05000302/LER-1978-004-03, /03L-0:on 780108,reactor Coolant Dose Equivalent I-131 Found Contrary to Tech Spec Limitations.Caused by Transient Spikes Following Reactor Trip & Known Leaking Fuel Pins.Corrective Action Unnecessary

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/03L-0:on 780108,reactor Coolant Dose Equivalent I-131 Found Contrary to Tech Spec Limitations.Caused by Transient Spikes Following Reactor Trip & Known Leaking Fuel Pins.Corrective Action Unnecessary
ML19308D356
Person / Time
Site: Crystal River 
Issue date: 01/31/1978
From: Cooper J
FLORIDA POWER CORP.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19308D350 List:
References
LER-78-004-03L, LER-78-4-3L, NUDOCS 8002270813
Download: ML19308D356 (13)
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LER-1978-004, /03L-0:on 780108,reactor Coolant Dose Equivalent I-131 Found Contrary to Tech Spec Limitations.Caused by Transient Spikes Following Reactor Trip & Known Leaking Fuel Pins.Corrective Action Unnecessary
Event date:
Report date:
3021978004R03 - NRC Website
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E I Coolant Dose Eouivalent I-131 was 1.11 microcuries per tram contrary to the r Lo_14}I14"4tations as set by Tech. Spec. 3.4.8. No safety implicatip.7s. Redundancy i

fo"Til I *f A. ' Third neem venen o f *S f e event as renarted by TM 's 77-67 and 77-91.

i m iThe DE-I131 returned to acceptable lever at 1000 on 8 January 1978.

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SUPPLE 12NTARI INFORMATION eport No.:

50-302/78-04/03L-0 2.

Facility:

Crystal River Unic #3 3.

Raport Date:

31 January 1978 4

Occurrence Date:

8 January 1978 3.

Identification of Occurrence:

The Dose Equivalent I-131 was greater than 1.0 nicrocurie per gram of primary coolant contrary to Technical Specification 3.4.8.

6.

Conditions Prior to Occurrence:

Mode 1 operation.

7.

Description of Occurrence:

At 0600, following a reactor trip and in the process of plant startup, operations was notified by the CHEM / RAD section that the Primary Coolant Dose Equivalent I-131 was 1.11 microcuries per gram. Action scacement 3.4.8.a was entered and the four hour sampling frequency was initiated. The Dose Equivalent I-131 had returned to acceptable technical specification limit of.73 microcuries per gram at the 1000 sampling. The action statement was satisfied and plant operations proceeded uneventful.

.gDesignation of Apparent Cause:

This event was caused by the expected transient spikes following a reactor trip and known leaking fuel pins.

9.

Analysis of Occurrence:

There was no safety hazard to the plant or general public due to this event as sampling demonstrated reducing levels of Dose Equivalent I-131.

10.

Cotractive Action:

Ne corrective action necessary as reactor coolant cleanup returned the Dose Equivalent I-131 to acceptable levels within four hours.

11.

Failure Data:

This is the third occurrence of this event as reported by LER's 77-67 and 77-91.

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REACTOR POWER HISTORY OF PRIOR FORTT-EIGT HOURS ITEM I e

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DATE-1.

4,73 HOUR MWHT NI RATIO (N753)

'(P723)

NI/MT

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  • /*FP
  • /*FP
  • /*FP 1:00 100.041 100.700 1.007 2:00 100.122 100.700 1.006

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  • 3:00 100.082 100.700 1.006 4:00 100.000 100.600 1.006 5:00 99.878 100.600 1.00<

<6:00 99 873 100.600 1.007 7:00 99.755 100.500 1.007 3:00

- 99.796 100.400 1.006 9:00 99.633 100.300 1.007 10:00 99.592 100.200 1.004

- ~11:00 99.633 100.300 f.007

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12:00 99.592 100.400 1.008 13:00 99.633 100.300

1. 0 0.'

I4: 00 99.592-- -

100.400 1.003

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15:00

! ~. !"5 9F. 6 100.400 1.512 16:00

' d. !"5 99. 6 100.400 1.512

' 17:00

  • * !. 2 2'; ff.3-100.303

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13:00 99.470 100.300 1.003 19:00 99.511 100.400 1.009 20:00 99.592 100.500 I.009 21:00 99.796 100.700 1.009 22:00 99.837 100.700 1.009 23:00 99.755 100.500 1.007 24:00 99.551 100.400 1.009 i

AVERAGE. DAILY MWTH POWER 97.640 */*FP 4

- AVERAGE DAILY NUCLEAE INST. POWER 100.471 */3FP -'

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' - ' RATIO OF NI TO MWHT = 1.029

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7,78 7

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HOUR MWHT NI RATIO (N753).

_ */*FP

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(P723)

. */*FP

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1:00 99.592 100.500 1.009 2.:00

__.99.551 __

_.1.C 0 5 0 0 1.010 3:00 99.551 100.500 1.010 0

4:00

.-ess-9ts.sv 10 0. 0 0 0 5 : 0 0__.._9 9. 551... ___. 10 0_, j5 0 0.

...__.1. 010 6:00 99.551 100.600 1.011 O

7:00 99.429, 100.400 1.010 B.LO 0_.. _.9.9_,.10 3 100.100. _.... 1.010...

9:00 98.980 100.000 1.010 0

10:00 99.021 100.000 1.010

.?___. 1 1.:_0 O__ _ 9 9.,.0 2 1...._

10.0_i.0.0.0

_ 1 01_0_

12:00 99.062 100.000 1.009 O

13:00 99.062 100.000 1.009

.._1_4:00

... 99.021

._10.0.000 __

1.0_10 15:00 98.980 100.000 1.010 0

16:00 98.980 100.000 1.010 17:00 99.062 100.100 1.010 18:00 99.103, 100.200 1.011 0

19:00 99.225 100.300 1.011 20:00 99.184 100.300 1.011

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21:00 99.134 100.400 1.012 0

22:00 96.336 97.600 1.013

\\23:00 72.471 75.100 1.036 s

24:00 59.625 62.700 1.052 O'

O AVERAGE DAILY MWTH POWER 92.202 */*FP AVERAGE D AILY NUCLEA R INST... POWER

.. ___9.7.J+92._*/ *F_P__.

O RATIO OF NI TO MWHT = 1.057.

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DATE 1.

8,78 0(m'

\\O' HOUR MWHT NI RATIO (N753)

.. ( P.7 2 3 ) _ _ _ _._. N I / M T.___ _.

=/*FP

  • /*FP
  • /*FP O

1:00 58.809 69.400 1.180

.. 2:00

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...0.000

.0.000 3:00

.000 0.000 0.000 O-4:00

.000 0.000 0.000

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6:00 10.359 8.800

.850 0

7:00 16.395 16.600 1.013

.S:00_.._20.634

'8.300.._

_. 1 371 9:00 30.914 39.300 1.271 0

10:00 48.940 57.200 1.169

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50.000

..._55.700

... _1.114._ -

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12:00 52.610 57.500 1.093 13:00 67.333 71.900 1.068

.__14 : 0 (L.. 6 9. 841

.72.900 1.043 15:00 70.024 73.200 1.045 O

16:00 49.209 72.600 1.049

. 17:00... 88.091

90. 200 1.024 f.

18:00 91.028 92.300 1.014 O

19:00 91.150 92.300 1.013 20:00 91.109 92.100 1.011 21:00 89.927 91.200 1.014 22:00 63.214 66.700 1.055 23:00 61.419

. _ _6 5. 0 0 0 ___. _ __ 1. 0 5 8....__.

24:00 61.705 65.200 1.057 O

OI AVERAGE DAILY MWTH POWER 50.114 */*FP

_ AVERAGE._ DAILY NUCLEAR. INS ~f' POWER _. _._53.267__ab RE O' '

. RATIO OF NI TO MWHT = 1.063 O.-

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FUEL BURNUP BY CORE REGION ITEM 2 i

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ITEM 2 i

i the burnup was calculated at 227.1 EFPD for the three enrichment regions.

l REGION NUMBER OF FA BURNLT A

56 0043 mfd /Mr B

61 8166 MID/MT C

60 4457 NHD/Mr AVE.

6870 Mwu/Mr l

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CLEAN-UP FLOW HISTolti ITEM 3 r

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e ITEM 3 DATE TIME DEMIN IN SERVICE LETDOWN FLOW uci/ GRAM i

8 Jm. 78 0600 B

100 GPM 1.1 8 Jm. 78 1000 B

100 GPM

.73 8 Jm. 78 1435 B

100 GPM

.51 4

8 Jm. 78 1950 3

100 GPM

.28 9 Jm. 78 0130 B

100 GPM

.35

i 9 Jm. 78 0615 3

100 GPM

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l NO HISTORY OF DECASSING OPERATIONS FOR THIS REPORT ITEM 4 i

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1 TDE DURATION WHEN DEI-131 EXC2DED 1.0 uci/ CRAM AND I-131 ANALYSIS Rt.SULTS I

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e As per Technical Specification 3.4.8:

i The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> sampling frequency was initiated at 0600 on 8 January 1978 and the dose aquivelant I-131 was 1.11 microcuries per gram. The 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> sampling frequency was terminated at 1000 when the DEI-131 was determined to be.73 microcuries per gram.

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