ML20034C778

Issue 57 to Abnormal Operating Procedure AOP-H-2, Abnormal Radioactive Gas Release from Plant

ML20034C778
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/25/1990
From:	PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20034C092	List: ML20034C091 ML20034C774 ML20034C775 ML20034C776 ML20034C777 ML20034C778 ML20034C779 ML20034C780 ML20034C781 ML20034C782 ML20034C783 ML20034C784 ML20034C785 ML20034C787
References
AOP-H-2, NUDOCS 9005100035
Download: ML20034C778 (5)

Text

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Pub llg FORT ST. VRAIN NUCLEAR GENERATING STATION age ;1: of 2 P

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ABNORMAL RADIOACTIVE GAS RELEASE FROM PLANT RESPONSIBLE h.

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AO P-H-2 Issue 57 Page 2 of 2 (H-2)

ABNORMAL RADIOACTIVE CAS REl_ EASE FROM Pl.AllT SYMPIOM-ACTION MATRIX-I l

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SYMPTOMS I

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1.2-8 1.3 1

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IReactor IReactor

'lActivity-IAny Release in I l

l ACTIONS IBuilding IBuilding lMonitors High IExcess or Limitsi j

i IVentilation

-IVentilatlon IRIS-6314-1 &

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l IExhaust Moble IExhaust Part-IRIS-6314-2, IAuthorization I

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IGas Activity liculate/ lodine Il-OIC, 5-3 I Fo rm f or The 1

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IHigh IActivity High,'l IRelease Or I

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IRIS-7324-1, IRIS-73437-1, I

IRadiological I

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II-03A, 3-6, IRIS-73437-2, 1

IWastes l

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lRIS-7324-2, II-01C, 2-1 I

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A0P APP H Issue 57 Public FORT ST. VRAIN NUCLEAR GENERATING STATIOgage 1-of 3-

- SerVICO*

PUBLIC SERVICE COMPANY,OF COLORADO O

ABNORMAL-RADI0 ACTIVE GAS RELEASE FROM PLANT t

DISCUSSION OF SYMPTOMS SYMPTOMS

'1.1 Reactor Bui'iding Ventilation Exhaust Noble Gas Activity 4

High.

RIS-7324-1 I-03A, 3-6.

RIS-7324-2 I-03A,- 1-7.

This-is the primary indication of concentrations of mixed I

noble gas releases.

All-gas exhausted from'the Reactor q

Building; passes through the ventilation system and past 1

-the exhaust vent monitor.-

j 1.2-Reactor Building Ventilation Exhaust Particulate / Iodine

.i Activity High.

RIS-73437-1, RIS-73437-2, I-01C, 2-1, 4

This is the primary indication of concentrations of I-131 l

releases. All gas exhausted from-the Reactor Building

j passes through the ventilation system and past.the exhaust 1

vent monitor.

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~1.3 Activity Monitors HioS RIS-6314-1 & -2, I-01C, 5-3.

These activity mon _itors detect concentrations of mixed noble gases at the-discharge of the gas waste-blowers.

i Upon detection of activity at the discharge of the' gas waste _ blowers, diversion valves in the gas waste blower suction line will divert the flow to the gas waste vacuum

-i tank. This action is necessary to control the release of radioactive gas to the environment.

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1.4 Any Release In Excess Of Linits Set Forth On The I

Authorization Form For The Release Of Radioactive Wastes.

Each planned discharge of rac'ioactive material must be specifically approved and docamented'on an authorization form (see Administrative Procedure P-3).

The' i

authorization may set specific limits on quantities and/or i

radiation levels. The discharge should be terminated if any of the stipulations of the authorization form are not met.

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FORM (D)372 22 3643

I AOPAPPH-2L Issue 57 i..

A Public' FORT ST. VRAIN NUCLEAR GENERATING-STA'ilON age 2 of 3--

p 107 Service

• PUBUC SERWCE COMPANY OF COLORADO O

DISCUSSION OF OPERATOR ACTION OPERATOR ACTION 2.1 Ensure that flow to the gas waste blowers has been diverted to the gas waste vacuum tank.

When a Stack Monitor. or a Gas Waste Blower Monitor trips, the suction of the Gas Waste Blowers is automatically diverted to the Vacuum Tank because the_ inputs to the-Blowers have a potential for containing radioactive gases.

The operator serves as back up to the automatic action.

2.2 Ensure FV-6351 clo' sed.

I FV-6351' is used only for making authorized gas waste _

releases from the Gas Waste Surge Tanks. In the event of a Stack Monitor trip,-FV-6351 should trip closed automatically to prevent ~ compounding _the: release..-The operator acts as a backup in this case.

If a release is inadvertently being made in excess of the limits set forth.

on the authorization form for a gas waste release, the a

operator must manually terminate the release.

1 2.3.

Evacuate reactor building and sound radiological' alarm.

I In keeping with the concept of maintaining personnel I

exposure as low as reasonably achievable, personnel should-

,l evacuate the Reactor Building and personnel entering the I

Reactor Building to perform corrective or lifesaving i

action should don protective devices (Anti-C's,' Scott Air l

Pack, etc.) prior to re-entry.

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I FORM 101372 22 3643

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A0P APP H !

.t Issue 57-nPublic FORT ST. VRAIN NUCLEAR GENERATING STATiogage 3 of 3_

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107 Service

• Pusuc sERWCE COMPANY OF COLORADO D.

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2.4 Direct operator to attempt to isolate / remedy radiation source.

l If.the activity'is coming from one of-the plant. systems,

. prompt operator' action can greatly reduce the extent of the problem. The following systems were_ identified as the-most likely and extensive sources of potential' leakage; s

however they are not the only possibilities._ The i

operator's knowledge of plant systems, conditions, and his-ingenuity in spotting indications of unusual conditions.

are important factors in-troubleshooting the situation and isolating _the source of activity. Experience has shown l-the buffer helium system to be a possible source of.High Activity..

a)

Check System 63, Radioactive Gas Waste, l

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Check System 23, Helium Purification'.-

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Check System 11, PCRV-Auxiliary Piping.

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Check System 13, Fuel Handling Purge.-

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Check System 14, Fuel Storage Faci.lity, OV f)

Check System 21, Helium Circulator Auxiliaries, j

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2.5 Swap suction of breathing air compressors.

In the event of possible radioactive contamination.of l

breathing air system, swap suction to TSC per 50P 45-03.

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2,6 Ensure CAS reports personnel accountability.

Initiate search, if necessary.

This will insure that all personnel are safe and accounted-for or whether a search for missing persons needs to be started.

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v FORM (D)372 22 3643 i