ML20011D384

From kanterella
Jump to navigation Jump to search
Forwards Facility Steam Generator Tube Rupture Dose Info, Including Summary of Integral Mass Releases Used in Dose Assessment Model,Dose Projections for Postulated Analysis & marked-up FSAR Pages,Per 891107 Telcon W/Nrc
ML20011D384
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 12/08/1989
From: Tucker H
DUKE POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8912270096
Download: ML20011D384 (11)
v • d • e


Text

11 1

' Duke heer Conpary lia B hke PO tha 33198 lice Praident Charlotte, N C 28242 Nuclear 1%Iuction (7M)373 4531

(

t f

DUKE POWER December 8, 1989 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C.

20555

Subject:

Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 Steam Generator Tube Rupture Analysis Gentlement Please find attached the Catawba Nuclear Station Steam Generator Tube Rupture (SGTR) dose infermation requested per a November 7, 1989 telephone conversation with the NRC staff.

l t

Attachment I contains a summary of integral mass releases used in the i

dose assessment model. Figure 1 presents the dose analysis assumptions for

[

the hot Icg - Steam Generator flashing fraction. The assumptions in i

Figure 1 conservatively bound actual tube uncovering.

Attachment II contains updated dose projections for the postulated SGTR analysis and comparisons to the dose projections in the Catawba FSAR and my SGTR submittal dated August 24, 1988. The revised dose projections reflect changes made due to the relocation of the Catawba Unit 2 Steam Generator level taps. Additional information regarding the Unit 2 level tap relocation is provided in my December 28, 1988 submittal to the NRC.

Due to the relocation of the lower level tap-irom_438.4 inches to 333 inches, the Steam Generator level would reach 33% of the revised span before the old instrument would have come on scale. This allows the operator to identify the ruptured Steam Generator, close the Main Steam Isolation Valvo, and terminate the release of radioactivity approximately 10 minutes earlier than in the current safety analysis. The revised doses are below the regulatory limits in 10 CFR 100.

Attachment III contains a mark-up of Catawba FSAR Table 15.6.3-1 reflecting the updated dose projections.-These changes will be incorporated into the FSAR during a future update.

Very truly yours, f

11. B. Tucker JGT/5/ DOSE Attachment 8912270096 891208 r

g-PDR ADOCK 05000413 P

PDC-

c-

'o o.

'U. S. Nuclear Regulatory' Commission December 8, 1989 Page 2 xc Mr. S. D. Ebneter Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta St., NW, Suite 2900 Atlanta, Georgia 30323 Mr.-W. T. Orders NRC Resident Inspector Catawba Nuclear Station Dr. K. N, Jabbour Office ot Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 14H25 Washington, D. C. 20555 9

0 m

d r

w

>vm w-

3

.g>.

..y._

i.~

8 s

  • , ~.

p '< -'

c=,.

r n.

e

.,,,m">

L t

~

.e

--. s -

1 i

+

.']f ;

k g.

ATTAC19 TENT I~

-a-

+,

/

SM4ARY OF-INTEGRAL MASS RELEASES' VSED IN THE DOSE ASSESSMENT M,ODEL 4

g. - _,

+

A sy '

d'

-5

.p'..

'g' g

4 t

.f.

4 y_

f f, '

g j

d

.. pr'

(

-l pf--

y T

M

-N k

.y' w

.)**

t' r

t a

f ',

.k, Y

[

7 3

I Y 9 4

.k,

)

.,y ;

.yy M

4 h

.n e

I 0 ['l

._y g'44 i

4 5

. ~.

g 1

4 Y

n f

k 1

i n j' 4

L:

'c

, = =

N L

'3, g

{

.g y

t t

._-p

-*'b'

?

rk r

'p,

.c.

\\

4

.h'i.

b' '. s

,h[. 5 N \\

l,,,

L 91'9' xq.,

1 (y

upg, r:9

/;

r.

.v o.

+ e s

, +

. s.;.

~

.y _[.-

)

+

i I'9

/ [

I [

4

.. _p; 6

_g

(

J[.,5IT

'.,p','

-t-e)'.'.s.

,.x

]' L'

/d. 't' f.

g_

N

[

3

,c. f +L'. j :_ ' 9'.

1

.'an -

j p

ju s

s

s DESIGN BASIS SGTR SISMARY OF INTEGRAL MASS RELEASES USED IN THE DOSE ASSES $NENT N0 DEL STEAM RELEASED FROM THE INTACT STEAM GENERATOR 0-2 HOURS, TO CONDENSER 5.96E6

  • lbs TO ATMOSPHERE 3.4 E5 lba 2-8 HOURS l

TO ATMOSPHERE 1.13E6 lba STEAM RELEASED TROM RUPTURED STEAM GENERATOR 0-2 HOURS

,i l

TO CONDENSER 1.99E6

  • lba TO ATMOSPHERE 7.38E4 lba 2-8 HOURS TO ATMOSPHERE O ** lba i

1 y

LEAKAOF FROM PRIMARY TO SECONDARY THRO'JGH THE RUPTURED SGTR 0-2 HOURS 1.95ES lbm 2-8 HOURS 0 ** lba

  • Dose assessment model assumes condenser is not available af ter 30 minutes and all subsequent releases are to atmosphere.
    • Dose assessment model assumes the Steam Generator with the_ tube rupture is isolated within two hours.

f t

. - -. ~

FICURE 1 Steam Generator Flashing Fraction VS Time

.18 -

as used in the Does

.17 -

Analysis Model

.18 -

.15 -

.14 -

.13 -

.12 -

.11 -

.1 -

.0.

.08 -

h

.07 -

.06 -

.06 -

.04 -

.03 -

.02 -

.01 -

0 0

30 40

- 80 80 100 Time ( min )

i l

l l

1 r

l i

l Nsten Dose' Analysis model assumes ruptured tube remains uncovered from 30 minutes to 45 minutes. This assumption bounds the actual tube uncovery conservatively.

I

m

'-.h

,,1

,'p,,

N 1)*

i

' {'

9

,)k.N,.

i

-('m._

s

..s,o

\\.-.-

'3

,3

. o y

s s.

,-e 93 s.

s,

- t

.e

+ -

m.o, vo,

e,y

=..

4 c

N, I'f I

4 n

2 g

- g. <,

t

-u.

~ * ' '...

a

' ~

..4 s

r 1_

l 4'.

e

<s.

i 4

',F-4 s

+

s L

y,-

1 J

i w.

6 i

, ' j

.1 1

s' i

g-

, n P

ATTACIBtINT 11 4,

W-f' DOSE' PROJECTIONS FOR.THE P0$TU1ATED--

STRAM GENERATOR TUBE RUPTURE ANALYSIS ^

1 71 F

5 l

Y w

h 7

E f }

5 v

L J

' ?

g

g-
q,

2;'

s g

L c

)

't fr.'

1. :'

+

- ?- } %,

S i

-,,k

,,i.

e s

Y

\\

V;--

a:

y 7

s

'A.-

7. ' j_

. 4 < ' - _ -

m J

~ - f; p

I i"'i.

p y

4 1

)

)

.4<

b

' k~l _

y r

+

l

{

t.naf s

5 3' '.l 3

!,l _ -

  1. 1 g

~.

t t

u

i :c m1

.g

'e I

'_l

,. I 4

+-

y' n 4

2 'M

~

)

&i

^

.~[__.

>t f

..g-k_

3

"._'Zi

'g..

,'p-.

l

-- y m_

,755 -

R_1

_..__.J'i_.

4,,___-

,ffa.

'@.z 1

s 4

s

.c.

3 ;

,){ t

.g, 5 af. 7 4

i e

=3

+:d.l'. ' +

.=: ( _

e 4

s r

t

._wJ. _. :

., ~'

s k

f.

-:. 7,.

1 4

y7, *

~':w-N, 1

e, ;

.acq 3'

4 i

i s

. ~i..

.,e=

,.)g

+

r f..i.,, _:

,A

s c-1 4

DESIGN BASIS SGTR t

DOSE PROJECTIONS FOR THE POSTULATED STEAM GENERATOR TUBE RUPTURE ANALYSIS l

1 DOSES ~(REM) i 1988 1988 SGTR UPDATED CASE 1 (NO IUDINE SPIKE)

FSAR SUBMITTAL SUBMITTAL EXCLUSION AREA BOUNDARY WHOLE BODY 6.4E-1 3.1E-1 3.1E-1 THYROID.

1.5 1.5 1.7 5

LOW POPULATION ZONE WHOLE BODY 2.1E-2 1.0E-2 1.0E-2 THYROID 8.8E-2 5.0E-2 5.6E-2 CASE 2 (WITH PRE-EXISTING IODINE SPIKE)

EXCLUSION AREA-BOUNDARY WHOLE BODY 7.1E-1 3.1E-1 3.1E-1 THYROID 4.4E+1 9.1E+1 1.0E+2 LOW POPULATION' ZONE WHOLE BODY 2.4E-2 1.0E-2 1.0E THYROID 1.5 3.0 3.3 CASE 3 (WITH COINCIDENT IODINE EXCLUSION AREA BOUNDARY WHOLE BODY l

3.1E-1 3.1E-1 THYROID 1

2.6E+1 2.7E+1 LOW POPULATION ZONE WHOLE BODY JE-2 1.0E-2 1.0E-2 THYROID 4.6E-1 9.0E-1 9.5E-1 1

i I

\\;

s-t L

i C

P 4

ATTACIMENT III FSAR MARK-UPS e

k 5

w

Cm The following assumptions and parameters are used to calculate the activity release and offsite dose for the postulated steam generator tube rupture:

1.

Prior to the accident, an equilibrium activity of fission products exists.

in the primary and secondary system caused by primary to secondary leakage in the steam generators.

gy 2.

The accident is initiated by the rupture f a steam generator tube, which results in the transfer of approximatelytIUt;E S pounds of reactor coolant into the shell side of the defective steam generator.

3.

Offsite power is lost.

4.

The primary to secondary leakage is 0.653 gal / min in the nondefective steam generators.

5.

The steam release from the defective steam generator terminates in 30 minutes.

The release from the nondefective steam generators terminates in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

6.

All noble gases which leak to the secondary side are released.-

7.

The steam generator iodine partition factor is 0.1 during the accident.

8.

For Case 1, the primary coolant concentration is at the equilibrium Technical Specification limit.

9.

For Case 2, the primary coolant concentration is at the maximum permitted t

for full power operation.

t 10.

For Case, 3, the iodine spike occurs at the onset of the. accident and continues for the duration of the accident.

The iodine concentrations are determined by increasing the equilibrium appearance rate by 500, 11.

Other assumptions are listed in Table 15.6.3-2.

Based on the foregoing model, the thyroid and whole body doses are calculated at the exclusion area boundary and the low population zone.

The results are presented in Table 15.6.3-2.

The doses at these distances are below the regulatory limits of the 25 rem whole body and 300 rem thyroid doses established in 10 CFR 100.

15.6.4 SPECTRUM OF BWR STEAM SYSTEM PIPING FAILURES OUTSIDE CONTAINMENT This section is not applicable to Catawba.

l 15.6.5 LOSS-OF-COOLANT ACCIDENTS 15.6.5.1 Identification of Causes and Accident-Description Acceptance Criteria and Frecuency Classification A loss-of-coolant accident (LOCA) is the result of a pipe rupture of the.

reactor coolant system (RCS) pressure boundary.

For the analyses presented l

15.6-8 t

b

.j Table 15.6.3-2 (Page 1)

Parameters for Postulated Steam Generator Tube Rupture Accident Analysis 2

{M C

e 1.

Data and assumptions used to estimate radioactive source from postulated

J L

accidents a.

Power level (MWt) 3565.

M b.

Percent of fuel defected 1.

.]

c.

Steam Generator tube leak rate prior 1.

M q

to and during accident (gpm) i.

d.

Offsite power Not available M

2.

Data and assumptions used to estimate I

activity released i

O.ol Non-flashi flow a.

Iodine partition factor for initial Jhi.

M 1

steam release from defective steam i., () pia;hing ()ow generator

_1 b.

Iodine partition factor for steam

.M O. 01 release from nondefective steam generators Q

c.

Iodine partition factorM n ;ac n;;r

'>< 0. ) 2.

M

a.. s - - --.wa
d. iAd$tlI'flAEing 5tcom oi6

]

e X.

Steam release from defective steam SM 73,7 7M X

1 generator (1b)

.(. X.

Steam release from three nondefective steam generators (1bs)

(0-2 hr)

N (2-8 hr)

@ 1,130,000.

g X.

Reactor coolant released to the W 1%375 %

defective steam generator (lbs) l 3.

Dispersion data l

a.

Distance to exclusion area 762.

K boundary (m) l b.

Distance to low population zone (m) 6096.

$99EC l

~

.~

e Table 15.6.3-2 (Page 2)

Parameters for Postulated Steam Generator i

Tube Rupture Accident Analysis p.- Q:'e Ra gh-X/Q at exclusion area boundary (sec/m2) 5.5E-04 h

c.

(0-2 hr)

M d.

X/Q at low population zone (sec/m3) 1.8E-05 (0-8 hr) d>&TQ.

l l

4.

Dose data l

i a.

Method of dose calculations Regulatory Guide M

1. 4 t

b.

Dose conversion assumptions Regulatory Guides k

1.4, 1.109 c.

Doses (Rem)

Case 1 (No iodine spike)

Exclusion Area Boundary I

Whole Body 6 M 3.\\E-l Thyroid

--l rS-

). f-Low. Population Zone Whole Body-2.1E-2.. i. 0 E Thyroid

.00 2-

5. 6 E
  • Case 2 (With pre existing iodine spike)

Exclusion area boundary Whole' body

-7.10:1-31E-I Thyroid 4.4E+1

\\.0 Ett Low population zone Whole body

- 2,4: 4 1.0 E-7 Thyroid

--l-fr-KV Case 3 (With coincident iodine spike)

Exclusion area boundary Whole body

~7.GE 31E-I Thyroid

-4,2E 1 2.7 Et l Low population zone Whole body 4-SE-2 10E-1 Thyroid-

-4 GE-1

% 5E- \\

!

Retrieved from "https://kanterella.com/w/index.php?title=ML20011D384&oldid=4640520"