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 |
Revision as of 19:38, 5 April 2019
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) l-ZLll3£t-z r< ti 4 'ffij\ ... ,, ** ,., Ill m AMENDMENT 27 POWERHOUSE UNIT2 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT H IGH PRESSURE COO L ANT IN J ECTION SYS T EM FLOW D I AGRAM FIGURE 7 .4-lb SH 1 H G c B A 8 HIGH SYSTEM DIAGRAM FIGURE 7 .4-lb SH 2 H G c B
,. c .. 8 AMENDMENT 27 POWERHOUS E UNIT1 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT HIGH PRESSURE COOLANT I NJECTION SYSTEM FLOW DIAGRAM FIGURE 7 .4-1 b SH 3 B A 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) '*
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- 22)
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£-tL-OL93Lt-Z PIS-3-74A REACTOR PRESS. LOW (TYPICAL OF 4) PIS-3-748 l y I I I I y REACTOR PRESS. LOW I I I I I LS PIS-68-95 PIS-68-96 I I I I I I I PIS-64-SBA DRYWELL PRESS. HIGH (TYPICAL OF 4) PIS-64-588 --TEST _._ 9-3 HS \ 75 51 AUTO I I I y DRYWELL PRESS. HIGH DET A3 DET 83 UNIT 2. RHR CLPCI) I THIS owe. DET 03 10A-K9A UNIT 1, RHR (LPCI) I 1-47 E 610-7 4-3. G7 1-RLY-74-10A-K73A 11 47E610 75 2, 08 '" <THIS DWG DET 03 UNIT 1 . CS DIV I AUTO INIT SIGNAL 1 RLY 75 14A K11A I ........ < ' < 0 _J SEAL-IN TRIP PUMP 1 2-45E765-4, CS INHIBIT PUMP 1 2 -730E927 -;* r'> TO UNIT PRIORITY DG BKR RE-TRIP !NIT LOGIC TO RHR PUMPS 2A AND 2C, DIV I (CHANNEL A) AUTO START AND PUMP TRIP LOGIC DIV I (CHANNEL A) DETAIL D UNIT 2 ECCS PREFERRED PUMP LOGIC DET C3 UNIT 1, RHR (LPCI) DIV II AUTO INIT SIGNAL ,.,.-=,,-,,:-:-,--:-,,-,,, 1 RLY-74-10A-K73B 1-47E610-74-3. K-71 ITHIS DWG, DET F3 UNIT 2, RHR (LPCI) DIV II !NIT SIGNAL 1 OA-K368 I I I I I I I I UNIT 1, CS DIV II AUTO INIT SIGNAL..-". 1-RL Y-7!S-14A-K11 B -..,J-47E610-75-2. H-8 I UNIT 2. RHR (LPCI) DIV II AUTO INIT SIGNAL THIS DIG DET Fl I t " ' T -TO RHR PUtr.f>S 28 AND 2D, PUMP TRIP LOGIC DIV II (CHANNEL 8) I I I I DET E3 I I I I I 2 I 2-45E7 65-4. CB I I I I 3 I I I I I I I I .,. I I I PIS-64-58C PIS-64-588 DRYWELL PRESS HIGH (SEE DETAIL B THIS SHEET) REACTOR PRESS LOW (SEE DETAIL A THIS SHEET) '°' PB J J HS\ RESET I I I I I I 1 I I LS-J-58A RX VESSEL LVL LOI (TYPICAL OF 4) LS-3-58C 10A-K9A y I 10A-K36A(B) TO UNIT 2 ECCS PREFERRED PUMP LOGIC THIS DIG, DET C-3 I I y 10A-K73A(B) RHR (LPCI) AUTO INIT LOGIC INHIBIT SIGNAL (OET G-3 THIS SHEET) I TO UNIT 1 RHR AND CORE SPRAY ECCS PREFERRED PUMP LOGIC CHANNEL A (B) RHR AUTO INIT SIGNAL, CHANNEL A (Bl T L...J1-47E61D-75-3, DET D3 I I I I I I LS-3-58B LS-3-58D I UNIT 1 ACCIDENT SIGNAL. DIV I (CH Al (DET C-3 THIS SHEET) I UNIT PRIORITY DG BKR RE-TRIP SIGNAL CH A c 1 > *-* UNIT 2 DIVISION I DRYWELL PRESS HIGH (SEE DETAIL B THIS SHEET) REACTOR PRESS LOW (SEE DETAIL A THIS SHEET) MOM PB _,.-...,,9-3 f HS\ RESET I SEAL-IN LS-3-58A RX VESSEL LVL LOW (TYPICAL OF 4) LS-3-58C l y LS-3-58B LS-3-58D y I I I I I I I I I I I I I I I I I I I I I I I I I THIS DIG. DET C-3 I 2-47E610-75-2, A 7"> --h 10A-K107A _/ 10A-K109A INHIBIT AUTOMATIC (LPCI) START OF RHR PUMPS 2A 2C INHIBIT AUTOMATIC OPENING OF LPCI INJECTION VALVE FCV 74 SJ INHIBIT THE INITIATION OF THE UNIT 1 ECCS PREFERRED PUMP LOGIC ON A UNIT 2 DIV I LPCI SIGNAL RHR (LPCI) AUTO INITIATION INHIBIT INDICATION. I 2-45E765-4, G-4 I 2-45E779-22. G-5 1 THIS DWG, DET D-J '-----------------{A 9-3 -IL-74-153 (9-3) RHR (LPCI) AUTOMATIC INITIATION INHIBIT LOGIC DE T G-3 HS (HS-74-154) \ 74-154 RHR <LPCI/ AUTO !NIT '-_;,,* INHIEiIT K YLOCK INHIBIT SWITCH 10A K36A(B) UNIT PRIORITY DG BKR RE-TRIP SIGNAL CH B 2-47E610-75-2, B-7 10A-K107B __/ I I I I 10A-K73B 10A K36B TO UNIT 2 ECCS PREFERRED PUMP LOGIC THIS DWG, OET E3 " 10A-K73A(B) RHR (LPCI) AUTO INIT LOGIC INHIBIT SIGNAL (DET H-3 THIS SHEET) I TO UNIT 1 RHR AND CORE SPRAY ECCS PREFERRED PUMP LOGIC CHANNEL A (B) 1-+7E610-7+-3, RHR AUTO INIT SIGNAL, CHANNEL A (B) U-47E610-75-3, DET F3 I-+ "> G-4 "> DIVISION II I I 4 I I I I I I I I I 5 I I I I I I I I I I 6 l I I I I 10A-K109B INHIBIT AUTOMATIC (LPCI) START OF RHR PUMPS (2B 20). INHIBIT AUTOMATIC OPENING OF LPCI 2-45E765-4, C-4 INJECTION VALVE FCV-74-(67). ..,__---------------!: 2-45E779-22. G-5 INHIBIT THE INITIATION OF THE UNIT 1 ECCS PREFERRED PUMP LOGIC ON A UNIT 2 (DIV II) LPCI SIGNAL 1 l-'"'-'"-'="-'--"'.:..:..-'-'"'-"'-"'-"'=""----1 1 THIS DWG, DET F-J ")o RHR (LPCI) AUTO INITIATION .__I_NH_I_*_Ir_IN_o_I_c*_r_I_o,_. ______ 9_3 ),.Q IL-74-154 I I I I I 7 RHR (LPCI) AUTOMATIC INITIATION INHIBIT LOGIC DET H3 COMPANION DRAWINGS: 1-47E610-74-1 , -2. -3 2-47E610-74-1 .-2 3-47E610-7+-1,-2,-3 I I I I B I I I I I I I I I 9 I I I I I > I I I I I I I I I I I I 10 I I I I I I I I I I 1 I NOTES: 1. ALL COMPONENTS ARE PREFIXED "2-* UNLESS OTHERWISE SHOWN. 2. FOR GENERAL NOTES AND REFERENCE DRAWINGS SEE 2-47E610-75-1 .2. 3. DELETED SYMBOLS: ANO GATE: OR GATE: (INPUT A) (INPUT BJ I I (INPUT A) (INPUT B) I I (OUTPUT) (OUTPUT) THE "AND* GATE GIVES AN OUTPUT SIGNAL IF AL.I.. INPUTS ARE PRESENT THE "QR* GATE GIVES AN OUTPUT SIGNAL IF AMY INPUT ARE PRESENT NOT GATE: (INPUT) (OUTPUT) THE *Nor* GATE GIVES AN OUTPUT SIGNAL ONLY IF THERE IS NO INPUT SIGNAL AMENDMENT POWERHOUSE UNIT 2 26 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT ECCS PREFERRED MECHANICAL PUMP LOGIC DIAGRAM CONTROL FIGURE 7.4-7b '-A '--'--'--8 '--'-C '---------D --------'--'--'--'--'--'--'--'--.....__ '--'--'-- BFN-22 Figures 7.4-7c through 7.4-7h (Deleted by Amendment
- 22)
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... ...... . *.. ,_,,,.. __ .. .-.. __ ..t.,-1,,..;.;,,.4, .. ;t.*..;..,, 1 .. ' _,_____ "-..,. ... ..,._, ..,_ u.-..,_ ._ 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; BFN-22 Figures 7.4-7j through 7.4-7n (Deleted by Amendment
- 22) z : ,::. -.. -_ *-* ..JUi j l L .U ( .... 1.: .* _ _._.i --***** 1 , 4 ** !IU ,,;_jJ, .* bJ, .
,_ I :, .l ,1 Jllr.1 ,._ !1-1 .. * .. :*:.1.1 i:..' ! I , __ *:-id*' I. ,.!_,_, *-.,. H.:..-,,, r tr "'"" 1°" "'"'* "" "'"'" "'"* ""' .... ,,, UNIT1 DIVISION I "'""""'"'"'""'"""' '""'""' """"""""""""""""""'"' """""'"'"'"" T>l<"-" o;.l["\<:S/,N lllJH'IJ T 1: C.l.llf.1U.U m 1*1 t<m" MT .1 AMENDMENT 27 POWERHOUS E UNIT1 BROWNS FERRY NUCLE A R PLANT FINAL SAFETY ANALYSIS REPORT ECCS PREF PMP RESIDUAL H EA T R E MOVAL SYSTE M MEC H ANICAL 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) : ,*:.}}