ML20028G963

LER 90-013-00:on 900903,unsampled Gas Released from Gaseous Waste Mgt Sys.Caused by Internal Leakage Past Discharge Isolation Valves.Administrative Controls in Place to Ensure That Gas Decay Tanks Sampled Prior to release.W/901002 Ltr

ML20028G963
Person / Time
Site:	Waterford
Issue date:	10/02/1990
From:	Hoffpauir J, Mcgaha J ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-013-01, LER-90-13-1, W3A90-0415, W3A90-415, NUDOCS 9010040314
Download: ML20028G963 (5)

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W3A90-0415 A4.05 QA October 2, 1990 10 . S . Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, D.C. 20555

Subject:

Waterford 3 SES Docket No. 50-382 License'No. NPF-38 Reporting of Licensee Event Report Gentlemen:

Attached is Licensee Event Report Number LER-90-013-00 for Waterford Steam Electric Station Unit 3. This Licensee Event Report is submitted pursuant to 10CFR50.73 (a) (2) (i) .

very truly yours, s kL. (

General Manager - Plant Operations (J'.R.McGaha JRM/LDC/rk Attachment cc: Messrs. R.D. Martin J.T. Wheelock - INPO Records Center E.L. Blake W.M. Stevenson D.L. Wigginton NRC Resident Inspectors office 9010040314 901002 gDR' ADOCK 05000382 PDC ZE2.2 IIj

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Sv8M'55aON T$9 lic ree. eempen iM9tCTIO SV0rftssrON Da tt) NO l l l AS$TR ACT (& amer to 1400 speces 4 e , easessmewry fdtoen e a,e spece typeentwa haes) Uti At 0525 hours0.00608 days <br />0.146 hours <br />8.680556e-4 weeks <br />1.997625e-4 months <br /> on September 3, 1990, Waterford Steam Electric Station Unit 3 was at 100% power when plant personnel commenced a batch release of Gaseous Waste Management (GWM) System Gas Decay Tank (GDT) 'B'. Approximately 55 seconds af ter the release was co'amenced, the local GW1 Ef fluent Radiation Monitor went into high alarm and automatically secured the batch release.

The most 'likely cause of this event is internal leakage past discharge isolation valves GWM-305C and 3051C causing a small volume of unsampled gas to be released from GDT 'C' during the gaseous release from GDT 'B'. Technical Specifications (TS) require that representative samples and analyses of gaseous effluents be obtained prior to relcaae; therefore, this event is reportable as plant operation prohibited by TS.

The GMi system is being evaluated to determine which valves are internally leaking and to identify long term corrective measures. Since enservative calculations of the estimated instantaneous dose rates showed that the unsampled release was well within TS limits, there was no safety sigdficance to this event.

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At 0525 hours0.00608 days <br />0.146 hours <br />8.680556e-4 weeks <br />1.997625e-4 months <br /> on September 3, 1990. Waterford Steam Electric Station Unit 3 was at 100% power when plant personnel commenced a batch release of Gaseous Waste Management (GWO System Gas Decay Tank (GDT) (EIIS identifier WE-TK) 'B'.

Approximately 55 seconds after the release was commenced, the local CWM Effluent l Radiation Monitor (PRM-IRE-0648) (EIIS identifier IL-MON) went into high alarm and automatically secured the batch release. An alert alarm was also received on both Plant Stack (E1IS identifier VL) Effluent Radiation Monitors just prior to the release being secured by the GW1 Effluent Radiation Monitor high alarm. y a

A post-release gaseous sample for Xenon (Xe) and Krypton (Kr) radionuclides- '

was drawn from CDT 'B' and resulted in an activity le.1 of 4.150 E-01 uC1/cc.  ;

-which corresponded to the pre-release sample activity of 4.773 E-01 uCi/cc from GDT 'B'. A gaseous sampic was also taken from GDT 'C' since it was in service-and isolated from the GDT discharge header at the time of the release. The l

activity level from CDT 'C' was 8.601 E-01 uCi/ce, which corresponded with the recorded activity level of 7.14 E-01 uC1/cc from the alarm history of GWM Effluent Radiation Monitor (PRM-1RE-0648).

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01 0 0l 3 0F 01 4 Text u m ma e m The most likely cause of this event is internal seat leakage of the GDT 'C' discharge isolation valves (EIIS identifier ISV) GkH-305C and GkH-3051C.

Internal leakage of the discharge isolation valves could have caused a small volume of unsampled gas to be released from GDT 'C' during the 55 second gaseous release from GDT 'B'. Technical Specification (TS) 4.11.2.1.2 requires that i

representative samples and analysen of gaseous effluents be obtained prior to release. Since GDT 'C' was not sampled prior to the inadvertent release from GDT 'C', this event is reportable under 10CFR50.73 (a)(2)(1) as plant operation ,

i prohibited by TS.

TS 4.11.2.11 requires that the dose rate due to noble gases in gaseous effluents shall be determined to be within the following i

- Dose Rate to the Total Body: 500 mrem / year

- Dose Rate to the Skin: 3000 mrem / year Conservative calculations were made to estimate the instantaneous dose rates I from the noble gases released. The results are as follows:

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- Dose Rate to the Total Body: 29.1 mrem / year

- Dose Rate to the Shint 69.7 mrem / year l The calculations were based on the post release sample activities from GDT

'C' for radionuclides from the noble gases Kr and Xe.

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w =ac w a.ne w nn Work A'attorization 01063948 has been initiated to investigate if GDT 'C' ,

dischs rge isolation valves GW-305C and GWM-3051C have internal seat leakage

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and will be completed prior to the end of Refuel IV (May 14 1991). All other paths of internal gaseous leakage to the CWM discharge header will be investigated. ,

Administrative controls are currently in-place which ensure that all GDTs are sampled prior to release. These controls will remain in effect until the GWM-system leakage is identified and corrected.

r The indicated dose rate calculations show that the estimated dose rates from the unanalyzed radionuclides released from GDT 'C' were well within the dose  !

rate limits established by TS 4.11.2.11 for gaseous effluents released to unrestricted areas. -fore, this event did not result in an increased risk  !

to the health and safet .,f the public or plant personnel.

SIM1hAR EVENTS None PLANT CONTACT J.G. Hoffpauir, Maintenance Superintendent, 504/464-3138.

N CPom 3 Af649)

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