ML17212A071: Difference between revisions
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| Line 21: | Line 21: | ||
1.7 1.6 1.5 en 0.. | 1.7 1.6 1.5 en 0.. | ||
w 1.4 rr | w 1.4 rr u, en | ||
u, en | |||
-1 en 0 w 0:: | -1 en 0 w 0:: | ||
1.3 0.. 1.5 3 .0 TIME(SEC) | 1.3 0.. 1.5 3 .0 TIME(SEC) | ||
| Line 50: | Line 48: | ||
I -. | I -. | ||
-~ oD | -~ oD | ||
~ TRAVEl.l'JG WATER SCREE~ | ~ TRAVEl.l'JG WATER SCREE~ | ||
\_ HEAD SHAF.!..T-+-#- --:..~~:tf'"re:::::_~ SEAWALL H---~ | \_ HEAD SHAF.!..T-+-#- --:..~~:tf'"re:::::_~ SEAWALL H---~ | ||
| Line 57: | Line 54: | ||
I | I | ||
. LifTING A ._._ ~ .... ~ -- | . LifTING A ._._ ~ .... ~ -- | ||
LUGS- ';-l~- --- o ** | LUGS- ';-l~- --- o ** | ||
-- --~+-. . . _- - -- - .... ~""'"'- | -- --~+-. . . _- - -- - .... ~""'"'- | ||
| Line 95: | Line 90: | ||
. 1-1= - c--- EXTREWE LOW LEVEL ELC-17 -0' . | . 1-1= - c--- EXTREWE LOW LEVEL ELC-17 -0' . | ||
~ | ~ | ||
~ . f- l- I-- ---==~=-OESIGN LOW LEVEL HC') 8'-0' FOR SERVICE WATER PUlo4PS ONLY | ~ . f- l- I-- ---==~=-OESIGN LOW LEVEL HC') 8'-0' FOR SERVICE WATER PUlo4PS ONLY | ||
+ r* o -,' ,. 60 to. WARM | + r* o -,' ,. 60 to. WARM | ||
...... ' WATER RECIRC I ~ ...... | ...... ' WATER RECIRC I ~ ...... | ||
I .... .. | I .... .. | ||
I .'. ,~ | I .'. ,~ | ||
. ,.,. . TEMPERItIG LINE | . ,.,. . TEMPERItIG LINE | ||
-: , I .* | -: , I .* | ||
qt ~ .~ | qt ~ .~ | ||
~ | ~ | ||
I I I | I I I | ||
)~( )=t\ )+( '. | )~( )=t\ )+( '. | ||
r I I r-EU-) 2a'-0' | r I I r-EU-) 2a'-0' | ||
,. .~ ~ .. I ~,~..r- | ,. .~ ~ .. I ~,~..r- | ||
~ \ , 't | ~ \ , 't | ||
.;,;~_. ':;.."" . ,," . ~ ~ - --,"" " | .;,;~_. ':;.."" . ,," . ~ ~ - --,"" " | ||
~ | ~ | ||
.. "': 7 - _.:.. ... | .. "': 7 - _.:.. ... | ||
: ~' ;~ '.~ !' | : ~' ;~ '.~ !' | ||
| Line 128: | Line 115: | ||
,....-"""":':":"-~I......-, | ,....-"""":':":"-~I......-, | ||
Ii | Ii | ||
, I | , I | ||
~~. i I r--- | |||
~~. i I | |||
r--- | |||
f- | f- | ||
* r"r: ~ | * r"r: ~ | ||
| Line 148: | Line 131: | ||
, - ~~ I '"I'" I I 4- | , - ~~ I '"I'" I I 4- | ||
~ | ~ | ||
SLUICE-GATE | SLUICE-GATE I | ||
I I | I I | ||
FLOW. ! | |||
I , ,#- .. .. | I , ,#- .. .. | ||
' : " . -. ~ .. ,. : "'--" | ' : " . -. ~ .. ,. : "'--" | ||
| Line 168: | Line 150: | ||
Figure 3.5-5 DELETED by FSARCR 02-MP3-13 | Figure 3.5-5 DELETED by FSARCR 02-MP3-13 | ||
!!r- | !!r-b, l ...... ---- | ||
b, l ...... ---- | |||
i - | i - | ||
, I ' c') | , I ' c') | ||
| Line 177: | Line 156: | ||
I .-.J j I | I .-.J j I | ||
1 ! 2' ::_. | 1 ! 2' ::_. | ||
.;...I~ ~ | .;...I~ ~ | ||
:- 5~__! *.} .. .:* ~l " | :- 5~__! *.} .. .:* ~l " | ||
.3 'i~ | .3 'i~ | ||
-t- | -t- | ||
/ / , I c., ~'~ -E L - ( - - - ' - '-.:-r-:- - ( .- : - ,- <[.- - ~- | / / , I c., ~'~ -E L - ( - - - ' - '-.:-r-:- - ( .- : - ,- <[.- - ~- | ||
| Line 189: | Line 164: | ||
L. | L. | ||
2 | 2 | ||
== _== V R ::::~OV. \!,'EST \\'AL ~ LOGS - -',' - - | == _== V R ::::~OV. \!,'EST \\'AL ~ LOGS - -',' - - | ||
2 -2 I ".. ,'tll" '3 C'~ ) * '.; ,~i-I B"" T 2-10' LG 'Ty D l "cl> (A-307j ':" NC~ 3:L..I~'- '6 . . :(i:'~) v~ , " i I- I FIGURE 3.5-6 MISSILE BARRIER BEAM COLUMN MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSI S REPORT AMENDMENT 3 AUG UST 19 83 | 2 -2 I ".. ,'tll" '3 C'~ ) * '.; ,~i-I B"" T 2-10' LG 'Ty D l "cl> (A-307j ':" NC~ 3:L..I~'- '6 . . :(i:'~) v~ , " i I- I FIGURE 3.5-6 MISSILE BARRIER BEAM COLUMN MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSI S REPORT AMENDMENT 3 AUG UST 19 83 | ||
| Line 197: | Line 171: | ||
HIGH ENERGY SYSTEMS LL. (BREAKS ONLY) | HIGH ENERGY SYSTEMS LL. (BREAKS ONLY) | ||
W 0:: | W 0:: | ||
~ | ~ | ||
0:: | 0:: | ||
| Line 207: | Line 180: | ||
HIGH ENERGY SYSTEMS (BREAKS ONLY) | HIGH ENERGY SYSTEMS (BREAKS ONLY) | ||
W 0:: | W 0:: | ||
!;t 0:: | !;t 0:: | ||
W 200 F ~---------. | W 200 F ~---------. | ||
| Line 239: | Line 211: | ||
-_.-,,,. *_--Il*****- ,3RSfffiS*E'C ;/ 3RSS*EI8 | -_.-,,,. *_--Il*****- ,3RSfffiS*E'C ;/ 3RSS*EI8 | ||
+ '-J- | + '-J- | ||
..,.. ,' :.,.*.*:~:.:*.*~i:4'~. :4 I | ..,.. ,' :.,.*.*:~:.:*.*~i:4'~. :4 I | ||
RHR HT 1 3RHS *EIB\ | RHR HT 1 3RHS *EIB\ | ||
EXCHANGER I ----* ' | EXCHANGER I ----* ' | ||
(TYP.) - - | (TYP.) - - | ||
FIGURE 3.6-4 RELATIVE LOCATIONS SAFETY RELATED EQUIPMENT | FIGURE 3.6-4 RELATIVE LOCATIONS SAFETY RELATED EQUIPMENT IL . 1I EL.51 1 -4" I | ||
IL . 1I EL.51 1 -4" I | |||
MILLSTONE NUCLEAR POWER STATION I | MILLSTONE NUCLEAR POWER STATION I | ||
I UNIT 3 I | I UNIT 3 I | ||
| Line 271: | Line 239: | ||
't -- - | 't -- - | ||
~l+1 II-rf --------....+ --3 V SHIELD WALL", , | ~l+1 II-rf --------....+ --3 V SHIELD WALL", , | ||
(TY P. 1 r ~J b::-:::-::ilf=-::c::f--,--_t | (TY P. 1 r ~J b::-:::-::ilf=-::c::f--,--_t I 1-- | ||
I 1-- | |||
\ 1- -;/ | \ 1- -;/ | ||
1 | 1 b:.:-----~_t-SHIELD WALL EL. 20'*0" I | ||
b:.:-----~_t-SHIELD WALL | |||
EL. 20'*0" I | |||
'~N/-='/4VA~/Ji ~.',...~.-...====~ | '~N/-='/4VA~/Ji ~.',...~.-...====~ | ||
~ ~ | ~ ~ | ||
RECOMBINER BUILDING | RECOMBINER BUILDING | ||
~ | ~ | ||
B | B b,'" | ||
b,'" | |||
SAFETY INJECTlON _ _ | SAFETY INJECTlON _ _ | ||
ACCUMULATOR TANK ----:-:- <, | ACCUMULATOR TANK ----:-:- <, | ||
| Line 298: | Line 258: | ||
UNIT 3 1 1 FINAL SAFETY ANALYSIS REPORT | UNIT 3 1 1 FINAL SAFETY ANALYSIS REPORT | ||
~ REACTOR | ~ REACTOR CONTAINMENT STRUCTURE 1 | ||
CONTAINMENT STRUCTURE 1 | |||
POLAR CRANE 3MHR - CRNI - 540 TON I | POLAR CRANE 3MHR - CRNI - 540 TON I | ||
i | i | ||
| Line 324: | Line 282: | ||
1" ,; 0;1 I r-T"'=':------' | 1" ,; 0;1 I r-T"'=':------' | ||
~ | ~ | ||
~'~!bd ! | ~'~!bd ! | ||
REJTOR | REJTOR | ||
| Line 338: | Line 295: | ||
j~:"; .~\, | j~:"; .~\, | ||
.il | .il | ||
~ 4' | ~ 4' EL.36'-6"7 3QSS*P3A 3QSS*P3B QUENCH SPRAY PUMP (TYP) | ||
P 3S\;A ~ 3S'Hi l.. EL.21'-6"7 | |||
EL.36'-6"7 3QSS*P3A 3QSS*P3B QUENCH SPRAY PUMP (TYP) | |||
P 3S\;A ~ 3S'Hi | |||
l.. EL.21'-6"7 | |||
/' '\ | /' '\ | ||
A' ~ &; | A' ~ &; | ||
| Line 380: | Line 333: | ||
SEE TABLE 3.6-6, | SEE TABLE 3.6-6, | ||
: 3. A PIPE B~EAK EXCLUSION ZONE EXTENDS FROM THE INBOARD SIDE OF THE CONTAINMENT PENETRATIONS TO THE LINE WALL. | : 3. A PIPE B~EAK EXCLUSION ZONE EXTENDS FROM THE INBOARD SIDE OF THE CONTAINMENT PENETRATIONS TO THE LINE WALL. | ||
FIGURE 3.6-8 MAIN STEAM SYSTEM MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FILE: 368.dgn/368.clt | FIGURE 3.6-8 MAIN STEAM SYSTEM MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FILE: 368.dgn/368.clt JANUARY 1'398 --J | ||
JANUARY 1'398 --J | |||
MPS-3 FSAR NOTES TO FIGURE 3.6-8 DATA FOR PIPE RUPTURE RESTRAINTS - MAIN STEAM SYSTEM Restraint Distance from N-S Distance from E-W Identification Break # Elevation Containment Containment Restraint Type Function of the Pipe Rupture Restraint 3MSS-PRR1LA (1) 66'-3" 53'-3" West 21'-8" South Limit Stop & Strap Prevent pipe whip into Crane Wall & Liner 3MSS-PRR2LA 2 66'-3" 45'-10" West 32'-2" South Sleeve in Crane Wall Protect Crane Wall 3MSS-PRR3LA 3 71'-8" 42'-6" West 34'-10" South Omni-Directional (2) 3MSS-PRR4LA 1&2 87'-6" 42'-6" West 34'-10" South Omni-Directional Prevent whip into Crane Wall 3MSS-PRR5LA 2 93'-6" 39'-3" West 38'-6" South Omni-Directional Prevent whip into Polar Crane Support 3MSS-PRR7LA 1 93'-6" 35'-11" East 20'-11" South Laminated Strap Prevent whip into Polar Crane Support 3MSS-PRR8LA 1, 2, & 3 93'-6" 14'-3" West 53'-2" South Limit Stop Prevent whip into Crane Wall 3MSS-PRR9LA 1, 2, & 3 93'-6" 14'-3" East 53'-2" South Limit Stop Prevent whip into Crane Wall 3MSS-PRR3SB (3) 66'-3" 52'-2" West 17'-5" South Omni-Directional Prevent whip into Steam Generator Supports 3MSS-PRR5SB 3 72'-6" 48'-11" West 25'-2" South Omni-Directional Prevent whip into Crane Wall 3MSS-PRR6SB 2 88'-9" 39'-3" West 18'-6" South Laminated Strap Prevent whip into Crane Wall 3MSS-PRR7SB 1 88'-9" 39'-3" West 18'-6" South Laminated Strap Prevent whip into Polar Crane Support 3MSS-PRR3SC (3) 66'-3" 52'-2" West 17'-5" North Omni-Directional Prevent whip into Steam Generator Supports 3MSS-PRR5SC 3 72'-6" 48'-11" West 25'-2" North Omni-Directional Prevent whip into Crane Wall 3MSS-PRR6SC 2 88'-9" 39'-3" West 18'-6" North Laminated Strap Prevent whip into Crane Wall 3MSS-PRR7SC 1 88'-9" 39'-3" West 18'-6" North Laminated Strap Prevent whip into Polar Crane Support 3MSS-PRR1LD (1) 66'-3" 53'-3" West 21'-8" North Limit Stop & Strap Prevent pipe whip into Crane Wall & Liner 3MSS-PRR2LD 2 66'-3" 45'-10" West 32'-2" North Sleeve in Crane Wall Protect Crane Wall 3MSS-PRR3LD 3 71'-8" 42'-6" West 34'-10" North Omni-Directional (2) 1 of 4 Rev. 16 | MPS-3 FSAR NOTES TO FIGURE 3.6-8 DATA FOR PIPE RUPTURE RESTRAINTS - MAIN STEAM SYSTEM Restraint Distance from N-S Distance from E-W Identification Break # Elevation Containment Containment Restraint Type Function of the Pipe Rupture Restraint 3MSS-PRR1LA (1) 66'-3" 53'-3" West 21'-8" South Limit Stop & Strap Prevent pipe whip into Crane Wall & Liner 3MSS-PRR2LA 2 66'-3" 45'-10" West 32'-2" South Sleeve in Crane Wall Protect Crane Wall 3MSS-PRR3LA 3 71'-8" 42'-6" West 34'-10" South Omni-Directional (2) 3MSS-PRR4LA 1&2 87'-6" 42'-6" West 34'-10" South Omni-Directional Prevent whip into Crane Wall 3MSS-PRR5LA 2 93'-6" 39'-3" West 38'-6" South Omni-Directional Prevent whip into Polar Crane Support 3MSS-PRR7LA 1 93'-6" 35'-11" East 20'-11" South Laminated Strap Prevent whip into Polar Crane Support 3MSS-PRR8LA 1, 2, & 3 93'-6" 14'-3" West 53'-2" South Limit Stop Prevent whip into Crane Wall 3MSS-PRR9LA 1, 2, & 3 93'-6" 14'-3" East 53'-2" South Limit Stop Prevent whip into Crane Wall 3MSS-PRR3SB (3) 66'-3" 52'-2" West 17'-5" South Omni-Directional Prevent whip into Steam Generator Supports 3MSS-PRR5SB 3 72'-6" 48'-11" West 25'-2" South Omni-Directional Prevent whip into Crane Wall 3MSS-PRR6SB 2 88'-9" 39'-3" West 18'-6" South Laminated Strap Prevent whip into Crane Wall 3MSS-PRR7SB 1 88'-9" 39'-3" West 18'-6" South Laminated Strap Prevent whip into Polar Crane Support 3MSS-PRR3SC (3) 66'-3" 52'-2" West 17'-5" North Omni-Directional Prevent whip into Steam Generator Supports 3MSS-PRR5SC 3 72'-6" 48'-11" West 25'-2" North Omni-Directional Prevent whip into Crane Wall 3MSS-PRR6SC 2 88'-9" 39'-3" West 18'-6" North Laminated Strap Prevent whip into Crane Wall 3MSS-PRR7SC 1 88'-9" 39'-3" West 18'-6" North Laminated Strap Prevent whip into Polar Crane Support 3MSS-PRR1LD (1) 66'-3" 53'-3" West 21'-8" North Limit Stop & Strap Prevent pipe whip into Crane Wall & Liner 3MSS-PRR2LD 2 66'-3" 45'-10" West 32'-2" North Sleeve in Crane Wall Protect Crane Wall 3MSS-PRR3LD 3 71'-8" 42'-6" West 34'-10" North Omni-Directional (2) 1 of 4 Rev. 16 | ||
| Line 422: | Line 373: | ||
OF IilUPTURE RESTRAINTS INSIDE AND OUTSIDE CONTAINMENT STRUCTURE, SEE FIGURE 3.6*11. | OF IilUPTURE RESTRAINTS INSIDE AND OUTSIDE CONTAINMENT STRUCTURE, SEE FIGURE 3.6*11. | ||
: 5. A TERMINAL END BREAK IS POSTULATED ON EACH MAIN FEEDWATER LINE AT THE F LINE WALL IN THE MAIN STEAM VALVE BUILDING. THIS TERMINAL END BREAK DEFINES THE EXTREMITY OF THE BREAK EXCUSION ZONE. | : 5. A TERMINAL END BREAK IS POSTULATED ON EACH MAIN FEEDWATER LINE AT THE F LINE WALL IN THE MAIN STEAM VALVE BUILDING. THIS TERMINAL END BREAK DEFINES THE EXTREMITY OF THE BREAK EXCUSION ZONE. | ||
FIGURE 3.6-10 FEEOWATER SYSTEM POSTULATED PIPE RUPTURE LOCATIONS MILLSTONE NUCLEAR POWER STATION UNIT3 FINAL SAFETY ANALYSIS REPORT CAD FILE:361O.dgn/361O.clt | FIGURE 3.6-10 FEEOWATER SYSTEM POSTULATED PIPE RUPTURE LOCATIONS MILLSTONE NUCLEAR POWER STATION UNIT3 FINAL SAFETY ANALYSIS REPORT CAD FILE:361O.dgn/361O.clt | ||
| Line 553: | Line 503: | ||
THRUST DEVELOPMENT | THRUST DEVELOPMENT | ||
,. )0 PIPE WHIP PIPE DYNAMICS | ,. )0 PIPE WHIP PIPE DYNAMICS | ||
** ,r PIPE-RESTRAINT PI PE-CONCRETE INTERACTION WALL IMPACT | ** ,r PIPE-RESTRAINT PI PE-CONCRETE INTERACTION WALL IMPACT INTERACTION FORCE, (SOFT-SOFT) INERTIAL LOADS (SOFT- HARD) | ||
INTERACTION FORCE, (SOFT-SOFT) INERTIAL LOADS (SOFT- HARD) | |||
LOCAL EFFECTS | LOCAL EFFECTS | ||
" LOCAL | " LOCAL | ||
>-,MPACT 1--------------- | >-,MPACT 1--------------- | ||
PENETRATION SPALL LOCAL WALL RESPONSE STRUCTURAL ADEQUACY | PENETRATION SPALL LOCAL WALL RESPONSE STRUCTURAL ADEQUACY STRUCTURAL RESPONSE FULL | ||
STRUCTURAL RESPONSE FULL | |||
---------------------- )0 STRUCTURE RESPONSE AND INTERACTION STRUCTURAL ADEQUACY RESPONSE FIGURE 3.6-19 PIPE RUPTURE ANALYSIS FLOW CHART MILLSTONE NUCLEAR POWER STAnON UNIT 3 FINAL SAFETY ANALYSIS REPORT | ---------------------- )0 STRUCTURE RESPONSE AND INTERACTION STRUCTURAL ADEQUACY RESPONSE FIGURE 3.6-19 PIPE RUPTURE ANALYSIS FLOW CHART MILLSTONE NUCLEAR POWER STAnON UNIT 3 FINAL SAFETY ANALYSIS REPORT | ||
2.0 | 2.0 | ||
~ | ~ | ||
-1<t1. 6 | -1<t1. 6 u-a.. | ||
u-a.. | |||
t | t | ||
(/) | (/) | ||
| Line 576: | Line 520: | ||
0::: | 0::: | ||
:I: | :I: | ||
t- 1.2 | t- 1.2 1.26 Z | ||
1.26 Z | |||
~ | ~ | ||
o | o | ||
~ ~~STEADY STATE o SLOWDOWN | ~ ~~STEADY STATE o SLOWDOWN | ||
~ | ~ | ||
o ffiO.S | o ffiO.S o | ||
o | |||
<t W | <t W | ||
t | t | ||
| Line 603: | Line 542: | ||
, . - l>.. | , . - l>.. | ||
~'" '£:I. . . . | ~'" '£:I. . . . | ||
. . '. : _ " ,'0." | . . '. : _ " ,'0." | ||
. '~ , " -,.' | . '~ , " -,.' | ||
@ A' . | @ A' . | ||
r/ . , , | r/ . , , | ||
\:-.'"./>. | \:-.'"./>. | ||
uC1l . | uC1l . | ||
~ , ' | ~ , ' | ||
VI | VI ro . . . 4. ~. | ||
ro . . . 4. ~. | |||
0 | 0 | ||
,','. Y". '. . '. '. | ,','. Y". '. . '. '. | ||
c: - )( | c: - )( | ||
LiJ ".~ .' >.. b. | LiJ ".~ .' >.. b. | ||
<, ~ | <, ~ | ||
I MODELED AS A SIMPLE SUPPORT IN THE DYNAMIC :.' \;>' ',.', - : 'V '. | I MODELED AS A SIMPLE SUPPORT IN THE DYNAMIC :.' \;>' ',.', - : 'V '. | ||
ANALYSIS .. ", " .. ' . | ANALYSIS .. ", " .. ' . | ||
---- (\J | ---- (\J | ||
~-+-----~INTERMEDIATE STRUCTURE 1'-1 .c: | ~-+-----~INTERMEDIATE STRUCTURE 1'-1 .c: | ||
(\J r<>~ | (\J r<>~ | ||
CO.o INTERNAL PRESSURE FOR CE DISTRI BUTED ALONG THE ELBOW_~'vl | CO.o INTERNAL PRESSURE FOR CE DISTRI BUTED ALONG THE ELBOW_~'vl FIGURE 3.6-21 PIPE, RESTRAINT, INTERM EDIATE STRUCTURE SYSTEM ATTACHED TO THE MATHEMATICAL MODEL STEAM GENERATOR . . .: | ||
FIGURE 3.6-21 PIPE, RESTRAINT, INTERM EDIATE STRUCTURE SYSTEM ATTACHED TO THE MATHEMATICAL MODEL STEAM GENERATOR . . .: | |||
:',~: ' . :.:,:~,...: ~.'>':>.:".~:' ~: MILLSTONE NUCLEAR POWER STATION UNIT 3 oo{. " ,-. | :',~: ' . :.:,:~,...: ~.'>':>.:".~:' ~: MILLSTONE NUCLEAR POWER STATION UNIT 3 oo{. " ,-. | ||
FINAL SAFETY ANALYSIS REPORT | FINAL SAFETY ANALYSIS REPORT | ||
| Line 645: | Line 575: | ||
sr -20. | sr -20. | ||
0 | 0 | ||
( J) | ( J) | ||
Z 0 -40. | Z 0 -40. | ||
f 0 | f 0 | ||
w 0:: | w 0:: | ||
f-W -60. | f-W -60. | ||
| Line 670: | Line 598: | ||
LCl | LCl | ||
-10. | -10. | ||
0 | 0 (J) | ||
(J) | |||
Z 0 -30. | Z 0 -30. | ||
I | I | ||
<.) | <.) | ||
w 0:: | w 0:: | ||
I W -50. | I W -50. | ||
| Line 686: | Line 611: | ||
180 160 140 120 v | 180 160 140 120 v | ||
0 100 | 0 100 (II | ||
(II | |||
...J lJJ (J | ...J lJJ (J | ||
0: 80 0 | 0: 80 0 | ||
| Line 699: | Line 622: | ||
<;t o | <;t o | ||
r-4uO. | r-4uO. | ||
cD | |||
.....J I | .....J I | ||
Z 320. | Z 320. | ||
<.? | <.? | ||
0:: | 0:: | ||
| Line 710: | Line 632: | ||
:'Q'. ~.: | :'Q'. ~.: | ||
fl.' | fl.' | ||
.'<1. | .'<1. | ||
<l | <l | ||
| Line 728: | Line 649: | ||
: ~'.: .' :II------r-~J_. | : ~'.: .' :II------r-~J_. | ||
.4,' : \;!: L..-_-~INTERMEDIATE STRUCTURE | .4,' : \;!: L..-_-~INTERMEDIATE STRUCTURE | ||
**.*4* | **.*4* | ||
, t;, . | , t;, . | ||
| Line 746: | Line 666: | ||
1-' | 1-' | ||
I I | I I | ||
~- ---~ | ~- ---~ | ||
I I | I I | ||
~ | ~ | ||
lSEE DETAIL "A" | lSEE DETAIL "A" | ||
- - - - - - +- - - - - - | - - - - - - +- - - - - - | ||
| Line 780: | Line 698: | ||
INTEGRAL WELDED ATTACHMENTS ARE NOT UTILIZED ON THE DRAIN LINES. | INTEGRAL WELDED ATTACHMENTS ARE NOT UTILIZED ON THE DRAIN LINES. | ||
: 3. PIPING GEOMETRY FOR THE REACTOR COOLANT SYSTEM LOOP FILL LINES ARE TYPICAL IN EACH STEAM GENERA TOR CUBICLE* | : 3. PIPING GEOMETRY FOR THE REACTOR COOLANT SYSTEM LOOP FILL LINES ARE TYPICAL IN EACH STEAM GENERA TOR CUBICLE* | ||
~ ''I.~''';'' .--_ -_~':'~.c::;~~~'~':'::'''':'.~. :.'' | ~ ''I.~''';'' .--_ -_~':'~.c::;~~~'~':'::'''':'.~. :.'' | ||
:~ .:*:*r*#*,~* - --= PIPE RUPTURE LOCATIONS ON THIS PIPING ARE POSTULATED TO OCCUR AT ANY TERMINAL END VALVE OR FITTING. INTEGRAL WELDED | :~ .:*:*r*#*,~* - --= PIPE RUPTURE LOCATIONS ON THIS PIPING ARE POSTULATED TO OCCUR AT ANY TERMINAL END VALVE OR FITTING. INTEGRAL WELDED | ||
| Line 824: | Line 741: | ||
SCALE :3":/'-O" | SCALE :3":/'-O" | ||
< ~.: :<,.~. | < ~.: :<,.~. | ||
',..:=.': .' | ',..:=.': .' | ||
~~ . : ~;. | ~~ . : ~;. | ||
REF.R . : 7 0 ' - O " - - - - - 1 3/8" LINER -----o-{I--- | REF.R . : 7 0 ' - O " - - - - - 1 3/8" LINER -----o-{I--- | ||
| Line 851: | Line 766: | ||
SHEA R ASSEM BLY ------1If---Hi8=--I!/,Y'/.JIII FIGURE 3.8-5 REINF. AROUND MAIN STEAM PENETRATIONS MILLSTONE NUCLEAR POWER STATION UN-IT 3 FINAL SAFETY ANALYSIS REPORT 6-6 (E-I) | SHEA R ASSEM BLY ------1If---Hi8=--I!/,Y'/.JIII FIGURE 3.8-5 REINF. AROUND MAIN STEAM PENETRATIONS MILLSTONE NUCLEAR POWER STATION UN-IT 3 FINAL SAFETY ANALYSIS REPORT 6-6 (E-I) | ||
70 -0 R 4 -6 | 70 -0 R 4 -6 LI NER 1'-3" A | ||
'1,*-,* No 18 CIRC BARS r - EXTRA DIAG e. VERT REINF | '1,*-,* No 18 CIRC BARS r - EXTRA DIAG e. VERT REINF | ||
~.q) FUEL T RANSFER TUB E | ~.q) FUEL T RANSFER TUB E | ||
| Line 879: | Line 792: | ||
N (J) GROUPS OF :3 '" '" '" '" | N (J) GROUPS OF :3 '" '" '" '" | ||
[0 <:: G G ~ °CD a: IWo "e p CD e=J I <l: ' | [0 <:: G G ~ °CD a: IWo "e p CD e=J I <l: ' | ||
~~ ~0 ~ | ~~ ~0 ~ | ||
CD ~cr . ..,..--... | CD ~cr . ..,..--... | ||
o | o l:> E: 8 ~ E: | ||
l:> E: 8 ~ E: | |||
~og e p E 00 e o | ~og e p E 00 e o | ||
0 e | 0 e | ||
| Line 897: | Line 807: | ||
: * -<:: ' (!) :> El ' '- No, 6 STIRRUPS TYP VERT REINF--! | : * -<:: ' (!) :> El ' '- No, 6 STIRRUPS TYP VERT REINF--! | ||
.0' | .0' | ||
~. ~ m g~e~ t::-..A ; I | ~. ~ m g~e~ t::-..A ; I | ||
.:,':1. *' . r .:...:~; 7 '-0" OI A | .:,':1. *' . r .:...:~; 7 '-0" OI A | ||
| Line 917: | Line 826: | ||
#18E XTRA DIAG. REINF. I~ #18 TYP. V ERT. REINF. | #18E XTRA DIAG. REINF. I~ #18 TYP. V ERT. REINF. | ||
I | I | ||
#IS TYP. VERT. REINE - -to I r --~ 18 CIRC BARS | #IS TYP. VERT. REINE - -to I r --~ 18 CIRC BARS I | ||
g~, '18 TYP. D lAG. REINE r. | |||
: t. #14 V ERT REINF. EXTRA I | : t. #14 V ERT REINF. EXTRA I | ||
:~.:.-:'; | :~.:.-:'; | ||
| Line 942: | Line 850: | ||
8 Q u G CD #6 <Cl12" TRANSVERSE STIRRUPS | 8 Q u G CD #6 <Cl12" TRANSVERSE STIRRUPS | ||
~ | ~ | ||
G o 1Jl ° ° G c U - | G o 1Jl ° ° G c U - | ||
IN GROUPS OF 3 p " 08 0 o | IN GROUPS OF 3 p " 08 0 o | ||
| Line 951: | Line 858: | ||
:~& '" E :." | :~& '" E :." | ||
~ ~.6 'nlB,CD : ... | ~ ~.6 'nlB,CD : ... | ||
.0:' h.>. | .0:' h.>. | ||
s 1~1~ '--4"j a | s 1~1~ '--4"j a | ||
| Line 976: | Line 882: | ||
..... V~ | ..... V~ | ||
-- -- I--- | -- -- I--- | ||
-i f-4"-an - .-- | -i f-4"-an - .-- | ||
j | j | ||
| Line 985: | Line 890: | ||
PEDESTAL TYPE-) | PEDESTAL TYPE-) | ||
6 REQUIRED -'--- | 6 REQUIRED -'--- | ||
I" 4 2 1'_lt 8 | I" 4 2 1'_lt 8 14 2 f -, | ||
14 2 f -, | |||
r I"~ | r I"~ | ||
PLAN 8 (E -2.) | PLAN 8 (E -2.) | ||
| Line 1,007: | Line 910: | ||
.. 16 .. | .. 16 .. | ||
3-8" CRANE WALL TOP OF CONC EL.l05 '7" | 3-8" CRANE WALL TOP OF CONC EL.l05 '7" | ||
.......,I......~ REFERENCE | .......,I......~ REFERENCE | ||
____++r~f-+--=L=INE; __ | ____++r~f-+--=L=INE; __ | ||
:.'f'. | :.'f'. | ||
~~: | ~~: | ||
li. RAIL £. WHEELS KEY PLAN DOME MAINTENANCE TRUSS I PARKED POSITIO N FIGUR E 3.8-12 ELEVATION DOME MAIN TENA NCE TRUS S MILLS TONE NUCLE AR POWER STATI ON UNIT 3 FINAL SAFET Y ANALY SIS REPORT | li. RAIL £. WHEELS KEY PLAN DOME MAINTENANCE TRUSS I PARKED POSITIO N FIGUR E 3.8-12 ELEVATION DOME MAIN TENA NCE TRUS S MILLS TONE NUCLE AR POWER STATI ON UNIT 3 FINAL SAFET Y ANALY SIS REPORT | ||
| Line 1,026: | Line 923: | ||
~~A=.~=,,=.~~~~ | ~~A=.~=,,=.~~~~ | ||
T EST MEMBER I AT KNUCKLE 4' | T EST MEMBER I AT KNUCKLE 4' | ||
r CONC. REBAR PLATE JOINT 6"RING I | r CONC. REBAR PLATE JOINT 6"RING I | ||
----Ji 69'-11!i RAO'----l n I 70'- 2/i" RAO!REF. | ----Ji 69'-11!i RAO'----l n I 70'- 2/i" RAO!REF. | ||
| Line 1,037: | Line 933: | ||
[, BLIND FLANGE VALVE | [, BLIND FLANGE VALVE | ||
'::.~p.~" .: | '::.~p.~" .: | ||
.,~:, | .,~:, | ||
JOINT TUBE PLAN- FUEL TRANSFER PENETRATION | JOINT TUBE PLAN- FUEL TRANSFER PENETRATION | ||
| Line 1,067: | Line 962: | ||
CONC 4"6" WAL.L. | CONC 4"6" WAL.L. | ||
REr: | REr: | ||
HORIZONTAL 't (4) 3/4" PIPES | HORIZONTAL 't (4) 3/4" PIPES t TEST HOLE TYP FIGURE 3.8 17 MULTIPLE PIPE PENETRATION ASSEMBLY MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 15 SEPTEMBER 1985 | ||
t TEST HOLE TYP FIGURE 3.8 17 MULTIPLE PIPE PENETRATION ASSEMBLY MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 15 SEPTEMBER 1985 | |||
PLAN SINGLE RADIAL PENETRATION THRU LINER FIGURE 3.8-18 UNSLEEVED PIPING PENETRATION MILLSTONE NUCLEAR POWER STATION UNIT 3 FI NAL SAFETY ANALYSIS REPORT AMENDMENT 15 SEPTEMBER 1985 | PLAN SINGLE RADIAL PENETRATION THRU LINER FIGURE 3.8-18 UNSLEEVED PIPING PENETRATION MILLSTONE NUCLEAR POWER STATION UNIT 3 FI NAL SAFETY ANALYSIS REPORT AMENDMENT 15 SEPTEMBER 1985 | ||
| Line 1,082: | Line 975: | ||
BELLOWS 6'-0"REF 4'-10~"REF | BELLOWS 6'-0"REF 4'-10~"REF | ||
'l 2'- 0" | 'l 2'- 0" | ||
~~~~m~u~~ff | ~~~~m~u~~ff | ||
:~ * .* .. A,lito | :~ * .* .. A,lito | ||
| Line 1,091: | Line 982: | ||
...!..."x ,..!.." 3 REOUIRED 2 2 ELEVATION LOOKING EAST FIGURE 3.8-20 FUEL TRANSFER TUBE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 2 APRIL 1983 | ...!..."x ,..!.." 3 REOUIRED 2 2 ELEVATION LOOKING EAST FIGURE 3.8-20 FUEL TRANSFER TUBE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 2 APRIL 1983 | ||
68' -9" RAO--l\,-----l:~f;: | 68' -9" RAO--l\,-----l:~f;: | ||
15'-0" 1 - 4 11 PARTING ~ 2 LINE 3'-6" REF INSIDE CONTAINMENT HI NGE _ _'---*Iii+l1 o AUXILIARY BUILDING | 15'-0" 1 - 4 11 PARTING ~ 2 LINE 3'-6" REF INSIDE CONTAINMENT HI NGE _ _'---*Iii+l1 o AUXILIARY BUILDING | ||
| Line 1,097: | Line 987: | ||
_I r-FLOOR El. | _I r-FLOOR El. | ||
24'-6"---~ -:;- ,.. | 24'-6"---~ -:;- ,.. | ||
r---FLOOR EL.24'-6" FLOO R :~: -;. .. :i: ::'''":'" *.: | |||
r---FLOOR EL.24'-6" | |||
FLOO R :~: -;. .. :i: ::'''":'" *.: | |||
~?~:\ EL. 25'-3'; .-: r.:.... | ~?~:\ EL. 25'-3'; .-: r.:.... | ||
INSIDE CONTAINMENT - - - - | INSIDE CONTAINMENT - - - - | ||
| Line 1,110: | Line 995: | ||
* NOVEMBER 1997 | * NOVEMBER 1997 | ||
I Sll 18 - llji MIN. | I Sll 18 - llji MIN. | ||
70'- O"RAD TO It REACTOR ARC LENGTH /- | 70'- O"RAD TO It REACTOR ARC LENGTH /- | ||
| Line 1,152: | Line 1,036: | ||
: :.'0.': | : :.'0.': | ||
FACE OF ROCK EXCAVATION- .~:*.. ~.~.~: | FACE OF ROCK EXCAVATION- .~:*.. ~.~.~: | ||
RING GIRDER ------~....;..:..- | RING GIRDER ------~....;..:..- | ||
.. ~:. ~O:. | .. ~:. ~O:. | ||
;~:>:-: | ;~:>:-: | ||
WATERPROOFING MEMBRANE - - - + . . ,*.* -*-*-C)-+ --11 | WATERPROOFING MEMBRANE - - - + . . ,*.* -*-*-C)-+ --11 2" SEAL COAT ,. | ||
(above and below *0 :.'.. -. - - - + - - - - - - DETAIL A membrane) 4"- # 4 CRUSHED STONE CONCRETE B L C C K - - - - - + i CONTAINMENT STRUCTURE FOUNDATION MAT POROUS MAT ERIAL.-----l~;;;=;:;========~~;;;;=:==\ | (above and below *0 :.'.. -. - - - + - - - - - - DETAIL A membrane) 4"- # 4 CRUSHED STONE CONCRETE B L C C K - - - - - + i CONTAINMENT STRUCTURE FOUNDATION MAT POROUS MAT ERIAL.-----l~;;;=;:;========~~;;;;=:==\ | ||
LEVELING CONCRETE FIGURE 3.8-23 (2 OF 2) | LEVELING CONCRETE FIGURE 3.8-23 (2 OF 2) | ||
| Line 1,184: | Line 1,064: | ||
MATER IAL | MATER IAL | ||
';:;.>. v: --RA DIAL WALL I I | ';:;.>. v: --RA DIAL WALL I I | ||
~~1----+--11 EXT RA HORIZ | ~~1----+--11 EXT RA HORIZ (4" L AYER) 4 " COMPRESSIBLE-+-------:.... I | ||
(4" L AYER) 4 " COMPRESSIBLE-+-------:.... I | |||
-Y-3'-0" MATERIAL f----+~ 8 DOWELS 31+----1----'--'- | -Y-3'-0" MATERIAL f----+~ 8 DOWELS 31+----1----'--'- | ||
~ r EL r-: 12 '- 6 " | ~ r EL r-: 12 '- 6 " | ||
.-4-"+-+-11 EXT RA HORIZ (4" LAYER ) | .-4-"+-+-11 EXT RA HORIZ (4" LAYER ) | ||
-.+f----+RIN G GIRDER 7 9'-d' R --+----+++--~I J---Ht---t-- 11 TARPAPER SLI P rL S U R ~A C E ( 2 LAYERS) | -.+f----+RIN G GIRDER 7 9'-d' R --+----+++--~I J---Ht---t-- 11 TARPAPER SLI P rL S U R ~A C E ( 2 LAYERS) | ||
BOT OF RING GIRDER | BOT OF RING GIRDER | ||
' p' d ' | ' p' d ' | ||
,<. ~:. '.~ | ,<. ~:. '.~ | ||
| Line 1,206: | Line 1,081: | ||
I I I q. | I I I q. | ||
SCALE FEET 4-4 ': :'~,:,":; rESF BLDG MAT | SCALE FEET 4-4 ': :'~,:,":; rESF BLDG MAT | ||
' , ' '-;,.~. :- | ' , ' '-;,.~. :- | ||
3-3 6" WATERSTOP FROM TOP OF CONTMT STRUCT MAT TO TOP OF RING GIRDER RING GIRDER CONCRETE FILL PIECE OF 9 WATERSTOP ( FROM TOP OF CONTMT STRUCT MAT) | 3-3 6" WATERSTOP FROM TOP OF CONTMT STRUCT MAT TO TOP OF RING GIRDER RING GIRDER CONCRETE FILL PIECE OF 9 WATERSTOP ( FROM TOP OF CONTMT STRUCT MAT) | ||
| Line 1,232: | Line 1,106: | ||
0.3 ( K/FT ) | 0.3 ( K/FT ) | ||
-0." | -0." | ||
. - 152.2 | . - 152.2 1 190.S (K/FT) (10U1 IUFT ) rI111.0 KIF T 0 | ||
1 190.S (K/FT) (10U1 IUFT ) rI111.0 KIF T 0 | |||
to-Z UJ 2 | to-Z UJ 2 | ||
a:: to- Z 0 a: | a:: to- Z 0 a: | ||
| Line 1,249: | Line 1,121: | ||
t WAT 2151.80 300 WAT 2000 1500 ISO 1000 SOO 0 0 500 1000 ISO 1500 RADIAL ~O~ENT SHEAR 2000 IK-FT/FTl I K/F T1 300 t WAT t WAT 10 20 30 40 SO 60 70 10 20 30 40 SO 60 70 I I I I [ | t WAT 2151.80 300 WAT 2000 1500 ISO 1000 SOO 0 0 500 1000 ISO 1500 RADIAL ~O~ENT SHEAR 2000 IK-FT/FTl I K/F T1 300 t WAT t WAT 10 20 30 40 SO 60 70 10 20 30 40 SO 60 70 I I I I [ | ||
I I I I I RAD IUS 1FT 1 I RAD I US (F T) | I I I I I RAD IUS 1FT 1 I RAD I US (F T) t WAT ....9.05 t WAT MAT/STRUCTURE INTERACTION 10.5 (FT-K/FT I 5.0 1~02 0 300 | ||
t WAT ....9.05 t WAT MAT/STRUCTURE INTERACTION 10.5 (FT-K/FT I 5.0 1~02 0 300 | |||
~~ | ~~ | ||
~ | ~ | ||
I K/FT I | I K/FT I 0.3 177 .2 150 1 | ||
0.3 | |||
177 .2 150 1 | |||
0 1"'" | 0 1"'" | ||
(I(lF T I (I(lFT IOU I 1'' ' | (I(lF T I (I(lFT IOU I 1'' ' | ||
| Line 1,283: | Line 1,149: | ||
-l 0.3 20 1. 2 | -l 0.3 20 1. 2 | ||
~ | ~ | ||
150 190 . 5 I K/FT I KIF T I>DU I I KIP l | 150 190 . 5 I K/FT I KIF T I>DU I I KIP l | ||
I-z uJ | I-z uJ | ||
| Line 1,296: | Line 1,161: | ||
~ ~~ | ~ ~~ | ||
0.8 | 0.8 | ||
.. I KIF T I | .. I KIF T I O. I 117.6 1,0*.' I.Uj a | ||
O. I | |||
117.6 1,0*.' I.Uj a | |||
IIt1FT I I kIF 1 I | IIt1FT I I kIF 1 I | ||
....z r"" | ....z r"" | ||
I Kif 1 I.IJ | I Kif 1 I.IJ | ||
:II a:: | :II a:: | ||
e a:: | |||
z U | |||
e | e | ||
~ | ~ | ||
I.IJ Z ...J ....Z< | I.IJ Z ...J ....Z< | ||
< e; < -l I SO = | < e; < -l I SO = | ||
I.IJ II: 0 II: en U U TANGENTIAL MOMENT IK-FT/FTl FIGURE 3.8- 28 CONTAINMENT STRUCTURE MAT LOADING MOMENT AND SHEAR DIAGRAMS DL +1.15P MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT | I.IJ II: 0 II: en U U TANGENTIAL MOMENT IK-FT/FTl FIGURE 3.8- 28 CONTAINMENT STRUCTURE MAT LOADING MOMENT AND SHEAR DIAGRAMS DL +1.15P MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT | ||
| Line 1,327: | Line 1,183: | ||
2 ISO IX: t- 'Z 0 IX: | 2 ISO IX: t- 'Z 0 IX: | ||
w | w | ||
~I t- O u a- 'Z | ~I t- O u a- 'Z | ||
.... a- .... ...J IX: | .... a- .... ...J IX: | ||
...J | ...J W ::::l 500 IX: CI) U 450 TANGENTIAL MOMENT | ||
W ::::l 500 IX: CI) U | |||
[K-FT/FT I FIGURE 3.8-29 CONTAINMENT STRUCTURE MAT LOADING MOMENT AND SHEAR DIAGRAMS MILLSTONE NUCLEAR POWER STATION OPERATING VACUUM UNIT 3 FINAL SAFETY ANALYSIS REPORT | [K-FT/FT I FIGURE 3.8-29 CONTAINMENT STRUCTURE MAT LOADING MOMENT AND SHEAR DIAGRAMS MILLSTONE NUCLEAR POWER STATION OPERATING VACUUM UNIT 3 FINAL SAFETY ANALYSIS REPORT | ||
150 ~ ..... T ISO "AT 100 50 o o 50 100 RADIAL MOMENT 150 IK-FT/FTI 153.40 "AT 10 20 30 40 50 60 70 I I , I I I I RADIUS 1FT) | 150 ~ ..... T ISO "AT 100 50 o o 50 100 RADIAL MOMENT 150 IK-FT/FTI 153.40 "AT 10 20 30 40 50 60 70 I I , I I I I RADIUS 1FT) | ||
~ "AT 50 18.5 (9.5 16.2 17.0 14.8 II(/S'I FT j II. I 0 | ~ "AT 50 18.5 (9.5 16.2 17.0 14.8 II(/S'I FT j II. I 0 | ||
....2 Z | ....2 Z | ||
a:: ... z | a:: ... z | ||
| Line 1,344: | Line 1,195: | ||
to) | to) | ||
C Q.. | C Q.. | ||
Z ...J oe -e Z | Z ...J oe -e Z | ||
.... Q.. | .... Q.. | ||
| Line 1,356: | Line 1,206: | ||
{ MAT I I,' | { MAT I I,' | ||
20 I | 20 I | ||
30 | 30 40 l | ||
SO 60 70 I | |||
40 l | |||
SO | |||
60 | |||
RADIUS (FT) | RADIUS (FT) | ||
{ MAT 100 31.6 33 .3 | { MAT 100 31.6 33 .3 | ||
~ | ~ | ||
50 23.6 I k/SQ FT I 25.6 .... | 50 23.6 I k/SQ FT I 25.6 .... | ||
26 | 26 a | ||
la.,/ | |||
o ** | o ** | ||
, ~ ~ | , ~ ~ | ||
| Line 1,377: | Line 1,222: | ||
CIl: | CIl: | ||
10 0.. | 10 0.. | ||
uJ Z ...J | uJ Z ...J Z | ||
t | |||
< 0.. < ...J Z uJ ::) CIl: 10 CIl: en u u 100 TANGENTIAL MOMENT (K-FT/FT) 121.10 FIGURE 3.8 31 CONTAINMENT STRUCTURE MAT LOADING MOMENT AND SHEAR DIAGRAMS MILLSTONE NUCLEAR POWER STATION 1.00 (SSE) | |||
< 0.. < ...J Z | |||
uJ ::) CIl: 10 CIl: en u u 100 TANGENTIAL MOMENT (K-FT/FT) 121.10 FIGURE 3.8 31 CONTAINMENT STRUCTURE MAT LOADING MOMENT AND SHEAR DIAGRAMS MILLSTONE NUCLEAR POWER STATION 1.00 (SSE) | |||
UNIT 3 FINAL SAFETY ANALYSIS REPORT | UNIT 3 FINAL SAFETY ANALYSIS REPORT | ||
| Line 1,393: | Line 1,235: | ||
~ I 10 | ~ I 10 | ||
<t: | <t: | ||
~ 100 w 90 | ~ 100 w 90 0 80 OJ | ||
0 80 OJ | |||
-c 70 w 60 u | -c 70 w 60 u | ||
z: 50 | z: 50 | ||
| Line 1,408: | Line 1,248: | ||
210 200 190 180 170 160 150 140 DaME r- 130 u, en (HOEK 120 r- 110 | 210 200 190 180 170 160 150 140 DaME r- 130 u, en (HOEK 120 r- 110 | ||
-c | -c | ||
~ 100 ILl 90 | ~ 100 ILl 90 D 80 co | ||
D 80 co | |||
<< 70 ILl 60 u | << 70 ILl 60 u | ||
z 50 | z 50 r- 40 C/) | ||
r- 40 C/) | |||
30 0 | 30 0 | ||
20 10 0 | 20 10 0 | ||
| Line 1,423: | Line 1,259: | ||
210 200 190 180 170 160 150 140 DOllE t- 130 242 u; CYLINDER 120 t- 110 | 210 200 190 180 170 160 150 140 DOllE t- 130 242 u; CYLINDER 120 t- 110 | ||
:::2 100 w 90 0 80 en | |||
:::2 100 w 90 | |||
0 80 en | |||
-c 70 w 60 u | -c 70 w 60 u | ||
z 50 | z 50 t 40 c.I) 30 a | ||
t 40 c.I) 30 a | |||
20 I0 0 287 I | 20 I0 0 287 I | ||
-0400 b.o ~oo | -0400 b.o ~oo | ||
| Line 1,436: | Line 1,267: | ||
210 200 190 180 170 160 150 140 DOllE J-- 130 677 u; CYLINDER 120 J-- 110 | 210 200 190 180 170 160 150 140 DOllE J-- 130 677 u; CYLINDER 120 J-- 110 | ||
::::2: 100 w 90 0 80 CD | |||
::::2: 100 w 90 | |||
0 80 CD | |||
-c 70 w 60 u | -c 70 w 60 u | ||
z 50 | z 50 | ||
| Line 1,452: | Line 1,280: | ||
210 _ | 210 _ | ||
200 190 180 170 160 _ | 200 190 180 170 160 _ | ||
150 140 | 150 140 t- 130 _ DOME CYLINDER u, | ||
t- 130 _ DOME CYLINDER u, | |||
120 | 120 | ||
.- 110 | .- 110 | ||
<C | <C | ||
:::iE 100 w 90 | :::iE 100 w 90 0 80 CO | ||
0 80 CO | |||
<C 70 uJ 60 u | <C 70 uJ 60 u | ||
z 50 | z 50 | ||
<C | <C co 40 30 Q | ||
co 40 30 Q | |||
20 10 0 | 20 10 0 | ||
~1I00 ~1200 ~eoo b.o ~oo RADIAL UOMENT (KIP-FT/FT) | ~1I00 ~1200 ~eoo b.o ~oo RADIAL UOMENT (KIP-FT/FT) | ||
| Line 1,471: | Line 1,293: | ||
DL+l.25P+l.0( T+TL )+1.25(2SSE) MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYS IS REPORT | DL+l.25P+l.0( T+TL )+1.25(2SSE) MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYS IS REPORT | ||
210 200 190 180 170 160 150 | 210 200 190 180 170 160 150 I | ||
LL 140 130 DOME CYL INDER 120 l I 10 | |||
<C | <C | ||
::E 100 w 90 | ::E 100 w 90 0 80 CD | ||
0 80 CD | |||
<C 70 w 60 u | <C 70 w 60 u | ||
z 50 | z 50 | ||
| Line 1,490: | Line 1,309: | ||
210 200 190 180 170 160 150 140 DaME t- 130 u.. CYLINDER 120 l- t 10 | 210 200 190 180 170 160 150 140 DaME t- 130 u.. CYLINDER 120 l- t 10 | ||
<C | <C | ||
::E 100 w 90 | ::E 100 w 90 0 80 en | ||
0 80 en | |||
<C 70 w 60 u | <C 70 w 60 u | ||
z 50 | z 50 | ||
| Line 1,504: | Line 1,321: | ||
170 160 ISO 1'10 nME | 170 160 ISO 1'10 nME | ||
~ 130 LL en INDER 120 I- 110 _ | ~ 130 LL en INDER 120 I- 110 _ | ||
~ 100 UJ 90 0 80 en | |||
~ 100 UJ 90 | |||
0 80 en | |||
<< 70 UJ 60 u | << 70 UJ 60 u | ||
z 50 | z 50 | ||
~ | ~ | ||
U) | U) | ||
| Line 1,520: | Line 1,333: | ||
210 200 190 180 170 160 150 140 DailE I-- 130 u, CYLINDER 120 I-- 110 | 210 200 190 180 170 160 150 140 DailE I-- 130 u, CYLINDER 120 I-- 110 | ||
:::iE 100 UJ 90 0 80 co | |||
:::iE 100 UJ 90 | |||
0 80 co | |||
<< 70 UJ 60 u | << 70 UJ 60 u | ||
:z 50 | :z 50 I- 40 U) | ||
I- 40 U) | |||
£::) | £::) | ||
30 20 10 0 | 30 20 10 0 | ||
| Line 1,536: | Line 1,344: | ||
210 200 190 180 170 160 ISO 140 | 210 200 190 180 170 160 ISO 140 | ||
.- 130 DOME CYLINDER LL 120 | .- 130 DOME CYLINDER LL 120 | ||
.- 110 | .- 110 | ||
::E 100 w 90 0 80 co | |||
::E 100 w 90 | |||
0 80 co | |||
<< 70 w 60 u | << 70 w 60 u | ||
:z 50 | :z 50 Cf) 40 30 0 | ||
Cf) 40 30 0 | |||
20 10 0 | 20 10 0 | ||
~oo I I | ~oo I I | ||
| Line 1,556: | Line 1,357: | ||
210 200 190 180 170 160 150 140 DOME I- 130 u, en I NDER 120 l 110 | 210 200 190 180 170 160 150 140 DOME I- 130 u, en I NDER 120 l 110 | ||
-c | -c | ||
:::E 100 w 90 | :::E 100 w 90 0 80 en | ||
0 80 en | |||
-c 70 UJ 60 u | -c 70 UJ 60 u | ||
z 50 | z 50 I 40 U) 30 a | ||
I 40 U) 30 a | |||
20 10 0 | 20 10 0 | ||
I ---I | I ---I | ||
| Line 1,573: | Line 1,370: | ||
.- 110 | .- 110 | ||
-c | -c | ||
~ 100 UJ 90 | ~ 100 UJ 90 to 80 CO | ||
to 80 CO | |||
-c 70 UJ 60 u | -c 70 UJ 60 u | ||
z 50 | z 50 | ||
| Line 1,589: | Line 1,384: | ||
~ 110 | ~ 110 | ||
-c | -c | ||
~ 100 w 90 | ~ 100 w 90 0 80 co | ||
0 80 co | |||
-c 70 w 60 u | -c 70 w 60 u | ||
z 50 | z 50 | ||
| Line 1,601: | Line 1,394: | ||
!..zoo 0.0 MERIDIONAL FORCE IKIP/FTI FIGURE 3.8-45 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL+I.OP+I.O( T+TL )+1.0 (SSE) MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT | !..zoo 0.0 MERIDIONAL FORCE IKIP/FTI FIGURE 3.8-45 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL+I.OP+I.O( T+TL )+1.0 (SSE) MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT | ||
210 200 190 180 170 160 150 | 210 200 190 180 170 160 150 f-1.L 140 130 DOME CYLI NDER 120 | ||
f-1.L 140 130 DOME CYLI NDER 120 | |||
~ 11O | ~ 11O | ||
~ 100 UJ 90 0 80 co | |||
~ 100 UJ 90 | |||
0 80 co | |||
<< 70 w 60 u | << 70 w 60 u | ||
z 50 | z 50 t-(f) 40 30 0 | ||
t-(f) 40 30 0 | |||
20 10 0 | 20 10 0 | ||
I I I | I I I | ||
-100 0.0 100 MEMBRANE SHEAR FORCE (KIP/FTl FIGURE 3.8 - 46 LOADING CONTAINMENT STRUCTURE WALL DL+l.0P+l.0( T+TL )+1.0 (SSE) AND DOME FORCE RESULTANTS MIL LSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT | -100 0.0 100 MEMBRANE SHEAR FORCE (KIP/FTl FIGURE 3.8 - 46 LOADING CONTAINMENT STRUCTURE WALL DL+l.0P+l.0( T+TL )+1.0 (SSE) AND DOME FORCE RESULTANTS MIL LSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT | ||
210 200 190 180 170 160 150 | 210 200 190 180 170 160 150 I-u.. | ||
I-u.. | |||
140 130 DIME CYLINDER 120 I 110 | 140 130 DIME CYLINDER 120 I 110 | ||
<C | <C | ||
:!: 100 uJ 90 | :!: 100 uJ 90 0 80 CD | ||
0 80 CD | |||
<C 70 uJ 60 u | <C 70 uJ 60 u | ||
:z 50 | :z 50 | ||
| Line 1,633: | Line 1,415: | ||
FIGURE 3.8-47 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL .. I. 15P MI LLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT | FIGURE 3.8-47 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL .. I. 15P MI LLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT | ||
210 200 190 180 170 160 150 140 | 210 200 190 180 170 160 150 140 I- 130 DhE CYLlNDEI U-120 l- I 10 | ||
I- 130 DhE CYLlNDEI U-120 l- I 10 | |||
<C | <C | ||
~ 100 UJ 90 | ~ 100 UJ 90 0 80 CO | ||
0 80 CO | |||
<C 70 uJ 60 u | <C 70 uJ 60 u | ||
z 50 | z 50 | ||
| Line 1,650: | Line 1,428: | ||
FIGURE 3.8-48 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS nL +1* 15P MILLSTONE NUCLEAR POWER STATION UNIT3 FINAL SAFETY ANALYSIS REPORT | FIGURE 3.8-48 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS nL +1* 15P MILLSTONE NUCLEAR POWER STATION UNIT3 FINAL SAFETY ANALYSIS REPORT | ||
210 200 190 180 110 160 150 140 | 210 200 190 180 110 160 150 140 t- 130 DhE en INDEIt u.. | ||
t- 130 DhE en INDEIt u.. | |||
120 t- I 10 | 120 t- I 10 | ||
<C | <C | ||
~ 100 uJ 90 | ~ 100 uJ 90 0 to co | ||
0 to co | |||
<C 10 uJ 60 CJ | <C 10 uJ 60 CJ | ||
:z 50 | :z 50 | ||
| Line 1,668: | Line 1,442: | ||
* t 5P MI LLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT | * t 5P MI LLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT | ||
210 200 190 180 170 160 150 140 | 210 200 190 180 170 160 150 140 f- 130 DhE CYLINDER U. | ||
f- 130 DhE CYLINDER U. | |||
120 l- I 10 | 120 l- I 10 | ||
::E 100 uJ 90 0 80 co | |||
::E 100 uJ 90 | |||
0 80 co | |||
-c 70 uJ 60 u | -c 70 uJ 60 u | ||
:z SO | :z SO f-CJ) 40 30 0 | ||
f-CJ) 40 30 0 | |||
20 10 0 | 20 10 0 | ||
~ ..oo b.o ~oo HOOP FORCE | ~ ..oo b.o ~oo HOOP FORCE | ||
| Line 1,687: | Line 1,454: | ||
210 200 190 180 170 160 150 140 DIME l- 130 I LL CYLI NDER 120 l- II 0 | 210 200 190 180 170 160 150 140 DIME l- 130 I LL CYLI NDER 120 l- II 0 | ||
-c | -c | ||
~ 100 w 90 | ~ 100 w 90 c 80 co | ||
c 80 co | |||
-c 70 UJ 60 u | -c 70 UJ 60 u | ||
z: 50 | z: 50 | ||
| Line 1,699: | Line 1,464: | ||
210 200 190 180 170 160 150 140 DOME l- 130 u, CYLINDER 120 f- 110 | 210 200 190 180 170 160 150 140 DOME l- 130 u, CYLINDER 120 f- 110 | ||
-c | -c | ||
~ 100 w 90 | ~ 100 w 90 0 80 co | ||
0 80 co | |||
-c 70 w 60 u | -c 70 w 60 u | ||
z 50 | z 50 | ||
| Line 1,709: | Line 1,472: | ||
FIGURE 3.8-52 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL+OPERATING VACUUM MILLSTONE NUCLEAR POWER STATION UNIT3 FINAL SAFETY ANALYSIS REPORT | FIGURE 3.8-52 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL+OPERATING VACUUM MILLSTONE NUCLEAR POWER STATION UNIT3 FINAL SAFETY ANALYSIS REPORT | ||
210 200 190 180 170 160 150 | 210 200 190 180 170 160 150 I-u, 140 130 DaME en INDER 120 l- II 0 | ||
I-u, 140 130 DaME en INDER 120 l- II 0 | |||
-c | -c | ||
:::E 100 UJ 90 | :::E 100 UJ 90 10 80 en | ||
10 80 en | |||
-c 70 UJ 60 u | -c 70 UJ 60 u | ||
z 50 | z 50 | ||
| Line 1,725: | Line 1,484: | ||
210 200 190 180 170 160 150 1~0 lIME l- 130 LL CYLINIER 120 l- 110 | 210 200 190 180 170 160 150 1~0 lIME l- 130 LL CYLINIER 120 l- 110 | ||
-c | -c | ||
~ 100 UJ 90 | ~ 100 UJ 90 0 80 en | ||
0 80 en | |||
-c 70 UJ 60 u | -c 70 UJ 60 u | ||
:z 50 | :z 50 | ||
| Line 1,753: | Line 1,510: | ||
MNPS-3 FSAR E | MNPS-3 FSAR E | ||
I | I 23 (H-II) | ||
23 (H-II) | |||
CONTMT. RECIRC. | CONTMT. RECIRC. | ||
CONTMT. -+_-.... | CONTMT. -+_-.... | ||
PUMP PIT EY-3C (11004) | PUMP PIT EY-3C (11004) | ||
-t | -t | ||
-t eo eo N---;Ht----------If-----:::!:=,....4;".....--I-~___t~-------__lH_-- | -t eo eo N---;Ht----------If-----:::!:=,....4;".....--I-~___t~-------__lH_-- | ||
| Line 1,778: | Line 1,532: | ||
:~!! | :~!! | ||
4" '4 | 4" '4 | ||
#4 CRUSHED STONE | #4 CRUSHED STONE 4"COMPRESSIBLE MATERIAL -SEE - SEE NOTE 10 10 n_ r EU-)34'-9" | ||
4"COMPRESSIBLE MATERIAL -SEE - SEE NOTE 10 10 n_ r EU-)34'-9" | |||
...---L,-.Jl1 Ift..-:-'"--t-'-------, _ _..L. __ | ...---L,-.Jl1 Ift..-:-'"--t-'-------, _ _..L. __ | ||
~; | ~; | ||
| Line 1,792: | Line 1,543: | ||
EL (-) 3 7 '- 6 " | EL (-) 3 7 '- 6 " | ||
rrEL(-)37~6" j~~§§~~~~MAT EL.{-)27'-3" j~~§§~~E1J~ ff | rrEL(-)37~6" j~~§§~~~~MAT EL.{-)27'-3" j~~§§~~E1J~ ff | ||
- .*2" 2 GROUT | - .*2" 2 GROUT | ||
,"; DRAIN DRAIN HOLES THRU THRU BLOCKBLOCK IN LINE LINE WITH HOLES L 74'-6"R v"-- 1l~~=~===~Ff:. | ,"; DRAIN DRAIN HOLES THRU THRU BLOCKBLOCK IN LINE LINE WITH HOLES L 74'-6"R v"-- 1l~~=~===~Ff:. | ||
| Line 1,812: | Line 1,562: | ||
14 FINISH SMOOTH TO | 14 FINISH SMOOTH TO | ||
.p*. | .p*. | ||
* v* . | * v* . | ||
SEAL SURFACE | SEAL SURFACE | ||
| Line 1,820: | Line 1,568: | ||
TO TO MAT MAT El.(-)27'*3" EL(-)27'-3" 21-21 (B-3 e.f.. E-3) SCALE 1/4 ":"= I'I' SCALE 1/4" I' 1/4 ":= I' ENG ENG.. SAFETY FEATURES FEATURES ' | TO TO MAT MAT El.(-)27'*3" EL(-)27'-3" 21-21 (B-3 e.f.. E-3) SCALE 1/4 ":"= I'I' SCALE 1/4" I' 1/4 ":= I' ENG ENG.. SAFETY FEATURES FEATURES ' | ||
~ | ~ | ||
.....---,/L--l-BLDG. | .....---,/L--l-BLDG. | ||
t-------,/L--l-BLDG. EC-32 SERIES SERIES ~~: | t-------,/L--l-BLDG. EC-32 SERIES SERIES ~~: | ||
| Line 1,830: | Line 1,577: | ||
~. ,. LELH34' -_- -If--9_"-+_EL.:;.,.,.,.:.. ir~~~~~ ;~tr~~CTlO:~~~ | ~. ,. LELH34' -_- -If--9_"-+_EL.:;.,.,.,.:.. ir~~~~~ ;~tr~~CTlO:~~~ | ||
;~$.~mCTlO:~;..J;~':=.5~~1:'T | ;~$.~mCTlO:~;..J;~':=.5~~1:'T | ||
:~:. 9" POROUS POROUS CONC. | :~:. 9" POROUS POROUS CONC. | ||
: ; : ;~'f~:nt~:-__:._jE_=LJ~~:~;;E | : ; : ;~'f~:nt~:-__:._jE_=LJ~~:~;;E | ||
| Line 1,876: | Line 1,622: | ||
SCALE - 1/4" SCALE-1/4"=I' =,' | SCALE - 1/4" SCALE-1/4"=I' =,' | ||
SEE NOTE a A SEE A g --"",", | SEE NOTE a A SEE A g --"",", | ||
2" 2" | 2" 2" | ||
9" pOROUS CONC. | 9" pOROUS CONC. | ||
| Line 1,942: | Line 1,687: | ||
6 0.660 0.011 4. PRESSURE TEST 1.0DL+ 1.15P (P=45psi) 2t---=:------..3Ior------------- | 6 0.660 0.011 4. PRESSURE TEST 1.0DL+ 1.15P (P=45psi) 2t---=:------..3Ior------------- | ||
11 EL. 58'-2 6 | 11 EL. 58'-2 6 | ||
I: .175R'1:'+1/2,~-J 2.5R'18*-9*=----J 1 | I: .175R'1:'+1/2,~-J 2.5R'18*-9*=----J 1 | ||
ELEVATION EQUIPMENT HATCH FIGURE 3.8-58 (2 OF 2) | ELEVATION EQUIPMENT HATCH FIGURE 3.8-58 (2 OF 2) | ||
| Line 1,985: | Line 1,729: | ||
.f-t~;;;i==9fb==:ilf==lF"k'IF=~="F=;;t! .LEL . 184 '-6' I CORRASe 1;l;~;:;;kr..fEL . 176 ~ 6 " II: NORTH 'bJ M 'O | .f-t~;;;i==9fb==:ilf==lF"k'IF=~="F=;;t! .LEL . 184 '-6' I CORRASe 1;l;~;:;;kr..fEL . 176 ~ 6 " II: NORTH 'bJ M 'O | ||
.<,,': ~~~~B WASTE y.. 2-2 JI2 CLlP LS OIS:~~:'L t---------l OET. F DET. G DET. H FUEL BLDG. | .<,,': ~~~~B WASTE y.. 2-2 JI2 CLlP LS OIS:~~:'L t---------l OET. F DET. G DET. H FUEL BLDG. | ||
ycJ/ BEND LINE EL9 6 '-~ " ELI 04' - 0 " | ycJ/ BEND LINE EL9 6 '-~ " ELI 04' - 0 " | ||
4:'1 9/16" GL | 4:'1 9/16" GL | ||
| Line 2,001: | Line 1,744: | ||
TURBINE BLDG. SECT, 1-1 | TURBINE BLDG. SECT, 1-1 | ||
,. AUX .BLDG. .,,"". | ,. AUX .BLDG. .,,"". | ||
PLAN | PLAN | ||
~:~ ~. ~: ~ | ~:~ ~. ~: ~ | ||
| Line 2,085: | Line 1,827: | ||
~._, *o ~~ | ~._, *o ~~ | ||
:~ | :~ | ||
~EQUIPMENT ACC ESS HATCH CABLE | ~EQUIPMENT ACC ESS HATCH CABLE fT SPREADING AREA f~ | ||
fT SPREADING AREA f~ | |||
FIGURE 3.8-64 (2 OF 4) 1 PLAN EL . 24 - 6" CONTROL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT. | FIGURE 3.8-64 (2 OF 4) 1 PLAN EL . 24 - 6" CONTROL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT. | ||
| Line 2,165: | Line 1,905: | ||
REV. 28.1 | REV. 28.1 | ||
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 | SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 3 | ||
3 | |||
FIGURE 3 .8-66 (SHEET 30F5) | FIGURE 3 .8-66 (SHEET 30F5) | ||
EMERGENCY GENERATOR ENCLOSURE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) | EMERGENCY GENERATOR ENCLOSURE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) | ||
| Line 2,182: | Line 1,914: | ||
REV. 28.1 | REV. 28.1 | ||
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 | SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8-66 (SHEET 5 OF 5) | ||
EMERGENCY GENERATOR ENCLOSURE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) | EMERGENCY GENERATOR ENCLOSURE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) | ||
AMENDMENT 8 MAY 1984 | AMENDMENT 8 MAY 1984 | ||
| Line 2,214: | Line 1,945: | ||
ENGINEERED SAFETY FEATURES BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) | ENGINEERED SAFETY FEATURES BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) | ||
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 | SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 F IGURE 3 .8 - 67 (7 OF 9) | ||
F IGURE 3 .8 - 67 (7 OF 9) | |||
ENGINEERED SAFETY FEATURES BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) | ENGINEERED SAFETY FEATURES BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) | ||
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 | SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3 .8-67 (8 OF9) | ||
FIGURE 3 .8-67 (8 OF9) | |||
ENGINEERED SAFETY FEATURES BUILDING MILLSTONE NUCLEAR POWER STATION | ENGINEERED SAFETY FEATURES BUILDING MILLSTONE NUCLEAR POWER STATION | ||
' UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) | ' UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) | ||
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 | SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 l | ||
l | |||
FIGURE 3 .8-67(9 OF9) | FIGURE 3 .8-67(9 OF9) | ||
ENGINEERED SAFETY FEATURES BUILDING Withheld under 10 CFR 2.390 (d)(1) | ENGINEERED SAFETY FEATURES BUILDING Withheld under 10 CFR 2.390 (d)(1) | ||
| Line 2,253: | Line 1,976: | ||
MAIN STEAM VALVE BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINA L SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) | MAIN STEAM VALVE BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINA L SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) | ||
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 | SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8 - 69 (SHEET 1 OF 4) | ||
FIGURE 3.8 - 69 (SHEET 1 OF 4) | |||
CIRCULATING AND SERVICE WATER PUMPHOUSE OCTOBER 1997 Withheld under 10 CFR 2.390 (d)(1) | CIRCULATING AND SERVICE WATER PUMPHOUSE OCTOBER 1997 Withheld under 10 CFR 2.390 (d)(1) | ||
| Line 2,261: | Line 1,982: | ||
CIRCULATING AND SERVICE WATER PUMPHOUSE SEPTEMBER 1995 Withheld under 10 CFR 2.390 (d)(1) | CIRCULATING AND SERVICE WATER PUMPHOUSE SEPTEMBER 1995 Withheld under 10 CFR 2.390 (d)(1) | ||
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 | SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE3.a-69 (SHEET 3 OF 4) | ||
FIGURE3.a-69 (SHEET 3 OF 4) | |||
C IRCU LATING AND SERV I CE WATER PUMPHOUSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) | C IRCU LATING AND SERV I CE WATER PUMPHOUSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) | ||
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 | SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FI GU R E 3.8-69(SHEET 4 OF 4) | ||
FI GU R E 3.8-69(SHEET 4 OF 4) | |||
CIRCULATING AND SERVICE WATER PUMPHOUSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) | CIRCULATING AND SERVICE WATER PUMPHOUSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) | ||
AMENDMENT 15 SEPTEMBER 1985 | AMENDMENT 15 SEPTEMBER 1985 | ||
| Line 2,288: | Line 2,004: | ||
REV. 28.1 | REV. 28.1 | ||
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 | SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8-71 CIRCULATING DISCHARGE STRUCTURE AND TUNNEL MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) | ||
FIGURE 3.8-71 CIRCULATING DISCHARGE STRUCTURE AND TUNNEL MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) | |||
,------~--------------------- ---****---------*- *- -****-*****-- - - - - - - -- - -- - - - -- - -- - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - -- - | ,------~--------------------- ---****---------*- *- -****-*****-- - - - - - - -- - -- - - - -- - -- - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - -- - | ||
| Line 2,338: | Line 2,052: | ||
SOLID AND LIQUID WASTE DISPOSAL BUILDING REV. 28.1 | SOLID AND LIQUID WASTE DISPOSAL BUILDING REV. 28.1 | ||
MNPS-3 FSAR SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 | MNPS-3 FSAR SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 N | ||
W A J3 J | |||
Withheld under 10 CFR 2.390 (d)(1) | Withheld under 10 CFR 2.390 (d)(1) | ||
FIGURE 3.8-74 (SHEET 3 OF 7) | FIGURE 3.8-74 (SHEET 3 OF 7) | ||
| Line 2,444: | Line 2,157: | ||
°I w 160 0:: | °I w 160 0:: | ||
:::l _ _ _~rCASE ill: T=150oF _S._S_. _ | :::l _ _ _~rCASE ill: T=150oF _S._S_. _ | ||
f | f 0:: | ||
0:: | |||
w 140 0... | w 140 0... | ||
::2: '. .~.--.;....------- | ::2: '. .~.--.;....------- | ||
w f | w f | ||
rCASE I: T=125° S.S. | rCASE I: T=125° S.S. | ||
120 100 80 ~-------l-------L------L.-----....L-----..L------l--- ... | 120 100 80 ~-------l-------L------L.-----....L-----..L------l--- ... | ||
o 10 20 40 50 60 NOTES: CASE I: NORMAL REFUELING - MAXIMUM TEMPERATURE FIGURE 3.8-79 CASE II A: NORMAL HEAT LOAD WITH LOSS OF COOLING FUEL POOL TEMPERATURE CASE n B: NORMAL HEAT LOAD- MAXIMUM To - WITH LOSS OF COOLING TRANSIENTS CASE ill: FULL CORE OFF LOAD- MAXIMUM TEMPERATURE MILLSTONE NUCLEAR POWER STATION S S. =STEADY STATE UNIT 3 To = INITIAL TEMP. (S.S.) WATER FINAL SAFETY ANALYSIS REPORT R = RANGE OF CONDITIONS FOR VARYING To WITH LOSS OF COOLING AMENDMENT 2 APRIL 1983 | o 10 20 40 50 60 NOTES: CASE I: NORMAL REFUELING - MAXIMUM TEMPERATURE FIGURE 3.8-79 CASE II A: NORMAL HEAT LOAD WITH LOSS OF COOLING FUEL POOL TEMPERATURE CASE n B: NORMAL HEAT LOAD- MAXIMUM To - WITH LOSS OF COOLING TRANSIENTS CASE ill: FULL CORE OFF LOAD- MAXIMUM TEMPERATURE MILLSTONE NUCLEAR POWER STATION S S. =STEADY STATE UNIT 3 To = INITIAL TEMP. (S.S.) WATER FINAL SAFETY ANALYSIS REPORT R = RANGE OF CONDITIONS FOR VARYING To WITH LOSS OF COOLING AMENDMENT 2 APRIL 1983 | ||
| Line 2,464: | Line 2,173: | ||
':-:r ',f.J', . | ':-:r ',f.J', . | ||
:.~ .. .----------......" | :.~ .. .----------......" | ||
:<1'. ' * :--_SPENT FUEL SHIPPING | :<1'. ' * :--_SPENT FUEL SHIPPING | ||
... CASK LOADING AREA SPENT FUEL POOL | ... CASK LOADING AREA SPENT FUEL POOL | ||
.(\', | .(\', | ||
T' SEE FIGURE 3.8-7 9 (GATES | T' SEE FIGURE 3.8-7 9 (GATES | ||
~. | ~. | ||
| Line 2,474: | Line 2,181: | ||
." .<;J:. | ." .<;J:. | ||
OUTSIDE SOO F SUMMER T = { 00 F WINTER | OUTSIDE SOO F SUMMER T = { 00 F WINTER | ||
': . '. '6' | ': . '. '6' | ||
, '\?' * , ' | , '\?' * , ' | ||
| Line 2,481: | Line 2,187: | ||
:D.' : ~' .. | :D.' : ~' .. | ||
*: :t::;, " * '<1 .' | *: :t::;, " * '<1 .' | ||
NOTES Toe = INITIAL TEMPERATURE OF CONCRETE (70 to 90°F) | NOTES Toe = INITIAL TEMPERATURE OF CONCRETE (70 to 90°F) | ||
*{ T= SOoF WHEN EMPTY (GATE IN PLACE) | *{ T= SOoF WHEN EMPTY (GATE IN PLACE) | ||
| Line 2,536: | Line 2,241: | ||
I I | I I | ||
I | I | ||
* I r | * I r | ||
lrY">n,.......... | lrY">n,.......... | ||
| Line 2,542: | Line 2,246: | ||
I OFF-GAS u )J.~ FT. | I OFF-GAS u )J.~ FT. | ||
l __ | l __ | ||
OUTLET PlPE | OUTLET PlPE | ||
* r - | * r - | ||
| Line 2,548: | Line 2,251: | ||
I GRADE ELEV. | I GRADE ELEV. | ||
I 14.0 rT. | I 14.0 rT. | ||
I | I | ||
,r I | ,r I | ||
Latest revision as of 11:32, 24 February 2020
| ML17212A071 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/29/2017 |
| From: | Dominion Nuclear Connecticut |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17212A038 | List:
|
| References | |
| 17-208 | |
| Download: ML17212A071 (225) | |
Text
{{#Wiki_filter:UNIT NUMBER SYSTEM LINE SEGMENT SAFETY DESIGNATION PIPE SIZE NUMBER / CLASS 3 - ASS I I 025 -11 -3 I~ 3-ASS-025-1-3 UNIT 3
/ AUX. STEAM SYSTEM 2 1/2" LINE NUMBER LINE NUMBER -3ASS025001-3 REFER TO SECTION 6 .3.1 LINE DESIGNATION 3-CVS-002-2-2 3 -CV S-002-1-4 SAFETY CLASS CHANGE FIGURE 3.2-1 LINE DESIGNATION. SAFETY CLASS BOUNDARIES MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
1.7 1.6 1.5 en 0.. w 1.4 rr u, en -1 en 0 w 0:: 1.3 0.. 1.5 3 .0 TIME(SEC) PRESSURE VS TIME 1.2
- 1. 1 1.0 4 1.0 L.- IL.--'-_..lIIIIIIt._ _--"'..,.;..._ _-'-E:--..........----->_'--_...... << - - . l . . - - ~ ~ - - - - J 10 2 .0 3.0 4 .0 5 .0 6 .0 FREQUE N C Y ( H Z )
F IGUR E 3.3 -1 DYNAMIC LOAD FACTOR CURVE FOR TORNADO PRESSURE DROP MILL ST ONE NU CLE AR POWER STATION UN IT 3 FINAL SA FET Y ANA LY S IS RE PORT AME NDM E NT II NOV E MBE R 1984
MNPS- 3 FSAR
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lJ l~ L I lJ 2J PLAN EL 39'-0" FIGURE 3.4-1 (SHEET 2 OF 4) CIRCULATING AND SERVICE WATER PUMPHOUSE MILLSTONE NUCLEAR POWER STATION UNI T 3 FINAL SAFETY ANALYSIS REPORT
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SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 F SWI FIGURE 3.5-1 TURBINE PLACEMENT Eo ORIENTATION FOR THREE UNIT SITE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1)
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3 .5-2 TURBINE PLACEMENT AND ORIENTATION PROFILE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1)
Figure 3.5-3 DELETED by FSARCR 02-MP3-13
Figure 3.5-4 DELETED by FSARCR 02-MP3-13
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OUTSIDE CONTAINMENT e. (BTP APCSB 3-1 MEB 3-1) HIGH ENERGY SYSTEMS LL. (BREAKS ONLY) W 0:: ~ 0:: ~ 200 F ~---------. ~ MODERATE ENERGY ~ (CRACKS) o 275 PRESSURE (PSI G) INSIDE CONTAINMENT ( REGULATORY GUIDE L46) HIGH ENERGY SYSTEMS (BREAKS ONLY) W 0:: !;t 0:: W 200 F ~---------. a.. ~ w EXCLUDED AREA ~ o 275 PRESSURE (PSIG) FIGURE 3.6-1 FLUID SYSTEMS SUBJECTED TO BREAK AND CRACK ANALYSIS MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYS I S REPORT
ENGINEERED SAFETY FEATURES BUILDING
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! MILLSTONE NUCLEAR POWER STATION I
UNIT 3 1 1 FINAL SAFETY ANALYSIS REPORT
~ REACTOR CONTAINMENT STRUCTURE 1
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\ INCORE INST R. I UNIT 3
'<; ACCESS TUNNEL 2-2 FINAL SAFETY ANALYSIS REPORT
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NOTES 3-MSS-003-33-2
- 1. LOOP A, INSIDE CONTAINMENT AND THE MAIN STEAM VALVE BUILDING, IS A MIRROR IMAGE OF LOOP D. SIMILARLY, LOOP B IS A MIRROR IMAGE OF LOOP C. CONSEQUENTLY, PIPE BREAKS AND RESTRAINTS ARE SHOWN ONLY IN LOOP C AND LOOP 0, BUT THEY ARE ALSO APPLICABLE TO THE OTHER MATCHING LOOPS.
- 2. CD-INDICATES PIPE BREAK NO.1 AT LOCATION SHOWN FOR
SUMMARY
OF POSTULATED PIPE BREAKS_ SEE TABLE 3.6-6,
- 3. A PIPE B~EAK EXCLUSION ZONE EXTENDS FROM THE INBOARD SIDE OF THE CONTAINMENT PENETRATIONS TO THE LINE WALL.
FIGURE 3.6-8 MAIN STEAM SYSTEM MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FILE: 368.dgn/368.clt JANUARY 1'398 --J
MPS-3 FSAR NOTES TO FIGURE 3.6-8 DATA FOR PIPE RUPTURE RESTRAINTS - MAIN STEAM SYSTEM Restraint Distance from N-S Distance from E-W Identification Break # Elevation Containment Containment Restraint Type Function of the Pipe Rupture Restraint 3MSS-PRR1LA (1) 66'-3" 53'-3" West 21'-8" South Limit Stop & Strap Prevent pipe whip into Crane Wall & Liner 3MSS-PRR2LA 2 66'-3" 45'-10" West 32'-2" South Sleeve in Crane Wall Protect Crane Wall 3MSS-PRR3LA 3 71'-8" 42'-6" West 34'-10" South Omni-Directional (2) 3MSS-PRR4LA 1&2 87'-6" 42'-6" West 34'-10" South Omni-Directional Prevent whip into Crane Wall 3MSS-PRR5LA 2 93'-6" 39'-3" West 38'-6" South Omni-Directional Prevent whip into Polar Crane Support 3MSS-PRR7LA 1 93'-6" 35'-11" East 20'-11" South Laminated Strap Prevent whip into Polar Crane Support 3MSS-PRR8LA 1, 2, & 3 93'-6" 14'-3" West 53'-2" South Limit Stop Prevent whip into Crane Wall 3MSS-PRR9LA 1, 2, & 3 93'-6" 14'-3" East 53'-2" South Limit Stop Prevent whip into Crane Wall 3MSS-PRR3SB (3) 66'-3" 52'-2" West 17'-5" South Omni-Directional Prevent whip into Steam Generator Supports 3MSS-PRR5SB 3 72'-6" 48'-11" West 25'-2" South Omni-Directional Prevent whip into Crane Wall 3MSS-PRR6SB 2 88'-9" 39'-3" West 18'-6" South Laminated Strap Prevent whip into Crane Wall 3MSS-PRR7SB 1 88'-9" 39'-3" West 18'-6" South Laminated Strap Prevent whip into Polar Crane Support 3MSS-PRR3SC (3) 66'-3" 52'-2" West 17'-5" North Omni-Directional Prevent whip into Steam Generator Supports 3MSS-PRR5SC 3 72'-6" 48'-11" West 25'-2" North Omni-Directional Prevent whip into Crane Wall 3MSS-PRR6SC 2 88'-9" 39'-3" West 18'-6" North Laminated Strap Prevent whip into Crane Wall 3MSS-PRR7SC 1 88'-9" 39'-3" West 18'-6" North Laminated Strap Prevent whip into Polar Crane Support 3MSS-PRR1LD (1) 66'-3" 53'-3" West 21'-8" North Limit Stop & Strap Prevent pipe whip into Crane Wall & Liner 3MSS-PRR2LD 2 66'-3" 45'-10" West 32'-2" North Sleeve in Crane Wall Protect Crane Wall 3MSS-PRR3LD 3 71'-8" 42'-6" West 34'-10" North Omni-Directional (2) 1 of 4 Rev. 16
MPS-3 FSAR NOTES TO FIGURE 3.8-6 CONTD NOTES TO FIGURE 3.6-8 DATA FOR PIPE RUPTURE RESTRAINTS - MAIN STEAM SYSTEM Restraint Distance from N-S Distance from E-W Identification Break # Elevation Containment Containment Restraint Type Function of the Pipe Rupture Restraint 3MSS-PRR4LD 1&2 87'-6" 42'-6" West 34'-10" North Omni-Directional Prevent whip into Crane Wall 3MSS-PRR5LD 2 93'-6" 39'-3" West 38'-6" North Omni-Directional Prevent whip into Polar Crane Support 3MSS-PRR7LD 1 93'-6" 35'-11" East 20'-11" North Laminated Strap Prevent whip into Polar Crane Support 3MSS-PRR8LD 1, 2, & 3 93'-6" 14'-3" West 53'-2" North Limit Stop Prevent whip into Crane Wall 3MSS-PRR9LD 1, 2, & 3 93'-6" 14'-3" East 53'-2" North Limit Stop Prevent whip into Crane Wall 3MSS-PRR1A 4&5 66'-3" 105'-2" West 21'-0" South Dual Function Protects the Break Exclusion Zone 3MSS-PRR2A 4&5 66'-3" 122'-5" West 21'-0" South Dual Function Protects the Break Exclusion Zone 3MSS-PRR3A 4&5 66'-3" 141'-2" West 21'-0" South Limit Stop Protects the Break Exclusion Zone 3MSS-PRR4A 4 56'-3" 173'-8" West 29'-0" North Limit Stop Protects the Control Building 3MSS-PRR5A 5&6 55'-10" 177'-0" West 66'-6" North Limit Stop Protects the Control Building 3MSS-PRR7A 7 or 8 55'-4" 214'-6" West 70'-7" North Limit Stop Protects the Control Building 3MSS-PRR13A 7, 8, or 9 54'-8" 234'-10" West 65'-9" North Limit Stop Protects the Control Building 3MSS-PRR1B 4&5 66'-3" 105'-2" West 7'-0" South Dual Function Protects the Break Exclusion Zone 3MSS-PRR2B 4&5 66'-3" 122'-7" West 7'-0" South Dual Function Protects the Break Exclusion Zone 3MSS-PRR3B 4&5 66'-3" 141'-2" West 7'-0" South Limit Stop Protects the Break Exclusion Zone 3MSS-PRR4B 4 56'-4" 168'-2" West 29'-0" North Limit Stop Protects the Control Building 3MSS-PRR5B 5&6 55'-10" 171'-7" West 71'-7" North Limit Stop Protects the Control Building 3MSS-PRR7B 7 or 8 55'-4" 214'-6" West 75'-7" North Limit Stop Protects the Control Building 2 of 4 Rev. 16
MPS-3 FSAR NOTES TO FIGURE 3.6-8 DATA FOR PIPE RUPTURE RESTRAINTS - MAIN STEAM SYSTEM Restraint Distance from N-S Distance from E-W Identification Break # Elevation Containment Containment Restraint Type Function of the Pipe Rupture Restraint 3MSS-PRR13B 7, 8, or 9 54'-8" 241'-10" West 71'-2" North Limit Stop Protects the Control Building 3MSS-PRR1C 5 66'-3" 105'-2" West 7'-0" North Dual Function Protects the Break Exclusion Zone 3MSS-PRR3C 5 66'-3" 141'-2" West 7'-0" North Limit Stop Protects the Break Exclusion Zone 3MSS-PRR4C 4 56'-5" 162'-8" West 29'-0" North Limit Stop Protects the Control Building 3MSS-PRR5C 5&6 55'-10" 166'-2" West 76'-8" North Limit Stop Protects the Control Building 3MSS-PRR7C 7 or 8 55'-4" 214'-6" West 80'-7" North Limit Stop Protects the Control Building 3MSS-PRR13C 7, 8, or 9 54'-8" 248'-9" West 76'-7" North Limit Stop Protects the Control Building 3MSS-PRR1D 5 66'-3" 105'-2" West 21'-0" North Dual Function Protects the Break Exclusion Zone 3MSS-PRR3D 5 66'-3" 141'-2" West 21'-0" North Limit Stop Protects the Break Exclusion Zone 3MSS-PRR4D 4&5 62'-5" 150'-1" West 29'-0" North Laminated Strap Protects the Control Building 3MSS-PRR5D 5&6 55'-10" 160'-9" West 81'-9" North Limit Stop Protects the Control Building 3MSS-PRR7D 7 or 8 55'-4" 214'-6" West 85'-7" North Limit Stop Protects the Control Building 3MSS-PRR13D 7, 8, or 9 54'-8" 255'-8" West 82'-0" North Limit Stop Protects the Control Building 3 of 4 Rev. 16
MPS-3 FSAR Notes (1).Pipe Rupture Restraints 3MSS-PRR1LA and 3MSS-PRR1LD are laminated straps which prevent the Main Steam line from impacting the Containment Liner subsequent to Break Number 3 on Main Steam Lines 3-MSS-030-92-2 and 3-MSS-030-95-2. The Limit Stop function was provided to prevent the Main Steam line from impacting the Crane Wall subsequent to a Terminal End Break at the Containment Penetration. This Terminal End Break was deleted as each Main Steam Line Break Exclusion Zone extends from the pipe to flued head weld at each containment penetration inside containment to each Main Steam Containment Isolation Valve Outside Containment. (2).Pipe rupture restraints 3MSS-PRR3LA and 3MSS-PRR3LD prevent pipe whip within the adjacent Steam Generator Cubicles 3RCS*SG1B and 3RCS*SG1C. The NSSS System Standard Design Criteria does not permit break propagation from a broken loop to an unbroken loop. Therefore, the restraints prevent pipe whip within the unbroken loop cubicles. (3).Pipe rupture restraints 3MSS-PRR3SB and 3MSS-PRR3SC prevent the pipe whip effects subsequent to a Terminal End break at the Main Steam Line pipe weld to the Containment Penetration flued head. The Main Steam System Break Exclusion Zone includes the pipe to flued head weld inside containment to protect the containment liner from jet impingement effects. 4 of 4 Rev. 16
NOTES
- 1. FOR THE TURBINE BY*PASS STEAM PIPING BREAKS WERE POSTULATED AT TERM INAL ENDS, AND AT i EVERY PIPING WELD TO FITTING AND VALVE.
HOWEVER, THE PORTION OF THE TURBINE BY*PASS PIPING FROM THE MAIN STEAM MANIFOLD WH ICH RUN IN PARALLEL WITH THE CONTROL BUILDING WALL IS PROVIDED WITH 5*DIAMETER BENDS IN LIEU OF FITTINGS TO PRECLUDE BREAKS FROM OCCUR* RING WITHIN THIS SECTION OF THE PIPING , THEREBY PROTECTING THE CONTROL BUILDING WALL FROM PIPE WHIP . SIMILARLY , FOR THE MOISTURE SEPARA* TOR STEAM PIPING. BREAKS WERE POSTULATED AT TERMINAL ENDS, AND AT EVERY PIPING WELD TO FITTING AND VALVE.
- 2. EXAMINATION OF THE MOISTURE SEPARATOR STEAM PIPING FOR EFFECTS OF PIPE RUPTURE AND JET IMPINGEMENT HAS DETERMINED THAT NO PROTECTIVE MEASURES ARE REQUIRED.
- 3. NOMENCLATURE:
@ - INDICATES BREAK AT TERMINA L ENDS.
~ 5 D IA . BEND @. INDICATES BREAK AT INTERMEDIATE TYf> I N 5 PLACES LOCATIONS. FIGURE 3.6-9 MAIN STEAM SYSTEM (CONTINUED) MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
NOTES
- 1. LOOP A INSIDE CONTAINMENT AND MAIN STEAM VALVE BUILDING IS A MIRROR IMAGE OF LOOP D.
SIMILARLY, LOOP B IS A MIRROR IMAGE OF LOOP C. CONSEQUENTLY, PIPE BREAK LOCATIONS ARE SHOWN ONLY IN LOOP B AND LOOP A ON MAIN FEEDWATER PIPING, BUT THEY ARE ALSO APPLI. CABLE TO THE OTHER MATCHING LOOPS.
- 2. G)INDICATES PIPE BREAK NO.1 FOR
SUMMARY
OF POSTULATED PIPE BREAKS SEE TABLE 3.6-9.
- 3. A PIPE BREAK EXCLUSION ZONE EXTENDS FROM EACH CONTAINMENT PENETRATION ON THE INBOARD SIDE TO THE F LINE WALL IN THE MAIN STEAM VALVE BUILDING.
- 4. FOR
SUMMARY
OF IilUPTURE RESTRAINTS INSIDE AND OUTSIDE CONTAINMENT STRUCTURE, SEE FIGURE 3.6*11.
- 5. A TERMINAL END BREAK IS POSTULATED ON EACH MAIN FEEDWATER LINE AT THE F LINE WALL IN THE MAIN STEAM VALVE BUILDING. THIS TERMINAL END BREAK DEFINES THE EXTREMITY OF THE BREAK EXCUSION ZONE.
FIGURE 3.6-10 FEEOWATER SYSTEM POSTULATED PIPE RUPTURE LOCATIONS MILLSTONE NUCLEAR POWER STATION UNIT3 FINAL SAFETY ANALYSIS REPORT CAD FILE:361O.dgn/361O.clt
MNPS-3 FSAR NOTE S
- 1. PIPE RUPTURE RESTRAINTS ON THE FEEDWATER SYSTEM ARE SHOWN FOR LOOPS A AND B. THESE RESTRAINTS ARE TYPICAL FOR LOOPS C AND D AND ARE AT IDENTICAL LOCATIONS.
- 2. PIPE RUPTURE RESTRAINTS MARKED
- ARE 3FW$ -PRRIOl DUAL FUNCTION PIPE SUPPORT - PIPE RUPTURE RESTRAINTS .
FIGURE 3.6-11 FEEDWATER SYSTEM PIPE RUPTURE RESTRAINTS JANUARY 1998
MPS-3 FSAR NOTES TO FIGURE 3.6-11 DATA FOR PIPE RUPTURE RESTRAINTS - MAIN FEEDWATER SYSTEM Distance from N-S Distance from E-W Restraint Identification Break # Elevation Containment Containment Restraint Type Function of the Pipe Rupture Restraint 3FWS-PRR2LA (1) 85'-1" 41'-3" West 36'-4" South Omni-Directional Prevent pipe whip into Crane Wall 3FWS-PRR3LA 3 89'-6" 47'-10" East 27'-2" South Omni-Directional Prevent pipe whip into Crane Wall 3FWS-PRR4LA (1) 86'-11" 47'-6" East 19'-6" South Pipe Crush Bumper Prevent pipe whip into Crane Wall 3FWS-PRR5LA 2&3 54'-3" 44'-1" East 21'-11" South Flat Stop Prevent pipe whip into Operating Floor 3FWS-PRR7LA (1) 63'-0" 39'-6" West 38'-3" South Omni-Directional Prevent pipe whip into Crane Wall 3FWS-PRR8LA (1) 89'-6" 32'-8" West 44'-3" South Omni-Directional Prevent pipe whip into Crane Wall 3FWS-PRR9LA (1) 89'-6" 3'-10" West 54'-10" South Pipe Crush Bumper Prevent pipe whip into Crane Wall 3FWS-PRR10LA (1) 89'-6" 25'-10" East 48'-7" South Pipe Crush Bumper Prevent pipe whip into Crane Wall 3FWS-PRR11LA (1) 87'-0" 46'-4" East 21'-8" South Flat Stop Prevent excessive load to steam generator nozzle 3FWS-PRR12LA 1&2 61'-4" 42'-9" East 25'-0" South Brace on (2) 3MSS-PRR7L 3FWS-PRR13LA 1&2 61'-4" 42'-9" East 25'-0" South Flat Stop (2) 3FWS-PRR3SB (1) 56'-4" 47'-2" West 9'-3" South Pipe Crush Bumper (2) 3FWS-PRR5SB 3 64'-7" 39'-4" West 23'-7" South Laminated Strap Prevent pipe whip into 3RCS*SG1B 3FWS-PRR6SB (1) 56'-4" 40'-1" West 26'-9" South Flat Stop Prevent excessive load to steam generator nozzle 3FWS-PRR7SB (1) 44'-3" 50'-9" West 9'-11" South Laminated Strap Prevent excessive load on containment penetration 3FWS-PRR8SB 1, 2 & 3 59'-10" 39'-4" West 23'-7" South Laminated Strap (2) 1 of 5 Rev. 16
MPS-3 FSAR NOTES TO FIGURE 3.6-11 CONTD NOTES TO FIGURE 3.6-11 DATA FOR PIPE RUPTURE RESTRAINTS - MAIN FEEDWATER SYSTEM Distance from N-S Distance from E-W Restraint Identification Break # Elevation Containment Containment Restraint Type Function of the Pipe Rupture Restraint 3FWS-PRR3SC (1) 56'-4" 47'-2" West 9'-3" North Pipe Crush Bumper (2) 3FWS-PRR5SC 3 64'-7" 39'-4" West 23'-7" North Laminated Strap Prevent pipe whip into 3RCS*SG1C 3FWS-PRR6SC (1) 56'-4" 40'-1" West 26'-9" North Flat Stop Prevent excessive load to steam generator nozzle 3FWS-PRR7SC (1) 44'-3" 50'-9" West 9'-11" North Laminated Strap Prevent excessive load on containment penetration 3FWS-PRR8SC 1, 2 & 3 59'-10" 39'-4" West 23'-7" North Laminated Strap (2) 3FWS-PRR2LD (1) 85'-1" 41'-3" West 36'-4" North Omni-Directional Prevent pipe whip into Crane Wall 3FWS-PRR3LD 3 89'-6" 47'-10" East 27'-2" North Omni-Directional Prevent pipe whip into Crane Wall 3FWS-PRR4LD (1) 86'-11" 47'-6" East 19'-6" North Pipe Crush Bumper Prevent pipe whip into Crane Wall 3FWS-PRR5LD 2&3 54'-3" 44'-1" East 21'-11" North Flat Stop Prevent pipe whip into Operating Floor 3FWS-PRR7LD (1) 63'-0" 39'-6" West 38'-3" North Omni-Directional Prevent pipe whip into Crane Wall 3FWS-PRR8LD (1) 89'-6" 32'-8" West 44'-3" North Omni-Directional Prevent pipe whip into Crane Wall 3FWS-PRR9LD (1) 89'-6" 3'-10" West 54'-10" North Pipe Crush Bumper Prevent pipe whip into Crane Wall 3FWS-PRR10LD (1) 89'-6" 25'-10" East 48'-7" North Pipe Crush Bumper Prevent pipe whip into Crane Wall 3FWS-PRR11LA (1) 87'-0" 46'-8" East 22'-1" North Flat Stop Prevent excessive load to steam generator nozzle 3FWS-PRR12LA 1&2 61'-4" 42'-9" East 25'-0" North Brace on (2) 3MSS-PRR7L 2 of 5 Rev. 16
MPS-3 FSAR NOTES TO FIGURE 3.6-11 DATA FOR PIPE RUPTURE RESTRAINTS - MAIN FEEDWATER SYSTEM Distance from N-S Distance from E-W Restraint Identification Break # Elevation Containment Containment Restraint Type Function of the Pipe Rupture Restraint 3FWS-PRR13LA 1&2 61'-4" 42'-9" East 25'-0" North Flat Stop (2) 3FWS-PRR1A (3) 44'-3" 105'-2" West 21'-0" South Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR3A (3) 44'-3" 141'-2" West 21'-0" South Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR4A (3) 47'-7" 146'-6" West 21'-0" South Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR5A (3) 49'-11" 105'-2" West 16'-6" South Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR6A (3) 49'-11" 124'-1" West 16'-6" South Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR7A (3) 60'-9" 124'-1" West 16'-6" South Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR9SA (3) 49'-11" 83'-5" West 16'-6" South Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR10SA (3) 51'-2" 124'-11" West 16'-6" South Pipe Crush Bumper Prevent interaction with adjacent feedwater line 3FWS-PRR1B (3) 44'-3" 105'-2" West 7'-0" South Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR3B (3) 44'-3" 141'-2" West 7'-0" South Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR4B (3) 47'-7" 146'-6" West 7'-0" South Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR5B (3) 49'-11" 105'-2" West 11'-6" South Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR6B (3) 49'-11" 124'-1" West 11'-6" South Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR7B (3) 60'-9" 124'-1" West 11'-6" South Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR9SB (3) 49'-11" 87'-10" West 11'-6" South Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR10SB (3) 51'-2" 124'-11" West 11'-6" South Pipe Crush Bumper Prevent interaction with adjacent feedwater line 3FWS-PRR1C (3) 44'-3" 105'-2" West 7'-0" North Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR3C (3) 44'-3" 141'-2" West 7'-0" North Dual Function Limit stress within Break Exclusion Zone 3 of 5 Rev. 16
MPS-3 FSAR NOTES TO FIGURE 3.6-11 DATA FOR PIPE RUPTURE RESTRAINTS - MAIN FEEDWATER SYSTEM Distance from N-S Distance from E-W Restraint Identification Break # Elevation Containment Containment Restraint Type Function of the Pipe Rupture Restraint 3FWS-PRR4C (3) 47'-7" 146'-6" West 7'-0" North Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR5C (3) 49'-11" 105'-2" West 11'-6" North Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR6C (3) 49'-11" 124'-1" West 11'-6" North Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR7C (3) 60'-9" 124'-1" West 11'-6" North Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR9NC (3) 49'-11" 87'-10" West 11'-6" North Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR10NC (3) 51'-2" 124'-11" West 11'-6" North Pipe Crush Bumper Prevent interaction with adjacent feedwater line 3FWS-PRR1D (3) 44'-3" 105'-2" West 21'-0" North Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR3D (3) 44'-3" 141'-2" West 21'-0" North Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR4D (3) 47'-7" 146'-6" West 21'-0" North Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR5D (3) 49'-11" 105'-2" West 16'-6" North Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR6D (3) 49'-11" 124'-1" West 16'-6" North Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR7D (3) 60'-9" 124'-1" West 16'-6" North Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR9ND (3) 49'-11" 83'-5" West 16'-6" North Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR10ND (3) 51'-2" 124'-11" West 16'-6" North Pipe Crush Bumper Prevent interaction with adjacent feedwater line 4 of 5 Rev. 16
MPS-3 FSAR Notes (1).Pipe Rupture Restraints 3MSS-PRR1LA and 3MSS-PRR1LD are laminated straps which prevent the Main Steam line from impacting the Containment Liner subsequent to Break Number 3 on Main Steam Lines Pipe rupture restraint provided to mitigate the effects of Arbitrary Intermediate Breaks (AIBs). USNRC Generic Letter 87-11 eliminates the requirement to analyze the effects of pipe whip subsequent to AIBs. Therefore, these restraints are installed but do not perform a safety function. (2).Pipe rupture restraint is provided to prevent an impact to the Steam Generator Cubicle Wall. Unrestrained pipe whip impact to this concrete barrier would result in catastrophic failure of the barrier. The effects of catastrophic failure of the barrier are unacceptable therefore the pipe whip into the barrier is prevented. (3).Pipe rupture restraints provided to limit stress in the Main Feedwater System Break Exclusion Zone. The pipe rupture restraints 3FWS-PRR1, 3FWS-PRR3, and 3FWS-PRR4 are on the Main Feedwater piping and the restraints 3FWS-PRR5, 3FWS-PRR6, 3FWS-PRR7, 3FWS-PRR9N, 3FWS-PRR9S, 3FWS-PRR10N, and 3FWS-PRR10S are on the Main Feedwater Bypass piping. Postulated break locations are on the Main Feedwater Piping in the Turbine Building and the Main Feedwater Bypass Piping in the Main Steam Valve Building where a fitting criteria was used as the basis to select the break locations in accordance with FSAR Section 3.6.2.1.2.3.b. Subsequent to stress reconciliation, the pipe break locations on the Main Feedwater Piping in the Turbine Building are located in accordance with the criteria delineated in FSAR Section 3.6.2.1.2.3.2.b. The latter criteria greatly reduced the number of postulated pipe breaks and the final postulated breaks, other than the terminal end break at the "F" line wall, were remote from the Break Exclusion Zone. No other postulated breaks were located in the Main Steam Valve Building and none were postulated on the Main Feedwater Bypass Piping as this piping was analyzed as part of the Main Feedwater System and resulted in stresses below the threshold stress defined in FSAR Section 3.6.2.1.2.3.b. 5 of 5 Rev. 16
3RCS-PRRG STEAM GENERATOR 3RCS.SGID 3-RCS-008-34-1 RCS-150-243-1 oJ 1'0
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l~" BYPASS LINE OFF LOOP STOP VALVE BYPASS LINE TYPICAL-ALL LOOPS- SEE NOTE 2 AND NOTE 3 NOTES
- 1. PRIMARY COOLANT PIPING NEED NOT BE ADDRESSED FOR PIPE WHIP AND FLUID JET IMPINGEMENT AS STATED IN SEcnON 3.6.1.3.3. THE PIPE RUPTURE RESTRAINTS 3RCS-PRBI. 3RCS-PRB2, 3RCS-PRB3 AND 3RCS-PRB4 ARE NOT REQUIRED. THESE ARE SHOWN FOR INFORMAnON ONLY.
2.JV\I\r DENOTES DUAL FUNCTION PIPE SUPPORT, - PIPE RUPTURE RESTRAINT ON THE LOOP STOP VALVE BYPASS LINE. THESE DUAL FUNCTION PIPE RUPTURE RESTRAINTS ARE TYPICAL FOR EACH LOOP STOP VALVE BYPASS PIPE.
- 3. POSTULATED PIPE RUPTURE LOCATIONS ARE lYPICAl FOR EACH CUBICLE.
FIGURE 3.6-12 REACTOR COOLANT SYSTEM PRIMARY COOLANT PIPING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FILE: 3612.dgn/3612.clt JANUARY 1998
MPS-3 FSAR NOTES TO FIGURE 3.6-12 DATA FOR PIPE RUPTURE RESTRAINTS REACTOR COOLANT SYSTEM - PRIMARY COOLANT PIPING Distance from N-S Distance from E-W Function of the Pipe Rupture Restraint Identification Break # Elevation Containment Containment Restraint Type Restraint 3RCS-PRB1A (1) 7'-0" 32'-11" East 18'-10" South Limit Stop None (1) 3RCS-PRB2A (1) 6'-10" 25'-10" East 30'-0" South Limit Stop None (1) 3RCS-PRB3A (1) 17'-6" 13'-11" East 12'-2" South Limit Stop None (1) 3RCS-PRB4A (1) 15'-6" 27'-6" East 11'-1" South Limit Stop None (1) 3RCS-PRR4A 14 27'-8" 19'-9" East 17'-1" South Limit Stop (2) 3RCS-PRR7A (3) 18'-6" 22'-1" East 20'-8" South Limit Stop (2) 3RCS-PRR8A (3) 18'-6" 19'-10" East 15'-9" South Limit Stop (2) 3RCS-PRR9A (4) 31'-6" 20'-1" East 18'-8" South Limit Stop (2) 3RCS-PRRGA (3) 24'-10" 22'-1" East 20'-8" South Elastic Sway (2) Strut 3RCS-PRRFA 13 31'-6" 20'-6" East 18'-2" South Shock Suppressor (2) 3RCS-PRREA Split 31'-6" 20'-6" East 18'-2" South Shock Suppressor (2) 3RCS-PRRCA Split 31'-6" 21'-2" East 19'-4" South Shock Suppressor (2) 3RCS-PRRBA 13 31'-6" 21'-2" East 19'-4" South Shock Suppressor (2) 3RCS-PRRA1A 14 30'-4" 22'-1" East 20'-9" South Shock Suppressor (2) 3RCS-PRRA2A 14 30'-4" 22'-1" East 20'-9" South Shock Suppressor (2) 3RCS-PRB1B (1) 7'-0" 32'-11" West 18'-10" South Limit Stop None (1) 3RCS-PRB2B (1) 6'-10" 25'-10" West 30'-0" South Limit Stop None (1) 3RCS-PRB3B (1) 17'-6" 13'-11" West 12'-2" South Limit Stop None (1) 1 of 5 Rev. 16
MPS-3 FSAR NOTES TO FIGURE 3.6-12 CONTD NOTES TO FIGURE 3.6-12 DATA FOR PIPE RUPTURE RESTRAINTS REACTOR COOLANT SYSTEM - PRIMARY COOLANT PIPING Distance from N-S Distance from E-W Function of the Pipe Rupture Restraint Identification Break # Elevation Containment Containment Restraint Type Restraint 3RCS-PRB4B (1) 15'-6" 27'-6" West 11'-1" South Limit Stop None (1) 3RCS-PRR4B 14 27'-8" 19'-9" West 17'-1" South Limit Stop (2) 3RCS-PRR7B (3) 18'-6" 22'-1" West 20'-8" South Limit Stop (2) 3RCS-PRR8B (3) 18'-6" 19'-10"West 15'-9" South Limit Stop (2) 3RCS-PRR9B (4) 31'-6" 20'-1" West 18'-8" South Limit Stop (2) 3RCS-PRRGB (3) 24'-10" 22'-1" West 20'-8" South Elastic Sway (2) Strut 3RCS-PRRFB 13 31'-6" 20'-6" West 18'-2" South Shock Suppressor (2) 3RCS-PRREB Split 31'-6" 20'-6" West 18'-2" South Shock Suppressor (2) 3RCS-PRRCB Split 31'-6" 21'-2" West 19'-4" South Shock Suppressor (2) 3RCS-PRRBB 13 31'-6" 21'-2" West 19'-4" South Shock Suppressor (2) 3RCS-PRRA1B 14 30'-4" 22'-1" West 20'-9" South Shock Suppressor (2) 3RCS-PRRA2B 14 30'-4" 22'-1" West 20'-9" South Shock Suppressor (2) 3RCS-PRB1C (1) 7'-0" 32'-11" West 18'-10" North Limit Stop None (1) 3RCS-PRB2C (1) 6'-10" 25'-10" West 30'-0" North Limit Stop None (1) 3RCS-PRB3C (1) 17'-6" 13'-11" West 12'-2" North Limit Stop None (1) 3RCS-PRB4C (1) 15'-6" 27'-6" West 11'-1" North Limit Stop None (1) 3RCS-PRR4C 14 27'-8" 19'-9" West 17'-1" North Limit Stop (2) 2 of 5 Rev. 16
MPS-3 FSAR NOTES TO FIGURE 3.6-12 DATA FOR PIPE RUPTURE RESTRAINTS REACTOR COOLANT SYSTEM - PRIMARY COOLANT PIPING Distance from N-S Distance from E-W Function of the Pipe Rupture Restraint Identification Break # Elevation Containment Containment Restraint Type Restraint 3RCS-PRR7C (3) 18'-6" 22'-1" West 20'-8" North Limit Stop (2) 3RCS-PRR8C (3) 18'-6" 19'-10"West 15'-9" North Limit Stop (2) 3RCS-PRR9C (4) 31'-6" 20'-1" West 18'-8" North Limit Stop (2) 3RCS-PRRGC (3) 24'-10" 22'-1" West 20'-8" North Elastic Sway (2) Strut 3RCS-PRRFC 13 31'-6" 20'-6" West 18'-2" North Shock Suppressor (2) 3RCS-PRREC Split 31'-6" 20'-6" West 18'-2" North Shock Suppressor (2) 3RCS-PRRCC Split 31'-6" 21'-2" West 19'-4" North Shock Suppressor (2) 3RCS-PRRBC 13 31'-6" 21'-2" West 19'-4" North Shock Suppressor (2) 3RCS-PRRA1C 14 30'-4" 22'-1" West 20'-9" North Shock Suppressor (2) 3RCS-PRRA2C 14 30'-4" 22'-1" West 20'-9" North Shock Suppressor (2) 3RCS-PRB1D (1) 7'-0" 32'-11" East 18'-10" North Limit Stop None (1) 3RCS-PRB2D (1) 6'-10" 25'-10" East 30'-0" North Limit Stop None (1) 3RCS-PRB3D (1) 17'-6" 13'-11" East 12'-2" North Limit Stop None (1) 3RCS-PRB4D (1) 15'-6" 27'-6" East 11'-1" North Limit Stop None (1) 3RCS-PRR4D 14 27'-8" 19'-9" East 17'-1" North Limit Stop (2) 3RCS-PRR7D (3) 18'-6" 22'-1" East 20'-8" North Limit Stop (2) 3RCS-PRR8D (3) 18'-6" 19'-10" East 15'-9" North Limit Stop (2) 3RCS-PRR9D (4) 31'-6" 20'-1" East 18'-8" North Limit Stop (2) 3 of 5 Rev. 16
MPS-3 FSAR NOTES TO FIGURE 3.6-12 DATA FOR PIPE RUPTURE RESTRAINTS REACTOR COOLANT SYSTEM - PRIMARY COOLANT PIPING Distance from N-S Distance from E-W Function of the Pipe Rupture Restraint Identification Break # Elevation Containment Containment Restraint Type Restraint 3RCS-PRRGD (3) 24'-10" 22'-1" East 20'-8" North Elastic Sway (2) Strut 3RCS-PRRFD 13 31'-6" 20'-6" East 18'-2" North Shock Suppressor (2) 3RCS-PRRED Split 31'-6" 20'-6" East 18'-2" North Shock Suppressor (2) 3RCS-PRRCD Split 31'-6" 21'-2" East 19'-4" North Shock Suppressor (2) 3RCS-PRRBD 13 31'-6" 21'-2" East 19'-4" North Shock Suppressor (2) 3RCS-PRRA1D 14 30'-4" 22'-1" East 20'-9" North Shock Suppressor (2) 3RCS-PRRA2D 14 30'-4" 22'-1" East 20'-9" North Shock Suppressor (2) 4 of 5 Rev. 16
MPS-3 FSAR Notes (1).Subsequent to the exemption regarding the need to analyze Large Primary Loop Pipe Ruptures as the Structural Design Basis for Millstone 3 from a portion of GDC-4 of Appendix A to 10 CFR Part 50, these pipe rupture restraints are no longer required. (2).The NSSS System Standard Design Criteria does not permit break propagation in excess of 20% of the flow area of the ruptured pipe to an unaffected leg within the broken loop. Therefore, these pipe rupture restraints limit displacement subsequent to a postulated break on the 8" Reactor Coolant Bypass line to meet the NSSS System Standard Design Criteria. (3).Pipe rupture restraints provided to mitigate the effects of Terminal End (TP) postulated breaks at the Reactor Coolant Bypass nozzle on either the Hot Leg and the Cold Leg. The Reactor Coolant Bypass piping was analyzed as part of the Primary Reactor Coolant Piping analysis and the Reactor Coolant Bypass piping has a significant effect on the main Primary Coolant line behavior. Therefore, in accordance with FSAR Section 3.6.2.1.1.1 the Reactor Coolant Bypass line connection to each Hot Leg and Cold Leg is not a Terminal End (TP) of the Reactor Coolant Bypass piping. (4).3RCS-PRR9A through D limit the steady state displacement of the shock suppressors. 5 of 5 Rev. 16
PIPE RUPTURE RESTRAINTS ON RESIDUAL HEAT REMOVAL PIPING AND 6 INCH LOW PRESSURE SAFETY INJECTiON SEE NOTE 2 NOTES:
- 1. POSTULATED PIPE RUPTURE AND RESTRAINT LOCA TlON ON THE LOW PRESSURE SAFETY INJECTION PIPING TO THE COLO LEGS ARE SHOWN ON LOOP B. THESE LOCATIONS ARE TYPICAL FOR ALL LOOPS.
- 2. POSTULATED PIPE RUPTURE AND RESTRAINT LOCATIONS ON THE RESIDUAL HEAT REMOVAL PIPING AND 6 INCH SAFETY INJECTION BRANCH PIPING ARE SHOWN ON LOOP D. LOCA nONS ARE TYPICAL FOR LOOP A. SAFETy INJECTION PIPING TO LOOP A. HOT LEG NOT SHOWN FOR CLARITY.
- 3. TABLE 3.6-18 STATES THAT A LONGITUDINAL SPLIT IS PREFERENTIAL ON THE INTRADOS OF THE REACTOR COOLANT SYSTEM PORTION OF THE ACCUMULATOR DISCHARGE. THE LONGITUDINAL SPLIT IS. THE ONLY INTERMEDIATE BREAK POSTULATED SINCE THE PIPING IS RELATIVELY SHORT AND A DETAILED STRESS ANALYSIS IN ACCORDANCE WITH FSAR SECTION 3.6.2.1.3 CONCLUDES CIRCUMFERENTIAL STRESS IS DOMINANT.
- 4. POSTULATED PIPE RUPTURE LOCA nONS FOR HIGH PRESSURE SAFETY INJECTION PIPING FROM THE CHS PUMPS TO THE COLD lEGS IS NOT SHOWN FOR CLARITY. lOCATIONS ARE TYPICAL FOR EACH lOOP AND INVOLVE TWO TERMINAL ENDS AND TWO INTER-MEDIATE POINTS BETWEEN THE COLD LEG AND FIRST CHECK VALVE UPSTREAM.
FIGURE 3 .6-13 REACTOR COOLANT SYSTEM-LOW PRESSURE SAFETY INJECTION
- 6. RESIDUAL HEAT REMOVAL PIPING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FILE: f lg 36 13. d gn / 36 13. cl t JANUARY 1998
MPS-3 FSAR NOTES TO FIGURE 3.6-13 DATA FOR PIPE RUPTURE RESTRAINTS REACTOR COOLANT SYSTEM LOW PRESSURE SAFETY INJECTION, HIGH PRESSURE SAFETY INJECTION, AND RESIDUAL HEAT REMOVAL PIPING Restraint Distance from N-S Distance from E-W Function of the Pipe Rupture Identification Break # Elevation Containment Containment Restraint Type Restraint 3RCS-PRR861 8 10'-3" 25'-1" East 6'-3" South Laminated Strap (1) 3RHS-PRS1A 9 13'-7" 20'-7" East 4'-6" South Limit Stop (1) 3RHS-PRS2A 4,5,6, or 7 14'-7" 29'-2" East 4'-6" South Laminated Strap (2) 3RCS-PRR6A 10 18'-9" 17'-2" East 17'-2" South Laminated Strap (3) 3SIL-PRR4A TP & Splits 16'-2" 20'-2" East 11'-10" South Shock Suppressor (4) 3RCS-PRR6B 10 18'-9" 17'-2" West 17'-2" South Laminated Strap (3) 3SIL-PRR4B TP & Splits 16'-2" 20'-2" West 11'-10" South Shock Suppressor (4) 3RCS-PRR6C 10 18'-9" 17'-2" West 17'-2" North Laminated Strap (3) 3SIL-PRR4C TP & Splits 16'-2" 20'-2" West 11'-10" North Shock Suppressor (4) 3RCS-PRR862 8 10'-3" 25'-1" East 6'-3" North Laminated Strap (1) 3RHS-PRS1D 9 13'-7" 20'-7" East 4'-6" North Limit Stop (1) 3RHS-PRS2D 4,5,6, or 7 14'-7" 29'-2" East 4'-6" North Laminated Strap (2) 3RCS-PRR6D 10 18'-9" 17'-2" East 17'-2" North Laminated Strap (3) 3SIL-PRR4D TP & Splits 16'-2" 20'-2" East 11'-10" North Shock Suppressor (4) 1 of 2 Rev. 16
MPS-3 FSAR NOTES TO FIGURE 3.6-13 CONTD Notes (1).Pipe rupture restraint prevents unrestrained pipe whip into the East-West Cubicle Wall. Catastrophic failure of the East-West Wall is credible if subjected to unrestrained pipe whip impact by either the Residual Heat Removal Piping or the Low Pressure Safety Injection piping to the Hot Leg. (2).Pipe rupture restraint is provided to prevent the Residual Heat Removal line from impacting the Containment Liner. Leak tight integrity is required subsequent to a Large LOCA and the unrestrained pipe whip subsequent to a postulated break on the Residual Heat Removal line would violate this criteria. (3).This terminal end break occurs at the Cold Leg Nozzle and results in a large LOCA. The NSSS System Standard Design Criteria requires that break propagation in the affected loop cannot exceed 20% of the flow area of the broken line. The Reactor Coolant System Loop Stop Valve Bypass Line identified has a nominal pipe size of 8" and therefore, if the 8" Loop Stop Valve Bypass Line is impacted, pressure boundary integrity must be assured. The pipe rupture restraint indicated prevents the impact. (4).The Terminal End (TP) break or Longitudinal Split (LS) does not result in a LOCA. The NSSS System Standard Design Criteria delineates requirements for a Large Line Break that does not result in a LOCA. The requirement is that a Non-LOCA cannot propagate into a LOCA. If unrestrained, the broken pipe would induce significant loading upon the Reactor Coolant System pressure boundary. The pipe rupture restraint is provided to prevent this effect. 2 of 2 Rev. 16
PRESSURI ZER 3RCS-TKI 3-RCS-OOG-Ga-. NOTES I . POSTULATED PIPE RUP TURE L OC A TfG~~ ON 3-RCS - OI4 1 PRESSURIZER SURGE LINE ARE LI S T~D I N TABLE 3.6-15 AS BREAKS 67l THROUGH t4I AND (fi)FOP. CLARIT Y. DUE TO THE ENERGY QUANTITt'OF BREAKS.LOCA ncms Ot~L Y FOR TERMINAL ENOS SEE NOTE 2 J.ffiU' ARE SHOWN_ PRESSURIZER 3RCS- T K1 2. POSTULATED PIPE RUPTURE LOCAT I ONS~N THE SAF~Y AND RELIEF LINE PI PI NG ARE BREAr.S 18 THROUGH IN TABL E 3.6-15 ON THE HIGH ENERGY PORTI Ofl SAFETY A RELIEF PI PING. PIPING DESI GNATED AS - - - I S MODERATE ENERGY BEYOND THE VALVES.
- 3. POSTUL ATED PI PE RUPTURE LOCt<TIONS ON THE PRESSURI ZER SPRAY LI NE ARE BREAKS(DTHROUGH @ IN TABLE 3.6- 15.
3- RCS*27 S-10*1 PRESSURI ZER SURGE LINE - SEE NOTE 1 3 -RCS-004 \ FIGURE 3_6 -14 REACTOR COOLANT SYSTEM PRESSURIZER CUBICLE PIPING PRESSURI ZER SPRAY LINES - SEE NOIE 3 MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FILE: 36 14.dgn / 36 14.c l t APRI L 1998
MPS-3 FSAR NOTES TO FIGURE 3.6-14 DATA FOR PIPE RUPTURE RESTRAINTS REACTOR COOLANT SYSTEM PRESSURIZER CUBICLE PIPING Restraint Distance from N-S Distance from E-W Identification Break # Elevation Containment Containment Restraint Type Function of the Pipe Rupture Restraint 3RCS-PRR1 11 22'-4" 15'-7" West 13'-5" South Laminated Strap (1) 3RCS-PRR3 (2) 22'-6" 5'-5" West 40'-6" South Limit Stop (3) 3RCS-PRR4 (2) 22'-6" 5'-0" West 44'-7" South Limit Stop (3) 3RCS-PRR5 (2) 22'-6" 8'-4" West 47'-8" South Omni-Directional (3) 3RCS-PRR6 (2) 22'-7" 19'-8" West 47'-8" South Omni-Directional (3) 3RCS-PRR7 (2) 22'-7" 19'-9" West 41'-6" South Omni-Directional (3) 3RCS-PRR8 (2) 23'-1" 11'-6" West 41'-0" South Limit Stop Prevents Impact to 3RCS*TK1 Ring Girder 3RCS-PRR906 (2) 78'-0" 9'-3" West 36'-3" South Pipe Crush Bumper (4) 3RCS-PRR945 (2) 76'-2" 10'-2" West 46'-6" South Laminated Strap (4) 1 of 2 Rev. 16
MPS-3 FSAR NOTES TO FIGURE 3.6-14 CONTD Notes (1).Pipe rupture restraint prevents the Pressurizer Surge Line from impacting the support system for the Steam Generator, 3RCS*SG1B. (2).See FSAR Table 3.6-16 for the specific break location. (3).The Crane Wall, Steam Generator Cubicle Wall and Pressurizer Cubicle Wall if subjected to unrestrained pipe whip of the Pressurizer Surge Line would catastrophically fail. As a result, damage to essential systems subsequently to secondary missiles, etc., is credible. The pipe rupture restraints are provided to prevent the unrestrained impact to these structures. (4).The NSSS System Standard Design Criteria does not permit break propagation from the Pressurizer Relief Line (Steam Phase) to the Pressurizer Spray Line (Liquid Phase). The pipe rupture restraint is provided to prevent the interaction. 2 of 2 Rev. 16
CHARGING PC)'-tP CUBICLES NOTES SEE NOTE 2 I. PQSTULATED BREAKS <DTHROUGH AND @ THROUGH ~ ARE ON THE REACTOR COOLANT SYSTEM PORTION OF NORMAL CHARGING AND ARE L [STEO IN TABLE 3.6- l 2.
- 2. PIPE BREAKS IN THE CHARGING PUMP CUBICL ES ARE POSTULATED ro SEAL WATER AT TERMINAL ENOS AND AT ANY VALVE , FITTING , QR INJECTION FILTER eONTtHUED OH INTEGRAL ATTACHMENT.
FIGURE 3.6 *t1 FIGURE 3.6-\5 CHEMICAL AND VOLUME CONTROL SYSTEM-CHARGING LINE PIPING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FILE: 36I5. dgn/3615.c l t JANUARY 1998
MPS-3 FSAR NOTES TO FIGURE 3.6-15 DATA FOR PIPE RUPTURE RESTRAINTS CHEMICAL VOLUME CONTROL SYSTEM - NORMAL CHARGING Distance from N-S Distance from E-W Function of the Pipe Rupture Restraint Identification Break # Elevation Containment Containment Restraint Type Restraint 3CHS-PRR911 35 13'-2" 52'-4" West 69'-7" North Pipe Crush Bumper (1) 3CHS-PRR912 35 12'-3" 52'-0" West 69'-0" North Pipe Crush Bumper (1) 3CHS-PRR913 34 12'-6" 51'-8" West 68'-7" North Solid Bumper (1) Note (1) Pipe rupture restraints were originally specified to limit stress in the containment penetration area and containment isolation valve. However, this break exclusion zone was eliminated based on technical justification provided in calculation 97-ENG-1329-M3, since a charging line break outside containment is a non-LOCA break which does not require containment isolation. 1 of 1 Rev. 16
NOTES
- l. ANY PORTION OF THE LETDOWN LINE PIPING WHICH IS SHOWN DOTTED,DENOTES A MODERATE ENERGY LINE.
- 2. PIPE BREAKS ON 3-CHS-002-BO-2 IN THE ESF BUILDING ARE POSTULATED AT ALL VALVES, FITTINGS,AND INTEGRAL ATTACHMENTS TO ESf BUILDING 3. A PIPE BREAK EXCLUSION ZONE EXTENDS FRO'" THE OUTBOARD SIDE OF SEE NOTE 2 CONTAINMENT PENETRATION TO THE OUTBOARD CONTAINMENT ISOLATION VALVE.
- 4. POSTULATED BREAKS (DTHROUGH ARE ON THE REACTOR COOLANT SYSTEM PORTION OF LETDOWN AND ARE LISTED ON TABLE 3.6-12 CONTINUATION OF
)-CHS-Q02-BI-2 FIGURE 3.6-16 CHEMICAL AND VOLUME CONTROL SYSTEM- LETDOWN LINE PIPING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FILE:3616.dgn/3616.clt JANUARY 1998
MPS-3 FSAR NOTES TO FIGURE 3.6-16 DATA FOR PIPE RUPTURE RESTRAINTS CHEMICAL VOLUME CONTROL SYSTEM - LETDOWN LINE Restraint Distance from N-S Distance from E-W Identification Break # Elevation Containment Containment Restraint Type Function of the Pipe Rupture Restraint 3CHS-PRR870 (1) 7'-0" 17'-0" West 36'-6" North Shock Suppressor (2) 3CHS-PRR858 (1) 5'-2" 22'-0" West 41'-0" North Shock Suppressor (2) 3CHS-PRR967 26 12'-6" 60'-2" West 75'-3" North Dual Function Limits Stress to Pipe Break Exclusion Zone 3CHS-PRR968 (3) 20'-2" 55'-10" West 78'-0" North Dual Function None Notes (1) The Terminal End (TP) postulated pipe break number 9 is the only break on the Class 2 portion of the Chemical & Volume Control System Letdown Line piping. This TP is at the inlet to the Regenerative Heat Exchanger, 3CHS*E1, and is remote from the Class 1 portion of the Chemical & Volume Control System Letdown Line piping. Therefore, break propagation from the Class 2 portion of the Chemical & Volume Control System Letdown Line piping to the Class 1 portion (i.e., Propagating a Non-LOCA into a LOCA) does not occur. (2) Pipe rupture restraints 3CHS-PRR870 and 3CHS-PRR858 are provided to prevent propagation of a Non-LOCA into a LOCA. The NSSS System Standard Design Criteria does not permit break propagation of a Non-LOCA into a LOCA. The pipe rupture restraints 3CHS-PRR870 and 3CHS-PRR858 limit displacement of the Class 1 piping subsequent to a pipe break on the Class 2 portion of the Chemical & Volume Control System Letdown Line piping. (3) Pipe Rupture Restraint 3CHS-PRR968 is provided to mitigate the effects of an Arbitrary Intermediate Break (AIB). USNRC Generic Letter 87-11 eliminates the requirement to evaluate the dynamic effects of AIBs. Therefore, this pipe rupture restraint has no safety-related function. 1 of 1 Rev. 16
OtAAClNG PU~p CUBICLES S[ £ NOTE ' NOTES 1 PIPE BREAKS IN THE CHARGING PUMP CUBICLES ARE POSTULATED
. AT VALVES. FITTINGS. INTEGRAL ATTACHMENTS, AND TERMINAL ENOS.
FIGURE 3 .6-17 CHEMICAL AND VOLUME CONTROL SYSTEM-SEAL WATER INJECTION PIPING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FIL E: fi<;l3617/fig3617.ci t J ANUARY 1'3'38
" %__ A\
')...B9G ~ 004 - 9 a* 4-"
3~ B DO - 0 0 4 2 T ll),J[ TO SGl.I NOTES
- 1. BRE AK LOCAT IONS ARE TYPICAL FOR ALL LOOPS OUTS IDE CONTAI NM ENT.
- 2. --- DEN OTES A COMBINATION PIPE SUPPORT I PIPE RUPTURE RESTRAINT.
- 3. STEAII CENERATOR llUllII10IIN LINE PIPINC llErllE£N TIE:'
1ll0lf1l0llll TAJ<< eeoe-nn &NO E..eH ~nllATE .lIIClQl IS 101 NUCLEAR. _ SEISMIC. BREAkS IJl[ POSlULolTEO IN olCCIlROAHCE WITH TIE: CRITERIA IH SEcn()l 3.6.2.L2.~o
&ND "J!E AT "lL FITTINGS, V"lVES .&HI) waDEl> "UolCIAE.NTS.
4.. A PIPE llR£AK EXCWSI()I ZONE IS OESIGmTED FOl THE
$TEAu GOERATIJl 1ll01lD0'lN lllE. TlE: OREAl EXClUSIlJl ZONE EXTEHOS nlOU THE OUTBOARll ClJI TAINIIDI T P£NETIlATllJl TO THE OUTl\OARO ClJITAllAlENT ISOUn()l VALVE. TIE: EXTENT Of TI£ BREAk EXClUS!lJI lONE IS T'lPICAl FOR "ll ~ 1IHEs.
TlE: BREAk EXCLUSllJl llH: CRITERIA IS 0EF11O Dl SECTllJl 3.6.2.1.2.2.
- 5. T£JlI.IDl"l Del AS OESCIlIllEl) IN NOTE 3 Of TollllE 3.6-30 .
FIGURE 3.6-18 STEAM GENERATOR SLOWDOWN SYSTEM MILLSTONE NUCLEAR POWER STAT ION UNIT 3 FINAL SAFET Y ANALYSIS REPORT CAD FILE: 36t8.<lQn/3618.cl t - - --- _._ - - - - - -- - - - - - - - - -- - - -- - - - --- - - ---- -- -- ---- _._ - - - -- -- - - --- - --- _._- - - - - - - - - - -- - - - - - - - - --- -- ---- JANUARY 19 98
MPS-3 FSAR NOTES TO FIGURE 3.6-18 DATA FOR PIPE RUPTURE RESTRAINTS STEAM GENERATOR BLOWDOWN SYSTEM Restraint Distance from N-S Distance from E-W Identification Break # Elevation Containment Containment Restraint Type Function of the Pipe Rupture Restraint 3BDG-PRR972A 2 22'-2" 37'-6" East 8'-10" South Laminated Strap Prevent impact to Steam Generator Shell 3BDG-PRR975A 1 21'-1" 37'-6" East 7'-4" South Pipe Crush Bumper Prevent impact to Steam Generator Shell 3BDG-PRR885 29 20'-6" 76'-3" West 10'-1" North Dual Function Limits Stress to the Break Exclusion Zone 3BDG-PRR886 5 20'-0" 77'-3" West 7'-2" North Shock Suppressor Limits Stress to the Break Exclusion Zone 3BDG-PRR941 6 20'-0" 77'-4" West 6'-9" North Shock Suppressor Limits Stress to the Break Exclusion Zone 3BDG-PRR948 7 19'-6" 76'-2" West 10'-7" North Solid Bumper Limits Stress to the Break Exclusion Zone 3BDG-PRR972B (1) 22'-2" 39'-1" West 11'-7" South Laminated Strap Prevent impact to Steam Generator Shell 3BDG-PRR975B 8&9 21'-1" 39'-9" West 9'-5" South Pipe Crush Bumper Prevent impact to Steam Generator Shell 3BDG-PRR973 10 20'-6" 59'-9" West 5'-4" North Dual Function Prevent impact to Containment Liner 3BDG-PRR887 30 20'-6" 75'-6" West 6'-9" North Dual Function Limits Stress to the Break Exclusion Zone 3BDG-PRR888 12 20'-0" 76'-5" West 3'-4" North Shock Suppressor Limits Stress to the Break Exclusion Zone 3BDG-PRR942 13 20'-0" 76'-5" West 2'-11" North Shock Suppressor Limits Stress to the Break Exclusion Zone 3BDG-PRR946 12,13, or 14 21'-7" 76'-4" West 5'-0" North Dual Function Limits Stress to the Isolation Valve Stem 3BDG-PRR950 14 19'-6" 74'-11" West 10'-6" North Solid Bumper Limits Stress to the Break Exclusion Zone 3BDG-PRR972C 17 22'-2" 37'-5" West 8'-10" North Laminated Strap Prevent impact to Steam Generator Shell 3BDG-PRR975C 15 & 16 21'-1" 37'-11" West 7'-3" North Pipe Crush Bumper Prevent impact to Steam Generator Shell 3BDG-PRR970 51 20'-6" 52'-1" West 10'-7" North Laminated Strap Prevent impact to Steam Generator Supports 3BDG-PRR971 (1) 21'-1" 45'-0" West 4'-9" North Pipe Crush Bumper Prevent impact to Steam Generator Supports 3BDG-PRR884 31 20'-6" 74'-11" West 17'-8" North Dual Function Limits Stress to the Break Exclusion Zone 1 of 2 Rev. 16
MPS-3 FSAR NOTES TO FIGURE 3.6-18 DATA FOR PIPE RUPTURE RESTRAINTS STEAM GENERATOR BLOWDOWN SYSTEM Restraint Distance from N-S Distance from E-W Identification Break # Elevation Containment Containment Restraint Type Function of the Pipe Rupture Restraint 3BDG-PRR883 19 20'-0" 74'-9" West 20'-8" North Shock Suppressor Limits Stress to the Break Exclusion Zone 3BDG-PRR943 20 20'-0" 74'-8" West 21'-2" North Shock Suppressor Limits Stress to the Break Exclusion Zone 3BDG-PRR947 21 19'-6" 74'-11" West 12'-2" North Solid Bumper Limits Stress to the Break Exclusion Zone 3BDG-PRR972D (1) 22'-2" 39'-1" East 11'-7" North Laminated Strap Prevent impact to Steam Generator Shell 3BDG-PRR975D 22 21'-1" 39'-7" East 9'-5" North Pipe Crush Bumper Prevent impact to Steam Generator Shell 3BDG-PRR974 25 20'-6" 58'-10" West 16'-7" North Laminated Strap Prevent impact to Containment Liner 3BDG-PRR882 32 20'-6" 72'-11" West 20'-7" North Dual Function Limits Stress to the Break Exclusion Zone 3BDG-PRR881 26 20'-0" 72'-9" West 23'-9" North Shock Suppressor Limits Stress to the Break Exclusion Zone 3BDG-PRR944 27 20'-0" 72'-8" West 24'-3" North Shock Suppressor Limits Stress to the Break Exclusion Zone 3BDG-PRR945 26,27,or 28 21'-7" 73'-1" West 22'-7" North Dual Function Limits Stress to the Isolation Valve Stem 3BDG-PRR949 28 19'-6" 73'-9" West 11'-10" North Solid Bumper Limits Stress to the Break Exclusion Zone Note (1) Pipe Rupture Restraint mitigates the effects of an Arbitrary Intermediate Break (AIB). USNRC Generic Letter 87-11 eliminates the need to evaluate the dynamic effects of AIBs. 2 of 2 Rev. 16
SLOWDOWN 1------------ THRUST DEVELOPMENT
,. )0 PIPE WHIP PIPE DYNAMICS
** ,r PIPE-RESTRAINT PI PE-CONCRETE INTERACTION WALL IMPACT INTERACTION FORCE, (SOFT-SOFT) INERTIAL LOADS (SOFT- HARD)
LOCAL EFFECTS
" LOCAL
>-,MPACT 1---------------
PENETRATION SPALL LOCAL WALL RESPONSE STRUCTURAL ADEQUACY STRUCTURAL RESPONSE FULL
)0 STRUCTURE RESPONSE AND INTERACTION STRUCTURAL ADEQUACY RESPONSE FIGURE 3.6-19 PIPE RUPTURE ANALYSIS FLOW CHART MILLSTONE NUCLEAR POWER STAnON UNIT 3 FINAL SAFETY ANALYSIS REPORT
2.0
~ -1<t1. 6 u-a..
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o ffiO.S o
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" : 1.-' :
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CONCRETE WALL
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---- (\J
~-+-----~INTERMEDIATE STRUCTURE 1'-1 .c:
(\J r<>~ CO.o INTERNAL PRESSURE FOR CE DISTRI BUTED ALONG THE ELBOW_~'vl FIGURE 3.6-21 PIPE, RESTRAINT, INTERM EDIATE STRUCTURE SYSTEM ATTACHED TO THE MATHEMATICAL MODEL STEAM GENERATOR . . .:
- ',~: ' . :.:,:~,...: ~.'>':>.:".~:' ~: MILLSTONE NUCLEAR POWER STATION UNIT 3 oo{. " ,-.
FINAL SAFETY ANALYSIS REPORT
LAMINATED MIN'K INSULATION OR EQUIVALENT STRIP PROCESS PI P E c.--:=-:L=- - - LUG SPHERICAL BEARING CLEVIS RETAINER RING I PIN I I BUSHING I L -1I ATTACHMENT STRUCTURE FIGURE 3.6-22 LAMINATED STRAP RESTRAINT FOR SMALL LINES MILLSTONE NUCLEAR POWER STATION UNIT 3 FIN AL SAFETY ANALYSIS REPORT
40 . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - , 20.
-0.
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--l I
sr -20. 0 ( J) Z 0 -40. f 0 w 0:: f-W -60. Z
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__l.__~-..l.----.L--------II..__ o 004 0.08 0.12 0.16 0.20 0.24 0.28 TIME (SEC.)
- 10-1 FIGURE 3.6- 23 FEEDWATER SYSTEM SHORT LOOP STRAP NEAR THE STEAM GENERATOR, NET SHEAR FORCE AT NODE 10 MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
- 60. , . . . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ,
- 40.
-80. ,.. I I I I I I 0.04 0.08 0.12 0.16 0.20 0.24 0.28 TIME (SEC.) *10- 1 FIGURE 3.6-24 FEEDWATER SYSTEM SHORT LOOP STRAP NEAR THE STEAM GENERATOR, NET SHEAR FORCE AT NODE 14 MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
- 50. , . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ,
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o 0.04 0.08 o .12 0 .1 G O . 20 0.24 0.28 TIME (SEC.) *10- 1 FIGURE 3.6 - 25 FEEDWATER SYSTEM SHORT LOOP STRAP NEAR THE STEAM GENERATOR, NET MOMENT FORCE AT NODE 14 MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
180 160 140 120 v 0 100 (II
...J lJJ (J
0: 80 0 u, 60 40 20 OL. L..-.._ _----J'---_ _- . l ---l. ---L --L ....J o 0.02 0.04 0.06 0.08 0.10 0.12 0.14 T I ME (SEC.l~ 10-1 FIGURE 3.6-26 DOTTED LINES INDICATE FORCE ACTING ON THE STRAP THE LOAD PATH NODE 8 MI LLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
640. r------------------------------. 560. 480.
.~ .--.- .
<;t o r-4uO. cD
.....J I
Z 320.
<.?
0:: W Z 240. W 160.
- 80. ~ELASTIC 0.04 0.08 0.12 0.16 0.20 0.24 0.28 TIME (SEC.) *10' FIGURE 3.6-27 FEEDWATER SYSTEM SHORT LOOP STRAP NEAR THE STEAM GENERATOR,ENERGY MI LLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
- 'Q'. ~.:
fl.'
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<l
--------- Lh------ *I
/>~.~,' I
~BREAK I
r,' . '<\ I , ~ .. LOCATION I , ~', t- I ' . "1 6' '<1' ", , ,.4 .
* <; ~' *
- ... ~ PIPE CRUSH Bl,JMP~, R
/.~~:l~~~~--;---- SHIMS
- . <1.4:
- ~'.: .' :II------r-~J_.
.4,' : \;!: L..-_-~INTERMEDIATE STRUCTURE **.*4*
, t;, . .~. ' ;
" ,~.
- U*:. '
- -:. 4:
- II '.' . :
- ';j'~'"
~ 4'A
- d',
',4'. ,i: STEAM GENERATOR FIGURE 3.6- 28 ENERGY BALANCE ANALYSIS MODEL MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
f f '
+ r=~=--=F=====~- .,
1-' I I
~- ---~
I I
~
lSEE DETAIL "A"
- - - - - - +- - - - - -
S (E) S (E) DETAIL II AII FIGURE 3.6-29 PIPE CRUSH BUMPER MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
PROCESS PIPE IMPACTED CRUSH PIPE BEARI NG PLATE
<t. THRU BOLT PIPE CRUSH BUMPER
--i+-- RECTANGULAR WASHER END VIEW OF PIPE FIGURE 3.6-30 PIPE CRUSH BUMPER MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
GAP ARCH PIPE RUPTURE RESTRAINT BODY
---t+-+-+--+-~P 3
SHIMS DEAD WEIGHT SUPPORT SHEAR BLOCK (TYP) I II I II I II A I II l f-----, JAM NUT NUT SLEEVE STUD HONEYCOMB RESTRAINT (2-PER SIDE) (2-PER SIDE) PANEL ATTACHMENT PANEL SECTION A-A FIGURE 3.6-31 OMNI- DIRECTIONAL PIPE RUPTURE RESTRAINT MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
MPS-3 MP3-UCR-2013-Q03 FSAR MMPS-3 FSAR NOTES'
;. ;;~:~P~~~SHOWNOOTTEll} DENOTES A MODERATE
- 2. ~p~Ar ~UCnILNS ARl AS DE.I'I>JHl IN TI1£
'Cf."TG-N "'ASIc, 'lRFAK LOCt.nON [I'L(ULATlON.
3.6.J-.:DlCATES ClRCU\1f£'1E,,*nAL. BREAK. 4 ..... NOItLTFS tI:::(U~Ff~Ff\TlAL AND '~DNGlTlJOlNAL BREAK. Updated Figure FIGURE 3.6-32 AUXILIARY FEEDWATER SYSTEM c .... O FILE; m33632.dgn/m33632.c:i-t JANUARY 2013
NOTES:
- 1. PIPING SHOWN---DENOTES A MODERATE ENERGY PIPING SYSTEM.
- 2. POSTULATED PIPE RUPTURE LOCATIONS AND THE GEOMETRY ARE TYPICAL FOR THE REACTOR COOLANT SYSTEM PRIMARY COOLANT PIPING DRAIN LINES <INCLUDING EXCESS LETDOWN) IN EACH STEAM GENERATOR CUBICLE. PIPE RUPTURE LOCA nONS ON THIS PIPING ARE POSTULATED AT ALL TERMINAL ENDS. VALVES AND FITTINGS.
INTEGRAL WELDED ATTACHMENTS ARE NOT UTILIZED ON THE DRAIN LINES.
- 3. PIPING GEOMETRY FOR THE REACTOR COOLANT SYSTEM LOOP FILL LINES ARE TYPICAL IN EACH STEAM GENERA TOR CUBICLE*
~ I.~; .--_ -_~':'~.c::;~~~'~':'::':'.~. :.
- ~ .:*:*r*#*,~* - --= PIPE RUPTURE LOCATIONS ON THIS PIPING ARE POSTULATED TO OCCUR AT ANY TERMINAL END VALVE OR FITTING. INTEGRAL WELDED
- 1>; :.' I 3-RCS-002-24;7-1 ATTACHMENTS ARE NOT UTILIZED ON THIS PIPING SYSTEM. THE LOOP
.>>: REACTOR _ FILL LINE GEOMETRY IS SHOWN AS DETAIL C AND D.
STEAM COOLANT) I GENERATOR PUMP I I 3RCS*PIO 3RCS.SOID 4.REFER TO FIGURE 3.6-15 FOR PIPE RUPTURE LOCATIONS FOR
- - NORMAL CHARGING LINE PIPING WITHIN RCS BOUNDARY.
5.REFER TO FIGURE 3.G-16 FOR PIPE RUPTURE LOCA nONS FOR LETDOWN LINE PIPING WITHIN RCS BOUNDARY. 3-IlCS-21!H4-1 REACTOR COOLANT PUMP
\ I
- t -3RCS.PPII'C~D<:1-~~~~~;;;~;;~_
J,; 3'RCS-031-13-1 1\ 3-RCS-002-135-1 [3-RCS-002-176-1 ~~><r-'l.- -\ SEE OETAIL '0' DETAIL' '0' T
' _ 3-CHS '002-240-2 FIGURE 3.6-33 REACTOR COOLANT SYSTEM SMALL BORE PIPING IN STEAM GENERATOR r3-RCS-002-174-1 CUBICLES
)..-~><t--1'L - -4 MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT DETAIL 'c' CAD FILE: 3633.dgn/3633.cit JANUARY 1338
CONTAINMENT RIBBED FIBERGLASS PROTECTION BOt..RD 2" COMPRESS IBLE ADJACENT MATERIAL------::::::- BUI LDING (BOTH SIDES OF (MEMBRANE) WATERPRoOFING ---,l-~lil'f o MEMBRANE RING GIRDER --.:...~. {SEE FIG.3 .8 .1-Z31 .* ,. a Z"CONCRETE SEAL FACE OF ROCK (ABOVE AND BELOW EXCAVATION
- MEMBRANE)
TOP OF RING GIRDER - -__H-:--- 4"-#4 CRUSHED STONE j i a >, I
\ I DETAIL A WATERPROOFING----~_+_-~~
MEMBRANE DETAIL A CONTAINMENT STRUCTURE FOUNDATION MAT CONCRETE BLOCt< ------~!1~;t=::;~;:;::;;::;:;:;:::========~ LEVELING CONCRETE FIGURE 3.8-1 CONTAINMENT STRUCTURE FOUNDATJON DETAIL MILLSTONE NUCLEAR POWER STATION UNIT3 FINAL SAFETY ANALYSIS REPORT CAD FILE: 381.d9n/381.ci t NOVEMBER 1997
~-NI8 BEND LINE It. LINER DIAGON A L BARS FIGURE 3.8-2 TYPICAL DETAIL OF DOME CYLINDER JUNCTION MILLSTONE NUCLEAR POWER STATION UNIT :3 FINAL SAFETY ANALYSIS REPORT
- - EL.(-)23'-11 3/4" 1/4" - 6000LB.HALF COUPLlNG,(DET HA B-1)
- EL .{-) 24'* 2 3/4" EL .(-)24'-6"-
I
- 1
- 1 TEST MEMBER AT II - KNUCKLE PLATE
- JOINT DETAIL KNUCKLE PLATE 72 - 72 ~TOP OF
,/ CONCRETE FILL (C- 8)
SCALE :3":/'-O"
< ~.: :<,.~.
',..:=.': .'
~~ . : ~;.
REF.R . : 7 0 ' - O " - - - - - 1 3/8" LINER -----o-{I---
~"BRIDGING Ft
!" STEEL MAT LINER rTO? OF 1---- KNUCKLE PLATE c::z::::;¢~!:;;;;:;:;z:::ps--L CONCRETE MAT TOP OF MAT REBAR ANCHORS EL.(-) 27' -3" NO. 10 DOWEL CONCRETE 1/4" LINER - - - - - ' (J \>
FULL PENETRATION DETAIL BRIDGING PLA TE WELD (TVP) SCALE: NONE TYP SECTION FIGURE 3.8 - 3 KNUCKLE PLATE KNUCKLE PLATE SCALE!) 1/4':1'-0" MILLSTONE NUCLEAR POWER STATION UNIT :3 FINAL SAFETY ANALYSIS REPORT CAD FILE: 383.dgn/383.cit NOVEMBER 1997
70'-0"RAD~ FLAT BAR (TYP.) 2'-2" 5 SPCS. AT 3'-0" 58'- 0" RADIUS SHEAR BAR PLACED UNDER RADIAL BARS SHOWING SHEAR BARS ONLY (A DO' L. BARS E. OETS. SEE SECT. 2-2, C-7) SCALE: 1/8": 1'-0" 4'- 6" 4'- 6" 70'-0" RADIUS 4 C 5"CL. NO. 18 DIAG. BARS -+--...".----l~~j_tr~r FLAT BARS BRIDGING TOP OF MAT EL(-)27'-3"
-. :j.~.
.. ~*.l" t
<t NO 188. NO.1' CIRC. BARS ~
SHEAR BARS ro
-'a 3"CL.
TYP. SECTION SCALE'1/8":1'-0" FIGURE 3.8-4 MAT REINFORCEMENT WITH RADIAL SHEAR BAR ASSEMBLY MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
MAIN STEAM PENETRATION MAIN STEAM PENETRATION 14'-0" SHEAR ASSEMBLY (24 ASSEMBLIES AROUND EA MAIN STEAM PENETRATION) 12ASSEMBLIES PLACED AS SHOWN W/PT "A' TOWARDSOUTSIDE FACE OF WALL, ALTERNATING W/12 ASSEMBLIES PLACED W/PTA TOWARDS INSIDE FACE OF WALL EXTRA HORIZ. BARS CL MAIN STM PENS EL.66'-3"J I J(C-4) 7'- 30" ELEVATION 11-II(F-3) SHOWING LOCATION OF SHEAR ASSEMBLIES AT MAl N STEAM PENE TRATIONS SCALE - 3'/'32 = I' - 0" MAIN STEAM EL.66'- 3" 'r:--J---i-~- SHEA R ASSEM BLY ------1If---Hi8=--I!/,Y'/.JIII FIGURE 3.8-5 REINF. AROUND MAIN STEAM PENETRATIONS MILLSTONE NUCLEAR POWER STATION UN-IT 3 FINAL SAFETY ANALYSIS REPORT 6-6 (E-I)
70 -0 R 4 -6 LI NER 1'-3" A
'1,*-,* No 18 CIRC BARS r - EXTRA DIAG e. VERT REINF
~.q) FUEL T RANSFER TUB E
~ y tjO""O No,ll STi R RUPS -
NQ. 18 T YP VERT RE I NF , No,18 EX TRA DlAG REINF I III
~
No,IS TYP VERT REINF - f- No ,18 TYP DIAG REIN F 8 e. No 14 EX TRA DIA G RE1N F ~> No. I S TYP HORIZ REINF E.- l - :'1( :> o '0 0 o I'" .'\ 1 TYP HORI~ REINF : r-No,14 EXTR A HORIZ REINF No. 18 T YP HORIZ REINF
'" , TYP,DIAG REINF,
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- 0 No, l1 'Q) 12" RADIA L STI RRUPS IN
~ I'" 11'\
N (J) GROUPS OF :3 '" '" '" '" [0 <:: G G ~ °CD a: IWo "e p CD e=J I <l: '
~~ ~0 ~
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l" No.6 'ci)12" TR ANSVERSE STIRRUPS 1'1 I", I'l "'), t: 0 O nO Jl", ,'" z 0 e p G p 0 IN GROUPS OF 3 :'~~;~ j.~ '
'" .:.: :':~~ 00:
i B (!) ~ I ~I '0
- * -<:: ' (!) :> El ' '- No, 6 STIRRUPS TYP VERT REINF--!
.0'
~. ~ m g~e~ t::-..A ; I
.:,':1. *' . r .:...:~; 7 '-0" OI A
~ I 6'-6f '-No, 18 EXTRA OIAG RE1NF PERS HATe H -l * .
N: '6 HORtZ i EINF
- L 'XTr 2 -2 ( EC- 4 9L ,H- 5)( 11 0 3 l) 1'-4i" 1'- 7 41 11' -0" 1'-a " 1'-4~8 I I I 1-1 (EC-49L,E -2) (11031)
SCALE 3/11 " =1'- 0" FIGURE 3. 8 - 6 REINFORCING DETAILS SECTIONS THROUGH RING BEAM OF PERSONNEL ACCESS LOCK MILLSTONE NUCLEAR POWER STAT ION UNIT 3 FINAL SAFETY ANALYSIS REPORT
- t. CADWELD FOR # 18 VERT BARS (MK-I) AT PERSONNEL, HATCH ONLY
" /
/A".~",,;r.o.-l CADWELD FOR
""'.1 V,," #18 VERT BARS (MK-t) AT PERSONNEL, HATCH ONLY REF: EC 49M-3 FIGURE 3.8-7 REINFORCING DElAI LS PERSONNEL ACCESS LOCK OPENING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
70' - O"R - LINER ~ I. 2'-0" 2'-0" J
, 4 2 ' _ 6 -i" Ir~"
1 ~~ ~
. :~~ I #18E XTRA DIAG. REINF. I~ #18 TYP. V ERT. REINF.
I
#IS TYP. VERT. REINE - -to I r --~ 18 CIRC BARS I
g~, '18 TYP. D lAG. REINE r.
- t. #14 V ERT REINF. EXTRA I
- ~.:.-:';
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-#11 STIRRUPS
#IS T YP. HORIZ. REINF Eo _ ~I :~~'~." iJj~ I 1114 EX TRA HORIZ. REINE .... #18 TYP. HORIZ. REINF.
~. I
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e pc c GROUPS OF 3 aoRo p ~ ( Vl " ( 0:: f' < I~
, <t 18 U en III 80 0 p e E e o < c c I U
-... 0::
8 Q u G CD #6 <Cl12" TRANSVERSE STIRRUPS
~
G o 1Jl ° ° G c U - IN GROUPS OF 3 p " 08 0 o
'o "'~
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- 1" HATCH on ~P ~
I.... ...o ~ r 1-8 I-OJ 1-11 1
-l1r 2
~~t~~' ," 4 -11.
3-3 4-4 FIGURE 3.8- 8 TYPICAL REINFORCING DETAILS SECTIONS THROUGH RING BEAM OF EQUIPMENT ACCESS HATCH MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
15'-0" (TYP) TYP ICAL QUADRANT FIGURE 3.8-9 REF.: EC 496 REINFORCING DETAILS EQUIPMENT ACCESS HATCH OPENING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
<l CONTAINMENT STRUCTURE 35 '*0" LIMIT OF BARS-b ( SYMMETRICAL) 17'-6"UMITS OF BARS - c LI MIT OF BARS -d 2'-5 " LIM IT OF BARS - a CONT ENCL. SPT. (TYP)
TEMP DOME VENT PLAN A(H-4) DET-A (J-3) 4'-0" LIMIT OF BARS-e PLAN B (J-5) Cf.cOL.
, 5" iCOL.
w 2 8 Z l ...J ..J o C1'l a.: U \() '- I<r CO(/) I y 1 -+---++- I (\J
=' d
..... V~
-- -- I---
-i f-4"-an - .--
j
-\()
-- I'" rEO.Sf? 2( L-5)
PLAN A (F-2) - I C\J I ". PEDESTAL TYPE-) 6 REQUIRED -'--- I" 4 2 1'_lt 8 14 2 f -, r I"~ PLAN 8 (E -2.) PED ESTAL TYPE-2 12 REQUIRED FIGURE 3.8-10 BASE PLATE DETAILS CONTAINMENT ENCLOSURE STRUCTURE MILLSTONE NUCLEAR POWER STATION UNIT 3 F INAL SAFETY ANALYSIS REPORT
E ct. CONT STRUCT NO. 18 CIRCUMF BARS (TOP) RADIAL BARS (TOP) NO.6 n BARS (109 PER GROUP) (27 GRPS REQD r. 1 GRP OF 56) SEE DET B (K-7) TEMPORARY OPENING DEVELOPED PLAN E U BAR Eo ANCHOR LOC (A-9, C-9) (EC-49P, F-2)( 11 034) 1/4" = 1'-0" FULL PENETRATION WELD BARS-a TO RING It (TYP) f CONTAINMENT STRUCTURE 4'-61.0. RING It 24" 'I. 2" TH (ASTM A588)
~-- NO 18 (TYP) a~~~~
It LINER DET B A (EV-IB)(22002) DETAIL- A TEMP DOME VENT (G-2) SCALE 1/2"=1'-0" FIGURE 3.8-11 RING AT APEX OF CONTAINMENT STRUCTURE DOME MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYS I S REPORT
5-1 ~'
.. 16 ..
3-8" CRANE WALL TOP OF CONC EL.l05 '7"
.......,I......~ REFERENCE
____++r~f-+--=L=INE; __
- .'f'.
~~: li. RAIL £. WHEELS KEY PLAN DOME MAINTENANCE TRUSS I PARKED POSITIO N FIGUR E 3.8-12 ELEVATION DOME MAIN TENA NCE TRUS S MILLS TONE NUCLE AR POWER STATI ON UNIT 3 FINAL SAFET Y ANALY SIS REPORT
70'- O"RAD. REF.
---II TY P TEST CONN DET MA(EV-IH,B-II)
(22008) EL.H27'-2 ~"
~"L1NE~
~~A=.~=,,=.~~~~ T EST MEMBER I AT KNUCKLE 4' r CONC. REBAR PLATE JOINT 6"RING I
----Ji 69'-11!i RAO'----l n I 70'- 2/i" RAO!REF.
SECTION 63-63 FIGURE 3.8-13 LINER KNUCKLE PLATE MI L L STONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
-fLiNER HIGH POINT OF CONC.
63.J L---FLOOR EL(-)24'-6" FI GURE 3.8-14 BASIC LINER DIMENSIONS MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYS I S REPORT
CONTAINM~ FUEL BUILDING STRUCTURE WALL TRANSFER TUBE WITH END PLATES [, BLIND FLANGE VALVE
'::.~p.~" .:
.,~:,
JOINT TUBE PLAN- FUEL TRANSFER PENETRATION
."'!.... 'c:I' RING AREA OF ANALYSIS(l}
(REF TABLE 3.B-2)
.. AREA OF ANALYSI S (2)
IREF. TABLE 3.B-2)
.'~ . . : :., LINER
. ,,~ ,': :=,-... :~ . .:. ,9. . .
TEST HOLES (PLUGGED) PIPE FLUED HEAD PENETRAITI~IO:.'N~-=~~~~~~~~ SLEEVE- INSU LATION HEAT EXCHANGER -;;;;i~~="lfl==~~F INNER UNIT EQUI-SPACED LUGS (ONE LUG , -'t'.
------ ---£ OF PIPE ON HORIZONTAL iLl L 4' 6" INNER UNIT TYPICAL COLD PIPE PENETRATION (UNSLEEVED)
TYPICAL HOT PIPE PENETRATION ( SLEEVED) FIGURE 3.8 -15 TYPICAL PIPING PENETRATIONS MILLSTONE NUCLEAR POWER STATION UN IT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 15 SEPTEMBER 1985
1
-4 1
2 I 2 I 8 COOLER RET URN .Jtz:z::z:::2:z:z::z:z:z::z::;~z::z:z:;;;;~~:z:z::z::;~~~~ TUBE
--~-ct INSULATION COOLER SUPPLY(SH9.WN OUT OF
"--~ 3SIDES '---~t--- POSITION) TUBE 1/2 'O.D x.095" J\.-- r LINER COOLER COOLER RETURN SUPPLY FIGURE 3.8-16 TYPICAL SLEEVED PIPING PENETRATION MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 15 SEPTEMBER 1985
74'-6" R AD RE:r: OUTSIDE: CONC 4"6" WAL.L. REr: HORIZONTAL 't (4) 3/4" PIPES t TEST HOLE TYP FIGURE 3.8 17 MULTIPLE PIPE PENETRATION ASSEMBLY MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 15 SEPTEMBER 1985
PLAN SINGLE RADIAL PENETRATION THRU LINER FIGURE 3.8-18 UNSLEEVED PIPING PENETRATION MILLSTONE NUCLEAR POWER STATION UNIT 3 FI NAL SAFETY ANALYSIS REPORT AMENDMENT 15 SEPTEMBER 1985
OUTSIDE INSIDE CONTAINMENT CONTAINMENT 74' "
-6 RAD REF OUTSIDE CONCRETE 3/8 1/2 HEADER ~r I
12" SCHED 80 SEAMLESS PIPE SLEEVE L 3x3x 3/16x 3"L I DET MC(EV-1M B-5) (22012) 7" REF 5'-11" PLAN r-~!""'"7--< 3 SIDES TYP FIGURE 3.8- 19
.... ELECTRICAL PENETRATION MILLSTONE NUCLEAR POWER STATION UNIT3 1 1 FINAL SAFETY ANALYSIS REPORT AMENDMENT 15 SEPTEMBER 1985
BELLOWS 6'-0"REF 4'-10~"REF
'l 2'- 0"
~~~~m~u~~ff
- ~ * .* .. A,lito
. ~ 4' 0' COMPRESSIBLE" .i MATERIAL ;:;. n ::~
21'-0" REF. SS STIFFENER PL. ...!..."x ,..!.." 3 REOUIRED 2 2 ELEVATION LOOKING EAST FIGURE 3.8-20 FUEL TRANSFER TUBE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 2 APRIL 1983
68' -9" RAO--l\,-----l:~f;: 15'-0" 1 - 4 11 PARTING ~ 2 LINE 3'-6" REF INSIDE CONTAINMENT HI NGE _ _'---*Iii+l1 o AUXILIARY BUILDING
--:'---il'-H+~- 0 -- --+---1
_I r-FLOOR El. 24'-6"---~ -:;- ,.. r---FLOOR EL.24'-6" FLOO R :~: -;. .. :i: ::":'" *.:
~?~:\ EL. 25'-3'; .-: r.:....
INSIDE CONTAINMENT - - - - LINER 142(H-5) TEMPORARY CONCRETE I ACCESS HOLES TO BE SEALED 142-142 LINER t VIEW PORT LH HINGED ACCESS BOTH DOORS LOCK COVER RH HINGED ACCESS LOCK COVER ct PERSONNEL ACCESS LOCK ESCAPE HATCH KEY PLAN DOORS ONE AT NTS EACH END
-l 142 FIGURE 3.8-21 PERSONNEL HATCH MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FILE: 3821.dgn/3821.cit
- NOVEMBER 1997
I Sll 18 - llji MIN. 70'- O"RAD TO It REACTOR ARC LENGTH /-
... AT 70"0" RAD ~
9"9!: ' I
- I" 09.
TYP) S"V 4 9 i
- 3" 65-B. RAD ToIL REACTOR ~ 1 11+---
MONORAIL SUPPORT LJ BRACKET (4 REQUIRED) r!,
- -f * """""---
MANUALLY OPERATED TROLLEY HOIST 12 REQUIRED) TEMPORARY CONCRETE ACCESS HOLES TO BE SEll LED BOLTED HATCH COVER UNBOLT FROM INSIDE I TO OPEN I
~ OF EQUIPMENT
'"MIN, 9
-. EL .5B'-Z" I ci HATCH EL 58'-_2'_'_.-+-_~ o, s
~ 'CD S I 0
.~ I"'b-0' r;;
t-+ ,, EL51'-4" HATCH COVER IN STORAGE POSITION DOUBLE GASKET - -~, ----. 1'-6" ESCAPE IIATCH (TO BE OPENED fROM EITHER SIDEI---"'.c-I-'--.J CONTAINMENT LINER (EV-IA) (22001) G< CONTAINMENT ~ 66'-0" RAD. STRUCTURE A
"+t-_.....::::-?V".--.::::--I-!- A-A (O-7)
B-B (C-5) FIGURE 3 ,8 -22 Ii. CONTAINMENT STRUCTURE EQUIPMENT HATCH MILLSTONE NUCLEAR POWER STATION KEY PLAN UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FILE: 3822.dgn /3822.clt NovEMBER 1997
TOP OF RING GIRDER EL.S'-IO" t*~~t~:
.~....: .
EXIST. ROCK EL. 9' - 0": ~. R: 14' -6" TYP. (CONTMT NO. II --+--+--1---1 J I . - - - - t - - - ST RUCT. E xr. WALL) I I - - - - r - - - - WATERPROOFING 1-+---++-++----+--- R = 79'-6"(ROCK EXCAV) m~~~ill~L_----,r----TOP OF MATEL.{-)27'- 3" 11-#4 I-I 4 CRUSHED STONE (EC -49X, E-5)( 11072) 2" SEAL COAT (above crushed stone) FIGURE 3.S-Z3 (I OF 2) CONTAINMENT STRUCTURE FOUNDATION DETAIL WITH RING GIRDER MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FILE: 38231.dgn/38231.ci"t NOVEMBER 1997
ADJACENT BUILDING
'~.'!'.: .
3-~.....~:.: '/~..'
~
- ~:
- :.'0.':
FACE OF ROCK EXCAVATION- .~:*.. ~.~.~: RING GIRDER ------~....;..:..-
.. ~:. ~O:.
;~:>:-:
WATERPROOFING MEMBRANE - - - + . . ,*.* -*-*-C)-+ --11 2" SEAL COAT ,. (above and below *0 :.'.. -. - - - + - - - - - - DETAIL A membrane) 4"- # 4 CRUSHED STONE CONCRETE B L C C K - - - - - + i CONTAINMENT STRUCTURE FOUNDATION MAT POROUS MAT ERIAL.-----l~;;;=;:;========~~;;;;=:==\ LEVELING CONCRETE FIGURE 3.8-23 (2 OF 2) CONTAINMENT STRUCTURE FOUNDATION DETAIL WITH RI NG GIRDER MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FILE: 38232.dgn/38232.ci t NOVEMBER 1~97
E 180" La C. OF ESF BLDG. WALLS & RADIAL WALLS SEE EC-23A (11213) TOP EL4'-0"
~ (EC-49Y,B-5) (11073) 00 360" W
PLAN fci) EL (-) 26~OI' SCALE : 1/ 3 2 = It _a" FIGURE 3.8-24 (IOF'3) DETAIL OF RING GIRDER AT ESF BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
~~
,:c...< " E SF BUIL DING I--~\ '
.~ ,
CONTMT STRUCT EXT WALL---J EL 4' -6" It I ~ ,-TOP OF RING GIRDER I I s
--. - EL 3-14"
~
RING GIRDER -t----tt_t__ CONTMT ST RUCT L TOP OF RADIAL WALL EL 1'- 0"
.....---Ht--+-*1 EXT W A L L -
'.~ :~'..' : <
4"COMPRESSIBLE-+----'~ I'-- * ' MATER IAL
';:;.>. v: --RA DIAL WALL I I
~~1----+--11 EXT RA HORIZ (4" L AYER) 4 " COMPRESSIBLE-+-------:.... I
-Y-3'-0" MATERIAL f----+~ 8 DOWELS 31+----1----'--'-
~ r EL r-: 12 '- 6 "
.-4-"+-+-11 EXT RA HORIZ (4" LAYER )
-.+f----+RIN G GIRDER 7 9'-d' R --+----+++--~I J---Ht---t-- 11 TARPAPER SLI P rL S U R ~A C E ( 2 LAYERS)
BOT OF RING GIRDER
' p' d '
,<. ~:. '.~
~ j
~_
~' . -- f-- EL H 26 '-3"
- .: .: ~ '
~~:--::--+---l
'.:'0:-- '0-0
~~~;.:~,::.::.: o 5 10 tTARPAP ER SLIP SURFACE (2 L AYERS)
I I I q. SCALE FEET 4-4 ': :'~,:,":; rESF BLDG MAT
' , ' '-;,.~. :-
3-3 6" WATERSTOP FROM TOP OF CONTMT STRUCT MAT TO TOP OF RING GIRDER RING GIRDER CONCRETE FILL PIECE OF 9 WATERSTOP ( FROM TOP OF CONTMT STRUCT MAT) (S PLI CE WATERPROOF MEMBRANE TO WATERSTOP) RIB BED FI BERGLASS WATERPROOF MEMBRANE FIGURE 3.8-24 (2 OF 3) CONTMT STRUCT DETAIL OF RING GIRDER AT ESF BUILDING DETAIL A MILLSTONE NUCLEAR POWER STATION o 1 2 3 4 5 UNIT 3 I I I I I I FINAL SAFETY ANALYSIS REPORT SCALE FEET A ME NDME NT 15 SEPTEMBER 1985
PROTECTION BOARD * :~:. ~ESF BLDG WALL TOP OF RING G~I~~O~~_ ....--.u---+_._.~~ .......:
<,I' ~ *. ~.
11 I 6 WATERSTOP (WIDTH OF RING GIRDER) PIECE OF 9" WATERSTOP FOR WATERPROOF MEMBRANE AT TOP OF SPLlCI~'~ I
,~:q 1-- WATERSTOP AT OUTSIDE RING GIRDER FACE OF CONTMT I STRUCT WALL (EC-749B) (1l516)
PIECE OF WATERSTOP INSIDE FACE O F - I RING GIRDER FOR SPLICING WATERPROOF I MEMBRANE I WATERSTOP IN TOP OF EXIST CONTMT STRUCT MAT (SEE NOTE EC-49Y, H-B) (11073) BOT OF BEAM EL(-) 26'-91~lt:~~'~:~'C':'I::l_-d~_~"~;":;~J:~ r TOP OF MAT EL(-) 27'-3" TARPAPER JT~ -':i\ LTARPAPER JT WATERPROOF MEMBRANE SPLlCE.D TO WATERSTOP-----J 5-5 (A-7) o 123 4 I I I I I SCALE FEET FIGURE 3.8- 24 (3 OF 3) DETAIL OF RING GIRDER AT ESF BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
~ WAl 1786.97 ~OO WAT 1500 12.00 900 ISO 600 300 0 0 300 600 900 150 170.37 12..00 1500 RAD IAL MOMENT SHEAR (K-FT/FT) [ K/F T )
300
~ MAT ~ WAl 10 20 30 40 SO 60 70 10 20 30 4-0 50 60 70
! I (
I RADIUS [ FT I I RADIUS CFT) t MAl 359.90 t MAT MAT/STRUCrURE INTERACTION 300 Z.2 I FT-K/fT) S ... 1209.7
~ ~~
150 ---.. 0.3 ( K/FT )
-0."
. - 152.2 1 190.S (K/FT) (10U1 IUFT ) rI111.0 KIF T 0
to-Z UJ 2 a:: to- Z 0 a: 150
..... 0 e,
uJ et U 'Z --l to-
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a:::
--l 2:
uJ ::J et 0 a:: (I) u
- u 300 TANGENTIAL MOMENT CK-FT/FT)
FIGURE 3. 8 - 25 CONTAINMENT STRUCTURE MAT LOADING MOMENT AND SHEAR DIAGRAMS MILLSTONE NUCLEAR POWER STATION DL+ 1. OP+l. OC T+TL) UNIT 3 FINAL S"AFETY ANALYSIS REPORT
t WAT 2151.80 300 WAT 2000 1500 ISO 1000 SOO 0 0 500 1000 ISO 1500 RADIAL ~O~ENT SHEAR 2000 IK-FT/FTl I K/F T1 300 t WAT t WAT 10 20 30 40 SO 60 70 10 20 30 40 SO 60 70 I I I I [ I I I I I RAD IUS 1FT 1 I RAD I US (F T) t WAT ....9.05 t WAT MAT/STRUCTURE INTERACTION 10.5 (FT-K/FT I 5.0 1~02 0 300
~~
~
I K/FT I 0.3 177 .2 150 1 0 1"'" (I(lF T I (I(lFT IOU I 1 ' ( K/FT I Z UJ 2 ex: 150 0 I I-ex: 0 UJ
-Z0<
U ~ Z -' I 0< e, 0< -' Z UJ ::t a:: 0< 0 a:: CI) u
- u 300 TANGENTIAL MOMENT IK-FT/FTl FIGURE 3.8-26 CONTAINMENT STRUCTURE MAT MOMENT AND SHEAR DIAGRAMS LOADING MILLSTONE NUCLEAR POWER STATION DL+l.25P+l.01 T+TL 1 UNIT 3 FINAL SAFETY ANALYSIS REPORT
MAT 2S0~.61 .500 t MAT 150 1000 sao o sao 1000 150 1500 2000 RADIAL MOMENT SHEAR (K-FT/FTl ( K/F T l 2500 .500
~ MAT ~ MAT 10 20 30 40 50 60 70 10 20 30 40 50 60 70 RADIUS (FTl I RADIUSIFTl
~ MAT 537.05 MAT MAT/STRUCTURE i
~
INTERACTION ~50 23.6 IFT-IUFT) ~.S 1587.0
~~
~OO 2.9
...- I KIF TI
-l 0.3 20 1. 2
~
150 190 . 5 I K/FT I KIF T I>DU I I KIP l I-z uJ
- IE 150 Z uJ ~
Z ....J I
~ ....J Z a:: ~ 0
}OO L> ~ L> 450 TANGENTIAL MOMENT 1i<-FT/FTl FIGURE 3.8- 27 CONTAINMENT STRUCTURE MAT LOADING MOMENT AND SHEAR DIAGRAMS DL+l.5P+l.O( T+TL l MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
t NAT 14511.114 &00 NAT 1200 1100 150 600 500 0 0 500 600 150 900 1200 RADIAL MOMENT SHEAR IK-FT/FT) I K/F T) 500 t NAT t NAT 20 30 40 50, 60 70 10 20 30 40 50 60 70 10 , , I I , I I I I I I I I I I RAD I US 1FT) RAD IUS 1FT l t NAT 2115.82 t NAT MAT/STRUCTURE INTERACTION 6.11 IFT-K/FTI J.S lI33. a ISO
~ ~~
0.8
.. I KIF T I O. I 117.6 1,0*.' I.Uj a
IIt1FT I I kIF 1 I
....z r""
I Kif 1 I.IJ
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I.IJ Z ...J ....Z<
< e; < -l I SO =
I.IJ II: 0 II: en U U TANGENTIAL MOMENT IK-FT/FTl FIGURE 3.8- 28 CONTAINMENT STRUCTURE MAT LOADING MOMENT AND SHEAR DIAGRAMS DL +1.15P MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
i WAT 500 WAT 750 600 450 ISO 500 ISO 0 o I SO 300 ISO 4S0 600 RADIAL MOMENT SHEAR 7S0 (K-FT/FTI ( K/F TI 786.59 500 { WAT 20 30 40 50 60 70 10 20 30 40 50 60 70 I I I RADIUS IFTI I ~ADIUS (FTI { WAT MAT/STRUCTURE INTERACTION 450 94.9 5.0 IFTK/FTl 1.3 500 ~ ~\ I k/FT 1 11,0 4-- 1 SO !90.S 20 1 . 0 I KIFT I 104.51 (ICIFT I I KIF T o 1 1 t
'Z W
2 ISO IX: t- 'Z 0 IX: w
~I t- O u a- 'Z
.... a- .... ...J IX:
...J W ::::l 500 IX: CI) U 450 TANGENTIAL MOMENT
[K-FT/FT I FIGURE 3.8-29 CONTAINMENT STRUCTURE MAT LOADING MOMENT AND SHEAR DIAGRAMS MILLSTONE NUCLEAR POWER STATION OPERATING VACUUM UNIT 3 FINAL SAFETY ANALYSIS REPORT
150 ~ ..... T ISO "AT 100 50 o o 50 100 RADIAL MOMENT 150 IK-FT/FTI 153.40 "AT 10 20 30 40 50 60 70 I I , I I I I RADIUS 1FT)
~ "AT 50 18.5 (9.5 16.2 17.0 14.8 II(/S'I FT j II. I 0
....2 Z
a:: ... z
... ...oe-c a::
to) C Q.. Z ...J oe -e Z
.... Q..
~
...J a:: oe c 50 a:: III to)
- to)
TANGENTIAL MOMENT IK-FT/FTI 75.90 FIGURE 3. 8 - 30 CONTAINMENT STRUCTURE MAT LOADING MOMENT AND SHEAR DIAGRAMS MILLSTONE NUCLEAR POWER STATION 1.25(!SSE) UNIT 3 FINAL SAFETY ANALYSIS REPORT .
{ MAT ISO MAT 100 ISO 50 o o 50 150 100 RADIAL MOMENT (K-FT1FT) 44.20 { MAT I I,' 20 I 30 40 l SO 60 70 I RADIUS (FT) { MAT 100 31.6 33 .3
~
50 23.6 I k/SQ FT I 25.6 .... 26 a la.,/ o **
, ~ ~
t-Z uJ 2 50 CIl: 10 t U t CIl: 10 0.. uJ Z ...J Z t
< 0.. < ...J Z uJ ::) CIl: 10 CIl: en u u 100 TANGENTIAL MOMENT (K-FT/FT) 121.10 FIGURE 3.8 31 CONTAINMENT STRUCTURE MAT LOADING MOMENT AND SHEAR DIAGRAMS MILLSTONE NUCLEAR POWER STATION 1.00 (SSE)
UNIT 3 FINAL SAFETY ANALYSIS REPORT
t CONTAINMENT WERIDIONAL FORCE RADIAL "OWENT
--4-~ WE"BRANE SHEAR HOOP MOMENT FIGURE 3.8- 32 LOAD PLOT NOMENCLATURE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
210 200 190 180 170 160 150 140 DailE
~ 130 L!
en, HDER 120
~ I 10 <t: ~ 100 w 90 0 80 OJ
-c 70 w 60 u z: 50 -c ~ 40 U) 30 0 491 20 10 0 I
-1800 ~lZDD I
-600
,0.0 ~oo RADIAL MOMENT (KIP-FT/FTI FIGURE 3.8-33 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL+l.5P+I.0( T+TL I MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
210 200 190 180 170 160 150 140 DaME r- 130 u, en (HOEK 120 r- 110 -c ~ 100 ILl 90 D 80 co << 70 ILl 60 u z 50 r- 40 C/) 30 0 20 10 0 I I 1- ---1
-300 -200 100 '0.0 100 RADIAL SHEAR
( KIP IF T ) FIGURE 3.8-34 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL+l.5P+1.01 T+TL I MILLSTONE NUCLE AR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
210 200 190 180 170 160 150 140 DOllE t- 130 242 u; CYLINDER 120 t- 110
- 2 100 w 90 0 80 en
-c 70 w 60 u z 50 t 40 c.I) 30 a 20 I0 0 287 I
-0400 b.o ~oo
~ERIDIONAL FORCE I KIP/FT I FIGURE 3.8-35 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL+I.5P+I.OI T+TL I MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
210 200 190 180 170 160 150 140 DOllE J-- 130 677 u; CYLINDER 120 J-- 110
- 2: 100 w 90 0 80 CD
-c 70 w 60 u z 50 -c J- 40 (/) 30 0 20 10 0 113 I I
-1000 0.0 '1000 HOOP FORCE
( KIP IF T ) FIGURE 3.8-36 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL+I. 5P+I. QC T+TL I MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYS I S REPORT
210 _ 200 190 180 170 160 _ 150 140 t- 130 _ DOME CYLINDER u, 120
.- 110 <C
- iE 100 w 90 0 80 CO
<C 70 uJ 60 u
z 50
<C co 40 30 Q
20 10 0
~1I00 ~1200 ~eoo b.o ~oo RADIAL UOMENT (KIP-FT/FT)
FIGURE 3.8-37 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS I DL+l.25P+l.0( T+TL )+1.25(2SSE) MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYS IS REPORT
210 200 190 180 170 160 150 I LL 140 130 DOME CYL INDER 120 l I 10
<C
- E 100 w 90 0 80 CD
<C 70 w 60 u
z 50
<C I
C/) 40 30 0 20 10 0
--~
I
-zoo ~IOO ~.o '100 200 RADIAL SHEAR I KIP IF T i FIGURE 3.8-38 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL+l.25P+I.OI T+TL )+1.25(tSSE) MILLS1DNE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
210 200 190 180 170 160 150 140 DaME t- 130 u.. CYLINDER 120 l- t 10
<C
- E 100 w 90 0 80 en
<C 70 w 60 u
z 50
<C t-U) 40 30 0
20 10 0 I I
-600 b.o 600 HOOP FORCE (KIP/FTJ FIGURE 3.8-39 LOADING CONTAINMENT STRUCTURE WALL DL + 1* 25P+ 1* 0( T+ TL ) + I
- 25 (t 5S E) AND DOME FORCE RESULTANTS MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYS IS REPORT
210 200 190 180 _ 170 160 ISO 1'10 nME
~ 130 LL en INDER 120 I- 110 _ ~ 100 UJ 90 0 80 en << 70 UJ 60 u
z 50
~
U)
'10 30 0
20 10 0
~oo I
-200 b.o MERIDIONAL FORCE IKIP/FT)
FIGURE 3.8-40 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL+l.25P+I.OC T+TL )+1.25(!SSE) MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
210 200 190 180 170 160 150 140 DailE I-- 130 u, CYLINDER 120 I-- 110
- iE 100 UJ 90 0 80 co
<< 70 UJ 60 u
- z 50 I- 40 U)
£::)
30 20 10 0 I
-40 b.o ~o MEMBRANE SHEAR FORCE lKIP/FT)
FIGURE 3.8-41 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL+I.25P+I.O( T+TL )+1.25 (iSSE) MI LLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
210 200 190 180 170 160 ISO 140
.- 130 DOME CYLINDER LL 120 .- 110
- E 100 w 90 0 80 co
<< 70 w 60 u
- z 50 Cf) 40 30 0
20 10 0
~oo I I
~ISOO ~IOOO -500 0.0 RADIAL MOMENT (KIP-FT/FT J FIGURE 3.8-42 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS oL + I
- 0P + I
- 0( T +TL ) + 1* 0 (SSE) MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
210 200 190 180 170 160 150 140 DOME I- 130 u, en I NDER 120 l 110
-c
- E 100 w 90 0 80 en
-c 70 UJ 60 u
z 50 I 40 U) 30 a 20 10 0 I ---I
~200 ~IOO 0.0 1100 200 RADIAL SHEAR IKIP/FTI FIGURE 3.8-43 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL+I.OP+I.OI T+TL }+I.O (SSE) MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYS IS REPORT
210 200
]90
]80 170
]60 150 140 DOME l- 130 LL CYLINDER 120
.- 110
-c
~ 100 UJ 90 to 80 CO
-c 70 UJ 60 u
z 50
-c I- 40 U) 30 0
20 10 0 I I I
-400 0.0 ..00 HOOP FORCE (KIP/FT)
FIGURE 3.8- 44 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL+l.0P+l.0( T+TL )+1.0 (SSE) MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
210 200 190 180 170 160 150 140 DOME
~ 130 u, CYLINDER 120 ~ 110 -c ~ 100 w 90 0 80 co -c 70 w 60 u
z 50
<t: ~ 40
(/) 30 c::a 20 10 0
~oo I
!..zoo 0.0 MERIDIONAL FORCE IKIP/FTI FIGURE 3.8-45 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL+I.OP+I.O( T+TL )+1.0 (SSE) MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
210 200 190 180 170 160 150 f-1.L 140 130 DOME CYLI NDER 120
~ 11O ~ 100 UJ 90 0 80 co << 70 w 60 u
z 50 t-(f) 40 30 0 20 10 0 I I I
-100 0.0 100 MEMBRANE SHEAR FORCE (KIP/FTl FIGURE 3.8 - 46 LOADING CONTAINMENT STRUCTURE WALL DL+l.0P+l.0( T+TL )+1.0 (SSE) AND DOME FORCE RESULTANTS MIL LSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
210 200 190 180 170 160 150 I-u.. 140 130 DIME CYLINDER 120 I 110 <C
- !: 100 uJ 90 0 80 CD
<C 70 uJ 60 u
- z 50
<C I U) 40 30 0 20 10 0
~1000 ~500 to koo '1000 RADIAL MOMENT (KIP-FT/FT)
FIGURE 3.8-47 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL .. I. 15P MI LLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
210 200 190 180 170 160 150 140 I- 130 DhE CYLlNDEI U-120 l- I 10 <C ~ 100 UJ 90 0 80 CO <C 70 uJ 60 u z 50 <C t- ~o (/) 30 0 20 10 0
~l50 ~lOO ~50 ~.o ~o RADIAL SHEAR
( K t PIF T ) FIGURE 3.8-48 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS nL +1* 15P MILLSTONE NUCLEAR POWER STATION UNIT3 FINAL SAFETY ANALYSIS REPORT
210 200 190 180 110 160 150 140 t- 130 DhE en INDEIt u.. 120 t- I 10 <C ~ 100 uJ 90 0 to co <C 10 uJ 60 CJ
- z 50
<C t- 40 en 30 Q 20 10 0
~200 ~.o ~oo
..ERIDIONAL FORCE
( KIP 1FT) FIGURE 3.8-49 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS Dl + t
- t 5P MI LLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
210 200 190 180 170 160 150 140 f- 130 DhE CYLINDER U. 120 l- I 10
- E 100 uJ 90 0 80 co
-c 70 uJ 60 u
- z SO f-CJ) 40 30 0
20 10 0
~ ..oo b.o ~oo HOOP FORCE
( KIP IF T ) FIGURE 3.8-50 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL +1.15P MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
210 200 190 180 170 160 150 140 DIME l- 130 I LL CYLI NDER 120 l- II 0 -c ~ 100 w 90 c 80 co -c 70 UJ 60 u z: 50 -c I-en 40 0 30 20 10 0 1 b.o 100 RADIAL YOMENT (KIP-FT/FT) FIGURE 3.8-51 LOADING CONTAINMENT STRUCTURE WALL DL+OPERATING VACUUM AND DOME FORCE RESULTANTS MILLSTONE NUCLEAR POWER STATION UNIT3 FINAL SAFETY ANALYSIS REPORT
210 200 190 180 170 160 150 140 DOME l- 130 u, CYLINDER 120 f- 110
-c ~ 100 w 90 0 80 co -c 70 w 60 u
z 50
-c f- 40 en 30 0
20 10 0
~5 b.o k '10 RADIAL SHEAR (KIP/FT)
FIGURE 3.8-52 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL+OPERATING VACUUM MILLSTONE NUCLEAR POWER STATION UNIT3 FINAL SAFETY ANALYSIS REPORT
210 200 190 180 170 160 150 I-u, 140 130 DaME en INDER 120 l- II 0
-c
- E 100 UJ 90 10 80 en
-c 70 UJ 60 u
z 50
-c I 40 U) 30 0
20 10 0
~zoo ~IOO ~.o MERIDIONAL FORCE (KIP/FT)
FIGURE 3.8- 53 CONTAINMENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL+OPERATING VACUUM MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
210 200 190 180 170 160 150 1~0 lIME l- 130 LL CYLINIER 120 l- 110
-c ~ 100 UJ 90 0 80 en -c 70 UJ 60 u
- z 50
-c I ~O U) 30 0
20 10 0 I
-100 boo 'Joo HOOP FORCE
( KIP IF T) FIGURE 3.8-54 CONTAIN MENT STRUCTURE WALL LOADING AND DOME FORCE RESULTANTS DL+OPERATING VACUUM MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
WIND D..ECl ION 155.0 408.0 HOOP MOMENT l KIP-FT/FT) II.e 55.2 SV.... ETRICAL A80UT DIAMETER HOOP FORCE lKIP/FT) PLAN OF CONTAINMENT CYLINDER FIGURE 3.8-55 CONTAINMENT STRUCTURE LOADING, TORMADO IINDS WALL AND DOME MILLSTONE NUCLEAR POWER STATION VELOCITV
- 5&0 MPH UNIT 3 EQUIVALENT TO l6AD Of 0.55 l/SQ. fT.
FI NAL SAFETY ANALYS IS REPORT LOAD DISTRleUTION 8ASED OM ASC( rAPER MO. 5219
NORTH END OF N-S tCONTMT. STRUCT, 21 3/8" (TYP.) nllt1rt!rH-ANd-UfL- 4' -0" RADIUS
--->-----, \-H--++-++-++-j-If-+++-++-++-++-'H-++-++--+/-:+"9-t+tt-++-++-++-+'f-t+t-+t-++-H-+t~
(T Y P. )
~~~~lnB&iJSE-~fMAT LRADIAL BARS 171/4" 13" 2'-61/4 "
SCALE = 3/8" = 1'-0" FIGURE 3.8-56 DETAILS OF WALL DIAGONALS AT CONTAINMENT MAT MILLSTONE NUCLEAR POWER STATIO~ UNIT 3 FINAL SAFfTY ANALYSIS RF_PORT
MNPS-3 FSAR E I 23 (H-II) CONTMT. RECIRC. CONTMT. -+_-.... PUMP PIT EY-3C (11004)
-t
-t eo eo N---;Ht----------If-----:::!:=,....4;".....--I-~___t~-------__lH_--
N---;Ht----------If-----:::!:=,....4;".....--I-~___t~-------__lH_-- s CONTMT. It: STRUCTURE STRUCTURE 6" ~ PERFORATED DRAIN PIPE (SEE NOTE 5) CONC. SEALER W PLAN EL (-)37:'6" SHOWING LAYOUT OF DRAINAGE SCALE 1/32": I' (MEMBRANE SANDWICHED BETWEEN TWO (2) 2" LAYERS BETWEEN OF COMPRESSIBLE MATERIALl RIBBED FIBERGLASS CONTMT. STRUCT. STRUCT. WALL 4" COMPRESS MAT. MAT. WATERPROOF __~~, MEMBRANE PROTECTION BOARD PROTECTION FIGURE 3.8-57 (SHEET 1 OF 2)(PART 1 OF 2) DETAILS OF WATERPROOF MEMBRANE 26-26 (H-2) NOVEMBER 1997
MNPS-3 FSAR
~ CONTMt CONTMT. STRUCT.
£ CONTMT RECIRC PUMP RIBBED FIBERGLASS 79'-0" 2'-6" ENG. SAF. FEAT. BLDG.
PROTECTION BOARD EC-32 SERIES (11213)
- ~!!
4" '4
#4 CRUSHED STONE 4"COMPRESSIBLE MATERIAL -SEE - SEE NOTE 10 10 n_ r EU-)34'-9"
...---L,-.Jl1 Ift..-:-'"--t-'-------, _ _..L. __
~;
~~ (2)*2" (2) *2" LAYERS LAVERS SANDWICH MEMBRANE
~~t:
2" GROUT 9" POROUS CONC. 26[
- 26. ~.
~ .26 t26(K-2) (K-2)
EL (-) 3 7 '- 6 " rrEL(-)37~6" j~~§§~~~~MAT EL.{-)27'-3" j~~§§~~E1J~ ff
- .*2" 2 GROUT
,"; DRAIN DRAIN HOLES THRU THRU BLOCKBLOCK IN LINE LINE WITH HOLES L 74'-6"R v"-- 1l~~=~===~Ff:.
1I~~=~===4r=f:.rr EU-)39'-3" EU -)39'-3" IN VERTICAL ~LOCK.
~LOCK.
4"CONC.HOLLOW BLOCKS SHALL BE LAYED IN IN A FASHION TO . 10" CONC. ro" POROUS CONC. PERMIT DRAINAGE ALONG ALONG WATERPROOF MEMBRANE MEMBRANE PERFORATED PERFORATED DRAIN PIPE ALL BLOCKS SHALL SHALL HAVE HAVE SMOOTH SURFACE WITH NO NO PROJECTIONS IN IN CONTACT WITH MEMBRANE MEMBRANE AND SHALL 11114t-- I"AGGREGATE CONC. 1I1~+--- I"AGGREGATE CONC.SEALER-~I~ CONC.SEALER--~I~ HAVE MORTARED JOINT STRUCK SMOOTH. f~ ;.~ STUDS STUDS ~ 2'- Oil 0" HORIZONTAL HORIZONTAL LAYERS LAYERS OF BLOCK BLOCK SHALL BE BE LAVED LAYED RADIALLY, KEEPING HOLES HOLES IN LINE. EA WAY. WAY, WELD TO TO 1114-+--34" 1114--+---34" 1.0. CONTMT. RECIRC. PUMP PUMP PIT LINER PIT LINER (f THICK STEEL It..) Il.) POROUS CONC. t9-i--PUMP
~i---PUMP CASING CASING r2" GROUT PROVIDE 1"; DRAIN HOLES THRU CONC. BLOCK IN POROUS CONC. LEVELING POUR POUR EA CORE CORE FOR FOR THE THE PASSAGE f THICK 2. WELD TO PIT LINER OF WATER INTO POROUS CONC.
BOT. CONTMT. CONTMT. RECIRC. PUMPPUMP
~~=l4=-::::1w:========j::=r:::::!!===9F=====';~:~%L(-)37'-6" z .~ N . j'~~~::;::::~~n== CASING j';;~*:;:=*i~M= EL.H49'-0" EL.(-)49'-0" u:'T---..=.,.--,J---- .. - t - . - , . . - -..........:.;* 4 U - l 39'- 3" E 5 0'_0 E L. (-) 5 L,H _-'_\-"--_r'-1-'r-~--'rf--if,J
'-\-"----r'-t-'y-~__,mlY 79'-6"R* .
14 FINISH SMOOTH TO
.p*.
- v* .
SEAL SURFACE
*.9.
~*.Y. 24 -24 (0-2)
TO TO MAT MAT El.(-)27'*3" EL(-)27'-3" 21-21 (B-3 e.f.. E-3) SCALE 1/4 ":"= I'I' SCALE 1/4" I' 1/4 ":= I' ENG ENG.. SAFETY FEATURES FEATURES '
~
.....---,/L--l-BLDG.
t-------,/L--l-BLDG. EC-32 SERIES SERIES ~~: ( 11213) (11213) EMBRANE 2" GROUT EL C6" 6 1----+_-,;;_,:...,-137'
;;37 -G" F-3 fa F-3 9" POROUS CONC.. - i - , ;~:...
~. ,. LELH34' -_- -If--9_"-+_EL.:;.,.,.,.:.. ir~~~~~ ;~tr~~CTlO:~~~
;~$.~mCTlO:~;..J;~':=.5~~1:'T
- ~:. 9" POROUS POROUS CONC.
- ; : ;~'f~:nt~:-__:._jE_=LJ~~:~;;E
~C;~!l;~ ~'-:~9: :
CONC. SEALER FINISH SMOOTH TO I-fl>::--- 1-t1"-~-4"CONC 4" CONC.. HOLLOW BLOCK SEAL SURFACE(TYP)-T---rT1 I-=:W~====,==-===--i =~:"':"""'-'=""":::Yi7:7-+-~I"'-- SEE
=:...!.::~'="";:"Yii-:::-+--'74I"'-- SEE NOTE (a fa F-4 2"
2" GROUT El.H39'-3" EL.H39'-3" MEMBRANE ~f----- POROUS
- ..........t.---- CONC.
10" 10" POROUS CONC. LEVELING SLAB EL.{-)4,'-3" EL.{-)4I '-3" J - - - - - - SEE NOTE Ia F-4 2" GROUT MEMBRANE EL.(-)43'-0" EL .H43'-0" FIGURE 3.8-57 (SHEET 1 OF 2)(PART 2 OF 2) 10" 10" POROUS CONC. CONC . (M ( MIN.) IN.) DETAILS OF WATERPROOF MEMBRANE 2" GROUT 22-22 2 2- 2 2 (D-I) (0-1) SCALE SC A L E 1/4": 1/4 " = I' I' POUR 2
- POUR INSTALLED INSTALL ED AFTER AF T ER POURPOUR I NOVEMBER 1997
ENG. ENG. SAFETY FEATURES FEATURES BLDG. £C-32 SERIES (11213)) (11213 MEMBRANE MEMBRANE g" POROUS 9" POROUS CONC. CONC . FINISH SMOOTHSMOOTH Z'(3/4"AGGRffiATE CONe.} 2'(3/4"AGGRffiATE CONC.) TO TO SEAL SURFACESURfACE CONC. CONC. SEALER
~ :\
.~.:",P E l. (-) 34' - gil - '-:\"7'
.:~c-: H-1-----1---~..,..+_:;-7-:-------=.l..:J-.--J-..-r::-~ SEE NOTE@F-3 NOTE(c} F - 3
.... :' ";'.:.~.~/.~:'
- i~ '.f. .
- ~ .
CRUSHED STONE EL.(-)3i EL.(-)3i-6" - 6" - NOTE"{Y F -4 SEE NOTE"{YF-4 SEE EL.(-)3S' -6" - EL.(-)3S'-6" -~*.....- . *- -
.~,.
.~,
-_. -. .- ._-----------~
- - - - - -...---.~
EL. EL. (- {- )39' - 3"3 II -- ~
~.~::"'.,
. .~'.-.,..--~_,'_,....-_-_-~__r~_---.:~;;;...;,,:-..J
-----r--~_,'_,.--_-_-~__r~---:~~~
10" POROUS POROUS CONC. CONC . 2- GROUT 2-LEVEliNG POOR POOR 23-23(0-1) SCALE - 1/4" SCALE-1/4"=I' =,' SEE NOTE a A SEE A g --"",", 2" 2" 9" pOROUS CONC. 9"POROUS CONC . PIT LINER SPACE R 2 x 2 x 3/4 SPACE MEMBRANE MEMBRANE PUMP PUMP CASING CASING BOLT BOLT --~
--~
2" 25(B -9) 25(B-9) B.F.GOOORICH (THICK R-3S PROVIDE HOLE HOLE TANNATURAL TAN NATURAL FOR FOR BOLT 7 RUBBER OR EQUAL EQUAL.. OR
,rO 21/4"x2" 2 J/ 4" x 2 "
~
3" 1-'::, WI DE TI WIDE TIEE BANDS BANOS 25-25 (0-10) (D -IO) SHOWING TYP TIE DET "A" BAND BAND CONN TlON flON
" A" tC-7) lC -7)
- I I/Z" =I' SCALE -II/l SCALE SCAL - I 1/2"="
E -I 1/2"=,' 6- a
~ PERFORt.TED PERFORt.TED CONC PIPE PIPE BROKEN BEYOND POROUS LAYER CAULK CAULK ALL AROUND AROUND t>IPE INTERIOR rIPE INTERIOR SEAlED SEALED WITH SS 55 LINER GROUT, 8- MIN-12 ftft MAX GROUT.
(TYPICAL 6 PLACES) CUT SSSS LINER APPROX APPROX -1/2" ~ LARGER TO e 1/2" '" TO FIT a" NOMINAL ~
~~ROUS -Tj 9" 8" NOMINAL'" STL . PIPE STL. PIPE ANDAND LINER OPENINGS CLOSED CLOSED POROUS BY SEAL W WELDED ELDED PLATE (TYPICAL 6 PLACES)25212-59108 SH SH 37
~.:R~:T ~t*~:.*;:.~~.:-.~-::..~-~..;."j~~t:J~~~~~
LAYER n 2-GROUT OFCONC .EL .(-)3S'-9" TOP OFCONC.EL.(-)3S'-9
~..:. lu.~"""'"""I...e-POROUS POROUS CONC CO NC --~ - - ...Jo...-
MEMBRANE----~----II M EMBRANE ----~-- CONC . HOllOW 4" CONC. HOLLOW BLOCK DET 11 8 11 811" (H -7 ) (H -7) FIGURE F IGU RE 3.8-57 3.8 -57 (20F2) SHOWING CONNECTION CONNECTION DETS OETS OF OF 6*0 6-0 DETAILS OF WATERPROOF MEMBRANE ME MBRANE POROUS DRAIN PIPE TO SS LINER LINER MILLSTONE NUCLEAR POWER STATION SCALE: ~n =
~"= 1'-0-1'-0*
UNIT 3 FINAL SAFETY ANALYSIS REPORT REPOR T FILE: 38572.dgn/38572.cit CAD FILE: 38 5 72. d gn /3 8 5 72.c i t March 20 200101 (00-42) (00 -42)
MNPS-3 FSAR
<-OGG, .914 6 ) (0 .0, .9383)
(.1323,.8951) ---, {.I951 , .8702) (. 2437,.8287) 1
----Io.._-EL. 175.25 El.174.5' EL.171.85' 1
EL.167.,6S EL.162.25 1 EL.155 .1S El.115.5' EL. 11 0.35' 1 El.104.0 SPRING LINE E L. 104 .25'1 EL.I03 .75' (.612,.4571 ) (.6464,.4121) (.6781.3577 ) (.6457, .3059) NOTES: PRESSURE TEST 1.00L 't 1.15P (.678,.2444) (p: 45 psi) (.6903,.2014) DISPLACEMENTS ARE IN INCHES (RADIAL ,VERTICAL) (.6999,.1621) (.7153,.135) (.7309,.1094) ( .6729,.0807) (0.0,0.0) EL:-27.25' (TOP OF MAT) FIGURE 3.8-58 (1 OF 2) DISPLACEMENT PROFILE FOR CONTAINMENT SHELL UNDER PRESSURE TEST (PREDICTED) NOVEMBER 1997
z 0 RADIAL TANG. ~ DISPL. DISPL. u 0 -IN. -IN . -J NOTES: 1 0.638 -
- 1. TANGENTIAL DISPLACEMENTS ARE HORIZONTAL, 2 0.633 - IN THE PLANE OF THE PAPER, POSITIVE TO THE RIGHT.
- 2. RADIAL DISPLACEMENTS ARE HORIZONTAL, 3 0.624 - NORMAL TO THE PLANE OF THE PAPER, POSITIVE INTO THE PAPER.
4 0.659 0.044
- 3. DISPLACEMENTS AT 6 AND 9 O'CLOCK ARE SYMMETRICAL TO THOSE GIVEN AT 12 AND 3 5 0.644 -0.0013 O'CLOCK RESPECTIVELY.
6 0.660 0.011 4. PRESSURE TEST 1.0DL+ 1.15P (P=45psi) 2t---=:------..3Ior------------- 11 EL. 58'-2 6 I: .175R'1:'+1/2,~-J 2.5R'18*-9*=----J 1 ELEVATION EQUIPMENT HATCH FIGURE 3.8-58 (2 OF 2) DISPLACEMENT PROFILE FOR CONTAINMENT SHELL UNDER PRESSURE TEST (PREDICTED) MI LLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 15 SEPTEMBER 1985
*- - *- - *- - -*-*- --- - - - - - --1 15-7 I
ST. GENERATOR i REACTOR (TYP.) REACTOR TIME DELAY DUCT FIG. 3.8-60 3RMS.,.RE41 REACTOR VESSEL HEAD STORAGE RING ( BELOW) 32° REMOVABLE
~CHECKERED PLATE 1 __,_.....- REACTOR VESSEL HEAD STORAGE RING (BELOW)
_ji 3Rt.4S*RED4A 1 l ELEVATION 56 -10 11 FIG. 3.8-60 PLAN EL. 51'-4" PLAN EL.3'-8" I iREACTOR I CONTAINMENT STRUCTURE SUMP PUMPS
,,,-REACTOR VESSEL HEAD
/ STOHAGE F\ING(BELOW)
CONSTRUCTiON OPENING _j1 CONTAINMENT DRAIN TRANSFER TANK
----~~UPPER INTERNALS STORAGE STAND PRESSURIZER
~----? RESSURlZER RELIEF TANK DRAIN PUMPS CONC.SUPPORT FIGURE 3.8-59 lTYPJ CONTAINMENT STRUCTURE, CON TAINME NT PLAN VIEWS INST. AIR COMPRESSOR EQUIPMENT MILLSTONE NUCLEAR POWER ST AT ION FIG. 3.8-60 UNIT 3 FIG. 3.8-60 FINAL SAFETY ANALYSIS REPORT 1 11 1 11 PLAN EL. 24 -6 PLAN EL. (-) 24 -6 REV. 28.1
/ CONTA INMENT ST RUCTURE ENCLOSURE r-11. REACTOR AUXILIAR Y HOOK POLAR CRANE CONTAI NM EN T ST RUC TURE LINER CONTAINMENT LIN ER (T YP,) (TYP,) - -
EL 9 5 ' 4 " CONTAINMENT ST RUCTURE WAl L I..OW£~ INTERNALS STORAGE 1 5'- O~ I D STANO NEUTRON EQUIPMENT SHIEL D TANK HATCH e.s: SURGE TANK-ISOLATION WATER LEvEl: BYPASS DURING REFUELING LINE &VALV,E.--......... lNCQRE £ 1...51 '- 4 " INST M. FUEL ASSEI.IBLY- --.. DRM"A SSY. GIJI(l: TUBE RC~I~,.'jING UPPER INTERNALS STORAGE SURGE LINE FUEL lPENOER FUEL TRANSFER =I!"'" /H=~;H--"E",,- L. 2. 4 '-6 " TUBE- - PRESSURIZER HEATER REMOVA L S PA C.E:
. \'l:\fK<><ro&,D;~
'ffNHNS~ T- +-JH--ti Jl EACTOR VESSEL HEAD , ACCESSHATCH TO ~-J.jj-t-PR£SSUR l lE R STORAGE. RING I ~ C O RE INSTR. ROO RELIEF TANK H. P E l ~24" 6" CONTA IN M EN T STRU Ct U RE LI NER - -
(TY P,) CONTA I NM EN T STRUCTUR E LI NE R (T YP,) 2 " T HI<. /' LE A D SHIEL D - - ' CONTA INMENT AI R 2" T HK RECIRCULA T ION COOL ING COIL ASSY. LEAD SHIEL D J- I 2- 2 , 3 -3 CONTA INMENT AIR RECIRC. FAN ( TY P ) FIGURE 3.8 -60 CONTAINMENT STRUCTURE, ELEVATION VIEWS MILL STONE NUCLEAR POWER STATION UNIT 3 FINAL SAF ET Y ANAL YSIS REPORT AMENDMENT 3 AUGUST 19 6 3
L GRO.GR.EL 24'-O*J CONTAINMENT STRUCTURE "- COL T/PARAPET
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ycJ/ BEND LINE EL9 6 '-~ " ELI 04' - 0 " 4:'1 9/16" GL
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ST RUCT URE 4 - CA NT STRIP
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l'o/I£>" r----1------~===::t:------+_--____1 SECT. 4-4 E: 10-~O ROADWAY SERVICE BLDG. ". ..... >. TURBINE BLDG. SECT, 1-1
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w P'_L!.:....-_-=!~-+~+_..'!t.!'L_--d=-J...J'i. INSERT It DIET. 0 G.LtCOL. Ll INE E-Z FL - -<i,"",,= _ _
~~ °lao~~' EL 5e'-0* DET. I REMO V.o.RL E <:;' 1.IlR EL.25'-6 "
," ,r> '0 - BOT OF SI DING EL .25'-O" -- Elo 57 '-6"
*..!. GRD.GREL.24 1. 0" DET.H
'-M ET FL SECT. 3-3 FIGURE 3 .8 - 61 CONTAINMENT ENCLOSURE BUILDING DET. C COLUMN DEl MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
SECURITY-RELATED-INFORMATION-Withhold under 10 CFR 2.390 FIGURE 3.8-62 (I OF 10) AUXILIARY BUILDING MILLSTONE NUCLEAR POWER STATION B UNIT 3 Fl NAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(l) REV. 28.1
SECURITY-RELATED-INFORMATION-Withhold under 10 CFR 2.390 FIGURE 3.8-62 (SHEET 2 OF 10) AUXILIARY BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(l) REV. 28.1
SECURITY-RELATED-IN FORMATION-Withhold under 10 CFR2.390 FIGURE 3. 8-62 (SHEET 3 OF 10) AUXILIARY BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(l) REV. 28.1
SECURITY-RELATED-INFORMATION-Withhold under 10 CFR 2.390 FIGURE 3. 8-62 (SHEET 4 OF 10) AUXILIARY BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(l) REV. 28.1
SECURITY-RELATED-INFORMATION-Withhold under 10 CPR 2.390 FIGURE 3.8-62 (SHEET 5OF10) AUXILIARY BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CPR 2.390 (d)(l) REV. 28.1
SECURITY-RELATED-IN FORMATION-Withhold under 10 CFR 2.390 FIGURE 3.8-62 (SHEET 6OF10) AUXILIARY BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(l) AMENDMENT 3 AUGUST 1983
SECURITY-RELATED-INFORMATION-Withhold under 10 CFR 2.390 FIGURE 3.8-62 {SHEET 7 OF JO) AUXILIARY BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1 Withheld under 10 CFR 2.390 (d)(l)
SECURITY-RELATED-INFORMATION-Withhold under 10 CPR 2.390 FIGURE 3.8-62 (SHEET 8OF10) AUXILIARY BUil DING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CPR 2.390 (d)(l) REV. 28.l
SECURITY-RELATED-INFORMATION-Withhold under 10 CFR2.390 FIGURE 3.6-62 {SHEET 90FIO) AUXILIARY BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(l) REV. 28.1
SECURITY-RELATED-INFORMATION-Withhold under 10 CFR 2.390 FIGURE 3.8-62 {SHEET 10 OF 10} AUXILIARY BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CPR 2.390 (d)(l) REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8-63(SHEET 1OF6) FUEL BU ILO ING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1 Withheld under 10 CFR 2.390 (d)(1)
(Cf SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8-63 (SHEET 2 OF 6) FUEL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 Fl NAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390
'r"""?,e_ z....::;
\
FIG URE 3.8 -63 (SHEET 3 OF 6) FUEL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 Fl NAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) REV. 28.1
--.JC SECURITY-RELATED-INFORMATIONWithhold '.<...;;-
under 10 CFR 2.390
'r"'lY 2-(
FIGURE 3. 8-63 (SHEET 4 OF 6) FUEL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8-63 (SHEET 5 OF 6} FUEL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8-63 (SHEET 60F6l FUEL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FI NAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) AMENDMENT 3 AUGUST 1983
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3. 8-64 (I OF 4} CONTROL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1 Withheld under 10 CFR 2.390 (d)(1)
+C~LLE~
NORTH\bJ ~:~ IL ...........
~._, *o ~~
- ~
~EQUIPMENT ACC ESS HATCH CABLE fT SPREADING AREA f~
FIGURE 3.8-64 (2 OF 4) 1 PLAN EL . 24 - 6" CONTROL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT.
24*-o* U.P.S. CAB. UP.S. CAB. I I 11 I 0 IA> RACK-' I [IJ R A SECURITY R£L RI( M TAGGING OFFICE VENTILATION p R~~*~ EQUIPMENT ROOM D UPPER LEVEL (EL 64'-6" II TELEPHONE JACI< CONTROL,COMPUTER,AND INSTRUMENT RACK ROOMS "3RP!UfHAIOIUI I IHRU 4 fitUCLEAR W!GTRUlllEMnTI IFu4 '-G" RECEPTIONIST PERSONNEL~ TUNNEL
-..... CABLE SPREADING AREA rEL.24'*6" ELEC.
PRIMARY ... . , .... ,...... - TUNNEL ., .
;IU)(ILIARIES CB-01 MAIN CONTROL SWITCHGEAR ROOM SOARD-
.. 1EL.4CG"
~* CONTROL BUILDING ELEVATION (LOOKING (AST)
CliEMICAL
!i l/OLIJldE
- - t - -CONT OUTLINE OF NEW-.........._ /
EXCLUSION AREA ~ DD q r-~/ I I I I I STA ELECT TURS-GEN 1!IEGIJANIGALI STLI GEN 6 I 1 I I FDWTR .... I I I HAIN RElllOTE CORT. _...J ~;P-;;;.-;t!L r7: -;-ET-;~;-1 FUtC PROT Q T A . - - _ . . . . LEGEND 4 I :I I 2 I I PRIMARY PRWECTIVE RELAY I E.Hj e HTR~L CONTROL ROOM HABITABILITY AREA I PNL 11
- AT THE CONTROLS"
---- MASONRY BLOCK WALLS IN SAF'ETY-RELATED AREAS l IIII II I FIGURE 3.8-64 (3 OF 4)
INSTRUMENT RACK ROOM L--i-__._~_1._._1~1l~J ~ CONTROL ROOM AREA MILLSTONE NUCLEAR POWER STATION TOILET UNIT 3 FINAL SAFETY ANALYSIS REPORT 11 CAD FILE" m3641.dgn/m3641.ctt 11 CONTROL BUILDING PLAN EL. 47'- 6 Rev. 26.1
~~~ED~
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- RE168
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b ~ ~ t 3 HVC
- RE16A D L;::::;:] D r.==J L'9.VC-RE91 D
I I 0 FIGURE 3.8-64 (4 OF4) 11 PLAN EL . 64'- 6 CONTROL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 3 AUGUST 1983
~
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)> 0 ()l SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390
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SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 {) FIGURE 3.8-66 (SHEET I OF 5) EMERGENCY GENERATOR ENCLOSURE MILLSTONE NUCLEAR POWER STATION , UNIT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1 Withheld under 10 CFR 2.390 (d)(1)
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8-66 (SHEET 2 OF 5) EMERGENCY GENERATOR ENCLOSURE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT thheld under 10 CFR 2.390 (d)(1) REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 3 FIGURE 3 .8-66 (SHEET 30F5) EMERGENCY GENERATOR ENCLOSURE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) AMENDMENT 8 MAY 1984
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8-66 (SHEET 40F5) EMERGENCY GENERATOR ENCLOSURE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8-66 (SHEET 5 OF 5) EMERGENCY GENERATOR ENCLOSURE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) AMENDMENT 8 MAY 1984
MPS-3 FSAR NOTES TO FIGURE 3.8-66 EMERGENCY DIESEL GENERATOR - EQUIPMENT INDEX EQUIPMENT MARK NO. EQUIPMENT DESCRIPTION 3BYS*PNLDG1F Emergency Generator 125 V DC Distribution Panel 3CES*PNLBD10 Safety-Related to Nonsafety-Related Signal to Isolator Panel 3EGA*TK1A(A-) Emergency Diesel Generator Air Start System Air Receiver Tanks 3EGA*TK2A(A-) Emergency Diesel Generator Air Start System Air Receiver Tanks 3EGD*EJ3A Emergency Diesel Generator Exhaust Expansion Joint 3EGD*P1A(AO) Crankcase Vacuum Pump 3EGD*SIL1A(A-) Emergency Diesel Generator Combustion Air Filter and Silencer 3EGD*SIL2A(A-) Emergency Diesel Generator Combustion Air Silencer 3EGD*SIL3A(A-) Emergency Diesel Generator Exhaust Muffler 3EGD*SP1A(AO) Crankcase Vacuum Oil Separator 3EGF*P1A(AO) Emergency Generator Fuel Oil Transfer Pumps 3EGF*P1B(BP) Emergency Generator Fuel Oil Transfer Pumps 3EGF*P1C(CO) Emergency Generator Fuel Oil Transfer Pumps 3EGF*P1D(DP) Emergency Generator Fuel Oil Transfer Pumps 3EGF*TK1A(A-) Emergency Generator Fuel Oil Storage Tank 3EGF*TK1B(B-) Emergency Generator Fuel Oil Storage Tank 3EGF*TK2A(A-) Emergency Generator Fuel Oil Day Tank 3EGF*TRS1A Manual Transfer Switch for Emergency Generator Fuel Oil Transfer Pump 3EGS-E1A(A-) Emergency Diesel Generator Intercooler Water Heat Exchanger 3EGS*E2A(A-) Emergency Diesel Generator Engine Jacket Watercooler 3EGS*EG-A(AO) Emergency Diesel Generator Skid A 3EGS*EG1AN Emergency Generator 4 kV Neutral Current Transformer Lead Box Page 1 of 2 Rev. 16
MPS-3 FSAR NOTES TO FIGURE 3.8-66 EMERGENCY DIESEL GENERATOR - EQUIPMENT INDEX EQUIPMENT MARK NO. EQUIPMENT DESCRIPTION 3EGS*EG1APWR Emergency Generator Power Lead Termination Box 3EGS*JBFLDA Emergency Generator Housing Mounted Junction Box 3EGS*JBRTDA Emergency Generator Housing Mounted Junction Box 3EGS-PNL1A Emergency Generator Distribution Panel (Skid Mounted) 3EGS*PNLA Emergency Generator Control Panel 3EGS*PNLDGA Emergency Generator Control Panel 3EGS*TBEG1A Emergency Generator Control and Relay Box 3EHS*MCC1A1 Emergency Diesel Generator 480 V Motor Control Center 3ENS*ACB-GNA Emergency Generator 4 kV Neutral Ground Breaker 3ENS*RES-GNA Emergency Generator 4160 V Neutral Ground Resistor 3HVP*DMPT1A&C Diesel Generator Building Tornado Damper 3HVP*DMPT5A&C Diesel Generator Building Tornado Damper 3HVP*DMPT6A&C Diesel Generator Building Tornado Damper 3HVP*FN1A(AO) Diesel Generator Building Ventilation Supply Fan 3HVP*FN1C(CO) Diesel Generator Building Ventilation Exhaust Fan 3HVP-FN2A Diesel Generator Building Ventilation Exhaust Fan 3HVP*MOD-23A(AO)FO Diesel Generator Building Ventilation Inlet Damper 3LAD*EXL10 Diesel Generator Building Emergency Lighting Transformer 3SCV*PNL250 240/120 V AC Single Phase Emergency Distribution Panel 3SCV*XD250 240/120 V AC Single Phase Emergency Distribution Panel NOTE: With the exception of 3EGF*TK1B, *P1B, and *P1D, the equipment index shows Emergency Diesel Generator A equipment. Emergency Diesel Generator B equipment is similar. Page 2 of 2 Rev. 16
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8 - 67 (1 OF 9) ENGINEERED SAFETY FEATURES BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT March 2001 (00-27)
- ,- ~ - -
Withheld under 10 CFR 2.390 (d)(1)
0( SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8-67 (20F9) ENGINEERED SAFETY FEATURES BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8- 67 (3 OF 9) ENGINEERED SAFETY FEATURES BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1 Withheld under 10 CFR 2.390 (d)(1)
-~c R- ,5 -o SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 r~r- .)"U FIGURE 3.8-67 (40F9)
ENGINEER ED SAFETY FEATURES BUILDING MILLSTONE NUCLEAR POW ER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1 Withheld under 10 CFR 2.390 (d)(1)
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8 - 67 (5 OF ~1 ENGINEERED SAFETY FEATURES BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1)
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8-67 (6 OF 9) ENGINEERED SAFETY FEATURES BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1)
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 F IGURE 3 .8 - 67 (7 OF 9) ENGINEERED SAFETY FEATURES BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1)
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3 .8-67 (8 OF9) ENGINEERED SAFETY FEATURES BUILDING MILLSTONE NUCLEAR POWER STATION ' UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1)
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 l FIGURE 3 .8-67(9 OF9) ENGINEERED SAFETY FEATURES BUILDING Withheld under 10 CFR 2.390 (d)(1) Marefl=-2eef fee- 2-r-) CAD FILE: 1222.dgn/1222.clt
o\'S KEY PLAN SECURITY-RELATED-INFORMATIONWithhold under
- 10 CFR 2.390
\"'""'~ 31
{) FIGURE 3.8-68 (1 OF 4) MAIN STEAM VALVE BUILD ING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8-68 ( 2 OF 4) MAIN STEAM VALVE BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 15-7 FIGURE 3.8-68(3 OF 4) MAIN STEAM VALVE BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1)
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8-68(4 OF 4) MAIN STEAM VALVE BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINA L SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1)
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8 - 69 (SHEET 1 OF 4) CIRCULATING AND SERVICE WATER PUMPHOUSE OCTOBER 1997 Withheld under 10 CFR 2.390 (d)(1)
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 MNPS-3 FSAR FIGURE 3.8-69 (Sheet 2 of 4) CIRCULATING AND SERVICE WATER PUMPHOUSE SEPTEMBER 1995 Withheld under 10 CFR 2.390 (d)(1)
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE3.a-69 (SHEET 3 OF 4) C IRCU LATING AND SERV I CE WATER PUMPHOUSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1)
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FI GU R E 3.8-69(SHEET 4 OF 4) CIRCULATING AND SERVICE WATER PUMPHOUSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) AMENDMENT 15 SEPTEMBER 1985
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8-70 (1 OF 4) RECOMBINER BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8-70 (2 OF 4) RECOMBINER BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3
. FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1)
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3 .8-70 (3 OF 4) RECOMBINER BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FI NAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1)
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8-70 (4 OF 4) RECOMBINER BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1) REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 FIGURE 3.8-71 CIRCULATING DISCHARGE STRUCTURE AND TUNNEL MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Withheld under 10 CFR 2.390 (d)(1)
,------~--------------------- ---****---------*- *- -****-*****-- - - - - - - -- - -- - - - -- - -- - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - -- - SECURITY-RELATED-INFORMATION-Withhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(l) FIGURE 3.8-72 ( 1 OF 4) SERVlCE BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
SECURITY-RELATED-INFORMATION-Withhold under 10 CFR 2.390 f Withheld under 10 CFR 2.390 (d)(l) FIGURE 3 .8-72(2 OF 4) SERVICE BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1
SECURITY-RELATED-INFORMATION-Withhold under 10 CFR2.390 I Withheld under 10 CPR 2.390 (d)(l) FIGURE 3.8-72 (3 OF 4) SERVICE BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
SECURITY-RELATED-INFORMATION-Withhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(l) FIGURE 3.8-72 (4 OF 4) SERVICE BUILDlNG MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3. 8-73 ( 1 OF 5) TURBINE BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3.8-73 (2 OF 5) TURBINE BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3*. 8-73 ( 3 OF 5) TURBINE BUILDING MILLSTONE NUCLEAR POWER STATION UNlT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3-8-73 (4 OF 5) TURBINE BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) 5-5 FIGURE 3 .8-73 ( 5 OF 5) TURBINE BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 3 AUGUST 1983
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3. 8 - 74 (SHEET 1 OF 7) SOLID AND LIQUID WASTE DISPOSAL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3.8-74 (SHEET 2 OF 7) SOLID AND LIQUID WASTE DISPOSAL BUILDING REV. 28.1
MNPS-3 FSAR SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 N W A J3 J Withheld under 10 CFR 2.390 (d)(1) FIGURE 3.8-74 (SHEET 3 OF 7) SOLID AND LIQUID WASTE DISPOSAL BUILDING AUGUST 1996
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3.8 - 74 (SHEET 4 OF 7) SOLID AND L IQU ID WASTE DISPOSAL BUILDING MILLSTONE NUCLEAR POWER STATION
. UNIT:3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 3 AUGUST 1983
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 YP) Withheld under 10 CFR 2.390 (d)(1) FIGURE 3.8 -74 (SHEET 5 OF 7) SOLID AND LIQUID WASTE DISPOSAL BUILDING Ml LL STONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3.8 -74 (SHEET 60F7} SOLID AND L !QUID WASTE DlSPOSAL BU IL DING MILL STONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY AN ALYS IS REPORT REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3.8 - 14 (SHEET 70F7) SOLID AND LIQUID WASTE DISPOSAL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3.8-75 (1 OF12) WAREHOUSE NO. 5 MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3.8-75 {20F12) WAREHOUSE NO. 5 Ml LLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3. 8- 7 5 ( 3 OF 12) WAREHOUSE NO. 5 Ml LLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3.8-75{4 OF 12) WAREHOUSE NO. 5 MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3.8-75(5 OF 12.) WAREHOUSE NO. 5 MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALSIS REPORT REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3.8-75 (6 OF 12} WAREHOUSE NO. 5 MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALSIS REPORT REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3 .8 -75 (7 OF 12) WAREHOUSE NO.5
. MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3.8-75 (8 OF 12) WAREHOUSE NO.5 MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3.8-75(90F 12} WAREHOUSE NO. 5 MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3 .8-75(10 OF 12) WAREHOUSE NO.5 MILLSTONE NUCLEAR POWER STATION UNIT :3 FINAL SAFETY ANALYS IS REPORT
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3.8 -75 (11 OF 12) WAREHOUSE NO.5 MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3. 8-75 (12 OF 12) WAREHOUSE N0.5 MILLSTONE NUCLEAR POWER STATION UNIT "3 FINAL SAFETY ANALYSIS REPORT REV. 28.1
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIG URE 3 . 8 - 76 (1 0 F 5) AU X I L I A RY B 0 I L E R ENCLO 5 URE MIL LSTONE N UC LE AR POWER STAT ION UN IT 3 FINAL SAFETY ANALYSIS REPORT
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3.8-76 (2 OF 5) AUXIL IARY BOILER ENCLOSURE MILLSTONE NUCLEAR POWER STATION UN IT :3 FINAL SAFETY ANALYSIS REPORT
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIG URE 3 . 8 - 76 ('3 0 F 5) AUXILIARY BOILER ENCLOSURE MILLSTONE NUCLEAR POWER STATION UNIT3 FINAL SAFETY ANALYSIS REPORT
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3 .8-76 (40F5l AUXI L IARY BOIL ER ENCLOSURE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT ~r ..
- [
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3.8 -76 (5 OF 5) AUXILIARY BOILER ENCLOSURE MILLSTONE NUCLEAR POWER STATION UNIT 3 FI NAL SAFETY ANALYSI S REPORT
SECURITY-RELATED-INFORMATIONWithhold under 10 CFR 2.390 Withheld under 10 CFR 2.390 (d)(1) FIGURE 3.8-77 ARRANGEMENT OF HORIZONTAL SHEAR KEYS MILLSTONE NUCLEAR POWER PLANT UNIT 3 FIr.lAL SAFETY ANALYSIS REPORT CAD FILE: 3877.d<;ln/3877.clt DECEMBER 1997
-------_.-._------~-
FOUNDATION MAT o o o o o o o o FOUNDATION MAT KEY QA CATEGORY I BACKFILL BEDROCK TILL OR COMPACTED FILL PIPE TO UNDERDRAIN SUMPS FIGURE 3.8-78 TYPICAL SHEAR KEY DETAIL MILLSTONE NUCLEAR POWER PLANT UNIT 3 FINAL SAFETY ANALYSIS REPORT
-T=15.2 HRS 220 R IT=20.4 HRS
. .I 200 CASE 1I B - - y "
CASE IT A 180 I..L
°I w 160 0::
- l _ _ _~rCASE ill: T=150oF _S._S_. _
f 0:: w 140 0...
- 2: '. .~.--.;....-------
w f rCASE I: T=125° S.S. 120 100 80 ~-------l-------L------L.-----....L-----..L------l--- ... o 10 20 40 50 60 NOTES: CASE I: NORMAL REFUELING - MAXIMUM TEMPERATURE FIGURE 3.8-79 CASE II A: NORMAL HEAT LOAD WITH LOSS OF COOLING FUEL POOL TEMPERATURE CASE n B: NORMAL HEAT LOAD- MAXIMUM To - WITH LOSS OF COOLING TRANSIENTS CASE ill: FULL CORE OFF LOAD- MAXIMUM TEMPERATURE MILLSTONE NUCLEAR POWER STATION S S. =STEADY STATE UNIT 3 To = INITIAL TEMP. (S.S.) WATER FINAL SAFETY ANALYSIS REPORT R = RANGE OF CONDITIONS FOR VARYING To WITH LOSS OF COOLING AMENDMENT 2 APRIL 1983
FUEL BLDG. INTERIOR T= SO to 104° F
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_ _ _ SPENT FUEL SHIPPING ___ CASK STORAGE AREA
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- <1'. ' * :--_SPENT FUEL SHIPPING
... CASK LOADING AREA SPENT FUEL POOL
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T' SEE FIGURE 3.8-7 9 (GATES
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- 7
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OUTSIDE SOO F SUMMER T = { 00 F WINTER
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NOTES Toe = INITIAL TEMPERATURE OF CONCRETE (70 to 90°F)
*{ T= SOoF WHEN EMPTY (GATE IN PLACE)
T=CASE II A &B, FOR FUEL POOL TEMP. WHEN FULL (GATE NOT IN PLACE) T (6 FEET BELOW GRADE) = 43° F MINIMUM FIGURE 3.8 -80 FUEL POOL - FUEL BUILDING TEMPERATURE CONDITIONS MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 2 APRIL 1983
250 225 200
- - - -- CASE IIA
. 1\., , ", - . - . - CASE IIB w
0:: CAS E IV
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125 ....... -. 100 ...........""T'"""T........~....-r-+-r.,......,.~f-r-T""'T"".,...-t....,....,-r-r-t-............,......,.-t-;r-r-T""'T""+-r-r-T~f-.,.- ...........--.-+-r--~.,-+-""T'"""T....,....,-l 0.0 5.0 10.0 15.0 20.0 25.0 30.0 35 .0 40 .0 45.0 50.0 55 .0 TIME AF TER MA X. TEMP. HAS REA CHED. HR FIGURE 3.8-81 NOTES: FUEL POOL TEMPERATURE TRANSIENTS CAS E IIA: NORMAL HEAT LOAD WITH LOSS OF COOLI NG FOR HIGHER ENRICHMENT FUEL CASE IIB: NORMAL HEAT LO AD-MA XI MUM TO- WITH OF COOLING CASE IV: FUL L CORE OF F LOAD WITH LOSS OF COOLING MILLSTONE NUC LEA R POWER STA TION UNIT 3 FI NAL SAFETY ANALYSIS REPORT J UNE 1992
MNPS-3 FSAR 10 rr.- 0 IN. lOP or SlACK EL. 389.00 F1. -: I I I I I I I I I I 120 FT.-O IN. . I I I I I r r I r I
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r I I I I I I I 375 Fr.-O Ht 120 FT.-O Itt ; I I PlAN I I I I I I I I
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- 16 16 834 -
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.- - - -25 Z5 2117 26 26 2319
.- - - -27 27 2532 28 28 2762
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- ..r~---.. --- 40 40 15423 Figure 3.8 -84 M "II I stone Stack - M athem ati c al Mod el M arch 20 0 1 (0 0 -50 )}}