ML20117F906
| ML20117F906 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/31/1995 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20117F866 | List: |
| References | |
| NUDOCS 9605200302 | |
| Download: ML20117F906 (26) | |
Text
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PINGP 753, Rev. 6 Page 1 of 7 Retention: Life
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PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1/1/95-12/31/95 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT 1RRADIATED FUEL)
- 1. Solid Waste Total Volumes and Total Curie Quantities:
.. ? : a
- ' :- t.3 ;;; a r3, ;;: '; ::
a>
ll '; '. *!; S t.,,
.CONTAINERej e
_ J, n A A D cf,:'tg g/ c i1 o'; ' v i ;fERIODe '
3 EST. TOTAL'J f DISPOSAL *!
~',, cK TYPE'OF WASTE 9e#;
s UNITS.' lll~(0.00 E00)(';
$ (0.00 E00) *; (1 (LIST)?yr aVOlf(As.
TOTALS;c UERRORl%"
<l';f';'y'-':J,;
, r:2 C !,: j. '? b;J'd
's B
A. Resins m3 ft3 Ci 3
B. Dry-Compacted m
ft3 Cl 3
117 C. Non-Compacted m
ft3 4136 94 Ci 5.32E-01 2.50E+01 3
D. Filter Media m
ft3 Ci s
2.1 S. Other (furnish description) m ft3 75 7.5 011
- 1. m-w 2.50E+01 gj jMc The solid waste information provided in this report is the volume and
? NOTE @ _ L,s' activity of the low-level waste leaving the Prairie Island site. No A
allowance is made for off-site volume reduction prior to disposal.
96052003o2 960515 PDR ADOCK 05000282 R
PINGP 753, Rc v. 6 Page 2 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1/1/9s-12/11/95 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)(continued]
- 2. Principal Radionuclide Composition by Type of Waste:
(Bold letter designation from Page 1)
TYPE Percent (%)
Abundance Nuclide (0.00EO)
C
- Fe - 55 4.58E+01
- Ni - 63 2.57E+01 Co - 60 1.96E+01 Cs - 134 249E+00 Co - 58 1.72E+00 Mn - 54 1.60E+00 Cs - 137 J.60E+00
- C
- 14 5.14E-01 S
- H-3 7.80E+0 Cs - 137 1.!ir+01 Co - 60 7.35E+00
- Ni - 63 3.22E+00
- = Inferred - Not Measured on Site
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PINGP 753, Rav. 6 Page 3 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period:1/1/9s-12/31/95 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)[ continued]
- 2. Principal Radionuclide Composition by Type of Waste (Continuation):
(Bold letter designation from Page 1)
TYPE Percent (%)
Abundance Nuclide (0.00E0)
= Inferred - Not Measured on Site
PINGP 753, Rev. 6 Page 4 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period:1/1/95-12/31/95 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)(continued]
- 3. Solid Waste Disposition:
Number of Shloments Mode Destination 3
Truck SEG - Oakridee. TN 1
Truck DSSI - Oakridee. TN
L l
PINGP 753, Rav. 6 Page 5 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period:1/1/95-12/31/95 l
NORTHERN STATES POWER License No. DPR-42/60 i
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT l
SOLID. WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)[ continued]
- 4. Shipping Container and Solidification Method:
Disposal No.
Volume Activity Type of Container Solidif.
3 3
(Ft /m )
(Cl)
Waste Code Code 95-03 75/2.1 1.67E-03 S
L N/A 95-25 1410/39.9 3.01E-01 C
L N/A 95-26 1410/39.9 1.27E-01 C
L N/A 95-27 1316/37.3 1.03E-0T c
L ii/A TOTALS 4
4211/119 5.3 R CONTAINER CODES:
L = LSA (Shipment type)
A = Type A B = Type B O = Highway Route Controlled Quantity SOLIDIFICATION CODES:
C = Cement TYPES OF WASTES:
A = Resins B = Dy Compaded C = Non-Compacted D = Filter Media S = Other
PINGP 753, Rev. 6 Page 6 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1/1/95-12/31/95 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS B. IRRADIATED FUEL SHIPMENTS (DISPOSITION)
Number of Shloments Modt Destri.ation 0
PINGP 753, Rev. 6 Page 7 of 7 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Period: 1/1/95-12/31/95 NORTHERN STATES POWER License No. DPR-42/60 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS C. PROCESS CONTROL PROGRAM CHANGES TITLE:
Process Control Program for Solidification / Dewatering of Radioactive Waste from Liquid Systems 6
5/10/95 Current Revision Number:
Effective Date:
($d... ' ',
'c if the effective date of the PCP is within the period covered by this (NOTE: ~s1 report, then a description and justification of the changes to the PCP is required (T.S.6.5.D). Attach the sidelined pages to this report.
Changes / Justification:
Expand purpose section.
Remove / Update Technical Specifications references. Ensure PCP contains information which was previously incorporated in Tech. Specs.
Made minor cosmetic changes.
UPDATED P.I. OPNS l PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY RADIATION PROTECTION PROCEDURES t o-NUMBER:
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PROCESS CONTROL PROGRAM DS9 G'M s FOR SOLIDIFICATION / DEWATERING OF Rev:
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RADIOACTIVE WASTE FROM LIQUID 4
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.C. REVIEW DATE:
REVIEWED BY:
DATE:
APPROVED BY:
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l UPDATED P.I. OPNS l l
PRAIRIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY RADIATION PROTECTION PROCEDURES NUMBER:
TITLE
- f PROCESS CONTROL PROGRAM DS9
^
FOR SOLIDIFICATION / DEWATERING OF
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6 RADIOACTIVE WASTE FROM LIQUID SYSTEMS Page 5 of 27 1.0 GENERAL 1.1 Purpose The purpose of this Process Control Program (PCP) is to detail the means by which the dewatering and/or solidification of radioactive waste from liquid systems can be assured, in accordance with applicable federal regulations and other requirements governing the disposal of solid radioactive waste.
1.2 Scope This PCP includes the following processes:
1.2.1 Solidification of liquid waste concentrates.
1.2.2 Manual solidification of waste liquids.
1.2.3 Manual solidification of wet trash by submersion.
1.2.4 Processing of wet trash by compaction / cementation.
1.2.5 Dewatoring of bead resin.
1.2.6 Dewatering of powered resin.
1.2.7 Dewatering of spent filter elements.
1.2.8 In-container Solidification of Bead Resin.
1.2.9 Reporting Requirements.
1.3 Definitions 1.3.1 Batch A quantity of liquid waste concentrates (for example, the contents of 121 Waste Concentrates Tank) to be solidified. A batch of waste concentrates can normally be drummed in not more than two days.
l UPDATED P.I. OPNS l PRAlRIE lsLAND NUCLEAR GENERATING PLANT RADIATION PROTECTION PROCEDURES NORTHERN STATES POWER COMPANY NUMBER:
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g% g gp* * *d PROCESS CONTROL PROGRAM D59 A
TITLE s
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FOR SOLIDIFICATION / DEWATERING OF REv:
6 ggd5Phe RADIOACTIVE WASTE FROM LIQUID EDWMD_. p?
SYSTEMS Page 6 of 27 1.3.2 Solidification The conversion of wet radioactive wastes into a form that meets shipping and disposai requirements.
l 1.3.3 Dewatering The process of removing water from a substance to meet specific limits.
2.0 SOLIDIFICATION OF LIQUID WASTE CONCENTRATES 2.1 Purpose To establish the process parameters which provide reasonable assurance of complete solidification of liquid waste concentrates.
2.2 Applicability This section of the PCP is applicable to solidification of liquid waste concentrates using the Atcor Solidification System and related equipment.
2.3 Beierences 2.3.1 C21.2.1 Solid Radioactive Waste Operating Procedure 2.3.2 C21.2.2 Trash Compactor Operation Operating Procedure
2.4 System Description
2.4.1 General Descriotion The solidification system for liquid waste concentrates includes 121 Waste Concentrates Tank (WCT), the Atcor Solidification System and related pumps, piping and equipment. Concentrates are accumulated from the 5 GPM ADT evaporator or the 2 GPM waste evaporator and stored in 121 WCT.
When a sufficient quantity exists in 121 WCT, the contents are transferred to the Atcor system for solidification in approved containers. The filled containers are held in the Atcor Drum Storage Aisles until solidification can be confirmed. The containers are then capped, deconned, and surveyed prior to storage for subsequent shipment and disposal. A flow diagram is shown on Figure 1.
1 UPDATED P.I. OPNS PRAIRIE lsLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY RADIATloN PROTECTION PROCEDURES TITLE NUMBER:
- e' PROCESS CONTROL PROGRAM DS9 Ml FOR SOLIDIFICATION / DEWATERING OF
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6
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RADIOACTIVE WASTE FROM LIQUID W "2 SYSTEMS Page 15 of 27 l
5.0 MANUAL SOLIDlFICATION OF WET TRASH BY SUBMERSION l
5.1 Purpose To establish parameters which provide reasonable assurance of complete solidification of liquid contained in wet trash.
5.2 Applicability This section of the PCP is applicable to solidification of wet trash with masonry cement.
Wet trash includes contaminated material such as mopheads, wet rags, paper towels, etc.
5.3 Sequence of Operation 1
5.3.1 Place desired amount of liquid in an approved container (normally / to / full).
1 2
2 3
ENOfE.2!
Contaminated liquids may be used for this purpose.
5.3.2 Commence mixing.
5.3.3 Add cement while continuing to mix at the rate of 1 cu. ft. (one bag) per 6.25 gal of liquid or until the mixture begins to thicken. Continue to mix until all of the cement is incorporated and the mixture is smooth. Remove the mixer (if applicable).
5.3.4 Immerse items of wet trash into the cemented mass using a stick or similar device. Attempt to put as many items of trash as possible into the container within the limits of ALARA.
5.4 Cure Time i
Solidification can normally be expected within two to three days.
UPDATED P.I. OPNS PRA!RIE ISLAND NUCLEAR GENERATING PLANT NORTHERN STATES POWER COMPANY RADIATION PROTECTION PROCEDURES TITLE NUMBER:
PROCESS CONTROL PROGRAM DS9 D'm FOR SOLIDIFICATION / DEWATERING OF REv:
6 us h RADIOACTIVE WASTE FROM LIQUID
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SYSTEMS Page 23 of 27 11.3 References 11.3.1 T.S.6.5.D Prairie Island Nuclear Plant Technical Specification.
l 11.3.2 Waste Form Technical Position, Revision 1. United States Nuclear Regulatory Commission.
11.3.3 STD-P-05-004 Process Control Program for Incontainer Solidification of Bead Resin. Scientific Ecology Group (SEG), Inc.
i 11.4 PCP Revisions Whenever the PCP is revised or changed, a description of the changes AN_Q j
justifications SHALL be included in the Annual Radioactive Effluent Release Report.
11.5 Reports of Mishaps Waste form mishaps SHALL be reported to the NRC (Director of the Division of Low-Level Waste Management and Decommissioning) AND the designated State disposal site regulatory authority within 30 days of knowledge of the incident. Mishaps are defined as failure of misuse of stabilized waste forms or containers that provide stability (HIC's). Such mishaps include, but are not necessarily limited to, the following:
11.5.1 The failure of high integrity containers used to ensure structural stability.
11.5.2 The misuse of high integrity containers, as evidenced by excessive free liquid, or excessive void space within the container.
11.5.3 Production of a solidified Class B or Class C waste form that exhibits any of the characteristics listed in the Waste Form Technical Position, Revision 1.
4 11.6 PCP Specimen Summary Reports Whenever cement stabilization (as defined by 10 CFR 61) of low-level waste is necessary, PCP test specimens are required for verification and surveillance.
Verification specimens are intended to provide assurance that the formulations used in the qualification testing program correspond to those actually used in the field.
Surveillance specimens are intended to provide verification that the waste forms remain stable with time. A summary report SHALL be prepared annually and submitted to the NRC (Director, Division of Low-Level Waste Management and Decommissioning) documenting the results of tests performed on the cement-stabilized waste form surveillance specimens during the calendar year.
i 1
NORTHERN. STATES POWER COMPANY j
PRAIRIE ISLAND NUCLEAR GENERATING PLANT OFF-SITE RADIATION DOSE ASSRRSMENT FOR 4
l January throuch' December 1995 An Assessment of the radiation dose due to the release from Prairie Island Nuclear Generating Plant during 1995 was performed in accordance with the Technical Specifications.
Computed doses were well below the 40 CFR Part 190 Standards and 10 CFR Part 50 Appendix I Guidelines.
)
Off-site dose calculation formulas and meteorological data from the l
-Off-site Dose Calculation Manual were used in making this assessment.
i Source terms were obtained f rom the Annual Radioactive Effluent and i
Waste Disposal Report prepared for NRC review for the year of 1995.
j i
l 9ff-site Doses from Gaseous Release Computed doses due to gaseous releases are reported in Table 1.
i Critical Receptor location and pathways for organ doses are reported in -
l Table 2.
Doses are a small percentage of Appendix I Guidelines.
i y-Off-site Doses from Liould Release i
Computed doses due to Liquid releases are reported in Table 1.
Receptor information is reported in' Table 2.
Doses,.both whole body j
and organ, are a small percentage of Appendix I Guidelines.
Doses to Individuals Due to Activities Inside the Site-Boundarv
-Occasionally sportsmen enter the Prairie. Island site for recreational activities.
These individuals are not expected to spend more than a few hours per year-within the site boundary.
Commercial and recreational river traffic exists through this area.
For purposes of estimating the dose due to recreational and river water transportation activities within the site boundary, it is assumed that the limiting dose within the site boundary would be received by an I
individual who spends a total of seven days per year on the river just off shore from the plant buildings (ESE at 0.2 miles).
The gamma dose i
from noble gas releases and the whole body and organ doses from the j
inhalation pathway due to Iodine 131, Iodine-133, tritium and long lived particulates were calculated for this location and occupancy time.
These doses were reported in Table 1.
Doses to Individuals Due to Effluent Releases from the ISFSI Construction of the ISFSI is completed and tha radiation monitors are in place and functional.
Three loaded fuel casks were placed in the storage facility during the 1995 calendar year and there has been no release of radioactive effluents from the ISFSI.
O Doses to Most Exposed Member of the General Public from Reactor Release and Other Uranium Fuel Cycle Sources There are no other uranium fuel facilities in the vicinity of the Prairie Island site.
The only other artificial source of exposure to the general public in addition to the plant effluent releases is from direct radiation of the reactors.
This direct radiation from pressurized water reactors has been shown to be negligible.
An array of TLD monitoring stations around the perimeter of the site boundary has consistently indicated that plant operation in the past years has no effect on ambient gamma radiation.
Therefore, the most exposed member of the general public will not receive an annual radiation dose f rom reactor effluent releases and all other fuel cycle activities in excess of the sum of the liquid and i
gaseous whole body and organ doses reported in Table 1 for the site boundary and critical :. e c e p t o r, respectively.
These doses are well below 40 CFR Part 190 standards of 25 mrem to the whole body, 75 mrem to the thyroid, and 25 mrem to any other organ.
1 Radiation Environmental Monitorina Procram Samplina Deviations There were no milk or vegetable sampling deviations during this reporting period.
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i l
l Table 1 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND PERIOD:
JANUARY throuah DECEMBER 1995 I
i 10 CFR Part 50 Appendix I Guidelines per 2-units site per year Gaseous Releases Maximum' Site Boundary Gamma Air Dose (mrad) 3.38E-02 20 Maximum Site Boundary Beta Air Dose (mrad) 1.03E-01 40 Maximum Off-site Dose to any organ (mrem)*
1.21E-01 30 Offshore Location Gamma Dose (mrad) 1.28E-01 Total Body (mrem)*
1.85E-01 Organ (mrem)*
2.24E-01 30 i
Liould Releases
]
Maximum Off-site Dose Total Body (mrem) 4.39E-03 6
Maximum Off-site Dose Organ - GI-LLI (mrem) 8.60E-03 20 Limiting Organ Dose Organ - Total Body 4.39E-03 6
I Table 2 OFF-SITE RADIATION DOSE ASSESSMENT - PRAIRIE ISLAND SUPPLEMENTAL INFORMATION PERIOD: JANUARY throuch DECEMBER 1995 1
Gaseous Releases Maximum Site Boundary Dose Location j
(from Building Vents)
Sector WNW Distance (miles) 0.4 Offshore Location Within Site Boundary l
Sector ESE Distance (miles) 0.2 Pathway Inhalation Maximum Off-site Sector SSE Distance (miles) 0.6 Pathways
- Plume,
- Ground, Inhalation, Vegetables Age Group Child Liould Releases Maximum Off-site Dose Location Downstream Pathway Fish i
l l
l
1995 Annual Rcdioactivo Effluont Report REV. O Page 1 of 10 Retention: Lifetime ANNUAL RADIOACTIVE EFFLUENT REPORT 02-JAN-95 THROUGH 31-DEC-95 SUPPLEMENTAL INFORMATION Facility:
Prairie Island Nuclear Generating Plant Licensee:
Northern States Power Company License Numbers: DPR-42 & DPR-60 A. Regulatory Limits 1.
Liquid Effluents:
a.
The dose or dose ccmmitment to an individual from radioactive materials in liquid effluents released from the site shall be limited to:
for the quarter 3.0 mrem to the total body 10.0 mrem to any organ for the year 6.0 mrem to the total body 20.0 mrem to any organ 2.
Gaseous Effluents:
a.
The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to:
noble gases s 500 mrem / year total body s3000 mrem / year skin I-131, I-133, H-3, LLP sl500 mrem / year to any organ b.
The dose due to radioactive gaseous effluents released from the site shall be limited to:
noble gases s10 mrad / quarter gamma
$20 mrad / quarter beta s20 mrad / year gamma s40 mrad / year beta I-131, I-133, H-3, LLP s15 mrem / quarter to any organ
$30 mrem / year to any organ l
.. ~ -
1995 ANNUAL RADIOACTIVE EFFLUENT REPORT REV. O PAGE 2 B.
Maximum Permissible Concentration 1.
Fission and activation gases in gaseous releases:
OLD 10 CFR 20, Appendix B, Table 2, Column 1 2.
Iodine and particulates with half lives greater than 8 days in gaseous releases:
OLD 10 CFR 20, Appendix B, Table 2, Column 1 3.
Liquid effluents for radionuclides other than dissolved or entrained gases:
OLD 10 CFR 20, Appendix B, Table 2, Column 2 4.
Liquid effluent dissolved and entrained gases:
2.0E-04 uCi/ml Total Activity C.
Average Energy Not applicable to Prairie Island regulatory limits.
1 D.
Measurements and approximations of total activity 1.
Fission and activation gases Total GeHP 25%
in gaseous releases:
Nuclide GeHP 2.
Iodines in gaseous releases:
Total GeHP 25%
Nuclide GeHP 3.
Particulates in gaseous releases:
Total GeHP 25%
Nuclide GeHP 4.
Liquid effluents Total GeHP 25%
Nuclide GeHP 1
E.
Manual Revisions 4
1.
Offsite Dose Calculations Manual latest Revision number:
13 l
Revision date 30-JAN-96 i
- ea d
1995 ANNUAL RADIOACTIVE BFFLUENT REPORT REV. O PAGE 3 1.0 BATCH EELEAERS (LIQUID)
QTR 01 QTR 02 QTR 03 QTR 04 1.1 NUMBER OF BATCH RELEASES 3.00E+01 8.50E+01 4.90E+01 6.00E+01 1.2 TOTAL TIME PERIOD (HRS) 4.53E+01 1.175+02 7.00E+01 1.07E+02 f
1.3 MAXIMUM TIME PERIOD (HRS) 2.98E+00 3.02E+00 2.55E+00 3.42E+00 1.4 AVERADE TIME PERIOD (HRS) 1.51E+00 1.38E+00 1.43B+00 1.78E+00 1.5 MINIMUM TIME PERIOD (HRS) 8.703-01 9.20E-01 1.05E+00 1.42E+00 1.6 AVERAGE MISSISSIPPI RIVER FLOW (CFS) 1.69E+04 4.13E+04 2.54E+04 2.64E+04 2.0 BATCH RELEASES (GASEOUS)
QTR 01 QTR 02 QTR 03 QTP: 01 2.1 NUMBER OF BATCH RELEASE 0 0.00E+00 3.30E+01 2.00E+00 1.00E+00 2.2 TOTAL TIME PERIOD (HRS) 0.00E+00 4.64E+02 3.00E-02 1.00R-02 2.3 MAXIMUM TIME PERIOD (MRS) 0.00E+00 2.50E+01 2.00E-02 1.00E-02 2.4 AVERAGE TIME PERIOD (HRS) 0.00E+00 1.41E+01 1.50E-02 1.00E-02 2.5 MINIMUM TIME PERIOD (HR3) 0.00E+00 2.00E-02 1.005-02 1.00E-02 i
I 3.0 ABWORMAL RELEASES (LIQUID) l l
QTR 01 QTR 02 QTR 03 QTR 04 3.1 NUMBER OF RELEASES 0.00B+00 0.00E+00 3.00E+00 0.00E+00 3.2 TOTAL ACTIVITT RELEASED (CI) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.3 TOTAL TRITIUM RELEASED (CI) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.0 ABBORMAL RELEASEE (GASEOUS)
QTR 01 QTR 02 QTR 03 QTR 04 4.1 NUMBER OF RELEASES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4.2 TOTAL ACTIVITY RELEASED (CI) 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
1995 ANNUAL RADICACTIVJ CFFLUENT CEPIRT ELV. O PATO 4 TAXLE 1A CASE 0US EFFLUENTS - SUMMATION OF ALL RELEASES QTR 01 QTR 02 QTR 03 QTR: 04 5.0 FIEEION AND ACTIVATION GAEEE 5.1 TOTAL RELEASE (CI) 2.00E+01 6.40E+01 0.00B+00 0.00E+00 5.2 AVERAGE RELEASE RATE (UCI/SEC) 2.54E+00 8.14E+00 0.00E+00 0.00E+00 5.3 GAMMA DOSE (MRAD) 7.59E-03 2.625-02 0.00E+00 0.00E+00 1
5.4 BETA DOSE (MRAD) 2.263-02 8.00E-02 0.00E+00 0.00E+00 5.5 PERCENT OF GAMMA TECH SPEC (%)
7.59E-02 2.62E-01 0.00E+00 0.00E+00 5.6 PERCENT OF BETA TECH SPEC (%)
1.13E-01 4.00E-01 0.00E+00 0.00E+00 6.0 IODINEE 6.1 TOTAL I-131 (CZ) 0.00E+00 5.18E-04 4.83E-06 0.00E+00 6.2 AVERAGE RELEASE RATE (UCI/SEC) 0.00E+00 6.59E-05 6.15E-05 0.00E+00 7.0 PARTICULATEE 7.1 TOTAL RELEASE (CI) 1.90E-08 9.13E-07 4.375-05 0.00E+00 7.2 AVERAGE RELEASE RATE (UCI/SEC) 2.42E-09 1.165-07 5.563-06 0.00E+00 8.0 TRITIUM 8.1 TOTAL RELEASE (CI) 9.40E+00 1.27E+01 1.18E+01 5.42E+00 8.2 AVERAGE RELEASE PATE (UCI/SEC) 1.20E+00 1.62E+00 1.50E+00 6.90E-01 9.0 TOTAL IODINE, PARTICULATE AND TRITIUM (UCZ/SEC) 1.20E+00 1.62E+00 1.50E+00 6.90E-01 10.0 DOSE (MREM) 1.69E-02 7.25E-02 2.17E-02 9.75E-03 11.0 PERCENT OF TECH SPEC (%)
1.13E-02 4.83E-02 1.45E-02 6.50E-03 L2.0 CROSS ALPHA (CI' 2.54E-08 0.00E+00 6.46E-09 0.00E+00
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1995 ANNUAL RADICACTIV3 EFFLUENT R2P2RT REV. O PAD 3 7 TAILD 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES QTR 01 QTR 02 QTR 03 QTR 04 16.0 VOLUME OF WASTE PRIOR TO DILUTION (LITERS) 5.16E+07 8.573+07 5.20E+07 9.40E+07 17.0 VOLUME OF DILUTION WATER (LITERS) 1.83E+11 9.57E+10 2.74E+11 i.83E+11
.I 18.0 FISSION AND ACTIVATION PRODUCTE 18.1 TOTAL RELEASE W/O M-3, RADGAS, ALPHA (CI) 4.383-02 1.515-01 1.85E-01 6.63E-02 18.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 2.39E-10 1.583-09 6.75E-10 3.62*.-10 19.0 TRITIUM 19.1 TOTAL RELEASE (CI) 1.66E+02 2.29E+02 1.54E+02 2.32E+02 19.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 9.07E-07 2.393-06 5.62E-07 1.27E-06 20.0 DISSOLVED AND BWTRAINED GAERS 20.1. TOTAL RELEASE (CI) 3.823-02 4.395-01 1.15E-03 5.55E-04 20.2 AVERAGE DILUTED CONCENTRATION (UCI/ML) 2.09E-10 4.59E-09 4.205-12 3.035-12 21.0 GROSS ALPHA (CZ) 9.173-05 3.005-04 0.00E+00 0.00E+00 22.0 TOTAL TRITIUM, FISSION AND ACTIVATION PRODUCTS (UCI/ML) 9.073-07 2.40E-06 5.635-07 1.27E-06 23.0 TOTAL BODY DOSE (MREM) 4.48E-04 1.443-03 7.21E-04 1.78E-03 24.0 CRITICAL ORGAN 24.1 DOSE (MREM) 4.483-04 1.443-03 2 91E-03 1.78E-03 24.2 ORGAN TOT BODY TOT BODY GI TRACT TOT BODY 25.0 PERCEMT OF TOTAL BODY TECH SPEC LIMIT (%)
1.495-02 4.80E-02 9.70E-02 5.93E-02 26.0 PERCENT OF CRITICAL ORGAN TECH SPEC LIMIT (%)
1.493-03 4.80E-02 2.915-02 5.93E-02
.__m.
m 1995 ANNUAL RADICACTIV3 CFFLUENT CT,POf.T COV. O PA*IJ 8 TA%LB 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 27.0 INDIVIDUAL LIQUID EFFLUENT CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR 01 QTR 02 QTRs.03 QTRt 04 QTR 01 QTR: 02 QTR: 03 QTR 04 6
AG-110M CI 2.575-03 9.21E-03 2.24E-02 8.88E-03 l
BE-7 CI 1.78E-04 BA-139 CI 6.81E-06 BR-92 CI 6.24E-06 CE-139 CI 1.14E-06 CO-57 CI 2.855-05 6.77E-05 4.39E-05 6.20E-05 CO-58 CI 1.20E-04 6.43E-04 3.38E-03 6.19E-02 2.66E-02 1.545-02 CO-60 CI 3.32E-05 7.25E-03 1.27E-02 9.86E-03 8.81E-03 CR-51 CI 6.07E-05 1.42E-02 2.125-02 1.69E-03 CS-134 CI 7.83E-06 7.445-06 4.15E-06.
7.03E-05 CS-137 CI 1.56E-04 1.84E-05 1.43E-05 2.17E-04 FE-55 C1 1.62E-03 6.56E-03 1.77E-04 2.49E-02 3.65E-02 6.15E-02 1.19E-02 FE-59 CI 8.71E-05 7.09E-04 7.385-03 7.97E-05 I-131 CI 3.87E-05 5.63E-04 2.64E-05 LA-140 CI 3.85E-05 MN-54 CI 2.93E-04 6.62E-04 5.673-04 5.375-04 NA-24 CI 2.62E-06 6.87E-06 NB-95 CI 4.31E-04 1.09E-03 3.82E-03 3.03E-03 NB-97 CI 4.84E-06 4.46E-06 1.518-05 7.98E-06 6.44E-07 ND-147 CI 1.77E-06 RU-105 CI 6.013-05 i
35-124 CI 7.51E-05 5.57E-03 8.14E-03 3.18E-03 SB-125 CI 2.25E-03 5.55E-03 7.81E-03 8.89E-03 CONTINUED
1995 AWUAL RADIDACTIV"J CFFLULNT REP 3%,T COV. O P A7,"3 9 TAILD 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES INDIVIDUAL LIQUID EFFLUENT (COETINUED)
CONTINUOUS MODE BATCH MODE NUCLIDE UNITS QTR 01 QTRs 02 QTRt 03 QTR: 04 QTRs 01 QTR: 02 QTR: 03 QTRs 04 8
SB-126 CI 1.54E-05 l
SC-47 CI 4.27E-05 1.53E-04 6.575-04 2.473-04 SN-113 CI 4.252-04 5.693-04 4.96E-03 5.90E-04 SR-85 CI 2.873-06 4.45E-06 SR-90 CI 1.61E-06 SR-92 CI 3.333-06 4.22E-05 3.345-05 1.033-05 TC-99M CI 3.59E-05 W-187 CI 8.49E-05 2.593-05 2N-65 CI 9.83E-06 5.57E-05 1.60E-04 1.14E-04 2R-95 CI 2.37E-04 6.22E-04 2.553-03 1.75E-03 2R-97 CI 2.07E-06 4.44E-06 1.54E-06 2.63E-06 TOTAL CI 1.62E-03 3.62E-04 6.565-03 8.20E-04 4.22E-02 1.51E-01 1.78E-01 6.553-02
1995 ANNUAL RADICACTIV3 EFFLUDIT RXPCCT CEV. O PAID 10 TA2LD 2A LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES (CONTINUED)
. 28.0 DISSOLVED AND ENTRAINED GASES CONTINUOUS MODE BATCH MODE NUCLIDE UNITS
.QTR 01 QTR 02 QTR 03 QTR 04 QTR 01 GTR 02 QTR 03 QTR 04-RR-85 CI 6.635-04 1.03E-03 i
XE-131M C1 1.143-03 1.02E-02 4.28E-04 I"'
XE-133 CI 1.78E-04 3.63E-02 4.14E-01 7.23E-04 5.53E-04 XE-133M CI 7.30E-05 2.883-03 XE-135 CI 2.49E-05 2.073-04 1.74E-06 XE-135M CI 1.853-05 XE-137 CI 1.06E-02 TOTAL CI 0.00E+00 1.78E-04 0.00E+00 0.00E+00 1.825-02 4.39E-01 1.15E-03 5.553-04
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