Revision as of 14:57, 2 April 2019

Text

Final Safety Analysis Report, Rev. 30, Chapter 3, Figures 3.2-1 - 3.8-84
	ML17212A071
Person / Time
Site:	Millstone
Issue date:	06/29/2017
From:	; Dominion Nuclear Connecticut
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML17212A038	List: ML17212A039; ML17212A041; ML17212A042; ML17212A044; ML17212A045; ML17212A047; ML17212A048; ML17212A049; ML17212A050; ML17212A051; ML17212A052; ML17212A053; ML17212A054; ML17212A056; ML17212A058; ML17212A059; ML17212A060; ML17212A063; ML17212A064; ML17212A065; ML17212A066; ML17212A067; ML17212A068; ML17212A069; ML17212A070; ML17212A071; ML17212A072; ML17212A073; ML17212A074; ML17212A076; ML17212A077; ML17212A079; ML17212A080; ML17212A081; ML17212A082; ML17212A083; ML17212A084; ML17212A086; ML17212A087; ML17212A088; ML17212A089; ML18295A107; ML18295A114; ML18295A123; ML18295A125;
References
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{{#Wiki_filter:UNIT NUMBER/UNIT3 SYSTEM DESIGNATION3-ASS I AUX.STEAM SYSTEM LINE SEGMENT SAFETYPIPESIZENUMBER/ CLASS I 025-11-3 I3-ASS-025-1-3 2 1/2" LINE NUMBER LINE NUMBER-3ASS025001-3 REFERTOSECTION 6.3.1 LINE DESIGNATION 3-CVS-002-2-2 3-CV S-002-1-4SAFETYCLASS 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)1.2 PRESSURE VS TIME 1.1 1.04 1.0 L.-IL.--'-_..lIIIIIIt. __--"'..,.;... __-'-E:--..........----->_'--_ ...... 10 2.0 3.0 FREQUENCY (HZ)4.0 5.0 6.0 FIGURE 3.3-1DYNAMICLOADFACTORCURVEFORTORNADO PRESSURE DROP MILL ST ONE NU CLE AR POWER STATION U N IT 3 F INAL SA FET Y ANA LYSISREPORT A M ENDMENT II NOVEMBER 1984 )(KEY PLAN SEAWALL I I 11'-1*ACCESS OPNG.tTYP)....--.**I EJ----.... --o*----,fL---------tt---------r REMOVABLE CHECKERED PLATE MNPS-3FSAR ,.-r., .21.-PlJWP HousEl 20'-2" SO:.I"*0 , 0 10-1 2Q-Z 3CWs:.-PI8 ,....,),---ClReWATERVALVE ACCESSMANHOt.EISTOPLOGtTYP) METAl COVER ClYF)0 FLUSH w..-ELl4'-6"-- ......_-o**STOPLOGGATE (TYP)20'*2" CIRC ,WATERPUMP 3CWS-PIA*::)REMOVABLEI CHECKERED PLATE (TYP)11'-1 0 (STOP LOG.MoNORAIL a.LifTING ALUGS- ---I I'--*'0 ZI-6 CHLORINE ROOM....*0-....-.oD'L:9RfMOVABLE--r HANDRAilTRAVEl.l'JG WATER _HEAD SHAF.!..T-+-#- " o I-PLANEL14 1-6 11FIGURE3.4-1 (SHEET1OF4)CIRCULATING AND SERVICE WATER PUMPHOUSE o I 20 I 40 I SCALE-FEET OCTOBER 1997 PUMPHOUSE 2" I I I , lJ I lJ 2J PLAN EL 39'-0"L FIGURE 3.4-1 (SHEET2OF 4)CIRCULATING AND SERVICE WATER PUMPHOUSE MILLSTONE NUCLEAR POWER STATION UNIT3 FINAL SAFETY ANALYSIS REPORT CH 1GH WATERLEVELEL2'-0'--r::--'-IoAEANSEALEVEL*_----..i:::"" LOW WATER LEVEL ELH2-0 ,.-(]rOR AL L EQUIPMENT-rDESIGN LOW LEvEL ELH5;6 EXCEPT SERVICE WATER-c---EXTREWELOWLEVEL ELC-17-0'. LOWLEVEL HC')8'-0'FOR SERVICE WATER PUlo4PS ONLY.*'LVAR"S 60 to.WARM WATER RECIRC TEMPERItIG LINE'.r-EU-)2a'-0'..r-\,'t":*, f**-, ..,:-r....-,',..'....,.,..I.*r*o.......'.!:0i-I I II'1+qt"'I I.":.'f i...;..J..., R:.'I-l-t--"-.1-1=l-I I--,I)+(I" ,..L (-t II1+-,-t t--t-I-""....-t-.-+I-I.f-I)=t\I........::";-: '...*,.1.I..,U 1.i.SII..tf ,--}.., rt r,--.--r t-.....I Ir I..CHLORINE NlOM',-'A£MOVAIU*Ill(TAL'COVER<TY!")..*'i ,....."".:.;:-----:-' .,,".....-.:...: ,"': 7_...SECTION 1-1FIGURE3 ,4-1 (SHEET3OF 4)C I RCU LAT ING AND SERVICE WATER PUMPHOUSE MILLSTONE NUCLEARPOWERSTATION UNIT 3 FINAL SAFETY ANALYSIS REPORT ,.: "'--" I!!-f-*I!i , Ii_.I r"r:i!i d!I'"'" I 4-I I jSCREENWASH PUMP R£WOVA8LE;r-CO"CRETE SLAB i , ,#-......,*1'OIl.........::EL..\/(-)7'0" I-,I SLUICE-I GATE FLOW.I I r 1I 1/{1 SECTION 2-2 FIGURE 3.4-1 (SHEET4OF 4)CIRCU LATINGAND SERVICE WATER PU MPHOUSE MILLSTONE NUCLEAR POWER STAT ION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE3.5-1 TURBINE PLACEMENT Eo ORIENTATION FOR THREE UNIT SITEMILLSTONENUCLEAR POWER STATIONUNIT3 FINALSAFETYANALYSISREPORT F SWI FIGURE 3.5-2 TURBINEPLACEMENTAND ORIENTATION PROFILE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT Figure 3.5-3 DELETED by FSARCR 02-MP3-13 Figure 3.5-4 DELETED by FSARCR 02-MP3-13 Figure 3.5-5 DELETED by FSARCR 02-MP3-13 L.2==_==V\!,'ESTL OGS c.,!!r-!::::-b, l......----!i-I'c')I I.-.J j I!2'::_.-"--','--+r------"*.}...:*.,:.......'----t-I , 1;//, L-(---'-'-.:-r-:-- (.-:-,-<[.---C-.---------------i*------- 2-2 I"..,'tll"* B"" T 2-1 0'LG'T y D l..." i I-I FIGURE 3.5-6 MISSILE BARRIER BEAM COLUMN MILLSTONE NUCLEARPOWERSTATION UNIT 3 FINAL SAFETY ANALYSI S REPORT AMENDMENT 3 AUG US T 1 9 83 OUTSIDE CONTAINMENT (BTP APCSB 3-1

e. MEB 3-1) HIGH ENERGY SYSTEMS LL. (BREAKS ONLY) W 0:: ::::> 0:: 200 F MODERATE ENERGY (CRACKS) 275 PRESSURE (PSI G)

INSIDE CONTAINMENT ( REGULATORY GUIDE L46) HIGH ENERGY SYSTEMS (BREAKS ONLY) W 0:: ::::> !;t 0:: W a.. 200 F EXCLUDED AREA w 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 ..-+-+--CONTMT RECIRC COOLER (TYP) RHR HI. EXCHANGER (TYP)---H-------,4O( \+----t--+---CRANE WALL 141---CONTAINMENT STRUCTURE REAC PUMP FIGURE 3.6-2 RELATIVE LOCATIONS OF SAFETY-RELATED EQUIPMENT-EL. 3 1-8 " j MILLSTONE NUCLEAR POWER STATION UNIT 1 FINAL SAFETY ANALYSIS ., , HIGH PRESSURE *SAFETY INJECTION P*UMP fTYP ) QUENCH SPRAY PUMP(TYP)---I++-.....:u. RHR HEAT EXCHANGER(TVP) PERSONNEL ACCESS LOCK REACTOR COOLANT PUMP-3RCS*PIC EN6INEEREO SAnn FEA *3FWA*PIA I ..._-4H-AU>< ILiARV FE EOWATER PUMP (TYP) HYDROGEN R*COMBINER BUILDING REACTOR COOLANT PUMP-3RCS*P1B 20" FEEDWATER LlNE(TYP) i-4----MAIN STEAM VALVE BUILDING FIGURE 3.6-3 RELATIVE LOCATIONS OF SAFETY-RELATED EQUIPMENT EL 24'-6" MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT ENGINEERED SAFETY FEATURES BUILDING RELATIVE LOCATIONS SAFETY RELATED EQUIPMENT EL.51 1-4" MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT 3RSS*EI8 I I I I I I I L J ,: I I L.1-_.-,,,.*_--Il*****- , ,3RSfffiS*E'C

/..+'-J-";'..,..,': 4 I RHR HT 1 3RHS*EIB\EXCHANGER----*I'(TYP.)----J I REACTOR \4---CONTAINMENT STRUCTURE ) :.-1 ">\ .:

MAIN .j. ...: ;".!" STREAM STEAM GENERATOR 'to .A 3RCS*SGIC STEAM GENERATOR 3RCS*SGIA rt9" l+/-! r " AI\ 30 M MAIN STEAM \. Ii 66'-8 M _ -II-rf --------....+ jJ ! . br===bl REMOVABLE SHIELD WALL", , :1 V I * ! (TY P. 1r-1-J

\ 1 /1--1--; -SHIELD WALL , EL. 20'*0" I...

RECOMBINER BUILDING B:',.: b,'" SAFETY INJECTlON __ ACCUMULATOR TANK ----:-:-<, 3 SIL *TKIC , I FIGURE 3.6-5 I I RELATIVE LOCATIONS OF SAFETY -RELATED EQUIPMENT ! SECTION t-I MILLSTONE NUCLEAR POWER STATION I UNIT 3 1 1 FINAL SAFETY ANALYSIS REPORT REACTOR , 1 I i CONTAINMENT STRUCTUREPOLARCRANE3MHR-CRNI-540 TONFIGURE3.6-6 RELA TIVE LOCATIONS OF SAFETY-RELATED EQUIPMENTSECTION2-2 MILLSTONE NUCLEARPOWERS TATION UNIT 3 FINAL SAFETY ANALYSIS REPORT OPERATING FLOOR EL.51'-4" , I I v I 1'.1./IA..:i" J:'.I 2-2\INCORE INSTR.'<;ACCESSTUNNEL [-!----+=")-STEELLINER PLATE (TYP)!1 l IMAINS TEAMNOZZLEITYP) , 1:.6"'....30"MAINSTORM---------W_._.20"FEEDWATER 'L , I'...;...,.r'/i:: J-----PRESSURhER !1.1 I...__f--3RCS*TKIj_-3RCS*SGIASTEAMGENERATORS-l-l--I-+----t--t ,'-1--1 I I (TYP)\17\1 1,7\--+--/\-,I!REFUELING CANAL El.l"-."1" ,;0;1 I r-T"'=':------'!REJTOR ,"\.3R f'S*REI r.-;;.: ',.;,.I-----'-=---'-----'=---,:: ,>1.:'--------:".: 'rr (..j ACCESS PLUG-

 .il  4'." EL.36'-6"7 QUENCH SPRAY PUMP (TYP)  3QSS*P3A 3QSS*P3B 3S'Hi 3S\;A A'P &;

l.. /' ../ "'-MTR DRV S G -.TURB DRV SG SAFETY INJECTIONFDW TR PUMP (TYP) AUX FDW TR PUMP (TYP) PUMP EL.4'-6" loc'

4-4 I

".,<\,.:.4"At ." I fI 0: r;," '2  .0-

114-----1-+RHR HT , EXCHANGER (TYP,)i .., ,..J ., ,..J I

CONTMT RECIRC. PUMP (TYP) I FIGURE 3.6-7 RELATIVE LOCATIONS I I .4 OF SAFETY-RELATED EQUIPMENT I tU-....-<1'..'"-----.:: --.1 I tU-SECTION 3-3, 4-4 11'!r=-=-'"MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPOFff 3-3 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 SEE TABLE

3. A PIPE EXCLUSION ZONE EXTENDS FROM THE INBOARD SIDE OF THE CONTAINMENT TO THE LINE 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 1 of 4 Rev. 16NOTES TO FIGURE 3.6-8 DATA FOR PIPE RUPTURE RESTRAINTS - MAIN STEAM SYSTEM Restraint IdentificationBreak #ElevationDistance from N-S ContainmentDistance from E-W ContainmentRestraint TypeFunction of the Pipe Rupture Restraint 3MSS-PRR1LA (1)66'-3"53'-3" West 21'-8" SouthLimit Stop & StrapPrevent pipe whip into Crane Wall & Liner 3MSS-PRR2LA 2 66'-3"45'-10" West 32'-2" SouthSleeve in Crane WallProtect 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-DirectionalPrevent 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" East20'-11" SouthLaminated Strap Prevent whip into Polar Crane Support 3MSS-PRR8LA 1, 2, & 3 93'-6"14'-3" West 53'-2" SouthLimit StopPrevent whip into Crane Wall 3MSS-PRR9LA 1, 2, & 3 93'-6"14'-3" East 53'-2" SouthLimit StopPrevent whip into Crane Wall 3MSS-PRR3SB (3)66'-3"52'-2" West 17'-5" South Omni-DirectionalPrevent whip into Steam Generator Supports 3MSS-PRR5SB 3 72'-6"48'-11" West 25'-2" South Omni-DirectionalPrevent whip into Crane Wall 3MSS-PRR6SB 2 88'-9"39'-3" West 18'-6" SouthLaminated StrapPrevent whip into Crane Wall 3MSS-PRR7SB 1 88'-9"39'-3" West 18'-6" SouthLaminated Strap Prevent whip into Polar Crane Support 3MSS-PRR3SC (3)66'-3"52'-2" West 17'-5" North Omni-DirectionalPrevent whip into Steam Generator Supports 3MSS-PRR5SC 3 72'-6"48'-11" West 25'-2" North Omni-DirectionalPrevent whip into Crane Wall 3MSS-PRR6SC 2 88'-9"39'-3" West 18'-6" NorthLaminated StrapPrevent whip into Crane Wall 3MSS-PRR7SC 1 88'-9"39'-3" West 18'-6" NorthLaminated Strap Prevent whip into Polar Crane Support 3MSS-PRR1LD (1)66'-3"53'-3" West 21'-8" NorthLimit Stop & StrapPrevent pipe whip into Crane Wall & Liner 3MSS-PRR2LD 2 66'-3"45'-10" West 32'-2" NorthSleeve in Crane WallProtect Crane Wall 3MSS-PRR3LD 3 71'-8"42'-6" West 34'-10" North Omni-Directional (2) MPS-3 FSAR NOTES TO FIGURE 3.8-6 CONT'D 2 of 4 Rev. 16 3MSS-PRR4LD 1 & 2 87'-6"42'-6" West 34'-10" North Omni-DirectionalPrevent 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" East20'-11" NorthLaminated Strap Prevent whip into Polar Crane Support 3MSS-PRR8LD 1, 2, & 3 93'-6"14'-3" West 53'-2" NorthLimit StopPrevent whip into Crane Wall 3MSS-PRR9LD 1, 2, & 3 93'-6"14'-3" East 53'-2" NorthLimit StopPrevent 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" SouthLimit Stop Protects the Break Exclusion Zone 3MSS-PRR4A 4 56'-3"173'-8" West 29'-0" NorthLimit Stop Protects the Control Building 3MSS-PRR5A 5 & 6 55'-10"177'-0" West 66'-6" NorthLimit Stop Protects the Control Building 3MSS-PRR7A 7 or 8 55'-4"214'-6" West 70'-7" NorthLimit Stop Protects the Control Building 3MSS-PRR13A 7, 8, or 9 54'-8"234'-10" West 65'-9" NorthLimit 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" SouthLimit Stop Protects the Break Exclusion Zone 3MSS-PRR4B 4 56'-4"168'-2" West 29'-0" NorthLimit Stop Protects the Control Building 3MSS-PRR5B 5 & 6 55'-10"171'-7" West 71'-7" NorthLimit Stop Protects the Control Building 3MSS-PRR7B 7 or 8 55'-4"214'-6" West 75'-7" NorthLimit Stop Protects the Control Building NOTES TO FIGURE 3.6-8 DATA FOR PIPE RUPTURE RESTRAINTS - MAIN STEAM SYSTEM Restraint IdentificationBreak #ElevationDistance from N-S ContainmentDistance from E-W ContainmentRestraint TypeFunction of the Pipe Rupture Restraint MPS-3 FSAR 3 of 4 Rev. 16 3MSS-PRR13B 7, 8, or 9 54'-8"241'-10" West 71'-2" NorthLimit 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" NorthLimit Stop Protects the Break Exclusion Zone 3MSS-PRR4C 4 56'-5"162'-8" West 29'-0" NorthLimit Stop Protects the Control Building 3MSS-PRR5C 5 & 6 55'-10"166'-2" West 76'-8" NorthLimit Stop Protects the Control Building 3MSS-PRR7C 7 or 8 55'-4"214'-6" West 80'-7" NorthLimit Stop Protects the Control Building 3MSS-PRR13C 7, 8, or 9 54'-8"248'-9" West 76'-7" NorthLimit 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" NorthLimit Stop Protects the Break Exclusion Zone 3MSS-PRR4D 4 & 5 62'-5"150'-1" West 29'-0" NorthLaminated Strap Protects the Control Building 3MSS-PRR5D 5 & 6 55'-10"160'-9" West 81'-9" NorthLimit Stop Protects the Control Building 3MSS-PRR7D 7 or 8 55'-4"214'-6" West 85'-7" NorthLimit Stop Protects the Control Building 3MSS-PRR13D 7, 8, or 9 54'-8"255'-8" West 82'-0" NorthLimit Stop Protects the Control Building NOTES TO FIGURE 3.6-8 DATA FOR PIPE RUPTURE RESTRAINTS - MAIN STEAM SYSTEM Restraint IdentificationBreak #ElevationDistance from N-S ContainmentDistance from E-W ContainmentRestraint TypeFunction of the Pipe Rupture Restraint MPS-3 FSAR 4 of 4 Rev. 16 Notes(1).Pipe Rupture Restraints 3MSS-PRR1LA and 3MSS-PRR1LD are laminated straps which prevent the Main Steam line from impacting t he Containment Line r subsequent to Break Number 3 on Main Steam Lines 3-MSS-030-92-2 and 3-MSS-030-95-2. The Limit Stop f unction 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 cont ainment penetration inside containment to each Main Steam Containment Isolation Valve O utside Containment.(2).Pipe rupture restraints 3MSS-PRR3LA and 3MSS-PRR3LD prevent pipe whip within the adjacent Steam Generator Cubicles 3RCS*SG1 B 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 pr event 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 in cludes the pipe to flued head weld inside cont ainment to protect the containment liner from jet impingement effects. BENDTYf>I N5PLACES NOTES 1.FORTHETURBINEBY*PASSSTEAMPIPINGBREAKSWEREPOSTULATEDATTERM INAL ENDS ,ANDAT iEVERYPIPINGWELDTOFITTINGANDVALVE. HOWEVER ,THEPORTIONOFTHE TURBINE BY*PASSPIPINGFROMTHEMAINSTEAM MANIFOLD WH ICHRUNINPARALLELWITHTHECONTROL BUILDINGWALLISPROVIDEDWITH5*DIAMETERBENDSINLIEUOFFITTINGSTOPRECLUDEBREAKSFROMOCCUR

RINGWITHINTHISSECTIONOFTHEPIPING

, THEREBY PROTECTING THECONTROL BUILDING WALL FROMPIPEWHIP.SIMILARLY ,FORTHEMOISTURESEPARA

TORSTEAMPIPING

.BREAKSWEREPOSTULATEDAT TERMINAL ENDS ,ANDATEVERYPIPINGWELDTOFITTINGANDVALVE. 2.EXAMINATIONOFTHEMOISTURESEPARATORSTEAMPIPINGFOREFFECTSOFPIPERUPTUREANDJET IMPINGEMENT HAS DETERMINED THATNOPROTECTIVEMEASURESAREREQUIRED. 3.NOMENCLATURE: @-INDICATESBREAKAT TERMINALENDS .@.INDICATESBREAKAT INTERMEDIATE LOCATIONS.FIGURE3.6-9MAINSTEAM SYSTEM (CONTINUED) MILLSTONENUCLEARPOWERSTATIONUNIT3FINALSAFETYANALYSISREPORT 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 SHOWN ONLY IN LOOP B AND LOOP A ON FEEDWATER PIPING, BUT THEY ARE ALSO CABLE TO THE OTHER MATCHING G)INDICATES PIPE BREAK NO.1 FOR

SUMMARY

OF POSTULATED PIPE BREAKS SEE TABLE 3.6-9. 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. 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.PIPERUPTURERESTRAINTSONTHEFEEDWATERSYSTEMARE SHOWNFORLOOPSAANDB .THESERESTRAINTSARE TYPICALFORLOOPSCANDD ANDAREAT IDENTICAL LOCATIONS.2.PIPERUPTURERESTRAINTSMARKED*ARE DUAL FUNCTIONPIPESUPPORT-PIPERUPTURE RESTRAINTS .FIGURE 3.6-11 FEEDWATER SYSTEMPIPERUPTURE RESTRAINTS 3FW$-PRRIOl JANUARY 1998 MPS-3 FSAR 1 of 5 Rev. 16NOTES TO FIGURE 3.6-11 DATA FOR PIPE RUPTURE RESTRAINTS - MAIN FEEDWATER SYSTEMRestraint IdentificationBreak #ElevationDistance from N-S ContainmentDistance from E-W ContainmentRestraint TypeFunction of the Pipe Rupture Restraint 3FWS-PRR2LA (1)85'-1"41'-3" West 36'-4" South Omni-DirectionalPrevent pipe whip into Crane Wall 3FWS-PRR3LA 3 89'-6" 47'-10" East 27'-2" South Omni-DirectionalPrevent pipe whip into Crane Wall 3FWS-PRR4LA(1)86'-11" 47'-6" East 19'-6" South Pipe Crush BumperPrevent pipe whip into Crane Wall 3FWS-PRR5LA 2 & 3 54'-3" 44'-1" East21'-11" SouthFlat Stop Prevent pipe whip into Operating Floor 3FWS-PRR7LA (1)63'-0"39'-6" West 38'-3" South Omni-DirectionalPrevent pipe whip into Crane Wall 3FWS-PRR8LA (1)89'-6"32'-8" West 44'-3" South Omni-DirectionalPrevent pipe whip into Crane Wall 3FWS-PRR9LA(1)89'-6"3'-10" West 54'-10" South Pipe Crush BumperPrevent pipe whip into Crane Wall 3FWS-PRR10LA(1)89'-6" 25'-10" East 48'-7" South Pipe Crush BumperPrevent pipe whip into Crane Wall3FWS-PRR11LA(1)87'-0" 46'-4" East 21'-8" SouthFlat Stop Prevent excessive load to steam generator nozzle 3FWS-PRR12LA 1 & 2 61'-4" 42'-9" East 25'-0" South Brace on 3MSS-PRR7L (2)3FWS-PRR13LA 1 & 2 61'-4" 42'-9" East 25'-0" SouthFlat 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" SouthLaminated Strap Prevent pipe whip into 3RCS*SG1B 3FWS-PRR6SB(1)56'-4"40'-1" West 26'-9" SouthFlat Stop Prevent excessive load to steam generator

nozzle 3FWS-PRR7SB(1)44'-3"50'-9" West9'-11" SouthLaminated Strap Prevent excessive load on containment

penetration 3FWS-PRR8SB 1, 2 & 3 59'-10"39'-4" West 23'-7" SouthLaminated Strap (2) MPS-3 FSAR NOTES TO FIGURE 3.6-11 CONT'D 2 of 5 Rev. 16 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" NorthLaminated Strap Prevent pipe whip into 3RCS*SG1C 3FWS-PRR6SC(1)56'-4"40'-1" West 26'-9" NorthFlat Stop Prevent excessive load to steam generator nozzle 3FWS-PRR7SC(1)44'-3"50'-9" West9'-11" NorthLaminated Strap Prevent excessive load on containment

penetration 3FWS-PRR8SC 1, 2 & 3 59'-10"39'-4" West 23'-7" NorthLaminated Strap (2)3FWS-PRR2LD(1)85'-1"41'-3" West 36'-4" North Omni-DirectionalPrevent pipe whip into Crane Wall 3FWS-PRR3LD 3 89'-6" 47'-10" East 27'-2" North Omni-DirectionalPrevent pipe whip into Crane Wall 3FWS-PRR4LD(1)86'-11" 47'-6" East 19'-6" North Pipe Crush BumperPrevent pipe whip into Crane Wall 3FWS-PRR5LD 2 & 3 54'-3" 44'-1" East21'-11" NorthFlat Stop Prevent pipe whip into Operating Floor 3FWS-PRR7LD(1)63'-0"39'-6" West 38'-3" North Omni-DirectionalPrevent pipe whip into Crane Wall 3FWS-PRR8LD(1)89'-6"32'-8" West 44'-3" North Omni-DirectionalPrevent pipe whip into Crane Wall 3FWS-PRR9LD(1)89'-6"3'-10" West 54'-10" North Pipe Crush BumperPrevent pipe whip into Crane Wall 3FWS-PRR10LD(1)89'-6" 25'-10" East 48'-7" North Pipe Crush BumperPrevent pipe whip into Crane Wall3FWS-PRR11LA(1)87'-0" 46'-8" East 22'-1" NorthFlat Stop Prevent excessive load to steam generator

nozzle 3FWS-PRR12LA 1 & 2 61'-4" 42'-9" East 25'-0" North Brace on 3MSS-PRR7L (2)NOTES TO FIGURE 3.6-11 DATA FOR PIPE RUPTURE RESTRAINTS - MAIN FEEDWATER SYSTEMRestraint IdentificationBreak #ElevationDistance from N-S ContainmentDistance from E-W ContainmentRestraint TypeFunction of the Pipe Rupture Restraint MPS-3 FSAR 3 of 5 Rev. 16 3FWS-PRR13LA 1 & 2 61'-4" 42'-9" East 25'-0" NorthFlat 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 BumperPrevent 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" West11'-6" South Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR6B(3)49'-11"124'-1" West11'-6" South Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR7B(3)60'-9"124'-1" West11'-6" South Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR9SB(3)49'-11"87'-10" West11'-6" South Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR10SB(3)51'-2"124'-11" West11'-6" South Pipe Crush BumperPrevent 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 ZoneNOTES TO FIGURE 3.6-11 DATA FOR PIPE RUPTURE RESTRAINTS - MAIN FEEDWATER SYSTEMRestraint IdentificationBreak #ElevationDistance from N-S ContainmentDistance from E-W ContainmentRestraint TypeFunction of the Pipe Rupture Restraint MPS-3 FSAR 4 of 5 Rev. 16 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" West11'-6" North Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR6C(3)49'-11"124'-1" West11'-6" North Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR7C(3)60'-9"124'-1" West11'-6" North Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR9NC(3)49'-11"87'-10" West11'-6" North Dual Function Limit stress within Break Exclusion Zone 3FWS-PRR10NC(3)51'-2"124'-11" West11'-6" North Pipe Crush BumperPrevent 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 BumperPrevent interaction with adjacent feedwater lineNOTES TO FIGURE 3.6-11 DATA FOR PIPE RUPTURE RESTRAINTS - MAIN FEEDWATER SYSTEMRestraint IdentificationBreak #ElevationDistance from N-S ContainmentDistance from E-W ContainmentRestraint TypeFunction of the Pipe Rupture Restraint MPS-3 FSAR 5 of 5 Rev. 16 Notes(1).Pipe Rupture Restraints 3MSS-PRR1LA and 3MSS-PRR1LD are laminated straps which prevent the Main Steam line from impacting t he Containment Line r subsequent to Break Number 3 on Main Steam Lines Pipe r upture restraint provided to mitigate the ef fects of Arbitrary Intermediate Breaks (AIBs). USNRC Generic Letter 87-11 eliminates the requirement to analyze the effects of pi pe whip subsequent to AIBs. Therefore, these restraints are installed but do not pe rform a safety function.(2).Pipe rupture restraint is provided to prevent an impact to the Steam Generator Cub icle Wall. Unrestrained pipe whip impact to this concrete barrier wo uld result in catastrophic failure of the barrier. The effects of cat astrophic failure of the barrier are unacceptable therefore the pipe whip into the ba rrier is prevented.(3).Pipe rupture restraints provided to limit stress in the Main Feedwater System Break Exclusion Zone. The pipe rupture restra ints 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 3 FWS-PRR10S are on the Main Feedwater Bypass piping. Po stulated break locations are on the Main Feedwater Piping in the Turbine Building and the Main Feedwater Bypass Piping in the Main St eam 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 stre ss reconciliation, the pipe break locations on the Main Feedwater Piping in the Turbine Building are located in accordance with the criteria delineate d in FSAR Secti on 3.6.2.1.2.3.2.b. The latter criteria greatly reduced the number of postu lated pipe breaks and the final postulated breaks, other than the terminal end brea k 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 F eedwater Bypass Piping as this piping was analyzed as part of the Main Feedwater System and resulted in stresses below the threshold stre ss defined in FSAR Section 3.6.2 .1.2.3.b. 3RCS-PRRG 3RCS.SGID 3-RCS-008-34-1 RCS-150-243-1 oJ 1'0 '.9CS -Io'Or

'J'I  BYPASS LINE OFF LOOP STOP VALVE BYPASS 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 INFORMA nON 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 FIGURE 3.6-12 REACTOR COOLANT PRIMARY COOLANT PIPING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FILE: 3612.dgn/3612.clt JANUARY 1998 MPS-3 FSAR 1 of 5 Rev. 16NOTES TO FIGURE 3.6-12 DATA FOR PIPE RUPTURE RESTRAINTS REACTOR COOLANT SYSTEM - PRIMARY COOLANT PIPINGRestraint Identification Break #ElevationDistance from N-S ContainmentDistance from E-W ContainmentRestraint TypeFunction of the Pipe Rupture Restraint3RCS-PRB1A (1)7'-0"32'-11" East 18'-10" SouthLimit Stop None (1)3RCS-PRB2A (1)6'-10" 25'-10" East 30'-0" SouthLimit Stop None (1)3RCS-PRB3A (1)17'-6"13'-11" East 12'-2" SouthLimit Stop None (1)3RCS-PRB4A (1)15'-6" 27'-6" East11'-1" SouthLimit Stop None (1)3RCS-PRR4A 14 27'-8" 19'-9" East 17'-1" SouthLimit Stop(2)3RCS-PRR7A (3)18'-6" 22'-1" East 20'-8" SouthLimit Stop(2)3RCS-PRR8A (3)18'-6" 19'-10" East 15'-9" SouthLimit Stop(2)3RCS-PRR9A (4)31'-6" 20'-1" East 18'-8" SouthLimit Stop(2)3RCS-PRRGA (3)24'-10" 22'-1" East 20'-8" SouthElastic Sway Stru t(2)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" SouthLimit Stop None (1)3RCS-PRB2B (1)6'-10"25'-10" West 30'-0" SouthLimit Stop None (1)3RCS-PRB3B (1)17'-6"13'-11" West 12'-2" SouthLimit Stop None (1)

MPS-3 FSAR NOTES TO FIGURE 3.6-12 CONT'D 2 of 5 Rev. 163RCS-PRB4B (1)15'-6"27'-6" West11'-1" SouthLimit Stop None (1)3RCS-PRR4B 14 27'-8"19'-9" West 17'-1" SouthLimit Stop(2)3RCS-PRR7B (3)18'-6"22'-1" West 20'-8" SouthLimit Stop(2)3RCS-PRR8B (3)18'-6"19'-10"West 15'-9" SouthLimit Stop(2)3RCS-PRR9B (4)31'-6"20'-1" West 18'-8" SouthLimit Stop(2)3RCS-PRRGB (3)24'-10"22'-1" West 20'-8" SouthElastic Sway Stru t(2)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" NorthLimit Stop None (1)3RCS-PRB2C (1)6'-10"25'-10" West30'-0" NorthLimit Stop None (1)3RCS-PRB3C (1)17'-6"13'-11" West12'-2" NorthLimit Stop None (1)3RCS-PRB4C (1)15'-6"27'-6" West11'-1" NorthLimit Stop None (1)3RCS-PRR4C 14 27'-8"19'-9" West17'-1" NorthLimit Stop(2)NOTES TO FIGURE 3.6-12 DATA FOR PIPE RUPTURE RESTRAINTS REACTOR COOLANT SYSTEM - PRIMARY COOLANT PIPINGRestraint Identification Break #ElevationDistance from N-S ContainmentDistance from E-W ContainmentRestraint TypeFunction of the Pipe Rupture Restraint MPS-3 FSAR 3 of 5 Rev. 163RCS-PRR7C (3)18'-6"22'-1" West20'-8" NorthLimit Stop(2)3RCS-PRR8C (3)18'-6"19'-10"West15'-9" NorthLimit Stop(2)3RCS-PRR9C (4)31'-6"20'-1" West18'-8" NorthLimit Stop(2)3RCS-PRRGC (3)24'-10"22'-1" West20'-8" NorthElastic Sway Stru t(2)3RCS-PRRFC 13 31'-6"20'-6" West18'-2" North Shock Suppressor(2)3RCS-PRREC Split 31'-6"20'-6" West18'-2" North Shock Suppressor(2)3RCS-PRRCC Split 31'-6"21'-2" West19'-4" North Shock Suppressor(2)3RCS-PRRBC 13 31'-6"21'-2" West19'-4" North Shock Suppressor(2)3RCS-PRRA1C 14 30'-4"22'-1" West20'-9" North Shock Suppressor(2)3RCS-PRRA2C 14 30'-4"22'-1" West20'-9" North Shock Suppressor(2)3RCS-PRB1D (1)7'-0"32'-11" East 18'-10" NorthLimit Stop None (1)3RCS-PRB2D (1)6'-10" 25'-10" East30'-0" NorthLimit Stop None (1)3RCS-PRB3D (1)17'-6"13'-11" East12'-2" NorthLimit Stop None (1)3RCS-PRB4D (1)15'-6" 27'-6" East11'-1" NorthLimit Stop None (1)3RCS-PRR4D 14 27'-8" 19'-9" East17'-1" NorthLimit Stop(2)3RCS-PRR7D (3)18'-6" 22'-1" East20'-8" NorthLimit Stop(2)3RCS-PRR8D (3)18'-6" 19'-10" East15'-9" NorthLimit Stop(2)3RCS-PRR9D (4)31'-6" 20'-1" East18'-8" NorthLimit Stop(2)NOTES TO FIGURE 3.6-12 DATA FOR PIPE RUPTURE RESTRAINTS REACTOR COOLANT SYSTEM - PRIMARY COOLANT PIPINGRestraint Identification Break #ElevationDistance from N-S ContainmentDistance from E-W ContainmentRestraint TypeFunction of the Pipe Rupture Restraint MPS-3 FSAR 4 of 5 Rev. 163RCS-PRRGD (3)24'-10" 22'-1" East20'-8" NorthElastic Sway Stru t(2)3RCS-PRRFD 13 31'-6" 20'-6" East18'-2" North Shock Suppressor(2)3RCS-PRRED Split 31'-6" 20'-6" East18'-2" North Shock Suppressor(2)3RCS-PRRCD Split 31'-6" 21'-2" East19'-4" North Shock Suppressor(2)3RCS-PRRBD 13 31'-6" 21'-2" East19'-4" North Shock Suppressor(2)3RCS-PRRA1D 14 30'-4" 22'-1" East20'-9" North Shock Suppressor(2)3RCS-PRRA2D 14 30'-4" 22'-1" East20'-9" North Shock Suppressor(2)NOTES TO FIGURE 3.6-12 DATA FOR PIPE RUPTURE RESTRAINTS REACTOR COOLANT SYSTEM - PRIMARY COOLANT PIPINGRestraint Identification Break #ElevationDistance from N-S ContainmentDistance from E-W ContainmentRestraint TypeFunction of the Pipe Rupture Restraint MPS-3 FSAR 5 of 5 Rev. 16 Notes(1).Subsequent to the exemption regarding the need to analyze Large Primary Loop Pipe Ruptures as the St ructural Design Basis f or Millstone 3 from a portion of GDC-4 of Appendix A to 10 CFR Part 50, these pipe r upture restraints are no longer required.(2).The NSSS System Standard De sign Criteria does not permit brea k 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 postula ted 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 Termin al End (TP) postulated breaks at the Reactor Coolant Bypa ss 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. Therefor e, 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 st ate displacement of the shock suppressors. PIPE RUPTURE RESTRAINT S ON RE SIDUAL 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 LOCATION S 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 CLARIT Y.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 ANAL YSIS 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 TWOMEDIATE POINTS BETWEEN THE COLD LEG AND FIRST CHECK VALVE UPSTREAM.FIGURE3.6-13 REACTOR COOLANT SYSTEM-LOW PRESSURE SAFETY INJECTION 6.RESIDUAL HEAT REMOVAL PIPINGMILLSTONENUCLEAR POWER STATIONUNIT3FINALSAFETYANALYSISREPORT C A D FILE: flg 3613.dgn/36 13.clt JANUARY 1998 MPS-3 FSAR 1 of 2 Rev. 16NOTES TO FIGURE 3.6-13 DATA FOR PIPE RUPTURE RESTRAINTS REACTOR COOLANT SYSTEM LOW PRESSURE SA FETY INJECTION, HIGH PRESSURE SAFETY INJECTION, AND RESIDUAL HEAT REMOVAL PIPING Restraint IdentificationBreak #ElevationDistance from N-S ContainmentDistance from E-W ContainmentRestraint TypeFunction of the Pipe Rupture Restra int 3RCS-PRR861 8 10'-3" 25'-1" East 6'-3" SouthLaminated Strap (1)3RHS-PRS1A 9 13'-7" 20'-7" East 4'-6" SouthLimit Stop (1)3RHS-PRS2A 4,5,6, or 7 14'-7" 29'-2" East 4'-6" SouthLaminated Strap (2)3RCS-PRR6A 10 18'-9" 17'-2" East 17'-2" SouthLaminated Strap (3)3SIL-PRR4ATP & Splits 16'-2" 20'-2" East11'-10" South Shock Suppressor (4)3RCS-PRR6B 10 18'-9"17'-2" West 17'-2" SouthLaminated Strap (3)3SIL-PRR4BTP & Splits 16'-2"20'-2" West11'-10" South Shock Suppressor (4)3RCS-PRR6C 10 18'-9"17'-2" West 17'-2" NorthLaminated Strap (3)3SIL-PRR4CTP & Splits 16'-2"20'-2" West11'-10" North Shock Suppressor (4)3RCS-PRR862 8 10'-3" 25'-1" East 6'-3" NorthLaminated Strap (1)3RHS-PRS1D 9 13'-7" 20'-7" East 4'-6" NorthLimit Stop (1)3RHS-PRS2D 4,5,6, or 7 14'-7" 29'-2" East 4'-6" NorthLaminated Strap (2)3RCS-PRR6D 10 18'-9" 17'-2" East 17'-2" NorthLaminated Strap (3)3SIL-PRR4DTP & Splits 16'-2" 20'-2" East11'-10" North Shock Suppressor (4) MPS-3 FSAR NOTES TO FIGURE 3.6-13 CONT'D 2 of 2 Rev. 16 Notes(1).Pipe rupture restraint prevents unrestrained pipe whip into the East-West Cubicle Wa ll. Catastrophic failure of the East-West Wall is credible if s ubjected to unrestrained pipe whip impact by either the Residual Heat Removal Piping or the Low Pressure Sa fety Injection piping to the Hot Leg.(2).Pipe rupture restraint is pr ovided to prevent the Residual Heat Removal line from impacting the Containment Liner. Leak tig ht 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 St andard 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 impa cted, pressure boundary integrity must be assured. The pipe rupture restraint indicat ed 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 require ment is that a Non-LOCA ca nnot propagate into a LOCA. If unrestrained, the broken pi pe would induce significant loading upon the Reactor Coolant System pressure boundary. The pipe rupture restraint is provided to prevent this effect. PRESSURIZER 3 RCS-TKI PR E S S URI Z ER SURGE LINE-SEEN O TE 1 PRESSURIZER 3RCS-TK1 3-RCS*27S-1 0*1 3-RC S-004-22-\PRE S S URI ZER SPR AY LIN ES-SEE NOIE 3 3-RCS-OOG-Ga-. J.ffi U'ENERGYSEEN OTE 2 NOTES I.POSTULATED PIPERUPTUREON3-RCS-OI4-64-1 PRESSURIZER S U R G E LINEARELI S INTABLE 3.6-15 A S BREAKS 67l THROUGH t4I AND (fi)F O P.CLARITY.D UE TO THE QUANTITt'OF BRE AKS.L OCA ncm s Y F O R TERMIN ALENO SARES HOWN_2.POSTULATEDPIPERUPTURE TH EANDR E LIEF LINEPIPING AR E BREAr.S 18 TH ROUGH IN TABLE 3.6-15ONTHE HI GH E NERGY PORTIOfl S A FETYARELIEF PIPING.P IPINGDESIGNATED A S---I S MODERATEENERGY BE YONDTHEVALVES.3.POSTULATED PIPE RUPTURE LOCt<TIONSONTHE PRESSURIZER SPRA Y LINEARE BREAKS (DTHRO UGH@INTABLE 3.6-15.FIGUR E 3_6-14REACTORCOOLANTSYSTEM PRESSUR IZER CUBICLE PIPINGMILLSTONENUCLEAR POWER STATION UNIT 3 FINALSAFETYANALYSISREPORT CAD FI L E: 3614.dgn/3614.clt A P RI L 1998 MPS-3 FSAR 1 of 2 Rev. 16NOTES TO FIGURE 3.6-14 DATA FOR PIPE RUPTURE RESTRAINTS REACTOR COOLANT SYSTEM PRESSURIZER CUBICLE PIPING Restraint IdentificationBreak #ElevationDistance from N-S ContainmentDistance from E-W ContainmentRestraint TypeFunction of the Pipe Rupture Restraint3RCS-PRR1 11 22'-4"15'-7" West 13'-5" SouthLaminated Strap (1)3RCS-PRR3 (2)22'-6"5'-5" West 40'-6" SouthLimit Stop (3)3RCS-PRR4 (2)22'-6"5'-0" West 44'-7" SouthLimit 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" SouthLimit 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" SouthLaminated Strap (4) MPS-3 FSAR NOTES TO FIGURE 3.6-14 CONT'D 2 of 2 Rev. 16 Notes(1).Pipe rupture restraint prevents the Pressurizer Surge Line from im pacting 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 Pres surizer Cubicle Wall if subjected to unres trained pipe whip of the Pressurizer Surge Line would catastrophically fail. As a result, damage to essential systems subse quently to secondary missiles, etc., is cr edible. The pipe rupt ure restraints are pr ovided to prevent the unrestrained impact to these structures.(4).The NSSS System Standard Desi gn Criteria does not permit brea k propagation from the Pressurizer Relief Line (Steam Phase) t o the Pressurizer Spray Li ne (Liquid Phase). The pipe rupture restraint is provided to prevent the interaction. CHA RGING P C)'-t P CU BICLES S E E N OTE2 ro SEA L WATER I NJE CTION FILTER eON T tHUED OH FIGURE3.6*t1 NOTES I.P Q S TU LAT ED B REA K S<D TH ROUG HA ND@THRO UGHAR E O N TH E REACTOR C OOL A N T SYSTEMPO RT IONOFN ORMA L CHARGI NG AND ARE L[S TEOINT ABLE 3.6-l 2.2.PIPEBREAKS INTHECHARGINGPUMPCUBICLESAREPOSTU LATEDATTERM INALENOSAND ATANY VALVE,FITTING , QRINTEGRALATTACHMENT.FIGURE 3.6-\5 CHEMICAL AND VOLUME CONTROL SYSTEM-CHARGING LINE PIPING MILLSTONENUCLEARPOWERSTATION UNIT 3 FINAL SAFETYANALYSISREPORT CAD FILE: 36I5.dgn/3615.cl t JANUARY 1998 MPS-3 FSAR 1 of 1 Rev. 16NOTES TO FIGURE 3.6-15 DATA FOR PIPE RUPTURE RESTRAINTS CHEMICAL VOLUME CONTROL SYSTEM - NORMAL CHARGINGRestraint IdentificationBreak #ElevationDistance from N-S ContainmentDistance from E-W ContainmentRestraint TypeFunction of the Pipe Rupture Restraint3CHS-PRR911 35 13'-2"52'-4" We st69'-7" North Pipe Crush Bumper(1)3CHS-PRR912 35 12'-3"52'-0" West69'-0" North Pipe Crush Bumper(1)3CHS-PRR913 34 12'-6"51'-8" West68'-7" North Solid Bumper(1)Note (1)Pipe rupture restraints were originally specified to limit stress in the co ntainment penetration area and containment isolation valve. However, this break exclusion zone was eliminated based on technical justification provided in calc ulation 97-ENG-1329-M3, since a char ging line break outside contain ment is a non-LOCA break which does not require containment isolation. NOTES 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 OFSEE NOTE 2 CONTAINMENT PENETRATION TO THE OUTBOARD CONTAINMENT ISOLATION VALVE. 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 1 of 1 Rev. 16NOTES TO FIGURE 3.6-16 DATA FOR PIPE RUPTURE RESTRAINTS CHEMICAL VOLUME CONTROL SYSTEM - LETDOWN LINE Restraint IdentificationBreak #ElevationDistance from N-S ContainmentDistance from E-W ContainmentRestraint TypeFunction of the Pipe Rupture Restraint 3CHS-PRR870 (1)(1)The Terminal End (TP) postulated pipe break number 9 is the only break on the Class 2 portion of the Chemical & Volume Contr ol 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 Contr ol System Letdown Line piping. Therefore, break propagation from the Class 2 portion of the Chemical & Volume C ontrol System Letdown Li ne piping to the Class 1 portion (i.e., Propa gating a Non-LOCA into a LOCA) does not occur. 7'-0"17'-0" West36'-6" North Shock Suppressor (2)(2)Pipe rupture restraints 3CHS-PRR870 and 3CHS-PRR858 are provi ded to prevent propagation of a Non-LOCA into a LOCA. The NSSS System Standard Design Criteria does not permit break propaga tion of a Non-LOCA into a LOCA. The pipe ruptur e restraints 3CHS-PRR870 and 3CHS-PRR858 limit disp lacement of the Class 1 piping subsequent to a pipe break on the Class 2 portion of the Chemical & Volume Control System Letdown Line piping. 3CHS-PRR858 (1)5'-2"22'-0" West41'-0" North Shock Suppressor (2)3CHS-PRR967 26 12'-6"60'-2" West75'-3" North Dual FunctionLimits Stress to Pipe Break Exclusion Zone 3CHS-PRR968 (3)(3)Pipe Rupture Restraint 3CHS-PRR968 is provi ded to mitigate the effects of an Arbitrary Intermed iate Break (AIB). USNRC Generic Letter 87-11 eliminates the requirement to evaluate the dynamic effects of AIBs. Therefore, th is pipe rupture restraint has no safety-related function. 20'-2"55'-10" West78'-0" North Dual Function None Notes OtAAClNG CUBICLES S[£NOTE'NOTES1PIPEBREAKSINTHECHARGINGPUMPCUBICLESAREPOSTULATED .ATVALVES.FITTINGS. INTEGRALATTACHMENTS,AND TERMINAL ENOS.FIGURE3.6-17 CHEMICAL AND VOLUME CONTROL SYSTEM-SEAL WATER INJECTION PIPING MILLSTONE NUCLEAR POWER STATIONUNIT3 FINALSAFETYANALYSISREPORTCADFILE: fi<;l361 7/fig3617.ci t JAN UARY 1'3'38 JANUARY 1998 T ll),J[TO SGl.I0 04-7 6-2 FIGURE 3.6-18 STEAM GENERATOR SLOWDOWN SYSTEMMILLSTONENUCLEAR POWER STATION UNIT3 FIN ALSAFETYA NALYSIS REPORT C AD FI LE: 36t8.<lQ n/3 6 1 8.c l t%__A\" N OT ES 1.BRE AK L OCAT IONSARETYP ICALFORALL LOOP S OUTS IDECON TAINMENT.2.---DENOTESACOMBINATIONPIPESUPPOR TIP IPE RUPTURERESTRA INT.3.STEAII CENERATOR llUllII10IIN LINE PIPINC llErllE£N TIE: '1ll0lf1l0llll TAJ<<eeoe-nn&NOE..eH.lIIClQl I S 101 NUCLEAR._SEISMIC.BREAkS IJl[POSlULol TEO IN olCCIlROAHCE WITH TIE: CRITERIA IH SEcn()l &ND"J!E A T"lL FIT TINGS, V"lVES.&HI)waDEl>"UolCIAE.NTS. 4..APIPE llR£AK EXCWSI()I ZONE IS OESIGmTED FOl T HE$TEAu GOERA TIJl 1ll01lD0'lN lllE.TlE: OREAl EX ClUSIlJl ZONE EXTEHOS nlOU T HE OUTBOARll ClJITAI NIIDI T P£NETIlATllJl TO THE OUTl\OARO ClJITA llAlENT ISOU n()l VA L VE.TIE: EXTENT Of TI£BREAk EXClUS!lJI lONEIST'lPICAl FOR"ll1IHEs.TlE: BREAk EXCLUSllJl llH: CRITERIA IS 0EF11*O Dl SECTllJl 3.6.2.1.2.2.5.T£JlI.IDl"l Del AS OESCIlIllEl) IN NOTE 3 Of TollllE3.6-30.-----_._-----------------------------------------_._----------------_._----------------------------- MPS-3 FSAR 1 of 2 Rev. 16NOTES TO FIGURE 3.6-18 DATA FOR PIPE RUPTURE RESTRAINTS STEAM GENERATOR BLOWDOWN SYSTEM Restraint IdentificationBreak #ElevationDistance from N-S ContainmentDistance from E-W ContainmentRestraint TypeFunction of the Pipe Rupture Restraint 3BDG-PRR972A 2 22'-2" 37'-6" East 8'-10" SouthLaminated StrapPrevent impact to Steam Generator Shell 3BDG-PRR975A 1 21'-1" 37'-6" East 7'-4" South Pipe Crush BumperPrevent impact to Steam Generator Shell 3BDG-PRR885 29 20'-6"76'-3" West10'-1" North Dual FunctionLimits Stress to the Break Exclusion Zone 3BDG-PRR886 5 20'-0"77'-3" West7'-2" North Shock SuppressorLimits Stress to the Break Exclusion Zone 3BDG-PRR941 6 20'-0"77'-4" West6'-9" North Shock SuppressorLimits Stress to the Break Exclusion Zone 3BDG-PRR948 7 19'-6"76'-2" West10'-7" North Solid BumperLimits Stress to the Break Exclusion Zone 3BDG-PRR972B (1)22'-2"39'-1" West11'-7" SouthLaminated StrapPrevent impact to Steam Generator Shell 3BDG-PRR975B 8 & 9 21'-1"39'-9" West 9'-5" South Pipe Crush BumperPrevent impact to Steam Generator Shell 3BDG-PRR973 10 20'-6"59'-9" West5'-4" North Dual Function Prevent impact to Containment Liner 3BDG-PRR887 30 20'-6"75'-6" West6'-9" North Dual FunctionLimits Stress to the Break Exclusion Zone 3BDG-PRR888 12 20'-0"76'-5" West3'-4" North Shock SuppressorLimits Stress to the Break Exclusion Zone 3BDG-PRR942 13 20'-0"76'-5" West2'-11" North Shock SuppressorLimits Stress to the Break Exclusion Zone 3BDG-PRR946 12,13, or 14 21'-7"76'-4" West5'-0" North Dual FunctionLimits Stress to the Isolation Valve Stem 3BDG-PRR950 14 19'-6"74'-11" West10'-6" North Solid BumperLimits Stress to the Break Exclusion Zone 3BDG-PRR972C 17 22'-2"37'-5" West8'-10" NorthLaminated StrapPrevent impact to Steam Generator Shell 3BDG-PRR975C 15 & 16 21'-1"37'-11" West7'-3" North Pipe Crush BumperPrevent impact to Steam Generator Shell 3BDG-PRR970 51 20'-6"52'-1" West10'-7" NorthLaminated StrapPrevent impact to Steam Generator Supports 3BDG-PRR971 (1)21'-1"45'-0" West4'-9" North Pipe Crush BumperPrevent impact to Steam Generator Supports 3BDG-PRR884 31 20'-6"74'-11" West17'-8" North Dual FunctionLimits Stress to the Break Exclusion Zone MPS-3 FSAR 2 of 2 Rev. 16 3BDG-PRR883 19 20'-0"74'-9" West20'-8" North Shock SuppressorLimits Stress to the Break Exclusion Zone 3BDG-PRR943 20 20'-0"74'-8" West21'-2" North Shock SuppressorLimits Stress to the Break Exclusion Zone 3BDG-PRR947 21 19'-6"74'-11" West12'-2" North Solid BumperLimits Stress to the Break Exclusion Zone 3BDG-PRR972D (1)22'-2" 39'-1" East11'-7" NorthLaminated StrapPrevent impact to Steam Generator Shell 3BDG-PRR975D 22 21'-1" 39'-7" East9'-5" North Pipe Crush BumperPrevent impact to Steam Generator Shell 3BDG-PRR974 25 20'-6"58'-10" West16'-7" NorthLaminated Strap Prevent impact to Containment Liner 3BDG-PRR882 32 20'-6"72'-11" West20'-7" North Dual FunctionLimits Stress to the Break Exclusion Zone 3BDG-PRR881 26 20'-0"72'-9" West23'-9" North Shock SuppressorLimits Stress to the Break Exclusion Zone 3BDG-PRR944 27 20'-0"72'-8" West24'-3" North Shock SuppressorLimits Stress to the Break Exclusion Zone 3BDG-PRR945 26,27,or 28 21'-7"73'-1" West22'-7" North Dual FunctionLimits Stress to the Isolation Valve Stem 3BDG-PRR949 28 19'-6"73'-9" West11'-10" North Solid BumperLimits 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.NOTES TO FIGURE 3.6-18 DATA FOR PIPE RUPTURE RESTRAINTS STEAM GENERATOR BLOWDOWN SYSTEM Restraint IdentificationBreak #ElevationDistance from N-S ContainmentDistance from E-W ContainmentRestraint TypeFunction of the Pipe Rupture Restraint SLOWDOWN 1------------ THRUST DEVELOPMENT )0PIPEWHIP ,.PIPE DYNAMICS**PIPE-RESTRAINT INTERACTION (SOFT-SOFT),rPIPE-CONCRETEWALLIMPACT '------------ INTERACTION FORCE, INERTIAL LOADS (SOFT-HARD)" LOCAL EFFECTS 1--------------- PENETRATION SPALL LOCAL WALL RESPONSE STRUCTURAL ADEQUACY LOCAL>-,MPACT ,., , STRUCTURAL RESPONSE----------------------RESPONSEAND INTERACTION STRUCTURAL ADEQUACY FULL)0 STRUCTURE 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..Po -F(/) 1.26 0::: t- o STATE o SLOWDOWN >-<, o <t W '<;(/)0.4 o 0.05 0.1 0.5 1.0 5.0 10.0 50.0 100.0 FRICTION FIGURE 3.6-20 VARIAT ION OF STEADY STATE STEAM SLOWDOWN V5. FR I CT ION MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

" : 1.-' : . :.CONCRETE WALL '\). " '. ,,' V": "J <{ * >.,'.' , . -l>.. '£:I. ... .. .' . . '. : _",'0." . , " -,.'@ A'. , ' r/ . \:-.'" , , ./>. u C1l , .' ro , VI ...4. 0 ,','. Y". '. . '. '. )(c: -LiJ ..' >.. b. <, ,.-MODELED AS A SIMPLE :.' \;>' ',.', -: 'V '.SUPPORT IN THE DYNAMIC ..", ".. '.ANALYSIS ----(\J INTERMEDIATE STRUCTURE 1'-1 c: (\J CO.o INTERNAL PRESSURE FOR CE DISTRI BUTED ALONG THE FIGURE 3.6-21 PIPE, RESTRAINT, INTERM EDIATE STRUCTURE SYSTEM MATHEMATICAL MODEL STEAM GENERATOR

'....: 
.... .: ATTACHED TO THE MILLSTONE NUCLEAR POWER STATION UNIT 3 oo{. " ,-. FINAL SAFETY ANALYSIS REPORT LAMINATED MIN'K INSULATION OR EQUIVALENT STRIP PI PE c.--:=-:L=---LUG CLEVIS RETAINER RING I PIN I I BUSHING I I L -1 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. m --l I sr -20.0 *(J) Z 0 -40. 0 << w 0:: f-W -60. Z -80. -100. -120. __ __---J__J_

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. ,..------------------------------, 30. 10. I LCl -10.0 (J) *Z 0 -30. <.) << w 0:: W z -70. -90. -110. "'-__----" ----L.. --'---'--...I..-'---__---' 0.04 0.08 o.12 0 .1 GO.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 *lJJ (J 0: 80 0 u, 60 40 20 o L..-..__----J'---__-.l ---l. ---L --L ....J 0.04 0.06 0.08 0.10 0.12 0.14 TI ME 10-1 FIGURE 3.6-26 FORCE ACTING ON THE STRAP DOTTED LINES INDICATE THE LOAD PATH NODE 8 MI LLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT 640. r------------------------------. 560. 480. <;t 4uO.o .--.-. r-.

cD .....J I Z 320. Z 160. 80.

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.' .'<1. ---------Lh------*I * <l I I r,' . '<\ I , ..

LOCATION I , t-'. "1'<1' , ,.4 . *<; * :... PIPE CRUSH R SHIMS :.:.:.' .4,': \;!:

.,. **.*4* , t;, . . ' ; " :U*:. ' :-:. 4: *II '.' .: 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 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 IMPACTEDCRUSHPIPE BEARI NG PLATE<t.THRU BOLT PIPE CRUSH BUMPER--i+--RECTANGULAR WASHER END VIEWOFPIPE FIGURE 3.6-30 PIPE CRUSH BUMPER MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT GAP ARCH PIPE RUPTURE RESTRAINT BODY P 3 SHIMS SHEAR (TYP) BLOCK DEAD WEIGHT SUPPORT SLEEVE (2-PER SIDE) I II I II I II I II l f-----, JAM NUT NUT STUD (2-PER SIDE) A HONEYCOMB PANEL RESTRAINT ATTACHMENT PANEL SECTION A-A FIGURE 3.6-31 OMNI-DIRECTIONAL PIPE RUPTURE RESTRAINT MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT MP3-UCR-2013-Q03 MMPS-3 FSAR Updated Figure FIGURE 3.6-32 AUXILIARY FEEDWATER SYSTEM c....O FILE;m33632.dgn/m33632.c:i-t NOTES';.

OOTTEll}DENOTES A MODERATE 2. 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 AND BREAK.JANUARY 2013 --*' ..:* .--_ ..

-:1>; :.' I 3-RCS-002-24;7-1

.>>: REACTOR _ STEAM COOLANT) GENERATOR I PUMP I I 3RCS.SOID 3RCS*PIO COOLANT PUMP I-t-J,; 1\ 3'RCS-031-13-1 --\ SEE OETAIL '0' DETAIL' '0' T '_3-CHS'002-240-2 r3-RCS-002-174-1 L--4 DETAIL 'c' NOTES: PIPING SHOWN---DENOTES A MODERATE ENERGY POSTULATED PIPE RUPTURE LOCATIONS AND THE GEOMETRY TYPICAL FOR THE REACTOR COOLANT SYSTEM PRIMARY PIPING DRAIN LINES <INCLUDING EXCESS LETDOWN) IN EACH GENERATOR CUBICLE. PIPE RUPTURE LOCA nONS ON THIS ARE POSTULATED AT ALL TERMINAL ENDS. VALVES AND 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* PIPE RUPTURE LOCATIONS ON THIS PIPING ARE POSTULATED TO OCCUR AT ANY TERMINAL END VALVE OR FITTING. INTEGRAL WELDED ATTACHMENTS ARE NOT UTILIZED ON THIS PIPING SYSTEM. THE LOOP FILL LINE GEOMETRY IS SHOWN AS DETAIL C AND D. 4.REFER TO FIGURE 3.6-15 FOR PIPE RUPTURE LOCATIONS NORMAL CHARGING LINE PIPING WITHIN RCS 5.REFER TO FIGURE 3.G-16 FOR PIPE RUPTURE LOCA nONS LETDOWN LINE PIPING WITHIN RCS FIGURE 3.6-33 REACTOR COOLANT SYSTEM SMALL BORE PIPING IN STEAM GENERATOR CUBICLES MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FILE: 3633.dgn/3633.cit JANUARY o RIBBED FIBERGLASS PROTECTION BOt..RD RING GIRDER {SEE FIG.3.8.1-Z31.*,.DETAIL A 2" COMPRESS IBLE MA TERIAL------::::::-(BOTH SIDES OF (MEMBRANE) WATERPRoOFING MEMBRANE CONTAINMENT DETAIL AZ"CONCRETESEAL (ABOVE AND BELOW MEMBRANE)TOPOF 4"-#4 CRUSHED STONE CONTAINMENT STRUCTURE FOUNDATION MAT a j i a>, I\I LEVELING CONCRETE ADJACENT BUI LDINGRINGGIRDER --__H-:---FACE OF ROCK EXCAVATION

CONCRETE BL OCt<

MEMBRANE 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

BEND LINEDIAGONAL BARS It.LINER FIGURE 3.8-2 TYPICAL DETAIL OF DOME CYLINDER JUNCTION MILLSTONE NUCLEAR POWER STATION UNIT:3 FINAL SAFETY ANALYSIS REPORT !" STEELMATLINER rTO?OF CONCRETE MAT (J\>DETAIL BRIDGING PLA TE Ft CONCRETE SCALE: NONE REBAR ANCHORS DETAIL KNUCKLE PLATE OF ,/CONCRETE FILL<',..:=.':..'.,.NO.10DOWEL 72-72 (C-8)SCALE:3":/'-O" 1----KNUCKLE PLATE--EL.(-)23'-11 3/4" 1/4"-6000LB.HALF COUPLlNG,(DET HA B-1)-EL.{-)24'*2 3/4" I: 1:1 TEST MEMBER AT I I-KNUCKLE PLATE: JOINT FULL PENETRATION WELD (TVP)TOPOFMAT EL.(-)27'-3" 3/8" LINER-----o-{I--- 1/4" LINER-----'REF.R.:70'-O"-----1 EL.(-)24'-6"- TYP SECTION KNUCKLE PLATE SCALE!)1/4':1'-0" FIGURE 3.8-3KNUCKLEPLATE MILLSTONENUCLEARPOWER STATION UNIT:3 FINAL SAFETYANALYSISREPORT CAD FILE: 383.dgn/383.cit NOVEMBER 1997

FLAT BAR (TYP.) 2'-2" 5 SPCS. AT 3'-0" 58'-0" RADIUS SHEAR BAR UNDER RADIAL SHOWING SHEAR BARS (A DO' L. BARS E. SEE SECT. 2-2, SCALE: 1/8": 4'-6" 4'-6" 70'-0" RADIUS 4 C 5"CL. NO. 18 DIAG. BARS FLAT BARS BRIDGING TOP OF MAT EL(-)27'-3" -.. .. <tNO 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 14'-0" EXTRA HORIZ. BARS 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" SHEAR ASSEMBLY

1If---Hi8=--I!/,Y'

/.JIII 6-6 (E-I) MAIN STEAM PENETRATION 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 CL MAIN STM PENS EL.66'-3"J I J(C-4) 7'-30" FIGURE 3.8-5 REINF. AROUND MAIN STEAM PENETRATIONS MILLSTONE NUCLEAR POWER STATION UN-IT 3 FINAL SAFETY ANALYSIS REPORT NF E 2-2 (E C-49L,H-5)(1103 l)No1 8 CIRC BARS r-EXTRADIAG e.VERTREI N o ,ll S Ti R RUPS-FUEL TRANSFERTUB.'\1 TYPREINF: r-:'1(:>o'0 0 o I'"'"""'" (.l'".', , TYP, DIAG R EINF,'.....v-."",'\:J)CD IL'-'IlL'{,.,r.oP.0 p f:J<:J (;.J e 0""'*10 I)i Cl**0I'"'"'"'"'" 11'\ CD e=J°CD."..'...,..--...00 e00 0 0'.: ';, 0 1 0 0 o-r o e e c<:J S Jl", 1'1 I",'" I'l ,'""'), t: I00: '0 ITYPVERTREIN F--!.-No,6STIRRUPS 0 ,..H*6'-6 f..'-No , 18 EXTRAOIAGRE 1NF 7'-0" O I A I PERSHATe-l No ,18 EXTRAV ER T REIN F N o , l1'Q)1 2" RADIAL STIRRUPS I N GROU PS OF:3 No.6'ci)12" TRANSVERSE STI RRUP INGR OUPS O F 3 YPVERTREINF ,TYPDIAG R EIN F 14 EXTRADIAG RE1NF YP HORIZ RE I NF 70-0 R 4-6'1,*-,***LINER 1'-3" Ay tjO""O TRADlAGR E I NFIIII NQ.1 8 TPVERTR EINF-f-8 No ,18 HORIZ REINF E.-l-e.NoAHORIZREINFNo.18 T I 6U 6 ,IB:.8 Jo,',-c..gE r.-, r.8-...I'oe h G N (J)a:[0<::G IWo"e p G I<l: CD o l:>E: 8E: p E!,;U 11'1 I'h r-: h o!!!l" O nO 0 z 0 ep Gp 0:*-<:: '(!):>El'm t::-..A;: ,'1*r.:.....:.'.1'-4 i" L N: '6'XTr H O RtZ iEINF*1'-7 1 11'-0" 1'-a"4 8 I I I No ,18 EX No ,IS TY N o.ISTYP No ,14 EXTR 1-1 (EC-49L,E-2)(11031)SCALE 3/11"=1'-0"FIGURE3.8-6 REINFORCING DETAILSSECTIONSTHROUGH RING BEAMOFPERSONNELACCESSLOCK MILLSTONEN UC LEAR POWER STATION U NIT 3 F INAL SA FETY ANALYSIS REPORT REF: EC 49M-3 t. CADWELD FOR

18 VERT BARS (MK-I) AT PERSONNEL, HATCH ONLY

/ CADWELD ""'.1 V,," #18 VERT (MK-t) AT HATCH 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" , 4 2 ' _ 6 -i" 2'-0" J XTRA DIAG. 1 REINF. I TYP. VERT. REINE --to I ERT REINF. I YP. HORIZ. REINF Eo _ TRA HORIZ. REINE ....

#18E #IS t. #14 V #IS T 1114EX     .

6 ..* ERT. REINF. lAG. REINE r. A DIAG. REINF. HORIZ. REINF. I #18 TYP. V I '18 TYP. D #14EXTR I #18 TYP. I

'"  18 CIRC BARS -#11 STIRRUPS Vl il;L" " ( e 8' /:i> "  pc E c (J fJ 0,,0 a oRo  p Ie  #14 <Cl 12" RADIAL STIRRUPS IN GROUPS OF 3 E ( #IS EXTRA VERT. REINF. , en I -... 0:: <t III U 0:: u CD  -f' p p p < e " .oE E G 18 U 80 0 e o < c Q 8 1Jl ° °  U 080 o G c 'o . '" W o 0 o c G  '" -#6 <Cl12" TRANSVERSE STIRRUPS IN GROUPS OF 3  "',.",   'nlB,CD '" E 'P.; :.":... .0:' h.>. s a *0 on r -l1r  '--4"j 
,"I-OJ 2 4

1" 1 -11. 15'-0" DIA I HATCH .... 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 I CAL QUADRANT REF.: EC 496 FIGURE 3.8-9 REINFORCING DETAILS EQUIPMENT ACCESS HATCH OPENING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT 35'*0" LIMIT OF BARS-b 17'-6"UMITSOFBARS-c<l CONTA INMENT STRUCTURE (SYMMETR ICAL)LI MITOFBARS-d CON T ENC L.SPT.(TYP)PLAN B (J-5)PLAN A(H-4)4'-0"LIMITOF BARS-e 2'-5" LIM ITOFBARS-a TEMP DOME VENT DET-A (J-3)L-5)iCOL., 5" 2-5-l 8 a.:\()'-I<r CO(/)I I (\J='d.....-----I------i f-4"-a n.--rEO.Sf?-j-\()--I'" 2(I C\J".-I-'---I" 1'_lt ," 4 2 8 14 2 f-, rCf.cO L.PLANA (F-2)PEDESTAL TYPE-)6 REQUIRED w Z...J..J o C1'l U y1-+---++-PLAN 8 (E-2.)PED ESTAL TYPE-212REQU IRED FIGURE 3.8-10 BASE PLATE DETAILSCONTAINMENTENCLOSURESTRUCTURE 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 U BAR Eo ANCHOR (A-9, (EC-49P, F-2)( 11 1/4" =FULL PENETRATION f CONTAINMENT STRUCTURE WELD BARS-a TO RING It (TYP) 4'-61.0.

RING It 24" 'I. 2" TH (ASTM A588) NO 18 (TYP) It LINER DET B 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 IS REPORT 5-1 .. 16.. 3-8" CRANE WALLTOP OF CONC EL.l05'7"<,-. <,<, .......,I...... REFERENCE____ N E;__>>;:.'f'. .,',',.li. RAIL £. WHEELS KEY PLAN I DOME MAINTENANCE TRUSS PARKED POSITION FIGURE 3.8-12 ELEVATION DOME MAINTENANCE TRUSS MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT 70'-O"RAD. REF. ---II TY P TEST CONN DET MA(EV-IH,B-II) (22008) EL.H27'-2

r T EST MEMBER I AT KNUCKLE -CONC. PLATE 6"RING I n I----Ji 69'-11!i 70'-2/i" 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

FUEL BUILDING STRUCTURE WALL TRANSFER TUBE WITH END PLATES [, BLIND FLANGE VALVE .: '" JOINT TUBE PLAN-FUEL TRANSFER PENETRATION ."'!.... 'c:I' . .: :., . ,': :=,-... . .:.,9... EQUI-SPACED LUGS (ONE LUG , -'t'. ON HORIZONTAL iLl L 4' 6" COLD PIPE AREA OF ANALYSIS(l} AREA OF ANALYSI S (2).. RING (REF TABLE 3.B-2) IREF. TABLE 3.B-2)LINER TEST HOLES (PLUGGED) PIPE FLUED HEAD PENETRAIT SLEEVE-INSU LATION HEAT EXCHANGER INNER UNIT ---------£OF PIPE INNER UNIT HOT PIPE ( FIGURE 3.8 -15 TYPICAL PIPING PENETRATIONS MILLSTONE NUCLEAR POWER STATION UN IT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 15 SEPTEMBER 1985 I 1 2 2 I RET URN TUBE INSULATION COOLER SUPPLY(SH9.WN OUT OF 3SIDES POSITION) TUBE 1/2 'O.D x.095" J\.--r LINER COOLER COOLER FIGURE 3.8-16 TYPICAL SLEEVED PIPING PENETRATION MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 15 SEPTEMBER 1985 1 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 I REF 12" SCHED 80 SEAMLESS PIPE SLEEVE 5'-11" L 3x3x 3/16x 3"L I DET MC(EV-1M B-5) (22012) 7" PLAN 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 'l 2'-0" "' ..".

.*A, * .. lito . 4' 0' COMPRESSIBLE" .i MATERIAL ;:;. n  21'-0" REF. SS STIFFENER PL.

...!..."x ,..!.."2 2 3 REOUIRED 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" 15'-0" 2 1-4 11 PARTING INSIDE CONTAINMENT oHINGE __'---*Iii+l1 0 --_I r-FLOOR

-:;-,: ... " .....: ,'

INSIDE CONTAINMENTLINER 142-142 LINER t LH HINGED LOCK RH HINGED ACCESS LOCK COVER ct PERSONNEL ACCESS LOCK ESCAPE HATCH KEY PLAN DOORS ONE AT NTS EACH END 3'-6" REF AUXILIARY BUILDING r---FLOOR EL.24'-6" FLOO R -;. .. :i: ::":'" *.: EL. 25'-3'; .-: r.:.... I 142(H-5) TEMPORARY CONCRETE ACCESS HOLES TO BE SEALED VIEW PORT BOTH DOORS -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

_._---E L.5B'-Z" TEMPORARY CONCRETE ACCESS HOLES TO BE SEll LED A-A (O-7)*I" 9 09.I Sll18-llji MIN.-.I I t-+, ,1 11+---L J r!,--f*"""""---ARC LENGTH/-AT 70"0" RAD9"9!:'I 4 HATCH COVER IN STORAGE POSITION 1'-6" ESCAPE IIATCH(TOBEOPENEDfROMEITHER SIDEI---"'.c-I-

'--.J G<CONTAINMENTSTRUCTURE A"+t-_.....::::-?V".--.::::--I-!- ci s'CD SI0..I"'b-0'r;;9 I o ,B-B (C-5)EL51'-4" 70'-O"RADTO It REACTOR TYP)S"V i*3" 65-B.RAD ToIL REACTOR 66'-0" RAD.DOUBLEGASKET-----....BOLTED HATCH COVER UNBOLT FROM INSIDE TO OPEN'"MIN,OF EQUIPMENT HATCHEL58'-_2'_' MONORAIL SUPPORT BRACKET(4REQUIRED) MANUALLY OPERATEDTROLLEYHOIST 12 REQUIRED)CONTAINMENT LINER (EV-IA)(22001)Ii.CONTAINMENT STRUCTURE KEY PLANFIGURE3 ,8-22 EQUIPMENT HATCH MILLSTONE NUCLEARPOWERSTATIONUNIT3 FINAL SAFETY ANALYSIS REPORT CADFILE: 3822.dg n/3822.clt NovEMBER1 997 TOP OF RING GIRDER EL.S'-IO"

....: . EXIST. ROCK EL. 9' -0":  R: 14' -6" TYP. (CONTMT NO. II --+--+--1---1 JI.----t---STRUCT. E xr. WALL) 4 11-#4 CRUSHED STONE 2" SEAL COAT (above crushed stone) II----r----

WATERPROOFING 1-+---++-++----+--- R =79'-6"(ROCK EXCAV) TOP OF MATEL.{-)27'- 3" I-I (EC-49X, E-5)( 11072) 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

. ..  .' ....  : :.'0.': FACE OF ROCK EXCAVATION-*..
... RING GIRDER

.. WATERPROOFING MEMBRANE ---+..,.----+--11

- - - C) * .'. 2" SEAL COAT (above and below membrane)

,. *0 :.'.. -. ---+------ DETAIL A 4"-# 4 CRUSHED STONE CONCRETE BLCCK-----+i CONTAINMENT STRUCTURE FOUNDATION POROUS MATLEVELING 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 LaC.OFESFBLDG.WALLS&RADIAL WALLSSEEEC-23A (11213)E 180" TOP EL4'-0"(EC-49Y,B-5) (11073)0 0 360" W PLAN fci)EL (-) SCALE: 1/32=It_a"FIGURE3.8-24 (IOF'3)DETAILOFRINGGIRDERAT ESF BUILDING MILLSTONENUCLEARPOWER STATIONUNIT3 FINAL SAFETY ANALYSIS REPORT ,: c...<"ESFBUILDING 'CONTMT STRU CT EXT WALL---J EL 4'-6" It I,-T OPOFRINGGIRDER I s--.-EL 3-14"R INGGIR DE R-t----tt_t__' -.-.-.---Y-3'-0" 3rEL r-: 1 2'-6" 1+----1----'--'- LTOPOFRA DIAL WALL EL 1'-0"<--RA DIAL WALL 8 DOWELS I C ONTMT STRUCT EXT WALL-4" COMPRES SIBLE-+-------: ....I MATERIAL EXTRAHORIZ (4" LAYER)..': I'--*;:;.>.v:II!!.....---Ht--+-*1 MATERIAL-.-.--.-4-"+-+-11 EXT RA H ORIZ (4" LAYER)J---Ht---t-- 1 1-.+f----+RIN G GIRDER 7 9'-d'R tTARPAP ER S LIP SURFACE (2 L AYERS)j'0-0"'p'd.:'0:--o51 0 I I I SCALE FEET--f--TARPAPERSLIP(2 LAYERS)L BOT OFRINGGIR DER EL H 26'-3":::.: q.4-4rESFBLDGMAT.",.,'3-3 FIGURE 3.8-24 (2 OF 3)DETAILOFRINGGIRDERAT ESF BUILDING MILLSTONENUCLEARPOWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT RIBBEDFI BERGLASS CONCRETE FILL DETAIL A P IECE OF 9 WATERSTOP (FROMTOPOFCONTMT STRUC T MAT)(SPLICEWATERPROOF MEMBRANE T O WATERSTOP) o12 345IIIIII SCALE FEET RINGG IRDER WATERPR OOF MEMBRANE CONTMT STRU CT 6" WA TERSTOP FROMT OPOFCONTMTSTRUCTMATTOT OPOFRINGGIRDER AMENDMENT 15 SEPTEMBER 1985 5-5 (A-7)WATERSTOPINTOPOF EXIST CONTMTSTRUCTMAT (SEE NOTE EC-49Y, H-B)(11073)BOTOFBEAM EL(-)rTOPOFMAT EL(-)27'-3" TARPAPER-':i\LTARPAPER JT WATERPROOF MEMBRANESPLlCE.DTO WATERSTOP-----J PROTECTION BOARD* BLDG WALLTOPOFRING .... .......:<,I'I*.6 11 WATERSTOP(WIDTHOFRING GIRDER)PIECEOF 9"WATERSTOPFOR WATERPROOF MEMBRANEATTOPOFI 1---1-WATERSTOPATOUTSIDERINGGIRDERFACEOF CONTMT I STRUCT WALL (EC-749B)(1l516)PIECEOFWATERSTOPINSIDEFACE OF-IRINGGIRDERFOR SPLICING WATERPROOF I MEMBRANE I o I 123III 4 I SCALE FEET FIGURE 3.8-24 (3 OF 3)DETAILOFRINGGIRDERAT ESF BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT WAl 1786.97 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/FT)300MATWAl I 1 0 20 30 40 SO 60 70 I 10 20 30 4-0 50 60 70!I (RADIUS[FTI RADIUS CFT)t MAl 359.90 t MAT/STRUCrURE MAT INTERACTION 300 Z.2 I FT-K/fT)S...1209.7150 0.3 (K/FT)0." 152.2---..-.-.1 190.S 10U1 r 111.0 (K/FT)(IUFT)IKIFT 0 to-Z UJ 2 a:: to-Z 0 a: 150.....0 uJ et U e,'Z--l to-<<--l 2: uJ::J a::: et 0 a:: (I)u*u 300 TANGENTIAL MOMENT C K-FT/FT)LOADING DL+1.OP+l.OC T+TL)FIGURE3.8-25 CONTAINMENT STRUCTURE MAT MOMENT AND SHEAR DIAGRAMS MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL S"AFETY ANALYSIS REPORT t WAT 2151.80 300 WAT 2000 1500 1000 ISO SOO 0 0 500 1000 ISO 1500 2000 RADIAL IK-FT/FTl 300 SHEAR I K/F T1 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 I US 1FT 1 I RAD I US (F T) t WAT ....9.05 t WAT MAT/STRUCTURE INTERACTION 300 10.5 , (FT-K/FT I 5.0 1 0 I K/FT I 0.3--.. 177 .2 --.. 150 1"'" (I(lF T I IOU 1 (I(lFT I 1( K/FT 0 Z UJ 2 150 ex: 0 I-ex: 0 UJ Z -0< U Z -' 0< UJ a:: e, ::t CI) 0< a:: u -' 0<* Z 0 u 300 TANGENTIAL MOMENT IK-FT/FTl FIGURE 3.8-26 CONTAINMENT STRUCTURE MAT LOADING MOMENT AND SHEAR DIAGRAMS MILLSTONE NUCLEAR POWER STATION DL+l.25P+l.01 T+TL 1 UNIT 3 FINAL SAFETY ANALYSIS REPORT MAT

.500 t MAT 150 1000 sao o sao 1000 150 1500 2500 2000 RADIAL MOMENT (K-FT/FTl

.500 SHEAR ( K/F T l MAT MAT 10 20 30 40 50 60 70 10 20 30 40 50 60 70 RADIUS (FTl I RADIUSIFTl MAT 537.05 i MAT MAT/STRUCTURE INTERACTION 23.6 IFT-IUFT) 1587.0 150 2.9190 . 5 I K/FT I I KIF T I 0.3>DU l I KIF T I 20 1. 2 '" I KIP l I-z uJ 150 :IE Z uJ Z ....J ....J Z }OO a:: L> 0 L> 450 TANGENTIAL MOMENT 1i<-FT/FTl FIGURE 3.8-27 LOADING CONTAINMENT STRUCTURE MAT 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 IK-FT/FT) 500 SHEAR I K/F T) t NAT t NAT I 10 I 20 I 30 40 , I RAD I US 50 , 1FT) 60 I 70 I I 10 , 20 I 30 40 I , RAD I US 50 I 1FT l 60 I 70 I t NAT 2115.82 t NAT MAT/STRUCTURE INTERACTION 6.11 IFT-K/FTI J.S lI33. a ISO 0.81 ,0*.' IIt1FT I I KIF T I 117.6O. I --. --.I.Uj r""I kIF 1 I I Kif 1 a .... z I.IJ :II a:: e .... a:: z -.... U e I.IJ Z ...J <.... I SO < I.IJ II: e; = en < II: U -l <* Z 0 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 750 i WAT 500 WAT 600 450 500 ISO ISO 0 o I SO 300 4S0 ISO 600 7S0 RADIAL MOMENT (K-FT/FTI 786.59 500 SHEAR ( K/F TI 20 RADIUS 30 40 IFTI 50 60 70 { I WAT 10 20 30 40 50 I I (FTI 60 70 I 450 500 { 11,0 I k/FT 1 WAT MAT/STRUCTURE INTERACTION 5.0 IFTK/FTl 1.3 94.9 !90.S 20 1. 0 1 SO 104.51 I KIFT I (ICIFT I I KIF T 1 1 o 'Z W 2 ISO IX: t-'Z 0 IX: t-O w u a-'Z* ...J .... a-.... ...J W ::::l IX: .... 500 IX: CI) U 450 TANGENTIAL MOMENT [K-FT/FT I FIGURE 3.8-29 CONTAINMENT STRUCTURE MAT MOMENT AND SHEAR DIAGRAMS LOADING MILLSTONE NUCLEAR POWER STATION OPERATING VACUUM UNIT 3 FINAL SAFETY ANALYSIS REPORT 150 .....T ISO "AT 100 50 o o 50 100 150 RADIAL MOMENT IK-FT/FTI 153.40 "AT 10 I 20 I 30 40 50 , I I RADIUS 1FT) 60 I 70 I "AT 50 II. I 14.8 II(/S'I FT j 16.2 18.5 17.0 (9.5 0 50 a:: c... to) oe .... a:: ... a:: C Q.. Q.. III .... Z -e a:: to) ...J ...J oe* ... Z .... 2 z-oe... Z c to) TANGENTIAL MOMENT IK-FT/FTI 75.90 LOADING 1.25(!SSE) FIGURE 3. 8 - 30 CONTAINMENT STRUCTURE MAT MOMENT AND SHEAR DIAGRAMS MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT . { MAT ISO MAT ISO 100 50 o o 50 150 100 RADIAL MOMENT (K-FT1FT) 44.20 { MAT I I,' 20 I 30 40 SO , l , RADIUS (FT) 60

70 I { MAT 100 50 o 50 23.6 la.,/ *
CIl: 10 CIl: 10 U 0.. < 0.. uJ ::) CIl: en I k/SQ 31.6 33 FT I 25.6 .... 26
a , t-Z uJ 2 Z-uJ <Z ...J < ...J Z CIl: < 10 u
u .3 100 TANGENTIAL MOMENT (K-FT/FT)121.10 LOADING 1.00 (SSE) FIGURE 3.8 31 CONTAINMENT STRUCTURE MAT MOMENT AND SHEAR DIAGRAMS MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT t CONTAINMENT WERIDIONAL FORCE RADIAL "OWENT WE"BRANE SHEAR HOOP MOMENT FIGURE 3.8-32 LOAD PLOT NOMENCLATURE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

DailE 130 en, HDER120 I 10 <t: 100 w 90 > 0 80 OJ -c 70 w 60 u z: 50 -c 40 U) 30 0 491 0 , I -1800 I -600 0.0 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 r-130 u, 120 r-110 -c 100 ILl 90 > D 80 co << 70 ILl 60 u z 50 << r-40 C/) 30 0 20 10 0 en I I ---1-300 -200 1-100 '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 DOllE 130 t-242 CYLINDER u; 120 t-110 < :::2 100 w 90 > 0 80 en -c 70 w 60 u z 50 < 40 c.I) 30 a 20 I0 0 287 I-0400 b.o 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 DOllE 130 J--677 CYLINDER u; J--<: ::::2: 100 w 0 80 CD -c w z -c 40 (/) 30 0 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 IS REPORT LOADING I DL+l.25P+l.0(T+TL)+1.25(2SSE)210_200 190 180 170160_150 140-DOME t-130_u, CYLINDER 120.-110<C:::iE 100 w 90>0 80 CO<C 70 uJ 60 u z 50<C.-40 co 30 Q 20 10 0 b.o RADIAL UOMENT (KIP-FT/FT) FIGURE 3.8-37 CONTAINMENT STRUCTURE WALL AND DOME FORCE RESULTANTS MILLSTONENUCLEARPOWER STATION UNIT 3 FINAL SAFETY ANALYS IS REPORT 210 200 190 180 170 160 150 -LL 140 130 120 DOME CYL INDER <C ::E I 10 100 w > 0 CD <C 90 80 70 w u z <C C/) 0 60 50 40 30 20 10 0 I-zoo '100 200 RADIAL SHEAR I KIP IF T i FIGURE 3.8-38 LOADING CONTAINMENT STRUCTURE WALL AND DOME FORCE RESULTANTS DL+l.25P+I.OI T+TL )+1.25(tSSE) MILLS1DNE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT 210 200 190 180 170 160 150 140 130 DaME t-u..CYLINDER 120 l-t10<C::E 100 w 90>0 80 en<C 70 w 60 u z 50<C t-40 U)30 0 2010 0 I b.o I-600 600 LOADINGDL+1*25P+1*0(T+TL)+I*25 (t 5SE)HOOP FORCE (KIP/FTJ FIGURE 3.8-39 CONTAINMENT STRUCTURE WALLANDDOMEFORCE RESULTANTS MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYS IS REPORT 180 nME 130 en INDER LL 120 I-110 _ << 100 UJ 90 > 0 80 en << 70 UJ 60 u z 50 << '10 U) 30 0 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

DailE I--130 CYLINDER u, I--<< :::iE 100 UJ 0 80 co << UJ u :z 50 << 40 U) 30 £::) 20 10 0 I-40 b.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-DOME.-130 LL CYLINDER 120.-110<<::E 100 w 90>0 80 co<<70 w 60 u:z 50<<.-40 Cf)30 0 20 10 0 I I-500 0.0 RADIAL MOMENT (KIP-FT/FT J FIGURE 3.8-42 CONTAINMENT STRUCTURE WALLANDDOME FORCE RESULTANTS MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT LOADING o L+I*0P+I*0(T+TL)+1*0 (SSE) 210 200 190 180 170 160 150 I-u, 140 130 120 DOME en I NDER -c :::E 110 100 w > 0 en -c 90 80 70 UJ u z << U) a 60 50 40 30 20 10 0 I 0.0 1100 ---I 200 RADIAL SHEAR IKIP/FTI LOADING FIGURE 3.8-43 CONTAINMENT STRUCTURE WALL 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]60 150 140 130 DOME l-LL CYLINDER 120.-110-c100 UJ 90>to 80 CO-c 70 UJ 60 u z 50-c I-40 U)30 0 2010 0 I I I-400 0.0..00 LOADING DL+l.0P+l.0(T+TL)+1.0 (SSE)HOOP FORCE (KIP/FT)FIGURE 3.8-44 CONTAINMENT STRUCTURE WALL AND DOME FORCE RESULTANTS MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT u, -c w > 0 co -c w u z <t: (/) c::a 210 200 190 180 170 160 150 140 130 120 110 100 90 80 70 60 50 40 30 20 10 0 DL+I.OP+I.O( T+TL )+1.0 (SSE) MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT DOME CYLINDER !..zoo I 0.0 MERIDIONAL FORCE IKIP/FTI FIGURE 3.8-45 CONTAINMENT STRUCTURE WALL AND DOME FORCE RESULTANTS 210 200 190 180 170 160 150 140-DOME f-130 1.L CYLI NDER 12011O<<100 UJ 90>0 80 co<<70 w 60 u z 50<<t-40 (f)30 0 2010 0 I I I-100 0.0 100 LOADING DL+l.0P+l.0(T+TL)+1.0 (SSE)MEMBRANE SHEAR FORCE (KIP/FTl FIGURE 3.8-46 CONTAINMENT STRUCTURE WALL AND DOME FORCE RESULTANTS MIL LSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT 210 200 190 180 170 160 150 -I-u.. 140 130 120 DIME CYLINDER <C :!: 110 100 uJ > 0 CD <C 90 80 70 uJ u :z <C U) 0 60 50 40 30 20 10 0 to koo '1000 RADIAL MOMENT (KIP-FT/FT) LOADING DL ..I. 15P FIGURE 3.8-47 CONTAINMENT STRUCTURE WALL AND DOME FORCE RESULTANTS MI LLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT 210 200 190 180 170 160 150 140-DhE I-130 U-CYLlNDEI 120 l-I10<C100 UJ 90>0 80 CO<C 70 uJ 60 u z 50<C t- (/)30 0 20 10 0 LOADING nL+1*15P RADIAL SHEAR(K t P IFT)FIGURE 3.8-48 CONTAINMENT STRUCTURE WALL ANDDOMEFORCERESULTANTS MILLSTONE NUCLEAR POWER STATION UNIT3 FINAL SAFETY ANALYSIS REPORT

-DhE t-130 en INDEIt u.. 120 t-I10 <C 100 uJ 90 > 0 to co <C 10 uJ 60 CJ :z 50 <C t-40 en 30 Q ..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-DhE f-130 U.CYLINDER 120 l-I10<::E 100 uJ 90>0 80 co-c 70 uJ 60 u:z SO<f-40 CJ)30 0 20 10 0..oo b.o LOADING DL+1.15P HOOP FORCE(KIP IFT)FIGURE 3.8-50 CONTAINMENT STRUCTURE WALL ANDDOMEFORCE RESULTANTS MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT 210 200 190 180 170 160 150 140 130 DIME I l-LL CYLI NDER 120 l-II0-c100 w 90>c 80 co-c 70 UJ 60 u z: 50-c I-40 en 0 30 2010 0 b.o RADIAL YOMENT (KIP-FT/FT) 1100 LOADING DL+OPERATING VACUUM FIGURE 3.8-51 CONTAINMENT STRUCTURE WALL AND DOME FORCE RESULTANTS MILLSTONE NUCLEAR POWER STATION UNIT3 FINAL SAFETY ANALYSIS REPORT 210 200 190 180 170 160 150 140 130 DOME l-u, CYLINDER 120 f-110-c100 w 90>0 80 co-c 70 w 60 u z 50-c f-40 en 30 0 20 10 0 b.o k'10 LOADING DL+OPERATING VACUUM RADIAL SHEAR (KIP/FT)FIGURE 3.8-52 CONTAINMENT STRUCTURE WALL ANDDOMEFORCE RESULTANTS MILLSTONE NUCLEAR POWER STATION UNIT3 FINAL SAFETY ANALYSIS REPORT -140 DaME I-130 u, en Il-II 0 -c :::E 100 UJ 90 > 10 80 -c UJ 60 u z 50 -c 40 U) 30 0 0 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 lIME l-130 CYLINIER LL 120 l-110 -c 100 UJ 90 > 0 80 en -c 70 UJ 60 u :z 50 -c U) 30 0 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 HOOP MOMENT l KIP-FT/FT) 408.0 II.e SV....ETRICAL A80UT DIAMETER HOOP FORCE lKIP/FT)55.2 PLAN OF CONTAINMENT CYLINDER LOADING, TORMADO IINDS VELOCITV*5&0 MPH EQUIVALENT TO l6AD Of 0.55 l/SQ.fT.LOAD DISTRleUTION 8ASED OM ASC(rAPER MO.5219 FIGURE 3.8-55 CONTAINMENT STRUCTUREWALLAND DOME MILLSTONE NUCLEAR POWER STATION UNIT 3 FI NAL SAFETY ANALYS IS REPORT NORTH END OF N-S tCONTMT. STRUCT, 21 3/8" (TYP.) nllt1rt!rH-ANd-UfL-4' -0" RADIUS --->-----, (T Y P. ) 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 UNIT 3 FINAL SAFfTY ANALYSIS RF_PORT MNPS-3 MNPS-3 FSAR E E ., ., 23 23 (H-II) (H-II) I I CONTMT. CONTMT. RECIRC.RECIRC. -+_-....

PUMP PUMP PIT EY-3C EY-3C (11004) ,

eo eo

s s CONTMT. CONTMT. It: It: STRUCTURE STRUCTURE 6" 6" PERFORATED

PERFORATED DRAIN DRAIN PIPE PIPE (SEE (SEE NOTE NOTE 5)

5) CONC.

CONC. SEALER SEALER W W PLAN PLAN EL EL (-)37:'6"

(-)37:'6" SHOWING SHOWING LAYOUT LAYOUT OF OF DRAINAGE DRAINAGE SCALE SCALE 1/32":

1/32": I' I' (MEMBRANE (MEMBRANE SANDWICHED

SANDWICHED BETWEEN BETWEEN TWO TWO (2) (2) 2" 2" LAYERS LAYERS OF OF COMPRESSIBLE COMPRESSIBLE MATERIALl MATERIALl RIBBED RIBBED FIBERGLASS

FIBERGLASS CONTMT. CONTMT. STRUCT. STRUCT. WALL WALL 4" 4" COMPRESS COMPRESS MAT.MAT. WATERPROOF WATERPROOF __ __ MEMBRANE

PROTECTION

PROTECTION BOARD BOARD FIGURE FIGURE 3.8-57 3.8-57 (SHEET (SHEET 1 1 OF OF 2)(PART 2)(PART 1 1 OF OF 2)2) DETAILS DETAILS OF OF WATERPROOF WATERPROOF MEMBRANE MEMBRANE 26-26 26-26 (H-2) (H-2) NOVEMBER NOVEMBER 1997 1997 MNPS-3 FSAR RIBBED FIBERGLASSCONTMT.STRUCT.79'-0" 2'-6" f THICK 2.WELDTOPIT LINER 1114--+---34" 1.0.CONTMT.RECIRC.PUMPPITLINER (fTHICKSTEEL It..) CASING 9" POROUS CONC.rEL(-)37'-6"-*2" GROUT rEU-)39'-3" ro" POROUS CONC.PERFORATED DRAIN PIPE I"AGGREGATE CONC.24-24 (0-2)SCALE 1/4": I'BOT.CONTMT.RECIRC.PUMP CASING EL.H49'-0" E L ,H 5 0'_0STUDS2'-Oil EA WAY,WELDTO PIT LINER POROUS CONC.2" GROUT POROUS CONC.LEVELINGPOUR 21-21 (B-3 e.E-3)SCALE1/4": I'PROTECTION BOARD 4"COMPRESSIBLE MATERIAL-SEENOTE10(2)*2" LAVERS SANDWICH MEMBRANE 26.t26(K-2) MAT EL.{-)27'-3" L 74'-6"R v"--4"CONC.HOLLOW BLOCKS SHALL BELAYEDINA FASHION TO PERMIT DRAINAGE ALONG WATERPROOF MEMBRANE ALL BLOCKSSHALLHAVE SMOOTH SURFACEWITHNO PROJECTIONS IN CONTACTWITHMEMBRANEAND SHALLHAVEMORTAREDJOINTSTRUCKSMOOTH .HORIZONTALLAYERSOFBLOCK SHALL BE LAVED RADIALLY,KEEPINGHOLESIN LINE.*v*.*.Y.TOMAT EL(-)27'-3" 2" GROUT 4"#4 CRUSHED STONE PROVIDE 1";DRAINHOLES THRU CONC.BLOCKINEACOREFORTHEPASSAGE OF WATER INTO POROUS CONC.,";DRAINHOLESTHRUBLOCKINLINEWITHHOLES IN VERTICALNOVEMBER 1997 FIGURE 3.8-57 (SHEET1OF 2)(PART2OF2)DETAILS OF WATERPROOF MEMBRANE 2" GROUT EL.H43'-0" POROUS CONC.EMBRANE 10" P OROUS CONC.(M IN.)2" GROUT*POUR2 INST ALLED AF TER P OUR I MEMBRANE EL.{-)4I'-3" 2 2-2 2 (0-1)SC ALE 1/4"=I'ELH34'f--9_ "-+_EL..,.,:;,..,.:.....;;37 C6" fa F-39" POROUS CONC.CONC.SEALERHOLLOWBLOCKSEENOTE fa F-4 2" GROUT EL.H39'-3" ENG.SAFETYFEATURES t-------,/L--l-BLDG. EC-32 SERIES(11213)MEMBRANE 6 10" POROUS CONC.LEVELING SLAB 2" GROUT 9" POROUS CONC....MNPS-3 FSAR f THICK 2.WELD TO PIT LINER FIGURE 3.8-57 (SHEET 1 OF 2)(PART 2 OF 2)DETAILS OF WATERPROOF MEMBRANE NOVEMBER 1997 1114-+--34" 1.0.CONTMT.RECIRC.PUMP PIT LINER (f THICK STEEL Il.)t9-i--PUMP CASING 9" POROUS CONC.-.2 ff GROUT r EU-)39'-3".10" POROUS CONC.PERFORATED DRAIN PIPE 11114t--I"AGGREGATE CONC.24-24 (0-2)SCALE 1/4"=I'£CONTMT RECIRC PUMP ENG.SAF.FEAT.BLDG.EC-32 SERIES (11213)n_r EU-)34'-9"...---L,-.Jl1 Ift..-:-'"--t-'-------,__..L.__..'., BOT.CONTMT.RECIRC.PUMP CASING EL.(-)49'-0" E L.(-)5 0'_0CONTMt STRUCT.79'-0" f;.STUDS2'-0" EA WAY.WELD TO PIT LINER..'.. EL.(-)43'-0" J------SEE NOTE Ia F-4:..........t.---- POROUS CONC.EMBRANE 10" POROUS CONC.(MIN.)2" GROUT*POUR 2 INSTALLED AFTER POUR I MEMBRANE EL.{-)4,'-3" POROUS CONC.r GROUT POROUS CONC.LEVELING POUR 21-21 (B-3 f..E-3)SCALE 1/4"=I'22-22 (D-I)SCALE 1/4": I' %L (-)37'-6" zN.u: 14'T---..=.,.--,J---- ..-t-.-,..-- ..........:.;*4U-l 39'-3" 79'-6"R*.FINISH SMOOTH TO SEAL SURFACE PROTECTION BOARD 4"COMPRESSIBLE MATERIAL-SEE NOTE 10(2)*2" LAYERS SANDWICH MEMBRANE 26[.26 (K-2) MAT EL.{-)27'-3" L 74'-6"R v"--4"CONC.HOLLOW BLOCKS SHALL BE LAYED IN A FASHION TO PERMIT DRAINAGE ALONG WATERPROOF MEMBRANE ALL BLOCKS SHALL HAVE SMOOTH SURFACE WITH NO PROJECTIONS IN CONTACT WITH MEMBRANE AND SHALL HAVE MORTARED JOINT STRUCK SMOOTH.HORIZONTAL LAYERS OF BLOCK SHALL BE LAYED RADIALLY, KEEPING HOLES IN LINE.ENG.SAFETY FEATURES.....---,/L--l-BLDG. EC-32 SERIES (11213) 1----+_EL-,;;_,:...,-137'-G" i .._:.. F-3'., 9" POROUS CONC.CONC.SEALER I-fl>::--- 4" CONC.HOLLOW BLOCK SEE NOTE (a F-4 2" GROUT El.H39'-3" MEMBRANE.p*.*.9.TO MAT El.(-)27'*3" 2" GROUT 4"'4 CRUSHED STONE RIBBED FIBERGLASS PROVIDE 1";DRAIN HOLES THRU CONC.BLOCK IN EA CORE FOR THE PASSAGE OF WATER INTO POROUS CONC.,";DRAIN HOLES THRU BLOCK IN LINE WITH HOLES IN VERTICAL 10" POROUS CONC.LEVELING SLAB 2" GROUT 9" POROUS CONC..-i-, FINISH SMOOTH TO SEAL SURFACE(TYP)-T---rT1 ENG.SAFETY FEATURES BLDG.£C-32 SERIES (11213)MEMBRANE g" POROUS CONC.SEE NOTE@F-3 CONC.SEALER Z'(3/4"AGGRffiATE CONe.}2-GROUT:.f..23-23(0-1) SCALE-1/4"=,'FINISH SMOOTHTOSEALSURfACE 10" POROUS CONC.LEVEliNG POOR E l.(-)34'-gil- ....CRUSHED STO NE EL.(-)3i-6"-SEENOTE"{YF-4 EL.(-)3S'-6"-*..*--_..EL.{-)39'-3 II-SEENOT E a A-g--......9"pOROUS CONC.MEMBRAN EPROVIDEHOLEFORBOLT 7 O 2J/4"x2" 3"WIDETI E BANDS , DET" A" lC-7)SCALE-I 1/2"="PITLINER PUMP CASING 25(B-9)BOLTB.F.GOOORICH (THICK R-3STANNATURALRUBBEROR EQUAL.2" SPACER2 x 2 x 3/4 25-25 (D-IO)SHOWINGTYPTIE BAND CONN flON SCALE-I I/Z"=I'4" CONC.HOLLOWBLOCKCAULKALLAROUND SS LINERCUTSSLINERAPPROX e1/2"'"LARGERTO FIT 8" NOMINAL'" STL.PIPE PIPE AND LINEROPENINGSCLOSEDBYSEAL WELDED PLATE (TYPICAL 6 PLACES)25212-59108 SH 37TOPOFCONC.EL.(-)3S'-9" POROUS CONC--6-PERFORt.TED CONC PIPE BROKEN BEYOND POROUS LAYER rIPEINTERIORSEALEDWITH GROUT.8-MIN-12 ft MAX (TYPICAL 6 PLACES)..:. DET 11 811 (H-7)SHOWINGCONNECTIONOETSOF 6*0 POROUS DRAIN PIPETOSSLINER SCALE:=1'-0*FIGURE 3.8-57 (20F2)DETAILSOFWATERPROOFME MBRANE MILLSTONE NUCL EAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPOR T CAD FILE: 385 72.dgn/385 72.cit March 20 01 (00-42)ENG.SAFETY FEATURES BLDG.£C-32 SERIES (11213)9" POROUS CONC.MEMBRANE CRUSHED STONE SEE NOTE"{YF-4 SEE NOTE(c}F-3 CONC.SEALER 2'(3/4"AGGRffiATE CONC.)2-GROUT 23-23(0-1) SCALE-1/4"=I' 10" POROUS CONC.LEVEliNG POOR FINISH SMOOTH TO SEAL SURFACE EL.(-)3i-6" EL.(-)3S'-6"....---..-------... EL.(-)39'-3"-.. SEE NOTE a A-9--"",", 9"POROUS CONC.MEMBRANE 2" PROVIDE HOLE FOR BOLT 7 O 21/4"x2" 3" 1-'::, WIDE TIE BANOS r DET"A" tC-7)SCALE-I 1/2"=,'PIT LINER PUMP CASING 25(B-9)BOLTB.F.GOOORICH (THICK R-3S TAN NATURAL RUBBER OR EQUAL.2" SPACER2 x 2 x 3/4 25-25 (0-10)SHOWING TYP TIE BAND CONN TlON SCALE-II/l=I'6-a PERFORt.TED CONC PIPE BROKEN BEYOND POROUS LAYER t>IPE INTERIOR SEAlED WITH GROUT, 8-MIN-12 ft MAX (TYPICAL 6 PLACES)9" POROUS LAYER 2-GROUT POROUS CONC CAULK ALL AROUND 55 LINER CUT SS LINER APPROX-1/2"LARGER TO FIT a" NOMINALSTL.PIPE PIPE AND LINER OPENINGS CLOSED BY SEAL WELDED PLATE (TYPICAL 6 PLACES)25212-59108 SH 37 TOP OFCONC.EL.(-)3S'-9 n 4" CONC.HOllOW BLOCK DET 11 8" (H-7)SHOWING CONNECTION DETS OF 6-0 POROUS DRAIN PIPE TO SS LINER SCALE:1'-0-FIGURE 3.8-57 (20F2)DETAILS OF WATERPROOF MEMBRANE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FILE: 38572.dgn/38572.cit March 2001 (00-42)ENG.SAFETY FEATURES BLDG.£C-32 SERIES (11213)9" POROUS CONC.MEMBRANE CRUSHED STONE SEE NOTE"{YF-4 SEE NOTE(c}F-3 CONC.SEALER 2'(3/4"AGGRffiATE CONC.)2-GROUT 23-23(0-1) SCALE-1/4"=I' 10" POROUS CONC.LEVEliNG POOR FINISH SMOOTH TO SEAL SURFACE EL.(-)3i-6" EL.(-)3S'-6"....---..-------... EL.(-)39'-3"-.. SEE NOTE a A-9--"",", 9"POROUS CONC.MEMBRANE 2" PROVIDE HOLE FOR BOLT 7 O 21/4"x2" 3" 1-'::, WIDE TIE BANOS r DET"A" tC-7)SCALE-I 1/2"=,'PIT LINER PUMP CASING 25(B-9)BOLTB.F.GOOORICH (THICK R-3S TAN NATURAL RUBBER OR EQUAL.2" SPACER2 x 2 x 3/4 25-25 (0-10)SHOWING TYP TIE BAND CONN TlON SCALE-II/l=I'6-a PERFORt.TED CONC PIPE BROKEN BEYOND POROUS LAYER t>IPE INTERIOR SEAlED WITH GROUT, 8-MIN-12 ft MAX (TYPICAL 6 PLACES)9" POROUS LAYER 2-GROUT POROUS CONC CAULK ALL AROUND 55 LINER CUT SS LINER APPROX-1/2"LARGER TO FIT a" NOMINALSTL.PIPE PIPE AND LINER OPENINGS CLOSED BY SEAL WELDED PLATE (TYPICAL 6 PLACES)25212-59108 SH 37 TOP OFCONC.EL.(-)3S'-9 n 4" CONC.HOllOW BLOCK DET 11 8" (H-7)SHOWING CONNECTION DETS OF 6-0 POROUS DRAIN PIPE TO SS LINER SCALE:1'-0-FIGURE 3.8-57 (20F2)DETAILS OF WATERPROOF MEMBRANE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT CAD FILE: 38572.dgn/38572.cit March 2001 (00-42) MNPS-3 FSAR DISPLACEMENTS ARE IN INCHES (RADIAL ,VERTICAL)SPRINGLINEE L.104.25'1 NOTES: PRESSURE TEST 1.00L't 1.15P (p: 45 psi)----Io.._-EL. 175.25 1 El.174.5'EL.171.85' EL.167.,6S 1 EL.162.25 EL.155.1S 1<-OGG,.9146)(0.0,.9383)(.1323,.8951) ---,{.I951 ,.8702)(.2437,.8287) El.115.5'EL.11 0.35'El.104.0 1 EL.I03.75'(.6781.3577 )(.612,.4571 )(.7153,.135) (.678,.2444) (.6999,.1621) (.6903,.2014) (.6464,.4121) (.6457,.3059)(.6729,.0807) (.7309,.1094) (0.0,0.0)EL:-27.25'(TOPOF MAT)FIGURE 3.8-58(1OF2)DISPLACEMENTPROFILEFOR CONTAINMENT SHELL UNDER PRESSURETEST(PREDICTED) NOVEMBER 1997 z 0 RADIAL TANG.DISPL.DISPL.u 0-IN.-IN.-J 1 0.638-2 0.633-3 0.624-4 0.659 0.044 5 0.644-0.0013 6 0.660 0.011 NOTES: 1.TANGENTIAL DISPLACEMENTS ARE HORIZONTAL,INTHEPLANEOFTHEPAPER,POSITIVETOTHERIGHT. 2.RADIAL DISPLACEMENTS ARE HORIZONTAL, NORMALTOTHE PLANEOFTHE PAPER, POSITIVE INTO THE PAPER.3.DISPLACEMENTS AT 6 AND 9 O'CLOCK ARE SYMMETRICAL TO THOSE GIVEN AT 12 AND 3 O'CLOCK RESPECTIVELY. 4.PRESSURE TEST 1.0DL+1.15P (P=45psi)2t---=:------..3Ior------------- EL.58'-2 11---I:. 1 6 2.5R'18*-9*=----J 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 FIG. 3.8-60 3Rt.4S*RED4A l ELEVATION 56 1-10 11 FIG. 3.8-60 FIG. 3.8-60 ST. GENERATOR (TYP.) REACTOR PLAN EL. 51'-4" I iREACTOR I PLAN EL. 24 1-6 11 TIME DELAY DUCT 3RMS.,.RE41 32° REMOVABLE PLATE 1 __,_.....- REACTOR VESSEL HEAD STORAGE RING (BELOW) ,,,-REACTOR VESSEL HEAD / STOHAGE F\ING(BELOW) CO N STRUCTiON OPEN I NG _j1 INTERNALS STORAGE STAND PRESSURIZER CONTAINMENT DRAIN TRANSFER TANK FIG. 3.8-60 I i REACTOR PLAN EL.3'-8" PLAN EL. (-) 24 1-6 11 REACTOR VESSEL HEAD STORAGE RING (BELOW) _ji CONTAINMENT STRUCTURE SUMP PUMPS CONC.SUPPORT lTYPJ CON T AINME N T INST. AIR COMPRESSOR EQUIPMENT RELIEF TANK DRAIN PUMPS *----*-*---*-*--- -*--*------------------1 15-7 FIGURE 3.8-59 CONTAINMENT STRUCTURE, PLAN VIEWS MILLSTONE NUCLEAR POWER ST AT ION UNIT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1 £1...51'-4" EL9 5'4" SU RGELI NE R E LIEF TA NK=I!"'"2 4'-6" PRESSU RI ZER HEATER RE MOVA L S PA C.E: , 3-3 lNCQRE INST M.DRM"A SSY.2" T H K LEAD SHIELD N EUTRO N S H IEL D T A N K S URGE T ANK-CONTA INMEN T LIN ER (TY P,)--.-+-J H--t i Jl , AC CE SS HA TCHTO I NSTR.R OO C O NTAIN MEN T STRU C t URE LI NER--(TY P ,)/CON T AINM ENT S TRU CTURE ENCLOSURE e.s: r-11.RE AC TOR 2-2 CONT A I N MENTAI R R E C IRC ULATION CO O L I NGCO ILAS SY.C ONTAINMEN T STRUCTUR E LINER (T Y P ,)I SO LATION BYP ASS LINE&VAL V ,E.--......... C O N T A I N M E N T STRUCTUR E LINER (T YP ,)E ACTOR V ES SEL HE AD STORA G E.R ING UPPER INTERNAL S S T OR A G E CONTAINMENT STRUCT URE W AlL EQUIPM E N T HATCH PO L ARCRANE J-I 2" T HI<./'LE ADSHI E L D--'WA TER LEvEl: DURIN G R EFUELI N G FUELASS EI.IBL Y---..G IJI(l: TUBE FU EL lPENOE R FUEL T RANSFER TUBE--INTERNA LS STORAGE STANO A UX ILIARY H OOK CONTAINM E NTAIR RE CIR C.FA N (TYP)FIG URE 3.8-60CONTAINMENTSTRUCTURE , ELEVATION VIEWS MILLSTONE N UCLEAR POWERSTATIONUNIT3 FINAL SAFETY ANAL YSIS REP ORT AM ENDMENT 3 A UGUST 1963 y cJ/.: 'BEND LINE E LI 04'-0" SECT , 1-1 CONTAI'I,IMENT STRUCTURE".......>.DET.I INSERT ItFIGURE3.8-61 CONTAINMENT ENCLOSURE BUILDING MILLSTONE NUCLEARPOWERSTATION UNIT 3FINALSAFETYANALYSISREPORT T/PARAPET ILP T iS !.LEL.184'-6'L.P.T l e ONe.E L.VARIES REMO V.o.R L E<:;'1.IlR eORRASe COMP:MATERIAL <l:.I"FIBERBOARO'*.6" STYROF OAM.',,""......'-METF L G.LtCOL.LlINEEL 5 e'-0*DIET.0--Elo57'-6" A UX.BLDG.FLEL4'-6"'" SECT.3-3__ NORTH'bJ 4-CANTSTRIPl'o/I£>" SECT.4-4 E: 4:'1 9/16" I G L0)GIRT EL8 7-2 b'mp.}: (4-4)E LEl.BO T.OF CO L CONTAINMENT STRUCTURE:r/PARAPET E L.)(37'-0" COLUMNDE l E-Z FL--<i,"",,=__DET.H ROADWAYFUELBLDG.AU X ILIAR Y BLDG.PLAN TU RBINE B LDG.LGRO.GR.EL24 '-O*J EL.2 5'-6" ," , r>'0-B OT OFSIDINGEL.25'-O"*..!.GRD.GREL.24 1.0" SERV ICEBLDG.WAS TE t---------l i<l a II: CLlPLS DET.H JI 2 DET.GL 4-3""L4"x3x'/4....." M'O ,., t!..-DET.C DET.B"-COL OET.F CONTAINMENT STRUCTURE y.........6"snROFOA.M'0: MEMBRANE*I"F" IBERBOARDCORRASe.<,,': 2-2 B SECURITY-RELATED-INFORMATION-Withhold under 10 CFR 2.390 FIGURE 3.8-62 (I OF 10) AUXILIARY BUILDING MILLSTONE NUCLEAR POWER STATION 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-INFORMATION-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-INFORMATION-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 FIGURE 3.8-63(SHEET 1OF6) FUEL BU I LO ING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-63 (SHEET 2 OF 6) FUEL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 Fl NAL SAFETY ANALYSIS REPORT (Cf '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 --.JC '.<...;;-'r"'lY 2-( FIGURE 3. 8-63 (SHEET 4 OF 6) FUEL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-63 (SHEET 5 OF 6} FUEL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-63 (SHEET 60F6l FUEL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FI NAL SAFETY ANALYSIS REPORTAMENDMENT3 AUGUST 1983 FIGURE 3. 8-64 (I OF 4} CONTROL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT IL........... ACC ESS HATCH NORTH\bJ CABLE SPREADING AREA PLAN EL.24 1-6"".'fTFIGURE 3.8-64 (2 OF 4)CONTROLBUILDING MILLSTONENUCLEARPOWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT. R A M p [IJ TAGGING OFFICE D RECEPTIONIST .. 24*-o* U.P.S. CAB. UP.S. CAB. I I 11 I 0 IA> RACK-' I I I TELEPHONE JACI< "3RP!UfHAIOIUI I IHRU 4 fitUCLEAR W!GTRUlllEMnTI CB-01 MAIN CONTROL SOARD-PRIMARY ;IU)(ILIARIES CliEMICAL !i l/OLIJldE ---1-t--CONT OUTLINE OF NEW-.........._ / EXCLUSION AREA DD q I I I I I I I STA ELECT 1 TURS-GEN 1!IEGIJANIGALI STLI GEN 6 I I FDWTR HAIN RElllOTE CORT. SECURITY R£L RI( _...J I I r7: FUtC PROT QTA.--_.... 4 I :I I 2 I I PRIMARY PRWECTIVE RELAY I E.Hj e I PNL l I I I I I I I INSTRUMENT RACK ROOM TOILET CONTROL BUILDING PLAN EL. 47'-6 11 . .. .. -..... TUNNEL ... .. , .... , ...... LEGEND VENTILATION EQUIPMENT ROOM UPPER LEVEL (EL 64'-6" CONTROL,COMPUTER,AND INSTRUMENT RACK ROOMS I Fu 4'-G" CABLE SPREADING AREA rEL.24'*6" SWITCHGEAR ROOM 1EL.4CG" CONTROL BUILDING ELEVATION (LOOKING (AST) ELEC. TUNNEL -CONTROL ROOM HABITABILITY AREA 11 AT THE CONTROLS" ----MASONRY BLOCK WALLS IN SAF'ETY-RELATED AREAS FIGURE 3.8-64 (3 OF 4) CONTROL ROOM AREA MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT 11 CAD FILE" m3641.dgn/m3641.ctt -., . \"3HVC*RE168-\bD t3HVC*RE16A D L;::::;:]L'9.VC-RE91 r.==J D 0 I I PLAN EL.64'-6 11 FIGURE 3.8-64 (4 OF4)CONTROL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 3 AUGUST 1983 "TIC:!l:()'TI l>-lrfDC r C>1 en r ::c U> -I l"'1 ITI )> 0 ()l z-1* 'Tl rT1 CD 111 C I -I ZZcn -< CZ01 )> (") rri z rr )> :a (J) '"Cl (./) 0 ::IJ !'11 !'11 ::u -c 0 CJ) ::u -I -I 0 :z ( i r-' ,..(: r-J 0 0 {) FIGURE 3.8-66 (SHEET I OF 5) EMERGENCY GENERATOR ENCLOSURE MILLSTONE NUCLEAR POWER STATION , UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-66 (SHEET 2 OF 5) EMERGENCY GENERATOR ENCLOSURE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT 3'FIGURE 3.8-66 (SHEET 30F5)EMERGENCY GENERATOR ENCLOSURE MILLSTONE NUCLEAR POWER STATION UN IT 3 FINAL SAFETY ANALYSIS REPORT A MENDMENT 8 MAY 1984 FIGURE 3.8-66 (SHEET 40F5) EMERGENCY GENERATOR ENCLOSURE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT

F IGURE 3.8-66 (SHEET5OF5)EMERGENCY GENERATOR ENCLOSURE MILLSTONE NUCLEAR POWER STATIONUNIT3 FINAL SAFETYANALYSISREPORTAMENDMENT8 MAY 1984 MPS-3 FSARPage 1 of 2Rev. 16NOTES TO FIGURE 3.8-66 EMERGENCY DIESEL GENERATOR - EQUIPMENT INDEXEQUIPMENT MARK NO.EQUIPMENT DESCRIPTION3BYS*PNLDG1FEmergency Generator 125 V DC Distribution Panel 3CES*PNLBD10 Safety-Related to Nonsafety-Re lated Signal to Isolator Panel3EGA*TK1A(A-)Emergency Diesel Generator Air Start System Air Receiver Tanks3EGA*TK2A(A-)Emergency Diesel Generator Air Start System Air Receiver Tanks 3EGD*EJ3AEmergency Diesel Generato r Exhaust Expansion Joint 3EGD*P1A(AO)Crankcase Vacuum Pump3EGD*SIL1A(A-)Emergency Diesel Generator Combustion Air Filter and Silencer3EGD*SIL2A(A-)Emergency Diesel Generato r Combustion Air Silencer3EGD*SIL3A(A-)Emergency Diesel Generator Exhaust Muffler3EGD*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*TRS1AManual Transfer Switch for Emergency Generator Fuel Oil Transfer Pump 3EGS-E1A(A-)Emergency Diesel Generator Intercooler Water Heat Exchanger 3EGS*E2A(A-)

Emer gency Diesel Generator Engine Jacket Watercooler 3EGS*EG-A(AO)Emergency Diesel Generator Skid A 3EGS*EG1ANEmergency Generator 4 kV Neutral Current Transformer Lead Box MPS-3 FSAR Page 2 of 2Rev. 16 3EGS*EG1APWREmergency Generator Power Lead Termination Box 3EGS*JBFLDAEmergency Generator Housing Mounted Junction Box3EGS*JBRTDAEmergency Generator Housing Mounted Junction Box3EGS-PNL1AEmergency Generator Distri bution Panel (Skid Mounted) 3EGS*PNLAEmergency Generator Control Panel 3EGS*PNLDGAEmergency Generator Control Panel 3EGS*TBEG1AEmergency Generator Control and Relay Box 3EHS*MCC1A1Emergency Diesel Generator 480 V Motor Control Center 3ENS*ACB-GNAEmergency Generator 4 kV Neutral Ground Breaker 3ENS*RES-GNAEmergency Generator 4160 V Neutral Ground Resistor3HVP*DMPT1A&CDiesel Generator Building Tornado Damper3HVP*DMPT5A&CDiesel Generator Building Tornado Damper3HVP*DMPT6A&CDiesel Generator Building Tornado Damper3HVP*FN1A(AO)Diesel Generator Building Ventilation Supply Fan3HVP*F N1C(CO)Diesel Generator Building Ventilation Exhaust Fan3HVP-FN2A Diesel Generator Building Ventilation Exhaust Fan3HVP*MOD-23A(AO)F O Diesel Generator Building Ventilation Inlet Da mper3LAD*EXL10 Diesel Generator Building Emergency Lighting Transformer 3SCV*PNL250 240/120 V AC Single Phase Emer gency Distribution Panel 3SCV*XD250240/120 V AC Single Phase Emergency Distribution PanelNOTES TO FIGURE 3.8-66 EMERGENCY DIESEL GENERATOR - EQUIPMENT INDEXEQUIPMENT MARK NO.EQUIPMENT DESCRIPTIONNOTE: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. FIGURE 3.8-67(1OF 9)ENGINEERED SAFETY FEATURES BUILDING MILLSTONE NUCLEARPOWERSTATION UNIT 3 FINAL SAFETY ANALYSIS REPORT March 2001 (00-27)-, 0( FIGURE 3.8-67 (20F9) ENGINEERED SAFETY FEATURES BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-67 (3 OF 9) ENGINEERED SAFETY FEATURES BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT R-,5 -o .)"U FIGURE 3.8-67 (40F9) ENGINEER ED SAFETY FEATURES BUILDING MILLSTONE NUCLEAR POW ER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-67 (5 OF ENGINEERED SAFETY FEATURES BUILDING MILLSTONE NUCLEARPOWERSTATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-67 (6 OF 9)ENGINEERED SAFETY FEATURES BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT F IGURE 3.8-67 (7 OF 9)ENGINEERED SAFETY FEATURES BUILDING MILLSTONENUCLEARPOWERSTATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-67 (8 OF9)ENGINEERED SAFETY FEATURES BUILDING MILLSTONE NUCLEAR POWER STA TION UNIT 3 FINAL SAFETY ANALYSIS REPORT.: l-..---FIGURE 3.8-67(9 OF9)ENGINEERED SAFETY FEATURES BUILDING Marefl=-2eef fee-2-r-)CAD FILE: 1222.dgn/1222.c lt o\'S -KEY PLAN 31 {) FIGURE 3.8-68 (1 OF 4) MAIN STEAM VALVE BUILD ING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-68 ( 2 OF 4) MAIN STEAM VALVE BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-68(3 OF 4) MAIN STEAM VALVE BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT 15-7 FIGURE 3.8-68(4 OF 4)MAIN STEAM VALVE BUILDING MILLSTONE NUCLEAR POWER STATIONUNIT3 FINA L SAFETY ANALYSIS REPORT , FIGURE 3.8-69(SHEET1OF4) CIRCULATING ANDSERVICEWATERPUMPHOUSE OCTOBER 1997 MNPS-3FSAR FIGURE 3.8-69 (Sheet 2 of 4)CIRCULATINGANDSERVICEWATERPUMPHOUSE SEPTEMBER 1995 'FIGURE3.a-69 (SHEET 3 OF 4)C IRCU LATING AND SERVICE WATER PUMPHOUSE MILLSTONE NUCLEARPOWERSTATION UNIT 3 FINAL SAFETY ANALYSIS REPORT .FIGURE 3.8-69(SHEET4OF 4)CIRCULATING AND SERVICE WATER PUMPHOUSE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT 15 SEPTEMBER 1985 FIGURE 3.8-70 (1 OF 4) RECOMBINER BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-70 (2 OF 4)RECOMBINER BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3.FINAL SAFETY ANALYSIS REPORT FIGURE3.8-70 (3 OF 4)RECOMBINER BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FI NAL SAFETY ANALYSIS REPORT FIGURE 3.8-70 (4 OF 4) RECOMBINER BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT .FIGURE3.8-71 CIRCULATING DISCHARGE STRUCTURE AND TUNNEL 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 ( 1 OF 4) SERVlCE 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(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 FIGURE 3. 8-73 ( 1 OF 5) TURBINE BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-73 (2 OF 5) TURBINE BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3*. 8-73 ( 3 OF 5) TURBINE BUILDING MILLSTONE NUCLEAR POWER STATION UNlT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1 FIGURE 3-8-73 (4 OF 5) TURBINE BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT REV. 28.1 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 FIGURE 3. 8 -74 (SHEET 1 OF 7) SOLID AND LIQUID WASTE DISPOSAL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-74 (SHEET 2 OF 7) SOLID AND LIQUID WASTE DISPOSAL BUILDING MNPS-3 FSAR.,.,.,., N W A J3 J FIGURE 3.8-74 (SHEET3OF7)SOLID AND LIQUID WASTE DISPOSAL BUILDING AUGUST 1996 FIGURE 3.8-74 (SHEET4OF 7)SOLIDANDLIQUID WASTE DISPOSAL BUILDING MILLSTONENUCLEARPOWER STATION.UNIT:3 FINAL SAFETY ANALYSIS REPORTAMENDMENT3 AUGUST 1983 YP) 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 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 FIGURE 3.8 -14 (SHEET 70F7) SOLID AND LIQUID WASTE DISPOSAL BUILDING MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-75 (1 OF12) WAREHOUSE NO. 5 MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-75 {20F12) WAREHOUSE NO. 5 Ml LLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3. 8-7 5 ( 3 OF 12) WAREHOUSE NO. 5 Ml LLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-75{4 OF 12) WAREHOUSE NO. 5 MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-75(5 OF 12.) WAREHOUSE NO. 5 MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALSIS REPORT FIGURE 3.8-75 (6 OF 12} WAREHOUSE NO. 5 MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALSIS REPORT FIGURE 3.8-75 (7 OF 12)WAREHOUSE NO.5.MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-75 (8 OF 12)WAREHOUSE NO.5 MILLSTONE NUCLEARPOWERSTATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-75(90F12} WAREHOUSE NO. 5 MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE3.8-75(10 OF 12)WAREHOUSE NO.5MILLSTONENUCLEAR POWER STATION UNIT:3 FINAL SAFETY ANALYS IS REPORT FIGURE3.8-75(11OF 12)WAREHOUSENO.5 MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3. 8-75 (12 OF 12) WAREHOUSE N0.5 MILLSTONE NUCLEAR POWER STATION UNIT "3 FINAL SAFETY ANALYSIS REPORT FIGURE3.8-76(10 F 5)AUXI LIARYB0ILER ENCLO5URE MIL LSTONENUC LE AR POWER STAT ION UN IT 3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-76(2OF 5)AUXIL IARY BOILER ENCLOSURE MILLSTONE NUCLEAR POWER STATIONUNIT:3 FINAL SAFETY ANALYSIS REPORT FIGURE3.8-76 ('30F 5)AUXILIARY BOILER ENCLOSURE MILLSTONE NUCLEAR POWER STATION UNIT3 FINAL SAFETY ANALYSIS REPORT FIGURE 3.8-76 (40F5l AUXI L IARY BOILERENCLOSURE MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT..r:[ FIGURE 3.8-76 (5 OF 5)AUXILIARY BOILER ENCLOSURE MILLSTONE NUCLEAR POWER STATION UNIT 3 FI NAL SAFETY ANALYSI S REPORT FIGURE 3.8-77 ARRANGEMENT OF HORIZONTAL SHEAR KEYS MI LLSTONE NUCLEAR POWER PLANTUNIT3 FIr.lAL SAFETYANALYSISREPORT 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 R IT=20.4 HRS . .I 200 CASE 1I B--y" CASE IT A 180 I..L ° I w 160 0:: :::l ___

ill: T=150oF _S._S_. _ << 0:: w 140 0... '.- w rCASE I: T=125° S.S. 120 100 80 ... o 10 40 50 60 CASE I: NORMAL REFUELING -MAXIMUM TEMPERATURE CASE II A: NORMAL HEAT LOAD WITH LOSS OF COOLING CASE n B: NORMAL HEAT LOAD-MAXIMUM To -WITH LOSS OF COOLING CASE ill: FULL CORE OFF LOAD-MAXIMUM TEMPERATURE S S.=STEADY STATE To = INITIAL TEMP. (S.S.) WATER R = RANGE OF CONDITIONS FOR VARYING To WITH LOSS OF COOLING FIGURE 3.8-79 FUEL POOL TEMPERATURE TRANSIENTS MILLSTONE NUCLEAR POWER STATION UNIT 3 FINAL SAFETY ANALYSIS REPORT AMENDMENT APRIL 1983 FUEL BLDG. INTERIOR T= SO to 104° F .. .... \> .,.....------, 'V:: ___SPENT FUEL SHIPPING ___ CASK STORAGE AREA ',f.J', .':-:r .. .----------......" ...' :<1'. ' * :--_SPENT FUEL SHIPPING CASK LOADING AREA SPENT FUEL POOL T' SEE FIGURE 3.8-7.(\', ......" .<;J:. 9

7 OUTSIDE SOO F SUMMER (GATES T ={ 00 F WINTER ': . '.'6'. rr,'\?'*, '

.-',1:1 FUEL TRANSFER CANAL .'V.' "

: :t::;, " * '<1 .':D.' : .. .' .' 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::.I ,'f" CAS E IV:::J I-"\<t'\\,.0::: 175\w ,\\a..*\1 I L I\\W.,\l-I*,:\\*,'\...J I , , 0 0 150.,"'\u,1'......'*I.."1/..........J.":::J., ,-CD ,......-.....-.-,.............-.125 20.0 25.0 30.0 35.040.0 45.0 50.0 55.0 15.0 10.0 5.0 100-4-........... ""T'"""T........ ........... ........... 0.0 TIME AF TER MA X.TEMP.HAS REA CHED.HR NOTES: C ASEIIA: NOR MAL HEAT LO AD WITH LOSS OF COOLI NG CASE IIB: NORMAL H E AT LO AD-MA XIMUMT O-WITH O F COOLIN G CASE IV: FULLC O RE OF F LOAD WIT H LOSS O F COOLING FIGURE 3.8-81 FUEL POOL TEMPERATURE TRANSIENTSFOR HIGHER ENRICHMENT FUEL MILLSTONEN UC L EARP OWERS TATION UNIT 3 FI NAL SAFE TY ANALYSIS REPORT J U NE 19 92

MNPS-3 FSAR-*r**PlAN-: I uFT.l__OFF-GAS OUTLET PlPE GRADE ELEV.14.0 rT.lOP or SlACKEL.389.00F 1.375Fr.-OHt r I I I I I I I I I I I I I I I I I*,*I I r lrY">n ,.......... ,'Tr"'+n rrt*\**r ,: I I I , r , I I I I I I I I I I I I I I I I I I I r r I r I120 FT.-O IN..120 FT.-O Itt;10rr.-0IN.J L---Zl FT-(;IN- [l-B ELEV AT]ON A-A Figure 3.8-83 Millstone Stack Elevations and Sections March 2001 (00-50) MNPS-3 FSAR UASS]9 28 15423 401]23-1 2114 4518 4017-J52 6711 36]Jl66 834-1046-741 1437 2319]752 1 296 200 J75-2117 324 656 227 508 578 3552 3009 1589 2762 1060 2 J33 50 257 444-289 2532 3272 5060 5648 1 2 34 35 36 37 38 39 3 4 40 5 s 21 22 23 24 Z5 26 27 28 2:J 32 33 30 31 17 18 13 20 15 16 13 14 7 8 9 10 11 12 18 22 26 28 32..----35.---36.---34.----293030.----31.----33.----27.-----23..----21.-----19.----25.----17.---20 t--+----233 r-, 12.----13.------9---10..----15.----7-16 14..---6..---8.------lJ.-----3.------5..---4 lf1 t--+-----37 m..---.-.---38 r<,40 o o If)n4: If)r>>N---;:--t--.-----Z lD to ro n Figur e 3.8-84 M"II I stone Stack-M athem atical Mod el M arch 2001 (00-50)}}

@@ Line 2: / Line 2: @@
 | number = ML17212A071
 | issue date = 06/29/2017
-| title = Millstone Power Station Unit 3 Final Safety Analysis Report, Rev. 30, Chapter 3, Figures 3.2-1 - 3.8-84
+| title = Final Safety Analysis Report, Rev. 30, Chapter 3, Figures 3.2-1 - 3.8-84
 | author name =
 | author affiliation = Dominion Nuclear Connecticut, Inc

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