3F1188-01, Special Rept 88-001:on 881009,RCS Sample Obtained & Analyzed for Iodine Activity Indicated Dose Equivalent Iodine (Dei) Exceeding Tech Spec Limit.Chemists Continued Sampling & Analysis of RCS at Intervals Until Dei Decreased

Special Rept 88-001:on 881009,RCS Sample Obtained & Analyzed for Iodine Activity Indicated Dose Equivalent Iodine (Dei) Exceeding Tech Spec Limit.Chemists Continued Sampling & Analysis of RCS at Intervals Until Dei Decreased

ML20205P429
Person / Time
Site:	Crystal River
Issue date:	11/01/1988
From:	Widell R FLORIDA POWER CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
3F1188-01, 3F1188-1, 88-001, 88-1, NUDOCS 8811080128
Download: ML20205P429 (11)

Text

P1

/

~

. 3 c,..M  ;'

sf;*,y$(3, c

(,)g.

'k [ _

Florida Power CORPORATION November 1, 1988 3F1188-01 U. S. Nuclear Regulatory Commission Attn: Document Control Desk washington, D. C. 20555

Subject:

Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Special Report 88-001 Daar Sir:

Enclosed is Special Report 88-001 which is submitted in accordance with Technical Specification 6.9.2.p.

Should there be any questions, please contact this office.

Sincerely,

~'

}l Rolf C. Widell, Director Nuclear Operations Site Support RCW:dlh Enclosure cc: Regional Administrator, Region 2 Senior Resident Inspector 8011000120 001101 PDR ADOCK 05000302 p S PNU i \

k Post Of fice Box 219

• Cry stal River, Florida 32629

• Telephone CM4) 795 3602 A Flonda Progress Company

f SUlmrr Special Broort 88-01

. Crystal River Unit 3 began plant shutdown for mintenance at 2200 on OcLober 7,1988. Plant chemists collected and analyzed Reactor Cbolant System (RCS) sa@les during the shutdown. At 1100 on October 9, an RCS sample was obtained and analyzcd for iodine activity in accordance with Technical Specification requirements. Analysis of the sa@lo showed Ebse Equivalent Iodine (DEI) to be 1.497 #C1/g. This value exceeded the Technical Specification limit of 1.0 pCi/g. Plant chenists continuod sampling and amlysis of the RCS at amroximtely four hour intervals until DEI decreascd below the ibchnical Specification limit.

In acconhnce with Itchnical Specification P.cquirements, this report contains the results of the DEI analysis, and hmntation of reactor powr history, fuel burnup, and the time duration during which DEI excecded the 7bdinical Specification limit.

Raactor Power IIIstory. Forty-eight hours before DEI exceeded the 7bchnical Specification limit, reactor power was raintained at approximtely 94% of rated therml powr. Thirty-six hcurs before DEI exceedcd 1.0 pCi/g, pcser decrease began. Reactor power history is presented in Table 1 and Figure 1.

Cleanup (Ictdown) Flow IIIstory. Reactor Coolant System letdcun flow was approximtely 75 gpn forty-eight hours before DEI excocded the Technical Specification limit. This flow rate was mintained for several weeks before shatdown. The plant was mintained in a steady state condition from 0930 to 1900 on Octcber 7. Therefore, the letdchn flow rate recorded at 0900 on that day was assuned to exist frun 1100 to abcut 1900. At 1920 on October 7 letdcun flow was Jacreased to approximtely 98 gpn.

Irtdcun flow readings are precentoi in Table 2 ard Figure 2.

Dogassing Operations. During the forty-eight hours before DEI exceeded the 7tchnical Specification limit, no RCS degassing operations occurred until 0925 on Octcher 9. Dcgassing was begun at that time and continued throughout most of the chy. Results of RCS sa@les durirg dcgassing are presentcd in Table 3 (no Figure 3).

Iodino Sapling Illstory. The first DEI sa@le to exceed the Technical Specification limit of 1.0 pCi/g was taken at 1110 on Octcber 9. An RCS sa@le taken approximtely eight hours later shched that DEI concentration had

, decreased bolcw 1.0 pCi/g. Samle times and DEI concentration values are l presentcd in Table 4 and Figure 4.

1 bel Ibrnp by (bru Regicn. This informtion is presentcd in Table 5 ard Figure 5.

I i

1 l

t l

l TAIRE 1: REACIUt IOGR IIISIWY DMS M  % RIP D!UE M  % RTP 10/07/88 11 94.6 10/08/88 12 43.6 12 94.6 13 44.1 13 94.6 14 42.5 14 94.3 15 42.8 15 94.3 16 43.8 16 94.4 17 44.2 17 94.6 18 47.8 18 94.4 19 53.3 19 93.7 20 52.8 20 92.7 21 53.4 21 92.5 22 53.2 22 92.4 23 47.3 23 87.9 2.4 37.8 24 HL.5 10/09/88 1 39.2 10/08/88 1 81.0 2 32.9 2 80.5 3 25.2 3 76.3 4 11.5 4 64.8 5 0.3 5 51.9 6 0.0 6 45.4 7 0.0 7 39.5 8 0.0 8 43.4 9 0.0 9 43.6 10 0.0 10 43.7 11 0.0 11 41.3

~ -

1 1

1

7 -

i 3

}

3 2

Y .

R .

O T

M .

9 1 8 8

9 S

I 1

H * .

5 1

9 r

e R * . b E1 1

t o

c w O Wr 1

e .

u -

O .

Oi Fg Po . 7 P 1 7

b r

e o

R .

t O

c O '

3 S

T .

R C .

U O

A .

3 H E .

2 R g .

g ,

9 a

i 1

o .

c

5 a .

1 C .

0 I

1 1

0 0 0 o 0 0 0 O 0

1 8 7 s 4 N 2 1 6aoa. $ ! I ogk X 8

E' P

MBW 2: REAC3GL IJmINGi HISIGN 10/7 0930 75 1920 98 10/8 2100 98.3 2200 97.9 2300 98.1 2400 97.9 10/9 0100 98 0200 78.9 0300 71.3 0400 51.3 0500 53.8 0600 62.1 0700 62.9 '

0800 69.3 i

0900 69.3 l 1000 69.4 l

1100 69.4 l i

t t

I

1

,1 1 mm -

.. 9

(

7 Y h 5

1 3

1

1 O .

3 Y

2 a .

R  !

1 2

O O .

9 T

1 )

8 0

S I  :

7 1

8 9

1 H 0 1

5 1 9 0 .

r N  :

3 1 b e

o W 2 0

1 t

c Oe

1 O

0 .

Du rg I

1 O .

9 7

i F  :

7 r E  :

0 .

b e

L  :

1 5 t o

0 . c R I I I !!I l' I i 3 (O O O 1

R U

T C . O C  ;

t I ' 3 2

H A O .

E  :

yi,

,2 1

R ei 9

t ,II' 1

0 .

I 7 1

0 .

5 1

O

,3

1 O

1

1 0 5 0 5 0 5 0 5 O 5 0 0 9 9 8 8 7 7 6 e 5 5 1

^2a.Ov c*o3eJ_

J b.

'D E E 3: IES GEIAS NI'IlOGEN HYIBOGEN RADIOACTIVE ,

SAMPIE TDE foc/ku) foc/ku) CAS fuci/oc) 10/09/88 - 1200 26.27 11.13 2.44 '

t 10/09/88 - 1615 14.02 7.61 2.96 10/09/88 - 2104 62.94 4.10 2.47  !

10/09/88 - 2258 55.41 4.04 Not Required t

I b

I k

4 l

i b

i l i I

a i i r i

s r

a i i

i 1

l t

i i

i 1

i

t l

SBut 4: IIERCER 000tJNr SifSHBt 100D05 03K3!NIRATIGi .  !

. t b

M SAMETE TDE I-131 (mci /a) 10/7 1035 .060  !

10/7 2145 .036

{

i 10/8 0730 .051 i

10/8 1925 .052 r l

10/9 1110 1.497 '-

10/9 1505 1.222 1

10/9 1915 .961 l 10/9 2330 .726  :

10/10 0550 .554 i i

k i

i i

(

i i

i

?

r I

i I

)

?

l l

,m -m.

O t) o.

Figure 4 l

RCS ACTIVITY uCi/cc l I l

I'

) del-131 1 .-

x ~

~

~

/ Cs-137

,/ ---------

0.1 -

' ~ '

, ~ -

r 0.01 -

,1 -

i  :

I ,

l l

0.001 -- -' ' . - -

{

j <

O.0001 B B B 5 10 0 4

B1 00B 0 6 1 01 O gt 300 g 013 g i91 gi@ \ T50 g 1 g @ g ,y,330

1 0 Ol'g10'OB 'g1 0'OB'g 10'09'g1 0'09'gg10 '0 9'ggO'09'g

o

/.

~

MIEE 5: REL IDOWP Bf GER Din:Trag RELIEtm ID. AVMUM IMEEP 2 25132.9 s

4 23591.3 5 15106.0 7 31734.1 8 22979.1 9 9433.4 i

l 6

e i

F I

I I

y Figura S CORE LOADING DIAGRAM, CYCLE 7 lQ 1

F'.*tt 74 43FIL CA W )

1 4 8 9 8 8 A pc4 tC8 F Elg M12 8 9 a 9 8 9 8 9 8 g

103 7 ac3 7 OC4 F R13 F L13 SC 9 8 9 8 9 8 9 8 9 $C C Mll F to2 F tos F c12 F tie F act Cie CT4 l

8 9 8 9 7C 9 2C 9 FC 9 8 9 8 O C10 F L11 F BM F FC7 7 110 F N06 7 CM cet '

g 9 8 9 8 9 FC 9 FC 9 8 9 8 9 7 809 F M10 F AO7 F A09 F tCl F 807 F 8 8 9 FC 9 2C 9 7C 9 FC 7C 9 8 8 F C11 C12 7 702 F Pot F FCl F E02 6 714 F C04 DOS Cv2 CY2 8 9 8 9 FC 9 FC 9 FC 9 FC 9 8 9 8 6 709 7 009 F $41 F 935 F (14 F 818 F 007 F F07 9 8 9 FC 9 FC f 48 9 7C 9 2C 9 8 9 vg F 7 11 4 F M14 F GC9 F IC2 F G:2 F mc3 7 "I

M13 CT! CT3 CT!

m 8 9 8 9 ft 9 FC 9 7C 9 FC 9 8 9 8 E

L0f F N09 F 101 F M02 7 F11 F Ell F N"JF F Lo1 8 8 9 7C 9 FC 9 FC 9 2C 9 FC 9 8 8 ,

t, til 012 7 LO! F S14 F 811 7 807 F L14 F 004 ACS CT! CT! ___

, 9 8 9 8 9 FC 9 7C 9 8 9 8 9

' N Fil F tov F (C6 7 P01 1 ( A07 F PC7 F

~

f, 9 8 9 FC 9 !C 9 7C 9 8 9 8 8 010 F (18 7 704 F B01 F F10 F FCl F 004 CT) 1 SC 9 8 9 8 9 8 9 8 9 $C 0 404 7 633 F 804 F Sit 1 814 F N01 CT4 C14 l p 8 9 8 9 8 9 8 9 8

. FC3 7 DC3 F CQ8 7 313 .. F F13 8 8 9 C 8 8 (04 604 F 818 (18

~

l 3

(

13 14 Il

. t 3 4 5 6 7 8 9 18 11 it Source: B&W Cy 7 Fuel Design Report .

N $7 J.L tis 14 M E"1.a twoup inusin i

___ - - . _ - _ _ . - . _ _ _ _ ~ . . . _ - - _ _ _ _ _ . . . _ _ _ _ _ _ . _ _ _ _ _ _ _ .._ -. __ _

._ ____ _.-- _ _