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LER 80-089/03L-0:on 801203,following Reactor Trip,Rcs Sample Revealed Dose Equivalent I-131 Level Was Greater than Tech Specs.Caused by Gas Leakage Through Fuel Cladding.Levels Monitored to Ensure That Gas Decayed to Below Limits
	ML19340E228
Person / Time
Site:	Davis Besse
Issue date:	01/02/1981
From:	Eshelman D, Stotz J; TOLEDO EDISON CO.
To:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19340E226	List: ML19340E225; ML19340E228;
References
	LER-80-089-03L, LER-80-89-3L, TAC-47043, NUDOCS 8101060692
	Download: ML19340E228 (4)
	v • d • e

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I '> l 2 l l (NP-33-80-114) on 12/3/80 at 1255 hours0.0145 days 0.349 hours 0.00208 weeks 4.775275e-4 months , following a reactor trip at 0924 hours0.0107 days 0.257 hours 0.00153 weeks 3.51582e-4 months , a Iol3) l Reactor Coolant System (RCS) sample revealed that the Dose Equivalent 1-131 level was l The icvel peakell l o 14 ) l greater than the 1.0 pC1/gm limit of Technical Specification 3.4.8.a.

[o{3) l at 1.37 uCi/cm at 1405 hours0.0163 days 0.39 hours 0.00232 weeks 5.346025e-4 months and fell to 0.92 at 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months . At 0205 tours on 12/4 /80[

l e J e } l the level was 0.72 pCi/gn. There was no danger to the health and safet_. of the public l l0l7j l '.J r t o tt a t ion pe r sOnnel .__ The highest level was still well below the allowabic limit ofl l

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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-114 DATE OF EVENT: December 3, 1980 FACILITY; Davic-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Reactor Coolant System (RCS) Dose Equivalent I-131 Exceeded Technical Specificatian Limits Af ter a Reactor Trip Conditions Prior to Occurrence: The unit was in Mode 3 with Power (MWT) = 0 and Load (Gross MWE) = 0.

Description of Occurrence: At 1255 hours0.0145 days 0.349 hours 0.00208 weeks 4.775275e-4 months on December 3, 1980 following a reactor trip at 0924 hours0.0107 days 0.257 hours 0.00153 weeks 3.51582e-4 months , an RCS sample was collected in accordance with Technical Specification 3.4.8, Table 4.4-4. The analysis of the sample by Chemistry and Health Physics person-nel showed that the radio-iodine content exceeded the Technical Specification 3.4.8 limit of 1.0.uCi/ gram Dose Equivalent of I-131. At 1405 hours0.0163 days 0.39 hours 0.00232 weeks 5.346025e-4 months the Icv 21 peaked at 1.36 JuCi/gm Dose Equivalent Iodine -131.

The following information is supplied per reporting requirements:

Specific Activity Analysis:

Date Time Activity (uCi/gm) 12/3/C0 0805 0.033 1255 1.26 1405 1.36 1608 1.30 1950 1.14 2300 0.92 12/4/80 0205 0.72 Power History - 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first limit exceeding sample:

12/1/80 from 1200 97.7% fp for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 12/2/80 from 0000 97.6% fp for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 12/3/80 from 0000 until 0942 97.4" fp 12/3/80 from 0942 until 1200 0.0% fp Fuci Burnup By Core Region - See attached computer printout Cleanup Flow History - 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first limit exceeding sample:

The letdown flow during this time period was kept constant at approxi-mately 64.25 gpm.

LER #80-089

_ _ --- n. .

TOLEDO EDISON COMPANY o DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLE:fENTAL INFOR'!ATION FOR LER NP-33-80-114 PACE 2 There was no degassing operation.

The Dose Equivalent I-131 exceeded 1.0 pCi/gm at 1255 hours0.0145 days 0.349 hours 0.00208 weeks 4.775275e-4 months on December 3, 1980 and was below that limit at 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months on December 3, 1980. The total time duration was 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months and 5 minutes. The maximum measured 1cvel was 1.36 pCi/gm Dose Equivalent I-131.

Designation of Apparent Cause of Occurrence: The cause of the 1.36 pCi/gm Dose Equiva-lent 1-131 level in the RCS was a slight amount of leakage of gas through the fuel rod cladding. Some leakage is normal following a reactor trip when the gases in the fuel rods are further compressed by the contracting cladding. Any small defects would allow some gas to escape.

Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. There was no venting of containment gases until the levels had decayed. The highest levels found in any sample was still well below the allowable limit of 60.pC1/gm per Figure 3.4-1 of Technical Specification 3.4.8.

Corrective Action: The action that was taken was to monitor the level of I-131 to ensure that it did decay off to below the Technical Specification limit of 1 pC1/gm. At 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months on December 3,1980 the level dropped to 0.92 pCi/gm and was down to 0.72,pci/gm at 0205 hours0.00237 days 0.0569 hours 3.38955e-4 weeks 7.80025e-5 months on Decembyr 4,1980.

Failure Data: There have been no previous reports of high iodine levels.

LER #80-089

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