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: ML16042A344; ML16180A424; ML16180A425; ML16180A426; ML16180A427; ML16180A428; ML16180A429; ML16180A430; ML16180A431; ML16180A432; ML16180A435; ML16180A436; ML16180A437; ML16180A438; ML16180A439; ML16180A440; ML16180A441; ML16180A442; ML16180A443; ML16180A444;
References
	txx-16006, CP-20160003
	Download: ML16180A444 (137)
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33.76 AMENDMENT 61 DECEMBER 19, 1986 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 EF- GAS BlllLlllN.G____"_

FIGURE 38 .13-1

YG VYYJ Mxx MXY Vxx 0

vxx 0 ... MXY Mxx

XP VYY 00

.....;::~ _ _.....,-.,. MYY MYX NOTES:

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 AMENDMENT 61 YP IS PARALLEL TO YG 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

37.5"

/~-,

6s

.I Ss}

© '

0 0

cO 7s SEE WELD DETA:~

y 0

y NOTES:

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

2. MEMBERS 2 & 3-8" SCH 160 PIPE x4! ~

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

4. MEMBER 7 IS A FICTITIOUS

~

MEMBER FROM THE CENTERLINE WELD AT JOINT 5s TO THE OUTER SURFACE OF THE SUPPORTED PIPE

5. LEGEND:

2 INDICATES JOINT AMENDMENT 61 DECEMBER 19, 1986

@ INDICATES MEMBER s INDICATES STRUCTURAL ATTACHMENT POINT COMANCHE PEAK S.E.S.

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

616~-7 0

o e 11.973 FUEL ASS'Y

+

AND CONTROL ROD Q 0 0 0 0 --A----A>-F'll-------4 0 G G GUIDE 00 THIMBLE 8.~66 TYP FUEL ASSEMBLY WITHOUT ROD CLUSTER CONTROL FUEL RODS 2611- REQ'D COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT Typical Fuel Assembly Cross AMENDMENT 92 Section 17X 17 AUGUST 31, 1994 FIGURE 4.2* 1

I 159.8 R E F - - - - -

II '!tool _: 'Joowl "-' -- '>-I ...... _:= 'J.J ....... = .._, 1--o! == '>-I 1-ool -= '>-I .._.

- ~*-'-JI > - .c:;;1 I 2

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

GRID ASSEMBLY 7.162 REF 0.875 DIA. REF TOP VIEW BOTTOM VIEW COMANCIE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT Typical 17Xl 7 Fuel Assembly Outline AMENDMENT 92 AUGUST 31, 1994 FIGURE 4.2-2

7579-59 END PLUG SPRING

6. 3"

( TYP)

U0 2 PELLETS FUEL-CLAD GAP llP~.o*

(TYP)

Z I RCA LOY CLAD SPECIFIC DIMENSIONS DEPEND ON DESIGN VARIABLES SUCH AS PRE-PRESSURIZATION. POWER HISTORY. AND DISCHARGE BURHUP COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT Typical AMENDMENT 92 Fuel Rod Schematic AUGUST 31, 1994 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 QJIOE TUBE FUEL ASSEMBLY ASSO&_Y ASSE"8-Y 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

160.95 150.40 r S PR I HG RETA I HER 1.1140 MAX. ~~~-.>-----~~~ *j ~-~---'-~

j__J I. 2'> 0 IA

\ ¥-=i!3i_ __; ;

'rt-~--------*-,-*--=-- -

$4'

=3-t=qp

- ---~-Ff . )

"'"" ""\ 0.361 DIA * - 0.315 DIA MAX I. 19200 ABSORBER LEHllTH l

COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT Typical AMENDMENT 92 Rod Cluster Control AUGUST 31, 1994 Assembly Outline FIGURE 4.2-9

0 . 381 DI A. NOM .

42.00 ABOSRBER MATERIAL r

loolll-~~~~~~~~~~~~~~~~~~~~151.9 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 4.2-11 184 Has Been Deleted AMENDMENT 84 FEBRUARY 28, 1992

POISOll LEllGIM

f(i=E-=-~~***~ E-W* lf~--~--~*ti*-- *---*-. e===: !n-f;f

-***-. ---- ~* -£?-

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

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

r-* 2.970 TYP. --1

[~:::~ypl l 1

TYP. I 88.00 SECONDARY SOURCE ANTIMONY BERYLLIUM 6.320 SQ

\!VABA ROD ~----B4C ALUMINUM OXIDE ABSORBER J

---p... 6y Vi5//;,,j -~

PRIMARY 32.50~

SOURCE 0.135 CALIFORNIUM i . . . . - - - - - 4.385 7.942 151.565 .................................................,.._ _,,.........................................------*--...J

.......................- ...................______ 155.950 f7ID rID x 151.565 143.107

- 8A58 T-w 0.381,. - + ! 0.3r~ +. 0381,. __ -~ _ _ ti>\ 0424';'

Y c

X + END PLUG LENG TH 9.583 J__ --- j~

~ J PRIMARY BURNABLE SECONDARY THIMBLE SOUACL ABSORBER SOUR CL PLUG COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNIT 2 AMENDMENT 84 Composite Core Component FEBRUARY 28, 1992 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

"'150.4

~~ ~

-=?J ) - 11 ~

1.. 88.0 SECONDARY SOURCE ANTIMONY BERYLLIUM

.1 NOTE: ALL DIMENSIONS ARE IN INCHES STAINLESS STEEL COMANCHE PEAK S. E.S.

t 0.381 0.432 FINAL SAFETY ANALYSIS REPORT OIA DIA Typical t t Secondary Source Assembly TH IM8lE AMENDMENT 92 SECONDARY SOURCE PLUG AUGUST 31, 1994 FIGURE 4.2-15

-q 13

- c:() F::>

-E:(J L:::>

COMANCHE PEAK S. E.S.

FINAL SAFETY ANALYSIS REPORT Typical AMENDMENT 92 Thimble Plug Assembly AUGUST 31, 1994 FIGURE 4.2-16

CPSES/FSAR Figure 4.3-1 has been deleted.

9 0 8 -4

)

)

-8

!i: 7 ::E O'I O'I

(/') 6 -12 w(/')

w Q.. Q..

0 0

(/',) 5 ,,,,,,,. ,,,,. -16 Cl) co::

w

c

,, ....I w

)

(!)

c 4 / -20 LL.

LL.

Pu239 / 0 7I LL.

0 z:

0 3 -211- ....

Q..

<..)

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)

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z:

II Q

0 0

co:: 2 -28 <..)

Q..

Pu2l+I - --

~

-- - ---- -- -32 0

0 8 L..-L!!!::...::::......1~~.J._~-l..~--Jl...-~.J._~-L.~~L-~....l-~--1-36 12 16 20 211- 28 32 36 ltO BURNUP, (GWD/MTU)

COMANCHE PEAK S. E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Production and Consumption AMENDMENT 92 of Higher Isotopes f 'l'u- .f ~ ~1 )

AUGUST 31, 1994 FIGURE 4.3-2

1600 NOTE: HOT FULL POWER RODS OUT

~

Q..

z:

0 l~O

- .................... WITHOUT BURNABLE POISON

~

Cl::

I-ffi

(,,,)

z:

0

(,,,)

800

~,

,, BURNUP DIFFERENCE z::

1300 MWD/MTU 0

ex:

~

...J ct !JOO

(..)

I WITH BURNABLE POISONS I-

-ex:

(.)

0 0 2000 14()00 6000 8000 10000 1~00 lllOOO CORE AVERAGE BURNUP (MWD/MTU)

COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Boron Concentration va Pint Cycle AMENDMENT 92 Bumup With and Wllhout Burnable Absorber Roda (Typical)

AUGUST 31, 1994 FIGURE 4.3-3

181 181 181 181 181 D 181 D 181 D 181 ~ ~ 181 181 181 D 181 D l8J 181 l8J D 181 181 D 181 D l8J D 181 181 181 181 181 181 D 181 D 181 181 l8J 181 181181 D 181 D 1810 24 BP'S 12 BP'S

~CORE CENTER 181 181 181 181 D 181 0 D 0 181 181 D 181 D 0 0 D 181 0 0 181 181 D DD 0 181 0 181 D 181 D D 0 D 0 0 181 0 0 Do 0 oD 181 0 0 0 181 9 BP' S 8 SP'S CORE CENTER CORE CENTER

~

o 181 D 181 0 f8I 0 0 Do 181OD0181 0 0 181 DD DODOO D 181 D DD 0 D 0 0 0 DD 0 D 0 0 o D o0 Do 0 oD 4 SP'S 3 BP'S COMANCHE PEAK S.E.S.

AMENDMENT 92 FINAL SAFETY ANALYSIS REPORT AUGUST 31, 1994 UNITS 1 and 2 Burnable Abaotber Arrangement Within an Aucmbly (Typical)

FIGURE 4.3-4

180° R P N M L K J H G F E D C B A 4 4 4 1

~4 lP ip*

9 9 2 23 23 4 8 4 24 3 3

24 12 4S 8 I 8 12 24 4

9 12 8 8 8 12 9 5

4 4 8 8 8 8 4 4 6

7 24 8 8 12 8 8 24 go* 8 4 8 8 12 12 8 8 4 9 24 8 8 12 8 8 24 4 4 8 8 8 8 4 4 10 9 12 8 8 8 12 9 11 24 12 8 8 4S 12 24 12 3 24 4 8 4 24 3 13 9 lP lP

9 14 23 23 4 4 4 944 BP Rods 15 12.5 w/o B 0 2 3 NUMBER INDICATES NUMBER or BURNABLE POISON RODS

s* INDICATES SECONDARY SOURCE ROD

p* INDICATES PRIMARY SOURCE ROD COMANCHE PEAK S.E.S.

'*' INDICATES DEPLETED PRIMARY SOURCE ROD Fr.JAL SAFETY ANALYSIS REPORT Typical Burnable Absorber AMENDMENT 92 Loading Pattern AUGUST 31, 1994 FKJURE 4.3-5

G F E D c B A I

~8 0.93 I

9

. ._ -~_. ._. EJDDDDDD 1 6

-~ EJ6DDDDD 1 2 0

1

....__.._..l.:O EJ6EJDDDD 2

~l.~a BGBBDD 13 ~l.:,___..12 EJGEJEJ EJD lj. ~6_EJBBEJEJ

_o......

15 o.~2 EJ.84- ~a.GS CALCULATED F:H = 1.40

.....__,,~_,

I LJ KEY:

VALUE REPRESENTS ASSa.tBLY RELATIVE POWER

'i.

COMANCHE PEAK S.E.S.

AMENDMENT 92 FINAL SAFETY ANALYSIS REPORT AUGUST 31, 1994 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

0 1 1 12 8

GDDDDDD

'_ -~ GEJDDDDD II-I.~ GGEJDDDD 12 1 01

__ G86GDD 13~1-:i---13 GGBGEJD I

0 86 l4- __......

_ _GGGG 8

~~~

I IS 0.80 CALCULATED F:H = 1.36

---~--~~L=..J I

K~:

VALUE REPRESENTS ASSEMBLY 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 E c

. F D B A 0.88 - -

I I KEY:

VALUE REPRESENTS ASSEMBLY RELAT IVE 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 1.03 ..... - ""' ---t 8

I 9 1 17

-: BDDDDDD

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

0 I. ._ . . ._'*~' BEJEJDDDD I

2

'- -ti.~- - ~ BBEJEJ DD GBEJEJ EJ D I

3 """---1,.:_,s I

~ _*-+-~_BEJBEJB 0

O.~ 666 I

5 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.: 6GEJDDDD 12 12 "- -to.~1- - -19 G EJ EJ EJ DD 13 "---4,.:1-----1,q GG 6 EJ EJD 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

G F E D c B A l - 0.83 8

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

9 1 6

.~ BDDDDDD o_.._o.~s GEJDDDDD I

'~ *: c:JEJEJDDDD 1 5 2 -1 .~- 2 BEJEJBDD 3

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

s_o*-~_BBB I CALCULATED F:H =

KEY:

1.3~

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

February 2, 1998 FIGURE 4.3-11

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

[X I. 19 I. 19 I. 17 I. 19 [X I. 17 I. 19 1.20 I. 20 lX I. 17 I. 17 I. 20 I. 18 1.04 1.08 I. 14 [X I. 18 I. 18 I. 16 I. 16 I. 18 I. 16 I. 16 I. 19 I. 19 lX 1.04 1.06 I. 10 I. 14 I. 16 lX I. 16 I. 16 lX I. 16 1. 16 lX I. 17 I. 15 I. I I 1.04 1.05 1.07 1.08 I. 10 I. 12 I. 10 I. 10 J. 12 I, 10 I. II I. 12 I. II 1.09 1.08 1.07 1.04 1.04 j .04 1.04 1.05 1.05 1.05 I .OS I .OS I .OS I .OS I. 06 1.06 1.06 1.06 I. 05 1.061 AMENDMENT 92 AUGUST 31, 1994 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 1.08 1.00 I. Ott 1.08 1.07 1.08 I. 10 1.08 l.'08 1.0 I 1.06 x 1.09 I. 10 x I. 10 I. 10 x

1.00 1.04 1.08 1.07 1.08 I. 10 1.08 1.08 1.10 1.08 1.00 I. Ott 1.08 1.07 I. 08 I. I 0 1.08 1.08 I. tO 1.08 1.08 1.0 I 1.06 x 1.11 I. II x I. 10 I. 10 x 1.10 I. 10 x

1.00 I. 03 1.09 I. II 1.09 I. I I 1.08 1.08 I. 10 1.08 I. 08 I. 11 1.09 0.99 I. 02 1.07 x I. I I I. II 1.07 1.07 1.09 1.07 1.07 I. II I. II x

0.98 1.00 1.03 I. 07 1.09 x 1.08 I. 08 x I. 08 1.08 x 1.09 1.07 1.03 0.98 0.99 1.00 1.02 1.03 1.06 I. 014 11. 04 1.06 1.04 I. Ott 1.06 I. 03 1.02 1.00 0.98 0.98 0.98 0.98 0.99 1.00 1.0 I 1.00 1.00 1.0 I 1.00 1.00 1.01 1.00 0.99 0.98 0.98 0.981 AMENDMENT 92 AUGUST 31, 1994 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

2.0

'. 5 p = o. s D = 0. I AO = 5. 9 !

a::

I.I.I 3:

0 Q..

8 1.0 N

...J p ::: 1.0

& D = 0. I g AO :::-8. 8 I 0.5 0.0 0 10 30 50 60 70 80 90 100 PERCENT OF ACTIVE CORE HEIGHT FROM BOTTOM COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Axial Power Amendment 95 Shapa Occurrin1 at SOL February 2, 1998 FIGURE *.H*

z.o POWER = 0. S 9 0 55 AO= -2~.03 I. 5 POWER = 0. 5 D = 0.21 AO 8.20 er:

w..J 3:

0 0..

t. 0 0

w..J N

<I:

t:

er:

0

i::

0.5 0.0 0.0 0. I 0. 2 0. 3 O.t+ 0.5 0.6 0.7 0.8 0.9 ! .o PERCENT OF ACTIVE CORE HEIGHT FROM BOTTOM COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT Typical Axial Power AMENDMENT 92 Shapes Occurring at MOL AUGUST 31, 1994 FIGUAE 4.3-15

= 0. :

rD p

= 0 . '32

~o =-2: 7 p = 0. ')

'. 5 D = 0 c AO *=o.S'.:l p = ! . 0 er::

w D = 0.'0

~

c 0...

0 i .o w

N

~

c

z:

0.5 0.0 0 10 20 30 40 50 60 70 80 90 100 PERCENT OF ACTIVE CORE HEIGHT FROM BOTTOM COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT AMENDMENT 92 Typical Axial Power AUGUST 31, 1994 Shapes Occurring at EOL FIGURE 4 . 3 -16

Axial Relative Power I. 5 1.0 CORE AVERAGE

-- -- ADJACENT TO D BANK 0.5

- - - - REMOVED FROM 0 BANK

- - - - - - PERIPHERAL LOW POWER ASSEMBLY 0.0 CORE CORE CORE HEIGHT TOP BO TI OM 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

0.759 0.792 4.3 I. 217 I. 224 0.6

o. 774 I. 255 0 I. 249

" -0. 5 '

I. 229 I. 229 I. 225 I. 218

-0. 3 -0 9~

I. 109 I, 077 I. 107 1.092

-0.2* 1.4 I. 202 I. 223

1. 170 I. 256

-2. r 2. 7::

0.523 1.217 I. 22 ! I. 217 O" 548 I. 203 I. 233 I. 210

4. 6 . 1.1

1.0' -0.6' I. 229 I. 229 I. 189 I. 220

-3.r -0.7%

I. 217 ...,.___ CALCULATED I. 211 ...,.___ MEASURED

-0.5'[ ...,.___ 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 AMENDMENT 92 and Measured Relative Fuel AUGUST 31, 1994 Assembly Power Distribution FIGURE 4. 3-24

627~-77 8~

- I-0 Cl) z:. -:.:~

o o z: !"- 't,.'.2.

l.U l,f')

x I-'°"

0 0

z 0:: 0

"'"':..:; 00

-' 3 :z 0 C> <

a:l 0... al c._

w

<::> LU

<( 0:: Q 0:: 0 LU 0 1-w u

> :z

<-~.

I-

_J

<.o ffi cu :::: c*i ::::>

u LJ..J

r:

0::

0 0

"" < 0 II

<( 0

" w u 1..1.. <..:>...:

a::

00 in u LI..

0 1-z:

1..1.J Ou

r ffi a..

0 N

0 N 0 ::I" N 0 0 (;>

M3MOd 3AllV13~ lVIXV COMANCHE PEAK S.E.S.

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

627~-5~

x REACTOR l 0 REACTOR 4-

\J REACTOR 2

REACTOR 5 0 e REACTOR 3 FQ 0

0 3.0 0

2.5 o*

0

x x ~x x

ii.

0 x 2.0

0 oO 8 .>P tf*,. x 0 Q:

0 I. 5 4-5 0 30 -25 15 -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:>

a.

'1:>

-1.6 I-z:

L.IJ -1. 8 u

I.I...

I.I..

UJ 0

u -2.0 Li.J 00:::

I-ct 00:::

Ll.J 0..

-2.2

E LIJ I-Ci::

_, -2.4 Ll.J 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

-6

-0 :::

W-l 31:

-8 0

0..

-~

<...)

E e::..

0..

<-<::> -10

<:i..

I-z; L.U

<.J LL LL LJ.J -12 0

<...)

0:::

L.U 3:

0 0..

...J z:

0 -lij 0:::

L.U

...J 0..

0..

0 0

-16

-18 0 20 40 60 80 100 POWER (PERCENT OF FULL POWER)

COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 AMENDMENT 92 Typical Doppler-Only Power AUGUST 31, 1994 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}

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

"U:'

0

~

u 0...

10 I 000 PPt,1 1500 ' ' " \

~

f-

,0 Cl.. 0

"° I-z:

U1 u

u_

u_ -10 i.J..J 0

u LU a::

f-

<:(

a::

i.J..J

-20 a.. 0 PPM 2i f-0:::

0 I-

<:(

0::: -30 w

a 0

~

-40 0 100 ~ 300 400 500 600 MODERATOR TEMPERATURE (°F)

COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSlS REPORT UNITS 1 and 2 AMENDMENT 92 Moderator Temperature Coefficient AUGUST 31, 1994 - BOL, No Rodi (Typic.al)

FIGURE 4.3-30

20 10 500 PPM

- 0 LL 0

~

u Cl..

f-

.0 Q_ -10

)

I-0 PPM z:

w u

LL u..

w -20 0

u w

er:

I-

<(

0:::

l.J.J Cl..

-30

~

f-0:::

0 I-

<t 0:::

w -40 0

~

-50 0 100 200 300 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

5 0

0 I.I..

-5 0

a..

t:

- I-Kl a_

Kl I-

-10

z::

1.1.J

(,..)

I.I..

UJ

-15 0

(,..)

1.1.J 0::

I-

<C 0:: -20 w

a..

~

1.1.J I-0::

0 I-

<C -25 0::

1.1.J c

0

£

-30 0 500 1000 1500 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

0

-5

O u..

0 0...

-10

E I-

<O (I..

.Q I- -15 LU u

I.I..

u..

I.I.I 0

u -20 w

c:::

)

I-c:::

l.IJ 0...

CJ I-

-25 co::

0 I-ct er::

w Q

~ -ll

-35 0 500 1000 1500 BURNUP (MWO/MTU)

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

FIGURE 4.3-33

-10

- 0:::

w 3:

0 0..

..... -!2

z:

w u

0:::

w 0..

E:

u c.. -

a..

.0 c...

.c

z:

w -16 u

u...

w_

w 0

u 0:::

i.:.... -18 3:

0 a..

-1

<(

f-rEOL 0

f-

-20

-2?.

0 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 0 1500

~

w 3:

0 c..

_J

<t I-0 I-2000 2500 0 20 4-0 60 80 100 POWER LEVEL {PERCENT FULL POWER)

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

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

BOL,EOL FIGURE 4.3-3!!

12288 ~

r:-,

& @ & r. ,

EJ 1S ol L-J IS'-

'o/ ~"'

,s/ IS CI t1l, L-.J ro'I

\. ) ~ 'a'

\. J r:-1

~

I CI ISD I L-.J L-.J

£ 0 'fl 0 ~

s~

:I ~9 0 ~ 'fl (o) \fl ~ 0

~

Vs

"'o/

£ rs 1 0 \fl 0 r:-, £ I DI IS CI L-J L--.J

~ 0 r. ,

~ r: ,

Co) ~

IS CI

~'\, IS '\. 1S DI L-.J ,s/ ,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

-c.. 4-0

(/)

E c..

c

.... 30 IX i

Q 0

IX

<C 20 I-z:

1.1..1 IX 1.1..1

"""' 10 Q

0 50 100 150 200 250 STEPS WITHDRAWN COMANCHE PEAK S.E.S FINAL SAFETY ANALYSIS REPORT Amendment 95 February 2, 1998 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

(/) I f IHORMALI ZED SCRAM TIME

..<(

0 0.7 u..

0 Q..

~ 0.6

~

w

<..)

0.5

~

t;;

0 w

0 Q..

0..

o."

~

Cl w

0.3

<..)

~

I-(/)

0.2 Ci 0.1 0.0 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 COMANCHE PEAK S. E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Trip Curve AMENDMENT 92 AUGUST 31, 1994 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-

z UJ

(..)

-5 0::

w

~ -10

~

(/)

It -15 0

...J

..:r BURN UP PERIOD STABILITY IHOEX x -20 CURVE (MWO/MTU) (HOURS) (HOURS- I)

""' I 1550 32.lt -0.01' I 2 7700 27 .2 -0.014

-25

-30 0 ll 8 12 16 20 21l 28 32 36 llO IJ4 ll8 52 56 60 611 68 72 Tl ME (HOURS)

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

10 8

l.~

t

...... 6 z:

C(

a::

0

<(

11 c- \

l 2 \

N

~.....

STABILITY INDEX= -0.076 (HR. - I) 1-

i a::

0 C(

g. -

0 2 *

\

-w.,,,,t>~

\ii e"lr * **** ..-..........

~ - q

z:

UJ 0::

If - 6

H42 u..

0 1- - 8

0 4

.....1 RCC E-11 I-2 I- -10

z:

<(

IX Cl -12 N43 N41

""'g.

- Ill

-16 0 q 6 12 16 20 2\l 28 32 36 ltO lilt 148 52 56 60 611 HOURS AFTER WITHDRAWAL Of RCC E-11 COMANCHE PEAK S.E.S FINAL SAFElY ANAi.YSIS REPORT Amendment 95 UNITS 1and2 February 2, 1998 XV Xenon Tesl Thermocouple Response Quadrant TKI Olfference Vt.. Time FIGURE 4 3-41

CPSES/FSAR Fi gures 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

Key:

1.096

.6.h/.6.h 1.001 GIG 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 1.238 1.000 1.001 1.000 1.002 1.000 1.126 1.161 1.093 1.086 0.916 0.967 1.001 1.001 1.002 1.002 1.001 1.001 1.025 1.025 0.990 0.975 0.823 0.466 1.002 1.002 1.002 1.002 1.000 0.997 For Radial Power Distribution 0.717 0.780 0.664 0.563 Near Beginning of Life, Hot Full 0.999 0.999 0.998 0.997 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 1 Figure 4.4-2 Amendment No. 103

Key:

1.096 Ah/Ah 0.996 GIG 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 1.242 0.985 0.989 0.988 0.998 0.981 1.129 1.165 1.095 1.086 0.916 0.963 0.992 0.990 0.995 0.996 1.009 1.006 1.024 1.025 0.989 0.973 0.819 0.468 1.000 1.000 1.003 1.004 1.018 1.018 For Radial Power Distribution 0.715 0.777 0.663 0.562 Near Beginning of Life, Hot Full 1.022 1.019 1.021 1.019 Power, Equilibrium Xenon Calculated F N -- 1.34

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

Key:

1.097

.6.h/.6.h 0.995 GIG 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 1.243 0.987 0.990 0.989 0.997 0.987 1.130 1.165 1.095 1.087 0.914 0.961 0.993 0.991 0.995 0.996 1.005 1.003 1.023 1.024 0.987 0.971 0.817 0.469 1.000 1.000 1.002 1.003 1.011 1.030 For Radial Power Distribution 0.711 0.774 0.660 0.560 Near Beginning of Life, Hot Full 1.016 1.013 1.019 1.025 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 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 0 0 0 0 JfilTD T 0

T 0 T 0

.T I

0 T

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)

COMANCHE PEAK S.E.S.

FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Distribution of Incore AMENDMENT 84 Instrumentation FEBRUARY 28, 1992 FIGURE 4.4-20

630 620 620.1 610 r<

µ.i 600

r:

~

r: 590 589.2

µ...

VJ T HOT

µ.i

~ 580 0

µ.i Ci T AVG

~ 570

~

r<

~

µ.i i::i...

T COLD 558.3

s 560

µ.i r<

557 550 540 530 0 20 40 60 80 100 PERCENT POWER COMANCHE PEAKS E S FINAL SAFETY ANALYSIS REPORT UNIT 1 REACTOR COOLANT SYSTEM Amendment 102 TEMPERATURE PERCENT POWER MAP FIGURE 4.4-21A fsOOOO I 0. dgn

620 618.8 610 600 r<

µ.i

r: 590 589.2 ffi~ T HOT

r:

µ... 580 VJ

µ.i

~ T AVG 0

µ.i 570 Ci

~ 559.6

~ T COLD r< 560

~

µ.i i::i... 557

s

µ.i r< 550 540 530 0 20 40 60 80 100 PERCENT POWER COMANCHE PEAKS E S FINAL SAFETY ANALYSIS REPORT UNIT2 REACTOR COOLANT SYSTEM Amendment 102 TEMPERATURE PERCENT POWER MAP FIGURE 4.4-21B fsOOOOOz.dgn

I CPE G Tf<JSDf< '"l 'IG REVISEOTOINCORPOR>TEDESICNC**t+VE:

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

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PIPESLOPEODOWN"llAROTO PR OVIOEWATERSEALBETWEEN PR ESSURIZER ANO MOTOR OPERATED v*AL VES .
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"* ~iiM'.;;~'.;~~£f;1~~~:~j);f;[~'.i~~:::1i:::J:J"~~~;H:;;i, II. TYCONHOSETO BE INSHLLEO AT THESE CONNECT IONS TO VENT PRESSURIZERDURINGDRA ININGANOFILLI NG.
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23. 0.83 INCH l .D. n ow RESTRICTORS IN PRESSURIZER STEA i.. SPACE LEV EL INSTRUMENT NOZZLES PROVIDE THE CLASS-I TO CLASS-2 TRANSITION.
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PCV-4S~C RC-11051 P6V-4SSB LOOP 2 RMllS STEAM GENERATOR Amendment 67 February 5, 1988 IRC I OAC COMAN!)£ PEAK S E S FINAL SAFETY ANALYSIS REPORT s"
IHI Pl.MP UNITS 1 ANJ 2 H.L. tlJ.
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 speci f ied 68 c) x 106 68 Amendment 68 February 15, 1988
l* MISSILE SHiELD UNIT20NLY
, *.,-*.,. JI r..:101~1 _
Cll>Q-1rtOOi-CATl"'4
~~~ ~f.'l~l(.'lo ~OOM
~~~
'SECTION LOOKING NORTH SECTION LOOKING EA§T 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.
FNAL SAFETY ANALYSIS REPORT Amendment 102 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
15, 092-1
...J
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LlJ I-
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Ll.J
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LIJ
~
...J oo 180° I Ol -ll~2C 101-14-28 270° AMENDMENT 8 NOVEMBER 30, 1979 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
15,092-2 goo
.....I
.....I LLJ
c Cl)
LU R3807-I
-=r:
0 LLJ
£ 0:: 180° LU z: 101-121u CORE 101-171 210° IOl-14-2A R3816-l
.....I
.....I R3816-3 LU
c Cl) 0::
LLJ
~
.....I oo 180° 101-14-2C I Ol -I lt2B 270° AMENDMENT 8 NOVEMBER 30, 1979 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
180 INTER & LOWER SHELL LONG. & GIRTH SEAM 160 140 120 CCI LL. 100 C!J a:
w 80 z
w 60 40 TNDT =. 70oF RT NOT = *70°F 20 0
200 -100 0 100 200 TEMPERATURE (°F)
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
200 200 180 r
~
INTER TO LOWER SHELL GRITH SEAM WELD CODE NO. E3.10 180 I INTER Iii LOWER SHELL ONG.
SEAMS WE LO CODE NO. G3.03 0
t 160 160
~
TNoT* 40of TNDT * -50of RTNor*400F 140 RTNOT .. -50of m
.... 1
~
120 120 u..
2
> n/
C1 100 0 I 100 cc w
zw so r / I 80 60 I
"TI i5 c
0 m
I
wn z-0 §' g o
I c ~
11 z
)>
ro Cf) n
)>
-1
=t I 20 40 20 I I 0
r; "
r n 0 0 3!~ zmZ
"' "O _ . '"ti - -I n *100 0 100 200 *100 0 100 200
' f "' 0 "
il" ~ -I - m TEMPERATURE (°F) TEMPERATURE (°F)
)> )>
i;:1.d*
. . . )>
Q) z -u
~3 I [ :J ~ m
=: <D n 0.. Cf) )>
..... :s I
! N A
...co Cf) 3Q. '<
a Cf)
..... <D m
co :s -u ~
co - 0 .Cf)
a
~ co
..... -I
~I
TNDT * .2Qof TNoT* *20oF 100 0 0 100 RTNor* 100F RTNDT'" -10°F 80 80 m
..J m..J
.,:. 60 .,:. 60 LL
(!)
u..
(!)
a: a:
w 40 w 40 z
w zw INT. SHELL RATE INT. SHELL RATE 20 R-1107*1 20 R-1107-2 0 '--~~....1-~~-i..~~~....___. 0 '----.l.---.J...---'----'
-100 0 100 200 -100 0 100 200 TEMPERATURE (°F) TEMPERATURE (°F)
TNoT* *200F 100 RTNOT* 1D°F 80 m..J
.,:. 60 LI..
(!)
a:
w 40 zw INT. SHELL RATE R-1107-3 20 COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT 0 i.--~~-'-~~....i..~~-----' UNITS 1 and 2
-100 0 100 200 Comanche Peale Unit l Cho.rpy V *Notch Impact Dato. for TEMPERATURE (°F) IntennediateShell Plates R-1107-1. Rl107-2 and R* 1107-3, Transverse Orientation FIGURE 5.3-3A Amendment 91 April 19, 1994
120 - - - - - - - - - - - - , 120 0
TNoT**200F TNoT* .zooF RT NOT** 20oF RTNOT* 10°F 0
100 100 a;
_, 80 a;
_, 80 r!. r!.
LI.
LI.
> 60 > 60 a: a:
w w zw zw 40 40 INT. SHELL INT. SHELL R-3807-1 R*3807*2 20 20 0
0 0
-100 0 100 200 *100 0 100 200 TEMPERATURE (°F) TEMPERATURE (°F)
TNoT* *20oF RTNoT* .200F 100 2
80 a;
r!. 0 LI. 60 a:
w z
w 40 INT. SHELL COMANCHE PEAK S.E.S.
20 R-3807*3 FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 0 Comanche Peak Unit 2 Charpy V-Notchlmpact Data for
-100 0 100 200 IntennediateShell Pla!a R-3807-1, R3807-2 and R-3807-3 Transverse Orientation TEMPERATURE (°F)
FIGURE s.3-:rn Amendment 91 April 15, 1994
TNor* -200F TNor**300F 100 100 RTNor*OOF RTNor*20°F 80
§... 80 m
..J m
..J
~ 60 ~ 60 u.. u..
C1 C1 a: a:
w 40 w 40 zw z w
20 LOWER SHELL 20 LOWER SHELL R-1108-1 R-1108*2 0 0
-100 0 100 200 -100 0 100 200 TEMPERATURE (°F) TEMPERATURE (°F)
TNDT * .30of 0 100
~
RTNOT *OoF 80 ii
..J
~ 60 u..
C1 a:
w 40 zw COMANCHE PEAK S.E.S.
20 LOWER SHELL FINAL SAFETY ANALYSIS REPORT R-1108*3 UNITS 1 and 2 8 Comanche Peak Unit 1 0 Charpy V-Notch Impact Data for Lower Shell Plates R-1108-1,R*ll08-2and R-1108-3,
-100 0 100 200 Transverse Orientation FIGURE 5.3-4A TEMPERATURE (°F}
Amendment 91 April 19, 1994
120 120 TNOT = .300F TNDT *30°F RT NOT= .300F RTNDT = +/-OoF 100 100 80 80 as- as-
....I
....I
!:::. 60 !:::. 60
(!)
(!)
a: a:
w w z z w 40 LU 40 LOWER SHELL LOWER SHELL 20 R-3816-1 20 R-3816-2 0
0 0
100 0 100 200 -100 0 100 200 TEMPERATURE (°F) TEMPERATURE (°F)
TNor= -400F RT Nor= 40°F 100 80
> 60
(!)
a:
w zw 40 LOWER SHELL 20 R*3816*3 COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT 0 UNITS 1 and 2
-100 0 100 -**
200 Cott1rulche Peak Unit 2 Charpy V-Notch Impact Data for Lower TEMPERATURE (°F) 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 ......,,.-M~~-- THRUST BEAR I NG OIL LIFT PUMP
+ MOTOR MOTOR SHAFT MOTOR STATOR MAIN LEAD CONDUIT BOX
- - - - - - - M O T O R UNIT ASSEMBLY LOWER RADIAL BEARING SEAL HOUSING NO. 3 SEAL LEAK OFF NO. I SEAL NO 2 SEAL LEAK OFF LEAK OFF PUMP SHAFT COOL I NG WATER INLET , 1 1 - - - - - - - COOLING WATER OUTLET
...-~.......+--+-------RADIAL BEARING DISCHARGE NOZZLE ASSEMBLY
~......_."'"*-+--1-------'fH ERMA L BARR i ER AND WE IR HEAT EXCHANGER SUCTION NOZZLE - - - - - IMPELLER COMANCHE PEAK S. E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Reactor Coolant Controlled Leakage Pump FIGURE 5 .4-l
4026-183 600 500 TOTAL r-- HEAD t:::l 4-00 LL C>
<(
w
c 300
_J
<(
t-o r-- I I
200 I
/
/
/
_,,,,,. REQUIRED NET 100

-- PO~IT!VE SL1CTION HEAD 0

0 I0 20 30 4-0 50 60 70 80 90 I 00 I I0 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
6798-2 220 0 BTCT I 200 0 2TCT 9 6 4TCT I 0 I 180 I
I 160 I I
-"'- 14-0
~
z:
I I
o I I
(I')
120 8 (I')
(I')
I LiJ
z:
I: 6 I
~ I/
0 f-100 tJ..J a::
f-
<t 80 I
a::
l.J_
I I
2? 6 01
~
60 0
/
~ f1//
4-0 o _.e,. 0."o LOWER BOUND Kid 20 0
0
-200 -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
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 AUX. FEEDWA!ER NOZhE _/
u FOUR ( 4) NARROW WATER LEVEi. TAPS 4.00 INSPECTION PORT TWO ( 2) TYP !CAL QOWNCOMER ANNULUS__.-
--TUBE SUPPORT PLATE TEN (10) TYPICAi SAMPLf. 'IAP WlOE RANGE SECONDAR'i* l'HELL DRAIN CHANNEL HEAD DIV10ER PLATE CHANNEL HEADJ PRIMARY NOZZLE CLOSURE RING PRIMARY MMJVJAV ___,, TWO (2) TYPICAL rwo JYPICAL
PRIMARY NOZZLE TWO (2) TY 0 !CAL i
COMANCHE PEAK S E S FINAL SAFETY ANALYSIS REPORT UNIT 1 LONGITUDINAL SECTION OF FEEDRING STEAM GENERATOR Amendment 102 FIGURE 5.4-4A
Steam Separators
--- Le~el of Auxiliary Feedwater Nozzle Tube Bundle Tube Supports~
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 Amendment 102 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
~
~
8
µ.,
~
r:ll
µ.,
CLASS I LUMINANT CPNPP GLEN ROSE, TEXAS FLOW DIAGRAM RESIDUAL HEAT REMOVAL SYSTEM Ml-0260 CP-37 Ml-0260 < FINAL PRINT >
I
\0
~
µ.,
~
µ.,
CLASS I LUMINANT CPNPP GLEN ROSE, TEXAS M2-0260 CP-21 M2-0260 < FINAL PRINT >
l
]' t
~---- - - -
---1--1-~
Ill: j 0AC
~,.,___.___~
-~ ~ I i ..
fis-i:iioLTc - - - ~ It---J-------1 I'.
~--~I c~_:_:_J--~::i--n
" 51
~_'_"'-oc<G --1~ III
"'---':OCF- - --
' . *- ______J.
I I
,. LDC f-:5 "
GIRJ!HG Jll\W I (6?i
~ (65
<=CXLOLiG-- - ~
~~-*-~-* .~ J 1
I___.__ __. ..
- C>i-'f:G I NG P\W' 4
~SISNKXI 5M I
/Cv"'°'-o;o~
~~- 31 IAC I QA( 1 ..... ( SIS SI 'UirSSH l 29 ~
e~~-*~~,N~- 1-..t__ _ __,
AMENDMENT 17 APRIL 7, 1981 NOTE:
COMANCHE PEAK S.E.S.
1. THIS DIAGRAM IS A SIMPLIFICATION OF THE SYSTEM INTENDED TO FACILITATE THE UNDER- FINAL SAFETY ANALYSIS REPORT STANDING OF THE PROCESS. FOR DETAILS OF UNITS 1 and 2 THE PIPING, VALVES, INSTRUMENTATION, ETC.
REFER TO THE ENGINEERING FLOW DIAGRAM. Residual Heat Removal System REFER TO PROCESS FLOW DIAGRAM TABLES FOR Process Flow Diagram THE CONDITIONS AT EACH POINT.
FIGURE 5.4-7, Sheet 2
NOTES TO FIGURE 5.4-7 (Sheet 1 of 4)
MODES OF OPERATION I 0212.63 Mode A - Initiation of RHR Operation When the reactor coolant temperature and pressure are reduced to 96 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.
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
NOTES TO FIGURE 5.4-7 (Sheet 2 of 4)
VALVE ALIGNMENT CHART Operational Mode
-A -B 2 c c 3 c c 10 0 0 11 0 0 12 c c 13 c c 14 c c 15 c c 16 p c 17 p c 18 p p 19 p p 20 c c 21 c c 22 0 0 23 0 0 24 0 0 26 0 0 0 = Open.
C Closed.
P =Partially Open.
February 15, 1988
NOTES TO FIGURE 5.4-7 (Sheet 3 of 4)
MODE A - INITIATION OF RHR OPERATION Pressure Temperature Flow Location Fluid (Qsig} (OF} (ggm}a (lbLhr)
Reactor 24 Coolant 400 350 3800 1.69 x 106 25 II 407 350 3800 1.69 x 106 26 . 542 350 3800 1.69 x 10 6 93 27 " 541 350 992 0.44 x 106 31 II 539 142 992 0.44 x 10 6 29 II 496 350 2808 1.25 x 106 32 ti 496 296 3800 1.69 x 10 6 28 II 480 296 3690 1.64 x 106 19 Loop 4 " 404 296 1992 0.885 x 106 19 Loop 3 II 419 296 1698 0.755 x 106 18 34 II 400 350 3800 1.69 x 106 35 " 407 350 3800 1.69 x 106 3800 1.69 x 6 36 542 350 10 93 37 II 541 350 992 0.44 x 106 41 " 539 142 992 0.44 x 106 39 II 496 350 2808 1.25 x 106 42 II 496 296 3800 1.69 x 106 38 " 479 296 3910 1.74 x 106 6
20 Loop 1 II 404 296 1955 0.87 x 10 20 Loop 2 II 404 296 1955 0.87 x 106 a At reference conditions 350°F and 400 psig.
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 Flow Location Fluid (psig) (OF) (gpm)a (lb/hr)
Reactor 24 Coolant 0 140 3800 1.87 x 10 6 25 It 7 140 3800 1.87 x 106 26 II 156 140 3800 1.87 x 106 27 " 149 140 3800 1.87 x 106 31 " 129 120 3800 1.87 x 106 29 It 93 120 0 0 18 32 " 93 120 3800 1.87 x 106 28 " 75 120 3800 1.87 x 106 19 " 2 120 1900 0.935 x 106 18 34 " 0 140 3800 1.87 x 106 35 " 7 140 3800 1.87 x 106 36 II 156 140 3800 1.87 x 106 37 II 149 140 3800 1.87 x 106 93 41 II 129 122 3800 1.87 x 10 6 39 " 93 122 0 0 42 " 93 122 3800 1.87 x 106 38 " 75 122 3800 1.87 x 106 20 2 122 1900 0.935 x 10 6 a At reference conditions 140°F and 0 psig.
Amendment 93 February 1, 1995
400 R AL R R co DOWN 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- RHriHttiHiiiliHfmHtnsmmmllHBiillmml l)
<{
lU Ct I t I I 100 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 COMANCHE PEAK S. E.S.
FINAL SAFETY ANALYSIS REPORT Amendment 93 February 1, 1995 UNITS 1 and 2 Nonna 1 RHR Coo 1down FIGURE 5.4-8
BTP RSB 5-1 SINGLE TRAIN R COOL
.. ao I\
LL LJ w
0:: 350
)
f--
<(
er w
Q_
300 *-
2.
w I-f--
z
<( 2".50
_J 0
0 L) 0::
0 200 *-
f--
u
<(
w IDlll!mrumo1J!BllliDmn 0::
150 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 COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT Amendment 93 UNITS 1 AND 2 February 1, 1995 SINGLE TRAIN AHR COOLDOWN FIGURE 5.4-9
4026-185 SPRAY NOZZLE SAFETY NOZZLE UPPER HEAD LI FT ING TRUMM ION SHELL LOWER HEAD HEATER SUPPORT PLATE 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 1:1:1 It.-1..J"1'~tt---_J
. - - - - - -I ""~t~"'::-::-:-~~_J.l....J
_:;...*_ I ~~~::'::-::""~;;;;;J....J I q n '
It
!I I--S~A~G~R~~-

;'rj.-;--

I ! \
VESSEL SUPPORT 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
r RCP. # 3 SG.# 3 N 4
~
90°----- - 270°
-~
\:ACTOR a CONTAINMENT
~
<t_ SUPPORT R.C.P. # 4 EMBEDMENTS BY OTHERS R.CP. #I TYP. FOR EACH SUPPORT 3'-cl' 0° IS.G.# I S.G.#: 4 ft. REACTOR COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT AMENDMENT 8 UNITS 1 and 2 NOVEMBER 30, 1979 PLAN- REACTOR SUPPORTS TUSI UNIT =M: I FIGURE 5.4-IZA
r RCP.# 2 N --
~
~~
270°----- ~~~ ~-+----+-900
~- r
-~ &CONTA[
iREACTOR
~
i SUPPORT IRce{I
~
1800 S.G.# I iREACTOR COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT AMENDMENT 8 UNITS 1 and 2 NOVEMBER 30, 1979 PLAN-REACTOR SUPPORTS TUSI UNIT#2
5. 4- 12 El
/~
~o>~
-~
\lL ~*
i I ;-- HOT AND COLD STOPS l.j
~
ll UPPER LATERAL SUPPORT SNUBBERS
LOWER LATERAL SUPPORT PIPE COLUMHS
ONLY 2 SNUBBERS REQUIRED.
TO BE INSTALLED AT LOCATIONS 2 AND 4 AS SHOWN.
DIRECTION OF THERMAL EXPANSION t~OTE: COMANCHE PEAK S E S SNUBBERS ST ONLY ON UNIT 2. FINAL SAFETY ANALYSIS REPORT HAVE REMOVED FROM UNIT 1.
UNITS 1 AND 2 TYPICAL STEAM GENERATOR SUPPORTS Amendment 102
.. FIGURE 5.4-13
LEG T I E RODS CROSS-OVER LEG PIPE COLUMNS COMANCHE PEAK S. E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Reactor Coolant Pump Supports FIGURE 5
4- 14
3842-5 SEISMIC SUPPORTS PRESSURIZER SKIRT BEAR I NG PLATE GROUT 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.
COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Crossover Leg Amendment 66 Restraint January 15, 1988 FIGURE 5.4-16
THIS FIGURE HAS BEEN DELETED.
COMANCHE PEAK S.E.S.
FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Typical Crossover Leg Amendment 66 Vertical Run Restraint January 15, 1988 FIGURE 5 .4-17
THIS FIGURE HAS BEEN DELETED.
COMANCHE PEAK S.E.S.
FINAL SAFETYANALYSIS REPORT UNITS 1 and 2 Typical Hot Leg Pfpe Amendment 66 Whip Restraint January 15, 1988 FIGURE 5 .4-18
0.5 INCH GAP INSULATION ----.. (TYPICAL)
,*./ .....
/ ...
I .,
. ~ ..
. .. v Ill
.. *i; - .

tol
. . ~
REACTOR COOLANT PIPE COOLING AIR PASSAGE - - -
(TYPICAL)
AMENDMENT 61 PRIMARY SHIELD CONCRETE - - DECEMBER 19, 1986 (TYPICAL)
COMANCHE PEAK S.E.S.
NOTE: Hot and Cold Leg Restraint may be eliminated (See Section 5.4.14.2.5) FINAL SAFETY ANALYSIS REPORT UNITS 1 and 2 TYPICAL LATERAL RESTRAINTS FIGURE 5 . 4-19
Spring Return To Auto From Both Sides OPEN AUTO CLOSE MCB CONTACT CLOSES ABOVE HI FLOW SETPOINT CONTACT CLOSES BELOW LOW FLOW SETPOINT OPEN MOTOR OPERATED MOTOR OPERATED VALVE VALVE (MOV) (MOV}
FLOW SW INSTRUMENT MOV TRAIN NO NO A FIS-610 FCV -610 B FIS-611 FCV-611 COMANCHE PEAK S.E.S.
FNAL SAFETY ANALYSIS REPORT UNITS 1 and 2 Amendment 91 April. '15, 1994 RHR PUMP MINI-FLOW VALVE INTERLOCK FIGURE 5 . 4- 2 0

ML16180A444

Text

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