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LER 81-031/03X-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
	ML20010F589
Person / Time
Site:	Davis Besse
Issue date:	08/25/1981
From:	Rowland M, Stolz J; TOLEDO EDISON CO.
To:	; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20010F577	List: ML20010F576; ML20010F589;
References
	LER-81-031-03X, LER-81-31-3X, NUDOCS 8109100394
	Download: ML20010F589 (7)
	v • d • e

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- LICENSEE EVENT REPORT (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI CONTRolstoCm l l l 1 I l lg lc l t l I of H! DI S! S 11 l@l 0101-;Oi0l0]0101-lOl01@[4 LICENSF NVYdEH 43 26 l 1lLtCENSE 11 1l 1l@]$ 1 L lA T $8l@

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7 6 00 EVENT DESCRtPTICN AND PROB ASLE CONSEGLENCES h j lo 121 l (NP-33-61-37) Or 3/12/31 at 1457 hours0.0169 days 0.405 hours 0.00241 weeks 5.543885e-4 months following a reactor trip, a Reactor Coolant The j g;13; i System (RCS) sample was collected in accordance with T.S. 3.4.8, Table 4.4-4.

loi4Il analysis of the sample showed that thelradio-iodine content was approaching the limit.!

Io Isl l At 2037 hours0.0236 days 0.566 hours 0.00337 weeks 7.750785e-4 months , 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.

2 I gI on July 30, 1981 with the level peaking at 1.2 uCi/gm. SO 1

8 9 COMP. VALVE SYSTEV C AUSE CAUSE SUSCODE COVPONENT CODE SU8 CODE CODE CODE SU8 CODE 7

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9 10 in 12 13 18 19 REPORT 20 REVISION SEOVENTI AL OCCURRENCE CODE TYPE No.

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l t l 0 l l The cause was a slight leakage of gas through the fuel cladding. Some leakage is 11 Ii i l n rmal following a reactor trip when the gases in the fuel rods are further comoressect i

The levels were monitored to ensure it decayed off to l gl by the contracting cladding.

l l , 3 l below limits. A technical specification revision to change the the limit is being l l

[q:q l evaluated per Facility Change Request 81-163. 80 l

7 8 9 IS O RY DISCOVERY OESCRIPTION STA US *.POWER OTHER STATUS l

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y lXlh l0l0lOl@l NA l l Al@l Per Table 4.4-4 of Tech Spec 3.4.8 l

ACTIVITY CO TENT LOCATION OF RELEASE REle SED OC RELE ASE AVOUNT OF ACTivtTY l 1 6 glZ NA l [ NA 80 44 d5 7 8 9 10 11 PERSONNEL EXPCSLRES NUVRER TYPE DESCRIPTION l f 1 7 l0l0l0 lN NA PERSONN E L INJUHiES NUUBER DESCRIPTION l i a 8 9 l01010l@l 11 12 NA 80 7

LOSS OF OR DAYAGE TO FACILITY TYPE DESCRIDTION l NA 2

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LDVR 81-072 NAME OF PREPARER

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 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 limit of 1.0 uCi/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.

Also, after a reactor trip at 0812 hours0.0094 days 0.226 hours 0.00134 weeks 3.08966e-4 months 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 hours0.02 days 0.481 hours 0.00286 weeks 6.58265e-4 months on July 30, 1981.

The following information is supplied per reporting requirements.

Power Historv 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 Reactor 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 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 hours0.0094 days 0.226 hours 0.00134 weeks 3.08966e-4 months .

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%

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 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 hours0.0236 days 0.566 hours 0.00337 weeks 7.750785e-4 months on May 12, 1981 and at 1330 hours0.0154 days 0.369 hours 0.0022 weeks 5.06065e-4 months on July 30, 1981. It was below that limit at 0350 hours0.00405 days 0.0972 hours 5.787037e-4 weeks 1.33175e-4 months on May 13, 2 1981, and 0130 hours0.0015 days 0.0361 hours 2.149471e-4 weeks 4.9465e-5 months on July 31, 1981. The total time duration was approximately 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months and 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months , 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 2130 1.2 2

0130 0.98 7/31/81 0.75 0535 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 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 and at 0535 hours0.00619 days 0.149 hours 8.845899e-4 weeks 2.035675e-4 months 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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