05000335/LER-1982-020

LER 82-020/03L-0:on 820605,after Short Reduction in Power by 5% While Increasing Power,Dose Equivalent Iodine Exceeded Tech Spec 3.4.8 Limit for 8-h.Caused by Reduction in Power Inducing Iodine Buildup.Nominal Level Reached in 10-h

ML20054N083
Person / Time
Site:	Saint Lucie
Issue date:	07/06/1982
From:	Pace P FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20054N081	List: 05000335/LER-1982-020, Forwards LER 82-020/03L-0
References
LER-82-020-03L, LER-82-20-3L, NUDOCS 8207150333
Download: ML20054N083 (5)

LER-2082-020,

Event date:
Report date:
3352082020R00 - NRC Website

text

. _ __ _

, l g

u.s. NucLEAa acculAToav COuuission

.NaCroau22e -

17 771' LICENSEE EVENT REPORT CONTROL SLOCe j (PLEASE PRINT CR TYPE ALL REQUIAED INFCAMATION) s i l l I l ! !h e f'"Ill o Is*l 1,1 S!!,I S1l@lOf01-l010101010l-lOl0l@l411(1l111l@l l

stC&NSE Nw *St A 25 it 6.G4454 Tvet JJ I l sisdTid@

7 3 ) LICENSEE CQ3g '. *s a 4 i

CCN'T fo~ITI "i',$ 1@l0 l 5101010131 315 @l016 a o I ave 01518 ~rsara I 2 @l n01710161812

>< auca r sara ao l@ {

j r s so .i :oc4ar w ueca tvENT DESCRIPTION' AN'O *ACS A8LE CONSECUENCE3 h 9 foTTl l Af ter a short reduction in power (down to 5%) while increasine power. dose I  ;

I fo TT1 I equivalent iodine (DEO) exceeded the T.S.3.4.8.a limit of 1.0 uCi/nm DEO I ,

fTT71 11 -131. The DEQ was first measured above the limit at 0001 on June 5, 1982

+

1

~

g gand remained above the 1imit for approximately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The attached  ;

~

g isheets contain the information required by T.S.3.4.8.d. This is the eighth ;

F5Til loccurrence of this type; 78-13, 78-24, 78-33, 80-39, 81-41, 81-56 and 82-17.I l

o I "

i coot

• sL8C t Cov*oNENTCoOE tv of ' N:st t, u t.] I C i cl@ L,,nj@ LXJ@

. .. u l Fl o U I EIL l X ! Xl@ a L..ZJ@ LZJ n @

$ 30V EN el AL QC0b4 e g gC1 m g *C a r alV's3 0 N

"0"I NO- CCCE T'Pi NC.

ttasso f

@sgg[EVINTVI^"

a L812 i L-J 10 1210 I jfj lo l 31 LLJ L--J

a LOJ 21 JJ JJ 2< 24 27 ;8 n ;d ja

[,thgY vafys)[7mim as . 1 oN CN 8L NT uft novR$ h sei som. 3, LZJ@LZJ@ l1s7. I@ lZJ@ 2,01 I 1 0 01 0 1o LYJ@

LNj@ lNl@ lu C i 419 ! 0.1!@

u >< :s <a <2 CAUSE DESCRIPYlOff ANO C09AEC.*1vt ACTIONS 27 I

u,,L,,,,,)lAfter an extended period of nower operation with a nominal level of fuel f

, g i cakage, l a reduction in power to 5% was a sufficient transient to cause g t odine i buildup (iodine spiking phenomenon) in the primary coolant. . The DEQ ;

. g lI-131 level decreased to below 1.0 uCi/gm ah er 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and to nominal ~

g_ y l levels after 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. ao

i a,

's'rNs* sPowta orweistatus @ NsI ,S v' oiscovsav esscairTion h h i s (F,,J@ l 01018 !@l NA l lA!@l* Operator Observation  !

- * .cnv,r " " **

I "V'~ ~

.su.s.o e.o'*c . a <s. .rist u LeCarico,.eaass@

t

_~ LLsj LzJ@ L7J@l ".ovoro NA .cnvirv @ l u

l NA 33 7 4 3 t '3 tt stasors~gg gas:$:.Ats s s wo. . e.,s :sso..nou@

ITTT1 10101 Ol@Lzj@l n "

I

' ' ' ,s.sa.~d'.d,'.ss "

w veia :ssca.*nc .@ I NA 8, 10101 , , Ol@l ,, .

u

'r#,'/, ' #" #((aMc

'@ NA l

[TTT] (Zj@l n

. .g3y g \

> Q W@Sg cm.sv.0m l NA  ! !II ffIIIII II i

, u <* n

! - r a> a P. L. Pace ,.cs s; (305) 552- % 54

! Navtona=ErmaEn

8207150333 820706 PDR ADOCK 05000335 S PDR

j .

REPORTABLE OCCURRENCE 335-82-20 LICENSEE EVENT REPORT PAGE i i

SUPPLEMENTARY INFORMATION <

TECHNICAL SPECIFICATION REPORT i DOSE EQUIVALENT IODINE l

1. Reactor Power History starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample

, in which the limit was exceeded.

l t

Time _ Average Reactor Power Average Reactor Power June 3, 1982 June 4, 1982 0000 99.20 99.20 0100 99.23 99.15

! 0200 99.23 99.07 0300 99.20 99.13 0400 99.15 99 15

! 0500 99.15 99.18 0600 99.13 99.09 0700 99.13 99.23 f 0800 99.15 99.26

! 0900 99.18 99.30

1000 99,20 99.28 1100 82.96 99.28

1200 68.88 99.13 1300 97.13 99.13 1400 99.28 99.36 1500 97.72 96.95 1600 97.77 85.35 1700 99.34 68.37 I

1800 99.34 47.26 1900 99.57 9.62 2000 99.89 0.85 2100 99.23 0.00 2200 99.26 0.00 2300 99.23 0.00 l

l  ;

i l

A i

a REPORTABLE OCCURRENCE 335-82-20 LICENSEE EVENT REPORT PACE 2 '

SUPPLEMENTARY INFORMATION

, TECIINICAL SPECIFICATION REPORT DOSE EQUIVALENT IODINE

2. Fuel Burnup by Core Region See Attachment "A"

3. Cleanup Flow ilistory starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded.

Date Time Flow Rate (GPM) 6-3-82 0000 - 0200 82 0300 - 0500 40 0600 41 0700 138 0800 141

' 38 0900 - 1400 1500 36 1600 - 1700 40 1800 80 1900 - 2100 82 2200 80 2300 82 6-4-82 0000 83 0100 - 0400 82 0500 38 0600 81 0700 - 0900 82 1000 35 1100 - 1400 82

, 1500 80 1600 72 1700 80 1800 72 1900 83 2000 - 2100 84 2200 80 2300 86 1

- - _ _ _ _ _ _ _ _ - _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ . . _ _)

. REPORTABLE OCCURRENCE 335-82-20 LICENSEE EVENT REPORT PAGE 3

4. llistory of Degassing Operation, if any, starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded.

There were no degassing operations during the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period prior to exceeding the dose equivalent iodine limit.

5. The time duration when the specific activity of the primary coolant exceeded 1.0 uCi/ gram dose equivalent I-131.

The dose equivalent (DEQ) exceeded the limit for a period of approximately 8_ hours.

Date 6-4-82 2200 DEQ 1-131 = 8.645E-01 pCi/gm 6-5-82 0001 DEQ I-131 = 1.283E00 "

6-5-82 0200 DEQ I-131 = 1.455E00 "

6-5-82 0400 DEQ 1-131 = 1.193E00 "

6-5-82 0600 DEQ I-131 = 1.039E00 "

6-5-82 0800 DEQ I-131 = 9.00E-01 "

6-5-82 1000 DEQ I-131 = 7.35E-01

.e ATTAC1BIENT A FUEL BURNUP BY CORE REGION Region Enrichment Number of Exposure (w/o) Assemblies (WD/11TU)

E 3.03 40 26981.7 E* 2.73 25 25045.4 F 3.65 40 16797.6

. F* 3.03 48 21007.4 G 3.65 32 4646.3 G* 3.20 24 5946.5 G/ 3.65 4 5188.7 GX 3.03 4 6178.8 Core Average: 17165.42 WD/t!TU .

1. e 2

i

. - . - _ - - . - - _ - _ . - -