Text

FSAR Amendment 107, Figures - Chapters 3, 4, and 5, Part 4 of 4
	ML16180A444
Person / Time
Site:	Comanche Peak
Issue date:	02/01/2016
From:	; Luminant Generation Co
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML16042A346	List: ML16180A424; ML16180A425; ML16180A426; ML16180A427; ML16180A428; ML16180A429; ML16180A430; ML16180A431; ML16180A432; ML16180A435; ML16180A436; ML16180A437; ML16180A438; ML16180A439; ML16180A440; ML16180A441; ML16180A442; ML16180A443; ML16180A444; TXX-1600, Transmittal of Electronic Licensing Basis Documents Including Certified FSAR Amendment 107;
References
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	Download: ML16180A444 (137)
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AMENDMENT 61 DECEMBER 19, 1986 14.38 19.38 24.38 2~U8 33.76 COMANCHE PEAK S. ES.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 FINITE ELEMENT MODEL OF THE FOUNDATION MAT FOR A PORTION OF

_.._T........ H E~D E F - GAS B lllLlllN.G____"_

FIGURE 38.13-1

YG Vxx 0

MXY Mxx NOTES:

VYYJ VYY 00

.....;::~ __

.....,-.,. MYY MYX Mxx vxx 0...

MXY

XP Mxx, MYY, Mxv, THE MOMENT RESULTANTS.ARE OUTPUT AT THE AVAILABLE LOCATIONS ON THE ELEMENTS.

Vxx. VYY ARE ALSO OUTPUT FOR THE TRANSVERSE SHEAR RESULTANT$

0 POSITIVE DIRECTION COMING OUT OF PAPER

@POSITIVE DIRECTION GOING INTO THE PAPER XP, YP -

PLANER COORDINATE SYSTEM XG.YG -

GLOBAL COORDINATE SYSTEM XP IS PARALLEL TO XG YP IS PARALLEL TO YG AMENDMENT 61 DECEMBER 19, 1986 COMANCHE PEAK S. E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 POSITIVE SIGN CONVENTION FOR RESULTS OF PLATE BENDING El f:'Ml='NT FIGURE 38.13-2

COMANCHE PEAK S. E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 MODEL - SUSPENDED CEILING FIGURE 38.13-3

r 10.5" t 6s 0

0 cO 7s 0

NOTES:

1. MEMBERS 1 & 6-6" SCH 160 PIPE

2. MEMBERS 2 & 3-8" SCH 160 PIPE

3. MEMBERS 4 & 5-TS 1 O" X 1 O" X 1 /2"

4. MEMBER 7 IS A FICTITIOUS MEMBER FROM THE CENTERLINE TO THE OUTER SURFACE OF THE SUPPORTED PIPE

5. LEGEND:

2 INDICATES JOINT

@ INDICATES MEMBER s INDICATES STRUCTURAL ATTACHMENT POINT 37.5"

/~-,

I Ss}

y y

x4! ~

~

WELD AT JOINT 5s AMENDMENT 61 DECEMBER 19, 1986 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 STRUDL INPUT ASME ANCHOR FIGURE 3B.14-l

GUIDE THIMBLE FUEL RODS 2611-REQ'D AMENDMENT 92 AUGUST 31, 1994 0 o e Q

0 0

616~-7 11.973 FUEL ASS'Y AND CONTROL ROD 0

0 +

--A----A>-F'll-------4 0 G G 00 8.~66 TYP FUEL ASSEMBLY WITHOUT ROD CLUSTER CONTROL COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT Typical Fuel Assembly Cross Section 17X 17 FIGURE 4.2* 1

I 159.8 REF-----

II

'!tool _: 'Joowl "-' --

'>-I...... _:=

'J.J.......

=

.._, 1--o!== '>-I 1-ool -= '>-I.._.

~*-'-JI >

.c:;;1 I 2

&/ / ' -

-<=/ f

<=i I e:-111--'......:=:=~--i t---"==-"'--:-.., -.........................

TOP VIEW 7.162 REF GRID ASSEMBLY AMENDMENT 92 AUGUST 31, 1994 0.875 DIA. REF BOTTOM VIEW COMANCIE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT Typical 17Xl 7 Fuel Assembly Outline FIGURE 4.2-2

6. 3"

( TYP) llP~.o*

(TYP) 7579-59 END PLUG SPRING U02 PELLETS FUEL-CLAD GAP Z I RCA LOY CLAD SPECIFIC DIMENSIONS DEPEND ON DESIGN VARIABLES SUCH AS PRE-PRESSURIZATION. POWER HISTORY. AND DISCHARGE BURHUP AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT Typical Fuel Rod Schematic FIGURE 4.2-3

CPSES/FSAR Figures 4.2-4A,B thru 4.2-7A,B have been deleted I 92 Amendment 92 August 31, 1992

CROM IJ!llVE !100 ASSO&_Y QJIOE TUBE ASSE"8-Y

/

FUEL ASSEMBLY COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Full Length RCC and Drive Rod Assembly With Interfacina Components FIGURE 4.2-8

r 1.1140 MAX.

j__J

\\

"'"" ""\\

160.95 150.40 S PR I HG RETA I HER

~~~-.>-----~~~

j ~-~---'-~

I. 2'> 0 IA

¥-=i!3i

'rt-~--------*-,-*--=-- - =3-t=qp

$4'

- ---~-Ff.

)

I.

19200 l

0.361 DIA AMENDMENT 92 AUGUST 31, 1994

- 0.315 DIA MAX ABSORBER LEHllTH COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT Typical Rod Cluster Control Assembly Outline FIGURE 4.2-9

r loolll-~~~~~~~~~~~~~~~~~~~~151.9 42.00 ABOSRBER MATERIAL 0. 3 81 D I A. N OM.

AMENDMENT 84 FEBRUARY 28, 1992 COMANCHE PEAK S. E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Full Length Absorber Rod All Ag-In-Cd Design FIGURE 4. 2-10

CPSES/FSAR Figure 4.2-11 Has Been Deleted 184 AMENDMENT 84 FEBRUARY 28, 1992

SPRINGS POISOll LEllGIM

f(i=E-=-~~***~

E-W*

lf~--~--~*ti*--

---*-. e===:!n-f;f

~*

-£?-

AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT Typical Burnable Poison Assembly FIGURE 4. 2-12

6.320 SQ r-* 2.970 TYP. --1

[~:::~ypl 1l TYP. I T-w

! f7ID rID 0.381,.

+

0.3r~

+.

0381,.

-~ _

J__

j~

PRIMARY SOUACL BURNABLE ABSORBER SECONDARY SOUR CL

\\!VABA ROD 0.135 88.00 SECONDARY SOURCE ANTIMONY BERYLLIUM

~----B4C ALUMINUM OXIDE ABSORBER J

---p...

6 y Vi5//;,,j

-~

PRIMARY SOURCE CALIFORNIUM 32.50~

i....----- 4.385 7.942 ti>\\

~

THIMBLE PLUG 0424';'

J 151.565.................................................,.. __

,,......................................... ------*--...J

................... ______ 155.950 AMENDMENT 84 FEBRUARY 28, 1992 x

151.565 143.107

- 8A58 Y

X + END PLUG LENG TH c 9.583 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNIT 2 Composite Core Component Rods and Assembly Outline FIGURE 4.2-128

CPSES/FSAR Figures 4.2-13A,B and 4.2-14 have been deleted l 92 Amendment 92 August 31, 1992

SECONDARY SOURCE t

0.381 OIA t

"'150.4

~~

~

-=?J

)

11

~

1..

88.0 SECONDARY SOURCE.1 TH IM8lE PLUG STAINLESS STEEL 0.432 DIA t

AMENDMENT 92 AUGUST 31, 1994 ANTIMONY BERYLLIUM NOTE: ALL DIMENSIONS ARE IN INCHES COMANCHE PEAK S. E.S.

FINAL SAFETY ANALYSIS REPORT Typical Secondary Source Assembly FIGURE 4.2-15

-q

- c:()

-E:(J AMENDMENT 92 AUGUST 31, 1994 13 F::>

L:::>

COMANCHE PEAK S. E.S.

FINAL SAFETY ANALYSIS REPORT Typical Thimble Plug Assembly FIGURE 4.2-16

CPSES/FSAR Figure 4.3-1 has been deleted.

)

!i: -

O'I

(/')

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0....

0

(/',)

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8 12 16 20 211-28 32 36 ltO BURNUP, (GWD/MTU)

AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S. E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Production and Consumption of Higher Isotopes f 'l'u-.f ~ ~ 1 )

FIGURE 4.3-2

1600

~

Q.. -

l~O

z:

0 -

~

Cl::

I-ffi 800

(,,,)

z:

0

(,,,)

z::

0 ex:

~

...J

!JOO ct

(..)

I

-I--ex:

(.)

0 0

NOTE: HOT FULL POWER RODS OUT WITHOUT BURNABLE POISON

~,,,

BURNUP DIFFERENCE 1300 MWD/MTU WITH BURNABLE POISONS 2000 14()00 6000 8000 10000 CORE AVERAGE BURNUP (MWD/MTU)

AMENDMENT 92 AUGUST 31, 1994 1~00 lllOOO COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Boron Concentration va Pint Cycle Bumup With and Wllhout Burnable Absorber Roda (Typical)

FIGURE 4.3-3

181 181 181 181 181 181

~ ~ 181 181 181 l8J D 181 181 181 181 181 181 181 181 l8J 181 181181 24 BP'S

~CORE CENTER 181 181 181 181 D 181 D 181 D 0 181 181 D DD 181 D D 0 D Do 0 oD 9 BP' S CORE CENTER

~

o 181 D 181 0 181OD0181 DODOO 0 D 0 0 0 0 o D o 0 4 SP'S AMENDMENT 92 AUGUST 31, 1994 D 181 D 181 D 181 D 181 D l8J D 181 D l8J D 181 D 181 D 181 D 181 D 1810 12 BP'S 181 0 D 0 181 0 D 181 0 0 0

181 0 181 D 0 0 181 0 0 181 0 0 0 181 8 SP'S

" CORE CENTER f8I 0 0 Do 0 0 181 DD D 181 D DD DD 0 D 0 Do 0 oD 3 BP'S COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Burnable Abaotber Arrangement Within an Aucmbly (Typical)

FIGURE 4.3-4

go*

180° R P N M L K J H G F E D C B A 1

4 4

4 2

3

~4 9

lP ip*

23 23 4

8 4

4 24 12 4S 8

I 8

5 9

12 8

8 8

6 4

4 8

8 8

7 24 8

8 12 8

8 4

8 8

12 12 9

24 8

8 12 8

10 4

4 8

8 8

11 9

12 8

8 8

12 24 12 8

8 4S 13 3

24 4

8 4

14 9

lP lP

23 23 15 4

4 4

NUMBER INDICATES NUMBER or BURNABLE POISON RODS

s* INDICATES SECONDARY SOURCE ROD

p* INDICATES PRIMARY SOURCE ROD

'*' INDICATES DEPLETED PRIMARY SOURCE ROD AMENDMENT 92 AUGUST 31, 1994 9

24 3

12 24 12 9

8 4

4 8

24 8

8 4

8 24 8

4 4

12 9

12 24 24 3

9 944 BP Rods 12.5 w/o B 0 2

3 COMANCHE PEAK S.E.S.

Fr.JAL SAFETY ANALYSIS REPORT Typical Burnable Absorber Loading Pattern FKJURE 4.3-5

G F

E D

c B

A I

~8 0.93 I

9 1

-~

6 EJDDDDDD 0

1

-~

2 EJ6DDDDD 1

....__.._..l.:O EJ6EJDDDD 2 ~l.~a BGBBDD 13 ~l.:,___..12 EJGEJEJ EJD lj. _o...... ~6_EJBBEJEJ 15 o.~2 EJ.84- ~a.GS CALCULATED F:H = 1.40

.....__,,~_,

LJ KEY:

I

'i.

AMENDMENT 92 AUGUST 31, 1994 VALUE REPRESENTS ASSa.tBLY RELATIVE POWER COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Nonnalizcd Power Density Distribution Near BOL, Unrodded Core, HFP, No Xenon (Typical)

FIGURE 4.3-6

G F

E D

c B

A I

-~-

- -~

I 9

1 12 GDDDDDD 0_

1

-~

8 GEJDDDDD II-I.~ GGEJDDDD 12 1

01 G86GDD I

13~1-:i---13 GGBGEJD l4-__

0 8

6_GGGG 8 I ~~~

CALCULATED F:H = 1.36

---~--~~L=..J K~:

VALUE REPRESENTS ASSEMBLY IS 0.80 I

RELATIVE POWER AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Nonnaliud Power Density Dist.

Near BOL, Unroddcd Core, HFP, Equilibrium Xenon (Typical)

FIGURE 4.3-7

G F

E 0.88 I

I D

c B

A KEY:

VALUE REPRESENTS ASSEMBLY RELAT I VE POWER AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Normaliud Power Density Distribution Near BOL, Group D 3S~, HFP, Equilibrium Xenon (Typical)

FIGURE 4.3-1

G F

E 0

c B

A t 8 1.03

---t I

9 1

17 BDDDDDD I

0

'----+----"l.~S B EJDD DD D I

I...__....._'*~' BEJEJDDDD 2

'---ti.~----~ BBEJEJ DD I

3 """---1,.:_,s GBEJEJ EJ D I

~ _

0*-+-~_BEJBEJB I

5 O.~ 666 CALCULATED F:H = 1.30

-+-,____.

KEY:

I VALUE REPRESENTS ASSEMBLY RELATIVE POWER AMENDMENT 92 AUGUST 31. 1994 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Nonnali7.cd Power Density Distribution Near MOL Unrodded Core, HFP, Equilibrium Xenon (Typical)

FIGURE 4.3*9

G F

E D

c B

A i 8 - o.91

. -t I

I 9 __

0 EJDDDDDD 10

.---+---to.~? GEJDDDDD II ~1.:

12 6GEJDDDD 12 "---to.~1-----19 G EJ EJ EJ DD 13 "---4,. :1-----1,q G G 6 EJ EJ D 1 ~ _o-1.:1-s __ GEJEJ 6 EJ 15 0.~6 EJEJEJ ::~~LATED F:H = 1.29 VALUE REPRESENTS ASSEMBLY RELATIVE POWER AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Normalized PoWCt" Demity Distribution Near EOL, Unrodded Core, HFP, Equilibrium Xenon (Typical)

FIGURE 4.3-10

l-0.83 8

I G

F E

D c

B A

- - t 9

1

.~

6 BDDDDDD o_.._o.~s GEJDDDDD I

'~

1 5 c:JEJEJDDDD 2-1.~-

2 BEJEJBDD 3

1 19 GGEJGBD lj......... 0.-~-Gc:JEJEJEJ s

_o*-~_BBB CALCULATED F:H = 1.3~

I t

KEY:

VALUE REPRESENTS ASSEMBLY RB.ATIVE POWER Amendment 95 February 2, 1998 COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS REPORT UNITS 1and2 Nonnalized Power Density Distribution Near EOL, Group D@ 35%, HFP, Equilibrium Xenon (Typical)

FIGURE 4.3-11

1.02 1.02 1.03 1.02 1.05 1.08 1.02 1.06 I. 12 x 1.03 1.08 I. 14 I. 17 I. 16 1.03 I. 10 lX I. 17 I. 18 lX 1.03 1.08 I. 14 I. 14 I. 16 I. 18 1.03 1.08 I. 14 I. 14 I. 16 I. 19 1.03 I, 10 x I. 16 I. J8 x 1.03 1.09 J. 14 I. 14 I. 16 I. 19 1.03 1.09 I. 15 I. 15 I. 16 I. 19 1.04 I. I I x I. 18 I. 18 [X 1.04 1.09 J. 15 I. 18 I. 17 I. 19 1.04 1.08 I. 14 [X I. 18 I. 18 1.04 1.06 I. 10 I. 14 I. 16 lX 1.04 1.05 1.07 1.08 I. 10 I. 12 1.04 1.04 j.04 1.04 1.05 1.05 I. 17 I. 17 I. 17 I. 19 J. 20 [X I. 17 I. 17 I. 20 I. 18 I. 17 I. 17 I. 20 I, 18 I. 19 I. 19 [X 1.20 I. 17 I. 17 I. 19 I. 17 I. 16 I. 16 I. 18 I. 16 I. 16 I. 16 lX I. 16 I. 10 I. 10 J. 12 I, 10 1.05 I.OS I.OS I.OS I. 18 I. 20 lX I. 17 I. 20 I. 16 I. 19

1. 16 lX I. II I. 12 I.OS I. 06 I. 18 I. 19 lX I. 17 I. 15 I. I I I. II 1.09 1.08 1.07 1.06 1.06 1.06 I. 05 AMENDMENT 92 AUGUST 31, 1994 1.061 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical RodwiJc Power Distribution in a Typical AslCltlbly Near &I, HFP, EQ, Xenon, Un.rodded Core FIGURE 4.3-12

0.98 0.98 0.99 0.98 l.00 I. 03 0.99 1.02 I. 07 x 1.00 I. 03 1.09 I. I I 1.09 1.0 I I. 06 x I. I l 1.11 x 1.00 I.Ott 1.08 1.07 I. 08 I. 10 1.00 I. Ott 1.08 1.07 1.08 I. 10 1.0 I 1.06 x 1.09 I. 10 x 1.00 1.04 1.08 1.07 1.08 I. 10 1.00 I. Ott 1.08 1.07 I. 08 I. I 0 1.0 I 1.06 x 1.11 I. II x 1.00 I. 03 1.09 I. II 1.09 I. I I 0.99 I. 02 1.07 x I. I I I. II 0.98 1.00 1.03 I. 07 1.09 x 0.98 0.99 1.00 1.02 1.03 1.06 0.98 0.98 0.98 0.99 1.00 1.0 I 1.08 1.08 l.'08 I. 10 I. 10 x 1.08 1.08 1.10 1.08 1.08 1.08 I. tO 1.08 I. 10 I. 10 x 1.10 1.08 1.08 I. 10 1.08 1.07 1.07 1.09 1.07 1.08 I. 08 x I. 08 I. 014 11. 04 1.06 1.04 1.00 1.00 1.0 I 1.00 1.08 I. 10 x I. 08 I. 11 1.07 I. II 1.08 x I. Ott 1.06 1.00 1.01 1.09 I. II x 1.09 1.07 1.03 I. 03 1.02 1.00 0.98 1.00 0.99 0.98 0.98 AMENDMENT 92 AUGUST 31, 1994 0.981 COMANCHE PEAK S. E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Rodwiae Power Diltribution in a Typical A.11ernbly Near EOL, HFP, Equih'brium Xenon, Unrodded Core FIGURE 4.3-13

a::

I.I.I 3:

0 Q..

2.0

'. 5 8 1.0 N

...J g

0.5 0.0 0

10 30 50 p ::: 1.0 D = 0. I AO :::-8. 8 I 60 70 p = o. s D = 0. I AO = 5. 9 !

80 90 100 PERCENT OF ACTIVE CORE HEIGHT FROM BOTTOM Amendment 95 February 2, 1998 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Axial Power Shapa Occurrin1 at SOL FIGURE *.H*

z.o I. 5 er:

w..J 3:

0

t. 0 0..

0 w..J N -

<I:

t:

er:

0

i::

0.5 0.0 0.0

0. I POWER = 0. S 9

0 55 AO=

-2~.03

0. 2

0. 3 O.t+

0.5 POWER = 0. 5 D = 0.21 AO 8.20 0.6 0.7 0.8 0.9

!.o PERCENT OF ACTIVE CORE HEIGHT FROM BOTTOM AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT Typical Axial Power Shapes Occurring at MOL FIGUAE 4.3-15

'. 5 er::

w

~

c 0...

0 i.o w

N --'

~

c

z:

0.5 0.0 0

10 20 p = 0. :

rD = 0. '32

~o =-2: 7 30 40 50 p = !. 0 D = 0.'0 60 p = 0. ')

D = 0 c AO *=o.S'.:l 70 80 90 100 PERCENT OF ACTIVE CORE HEIGHT FROM BOTTOM AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT Typical Axial Power Shapes Occurring at EOL FIGURE 4. 3 -16

Axial Relative Power I. 5 1.0 0.5 0.0 CORE BO TI OM CORE AVERAGE ADJACENT TO D BANK REMOVED FROM 0 BANK PERIPHERAL LOW POWER ASSEMBLY CORE HEIGHT CORE TOP AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Comp of Anembly Axial Power Diat. with Core Average Axial Diat. D. Bank SLightly Inserted FIGURE 4.3-17

CPSES/FSAR Figures 4.3-18 thru 4.3-23A,B have been deleted I 92 Amendment 92 August 31, 1992

o. 774 0

I. 109 I. 107

-0.2*

I. 202

1. 170

-2. r 0.523 1.217 O" 548 I. 203

4. 6.

1.1

0.759 0.792 4.3 I. 217 I. 224 0.6 I. 255 I. 249

-0. 5 '

I. 229 I. 225

-0. 3

I, 077 1.092 1.4 I. 223 I. 256

2. 7::

I. 22 !

I. 233 1.0' I. 229 I. 189

-3.r I. 217 I. 211

-0.5'[

AMENDMENT 92 AUGUST 31, 1994 I. 229 I. 218

-0 9~

I. 229 I. 220

-0.7%

I. 217 I. 210

-0.6'

...,.___ CALCULATED

...,.___ MEASURED

...,.___ DIFFERENCE PEAKING FACTORS I. 5 1.357 2.07 LOCATED AT M-8 SOUTH COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT Comparison Between Calculated and Measured Relative Fuel Assembly Power Distribution FIGURE 4. 3-24

z:.

-:.:~

oo z: !"-

't,.'.2.

l.U l,f')

x I-'°"

0 0

z 0::

-' 3

z 0

C> <

a:l 0... al N

0 w

c._

LU

<( 0::

0:: 0 w u

> :z

<-~.

cu :::: c*i 0:: 0 II 0

"" 0 u

1..1.. <

Q LU I-

_J u

<( 0 M3MOd 3AllV13~ lVIXV

I" 0

N

(;>

0 8~

I-0 Cl) 0 00 0

1-

<.o ffi LJ..J

r:

w a::

00 in u LI..

0 1-z:

1..1.J Ou

r ffi 0

N 0

a..

627~-77 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Comparison of Calculated and Measured Axial Shape FIGURE 4.3-25

0 0

0 627~-5~

x REACTOR l 0 REACTOR 4-

\\J REACTOR 2

REACTOR 5 x

x

~ x x e REACTOR 3 FQ 3.0 2.5 2.0

ii.

0 x

8

.>P tf*,. x 0 0 oO Q:

0 I. 5 o*

4-5 0 30 20 10 -5 0

5 10 15 20 25 30 INCORE AXIAL OFFSET (3)

COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Measured Values of Fq for Full PowPr Rod Configurations FIGURE 4. 3-26

-1.2 I.I...

0 -

x u

Q..

-1.4 Q)

I-

'1:>

-1.6

-a.

'1:>

I-z:

L.IJ

-1. 8 u

I.I...

I.I..

UJ 0 u

-2.0 Li.J 00:::

I-ct 00:::

-2.2 Ll.J 0..

E LIJ I-Ci::

Ll.J

-2.4 0..

0..

0 Q

-2.6 500 600 700 800 900 1000 1100 1200 EFFECTIVE FUEL TEMPERATURE Teff (°F)

AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT Typical Doppler Temperature Coefficient at BOL and EOL Cycle 1 FIGURE 4. 3-27

0:::

W-l 31:

0 0..

~ -

E

<...)

e::..

0..

<:i..

I-z; L.U

<.J LL LL LJ.J 0

<...)

0:::

L.U 3:

0 0..

...J z:

0 0:::

L.U

...J 0..

0..

0 0

-6

-8

-10

-12

-lij

-16

-18 0

20 40 60 80 100 POWER (PERCENT OF FULL POWER)

COMANCHE PEAK S.E.S.

AMENDMENT 92 AUGUST 31, 1994 FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Doppler-Only Power Coefficient - SOL, EOL FIGURE 4.3-28

0

-500 u

Q..

i..

I-

<.J 1.1.J u..

1.1.J Q

ex 1.1.J

=

0 Q..

>-=

s a::

1.1.J

....J Q..

Q..

0 Q

-1000

-1500 0

20 llO 60 80 IOO POWER {PERCENT OF FULL POWER}

Amendment 95 February 2, 1998 COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS REPORT Typical Doppler-Only Power Defect* BOL EOL FIGURE 4.3-29

"U:'

10 0 -

~

u 0...

~

f-

,0 -

0 Cl..

"° I-z:

U1 u

u_

u_ -10 i.J..J 0 u LU a::

f-

<:( -20 a::

i.J..J a..

2i f-0:::

0 I-

<:( -30 0:::

w a

0

~

-40 0

100 I 000 PPt,1 1500 "\\

0 PPM

~

300 400 500 600 MODERATOR TEMPERATURE (°F)

AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S.

FINAL SAFETY ANAL YSlS REPORT UNITS 1 and 2 Moderator Temperature Coefficient

- BOL, No Rodi (Typic.al)

FIGURE 4.3-30

20 10 LL 0

0 -

~

u Cl..

f-

.0 -

-10 Q_

)

I-z:

w u

LL

-20 u..

w 0 u w

er:

I-

<(

0:::

-30 l.J.J Cl..

~

f-0:::

0 I-

<t 0:::

-40 w

0

~

-50 0

100 500 PPM 0 PPM 200 300 4oo 500 600 MODERATOR TEMPERATU~E (°F)

AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Moderator Temperature Coefficient, EOL FIGURE 4.3-31

I.I..

0 -0 a..

t:

I-Kl -

a_

Kl I-

z::

1.1.J

(,..)

I.I..

UJ 0

(,..)

1.1.J 0::

I-

<C 0::

w a..

~

1.1.J I-0::

0 I-

<C 0::

1.1.J c

0

£ 5

0

-5

-10

-15

-20

-25

-30 0

500 1000 SOLUBLE BOROH CONCENTRATIONS (PPM)

AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Moderator Temperature Coefficient u a Function of Boron Concentration

- BOL, No Rods (Typical)

FIGURE 4.3-32 1500

u..

O -0 0...

E I-

<O -

(I..

.Q I-LU u

I.I..

u..

I.I.I 0 u w

c:::

)

I-c:::

l.IJ 0...

CJ I-co::

0 I-ct er::

w Q

~

0

-5

-10

-15

-20

-25

-ll

-35 0

500 BURNUP (MWO/MTU)

Amendment 95 February 2, 1998 1000 1500 COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS REPORT UNITS 1 and2 HFP Temperature Coefficient for the Critical Boron Concentration (Typical)

FIGURE 4.3-33

0:::

w 3:

0 0..

z:

w u

0:::

w 0.. -

E:

u c..

a..

.0 -

c...

.c

z:

w u

u...

w_

w 0 u 0:::

i.:....

3:

0 a..

-1

<(

f-0 f-

-10

-!2 -16

-18

-20

-2?.

0 rEOL 20 40 60 80 100 POWER LEVEL (~ OF FULL POWER)

COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typacal To<a.I ~

Coefficient

BOL.EOL FIGUAE 4.J-34 Amendment 96 August 2, 1999

0 500 1000

=<::

u c..

CL I-

<.,)

w LL.

WJ 1500 0

~

w 3:

0 c..

_J

<t I-0 I-2000 2500 0

20 4-0 60 80 POWER LEVEL {PERCENT FULL POWER)

AMENDMENT 92 AUGUST 31, 1994 100 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Total Power Defect -

BOL,EOL FIGURE 4.3-3!!

12288 ~ &

EJ r:-,

IS'-

~"'

r.,

1S ol IS CI L-J

'o/

,s/

L-.J

t1l, ro'I

~

'a'

~

\\. )

\\. J r:-1 I C I ISD I L-.J L-.J

£ 0

'fl 0

~

s~

:I

~9 0

~ 'fl (o)

\\fl

~ 0 Vs

"'o/

~

£ 0

\\fl 0

£ rs 1 r:-,

I DI IS CI L-J L--.J

~ 0

~

Co)

~

r.,

~'\\,

IS '\\.

r:,

IS CI 1S DI L-.J

,s/

~ ~ @

£

~

SHUTDOWN BANK SA 8

SHUTDOWN BANK Ss 8

SHUTDOWN BANK

& So 4 & 4 SHUTDOWN BANK SE 1i CONTROL BANK A

lj.

CONTROL BANK B

8 CONTROL BANK c

8 CONTROL BANK D

COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Rod Cluster Control Assembly Pattern FIGURE

£1.3-36 0

c..

(/) -

E c..

c 30 IX i Q

0 IX

<C 20 I-z:

1.1..1 IX 1.1..1 Q

10 0

50 100 150 STEPS WITHDRAWN Amendment 95 February 2, 1998 200 250 COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS REPORT Accidental Simultaneous Wlthdrawel of 2 Control Banks EOL. HZP Banks C and B Moving in Same Plane (Typical)

FIGURE 4.3-37

1.0 0.9 0.8 I-0 Q..

c

(/)

..<(

0.7 0

u..

0 Q..

0.6

~

w

<..)

0.5

~

t;;

0 - o."

0 w Q..

0..

~

Cl 0.3 w

<..)

~

I-(/)

0.2 Ci 0.1 0.0 I

f IHORMALI ZED SCRAM TIME 0.0 0.1 0.2 0.3 O."

0.5 0.6 0.7 0.8 0.9 1.0 I.I 1.2 1.3 I."

1.5 1.6 1.7 TIME AFTER DROP BEGIMS/DROP TIME TO TOP OF OASHPOT AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S. E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Trip Curve FIGURE 4.3-38

}_

~ 0.5 o.o L ______

_c:=::::::::====~

100 50 0

ROD POSITION (PERCENT INSERTED)

AMENDMENT 92 AUGUST 31, 1994 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Normalized Rod Worth Vs Percent Insertion

All Rods But One (Typical:

FIGURE 4.3-39

5 0

t-

-5

z UJ

(..)

0::

w

~ -10

~

(/)

It -15 0

...J

..:r x -20

-25

-30 0

ll 8

CURVE I

2 12 16 BURN UP (MWO/MTU) 1550 7700 20 21l PERIOD (HOURS) 32.lt 27.2 28 STABILITY IHOEX (HOURS-I)

-0.01' I

-0.014 32 36 llO Tl ME (HOURS)

IJ4 ll8 52 56 Amendment 95 February 2, 1998 60 611 68 72 COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS REPORT UNITS 1and2 Axlal Offset Vs. Time PWR Core wllh a 12-Ft Height and 121 Assemblies FIGURE 4.3-40

l.~

t z

C(

a::

0 <(

c-l N

1-:i 10 8

6 11 2

0 a::

0 C( g. - 2

~ - q z:

UJ 0:: If - 6 u..

0 1-

.....1 I-I-

z:

<(

IX Cl

""' g.

- 8

-10

-12

- Ill

-16 0

\\

\\ * **

\\

STABILITY INDEX= -0.076 (HR. - I) q 6

12

_..... ~.....

\\ii e"lr

-w.,,,,t>~

H42 0

4 RCC E-11 2

N43 N41 16 20 2\\l 28 32 36 ltO lilt 148 52 56 60 611 HOURS AFTER WITHDRAWAL Of RCC E-11 Amendment 95 February 2, 1998 COMANCHE PEAK S.E.S FINAL SAFElY ANAi. YSIS REPORT UNITS 1and2 XV Xenon Tesl Thermocouple Response Quadrant TKI Olfference Vt.. Time FIGURE 4 3-41

CPSES/FSAR Figures 4.3-42 thru 4.3-45 have been deleted 192 February 2. 1998

CPSES/FSAR Figures 4.4-1 thru 4.4-19 have been deleted I 92 Amendment 92 August 31, 1992

1.096 1.001 1.029 1.120 1.001 1.001 1.153 1.074 1.185 1.000 1.001 1.000 1.166 1.209 1.162 1.185 1.000 1.000 1.001 1.000 1.223 1.170 1.188 1.065 1.000 1.001 1.000 1.002 1.126 1.161 1.093 1.086 1.001 1.001 1.002 1.002 1.025 1.025 0.990 0.975 1.002 1.002 1.002 1.002 0.717 0.780 0.664 0.563 0.999 0.999 0.998 0.997 Key:

.6.h/.6.h GIG 1.238 1.000 0.916 0.967 1.001 1.001 0.823 0.466 1.000 0.997 For Radial Power Distribution Near Beginning of Life, Hot Full Power, Equilibrium Xenon Calculated F N = 1.34

.6.H COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Normalized Radial Flow and Enthalpy Distribution at 4-Ft Elevation Typical of Cycle Figure 4.4-2 Amendment No. 103 1

1.096 0.996 1.026 1.120 1.002 0.994 1.155 1.072 1.188 0.991 0.998 0.988 1.169 1.212 1.165 1.189 0.990 0.986 0.990 0.998 1.228 1.173 1.191 1.065 0.985 0.989 0.988 0.998 1.129 1.165 1.095 1.086 0.992 0.990 0.995 0.996 1.024 1.025 0.989 0.973 1.000 1.000 1.003 1.004 0.715 0.777 0.663 0.562 1.022 1.019 1.021 1.019 Key:

Ah/Ah GIG 1.242 0.981 0.916 0.963 1.009 1.006 0.819 0.468 1.018 1.018 For Radial Power Distribution Near Beginning of Life, Hot Full Power, Equilibrium Xenon Calculated F N - 1.34

.AH COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS UNITS 1 and 2 Normalized Radial Flow and Enthalpy Distribution at REPORT 8-Ft Elevation Typical of Cycle 1 Figure 4.4-3 Amendment No. 103

1.097 0.995 1.026 1.121 0.999 0.993 1.157 1.073 1.189 0.991 0.996 0.989 1.170 1.215 1.166 1.190 0.990 0.980 0.991 0.990 1.231 1.175 1.193 1.066 0.987 0.990 0.989 0.997 1.130 1.165 1.095 1.087 0.993 0.991 0.995 0.996 1.023 1.024 0.987 0.971 1.000 1.000 1.002 1.003 0.711 0.774 0.660 0.560 1.016 1.013 1.019 1.025 1.243 0.987 0.914 0.961 1.005 1.003 0.817 0.469 1.011 1.030 For Radial Power Distribution Near Beginning of Life, Hot Full Power, Equilibrium Xenon Calculated F N - 1.34

.6,H COMANCHE PEAK S.E.S Key:

.6.h/.6.h GIG FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Normalized Radial Flow and Enthalpy Distribution at 12-Ft Elevation Typical of Cycle 1 Figure 4.4-4 Amendment No. 103

CPSES/FSAR Figures 4.4-1 thru 4.4-19 have been deleted I 92 Amendment 92 August 31, 1992

0 T 0

TO T 0 T 0 T T

T JfilTD 0

0 0

0 T

T 0 T T

T I

0 0

TD TO T

0 T 0 T T

T 0 T 0

0 0

u TO TO TO TO T

0 T 0 TO 0 T 0

0 0

D T

T TD TD T

T 0 T T

D 0

D D

D T

T D T TD T

D T L D D

D D

TO T

TD T

D T D T D

TD T - THERMOCOUPLE (50) 0 - MOVABLE INCORE DETECTOR (58 LOCATIONS)

AMENDMENT 84 FEBRUARY 28, 1992 COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Distribution of Incore Instrumentation FIGURE 4.4-20

630 620 610 r<

600

µ.i

r:

~

r:

590

µ...

VJ

µ.i

~ 580 0

µ.i Ci

~ 570

~

r<

~

µ.i i::i...

s 560

µ.i r<

557 550 540 530 0

20 fsOOOO I 0. dgn T HOT T AVG T COLD 40 60 80 PERCENT POWER Amendment 102 620.1 589.2 558.3 100 COMANCHE PEAKS E S FINAL SAFETY ANALYSIS REPORT UNIT 1 REACTOR COOLANT SYSTEM TEMPERATURE PERCENT POWER MAP FIGURE 4.4-21A

620 610 600 r<

µ.i

r:

590 ffi

~

r:

580

µ...

VJ

µ.i

~

0

µ.i 570 Ci

~

r<

560

~

µ.i 557 i::i...

s

µ.i 550 r<

540 530 0

20 fsOOOOOz.dgn T HOT T AVG T COLD 40 60 PERCENT POWER Amendment 102 618.8 80 589.2 559.6 100 COMANCHE PEAKS E S FINAL SAFETY ANALYSIS REPORT UNIT2 REACTOR COOLANT SYSTEM TEMPERATURE PERCENT POWER MAP FIGURE 4.4-21B

I CPE r

¥

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6 mel04170.dgn Ml-0250

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F0*-100!!-001~~8 0 l "£11 S*-0020-08-00195!-0?-0l.

2. 3r INSIDE DIAMETER. (BY WESTINGHOLJSEI

3. 27.5'1NSIDEDIAMETER.<BY WESTINGHOUSEl

5. ELBOW FLOW METUlS INSTALLATION SEE RH G ON ORAil'ING t.'1-0200.

6. vrnT PIPE FUR~ I SHEO WI TH REACTOR VESSEL HEAD.

9.CONNECTION LOCATEOINBOTTOMHALFOFREAC TORCOOLANT PIPINGON 45°ANGLETOVERTICAL.

II. 6t'Al~l:GL OM~-~i6J.R~~r l ~l~ OV IOED. (SEE MECHANI CAL SrnBOLS ANO NOTES 12.STRAP-ON!SURFACEMOUNTEDlRTDLOCATEDATBOTTOl.'OFPIP[.

14.A FLOWRESTRICTINGSCOOPWITHABORE OF0.234' WILLBESUPPLIED BYVENOORWI THTHE LOOP1AN04HOTLEGS.

15.1*i1~1CATES HER~ETICA L LT SE ALED VALVE.

20. LOCATE CONM:CTION ON UPPER 90° Of PIPE CIRCUl.IHRENCL

24. DELETEO 25.DELE TED

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THISFLOW OIACRAMHASBEENREDRAWN FROMWESTINCHOUSED!lAWING fl.IJM&R 1138[ 92 SH IOF 2. REV 6 WITH EXCEPTIONS AS FOLLOWS:

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13.DIGITALPRESSURIZERINOICATORLOCATEOONTHISLINEDOWNSTREAM OF SAMPLE HEU EXCHANGER.
15. 1>t:i INDICATES HERMETICALLY SEALED VALVE.
16.SEEREfERENCE"G"ONMECHAN1 CALSH'BOlS AND NOTESDflAWINGNO.
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17.ALLQLllCKCONNECTCOUPLINGSSHALLBESWAGELOl\\SS-QC4-S- 400ANO SS-QC4-3-400FURN1Sf!EDWI THSAMF'LEVESSEL.
15.NITROGENSUPPLYREQU1 REDFORCOLOOVERPRESSURE PROTECTION.
20.FLANCESUSEO IN THEINSTRUMENTCONNECTIONSFORHT-0470..t.RERATEO AT ISO LBS.
23. 0.83 INCH l.D. n ow RESTRICTORS IN PRESSURIZER STEAi.. SPACE LEVEL INSTRUMENT NOZZLES PROVIDE THE CLASS-I TO CLASS-2 TRANSITION.
l-TE-3650E-I 1-TE-3650E-2 1-TE-3650£- 3 1-TE-3650E-4 26.TOf"ACILITATE PIPESU'PORTllESICN, PIPE ISUPCRAOEOTOSCHEOL.l.E160S.
27.TO FACILITATE PIPESUPPORTDESIGN. PIPEIS UPGRAOEOTOSCHEOL.l.ESOS.
28. :~~~:~t;~L~LE~ :E~~tE~O~~s~n~~1~~~1'~~~ ~801~3~p~~R1~C~!~~~c HA VE 29.THESTRAP-ONRTD"S IDENTIFIEDI NTHEFOLLOWINGT ABLEHAVE BEEN ABANDONED IN PLACE.
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30. THE FOLL OW1NCLANYARO POTENTIOMETERSIREFDCN002381ARE ABANDONED IN PLACE;
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STEAM GENERATOR iTUM CE.NEIU. TOR LOOP 3 LOOP 2 Amendment 67 February 5, 1988 COMAN!)£ PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 ANJ 2 PROCESS FLOW DIAGRAM REACT~ COO.ANT SYSTEM
~roufll[ !l.l-2
CPSES/FSAR NOTES TO FIGURE 5.1-2 RCS AT STEADY STATE FULL POWER OPERATION ITEM FLUID PRESSURE TEMP FL ow a VOLUME
{Qsig)
{OF}
(91~m) b
{lb/hr}C
{cu.ft.}
1 RC 2235.0 618.8 110, 250
36. 7125 68 2
RC 2233.1 618.8 110,250 36.7125 68 3
RC 2195.9 559.3 99,839 36.7125 68 4
RC 2192.4 559.3 99,839 36.7125 68 5
RC 2285.1 559.6 98,900
36. 7125 68 6
RC 2283.2 559.6 98,900 36.7125 68 7-12 See Loop 1 Specifications (1-6) 68 13-18 See Loop 1 Specifications (1-6) 68 19-24 See Loop 1 Specifications (1-6) 68 25 RC 2285.1 559.6 1.0 0.0004 68 26 RC 2285.1 559.6 1.0 0.0004 68 27 RC 2235.0 559.6 2.0 0.0008 68 28 Steam 2235.0 652.7 720 68 29 RC 2235.0 652.7 1080 68 30 RC 2235.0 652.7 2.5 0.0008 68 31 RC 2235.0 652.7 0
0 68 32 Steam 2235.0 652.7 0
0 68 33 RC 2235.0
<652.7 0
0 Minimize 68 34 Nitrogen 3.0 120 0
0 68 35 RC 2235.0
<652.7 0
0 Minimize 68 36 Nitrogen 3.0 120 0
0 68 37 Nitrogen 3.0 120 0
0 68 38 Nitrogen 3.0 120 456 68 39 PRT Water 3.0 120 1350 68 a)
Flow measured at 1300F and 2300 psig; charging and letdown not 68 included b)
At the conditions c )
x 106 speci f ied 68 68 Amendment 68 February 15, 1988
l*
MISSILE SHiELD UNIT20NLY JI
'SECTION LOOKING NORTH
~~~
SECTION LOOKING EA§T Cll>Q-1rtOOi-CATl"'4
~f.'l~l(.'lo ~OOM
..... r..:101~1
~~~
COMANCHE PEAK S.E.S.
NUCUAR PLANT UNn'S hnd2 REAc:1at OOG&.MT SYSTEM~
Figure 5.1-3
THIS FIGURE HAS BEEN DELETED.
COMANCHE PEAKS.ES FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Vessel lnservice Inspection Tool Figure 5.2-1
Amendment 102 COMANCHE PEAK S. E.S.
FNAL SAFETY ANALYSIS REPORT Amendment 102 UNIT 1
~CS Heatup Limitations I
Fi~ure 5.2-2 Sht. 1 Amendment 101 b
Amendment 102 COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT Amendment 102 UNIT 2 RCS Heatup Limitations Figure 5.2-2. Sht. 2 Amendment 102
THIS FIGURE HAS BEEN DELETED.
COMANCHE PEAK S.E.S.
Amendment 102 FNAL SAFETY ANALYSIS REPORT UNIT 1 RCS Cooldown Limitations I
Figure 5.2-3.
Sht. 1 Amendment 102
Amendment 102 COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNIT 2 RCS Cooldown Limitations Figure 5.2-3. Sht. 2 Amendment 101 b
...J
...J LlJ
c Cl)
LlJ I-0 Ll.J
E Ci::
LlJ I-z:
CORE
...J
...J LIJ
c Cl)
Ci::
LIJ
~
...J IOl-121lA 101-171 RI 107-1 oo I Ol -ll~2C AMENDMENT 8 NOVEMBER 30, 1979 15, 092-1 90° Rll0?-3 180° 270° IOl-142A RI I 08-1 180° 101-14-28 270° COMANCHE PEAK S.E.S.
FNAL SAFETY ANALYSIS REPORT UNITS 1 and 1.
Unit No. 1 Reactor Vessel Beltline Region Material Identification FIGURE 5.3-1A
.....I
.....I LLJ
c Cl)
LU
-=r:
0 LLJ
£ 0::
LU z:
CORE
.....I
.....I LU
c Cl) 0::
LLJ
~
.....I 101-171 101-121u R3816-l oo 101-14-2C AMENDMENT 8 NOVEMBER 30, 1979 15,092-2 goo R3807-I 180° 210° IOl-14-2A R3816-3 180° I Ol -I lt2B 270° COMANCHE PEAK S.E.S.
FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Unit No. 2 Reactor Vessel Beltline Region Material Identification FIGURE 5.3-1 B
CCI _,
LL.
C!J a:
w z
w 180 160 140 120 100 80 60 40 20 0
200 INTER & LOWER SHELL LONG. & GIRTH SEAM
-100 0
TEMPERATURE (°F)
TNDT =. 70oF RT NOT = *70°F 100 200 COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Comanche Peak Unit l Beltllne Region Weld Metal Charpy V-Notch Impact Data Weld Code No. Gl.67 FIGURE 5.3-2A Amendment 91 April 15, 1994
)> )>
~3
=: <D
..... :s co Q.
3
..... <D co :s co -
~ co I
I "TI i5 c
0 m
'f o:l I
I
~I
wn z-o 0 §' g r; "
r n
3!~
"O _. '"ti
"' 0 il" ~
~~ c:::
i;:1.d*
[
n !
200 180 r 160 ~
1 t m
120
~
u..
100 C1 cc w z so r w
I 11 -1 z
)> n ro
=t 20 Cf) $:
c ~ )>
zmZ
-I n
-I - m
...... z Q)
)> -u
J ~ m 0.. Cf) )>
N Cf) A
a Cf) m *
-u ~
0 Cf)
a.
-I 200 INTER TO LOWER SHELL GRITH SEAM 180 I INTER Iii LOWER SHELL ONG.
0 WELD CODE NO. E3.10 SEAMS WE LO CODE NO. G3.03 160 TNoT* 40of 140 ~
TNDT * -50of RTNor*400F RT NOT.. -50of 120 2
0 n/ I 100
/
I 80 I
60 40 20 I 0
I 0
100 0
100 200
100 0
100 200 TEMPERATURE (°F)
TEMPERATURE (°F)
m
..J LL ->
(!)
a:
w z w
m
..J LI..
(!)
a:
w z w
100 TNDT *.2Qof 0
RTNor* 100F 0
80 60 40 INT. SHELL RATE 20 R-1107*1 0 '--~~....1-~~-i..~~~....___.
-100 0
100 200 100 80 60 40 20 TEMPERATURE (°F)
TNoT* *200F RTNOT* 1D°F INT. SHELL RATE R-1107-3 0 i.--~~-'-~~....i..~~-----'
-100 0
100 200 TEMPERATURE (°F) m
..J u..
(!)
a:
w z w
100 TNoT* *20oF RTNDT'" -10°F 80 60 40 INT. SHELL RATE 20 R-1107-2 0 '----.l.---.J...---'----'
-100 0
100 200 TEMPERATURE (°F)
COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Comanche Peale Unit l Cho.rpy V *Notch Impact Dato. for IntennediateShell Plates R-1107-1. Rl107-2 and R* 1107-3, Transverse Orientation FIGURE 5.3-3A Amendment 91 April 19, 1994
a; r!.
LI.
<.:> a:
w z w
a; r!.
LI.
<.:> a:
w z
w 120 ------------,
0 100 80 60 40 20 0
-100 100 80 60 40 20 0
-100 TNoT**200F RT NOT** 20oF INT. SHELL R-3807-1 0
0 100 200 TEMPERATURE (°F)
TNoT* *20oF RTNoT*.200F 2
0 INT. SHELL R-3807*3 0
100 200 TEMPERATURE (°F) a; r!.
LI.
<.:> a:
w z
w 120 100 80 60 40 20 0
100 TNoT*.zooF RT NOT* 10°F 0
100 0
INT. SHELL R*3807*2 200 TEMPERATURE (°F)
COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Comanche Peak Unit 2 Charpy V-Notchlmpact Data for IntennediateShell Pla!a R-3807-1, R3807-2 and R-3807-3 Transverse Orientation FIGURE s.3-:rn Amendment 91 April 15, 1994
100 TNor* -200F RTNor*OOF 80
§...
m
..J
~ 60 u..
C1 a:
w 40 z
w 20 LOWER SHELL R-1108-1 0
-100 0
100 200 TEMPERATURE (°F) 100 TNDT *.30of 0
RT NOT *OoF ~
80 ii
..J
~ 60 u.. ->
C1 a:
40 w z w
20 LOWER SHELL R-1108*3 8
0
-100 0
100 200 TEMPERATURE (°F}
100 80 m
..J
~ 60 u..
C1 a:
w 40 z
w 20 0
-100 TNor**300F RTNor*20°F LOWER SHELL R-1108*2 0
100 200 TEMPERATURE (°F)
COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Comanche Peak Unit 1 Charpy V-Notch Impact Data for Lower Shell Plates R-1108-1,R*ll08-2and R-1108-3, Transverse Orientation FIGURE 5.3-4A Amendment 91 April 19, 1994
as-
....I
(!)
a:
w z w
(!)
a:
w z w
120 100 80 60 40 20 0
100 100 80 60 40 20 0
-100 TNOT =.300F RT NOT=.300F LOWER SHELL R-3816-1 0
0 100 200 TEMPERATURE (°F)
TNor= -400F RT Nor= 40°F 0
LOWER SHELL R*3816*3 100 200 TEMPERATURE (°F) 120 100 80 as-
....I
!:::. 60
(!)
a:
w z 40 LU 20 0
-100 TNDT
30°F RTNDT = +/-OoF LOWER SHELL R-3816-2 0
100 200 TEMPERATURE (°F)
COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Cott1rulche Peak Unit 2 Charpy V-Notch Impact Data for Lower Shell Plates R-3816-1. R-3816-2 and R-3816-3 TrllllSver11e Orientaion FIGURE 5.3-4B Amendment 91 April 15, 1994
FLYWHEEL UPPER RADIAL BEARING THRUST BEARING MOTOR SHAFT MOTOR STATOR MAIN LEAD CONDUIT BOX LOWER RADIAL BEARING NO.
3 SEAL LEAK OFF NO 2 SEAL LEAK OFF PUMP SHAFT COOL I NG WATER INLET DISCHARGE NOZZLE WE IR SUCTION NOZZLE
......,,.-M~~-- THRUST BEAR I NG OIL LIFT PUMP
+ MOTOR

MOTOR UNIT ASSEMBLY SEAL HOUSING NO.

I SEAL LEAK OFF
,11------- COOLING WATER OUTLET
...-~.......+--+-------RADIAL BEARING ASSEMBLY
~......_."'"*-+--1-------'fH ERMA L BARR i ER AND HEAT EXCHANGER

IMPELLER COMANCHE PEAK S. E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Reactor Coolant Controlled Leakage Pump FIGURE 5.4-l
600 500 r--
t:::l 4-00 LL C>
<(
w
c 300
_J
<(
t-o r--
200 100 0
/
TOTAL HEAD
/
/
I I
I REQUIRED NET PO~IT!VE SL1CTION HEAD 4026-183 0
I 0 20 30 4-0 50 60 70 80 90 I 00 I I 0 FLOW - THOUSANDS OF GPM COMANCHE PEAK S. E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Reactor Coolant Pump Estimated
,__,_E:.e.rfonnance Character1st1c FIGURE
5. 4-2
z: -
I -(I')
(I')
(I')
LiJ
z:
I:
0 f-tJ..J a::
f-
<t a::
l.J_
2?
220 200 180 160 14-0 120 100 80 60 4-0 20 0
-200 6798-2 0
BTCT I
0 2TCT 9
6 4TCT I
0 I I
I I
I
~
I o I 8
I I
I 6
~ /
I I
I 6
01 I 0 ~
~
f1//
/
o 0."o 0
_.e,.
LOWER BOUND Kid
-150
-100
-50 0
50 100 150 200 REFERENCE TEMPERATURE (T-NDTr)-°F COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Krd Lower Bound Fracture Tough-ness SA-533, Grade B, Class l lB:~Jerence_Llll_ ___ _
FIGURE 5.4-3
AUX. FEEDWA!ER NOZhE _/
u FOUR ( 4) NARROW WATER LEVEi.
TAPS QOWNCOMER ANNULUS__.-
WlOE RANGE SECONDAR'i* l'HELL DRAIN CHANNEL HEADJ PRIMARY MMJVJAV _ __,,
rwo JYPICAL Amendment 102 OUTLET NOZZLE WITH SEVEN (7) FLOW VC::NTU,RI
,.,.--SECONDARY SEPARATOR 1"41">.---**-*SECONDARY SIDE MANWA'!
TWO (2) TY?ICAL PR MARY SEPARATOR NORMAL Oi"ERATING WATER LEVEL (APPROX.)
~FEEDWATER DISTRIBUTING RING 4.00 INSPECTION PORT TWO ( 2) TYP !CAL
--TUBE SUPPORT PLATE TEN (10) TYPICAi SAMPLf. 'IAP CHANNEL HEAD DIV10ER PLATE PRIMARY NOZZLE CLOSURE RING TWO (2) TYPICAL
PRIMARY NOZZLE TWO (2) TY0 !CAL i
COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 1 LONGITUDINAL SECTION OF FEEDRING STEAM GENERATOR FIGURE 5.4-4A
Tube Supports~
Amendment 102 Steam Separators Le~el of Auxiliary Feedwater Nozzle Tube Bundle Preheater Outlet
,,---- Feedwater Nozzle
/
16" Sch. 80 Preheater Section COMANCHE PEAK S E S Fl NAL SAFETY ANALYSIS REPORT UNIT 2 LONGITUDINAL SECTION OF PREHEAT STEAM GENERATOR Fl GURE 5.4-48
If, t 90-96 A
A SECTION A-A COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Steam Line Flow Restrictor FIGURE 5.4-5
Ml-0260 Ml-0260 CLASS I LUMINANT CPNPP GLEN ROSE, TEXAS FLOW DIAGRAM RESIDUAL HEAT REMOVAL SYSTEM
< FINAL PRINT >
CP-37
~
~ 8
µ.,
~
r:ll
µ.,
I CLASS I LUMINANT CPNPP GLEN ROSE, TEXAS M2-0260 M2-0260
< FINAL PRINT >
CP-21
\\0
~
µ.,
~
µ.,
l
]' t
~----
---1--1-~
Ill:
j 0AC
-~ ~ I i..
~,.,___.___~
I'.
fis-i:iioLTc - - - ~ I t---J-------1
~--~I c~_:_:_J--~::i--n
~_'_"'-oc<G --1~ @
"'---':OCF '. *-
I I
I
______J II (6?i
~
(65
<=CXLOLiG-- -~
1
~~-*-~ - *.~ J I __ _._ _ __.
/Cv"'°'-o;o~
~~-
31 IAC I QA(
e~~-*~~,N~- 1-..t_ ___ _,
NOTE:
1.
THIS DIAGRAM IS A SIMPLIFICATION OF THE SYSTEM INTENDED TO FACILITATE THE UNDER-STANDING OF THE PROCESS.
FOR DETAILS OF THE PIPING, VALVES, INSTRUMENTATION, ETC.
REFER TO THE ENGINEERING FLOW DIAGRAM.
REFER TO PROCESS FLOW DIAGRAM TABLES FOR THE CONDITIONS AT EACH POINT.
51 GIRJ!HG Jll\\W I
C>i-'f:G I NG P\\W' 4 LDC f-:5
~SISNKXI 5M I
1
(
SIS SI 'UirSSH l
~
29 AMENDMENT 17 APRIL 7, 1981 COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Residual Heat Removal System Process Flow Diagram FIGURE 5.4-7, Sheet 2
MODES OF OPERATION NOTES TO FIGURE 5.4-7 (Sheet 1 of 4)
Mode A - Initiation of RHR Operation When the reactor coolant temperature and pressure are reduced to RHRS operational conditions. approximately 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after reactor shutdown, the second phase of plant cooldown starts with the RHRS being placed in operation. Before starting the pumps. Component Cooling Water is established through the heat exchanger.
Upon initial startup of the RHR pump. the miniflow valves automatically position open to protect the pump and RHR boration requirements are established. Once boration is completed. power is restored and the RHR to Hot Leg Recirculation Isolation Valves are opened.
Startup of the RHRS includes a warm-up period during which time reactor coolant flow through the heat exchangers is limited to minimize thermal shock on the RCS.
I 0212.63 96 The rate of heat removal from the reactor coolant is controlled manually. not to 96 exceed 100°F per hour.
Cooldown rate is based on equipment stress and a maximum Component Cooling water temperature of 122°F through the RHR heat exchanger. A constant flow is regulated automatically by control valves in the heat exchanger bypass line.
Mode B - End Conditions of a Normal Cooldown This situation characterizes most of the RHRS operation.
As the reactor coolant temperature decreases. the flow through the residual heat exchanger is increased until all of the flow is directed through the heat exchanger to obtain maximum cooling.
Note:
For the safeguards functions performed by the RHRS refer to Section 6.3.
Amendment 96 August 2. 1999
VALVE ALIGNMENT CHART 2
3 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 26 0 = Open.
C Closed.
P =Partially Open.
NOTES TO FIGURE 5.4-7 (Sheet 2 of 4)
Operational Mode A
B c
c c
c 0
0 0
0 c
c c
c c
c c
c p
c p
c p
p p
p c
c c
c 0
0 0
0 0
0 0
0 February 15, 1988
93 18 93 NOTES TO FIGURE 5.4-7 (Sheet 3 of 4)
MODE A - INITIATION OF RHR OPERATION Pressure Temperature Location Fluid (Qsig}
(OF}
Reactor 24 Coolant 400 350 25 II 407 350 26 542 350 27 541 350 31 II 539 142 29 II 496 350 32 ti 496 296 28 II 480 296 19 Loop 4 404 296 19 Loop 3 II 419 296 34 II 400 350 35 407 350 36 542 350 37 II 541 350 41 539 142 39 II 496 350 42 II 496 296 38 479 296 20 Loop 1 II 404 296 20 Loop 2 II 404 296 a At reference conditions 350°F and 400 psig.
Flow (ggm}a (lbLhr) 3800 1.69 x 106 3800 1.69 x 106 3800 1.69 x 106 992 0.44 x 106 992 0.44 x 106 2808 1.25 x 106 3800 1.69 x 106 3690 1.64 x 106 1992 0.885 x 106 1698 0.755 x 106 3800 1.69 x 106 3800 1.69 x 106 3800 1.69 x 106 992 0.44 x 106 992 0.44 x 106 2808 1.25 x 106 3800 1.69 x 106 3910 1.74 x 106 1955 0.87 x 106 1955 0.87 x 106 Amendment 93 February 1, 1995
NOTES TO FIGURE 5.4-7 (Sheet 4 of 4)
MODE B - END CONDITIONS OF A NORMAL COOLDOWN Pressure Temperature Location Fluid (psig)
(OF)
Reactor 24 Coolant 0
140 25 It 7
140 26 II 156 140 27 149 140 31 129 120 29 It 93 120 18 32 93 120 28 75 120 19 2
120 18 34 0
140 35 7
140 36 II 156 140 37 II 149 140 93 41 II 129 122 39 93 122 42 93 122 38 75 122 20 2
122 a At reference conditions 140°F and 0 psig.
Flow (gpm)a (lb/hr) 3800 1.87 x 106 3800 1.87 x 106 3800 1.87 x 106 3800 1.87 x 106 3800 1.87 x 106 0
0 3800 1.87 x 106 3800 1.87 x 106 1900 0.935 x 106 3800 1.87 x 106 3800 1.87 x 106 3800 1.87 x 106 3800 1.87 x 106 3800 1.87 x 106 0
0 3800 1.87 x 106 3800 1.87 x 106 1900 0.935 x 106 Amendment 93 February 1, 1995
R AL R R co DOWN 400 n
LL u
UJ 350 a:
.::i I-4:
a:
mo lU Cl.
w I-2

SO
'.z
<(
__J 0
200 *-
0 u 0:
0 1:SO *-
I-l)
~' RHriHttiHiiiliHfmHtnsmmmllHBiillmml
<{
lU Ct 100 I
t I
I 10 1:S 20 2:S 30 3:S 40 TIME AFTER REACTOR SHUTDOWN (I-OURS) 212 F AT T=7 :S HOURS 200 F AT T=l3 D HOURS Amendment 93 February 1, 1995 COMANCHE PEAK S. E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Nonna 1 RHR Coo 1 down FIGURE 5.4-8
BTP RSB 5-1 SINGLE TRAIN R COOL I\\
LL LJ
.. ao w
0::
350
)
f--
<(
er w
Q_
2.
w I-f--z 300 *-
<(
2".50
_J 0
0 L) 0::
0 200 *-
f--u
<(
w 0::
150 IDlll!mrumo1J!BllliDmn 15 20 2'.S 30 3'.S 40 I ME AFTER REACTOR SHUTDOWN ( 1-0uH.::i 21;.1 F AT T=H HOURS 200 F AT T=15 2'.S HOURS Amendment 93 February 1, 1995 COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 SINGLE TRAIN AHR COOLDOWN FIGURE 5.4-9
HEATER SUPPORT PLATE 4026-185 SPRAY NOZZLE SAFETY NOZZLE UPPER HEAD LI FT ING TRUMM I ON SHELL LOWER HEAD INSTRUMENTATION NOZZLE ELECTRICAL HEATER SUPPORT SKIRT SURGE NOZZLE COMANCHE PEAK S. E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Pressurizer FIGURE 5.4-10
SAFETY HEADS DISCHARGE LINE CONNECTION SPRAY WATER INLET
~ ii 1:1 t.-1..J"1'~tt---_J I
I ~t~"'::-::-:-~~_J.l....J
1
_:;...*_ I ~~~::'::-::""~;;;;;J....J q
I n '
VESSEL SUPPORT It
!I I--S~A~G~R~~-

;'rj.-;--

I ! \\
DRAIN CONNECTION VESSEL SUPPORT COMANCHE PEAK S. ES.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Pressurizer Relief Tank FIGURE 5.4-11
8555-29 COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Reactor Vessel Supports FIGURE 5.4-12
N 4 90°-----
RCP. # 3 SG.# 3
~
<t_ SUPPORT R.C.P. # 4 EMBEDMENTS BY OTHERS TYP. FOR EACH SUPPORT S.G.#: 4 r
270°
-~ \\:ACTOR a CONTAINMENT 3'-cl' -
0° IS.G.# I ft. REACTOR AMENDMENT 8 NOVEMBER 30, 1979
~
R.CP. #I COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 PLAN-REACTOR SUPPORTS TUSI UNIT =M: I FIGURE 5.4-IZA
RCP.# 2 N --
270°-----
IRce{I
~
~~
S.G.# I r
~-+----+-900 r
~~~
~-
iREACTOR
&CONTA[
-~
~
1800 i SUPPORT iREACTOR AMENDMENT 8 NOVEMBER 30, 1979
~
COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 PLAN-REACTOR SUPPORTS TUSI UNIT#2
5. 4-12 El
~o>~
/~
-~
\\lL i
~*
I
-- HOT AND COLD STOPS t~OTE

ONLY 2 SNUBBERS REQUIRED.
TO BE INSTALLED AT LOCATIONS 2 AND 4 AS SHOWN.
SNUBBERS HAVE ST ONLY ON UNIT 2.
REMOVED FROM UNIT 1.
Amendment 102 l.j
~
ll UPPER LATERAL SUPPORT SNUBBERS
LOWER LATERAL SUPPORT PIPE COLUMHS DIRECTION OF THERMAL EXPANSION COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNITS 1 AND 2 TYPICAL STEAM GENERATOR SUPPORTS FIGURE 5.4-13
CROSS-OVER LEG LEG TI E RODS PIPE COLUMNS COMANCHE PEAK S. E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Reactor Coolant Pump Supports FIGURE 5
4-14
PRESSURIZER SKIRT SEISMIC SUPPORTS BEAR I NG PLATE GROUT 3842-5 COMANCHE PEAK S. E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Pressurizer Supports FIGURE 5.4-15
THIS FIGURE HAS BEEN DELETED.
Amendment 66 January 15, 1988 COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Crossover Leg Restraint FIGURE 5.4-16
THIS FIGURE HAS BEEN DELETED.
Amendment 66 January 15, 1988 COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Crossover Leg Vertical Run Restraint FIGURE 5.4-17
THIS FIGURE HAS BEEN DELETED.
Amendment 66 January 15, 1988 COMANCHE PEAK S.E.S.
FINAL SAFETYANALYSIS REPORT UNITS 1 and 2 Typical Hot Leg Pfpe Whip Restraint FIGURE 5.4-18
I.,
. ~..
..... v Ill
.. *i; -.
tol
. ~.
INSULATION ----..
. /
/
REACTOR COOLANT PIPE COOLING AIR PASSAGE ---
(TYPICAL)
PRIMARY SHIELD CONCRETE --
(TYPICAL)
NOTE:
Hot and Cold Leg Restraint may be eliminated (See Section 5.4.14.2.5) 0.5 INCH GAP (TYPICAL)
AMENDMENT 61 DECEMBER 19, 1986 COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 TYPICAL LATERAL RESTRAINTS FIGURE 5. 4-19
CONTACT CLOSES ABOVE HI FLOW SETPOINT CONTACT CLOSES BELOW LOW FLOW SETPOINT Spring Return To Auto From Both Sides OPEN OPEN MOTOR OPERATED VALVE (MOV)
AUTO Amendment 91 April. '15, 1994 CLOSE MCB MOTOR OPERATED VALVE (MOV}
TRAIN A
B FLOW SW INSTRUMENT NO FIS-610 FIS-611 MOV NO FCV -610 FCV-611 COMANCHE PEAK S.E.S.
FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 RHR PUMP MINI-FLOW VALVE INTERLOCK FIGURE 5. 4-2 0

ML16180A444

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