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=Text=
=Text=
{{#Wiki_filter:.',-, .; : Jersey Central Power & Light Company
{{#Wiki_filter:.
,-g~'Madison Avenue at Punch Bowl Road
                , .; :                                                                 Jersey Central Power & Light Company g~'                                                                 Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 (201)455-8200 50 ->f 9' November 27, 1979 Mr. Thomas Wambach Division of Operating Reactors SEP Branch U.S. Nuclear Regulatory Commission 7920 Norfolk Ave.
.Morristown, New Jersey 07960 (201)455-8200 50 ->f 9'November 27, 1979 Mr. Thomas Wambach Division of Operating Reactors SEP Branch U.S. Nuclear Regulatory Commission 7920 Norfolk Ave.
Bethesda, Maryland 20555
Bethesda, Maryland 20555


==Dear Mr. Wambach:==
==Dear Mr. Wambach:==


In response to Mr. Jabbour's request, made early this month, I am transmitting the following materials to be used as inputs to the seismic analysis for the Oyster Creek Nuclear Generating Station.
In response to Mr. Jabbour's request, made early this month, I am transmitting the following materials to be used as inputs to the seismic analysis for the Oyster Creek Nuclear Generating Station. I am also sending copies of the same materials to Mr. S. M. Ma of EG6G by an express mail.
I am also sending copies of the same materials to Mr. S. M. Ma of EG6G by an express mail.
Drawings
Drawings 1.B 6 R 4037 (sheet 1 of 2)
: 1. B 6 R 4037 (sheet 1 of 2)                 Condensate Water Storage Tank *
Condensate Water Storage Tank
: 2. B 6 R 4037 (sheet 2 of 2)               Condensate Water Storage Tank *
* 2.B 6 R 4037 (sheet 2 of 2)
: 3. B 6 R 4503                             Turbine Building Exterior Wall Sections
Condensate Water Storage Tank
: 4. B 6 R 4504                             Office Building Exterior Wall Sections
* 3.B 6 R 4503 Turbine Building Exterior Wall Sections 4.B 6 R 4504 Office Building Exterior Wall Sections 5.B 6 R 4505 Roof Plan and Details 6.B 6 R 4506 Roofing Details 7.B 6 R 4507 Exterior Expansion Joirits 8.B 6 R 4110 Machine Shop Foundation Condensate Water Storage Tank is a vertical type with a conical roof
: 5. B 6 R 4505                             Roof Plan and Details
*having a diameter of 45 ft. and a height (cylindrical portion) of 45 ft.
: 6. B 6 R 4506                             Roofing Details
: 7. B 6 R 4507                             Exterior Expansion Joirits
: 8. B 6 R 4110                             Machine Shop Foundation Condensate Water Storage Tank is a vertical type with a conical roof having a diameter of 45 ft. and a height (cylindrical portion) of 45 ft.
Material used for the tank is Aluminum Alloy and a nominal capacity for the tank is 525,000 gallons.
Material used for the tank is Aluminum Alloy and a nominal capacity for the tank is 525,000 gallons.
r s*, e + 4"@*f un 182 p7 912o40 sse Jersey Central Power / Ught Company is a Member of the General Pubhc Utilities System  
r s*
,-.Page 2 November 27, 1979 Mr. Thomas Wambach Listed below is an itemized list of equipment weights used in developing the dynamic model of the Reactor Building.
e + 4" un            182      @*f p7 912o40 Jersey Central Power / Ught Company is a Member of the General Pubhc Utilities System sse
Equipment Elevation Weight (Kips)
 
Torus with water 6" 2550 Reactor Enclosure Drain Tank and Pumps (located directly below the reactor) 5'100 Recire. Piping and water 23'6" 135 Recire. pumps in Drywell 23'6" 220 Recire. Valves 23'6" 68 Control Rod Drive Eqpt.
Page 2 November 27, 1979 Mr. Thomas Wambach Listed below is an itemized list of equipment weights used in developing the dynamic model of the Reactor Building.
23'6" 200 Containment Spray Heat Ex.
Equipment                                           Elevation     Weight (Kips)
23'6" 16 Isolation valves 23'6" 50 Elec. Eqpt. Ins. and Air Lines 23'6" 45 HV and AC 23'6" 16 Closed Cooling Water Heat Ex.
Torus with water                                     6"       2550 Reactor Enclosure Drain Tank and Pumps (located directly below the reactor)                   5'         100 Recire. Piping and water                             23'6"         135 Recire. pumps in Drywell                             23'6"         220 Recire. Valves                                       23'6"           68 Control Rod Drive Eqpt.                               23'6"         200 Containment Spray Heat Ex.                           23'6"           16 Isolation valves                                     23'6"           50 Elec. Eqpt. Ins. and Air Lines                       23'6"           45 HV and AC                                             23'6"           16 Closed Cooling Water Heat Ex.                         51'3"           60 Regen. Clean up Heat Ex.                             51'3"           42 Non-regen. Heat Ex.                                   51'3"           23 Shut down Heat Ex.                                   51'3"           48 Recire. Piping and Water                             51'3"         135 HV and AC 6 Elec. Eqpt. 6 Inst. and Air .ines         51'3"           64 Clean up Demin. Tanks                                 75'3"           33 Clean up Filters                                     75'3"           26 HV and AC 6 Elec.Eqpt. 6 Inst. and Air Lines         75'3"           64 Spent Fuel Pool Heat Ex.                             75'3"           16 Water in Spent Fuel Stg. Pool                         80'6"       2520 Fuel and Eqpt. in Pool                               80'6"       1000 Pumps and Pipes - Misc.                               95'3"         500 HV and AC 6 Elec. Eqpt. 6 Inst. and Air Lines         95'3"           60 Emergency Condensers                                 95'3"         288 Liquid Poison Tank                                   95'3"           16 Reactor Service Platform 6 Refueling Eqpt.         119'3"           30 Shipping Cask                                       119'3"         150 Lifting Slings                                     119'3"           14 Elevator                                           119'3"           20 HV and AC 6 Elec. Eqpt. 6 Inst. and Air Lines       119'3"           64 Crane                                               Roof           195 HV and AC 6 Elec. Eqpt.                             Roof             60 Reactor Pressure Vessel                                           3021 Dry Well                                                           1800 The equipment weights used in developing the Turbine Building model are given in the " Seismic Analysis of the Turbine Building (1965) prepared by John A. Blume 6 Associates. A copy of the page with weights is attached to this letter.
51'3" 60 Regen. Clean up Heat Ex.
1473 183
51'3" 42 Non-regen. Heat Ex.
 
51'3" 23 Shut down Heat Ex.
Page 3 November 27, 1979 Mr. Thomas Wambach A shield wall spring constant   (Ki ) of 510,000 Kpf and a reactor spring constant (K 2) f 48,000 Kpf were   used in the " Seismic Analysis of the Reactor Pressure Vessel (1966) prepared by John A. Blume Associates.
51'3" 48 Recire. Piping and Water 51'3" 135 HV and AC 6 Elec. Eqpt. 6 Inst. and Air .ines 51'3" 64 Clean up Demin. Tanks 75'3" 33 Clean up Filters 75'3" 26 HV and AC 6 Elec.Eqpt. 6 Inst. and Air Lines 75'3" 64 Spent Fuel Pool Heat Ex.
Tha two springs are shown in Figure 1 (enclosed). Spring constant K2 was supplied to us by General Electric. Spring constant K1 was defined as:
75'3" 16 Water in Spent Fuel Stg. Pool 80'6" 2520 Fuel and Eqpt. in Pool 80'6" 1000 Pumps and Pipes - Misc.
K =E 1 g where:
95'3" 500 HV and AC 6 Elec. Eqpt. 6 Inst. and Air Lines 95'3" 60 Emergency Condensers 95'3" 288 Liquid Poison Tank 95'3" 16 Reactor Service Platform 6 Refueling Eqpt.
F = Arbitrary horizontal load applied at centerline of support truss (see Figure 2, enclosed).
119'3" 30 Shipping Cask 119'3" 150 Lifting Slings 119'3" 14 Elevator 119'3" 20 HV and AC 6 Elec. Eqpt. 6 Inst. and Air Lines 119'3" 64 Crane Roof 195 HV and AC 6 Elec. Eqpt.
Roof 60 Reactor Pressure Vessel 3021 Dry Well 1800 The equipment weights used in developing the Turbine Building model are given in the " Seismic Analysis of the Turbine Building (1965) prepared by John A. Blume 6 Associates. A copy of the page with weights is attached to this letter.
1473 183  
'.Page 3 November 27, 1979 Mr. Thomas Wambach A shield wall spring constant (K ) of 510,000 Kpf and a reactor i spring constant (K )
f 48,000 Kpf were used in the " Seismic Analysis of 2 the Reactor Pressure Vessel (1966) prepared by John A. Blume Associates.
Tha two springs are shown in Figure 1 (enclosed).
Spring constant K2 was supplied to us by General Electric. Spring constant K1 was defined as:
K =E 1 g where: F = Arbitrary horizontal load applied at centerline of support truss (see Figure 2, enclosed).
8 = Horizontal displacement at point of application of force F (see Fig. 2) .
8 = Horizontal displacement at point of application of force F (see Fig. 2) .
The shear area used in the Reactor Building model is equal to 0.7 time. the concrete gross area (A ) given in sheet 1 of the " Seismic c Analysis of the Reactor Building " (1965) orepared by John A. Blume 6 Associates. We have not been able to identify the shear area used in the Turbine Building model.
The shear area used in the Reactor Building model is equal to 0.7 time. the concrete gross area (A c) given in sheet 1 of the " Seismic Analysis of the Reactor Building " (1965) orepared by John A. Blume 6 Associates. We have not been able to identify the shear area used in the Turbine Building model.
Very '.ruly yours, CQ<J YOSHITO NAGAI[ g2 e sw cc: S. M. Ma - EG6G T. E. Tipton J. Knubel W. R. Schmidt - M.P.R.
Very '.ruly yours, CQ           <J YOSHITO NAGAI[ g2 e sw cc:   S. M. Ma - EG6G T. E. Tipton J. Knubel W. R. Schmidt - M.P.R.
1473 184  
1473 184
.JOHN A. ELU:JE AND ASSOCIATES, ENflNEERS
 
_ JERSEY CENTRAL NUCLEAR REACTo2 PEOJECT EARTHQUAKE ANALYSIS TURBINE BU/LDING JVE/GH TS -----
JOHN A. ELU:JE AND ASSOCIATES, ENflNEERS
-:: ;--. ' '..JUEIGHT /@ EL. 4(o'- fo " 14/ALL S BELOW=9,060 K/5EAMS . @ 46 '- 6 "_/ 0 61=i. . _ _SLAS S 4 6 '- & ''
_ JERSEY CENTRAL NUCLEAR REACTo2 PEOJECT EARTHQUAKE ANALYSIS TURBINE BU/LDING JVE/GH TS -----        -
I4,/9/=WAL L S FROM C& '- 6 " TO 74 '- O " 2,060=SL A B $ 63 '- 9 " 4/S=SLAB@74 ' - 0 "=369 SEAMS @63 ' - 9 "=/55 BEAM S G'74 ' - O "=9/L/VE LOADS@ d& ' - 6 "= /2, //O P/ PES @ 46 '- 6 " 2,826=S TEEt. FRAMING A B OVE 46 '- 6" (ESTIMATED) 2,200=TOTA L WE/G HT @ 46 '- 4"= 44,638 K J+'E/G H T 2@ EL . 23 '- fo " 9,922 K WALLS B GL OW
JUEIGHT / @ EL. 4(o'- fo "
=2/4 COL. BEL OW
14/ALL S     BELOW                               =   9,060 K
=8,309 Wall 3 ABOYE=69//3EAMS=SL A S - @ 23'- fe "~4 580=SLAB@ SG '-O" 2,2 /6=SLAB@ 2 7'-O" 280=L/VE L OA D S---
  /5EAMS . @ 46 '- 6 "           . . _ _        _
--- - - -= fo,386 S44 P/ PES=TOTA L WE/GHT @ 23 '- 6 " -
                                                  =    /i 0 61 SLAS S 4 6 '- & ''                             =  I4,/9/
= 35,823 K i I 1473 18,.3-.es e e*SHEET /  
WAL L S FROM             C& '- 6 " TO 74 '- O " =  2,060 SL A B $ 63 '- 9 "                             =    4/S SLAB       @ 74 ' - 0 "                         =     369 SEAMS @             63 ' - 9 "                   =     /55 BEAM S G '74 ' - O "                             =       9/
.E L . 1 O 'S'
L/VE LOADS           @ d& ' - 6 "               = /2, //O P/ PES @ 46 '- 6 "                               =  2,826 S TEEt. FRAMING A B OVE 46 '- 6" (ESTIMATED)                                     =  2,200 TOTA L WE/G HT @ 46 '- 4"                       = 44,638 K J+'E/G H T 2 @ EL . 23 '- fo "
~1 */3'L"..i K2 E L. 8 2' ct" 6 M'" 3 M-.EL. 84.*- 7."$s.': x2/.,.:: ,...'M.-,^N Reactor_-::--\ Reactor- shell
WALLS B GL OW                                   =   9,922 K COL. BEL OW                                     =       2/4 Wall 3 ABOYE                                     = 8,309
.._.I l'- 9 1.D.
  /3EAMS                                           =     69/
.;4 hick.iese 1%" Preeeure::-19'-O'A'O.D.
SL A S - @ 23'- fe "                           =  ~4 580 SLAB     @ SG '-O"                               =  2,2 /6 SLAB     @ 2 7'-O"                               =
ye.,ee,lj=(6 tee.1 Ghell) '
280 L/VE     L OA D S---     --         - - - -   = fo,386 P/ PES                                           =     S44 TOTA L WE/GHT @ 23 '- 6 " -                     = 35,823 K i   I 18,.3 1473 es e e
.Ahield q1'. 0"'.'-l(o'-10" 1.D.,i 15'- 0"_-::\)<e'-IVt" + hick.
* SHEET /
A.-t<..-:.y EL. 3 8'-5 '
 
F-6-. . 't G '- o ' O . D .
E L . 1 O 'S' ~1 */3'L" i                                                                                                                             '
'''<.r.t .'*16'-o" I* D-
K2 E L. 8 2' ct" 6 M                                                                                     3 x2 EL. 84.*- 7."                     $s             .,
..Concre e." m n'":.-Pedes +a f
                                                                                                                            .': M   /
: '*4'- o..--7.16'- cf A'-o'''-\...4 ,'s:*......,'j *. , EL.10' ~6"-,. .,-..FIGURE 1 REACTOR PRESSURE VESSEL, JEr.SEY CENTRAL NUCLEAR POWER PLANT
                                                                                                    .-               ,   M^N
..D~#]D D W}hl r" 1_e w.N.}..- - ---.a_'.._.i...,..~ 4'M$$'-wwn.mMis @: M.W: .
                                                                                                                                      \ Reactor- shell Reactor I l'- 9 1.D.             .;           4 hick.iese 1%"
.-- - --. .~. , y,x.w-w.r.f . %m
Preeeure                                               ::
,...-W ls ) E 3 ' $ d W . W i$. @. ,.s.A 9 d, u .N
ye.,ee,l                                                j          =
.-e:-8--.. e y e . ;
                                                                                              -19'-O'A'O.D.
n.,:.? . :, ,.,.;... . 9 . . : . .. .
q1'. 0"                '.
.4..3..-,.. ,..;..)415\86-.. a. ....q.... ; .=. ---,-,i. . .... .. . ... . , .--,-......
(6 tee.1 Ghell) '                                       .
...E q_ ,'---y/l%,)'.,!!n:-4,.1-\;' . ./,'->y'>>gg-A s c- Tanss Meusta.
Ahield l(o'-10" 1.D.                                           ,i                 15'- 0"               -
Deflection (6) of the Ring in the Direction of Applied Load
IVt" + hick.                                           A
.FIGURE 2 SUPPORT TRUSS STIFFNESS, REACTOR PRESSURE VESSEL, JERSEY CENTRAL NUCLEAR POWER PLANT u 2 0\413\81. . -Ma 9/}}
                                                                                        \  t                   <
                                                                                                                  )      <e'--
                                                                              .-                                         :.     y EL. 3 8'-5 '                                   -
F       -6
                                                                                <.                                       . 'r            t G '- o ' O . D .
16'-o" I* D-
          .                                                                    ..                                   t .'* "
Concre e                                   m n'":
Pedes +a f 4'- o. 7.
                                                                              \.
16'- cf           ''
A'-o' 4 ,'                                   s:
EL.10' ~6"                               ,     ..
                                                                                          ,                     j *. ,  -
FIGURE 1 REACTOR PRESSURE VESSEL, JEr.SEY CENTRAL NUCLEAR POWER PLANT D~#]D D     W } hl                   r 1_e w.N               .
                                                            .}..                     a
                                                                                                                                                        '.._.i.
. .~. , y,x.w-w.r.f . %m                                                                      - .
~ 4'               M$$'-wwn.mMis e@: M.W: .:                                                                                        -
W
.. e yls 8e . ); E 3 ' $ d W . W i$. @. ,.s.A 9 d, u .N n.,:.     ? . :, ,                 ,.;
        . . 9 . . : . .. .             .4..                 ,.     . ,.
                                                                                                                                                              )415 \86 3..-
                                                . ; .=. -
    .. a. ..
                      ..q..     . . .   .
                                                                                                                                                  ,i
 
E q              _ ,
                                                      -y         '
                              /
l                         %,)
n:
4,                   .
1
                          \                           ;
                            '..                     /
                                  ->           y'
                      >>                   gg-         A s
c
                                                  - Tanss Meusta.
Deflection (6) of the Ring in the Direction of Applied Load FIGURE 2 SUPPORT TRUSS STIFFNESS, REACTOR PRESSURE VESSEL, JERSEY CENTRAL NUCLEAR POWER PLANT u       2 0
                                                                    \413 \81 Ma 9
                                                                  /}}

Latest revision as of 12:59, 22 February 2020

Forwards Drawings 4037,Sheets 1 & 2,4503-4507 & 4110 for Input to Seismic Analysis.Lists Equipment Weights Used in Developing Dynamic Model of Reactor Bldg.Equipment Weights Used in Turbine Bldg Model Encl.W/O Drawings
ML19210E338
Person / Time
Site: Oyster Creek
Issue date: 11/27/1979
From: Nagai Y
JERSEY CENTRAL POWER & LIGHT CO.
To: Wambach T
Office of Nuclear Reactor Regulation
References
TASK-03-06, TASK-3-6, TASK-RR NUDOCS 7912040358
Download: ML19210E338 (6)
v • d • e


Text

.

, .; : Jersey Central Power & Light Company g~' Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 (201)455-8200 50 ->f 9' November 27, 1979 Mr. Thomas Wambach Division of Operating Reactors SEP Branch U.S. Nuclear Regulatory Commission 7920 Norfolk Ave.

Bethesda, Maryland 20555

Dear Mr. Wambach:

In response to Mr. Jabbour's request, made early this month, I am transmitting the following materials to be used as inputs to the seismic analysis for the Oyster Creek Nuclear Generating Station. I am also sending copies of the same materials to Mr. S. M. Ma of EG6G by an express mail.

Drawings

1. B 6 R 4037 (sheet 1 of 2) Condensate Water Storage Tank *
2. B 6 R 4037 (sheet 2 of 2) Condensate Water Storage Tank *
3. B 6 R 4503 Turbine Building Exterior Wall Sections
4. B 6 R 4504 Office Building Exterior Wall Sections
5. B 6 R 4505 Roof Plan and Details
6. B 6 R 4506 Roofing Details
7. B 6 R 4507 Exterior Expansion Joirits
8. B 6 R 4110 Machine Shop Foundation Condensate Water Storage Tank is a vertical type with a conical roof having a diameter of 45 ft. and a height (cylindrical portion) of 45 ft.

Material used for the tank is Aluminum Alloy and a nominal capacity for the tank is 525,000 gallons.

r s*

e + 4" un 182 @*f p7 912o40 Jersey Central Power / Ught Company is a Member of the General Pubhc Utilities System sse

Page 2 November 27, 1979 Mr. Thomas Wambach Listed below is an itemized list of equipment weights used in developing the dynamic model of the Reactor Building.

Equipment Elevation Weight (Kips)

Torus with water 6" 2550 Reactor Enclosure Drain Tank and Pumps (located directly below the reactor) 5' 100 Recire. Piping and water 23'6" 135 Recire. pumps in Drywell 23'6" 220 Recire. Valves 23'6" 68 Control Rod Drive Eqpt. 23'6" 200 Containment Spray Heat Ex. 23'6" 16 Isolation valves 23'6" 50 Elec. Eqpt. Ins. and Air Lines 23'6" 45 HV and AC 23'6" 16 Closed Cooling Water Heat Ex. 51'3" 60 Regen. Clean up Heat Ex. 51'3" 42 Non-regen. Heat Ex. 51'3" 23 Shut down Heat Ex. 51'3" 48 Recire. Piping and Water 51'3" 135 HV and AC 6 Elec. Eqpt. 6 Inst. and Air .ines 51'3" 64 Clean up Demin. Tanks 75'3" 33 Clean up Filters 75'3" 26 HV and AC 6 Elec.Eqpt. 6 Inst. and Air Lines 75'3" 64 Spent Fuel Pool Heat Ex. 75'3" 16 Water in Spent Fuel Stg. Pool 80'6" 2520 Fuel and Eqpt. in Pool 80'6" 1000 Pumps and Pipes - Misc. 95'3" 500 HV and AC 6 Elec. Eqpt. 6 Inst. and Air Lines 95'3" 60 Emergency Condensers 95'3" 288 Liquid Poison Tank 95'3" 16 Reactor Service Platform 6 Refueling Eqpt. 119'3" 30 Shipping Cask 119'3" 150 Lifting Slings 119'3" 14 Elevator 119'3" 20 HV and AC 6 Elec. Eqpt. 6 Inst. and Air Lines 119'3" 64 Crane Roof 195 HV and AC 6 Elec. Eqpt. Roof 60 Reactor Pressure Vessel 3021 Dry Well 1800 The equipment weights used in developing the Turbine Building model are given in the " Seismic Analysis of the Turbine Building (1965) prepared by John A. Blume 6 Associates. A copy of the page with weights is attached to this letter.

1473 183

Page 3 November 27, 1979 Mr. Thomas Wambach A shield wall spring constant (Ki ) of 510,000 Kpf and a reactor spring constant (K 2) f 48,000 Kpf were used in the " Seismic Analysis of the Reactor Pressure Vessel (1966) prepared by John A. Blume Associates.

Tha two springs are shown in Figure 1 (enclosed). Spring constant K2 was supplied to us by General Electric. Spring constant K1 was defined as:

K =E 1 g where:

F = Arbitrary horizontal load applied at centerline of support truss (see Figure 2, enclosed).

8 = Horizontal displacement at point of application of force F (see Fig. 2) .

The shear area used in the Reactor Building model is equal to 0.7 time. the concrete gross area (A c) given in sheet 1 of the " Seismic Analysis of the Reactor Building " (1965) orepared by John A. Blume 6 Associates. We have not been able to identify the shear area used in the Turbine Building model.

Very '.ruly yours, CQ <J YOSHITO NAGAI[ g2 e sw cc: S. M. Ma - EG6G T. E. Tipton J. Knubel W. R. Schmidt - M.P.R.

1473 184

JOHN A. ELU:JE AND ASSOCIATES, ENflNEERS

_ JERSEY CENTRAL NUCLEAR REACTo2 PEOJECT EARTHQUAKE ANALYSIS TURBINE BU/LDING JVE/GH TS ----- -

JUEIGHT / @ EL. 4(o'- fo "

14/ALL S BELOW = 9,060 K

/5EAMS . @ 46 '- 6 " . . _ _ _

= /i 0 61 SLAS S 4 6 '- & = I4,/9/

WAL L S FROM C& '- 6 " TO 74 '- O " = 2,060 SL A B $ 63 '- 9 " = 4/S SLAB @ 74 ' - 0 " = 369 SEAMS @ 63 ' - 9 " = /55 BEAM S G '74 ' - O " = 9/

L/VE LOADS @ d& ' - 6 " = /2, //O P/ PES @ 46 '- 6 " = 2,826 S TEEt. FRAMING A B OVE 46 '- 6" (ESTIMATED) = 2,200 TOTA L WE/G HT @ 46 '- 4" = 44,638 K J+'E/G H T 2 @ EL . 23 '- fo "

WALLS B GL OW = 9,922 K COL. BEL OW = 2/4 Wall 3 ABOYE = 8,309

/3EAMS = 69/

SL A S - @ 23'- fe " = ~4 580 SLAB @ SG '-O" = 2,2 /6 SLAB @ 2 7'-O" =

280 L/VE L OA D S--- -- - - - - = fo,386 P/ PES = S44 TOTA L WE/GHT @ 23 '- 6 " - = 35,823 K i I 18,.3 1473 es e e

  • SHEET /

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Deflection (6) of the Ring in the Direction of Applied Load FIGURE 2 SUPPORT TRUSS STIFFNESS, REACTOR PRESSURE VESSEL, JERSEY CENTRAL NUCLEAR POWER PLANT u 2 0

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