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-NOTICETHE ATTACHED FILES ARE OFFICIAL RECORDS OF THE INFORMATION & REPORTS MANAGEMENT BRANCH. THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME PERIOD AND MUST BE RETURNED TO THE RECORDS & ARCHIVES SERVICES SECTION P1-22 WHITE FLINT PLEASE DO NOT SEND DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVAL OF ANY PAGE(S) FROM DOCUMENT FOR REPRODUCTION MUST BE REFERRED TO FILE PERSONNEL.
-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
2 of 8 12 10/23/90
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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
5 of 8 15 10/23/90
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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
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-2i I
I I -
PROCESS CONTROL PROGRAM FOR LIQUIDS
AND WET RADIOACTIVE MATERIAL
PRCP-B
Revision 1
October 23, 1990
Duane Arnold Energy Center
Iowa Electric Light and Power Company
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
3 of 7 21 10/23/90
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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.
Essential Waste 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 (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
for Packaging and Transporting Radioactive Materials.
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: (
1. DAEC Radwaste Handling Procedures
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
Duane Arnold Energy Center
Iowa Electric Light and Power Company
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.
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
5 of 7 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 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
1.0 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
PROCESS CONTROL PROGRAM FOR DEWATERING
WET RADIOACTIVE SOLID WASTE
IN CARBON STEEL LINERS
PRCP-E
Revision 2
October 23, 1990
Duane Arnold Energy Center
Iowa Electric Light and Power Company
(.
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
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
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:
1. Sealing components,
2. Exterior 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
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.
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 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
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 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
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.
6 of 8
38 10/23/90 Rev. 2
PRCP-E
References C
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".
(
(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) .
PROCESS CONTROL PROGRAM FOR DEWATERING
MECHANICAL CARTRIDGE
AND BAG FILTERS
IN HIGH INTEGRITY CONTAINERS
OR CARBON STEEL LINERS
PRCP-F
Revision 1
October 23, 1990
Duane Arnold Energy Center
Iowa Electric Light and Power Company
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
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 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 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
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 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:
1. Sealing components,
2. Exterior surface,
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.
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 compliance with 1OCFR71 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 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
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 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
HOURS AT EACH WIND SPEED AND DIRECTION
M OD OF RECORD = 90010101-90123124
STABILITY CLASS: B DT/DZ
ELEVATION: SPEED:WS33 DIRECTION:WD33 LAPSE:DEL T
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
PERIODS OF CALM(HOURS): 127
VARIABLE DIRECTION 0
HOURS OF MISSING DATA: 496
ENTER: (RETURN] CONTINUE, [SO] START OVER, [EX] TO EXIT
51
02/22/91 10:39
SITE: DUANE ARNOLD
HOURS AT EACH WIND SPEED AND DIRECTION
M OD OF RECORD = 90010101-90123124
STABILITY CLASS: C DT/DZ
ELEVATION: SPEED:WS33 DIRECTION:WD33 LAPSE:DEL T
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
PERIODS OF CALM(HOURS): 127
VARIABLE DIRECTION 0
HOURS OF MISSING DATA: 496
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
HOURS AT EACH WIND SPEED AND DIRECTION
W OD OF RECORD = 90010101-90123124
STABILITY CLASS: D DT/DZ
ELEVATION: SPEED:WS33 DIRECTION:WD33 LAPSE:DEL T
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
PERIODS OF CALM(HOURS): 127
VARIABLE DIRECTION 0
HOURS OF MISSING DATA: 496
ENTER: [RETURN] CONTINUE, [SO] START OVER, [EX] TO EXIT
53
SITE:, DUANE ARNOLD
HOURS AT EACH WIND SPEED AND DIRECTION
OD OF RECORD = 90010101-90123124
STABILITY CLASS: E DT/DZ
ELEVATION: SPEED:WS33 DIRECTION:WD33 LAPSE:DEL T
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
VARIABLE DIRECTION 0
HOURS OF MISSING DATA: 496
ENTER: [RETURN] CONTINUE, (SO] START OVER, [EX] TO EXIT
54
02/22/91 10:41
SITE: DUANE ARNOLD
HOURS AT EACH WIND SPEED AND DIRECTION
M OD OF RECORD = 90010101-90123124
STABILITY CLASS: F DT/DZ
ELEVATION: SPEED:WS33 DIRECTION:WD33 LAPSE:DEL T
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
PERIODS OF CALM(HOURS): 127
VARIABLE DIRECTION 0
HOURS OF MISSING DATA: 496
ENTER: [RETURN] CONTINUE, [SO] START OVER, [EX] TO EXIT
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
ELEVATION: SPEED:WS33 DIRECTION:WD33 LAPSE:DEL T
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
PERIODS OF CALM(HOURS): 127
VARIABLE DIRECTION 0
HOURS OF MISSING DATA: 496
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
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
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
-----------------------------------------------------------------
PERIODS OF CALM(HOURS): 127
VARIABLE DIRECTION 0
HOURS OF MISSING DATA: 496
ENTER: [RETURN] CONTINUE, [SO] START OVER, [EX] TO EXIT
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
ELEVATION: SPEED:WS156 DIRECTION:WD156 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 >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 -----------------------------------------------------------------
PERIODS OF CALM(HOURS): 73
VARIABLE DIRECTION 0
HOURS OF MISSING DATA: 505
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
ELEVATION: SPEED:WS156 DIRECTION:WD156 LAPSE:DEL T
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
ENTER: [RETURN] CONTINUE, [SO] START OVER, [EX] TO EXIT
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
HOURS AT EACH WIND SPEED AND DIRECTION
M OD OF RECORD = 90010101-90123124
STABILITY CLASS: C DT/DZ
ELEVATION: SPEED:WS156 DIRECTION:WD156 LAPSE:DEL T
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
----------------------------------------------
PERIODS OF CALM(HOURS): 73
VARIABLE DIRECTION 0
HOURS OF MISSING DATA: 505
ENTER: [RETURN] CONTINUE, (SO] START OVER, [EX] TO EXIT
60
I
02/22/91 10:58
SITE: DUANE ARNOLD
HOURS AT EACH WIND SPEED AND DIRECTION
W OD OF RECORD = 90010101-90123124
STABILITY CLASS: D DT/DZ
ELEVATION: SPEED:WS156 DIRECTION:WD156 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
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
VARIABLE DIRECTION 0
HOURS OF MISSING DATA: 505
ENTER: [RETURN] CONTINUE, [SO] START OVER, [EX] TO EXIT
61
02/22/91 10:59
SITE:.DUANE ARNOLD
HOURS AT EACH WIND SPEED AND DIRECTION
M OD OF RECORD = 90010101-90123124
STABILITY CLASS: E DT/DZ
ELEVATION: SPEED:WS156 DIRECTION:WD156 LAPSE:DEL T
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
VARIABLE DIRECTION 0
HOURS OF MISSING DATA: 505
ENTER: [RETURN] CONTINUE, [SO] START OVER, [EX] TO EXIT
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
HOURS AT EACH WIND SPEED AND DIRECTION
WOD OF RECORD = 90010101-90123124
STABILITY CLASS: F DT/DZ
ELEVATION: SPEED:WS156 DIRECTION:WD156 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 >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
PERIODS OF CALM(HOURS): 73
VARIABLE DIRECTION 0
HOURS OF MISSING DATA: 505
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
HOURS AT EACH WIND SPEED AND DIRECTION
M OD OF RECORD = 90010101-90123124
STABILITY CLASS: G DT/DZ
ELEVATION: SPEED:WS156 DIRECTION:WD156 LAPSE:DEL T
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 -----------------------------------------------------------------------
PERIODS OF CALM(HOURS): 73
VARIABLE DIRECTION 0
HOURS OF MISSING DATA: 505
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
ELEVATION: SPEED:WS156 DIRECTION:WD156 LAPSE:DEL T
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 ------------------------------------------------------------------------
PERIODS OF CALM(HOURS): 73
VARIABLE DIRECTION 0
HOURS OF MISSING DATA: 505
ENTER: [RETURN] CONTINUE, [SO] START OVER, [EX] TO EXIT
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
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