ML20054L587

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RO 82-017:on 820614,observed That Pressure Had Fallen to Less than 1 Psig on South Waste Gas Decay Tank.Max Release Constitutes Small Fraction of Annual Allowable Limit.Cause & Corrective Action Included in LER Due 820628
ML20054L587
Person / Time
Site: San Onofre Southern California Edison icon.png
Issue date: 06/15/1982
From: Ray H
SOUTHERN CALIFORNIA EDISON CO.
To: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
RO-82-017, RO-82-17, NUDOCS 8207080270
Download: ML20054L587 (1)


Text

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U.S. Nuclear Regulatory Commission 3

Office of Inspection and Enforcement Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. R. H. Engelken, Regional Administrator

Dear Sir:

Subject:

Docket No. 50-206 Written Confirmation of Prompt Notification Licensee Event Report No.82-017 San Onofre Nuclear Generating Station, Unit 1 In accordance with Appendix B Technical Specification 5.6.3.a~.(2), to Provisional Operating License DPR-13, this submittal confirms the June 15, 1982, prompt notification of a reportable occurrence involving an unplanned i

release from the South Waste Gas Decay Tank at San Onofre Nuclear Generating Station, Unit 1.

Verbal notification was made to L.F. Miller, San Onofre Unit 1, Resident Inspector, and G.P. Yuhas, Region V Radiation Specialist.

At 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> on June 13, 1982, during routine surveillance, the South i

Waste Gas Decay Tank was observed to be pressurized to 25 psi (g). When

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i next observed at 0210 on June 14, 1982, the pressure had fallen to,lessi i

than 1 psi (g).

Immediate actions included placing the Center Waste Gar Decay Tank into service and sampling the South Waste Gas Decay Tank.

The sample composition was determined to be approximately 94% nitrogen, 4% hydrogen, and 2% oxygen.

Radionuclide analysis of the 1260 c.c.

sample showed an activity of 1.034 x 10-4 uC/cc. Based on our preliminary-calculations, for a tank of the size and pressure in question, this

corresponds to a maxhnum release of 9.88 x 10-4 Curies.

This is a small fraction of the annual allowable release limit established in the Technical Specification.

At this time, the cause of the leakage has not yetlbeen identified and the investigation is continuing. A determination of the cause of the occurrence and a description of corrective actions will be detailed in the follow-up 14-day report and LER No.82-017 due June 28, 1982.

If you should have any questions about this matter, please contact me.

Sincerely, NM

/fy/En B2070s0270 820615

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PDR ADOCK 05000206 S

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cc:

L.F. Miller (USNRC Resident Inspector, San Onofre, Unit 1)

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