ML20207N189

From kanterella
Jump to navigation Jump to search
Forwards Addl Info to Support Request to Amend Tech Specs to Allow Refueling & Operation W/Vantage 5 Fuel.Graphics Illustrating Reactor Core Safety Limits W/Three Loops in Operation & Moderator Temp Coefficient Vs Power Level Encl
ML20207N189
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 10/13/1988
From: Bradham O
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8810190014
Download: ML20207N189 (8)


Text

-__ -______ _ ___ _ _ _

Rcergn m s oss con,ser e7 m

gin, ige sc 2ns Nuci.ar operation.

SCE&G

' = " "

October 13, 1988 i

Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Virgil C. Summer Nuclear Station i

Docket No. 50/395 Operating License No. NPF-12 Technical Specifications Change VANTAGE 5 fuel Gentlemen:

In support of the review of the South Carolina Electric & Gas Ccmpany request to amend the Technical Specifications to allow refueling and operating with VANTAGE 5 fuel, the Staff has requested additional copies of the following figures from Technical Specifications.

Figures: 2.1-1 3.2-2 3.1-0 3.9-1 3.1-3 3.9-2 3.2-1 These figures are attached to this letter, and should you have any questions concerning this matter, please call at your convenience.

Very truly yours k

A

/

0. S. Bradham i

MOB /OSB: led l

Attachments l

{

c:

D. A. Nauman/J. G. Connelly, Jr./0. W. Oixon, Jr./T. C. Nichols, Jr.

4 E. C. Roberts W. A. Williams, Jr.

R. L. Prevatte Regional Administrator J. B. Knotts, Jr.

I J. J. Hayes, Jr.

H. G. Shealy General Managers M. D. Blue

(

C. A. Price /R. M. Campbell, Jr.

L. R. Cartin i

R. 8. Clary NSRC K. E. Hodland RTS (TSP 880013) ok J. C. Snelson NPCF G. O. Percival File (813.20) 8910190014 gggog3 DR ADOCK 05000395 p

PDC

p 670 665 UNACCEPTABLE CPERATION

}

660

- (2% 657) 655 i ins 650

- (2%.648) 645 2d"

[

^

(

estA W

640 N

-g E

g 635 N

Nm (96%,63 f) i t

(2 %.630) 2250 2

630 pSr4 g

l N

=

625 m

s

(

a

{

-g 3

\\

s 620 I -

\\

20M

\\

i h

l PSIA (98 %.620)

Q I

5 615

- (2 % 613)

{

' N I

\\ \\

(f 20%,607) l g

w 610 3

605

\\

k 8

s 1775 N

~

g g

600 N

estA y

b 595 I' '"' #"I l0 %")

I 5

N*

l 590 g\\

'\\

I.

585 l

^ %

if20%,586) 580

-L-D' 575 ACCEPTABLE OPERATION (116%,577)

[

570 i

i i i

i i !

! (f20%,574) 0 10 20 30 40 50 60 70 80 90 100 110 120 POWER (PERCENT)

)

When opera ting in the reduced RTP region of Technical l

Specification 3.2.3 (Figure 3.2 2) the restrictedpower levelmust be co'sidered 100*4 RTP for this figure.

Figure 2.f.f Reactor Core Safety Limit. Three loops in Operation i

Summer. Unit 1 22

I i

^9 l

i.

g

.8 h

5

'7 UNACCEPTABLE i

OPERATION ACCEPTABLE I

.6

\\

OPERATION g

T s

\\

l' I

\\

g

.3 s

X l

\\

t

.1 0

O 10 20 30 40 50 60 70 80 90 100

% OF RATED THERMAL POWER FIGURE 3.10 MODERATOR TEMPERATURE COEFFICIENT VS POWER LEVEL Summer UNtT1 3/4 1 5a

0 0

5,

_~

2 9,

0

- 0

- _ - _ - _ - _j 3,

__.[-

2 1

_. p 0

0 1,

2

- M E

LB A

3 T

0 I-0 P

E E

D 9,

C S

pO C

1 M

A 4

Jt U

5 D

E 0

_ _ - O 0

M 7

y m

1

)

N p

_ I __

I 0 p G

0

(

_ gr_

R 5, N A)

M5 O

1 I

T D

N A

3 N

1 0 T WA R

1. O 0

3 N

D 4, 3,

E E

SD

}s~_.-

R T 3 1

C U U N

S G HE O

I C

DO F

0 E

- _ - /

0 N R (M 1, O 1

8 I

1 R

Q U

/

O 8

E R

/ _ -

S 0 C 0 R 9

7_/

S E &

L B

0 A 4, 0

j 7

T 3 P 5 E E C D C

A O A

T

/

0 0

4 5

3 E

5 B5 E

L D

l

_ - _ O AE 5

0 T D E

0 A

P O D

3 t

t cA O

t c

A A

T

- - 0 0

1 5

0 7

5 6

5 S

5 4

5 3

5 2

5 1

6 5

4 3

2 1

]o.:y5k2 c

z;y mE

)

  1. a
  • Ez.

W*

i.

l

i 1.2 1.1 1

+

.9

~~

i

.8 I

.7 n~4 i

uo

.6

[

W I

15

,4 L

T F

W

.3 Core Heicht (ft)

M

.2 0.0 1.0 F

6.0 1.0 12.0 0.925

.1 L

t i

0 l

0 1

2 3

4 5

6 7

8 9

10 11 12 BOT 10M TOP OF CORE HEIGHT, FT.

op FUEL FUEL i

i FIGURE 3.21 l

l K(z) NORMAll2ED Fo(1) AS A FUNCTION OF CORE HEIGHT 1

I l

F i

l l

I r

i l

i I

)

l l

I Summer UNIT 1 3/4 2 7 l

MEASUREMENT UNCERTAINTIES OF 2.1% FOR FLOW AND 4.0% FOR INCORE MEASUREMENT OF FN.ig ARE INCLUDED IN THIS FIGURE 38 ACCEPTABLE UNACCEPTABLE OPERA *10N REGION OPERATION REGION l

36 I

i 34 w

_I g 32

[

I w

I E

e EO a

N R

O (1.00,28.95) m (1.00,.18.66) l 28

,[ [,

(1.00,28.37)

'(-

SEE NOTE (1.00,28.08) y 3,

(1.00,27.79) i Sn s.r.

(1.00,27.50) a i

1 26 24

.9

.95 1

1.05 1.1 4

R = F%W1.56 [1.0 + 0.3(1.0 P))

FIGURE 3.2 2 RCS TOTAL FLOW RATE VS R THREE LOOP OPERATION P:OTI: When eserateg in thes region, the tostrioed power leweis shaW cosadored to be 100% of rated thermal power (RTP)for f agure Lt.1 SUMMER UNIT 1 3/4210

30 27.5

j 25 MO 3

22.5 Ia j

20 e

17.5 f

15 7

AC:!PTABLE" i

/

s 12.5 f

u s

10 2

4 r

W UNACCEPTABLE 7.5

/

g

\\

l/

a

~

5 2.5 I

O 2

2.25 2.5 2.75 3

3.25 3.5 3.75 4

4.25 FUEL ASSEMBLYINITIAL ENRICHMENT,WT.% U 235 FIGURE 3.91 MINIMUM REQUIRED FUEL ASSEMBLY EXPOSURE A5 A FUNCTION OF INIT!AL EN RICHMENT TO PERMIT STORAGE IN REGION 2

$UMM ER - U NIT 1 3/4915

45 42.5 i

40 3

37.5 o

r Mo 35 B

/

I 32.5

/

d l

/

ACC[H

(

30 A

i 27.5 x

f w

25

}

s 22.5 t N ^C" "A

20 I

f o

V 17.5 15 12.5 f

/

d 10 l

7.5

=

5

/

2.5 i

0 1.25 1.5 1.75 2

2.25 2.5 2.75 3

3.25 3.5 3.75 4

4.25 i

FUEL ASSEMBLYINITIAL ENRICHMENT,WT.% U 235 I

i FIGU RE 3 9-2 MINIMUM REQUIRED FU!L ASSEMBLY EXPOSURE A5 A FUNCTION I

05 INITIAL ENRfCHMENT TO PERMIT STORAGE IN REGION 3 i

i

?

i SUMMER UNIT 1 3/4916 i

-