ML17212A072

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Final Safety Analysis Report, Rev. 30, Chapter 3, Figures 3A.1.2-1 - 3.9N-12
ML17212A072
Person / Time
Site: Millstone Dominion icon.png
Issue date: 06/29/2017
From:
Dominion Nuclear Connecticut
To:
Office of Nuclear Reactor Regulation
Shared Package
ML17212A038 List:
References
17-208
Download: ML17212A072 (114)


Text

z 200 L-

...I..-

...I..-_---J._....,I"",I",__--..r (f) lJJ

r:

u Z

150 100 50 o

5 10 P : 75 psi 15 INCH ES 20 25 FIG UR E 3A.1. 2-1 ONE HUNDRED-ELEMENT IDEALIZATION OF THIN-WALL CYLINDER MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT L..-

..J

z r

1.0 0.5

~

I 6

II 16 21 CD

2 7

12 17 22

3 8

13 18 23 0

0

@)

4 9

14 19 24 8)

5 1O 15 20 25 o

o 1.0 0.5 FIGURE 3A 1.4-1 ELEMENT PLOT MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

25 2.0 1.5 1.0 IJJI 0

= e, 0.5

~

16 ELEMENT SOLUTION

-LOVE V = 0.25 Pr = Po (cos 8 + cos 28)

T re = Po sinS o

0.2 0.4 r

a 0.6 0.8 1.0 FIGURE 3A 1.4-2 HARMONIC AXISYMMETRIC PLAIN STRAIN MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

z COOLANT 1 RADIAL AND AXIAL GRID LINES EQUALLY SPACED AT 1-INCH INTERVALS R

t2.0

.~

COOLANT

3 v

r~

0u I

I N

~r ou 24.0 0.0

/0.0 GEOMETRIC CENTER I

OF CYLINDER I

I

~

FIGURE 3A.1. 5-1 TAC 2D SAMPLE PROBLEM THERMAL MODEL MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

1.6

1. 4 1.2 1.0 0.8 0.6 0.4 0.2 a

900 10 0 800 700 I

I u,

I 0

I W

I a::

600 I

)

r =0 *5 INCH i

~

Z =0.5 INCH I

~

a::w 500 1-a.

i

E j

lJJ 400 j

LEGEND :

300 SER IES SOLUTION 0

TAC 20 RESULTS 200 TIME-HOURS FIG U RE 3A I.5 - 2 TRANSIENT TEMPERATURES IN A RIGHT CIRCULAR CYLINOER COMPARISON OF TAe 20 RESULTS WITH SERIES SOLUTION MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

...,....,~~,....,.-,....,.-.,-,- -

EL.

00 EL.

60.0 6

2 EL.

48 *0 3

EL.

36.0

~

4 EL.

24.0

~

Y EL

  • 12.0

~---x z

C==>' MASS NUMBERS 6.: MEMBER NUMBERS FIGURE 3A.1.6-1 STRUCTURAL MODEL MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

J STRUCTURAL LUMPED MASS MODEL EL. 0.0 FT EL. 1150 FT.

II

£1-,

\\

NOTE :

NOT TO SCALE FIGURE 3A.1.7-1 FINITE ELEMENT GRID FOR PLAXLY - FLUSH COMPARISON MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT


~

0.10 0.20 t----fMi~_+----_+_----~----I__---__+----__j 1.00 090 0.80 0.70 C'

Z 0.60 0

~<t 0.50 0:::

W

.....J I

w uu I

<t i

I I

I\\.

i 0'----~_

__L___'____

___J____1.__

__.L..__.1...._.._......1.__

__..L__...L.__

__J o

0.10 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 1.10 1.20 PERIOD-SECONDS LEGEND PLAXLY RESULTS x x x FLUSH RESULTS FIGURE 3A.1. 7-2 HORIZONTAL AMPLIFIED RESPONSE SPECTRA AT TOP MASS IN BEAM STRUCTURE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

/

EFFECT IVE LTM AREA :-2,400 sa FT W: 18 FT, H: 133FT

( 150, 18) 15 0 1

X

....--O-----------------~~...J

( 150,0) z.

TURBINE LTM

TARGET, 2,400 SO FT

~

~ -.-::-:....----

.--..-.---'--.. 8

~-URBINE AXIS NOTE BUSH 1973 FIGURE 3A.2.3-1 TARGET FOR LOW TRAJECTORY MISSILE MILLSTONE NUCLEAR POWER STATION UNIT 3

FINAL SAFETY ANALYSIS REPORT

~J

_.~-----------------

0189" t /06526"

~07558" y

To 0564" z

x FIGURE 3A.3-1 MATHEMATICAL MODEL FOR FLEXIBILITY ANALYSIS VERIFICATION MILLSTONE NUCLEAR POWER STATION UN IT 3 FINAL SAFETY ANALYSIS REPORT 1...-

._-- - ~.

FIGURE 3A.3-2 NUPIPE PROGRAM FORCE TIME HISTORY VERIFICATION MILLSTONE NUCLEAR POWER STATION UNIT 3 FI NAL SAFETY ANALYS I S REPORT

"PcttA IIN(j CUNOI I IUNS THERMAL ANCHOR MOVEMENT PRESSURE TEMPERATURf OPER FOR OPERATING MODES.

PIPE MODE (PS I)

Of

\\ ANO i 6"

SEISM IC AN CHOR 200 400 Y

00" MOVEMENT SAME I

4" IRECTIONS 1y.."

II

,,~,. AORBOTH 0 Ela,Ta -abTb/ AT 15 :440 PSI 6"

200 700 0 14 '"

0 141 2

4" 0

70 I ~*

200 700 a 6. T, : 00002 a 6. Tz : 0.0004 'H/ FT 6"

700 70 z

x 3

4 "

700 70 I ~.."

700 70 VALVE WEIGHT 60~

/500# FORCE 8

1V4" STANDARD SMLS.

SOCKET WELDED 6" STANDARD, SMLS FIGUR E 3 f\\. 3 ~ 3 MATHEMATICAL MODEL FOR 4" STANDARD LONG I CLASS I STRESS VERIFICATION WELD, FLUSH MILLSTONE NUCLEAR POWER SlAT ION ELASTO JOINT UNIT 3 FINAL SAFETY ANALYSIS REPORT

\\,

2 1. 5 "

12,000 LB DISCHARGE THRUST FORCE

--+

8.75" 0.0 x6"1. D.NOZZLE 1~* PAD (REINFORCED CONDITION) 34.125" 0.0 x I Y16" THICK RUN PIPE NOTE VALVE WEIGHT: 660 LBS CG: Ysx78:.26 VALVE LENGTH: 78",

VALVE OPENING TIME: 0 O!S SECOND (ASSUME)

NOZZLE LENGTH :6" NOZZLE 0.0. : 8 7 5" 10 :6.0 "

VALVE SET PRESSURE : 850 PSi FIGURE 3A.3-4 TEST PROBLEM-SAVAL MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

Ai Ae L

GAS I

I P,

Po

~

L

  • 1 CLOSED OPEN END END CASE (A)

FOR COMPARISON WITH ANALYTICAL RESULTS.

INITIAL CONDITIONS =

P,/Po =4.72.

0 0/ 0, =0.60 DIMENSIONS =

AeiAI =0.6, L = PIPE LENGTH SPECIFIC HEAT RATIO =

r =Cp/Cv =1.4 P =PRESSURE, a = SOUND VELOCITY, A =FLOW AREA FIGURE 3A.3 - 5 SUDDEN DISCHARGE OF A GAS FROM A PIPE LINE THROUGH A NOZZLE MILLSTONE NUCLEAR POWER STATION UNIT 3

FINAL SAFETY ANALYSIS REPORT

Ai Ae =0.25Aj

/

GAS I

I

..-----------5FT-----------,

OPEN END CASE (B) FOR COMPARISON WITH EXPERIMENTAL DATA AND HAND CALCULATION.

PRESSURE = Po =14.7 psia, PI = 14.710.229 = 64.2 psia AREA = Ai = : (0.25)2 = 0.0491 't 2, Ae = 0.25Aj =

0.0123ft 2 GAS CONSTANT = R = 53.35 ft - Ibf IlboR TEMPERATURE = To =79 0 F =539 0 R, T. = To DENSITY = P, = ~ =O.07361b/ft 3 P = -!L. =0.3215 Ib/ft 3 o

RTo I

RT 1 I

FIGURE 3A.3-6 SUDDEN DISCHARGE OF A GAS FROM A PIPE LI N E THROUGH A NOZZLE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

. -------_._-_.__..._-_._------~

~.OO r----,...--".,_-........------------------------------,

4.00 0

Q.

Q.

0 Z

W 0

3.00 w

(J) 0

..J U

r-et 2.00 w

0::

~w 0::

a..

1.00 8.00 7.00 6.00 3.00 4.00 5.00 TIME (o,f/L) 2.00 1.00 0.00 L

..L

--L

---L

---.l_

-'-_L-

..l-

-l..-

--.l 0.00 (CASE A )

ST EHAM ANALYTICAL SOLUTION ( re f 12 £. 13 )

FIGURE 3A.3-7 COMPARISON OF PRESSURE RESPONSE AT THE CLOSED END MILLSTONE NUCLEAR POWER STATION UNI T 3 FINAL SAFETY ANALYSIS REPORT L

\\oor-------------------------------_--,

3.20 0.0

0.

0 Z

W Z w a..

2.40 0

r

~-

w a::

(f)

(f) 1.60 w

0:

a..

080 L-----...1.--------!-----~------J-----::_L_:----~_::_::_---~::":_:__---_:_'

000 1.00 2.00 3.00 5.00 600 7.00 8.00 (CASE A)

FIGURE 3A.3 - 8 STEHAM COMPARISON OF PRESSURE RESPONSE ANALYTICAL Sa...UTION AT THE OPEN END (REF 12 & 13)

MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

--~._--------------_

..._-_._.~--------------------

I

_ \\ \\

100

a.
a.

0 Z

W O~

0 w U>

0 -J

<..)

~

w a::

0.60

J U>

U>

W a::

0 040 020 L

-L

.-L

~:__---~;:;_---__;~-----:r:.

0.00 1.00 200 3.00 4.00 5.00 6.00 700 TIME (0\\ r/L)

FIGURE 3A.3-9 COMPARI SON OF PRESSURE RESPONSES BY (CASE B)

STEHAM e, EXPERIMENT STEHAM MILLSTONE NUCLEAR POWER STATION ANALYTICAL SOLUTION UN IT 3 (REF 12 £, 13)

FINAL SAFETY ANALYSIS REPORT

.J

626.64 1

o o

1,500'-18" ° f =0.02 Q =7.'iI:jcfs ---.

v=3,750 ft /sec o

2,200'- 30"0, f =0.04 2 000' - 36"0 f =0.024 Q = 17.96 cts --..

r;";\\

Q = 30cfs -...

v = 3,140 ft/sec

~

v = 3,300 ft /Iec FIGURE 3A.3-IO HYDRAULIC NETWORK FOR VERIFICATION PROBLEM MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

LEGEND 0

PIPE NUMBER PIPE JUNCTION 5*

NODE NUMBER

---{X]

VALVE o

2 3

4 CD 5

2 t--:

3 0

l 4

0 CD 5

7 3

4 5

6 7

8 6 2

3 4

5 6

I Q

FIGURE 3A.3-11 HYDRAULIC NETWORK FOR WATHAM VERIFICATION MILLSTONE NUCLEAR POWER STATION UNIT 3

FINAL SAFETY ANALYSIS REPORT

~ _

0

\\~~r'-""""'-----""""--------------------------------'

18 17 16 15 14 13 12

\\1 B

9 10 TIME (SECONDS) 4

3 2

20QL.-_..J-_-.L__.J..-_--L.__.L--_-.l..-_--I__J-_----L__.L-_-.l..-_----lL.-_....I.-_---L__.L-_--J...__1..-_-J o

LEGEND

-'-' WATHAM

--- STREETER (REf. 48J


WHAM (REF. 491 FIGURE 3A.3-12 HEAD-VERSUS-TIME PLOT FOR JUNCTION J MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

--_..-. ~..-_.*. """'-~'.~.-~.....-----_._.,.-

--'._.._~_..

'.._~..~-----_

19 18 17 16

~f\\

I ~

I I I

I I

I I \\

I I~

14 FIGURE 3A.3-13 HEAD-VERSUS-TI ME PLOT AT VALV E MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT 13 12 I

I I,

,I (14' j.

I '\\' \\','

\\

/!

I J VV

,,R I

,!\\ I

'1111

~

8 9

' 0 11 TIME (SECONDS)

I I

I 'I'If

~

I \\\\

\\.

\\

I *

\\\\

I.

I, I

III WI II I

lu :

~V\\r 6

f L,I

III,

~

n 2

W...TH.....

STREE TER (REF 481 WH.....

(REf HI 400 200 1000 12 0 0 LEGEND

~----------------~

36

-z x

fliF ES:

= ~NOTES MASS POINTS

~-

= noo FT.

-~

= START ANGLE=45"

, J

= 'K.. COORDINATE OF ORIGIN OF ARC = 0.0 FT.

~ ::

= 7L COORDINATE OF ORIGIN OF ARC = 0.0 FT.

= fA.O IN.

= IlNCLUDE ANGLE BE TWEEN NODES = 6.923*

Hr;'_E = rHO. OF INCLUDED ANGLES I N ARC = 26 FIGURE 3A.3.14 DESIGN INPUT TO A PROBLEM MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT NOVEMBER 198 7

80.00 N

0......

60.00 Lf) en

-.J w

U 0::::

40.00 0

LL 20.00 YMAX = 9826.92 AT TIME 0.012 YMIN = 0.00 AT TIME 0.000 0.00 0.00 0.04 0.08 0.12 0.16 0.20 0.24 0.28 0.32 0.36 FIGURE 3A3.15 PIPE 1 SEGMENT 1

FORCE-TIME HISTORY MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT NOVEMBER 1987

IS"

............+-------8.5"--

4"-----++--- 4" ----1 BUFFER MATERIAL

. __.__ ~~__ ---1.

~~__+__

/

1.66" OIDIA.

1.526" OIDIA.

1.66" OIDIA.

I 1.38" I/DIA NOTES NOT DRAWN TO SCALE.

PIPE MATERIAL: A 106 STEEL.

FIGURE 3A.2.1I-1 CANTILEVER PIPE USED IN MIT EXPERIMENT MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

100.0 90.0 80.0 70.0 60.0 50.0

~O.O 30.0

20. 0 0

Z 10.0 0w 9.0 w

8.0 if) 7.0 If) 6.0 w

5.0 rw Z

~.O 3.0

'>-- 2.0 w

0

...J W

1. 0 0.9 O.B O. 7 0.6 0.5 o.~

0. 3 0.2 0.1 FREQUENCY (CPSI FIGURE 3.78-1 HORIZONTAL DESIGN RESPONSE SPECTRA 0.17 G SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

100.0 90.0 80.0 70.0 60.0 50.0

~O.O 30.0 20.0 a z 10.0 0

9.0 u

u.J 6.0 If) 7.0 If) 6.0 u.J 5.0 I

U Z

~.O 3.0

  • . 0 u

0

..J u.J 1.0 0.9 o.e 0.7 0.6 0.5 o.~

0.3 O.~

0.1 FREQUENCY (CPS)

FIGURE 3.78-2 HORIZONTAL DESIGN RESPONSE SPECTRA 0.09 G OBE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

1"11111111"111111 11 111111111111 11 I I I I I I 1 1 I I

11111111111""1" 11111111 111 111111 11I I I I 1 I I I

1111111111111"1"11111111 i11111 11 111I I I I I I I I

10.00 5.004.00 3.00 2.00 1.00 0.500. 40 0.30 0.20 0.\\0 0.05 0.04 0.0 3 0.02 0.0 \\

10 0. 0 r--~~~~....."....-rr--"'~"""""'""","""T""">,........,...-r-~--'~"";-'~--"'r-""'::>r"<~~,...,.....""""",""r-r---"':---"T7",,=,,,,,"7""""Ir-1~~~7"'<"1~"""7I""-r-1 90.0 80.0 70.0 60.0 SO. 0 40.0 30.0 20.0 100. 0 90.0 BO. 0 70. 0 60.0 50.0 40.0 30. 0 20.0

10. 0
10. 0 9.0 9.0 B.0 B. 0 7.0
7. 0 6.0 6.0
5. 0 5.0 400 3.0
3. 0 2.0
2. 0 u

W U')

Z 1.0 1. 0 0.9 0.9

~

o. B
o. B I-0.7 0.7 u

0.6 0.6 0

..J 0.5 w

0.5 0.4

0. 4 0.3 0. 3 0*2 0.2 0.10 0.\\

0.0 9 0.09 o.OB

o. OB 0.0 7 0.07 0. 06 0. 06
0. 05 0.05 0.04
0. 0 4 0.03 o.O J 0.02 C. 0 2 0.0 1 0.\\

MI LLS 3

\\. 0 ERRT HQURKE FREQUENCY (CPS )

10. 0 FIGURE 3.78-3 HORIZONTAL TIME HISTORY RESPONSE SPECTRA 0.5 PERCENT DAMPING VALUE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

11111111111111111111111111""1111111111 II I 1 1 1111111111111111"1111111111111111111111 II 1 1 I 1111111111111111111111111111111111111111 II I I I 10.00 5.004.00 l.OO 2.00 1.00 0.500.40 0.30 0.20 O*tO 0.05 0.04 0.03 0.02 0.01 100.0 PERIOD (SECS) 100.0 90*0 90.0 80.0 80.0

~IO.0 70.0 60.0 60.0 50.0 50.0

~o.0 40*0 30*0 30*0 20.0 20.0

\\0.0 10*0 9*0 9.0 8.0 8.0 7.0 7.0 6.0 6.0 5.0 5.0

  • .0

'-Jl**

3.0 3*0 2.0 2.0 u

w

(/)

Z 1*0 1.0 0.9 0.9 0.8 0.8 e

0.7 0.7 U

0*6 0.6 0

W 0.5 0.5 0*'

0.'

0.3 0.3 0.2 0.2 0.10 0.1 0.09 0.09 0.08 0,08 0.01 0.07 0.06 0.06 0.05 0.05 0.04 0.0-4 0.03 0*03 0.02 0.02 0.01 0.01 0.1 1.0 to.0 100.0 MILLS 3 ERRTHQURKE FREQUENCY (CPSI FIGURE 3.78-4 HORIZONTAL TIME HISTORY RESPONSE SPECTRA 1.0 PERCENT DAMPI NG VALUE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

1111111111111111""11 11 1111111111 111 11 1 I I I 1 1

111"1"11 111111111111111 11 1111111111 11 1I I I I I

111111111111111111 1111111 1"111 11 11111 11 I' I,

, I 10.0 0 5.00 * *00 3.00 2.00

1. 00 0.500.'0 0.'0 0.20 0.1 0 0.050.0' 0.0' 0.02 0.0 1 100. 0 r---.---~~~~-rx-"""""'~~~""""T-r-...---r->..."r.""""':"""':-''--.:::>r~~'CO""-;.r-'''--:--T7"-.:::>r7""""':~r:--,=""",,,:-v.....,.....:-r-,........-r...,

90*0 80.0 70.0 60.0 50. 0 40.0 30.0 20.0

\\00.0 90.0 80.0 70.0 60.0 50. 0 40.0 30. 0 20. 0 10.0 10. 0 9.0 9.0

e. 0 8.0 7.0 7.0 6.0 6.0 5.0 5.0 4.0 4.0 3.0 3.0
2. 0 2.0 uw (j)

Z

\\.0 1.0 0.9 0.9

)0-0 *8 0.8 f-0.7 0.7 U

0.6 0.6 0

--J W

o.S 0.5 0.4 0.4 0.3 0.3 0.2 0.2 0. 10 0 01 0*09 0.09 0.08 0.06 0. 0 7 0.07 0.0 6 0.06 o.OS a.OS 0.0.

0.04 0.03 0.03 0.02 0.02 0.0 \\

0. \\

1. 0 10.0 MILLS 3 -

ERRTHQURKE FREQUENCY

( CPS 1 FIGURE 3.78-5 HORIZONTAL TIME HISTORY RESPONSE SPECTRA 2.0 PERCENT DAMPING VALUE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

11lI11"111 1I11" 1I11 11 11 11 111111111 I I I 1 I I I I

111111111111111111111 11111 "11 1111II ' 1 1 I 1 1 I I

I 111111111111111111111 11 111 111 '1" 11 II 1 I 1I 1 1 I I

I

\\0.00 5.00

  • *00

'.00 2.00

\\.00 0.500.

  • 0 O.SO 0.20 0.10 0.050.0.

0.0' 0.02 0.0\\

40.0 20.0 30.0

\\ 0.0

\\. 0 0.\\

0.10 0*1 0.09 0.09 0.08 0.08 0.07 0.07 0.06 0.06

0. 05 0.05 0.04 0.0.

0.03 0.03 0.02 0.02 20.0 0.01 40.0 30.0 100.a

,....-.~~~~v-."..---..::or~C"""'I::"1r"<""""T-,.,.-"T'""T'-O:--"'T"?.:....:;..;,;....:.,:;.::,r-:~~,.....,.........,...,.,......l'""T""---O::--T'7""OI'"""~.--.,.,~.,.......,--..,.."'t"T'<-r-,.,...-r...,

100.0 90.0 90.0 80.0 80.0 70.0 70.0 50.0 50.0 50.0 50.0 10.0

\\0.0 9.0 9.0 B.0 8.0 7.0 7. 0 5.0 5.0 5.0 5.0 4.0 4.0 3.0 3.0 2.0 2. 0 u

W (J) z 1.0 1.0 0.9 0.9 0.8 0.8 I-0.7 0.7 u

0.5 0.6 0

.-J 0.5 W

0.5 0.4 0.4 0.3 0.3 0.2 0.2 MI LL S 3 ERR THQURKE FREQUENCY ( CPS)

FIGURE 3.78-6 HORIZONTAL TIME HISTORY RESPONSE SPECTRA 5.0 PERCENT DAMPING VALUE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

1111111111111111"1111111111111111111111 II 1 1 1 1111111111111"1"111"1111111[111111111 II 1 1 1 1111111111111111"1111111111111"1111111 II 1 1 1 to.00 5.00.4.00 3.00 2.00 1.00 0.500.40 0.30 0.20 0.\\0 0.05 0.04 0*03 0.02 0.0\\

PERIOD (SEeS) 100.0 90.0 100.0 f-90.0

~~H:;ZR"";;:S;JS;ZP~~~+=l+=Yh~;2~~~~~~4:q~:s;~;;:sg3;;tS~H~~¥H~

80.0 80.0 70.0 70.0 60.0 60.0 50.0 50.0

'0.0

'0*0 30.0 30*0 20.0 20.0 10.0 10.0 9.0 9.0 8.0 8.0 7.0 7.0 6.0 6.0 5.0 5.0

  • . 0 "0

3.0 3.0 2.0 u w (J)

Z 1.0 1.0 0.9 0.9 0*8 0.8 0

0.7 0.7 u

0*6 0*6 0

W 0.5 0*5 o.*

0.'

0.3 0.3 0.2 0.2 0-10 0.1 0*09 0.09 0.08 o.ce 0*01 0.07 0.06 0.06 0*05 0.05 0*04 0.0.4 0.03 0.03 0*02 0.02 0*01 1 *0 10.0 MILLS 3 ERRTHQURKE FREQUENCY (CPS) 1.0

'E_CHIT HU[NT FIGURE 3.78-7 HORIZONTAL TIME HISTORY RESPONSE SPECTRA 7.0 PERCENT DAMPING VALUE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

1111111111111111111111111111111111111111 II 1 1 1 1111111111111111111111111111111111111111 II 1 I I 11111111111111111111111"1"11111111111111 I I I to.OO 5.00,LDO

'.00 2.00 1.00 0.&00.'0 0.'0 0.20 0.10 0.060.04 0*01 0.02 u.tn PERIOD (SECS)

\\00.0 90.0 80.0 70.0 60*0 50.0

~o.0 40*0 30.0 30.0 20.0 20*0 10.0 10.0 9.0 9.0 8.0 8.0 7.0 7.0 6.0 6.0 5.0 5.0

,.0

,.0 3.0 3.0 2.0 toll*

  • u w

If)

Z

\\.0

\\.0 0.9 0.9 0.8 0.8 0.7 0.7 U

0 0.6 0.6

-J W

0.5 0.5 O.,

0.'

0.3 0*3 0.2 0.2 0.\\ 0 0.1 0*09 0.09 0*08 0.08 0.07 0.07 0.05 0.06 0*05 0.05 0.04 0.04 0.03 0.03 0.02 0.02 0.01 0.01 0.\\

\\.0 10.0 100.0 MILLS 3 ERRTHQURKE FREQUENCY (CPS)

FIGURE 3.78-8 HORIZONTAL TIME HISTORY RESPONSE SPECTRA 10 PERCENT DAMPING VALUE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

CONTAINMENT SHELL 0'-0" INTERNAL STRUCTURE

-9 I

-0)

N (N-S)

~--*XG M(6

-\\.0 I

-0)

N Mg 9

-I",

-N N

-0 I

orr>

N Me 8

=co

_I

\\()

ro "0

I orr>

N M7

=<;t o

-\\.0 N

=<;t-I

"\\.0

-I

-\\.0

=0 I

orr>

N 11 M3

=rr>

I

-co orr>

I

-<;t

-\\.0 I

  • 0 N

12 M(

10 M2 2

=0 I

-\\.0-EL. (-) 27'-3" KH x FIGURE 3.78-9 DYNAMIC MODEL OF THE CONTAINMENT STRUCTURE KH, Kv, KR

HORIZONTAL, VERTICAL, ROCKING TORSIONAL SUBGRADE SPRINGS AND MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

EL. 85.33' --

EL.40.0' EL.23.5'

-N-S

~------"'XG EL.9.0'

- ROCK SPRINGS

-SIX DEGREES-OF-FREEDOM; 2 HORIZONTAL, VERTICAL, 2 ROCKING, TORSIONAL FIGURE 3.78-10 DYNAMIC MODEL OF THE MAIN STEAM VALVE BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

EL. 66'-0" Ya EL.51'-0" (N-S)

XG PLANT ZG ELEVATION RIGID, MASSLESS EL. 24'-0" x

49 55 LAYER I Z

36 41 EL. 15'-0" 2

44 SO 56 LAYER 2 2

37 42 EL. 10'-0" 3

51 57 LAYER 3 3

8 13 18 23 28 33 38 43 EL. 0'-0" 4

10 16 22 28 34 40 46 52 58 LAYER 4 4

9 14 19 24 29 34 39 44 EL. (- )10'- 0" EL.(-)14'-0" LAYER 5 I. 9.0'.1.

12.0'

.~ 10.0'.1. 10.0' ~.

10.0'..I. 10.0'.~

12.0'

.~ 9.0'

~. 10.0'

~

FIGURE 3.7B-~ I DYNAMIC MODEL OF NOTE: o -INDICATES NODE OF STRUCTURE THE EMERGENCY GENERATOR ENCLOSURE N-S VIEW MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

EL.66'-0"

Ya 1

'1 4 0'1

'I

    • 7.0 ** ' ** 7.0
  • 11.0'

.tll

.1.

10.0'.14 10.0'.1.

9.0'.1.

9.0'.1.

10.0'.1.

11.0' 1

11.0' 11.0' (E-W)

ZG

~

XG RIGID, MASSLESS 74 52 VAULT AREA 8

12 16 20 24 28 32 10 16 21 26 31 36 41 9

13 J7 21 25 29 33 38 37 30 4Z 47 ROCK 10 14 18 22 26 34 39 38 43 48 x

3 4

2 EL. 24'-0" -----_-~~___r~~__.:_...,

LAYER NO. I EL. 15'-0" Z

Z EL.IO'-O" LAYER NO.2 3

LAYER NO.3 EL. 0'-0" 4

LAYER NO.4 EL.(-)Id*d' "LAYER NO.5 EL.{-)J4-0 PLANT ELEVATION NOTEo -INDICATES NODE OF STRUCTURE FIGURE 3.78 -12 DYNAM IC MODEL OF THE EMERGENCY GENERATOR ENCLOSURE E-W VIEW MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

2.50 ~---------------------------------------...,

2.00 C)

Z 0

~

0::

W

-J w

u u

<t 1.50 1.00

,,t

,.J \\,..... ---

" -",,~:-----

~--,---------------

1.50 0.05 0.10 0.25 0.30 0.35 PERIOD (SECONDS)

LEGEND

--- 0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+ OR - 15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78-13 REACTOR CONTAINMENT MAT EL. -37 1-3" AMPLIFIED RESPONSE SPECTRA N-S EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

2.00 2.50....-------------------------------------------,

6 1.50

<t a::

r-w

..J 1LI U

U

<t 1.00

,,1fII'

,I

,-v \\I

............... __------~ '------------

0.50 0.00 L---L-----l.---..l...-----L----lL----:-1..:----=-=-=----=-"7::--~:_7;:__-_:::_::::::_-~_::;:_--~

0.00 0.05 0.10 0.15 0.20 0.25 0.30 0.35 0.60 PERIOD (SECONDS)

LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING FIGURE 3.78-14 NOTE REACTOR CONTAINMENT FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN MAT El. -37'-3 11

+ OR -

15% OF RESONANCE PERIOD, USE PEAK VALUES AMPLIFIED RESPONSE SPECTRA E - W EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

125....-----------------------------------------,

1.00 6 0.75

~a:w

~ 0.50 uu

<t 0.25 I'--------...

~~-------

0.25 0.30 0.35 PERIOD (SECONDS) 0.20 0.15 0.10 0.05 0.00 L---L---.1---...L----L----.JL-----l----.l.---.l----L-----L:-------:-~--=_"O 60 MO LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+ OR -

15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78-15 REACTOR CONTAINMENT MAT EL. -37'-3" AMPLIFIED RESPONSE SPECTRA VERTICAL EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

5.00.------------------------------------------,

4.00 zo 3.00 I

<t a:

LaJ

..J LaJ

~\\.,...-

2.00 u

u

<t 1.00

........'7=====-:::::::--=:::::""'-__

~~--~~-~~-----~~---

0.00 L-__....1-__---l.

.l...-__-.L...__--I.

...l-__

l____....l.______'_

~

0.00 0.05 0.10 0.15 0.20 0.25 0.30 0.35 0.40 0.45 0.50 0.60 PERIOD (SECONDS)

LEGEND


0.005 OSCILLATOR DAMPING


0.0\\0 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+ OR -

15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.7B-16 REACTOR CONTAINMENT STEAM GENERATORS SUPPORT SLAB EL.3 1-0" AMPLIFIED RESPONSE SPECTRA N-S EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

6.00~-----------------------------------------.

5.00 n

~ 4.00

'11\\

1/,

Z o

1

~ 3.00 0::

LLI I

I W

I

.J U

I U

I

<[ 2.00 I

I

/

I I

I 1.00 I

.........../

0.05 0.10 0.15 0.20 0.25 0.30 0.35 0.40 0.45 0.50 0.55 PERIOD (SECONDS)

LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR - 15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78 -17 REACTOR CONTAINMENT STEAM GENERATORS SUPPORT SLAB EL.3'-O" AMPLIFIED RESPONSE SPECTRA E-W EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

5.00.-------------------------------------------,

0.55 0.50 0.45 0!40 0.25 0.30 0.35 PERIOD (SECONDS) 0.20 0.15 0.10 0.05 0.00 L.--__....L.__-l..__-..L

.1...-__....L...__-L__---'

...l--__...J....__-.l..__--.l'---_----'

000 Q~

4.00

(!)

Z 3.00 0

!i 0::

W

-.J 2.00 W

U U

<t 1.00 LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR -15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78-18 REACTOR CONTAINMENT STEAM GENERATORS SUPPORT SLAB EL. 3'-a" AMPLIFIED RESPONSE SPECTRA VERTICAL EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

6.00 5.00

(; 4.00 z

Q

~

3.00 0::

W-J W

UUe:t 2.00 1.00 I

I...

\\ \\It

\\.....................,

......,....---....---............~-:::::_::_==_::::'-:::::-:---:~---

.... _-----~......-....-

0.60 0.55 0.40 0.25 0.30 0.35 PERIOD (SECONDS) 0.00 ~----::~--~:---~---.L---..L--_-L..

__--1

-_..I..--__.....I..-__----1-__---..Jl--_~

0.00 LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR - 15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78 -19 REACTOR CONTAINMENT TOP OF PRIMARY SHIELD WALL EL. 24'-6*

AMPLIFIED RESPONSE SPECTRA N-S EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

10.00....------------------------------------------,

8.00 0.60

--........ '=====::=:-:====:==~:'='I-

-~------------------

0.25 0.30 0.35 PERIOD (SECONDS) 0.20 0.15 0.10 0.05 2.00 0.00 l...-__-L.__---L

~_____l...

L.____1____.l.

..L____L.._:__-__:_L:_:_-__:=_=_=:__-"'":"'

0.00 (9

Z 6.00 0

!;t a::w

-J 4.00 w

(J (J

<t LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+ OR -

15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78-20 REACTOR CONTAINMENT TOP OF PRIMARY SHIELD WALL EL. 24 1-6" AMPLIFIED RESPONSE SPECTRA E-W EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

5.00,.--------------------------------------------.,

4.00 0.60 0.55 0.50 0.45 0.40 0.25 0.30 0.35 PERIOD (SECONDS) 0.20 0.15 0.10 0.05 1.00 0.00 L--__...l..-__-l....__---..I.

.L--__-L-__.......L..__---I

...1--__-.L-__--'"

l-_----'

0.00

~

3.00 l

e:(

a::wd 2.00 uu e:(

LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+ OR -

15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78 -21 REACTOR CONTAINTAINMENT TOP OF PRIMARY SHIELD WALL EL.24'-6 11 AMPLIFIED RESPONSE SPECTRA VERTICAL EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3

FINAL SAFETY ANALYSIS REPORT

10.00 ~---------------------------------------......,

0.60 0.55 0.50 0.40 0.25 0.30 0.35 PERI00 {SECONDS}

"'I

\\"....,..........................,

0.20 0.15 0.10 0.05 0.000.00 8.00

(!)

Z 6.00 0

}-

<ta:w

-J 4.00 W

UU

<t 2.00 LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+ OR - 15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78-22 REACTOR CONTAINMENT OPERATING FLOOR EL. 50'.10 11 AMPLIFIED RESPONSE SPECTRA N-S EXCITATION S,SE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

12.00,----------------------------------------.

10.00 0.55 0.50 0.45 0.40 0.25 0.30 0.35 PERIOD (SECONDS)

  • I I','

V\\

I I

I I

I

'------- --~=-==-==-=':::'::===-=-=~---

0.00 ~--;:;~---;:~-----;~---::~:-----::-!:-:--~=---:-l----L--.-L----.l.-----...l----.J 000 00

.6

<:; 8.00 2.00 zo

!:i 6.00 a::w

....J W

UU<l 4.00 LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING

, NOTE FOR EOUIPMENT WITH A NATURAL PERIOD WITHIN

+ OR-15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78-23 REACTOR CONTAINMENT OPERATING 'FLOOR EL. 50 1-10" AMPLIFIED RESPONSE SPECTRA E-W EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

5.00 r-----------------------------------------,

0.55 0.50 0.45 0.40 0.25 0.30 0.35 PERIOD (SECONDS) 0.20 0.15 0.10

IIIII, It

,, I, I II" I

l' I

....,~~_::-:_=_=:::_:_:-:_=_=:_==_::_::_::_::_=_:_==:_::_::_=:_:-=-_==_::_:::-=--===-=:~~--

0.05 0.00 L..---...I---~----I---.1..----L....----'----L---...I---......L..-----L---.L...-----'0 60 ODO 4.00

<9 Z

3.00 0

I-

<X:

a::w

....J 2.00 I.LI Uu

<X:

1.00 LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR -15 % OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.7B-24 REACTOR CONTAINMENT OPERATING FLOOR EL.50'-10" AMPLIFIED RESPONSE SPECTRA VERTICAL EXCITATION MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

20.00r-----------------------------------------,

0.50 0.45 0.40 0.25 0.30 0.35 PERIOD (SECONDS) 0.20 0.15 0.10 0.05 0.00 L-__-L..__-L__---l

.l...-__.....L..__---l.

L-__..L-__--1-__----I.

.L.-_----J 0.00 0.60 16.00

(!)

Z 12.00 Q

!;.ta:

ILl

-l 8.00 ILl Uu

<t 4.00 LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR -15 % OF RESONANCE PERIODI USE PEAK VALUES FIGURE 3.78-25 REACTOR CONTAINMENT TOP OF CRANE WALL EL 109 1

- III AMPLIFIED RESPONSE SPECTRA N-S EXCITATION SSE MILLSTONE NUCLEAR 'POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

24.00,----------------------------------------...

20.00 c:; 16.00 z

Qti 12.00 a:::w

....J UJ Uu<t 8.00 4.00 LEGEND 0.05 0.10 0.15 025 0.30 0.35 PERIOD (SECONDS) 0.50 0.55 0.60


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR - 15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE.3.78-26 REACTOR CONTAINMENT TOP OF CRANE WALL EL.l09'-I" AMPLIFIED RESPONSE SPECTRA E-W EXCITATION SSE MILLSTONE NUCLEAR' POWER STATION UNIT :3 FINAL SAFETY ANALYSIS REPORT

10.00.------------------------------------------,

8.00 0.60 0.55 0.50 0.45 0.40 0.25 0.30 0.35 PERIOD (SECONDS)


~------

0.20 0.15 0.10 0.05 2.00 0.00 1-..__--L-__--L__--l

.L-__....l...-__...-L__---IL-.-__...I...-__--I....__--...L

.L-_----'

0.00

(!)

Z 6.00 0

~a::

lLJ

-l 4.00 w

U U

~

LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR - 15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78-27 REACTOR CONTAINMENT TOP OF CRANE WALL EL.I09'-1 11 AMPLIFIED RESPONSE SPECTRA VERTICAL EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

20.00 r-------------------------------------------,

0.60 0.55 0.50 0.45 0.25 0.30 0.35 PERIOD (SECONDS) 0.10 0.05 4.00 0.00 L---..L.----L---..l---..L-__...l.....__----l.

L-__...L-__-l..__--:-!:-:-_--::-~--7 0.00 16.00

(!)

Z 12.00 Q

~

a::w

...J 8.00 W

UU<t LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+ OR - 15% OF RESONANCE PERIOD. USE PEAK VALUES FIGURE 3.78-28 REACTOR CONTAINMENT SPRINGLINE. EL. 1041-0" AMPLIFIED RESPONSE SPECTRA N-S EXCITATION SSE MILLSTONE NUCLEAR' POWER STATION UNIT

3 FINAL SAFETY ANALYSIS REPORT

20.00.--------------------------------------------,

16.00 0.60 0.25 0.30 0.35 PERIOD (SECONDS) 0.20 0.15 0.10 0.05 4.00 0.00 L-__-L__---.l.

...L.-__---I...__---IL-__.....I.-__--l.

..L-__-l-__---l__--:~__-:-'

0.00 6 12.0 0 tr 0::

W

..JW 8.00 uu

~

LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+ OR -

15*% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78-29 REACTOR CONTAINMENT SPRINGLlNE El. 104 1.0" AMPLIFIED RESPONSE SPECTRA E -W EXCITATION SSE MILLSTONE NUCLEAR 'POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

10.00,.....----------------------------------------,

0.50 0.45 0.25 0.30 0.35 PERIOD (SECONDS) 0.20 0.15 0.10 0.05 2.00 0.00 L---..L----L.....----L....-----L---.JL-.---.l...---..L----I------L------'----L------:--l O

0 0.00

.6 8.00 z

6.00 0

!i Q::

1LI

-l 4.00 lI.J

()

()

<X LEGEND

--- 0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PER100 WITHIN

+ OR -15 % OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78-30 REACTOR CONTAINMENT SPRINGLINE EL.I04'-O" AMPLIFIED RESPONSE SPECTRA VERTICAL EXCITATION MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

24.001 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

20.00

(; 16.00 5

~ 12.00 a::w

...J W

U U<{

8.00 4.00 0.25 0.30 0.35 PERIOD (SECONDS) 0.45 050 0.55 0.60 LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR-15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78-31 REACTOR CONTAINMENT DOME APEX EL. 163'-4" AMPLIFIED RESPONSE SPECTRA N-S EXCITATION.sSE MILLSTONE NUCLEAR POWER STATION UNIT 3

FINAL SAFETY ANALYSIS REPORT

20.00,..------------------------------------------,

16.00 6

12.00 t-

<l

~

W

...J W

8.00 U

U

<l 4.00

~'------................----

0.60 0.55 0.50 0.45 0.40 0.25 0.30 0.35 PERIOD (SECONDS) 0.20 0.15 0.10 0.05 0.00 l-.__...L__---l...__--l

.l-__.....L__---..l..

L-__...L-__--L__---l__---:-.l..:-_~

0.00 LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR - 15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78-32 REACTOR CONTAINMENT DOME APEX EL. 163 1-4 11 AMPLIFIED RESPONSE SPECTRA E-W EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

12.00 1 10.00

---_.~=-========:-===:==-==---------

f',,,

I I

\\

,I' \\

,I'

\\

\\

I

\\

I

'J

\\

\\

\\

\\

(; 8.00 2.00 zo li 6.00 0::

W

..J W

U

~

4.00 0.60 0.55 0.50 0.45 0.40 0.25 0.30 0.35 PERIOD (SECONDS) 0.20 0.15 0.10 0.05 0.00 =-_----:::-:-:__-:7.:-_~=_-~..I::_=_-__:~__:-~_:__--L---..L---L----l---.L---..-J 0.00 LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING

, NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR-15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78-33 REACTOR CONTAINMENT DOME APEX EL. 163 1

- 4 II AMPLIFIED RESPONSE SPECTRA VERTICAL EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3

FINAL SAFETY ANALYSIS REPORT

1.50,---------------------------------------------.

<..?

1.00 Z

0

~

<{

0.75 a::

W

.-oJ W

U U

<{

0.50 0.25 1.10 1.00 0.90 0.80 0.50 0.60 0.70 PERIOD (SECONDS) 0.40 0.30 0.20 0.10 0.00 l-.-__---'--__--'

...l--__---'-

L-__.....L-__---L

..L-__-L.__-ll--__-L.__---l 0.00 1.20 LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING 0.020 OSCILLATOR DAMPING

--- 0.040 OSCILLATOR DAMPING


0.080 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+ OR -15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78 - 34 MAIN STEAM VALVE BUILDING MAT EL. gl_O" AMPLIFIED RESPONSE SPECTRA N-S EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

1.50r------------------------------------------.

(!)

1.00 Z0.-.

c:r 0.75 a::w

-I W

U Uc:r 0.50 0.25 1.20 1.10 1.00 0.90 0.80 0.50 0.60 0.70 PERIOD (SECONDS) 0.40 0.30 0.20 0.10 0.00 L-__....L-__-...I.

~___J...___....:L.___...1..______..1.

.l.___.....L..___.___JL___..L___.-J 0.00 LEGEND


0.005 OSCILLATOR DAMPING

--- 0.010 OSCILLATOR DAMPING 0.020 OSCILLATOR DAMPING 0.040 OSCILLATOR DAMPING


0.080 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR - 15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78 -35 MAIN STEAM VALVE BUILDING MAT EL. 9 1

- 0" AMPLIFIED RESPONSE SPECTRA E-W EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

1.50,-----------------------------------------.......,

1.25

~

1.00 zo

~

a::

0.75 w

--l W

Uu

<I 0.50

~.._---

1.10 1.00 0.90 0.80 0.50 0.60 0.70 PERIOD (SECONDS) 0.40 0.30 0.20 0.10 0.00 L..-__-L..__---lI.....-__...L-__-..L l..-__-I-__-...l

..l-__--L L--__...1-__~

0.00 1.20 LEGEND


0.005 OSCILLATOR DAMPING 0.010 OSCILLATOR DAMPING


0.020 OSCILLATOR DAMPING


0.040 OSCILLATOR DAMPING


0.080 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+ OR-15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.7 B - 36 MAIN STEAM VALVE BUILDING MAT EL. 9 1-0" AMPLIFIED RESPONSE SPECTRA VERTICAL EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

5.00~----------------------------------------..

4.00 o

Z 3.00 0

~

a::w

--J 2.00 w

uu<r 1.0 0

~

~

....----------------~-----~------

1.00 0.90 0.80 0.50 0.60 0.70 PERIOD (SECONDS) 0.40 0.30 0.20 0.10 0.00 l--__--J.....__----I.

..1..--__-L-__----Jl-__..L-__-..L

..L...-__--'-__--'

~__.......

0.00 1.2.0 LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING


0.020 OSCILLATOR DAMPING

-- 0.040 OSCILLATOR DAMPING


0.080 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR - 15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78 - 37 MAIN STEAM VALVE BUILDING FLOOR SLAB EL.41 1-0" AMPLIFIED RESPONSE SPECTRA N~S EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

5.00r-----------------------------------------......,

Q50 OBO O~O PERIOD (SECONDS) 0.40 0.30 0.20 0.10 0.00 L-__.....L-__----..I.

.L..-__-!...__-----IL-..__....I....-__-.J...

.l.-__....1-__---l:-:-_---:....L...:-__~

0.00 4.00

(,!)

Z 0

ti a::w

....J 2.00 w

U U

<X LEGEND 0.005 OSCILLATOR DAMPING

- -- 0.010 OSCILLATOR DAMPING


0.020 OSCILLATOR DAMPING 0.040 OSCILLATOR DAMPING


0.080 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+ OR - 15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.7 B - 38 MAIN STEAM VALVE BUILDING FLOOR SLAB EL. 41' - 0" AMPLIFIED RESPONSE SPECTRA E-W EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

1.25 r---------------------------------------~

1.00 6

0.75 I-<t a:w

...Jw 0.50 uu c::r 0.25


=~----

0.50 0.60 0.70 PERIOD (SECONDS) 0.40 0.30 0.20 0.10 0.00 LO-----l---..L----L---L-----L-----L----:-:---~:--~::----:-~------:::~-~1.20 0.0 LEGEND


0.005 OSCILLATOR DAMPING

- -- 0.010 OSCILLATOR DAMPING 0.020 OSCILLATOR DAMPING 0.040 OSCILLATOR DAMPING


0.080 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+ OR -

15% OF RESONANCE PERIOD I USE PEAK VALUES FIGURE 3.78 -39 MAIN STEAM VALVE BUILDING FLOOR SLAB EL 411-0 II AMPLIFIED RESPONSE SPECTRA VERTICAL EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

10.00r-------------------------------------------,

1.00 1.10 0.80 0.50 0.60 0.70 PERIOD (SECONDS) 0.40 0.30 0.20 0.10 0.00 L..-.__....L-__--I.

...L-.__-L__----Il--__.......L-__---1.

.L..-__-'-__--I.

-'-__-1 0.00 1.20 8.00

(.!)

Z 6.00 0

i=

<t 0:::

W

-J 4.00 W

uu

<t 2.00 LEGEND


0.005 OSCILLATOR DAMPING

-- 0.010 OSCILLATOR DAMPING

- -- 0.020 OSCILLATOR DAMPING

-- 0.040 OSCILLATOR DAMPING


0.080 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+ OR - 15% OF RESONANCE PERIOD. USE PEAK VALUES FIGURE 3.78-40 MAIN STEAM VALVE BUILDING ROOF SLAB EL. 85 1

- 4" AMPLIFIED RESPONSE SPECTRA N-S EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

10.00r------------------------------------------,

8.00 1.10 1.20 0.90 0.80 0.50 0.60 0.70 PERIOD (SECONDS) 0.40 0.30 0.20 0.10 2.00 0.00 L..__....L.__---.1

.l-__--L__----l

...J.....__--l.

.l...-__....l.-__-.1

.J-__--I 0.00

(!)

Z 6.00 0

~

' Il:

IJJ

...J W

4.00 U

U<[

LEGEND


0.005 OSCILLATOR DAMPING 0.010 OSCILLATOR DAMPING


0.020 OSCILLATOR DAMPING

-- 0.040 OSCILLATOR DAMPING


0.080 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+ OR - 15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78 - 41 MAIN STEAM VALVE BUILDING ROOF SLAB EL.85 1-4" AMPLIFIED RESPONSE SPECTRA E-W EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

2.00..------------------------------------,----------,

1. 75 1.50

~

1.25 zo

~

1.00 0:::

W

.....J W

Uu<t 0.75 0.50 0.25 1.10 1.0 0 0.90 0.80 0.40.

0.50 0.60 0.70 PERIOD (SECONDS) 0.3 0

0. 20 0.10 0.00 L-__--L__.--JL-__....L-__--L

..l.-__-.1..

..1--__-.l..

.l...-__-L L-_----J 0.00 1.20 LEGEND


0.005 OSCILL ATOR DAMPING 0.010 OSCILLATOR DAMPING

--- 0.020 OSCILLATOR DAMPING

-- -- 0.040 OSCILLATOR DAMPING


0.0 80 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR.- 15 % OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78 -42 MAIN STEAM VALVE BUILDING ROOF SLAB EL. 85'- 4" AMPLIFIED RESPONSE SPECTRA VERT ICAL EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3

FINAL SAFETY ANALYSIS REPORT

6.00 4.00

<.!)

zo 2.00

<ta::

~

0.00 ~------oo;;;;;::-------J~------\\-------====--.......,,~=====~--------j Wuu<t en -2.00 a:l

<t

-4.00

-6.00

- 8.00 '--_-'--_--L__...L..-_--L___'____--'-__L..-_--'-_------'__-'--_~___'___

____l..___'___

_J 0.00 2.00 4.00 6.00 8.00 10.00 12.00 14.00 16.00 18.00 20.00 22.00 24.00 26.00 28.00 30.00 FREQUENCY (CPS)

FIGURE 3.78-43 EMERGENCY GENERATOR ENCLOSURE TRANSFER FUNCTION AT BASE OF STRUCTURE EL. 9 1- 0 11 FOR HORIZONTAL ACCELERATION N-S EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 3 AUGUST 1983

5.00 2.50

~ 0.00 r------""'=---t-7~::::=....-_:r",;::;::::;;;~========------_i z

Q

~ -2.50 l.LJ

...J W

~ -5.00

<t in OJ

<t -7.50

-10.00

-12.50 0.00 2.00 4.00 6.00 8.00 10.00 12.00 14.00 16.00 18.00 20.00 22.00 24.00 26.00 28.00 30.00 FREQUENCY (CPS)

FIGURE 3.78-44 EMERGENCY GENERATOR ENCLOSURE TRANSFER FUNCTION AT FLOOR SLAB EL. 51 1- 0 "

FOR HORIZONTAL ACCELERATION N-S EXCITATION SSE 1

MIL.L~iONE NUClaiAft ~QW6ft iTAf\\ON UNIT :3 I

r \\

FINAL SAFETY ANALYSIS REPORT

15.00 20.00,.....------------------------------------....,

10.00 Cl Z o 5.00 Q:

~ 0.00 ~===::=--=_--__+-~~:::::::~-_J_=~~;;;;:====----------~--~

w u

~ -5.00 en CO <<

-10.00

-15.00

-20.00 '--_-!.-_-----L__-l..-_--L__..L-_--'-__'--_-'-_-----L__-l..-_--L__..L-_--'-__'--_.....

0.00 2.00 4.00 6.00 8.00 10.00 12.00 14.00 16.00 18.00 20.00 22.00 24.00 26.00 2800 30.00 FREQUENCY (CPS)

FIGURE 3.7 B-45 EMERGENCY GENERATOR ENCLOSURE TRANSFER FUNCTION AT ROOF SLAB EL. 66 !... 011 FOR HORIZONTAL ACCELERATION N-S EXCITATION *SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 3 AUGUST 1983

6.00r-------------------------------------.....

4.00 2.00

(,!)

~-------------

Z o

0.001="""""'="""""''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''''=''''''''''''''''''''''''''''=''''''=''''''.....-_''''''---- ---+---------1

~

0:::

W

...J -2.00 W

U U<< -400 en rn c::(

-6.00

-8.00

- 10.00 L....-_---........_-----_--'---_----L__-'--_--L-__-'--_---........_---'__--'---_----L__-'--_--L-__.L....-_-'

0.00 2.00 4.00 6.00 8.00 10.00 12.00 14.00 16.00 18.00 20.00 22.00 24.00 26.00 28.00 30.00 FREQUENCY (CPS)

FIGURE 3.78 -46 EMERGENCY GENERATOR ENCLOSURE TRANSFER FUNCTION AT BASE OF STRUCTURE EL. 9!....OIl FOR VERTICAL ACCELERATION VERTICAL EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 3 AUGUST 1983

15.00 20.00,----------------------------------------,

10.00 C!)

Z o 5.00

!;t 0::

W

...J 0.00 t----......---......"""""'''''''''''''''''''''''''''''''''''''''''''''''''''~'''''''''''''''''~----=----+_--------l w

u u

ct en -500 OJ ct

-10.00

-15.00

-20.00 L..-_-'--_----L.__..l.--_-l-_-...L__..L-_-L-_---"__-L-_---L_---1__-L-_--I.-_----JL..----l 0.00 2.00 4.00 6.00 8.00 10.00 12.00 14.00 16.00 18.00 20.00 22.00 24.00 26.00 28.00 30.00 FREQUENCY {CPS}

FIGURE 3.78-47 EMERGENCY GENERATOR ENCLOSURE TRANSFER FUNCTION AT FLOOR SLAB EL. 51'- 0" FOR VERTICAL ACCELERATION VERTICAL EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

15.00 20.00r------------------------------------.....,

10.00 z o 5.00

~

a::

w

-J 0.001----------------------""""""====-----;---------1 w

u u

U> -5.00 OJ

<t

-10.00

-15.00

-20.00 1.....-_--L.-_----I__....L...._-..L__...I....-_-.L__L-_-1-_---I__....L...._---L__...I....-_---L.__.l....-_...J 0.00 2.00 4.00 6.00 8.00 10.00 12.00 14.00 16.00 18.00 20.00 22.00 24.00 26.00 28.00 30.00 FREQUENCY (CPS)

FIGURE 3.7B~48 EMERGENCY GENERATOR ENCLOSURE TRANSFER FUNCTION AT ROOF SLAB EL. 66'-0" FOR VERTICAL ACCELERATION VERTICAL EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 3 AUGUST 1983

8.00 r---------------------------------------..,

6.00 4.00 zo 2.00 t-<<

Il:

W

...J 0.00 t-........"""""''''''''''''''''''=='''''---=;:;;;;;:;;::

----~~-----_+ ---______=:::;;;:;====-..-------__l w

uu<< -2.00

(/)

CD<<

-4.00

-6.00

- 8.00 L--_-'--_---'__-'--_---L__-'---_-'-__L--_-'--_-'-__-'--_--'-__-'---_-'-_-----lL-_---.J 0.00 2.00 4.00 6.00 8.00 10.00 12.00 14.00 16.00 18.00 20.00 22.00 24.00 26.00 28.00 30.00 FREQUENCY (CPS)

FIGURE 3.7 B-49 EMERGENCY GENERATOR ENCLOSURE TRANSFER FUNCTION AT BASE OF STRUCTURE EL. 9 1- 0 "

FOR HORIZONTAL ACCELERATION E-W EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMEN DMENT 3 AUGUST 1983

20.00,..-------------------------------------,

15.00 10.00 C)

Z o 5.00

!;t 0:::

~ 0.00 1=:::=::::;;;"".".......----

=----+-----::::;;;;;o~~~-~6==:::==:=;;;:~"-----_l w

u u << -5.00 en al

-10.00

-15.00

- 20.00 L-_....L-_---L__.l.--_--I...-_-..1.__..l....-_--I...-_----L__~_

___I_._

_...JL___....I...__

___I..__L_____J 0.00 2.00 4.00 6.00 8.00 10.00 12.00 14.00 16.00 18.00 20.00 22.00 24.00 26.00 28.00 30.00 FREQUENCY (CPS)

FIGURE 3.78-50 EMERGENCY GENERATOR ENCLOSURE TRANSFER FUNCTION AT FLOOR SLAB EL. 51 1- 0" FOR HORIZONTAL ACCELERATION E-W EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

15.00

-15.00 20.00 r---------------------------------------,

_10.00 C>

z Q 5.00 c::r:

0:::

~ 0.00 r::======---_--==------\\-----=~~--______)L-~~~===~~:::;;'-----------l w

u u

c::r:

en -5.00 CD c::r:

-10.00

- 20.00 '--_-'--_---'__-'--_---'-__...L..-_---Ul'---_'--_-'--_---'__-'--_---'-__...L-_----L.__.L...-_--'

0.00 2.00 4.00 6.00 8.00 10.00 12.00 14.00 16.00 18.00 20.00 22.00 24.00 26.00 28.00 30.00 FREQUENCY (CPS)

FIGURE 3.78-51 EMERGENCY GENERATOR ENCLOSURE TRANSFER FUNCTION AT ROOF SLAB EL. 66!..OIl FOR HORIZONTAL ACCELERATION E-W EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 3 AUGUST 1983

5.00 r------------------------------------------,

4.00

(!)

Z 3.00 0

1i

~

W

...J 2.00 w

u u

<t 1.00

=---....

0.00 =-_---::-":-:"__-::-':-=-_---=--=-=-_---::-'::-__~---...L.-----.1...------Il-----l----...1..---L---...J 0.00 0.50 0.60 0.70 0.80 0.90 1.00 1.10 1.20 PERIOD (SECONDS)

LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING 0.020 OSCILLATOR DAMPING FIGURE 3.78 - 52 EMERGENCY GENERATOR ENCLOSURE EL. 24 1-6" FLOOR SLAB NOTE AMPLIFIED RESPONSE SPECTRA FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR-15% OF RESONANCE PERIOD, USE PEAK VALUES N-S EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

5.00 r-----------------------------------------....,

4.00

<9 Z

3.00 0

~

a:

w

...J 2.00 u

W u <<

1.00

-==.---....-:...------ :--....

0.00 '---__.....l...-__-.L

..L-__-.L-

'--__-'--__--L

.l-..__.....I 0.00 0.10 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 1.10 1.20 PERIOD (SECONDS)

LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING 0.020 OSCILLATOR DAMPING FIGURE 3.78-53 EMERGENCY GENERATOR ENCLOSURE EL. 24 1-6" FLOOR SLAB NOTE AMPLIFIED RESPONSE SPECTRA FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR-15 % OF RESONANCE PERIOD, USE PEAK VALUES E-W EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

5.00,-----------------------------------------,

4.00 (9

Z 3.00 0

!:t 0:::

W

.J w 2.00 u u

<t 1.00

-= --

0.00 l..-__--l.-__----L

-'--__--L..__---I

..l...-__-L.

L....-__...l...-__--.L

.L..-__....J 0.00 0.10 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 1.10 1.20 PER 100 (SECONDS)

LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING

--- 0.020 OSCILLATOR DAMPING FIGURE 3.7 B - 54 EMERGENCY GENERATOR ENCLOSURE FLOOR SLAB EL. 24 1-6" NOTE AMPLIFIED RESPONSE SPECTRA FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR-15% OF RESONANCE PERIOD, USE PEAK VALUES VERTICAL EXCITATION' SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

12.00...--------------------------------------------,

10.00 t:>

8.00 Z

0 t-6.00

<<a:::

1IJ

...J W

Uu 4.00 2.00 LEGEND 0.20 0.40 0.50 0.60 0.70 PERIOD (SECONDS) 0.80 0.90

1. 0 0 1.10

0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING

--- 0.020 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR-15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78-55 EMERGENCY GENERATOR ENCLOSURE FLOOR SLAB EL. 51 1-0" AMPLIFIED RESPONSE SPECTRA N-S EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

10.00...-----------------------------------------....,

1.20 1.10 1.00 0.90 0.80 0.50 0.60 0.70 PERIOD (SECONDS) 0.40 0.30 0.00 l..-__....L.-__--I.

.L......__--'-__---'

...L-__--1..

L-__-L..__--l.

.1-__...J 0.00 8.00 C>

Z 6.00 0

~a:

w

...J 4.00 wuu<<

2.00 LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING

-- 0.020 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR-15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78 - 56 EMERGENCY GENERATOR ENCLOSURE FLOOR SLAB EL.51 1-0" AMPLIFIED RESPONSE SPECTRA E-W EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

5.00,-----------------------------------------,

4.00 C)

Z 0

~

<{

0::

W

-J W

u U

<{

3.00 2.00 1.00 0.00 0.00 0.10 0.20 0.30 0.40 0.50 0.60 0.70 PERIOD (SECONDS) 0.80 0.90 1.00 1.10 1.20 LEGEND

--- 0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING

-- 0.020 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR-15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.78 -57 EMERGENCY GENERATOR ENCLOSURE FLOOR SLAB EL. 51 1-0" AMPLIFIED RESPONSE SPECTRA VERTICAL EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

15.00,--------------------------------------------..,

12.00 (9

Z 9.00 0

~

0::

I.LJ

....J 6.00 lLJ U u <t 3.00 0.00 0.00 0.10 0.20 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 1.10 1.20 PERIOD (SECONDS)

LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING

--- 0.020 OSCILLATOR DAMPING FIGURE 3.78-58 EMERGENCY GENERATOR ENCLOSURE ROOF SLAB EL. 66'-0" NOTE AMPLIFIED RESPONSE SPECTRA FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR - 15% OF RESONANCE PERIOD, USE PEAK VALUES N -S EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

12.00~----------------------------------------,

10.00

(; 8.00 zo

~ 6.00 a::w-'

lJJ U

~ 4.00 1.10 1.00 0.90 0.80 0.50

. 0.60 0.70 PERIOD (SECONDS) 0.40 0.30 0.20 0.10 0.00 '---__-l-__---'

-'---__..........__-----_--,--..L-.__-..L l..-__-'--__--1.

..I...-__-J 0.00 1.20 LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING

--- 0.020 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR-15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.7B-59 EMERGENCY GENERATOR ENCLOSURE ROOF SLAB EL. 66 1-0" AMPLIFIED RESPONSE SPECTRA E -W EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

5.00.------------------------------------------,

4.00 C>

Z 3.00 Q

~

<t a::: w

--J 2.00 w

u u <<

1.00 0.00 0.00 0.10 0.20 0.30 0.40 0.50 0.60 0.70 0.80 1.20 PERIOD (SECONDS)

LEGEND


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING

--- 0.020 OSCILLATOR DAMPING FIGURE 3.78-60 EMERGENCY GENERATOR ENCLOSURE ROOF SLAB EL. 66'-0" NOTE AMPLIFIED RESPONSE SPECTRA FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR - 15% OF RESONANCE PERIOD, USE PEAK VALUES VERTICAL EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

6.00r------------------------------------------,

5.00 C; 4.00 z o

~ 3.00 0::

W

-.J W

U u

<t 2.00 1.00

--';;;'::!I 0.00 '--__....L-__-L..__-----'-

.L.-__-'--__---L.__---1

.L..-__-'--__---L.__---1__---'

0.00 0.10 0.30 0.40 0.50 0.60 0.70 0.80 0.90 1.00 1.10 1.20 PERIOD (SECONDS)

LEGEND FIGURE 3.78-61


0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING EMERGENCY GENERATOR ENCLOSURE DIESEL GENERATOR MAT EL. 24' - 6" 0.020 OSCILLATOR DAMPING AMPLIFIED RESPONSE SPECTRA N-S EXCITATION SSE NOTE MILLSTONE NUCLEAR POWER STATION FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN UNIT 3

+OR-15% OF RESONANCE PERIOD, USE PEAK VALUES FINAL SAFETY ANALYSIS REPORT

5.00 r------------------------------------------.

4.00 C>

Z 0

l-e:[

a::

1LI

...J 1LI U

~

3.00 2.00 1.00 0.40 0.50 0.60 0.70 PERIOD (SECONDS) 0.80 0.90 1.00 1.10 1.20 LEGEND

--- 0.005 OSCILLATOR DAMPING


0.010 OSCILLATOR DAMPING

-- 0.020 OSCILLATOR DAMPING NOTE FOR EQUIPMENT WITH A NATURAL PERIOD WITHIN

+OR 15% OF RESONANCE PERIOD, USE PEAK VALUES FIGURE 3.7 B-62 EMERGENCY GENERATOR ENCLOSURE DIESEL GENERATOR MAT EL. 24' _6" AMPLIFIED RESPONSE SPECTRA VERTICAL EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

0.20 MAX 0.17685 0.15 -

AT 8.6100 0.10 -

C) 0.05 r-z o

~

a::

w w

u u

0.00

-0.05 a

~

f-II,.

,~ ~

IW ~

~

-0.10 f

-0.15...

-0.20 I

I I

I I

r r

I I

I I

I I

I 0.00 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.00 9.00 10.00 11.00 12.00 13.00 14.00 15.00 TIME (SECONDS)

FIGURE 3.78-63 EMERGENCY GENERATOR ENCLOSURE HORIZONTAL ACCELERATION TIME HISTORY AT BEDROCK N-S EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

0.40,..--------------------------------------,

MAX 0.30140 AT 8.8600 0.30 0.20 0.10 zo f-

~ 0.00 W-l W

Uo -0.10

<{

-0.20

-0.30

- 0.40 1-.._.....L-_--l..__L..-_.....L-_----L__l....-_--'-_---L__...L.-_--..L..._---..I.__..l-_--'-_----I_--l 0.00 1.00 2.00 3.00 4.00 5.00 6.00 7.00 8.0.0 9.00 10.00 11.00 12.00 13.00 14.00 15.00 TIME (SECONDS)

FIGURE 3.7B -64 EMERGENCY GENERATOR ENCLOSURE HORIZONTAL ACCELERATION TIME HISTORY AT BASE OF STRUCTURE N-S EXCITATION SSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

+Fy 1" Ay

  • '?-..
  • s
  • !2..

I. *

-WICATES MASS POINT 2.* -INDICATES CONSTRAINT POINT

3. * -INDICATES RElfRlRCED TEE
4. SNUBBERS AT POINTS607 AND 723 ARE ATTACHED TO EQUIP. SUPPORTS 5. NSS-NORTH SOUTH SHOCK SUPPRESSOR
6. EW-EAST WEST RESTRAINT

!I!!II o

N 5!17

-0 oft IlSO

-C!.,

!llIll

~

!ISS

-g

!l1I7 EW

-0 N

570

't'~':~r' 0.57 1.29 '

!l80 2.' - 3" 425 1145 2.2S'"

"AHS -0I0-23-2 If-V2 VGW060-lC-2 SH

'-RHS-008-41-2 1'-6" l3'RIlS -OIO-4 -2 CL.1I02(TYP.)

,111"010" AEO.

492

  • 0, N

490 o

N 485 II-FE-SIS 600#OAIFICE fL8 I-------'---=---

HS 4011 2.92' EW

'0 N

46 !I 0.50'(TYP) t-o 465 "70 620 rli. 5AH5* EIA

.L.---=-'-'-"'------9'-..Il2S AHR HEAT ElCCHANHR 1550 t" r: E IN LET fA OUTLET I ~

EL. 9~S~*

FIGURE 3.78-65 TYPICAL MATHEMATICAL MODEL OF A PIP I N G SYSTEM MILLSTOt£ NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT 5.0' S.TS' 475 480

_DETA I L A

' -AHS -OIO 2 660 6SS 4.25' SlIll 5 - A H5- 0 10 2 ESF BUILDING4'"

5 - RHS-OIO-6-2 S.70' 5-AH5-010-7-2

£

- l OISCHAAOE 740 EL. 9' - 5~4" 745

,;<-"....,..-=.

  • 7 0 0

/

~

' /............. -<,

~ SAHS* PIA RHA PUMP I

(~SUCTlON ;

5115 ANCHOA(EL. 12', 0")

~PA08. 7100 (AX-7IA)

-N PAOB.7102 (AX-7IS) 5S!!

'0

-0 El¥,.;.,

S9!!

700 o

701

-0 N

VSS NSS SH

-0 N

705 ESS

-0 702

  • 0

'0,

-N

'0

  • 0

c>-zo

~

0:

LaJ

...J Wo

(.)

<t FREQUENCY (Hz)

FI GURE 3.78-66 REPRESENTATION OF FAMILY OF PEAK RESPONSE CURVES WITHIN BROADENED RESONANT PEAK MI LLSTONE NUCL EAR POWER STAT ION UNIT 3 FINAL SAFETY ANALYSIS REPORT

HYPOTHETICAL RESPONSE~

0>-z o

~

0::

1JJ

....J 1JJ U

~

ACTUAL RESPONSE' PEAK BROADENING 1%fn fn FREQUENCY (Hz)

FIGURE 3.78-67 HYPOTHETICAL vs ACTUAL RESPONSE OF MULTIPLE MODES WITH IN BROADENED RESPONSE PEAK MI LLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

2.0 10 11 1:1:25%

9 MODES 7

8 9

1:t: 20%

3 4

5 6

r--"':

PEAK

~

I :t:10% BROADENING 1:1:15 Vo 2°1c~--------------==-~--------------11.3 1.3 1.5 1.0 1.3 1.5 2.0 K

o 2

3 4

5 6

7 8

9 10 MODE SPREAD % fn (BETWEEN MODES) 11 12 FIGURE 3.78-68 JUSTIFICATION OF STATIC LOAD FACTOR MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

3.0..----------------------------------...JIJ,...,

r 15%PEAK BROADING =t.t At 2.5 2.0

(!)-

Zo

~<<

1.5 0::

I.LI

..J I.LI U

U<<

1.0 0.5 o

QmoxAPPLIED OVER TH IS FREQUENCY BAND fp

<;I =go FROM TH IS FREQUENCY ON go 7

FREQUENCY (CYCl ES/SEC)

CUTOFF tc= 2C CPS go= 34 20 FIGURE 3.7 B - 69 TYPICAL AMPLIFIED RESPONSE SPECTRA MIllSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

JOINT NUMBER 2

3 4

5 6

7 o

o o

o b

(TYPICA L )

~====a::::=::::J:c:~c::==::tC=::::r::I==:::::::J1 CANTILEVER (CANT) 2 j~=============~~

FIXED-FIXED (FF)

SIMPLE-SIMPLE (SS) 4 a===============~11 SIMPLE-FIXED/NO OVERHANG (SF) 5

~========::;::::==3 IfJJ SIMPLE -F IXED/I6 %

OVERHANG J)J SI MPLE-FIXED/33 % C1IERHANG 7 g====:;:;::======::=:=J SIMPLE -FIXED/50% OVERHANG 14------ 60 IN. ------.l FIGURE 3.78-70 MODEL BEAMS MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

51---------..

4

....J

<t U

3 I-a:

u

~

0 2

c:>

z -c,

~

<t 0

1 OL----------L.--------&.:-------~

o 10 20 30 FREQUENCY (HZ)

NOTE:

APPLICABLE TO BOTH OBE E. SSE, INDEPENDENT OF PIPE DIAMETER FIGURE 3.7B-71 DAMPING VALUE FOR SEISMIC ANALYSIS OF PIPING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 15 SEPTEMBER 1985

FIGURE 3. 7N-l MULTI-DEGREE OF FREEDOM SYSTEM MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

FIGURE 3.9.8-1 REACTOR COOLANT PPG.

MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

~.6 -1 STEAM GENERAlOR 3RC5-6610

'P,

' *.I'~...

,-, iREACTOR VESSEL 3 RCS-RVI


~

I~

1.10' "045

...c.

rO-o*

'-.00.

7

z 44 STEAM GENERATOR Y

88 NOTE:

LOOP 2 SHOWN -ADD 200 TO FIGURE 3.98-2 ALL NODE NUMBERS.

DYNAM IC MODEL-TYPICAL RCS LOOP MI LLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

Y 135 60 64 i

3 t X1

~X2 X2t 74 **=======0 X

202 z

/'

LOOP 4 I

435 1 335 CRANE WALL TOP VIEW XI 66 J:

6l X2 59 X3 71 LEGEND:

INFINITELY RIGID MEMBER

=== VERY STIFF MEMBERS

~

MATRIX ADDITION MEMBER

--<>-- NODE WITH NO MASS NODE WITH MASS FIGURE 3.9 B-3 DYNAMIC MODEL-CENTER SECTION MILLSTONE NUCLEAR POWER STATION UNIT 3

FINAL SAFETY ANALYSIS REPORT

103.61 85.63 49.65 31.66

-o X

13.67

-4.32

  • 22.30

-4Q29 61.95 43.96 25.91 7.99

-10.00

-27.99

-45.98

-58.28

--...L.

.......L..-

...L....-

Io.....-


oL

-63.97 X10' FIGURE 3.98-4 X2 VIEW-ROTATED AXES MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

CL OF

!T"CONTAINMENT STRUCTURE 1f I I I

/

LOOP 2 UPPER STEAM GENERAL SNUBBERS LEGEND:o COLUMNS CJ SNUBBERS FIGURE 3.98 - 5 SNUBBER ORIENTATION MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

MPS-3 FSAR FIGURE 3.9N-1 REACTOR PRESSURE VESSEL AND INTERNALS SYSTEM MODEL 20 a

-20

-40

-60

-80

-100

-120

-140

-160

-180

...,200

-220

-240

-260

-280

-300 -

120 100 80 60 40 usc Hold-down springZ4 10-._~

42 61 4J f

  • -03 44i

/

<<i I

./

46f~

L Lower Radial Keys 16 17 14 15 11 o

10 12 13 21

.~

221 I

I 23 i

__ ",'.. 24 8

251


;- i 21: 20 28 '-;---,~..

UCP Alignment

~ ~i......--~,52 31 t 53 pan 32 54 33 -

55 34.

56 36 :

57""

~7 l 513 Fuel

~~.--~--

I 50

<40.-'-

,GO 41 r CB RPV ______

2 3 -

4 5

RPV* CB Nozzle

)):. I..un[::a:i ~ss Rev. 21.3

MPS-3 FSAR FIGURE 3.9N-2 DELETED BY PKG FSC 07-MP3-039 Rev. 21.3

NST (I) AND PSW (2)

ROTATIONAL STIFFNESS NST (I) AND PSW (2)

HORIZONTAL ST IFFNESS RPV HOR IZONTAL STI FFNESS RPV ROTATIONAL STIFFNESS RPV NOZZLE i LOOP ROTATIONAL STIFFNESS LOOP HORIZONTAL STIFFNESS NOTE S:

I. NEU TRON SHIELD TANK

2. PRIMARY SHIELD WALL NST (I) AND LOOP VERTICLE STIFFNESS FIGURE 3.9N-3 RPV SUPPORT MODEL FOR WESTI NGHOUSE INTERNALS RESPONSE ANALYSIS MILLSTONE NUCLE AR POWER STAT' 0 N UNIT 3 FI NAL SAFETY ANALYSIS REPORT

ROD TRAVEL HOUSING OPERATING COIL STACK ASSEMBLY LATCH HOUSING DRIVE ROD ASSEMBLY DISCONNECT ROD ASSEMBLY CABLE CONNECTION LATCH ASSEMBLY FIGURE 3.9N-4 CONTROL ROD DRIVE MECHANISM MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FILE: 39n4.dgn/39n4.cit December 1997

1fIlW-_---DRIVE ROD ASS'Y.

ROD TRAVEL HOUSING LATCH HOUSING

-,.L-~-U~~~1,""""_-o RI NG

~"'1i""'-L1FT POLE LI FT COILlC)

~...:...--..a:IiilIi!-'t1""tr-SH I M

~...4-;-\\-f'_-L1FT RETURN SPRING

"'-__ FLUX RING LOCK WIRE MOVABLE GRIPPER POLE MG COIL IB)

SHIM MOVABLE GRIPPER SPRING

.II.~........ _LOCK PLUNGER MOVABLE LATCH LATCH PIN

"#~f-: LATCH ARM II:

LINKPIN "t~2:::LATCH LI NK III LI NK PI N

L,'~r---LOCK WIRE

?t""'~--'--SUPPORT TUBE MOVABLE LATCH

'-if,fi....cr-- STATIONARY GRIPPER POLE iit~~r~fr"'!tt"- FL UX RI NG

=~.......j..O-+.-- GUI DE TUBE

......~~!'1-- SHIM SG COILIA)

  • &;..'-.......f--STATIONARY GRIPPER SPRING

~__-PLUNGER HALF FLUX RING

~""'~l~LOCK WIRE

.-*-;:s:;J.:'-- SHI M

~....--LIFT RETURN SPRING

...wo".......-SPRING RETAINER LATCH PIN LOCK PLUNGER STATIONARY LATCH LINK PIN

~

LATCH LINK LINK PIN SUPPORT TUBE STATIONARY LATCH

~I~~~ LATCH ARM

~'-+---LATCHSTOP FIGU RE 3. 9N-5 CONTROL ROD DRIVE MECHANISM SCHEMATIC MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

BEFORE LOAD TRANSFER AFTER LOAD TRANSFER a

LIFT COIL OFF A

15.629 AT 70° 8

15.625 CD 0.004 8

I I

I ILIFT COIL OFF A

15.625 AT 70° 8

15.566 G) 0.05'3 LIFT COIL ON 16.254 16.250 0.004 ILiFT COIL ON 16.250 16.1'31 0.05'3 LIFT COIL OFF A

15.711 AT 6SOo B 0 15.684 0.027 I

I I

I IILIFT COIL OFf A

15.684 AT 6S0o a

0 15.627 0.057 LI FT COIL ON 16.361 16.311 0.050

\\ LIFT COIL ON 16.311 16.277 0.034 I

I FIGURE 3.9N-6 NOM INAL LATCH CLE ARANCE AT MINIMUM AND MAXIMUM CLEARANCE MILLSTON E NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FILE:39n6dgn/39n6.clt December 1997

0.080 0.070 Vl LU

z:

u z 0.060 LifT COIL LIFT COIL OFf } ~G CLEARANCE AFTER ON LOAD TRANSFER LU 0 C Ill:

CJ 0.050 LU Or:

0 0.040 0 z:

4(

II)

UJ

z:

u I

~

..J 0.030 0.020 UJ z

Ill:

oCt UJ

..J 0.010 0.000 0

100 200 300 400 500 600 700 TEMPERATURE (Of)

FIGURE 3.9N-7 CONTROL ROD DRIVE MECHANISM LATCH CLEARANCE THERMAL EFFECT MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FILE:39n7dgn/39n7.clt December 1997

FUEL ASSEMBLY UPPER CORE GUIDE PIN PLATE GUIDE PIN CORE BARREL CORE SUPPORT COLUMN LOCKING NUT ENERGY ABSORBER ASSEMBLY OFF-SET INSTRUMENTATION COLUMN SECONDARY CORE SUPPORT BUTT TYPE COLUMN INSTRUMENTATION GUIDE COLUMN (CRUCIFORM)

LOWER TIE PLATE

~UPPER TIE PLATE RADIAL SUPPORT KEY UPPER CORE BARREL ~"'.--LOWERCORE BARREL ------------.-.1 FIGURE 3.9N-8 LOWER CORE SUPPORT ASSEMBLY (CORE BARREL ASSEMBLY)

MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

,.. ~

... I,...A,

.... I,...A,

... I,...A,

,.. ~

.-~

,..~

I I-...

  • I-l

~1-1

-1-1 II II I
  • II II II

~..

~

~

I l'\\."","~

.~

/

~

/."

~

""'"~

r\\

~

II

~.

II...

~

t'I t'I I~

I.

t'I I

4 4

~

I II

~II fo..

"II t\\

I I

I I "

I "I

~I I

I I

I~

t'I I

~

\\.~ "

~

- ~ I-l:lI

~ -~ "

.... ~ III~ "

.... ~ I..bo I-t7 II:~ "

....r-t III:=

t I J

\\0-l I'l:~

I-ta I-b

  • l:-

I-I:-

-lD

-Ia II1:1 III:~

a ~

III~

III~

II=

la~

I

.~

I..':I

~

II~

II: ~

a::

II:~

=

I I -

I I

I I

!-t8

  • l:D II l:lI
  • ~

I a ~

  • l:-

Lcr ~

r rcr l~

L I~ ~

(~

(D (j

~~

(0

(~

to Lo.

..... JII L~ ~

~I'\\..... /4 (~... "r~.. "11\\ ~.. "..... I~ t\\

V

~

g r#l f-FIGURE 3.9N-9 UPPER CORE SUPPORT ASSEMBLY MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT I

'1 II It I

I I

FIGURE 3.9N-IO PLAN VIEW OF UPPER CORE SUPPORT ASSEMBLY MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

---"'"I***


(**

I*


(*

I**


(****


----(**

I I

I

- ------- ----C 1

I I

I**

---~

I I

I I*

BOLT (SEE DETAll A)

SPECIMEN BASKET (SEE DETAlLS C AND D)

LOWER NEUTRON SHIELD PANEl--

DOWEL PIN ----'

(SEE DETAIL B)

UPPER NEUTRON SHIELD PANEL flGlRE 3.9N-U NEUTRON SHIELD PANEL DESIGN WILLSTONE NUCLEAR POWER PLANT UNIT 3 FINAL SAFETY ANALYSIS REPORT JANUARY 1991

NEUTRON SHIELD PANEL i INCH SOCKET HEAD CAP SCREWS TYPICAL 7 PLACES PER SPECIMEN BASKET 28 PLACES TOTAL SPECIMEN \\

BASKET DETAIL A

~ INCH SOCKET HEAD CAP SCREW TYPICAL 16 PLACES PER PANEL 128 PLACES TOTAL NEUTRON SHIELD ~.

PANEL NEUTRON SHIELD PANEL

~ INCH DOWEL PINS TYPICAL 2 PLACES PER SPECIMEN BASKET 8 PLACES TOTAL SPECIMEN \\

BASKET DETAIL B

2~ INCH DOWEL PIN TYPICAL 3 PLACES PER PANEL 24 PLACES TOTAL Nt:.ufRON SHIELD ~

PANEL FIGURE 3.9N-12 NEUTRON SHIELD PANEL DESIGN DETAILS MILLSTONE NUCLEAR POWER PLANT UNIT 3 FINAL SAFETY ANALYSIS REPORT JANUARY 1991