ML20212E075

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Rev 2 to Process Control Program Description
ML20212E075
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 10/15/1986
From: Rolonda Jackson, Mckay J, Megan Wright
MIDDLE SOUTH UTILITIES, INC.
To:
Shared Package
ML20212D758 List:
References
PROC-861015, NUDOCS 8703040265
Download: ML20212E075 (7)
v • d • e


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l PROCESS CONTROL PROGRAN DESCRIPTION l REVISION NO. 2 1

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e Revision No. 2 Date: 10/86 GRAND GUIS NUCLEAR STATION PROCESS CONTROL PROGRAM DESCRIPTION SAFETY RELATED EVALUATION APPLICABILITY SAFETY EVALUATION ENVIRONMENTAL EVALUATION

@ APPLICABLE  % APPLICABLE l[l NOT APPLICABLE l[l NOT APPLICABLE Reviewed / Approved: L rdA/,N [

Supervisor, Radiological Services

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Reviewed / Approved: / Nh U" Supervisor, Envi ptalServices Date Reviewed / Approved: / / /

Manager,Radiologeal&EnvironmentalServicesDate Reviewed / Approved: b / */ N Dirctor,NuclegSport Date Reviewed /Appro' red: // [  ! / b db shairman, Pladt Balety vTek Committee Date J

i grand GULF, UNIT 1 . Rev. 2 - 10/86 1

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PCP TABLE OF CONTENTS P, ag DESCRIPTION APPROVAL SHEET.......................................... i TABLE OF C0NTENTS................................................... ii LIST OF EFFECTIVE PAGES............................................. iii A. Introduction................................................... I

3. Administrative Controls........................................ 2 C. Waste Streams.................................................. 2 D. Conditioning of Wastes and Sampling for Verification g~~

of Solidification.............................................. 2 E. Packaging Requirements......................................... 3 F. Sampling for Verification of Curie Content..................... 4 L

i it GRAND GULF, UNIT 1 Rev. 2 - 10/36 N_____________-___---__-_______________________--_____-_-____-____---_______-___________

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PCP LIST CF EFTECTIVE PAGES PAGE REV.

NO. NO.

i - 111 2 1-4 2 e

111 GRAND GULF, UNIT 1 ,

Rev. 2 - 10/86

GRAND GULF NUCLEAR STATION PROCESS CONTROL PROGRAM (PCP) DESCRIPTION REQUIREMENTS FOR PROCESSING OF RADI0 ACTIVE LIQUIDS AND WET SOLI _DS A. Introduction A large portion of the waste produced in a nuclear power station is in a form which is either liquid or in a wet solid form (e.g., resins, filter sludge, oil) and requires processing to obtain an acceptable, solid, monolithic form for burial. Radioactive wet solids (resins) are JL processed by dewatering or solidification to assure there is no free-standing water. Compliance with 49CFR, 10CFR20, 10CFR61, 10CFR71 and other applicable regulations is assured by adherence to approved procedurea and instructions.

The Grand Gulf Nuclear Station (GGNS) Radwaste 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 the processing of wet wastes.

Radwaste processing activities are coordinated with the Radiation Control Section to ensure personnel exposures are kept ALARA.

Dewatering of resins is performed on-site by a qualified vendor using a mobile dewatering system. Resins are dewatered in steel liners or polyethylene High Integrity Containers as is necessary. Dewatering is performed according to vendor's procedures. If the Contractor's PCP 1 Topical Report has been approved by the U. S. Nuclear Regulatory Commission (NRC), the accepted 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 Plant Safety Review Committee's (PSRC) responsibility to make certain that the Contractor's equipment and procidures are adequate to ensure compliance with 10CFR20, 10CFR61, and 10CFA71.

Oil, oily sludges and other wet solids will be solidified or absorbed prior to shipment offsite for disposal. Solidification will be periodically performed on-site by a contractor utilizing a mobile solidification system. If the Contractor's PCP Topical Report has been approved by the U. S. Nuclear Regulatory Commission (NRC), the accepted report is justification to ennure 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.

GRAND GULF, UNIT 1 ,

Rev. 2 - 10/86

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3. Administrative Controls Directions for entensive or comples jobs where reliance on memory cannot be trusted shall require the appropriate written procedure to be present and referred to directly.

Directives shall include appropriate quantitative and/or qualitative criteria for verifying that the specified activities have been satisfactorily accomplished.

Castractor procedures will be reviewed and approved by the Radweste Operations Section and Chemistry / Radiation Control Section, to ensure compliance with the applicable portions of the PCp. Changes to Contractor's procedures will be screened by the Radweste Operations [

8ection and Chemistry / Radiation Control and forwarded to PSRC for '

review wnen changes significantly affect equipment or process ,

parameters.

Documentation will be maintained on each batch of processed waste indicating source of waste, date processed, processing parameters,  ;

physical and chemical characteristics, dose rates, contamination levels

  • and other pertinent data required to classify the waste. Documentation will also be maintained to ensure that containers, shipping casks, and methods of packaging wastes meet applicable Federal regulations and '

disposal site criteria.

C. Waste Streams 2,.

GGNS has four radwaste streams as follows: -

Stream #1 - Condensate Clean Tank or Condensate Phase Separator Tanks (condensate filter backwash) ,

Stream #2 - Reactor Water Clean Up Phase Separator Tanks (RWCU and Fuel Fool Clean Up filter backwash)

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Stream #3 - Liquid Padweste Floor Drain and Equipment Drain Systems (filter sludge)  :

I Stream #4 - Condensate and Liquid Radweste Systems (resin)

Other waste streams will be designated as conditions warrant.

D. Conditionina of Waste and Samplina for Verification of Solidificatio_n_

A verification of the solidification of liquid radwestes must be performed on at~1 east every tenth batch of waste. However, if trends (

indicate the possibility of changing parameters which may have an effect on the methods and materials used to produce a sonolithic solid with t.o free-standing liquid, then more frequent sampling may be +

required. When increased sampling is required, the frequency will be established by the Chemistry / Radiation Control Superintendent.

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GRAND GULF, UNIT 1 ,

Rev. 2 - 10/86 L

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, d) Af ter curing, the proportions of the solidification agents whict produced the most stable billet shall be used.

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

For batches of miscellaneous wastes, a grab sample will be obtained and a verification of solidification analysis will be performed as specified in steps a) through e) above.

O If a contractor is performing solidification services, then the contractor will specify the chemical analysis requirenents and the acceptable ranges for the physical and chemical characteristics of the waste being processed. The contractor's procedures shall address i 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 for the verification of solidification shall be used for subsequent batches of the same waste stream.

E. Packaging Requirements Radioactive waste generated at GGNS will be shipped to a licensed disposal site for burial. Prior to shipment, performance and/or verification of the following shall be made to ensure compliance with 49CTR,10CFR20,10CFR61,10CFR71 and other applicable regulations and burial site criteria:

  • total contained activity
  • external dose rate
  • external contamination levels
  • physical form
  • chemical form
  • waste classification
  • absence of free-standing liquids '3-l GRAND CUlf, UNIT 1 ,

Rev. 2 - 10/86 k-

l All shipping containers will be sampled for surface contamination and decontaminated, as necessary, prior to shipment, g, The isotopic and curie content of each shipping container shall be determined. -

F. Sampling for Verification of Curie content An isotopic analysis shall be performed on at least every tenth batch of each waste stream so that t.be waste can be classified in accordance with 10CFR61. Ilowever, more frequent analysis may be performed if deemed necessary by the Chemistry / Radiation Control Superintendent.

The total activity in the container may be determined by either isotopic analysis or by dose rate conversion.

GRAND GULF, UNIT 1 Rev. 2 - 10/86 k .

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