05000280/LER-1979-015-03, /03L-0 on 790422:liquid Waste Disposal Radiation Monitor Failed to Give High Alarm & Trip Release Valve. Caused by Procedural Inadequacy.Procedures Modified

/03L-0 on 790422:liquid Waste Disposal Radiation Monitor Failed to Give High Alarm & Trip Release Valve. Caused by Procedural Inadequacy.Procedures Modified

ML18114A602
Person / Time
Site:	Surry
Issue date:	05/22/1979
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18114A599	List: 05000280/LER-1979-014-03, /03L-0 on 790422:liquid Waste Disposal Radiation Monitor Failed to Give High Alarm & Trip Release Valve. Caused by Instrument Drift in High Alarm Setpoint.All Liquid Waste Releases Were Secured & Alarm Board Checked 05000280/LER-1979-015-03, /03L-0 on 790422:liquid Waste Disposal Radiation Monitor Failed to Give High Alarm & Trip Release Valve. Caused by Procedural Inadequacy.Procedures Modified 05000280/LER-1979-016-03, /03L-0 on 790425:cracks Noted in Concrete Support for 1-RH-E-1A & 1-RH-E-1B.Caused by Thermal Expansion of Heat Exchanger.Cracks Repaired.Heat Exchanger Supports Will Be Modified to Allow for Thermal Expansion ML18114A598
References
LER-79-015-03L-01, LER-79-15-3L-1, NUDOCS 7905250154
Download: ML18114A602 (2)

LER-1979-015, /03L-0 on 790422:liquid Waste Disposal Radiation Monitor Failed to Give High Alarm & Trip Release Valve. Caused by Procedural Inadequacy.Procedures Modified

Event date:
Report date:
2801979015R03 - NRC Website

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I While reviewing Liquid Waste Release'1:orms it was determined that on two occasions, on 4-22-79, releases were made which contained'1;sotope activity suinrn'.3-tions gr~ater i *) :.! i than l.SE-03 µCi/cc.

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(Attachment, page 1 of l)e Surry Power Station, Unit 1 Docket No: 50-280 e

Report No: 79-015/031-0 Event Date: 04-22-79 Liquid Waste Release

1.

Description of Event

Uhile reviewing Liquid Haste Release forms, it was determined that on two occasions, on 4-22-79, releases were made which'contained isotope activity -su~ations

• greater than l.5E-03 µCi/cc.

In each case, the Liquid Waste Radiation monitor did not alarm high and trip the release valve as. required by Technical Specification 3.7.E.

2.

Probable Consequences and Status of Redundant Systems:

3.

4.

The Liquid Haste Radiation monitor, on high activity [1.5 E-03 * "µCi/cc]~ provides a tr'ip signal to the Liquid *waste Release valve.

Since the-monitor can be calibrated to one isotope only, administrative control disallows any releases which contain activ-ity summations greater_ than l.5E-03.

However, a procedural inadequacy resulted in the aforeRentioned releases.

Since the releases did not exceed the limits allowed by Technical Specification 3.11.A.2 and 10CFR20 App. B, the health and safety of the public were not affected.

Cause

A procedural inadequacy caused this event.

Immediate Corrective Action

A check of the waste releases was done to verify compliance with 10 CFR 20, Appendix B.

5.

Subsequent Corrective Action:

The Liquid Waste Release forms have been modified to include additional checks and signatures.

Personnel were instructed to use more care in filling out release forms.

6.

Actions Taken to Prevent Recurrence:

No further corrective action will be required.

7?

Generic IBplications:

none