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{{#Wiki_filter: | {{#Wiki_filter:FIG 6.0-1 6'"SS 6"55 FROM MNCEUP TANK WU-T1 14"'SS 6"SS 8" S5 8" S5 PIPE AND VALVE JACKETED lCfSS 10'S$RE'ACTOR BUILDING 2 1/Z"SS 21/1'SS ,_ | ||
lX'SS p.6.FIG-1 FROM RNER TO RIVER WATER...._-,.-,,,_DISCHARGE UNE UPDATE-15 04/00 MU-V14M en In'co v--"'''''''-ES SIMPLIFIED SCHEMA TIC DIAGRAM EMERGENCY CORE COOLING SYSTEM AmerGen TMI-UNIT 1 t.tU-V12 10":;5 j 1.r'3S VENT F.\HI t llA t/)'1)i.O BORATED WAfER LO':0&: LO-LO TANK&LO-LO DH-T1 00-\'59 DH-VSA ES'*DH-V7A" , UU-P1C MU-P19 WAKEUP PUMPS DH-Ci9 HI to'ES lOW Flaw AI.ARN Itm:RlDCK FROMHI..LO LOW flOW AlARM fNI'ERlOCK fftOY ES ES | |||
......-i><J-,... | |||
...--------------------....-uII MU-P1A INTERlOCK l.O ES FROM ES R8 14" 5S 14" 5S HI LO_.......... | |||
-...J Ht LO t"!r)b l/X.j3'-'I{:;::;'''HI ES INTERlOCK to£S.ei INTERlOCK WITH ES fit.'..'-"..INtERlOCK WfTH ES:¥(q\J LD...c**(F1, r to., I--'r'\-_...J | |||
(.l'RF-ACTI1R 9111lO1NC EMlF.c.f.NO" SUMP)HI HI: LO LO HI HI to to.n en 011*--CAD FILE: 6512R15.DWG FIG 6.0-2 p.6.FIG-2 TMI UFSAR | |||
Figures 6.0-3 through 6.0-4 | Figures 6.0-3 through 6.0-4 Deleted | ||
TMI UFSAR | TMI UFSAR | ||
Figure 6.1-1 | Figure 6.1-1 Deleted | ||
NPSH. | NPSH.ft IMP (S.G...11)I I I ,/,'/:I:/en L L:I: z*I V f l=E=Q.QIO-=--u CQ Q.CQ==t"':t==N Total Developed Head, ft p.6.FIG-6 BimNuclear 1MI Unit-1 Makeup Pump Characteristics Update-1 7/82 Fig.6.1-2 | ||
*....*500- | *....*500-0 0*:t:-0 400*Q.0 300.oJ*>*c 200.oJ 0....100 00 ,....y-BPH-30 20:I: CJ)10o o 2 3 4 5 p.6.FIG-7 Capactty, gpm x 10'EJil!JN......TMI Untt I Decay Heat Re.oval Pu.p Charactertettce CADO ISIA.SKM.OO,0336.00I-.0000 Update-12 3/94 Ftg.6.1-3 211-.-..........::I...*...*..**...210 2&0 240 220 200 180 1&0 140 120 lao Coal.r lnl.t Ilt.r T**plraturl (Rllctor luildinl Sumpature)D.Sian Pirfar**nci Snj_ctaD" later'**p.rlture (Coaler Disch.rae re.perature) | ||
EIERCENCY DESIGN Injection Fl**'er Cooler*3000.,......---+-....-o+---......S.rvic***ter Flo.Pet Cooler.300a IPI service later Inlet 1111II.95 FE:)*10 1.1 120 28 40 60 80 IGO Hlet ,rlnst,rled, Itu/hr(I)Current design for he ervice Water Inlet temperature (Decay Closed Cooling Water System)is 99.5T.o p.6.FIG-8 UPDATE-14 4/98 DECAY HEAT REMOVAL COOLER CHARACTERISTICS CAD FILE: 6561R14.DWG FIG 6.1-4 TMI UFSAR | |||
Figure 6.2-1 | Figure 6.2-1 Deleted | ||
300 tL**,::J...0 0 l-*Q.**t-ea c:--"..J-:I a)L 0..0 0*IX 200 150 100 t£SIGN CXH)ITI(N; el)1001 Saturoted Atr (2) | |||
.. | ACFM Atr Fl**(3)ee"C**lln.W.,.r1710 GPM W.'er Fl**Cooler P".dtcted D**tgn P.rr*.-**no.D**t8n 80.'.Perf'.r**nce A.Provtd.d B, Manufacturer. | ||
o o 20..0 60 10 100 H**t Tran.'err.d.8tu/hr x 10-6 (Per Unit Ba.t.)UPDATE-14 4/98 he fan cooler heat removal rates in Fig.6.3-1 are based on the design conditions. | |||
This Figure does not reflect the current heat removal capability or conditions in the plant.See Section 6.3.2.p.8.FIG-10 | |||
--Reactor Building Emergency Cooler CAD FILE: 6559R14.DWG FIG 6.3-1 | |||
..N N N.., U CI Z N C*as 0-....-as*...*..*Z*c:a....--...***...........*..*....-as-...a..u...........N*Z M...-fa a......., c...**-"*0 c....a*u a-u z 0-w z z*0*N*******Z*-**......N-Totll H'la, It f i******N-IN, (Sp.er.*1.0)i I**-*:I**--*--........N-..'SM, ft I Efficilncy laj[J Nuclear'M'Unit-l Update-1 7/82 R.actor Building Spray Pump (BS-P 1 A)Performance Test p.6.FIG-ll Fig.6.4-1 TMI UFSAR | |||
Figure 6.5-1 | Figure 6.5-1 Deleted C"'I-==CD@-I I G r I L-e@I*-1ft;;Jl.......... | ||
...*-/I(,'-" | l_-_-....@------------,----..IT G e BE Nuclear TMI Unit-l Update-1 7/82 Multinode Representation of Nuclear Steam Supply System p.6.FIG-13 Fig.6.6-1 | ||
/ | ...*-/I (,'-" J I I I'""'--I.............'-., ,\I.\\\\\\r I*....****CDntllnllnt glulI Prlssure 0:imNuclear TMI Unit-1*--.....--e N CI-lilt.-'--CL*'-*--CI--c**CI CI-.CI-Update-1 7/82 p.6.FIG-14 Reactor Building Pressure Versus Time for 8.55 ft?Cold Leg Break (Pump Suction)Fig.6.6-2 u E...-=...-u--c I T I/J'I (\."'" I I I I\'--..""""'-......""""'--'"'""" 1\,\\\\\1 I CI....CI CD CI..Contlin.ent Glule Pressure Bil!l Nuclear TMI Unit-l Update-1 7/82 p.6.FIG-15 Reactor Pressure Versus Time for 7.0 ft Cold Leg Break suction)Fig.6.6-3 | ||
..,/'r,-//I/ | /J I""-, , J I t\"""""""""-r"..""""-""'lll"-'""""-I"-\\\*-e:::t--c**e:::t e:::t-.e:::t e:::t....e:::t co Contlinlent Glule Pressure BimNuclear TMI Unit-l o-Update-1 7/82 p.6.FIG-16 Reactor Building Pressure Versus Time for 5.13 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-4 i/J//I" I\\" I'-'-"'"......""'-""-I""\\\\\\\1 ,-Q CD---c CD E.-Q Q=..-=CD Containment GauRe Pressure Bi!I Nuclear 1MI Unit-1-I==-Update-1 7/82 p.6.FIG-17 Reactor Building Pressure Versus Time for 3.0 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-5 | ||
// | ..,/'r,-//I/t 1\I I\."-"-!'..."""'-'"""-"""-""\.\\T'£1 l\{.*:IQ,:I IX--o*oC**...o o-.o-o-o-Contlin.ent Glule Pressure[FfiE]Nuclear 1MI Unit-l o-Update-1 7/82 p.6.FIG-18 Reactor Building Pressure Versus Time for 2.0 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-6 1 I/I J\, I"............... | ||
..--// | ......."'"-""\\,\i\\\\\,...CI....CI*'-::IDo::I--CI'--::-c**............-..1ft.....Contaln.lnt aaUII Prlssurl........-.CI BimNuclear 1MI Unit-'Update-1 7/82 p.6.FIG-19 Reactor Building Pressure Versus Time for 0.5 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-7 | ||
/7, | //v J 7 , II (\'\-/V-...----Average Core Inlet Velocity, inJs B:il!I Nuclear TMI Unit-1 o o G E o a::a....Update-1 7/82 p.6.FIG-20 Average Core Inlet Velocity Versus Time for a 7.0 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-8 i 1/,/I J I'"\., I J I I/""'" ,,,,,,,,-""'-.i'-............ | ||
/'//I(\,,II\'I"",,.........................................'""'""'-\"-\,\\\\\N=..CLa:-=..---c..&.-o=.o-o-o..Contain. | -....."'JIiIo... | ||
! | '"'-I'""'" ,I" I"-'"\., 1\\\c-.....==-=a:: c-.....--c..*-c CI-CICantaiRient Gaule Pressure m!lNuclear TMI Unit-l CI-Update-1 7/82 p.6.FIG-21 Reactor Building Pressure Versus Time for 14.1 ft 2 Hot Leg Break Fi*6.6-9 | ||
..--//i I ,!:/i I If I I I I ,."'"\I I:!I I i I I J i/I , ,\I I I I t"""'"""'" ,...",'" I1'-.II I i I i'l ,...I" I" , I\\I\I\I I I , I I*...:=IQ.:=I a::-...a u---c**t-.a-a-a 1ft Contain**nt;au.I Pressure BE Nuclea, TMI Unit-1 a-Update-1 7/82 p.6.FIG-22 Reactor Building Pressure Versus Time for 11.0 ft 2 Hot Leg Break Fig.6.6-10 | |||
/7 , I I I\."\, J I J I\.........""-....,""""-""'"'\1\"\.,\\\\\ell-CD....-a.a::....CD e::t---c CD e.....e::t-.e::t Containment GauRe Pressure Bi[)Nuclear 1MI Unit-1 Update-1 7/82 p.6.FIG-23 Reactor Building Pressure Versus Time for 8.55 ft 2 Hot Leg Break Fig.6.6-11 | |||
/'//I (\, , II\'I"", ,................... | |||
...................... | |||
'""'""'-\"-\,\\\\\N=..CLa:-=..---c..&.-o=.o-o-o..Contain.ent Gaule Pressure o N o-Fig.6.6-12 p.6.FIG-24 Bil!J Nuclear TMI Unit-1 Reactor Building Pressure Versus Time for 5.0 ft 2 Hot Leg Break Update-1 7/82 | |||
!JO lV\/).,T,r" 1I'"""t I-.:10 20 30.to!JO 10 70 10 10 100 110 no 130 140 1 0.0 s.o 25.0 10.0 3O.u 31.0:i 20.0!;"" l 11.0 Time (sec:)......ItILAHlCONTlIlPT MW*10103.IIIG.,0 UPDATE-14 4/98 MINIMUM CONTAINMENT BACKPRESSURE p.6.FIG-25 CAD FILE: 6622R14.DWG FIG 6.6-13 FIG 6.0-1 6'"SS 6"55 FROM MNCEUP TANK WU-T1 14"'SS 6"SS 8" S5 8" S5 PIPE AND VALVE JACKETED lCfSS 10'S$RE'ACTOR BUILDING 2 1/Z"SS 21/1'SS ,_ | |||
lX'SS p.6.FIG-1 FROM RNER TO RIVER WATER...._-,.-,,,_DISCHARGE UNE UPDATE-15 04/00 MU-V14M en In'co v--"'''''''-ES SIMPLIFIED SCHEMA TIC DIAGRAM EMERGENCY CORE COOLING SYSTEM AmerGen TMI-UNIT 1 t.tU-V12 10":;5 j 1.r'3S VENT F.\HI t llA t/)'1)i.O BORATED WAfER LO':0&: LO-LO TANK&LO-LO DH-T1 00-\'59 DH-VSA ES'*DH-V7A" , UU-P1C MU-P19 WAKEUP PUMPS DH-Ci9 HI to'ES lOW Flaw AI.ARN Itm:RlDCK FROMHI..LO LOW flOW AlARM fNI'ERlOCK fftOY ES ES | |||
......-i><J-,... | |||
...--------------------....-uII MU-P1A INTERlOCK l.O ES FROM ES R8 14" 5S 14" 5S HI LO_.......... | |||
-...J Ht LO t"!r)b l/X.j3'-'I{:;::;'''HI ES INTERlOCK to£S.ei INTERlOCK WITH ES fit.'..'-"..INtERlOCK WfTH ES:¥(q\J LD...c**(F1, r to., I--'r'\-_...J | |||
(.l'RF-ACTI1R 9111lO1NC EMlF.c.f.NO" SUMP)HI HI: LO LO HI HI to to.n en 011*--CAD FILE: 6512R15.DWG FIG 6.0-2 p.6.FIG-2 TMI UFSAR | |||
Figures 6.0-3 through 6.0-4 | Figures 6.0-3 through 6.0-4 Deleted | ||
TMI UFSAR | TMI UFSAR | ||
Figure 6.1-1 | Figure 6.1-1 Deleted | ||
NPSH. | NPSH.ft IMP (S.G...11)I I I ,/,'/:I:/en L L:I: z*I V f l=E=Q.QIO-=--u CQ Q.CQ==t"':t==N Total Developed Head, ft p.6.FIG-6 BimNuclear 1MI Unit-1 Makeup Pump Characteristics Update-1 7/82 Fig.6.1-2 | ||
*....*500- | *....*500-0 0*:t:-0 400*Q.0 300.oJ*>*c 200.oJ 0....100 00 ,....y-BPH-30 20:I: CJ)10o o 2 3 4 5 p.6.FIG-7 Capactty, gpm x 10'EJil!JN......TMI Untt I Decay Heat Re.oval Pu.p Charactertettce CADO ISIA.SKM.OO,0336.00I-.0000 Update-12 3/94 Ftg.6.1-3 211-.-..........::I...*...*..**...210 2&0 240 220 200 180 1&0 140 120 lao Coal.r lnl.t Ilt.r T**plraturl (Rllctor luildinl Sumpature)D.Sian Pirfar**nci Snj_ctaD" later'**p.rlture (Coaler Disch.rae re.perature) | ||
EIERCENCY DESIGN Injection Fl**'er Cooler*3000.,......---+-....-o+---......S.rvic***ter Flo.Pet Cooler.300a IPI service later Inlet 1111II.95 FE:)*10 1.1 120 28 40 60 80 IGO Hlet ,rlnst,rled, Itu/hr(I)Current design for he ervice Water Inlet temperature (Decay Closed Cooling Water System)is 99.5T.o p.6.FIG-8 UPDATE-14 4/98 DECAY HEAT REMOVAL COOLER CHARACTERISTICS CAD FILE: 6561R14.DWG FIG 6.1-4 TMI UFSAR | |||
Figure 6.2-1 | Figure 6.2-1 Deleted | ||
300 tL**,::J...0 0 l-*Q.**t-ea c:--"..J-:I a)L 0..0 0*IX 200 150 100 t£SIGN CXH)ITI(N; el)1001 Saturoted Atr (2) | |||
.. | ACFM Atr Fl**(3)ee"C**lln.W.,.r1710 GPM W.'er Fl**Cooler P".dtcted D**tgn P.rr*.-**no.D**t8n 80.'.Perf'.r**nce A.Provtd.d B, Manufacturer. | ||
o o 20..0 60 10 100 H**t Tran.'err.d.8tu/hr x 10-6 (Per Unit Ba.t.)UPDATE-14 4/98 he fan cooler heat removal rates in Fig.6.3-1 are based on the design conditions. | |||
This Figure does not reflect the current heat removal capability or conditions in the plant.See Section 6.3.2.p.8.FIG-10 | |||
--Reactor Building Emergency Cooler CAD FILE: 6559R14.DWG FIG 6.3-1 | |||
..N N N.., U CI Z N C*as 0-....-as*...*..*Z*c:a....--...***...........*..*....-as-...a..u...........N*Z M...-fa a......., c...**-"*0 c....a*u a-u z 0-w z z*0*N*******Z*-**......N-Totll H'la, It f i******N-IN, (Sp.er.*1.0)i I**-*:I**--*--........N-..'SM, ft I Efficilncy laj[J Nuclear'M'Unit-l Update-1 7/82 R.actor Building Spray Pump (BS-P 1 A)Performance Test p.6.FIG-ll Fig.6.4-1 TMI UFSAR | |||
Figure 6.5-1 | Figure 6.5-1 Deleted C"'I-==CD@-I I G r I L-e@I*-1ft;;Jl.......... | ||
...*-/I(,'-" | l_-_-....@------------,----..IT G e BE Nuclear TMI Unit-l Update-1 7/82 Multinode Representation of Nuclear Steam Supply System p.6.FIG-13 Fig.6.6-1 | ||
/ | ...*-/I (,'-" J I I I'""'--I.............'-., ,\I.\\\\\\r I*....****CDntllnllnt glulI Prlssure 0:imNuclear TMI Unit-1*--.....--e N CI-lilt.-'--CL*'-*--CI--c**CI CI-.CI-Update-1 7/82 p.6.FIG-14 Reactor Building Pressure Versus Time for 8.55 ft?Cold Leg Break (Pump Suction)Fig.6.6-2 u E...-=...-u--c I T I/J'I (\."'" I I I I\'--..""""'-......""""'--'"'""" 1\,\\\\\1 I CI....CI CD CI..Contlin.ent Glule Pressure Bil!l Nuclear TMI Unit-l Update-1 7/82 p.6.FIG-15 Reactor Pressure Versus Time for 7.0 ft Cold Leg Break suction)Fig.6.6-3 | ||
..,/'r,-//I/ | /J I""-, , J I t\"""""""""-r"..""""-""'lll"-'""""-I"-\\\*-e:::t--c**e:::t e:::t-.e:::t e:::t....e:::t co Contlinlent Glule Pressure BimNuclear TMI Unit-l o-Update-1 7/82 p.6.FIG-16 Reactor Building Pressure Versus Time for 5.13 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-4 i/J//I" I\\" I'-'-"'"......""'-""-I""\\\\\\\1 ,-Q CD---c CD E.-Q Q=..-=CD Containment GauRe Pressure Bi!I Nuclear 1MI Unit-1-I==-Update-1 7/82 p.6.FIG-17 Reactor Building Pressure Versus Time for 3.0 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-5 | ||
// | ..,/'r,-//I/t 1\I I\."-"-!'..."""'-'"""-"""-""\.\\T'£1 l\{.*:IQ,:I IX--o*oC**...o o-.o-o-o-Contlin.ent Glule Pressure[FfiE]Nuclear 1MI Unit-l o-Update-1 7/82 p.6.FIG-18 Reactor Building Pressure Versus Time for 2.0 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-6 1 I/I J\, I"............... | ||
..--// | ......."'"-""\\,\i\\\\\,...CI....CI*'-::IDo::I--CI'--::-c**............-..1ft.....Contaln.lnt aaUII Prlssurl........-.CI BimNuclear 1MI Unit-'Update-1 7/82 p.6.FIG-19 Reactor Building Pressure Versus Time for 0.5 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-7 | ||
/7, | //v J 7 , II (\'\-/V-...----Average Core Inlet Velocity, inJs B:il!I Nuclear TMI Unit-1 o o G E o a::a....Update-1 7/82 p.6.FIG-20 Average Core Inlet Velocity Versus Time for a 7.0 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-8 i 1/,/I J I'"\., I J I I/""'" ,,,,,,,,-""'-.i'-............ | ||
/'//I(\,,II\'I"",,.........................................'""'""'-\"-\,\\\\\N=..CLa:-=..---c..&.-o=.o-o-o..Contain. | -....."'JIiIo... | ||
! | '"'-I'""'" ,I" I"-'"\., 1\\\c-.....==-=a:: c-.....--c..*-c CI-CICantaiRient Gaule Pressure m!lNuclear TMI Unit-l CI-Update-1 7/82 p.6.FIG-21 Reactor Building Pressure Versus Time for 14.1 ft 2 Hot Leg Break Fi*6.6-9 | ||
..--//i I ,!:/i I If I I I I ,."'"\I I:!I I i I I J i/I , ,\I I I I t"""'"""'" ,...",'" I1'-.II I i I i'l ,...I" I" , I\\I\I\I I I , I I*...:=IQ.:=I a::-...a u---c**t-.a-a-a 1ft Contain**nt;au.I Pressure BE Nuclea, TMI Unit-1 a-Update-1 7/82 p.6.FIG-22 Reactor Building Pressure Versus Time for 11.0 ft 2 Hot Leg Break Fig.6.6-10 | |||
/7 , I I I\."\, J I J I\.........""-....,""""-""'"'\1\"\.,\\\\\ell-CD....-a.a::....CD e::t---c CD e.....e::t-.e::t Containment GauRe Pressure Bi[)Nuclear 1MI Unit-1 Update-1 7/82 p.6.FIG-23 Reactor Building Pressure Versus Time for 8.55 ft 2 Hot Leg Break Fig.6.6-11 | |||
/'//I (\, , II\'I"", ,................... | |||
...................... | |||
'""'""'-\"-\,\\\\\N=..CLa:-=..---c..&.-o=.o-o-o..Contain.ent Gaule Pressure o N o-Fig.6.6-12 p.6.FIG-24 Bil!J Nuclear TMI Unit-1 Reactor Building Pressure Versus Time for 5.0 ft 2 Hot Leg Break Update-1 7/82 | |||
!JO lV\/).,T,r" 1I'"""t I-.:10 20 30.to!JO 10 70 10 10 100 110 no 130 140 1 0.0 s.o 25.0 10.0 3O.u 31.0:i 20.0!;"" l 11.0 Time (sec:)......ItILAHlCONTlIlPT MW*10103.IIIG.,0 UPDATE-14 4/98 MINIMUM CONTAINMENT BACKPRESSURE p.6.FIG-25 CAD FILE: 6622R14.DWG FIG 6.6-13}} | |||
Latest revision as of 10:54, 8 July 2018
Text
FIG 6.0-1 6'"SS 6"55 FROM MNCEUP TANK WU-T1 14"'SS 6"SS 8" S5 8" S5 PIPE AND VALVE JACKETED lCfSS 10'S$RE'ACTOR BUILDING 2 1/Z"SS 21/1'SS ,_
lX'SS p.6.FIG-1 FROM RNER TO RIVER WATER...._-,.-,,,_DISCHARGE UNE UPDATE-15 04/00 MU-V14M en In'co v--"''-ES SIMPLIFIED SCHEMA TIC DIAGRAM EMERGENCY CORE COOLING SYSTEM AmerGen TMI-UNIT 1 t.tU-V12 10":;5 j 1.r'3S VENT F.\HI t llA t/)'1)i.O BORATED WAfER LO':0&: LO-LO TANK&LO-LO DH-T1 00-\'59 DH-VSA ES'*DH-V7A" , UU-P1C MU-P19 WAKEUP PUMPS DH-Ci9 HI to'ES lOW Flaw AI.ARN Itm:RlDCK FROMHI..LO LOW flOW AlARM fNI'ERlOCK fftOY ES ES
......-i><J-,...
...--------------------....-uII MU-P1A INTERlOCK l.O ES FROM ES R8 14" 5S 14" 5S HI LO_..........
-...J Ht LO t"!r)b l/X.j3'-'I{:;::;HI ES INTERlOCK to£S.ei INTERlOCK WITH ES fit.'..'-"..INtERlOCK WfTH ES:¥(q\J LD...c**(F1, r to., I--'r'\-_...J
(.l'RF-ACTI1R 9111lO1NC EMlF.c.f.NO" SUMP)HI HI: LO LO HI HI to to.n en 011*--CAD FILE: 6512R15.DWG FIG 6.0-2 p.6.FIG-2 TMI UFSAR
Figures 6.0-3 through 6.0-4 Deleted
Figure 6.1-1 Deleted
NPSH.ft IMP (S.G...11)I I I ,/,'/:I:/en L L:I: z*I V f l=E=Q.QIO-=--u CQ Q.CQ==t"':t==N Total Developed Head, ft p.6.FIG-6 BimNuclear 1MI Unit-1 Makeup Pump Characteristics Update-1 7/82 Fig.6.1-2
- ....*500-0 0*:t:-0 400*Q.0 300.oJ*>*c 200.oJ 0....100 00 ,....y-BPH-30 20:I: CJ)10o o 2 3 4 5 p.6.FIG-7 Capactty, gpm x 10'EJil!JN......TMI Untt I Decay Heat Re.oval Pu.p Charactertettce CADO ISIA.SKM.OO,0336.00I-.0000 Update-12 3/94 Ftg.6.1-3 211-.-..........::I...*...*..**...210 2&0 240 220 200 180 1&0 140 120 lao Coal.r lnl.t Ilt.r T**plraturl (Rllctor luildinl Sumpature)D.Sian Pirfar**nci Snj_ctaD" later'**p.rlture (Coaler Disch.rae re.perature)
EIERCENCY DESIGN Injection Fl**'er Cooler*3000.,......---+-....-o+---......S.rvic***ter Flo.Pet Cooler.300a IPI service later Inlet 1111II.95 FE:)*10 1.1 120 28 40 60 80 IGO Hlet ,rlnst,rled, Itu/hr(I)Current design for he ervice Water Inlet temperature (Decay Closed Cooling Water System)is 99.5T.o p.6.FIG-8 UPDATE-14 4/98 DECAY HEAT REMOVAL COOLER CHARACTERISTICS CAD FILE: 6561R14.DWG FIG 6.1-4 TMI UFSAR
Figure 6.2-1 Deleted
300 tL**,::J...0 0 l-*Q.**t-ea c:--"..J-:I a)L 0..0 0*IX 200 150 100 t£SIGN CXH)ITI(N; el)1001 Saturoted Atr (2)
ACFM Atr Fl**(3)ee"C**lln.W.,.r1710 GPM W.'er Fl**Cooler P".dtcted D**tgn P.rr*.-**no.D**t8n 80.'.Perf'.r**nce A.Provtd.d B, Manufacturer.
o o 20..0 60 10 100 H**t Tran.'err.d.8tu/hr x 10-6 (Per Unit Ba.t.)UPDATE-14 4/98 he fan cooler heat removal rates in Fig.6.3-1 are based on the design conditions.
This Figure does not reflect the current heat removal capability or conditions in the plant.See Section 6.3.2.p.8.FIG-10
--Reactor Building Emergency Cooler CAD FILE: 6559R14.DWG FIG 6.3-1
..N N N.., U CI Z N C*as 0-....-as*...*..*Z*c:a....--...***...........*..*....-as-...a..u...........N*Z M...-fa a......., c...**-"*0 c....a*u a-u z 0-w z z*0*N*******Z*-**......N-Totll H'la, It f i******N-IN, (Sp.er.*1.0)i I**-*:I**--*--........N-..'SM, ft I Efficilncy laj[J Nuclear'M'Unit-l Update-1 7/82 R.actor Building Spray Pump (BS-P 1 A)Performance Test p.6.FIG-ll Fig.6.4-1 TMI UFSAR
Figure 6.5-1 Deleted C"'I-==CD@-I I G r I L-e@I*-1ft;;Jl..........
l_-_-....@------------,----..IT G e BE Nuclear TMI Unit-l Update-1 7/82 Multinode Representation of Nuclear Steam Supply System p.6.FIG-13 Fig.6.6-1
...*-/I (,'-" J I I I'""'--I.............'-., ,\I.\\\\\\r I*....****CDntllnllnt glulI Prlssure 0:imNuclear TMI Unit-1*--.....--e N CI-lilt.-'--CL*'-*--CI--c**CI CI-.CI-Update-1 7/82 p.6.FIG-14 Reactor Building Pressure Versus Time for 8.55 ft?Cold Leg Break (Pump Suction)Fig.6.6-2 u E...-=...-u--c I T I/J'I (\."'" I I I I\'--..""""'-......""""'--'"'""" 1\,\\\\\1 I CI....CI CD CI..Contlin.ent Glule Pressure Bil!l Nuclear TMI Unit-l Update-1 7/82 p.6.FIG-15 Reactor Pressure Versus Time for 7.0 ft Cold Leg Break suction)Fig.6.6-3
/J I""-, , J I t\"""""""""-r"..""""-""'lll"-'""""-I"-\\\*-e:::t--c**e:::t e:::t-.e:::t e:::t....e:::t co Contlinlent Glule Pressure BimNuclear TMI Unit-l o-Update-1 7/82 p.6.FIG-16 Reactor Building Pressure Versus Time for 5.13 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-4 i/J//I" I\\" I'-'-"'"......""'-""-I""\\\\\\\1 ,-Q CD---c CD E.-Q Q=..-=CD Containment GauRe Pressure Bi!I Nuclear 1MI Unit-1-I==-Update-1 7/82 p.6.FIG-17 Reactor Building Pressure Versus Time for 3.0 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-5
..,/'r,-//I/t 1\I I\."-"-!'..."""'-'"""-"""-""\.\\T'£1 l\{.*:IQ,:I IX--o*oC**...o o-.o-o-o-Contlin.ent Glule Pressure[FfiE]Nuclear 1MI Unit-l o-Update-1 7/82 p.6.FIG-18 Reactor Building Pressure Versus Time for 2.0 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-6 1 I/I J\, I"...............
......."'"-""\\,\i\\\\\,...CI....CI*'-::IDo::I--CI'--::-c**............-..1ft.....Contaln.lnt aaUII Prlssurl........-.CI BimNuclear 1MI Unit-'Update-1 7/82 p.6.FIG-19 Reactor Building Pressure Versus Time for 0.5 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-7
//v J 7 , II (\'\-/V-...----Average Core Inlet Velocity, inJs B:il!I Nuclear TMI Unit-1 o o G E o a::a....Update-1 7/82 p.6.FIG-20 Average Core Inlet Velocity Versus Time for a 7.0 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-8 i 1/,/I J I'"\., I J I I/""'" ,,,,,,,,-""'-.i'-............
-....."'JIiIo...
'"'-I'""'" ,I" I"-'"\., 1\\\c-.....==-=a:: c-.....--c..*-c CI-CICantaiRient Gaule Pressure m!lNuclear TMI Unit-l CI-Update-1 7/82 p.6.FIG-21 Reactor Building Pressure Versus Time for 14.1 ft 2 Hot Leg Break Fi*6.6-9
..--//i I ,!:/i I If I I I I ,."'"\I I:!I I i I I J i/I , ,\I I I I t"""'"""'" ,...",'" I1'-.II I i I i'l ,...I" I" , I\\I\I\I I I , I I*...:=IQ.:=I a::-...a u---c**t-.a-a-a 1ft Contain**nt;au.I Pressure BE Nuclea, TMI Unit-1 a-Update-1 7/82 p.6.FIG-22 Reactor Building Pressure Versus Time for 11.0 ft 2 Hot Leg Break Fig.6.6-10
/7 , I I I\."\, J I J I\.........""-....,""""-""'"'\1\"\.,\\\\\ell-CD....-a.a::....CD e::t---c CD e.....e::t-.e::t Containment GauRe Pressure Bi[)Nuclear 1MI Unit-1 Update-1 7/82 p.6.FIG-23 Reactor Building Pressure Versus Time for 8.55 ft 2 Hot Leg Break Fig.6.6-11
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'""'""'-\"-\,\\\\\N=..CLa:-=..---c..&.-o=.o-o-o..Contain.ent Gaule Pressure o N o-Fig.6.6-12 p.6.FIG-24 Bil!J Nuclear TMI Unit-1 Reactor Building Pressure Versus Time for 5.0 ft 2 Hot Leg Break Update-1 7/82
!JO lV\/).,T,r" 1I'"""t I-.:10 20 30.to!JO 10 70 10 10 100 110 no 130 140 1 0.0 s.o 25.0 10.0 3O.u 31.0:i 20.0!;"" l 11.0 Time (sec:)......ItILAHlCONTlIlPT MW*10103.IIIG.,0 UPDATE-14 4/98 MINIMUM CONTAINMENT BACKPRESSURE p.6.FIG-25 CAD FILE: 6622R14.DWG FIG 6.6-13 FIG 6.0-1 6'"SS 6"55 FROM MNCEUP TANK WU-T1 14"'SS 6"SS 8" S5 8" S5 PIPE AND VALVE JACKETED lCfSS 10'S$RE'ACTOR BUILDING 2 1/Z"SS 21/1'SS ,_
lX'SS p.6.FIG-1 FROM RNER TO RIVER WATER...._-,.-,,,_DISCHARGE UNE UPDATE-15 04/00 MU-V14M en In'co v--"''-ES SIMPLIFIED SCHEMA TIC DIAGRAM EMERGENCY CORE COOLING SYSTEM AmerGen TMI-UNIT 1 t.tU-V12 10":;5 j 1.r'3S VENT F.\HI t llA t/)'1)i.O BORATED WAfER LO':0&: LO-LO TANK&LO-LO DH-T1 00-\'59 DH-VSA ES'*DH-V7A" , UU-P1C MU-P19 WAKEUP PUMPS DH-Ci9 HI to'ES lOW Flaw AI.ARN Itm:RlDCK FROMHI..LO LOW flOW AlARM fNI'ERlOCK fftOY ES ES
......-i><J-,...
...--------------------....-uII MU-P1A INTERlOCK l.O ES FROM ES R8 14" 5S 14" 5S HI LO_..........
-...J Ht LO t"!r)b l/X.j3'-'I{:;::;HI ES INTERlOCK to£S.ei INTERlOCK WITH ES fit.'..'-"..INtERlOCK WfTH ES:¥(q\J LD...c**(F1, r to., I--'r'\-_...J
(.l'RF-ACTI1R 9111lO1NC EMlF.c.f.NO" SUMP)HI HI: LO LO HI HI to to.n en 011*--CAD FILE: 6512R15.DWG FIG 6.0-2 p.6.FIG-2 TMI UFSAR
Figures 6.0-3 through 6.0-4 Deleted
Figure 6.1-1 Deleted
NPSH.ft IMP (S.G...11)I I I ,/,'/:I:/en L L:I: z*I V f l=E=Q.QIO-=--u CQ Q.CQ==t"':t==N Total Developed Head, ft p.6.FIG-6 BimNuclear 1MI Unit-1 Makeup Pump Characteristics Update-1 7/82 Fig.6.1-2
- ....*500-0 0*:t:-0 400*Q.0 300.oJ*>*c 200.oJ 0....100 00 ,....y-BPH-30 20:I: CJ)10o o 2 3 4 5 p.6.FIG-7 Capactty, gpm x 10'EJil!JN......TMI Untt I Decay Heat Re.oval Pu.p Charactertettce CADO ISIA.SKM.OO,0336.00I-.0000 Update-12 3/94 Ftg.6.1-3 211-.-..........::I...*...*..**...210 2&0 240 220 200 180 1&0 140 120 lao Coal.r lnl.t Ilt.r T**plraturl (Rllctor luildinl Sumpature)D.Sian Pirfar**nci Snj_ctaD" later'**p.rlture (Coaler Disch.rae re.perature)
EIERCENCY DESIGN Injection Fl**'er Cooler*3000.,......---+-....-o+---......S.rvic***ter Flo.Pet Cooler.300a IPI service later Inlet 1111II.95 FE:)*10 1.1 120 28 40 60 80 IGO Hlet ,rlnst,rled, Itu/hr(I)Current design for he ervice Water Inlet temperature (Decay Closed Cooling Water System)is 99.5T.o p.6.FIG-8 UPDATE-14 4/98 DECAY HEAT REMOVAL COOLER CHARACTERISTICS CAD FILE: 6561R14.DWG FIG 6.1-4 TMI UFSAR
Figure 6.2-1 Deleted
300 tL**,::J...0 0 l-*Q.**t-ea c:--"..J-:I a)L 0..0 0*IX 200 150 100 t£SIGN CXH)ITI(N; el)1001 Saturoted Atr (2)
ACFM Atr Fl**(3)ee"C**lln.W.,.r1710 GPM W.'er Fl**Cooler P".dtcted D**tgn P.rr*.-**no.D**t8n 80.'.Perf'.r**nce A.Provtd.d B, Manufacturer.
o o 20..0 60 10 100 H**t Tran.'err.d.8tu/hr x 10-6 (Per Unit Ba.t.)UPDATE-14 4/98 he fan cooler heat removal rates in Fig.6.3-1 are based on the design conditions.
This Figure does not reflect the current heat removal capability or conditions in the plant.See Section 6.3.2.p.8.FIG-10
--Reactor Building Emergency Cooler CAD FILE: 6559R14.DWG FIG 6.3-1
..N N N.., U CI Z N C*as 0-....-as*...*..*Z*c:a....--...***...........*..*....-as-...a..u...........N*Z M...-fa a......., c...**-"*0 c....a*u a-u z 0-w z z*0*N*******Z*-**......N-Totll H'la, It f i******N-IN, (Sp.er.*1.0)i I**-*:I**--*--........N-..'SM, ft I Efficilncy laj[J Nuclear'M'Unit-l Update-1 7/82 R.actor Building Spray Pump (BS-P 1 A)Performance Test p.6.FIG-ll Fig.6.4-1 TMI UFSAR
Figure 6.5-1 Deleted C"'I-==CD@-I I G r I L-e@I*-1ft;;Jl..........
l_-_-....@------------,----..IT G e BE Nuclear TMI Unit-l Update-1 7/82 Multinode Representation of Nuclear Steam Supply System p.6.FIG-13 Fig.6.6-1
...*-/I (,'-" J I I I'""'--I.............'-., ,\I.\\\\\\r I*....****CDntllnllnt glulI Prlssure 0:imNuclear TMI Unit-1*--.....--e N CI-lilt.-'--CL*'-*--CI--c**CI CI-.CI-Update-1 7/82 p.6.FIG-14 Reactor Building Pressure Versus Time for 8.55 ft?Cold Leg Break (Pump Suction)Fig.6.6-2 u E...-=...-u--c I T I/J'I (\."'" I I I I\'--..""""'-......""""'--'"'""" 1\,\\\\\1 I CI....CI CD CI..Contlin.ent Glule Pressure Bil!l Nuclear TMI Unit-l Update-1 7/82 p.6.FIG-15 Reactor Pressure Versus Time for 7.0 ft Cold Leg Break suction)Fig.6.6-3
/J I""-, , J I t\"""""""""-r"..""""-""'lll"-'""""-I"-\\\*-e:::t--c**e:::t e:::t-.e:::t e:::t....e:::t co Contlinlent Glule Pressure BimNuclear TMI Unit-l o-Update-1 7/82 p.6.FIG-16 Reactor Building Pressure Versus Time for 5.13 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-4 i/J//I" I\\" I'-'-"'"......""'-""-I""\\\\\\\1 ,-Q CD---c CD E.-Q Q=..-=CD Containment GauRe Pressure Bi!I Nuclear 1MI Unit-1-I==-Update-1 7/82 p.6.FIG-17 Reactor Building Pressure Versus Time for 3.0 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-5
..,/'r,-//I/t 1\I I\."-"-!'..."""'-'"""-"""-""\.\\T'£1 l\{.*:IQ,:I IX--o*oC**...o o-.o-o-o-Contlin.ent Glule Pressure[FfiE]Nuclear 1MI Unit-l o-Update-1 7/82 p.6.FIG-18 Reactor Building Pressure Versus Time for 2.0 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-6 1 I/I J\, I"...............
......."'"-""\\,\i\\\\\,...CI....CI*'-::IDo::I--CI'--::-c**............-..1ft.....Contaln.lnt aaUII Prlssurl........-.CI BimNuclear 1MI Unit-'Update-1 7/82 p.6.FIG-19 Reactor Building Pressure Versus Time for 0.5 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-7
//v J 7 , II (\'\-/V-...----Average Core Inlet Velocity, inJs B:il!I Nuclear TMI Unit-1 o o G E o a::a....Update-1 7/82 p.6.FIG-20 Average Core Inlet Velocity Versus Time for a 7.0 ft 2 Cold Leg Break (Pump Suction)Fig.6.6-8 i 1/,/I J I'"\., I J I I/""'" ,,,,,,,,-""'-.i'-............
-....."'JIiIo...
'"'-I'""'" ,I" I"-'"\., 1\\\c-.....==-=a:: c-.....--c..*-c CI-CICantaiRient Gaule Pressure m!lNuclear TMI Unit-l CI-Update-1 7/82 p.6.FIG-21 Reactor Building Pressure Versus Time for 14.1 ft 2 Hot Leg Break Fi*6.6-9
..--//i I ,!:/i I If I I I I ,."'"\I I:!I I i I I J i/I , ,\I I I I t"""'"""'" ,...",'" I1'-.II I i I i'l ,...I" I" , I\\I\I\I I I , I I*...:=IQ.:=I a::-...a u---c**t-.a-a-a 1ft Contain**nt;au.I Pressure BE Nuclea, TMI Unit-1 a-Update-1 7/82 p.6.FIG-22 Reactor Building Pressure Versus Time for 11.0 ft 2 Hot Leg Break Fig.6.6-10
/7 , I I I\."\, J I J I\.........""-....,""""-""'"'\1\"\.,\\\\\ell-CD....-a.a::....CD e::t---c CD e.....e::t-.e::t Containment GauRe Pressure Bi[)Nuclear 1MI Unit-1 Update-1 7/82 p.6.FIG-23 Reactor Building Pressure Versus Time for 8.55 ft 2 Hot Leg Break Fig.6.6-11
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......................
'""'""'-\"-\,\\\\\N=..CLa:-=..---c..&.-o=.o-o-o..Contain.ent Gaule Pressure o N o-Fig.6.6-12 p.6.FIG-24 Bil!J Nuclear TMI Unit-1 Reactor Building Pressure Versus Time for 5.0 ft 2 Hot Leg Break Update-1 7/82
!JO lV\/).,T,r" 1I'"""t I-.:10 20 30.to!JO 10 70 10 10 100 110 no 130 140 1 0.0 s.o 25.0 10.0 3O.u 31.0:i 20.0!;"" l 11.0 Time (sec:)......ItILAHlCONTlIlPT MW*10103.IIIG.,0 UPDATE-14 4/98 MINIMUM CONTAINMENT BACKPRESSURE p.6.FIG-25 CAD FILE: 6622R14.DWG FIG 6.6-13