ML17226A116

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Revision 25 to the Updated Safety Analysis Report, Chapter 15, Figures 15.0-1 Through 15.5-1
ML17226A116
Person / Time
Site: River Bend  Entergy icon.png
Issue date: 07/28/2017
From:
Entergy Operations
To:
Office of Nuclear Reactor Regulation, Office of Nuclear Material Safety and Safeguards
Shared Package
ML17226A087 List:
References
RBG-47776, RBF1-17-0089
Download: ML17226A116 (35)
v • d • e


Text

16( 140 1w 8C 60 40 D w a 8 0 Lu c 4 / 0 G NATURAL PUMP CtRCULATlON 20 40 60 80 100 0 CORE FLOW (Y RATED) FIGURE 15.0.1 im GENERIC POWER/FLOW MAP RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 100 80 SCRAM WORTH AT 100% =

0 0.5 1 .o 1.5 2.0 2.5 3 3.5 TIME AFTER SENSED PLANT VARIABLE EXCEEDS SCRAM SETPOINT FIGURE 15.0-2 SCRAM REACTIVITY CHARACTERISTICS 120 100 0 00 6 8 E c -~ SCRAM TECHNICAL SPECIFICATION ROD POSITION TIME % INSERTION SECONDS 0 1 10 40 75 0.060 4 0.100 - 0.1w 0.060 + 0.138 - 0.188

+ 0.317 - 0.307 0.060 + 0.874 - 0.924 0.050 + 1.020 - 1.07 0.5 1 .o 1.5 2.0 2.5 3 .O I 3.5 4.0 FIGURE SCRAM TIME CHARACTERISTICS RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 40 I- 2 20 w a 10 - RIVER B CORE EOC1 - RIVER BEND EOEC I 1 0.02 0.1 0.2 0.4 0.7 1.0 FRACTIONAL 1 NSERTION FIGURE 15.0-4 CONTROL CELL CORE SCRAM R EACTlVlTY COMPARISON

~~- RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 150. (1 w + !& ux 1 10. 0. TINE ISEC) , 10. -25. FEEOURTEA FLOW t 4 20. -11 I ' '4 10. 1. z -1. - > I FIGURE 15.1-1 AUTO FLOW CONTROL RIVER BEND STATION UPIWT"' SAFETY ANALYSIS REPORT 0 c I NEUTRON FLUX 2 AVE SURFACE HEAT 3 CORE INLET FLOW CORE INLET SUB 0. 25. 65. I VESSEL PRES RISE (P 2RELlEF VALVE FLOW FLUX 3 BYPASS VALVE FLOW 125. 25. I\ I .I C. 2c. 43. EL. TlME (SEC) TlME (SEC) I LEVEL(INCH-REF-SEP-SKIRT 2 VESSEL STEAMFLOW 3 TURBINE STEAMFLOW 150. 4 FEEDWATER FLOW 1 FIGURE 15.1-2 OF FEEDWATER HEATER, I MANUAL FLOW CONTROL RIVER BEND STATION I UPDATED SAFETY ANALYSIS REPORT RIVER BEND STATIONUPDATED SAFETY ANALYSIS REPORTFEEDWATER CONTROLLER FAILUREFIGURE 15.1-3TIME (SECONDS)TIME (SECONDS)TIME (SECONDS)TIME (SECONDS)REACTIVITYCOMPONENT(S)(PERCENTOFRATED)

I NEU 1011 FlUX 2 AV( SUIIHtt nux I VES a

HOI u ur no 2 SAF "um I lf i! ..... 5 UJ 1-l tt.t \\ IM.t !.... ( 0 1-z UJ u 0:: UJ **.* e:: IM.t \. ... rr r-..-. *** '*' l t.t "*' . .. .... ** * ** .. "** .... TIME (SECOND S) TIME (SECONDS)

I I.EY L II NCH -lll' rP*SitiiTI 2VU tl STUNlC \.1 IIUCTIYIT U.l IIUCTI TT , .... * :tmm l.t iii l; / i= z UJ z 0 / ... 0 t-Jj u ...___.___

>-1-> ... i= .... UJ FIGURE 15.2-1 0:: PRESSURE REGULATOR

  • I tt. I *** ... . .... ll.t -*l.t *** * ** "** **** .. .. DOWNSCA LE FAI LU RE TIME (SECON DS) TIME (S ECONDS) Perc e nt rated power refe renced to 3039 MWt RIVER BEND STATION UPDATED SAFETY ANALYSIS REPO RT RE VI S IO N 17 150. 0 100. a !+ z 8 50. a & W 0.

300. 200. I I - 2. u. 6. 8. TIME (SECI TIME (SECI I 12 I I I r, I TIME (SEC) - M ;n z W 7 D CL x er, CI + ._ *- 0. k- -1. > k- u W a - a -2.

2. 4. 6. 8. TIME [SEC) 15.2-2 RIVER BEND STATION RIVER BEND STATIONUPDATED SAFETY ANALYSIS REPORTLOAD REJECTIONWITH BYPASS FAILUREFIGURE 15.2-3TIME (SECONDS)TIME (SECONDS)TIME (SECONDS)TIME (SECONDS)REACTIVITYCOMPONENT(S)(PERCENTOFRATED) 0 W c U LL 0 z u w a %

150. 100. 0. 0. 2. 4. 6. 8. TIME ISECI I I -loo.o. F...,....I

2. 11. I TIME (SECI 1. I I 8. I I ~ 0. I
2. u. 6. 8. TIME ISECl -

r UPDATED SAFETY ANALYSIS REPORT 1 H£UTIOtFlUI 2 AV( SU fACt FL ! COlt I E.l r lOII o I I w I f-"' :.r I IM.t j <.Iii C LL 0 z w w .... e:: **t. *.* *.* * .* TIME (SECO NDS) l lE. Yf.LI IICH**lF *S£1'* ITJ 2 VtsSEL lftAIIILON 3 TUIIIII Sf£AULOII t .... ' .... .. I . . . *I* .*.* *** , .. . .. TIME (SE CONDS) l VESSEL PIUI RIUII'S I 2 UfUY 'UU£ rLOII **** ' 'lli.m n&! .*. ' -I ----*; I ...... L_ ***

.... . ..* * ** TIME (SECONDS) 1 ** I ' 't' lJlO' , ** C!)IIJI I l (fl i= z w z o I c 1 I I [l. ***I lw I> 2 0 u f-> f= I I I I I 0 *t.tl 1 JJ <( w 0::: . .. , .. . . TIME (SECONDS)

Percen t rated power referenced to 3039 MWt FIGURE 15.2-5 TURBINE TRIP WITH BYPASS FAILURE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 17

VESSEL PRES RISE (PSI) 2 RELIEF VALVE FLOW 3 BYPASS VALVE FLOW I LOSS OF CONDENSER VACUUM AT 2 INCHES PER SECOND RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT i- 1. 300. I. I -2. I UPDATED SAFETY ANALYSIS REPORT

G loo. tr_' h 6 50. J: n: +- 0. 0. 2. u. 6. ISECI 200.

0. 00. 0. 2. LEVEL (INCH-REF-SEP-SKIRT) 2 VESSEL STEAMFLOW 3 TURBINE STEAMFLOW FEEDWATER FLOW - I 6. 8.

300. - VESSEL PRES RISE (PSI) 2 RELIEF VALVE FLOW 3 SAFETY VALVE FLOW ( ) RELIEF VALVE FLOW ( ) BYPASS VALVE FLOW ( ) 0. 0. 0. B :: z =, c 3 8 -2. -P 4 VOID REACTIVITY 2 DOPVEACTIVITUC .J3-SCRAM REACTIVITY - TOTAL REACTIVITY 4. 6. FIGURE 15.2-9 OF ALL CONNECTIONS I I BEND STATION LL SI) 125. 7s. 25. 0. 10. 20. 30. 40. (SECI 75. -2s. 25. 0. 10. 20 30. UO. iIHE ISCCI ~-

REPORT 1040 PSIA, 549°F TO 100 PSI, 33OOF 100 PSI, 33OOF TO 14.7 PSI, 125OF1 NORMAL SHUTDOWN DEPRESSURIZE VESSEL TO (OFFSITE POWER)

MAIN CONDENSER I' I I ADS/ RELIEF VALVE ALTERNATE PATH NORMAL SHUTDOWN (ONSITE POWER) DEPRESSURIZE VESSEL VIA MANUAL REUEF VALVE ACTUATION

+ RHR SUPPRESSION POOL COOLING NORMAL SHUTDOWN INITIATED P = 1040 PSIA T = 549OF I I I ADSfREUEF VALVE ALTERNATE PATH AUTOMATIC RELIEF VALVE ACTUATION DEPRESSURIZE VESSEL VIA MANUAL REUEF VALVE ACTUATION

+ RHR SUPPRESSION POOL COOLtNG SHUTDOWN ACHIEVED VESSEL HEAD r REMOVED ~~

SUMMARY

OF PATHS AVAILABLE TO ACHIEVE COLD SHUTDOWN -

BEND UPDATED SAFETY ANALYSIS REPORT Initial pressure- 1072 psiaInitial temperature- 553 °FFor purposes of this analysis, the following worst-case conditions are assumedto exist:(1)The reactor is operating at 102% nuclear boiler rated thermal power; (2)A loss of power transient occurs (see Section 15.2.6); and(3)A simultaneous loss of onsite power (Division 1), which eventually results Inthe operator not being able to open one of the RHR shutdown cooling linesuction valves.Initial pressure- 1072 psia Initial temperature- 553 °FOperator ActionsDuring approximately the first 10 minutes, reactor decay heat is passed to thesuppression pool by the automatic operation of the SRVs. Reactor water level is returned to normal by the automatic operation of HPCS and RCIC.After approximately 10 minutes, it isassumed one RHR heat exchanger isplaced in the suppression pool cooling mode to remove decay heat. At this time,the suppression pool will be 113° F. At approximately 24 minutes into thetransient, the operator initiates depressurization of the reactor vessel. Controlled depressurization procedures consist of controlling vessel pressures and water level by using selected SRVs, RCIC and HPCS systems.When the reactor pressure approaches 100 psig, the operator prepares foroperation of the RHR system in the shutdown cooling mode. At this time (152min), the suppression pool temperature is 168°F.System pressureapproximately 100 psig System temperatureapproximately 340 °FThe operator establishes either one of two closed cooling paths as follows:(a)Utilizing RHR Loop B, water from the suppression pool is pumpedthrough the RHR heat exchanger (where a portion of the decay heatis removed) into the reactor vessel. The cooled suppression pool water flows through the vessel (picking up a portion of the decay heat), out the ADS valves, and back to the suppression pool. This alternate cooling path is shown in Figure 15.2-15. Cold shutdown is achieved approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after the transient occurs.(b)Utilizing RHR Loops B and C together, water is taken from thesuppression pool and pumped directly into the reactor vessel. The water passes through the vessel (picking up decay heat) and out the ADS valves returning to the suppression pool as shown In Figure15.2-12. Suppression pool water is then cooled by the operation ofRHR Loop B in the cooling mode as shown in Figure 15.2-12. in this alternate cooling path, RHR Loop C is used for injection and RHR Loop B for cooling. Cold shutdown is achieved approximately 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> after the transient occurred.System pressureapproximately 100 psig System temperatureapproximately 340 ºFOperator ActionsUtilizing RHR Loop A, as Shown in Figure 15.2-16, instead of Loop B, analternate cooling path is established as in Activity C1 of item 2(a) above.RIVER BEND STATIONUPDATED SAFETY ANALYSIS REPORTACTIVITY C1 ALTERNATE SHUTDOWNCOOLING PATH UTILIZINGRHR LOOPS B AND CFIGURE 15.2-12REVISION 14SEPTEMBER 2001 REVISION 14SEPTEMBER 2001RIVER BEND STATIONUPDATED SAFETY ANALYSIS REPORT RPV PRESSURE RESPONSEFAILURE OF RHR SHUTDOWN COOLINGACTIVITY C1(A)FIGURE 15.2-13 REVISION 14SEPTEMBER 2001RIVER BEND STATIONUPDATED SAFETY ANALYSIS REPORT RPV PRESSURE RESPONSEFAILURE OF RHR SHUTDOWN COOLINGACTIVITY C1(B)FIGURE 15.2-13a REVISION 14SEPTEMBER 2001RIVER BEND STATIONUPDATED SAFETY ANALYSIS REPORT TEMPERATURE RESPONSEFAILURE OF SHUTDOWN COOLINGACTIVITY C1(A)FIGURE 15.2-14 REVISION 14SEPTEMBER 2001RIVER BEND STATIONUPDATED SAFETY ANALYSIS REPORT TEMPERATURE RESPONSEFAILURE OF SHUTDOWN COOLINGACTIVITY C1(B)FIGURE 15.2-14a (I 11 I

FIGURE 15.2-1 5 ACTIVITY C1 -ALTERNATE SHUTDOWN COOLING PATH UTILIZING RHR LOOP B RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT L

I I

I FIGURE 6 ACTIVITY C2-ALTERNATE SHUTDOWN COOLING PATH UTILIZING RHR LOOP A RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT e 0. 0. 10. 20. 30. UO . TIME (SECI 11 FtEDWRTEP FLM 5 150. 1 4 0. 10. 20. 30. UO . TIME ISECl .u x 125. 75. 25. -25. 0. 10. 20. TINE tSECi I. UO . U TOTRL FiEqCTIVITY I 10. TIME 20. ISECI 30. UO. FIGURE 15.3-1 TRIP OF ONE RECIRCULATION PUMP RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT I VESSEL PRES RISE (PSI) FLUX 2 RELIEF VALVE FLOW 125. 3 BYPASS VALVE FLOW 75. 25. -25. CI . 10. 20. 311. '10. TIMF [SECI I LEVEL (INCH-REF-SEP-SKIRT I VOID REACTIVITY 2 VESSEL STEAMFLOW 3 TURBINE STEAMFLOW 4 FEEDWATER FLOW 1. I 2 OOPPLER REACTIVITY 3 SCRAM REACTIVITY 4 TOTAL REACTIVITY 3 -0 111. 211. 311. 40. TIMt ISf C1 FIGURE 15.3-2 TRIP OF BOTH RECIRCULATION PUMPS RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 150. II CORE INLET SUB ;; loo. Y IE LL Q I- z u w w 50. a P- c I I I I 0. 10. 20. 30. 40. 0. TIME (SECJ I 150. 100. 50. 0. 0. 10. 20. 30. 110. TIME lSECl I) TIME (SEC) 4 TOTFIL RtLCn VITY 2 7 2 3 1 3 1 3 u 1 1 ~ 10. TIME 20. (SECI 30. 110. I FIGURE 15.3-3 FAST CLOSURE OF ONE MAIN RECIRCULATION VALVE I RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT Q "' f-< < "' 0 fZ "' u "' i.t.l 0.. 1 NE UT RON FLUX 2 AVE. S URFACE H EAT F LU X 3 CO ME IN LET F LO W a so.l i \ I I I 4 CO ME INLET S UB &00. %0. 2 ..... ... ** T IM E (SEC) LE VEL (INCH REF-SEP-SKIRT) 2 3 4 uo 2 ,....._ aao. f2 '/ . I' L\, L:.l ;_\ 2 2 2 4 \. :l ' 4 . :110. o ..... Ui. a. ** TIME (S EC) -.: P ercen t rated power referenced to 2894 MWt = "' fZ ""' :z: 0 u ,.. .... > 6 .., til 1 U5 75 2 1 VE SS EL P RES RISE (PS I) %) %) \ 2 /::-45 I 4 5 45 ....... . 1/ ' 3 3 3 3 25 12 3 2 ? ' 2 ....*.... . -.15.0. 10. x . --... TIME (S E C) 1. VOl 0 H.EA CT IV I" I'Y 2 DOPPLER HEACTIVI TY 3 SC RA M REAe'£l.VlTY '* I ¥ ,/ I I 4 TO TA L REACTIVI TY -** ...2.0: 20. TIM E (S EC) FIGURE 15.3-4 F AS T CL OSURE OF TWO MAI N RE C IR CULA TI NG V ALVES RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 17 150. 3 13 0. 10. 20. 30. YO. 43 TIME ISECl 3 7 4 >r I- w - - I- u &l U a FIGURE 15.3-5 SEIZURE OF ONE RECIRCULATION PUMP RIVER BEND STATION UPDATE D SAFETY ANALYSIS REPORT 1 NEUTRON FLUX I 1 I I 2 AVE SURFACE HEAT FLUX 3 CORE INLET FLOW 4 CORE INLET SUB 50. .oo. 50. 0. 0. 10. a. 30. UO. TIP!* ISECI 1 LEVEL (1NCH.REF.SEP-SKlRTl I I I 2 FCV 1 POSITION (",>I 3 PUMP SPEFD 1 I"*,) 4 FEEOWATER FLOW

0. 10. 20. 30. '10. TIME (SECI 1 VESSEL PRES RISE (PSI) I I I 12 RELIEF VALVE FLOW 4 DIFFUSER FLOW 1 ("->I 100. 50. 0. -50. 0. 10. 20. 30. 40. TIME [SECI 1 VOID REACTIVITY I I I 12 DOPPLER REACTIVITY 3 SCRAM REACTIVITY
1. - Y, c 0. m L W L S 0 U
  • B B-- -1. w - i$ -2. 0. uii 2. 4. 6. 8. TIRE (SECI FIGURE 15.4-1 ABNORMAL STARTUP OF IDLE RECIRCULATION PUMP RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 1 ? VESSEL STEAMFLOW 3 TURBINE STEAMFLOW 4 FEEDWATER FLOW LEVEL (INCH REF SEP SKIRT) 250. J . II x 1 VESSEL PRES RISE (PSI) 12 RELIEF VALVE FLOW 3 BYPASS VALVE FLOW 4 DIFFUSED FLOV! 1 (%,I t 0. 10. 20. 30. 40. TIME (SECI >- > I- I- -I. - - $ -2. I FIGURE 15.4-2 __ FAST OPENING OF ONE MAIN RECIRCULATION LOOP VALVE AT 30% PER SECOND RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT 1 50. 1 NEUTRON FLUX ' I I jS Ft...ux i 4 COflE INL&:f SUB m t oo. lil i $0. *SEer'* t LEVEl. INCH-REF-SEP

-SKIRT 2 VESSEL STIOAMFLOW 2'50. *::J .TtJRBINE STEAMFLOW 4 FEEDWATER FLOW Pe rc e nt rated po wer referenced to 2894 MWt ;; I 200 _y; ......-"/ 100 *-2!lt \... 0 :-* *--100.0. 10. I.IS """' 1 VliSSEl..

PRES f'\ISE ( 2 RELIEF VP. LVI: f' 1.0 3 BYPASS VALVE FLO 4 DIFFUSER FLOW I I $ Olf'FVSE:ft FLOW:! ( IS_ SH w *W * ) .l. 20.--30. .. _ 110. TIME *SECI 'VOID REACTIVITY 2 DOPi'LER R£ACTIV tTY I F I 1 ll o .1 .va W<ct \I :::J-----===: I I E i 15\:C) 8. FIGURE 15.4-3 FAST OPENING OF BOTH MAIN RECIRCULATION LOOP VALVES AT 13% PER SECOND RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 17 1 NEUTRON FLUX 2 PEAK FUEL CENTER TEMP 3 AVE SURFACE HEAT FLUX I4 FEEDWATER FLOW 150. ! I I I 5 VESSEL STEAM FLOW L 1 LEVEL (INCH-REF-SEP-SKIRT)

FIGURE 15.5-1OF HPCS 2 W R SENSED LEVEL (INCHES) 3 N R SENSED LEVEL (INCHES) 5 DRIVE FLOW 1 (%) 125.. "4 CORE INLET FLOW (%) u5 Y5 4 5; 45 75. 3 .3,-----J-

INADVERTENT STARTUP 3 4 ? I ? 3 ? I I I 1 VESSEL PRES RISE (PSI) 2 STM LINE PRES RISE (PSI) 3 TURBINE PRES RISE (PSI) 4 HPCS FLOW (% OF FW) 5 CORE AVE VOID FRAC(%) 6 TURBINE STEAM FLOW (%) L 4 u Ll 3 3 3 12 - -_ 17 l?! -25. -1111l111*

U 0. 10. 20. 30. 40. TIME [SECl

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