Text

RO-77-91:on 770717,reactor Coolant Dose Equivalent I-131 Level Found Contrary to Tech Specs.Caused by Expected Spikes Following Reactor Trip & Known Leaking Fuel Pins.Reactor Coolant Cleaned Via Demineralizers
	ML19308D436
Person / Time
Site:	Crystal River
Issue date:	08/10/1977
From:	Stewart W; FLORIDA POWER CORP.
To:	;
Shared Package
ML19308D416	List: ML19308D415; ML19308D436;
References
	NUDOCS 8002280748
	Download: ML19308D436 (19)
	v • d • e

~ ~ ~ ~ .__ _

LICENSEE EVENT REPORT

)l .

. .,h CONTROL DLOCK:l l l l l l l [pLCASE PRINT ALL RCOUIRED INFCRT.1AT;07r, 1 6.

8 AME LCENSE NUMOCR

TYPE lFlL lCl Rl P } 3l 7 09 14 l__0 l 0-l-l 0 l 0 l 0 l 0 l 0 l-l 0 l 0 l 15 25 l 4l 1l 1l 1l1l l0 l3 l 26 , 30 31 32 CATECORY TP DOCKET NUMOER EVENT oATE REPont CATE QCON'T l 7 8 57 l-l 50 d59 lL l 60 l0l5l0l-l0l3l0l2l 61 68 l 0 l 7 l 1. l 7 p l7 l l 0 l 8 l1 l0 l7 l 7[

69 74 75 80 EVENT DESCRIPTION c2 7 09 l Following a Reactor trip, the Reactor Coolant Dose Equivalent I-131 was 1.428 uci/ gram j g [ contrary to Tech Specs 3.4.8. Redundancy NA. Second occurrence of this event. Refe r j s g[fLER77-67. The DE I-131 returned to acceptable level at 1325 on 17 July 1977. ~

0 7 89 05 l (LER 77-91) 7 o9 l

@l 7 89 80 1

SEE Yo"o*e* couPoranT ceCE uES"[AEER vot4TcN O lC lG l lFl lZ lZ lZ lZ lZ l2 l lN l l Z l 9 l9 l9 l lNl 4 7 89 10 11 12 17 43 44 47 48 g CAUSE DESCRIPTION ',s as 7 89 l The increase of DE I-131 was due to expected spikes following a Reactor trip and ic2cwn le'alcir(g 0s l fuel pins. The Reactor Coolant was cleaned via the demineralizers.

7 J19 l l 80 7 l ST S % POWER g

78 pl l 0l 0l 5l l UTHER STATUS NA l

DISC /ERY lB l l D!SCoVERY CESCA:PTioN NA l

9 10 12 13 44 45 46 80 L Eo CF Q

7 8 W

9 lZlE *SE l 10 AMOUNT CF ACTMTY NA l l LOCATON OF RELEASE NA l

11 44' 45 PERSONNEL EXPOSURES 80 NUMBEP TYPE CESCArPTON Q l 0l 0l 0l 0l Zl 7 89 l NA l

11 12 13 SO -

PERSONNEL INJunlES NUMDER DESCRIPTON

$ l0l0l0l l NA 7 09 .11 12 l 1 60 OFFSITE CONSEQUENCES lII5l l NA

7 09 l )

LOSS OR OAMAGE TO FAC:UTY 80 !

TY DESCRIPTCN .

@ @PE 7 89 l NA l

10 PUBUCITY 3l 7 89 NA j

L:0

< 0U OITIONAL FACTORS 02 2807MI Lad

]l SEE ATTACHED TECH SPEC REQUIRED DATA AND SUPPLEWNTARY INFORMATION }

NAME. :u. p. se ware Cit e

n ONE: (813) 866-4159 l e CP O A fi l . ' f. 7 I

SUPPLEMENTARY INFORMATION Report No.: 50-302/77-91 .

! 2. Facility: Crystal River Unit #3 ,

3. Report Date: 10 August 1917

4. Ctcurrence Date: 17 July 1977

5. Identification of Occurrence:

The Dose Equivalent I-131 was greater than 1.0 pei per gram of primary coolant contrary to Technical Specification 3.4.8.

6. Conditions Prior to Occurrence:

Mode 1 operation.

7. Description of Occurrence:

At 0940, in the process of plant startup, the Chem / Rad department actified Operations .-

that the primary coolant Dose Equivalent I-131 was 1. 428 pei/ gram. Action statement 3.4.8.a was entered and clean-up of the Reactor Coolant was immediately initiated via 5' the demineralizers. The DEI-131 was reduced to .8 pei/ gram at 1325.

8. Designation of Apparent Cause:

O This event Reactor trip. was caused by known leaking fuel pins and expected spikes fo

9. Analysis of Occurrence:

There were no safety implications as sampling demonstrated reducing levels of DE I-131.

10. Corrective Action:

No corrective action deemed necessary as Reactor Coolant cleanup returned the DE-I 131 to acceptable levels.

11. Failure Data:

This was the second occurrence of this event, refer LER 77-67 dated 15 July 1977.

l J

ur --w, '--p t- T--P- - - -

t g--T T =9U

1 I

1

9 l

i I

I I

I REACTOR POWER HISTORY OF PRIOR FORTY-EIGHT HOURS ITEM I S

l I

l 1

I I

j i

-__ _ _ _ _ _ - _ _ _ _ _ . _ _ _ __ =_.~n...

Q .

t:

O- DATE 7,17,77 -

O.

HOUR MWHT NI RATIO . . . .

(N753) (P723) NI/MT i O. / FP */=FP */+FP 1:00 85.4t+0 0. . __ ._ 1. 016 0 . .. .

.- 2:00 85.1640 0 1.048 OT 3:00 85.440 0 1.048 4:00 85.685 0 .. .1.040 . . _ _ _ _ . _ _ _ _ . . . . . . . _ _

5:00 28.100 0 .918 O 6:00 2.284 0 0.300 I.__.. 7:00 .. 1.794 _.. 0._ .. 0 . 0 0.0. .

8:00 2.243 0 0.000 -

l O'. '

9:00 8.687 0 .783 l 10:00. 9 . 7t6 7 _. 0 ._ .__ .._ . 8 31__. . . )

11:00 10.522 0 .874 '

1 63 12:00 11.664 00 .883

. . 13:00 . . _ _1 1. 7 16 6 . . . 0 0 . .. . ,8.60 -

14:00 12.072 0 .853 O' ~15:00 12.561 ,0 .860 f.

16:00 12.6t&3 0 _ ; .,_ , . 8 3 1 __ _ _ __,.__ _ . _ __ . . _ _ _

17:00 12.316 .0 . 8 016 O 18:00 itt . 8 0 tt 00 .871

_ _ . . 1 9..:.0 0...__ 2 7 . 8 9.6 0 la_15.1 20:00 37.316 0 1.171 21:00 48.817 0 1.123

. 22:00 71.Ol+tt 0... _... 1,075 23:00 74.796 0 . 1.079 O ,

24:00 80.139 0 1.018 -

3

__ sVERAGE DAILY MWTH POWER __.. . ._ _. ..___ __ . 316 . 717. = /

F P '

AVERAGE DAILY NUCLEAR INST. POWER 35. t+83 */*FP

' RATIO OF NI TO MUHT = 1.022 G-O 9

O i . . .

O '.-

N 6

1 0' -.e__

O. .

e

G

~

' DATE 7.16,77 O -

2. .

Q HOUR MWHT NI RATIO ,

(N753) (P723) NI/MT

FP-

^

~ */*FP - * /

F P ' - -- -- - -- -

O ., 1:00 90.0e0 0 1.027 T(, 2:00 90.131 00 1.027 ji ~ 3 r 0 (T - 90'049 . 0 1.02r ~~- - - - =

4:00 90.334 0 1.025 g{3 . ,; 5:00 89.967 0 1.024

. - . 6 ': 0 0 ~ - 8 9 . 8 G 4 ~ -- - 0 -- - - 1 ~. 0 24 '-

I 7:00 89.478 Ocg 8:00 90.171 0 1.025 .

0 1.024 -

1 '9T0u 90 ~70 0 1.023 .

3.T 10:00 94.984 0 1.022 .

e 11:00, 96.615 0 1.015

~ 12 ': 0 0 - - 97T 0 23' -- -- 0' r:012 -- -- - - - - - - --'

13:00 97.308 0 1.010 g;! , 14:00 97.471 0 1.011 2 15 :~0 0-- 97.553 0- i:-01-1 -

gg 16:00 97.390 1.011

.- 17:00 97.390 1.012 f-q-- 7 8 r 0 0- 97.790 17012 - - -

g 19:00 97.431 0 1.014 E 20:00 97.227 0 1.014 ,

arTUO 97734V u I Vro I

g. 22:00 97.553 0 1.017 23:00 95.065 0 1.016 937638 24100- --1.020 -~

OE z-6 g4 AVERAGE DAILY MWTH POWER 94.255 */*FP

. AVERAGE DAILY NUCLEAR INST. POWER 95.967 */*FP

~

7. . .

G --j RATIO OF NI TO MWHT = 1.018 .

'**J

~

p' W

6

.g -

. . . . . . . . . . - . - . - ~ . . . . . . . . . . . . . . . . - . .

w I $$

3% -

,'=.=.-e

. . . . . . . .+e......,. . . . . . . . . . . . . _ . - . . ....-.e _ . - - . . .. .

..~ -_-

. - ~

l I k i

i y .

e J ~ -- .

l. _ , _ _ . _ _ . _ - . , , -_

t l ... -

DA-TE 7,15,77 o(r -

.ij l g. ' HOUR MWHT NI RATIO

{

(N753) (P723) NI/MT * '

/.FP +/*FP -/*FP '

g 1:00 97.064 0 ? 016 2 2:00 96.900 0 1.015

. - 3:00 - 97.064 --- - - - - - - - - - - - - - - - -

~ 0 0 ----- 1. 016 - -- --

g' 4:00 97.553 0 1.015 5:00 91.436 0 1,019 6:00 50.408 0 -

1.115 - - -- --

g ., 7:00 38.785 0 1.119 1_.-

.- .8:00 54.976 0 1.113 9 : 0 0~~ '~' 55 .17 9 -~ -- - 0- - t 7182 --- =

g3 10:00 54.976 0 1.108 11:00 55.873 0 1.106

- - 12 : 0 0- 72.145 0-- -- 1 r 0 0 0 ---- - - - -

07. 14:00 13:00 86.542 0 1.042

--,.g 86.909 0 81 1.033 15 : 0 0 -- - 87 . 0 31- ---- - 0-- 1 T 018--- - - - - - - - - - ---

g.]'I 16:00 88.622 0 1.013 '

17:00 89.396 0 1.025 6 18:00 90.294 -- -

0 -- ~ 1. 0 19 - - - - -- --- - - - - - - - - . - - - - - - - - - ---

g 19:00 90.049 0 1.018 20:00 90.253 0 1.019 q:_- . 21. 00 --90:253 - - - 0 1r020 - - - -

g 22:00 90.253 0 1.023 "3:00 90.253 0 1.024 s 24:00 90.090 ---

0 - - -- 1. 0 2 6 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

'D .

g' AVERAGE DAILY MWTH POWER 80.513 */ FP AVERAGE DAILY NUCLEAR. INST. POWER 83.721 */ FP 9- RATIO OF NI TO MWHT = 1.040 l,

95-3 3; .

). _.

D r

..s. _

...a_-

3

- ~-

-aWse aMe l

l l

I l

FUEL BURNUP BY CORE REGION ITEM 2 1

A.

i 9

I I

l l

Y i

l - _ - _ - _ . . _ _ - _ _ - - _ . - ---- - - - - - - _ - - - - - . - - - - - - - - . . . - , .

f t

i l The Burnup was calculated at 85.6 EFPD for the three enrichment regions.

{ REGION NO. of FA BURNUP i

A 56 2805 MD/MT l

. B 61 2968 MD/M C 60 1836 MD/MT AVE 2533 MD/MT ;

i t

4 I

l l

I I

i.

.h

--- e- ,- ,w-v ,, . , .- , - - - - ,,s--,.-.w-,,.m-y- - - -g-. g,e--u ,w, , - - , ,-w,.,,,v.--,w--w------.- . -- . , , , - -.-,w---,,-.,,-ww--e-+,--w--e--e--w------e_

4 4 *

[

CLEAN-UP FLOW HISTORY PRIOR FORrY-EIGHT HOURS ITEM 3 I

I m

a f

l l

l I

. - . _,-- .+y, . . . , -

,-,,w.-,g--q,,w-9. -.w,we wa .----.myMar-wgg- atrey-r+

1

.1

- e LETDOWN FLO',{

DATE 'i1ME DEMIN IN SERVICE

. 1 July '77 2:10 B 98 spm f

i 15 July '77 9:45 B 50 gpm -

I .

15 July '77 15:00 - .' B 60 spm j I

~

16 July '77 No data 17 July '77 3:45 B 100 gpm 17 July '77 8:15 B 100 gpm 17 July '77 12:10 B 100 gpm.

! \

l

. . l l

. I 1' l G .

I i

f ee o

t 1

f i

l 1

t j . .

i l .- - .a .. _ ;-. _ . . w' . .

i La

. :t i

. s........-

i, . .

k, .-

! 1

+ e ' .

. g og e-,-----, ,,n ,,, - - .,- , - - - - , , , , , ,,---,--,,,,,--.w---.,,,,,.,

,----,--,-,-----,_,--,--r,-----,v-_-,__, , a,,,. ..ww ,w

r - _ _- - - , - - , - - - - - - - , . , - - , - - - -

O

+

0 e

i HISTORY OF DEGASSING OPERATIONS ITEM 4 .

l #

9

~

l i

I l

l I

I l

l

F s-o 3- ,

O

. .1 I

HISTORY OF DE-GASSING OPERATIONS !

t i .

1 i

! 15' July 197 20:17 ,

Vented M!r! when aver pressurized. se.sived a

Hi Radiation alarm on RMA-2 and RNA-3 and closed vent innsdiately.

l I

4-

\O 1

i f

l O

- +

)

TIME DURATION WHEN DEI-131 EXCEEDED 1.0 uci/ GRIM AND I-131 ANALYSIS RESULTS ITEM 5 .

5

.l

l. - -

\

)

~

. r NE 4 0F FORM 912932 RCS LTDH I-131DE AFTER >15%/HR 92% REACTOR PWR DATE:L tit 1E OF SAMPLING: 7/ 17/ 77 595 DATE a TIME OF COUNTING: 7/ 17/ 77 445 SAMPLE VOLUME: 5.00 ML SAMPLE GEOMETRY CODE:5 AMP-2 COUNTING TIME = 1000 SECONDS , SAMPLE LOC.: CE- 119 ELAPSED TIME = 1 HOURS QUANTATIVE ANALYSIS QUANTITY ~ 2 SIGMA STD. DEV. 2 SIGMA /

ISOTOPE UCI/ML UCI/ML % ERROR -

I-131 0.0347265 +- 2.25950E-04 1.301311678 CS-128 0.0102613 +- 9.49882E-04 18.51387251 I-133 0.022363 +- 2.04758E-04 1.791173512 I-132 1.28975E-03 '- 1.10986E-04 17.21046714

/ ^ ~}4 2.78693E-04 +- 5.61764E-05 40.31418084

r J4 8.03355E-04 +- 1.56692E-04 39.00940431 N35 4.57665E-03 +- 2.95552E-04 12.9156479 HA-24 0.0113406 +- 2.16056E-04 3.81030986 RB-88 0.143948 +- 7.69852E-03 10.69625142 Jo.L3ULATED F-18 ACTIVITY = 0.06350944 UCI/ML B MU DEMIN OH SERVICE LETDOWH FLOW PATE GPM: 100 1

1

?

y- - - . - , - - , , . - - - - ,,,.1 ..vu,- e

p- _1 .2 ._u__- . . . _

1 i

j-P;:

6- 0F FORM 912932 j RC5 LTDM I-131DE AFTER >15%/HR 92%. REACT.OR PWR i

ACTIVITY SUMATIONS 1

1 TOTAL MEASURED SUM = 2.301E-01 UCI/ML t, .

TOTAL LLD ACTIVITY-SUM = 5.023E-02 UCI/ML I DOSE EQUIVALENT I-131 = 4.147E-02 UCI/ML I-131/I-133 RATIO = 1.519 UCI/ML ~

.. I-133/I-135 RATIO = 4.996- UCI/ML 1,

i

?

l 1

W 4

e l

1 1

i b

i j

1 J

t i

I

~w m --.-vw.--,- n. s ,--n --- sv , .w,---,. ,e e-.n-e----.--e -~,w. , ----- n .,,.w-. ,,n w, , g y,v e re n p - mm , p v y w w w- ,-ee ,

g .%

Q a:

OFg ,

FORM 9:2932 .

' ' ' . POWER CHANGE 01: REACTOR PWR ,

DATE & TIME OF rAMPLING: 7/ 17/ 77 815 DATE & TIME OF-COUNTING: 7/ 17/ 77 915 9 AMPLE VOLUME: 5.00 ML SAMPLE GEOMETRY CODE:5 AMP-4 COUNTING TIME = 500 SECONDS SAMPLE LOC.: CE- 119 ELAPSED TIME = 1 HOURS 4

QUANTATIVE ANALYSIS QUANTITY 2 SIGMA STD. DEV. 2 SIGMA

ISOTOP2 UCI/ML UCI/ML '; ERROR .e

, ---e.---- --e.----- --- -e.--- --e.-- -----a.-

I-131 0.89213 +- 5.78318E-03 1.296488180 s I-133 1.72768 +- 8.72974E-03 1.010573717

! CS-137 4.62759E-03 +- 1.47741E-03 63.85224274 MO-99 0.0521652 +- 0.011918 45.69329745 I-132 0.401554 +- 6.76863E-03 3.371217819 TP 0.0433491 +- 2.15906E-03 9.961267939 (v5MJ!? 0.0131314 +- 2.69592E-03 41.06066375 0.617831 +- 0.0127164 4.116465506 Un-24 0.0181996 +- 1.97838E-03 21.74091738 CALCULATED F-18 ACTIVITY = 0 UCI/ML B MU DEMIN OH SERVICE LETDOWN FLOW RATE GPM: 100 i

s I %,

e l

l

)

i i

i I

eD e - - me en en e ee e en - em - en es em - en es en me - aus --- ema - as - en en am -- en aus - en as --- - e> am se - - en - - - - - - -

r. .

f 6' 0F [ . . FORM 912932

. 3% POWER CHANGE 0% REACTOR PWR ACTIVITY SUMATIONS 1

i TOTAL MEASURED SIJM = 3.771E+00 UC ! "1L TOTAL LLD ACTIVITY SUM = 7.395E-01 UCI/ML 4

i

~

DOSE EQUIVALENT I-131 = 6 42W +rd UCI/ML I-131/I-153 RATIO = 0.51c- uCI/ML i l I-133/I-135 RATIO = 2.796 UCI/ML .

4 1

I 1

4 a i-j i

i 1

! l 1

i-l i

l r

I i

1 I

m ~

V' 4 ' 0F k FORM 912932

'. 31 DE >1UCI ML SAMP. 5% REACT 0'R PWR DATE & TIME OF SAMPLING: 7/ 17/ 77 1210 DATE'& TIME OF COUNTING: 7/ 17/ 77 1310 SAMPLE V0'UME: L 5.00 f.L SAMPLE GEOMETRY CODE:5 AMP-3 COUNTING TIME = 500 SECONDS SAMPLE LOC.: CE- 119 ELAPSED TIME = 1 HOURS QUANTATIVE ANALYSIS QUANTITY 2 SIGMA STD. DEV. 2 SIGMA ISOTOPE UCI/ML UCI/ML % ERROR

, I-131 0.538133 +- 2.57313E-03 0.956317490 .

I-133 0.889983 +- 3.67266E-03 0.825332619 CS-137 2.43072E-03 +- 5.67634E-04 46.70500922 MO-99 0.0158054 +- 3.70077E-03 46.82918496 I-132 0.097S068 +- 2.31682E-03 4.73754381 1A E5 5.94111E-03 +- 6.90183E-04 23.23414311 j9 5.93565E-03 +- 9.87379E-04 33.26944816

,oS 0.245408 + 4.72248E-03 3.848676490 HA-24 6.47694E-03 +- 7.14317E-04 22.0572369 CALCULATED F-18 ACTIVITY = 3.45160E-03 UCI/ML B MU DEMIN OH SERVICE LETDOWN FLOW RATE GPM: 100

)

J e

-v---y,- +w r gw r-y.- y c -. -+r,y- e--

'M m

. ^. .*..

g op . 8. ,

FORM 912932- .j 4

31 DE >1UCI/ML SAMP. 5'4 REACTOR PHR , ,

I i- ACTIVITY SUMATIGHS j - - - - _ - - - - - - - - - - - -

i.

1

?.

t TOTAL MEASURED SUM = 1.808E+00 UUI/ML 4

i i- TOTAL LLD ACTIVITY SUM = 2.686E-01 UCI/ML i

1

! DOSE EQUIVALENT I-131.= 8.035E-01 UCI/ML I-131/I-133 RATIO = 0.605 UCI/ML

i I-133/I-135 RATIO = 3.627 UCI/ML &,

i l

i l i i t >

1 l

l i

I [

l l I

i f

i G .

1 I

l et-*-s'amuteee-4e=Te*We atM-* m--*'arw-Pr='T-+-9PTn+wr=S2-u-wir*--a-v-4eTrWhW*W*Fv&*M':=e-T="tr'NWevt'+'-T-9-TFM* v-Ne'wM*V'-*W_. atur ruryw w -rr-w' W_. _,-rj.gy qwr- Fwe?M ur

ML19308D436

Text

Navigation menu

Search