ML18054A807
| ML18054A807 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 06/22/1989 |
| From: | Johnson B, Kozup C CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LER-89-TS1, NUDOCS 8906260393 | |
| Download: ML18054A807 (4) | |
Text
POWERING MICHIGAN'S PROGRESS General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-0550 June 22, 1989 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
LICENSEE EVENT REPORT 89-TSl - RADIATION MONITOR INOPERABLE FOR GREATER THAN SEVEN DAYS License~ Event Report (1ER) 89-TSl (Radiation Monitor Inoperable for Greater than Seven Days) is attached.
This is a Technical Specification (TS) Special Report that is being submitted pursuant to TS 3.23.2 Action Statement 38 which requires the minimum operable channels to be restored within seven days or a Special Report be submitted within the following 30 days outlining the action taken, the cause of the inoperability and the plans for returning the system to operable status.
The report is being submitted in LER format with a Special Report number i.e. TSl even though it is not reportable per IOCFRS0.73.
It does, however, provide information that can be utilized in the NRC trending process.
Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, USNRC
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NRC Resident Inspector - Palisades Attachment 8906260393 890622 PDR ADOCK 05000255 S
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- .*.. _,,.,_,~ fl-li..P*-* ry,.._,mn lin..i (111 Abstract At 1635 on May 16, 1989 the West Engineered Safeguards Room radwaste ventilation isolation monitor RIA-1811 [IL;RE] slowly failed downscale and was declared inoperable.
In accordance with Technical Specification (TS)
Table 3.24.2, alternate methods of assessing the West Engineered Safeguards Room environment were implemented per Health Physics Procedure 6.51, "Radiological Effluent Operating Procedure".
However, the radiation monitor was not returned to service within seven days of the event as required by TS.
RIA-1811 was repaired, tested and declared operable at 2200 on May 24, 1989.
Therefore, this Special Report is being submitted per TS Table 3.24.2.
The reactor was critical with the Plant operating at 80 percent of rated power when both the monitor was declared inoperable and subsequently returned to service.
The monitor failed when water originating from maintenance on the waste gas vent collection header contacted the monitor and failed its pre-amplifier board.
Failure to return the monitor to service within seven days has been attributed to failure to apply appropriate attention to the secondary Action Statement which requires a Special Report be submitted if the monitor is not returned to service within seven days.
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- I NRC Forlft lllA 19-831 LICENSEE EVENT REPORT ILEA) TEXT CONTINUATION U.S. NUCLEAll REQULATOllY COMMISllON APPROVED OMB NO. 3150-010' EXPIRES: 8/31185
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....., 1171 N.. C FO.. M 19-831 Description At 1635 on May 16, 1989 the West Engineered Safeguards Room radwaste ventilation isolation monitor RIA-1811 [IL;RE] slowly failed downscale and was declared inoperable.
In accordance with Technical Specification (TS)
Table 3.24.2, alternate methods of assessing the West Engineered Safeguards Room environment were implemented per Health Physics Procedure 6.51, "Radiological Effluent Operating Procedure".
However, the radiation monitor was not returned to service within seven days of the event as required by TS.
RIA-1811 was repaired, tested and declared operable at 2200 on May 24, 1989.
Therefore, this Special Report is being submitted per TS Table 3.24.2.
The reactor was critical with the Plant operating at 80 percent of rated power when both the monitor was declared inoperable and subsequently returned to service.
The radiation monitor failed when water originating from the waste gas vent collection header entered the monitor housing which contains the detection element and pre-amplifier.
The waste gas vent collection header piping was cut into to permit removing an occlusion, believed to be spent ion exchange resins and was expected to be dry.
RIA-1811 contains a Geiger-Mueller detector and provides automatic isolation capabilities for the ventilation dampers in the West Engineered Safeguards Room upon detection of airborne radiation.
When Operations personnel discovered that RIA-1811 had failed, its associated ventilation dampers were closed,- the monitor declared inoperable and alternate sampling methods instituted.
Cause Of The Event The unexpected water within the waste gas vent collection header is believed to have originated from resin sluicing activities occurring in 1986.
While sluicing resins from the spent resin storage tank T-69, an overpressure was applied to provide the motive force for moving resins out the top of the tank as required by design.
Up until approximately 1986, as difficulties were experienced with obtaining resin outflow, Operations personnel would open the tank's vent to relieve pressure.
This past practice allowed water and resin to enter the waste gas vent collection header.
RIA-1811 failed when water emitted from the vent header entered the housing which contains the monitor's detection element and pre-amplifier causing failure of the pre-amplifier circuit board.
The failure to return the monitor to service within seven days as required by TS has been attributed to failure to apply appropriate attention to the secondary Action Statement which requires a Special Report be submitted if the monitor is not returned to service within the seven days.
NRC Form lMA 19-831 LICENSEE EVENT REPORT ILER) TEXT CONTINUATION U.I. NUCLEAR REGULATORY COMMllllOH APPROVED OMB ND. 3150-0104 I
EXPIRES: 8/31185 i,"I* t':":":':":":="~~~---------------T==~=:o:-::::----..,.-------------------t FACILITY NAME 111 DOCKET NUM91R 121 Lllll NUMalll Ill
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0 I 0 0 13 OF 0 I 3 TEXT fir,_.-*,._. --NlfC Fomt.-,.**11171 Corrective Actions Special Operating Procedures have been in place since approximately 1986 which contain specific statements disallowing any tank or demineralizer to be vented during sluicing activities.
A review of procedures, guidelines and Plant practices pertaining to work order planning was conducted.
Additionally, interviews with the Plant Maintenance Superintendent and a construction engineer were held to discuss this particular activity and general work order planning.
It was concluded that current planning practices are sufficient with respect to equipment protection during maintenance activities and that this event is considered isolated.
Therefore, no further specific actions are believed required in this area.
To enhance management attention of secondary Action Statements, Operations personnel will add these action statements to the Plant Daily Status sheet and will identify them on work orders such that appropriate priority is given to scheduling repairs.
Analysis Of The Event Radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the release of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluent.
No safety hazard to ~he general public existed during the period RIA-1811 was inoperab1e due to the availability of process and area monitors throughout the Plant systems.
Indication of an occurring transient would have been detected and operators alerted by increased activity on these monitors.
Additionally, the alternate preplanned method of assessing the West Engineered Safeguards-Room environment was in-place within the time allotted by TS.
This Special Report is being submitted pursuant to TS 3.24.2 Action Statement 38 which requires the minimum operable channels be restored within seven days or a Special Report be submitted within the following 30 days outlining the action taken, the cause of the inoperability and the plans for returning the system to operable status.
Additional Information RIA-1811 is a model number 842-5 radiation monitor manufactured by Victoreen Instrument Division.
For additional information regarding the submittal of TS Special Reports pertaining to radiation detection instrumentation, reference Licensee Event Report 87-034.
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N,_C FO"M :tea*
19-831