ML20215L287

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Rev 2 to Process Control Program Description
ML20215L287
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 10/15/1986
From: Bell R, Rolonda Jackson, Mckay L
MISSISSIPPI POWER & LIGHT CO.
To:
Shared Package
ML20215L161 List:
References
PROC-861015, NUDOCS 8610280561
Download: ML20215L287 (11)
v • d • e


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e PROCESS CONTROL PROGRAM DESCRIPTION GRAND GULF NUCLEAR STATION October, 1986 Revision 2 8610280561 861022 PDR ADOCK 05000416 P PDrt GRAND GULF, UNIT 1 Rev. 2 - 10/86 k

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

@ APPLICABLE ( APPLICABLE

((l NOT APPLICABLE l]l NOT APPLICABLE Reviewed / Approved: v /d+[, 8 Cd / /C I/8f, Supe'rvisor, Radiological Services Date Reviewed / Approved: / /

Supervisor, Envi tal Services Date Reviewed / Approved: / /  !

Manager,Radiologeal&EnvironmentalServicesDate Reviewed / Approved: / */

Dir~ector, Nuclep Stport Date Reviewed / Approved: / [ [ / _, / b~ db Chairman, Plaht $afety eviek Committee

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

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PCP TABLE OF CONTENTS Page DESCRIPTION APPROVAL SHEET.......................................... i TABLE OF C0NTENTS................................................... ii LIST OF EFFECTIVE PAGES............................................. iii A. Introduction................................................... I B. Administrative Controls........................................ 2 C. Waste Streams.................................................. 2 D. Conditioning of Wastes and Sampling for Verification o f S o l i d i f i ca t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 E. Packaging Requirements......................................... 3 F. Sampling for Verification of Curie Content..................... 4 i

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

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PCP LIST OF EFFECTIVE PAGES PAGE REV.

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iii GRAND GUI.F, UNIT 1 Rev. 2 - 10/86

GRAND GULF NUCLEAR STATION PROCESS CONTROL PROGRAM (PCP) DESCRIPTION REQUIREMENTS FOR PROCESSING OF RADIOACTIVE LIQUIDS AND WET SOLIDS 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 procedures 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 procedures are adequate to ensure compliance with 10CFR20, 10CER61, and 10CFR71.

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 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.

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

1 B. Administrative Controls 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.

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

Contractor procedures will be reviewed and approved by the Radwaste 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 Radwaste Operations Section and Chemistry / Radiation Control and forwarded to PSRC for review when 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. Vaste 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 Pool Clean Up filter backwash)

Stream #3 -

Liquid Radwaste Floor Drain and Equipment Drain Systems (filter sludge)

Stream #4 -

Condensate and Liquid Radwaste Systems (resin)

Other waste streams will be designated as conditions warrant.

D. Conditioning of Waste and Sampling for Verification of Solidification A verification of the solidification of liquid radwastes must be

, performed on at least every tenth batch of waste. However, if trends i

indicate the possibility of changing parameters which may have an effect on 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 I

established by the Chemistry / Radiation Control Superintendent.

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

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7 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) After curing, the proportions of the solidification agents which 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.

If a contractor is performing solidification services, then the contractor will specify the chemical analysis requirements and the acceptable ranges for the physical and chemical characteristics of ' .2 waste being processed. The contractor's procedures shall address corrective actions to be taken if samples fail to verify solidification j or the absence of free-standing liquids. i 7

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 49CFR, 10CFR20, 10CFR61, 10CFR71 and other applicable regulations and burial site criteria:

  • total contained activity
  • cxternal dose rate
  • external contamination levels
  • - physical form o chemical form
  • waste classification
  • absence of free-standing liquids "2-GRAND GULF, UNIT 1 Rev. 2 - 10/86

f.

All shipping containers will be sampled for surface contamination and decontaminated, as necessary, prior to shipment. 7, 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 the waste can be classified in accordance with 10CFR61. However, more frequent analysis may be performed if deemed necessary by the Chemistry / Radiation Control Superintendent.

The tc.a1 activity in the container may be determined by either iso' nic analysis or by dose rate conversion.

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

ATTACHMENT III EXPLANATION OF CIIANGES IN REVISION 2 0F GGNS PCP i

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EXPLANATION OF CHANGES IN REVISION 2 0F GGNS PCP 1

A. Introduction

  • Elimination of Evaporator Bottoms as a waste stream. Installed evaporator systems have not been used to process radwaste and current GGNS radwaste management plans do not include utilization of these systems.
  • Addition of contaminated oil as a waste form.
  • Reference to GGNS Radwaste Solidification System, solidification media, and conditioning additives removed. The in-house system is non-operational and there are no plans to use it as installed. Nuclear Plant Engineering Department continues to evaluate solidification systems for use at GGNS in the future.

Should the need arise for solidification services, a vendor would be contracted to bring in a mobile solidification system.

  • The Vendor's Topical Report, if accepted by the NRC, is justification to ensure compliance. If not approved by the NRC, the Topical Report, operating procedures, and equipment would be evaluated and approved by the PSRC prior to any radwaste processing to ensure the final waste form product would be acceptable under the requirements of 49CFR, 10CFR20, 10CFR61, 10CFR71 and other applicable regulations. This was the intent of paragraph two of Rev. 1. These statements have been reworded for clarity.
  • Reworked statement to clarify that wet solids (resins) are processed by vendor dewatering system. Specified containers used for processing.
  • Added statement to clarify that radwaste processing activities are coordinated with Radiation Control Section to ensure ALARA considerations are addressed.

B. Administrative Controls

  • Changed statement that PSRC will review all Contractor's procedures. This review is only required if NRC has not already approved contractor's Topical Report as clarified in Introduction Section. Radwaste Operations and Chemistry / Radiation Control will screen all procedures.
  • Added statement that documentation will be maintained on containers, shipping casks, and methods of packaging.

C. Waste Streams

  • Deleted Evaporator Bottoms from list of waste streams
  • Combined Floor Drain and Equipment Drain Systems into one waste stream since the two are always mixed prior to transfer to the mobile processing system.

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D D. Conditioning of Wastes and Sampling for Verification of Solidification (in Rev.1, Section D. _ Conditioning of Specific Batches of Waste and Section E. Sampling for Verification of Solidification)

  • Deleted portions of Section D that pertained to operation of in-house solidification system.
  • Deleted statement that PSRC must approve contractor's solidification procedures. This review is only required if NRC has not already approved contractor's Topical Report as clarified in Introduction Section.

E. Packagina Requirements (in Rev. 1, Section F)

  • Added statement that radwaste will be shipped to a licensed disposal site for burial.
  • Added commitment to verify absence of free-standing liquids
  • Added the word " shipping" to identify which containers will be sampled and surveyed.

F. Samplina for Verification of Curie Content (in Rev. 1, Section G)

  • Added action to statement regarding increased sampling frequency for clarity.

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