ML20024H221

From kanterella
Jump to navigation Jump to search
Rev 1 to Vogtle Electric Generating Plant Unit 1 Cycle 3 Core Operating Limits Rept.
ML20024H221
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 05/24/1991
From:
GEORGIA POWER CO.
To:
Shared Package
ML20024H220 List:
References
NUDOCS 9105300243
Download: ML20024H221 (10)


Text

1

. l i

i I

V0GTLE ELECTRIC GEf1ERATING PLANT (VEGP) UtilT 1 CYCLE 3 CORE OPERATING LIMITS REPORT  !

i REVISION 1  !

l MAY 1991 l

l 3

i i

'l i

-l l

1 t

i

-l l

1 i

t i

i f

l 9105300243 910524  ;

PDR ADOCK 05000424 P PDFs i

COLR for VEGP UNIT 1 CYCLE 3 1.0 CORE OPERATING LIMITS REPOST This Core Operating Limits Report (COLR) for VEGP UNIT 1 CYCLE 3 has been prepared in accordance with the requirements of Technical Specificat ion 6.8.1.6.

The Technical Specifications affected by this report are listed below:

3/4.1.1.1 SHUTDOWN MARGIN - MODES 1 and 2 3/4.1.1.2 SHUTDOWN MARGIN - MODES 3, 4 and 5 3/4.1.1.3 Moderator Temperature Coefficient 3/4.1.3.5 Shutdown Rod Insertion Limit 3/4.1.3.6 Control Rod Insertion Limits 3/4.2.1 Axial flux Difference 3/4.2.2 Heat Flux Hot Channel Factor - F;(Z) 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor - Fd I REV. 1 PAGE 1 of 9

-_ - . - .. - . - . - . . - . - .. - .~ _~ - - .. ..- -. . - -

9 COLR for VEGP UNIT 1 CYCLE 3 l 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified in Technical Specification 6.8.1.6 2.1 SHUTDOWN MARGlN - MODES 1 AND 2 (Specification 3/4.1.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.3% Ak/k.

2,2 SHUTDOWN MARGIN - MODES 3. 4 AND 5 (Specification 3/4.1.1.2) 2.2.1 The SHUTDOWN MARGlN shall be greater than or equal to the limits shown in Figures 1 and 2.

2.3 Moderator Temperature Coefficient (Specification 3/4.1.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

The BOL/AR0/HZP - MTC shall be less positive than +0.7 x 10

Ak/k/ F for power levels up to 70% RTP with a linear ramp to O Ak/k/ F at 100% RTP.

The E0L/AR0/RTP-MTC shall be less negative than -4.8 x 10

Ak/k/ F.

2.3.2 The MTC Surveillance limit is:

The 300 ppm /AR0/RTP-flTC should be less negative than or equal to -4.05 x 10' Ak/k/ F.

where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero THERMAL POWER E0L stands for End of Cycle Life RTP stands for RATED THERMAL POWER 2.4 Shutdown Rod Insertion Limit (Specification 3/4.1.3.5) 2.4.1 All shutdown rods shall be withdrawn to a position greater than or equal to 222 steps.

2.5 Control Rod Insertion Limits (Specification 3/4.1.3.6)

2. 5.-l . The control rod banks shall be limited in physical insertion as shown in Figure 3.

REV 1 PAGE 2 of 9

1

. . l

, l 1

COLR for VEGP UNIT 1 CYCLE 3 2.6 Axial Flux P.fference (Specification 3/4.2.1)

(CAOC methodology) 2.6.1 The AXIAL FLUX DIFFERENCE (AFD) target band is 45%, -5% for core average accumulated burnup s 3000 MWD /MTV.

2.6.2 The AFD target band is +3%, -12% for core average accumulated burnup > 3n00 MWD /MTV.

where: MWD /MTV stands for megawatt days /matric ton of initial uranium metal.

2.6.3 The AFD Acceptable Operation Limits are provided in Figure 4.

2.7 Heat Flux Hot Channel Factor - F o (Z) (Specification 3/4.2.2)

(F y methodology)

RTP Io 2.7.1 F,(Z) s

  • K(Z) for P > 0.5 P

RTP Fo (Z) s

  • K(Z) For P s 0.;

0.5 where

P = THERMAL POWER RATED THERMAL POWER RTP 2.7.2 F, = 2.30 2.7.3 K(Z) is provided in Figure 5.

REV. 1 PAGE 3 of 9

COLR for VEGP UNIT 1 CYCLE 3 L RTP 2.7.4 F,y = F,y * (1 + PF,y * (1-P))

RTP where: 1. F,y is less than or equal to 1.775 for all core planes containing Bank "D" control rods

2. For all unrodded core planes:

RTP F,, is less than or equal to 1.705 for core elevations below 3.7 ft.

RTP F,, is less than or equal to 1.660 for core elevations between 3.7 ft. and 8.1 ft.

RT P F,y is less than or equal to 1.765 for core elevations above 8.1 ft.

2.7.5 PF,y = 0.2 2.8 Nuclear Enthaley Rise Hot Channel Factor -I3 F( (Specification 3/4.2.3)

RTP FdsF, I

3 (1 + PF 33 + (1-P))

where: P = THERMAL POWER RATED THERMAL POWER RTP 2.8.1 F,3

= 1.55 2.8.2 PF3 , = 0.3

. w .no.u.a.a RFV. 1 PAGE 4 of 9

, COLR FOR VEGF Utai i CYCLE 3 M

d C

O N

\ 8 N

w 4

N w

M O W C C C ~

8' w C J ~

C 3 A n

>- C, at w WMN C V4 O U E E

<CWe 2LW e

eZ 3 DOC 5_ @ _=

-  : =

& " t;W C_ m"C W

< OE

/ C w ~ $E c

" 2 w C

+ b m 'e E_ cc E

'_ ca 2 " 2 6 C 2 =S 2 8 C

C e

n 2

C EE c-6 < N C 10

-C E - C =w C2 , C a=

<~ *- La C

>"2

'50 C

J hd c :

Gu w__ r C_

_ -- E.

ks c, _ - -

<CC C C.

&d Q C E

' &w C~ c 2 C C C -

w *

= .Ot O

8 C

c C

c C

C C

C- h e ~ - c e ,

().y?' Alt;1Devv.t4MOQ1hHS I

e*e-  : ,- 4 Q rrRIL , va <

n 8, CC;c roc VEGr UNIT 1 CYCLE 3

, n e.

'C W

N I

\ 8 h

s y c n n J

c::

  • O L

a W >- 2 e U

U < o. -

e

<CwC { w 2aw R g I-DCC ii5 - --^

\, -

~._ ..M O

- w :-

>* C 17

< 9E g --

>- _~ e -

2 -

c5 6

v-w *t-

.- 8- u .

e.

= c-0 w

u  ; $5 r-z z

C C

nE au

  1. C C O C E<*

wC-E C C

m E E.--

UO llE U ='

cr ., o w ' ' -

COC C b

'g e .- -

O E O =

C. E t m -

n .

w w 8 -

- S, C

w C

c C C C C C C C C C C C C W C d g M N (y/W%) NID8vW NMOO1nHS REV. 1

.' e' COLR F0E YEGP Ut417 1 CYCLE 3 I

l 222 -

~ ' ' ~ ~ ~ ' f (76.7,' 222) 7 -(26.7, 222)- '

220 E / \ \ /

200l l [ BANK B [ l g

180 I /i i / '

I

$ M l

@ 160 l (0,161) l l

[l l l [l h" l l l

/

l[B ANK C i i i / I r i i  ! i l/l I s i i I/! l t I 9 I i / i i i i / i I t /i I s i  ! /I i i  !

!' E I /  ! I l I / E a I i

/t BANx o I I i /t i E /1/*

I I  ! l / l i I

o I I I I /i  !  ! E E

!'/I (0, 46)

I l l

I l [

1/ I

]

I l

I l

I l E I/I I I I I E l l }

20 I I I i / 4 I I O

  • 60 80 100 O 20 40 RELATIVE POWER (PERCENT)

F IG'JRE 3 ROL EAra 1tiSERi]ON Llt'lis VER5US THERMAL POWER PAGE 7 of 9

COLR FOR VEGE OMT 1 CYCLE 3 140 120 UNACCEPTABLE 100 OPERATION

[2 ( 11,90) (11,90) o S

E 80 3l:

O c.

.,J E

c

' 60 5 ACCEPTABLE OPERATION c

w P-

< ( 31,50) (31,50) c l 40 l

l 20 0

50 -40 30 20 10 0 10 20 30 40 50 FLUX DIFFERENCE. 41 (percent)

FIGURE 4 A)l AL FLUX OlFFERENCE LIMITS A5 A FU*CTI0ti 0F RATED THERMAL FDJ; l REV. 1 PAGE 8 of 9

r CO:R F0E VEGF UNIT 1 CYCLE 3 i

l i

L l 1.50 l

l 1.25 I

1.00 l

R 0.75 i

0.50 CORE _._

HEIGHT K(Z) 0.000 1.000

6.000 1.000
  • 0.835 0,939 r, 0.25 -. ,

12,000 0,652 O

6.0 B.0 10.0 12.0 l 0 2.0 4.0 1

CORE HEIGHT (ft) 1 f:GUEE 5 K(?) - fiOUGLIZED F (2) 0 A5 A FUN:T:DN OF COP.E HEIGHT FAGE 9 of 9 REV. I 1

1.... . - - - - -. . . - . . . . . . , _ . . . . - - . . . . . - . . . . - . . -. - - . _ - . -- -.-. - . . , ,