Text

6 to Updated Final Safety Analysis Report, Chapter 15, Accident Analyses, Figures
	ML18249A153
Person / Time
Site:	Brunswick
Issue date:	08/13/2018
From:	; Duke Energy Progress
To:	; Office of Nuclear Reactor Regulation
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ML18249A165	List: ML18249A126; ML18249A128; ML18249A129; ML18249A130; ML18249A131; ML18249A133; ML18249A134; ML18249A135; ML18249A140; ML18249A142; ML18249A143; ML18249A145; ML18249A146; ML18249A147; ML18249A148; ML18249A149; ML18249A150; ML18249A151; ML18249A153; ML18249A154; ML18249A155; ML18249A159; RA-18-0004, Duke Energy Transmittal of Topical Report DUKE-QAPD-001-A, Amendment 43; RA-18-0131, Technical Requirements Manual, Revision 66;
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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

26 Chapter:

15 Page:

1 of 2 LIST OF FIGURES FIGURE NUMBER TITLE FIGURE 15-1 PLANT SAFETY ANALYSIS METHOD FOR IDENTIFYING AND EVALUATING ABNORMAL OPERATIONAL TRANSIENTS FIGURE 15-2 PLANT SAFETY ANALYSIS METHOD FOR IDENTIFYING AND EVALUATING ACCIDENTS FIGURE 15-3 LOSS OF 100 DEGREE FEEDWATER HEATING MANUAL FLOW CONTROL, UNIT 2 -CYCLE 7 FIGURE 15-4 DELETED IN REVISION 21 FIGURE 15-5 FEEDWATER CONTROLLER FAILURE MAXIMUM DEMAND (EOC),

UNIT 1-CYCLE 22 FIGURE 15-6 DELETED IN REVISION 22.

FIGURE 15-7 FEEDWATER CONTROLLER FAILURE MAXIMUM DEMAND (EOC), UNIT 2 -

CYCLE 23 FIGURE 15-8 DELETED IN REVISION 22.

FIGURE 15-9 DELETED IN REVISION 22.

FIGURE 15-10 FEEDWATER CONTROLLER FAILURE WITH TBPOOS, ICF, AND NFWT, UNIT 2 - CURRENT CYCLE (EOC 23)

FIGURE 15-11 INADVERTENT HPCI ACTIVATION, UNIT 1 - CYCLE 9 (BOC9 TO EOC9)

FIGURE 15-12 INADVERTENT HPCI ACTIVATION, UNIT 2 - CYCLE 10 FIGURE 15-13 PRESSURE REGULATOR FAILURE (OPEN), UNIT 1 - CYCLE 1 FIGURE 15-14 PRESSURE REGULATOR FAILURE (OPEN), UNIT 2 - CYCLE 1 FIGURE 15-15 INADVERTENT OPENING OF A RELIEF OR SAFETY VALVE, UNIT 2 - CYCLE 1 FIGURE 15-16 GENERATOR LOAD REJECTION WITH 25 PERCENT BYPASS, UNIT 1 - CYCLE 1 FIGURE 15-17 GENERATOR LOAD REJECTION NO BYPASS WITH ICF, UNIT 1 - CURRENT CYCLE (EOC 22)

FIGURE 15-18 GENERATOR LOAD REJECTION, NO BYPASS, WITH ICF, UNIT 2 - (EOC 23)

FIGURE 15-19 TURBINE TRIP WITH 25 PERCENT BYPASS, UNIT 1 - CYCLE 1 FIGURE 15-20 TURBINE TRIP WITHOUT BYPASS WITH ICF, UNIT 1 - CURRENT CYCLE (EOC 22)

FIGURE 15-21 TURBINE TRIP WITHOUT BYPASS, WITH ICF, UNIT 2 (EOC 23)

FIGURE 15-22 DELETED IN REVISION 22.

FIGURE 15-23 DELETED IN REVISION 22.

FIGURE 15-24 CLOSURE OF ALL MSIV FLUX SCRAM, UNIT 1 - CURRENT CYCLE (CYCLE 22)

FIGURE 15-25 CLOSURE OF ALL MSIV FLUX SCRAM, UNIT 2 - (CYCLE 23)

FIGURE 15-26 EXTENDED POWER UPRATE MSIV CLOSURE WITH FLUX SCRAM (102 PERCENT INITIAL POWER)

FIGURE 15-27 UNIT 2 - CYCLE 1 LOSS OF AUXILIARY POWER (TRANSFORMER) WITH 25 PERCENT BYPASS FIGURE 15-28 UNIT 2 - CYCLE 1 LOSS OF AUXILIARY POWER (ALL GRID CONNECTIONS)

WITH 25 PERCENT BYPASS FIGURE 15-29 UNIT 1 - CYCLE 1 LOSS OF FEEDWATER FLOW FIGURE 15-30 UNIT 2 - CYCLE 1 LOSS OF FEEDWATER FLOW FIGURE 15-31 WATER LEVEL RESPONSE WITH REACTOR CORE ISOLATION COOLING FOR LOSS OF FEEDWATER FLOW EVENT AT ORIGINAL POWER I_

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

26 Chapter:

15 Page:

2 of 2 LIST OF FIGURES FIGURE NUMBER TITLE FIGURE 15-32 PRESSURE RESPONSE WITH REACTOR CORE ISOLATION COOLING FOR LOSS OF FEEDWATER FLOW EVENT AT ORIGINAL POWER FIGURE 15-33 UNIT 2 - CYCLE 1 TRIP OF ONE RECIRCULATION PUMP FIGURE 15-34 UNIT 1 - CYCLE 1 TRIP OF TWO RECIRCULATION PUMPS FIGURE 15-35 UNIT 2 - CYCLE 1 TRIP OF BOTH RECIRCULATION PUMPS FIGURE 15-36 UNIT 1 - CYCLE 1 SEIZURE OF ONE RECIRCULATION PUMP FIGURE 15-37 UNIT 2 - CYCLE 1 SEIZURE OF ONE RECIRCULATION PUMP FIGURE 15-38 SEIZURE OF OPERATING RECIRCULATION PUMP SINGLE LOOP OPERATION FIGURE 15-39 UNIT 2 - CYCLE 1 ABNORMAL STARTUP OF IDLE RECIRCULATION PUMP FIGURE 15-40 UNIT 1 - CYCLE 1 ABNORMAL STARTUP OF IDLE RECIRCULATION PUMP FIGURE 15-41 UNIT 1 - CYCLE 1 RECIRCULATION FLOW CONTROL FAILURE - INCREASING FLOW FIGURE 15-42 UNIT 2 - CYCLE 1 RECIRCULATION FLOW CONTROL FAILURE - INCREASING FLOW FIGURE 15-43 UNIT 2 - CYCLE 1 MAXIMUM ROD WORTH VERSUS POWER LEVEL FIGURE 15-44 UNIT 2 - CYCLE 1 ROD DROP ACCIDENT (POWER RANGE) PEAK FUEL ENTHALPY FIGURE 15-45 MAIN STEAM LINE BREAK ACCIDENT BREAK LOCATION I_

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-1 Page:

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-3 Page:

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-4 Page:

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

26 Figure:

15-5 Page:

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

26 Figure:

15-7 Page:

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

26 Figure:

15-10 Page:

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-11 Page:

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-13 Page:

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-14 Page:

1 of 1 PRESSURE REGULATOR FAILURE (OPEN), UNIT 2 - CYCLE 1

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-15 Page:

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-16 Page:

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

26 Figure:

15-17 Page:

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

26 Figure:

15-18 Page:

1 of 1 GENERATOR LOAD REJECTION, NO BYPASS, WITH ICF, UNIT 2 -CURRENT CYCLE (EOC 23)

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-19 Page:

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

26 Figure:

15-20 Page:

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

26 Figure:

15-21 Page:

1 of 1 TURBINE TRIP WITHOUT BYPASS, WITH ICF, UNIT 2 - CURRENT CYCLE (EOC 23)

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

26 Figure:

15-24 Page:

1 of 1 CLOSURE OF ALL MSIV, FLUX SCRAM, UNIT 1 - CURRENT CYCLE (CYCLE 22) 11/01/17

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

26 Figure:

15-25 Page:

1 of 1 CLOSURE OF ALL MSIV, FLUX SCRAM, UNIT 2 -CYCLE 23

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UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-26 Page:

1 of 1 EXTENDED POWER UPRATE MSIV CLOSURE WITH FLUX SCRAM (102 PERCENT INITIAL POWER)

-25.0 25.0 75.0 125.0 175.0 225.0 275.0 325.0 375.0 0.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 Time (sec)

Vessel Press Rise (psi)

Safety Valve Flow Relief Valve Flow Bypass Valve Flow

-50.0

-25.0 0.0 25.0 50.0 75.0 100.0 125.0 150.0 175.0 200.0 0.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 Time (sec)

Level - Inch above Sep Skirt Vessel Steam Flow Turbine Steam Flow Feedwater Flow

-2.0

-1.5

-1.0

-0.5 0.0 0.5 1.0 1.5 0.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 Time (sec)

Void Reactivity Doppler Reactivity Scram Reactivity Total Reactivity 0.0 50.0 100.0 150.0 200.0 250.0 0.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 Time (sec)

Neutron Flux Ave Surface Heat Flux Core Inlet Flow Core Inlet Subcooling

% Rated

% Rated HH Reactivity Components($)

% Rated HH 4 + t HH

~

mo Zc mA G)m

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-27 Page:

1 of 1 LOSS OF AUXILIARY POWER (TRANSFORMER) WITH 25 PERCENT BYPASS, UNIT 2 - CYCLE 1

(., DUKE ENERGY 0 w I-C[

0::

LL 0

t-z w

u 0::

w Q.

I NEUTRON FLUX I VESSEL PRES. RISE (PSI) 2 PEAK FUEL CENTER TEMP.

2 STM. LINE PRES. RISE(PSI)

'3 AVE. SURFACE HEAT FLUX 3 TURBINE PRES. RISE (PSI) 4 FEEDWATER FLOW 4 BYPASS VALVE FLOW (%)

150.t----+-----t-----15 VESSEL STEAM FLOW 200.t----+-----t-------15 RELIEF VALVE FLOW 6 TURBINE STEAM FLOW 2

I LEVEL ( INCH* REF-SEP-SKIRT)

I NEUTRON FLUX 2 WR SENSED LEVEL (INCHES) 2 SURFACE HEAT FLUX 3 NR SENSED LEVEL (INCHES) 100.

4CORE INLET FLOW(%)

120.

5 DRIVE FLOW I (%)

2 0 w t-

50.

<( 80.

0::

LL 0

t-z l&J 0.

u 40.

0::

w Q.

50................................._ ___..._ ___

0

10.

20.

30.

40.

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-28 Page:

1 of 1 LOSS OF AUXILIARY POWER (ALL GRID CONNECTIONS)

WITH 25 PERCENT BYPASS, UNIT 2 - CYCLE 1

(., DUKE ENERGY I NEUTRON FLIJ)(

I VESSEL PRES. RISE (PSI) 2 PEAK FUEL CENTER TEMP.

2 STM. LINE PRES. RISE(PSI)

!AVE. SURFACE HEAT FLU)(

3 TURBINE PRES-RISE (PSI) 4FEEOWATER FLOW 48YPASS VALVE FLOW(%)

150.t-------tt----+-----1* !iVESSEL STUM FLOW 125.1-+---------11------+-----1!iRELIEF VALVE FLOW(%)

~

=

100.------11------+----+-----+----

o... z...

u

~ 50_.... _-...:-....111,.:... __

---1, ___

--i-__

IL 2

20.

4 -

TIME ( SEC.II LEVEL (INCH*REF *SEP-SKIRT) 2 WR SENSED LEVEL (INCHES) 3NR SENSED LEVEL(INCHES) 6 TURBINE STEAM FLOW 75.Hf---'\\-t---,l--* ~,_.----+---+------::2

10.

20.

30.

I NEUTRON FLU)(

TIME (SEC.)

2 SURFACE HEAT FLUX 40-I e

10o.------1t-----+-----14CORE INLET FLOW(%)

1201-----1------+----+--,...-:-r---

50RIVE FLOW t (0,4) 0 w

~ 80.

a:...

0...

a:

Ill u a:

II.I IL

10.

20.

40.

25.

50

75.

100.

TIME (SEC.)

CORE FLOW(%)

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-29 Page:

1 of 1 LOSS OF FEEDWATER FLOW, UNIT 1 - CYCLE 1 150.L.

i

.. J I

-* -t---+~l-.,--1'1.JJl-i !

I rl-"""~,-::--+~1

--i- -----*

--i----

1---

1

' 111'1.UJ 2

l'I.JJl 1211.

5.,.f--- -

le 15 I

I

~-------~--------t -

~

I II).

lSECJ ob_.1-1................... ~---~------~

COflE Fi..1':~ ti:!

L..... 't I i

-+---

I

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-30 Page:

1 of 1 LOSS OF FEEDWATER FLOW, UNIT 2 - CYCLE 1

(., DUKE ENERGY 0

~

a:

0... z w

u a:

L,J

a.

I NEUTRON FLUX I VESSEL PRES. RISE (PSI) 2 PEAK FUEL CENTER TEMP.

2 STM. LINE PRES. RISE(PSt) 3AVE. SURFACE HEAT FLUX 3 TURBINE PRES. RISE (PSI) 4 FEEOWATER FLOW 4 BYPASS VALVE FLOW(%)

150.i------"t-----"t--------t5VESSEL STEAM FLOW ZOO.t----+-----+-------t5RELIEF VALVE FLOW(%)

z

20.

3.

40,.

TIME (SEC.)I LEVEL(INCH*REF*SEP-SKIRT) 2 WR SENSED LEVEL (INCHES) 3 NR SENSED LEVEL (INCHES) 6 TURBINE STEAM FLOW

10.

20.

30.

I NEUTRON FLUX TIME (SEC.)

2 SURFACE HEAT FLUX 40-200 1-----+----+-------1* CORE INLET FLOW(%)

120 '----+-----1------t----;-----

5 DRIVE FLOW I (0k) 0

80.

a:

llo 0... z lal u a:

lal

a.

25.

50

75.

100.

TIME (SEC.,

CORE FLOW (%)

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-31 Page:

1 of 1 WATER LEVEL RESPONSE WITH REACTOR CORE ISOLATION COOLING FOR LOSS OF FEEDWATER FLOW EVENT AT ORIGINAL POWER

(., DUKE ENERGY JO JIIO UVl!L INSIDE ll"'OUD LIVI&. oun,ci. SHflOUD TCW Of ACTIVE fUIEL 2111 It IOTIOM Of' AC'JIVI FUii. 11.* ft 1000

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-32 Page:

1 of 1 PRESSURE RESPONSE WITH REACTOR CORE ISOLATION COOLING FOR LOSS OF FEEDWATER FLOW EVENT AT ORIGINAL POWER

(., DUKE ENERGY J

i f

\\_

- **** I ** I I

I JIIII

\\

fllACTOfl Pfllnulll MAINTAINID SY Tu.lllNI *Yf!Ut VALVI I -,.......

I I

1000

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-33 Page:

1 of 1 TRIP OF ONE RECIRCULATION PUMP, UNIT 2 - CYCLE 1

(., DUKE ENERGY 150.

C w I-C II:

~ 100 0

5 I NEUTRON FWX 2 PEAK FUEL CENTER TEMP I VESSEL PRES. RISE(PSI) 2 STM. LINE PRES. RISE (PSI) 3 TURBINE PRES. RISE IPSI) 40IFFUSER FLOW I PC 3AVE. SURFACE HEAT FLUX 4FEEOWATER FLOW 5 VESSEL STEAM FLO W 160.1----+----t----l 5 DIFFUSER FLOW 2 PC 5

6 TURBINE STEAM FLOW I-z w

u II: *~

~~-

2 2

~

4

~

I w

IL 50 0 0.

I

4.

I

12.

16 TIME ( SEC.)I LEVEL (INCH-REF *SEP-SKIRT) 2 WR SENSED LEVEL 3 NR SENSED LEVEL (INCHES)

4.

6.

12.

I NEUTRON FLUX TIME (SEC.)

2 SURFACE HEAT FLUX

16.

15*0.1-----+---------14 CORE INLET FLOW 120J-----l----+----t----ll----

5 DRIVE FLOW I (0-',)

2 34

4.

8.

12.

16.

TIME (SEC.)

0 w

~ 80. t----t-----tt------,...... ---r--+---

a:...

0 I-

~ 40.t-------ll-----+------+-----+----

r 0.............. 1,&.&.... L------------'~---L---

o.

25.

50

75.

100.

CORE FLOW (%)

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-34 Page:

1 of 1 TRIP OF BOTH RECIRCULATION PUMPS, UNIT 1 - CYCLE 1

(., DUKE ENERGY 0

Cl a:

IL 0

t-z "'

u a:...

~

150 5

I NEUTRON FLUX 2 PEAK FUEL CENTER TEMP 3 AVE SURFACE HEAT FLUX 4 FEEDWATER FL!JN 5 VESSEL STEAMFlDW

8.

12.

TIME(SEC)

I LEI/EL (INCH - REF-SEP-SK1Rl1 2 DIFFUSER FlDW I (%)

3 DIFFUSER FLOW 2 (%)

4CCRE INLET FLO.V (%)

S DRIVE FLOW I (%)

I VESSEL PRES. RISE ( PSI) 2 STEAM LINE PRES RISE (PSI) 3 TU RINE PRES RISE (PSI) 4 CORE INLET SUB( BTU/LB) 5 CORE AVE VOID FRAC(%)

6 TURBINE TEAM FLOW(%)

5 2

16.

I NEUTRON FLUX 2 SURFACE HEAT FLUX 1sol----+---+----+----t---

1201---4---+----+---+---

8.

12.

TIMFISEC)

16.

s...

~

IL 0

t-z...

u a:...

00~....i.~...,2:1.s~-----,50,1;.---....,1~s.---.oo~---

coRE FLOW (%)

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-35 Page:

1 of 1 TRIP OF BOTH RECIRCULATION PUMPS, UNIT 2 - CYCLE 1

(., DUKE ENERGY I NEUTRON FWX I VESSEL PRES. RISE (PSI) 2 PEAK FUEL CENTER TEMP.

2 STM. LINE PRES. RISE(PSI)

SAVE. SURFACE HEAT FLU><

3TURBINE PRES. RISE (PSI) 4FEEDWATER FLOW 401FFUSER FLOW I PC 1so.1-------------SVESSEL STEAM FLOW 160.l----'--..,_---l------l!!DIFFUSER FLOW 2 PC 6 TURBINE STEAM FLOW

4.

-80¥-1.................. ~---f----:-----"':----

a.

12.

16.

o 4.

a.

12.

16.

TIME (S_EC.)ILEVEL(INCH*REF*SEP-SKIRT)

I NEUTRON FLUX TIME (SEC.)

2 WR SENSED LEVEl, 2 SURFACE HEAT FLUX

S NR SENSED LEVEL ( INCHES I l'"'01-----1---------4CORE INl.ET FLOW(%)

120.1-----+----1------------

~.

5 DRIVE FLOW I (04)

TIME (SEC.)

0 w

~ ao.1----1------1f.--..,,c..--1---.~--1----

~

... z

~ 40.-----------'---4-------

r so

75.

100.

CORE FLOW(%)

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-36 Page:

1 of 1 SEIZURE OF ONE RECIRCULATION PUMP, UNIT 1 - CYCLE 1

(., DUKE ENERGY II; 1-z..,

u a:..,

Q.

I NEUTRON FLUX 2PEAK FUEL CENTER TEMP.

I VESSEL PRES RISE 2STEAMLINE PRES

}~&~tR~~MP 150.. i----+---+---~ 5 VESSEL STEAM FLOW 80 3TURBINE PRES RI 4CCH: INLET S..S RISE (PSI)

SE(PSI}

\\BTU/LB) 5CCRE AVE VOID FRAC{0/gl LOW! Vol 5

4.

3 80 0

~,

B

12.

16.

TIME(SEC)

I LEVEL( INCH-REF-SEP-SKIRT) 2DIFFUSER FlDW I (%)

3 DIFFUSER FlDW 2 (0£cil 4 CORE INLET FLOW( 1/c,}

5 DRIVE FLOW I(%}

5/4'-

_5

............_6 -

4 4

I 2

-....... ~

)

4.

I NEUTRON FLUX 2 SURFACE t-EAT FLUX 6 TURBINE STEAM F 5

5 6

6 4

4 2

I I

8.

12.

16.

TIME(SEC}

12nl--------il----+---+----+---

4 5

0

~

a: 8Ql----+---+-,---'~-7!----+--

0 as u a:

\\IJ Q.

8.

12.

16.

25.

!:O.

75 100 TIME (SEC}

CORE FlDW (°lo)

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-37 Page:

1 of 1 SEIZURE OF ONE RECIRCULATION PUMP, UNIT 2 - CYCLE 1

(., DUKE ENERGY 150.

0 "'...

C a:

IL 100.

0... z...

u II:

50.

D.

I NEUTRON FWX 2PEAK FUEL CENTER TEMP.

3AVE. SURFACE HEAT FLUX 4FEEOWATER FLOW 5 VESSEL STEAM FLOW 160 5

/

80 5

0 \\

.\\ 4

-ao *.

I 5

6 -r---

3

.............-l 6

I VESSEL PRES. RISE (PSI) 2 STM LINE PRES RISE (PSI) 3 TURBINE PRES. RISE 401FFUSER FLOW I P (PSI)

C 5 DIFFUSER FLOW 2 P C 6 TURBINE STEAM FL ow 4

2 I

8.

12.

16.

0

4.

8.

12.

16.

TIME ( SEC.)I LEVEL (INCH-REF *SEP*SKIRT) 2 WA SENSED LEVEL 3NA SENSED LEVEL(INCHES)

TIME (SEC.)

I NEUTRON FLUX 2 SURFACE HEAT FLUX 15*0. 1------,1------11-----4 CORE INLET FLOW 1201----~---11------11------1---

5 DRIVE FLOW I (0.C.)

TIME ISEC.)

0..,

~ 10.1----11------tf-+----r-...:....---+---

a:

IL 0... z..,

~ 40.

CL

25.

50

75.

100.

CORE FLOW 1%)

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-38 Page:

1 of 1 SEIZURE OF OPERATING RECIRCULATION PUMP SINGLE LOOP OPERATION

( ~ DUKE I

ENERGY.

3 0

a..

1.7 1.6 1.5 E 1.3 0

1.2

\\.1

-~

/'

~

"\\

I

'I\\

I

......... V 1.0 0.0 0.5 1.0 1.5 2.0 2.5 3.0 J.5 Time (sec.)

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-39 Page:

1 of 1 ABNORMAL STARTUP OF IDLE RECIRCULATION PUMP, UNIT 2 - CYCLE 1

(., DUKE ENERGY 0 uJ I-C(

a:

~

0 I-z uJ 0 a:

uJ

11.

150 100 13 245 50 0 o.

15'0.

100.

50.

I-0 o.

I 13

~

4 5

IX __i

'l 2

10.

5

10.

I NEUTRON FLUX 2 PEAK FUEL CENTER TEMP.

3AV£. SURFACE HEAT FLUX 4FEEDWATER FLOW 5 VESSEL STEAM FL OW 200 120 I

3

-125 4

40.

-40

20.

30.

40-0 3

TIME (SEC\\ LEVEL (INCH*REF*SEP*SKIRT) 2 WR SENSED LEVEL 3 NR SENSED LEVEL 4 CORE INLET FLOW 5 DRIVE FLOW I (%)

3 4

3 2

L 5

20.

30.

40.

TIME (SEC.)

(INCHES)

(%)

120 0 w I-a:

~

0 I-z

-4 uJ u a:

w

11.

80 40 0 o.

5 6

4

10.

I NEUTRON FLUX 5

6 2

d I VESSEL PRES. RISE (PSI) 2 STM LINE PRES RISE (PSI}

3 TURBINE PRES. RISE 4DIFFUSER FLOW I P (PSI}

C 5 DIFFUSER FLOW 2 P C 6 TURBINE STEAM Fl OW 5

6 2

4

20.

30.

40, TIME (SEC.)

2 SURFACE HEAT FLUX t11

I*

t~OT ~

I 25

50.

75.

100.

CORE FLOW (%)

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-40 Page:

1 of 1 ABNORMAL STARTUP OF IDLE RECIRCULATION PUMP, UNIT 1 - CYCLE 1

(., DUKE ENERGY ci 100.

w a:

a:

~

..... z w

SC.

li w e; ob.

l!11.

10.

2G.

TIHE

20.

Tit£ 100 ~

511

~

JD.

IIIJ.

-liD~-

ISECl c Ill.

w...

IE

~

z::

~..

~

,a.

11,1:

ISECl l'ID!lfl."8ft i W:.\\ltA'r, l Dlf'FIIEO Fla<

II 111111 IP'SU ISi: '"'"

Ill 1 ~ DlmilM Puii I l\\1111,., STOii ~

1111

~

I

' l I

I

/

1---...

10.

IQ.

IU.

11HE ISECl IIL lS,.

CH FLOW m

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-41 Page:

1 of 1 RECIRCULATION FLOW CONTROL FAILURE - INCREASING FLOW, UNIT 1 - CYCLE 1

(., DUKE ENERGY z

~ so.

Db)-J *....LLJL..1..J....,l...L\\,;!-----.Jllll.l-----.i~!-.--..~ICll=--"1.-- ~

CORE FLOM l1/2I

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-42 Page:

1 of 1 RECIRCULATION FLOW CONTROL FAILURE - INCREASING FLOW, UNIT 2 - CYCLE 1

(., DUKE ENERGY PEAK NEUTRON FLUX,279.4 3/4 I NEUTRON FWX I VESSEL PRES. RISE (PSI) 2 PEAK FUEL CENTER TEMP.

2 STM. LINE PRES. RISE(PSI) 3AVE. SURFACE HEAT FLUIC 3 TURBINE PRES. RISE (PSI) 4FEEOWATER f'LOW 401FFUSER FLOW I PC 1!50.l-----1-++----t--------t5VESSEL STEAM FLOW 160.. 1-----+----+-----1!5DIFFUSER FLOW Z PC 4

4 6 TURBINE STE*M FLOW

~

100.t------+----l+----,,,,.,..F'~-~l---~I--.,........

0

... z ILi u

5 50.1-----t+--~""'=:.....:::-d~--l--f---

lL

8.

12.

16.

TIME ( S_EC.)I LEVEL (INCH-REF-SEP-SKIRT) 2 WR SENSED LEVEL 3NR SENSED LEVEL(INCHES) 150 1----+----t------14 CORE INLET FLOW 120 5 COUPLER POSITION 1PC 5

5 5

4.

8.

12.

18.

TIME (SEC.)

C..,

~

IIC...

0... z..,

~

IL 80 40

~-

0 0.

8.

12.

16, I NEUTRON FLUX TIME (SEC.)

2 SURFACE HEAT FLUX */

)

I u, 2

~

I. *

\\

25.

50

75.

100 CORE FLOW (%)

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-43 Page:

1 of 1 MAXIMUM ROD WORTH VERSUS POWER LEVEL, UNIT 2 - CYCLE 1

(., DUKE ENERGY 0.05

'0.04

~

f 0 o.o?>

3 3

cl 1 0.01

I

~

)C

~

~ 0.01 0

0 0.1.

-~

~

r--....... ~

0..4 0. Co

0. 8 1.0 F'rl.AC:f'lou a/_ 12A'Tk0 Powl!:IL

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-44 Page:

1 of 1 ROD DROP ACCIDENT (POWER RANGE) PEAK FUEL ENTHALPY, UNIT 2 - CYCLE 1

(., DUKE ENERGY 1.'l.O 110

'l.00 1 C,Q 150 110 lbo 150

~ IAO 1 130

)-

(l_

110

..J

-i

'.I 110 r-2 Lil 100

.J Ill

'J qo

~

ii Bo

~

C.

lo bo

'50 Ao

,o

'10 10 0

0 0.0 I X

- --- --------------1.

\\

11 I

FttJAL MAXIMUM h.111-lALP'T' No.

1...ir1'1AL ?owi::rz.

i 3 "lo DF' r2A 'l'U:,

1..

30"lo O( IZATE D

\\

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1~11'1AL I\\AA)(tMUM CE~1'f".1'2.LINE:

frs.1-(HALP'i' 001 a.o~

Ale'.. / C0~1'rt.OL fl.OD D O.L

UPDATED FSAR ACCIDENT ANALYSES CHAPTER 15 FIGURES Revision:

24 Figure:

15-45 Page:

1 of 1 MAIN STEAM LINE BREAK ACCIDENT BREAK LOCATION

(., DUKE ENERGY P.1'2.EAi 12£AC.:fol2 -ful2P.>1AJE: Ol'hVE.U FEED PtJM.D~

_/'f.,"{PA~'l L VALVES 1' t..l 11 P.>IAJ I:

P->'!'PA~S

'$'1'~--ffM C.OAlO.

GEAJEflA-(oQ

ML18249A153

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