ML20071Q219

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Process Control Program
ML20071Q219
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 12/17/1982
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20023B337 List:
References
PROC-821217, NUDOCS 8212290256
Download: ML20071Q219 (30)
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Text

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PROCESS CONTROL PROGRAM NORTH ANNA NUCLEAR POWER STATION UNITS 1 & 2 VIRGINIA ELECTRIC & POWER COMPANY i

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8212290256 821217 PDR ADOCK 05000338 P pop

D D NORTH ANNA STATION PROCESS CONTROL PROGRAM TABLE OF CONTENTS Page 1.0 SCOPE 2.0 SYSTEM DESCRIPTION 3.0 CHARACTERISTICS OF WASTE FEED 4.0 SYSTEM OPERATION -G-5.0 COLLECTION AND ANALYSIS OF SAMPLES 6.0 STATION RECORDS 7.0INTERFANEBETWEENSTATIONANDCONTRACTORSERVICES ,

APPENDIX A - SAMPLE FORMS J 4

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l.0 SCOPE 1.1 Purpose ,

The purpose of the North Anna Nuclear Power Station

Process Control Program is to assure that:
a. Solidified liquid wastes, dewatered resins and aqueous filter media are packaged in the proper i container based on their activity level; Ir
b. Dewatered resins and aqueous filter media are packaged with no detectable free standing liquid prior to transportation; and
c. That liquid wastes are solidified and contain no detectable free standing liquid.

1.2 Applicability This Process Control Program shall be implemented by all personnel who operate dewatering equipment, operate solidification equipment, package spent filter cartridges, collect and process samples used to verify conditions required by this program, and prepare documentation for shipping of radioactive waste.

2.0 SYSTEM DESCRIPTION 4

2.1 Dewatering System Two sources of spent resins for dewatering and disposal exist at the North Anna Station. The first is the Spent Resin Holdup Tank which collects for decay and disposal spent resins from the primary coolant purification system. These resins are dewatered in disposable high integrity containers. The second is the High Level Liquid Waste Treatment System. This system utilizes resins which are received on-site in disposable containers. When the resins in these containers are chemically exhausted, or the activity level of the resins approaches the limit for the container, the resins are dewatered. The following sections provide a description for each dewatering system.

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2.1.1 Dewatering System For Resins In The Spent Resin Holdup Tank The dewatering system for spent resins in the l Spent Resin Holdup Tank consists of the Spent 'l Resin Holdup Tank, the Radwaste Metering f Pump (1-LW-P-18), the Spent Resin Recirculation Pump (1-LW-P-21), the dewatering container, the shipping cask, the dewatering pump, the TV monitor, interconnecting hose and piping, valves, instrumentation and controls, and B sample taps.

- 2.1.la Spent Resin Holdup Tank 4

The Spent Resin Holdup Tank is a 1600 gallon atmospheric tank. It collects spent resins from the primary coolant 1

purification system to provide for

' radioactive decay and temporary storage.

2.1.1.b Spent Resin Transfer Pump (1-LW-P-18)

The Radwaste Metering Pump is a 10 gpm, centrifugal pump. It takes suction from the bottom of the Spent Resin Holdup tank and discharges through flexible hose to the dewatering container.

2.1.1.c. Spent Resin Recirculation Pump (1-LW-P-21)

The Spent Resin Recirculation Pump is a 10 gpm, centrifugal pump. It takes suction from the bottom of the Spent Resin Holdup Tank and discharges to the top of the Spent Resin Holdup Tank.

2.1.1.d Dewatering Container The dewatering container can be any certified high integrity container designed for use in dewatering and approved for transportation and disposal of dewatered spent resins.

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. o 2.1.1.e Shipping Cask The shipping cask can be any licensed shipping cask, designed for use with the o high integrity container utilized, which  !

provides adequate radiation shielding and package integrity for transportation of dewatered spent resins.

2.1.1.f Dewatering Pump The dewatering pump is an air driven 1-1/2" Sandpiper Pump, or equivalent.

2.1.1.g TV Monitor The TV monitor is a remote display television utilized, when required, to monitor the container filling operation. This monitor provides information to the operator on container resin and water level, and resin slurry consistency.

2.1.1.h Interconnecting Hose and Piping The resin transfer line used to sluice resin from the primary coolant purification demineralizers to the Spent Resin Holdup Tank, as well as connections from the tank to the Spent Resin Transfer Pump, Spent Resin Recirculation Pump, and plant ventilation system, are permanently installed stainless steel piping. The connection from the Spent Resin Transfer Pump to the dewatering container, the connection from the dewatering container to the dewatering pump, and the connection from the dewatering pump back to the Spent Resin Holdup Tank are all flexible rubber hose.

2.1.1.i Valves i valves are installed in the system as l l

required to select flow paths and isolate ,

portions of the dewatering system as may l be required.

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2.1.1,j Instrumentation & Controls Controls are provided to remotely start ,

and stop pumps, remotely open and close l valves, remotely monitor the container l fill head level and influent flow, and remotely indicate the container fill and discharge flow. .

2.1.1.k Sample Taps As an example, a sample tap is provided on the discharge side of the Spent Resin Recirculation Pump.

2.1.2. Dewatering System For Resins Received In Disposable Containers The High Level Liquid Waste (HLLW) System contains from two to seven disposable filter /demineralizer vessels. The dewatering system for the HLLW disposable filter /demineralizer vessels consists of the disposable vessel and the dewatering pump.

2.1.2.a Disposable Vessel The disposable filter /demineralizer vessel can be any container designed for use as a disposable filter / demineralizer vessel, with provisions for dewatering.

2.1.2.b Dewatering Pump The dewatering pump is an air driven

, 1-1/2" Sandpiper pump or equivalent.

2.1.3 Dewatering System For Filter Cartridges High Level Liquid Waste Filter is a filter which utilizes disposable cartridge filters. The cartridges are air dried prior to disposal and no dewatering system or equipment exists for dewatering spent filter cartridges.

2.2 Solidification System There is presently no operating solidification system on site. In the event contractor services are utilized for solidification, the contractor will be required to l

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Provide to VEPCO a complete system description for the solidification system to be used. The system description provided will be subject to VEPCO review and acceptance and once accepted will be incorporated by reference into j

this Process Control Program. The solidification system t will not be operable until the system description is l accepted by VEPCO.

3.0 CHARACTERISTICS OF WASTE FEEDS 3.1 Dewatered Resins i

Resins to be dewatered are either sluiced in slurry form to the disposable dewatering high integrity container, or are contained in a disposable container. Low activity resin may be shipped in a carbon steel liner.

3.2 Filter Elements spent filter elements are removed from the filter vessel housing and are processed as individual units.

3.3 Liquids For Solidification Presently liquid wastes are not fed to a solidification ,

system. In the event contractor services are utilized for solidification, the waste stream characterization will be provided by either:

a) VEPCO personnel collecting and analyzing camples in accordance with station approved procedures; or b) the contractor collecting and analyzing samples in accordance with station approved procedures.

The procedures will consider the solidification process utilized and will analyze for parameters or constituents which may effect the solidification process. Sample collection and analysis procedures will be subject to VEPCO review and acceptance, and once accepted will be incorporated by reference into this Process Control Program. The solidification system will not be operable until the sample collection and analysis procedures are accepted by VEPCO.

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4.0 SYSTEM OPERATION 4.1 Dewatering 4.1.1 Dewatering Resins in the Spent Resin Holdup Tank Exhausted resins from the primary loop cleanup system are sluiced to the Spent Resin Holdup Tank for decay and storage. The spent resin storage time in the tank is maximized to the extent possible to allow for maximum radioactivity decay. During the period of resin storage, the tank contents are periodically mixed using the Spent Resin Recirculation Pump to prevent excessive settling and resin packing. Prior to resin transfer to the dewatering container, the tank contents will be mixed. A sample for isotopic analysis may be taken from the sample tap on the recirculation line. Sample requirements are defined in PCP Section 5.0. If a sample is taken from the recirculation line, a portion of the recirculating slurry is drawn off into a sample container, the sample container contents decanted, and the isotopic analysis performed in accordance with approved procedures in the station Health Physics Procedures Manual, Section 3.

Following mixing and sampling (if performed), the radwaste metering pump is used to transfer resin slurry to the disposable dewatering container. The Spent Resin Recirculation Pump will be operating during resin transfer. The operator fills the container with slurry until the container has been filled. This is verified by the remote TV monitor. When the container is filled, the transfer of slurry to the container is stopped. The excess water is then removed by the dewatering pump. This water is transferred back to the Spent Resin Holdup Tank. After the excess water is drained, slurry is again transferred to the container until the container is filled with the resin and water mixture. The container is again drained using the dewatering pump. This process continues until the container is filled with resin (i.e., sluicing water removed). The resin filled container is dewatered in accordance with one of the following approved station dewatering procedures:

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. VEPCO Procedure 1-OP-20.2 for dewatering disposable containers.

. Chem-Nuclear Systems Inc. procedure FO-OP-003, " Dewatering Procedure for CNSI Conical-bottom High Integrity containers Containing Bead-Tfpe Ion Exchange Resin, 1%

Free-Standing Water."

l Each procedure specifies a series of minimum periods for dewatering pump operation and shutdown, and provides a minimum time period for sample collection. These procedures are not included as they are considered proprietary. The procedures have been tested for compliance in dewatering to less than the specified percentage as required by Chem-Nuclear Systems, Inc., State of South Carolina Radwaste Material License No. 97.

The approved procedures must be completely followed and the documentation required by the above procedures must be completed.

4.1.2 Dewatering Resins In Disposable filter /Demineralizer vessels Exhausted resins from the High Level Liquid Waste System are contained in disposable filter /demineralizer vessels. The vessels may be removed from service when either calculations indicate the resins contain close to 1 pCi/gm radioactivity, or the resins have insufficient ion exchange capacity remaining for adequate liquid processing. Once removed from service, the vessels are drained and dewatered in accordance with one of the following procedures. The procedure selected will be determined by the container to be dewatered.

e VEPCO procedure 1-OP-20.2 for dewatering disposable containers.

. Chem-Nuclear Systems Inc. procedure 06601-27-01, " Dewatering Procedure for the Annular Ll4-195 and L21-300 Demineralizer Liners, 1% FSW."

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e Chem-Nuclear Systems Inc. procedure l FO-OP-005, " Dewatering Procedure for the  !

10 Cu.Ft. Filtration Unit Containing Ion  !

Exhange Resins, 14 FSW.' 5 e Chem-Nuclear Systems Inc. procedure FO-OP-001, " Dewatering Procedure for the 24-inch Diameter Pressure Demineralizer Vessel containing Activated Carbon, 0.5%

Free-Standing Water."

o Chem-Nuclear Systems Inc. procedure FO-OP-004, " Dewatering Procedure for the 24-inch Diameter Pressure Demineralizer vessel Containing Ion Exchange Resins, 0.5% FSW."

o Chem-Nuclear Systems Inc. procedure FO-OP-007, " Dewatering Procedure for the Ll4-195 and 14-170 Conical-Bottom

. Demineralizer Vessels, 0.5% Free-Standing Water."

Each procedure specifies a series of minimum periods for dewatering pump operation and shutdown, and provides a minimum time period for sample collection. These procedures are not included as they are considered proprietary. The procedures have been tested for compliance in dewatering to less than the specified percentage as required by Chem-Nuclear Systems, Inc., State of South Carolina Radwaste Material License No. 97.

The above procedures must be completely followed and the documentation required by the above procedures must be completed.

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4.2 Spent Filter Cartridge Disposal When used High Level Liquid Waste cartridge filters are to be removed from service, the vessels will be drained and the elements removed. [ Note: The wound type elements used do not contain void spaces which can trap liquid in pockets.] In accordance with Health Physics i

Department Procedures, a sample of the element will be removed for radioassay following removal of the element from the filter vessel. The element will be allowed to air dry.

The element will be considered to contain less than 0.5% free-standing water when it can be placed on a clean dry plastic sheet for a minimum of four hours and, when removed, the plastic contains no free liquid. If free liquid remains on the plastic, the filter element will continue to be placed on a dry piece of plastic for four hour increments until, when the element is removed from the plastic, no free liquid remains on the plastic.

Drying of the elements may be assisted by placing the elements in a flow of warm dry air or any other means which meets station HP procedures for control of airborne particulates. However, the four-hour dryness verification shall occur with no drying air flow present, contractors may use mechanical filters for this service that would be controlled by contractor procedures.

4.3 Solidificaton There site.

is presently no operating solidification system on In the event contractor services are utilized for solidification, the contractor will be required to provide to VEPCO system operating procedures. The system operating procedures must define the process control parameters which assure the proper proportioning and mixing of waste and solidification agents. The operating procedures shall also specify minimum data logging requirements to document system operation within the specified ranges. The system operating procedures will be subject to VEPCO review and acceptance, and once accepted will be incorporated by reference into this Process Control Program. The solidification system will '

not be operable until the system operating procedures are J

accepted by VEPCO.

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5.0 COLLECTION AND ANALYSIS OF SAMPLES 5.1 General Rquirements 5.1.1 Definitions 5.1.1.a Batch - The amount of waste which fills one disposable liner or drum.

5.1.1.b Transfer - The delivery of liquid or slurry radioactive waste to a solidification or disposable container.

There may be several transfers made from several sources that compose a batch. If the transfers are made from the same source and the contents of the source are known not to change during the time of the transfers, the volume of each transfer need not be known. If the transfers are made from several different sources, the volume of each transfer must be known. If several transfers are made from one source which has inputs to that source during the duration of the transfers, the volume of each transfer must be known.

5.1.1.c Sample - A portion of a transfer or batch that represents the contents of that transfer or batch.

5.1.1.d Composite - A mixture of samples proportional by volume to the individual transfers making up a batch, thus resulting in the' test specimen being representative of the batch.

5.1.1.e Direct In-Container Sample - A sample removed from the disposable container after the container has been filled, the contents of which are a composite of ,

samples taken from various positions within the container.

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5.1.2 Frequency of Samples 5.1.2.a Dewatered Resins - A sample for radioassay purposes shall be taken from each batch, a The sample may be a representative sample  !

taken at the source (when the source remains unchanged during the transfer of a batch), a composite sample composed of samples collected at the source, or a direct in-container sample. g 5.1.2.b Spent Filter Cartridges A sample of each spent filter cartridge shall be obtained for radioassay purposes.

5.1.2.c solidification A samplo of at least every tenth batch of each type of liquid or slurry radioactive waste (e.g., boric acid solutions, spent resins, evaporator bottoms) shall be used to demonstrate solidification.

If any test specinen fails to solidify, the batch under test shall be suspended until such time as additional test specimens can be obtained, alternative solidification parameters can be determined in accordance with the procedures incorporated by reference into this Process Control Program, and a subsequent test verifies solidification. Solidification of a batch may then be resumed using the alternate solidification parameters determined.

If the initial test specimen from a batch of waste fails to verify solidification, then representative test specimens shall be collected from each successive batch of the same type of waste until three (3) consecutive initial test specimens demonstrate solidification. The operating procedure incorporated by reference into this Process Control Program shall be modified as required to assure solidification of subsequent batches of waste.

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5.1.3 ALARA Considerations 5.1.3.s Prior to obtaining any samples or

  • performing any waste transfers, a Radiation Work Permit (RWP) will be obtained. All activities shall be in compliance with the conditions of the RWP. The Health Physics department will stipulate protective clothing requirements and protective measures to be implemented to maintain doses ALARA.

5.1.3.b For high activity wastes, where handling of samples could result in personnel radiation exposures which are inconsistent with the ALARA principle, representative diluted samples will be tested / assayed or representative non-radioactive samples will be tested (for solidification verification only).

5.2 Dewatered Resins 5.2.1 Sample collection Representative sample (s) shall be taken of each batch of spent resins. Samples may be taken from the sample tap on the Spent Resin Recirculation pump discharge line, or as a direct in-container sample from the disposable container. For samples taken at the recirculation pump discharge, the tank contents shall be recirculated to provide a minimum of one tank contents changeover prior to obtaining a sample. The design of the direct in-container sampling probe assures a representative sample and, therefore, no mixing requirements exist when direct in-container sampling is used. Samples shall be taken in accordance with approved Health Physics Department Procedures / Instructions.

5.2.2 Sample Analysis The spent resin sample shall be analyzed by radioassay techniques in accordance with approved procedures in the station Health Physics Procedures Manual. A sample of the output data

documenting the radioassay is provided in Appendix i A.

5.2.3 Acceptance Criteria i

The results of the radioassay are considered acceptable when it has been verified and documented that the spent resins are packaged in a container which is acceptable for transportation and burial considering the radioactivity .

concentrations which exist in the waste. Standard containers are acceptable for waste containing less than 1 pCi/gm activity when dewatered to less than 0.5% water. High Integrity containers are required for wastes containing more than 1

pCi/gm activity and must be dewatered to less 4

than 1.0% water.

5.3 Spent Filter Cartridges 5.3.1 Sample Collection A sample of the cartridge filter element material shall be removed from the filter element. This sample shall be removed in accordance with a Health Physics departmenc procedure / instruction.

5.3.2 Sample Analysis

The cartridge filter sample shall be analyzed by radioassay techniques in accordance with approved procedures contained in the Health Physics l Procedures Manual, Section 3. A sample of the output data sheet documenting the radioassay is
provided in Appendix A.

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5.3.3 Acceptance Criteria l

The results of the radioassay are considered '

acceptable when it has been verified and documented that the spent filter cartridge is packaged in a container which is acceptable for transportation and burial considering the radioactivity concentrations which exist in the waste. Standard liners and drums are acceptable for waste containing less than 1 uCi/gm activity, and High Integrity Containers are required for waste containing more than 1 uCi/gm activity.

5.4 Liquid < for Solidification There is presently no operating solidification system on-site. In the event contractor services are utilized for solidification, the contractor, or VEPCO, shall provide procedures for sample collection and sample analysis. The sample collection and sample analysis procedures shall be for both radioactivity determinations, and solidification verification. These procedures will be subject to VEPCO review and acceptance, and once accepted will be incorporated into this Process Control Program by reference. The sol..dification system will not be operable until the sample collection and analysis procedures are accepted by VEPCO.

All chemicals used to condition or solidify waste or simulated waste in solidification tests shall be representative of the actual chemicals to be used in full scale solidification. If chemicals of a different type or from a different manufacturer are used, the new material shall be tested to verify it produces a solid product prior to full scale solidification.

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6.0 STATION RECORDS Station records shall be maintained for sample radioassay, verification of: dewatering per applicable procedure, filter -

element dryness, solidification, solidification system operation within specified process parameters, and documentation of: packaged container weight and packaged container survey results. Table 6.1 specifies the forms to be used for the above data, references the samples provided in Appendix A, and stipulates whether the form is a sample or mandatory. Where forms are a sample only, any form may be used provided it contains the minimum information provided on the sample.

TABLE 6.1

SUMMARY

OF FORMS REQUIRED TO IMPLEMENT THIS PROCESS CONTROL PROGRAM Form Sample i Data In Appendix A Mandatory Sample Radioassay 1 No Verification of Spent Resin Dewatering 2 through 5* Yes*

Verification of Filter NA (Logbook Data NA Element Dryness Sufficient)

Verification of None - To Be Provided NA Solidification By Solidification Contractor Verification of Solidifi- None - To Be Provided NA cation System Operation By Solidification Within Specified Process Contractor Parameters Documentation of Packaged 6 Yes Container Weight Documentation of Packaged Container Survey 6 Yes

  • Applicable form based upon dewatering procedure utilized.

, l 7.0 INTERFACES BETWEEN STATION AND CONTRACTOR SERVICES 7.1 Dewatering Spent Resins 7.1.1 Station Responsibilities 7.1.1.a RWP preparation and issue.

7.1.1.b HP coverage, including determination of special protective measures and shielding requirements.

7.1.1.c Resin sample collection.

7.1.1.d Resin sample radioassay 7.1.1.e Transfer of spent resins from the Spent.

Resin Holdup Tank to the dewatering container.

7.1.1.f Operation of the dewatering equipment in accordance with approved procedures.

7.1.1.g verification (QA/QC) of operation in accordance with approved procedures.

7.1.1.h Weighing the filled waste container when ready for shipment.

7.1.1.1 Survey the filled waste container when ready for shipment.

7.1.1.j Prepare and maintain all records.

7.1.2 Contractor Responsibilities 7.1.2.a Operate contractor provided treatment system in accordance with approved procedures.

7.1.2.b Place fresh demineralizer vessels in service, and take spent demineralizer vessels out of service.

7.1.2.c Remove shielded vessels for disposal.

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7.1.3 Physical Interfaces 7.1.3.a Process Fluids

1) High Level Liquid Waste Tank Discharge 25 gpm,30-150 psig, maximum temperature 125F; l-1/2",

150 psi hose with Kam-Lock fitting.

2) Filter Atmospheric Vent Hose - 1/2" ,

tygon hose connected to a 1/2" j needle valve (150 psi rating) ,

connected to a Kam-Lock fitting.

3) Demineralized Water Discharge:

5-25 gpm at 150 psig, 1-1/2", 150 psi hose with Kam-Lock fitting.

4) Resin Transfer 1/2", 150 psi hose, 25 gpm max, 150 psi max, quick disconnect fitting at '

disposable liner fill head.

5) Dewatering Line 1/2" hose' connection at disposable liner fillhead, quick disconnect fitting.
6) Crane Services for loading and unloading vessels.
7) Protective clothing and dosimetry devices for Chem-Nuclear System Inc. operators.
8) Shielding 7.2 Filter Cartridges The utility is responsible to remove the cartridges from '

the filter housing. All actions following cartridge removal are utility actions and, therefore, ,

there are no additional interfaces, j, 7.3 Solidification i  ?

There is presently no operating' solidification system on >

site. In the event contractor services are utilized for solidification, the contractor will be' required to af 1

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1 provide a list of physical interfaces, services required, and breakdown of utility / contractor responsibilities.

These documents will be subject to VEPCO review and acceptance, and once accepted will be incorporated into this Process Control Program by reference. The solidificp. tion system will not be operable until the definition of physical interfaces, services required, and utility / contractor responsibilities are accepted by VEPCO.

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4 O APPENDIX A SAMPLE FORMS

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  • A E*k I *I A- hE h E E *! - E E A -
  • E I  ! 5 =* I* 2 E E I .* h.'i.h h octo************* 5 OCT 1982 4:51:37 PH *****************
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  • 4.* 4. * * * *
  • 4 * * * * * * * * * *
  • 4. *
  • 4 4. * * * * *
  • 4 4. * * * * *
  • 4 4 * * * *
  • 4. * * *
  • 4: + +
  • SAMPLE COPY FOR INFORMRTION ONLY  !

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SAMPLE DATE: 15 RUG 82 1200:00 SRMPLE IDENTIFICATION: RAD. WRSTE TYPE OF SRMPLE: RESIN .

SRMPLE QURNTITY: 15.00000 UNITS: CC,' i SAMPLE GEOMETRY: 15 NL SHELF  !

EFFICIENCY FILE NAME: GELI.SHLF21 oc*o*****************+++++++++++.*****++++++++++++++++++++++***

RCQUIS! TION DATE: 50CT82 1635:33

  • FWHM(1332) 2.225 PRESET TIME (LIVE): 300. SEC
  • SENSITIVITY: 5.000 ELRPSED REAL TIME: 303. SEC
  • SHRPE PARAMETER : 20.0 %

ELAPSED LIVE TIME: 200. SEC

  • NBR ITERATIONS: 5.

4.*****************4.****************4.**************************

DETECTOR: GELI.#2

  • LIBRRRY:GELI. LIB 69 DATE CALIBRATED: 50CT82 1128:54
  • ENERGY TOLERANCE: 1.500KV KEV /CHNL: 0.9998521
  • HALF LIFE RATIO: 8. 00 OFFSET: 0.0756639 KEV
  • RBUNDANCE LIMIT: 80.00%

h, h o**************++++++++++++++++++++++++++++++++++++++ tS sk ENERGY WINDOW 50.068 TO 2047.773 PK IT ENERGY RRER BKGND FWHM CHRNNEL LEFT PW CTS /SEC  % ERR FIT 1 0 81.01 3477. 1373. 1. 15 80.94 77 9 1.159E 01 2. 3 2 0 276.59 540. 718. i. 92 276.55 272 9 1.801E 00 8. 2 3 0 203. 09 1414. 708. 1.19 303.06 298 10 4.712E 00 3. 8 4 0 356.15 3927. 825. 1.30 356.13 351 12 1.309E 01 1. 9 5 0 383.98 569. 549. 1. 20 383.97 380 9 1.897E 00 7. 2 6 0 437.13 125. 587. 1.92 437.12 433 9 4.175E-01 28.8 7 0 661.61 4341. 384. 1.85 661.63 656 12 1.447E 01 1. 6 8 0 1172.99 3793. 189. 1. 93 1173.09 1166 14 1.264E 01 1. 7 9 0 1332.25 3311. 60. 2. 32 1332.37 1325 14 1.104E 01 1. 8 3 I l

PERK SERRCH COMPLETED -

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SUMMARY

OF NUCLIDE ACTIVITY TOTAL LINES IN SPECTRUM 9 LINES NOT LISTED IN LIBRARY 2 IDENTIFIED IN

SUMMARY

REPORT 7 77.78%

ACTIVATION PRODUCT e

NUCLIDE ENERGY AREA 8KGND EFF UC/UT  % ERROR CO-60 1173.21* 3793. 189. 1.230E-03 1.8eSE-02 1.70 1332.46 3311. 60. 1.111E-03 1.824E-02 1.77 ZN-69M 438.63* 125. 587. 2.830E-03 2.821E-04 28.78 5415 9 FISSION PRODUCT NUCLIDE ENERGY AREA BKGND EFF UC/UT  % ERROR CS-137 661.64* 4341. 384. 1.971E-03 1.475E-02 1.65 BA-133 356.30* 3927. 825. 3.353E-03 1.029E-02 1.90 80.99 3477. 1373. 4.873E-03 1.169E-02 2.27 303. 00 1414. 708. 3.852E-03 1.112E-02 3.76 l

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7. 3 FIGURE 1 l

(' CNSI Conical-Bottom EnviroSAFETM High Integrity Containers .

Dewatering Cbmpletion Record - 1% FSW Customer

  • Plant i

l' Vessel Designation Vessel Scrial #  !

l' FU-OP-003 Proc. Step, Description Date Time CNSI Operator 4.2.3 Start Dewatering Purip Secure Dewatering Pump Total Pump Time

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4.2.4 Let Vessel Stand For )_16 Hours 4.2.5 Start Dedatering Pump

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Secure Dewatering Pump gf r

{255~;. Total Pump Time *

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4.2.6 Let Vessel Stand For > 16 Hours-4.2.8 Start Dewatering Purrp Secure Dewatering Pump .

Total Pumping Time

  • 4.2.9 Volume Of Water Collected mls Cccments:
  • Punping Time Must Be > 8 H6urs
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  • REV. SHEET I FO-OP-003 E 7 g . .. ~ . .. -

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{ CNSI 24-INCH DIAMETER M1 ESSURE DEMINERALIZER CONTAINING ION-EXCHANGE RESINS k DEWATERING COMPLETION RECDHD - 0.5% FSW

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u Customer: -

Plant:

l Vessel Serial Nunber:

FU-OP-001 '

Proc. Step Description Date Time CNSI Operator

. 4.2.1 Start Dewatering Pump 4.2.3 Secum Dewatering Pump -

Total Pumping Time (Must Be > 4 Hours) '

4.2.5 Start Dewatering Ptrp (After > 24 Hours) d h

~

(: 4.2.7 Stop Dewatering Pucp _ q%

y~

-, - Total Pumping Time (Must Be > 1 Hour) -

h -

d 4.2.8 Water Removed (During 2nd rewatering)' mis 4.2.9 Start Dewatering Punp (Af ter > 24 lburs)

Stop Dewatering Nrp Total Pumping Time (Must Be > 1 Hour)

Water Removed rr.ls (During 3rd Dewatering)

Omments:

l

\

c- .

DOCUMENT R E V. SHEET

~

FO-OP-004 A 6  ;

. . CN501002/8 78

F.- 3

. FIGURE 1 24-Inch Diameter Pressure Demineralizer Cbntaining Activated Carbon Dewatering Cbmpletion Heocrd - 0.5% FSW ~ -

"1 Customer: Plant:

Vessel Serial Ntrnber:

FO-OP-001 1 Proc. Step Description Date Time CNSI Operator I ll 4.2.1 Start Dewatering Punp 1 4.2.3 Secum Dewatering Pump Total Pump Time

  • 4.2.4 let Vessel Stand For > 14 Hours 4.'2.5 Start Dewatering Punp
  • s Secure Dewatering Pump .

Total Pumping Time

  • k 4.2.6 let Vessel Stand For > 14 Hours

'd. 4.2.7 Start Dentering Punp ah

. d ~

Secum Dewatering Pump _

Total Pumping Time

  • 428 let Vessel Stand For )_14 Hours 4.2.10, Start Dewatering Punp ,

Secure Dewatering PuT.I ,

Total Pumping T2me*

4.2.11 Volume Of Water Collected mls 4.2.12 Let Vessel Stand For )_14 Hours 4.2.13 Start Dewatering Pump Secure Dewatering Punp Total Pumping Time *.

4.2.14 Voltrne of Water Collected mis

  • Pumping Time Must Be )_ 8 Hours .

DOCUMENT REV. SHEET FO-OP-vol A 7 L _ J

.+- .

esso soom.ve

. .( - -

3

, FIGURE 1 (Cont'd)

(

g. FG-OP-001 .

Proc. Step Description Ihte Time CNSI Operator 4.2.15 Let Vessel Stand For > 14 Hours '

4.2.16 Start Dewatering Pump.

Secure Dewatering Pmp __

Total Pm: ping Time

  • 4.'2.17 Voltrne Of Water Cbilected mls I.et Vessel Stand For > 14 lburs k

(If Necessary) Start Dewatering Pur:p _ _

Secure Dewatering Pump . L ,

Total Pumping Time

  • h p, Volume of Water Collected mls
  • Pumping Time Must Be > 8 Hours -

(,.

A Corments: -

(

C DOCUMENT REV. SHEET - ,

i }D-OP-001 -

A 8 L >

. * - l l - -- -

cNso 1002/o 7e t

' ' .f FIGURE 1

[ O3SI 14-195 or 14-170 Demineralization essel

'- Dewatering Completion Record - 0.5% FSW.

(; ,

l i Customer: Plant: -

l . .

Vessel Serial Number: Vessel Type:

i FO-OP-007 ,

Proc. Step Description Date Time Operator 4.2.2 Start Dewatering Pucp 4.2.3 Secum Dewatering Pump Total Ptriping Time

  • 4.2.4 Let Vessel Stand for > 16 Hours 4.2.5 Start Dewatering Punp _

j Secure Dewatering Pump , M9 Total Ptr: ping Time

  • ek (C_

4.2.6 let Vessel Stand for > 16 lburs yv-

~

4.2.7 Start Dewatering Punp s.

Secure Dewatering Pump Total Pumping Time *

, 4. 2. {i let Vessel Stand for > 16 lburs 4.2.10 Start Dewatering Punp Secum Dewatering Pump Total Pumping Time

  • 4.2.11 Volume (bilected mls let Vessel Stand for ),16 Hours 4.2.12 Start Dewatering Punp Secure Dewatering Punti Total Pumping Time
  • i

" Volune Collected mis L,, *

  • PlMPING TIME MUST BE > 8 HOURS DOCUMENT ,

REV. SHEET K) OP-007 B 6 q . .. -- . . - i . ;

o

"" BARNWELL WASTE MANAGEMENT FACILITY <si casives out,

"'" Operated by: CHEM-NUCLEAR SYSTEMS,INC. Date

,,,,w P. O Box 726, Barnwell. South Carolina 29812 Shepment No date AS# l (803)259 t781 Contace Type W Cask RADIOACTIVE SHIPMENT RECORD FORM Date ene (2) Phare e page og Trailer No TO g Radate (4) Volume AHoCation No LINfR StRfAL e Rea4ngs Weight i h - tai Desce.gwinn as uaiensis (bl (c) (di (et Trench a LOC WCC

( 3 RADtOACTIVE MA Tt H AL L S A , N O S Total e of Pkgs Tolat Actevey ORfvER SIGNATURE Total volume Type Contasners

( ) RADIOACitvF MATE RaAL NOS

  • Tms Shipment TNs stupment TWW Personnd Esp DATE AND TIME RECElvED ( ) RADIOACTIVE MATE RtAL $PECIAL FORM N OS Tms SNomert Trws Shipment (N)a '

( e RAniOAc tivt OF vlCF N O S RAD MA T F Rf At mes cu N Ul*C' fat (71 I8I (91 f t03 test s t2, teh (14 (t53 giss este (tap seem noms- posesse ter Acesey payeeses is9p (2 00 ,[

Chomsees wesee u-zas U-23s Desessense Deepesense esa succes Ate g each some Germ (greme)

Cenemaner maosafiose ttwets namesesse Tsens. Lemos

%ecreemen Th-232 Cenesener Comeesner sees, e seen ennes sauceae tiliosamene rectese~SC C_ pass Weed tee nee Essa I (seCf3 weisht weaume Cenemaner seiresco (Tip recaese s resse o.eas, (pounde) (Co. Ft) Sestseco esucase i (a) Desse tesessie-T) l

. l i l la $

B J_ ef l

e t l l

1 i

R

' I I 5 (215 l '

  • ^' xx xx x xxx xlxxx (22)( ) Yes ( ) No THIS WHICLE IS CONSIGNED EXCLUSIVE USE LOADING AND UNLOADING MUST BE (24) "Certshcate es hereey made so the Soush Carohna Department of Health and Envvonmensaf Coreal that ties sNomers of low-ACCOMPLISHED BY CONSIGNOR OR CONSIGNEE JR MtS DE SIGNATED AGENT level raecacteve waste has been mspected e accordance weh shs eequwemeres of Soum Carchna Raeoactive Watenal labeled nd e e pr ondem for shrt'a son cor lo a it bee r axms Department Transportation led optic e g,gne,ure Date By Form No CNS 201 Company Date im aM organization (voo)

(See Reverse Sede for instructms for Completing TNs Form) TW % ( ) _

Whe+ Accompany Shement, Yesow Customer Penk Carrier

_ _

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