ML21286A378

Amendment 29 to Updated Final Safety Analysis Report, Chapter 7, Figure 7.2, Reactor Protection System

ML21286A378
Person / Time
Site:	Browns Ferry
Issue date:	10/04/2021
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
Shared Package
ML21286A574	List: ML21277A142 ML21286A195 ML21286A196 ML21286A197 ML21286A198 ML21286A199 ML21286A200 ML21286A201 ML21286A204 ML21286A205 ML21286A206 ML21286A210 ML21286A211 ML21286A212 ML21286A213 ML21286A216 ML21286A217 ML21286A218 ML21286A219 ML21286A220 ML21286A221 ML21286A222 ML21286A223 ML21286A224 ML21286A225 ML21286A226 ML21286A227 ML21286A229 ML21286A230 ML21286A231 ML21286A232 ML21286A233 ML21286A234 ML21286A235 ML21286A236 ML21286A237 ML21286A238 ML21286A239 ML21286A240 ML21286A241 ML21286A242 ML21286A243 ML21286A244 ML21286A245 ML21286A246 ML21286A247 ML21286A248 ML21286A249 ML21286A250 ML21286A252 ... further results
References
Download: ML21286A378 (18)

Text

c;;zo~ V-WLJSV-~ :1 L9 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT A

REACTOR PROTECT ION SYSTEM SINGLE LINE FIGURE 7.2-1

REACTOR PROTECTION SYSTEM AUXILIARY INSTRUMENT ROOM PANEL FIGURE 7.2-2

BFN-22 Figures 7.2-3a through 7.2-3l (Deleted by Amendment 22)

l A ';j&;Si CRO CISCHA>lGE VOLUHE HIGH WATER LEVEL

....TOOIIN c MODE I

A SYPASS l<lOE SWITCH AUTOMATIC

~ESET

• ~

IN SHJTOOWN)

A EAST CRO DISCHARGE VOLUME HIGH WATER LEVEL A BWASS A PRIMARY CONTAII'+ENT HIGH PRESSLJiE A NJCLEA~ SYSTEM A MAf'tU.AL H!GH PRESSURE SCRAM A REACTO~ LOW WAT£R LEVE:L

'}NEUTRON MC>>>ITORING SYSTEM E

REACTOR P"flOTECTION SYS'I'EM REAC'I'OR PROTECTION SYSTEM REACTOR PROTECTION SYSrEM LOGIC ,,

LOGIC LOGIC NOTE. CONTACTS SHOWN IN NORMAL. COI'IJITlON AI

"

• OPEN O~Y WHEN REACTOR ll£RMAL POWER >30~

• • • BYPASS OF MSL.IV ONLY WHE:N HOOE SWlTCH IS NOT IN RUN AMENDMENT 22 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT LOGICS IN SYSTEM B

ACTUATORS LOGIC LOGIC LOGIC LOGIC LOGIC LOGIC AI A2 A3 Bl 82 83 EAI GA2 CAJ Fat Ha2 Del ACTUATOR LOGICS ASSOCIATED ACTUATOR LOGICS ASSOCIATED WITH TRIP SYSTEM A WITH TRIP SYSTEM B

~

%:a

,.o

.. )>

~

t AAI AAl r., r.,

CA3 GAl

1. AAI

1. ' AA3

• {)82

1. 8a1 Ha2 0a3

~ Ha2

1. ' 0a3

~ Da2

t 8a3

-n iii*

Cl 3110 ,...,.:z:

r::C

-n"'"

.... fTl z ~CA2  :;!c GA2 #GA2 ;t CA2 # 8a1 -:1 Fat #Fat ~ 8at c;,.o "'"'

c JJ e'Sl Ill ii'

-e:O

-<;a 0

~

m .. "'

.... ~ 3

z:c fTl t:"

,.. 0

,g ... ~n z

-<r --l U1 -

n

.. 2

)>

n vom

"';;o ~

GROUP I SOLENOIDS GROUP 2 SOLENOIDS GROUP 3 SOLENOIDS GROUP 4 SOLENOIDS GROUP 1 SOLENOIDS GROUP 2 SOLENOIDS GROUP 3 SOLENOIDS GROUP 4 SOLENOIDS

""0 ;10

~

m-u

-ur m

0,..

>QZ NOH. CONTACTS SHOWN IN NORMAL CONDITION

MAIN STE:AM LINES TURBINE TlRB!NE ISOLATED CONTROL STOP VALVE VALVE FAST CLOSURE CLOSURE I

MOOE SWITCH I

NUCLEAR SYST(t.t T

IN "'-"' PRESSURE

>600 PSI NUCLEAR SCRAM NEUTRON SYSTEM DISCHARGE MONITORING PRESSURE VCLUME SYSTEM HIGH WATER TRIP LEVEL HIGH MOOE PRIMARY' REACTOR REACTOR SWITCH CNTMl VESSEL THERMAL IN PRESSLilE WATER POWER >30" St-I.ITOOWN HIGH LEVEL LOW 1 1 SCRAM AMENDMENT 22 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT REACTOR PROTECTION SYSTEM SCRAM FUNCTIONS FIGURE 7.2 6

BFN-16 Figure 7.2-7 Deleted by Amendment 13.

AMENDMENT 25 Fii1AL SAFETY Ai1ALYSIS REPORT

I;!

=.""" L-----i'l---'-~~

--;---=~,~,

BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT INsRlRAU~TEON~ ptNOGTlNCETEIROINNGSYoVAEGMRAM FIGURE 7 .2-7d

_j I

-I I

-l F!NALSAFETYANALYSISREPORT I 'iEACTORFROTECTIONSYSTEM

~ JX: L I ARY INSTRUMENT

REACTOR PROTECTION SYSTEM AUXILIARY INSTRUMENT ROOM PANEL FIGURE 7 2-9

SENSORS n A S n c 0 I

TRIP SYSTEM A POWER BUS t ~

{© ~

} c t I TRIP SYSTEM B POWER BUS CHANNELS TRIP SYSTEM A TRIP SYSTEM B

~

NOTE CONTACTS SHOWN IN NORMAL OJNDITION !0 AI

!© A2 Sl S2 REACTOR PROTECTION SYSTEM LOGICS TYPICAl. CCN'IGLRA TION FOR

• SCRAM DISCHARGE VOl. LIME HIGH WATER LEVEL TI..R6INE CONTRCF.. VAL.VE FAST CLOSLRE REACTOR VESSEL LOW WATER LEVEL PRIMARY CONTAINMENT HIGH PRESSURE I'IJCLEAR SYSTEM HIGH PRESSURE AMENDMENT 22 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT TYPICAL ARRANGEMENT OF CHANNELS AND LOGICS FIGURE 7.2-10

TRIP SYSTEM A POWER BUS TRIP SYSTEM B POIER BUS

]

5 l SVOH SWS-l ll A

TUABINE STOP VALVE CLOSURE CHANNELS TRIP SYSTEM B TRIP SYSTEM A

~-------------~

~

c

,..o ~

%~

E c G 8 F .0 H i:-t i ;1 rJ.

U'I zrrl

!!!1[ m'" 0

-tllll

~, ~ o<llll ~ 82 81

~~, ~~

,.c rrl z

AI 1\l.

~.JOiJ rn -I

.!. 0 ct -cr REACTOR PROTECTION SYSTEM LOGICS

.a I! a* U~~m

. ~* 1 __. NOTE: CONTACTS SHOWN IN NOR~l COfiJITIOM {STOP VALVES >9()!1. OP£NI I !l i10.

~

~~

(j)

_.-4 I

I t t A-ll .....,121  ! AOOOCill l.-.21 l ~I) ,j, AOOIDal t*'"'""

1- AOBilAUI A080AI21

• A086"lll :1 A086A(21 AOOID121 t*oa&C<)) AOI6Ct21 ~ *'"'"'" :t *-21 r-=1-AC POWER rl~'

AC POWER I

IMOTOR- lt.IOTDR '

GENERATOR GENER,TOR SET AI >,. 81 >H SET 01

'-y--1 ~

......__, ~ \......y-' ~ \......y-J "-y--J STEAM STEAM STUll STEAM STEAII STEAM STEAM STEAM LINE C . LINE B LINE 0 LINE A LINE B LINE C LINED LINE A MAIN UEAM LINE ISOLATION CHANNELS (SWITCH CONTACTS SHOWN IN POSITIONS WHEN ISOLATION VALVES MO~E TIIAN 900. OPEN!

TRIP SYSTEM A TRIP SYSTEM B l I l

f. <...

II (I) ac 1 ll-1!.

!!m z.,a...

,.o r~;

4.10

)>

z 0

~

rrl SHAll {

LINE A A E AI r:}su-u STEAJll c c r LINE B LINE J.

"L I

A2 STEAM STEAM

}LINEO L1 NE {

n 1 Bl

} Ll~

STEt.M STEAM C LINE {! 0 II 1

Bl

}

STEAM LINED

~!(l

~~ ~

REACTOR PROTECTION SYSTEM LOGICS

.... ;: & ,. c rrl

!CONTACTS SHIM'N lit NORMAL CONDITIONI N-'!

~I i.

rn

-cr z KEY: A08DA - STEAM LINE A, INBOARD VALVE 1-14 AOIIOC- STEAM LINE C, INBOARD VALVE 1-37 i*! 4.10111 ij;)o

-I AOB6A- STEAM LINE A, OUTBOARD VALVE 1-15 A086C-A0800 -

STEAM LINE C, STEAM LINE 0, OUTDMRD VALVE 1- 38 INBOARD VALVE 1- 5 l i

gtf m"V

,r o,.

I m___., A0808- STEAM LINE B. INBOARD VALVE 1-26 A086B- STEAM LINE B, OUTBOARD VALVE 1-27 A086D- STEAM LINED, OUTBOARD VALVE 1-52

oX

BFN-16 Figure 7-2-13 Deleted