|
---|
Category:Drawing
MONTHYEARNRC-23-0062, Response to Request for Additional Information for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.122023-10-12012 October 2023 Response to Request for Additional Information for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 ML22325A1542022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Figures (for Public Use) ML21055A3012021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2512, Side Stream Lrwp System P&ID ML21055A3382021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-3045, Diagram Main Steam Isolation Valve Leakage Control System ML21055A3372021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6SD721-2530-01, Rev. AC, One Line Diagram, 120VAC Inst. & Cont., Power Feeders Division 1 & 2 Reactor Building ML21055A3352021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-4953, Radwaste Building Heating Ventilating and Air Conditioning Flow Diagram ML21055A3342021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721TS-2002-3, Technical Support Center Miscellaneous Diagrams of HVAC Systems ML21055A3332021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721N-2050, P & Id Equipment Drains & Floor Drains Divisions I & II R.H.R Complex ML21055A3322021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-5861, Process Diagram Core Spray System ML21055A3302021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6SD721-2530-10, One Line Diagram 260/130V Ess Dual Battery 2PA Distribution - Division I ML21055A3292021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6SD721-2530-11, One Line Diagram 260/130V. Ess. Dual Battery 2PB Distribution - Division II ML21055A3282021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-4945, Piping & Instrumentation Diagram Fill Station Auxiliaries, Cooling Water Booster Pumps ML21055A3272021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6SD721-2500-01, One Line Diagram Plant 4160V. & 480V. System Service ML21055A3262021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 4M721-5875, High Pressure Coolant Injection System-Simplified Drawing Test Mode During Plant Operation ML21055A3252021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6A721-2402, Fire Protection Evaluation Reactor and Auxiliary Buildings Basement - Plan - El. 562'-0 ML21055A3242021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2833, Diagram Reactor Re Circulation System Nuclear Boiler System ML21055A3232021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 4M721-5668, Core Spray - Accident Condition ML21055A3222021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-5007, Diagram Primary Containment Pneumatic Supply System ML21055A3202021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2711, Flow Diagram Air Conditioning & Ventilation Radwaste Control Room & Health Physics Lab ML21055A3192021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-4100, Diagram Torus Water Management System ML21055A3182021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6SD721-2510-01, Rev. BC, One Line Diagram 480V E.S.S. Bus 72B, 72C, 72E, & 72F ML21055A3172021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-5538, System Diagram Nuclear Boiler System Instrument Information Tables ML21055A3142021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721N-2047, P&ID Diesel Generator System Division II R.H.R Complex ML21055A3132021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-4127, Reactor Drywell Cooling System Flow Diagram (P&Id) ML21055A3122021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6SD721-2500-08, One Line Diagram 4160V Diesel Gen. Buses L1EA, 12EB, 13EC & 14ED Diesel Generator Building ML21055A3112021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 4M721-5871, Core Spray System Minimum Flow Bypass Mode Suction from Suppression Pool ML21055A3102021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 5M721-2756, Diagram - Steam Tunnel Cooling System Reactor Building ML21055A3092021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721TS-2002-1, Technical Support Center Diagram of HVAC Systems ML21055A3082021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6SD721-2530-12, One Line Diagram 260/130 BOP Battery 2PC Distribution ML21055A3052021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 4M721-5866, Low Pressure Coolant Injection System Test Mode During Plant Operation ML21055A3032021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2110-03, Logic Diagram Control Rod Drive Hydraulic System Part 3 ML21055A2812021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2263, Evaporator Feed Diagram Radwaste System ML21055A2682021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6C721-2361, Reactor Building Framing Section 40-40 Upper Area ML21055A2692021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2089, System Diagram Nuclear Boiler System ML21055A2702021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2220-06, Rev. D, Logic Diagram High Pressure Coolant Injection System ML21055A2712021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6M721-2017-1A, Diagram Off Gas Process System and Vacuum System Sheet 1A Vacuum System and Recombiner Chains ML21055A2722021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2215, Chemical Waste System Diagram Radwaste System ML21055A2732021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2090-05, Rev. a, Logic Diagram Nuclear Boiler System ML21055A2742021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2003, Diagram - Main Turbine Extraction Steam System ML21055A2752021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Figure 6C271-2539, Rev. Q, Steam Tunnel Upper Pipe Whip Restraint Structure Plan and Section ML21055A2762021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing M-2240-1, Rev. Aq, (Zone B/C-8) ML21055A2772021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2005, Diagram Feedwater Heater Drains, Emergency Drains and Heater Air System ML21055A2782021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 5I721-2440-06, Logic Diagram Emergency Equipment Cooling Water System Valves Div. I Auto Open ML21055A2792021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2007-01, Arrangement of Equipment on Combination Operating Panel H11P603 ML21055A2802021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2271, Heating Flow Diagram for Turbine-Radwaste & Reactor Buildings ML21055A2942021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2008-1, Rev. Ak, Diagram - Turbine Building Closed Cooling Water System ML21055A3392021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-5743, Biocide Injection/Dehalogenation Systems Functional Operational Sketch and Diagram ML21055A3002021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6C721-2349, Reactor Building Framing Plan Elevation 684' - 6 North West Area ML21055A2982021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 4I721-2440-05, Logic Diagram Emergency Equipment Cooling Water System Valves - Auto Open Division II ML21055A2972021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6A72IN-2044, Fire Protection Evaluation Residual Heat Removal Complex Section A-A and B-B 2023-10-12
[Table view] Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML22325A1242022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Appendix a, Applicable Regulatory Guides ML22325A1252022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 8, Electric Power ML22325A1262022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML22325A1272022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 14, Initial Tests and Operation ML22325A1292022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Main Page ML22325A1302022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features ML22325A1312022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 4, Reactor ML22325A1322022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 15, Accident Analysis ML22325A1332022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML22325A1342022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems ML22325A1352022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls ML22325A1362022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Appendix B, Aging Management Programs and Activities ML22325A1382022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems ML22325A1392022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 3, Design of Structures, Components, Equipment, and Systems ML22325A1422022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 2, Site Characteristics ML22325A1432022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations ML22325A1442022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML22325A1452022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML22325A1462022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance ML22325A1472022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, List of Effective Sections, Tables, and Figures ML22325A1542022-11-17017 November 2022 4 to Updated Final Safety Analysis Report, Figures (for Public Use) NRC-22-0052, Replacement Files for Submittal of Revision 24 to the Fermi 2 Updated Final Safety Analysis Report (UFSAR) Through EIE on November 9, 20222022-11-17017 November 2022 Replacement Files for Submittal of Revision 24 to the Fermi 2 Updated Final Safety Analysis Report (UFSAR) Through EIE on November 9, 2022 ML21055A2202021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2230-04, Rev. E, Logic Diagram Reactor Core Isolation Cooling System ML21055A1742021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2796-01, Rev. F, Remote Shutdown System Division I System Diagram ML21055A2192021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6A721-2411, Fire Protection Evaluation Reactor and Auxiliary Buildings Section D-D ML21055A2182021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6C721-2431, Reactor Support Sections & Details ML21055A2172021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2200-4, Rev. D, Logic Diagram Residual Heat Removal System ML21055A2162021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2043, Diagram High Press Coolant Injection System Barometric Cndr (HPCI) Reac Building ML21055A2152021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6C721-2313, Reactor & Auxiliary Building Foundation Reinforcing Plan ML21055A2142021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6I721-2196-01, Area Radiation Monitor System Diagram Sht 1 of 2 ML21055A2132021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2090-6, Logic Diagram Nuclear Boiler System Document Control No. B21-00 ML21055A2122021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6A721TS-2002, Onsite Technical Support Center Grade Floor Plan ML21055A2112021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6C721Y-2003, Rev. G, Condensate Storage Tanks Retaining Barrier Details ML21055A2102021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2004-1, Diagram Condensate System ML21055A2092021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2140-01, Rev. B, Logic Diagram Neutron Monitoring System Part 1 ML21055A2082021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6C721-2441, Reactor Drywell Framing Plan El. 646-91516 Unit 2 ML21055A2072021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2200-09, Rev. B, Logic Diagram Residual Heat Removal System ML21055A2062021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 4I721-2440-08, Logic Diagram Emergency Equipment Cooling Water System Valve - Auto Close Division II ML21055A2052021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2181-06, Rev. O, Diagram Process Radiation Monitoring Subsystems ML21055A2042021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 4I721-2440-07, Logic Diagram Emergency Equipment Cooling Water System Valve - Division II ML21055A2032021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2570-01, Functional Logic Diagram Operation of Power Line Feed & Tie Breakers 4160V Buss 64B & 11EA ML21055A2022021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6I721-2230-01, Logic Diagram Reactor Core Isolation Cooling System ML21055A2012021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2513, Side Stream Lrwp System P&ID ML21055A2002021-02-0202 February 2021 3 to Final Safety Analysis Report, Drawing No. 6A721-2406, Fire Protection Evaluation Reactor and Auxiliary Buildings Cable Spreading Area Plan El. 630'-6 ML21055A1992021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6I721-2400-03, Diagram of Samples in Turbine Bldg ML21055A1982021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2035, Diagram High Pressure Coolant Injection System (HPCI) Reactor Building ML21055A1792021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2010-1, Rev. a, Diagram General Service Water System ML21055A1852021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2551, Flow Diagram of Floor Drains in the Radwaste Building ML21055A1842021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing No. 6M721-2007, Diagram Circulating Water System ML21055A1832021-02-0202 February 2021 3 to Updated Final Safety Analysis Report, Drawing 6M721-2029, Rev. H, Process Diagram Information Tables Sheet 1 Radwaste System 2022-11-17
[Table view] |
Text
8 7 6 5 4 3 2 1 PEN SUPRESSIDN REF TITLE D.E.C .N . G.E.N .
,------,----------,--------- P L VALVES ND I I : REF, 24 DIAGRAM-CONTROL ROD DRIVE I A 1 HYDRAULIC SYSTEM (CRD) M-2081 729E612AB H VENT MYE N661 B
MYE N661 D W I
,,0,_
-'" 2 DIAGRAM-STAND-BY LIQUID CONTROL SYSTEM (SLC)
M-2082 729E601AB H r:-i ,r-I H21 P081 H21 P081 7
I I
-C)
CD 3
DIAGRAM-RESIDUAL HEAT REMOVAL SYSTEM-DIVISIDN I (RHR)
M-2084 729E602AB I ' DIAGRAM-RESIDUAL HEAT REMOVAL F229 * - :1
~ LXE ~J w
°'
4 SYSTEM-DIVISION II CRHR)
M-2083 729E602AB
~
/' r----
L ~Oi/ ~Ni61J " 1' 5
DIAGRAM-CORE SPRAY SYSTEM CCSS)
M-2034 731E981 LC I M-49701 2"
.LC CONDENSATE ,,.--,
/ LT ,
H21 P492 H21 P492
(/') VJ
\I :1
~ u....J t
VENT 6
DIAGRAM-HIGH PRESSURE COOLANT INJECTION SYSTEM CHPCI)
M-2035 729E600AB
< M-2010-1 (H-5) 7 10'
,, 10' STORAGE TANK r-- ~,~~b1§/J--- -r- 1___ -r-_ _t _ _ _ :_ _ _ _ _ 7 ~
- F038 7
DIAGRAM-HIGH PRESSURE COOLANT INJECTIDN SYSTEM BAROMETRIC CONDENSER CHPCD M-2043 729E600AB F233 2"
F231 3/4'
~--JSSE-- ~~n~ T "t::1"'
m" 0 "'
~
8 DIAGRAM-REACTOR CORE ISOLATION CODLING SYSTEM (RC!C)
M-2044 729E604AB
~
F232 F230* 1/2---------~ D\./G I
~v~~
Pll I I Pll I I Pll I I PU 1----J - _J u
-'°' 9 DIAGRAM-REACTOR CORE ISOLA TIDN CODLING M-2045 729E604AB v/lTH VEEPH LE 316"¢ TELL TALE L.'..J DRAIN i
- I I M-3226-1 M-2006 I :I :L ____ ,.. , L___ - REF. 18 (F-3) )
$-037 -"'" 10 SYSTEM BAROMETRIC CONDENSER CRC!C)
DIAGRAM-REACTOR \.JATER CLEAN-UP-SYSTEM (R\.JCU)
M-2046 731E348AB I I A '
DRAIN I '-""""--,
- 10'
- Pll OF042 L- t;-j C ND STORAGE SYS REF 18, CE-5) 7 L---------(:.!\I:!~
'-Av~:.
LRE-PltRB l 3/4
'° 11 12 DIAGRAM-REACTOR ~ATER CLEAN-UP FILTER/DEMINERALIZER (R~CU)
DIAGRAM-FUEL POOL CODLING SYSTEM (FPC)
M-2047 M-2048 731E380AB 729E609A
7 H21 L__ _ _,i'--"'---------1------, I SECONDARY CONTAINMENT I P080 : DIAGRAM-FUEL POOL COOLING G I I TD STARTEC *-------7 : CDND STORAGE SYS t-- ~~--, PT PI ) 1/MXE PXE E51N004 13 SYSTEM FILTER/DEMINERALIZER CFPC)
M-2049 732184AB G
I
- PNL-H11P919 P IN T #136 f--{ MYE I
i
~ REF 18 (H-1) ( - 7
'-;::==::::::::=:::::::::::::::;-' I
£3
§
~
§
~
§
~
§ i:;J L444 R400 TO ST ARTREC ~
E51 1'-(8251
---< REF B, <F-4) 3°: 14 DIAGRAM-REACTOR BLDG. CLOSED CODLING ~ EMERG EQUIP CODLING ~ATER SYSTEM M-2027
- 1-2042-05 NGASl I M-3228-1 : ~ ~ ~ ~ ,. PNL-H11P919 I 15 DIAGRAM-DEMINERALIZED SERVICE M-2678 1 (C-5) ZSV p..C:."---j : CRD SYS .,I :; :; :; ; :::: 3/4# POINT #131 - - - , j VATER RISER SYSTEM I N513 H21 REF L (D-6) l I w w w w (") I VENT 1-2042-19
???
1
~ ~
1 X33Bo.. I A&.B P080 I r:,--s- ,7-sc:7 /-'C""'- I (D-2) I 16 SYSTEM M-2089 729E616AB J/ 4
<NOTE 7 TYP) 1 MYE N658 -+- N658 MYE v2 :
2021 I F1 5 B 10..
7:116 Fl]S I
- 10*
F036 r-----------~--
I
- i 2E0 -- ~tcf2 ---< D-5 (
PXE N009 17 DIAGRAM-REACTOR VATER CLEAN-UP SYSTEM M-2088 729E6l 4A PHASE SEPARATORS CR~CU)
A I C 7---IXf---'i' H H 3 ; 4* I I ~---~ I I I p.."-.~ ,:,,i L
- DRAIN I ~ DIAGRAM-CONDENSATE STORAGE I I I I H21 U F504 I I SS: 18 M-2006
~
1 O'> -
H2 l SYSTEM M 1 1 I F177 SPECTACLE r--. *
- 900#SS : I POBO I POBO [i5 3;4* FLANGES i:'. I 3 : I/P i CLASS A I ~,..c.~ I ~;::I~ : ~;::I~ '-r",,,DRN (TYP. 8 PLACES) FlBD 7
ZXE j K823 , / 19 DIAGRAM-ST A TIDN AIR SYSTEM M-2085 6H6H6H6f----'-4~. ::/ g ~
\ ::::
! 900#SS I
L ~~f l I
- a~~ : :a~~ I
- j 4*
~
N402 -------
i--------~----_-_-_-_-_-_-_-_-_-_-_~- ---- ----
r,;~~~;::,;;:=
DC / ' C r- 20 DIAGRAM-FEED~ATER SYSTEM M-2023 (x 33Bb I CLASS A A : A I C 1!; S (
~ d~ 7 w FOR VENDOR I SQ -
e I H21 : H21 : H21 S5 4 : I SUPPLIED VALVE I 21 DIAGRAM-REACTOR RECIRCULATION M-2833 729E603AB
-'°'"
1 F500 P016 1 P016 t P016 F159 c; ~ 1 DC I CONTROL E IAS '"L SYSTEM CRRD 3/4' 1
1 r-+---- I I 3/4* DRN '° m .,. co t-'jL+(~ I SCHEMATIC AND f-.__._+._W("ly95-105
,:' 22 DIAGRAM-RESIDUAL HEAT REMOVAL SERVICE ~ATER SYSTEM M-2012 1 8 8 8 8 ,cl I COMPONENTS SEE ::, \ PSIG B I PB I L------ 7 ,,-v--,-.,.-.-.-Y"' § § § § F'1/2"-J fL + I D\./G 640761-1 DE '--- DIAGRAM-NUCLEAR BOILER
~ ~ ~ ~ ):1 : (DECO FILE NO, ~ M-2090
,---u ~ ~ ~~~
1 L---------------7 FC 1 23 729E616AB r;;;-
SYSTEM E41DC0430~---
/4'.__ ---------
7~
AND-BY1 ZSV ~=~=~ ,C
! t1J l'.J t1J d f"#'{),1(4- ~~~-=-1_:i~~~------J DIAGRAM-HIGH PRESSURE COOLANT
\l447
- 24 729E627AB
,1. ,1.
g.
1 '
~ '- / I
'" INJECTI N. FCD F C/
Q---"
1
~
I
~
AC ISOLATION SIGNAL N512 A~B
)ISOLATION >-..T--T SIGNAL MD DC L---_z"G E41DC0431 1
1
'-'.A.-"--'-\_ (E@t F002 25 LEGEND OF SYMBOLS & INST IDENT FDR PLANT SYSTEM DIAGRAMS M-2001 F
'---------~ ~ I ,-----, r----~ I
- I X-ll .1 M-2297-1 I E4150 I M-3172-1 I I 26 PRIMARY CONT MONITOR SYS 1-2679-01
.. I,, 10 L._ _ _ ____j
~ .. F00 3 L._ _ _ ____J I 10' FTL L400 FTL L402 v,
E4150 F002 I
i "'
t-w 1* ~c J t F156 F157 E:)
vi"'
~~ " /
PXEN0!6 @ 27 PIPING AND INSTRUMENT SYMBOLS Rl-25 197A567 L~ ~ ~
t-- vi (,1 0, C 314* VENT
' ) REF 7, CE-5) )---- R608 9
1
~
E4150~* !'] d E4150 FE F600 J MD 900#CS 900#CS ~ -
- By N400 FTH \-L_ F014 3/4
~ i CLASS A CLASS
&, 0 I
l __
L
- ----) ~~J~ACSR LATIN D '
o--.--
/ vi"'
uv'J F004 MD i PS )
E/S K600 B 3 )---t---J I
1 NOTES,
~
FTH)
> c / '-
'-----(
~
L401 L403 ISOLATION>- ---~~---7 :
I B i :;::*_ 600# GROUP 'B'.1_150# GROUP 'D' ""' ~-_J
&, I I
d
- . 7 -----
4 I DC o<C I 1, THIS DIAGRAM REPLACES GENERAL ELECTRIC DIAGRAM #729E600AB SH 1 REV 3.
02~ £-J --
I AiB
,::--H--- -u m_J C NUCLEAR BOILER SYS I ___ I i 1 I, EF 24 MD F019 E 4 l C0437 I / "- 2. SPECIFIC SYSTEM DESIGN REQUIREMENTS ARE GIVEN IN THE HIGH PRESSURE COOLANT rl_---"R=E'--F_1cl6~C:.':'3i= 4) >r--__:_ 'Q 3/; \! I E41DC0402 : : E5100F023 L_-< RCIC E41DC0438 PXE 1~012 PT L473 INJECTION SYSTEM DESIGN SPECIFICATION NUMBER 3071-504.
F5290#ssl
~---.!', . -
r----L~~i REF B, CG-5) 3, THE PLANT IDENTIFICATION NUMBER FOR THE HPCI SYSTEM IS E4100, DRN. *3/4"/ I i 150# c.s. H21 PTT I
Fl55
- I M-3175-1 I ,.-., E4150 F041 -'° CLASS B P014 4, FDR ASSEMBLY D\./G ND, SEE KEY PLAN M-2320,
/ ',,.
~ -
' CLASS I 7--;_;
1 I
I 17 ",
~ -",, ' /
,0, C -
I/PI",
3/4' VENT
- 5. FDR GENERAL ARRANGEMENT SEE A-2000.
0 i/ PXE PXE 4- F009 DC i (:)
I I,.~... 11.~.I zsv ~00'.:! J 6. TORUS SUCTION LINE IS MONITORED FDR LEAKAGE.
'-. r-
~o;y \'o;s) I
-c'°'"
--I I ~
I N515 1 I 1'-'.'J\'2 H21 I MD I -*-
1 I Fl73 Fl74 7. EXCESS FLOV CHECK VALVES TYP F500 HAVE LOCAL RESET AND BOTH LOCAL AND E
I A~B I (x32~
. /--::-7 I
I I
H21 P036 I
I H21 P036 H21 P036 E4150.
FOOS I
' - *. - ' .. - - - - -* 7 o, , --- l __ z:2:,
P014 CONTROL ROOM POSITION IND I CA TI N.
E I
C/Q- i DC E41DC0429 I
w r I
~*Z I .... -.l....__.._, B. TORUS PENETRATIONS X206A- D ARE ALSO USED BY THE PRIMARY CONTAINMENT M NITDRING I SYSTEM. CT50l SEPARATE EXCESS FL V CHECK VALVES ARE PROVIDED FDR EACH SYSTEM.
'1/T t--W V,Z I
I : I ' PXE N019
"' MD 1
~
I ' t--
z_J I F503 90#ssl I r----.J -- : PI -5)
- < I ~ ::,u I I
,-----:0, ' / D 9, ALL HPCI PIPING AND EQUIPMENT SHD\./N ON THIS DIAGRAM IS QA LEVEL I I~
-'° I I
IRCIC VENT CLASS ~111
- : ~-~
I MYE N6D58 MYE N6B58 R609 r-----~
REF 7, CG G-4)
(,1
~1b1~
r-- "' HPCI SYS.
REF 7 (G-2) 10 '
I M-3172-1 I E4150F001 ~
LT \ r:-s I I
C UNLESS NOTED THER\./ISE,
' I M-2044 (F
' H21 H21 L_____ --7 CE K820 m
'"' 1
-5)
MYE N657 ._
-'- PDSE N660 POBI POB!
SPECTACLE ~
r7-'--s7 1
-< B 3 (
I I
I 0: a_ STEAM SUPPLY I I I DRAIN PDT L441~4
-:,~-- C)
~ ~
I
" I FI 3/4" H21 B B H21 FLANGE E4150D010 ------J
,7-sc:7 p
PXE N009 i
1 E/S K600 I "' I TO STARTREC 900# c.s.
L_ I (,1 I
P-"--1' I 10* I PNL #Hl!P919 LT L__J
' R007 POB! P081 ~----------------------' f---. ROG! H21 : TI 1 O
CLASS B E4150 FOBO
- C 1 F301 ~ E41DC0435 e'>-"- P014 1 R002 ) I I FOR TURBINE-PUMP DETAILS
_J u
POINT #128 1-2042-19 CG-3) I__,}-\ L442 r-- : E/V ] DC L : 3/4' 2~ F145 :]TEST o.: .~ @TH FTH ' - - - ~ - - ~ H21 I T STARTREC I SEE DVG ND. M-2043 '\' '--:I E II F454
., ts - D 0
O L410 L411 P014 L_,.PNL-Hl!P919 I I I
1 6° I
1 0 3;4* i NO?@ i
--eel-- NIAS H21
">- " 1
- , ,___,, r,..-"-s;-- r?'"'-sc:7 POINT #138 T\.J I "' I
" ., -
PB Fl 46 o.:
ts
- l I
I I ' /
FE FXE NOOB FSE N006 --1-0 c------, 1;,;
f-_.f--:]
I-2042-11 DRN, (C 3 >
L407
')
-X-1 P420
- 11. FOR VENT, DRAIN AND TEST CONNECTIONS VITH THE DOUBLE VAL VE ARRANGEMENT,
-"' '°-
OC I L'J AFTER THE NUCLEAR VALVE (FIRST VAL VD THE CLASSIFICATION IS GROUP D, w
~
C)
DRN,
- 8:i:l ~~
'- / ----*
PI "' L----~----D I F228 I SEISMIC II, QA ID <EXCEPT FOR VENT WITH VALVES E4100F032 & E4100F033l.
L49 Pl4 1 - - - 4 R00 6
<[ "-
la.. w c,Q : , De Lfrs----...J F144 1
, DC MD
/ 'C FTL FTL L4DB
)
H21 eo14 H21 L --,
PT L406 zsv N503 A
zsv )
N503 B
- 12. VALVE E4100F005 HAS THE HARD\./ARE CAPABILITY TD OPERATE AS AN AIR-OPERATED, EXCERCISABLE CHECK VALVE, ND AIR SUPPLY LINES ARE ROUTED TD THE VALVE, THE w w d "' I>:
'i;
~
- ! f-=-j
~~
3;4*
I-M-3167-1
---~
I c I r----,. HPCI SYS
.... EXCERCISABLE FUNCTION IS NOT OPERABLE.
D I.
z TD PRIMARY I
lo ru
- 1-o
~
E41DC0434 r ----
FINS
-'-'-'-'-"-~
14 ' w F005 ~NOTES 12 & 13 )
7
)
I 14' [M-3167-1 l 1 REF 7, (F-6)
' F054 F.C.
~
-'" 13. VALVE E4100F005 IS AN ASME CLASS 1 VALVE INSTALLED IN A CLASS 2 APPLICATION, D
I I
20~ E4150 F006 E4100 GOOl 3/4N E4150 FOOl L..!..J I
'1
~
'------~ 7 PUMP DISCHARGE
-"' t F031 '"
D 1 z m
- : F016 TD STARTREC !2~
r________________ 1! 900#CS 600#CS F i PNLpmi~ 919 iE~lDC0436 C7-"7 7 we>
~~ ~ <: ' TRANSMITTER I DIV POVER TRIP UNIT
-'° "::, -'° "
¢
_j 222 t-- w NUMBER SUPPLY L L I FEED\JATER SYS. (') 1 CLASS A CLASS B 1 #137 I-2042-15 1 r--- PSE ~ DCOS o :S *;.:i. F027 :,:
6 ,£ h
~ ~1 1 55
--- .. - **- **- **- ** C 1
- I Ji'
-I,,' f-,4-< REF 20, (F-2) (
- E 1
1 I
F219 F218 TEST E-llio4'--'ll0iif--l :
I
_.1 I
I 1
I I
1 I
N027 P-"--1 H21
~
~
~ u
"' I'~ "'
>- W I v, X w
V,
(,1 -
I t--
cc':_
PXE-N009 PXE-N013 K600 K600 1
=-----~ :
FEED\.JATER SYS 1 E41DC0403 GROUP GROUP 1 F221 F 227 1 I I ___
A I :~B I 1 :
POl 4 I
- : l"I n.. u... w ~
-U a_
,.._ IX
"- w tF030 -
/0,c
/ D PXE-N016 K600
~ P~~
I W e> I W j l: j
~ I 1* I
- REF 20, (F -2) (- .J F226 F225 INVERTER FIC : F046
°' ::,"' z I
'ci----J
'-/ TEST[:
- B-4 __ ....J ~ PXE-N019 K600 11 ,- 4 ,-.- 1 '
r--------------------0---------- ) ISOLATIDN SIGNAL:;.:-ff~--p, c ~ 14 314 ' v;D TO sTiRTER TURBINE 13 :l__ +,l::c:f O 0,,, 31
a m ISOLA TI N PNL _____. C/ '- I PXE -*N055A,C I B21K609A, K609C N655A,C MD F151 GROUP B GROUP D IF220 1 m H11P919 POINT #132 * )
1-2042-15<C-5> ---....- REF 7, <E-B)
) ~
w
<:t i
I L __
J.J /
-rDc
'C u
- ~ ...
4 F 64 L--i--- *-
t--
_J S-W I
I I PXE -N055B,D II B21K609B, K609D N655B,D
~ ~ 5 .L I E9 O :
", V F223 CONTROL § 150# c.s. / I 150# CS, ,:' i 1* HPCI KEEP FILL LOGIC MD ., '° u ::, ry-~
DC ciPXE-N057A I B21K609A, K609C N657A,N660A
<: ,-a CLASS B CLASS B E 4 l5
, ~
zC)
-"' * * ' I,
[M-4361-1 l' M-4100(G4)
F012 (,') r:r:1
!F065
/-
~
C)PB EJV F428 i 17 ciPXE -N057B II B21K609B, K609D N657B,N660B z 1F077
" 1 ' V-.J 3/4 6WM-E41-5878 U
~1:5 VJ I CJ 1-:::c;-7 E/V 'I DC PXE-N058A,C I B21K609A, K609C N658A,C
- ~-f~_'-D/
O -c'°'"'" C/Q F076 E4150 I
7 H21 I F429 F224 TEST II P428 1 I PXE -N058B,D II B21K609B, K609D N658B,D
~-/4~~--= ' ~----~~-~l14*
t- F075 I
~
s:
_j
~J:/46 "'
"I>-
<L
"' t--
c, I
Mii""7
/ 'c w 3/4' DR PB *
-u
~ ~ ] VENT I
r-- ---~
I I
- E H21 P420 LXE-N061B,D II B21K609B, K609D N661B,D C E4150 F079 4*
TEST
's-F032 F033 PNL 0
'r{_
I
\...£_...JI I
1 1
NIAS E
t 1
xr-
-I I
1 I
NIAS
-X-LXE-N062B,D II B21K609B, K609D N662B,D C
~* . ISOLATION
(:),,'
,, I I
I MD I -&
~t "I>-
°'
c, a_
t--
-~:t 24' v
16' E4150
-"
-v,.. 1 CR
' 1 20*
DC I~
~ DE l<il DC
~
900# C,S.
LASS D, QA I_EVEL III LEGEND ir:i' 'o
/ , c L,_
I u FO-cl 1314 ~ J TEST 'l°----p, I C zsv zsv lIDENTIFIES E41DC0403 L!JTEST L.!..JTEST uTEST : ~ ~ IM1i7 N505 A
N505 B
!. IM- D~G ND.
AND ERECTION.
PIPING ISOMETRIC FDR F ABRICA TI N 4' IM-4361-1 I 4* !'] d X-221 H F028 3/4H F029 I 2* zsv F.C F055 F,C. 6\./M-[41-4045-1 1 ,,.,.,.-- .., \ (I)
I M-3713-1 N504 INSTRUMENT~ CONTROL SYSTEM NOTES:
3
~ ~ r-.--~ A
~
1 ,.
I LT \
\L452/ X-214 CV) u
- ~
tll
/ E4150
CSS REF , (E-?)
5 zsv [F056 A. UNLESS DTHER~ISE SHOVN ALL INSTRUMENT N .'S ON THIS DIAGRAM i ,,.. 1 lD _j F022 3/4 J TEST \./ALL 9 .
I X206Il }---...... x .... W N504 I t--- ARE FDR SYSTEM E41.
TEST EL. 575'-6 1/2 6 B
1 REF 26 L
.............. 1
-..J,.._ I
!"'---+---------------------------------------
F047 M-~~6~-=-~------------------------ CORE TEST SPRAY B, NOTE REMOVED. 6M721-2035 I <,--E-::_3-?--IC>l-------.:::,J 24 I I 900# c.s, LATEST REVISION 1 LINE I
'-------" F163A I I
I X-220 I I
I I
I CLASS D _._.VENT
-,.,F166A C. NOTE REMOVED.
BP L!1Q+:;,7 1
J E5150
'-1*:,. F084 1
PROVIDE HOLD DO\./N 2
1 1
1 F1634-------.
150# c.s. il"~~I~.~--_,
'---- I I AGAINST BLD\-IING I k--------K>!-- E-3 > REF 26 CLASS D wVENT 1 I REACTION ,
1 I -- ..........._ L .,_ ____ _,. -,., F166B I I ' .' F167B Ma--,
DRAIN ,-.ii I
I I I I I "-.... ----.. HPCI SYS
-'°
'vi "'-=cg~~_A-'t-A__~~t~=--"-t=~~~g'==t' II - - -
_/-.71I I/.J-, '------1~~0_§~)
FIE-R613 C-5 --,
r----j REF 7, CE-5) ) PXEN016 s I ~VENT "'u I LT \ . s.s.
B -"'
I I
I
---+\' t I I I I\
I L453 /
1 I
I I
I I
j HPCI SYS REF 7, CG-5) ) PXEN019 Fl67C ~ t________J Fl66C B
---e il ~
CD FIC-K615 C-6
~
I
_B~~_2.§..., F164A j SUPPRESSION POOL : I DRAIN c.'
w < E-3 (------K>f--------;.>1 STRAINER F164B I' 16'wM-E41-5298-1 NUCLEAR SAFETY RELATED L-----------i<:::+--E-=3---) -----j
'-------" LO E41DOD002 REF 26
~ E-3 ) PXEN013 Q' --1......... :
.,,,.,. I I -.._ 0 B
I v
L.. _ _ _ _ _,,
(X2o6CJ-.--.....,,...,--- 1 ~------------------ ---------------------...J '--... r-- Fl~!!
L I I
1,.....1-,,I I LT X-225 1
,...J-.,
1X2o6Bl ,__ __ _
/ t----j D-5 ) PXEN009
~ C /Q------ i_IJ_c I i::i:Z
~z G3 THIS IS A MICROSTATION PRODUCED DRAWING.
\L450)
~
/LT\
1 L451 ' £--J IMDl--< 1 SIGNAL I I I
bu ,._, w CHANGES OR REVISIONS MUST BE BROUGHT
, __ .... ISOLATION I z"' m
\
F045 I
I I ~W CD CJ, TO THE ATTENTION OF THE PLANT ENGINEERING
- [M-3163-1 l, 16' E 41DC0439 16' I I
~ Q (\J DESIGN GROUP TO ENSURE THAT CONFIGURATION I
V E4150 F042 DC TD AC ---l~,,,;;c,J------ ----
INVERTER 1-" EIS--..._
K-603 I
-'[;s',
K600
' =A
- z t-- u CONTROL IS MAINTAINED.
- THIS DRAWING WAS REFORMATTED BY I 3/4 ~ TEST Hll
/
HI!
MICROSTATION AT REVISION "BG". ALL INC.CODE Detroit Edison Fermi 2 P612 P612 PREVIOUS APPROVAL SIGNATURES ARE T,TLE F044 P ~ER SUPPLY ON FILE ON MICROFILM IN DOCUYENT CONTROL. T DIAGRAM BPlDCD'S INCORPORATED: A PORTION OF THIS DRAWING PREPARED BY DATE HIGH PRESSURE COOLANT IS AFFECTED BY THE FOLLOWING:
TM 19-0019, REV. ~ INJECTION SYSTEM (HPCI)
TC CHANGE DOCUMENT A OTHER REVISIONS:
CHECKED BY DATE I APERTURE CARD TITLE REACTOR BLDG IA DIAG _HPCLSYSREACTOR_ BLDG~_
APPROVEO BY PLANT IDENTIFICATION SYSTEM NUMBl!:R ARMS RECIPIENT #
E4100 PREPARED BY DATE DATE DOCUMENT TYPE CDDEDDDMEC NUC OPS FILE NO DA'l'E ISSUED TO l6 MOHAMED NUMAN 4/12/2020 l0-1*ldi,6 OTHER APPROVALS DATE 1801 tolg-/'2.-0~~
It: DATE l!:DP POSTING ENTRIES REQ tTIRE TBE APPROVED BY Gire.~ Ared.2 4u
~ 1"1-oti', I ,/i/1.-0
""1 ADDITION OJ' THE ARMS STATUS CODE:
EITHER "AFC" OR "ASH~ DRA1'1NG NVMBER 6M721-2035 REV.
BP
~
8 7 6 5 4 3 ? 1