ML20087C215
| ML20087C215 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/30/1975 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 583, SR-S1-75-02, SR-S1-75-2, NUDOCS 8403120377 | |
| Download: ML20087C215 (4) | |
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VIROINIA ELECTRIC AND POWER COM1%NY
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fh N/fjVi \\P Mr. Norman C. Moseley, Director Serial No. 583 Office of Inspection and Enforcement P0&M/JTB:c1w U.S. Nuclear Regulatory Commission Region II - Suite 818 Docket Nos. 50-280 230 Peachtree Street, Northwest 50-281 Atlanta, Georgia 30303 License Nos. DPR-32 DPR-37
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Dear Mr. Moseley:
The Virginia Electric and Power Company hereby submits forty (40) copies of Special Report No. SR-St-75-02.
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 next meeting of the System Nuclear Safety and Operating Committee.
Very truly yours, 6. 20 1. J u s +
C. M. Stallings Vice President-Power Supply and Production Operations Enclosures 40 copies of SR-SI-75-02 cc: Mr. K. R. Coller 8403120377 750630 PDR ADOCK 05000280 B
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SPECIAL REPORT-SIR-S1-75-02 i
VENTILATION VENT GASEOUS RELEASE
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DOCKET NOS. 50-280-50-281 LICENSE NOS. DPR-32 DPR-37
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JUNE 11. 1975 -
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I SURRY-POWER STATION
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VIRGINIA ELECTRIC'AND POWER COMPANY i
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INTRODUCTION In accordance with Technical Specification 6.6.B.3 for Surry Power Station, this report describes the release of gaseous wastes in excess of 4 per cent of the Technical Specification limit established by Technical Specification 3.11.B.1.
II.
SUMMARY
OF OCCURRENCE During the months of April and May, several non-routine operations contributed significantly to the quantity of liquid waste generated by Unit Nos. I and 2.
These non-routine operations included dcmineralizer resin transfer and drainage of numerous pipes and components for maintenance during Unit No. 2 refueling shutdown.
The increased generation'of liquid waste has required the continuous operation of liqu2 waste facilitics at full capacity.
This has resulted in an increase in Iodine-131 activity within the auxiliary building.
On May 2, 1975 the rate of liquid waste release from the station was-increased to 10 per cent of the Technical Specification limit to reduce the quantity of stored liquid waste.
A continuous controlled release was maintained at a level'of 10 per cent of the Technical Specification limit' until mid-June.
On May 14, 1975, routine sampling of the ventilation vent gaseous activity revealed an Iodine-131 activity of 6.5 per cent of the Technical Specification limit.
Since that_ time,. ventilation vent Iodine-131: activity 1has exceeded 4 per cent on a number of occasions.
Based on existing-liquid
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waste inventory and p' ojected liquid waste generation, it is estimated that L
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-it may be necessary to continue operation of. liquid waste facilitics at'
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The quarterly limit of 16 per cent of the Technical Specification limit averaged over the quarter as defined in Technical Specification 3.11.B.2.
will not be exceeded.
III. CONCLUSION The generation and accumulation of large quantities of liquid waste, has required the continuous operation of liquid waste facilities at full capacity.
This has resulted in an in' crease in Iodine-131 activity within the auxiliary building.
As a result, ventilation vent Iodine-131 activity has exceeded 4 per cent of the Technical Specification limit.-
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