05000302/LER-1980-052-03, /03L-0:on 801208,RCS Dose Equivalent I-131 Exceeded Tech Spec Level.Caused by Leaking Fuel Pins & Anticipated Dose Equivalent Iodine Transient Following RCS Transient.Rcs Circulated Through Makeup & Purification Sys

/03L-0:on 801208,RCS Dose Equivalent I-131 Exceeded Tech Spec Level.Caused by Leaking Fuel Pins & Anticipated Dose Equivalent Iodine Transient Following RCS Transient.Rcs Circulated Through Makeup & Purification Sys

ML20002C207
Person / Time
Site:	Crystal River
Issue date:	01/05/1981
From:	Hernandez V FLORIDA POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20002C205	List: 05000302/LER-1980-052, Forwards LER 80-052/03L-0 05000302/LER-1980-052-03, /03L-0:on 801208,RCS Dose Equivalent I-131 Exceeded Tech Spec Level.Caused by Leaking Fuel Pins & Anticipated Dose Equivalent Iodine Transient Following RCS Transient.Rcs Circulated Through Makeup & Purification Sys
References
LER-80-052-03L, LER-80-52-3L, NUDOCS 8101090622
Download: ML20002C207 (13)

LER-1980-052, /03L-0:on 801208,RCS Dose Equivalent I-131 Exceeded Tech Spec Level.Caused by Leaking Fuel Pins & Anticipated Dose Equivalent Iodine Transient Following RCS Transient.Rcs Circulated Through Makeup & Purification Sys

Event date:
Report date:
3021980052R03 - NRC Website

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IVtNT OESCAs#tCN a.NC **Cs A3LI CONst:WENCIS

,,,jg At 0930 during Reactor shutdown it s discovered by Reactor Coolant System samplig

,,g, that the Dose Eq.uivalent I-131 exceeded 1.0 microcuries per gram. This created

,,,y, an event contrary to T. S. 3.4.8.

Redundancy N/A. There was no effect upon i o,,! I the health or safety of the general'public. This is the nineteenth occurrence io..it reported under this specification.

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,,,,, g Dose Equivalent I-131 returned to less than 1.0 microcuries per gram at 2230.

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SUPPLEMENTARY INFORMATION Riport No.:

50-302/80-052/03L-0 Facility:

Crystal River Unit #3 R: port Date:

5 January 1981 Occurrence Date:

December 8, 1980 Identification of Occurrence:

Primary Coolant Dose Equivalent I-131 was greater than 1.0 microcuries per gram contrary to Technical Specification 3.4.8.a.

Conditions Prior to Occurrence:

Mode 3 (hot standby 0%).

Description of Occurrence:

Between 2030 and 2330 on December 7, 1980 Reactor power was de-creased from P4% to 0% for maintenance. The Reactor Coolant System was sampled at 2334 and the Dose Equivalent I-131 was determined to be within specificaticn. At 0730 on December 8, 1980 the RCS was sampled to investicate a higher than usual Gross Beta radioactivity result and the Dose Equivaler.t I-131 was de-termined to be 1.45 microcuries per gram at 0930.

Designation of Apparent Cause:

The cause of this event is attributed to leaking fuel pins and an anticipated Dose Equivalent Iodine transient following the Reactor Coolant System transient of the previous night.

Analysis of Occurrence:

Redundancy N/A. There was no effect upon the health or safety of the general public.

Corrective Action

The Reactor Coolant System was recirculated through the Makeup and Purification System; Dose Equivalent I-131 was determined to be less than 1.0 microcurie per gram at 2230 December 8, 1980.

Failure Data:

This is the nineteenth occurrence reported under this specifica-tion.

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C' Reactor Power History of Prior forty-eighe Hours Item I L

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Evene Date:

12/8/80 l

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DATE 12, 6,80 L

5 HOUR GMWE TURD G NWTH NI RATIO RATIO

(

'F?!"'

'TS5A'

'+MM (P7 9-M- --N UM T

1. FJNT

• /=FP BTU /KWH

• /aFP

• /aFP

• /aFP

=/cFP 1

96.21 9901 96.94 99.10 1.022

.99?

2 96.23 9890 76r94 77.14 1."22

.V93

'- 1 3

96.28 9892 96.94 99.00 1.021

.993 1

4 96.25 9898 96.94 99.40 1.025

.993 5

96d5 7887 76-94

77. ?;0 1--O o '-

^^"

'E 6

96.25 9894 96.90 99.50 1.027

.993 M

7 96.27 9896 96.9F.

99.50 1.026 993 O

96.25 9697 77.02 79 r64 1.027

.992 h

9 94.77 9901 95.43 98.60 1.033

.993 N

10 95.06 9898 95.72 99.00 1.034

.993 "5

!?

95v82 9994

%G3 9MA 1.032

.or 12 96.00 9904 96.74 99.70 1.031

.992 IE 13 96.01 9904 96.78 99.80 1.031

.992 1 12 06.05 0800 06.74 oo 70 1 031 093 E

15 96.08 9897 96.78 99.60 1.029

.993 I

2' 16 96.09 9898 96.78 99.60 1.029

.993

'2 '

!?

96 !?

0395 94 79 CS.on 3 n37

.993

$2; 18 96,13 9893 96.78 99.90 1.032

.993

'E 19 96.08 9900 96.78 99.90 1.032

.993 i

I 5'

20 94,07 0900 06.02 1MJD 1.033 093 4

21 96.02 9902 96.74 100.00 1.034

.993 2

4 21 22 96.09 9892 96.70 99.90 1.033

.994

(

l 23 o6E 9894 9 4,-7 4 09,90 1,033

.o93 24 96.00 9897 96.70 99.90 1.033

.993

(

3 2

31 i E AVERAGE DAILY GENERATOR GROSS 821.02 MWH(E)

Pl 0 VE RAGE-D AIt,Y--THE RMAl,- POWER 2374 J2--NWHLTJ A

AVERAGE DAILY TURDINE GROSS HEAT. RATE 9898 BTU /KWH I 21 AVERAGE DAILY MWTH POWER 96.714 */*FP

'3' '

nVEEGE-DAILY-NUCLEAR--INST,-POWER 99,567- =AT-P-n l

3.1 RAT-TO-OF--NI-TO--NWTH - 1J30 o

7i 43#

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l E4 8

53 N

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'DATE 12, 7,80 c

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1 HOUR GMWE TURB G MWTH NI RATIO RATIO i

'E710' (TSG4)

'P757)

(P???'

HI-/NT MEJN-T 1

• /=FP BTU /KWH

./=FP

• /=FP

• /=FP

=/=FP 1

1 96.06 9892 96.70 100.10 1.035

.993 2

96 4 9839 96.66 14 h40 1.036

.?94 1

3 96.00 9894 96.66 100.00 1.035

.993 1

4 95.71 9890 96.29 99.60 1.034

.994 5

9M5 999" 96,29 99.60

.034

??3 2

6 95.43 9896 96.04 99.50 1.036

.994 I

E 7

92.26 9899 92.74 96.70 1.043

.995

'E O

93.1-9 9023 93.94

? ?. 74) 1 r440

.992 9

95.91 9892 96.53 100.00 1.036

.994 10 95.93 9889 96.53 99.90 1.035

.994 of n1 969-1 9442 o?.30

? n07 o9" d'

12 96.09 9888 96.70 97.30 1.006

.994 I

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13 96.11 9890 96.70 97.20 1.005

.994 is tu 9A.no on9n 9/. 7n 07 3n 1_ nog equ 2

15 96.00 9900 96.70 97.20 1.005

.993 E

16 96.12 9889 96.74 97.20 1.005 994

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96 W 9No?

94,74 o'.30

? nO4

.9S" 18 96.13 9888 96.70 97.50 1.008

.994 f I.4

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19 96.05 9898 96.74 97.50 1.008

.993 24 gn rus 9393 og._vu o7 Sn i_gnn oo3 E

21 93.82 9882 94.21 95.50 1.014

.996 2

22 61.94 9975 61.05 66.30 1.086 1.015

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la 1o 2'-?0 1 ?75 902 2'

il 24 0.00 0

3.10 0.00 0.000 0.000 i(

297 2

3L l

E AVERAGE DAILY GENERATOR GROSS 742.20 MWH(E)

D3 AVFR AGC-D AT4,Y-THE RM Al,-POWER 94 4 A54 4Wil4-T 1 AVERAGE DAILY TURDINE GROSS HEAT RATE 9072 BTU /UWil

'3 AVERAGE DAILY MWTH POWER 87.582 */aFP

- AVE R AGEr-DA I LY-N UCLE A R-IJ4 G T-,--POWE R 99.446 a ATJ-37

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RATJMF-N T---TO-NWTH =-1,024 f

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DATE 12, 8,80

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HOUR GMWE TURB G NWTH NI RATIO RATIO (E710)

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(P753)

(P723)

NI/MT M E,'M T 4

C 1

• /*FP BTU /KWH

• /*FP

• /=FP

• /*FP

• /*FP e

1 0.00 0

1.43 0.00 0.000 0.000

(* [

2 0.00 0

1.55 0.00 0.000 0.000 7

3 0.00 0

1.63 0.00 0.000 0.000 4

0.00 0

1.63 0.00 0.000 0.000 to-5 0.00 0

1.67 0.00 0.000 0.000 (U

6 0.00 0

1.67 0.00 0.000 0.000 3

7 0.00 0

1.75 0.00 0.000 0.000 is 0

0.00 0

1,71 0.00 0.000 0.000

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0.00 0

1.75 0.00 0.000 0.000 E

10 0.00 0

1.75 0.00 0.000 0.000 to 11 0.00 0

1.79 0.00' O.000 0.000 s

( 6 12 0.00 0

1,79 0.00 0.000 0.000 3

13 0.00 0

1.84 0.00 0.000 0.000 i,

14 0.00 0

3.34 0.00 0.000 DTEUD

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E 15 0.00 0

1.84 0.00 0.000 0.000 2

16 0.00 0

1,39 0.00 0.000 0.000 7

n' 17 0.00 0

3.06 5.70 1.864 0.'000 Y

i(

22 18 0.00 0

10.32 15.70 1.522 0.000 E

9 19 15.54 15019 20.27 27.80 1.372

.767 25 20 53.38 10371 54.20 63.90 1.179

.986 g(

=

21 70.50 10035 70.72 79.90 1.130

.997 i

n 22 81.24 9930 01.40 83.60 1.008

.998 k

i n

23 94.82 9959 96,13 98.80 1.028

.9G6 i

a' 24 96.61 9908 97.47 99.20 1.018

.991 30 f

146.01 PiWM( E )

l AVERAGE DAILY GENERATOR GROSS 472.12 MWil(I) a S'

AVERAGE DAILY THERMAL POWER I @

AVERAGE DAILY TURBINE GROSS HFAT RATE 271D FTU/KWH 19.255 -/aFP I

2 AVERAGE DAILY MWTH POWER AVERAGE DAILY NUCLEAR INST. POWER 19.983 */*FP n

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39 9

RATIO OF NI TO MWTH = 1.038

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e Tual 3urnup by Core Region Item 2

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Event Daca:

12/8/80 4

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The burnup was calculaced ac 102.5 EFFD for the tkree (3) enrichment regions.

t REGION NUMB R of FA BURNUP l

Batch 8

9 20,919 M/M l

60 18,780 M/M

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D 52 8,166 M/M' E

56 2,537 MyD/MTU_

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CLEANUP FLOW HISTORY ITEM 3 EVENT DATE:

12/8/80 C

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i I_ tem 3 Cleanup flow history forty-eight (48) hours prior to the first sample in which the limit was exceeded indicated a letdown flowrate of forty three (43)gpm.

The "B" Makeup & Purification Demineralizer was in service.

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.c Degas Operations Item 4 Event Date:

12/8/80 DATE TIME LOCATION

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12/6/80 0556 PZR 12/6/80 1140 "C" WGDT i

12/6/80 1420 PZR 1

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f Tim Duration When DEI-131 Exceeded 1.0 u C1/ gram and I-131 nalysis Results Item 5 Evene Data:

12/8/80

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....m.,,

e ITEM 5 As per Technical Specification 3.4.8, the four (4) hour sampling frequency as depicted on the table below was initiated at 0930 on 12/8/80 and the Dose Equivalent I-131 was 1.45 microcuries per gram. The four hour sampling frequency was terminated at 2230 on 12/8/80 when the DEI-131 was determined to be.386 microcuries per gram. The time duration when the specific activity of primary coolant exceeded 1.0 micrucuries per gram Dose Equivalent is fourteen (14) hours.

DATE TIME DEI-131 12/8/80 0930 1.45 12/8/80 1030 1.36 12/8/80 1430 1.32 12/8/80 1830 1.52 12/8/80 2230

.386 l

12/9/80 0332

.617 12/9/80 0812

.457 l

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