View source for 05000346/LER-1981-031-03, /03X-2:on 810512,RCS Sample Showed radio-iodine Content Approaching Limit.Caused by Slight Leakage of Gas Through Fuel Cladding.Levels Monitored to Ensure That Gas Decayed to Below Limits

{{Adams
| number = ML20010F589
| issue date = 08/25/1981
| title = /03X-2:on 810512,RCS Sample Showed radio-iodine Content Approaching Limit.Caused by Slight Leakage of Gas Through Fuel Cladding.Levels Monitored to Ensure That Gas Decayed to Below Limits
| author name = Rowland M, Stolz J
| author affiliation = TOLEDO EDISON CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION III)
| docket = 05000346
| license number = 
| contact person = 
| document report number = LER-81-031-03X, LER-81-31-3X, NUDOCS 8109100394
| package number = ML20010F577
| document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
| page count = 7
}}
{{LER
| Title = /03X-2:on 810512,RCS Sample Showed radio-iodine Content Approaching Limit.Caused by Slight Leakage of Gas Through Fuel Cladding.Levels Monitored to Ensure That Gas Decayed to Below Limits
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000346
| LER year = 1981
| LER number = 31
| LER revision = 3
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

=text=
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NRC F0RM 366 (7-771 LICENSEE EVENT REPORT CONTRolstoCm l l
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CON'T 68 63 EVENT DATE 74 75 REPQHT D ATE SJ 00 63 COLK ET ?.LVeg a 7
6 EVENT DESCRtPTICN AND PROB ASLE CONSEGLENCES h lo 121 l (NP-33-61-37) Or 3/12/31 at 1457 hours following a reactor trip, a Reactor Coolant j
The j
System (RCS) sample was collected in accordance with T.S. 3.4.8, Table 4.4-4.
g;13; i loi4Il analysis of the sample showed that thelradio-iodine content was approaching the limit.!
Io Isl l At 2037 hours, the level peaked at 1.52 uCi/gm dose equivalent iodine I-131 with the l
[ !s j l limit being 1.0 uCi/gm. There was no danger to the health and safety of the public on There was another iodine spike after the reactor trip at 0812 houtts
[]l station personnel.
gI on July 30, 1981 with the level peaking at 1.2 uCi/gm.
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VALVE SYSTEV C AUSE

==CAUSE==
CODE CODE SU8 CODE COVPONENT CODE SU8 CODE SUSCODE l Rl C )@ lE l@ lC l@ l Fl Ul El Ll Xl X]@ ]@ ]@
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10 in 12 13 18 19 20 REVISION SEOVENTI AL OCCURRENCE REPORT EVENT YE AR REPORT NO.
CODE TYPE No.
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33 34 J3 30 al 40 di 47 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 l t l 0 l l The cause was a slight leakage of gas through the fuel cladding. Some leakage is i
11 Ii i l n rmal following a reactor trip when the gases in the fuel rods are further comoressect The levels were monitored to ensure it decayed off to l
i gl by the contracting cladding.
A technical specification revision to change the the limit is being l
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evaluated per Facility Change Request 81-163.
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==DESCRIPTION==
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==DESCRIPTION==
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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT CNE SUPPLDIENTAL INFORMATION FOR LER NP-33-81-37 i
2 DATES OF EVENT: May 12 and July 30, 1981 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Reactor Coolant System (RCS) Dose Equivalent 1-131 2l exceeded technical specification limits after reactor trip Conditions Prior to Occurrence: The unit was in Mode 3 with Tower (MWT) = 0 and Load (Gross FME) = 0.
Description of Occurrence: At 1457 hours 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 limit of 1.0 uCi/gm. At 2037 hours on May 12, 1981, the level peaked at 1.52 uCi/gm.
Also, after a reactor trip at 0812 hours on July 30, 1981, a similar event occurred.
2 The first sample was.98 uCi/gm, and the second sample exceeded the limit. The level peaked at 1.2 uCi/gm at 1730 hours on July 30, 1981.
The following information is supplied per reporting requirements.
Power Historv Reactor power was constant until 0022 hours on May 12, 1981 when it was reduced in anticipation of Reactor Coolant Pump (RCP) 2-1 being shutdown due to a seal problem.
At 0058 hours, RCP 2-1 was taken out of service with reactor power at 75%.
Date Time Reactor Power 5/10/81 1400 100%
5/11/81 1200 100%
j 5/12/81 0100 73%
0200 74%
0300 74%
1457 TRIP On July 30, 1981, reactor power was decreased from 99.8% to 30% in six minutes to maintain condenser vacuum, then tripped at 0812 hours.
l 7/28/81 All day 99.46%
7/29/81 Till 1100 99.76%
1100 98.21%
1200 98.59%
1300 98.99%
l 2
1400 99.6%
i 2300 99.6%
i'

TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE PAGE 2 SUPPLEMENTAL INFORMATION FOR LER NP-33-81-37 Date
_ Time Reactor Power 7/30/81 0100 99.8%
2 0812 TRIP Fuel Burnup by Core Region - See attached computer printout Cleanup Flow Historv - 48 hours prior to the first limit exceeding sa=ple:
The letdown flow during this time:
May 10, 1981 - 86 gpm May 11, 1981 - 86 gpm May 12, 1981 - 102 gpm July 28, 1981 - 65 gpm 2
July 29, 1981 - 65.5 gpm July 30, 1981 - 64 gpm There was no degassing operation.
The dose equivalent I-131' exceeded 1.0 uCi/gm at 2037 hours on May 12, 1981 and at 1330 hours on July 30, 1981.
It was below that limit at 0350 hours on May 13, 2
1981, and 0130 hours on July 31, 1981. The total time duration was approximately 9 hours and 11 hours, respectively. The maximum level was 1.52 uCi/gm on May 12 and 1.2 uC1/gm on July 31, 1981.
Specific Activity Analysis Date Time Activity (uCi/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 i
0.98 7/30/81 1025 1330 1.1 1730 1.2 2
2130 1.2 7/31/81 0130 0.98 0535 0.75 1400 0.44 l

TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR PO'w'ER STATION UNIT ONE SUPPLEMEWAL INFORMATION FOR LER NP-33-81-37 PAGE 3 Designation of Apparent Cause of Occurrence: A reactor trip typicall 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 contractiag 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 allown-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 hours on May 13, 1981, the level. dropped to.74 uCi/gm and at 0535 hours on 2l July 31, 1981, it dropped to.75 uCi/gm. A Technical Specification 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-33-81-15 (81-016).
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