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-NOTICE-

SEMI-ANNUAL REPORT

RADIOACTIVE EFFLUENT RELEASES

JUNE 27, 1990, THROUGH DECEMBER 26, 1990

TABLE OF CONTENTS

PAGEITEM

TITLE PAGE. . . .

TABLE OF CONTENTS .

INTRODUCTION. . . .....

LIQUID EFFLUENT TABLE . . .

. 3

. 4

GASEOUS EFFLUENT TABLE. . . . .

SUMMARY OF RADIOACTIVE SOLID WASTE.

SUMMARY OF CHANGES TO THE OFFSITE DOSE

ASSESSMENT MANUAL. . . . . ..........

. 6 - 8

. 9

SUMMARY OF CHANGES TO THE PROCESS CONTROL PLAN

WITH REVISED PROCEDURES INCLUDED... . . . . . .. 10-48

SUMMARY OF METEOROLOGICAL DATA . . . . . . 49-65

2

INTRODUCTION

This semi-annual report covers the period of June 27, 1990, through December 26, 1990. These dates were chosen so as to match as closely as possible the end of the calendar period with sampling performed under the DAEC Surveillance Testing Program (STP). The dates, therefore, accurately reflect the sampling periods for gaseous effluents and are limited by the quarterly composite sampling dates for Strontium 89 and 90. The next SemiAnnual Report will begin with the last date from this report.

The DAEC resumed normal operations at the end of the 3rd Quarter of 1990 after completion of the scheduled cycle 10/11 refueling outage.

There were no liquid releases from DAEC during the semiannual period covered by this report-. No-changes-were-made-to--the Offsite Dose Assessment Manual (ODAM) during the period covered by this report. Likewise, there were no abnormal occurrences during the semi-annual period that would have required special reporting per the Duane Arnold Energy Center Technical Specifications.

Changes to the Process Control Plan (PRCP) are summarized on page 10 and revised procedures have been included.

3

SEMIANNUAL RADIOACTIVE MATERIAL RELEASE REPORT (1990)

LIQUID EFFLUENT *

Nuclides Released Unit 3rd Quarter 4th Quarter

strontium-89 Ci O.OE+00 O.OE+00 strontium-90 Ci O.OE+00 O.OE+00 cesium-134 Ci O.OE+00 O.OE+00 cesium-137 Ci O.OE+00 O.OE+00 iodine-131 Ci O.OE+00 O.OE+00

cobalt-58 Ci O.OE+OO O.OE+OO cobalt-60 Ci O.OE+OO O.OE+OO iron-55 Ci O.OE+OO O.OE+OO iron-59 Ci O.OE+OO O.OE+OO zinc-65 Ci O.OE+OO O.OE+OO

manganes-e=54Ci O.OE+OO O.OE+O chromium- 51 Ci O.OE+00 O.OE+00

zirconium-niobium-95 Ci O.OE+00 O.OE+00 molybdenum-99 Ci O.OE+00 O.OE+00 technetium-99m Ci O.OE+00 O.OE+00 barium-lanthanum-140 Ci O.OE+00 O.OE+00

cerium-141 Ci O.OE+0 O.OE+00

other (specify) Ci O.OE+00 O.OE+00 Ci O.OE+00 O.OE+00 Ci O.OE+00 O.OE+00 Ci O.OE+00 O.OE+00 Ci O.OE+00 O.OE+00

Total for period (above) Ci O.OE+00 O.OE+00

xenon- 133 Ci O.OE+00 O.OE+00

xenon-135 Ci O.OE+00 O.OE+00

* No liquid release June 27, 1990, through December 26, 1990.

4

SEMIANNUAL RADIOACTIVE MATERIAL RELEASE REPORT (1990)

GASEOUS EFFLUENTS *

Nuclides Released Unit 3rd Quarter 4th Quarter

1. Fission gases

krypton-85 Ci O.OE+00 2.9E-04 krypton-85m Ci O.OE+00 O.OE+00 krypton-87 Ci O.OE+00 O.OE+00 krypton-88 Ci O.OE+00 O.OE+00 xenon-133 Ci 1.3E-06 4.OE-01 xenon-135 Ci 2.4E+00 2.5E+00 xenon-135m Ci 3.OE-01 3.7E+00 xenon-138 Ci O.OE+00 O.OE+00 tritium Ci 2.7E+00 1.7E+00 Total for period Ci 5.4E+00 8.3E+00

2. Iodines

T IT

iodine-131 iodine-133 iodine-135 Total for period

__________________________________ a.

Ci Ci Ci Ci

5. 0E-05 3. 7E-05 3. 8E-06 9. 1E-05

3. 0E-05 4. 5E-05 0. OE+00 7. 5E-05

3. Particulates

* Release period is June 27, 1990, at 1990, at 0800.

0900 through December 26,

5

strontium-89 Ci 3.1E-06 2.1E-06 strontium-90 Ci 7.2E-08 5.1E-09 cesium-134 Ci O.OE+00 O.OE+00 cesium-137 Ci 3.7E-07 O.OE+00 barium-lanthanum-140 Ci O.OE+00 O.OE+00 chromium-51 Ci 3.5E-05 9.5E-05 manganese-54 Ci 6.3E-04 1.2E-04 iron-59 Ci 4.4E-05 O.OE+00 cobalt-58 Ci 1.6E-04 1.7E-05 cobalt-60 Ci 1.6E-03 4.7E-04 Total for period Ci 2.5E-03 7.OE-04

SUMMARY

(June 27, 1990, - December 26, 1990)

SHIPMENTS MADE TO BURIAL FACILITIES

FINAL DISPOSITION TO BARNWELL, SC Waste Type

Spent Resins, Mechanical Aqueous Filter

FINAL DISPOSITION TO RICHLAND, WA Waste Type

Spent Resins Dry Active Waste

No. of Shipments

7

No. of Shipments

2 1

Volume Activity

lM) (Cil 3.70E+01 1.03E+03

Volume Activity

(lM) (Ci 7.69E+00 4.41E+02 2.97E+00 1.13E+01

SHIPMENTS MADE TO PROCESSING FACILITIES

SHIPMENTS FOR PROCESSING AT SCIENTIFIC ECOLOGY GROUP (OAK RIDGE, TN)

No. of Waste Type Shipments

Dry Active Waste 5

SHIPMENTS FOR PROCESSING AT WALTZ MILL (MADISON, PA) No. of Waste Type Shipments

Dry Active Waste 2

Volume li

1.46E+02

Volume l)

7.25E+01

Activity (Ci)

9.85E+00

Activity 1Ci1

1.17E-01

SUMMARY (con't)

(June 27, 1990, - December 26, 1990)

TOTAL SOLID WASTE DISPOSITION

No. of Shipments: Mode of Transportation: Truck (Exclusive Use) Destination: Barnwell, SC

Madison, PA Oak Ridge, TN Richland, WA

No. of Shipments

17

7 2 5 3

Volume nd)

Waste Shipped

Waste Buried *

* Includes waste buried directly by DAEC and waste buried

Waste Classification:

"C" Stable "B" Stable "A" Unstable "A" Stable

2.66E+02

1. 13E+02

Activity (Ci)

1.49E+03

1.48E+03

by processing facilities.

No. of Shipments

1 1 8 7

SUMMARY

(June 27, 1990 - December 26, 1990)

MAJOR NUCLIDE COMPOSITION

NUCLIDE3rd QTR

(Ci)

DA

4th QTR (Ci)

W

TOTAL (Ci)

PERCENT ABUNDANCE

PRINCIPLE NUCLIDES

Co-60 1.09E+00

Fe-55 3.59E+00

Mn-54 3.10E-01

Co-58 9.66E=02

Fe-59 1.17E-01

Ni-63 8.13E-02

NUCLIDES WITH Z>92

TRUs*

Pu-241

Cm-242

ALL OTHERS **

TOTALS

6.50E-05

2. 11E-03

2. 30E-04

4.90E-02

5. 34E+00

3. 17E+00

1.08E+01

9 .27E-01

-2-.-88E=0-1

3.52E-01

2. 44E-01

1. 97E-04

6. 33E-03

6.80E-04

1.43E-01

1.59E+01

4.26E+00

1.44E+01

1.24E+00

-3.85E=0-1

4.69E-01

3.25E-01

2.62E-04

8.44E-03

9. 1OE-04

1.92E-01

2.12E+01

2.OOE+01

6.77E+01

5. 83E+00

-1-.-81-E+00

2. 20E+00

1. 53E+00

1.23E-03

3. 97E-02

4.28E-03

9.02E-01

1. OOE+02

* ALPHA EMITTING TRANSURANICS WITH HALF-LIFE GREATER THAN FIVE (5) YEARS

** Ce-144, Cs-137, Cs-134, Cr-51, Zn-65

7

SUMMARY

(June 27, 1990 - December 26, 1990)

MAJOR NUCLIDE COMPOSITION

SPENT RESINS, MECHANICAL AQUEOUS FILTERS

NUCLIDE3rd QTR

(Ci)4th QTR

(Ci)TOTAL (Ci)

PERCENT ABUNDANCE

PRINCIPLE NUCLIDES

Co-60 2.08E+02

Fe-55 1.63E+02

Cs-137 1.09E+01

Mn-54 --8.45E+0-1

Cs-134 7.37E+00

Co-58 4.02E+01

Cr-51 5.26E+01

Ni-63 4.15E+00

H-3 2.84E-02

C-14 1.10E-01

NUCLIDES WITH Z>92

TRUs* 1.07E-03

ALL OTHERS ** 5.96E+00

TOTALS 5.77E+02

3.26E+02

2. 60E+02

7.26E+00

1-.- 63E+02

4.61E+00

8.0 0E+01

3.07E+01

6.87E+00

2.43E-02

2.42E-01

7. 1OE-04

1.20E+01

8.91E+02

5. 34E+02

4.23E+02

1.82E+01

-2-.48E+02

1.20E+01

1.20E+02

8. 33E+O1

1.10E+01

5.27E-02

3.52E-01

1. 78E-03

1.80E+01

1.47E+03

3. 64E+O1

2.88E+01

1. 24E+00

1-.-69E+0-1

8.17E-01

8. 17E+00

5. 67E+00

7.49E-01

3. 59E-03

2.40E-02

1.21E-04

1.23E+00

1. OOE+02

* ALPHA EMITTING TRANSURANICS WITH HALF-LIFE (5) YEARS AND INCLUDES Pu-241 AND Cm-242

GREATER THAN FIVE

** Ag-110m, Co-57, 1-131, Sr-89, Sr-90, and Fe-59

8

SUMMARY OF CHANGES

TO THE OFFSITE DOSE ASSESSMENT MANUAL (ODAM)

For the period of June 27, 1990, through December 26, 1990, no changes were made to the Offsite Dose Assessment Manual (ODAM).

9

SUMMARY OF CHANGES

TO THE PROCESS CONTROL PLAN (PRCP)

During the period of June 27, 1990, through December 26, 1990, the following changes were made to the existing PRCP's:

PRCP C: "Irradiated Components in Carbon Steel Liners" was revised to require additional quality assurance measures by the processing vendor. Specifically, it requires the vendor to verify materials placed in the burial container as documented on the vendor inventory-sheets-match-t-he-waste-contents- asspelled out on the shipping manifest.

PRCP A, B, C, E, F: All PRCP's listed were revised to require services and material for waste processing, that exceed DOT Type A Quantities, be procured as Quality Level II. These services and material must be in compliance with 10CFR71 and 49CFR for Packaging and Transporting Radioactive Materials.

10

PROCESS CONTROL PROGRAM FOR DEWATERING

WET RADIOACTIVE SOLID WASTE

PRCP-A

Revision 8.

October 23, 1990

Duane Arnold Energy Center

Iowa Electric Light and Power Company

Approved by:

Approved by:

U-,, -.

Radwaste Supervisor

/ - 5 -eduQI ~a)

/1 -9c) Date

/ / 79

DateRadiation Protection S')pervisor

Reviewed by:.

Date

Approved by i-i

WnY Superintendent-Nuclea

1 of 8 11

Date

10/23/90 Rev. 8

:

PRCP-A

Introduction

This Process Control Program describes the dewatering of wet radioactive waste

solids from liquid systems at the Duane Arnold Energy Center and packaging the

waste in high integrity containers (HIC) or steel containers (also referred to

as liners).

Wet wastes are those wastes produced from the liquid radwaste treatment system.

These wastes may typically be described as resins (bead and powdered), filter

material, waste sludges, and filter precoat media. The dewatering process

removes liquid from the waste in a HIC or steel liner to meet the criterion in

10 CFR Sections 61.56 (a)(3) and 61.56 (b)(2) and burial site requirements for

free-standing liquid. Stability for Class A waste is provided by the high

integrity container as authorized by Section 61.56 (b)(1), where required. For

Class B and C waste materials stability will be provided at the Barnwell site

by use of concrete structural overpacks.

Vendor

Westinghouse RS Inc, Formerly Westinghouse Hittman Nuclear and Development

Corporation of Moorestown, New Jersey, is the vendor of the dewatering and

packaging services as well as the RADLOKTh high integrity containers and steel

liners used at the DAEC. Hittman personnel perform the dewatering and packaging

operations described herein.

Dewatering System Description

The Hittman dewatering system employs dewatering equipment to dewater the wet

radioactive waste solids in a HIC or steel liner. The Hittman system consists

of an overflow drum, container level indicators, and interconnecting piping and

valves. Attachment 1 is a diagram of the dewatering system as it is typically

configured. A waste-filled HIC or steel liner is dewatered in the radwaste

processing area using dewatering equipment which is located in the radwaste

building. The dewatering system uses service air supplied by the DAEC and

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PRCP-A

exhausts air into the DAEC Radwaste Ventilation System. Water removed from the

HIC or steel liner, during dewatering, is returned to the DAEC radwaste system

and is treated as liquid radwaste.

The Hittman dewatering system is equipped with instruments to provide

information about the dewatering process. These include mechanical and

electrical liquid level indicators with sensors in the HIC or steel liner,

vacuum receiver tank, and dewatering manifold assembly. Drainable liquid tests

are performed using a vacuum pump and vacuum bottle to verify liquid content

of the HIC or steel liner prior to shipment.

Operation

The radioactive wastes that are dewatered and packaged in a HIC or steel liner

for disposal are normally, but not limited to, wastes from the condensate phase

separators, reactor water cleanup phase separators, waste sludge tanks, or the

spent resin tank.

Wastes from any of the above mentioned systems are piped to a waste holding tank

which is piped directly to the vendor's equipment. The wastes are transferred

to the HIC or steel liner using the vendor's equipment as shown in Attachment

1. A conductivity probe near the top of the HIC or steel liner interior that

actuates an audible alarm and light provides an indication of the waste level

during the HIC or steel liner filling and after dewatering.

After a HIC or steel liner is filled with waste, dewatering is performed by

pulling a suction on the filter assemblies in the HIC or steel liner until loss

of suction occurs. Loss of suction for the rapid dewatering underdrain is

defined as, (1) a vacuum drop of several inches of Hg from one steady vacuum

to another and (2) a loss of continuous water flow in the dewatering hose. Pump

down by suction on the bottom underdrain manifold is continued for a specified

time with the dewatering pump and the vacuum pump.

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PRCP-A

A drainable liquid test is performed by allowing the HIC or steel liner to rest

for a stated time, then siphoning from the bottom underdrain manifold for a

specified time to remove any liquid that has drained into it. The drainable

liquid test is passed if the volume of water removed is less than a volume

demonstrated by the vendor to indicate less than 1% free-standing liquid in the

waste for the HIC being tested, or less than 0.5 percent drainable liquid for

any container being sent to the Nevada burial site.

In the event the waste in the HIC or steel liner does not pass the drainable

liquid test, a cycle of waiting a specified time, operating the dewatering and

vacuum pumps, waiting a specified time, and then performing a drainable liquid

test is repeated until the free-standing liquid criterion is met. Specific

times appropriate for the HIC or steel liner and waste being dewatered have been

determined by the vendor and are stated in the dewatering procedure.

Essential Waste Characteristics and Verification

The requisite characteristics of the radioactive waste addressed by this Process

Control Program are stated in 10 CFR Section 61.56, State of Nevada, State of

Washington, and State of South Carolina License conditions, as appropriate.

The wastes subject to the process control plan are from sources within the DAEC

that are well characterized and generally recognized as meeting the essential

qualities of Section 61.56 (a), and burial site requirements. By knowing the

source and kind of each of the subject wastes, IELP is able to ensure that the

qualities of the wastes continue to meet the requirements of Section 61.56 (a),

and are compatible with the HIC or steel liner itself. In addition, the DAEC's

chemical control program helps prevent listed substances from being admitted

into the waste streams that are deposited into the HIC or steel liner.

10 CFR Section 61.56 (b) includes provisions for stability of radioactive waste

after its disposal. For the wastes covered by this PRCP, Iowa Electric intends

to provide stability when required by burial site licensing condition and Part

4 of 8 14 10/23/90

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PRCP-A

61 by placing the waste in a high integrity container that will be stable after

disposal as authorized in Section 61.56 (b)(1).

Both 10 CFR Sections 61.56 (a)(3) and 61.56 (b)(2) require as little

free-standing and noncorrosive liquid as is reasonably achievable and no more

than 1% of the volume of the waste when the waste is in a disposal container

designed to ensure stability, except for the Nevada site which stipulates less

than 0.5 percent in any container. Iowa Electric intends to accomplish this

by dewatering as described herein and to perform surveillance to assure that

it has been done. For a given type of waste, the operating procedure requires

the vacuum pump and dewatering pump be operated for stated time interval(s).

Dewatering is considered complete when the volume of liquid that can be

suctioned from the HIC or steel liner during a defined time is no greater than

an amount stated in the operating procedure pertaining to that kind of waste.

The conditions stated in the procedure will have been demonstrated by the vendor

of the dewatering service to achieve less than 1% or 0.5 percent free-standing

water in the waste, appropriate to the burial site being sent to.

High Integrity Container

Wastes covered by this PRCP will be packaged in RADLOKT" high integrity

containers or steel liners. The RADLOKTh containers have been certified by the

South Carolina Bureau of Radiological Health for the intended use. Steel liners

will qualify as strong, tight containers as per 49CFR.

Each container will be visually inspected before use for acceptable condition

of:

1. Sealing components,

2. Exterior surface,

3. Dewatering filter elements, and

4. Dewatering verification tube.

After filling and dewatering has been completed, the fill port opening in the

container is closed in accordance with written procedures. The procedure

requires verification that the closure gasket is in place and that the threaded

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PRCP-A

fill port lid is tightened to a specified torque value when required by

procedure.

Quality Assurance

Control of the dewatering and packaging processes is maintained by conducting

these operations according to written procedures addressing container

inspection before filling, dewatering, container closure, and cask loading.

The vendor verifies and documents that key steps have been performed.

Iowa Electric maintains assurance that dewatering and packaging is performed

as intended by separately verifying and documenting that the key steps were

performed. All services and materials procured for processing greater than

Type-A quantities of radioactive waste will be procured as Quality Level II.

All services and material must be procured in compliance with 10CFR71 and 49CFR

for Packaging and Transporting Radioactive Materials.

Iowa Electric's quality assurance program is subject to 10 CFR Part 50, Appendix

B, as applied to dewatering and packaging of radioactive waste.

Administration

The Radiation Protection Department maintains or requires the vendor to maintain

procedures which will ensure that all applicable requirements are met prior to

shipment of radioactive waste. Iowa Electric Light and Power will review

applicable vendor's operating procedures before authorizing the vendor to

dewater radioactive waste. Site specific procedures developed by the vendor

for the DAEC will be reviewed by the Radiation Protection Supervision. Most

recent revisions will be stamped as approved on both working and controlled

vendor procedure copies. Processing procedures internal to the vendor will be

reviewed and approved by the vendor. The Radwaste Group of the Radiation

Protection Department is responsible for ensuring compliance with the PRCP, for

vendor verifications, and for recordkeeping.

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PRCP-A

At least once every 24 months, IELP will audit the radwaste Process Control

Program and operating procedures that implement it (in accordance with Technical

Specification 6.5.2.8.j.) Any change to the Process Control Program will be

made in accordance with Technical Specification 6.15, approved by the Plant

Superintendent-Nuclear, reviewed by the Operations Committee, and submitted to

the NRC in the next Semi-Annual Radioactive Material Release Report after the

change is made.

Training

Before a vendor employee performs a dewatering or packaging procedure that is

subject to this PRCP, they must have received relevant training, and Iowa

Electric must have received documented confirmation of their training along with

a statement of their qualifications.

References

1. DAEC Radwaste Handling Procedures

2. Westinghouse Hittman Nuclear Incorporated procedure STD-P-03-010, "Transfer

and Dewatering Bead Resin in Hittman RADLOK High Integrity Containers with

Single Layer Underdrain Assembly to Less Than 1% Drainable Liquid".

3. Westinghouse Hittman Nuclear Incorporated Procedure STD-PCP-03-040,

"Powdered Resin Transfer and Dewatering procedure using steel containers".

4. Westinghouse Hittman Nuclear Incorporated Procedure STD-P-03-046, Transfer

and Dewatering Ion Exchange Resin and/or Activated Charcoal Filter Media

using the Hittman Rapid Dewatering System.

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PRCP-A

ATTACHMENT 1

8 of 8 18 10/23/90

Rev. 8

-2i I

I I -

PROCESS CONTROL PROGRAM FOR LIQUIDS

AND WET RADIOACTIVE MATERIAL

PRCP-B

Revision 1

October 23, 1990



Approved by: 2 ,L

Radwaste Supervisor

I-'

Approved by:

Reviewed by:

Radiation Protection pervisor Date

DateCha rman, Operations Committee

Approved by: ay* , .Date

1 of 7

19 10/23/90 Rev. 1

/ -6 -F

Date

nSuperintendent-Nuclepr

PRCP-B

Introduction

This Process Control Program (PRCP) describes the solidification, absorption and/or stabilization of liquids and wet waste materials produced at the DAEC. These wastes, regardless of their classification, are processed to assure that the final product is acceptable for transportation and will meet the disposal site license conditions.

Liquid wastes consist of contaminated aqueous solutions, oils, neutralized acids, solvents, sludges, antifreeze and other liquids all of which may be mixed with one another or in pure form. Wet material wastes may consist of mops, rags, anti-contamination clothing, machine turnings and other material or equipment which may contain sufficient residual liquid to warrant special processing.

Vendor

The DAEC's Radwaste Group normally processes all waste; however, a vendor may be utilized to process large volume quantities of liquids or liquids with special containment characteristics. Should a contract vendor be utilized to process and package the waste on site in the future a vendor's topical report shall be required. The vendor's topical report will be reviewed to assure that they are compatible with plant requirements. If the vendor has an approved typical report, it shall be referenced in DAEC's PRCP. If the vendor does not have an approved topical report, the vendor's topical report will be included in the DAEC PRCP by reference and submitted to the NRC for review and approval.

System Description

The liquids and wet waste materials processing systems are composed of an approved absorption or solidifying agent, 17H 55 gallon drums or metal LSA boxes, transfer pumps and mixing equipment if required.

Liquids waste which is to be absorbed will require the use of equipment such as a liquid transfer pump and volume measuring containers. In addition, mixing

2 of 7 20 10/23/90

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PRCP-B

equipment, consisting of a mortar mixing trough and/or a motor driven one yard

concrete mixer, is used to assure that the absorbent is well blended with the

liquid. Absorbed wastes are blended with the absorbent and then transferred

to a shipping container.

Liquid waste which is to be solidified will also require the use of a transfer

pump and a volume measuring device or container. Liquids are mixed with the

solidifying media inside the shipping drum. Aqueous wastes generally do not

require the use of mixing equipment, however, oils and neutralized acids will

require a one-half inch electric motor equipped with a stirring rod. Figure 1

illustrates the various liquid waste package systems typically used at the DAEC.

Operation

Liquids to be absorbed are inspected for the quality of the material prior to

absorption and sampled to determine the radioactivity. An isotopic analysis

is also performed. A 17H 55 gallon shipping drum is prepared by placing a layer

of absorbent in the bottom, then two plastic bag liners and layer of absorbent

in the bottom of the liner. The shipping drum is then positioned inside the

controlled area adjacent to the mortar mixing trough. A measured volume of the

liquid, usually twelve t fifteen gallons, is mixed with an absorbent in either

the concrete mixer or the mortar mixing trough until a reasonably dry mixture

is achieved. The absorbed mixture is then transferred into the bag liner, on

top of the absorbent layer, and topped off with another layer of absorbent.

The layers of dry absorbent on the bottom and top of the absorbed liquids assure

that the container meets the DOT required absorbent ratio. The drum lid is

lightly secured and the drum inverted for the 24 hours and then inspected for

free standing liquid.

Liquid wastes to be solidified are also inspected for quality and sampled for

radioactivity. A 17H 55 gallon shipping drum is placed inside the controlled

area, adjacent to the container of contaminated liquid, and the liquid to be

solidified is pumped into the new drum. The solidifying media is added and the

mixture stirred if necessary. The drum is allowed to stand overnight and

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PRCP-B

inspected 24 hours later for free standing liquid. It is not necessary to

invert the solidified drum because the solidified matrix is heavier than the

liquid hence any free liquid will be forced to the surface.

Wet trash and other material which cannot be dried are packaged in a 55 gallon

drum or a metal LSA box for shipment. The LSA box is prepared by placing

approximately one inch of absorbent and then a plastic liner into the box and

then a one inch layer of absorbent in the liner. The wet trash is then placed

into the box by layering approximately 12" of material and covering with

approximately one inch of absorbent until the waste is about two inches from

the top of the box. The liner is sealed and the box lid secured. A free liquid inspection is performed after 24 hours by removal of the bottom drain plug in the LSA Box. The 55 gallon drum is prepared by placing approximately four inches of absorbent and then two liners into the drum and then about two inches of absorbent into the liner. The wet trash is placed in the drum by layering approximately six inches of material and covering with about two inches of absorbent until the level is two inches below the top of the drum. The liners are sealed and the drum lid secured. The drum is stored upside-down for at least 24 hours and then inspected for free standing liquid.


The requisite characteristics of the radioactive waste addressed by this Process Control Program are stated in 10 CFR Part 61.56.

The wastes subject to the process control program are from sources within the

DAEC that are well characterized and generally recognized as meeting the

essential qualities of Part 61.56(a), other than (a)(3). By knowing the source and kind of each of the subject wastes, IELP is able to ensure that the qualities of the wastes continue to meet the requirements of Part 61.56(a), other than (a)(3), and are compatible with the stabilizing media and the container itself.

10 CFR Part 61.56 (b) includes provisions for stability of Class B and C

radioactive waste after its disposal. Only Class A waste forms are covered by

4 of 7

22 10/23/90 Rev. 1

PRCP-B

this PCP hence Part 61.56(b) is not applicable. 10 CFR Parts 61.56 (a)(3)

require as little free-standing and noncorrosive liquid as is reasonably

achievable, and no more than 1% of the volume. Iowa Electric intends to

accomplish this by the processes as described herein and to perform surveillance

to assure that it has been done. For a given type of waste, the Radwaste

Handling Procedures require an inspection for free liquids 24 hours after

packaging and corrective action as necessary.

Quality Assurance

Control of the absorption and solidification processes is maintained by

conducting these operations according to written procedures addressing

packaging of contaminated liquids and wet or oily trash. Procedures also

identify requirements for container control, handling and inspection, handling

and closure of metal drums, handling and closure of metal LSA boxes, and

requirements for transportation of waste to the various authorized disposal

site(s).

An extensive quality control audit program with appropriate hold and witness

points is included in the Radwaste Handling Procedures.

All services and materials procured for processing greater than Type-A

quantities of radioactive waste will be procured as Quality Level II. All

services and materials must be procured in compliance with 10CFR71 and 49CFR


Administration

The Radiation Protection Department maintains procedures which will ensure that

all applicable requirements are met prior to shipment of radioactive waste.

In the event a vendor's service is required, IELP will review applicable

vendor's operating procedures before authorizing a vendor to process

radioactive waste. The Radwaste Group of the Radiation Protection Department

5 of 7 10/23/90

23 Rev. 1

PRCP-B

is responsible for ensuring compliance with the PCP, Vendor oversight, and for record keeping.

At least once every 24 months, IELP will audit the Radwaste Process Control Program and operating procedures that implement it (in accordance with Technical Specification 6.5.2.8.j.) Any change to the Process Control Program will be made in accordance with Technical Specification 6.15, approved by the Plant Superintendent-Nuclear, reviewed by the Operations Committee, and submitted to the NRC in the next Semi-Annual Radioactive Material Release Report after the change is made.

Training

Before an IELP or a vendor employee performs a packaging procedure that is subject to this PRCP, they must have received relevant training, and Iowa Electric must have documented confirmation of the training.

References: (


6 of 7 24 10/23/90

Rev. 1

PRCP-B

FIGURE 1

2" VOID r~

2" ABSORBENT

6" WASTE

2" ABSORBENT

f - -:- p e a ~~ 6" WASTE .\ ygy \

2* ABSORBENT

4** ABSORBENT

ABSORBED WET WASTE

55 GALLON DRUM

-LINER

I- -

12"

12"

-I

~. - .

* --. .. .

4 -

* - S .*...S~a -. 4 iiV~j, - 4. * .- .. ~ -s *.

* N

* -- I-1" *,* - *..,* LI

'/CIA - D

U

-- 1

2"

ABSORBED WET WASTE

2" VOID

2" ABSORBENT --T

ABSORBED LIQUID

55 GALLON DRUM

SOLIDIFIED LIOUID

FIGURE 1

7 of 7 25 10/23/90

Rev. 1

55 GALLON

DRUM

.

.

I

PROCESS CONTROL PROGRAM FOR PROCESSING

IRRADIATED COMPONENTS IN CARBON STEEL LINERS

PRCP-C

Revision 3

October 23, 1990



Approved by:

Approved by:

L- I

Radwaste Supervi sor

/- C- I

Radiation Protection Super-visor

Reviewed

Chairman, Operations Committee

Approved by:

i /t Superintendent-Nuc ear

//- '- f Date

Date

Date

Date

1 of 7 26 10/23/90

Rev. 3'

PRCP-C

INTRODUCTION

This Process Control Program describes the packing and dewatering of irradiated

components into waste liners from storage in the Spent Fuel and Cask Pools here

at the Duane Arnold Energy Center.

Irradiated components in general describe any item that has been exposed to a

neutron flux. Components typical of this waste stream at DAEC include expended

control rod blades, fission chamber detectors (SRM and IRM) and their associated

dry tubes, local power range monitors (LPRMS) and other irradiated parts.

Depleted neutron sources may also be disposed of using this Process Control

Program provided that they qualify for disposal under the waste classification

requirements of 1OCFR61.

The packaging process describes how irradiated components are to be handled and

packaged in accordance with the applicable burial site criteria and/or

requirements.

The dewatering process removes liquid from the waste in the disposal liner to

meet the criteria set forth in 10CFR61.56 (a) (3), 1OCFR61.56 (b) (2) and

applicable burial site requirements for free standing liquid. Irradiated

components are considered inheritently stable.

VENDOR

WasteChem Corporation of Mahwah, NJ is the vendor for the packaging and

dewatering of irradiated components in carbon steel liners. WasteChem

personnel, assisted by DAEC personnel as required, perform the dewatering and

packaging operation described herein. The cask for transport of the irradiated

components is to be provided by Transnuclear, Incorporated of Hawthorne, NY.

DEWATERING SYSTEM DESCRIPTION

The cask has a drain system used for draining water from the cask after loading

of the waste liner. Cask cavity water is removed by opening the vent port for

2 of 7 27 10/23/90

Rev. 3

PRCP-C

venting and installing the drain connector and a hose for draining. Water

drained from the cask will be directed to the liquid radwaste system for

processing.

After the cask is drained, the vacuum drying system (VDS) is utilized to perform cavity drying. The VDS is utilized to remove residual moisture from the cask

cavity by vacuum drying. After a loaded cask is removed from the cask pool and thoroughly drained, it is connected to the VDS and placed under a vacuum. Any

water which has not drained from the cavity evaporates from the cavity surface

or surface of the irradiated hardware.

The water vapor in the cavity is then condensed by braking the vacuum. The

resulting condensate is drained into a tank which is connected to the cask

drain. Any remaining water vapor is then removed by continuing the vacuum

pumping until a dryness test is successfully completed. Upon completion of

drying, the VDS is used for cask leakage and tightness testing.

The VDS system consists of a 70 CFM vacuum pump, an in-line filter, vacuum

gages, a drain bottle (one gallon capacity) and associated piping, hoses and

valves. The total VOS system is skid mounted to facilitate easy access and

mobility. Dewatering of the liner containing the irradiated waste will be in

accordance with a WasteChem procedure specific to the irradiated component waste stream.

OPERATION

The irradiated component wastes that are dewatered and packaged in a stainless

steel liner for disposal are normally, but not limited to, wastes removed from

inside the reactor pressure vessel or associated components. Wastes from the

above activities are changed out periodically and stored normally in the spent

fuel and/or cask storage pool. When a quantity sufficient to fill a steel liner is accumulated they will be packaged and dewatered using vendor equipment and

procedures.

3 of 7 28 10/23/90

Rev. 3

PRCP-C

After a steel liner is filled with waste, dewatering is performed by pulling a suction on the cask cavity and the surface of the irradiated components until no significant amount of water is collected in the drain bottle. Dryness is then verified by measuring an increase in the internal pressure of the cavity.

ESSENTIAL WASTE CHARACTERISTICS AND VERIFICATION

The requisite characteristics of the radioactive waste addressed by this Process Control Program are stated in 10 CFR Section 61.56 and State license conditions, as appropriate.

The wastes subject to the process control plan are from sources within the DAEC that are well characterized and generally recognized as meeting the essential qualities of 10 CFR Section 61.56 (a), and burial site requirements. By knowing the source and kind of each of the subject wastes, IEL&P is able to ensure that the qualities of the waste continue to meet the requirements of 10 CFR Section 61.56 (a), and are compatible with the steel liner. In addition, the DAEC's Chemical Control Program helps prevent listed hazardous substances from being admitted into the waste streams that are deposited into the steel liner.

10 CFR Section 61.56 (b) includes provisions for stability for radioactive waste after its disposal. The structural stability for irradiated components is provided by the waste form itself since it is a solid monolith.

Both 10 CFR 61.56 (a)(3) and 61.56 (b)(2) requires as little free-standing and noncorrosive liquid as is reasonably achievable and no more than 1% of the volume of the waste in a disposal container designed to ensure stability. Iowa Electric intends to accomplish this by dewatering and drying of the steel liner and cask as described herein and to perform surveillance to assure that it has been done. For a given type of waste, the operating procedure requires the vacuum pump be operated for stated time interval(s) as long as additional water enters the drain bottle. Once no significan amount of water is collected in the drain bottle, a vacuum is pulled three additional times. Finally to test for dryness a pressure reading test is performed. If the pressure increase does

4 of 7 29 10/23/90

Rev. 3

PRCP-C

not exceed an amount stated in the operating procedures the cask and liner is

considered to be dry and to meet free-standing liquid requirements.

PACKAGINGS

Wastes covered by this PRCP will be packaged in carbon steel liners. Containers

will be inspected prior to use to ensure that they are acceptable for use.

QUALITY ASSURANCE

Control of the dewatering and packaging is maintained by conducting these

operations according to written procedures addressing container inspection

before filling, dewatering, container closure, and cask loading. The vendor

verifies and documents that key steps have been performed.

Iowa Electric requires the vendor to specifically verify, by comparison, that

the liner contents documented on pool inventory sheets are the same as the

characterization of contents to be used on the shipping manifest.





All services and material must be procured in compliance with 10CFR71 and 49CFR




ADMINISTRATION




5 of 7 30 10/23/90

Rev. 3

PRCP-C


package and to dewater radioactive waste. Site specific procedures developed

by the vendor for the DAEC will be reviewed by Radiation Protection Supervision.

Most recent revisions will be stamped as approved on both working and controlled

vendor procedure copies. ProCessing procedures internal to the vendor will be

reviewed and approved by the vendor. The Radwaste Group of the Radiation

Protection Department is responsible for ensuring compliance with the PRCP, for

vendor verification, and for recordkeeping.

At least once every 24 months, IEL&P will audit the Radwaste Process Control

Program and Operating Procedures that implement it (in accordance with Technical

Specification 6.5.2.8.j). Any change to the Process Control Program will be




change is made.

TRAINING





REFERENCES

1.0 DAEC Radwaste Handling Procedures.

2.0 Wastechem Procedure No. 0013G, "Procedure for calculating the Radionuclide

contents, concentration and waste classification of liners containing

activated metal components."

3.0 WasteChem Procedure No. 0021F, "Procedure for Processing of Irradiated

Hardware using the WasteChem Underwater Shear/Compactor (USC)".

6 of 7 31 10/23/90

Rev. 3

PRCP-C

4.0 WasteChem Procedure No. 0024F, "Procedure for Processing of Incore

Instrumentation".

5.0 Transnuclear Manual OM-7, "TN-RAM Cask Operations Manual".

6.0 Title 10 of Code of Federal Regulations - Energy.

7.0 Title 49 of Code of Federal Regulations - Transportation

8.0 Iowa Electric's Quality Assurance Program.

9.0 DAEC Technical Specifications

7 of 7 32 10/23/90

Rev. 3

VP


WET RADIOACTIVE SOLID WASTE

IN CARBON STEEL LINERS

PRCP-E

Revision 2

October 23, 1990



(.

Approved by,.

Radwaste Supervisor

Approved by: /A;

Radiation Protection Supervisor

Reviewed by:4,Z ,i d . Chairman, Operations Committee

Approved by: t ( U? -. 6_aI

Superi ntendent-Nucl ear

1 of 8 33

Date

Date

Date

Date

C

10/23/90 Rev. 2

PRCP-E

Introduction

This Process Control Program describes the dewatering of wet radioactive waste

solids from liquid systems at the Duane Arnold Energy Center and packaging the

waste in a carbon steel liner.

Wet wastes are those wastes produced from the liquid radwaste treatment system.

These wastes may typically be described as resins (bead and powdered), charcoal,

filter media, waste sludges, and filter precoat media. The wastes included in

this program are specifically those containing nuclides with a radioactive

half-life greater than 5 years and a concentration in the resin of less than

1Ci/m 3 . The dewatering process removes liquid from the waste in a carbon steel

liner to meet the criterion in 10 CFR Sections 61.56 (a)(3) and 61.56 (b)(2)

for free-standing liquid.

Vendor

Westinghouse Hittman Nuclear and Development Corporation of Columbia, Maryland,

is the vendor of the dewatering and packaging services and of the carbon steel

liners used at the DAEC. Hittman personnel perform the dewatering and packaging

operations described herein.

Dewatering System Description

The Hittman dewatering system employs dewatering equipment to dewater the wet

radioactive waste solids in a carbon steel liner. The Hittman system consists

of an overflow drum, container level indicators, and interconnecting piping and

valves. Figure 1 is a diagram of the dewatering system as it is typically

configured. A waste-filled carbon steel liner is dewatered in the radwaste

building loading bay using dewatering equipment which is located in the radwaste

building. The dewatering system uses service air supplied by the DAEC and

exhausts air into the DAEC Radwaste Ventilation System. Water removed from the

carbon steel liner, during dewatering, is returned to the DAEC radwaste system

and is treated as liquid radwaste.

2 of 8 34 10/23/90

Rev. 2

PRCP-E

The Hittman dewatering system is equipped with instruments to provide

information about the dewatering process. These include mechanical and

electrical liquid level indicators with sensors in the carbon steel liner and

vacuum receiver tank. Vacuum gauges indicate amount of vacuum in the vacuum

receiver tank and carbon steel liner. Drainable liquid tests are performed

using a vacuum pump and vacuum bottle (VB-1 in Figure 1.) to verify liquid

content of the carbon steel liner prior to shipment.

Operation

The radioactive wastes that are dewatered and packaged in a carbon steel liner

for disposal are normally, but not limited to, wastes from the condensate phase

separators, waste sludge tank, spent resin tank, portable demineralizers and

filters, or concentrated waste tank.

Wastes from any of the above mentioned systems are piped to a waste holding tank which is piped directly to the vendor's equipment. The wastes are transferred

to the carbon steel liner using the vendor's equipment as shown in Figure 1.

Conductivity probes near the top of the carbon steel liner interior that actuate

an audible alarm and light provide an indication of the waste level during the

carbon steel liner filling and after dewatering.

After a carbon steel liner is filled with waste, dewatering is performed by

pulling a suction on an underdrain manifold in the carbon steel liner until loss

of suction occurs. Loss of suction is indicated by a decrease in vacuum in the

vacuum receiver tank to 10 inches Hg or less on the vacuum gauge. Pump down

by suction on the bottom underdrain manifold is continued for a specified time

with the dewatering pump and the vacuum pump.

A drainable liquid test is performed by allowing the carbon steel liner to rest

for a stated time, then siphoning from the bottom underdrain manifold for a

specified time to remove any liquid that.has drained into it. The drainable

liquid test is passed if the volume of water removed is less than a volume

3 of 8 35 10/23/90

Rev. 2

PRCP-E

demonstrated by the vendor to indicate less than 1% free-standing liquid in the

waste for the carbon steel liner being tested.

In the event the waste in the carbon steel liner does not pass the drainable

liquid test, a cycle of waiting a specified time, operating the dewatering and

vacuum pumps, waiting a specified time, and then performing a drainable liquid

test is repeated until the free-standing liquid criterion is met. Specific

times appropriate for the carbon steel liner and waste being dewatered have been

determined by the vendor and are stated



Control Program are stated in 10 CFR Section 61.56.



qualities of Section 61.56 (a), other than (a)(3). By knowing the source and

kind of each of the subject wastes, IELP is able to ensure that the qualities

of the wastes continue to meet the requirements of Section 61.56 (a), other than

(a)(3), and are compatible with the carbon steel liner itself. In addition,

the DAEC's chemical control program helps prevent listed substances from being

admitted into the waste streams that are deposited into the carbon steel liner.

Both 10 CFR Sections 61.56 (a)(3) and 61.56 (b)(2) require as little


than 1% of the volume of the waste when the waste is in a disposal container

designed to ensure stability. Iowa Electric intends to accomplish this by

dewatering as described herein and to perform surveillance to assure that it

has been done. For a given type of waste, the operating procedure requires the

vacuum pump be operated for stated time interval(s). Dewatering is considered

complete when the volume of liquid that can be suctioned from the carbon steel

liner during a defined time is no greater than an amount stated in the operating

procedure pertaining to that kind of waste. The conditions stated in the

4 of 8 36 10/23/90

Rev. 2

PRCP-E

procedure will have been demonstrated by the vendor of the dewatering service to achieve less than 1% free-standing water in the waste.

Carbon Steel Liner

Wastes covered by this PRCP will be packaged in carbon steel liners.

Each container will be visually inspected before use for acceptable condition of:



3. Dewatering tubes, and

4. Dewatering verification tube.

After filling and dewatering has been completed, the fill port assembly is

removed from the container and the container is closed in accordance with

written procedures. The procedure requires verification that the closure gasket is in place.

Quality Assurance

Control of the dewatering and packaging processes is maintained by conducting

these operations according to written procedures addressing carbon steel liner inspection before filling, dewatering, carbon steel liner closure, and cask loading. The vendor verifies and documents that key steps have been performed.


as intended by separately verifying and documenting that the key steps were performed. All services and materials procured for processing greater than Type-A quantities of radioactive waste will be procured as Quality Level II.

All services and materials must be procured in compliance with 10CFR71 and 49CFR for Packaging and Transporting Radioactive Materials.

5 of 8

37 10/23/90 Rev. 2

PRCP-E

Iowa Electric's quality assurance program is subject to 10 CFR Part 50, Appendix B, as applied to dewatering and packaging of radioactive waste.

Administration



shipment of radioactive waste. IELP will review applicable vendor's operating

procedures before authorizing the vendor to dewater radioactive waste. Site

specific procedures developed by the vendor for the DAEC will be reviewed by

Radiation Protection Supervision. Most recent revisions will be stamped as

approved on both working and controlled vendor procedure copies. The Radwaste

Group of the Radiation Protection Department is responsible for ensuring

compliance with the PRCP, for Vendor oversight, and for recordkeeping.

At least once every 24 months, IELP will audit the radwaste Process Control

Program and operating procedures that implement it (in accordance with Technical

Specification 6.5.2.8.j.) Any change to the Process Control Program will be




change is made.

Training





6 of 8

38 10/23/90 Rev. 2

PRCP-E

References C


2. Westinghouse Hittman Nuclear Incorporated procedure STD-P-04-002, "PCP form

Dewatering Ion Exchange Resin and Activated Charcoal Filter Media to 1/2

Percent Drainable Liquid".

3. Westinghouse Hittman Nuclear Incorporated procedure STD-PCP-03-001,

"Powdered Resin Transfer and Dewatering Using Steel Container".

(

(7.7 of 8

3910/23/90 Rev. 2

Waste Transfer Line i-.

Fill Valve Iquid level indicator, LL-1

; Level-indicator, RL-I

,* Vacuum Gauge

IVent to Radwaste Ventilation System Pumn

oY-1 vacuum Vent to Radwaste Ventilation System 00 BttleDAEC Service air V nt to -

Ven TI Radwaste > Vent la on- - co nventilation

SteeSystem M vent To Radwaste

Ventilation connenli c

SystemS e

Dewaerin

:Carbo~ Vacuum Dwtrn vertlow I Steel, Reever *Dwtrn

Drum Lhner ;:ln Overfow lnk r collection

Drum R-1 Drum

Radwaste floor drain system Radwaste floor drain system (DO C)

Wo Figure 1. Dewaterinq Process, Typical Configuration

C) .


MECHANICAL CARTRIDGE

AND BAG FILTERS

IN HIGH INTEGRITY CONTAINERS

OR CARBON STEEL LINERS

PRCP-F

Revision 1

October 23, 1990



Approved by: 7 Qi, /y1,A <VTRadwaste Supervisor

/Approved by:

Radiation Protection S pervisor

Reviewed by:A 2Chafmian, Operations Committee

//-H-Fc Date

Date

Date

Date

Approved by:.

1 of 8 41 10/23/90

Rev. 1

,

PRCP-F

Introduction

This Process Control Program describes the packaging and dewatering of wet mechanical cartridge and bag filters from various liquid systems at Duane Arnold Energy Center and packaging the waste in high integrity containers or carbon steel liners.

Wet mechanical cartridge and bag filters wastes may typically be described as cartridge filters that are used for filtering water in the CRD Repair Room ultrasonic sink, torus desludging project and other systems that may produce cartridge and/or bag filters.

The packaging process describes how mechanical filters are to be handled and packaged in accordance with Barnwell, South Carolina burial site requirements.

The dewatering process removes liquid from the waste in a HIC or steel liner to meet the criterion in 10CFR Section 61.56 (a) (3) and 61.56 (b)(2) and burial site requirements for free standing liquid. Stability is provided by the high integrity container as authorized by Section 61.56 (b)(1), where required.

VENDOR

Westinghouse-Hittman Nuclear Incorporated of Moorestown, New Jersey, is the vendor of the dewatering and packaging services as well as the RADLOKR high integrity containers and steel liners used at DAEC. Hittman personnel, assisted by DAEC personnel as required, perform the dewatering and packaging operations described herein.

DEWATERING SYSTEM DESCRIPTION

The Hittman dewatering system employs dewatering equipment to dewater the wet mechanical waste filters in a HIC or steel liner. The Hittman system consists of a vacuum pump with minimum suction of 25 inches of mercury and 1/4 inch hose, Vacuum Receiver Tank (VRT) with hoses and fittings, filter handling/dewatering

2 of 8 42 10/23/90

Rev. 1

PRCP-F

tools including dewatering wand, bag knife, filter tongs, filter hook,

dewatering pump skid with 1 - 1/2 " diaphragm pump, interconnecting hoses and

quick disconnect fittings as required, hoses with fittings as required to

connect from service air system to the dewatering pump, and dewatering

collection drum marked at 5 gallon intervals.

The Hittman dewatering system used for a mix of cartridge filters, filter bags,

and other mechanical filters from various systems consists of equipment to

provide dewatering of a HIC or steel liner adequate to meet requirements for

drainable liquids at Barnwell, S.C. and Beatty, Nevada. The Hittman dewatering

system for mechanical filters is also equipped to dewater plastic bags

containing filters prior to their placement in a HIC or steel liner.

Dewatering of a HIC or steel liner containing mechanical filters will be in

accordance with a Hittman procedure specific to a mechanical filter waste

stream.

Upon completion of dewatering operations according to Hittman procedures,

absorbent material is released into the bottom of the HIC or steel liner to

absorb any remaining drainable liquid. Attachment No. 1 is a diagram of the

absorbent release mechanism used in a HIC or steel liner.

OPERATION

The mechanical filter wastes that are dewatered and packaged in a HIC or steel

liner for disposal are normally, but not limited to, wastes from Torus

desuldging and CRD Repair Room.

Wastes from the above activities are changed out periodically and stored,

usually in the lanes area in the Radwaste Building basement. When a quantity

sufficient to fill a HIC or steel liner is accumulated, they will then be

packaged and dewatered using the vendors equipment and procedure.

3 of 8 43 10/23/90

Rev. 1

PRCP-F

After a HIC or steel liner is filled with waste, dewatering is performed by

pulling a suction on an underdrain filter in the HIC or steel liner until loss

of suction occurs. After loss of continuous liquid flow, dewatering continues

for one (1) hour. Volumes of water are recorded in the collection drum at 15

minute intervals during the dewatering.

When the one (1) hour dewatering period has been completed, report dewatering

data to Hittman office for guidance/confirmation of acceptance. When acceptance

has been confirmed, the absorbent material is released into the area at the

bottom of the HIC or steel liner where minuscule quantities of drainable liquid

could have accumulated. The HIC or steel liner manway lids are closed as per

Hittman procedures. The area is cleaned up, decontaminated and equipment

disassembly is completed.

ESSENTIAL WASTE CHARACTERISTICS AND VERIFICATION


Control Program are stated in 10 CFR Section 61.56, State of Nevada and the

State of South Carolina license conditions, as appropriate.



qualities of 10 CFR Section 61.56 (a), and burial site requirements. By knowing

the source and kind of each of the subject wastes, IEL&P is able to ensure that

the qualities of the waste continue to meet the requirements of 10 CFR Section

61.56 (a), and are compatible with the HIC or steel liner. In addition, the

DAEC's Chemical Control Program helps prevent listed substances from being

admitted into the waste streams that are deposited into the HIC or steel liner.

10 CFR Section 61.56 (b) includes provisions for stability for radioactive waste

after its disposal. For the wastes covered by this PRCP, Iowa Electric Light

intends to provide stability when required by burial site licensing conditions

and Part 61 by placing the waste in a high integrity container that will be

stable after disposal as authorized in Section 61.56 (b)(1).

4 of 8 44 10/23/90

Rev. 1

PRCP-F

Both 10 CFR Sections 61.56 (a)(3) and 61.56 (b)(2) requires as little


than 1% of the volume of the waste is in a disposal container designed to ensure

stability, except for the Nevada site which stipulates less than 0.5 percent

in any container. Iowa Electric intends to accomplish this by dewatering as

described herein and to perform surveillance to assure that it has been done.

For a given type of waste, the operating procedure requires the vacuum pump and

dewatering pump be operated for stated time interval(s). Dewatering is

considered complete when the volume of liquid that can be suctioned from the

HIC or steel liner during a defined time is no greater than an amount stated

in the operating procedures pertaining to that kind of waste. The conditions

stated in the procedure will have been demonstrated by the vendor of the

dewatering service to achieve less than 1% or 0.5 percent free-standing water

in the waste, appropriate to the burial site being sent to.

PACKAGINGS

Wastes covered by this PRCP will be packaged in RADLOK high integrity containers

or steel liners. The RADLOK containers have been certified by the South

Carolina Bureau of Radiological Health for the intended use. Steel liners will

qualify as strong, tight containers as per 49CFR.

Each container will be visually inspected before use for acceptable condition

of:



3. Dewatering filter elements, and

4. Dewatering verification tube or equivalent.

5 of 8 45 10/23/90

Rev. 1

PRCP-F

After filling and dewatering has been completed, the fill port opening in the

container is closed in accordance with written procedures. The procedure

requires verification that the closure gasket is in place and that the threaded

fill port lid is tightened to a specified torque value when required by

procedure.

QUALITY ASSURANCE

Control of the dewatering and packaging is maintained by conducting these

operations according to written procedures addressing container inspection

before filling, dewatering, container closure, and cask loading. The vendor

verifies and documents that key steps have been performed.





All services and materials must be procured in compliance with 1OCFR71 and 49CFR




ADMINISTRATION





dewater radioactive waste. Site specific procedures developed by the vendor

for the DAEC will be reviewed by Radiation Protection Supervision. Most recent

revisions will be stamped as approved on both working and controlled vendor

procedure copies. Processing procedures. internal to the vendor will be reviewed

and approved by the vendor. The Radwaste Group of the Radiation Protection

6 of 8 46 10/23/90

Rev. 1

PRCP-F

Department is responsible for ensuring compliance with the PRCP, for vendor

verification, and for recordkeeping.

At least once every 24 months, IEL&P will audit the Radwaste Process Control

Program and Operating Procedures that implement it (in accordance with Technical

Specification 6.5.2.8.j). Any change to the Process Control Program will be




change is made.

TRAINING





REFERENCES

1. DAEC Radwaste Handling Procedures.

2. Westinghouse-Hittman Nuclear Incorporated Procedure F430-P-010, Revision

0, "Procedure for Torus Cleaning, Filter Packaging and Dewatering".

7 of 8 47 10/23/90

Rev. 1

C

(

PRCP-F

ATTACHMENT 1

.- FILTERS ~

RAPID DEUATERING UNOERDRAIN FILTER

CORD SLEEVE

ABSORBENT RELEASE CORD

ADHESIVE

FILTERS

PERFORATED CORE

HOLE COVER (ADHERE TO CORE INSIDE WALL)

STIC GRID

- ABSORBENT -BARRIER

TADE

ARSORBENT /~* //

1117/' .//

,~x ~' / /

8-30TTOM OF RADLOK

8 of 8 48 10/23/90

Rev. 1

SUMMARY OF METEOROLOGICAL DATA

The following pages are a summation of meteorological data accumulated during the calendar year 1990 by the MIDAS System at the Duane Arnold Energy Center (DAEC). Each table includes wind speed, wind direction, and stability class at the specified sensor height (33' or 156'). A summary table of all stability classes at each height is also included.

Data recovery for the year was satisfactory per the Regulatory Guide 1.23 standard of 90%. For atmospheric stability, wind speed, and wind direction recovery was 94.3% at 33 feet and 94.2% at 156 feet.

49

SITE: DUANE ARNOLD

HOURS AT EACH WIND SPEED AND DIRECTION

WOD OF RECORD = 90010101-90123124

STABILITY CLASS: A DT/DZ

ELEVATION: SPEED:WS33 DIRECTION:WD33 LAPSE:DEL T

WIND SPEED(MPH)

WIND DIRECTION

N

NNE

NE

ENE

E

ESE

SE

SSE

S

SSW

SW

WSW

W

WNW

NW

NNW

1-3 4-7 8-12 13-18 19-24

8 26 9 2 1

12 35 19 1 0

10 20 12 1 0

5 8 1 1 0 4 14 2 2 0

5 26 3 2 0

4 19 14 2 0

1 23 22 0 0

1 5 33 9 3

2 3 14 14 6

3 6 15 17 7

2 6 14 8 1

1 6 8 7 0

3 3 8 9 6 3 3 29 19 17

1 8 9 12 0

L 65 211 212 106 41 4 642

PERIODS OF CALM(HOURS): 127

VARIABLE DIRECTION 0

HOURS OF MISSING DATA: 496

ENTER: [RETURN] CONTINUE, [SO] START OVER, [EX] TO EXIT

50

>24

0

0

0

0

0

0 0

0 0 0 1 1 0

2

0

0

TOTAL

46

67

43

15

22 36

40

47 51

39 49 33

22 31 71

30

02/22/91 10:48

SITE: DUANE ARNOLD


M OD OF RECORD = 90010101-90123124

STABILITY CLASS: B DT/DZ


WIND SPEED(MPH)

WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL

N 0 2 3 0 0 0 5 NNE 0 1 2 1 0 0 4

NE 0 3 1 0 0 0 4

ENE 0 0 2 0 0 0 2

E 1 2 2 2 0 0 7

ESE 0 0 2 1 0 0 3

SE 1 4 5 0 0 0 10

SSE 0 1 6 0 0 0 7

S 1 3 6 8 1 0 19

SSW 0 0 0 4 0 1 5

SW 0 0 3 2 3 1 9 WSW 0 3 5 1 0 0 9 W 1 2 2 4 2 0 11

WNW 0 0 2 0 2 2 6

NW 0 5 11 10 1 0 27

NNW 0 2 5 5 2 0 14

L 4 28 57 38 11 4 142




ENTER: (RETURN] CONTINUE, [SO] START OVER, [EX] TO EXIT

51

02/22/91 10:39

SITE: DUANE ARNOLD


M OD OF RECORD = 90010101-90123124

STABILITY CLASS: C DT/DZ


WIND SPEED(MPH)

1-3 4-7 8-12 13-18 19-24 >24 TOTAL

1 1 5 1 0 0 8

0 2 2 2 0 0 6 0 0 1 0 0 0 1

0 2 1 0 0 0 3 0 1 0 0 0 0 1 1 2 3 0 0 0 6

0 2 3 0 0 0 5 0 5 6 0 0 0 11

0 1 9 5 0 0 15

0 2 2 3 3 1 11

0 3 9 4 1 1 18

1 3 6 0 1 0 11

0 2 3 1 1 1 8

1 3 4 4 3 4 19

0 3 17 9 1 0 30

0 2 11 11 0 0 24

LL 4 34 82 40 10 7 177




ENTER: [RETURN] CONTINUE, (SO] START OVER, [EX] TO EXIT

52

ND

TIONWI

DIREC

N NNE NE ENE E

ESE SE

SSE S SSW SW

WSW W WNW NW NNW

02/22/91 10:50

SITE: DUANE ARNOLD r

02/22/91 10:51


W OD OF RECORD = 90010101-90123124

STABILITY CLASS: D DT/DZ


WIND SPEED(MPH)

WIND1

1 1

1

1

1 1

1 1

1 1

DIRECTION

N

NNE NE

ENE

E

ESE SE

SSE

S SSW SW

WSW W WNW

NW NNW

3 4-7 8-12 13-18 19-24

9 24 33 8 1

1 31 36 16 0

3 73 56 3 0

8 41 46 13 0

5 37 32 15 0

2 49 29 1 0

4 77 43 4 0

7 104 98 6 0

8 81 164 58 4

1 36 58 36 9

0 23 46 20 14

2 36 18 12 5

6 22 23 24 8

9 24 47 35 25

4 39 94 79 37

3 35 153 80 17

>24

0 0

0

0 0

0 0 0 2

1 2

1 0

5 0

0

TOTAL

75

94

145 109 101 92

138 225 327 151 115 86 86

145 253 288

iL 172 732 976 410 120 11 2430





53

SITE:, DUANE ARNOLD


OD OF RECORD = 90010101-90123124

STABILITY CLASS: E DT/DZ


WIND SPEED(MPH)

WIND

DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL

N 17 53 25 15 4 0 115

NNE 34 64 53 29 1 0 181

NE 34 62 48 16 0 0 161

ENE 29 63 46 5 0 0 143

E 39 69 22 5 0 0 137

ESE 34 107 48 3 0 0 192

SE 50 208 66 4 0 0 331

SSE 87 255 138 9 0 0 490

S 76 282 241 45 1 0 645

SSW 48 112 83 28 0 1 273

SW 34 60 29 11 3 0 137

WSW 24 43 16 14 5 0 102

W 22 34 25 15 4 0 101

WNW 12 53 49 24 13 5 156

NW 7 81 97 24 23 4 237

NNW 18 45 94 35 4 1 197

L 565 1591 1080 282 58 11 3598

-w-------------------------------------------------------PERIODS OF CALM(HOURS): 127




54

02/22/91 10:41

SITE: DUANE ARNOLD


M OD OF RECORD = 90010101-90123124

STABILITY CLASS: F DT/DZ


WIND DIRECTION

N

NNE NE ENE

E ESE

SE SSE

S SSW SW WSW

W

WNW NW

NNW

WIND SPEED(MPH)

1-3 4-7 8-12 13-18 19-24

5 3 0 3 3 13 13 3 1 0

10 23 0 0 0

11 3 0 1 0

18 5 1 0 0

18 1 4 1 0

33 14 1 0 0

55 24 3 0 0

73 49 3 0 0

49 31 5 0 0

23 16 1 0 0

14 18 2 0 0

13 13 8 0 0

8 8 6 0 0

11 9 3 0 0 5 1 2 1 0

L 359 231 42 7 3 0 665





55

>24

0

0 0

0 0 0

0

0

0 0

0

0 0

0

0 0

TOTAL

14

31

33 16

25 26

50 86

128 90 42

35

34 22

23 10

02/22/91 10:53

SITE: DUANE ARNOLD

HOURS AT EACH WIND SPEED AND DIRECTION M OD OF RECORD = 90010101-90123124

STABILITY CLASS: G DT/DZ


WIND

DIRECTION

N NNE NE

ENE E

ESE SE SSE

S SSW

SW WSW

W

WNW NW

NNW

WIND SPEED(MPH)

1-3 4-7 8-12 13-18 19-24

3 1 0 0 0 10 8 0 0 0

29 16 0 0 0

35 4 0 0 0

22 0 0 0 1

18 1 0 0 0

26 0 0 0 0

46 4 0 0 0

72 8 0 0 0

73 7 2 0 0

66 8 0 0 0

27 6 0 0 0

16 4 0 1 0

7 3 0 0 0 4 2 0 0 0 1 0 0 0 0

L 455 72 2 1 1 0 610




ENTER: [RETURN] CONTINUE, (SO) START OVER, (EX] TO EXIT

56

>24

0 0 0

0 0

0 0 0 0

0

0

0

0 0

0

TOTAL

4 18 48

41 34

29

36 70

91 87

78 36 21

10 6

0 1

02/22/91 10:42

SITE: DUANE ARNOLD

W HOURS AT EACH WIND SPEED AND DIRECTION MOD OF RECORD = 90010101-90123124

STABILITY CLASS: ALL DT/DZ


---------------------------------------------------------------WIND SPEED(MPH)

WIND

DIRECTION

N

NNE NE

ENE

E

ESE

SE SSE

S SSW

SW WSW

W

WNW NW

NNW

1-3 4-7 8-12 13-18 19-24

43

80 96

88

99

88

128 206 241 183 136 80

59 40

29

28

110 154 197 121 128 186 324 416 429 191 116 115 83 94

142 93

75 115 118 96

59 89

132 273 456 164 103 61

69 116 251 274

29

50

20 20

24

8 10

15 125 85 54 35

52

72 141 144

9

1

0 0

1

0

0 0

9 18 28 12 15

49 79 23

>24 TOTAL

0

0

0 0

0

0

0 0

2 4 5 2

1 18 4 1

267 401 435 329 327 384 610 936

1276 656 448 312 283 389 647 564

L 1624 2899 2451 884 244 37 8264

-----------------------------------------------------------------





57

02/22/91 10:43

SITE: DUANE ARNOLD

- HOURS AT EACH WIND SPEED AND DIRECTION AM OD OF RECORD = 90010101-90123124

STABILITY CLASS: A DT/DZ


---------------------------------------------------------------

WIND SPEED(MPH)

WIND

DIRECTION

N

NNE

NE

ENE

E

ESE

SE

SSE

S

SSW

SW

WSW

W

WNW

NW

NNW

1-3 4-7 8-12 13-18 19-24 >24 TOTAL

1 22 14 4 2 0 43

2 27 25 10 0 0 64

1 15 23 5 0 0 44

1 8 7 0 0 0 16

0 6 10 0 0 0 16

0 12 20 1 0 0 33

0 3 27 12 0 0 42

0 8 13 22 1 0 44

1 3 11 20 2 0 37

1 0 7 21 8 0 37 0 3 15 15 14 4 51 3 6 8 10 10 2 39 2 4 6 5 1 0 18

0 5 6 4 6 3 26

3 4 22 24 20 7 80 3 10 8 12 6 1 40

L 18 136 222 165 70 17 630 -----------------------------------------------------------------




ENTER: [RETURN] CONTINUE, (SO] START OVER, (EX] TO EXIT

58

02/22/91 10:57

SITE: DUANE ARNOLD

W HOURS AT EACH WIND SPEED AND DIRECTION W OD OF RECORD = 90010101-90123124

STABILITY CLASS: B DT/DZ


WIND

DIRECTION

N

NNE

NE

ENE E ESE SE SSE S SSW SW WSW W WNW NW NNW

WIND SPEED(MPH)

1-3 4-7 8-12 13-18

1 2 4 1 0 0 0 3 0 3 2 0

1 1 0 0 0 0 1 0 0 0 2 0

0 2 4 4 0 1 5 6 0 1 3 9 0 0 3 2 1 1 3 4 1 0 3 1 0 2 2 1 0 0 4 0

0 1 4 14 0 3 5 9

L 4 17 45 54 14 8 142

PERIODS OF CALM(HOURS): 73 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 505


59

19-24

0 0

0

0 0 0 0 0 2 2

0

1 2 1 2 4

>24

0

0

0 0 0 0 0 0 0 1 3

0 0 3 1

0

TOTAL

8 3

5 2

1 2

10 12 15 8

12 6

7 8

22

21

02/22/91 10:58

SI-TE: DUANE ARNOLD


M OD OF RECORD = 90010101-90123124

STABILITY CLASS: C DT/DZ


WIND SPEED(MPH)

WIND

DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL

N 0 4 5 1 1 0 11

NNE 0 1 4 3 0 0 8

NE 0 1 0 0 0 0 1

ENE 0 0 0 0 0 0 0

E 0 2 0 0 0 0 2

ESE 0 1 1 0 0 0 2

SE 0 1 5 3 0 0 9

SSE 0 3 3 5 0 0 11

S 0 2 1 10 1 0 14

SSW 0 1 3 2 0 5 11

SW 1 1 6 6 4 1 19

WSW 0 1 3 1 1 0 6

W 1 3 2 0 1 0 7 WNW 0 4 3 8 1 4 20

NW 0 3 10 11 5 3 32

NNW 0 0 5 13 3 0 21

L 2 28 51 63 17 13 174

----------------------------------------------





60

I

02/22/91 10:58

SITE: DUANE ARNOLD


W OD OF RECORD = 90010101-90123124

STABILITY CLASS: D DT/DZ


WIND SPEED(MPH)

WIND DIRECTION

N

NNE

NE

ENE

E

ESE

SE SSE

S SSW SW

WSW W WNW NW

NNW

1-3 4-7 8-12 13-18

8 18 39 24

8 29 33 33

4 45 44 18

5 49 41 20

3 37 22 26

9 26 47 7

7 38 75 32

6 42 111 72

10 37 105 112

9 21 61 41

13 20 31 39

6 25 21 9

4 22 23 8

5 16 50 37

16 25 70 101

9 20 110 119

19-24

8

2

0 6 6

0

5 12

19 18

12

9 10

20 54

26

>24 TOTAL

7 104

0 105

0 111

0 122

0 94

0 89

0 158

0 244

1 290

4 156

7 126

4 75

5 72

17 145

22 288 3 287

L 122 470 883 698 207 70 2466

1w ---------------------------------------------------PERIODS OF CALM(HOURS): 73




61

02/22/91 10:59

SITE:.DUANE ARNOLD


M OD OF RECORD = 90010101-90123124

STABILITY CLASS: E DT/DZ


WIND

DIRECTION

N NNE

NE ENE

E ESE

SE

SSE

S SSW

SW WSW

W WNW NW

NNW

WIND SPEED(MPH)

1-3 4-7 8-12 13-18 19-24

8 28 50 42

9 37 71 59

7 28 53 27

7 41 46 32

9 50 64 12

6 43 94 33

11 54 212 78

17 71 271 173

12 61 204 182

14 53 117 78

14 59 72 33

11 43 25 13

9 26 33 15

4 18 52 46

6 38 95 88 16 25 74 68

7

2 1 5

2

1 6

18

19

14 12

8 3

19 24

7

L 160 675 1533 979 148 58 3584

I& ---------------------------------------------------PERIODS OF CALM(HOURS): 73




62

>24

2 0

0 0 0

0

0

0

2 1

4 4

8 15

21 1

TOTAL

137 178 117 132 137 177 365 552 492 282 197 104 95

155 272 192

02/22/91 10:59

SrTE:,.DUANE ARNOLD


WOD OF RECORD = 90010101-90123124

STABILITY CLASS: F DT/DZ


---------------------------------------------------------------WIND SPEED(MPH)

WIND DIRECTION

N

NNE

NE

ENE

E

ESE SE

SSE S SSW SW

WSW

W WNW

NW

NNW

1-3 4-7 8-12 13-18 19-24 >24 TOTAL

2 9 1 3 4 0 19

4 10 9 2 0 0 25

1 9 14 1 0 0 26

2 7 4 1 0 0 14

2 8 7 2 0 0 19

2 5 7 2 1 0 18

4 17 24 1 0 0 47

4 31 27 8 0 0 70

10 32 37 7 0 0 86

3 34 20 8 0 0 66

4 26 31 2 0 0 63

9 27 13 2 0 0 51

4 20 14 5 0 0 43

6 18 25 6 1 0 56

7 8 13 2 0 0 30

3 6 6 5 0 0 20

L 67 267 252 57 6 0 653




ENTER: (RETURN] CONTINUE, [SO] START OVER, [EX] TO EXIT

63

02/22/91 10:59

SrYTE: DUANE ARNOLD 1: 1

02/22/91 11:06


M OD OF RECORD = 90010101-90123124

STABILITY CLASS: G DT/DZ


WIND DIRECTION

N NNE NE

ENE E ESE SE SSE

S SSW SW WSW W WNW NW

NNW

WIND SPEED(MPH)

1-3 4-7 8-12 13-18 19-24

5 9 1 0 0 8 7 5 1 0 7 14 7 0 0 4 7 3 0 0

13 9 2 1 0 10 24 0 1 0

6 30 9 0 1 4 43 35 0 0 8 48 17 1 0 9 26 5 0 0

10 24 5 1 0 7 10 1 0 0

14 14 4 0 0 16 29 8 0 0

8 18 6 0 0 8 20 3 0 0

L 137 332 111 5 1 1 606 -----------------------------------------------------------------------




ENTER: (RETURN] CONTINUE, (SO] START OVER, [EX] TO EXIT

64

>24

0 0 0 0 1 0 0 0

0 0

0 0

0 0

0

0

TOTAL

15 21 28 14

26 35 48 85 76 46 43 21 32 53 32 31

4

S fTB?. DUANE ARNOLD C p

02/22/91 11:01

- HOURS AT EACH WIND SPEED AND DIRECTION

W OD OF RECORD = 90010101-90123124

STABILITY CLASS: ALL DT/DZ


WIND DIRECTION

N

NNE

NE ENE E

ESE SE SSE

S SSW

SW

WSW

W

WNW NW

NNW

WIND SPEED(MPH)

1-3 4-7 8-12 13-18 19-24

25 92 114 75 22

31 111 147 111 4

20 115 143 51 1

20 113 101 53 11

27 112 106 41 8

27 111 171 44 2

28 145 356 130 12

31 199 465 286 31

41 184 378 341 43

36 135 216 152 42

43 134 163 100 42

37 112 74 36 29

34 91 84 34 17

31 90 148 101 48

40 97 220 240 105 39 84 211 226 46

L 510 1925 3097 2021 463 167 8255 ------------------------------------------------------------------------





65

>24

9 0 0

0 1

0

0 0

3

11

19

10

13 42 54

5

TOTAL

337 404 332 300 295 356 679

1018 1010

606 511 302 274 463 756 612

duane arnold energy center unit 1 semiannual effluent release … · 2012-12-05 · final...

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