ML18305A297

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0 to Updated Final Safety Analysis Report, Chapter 5, Appendix 5B, Figures
ML18305A297
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 04/14/2018
From:
Duke Energy Carolinas
To:
Office of Nuclear Reactor Regulation
Shared Package
ML18305A363 List:
References
RA-18-0200
Download: ML18305A297 (37)


Text

{{#Wiki_filter:Catawba Nuclear Station UFSAR Appendix 5B. Figures Appendix 5B. Figures

Catawba Nuclear Station UFSAR Figure 5-1 (Page 1 of 1) (17 APR 2012) Figure 5-1. Flow Diagram of Reactor Coolant System ( Unit 1 Only ) ? ..,re,-;;.-;-----i "~-~~----~ "\\ii,/ lllTE*-~~----7 ~ i '""I ~ i ~ i ' "'"' ---©-~----i .... _! ___ ¥'=-'---~ 'B,_________ CHEU"'"'"'"'...._ __ i 1111 IIHi !ill L_ i-----@;,..--;-,.... ~----~~-~" i ~ - - - -~--* - icii,, i ~ l,IITE. QA CONDITION! CATAWBA NUCLEAR 5TAHON UNIT 1 FLOIIDJAORAMOF REACTOR C~~~~NT SYSTEM

Catawba Nuclear Station UFSAR Figure 5-2 (Page 1 of 1) (17 APR 2012) Figure 5-2. Flow Diagram of Reactor Coolant System ( Unit 2 Only ) ~ i "~---@;,~---i ~ ""~-- 6 ~ ... -. - - -1 "'~--~~---: ' @} ~ I t----~;-.--"' i 7 I I ~- -----@;..~ __, '@---{,}.~.- -~ ------ ___ -_c:

Catawba Nuclear Station UFSAR Figure 5-3 (Page 1 of 1) (18 APR 2009) Figure 5-3. Flow Diagram of Reactor Coolant System

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Catawba Nuclear Station UFSAR Figure 5-4 (Page 1 of 1) (22 OCT 2001) Figure 5-4. Simplified Schematic of Reactor Vessel Head Vent System I D I ID. I - 19117 .,_ IIPPEll)III !I,, CIW'TBI !I TJ1III..EI - FJUUIIEI FIIIIIE &-14 IEIClllll VEIIIEL IENI WENT lll'IIIBI IDf'LIFIEII IIIHl¥ITIC .. ~ ..... IMLND.

Catawba Nuclear Station UFSAR Figure 5-5 (Page 1 of 1) (24 APR 2006) Figure 5-5. Flow Diagram of Reactor Coolant System ( Unit 1 Only ) .. *-1; !!!!!I m;111r 11111111

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Catawba Nuclear Station UFSAR Figure 5-6 (Page 1 of 1) (18 APR 2009) Figure 5-6. Flow Diagram of Reactor Coolant System I 8~ f ' y ~ I Bl I I f I Bl f I I Bl I I

Catawba Nuclear Station UFSAR Figure 5-7 (Page 1 of 1) (22 OCT 2001) Figure 5-7. Identification and Location of Catawba Unit 1 Reactor Vessel Beltline Region Weld and Forging Material CORE ..J ..J w

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Catawba Nuclear Station UFSAR Figure 5-8 (Page 1 of 1) (22 OCT 2001) Figure 5-8. Identification and Location of Catawba Unit 2 Reactor Vessel Beltline Region Weld and Plate Material CORE ...J ...J 101-142A Wt-------------

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Catawba Nuclear Station UFSAR Figure 5-9 (Page 1 of 2) (22 OCT 2001) Figure 5-9. Reactor Vessel

Catawba Nuclear Station UFSAR Figure 5-9 (Page 2 of 2) (22 OCT 2001)

Catawba Nuclear Station UFSAR Figure 5-10 (Page 1 of 1) (27 MAR 2003) Figure 5-10. Reactor Vessel Head View Showing Top-Mounted Control Rod Mechanism Housing Locations and Capped UHI Head Adaptors UH I HEAD ADAPTOR (Capped)

Catawba Nuclear Station UFSAR Figure 5-11 (Page 1 of 1) (27 MAR 2003) Figure 5-11. CRDM Head Adaptor

Catawba Nuclear Station UFSAR Figure 5-12 (Page 1 of 1) (22 OCT 2001) Figure 5-12. Reactor Coolant Controlled Leakage Pump FLYWHEEL THRUST BEARING MAIN LEAD CONDUIT BOX LOWER RADIAL __ -,-- BEARING NO. 3 SEAL LEAK OFF NO. 2 SEAL LEAK OFF PUMP SHAFT COOLING WATER INLET DISCHARGE NOZZLE WEIR SUCTION NOZZLE THRUST BEARING OIL LIFT PUMP PLUS MOTOR MOTOR UNIT ASSEMBLY SEAL HOUSING NO. 1 SEAL LEAK OFF MAIN FLANGE COOLING WATER OUTLET RADIAL BEARING ASSEMBLY THERMAL BARRIER AND HEAT EXCHANGER CASING IMPELLER

Catawba Nuclear Station UFSAR Figure 5-13 (Page 1 of 1) (22 OCT 2001) Figure 5-13. Reactor Coolant Pump Hot Performance Curve j J I '"'00 ------ I i-w f'-.-. 4J i.. I -400

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Catawba Nuclear Station UFSAR Figure 5-14 (Page 1 of 1) (22 OCT 2001) Figure 5-14. Steam Generator (Unit 1) S,E~H OUfLET NOZZLE STEAM ORUM HEAD STEAM Drn.JH MlltN FEE*W/ITER t..OZZLE RECIRCLLATION NOZZLE CONICAL SHELL LFPER LI\\TERAL Sllf'P*RT TRUNNION INSPECT1DN PORTS SECO~ARY Sf-ELL lUBE BUNDLE SLOIJOOWN fUZZLE Tl.llESHEET PR IMAAY HEAD 11'>1...ET/OUTLET NOZZLE SECONDARY CYCLONES PRIMARY CYCLDNES AU)(JLJI\\RY FEEDWATER NOZZLE FLAT BAR 'U'BEND RESTRAINT SYSTEM Li\\fTICE GRIDS PRIHJ\\RY HAN~AY

Catawba Nuclear Station UFSAR Figure 5-15 (Page 1 of 1) (22 OCT 2001) Figure 5-15. Counter Flow Preheat Steam Generator (Unit 2) Lower Narrow Range Level Tap, Coolant Inlet Steam Outlet To Turbine 1uoe tsunale Pre-heat area Tube Sheet Hanway

Catawba Nuclear Station UFSAR Figure 5-16 (Page 1 of 1) (27 MAR 2003) Figure 5-16. Flow Diagram of Conventional Chemical Addition System i!l lji ! i

Catawba Nuclear Station UFSAR Figure 5-17 (Page 1 of 1) (17 APR 2012) Figure 5-17. Flow Diagram of Residual Heat Removal System ,_1r QACQNDITIONZ QA CONDITION I DIG-... CN-FSAR-~;~_ 5_ 17

Catawba Nuclear Station UFSAR Figure 5-18 (Page 1 of 1) (17 APR 2012) Figure 5-18. Flow Diagram of Residual Heat Removal System ,--- - --- - - --- - - --- - - ---.~ --@-@--~ I 'I!"' I I I /ii,\\c f-~ y I I I---@ I I I I I ~:m@[b:_-* ~~~~+¥-~~~~ CATAWBAN=AR-=:'*NUNIT 1 FLO~

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Catawba Nuclear Station UFSAR Figure 5-19 and 5-20 (Page 1 of 1) (22 OCT 2001) Figure 5-19. Deleted Per 2000 Update Figure 5-20. Deleted Per 2000 Update

Catawba Nuclear Station UFSAR Figure 5-21 (Page 1 of 1) (22 OCT 2001) Figure 5-21. Pressurizer RELIEF NOZZLE~ ~ I HEAHR SUPPOR, PLATE. ~---;::,=----H~ SPRAY NOZZLE SAHH NOZZLE ~AHWAY OH NOZ2 LE INSTRUMENTAT I ll FTI NG TRUN ION LOWER HEAD Ow HOZZLE INSUUMENTATI ~ ELECTRICAL HATER SUPPORT SKIRT Su RGE HOU LE

Catawba Nuclear Station UFSAR Figure 5-22 (Page 1 of 1) (22 OCT 2001) Figure 5-22. Pressurizer Relief Tank DISCHARGE LINE CONNECTION VESSEL SUPPORT SPRAY WATER INLET ,~F--:-=-----= - iJ I I I I I I I I I I L _ _J I \\ \\ -r--- I '-L--- --- -:.==-==~+- -=--=--=f-=--=-----=-----=-~: l INTERNAL SPRAY u r~PARG£R PIP£ J.- ---r*--


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Catawba Nuclear Station UFSAR Figure 5-23 (Page 1 of 1) (22 OCT 2001) Figure 5-23. Typical Steam Generator Lower Lateral Support ~ ". A - * *.., iJ ,f.t, ~ 'Primary Shield Wall Steam Generator Lower Lateral Support / / Crane Wall ./

Catawba Nuclear Station UFSAR Figure 5-24 (Page 1 of 1) (22 OCT 2001) Figure 5-24. Typical Steam Generator Upper Support (Unit 2) \\"',,..,! Ste4m Ge er~tor

Catawba Nuclear Station UFSAR Figure 5-25 (Page 1 of 1) (22 OCT 2001) Figure 5-25. Typical Column Assembly for the Steam Generator and Reactor Coolant Pump

Catawba Nuclear Station UFSAR Figure 5-26 (Page 1 of 1) (22 OCT 2001) Figure 5-26. Typical Reactor Coolant Pump Lateral Support Bu~per ---l------7 Reactor Coolant Pump Lug Bumper Bumper rane Wall

Catawba Nuclear Station UFSAR Figure 5-27 (Page 1 of 1) (22 OCT 2001) Figure 5-27. Typical Reactor Coolant Pump Lateral Support Reactor Coolant Lug Bumper ----1------7 Bumper Bumper Crane Ha 1

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(22 OCT 2001) Figure 5-28. Pressurizer Support System Elevation Pressurizer O ~ '. d --~ ; i ~ **,t;, ** * ~-** ::4. El. 578 '+Bt,. 11 ~** -

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Catawba Nuclear Station UFSAR Figure 5-29 (Page 1 of 1) (22 OCT 2001) Figure 5-29. Pressurizer Lower Lateral Support -~ ,' /~' Pressu izer .**ti

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Catawba Nuclear Station UFSAR Figure 5-30 (Page 1 of 1) (22 OCT 2001) Figure 5-30. Pressurizer Upper Lateral Support /~._,.; ~ *:i

Catawba Nuclear Station UFSAR Figure 5-31 (Page 1 of 1) (22 OCT 2001) Figure 5-31. Typical Reactor Vessel Support I Primary <D Shield Wall --1 Reactor Vessel '.iupport Lug r r-- ~r-1 -- --=r r* I I I L_.i L 0 0 0 Primary Shield l-la 11

Catawba Nuclear Station UFSAR Figure 5-32 (Page 1 of 1) (22 OCT 2001) Figure 5-32. Typical Unit 1 Steam Generator Upper Support Support Ring __,( Operating J ---{_ Floor A._,

Catawba Nuclear Station UFSAR Figure 5-33 (Page 1 of 1) (22 OCT 2001) Figure 5-33. Flow Diagram of Unit 2 Reactor Coolant System (NC)

Catawba Nuclear Station UFSAR Figure 5-34 (Page 1 of 1) (15 NOV 2007) Figure 5-34. Flow Diagram of Unit 2 Reactor Coolant System (NC)

Catawba Nuclear Station UFSAR Figure 5-35 (Page 1 of 1) (21 OCT 2010) Figure 5-35. Reactor Coolant System 21EE/151aOFO!...,"""""'"'"""*"'TEIH0-17i,:C I iEE1151aOFO!Ml""'""'"'""""l*n--11voe I PEL.EIISEDF<I0!999F.. aLJ'D'TE OACONOITION2 QACONDITIONl CATAWBA~LEARSTATiaN~IT2 FLOW DIAGRAM OF REACTOR C~~~T SYSTEl-t

Catawba Nuclear Station UFSAR Figure 5-36 (Page 1 of 1) (21 OCT 2010) Figure 5-36. Conventional Chemical Addition (YA) N-FSAR-FIG.5-36

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