ML20212E031

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Rev 1 to Process Control Program Description
ML20212E031
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 02/29/1984
From: Mckay J, Galen Smith, Jay Wallace
MIDDLE SOUTH UTILITIES, INC.
To:
Shared Package
ML20212D758 List:
References
PROC-840229, NUDOCS 8703040256
Download: ML20212E031 (9)
v • d • e


Text

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e O c ATTACHMENT VII PROCESS CONTROL PROGRAM DESCRIPTION REVISION NO, I hh30 6 861231 n " eng;s PENV ODCM ATTS - 7

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Revision No. I Date 2/84 GRAND GUIF NUCLEAR STATICE PROCESS CCNTROL PROGRAM DESCRIPTICN SAITTY REIATED EVALUATICN APPLICABILITY SAtrd EVALUATIN DNIRCNMENTAL EVALUATICN APPLICABIE APPLICABLE X NCTI APPLICABLE X NOT APPLICABIE Reviewed / Approved g m [ M 42 [ / a s e_ s 8[/S[d%f

. p$upervisor of Radiological S# vices / Data Reviewed / Approved: w.m O id 2/ /f/8y

  • l ~ $ulsevisoz'of Enviromental Services /Date ,

Reviewed / Approved: b Manager of Radiologip. & Environmental Services /Date Reviewed / Approved:

b Manager of Nuclear Services /Date Reviewed / Approved: . . A/Y//C/

Chairinan, Plant Safety Review Cmmittee/Date i

GRAND GUIE, UNIT 1 Rev. 1 - 2/84

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.- PCP TABLE OF CONrfMTS M

osscawrIm APPBNAI, SETF . . . . . . . . . . . . . . . . . . . . . . . . . i ii TABLE & CONrarrs . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

iii LIST T EFFECTIVE PAGES . . . . . . . . . . . . . . . . . . . . . . . . . . . .

1 A. Introduction ..................................

1 B. Administrative Controls . . . . . . . . . . . . . . . . . . . . . . .

2 C. Waste Streams .................................

Conditioning of Specific Batches of Wasta ..... 2 D.

E. Sanpling for Verification of Solidification ... 3 j F. Packaging Requireraents . . . . . . . . . . . . . . . . . . . . . . . . 3 Sanpling for Verification of Curie Content .... 4 G.

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11 GRAND GUIE, UNIT 1 Rev. 1 - 2/84

. PCP LIST OF EFTECTIVE PAGES PAGE REV.

NO. NO.

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1-4 1 iii GRAtO GUIE, UNIT 1 Rev.1 - 2/84

GRAND GULF NUCLEAR STATION <

PRCCESS C.ONTROL PROGRAM (PCP) DESCRIPTION i

REQUIREMENTS FOR PROCESSING OF RADI0 ACTIVE 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, evaporator bottoms) and requires processing to obtain an acceptable, solid, monolithic form for burial. The Grand Gulf Nuclear Station (GGNS) Radwaste Solidification System provides for the solidification of these radioactive wastes. The radioactive wastes are mixed with cement or other binding media (e.g., asphalt. Dow media) and ,

conditioning additives to produce a monolithic solid with no free-standing liquids. In addition, radioactive wet solids may also be processed by dewatering 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.

If the solidification of waste is being performed by a contractor utilizing a mobile or temporary solidification system, the Plant Safety Review Comittee (PSRC) must review and approve procedures and the major equipment to be used. If the Contractor's PCP Topical Report has been approved by -

the U.S. Nuclear Regulatory Comission (NRC), the accepted report is justification to ensure compliance with 10CFR20, 10CFR61, and 10CFR71 as i 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.

8. Administrative Controls I Directions for extensive or complex jobs where reliance on memory cannot be trusted shall require the appropriate written procedure to be present and l referred to directly.

Directives shall include appropriate quantitative and/or qualitative l

criteria for verifying that the specified activities have been i

satisfactorily accomplished.

Contractor procedures will be reviewed and approved by the PSRC, to ensure t compliance with the applicable portions of the Process Control Program.

Changes to Contractor's procedures will be screened by the Radwaste i Operations Section and Chemistry / Radiation Control and forwarded to PSRC for review when changes significantly affect equipment or process parameters.

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f GRAND GULF, UNIT 1 Rev. 1 2/84

f 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.

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

Stream #1 - Condensate Clean Tank or Condensate Phase Separator Tanks '

(condensate filter backwash)

Stream #2 - RWCU Phase Separator Tanks (RWCU and FpCC filter demineralizerbackwash) i Stream #3 - Liquid Radwaste Floor Drain Filter (Ecodex)

Stream #4 - Liquid Radwaste Equipment Filter (Ecodex)

Stream #5 - Resins from Condensate and Liquid Radwaste Systems l

Stream #6 - Evaporator Bottoms from resin regeneration i

Stream #7 - Evaporator Bottoms from miscellaneous chemicals Stream #8 - Evaporator Bottoms from Floor Drain wastes Other waste strears will be designated as conditions warrant.

D. Conditioning of Specific Batches of Waste The Radwaste Solidification System will be operated in accordance with approved procedures in a manner which will permit segregation of waste 1 inputs into waste streams. With proper segregation, the only parameters that are normally variable are pH, percent solids, and chemical  :

i contaminants (e.g., glycol, oil). .

> These parameters must be analyzed and conditioned in accordance with  ;

approved procedures. Conditioning may include adjustment of water content or pH.

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In the event that the specific activity of the waste exceeds the limits for i maximum activity which can be safely processed, the waste will be adjusted l

according to directions from the Chemistry / Radiation Control l

Superintendent, or an appointed designee.

! When a Contractor provides solidification services, the Contractor will i specify the chemical analysis requirements and the acceptable ranges for the physical and chemical characteristics of the waste being processed.

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GRAND GULF, UNIT 1 Rev. 1 - 2/84

E. Samplina 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 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 established by the Chemistry /

Radiation Control Superintendent.

Verification of solidification shall be perfonned 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 i verification of solidification analysis will be performed as specified in steps a) through e) above.

i If a Contractor is performing solidification services, then the 1 j

Contractor's procedures for verification of solidification may be used if approved by the PSRC.

The proportions of the solidification agents used for the verification of solidification shall be used for subsequent batches of the same waste stream.

F. P_ackagina Requirements Prior to shipment, verification of the following shall be made to ensure compliance with 49CFR, 10CFR20, 10CFR61, 10CFR71 and other applicable regulations and burial site criteria:

o total contained activity o external dose rate o external contamination levels o physical fonn o chemical form o waste classification GRAND GULF, UNIT 1 -3 Rev. 1 - 2/84

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. . D All containers will be sampled for surface contamination and decontaminated, as necessary, prior to shipment.

The isotopic and curie content of each container shall be determined. 1 l

6. Sampling for Verification of Curie Content 1 An isotopic analysis shall be performed on at least every tenth batch of l each waste stream so that the waste can be classified in accordance with 10CFR61. However, more frequent analysis may be deemed necessary by the
  • Chemistry / Radiation Control Superintendent.

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

I Rev. 1 - 2/84 GRAND GULF UNIT 1 r- - .--.n, . - . . -

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