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LER 79-007/03L-0 on 790117:reactor Coolant Dose Equivalent I-131 Exceeded 1.0 Mci.Caused by Expected Transient Spikes Following Reactor Trip & Known Leaking Fuel Pins
	ML19296A225
Person / Time
Site:	Crystal River
Issue date:	02/09/1979
From:	Cooper J; FLORIDA POWER CORP.
To:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19263C366	List: ML19263C364; ML19296A225;
References
	LER-79-007-03L, LER-79-7-3L, NUDOCS 7902220044
	Download: ML19296A225 (55)
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, g , Chem / Rad sampling revealed that the Reactor Coolant Dose Equivalent I-131 ;

o , t exceeded 1.0 microcuries oer gram contrarv to Technical Soecification 3.4.S.P ois I No safety ha:ard as RCS clean un reduced DET-131 to accentable levels. I

, , , , Redundancy N/A. Fcr the 17 January event, DEI-131wasiluci/ gram at 0200 or,

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SUPPLEMENTARY INFORMATION Report No.: 50-302/79-007/03L-0 Facility: Crystal River Unit #3 Report Date: 9 February 1979 Occurrence Date: 17 January 1979 and 30 January 1979 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.

Canditions Prior to Occurrence:

First event: Mode 3 hot standby (0%), Second eveat: Mode 3 hot standby.

Description of Occurrence:

At 1315, 17 January and again at 0630, 30 January following a reactor trip, Chem / Rad primary coolant sampling revealed that the Dose Equivalent I-131 exceeded 1.0 microcuries per gram of primary coolant.

For 17 January, Dose Equivalent I-131 was 3.61 microcuries per gran and for 30 January, Dose Equivalent I-131 was 2.46 microcuries per gram. In both cases, Action Statement 3.4.8 was entered and the four (4) hour sampling frequency was initiated. For the 17 January event, the Dose Equivalent I-131 had returned to within acceptable limits of 1.0 microcuries per gram at 0200 on 19 January 1979. For the event of 30 January, the Dose Equivalent I-131 had returned to within acceptable limits of 1.0 microcuries per gram at 1435, on 31 January 1979.

Designation of Apparent Cause:

These events were due to expected transient spikes following a Reactor trip and known leaking fuel pins.

Analysis of Occurrence:

There was no safety hazard to the plant or general public as sampling demonstrated reducing levels of DEI-131. Both transients were within the capabilities of plant purification systems.

Corrective Action:

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

Failure Data:

This is the eighth and ninth occurrence of an er_nt of this type.

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Reactor Power History of Prior Forty-eight Hours

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Item 1 Event Date: 17 January 1979 i

DATE 1 ,1 5 , 7'-

HOUR GMWE TURB G riW'H NI RATIO RATIO (C710) (T856) (P753) (P723) NI/MT ME/iiT a/aFP BTU /KWH '/aFP a/aFP--- a/aFP a/aFP 1 98.44 9892 99.71 100.80 1.011 . 987 2 98,42 9900 99.80 100.90 1.011 . 986 3 98.28 - - - 9892 - --99.55 -- 100;70--- 1.-012 . 987 4 98.56 9888 99.80 100,90 1.011 . 988 5 98.55 9890 99.80 100.80 1.010 . 988 6 98.41 9903 99.-80 100.90-- 1.011 . 986 7 98.53 9896 99.84 100.90 1.011 . 987 8 98.50 9899 99.84 100.60 1.008 . 987 9 98.42 10225 -99.-51 100.50- l.010 . 989 10 98.40 9912 99.84 100.40 1.006 . 986 11 98.02 9899 99.35 100.10 1.006 . 987 12 97.44 -9891 --98.65----99.-70 iT011 -- - 988 -

13 97.45 9886 98.65 99.80 1.012 . 988 14 97.42 9884 9 8 . /,1 99.90 1.013 . 938

-15 97.49 - - -- 9 8 7 9 96 .- 6 9---- -99d0 1.-0 0 9-- . 988 - - - --

16 97.59 9881 c3.86 99.60 1.008 . 987 17 98.13 9879 99.39 101.30 1.019 . 987 18 98.27 9879 - 4 9.51 - 00.90 1.-014 - ;988-19 98.82 9883 100.00 100,10 1.001 . 988 20 98.71 9885 99.92 100.10 1.002 . 988 21 98.71 9885 99.92 -100 -10 1.002- . 988-22 98.74 9886 99.96 100.20 1.002 . 938 23 98.80 9880 99.92 100.20 1.003 . 989 24 98.75 9881 99.92 100.20---1.003 . 988

. __.. _ _e AVERAGE DAILY GENERATOR GROSS 840.34 MUH(E)

AVEPAGE DAILY THERMAL POWER 2440.58 MWH(T)

AVERAGE DAILY TURBINE--GROSS HEAT RATE -9903-BTU /KWH AVERAGE DAILY MWTH POWER 99.534 a/aFP AVERAGE DAILY NUCLEAR INST. POWER 100.383 a/aFP RATIO OF NI TO MWTH = 1.009 n -

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DATE 1,16,79 HOUR G riWE . .._TURB_G FjWIH NI RAIlCL _ _ R ATIO (E710) (T856) (P753) (P723) NI/MT ME/MT a/=FP BTU /KWH a/aFP a/=FP */=FP a/aFP 1 98.76 9882 99.92 1002 30 1.004. .983 -.

2 98.81 9877 99.92 100.40 1.005 .989 3 98.77 9884 99.96 100.30 1.003 .988 4 98.74 9887 992 9_6 1 0.0_ 3 0 1 m 0.0 3 _ _ _ ._9 8 8 .. -_ _

5 98.80 9886 100.00 100.20 1.002 .988 6 98.75 9892 100.00 100.20 1.002 .987 7 98.76 9892 100.04 100.40 1 004 .987 8 98.80 9890 100.04 100.50 1.005 .988 9 98.64 9886 99.84 100.30 1.005 .988 10 .._98 50 9_894 99_,_a_0 10 D 0 i m005__ _ 987 11 98.60 10209 99.59 100.00 1.004 .990 12 98.20 9893 99 47 100.00 1.005 .987 13 98.39 9888 99 u 39 100.20 L3 0 6_ _ , 9 8 8. ..-

14 98.80 9877 99.92 100.30 1.004 .989 15 98.60 9887 99.80 100.10 1.003 .988 16 98.56___.. . 9 8 8 5._ ___9.9 . 7 6 _ _10 L.0 0_ _. . 1. 0 0 2 _ .988. - .

17 98.82 9883 100.00 100.30 1.003 .988 18 98.83 9885 100.04 100.30 1.003 .988 19 98.85 9 8 8 '+ _ 10 0..Q 4 __._1 0 0. 3 0 .__ . 1_. 0 0 2 _ .988 20 9G.85 9882 100.00 100.30 1.003 .98?

21 98.77 9887 100.00 100.20 1.002 .988 22 98.90 9873 99. 96-_ 100.30._ 1.003 .989 23 98.83 9881 100.00 100.40 1.004 .988 24 98.83 9882 100.00 100.30 1.003 .988 AVERAGE DAILY _ GENERATOR. GROSS __. ____.._84L 01 MWH(E)_

AVERAGE DAILY THERMAL POWER 2449.58 MWH(T)

AVERAGE DAILY TURBINE GROSS HEAT RATE 9899 BTU /KWH AVERAGEJAILY fiWTH POWER - -

_9S.901 a/aFP AVERAGE DAILY NUCLEAR INST. POWER 100.258 a/aFP RATIO OF NI TO MWTH = 1.004

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UATE 1,17,79 HOUR GMWE TURB G MUTH NI RATIO RATIO (E710) (T856) (P753) (P723) NI/MT ME/MT a/~FP BTU /KWH -f=FP -/ FF -/=FP a / a F P - -- - - - -

1 98.94 9871 100.00 100.00 1.000 .989 2 98.89 9873 99.96 100.20 1.002 .969 99--88 1-00-10 3 - 98 r83 9971 1.002- .990 4 98.71 9881 99.88 100.10 1.002 .968 5 98.71 9880 99.88 100.10 1.002 .988 6 -98.70- -9081 99--98 100710 1.002 7988 - - -

7 98.83 9883 100.00 100.30 1.003 .988 8 98.71 9891 99.96 100.40 1.004 .988 9 -98.70 -9893-- -100--00 1110740 17004 ~.987'--- -

10 98.54 9888 9o.76 100.20 1.004 .988 11 38.90 9888 43.64 41.90 . 960 .991 12-- - 0700 J .00 U.00 0.000 0 : 0 0 0 --

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.00--- 0.00 0.000 0.000 AVERAGE DAILY GENERATOR GROSS 365.68 MWH(E)

AVERAGE DAILY THERMAL POWER 1065.42 MWH(T)

AVERAGE DAILY TURDINE-GROSS ~ HEAT-RATE 4529-BTU /KWH AVERAGE DAILY MUTH POWER 43.451 + /=FP AVERAGE DAILY NUCLEAR INST. POWER 43.492 a/*FP RATIO OF NI TO MUTH = 1.001 e

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Fuel Burnup by Core Region Item 2 Event Date: L7 January 1979

Item 2 The burnup was calculated at 370 EFFD for the four (4) enrichment regions.

REGION NUMBER of FA ~BURNUP A 52 12170 WD/M B 61 12383 WD/M C 60 8304 M/M Oconee 4 13115 "I Ave. 17,/

WD/MTU 11059 i

Clean-up Flow History Item 3' Event Date: 17 January 1979 e

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Item 3 Cleanup flow history starting forty-eight (48) hours prior to the first sample in which the limit was exceeded is as follows:

DATE TIME LETDOWN FLOW DEMIN 1/15/79 0120 50 GPM 1/16/79 0010 50 1/16/79 0150 1/17/79 0005 48 G?"

1/17/79 1315 46 A 1/17/79 1715 46 A 1/17/79 2115 48 A 1/18/79 0118 100 " A 1/18/79 0300 100 " A 1/18/79 0600 100 " A 1/18/79 1005 100 " A 1/18/79 1415 100 " A 1/18/79 1800 90 " A 1/18/79 2200 90 " A 1/19/79 0200 90 " A 1/19/79 0555 90 " A

No History of Degassing Operations For This Report Item 4 Event Date: 17 January 1979

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Ti=e Duration When DEI-131 Exceeded 1.0 y C1/ gram and I-131 Analysis Results Item 5 Event Date: 17 January 1979 O

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i ITEM 5 As per Technical Specification 3.4.8, the four (4) hour sampling frequency as depicted on the table below was initiated at 1315 on 17 January 1979 and the Dose Equivalent I-131 was 3.61 microcuries per gram. The four (4) hour sampling frequency was terminated at 0555, 19 January 1979 when the DEI-131 was determined to be 0.69 microcuries per gram.

DEI-131 was5 1 p C1/ gram at 0200, 19 January 1979, when the sample results were 0.96u C1/ gram. The time duration when the specific activity of primary coolant exceeded 1.0 pCi/ gram Dose Equivalent is 41 hours4.74537e-4 days 0.0114 hours 6.779101e-5 weeks 1.56005e-5 months .

DATE TIME DEI-131 (uCi/ gram) 1/17/79 1315 3.61 1/17/79 1715 4.19 1/17/79 2115 4.50 1/18/79 0113 3.79 1/18/79 0300 3.58 1/18/79 0600 2.84 1/18/79 1005 3.21 1/18/79 1415 2.52 1/18/79 1800 1.96 1/18/79 2200 1.32 1/19/79 0200 0.96 1/19/79 0555 0.69

Reactor Power History of Prior Forty-eight Hours

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Item 1 Event Date: 30 January 1979 i

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AVER.,GE DAILY TIlERMAL POWER 1750.30 MUH(T)

A V E r v.G E D A I L ET U R B I N E. . G R O S S. H E A T. f. ,iT E 7957 BTU /KWH AVERAGE DAILY MWTH POWER 71.639 +/oFP AVERACE LAILY NUCLEAR INST. POWER 74.380 a/oFP R ;-4 T I U GF n1 TO .-i W T H - 1 033

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24 90.30 9379 90.90 93.90 1.000 .999

,T/ERAGE DAILY GENERATOR GROS 5 806.06 MWH(E)

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AVERAGE D AIt T- THERMAL POWER ~ 2322.2?'MWH(T) s AVERAGE DAILY TURBINE GROSS HEAT RATE 9338 BTU /KUH MERAGE DAILY MUTH POWER 94.710 o/cFP AVERAGE DAIL',' NUCLEAR INST.~ POWEi' 95.000 </aFP RATIO OF-'N1~TO MWTH = r'004 ~~ -

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_ 13 12.'46 1'+022 ~;2.04 22.30 . 998 . 545 ._ _ 1 11 .17.33. 1300.0 ~1 u0 0 3l - 90 . 997 . 577 , . - , e- .e 4 r , c- a- - Id e .- 10.30 1.n c._, e- .s .t ca us ..s iu i . n041 v . s s - is 46.80 10320 52.00 32.30 1.006 . 900 -___ 17 .49.m 1D 2th S tu 13. _ _ R 20_ _.1.001 . 920 .n ic s.,_ , ,a s e ., idne, .s. c -- ,- a . . a o,, .-.,,.o,. 4 . 000 . 710 - 1- Uti.14 10192 56.97 5~,30 1.006 . 913 - _ 20 ;+ 7 . 2 7- ___1031?_ '5 Li..90 55 20_ ! u0 0 '1 . 006 1 98 19 10515 50."5 31 00 1.000 . 945 ^2 4 .: 30 , 10326 54.00 55.00 1.000 . 900 23 *a9.79 10331 5 4. 9 0 ~ 5 . 0_0 _______ 1. 0 0 0 ,- 90o 006 _ _ N I47 79 10327 54.93 55.00 1.000 . riVERAGE DAILY GENERATOR GROSS 364.27 MWH(E) MERADE DAILY T H E R h A L ..P.0 tJ E 'i __ .. 1128 '58 t MWH ( T) ._ n /ET: ADE DAILY TURBINE GROSS HEAT RATE 7986 DTU/i(WH Ai2 RAGE DAIL, MUTH POWER 'vo . 0 27 e / e FP AVERADE DAILY NUCLEAR. INST,_POWEn ut.063 */oFF T:ATIO OF NI._TO.MWTH = 1.001 ._ _._ _ _ _ - - * . e e- . .m -u.o-- --e % w..mmw w = - - - - w .- ee-- e.- m e *- m.- eu.6-eme-* * -ie wem eu.- e em wh -. *-e .--um==mN Fuel Burnup by Core Region Ites 2 Event Date: 30 January 1979 2 ITEM 2 The burnup was calculated at 381 EFPD for the four (4) enrichment regions. REGION NUMBER OF FA BURNUP A 52 12521 MWD /MTU B 60 13267 MWD /MTU C 61 8599 MWD /MTU Oconee 4 13359 MWD /MTU Ave. 177 11441 MWD /MTU Clean-up Flow History Item 3 Event Date: 30 January 1979 ITEM 3 Cleanup flow history starting forty-eight (48) hours prior to the first sample in which the limit was exceeded is as follows: DATE TIME LETDOWN FLOW DEMIN 1/28/79 0100 70 GPM 1/29/79 0010 47 GPM 1/30/79 0130 70 1/30/79 0450 70 1/30/79 0630 48 A 1/30/79 1030 48 A 1/30/79 1425 70 A 1/30/79 1820 70 A 1/30/79 2230 70 A 1/31/79 0230 75 A 1/31/79 0630 49 A 1/31/79 1030 48 A 1/31/79 1435 48 A 1/31/79 1930 50 A No History of Degassing Operations For This Report Item 4 s Event Date: 30 January 1979 i Time Duration When DEI-131 Exceeded 1.0 p C1/ gram and I-131 Analysis Results Item 5 Event Date: 30 January 1979 4 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 0603 on 30 January 1979 and the Dose Equivalent I-131 was 2.46 microcuries pergram. The four (4) hour sampling frequency was terminated at 1930, 31 January 1979 when the DEI-131 was determined to be 0.68 microcuries per gram. DEI-131 wassluC1/ gram at 1435, 31 January 1979 when the sample results were 0.83 uCi/ gram. The time duration when the specific activity of Primary Coolant exceeded 1.0 pCi/ gram Dose Equivalent is 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months . DATE TIME DEI-131 (uci/aram) 1/30/79 0630 2.46 1/30/79 1030 3.69 1/30/79 1425 4.74 1/30/79 1820 3.08 1/30/79 2230 2.37 1/31/79 0230 2.10 1/31/79 0630 1.39 1/31/79 1030 1.16 1/31/79 1435 0.832 1/31/79 1930 0.680 -

ML19296A225

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