ML20059C923

Rev 3 to Process Control Program

ML20059C923
Person / Time
Site:	Grand Gulf
Issue date:	04/11/1990
From:	Rolonda Jackson ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20059C919	List: AECM-90-0149, Forwards Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Rev 3 to Process Control Program ML20059C921 ML20059C923
References
PROC-900411, NUDOCS 9009050415
Download: ML20059C923 (9)

Text

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--r y I PROCESS CONTROL ~ PROGRAM DESCRIPTION.

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' GRAND GULF NUCLEAR STATION.-

PROCESS CONTROL PROGRAM DESCRIPTION.

h. SAFETY RELATED

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EVALUATION-APPLICARILITY

, SAFETY EVALUATION ENVIRONMENTAL EVALUATION

[] APPLICABLE [] APPLICABLE:

[X] NOT APPLICABLE (X) NOT APPLICABLE Reviewed / Approved: -

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/ OIUOO 3 Radiation Contro uperintendent Date

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GRAND GULF, UNIT 1 Rev. 3 - 4/90 PCPREV3/JRSFLR-2 EI

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TABLE OF CONTENTS E&ER DESCRIPTION APPROVAL SHEET ................................... ....... . 1

-TABLE OF_ CONTENTS ................................................... 1 11- '

LIST _0F EFFECTIVE PAGES ....................,.......................... iii A . -

Introduction'.................................................... 1

'B. Administrative Controls ......'...................................- ~2 C.< Weste Streams.................................................... 2 .i t

.D. Conditioning of Wastes.and-Sampling for Verificacion

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i aof Solidification................................................ 3 E. Sampling for Verification of Curie Content ...................... 4: 3  ;

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, GRAND G'JLF NUCLEAR STATION

' PROCESS' CONTROL PROGRAM (PCP) DESCRIPTION 1 REQUIREMENTS FOR PROCESSING OF RADIOACTIVE LIQUIDS AND WET SOLIDS h-i

. ~A.. Introduction 1;

l' A large portion of the radioactive. waste produced.in a nuclear power station is in a form which is either liquid (e.g. oil', oily sludge,.EHC'-

fluid, glycol) or~ in a wet solid form (e.g. resins, filter sludge): and L requires ~ processing to obtain an acceptable,. solid, monolithic form for 3 k burial. Some of this waste may be sent to a licensed offsite vendor for volume reduction or other preparation for burial. Radweste processing activities at Grand Gulf Nuclear Station (GGNS) are coordinated with the Radiation Control'Section to ensure personnel exposures are kept ALARA.

The GGNS Radweste Solidification System was originally intended for the solidification of wet radioactive waste. The installed solid radwaste ,

. system has never been utilized and vendor services are employed for ths ~!

processing =of wet wast'es. l Radioactive wet solids (powdered and bead resins) are processed by.

dowatering,-vitrification or. solidification to assure there is no '

free-standing water. Dewatering of resins is performed onsite by a-qualified vendor using a mobile dowatering system. Rosins are:dowatered!1n steel liners or High Integrity. Containers as necessary, according to y L vendor's procedures. Resins may also be processed offsite by vitrification L

I at a licensed vendor facility, or they may be dried and used ast loose fill material'in packages of supercompacted waste. If the Contractor's PCP '

-TopicaljReport for dowatering, solidification o vitrification has been approved by the U. S.-Nuclear Regulatory Commission (NRC), the approved report:-is justification to ensure compliance with 10CFR20, 10CFR61, and 10CFR71 as required,by GGNS Technical Specifications. If the NRC has not j approved the Contractor's PCP Topical Report, then it is the Plant Safety j Review Committee's :(PSRC) responsibility to make certain that the (

Contractor's equipment and procedures are adequate to ensure compliance

. with.10CFR20, 10CFR61, and 10CFR71.

Radioactive liquids (e.g. oil, oily sludges, EHC fluid, glycol) may be shipped offsite for volume reduction by incineration or absorbed and "

incinerated at a licensed vendor facility. Alternately, radioactive liquids . and wet solids, including resins, may be solidified prior to 3

disposal. Solidification may be performed onsite by a contractor utilizing a mobile solidification system or offsite at a licensed vendor facility.

If the Contractor's PCP Topical Report for incineration or solidification has been. approved by the NRC, the approved report is justification to ensure compliance with 10CFR20, 10CFR61, and 10CFR71 as required by GGNS Technical' Specifications. If the NRC has not approved the Contractor's PCP Topical Report, then it is the PSRC's responsibility to make certain that the Contractor's equipment and procedures are adequate to ensure compliance with 10CFR20, 10CFR61, and 10CFR71.

. GRivND GULF, UNIT 1 Rev. 3 - 4/90 PCPREV3/JRSFLR-5

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f If incineration, solidificationior-vitrification istto_be performed ~offsite; j< at' a licensed - vendor ' facility the waste will be packaged ~ and shipped in

" ' '  : accordance with the requirements in 49CFR. The processing facility will . '

take title to the' waste and certify.that itLhas been properly incinerated, a solidified or vitrified prior to disposal.

, i B. Administrative Controls'

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Compliance with 49 CFR, 10CFR20, 10CFR61, 10CFR71<and state and disposal, site-criteria is assured by adherence to approved procedures'and instructions. Adherence to GGNS and ~ contractor procedures will be required

-for all activities related to processing of radioactive waste for burial.

Directions-for extensive or complex jobs where reliance on memory cannot be

• > trusted shall require the appropriate written. procedure to be present and-referred'to directly. Procedures shall include appropriate quantitative =

and/or qualitative criteria for verifying that the specified activities-have been satisfactorily accomplished.

Contractor procedures for onsite processing will be reviewed and approved

by the Radwaste Operations Section, Radiation Control Section and the PSR0 .

to ensure compliance with=the applicable portions of the PCP. Changes to 3

Contractor's procedures-will be approved by the Radweste Operations Section and Radiation Control and screened for forwarding to PSRC for review and.

approval when changes significantly affect- equipment or proc 6ss: parameters.

Documentation of these reviews -and approvals will be maintained as QA: 3-records.

in Documentation of pertinent data required to classify waste will be maintained on each batch of processed waste as required by Lapproved procedures. Documentation;will also be maintained to ensure that containers, shipping casks, and methods of packaging wastes meet applicable

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Federal regulations and disposal site criteria. , These documents will be n maintained-as QA records.

.C. Waste Streams GGNS has five radwaste streams as follows:

Stream #1 -

Condensate Precoat Filter Waste Stream #2 -

Reactor Water Clean Up and Fuel Pool Clean Up Precoat Filter Waste Stream #3 -

Liquid Radweste Floor Drain and Equipment Drain Systems Filter Waste Stream #4 -

Condensate and Liquid Radwaste Systems Domineralizer Waste Resin Stream #5 -

Contaminated Waste Oil GRAND GULF, UNIT 1 Rev. 3 - 4/90 PCPREV3/JRSFLR-6

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OtherYaitestreamswill'be;designatedasconditions= warrant'- Occasional-.

' ' limited' volumes of other waste may also be processed,Lincluding but not 3:

lini.ted'to :such liquids as'EHC fluid and glycol.-

D. Conditionina of Waste and Samplina for Verification of Solidification A verification of the solidification of liquid radwestes must:be performed' on'at:1 east every tenth container in a batch of waste. However, if trends l3 L ,

indicate the possibility of changing parameters which may have an' ef fect on P the' methods and materials used to-produce a monolithic solid with no-free-standing liquid, then more frequent sampling may be; required. When increased sampling < is required,; the frequency. will be established by the

-Radiation Control Superintendent.

1 NOTE:

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t - A Batt.h is defined as an isolated quantity of feed waste Jto be processed having constant physical and chemical-

characteristics; a quantity of material that is determined to be a homogenous mixture for purposes of 3_

producing stable, solidified billets for disposal as radioactive waste.

Example: ~ Thefcontents of a waste holding / storage / mixing tank that has been isolated (so that additional waste cannot be introduced) w uld constitute a batch. <

V Verification of solidification shall be performed as follows:

a) Three test samples will be taken from'the batch. The normal sample volume as specified in approved procedures will be used unless radiological conditions necessitate.a smaller volume.

b) The solidifying agents will be-added to the test' samples in different proportions.,

c) The test samples will be allowed to set or cure.

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d) After curing, the proportions of the solidification agents which produced the maximum practical compressive strengths shall be used.

NOTE:

The-most stable billet does not have to be used, 3 but the objective is not simply to achieve the minimum acceptable compressive strength.

e) If none of the samples are found to be satisfactory, the test shall be repeated until an acceptable solidified billet with no free-standing l3 liquid is obtained.

GRAND GUIE, UNIT 1 Rev. 3 - 4/90 PCPREV3/JRSFLR-7

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For batches. of miscellaneous ~ wastes, a verification of solidification lst 1 analysis willibe performed as-specified.in steps a) through e) above.

EIf.a contractor is perforcing1 solidification services, then the contractor will specify the chemical analysis requirements and the acceptable ranges

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for the physical and chemical ~ characteristics' of the waste- being processed Laccording to contractor's procedures.

The contractor's procedures shall- l3 address corrective actions - to be .taken;if samples fail to verify solidification-or the absence of free-standing liquids.

The proportions.of the solidification agents used for the test batch

-producingthe~ maximum-practicalcompressivestrengthsfortheverification..l3 of solidification shall be u: d for subsequent batches of the same waste

- stream. 4 E . :- Samplina for Verification'of Curie Content An isotopic analysis;shall be' performed on~at least every tenth container

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in a-batch'of each vaste stream so that the waste can be classified in I accordance with 10CFR61. .However, more frequent analysis asy.be performed if deemed necessary by the Radiation-Control Superintendent. l3

-The isotopic and curie content of each shipping container shall be

. determined in accordance with'49CFR packaging requirements. The total 3 activity in the container may be determined by either isotopic analysis or '

by dose-rate-to-curie conversion.

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