ML20059C873

From kanterella
Jump to navigation Jump to search
Changes to ODCM & Process Control Manual
ML20059C873
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 08/30/1990
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20059C867 List:
References
PROC-900830, NUDOCS 9009050399
Download: ML20059C873 (5)


Text

f.

?

I.

t i

t. ;

I t

l-l CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL AND PROCESS CONTROL MANUAL i-t 1

I 9009050399 900830 ADOCK 0500 3 Page 22 of 23

{DR

,^.

C.. . ' , . m. .

< i  ::i/ '

. g q :' aa p :,:

p g,-

7 .

4; , '

e g .1- +

s,-_ ..

2 . . , . o. -

,' \  ;

jS~ j

  1. j.'s  ; .h . ,

h , ', 3 .i

, n: , -

.)

_! 0 [, ,

+

H '

y * 'l

h. .I

(

.q. . .

'No' changes were made to the.0ffsite Dose Calculation Manual.or the Process

p Control-Program during theLfirst six months of-1990.

w..

] ,

';I'f '

s 3 s , ,

e.;

!.t , "

p 2 1 9, . ,

J, a:

+

. l v $

g r W

( '. .

88, t:

i') .

it o

t' i

4

.r i.

l i

s

[

'(i u I, a i

b' rv -

1

.7 Page 23 of 23 w ,

a

'-.L a -. 2

- ; , . . . . ~ . , . ' -,_ n , . . . . , , ,, _ . , , , _ . . _ . . , . _ . , . . , . _ _ , , _ , _ , , . . . , _ , , , , . _ , . .

. , ~ , n .

+

. 1

{

t 4 ,

O f i

a i

ATTACHMENT 2 Page 1 of 3

e#y ., - H .-,2l gc;- . .

4

,+3 4 ;

r ..- ,.

x

.,r.

- r. v eg

y. , ,  ; , o f g.

v, .*;,f , , ,

i I' I i .) $

f 'h': * ,

,'[..37a[p 4 , , . , .

+ _: 6...i '

L <t '

.w. s h, -[9y%.j y:k h , ";<

t.

' ' q 6:.l '

q i .' , ~i

,r ,

.,1 o? r. < -y.5 i- t :3,

.,4 - !

8 ,, y .

m ..

s-~ . c, o

3--

a 1 c

>q s

m ,

c w;pg ,

l 7,

-- t

.. 1 j

i

\.

-)

1 F , . l e

I

" I.-l;

.i j

i: .' < .t L;* .

.l

...s.  :

~ , i r, . .

u ,

y;, s U; a . -

a it 4

, . REVISED DESCRIPTION OF THE-UNPLANNED: RELEASES ~ ,

.-l

-TO 't

n. _ ' o . -'

.g

. ' UNRESTRICTED-AREAS 7 .- it 1 .DURING THE THIRD AND; ci

?f+

= FOURTH QUARTERS OF- 1 o

1989 .i ,

/ i-!r 'l m- ..

> 4;7:

o --

F, . '

q1

'y..

'- s!

bu (c

m ,

.g <

&, cl o

) .

.j' '

31.^. .I s'.

-r t.'.

l .,<

-. ;J p- q Ej.

3 s .. j f f' . ,)

.: i w' i  :}

m. .
i,

,a k I h  ?

.1 U , .,

,i

- L k

E.["

-f m

?

1 x , Pat,e 2 of 3 j r

s

__A .'

,- j ".: .,

I."'-'I ,

..,+.,~m-_,._.~,..,,.._,.. .....~..-.mm. .

_..r 4 4 . m . . ,. , . ,.-...:4.*

'{

7 t .,  :.

4 -

i

  • i o  !

There were four unplanned releases during the second half of 1989:

1. On November 10, 1989, Arkansas Nuclear One, Unit I tripped, when an Instrument and Control Technician performing a surveillance test inadvertently grounded the power supVfy for the "B" reactor protection system cabinet creating a transient causing a high pressure reactor i scram. During this trip the main steam safety valves 'tifted, releasing j steam from the secondary plant system. The secondary system contains a small amount of tritium, some of which was released when tn main steam <

safety valves lifted. This release produced a total body .se of i 1.73*10 8 mrem which represents approximately 2.31x10 2% of the  ;

Technical Specification 3.25.2.3 A.1) limit of 7.5 mrem per calendar quarter. No adverse consequences are expected.

2. On November 15, 1989, Arkansas Nuclear One, Unit 1 tripped when the  ;

inadvertent closure of a main feedwater isolation valve resulted in 1 automatic actuation of the reactor protection system on high reactor coolant system pressure. During this trip the main steam safety valves I lifted, releasing steam from the secondary plant system. The secondary system contains a small' amount of tritium, some of which was released  ;

when the main steam safety valves lifted. This release produced a total body dose of 1.73*10.a mrem which represents approximately l 2.31*10 2% of the Technical Specification 3.25.2.3 A.1) limit of 7.5 mrem per calendar quaiter. No adverse consequences are expected.

3. On December 28, 1989, Arkansas Nuclear One, Unit 1, an automatic reactor trip and actuation of the Emergency feedwater System occurred as a result of the loss of all main feedwater flow caused by the inadvertent tripping of a main feedwater pump. During this trip the main steam safety and the Emergency Feedwater Turbine Exhaust valves lifted to relieve system pressure, releasing steam from the secondary plant system. The secondary system contains a small amount of tritium that was released. This release produced a total body dose of 2.94*10 8 mrem. This is approximately 3.92*10 7% of the Technical Specification 3.25.2.3 A.1) limit of 7.5 mrem per calendar quarter. No adverse consequences are expected.
4. On December 31, 1989, Arkansas Nuclear One, Unit 2, a reactor trip occurred when 'B' Steam Generator water level reached a high level setpoint, and the Reactor Protective System generated a reactor trip  !

signal. During this trip, steam from the secondary plant system was released via the emergency feedwater turbine exhaust. The release contained tritium and produced a total body dose of 2.82*10 8 mrerr..

This is approximately 3.76*10 7% of the Technical Specification 3.11.2.3a limit of 7.5 mrem per calendar quarter. No adverse consequences are expected, f

l Page 3 of 3 1