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LER 81-031/03L-0:on 810512,RCS Sample Collected Following Reactor Trip Revealed radio-iodine Content Approaching Limit.Caused by Slight Leakage of Gas Through Fuel Cladding. Levels Monitored,Ensuring Leakage Decayed Off Below Limits
	ML20004F160
Person / Time
Site:	Davis Besse
Issue date:	06/11/1981
From:	Rowland M, Stotz J; TOLEDO EDISON CO.
To:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20004F154	List: ML20004F153; ML20004F160;
References
	LER-81-031-03L, LER-81-31-3L, TAC-47043, NUDOCS 8106160569
	Download: ML20004F160 (5)
	v • d • e

NRC FORM 366 nm - U. S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: l l l f l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) ,

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EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l (NP-33-81-37) On May 12,1981 at 1457 hours0.0169 days 0.405 hours 0.00241 weeks 5.543885e-4 months following a reactor trip, a Reacter __l g l Coolant System (RCS) sample was collected in accordance with Technical Specification l p;T-] l 3.4.8, Table 4.4-4. The analysis of the sample showed that the radio-iodine content l g l was approaching the limit. At 2037 hours0.0236 days 0.566 hours 0.00337 weeks 7.750785e-4 months , the level peaked at 1.52 uCi/gm dose equi- l g l valent iodine I-131 with the limit being 1.0 uCi/gm. There was no danger to the l o7 l health and safety of the public or station personnel. There was no venting of con-- l oa l tainment gases until limits dropped below the 1.0 uCi/gm limit. .

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_ l 36 l@ 181818 1" I 37 l_Y]@ lN l@ (N Jg lB l0 l1 l5 [g 40 41 42 43_ 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i o l The cause was a slight leakage of gas through the fuel cladding. Some leakage is l i

g l normal.following a reactor trip when the gases.in the fuel rods are further compressedI g l by the contracting cladding. The levels were monitored to ensure it decayed off to l g l below limits. A technical speci. cation revision to change the li6it is being evalu- l

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TOLEDO EDISON COMPANY ,

, 3 DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-81-37 DATE OF EVENT: May'12, 1981 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF DCCURRENCE: Reactor Coolant System (RCS) Dose Equivalent I-131 Exceeded Technical Specification Limits Af ter Reactor Trip at 1457 Hours Conditions Prior to Occurrence: The unit was in Mode 3 with Power (MWT) = 0 and Load (Gross MRE) = 0.

Description of Occurrence: At 1457 hours0.0169 days 0.405 hours 0.00241 weeks 5.543885e-4 months on May 12, 1981 following a reactor trip, an RCS sample was collected in accordance with Technical Specification 3.4.8, Table 4.4-4. The analysis of the sample showed that the dose equivalent I-131 was .94 uCi/gm. A second sample was taken which exceeded Technical Specification 3.4.8 1Luit of 1.0 uC1/gm. At 2037 hours0.0236 days 0.566 hours 0.00337 weeks 7.750785e-4 months on May 12, 1981, the level peaked at 1.52 uCi/gm.

The following information is supplied per reporting requirements:

Power History Reactor power was constant until 0022 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months on May 12, 1981 when it was reduced in anticipation of Reac:or Coolant' Pump (RCP) 2-1 being shutdown due to a seal problem. .

At 0058 hours6.712963e-4 days 0.0161 hours 9.589947e-5 weeks 2.2069e-5 months , RCP 2-1 was taken out of service with reactor power at 75%. . .

Date Time Reactor Power 1400 100%

5/10/81 1200 100%

5/11/81 0100 73%

5/12/81 0200 74%

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' 0300- 74%

1457 TRIP

' Fuel Burnup By Core Region - See attached computer printout Cleanup Flow History - 48 h6urs prior to the f.irst limit exceeding sample:

l

The letdown flow dur.ing this time:

May 10, 1981 - 86 gpm May 11, 1981 - 86 gpm May 12, 1981 - 102 gpm Tnere was no degassing operation. '

LER #81-031

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TOLEDO EDISON COMPANY -

DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE .

PAGE 2 SUPPLEMENTAL INFORMATION FOR LER NP-33-81-37 ,

The dose equivalent I-131 exceeded 1.0 uCi/gm at 2037 hours0.0236 days 0.566 hours 0.00337 weeks 7.750785e-4 months on May 12, 1981, and was below that limit at 0350 hours0.00405 days 0.0972 hours 5.787037e-4 weeks 1.33175e-4 months on May 13, 1981. The total time dura-tion was approximately 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months . The maximum level was 1.52 uCi/gm.

Specific Activity Analysis:

Date Time Activity (uC1/gm) Dose Equivalent'I-131 5/12/81 0500 0.132 1845 0.94 2037 1.52 5/13/81 0013 1.14 ,

0350 0.99 0555 0.74 '

0815 0.16 Designation of Apparent Cause of Occurrencei A reactor trip' typically causes an iodine spike in the RCS. This is caused by a slight amount of gas leakage through the fuel rod cladding due to transient conditions. The gas leak is a result of'in-creased compression of gas 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 were still well below the allowa-ble limit of 60 uCi/gm per Figure 3.4-1 of Technical Specification 3.,4.8.

Corrective Action: A corrective action is not applicable.. Iodine spikes are typical following a reactor trip. No damage is indicated to the fuel. Monitoring of I-131 level was continued until it dropped below Technical Specification limit of 1 uCi/gm.

At 0555 hours0.00642 days 0.154 hours 9.176587e-4 weeks 2.111775e-4 months on May 13, 1981, the level dropped to .74 uCi/gm. A Technical Specifi-cation revision to change the limit is being evaluated per Facility Change Request 81-163.

Failure Data: .There have been two previous reports'of high iodine levels - see Licensee Event Reports NP-33-80-114 (80-088) and NP-33-81-14 (81-016) .

LER #81-031 ,

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ML20004F160

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