ML20012E015

From kanterella
Jump to navigation Jump to search
Cycle 1 Core Operating Limits Rept
ML20012E015
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 03/22/1990
From:
GEORGIA POWER CO.
To:
Shared Package
ML20012E012 List:
References
NUDOCS 9003290217
Download: ML20012E015 (10)


Text

o ci i

ENCLOSURE 4 FOR UNIT 2 L

l-i-

)

V0GTLE ELECTRIC GENERATING PLANT (VEGP) UNIT 2 CYCLE 1 CORE OPERATING LIMITS REPORT l

l 9003290217 900322 PDR ADOCK 05000424

. P -

PDC l-l 1

l

_]

d

' b i

i COLk for VEGP UNIT 2 CYCLE 1 i

1.0 CORE OPERATING LIMITS REPORT i

This Core Operating Limits Report (COLR) for VEGP UNIT 2 CYCLE 1 has been prepared in accordance with the requirements of Technical Specification 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 j

3/4.1.1.3 Moderator Temperature Coefficient 3/4.1.3.5 Shutdown Rod Insertion Limit 1

3/4.1.3.6 Control Rod Insertion Limits 3/4.2.1 Axial Flux Difference 1

3/4.2.2 Heat Flux Hot Channel Factor - F (Z) i Q

N 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor - FAH t

i i

b

(

1 i

L

-m

-n

's e

w

l'f _: + ;

1 7 w m

s y'

4

]

l COLR for VEGP UNIT 2 CYCLE 1 2.0 OPERATING 141111 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 L2.1 SHUTDOWN MARGIN - MODES 1 A@_2_(Specification 3/4.1.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.3% A k/k.

2.2-SHUTDOWN MARGIN - MODES 3. 4 AND 5 (Specification 3/4.1.1.2)

. 2.2.1 The SHt)TDOWN MARGIN shall be greater than or equal to the limits shown in Figures 1 and 2.

2.3 Moderator Temoerature 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 oak /kOF.

iiie' E0L/AR0/RTP-MTC shall be less negative than -4.0 x 10-4 6 k/k/0F, L

l 2.3.2-The MTC Surveillance limit is:

e The 300 ppm /AR0/RTP-MTC should be less negative than or equal to

-3.1 x 10-4 A k/k/0F.

L where:

BOL stands for Beginning of Cycle Life L

ARO stands for All Rods Out L

HZP stands for Hot Zero THERMAL POWER E0L stands for End of Cycle Life RTP stands for RATE 0' THERMAL POWER L

l:

t..

l

+-----.

m s

mm -

.n i

yt j

i COLR for VEGP UNIT 2-CYCLE 1 2 ^. 4 Shutdown Rod Insertion Limit (Specification 3/4.1.3.5) 2.4.1 The 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) 2.5.1 The control rod banks shall be limited in physical insertion as shown in Figure 3.

t 2.6 Axial Flux Difference (Specification 3/4.2.1) i (CAOC methodology) 2.6.1 The AXIAL FLUX DIFFERENCE (AFD) target band is +5%, -5% for core average accumulated burnup <3000' MWD /MTV.

2.6.2 The AFD target band is +3%, -12% for core average accumulated burnup >3000 MWD /MTV.

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

2.6.3

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

j l

L 2.7 Heat Flux Hot Channel Factor - Fg(Z) (Specification 3/4.2.2)

(Fxy methodology)

RTP-l-

FQ F (Z) s

  • K(Z) for P > 0.5 2.7.1 Q

P RTP F (Z) s

  • K(Z) for P s 0.5 Q

0.5 l

THERMAL POWER L

where: P

=

RATED THERMAL POWER RTP 2.7.2 FQ 2.30

=

l'

b; 9 4:

i k

COLR for VEGP UNIT 2 CYCLE 1 2.7~3 K(Z) is provided in Figure 5.

L' RTP Fxy - Fxy * (1 + PFxy * (1-P))

RTP-

2.7.4 where

1.

Fxy is less than or equal to 1.71 for all core planes containing Bank."D" control rods 2'.

For all unrodded core planes:

l-L RTP Fxy is-less than or equal to 1.54 for core elevations up to and including 5.5 ft.

l L

RTP l

Fyy is less than or equal to 1.62 for core p

elevations above 5.5 ft.

1 9

2.7.5 PFxy - 0.2

{

1 2.8 Nuclear Enthalov Rise Hot Channel Factor - FfH (Specification 3/4.2.3) i l

l-RTP i

l 2.8.1 FjHsF6H * (1 + PFA H * (1-P))

where:

P THERMAL POWER RATED THERMAL POWER RTP 2.8.2 F3H 1.55

=

l 2.8.3 PFAH 0.3

=

i l

.* L p

l-i

. UNIT 2 l.

5.00 i

I l

4.00 l

ACCEPTABLE OPERATING y

REGION 32 n

(2500,3.0) 8.

i d

3.00

'n f

l

~

REQUIRED O

h tr SHUTDOWN j

MARGIN

.h l

z e

3 2.00 5

ACCEPTABl..E 5

OPERATING REGION q

,1.3) 1.00 0.00 0

400' 800 1200 1600 2000 2400 RCS BORON CONCENTRATION (ppm) i FIGURE 1 UNIT 2 REQUIRED SHUTDOWN MARGIN FOR MODES 3 AND 4 (MODE 4 WITH AT LEAST ONE REACTOR COOLANT PUMP RUNNING)

..=

~

.y UNIT 2 7.00 6.00 ACCEPTABLE OPERATING I

(2500,5.0) 5.00 2

REQUIRED

.12 SHUTDOWN y

MA N

g

~

4.00 z

w a

5i' Z

3.00 o

3 UNACCEPATABLE cz-OPERATING F

U S

REGION m

v) 2.00 Q

m m

1.00 (450,1.0) 0.00 0

400 800 1200 1600 2000 2400 RCS BORON CONCENTRATION (ppm)

FIGURE 2 UNIT 2 REQUIRED SHUTDOWN MARGIN FOR MODE.5 (MODE 4 WITH NO REACTOR COOLANT PUMPS RUNNING)

c

=

COLR FOR VEGP UNIT 2 CYCLE 1 i

r-p-7q 200,

I.- B

/

180 g

E/

/

E

@ 160 l (0,161)

/

M 140 L

/

/

E

  • u

/

/

E y

E

/

/

E 100 g

E

/

/

E l*lE

[

[

BANK D l

E

/

/

E 60 g

B/

/.

B

[(0,46)

[

f l

E

/

B 20 2

B

/

E o bem$Yd$$dmummmmmmmmanummmmmmmmmmad 0

20 40 60 80 100 RELATIVE POWER (PERCENT)

FIGURE 3 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER

,e m=

COLR.FOR VEGP< UNIT 2 CYCLE 1 140 i

-120-i

-j

.jon UNACCEPTABLE OPERATION i

( 11,90)

(11,90) 80

/

3 a.

'N.

f 1

E l

Ey 60 ACCEPTABLE OPERATION r

O f

n L

=y.

( 31, 50)

(31,50) p-1 40 20 l-l' e

0

=

50

-40

-30

-20

-10 0

10 20 30 40 50~

FLUX DIFFERENCE, Al(percent)

L FIGURE 4 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER

.a.

Q

<g COLR FOR VEGP-. UNIT 2 CYCLE 1 s.-

+;

1.50 1.25-1.00

-mummmmmmmmmmmeunummmmmmmmmmme 7

./ 8 -

0.75

.3x

e'

,:s.

0.50:

CORE HEIGHT K(Z) 0.000 =

1.000 6.000 1.000 0.25 10.835 0.939 12.000 0.652 0

0 2.0 4.0 6.0 8.0 10.0 12.0 CORE HEIGHT (ft)

FIGURE 5 K(Z) - NORMALIZED F (Z) AS A FUNCTION OF CORE HEIGHT Q

.... _.. -