ML20086S303

USRE-S1-74-03:on 741107,small Amount of Low Level Radioactivity Released to James River Via Component Cooling Svc Water.Caused by Inoperability of Pump 1-SW-P-6 Due to Lack of Water Lubrication

ML20086S303
Person / Time
Site:	Surry
Issue date:	12/13/1974
From:	Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
USRE-S1-74-03, USRE-S1-74-3, NUDOCS 8403010489
Download: ML20086S303 (5)

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Y @ @. gx;A.iida gg 5W 'h Mr. Norman C. Moseley, Director Serial No. g \) Directorate of Regulatory Operations P0&M/JTB:clw United States Nuclear Regulatory Commission Region II - Suite 818 Docket No. 50-280 230 Peachtree Street, Northwest License No. DPR-32 Atlanta, Georgia 30303

Dear Mr. Moseley:

Pursuant to Siirry Power Station Tdchnical Specification 6.6.B.2,

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the Virginia Electric and Power Company hereby submits forty (40) copies of Unusual Safety Related Event Report No. USRE-SI-74-03. The substance of this report has been reviewed by the Station Nuclear Safety and Operating Committee and will be placed on the agenda for the r. ext meeting of the System Nuclear Safety and Operating Committee. Very truly yours, OIdb C. M. Stallings Vice President-Power Supply and Production Operations Enclosures 40 copics of USRE-S1-74-03 cc: Mr. K. R. Goller b j S -. l l

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                                   *s UNUSUAL SAFETY RELATED EVENT REPORT NO. USRE-SI-74-03 SERVICE WATER RADIATION MONITOR SYSTEM DECEMBER 13, 1974 DOCKET NO. 50-280 LICENSE NO. DPR-32 SURRY POWER STATION VIRGINIA ELECTRIC AND POWER COMPANY l

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O O I. INTRODUCTION In accordance with Technical Specification 6.6.B.2 for Surry Power Station, Operating License Number DPR-32, this report describes an unucual safety related event which was detected in connection with an unplanned release of low level radioactive water which was described in Abnormal Occurrence Report No. A0-S1-74-13. An unusual safety related event is defined by Technical Specification , 1.0.J.2 as: Any substantial variance, in an unsafe or less conservative direction, from performance specifications contained in the Technical Specifications or from performance specifications, relevant to safety related equipment, contained in the Final Safety Analysis Report. II.

SUMMARY

OF OCCURRENCE On November 7,1974 a small amount of low level radioactivity was released to the James River via the component cooling service water. This was described in the Abnormal Occurrence Report. Number A0-SI-74-13. The radiation monitor (RM-SW-107) on the service water side of the com-ponent cooling water heat exchangers did not alarm when the service water contained radioactive contamination. As described in A0-S1-74-13 the service water became contaminated as a result of a tube leak in the com-ponent cooling water heat exchanger. III. ANALYSIS OF OCCURRENCE l The radiation mo'nitor and its setpoints were checked and found to be operating satisfactorily. The flow through the monitor was checked and-found to be less than that required to proper operation. s t .

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               -  Subsequent investigation revealed that the pump (1-SW-P-6) which takes suction on the sample lines from the service water side of the component cooling water heat exchangers to provide flow to the detector was in-operative, although there was some flow through the line. This flow resulted from the discharge of the pump operating at 16 inches of mercury vacuum and the suction operating at 12 inches of mercury vacuum. An internal investigation of the pump bearing revealed that the bearing was wiped due to lack of water lubrication as the pump was operating without a prime and the system design would not allow a prime to be maintained.

Therefore, the initial design was inadequate. IV. CORRECTIVE ACTION TO PREVENT RECURRENCE The corrective action planned is as follows:

1. Repair the pump (1-SW-P-6)

2. Route the discharge of the pump to the circulating water discharge tunnel via an atmospheric return, instead of directly. This will allow the pump to develop-a discharge head pressure to keep the radiation monitor full.

3. Install a miniflow line from discharge to suction 9

of the pump to facilitate pump priming.

4. Reroute the sample lines on the upper' component cooling water heat exchangers outlet lines (1-CC-E-A & B). This will allow suction to be taken on the lower side of the pipe thus ensuring

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          ' ' '. AN'ALYSIS AND EVALUATION OF SAFETY IMPLICATIONS Due to the non-functioning of the radiation monitor, leakage from the component coolers was not detected as rapidly as would have been possible with it operating satisfactorily. The leak was detected by other methods as described in A0-SI-74-13. The leakage which was not detected by the inoperable monitor was insignificant and was well below the limits of 10 CFR 20 and the Technical Specifications. Therefore, there were no safety implications associated with this event.

VI. CONCLUSIONS The licensee concludes that: ,

1. The event described herein was caused by an inoperable sample pump. The inoperaoility has been contributed to an inadequate design to satisfy the service conditions.

2. The event described herein did not affect the safe operation of the station.

3. The event described herein did not affect the health or safety of the general public.

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