell.

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6.3 No one will be permitted within 300 feetofthevesselwhile'S} igg h 4 the pressure is being increased above 5 psi for the first 'NN' M M f,[ l

                                                                                                                                                                  'i tine or while the vessel pressure exceeds the design pressure.                                                                                                   M.kss$ l J.Q 6 j 6.4   If there is any urgent need that authorized employees of                                                   ggg;g j CBI Company inspect the vessel:                                                                                   .f..
                                                                                                                               +9ifig$l 6'.4.1    For vessel pressures below 56 psi reduce the pres-                                                       +M '

sure 1 psi bafore approaching the vessel. . g,;,, p , 6.4.2 For vessel pressures above 56 psi reduce the ylg~ ., pressure to 56 psi.

                                                                                                                                        %Asi 6.5   Enforcement of the above clearance requirements shall be a                                                           , U PM
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joint responsibility of The Detroit Edison Company and Chicaao Bridge & Iron Company. m:9h , 6.6 Safety requirements found in Sections 8.7 and 8.9 must be , i, observed during the solution film and leakage rate tests. ,y.gf 7.0 TEST AREAS m, m: . 7.1 Drywell V2C-

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7.1.1 ' Accessible circumferential and longitudinal welds.

                                                                                                                                                   .g 7,1.2    Welds in penetrations including test covers.
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7.3.3 Insert to shell welds. , . r.w r.v g %ry 7.1.4 Welde in vent line. *d4*M@l

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{ 7.1.5 Equipment door gaskets. s . 7,gg 7.1.6 Top flange gaskets. dhx

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7.1.7 Gaskets on penetration closures having a double gasket detail. . Wll$llr j & l

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evCRS 1 DATs 2/16/73 e , y! . ] 7.1.8 Personnel lock door gaskets (interior & exterior doors)0 p 19 , 7.1.9 Expansion joints on vent lines. < U}i;j . . ~

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7.2 Suppression Chamber $w.aq Mk j j

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NOTE: All welds on outside of torus, below water level,  ;.Qjal tci besuitablydriedasnecessaryforvisualinspection:,$g Q.1 of any water leakage.

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7.2.1 Accessiblecircumferentialandlongitudinalwelds.w.$pp.' 7.2.2 Welds in penetrations including test covers. oJQpgp MjlW$t 7.2.3 Insert to shell welds. 73 5 : gid,h$-) m '

                                                                                                                              >             E1 7.2.4     Gaskets on penetration closures having a double                                                 4 gasket detail.

l4QkQ 8.0 TEST SEOUENCE AND REQUIREMENTS 6

                                                                                                                                           ?Mh 8.1     Install the instrumentation and reference system and conduct
                                                                                                                                        @%o the initial testing of the reference system per procedure                                                 ' k,' %,

EIP-69-5562. O:kf

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NOTE: The instrumentation is listed in Paragraph 5.0. y; _ - Page 9 of this procedure shows the location of the ,.,_4 reference chambers and instrumentation. g, ', The drywell reference chamber represents 59% and the. w c torus reference chamber 41% of the total air volume C. ' of the containment vessel.

                                                                                                                                           ;p+-ya 8.2      Perform the closure gasket interspace test per procedure VST-69-5562.                ,

e' '.y@'y l, Test pressure = 56 ps.t. , , . . Test areas: 7.1.5, 7.1.6, 7.1.7, 7.2.4. ,,,P.

                                                                                                                                   . , ,S; p 8.3      Fill the suppression chamber with water per procedure VOT-69-5562 Paragraphs 2.2 and 2.2.1.
                                                                                                                                      " #.!Mmv.      en 8.4     Connect the air lines, gage lines, dial gages and recording # ^jk gage per procedure VOT-69-5562, Paragraph 2.1 and Paragraphs                                                    "^

2.3 through 2.6 and pressurizs the vessel to 5 psi. . ,... g..,ga, .j I

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IDENTWICATION ' C] * [' VCI-69-5562 ;o:s k: TITLc VESSEL CONTRACT INSTRUCTION FOR STRENGTH wgg  : LEAK AND LEAKAGE RATE TESTING paae so, 8 or TQ f PRODUCT NUCLEAR CONTAINMENT VESSEL m ev. no. 1 7,7 , M,Qp { cusvoura THE DETROIT EDISON COMPANY av CRS oATE '2/16/73%

                                                                                                                                                             ' w; 8.5      Perform the 5 psi solution film test of the containment," Q.                                                                            1 vessel per procedure VST-69-5562.                                                    Vessel pressure = 5 psi.E                 '

Test area: 7.1 and 7.2. _,,,

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8.6 Perform the vessel overload test per procedure VOT-69-5562 4 .. Paragraph 2.7 through Paragraph 4.2. l . , "P "'

                                                                                                                                                                  .s ( t -                       c 8.7      If the maximum temperature during the leakage rate test is Q, }(f).'                                                                    C expected to increase above the ambient temperature at the' %< W start of the test, reduce the pressure in the vessel to the MQjfjp                                                                                             

following calculated gauge pressure (PT) to avoid the possi ;jijg / bility of exceeding the specified leakage rate test pressure.u 4 m ,i%M.  : _ ,_ ._ d$l@ (460 + ambient temp. 'F at. "9f start of leakage rate test) _14,7;,g - 1 PT = 56 + 14.7 ,, (460 + maximum expected temp hhk

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8.8 With the vessel pressure at PT, of the vessel per procedure VST- conductasolutionfilmtesthw% 69-5562 Test Area:7.1 & 7.2 rpi" 8.9 Disconnect the air and gage lines and blank all valves ,Q , adjacent to the vessel. Test these valves for leakage with "v detector solution. @@

                                                                                                                                                                                 .sth 8.10 Perform the vessel leakage rate test per procedure VLT-69                                                                                       - u p '

5562. . Leakage, rate test pressure PT in Step 8.8. Lock cg g exterior door is to be open. 8.11 Remove all overload and leakage rate test equipment. DD, ' y.:syJQ ', w-

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eDENTWICAT60N VST 69-5562 4nyut;r. 3

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r . TiTt.E VESSEL SOLUTION FILM TEST PROCEDURE wicii ,,f PAGE NO. 1 OF 3 ~A&y y PRODUCT NUCLEAR CONTAINMENT VESSEL RE v. NO. 0 * $$pp[ , CUSTOMER THE DETROIT EDISON COMPANY ev CRS DATE 12/27/72Q j O 08 MEM GEN iNSP CORP NU REG CONST REG MFG Sy gAyg ' '*~ ,, h

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1.O SCOPE .,g,;.;; 'g ] This procedure applies to solution film testing of vessels and M N*l vessel components. t #! Iib $f , 2.0 TEST PROCEDURE

                                                                                                             'Mhkoh k, s fN7. ..e.fl 2.1    Remove weld slag, dirt and debris from areas to be leak                                )                b tested.                                                                                . d &; < 1 2.2    Pressurize the test areas to the required test pressure.
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                                                                                                                 , ' Ac ffy l 2.2.1  On double gasketed enclosures apply test pressure of E' N l 56 psi between the gaskets.                                                        MI!8 j rip \

2.2.2 Vessel Pressure = 5 psi for solution film test before si overload test. +Wi' 4;m 2.2.3 Vessel Pressure = P T (from VCI Step 8.10) after over- :r.. l load test. ggpl,,

                                                                                                                            ,~1 2.3    Apply a solution film in a continuous film free of bubbles to all test areas.                                                                         G?M.
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2.4 Evaluation of leaks: Ye d6 2.4.1 Any leak detected that does not affect the structural' 3'$ l

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ioeNTwlCATION ~f VST 5562 ,. ] TITLE VESSEL SOLUTION FILM TEST PROCEDURE . PAGE NO. 2 op u I enoouct NUCLEAR CONTAINMENT VESSEL REV,NO. 0 3'[' f3., V, custouca THE DETROIT EDISON COMPANY evCRS oAve 12/27/72 ,

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integrityofthevesselasagreedbetweenCBIandl.y l the customer, but which might prevent a successful.h. 3I Leakage Rate Test shall be temporarily sealed. . An 'M $l example is a leak in a temporary closure. 3 g , 2.4.2 Any leak detected that affects the structural gg,jpg ' ' ; integrity of the vessel shall be repaired. m i ' :.Jll 4 2.5 To make repairs to the vessel or personnel lock interior *"Y ,f ' bulkhead proceed as follows: nyN 2.5.1 Release the pressure to atmosphere by opening the' Y$hNv the pressure release valve. };)k{gg; 2.5.2 Immediately after the pressure has been released, 4.m*. i open a large enough connection to prevent the 87.:$$ j formation of a vacuum in the vessel. _;pgQ; ] p qqp ' 2.5.3 Before making weld repairs or doina any work that GT might cause a spark, check vapor space to "N,) make sure that it is free from any explosive M D@ fnixtu re . ' N :tflfGR 4.g% M . lJ 2.5.4 Weld repairs are to be made and recorded in accor- O dance with the Construction Quality Assurance "d W l Program. W , j 2.5.5 Retest repaired areas and previously untestedu:.area ,y 2.6 To make repairs to the ersonnel lock barrel or exterior '  ; bulkhead, proceed as fo lows: .:n l' 2.6.1 Close the lock inner equalizing valve and open the , outer equalizing valve to release the pressure from ,, the lock. .e  ; ;t";;g 2.6.2 Before making weld repairs or doing any work that :M @ might cause a spark, check vapor space to make m .y e .. sure that it is free from any explosive mixture. ' "y J

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                                                                                                            .            @ %,.,y 2.6.3   Weld repairs are to be made and recorded in accordance with the Construction Quality                           - pd'((

Assurance Program. . , 3

                                                                                                                 ,t.     ? v: r 4 l 2.6.4   Retest repaired areas and previously untested areas.
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IDENTIFICATION - t.fteNh4[p.

                                                                                                                                              + y d e, .-       k VST 5562
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                                                                                                                                 ,3pgpls$    >;bh tH TITLE           VESSEL SOLUTION FILM TEST PROCEDURE PAGE NO.          3          oP          3    A SMyMy                   -

PAO DUCT NUCLEAR CONTAINMENT VESSEL cusrousa THE DETROIT EDISON COMPANY n Ev. No. ey CRS 0 DATE

                                                                                                                              ' N, c y ~D.

fQ p 12/27/72i '* .,; b? g d 3.0 ACCEPTANCE CRITERIA hk$$hffh b.t! Ed'IQ' .Y/fjt 3.1 No detectable leakage as outlined in Step 2.4. ,

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4.O DOCUMENTATION 4T M?%i:f#n 4.1 The satisfactory completion of this test shall be recorded on the Shop or Field QA Check List in accordance with the *M/@ requirements of the applicable revision of the construction h!'3ME or Shop Quality Assurance Program.

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VESSEL OVERLOAD TEST PROCEDURE Jh' ' % }%[.' TITLE PAGE NO. 1 or $.  ! PRODUCT NUCLEAR CONTAINMENT VESSEL REV.NO. 0 4 m cusTOME R THE DETROIT EDISON COMPANY eY CRS DATE 12-27-72S  : y, -- c CORP REG REG a 7 m;  ; O OB MEM GEN INSP Nu CONST MFQ SY DATE M" W l W ENOR ENOR WELD TEST QA QA QA ' M'l., { GMT RLB CNS RS VMY CRS 12/27/7.2' fw GM AHB PREPAREo CHECKED WWL 12/27/72 /. l l CH AuTHO RizEo WWL 1/22/72 ' N;h'f$ " TYPED a.

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This procedure covers the Hydro-Pneumatic overload test of the' 9 'J9 l drywell and suppression chamber. , J$$dJj 2.O TEST PROCEDURE .N' AMkyiNN

                                                                                                                        * %. >;u*p/        ;                      l NOTE:        CBI TESTING PERSONNEL SHALL INSTALL TWO TEMPERATURE                                               '7SD l DEVICES TO MEASURE THE SHELL TEMPERATURE. SHOULD THE                                               - (R:, , )

VESSEL TEMPERATURE START TO DROP DURING THE TEST, o

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l BLOWDOWN SHOULD BE STARTED IN TIME TO REDUCE THE VESSEL ' - i PRESSURE TO 22 1/2 PSI BEFORE THE VESSEL TEMPERATURE hh[, l , DROPS BELOW 30* F. '~ ^ t J n.;1&p 2.1 Connect air and gage lines, with dial gages and recording ,q l gage, to the vessel as shown on sheet 5 , #f r" . :;r . NOTE: THE CONTROLLING VALVES FOR THE AIR SUPPLY AND ' THE GAGES ON THE GAGE LINE ARE TO BE LOCATED i AT A MINIMUM DISTANCE OF 300 FEET FROM THE OUT- .- SIDE OF THE DRYWELL (VALVES 2, 3, 4, 5, 6, 7, 8, & 9) I

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VOT-69-5562pg.g h c. dv q Tir te VESSEL OVERLOAD TEST PROCEDURE e ^fMINM i PAGE NO. 2 or 5 W ' ?f9D l pnoouct NUCLEAR CONTAINMENT VESSEL ReV,NO. 0

                                                                                                     ?MM custouen THE DETROIT EDISON COMPANY                     sv CRS     oAre       12-27-72 h d !
                                                                                           , :dk 2.2     Fill the suppression chamber with water to an elevation sim.

3 inches above the c'enterline [approximately 133,360 , L Ng%* " ! - cu-ft (997,000 gallons)]. WN$@. %M l 2.2.1 Inspect the exterior of the suppression chamber n ', :q" i "y 1 for any leakage or distortion from water loading...., @jh . ,. 1 2.3 Open shutoff valves 1, lA & 10; isolation valves 2,3 & 4: air supply valve 5, and valve 9 $..'l{ a,,y 2.4 Close blow-off valves 6 & 7; and valve 8 #!N Q l

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2.5 Close or blank all other connections in the drywell and - l Suppression Chamber. t

                                                                                                      -w;;e>;       *f . ;l 2.6    Close the inner and outer door and equalizing valves of the ,                                        .

J personnel lock. V W- ) m. NOTE: IMMEDIATELY AFTER CLOSING THE LAST OPENING IN THE

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DRYWELL AND SUPPRESSION CHAMBER START PUMPING AIR { TO AVOID THE POSSIBILITY OF A VACUUM OCCURING INSIDE ' THE VESSEL. o,;. y Maintain the mandatory CBI safety & clearance rules. "k 2.7 With valve 5 open, pressurize the vessel to 35 psi.  ! Then increase the vessel pressure in 7 psi increments e  ! until the required test pressure of 70 psi has been y;  ! reached. 4 NOTE: AT THE PRESSURE INCREMENTS AND AT HOURLY

                                                                                                                       ,y INTERVALS, THE PRESSURE READINGS OF THE                                                             ;

DIAL AND RECORDING GAGES SHALL BE RECORDED ON THE TEST DATA SHEET. INCREMENT HOLDING l mp,g{ Z TIME SHALL BE 10 MINUTES, OBSERVING THE I y;M MC VESSEL PRESSURE. ,

                                                                                                  ,,                -3 2.8  Close valve 5 and hold the 70 psi test pressure for                   -
                                                                                                    .WW$

20 minutes, adding or releasing air to compensate for ' temperature variations. Open valve 5 to increase pressure. "${. y j or open valve 7 to decrease pressure. g.

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2.9 Close valve 9 and open valve 8 to interconnect the locks  ! with the drywell.  ; j r., i f L'/

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                                                                                                                                              'T IDENTWCATION 4 - < Q.[ f' A
                                                                                                                 ,                               i VOT .69-55_6 h                           [

J W T TLE VESSEL OVERLOAD TEST PROCEDURE '

                                                                                                                  ,e %. +nw l' 0" PAGE NO. 3        or       *5L       7.                "

PRODUCT NUCLEAR CONTAINMENT VESSEL n ev. no. O dd %t cusTOuen THE DETROIT EDISON COMPANY ev CRS DATs 12-27-72] ,(

                                                                                                                   . ,a $                     i 2.10     Hold the 70 psi test pressure for another 40 minutes, -lthAf                                                      s-adding or releasing air to compensate for temperature.

variations, such that the 70 psi overload pressure is ' h " f;gb M3 . maintained for a total of not more than one hour. Open valve 5 to increase pressure or open valve 7 to fgfgg' decrease pressure. . $;y. .pI ..y 2.11 Open blowoff valve 7 and reduce the pressure in the gp Jf g vessel and airlock to the design pressure of '.i6 psi and. , yg hold for sufficient time to permit inspection of the f .I,, airlockexteriorbulkheadanddoorforvisiblepermanent"Th& distortion. If any defects are detected, release pressure @ j@) make the necessary corrections, and retest. gg. w'AWW 2.11.1 Weld repairs are to be made and recorded in accordance with the Construction Quality

                                                                                                                                'm M@

Assurance Program. ' $1@ 2.12 Close valve 8 and open valve 9 or the lock exterior q >ag \ dQ. i equalizing valve. Reduce the pressure in the lock to ' f 7j atmospheric. Inspect the vessel and airlock interior 'O' bulkhead and door for visible permanent distortion. -pg;;. If any defects are detected, release pressure, make the

  • 4Q (; g necessary corrections, and retest.

2.12.1 Weld repairs are to be made and recorded in 'N a' ) accordance with the Construction Quality >4h

                                                                                                                               . 8 k, Assurance Program.

3.0 ACCEPTANCE CRITERIA 'b

                                                                                                                            > g egv 3.1     No visible, permanent distortion of the vessel as                                                   ;          f judged by the personnel under 4.1.                                                         ,M[Y$

4.0 DOCUMENTATION . T. .jv .@j j e; 4y; 4.1 Mark the following data on the face of the recording chart: 5'*Je!" Design Pressure 56 psi ~1 Ohh Specified Test Pressure 70 psi ., Contract Number 69-5562 ^ , M' ; _ Test Procedure Number VOT-69-5562 Rev. I Date of Test: q).'j[i,7 l l o \ The CB&I Project Foreman, the CB&I Welding and Quality I Assurance Supervisor, the Authorized Inspector and ,.

                                                                                                                                           +

Customer's Inspector with their respective signatures. l

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t ' .. N-4 [ $ IDENTIFICATION VLT 69-5$62 4f;.s lNd' 34 Q{

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TittE VESSEL LEAKAGE RATE TEST PROCEDURE ' i$$i . i NUCLEAR CONTAINMENT VESSEL PAGE NO. 1 OF

                                                                                                                        .*       bW f ,g                      h PAODUCT                                                              n Ev, No. 1                        , g4g Cus10 men THE DETROIT EDISON COMPANY                                 Sv CRS        oATE       2/16/73.. W O ,

aff < ' CORP REG REG >*' .p t ' O 08 MEM QEN iNSP NU CONST MFG SV DATE f.; 44s ' W ENGR ENGA WELO TEST QA QA QA

                )                                                                                                                             .Qi .., ,y,y j'y(

y GMT RLB CNS RS VMY PREPARED CRS 12/27/72 6 w

                "                          GM         AHB                          CHECKED        NWL          12/27/72                                 ~c CH                                      AursonizEo WWL TYPED 2/16/73                   [i:hp l FC            12/27/72,
                                                                                                                                      'q.g,yy 1 1.O      SCOPE                                                                                                       " *MU I
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Thisproceduredetailstherequirementsoftheleakageratetests,.pN).s noted in VCI-69-5562. ,

                                                                                                                           ; :%:A d'ppe; '

2.0 TEST PROCEDURE ' %d;7  ; NOTE: DURING THE LEAKAGE RATE TEST OF THE VESSEL, ONLY AUTHO-RIZED PERSONNEL SHALL BE ALLOWED ON OR ADJACENT TO THE . .;f[ VESSEL AND INSTRUMENTS. NO WORK SHALL BE PERFORMED WITHIN. ' 25 FEET OF INSTRUMENTS , VALVES OR THE OUTSIDE OF THE VESSEL.M ; ud CBI TESTING PERSONNEL SHALL INSTALL TWO TEMPERATURE # 2 ~l DEVICES TO MEASURE THE SHELL TEMPERATURE. l

&g ,

SHOULD THE VESSEL TEMPERATURE START TO DROP DURING THE 'E TEST, BLOWDOWN SHOULD BE STARTED IN TIME TO REDUCE THE y.

                                                                                                                                               ' ~'

VESSEL PRESSURE TO 22 1/2 PSIG BEFORE THE VESSEL , TEMPERATURE DROPS BELOW 30 F. IF THE VESSEL PRESSURE EXCEEDS 56 PSIG DURING THE PEAK PRESSURE TEST, THE ' C' EXCESS PRESSURE ABOVE 56 PSIG MUST BE BLOWN OFF AND THE . LEAKAGE TEST RERUN. ,,,,,, , 2.1 Open valve B to equalize the pressure in the vessel and ,. reference system. . . ,r , s . - l 'yn

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{ ..g%,iy, .; O< l , iceNTwlCATION VLT 69-5562 kg

                                                                                                                . .:1[j            'w l 2
           ""        VESSEL LEAKAGE RATE TEST PROCEDURE                                                               Y                I PAGE NO. 2          OF      6*. $                             $

PRODUCT NUCLEAR CONTAINMENT VESSEL n ev. NO. 1 a s'+ 1 cusvourn THE DETROIT EDISON COMPANY av CRS DATc 2/16/73b Y

                                                                                                              ,h                               '

2.2 Open fluid reservoir valves D and E in secuence to allow. m~ "6 the fluid to flow into the manometer to approximately mid

  • height. Close valves E and D in that order. ,J rh:; t Unity oil D-2969 or equal. (Specific Gravity = 1.0)Use . Meriam' g p

2.3 Releaseairfromthevesselbyopeninoavesselvalveuntil@f$$ about 6" differential water pressure is indicated on the g,phQ manometer. Close the valve and leak test it with solution "9QQy,g. s film. Repair if required. g;g 2.4 Start the fans in the vessel. N 2.5 After vessel conditions have been allowed to stabilize a M@N .gg$$#- minimum of 4 hours, record the following data at hourly ,'.4 intervals: Mhl

                                                                                                                      ~a m 4,@

(A) Instrument enclosure temperature t e (Dec F) (B) Barometric Pressure (mm Hg) g" ^.,g , ~ (C) Vessel Gage Pressure (psi) (D) Individual Resistance Bulb Readings, B. (Dec F)

                                                                                                                 ' d - dd bh (E)    Individual Dewpoint Sensor Readings, D. (Deg F)

(F) Ambient Temperature at Top of Vessel (Deg F) ,p' ay (G) The Pressure Differential Between the Vessel and the ' g Reference System as indicated by the Panel Manometer, AP (in. H 20*) A[ "

  • Readings will be to the nearest hundredth of an inch . ,

on both columns of manometer.  %:

                                                                                                                       ~,

2.6 Calculate the following on an hourly basis: %M s (A) Corrected Barometric Pressure (mm Hg) " N. - Corrected Barometric Pressure = Barometric Pressure s* Pap "

                                                                         - ( . 0 0 4) (te-75)
                                                                                                                 ^ %.%

(B) Vessel Absolute Pressure (psia) ,, .p;97 P= Vessel Gage Pressure + Corrected Barometric ' N ?*I Pressure (.019 33677) NM ,. l k(C) Weighted Average Internal Air Temperature (*R) ,4:- 14e , T= .37 (B1 + B 2 8-B3) + .46 (BA + B5 + D6 + B7 + Df') +

    -                                  3                          5                                                 .> ' i .pf.'      ,
                                      *17 (B9 + B10)                                                                                -

2 WF

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                                                                                                                .#G1 w                                                           IDENTIF8 CATION VLT                   69 5563                        1 "x a 4

4: 1

                                                                                                                   %*NH T' T 'E        VESSEL LEAKAGE RATE TEST PROCEDURE                                                         .v             P              w' PAGE NO. 3                    or 6 ' $. M. -'?

paoover NUCLEAR CONTAINMENT VESSEL cusTouen THE DETROIT EDISON COMPANY n ev, No. 1 ev CRS oats 2/16/73% f 2$ , . , a M.Fh h:- h(D) Weighted Average Internal Dewpoint Temperature ('F)[kk ,

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DPT = .37 (D1 + D2) + .63 2 4 ( D3 + D4 + D5 + D6)dN l: l (E) The partial pressure of water vapor, PV, in psi the bhk M/ .; average to make this dewpoint temperature, use standard steam tables conversion. t et$ [d[Mr s/Ndis , (F) The hourly percent leakage rates corrected for the .)A,g': change of containment water vapor pressure. Positive l.jf ' values indicate containment in leakage, and negative'm E values indicate containment out leakage. ..a Q$@r

                                                                                                                              .Q;&#kRh Percentage                           -

Leakage =L= 100 AP 1 +pyy - jT Rate /Hr P1 - Py1 . (27.7 '!Mkpgj? .

                                                                                                                         %       .QQ,ib (27.7 2   + pv2 T2-
                                                                                                                                'NN
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P1, Pvi, API, T1: Initial variables (immediately 4lf,. N( j preceeding current data) yr A.ev ; AP2, Pv2, T2  : Current variables y 3 (G) The cumulative leakage rate : EL [iYI'. 4 ,v 2.7 Perform a linear regression analysis and deviation analysis , y

                                                                                                                                        ~~

for the least mean square calculation using the point l slope equation of a straight line where: ~#' "4'l y = mx + b 15M , <

                                                                                                                        " # S S N.. ,             '

Where y = EL = Cumulative percentage leakaae rate x = Elapsed time in hours from first test "Wl % measurement after stabilization , g';. , e !

                                                                                                                                      ~           '

N = Number of data points 1 m = Slope z..gg7'M

                                                                                                                                   '"          3 l b=

Sm =Variance y interceptof slope 7. y

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                 'E VESSEL LEAKAGE RATE TEST PROCEDURE M>
                                                                  .                      PAGE NO. 4        OF     b ' -rddkh' PRO DUCT         NUCLEAR CONTAINMENT VESSEL                             REV.NO. 1                      'f,g cusTOME a THE DETROIT EDISON COMPANY                                    av CRS     DATE  2 /16 /73 ' N* fc? h, .e
                                           .                                                                                 . mh m:,:$ y         "

m = NExy - ExIy g { I NEx2 - (Ex)2 .gcg ,, b = EyIx2 - ExExy N5Nbf j NEx2 - (Ex) 2 , p JdpyQ j

                                                                                      ~
                                                                                                                             ' i.yj[ I S m=      1  ~ NEy2- (Ey ) - m2 2
                                                                                                                                   #f N-2  .NEx2 - (Ex)2           _

Mg s <- @tg 2.8 After a minimum test period of 24 hours calculate the 24 , syj4$ l hour containment vessel leakage rate and submit it to the 4E customer representative at the site. The test shall be I' NY l concluded unless CBI is notified that additional testing #$I@ is required. In the latter case, the additional testing ,1 shall be the subject of mutual agreement between CBI and Mdt the customer representative. h, 2 y Lm = 24 x m t0.95 X S m sp[p

                                                                                                                                       - , . - .).
7. m -

L,n : Calculated 24 hour leakage rate ' v.; '

                                                                                                                                               'b m : as in Step 2.7
                                                                                                                                      .'. S Sm : as in Step 2.7 A ,.

to.95 : 95% confidence factor for N degrees of , freedom . 2.9 Install a flowmeter into a blowdown line and establich a . . . .. leakage rate (scfm) equivalent to 75% of the specified

  • allowable leakage rate per 24 hours using a free vessel N.6V L volume of 346000 cu. ft. . . ..

P .. L;6 M4. Lo (scfm) = 346000 x 24.75 L x P x Tsta 4;,$7 x 60 Pst.d T Lo (scfm)  : Vessel leakage in scfm equivalent to 75% of the specified allowable leakaoe rate per .Qfa 24 hours e,:

          --                                        P : Pressure at start of verification test (psi)

T : Temperature at start of verification test ( ' R)

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                 " 'E            VESSEL LEAKAGE RATE TEST PROCEDURE                                                     ' Wid                                   5 oF 6"MN, 5                                                                 #-

PAGE NO. PRO DUCT NUCLEAR CONTAINMENT VESSEL n ev. NO. 1 . . f>ghi;M i " ' cusrouca THE DETROIT EDISON C_OMPANY av CRS Dart 2/16/73 f Tstd : Standard temperature (

  • R) Q;i Pstd : Standard pressyre (
  • R) M W!

L : Specified allowable leakage rate , ,,,jg 2.10Continuesteps2.5through2.7andrecordtheflowmeter@ reading hourly. h-

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2.11 After a period of 10 to 12 hours calculate the average 24 M $ hour leakage rate, Lo through the flowmeter using the WM , 5 readings of flowmeter as a function of time. .a r:gg/gu

                                                                                                                                ,.. w,p g 2.12 Calculate the percent error between the calculated and the'y,P .!

actual flowrates during the verification test. -Q@# r %f  ?

                                            % Error = (Lc - Lo) - Lm                                                             ,
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                                                                                                                                 . d%A$c L c : Calculated 24 hour composite leakage rate                                         N@

duri~ng verification test $ pg;'. I w$, L o : Percent leakaae rate per 24 hours imposed on vessel per flowmeter readings yjg'el Lm : Measured 24 hour leakage rate during vessel { test (without variance) from Step 2,8 J.h .%

                                                                                                                                                                  ]
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2.13 Open a vessel valve to release pressure from the vessel '"*1Y until atmospheric pressure is reached. 2.14 Open a large enough connection in the vessel to prevent 'pi N4@$ jj the formation of a vacuum. w,;w \ 2.15 Remove all leakage rate test eauipment. l y.g "' j l 3.0 ACCEPTANCE CRITERIA 4QW 3.1 The calculated 24 hour leakage rate shall demonstrate a ,

                                                                                                                                         ,A. D. , r , .

95% confidence that the calculated leakage is less than' 75% on the maximum allowable containment leakage rate. io ,, ': r ' a" +" , '4U .' 'i 3.2 The calculated 24 hour leakage rates for the vessel test and the supplemental verification test shall demonstrate, " an agreement within i 25%. - .;qP7 ..,7 qpl .. t 1

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                                                                                                             .65s       ;AM                                              4, IDENTIFICATION                                                               g VLT 5562                 ,, ,(@7 Q ;.~                                       E! fi TITLE         VESSEL LEAKAGE RATE TEST PROCEDURE                                                     -                                                   5 PAGE NO. 6               OF 6             'd",4$idt d4t enooucT NUCLEAR CONTAINMENT VESSEL                       nev. NO, 1                                                                                    p cusTowEn THE DETROIT EDISON COMPANY                      av CRS       DATE        2/16/73"4t?/y;.
                                                                                                                       *9,4fTft/4 4.0        DOCUMENTATION                                                                      E' RhtN,9fAj   W
                                                                                                                                          $$m.ti
  • 4.1 A Leakage Rate Test Report containing actual data, rate calculations and conclusions will be prepared. leakage.a 3'.,'pg's p
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IDENTIFICATION 4 ,.

                                                                                                                              ~ a 4**                  '.i EIP 5562' % 4. /

TITLE LEAKAGE RATE TEST EQUIPMENT INSTALLATION  %,d PROCEDURE PAGE NO. ,1 OF f [j J . paoouCT NUCLEAR CONTAINMENT VESSEL aEv. No. 1 ..,. 2 /16/73 ~ 5;-

                                                                                                                               , C ,q               gn CUsTouE R THE DETROIT EDISON COMPANY                                    ev CRS         DATE                                                      g t
                           *'"      "   "'            '                                                                ^
  • l ENn EN0n w 'to T E s"T ' QA QA {

y GMT RLB CNS RS VMY PREPARED CRS 12/27/72 y'$ g GM AHB CHECKED WWL 12/27/72 A - y CH AUTHORIZED WWL 1/22/73,n 'j 1, TvPED FC 12/27/72' N %, s >4. h

                                                                                                                                    'G                     lV 1.0       SCOPE                                                                                                            .g                  ' '

This procedure applies to the installation of equipment for the . performance of the vessel leakage rate test by the reference .:.fjf$ system method. .OrfQg 2.0 INSTALLATION PROCEDURE b

                                                                                                                                 " >@??),i!

2.1 Test each reference chamber in the shop prior to shipment. sS Test by pressurizing with an air refrigerant mixture to e ' 4d about 70 psi and sniffer test all joints with a halogen leakq - ._ detector or test by evacuating and helium probe all joints

  • with a helium mass spectrometer connected to the system. jy
                                                                                                                                           ,,Ag3 2.2    If any leaks are detected, release the pressure, repair, and                                                           ;,7 retest until no leaks are indicated with the leak detector.                                                      . LP The leak detector shall be capable of detecting leaks in                                                   av the reference chambers of 5 x 10-6 std cc/sec or larger.
  • t'-

y 2.3 Assemble the reference chamber (s) and connecting tubing at . r ,,, the construction site. Do not connect tubing to the n!, reference system panel.  ;.

                                                                                                                                              ,s;;

NOTE: THE EXTERIOR INSTRUMENTS FOR THE LEAKAGE RATE TEST SHOULD BE ag LOCATED AS NEAR AS PRACTICABLE TO THE NOZZLES WHERE THE . TUBING CONNECTS TO THE VESSEL. EXTERIOR TUBING SHOULD BE. 9jf;g MINIMIZED. BOTH TUBING AND INSTRUMENTS SHOULD BE PROTECTED i , , . q'hy.

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                                       ,                                                                                                                     *: kf                     j tDENTIF4 CATION                                      Y EIP 5562                      emf.~ $,

t Titte LEAKAGE RATE TEST EQUIPMENT INSTALLATION o* ." PROCEDURE ,,oe no, 2 op 4 'MEd <W paoover NUCLEAR CONTAINMENT VESSEL nev, no. 1 '% i, { cusrouca THE DETROIT EDISON COMPANY sv CRS o^te 2/16/73 N _ y gj  % l FROM THE WEATHER. INTERIOR TUBING SHOULD BE KEPT AT LEASTjg i 12 INCHES FROM STEEL EXCEPT FOR THE PENETRATIONS. INSTALL'.c d .( TEMPERATURE MEASURING EQUIPMENT FOR TEMPERATURE READINGS

  • M ~ ' ?1 DURING STEPS 2.7 AND 2.8. CONNECTIONS SHOULD BE MADE g  ;

THROUGH THE TEMPORARY TEST CAPS OF "NON-SPARE" PENETRATIONS. + x I THE LOCATION OF THE INSTRUMENTATION AND THE PENETRATIONS TO) BE USED ARE TO BE DETERMINED BY CBI. APPROVAL OF THE PENE- f hq. l TRATIONS AND LOCATION OF THE INSTRUMENTATION SHALL BE ,_O h.' OBTAINED FROM THE ENGINEER. 4A&[r' 2 .4 Pressurize the reference chamber system with nitrogen gas @D k to about 70 psi through the valve A-2 at the vessel pene g g g tration. ., 2.5 Leak test tubing and chamber joint connections with a 'YSM" solution film. Repair and retest and repeat as necessary ygg until no leakage is detectable. Yhijp 2.6 Vent the reference system. N 49e 1 2.7 Connect temperature sensor devices through the vessel wall MR to the temperature measuring instrument, calibrate and gg install in the locations required. , w y. wp l 2.8 Connect dewpoint sensors through the vessel wall to the dew ' M -  ! point measuring instrument, calibrate above an ice bath and ye install in the locations required. , j Mp

                                                                                                                                                                         +Ghy
                                                                                                                                                                           ' ~

2.9 Install reference system in final position. Connect the reference system at the vessel penetration valve A-2 to a Go vacuum pump and gage. Evacuate the reference system so , s ,# that after isolating the vacuum pump and allowing time.for WP{ pressure equalization, the system pressure will be 200 . 7gg. f jj microns Hg or less, ^ WS k 2.10 Conduct an absolute pressure test of the evacuated portion k3 *gt of the reference system for a minimum period of 24 hours, t recording data periodically. Plot absolute pressure and- 9/ temperature versus time in order to determine for similar temperature periods the rate of pressure rise caused by- =

  • t;Mr@,, ' ~" 'i both out-gassing and in-leakage. ,

A%:/ _,_ Temperature of = .37 (B1 + B2 + BM t .4 6 (B5) + .17 (B9) Reference System 3 q.g.gy--

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   ' Y Gol60 A REV 442                                  ,
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l IDENTIFICATeoN 'M i *

                                                                                                                                     ,<6' ~

EIP 5562 wd 4 ( Ym.z LEAKAGE RATE TEST EQUIPMENT INSTALLATION - h PROCEDURE PAGE NO. 3 or 4 , };;gfjij' p enoouct NUCLEAR CONTAINMENT VESSEL REV.NO. -l y,g cusrowenTHE DETROIT EDISON COMPANY ev CRS oAva 2/16/73"  :

                  )2.11Asdeterminedin2.10therateofpressurerisecausedby *m both out-gassing and in-leakage only shall not exceed 400 %                                                           ,

microns Hg per 24 hours. If the system exceeds this allow-; 'L able retest the reference system with a solution film. - - 4 h.$ w:" , 2.12theData from reference 2.10 system panelandshall2.11be submitted and the to theabsolute  ?- M pr customer for review and approval. If it is mutually agreed 7 fp{ by the customer and CBI that leakage indicated is within the. allowable for the reference system, the absolute pressure g test of the reference system may be concluded and the system 4 j 4 f. shall be vented to atmospheric pressure with nitrogen. 4pg# NN 1 2.13 Connect the tubing from the reference system to the reference - system panel as shown on Page 4. Do not admit fluid to the .ddF  ! differential manometer until after the pressure is equalized 3F # between the reference system and the vessel. (See VLT - 1 69-5562). d,,.gpg g$ 2.14 Open valves "A" and "C" and close valves "B", "D" and "E").inighgb the reference system panel. 3 . 95.4;R.. .! j, W/ckc$ ,i 2.15 Pressurize the reference panel and reference system with nitrogen gas to about 70 psi through valve "C". Close valvej y g I "C". s j 2.16 Leak test the tubing connection to the reference system panel' with a solution film. Repair and retest and repeat as "M" necessary until no leakage is detectable in this connection. M

                                                                                                                             #mWp 2.17 Remove the nitrogen supply line.                                                                      -4 g 2.18 Install f ans in the vessel, ggI k 3.0     TEMPORARY VACUUM TEST EQUIPMENT                                                                         gg 3.1    Welch Duo-Seal Mechanical Vacuum Pump.                                                      >$i tdh!

3.2 CVC Pirani Vacuum Gage. ghg ' Range: 0-50 microns Hg g.y3pv 0-2000 microns Hg y g., 1.J ', {$@b 4 k 4.0 DOCUMENTATION 4.1 The data recorded during the vacuum testing of the reference, ,

     -                      system along with the Pressure and Temperature Plots and                                            'C W
     --                     Pressure Rise Calculations will be included in the Leakage Rate Test Report.                                                                                         7
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DOCUMENT CONTF%. upper BEAM SEAT ANALYSIS TN V-kBAoof MAY161974 TABLE OF CONTENTS

                                                                    &          SIM c

[M un he bec se g SHEET REVISION DESCRIPTION BM-1 0 Method and Summary BM-2 0 Loading Conditions BM-3 0 Input-Load Condition A-0BEQ BM-4 0 " BM-5 0 Output Load Condition A-0BEQ BM-6 0 " BM-7 0 " j BM-8 0 Input Load Condition B-DBEQ BM-9 0 " ) BM-10 l 0 Output Load Condition B-DBEQ i BM-11 0 " BM-12 0 " BM-13 l 0 Input Load Condition 0-0BEQ J BM-14 0 " BM-15 0 Output Load Condition D-0EEQ {' BM-16 0 " BM-17 0 " BM-18 0 Load Condition E & F - Introduction BM-19 0 " BM-20 0 " BM-21 0 " BM-22 0 Load Condition E-DBEQ BM-23 0 " BM-24 0 " BM-25 0 " BM-26 0 " BM-27 0 Load Condition F-0BEQ BM-28 0 BM-29 0 " BM-30 0 " BM-31 0

                                    = = = =                   3 i~ o TDOA T R                    "

15CERVE im lA 5542 4 JVL 81974 l The Ralph M. Parsons Co. a #, . SUBJECT MADE BY CHKD BY sy C AR D-ase No. l Upper Beam Seats LDF g 69 , Table of Contents 5 SY'74 Det. sHT M-Og , 00 64 REV 4 73 I

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l- - 10448-083 - Lambo Birmingham Design UPPER BEAM SEATS The upper beam seats and ring girder are analyzed for the permanent loads and loading combinations per Sargent and Lundy's 1.oading combination on sheet BM-2 of this report. _ The analysis is performed assuming all beam seats and the ring girder are reduced in section properties per previous analysis performed by CBI and approved per Detroit Edison letter EF2-22,054, dated December 7, 1973. , l For the loading condition A & B a live load of 42.5 kip is included. This is applied at the maximum loaded beam seat. This load will occur only during refueling. Loading conditions C thru F include a rupture load. There-fore, the 42.5 kip live load could not occur during these conditions. Loading condition B, with the 42.5 kip live load included, resulted in a worse loading condition than loading con-

  .                dition C. Therefore, this condition was not investigated.

Loading condition E and F require a rupture force acting upward, the CBI computer program used for the previous analy-sis was not designed to handle an upward force on the beam seat and ring girder. See sheets BM-18 thru BM-31 for these conditions. The analyses were performed with both seismic conditions (OBEQ and DBEQ). The beam seats and ring girder were found to be adequate to ca.rry all loads. Buckling allowables of the shell for DBEQ loading is not de-fined in the code. A factor of safety against buckling = 1.5 is used. SUBJECT MAoE BY CHKD BY gy CHARoE feo. Upper Beam Seats LDF c fl5 g c,,, so-sss2 E-714 [ 0 ~19 o.t. swt BM-lo_ , GO 6 4 REV 4.13 ,,__, ,,,

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INPUT F f' R UPPFR 9 E A r4 SFAT-ANAtYSIS: L cA o I N 6, C eMO[T teu A -

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i. ELEVATIONS OF 1 F )U AT OR = 507.0000 FT. TOD OF STEEL (TOP OF GlPDER)= 607.0000 FT. 408.00 RADIUS Of SPHERE IN. SHELL THICKNFSS 0.R750 IN. MODULUS OF FLASTICITY 27400000. PSI , FACTOP GF SAFETY (BUCKLINGl  ?. 0 ALLOWABLE TENSILE STRESS 17500. PSI VER TIC AL SCISMIC FACTOR .100 AISC BFNDING ALLOWABLE 20280. PSI .,,, LOA 05 i GIVEN DEAD ANO EARTHQUAKE LOA 05 ON THE BEAMS NO AZIMUTH LOAD' FO LOAD (DEG.) (LBS) (LBS) 1 172.60 34000. 3400. - 2 147.40 31000. 3103. 3 171 00 23000. 2300. 4 189.00 23000. '2300. 5 212 60 27000. 2700. 6 237.40 28000. 2800. A GIVFN LIVE LOAD OF 4(p00. L BS AC T I Nr. AT 122.60 DEGREES i a CHIC AGO BR 10GE AND IP3N CO. BIRMINGHAM ENG 64-55620; OATE 04-09-74; BY t 0F ; SHTSH.3REV o UPDER OFAM SFAT$: CrNTRACT 5 10 W C9 5 m 4 e e

~~ l0948-086 . IN9t1T CONT I NIIF O L c AD C ONU IT ON N - OSE $ STRE SSF S DUF TO LOADS AROVE BEAM SEATS (SEE SECT 104 1C) l MAX. TENS. CIRCllMF. STRESS RESULTi, 12310. LB/tN j max. COMP. C I R CtlM F. STRESS PESULT. -800. LB/IN MAXIMJM COMPRERRIVF MERIDIONAL STRESS -2450. PSI _

  ~~

WinTH [1F GIROEu 12.00 IN ~ i BEAM SEAL' DIMENSIONS IN INCHES l 81 = l14.0000 D1 = 1.0000 i

             ?~~

H2 = 1.2000 l D2 = 6.0000

         *                                                                                         '~        ~

RING GIROFP OIMFNSIONS IN INCHES l 1

                                                                                                      ~

DH = 10.0000 i TH e 1.0000 BV = 10.0000 l TV = 1.5000 ,__ l

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                                        . . . .                                                      =

1 l CHICAGO BRIOSF AND IDON CO. BIRMINGHAM ENG UPPER BEAM SEAT 5; CONTRACT 69-55e20; DATE 04-09-748 BY LDF; SHT BM-4 RE V O G - O . "l* CM e > QM -

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f0948-087 OUTPUT FOR UPP ER 3EAM SFAT ANALYSIS LCAO (. O M O \ T I O N A - O P2 G G ANGLF THFTA = 17.25163 DEG CC'MD ONE NT S OF BEAM L7 ADS ACTING ON SHELL AND RING GIRDER NG 6 Z l Milt H VERT LOAD SHFLL COMP RING COMP (DEG) (L6S) (LBS) (LBS) 1 122.60 37400. 39162. 11614. 2 147.40 34100. 35706. 10589. 3 171.00 25300. 26492. 7857. 4 189.00 25300. 26492. 7857. 5 212.60 29700. 31099. 9223. 6 237.43 30000. 32251. 9565. PRODERTilS OF RING GIRDER WIDTH OF SHELL ACTING WITH GIRDER = 29.5 IN AREA 0F SHELL ACTING WITH GIRDER = 25.8 IN-2 AR E A OF THE ATTACHED GIPDER = ?5.0 IN-2 TOTAL ARFA OF RING GIROFR = 50.79 IN-2 M7MhNT OF INFRTIA ABOUT Y AXIS = 1170.17 IN-4 SECTION MODULUS OF INSIDE = 179.86 IN-3

                                                 =   148.79       IN-3                                                  i SECTidN MUUULUS OF QUISIDE i

I I i l l i l l 1 CMICAGO GRIDGF AND IR ON CO. BIRMINGHAM ENG UPPER 9FAM SEATS: CONTRACT 69-5562U: D AT E 04-09-74; BY LDF; SHT BM SREV 0 i 5 h J14 CRS

I0948-088 L o A c t N (> Cow etT IO N A IO B& Q) CIRCUMFEAENTIAL SlRESSES OUE TO MAXIMUM POSITIVE MOMENT TYPF LOAD DUE TO AMT LOAD > INS STRESS OUTS STRESS (PSI) (PSil MOMENT (DEAD LOAD 648972 IN-LH 3609. -4362. THRUST ON BEAMS) 6541. LBS 129. 129. MOMENT (LIVF LOAO 1102329 IN-LR 6129. -7409. THRUST ON BEAMS) -3443. LRS -68. -68. CIRCUM (OTHER LOA 0 12310. LB/IN 00 7144. ~ STRESS AROVF RFAM) -800. LB/IN -464. TOTAL 16942. PSI -12174. PSI At.LOWABLE STPESS = 20280. PSI l CIRCUMrEDENTIAL StutSSES OUE TO MAXIMUM NEGATIVE MOMENT TYPF LOAD DUF T fl AMT LOAD INS STRESS OUTS STRESS (PSI) (PSI) MOMENT (DEAD LOAD -762622 IN-LB -4240. 5126. 1 THAUST ON BEAMS) -9361. LBS -184. -184. MOMENT (LIVE LOAD -518453 IN-LB -2883. 3485. THRUST ON dFAMS) -4699. LBS -93. -93. CIRCUM (DTHER LOAD 12310. LR/IN OR 7144. STRESS A60VE BEAM) -800. LB/IN -464. TOTAL -7864. PSI 15477. P SI i l ALLOWA6LE STRESS = 20280. PSI GUCKLING STRESS = -184.' +( -93. 1+( -464. )= -741. PSI 3FI 3( 27400000. It 1170.17 ) AL t.0 W A BL F SUCKLING STRFSS= ------= -------------------------- = 5688. PSI 2 2 2R A 2( 408.00 ) ( 50.79 ) CHICAGO BRIDGE ANO IRON CO. BIRMINGHAM ENG UPDER 3EAM SEATS; CONTRACT 69-55620; DATE 04-09-74; BY LDF; SHTSm4 REY 0 C - (? 1 4 CSS

l0948-089 ' LoAbius cosiotrieu A (oBee) ^ , SHELL MERIDIONAL STRESSES e &, MAXIMUM LOAD ON BEAM SEAT = T9900.0 LBS CONSIDER LOAD TO ACT ON A CIRCUMFERENTIAL ARC AT THE BOTTOM OF THE 8EAM SEAT E00At TO 107.58 INCHES. '

                                                                                                                 ~

MERIDIONAL STRESS FROM LOADS ABOVE BEAMS = -2450. PSI LOCAL BEAP SEAT MERIDIONAL STRESS = -889. PSI TOTAL. = -3339. PSI ALLOWABLE MERIDIONAL STRESS = SNN + (T) ( 0.8750 ) SNN= 1800000. ---- = 1800000. -------- = 3860.3 PST R ( 408.0 ) - SCAT BENDING STRESSFS SECT ION MODUL US TOP = 45.56 IN-3 SFCTION MODULUS BOTTOM = 12.96 IN-3 W D'w N T DUE TO GIRDFR = 179775. IN-LBS STRESS AT TOP = 3946. DS! < 20280. PSI STRFSS AT BOTTOM = 13875. PSI < 20280. PSI WELD LOADS (LOADS FOR WELDS C AND E ARE THOSE ON EA 0F THE 2 WELOS C AND ON EA Of THE 2 WELDS El (UNIT SHEARS ARE GIVEN FOR EA 0F THE 2 FILLETS ASSUMFD AT EA WELO) WELO A: V= 24812. LBS UNIT SHR= V*Q/(2*ll 796. LBS/IN WFLO R: V= 24812. LBS UNIT SHR= V*Q/(2*I)= 955. LBS/IN WELD C: P= 19975. LBS UNIT SHR= P/12*L) = 710. LBS/IN WELD 0: Vs 39950. LBS UNIT SHQ= V*Q/(2*l)= 4158. LBS/IN wtLO r: p= 19979 LRS UNIT SHP= P/(2*L) = 3329. LBS/IN CHICAGO AHidGE AND IRON CO. BIRMINGHAM ENG UPPER n' als 5F A15; C. A1 RAL I o9-5562U; b^TE 04-09-74; BY LDF; SHTBtsq REV O 9 10 7 +. cFS

              --                           ~                                                             ,

. ~ ~ 10968-090 INPUT FCA UPPER REAM SEAT ANALYSIS: LOAO CoraolTIO3 E C. (I-l 6 G - ELE VA T IUNS Or ECUATTt = 547.0000 FT. TOP OF < TEEL (TOP OF GIR9FP)= 60 7.0000 F T . R A D IU S r.'f SPHERE 408.00 IN. SHELL THICKNESS 0.8750 IN. MODULilS OF LLASTICITY 27400000. PSI FACTOR OF SAFFTY(BUCKLING) 1. 5 ~ ALL OW ABt.E T ENSILE STRESS 33800. PSI VFRTICAL SEISMIC FACTOR .200 { AISC BEN 0!NG ALLOWAPLE 33800. PSI LOADS

              '31 V F N DEAD AND F4RTHOUAKE LCA05 ON THE BEAMS ND         A7.14UTH  LOAD        EO LnAn (DEG.)   (LBS)        (L65) 1         122.60   34000,       6800.

2 147.40 31000. 6200 3 171.00 23000. 4600. 4 189.00 23000. 4600. j 5 I 212.60 27000. 5400. 6 237.40 28000. 5600. A GIVFN LIVE LOAD OF 42500. LRS ACTING AT 122.60 DEGREF%  ! l l l l l CHIC AGO BR IDGE AND IRON CO. BIRMINGHAM ENG UPPER BEAM SEATS: CONTRACT 69-55620: DATF 04-08-74; PY LnF: SHT Eng rey 5 - 10 ~)t C[L$

10948-091- - J INPUT CONTINUED LO AO C CW D IT 4 o N B ' D 6 f. S ' STRESSES OUE TO LOADS ABOVE BEAM SEATS (SEE SECTION 1C1 - 9AX. TENS. CIRCUMF. STRESS RESULT. 12510. LB/IN MAX. COMD. CIRCUMF. STRESS RESULT. -1000. LS/IN 4AXIMUM CCMPRESSIVE MFR IGION AL STRESS -2680. P SI 410T H ()F GIRDER 12.00 IN OFAM SEAT 01 '4 E N S I ON S IN INCHES 41 = 14.0000 01 = 1.0000 62 = 1.0000 l D2 = 6.0000 RING GIROER DIMENSIONS IN INCHES BH= 10.0000 ~~ TH = 1.0000 By = 10.0000 , TV= 1.5000 l l l l 1 CHIC AGO RPIOGF 6ND IRON CD. BIRMINGHAM ENG UPPER BFAM SEATS; CONTRACT 69-5562U; D AT E 04-08-74; BY LOF; SHT BM iREV i G.t0-14 CILS I

IO948-VS'l - 1 d OUTPUT FOR UPP ER HFAM SEAT ANALYSI5 LOAO C, C L) O I T) C M B = Q $$ Q I A NGL E T HE T A = 17.25163 OEG J l COMPONE NT S OF BFAM LO ADS t.CT ING ON SHELL AND RING GIRDER

                                                                                                                        )

VERT LOAO SHElt COMP RING COMP

                                                                                                             ~
                                                                                                                   "3 NO      AZIMUTH (DEG)              (LBSI            (LBSI                       (LBS)                            ,

1 122.60 40800. 42722. 12670. 2 147.40 37200. 38952. 11552. 3 171.00 27600. 28900. 8571. j 4 189.00 27600. 28900. 8571. ' i 5 212.60 32400. 33926. 10061.  ! 6 237.40 33600. 35183. 10434. PROPERTIES OF RING GIRDER WIDTH OF SHELL ACTING WITH GIROER = 29.5 IN AREA 0F SHELL ACTING WITH GIRDER = 25.8 IN-2 l AREA 0F THE ATTACHED GIROFR = 25.0 IN-2 _' TOTAL AREA OF RING GIRDER = 50.79 IN-2 l MOMENT OF INFRTIA ABOUT Y AXIS = 1170.17 IN-4 i SECTiqN MODULUS OF INSIDE = 179.86 IN-3 ) SFCT!UN MODULUS OF OUTSIDE = 148.79 IN-3 I l l J CHIC AGO BRIDGE AND !RON CO. BIRMINGH&M ENG UPPER SEAM SFATS; CONTRACT 69-5562V; D AT E 04-08-74; BY LDF; SH T BM'OREV G to 14 CILS  ! l I

g L O A catM A Co y o1Tiou B [O BE C - 4

 .'       CIRCUMrE4ENTIAL STP ESSES OUE TO MAXIMUM POSITIVE MOMENT TYPE LOAD                 DUF TO                     AMT LOAD                                                                      INS STRESS                OUTS STRESS (PSI)                                                                                                         (PSI)

MOMENT .(0040 LOAD 707970 IN-LR 3936. -4758. THRUST ON OFAMS) 7136. LBS 140. 140. I MOMENT (LIVE LOAD 1102329 IN-LB 6129. -7409. ' THRUST ON BFAMS) -3443. LBS -68. -68. ) CIRCUM (OTHER LOAD 12510. LH/IN OR 7260. STRESS A60VF BEAM) -1000. LB/IN -580. l TOTAL 17398. PSI -12675. PSI , ALLOWABLE STRESS = 33800. PSI I

         'CIRCUMFERENTIAL STRESSES OtlE TO MAXIMUM NEGATIVE MOMENT TYPF LOAD                 DUE TO                     AMT LOAD                                                                       INS STRESS               OUTS STRESS (PSI)                                                                                                        (PSI)

MOMENT (DEA 9 LOAD -8 319 51 !N-LB -4625. 5592. THRUST ON BEAMS) -10212. LMS -201. -201. MOMENT (L IVE LOAD -518453 IN-L6 -2883. 3485. THRUST ON RFAMS) -4699. LBS -93. -93. CIRCUM (DTHER LOAD 12510. LB/IN OR 7260. STRESS ABOVE BEAM) -1000. LB/IN -580. l TOTAL -8382. PSI 16042. PSI ALLOWARLE STRF.SS = 33300. PSI BUCKLING STRESS = -201. +( -93. 1+( -580. l= -874. PSI 3El 3t 27400000. )( 1170.17 l ALLnWABLF RUCKLING STRESS = ------= -------------------------- = 7$84 PSI 2 I 2 f,5 R A l.6( 408.00 ) ( 50.79 I l f CHIC Ab0 BR10GF AND IRON CO. SIRMINGHAM ENG UPPER BLAM SE ATS; CONTR ACT 69-5562U; DATE 04-08-74; BY LDF; SHT BM-n REV 6 10-14 CBS

                                                        --10948-094                                              ,
                                                                                                               . y.

L O A b l N 6, C O N D tTI ON b ( D F3(EG) 4% SHELL MERIDIONAL STRESSES -

                                                                                                               ~@O MAXIMUM LOAD ON BEAM SEAT =                 83300.0 LBS CONSIDER LUA0 IU ACT ON A CIPCUMFERENTIAL ARC AT THE BOTTOM OF THE BEAM SEAT EQUAL TO                107.58 INCHES.                                                            .x MERIDIONAL STRESS FROM LOADS ABOVE REAMS =                               -2680. PS[

LOCAL BEAM 5 EAT MERIDIONAL STRESS = -927. PSI TOTAL = -3607. PSI , ALLOWABLE MER1010NAL STRESS = SNN (T) ( 0.8750 i SNN= 1800000. ---- = 1800000. -------- = 3860.3 PSI R ( 408.0 1 SEAT RENDING STRESSES

e. m SECTION MODULUS TOP = 45.56 IN-3 SECTION MODUL US ROTTOM = 12.96 IN-3 MOMENT DUE TO GIRDER = 187425. IN-TBS STRESS AT TOP = 4114. PSI < 33800. PSI STRESS AT BnTTOM = 14465. PSI < 33800. PS!

WFLD L O ADS (LnA05 rnR WELDS C AND E ARE THOSE ON EA 0F THE 2 WELOS C AND ON EA OF IHE 2 WELOS El (UNIT SHEARS AR E GIVFN FOR EA 0F THE 2 FlLLETS ASSUMED AT EA WELD WELD A: V= 25668. LPS UNIT SHR= V*Q/(2*l)= 830. L95/IN WELD P: V= 25868. LRS UNIT SHR: V*Q/(2*Il= 996. LBS/IN WEL D C: P= 20875. LBS UNIT SHR= D/(2*L) = 740. LBS/IN HELO 0: V= 41650. LBS UNIT SHR= V*Q/(2*ll= 4335. LBS/IN WELD E P= 20825. LBS UNIT SHR= P/(2*L) = 3471. LBS/IN CHICAGU BRIDGE AND ! WON CO. , BIRMINGHAM ENG USPER U'" Sr'Tt: C , T 'I t " T 6 9 c,5 5 ? '! : 7ATF 04-03-74: By LOF; S HT 8442 REV 5-to 11 cg5

m 1 t Loc o coM o n ref4 0 - o BE dl s ELEVATIONS OF EQUATOR = , 597.0000 FT. ' __._..IOP OF STEEL (TOP OF GIRDER)= 607.0000 FT. RADIUS OF SPHERE 408.00 IN. SHELL THICKNESS 0.8750 IN. MODULUS OF ELASTICITY 27400000. PSI F AC TOR OF SAFETY (BUCKLING) 2.0 ALLOWA6LE TENSILE STRESS 17500. PSI VERTICAL SEISMIC FACTOR .100 AISC BENDING ALLOWABLE 20280. PSI LOADS GIVEN DEAD AND EARTHQUAKE LOADS ON THE BEAMS NO AZIMUTH LOAD EQ LOAD (DEG.) (LBS) (LBS)

            ._                 J___ _. 12 L. 6 0                          34000.             3400.

2 147.40 31000. 3100. 3 _ . 1.71.00 23000. 2300. _ 4 .169.00 23000. 2300. , 5 212.60 27000. 2700. I 6 237.40 28000. 2800. {

                                                                                                                                                  \
                                      ~                ~

A G I V EIi 'LI~V E'~L O A D O F 43400. LBS ACTING AT 122.60 DEGREES I I 1 l i CHICAGO BRIDGE AND IRON CO. BIRMINGHAM ENG UPPER BEAM SEATSi CONTR ACT 69-55620; DATE 04-22-74; BY LDF; SHTBM13REV O _ - _ _ _5-h.% C (L $ __ l 8 9 6 O

fr8 - 0 9 6 -

         , INPUT CONTINUED                                                                                                                                                                                  I                                         c LMD                                 G .> ' ' *D p g g g              _.

oyQ STRESSES DUE TO LOADS ABOVb BEAM SEATS ISEE SECTION IC) MAX. TENS. CIRCUMF. STRESS RESULT. 12310. LB/IN ' MAX. COMP. CIRCUMF. STRESS RESULT. -800. LB/IN MAXIMUM COMPRFSSIVE MERIDIONAL STRESS -2450. PS! WIDTH OF GIRDER 12.00 IN ' BEAM' SEAT DIMENSIONS IN INCHES B1 = 14.0000 D1 = 1.0000 ' d2 = ~ ' ' ~ 1.0000 D2 = 6.0000 _..R I NG_G I R DE_R _D I M E NS 10NS IN INCHES _,. _, , _ , , BH = 10.0000- -.... . _ . . . .. BV = 10.0000 TV= 1.5000 l CHICAGO BRIDGE AND IRON CO. BIRMINGHAM ENG UPPER BrAM SEATSt CONTRACT 69-5562U; D AT E 04-22-74; BY LOF; SHT BM uL REV 0 5 is -H cAS

 . _ - . -              .            -                                                   . . _ . _ . .                                                                                            .-                                                         l l

N . 4u.i. .a. .p. ee p.s ei _* * ---

OUTPUT FOR UPPER BEAM SEAT ANALYSIS Lb hh [T 1 ct4 O c g Q ANGLE THET A n 17.25163 DEG COMPONENT S OF BEAM LOADS ACTING ON SHELL AND RING GIRDER NO AZIMUTH VERT LOA 0 SHELL COMP RING COMP (DEGI .. . . . ILBS) (L85) (LBS) 1 122.60 37400. 39162. 11614. 2 147.40 34100. 35706. 10589. 3 171.00 _, 25300. 26492. 7857. 4 . 189.00 25300. 26492. 7857. 5 212.60 29700. 31099. 9223. 6 237.40 - 30800. 32251. 9565. PROP"5R, TIES OF RING GIRDER WIDTH OF SHELL ACTING WITH GIROER = 29.5 IN l AREA 0F SHELL ACTING WITH GIRDER = 25.8 IN-2 AREA OF THE ATTACHED GIRDER = 25.0 IN-2 TOTAL AREA 0F RING GIROER = 50.79 IN-2 MOMENT OF INERT!A ABOUT Y AXIS = 1170.17 IN-4 i SECTION MODULUS OF INSIDE = 179.86 IN-3 ' SECTION MODULUS OF OUTSIDE = 148.79 IN-3  ! l i j I { i _..__._.j l

                                                                                                                                                                    -i l

CHICAGO BRIDGE AND IR ON CO. BIRMINGHAM ENG UPPER BEAM SEATS; CONTRACT 69-5562U; D AT E 04-22-74; BY LDF; SHTBM-15REV O E-n 1t CILS h-e_._p.._hu .gha.e .M.._. l

. . . _ . . . - . ._ . -                 . _ _ . _ . . .         N'D*mt ---                         . . -                 . . . . . _ _ - . . .                         - . _ _ _ _ _             1
                                                      .                L o A O t k4              G op o lTio bt                              O (Oge Q)

C'fiduP5FER5'NT I AL' STRE55ES DUE TO M AXIMUM POSITIVE MOMENT j

                                                                                                                                                                                               . l TYPE LUAD                                OUE TO               AMT LOAD.                           INS STRESS                                     OUTS STRESS
  .                                                                                                                      (PSI)                                  (PSI)                       - ..
           . MOMENT                           (DEAD LOAD            ' 648972 IN-LB                                   3608.                                 -4362.

THRUST ON BEAMS) 6541. LBS 129. 129. '] MOMENT (LIVE LOAD 1125672 IN-LB 6259. -7566. ' THRUS1 GN BEAMS) -3515. LBS -69. -69. CIRCUM (OTHER LOAD 12310. LB/IN OR 7144. 5 TRESS . ABOVE B,EAM) -800. LB/IN -464. TOTAL 17070. PS! -12332. PSI ALLOWABLE STRESS = ,_._20280. PSI , o l

                                                                                                                                                      ~~                 "~
      -CIRCUMFt:RENTI AL STRESSES DUE TO MAXIMUM NEGATIVE SON $Ni

< 1 TYPE LOAD DUE TO AMT LOAD INS STRESS OUTS STRESS (PSI) (PSI) , MOMENT (DEAD LOAD -762622 IN-L8 - 4240.~ 5126. T.H R U1T __._ . .ON BEA,MS) __,9,3J.1, ._ L B S _ _ ,.,,, - 1 8 4 . ,

                                                                                                                                                            . - 18,4.
          - MOMENT                            (LIVE LOAD             -529431 IN-LB                              -

2944. 3558. i TH4UST ON BEAMS) -4799. Ld5 -94. -94. l

                                                                                                                                                                            ~ ~ ~

CIRCUM ~ (OTHER LOAD 12310. LB/IN OR ~~7144. STRESS ABOVE BEAM) -800. LB/IN -464. TOTAL - 7927.- PSI 15549. PSI ALLOWABLE STRESS = 20280. PSI

                                                                          ~                                                                                                           -

BUCKLING STRESS =~ 184. +( -94. 1+( - 4 R.' ~is -743. PSI i 3EI 3( 27400000. )( 11_7,0.17 I l ALLOWA6LE BUCKLING STRESS = ------= -------------------------- = 5688. PSI i 2 - 2 2R A 2( 408.00 i ( 50.79 ) HICAGO BRIDGE AND IRON.CO. BikMINGHAM ENG 69-55620i DATE 04-22-74; BY LDF; SHT BM6 REV O UPPER BE_AM SEA _TSi_ CONTRACT 5 -in i t cits de Tup.e-De.' p *4P4ep.s e e  %,g4

                                                                                      +ee.e.

e

  • OFDW" N 66*

109';B-U33 &l SHELL__MERIDIDN,AL STRESSES __L DA p>lN/, (_0 N D IT t c N Q [6$QG) - -l

                                                                                                                                                                  .a MAXIMUM LOAD ON BEAM SEAT =                                80800.0 LBS                                                                   -"i !

CON S,l D E R. LOAD.TO.ACT ON A CIRCUMFERENTIAL ARC AT THE BOTTOM OF THE BEAM -N-SEAT EQUAL TO 10T.58 INCHES. MER IDIONAL STRESS FROM LOADS ABOVE BEAMS = -2450. PSI ___.._ .._LQCAL BEAM SEAT MERIDIONAL STRESS = - 899. PSI

                .          .               .     . _ _ _ , _ . .                    ._. TOTAL.               =
                                                                                                                            -3349. PSI ALLOWABLE MERIDIONAL STRESS = SNN                                                                                                                 -

(T) ( 0.8750 ) SNN= 1800000. ---- = 1000000. -------- = 3860.3 PSI R ( 408.0 i SEAf BENDING STRESSES _ SECTION MODULUS TOP = 45.56 IN-3 SEC110N MUDULUS BOTTOM = 12.96 IN-3 -- MGMENT DUE TO GIROER = 181800. IN-LBS STRESS AT TOP = 3990. PSI < 20280. PS! STRESS AT BOTTOM = 14031. PSI < 20280. PSI - l 1 dELO LDADS (LOADS FOR WELDS C AND E ARE THOSE ON EA OF THE 2 WELDS C AND ON

               . ._ _ - _ _ _... _ _ .L A . 0 F THE 2 WELDS El (UNIT SHEARS ARE GIVEN FOR EA OF THE 2 FILLETS ASSUMED AT EA WELD)

WhLD A: V= 25092. LBS UNIT SHR= V*0/(2*I)= 805. LBS/IN . WELp .1: V= 25092. LBS UNIT SHR= V*Q/(2*I)= 966. LBS/IN l WELD C: P= 20200. LBS UNIT SHR= P/(2*L) = 718. LBS/IN

           . ._. 4 L D . D .: V =.._ .. _ 4 Q_4.0 0 . LBS                          UNIT SHR= V*Q/(2*!)=                              4205.        LBS/IN WELU E: P=                                  20200. LBS          UNIT SHR= P/(2*L)                             =   3367.        LBS/IN                   l l

l l

                                                                                                                                                                           )

EHIC_AG JRIDGE AND 1RON CO. BIRMINGHAM ENG UPPER dEAM SEATS; CONTRACT 69-5562U; DATE 04-22-T4; BY LDF; SHTSMT7REV O E 7 9 C115 _r 9 ._.*N a. p . ee +mNh 4 T M*h** O **N m 4 6 m

10948-100

                                                                                                                                   ' ~

BIRMINGHAM DESIGN Locethn , LoAo Couerttou E 4 r - RtwG 6 t n es st E F F s c T- ,

                                                                                                     ,                               3
                                                                                                           .                            "I
                                                                                                                                       ~

t yd.7 -esd .

                             ,                      /       s,
                                                   //                                                                    , ,

j e/- e

                                        ,/ '

i

                                      ?;t, e,

P Y E $0 y - G , [ I P = Given load on beam seat in pounds With the above load P transposed into its components, we can for purposes of analysis, assume the beam seat to be momentless, the tangential loads (P/Cos0) are carried directly by the shell,' and .. I the horizontal loads (P Ten 0) are carried directly by a continuous i ring girder. l IF THE 6tvt.8 LoAo P is A C. T tM G U P W AR Q , TH G H C R IT.ON TA L L e A o (, P t A H 9), W t LL B E. A c.T ( M G RAO ALLY CUTW AR.O CM l THE R t H C, G t R D C- R.  ! l 4 1 SUBJE CT MADE BY CHKD BY gy CHARGE NO. U P P E R. f6E AM SEATS Lor CM > W 69-5567. DATE " Chkd DATL 67*l4 $-l0-It Date SHTb OF Y1 . . . _ -- .. - . - . = . . - . - . _ -

10946-101 , CHICAGO BRIDGE & IRON COMPANY 4/15/68-4 B'H8M. ENGINEERING DEPT. o The girder section properties are computed in the normal manner about the vertical neutral axis, and are calculated by considering the girder as follows:

                                                                                        *Per Code Case 1290
                                                       /,

N. , p, 'Nss OC 6HELt, k, s' s

                                             /                                   '
                                                         // Y       <Y     f       l
                                   /'N                                                                          ~
                                           \                    *g The properties found are:

I = moment of inertia (in 4) Z = section modulus (shell side) (in 3) shell Z = section modulus (flange side) (in 3) flg A = area of girder (incl. shell) (in 2) L = length of shell acting as girder (1.56Kt) (in) After applying the loads, the ring girder's maximum positive and negative moments are found. The method used to analyze the ring is as follows. The horizontal components of the given beam loads act as radial loads on the ring girder using the given azimuths. THE$i LOAO3 ARE IN NT I NT O C. B I PR04AAM 4 0 Ei, TW is Pnt o G. 8 A M AW A LY1ES THE fttt4C, A5 F o L L ew s ', sweact Upper Dean Seats contN'Mk.t. 6 7 ~l4re LCF snt.fLibe c~n.o en.cs.o @ 5 o.t.5-9 M n ., n o. o.t. m., uo. o.t. __ n ., so. o.t.

                                                        )Ub1b~IUL 1

r - -- - 4/15/68-5 CHICAGO BRIDGE & IRON COMPANY B ' HAM. ENGINEERING DEPT. y The analysis of the. ring assumes a constant moment of inertia and P' modulus of' elasticity. The mathematics are based upon the

  • I Hardy-Cross column analogy for rings as referenced in Theory of Modern Steel Structures, Vol. 2 by Grinter, page 259. This analysis gives the bending moments and the thrust in the ring due to the radial loads.

The stresses in the ring are the summation of the following stresses: o,= M/Z where o m = stresses due to moments (PSI) M = moment (in-lbs) Z = section modulus - shell or flg (in 3) ot = N0 /A where ot=ring stress from circumferential thrust in due to radial loads (PSI) N0= circumferential thrust in ring due to radial loads (lbs.) , A = area of ring girder (in 2) Uo=NO x L where 0 0 = stress in ring girder due to stress in A shell from all loads above work point (psi) Ng = circumferential stress in shell from all loads above work point ( lbs/in) L = length of shell acting with ring (in) A = area of ring girder (in2) , j l In addition to the bending analysis of the girder, the girder is checked for buckling. This condition would occur as the loads approach an infinite number, i.e. , the ring would be in com- q l pression across the full cross section. I l 6) sudact Upper Beam Seats cent oate F~M 4 ey_LCF snt BW'LO e q asv i 4 e eneckoo O 5 oate 6"M Rev No. Date Rev No. Date Rev No. Deto

m __3

 .                                                                                          4/15/68-6                    '

CHICAGO BRIDGE & IRON COMPANY B ' HAM ENGINEERING DEPT. The loads considered are the thrust stresses (at) Plus the W circumferential stresses due to all other loads (oo). The thrust loads are the maximum negative and the maximum stresses due to other loads are generally the refueling stresses. The allowable buckling stress can be found by considering the critical load to bes < p1 = 3EI From Roark " Formulas for Stress and Strain" 4th ed, case 12 pg.342 r3 p1 = critical radial load (lbs/in) E = modulus of elasticity (psi) I = moment of inertia (in 4) r = radius of ring (in) j The circumferential stress for a ring with a uniform radial load can be shown to be o = P_r, r where o = stress (psi) A P = radial load (lbs/in) r = radius of ring (in) A = area of ring (in 2) The allowable buckling stress can be found by substituting the critical for the radial load and using a factor of safety of 2. I o = 3 EI pot OBE Q l 2rA2 I l

                 ,y-     _

3 ET_ poA D BE Q ( F A cTM c5 S A F O 5( : le h j I,5 r2 A . . . . l 1 swe).ci Upper Beam Seats cont %Mo.t. E'7-74 er LOF sntEM l i .e R.v No. Det. m.v i .o en.ca.o CPS o t.5-h % R.v No. Date R.v No. Det. I

ius4u-iun . _ . . _ . _ _

                                                                              .. , BIRMINGHAM DESIGN pro 4R AM 4 05
                                                                                                                        .-W 4.-562 U NER BEAM SEAT-DBEO-LOAD Cor4DITIUN E LDF 5-6-74 d(R)           N(f)        d(M)            DATA SHEET NU.             PLOT CODE                                    .<--

6 0 0 1 0 H AI)I US MUD-ELAS i40M-I NER AREA C(l) C(2) 389.72 27400000.0" 1I70.I7 50.79 6.50 7,87 EQUILIHRIUM LdADS FV FH M/R IWPUT -30785.00 16448.00 0.0 COMPUTED -38786.34 16447.64 0.0 INPUT LOADS AND THEIR LOCATIONS _ RADIAL LUADS AND ANOLES LUADS 12670.00 11552.00 8571.00 8571.00 10061.00 ANGLES 122.60 147.40 171.00 189. 00 212.60 LOADS -5900.00 A140LES 237.40 da TAdGE JFI A LDADS NO MJtEN1/R LJADS UNIT STRESS VALUES FOR CIRCULAa RINOS ., PRIdIJUT AT EQUAL AWOLE INCREMEWTS _, X V/A T/A !a ( FORCE-LO ) 0.0 -b.941HE+0i 1.4232E+02 8.2086E+0S

6. 00 - 7. 3359E+0 i 1.2325E+02 6.84J2E+0S.

I2.00 -8.SO96E+01 I.0029E+02 5.2137E+05 l

18. 00 -V. 4 /4 3E+01 7.3872E+0i J.3694E+05 l 2 4 . rK) - 1. 0046E+02 4.4459E+0i 1.3669E+05 I 3 0. 09 - 1. 034 7E+0? I.2bd/E+01 -7.30/3E+04 I 36.')0 -1.030JE+02 -2.1i63E+0i -2.8550E+05 ~

l 4 2. 0 ') -9.H993E+01 -S.6170h+0i -4.9336E+05 4 8. 01 -0. I 24 8 E+01 -0. I 7H4 E+01 -6.8914E+05 S 4. 00 - 7. 97 /2 E+0 i -1.2734E+02 -B.6520E+0S 6 J. .n -6. 460bE+0 i -1.6214E+02 -1.0139h+06

60. h) -4.5H63E+0i -1.V552E+02 -I.1278E+06
                              /d.JO -2. J /28E+0i -2.2682E+0? -1.1998h+06 7H.0J        1. 5461 E+00 -2. SS37E+02 - I . 22 30E+06                                            1 d4.01         2.9640E+0! -2.HO58h+12 -1.1915E+06                                                      l 90.0)         6. 01 /4 E+0 i -3. OlH7E+02 - 1. 0998E+06                                               i l

96.00 V.2709E+01 -3.1873E+02 -9.4324E+0S I C?. T) 1. 26 /6 E+ 02 -3. 3069E+ 02 -7. l H 33E+05 l 10 >1. 4.) 1. 61/dE+02 -3. 3 737E+02 -4. 2248E+05 l 114. 01 i . 9 / 22 E+02 -J. JH46E+02 -5. 424 3E+04 120.00 2. 3d4 /E+02 -3. 3373E+02 3.8660E+05 126.0-) ).7889E+0i -J.3783E+02 6.OV2JE+0b l .$ d . )J 5.3M00E+UI -3.470/E+02 6.d260E+05 l 36. 00 9. 0354E+01 -3. 4 989E+')2 d.3042E+0S MADE BY CHKO BY B" CHA O SUBJECT U PPE R B tE A M SEAT 5 t. o r- c 12 5 > 69,5 7_ DATE DATE f-> % 50 H- Dete SHT_M OF CO dd fttv 4 73

1 U 3 tB F UM BIRMINGHAM DESIGN tocation .,. x V/A TA M (re e m ) 144.00 1.2686E+02 -3.4614E+02 1.0533E+06 15 0. 00 -6. 4394E+01 -3. 4 609E+02 1.148JE+06 - 1 S6. O') -2. 793 /E+01 -3.528dE+02 l . 05 3JE+06 . 162.00 9.07/2E+00 -3.5292E+02 1.0339E+06 160.00 4. 5 741 E+0i -3.4620E+02 1.090JE+06 I/4.00 -H.716dE+01 -3.4169E+02

1. 04 79 E+06 1 H 0. O'.) -S.I44bE+01 -J.3950E+02 9.0576E+05 iH6.On -1.6286E+01 -J.3094E+02 8.J644E+05 192.00 -1.5087E+02 -3.2504E+02 6.6SI2E+05 19 8. 'M - 1.1694 E+02 -J. 2206 E+ 0? 3.9047E+05 204.00 -d.3620E+0i -3.1336 ti+ nd 1.8490E+05 ~

210. 00 -b. I 4 98E+01 -2.9926E+02 4.6552E+04 216.00 -2.1686E+02 -2.91RHE+02 -2.5768E+05 222. 00 - 1. HH4 2E+02 -7. HH81 E+02 -6. 75 40E+05 228.00 -I.oH53E+02 -2.8134E+02 -I.03!IE+06 234. 00 -I . 296JE+02 -2. 6986E+02 -I . J265E+0o . 240.00 I . 39 I I E+01 -2. 4 950E+02 - 1. 4608E+06 246.00 3.H474E+0! -2.1916E+02 -1.4065E+06 752.00 5.9725E+0i -1.8637E+02 -1.3052E+06 2b H . 00 7. /44 JE+01 -l.5178E+02 -1.1639E+06 264.03 9.14 /6E+01 - 1.1609E+02 -9. 8997E+05 270.'O l . 0174 E+02 - 7. 9964 E+n t - 7. 91 13E+ 0$ 2 / 6. 'O 1.0H232+02 -4.409JE+01 -0.7510E+05 282.00 1. I i 01 E+02 -9.1389 E+ 00 -3. 4 959E+05 2H6.00 1.1020E+02 2.4258E+01 -l.220HE+05 294.01 1.0600E+02 Q.5495E+01 1.0025E+05 300.0J 9.8673E+0! 8.4010E+0i 3.10/IE+05 306.03 n.8b21E+0i 1.0930E+02 5.03lHE+0S J12.00 /.5910E+01 1. 3 091 E+02 6.7223E+05 J18.00 6.124DE+0! 1.4847E+02 8.1324E+05 324.00 4.4V6/E+01 1.ol67F+02 9.2242E+05 330. 00 2.754DE+01 1.7029E+02 9.9695E+05 336.00 9.4677E+00 1. 74 I /E+02 I.0350E+06 J4 2. 00 -n. 704oE+no I.7325E+02 1.0357E+06 346.00 -?.6650E+01 1.6755E+0? 9.9026E+05 Jb4.00 -4.369JE+01 i.57iHE+02 9.2692b+05 36 0. i r) -5.9414E+01 1.423JE+02 8.20H9E+05 36 0. 00 -S. V4 i HE+01 I.4232E+02 8.2nH6E+05 l 1 l l SUBJECT MADE BY CHKD BY gy CHARGE NO. UPPER BEAM SEATS t. 0F cfRS > 69-556'2-DATE DATE S F14 5 to ~l+ Dei. sHTB W or CO 64 REV 4 73 _ ,_ _ _ . , _

1 10968-106 d BIRMINGHAM DESIGN t.ocetion

                                                                                                               ; LW eul 4 f )UT AT LJA0 AllD/OR mud,E 4T Pal;4TS                                                     -

S V/A T/A M(roAce-Li> I22.60 -I.V287E+00 -3.2983E+02 6.0000E+05 122.59 2.4747E+02 -3.2985E+02 5.9915E+05 14 7. 4 0 -8. 01 ddE+0 i -3. 4108E+02 I.2127E+06 ' 14 /.37 1.4720E+02 -3.4109E+02 I.2122E+06 v71.00 -1.0503E+02 -3.4035E+02 I.I465E+06 170.99 6.3667E+0i -3.4037E+02 i.I463E+06 1 H9. 00 -I . 6 /d 7E+02 -3. 24 33E+02 8'.2857E+05 IHH.90 8.2260E-01 -3.2435E+02 6.2857E+05 . 212.61 -2.3617E+02 -2.9156E+92 6.7444E+03 212.59 -3.8135E+01 -2.9159E+02 6.8769E+03 23/.40 2. 314 2 E+ 00 -2. 6172 E+ 02 - 1. 4 6HO E+06 237.39 -I.1390E+02 -2.6174E+02 -1.4677E+06 i>R 114 fUuT UF ;4 A X1,..dia AllD l4 iHl 40'4 V ALUES OF SHE AR. TilRUST, A11D MOMENf

     /AL'JE3 TAKEW FRO 4 9UTH OF THE fADLES ABUVE 4AXl.4JM V/A=                        2.4 /47E+02       AT   I22.59        UdGREES
     '41 N I .4dM V/ A=                   -2.3617E+02        AT 212.60          DEGREES
     #4 A X 1:4JM T/A=                      1.1417E+02       AI 336.00          DEGHEES
     '41 N I .40l!. T/ A =                -3.5292E+02        AT   162.00        DEGREES
     .4 A X I ..id.4 M( FORCE-LO )=         1.dl27E+06       Al   147.40        DEGREES-M l W 1.40il, 44 ( FURC E-LG ) =     -1.4680E+06        AT   237.40        DEGREES-l i

l j 1 l l l l l l 1 BUBJECT MADE BY CHKD BY gy CHARGE N OPPER  % AM SEATS LoF C IM. g E c,,, M4h OATE DATE 0g.gOF

7. /.7 4 C f l0.*4 Dete SHT .

03 6 4 REv 4 73

10948-10/ Location Loao c.o s o trie n E C DB E (i)

                                                                      - R tt4 6       GtROER C IR.C. v M F E ( c.H T t A L     57RE SSE $ DVG To MvsMUM PotlitvE MOMENT,                            j l

TYPE LeAo ouE To A MT. l.o A D INS. STRESS ouTL STRESS j (PSI) (P5f) ( M okERT (D E A*D Lo^ D 1217 ~10 0 lN.lb 6 "I 3 (s -S66' TMv57 Lwt loa o) - 17 3 to i 4 -Mi - 34/ . < c#Rc, 12. 5to Ib/m e, 72.60 (oT H eit t.c4 0 STAe55 -10 00.16,u/ - 580 ASovE B6AM) T6TAL I"5 65 5 ps - 90 ~7 7 psi , { I ALL o we s et 518 E 55 = 33800F5' ( ( t&c u M t:E RE wr t A L ST RE sses ove To Max tMvm NE(i nTivG N o M6 HT, T NPC 'Lomo on T o A MT , Lo A D ins,srRtss ouT5,57A,e55 (P58) (, P 5 t) M0 MEN 1 (ogno to Ao - 146 V o co tw.lb - 9 l 54 erg 7 3

                                   ^

vsav$r l !2.9 3 \b - 16L - 2_ G 't. Liv e t orso ) - cigc. (oTHER toAo n.5s0 '6/<a oo 7760

            $r8Ess            A Gove SEAM)         - t oav 'b             -

FBo TO TA L - 9 99ff5/ 1697/rst A L L ow6 9Lc 57Res5 2 33 g oO rf / , SUL k L\M6 STRESS = - 34 I + (- 59& = ~ 9 2 0 a u.ow.sucruwa svness = 75s4 est (sescBM9) l SUBJECT MADE BY gy CHARGE ND. i UPPiw REAM SEATS LCF CH CRK D<Y> 6 9- 566 E I DATE DATE [- 7 ~47- $

  • l C -li Date SHT OF f20 6 4 REV 4 7 3

1 10948-108 . BIRMINGHAM DESIGN l

                      !M t -
t. o ri o co n o rrenu E (DBE G) O
                                                                                                                                                                                                                                                                       ' ~

C H td.t. ME nto lo N AL. STRE ss G S .. .

                                                                                                                                                                                                                                                                           '4 FF oM L o Ao co noirsoN 8 THE STRE S S WA% F ouluo TO B6
                                                              - 3 6 0"/ p s f.                               'f H E' M AX t MUM LoAo CN AH INOlVf D VAL S L /\ M S E AT                              U N D E R,,                        LoAO Collo tTj o N E 15 La w Tiw4                                                                                      . . .

TH6'f CF LoAC C oN O IT i c H B , T H E RtF M C , T H G S H E L.t.

                                                                  /*1 G M O lo N A L S TP4 05 15 LESS THAN LoAo CcHDirloN B.                                                                                                                                                .
            ,,                                             G ifto cra                    s tr A T'S                                                                                                        .        ..                   . . . .
                                                                                                                                                                                                                                         ...........g
                              . . . . .                   THE CM R.O E R SEATS W E RE.                                                             F out/P To BE A o E Qu f%T F, U N D G ft., _.. ...;
            ..                  ...                     - L o A o c.oN o t Ti o N B j FoK A MMIMun GWAM 5 e t;T Lo Ao .                                                                                                                                       ...L             .
                              .. . .. ... . O F . 8 3 3 c o 4 5. Ac. RING Qo w H. .

fHE d lR D e F. BE AN ALYZEO AS T ~ ~ " ~"

                           .. ...                                                                           SEAT AT                                     5        W 4L.t-A SI M P Ly                              S u p po RT E D BEAM W (T H T'H E RuPTvRE loa.O..L .
         . . . . . .  .                     , . _ .          A C.T l N 6i . UPWARD. IT 15 A 5.s ta two B o LT 5 A RE . . . . ... __ _, .                                                                                              *
                          . J. . . . _ . A D E Q U A T E.                                                 To TR A N S F E R TH t! TOTA L ' V P LoAO , T ,0 , . .'._ t ,.                                                                                                            . ,

I . "T" H E C.elR D E R SEAT. F o A Thi s ( *N o iTs o N TH s . TOT A L . ' _i

     .                ... .              .....                U P . Lo A o ON THE G I & D 6 R. 5E4 T ./5 A P I' L L E O A T.                                                                                                                                          !
  .                  ...                                  _.T H E . PJ o.LT.5 . .. ...__. .. ..               .                                   . . . . .                    . _ _ _ . .              ..       . ._ _ _ _ .. .'.. l ..J.....                                    .

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                               . . . . _ _ . . . . . .                     . . ' . . . . . ._.....-                                                       M ,= f 4 ,2 5 $ 1,,,1ft.v (.4 ti)
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                                '                              '                                                                                       4"e, cror,y -$rer            .b *- 4 0 37[. =""4 98pr 4 '43 $*e'pu Hn
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SUBJECT MADE SY CHKD BY gy CHARGE NO. U F PEtt, BEAM, SEATS LOF CtL S > W Chkd 6 #/- 5 f(,2. k. **"." DATE E ' DATE\\ 'i $' Date

                                                                                                                                                    ,'),.                                                    SHTY'U DF                                         .I...
                                                                                                                                $~.3i 4                                                                                                                        . . . . . .

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Iogs8 ;ag } m BIRMINGHAM DESIGN _ l Prof R AM 405 ** : 69-$u')2 JPPER DEA 4 SEA 1-UHEO-LOAD CJf401110t4 F LDF S-6-74 a(d) id ( T ) 14 ( M ) DAfA SHEFT t4U. PLOT CJUE 6 0 0 i O W A'110S M Ju-liL AS ta4-I rlER AREA C(I) C(2) l J iS. 74 2/4 00000.0 Ii10.I7 bO.79 6.50 '7.87 . .d EUUlLIPRluti LUADS FV FH M/R " , INPUf -JS2bv.00 154dv.00 0. 0 CJ!.lPU TED -35289. 71 15490.68 0.0 IWPu r LUADS A:40 THEL y LOCA flJi1S (Al)lA LJADS Ail D A l4 G L E S LUAOS 11614.00 10589.00 78b/.00 7db7.00 9223.00 ANULES 122.60 147.40 171.00 189.00 212.60 LOAOS -5900.00 , AWOLES 23/.40  ; du fAWGEi411AL. LOAOS l itu d'l tE W1 / d L M D S l Ui41T ST RESS VALul 9 FUR CidCULAR RINGS

                                                                                                                                    ~

PRiclfauT AT EQUAL ANGLE INCREMEr4TS X V/ A T/A M(FURCE-LG) 0.0 -b.594bH+01 1.3052E+02 7.55M9E+05 1

6. 00 -6. H708E+01 1.1262E+02 6.2771E+05
12. 00 - /. V409E+01 9.I186E+0i 4.7S39E+05 '

I d. 00 -e. 7c96E+0! 6.6607E+01 3.0354E+05 1 24.00 -V.326<4E+0i 3.VJ23E+0! l.1743E+0S 1 3 0. 00 -V. 5 W 5E+01 2 9. 83 00E+ 00 - 7. 70948+04 36.00 -9.5265E+01 -2.1336E+0i -2.7369E+05 -- 42.0) -V.1348E+01 -5.3603E+01 -4.ob69E+05 l 441.03 -8.4021E+01 -8.6370E+0i -6.4617E+05 S4.93 -7.326JE+01 -!.I902E+02 -H.0809E+05 . 60.00 -S.9IlVE+0i -1.5093E+02 -9.44e1SE+05 60.OJ -4.1009E+01 -1.HI4RE+02 -1.0444E+06 i

72. 00 -2. I I /9E+0! -2.1005 E+02 - 1. I I 34 E+06  !
                               / H. UJ    2. 2035E+00 -2.3006E+02 - 1.1334E+06 84.00       2.aiSIE+01 -2.9894 E+02 -l .1026E+06 Y O. 00     5.6309E+0i -2. /819E+02 - 1. 0163E+06                                             .

96.07 8. 62 /1 E+01 -2.9332E+72 -8.7035E+0S - 102.00 I.I75SE+02 -3.0394E+02 -o.6143E+05 100.01 1. 4 9 /6E+02 - 3. 096 7 E+ 12 -3. H731 E+ 05 f 114.00 I.H226E+02 -J.1026E+02 -4.6747E+04 - ' I20.01 2.I455E+02 -3.0549E+02 3.6037E+05 { l26.09 1. 77M E+01 -J.n881E+12 5.6738E+05 132.00 5.059/E+0! -3.1683E+02 6.3738E+05 138.99 9.3VJVC+01 .4. l H9 / s +12 7. /5 74 r+nS q l SUBJECT MADE BY CHKD BY ey CHARGE ND, U PPE R BE Ars SE AT S Lor CM > W Chkd 69-5562. DATE E DATE

f. 7.g 5 % 4 +- D. .. ssT 5 M-ZIDF f co n av 4.p

10948-110 l I g mBIRMINGHAM DESIGN l l I X V/A T/A m(rau.p)_

                                                                  .                                                        l 144.0:) I.I719E+02 -3.1511E+02                     9.8173E+05                                                 i 150.00 -d. d547E+01 -3.146/E+02                    1.0704E+06                                                 l 156.00 -2.5235E+0i -3.2051E+02                     9.8440E+05                                                 i 162.00        8. 3661 E+00 -3.202 t E+02           9.67tlE+05                                         '

l 168.00 4.1614E+01 -3.1376E+02 1.0185E+06 { l /4. 00 -8.0615E+01 -3.0938E+02 9.7859E+05 I 16 0. 00 -4. 6280E+01 -3. 0719E+02 8.4642E+05 I 186. 00 - 1. 64 79E+01 -2. 99 22 E+ 02 7.8013E+05  : 192.00 -1.4029E+02 -2.9376E+02 6.1946E+05 198. 00 - 1. 0963E+02 -2. 9104 E+02 63.6315E+05 204.00 -7.9517E+01 -2.8315E+02 1.6928E+05 210. 00 -9. 04 94 E+0i -2. 7038E+02 3. 614 5 E+ 04 216.40 -2.0432E+02 -2,6385E+02 -2.4991E+05 2 22. 00 - 1. /678E+02 -2. 6134 E+02 -6. 4078E+05 1 228.03 -I.4972E+02 -2.5487E+02 -9.7558E+05 234. 00 -l . 2353E+02 -2. 44 79E+02 - 1. 2557E+06 240.00 1. 74 77 E +01 -? 2619E+02 -1.3801E+06 246. O') J.V705E401 -I .9793E+02 -i . 320VE+06 z'2 2. 0') 5.8854E+0i -1.074dE+02 -1.219JE+0c 258.00 /.4 72dE+0i -l . 354 7E+02 -1. 081/E+06 264.0') H. 7 I 94 E+0i -1.025IE+02 -9.I499E+05 270.00 9.6186E+01 -6.9224E+0i -7.262VE+05 276.00 1.0170E+0? -3.6246E+01 -5.2z72E+05 2H2.30 1. 0381 E+02 -4. l e l l E+ 00 -J. I l 34E+05 2-8. 00 1.026 3E+ 02 2,6387E+31 -9.9032E+04 JV4.0) Y.6354E+0i 5.490dE+01 1.0764E+0b J S ) . 00 V.I220E+0i 8. 087 I E+ ')1 3.0256h+05

              .$ t # D . 03 d.lb22G+01        1.0JH2E+02         4.801/E+05 31 '> . 00   6.9596h+0i        1. 2 334 E+')?     6.3553d+0:2 318.00       S.5820d+01        1.3 Vile +02       7.6446b+05
              .524. 00      4.0602h+01        1. BOB 4E+02       H.6357h+05 uu.J)        2.43I66+0!        l.5H34E+02         9.3036E+05 3J6.ud        /. 5926 E+ 00    1.6147E+02         9.6321E+05                                   -

392.00 -V.2880E+00 1.6019E+02 9.6145E+05

              .34h. N -2.5804E+01             I.5452E+02         9.2535E+05 154.03 -<e.IDO2h+01             1.445HE+0?         d.b6iJu+05 J6(,.30 -;.5941E+01             1.J053E+02         7. %V 3E+05 J60.0.3       .a.59c h+0i       1.J052E+02            /.5bH9h+0S SUBJECT                                     MADE BY    CHKD BY          gy                  C UP9eR SUM SEAT 5                     L OT"       CILS      >                     69 HARGE ND.5f 42.

DATE DATE F 7 ~14 5 - t 9 -% Dm sHTMDF KO 64 REV 4 73 _ _ - -____--_ - __________ -_ _______________-_______-_____ J

__ q 10948-111 ~

                                                                                                    ~

g .

u. BIRMINGHAM DESIGN
                                                                                                                            %l u
                                                                                                                   .   .r.

PRlafJUT AT LOA 0 A!4D/UU MDi4EWT PUINTS , X. . v/A T/A M(FoA C E 'l 6) 122.60 -3.3342E-01 -3.0173E+02 5.5/27E+05 122.59 2.202dE+02 -3.0175E+02 b.S649E+05 14 7. 40 - /. 2 727E+01 -3.1024 E+02 1.1288E+06 141.39 I . 3570E+02 -3.1025E+02 I.1283E+06 171. 00 -9. 6788E+01 -3.0826E+02 1.0696E+06 .. . 170.09 5.7854E+0i -3.082aE+02 1.0694E+06 ~~ 189. 00 - l . 5566 E+02 -2.9 312E+02 7.712iE+05 188.99 -1.013*E+00 -2.9314E+02 7. 7122E+0S 212.60 -2.1997E+02 -2. 6342E+02 -J. 3482E+03 212.59 -3.842iE+0i -2. 634 S E+02 -J. 214 7E+0J 237.40 6. 9564 E+00 -2. 3 /60E+02 - 1. JV 10E+06 2J. / . 30 - 1. 0925 E+02 -2. 3 762 E+02 - l . 3906E+06__

                                                                                                                             ~

i>RIN fJUT OF MAXI...UM AND I41dl:4UM VALUES LF SHEAR. THRUST. AND muMENT VALUES TAKEN FRUM BOTti UF THE TABLES AisuvE MAXIi40,i V/ A= 2.2d24E+02 AT 122.ov JEGREES MIN 1mVM V/ A= -2. I OV /E+0? AT 212.60 UEGREES

        .4A X 1 AUM T/ A=                   1. 614 lb+02      AT  336.00     l)E3REES Mii41:4dM T/ A=                   -3.20SIE+02         AT   156.00    DEGREES r4A XI .4UM *i( FURCE-LG )=         1.128BE+06        AT   147.40    DEGREES 4IWIMUM a(FORCE-LG)=              -1.391OE+06         AT   237.40    I)EGREES 4       %
                                                                                                                  ~

SUBJECT MADE BY CHKD BY By C UPPER BE AM S EA TS Lor CR5 > W Chkd 6 C1 HARGE NO.5567. C.Y.$4 5? INg o.i. sstBkdor to s nv a.n

10948-1l'l . i h t*w BIRMINGHAM DESIGN LoAo (.o Fto ri t o,w F (CBE.Gd ~ . RjN 6 Gt RO ER C tv.uMFG REM Ti AL STRE5SE$ DuE TO MXIMuM P o $ 1TIV E ' f40k E t4T 4 T N Pt. (cAC DOE To " A(91, Le A O 195, STRE 55 e uts. S TRE 55 . (P S Q (P 11)  ! f4c M E.NT D E A0 t,o A o i l 2.$ Soo in4 G 7.7 0 . ~ 7 f C/ / , , THRUST LwIt e Ao) - l5 745 lb -

                                                                                   ~31 0             -

3Io .. . C tR(. (OT HER LcAo ll'lto M w ~/l 4 4 ,

    .             si As.55        ABove BEAM) "- freo %                                                -- + 6 +

TOTAL. I'5 to4g sf - 15 3 6 5p f f . ALLewAeLE STne 55 : t ottro es t u. ctRcv M FtAE.MTi m. STRESM.S CVE To MytMvM 146 4 ATIVE M c Mg s7*, TYPE LoAQ ou E To A M T.L e A 0 \MS, STRESS 00T5 57RE55 (PSI) (P S )) . M e, Mt.M T locao i.oAo -l S cf I o oo m a 1734 9349 rHau sr twit $o) - it ett 16 -23V - 23 E j cin c , (oraar i.eAC 113 t o k- "l [ 44 sr ec.ss Aeova etw) goo '% -+4+ _ 1 TOTAL - 94 3 6 e s t 16 EF5 rst  ! ALL ow ABLG STRESS = to2 So rs t f

                                                                                                                                     \

s u c. s t i g t, st RE ss = -? 10 + (- 46 4) : ~17 4 / 5/ A L L ow. B u c k Litm 57 9.E 5 5 : 66 99 F5I [5EE SH T Y'b') l MADE BY CHKD BY CHARGE NO. SUBJECT B"

  .         UPPE R       T3 tE A M SE.AT5             Lop          cM       >                69 6662.                         .

DATE DATE h*7*'l& 5 'O-% Dete SHT N0 0F l 2064 REV 4 73

F. 10948-113 m"

             .                                                                      to.tw BIRMINGHAM           DESIGN LoAo cos oivion             F     (O BG fR)

C N t. L t. MERto lo N At STRE ss E 5 FP os LoAo conoirsoN D THE STRESS WA% Fou tuo T o f5 tf.

                         ~ 3,3 4 / p s I.       THE A1 A X i M U M LoAo c4 Al bf JNOWl DUAL B E A M , S ti. AT     UNDER,          LoAO Cc Wo irt o N F 15 Le ss THan TH/g7 OF LOAD C o N O IT io N D, T H EftE F o R E , T H G SHELL N

M G R \ C lo ta A L S TRE SS 15 LE55 Tit A t4 LOAD COH O )TloN A. 4 C tBoc R SEAT 5 THE (n t R D E R SGATS W E RE F o vf/ P To SE A D E Qu hT @, U NOG fA L t0 A D C.oN O t Ti o N O j F O R. A MwlMuM GeAM seat LeAo CF TOToo l b 5. A c.Tl N G Oo w H , f THE GiR O e tt SEAT' AT  % W i t L. SE AM A LYZEO, A5 , A SI M ply S u p po p.T E o BEAM W LT H THE RUPTURE LoAo A< TIN A UPWARD. IT 15 A 53 9 m e ca BOLTS ARE . A D E Q u A T E. To TRA N S FER THE TOTA L VP LOAO T~ o THE 6, t R o g g seat, FOA This Get40tTsoN THs. TOTAL -

   .                      U P Lo A o       ON THE           glr DE R            SEAT 15 A rf klE O AT              ;

THE SoLTS, { 1 P = l9 0D o 16 ; R 9s o o II, - \ a a 4 v. e .g.u a ~ f I i' if

                                                                 '~

rnos tu rour. pas to%e , co s o iT t o N A l

                                                     , . c;, n,                   S,.,, = 45, s s su s.

s corr : 17 <7s iN 3 14 " Mm,: f,.u h ,2 5) ' y t.p (4 LS): 40 315 w.tk ,

   -                                                                                 M
                                                                    -fe croi9 = ~[~g ' $.        A0375[ = 8 98fso gnu       4 2 02
                                                                                     .01- : y*37E : 311(p,4.2.a290hs
                                                                    -l 4, (e,rt.) =Sa ",11,74
                                                                                                                                         )

_ l ,. s m I CHARGE NO, SUBJECT MADE BY CHKD BY gy U F PdF BEAM SEATS LDF c t2.5 > 6 fr-ff/,2. k .. DATE 5:.3.74 0 ATE

                                                                        - i . .w     o.t.           swT 8
  • or h

60 6 4 REV 4 7%

                                                                                                        =

3 c 4 .i m# 4 _5-2 5 s . t

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3Q-4 - , ;; s i5'v .

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4 s . t d . n r 8 e r o t t i i s 8 2 N o D r e t a n o e e r C Z- s c n e n N . ~ /. A a r i g n O p r O n 0 / u E r .

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a ,. l C f l a v l l a l l E r o o i d e y v t A m e t s Y i c e r F o r 8s o a y

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D r p t o s C n p d r l a S. j r e . p n E e p u b e l 9@ A I D V A Q OP r i n e g (!R z n m-E Z T N U I W 7 m d C /- 7-7 7 g s n a d t N e o t j c o N r P s A 1 e t(o o u-e P. P e o N l@ Z, b

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t e e i r K- n o

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R t a t v d[ e w M E F t n e i n o t i o r b d/, r o r r M m p 2I. g _ O m t s p gY u a . n A 4f A C c c E a I R o o D L O. / P B T r E E C I Q U I N _ E .. _ la ]}fMx86], c l 81, m + g E  : bA. m[ i t Bas G N l E or 4 N t I N no K S t 0 C 1 l A H n. @amgt i00Q 1 7_ e ,1 A u R -vn E i T gh j ;i N Ap t8 E G J

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DS.V: . .s Oak Brook Eng. ,- 3 ' Location

                                                                                                                                                            .             DOCUMENT CONTROL                                                      -

STRESSES IN TORUS CYLINDER T2.5- 04.x-2J1-BA M~0M-2204Ag DUE TO LOADINGS FROM j ,, 24" DIA. HPCJ PIPE AND 12" DIA. RCIC PIPE SEP181973 ' FERMI 2 STATUS F .

                                                           -                                                                                                             CO MI                                                    '%.              '

LTR. NO DMEDEC-M6 The torus cylinder is analytod for the thrust due to J l blowdown of'the HPCI and RCIC discharge lines. d

                                                                                                                                                                                                                                    .1 The loads for the BPCI pipe system is,a thrust of'941 kips                                                                                                                                                -T ac' ting perpendicular to the exit plane of the 45' elbow,                                                                                                                                                    1[

while for the RCIC pipe the thrust is 2.2 kips perpendicular 7 to th'e exit plane. (Refer <to DECO letter EF2-18523, dated 7-12-73). 9g  ; M. Stress intensities are determined based on a circular insert 4'-9" dia by 2" thick of HPCI pipe and 6'-2" dia. q, by 2" thick for the RCIC pipe. C

                              \                                                                                                                                                                                                 : *f The stresses in the shell due to the penetration loadings                                                                                                                                                )k       L have been calculated by CBI Computer Program 1027," Stress                                                                                                                               .
                                                                                                                                                                                                                                      .f Intensities at Loaded Attachments in Cyl'nders                                                                        i           and Epheres."                                                                      .

This program uses th.e methods and nomenclature of Welding .,7 Research Council Bullet,in #107. See' Sheet 40ACofstress e Repert for program write-up. 4

                                                                                                                                                                                                                                      .N The program p51ntout includes a tabulation of the stresses                                                                                                                                                ~f caused by the penetration loads excluding any initial stresses                                                                                                                                               c'{

present in the shell and also a tabulation of the combined effect of the penetration loads and the functional 11oads (initial stresses) . g 5 0 M I 2! DR.Y I 9@'# I OCT l'7197 m l Yi 3 g g n M. ntSH3 E  ? gz-288 sh

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l0948-070

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                                                                            ,,      oak Brook ang.                       . ..

AIJXMULBLE STRESSES The total stress intensities at a point have been compated to the following allowable stress intensities from Table I N-413 and Figure N-414 of Section III of the ASME Code: (RefertoTableonpageh). At attachment-to-shell junction Membrane - PL 1 1.5 Sm = 26250 psi .t Surface - Q 1 3 Sm = 52500 psi i At .5 dt from attachment-to-shell junction Membrane - Pm < l.1 Sm = 19250 psi Surface - Q 1 3 Sm = 52500 psi l At edge' of reinforcement Membrane - Dm i 1.1 Sm = 19250 psi - b Surface - Q < 3 Sm = 52500 psi i 1 l -l i

     ;                  TOTAL STRESS IN SUPPRESSION CHAMBER 4

The total stresses in the suppression chamber shell due to the combination of the functional loads and the specified pene-

                                                  ~

tration loadings have been determined for the accident condition. l i l rv. m , .... .. c-o.. " b. Q-h

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CHICAGO BRIDGE & IRON COMPANY Location Oak Brook Eng. l STRESSES DUE TO FUNCTIONAL LOADS l

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l i It is assumed that a membrane condition exists at the edge f of the insert and that the surface stress due to the i functional loads equals the membrane stress at that point. Stresses are taken as Sm in the circumferential direction and Sm/2 in the meridional direction. The initial. membrane ' stresses are also used at .5 E whenever. 5 M falls within the edge of reinforcing. - i At the attachment-to-shell junction, the stresses due to the - j functional loads may be assumed to equal'Sm (17500) psi) per Par. N-451(a) of pection III of the ASME Code. Surface { stresses at.this location are conservatively taken as 150% of the membrane stresses. These initial surface stresses are also used at .5 M whenever .5 M falls within the edge of reinforcing. l t I i

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                                  'P'RO'G 1D272 REV 4/73.__.__                                                                                                                _ _ _ .

EXCEPT'AS NOTED ON INPUT DATA SHT, NOTATION AGREES WITH THAT IN WRC

                                                                                                                                                                                       . - .     .      . ..L '

INPUT -

                                                                                                                                                                                                             'u KN                                   KB                 RM                                                                                        ?'

T LOC q 1.00

                                                                                ~~

1.00 183.294 0.587 0.5000 ,th

                                                         +R O                            .      TI                 TP                                 h                                              

3; i 12.000 2<000 0.0 16. 5 0 0 ._ ._. _ _ _ _ _ _ y P VL VC MC ML

                                                    -6430.                                         O.          6430.
                                                                                                                                         -342300.                                      O.
                                                                                                                                                                                               . __..J .      -
                                                                                                                                                                                                        *Ic INITI AL STRESSES NEXT TO ATTCHMNT SX(AU)              SO(AU)                      SX(CU)      SO(CU)                    SX(AM)             50(AM) f
                                                                                                                                                                                .S X ( C*. )        50(f4
      . _ . . . . . . . _            .___2_6250._                  2_6250._._                  262_50._. 26.250._ __17500. ._17500.. __17500.. _ 11).$                                                      -

INITIAL STRESSES AT LOC *SCR1(R*T)

  • SX(AU) SO(AU) SX(CU) SO(CU) SX(AM) SO(AM) SX(CM) 50(Ch

___ . _. . . _ _ 2 6 2 5_0. 6,2_50.___26_25,0f 26250. 8750. 17500. 8750. 175W) 1 INITIAL STRESSES AT EDGE OF REINF "' k' SX(AU) SO(AU) SX(CU) 50(CU) SX(AM) SO(AMi SX(CM) 50K[ 8750. __17500. 8750. 17500. 8750. 17500.. 8750. 1754W

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_ .. _ _ . _ . - . . - . . . . _ . ._. _ . . . _ - s l OpTPUT

                                                                                                                                                                                                          ' {' j 6IJL AARD COEFICIENT S                                                                                                                                                    f.
  ,                                                   NEXT TO ATTCHMNT                                AT LOC *SQRT(R*T)                         AT E DQE O F RE l_NF                                 m_t NX/P                                            48.065                         . 37.908                                        31 992                                g MX/P                                              0.104                                  0.056                                        0 015                             Y NX/MC                                          20.168                               27.415                                         27.235                          f .,

MX/MC' O.057 0.044 0.021 NX/ML 11.355 12.302 9.546 i MX/FL . 0.080 0.047 0.015 A l N0/P 35.971 20.008 13.17T

  • M0/P 0.145 0.090 0.037 ._a N0/MC 12.306 13.438 11.513 M0/MC 0.097 0.084 0.052 i.

N0/PL 35.770 28.573 22.186  ; { M0/ML 0.050 0.C33 0.010 . __ . 4 l I f-;

                                                                                                                                                                                                       .. 7 I-l
                                      , ENRICO FERM1 ATOMIC P0 DER PLAhT UNIT 82
                              ~ CBI CONTRACT f69-5562,                                                                                    .

R OUND ATTCHMT HPCI TURBINE EXHAUST ON AJ YLINORICAL VESSEL 6

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                                                       ..___           - .              . ..._.__ ._1 0.9 4.8 : 0 7.5. .._.. _ . . .                                                         . ._.
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I _. _ _.. .JUTPUT EXCLUDING INI TI AL STRESSES . l __N E X T. . T O A_T TC H M NT (U= CUTS; L= INS; M= CTRL); R0= 12.000; I (AU) (AL) -( BU) (BL) (CU) (CL) (DU) (OL). _. l SX -2050. -363 2050. -363. 7172. -1899. -3073. 1172. 50 2309. -1048. 2309. -1048.. 9075. -56_24. -4456. 3529. TAU 85. 85. -85. -85. O. O. O. O. _ __ . . S I_. 2335._'_1058. 2335. 1058. 90.75. 5624.. 4456. 3529. (AM) (BM) (Cw) (OM) SX 843. 843. 2637. -950. SO 631. 631. 1725. -463. 3  ; TAU 85. -85. O. O. t SI 873. 873. 2637. 950. AT LOCVSQRT(R*T) (U= OUTS; L= INS; M= CTRL); R0= 21.573; . i (AU) (AL) (BU) (BL) (CU) (CL) (OU) (OL) SX 1307. ._._2_2 _ _. 1 3 0 7 . _ _ 2 2.. _64._ -1492. 109. +

                            '50            1392. ._ -690.                           1392.                    -690. .                4106.

4796. . -2764.. -2011. 1383. TAU 47. 47. -47. -47. O. O. O. O. SI 1414. 719. 1414. 719. 4796. 2764. ~2011. 1383. J (AM) (BM) (CW) (OM) SX' 665. 665. 2021. -691. 50 351. 351. 1016. -314. TAU 47. -47. O. O.

                             $1                                 672.                                            672.                                      2021.                                   691.

i AT EDGE OF REINF (U=0UTS; L= INS; M= CTRL); { RO= 28.500; j (AU) (AL) (BU) (BL) (CU) (CL) ~ ~(DU) (OL) ~~ ~' j 3565 7 ~~~2T9 ~ ' ~i2166. -1393. "-5Ufi.

                                                                                                                 ~

3565. ~1913. SX 259. SO 4880. -3305. 4880. -3305. 18854 -14341. -9094. 7732.

                                                                                                                                                                                                ~
     -- - 749- 722!~~ ~f2k.                                                        If22.                      -122.                       ~ 0 ."                 0.               6.                    0.

SI 4891. 3572. 4891. 3572. 18854. 14341. 9094. 7732. (AM) (CM) (CN) (04) SX 1912. ' ~ ' Til~2~ ~ ~ ~ ~ ~ -~63 8 6. -1563. ' j SO 787. 787. 2256. . -681. j TAU 122. %T2~2.~~ 0. O. I St . 1925. 1925. 5386. 1563. I

                                                                                                                                                                                                               ~
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                              , ' $~NTIT,C FIRW1 ~4 TM I C POWEA'PLAhI~ UNIT #2                                                                                                                                                     I CBI CUNTRACT #69-5S62,                                                                                                                                                                      -

~~ RCUND ATTCHMT HPCI TURBINE EXHAU5T ON A CYETN D PTCAl-~~YE STEF ~~ ~ J _ . ., . _ . _ . _ . _ M \ 0.HT~ 07 1. gy.gg((&. g

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_ . O_UTP_UT INCt UD ING' INI TI AL . STRESSE_S .. . . . _ _ . _ . . _ _ _ _ . . _ . .. ..

       ~
                                             . N E XT' .TO .. AT T CHHb T (U=0VTS., Ly I N S ;__M= C T R L) ;.                                                            _ _.                   ._                          ..J                  b R0= 12 000; (AL)                  (BU)                   (BL)                                 (CL) jf
  ~ ~ ~ ' ~                          T (A'U)                                                                                 . (CU)                                    (DU)              (DL)' %

SX 28300. 8387.- 28300. 8387. 33422. 6851. 23177. 9922.

   -. . , _ _ _ _ _SO                                          28559.                        7702.                 28559.                  7702._ 3 5 3 2_5,. ____31_2_6_. _2_1794. - 123 79_s TAU                       85.                      85.               -85.                   -85                     O.                  O. ..             O.                   O.          'g SI             28585.                       8397.                 28585... .8397,                       3532b                  6.851 ,. 23177_n_ ._1,2219                                    )
  ~'"~                                                              ^

(AM) (BM) (CM) (DM) SX 18343. 18343. 20137. 16550.^il 50- 18131. 18131. 19225.' 17037.t il TAU

85. -85. 'O. O. -

SI 18373. 18373. 20137. ___ 17037_,.

  ~~

AT LOC *SQRT(R *TI (U=0UTS; L= INS: 'M= CTRL); N d R0= 21.573;~~ . M

     ~~

(AU)' ( A1.) (80) (BL) (CU) (CL) (DU) >(OL) . f l!

  '~~

SX 27557. -8728. 27557. -8728. 30356. -8814. 24758'. -8641 SO 27642. 8060. 27642. 8060. 31046. 5986. 24239. 10133.- ,

 ~ ~ ~ ~ ~

TAU 4.7 . 47. -47. -47. O. _0. O. 'O . / Si 27664. 16787. 27664. 16787. 31046'. 14800. 24758. IJ774. .f s (AM) (BMI (CM) (DM) /

                                               .SX                                            9415.                                        9415.                             10771.                                      8059. 'h                       I 17851.                                                                     17186.' (
   ~

iS O 17851. 18516. TAU 47. -47. O. __0.. 4 SI - 17851. 17851. 18516. 17186. P

                                                                                                                                                                                                                                         .        L AT EDGE OF RE INF (U=0UTS; L= INS; M= CTRL);                                                                       ~                      - -                              ~~
 -~

R0= 28.500;

 ^
                                                    ,                  CAU)                    (AL)                 (BU)                    (BL)                 (CU)            (CL)                  (OU)               ( DL ) : M S'X            12315.                        9009,                12315.                 _ 9009'.._       20916.                7357.                3715.          10660. V SO             22380.                     14195.                  22380.                 14195.           36354.               3159.                 8406.          25232. M O.               O.                    O.
 ~~

TAU 122. 122. -122. -122. O. SI 22381. 14198. 22381. 14198. 36354. 7357. 8406 2523f. - (AM) ~ (BN) (CM) ~ (DW)

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