ML19308D080

RO-77-67:on 770624,dose Equivalent I-131 Exceeded Tech Specs Limit.Caused by Known Leaking Fuel Pins & Expected Spikes After Reactor Trip.Reactor Coolant Cleaned Up.Reactor Power History of Prior 48 Hrs & Specific Activity Analyses Encl

ML19308D080
Person / Time
Site:	Crystal River
Issue date:	07/15/1977
From:	Stewart W FLORIDA POWER CORP.
To:
Shared Package
ML19308D079	List: ML19308D078 ML19308D080
References
NUDOCS 8002270580
Download: ML19308D080 (22)

Text

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UCL uce tvcNi ner v.u ,

.( CONTRCL SLOCK:l  ; l l l l l (PLEAS 3 PRINT AU. ntQutRED IfJFC 7.1A*:.:.

>) 1 6 I

• p E. LCENSE NUM6EA .

vet l0 l0 l-l0 l 0 l 0 l 0 l 0 l-l 0 l 0 l l 4 l 1 l1 l1 l 1l [0l3l32 ,j

( ]8 9l FlL l ClR lP l3 l 7 14 15 25 ES 30 31 )

CATECr Av t1v "E SEN5 CCCx'ET NuueEn tvENT CATE E C:"1 l57 l.-J IL i l' I lo i s lo 1-10 13 lo l2 l 101612l'17 1 7 I I017iREPlAf 1 7 l1 5AI'7 7 8 56 59 60 61 68 69 74 75 t EVENT Cf.SCRPTICN Fol?.owing a Reactor trip, the Reactor Coolant dose equivalent -131 was 1.95 012 l 7 89 Redundancy NA. This event .;

Ct2 l nerocuries/ gram contrary to Technical Specification 3.4.8. . .

7 09 .

lcgl l was non-repetitive. The Reactor Coolant was cleaned by the demineralizers and the f 7 89 . .

o5 l action staCemant was satisfied within 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> _

7 09 (LZR 77-67) 12.iil I .

7 89 E CE CCMpCNENT CCCE MAP 14 %C.ATCN a17 lClCl lF l l Zl Z l Zl Zl Zl Z] lNl lZ [9 l9 l9 l lN l

• 7 89 10 11 12 17 43 44 47 48 ,

9 CAUSE DESCR!PT:CN g [The increase of D.Z.I-131 was due to expected spikes folicwing a Reactor trip and known [

f-7 89 ois l leaking fuel pins. Reactor Coolant was cleaned up via denineralizers. .

E 7 89 Dh fa:Ury METHCo CF

• status 4 POWER oTHER STATUS C SCCVERY CISCovERY CESCA@f:CN in I Gl l0 l0 l0 l l NA l l3 l l NA 74 9 10 12 13 44 45 48 E AC CC4 RENT AE'.EASfo CF RE'. EASE AMCUNT CF ACTMTY LCCATCN CF RELEASE b

7 8

! 21 9 10 11 NA 44 45 NA L

PERSCNNEL EXPOSURES NuueEA rvot CESCAumCN NA ITTil l o l 0 ! 01 12 l l 7 89 11 12 13 PERSCNNEL IN.;tJR:ES NUM6ER CLSCAPTCN 114 l 010l 0l l NA 7 89 11 .12 i CFFSITE CONSECUENCES t is l NA -

7 89 E LCSS OR CAMAGE TO FAC:LITY Tvrt CESCRATCN .

~ll!aj LZj l NA .

7 89 10 "

g y, 8002270 580 .

7 89 .

1. UU'"U"" '##U"8 See attached Tech Spec. raquired data and Stipplecentary Infornation 7 89 '

5l 7 89 g n

j ,,

NAME.

• J.

. P. S tewart { v/y ppens: (313) 966-4159 e.r o m . c .-

Supplementery Infor=atiot n 1. Report No.: 50-302/77-67

2. Facility: Crystal River I'nic #3

3. Report Date: 15 July 1977

4. Occurrence Date: 24 June 1977

5. Identification of Occurrence:

The Ib e Equivalent I-131 greater than 1.0 ucI per gram of pri=ary coolant contrary -

to Tec.'mical Specificacica 3.4.8.

6. Conditions Prior to Occurrence:

Y. ode 3, hot standby operation.

7. Description of Occurrence:

At 1155, following a Reactor trip, operations was infor=ed that the primary coolant dose equivalent I-131 was approximately 1.95 ucI/ gram. Action statement 3.4.8.a l vas entered and cleanup of the Reactor Coolant was i= mediately initiated via the .

deminerali=ers. The action statement requirecent was satisfied in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and

• 30 minutes.

8. Designatien of Apparent Cause:

This event was caused by known leaking fuel pins and expected spikes following a Reactor trip. -

9. Analysis of Occurrence:

There were no safety implications as sampling demenstrated reducing levels of

• D.E. I-131.

10. Corrective Action:

No corrective action deemed necessary as Reactor Coolant cleanup returned the D.E.I-131 to normal levels.

11. Failure Data:

This is the first occurrence of this event.

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NI RATIO '

g7 HOUR MWHT nh F (N753) (P723) NI/MT v JL .:'

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g 1:00 99.715 00' .??7 I 2:00 99.715 00 .997 v1,h,k a 00

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<:00 99.062 00 1.003 g ..-

0:00 90.103 0 1.000

'M~ '?: 00 98.359 f l 0 1.003

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14: 00 97.'196 0 1.018 1U:00 97.227 7 0 1.017 g -- 16:00 97.186 0 1.018 7 17.00 97.227 0 1.017

3. 13:00 97.308 . 0 1.016 g7 19:00 97.227 00 1.016 20:00 97.268 00 1.015 a -21:00 97.268 00 1.015 - -- -

g--- 22:00 97.349 00 1.014 23:00 97.349 00 1.014 2'+ : 0 0 97.186 00 1.012 O2 AVERAGE DAILY MWTH POWER C3.049 ./*FP 07 ~~

AVERAGE DAILY NUCLEAR INST d!' < E R 99.050 */*FP

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RATIO OF NI TO MWHT = 1.010 f {* * ..

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HOUR HWHT WI RATIO (N753) (P723) NI/MT 0 */*FP */*FP "/*FP 1 00 97.064 0 1.013 5 00 97.268 , 0 1.012 CI 3:00 97.308 g 0 1.011 -

'4 : 00 97.106 00 1.010 5:00 97.145  ; 00 1.013 CI 6.00 97.156 0 1.013 7:00 ?7.104 0 1.016 '

S:00 30.873 ~

0 1.212 53 0;C0 97.268 0 1.015 10:00 97.390 0 1.014 11:00 97.431 0 1.014 b) '.2 00 48.491 0 2.025 13:00 46.401 $ 0 2.025 ,

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AVERAGE DAILY MUTH POWER 70.150 */se?

AVERAGE DAILY NUCLEAR INST. PGWER ?G.413 a/>F?

PATIC OF NI 70 MNHT = 1.403

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COUHTUlG TIME = 1000 SECONDS ELA? SED TIME = 1 HOURS QUANTATIVE ANALYSIS .

2. SIGMA STD. DEY. 2 S'IGMA QUANTITY  % ERROR.

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1.41377E-03 +- 1.46755E-04 I-132 +- 3.05187E-04 23.336 4 295

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FORM 912932 r~ 4 0F .7 (s.a]>nE A.=TER asACTOR 0. s.EAC r0R su.: scRAn DATE

• TIME OF GAMFLING: 6/ 24/ 77 435 en:: .. iu. ,1:_ u. r i... .uU s, l _i uki e,_~ . __

., e, .'

SAM. OLE VOLUME: 5.00 ML SAMFLE GEOMETRY CCDE:5AnF-2 -

COUNTING TIME = 1000 SECONDS iAMPLE LOC.: CE- 119 ELAPSED TIME = 1 HOURS QUANTATI'!E RHALYSIS QURHTITY 2 SIGMA STD. DEV. 2 SIGMA ,

UCI/ML - UCI/ML  % ERROR j ISOTCFE _______________ _______

HF-239 4.53360E-05 +- 2.909925-05 129.3712723 7 I-131 1.1506 +- 1.34673E-03 0.234091778 .

+- 1.632.SG,E-05 0 293034043 .

I-L-s-12. 1 3 3 ,, ,1. ,153S4 2 . v 1 0 ,s- c - o..,o + ,,.o ,- u*. o E-9,.

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I-132 0.321035 +- 1.50664E-03 0.938614170

-CO-5o 0,0224426

+- 6.92166E-04 6.168322743

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0.0145451 +- S.26263E-04 11.36139315 35' . c 0.508386

+- 2.74197E-03 1.078696109 b >24 0.0174717 +- 5.29445E-04 ,

6.060600557 CALCULATE 5~F-18 5CTIVITY = 0 UCI/ML H0 MU DEMIM OH SERVICE LETDOWN FLOW RATE GFMt 55 .

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i 0 ?. F3 ACTOR ?GF vine A~TER FEAC TIa 3C? *H ,

A C T ___

_______ I V ______

I T'_I S U i1 A T I G H 3 TOTAL MEA 3URED SUM = 3.192Ee00 UCI/ML .

TOTAL LLD ACTIVITY SUM = 1.279E-01 UCI/ftL DOSE EQUI'/ALENT I-131 = 1.51TE*00 UCI.'ML I,.131/I-133 RATIO = 0.997 UCI/ML-

-t-133.'I-135 RATIO = 2.270 UCI/ML . .

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• FO?rt 912932 CS I-121 DE 0% REACTOR FWR

~, ATE & TI:!E OF SAMPLINC: 6- 24/ T-' 1000  ;

DATE i TIME OF COUNTI!1G: 6/ 24< 77 1100 l SAMPLE VOLUME: 1.00 ML SAMPLE GECMETRY CODE:5 AMP-4 COUHTING TIME = 600 SECONDS SAMPLE LOC.: CE- 156 ELAPSED TIME = 1 HOURS QUANTATIVE ANALYSIS QUANTITY 2 SIGMA STD. DEV. 2 SIGMR  ;

ISOT0?E UCI/ML UCI/ML  % ERROR .

I-131 1.89529 +- 0.0142587 1.504645727 CS-137 0.0158738 --

3.25236E-03 40.96480842

- CO-58 9. 60041E- 03 +- 3.49798,E-03 72.37020178 m =4 .... G. 0.3 . .. bo o m

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0.47448 +-~0.0201553 S.495742708 -

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0.012393 -

+- 2.67606E-03 43.18663762 CALCIJLATED F-18 ACTIVITY.

= 0 i)CI/ML S MU DEMIN OH SERVICE LETDOWN. FLOW RATE GPM: , 9 5.. . -

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. i 0F h FORT 1 912933 CS I-131 DE 07 FERCTOR FWR

. ACTI'/ITY SUr1ATIONE TOTAL T1EA5URED 3U 1 = 2.435E-00 UCI/t1L TOTAL LLD ACTIVITY sui 1 = 1.179E+00 UCI/t1L DOSE EGUIVRLEHT I-121 = 1.957E-0G UCI/f1L I-131/I-133 RAITO < LLD I-133/I-135 RATIO < LLD 5 O .

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COUt4 TING TIME = 600 SEC0t1DS SAMPLE LOC.: CE- 119 ELAPSED TIME = 0 HOURS QUANTATIVE ANALYSIS QUAT 4TITY 2 SIGMA STD. DEV. 2 SIGMA i ISCTOPE UCI/ML - UCI/ML:  % ERROR '

1.40536 +- 0.0120196 1.710536802 '

'l I-131 I-132 0.139836 +- 6,79773E-03 9.722431992  ; l

+- 1.72802E-03 51.71111537 ,l C S 36 6.68336E-03 MM-54 0.02.15442 +- 2.89547E-03 26. 87'd 4572 l I-135 0.215047 +- 0.0132309 12.3051: '00 ,

Wt-21 0.0104907 +- 2.25112E-03 42.9.548794 l m

CALCULATED F-19 ACTIVITY = 0 IJCI/ML

-8 MU DEMIH Otl SERVICE LETDOWtl FLOW RATE GPM: 95

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RCS I-131 DE 4HR SAMPLE 0'. REACTG5 FWR -

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8, .v 7. . ,s .. r ?'s TOTAL MEASURED SUM = 1.799E,00 UCI/ML TOTAL LLD ACTIVITY SUM = 6.380E-01 UCI/ML DOSE EQUIVALENT I-131 = 1.443E+00 UCI/ML /

I-131/I-133 R ATI-0 < LLD .

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QUANTRTIVE ANALYSIS

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~3.HP-239 ' 2.88350E-03-1 +- 2.90605E-03 0.234625643 .

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0,362296405 D- I- 121. % O.695125 ..

~ 0. 588485~ Tc -._; ~-+2 1.06603E-03 18.75751024

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-- 7 0-58 ..i 1.73366E'04.~. - 22.S027413?'

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OF ,

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, ACTIVITY SUt1ATIONS TOTAL MEASURED SUt1 = 1.454E-00 UCI/nL

= 7.533E-02 UCI/ML TOTAL i.LD ACTIVITY SUM . .-

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CLEAN UP FLOW HISTORY PRIOR 48 HOURS June 22, 1977 21:45 Domin B ON 21:47 Domin 3 0FF June 24, 1977 06:30 . Domin B ON June 26, 1977 16:50 Domin B 0FF F.

Flow rate 55 gpm to 120 gpm.

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FUEL BURN UP BY CORE REGION ITEM 2 Bum up Midnight on June 30, 1977

~

72.366 EFPD Bum up at tizna' of incident June 24,1977 11:55 71.539 EFPD e

i

4

.a gos POWER CORPOR ATION CRYSTAL RIVER AUCLEAR

-OP ER ATING TEP 3RT JUN 1977

. ).IU UcTICN DEPARTME.

FUEL -INVENTCRY SY FUEL ASSEMBLIES

( )

ASSBY MSTU. MBTU MBTU ASS 3Y MBTU MBTU MBTU IO ON HAND BURNED ON HAND 13 CN HAND aVRNEO CN-HAND BEFORE- ENO SEFCRE ENO AOL 517096 32885 484212 A5l 524206 27500 496706 A02 524206 27500 496706 A52 524206 27500 496706 A03 517986 31710 486275 A53 531834 25252 506582 A04 531834 25252 506582 156 516324 32167 484157 -

A05 531834 25252 506582 A35 534625 23197 511428 A06 528958 29925 499033 A56 516324 32167 484157 A07 528958 29925, 499033 Sol 856678 35173 821505 A08 524206 27500 496706 302 856678 35173 821505 A09 528958 29925' 499033 803 869196 30436 838759 A10 528958 29925 499033 804 873329 23479 849S51 A ll 534625 23197 511428 SOS 869196 30436 838759 A12 517096 32385 484212 S06 869196 30436 838759 A 13 517096 32885 484212 907 862268 33231 829037 A14 522623 31390 491233 808 860514 35077 825437 A15 524206 27500 496706 809 869196 30436 838759 -

A 16 517096 32885 484212 310 857455 34628 822S27  ;

A17 517096 32285 484212 Bil 874952 25764 849188 A la 522623 31390 491233 B12 869196 30436 838759

A19 517985 31710 486275 313 860514 35077 825437 A20 5L7096 32S85 314 860514 35077 825437 48*212 A 21 522623 31390 491233 315 8605L4 35077 825437 A22 534625 23197 511428 S16 860514 350'77 825437 A23 522623~ 31390 491233 817 874952 25764 849188 A24 517096 32S85 484212 918 857455 34623 322827 A25 524206 27500 496706 819 862268 33231 829037 A26 518425 30700 487725 820 857455 34628 922S27 A27 534625 23197 511428 821 874952 25764 849188 A28 534625 23197 '

1428 822 862268 33231 829037 A29 516447 33171 -33277 323 862268 33231 829037 A30 516324 32167 484157 324 860195 31389 828806 A31 534625 23197 5 L l 4 ~.3 B25 857455 34628 822827 A32 531834 25252 506582 S26 874952 25764 849188 A33 518425 30700 487725 827 873329 23479 849851 A34 534625 23197 511428 823 869196 30436 838759 A35 524206 27500 496706 329 869196 30436 838759 A36 517986 31710 486275 830 869196 30436 838759 A37 528958 29925 499033 331 860195 31389 828806 A38 516447 33171 483277 332 857455 ~4623 822827 A39 518425 30700 487725 333 857455 34628 822827 A40 517985 31710 486275 B34 860195 31389 S28806

, A4l -517096 32885 484212 835 860195 31389 823806 A 42 528958 29925 499033 S36 862268 33231 82903%

A43 534625 23197 511428 837 871553 24626 846927 A44 516447 33171 483277 338 873330 23479 849851 A45 518425 30700 487725 339 874952 25764 849188 A46 524206 27500 496706 3'O 873329 23479 84985L A47 516324 32167 484157 341 862268 33231 329037 A48 528958 29925 499033 342 874952 25764 849188

'- / A49 528958 29925 499033 343 960514 35077 825437 A 50 516447 33171 483277 344 374952 25764 S49138

5!

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-, , . . . _ . _ , _ _ , . _ _ _ . , , _ . , , . , , _ _ _ , . . m . . _ . _ . _ . - , . . - _ . . _ _ , _ _ _ . , , , .

i

. CRYSTAL RIVER NUCLEAR

, -4 f 0 A PouER CORPORATION li douCTION OEPARTM T-OP ERATING REPORT JUN 1977 i FUEL INVENTORY BY FUEL ASSEMBLIES

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ASSBY MSTU MBTU MSTU ASSBY MBTU MBTU MBTU 10 ON HAND BURNED ON HAND 10 ON HANO . BURNED CN HAND SEFORE END EEFORj ENO S45 873329 23479 849851 C23 1051279 17592 1033687 B46 862268 33231 829C37 C24 1049548 16835 1032714 S47 874952 25764 849188 C25 1049548 16335 1032714 848 857455 34628' 822827 C26 1051279 17592 1033687 ~

S49 860514 35077 825437 C27 1048402 17519 1030884 S50 860514 35077 825437 C23 1045453 21937 1023517 B51 857455 34628 822827 C29 1063486 13033 1050453 B52 856678 35173 821505 C30 1063486 13033 1050453 353 862263 33231 829037 C31 1049548 16835 1032714 654 873330 23479 849851 C32 1C49548 16835 1032714 855 a63135 30475 832660 C33 1051279 17592 10336a7 B56 873330 23479 849851 C34 1063486 13033 1050453 857 863135 30475 832660 C35 1045453 21937 1023516 358 863135 .0475 832660 C36 1C48402 17519 1030884 B57 863135 30475 832660 C37 1C45453 21937 1023517 /

860 873330 23479 849851 C3a 1064138 11111 1053076  ;

~

361 856678 35173 S21505 C39 1063486 13033 1050453 Col 1040592 20646 1C19947 C 40 1063436 13033 1050453 CO2 1049543 16835 1C32714 C41 1064188 11111 1053076 C03 1051279 17592 10336a7 C42 1064108 11111 1053076 1063486 13033 1050453 C43 1017122 31193 985930

• 1049548 16a35 1C32714 C44 104a402 17519 1030884 '

O C04 C05 C06 1040592 20645 1C19947 C45 1017122 31193- 985930 C07 1040592 20646 1019747 C46 105l279 17592 1033687 Caa 104a402 17519 1C30884 C47 1051279 17592 1033687 C09 1045453 21937 1023517 C48 1051279 17592 1033687 C10 1048402 17519 1030884 C49 1045453 21937 1023516 C 11 1045453 21937 1023516 C50 1045453 21937 1023517 C12 1048402 17519 1030884 C51 1063486 13033 1050453 Cl3 1048402. 17519 1030884 C52 1060173 14446 1045227 C14 1051279 17592 1033687 C53 1064188 11111 1053076 C15 1049548 16335 1032714 C54 1064138 11111 1053076 C16 1049548 16835 1C32714 C55 1060173 14946 1045227 C17 1017172 31193 985929 C56 1064188 11111 1053076 l CIS 1017122 31193 985929 C57 1064188 11111 1053076 i C 19 1Q40592 20645 1C19947 C58 1069188 11111 1053076 l C20 1063486 13033 1050453 C59 1060173 14946 1045227 C21 1048402 17519 1030884 C60 1060173 14946 1045227  :

C22 1045453 21937 1023516 TOTAL 4570664 l I

TOTAL BATCH A 1645616 i

l TCTAL BATCH S 1873694  ;

TCTAL BATCH C 1051354

()

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d'L0 i 3?L;;Op,

3-TIME DURATION WHEN D.E.I-131 EXCEEDED 1.0 uc/ gram 6/23/77 DATE TIME FLOW RATE I 131 6/23 2010 55 gym 0.206 uci/ gram

. 6/24 0435, 55 gym 1.517 uci/ gram 6/24 1000 95 1.957 uci/ gram 6/24 1315 95 1.443 uci/ gram 6/24 1715 55 0.864 uci/ gram

'l

~

Degassification History: None i

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1

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