ML20215K273

From kanterella
Jump to navigation Jump to search
Process Control Program,North Anna Power Station Units 1 & 2
ML20215K273
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 11/27/1985
From:
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20215K253 List:
References
PROC-851127, NUDOCS 8610280081
Download: ML20215K273 (42)
v • d • e


Text

.#

REQUEST D CHANGE PROCDURE ADMM.'.

NORT"

';A P':%F:'.;TA T10.

At:Ichedpt i 1

jj f

mur-

.a....

1 y :e

(

,'m - 1 3 e

' ~

~

...suc.x as s.

O AdNORMAL 0 CURVE sooE O OPERAT:NG O %ELDINc 0 ADM:';:STRATIVE O EMERGENC

Of RIODIC TEST o

O ANNUNC:ATOR O IN-SERVICE INSPECT:0N r HEALTH eHYS:CS O

O CAL:3?ATION O MAINTENA'CE O SPECIAL TEST C

O CiEMIST7

O NON-DESTRUCTIVE TEST O START-UP TEST O

?RCCEDURE NO:

2 UNIT NO:

3 REVISION DATE:

k

&~0T$Y T '.!L E :

J U W 1 A.w4 -

M

/J CHANGES REQUESTED:

(GIVE STEP NUMBER, EXACT / SUGGESTED WORDING, AND LIST REFERENCES, STAPLE e,

i COPY OF PROCEDURE WITH SUGGESTED CHANGES MARKED TO THIS FORM.)

s

-Me ehdd i

i

REFERENCES:

REASON FOR CHM;GES: [

gg gg g

,i 7

,. g gg g, l L* K s Un. 07 & 64 & Gbv d/ m_% M stleuk & M '

1stuh%

0 ef

/

- ()

I I

i l

CH.4GE REQ' ' STED SY:

i b.

d DATE:

9;

//'$d [

l 6

/1 ACTION TAKEN:

[/

LO 1

i e

l DCES THIS CHRiGE THE OPERATING METHODS AS DESCRIBED IN T.IE FSAR?

l L5 n.S O No DOES THIS CHR;GE INVOLVE A CHA' IGE TO T.4E TECH. SPECS?

O YES Ir*F DOES THIS CHANGE INVOLVE A POSSIBLE UNREVIEWED SAFETt QUESTION? O YES

.;0

!? ALL "NO", NO " SAFETY ANALYSIS" IS REQUIRED. IF ANY "YES", A " SAFETY ANALYSIS" IS REQUIRED.

(ICCFR50.59)

APPROVED COPY TO BE PROVIDED TO LICENSING COORD. FOR INCLUSION IN AN';UAL REPORT.

RECOMMENDED ACTION:

1i ROV DISAPPROVED DOES THIS PROCEDURE N ATE A OA DOCUME';T' YESs NO Si (COGNIZA';T SUPERVISOR) 12 DATE:

13

/

r

//-3 Y~8$~

Kr:IExED scR acA1.: Y ASSisANCE req w ExExn 860228 CHANGES MADE:

O YES d

1.

05000g8 DA A f fi[ l.

3 n,,- o uS a) i '3 REV;EWED 3Y S~'. 0'/ Ni' CLEAR SAFETY AND OPEPJT!NG CO'GITTEE:

'} l li l[

(7 APPROVED y 0 D:SAPPROVED Q APPROVED AS MODIFIED BY CC'^~~rr GRMAN SIGNATURE:

ff/

13 DATE:

L9 i H

1/ J1 (C o

EW PRCCEDUKE REVifION 9 ATE

'O 4

20 l U

.~.

2.=

b_..Ll L.4 M{_d

..b

~

~~.

~~

a

- r

Proccas Control Program Page 1 of 27 11-27-85 k

P PROCESS CONTROL PROGRAM NORTH ANNA POWER STATION UNITS 1 & 2 VIRGINIA POWER

(

k l

r-

.m.

Process Control Program Page 2 of 27 11-27-85 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 5.0 COLLECTION AND ANALYSIS OF SAMPLES 6.0 STATION RECORDS 7.0 INTERFACE BETWEEN STATION AND CONTRACTOR SERVICES k

APPENDIX A - SAMPLE FORMS

\\

i I

(.

f 1

1 Process Control Program Page 3 of 27-11-27-85 1.0 SCOPE 1.1 Purpose The purpose of the North Anna Nuclear Power Station Process Control Program is to ensure that:

Soldified liquid wastes, dewatered resins, and aqueous filter media a.

are packaged in the proper container based on their activity level; b.

Dewatered resing and aqueous filter media are packaged with no detectable free standing liquid prior to transportation; Liquid wastes are solidified or, in the case of contaminated oil, c.

may be aborbed in an approved absorbent and contain no detectable i

free standing liquid; and d.

Resultant soldified/ absorbed wastes are in compliance with the provisions of 10 CFR Part 61.

1.2 Applicability This Process Control Program (PCP) shall be implemented by all personnel who operate dewatering equipment, operate solidification equipment, process waste oil, packaged spent filter cartridges, collect and process samples used to verify conditions required by the Program,

^

and prepare documentation for shipping of radioactive waste.

2.0 SYSTEM DESCRIPTION 2.1 Dewatering System Four 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 for the primary coolant purification system. These resins are dewatered in disposable high integrity containers. The second is the High Level Liquid Waste y_

2 Process Control Program Page 4 of 27 l

11-27-85 l

2.0 SYSTEM DESCRIPTION (cont.)

Treatment System. Ths system utilizes resins which are received l

on-site in pre-loaded 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

~

third source of spent resin is also from the M Level Liquid Waste Treatment System. These resins are loaded into pressure vessels i

already on-site. When chemically exhausted,'the resins are sluiced to an applicable container for dewatering. The fourth source of spent

(

resin is from the condensate polishing demineralizer system. This is a I

powdered resin system and the contaminated resins are transfered to a j

seperate holdup tank for later transfer to a dewatering container.The following sections provide a description for each dewatering system.

2.1.1 Dewatering System For Resins In The Spent Resin Holdup Tank The dewatering system for spent resins in the Spent Resin Holdup j

Tank consists of the Spent Resin Holdup Tank, the Radwaste i

Metering 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 f

piping, valves, instrumentation and controls, and sample taps.

2.1.1.a Spent Resin Holdup Tank The Spent Resin Holdup Tank is a 1600 gallon atmospheric tank.

It collects spent resins from the primary coolant purificaiton system to provide for i

radioactive decay and temporary storage.

a-k Process Control Program Page 5 of 27 11-27-85 t

i 2.1.1.b Spent Resin Transfer Pump (1-LW-P-18) f The Radwaste Metering Pump is a 12 gpm, progressive L

cavity pump.

It takes suction from the discharge of t

1-LW-P-21 (Bead Resin), 1-LW-P-25 (Powered Resin) or

[

f liquid waste evaporator bottoms, (NOT USED).

1-LW-P-18

~

discharges through a flexible hose to the dewatering 4,

container.

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

The Spent Resin Recirculation Pump is a 70 gpm, j

r I

centrifugal pump. It takes suction from the bottom of the Spent Resin Holdup Tank and discharges to the top f

(

of the spepr Resin Holdup Tank, e

r 2.1.1.d Dewatering Container The dewatering container can be any certified high integrity container designed for use in dewatering and I

~

L approved for transportation and disposal of dewatered j

t spent resins.

[

t 2.1.' 1. e Shipping Cask l

t The shipping cask can be any licensed shipping cask, designed for use with the high integrity container j

utilized, which provides adequate radiaiton shielding

(

and package integrity for transportation of devatered spent resins.

7 2.1.1.f Dewatering Pump The dewatering pump is an air driven, 1-1/2",

" Sandpiper" pump or equivalent.

l r

i

Process Control Program Page 6 of 27 11-27-35 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.

2.1.1.1 valves Valves are installed in the system, as required, to select flow paths and isolate portions of the dewatering system as may be necessary.

.2.1.1.j Instrumentation and Controls Controls are provided to remotely start and stop pumps, remotely open and close valves, remotely monitor the container fill-head level and influent flow, and remotely indicate the container fill and discharge flow.

[

Process Control Program Page 7 of 27 11-27-85 2.1.1.k Sample Taps As an example, a sample tap is provided on the discharge side of the Spent Resin Recirculation Pump.

2.1.1.1 Spent Powdered Resin Recirculation Pump 1-LW-P-25 The spent powdered resin recirculation pump is a pregressive cavity pump, which takes suction from the bottom of the spent powdered resin tank and discharges to the top of the tank and provides positive pressure to the suction of 1-LW-P-18.

2.1.2 Devatering 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 /demeralizer 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 Sysyem for Resins Loaded Into Pressure Vessels On-Site The High Level Liquid Waste (HLLW) Cystem may contain sluicable filter /demineralizer vessels. The dewatering system for HLLW sluicable filter /demineralizer vessels consits of sluciable pressure vessels, a dewatering pump, applicable container and i

heat enhanced dewatering system.

j

Process Control Program Page 8 of 27 11-27-85 2.1.3.a Sluicable Pressure Vessel The sluciable filter /demineralizer vessel can be any container designed for use as a sluciable filter /demineralizer vessel.

2.1.3.b The dewatering pump is an air driven, 1-1/2",

" Sandpiper" pump or equivalent.

2.1.3.c The applicable container can be any container designed for use in dewatering and approved for transportation and disposal of dewater resins.

2.1.3.d-The heat enhanced dewatering system can be any system designed for use in dewatering resin materials using heated air circulated through the media to prepare liners for transportation and disposal.

2.1.4 Dewatering System For Filter Cartridges The High -Level Liquid Waste Filter utilizes disposable cartridge filters. The cartridges are air dried prior to disposal; therefore, no dewatering system or equipment is needed nor exists for dewatering spent filter cartridges.

2.2 Solidification System There is no permanently installed, operating soldification system on-site.

In the event contractor services are utilized for soldification, the contractor will be required to provide to Virginia Power a complete description of the solidification system to be used. The system description provided will be subject to Virginia Power review and acceptance and once accepted, will be incorporated by reference into this Process Control Program. The soldification system will not be operable until the systen description is accepted by Virginia Power.

4 Process Control Program Page 9 of 27 11-27-85 2.3 Absorption System The oil absorption equipment consists of a batch tank (approximately 275 l

t gallons), a recirculation pump, a mixing pan, and a mixing hoe.

i 2.3.1 The batch tank is a 50 cubic foot, carbon steel, cask liner modified to contain a lower drain / recirculation line, and is mounted on four two-foot legs.

l 2.3.2 The recirculation pump is an air dricen, 1-1/2", " Sandpiper" pump or equivalent.

i 2.3.3 The mixing pan is a 4 foot b'y 3 foot by 1-1/2 foot stainless steel container.

2.3.4 The mixing hoe is a standard garden hoe.

3.0 CHARACTERISTICS OF WASTE FEEDS 4

3.1 Dewatered Resins 1

Resins to be dewatered are either sluiced to the disposable dewatering high integrity container or are contained in a disposable container.

b Low activity resin may be shipped in a carbon steel liner.

3.2 Filter Elements l

Spent filter elements are removed from the filter vessel housing and are i

processed as individual units.

3.3 Liquids For Solidiciation f

Presently liquid wastes are not fed to a solidiciation system.

In the i

l event contractor services are utilized for.solification, the waste stream characterization will be provided by either:

l a.

Virginia Power personnel collecting and analyzing samples in i

accordance with station approved procedures; or b.

The contractor collecting and analyzing samples in accordance with i

station approved procedures.

~

.w Process Control Program Page 10 of 27 11-27-85 The procedures will consider the solidification process utilized and will analyze for parameters or constituents which may affect the 1

solidification process. Sample collection and analysis procedures will i

be subject to Virginia Power review and acceptance and once accepted, will be incorporated by reference into the Process Control Program.- The.

l soldification system.will not be operable until the sample collection and analysis procedpres are accepted by Virginia Power.

3.4 Contaminated Waste Oil: Solidfication/ Absorption l

t Radioactively contaminated waste oil is collected and stored until such f

i time as a volume, sufficient to warrant a shipment to a disposal facility, is to be processed. Approved Health Physics procedure (s) will be used for the absorption process; Virginia Power approved vendor procedures will be used for solidification, as delineated in step 3.3.

4.0 SYSTEM OPERATION 4.1 Dewatering 4.1.1 Dewatering Resins From the Spent Resin Holdup Tank Spent 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 maxfaum 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 Section 5.0.

If a sample is taken from the recirculation line,'a portion

J.

Process Control Program Page 11 of 27 11-27-85 l

of the recirculating slurry is drawn into a sample container, the sample container contents decanted,' and an 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 l

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 l

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. Af ter the l

excess water is removed, 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., slicing water removed). The resin-filled container

~

is dewatered-in accordance with one of the following station approved dewatering procedures:

l b

Process Control Program Page 12 of 27 11-27-85 Virginia Power Procedure 1-OP-20.2 for dewatering disposable containers.

Virginia Power Procedure 1-OP-20.6 " Dewatering Procedure for CNSI 14-195 or Smaller Liners Containing Bead Resins".

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

4.1.2 Dewatering Resins In Disposable Filter /Demineralizer Vessels I

Spent resins from the High Level Liquid Waste System are contained in disposable filter /demineralizer vessels. The i

vessels may be removed from service when either calculations indicate the resin 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.

l l

Process Control Program Page 13 of 27 11-27-85 Virginia Power Procedure 1-OP-20.2 for dewatering disposable containers.

Virginia Power Procedure 1-OP-20.3, " Dewatering Procedure for the 24-inch Diameter Pressure Demineralizer Vessel Containing Activated Carbon.

0.5% Free-Standing Water."

Virginia Power Procedure 1-0P-20.4, "Dwatering Procedure for the 24-tach Diameter Pressure Demineralizer Vessel Containing Ion Exchange Resins, 0.5% FSW."

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 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 procedure (s) must be strictly followed and the documentation required by the above procedures must be completed.

Process Cct.?vol Program Page 14 of 27 11-27-85 4.1.3 Dewatering Ion Exchange Media Loaded Into Pressure Vessels On-Site Spent ion exchange media from the High Level Liquid Waste System may be removed f rom service when they are chemically depleted or become fouled.

Once they are removed from service, the media is transfered to an applicable liner for dewatering for transportation and burial. The liner shall be dewatered in accordance with 1-OP-20.6, which specifies a series of minimum periods for dewatering pump operation and shut down and provides a minimum time period for sample collection. The procedure is 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.

4.1.4 Dewatering Spent Powdered Resin From Spent Powdered Resin Holdup Tank Spent powdered resins from the condensate polishing demineralizer system are transfered to the spent powdered. resin holdup tank for I

storage. The spent powdered resin recirculation pump will recirculate the tank providing suction pressure to 1-LW-P-18 which pumps the resin into a dewatering container. As the dewatering container is filled, a dewatering pump removes excess water. The resin filled container is dewatered in accordance with the station approved dewatering procedure 1-OP-20.7 for dewatering CNSI 14-195 or samller liners containing Ecodex, Powdex resin, or diatomaceous earth. This procedure specifies a series of minimum periods for dewatering pump operation and shutdown and provides a minimum time period for sample collection. The procedure has been tested for compliance in

- ~ ~

Process Control Program Page 15 of 27 11-27-85 dewatering to less than the specified percentage as required by Chem-Nuclear System, Inc., State of South Carolina Radwaste material License #97.

The approved procedure must be strictly followed and the documentation required by the above procedure must be completed.

4.2 Spent Filter Cartridge Disposal When used, High Level Liquid Waste cartridge filters are to be removed from service, the vessels 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 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 s

to be placed on a dry piece of plastic for four hour increments until, j

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 i

i elements in a flow of warm, dry air or any other means which meets 1

i station HP procedures for control of airborne particulates. However, 3

the four-hour dryness verification shall occur with no ' drying air flow W

present. Contractors may use mechanical filters for this service that

[

f would be controlled by contractor procedures.

I 1

h g

e---

-, - -, -3

,g w+

,,,-g

Process Control Program

-Page 16 of 27 11-27-85 4.3 Solidification There is no permanently installed, operating soldification system on site.

In the event contractor services are utilized for solidification, the contractor will be required to provide to Virginia Power system operating procedures. The system operating procedures must define the process control parameters which assure the proper proportioning and mixing of waste and rolidification agents. The operating procedures shall also specify minimum data logging i

requirements to document system operation within the specified ranges.

The system operating procedures will be subject to Virginia Power review and acceptance and once accepted, will be incorporated by reference into this Process Control Program. The solidification system

,j system will not be operable until the system operating procedures are accepted by Virginia Power.

Presently accepted procedures for use are:

e Chem-Nuclear Systems, Inc. procedure SD-OP-027, " Operating i

Procedure for CNSI Portable Cement /0il Soldification Unit No. I 1

(PSU/0il-C-1)";

Chem-Nuclear Systems. Inc. procedure SD-OP-026 " Process Control Program for Cement /011 Solidification"; and Chem-Nuclear Systems, Inc. procedure SD-OP-003, " Process Control Program for CNSI Cement Soldification Units."

L 4.4 Absorption Radioactively contaminated waste oil will be processed in accordance with Health Physics Department procedure (s).

The process parameters, acceptance criteria, and packaging requirements are specified in the l

applicable procedure (s).

f l

l Process Control Program Page 17 of 27 11-27-85 5.0 COLLECTION AND ANALYSIS OF SAMPLES 5.1 General Requirements 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 sluiced radioactive 1

. waste to a soldification 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 j

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 l

disposable container after the container has been filled; the contents of which are a composite of samples i

taken from various positions within the container.

(

Process Control Program Page 18 of 27 11-27-85 5.1.2 Frequency of Samples 5.1.2.a Dewatered Resins - A sample for radioassay purposes shall be taken from each batch. The sample may be a representative sample taken at the source (when the source remains unc~ hanged during the transfer of a batch), a composite sample composed of samples collected at the source, or a direct in-container sample.

5.1.2.b Spent Filter Cartridges A sample of each spent filter cartridge shall be obtained for radioassay purporses.

5.1.2.c Solidification / Absorption i

A sample of at least every tenth batch of each type of liquid or sluiced radioactive waste (e.g., boric acid solutions, spent resins, evaporator b.ottoms) shall be b

used to demonstrate solidification / absorption.

j If any test specimen fails to solidify or absorb, the batch under test shall be suspended until such time as

/

additional test specimens can be obtained, alternative

}

soldification/ absorption parameters can be determined in accordance with the procedures incorporated by reference into this Process Control Program, and a subsequent test verifies soldification/ absorption. Processing of a batch may.then be resumed using the alernate parameters determined.

1' l

Process Control Program Page 19 of 27 11-27-85 If the initial test specimen from a batch of waste fails acceptance criteria, 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 / absorption. The operating procedure (s) incorporated by reference into this Process Control Program shall be modified, as required, to assure solidification / absorption of subsequent Latches of waste.

5.1.3 ALARA Considerations 5.1.3.a 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.

i 5.1.3.b For high activity wastes where handling of samples could result in personnel radiation exposures which are i

inconsistent with the ALARA principle, representative diluted samples will be tested / assayed or representative non-radioactive samples will be tested (for soldification/ absorption verification only).

~.,

e Process Control Progran Page 20 of 27 11-27-85 5.2 Dewatered Resins 5.2.1 Sample Collection Representative sample (s) shall be taken of each batch of spent powdered or bead 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 l

~

samples taken at the recirculation pump discharge, the tank contents shall be recirculated to provide a minimum of one tank l

contents changeover prior to obtaining a sample. The design of the direct, in container sample 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 t

in accordance with approved procedures in the station Health r

Physics Procedures Manual. A sample of output data documenting a l

radioassay is provided in Appendix A.

5.2.3 Acceptance Criteria 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 I

wastes containing more than 1 pCi/gm activity and must be dewatered to less than 1.0% water.

i

...-yw-.-.

+

y-, - - -,.

,.g

-,-.,._-,.7-

,,y

.a

-.%,.ev.--ywy +-

gg y

+-

pye-cw'-r'.+.--'

~

~ '

+

Process Control Program Page 21 of 27 11-27-85 5.3 Spent Filter Cartridges 5.3.1 Sample Collection A sample of the cartridge filter element material shall be removed from the filt.er element. This sample shall be removed in accordance with a Health Physics Department procedure / instruction 5.3.2 Sample Analysis The cartridge filter sample shall be analyzed by radioassay i

techniques in accordance with approved procedures contained in the Health Physics Procedures Manual, Section 3.

A sample of an output data sheet documenting a radioassay is provided in l

Appendix A.

5.3.3 Acceptance Criteria 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 concentration which exist in the vaste. Standard liners and drums are acceptable for waste containing less than 1 pCi/gm activity and High Integrity Containers are required for wasta containing more than 1 pCi/gm activity.

m e

y y

r---

g

--77 e

=-e--

+ -

e

~

Process Control Program Page 22 of 27 2

11-27-85

(

S.4 Liquids for Solidification There is no permanently installed, operating solidification system on-site.

In the event contractor services are utilized for solidification, the contractor or Virginia Power shall provide procedures for sample collection and sample analysis. The sample collection and sample analysis procedures shall be for both

)

radioactivity determiantion and solidification verification.

These procedures will be subject to Virginia Power. review and acceptance and once accepted, will be incorporated into this Process Control Program by reference (See Section 4.3).

The solidification-system will not be operable until the sample collection and analysis j

i procedures are accepted by Virginia Power.

(

All chemicals used to condition or solidify waste or simulated waste in soldification tests shall be representative of the actual chemicals to be used in full scale. solidification.

If chemicals of a different type f

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.

5.5 Waste 011 Absorption i

5.5.1 Sample Collection Representative samples shall be taken of each batch of radioactively contaminated waste oil. Samples may be taken from the recirculation pump discharge line.

5.5.2 Sample Analysis The oil samples shall be analyzed by radioassay techniques in

(

accordance with approved procedures in the Health Physics Procedures Manual.

I i

Process Control Program l

Page 23 of 27 11-27-85 5.5.3 Acceptance Criteria Any activity indentified in the oil samples greater than Minimum t

Detectable Activity (MDA) shall deem the oil radioactively contaminated, thus requiring processing and disposal 'n accordance with approved Health Physics Procedures'.

6.0 STATION RECORDS Station records shall be maintained for sample radioassay, verification of 7

dewatering per applicable procedure, filter element dryness.

^

soldification/ absorption, soldification system operations 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 samole.

i 1

Process Control Program Page 24 of 27 11-27-85

/

TABLE 6.1

SUMMARY

OF FORMS REQUIRED TO IMPLEMENT THIS PROCESS CONTROL PROGRAM Form Sample #

L Data In appendix A Mandatory Sample Radioassay 1

No Verification of Spent Resin Dewatering 2 through 5*

Yes*

Verification of Filter NA (Procedure Element Dryness sign-offs)

Yes Verification of None - To Be Provided NA Soldification By Solidificaiton Contractor Verificaiton of Solidification None - To Be Provided NA

(

System Operation Within By Solidification Specified Process Parameters Contractor Verification of Absorption 7

Yes Documentation of Packaged 6

Yes l

Container Weight Documentation of Packaged 6

Yes Container Survey l

  • 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 Responaibilities 7.1.1.a RWP preparation and issue.

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

7.1.1.c Resin sample collection.

Process Control Program Page 25 of 27 11-27-85 g

3 7.0 (cont.)

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 e

approved procedures.

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

7.1.1.1 Surveying 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.

7.1.3 Physical Interfaces 7.1.3.a Process Fluids 1.

High Level Liquid Waste Tank Discharge: 5-25 gpm at 30-150 psig; maximum temperature-125F; 1-1/2", 150 psi hose with Kam-Lock fitting.

2.

Filter Atmospheric Vent Hose:

1/2" tygon hose connected to a 1/2" needle valve (150 psi rating) connected to a Kam-Lock fitting.

.. _... _ - - ~. - -

Process Control Program Page 26 of 27 11-27-85 7.0 (cont.)

3.

Demineralized Water Discharge: 5-25 gpm at 150 psig; 1-1/2", 150 psi hose with Kam-Lock fitting.

4.

Resin Transfer: ~1-1/2", 150 psi hose; 25 gpm max at 150 psi max; quick disconnect fitting at disposable liner fill head.

5.

Dewatering Line:

1-1/2" hose connection at disposable liner fillhead; quick disconnect fitting.

6.

Crane Services for loading and unloading vessels.

7.

Protective clothing and dosimetry devices for contractor operators.

8.

Shielding.

7.2 Filter Cartridges

(

The utility is respobsible for removing the cartridges from the filter housing. All actions following cartridge removal are utility actions; therefore, there are no additional interfaces.

7.3 Solidification There is no permanently installed, operating solidification system on-site. In the event contractor services are utilized for solidification.

the contractor wiil be required to provide a list of physical interfaces, services required, and breakdown of utility / contractor j

responsibilities. These documents will be subject to Virginia Power i

review and acceptance and once accepted, will be incorporated into this j

Process Control Program by reference (See Section 4.3).

The solidification system will not be operable until the definition of physical interfaces, services required, and utility / contractor j

responsibilities are accepted by Virginia Power.

':.- ' ~

k Process Control Program

- Page 27 of 27 11-27-85 7.4 Absorption The utility is responsible for all activities pertaining to processing of radioactively contaiminated waste oil using the absorption technique.

n

(

t 1

i

\\

l

~ " * * ' '

+*-

+ -~

4

Process Control Program Appendix A Page 1 of 10 11-27-85 fi APPENDIX A SAMPLE FORMS

(

1

'j i

.=,%-

....,..-....+-....

..-4

+ -..

Process Control Program Appendix A Page 2 of 10 11-27-85

,ow.4o.t*w ow.,+%+wowu+w+e*ww+oweno+wn+w,

+++++++++4w,,++++

13-JAN-S6 10:40:01

+++%+++++++++++,~

  • w wwn wwuowww* nw* e***w ** *
  • e u *+ w we+oonn LED 356 0001 SAMPLE DATE:

13-JAH-86 09:30:00 SAHPLE IDENTIFICATICH:

FOR SHIPHENT TYPE OF SAHPLE:

LIQUID SAMPLE QUANTITY:

15.00000 UNITS:

HLS SAMPLE GECHETRY:

15 HL VIAL EFFICIENCY FILE HAHE:

GELI. TAB 11.,

e m *n * **u

  • x r : : x : n *
  • w
  • w*u* *
  • w**** ** ** * * * * * * * ** * ** + + +
  • '{,s ;. & '.' < 5: a_? ;,!Nih*A \\

.M". ;;

~

ACQUIRE TOATE::$.35TAK-86:.'LO':S:36,.,

  • ar H H H:(.L 3 3 2 )'. : "

l2';225 v

PRESET'.TIMECLIVE)'Y:-!NNidGod.WECW SENSITIVITY $* * * > LO ELAP.SEU.'. R. E4. b, TIME...m.i,.$,$,

N il.

EL) ? SED: LIVE.nTIME m..%3;.5. 09..'m$,,S.E.C5.S. S..HA.,P,,E'.:P.. A.R M. ETE ?

W

.g.

600#SECw'n4H8RyIT'ERATIGHSv:

5.-

i

..g Qqy;. u.9. l$.q,yi+y%. gpq).> j.g.e n.;;.n; s

.t1 u..

....m..

c.

.u.

.4 44 HMM 4% % % %%MMM % %%% % % %%%% %% %% % %% %%%N% % %%%%#4 %%%M%%% % % % %% % % % k DETECTOR: GELI #1

. l.

W LIBRARY:GELI. LIB 69 CAL 18 DATE:

12-JAN-86 20:59:49 4 ENERGY TOLERANCE:

1.500KV KEV /CHHL:

0.9998423

  • HALF' LIFE RATIO:

S.00 CFFSET:

0.1823709 KEV M ABUNDANCE LIMIT:

80.00%

\\

t k % %%%4 % M N4M kNMWM %%% %% %% %%% # %%%% % %4 NMMMM M MMMMMMM%H k4%+4 % + % + +

l-l hi-Q$p' Y.

j'k

? d.

i,W r:-

,M_

~

.? {;;:f '.x.;fll ENERGY HINDOH4 = ':50.117' TO.W 2047'.86
  • PK,IT.' E.NE.,y.Gt<)..:'>.AR..EA'NhNd$$$'@fd%fN.h5%N7N.-:

M*Ef.D

.NhN1N '

BKGND"Q;FM NN.EL}.LEFT.;PM. CTS /SEC % ERR FIa l % R M cg W QE:t' 9 ;,fm.?q.;34.%,.# %m,H.K;~CHA W w4,p.%yO..

R 8?SM

- ~ ~.

-m m

t.

M hW?.~ *

~.;s.

0" K122'236%.'v:535W 'l. -ew:3633 :'b.1'.IH: %.IL22220' itL9 7'8.91E-01 16.5 1

2.

O ~'198.72

. 194..

4134;- L 85 198.57 196 6 3.23E-01 47.4 3

.0 364.67

... 825..

2854.-

E.99 364.54. 361 7 1.38E 00 9.8 4

0 :510.98 e 2 0 7 1 8.,..

5132.

~.2.96 510.87., 505' 13 3.45E 01 C.8

.mf

. **- 2:08

. 569.42' 566 7 3.35E-01 40.7 l3236' :

5 O.

569.5E

.. : 201.ll.'.:.4418..'1;97

".604.76 601 8 1.58E 00 10.5 g.

6 'O'.604.85 9 48.' *'

7 '. 0 - 66 E.67. ^0926.'

2582. A 1.90'.* I'661.59. ' 657' 11 3.21E 00 4.4

~

8 0 ' "-79 5.'79 ' '

652. ' ' 'i2201,'.Y.'87' 795.73 ~.792

~ 9 1.09E 00 8.5 I

9 0

810.71' 49825.'

1625.~ 1.87:

810.66 804 13 8.30'E 01 0.5

~

~762.

1.55 834.90 831 8 4.15E-OL 16.9 10 0

834.95 249.

11 0

864.07 329..

883.'

1.97 864.02 859 10 5.49E-01 13.9 12 0~ ;1173:! s.

1.303.

2547..l.2.03 1L73.17 L L68 11.L.22E 01 1.3 13 ;4L132[.63

, f504.;

..:' :176;.' M 45 1321.66'.1*31T 22 8.40E-01 5.1 7.68E 00 14 4,1332.47

. 6516..

' L'48;. 2.03 1332.50 1317 22 1.09E 01 1.2 15 0 2460*.20^ &. 24.: : -

?.;23. _ < 2. 64 'L460.25.145T 7'3.92E-02 35.3 16 0.1674.66-167.

. : 74.. :2.'11 1674.74 1668 27 2.79E-01 10.6

"**' $Q 5ft:f; & <T (.*Q': $y: ' f*l?c s ':

PE.K SEARCH;C0kf.PLETED (REV 13)

A

,s.

'.~. 4.,L

^

~'

-4.

...,,,.W...*'.

  • si, ',6,' S * '.,,.

SAMPLE l

Process Control Program Appendix A Page 3 of 10 11-27-85 NUCLIDE IDENTIFICATION SYSTEH (REV 1/84)

SUUHARY OF NUCLIDE ACTIVITY-L'!iES HOT LISTED IN LIBRARY

, 2d TOTAL LIHES IN SPECTRUM 7

..'56.2 y.y.

.5%... l -y y,. 0,.s ~ - -

liTIFIED N

SUMMARY

REPORT 9

. g -.

ACTIVATIDH PiiDCUCT v :.n liUCLIDE ENERGY AREA BACKGROUND 2' EFF-

% AB'

- UCI / UNIT HH-54 S34.83+

249.

. 76 2. -

LO;125E 01 -

99.90 6.OOSE -5

e'

~..

l q ;; ~;. ~ ; -.

xt CO-57 122.06*

535.

. 3633.. ~ ? 0.575E: 01

& L*SSi60:

3.265E -5

.. ~

!^ !?

5.GGa:

"9A

^

?

....,. v o.. ~.... v. u w y

..r Mt J.

k *a -. - - ~

v.

a

-)p... c r.. r++.

-e 3..s *4L.e, x +*.:

w y

. pe

..3 S

q,o.~.py-r 'n rw

~s

a -:*

.r. Y f'" & Ih f f'*h $~N? lf3h' h $ $ Y &;

A

~

CO-53 S10.S0*

49 S25.~ > *, _ 1625wXd.; 02:122E%01c.:*%99:2569:\\;T.16SE -2 c

s.).6,}'.{;.WG N:: h;1?,. %.Y.!6. %.i.'.:*:.._.;

3

- e.....y. 7,.. ;7

~4 i

CD-6C 1173.21+

7303.

547*

l.900E bO; 9959h 2.440E ~3 1332.46 6516.

48...,*0.790E 00;,

.1.00.00., L2.476E -3

. '.O'.:a 3_.

'i

_.t...

t.i..:s c.. -

'ALOGEN F:CSION PRODUCT

~

'.3:>rr; m. '

.t.-7',.

i-3 r

_'r'..,;

CCLIDE EliERGY AREA. BACKGROUND *.. /..EFE.. _

-.4/CI / UNIT

.% AB.

I-131 364.48*

S25.

2S54.

. O.269E' 01 -

- 81 ~. 20.' ' 1.13SE -4

.?.w.. bA.z;f

&..l &'6-jj%* ;~9;; ;.,

. a.: ; - n.:.n a :v -.q, f r.+. - '

l

.m c n ' :;::f, d A;;rYn,T;n~.l'W.C.,, :

4::;k ~ ;%

., ?:.p;1gv.Q,J*4 k+&+.3 }r.dy,- -

a

'! V ux,T.m,,yx.,,&j.

s.

.^"

r y

d yff 9?m.:M.y FISSION PRODUCT lLIDE ENERGY AREA BACKGR. OUND:~.b.,. 'b_ EFF G.s... ' ' :Z'..AB C. ". :UC.I ~/ UNIT

~. -

Ld-134 604.69*

?46.

.'4418. - - 0 L 175E' = 01_-

,; 97.60.', 1:66ZE.-4

.x.

.T :-- : :

661.64+

!?:6.

2592.

O.161E O!

90.00 3.989E -4 t

t

~~

N;TLRAi PRCDUC i.:CLIDE ENERGY AREA BACKGROUND

- % EFF -

%^ AB UCI / UNIT ll~. D 14t.O.00*

24.

23..

0.734E 00-

~11.00 '.'S.741E -5

, i,:n 4:t.% '-

n. :.

+

I e

b I

i f

SAMPLEI i

t l

1 i

'T*' **--~*'""*" '? 1.

[;

Process Control Program Appendix A Page 4 of 10 11-27-85 VIRGINIA POWER NORTil ANNA POWER STATION UNIT 1 DEWATERING DATA SHEET FOR 24 INCH DIAMETER PRESSURE VESSEL CONTAINING ACTIVATED CARBON VESSEL SERIAL NUMBER SHIPPING NUMBER STEPS DATE TIME INITIALS 4.5 Start Dewatering Pump 4.6 Stop Dewatering Pump 4.7 Start Dewatering Pump 4.8 Stop Dewatering Pump

(

4.9 Start Dewatering Pump 4.10 Stop Dewatering Pump 4.12 Start Dewatering Pump 4.13 Stop Dewatering Pump Volume Water Collected mils 4.14 Start Dewatering Pump-4.15 Stop Dewatering Pump Volume Water Collected mils 4.16 Start Dewatering Pump 4.17 Stop Dewatering Pump Volume Water Collected mils SAMPLE 2

Process Control Program Appendix A Page 5 of 10 11-27-85 l

DEWATERING DATA SHEET FOR 24 INCH DIAMETER PRESSURE VESSEL CONTAINING ACTIVATED CARBON (CONTINUED)

STEPS DATE TIME INITIALS 4.18 Start Dewatering Pump 4.19 Stop Dewatering Pump Volume Water Collected mils COMMENTS:

i f

1 sf L

i L

I I

I i

i f

6 SAMPLE 2

1.

.~

Process Control Program Appendix A Page 6 of 10 11-27-85 VIRGINIA POWER NORTH ANNA POWER STATION UNIT 1 DEWATERING DATA SHEET FOR 24 INCH DIAMETER PRESSURE VESSEL CONTAINING ION EXCHANGE RESINS VESSEL SERIAL NUMBER SHIPPING NUMBER STEPS DATE TIME INITIALS i

4.5 Start Dewatering Pump 4.6 Stop Dewatering Pump J

4.8 Start Dewatering Pump 4.9 Stop Dewatering Pump Volume Water Collected mis

(

4.10 Start Dewatering Pump 4.11 Stop Dewatering Pump Volume Water Collected mis COMMENTS:

i i

i SAMPLE 3

= _ _.

Process Control Program Appendix A Page 7 of 10 11-27-85

-[

VIRGINIA POWER NORTH ANNA POWER STATION UNIT 1 DEWATERING DATA SHEET FOR CHEM-NUCLEAR 14-195 OR SMALLER LINER LINER SERIAL NUMBER SHIPPING NUMBER DEWATERED TO 0.5% / 1.0% (CIRCLE ONE)

STEPS DATE TIME

_I_N_I.T, I ALS 4.5 Start Dewatering Pump 4.6 Stop Dewatering Pump 4.7 Start Dewatering Pump

( -'

4.8 Stop Dewatering Pump 4.11 Start Dewatering Pump 4.12 Stop Dewatering Pump Volume Of Water Collected

~ gal If Necessary 4.14 Start Dewatering Pump 4.15 Stop Dewatering Pump Volume Of Water Collected gal 4.16 Start Dewatering Pump 4.17 Stop Dewatering Pump Volume Of Water Collected gal SAMPLE 4

Process Control Program Appendix A l

Page 8 of 10 11-27-85 7

i STEPS DATE TIME INITIALS 0

4.18 Start Dewatering Pump 4.19 Stop Dewatering Pump 4

I Volume Of Water Collected gal f

COMMENTS:

i i

)

(

4 i

b l

l i

i I

4 SAMPLE 4

I

~: -

. -. :1~

'r, ___. -. -.

a. _.)

l Process Control Program Appendix A

.Page 9 of 10 11-27-85

(

VIRGINIA POWER NORTH ANNA POWER STATION UNIT 1 DEWATERING DATA SHEET FOR CHEM-NUCLEAR 14-195 OR SMALLER LINER CONTAINING ECODEX, POWDEX, OR DIATOMACEOUS EARTH LINER SERIAL NUMBER.

2 SHIPPING NUMBER J

STEPS INCH Hg DATE TIME INITIALS ~

4.7 Start Dewatering 4.8 Close Valve #4

\\

4.9 Close Valve #3 4.10 Close Valve #2 i

(

4.11 Close Valve #1, f

4.13 Start Dewatering Close Valve #4 Close Valve #3 Close Valve #2 l

Close Valve #1

{

I 4.15 Start Dewatering l

Close Valve #4 Close Valv'e #3 1

Close Valve #2 Close Valve il SAMPLE 5

Process Control Progrcm Appendix A Page 10 of 10 11-27-85 BARNWELL WASTE MANAGEMENT FACILITY

.a.

a cENERATOR NAME Operated ty CHEM-NUCLEAR SYSTEMS. INC.

CARRIER AoORE SS ADD *ISS P. O. Box 726, Barnnell, South Carolina 29812 (803) 259 1781 TREPHONE SHIPPING DATE RADIOACTIVE SHIPMENT MANIFEST FORM SHIPMENT TYPE SHIPMENT SURFACE DPOSURE mR/hR CITY STATE SHIPMENT NO.

LINER SERIAL NO CONTACT PHONE m anmeloned tec ga USE THIS NUMBER ON VOLUME ALLOCAit0N NO.

PAGE DRIVER SIGNATURE DATE CHEM NUCLEAR SWTEMS INC.

ALL CONilNUATION PAGES g

P.M 80X 726.OSBORN ROAD BARNWELL. S C. 29812 SHIPMENT Totals m 1of at sNM PnOPER SHIPPWeG MAed & HAZARD CLAS$

e asunsate 16s ISOTOPE CRAMS as nova een EEH csass (PER 49 CF A 872 800 PS "as M g'",

aD "I E Un u 233 l

UN2900_

,,cuct,

ma g,,

R_-*~tme Waternet

.e M-Radioactive Material hssela n o s

""tive Malertal UN291L stoms U 235 Radioactes Malenallow soecific activetv. n o a

""1sve Malertal UN291L

_IQIll R y_h_teve Material n o a -Radoeckve Material UN29 L UN2910 Radioact we Maserial : - -d cuantity. n o s a-tfve Material UN2974 TOTAL PALLET Rhtsve Mater 6at soccLas for a. n o s * "- tme Malertal UN2911 -

WOLUME (CU FT )

RhtNo Walenal. enstruments and articles **%ve Matenal Other (Soec,M ornwASTE FORM CtASS ose CHEMICAL FORM AND gnas PHYsaCAL FORM /

NAME AND%OFCHELATING AGENT (S)

DAO80C SOLIOfFICAlf0N AGENT se WASTE DESCRtPTION USB T*'hhcation is hereby made lo the South Carolana Department of Heahh and Environmental Control thW thes shipmerd eQ ( ) Yes ( ) No THIS VEHICLE 8S CONSIGNED EXCLUSIVE USE. LOAD 4NG AND UNLOADING MUST 8E of low level rasoectme waste has been inspected in accordance adh the requwements of South Carohna Raeoactrue 1213536 01 as ACCOMPLISHED BY CONSIGNOR OR CONSIGNEE OR HIS DESIGNATED AGENT.

Material tatense No. 097 ar. amended, and the Nuclear Regulatory Comrvuss on's Lxense No.

amended. and the effecthe BarrheeN See DesposalCritana wdhen 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to shipment, and further cettefication es s33 SMPORTANY: *Thss is to cartefy shat the above named madenals we property classahed, descrM packagetE marted made that the enspection revealed no nems of non-comphance wdh an oppiscable laws. rules and reguf40ans

  • and labeied, and are en psopor condsson for transportaleon accordinglothe applicatAs regulatsons of the Department of Transportation.

Dale' By:

Tdie and Organsratuhi Telephone f*n (

)

'//////////////////////// cuss use onts //////////////////H///7)

D"'F o nos m.t..M meets c.ns. r-erri.e.,

ur M Se A,r D

a 1,es mat.rm was s,os o.

accor-. -,,.c.r OlSPOSAL SITE COPY H P sneal Daie/ Time soned O Discrepancr.

Locah n Cooe Farm Na CNS-201 Trench No.

(9-83)

Waste Oass. Code Personnel Enposure us assistsvioses on atviess saw fos ratesGout feesfonte Dagg-idle Authonrad Segnature 1

S AMPLE 6

r' FORM HP - 3.2.15 Page 1 of 1 11-27-85 r

INSPECTION RESULTS HEALTH PHYSICS QC INSPECTOR BATCH ID #

SAT UNSAT DATE/ SIGNATURE DATE/ SIGNATURE i

1

(

I t

6 1

I SAMPLE 7

~m

- ~ ~ - * - - - - -..... - -

T Page 8 ATTACHMENT 5 (7/85 - 12/85)

MAJOR CHANGES TO RADIOACTIVE SOLID WASTE TREATMENT SYSTEMS No major changes to the radioactive solid waste treatment systems were made for the time period covered by this report.

i w

Page 9 ATTAClefENT 6 (7/85 - 12/85)

RADI0 ACTIVE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION INOPERABLE No radioactive effluent monitors were declared inoperable, as defined according to the criteria presented in Technical Specification 3.3.3.10.b and 3.3.3.11.b, for the time period covered by this report.

I i

i i^

Page 10 ATTACHMENT 7 (7/85 - 12/85)

UNPLANNED RELEASES No unplanned releases, as defined according to the criteria presented in 10 CFR Part 50.73, occurred during the time period covered by this report.

wm W

Retrieved from "https://kanterella.com/w/index.php?title=ML20215K273&oldid=3975225"