3F0989-08, Special Rept 89-001:on 890826,dose Equivalent Iodine Dei of RCS Samples Exceeded Tech Specs Limit.Sampling & Analysis of RCS Continued at 4 H Intervals Until Dei Decrease Below Tech Spec Limit.Dei Analysis Results Presented

From kanterella
Jump to navigation Jump to search
Special Rept 89-001:on 890826,dose Equivalent Iodine Dei of RCS Samples Exceeded Tech Specs Limit.Sampling & Analysis of RCS Continued at 4 H Intervals Until Dei Decrease Below Tech Spec Limit.Dei Analysis Results Presented
ML20248A897
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 09/21/1989
From: Ken Wilson
FLORIDA POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
3F0989-08, 3F989-8, 89-001, 89-1, NUDOCS 8910030040
Download: ML20248A897 (9)


Text

.;

i

' )e 4

t' V

L f,o ese $,

  • I L :go i' i..

I..

l.

. Power

. CORPORATION l

September 21, 1989 3F0989-08 U. S. Nuclear Regulatory n,-iacion

. Attn: W = ant Control Desk Washington, D. C. 20555 l

Subject:

. Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 l Special Report 89-001

Dear sir:

l Enclosed is Special Report 89-001 which is submitted in accordance with Technical Specification 6.9.2.f.

Should there be any questions, please contact this office.

Sincerely, l

l p% i K. R. Wilson l Manager, Nuclear Licensing >

l KRW:ead i i

l

~

Enclosure oc: Regional Administrator, Region 2 Senior Resident Inspec, tor 1

l

. I l .

/ (, i 8910030040 890921 l PDR ADDCK 05000302 1 g PNU POST OFFICE BOX 219 + CRYSTAL RIVER, FLORIDA 32629 0219 = (904) 795-6486 j

^

c-__=-----_______-- _ - --_ _ 2 ?!'!"?'"? ' "'"'L__ __ _ __-_- ___-_ A

t..

s

! SUBJECT Special amnrt 89 Crystal River Unit 3 began plant shutd wn for maintenance at 2200 on August 25, 1989. Plant chemists collected ard analyzed Reactor Coolant System (RCS) samples durirg the shutdown. At 2040 on August 26, an RCS sample was obtained and analyzed for iodine - activity in accordance with Technical Specification (Tech. Spec.) requirements. . Analysis of the sample showed Dose Equivalent Iodine (DEI) to be 1.09 pCi/g. This value exceeded the Technical Specification limit of 1.0 pCi/g. Plant chemists continued sampling and analysis of the RCS at approximately fceur hour intervals until DEI decreased below the Technical Specification limit. Dose Equivalent Iodine decreased to below the Technical Specification limit by 0045 on August 26, 1989.

In acconiance with 7bchnical Specification Requirements, this report contains the results of the DEI analysis, and documentation of reactor power history, fuel burnup, and the time duration during which DEI exceeded the Technical Specification limit.

Fme+rw- Power History. Forty-eight hours before DEI exceeded the 7bchnical Specification limit, reactor power was maintained at approximately 94% of rated tha = 1 power. Forty-six hours before DEI exceeded 1.0 pCi/g, power decrease began. Reactor power history is presented in Table 1 and Figure 1.

Cleanup (Letdown) Flow History. Reactor Coolant System letdown flow was approximately 70 gpm forty-eight hours before DEI exceeded the Technical Specification limit. Operators maintained this flow rate until DEI decreased to below the Technical Specification limit. Istdown flow readings are presented in Table 1.

numaning Operations. Reactor Coolant System degassing operations began at 1430 on August 26. Degassing continued throughout the event.

Iodine W ing History. The first DEI sample to exceed the 7bchnical Specification limit of 1.0 pCi/g was taken at 2040 on August 26, 1989. An RCS sample taken four hours later showed that DEI concentration had decreased below 1.0 pCi/g. Sample times ard DEI concentration values are presented in Table 2 and Figure 2.

Ibel Burnup by Oxe Region. This information is presented in Table 3 and Figure 3.

l 1

.; i

'mBLE 1 - REACITE ICWER AND IETDOW FIDIE Page 1 of' 2 REACIIR IE1 DOM IB33 TJHE F0WER f%FP) FIOW (man) 8/24/89 0000 95.33176 70.

95.31996 '70 0200 95.25589 70 95.27751 70 0400 95.60534 70 96.92610 70 0600 95.69418 70 l 96.02476 70 0800 95.80385 70 95.85141 70' 1000 95.156C5- 70 95.13915 70 1200 95.22327 70 94.94221- 70 1400 94.43435 70 93.72995 70 1600 93.75825 70 93.78852 70 1800 93.83490 70 94.33254 69.336 2000 94.29 69.336 94.43 69.336 2200 94.43 69.336 95.44 69.336 8/25/89 0000 93.86 69.336 93.02 69.336 0200 92.26 69.336 89.72 69.336 0400 84.75 69.336 l 81.46 69.336 0600 79.13 69.336 l 76.42 69.336 0800 75.48 69.453 74.74 69.453 1000 73.24 69.453 i

72.16 69.453 1200 71.59 69.453 70.62 69.453 I

l' )

E -

p i.

ls-l L

TMEE 1 - REACKR POWER AND IEIDOW FIJ0WS Page 2 of 2 REACKR IEIDOW j IB2E TDS IGER (%FP) FIDW (mun) 8/25/89 1400- 69.51 69.453 68.48 69.453 1600 67.91 69.453 66.9 69.453 1800 65.02 69.453 62.46 69.453 2000 59.69 69.453 56.27 69.453 2200 53.16 69.453 48.4. 69.453 8/26/89 0000 45.28 69.453 44.68 69.57 0200 40.97 69.57 34.7 69.57 0400 28.79 69.57 25.94 69.57 0600 18.66 69.57 14.58 69.57 0800 11.19 69.57 4.63 69.57 1000 1,69 70 1.41 70 1200 0 70 0 70 1400 0 70 0 70 1600 0 70 0 70 1800 0 7C 0 70 2000 0 70 0 70 2200 0 70 0 70 0000 0 70

, -N

... y

e  !

8 t

i

. O e

N g

/ "

f-  :

y . 8;

/  :

. 8e2

/ . A L

/ ~

g O  :

3 e o '. / -

~

OE /

N L)  ! I o

e.n l :8m U J O ' - 8n O

O [  :

E f  :

8-g

. R

~

o

~

f

.~ "N

. 8

(,  :

8g

~ 83' e o 8 8 8 R S S S R a (d.dE) J9 mod JoPDSM

l 4.

l-ll EWLE 2 - pnRR BQUIVAUNT IMENE-131 HIMUN o

b ggg Img IEI-131 (MICRO Ci / G)-

. 8/26/89 2040 1.0889

-( - 8/27/89- 0045. 0.84416 0400 0.71417 0800 0.63225

- - - . - = . - . - . _ _ - _ - . - _ - . _ - - . - - . _ _ . _ . . _ - . _ - - - _ . _ _ _ _ . _ _ . . . - - _ _ _ -- ._ -

Jlli 1 i I l l!

]1{!1I f

3 8 1

0 z

6 0

1 3

1 1

t " 4 0

n l

e a9 8 i v9 1 u,

q7 2 2 0

Ed n e

a i m

T e6 '

s2 l ot us 3 Dg 3

/

u 07 A 0l/

- 3 2

e r 2 u 2 g

i F

u

)

3

/

0 2,5 2

/

3 5 4 3 2 1 0 9 8 7 6 5 4 3 2 1 0 1 1 1 1 1 1 0 0 0 0 0 0 0 0 0 0 yh\ 8yv ,eyEo

.e-i,

'DdEE 3 - REL BMUI REEERS

' AVERAGE NlEEER OF BBlLQI R1RNUP DDIDMtri ASEMBLUS 4 27,185.9 1

5. 16,722.9. 4 7A' 35,388.1 24 8 25,860.5 60 2- 28,630.0. 8 9 13,705.1 80 I

i

)

I l

4 ., j FIGURE 3 -

FUEL BATCH LOCAT1ONS -

CYCLE 7 l i

1 8 8 9 8 8 l l

8: 9' '8 9 8 9 8 9 8 l SC 9 B- 9 8 9 8 9- B' 9 BC

'l f 8 9 '8 9 7C 9 2C 9 7C 9 8 9 8 9 8 '9 8 9 7C 9 7C' 9 8 9- 8 9

-8~ 8 .9 7C 9 2C 9 7C 9 2C 9 7C 9 8 8  !

! 8 9 8 9 7C 9 7C 9 7C 9 7C 9 8 9 8 4

9 8 9 2C 9 7C 9 4B 9 7C 9 2C- 9 8 9 8 9 8 9 7C 9 7C 9 7C 9 7C 9 8 9 8 8 8 9 7C 9 2C 9 7C 9 2C 9 7C 9 8 8 l

[-

9 8 9 8 9 7C 9 7C 9 8 9 8 9 8 9 8 9 7C 9 2C 9 7C 9 8 9 8 i i i SC 9 8 9 8 9 8 9 8 9 BC u ,

8 9 8 9 8 9 8 9 8 8 8 9 8 8 i

g