ML17059A917
| ML17059A917 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/30/1995 |
| From: | NIAGARA MOHAWK POWER CORP. |
| To: | |
| Shared Package | |
| ML17059A918 | List: |
| References | |
| NUDOCS 9509050233 | |
| Download: ML17059A917 (42) | |
Text
NINE MILE POINT NUCLEAR STATION - UNIT 1 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY - JUNE 1995 NIAGARAMOHAWKPOWER CORPORATION 9509050233 950828 PDR ADOCK 05000220 R
Page 1 of 2 NINE MILEPOINT NUCLEAR STATION - UNIT 1 SEMI-ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT JANUARY-JUNE 1995 SUPPLEMENTAL INFORMATION
~Fa i~li:
Nine Mile Point Unit¹I L~i~ns:
Niagara Mohawk Power Corporation TECHNICALSPECIFICATION LIMITS A)
FISSION AND ACTIVATIONGASES 1.
The dose rate limitof noble gases from the site to areas at and beyond the site boundary shall be less than or equal to 500 mrem/year to the total body and less than or equal to 3000 mrem/year to the skin.
2.
The air dose due to noble gases released in gaseous effluents from the Nine Mile Point 1 Station to areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 5 milliroentgen for gamma radiation and less than or equal to 10 mrad for beta radiation and during any calendar year to less than or equal to 10 milliroentgen for gamma radiation and less than or equal to 20 mrad for beta radiation.
B8cC) TRITIUM,IODINES AND PARTICULATES, HALFLIVES ) 8 DAYS 1.
The dose rate limitof Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half-lives greater than eight days, released to the environs as part of the gaseous effluents from the site, shall be less than or equal to 1500 mrem/year to any organ.
2.
The dose to a member of the public from Iodine-131, Iodine-133, Tritium and all radionuclides in particulate form with half lives greater than eight days as part of gaseous effluents released from the Nine Mile Point 1 Station to areas at and beyond the site boundary shall be limited during any calendar quarter to less than or equal to 7.5 mrem to any organ and, during any calendar year to less than or equal to 15 mrem to any organ.
D)
LIQUIDEFFLUENTS 1.
The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E~ microcuries/ml total activity.
2.
The dose or dose commitment to a member of the public from radioactive materials in liquid effluents released from Nine Mile Point Unit 1 to unrestricted areas shall be limited during any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ, and during any calendar year to less than or equal to 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
Page 2 of 2 MEASUREMENTS AND APPROXIMATIONSOF TOTALRADIOACTIVITY Described below are the methods used to measure or approximate the total radioactivity and radionuclide composition in effluents.
A)
FISSION AND ACTIVATIONGASES Noble gas effluent activity is determined by on-line gamma spectroscopic monitoring (intrinsic germanium crystal) or gross activity monitoring (calibrated against gamma isotopic analysis of a 4.0L Marinelli grab sample) of an isokinetic stack sample stream.
B)
IODINES Iodine effluent activity is determined by gamma spectroscopic analysis (at least weekly) of charcoal cartridges sampled from an isokinetic stack sample stream.
C)
PARTICULATES Activityreleased from the main stack is determined by gamma spectroscopic analysis (at least weekly) of particulate filters sampled from an isokinetic sample stream.
For emergency condenser vent releases, effluent curie quantities are estimated based on the isotopic distribution in the Condensate Storage Tank water and the Emergency Condenser shell water.
Actual isotopic concentrations are found via gamma spectroscopy.
Initial release rates of Sr-89, Sr-90 and Fe-55 are estimated by applying scaling factors to release rates of gamma emitters.
For emergency condenser vent
- releases, the activity ofTritium released during normal operation or during batch releases is conservatively estimated by multiplying recent condensate storage tank H-3 activity by assumed steaming rates out the vents.
D)
TRITIUM Tritium effluent activity is measured by liquid scintillation or gas proportional counting of monthly samples taken with an air sparging/water trap apparatus.
E)
LIQUIDEFFLUENTS Isotopic contents of liquid effluents are determined by isotopic analysis of a representative sample of each batch and composite analysis of non-gamma emitters.
F)
SOLID EFFLUENTS Isotopic contents of waste shipments are determined by gamma spectroscopy and water content analyses of a representative sample of each batch.
Scaling factors established from primary composite sample analyses conducted off-site are applied, where appropriate, to find estimated concentration of non-gamma emitters.
For low activity trash shipments, curie content is estimated by dose rate measurement and application of appropriate scaling factors.
ATTACHMENT1 Summary Data Page 1 Of 2 Unit1 X
Unit 2 Uquld Effluents:
Reporting Period Janus
- June 1995 10CFR20, Appendix B, Table ll, Column 2 Average MPC - uCi/ml (Qtr. +1
~
~NA Average MPC - uCi/ml (Qtr. 2) a
~NA Average Energy (Fission and Activation gases - Mev):
Qtr. 1 Qtr. 2 Ey I 1.67E-01 Ei ~ 2.45E-01 Ey
~ O.OOE+00 E> ~
O.OOE+00 Liquid: There were no liquid releases during the reporting period.
Number of batch releases Total time period for batch releases (hrs) 0
~NA Maximum time period for a batch release (hrs):
~NA Average time period for a batch release (hrs):
~NA Minimum time period for a batch release (hrs):
~NA Total volume of water used to dilute the liquid effluent during release period (L)
NIA Total volume of water used to dilute the liquid effluent during reporting period (L) 1.93E+ 11 UNIT 1 /OIy/.YJ Gaseous (Emergency Condenser Vent):
There were no releases from the operation of the emergency condenser vent.
Number of batch releases Total time period for batch releases (hrs) 0 NIA Maximum time period for a batch release (hrs):
N/A Average time period for a batch release (hrs):
~NA Minimum time period for a batch release (hrs)
N/A Gaseous (Primary Containment Purge):
Number of batch releases Total time period for batch releases (hrs) 8.00E+ 00 Maximum time period for a batch release (hrs)
Average time period for a batch release (hrs) 8.00E+ 00 8.00E+ 00 Minimum time period for a batch release (hrs) 8.00E+ 00
0
ATTACHMENT 1 Summary Data Page 20f 2 Unit 1 X
Unit 2 Abnormal Releases:
There were no abnormal releases during the reporting period.
A.
Liquids:
Reporting Period Janus
- June 1995 Number of releases 0
B.
Gaseous:
Total activity released
~NA Ci Number of releases 0
Total activity released
~NA Ci
ATTACHMENT2 Unit 1 X
Unit 2 Reporting Period Janus
- June 1995 GASEOUS EFFLUENTS - SUMMATIONOF ALLRELEASES, ELEVATEDAND GROUND LEVEL 1
QUARTER'w EST. TOTAL QUARTER ERROR C.
E.
Fission & Activation ases 1.
Total release 2.
Average release rate lodines 1.
Total iodine-131 2.
Average release rate for period Particufatess 1.
Particulates with half-lives )8 days 2.
Average release rate for period 3.
Gross alpha radioactivity Tritiums 1.
Total release 2.
Average release rate for period Percent of Tech. S ec. Limits Fission and Activation Gases Percent of Quarterly Gamma AirDose Limit (5 mR)
Percent of Quarterly Beta Air Dose Umit (10 mrads)
Percent of Annual Gamma Air Dose Umit to Date (10 mR)
Percent of Annual Beta Air Dose Limitto Date (20 mrads)
Percent of Whole Body Dose Rate Umit (500 mrem/yr)
Percent of Skin Dose Rate Umit (3000 mrem/yr)
Tritium lodines and Particulatess with half-lives rester than 8 da s
Percent of Quarterly Dose Limit (7.5 mrem)
Percent of Annual Dose Umit (15 mrem)
Percent of Organ Dose Rate Umit (1500 mrem/yr)
Ci pCi/sec Ci yCi/sec Ci yCi/sec Ci Ci pCi/sec 6.73E-02 7.72E-01 5.59E-05 7.19E-06 5.31E-04 6.43E- 05 3.61E-05 1.60E+ 00 5.82E-01 7.42E-03 8.31E-03 3.71E-03 4.16E-03 1.77E-04 7.18E-05 1.97E-01 9.92E-02 4.00E-03 O.OOE+ 00 O.OOE+ 00 4.41E-05 5.61E-06 5.40E-04 7.26E-05 5.47E-05 1.10E+01 2.03E+ 00 O.OOE+ 00 O.OOE+ 00 3.71E- 03 4.16E-03 O.OOE+ 00 O.OOE+ 00 1.17E-01 1.50E-01 6.2SE-03 5.00E+01 3.00E+01 3.00E+01 2.50E+ 01 5.00E+01 Concentrations less than the lower limitof detection of the counting system used aro indicated with a double asterisk. A lower limit of detection of 1.00E-04 yCi/ml for required noble gases, 1.00E-11 pCi/ml for required particulates, 1.00E-12 yCi/ml for required lodines, and 1.00E-06 yCi/ml for Tritium, as required by Technical Specifications, has been verified.
Tritium, Iron-55, and Strontium results for the second quarter were not received from tho off-site vendor at the time of this report. These numbers include estimates, and actual numbers will bo provided in tho next Semi-Annual Report.
ATTACHMENT3 Unit 1 X
Unit 2 Reporting Period Janus
- June 1995 GASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOUS MODE Nuclides Released 1
QUARTER 2~
QUARTER Fission Gasest Argon-41 Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-127 Xenon-133 Xenon-133m Xenon-135 Xenon-135m Xenon-137 Xenon-138 2.
lodinsst Iodine-131 Iodine-133 Iodine-135 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci
~ 0
~ 0
~ 0
~ 0
~ 0
~ 0 2.61E-02
~t 4.06E-02
~ 0
~ 0
~ 0 5.59E-OS 1.05E-04
~ 0 0 ~
~ 0 0 ~
~ 0
~ 0
~ 0
~ 4
~ 0
~ 0
~ 0
~ 0
~ 0 4.41E>>05 7.32E-04
~ 0 3.
Particulates Strontium-89 Strontium-90 Cesium-134 Cesium-137 Cobalt-60 Cobalt-58 Manganese-54 Barium-Lanthanum-140 Antimony-125 Niobium-95 Cerium-141 Corium-144 Iron-59 Cesium-136 Chromium-51 Zinc-65 Iron-55 Molybdenum-99 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 5.25E-06
~ 0
~ 0 2.56E- 05 3.95E-04 2.23E-05 6.24E-05
~ 0
~ 0
~ 0
~t
~ 0
~ 0
~ 0
~ 0
~ 0 1.95E-OS 2.41E-04 2.81E-OS 0 ~
4.79E-06 1.09E-04
~ 0
~ 0
~ 0
~ 0
~ 0
~ 0
~ 0
~ 0
~ 0
~ 0 OO 1.54E-04
~ 0 4.
Tritiums Ci 1.17E+00 1.04E+ 01 Concentrations less than the lower limitof detection of the counting system used aro indicated with a double asterisk.
A lower limitof detection of 1.00E-04 yCi/ml for required noble gases, 1.00E-11 yCi/ml for required particulates, 1.00E-12 yCi/ml for required lodines, and 1.00E-06 yCi/ml for Tritium, as required by Technical Specifications, has been verified.
Tritium, Iron-55, and Strontium results for the second quarter were not received from the off-site vendor at the time of this report. These numbers include estimates and actual numbers willbe included in the next Semi-Annual Report.
No batch mode release occurred during the reporting period.
0
ATTACHMENT4 Unit 1 X
Unit 2 Reporting Period Janus
- June 1995 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES There were no releases via the emergency condenser vent operation. Only leakage from the vents results in an assumed release based on the concentrations in the condensato storage tanks and condenser shell.
CONTINUOUS MODE BATCH MODE There were no batch releases during the reporting period.
1'UARTER 2'UARTER 1st QUARTER 2ad QUARTER Fission Gasost Argon-41 Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-133 Xenon-133m Xenon-135 Xenon-135m Xenon-137 Xenon-138 Xenon-127 lodinost Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci OO 0 ~
4 ~
5.72E-04
~ 0
~ 0
~ 0 OO 04
~ 0
~ 0 0 ~
~ 0
~ 0 0 ~
OO OO Iodine-131 Iodine-133 Iodine-135 Particulatest's Ci Ci Ci
~ 0
~ 0
~ 0
~ 0
~ 0 Strontium-89 Strontium.90 Cesium-134 Cesium-137 Cobalt-60 Cobalt-58 Manganoso-54 Barium. Lanthanum-l 40 Antimony-125 Niobium-95 Cerium-141 Corium-144 Iron-59 Cesium-136 Chromium-51 Zinc-65 Iron-55 Molybdenum-99 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 0 ~
~ 0 0 ~
5.53E-07 0 ~I1 0 ~
0 ~
~ 0
~ 0 2.41E-07 2.90E-08 OO
~ 0 2.65E-06
~ 1 3.09E-08 OO 0 ~
~ ~
~ 0 6.74E-07 Tritium Ci 4.27E-01 6.18E-01 Concentrations less than the lower limit of detection of tho counting system used are indicated with a double asterisk.
A lower limit of detection of 1.00E-04 pCi/ml for required noble gases, 1.00E-11 pCi/ml for required particulates, 1.00E-12 pCi/ml for required lodinos, and 1.00E-06 pCi/ml for Tritium, as required by Technical Specifications, has boon verified.
Iron.55, and Strontium results for tho socond quarter wore not received from the off-site vendor at the time of this report.
These numbers include estimates, and actual numbers will bo included in tho next Semi-Annual Rcport.
.0
ATTACHIVlENT5 Page 1 Of 2 Unit 1 X
Unit 2 Reporting Period Janus
- June 1995 UQUID EFFLUENTS - SUMMATIONOF ALLRELEASES 1
2w EST. TOTAL QUARTER QUARTER
~ERROR A.
Fission(IE Activation Products 1.
Total release (not including Tritium, gases, alpha) 2.
Average diluted concentration during reporting period B.
Tritium 1.
Total release 2.
Average diluted concentration during reporting period C.
Dissolved and Entrained Gases 1.
Total release 2.
Average diluted concentration during reporting period Ci
/rCI/ml Ci yCI/ml Ci yCI/ml No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releasee No Releases No Releases No Releases 5.00E+01 5.00E+01 5.00E+01 D.
Gross Al ha Radioactivit 1.
Total release Ci No Releases No Releases 5.00E+01 E.
Volumes 1 ~
Prior to dilution 2.
Volume of dilution water used during release period 3.
Volume of dilution water available during reporting period Liters Uters Uters No Releases No Releases 6.20E+ 10 No Releases No Releases 1.31E+ 11 5.00E+01 5.00E+01 5.00E+01 F.
Percent of Technical 9 ecification Limits Percent of Quarterly Whole Body Dose Umit (1.5 mrem)
Percent of Quarterly Organ Dose Umit (5 mrem)
Percent of Annual Whole Body Dose Umit to Date (3 mrem)
Percent of Annual Organ Dose Limitto Date (10 mrem)
Percent of 10CFR20 Concentration Limit Percent of Dissolved or Entrained Noble Gas Umit (2.00E-04 yCI/ml)
No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases
ATTACHMENT5 Page 2 of 2 Unit1 X Unit 2 UQUID EFFLUENTS RELEASED Reporting Period Janus
- June 1995 BATCH MODE Nuclides Released 1
QUARTER gal QUARTER Strontium-89 Strontium-90 Cesium-134 Cesium-137 Iodine-131 Ci Ci Ci Ci Ci No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases Cobalt-58 Cobalt.60 Iron-59 Zinc-65 Manganese-54 Chromium-51 Ci Ci Ci Ci Ci Ci No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases Zirconium-Niobium-95 Molybdenum-99 Technetium-99m Barium-Lanthanum-140 Cerium-141 Ci Ci Ci Ci Ci No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Roloases Tungsten-187 Arsenic-78 iodine-133 Iron-55 Neptunium-239 Praseodymium-144 Iodine-135 Ci Ci Ci Ci Ci Ci Ci No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Releases No Reloasos No Releases No Releases No Releases Dissolved or Entrained Gases Tritium Ci Ci No Releases No Releases No Releases No Releases
ATTACHMENT6 Page 1 of 6 Unit 1 X
Unit 2 Reporting Period Jenuar
- June 1995 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS: There were no shipments sent for burlai.
A.l TYPE Volume im3)
~Activlt
'ci)
Class Class 1.
Spent Resins 0
0 0
0 0
0 Filter Sludge Concentrated Waste Evaporator Bottoms Total 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 2.
Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment) 0 0
0 0
0 0
3.
Irradiated Components 0
0 0
0 0
0 The estimated total error is 5.00E+01%.
Eleven Unit 1 steel encased high integrity containers of waste Class A bead resin was placed in interim storage at Nine Mile Point during the reporting period. The total activity was 5.69E+01 curies and the volume was 5.12E+Olms.
ATTACHMENT6 Page 2 of 6 Unit 1 X
Unit 2 Reporting Period Janua
- June 1995 SOUD WASTE AND IRRADIATEDFUEL SHIPMENTS A.1 TYPE Container
~Pa eke e
Solidification
~Aeet 1.
Spent Resin
~NA
~NA Filter Sludge Concentrated Waste
~NA
~NA
~NA 2.
Dry Compressible Waste, Dry Non-Compressible Waste (Contaminated Equipment)
~NA
~NA N/A 3.
Irradiated Components N/A N/A N/A
ATTACHMENT6 Page 3 of 6 Unit1 X Unit 2 Reporting Period Janus
- June 1995 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS A.2 ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE) a.
Spent Resins, Filter Sludges, Concentrated Waste:
There were no shipments Nuclide Percent b.
Dry Compressible Waste, Dry Non-Compressible Waste IContarnlnated Equipment):
There were no shipments.
Nuclide Percent c.
Irradiated Components:
There were no shipments.
Nuclide Percent d.
Other:
There were no shipments.
Nuclide Percent
ATTACHMENT6 Page4of 6 Unit 1 X Unit 2 Reporting Period Januar
- June 1995 SOUD WASTE AND IRRADIATEDFUEL SHIPMENTS A.3.
SOLID WASTE DISPOSITION There were no shipments Number of Shi ments Mode of Trans ortation Destination 0
~NA
~NA B.
IRRADIATEDFUEL SHIPMENTS (DISPOSITION):
There were no shipments.
Number of Shi ments 0
Mode of Trans ortation
~NA Destination NIA
ATTACHMENT6 Page 50f 6 Unit 1 X
Unit 2 Reporting Period Janus
- June 1995 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS C.
SOLID WASTE SHIPPED OFF-SITE TO VENDORS FOR PROCESSING AND SUBSEQUENT BURIAL There were no shipments sent for buriai: all shipments were returned to Nine Mile Point after volume reduction processing, Below is a summary of Dry Active Waste that was shipped off-site for processing and burial by vendor facilities (I.e., ALARON, AMERICANECOLOGY RECYCLE CENTER, INC., and/or SCIENTIFIC ECOLOGY GROUP) during Janus
- June 1995.
These totals were reported separately from "10CFR61 Solid Waste Shipped for Burial" since (a) waste classification and burial was performed by the vendors, and (b) Technical Specification 6.9.1 requires reporting of "information for each class of solid waste (as defined by 10CFR61) shipped off-site during the reporting period." The information provided in this section, therefore, is in addition to that required by the Technical Specifications.
The following data represents the actual shipments made from the off-site vendors of our non-compacted commingled trash that was processed prior to burial.
C.1.
TYPE OF WASTE - noncompacted commingled trash shipped to Oak Ridge, TN for processing prior to burial at Barnwell, SC Burial Volume
~mr Activity
~CI Est. Total
~Er '
0 5.00+01 C.2.
ESTIMATE OF MAJOR NUCLIDE COMPOSITION There were no shipments.
Nuclide Percent C.3.
SOLID WASTE DISPOSITION: There were no shipments for buriai; all shipments were returned to Nine Mile Point after volume reduction processing.
Ten shipments to off-site processors were made.
Number of Shi ments Mode of Trans ortetion Destination 0
~NA N/A
ATTACHMENT6 Page 6 of 6 Unit 1 X
Unit 2 Reporting Period Janua
- June 1995 SOLID WASTE AND IRRADIATEDFUEL SHIPMENTS D. SEWAGE WASTES SHIPPED TO A TREATMENTFACILITYFOR PROCESSING AND BURIAL There were no shipments of sewage sludge with detectable quantities of plant-related nuclides from NMP to the treatment facility during the reporting period.
ATTACHMENT7 Unit1 X Unit2 Reporting Period Janus
- June 1995
SUMMARY
OF CHANGES TO THE OFFNITE DOSE CALCULATIONMANUAL One change to the Unit 1 Off-Site Dose Calculation Manual was made during the reporting period.
A copy of revision 15 is attached and below is a summary of the change presented to and approved by the Station Operation Review Committee in February 1995.
The summary also includes the justification for the change.
A change to section 3.1, "Set.point Determinations", was made to incorporate the off gas alarm set-point (Hi Alarm) of five (5) times normal full power background, the actions to take when the a(armis received and the basis for the alarm as stated in the NRC's safety evaluation for Technical Specification Amendment No. 149 - deletion of the automatic reactor scram and main steam line isolation function of the main steam line radiation monitor. The off-gas radiation monitor alarm set-point of five (5) times normal full power background willprovide assurance that increased significant levels of radioactivity in the main steam lines will be controlled expeditiously to limitboth occupational doses and environmental releases.
Therefore, this change does not reduce the accuracy or reliability of the dose calculations or set-point determinations in accordance with Technical Specifications.
ATTACHMENT8 Unit 1 X Unit 2 Reporting Period Janus
- June 1995
SUMMARY
OF CHANGES TO THE PROCESS CONTROL PROGRAM There were no changes to the Unit 1 Process Control Program during the reporting period.
ATTACHMENT9 Unit 1 X
Unit 2
SUMMARY
OF INOPERABLE MONITORS Reporting Period Janus
- June 1995 There ware no inoperable monitors for a period greater then 30 days during the reporting period.
0
UPDATE TO THE PREVIOUS REPORTS
0
A Unit 1 X
Unit 2 Reporting Period Jul
- December 1994 UPDATE OF RELEASE AND DOSE DATAFOR GASEOUS (ELEVATEDAND GROUND LEVEL)AND LIQUIDEFFLUENTS Update of data using actual results from the off-site vendors for Strontium, Tritium, and Iron-55 for the fourth quarter 1994.
Nucildet Sr-89 Sr-90 H-3 Fe-55 GASEOUS 4>> QUARTER 1994
~ActiVit Ci 2.66E-OS O.OOE+ 00 t
7.42E+ 00 O.OOE+ 00 UQUID 4>> QUARTER 1994
~Aet vit Ci No Releases No Releases No Releases No Releases Particu'letes 1.
Particulates with half-livos >8 days 2.
Average release rate for period Ci
/ICI/sec GASEOUS 1.26E-04 1.58E-OS LIQUID
~NA N/A Tntium Tritium lodines end Particulates with half-lives rester than 8 da s
- 1. Total release 2.
Average release rate for period Ci
/rC//sec (gaseous)
/ICI/ml (liquid) 7.42E+ 00 9.33E-01 GASEOUS
~NA
~NA LIQUID 1 ~
Porcont of Quartorly2 Dose Umit 2.
Percent of Annual2 Dose Umit to Date 3.
Percent of Organ
- Dose Rate Limit (Gaseous)(Quarterly)
- Dose Umit (Uquid)
(Annual fk Quarterly) 4.
Percent of 10CFR20s Concentration Limit (Uquid) 5.
Percent of Dissolved or Entrained Noble Gas (Uquid) 1.62E-01 (Quarterly) 1.98E-01 (Annual) 3.22E-03 (Quarterly)
~NA (Annual)
N/A
~NA
~NA (Quarterly)
~NA (Annual)
~NA (Quarterly)
~NA (Annual)
Concentrations less then the lower limit of detection, as required by Technical Specifications are indicated with a double asterisk.
The dose is to the maximally exposed organ for gaseous offluents.