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LER 78-008/03L-0:on 780122 During Sampling,Reactor Coolant Dose Equivalent I-131 Found to Be 1.42 Uci Per Gram.Caused by Transient Spikes Following Trip & Leaking Fuel Pins.No Action Needed
	ML19317G301
Person / Time
Site:	Crystal River
Issue date:	02/08/1978
From:	Cooper J; FLORIDA POWER CORP.
To:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19317G297	List: ML19317G296; ML19317G301;
References
	LER-78-008-03L, LER-78-8-3L, NUDOCS 8002280916
	Download: ML19317G301 (13)
	v • d • e

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. , ..s N AC F@CM 364 U. S. NUCLEAA RECULATp: V CoMMIS31oM e 0 171 LICENSEE EVENT REPORT EXHIBIT A ;

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3. it at. Car CA,4 80 i 4 svtNr otscaiPricN ANo raosAsLt ecxstcusNess go,2, [ Following a Reactor trip, Chem / d sampling revealed that the Reactor ,

, o ,,, , Coolant Dose Equivalent I-131 was 1.42 microcuries per gram contrary 'to ,

io .,,the li=itations set forth in Tech Spec 3.4.8. No safety hazards as RCS , ;

,, ,,, , cleanup reduced DEI-131 to acceptable levels. Redundancy NA. Fourth oc-

,, ,,, ; , currence of this event as reported by LER's 77-67, 77-91, & 78-004/-3L M . ,

gi The DEI-131 returned to acceptable level at 1720 en 22 Jan. 1978. , i laleIl **

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, , , o , l This event was caused by expected transient spikes folicwing a Reactor trip,

, , ; , , , and to ' mown leaking fuel pins. No corrective action necessary as the ,

,,, , ; Reactor Coolant cleanup returned the DEI-131 to acceptable level. ,

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. (SEE ATTACllED SUPPLEMENTARY INFORMATION SIIEET) 8002 280 7/6 g

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. . s SE LNARY INFORMATION 1 port No. : 50-302/ 78-008 /03L-0 V

2. Facility: Crystal River Unit #3

3. Report Date: 8 February 1978 '

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4. Occurrence Date: 22 January 1978 l

5. Identification of Occurrence:

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

6. Conditions Prior to Occurrence:

Mode 3 hot standby operation. l l

7. Description of Occurrence:

j At 0530, following a Reactor trip, Chem / Rad prinary coolant sampling revealed that f the dose equivalent I-131 was 1.42 microcuries per gram. Action Statement 3.4.8.a -

of Technical Specification 3.4.8 van entered and the four hour sampling frequency '

was initiated. The Dose equivalent I-131 had returned to an acceptable Tech Spec '

limit of .81 microcuries per gram at the 1720 sampling and the Action Statement was satis fied.

SO' .signation of Apparent Cause:

O This event was due to expected transient spikes following a Reactor trip and known laaking fuci pins.

9. Analysis of Occurrence:

Tnere was no safety hatard to the plant or general public as sampling demot.:;~r i reducing levels of DEI-131.

10. Corrective Action:

No corrective action necessary as Reactor coolant cleanup returned the DEI-131 to acceptable levels. -

11. Failure Data:

This is the fourth occurrence of this event as reported by 1ER's 77-67, 77-91, and l

l 78-004/03L-0.

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REACIOR POWER HISTORY OF PRIOR FORTY-EIGHT HOLTS ITEM 1 e

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. . .s DATE 1.20,73-i HOUR 'MWHT. RI ' RATIO i- !

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. 1:00 100.122 100.100 -1.000 2:00 100.122 100'.200 1.001

' ' 3:00 99.918' 100.100 1.002

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5: 00 ??.878 100.100 1.002 i 6:00 99.373 100,100 1.002 I

7:00. 99.918 100.100 1.002

.. 8:00 99.918 100.200 1.003

?: 00 99.913 100.200 1.003 I 2- 10:00 . 99.913 100,300 1.004.

11:00 99.?59 100.400 1.004

. 12:00 99.429 100.000 1.006

- 13:00 . 99.511 . 99.900 1.004

! 14:00 99.511 100.000 1.005 15:00 ??.338 99.500 1.004 '

' 16:00 99.266 .99.600 1.003.

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17: 00 99.383 99.600 1.002 13:00 99.715 99.900 1.002 1

19:00 100.408 100.500 1.001 .;

i 20.00 99.940 99.100 1.002 21:00 99.837 100.100 1.003 4 \ 22:00 99.878 100.200 1 003 i- 23:00 99.959 100.300 1.003 j 24:00 100.163 100.400 1.002 i

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! AVERAGE DAILY.dWTH FOWER 99..vo o, 2FP AVERAGE DAILY NUCLEAR INST. POWER 100.054 */*FP

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RATIO OF NI TO MWHT = 1.003

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14: 00 99.718 1.004 ;]

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99.'?18 100.200 20:00 100.200 1.003 21-00 99.973 1.003 09,G 3 100.200 22:00 100.000 1.003 23:00 99.718 1.003 97.759 100.300 24: 00

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.i ITEM 2 l The burnup was calculated at 239.6 EIPD for the three enrichment regions.

REGION NUMBER OF FA BURNUP

, A 56 8466 WD/MI B 61 8610 W"/E 1

c 60 4720 WD/Mr l AVE. 7246 WD/E ', l

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ITEM 3 l DATE TIME DEMDI IN SERVICE LETDOWN FLOW MICR0 CURIE / GRAM j 22 Jm. '78 0530 B 55 1.4 I 22 Jan. '78 0930 3 58 1.3 ,-

22 Jan. '78 1345 3 60 1.03 f-22 Jan. '78 1720 3 60 .81 22 Jan. '78 2155 A&B 100 .58

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NO HISTORY '

. 2 SING OPERATIONS FOR THIS REPORT ITEM 4 9 I e l I

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TIME DURATION 'REN DEI-131 EXCEEDED 1.0 uci/ GRAM AND j I-131 ANALYSIS RESULTS s1 ITEM S l

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% s -

ITEM S -

As per Technical Specification 3.4.8.

The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months sampling frequency was initiated at 0530 on 2~. January 1978 and the dose equivalent I-131 was 1.40 microcuries per gram. The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months sampling frequency was terminated at 2155 when the DEI-131 was decernined to be .58 microcuries per gram.

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ML19317G301

Text

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