ML20112G449

From kanterella
Revision as of 19:33, 17 May 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Rev 0 to Procedure RWS-0204, Process Control Program
ML20112G449
Person / Time
Site: River Bend Entergy icon.png
Issue date: 01/07/1985
From:
GULF STATES UTILITIES CO.
To:
Shared Package
ML20112G447 List:
References
RWS-0204, RWS-204, NUDOCS 8501160343
Download: ML20112G449 (12)


Text

r ENCLOSURE 1 l -

I PROCESS CONTROL PROGRAM

's j TABLE OF CONTENTS SECTION PAGE NO.

1.0 PURPOSE 2

2.0 REFERENCES

2 3.0 RESPONSIBILITIES 3 i

i 4.0 DEFINITIONS 3 i

! 5.0 PROCEDURE 3 1

5.1 General Requirements 3 5.2 Collection of Samples 4 5.3 Chemical Analysis of Waste Samples 5 5.4 Radiochemical Analysis of Waste Samples 6

. 5.5 Waste Conditioning 6 5.6 Test Solidification 6 5.7 Process Formulations 7 5.8 Documentation 7 t

6.0 ACCEPTANCE CRITERIA 7 7.0 DOCUMENTATION 8 I

ATTACHMENTS ATTACHMENT 1 - WASTE SOLIDIFICATION DATA SHEET 9

!I c!

I io ,

l -

l 1

i-l!

'i 8501160343 850107

! i- PDR ADOCK 05000458 l A PDR

'. N/A N/A RWS-0204 REV. O PAGE 1 0F 11 i

F . -

4 t

3, 1.0 PURPOSE 3- 1.1 The purpose of the Process Control Program (PCP) for radwaste 3 solidification is to provide reasonable assurance and documentation

'! of the solidification of processed radioactive wastes as set forth

in 10CFR20, 10CFR61, 10CFR71, the RBS 3/4.11.3 Technical i Specification, Federal and State regulations, burial ground requirements, and other requirements governing the disposal of

, radioactive wastes.

1.2 The PCP contains the sampling, tests, analyses, and formulation

- determination by which waste classification and solidification of j radioactive wastes is assured.

2.0 REFERENCES

2.1 ASTM STANDARD Part 13 2.2 Chem-Nuclear Systems Incorporated Process Control Program, SD-0P-003 2.3 10CFR 20, Standards for Protection Against Radiation, 1980 i

,j 2.4 10CFR 61 Waste, 1981 Licensing Requirements for Land Disposal of Radioactive 3

i 2.5 10CFR 71, Packaging of Radioactive Material for Transport and

( Transportation of Radioactive Material Under Certain Conditions, j Nov., 1979 2.6 Regulatory Guide 8.8, Information Relevant to Ensuring that Occupa-1 tion Radiation Exposures at Nuclear Power Stations will be as Low as jj Reasonably Achievable, Rev. 3, 1978 .

,h 2.7 S0P-0108, Operation of the Process Liquid Radwaste System

)

t

, -i 2.8 RBS FSAR 11.4, Radioactive Solid Waste System f 3

) 2.9 COP-0019, Sampling of Liquid Radwaste Sludge and Resin Holding Tanks 1

!! 2.10 RWP-0307, Radioactive Waste Segregation Ii ~

2.11 RWP-0304, Radioactive Waste Storage and Accountability

'i l? 2.12 RSP-0200, Radiation Work Permits i 2.13 ADM-0006, Control of Plant Records 3

2.14 ADM ,0038, Radioactive Waste Management Program 2.15 RBS Technical Specifications

' )i i

. 7 i

N/A RWS-0204 REV. O PAGE 2 0F 11 N/A g l l ll l l l ji .

i -

i

3.0 RESPONSIBILITIES s

j 3.1 The RBS Radwaste Section shall be responsible for the implementation

of the PCP and adhere to compliance with RBS Technical Specification i 3/4.11.3 Ref. 2.15.

i '4.0 DEFINITIONS

} 4.1 Solidification - The conversion of wet wastes into a form that

  • meets

! shipping and burial ground requirements.

4.2 Batch - A specified quantity of waste material requiring solidifica-i tion, any portion of which would have the same physical and chemical i characteristics as the whole.

I l 4.3 Waste Classification - The determination of waste class as outlined

} in 10CFR61 by radionuclide isotopic analysis and/or correlation with i measured nuclides.

Free Liquid - Any nonabsorbed liquid in a radwaste package. The 4.4 shipment of any free liquid in a package of radwaste is absolutely prohibited.

i

4.5 DAW - Dry Activated Waste.
4.6 CNSI - Chem-Nuclear Systems Inc.

-j 5.0 PROCEDURE 5.1 General Requirements I-5.1.1 As required by RBS Effluent Technical Specification

} 3/4.11.3, the PCP shall be used to verify the solidification 1 of at least one representative test sample from at least every tenth batch of each type of wet radioactive waste

' ;[ processed.

').

,i 5.1.2 For the purpose of the RBS PCP, a batch shall consist of a lJ particular amount of liquid wastes / sludges requiring 1 solidification (i.e., the amount of waste content within a j tank requiring solidification). If new material is added to 4 a tank's contents which is currently being processed, a new L,-

batch is created and further sampling must be performed li'i prior to solidification.

} 5.1.3 If any sanple fails to solidify, solidification of the batch l under test shall be suspended until such time as additional test samples can be obtained, alternative solidification

" parameters can be determined in accordance with the PCP and i]l t

, g a subsequent test verifies solidification. - Solidification

j of the batch may then be resume.d using the alternative j solidification parameters determined by the vendor PCP.

l} .N/A N/A RWS-0204 REV. O PAGE 3 0F 11 ii l*

i

~

1 1

5.1.4 If the initial test sample from a batch of waste fails to 3 verify solidification, then representative test samples i shall be collected from each consecutive batch of the same

] type of waste until three (3) consecutive test specimens j demonstrate solidification using the alternate parameters of

} Step 6.1.3.

i '

5.1.5 For high activity wastes, where handling samples could result in personnel radiation exposures which are inconsis-t tent with ALARA principles, representative non-radioactive samples may be test solidified. These samples shall be as

~

- close to the actual waste and chemical properties as possi-i ble. Typical unexpended mixed bead resin may be used to i! simulate the spent bead resin.

1

) 5.1.6 Where practical, all chemicals used to condition or solidify j waste (or simulated waste) in solidification tests shall be

, ] identical to the actual chemicals to be used in full scale

,f . solidification.

. 5.1.7 All solidification and sampling activities inside a Radiation Controlled Area shall be conducted in accordance with the applicable Radiation Work Permit requirements

) (Reference 2.12).

,1

.; 5.2 Collection of Sanoles 4 5.2.1 Waste Solidification Data Sheet (Attachment 1)

, 5.2.1.1 The Waste Solidification Data Sheet will contain pertinent information on the characteristics of the

, test sample solidified in order to verify solidi-fication of subsequent batches of similar waste without retesting.

.i 5.2.1.2 The test sample data for waste shall include, but 4 is not limited to: the type of wastes solidified;

! percent total dissolved solids; pH; volume of

- - - sample; amount of oil- in the - sample; the waste to

-i portland cement ratio; the portland cement to the j other ingredients as determined by the vendor t (similar to CNSI) supplied ratio.

5.2.1.3 The Waste Splidification Data Sheet will include the batch number, batch volume, waste type, waste total waste received, total classification, portland cement added. total other ingredients

i. added and the date solidified.

1 I'

3

- N/A. N/A RWS-0204 REV. O PAGE 4 0F 11 i,

, I1 ' .

2 _

1 i 5.2.1.4 If waste pretreatment is necessary prior to actual j batch solidification per the results of Step 5.5, 4 the agent used and amount added shall be denoted in 1

the remarks section of the Waste Solidification i Data Sheet.

i 5.2.2 Taking Samples j 5.2.2.1 A sample of the contents of the Waste Sludge Tank

! that flows into the vendor's fill head and any

! other wastes requiring solidification must be taken

in order to determine the actual process
formulation for solidification, any pretreatment of
the waste needed prior to solidification, and the J waste classification of the tank contents to be j solidified.
5.2.2.2 Sample sizes, as determined by the Radwaste Sec-

] tion, shall be compatible with the standard size

samples used for radioactivity and chemical analy-J sis.

~;

5.2.2.3 If the radioactivity levels are too high to permit

~ full size samples to be taken, then smaller samples shall be taken with the results corrected accord-ingly.

j 5.2.2.4 Sufficient sampling lead time of the vendor's fill t head allotted prior to the planned waste 2 solidification of a batch to allow adequate time to complete the required testing and verification of

solidification, as applicable.

?

. 5.2.2.5 The contents of the waste tank that is to be Ia solidified should be recirculated (mixed) prior to

.L sampling to ensure that a representative sample is f obtained.

'i? 5.2.2.6 Sampling of resins will be performed per Reference.

j 2.9.

5.3 Chemical Analysis of Waste Samples I 5.3.1 Waste samples shall be analyzed for total dissolved solids,

'; pH and conductivity by the vendor. Oil content and gamma isotopic analysis will be performed by the Chemistry Depart-

? ment. Information shall be recorded on the Waste Solidi-j '

fication Data Sheet (Attachment 1).

li i

j N/A N/A RWS-0204 REV. O PAGE 5 0F 11 i

f

a 1

2

.i 5.3.2 Spent resin beads shall be sampled and analyzed for oil 3 content and pH by the water surrounding the beads. Informa-i tion shall be recorded on the Waste Solidification Data

'; Sheet (Attachment 1).

s

> 5.4 Radiochemical Analysis of Waste Samples 5.4.1 A gamma isotopic analysis will be performed on each batch to

be solidified.

J l 5.4.2 This analysis will be used to determine acceptability for

. solidification as well as waste classification of the waste

,} to be solidified i)

({ 5.4.3 The results of the gamma isotopic analysis shall be attached to the Waste Solidification Data Sheet (Attachment 1).

I 5.5 Waste Conditioning j 5.5.1 Prior to the test sample solidification, the pH of the sample shall be adjusted to a range as specified by vendor's

>. PCP.

2 5.5.2 Should adjustment be necessary, the agent and quantity used shall be recorded on the Waste Solidification Data Sheet

(Attachment 1).

'l

..6 5.5.3 If oil is present in quantities greater than 1% by volume, 1 dilution of the batch to below 1% is required prior to solidification.

$. 5.5.4 If reduction of the oil' content is impossible or impracti-o cal, solidification of the batch shall not be attempted using the Normal Solidification System, but shall be accom-J plished using a bulk processing method as described in the

,j . vendor's PCP at RBS.

5.6 Test Solidification

)]) 5.6.1 Whenever pretreatment of a batch is- necessary, the waste

~.

? sample shall have the required pretreatment accomplished prior to the test solidification.

4 5.6.2 Prepare the test solidification vessel (suitable sized disposable beaker) with a mixing device.

1 5.6.3 Transfer a known representative volume of the waste to the 1- test solidification container.

[

}

I *

N/A N/A RWS-0204 REY. O PAGE 6 0F 11 i L  !

'l L

1- .

3 3

1

5.6.4 Add the appropriate proportional amount of portland cement j and other ingredients as applicable, determined by the 3

vendor's PCP.

j- 5.6.5 Initiate mixing of the waste, portland cement and other i ingredients. After ten (10) minutes of mixing or when a I homogeneous mixture is obtained, allow the waste to stand j for the length of time required by the vendor's PCP.

t j 5.6.6 If any free liquid is observed on the top of the sample, decant the liquid into a clear volumetric beaker and record

the amount of liquid transferred. Calculate the percent of i free liquid and record the date on the Waste Solidification j Data Sheet (Attachment 1).

5.7 Process Formulations i Prior to actual solidification of the waste to be solidified, i classification and acceptability for near-surface disposal shall be

determined. This will involve calculating the activity within the i- projected waste containers using the isotopic analysis determined in
Step 5.4.1, in the solidification formulas determined below.

I 5.7.1 Solidification will be performed as per formulas stated in j vendor's PCP and operating sequences specified in References 2.10 and 2.11.

9-l 5 5.8 Documentation

?

l 5.8.1 Upon completion of Attachment 1 document per Reference 2.13

]- (ADM-0006).

'I 6.0 ACCEPTANCE CRITERIA i

6.1 Test Solidification Acceptability -

6.1.1 The test sample solidification will be considered acceptable fg from a free liquid standpoint if it is the lessor of either g 1% by volume or burial site limits.

6.1.2 The test sample solidification will be considered acceptable

[ from a solid mass standpoint (i.e., structural stability) if 1 it is evident from it's physical appearance that the solid-

! ified waste maintains its shape when removed from the j container.

6.1.3 If either or both of the above checks fail to meet . the 1 stated criteria, alternative solidification parameters must I

be determined according to vendor PCP SD-09-003 before

,l solidification can proceed, i.

i 1

)

I N/A N/A RWS-0204_ REV. O PAGE 7 0F 11 I 4 I I ll I

  • ~

'f 6.1.4 If the initial test solidification of a batch is unaccept-y able, then a representative sample shall be test solidified

on each subsequent batch of the same type of waste until j three consecutive test samples verify solidification using j the alternate parameters of Step 6.1.3.

4

6.1.5 If a test sample fails to provide acceptable solidification j of waste, mix equal volumes of dry cement and water to j ensure that the problem is not due to a bad batch of cement.

.?

7.0 DOCUMENTATION i Attachment 1 - Waste Solidification Data Sheet.

i "END" b

i e

'h J

i t

( l 3

l1

'{

l,

[.

1 . .

1 1

l'

g N/A N/A RWS-0204 REY. O PAGE 8 0F 11 l' l I

!}

. - .. .. . = _ - _ .

4 s a

ATTACHMENT - 1 WASTE SOLIDIFICATION DATA SHEET k

j WASTE SOLIDIFICATION DATA SHEET

. Batch No. :

i 4~ i Sampie ilo.:

Date:

Prepared By:

I. Prior Batch Sample Solidification

. Verify prior batch sample solidification performed. Check one below and 7, show date and batch number of sample.

Evaporator Bottems Date: Batch No:

It . Chemical Wastes Date: Batch No:

.. 1 Resins Date: Batch No:

4 -- Other e

II. Batch Sample Analysis

3. ,

. A. Lab Results j..

Sample Volume If less than 7 or greater than pH of Waste 10 refer to Section 5.5 of PCP.

{

Percent Total Dissolved Solids

.f ,

t- Specific Gravity

. If greater than 1% refer to

& Waste Oil Content Section 5.5 of PCP.

t i .f. Radionuclide Content Attach copy of isotopic gamma Jj analysis printout.

1 Waste Classification.

i 3 B. Waste Pretreatment

-d

,i pH - Identify agent used and quantity to adjust pH of the waste in

-1 the sample.

[ Agent / Quantity Adjusted pH value Performed by:- Date:

i s

,t .

, ATTACHMENT - l' PAGE 10F 3 RWS-0204 REV. O PAGE 9 0F 11 i ,

.1 - .

t

'6 '-

:4 i t j.
'- ATTACHMENT - 1 WASTE SOLIDIFICATION DATA SHEET f III. Test Solidification (Required on at least every tenth batch of each

.! - type of wet radioactive waste.)

'] A Test Solidification Formula:

e i Volume of Waste:

1 1 Volume of Cement:

,j Volume of other ingredients:

I Waste / Cement Ratio:

c Cement / Ingredient Ratio:

j. Total Volume

- B. Free-Standing Water Analysis:

i Volume of Decanted Water

!h Volume of Sample:

-)  % Free-Standing Water

4N! C. Solidification Acceptabilit3 I

6 1. Percent of free-standing water calculated in Section III.B l .j (above) must be less than disposal facility criteria.

2. Visual physical appearance: -. Verify that the solidified waste would maintain its shape if removed from the container,

,2 l ;8 : 3. Other (state additional results here)

,2 i

! ]1 Performed By: Date:

- 'IV. Batch Solidification j-1 A. Formula (Per Drum Basis) i Waste to be solidified (gallons) g[

i Cementadded(pounds)

'1.

, .'I Other ingredient (added) i U

l-t j ATTACHMENT - 1~ PAGE 2 0F 3 RWS-0204 REY. O PAGE 10 0F 11

!L 1

^

E .I - _ --

.i

'i; i I

- ATTACHMENT - 1 WASTE SOLIDIFICATION DATA SHEET 1

1 2

,4 SOLIDIFICATION ACCEPTABLE / UNACCEPTABLE

(circleone)

+

B. Remarks 4

14

[ Performed By: Date: _

Reviewed By: Date:

i ;.

i e

  • t l

l'

,4

-i l }'

l-k a . _ _ , _ _ _ .

l z,

,I l'i i

t f'

l I

( . ..

l -'l 4 G_ _

. ATTACHMENT - 1 PAGE 3 0F 3 RWS-0204 'REV. O PAGE 11 0F 11.

Ii Ii ll .

.