05000324/LER-1981-063-03, /03L-0:on 810703,reactor Coolant Activity Exceeded Tech Spec During Reactor Startup.Caused by Scram W/Increase in Coolant Fission Product Inventory Originating from Leaking Fuel Element.Reactor Power Increased

From kanterella
(Redirected from ML20009H485)
Jump to navigation Jump to search
/03L-0:on 810703,reactor Coolant Activity Exceeded Tech Spec During Reactor Startup.Caused by Scram W/Increase in Coolant Fission Product Inventory Originating from Leaking Fuel Element.Reactor Power Increased
ML20009H485
Person / Time
Site: Brunswick 
Issue date: 07/28/1981
From: Pastva M
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20009H481 List:
References
LER-81-063-03L, LER-81-63-3L, NUDOCS 8108100173
Download: ML20009H485 (5)
v • d • e


LER-1981-063, /03L-0:on 810703,reactor Coolant Activity Exceeded Tech Spec During Reactor Startup.Caused by Scram W/Increase in Coolant Fission Product Inventory Originating from Leaking Fuel Element.Reactor Power Increased
Event date:
Report date:
3241981063R03 - NRC Website
v • d • e

text

NRC FORM 366 U. S. NUCLE AR REGULATORY COMMISSION (7 77)g*

LICENSEE EVENT REPORT CONTROL BLOCK: l l

l l

l l

l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIEN) 1 6

lo ltl l N l C l B l E l P l 2 l@l 0 l 0 l - l 0 l 0 l 0 l 0 l 0 l-l0 l 0 l@l 4 l 1l ll 1l 1l@l l

l@

7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE JO

$7 CAT 58 CON'T lolil S$R I b hl 0 l 5 l 0 l-l 0 l 3 l 2 l4 @] 0 l 7 l0 l3 l 8 l1 l@l0 l 712 l 818 l1 l@

7 8

60 61 DOCKET NUMBER 68 69 EV8NT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND F ROBABLE CONSEQUENCES h 10 l 2 l l During a reactor startup following a reactor scram from 9% power on July 2. 1981.

I l reactor coolant activity exceeded the technical specification limit of 0.2 pCi/gm.

l o 3 dose equivalent for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, with the highest recorded activity at.2589 pCi/gm.l [o l4 l l Iiy l This event did not affect the health or safety of the public.

l o s 10 l6 l l l

I O l 71 1 I

l 0 l81 l Technical Specifications 3.4.5, 6.9.1.9b i

80 7

8 9 SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE g

l P l B l@ {@ {@ l Zl Zl Zl Zl Zl Zl@ l Z l@ y @

7 8

9 to 11 12 13 18 19 20 SEQUENTI AL OCCURRENCE REPORT REVISION LE R /RO EVENT YEAR REPORT NO.

COO 6 TYPE N O.

@ gU l 8l 1l l_l l0 l6 3 l y

l0l3l lL l

[-J W

RE

_ 21 22 23 24 26 27 N

M JO 31 32 AK N AC 0 ON PL NT MET HOURS SB B FOR B.

SUPPLIE V N F CTUREH lxJ@LzJ@

Lzj@

l zi@

l0Iol010I LN_J@

LtJ@

12_]@

lzI9I9I9l@

33 34 36 36 3/

40 41 42 s1 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h was a result of the scrnm uirh n ciih a n n ii nn e-innennco in cool;ht l1lOllThe hich coolant activity I

l1 l1[ lfission product inventory originatinn from a leakinc fuel element.

Ronernr nnune [was increased and the iodine act.ivity returned to within specifications.

The Unit No.12 i 2 i 3 l fuel bundles wil_1 be sipped during the next refueling otitage and ti:e leaking bundles l

l t 4 l removed from the core.

80 7

8 9 STA S

% POWE R OTHER STATUS Dis OV RY DISCOVERY DESCRIPTION NA l (A_j@l Coolant Sampling l

l115 l W@ l0 l 0 l1 l@l ACTIVITY CO TENT RELEASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE NA l l

NA l

, l 1 l G l d @ W@l 7

8 9 10 11 44 45 80 PERSONNEL E XPOSUR:S NUVBER TYPE

DESCRIPTION

NA l

l0l0l0l@ W @l 1 7 IES PERSONNEL INJU DESCRIPTION @

NUMBER NA l

l0l0l0l@l i a 80 7

9 11 12 LOSS OF OR DAMAGE TO FACILITY h TYPE DE SCRiPTION v

NA l

W lZl@l 80 7

8 9 10 PUUt ICIT Y NRC USE ONLY ISSUE D

DESCRIPTION

NA l

lllll1Illllll*4 M Whl 68

84 i

8108100173 810728 M. J. Pastva, Jr.

919-457-9521 o

PDR ADOCK 05000324 "

p 2L R @ '

r 3.-

Off-Gas Analysis Prior to this incident, the following Unit No. 2 steam jet air ejector (SJAE) off gas level was measured:

Date Reactor Power %

Off-Gas pCi/sec at SJAF 6/18/81 96%

2.40943 E 4 6/19/81 96%

2.5227 E 4 6/30/81 86.4%

2.0104 E 4 Following this incident, the following Unit No. 2 steam jet air ejector (SJAE) off gas level was measured:

Date Reactor Power %

Off-Gas pCi/sec at SJAE 7/6/81 86.2%

1.874013 E 4 7/8/81 88.2%

2.41197 E 4 7/9/81_

87.8%

2.29793 E'4 l

l 7

i L-

. ~,

-..- ~,.-.

. _ ~ - - _..

i LER INFORMATION SHEET IODINE CONCENTRATIONS pCi/ML e

1 Date Time T Power l-131 1-132 l-133 I-834 l-135 l-13I Dose Eaulvalent 6/28/81-0835' 20%

l.046E-l 9.662E-3

< MDA 7.958E-3 2.374E-3 1.05lE-1

'6/28/81 1250-20%

7.229t'-2 9.33E-3

< MDA 2.505E-2 8.080E-3 7.328E-2 6/28/81' 1750 49%

4.236E-2 1.ll5E-2 7.648E-3 4.617E-2 1.663E-2 4.626E-2 6/30/81 1045 84%

.l.06tE-3 1.142E-2 9.728E-3 4.469E-2 1.978E-2 5.807E-3 7/1/88 1355 91%

8.203E-4 1.348E-2 1.034E-2 4.480E-2 l'.761 E-2 5.637E-3 7/2/81 0153 Unit No. 2 7cator Scram 7/2/81 0639 0%

7/2/81 Unit No. 2 Reactor Startup @ 0639

7/2/88 0724 0%

1.235E-3 1.587E-2 9.816E-3 2.152E-3 7.656E-3 5.149E-3

'7/2/81 1824 Unig ho. 2 Reacter Critical 7/2/81 l145 Cri t ica l 9.669E-4 I.394E-2

_6.262E-3 < MDA 3.080E-3 3.445E-3 7/2/81 1523 Uni t No. 2. Reactor 'Porer Level 9.0% Power Level 7/2/81

.2011 Unit No. 2 Reactor Scram approximately 9.0% Power 7/2/81 2320

_ Unit No. 2 Reactor Sta rtup @ 2320 7/3/81 0115 0%

1.625E-1 2.839E-2 1.589L-1 1.572E-2 2.808E-2 2.100E-l 7/3/81 0326 4%

1.614E-1 2.398E-2 1.403E-l. < MDA 1.861E-2 2.028E-l l

- 7/3/81 0526' 10%

l.87tE-l 2.618E-2 1.460E-4 < MDA l.675E-2

~

2 300E-l 7/3/81 0835 10%

2.142E-l 2.627E-2 1.534E-1 < MDA 1.400E-2 2.589E-1 7/3/81 1810 1.575E-l 2.037E-2 1.170E-l 9.820E-3 1.270E-2' l.918E-1

~7/3/81 1320 45%

't.323E-1 8.906E-2 8.660E-2 1.999E-2 1.137E-2 1.580E-l i-7/3/81 1616 48%

4.627E-2 9.'r55E-3 3.705E-2 1.965E-2 8.149E-3

.- B-104 gpm 65 Reject 5 602E-2 i

i I

n

4 I

1 i

i l

.:L[:lb:

5 52

= g;-.:g;;;;;;:; :;;;;;;-lc;;;:-.::;;;;;;;;;;;;-

50 4a m,

mw

.. ~

48 l

m r

r r

i l

4:

42 L"

40 -

l l

38 l

so [5

34

(@

32 W::

30 l

r m

I r

28 l

28 24 m

n.,

20 l

g:

I ta i

l 16 14 12 ji es 06 m

04 t

']

-.e-e...em..e-.

m m.-

02 01 03 06 C7 09 11 13 15 17 19 21 23 3 27 29 31 33 36 27 39 41 43 45 47 49 51 t

Core Rings Representation of 560 Bundle Core j

i l

I

O*

I PDESENT' R-2 E TCSURE CISTR I 8tJ110N Unit 2 7-1-81 4

b WNG 1

2 3

4 5

A 7

avr LV t.

17 0960 t3P.

4672.

a =.1 7.

4 art O'l

_ _ _ _ _11 11953.

9215.

8151.

1492.

7FO' M_c t.._ 4 7 4. 2 4 3 c %

l 61AS.

8368 7 77M.

10 1551n. 11 ! ?.

105 E. 103 1.

10125 Mc 3. 10i92 1Cr m 9

1rSf'. 1 P 47. Ill*C. 11'.ac.

M r9 2744, lies. 3-)c7to.

s d

17344 2'th7.

Ile43. 11972. 11534 Sjoa. 1: 7so, lic;;,

O

[ ~ '~'

~ 1' 17500. 142??. 1 1'* ). 12204 11 H '

>608 1J209 11 U2.

2 G

IP241. t r CW.

12435 12:27 1?Si 5 102'O.,1.40.3.5. 1235*. -

. - ~.

S iP4 75. 154al. 12 cal. 13222. 17654 1C434. 14493. 1303'.

4 4

197?S. I S*1 F.

130 43 13G3 4. 13391. 11171 15 14 13491.-

'l 104.74 1 MM. 13 2 M. 13.1455.

13767 '. 1161.9. 15044 15744.

4. {

2 1 7 '"* 1.

142"J. 11863. 12445. ~ M,21 tc~?q. 13m3. 124F4 1

12*cc.

E7:1.

? ~ ~2 5.

7/0".

7757 (675.

??3S..

774 e.

2 AVE 1 5_B 2 6. 12742. ; G 10 6

! ') *

  • 7 1.

IreC9 2"76. 11'10.

.a.

I h

e 6

L*

W'

' W ~ d :##( " M$ N

,s-h '.

4

' O. v y'r f5 i

- y

.,r..v) t;.

.3

.s n_...

y

  • $.,-}';

-,e.g 7l',ss['v ;

~'%

1 N 'g. -

l e

4.

e

. " U$ 7 j ',

,?;.N[ W M $3 f

Q,, '

K3 %r

,W "Y.

y,(~_ G M e r %1

^~

+

d jc,.

.-V

  • .~^ p r'
  • :',, M k.e a,f'&rj y ;'$ El

n p" "CCMT D~

rYD ACf fD E" hTOTO.Y D f fTTA 1 -. g'y.,

w.,,,j f;, (~.,.f[: % y p.sv.-~..+.

,.ys

.--~I v? f h *- *

  • M

.P. s..y.y.-n',.h y M p,, w;w,p,.,'*gw - ' ,-

4 -4' gy, y'

' '.,f

  1. f.

.,,u...,y m'.i

. ta

- j s %,e

. q. - i j 3,r,.,,.,,....

t

, y J.4, % o.r

,..__.,.1 y..

N.'

e

,, g 74 M d.V M;-./n'g; M, :l Q y,;39 9 4; f,, e@ % Q M 9 Q Q % ' # y g - 9 73, f

m_.

--w--

4h9 M

a m dy M v- -y 9,

mm s

a,,N3 w,.1k;m. e,,.. c$ N.h,g M;% &. m.,JGD Q @.d 50gp M

('.

  • i g, m ~y.w w. W;'3 y p 5 m.g. p y# b %g. w M. W h. h.h a %n -4, g.. p ff 4 Log.r,4.r,4 m
s m.wg.. e wr g y

w3 wv nbyn e _gg y n n i.e.n.< k y mp

2. w

+ + Mh e y.j g.,9 -

,uuu.

4.,

s Ao oA

.4

.w

.....-;.y,.

p el A M &p %"4 12 7062. 5526.N, 4838;;[4665.'.c 4603f43588J; ;4815 ^ E4519.P b-3 JO lC.IN.(m@.a.J.,a 11 hi2223. s'.9473.E.84.204. 8147'.W8039N 637,3. 6,mnu 484982 M 929fu

&.. ni4 Mt y

.m

<c m a ~,m n now n ot,c - e me - c un n nw -

nW~w&w n.rM'p.,

W,. V c W

D4.G

  • 6' +9M.f 2'

=7

.. '. " ' '.4 :

~.p"122%;n >904.9W>A12V82d~.1MSr9W~dM.G

~m M,,..' 416891.,M./,.132.8. &,M, 447Pf-t%' 41196tfv.t%..,'b, e-T

.v e,W s W,,. W iny g,. h.

9.

1 3

P.

.12077. 2.M n

(.

W

@m h.u17.490.~4IKChg' $4 4474"I.414.8 di.2026. W 2225. ~ ~ ~.

9Dt ?.

. -..c.c. -

E i y*- E V Ntd

  • w-'> "' w* 2"

'n

_7T 4 701W OD N N ' "* ' ' =

M4'L '%; ia E4 - - '

i

, :M '67 d86U3b1NkSM1284'3Nb27Eh1U9I5NfSOM2k M[294bhMM M

0 ' 5}18825015865/13090@4eom.eohww'4W.4475 329.,3 g I h h g h' g-jgh 355.9M3169 092 L'

i 4 cn m %,>= 1 < a m t..

4 em ' 4 moo -

4 i $

iM k

k e

w w, wa giw 3w kw d Aaw6sasm..a 8,uden.ws,n9we;apwwkgnWm =e

4. s Mn w

v m.,w A. VE. N6U96.2.1UU.3b4,1. 0,33. )# 257N1,.09,2.M. m.hb1EU72N1,U.603.$ S.v@,m 3d.v.v,q%y.[.g@.g(

31 553 DAN m.,

mm: %-

s x

' _ :O.a

,f Y jf'n -x m.s'nQ,n}&.~&.,

7N %,.'

%Q%

. %,f f. Q,:

n

~. ~

.mycm l

mz -

. m,.u o

.m

w ~ n.w

.. e :

w

, $ww w. M Q 4 k, n.h.(s

z y
i.:n > y,mme
w b.

n: p.w..m,. ~. a. &~ ;.a -

~

n n ~ c.,n 7 9 a. v

.m,n s

a w >>

4 f.. f"..- q w w Y

E

. k. % -.. Q&.., p:V.

O " mp' w,li.lw>, M..y.['] $lld *. &. +^,$g-i.

.-w s.

a a,

YA f., :./,R k.

f

-&^ 3 g,,

D Y#

f ' l:)

I b.

R y

d,es g3S

.w*-

94't..

er..,.g. *

../

- 4 f,

,,. y +,... w y

.i y

e

. M i

-'d, t~.5,

,i+O.

t ' Ige f.

P.i d'>...

&+.'.'-(l'$ f D fR?[ h'rt'4 h g

,,i<

  • ?$-

'? V,k*%

1,C.***bf. a 'Qh * *',b.',t*Wh &5@(T? ^ &w?.? ' $. N 4

  • . ~

9-.

F y !'V. P 6',* 4'@

O 9 % '.e.

4

^

L.

N?

w m u L pw&',[$,(ly

? ;&W

/

c w w; w@f ;;c..n s-:w w:

+:

q:

m ee L<:;Q,y 4,rg.; 4 p %:;.,c.f.,,,c Lg)%;;j;g.

1 wmsw.QpVN M6jdiN.MQ)S&^ $ 'RWQM;Q

. w.

e'\\

yy elf,w%ys.,

94@pp k,. q g v yn:

fd

. y.h >

e aw n:-:m.

O,, h. m. n.- 6 A, n. % m&,.4; m ) ; J,As43h.*.4 ;' E % g n

n m n, esn%.y 4 6%%y;aa

.. m% u..m.,& c

=...

w:

p:a a

.s ws w

n n

4 (, q, %%.,

.y4.we

^~

m.

w..

s

.-m edy> q4,;6 v. w 3.,g.c; "m

,+q-Q., a. e te g e pj f c ?r,n n.w't.

f.a.,. -

77

..v r.

. y% T. mm.a ? 'r 7 e&~y.m ^, ~.

.e. u e

m m.

't a W ' m 3'.W M ~~

.A,i

.. - n
ri.u,wy M W1;u %, %

..,. =

.m:

n W

L2.

sw w, c vj it. Q w %t;Q ~A w$.j,e -.* yf(. '

j-**f Q f,;Qs;,%wl % y x:'m(.

Wf

- ?;

.W. q ?s % %.,.. '

~

r

~u " :.Ywr'

.e

.,I r ' O*d -d,Ni * -

7'* h, :

n m.

t

.w v.

j., % %

Q, 1 s %;g*.

.$h

.Q

(.

W'; M..' its, h r & # 4 /4 Y*id,.

4 / ddA. < % W', Il[tp_ l,s'e. t 9.- (

p, g.f e

  • h

. [

s "..

4

><,:;.,.l * [ <,m:,P

,r.a.gf e

s.*-

U,

.,t

~

p/,1"; p;..y

+-

t, 4'

% 4 j '- ' g. 3 ' A. n;.. ', h ; n 8

.6

. gj,

,,7 s ;p,

.e.

e.*

t o.,..a..,

<v s

3

- c

,N,

..S,@'

f" s*y,,n r

N

+.,

+ p. -

se-5 y

. #,qc.

43evoyy wp. ;@9 3 4', fJ,q ;, ~e

, pi,ggQ; A<. 9 3 '

,.4..

$~.

.,..-a-

' yp s.

m

-?

.m;3 C,

1

" ' *rO-et.N v..

,0, 9

-, }g R g}

), {

  • " o '

~ E'

. ?

l

)

'\\[

.t y

y

,v.

,t g g gg

{.

m.

, ra :

,,y*,

,=

r

'f.

s

.e s

n, m e,; p.,,, e 1

., / ;,.

y..n, e. O, -

e

.3-

.#.q m -

,e 4g..

e[.j?y t.

7 c

J

'**'tu,y 4 :

4 m m<n. _ ; y +..,.yt ?.e ;

- ys_ 3,

' y m.'. <

  • -,.-+

b,,,.?.

' Q

% G mn,

r ~

  • w
- tj

[

i x. y v,1 gi u

y f

^

Retrieved from "https://kanterella.com/w/index.php?title=05000324/LER-1981-063-03,_/03L-0:on_810703,reactor_Coolant_Activity_Exceeded_Tech_Spec_During_Reactor_Startup.Caused_by_Scram_W/Increase_in_Coolant_Fission_Product_Inventory_Originating_from_Leaking_Fuel_Element.Reactor_Power_Increased&oldid=4650966"