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LER 80-042/03L-0:on 801008,dose Equivalent I-131 Exceeded 1.0 Uci/G Creating Event Contrary to Tech Spec 3.4.8.Caused by Leaking Fuel Pins & Anticipated Iodine Transient Following RCS Transient.Purification Flow Increased
	ML19340B584
Person / Time
Site:	Crystal River
Issue date:	11/05/1980
From:	Hernandez V; FLORIDA POWER CORP.
To:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19340B582	List: ML19340B581; ML19340B584;
References
	LER-80-042-03L, LER-80-42-3L, NUDOCS 8011110328
	Download: ML19340B584 (13)
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,,,,, ; The cause of this event is attri uted to leaking fuel pins and an anticipated ,

, , , , , Iodine transient following a Reactor Coolant System transient. Reactor Coolant ,

, , purification flow was increased; Dose Equivalent I-131 was less than 1.0 microcuriep

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SUPPLEMENTARY INFORMATION Report No.: 50-302/80-042/03L-0 Facility: Crystal River Unit #3 Report Date: 5 November 1980 Occurrence Date: 8 October 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 1 power operation (98%)

Description of Occurrence:

At 1126 during Reactor startup after a Reactor trip it was discovered that Pese Equivalent I-131 exceeded 1.0 microcuries per gram. This determination was made by analysis of a Reactor Coolant sample drawn at 0850. Redundancy was not applicable.

Designation of Apparent Cause:

The cause of this event is attributed to leaking fuel pins and an anticipated Iodine transient following a Reactor Coolant System transient.

Analysis of Occurrence:

There was no effect upon the general public health or safety.

Corrective Action:

Reactor Coolant purification flow was increased to aid cleanup. Dose Equivalent I-131 was less than 1.0 microcuries per gram at 1259.

Failure Data:

This is the eighteenth event reported under this specifica-tion.

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Reactor Power History of Prior Forty-eight Hours

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.=. 5 96.40 6 94.16 9T D0

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d5 9 99.39 tbD. \D

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.lt 1: 99.31 100.18

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d' 19 19 43 100 .30 E. !S 99.34 too.20 16 99.31__-100.20 . . _ _ _ _ . _ _ . . . _

i- 17 99.23 100 ED

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99,74,_.100 60. _ _ _ _ _ _ _ _ _ _ . . . _ _ _ _

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T DATE 10, 7,80 Y _. . .

4 I HOUR GMWE- TURB G MWTH NI RATIO RATIO WI7MT- ME/MT

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/*FP =/*FP y */=FP BTU /KWH */=FP */*FP s, *1 95.81 10007 98.04 99.30 1.013 .977 w '2-- 95 80 ~10543 ~98 04 99-10 1T011 . 9 77 - ' -- - ~ -- - --

U 3 95.79 10005 98.00 99.00 1.010 .977 E '4 95.88 9995 ~

98.00 98.90 ~

1.009 .978

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u 5 9E23 9861 ~9G72~ 93. 8 0-- 1.~ 023 -~.995-E 6 95.18 - 10002 97.31 98,20 1.009 .978 E 7 97.45 9980 99.51 99.90 1.004 .979 ~ -'--

Tu 8 97 38 9 9 91-~~~~ 9 9; 55---- ~ 9 97 9 0 ~~~~ ~17 0 0 4-~~ ~ ~ ~. 978 ~ -

<W 9 97.37 9992 - 99.55 100.10 1.006 .978 E 10 97.44 9985 99.55 100.20 1.007 .979

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a9 11 97. 35~ i00'0'0 99743 100T40' C008-~ .977 E 12 97.32 10027 99.88 100.70 1.000 .974 E 13 95.98 10168 99.88 100.80 1.009 .961 100T80 T- 1V 97736 i~0018 99 80 17010-~ . 97E '-

E 15 97.36 9995 99.55 100.50 1.010 .978

. H 16 97.39 9990 99.55 100.3D 1.008 .978 97.36 99755

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25 i'7 999~6~- 100 30 17008----- 978' a 18 97.36 9993 99.55 100.20 1.007 .978

19 97.32 9991 99.47 100.00 1.005 .978

~~~ 2 0 " - '96;43 - ~9992 - 98;53 99. 1.006 -- .979 - --

i' T 21 96.25 9987 98.29 98.90 1.006 .979 I 22 96.25 9978 98.21 9P.70 1.005 .980

,. 23 96-21 9977 ---- ~ 98 16~ 78790 - ~1.007 7980 -- - - -

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24 96.46 9978 98.41 99.00 1.006 .980 E - -- --- - _. _ - _ _ _ -- _ -

J AVERAGE DAILY GENERATOR GROSS 824.97 MWH(E)

~-~ 2419. 04 MWH ( T)'

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AVERAGE DAILY THERMAL POWER -~~- ~ ~~~

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AVERAGE DAILY TURBINE GROSS HEAT RATE 10019 BTU /KWH f AVERAGE DAILY MWTH POWER 98.656 */*FP AVERAGE DAILY NUCLEAR INST. POWER ~ ~ ~ ' 9 9 . 4 5 8 - = / = F P -- --~ -

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4 Ti F ~ RATIO ~OF NI TO MWTH =~T.008 -~ - - - - -

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HOUR GMWE TU RB .G NWTH NI RATIO ~_ RATIO _

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/=FP BTU /KWH */=FP */=FP =/=FP =/*FP 9 1 13.08 0 14,93 13.-70 .918 .874 _-

1 2 0.00 0 .00 0.00 0.000 0.000 I

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E 5 0.00 0 .41 0.00 0.000 0.000

' f. 6 .16 196 7.59 10.00 1.318 .P22

" 7 18,56 15182 25,98 _.31,00 _.1,193 ..714 . . _ .

3 8 51.26 11068 56.36 60.60 1.075 .910

' E 9 84.34 9908 84.99 97.50 1.147 .992 "5

14 - 93.64 9945 95,19 38.00 1,030_._ 984 _ _ _ _

d 11 93.13 9939 94.62 98.40 1.040 .984 IE 12 93.37 9938 94.82 98.40 1. 0 3f. .985

98,40 1.03E .S84

- 13 93147 9953 95.02 _ _ _ _ _ _

5 14 93.45 9959 95.07 98,20 1.033 .983 15 93.57 10526 95.11 98.30 1.034 .984 I( '

14 93,58 9958 OS E 08.3D 1.033 983 __

h- 17 93.95 9959 95.19 98.50 1.035 .987

. ( 3 18 94.02 9965 95.72 98.50 1.029 .982

- " 19 - -94,43 9948 94,41 98.80 1_ 025 -989

- 3 20 95.27 9976 97.15 99.00 3.019 .981 I'$ 21 95.78 9978 97.72 98.90 1.012 .980

-_22_ S6.02 9983 .98..D 4____ S9. D C . _1. 010 - ..__ . 9 7 9._ .._ . _.

- E 23 96.23 9985 98.29 99.00 1.007 .979 s* .:_ 24 96.42 9973 98.37 99.10 1.007 .980 u.

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' E E -AVERAGE-DAILY-GENERATOR.. GROSS- -_ 564. 28 MWH(FJ _ _ _ _

i. AVERAGE DAILY THERMAL POWER 1668.33 MWH(T)

' 2' AVERAGE DAILY TURBINE GROSS HEAT RATE 7765 BTU /KWH A._ AVERAGE DAILY MWTH POWER . _ . 68.040 */aFP ___.

2 AVERAGE DAILY NUCLEAR INST. POWER 70.492 */=FP s

RATIO OF NI TO MWTH = 1.036 T

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ITEM 2 The burnup was claculated at 45.2 EFPD for the three (3) enrichment regions.

BATCH NUMBER of FA BURNUP B 9 MWD /MTU 19272 C 60 MWD /MTU 17096 D 52 MWD /MTU 6105 E 56 MWD /MTU 1110 AVE. MWD /MTU 8920 J

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CLEANUP FLOW HISTORY ITEM 3 EVENT DATE: 8 October 1980 9

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l ITEM 3 Cleanup flow history forty-eight (48) hours prior to the first sample in which the limit was exceeded indicated a letdown flowrate of fifty (50) gpm.

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DATE TIME FLOWRATE 10/6/80 0050 50 gpm 10/7/80 0030 50 gpm 1

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Degas Operations Item 4 Event Date: 10/8/80

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DATE tit!E Location 10/6/80 2142 WGDT-C (d

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Time Duration When DEI-131 Exceeded 1.0 u C1/ gram and I-131 nalysis Results Item 5 4

Event Data: 8 October 1980

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i ITEM 5 As per Technical Specification 3.4.3, the four (4) hour samplirs frequency as depicted on the table below was initiated at 0850 on 8 October 1980 and the Dose Equivalent I-131 was 1.05 microcuries per gram. The ,four hour sampling frequency was terminated at 1650 on 8 October 1980 when the DEI-131 was determined to be .485 microcuries per gram. The time duration when the specific activity of primary coolant.excee.ded 1.0 microcuries per gram Dose Equivalent is less than four (4) hours.

DATE TIME DEI-131 (pCi/ gram) i 10/8/80 0850 1.05 10/8/80 1250 .665 10/8/80 1650 .485 t

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ML19340B584

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