ML18022A325: Difference between revisions
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| number = ML18022A325 | | number = ML18022A325 | ||
| issue date = 10/05/2017 | | issue date = 10/05/2017 | ||
| title = | | title = Updated Final Safety Analysis Report (Ufsar), Amendment 27, 7.4 Figure - Emergency Core Cooling Control | ||
| author name = | | author name = | ||
| author affiliation = Tennessee Valley Authority | | author affiliation = Tennessee Valley Authority | ||
Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:BFN-18 Figure 7.4-1a (Deleted by Amendment 18) | |||
HO~ l -ZLll3£ t -z r< ti H | |||
Ill G m | |||
c | |||
'ffij\...,,**,., | |||
B AMENDMENT 27 POWERHOUSE UNIT2 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT HIGH PRESSURE COOL ANT A IN J ECTION SYSTEM FLOW DI AGRAM FIGURE 7 .4-lb SH 1 4 | |||
H G | |||
c B | |||
HIGH P~ET~~UN SYSTEM I N~~ow DIAGRAM FIGURE 7 .4-lb SH 2 8 | |||
B | |||
~ ,. c.. | |||
AMENDMENT 27 POWERHOUS E UNIT1 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT HIGH PRESSURE COOLANT A I NJECTION SYSTEM FLOW DIAGRAM FIGURE 7 .4-1 b SH 3 8 | |||
BFN-22 ' :. | |||
\.," | |||
~ | |||
Figures 7.4-2a through 7.4-2h (Deleted by Amendment 22) | |||
I | |||
BFN-22 Figure 7.4-3 | |||
{Deleted by Amendment 22) | |||
BFN-19 Figure 7-4-4 (Deleted by Amendment 17) | |||
I I '~ I I I I I l I 10 I 11 I 12 SY~BOLS l~W: | |||
10 L""!'i11,'"LOC~IC, | |||
~**__,,_**--~_. ___., .... -~ | |||
t | |||
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1 . I L L - l l T l l M ! . . .Dlll"I-"''"-,_""" _ _ _ | |||
:: ::.r.:- ----- _, __ ....,............... | |||
~**="='"=--=~=*---@.~ ...... | |||
AMENDMENT 26 POIERHOUSE UNIT:Z | |||
- BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT ECCS PREFERRED PUMP MECHANICAL CONTROL DIAGRAM FIGURE 7. 4-5a l I I ! I I I I I I I 10 | |||
BFN-22 Figures 7.4-5b and 7.4-5c (Deleted by Amendment 22) | |||
~. | |||
AME NDMENT 23 BROW NS f[ RRY tt UC LE ... R PLMH r hlAL SAFCTY Att,f,.LYSIS 11£PORT PR£-ACD 4. COii Jl!:D SIGN AL WrOf.toNICAL C-3MTROL DJ,1,[; i;" A\1 fJGVft( 7 .f-5d | |||
BFN-22 Figures 7 .4-5e through 7 .4-5h (Deleted by Amendment 22) | |||
H ~\~fi/i[oc, m:rn:- 1:"~' ~1":'l'l.'Jo'"' | |||
""'""" ' | |||
BFN-22 Figures 7.4-8a through 7.4-8d (Deleted by Amendment 22) | BFN-22 Figures 7.4-8a through 7.4-8d (Deleted by Amendment 22) | ||
BFN-22 Figure 7.4-9 (Deleted by Amendment 22) : ,*:. | |||
}} | BFN-22 Figure 7.4-9 (Deleted by Amendment 22) | ||
: ,* :.}} |
Latest revision as of 00:27, 18 March 2020
ML18022A325 | |
Person / Time | |
---|---|
Site: | Browns Ferry |
Issue date: | 10/05/2017 |
From: | Tennessee Valley Authority |
To: | Office of Nuclear Reactor Regulation |
Shared Package | |
ML18018A778 | List:
|
References | |
Download: ML18022A325 (30) | |
Text
{{#Wiki_filter:BFN-18 Figure 7.4-1a (Deleted by Amendment 18)
HO~ l -ZLll3£ t -z r< ti H Ill G m c
'ffij\...,,**,.,
B AMENDMENT 27 POWERHOUSE UNIT2 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT HIGH PRESSURE COOL ANT A IN J ECTION SYSTEM FLOW DI AGRAM FIGURE 7 .4-lb SH 1 4
H G c B HIGH P~ET~~UN SYSTEM I N~~ow DIAGRAM FIGURE 7 .4-lb SH 2 8
B
~ ,. c..
AMENDMENT 27 POWERHOUS E UNIT1 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT HIGH PRESSURE COOLANT A I NJECTION SYSTEM FLOW DIAGRAM FIGURE 7 .4-1 b SH 3 8
BFN-22 ' :.
\.," ~
Figures 7.4-2a through 7.4-2h (Deleted by Amendment 22) I
BFN-22 Figure 7.4-3 {Deleted by Amendment 22)
BFN-19 Figure 7-4-4 (Deleted by Amendment 17)
I I '~ I I I I I l I 10 I 11 I 12 SY~BOLS l~W: 10 L""!'i11,'"LOC~IC,
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AMENDMENT 26 POIERHOUSE UNIT:Z - BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT ECCS PREFERRED PUMP MECHANICAL CONTROL DIAGRAM FIGURE 7. 4-5a l I I ! I I I I I I I 10
BFN-22 Figures 7.4-5b and 7.4-5c (Deleted by Amendment 22)
~.
AME NDMENT 23 BROW NS f[ RRY tt UC LE ... R PLMH r hlAL SAFCTY Att,f,.LYSIS 11£PORT PR£-ACD 4. COii Jl!:D SIGN AL WrOf.toNICAL C-3MTROL DJ,1,[; i;" A\1 fJGVft( 7 .f-5d
BFN-22 Figures 7 .4-5e through 7 .4-5h (Deleted by Amendment 22)
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AMENDMENT 27 PO'llERl-IOUSE UNJTI BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT ECCS PREFERRED PUMP MECHANICAL CONTROL DI AGRAM FIGURE 7 .4--5i
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cs DIV II AUTOMATIC 1 "-' " " " " ' " " '"' " ' " " " " ' ' ' * ' - INII~1~:°N INHIBIT AMENDMENT 27 POWERHOUSE UNIT3 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT 1~:11:rnu 1 ECCS PREFERRED PUMP MECHANICAL CONTROL DIAGRAM FIGURE 7 .4-5m I I I I I I I I I
H D c AMENDMENT 27 POWERHOUS E UNIT2 BROWNS FERRY NUCLE AR PLANT FINAL SAFETY ANALYSIS REPORT RESIDUAL HEAT REMOVAL SYSTEM A FLOW DI AGRAM FIGURE 7 .4--60 SH 1
m ' D c B AMENDMENT 27 POWER HOU SE UNITI BROWNS FERRY ~~;~~~isp~~~~RT FINAL SAFETY A RESIDUALFt6~TD~~~~XC L SYSTEM FIGURE 7.4-Sa SH 2 7 5 4
H G D c B AMENDMENT 27 FINAL SAFETY ANALYSIS REPORT RESIDUAL HEAT REMOVAL SYSTEM A FLOW DIAGRAM FIGURE 7. 4-6a SH 3
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rt!it ' RHR STEA~ LINE MECHAN I CAL CONTROL DI AGRAM
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LEAK DETECTION FIGURE 7 .4-6b SH 1
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- 74-5C 74-11 XS I I I I 74-1C 74-1 --
J-
- ZI:7-~-10 ?'RS' ;-v I 1
ZS
~ VENT .G. TELL-TALE 1/2" '-~ '
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--ITHIS DRAWING. F4 "'>
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POWERHOUSE
- TO re 74-10 74-10 -- <---- ----,, __J";;' YTHIS DRAWING, F4 TI 4-109 TW '
L-m HS 74-100A I 4-1D08m-.i r 'vJ~----~I LOG I 9-47
~-10T~E~~~~o::::~-------------tJ *~ 74 s~ ~RHR' !~_r.-s ___ r.-s_ ro5 UNIT 2 RHRSW _ _ _ _J 2-47ES1D-23-1. F7 \- -:::::::::----, 74-9 1---------1,4-10~9"'"T_;~--l_/'1.--.....
L--------=11-45E779-10
,----L-----------@~==--...!:=====!.:=::;:..~11 ....::::::::::.._.::::;::::~ PUMP r1 ~-----
llA7400SHI I L ....T x T .X._j_ BROWNS FERRY NUCLEAR PLANT
-
- _1_25 59 _1_25 59 __!25-59 ------ 4H_~ 04 1 r- A __, -----<,>----~------,~ ----------- -...,
>---~ ~:-s.~ I 1:~. l J::.~ I~ ~:ra4 ~ t9- 3 -------..+/-_----=~ 59_ _ _ _ ,_ _ _ _ J FINAL SAFETY ANALYSIS REPORT
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FROM Fcv- 74 _ 35 I 2_47 E2 S10_74 _1. L---========:::::'.:___ ,_ E2 >-J I K-L--J:~t--H 1-47Ea52-1, TO DRW 01
> LJ 2-730E937-S 1L - - - - - - - '1 ~
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-~_...J_,,--::J-l.f--.....J-'-1-~2lll~l-4-7E_2Ts_1_o-_1_4_-1_._I'_ _>_ _J RESIDUAL HEAT REMOVAL SYSTEM 2
I ......,. - 1 - - - COMPANION DRAWING: MECHANICAL CONTROL DIAGRAM
- 117 n 'k:..J ~ ~ SYS I - 2-47E2610-74-1 - 3 I "' ~ FLUSH PUMP 1-47E610-74-1A 3-47E610-74-l, 2 FIGURE 7.4-6b SH 2 I I I I 1 I I I I I I I I I 2 I I I I I I I I I 3 I I I I I I I I I 4 I I I I I I I I I 5 I I I I I I I I I 6 I I I I I I I I I 7 I I I I I I I I I 8 I I I I I 10 I I I
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G D c B AMENDMENT 27 POWERHOUS E UNIT1 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT RESIDUAL HEAT REMOVAL SYSTEM A MECHAN I CAL CONTROL DI AGRAM FIGURE 7 .4-6b SH 3 7 5 4 3
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BROWNS FERRY NUCLE AR PLANT
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@RHRSTE AMLINELE Al< DETEC T ION FIGURE 7. 4-6b SH 4
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BFN-22 Figure 7.4-7a (Deleted by Amendment 22) ~*- ,/*.**
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LS-J-58A
'-C '°'- PB9-J RX VESSEL LVL LOI (TYPICAL OF 4) LS-3-58B J HS\ LS-3-58C LS-3-58D - ~:Jl '-- - RESET -
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1-RLY-74-10A-K73A D- I -D
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- 1 RLY 75 14A K11A - - I -
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- 10A-K36A(B)
SIGNAL. DIV I (CH Al (DET C-3 THIS SHEET) THIS DIG. DET C-3 I h -
- 10A-K107A _/ - ........ 10A-K109A ~
TO UNIT 2 ECCS PREFERRED PUMP LOGIC INHIBIT AUTOMATIC (LPCI) START OF RHR PUMPS 2A ~ 2C
- ~ 10A-K9A I 2-45E765-4, G-4 THIS DIG, DET C-3 E- - <THIS DWG DET 03 0
SEAL-IN I INHIBIT AUTOMATIC OPENING OF LPCI
~E TRIP PUMP 1 2-45E765-4, CS 10A-K73A(B) RHR (LPCI) AUTO INIT LOGIC INHIBIT SIGNAL I UNIT PRIORITY DG BKR RE-TRIP SIGNAL CH A 2-47E610-75-2, A 7">
INJECTION VALVE FCV 74 SJ I 2-45E779-22. G-5 > (OET G-3 THIS SHEET)
- INHIBIT PUMP INHIBIT THE INITIATION OF THE UNIT 1 ECCS PREFERRED PUMP LOGIC ON A UNIT 2 DIV I LPCI SIGNAL TO UNIT PRIORITY DG BKR TO RHR PUMPS 1 2 -730E927 -;* r'> 1 THIS DWG, DET D-J NOTES:
- 1. ALL COMPONENTS ARE PREFIXED "2-* UNLESS OTHERWISE SHOWN.
RE-TRIP !NIT LOGIC 2A AND 2C, 2. FOR GENERAL NOTES AND REFERENCE DRAWINGS SEE 2-47E610-75-1 .2.
- DIV I (CHANNEL A) AUTO START AND RHR (LPCI) AUTO INITIATION '--
INHIBIT INDICATION. PUMP TRIP LOGIC DIV I (CHANNEL A) DETAIL D I TO UNIT 1 RHR AND CORE SPRAY ECCS PREFERRED PUMP LOGIC CHANNEL A (B)
'-----------------{A - 9-3 IL-74-153
- 3. DELETED T ~-47E61D-74-3, c 1 >
- RHR (LPCI)
F-UNIT 2 ECCS PREFERRED PUMP LOGIC DET C3 RHR AUTO INIT SIGNAL, CHANNEL A (Bl DET D3 L...J1-47E61D-75-3,
*-* AUTOMATIC INITIATION INHIBIT LOGIC DE T G-3 ~F - SYMBOLS: - ANO GATE: OR GATE: '--
(INPUT A) (INPUT BJ
- UNIT 2 (INPUT A) (INPUT B)
DIVISION I I I '--
- I I G- DRYWELL PRESS HIGH ~G - (SEE DETAIL B THIS SHEET) - REACTOR PRESS LOW (OUTPUT) '--
(SEE DETAIL A THIS SHEET)
- LS-3-58A (OUTPUT)
RX VESSEL LVL LOW THE "AND* GATE GIVES AN OUTPUT MOM PB LS-3-58B SIGNAL IF AL.I.. INPUTS ARE PRESENT
- (TYPICAL OF 4) THE "QR* GATE GIVES AN OUTPUT SIGNAL IF '--
_,.-...,,9-3 f HS\ LS-3-58C LS-3-58D AMY INPUT ARE PRESENT .....__
- ~_;)2 RESET NOT GATE:
UNIT 1, RHR (LPCI) l
- DIV II AUTO INIT SIGNAL ,.,.-=,,-,,:-:-,--:-,,-,,, - UNIT 2, RHR (LPCI) 1 RLY-74-10A-K73B 1-47E610-74-3. K-71 y y (INPUT)
DIV II !NIT SIGNAL H- ITHIS DWG, DET F3 1 OA-K368 ~H UNIT 1, CS DIV II AUTO INIT SIGNAL..-". 1-RL Y-7!S-14A-K11 B -..,J-47E610-75-2. H-8 I I '--
- I I (OUTPUT)
UNIT 2. RHR (LPCI) DIV II AUTO INIT SIGNAL THIS DIG DET Fl I NORMA.MA~ (9-3) THE *Nor* GATE GIVES AN OUTPUT SIGNAL ONLY IF THERE IS NO INPUT SIGNAL
- t ~10A-K7JB " ' HS (HS-74-154) \ 74-154 RHR <LPCI/ AUTO !NIT - SEAL-IN '- _;,,* INHIEiIT K YLOCK '--
INHIBIT SWITCH
- UNIT PRIORITY DG BKR 10A K36A(B) - T RE-TRIP SIGNAL CH B 2-47E610-75-2, B-7 10A-K107B __/
I - TO UNIT 2 ECCS 10A-K109B INHIBIT AUTOMATIC (LPCI) START OF RHR PUMPS (2B ~ 20).
- 10A-K73B PREFERRED PUMP LOGIC 2-45E765-4, C-4 - 10A K36B - THIS DWG, OET E3 " INHIBIT AUTOMATIC OPENING OF LPCI - INJECTION VALVE FCV-74-(67). ..,__---------------!: 2-45E779-22. G-5 - 10A-K73A(B) RHR (LPCI) AUTO INIT LOGIC INHIBIT SIGNAL INHIBIT THE INITIATION OF THE UNIT 1 (DET H-3 THIS SHEET) ECCS PREFERRED PUMP LOGIC ON A UNIT 2 (DIV II) LPCI SIGNAL l-'"'-'"-'="-'--"'.:..:..-'-'"'-"'-"'-"'=""----1 1 1 THIS DWG, DET F-J ")o - RHR (LPCI) AUTO INITIATION .__I_NH_I_*_Ir_IN_o_I_c*_r_I_o,_._ _ _ _ _ _-{ii)~ 9_3 J- - I 2-45E7 65-4. CB I
TO UNIT 1 RHR AND CORE SPRAY ECCS PREFERRED PUMP LOGIC CHANNEL A (B)
~ ),.Q IL-74-154 AMENDMENT 26 1-+7E610-7+-3, I-+ "> - TO RHR PUtr.f>S 28 AND 2D, RHR (LPCI) POWERHOUSE PUMP TRIP LOGIC AUTOMATIC - DIV II (CHANNEL 8) RHR AUTO INIT SIGNAL, CHANNEL A (B) U-47E610-75-3, G-4 "> INITIATION INHIBIT UNIT 2 - DET E3 DET F3 LOGIC DET H3 BROWNS FERRY NUCLEAR PLANT - DIVISION II FINAL SAFETY ANALYSIS REPORT K- ECCS PREFERRED PUMP LOGIC - MECHANICAL CONTROL DIAGRAM - COMPANION DRAWINGS:
1-47E610-74-1 , -2. -3
- 2-47E610-74-1 .-2 - 3-47E610-7+-1,-2,-3 FIGURE 7.4-7b I I I I ~ I I I I I I I I I I I I I 2
I I I I 3 I I I I I I I I 4 I I I I I I I I I I 5 I I I I I I I I 6 I I I l I I I I I I I I I 7 I I I I BI I I I I I I I 9 I I I I I I I I I I 10 I I
BFN-22 Figures 7.4-7c through 7.4-7h (Deleted by Amendment 22)
~ ~
AMENDMENT 23 8"°'HS P't:RRY HUCLEAR rLANT FINAL SAFETY At4ALYSIS R£PORT PRE-ACD l COt1 A CO SICtlAI. Air:CHAMICA.l COMTIOL OIACIMI f'IOURE 7.4-7;
- .. ,_,,,.. __ ,.,...__,...W!A:O., j.! .~ >1--...i-,.Ji~l* ...-.. 1o.-- - ~** -t'*iiioo-: :1-*,.,..,,..;n...+=~~*~* ;."".,.,,_,,_. __ ..t.,-1,,..;.;,,.4, ~1'-ll--- lo;~fl:.;J. ioo1IJi .;:t.;../...--~ .. ;t.*..;..,,1 .. ' ***--~ -'-*- * * * * * * *******., _ . , . . . ..~. . . . . . .J!~~.,. .i~
_,_____ ~ "-..,. ... ..,._, . . , _ u.-..,_ ._...... .
BFN-22 Figures 7.4-7j through 7.4-7n (Deleted by Amendment 22)
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UNIT1 DIVISION I T>l< "- " o;.l [ " \<:S /,N lllJH'IJT 1:C.l.llf.1U.Um 1 *1t< m "MT
.1 AMENDMENT 27 POWERHOUS E UNIT1 BROWNS FERRY NUCLE AR PLANT FINAL SAFETY ANALYSIS REPORT ECCS PREF PMP RESIDUAL HEA T REMOVAL SYSTE M MEC HANICAL CONTROL DIAGRAM FIGURE 7 .4-7p
BFN-16 Figure 7-4-8 Deleted by Amendment 9.
BFN-22 Figures 7.4-8a through 7.4-8d (Deleted by Amendment 22)
BFN-22 Figure 7.4-9 (Deleted by Amendment 22)
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