05000302/LER-1980-009-03, /03L-0:on 800209,following Power Reduction & on 800211,during Startup Operations,Rcs Sampling Revealed Dose Equivalent I-131 Exceeded Tech Specs.Caused by Leaking Fuel Pins & Iodine Transient Following RCS Transient
| ML19296D911 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/29/1980 |
| From: | Lancaster K FLORIDA POWER CORP. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19296D909 | List: |
| References | |
| LER-80-009-03L, LER-80-9-3L, NUDOCS 8003130493 | |
| Download: ML19296D911 (48) | |
| Event date: | |
|---|---|
| Report date: | |
| 3021980009R03 - NRC Website | |
text
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- - mrn LICENSEE EVENT REPORT EXHIBIT A (pt.tr.s paiaer ca rves Act atcusato isromuAr css ccuractsLccoi I
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mcN Anc eacs AaL2 ccastcutscss tvtNicepon 9 February 1980 f ollowi,, a power reduction and at;ain at 1332 on 3
At 1
,,, g
,. 11 February 1980 during plant startup operations, Reactor Coolant System 9
psampling revealed that the dose equivalent I-131. exceeded 1.0 microcuries ner This created an event contrary.to Technical Specification 3.4.3.
Redun-1
_,,,, gram.
~
No affect upon the plant or general public as RCS purification re-
,dancy NA.
These are the fifteenth and sixteenth
,vealed DEI-131 to acceptable levels.
, occurrences of this type reported.
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[The cause of this event is attributed to leaking fuel pins and an anticipated
,,2 gIodine transient followine a Reactor Coolant svsron transient.
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.getion required as Reactor Coolant System purification returned DEI-131 to
.gwithin. acceptable levels.
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- - Name of preparer:
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Lancaster (904) 795-64g6 (SZZ Al"'u-"1 SUT?LCfENT.m ITIORECICN se.:..M 8003130
)
i e
SUPPLEMENTARY INFORMATION Report No.:
50-302/80-009/03L-0 Facility:
Crystal River Unit #3 Report Date:
29 February 1980 Occurrence Dates:
9 February 1980 and 11 February 1980.
Identification of Occurrence:
The dose equivalent Iodine 131 concentration exceeded 1.0 microcuries per gram of primary coolant contrary to Technical Specification 3.4.8.
Conditions Prior to Occurrence:
9 February 1980 event Mode 1 60% power.
11 February 1980 event Mode 1 72% power.
Description of Occurrence:
At 1930 on 9 February 1980 following a power reduction to approximately 60% power, it was discovered through Reactor Coolant sampling that the DEI-131 was 1.41 microcuries per gram.
Entered the Action Statement of Technical Specification 3.4.8.
The four (4) hour sampling frequency was initiated and DEI-131 returned to within specification at (204 on 11 February 1980.
At 1332 on 11 February 1980 during Plant Startup Operations, it was discovered through Reactor Coolant System Sampling that the DEI-131 was 1.05 microcuries per gram.
Entered the Action Statement of Technical Specification 3.4.8.
The four (4) hour sampling frequency was initiated.
DEI-131 returned to within specification at 0530 on 12 February 1980.
Designation of Apparent Cause:
The cause of these events is attributed to leaking fuel pins and an anticipated Iodine transient following a Reactor Coolant System transient.
Analysis of Occurrence:
No effect upon the plant or general public as Reactor Coolant sampling demonstrated reducing levels or DEI-131.
Both transients were within the capabilities of the Plant Purification System.
Corrective Action
No corrective action required as the Reactor Coolant System purification system returned the DEI-131 to within acceptable limits.
Failure Data:
These are the fifteenth and sixteenth occurrences of this type reported.
/rc
Reactor Power History of Prior Forty-eight Hours Ren Event Date: February 9, 1980 @ 1930
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39.25 2 0 0 '+ 6 91.64 92.00 1., 0 l 3
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3 09.24 10050 91.35 92.60
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4 89.24 10014 91.31.
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5 39.26 10046 91.64 92.70 1.012
.974 T
5 89.2.6 LO O 46 91M4 92.70 L_0J 2 974 6
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7 89.30 20045 91.64 92.?0 1.014
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90.86 98.70
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12 95.42 10088 90.53 98.70 1.002 960 L
12 c5.u2 100S8 o5,53 98.70 1.002 C65 13 "ti.00 10077 o7 To 99.30 1.00e
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- - RATIO OF NI TO NWTH =
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"- AYEitnGE--DA ILY-TU E D It E - G r:OE S i!Er4T - E n TE ---9004 i-iWKUH u
7 i.VERAGE DAILi' 11WTH P O L'Z R 5G.199 c / ci P
? A/EPAGE DAILY i1UCLE AR IrGT. PnuCE 61.950
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FUEL BURNUP BY CORE REGION ITEM 2 EVENT DATE:
February 9, 1980 @ 1930 e
ITEM 2 The burnup was calculated at 152.061 EFPD for the three (3) enrichment regions.
REGION NDfBER of FA BURNUP B
61 19608 5'D/MTU C
60 15265 5'D/MTU D
56 4028 L'D/MTU AVG.
13207 L'D/MTU
CLEANUP FLOW HISTORY ITEM :/3 EVENT DATE:
February 9, 1980 @ 1930
ITDi 3 Cleanup flow history forty-eight (48) hours prior to the first sample in which the limit was exceeded indicated a letdown flowrate as shown below:
DD!IN FLO'JRATE 2/7/80 90210 47 gpm 2/8/80 90230 90 gpm 2/9/80 90035 47 gpm e
DEGAS OPERATIONS ITEM 4 EVENT DATE:
February 9, 1980 9 1930 NO DECAS OPERATIONS
Time Duration 'n' hen DEI-131 Exceeded 1.0 uci/ gram and I-131 Analysis Results ITE!! 5 EVENT DATE: February 9, 1980 9 1930
ITEM 5 As per Technical Specification 3.4.8, the four (4) hour sampling frequency as depicted on the table below was initiated at 1930 on February '. 1980 and the Dose Equivalent I-131 was 1.41 microcuries per gram.
The four hour sampling frequency was terminated at 1204 on February 11, 1980, when the DEI-131 was determined to be.899 microcuries per gram.
The time duration when the specific activity of primary coolant exceeded 1.0 microcuries per gram Dose Equivalent is 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />, 34 minutes.
DATE TIME DEI-131 (uci/ gram) 2/9/80 1930 1.41 2/9/80 2330 3.15 2/10/80 0320 2.07 2/10/50 0721 1.78 2/10/80 1121 1.34 2/10/80 1520 1.17 2/10/80 1945 1.55 2/10/80 2330 1.58 2/11/80 0220 1.35 2/11/80 0400 1.22 2/11/80 0540 1.11 2/11/80 0728 1.22 2/11/80 0932 1.13 2/11/80 1204
.899
Reactor Power History of Prior Forty-eight Hours Item 1 Event Date:
February 11, 1980 3 1332
N iE 2,
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r HOUR G n'.J E TUPD G MUTH Ni
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5 97.67 7973 99.71 99.80 1.001 990
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97.o3 9982 99.76 99.50
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~_k AVERADE DAILY GE;'E P. A T O P G P OT.5 484. 82 tiUH ( E S AVERAGE DAILY THERMAL POWER lt(27.04 MUH(T)
---AVE-fla0E-DA11-T-i U RPIftE-G ROSS - HE A T-- R A TE-- -90 044 PTU, K!4H -
.a; AVERAGE DAILY MUTH POWER 58.19:
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'c FP p.WERAGE DAILY NUCLEAR Ir/ST, POUEF ol.950 e
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- . RATIO OF NI TO MUTH = 1.064 i.
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41 Date:
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FUEL BURNUP BY CORE REGION ITD1 2 EVENT DATE:
February 11, 1980 @ 1332
ITDI 2 The burnup was calculated at 152.06 EFPD for the three (3) enrichment regions.
REGION NDiBER OF FA BURNUP B
61 19608 MWD /MTU C
60 15265 MWD /MTU D
56 4028 MWD /MTU AVG.
13207 MWD /MTU
CLEANUP FLOW HISTORY ITEM 3 EVENT DATE:
February 11, 1980 @ 1332
ITEM 3 Cleanup flow history forty-eight (48) hours prior to the first sample in which the limit was exceeded indicated a letdown flowrate as shown below:
DEMIN FLOWRATE 2/9/80 @ 0035 47 gpm 2/10/80 @l945 90 gpm 2/10/80 @2330 60 gpm 2/11/80 @0135 55 gpm 2/11/80 00220 120 gpm 2/11/80 @l204 140 gpm 2/11/80 @l332 90 gpm
DEGAS Operations ITEM 4 EVENT DATE:
February 11, 1980 0 1332 No degas
TIME DURATION WHEN DEI-131 EXCEEDED 1.0 uci/ gram and 1-131 ANALYSIS RESULTS ITEM 5 EVENT DATE:
February 11, 1980 @l332
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 1332 on February 11, 1980 and the Dose Equivalent I-131 was 1.05 microcuries per gram.
The four hour sampling frequency was terminated at 0530 on February 12, 1980 when the DEI-131 was determined to be.9 microcuries per gram.
The time dura-tion when the specific activity of primary coolant exceeded 1.0 micro-curies per gram Dose Equivalent is 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> 58 minutes.
DATE TIME DEI-131 ( pC1/ gram) 2/11/80 1332 1.05 2/11/80 1735 2.23 2/11/80 2130 1.65 2/12/80 0130 1.10 2/12/80 0530
.9