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, e l rhis event was caused b, an expected spi'xe following a Reactor trip and known; leaking fuel pins. No c- &ctive action necessary.as the Reactor Coolant , | , e l rhis event was caused b, an expected spi'xe following a Reactor trip and known; leaking fuel pins. No c- &ctive action necessary.as the Reactor Coolant , | ||
System Purification returned the DEI-131 to within acceptable limits. , | System Purification returned the DEI-131 to within acceptable limits. , | ||
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: w. t c .ac bate( Js Cooper , Jr- , (90_4) 795-6486 | : w. t c .ac bate( Js Cooper , Jr- , (90_4) 795-6486 | ||
/ | / | ||
(SEE ATTACHF SUPPLEMENTARY INFOR'4ATION SHEET) * <51,3 | (SEE ATTACHF SUPPLEMENTARY INFOR'4ATION SHEET) * <51,3 79001105/O s | ||
79001105/O s | |||
Supplementary Information Report No.- 50-302 / 077-03 L-0 Facility: Crystal River Unit #3 Report Date: 4 September 1979 Occurrence Date: 16 August 1979 Identification of Occurrence: | Supplementary Information Report No.- 50-302 / 077-03 L-0 Facility: Crystal River Unit #3 Report Date: 4 September 1979 Occurrence Date: 16 August 1979 Identification of Occurrence: | ||
The Dose Equivalent 1-131 was greater than 1.0 microcurie per gram of primary coolant contrary to Technical Speci-fication 3.4.8. | The Dose Equivalent 1-131 was greater than 1.0 microcurie per gram of primary coolant contrary to Technical Speci-fication 3.4.8. | ||
Conditions Prior to Occurrence: | Conditions Prior to Occurrence: | ||
| Line 134: | Line 95: | ||
/rc gg. . 94 JaiG.LY- | /rc gg. . 94 JaiG.LY- | ||
Reactor Power History of Prior Forty-eight Hours Iten I Event Date: 16 Au.ust 1979 o>s33, 63 tb 0' %>it b, | Reactor Power History of Prior Forty-eight Hours Iten I Event Date: 16 Au.ust 1979 o>s33, 63 tb 0' %>it b, | ||
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--t O 38 RAT.IQ OF N1. TO ,fJ TH = 1.001 r139 140 | --t O 38 RAT.IQ OF N1. TO ,fJ TH = 1.001 r139 140 t | ||
t | |||
'2 kid | '2 kid | ||
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'l RATIO HOUR G M!.jF TURB G M'r H MI 9ATIO O 2 (g7 g) (7333, <p733) (g723, g;jg7 ggjg7 3 __, . . . . ,. - . , _ _ . , _ . - _ . . | 'l RATIO HOUR G M!.jF TURB G M'r H MI 9ATIO O 2 (g7 g) (7333, <p733) (g723, g;jg7 ggjg7 3 __, . . . . ,. - . , _ _ . , _ . - _ . . | ||
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- 4 0.00 0 .00 0.00 0.000 0.000 O lij 5 0.00 0 .00 0,00 9,900 3,100 q | - 4 0.00 0 .00 0.00 0.000 0.000 O lij 5 0.00 0 .00 0,00 9,900 3,100 q | ||
;1 01 111 O lm e , r.' - | |||
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| Line 508: | Line 288: | ||
- :4, 4 | - :4, 4 | ||
+ :5: | + :5: | ||
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! '371 I C 13sl g J,-+TIO OF NI TO iiWTH = ' | |||
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d | d | ||
| Line 552: | Line 311: | ||
;511 i :1 | ;511 i :1 | ||
,5 | ,5 | ||
<r.-.,..n 0 13] =>'.} (t.k.i d pl | <r.-.,..n 0 13] =>'.} (t.k.i d pl | ||
!ssi 0 561: | !ssi 0 561: | ||
.57 sf O | .57 sf O | ||
7 | 7 Fuel Burnup by Core Region Item 2 Event Date: 16 August 1979 (n'; 9 , r3 els) i d :sj | ||
Item 2 The burnup was calculated at 11.7 EFPD for the three (3) enrich:nent regions. | |||
Fuel Burnup by Core Region Item 2 Event Date: 16 August 1979 (n'; 9 , r3 els) i d :sj | |||
REGION NUMBER of FA BURNUP A MWD /MTU B 61 13,568 MWD /MTU C 60 10,517 MWD /MTU D 56 297 MWD /MTU Ave. 9024 MWD /MTU 337320 | REGION NUMBER of FA BURNUP A MWD /MTU B 61 13,568 MWD /MTU C 60 10,517 MWD /MTU D 56 297 MWD /MTU Ave. 9024 MWD /MTU 337320 | ||
| Line 570: | Line 325: | ||
Item 3 Clean-up history starting fortv-eight (48) hours prior to the first sample in which the limit was exceeded is as follows: | Item 3 Clean-up history starting fortv-eight (48) hours prior to the first sample in which the limit was exceeded is as follows: | ||
DATE TIME LETDOW'1 FLOW 8/14/79 0212 61 gpm 8/15/79 0100 68 gpm 8/16/79 0130 60 gpm e> - . . . , | DATE TIME LETDOW'1 FLOW 8/14/79 0212 61 gpm 8/15/79 0100 68 gpm 8/16/79 0130 60 gpm e> - . . . , | ||
*)%) ( ) , ,-% , | *)%) ( ) , ,-% , | ||
| Line 577: | Line 331: | ||
%.)43* } r -e *L$ | %.)43* } r -e *L$ | ||
Degas Operations Item 4 DATE TABLE TIME 8/14/79 Degassed Pressurizer 1600 8/16/79 Reactor Trip 0255 Y | Degas Operations Item 4 DATE TABLE TIME 8/14/79 Degassed Pressurizer 1600 8/16/79 Reactor Trip 0255 Y | ||
s~ | s~ | ||
o <ri &.. | o <ri &.. | ||
au 4.g | au 4.g | ||
Time Duration When DEI-131 Exceeded 1.0 u C1/ gram anc I-131 Analysis Results Item 5 Event Date: 16 August 1979 m<- I Jg_e,' | Time Duration When DEI-131 Exceeded 1.0 u C1/ gram anc I-131 Analysis Results Item 5 Event Date: 16 August 1979 m<- I Jg_e,' | ||
.s, .tf L. . . t | .s, .tf L. . . t | ||
Item 5 As per Technical Specification 3.4.8 The four (4) hour sampling frequency was initiated at 0509 on 16 August 1979 and the Dose Equivalent I-131 was 2.059 microcuries per gram. The four (4) hour samnling frequency was terminated at 1415, on 18 August 1979 when the DEI-131 was determined to be .3685 microcuries per gram. DEI-131 was 5 1 a Ci/ gram at 0500 cn 18 August 1979 when the sample results were .7437 uci/ gram. | Item 5 As per Technical Specification 3.4.8 The four (4) hour sampling frequency was initiated at 0509 on 16 August 1979 and the Dose Equivalent I-131 was 2.059 microcuries per gram. The four (4) hour samnling frequency was terminated at 1415, on 18 August 1979 when the DEI-131 was determined to be .3685 microcuries per gram. DEI-131 was 5 1 a Ci/ gram at 0500 cn 18 August 1979 when the sample results were .7437 uci/ gram. | ||
O m , - 3. , _ | O m , - 3. , _ | ||
'}0 1%.5+ERs}} | '}0 1%.5+ERs}} | ||
Latest revision as of 15:59, 16 March 2020
| ML19253A843 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/04/1979 |
| From: | Cooper J FLORIDA POWER CORP. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19253A837 | List: |
| References | |
| LER-79-077-03L, LER-79-77-3L, NUDOCS 7909110510 | |
| Download: ML19253A843 (14) | |
Text
{{#Wiki_filter:NRC PCnM %6 (, U. S. NUCLE AR R EGUL AT on Y CoMMis51CN (7 718 LICENSEE EVENT REPORT EXfilDIT A I f- 1 I I l iett Ast reu=r on ivet ALL asowato iNeonMaticN coNinolstoc< l. .@ 4 1 o i d i Lls us,.. C Rlm t 3 t@[0 i O!- t 01 00 1 ! O0 f 110 ! Ol @l I 1l 1 1 1 1 r G ,, I - l @ , . .. , s .a , . . . . . -
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CC*.T o i [ @ @l0f 510t -1 0 i 3r0 t 2 g O! 8J 1 l 6 f 7f 9 Q[ 0! 91. .01417 ., .. , ....... l 9 l@.. , . . .. m......... . . . . . . . . avENT OtsCAirT&ON AfeQ #aOg Ag([ coae 5(OLENC(3 g l At 0509 following a Reactor trip, Chem / Rad sampling revealed that the g reactor coolant Dose Equivalent I-131 exceeded 1.0 microcurie per gram , o , [ contrary to Technical Specification 3.4.8. No safety hazard as Reactor l o , , Coolant System Purification reduced DEI-131 to acceptable levels. Redundancy , [7pq t .n The DEI-131 was .7437 microc.iries per'eram at 0500 on 18 August 1979. ; y ; This is the twelfth occurrence reported under this Technical Specification. g I L,2,1_,j e, i *a svirtu eaasi : . .s e co . u,.. coon coce sa::: co >>cs c .? ::st so ::: s.,:::: al+ lC lGl g ] g l Zlu @ J ZI a Zi Zl Z( Z ;g [)), Q, g
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(SEE ATTACHF SUPPLEMENTARY INFOR'4ATION SHEET) * <51,3 79001105/O s
Supplementary Information Report No.- 50-302 / 077-03 L-0 Facility: Crystal River Unit #3 Report Date: 4 September 1979 Occurrence Date: 16 August 1979 Identification of Occurrence: The Dose Equivalent 1-131 was greater than 1.0 microcurie per gram of primary coolant contrary to Technical Speci-fication 3.4.8. Conditions Prior to Occurrence: Mode 3 hot standby. Description of Occurrence: At 0509, following a Reactor trip, Chem / Rad sampling revealed that the Dose Equivalent I-131 exceeded 1.0 microcurie per gram of primary coolant. Dose Equivalent I-131 was 2.059 microcuries per gram. Action statement of 3.4.8 was entered and the four hour sampling frequency was initiated. The Dose Equivalent I-131 returned to within acceptable limits at 0500 on 18 August 1979. Designation of Apparent Cause: This event was due to an expected transien; spike follow-ing a Reactor trip and known leaking fuel pins. Analysis of Occurrence: There was no safety hazard to the plant or general public as sampling demenstrated reducing levels of DEI-131. The transient was within the capabilities of the plant puri-fication system. Corrective Action: No corrective action deemed necessary as Reactor Coolant purification returned the DEI-131 to within acceptable limits. Failure Data: This is the twelfth occurrence reported under this Technical Specification. /rc gg. . 94 JaiG.LY-
Reactor Power History of Prior Forty-eight Hours Iten I Event Date: 16 Au.ust 1979 o>s33, 63 tb 0' %>it b,
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7 Fuel Burnup by Core Region Item 2 Event Date: 16 August 1979 (n'; 9 , r3 els) i d :sj
Item 2 The burnup was calculated at 11.7 EFPD for the three (3) enrich:nent regions. REGION NUMBER of FA BURNUP A MWD /MTU B 61 13,568 MWD /MTU C 60 10,517 MWD /MTU D 56 297 MWD /MTU Ave. 9024 MWD /MTU 337320
Clean-up Flow History Iteet 3 Event Date: 16 August 1979
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Item 3 Clean-up history starting fortv-eight (48) hours prior to the first sample in which the limit was exceeded is as follows: DATE TIME LETDOW'1 FLOW 8/14/79 0212 61 gpm 8/15/79 0100 68 gpm 8/16/79 0130 60 gpm e> - . . . ,
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History of Degassing Operations for This Report Item 4 Event Date: 16 August 1979 ( . p > q
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Degas Operations Item 4 DATE TABLE TIME 8/14/79 Degassed Pressurizer 1600 8/16/79 Reactor Trip 0255 Y s~ o <ri &.. au 4.g
Time Duration When DEI-131 Exceeded 1.0 u C1/ gram anc I-131 Analysis Results Item 5 Event Date: 16 August 1979 m<- I Jg_e,'
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Item 5 As per Technical Specification 3.4.8 The four (4) hour sampling frequency was initiated at 0509 on 16 August 1979 and the Dose Equivalent I-131 was 2.059 microcuries per gram. The four (4) hour samnling frequency was terminated at 1415, on 18 August 1979 when the DEI-131 was determined to be .3685 microcuries per gram. DEI-131 was 5 1 a Ci/ gram at 0500 cn 18 August 1979 when the sample results were .7437 uci/ gram. O m , - 3. , _
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