ML16127A485

008_04 Reactor Coolant SYSTEM-Figures

ML16127A485
Person / Time
Site:	Three Mile Island
Issue date:	04/11/2016
From:	Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML16127A520	List: ML16127A469 ML16127A471 ML16127A474 ML16127A476 ML16127A477 ML16127A479 ML16127A480 ML16127A481 ML16127A483 ML16127A484 ML16127A485 ML16127A486 ML16127A491 ML16127A492 ML16127A493 ML16127A494 ML16127A495 ML16127A496 ML16127A498 ML16127A499 ML16127A500 ML16127A501 ML16127A502 ML16127A503 ML16127A504 ML16127A506 ML16127A507 ML16127A508 ML16127A510 ML16127A511 ML16127A512 ML16127A513 ML16127A514 ML16127A516 ML16127A517 ML16127A518 ML16127A519 ML16127A521 ML16130A150 ML16130A151 ML16130A152 ML16130A153 ML16130A154 ML16130A155 ML16130A156 ML16130A157 ML16130A158 ML16130A159 ML16130A161 ML16130A162 ... further results
References
TMI-16-035
Download: ML16127A485 (13)

Text

TMI UFSAR

Figure 4.2-1 Deleted

8'-0" 79 1-8 J/2 31 1-0" 9 1-0"

_l 2ijl-O"[ffi1!]Nuclear TMI Unit-1 Update-1 7/82 p.4.FIG-2 Reactor Coolant System Arrangement

-Elevation Fig.4.2-2 3 1-J I 5/8" 11 1-10 1 1-3 21/32" I/ijl l 111-625/32" la]!]Nuclear 1MI Unit-1 30 1-7 5/8" Update-1 7/82 p.4.FIG-3 Reactor Coolant System Arrangement

-Plan Fig.4.2-3 p.4.FIG-4 CORE fLOODl1I6___IIOZZLU (21"-11 fORGIRGS IlIII89lll IlIllIlIlil COOL"'I OIITL£T IIOZZLU 121"-Ill fOR'11I65 1125T300VA-II 1125T300VA-21 METAL RUlECTI VE.RSULATIOlI 20'-II" e ACROSS ROULE FACUI_______-CLOSuRE SIUOS MIl-25 161103661 COOl"'l IRltT ROZZlES 1111"-II fORGIRGS 11261331 VA-II 11261331 VA-II 11221111 VA-21-----r e 1221212 VA-21 21" 311'-0" MIl-16 fORGIRG C122122I1U*

II 5U I DE LUGSIMCORE IMS1RUMUUlIOM MOULlS e521 TMI Unit-1 Reactor Vessel Outline Update-1 7/82 Fig.4.2-4 P 4.FIG-5 UPPER HIGH LEV£!.EMERGENCY fEEOWATER INlET UPPER HIGH LEVEL SENSING UPPER LOW lEvEL SENSING lOW LEVEl TMI-1 Updated Final Safety Analysis Report STEAM GENERATOR OUTLINE Figure 4.2-5 Rev.20, 04110 TMI-1 UFSAR Rev. 20, APRIL 2010

Figure 4.2-6 Deleted VENT NOZZlE-SPRAY NOZZLE----VESSEL SUPPORTS ROTATED RELIEF VALVE NOZZLE (TYP OF 3)SPRAY LINE NOZZLE LEVEL SENSING NOZZLE (TYP OF 3)STEAM SPACE NORMAL lATER LEVEL THERMOIEll (SAMPLE NOZZLE BEHIND)HEATER BUNDLE LEVEL SENSING NOZZLE (TYP OF 3)

SURGE DIFFUSER------SURIiE liNE NOZZLE p.4.FIG-7 lai!l Nuclear 1MI Unit-l Pressurizer Outline Update-1 7/82 Fig.4.2-7

..,, -?' .. N I co 1' Q I 00 :D CD m n po+ 0 ... n 0 0 ar po+ ,, c a 'a =* z c -o -I .. c 'Cl a. ....., ........_

CD CQ I ...... O> lfo. 1 SEAL VAPOR LEAKAGE LEAKOFF TO ATMOSPHERE

• • 2 SEAL LEAKOFF UPPER SEAL HOUSING PUMP SHAFT LOWER SEAL HOUSING MAIN FLANGE COOLING WA TEI COOLING WATER OUTLET INLET RADIAL BEARINt ASSEMBLY DISCHARGE NOZZLE Labyrinth Seal Diffuser and Tberll&l.

larrier CASING SUCTION

'--------------------IMPELLE*

/V v-7-I-+J C.-0 A.C QO-.-en u c:a--=C")-=N....e:::t-.-==...E a.=ao aJ.....Q=ut CD'C C<<J en=:::J f'"'"-a.c...=CD*0=L&-in==(")CI N CI--Tot aIH I ad ,ft 1MI Unit-1 Update-1 7/82 p.4.FIG-9 Reactor Coolant Pumps Estimated Performance Characteristics Fig.4.2-9 620 Reactor Outlet Temperature 600--JI Ste....T e",p.LA............

.580 Q)" Reactor Average":::J+'Tetnperature tUQ)a.E 560 Q)....Reactor Inlet Temperature 5aw 520 o 20 40&0 10 100 p.4.FIG-IO Reactor Powr,%Bil!l Nuclear TMI Unit-1 Systems Temperature Versus Load Update-1 7/82 Fig.4.2-10 "0.....CJ I......:;""'1:J im......I>>CD CJ.CJ.ii'C:i"......-'CD OCJ.C=z::I Z c::'.'C-4 I-4-A n en-::r I:;;...<..CD...en c en::a CD I>>n...0...<CD en c: en!!."'a"'" CL...., I>>,.............

CD w CO I I N--240 200 160 z o-4-4120=r ,...." 80 40 oy3025 l/W 20/V/ I 5 Years of Ojleration

, I/I , o 0.2 0.4 0.6 0.8'1.01.2 1.41.61.82.02.2 2.4 2.6 2.8 3.0 Integrated Neutron Exposure (E>1 mev), n/cm 2 x 10-19 50012 4612 4612 4 6 Iii iii ii'..., z Integrated Neutron Exposure (E>I mev),n/cm 2 2.Curve from ASME Paper No.63-WA-JOO Numbers indicate references in Table NOTES: I.All data is for 30 ft-Ib"Fix"Maximum Curve For I o c:: n r+400 550 F Data (See Reference I, Table q-13)300 1----4-----t--+--t----t---

/Trend Curve For 200 550 F Data (See Reference 2, Table q-13)100 5

__13+-3/'14: 15 o I I'r+LJ I LL.JII U 10 18 10 19 10 20 10 21 r+o::J r+"<......*::J en"....CI:I"0 CI..*r+c::..CI:J n..CI*M CI"'C'+;.o I 1--06 Nwe c....N....m<(nC'D C_..:::I Z C'D en C'D c:_.-en....C;-I-...n C'D-ec I..I>>-C'D..z C'D c:-..0=m>c"C 0 en c:..C C'D.."'"'CI.." 0 a...I>>......................

CD w CO I I N...N TMI UFSAR

Figures 4.3-3 through 4.3-5 Deleted

TMI UFSAR

Figure 4.2-1 Deleted

8'-0" 79 1-8 J/2 31 1-0" 9 1-0"

_l 2ijl-O"[ffi1!]Nuclear TMI Unit-1 Update-1 7/82 p.4.FIG-2 Reactor Coolant System Arrangement

-Elevation Fig.4.2-2 3 1-J I 5/8" 11 1-10 1 1-3 21/32" I/ijl l 111-625/32" la]!]Nuclear 1MI Unit-1 30 1-7 5/8" Update-1 7/82 p.4.FIG-3 Reactor Coolant System Arrangement

-Plan Fig.4.2-3 p.4.FIG-4 CORE fLOODl1I6___IIOZZLU (21"-11 fORGIRGS IlIII89lll IlIllIlIlil COOL"'I OIITL£T IIOZZLU 121"-Ill fOR'11I65 1125T300VA-II 1125T300VA-21 METAL RUlECTI VE.RSULATIOlI 20'-II" e ACROSS ROULE FACUI_______-CLOSuRE SIUOS MIl-25 161103661 COOl"'l IRltT ROZZlES 1111"-II fORGIRGS 11261331 VA-II 11261331 VA-II 11221111 VA-21-----r e 1221212 VA-21 21" 311'-0" MIl-16 fORGIRG C122122I1U*

II 5U I DE LUGSIMCORE IMS1RUMUUlIOM MOULlS e521 TMI Unit-1 Reactor Vessel Outline Update-1 7/82 Fig.4.2-4 P 4.FIG-5 UPPER HIGH LEV£!.EMERGENCY fEEOWATER INlET UPPER HIGH LEVEL SENSING UPPER LOW lEvEL SENSING lOW LEVEl TMI-1 Updated Final Safety Analysis Report STEAM GENERATOR OUTLINE Figure 4.2-5 Rev.20, 04110 TMI-1 UFSAR Rev. 20, APRIL 2010

Figure 4.2-6 Deleted VENT NOZZlE-SPRAY NOZZLE----VESSEL SUPPORTS ROTATED RELIEF VALVE NOZZLE (TYP OF 3)SPRAY LINE NOZZLE LEVEL SENSING NOZZLE (TYP OF 3)STEAM SPACE NORMAL lATER LEVEL THERMOIEll (SAMPLE NOZZLE BEHIND)HEATER BUNDLE LEVEL SENSING NOZZLE (TYP OF 3)

SURGE DIFFUSER------SURIiE liNE NOZZLE p.4.FIG-7 lai!l Nuclear 1MI Unit-l Pressurizer Outline Update-1 7/82 Fig.4.2-7

..,, -?' .. N I co 1' Q I 00 :D CD m n po+ 0 ... n 0 0 ar po+ ,, c a 'a =* z c -o -I .. c 'Cl a. ....., ........_

CD CQ I ...... O> lfo. 1 SEAL VAPOR LEAKAGE LEAKOFF TO ATMOSPHERE

• • 2 SEAL LEAKOFF UPPER SEAL HOUSING PUMP SHAFT LOWER SEAL HOUSING MAIN FLANGE COOLING WA TEI COOLING WATER OUTLET INLET RADIAL BEARINt ASSEMBLY DISCHARGE NOZZLE Labyrinth Seal Diffuser and Tberll&l.

larrier CASING SUCTION

'--------------------IMPELLE*

/V v-7-I-+J C.-0 A.C QO-.-en u c:a--=C")-=N....e:::t-.-==...E a.=ao aJ.....Q=ut CD'C C<<J en=:::J f'"'"-a.c...=CD*0=L&-in==(")CI N CI--Tot aIH I ad ,ft 1MI Unit-1 Update-1 7/82 p.4.FIG-9 Reactor Coolant Pumps Estimated Performance Characteristics Fig.4.2-9 620 Reactor Outlet Temperature 600--JI Ste....T e",p.LA............

.580 Q)" Reactor Average":::J+'Tetnperature tUQ)a.E 560 Q)....Reactor Inlet Temperature 5aw 520 o 20 40&0 10 100 p.4.FIG-IO Reactor Powr,%Bil!l Nuclear TMI Unit-1 Systems Temperature Versus Load Update-1 7/82 Fig.4.2-10 "0.....CJ I......:;""'1:J im......I>>CD CJ.CJ.ii'C:i"......-'CD OCJ.C=z::I Z c::'.'C-4 I-4-A n en-::r I:;;...<..CD...en c en::a CD I>>n...0...<CD en c: en!!."'a"'" CL...., I>>,.............

CD w CO I I N--240 200 160 z o-4-4120=r ,...." 80 40 oy3025 l/W 20/V/ I 5 Years of Ojleration

, I/I , o 0.2 0.4 0.6 0.8'1.01.2 1.41.61.82.02.2 2.4 2.6 2.8 3.0 Integrated Neutron Exposure (E>1 mev), n/cm 2 x 10-19 50012 4612 4612 4 6 Iii iii ii'..., z Integrated Neutron Exposure (E>I mev),n/cm 2 2.Curve from ASME Paper No.63-WA-JOO Numbers indicate references in Table NOTES: I.All data is for 30 ft-Ib"Fix"Maximum Curve For I o c:: n r+400 550 F Data (See Reference I, Table q-13)300 1----4-----t--+--t----t---

/Trend Curve For 200 550 F Data (See Reference 2, Table q-13)100 5

__13+-3/'14: 15 o I I'r+LJ I LL.JII U 10 18 10 19 10 20 10 21 r+o::J r+"<......*::J en"....CI:I"0 CI..*r+c::..CI:J n..CI*M CI"'C'+;.o I 1--06 Nwe c....N....m<(nC'D C_..:::I Z C'D en C'D c:_.-en....C;-I-...n C'D-ec I..I>>-C'D..z C'D c:-..0=m>c"C 0 en c:..C C'D.."'"'CI.." 0 a...I>>......................

CD w CO I I N...N TMI UFSAR

Figures 4.3-3 through 4.3-5 Deleted