Text

Updated Final Safety Analysis Report (Ufsar), Amendment 27, 14.5 Figure - Analyses of Abnormal Operational Transients
	ML18024A339
Person / Time
Site:	Browns Ferry
Issue date:	10/05/2017
From:	; Tennessee Valley Authority
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML18018A778	List: ML18018A780; ML18018A781; ML18018A783; ML18018A784; ML18018A785; ML18018A787; ML18018A788; ML18018A790; ML18018A792; ML18018A793; ML18018A795; ML18018A796; ML18018A797; ML18018A798; ML18018A800; ML18018A801; ML18018A802; ML18018A804; ML18018A806; ML18018A807; ML18022A114; ML18022A115; ML18022A116; ML18022A117; ML18022A118; ML18022A119; ML18022A120; ML18022A121; ML18022A123; ML18022A124; ML18022A125; ML18022A127; ML18022A128; ML18022A129; ML18022A130; ML18022A131; ML18022A132; ML18022A133; ML18022A148; ML18022A155; ML18022A156; ML18022A157; ML18022A158; ML18022A159; ML18022A161; ML18022A162; ML18022A163; ML18022A164; ML18022A165; ML18022A166; ... further results
References
	Download: ML18024A339 (59)
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BFN-19 Figures 14.5-1, 14.5-2, 14.5-3, and 14.5-4 (Deleted by Amendment 19)

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AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT LOSS OF FEEDWATER FLOW LONG TERM 102P/100F FIGURE 14.5-17c

NEUTRON F'LUX PK F'UEL CENTE. TEMP.

AVE SURF'ACE H AT F'LUX n;:t;cw,;;ER F'LC 0

w I-e::::

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a. 10. 20. 30. 40.

TVA os2n1 011.lO 1747.S TIME (SEC)

LEVEL(INCH-REF SEP-SKRT~

W R SENSED LE EL(INCHES N R SENSED LE EL(INCHES CVRC: *;;~L~i r"LO' \~i

-120.'-"--'-'-.........._._..._..._._._ _ _ _ ___.__ _ _ _ __.__ _ _ _ __,___ _ __

0. 10. 20. 30. 40.

TVA 052797 01 lJO 17*7.6 TIME (SEC)

AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT LOSS Of AUXILIARY POWER TRANSFORMERS 102P/100f FIGURE 14.5-180

VESSEL PRES R:SE (PSI)

STM LINE PRES f'llSE (PSI)

TURBINE PRES SE (PSI)

\:vi\E ll*cC:i SUc (6TU/L61vl/

250.

10. 20. JO. 40.

!VA 1l 11.l0 061797 11'7.6 TIME (SEC)

NEUTRON FLUX SURFACE HEAT LUX 0

w r- 80.

<l'.:

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u 40.

0:::

w 0....

Q.LL.J.....J.-..i.....:....1...1...._,_...__ _-======d:====:;:::::_~-L~~~~_JL__~~~

o. 25. 50. 75. 100.

NA 011.lO 062797 1747.6 CORE FLOW(%)

AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT LOSS OF AUXILIARY POWER TRANSFORMERS 102P/IOOF FIGURE 14.5-18b

I), 10. 2'J' i[M( (5ECl 0

u.J c

1.i:::

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10. 20. 50.

~* '): :...: TIME (SEC>

Cf':!'>, ""°*'

AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT LOSS OF AUXILIARY POWER ALL GRID CONNECTIONS 102P/105F FIGURE 14.5-19a

vO!C R(,;Cfl'lifV j I

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IVA OIC.I c:ro~'l7 1J<tO.l AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT LOSS OF AUXILIARY POWER ALL GRID CONNECTIONS 102P/105F FIGURE 14.5-19b

,\IEUiRCN Fi.ux I PK FUEl CENTE~ TE~P.

I ~VE SURFACE H Ar FLUX r"EE:DWr\iEri r1...c*;

0 w

1CO.

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rv..

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O'Jll.9 TIME (SEC)

LEVEL(INCH-REFtSEP-Si<Ril w R SENSED LE EL(INCHES N R SENSED LEtEL(INCHES CGRE INLEi F'LO' / \r.j 1so. l------t~=<M:-fi:,e~w-1--1--~:-;;~,,_,- - t - - - - - - - r - - - -

0.w....~J..J_._.._._........._ _ _ _ _ __.__ _ _ _ __,___ _ _ _ _....__ _ _ ~

o. 4. 8. 12. 16.

r'IA 062797 OOOJE Q91J.9 TIME (SEC)

AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT RECIRCULATION FLOW CONTROL FAILURE-DECREASING FLOW 102P/100F FIGURE 14. 5-20a

~Q_._._.._._~_._,._._..._._ _ _ _ _ _...__ _ _ ___.__ _ _ _ __,__ _ __

. 0. 4. 8. 12. 16.

lV*

061797 OOB~E 091J.9 TIME (SEC)

NEUTRON F"LUX SURFACE HEAT 1LUX 120. 1 - - - - - - - + - - - - - + - - - - - - - r - - - - - - t - - - - -

Cl w

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0. 25. 50. 75. 100.

,..,. 008JE C52797 091J.9 CORE FLOW (%)

AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT RECIRCULATION FLOW CONTROL FAILURE-DECREASING FLOW 102P/100F FIGURE 14.5-20b

0 w

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NA 05'7~7 OCACI

0918.S TIME (SEC)

I* LEVEL(INCH-RfflSEP-SKRTl

~ w R 5ENSEO LE EL(INCHES N R SENSED LE EL(INCHES CurtE INLET FLG I (7.j 1:0.l--~~~~--!i~~~:--R~~;w-.+-f--~~~,~~'~~r--~~~~---t~~~~-

100. l.-----+------+-------r------;----

AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT ONE RECIRCULATION PUMP TRIP 102P/100F FIGURE 14.5-21a

~o_ ............................................_..__ _ _ _ _ _,___~ __ ___.~-----'----~

. 0. 4. 8. 12. 16.

'NA CCACI 052791 091 e.~ ilME (SEC)

NEUTRON F"LUX SIJRF'ACE HEAT LUX 120. r - - - - - - : - - - - - - + - - - - - - + - - - - - - + - - - - -

a w

f- 80.

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0. 25. 50. 75. 100.

rw. CCACI C5279? 0918.~ CORE FLOW (%)

AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT ONE RECIRCULATION PUMP TRIP 102P/100F FIGURE 14.5-21b

BFN26

Figure14.522a

DeletedbyAmendment26.

BFN26

Figure14.522b

DeletedbyAmendment26.

l'EUTRON FLUX PK CTR TJf> Clit-0 AV ROOl AV£. SIM'"ACE HE.Al FlJJX

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i3

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15!0.J TIME <SECJ 12 . 16.

ADMENDMENT 20 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT TWO RECIRCULATION PUMP TRIP WITH VFDS 1 DOP/100F FIGURE 14. 5-22c

l£1/Q(Jt-£H-REF- P-~RTl U R 9':NS.D lEvEL 11\CHESl N R a:.NSEO LE\.'!L 11\lCHE.Sl CCRE lhlf.T Fl.OW IY.l 1s-0.f------f------+------l--'--llfill<LilWL.L.--J-____c<Z.L_ _

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0.

1$9.l 8.

TIME <SECl ADMENDMENT 20 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT TWO RECIRCULATION PUMP TRIP WITH VFDS 1 OOP /1 OOf FIGURE 14.5-22d

VESSEL PRES RISE. (f'S[)

2 STN L.Jt.f PRES Rf if: <PSI>

~ Tl.RSI~ PRES 1m CPSfl

~.I~TC"~( TU!l9tt)

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ADMENDMENT 20 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT TWO RECIRCULATION PUMP TRIP WITH VFDS 1 OOF/100F FIGURE 14.S-22e

N£UTRON FLUX t Sl>>ACl !EAT FU 1~0.

17

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~ CORE FLOW (X J ADMENDMENT 20 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT TWO REC! RCULAT ION PUMP TR IP WITH VFDS 100P/1 OOF FIGURE 14. 5-22 f

~

NEUTRON FLUX I

I Pl< F'UE.L C:ENTE.. TE.MP.

AVE SURFACE H AT FLUX i'E<:cw.:_;r,:;< f"LO 0

w

!- !GO.

<(

n:::

~

0 I-z LJ u 50.

~

w CL

10. 20. JO. 40.

!VA' 00946 OoZl97 09~2.J TIME (SEC)

10. 20. JO. 40.

NA 0627'7 00946 09~2.l TIME (SEC)

AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT ONE RECIRCULATION PUMP SEIZURE 102P/100F FIGURE 14. 5-23a

I VESSEL. PRES RI E fPSI)

STM LINE: PRES 1SE (~SI)

TUR81NE PRES SE (PSI) iJIFFU se:;;: r-1..c;; ,

JC0. 1-------l'--atf:r7.;@-..;=.;,.:;w...J2------+-------;-------

LOW (:1:)

-150. l....L...J.....L...L..L....1-1-1-L...L-----.L-------'------......_----

. o. 1o. 20. :io. 40.

~ti 791o9*6 om.J TIME (SEC) rt NEUTRON FLUX I SURFACE Hf;AT F1LUX 120.1-------+-----~-----+------+-----

Cl w

f- 80.

0:::

LI...

0 f-z w

u 40.

0:::

w a.

0.LLJ.....L..L..L...L...l-1-L...l..--====:::====::t::::::.----__J_------L-----

O. 25. 50. 75. 100.

TVA 061197 009*6 09~2.J CORE FLOW (%)

AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT ONE RECIRCULATION PUMP SEIZURE 102P/100F FIGURE 14.5-23b

BFN26

Figure14.524a

DeletedbyAmendment26.

' VESSE'.L F'RES R1$E (PSI)

SiM LINE PRES ISE (PSI)

TURBINE PRES SE (PSI)

C.IF'ri.iSC:r< ri..OW 200. f-------+-OO~~~:;w-.Q..--------------+-----

LO~ (7.)

I

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0. 4. 6. 12. 16.

!VA 070J91 0268*

1012.2 TIME (SEC)

NEUTRON f'LUX SURFACE HEAT UX I \

Cl w

I- 80.

<(

a:::

LL..

0 I-z w

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a:::

w 0....

D............................_._.__._......,_ _ _ _ _...__ _ _ __..,.--.,__ _ _-.1..-_ _ _ ~

0. 25. 50. 75. 100.

IV* 02684 OIOJ97 IO!U CORE FLOW (%)

AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT RECIRCULATION FLOW CONTROL FAILURE-INCREASING FLOW 75P/52F FIGURE 14.5-24b

~UTRON nux PK cm Ttfl' Cl-fJS AV ROD!

AVE 9.IRFl\CE. ~A Fi.lit f"~ECWATER f"LOIJ T!l'f CSECJ ADMENDMENT 20 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT RECIRCULATION FLOW CONTROL FAILURE-INCREASING FLOW 75P/52F VFD SPEED CONTROL MAXIMUM PUMP TORQUE SET BY BREAKDOWN TORQUE FIGURE 14.5-24c

l£\oiUI~F--!: ~-9<RTJ

h R: SQ.E£O LEVEL 1~1-f:Sl 1 N R Sfl.St(l LE'-'E.l l~Sl 250_

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Tll'E !SEC> "* 16.

ADMENDMENT 20 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT RECIRCULATION FLOW CONTROL FAILURE-INCREASING FLOW 75P/52F VFD SPEED CONTROL MAXIMUM PUMP TORQUE SET BY BREAKDOWN TORQUE FIGURE 14. 5-24d

-1000L. .L..L.L..J...1..JLI-.L..L,-'-.-----,.L.-----l-',-.- - - - - ! - ' & - .- - - -

,., f.~~ Tiff: ISEC l ADMENDMENT 20 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT REC! RC UL AT ION FLOW CONTROL FAILURE-INCREASING FLOW 75P/52F VFD SPEED CONTROL MAXIMUM PUMP TORQUE SET BY BREAKDOWN TORQUE FIGURE 14.5-24e

Plff'lsPf.f.O ()-:1 Pltf" 2 SPilll (;.!)

F't.WITOO'll.£ Ci'l ORM. Fl.O'.JlOCP CXl

....1-----+-----+------+-----1----

zoo.

0

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~

a. J>. JS.

'* Tll-£ ISEC)

ADMENDMENT 20 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT RECIRCULATION FLOW CONTROL FAILURE-INCREASING FLOW 75P/52F VFD SPEED CONTROL MAXIMUM PUMP TORQUE SET BY BREAKDOWN TORQUE FIGURE 14. 5-24 f

h NEIJTRON F'\..UX PK F'UEL CENiE TEMP AVE SURFACE H AT FLUX FC:C:C'NATC:R FLO

i 100.

w.J

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e:::

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0

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u so.

er:

w 0..

20. 40. 60. eo.

TIME (SEC)

LE'JEL(INCH-REF' SEP-SKRfl W R SENSED LE EL(INCHES N R SENSED LE EL(INCHES ccnc: il.fL.C:'i r"LO \4/

o.

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0. 20. 40. 60. 80.

TV*

010191 Ole.JB 1123.J TIME (SEC)

AMENDMENT 17 BROWNS f ERRY NUCLEAR PLANT f INAL SAFETY ANALYSIS REPORT IDLE RECIRCULATION LOOP STARTUP 75P/52F COUPLER POSITfON 19%

FIGURE 14.5-250

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ADMENDMENT 20 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT IDLE RECIRCULATION LOOP STARTUP 75P/52F VFD SPEED CONTROL 1 OO'F IDLE LOOP 400 RPM MAX, PUMP SPEED FI GU RE 14. 5-25c

LEva<I~REF'-~ P-SKRT)

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so.

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HME ISECl ADMENDMENT 20 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT IDLE RECIRCULATION LOOP STARTUP 7 5P /52F VFD SPEED CONTROL 100-F IDLE LOOP 400 RPM MAX. PUMP SPEED FIGURE 14. 5-25d

VESSEL ms RI::£ <PST>

t STM LI~ PRES RIPE CPSJ)

TLR9[1£ ~S RI~ (PSJl Tl.RB!t..E'. ST[flH f-L ~ (i()

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TIME CSECl ADMENDMENT 20 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT IDLE RECIRCULATION LOOP STARTUP 75P/52F VFD SPEED CONTROL 1 OO'F IDLE LOOP 400 RPM MAX. PUMP SPEED FI GU RE 14.5-25e

Pt.tP I SoEED I

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I, NEUTRON FLUX ~

PK FUEL CENiE TEMP AVE SURFACE H AT Fl,UX Fi.:EL::"';,:;iC:i\ FLCY Cl w 100.

~

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0. '

o. 20. 40. 60. 80.

lYA o~o 191 016CJ 1 128.0' TIME (SEC)

I LEVEL(INCH-REF SEP-SKRTl

\V R SENSED L~ EL(INCHES N R SENSED LE EL(INCHES CuRt. iHi...ET rLO'. (%)

0.

20. 40. 60. 80.

1'1* 016Cl 070197 I 1215.0 TIME (SEC)

AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT IDLE RECIRCULATION LOOP STARTUP 75P/52F COUPLER POSITION 111 FIGURE 14.5-26a

225 I CORE INLET SU Bk (BTUgBM}

STM LINE PRES 1SE PSI~

TURBINE PRES F< SE 01F'*usc:R .=-;,.c;*.** ;

...... - - - * - - - ... I -

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l l

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o. 20. 40. 60. 80.

IV& Cld<:J 070191 1128.0 TIME (SEC)

' NEUTRON F"LUX

SURF" ACE HEAT f _ux

~r I

0 w

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I/

~

u...

0 1-z w

u

~ 40. ....

w n..

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0. 25. 50. 75. 100.

TVA 016Cl 070197 1128.Q CORE FLOW (%)

AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT IDLE RECIRCULATION LOOP STARTUP 75P/52F COUPLER POSITION 11J FIGURE 14.5-26b

NEUTRON F"LUX PK FUEL CENTE. TEMP AVE SURFACE H AT f'lUX

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TVA 1210~

021Jga 1a1J.J TIME (SEC)

-so.1...1-..1-L-'-'-'-.J...J......J-J------L-----....L..-----.J.__ _ __

0. 20. 40. 60. 80.

!VA 12105 021J95 181J.J TIME (SEC)

AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT IDLE RECIRCULATION LOOP STARTUP 30P/52F COUPLER POSIT!ON 19%

FIGURE 14.5-270

' CORE INLET suel (eru~Le'~)

STM LINE PRE:S ~ISE PSI~

TURBINE PRES RISE PSI CilF"rUSErt r~OW 1 (,.j

-- ,,._r-. ..... ,_, i 225.

TURBINE:' STEAM LOW ' (7.)

125.

\ v *~

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rr "I * * .

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o. 20. 40. 60. 80.

!VA 021 J9S 1210, .

ID 1l.J TIME (SEC)

NEUTRON FLUX SURF"ACE HE:AT UX 120. > - - - - - - - + - - - - - - l - - - - - - - + - - - - - - + - - - -

a w

- 80.

<(

0:::

l.J..

0 I-z w

u 40.

a::

w a..

25. 50. 75. 100.

!'\IA 021J98 1210~

IS1J.J CORE FLOW (%)

AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT IDLE RECIRCULATION LOOP STARTUP 30P/52F COUPLER POSITfON 19%

FIGURE 14.5-27b

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l LEV L ! (.~CH-RU-~E? *SKR r l 2 OOP LE.R R:~:; *1;: **

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3 TVR lNE SIEAllFL ~

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11 ME I SECOHOS I AMENDMENT 17 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT FEEDIATER CONTROLLER FAILURE-MAXIMUM DEMAND 75P/108F FIGURE 14. 5-28

h~\

i NEUTRO~ FL~ I VE 55£L 2 AV~ SURFACE 2 SAH rv I 3 CORE ! NLET

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