ML20008F613
| ML20008F613 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 03/19/1981 |
| From: | Mckee P FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20008F609 | List: |
| References | |
| WP-100, NUDOCS 8104210377 | |
| Download: ML20008F613 (40) | |
Text
.-
e Rav. O 3/19/81 c
l Document section NFORM ATION ONLY C. R. Nucksst CHEMISTRY AND RADIATION PROTECTION PROCEDURE WP-100 FLORID \\ POWER CORPORATION CRYSTAL RIVER UNIT 3 RADIOACTIVE WASTE SOLIDIFICATION REVIEWED BY: Plant Review Co: mittee f, ?' ff/$ L%.'
Y Date 3/19/81 Meeting No.
81-11 APPROVED BY: Nuclear P1.
Mar ger A
- 810.421o3 M
9 l.0 PURPOSE AND SCOPE l
This document satisfies the NRC requirement as stated in 1.1 NUREC-0133, paragraph 3.5.
1.2 This Process Control Program (PCP) provides a guideline for insuring that all activities related to the solidification of radweste are regulated and directed toward a satisfactory result. A satisfactory result means the " complete solidifica-tion of processed wastes... with the absence of free water in the processed wastes..."
n
2.0 DESCRIPTION
2.1 The PCP is not intended to be used as an operating or waste procedure. It should be considered as a method to manage the solidification process by giving an overall view of the inter-facing procedures, equipment, and boundary conditions.
l
3.0 REFERENCES
l 3.1 American National Standard N45.2-19H, " Quality Assurance Program Requirements for Nuclear Power Plants" American National S. andard N18.7-1976, " Administrative Controls 3.2 and Quality Assurance for the Operational Phase of Nuclear l
Power Plants" l
)
3.3 Code of Federal Regulations, Title 49 l
3.4 NUREC-0133, " Preparation of Radiological Effluent Technical i
Specifications for Nuclear Power Plants" l
l l.
Page 1 WP-100 Date 3/19/81 Rev. 0
-w.
--,n,,-,e.
-,--. --,-,~... -..
n.
w..,-
a
,m.,.,,.-,-
..n
I 9
3.5 NUREG-0472, " Radiological Ef fluent Technical Specifiestions for PWR's" 3.C ANSI N199, " Liquid Radioactive Waste Processing Systems for Pressurized Water Reactor Plants" 3.7 CNS1, SD-OP-002, Process Control Program for Ursa Formaldehyde 3.8 CNSI, SD-OP-002, Process Control Program for Cement Solidifica-tion Units
- 3. 9 FPC Drawing #FD-302-681 3.10 FPC Drawing #FD-302-682 3.11 WP-101, Packaging, Storing, and Shipping of Radioactive Wastes 3.12 OP-413, Waste Drumming System 4.0 LIMITATIONS AND SPECIAL CONDITIONS 4.1 This section sets forth the required analyses for determining i
the solidification steps on the two types of wastes: evapo-rator bottoms and ion exchange resins. Waste analyses should be made on homogeneous mixtures.
4.1.1 All radf oactive vastes should be surveyed for dose rate prior to transfer to the solidification vessel. This radiation sur-vey la rer.. sired so that one can make proper decisions concern-ing ALARA, the type of 1in=r and cask needed, and contamination safeguards. A sample of a homogeneor.s mixture of the waste should be taken and analyzed for isotopes and curie content.
4.1.2 Chemistry analyses are necessary for successful solidification since the process can be dependent on certain ione, pH, and oil.
(
Page 2 WP-100 Date 3/19/81 Rev. 0
9 4.1.2.1 Waste samples should be collected and analyzed by batch or
('
tankful, whichever is the larger homogeneous mixture.
4.1.2.2 Urea formaldehyde (UF) solidification of wastes should be analyzed for the folicwing parameters:
Parameter Lower Limit Upper Limit
- 1. pH 3 (b)
- 2. oil less than (e) 1.0% by volume
~
(visual check)
- 3. Sulfate (a) less than 15%
by weight (c)
- 4. Boron no specifications waste bubble with
- 5. Carbonate slight acid addition (d)
The sulfate analysis will only be performed when the NOTE:
a.
s waste stream is known to contain sulfates due to resin regeneration, etc.
b.
If the pH is 3 or less, then NaOH must be added to raise the pH within limits.
3 of waste) (2.8x10-3)
NaOH (grams) = (ppm boron) (ft If the sulfate ion is determined to be more than 15%
c.
by weight, then the excess should be precipitated using BaC1.
2 3
LBS BaC12 = (6.6x10-4)(waste volume, ft )(PPM SO ")
4 d.
If carbonate is present, then add an anti-foaming agent to the liner before the addition of waste in the following quantities:
f Page 3 WP-100 Date 3/19/81 Rev. O s
l - - -
e 4
Liner Quantity
(
3 04 3 gals.
303 2.5 gals.
306 2 gals.
310 2 gals.
If oil exists in quantities greater than 1%, then e.
the amount of oil present should be reduced to 1% or less by skimming or using a demulsification agent.
4.1.2.3 Cement solidification of vastes requires the consideration of the parameters listed in Enclosure 3.
4.1.3 Required Sampling Frequency 4.1.3.1 The frequency of waste sampling and analysis is determined by I
the largest homogeneous mixture available to sample.
If the constituents of a previously analyzed volume are a.
changed by the addition of a different material, then the new volume must be resampled and analyzed as stated in See-tion 4.1.1, under the particular type of solidification to be used.
1
(
b.
Chemistry analyses are not required on each new volume provided the analysis rencins representative of a vaste l
batch.
c.
Tacks should be recirculated so that a representative sample can be obtained and maintained on recirculation until solidification of the contents is complete.
l i
Page 4 WP-100 Dste 3/19/81 Rev. 0
.~.
s a
4.1. 4 Analysis of Solidification Media a
4.1.4.1
'JF Solidification:
UF will be sampled at the time of reception and each 30 a.
days thereaf ter for pH and color. UF should not be used unless the pH is between 5.5 and 8.0, and the color is milky white.
4.1.4.2 The cata'yst for the UF will be analyzed for clarity and specific gravity.
H SO4 - clear with specific gravity = 1.20 to 1.24 NOTE:
2 4.2 The ratio of solidification media to waste is listed in the I
following table:
l Binder / Media Waste Type Waste: Media UF all CR-3 wastes approx. 2:1 Cement evaporator bottoms approx. 1:1 Cement ion exchange resins approx. 1.5:1 4.3 A test solidification should be made before attempting to solidify a vaste stream.
4.3.1 UF - Test Solidification 4.3.1.1 The minimum sampling requirement for test solidification is every tenth batch of each type of wet radioactive waste (filter sludges, spent resins, evrporator concentrates, boric acid solutions, sodium sulfate solutions, and filter media). If any test specimen fails to solidify, the batch in the disposable liner shall not be solidified until a new test specimen can be obtained, alternative solidifiestion parameters determined, and l
l Page 5 WP-100 Date 3/19/81 Rev. 0
t o
a subsequent test verifies solidification. Solidification of
(
the batch may then be resumed using the alternative solidifica-tion parameters.
4.3.1.2 If the first test specimen from a batch of waste faila to veri-fy solidification, a sample will be collected and analyzed in accordance with the PCP for each c:nsecutive batch of the same type of wet waste until three (3) consecutive test spe,cimens verify solidification. At this point normal sampling require-ments may resume.
4.3.1.3 If the waste being received is fran a storage tank, and if waste is added to the tank, a new test shall be conducted to assure the new characteristics do not alter the solidification parameters.
4.3.2 Cement Solidification i
Test solidifications as outlined in Enclosure 3.
PROCEDURE i
l 5.0 FPC SYSTEM DESCRIPTION AND ALLIED PROCESSING STEPS 5.1 The primary resin transferring system for solidification is controlled by OP-413. Waste Drumming System. This Operating l
Procedure gives the valve and pump lineups in its procedural guidelines. Section 5.1 of this procedure gives an overview of the flow path for resin transfer from the spent resin tank to the shipping container and the return path of the decant water.
l
.(
Page 6 WP-100 Date 3/19/81 Rev. 0
t
(
l 5.1.1 The resin is homogeneously mixed in the spent resin tank (7,000 ll' gal. capacity) using the slurry pump, WDP-11,, WW-72, and check valve WW-336. Domineralized water can be added through WW-837 to the suction side of the pump to insure that the proper water: resin mixture is obtained.
5.1. 2 Resin transfer to the solidification apparatus is made from the l
i spent resin tank through WW-104, WDP-11, WDV-124, WW-319, and WDV-662. Again, desineralized water can be added to the resin t
through WW-837 to insure a proper slurry.
5.1.3 Water is decanted before solidification and returned to the l
l spent resin tank through WW-663 and WW-261.
5.1.4 At the conclusion of each resin transfer. the piping forward of i
WDV-104 aust be flushed using WDV-837.
. 5.1. 5 Established two-way communication between Operators a; the
(
vaste panel and Operators at the solidification site. is re-quired during resin transfer.
- 5. 2 FPC procedural guidelines concerning the transfer of liquid waste f or solidification are given in OP-413, Waste Drumming l
System. Section 5.2 of this procedure gives an overview of the
~ flow patha of liquid wastes from the various tanks to the l
l solidification apparatus. Liquid wastes ein be stored in two concentrated boric acid storage tanks (OBAST - 7,000 gal.
capacity each) and in two concentrated waste storage tanks (CWST - 7,000 gal. capacity each.) The CWST's are to be utilized as concentrated miscellaneous waste storage tanks (C5'ST's) whenever possible.
Page 7 WP-100 Date 3/19/81 Rev. 0
q
- 5. 2.1 Waste from CWST-3A (WDI-7A) follows the path described in Step
(
5.2.1.1.
I 5.2.1.1 CWST-3A is to be recirculated to insure a homogeneous mixture for sampling and analysis through WDV-212, WDV-213, WDP-12A, I
WDV-235, WDV-217, and WDV-295, or any appropriate recirculation path for at least two tank volumes.
5.2.1.2 Waste liquid is transferred to the solidification apparatus f rom CWST-3A (WDI-7A) via WDV-212, WDV-213, WDP-2A, WDV-235, WDV-219, WDV-658, WDV-660, and WDV-661.
5.2.1.3 Waste lines are flushed to the solidification apparatus using demineralized water via DWV-133, WDV-210, WDV-217, WDV-219, WDV-658, WDV-660, and WDV-661.
5.2.1.4 Should pump WDP-12A fail, waste can be transferred using pump WDP-12B and valves WDV-216, WDV-236, WDV-220, WDV-658, WDV-660,
(
and WDV-661.
5.2.2 Waste from CWST-3BB (WDI-7B) follows the path described herein:
5.2.2.1 CWST-35 is recirculated to insure a homogeneous mixture for sampling and analysis through WDV-215, WDV-216, pump 3B (WDP-f 12B), WDV-236, WDV-218, and WDV-296, or any appropriate recir-culation path for at least two tank volumes.
5.2.2.2 Waste liquid is transferred to the solidification apparatus f rom CWST-3B via WDV-215, WDV-216, WDP-123, WDV-236, WDV-220, i
WDV-658, WDV-660, and WrV-661.
5.2.2.3 Waste lines are flushed to the solidification apparatus with demineralized water using DWV-133, WDV-221, WDV-218, WDV-220, WDV-658, WDV-660, and WDV-661.
.(
. P-100 Dste 3/19/81 Rev. 0 Page 8 W
,v-7 m
- 5. 2. 2. 4 Should pump WDP-12B fail, waste can be transferred using pump
\\
WDP-12A via WDV-215, WDV-214 WDV-213, WDP-11A, WDV-235, WDV-219. WDV-658, WDV-650, and WDV-661.
5.2.3 Waste from CBAST-3A (WUI-8A) follows the path described herein:
5.2.3.1 CBAST-3A is recirculated to insure a homogeneous mixture for sampling and analysis via WDV-142, WDV-145, WDF-13A, WD7-237, WDV-147, and WDV-140, or cny appropriate recirculation path for at least two tank volumes.
5.2.3.2 Waste liquid is transferred to the solidification apparatus from CBAST-3A via WDV-142, WDV-145, WIP-13A, WDV-237, WDV-149, WDV-658, WDV-660, and WDV-561.
g 5.2.3.3 Waste lines are flushed to the solidification apparatus using WDV-138 WDV-147 WDV-149, WDV-658, WDV-660, and WDV-661.
5.2.3.4 Should pump WDP-13A fail, waste can be transferred using pump i
WDP-13B via WDV-142, WDV-144, WDV-146, WDP-13B, WDV-238, WDV-151, WLV-658, WDV-660, and WDV-611.
5.2.4 Waste from CBAST-3B (WUI-8E) follows the path described herein:
5.2.4.1 CBAST-3B is recirculated to insure a homogeneous mixture f or sampling and analysis via WDV-143, WDV-146, WDP-13B, WDV-238, WDV-150, and WDV-141, or any appropriate recirculation path for at least two tank volumes.
1 5.2.4.2 Waste liquid is transferred to the solidification apparatus from CBAST-3B via WDV-143, WDV-146, WDP-13B, WDV-238, WDV-151, l
WDV-658, WDV-660, and WDV-661.
l 5.2.4.3 Waste lines are flushed to the solidification apparatus with l
l desineralized water using WDV-139, WDV-150, WDV-151, WDV-6 58, l
l WDV-660, and WDV-661.
l l
Page 9 WP-100 Date 3/19/81 Rev. O
,$(4%l? s$1tqff*
0
/9 d%
/'
k pg,\\\\\\ev;'f4Q
%\\\\/j//
%f////
g y
NV's#g, 4 d" W
4 im e ev tu 1ios TEST TARGET (MT-3) l.0 lf m Ei y ll;,3 Il!E I.l
[ "3 liiiil 1.8 1.25 1.4 11 1.6 11 e
6" d,f,[f,%
[.$(g
'4 [' $
,s t
0
///j'
/
TEST TARGET (MT-3) l.0
!!!m na e a bn22 b tu
=
l,l
4 6"
y w I>p, d
ez
- a,:#
f4*
- >s
<&p%y v'o r
t
- 5. 2. 4. 4 Should pump WDP-13B fail, waste can be transferred using pump t
WDP-13A via WW-143, WW-144, WW-145, WDP-13A, WW-237, WDV-149, WDV-658, WD7-660, and WW-661.
5.3 The FPC requirement for core sectioning piping la the waste receptacle is described in OP-413, Wasta Drumming System.
5.4 The FPC requirement for secondary dewatering of the solidified liner is described in OP-413, Waste Drumming System.
5.5 The FPC requirement for a Quality Control (QC) check of the devatared solid is described in OP-413, Waste Drumming System.
5.6 The FPC procedure for receiving transport vehicles and shipping radwaste is fully covered in WP-101, Packaging, Storing, and Shipping of Radioactive Wastes, including the necessary forms f
to be completed, QC checka, and required Health Physics sur-I veys.
l 6.0 CNSI UREA FORMALDEHYDE SOLIDIFICATION SYSTEM DESCRIPTION AND ALLIED PROCESSING STEPS AS USED IN CR-3 Section 6.0 gives an overview of the pathway of the vaste l
liquid af ter leaving the plant piping and its solidification with UF.
I 1
6.1 UF SOLIDIFICATION SYSTEM, CNSI PROCEDURAL DESCRIPTION OF THE SYSTEM Chem-Nuclear Systems, Inc.'s (CNSI) Solidification Systems a.
l 7 thru 13 utilize UF to convert all types of wet radioac-tive waste (filter sludges, spent resin, evaporator bot-toms, boric acid solutions, and sodium sulfate solutions) into a solid matrix.
. (
Page 10 WP-100 Date 3/19/81 Rev. O v-nv--
e
+r-p,-me-
-,v---g
+-omw-n"
-,,,g,,-
~
-w,e ry----p-,,
,.,4
.weww-:ye wr.mrrm
,e-ww-,-p, oww wmg,,g,.
y+wg,---n,,-,,g-mae-n,,,---
-w.nw-mvwm-e*~---.-
l o
b.
Sulfuric acid is added to a homogeneous mixture of wet 5
radioactive vaste and urea formaldehyde until solidifica-tion occurs.
c.
These solidification systems consist of the following sub-systems waste transfer, dewater, catalyst addition, air sparging, and off gas vent system. The unit also contains a pneumatic control panel and an electrical control con-sole.
6.1.1 Waste Transfer Systen 6.1.1.1 The purpose of the waste transfer system is to transfer radio-l active waste from the utility to a disposable container for processing and ultimately shipping for disposal.
6.1.1.2 The major components of the vaste transfer are a 2-in. Teflon-1 lined hose with an outer stainless steel braiding, manually-operated sample valves, and full head isolation valve, and an air-operated ball valve.
6.1.1. 3 Valve WS-1 (plant isolation valve) is an air-operated ball valve which will automatically shut on both a high level in the disposable liner and an improperly positioned fill head on a disposable liner. Valve WS-1 can be locally controlled from l
j the electrical control console or remotely controlled from a remote pendant. A switch on the electrical control console is used for selecting local or remote control.
i 6.1.1. 4 Valves US-3 and WS-4 (waste sample valves) and valve WS-2 (vaste container isolation valve) are manually sperated hall valves.
(
Page 11 WP-100 Date 3/19/81 Rev. 0
.. - - ~.-
6.1.1. 5 A portable radiation detection probe is attached to valve WS-1 (plant isolation valve).
~he probe has a meter readout (mR/hr) located on the electrical control console and a red radiation alarm light located on the remote control pendant for valve WS-1.
The red radiation alarm light is energized by the meter when radiation levels reach a preset limit.
6.1.1. 6 All hoses, valves, and fittings in the waste transfer path must pass a hydro-check at a minimum of plant service water pres-sure.
6.1.2 Dewater System 6.1. 2.1 The purpose of the devatering system is to remove slurry water, which acts as a transportation medium, from both resin and sludge. By dewatering resin and sludges, the CNSI Solidifi-cation System performs a volume reduction function.
i 6.1. 2. 2 The major components of the dewatering system are:
An air-driven, diaphragm-operated, positive-displacement a.
pump. The air supply to the pump is fed off the main air inlet to the unit. The air passes through a filter, lubri-cator, and a three-way valve (SA-1). The three-way valve selects either the dewater pump or the urea formaldehyde transfer pump. The purpose of the devatering pump is to remove the slurry liquid and transfer it back to the utility where it can either be further processed or released.
b.
Pressure gauges are located on both the suction and dis-charge of the dewatering pu=p-These gauges are used to i
l
(
Page 12 WP-100 Date 3/19/81 Rev. O
determine whether or not the dewatering pump is functioning a(
properly. The suction gauge is a dual purpose gauge (pres-sure and vacuum) and is utilized to determine the status of the liner. (If suction gauge indicates vacuum, the liner will be dry.)
The suction hose for the dewatering pump is a 1-1/2 in.,
c.
reinforced, non-collapsible rubber hose. The discharge hose is a 1-1/2 in., Teflon-lined hose with an outer stain-less steel braiding for inner pressure protection.
d.
Both sample and flush connections are available for the dewater system.
The pump suctica line is equipped with a 1-1/2 it. Y-type e.
strainer.
f.
All valves in the dewater system are manually-operated ball
\\
valves.
6.1.3 Urea Formaldehyde Transfer System 6.1.3.1 The purpose of the UT transfer system is to store the UF until needed and then transfer the UF to a disposable liner so it can I
be utilized in solidification.
j 6.1.3.2 The major components of the UF transfer system are:
1 A UF storage container, which is usually a spare disposable a.
liner equipped with a PVC (polyvinyl chloride) standpipe.
b.
An air-driven, diaphragm-operated, positive-displacement l
The air supply line to the pump contains both a fil-I pump.
ter and lubricator. Air passes through a three-way selec-l Page 13 WP-100 Date 3/19/81 Rev. 0
tor valve to either the UF transfer pump or the dewatering
(
PueP-The pamp is equipped with suction and discharge pressure c.
gauges and sample and flush connections.
6.1.4 Catalyst Addition Systen 6.1.4.1 The function of the catalyst addition system is to transfer the catalyst from the shipping container to the disposable liner for solidification.
6.1. 4. 2 The major components of the catalyst addition system are the catalyst transfer pump and the discharge regulating valve. The catalyst transfer pump is a centrifugal, constant-speed pump equipped with a special liner and impeller to protect the pump from acid corrosion. The discharge regulating valve maintains t
a predetermined acid flow rate to the disposable liner.
6.1.4.3 In the catalyst addition mode, the catalyst is added to the disposable liner via the air sparging header, which gives ideal mixing conditions. In the catalyst addition mode, valve C-3 is open.
6.1.5 Air SparEing System 6.1.5.1 The function of the air sparging system is to mix the catalyst, UF, and radioactive waste. The mixing is performed by bubbling air through the mixture to obtain a homogeneous mix.
6.1. 5. 2 The major components of the air sparge system are the air sparge header which is placed inside the disposable liter, the control regulator, and gauge located at the pneumatic control panel.
l l
(
Page 14 WP-100 Date 3/19/81 Rev. 0
6.1. 6 off-Gas vent System k
The purpose of the off gas vent system is to create a slight 6.1.6.1 vacuum at the top of the liner to draw off radioactive airborne contamination and discharge it to the utility off-gas system.
6.1. 6. 2 The off gas vent system is in operation during waste transfer, resin transfer, and UF addition.
6.1. 6. 3 The major components of the off-gas vent system are the blower, which is used to take a suction on the liner; a 1-1/2 in. spi-roflex hose; and a vacuum breaker which will open at 1 psig to prevent the blower hose from collapsing.
6.1.6.4 The blower is normally mounted on the stand with valve US-1 and the sample valves.
6.1.7 Pneumatic Control Panel 6.1.7.1 The purpose of the pneumatic control panel is to line up sud
('
deliver pressurized air at 100 + 20 psig for the following functions:
a.
Sparge Air b.
Fill Head Cooling c.
Camera Air d.
Plant Waste Connections e.
UF and Dewater Pump Control
^
6.1.7.2 All the above functions are equipped with a pressure regulator and a pressure gauge, except fill head cooling air and camera air.
(
Page 15 WP-100 Date 3/19/81 Rev. 0 5
-e-
--n.,
l 6.1. 7. 3 The driving air supply for both the dewatering and UF pumps
(
come off the main air line prior to passing through the pneu-matic control panel.
6.1.7.4 The pneumatic control panel is also equipped with an air dryer for removing moisture from the supply air.
6.1.8 Electrical Control Console 6.1. 8.1 The purpose of the electrical control console is to provide power and indication for the following components:
Pump and Valve Indication and Operation a.
b.
Level Indication c.
Radiation Level Readout d.
Remote Viewing Camera e.
Catalyst Pump Control f.
Off-Gas Vent Blower Control
(~
6.1.8.2 Pump and Valve Indication and Operation:
6.1.8.2.1 Valve indication is supplied for valve WS-1 (plant isolation) at the electrical control console. The valve can be operated l
in either local or remote control. In remote control, the i
valve is opened and closed by a pendant cord attached to the control panel.
In local control, valve WS-1 is operated by pushbuttons on the control panel. For the valve to be operated locally, the " Location" switch on the electrical control con-sole must be in the
- Local" position.
6.1.8.2.2 An interlock is installed on the filling head to prevent WS-1 from being opened unless the fill head is positioned correctly l
l
(
I 1
l Page 16 WP-100 Date 3/19/81 Rev. 0 l' -
on the barrel top liner. This is accomplished by a "Proxisity"
(
switch located in the bottom of the fill head. This interlock is to prevent the Operator from opening valve 1G-1 and creating a potential uncontrolled release by not having the fillirig head positioned properly.
6.1.8.2.3 An interlock is installed oc the filling head to shut valve WS-1 on high pressure in the disposable liner. This is accom-plished by a pressure switch located in the suction header of the off-gas blower.
4 6.1.8.2.4 Valve WS-1 will shut automatically on a high-high level condi-tion in the disposable liner.
6.1.8.2.5 A red indicating light is on the electrical control console to indicate valve WS-1 is open and a green light shows when WS-1 is shut.
6.1.8.2.6 There is a 30 see. time delay built into the automatic closing l
device for WS-1 to allow the Operator to prevent prenature closing of valve WS-1.
WS-1 vill shut automatically on a high-high level condition in the disposable liner.
6.1.8.3 14 vel Indication:
6.1.8.3.1 Four different level positions are supplieJ: the devater level which is yellow, vaste level which is black, LT level which is l
i white, and high level which is red. The level probes conneet to the filling head by means of disposable, dual, banana jacks which are color coded for each level set point. The level probes will be placed at the set points deter =ined by the specific PCP.
(
l Page 17 WP-100 Date 3/19/81 Rev. 0 t
6.1.8.3.2 "he level inside the disposable liner is indicated on the elec-(
trical control console by a series of level indicatora. A level indicator exists for each probe when it is in the
" Sludge" position. A white indicator shows when the correct level has been obtained.
6.1.8.3.3 Visual level references are attached to the sparge tube as a backup to prevent overfilling should the electrical indicators fail.
6.1. 8. 4 Re=ote radiation level indication is available at the electri-cal control console. The radiation detector monitors the waste passing through the vaste transfer hose or may be positioned at any desired location.
6.1.8.5 The electrical control console contains a remote television moni-tor for viewing the contents of the disposable liner.
s 6.1.8.6 The acid pump and vent blower controls are identical in design and operation. They consist of an "Off-On" switch and a red i
indication light to show when the equipment is energized. They l
are aquipped with overload circuits.
6.1. 9 Fill Head Assembly 6.1. 9.1 The fill head assembly is mounted atop the disposable line and directs the flow of waste, estalyst, UF, and air to the liner.
6.1.9.2 The fill head is equipped with an adjustable high level switch which will shut valve US-1 on a high level. The high level switch is a float-type switch.
6.1. 9. 3 A camera is mounted in the fill head and directed into the dis-posable liner.
f Page 18 WP-100 Dste 3/19/81 Rev. O
o 1
6.2 REQUIRFE.NTS t
6.2.1 Prerecuisites 6.2.1.1 The CNSI Solidification Systems require the following support services from FPC:
a.
Electrical Power 1.
For skid-sounted units,120 volts; 10 amps.
2.
For all trailer-mounted units, 480 volts; 70 amps.
b.
Service Air; 25 SCFM at 100 + 20 psi c.
Service Water 6.2.1.2 Af ter the above services are connected to the solidification system, the CNSI Operi. tor will control the portion of services which are supporting the solidification system.
6.2.2 Precautions 6.2.2.1 Any changes to equipcent or Operating Procedures shall be per-formed in accordance with CNSI's prescribed Quality Assurance (QA) procedures and will have been approved by the CNSI QA Department prior to instituting any change. This applies to all related drawings, procedures, and equipment. These changes must also be reviewed by CR-3 Nuclear Quality Assurance / Quality Con-trol (NQA/QC) and the Plant Review Committee (PRC).
6.2.2.2 At all times the representative of CNSI shall follow the proper radiological precautions to minimize the spread of conta=ination and to limit personal exposure to ionizing radiation.
6.2.2.3 When performing a devatering operation, the air sparging systen shall be in operation. This is to prevent the resin fron set-(
Page 19 WP-100 Date 3/19/81 Rev. 0
. =_ _ - - __-. - - - _ _. -,
l tling out and forming a semi-solid mass which would prevent ade-
\\
quate dewatering.
1 6.2.2.4 During all processing evolutions, the solidification system Oper-ator shall wear the dosimetry assigned by the Health Physics Department.
6.2.2.5 During all operations of the solidification system, the CNSI l
l Operator shall wear the proper clothing as outlined by Radiation Protection Procedures.
.i 6.2.2.6 Prior to receiving waste, visually check all hoses for signs of wear.
6.2.2.7 Cask or disposal liners should be shipped as soon as possible af ter solidification to reduce radiation levels in the area of the solidification system.
6.2.2.8 Area monitoring should be performed by the CNSI Operator daily.
t Monitoring results should be recorded on CNSI Fora 202.
s 6.3 OPERATING PROCEDURE 6.3.1 Initial Cpaditions 6.3.1.1 Obtain a Radiation Work Permit (RWP) from the Health Physics l
Department.
Establish a controlled area in the vicinity of the solidification 6.3.1.2 unit.
i STEPS 6.3.1.3 THROUGi 6.3.1.14 MAY E PERFORMED IN ANY NOTE:
SEQUENCE.
Monitor the area to be utilized for operation of the solidifica-6.3.1.3 i
tion unit for surface contamination and radiation levels.
Page 20 WP-100 Date 3/19/81 Rev. 0
6.3.1.4 Position the solidification unit, polymer storage tank, and dis-(
posable liner in their assigned positions.
6.3.1.5 Establish the following services on the solidification unit:
a.
Electric Power b.
Service Air at 25 SCFM; 100 + 20 psi c.
Service Weter 6.3.1.6 Verify that the required amounts of polymer, sulfurie acid, caseaaite, disposable liners, and lids are availabic.
6.3.1.7 Establish the following connections:
a.
Pil to J11 b.
P6 to J6 c.
P13 to J13 d.
P4 to J4 e.
P7 to J7
?
f.
F10 to J10 g.
PS to J8 h.
P9 to J9 1.
PS to J5 l
- j. P12 to a trailer receptacle (applies only to trailer-mounted i
units)
I 6.3.1.8 Connect the polymer transfer line between the polymer storage tank and the suction side of the polymer transfer pump.
6.3.1.9 With the installed erane, lif t the filling head fron its storage tray and place into position for connection of the following ser-vices. (For units that are not trailer-mounted, the erane vill be needed to lif t the fillin;; head.)
l l
4 Page 21 WP-100 Date 3/19/81 Rev. 0 w,
m
.+---,m
-.y-w w
l a.
EF Transfer Hose b.
Waste Transfer Hose e.
Dewater Suetion Hose d.
Blower Suetion Hose e.
Catalyst Transfer Hose f.
J2 to P2 g.
J3 to P3 h.
J1 to P1 1.
J15 to P15 6.3.1.10 If necessary, resove valve ~45-1 frae the plant connection stand.
6.3.1.11 Following proper radiological precautions, remove any blank fla=ges from both valve WS-1 and the unit's radvaste connection.
6.3.1.12 Attach valve WS-1 and the sample spool piece to the mit's rad-vaste connection. Torque all bolts to a lubricated value of 70 ft-lbs.
NOTE:
Ar.r.A EACH USE, THE FIZIITALLIC GASKETS INSTAI.I.ED BE'4EEN VALVE WS-1 AND THE ENIT'S RA3 TASTE CONNECTION SHOC:.D BE REPLACED.
6.3.1.13 Following proper radiological precautions, connect radwaste ec=-
nection bose to the sa=ple side of valve WS-1 and to valve WS-2 on the fill head assembly. Torque all bolts to a lubricated value of 70 f t-lbs.
NOTE: IEE FLEXITALLIC GASKI S INSTAILED EE'"4ET.N WS-2 AND THE WASTE TRANSFER HOSE AND Tr~.r. SAXP'.I SIZ '45-1 AND THE TRANSFEP HOSE SHOC.D BE REPLACED AFTER EACH USE.
I Page 22 WP-100 Date 3/19/81 Rev. 0 4
i l
6.3.1.14 Connect the polymer transfer line between LT pump discharge t
valve, UF-1, and UF liner isolation valve, LT-7.
6.3.2 System Pre-Operational Cheeks 6.3.2.1 Remove the secondary lid from the cask.
CAUTION: DO NOT USE THE INSTALLED CRANE FOR REMOVING THE SECONDARY LID.
6.3.2.2 Remove barrel top from disposable liner and ir.spect for foreign material and damage.
CAUTION: INTERNAL PRESSURE COULD BUILD UP INSIDE THE DISPOSABIE LINER. REMOVE BARREL TOP WITH CARE.
6.3.2.3 Place the air sparge header assembly inside the disposable liner and adjust the level leads to the set points defined by the initial test specimen or the current test specimen.
6.3.2.4 Position the solP.ification fillirs head over the disposable
.. the sparging liner opening. Imave enough clearance so that header and level leads can be installed in their connections on the filling head assembly.
6.3.2.5 Following proper radiological precautions, insert the air sparging header into the connection on the filling head assembly.
6.3.2.6 Following proper radiological precautiens, insert the level leads into the lead connection points as follows:
I a.
Yellow - Dewater b.
Black - Waste c.
White - UF f
Page 23 WP-100 Date 3/19/81 Rev. 0
~
i 6.3.2.7 Place the contrel power switch on the control console in the "On" position.
6.3.2.8 Position the filling head on the disposable liner. Verify proper position by checking that the filling head position light on the electrical control console is energized.
6.3.2.9 Actuate main air selector switch on the control console and check available air pressure. Air pressure should be 100 + 20 psig.
6.3.2.10 Check for proper operation of valve WS-1 by taking it from fully open to the fully shut position from the control console and locally at the valve station.
g 6.3.2.11 Energize TV camera, TV monitor, and container light.
i 6.3.2.12 Check for proper operation of alarms and alarm lights at the control panel.
(
6.3.2.13 Obtain from the radwaste system Operator the approximate amount of vaste to be transferred.
6.3.2.14 Perform the following valve lineup:
1.
Shut or check shut valves WS-1, WS-3, US-4, CT-5, DW-2, DW-5, UF-2, UF-5, CI-2, and DW-7.
2.
Open or check opea valves WS-2, UF-7, CT-3, DW-1, DW-6, UF-6, and UF-1.
3.
Check the metering position of valve CT-1.
(Valve CT-1 should be set to allow a transfer rate of 1 to 2 gpm. A transfer rate of 1 to 2 gpm corresponds to a valve setting l
i Page 24 WP-100 Date 3/19/81 Rev. O i
l
of 2.5 to fully open.) If valve CT-1 is not in proper position, adjust valve CT-1 to the proper position.
4.
Place valve SA-1 in the "UF kump" position.
f-3.2.15 The Operator shall check for leaks all hose connections under a pressurized condition. Document in the daily log.
6.3.2.16 Open valve WS-1 from the electrical control console and start the off gas vent blower. Inform the radioactive waste system operator that the solidification system is ready to receive vastt.
6.3.3 Radioactive Liquid Waste Transfer and Disposable Liner Filling l
6.3.3.1 Prior to receiving radioactive vaste, verify all initial condi-tions and system pre-operational checks are complete. Document in daily log.
l 6.3.3.2 Verify that the transfer of radioactive vaste has begun by 1
viewing the TV nonitor and inform the radioactive waste system operator that you are receiving waste.
6.3.3.3 Record the waste line fixed monitor radiation readings on an hourly basis in the daily operations log.
6.3.3.4 When the waste reaches the waste level set point, shut valve WS-1 and inform the radwaste system operator to secure waste transfer.
6.3.3.5 When the vaste transferring operation is complete, inform the radioactive vaste system operator to perform the necessary l
valve lineup to flush the waste transfer header.
6.3.3.6 When the radioactive waste system operator reports that he is ready to flush, open valve WS-1.
l f
I-l Page 25 WP-100 Date 3/19/81 Rev. O
6.3.3.7 Continuously monitor liner level during flushing operations.
t 6.3.3.8 Monitor the waste transfer header for radiation levels. If adequate flushing has takan place, the radiation levels on the waste transfer header should approximate background. If radia-tion levels are significantly greater than background, further flushing is required.
6.3.3.9 Af ter adequate flushing has takan place, shut valve US-1.
6.3.3.10 Obtain concurrence on the volume of waste received.
6.3.3.11 Actuate the air sparge selector switch on the pneumatic control console and increase pressure by adjusting the reg ilating valve until a gentle rolling motion is noticed on the surfaep of the liquid by viewing the remote monitor.
6.3.3.12 Start UF trarzfer pu=p by increasing speed regulator pressure to 40 + 10 psi.
8-6.3.3.13 Honitor the disposable liner for UF flow and continue adding UF until the proper polymer-to-waste sixture, as defined by the l
initial test specimen or the most current test specinen, has l
been achieved.
6.'3.3.14 Continue sparging for a total sparging time of at least I hr.
and at least 15 min. of sparging af ter all UF has been added.
This insures go1J. mixing of the polymer and weste.
6.3.3.15 Af ter sparging fc the necessary time, commence catalyst addi-tion using the following procedure:
a.
Start the catalyst transfer pump and add catalyst until a noticeable increase in the mixture's viscosity is visible in the re=ote monitor.
g
?
Page 26 WP-100 Dste 3/19/81 Rev. 0
b.
Verify that solidification has occurred and the rolling
(,
motion of the liquid has stopped by viewing the remote monitor.
c.
Secure the air sparge system.
d.
Secure the catalyst transfer pump and open valve CT-2 to drain any residual catalyst from the catalyst line.
Af ter all residual catalyst has been returned to the e.
storage container, shut valve CT-2.
6.3.3.16 Allow the solidified matrix to stand for at least 2 hrs., then perform the following steps to insure all free liquid is removed:
Commence the air sparge at 40 psig for 5 min., then secure a.
air sparge.
b.
Shut or check shut valve CT-3 and DW-7.
c.
Open or check open valves DW-1, DW-6, and CT-5.
d.
Place valve SA-1 in the "Dewater Pump" position.
Start the devatering pump.
e.
1.
Place the pump air switch in the "On" position.
2.
With the speed control regulator, increase pump regula-tor to 40 f; 20 psig.
f.
When liquid is no longer evident on the suction of the i'
dewatering ptmp for fif teen consecutive minutes, secure the dewatering pump.
g.
Shut or check shut the following valves:
l r
CT-3, CT-5, DW-7, DW-6, and DW-1 l
(
I Page 27 WP-100 Date 3/19/81 Rev. 0
---er-w-e
~ " " * ' ' ' " "
- 6.3.3.17 Secure the main air switch and the off gas vent blower.
6.3.3.18 Secure TV camera and monitor.
6.3.3.19 Following proper radiological precautions, raise the filling head off the disposable liner and place in its storage loca-tion.
6.3.3.20 Check the quality of the matrix.
a.
Perform a visual inspection.
b.
Perform a hardness examination by probing the solidified product with a rigid device.
c.
Record the condition of the matrix in the daily operations log.
6.3.3.21 As necessary, add cascamite or a similar product to the top of the ma.rix.
6.3.3.22 Install the lid on the disposable liner.
t 6.3.4 Resins, Sludges, and Miscellaneous Media 6.3.4.1 Perform Steps 6.3 thru 6.3.2.3.
6.3.4.2 Place dewatering header inside the disposable liner.
6.3.4.3 Position the solidification filling head over the disposable l
liner opening. Leave enough clearance so the sparging header, dewatering header, and level leads can be adapted to their fill head connections.
6.3.4.4 Perform Steps 6.3.2.7 thru 6.3.2.13 6.3.4.5 Place valve SA-1 in the 'Dewater" position.
6.3.4.6 Open valve WS-1 from the electrical control console (the remote pendant may be used for opening and ahtitting valve WS-1) and
(
Page 28 WP-100 Date 3/19/81 Rev. C
start the off gas vent blower. Inform the radioactive waste system Operator that the solidification system is ready to receive vaste.
6.3.4.7 Actuate the air sparge selector switch on the pneumatic control panel and increase pressure by adjusting the regulating valve until a gentle rolling motion is noticed on the surface of the slurry by viewing the remote TV nonitor.
- 6. 3. 4.8 When waste reaches the dewatering set point (2 ft. frce the bottom of the liner), start the devatering pu=p from the con-trcl console.
1.
Check valve SA-1 in the fDewater" position.
2.
Adjust regulator pressure to 40 + 10 psi.
NOTE: ;E REQUIREMENT FOR SOLIDIFYING DEWATERED RESIN IS BASED ON TE TECHNICAL SPECIFICATIONS FOR TE UNIT. IF SOLIDI-I FICATION IS NOT REQUIRED BY TE TECHNICAL SPECIFICA-l l
t TIONS, TE LINDt MAY BE FIT. LED TO WITHDi 3-IN. OF TE TOP OF THE LINER. EACH LIliER MUST BE EVATERED TO LESS TRAN 1: FREE WATER PER STATE OF SOLTH CAROLINA AND BARN-l l
WELL SITE CRITERIA.
6.3.4.9 Continue pumping until the puc:p loses suction and suction can-not be regained.
6.3.4.10 Perform radiation surveys of the solidification unit operating space and waste header hourly during operation.
6.3.4.11 If solidifiestion is to be performed, proceed to Step 6.3.5.
If solidification is not to be performed, proceed to Step 6.3.5.10.
(
Page 29 WP-100 Date 3/19/81 Rev. O
6.3.5 Solidification of Resin. Sludges, and Miscellaneous Media
('
6.3.5.1 When the devatered media reaches the set point defined by the initial test solidification or by the most recent test solidi-fication, shut vsive WS-1 and secure the dewatering pump.
Inform the radwaste system operator to secure pumping and line up to flush.
6.3.5.2 When the radwaste system op; stor reports that he is ready to flush, open valve WS-1.
6.3.5.3 When the radiation level on the waste transfer hose approaches background, shut valve WS-1 and inform the radwaste system operator to secure flushing.
6.3.5.4 If the flush operation increased waste level in the disposable liner to greater than the vaste level set point, dewater down to the vaste level set point.
1.
Check valve SA-1 in the "Dewater" position.
l 2.
Adjust regulator pressure to 40 + 10 psi.
I 3.
When the vaste level probe clears (alarm light at the elec-trical control panel will cica-), secure the dewatering pump.
6.3.5.5 Place valve SA-1 in the "UF Transfer" pump position.
6.3.5.6 Start the UF transfer pump and transfer UF to the disposable liner.
1.
Adjust regulator to 40 j-10 pai.
2.
Monitor for flow and continue adding UF until the waste-to-UF ratio, as defined by the most current test solidification specimen, has been achieved.
3.
Secure the UF transfer pump.
(
i Page 30 WP-100 Dats 3/19/81 Rev. 0 4
yn,
..c, y-. - -
-.---u,,w,,,--,-,
,~,...
,~,,,-.,_y,
-.-c,
_,,,,-,-~,,---.,,-.--,,,_,w--~-,c.,
--.--e-%
.-.w
l NOTE: DURING UF ADDITION, MONITOR CONTEh7S OF THE LLNER FOR I.
FOAMING. IF FOAMING EXISTS, SECURE UF ADDITION AND INFORM MANAGER, MOBILE SERVICES OF THE PROBLEM.
- 6. 3. 5.7 Continue sparging for a total time of at least I hr. and at least 15 min. af ter securing UF addition.
6.3.5.8 After sparging the necessary time, commence catalyst addition using the following procedure:
1.
Start the catalyst transfer pump and add catalyst until a noticeable increase in the mixture's viscosity is visible in the remote monitor.
2.
Secure the catalyst transfer pump and open valve CI-2 to drain any residual catalyst from the catalyst line.
3.
Secure the air sparge system.
4.
Verify that solidification has occurred and the rolling motion of the liquid has stopped by viewing the remote monitor.
6.3.5.9 Allow the solidified matrix to stand for at least 2 hrs., then perform the following steps to insure all free liquid is removed:
Commuce the air sparge at 40 psig for 5 min., then secure a.
air sparge.
b.
Shut or check shut valve CT-3 and DW-7.
Open or check open valves DW-1, DW-6, and CT-5.
c.
d.
Place valve SA-1 in the "Dewater" ptsp position.
e.
Start the dewatering pump.
(
Page 31 WP-100 Date 3/19/81 Rev. 0 1
. _.. _. ~. - -.. _ _ _ _ _.. - _. - -., - _.. _ _ _ _ - -
l 1.
Place the pump air switch in the "On" position.
'k 2.
With the speed control regulator, increase pump regula-tor to 40 + 20 psig.
f.
When liquid is no longer evident on the suction of the dewatering pump for fif teen consecutive minutes, secure the dewatering pump.
g.
Allow liner to sit for 4 hrs., then repeat (f) above.
h.
Shut or check shut the following valves:
CT-3, CT-5, N-7, W-6, and W -1 6.3.5.10 Secure main air switch.
6.3.5.11 Secure TV camera and monitor.
6.3.5.12 Following proper radiological precautions, raise the filling head off the disposable liner and place in its storage loca-tion.
I 6.3.5.13 Check the quality of the matrix.
a.
Perform a visual inspection.
b.
Perform a hardness examination by probing the solidified product with a rigid device.
c.
Record the condition of the matrix in the daily cperations log.
6.3.5.14 As necessary, add cascamite or a similar product to the top of the matrix.
6.3.5.15 Install the lid on the disposable liner.
6.3.6 Cask closure and Shipment Release 6.3.6.1 For cask closure, refer to the cask handling procedure and WP-101, Packaging, Storing, and Shipping of Radioactive Wastes, f
for the shipping of radioactive waste.
(
Page 32 WP-100 Dste 3/19/81 Rev. O
6.3.6.2 If a cask is used for shipment of vaste, a tamper seal must be I-affixed to the cask prior to shipment.
6.3.6.3 A Radioactive Shipment Record (RSR) is provided to certify the total volume of waste and curie content for each liner.
6.3.6.4 The RSR and shipment meno shall be submitted to the Radioactive Waste Disposal Group for verification and the appropriate sig-nature.
6.4 RECORDS 6.4.1 Analysis of Solidified Material A copy of the isotopic analysis shall accompany the shipment and the original submitted to the Quality files.
6.4.2 Containment and Radiation Surveys A copy of the final track survey shall accompany the shipment and the original submitted to the Quality files.
6.4.3 Radioactive Shipment Report (RSR-CNSI)
The RSR shall be filled out in accordance with the instructions contained on the reverse side of the form. The RSR form will be distributed as indicated on the form.
6.4.4 Radioactive Shipment Record (RSR-FPC)
An RSR shall be filled out per WP-101, Packaging, Storing, and Shipping of Radioactive Wastes, and appropriate copies submit-ted as designated on the form.
6.4.5 PNP Forms The PNP form copies upon completion shall accompany the ship-ment.
f
(
- l Page 33 WP-100 Date 3/19/81 Rev. 0
~..
k 7.0 CNSI CEMENT SOLIDIFICATION SYSTEM DESCRIPTION AND ALLIED PROCESSING AS USED AT CR-3 g
7.1 The system description of the CNSI cement solidification system is addressed in th PCP document listed in Enclosure 3.
- 7. 2 The processing steps for CNSI's cement solidification system are describing in the Operating Procedure in Enclosure 3.
8.0
SUMMARY
OF EQUIPMENT NEEDS FOR SOLIDIFICATION OF RADWASTE w
8.1 A liner and cask for transport of the solidified waste should be ordered on the basis of the radiation dose survey and the criteria given in Enclosure 1.
All liners used for solidifica-tion must be epoxy-lined.
l 8.2 The solidification media should be ordered in quantity to satisfy the following ratio:
8.2.1 a.
UF - Waste: UF = approx. 2:1 3 og gy b.
Catalyst - 35 gals./100 f t 8.3 Cranes and handling equipnent should be used considering radia-I tion factors and the gross weight capability of each, keeping in MM:
l a.
Concept of ALARA b.
Densities - Waste, 62.43 lbs/ft3 3
UF, approximately 80.1 lbs/ft 3
Cement, approximately 280 lbs/ft c.
Liner Emptyveight d.
Liner Size 8.4 Tools as necessary (i.e., calibrated torque wrenches, survey meters, chockers, labels).
(
Page 34 WP-100 Date 3/19/81 Rev. 0
l i
8.5 The cask Certificate of Compliance (Coc) and loading and han-(
dling procedures shall be available for review and must be the current revision for the applicable container per WP-101, Pack-aging, Storing, and Shipping of Radioactive ilastes.
9.0 ON-SITE STORACE OF SOLIDIFIED RADI0 ACTIVE WASTE 9.1 It may be necessary to store solidified radioactive vaste liners on-site for periods of time up to 1 yr. due to the cask scheduling and allocation system. When this occurs, these liners are to be surveyed for dose rates and placed outside the plant on the south berm inside the fenced Radiation Controlled Area (RCA). As necessary, these liners are to be shielded with temporary or permanent shielding (including other liners) to reduce the dose rate at the fence to the levels dictated by the
(
plant Health Physics Department.
9.2 A periodic check of in':>antory and liner conditions is to be performed and any problar.a noted and corrected. An effort should be made to ship the oldest liners out first whenever possible.
ENCLOSURES j
Chem-Nuclear Transport Container Inventory Common CNSI Liners Used for Solidification Chem-Nuclear Process Control Program and Operating Procedure for the Mobile Cement Solidification Unit
(
Page 35 WP-100 Date 3/19/81 Rev. 0 w-,
~
~
CllEH-HilCLEAR TRAtlSPORT CONTAINER INVEN'ITMlY Parja 1 of 2' -
CHSI PB Shielt31n9 Liner
- Haximum
- Average At l'roxim.n te j
l Transport Equivalence Drum (55 Gal) Capacity Itadlevels Radlevels container Payloa.1 Container Clansification Djmensions (inchess)
Capacity (Ft )
(R/hr)
(P/hr)
Emp.Wt.(Ibs)
(Ibs) 3 (LL-28-4) tlSA/6275/D( )
14 7/8"5 x 40" 11.50 N/A 3.5 50,0006 50,000t 20 150 1,850
~3 i
Type B
. CNS 1-8 IISA/9070/B 24"5 x 34-1/2" Hil 1
8 0.200 0.200 200 550 Type D CHS 1-13G t!SA/9044/n( )F 26-1/2"9 x 54" 6.20 1
13 5,000t 5,000t 23,250 5,000
'rppH~u tJSA/9001/B( )
26-1/2"9 x 54" 5.7 33 1,000t 1,000t 20,950 5,000 1
~
_11.1.-57-65)
USA /5005/nt )r 36-p x 116-3/4" 7.00 3
no
,39 100t 10,000+
57,000 _,
9g00 Type B
,,,5,7 050,_,,
10,000
_eCNS 4-45 USA /6375/a( )P 26"5 x 159" 6.5 - 7.5 4
_,,a
_1g,ggg __ _1_0,090,t, g
Type H
_Ba IC 50,
40,300 5,700 46"E x 100" 3.38 4
fi j
d t!S 4-85
.uShf6g3/li SPEC CNS 6-75 (ISA/9100 /A 53"5 x 74-1/2" 4.00 6
85
)70 i$g 318000 10,3o0 l
, (sic-)]-901
~5 tron 9, Ti9ht 2
CHS 6-00-1 Container, Type A 59"5 x SB"
>l R/hr 6
>1 R/hr 9 No 5.00 6
l Quantitles Online (59"5 x 60-1/4")
85 3 ft.
3 ft.
47,500 Est.
I.imit
~3Pl;C 7A
__.5.00 4
85 500t 500+
44,000 7,500 CNS 6-80-2 USA /9111/A 59"5 x 50" s 00 4
11 5 500t 500+
47,500 7,500 rHS 6-Br)-p,__
In Licent'ing 59"5 x 58" SPEC 7A 53,400 H
0 Inc.n aller 6,M A
CHS 6-101 tlSA/9105/A 34" x 40" x 156" SPEC 7A 35,000 7,000 7
87
. cus 7-100 (ISA/9113/A 75-1/2"p x 40-3/4" 3.50 150 100 _
(LI.:50:.100L _ isSA/6601/pt 1 62"4 x 75" 4.50 0
126 250t 250t 50,000 12,WO CHS 0-120 Type B
>1
/hr 9 > 1 R/Isr 9 31,000 No pe A 54" x 40" x 147" 2.00 12 N/A CNS 12-180 3 ft.
3 ft.
I.imi t t ie,
( AI.-31-120)
.thiantitic.'Loniv *
- CIIS14-190 Type B 73"5 1/4" 2.75 14 195 15 5
60,200 10,720 i
1
,jps-jo-220) ilSA/5026 /n ( )
4
'StYhiigNT911t
>1 H/hr e > l R/hr e g7,700 CHS 14-195L Container, Type A 77"5 x Ho" 2.00 14 200 3 ft.
3 ft.
31,550 Quantities only**
Page 36 WP-100 I) ate 3/19/81 Rev. O ENCLOSURE 1 (Page 1 of 2) s
e
^
i CHEtt-NUCIEAR TRANSPORT C(IITAINER INVEtrIDI4Y l'asso 2 of 2 Cl33I PD Shieldin9 lai ne r
- Max ienusa
- Average Approxim.ite Transport squivalenc, Drum (55 Gal) Capa lty Radlevels Radinvels container Pay lawl Container Clannification Dimensions (inches)
Capacity (Pt )
(R/hr)
(R/hr)
Dup.HL. (ibm)
(llm) l
~ SPEC 7A CNS 14-195H tlSA/9094/A 77"5 x 80" 2.75 14 200 25 15 39,650 16,850 Strong, Tight
]
CNS 14-220I.
Container, Type A 77-1/2"W x 89" 1.75 14 200
>l R/hr 9 >l R/hr 9 33,200 (AL-27-240) puantitles Only**
3 ft.
3 ft.
Strong, Tight CNS 14-220N Container, Type A 75"W x 87-3/4" 2.15 14 N/A
>l R/hr e -1 :t/hr 9 39,900
_.(At-27-240) puantitles Only**
3 ft.
3 ft.
Strong, Tight CNS 15-160s container, Type A 124" x 35"x 72" 2.50 15 2973
>1 R/hr 9 >l R/hr 9 42,000 I"I" Quantitles Only **
3ft.___
3 ft.
1 CNS 15-160s Type D i
IISA/6144/n 126" x 36" x 75" 1.50 15 29 83 5
1 37,000 5,000 CH3 18-450 SPEC 55 86" x 86" x 100*
1-2 18 308 5
1 36,950 g
i SPEC 7A CNS 21+300 11SA/9096/A 83"$ x 109" 1.50 21 322 5
1 30,200 27,250 ~
SilIEtaED CIDSED, TITANS-l
_ VAN PORT VEllICIE 7'5" x 40" x 9' O.50 75 t*/A 1
0.500 20 000 26,00n t
IlUI.K SilIPMENT Dump-type vehicles for the transport of bulk LSA, radioactive wastus = 620 (LJ capacity, 36,0006 CNS D1t-C ONI,Y lb payload capacity (dependin9 on various state limits). Dimensions - 18' x 52" x 04" Closed box-type containera for the sh!pement of bulk, I.SA, radioactivo wastes-360 ftl capacity, CNS Irlt-S STC 40,0006 lb payload capacity (depending on various state limits). Dimensions: without inserto -
5 78" x 190" x 52"
.l j
- Based on Cobalt 60 gamma ener9y, these Red levels are generalpy found to be censervative, however, equivalent shielding should be carefully evaluated in relation to the specific isotopes involved.
on These casks are considered " strong, tight containers" and radiation levels of the contents shall not exceed 1 R/hr 9 3 foot from the unshielded surface. The 6-00-1 and 14-195r. canks are currently in licensing for Spec 7A certification.
i 1
i Page 37 WP-100 Date 3/19/81 Rev. 0 ENCLOSURE 1 (Page 2 of 2)
ENCLOSURE 2
(
COMMON CNSI LINERS USED FOR SOLIDIFICATION LI?ER IEIGE CAPACI'"Y fM )
WASTr g
303 76.5" 200 46" 15" 1
304 105.5" 322.2 66" 22" 305 93.5" 308 59" 19.S" Adjust vaste probe first. The nur.ber given for the UF level is
(
that many inches above the waste level. Inches given are approximate only and are only as a guide. These levels depend on waste density and acidity.
NOTE: The numbers are not actual values. Actual values are to be obtained through analytical procedures. These values are approximations only.
(.
Page 38 WP-100 Date 3/19/81 Rev. O a
ENCLOSURE 3 k
CHD(-NUCLEAR SYSTD'.S. INC. PROCECS CONTROL PROGRAM AND OPERATDiG PROCEDURE FOR THE MOBILE CDfENT SOLIDIFICATION UNIT
- Part I -
PROCESS CONTROL PROGRAM FOR CNSI CDfENT SOLIDIFICATION UNITS
(
- Part II -
TDf?ORARY OPERATINC PROCEDURE FOR CNSI MOBILE CDiENT SOLIDIFICATION UNIT NO.1 (l'SJ-C-1) i l
I l
i I
I Page 39 WP-100 Date 3/19/81 Rev. 0 l
, - - -