ML20029B240

Semi-Annual Effluent Release Rept June-Dec 1990

ML20029B240
Person / Time
Site:	Duane Arnold
Issue date:	02/26/1991
From:	Denise Wilson IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
DAEC-91-0143, DAEC-91-143, NUDOCS 9103060280
Download: ML20029B240 (67)

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C fetruary 26, 1991 DAEC-91-0143

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Regional Administrator

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Mr. A. Bert Davis c 4Y fu U.S. Nuclear Regulatory Commission Region III 799 Roosovolt Road Glen Ellyn, Illinois 60137

Subject:

Semi-Annual Effluent Rolonso Report June 27, 1990, through December 26, 1990, for the Dunno Arnold Energy Contor, Unit No. 1 Docket:

50-331

Dear Mr. Davis:

Please find enclosed a copy of the Semi-Annual Report for

-the Duano Arnold Energy Contor, Unit No. 1, for the period June 27, 1990, through Docomber 26, 1990.

This report satisfies the requirements for the Semi-Annual Etfluent Roloaso Report, as stated in Section 6.11.lf of Technical specifications, (Appondix A to the Operating License DPR-49).

Sineorely, d)aahe}

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David L. Wilson Plant Superintendent - Nucionr DLW/RL/hc Enclosuret Semi-Annual Etfluent Roloase Roport cc Director of Nuclear Regulatory Commission (original w/a)

Attn Document Control Desk U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D. C.

20555 NRC Resident Inspector (w/ attachment)

S.

P. Sands, NRC Project Manager D. Minock (w/o attachments)

VEB1I g File A-1180, NRC-7a

?1030602E:0 910226 PDR ADOCK 05000331

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SEMI _ ANNUAL REPORT RADIOACTIVE EFFLUENT RELEASES JUNE 27, 1990, T}{ROUGil DECEMBER 26, 1990

e TABLE OF CONTENTS ITEM PAGE TITLE PAGE.

1 9

TABLE OF CONTENTS 2

INTRODUCTION.

3 LIQUID EFFLUENT TABLE 4

GASEOUS EFFLUENT TABLE.

5

SUMMARY

OF RADIOACTIVE SOLID WASTE.

6-8

SUMMARY

OF CilANGES TO THE OFFSITE DOSE ASSESSMENT MANUAL.

9

SUMMARY

OF CliANGES TO Tile PROCESS CONTROL PLAN WITli REVISED PROCEDURES INCLUDED.

.10-48

SUMMARY

OF METEOROLOGICAL DATA.

.49-65 2

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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 Semi-Annual Report will begin with the last date from this report.

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

There were no

• s.edses from DACC during the semi-annual period cove et oy this report.

No changes were made to the Offsite Dose Assessment Manual (ODAM) during the period covered by this report.

Likewise, there were r.o abnormal occurrences during the semi-annual period that would have required special reporting per the Duano Arnold Energy Center Technical Specifications.

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

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t SEMIANNUAL RADIOACTIVE HATERIAL RELEASE REPORT (1990)

LIQUID EFFLUENT

• Nuclides Released Unit 3rd Quarter 4th Quarter 4

strontium-89 Ci 0.0E+00 0.0E+00 strontium-90 C1 0.0E+00 0.0E+00 cecium-134 C1 0.0E+00 0.0E+00 cesium-137 C1 0.0E+00 0.0E+00 lodine-131 C1 0.0E+00 0.0E+00 I

cobalt-50 C1 0.0E+00 0.0E+00 cobalt-60 Ci 0.0E+00 0.0E+00 iron-55 C1 0.0E+00 0.0E+00 iron-59 Ci 0.0E+00 0.0E+00 zinc-65 Ci 0.0E+00 0.0E+00 manganese-54 C1 0.0E+00 0.0E+00 chromium-51 C1 0.0E+00 0.0E+00 zirconium-nlobium-95 C1 0.0E+00 0.0E+00 molybdenum-99 C1 0.0E+00 0.0E+00 technetium-99m C1 0.0E+00 0.0E+00 usrium-lanthanum-140 C1 0.0E+00 0.0E+00 cerium-141 Ci 0.0E400 0.0E+00 Other (specify)

C1 0.0E+00 0.0E+00 C1 0.0E+00 0.0E+00 Ci 0.0E+00 0.0E+00 Ci 0.0E+00 0.0E+00 Ci 0.0E+00 0.0E+00 Total for period (above)

Ci 0.0E+00 0.0E+00 I

xenon-133 C1 0.0E+00 0.0E+00 xenon-135 Ci 0.0E+00 0.0E+00

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

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1 SEMIANNUAL RADIOACTIVE MATERIAL RELEASE REPORT (1990)

GASEOUS EFFLUENTS

• Nuclides Released Unit 3rd Quarter 4th Quartor

1. Fission gases krypton-85 C1 0.0E+00 2.9E-04 krypton-85m C1 0.0E+00 0.0E+00 krypton-87 C1 0.0E+00 0.0E+00 krypton-88 Ci 0.0E+00 0.0E+00 1

xenon-133 C1 1.3E-06 4.0E-01 xenon-135 C1 2.4E+00 2.5E+00 xenon-135m C1 3.0E-01 3.7E+00 xenon-138 C1 0.0E+00 0.0E+00 tritium C1 2.7E+00 1.7E+00 Total for period C1 5.4E+00 8.3E'00

3. Iodines iodine-131 Ci 5.0E-05 3.0E-05 lodine-133 C1 3.7E-05 4.5E-05 iodine-135 C1 3.8E-06 0.0E+00 Total for period Ci 9.1E-05 7.5E-05

3. Particulates strontium-89 C1 3.1E-06 2.1E-06 strontium-90 Ci 7.2E-08 5.1E-09 cesium-134 C1 0.0E+00 0.0E+00 cesium-137 C1 3.7E-07 0 OE+00 barium-lanthanum-140 Ci 0.0E+00 0.LF^00 chromium-51 C1 3.5E-05 9.5E-05 manganese-54 C1 6.3E-04 1.2E-04 1ron-59 C1 4.4E-05 0.0E+00 cobalt-58 C1 1.6E-04 1.7E-05 cobalt-60 C1 1.6E-03 4.7E-04 l

Total for period C1 2.5E-03 7.0E-04 Release period is June 27, 1990, at 0900 through December 26, 1990, at 0800.

5

SUMMARY

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

SHIPMENTS MADE TO BURIAL FACILITIES i

FINAL DISPOSITION TO B.ARNWELL, SC No. of Volume Acti s-i ty Waste Type Shipments (M')

(Ci)

Spent Resins, Mechanical Aqueous Filter 7

3.70E+01 1.03E+03 FINAL DISPOSITION TO RICHLAND, WA No. of Volume Activity waste Type Shipments (M')

(C1) 2 7.69E+00 4.41E+02 Spent Resins 1

2.97E+00 1.13E+01 Dry.etive Waste SHIPMENTS MADE TO PROCESSING FACILITIES u

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

No. of Volume Activity Waste Type Shipments (M')

(C1) 5 1.46E+02 9.85E+00 Dry Active Waste SHIPMENTS FOR PROCESSING AT WALTZ MILL (MADISON, PA)

No. of Volume Activity Waste Type Shipments (M')

(C1) 2 7.25E+01 1.17E-01 Dry Active Waste

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SUMMARY

(con't)

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

TOTAL SOLID WASTE DISPOSITION No. of Shipments 17 No. of Shipments:

Mode of Transportation:

Truck (Exclusive Use) 7 Barnwell, SC Destination:

2 Madison, PA 5

l Oak Ridge, TN 3

Richland, WA volume Activity (M')

(C1) 2.66E+02 1.49E+03 Waste Shipped 1.13E+02 1.48E+03 Waste Buried * :

Includes waste buried d rectly by DAEC and waste buried by processing facilities.

Waste Classification:

No. of Shipments 1

"C" Stable 1

"B" Stable 8

"A" Unstable 7

"A" Stable

-_=___ _ _

SUMMARY

(June 27, 1990 - December 26, 1990)

MAJOR NUCLIDE COMPOSITION DAW 3rd QTR 4th QTR TOTAL PERCENT t

NUCLIDE (C1)

(C1)_

(Cl)

ABUNDANCE PRINCIPLE NUCLIDES Co-60 1.09E+00 3.17E+00 4.26E+00 2.00E+01 1

Fo-55 3.59E+00 1.08E401 1.44E+01 6.77E+01 Mn-54 3.10E-01 9.27E-01 1.24E+00 5.83E+00 Co-58 9.66E-02 2.88E-01 3.05E-01 1.81E+00 Fe-59 1.17E-01 3.52E-01 4.69E-01 2.20E+00 N1-63 8.13E-02 2.44E-01 3.25E-01 1.53E+00 NUCLIDES WITH Z>92 TRUs*

6.50E-05 1.97E-04 2.62E-04 1.23E-03 Pu-241 2.11E-03 6.33E-03 8.44E-03 3.97E-02 Cm-242 2.30E-04 6.80E-04 9.10E-04 4.28E-03 ALL OTHERS **

4.90E-02

1. 43E-01 1.92E-01 9.02E-01 TOTALS 5.34E+00 1.59E+01 2.12E+01 1.00E+02 ALPHA EMITTING TRANSURANICS WITH HALF-LIFE GREATER THAN FIVE (5) YEARS Co-144, Cs-137, Cs-134, Cr-51, Zn-65 7

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SUMMARY

(June 27, 1990 - December 26, 1990)

MAJOR NUCLIDE COMPOSITION SPENT RESINS, MECHANICAL AQUEOUS FILTERS 3rd QTR 4th QTR TOTAL PERCENT NUCLIDE (Cl)

(C1)

(C1)

ABUNDANCE PRINCIPLE NUCLIDES Co-60 2.08E+02 3.26E+02 5.34E+02 3.64E+01 Fe-55 1.63E+02 2.60E+02 4.23E+02 2.88E+01 Cs-137 1.09E+01 7.26E+00 1.82E+01 1.24E+00 Mn-54 8.45E+01 1.63E+02 2.48E+02 1.69E+01 Cs-134 7.37E+00 4.61E+00 1.20E+01 8.17E-01 Co-58 4.02E+01 8.00E+01 1.20E+02 8.17E+00 Cr-51 5.26E+01 3.07E+01 8.33E+01 5.67E+00 N1-63 4.15E+00 6.87E+00 1.10E+01 7.49E-01 H-3 2.84E-02 2.43E-02 5.27E-02 3.59E-03 C-14 1.10E-01 2.42E-01 3.52E-01 2.40E-02 NUCLIDES WITH Z)92 TRus*

1.07E-03 7.10E-04 1.78E-03 1.21E-04 ALL OTHERS **

5.96E+00 1.20E+01 1.80E+01 1.23E+00 TOT '.LS 5.77E+02 8.91E+02 1.47E+03 1.00E+02 ALPHA EMITTING TRANSURANICS WITH HALF-LIFE GREATER THAN FIVE (5) YEARS AND INCLUDES Pu-241 AND Cm-242 Ag-110m, Co-57, I-131, Sr-89, Sr-90, and Fe-59 8

.1

SUMMARY

__OF CHANGES TO 'n!E OFF, SITE DOSE ASSESSMENT MANUAL (ODAM)

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

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SUMMARY

OF CHANGES t

TO THE PROCESS CONTROL PLAN (PRCP) s During the period of June 27, 1990, through December 26, 1990, the following changes were made to tho existing PRCP's:

PRCP C

" Irradiated Components in Carbon Steel Linors" was revised to require additional quality assuranco measures by the processing vondor.

Specifically, it requires the vendor t) verify materials placed in the burial container as documented on the vendor inventory sheets a~.ch the wasto contents as spellod out on the shipping manifest.

PRCP A, D, C, E, F: A13 PRCP's listed were revised to require services and material for wasto processing, tLat exceed DOT Typo A Quantities, be p.ocured as Quality Lovel II.

Those services and material must be in compliance with 10CFR71 and 49CFR for Packaging and Transporting Radioactive Materials.

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PROCESS CONTROL PROGRAM FOR DEVATERING WET RADICACTIVE SOLIO WASTE PRCP-A Revision 8 October 23, 1990

-1 Ouane Arnold Energy Center Iowa Electric Light and Power Company Approved by:.

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PRCP-A Introduction This Process Control Program describes the dewatering of wet radioactive waste solids from liquid systems at the Ouane Arnold Energy Center and packaging the waste in high integrity containers (HIC) or steel containers (also referred to asliners).

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 Mooresto.1, New Jersey, is the vendor of the dewatering and packaging services as well as the RADLOKm high integrity containers and steel liners used at the DAEC. Hittman personnel perform the dewatering and packaging operations described herein.

Dewaterina System Descriotion 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 OAEC and 2 of 8 12 10/23/90 Rev. 8

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t PRCP-A I

i exhausts air into the OAEC Radwaste Ventilation System. Water removed from the HIC or steel liner, during dewatering, is returned t. the OAEC radwaste system and is treated as liquid radwaste.

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s The Hittman dewatering system is equipped with instruments to provide information about the dewatering process.

These include mechanical and H

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

vacuum receiver tank, and dewatering manifold assembly. Orainable liquid tests are performed using a vacuum pump and vacuum bottle to verify liquid content of the HIC or steel liner prior to shipment.

t Doeration i

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, vaste sludge tanks, or the spent resin tank.

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

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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 down 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 af ter dewatering.

LAf ter 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 l

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 thin a volume demonstrated by the vender 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 Vaste Chq.racteristics 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 L hington, 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 ccmpatible with the HIC o" 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 vastes 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.

Hiah Intearity Container Wastes covered by this PRCP will be packaged in RADLOKt" high integrity containers or steel liner:,

The RADLOKr* 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 5 of 8 15 10/23/90 Rev. 8

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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 4

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.

.lowa. 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 indor to maintain procedures.which will ensure that-all applicable requirements ce met prior to shipment of radioactite waste.

Iowa Electric Light and Power will review applica,ble. vendor's operating procedures before authorizing the vendor to dewaterLradioactive 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, 1ELP will audit the raduaste Process Control Program and operating procedures that implement it (in accordance with Technical Specification 6.5.2.8.J.)

Any change to the Process Centrol 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.

Trainina 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.

Referenc11 1.

DAEC Rc1 waste 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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P PROCE$$ CONTROL PROGRAM FOR LIQUIDS AND WET RADIDACTIVE MATERIAL PRCP-B Revision 1 October 23, 1990 Duane Arnold Energy Center lowa Electric Light and Power Company Approved ~by ZOM

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l PRCP-B Introduction

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This Process Cor. trol Program (PRCP) describes the solidification, absorption and/or stabilization of liquids and wet waste materials produced at the OAEC.

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.

LLn.dE The OAEC's 'tadwaste Group normally processes

'I 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 th DAEC PRCP by reference and submitted to the NRC for review and appioval, System Dascription 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 wastt 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

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i 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 ligeld.

Absorbed wastes are blended with the absorbent and then transferred to a shipping container.

Liquid waste which is to be sf ?fied 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 oackage systems typically used at the OAEC.

Ooeratiga 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 ti,+ tottom 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 of f 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 00T required absorbent ratio.

The drum lid is lightly secured and the drum inverted for the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 drua 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 3 of 7 21 10/23/90 Rev. 1

PRCP-8 inspected 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> later for free standing liquid.

It is not necessary to

(

invert the solidified drum because the s slidified matrix is heavier than the liquid hence any free liquid will be forced to the surface.

Vet 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 in::h 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 ind 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 Ifners are sealed and the drum lid secured, The drum is stored upside-down for at least

(

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and then inspected for free standing liquid.

Essential Vaste Characteristics and Verification 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 l.

(a)(3), and are compatible with the stabilizing media and the container itself.

l 10 CFR Part 61.56 (b) includes provisions for stability of Class 8 and C radioactive waste after its' disposal.

Only Class A waste forms are covered by 4 of 7 22 10/23/90 Rm1

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 L

Handling Procedures require an inspection for free liquids 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 wi.11 be procured as Quality Level II.

All

= services and materials must be procured in compilance with 10CFR71 and 49CFR for Packaging and Transporting Radioactive Materials, i

Admin'istration 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 raquired, IELP will review applicable vendor's operating procedures before authorizing a vendor to process radioactive waste.

The Radwaste Group of the Radiation Protection Department L

5 of 7 10/23/90 23

_ _ Re. 1,

PRCP-B is responsible for ensuring compliance with the PCP, Vendor oversight, and for I 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 af ter the change is made.

Trainina-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

um. ted confirmation of the training.

References:

1.

DAEC Radwaste Handling Prc.cedures 6 of 7 24 10/23/90

PRCP-B FIGURE 1

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f t

PROCESS CONTROL PROGRAM FOR PROCESSING

.IRRA0! ATE 0' COMPONENTS IN CARBON STEEL LINERS PRCP-C.

4 Revision 3 October 23, 1990 Quane-Arnold Energy Center Iowa Electric Light and Power Company

-Approved b'y:

C M

// 7 9 0 V/

Radwaste-Supervisor:

Date.

1, Nj l

Approved.by:

/M c. -

. %.' e t e

,e h / i"[? <

3 Radiation-Protection-Supenviser Dake.

Reviewed by: /

J

//-/5 /O Cha[rman,-!OperationsCommittee-Date

-ApprovedLby: 1 b

Rhf NM/5N6 htSuperintendent-Nuckar Date 1 of 7 26 10/23/90 Rev. 3

l PRCP-C INTRODUCTION f.

Ti.. Process Control Program describes the pac <.ing and dewatering of irradiated components into waste liners from storage in the Spent Fuel and Cask Pools here at the Ovane Arnold Energy Center.

Irradiated components in general dese: 1be any item that has been exposed to a neutron flux. Components typical sf 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.

Cepleted neutron sources may also be disposed of using this Process Control Program provided that they qualify for disposal under the waste classification requirements of 10CFR61.

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), 10CFR61.56 (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.

QQBII. RING 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 i

1 2 of 7 27 10/23/90

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. Af ter 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 VDS 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 componen), 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, vastes 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 suf ficient to fill a steel liner is accumulated they will be packaged and dewatered using vendor equipment and procedures.

I i

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.

Oryness 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 vastes 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

+he 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 requirerents of 10 CFR Section 61.56 (a), and are compatible with the steel liner.

In addition, the OAEC'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 as'sure that it has been done. :For a given' type of-waste, the. operating procedure requires the 1

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 pres 2ure reading test is performed.

If the pressure increase does

(

4 of 7 29 10/23/90 E

i

PRCP-C t

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.

OVALITY 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.

Iowa Electric maintains assurance that dewatering and packaging is performed as intended by separately verifying and documenting that the key: steps were pe r'fo rmed.

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 reouires 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 l

5 of 7 l

30 10/23/90 Rev. 3

PRCP-C applicable' vendor's operating procedures before authorizing the vendor to 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 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 af ter 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 1.0 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)".

I 6 of 7 31 10/23/90

PRCP-C t

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

(

PROCESS CONTROL PROGRAM FOR DEWATERING WET RADIOACTIVE SOLIO WASTE IN CARBON STEEL LINERS PRCP-E Revision 2 October 23, 1990 Duane Arnold Energy Center Iowa Electric Light and Power Company

(

Approved by (L

Uh

// lo -90 Radwaste Supervisor Date 3

Approved by:

Wal" n,.xr,3

/s 7 '9 e Radiation Protection Supervisor Date

//!/JNo Reviewed by:

-2 Ch[rman,OperationsCommittee Date ndSuperintendent-Nuclear blFf II/ts/9/'

Approved by:

hC Date

(

1 of 8 3 3 _.

10/23/90

PRCP-E Jntroduction 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 3

ICi/m.

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, Mary'.and, 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.

Dewaterino System Description The Hittman dewatering system employs dewatering equipment to dewater the wet radioactive waste solidt 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 10/23/90 34 Rev. 2

i q,

i 1

PRCP-E i

(

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.

Operatis The radiocctive wastes that are devatered 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 af ter 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.

z vacuum receiver tank to 10 inches Hg or less on the vacuum gauge. -Pump down by suction on the bottom underdra b manifold is continued for a specified time with the devatering pump and tk.e 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 t

w

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-stending 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 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.

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), 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

- 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, Iowa Electric intends to accomplish this by den.tring 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 li_ quid that can be suctioned from the carbon steel liner during a def:ned time is no greater than an amount stated in the operating j

procedure pertaining to that kind of waste.

The conditions stated in the l

l 4 of 8 36 10/23/90 Rev. 2.

PRCP-E procedure will have been demonstrated by the vendor of the dewatering 1.ervice f

to achieve less than 1% free-standing water in the waste.

Carbon Steel L.iner Wastes covered by this PRCP will be packaged in carbon steel liners.

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

1, Sealing components, 2.

b terior surface, 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 wri tten _ procedures. The procedure requires verification that the closure gasket

(

is in place.

Qpality 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.

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 materials must be procured in compilance with 10CFR71 and 49CFR j

for Packaging and Transporting Radioactive Materials,

(

5 of 8

[

37_

- - -10/23[90

i

.:. r-PRCP-E

L Iowa Electric's qualit.y assurance program is subject to 10 CFR Part 50,- Appendix B, as applied to deutering and packaging of radioactive waste.

6dministration 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, 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 n r recordkeeping.

At-least-once every 24' months, IELP wi-11 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 feport after the change'is made.

I Trainino 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.

l l

L 6 of 8 10/23/90 38 Rev. 2

PRCP-E References

('

1. DAEC Radwaste Handling Procedures

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",

1

(

7 of 6 10/23/90

'g Rev. 2

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Waste Transfer Line Fill O Valve ^

tiquid level ladicator. LL-l level-indicator. RL-1 Radwaste 9entilation 5ystes yacuum Gauge vacuum Vent to Ra&easte Ventilation System Puep Vacuum

7.. :

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V-1 1

g, Vent to Radweste Ventilation System

>d t'

Vacuum

DAIC Service air Vent to 00 sottle I

Radwaste g

.l DS-l Q'

.tewatering Ventilation-x-

go I

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Vent To Radwaste M

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Dewatering Process, typical Configuration

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PROCESS CONTROL PROGRAM FOR DEWATERING i

MECHANICAL CARTRIDGE AND BAG FILTERS IN HIGH INTEGRITY CONTAINERS OR CARBON STEEL LINERS PRCP-F Revision 1 October 23, 1990 Ouane Arnold Energy Center Iowa Electric Light and Power Company i

i Approved by:

(L 4Wtt

//'6 '90 ~

v o Radwaste' Supervisor Date

//[Y/ P6

-Approved by:

/

$oe t

RadiationProtectionShpervisor Date-I

1. //#4 Reviewed by:

-,x>

,-/

y Chafrman, Operations Committee-

-Date Approved by:

ob kh

////Shc>'

~~

s IkdtSuperintendent-Nuc1kar Date

(

1 of 8 41 10/23/90 RnL X

l PRCP-F Introduction This Process Control Program describes the packaging and dewatering of wet mechanical cartridge and bag filtert 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 accardance with Barnwell, South Carolina burial site requirements.

I The dewatering pr1 cess removes liquid from the waste in c 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.

YENDOR 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 i

l 2 of 8 42 10/23/90

~

.w

.1 PRCP-F tools' including dewatering wand, bag knife, filter tongs, filter hook, I

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, i

The Hittman dewatering system used for a mix of cartridge filters, filter bags, and other mechanical filters from various systems consists of eqaipment 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 CR0 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 l

packaged and dewatered using the vendors equipment and procedure.

(.

3 of 8 43 10/23/90 w

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'i_s completed.

E51ENTIAL 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 and the State of _ South Carolina license conditions, as appropriate.

-.The vastes subject to the process control plan are from sources within the OAEC 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 land kind of each of the subject wastes, IEL&P-is able to ensure that th_e 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 L

after its disposal.

For the wastes cover?d 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 F

stable af ter disposal as authorized -in Section 61.56 (b)(1).

4 of 8 44 10/23/90

% e

1

,- 1 PRCP-F

['l Both 10 CFR Sections 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 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 suct.ioned 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 dewate_ ring 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-RAOLOK high integrity contain'ers or steel' liners.

The RADLOK containers have been certified by the South-Carolina. Bureau of Radiological Health for the: intended use. Steel liners will qual'ify as. strong,' tight containers as per 49CFR.

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

y 1.

-Sealing components, i

2.-

Exterior surface, L

3.-

Dewatering filter elements, and 4.

Dewatering verification-tube or equivalent.

(

5 of 8 45 10/23/90 rew f

a s

PRCP-F-i After filling and dewatering has been completed, the fill port opening in the j

container is closed _in accordance with written procedures.

The procedure requires verification that the closure gasket is in place and that the threaded ffil port lid is tightened to a specifted torque value when required by procedure.

OVALITY ASSURANCE Control of the devatering 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 vtrifies and documents that key steps have been performed.

Iowa Electric maintains-assurance that devatering 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 radfoactive vaste will be procured as Quality Level II.

All services and materiels 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 8,- 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.

luwa Electric Light and Power will review applictble-vendor's operating procedures before authorizing the vendor to dewater radioactive waste.

Site specific procedures developed by the vendor for the OAEC will be reviewed oy Radiation Protection Supervision. Most recent revisions will be stamped as approyed on both working and controlled vendor procedure copies. -Pro::essing procedures internal to the vendor will be ieviewed and approved by the vendor.

The Radwaste Group of the Radiation Protection l

6 of 8 L

46 10/23/90 L

Rev. 1

s PRCP-F Department is responsible for ensuring compliance with the PRCP, for vendor I

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 wi'l be made in accordance with Technical Specificat! n 6.15, approved by the Plant Superintendent-Nuclear, reviewed by the Operations Committee, and submitted to the NRC in the next Semi-Annual Pr.dioactive Material Release Report after the change is made.

TRA(N(MQ Before a vendor employee performs a dewatering or packagin0 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 F430-P-010, Revision 0, " Procedure for Torus Cleaning, Filter Packaging and Dewatering" l

U 7 of 8 47 10/23/90 Rev. 1

6 PRCP-F I

N 1C E NI I

~ ritttes ~

1

/

AB$0RitNT tittA$t CORD telt:0 UN0ttttAIN r!Li[R

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f 2

i Abt!!yt U[_ i

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ot:r:uit; ;;st i

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4 l f + h *'yf* **s5' sf,!

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tY SotTOM OF RADLOK

=

l 8 of 8 48 10/23/90 l

Ram.1.

4 i

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 Conter (DAEC).

Each table includes wind speed, wind direction, and stability clars at the specified sonsor 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 foot and 94.2% at 156 feet.

49 p9, v.

~#.-.,g,,

y w

p r.+,.

y.

-.--+4 e

m

i SITE: DUANE AANOLD 02/22/91 10:48 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =

90010101 90123124 STABILITY CLASS:

A DT/DE

-ELEVATION:

SPEEDWS33 DIRECTION WD33 LAPSE DEL T WIND SPEED (MPH)

U1ND DIRECTION 13 47 8 12 13 18 19 24

>24 TOTAL N

8 26 9

2 0

46 NNE 12 35 19 1

0 0

67 NE 10 20 12 1

0 0

43 ENE 5

8 1

1 0

0 15 E

4 14 2

2 0

0 22 Est-5 26 3

2 0

0 36 SE 4

19 14 2

0 0

40 51, 1

23 22 0-0 0

47 8

1 5

33 9

3 0

$1 SSW 2

3 14 14 6

0 39 SW 3

6 15 17 7

1 49 WSW 2

6 14 8

1 1

33 W

1 6

8 7

0 0-22 WNW

-3 3

8-9-

6 2

31 NW 3

3 29 19 17 0

71 NNW 1

8 f

12 0

0 30 TOTAL 65 211 212 106 41 4

64;

-PERIODS OF CALH(HOURS):

127-

. VARIABLE DIRECTION O

HOURS OF HISSING DATA:

496 ENTER -(RETURN) CONTINUE, (50) START OVER, [EX) TO DXIT a

50

- _ = - - _--

~.

o

. SITE: DUANE ARNOLD 02/22/91 10:39 i

HOURS AT EACH WIND SPEED AND DIRECTION

-PERIOD Dr RECORD =

90010101-90123124 STABILITY CLASS:

B DT/DE

-ELEVATION:

SPEEDWS33 DIRECTION WD33 LAPSE DEL T WIND SPEED (MPH) r WIND 98RECTION 1-3 4-7 8-12 13-18 19-24

>24 TVTLL N

0 2

3 0

0 0

5 NNE O

1 2

1 0

0 4

NE O

3 1

0 0

0 4

ENE O

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 O

1 6

0 0

0 7

S 1

3 6

8 1

0 19 SSR 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 Wim 0

0 2

0 2

-2 6

NW 0

5 11 10 1

0 27 NtN 0

2 5

5 2

0 14 TOTAL 4

28 57 38 11 4

142 PERIODS OF CALH(HOURS):

127 VAR 5ABLE DIRECTION O

HOURS-OF MISSING DATA:

496 ENTERI (RETURN) CONTINUE, (S0) START OVER, [EX) 70 EXIT

$1

I I

' SITEa DUANE ARNOLD 02/22/91 10:50 t

HOURS AT EACH WIND SPEED AND DIRECTION

' PERIOD OF RECORD =

90010101-90123124

. STABILITY CLASS:

C DT/DE.

ELEVATION:

SPEED WS33 DIRECTION WD33 LAPSE DEL T WIND SPEED (MPH)

WIND D2RECTION 1-3 4-7 6-12 13-18 '9-24

>24 TOTAL w..

N 1

1 5

1 0

0 8

1 NNE O

2 2

2

)

0 6

NE O

0 1

0 0

0 1

ENE O

2 1

0 0

0 3

E O

1-0 0

0 0

1 ESE 1

2 3

0 0

0 6

SE 0

2 3

0 0

0 SSE O

6 0

0 0

11 9

0 1

9 5

0 0

1$

SSW 0

2 2

3 3

1 11 SW 0

3 9

4 1

M.

18 WSW 1

3 6

0 1

0 11 W

0 2

3 1

1 1

8 L

WNW 1

2 4

4 3

4 19 NW 0

3 17 9

1 0

30 NNW 0

2 11 11 0

0 24 TOTAL 4-34 82 40 10 7

177 PERIODS or CALH(HOURS):

127 VARIABLE DIRECTION O

HOURS OF HISSING DATA:

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

52

,_.m.__

...#m_m,

,,,.my.wm.w.y.

,,,,.,,_e.,,,-,.,,,_,...,,,yy,,y,w,y

,,m,m-c.,.

,,..s,-.

m,, -....w.

y.y-,

m_.

S3TE: DUANE ARNOLD 02/22/91 10:51 HOURS AT EACH WIND SPEED AND D1RECTION PERIOD OF RECORD =

90010101-90123124 STAB 3LITY CLASS:

D DT/D2 3

ELEVATION:

SPEEDWS33 DIRECTION WD33 LAPSE DEL T WIND SPEED (MPH)

[

WIND D2RECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

9 24 33 8

1 0

75 NNE 11 31 36 16 0

0 94 NE 13 73 56 3

0 0

145 ENE 8

41 46 13 0

0 109 E

15 37 32 15 0

0 101 ESE 12 49 29 1

0 0

92 SE 14 77 43 4

0 0

138 SSE 17 104 98 6

0 0

225 5-18 81 164 58 4

2 327 SSW 11 36 58 36 9

1 151 SW 10 23 46 20 14 2

115 WOW 12 36 18 12 5

1 86 W

6 22 23 24 8

0 86

-WNW 9

24 47 35 25 5

145 NW 4

39 94 79 37 0

253 NdW-3 35-153=

80-17 0

288 TOTAL.

172 732 976 410 120 11 2430 PER10T9 0F CALM (HOURS):

127 VAR!AboE DIRECTION O

9=

-HOURS OF HISSING DATA:

496 ENTER: (RETURN) CONTINUE, (S0) START OVER,. [EX) TO EXIT

+

53 u.

.m.______._

e 62tEs DUANE ARNOLD 02/22/91 10:41 i

HOURS AT EACH WIND SPEED AND DIRECTION PER80D OF RECORD =

90010101-90123124 STABILITY CLASS:

E DT/DE ELEVATION:

SPEED WS33 DIRECT 10N:WD33 LAPSE DEL T WIND SPEED (HPH)

WIND

'D8RECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

17

$3 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 1

E 39 69 22 5

0 0

137 ESE 34 107 48 3

0 0

192 SE

$0 208 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 30 29 11 3

0 137 USW 24 43 16 14 5

0 102 0

22 34 25 15 4

0 101 WNW 12 53 49 24 13 156 NW 7

81 97 24 23 4

237 NNW 18 45 94 35 4

1 197 TOTAL

$65 1591 1080 282 58 11 3598 P9RIODS OF CALH(HOURS):

127 JARIABLE DIRECTION O

HOURS OF HISSING DATA:

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

i l-54

88 El DUANE ARNOLD 02/22/91 10:53 HOURS AT EACH WIND SPEED AND DIRECTION PERZOD OF RECORD =

90010101-90123124 STABILITY CLAdSe F

DT/DE ELEVATION:

SPEED:WS33 DI RECTION: WD33 LAPSE DEL T WIND SPEED (MPH)

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

>24 TOTAL N

3 0

3 3

0 14 NNE 13 13 3

1 0

0 31 NE 10 23 0

0 0

0 33 ENE 11 3

0 1

0 0

16 E

18 5

1 0

0 0

25 ESE 18 1

4' 1

0 0

26 SE 33 14 1

0 0

0

$0 SSE' 5$

24 3

0 0

0 86 5

73 49 3

0 0

0 128 SSU 49 31 5

0 0

0 90 SW 23 16 0

0 0

42 WSM-14 18-0 0

0 36 0

13 13 8

0 0

0 34 WNW-8

-8

-6 0

0 0

22 IN -

11 9

3 0

0 0

23 NNd 5

1 2

1 0

0 10 TOTAL 359 231 42 7

3 0

665 PERIODS OF CALM (HOURS):

127 VARIABLE DIRECTION 0

HOURS OF MISSING DATA:

496 ENTER: (RETURN) CONTINUE, [SO) START OVER, [EX) TO EXIT 55

I SITES DUANE ARNOLD 02/22/91 10:42 HOURS AT EACH WIND SPEED AND DIRECTION J

PERIOD OF RECORD =

90010101 90123124 STAB 2LITY CLASS:

0 DT/D1 ELEVATION:

SPEED WS33 DIRECTION WD33 LAPSE DEL T 1

WIND SPEED (MPH)

WIND DIREC;10N 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

3 1

0 0

0 0

4 NNE 10 8

0 0

0 0

18 NE 29 16 0

0 0

0 48 ENE 35 4

0 0

0 0

41 E

22 0

0 0

1 0

34 ESE 18 1

0 0

0 0

29 SE 26 0

0 0

0 0

36 SSE 46 4

0 0

0 0

70 5

72 8

0 0

0 0

91 SSW 73 7,

2 0

0 0

87 SW 66 8

0 0

0 0

78 WSW 27 6

0 0

0 0

36 W

16 4

0 1

0 0

21 WNW.

7-3 0

0-0 0

10 l

IR1 4

2 0

0 0

0 6

NUW 1

0 0

0 0

0 1

TOTAL 455 72 2

1 1

0 610 PERIODS OF CALM (HOURS):

127 VARIABLE DIRECTION O

HOURS OF HISSING DATA:

496 ENTER: (RETURN) CONTINUE, (80) START OVER, (EX) TO EXIT 1

56

=<-,.,s._

m---..

.-..-..y-._,_,,,

_-,.,_.._~._,,..w_,

,_m....

-mm,,.,

y,.e.,..m..

y

,- v

_.__._.__.__.m_._

i

$1TE: DUANE ARNOLD 02/23/91 10:43 HOURS AT EACH WIND SPEED ANO DIRECTION PERIOD OF RECORD =

90010101-90123124 STABILITY CLASS:

ALL DT/DZ E!.EVATION:

SPEED WS33 DIRECTION WD33 LAPSE DEL T WIND SPEED (HPH)

WIND D8RECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

43 110 75 29 9

0 267 NNE 80 154 115 50 1

0 401 NE 96 197 118 20 0

0 435 ENE 88 121 96 20 0

0 329 E

99 128 59 24 1

0 327 ESE 88 186 89 0

0 0

384 SE 128 324 132 10 0

0 610 SSE 206 416 273 15 0

0 936 S

241 429 456 125 9

2 1276 SSW 183 191 164 85 18 4

656 SW 236

~116 103 54 28 5

448 WSW 80 115-61 35 12 2

312 W

$9 83 69 52 15 1

283 WNW 40 94 116 72 49 18 389 NW 29 142 251 141 79 4

647 NNW 28 93 274 144 23 1

564 TOTAL 1624 2899 2451 884 244 37 8264 PERIODS OF CALH(HOURS):

127 VARI ADLE DIRECTION O

. HOURS OF HISSING DATA:

496 ENTER: (RETURN) CONTINUE, (50) START OVER, [EX) TO EXIT i

57

. ~ - -

,___._.___,_.___mm.__

m. _..

i 58TE: DUANE ARNOLD 02/22/91 10:57 HOURS AT EACH WIND SPEED AND DIRECTION PER30D OF RECORD =

90010101-90123124 STABILITY CLASS:

A DT/DE ELEVATION:

SPEEDWS156 DIRECTIONWD156 LAPSE DEL T WIND SPEED (MPH)

W2ND I

D3RECTION 1-3

• -7 8-12 13-18 19-24

>24 TOTAL N

1 22 14 4

2 0

43 NNE 2

27 25 10 0

0 64 NE 1

15.

23 5

0 0

44 ENE 1

8 7

0 0

0 16 E-0 6

10 0

0 0

16 ESE 0-12 20 1

0 0

33

'SE O

3 27 12 0

0 42 SSE O

8 13 22 1

0 44 S

1 3-11 20 2

0 37

]

SSW 1

0 7

21 8

0 37 SW 0

3 15 15

. 14 4

51 WSd:

3 6

8 10 10 2

39 d

2 4

6 5

1 0

18 WNW 0

5 6

4 6

3 26 NW 3

4 12 2 24 20 7

80 NNW 3

10 8

12 6

1 40

. TOTAL 16 136 222 165 70 17 630 PER2005 Or CALM (HOURS):

73-VAR 3ABLE DIRECTION O

HOURS CF MISSING DATA:

$05 ENTER: (RETURN) CONTINUE, (SO) START OVER,:[EX) TO EXIT k

58

i i

0 SI?E DUANE ARNOLD 02/22/91 10:58 HOUR $ AT EACH WIND SPEED AND DIRECTION pen 80D OF RECORD =

$0010101-90123124 GTABILITY CLASS:

B DT/DE ELEVATION:

SPEED WS156 DIRECTION:WD156 LAPSE: DEL T WIND SPEED (HPH)

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

>24 TOTAL 2

N 1

2 4

1 0

0 8

NNE 0

0 0

3 0

0 3

NE O

3 2

0 0

0 5

ENE 1

1 0

0 0

0 2

E 0

0 1

0 0

0 1

ESE O

O 2

0 0

0 2

l SE O

2 4

4 0

0 10 SSE O

1 5

6 0

0 12 5

0 1

3 9

2 0

15 SSW 0

0 3

2 2

1 e

SW~

1 1

3 4

0 3

12 WSW 1

0 3

1 1

0 6

W 0

2 2

1 2

0 7

-WNW 0

0 4

0

1 3

8 NW 0

1 4

14 2

1 22 HNW 0.

3 5

9 4

0 21 TOTAL 4

17 45 54 14 8

142 PERIODS OF CALH(HOURS):

73 VARIABLE DIRECTION 0

HOURS OF HISSING DATA:

505 ENTER: [ RETURN) CONTINUE, [SO) START OVER, (EX) TO EXIT 59

O i

j 833E DUANE ARNOLD 02/22/91 10:$8 i

HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =

90010101-90123124 STABILITY LLASS:

C DT/DE ELEVATION:

SPEED WS156 DIRECTION WD156 LAPSE DEL T i

WIND SPEED (HPH)

WIND D3RECTION 13 47 8 12 13 18 19 24

>24 TOTAL N

0 4

5 1

1 0

11 NNE O

1 4

3 0

0 8

NE 0

1 0

0 C

0 1

ENE O

O O

O O

O O

E O

2 0

0 0

0 2

ESE O

1 1

0

'i 0

2 SE O

1 5

3 0

0 9

SSE 0

3 3

0 0

11 S

0 2

1 10 1

0 14 SSW-0 1

3 2

0 11 SW 1

1 6

6 4

1 19 MSM 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

1 10 11 5

3 32 NNW 0

0 5

13 3

.0 21 TOTAL 2

28

$1 63 17 13 174 PER80DS OF CALM (HOURS):

73 VARIABLE DIPECTION

.0 HOURS OF.MISSINO DATA:

505 ENTER: [RETUR!!) CONTINUE, [SO) START OVER, [EX) 70 EXIT l

i l

I i

60

Sait DUANE ARNOLD 02/22/91 10:59 HOURS AT EACH WIND SPEED AND DIRECTION PER30D OF RECORD =

90010101 90123124 STABILITY CLASS:

D DT/DE ELEVATION:

SPEEDWS156 DIRECTION WD156 LAPSE DEL T WIND SPEED (HPH)

WIND D8RECTION 13 47 8 12 13 18 19 24

>24 TOTAL N

8 18 39 24 8

7 104 NNE 8

29 33 33 2

0 105 NE 4

45 44 18 0

0 111 ENE 5

49 41 20 6

0 122 E

3 37 22 26 6

0 94 ESE 9

26 47

'7 0

0 89 SE 7

38 75 32 5

0

-158

-SSE 6

42 111 72 12 0

244 8

10 37 105 112 19 1

290 SSW 9

21 61 41 18 4

156 SM 13 20 31 39 12 7

126 WSW 6

25 21 9

9 4

75 0

6 22 23-8 10 5

72

' W";

5 16 50 37 20 17 145

.tu 16 25 70 101 54 22 288 Ncw 9

20 110 119 26 3

287 TOTAL-122 470 883 698 207 7'

2466 PERIODS OF. CALM (HOURS):

73 VARIABLE DIRECTION 0

HOURS OF MISSINO DATA:

505 ENTER (RETURN) CONTINUE, (50) START OVER, (EX) TO EXIT 61

I

~

w s

SZiE DUANE ARNOLD 02/22/91 10:59 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =

90010101-90123124 STABILITY CLASS:

E DT/DZ ELEVATION:

SPEED WS156 DIRECTION WD156 LAP 3EIDEL T WIND SPEED (HPH)

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

>24 TOTAL H-8 28 50 42 7

2 137 NNE 9

37 71 59 2

0 178 i

NE 7

28 53 27 1

0 117 ENE 7

41 46 32 5

0 132 E

9 50 64 12 2

0 137 ESF 6

43 94 33 1

0 177 SE 11 54 212 78 6

0 365 SSE 17 71 271 173 18 0

552 S

12 61 204 182 19 2

492 SSW 14 53 117 78 14 1

282 SW 14 59 72 33 12 4

197 WSW 11 43 25 13 8

4 104

'M-9 26 33 15 3

8 95 MNW 4

18 52 46 19 15 155 NW 6

38 95-88 24 21 272 NNW 16 25 74 68 7

1 192 TOTAL 160 675 1533 979 148 58 3584 PER1005 0F CALH(HOURS):

73

. VARIABLE DIRECTION 0

I

' HOURS OF HISSING DATA:

505 FJITER: (RE7 URN] CONTINUE,.(S0) START OVER, [EX) TO EXIT L

i l

l l

62 i

l i

,,.-a.+r,

.,n-

,. - ~,, -,.., - -

.. )

i t

'S&TE: DUANE ARNOLD 02/22/91 10:59 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECvAD =

90010101-90;23124 STABILITY CLASS:

F DT/DE ELEVATION:

SPEEDWS156 DIRECTION WD156 LAPSE DEL T WIND SPEED (MPH)

WIND D8RECTION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N.

2 9

1 3

4 0

19 NNE 4

10 9

2 0

0 25 NE 1

9 14 1

0 0

26 ENE 2

7 4

1 0

0 14

.E 2

8 7.

2 0

0 19 ESE 2

5 7

2 1

0 18 SE 4

17-24 1

0 0

47

$$E 4

31 27 8

0 0

70 10 32 37 7

0 0

86 SSW 3

34 20 8

0 0

66 SW 4

26 31 2

0 0

63 WSW 9

27 13 2

0 0

51 W

4 20 A4 5

0 0

43 WNd 6

18 25 6

1 0

56 NW 7

8 13 2

0 0

30 NNW 3

6 6

5 0

0 20 TOTAL 67 267 252 57 6

0 653 PERIODS Cr CALH(HOURS):

73 i

VARIt.BLE DIRECTION 0

HOURS OF HISSIN0 DATA:

505 ENTER: (RETURN) CONTINUE,-(SO) START OVER,'[EX) TO EXIT I

4 63

6.

SITE: DUANE ARNOLD 02/22/91 11:06 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =

90010101-90123124 STABILITY CLASS 0

DT/DZ ELEVATION:

SPEEDWS156 DIRECTION WD156 LAPSE DEL T WIND SPEED (HPH)

WIND l

DIRECTION 1-3 47 8-12 13-18 19-24

>24 TOTAL N

5 9

1 0

0 0

15 NNE 8

7

.5 1

0 0

21 NE 7

14 7

0 0

0 28 ENE-4 7

3 0

0 0

14 E

13 9

2 1

0 1

26 ESE-10 24 0

1 0

0 35 SE 6

30 9

0 1

0 40 SSE 4

43 35 0

0 0

85 S.

8 48 17 1

0 0

76 SSW-9 26 5

0 0

0 46 SW 10 24 5

1 0

0 43 WSW 7

10 1

0 0

0 21 W

14 14 4

0 0

0 32 WNW 16 29 8

0 0

0 53 NU 8

18 6

0 0

0 32 NNW 8

20 3

0 0

0 31 TOTAL 137 332 131 5

1 1

606

. PERIODS OF CALM (HOURS):

73 VARIABLE DI**CTION O

HOURS OF HItaING DATA:

505 ENTER: (RETURN)_ CONTINUE, (SO) START OVER, (EE) TO EXIT N

t 64

..A.

g e' o

SITE: DUANE ARNOLD 02/22/91 11:01 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =

90010101-90123124 STABILITY CLASS ALL DT/DE ELEVATION:

SPEEDlWS156 DIRECTION WD156 LAPSEDEL T WIND SPEED (MPH)

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

>24 TOTAL N

25 92 114 75 22 9

337 NNE 31 111 147 111 4

0 404 NE 20 115 141 51 1

0 332 ENE 20 113 101 53 11 0

300 E

27 112 106 41 8

1 295 ESE 27 111 171 44 2

0 356 SE 28 145 356 130 12 0

679 SSE 31 199 465 286 31 0 1018 41 184 378 341 43 3 1010 SSW 36 135 216 152 42 11 606 SW 43 134 163 100 42 19 511

'WSW 37 112 74 36 29 10 302 W

34 91 84 34 17 13 274 WNW 31 90 148 1C1 48 42 463 NW 40 97 220 240 105

$4 756 NNW 39 84 211 226 46 5

612 TOTAL 510 1925 3097 2021 463 107 8255

. PERIODS OF CALM (Il0URS):

73 VARIABLE. DIRECTION O

HOURS OF MISSING DATA:

505 ENTER (RETURN) CONTINUE, {SO) START OVER, [EX) TO EXIT 65

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