ML20082R322
| ML20082R322 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 12/31/1994 |
| From: | Hagan J Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N95015, RERR-17, NUDOCS 9505020048 | |
| Download: ML20082R322 (206) | |
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Public Service Electric and Gas Cornpany l J:seph J. Hagan Public Service Electnc and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 m,.... . ., o-.
APR 271995 LR-N95015 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen: l l
RADIOACTIVE EFFLUENT RELEASE REPORT - 17 l HOPE CREEK GENERATING STATION
! DOCKET NO. 50-354 l
l In accordance with Section 6.9.1.8 of Appendix A to the Operating l License for Hope Creek Generating Station, Public Service Electric and Gas Company hereby transmits one copy of the annual Radioactive Effluent Release Report, RERR-17. This report summarizes liquid and gaseous releases and solid waste shipments from the Hope Creek Generating Station for the period of January 1, 1994 through December 31, 1994.
Should you have any questions regarding this transmittal, please feel free to contact us.
Sincerely, ,
Attachment (1) -
i 950502004B 941231 PDR ADOCK 05000354 R PDR
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Document Control Desk -2_ APR 271995 LR-N95015 ALL WITH ATTACHMENT:
C Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. D. H. Moran, Licensing Project Manager - Hope Creek U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 14E21 11555 Rockville Pike Rockville, MD 20852 Mr. R. Summers (SO9)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV NJ Department of Environmental Protection Division of Environmental Quality l CN 415
! Trenton, NJ 08625 l
95-4933
HOPE CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE PIPORT HCGS RERR-17 DOCKET NO. 50-354 OPERATING LICENSE NO. NFP-57 J.
April 1995 O
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HOPE CREEK GENERATING STATION
- RADIOACTIVE EFFLUENT RELEASE REPORT i JANUARY - DECEMBER 1994 j i
i Table of Contents '
INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2
. . . . . . . . 2 4 PART A. PRELIMINARY SUPPLEMENTAL INFORMATION .
j 1.0 REGULATORY LIMITS . . . . . . . . . . . . . . . . . . 2 l 1.1 Fission and Activation Gas Release Limits . . . . 2 1.2 Iodine, Particulates, and Tritium . . . . . . . .2 1.3 Liquid Effluents Release Limits . . . . . . . . . 3 4 1.4 Total Dose Limit . . . . . . . . . . . . . . . . 3 2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) . . . . . . . 3 i
3.0 AVERAGE ENERGY . . . . . . . . . . . . . . . . . . . . 4 4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY 4 4
5.0 BATCH RELEASES . . . . . . . . . . . . . . . . . . . . 6 6.0 UNPLANNED RELEASES . . . . . . . . . . . . . . . . . . 6 7.0 ELEVATED RADIATION MONITOR RESPONSES . . . . . . . . . 7 ,
] 8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUEPT RELEASE REPORTS . . . . . . . . . . . . . . .7 PART B. GASEOUS EFFLUENTS . . . . . . . . . . . . . . . . . .7 PART C. LIQUID EFFLUENTS . . . . . . . . . . . . . . . . . . .7 l l
PART D. SOLID WASTE . . . . . . . . . . . . . . . . . . . . .7 i PART E. RADIOLOGICAL IMPACT ON MAN . . . . . . . . . . . . . .7 Liquid Pathways . . . . . . . . . . . . . . . . . . . 8 Air Pathways . . . . . . . . . . . . . . . . . . . . . 8 Direct Radiation . . . . . . . . . . . . . . . . . . . 9 Total Dose . . . . . . . . . . . . . . . . . . . . . . 9 Dose to Members of the Public on Site . . . . . . .10 Assessment . . . . . . . . . . . . . . . . . . . . . 11 PART F. METEOROLOGICAL DATA . . . . . . . . . . . . . . . . 12 PART G. OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES . . . 12 PART H. INOPERABLE MONITORS . . . . . . . . . . . . . . . . 12 ,
1 PART I. PROCESS CONTROL PROGRAM (PCP) CHANGES. . . . . . . . 13 PART J. ENVIRONMENTAL MONITORING LOCATION CHANGES. . . . . . 13 1 1
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HOPE CREEK GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 1994
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INTRODUCTION This report, HCGS-RERR-17, summarizes information pertaining to the releases of radioactive materials in liquid, gaseous and solid form from the Hope Creek Generating Station (HCGS) for the period January 1, 1994 to December 31, 1994.
The Hope Creek Generating Station (HCGS) employs a General Electric j (GE) Boiling Water Reactor designed to operate at a rated core j thermal power of 3293 MWt with a gross electrical output of approximately 1118 MWe and a not output of approximately 1067 MWe.
The HCGS achieved initial criticality on June 28, 1986 and went into commercial operation on December 20, 1986.
This report is prepared in the format of Regulatory Guide 1.21, Appendix B, as required by Specification 6.9.1.7 of the Hope Creek Technical Specifications. Our responses to parts A-F of the
" Supplemental Information" section of Regulatory Guide 1.21, Appendix B, are included in the following pages.
As required by Regulatory Guide 1.21, the' Hope Creek Technical ,
i Specification limits are described in detail within this report along with a summary description of how total radioactivity measurements and their approximations were developed. ,
To facilitate determination of compliance with 40CFR190 requirements, the following information on electrical output is provided.
Hope Creek generated 7,125,537 megawatt-hours of electrical energy (net) during the reporting period.
The Sr-89, Sr-90 and Fe-55 analyses for the second half of 1993 (refer to RERR-16) have been completed; amended pages to RERR-16 are included in this report.
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PART A. PRELIMINARY SUPPLEMENTAL INFORMATION 1.O REGULATORY LIMITS 1.1 Fission and Activation Gas Release Limits The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary, shall be' limited to the following:
For noble gases: Less than or equal to 500 arems/yr to the total body and less than or equal to 3000 mrams/yr to the skin.
In addition, the air dose due to noble gases released in gaseous affluents from the site to areas at and beyond the site boundary, shall be limited to the following:
During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than.or equal to 20 mrad for beta radiation.
1.2 Iodine, Particulates, and Tritium The dose rate due to radioactive materials released in gaseous affluents from the site to areas at and beyond the site boundary, shall be limited to the following:
For Iodine-131,I-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrams/yr to any organ.
In addition, 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 8 days in gaseous affluents released, from each reactor unit, to areas at and beyond the site boundary, shall be limited to the following:
During any calendar quarter: Less than or equal to 7.5 mrams to any organ and, During any calendar year: Less than or equal to 15 areas to any organ.
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1.3 Liquid Effluents Release Limits j The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations.specified in 10CFR20, 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-4 microcuries per milliliter.
In addition, the dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited to:
During any calendar quarter: Less than or equal to 1.5 mreas to the total body, and less than or equal to 5 mreas to any organ, and During any calendar year: Less than or equal to 3 areas to the total body, and less than or equal to 10 mreas to any organ.
1.4 Total Dose Limit The annual (calendar year) dose or dose commitment to , I any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 areas to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 areas).
2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)
Regulatory Guide 1.21 requires that the licensee provide the MPCs used in determining allowable release rates or concentrations for radioactive releases,
- a. MPC values were not used for gaseous releases in the determination of maximum release rates for fission gases, iodines, or particulates.
- b. MPC values as stated in 10CFR20, Appendix B, i Table II, Column 2 are used for liquid affluents in accordance with current Technical specifications.
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3.0 AVERAGE ENERGY Regulatory Guide 1.21 requires that the licensee provide the average energy of the radionuclide mixture in releases of fission and activation gases, if applicable.
Release limits for HCGS are not based upon average energy.
Therefore this section is not applicable to HCGS.
4.0 MEASUseMeMTS AND APPROIINATION OF TOTAL RADIOACTIVITY 4.1 Liquid Effluents Liquid affluents are monitored in accordance with Table 4.11.1.1.1-1 of the Technical Specifications. During the period of record, all batch liquid wastes were routed to the sampling tanks for monitoring prior to release.
Technical Specifications require these tanks to be uniformly mixed for sampling and analysis before being released. Batch releases are defined as releases from the equipment drain sample tanks, floor drain sample tanks, detergent drain tanks, and the condensate storage tank dike. Normally, there are no continuous liquid releases. Specific activities from analyses were multiplied by the volume of effluent discharged to the environment in order to determine the total liquid activity discharged.
The detection requirements of Table 4.11.1.1-1 of the ,
Technical Specifications are achieved or exceeded.
Radionuclides measured at concentrations below the Technical Specification detection limit (LLDs) are treated as being present. Radionuclides for which no activity was detected while meeting the required LLDs are treated as absent.
4.2 Gaseous Effluents Gaseous affluent streams are monitored and sampled in accordance with Table 4.11.2.1.2-1 of the Technical
' Specifications. The north plant vent (NPV) and south plant vent (SPV) are the final release points for most planned gaseous effluent releases. A small quantity of gaseous effluent will be released via the filtration, recirculation, and ventilation system (FRVS) vent during testing periods. The NPV and SPV are continuously monitored for iodine, particulates and noble gases; the FRVS is continuously monitored for
( noble gases. The NPV and SPV monitors have moving l
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( particulate and fixed charcoal filters; the FRVS l
i monitor has fixed particulate and charcoal filters.
The filters and charcoal are changed weekly, and are
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j analyzed on a multichannel analyzer. The NPV and SPV are sampled monthly for noble gases and tritium. ;
The detection requirements of Tables 4.11.2.1.2-1 of l the Technical Specifications are achieved or exceeded.
! Radionuclides detected at concentrations below the I
Technical Specification detection limit-(LLDs) are treated as being present. Radionuclides for which no .
- activity was detected while meeting the required l LLDs are treated as absent. .
Continuous Mode gaseous releases. are quantified by :
routine (weekly) sampling and isctopic analyses of the
- plant vents. If noble gases are detected during the -
routine sampling,the measured concentrations are adjusted '
using the radiation monitoring . readings to obtain an -
average concentration for the period. This average !
concentration is then multiplied by the total vent flow value for the entire sampling period in order to estimate !
the normal continuous release of radioactivity through the plant vent. ,
When monthly vent grab samples yield no detectable activity, continuous mode releases are quantified by i integrating Radiation Monitor System readings. ,
Noble gas isotopic abundances for these integrations i are based on the ANSI N237-1976/ANS-18.1 mix for BWRs.
- Doses calculated from this data employ the methods from Section 2.0 and Appendix C of the Hope Creek ODCM.
Batch Mode' gaseous releases (primary containment purge) ,
are quantified by pre-release sampling and isotopic analysis. Specific activities for each isotope are multiplied by the total purge flow volume for that batch in order to estimate the batch release of radioactivity through the plant vent.
Elevated plant vent radiation monitoring system readings while the channel is in an alarm state are treated as batch mode releases. If specific activity data from grab samples taken'is not available, then the abnormal release is quantified by the use of the plant :
vent radiation monitors. The monitor's response is l converted to a " specific activity" using historical efficiency factors.- The " specific activity" is j multiplied by the volume of effluent discharged while ;
the channel was in an alarm state in order to estimate t the total activity discharged.
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i 4.3 Estimated Total Error The estimated total error of reported liquid releases is within 25%.
The estimated total error of the reported continuous gaseous releases is within 50% when concentrations i exceed detectable levels. This error is due primarily to variability of waste stream flow rates and changes in isotopic distributions of waste streams between sampling periods. The estimated total error of the reported batch gaseous releases is within 10%.
Error estimates for releases where sample activity is below the detectable concentration levels are not included since error estimates at the LLD are not defined. ,
The estimated total error of reported solid releases is within 25%.
5.0 B&TCE RELEASES Summaries of batch releases of gaseous and liquid affluents are provided in Tables 4A and 4B.
6.0 UNFLANNED matmasES During this reporting period there was 1 unplanned release.
On March 9,1994 approximately 200 gallons of water containing very low levels of radioactivity was released from the circulating dewatering sump to the Delaware River. The circulating dewatering sump is designed as a non-radioactive system. The source of the contamination was from water that was manually pumped into the sump from the condenser bay floor area. The sump reached its preset level and automatically pumped the water in the tank to the cooling tower bloriown line. The cooling tower blowdown flows directly into the Delaware River. Samples taken from the dewatering sump were analyzed and found to contain Zinc-65, Manganese-54, and Iodine-131 at levels less than 1.0E-6 uci/ml. The Cooling Tower blowdown line is the normal. pathway for radioactive liquid release and provides a minimum dilution of 12,000 gym.
All concentrations of radionuclides were well below the limits specified in 10 CFR 20 Appendix B, Table II, Column II. The unplanned release was monitored by two radiation monitors. Due ,
to the low concentration of radioactivity in the sump, the radiation monitors did not alarm while the dewatering sump was being released. Root cause of this incident was a failure to adequately sample the dewatering sump prior to release.
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i j 7.0 ' ELEVATED RADIATION MONITOR RESPONSES 1
During this reporting period, there were no elevated radiation monitor readings.
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8.0 MODIFICATION TO PREVIOUS EADICACTIVE EFFLUENT RELEASE REPORTS l l Our last report (RERR-16) did not inclu( the quarterly Sr-89, Sr-90 and Fe-55 composite data for the second half of 1993. Amended pages to RERR-16 are included at the and of i this report, i
i PART E. GASEOUS EFFLUENTS J
See Summary Tables 1A through 1C. ,
t PART C. LIQUID EFFLUENTS See Summary Tables 2A through 2B.
. t PART D. SOLID WASTE ;
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See Summary in Table 3. ;
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PART E. RADIOLOGICAL IMPACT ON M&M r The reporting period for the Radiological Effluent Release Report (RERR) changed from a six month reporting period to a twelve month reporting period. Beginning with this report (RERR-17) dose estimations to man are based on a 12 month ,
! period.
The calculated individual doses in this section are based on actual locations of nearby residents and farms. The population .
dose impact is based on historical site specific data i.e., l food production, milk production, feed for milk animals and ,
l seafood production.
The doses were calculated using methods described in Regulatory Guide 1.109 and represent calculations for the 12 j month reporting interval. Individual doses from batch and [
- continuous releases were calculated using the annual average i historic meteorological dispersion coefficients as described !
l in the Offsite Dose Calculation Manual. Fopulation doses were i calculated using the meteorological dispersion coefficients ;
i for the twelve month reporting interval. ;
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I Liauld Pathways Doses to the " maximum hypothetical individual" in the population from liquid releases are primarily from the seafood ingestion pathway. Calculated doses are as shown below.
Total body dose : 1.86E-01 aren Highest organ dose (LIVER): 4.44E-01 aren Dose to the 4.5 million individuals living within the 50 mile radius of the plant site:
Total population dose: 1.10E+00 person-ren Average population done: 2.44E-04 mram/ person Air Pathways The calculated doses to individuals via the air pathway are shown below:
Total body dose: 6.49E-01 aren Skin dose: 1.42E+00 aren Highest organ dose due to radioiodines and particulates with half lives. greater than 8 days:
1.25E-03 mram to the THYROID Dose to the 4.5 million individuals living within the 50 mile radius of the plant site:
Total population dose: 8.15E-01 person-ren Average population dose: 1.91E-04 aren/ person 8
Direct Radiation Direct radiation may be estimated by Thermoluminescent dosimetric (TLD) measurements. One method for comparing TLD measurements is by comparison with pre-operational data. It should be noted that-the TLDs measure direct radiation from both the Salem and Hope Creek Generating Stations at Artificial Island, and natural background radiation.
TLD data for the twelve month reporting period is given below:
TLD Location Measurement !
25-2 0.4 mi. NNE 4.1 mrad / month SS-1 1.0 mi. E 3.5 mrad / month These values are interpreted to represent natural background, since the values are within the statistical variation associated with the pre- t operational program results, which are 3.7 mrad / month for location 25-2, and 4.2 mrad / month for location SS-1.
i Total Dose 40CFR190 limits the total dose to members of the public due to radioactivity and radiation from uranium fuel cycle sources to: ,
<25 aren total body or any. organ l
<75 area thyroid I for a calendar year. For Artificial Island, the major sources of dose are from liquid and gaseous affluents from the Hope Creek and Salem plants.
The following doses to a " maximum hypothetical individual " have been calculated for the twelve month reporting period. They are the sum of gaseous'and liquid pathway doses for the Salen 1 and 2 and Hope Creek plants:
1.420 area total body 1.290 mram organ (GI-LLI) 0.089 mram thyroid l
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Dose to menbers of the oublic due to activities inside the site boundarv.
In accordance with the requirements of Technical Specification 6.9.1.7, the dose to members of the public inside the site boundary has been calculated based on the following assumptions:
- a. Such persons are participating or spectators in company softball league
- b. 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> per week on site
- c. dose due to airborne pathway (inhalation and immersion)
- d. persons are located about 3/4 mile east of plant discharge points (baseball fields)
- e. occupancy coincides with batch gaseous discharges For the 12 month reporting period, the calculated doses are:
9.58E-04 mrem total body 9.70E-04 mrem organ (Lung) 9.58E-04 mrem thyroid 10
Assessment Gaseous and liquid effluents released from Hope Creek resulted in a minimal dose to the maximum hypothetical individual. The dose for the 12 month period was a small fraction of all applicable limits.
Individual noble gas radionuclide concentrations are too low to measure directly. Calculated doses from noble gases are based on a default isotopic mixture, which assumes little decay, and has principally short lived species with large dose factors. Because of this assumed isotopic mix, calculated doses are probably conservative by a factor of 25.
The following two trend graphs show the total curies of gaseous and liquid effluents released for Hope Creek from 1988 through 1994. Calculated doses in the graphs are to the maximum hypothetical individual.
I Hope Creek Gaseous Emuents i
Curies of Noble Gases Released and Calculated Doses 1.00E+03
~
-r- ;% -
1.00E+02
'- - - - - - - - - = - - -- -- -
a 1.00E+01 1 1.00E-02 '
b 1.00E-03 1.00E-04 '
3 ; t ; ; 2 Year Hope Creek Liquid Emuents Curies Released and Calmisled Doses 1.40E+00
,. u e
e 1.00E+00
/A ~
a 8.00E-01 r'-/\
8 e-0, \ / / \-
- 3. , a\ / M \\ .
=
!" .,.m, ~1'V# \\ % ._ /M t
" Ni - .
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Year 11
PART F. METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmospheric stability class at the 300 foot elevation are provided for 1994 in Tables 5 and 6.
PART G. OFFSITE DOSE CALCULATION MANUAL (ODCM) CRANGES During this period, there was a revision to the HCGS ,
Off-site Dose Calculation Manual. The revision consisted of updating the ODCM to reflect current operational parameters. The changes to the manual did not effect dose calculation methodology or results. Copies of the revised ODCM pages are attached to the and of this report.
PART E. INOPERABLE MONITORS During this period the following effluent monitors were inoperable for greater than 30 days.
- North and South Plant Vent Radiation Monitors The north and south plant vent radiation monitors were declared inoperable from 5/93 to 10/94 due to possible degraded charcoal cartridges. Analysis performed on charcoal cartridges taken from warehouse stock indicated degraded iodine retention capability. In May 1993 approximately 20 charcoal cartridges were taken out of warehouse stock for use in plant radiation monitor sampling stations. It is not known if any of these charcoal cartridges were actually used for monitoring gaseous affluent releases. In October 1994 new charcoal cartridges where received and all warehouse cartridges were discarded. Due to excellent fuel performance during this period, reactor coolant levels of iodine were extremely low. After accounting for charcoal degradation, releases of radioactive iodine from plant ventilation systems during the 5/93 to 10/94 time period were far below Technical Specification limits.
- Cooling Tower Blowdown Flow Monitor The cooling tower blowdown flow monitor could not be returned to service within the 30 day time period due to the cooling tower basin being drained for maintenance and replacement of the flow monitor. The monitor was inoperable for a period of 45 days during this reporting
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period.
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PART I. PROCESB CONTROL PROGRAM (PCP) CHANGES During the reporting period, there were no changes to the process control program.
PART 3. ENVIRO 30tENTAL MONITORING LOCATION CRANGES During the reporting period, there were no changes made to the Environmental Monitoring sample locations.
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HOPE CREEK GENERATING STATION TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1994 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Est. (1) ist 2nd Total Units Qtr Qtr Error %
A. Fission and Activation Gases
- 1. Total release Ci 2.12E+01 1.35E+01- 25
- 2. Average release rate for period pCi/sec 2.73E+00 1.72E+00
- 3. Percent of technical specification limit (T.S. 3.11.2.2(a)) % 2.53E-01 1.84E-01 B. Iodines '
- 1. Total Iodine-131 Ci 2.56E-05 0.00E+00 25
- 2. Average release rate for period .pci/sec 3.29E-06 0.00E+00
- 3. Percent of technical specification limit (2)
(T.S. 3.11.2.3(a)) % 3.61E-03 1.83E-04 C. Particulates
- 1. Particulates with half-lives >8 days C1 1.13E-04 3.88E-04 25
- 2. Average release rate for period #Ci/sec 1.45E-05 4.94E-05 i
- 3. Percent of technical specification limit (2)
(T.S. 3.11.2.3(a)) % 3.61E-03 1.83E-04
- 4. Gross alpha Ci 0.00E+00- 7.26E-06 D. Tritium
- 1. Total Release ci 1.86E+00 9.38E-04 25
- 2. Average release rate for period pCi/sec 2.39E-01 1.19E-04
- 3. Percent of technical specification limit (2)
(T.S. 3.11.2.3(a)) % 3.61E-03 1.83E-04 (1) For batch releases the estimated overall error is within 10%
l (2) Iodine, tritium and particulates are treated as a group r
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HOPE CREEK GENERATING STATION
- TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1994 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Est. (1) 3rd 4th Total l Units Qtr Qtr Error 4 ,
A. Fission and Activation Gases
- 1. Total release Ci 1.67E+01 2.01E+02 25
- 2. Average release ;
rate for period #Ci/sec 2.10E+00 2.53E+01 i
- 3. Percent of technical specification limit (T.S. 3.11.2.2(a)) % 2.28E-01 2.72E+00 B. Iodines
- 1. Total Iodine-131 Ci 1.67E-06 9.15E-05 25
- 2. Average release '
rate for period #Ci/sec 2.10E-07 1.15E-05
- 3. Percent of technical specification limit (2) ,
(T.S. 3.11.2.3(a)) % 6.21E-04 1.22E-02 ;
C. Particulates
- 1. Particulates with half-lives >8 days Ci 2.30E-04 1.10E-04 25
- 2. Average release 1 rate for period pCi/sec 2.89E-05 1.38E-05
- 3. Percent of technical specification limit (2)
(T.S. 3.11.2.3(a)) % 6.21E-04 1.22E-02
- 4. Gross alpha Ci 1.53E-08 0.00E+00 D. Tritium l
- 1. Total Release ci 0.00E+00 2.30E+01 25
- 2. Average release i rate for period #Ci/sec 0.00E+00 2.90E+00
- 3. Percent of technical <
specification limit (2)
(T.S. 3.11.2.3(a)) % 6.21E-04 1.22E-02 (1) For batch releases the estimated overall error is within 10%
(2) Iodine, tritium and particulates are treated as a group ,
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HOPE CREEK GENERATING STATION TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1994 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Nuclides Released Unit Qtr Qtr Qtr Qtr
- 1. Fission Gases Krypton-83m Ci 1.84E-01 1.34E-01 0.00E+00 0.00E+00 Krypton-85m C1 1.84E-01 1.34E-01 0.00E+00 0.00E+00 ,
Krypton-87 Ci 7.37E-01 5.38E-01 0.00E+00 0.00E+00 Krypton-88 Ci 7.37E-01 5.38E-01 0.00E+00 0.00E+00 Krypton-89 Ci 4.98E+00 3.63E+00 0.00E+00 0.00E+00 Xenon-133 Ci 3.13E+00 2.69E-01 5.65E-03 0.00E+00 Xenon-135 Ci 9.22E-01 6.73E-01 9.56E-04 0.00E+00 Xenon-135m Ci 1.11E+00 8.07E-01 0.00E+00 0.00E+00 Xenon-137 Ci 5.71E+00 4.17E+00 0.00E+00 0.00E+00 Xenon-138 Ci 3.50E+00 2.56E+00 0.00E+00 0.00E+00 TOTALS Ci 2.12E+01 1.35E+01 6.61E-03 0.00E+00
- 2. Iodines Iodine-131 Ci 2.56E-05 0.00E+00 1.09E-08 0.00E+00 Iodine-133 Ci 2.96E-05 1.57E-05 0.00E+00 0.00E+00 TOTALS Ci 5.52E-05 1.57E-05 1.09E-08 0.00E+00
- 3. Particulates (half-life >8 days)
Cobalt-60 Ci 0.00E+00 6.03E-06 0.00E+00 0.00E+00 Manganese-54 Ci 3.13E-05 2.36E-04 0.00E+00 1.15E-05 Iron-59 Ci 0.00E+00 4.35E-05 0.00E+00 0.00E+00 Chromium-51 Ci 0.00E+00 3.06E-05 0.00E+00 0.00E+00 Zinc-65 Ci 8.15E-05 5.82E-05 0.00E+00 2.16E-06 Strontium-89 Ci 0.00E+00 0.00E+00 0.00E+00 1.99E-10 TOTALS Ci 1.13E-04 3.74E-04 0.00E+00 1.37E-05 16
I HOPE CREEK GENERATING STATION TABLE 1P EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1994 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE t
I 3rd 4th 3rd 4th Nuclides Released Unit Qtr Qtr Qtr Qtr
- 1. Fission Gases ,
Krypton-83m Ci 1.67E-01 1.99E+00 0.00E+00 0.00E+00 Krypton-85m Ci 1.67E-01 1.99E+00 0.00E+00 0.00E+00 Krypton-87 Ci 6.68E-01 7.96E+00 0.00E+00 0.00E+00 Krypton-88 Ci 6.68E-01 7.96E+00 0.00E+00 0.00E+00 Krypton-89 Ci 4.50E+00 5.37E+01 0.00E+00 0.00E+00 Xenon-133 Ci 3.34E-01 3.98E+00 0.00E+00 0.00E+00 Xenon-135 Ci 8.36E-01 1.21E+01 0.00E+00 0.00E+00 Xenon-135m Ci 1.00E+00 1.19E+01 0.00E+00 0.00E+00 Xenon-137 Ci 5.18E+00 6.17E+01 0.00E+00 0.00E+00 Xenon-138 Ci 3.18E+00 3.7SE+01 0.00E+00 0.00E+00
- 2. Iodines l Iodine-131 Ci 1.67E-06 9.15E-05 0.00E+00 0.00E+00 Iodine-133 Ci 1.62E-03 4.00E-03 0.00E+00 0.00E+00 TOTALS Ci 1.62E-03 4.09E-03 0.00E+00 0.00E+00
- 3. Particulates (half-life >8 days)
Manganese-54 Ci 6.72E-05 1.07E-04 0.00E+00 0.00E+00 Zinc-65 C1 1.62E-04 0.00E+00 0.00E+00 0.00E+00 Cobalt-60 Ci 0.00E+00 2.67E-06 0.00E+00 0.00E+00 i TOTALS Ci 2.30E-04 1.10E-04 0.00E+00 0.00E+00 17 l l
l HOPE CREEK GENERATING STATION TABLE 1C EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1994 GASEOUS EFFLUENTS-ELEVATED RELEASES There were no elevated gaseous releases during this reporting period.
18 -
- HOPE CREEK GENERATING STATION
- TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1994 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est.
1st 2nd Total Units Qtr Qtr Error %
A. Fission and activation products
- 1. Total release (not '
including tritium, gases, alpha) Ci 7.50E-02 3.63E-01 25-
- 2. Average diluted concentration during release period. #Ci/mL 1.19E-07 4.93E-07
- 3. Percent of technical specification limit (T.S. 3.11.1.2.(a)) % 1.83E+00 6.59E+00 B. Tritium
- 1. Total release Ci' 1.26E+01 1.17E+01 25
- 2. Average diluted concentration during release period #Ci/mL 1.99E-05 1.60E-05
- 3. Percent of technical specification limit (T.S. 3.11.1.1) % 6.63E-01 5.33E-01 C. Dissolved and entrained noble gases
- 1. Total release Ci 9.56E-04 1.43E-03 25
- 2. Average diluted concentration during release period. gci/mL 1.52E-09 1.96E-09
- 3. Percent of technical specification limit (T.S. 3.11.1.1) % 7.60E-04 9.80E-04 D. Gross alpha activity
- 1. Total release Ci 0.00E+00 0.00E+00 25 j E. Volume of waste release (prior to dilution -
Batch Release) liters 2.86E+06 3.41E+06 25 F. Volume of dilution water I
,e' used during entire period liters 1.25E+10 1.15E+10 25 l 19
i HOPE CREEK GENERATING STATION TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1994 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est.
3rd 4th Total Units Qtr Qtr Error %
A. Fission and activation products
- 1. Total release (not including tritium, gases, alpha) Ci 3.82E-02 6.02E-02 25
- 2. Average diluted concentration during release period. pCi/mL 1.13E-07 1.11E-07
- 3. Percent of technical specification limit (T.S. 3.11.1.2.(a)) % 1.07E+00 2.90E+00 B. Tritium
- 1. Total release Ci 3.41E+00 5.60E+00 25
- 2. Average diluted concentration during release period pCi/mL 1.01E-05 1.03E-05
- 3. Percent of technical specification limit (T.S. 3.11.1.1) % 3.37E-01 3.43E-01 1
C. Dissolved and entrained noble gases
- 1. Total release Ci 1.01E-03 1.48E-03 25
- 2. Average diluted concentration during release pericd. pCi/mL 2.97E-09 2.73E-09
- 3. Percent of trennical specification 3imit (T.S. 3.11.1.1) % 1.49E-03 1.37E-03 D. Gross alpha activity
- 1. Total release Ci 0.00E+00 0.00E+00 25 E. Volume of waste release (prior to dilution -
Batch Release) liters 1.57E+06 3.62E+06 25 F. Volume of dilution water used during entire period liters 1.41E+10 1.05E+10 25 20
. HOPE CREEK GENERATING STATION TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1994 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE ___
1st 2nd 1st 2nd Nuclides Released Unit Qtr Qtr Qtr Qtr Chromium-51 Ci 0.00E+00 0.00E+00 2.52E-02 3.48E-02 Manganese-54 Ci 0.00E+00 0.00E+00 1.61E-02 5.67E-02 Iron-55 Ci 0.00E+00 0.00E+00 1.33E-02 1.67E-01 Iron-59 Ci 0.00E+00 0.00E+00 4.45E-03 6.09E-03 Cobalt-58 Ci 0.00E+00 0.00E+00 8.99E-04 1.28E-03 Cobalt-60 Ci 0.00E+00 0.00E+00 2.26E-03 5.34E-02 Zinc-65 Ci 0.00E+00 0.00E+00 1.13E-02 4.20E-02 Zinc-69m Ci 0.00E+00 0.00E+00 0.00E+00 7.22E-05 Silver-110m Ci 0.00E+00 0.00E+00 7.04E-04 7.23E-04 Technetium-99m Ci 0.00E+00 0.00E+00 5.69E-04 5.34E-04 Arsenic-76 Ci 0.00E+00 0.00E+00 0.00E+00 1.28E-04 Cesium-134 Ci 0.00E+00 0.00E+00 1.11E-06 0.00E+00 Cesium-137 Ci 0.00E+00 0.00E+00 3.79E-06 0.00E+00 Niobium-97 Ci 0.00E+00 0.00E+00 2.32E-04 0.00E+00 TOTALS Ci 0.00E+00 0.00E+00 7.50E-02 3.63E-01 Tritium Ci 0.00E+00 0.00E+00 1.26E+01 1.17E+01 Xenon-133 Ci 0.00E+00 0.00E+00 1.33E-04 1.92E-04 Xenon-135 Ci 0.00E+00 0.00E+00 8.23E-04 1.24E-03 TOTALS Ci 0.00E+00 0.00E+00 1.26E+01 1.17E+01 21
\ ___ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _
i l-1
! HOPE CREEK GENERATING STATION
- TABLE 2B i
! EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1994 i
- LIQUID EFFLUENTS i
CONTINUOUS MODE BATCH NODE
}
. 3rd 4th 3rd 4th Nuclides Released Unit Qtr Qtr Qtr Qtr Chromium-51 Ci 0.00E+00 0.00E+00- 1.28E-02 6.34E-03 Manganese-54 Ci 0.00E+00 0.00E+00 1.11E-02 2.58E-02 l Iron-55 Ci 0.00E+00 0.00E+00 1.88E-03 4.12E-03 j Iron-59 Ci 0.00E+00 0.00E+00 6.43E-04 1.72E-04
. Cobalt-58 Ci 0.00E+00 0.00E+00 3.23E-04 5.38E-04 4 Cobalt-60 Ci 0.00E+00 0.00E+00 2.70E-03 6.57E-03
! Zinc-65 Ci 0.00E+00 0.00E+00 8.16E-03 1.64E-02 l Silver-110m Ci 0.00E+00- 0.00E+00 2.74E-04 1.97E-04 Technetium-99m Ci O.00E+00 0.00E+00 '2.39E-04 1.08E-04 l Arsenic-76 Ci 0.00E+00 0.00E+00 2.73E-05 6.73E-06 3 Cesium-137 Ci 0.00E+00 0.00E+00 0.00E+00 9.51E-06 f ___________________________..____________..______________________.
! TOTALS Ci 0.00E+00 0.00E+00 3.82E-02 6.02E-02 i
l -
l Tritium Ci 0.00E+00 0.00E+00 3.41E+00 5.60E+00 <
l Xenon-133 Ci 0.00E+00 0.00E+00 2.07E-04 2.92E-04
(
1 Xenon-135 Ci 0.00E+00 0.00E+00 7.98E-04 1.19E-03 I
4 TOTALS Ci 0.00E+00 0.00E+00 -3.41E+00 5.60E+00 l
l 1
1 k
4 1
9 I
i 22 3
i t
)
i, j HOPE CREEK GENERATING STATION d
TABLE 3 i EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT l JANUARY - DECEMBER 1994 '
4
- SOLID WASTE AND IRRADIATED FUEL SHIPMENTS t' :
i SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL j
(Not irradiated fuel)
! 12-month Est. Total i
- 1. Type of wasta Units (1) period Error, 4 j a. Spent resins, filters, m3 1.10E+02 j sludges, evaporator bottoms Ci 2.92E+03 25 j Dry compressible waste, m3 6.60E+01 ;
b.
j contaminated equipment. Ci 1.41E+01 25 l ll c. Irradiated components, m3 0.00E+00 l 1 control rods Ci 0.00E+00 25 l q
- d. Others (described) m3 7.04E+01 i
) Oil, Sewage Sludge Ci 2.71E-02 25 :
I i ,
i
- 2. Estimate of major nuclide composition l
RESINS DAW Oil
! (4) (Ci) (%) (Ci) (%) (Ci)
Zinc-65 23.2 6.77E+02 2.2 1.00E-02 1.8 4.88E-04 Iron-55 60.3 1.76E+03 71.2 4.20E-01 89.5 2.43E-02 Manganese-54 10.7 3.12E+02 8.3 5.00E-02 3.5 9.49E-04 l
! Cobalt-60 3.6 1.10E+02 1.6 1.00E-02 5.2 1.41E-03 j Chromium-51 1.2 3.50E+01 10.9 6.00E-02 0.0 0.00E+00 Iron-59 0.0 0.00E+00 5.2 3.00E-02 0.0 0.00E+00 l
3
- 2. (Continued)
Sewage Sludge l (%) (Ci) i
- Iron-55 56.9 5.57E-6 Cobalt-60 15.8 1.55E-6
}
i Nickel-63 15.7 1.54E-6 l
Manganese-54 8.4 8.23E-7 Zinc-65 3.1 3.04E-7 (1) Volumes are measured, activities are estimated J
23 i
.i i I i l 1
1 i
HOPE CREEK GENERATING STATION TABLE 3 (CONT'D)
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT l JANUARY - DECEMBER 1994 i SOLID WASTE AND IRRADIATED FUEL SHIPMENTS I
- 3. Solid Waste Disposition Number of Mode of Type of Shipments Transportation Destination Containers >
27 Truck Barnwell, SC HIC and 17E Drums 18 Truck Oak Ridge, Tn Strong, Tight Containers 1
l l
I l
! IRRADIATED FUEL SHIPMENTS (Disposition) l l
Number of Mode of Shipments Transportation Destination ;
l None N/A N/A 24 i
HOPE CREEK GENERATING STATION TABLE 4A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1994
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY
- 1. Dates: January 1 - March 31, 1994
- 2. Type of release: Gas
- 3. Number of releases during the lat Qtr: 1
- 4. Total time duration for all releases of type listed above:
2.17E+03 min ;
- 5. Maximum duration for release of type listed above:
2.17E+03 min
- 6. Average duration for release of type listed above:
2.17E+03 min
- 7. Minimum duration for release of type listed above:
2.17E+03 min i
- 8. Average stream flow (dilution flow) during the period of release: N/A ,
f l
- o a*
HOPE CREEK GENERATING STATION TABLE 4A (CONT'D)
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1994
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY
- 1. Dates: April 1 - June 30, 1994
- 2. Type of release: Gas e
- 3. Number of releases during the 2nd Qtr: 2
- 4. Total time duration for all releases of type listed above:
1.93E+03 min
- 5. Maximum duration for release of type listed above:
1.37E+03 min
- 6. Average duration for release of type listed above:
9.66E+02 min
- 7. Minimum duration for release of type listed above:
5.65E+02 min
- 8. Average stream flow (dilution flow) during the period of release: N/A l
l 26
- -s. L m -
. HOPE CREEK GENERATING STATION TABLE 4A (CONT'D)
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1994
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY
)
- 1. Dates: July 1 - September 30, 1994 l
- 2. Type of release: Gas
- 3. Number of releases during the 3rd Qtr: 0
- 4. Total time duration for all releases of type listed above: i 0.00E+00 min
- 5. Maximum duration for release of type. listed above:
0.00E+00 min
- 6. Average duration for release of type listed'above:
0.00E+00 min
- 7. Minimum duration for release of type listed above:
0.00E+00 min l
- 8. Average stream flow (dilution flow) during the period of l release: N/A l i
i 4 .
l
_ . ._______m __ _ - _ _ _ ___
HOPE CREEK GENERATING STATION TABLE 4A (CONT'D)
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1994
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY
- 1. Dates: October 1 - December 31, 1994
- 2. Type of release: Gas
- 3. Number of releases during the 4th Qtr: 2
- 4. Total time duration for all releases of type listed above:
8.31E+02 min
- 5. Maximum duration for release.of type listed above:
5.45E+02 min
- 6. Average duration for release of typa listed above:
4.16E+02 min
- 7. Minimum duration for release of type listed above:
2.86E+02 min
- 8. Average stream flow (dilution flow) during the period of release: N/A 28
HOPE CREEK GENERATING STATION TABLE 4B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1994
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY
- 1. Dates: January 1 - March 31, 1994
- 2. Type of release: Liquid
- 3. Number of releases during the 1st Qtr: 88
- 4. Total time duration for all releases of type listed above:
6.70E+03 min
- 5. Maximum duration for release of type listed above:
1.74E+02 min
- 6. Average duration for release of type listed above:
7.62E+01 min
- 7. Minimum duration for release of type listed above:
1.0E+01 min
- 8. Average stream flow (dilution flow) during the period of release: 24836 gpa I
29
l l
HOPE CREEK GENERATING STATION TABLE 4B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1994
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY
- 1. Dates: April 1 - June 30, 1994
- 2. Type of release: Liquid
- 3. Number of releases during the 2nd Qtr: 93
- 4. Total time duration for all releases of type listed above:
7.32E+03 min
- 5. Maximum duration for release of type listed above:
1.25E+02 min
- 6. Average duration for release of type listed above:
7.70E+01 min
- 7. Minimum duration for release of type listed above:
1.6E+01 min
- 8. Average stream flow (dilution flow) during the period of release: 26449 gpa 30
HOPE CREEK GENERATING STATION TABLE 4B l
(CONT'D) l EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1994
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY
- 1. Dates: July 1 - September 30, 1994
- 2. Type of release: Liquid
- 3. Number of releases during the 3rd Qtr: 44
- 4. Total time duration for all releases of type listed above:
3.27E+03 min
- 5. Maximum duration for release of type listed above:
1.05E+02 min
- 6. Average duration for release of type listed above:
7.44E+01 min
- 7. Minimum duration for release of type listed above:
1.5E+01 min
- 8. Average stream flow (dilution flow) during the period of release: 27373 gpm u
31
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0.0 3 0.1 26 1.3 71 3.4 69 3.3 34 1.6 8 0.4 211 10.2 N 0 0 0.0 5 0.2 28 1.3 60 2.9 35 1.7 18 0.9 1 0.0 147 7.1 NME 0.0 1 0.0 30 1.4 34 1.6 61 2.9 23 1.1 12 0.5 161 7.8 NE O 0.0 0 0.0 16 0.8 49 2.4 46 2.2 10 0.5 5 0.2 126 6.1 ENE G 0.1 17 0.8 22 1.1 3 0.1 2 0.1 1 0.0 48 2.3 E O 0.0 3 0.1 0.0 O 0.0 1 0.0 9 0.4 13 0.6 3 2 0.1 0 28 1.3 ESE 1.0 0.6 0.4 O 0.0 5 0.2 IT 0.8 13 0.6 21 12 9 77 3,7 SE 0.0 8 0.4 18 0.9 28 1.3 24 1.2 13 0.6 3 0.1 94 4.5 SSE 0 0 0.0 4 0.2 20 1.0 31 1.5 35 1.7 13 0.6 0 0.0 103 5.0 5 1.8 0.0 0.1 D 0.0 10 0.5 12 0.6 29 1.4 37 1 2 91 4.4 ssW 1.1 8 0.4 0.0 0 0.0 7 0.3 18 0.9 28 1.3 22 1 84 4.0 sv 1.1 1.4 17 0.8 0.1 4.5 Wsu o 0.0 5 0.2 17 0.8 23 30 2 94 0.0 3 0.1 12 0.6 17 0.8 49 2.4 17 0.8 4 0.2 102 4.9 W 0 2.2 1.5 0 0.0 4 0.2 to 0.5 22 1.1 46 32 22 1.1 136 6.6 WWW 47 2.3 78 3.8 82 4.0 56 2.7 297 14.3 NW D 0.0 5 0.2 29 1.4 0.0 0 0.0 27 1.3 64 3.1 84 4.0 52 2.5 49 2.4 276 13.3 NNW 0 0.0 64 3.1 306 14.7 551 26.6 643 31.0 336 16.2 175 8.4 2075 100.0 0
missius N0uts: 85 mEAN WINO SPEED: 14.2 Table 5 Page 8 of 18 r -
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JOINT DISTRIBUTION OF WIIS DIRECT 10W AIS SPEED ARTIFICIAL ISLAND 1/94 - 3/94 ST ATMOSPMERIC STABILITY CLASS WIND: 300 FT DELTA T: (300-33FT) DIRECTION VS SPEED ONLT WINO SPEED GREJPS OrW) 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUN PERCENT 0.0-0.5 0.6-3.5 M PERCENT M PERCENT M PERCENT M PERCENT M PERCENT M PERCENT M PERCENT DIRECTION 1.2 71 3.4 72 3.4 34 1.6 8 0.4 214 10.2 0 0.0 3 0.1 26 W
1.3 61 2.9 35 1.7 18 0.9 1 0.0 148 7.0 O 0.0 5 0.2 28 2.9 23 1.1 12 0.6 161 7.7 NME 0.0 30 1.4 34 1.6 61 NE O 0.0 1 2.3 46 2.2 10 0.5 5 0.2 126 6.0 0.0 0 0.0 16 0.8 49 EW G 17 0.8 23 1.1 3 0.1 2 0.1 1 0.0 49 2.3 O 0.0 3 0.1 0.1 0.0 E
0.0 9 0.4 13 0.6 4 0.2 2 0 29 1.4 ESE O 0.0 1 0.6 21 1.0 12 0.6 10 0.5 78 3.7 0.0 5 0.2 17 0.P 13 SE 0 28 1.3 25 1.2 13 0.6 8 0.4 100 4.8 0.0 8 0.4 18 DA SSE 0 32 1.5 35 1.7 14 0.7 2 0.1 107 5.1 0.0 4 0.2 20 1.0
$ 0 1.4 37 1.8 0.0 2 0.1 91 4.3 o 0.0 10 0.5 12 0.6 29 1 Ssu 0.9 28 1.3 22 1.0 8 0.4 1 0.0 84 4.0 0.0 7 0.3 18 0.8 SW D 0.2 17 0.8 23 1.1 33 1.6 17 2 0.1 97 4.6 Wsu 0 0.0 5 0.8 50 2.4 17 0.8 4 0.2 103 4.9 0 0.0 3 0.1 12 0.6 17 W
0.2 to 0.5 24 1.1 48 2.3 32 1.5 22 1.0 140 6.7 0 0.0 4 WNW 0.2 29 1.4 47 2.2 78 3.7 82 3.9 54 2.7 29T 14.1 NW 0 0.0 5 64 3.0 85 4.0 52 2.5 49 2.3 277 13.2 0 0.0 0 0.0 27 1.3 NNW 14.6 556 26.5 655 31.2 337 16.0 183 8.7 2101 100.0 0 0.0 64 3.0 306 MISSING MOURS: 59 EAN Wile SPEED: 14.3 Table 5 Page 9 of 18
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0.0 0 0.0 20 0.9 29 1.3 27 1.3 12 0.6 0 0.0 88 4,3 NME O 0.0 1 0.0 13 0.6 34 1.6 24 1.1 12 0.6 0 0.0 84 3.9 NE O 0 0.0 1 0.0 16 0.7 21 1.0 13 0.6 1 0.0 0 0.0 52 2.4 EdE 0.0 0 0.0 0 0.0 12 0.6 to 0.7 2 0.1 1 0 0.0 31 1.4 E
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- 0 0.0 4 0.2 26 1.2 52 2.4 64 3.0 43 2.0 8 0.4 197 9.2 0.0 3 0.1 28 1.3 44 2.0 100 4.6 30 1.4 11 0.5 216 10.0 u 0 0.7 49 2.3 51 2.4 24 1.1 8 0.4 152 7.1 WSW 0 0.0 5 0.2 15 0.0 3 0.1 16 0.7 38 1.8 55 2.6 34 1.6 4 0.2 150 7.0 W D 0 0.0 5 0.2 15 0.7 22 1.0 32 1.5 18 0.8 5 0.2 97 4.5 WNW 1.3 2.4 39 1.8 1.0 NW 0 0.0 2 0.1 21 1.0 27 51 21 161 7.5 0.0 0.0 17 0.8 41 1.9 64 3.0 45 2.1 18 0.8 186 8.6 wuW 0 1 0.0 38 1.8 2 72 12.6 559 26.0 757 35.2 416 19.3 110 5.1 2152 100.0 0
MISSING HOURS: 32 NEAN WIND SPEED: 14.2 <
Table 5 Page 17 of 18
_ _ _ _ _ . _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ - _ - r _ __________________________.____.__________m_ _ _ _ - _ - _ _ _ _ _ . _ _ _ - . _ _ _ . _ _ _ _
ARTIFICIAL ISLAND 4/94 - 6/94 JOINT DISTRl9UTION OF WIND DIRECTION Am SPEE0 SY ATMOSPMERIC STASILITY CLASS win: 300 FT DELTA T: (300-33FT) elRECTION VS SPEED ONLY WIND SPEED GROUPS (MPM) 0.6-3.5 3.6-7.5 T.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT 0.0-0.5 SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT DIRECTION SUM PERCENT SUM PERCENT 0 0.0 16 0.7 33 1.5 84 3.9 25 1.2 1 0.0 159 7.4 '
N 0 0.0 1.3 0.6 0 0.0 88 4.1 0.0 0 0.0 20 0.9 29 1.3 27 12 NNE O 0.6 0 0.0 3.9 0.0 13 0.6 34 1.6 24 1.1 12 84
- 0 0.0 1 0.6 0.0 0 0.0 2.5 0.0 1 0.0 16 0.7 22 1.0 13 1 53 ENE O 0.1 0.0 0.0 1.4 0.0 0 0.0 12 0.6 16 0.7 2 1 0 31 E O 0.0 0.0 0.0 1 0.0 to 0.5 20 0.9 15 0.7 0 0 46 2.1 ESE O 1.6 36 1.7 0.7 118 5.5 0.0 3 0.1 5 0.2 25 1.2 34 15 SE O sn 2.3 0.0 5 0.2 15 0.7 57 2.6 74 3.4 10 0.5 211 9.8 SSE O 0.4 9.6 0.2 27 1.3 51 2.4 69 3.2 46 2.1 9 206 5 0 0.0 4 3.0 43 2.0 8 0.4 9.1 0.0 4 0.2 26 1.2 52 2.4 64 197 sSW 0 2.0 100 4.6 30 1.4 11 0.5 217 10.1 0 0.0 3 0.1 29 1.3 44 SW 2.3 2.4 24 1.1 8 0.4 152 7.1 0 0.0 5 0.2 15 0.7 49 51 Wsw 1.8 55 2.6 34 1.6 4 0.2 7.0 W 0 0.0 3 0.1 16 0.7 38 150 0.2 15 0.7 22 1.0 32 1.5 18 0.8 5 0.2 97 4.5 WWW 0 0.0 5 1.3 51 - 2.4 39 1.8 21 1.0 161 7.5 0.0 0.1 21 1.0 27 w 0 2 0.8 41 1.9 64 3.0 45 2.1 18 0.8 186 8.6 Nw 0 0.0 1 0.0 17 1.8 273 12.7 560 26.0 759 35.2 416 19.3 110 5.1 2156 100.0 0 0.0 38 MISSING MOURS: 28
)
MEAN WIND SPEED: 14.2 Table 5 Page 18 of 18
I i-i l
l HOPE CREEK GENERATING STATION j
- TABLE 4B j (CONT'D)
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT l JANUARY - DECEMBER 1994
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE l
BATCH RELEASES ONLY
- 1. Dates: October 1 - December 31, 1994
- 2. Type of release: Liquid
- 3. Number of releases during the 4th Qtr: 89
- 4. Total time duration for all releases of type listed above:
7.26E+03 min
- 5. Maximum duration for release of type listed above:
1.30E+02 min
- 6. Average duration for release of type listed above:
8.15E+01 min
- 7. Minimum duration for release of type listed above:
1.6E+01 min
- 8. Average stream flow (dilution flow) during the period of release: 19847 gpa i
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WIND SPEED GROUPS (MPN) 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 sum PERCENT 0.0-0.5 0.6-3.5 3.6-7.5 Sim PERCENT SLM PERCENT SLM PERCENT SLM PERCENT SLM PERCENT SUM PERCENT DIRECil04 SUM PERCENT 0.5 8 0.4 2 0.1 41 1.9 0.0 12 0.6 8 0.4 10 W 0 0.0 1 0.3 5 0.2 1 0.0 0 0.0 17 0,8 0.0 0 C.0 5 0.2 6 0.0 0.8 o NNE O 0.2 6 0.3 5 0.2 0 0.0 0 16 O 0.0 1 0.0 4 0.0 0 0.0 0 0.0 8 0.4 r NE 0.0 4 0.2 2 0.1 1 >
ENE O 0.0 1 0.0 2 0.1 0 0.0 0 0.0 10 0.5 0.0 0 0.0 7 0.3 1 0.0 17 0.8 E O 0.0 5 0.2 7 0.3 3 0.1 0 0.0 2 0.1 0 0.5 79 3.7 ESE O 0.2 9 0.4 27 1.3 28 1.3 10 O 0.0 1 0.0 4 50 2.4 5 0.2 1 0.0 94 4.4 SE 0.0 14 0.7 24 1.1 SSE O 0.0 0 1.8 42 2.0 12 0.6 0 0.0 116 5.5 0.1 22 1.0 37 S 0 0.0 3 1.6 56 2.7 9 0.4 1 0.0 116 5.5 0.0 3 0.1 13 0.6 34 0.1 59 2.8 i
SSW 0 0.7 17 0.8 22 1.0 3 0.1 2 0 0.0 1 0.0 14 0.4 0.0 0 0.0 38 1.8 SW 0.1 8 0.4 18 0.9 8 1 WSW 0 0.0 3 0.7 12 0.6 0 0.0 0 0.0 35 1.7 0.0 2 0.1 7 0.3 14 1.9 W 0 0.3 21 1.0 10 0.5 3 0.1 0 0.0 41 0.0 0 0.0 7 1.5 WNW 0 4 0.2 10 0.5 to 0.5 4 0.2 1 0.0 31 0 0.0 2 0.1 0.3 5 0.2 0 0.0 38 1.8 MW 0.6 12 0.6 6 NNW 0 0.0 2 0.1 13 10.6 2 73 12.9 82 3.9 17 0.8 756 35.8 0.0 22 1.0 138 6.5 224 0
MEAN WIND SPEE0: 12.5 MIS $1NG: 0 Table 6 Page 4 of 13
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WIND: 300 FT DELTA T (300-33FT) ALL STAetLITY CLASSES WIND SPEED GROUP $ (MPM) 0.6-3.5 3.6-7.5 7.6-12.5 12.6 18.5 18.6 24.5 GE 24.6- SUM PERCENT 0.0-0.5 Stm PERCENT SLM PERCENT SLM PERCENT SLM PERCENT SUM PERCENT SUM PERCENT OIREttt0N SUM PERCENT 1.3 31 1.5 ' 48 2.3 29 1.4 3 0.1 134 6.3 N O 0.0 1 0.0 22 0.1 11 0.5 26 1.2 25 1.2 4 0.2 0 0.0 69 3.3 NME O 0.0 3 1.0 13 0.6 6 0.3 9 0.4 64 3.0 O 0.0 4 0.2 10 0.5 22 NE 0.1 11 0.5 9 0.4 13 0.6 4 0.2 1 0.0 40 1.9 ENE O 0.0 2 0.5 8 0.4 0 0.0 0 0.0 36 1.7 O 0.0 3 0.1 15 0.7 10 E
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ARTIFICIAL ISLAND 7/94 - 9/94 JOINT DISTRIBUTION OF WINO DIRECTION AND SPEED BY ATMOSPNERIC STASILITY CLASS
- WINO: 300 FT DELTA T: (300-33FT) DIRECTION VS SPEED ONLY WIND SPEED GRWPS 09N) 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT 0.0-0.5 StM PERCENT SLM PERCENT SUM PERCENT SLM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT DIRECTION 0.0 22 1.0 31 1.5 48 2.3 29 1.4 3 0.1 134 6.3 N 0 0.0 1 1.2 4 0.2 0 0.0 69 3.3 O 0.0 3 0.1 11 0.5 26 1.2 25 NME 0.6 6 0.3 9 0.4 64 3.0 O 0.0 4 0.2 to 0.5 22 1.0 13 NE 0.6 4 0.2 0.0 40 1,9 O 0.0 2 0.1 11 0.5 9 0.4 13 1 ENE 0.0 0.0 1.7 o 0.0 3 0.1 15 0.7 to 0.5 8 0.4 0 0 36 E
0.1 7 0.3 20 0.9 18 0.9 5 0.2 0 0.0 53 2.5 ESE O 0.0 3 2.7 39 1.8 to 0.5 163 7.7 0.0 5 0.2 21 1.0 12 1.5 56 SE O 0.3 0.0 9,4 0.0 4 0.2 51 2.4 70 3.3 65 3.1 7 1 19e SSE O 0.7 0 0.0 9.4 0.0 6 0.3 48 2.3 66 3.1 65 3.1 14 199 S 0 5.2 27 1.3 2 0.1 255 12.1 0 0.0 6 0.3 45 2.1 66 3.1 109 SrJ 4.0 82 3.9 25 1.2 6 0.3 257 12.2 SW U 0.0 3 0.1 57 2.7 84 0.2 33 1.6 59 2.8 41 1.9 3 0.1 0 0.0 141 6.7 WSu 0 0.0 5 0.2 0.1 6.3 v 0 0.0 3 0.1 27 1.3 45 2.) 52 2.5 4 2 133 0.1 19 0.9 52 2.5 32 1.5 8 0.4 3 0.1 116 5.5 WNw 0 0.0 2 2.5 9 0.4 0.0 123 5.8 0 0.0 6 0.3 18 0.9 36 1.7 53 1 NV 0.4 0.0 6.2 0.0 9 0.4 32 1.5 53 2.5 28 1.3 9 1 132 NNw 0 3.1 42T 20.2 681 32.2 708 33.5 193 9.1 39 1.8 2113 100.0 0 0.0 65 MIS $lus Mouts: 95 MEAN WIND SPEED: 12.0 Table 6 Page 9 of 18
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ARTIFICIAL ISLAND 10/94-12/94 J0lNT DISTRIBUTION OF WIND OIRECTION AND SPEED BY ATMOSPNERIC STASILITY CLASS WINO: 300 FT DELTA T: (300-33FT) ALL $1AsILITY CLASSES WINO SPEED GROUPS (MPN) 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 $UM PERCENT 0.0-0.5 0.6-3.5 SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT DIRECTION SUM PERCENT 0.4 30 1.4 71 3.3 45 2.1 18 0.8 177 8.3 0.0 5 0.2 8 N O 0.8 33 1.6 78 3.7 42 2.0 2 0.1 177 8.3 NME O 0.0 4 0.2 18 4.0 44 2.1 0 0.0 177 8.3 0.1 15 0.7 32 1.5 84 NE O 0.0 2 0.9 42 2.0 3 0.1 3 0.1 84 4.0 0.0 0.0 15 0.7 20 ENE O 1 9 0.4 30 1.4 to 0.5 4 0.2 0 0.0 55 2.6 o 0.0 2 0.1 0.1 0.1 1.6 E
0.0 7 0.3 9 0.4 11 0.5 3 2 33 ESE O 0.0 1 0.7 18 0.8 7 0.3 9 0.4 57 2.7 0.0 1 0.0 8 0.4 '4 SE O 1.0 18 0.8 35 1.6 15 0.7 4 0.2 98 4.6 O 0.0 4 0.2 22 0.6 0.0 76 3.6 SSE 0.1 0.5 31 1.5 20 0.9 12 0 5 0 ' 0.0 2 11 1.6 74 3.5 33 1.6 12 0.6 172 8.1 0 0.0 4 0.2 15 0.7 34 SSW 0.8 52 2.4 73 3.4 12 0.6 2 0.1 158 7.4 0 0.0 3 0.1 16 sw 0.2 33 1.6 47 2.2 41 . 1.9 19 0.9 4 0.; 149 7,0 WSW 0 0.0 5 1.5 32 1.5 16 0.8 to 0.5 132 6.2 0 0.0 7 0.3 36 1.7 31 W
1.1 18 0.8 26 1.2 22 1.0 13 0.6 107 5.0 WNW 0 0.0 5 0.2 23 1.6 1.0 210 9.9 0.4 22 1.0 49 2.3 75 3.5 35 21 MW 0 0.0 8 2.5 117 5.5 53 2.5 22 1.0 261 12.3 NNW 0 0.0 3 0.1 12 0.6 54 i
12.7 502 23.6 807 38.0 365 17.2 122 5.7 2123 100.0 0 0.0 57 2.7 270 MISSING MOURS: 85 MEAN WINO SPEED: 14.4 Table 6 Page 17 of 18
JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED ARTIFICIAL ISLAND 10/94-12/94 BY ATMOSPMERIC STAetLITY CLASS WIND: 300 FT DIRECTION VS SPEE0 ONLY DELTA T: (300-33FT)
WIND SPEED GROUPS OFN) 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUN PERCENT 0.0-0.5 0.6-3.5 3.6-7.5 SL88 PERCENT SUM PERCENT SLM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT DIRECT 10N 75 3.4 47 2.1 18 0.8 185 8.4 0.2 9 0.4 31 1.4 N O 0.0 5 84 3.8 42 1.9 2 0.1 183 8.3 0.2 18 0.8 33 1.5 8.2 NME O 0.0 4 1.6 84 3.8 44 2.0 0 0.0 180 0.0 2 0.1 15 0.7 35 0.1 3 0.1 86 3.9 NE O 0.7 20 0.9 43 1.9 3 0 0.0. 2 0.1 15 10 0.5 4 0.2 0 0.0 56 2.5 ENE 0.1 to 0.5 30 1.4 O 0.0 2 0.5 3 0.1 2 0.1 35 1.6 E
0.0 8 0.4 10 0.5 11 3.0 ESE O 0.0 1 0.7 24 1.1 9 0.4 9 0.4 66 0.0 0.0 8 0.4 15 0.2 106 4.8 SE O 1 1.3 18 0.8 37 1.7 15 0.7 4 9 0.0 4 0.2 28 0.9 12 0.5 0 0.0 82 3.7 SSE 0.1 15 0.7 32 1.5 20 S 0 0.0 3 1.5 76 3.4 33 1.5 12 0.5 176 8.0 0.0 4 0.2 17 0.8 34 0.1 163 7.4 SSu 0 0.8 54 2.4 74 3.4 12 0.5 2 0 0.0 4 0.2 17 0.9 4 0.2 154 7.0 SW 0.2 34 1.5 51 2.3 41 1.9 19 WSW 0 0.0 5 33 1.5 32 1.5 16 0.7 to 0.5 137 6.2 0.0 7 0.3 39 1.8 4.9 W 0 1.1 19 0.9 26 1.2 22 1.0 13 0.6 109 WNW 0 0.0 5 0.2 24 3.6 35 1.6 21 1.0 216 9.8 9 0.4 22 1.0 50 2.3 79 ~
Nu 0 0.0 2.5 125 5.7 54 2.4 22 1.0 272 12.3 0 0.0 4 0.2 12 0.5 55 NNW 23.6 841 38.1 370 16.8 122 5.5 2206 100.0 2.8 291 13.2 520 0 0.0 62 MISSIWs nouRS: 2 MEAN WIND SPEED: 14.3 Table 6 Page 18 of 18
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l ARTIFICIAL ISLAND 1/94 - 3/94 JOINT DISTRIBUTION OF Wi m DIRECTION AND SPEED BY ATMOSPNERIC STA8tLITY CLASS WIND: 300 FT DELTA T: (300-33FT) ALL STARILITY CLASSES WIND SPEED GROUPS (NPN) 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 sum PERCENT 0.0-0.5 SUM PERCENT SLM PERCENT SUN PERCENT SUM PERCENT SUM PERCENT SUN PERCENT SUN PERCENT DIRECTION 0.1 26 1.3 71 3.4 69 3.3 34 1.6 8 0.4 211 10.2 N 0 0.0 3 1.7 18 0.9 0.0 147 7,1 O 0.0 5 0.2 28 1.3 60 2.9 35 1 NNE 0.0 30 1.4 34 1.6 61 2.9 23 1.1 12 0.6 161 7.8 NE O 0.0 1 46 2.2 to 0.5 5 0.2 126 6.1 G 0.0 0 0.0 16 0.8 49 2.4 ENE 0.1 17 0.8 22 1.1 3 0.1 2 0.1 1 0.0 48 2.3 E O 0.0 3 0.6 3 0.1 2 0.1 0 0.0 28 1.3 O 0.0 1 0.0 9 0.4 13 ESE 0.2 17 0.8 13 0.6 21 1.0 12 0.6 9 0.4 77 3.7 SE 0 0.0 5 1.3 24 1.2 13 0.6 3 0.1 94 4.5 O 0.0 8 0.4 18 0.9 28 SSE 0.2 20 1.0 31 1.5 35 1.7 13 0.6 0 0.0 103 5.0 S O 0.0 4 0.5 12 0.6 29 1.4 37 1.8 1 0.0 2 0.1 91 4.4 SSW 0 0.0 10 1.3 22 1.1 8 0.4 0.0 84 4.0 0 0.0 7 0.3 18 0.9 28 1 SW
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0.0 9 0.4 13 0.6 4 0.2 2 0.1 0 0.0 29 ESE O 0.0 1 0.6 21 1.0 12 0.6 to 0.5 78 3.7 O 0.0 5 0.2 17 0.P 13 SE OA 28 1.3 25 1.2 13 0.6 8 0.4 100 4.8 O 0.0 8 0.4 18 0.7 0.1 5.1 SSE 0.2 20 1.0 32 1.5 35 1.7 14 2 107 5 0 0.0 4 37 1.8 0.0 2 0.1 91 4.3 to 0.5 12 0.6 29 1.4 1 SSW 0 0.0 1.3 22 1.0 8 0.4 0.0 84 4.0 0 0.0 7 0.3 18 0.9 28 1 SW 0.8 23 1.1 33 1.6 17 0.8 2 0.1 97 4.6 WSW 0 0.0 5 0.2 17 0.8 0.2 4.9 0.1 12 0.6 IT 0.8 50 2.4 17 4 103 W D 0.0 3 1.1 48 2.3 32 1.5 22 1.0 140 6.7 0 0.0 4 0.2 10 0.5 24 WWW 0.2 29 1.4 47 2.2 78 3.7 82 3.9 56 2.7 297 14.1 w 0 0.0 5 1.3 64 3.0 85 4.0 52 2.5 49 2.3 277 13.2 WNW 0 0.0 0 0.0 27 14.6 556 26.5 655 31.2 I (7 16.0 183 8.7 2101 100.0 0 0.0 64 3.0 306 l
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I ARTIFICIAL ISLAND 4/94 - 6/94 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPNERIC STABILITY CLASS WIND: 300 FT LAPSE RATE: -0.4 TO 1.5 DEG C/100M DELTA T: (300-33FT) CLASS E j
WIND SPEED GROUPS (MPN) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT SLM PERCENT SUN PERCENT SLM PERCENT SLM PERCENT SLM PERCENT SLM PERCENT DIRECTION SLM PERCENT N O 0.0 0 0.0 5 0.2 9 0.4 24 1.1 15 0.7 1 0.0 54 2.5 0 0.0 0 0.0 7 0.3 9 0.4 11 0.5 6 0.3 0 0.0 33 1.5 NNE NE 0 0.0 0 0.0 3 0.1 6 0.3 7 0.3 3 0.1 0 .0.0 19 0.9 O 0.0 1 0.0 3 0.1 2 0.1 6 0.3 0 0.0 0 0.0 12 0.6 ENE 0 0.0 0 0.0 3 0.1 5 0.2 2 0.1 0 0.0 0 0.0 10 0.5 E
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MEAN WIND SPEED: 14.8 MISSING: 9 Table 5 Page 14 of 18
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Wile SPEED GRGPS (IPN) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6 24.5 GE 24.6 SUN PERCENT SUM PERCENT St#1 PERCENT SUN PERCENT SUN PERCENT SUN PERCENT DI*ECTION SUM PERCENT SUM PERCENT N 0 0.0 0 0.0 16 0.7 33 1.5 84 3.9 25 1.2 1 0.0 159 7.4 O 0.0 0 0.0 20 0.9 29 1.3 27 1.3 12 0.6 0 0.0 88 4.1 NNE O 0.0 1 0.0 13 0.6 34 1.6 24 1.1 12 0.6 0 0.0 84 3.9 NE 0.0 0.0 16 0.7 21 1.0 13 0.6 1 0.0 0 0.0 52 2.4 ENE 0 1 0.0 0 0.0 12 0.6 16 0.7 2 0.1 1 0.0 0 0.0 31 1.4 E O O 0.0 1 0.0 10 0.5 20 0.9 14 0.7 0 0.0 0 0.0 45 2.1 4 ESE I O 0.0 3 0.1 5 0.7 25 1.2 33 1.5 36 1.7 15 0.7 117 5.4 SE 0.0 5 0.2 15 0.1 57 2.6 74 3.4 50 2.3 to 0.5 211 9.8 l SSE 0 0 0.0 4 0.2 27 1.3 51 2.4 69 3.2 46 2.1 9 0.4 206 9.6 i S I 0 0.0 4 0.2 26 1.2 52 2.4 64 3.0 43 2.0 8 0.4 197 9.2 SSW 4.6 1.4 0.5 10.0 0 0.0 3 0.1 28 1.3 44 2.0 100 30 11 216 SW 0.0 5 0.2 15 0.7 49 2.3 51 2.4 24 1.1 8 0.4 152 7.1 WSW D 0.0 3 0.1 16 0.7 38 1.8 55 2.6 34 1.6 4 0.2 150 7.0 W 0 0.0 5 0.2 15 0.7 22 1.0 32 1.5 18 0.8 5 0.2 97 4.5 WNW 0 0.0 2 0.1 21 1.0 27 1.3 51 2.5 39 1.8 21 1.0 161 7.5 NW 0 0 0.0 1 0.0 17 0.8 41 1.9 64 3.0 45 2.1 18 0.8 186 8.6 NNW i
1.8 2 72 12.6 559 26.0 757 35.2 416 19.3 110 5.1 2152 100.0 0 0.0 38 MISSINc MouRS: 32 MEAN WIIe SPEED: 14.2 Table 5 Page 17 of 18
ARTIFICIAL ISLAND 4/94 - 6/94 JOINT DISTRIBUTION Of Wilm DIRECTION AND SPEED BY ATMOSPNERIC STABILITY CLASS WINO: 300 FT DELTA T: (300-33FT) DIRECTION VS SPEED ONLY WIND SPEED GRCJPS (MPN) 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 $UM PERCENT 0.0-0.5 SLM PERCEP' SLDI PERCENT SUM PERCENT SUM PERCENT SUM PERCENT DIRECTION SLM PERCENT SUM PERCENT 0 0.0 16 0.7 33 1.5 84 3.9 25 1.2 1 0.0 159 7.4 N O 0.0 0.6 0.0 4.1 0.0 20 0.9 29 1.3 27 1.3 12 0 88 NME O 0.0 0 1.1 0.6 0 0.0 84 3.9 O 0.0 1 0.0 13 0.6 34 1.6 24 12 NE 0.6 0.0 0 0.0 53 2.5 O 0.0 1 0.0 16 0.7 22 1.0 13 1 ENE 0.0 0 0.0 1.4 0 0.0 12 0.6 16 0.7 2 0.1 1 31 E O 0.0 0.0 0 0.0 0.0 1 0.0 to 0.5 20 0.9 15 0.7 0 46 2.1 ESE O 1.6 36 1.7 0.7 118 5.5 O 0.0 3 0.1 5 0.2 25 1.2 34 15 SE sn 2.3 to 0.5 9.8 0.0 5 0.2 15 0.7 57 2.6 74 3.4 211 SSE O 0.4 9.6 0.0 4 0.2 27 1.3 51 2.4 69 3.2 46 2.1 9 206 5 0 2.0 9.1 0.0 4 0.2 26 1.2 52 2.4 64 3.0 43 8 C.4 197 SSW 0 4.6 1.4 0.5 217 10.1 0 0.0 3 0.1 29 1.3 44 2.0 100 30 11 SW 2.3 2.4 24 1.1 8 0.4 152 7.1 WSW D 0.0 5 0.2 15 0.7 49 51 0.1 16 0.7 38 1.8 55 2.6 34 1.6 4 0.2 150 7.0 W 0 0.0 3 0.8 0.2 97 4.5 0.2 15 0.7 27 1.0 32 1.5 18 5 WNW 0 0.0 5 2.4 39 1.8 1.0 161 7.5 0.1 21 1.0 27 1.3 51 21 w 0 0.0 2 0.8 41 1.9 64 3.0 45 2.1 18 0.8 186 8.6 NNW 0 0.0 1 0.0 17 12.7 560 26.0 759 35.2 416 19.3 110 5.1 2156 100.0 0 0.0 38 1.8 2 73 MISSING HOURS: 28 MEAN WIND SPEED: 14.2 Table 5 Page 18 of 18
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JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED ARTIFICIAL ISLAND 7/94 - 9/94 BY ATMOSPMERIC STABILITY CLASS WINO: 300 FT LAPSE RATE: -1.4 To -0.5 DEG C/100M CLASS 0 DELTA 1: (300-33FT)
WIND SPEED GROUPS (MPM) 12.6-18.5 18.6-24.5 CE 24.6 SUM PERCENT 0.6-3.5 3.6-7.5 7.6-12.5 0.0-0.5 SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT DIRECTION 0.5 8 0.4 2 0.1 41 1.9 0.0 12 0.6 8 0.4 10 0.8 N O .0.0 1 0.3 5 0.2 1 0.0 0 0.0 17 0.0 5 0.2 6 0.0 16 0.8 NME O 0.0 0 6 0.3 5 0.2 0 0.0 0 0.0 1 0.0 4 0.2 0.0 0 0.0 8 0.4 NE O 4 0.2 2 0.1 1 0.0 0 l ENE O 0.0 1 0.0 0.0 2 0.1 0 0.0 0 0.0 10 0.5 0.0 0 0.0 7 0.3 1 0.1 0 0.0 17 0.8 E O 0 0.0 5 0.2 7 0.3 3 0.0 2 0.1 27 1.3 21 1.3 10 0.5 79 3.7 ESE O 0.0 4 0.2 9 0.4 4.4 SE O 0.0 1 1.1 50 2.4 5 0.2 1 0.0 94 0.0 0 0.0 14 0.7 24 0.6 0 0.0 116 5.5 SSE O 22 1.0 37 1.8 42 2.0 12 0 0.0 3 0.1 56 2.7 9 0.4 1 0.0 116 5.5 S
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BY ATMOSPNERIC STABILITY CLASS WINO: 300 FT DELTA T: (300-33FT) ALL STABILITY CLASSES WIND SPEE0 GROUPS (MPN) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 $UM PERCENT SUM PERCENT SUM PERCENT SLM PERCENT SLM PERCENT SUN PERCENT SLM PERCENT DIRECTION SUM PERCENT M 0 0.0 1 0.0 22 1.3 31 1.5 48 2.3 29 1.4 3 0.1 134 6.3 NNE O 0.0 3 0.1 11 0.5 26 1.2 25 1.2 4 0.2 0 0.0 69 3.3 NE 0 0.0 -4 0.2 to 0.5 22 1.0 13 0.6 6 0.3 9 0.4 64 3.0 ENE O 0.0 2 0.1 11 0.5 9 0.4 13 0.6 4 0.2 1 0.0 40 1.9 E O 0.0 3 0.1 15 0.7 to 0.5 8 0.4 0 0.0 0 0.0 36 1.7 ESE O 0.0 3 0.1 7 0.3 20 0.9 18 0.9 5 0.2 0 0.0 53 2.5 SE O 0.0 5 0.2 21 1.0 32 1.5 56 2.7 39 1.8 10 0.5 163 7.7 SSE 0 0.0 4 0.2 51 2.4 70 3.3 65 3.1 7 0.3 1 0.0 198 9.4 S 0 0.0 6 0.3 48 2.3 66 3.1 65 3.1 14 0.7 0 0.0 199 9.4 SSW 0 0.0 6 0.3 45 2.1 66 3.1 109 5.2 27 1.3 2 0.1 255 12.1 SW D 0.0 3 0.1 57 2.7 84 4.0 82 3.9 25 1.2 6 0.3 257 12.2 WSW 0.0 5 0.2 33 1.6 59 2.8 41 1.9 3 0.1 0 0.0 141 6.7 W D 0.0 3 0.1 27 1.3 45 2.1 52 2.5 4 0.2 2 0.1 133 6.3 WNW 0 0.0 2 0.1 19 0.9 52 2.5 32 1.5 8 0.4 3 0.1 116 5.5 .
NW D 0.0 6 0.3 18 0.9 36 1.7 53 2.5 9 0.4 1 0.0 123 5.8 l NNW 0 0.0 9 0.4 32 1.5 53 2.5 28 1.3 9 0.4 1 0.0 132 6.2 1 0 0.0 65 3.1 427 20.2 681 32.2 708 33.5 193 9.1 39 1.8 2113 100.0 MIS $1NG NouRS: 95 MEAN WIND SPEE0: 12.0 Table 6 Page 8 of 18
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JOINT DISTRiguTION Of WIND DIRECTION AND SPEED ARTIFICIAL ISLAND 7/94 - 9/94 BY ATMOSPMERIC STAtlLITY CLASS
- WIND: 300 FT DELTA 1: (300-33FT) DIRECTION VS SPEED outY WIND SPEE0 GROUPS (MPN) 0.6-3.5 3.6 7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUN PERCENT 0.0-0.5 StM PERCENT Stm PERCENT SUN PERCENT SIM PERCENT StM PERCENT DIRECTION SUM PERCENT SUM PERCENT 0.0 22 1.0 31 1.5 48 2.3 29 1.4 3 0.1 134 6.3 l N 0 0.0 1 1.2 4 0.2 0 0.0 69 3.3 O 0.0 3 0.1 11 0.5 26 1.2 25 NME 0.2 to 0.5 22 1.0 13 0.6 - 6 0.3 9 0.4 64 3.0 NE O 0.0 4 0.6 4 0.2 0.0 40 1.9 O 0.0 2 0.1 11 0.5 9 0.4 13 1 ENE 0.7 to 0.5 8 0.4 0 0.0 0 0.0 36 1.7 O 0.0 3 0.1 15 E
0.1 7 0.3 20 0.9 18 0.9 5 0.2 0 0.0 53 2.5 ESE O 0.0 3 2.7 39 1.8 to 0.5 163 7.7 O 0.0 5 0.2 21 1.0 12 1.5 56 SE 2.4 70 3.3 65 3.1 7 0.3 1 0.0 198 9.4 SSE o 0.0 4 0.2 51 0.0 9.4 0.3 48 2.3 66 3.1 65 3.1 14 0.7 0 199 5 0 0.0 6 1.3 0.1 255 12.1 0.0 6 0.3 45 2.1 66 3.1 109 5.2 27 2 SSW 0 3.9 1.2 6 0.3 257 12.2 0 0.0 3 0.1 57 2.7 84 4.0 82 25 SW 0.2 33 1.6 59 2.8 41 1.9 3 0.1 0 0.0 141 6.7 WSW 0 0.0 5 2.5 4 0.2 2 0.1 133 6.3 l 0 0.0 3 0.1 27 1.3 45 2.1 52 W 8 0.4 3 0.1 116 5.5 l 0.0 2 0.1 19 0.9 52 2.5 32 1.5 WNW 0 2.5 9 0.4 0.0 123 5.8 -
0 0.0 6 0.3 18 0.9 36 1.7 53 1 I Nu 0.4 0.0 132 6.2 9 0.4 32 1.5 53 2.5 28 1.3 9 1 NNW 0 0.0 I
427 20.2 681 32.2 708 33.5 193 9.1 39 1.8 2113 100.0 0 0.0 65 3.1 MIS $1NG MOURS: 95 MEAN WIND SPEED: 12.0 1
Table 6 Page 9 of 18
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l ARTIFICIAL ISLAND 10/94-12/94 JOINT olSTRIBUTION OF WINO DIRECTION Am SPEED 8Y ATNOSPNERIC STA8ILITY CLASS Wie: 300 FT DELTA T: (300-33FT) ALL STAsttitY CLASSES Wie SPEED GROJPS (9FM) 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 CE 24.6 SW PERCENT ,
0.0-0.5 SUM PERCENT SUM PERCENT SUM PERCENT SW PERCENT SUM PERCENT otRECTION SLN PERCENT SUM PERCENT 0.4 30 1.4 71 3.3 45 2.1 18 0.8 177 8.3 N 0 0.0 5 0.2 8 8.3 0.2 18 0.8 33 1.6 78 3.7 42 2.0 2 0.1 177 WNE O 0.0 4 4.0 44 2.1 0 0.0 177 8.3 O 0.0 2 0.1 15 0.7 32 1.5 84 NE 0.0 15 0.7 20 0.9 42 2.0 3 0.1 3 0.1 84 4.0 ENE O 0.0 1 0.5 4 0.2 0 0.0 55 2.6 fl 0.0 2 0.1 9 0.4 30 1.4 10 E 0.1 1.6 0.0 7 0.3 9 0.4 11 0.5 3 0.1 2 33 ESE O 0.0 1 0.8 7 0.3 9 0.4 57 2.7 O 0.0 1 0.0 8 0.4 94 0.7 18 SE 4 0.2 22 1.0 18 0.8 35 1.6 15 0.7 4 0.2 98 4.6 SSE O 0.0 0.9 12 0.6 0 0.0 76 3.6 0 0.0 2 0.1 11 0.5 31 1.5 20 5 3.5 33 1.6 12 0.6 172 8.1 D 0.0 4 0.2 15 0.7 34 1.6 74 SSW 0.1 16 0.8 52 2.4 73 3.4 12 0.6 2 0.1 158 7.4 Su o 0.0 3 7.0 0.2 33 1.6 47 2.2 41 1.9 19 0.9 4 0.2 149 WSW 0 0.0 5 1.5 0.8 10 0.5 132 6.2 0.0 7 0.3 36 1.7 31 1.5 32 to W 0 1.0 107 5.0 0.0 5 0.2 23 1.1 _ 18 0.8 26 1.2 22 13 0.6 WNW 0 1.6 1.0 210 9.9 0.0 8 0.4 22 1.0 49 2.3 75 3.5 35 21 W 0 2.5 117 5.5 53 2.5 22 1.0 261 12.3 NNW 0 0.0 3 0.1 12 0.6 54 2.7 270 12.7 502 23.6 807 38.0 365 17.2 122 5.7 2123 100.0 0 0.0 57 MISSING NOURS: 85 MEAN WIND SPEED: 14.4 Table 6 Page 17 of 18
ARTIFICIAL ISLANO 10/94-12/94 JOINT OISTRl8UTION OF WINO clRECTION AND SPEED SY ATMOSPMERIC STAtiLITY CLASS WINO: 300 FT DELTA T: (300-33FT) DIRECil0N VS SPEED ONLY WIND SPEED GROUPS (MPM) 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT 0.0-0.5 0.6-3.5 SLM PERCENT SUM PERCENT SLM PERCENT SUM PERCENT SUM PERCENT SLM PERCENT SLM PERCENT DIRECTION 9 0.4 31 1.4 75 3.4 47 2.1 18 0.8 185 8.4 w 0 0.0 5 0.2 8.3 4 0.2 18 0.8 33 1.5 84 3.8 42 1.9 2 0.1 183 NwE O 0.0 2.0 0 0.0 180 8.2 O 0.0 2 0.1 15 0.7 35 1.6 84 3.8 44 NE 0.7 20 0.9 43 1.9 3 0.1 3 0.1 86 3.9 O 0.0 2 0.1 15 2.5 ENE 0.1 10 0.5 30 1.4 to 0.5 4 0.2 0 0.0 56 E 0 0.0 2 0.5 3 0.1 2 0.1 35 1.6 O 0.0 1 0.0 8 0.4 10 0.5 11 ESE 0.4 0.7 24 1.1 9 0.4 9 0.4 66 3.0 SE 0 0.0 1 0.0 8 15 4.8 0.2 28 1.3 18 0.8 37 1.7 15 0.7 4 0.2 106
$$E O 0.0 4 0.5 0 0.0 82 3.7 0.0 3 0.1 15 0.7 32 1.5 20 0.9 12 5 0 1.5 0.5 176 8.0 0 0.0 4 0.2 17 0.8 34 1.5 76 3.4 33 12 SSW 0.2 17 0.8 54 2.4 74 3.4 12 0.5 2 0.1 163 7.4 SW 0 0.0 4 0.9 0.2 7.0 0.0 5 0.2 34 1.5 51 2.3 41 1.9 19 4 154 wSW D 0.7 0.5 6.2 0.3 39 1.8 33 1.5 32 1.5 16 10 137 v 0 0.0 7 1.0 0.6 4.9 0 0.0 5 0.2 24 1.1 19 0.9 26 1.2 22 13 109 WNW 0.4 22 1.0 50 2.3 79 3.6 35 1.6 21 1.0 216 9.8 uw 0 0.0 9 2.4 1.0 12.3 0 0.0 4 0.2 12 0.5 55 2.5 125 5.7 54 22 272 NNW 2.8 291 13.2 520 23.6 841 38.1 370 16.8 122 5.5 2206 100.0 0 0.0 62 MISSING MouRS: 2 MEAN WINO SPEED: 14.3 Table 6 Page 18 of 18
. _ _ - _ _ ~ _ . _ . _ - _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ - - . _ _ _ - _ _ _ _ _ _ - _ - _ _ _ - _ - - _ - . - _ - _ . _ _ _- -_- - - m v - _ _ - . _ _ _ - - - - _ - _
l f'
AMENDMENT TO RERR 16 I
r*
l J
S.0 NODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORT 8
- our last report (RERR-15) did not include the quarterly Sr-89, Sr-90 and Fe-55 composite data for the first half of 1993. Amended pages to RERR-15 are included at the end of this report.
1 PART B. GASEOUS EFFLUENTS See Summary Tables 1A through 1C.
PART C. LIQUID EFFLUENTS See Summary Tables 2A through 2B. i
{
~
PART D. SOLID WASTE i
! See Summary in Table 3.
1 i
I PART E. RADIOLOGICAL INPACT ON NAN The calculated individual doses in this section are based on actual locations of nearby residents and farms. The population
, dose impact is based on historical site specific data i.e.,
7 food production, milk production, feed for milk animals and seafood production.
4 I The doses were calculated using methods described in !
i Regulatory Guide 1.109 and represent calculations for the six
- month reporting interval. Individual doses from batch and I continuous releases were calculated using the annual averaQa
! historic meteorological dispersion coefficients as described l
in the Offsite Dose Calculation Manual. Population doses were
. calculated using the meteorological dispersion coefficients l l for the six month reporting interval.
}
Liould Pathways .
j Doses to the " maximum hypothetical individual" in the
- i j
population from liquid releases are primarily from the
- seafood ingestion pathway. Calculated doses are as j
shown below.
4 Total body dose : 4.79E-02 mrem Highest organ dose (LIVER): 1.17E-01 mrem
- Dose to the 6 million individuals living within the 50 mile radius of the plant site:
\
i i
,-- .- -. . - - - -- - - - - - . - - ~ - ,
4 1
i ~-
l
. Total population dose: 5.38E-01 person-rem Average population dose: 9.01E-05 aren/ person
(
I Air Pathways i The calculated' doses to individuals via the air i
- pathway are shown below
} Total body dose: 1.57E-01 aren k ;
) Skin dose: 3.43E-01 arem' 1'
j Highest organ dose due to radiciodines and 3
particulates with half lives greater than 8 days:
1
- 1.54E-04 mram to the LIVER 4 Dose to the 6 million individuals living within the
! 50 mile radius of the plant site:
l i Total population dose: 3.01E-01 persoh-rem ,
Average population dose: 5.04E-05 mram/ person s i Direct Radiation Direct radiation may be estimated by Thermoluminescent l
dosimetric (TLD) measurements. One method for
- comparing TLD measurements is by comparison with pre- ,
! operational data. It should be noted that the TLDs
- measure direct radiation from both the Salem and Hope
- creek Generating Stations at Artificial Island, and
- natural background radiation. <
! TLD data for the six month reporting period is given below:
- i l TLD Location Measurement i
2S-2 0.3 mile 5.8 mrad / month f SS-1 0.9 mile 6.3 mrad / month l I
These values are interpreted to represent natural 4 background, since the values are within the statistical variation associated with the pre-operational program results, which are 3.7 mrad / month for location 2S-2, and 4.2 mrad / month for location
! SS-1.
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HOPE CREEK GENERATING STATION TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1993 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est.
3rd 4th Total Units Quarter Quarter Error %
A. Fission and activation products
- 1. Total release (not including tritium, gases, alpha) Ci 8.76E-02 8.92E-02 -25
- 2. Average diluted concentration during release period. #Ci/mL 5.58E-08 1.54E-07
- 3. Percent of technical specification limit (T.S. 3.11.1.2.(a)) % 1.44E+00 1.75E+00 B. Tritium
- 1. Total release Ci . 2.22E+01 1.31E+01 25-
- 2. Average diluted concentration during release period -
- Ci/mL 1.42E-05 2.26E-05
- 3. Percent of technical specification limit ,
(T.S. 3.11.1.1) % 4.73E-01 7.53E-01 l C. Dissolved and entrained noble gases
- 1. Total release Ci 2.42E-03 1.28E-03 25
- 2. Average diluted concentration during release period. #Ci/mL 1.54E-09 2.21E-09
- 3. Percent of technical specification limit (T.S. 3.11.1.1) % 7.70E-04 1.11E-03 D. Gross alpha activity
- 1. Total release Ci 0.00E+00 0.00E+00 25 E. Volume of waste release '
(prior to dilution -
Batch Release) liters 4.58E+06 2.98E+06 25 f F. Volume of dilution water ;
used during entire period liters 1.90E+10 1.22E+10 25 l 15
. . -. - . . . . . . . . . ~. - . .
)
f
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i I; HOPE CREEK GENERATING STATION
.) TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l JULY - DECEMBER 1993 j
! LIQUID EFFLUENTS
(
i CONTINUOUS MODE BATCH MODE l' '
4 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter ;
l Niobium-97 Ci 0.00E+00 0.00E+00 4.33E-04 0.00E+00 l 4.44E-02
~
Chromium-51 Ci 0.00E+00 0.00E+00 3.64E-02 [
Manganese-54 Ci 0.00E+00 0.00E+00 1.53E-02 1.68E-02 ,
r Iron-55 Ci 0.00E+00 0.00E+00 1.44E-02 8.05E-03 l Iron-59 Ci 0.00E+00 0.00E+00 1.76E-03 4.94E ;
j Cobalt-58 Ci 0.00E+00 0.00E+00 1.22E-04 9.69E-04 ,
1 Cobalt-60 Ci 0.00E+00 0.00E+00 2.85E-03 2.61E-03 ;
Zinc-65 Ci 0.00E+00 0.00E+00 1.50E-02 1.05E-02 i j Zinc-69m Ci 0.00E+00 0.00E+00 0.00E+00 2.33E-05 Silver-110m Ci 0.00E+00 0.00E+00 9.05E-04 4.13E-04 .
6.10E-07 j Sodium-24 Ci 0.00E+00 0.00E+00 4.40E-06 !
) Technetium-993 Ci 0.00E+00 0.00E+00 4.50E 4.10E-04 ,
j Arsenic-76 Ci 0.00E+00 0.00E+00 1.03E-05 0.00E+00 !
j Casium-137 Ci 0.00E+00 0.00E+00 3.34E-07 4.82E-05 {
Zirconium-97 Ci 0.00E+00 0.00E+00 1.45E-05 0.00E+00 >
l y ,
- 8.76E-02 8.92E-02 TOTALS Ci- 0.00E+00 0.00E+00 [
j j Tritium Ci 0.00E+00 0.00E+00 2.22E+01 1.31E+01
- Xenon-133 Ci 0.00E+00 0.00E+00 3.14E-04 9.26E-05 Xenon-135 Ci 0.00E+00 0.00E+00 2.10E-03 1.19E-03 j
4 I i TOTALS Ci 0.00E+00 0.00E+00 2.22E+01 1.31E+01 i I .
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J Change #9 l Pages: Appendix A and Appendix B t
Change to:
Updated Appendix A and Appendix B to include data from liquid releases occurring from 1991 through 1993. Recalculated a default effective MPC using the updated information.
Change #10 Updated Figures E-1 and E-2 for Environmental Sampling Locations.
Change #11 Page: 23 Change to:
Changed the reporting requirement of the Radioactive Effluent Release Report from semi-annual to annual. This change is in accordance with Technical Specification Amendment 67.
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i REVISION 14 OF THE HOPE CREEK OFFSIT.3 DOSE CALCUIATION MANUAL Y Attached is a breakdown of the revisions made to the Hope Creek f Generating Station Offsite Dose Calculation Manual (ODCN). The revision was made to update the setpoint formula for liquid i affluent monitors by providing'a comprehensive method for I accounting for non-gamma emitting radionuclides and to correct previous typographical errors.
] J
- i Change #1 i
l Page 4
{
i Change From: :
1 i
1 MPC,
- CTBD l -------------- + bkg j SP $
j RR
) with:
1 1
)
l EC i
- MPC, = -------------------
1 C, i E MPCs l
Change To:
MPC,
- CTBD
- CF j
SP $ -------------------- + bkg l
with:
j E C, (gamma emitters only) j MPC, = -------------------------------
i Ci (gamma) ;
- r ____________ i i MPC, i 1
I' 1
i
i i
4 Where:
4 i SP = alarm setpoint corresponding to the maximum
- allowable release rate (uci/ml). ,
MPC, = an effective MPC value for the mixture of !
i radionuclides in the affluent stream. (uci/ml) !
Ci = the concentration of radionuclide in the liquid
{
j effluent (uci/ml).
the MPC value corresponding to radionuclide i from MPC, =
l 10 CFR 20, Appendix B, Table II, Column 2
=
(uci/ml).
the cooling-tower blowdown discharge rate at the J CTBD ,
time of release (gal / min).
! RR = the liquid affluent release rate (gal / min) at the j monitor location (i.e., at the liquid radwaste e monitor or at the CTBD monitor).
Y bkg = the background of the monitor. (uci/al) .
CF = correction factor for contribution of non-gamma j emitting radionuclides, radiation monitor ,
i inaccuracies, and sampling variability.
l t l Reasons ,
s change in formula will allow for a single correction factor (CF) to account for the contribution of non-gamma emitting nuclides, inaccuracies associated with radiation detection, and sample j
variability. The contribution of non-gamma emitting nuclides is J
required by Technical Specification 3.11.1.1. ,
'l I Justifications l The instrumentation used to detect radioactivity in the liquid '
effluent stream is only sensitive to gamma radiation. Non-gamma l
emitting radionuclides such as iron-55, strontium-89,90, and tritium will be accounted for through the use of a correction factor. The correction factor (CF) will reduce the ' predetermined i setpoint for the liquid radwaste monitor to ensure the liquid j release is terminated before the limits specified in 10 CFR 20 j Appendix B, Table II are reached. The correction factor will also account for radiation monitor uncertainties and provide l
additional conservatism to allow for changes in radionuclide distribution that may occur when a release is in progress.
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--a--* ,~4 sa 4 u, m ,4 :a n -s.,_ --- --~.n - -
% -,sL- - - - - _
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! Change #2 i
j Page 4 1
Change from:
I
- Note: The concentration mix must include the most recent
! composite of alpha emitters, Sr-89, Sr-90, Fe-55 and H-3 as per Technical Specification 3.11.1.1.
l 1
- Change to
4 i Removed note from page. Nuclides stated in the note are accounted for in the correction factor listed in the formula as shown in j change #1.
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J Change #3
! Page 5 i
l Change to:
i j 1. Added new effective NPC default value from Appendix A.
j 2, Added a 0.5 correction factor for calculating setpoints in accordance with equation 1.2.
j 3. Added a 0.75 conservatism factor when calculating default j setpoints to allow for variations in nuclide distribution.
4
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Change #4 j Pages 11,24,33,35,39,41,42 I
i Change to:
a a
j Corrected typographical errors from previous revisions
- (misspelled words, missing exponents).
I Change is ,
Pages 1,11,111 l Reformatted document for easier reading i
i 1
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. _ _ .- i
- u .A:s 4sA we. --mm A-- ~J Change #6 Pages 29,31 Added site related ingestion dose commitment factor and bioaccumulation factor for Arsenic-76.
Reason:
To enable dose projections to be performed due to the release of Arsenic-76 in liquid effluents. Bioaccumulation values for Arsenic-76 were taken from United States Atomic Energy Commission Report, UCRL-50564, Concentration Factor of Chemical Elements in Edible Anuatic Oraanisms.
Site related ingestion dose commitment factor for Arsenic-76 was calculated using ODCM equation 1.6 and dose conversion factors from Federal Guidance Report #11, Limitinc Values of Radionuclide Intake and Air Concentration and Dose Conversion factors for Inhalation, Submersion, and Incestion.
Change #7 Page 28 Change to:
- 1. Changed default value of MPC, to value calculated in Appendix A.
- 2. Calculated default setpoints for RE4861 (Liquid Radwaste) and RE8817 (Cooling Tower Blowdown) uaing the updated MPC,.
Change #8 Page 35 Changed ventilation setpoint ( S,) to ventilation setpoint (SP) to be consistent with equation 2.3. Removed S, (Q) parameters for clarity.
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HOPE CREEK ODCM REVISION 14 ;
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REVISION 14 OF THE HOPE CREEK OFFSITE DOSE CALCULATION MANUAL Attached is a breakdown of the revisions made to the Hope Creek Generating Station Offsite Dose Calculation Manual (ODCM). The revision was made to update the setpoint formula for liquid effluent monitors by providing a comprehensive method for accounting for non-gamma emitting radionuclides and to correct previous typographical errors.
l
! Change #1 l
Page 4 Change From:
MPC,
EC i MPC, = -------------------
Ci E
MPC, Change To:
MPC,
- CTBD
E C, (gamma emitters only)
MPC, = -------------------------------
Ci (gamma) 3 ____________
MPCi l
i i
i f
i
' Where:
i
! SP' = alarm setpoint corresponding to the maximum j allowable release rate (uci/ml).
- MPC, = an effective NPC value for the mixture of radionuclides in the affluent stream. (uci/ml)
C,i
= the concentration of radionuclide in the liquid il effluent (uci/ml).
the MPC value corresponding to radionuclide i from MPC =
j 3
10 CFR 20, Appendix B, Table II, Column 2
! (uci/ml).
the cooling-tower blowdown discharge rate at the CTBD =
l time of release (gal / min).
RR = the liquid affluent release rate (gal / min) at the i l
monitor location (i.e., at the liquid radwaste l monitor or at the CTBD monitor).
5 bkg = the background of the monitor. (uci/ml). ,
l j CF = correction factor for contribution of non-gamma i emitting radionuclides, radiation monitor i.
inaccuracies, and sampling variability. ;
i- ;
i Reasons '
1 I
Change in formula will allow for a single correction factor (CF) ;
to account for the contribution of non-gamma emitting nuclides, i inaccuracies associated with radiation detection, and sample !
j variability. The contribution of non-gamma emitting nuclides is l
. required by Technical Specification 3.11.1.1.
- I i l s
- Justifications The instrumentation used to detect radioactivity in.the liquid j l effluent stream is only sensitive to gamma radiation. Non-gamma 1 i emitting radionuclides such as iron-55, strontium-89,90, and l tritium will be accounted for through the use of a correction ~
factor. The correction factor (CF) will reduce the predetermined setpoint for the liquid radwaste monitor to e'qure the liquid j
release is terminated before the limits spec. led in 10 CFR 20 Appendix B, Table II are reached. The correction factor will also account for radiation monitor uncertainties and provide additional conservatism to allow for changes in radionuclide distribution that may occur when a release is in progress.
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l
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i Change #2 Page 4 l
Change from: l l
- Note: The concentration mix must include the most recent composite of alpha emitters, Sr-89, Sr-90, Fe-55 and H-3 as per Technical specification 3.11.1.1.
Change to:
Removed note from page. Nuclides stated in the note are accounted for in the correction factor listed in the formula as shown in change #1.
Change #3 Page 5 Change to:
- 1. Added new effective MPC default value from Appendix A.
2, Added a 0.5 correction factor for calculating setpoints in accordance with equation 1.2.
- 3. Added a 0.75 conservatism factor when calculating default setpoints to allow for variations in nuclide distribution.
Change #4 l Pages 11,24,33,35,39,41,42 Change to:
Corrected typographical errors from previous revisions (misspelled words, missing exponents).
Change #5 Pages 1,11,111 Reformatted document for easier reading I
l 3 ,
1
1 Change #6 Pages 29,31 Added site related ingestion dose commitment factor and bioaccumulation factor for Arsenic-76.
Reason:
To enable dose projections to be performed due to the release of Arsenic-76 in liquid affluents. Bioaccumulation values for Arsenic-76 were taken from United States Atomic Energy Commission Report, UCRL-50564, Concentration Factor af Chemical Elements in Edible Anuatic Orqpnisms.
Site related inger.cion dose commitment factor for Arsenic-76 was calculated using ODCM equation 1.6 and dose conversion factors from Federal Guidance Report #11, Limitina values of Radionuclide Intake and Air Concentration and Dose Conversion factors for Inhalation. Suh==rsion, and Incestion.
Change #7 ,
Page 28 ,
1 Change to:
- 1. Changed default value of MPC, to value calculated in j Appendix A. ,
- 2. Calculated default setpoints for RE4861 (Liquid Radwaste) and l RE8817 (Cooling Tower Blowdown) using the updated MPC . !
Change #8 Page 35 Changed ventilation setpoint (S,) to ventilation setpoint (SP) to be consistent with equation 2.3. Removed S, (Q) parameters for clarity.
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l Change #9 i
Appendix A and Appendix B Pages:
Change to:
Updated Appendix A and Appendix B to include data from liquid releases occurring from 1991 through 1993. Recalculated a default effective MPC using the updated information.
Change #10 Updated Figures E-1 and E-2 for Environmental Sampling Locations.
Change #11 Page: 23 Change to:
Changed the reporting requirement of the Radioactive Effluent Release Report from semi-annual to annual. This change is in accordance with Technical Specification Amendment 67.
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OFFSITE DOSE CALCULATION NANUAL l FOR PUBLIC SERVICE ELECTRIC AND GAS COMPANY ROPE CREEK GENERATING STATION Revision 14 July 1994 i
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Approval:
SORC Chairman: - Date: 7/4hd Mtg.# CN -033 l '/
f ssggjgth Y
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Hope Creek ODCM Rev 14 h
! EOPE CREEE GENERnTING STATION OrrsITE DOSE CaLCvLaTIOm NamenL I TABLE OF CONTENTS INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 h i
i 1.0 LIQUID EFFLUENTS
{ 1.1 Radiation Monitoring i Instrumentation and Controls . . . . . . . . . . . . . . . 2 4
i '
1 1.2 Liquid Effluent Monitor i Setpoint Determination . . . . . . . . . . . . . . . . . . 3 i
1.2.1 Liquid Effluent Monitors . . .. . . . . . . . . . 4 -
} 5 j 1.2.2 Conservative Default Values . . . . . . . . . . .
4
} 1.3 Liquid Effluent Concentration j Limits -10 CFR 20 . . . . . . . . . . . . . . . . . . . . . 6 i
I 1.4 Liquid Effluent Dose j Calculations - 10 CFR 50 . . . . . . . . . . . . . . . . . 7 1.4.1 Member of the Public Dose -
Liquid Effluents . . . . . . . . . . . . . . . . 7 3 1.4.2 Simplified Liquid Effluent 4
Dose Calculation . . . . . . . . . . . . . . . 9 1
i 1.5 Liquid Effluent Dose Projections . . . . . . . . . . . . 10 I
i 2.O GASEOUS EFFLUENTS
} 2.1 Radiation Monitoring i Instrumentation and Controls . . . . . . . . . . . . . . 11 i
l 2.2 Gaseous Effluent Monitor ;
Setpoint Determination . . . . . . . . . . . , . . . . . 12 l
i i 2.2.1 Plant Vent and FRVS Monitors . . . . . . . . . 12 j 2.2.2 Conservative Default Values . . . . . . . . . . 14 1
2.3 Gaseous Effluent Instantaneous i Dose Rate Calculation - 10 CFR 20 . . . . . . . . . . . . 15 l
I 2.3.1 Site Boundary Dose Rate -
Noble Gases . . . . . . . . . . . . . . . . . . 15 2.3.2 Site Boundary Dose Rate -
j' Radioiodine and Particulates . . . . . . . . . 17 i
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Hope Creek ODCM Rev 14 l
l 2.4 Noble Gas Effluent Dose 18 Calculations - 10 CFR 50 . ........ . . . . . . .
2.4.1 UNRESTRICTED AREA Dose - 18 Noble Gases . . . .. . . ......... . .
2.4.2 Simplified Dose Calculation 19 for Noble Gases . ... . .. . .. . . . . . .
2.5 Radiciodine and Particulate Dose 20 Calculations - 10 CFR 50 . .. . . .... . . . . . . .
2.5.1 UNRESTRICTED AREA Dose -
Radioiodine and Particulates . . . . . . . . . 20 2.5.2 Simplified Dose Calculation for 21 Radiciodines and Particulates . . . . . . . . .
Gaseous Effluent Dose Projection . .... . . . . . . . 22 2.6 3.0 SPECIAL DOSE ANALYSIS 3.1 Doses Due to Activities Inside 23 the SITE BOUNDARY . . . . .... . .... . . . . . . .
3.2 Total Dose to MEMBERS OF THE PUBLIC - 23 40 CFR 190 . . . . . . . .... .... . . . . . . . .
1 Effluent Dose Calculation . . . . . . . . . . . 24 '
3.2.1 Direct Exposure Determination . .. . . . . . . 24 3.2.2
. . . . . . . . 25 4.0 RADIOIAGICAL ENVIRONMENTAL MONITORING PROGRAM
. . . . ....... . . . . . . . . . 25 4.1 Sampling Program Interlaboratory Comparison Program ......... . . 25 4.2 l
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Hope Creek ODCM Rev 14 1
! TABLES i
1 i 1-1 Parameters for Liquid Alarm Satpoint Determination . . . . . . . . . . . . . . . . . 28 ,
j
- 1-2 Site Related Ingestion Dose Commitment Factors, Aio . . . . . . . . . . . . . . . . . 29 j
Bioaccumulation Factors (BFi) . , . . . . . . . . . . . . 31 j 1-3 3 34 j 2-1 Dose Factors for Noble Gases . . . . . . . . . . . . . .
l 2-2 Parameters for Gaseous Alarm 35 j Setpoint Determination . . . . . . . . . . . . . . . . .
2-3 controlling Locations, Pathways
] and Atmospheric Dispersion for j; Dose Calculations . . . . . . . . . . . . . . . . . . . . 36
- 2-4 Pathway Dose Factors - '
Atmospheric Releases . . . . . . . . . . . . . . . . . . 37 4
A-1 Calculation of Effective MPC . . . . . . . . . . . . . . A-3 f
3 B-1 Adult Dose Contributions Fish end B-4 Invertebrate Pathways . . . . . . . . . . . . . . . . . .
- C-4 1 C-1 Effective Dose Factors . . . . . . . . . . . . . . . . .
D-1 Infant Dose Contribution Fraction of Dose . . . . . . . . D-3 l D-3 l D-2 Fraction of Dose Contributions by Pathway . . . . . . . .
E-1 Sample Locations . . . . . . . . . . . . . . . . . . . . E-2
{
2
' APPENDICES Appendix A - Evaluation of Conservativa, Default MPC Value for Liquid Effluents . . . . . . . . . . . A-1 l Appendix B - Technical Basis for Eff1ctive Dose B-1 l
Factors - Liquid Radioactive Effluents . . . . . . .
l Appendix C - Technical Basis for Effective Dose C-1 j Factors - Gaseous Radioactive Effluents . . . . . .
Appendix D -
Technical Basis for Effective Dose D-1
' Parameters - Gaseous Radioactive Effluents . . . . .
\
l Appendix E - Radiological Environmental Monitoring 4
Program - Sample Type, Location and Analysis . . . . E-1
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i i Hope Creek ODCM Rev 14 j
J j BOPE CREEK GENERATING STATION OFFSITE DOSE CALCULATION NANUAL j INTRODUCTION
- Tho Hope Creek Offsite Dose Calculation Manual (ODCM) describes the acthodology and parameters used in
\
l j 1) the calculation of radioactive liquid and gaseous affluent monitoring instrumentation alarm / trip setpoints; and l l
- 2) the calculation of radioactive liquid and gaseous concentrations, dose rates and cumulative quarterly and yearly doses.
Tha methodology stated in this manual is acceptable for use in dszonstrating compliance with 10 CFR 20.106, 10 CFR 50, Appendix I and 40 CFR 190.
More conservative calculation methods and/or conditions (e.g., location ~
cnd/or exporitre pathways) expected to yield higher computed doses for tha maxima *Jy exposed person may be assumed in the dose evaluations.
Th3 ODCM will be maintained at the station for use as a reference guide and training document of accepted methodologies and calculation.
Changes will be made to the ODCM calculation methodologies and parameters as is deemed necessary to ensure reasonable conservatism in kesping with the principles of 10 CFR 50.36a and Appendix I for dsmonstrating radioactive effluents are ALARA.
NOTE: As used throughout this document, excluding acronyms, words appearing all capitalized denote the application of definitions as used in the Hope Creek Technical Specifications.
1
Hope Creek ODCM Rev 14 1.0 LIOUID EFFLUENTS 1.1 Radiation Monitorina Instrumentation and controls i
The liquid effluent monitoring instrumentation and controls at Hope Creek for controlling and monitoring normal radioactive material releases in accordance with the Hope Creek Radiological Effluent Technical Specifications are summarized as follows:
i 1
(and Automatic Termination) - Liquid l 1) Alarm Radwaste Discharge Line Monitor provides the alarm and automatic i
j termination of liquid (RE4861) radioactive material releases from the liquid waste management system as required by Technical 4 Specification 3.3.7.10.
i
)
- 2) Alarm (oniv) - The Cooling-Tower Blowdown Effluent Monitor j (RE8817) provides an Alarm function only for releases into the j environment as required by Technical Specification 3.3.7.10.
- Liquid radioactive waste flow diagrams with the applicable, i associated radiation monitoring instrumentation and controls are presented in Figure 1-1.
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Hope Creek ODCM Rev 14 l 1.2 Liauid Effluent Monitor Setcoint Determination Per the requirements of Technical Specification 3.3.3.10, alarm setpoints shall be established for the liquid monitoring instrumentation to ensure that the release concentration limits of Specification 3.11.1.1 are met (i.e., the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR 20 Appendix B. Table II, column 2, for radionuclides and 2.0E-04 uCi/ml for dissolved or entrained noble gases). The following equation
- must be satisfied to meet the liquid effluent restrictions:
I C (F + f) c$ -------------
(1.1) f whsre:
C = the effluent concentration limit of Technical Specification (3.11.1.1) implementing the 10 CFR 20 MPC for the site, in l uCi/ml.
c = the setpoint, in uCi/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, represents a value which, if exceeded, would result in concentrations exceeding the limits of 10 CFR 20 in the UNRESTRICTED AREA.
f =.the flow rate at the radiation monitor location, in volume per unit time, but the same units as F, below.
F = the dilution water flow rate as measured prior to the release point, in volume per unit time.
[ Note that if no dilution is provided, c 1 C. Also, note that when (F) 10 large compared to (f), then (F + f) = F.]
* Adopted from NUREG-0133 3
Q Hope Creek ODCM Rev 14 1.2.1 Liquid Effluent Monitors The setpoints for the liquid affluent monitors at the Hope Creek Generating Station are determined by the following equation:
MPC,
- CTBD
RR with:
ECi (gamma emitters only)
MPC, = ---------------------------- (1.3)
C;(gamma) r _____.____
MPC i where:
SP = alarm setpoint corresponding to the maximum allowable release rate (uci/al) .
MPC,= an effective MPC value for the mixture of radionuclides i in the affluent stream, (uci/ml). l Ci = the concentration of radionuclide in the liquid affluent (uci/ml)*.
M P C,i = the NPC value corresponding to radionuclide i from 10 CFR 20, Appendix B, Table II, Column 2 (uci/al).
CTBD = the Cooling-Tower Blowdown Discharge rate at the time of release (gal / min).
RR = the liquid affluent release rate (gal / min) at the monitor location (i.e., at the liquid radwaste monitor or at the CTBD monitor).
CF = correction factor for contribution of non-gamma emitting radionuclides, radiation monitor inaccuracies, and ,
sampling variability. l bkg = the background of the monitor (uci/ml).
The radioactivity monitor setpoint equation (1.2) remains valid during outages when the Cooling-Tower Blowdown discharge is potentially as its lowest value. Reduction of the waste stream flow (RR) may be necessary during these periods to meet the discharge criteria. Procedural restrictions prevent simultaneous liquid releases.
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Hope Creek ODCM Rev 14 1.2.2 conservative Default values l
l Conservative alarm setpoints may be determined through the use of )
default parameters. Table 1-1 summarized all current default i
)
values in use for Hope Creek. They are based upon the following:
l a). substitution of the effective NPC value with a default value of 1.10E-04 uCi/al for radwaste releases (Refer to Appendix A for justification); i b) substitutions of the Cooling-Tower Blowdown discharge rate with the minimum average flow, in gal / min; and, c) substitutions of the affluent release rate with the ,
highest allowed rate, in gal / min. !
d) substitution of a correction factor of 0.5 to account for non-gamma emitting nuclides, radiation monitor uncertainties, and variability in sample analysis.
e) substitution of a 0.75 conservatism factor to allow for variations in nuclide distribution.
With preestablished alarm setpoints, it is possible to control the radwaste release rate (RR) to ensure the inequality of equation (1.2) is maintained under changing values for MPCs and for differing Cooling-Tower Blowdown discharge. 1 i
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e Hope Creek ODCM Rev 14 1.3 Lieuid Effluent concentration Limits - 10 CFR 20 i Technical Specification 3.11.1.1 limits the concentration of radioactive material in liquid effluents (after dilution in the Cooling-Tower Blowdown Discharge System) to less than the concentrations as specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than noble gases. Noble gases are limited to a diluted concentration of 2.0E-04 uCi/al. Release '
rates are controlled and radiation monitor alarm setpoints are established as addressed above to ensure that these concentration limits are not exceeded. However, in the event any liquid release results in an alarm setpoint being exceeded, an evaluation of compliance with the concentration limits of Technical -
Specification 3.11.1.1 may be performed using the following equation:
C, RR 11 (1.4)
ci = actual concentration of radionuclide i as measured in the undiluted liquid effluent (uci/ml).
MPC, = the NPC value corresponding to radionuclide i from 10 CFR 20, Appendix B, Table II, Column 2 (uci/ml).
= 2E-04 uCi/ml for dissolved or entrained noble gases.
RR = the actual liquid affluent release rate (gal / min)
CTBD = the actual Cooling-Tower Blowdown discharge at the time of release (gal / min).
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l Hope Creek ODCM Rev 14 1.4 Limuid Effluent Dose calculation - 10 CFR 50 1.4.1 MWMBER OF THE PUnLIC Dome - Lieuid Effluents Technical Specification 3.11.1.2 limits the dose or dose commitment to MEMBERS OF THE PUBLIC from radioactive materials in liquid affluents from Hope Creek Generating Station to:
- during any calendar quarter: )
5 1.5 mram to total body )
1 5.0 mram to any organ !
- during any calendar year: , !
$ 3.0 mrem to total body
$ 10.0 arem to any organ l
Per the surveillance requirements to Technical Specification 4.11.1.2, the following calculation i methods shall be used for determining the dose or dose ;
commitment due to the liquid radioactive effluents from i Hope Creek. j 8.35E-04
- VOL
= --------------------
- Ao) 1.5 D. *I (Ci i CTBD where:
D. = dose or dose commitment to organ o, including total body (arem).
Ao i
= site-related ingestion dose commitment factor to the total body or any organ o for radionuclide 1 (aren/hr per uCi/al).
Ci = average concentration of radionuclide i, in undiluted liquid affluent representative of volume VOL (uCi/ml).
VOL = volume of liquid affluent released (gal).
CTBD = Average Cooling-Tower Blowdown discharge rate during release period fgal/ min).
8.35E-04 = conversion factor (1.67E-2 hr/ min) and a near field dilution factor of 0.05 (refer to Appendix B, Page B-4 for definition).
7
Hope Creek ODCM Rev 14 The site-related ingestion dose / dose commitment factors (Aw) are presented in Table 1-2-and have been derived in accordance with a i NUREG-0133 by the equation: ,
Ag = 1.14E5 [(UI
- BI) i + (UF
- BF i) ) DFi (1.6) where: f Aw
= composite dose parameter for the total body or critical organ o of an adult for radionuclide i, for the fish and invertebrate ingestion pathways (area /hr'per uCi/ml).
1.14E5 = conversion factor (pci/uci
- ml/kg per hr/yr).
UI = adult invertebrate consumption (5 kg/yr). ,
bis = bioaccumulation factor for radionuclide i in invertebrates from Table 1-3 (pCi/kg per pCi/1).
U2 = adult fish consumption (21 kg/yr).
BFj = bioaccumulation factor for nuclide i in fish from Table 1-4 (pci/kg per pCi/1).
= dose conversion factor for nuclide i for' adults in preselected organ, o, from Table E-11 of Regulatory Guide 1.109 (aren/pci).
The radionuclides included in the periodic dose assessment per the requirements of Technical Specification 3/4.11.1.2 are those as identified by gamma spectral analysis of the liquid waste samples collected and analyzed per the requirements of Technical Specification 3/4.11.1.1, Table 4.11.1.1.1-1.
Radionuclides requiring radiochemical analysis (e.g., Sr-89 and Sr-90) will be added to the dose analysis at a frequency ,
consistent with the required minimum analysis frequency of Technical Specification Table 4.11.1.1.1-1.
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Hope Creek ODCM Rev 14 1
1.4.2 Sinnlified Lisuid Effluent Dose calculation In lieu of the individual radionuclide dose assessment as presented in Section 1.4.1, the following simplified dose l calculation equation may be used for demonstrating compliance with l the dose limits of Technical Specification 3.11.1.2. (Refer to ;
Appendix B for the derivation and justification for this simplified method.)
Total Body 1.94E+02
- VOL D. = ------------------
- E C, (1.7)
CTBD Maximum Oraan 4.28E+02
- VOL D., = ------------------
- EC i (1.8)
CTBD l l
where:
D. = conservatively evaluated total body dose (aram).
D., = evaluated maximum organ dose (area).
C, = average concentration of radionuclide i, in undiluted liquid effluent representative of the volume VOL (uci/ml).
l VOL = volume of liquid effluent released (gal).
t CTBD = average Cooling-Tower Blowdown discharge rate a during release period (gal / min).
i 1.94E+02 = conversion factor (1.67E-2 hr/ min) the ingestion dose i commitment factor (Zn-65, total body -- 2.32E5
- arem/hr per uci/ml), and the near field dilution factor
- of 0.05 (See Appendix B).
j 4.28E+02 = conversion factor (1.67E-2 hr/ min) the conversion 1 maximum organ dose conversion factor (Zn-65, Liver --
i 5.13E5 mram/hr per uCi/ml), and the nearfield dilution j factor of 0.05 (See Appendix B).
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Hope Creek ODCM Rev 14 l
1.5 Limuid Effluent Dose Proiactions Technical Specification 3.11.1.3 requires that the liquid radioactive waste processing, system be used to reduce the radioactive material levels in the liquid waste prior to release
-when the 31-day projected 6oses exceed:
I
- 0.06 mram to the total body, or
- 0.2 mram to any organ.
The applicable liquid waste processing system for maintaining radioactive material releases ALARA are the drain filters and domineralizers as delineated in Figure 1-1.
Dose projections are made at least once per 31-days by the following equations:
D, =
(D. / d)
- 31d (1.9)
D., = (D., / d)
- 31d (1.10) where:
l D, = the total body dose projection for current 31-day i period (aram).
D. = the total body dose to date for current calendar quarter as determined by equation (1.5) or (1.7).
D., = the maximum organ dose to date for current calendar quarter as determined by equation.(1.5 or (1.8) (area)..
d = the number of days in current calendar quarter at the end of the release.
31d = the number of days of concern.
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2.o easmous arrLuxurs
{ 2.1 Radiation Monitoring Instrumentation and Controls t
l The gaseous effluent monitoring instrumentation and controls
- at Hope Creek for controlling and monitoring normal i radioactive material releases in accordance with the ;
- Radiological Effluent Technical Specifications are summarized '
j as follows: l I l
- 1) Filtration. Racirculation, and Ventilation System -
1
! The FRVS is maintained in a standby condition. Upon reactor l building isolation, the FRVS recirculation system recirculates i the reactor building air through HEPA and charcoal filters.
] Releases are made to the atmosphere via a reactor building l j vent or the South Plant Vent depending on mode of operation. 1 j Noble gas monitoring is provided by RE-4811A. l 0
- 2) South Plant Vent -
t j The SPV receives discharge from the radwaste evaporator,
'. reactor building purge, auxiliary building radwaste area, l condensate domineraliser, pipe chase, feedwater heater, and untreated ventilation sources. Effluents are monitored (for noble gas) by the RE-4875B monitor. l
- 3) North Plant Vent -
l The NPV receives discharge from the gaseous radwaste i treatment system (offgas system) and untreated ventilation air
! sources. Effluents are monitored (for noble gases) by the RE-4573B monitor.
I j Gaseous radioactive waste flow diagrams with the applicable, 5 associated radiation monitoring instrumentation controls are .
presented in Figures 2-1 and 2-2.
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i Hope Creek ODCM Rev 14 2.2 Gaseous Effluent Monitor Setpoint Determination 2.2.1 Plant Vent. FRYS Per the requirements of Technical Specification 3.3.7.11, ,
alarm setpoints shall be established for the gaseous l effluent monitoring instrumentation to ensure that the release rate of noble gases does not exceed the limits of Specification 3.11.2.1, which corresponds to a dose rate at the SITE BOUNDARY of 500 mram/ year to the total body or 3000 mrea/ year to the skin. Based on a grab sample analysis of the applicable release (i.e., of FRVS, pipe chase, gaseous radwaste treatment system air, etc. ) , the '
radiation monitoring alarm setpoints may be established by the following calculation method. The measured radionuclide concentrations and release rate are used to calculate the fraction of the allowable release rate, as limited by Specification 3.11.2.1, by the equation:
FRAC = [4.72E+02
- X/Q
- VF * (Ci
- iK)] / 500 (2.1)
FRAC = [4.72E+02
- X/Q
- VF * (Ci* (4 + 1.1M))] i / 3000 (2.2) where:
FRAC = fraction of the allowable release rate based on the identified radionuclide concentrations and the release flow rate. '
X/Q = annual average meteorological dispersion to the controlling site boundary location (sec/m3).
VF = ventilation system flow rate for the applicable ;
release point and monitor (ft3/ min).
Ci = concentration of noble gas radionuclide i as determined by radioanalysis of grab sample (uCi/cm3)
Ki = total body dose conversion factor for noble gas radionuclide 1 (aren/yr per uCi/m3), from Table 2-1 Ig = beta skin dose conversion factor for noble gas ,
radionuclide 1 (arem/yr per uCi/m3), from Table 2-1
% = gamma air dose conversion factor for noble gas radionuclide i (arad/yr per uCi/m3), from Table 2-1 1.1 = mrem skin dose per arad gamma air dose (mram/arad) 4.72E+02 = conversion factor (cm3/ft3
- min /sec) !
500 = total body dose rate limit (aren/yr) :
3000 = skin dose rate limit (mren/yr) !
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Hope Creek ODCM Rev 14 9
+
- Based on the more limiting FRAC (i.e., higher value) as determined i
above, the alarm setpoints for the applicable monitors may be calculated by the equation:
j SP = [AF
- I Ci / FRAC) + bkg (2.3).
i i
4 where:
i
! SP = alarm setpoint corresponding to the maximum i allowable release rate (uci/cc). *
- FRAC = highest fraction of the allowable release rate as j determined in equation (2.2). )
background of the monitor (uci/cc).
{ bkg =
AF = administrative allocation factor for the specific ,
j monitor (0.2 NPV, 0.2 SPV, 0.1 FRVS). l l
The allocation factor (AF) is an administrative control. imposed to.
l ensure than combined releases from Salem Units 1 and 2 and Hope I i
j Creek will not exceed the regulatory limits on release rate from l the site (i.e., the release rate limits of Technical Specification l 3.11. 2.1) . Normally, the combined AF value for Salen Units 1 and 2 is 0.5 (0.25 per unit), with the remainder 0.5 allocated to Hope
)
? Creek. Any increase in AF above 0.5 for the Hope Creek Generating Station will be coordinated with the Salen Generating Station to i ensure that the combined allocation factors for all units do not
} exceed 1.0.
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t Hope Creek ODCM Rev 14 2.2.2 conservative Default Values
)
J A conservative alarm setpoint can be established, in lieu of the individual radionuclide evaluation based on the grab sample analysis, to eliminate the potential of periodically having to adjust the setpoint to reflect minor changes in radionuclide distribution and variations in release flow' rate. The alarm setpoint may be conservatively determined by the default values presented in Table 2-2.
These values are based upon:
- the maximum ventilation (or purge) flow rate;
- a radionuclide distribution adopted from ANSI N237-1976/ANS 18.1 " Source Tara Specifications", Table 5 and;
- an administrative allocation factor of 0.5 to conservatively ensure that any releases from Hope Creek do not exceed the maximum allowable release rate.
For the noble. gas radionuclide distribution from ANSI N237-1976/ANS 18.1 (Note Table C-1), the alarm setpoint based on the total body dose rate is more restrictive than the corresponding setpoint based on the skin dose rate. The resulting conservative, default setpoints are presented in Table 2-2.
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4 j 2.3 Gaseous Effluent Instantaneous Dose Rate Calculations - 10 CFR 20 2.3.1 site Boundary Dose Rate - Moble Gases Technical Specification 3.11.2.la limits the dose rate at the SITE BOUNDARY due to noble gas releases to $ 500 mram/yr, total body and S 3000 mram/yr, skin. Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded. In the event any gaseous releases from the station i
results in an alarm setpoint (as determined in Section 2.2.1) being exceeded, an evaluation of the SITE BOUNDARY dose rate resulting from the release shall be performed using the following equations:
D. = X/Q
- I (Ki
- Qi) (2.4) ,
and D, = X/Q
- I ( (I4 + 1.1%)
- Qi (2.5) where:
D. = Total body dose rate (arem/yr). ,
D, = skin dose rate (arem/yr). )
X/Q = atmospheric dispersion to the controlling SITE I BOUNDARY location (sec/m3).
Qi = average release rate of radionuclide i over the release period under evaluation (uci/sec).
Ki = total body dose conversion factor for noble gas radionuclide i (arem/yr per uci/m3), from Table 2-1 Ig = beta skin dose conversion factor for noble gas radionuclide 1 (mrad /yr per uci/m3), from Table 2-1 Mi = gamma air dose conversion factor for noble gas radionuclide 1 (mrad /yr per uci/m3, from Table 2-1.
1.1 = mrem skin dose per mrad gamma air dose (mrem /arad) 15
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! Hope Creek ODCM Rev 14 i
As appropriate, simultaneous releases from Salem Units 1 and 2 and Hope Creek will be considered in evaluating compliance with the release rate limits of Specification 3.11.2.la, following any releases exceeding the above prescribed alarm setpoints. Monitor indications (readings) may be averaged over a time period not to exceed 15 minutes when determining noble gas release rate based on correlation of the monitor reading and monitor sensitivity. The 15-minute averaging is needed to allow for reasonable monitor response to potentially changing radioactive material concentrations and to exclude potential electronic spikes in monitor readings that may be unrelated.to radioactive material releases. As identified, any electronic spiking monitor responses may be excluded from the analysis.
NOTE: For administrative purposes, more conservative alarm setpoints than those as prescribed above may be imposed. However, conditions exceeding these more limiting alarm setpoints do not necessarily indicate radioactive material release rates exceeding the dose limits of Technical Specification 3.11.2.la. Provided ac' i releases do not result in radiation monitor indications t :eeding alarm setpoint values based on the above criteria, no further analyses are required for demonstrating compliance with the limits of Specification 3.11.2.la.
Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented in ,
Table 2-4 may be used for evaluating the gaseous affluent dose rate. ,
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Hope Creek ODCM Rev 14 4
2.3.2 Site Boundary Dose Rate - Radiciodine and Particulates Technical Specification 3.11.2.lb limits the dose rato to 5 1500 mrem /yr to any organ for I-131, To I-133, tritium and demonstrate part'culates compliance withwith this half-lives greater than 8 days.
limit, an evaluation is performed at a frequency no greater than that corresponding to the sampling and analysis time period (e.g.,
nominally once per 7 days). The following equation shall be used for the dose rate evaluation:
i
' D, = X/Q
- E (Rg
- Qi) (2.6) d #
j where:
D, = average organ dose rate over the sampling time period I
(arem/yr).
X/Q = atmospheric dispersion to the controlling SITE BOUNDARY location for the inhalation pathway (sec/m3).
! Rw = dose parameter for radionuclide 1 (arem/yr per uCi/m3) and organ o for the child inhalation pathway from Table 2-4.
l Qi
= average release rate over the appropriate sampling period and ,
analysis frequency for radionuclide 1 - - I-131, I-133, l tritium or other radionuclide in particulate form with half-life greater than 8 days (uCi/ soc).
By substituting 1500 mrem /yr for D, and solving for Q, an allowable release rate for I-131 can be determined. Based on the annual average meteorological dispersion (See Table 2-3) and the most j
limiting potential pathway, age group and organ (inhalation, child, thyroid -- Ri = 1.62E+07 mrem /yr per uCi/m3), the allowable release i
rate for I-131 is 34.7 uCi/sec. Reducing this release rate by a i
factor of 2 to account for potential dose contributions from other radioactive particulate material and other release points (e.g.,
Salem), the corresponding release rate allocated to Hope Creek is 4
17.4 uCi/sec. For a 7-day period, which is the nominal sampling and i analysis frequency for I-131, the cumulative release is 10.5 Ci.
i Therefore, as lor.g as the I-131 release in any 7-day period do not i exceed 10.5 Ci, no additional analyses are needed for verifying compliance with the Technical Specification 3.11.2.1.b limits on allowable release rate.
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Hope Creek ODCM Rev 14 2.4 Moble Gas Effluent Dose Calculations - 10 CFR 50 2.4.1 UumamTRICTED 19E1 D333 - Moble Games Technical Specification 3.11.2.2 requires a periodic assessment of i releases of noble gases to evaluate compliance with the quarterly dose limits of 5 5 mrad, gamma-air and 5 10 mrad, beta-air and the calendar year limits s 10 mrad, gamma-air and 5 20 mrad, beta-air.
I l
The limits are applicable separately to each generating station and are not combined site limits. The following equations shall be used to calculate the gamma-air and beta-air doses.
D, = 3.17E-08
- X/Q
- I (14
- Qi) (2.7) and D. = 3.17E-08
- X/Q
- I (N3
- Qi) (2.8) where:
D, = air dose due to gamma emissions for noble gas radionuclides (arad).
D. = air dose due to beta emissions for noble gas radionuclides (arad).
X/Q = atmospheric dispersion to the controlling SITE BOUNDARY location (sec/m3).
Qi
= cumulative release ~of noble gas radionuclide i over the period of interest (uci).
= air dose factor due to gamma emission from noble gas radionuclide 1 (arad/yr per uci/m3, from Table 2-1.
N3 = air dose factor due to beta emissions from noble gas radionuclide 1 (arad/yr per uci/m3, Table 2-1).
3.17E-08 = conversion factor (yr/sec).
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Hope Creek ODCM Rev 14 2.4.2 54=nlified Dose Calculation for Moble cases In lieu of the individual noble gas radionuclide dose assessment as presented above, the following simplified dose calculation equations may be used for verifying compliance with the dose limits of Technical Specification 3.11.2.2 (Refer to Appendix C for the derivation and justification of this simplified method).
3.17E-08 D, = ------------
- X/Q
- NLr
- I Qi (2.9) 0.50 and 3.17E-08 D, = ------------
- X/Q
- N,
- I Qi (2.10) 0.50 where:
j Mkr = 8.1E3, effective gamma-air dose factor (mrad /yr per uCi/m3).
, N, = 8.5E3, effective beta-air dose factor (arad/yr per uCi/m3).
Q; = cumulative release for all noble gas radionuclides (uci).
0.50 = conservatism factor to account for potential variability in the radionuclide distribution. ;
I Actual meteorological conditions concurrent with the release period l or the default, annual average dispersion parameters as presented in Table 2-3, may be used for the evaluation of the gamma-air and beta-air doses.
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Hope Creek ODCM Rev 14 2.5 Radiciodine and Particulate Dose Calculations - 10 CFR 5g 2.5.1 UNRESTRICTED AREA Dose - Radiciodine and Particulates In accordance with the requirements of Technical Specification 3.11.2.3, a periodic assessment shall be performed to evaluate compliance with the quarterly dose limit 5 15 mrem to any organ.
The following equation shall be used to evaluate the maximum organ dose due to release of I-131, I-133, tritium and particulates with half-lives greater than 8 days:
D., = 3.17E-08
- W
- S F, *I (%,
- Qi) (2.11) where:
D., = dose or dose commitment via all pathways p and age group a (as identified in Table 2-3) to organ o, including the total body (mrem).
W = atmospheric dispersion parameter to the controlling location (s) as identified in Table 2-3.
X/Q = atmospheric dispersion for inhalation pathway and H-3 dose contribution via other pathways (sec/m3).
D/Q = atmospheric deposition for vegetation, milk and ground plane exposure pathways (1/m2).
R, '= dose factor for radionuclide 1 (mren/yr per 4
uCi/m3 or m2 - aram/yr per uCi/sec) and organ o from Table 2-4 for each age group a and the applicable pathway p as identified in Table 2-3. Values for R 4 were derived in accordance with the methods described in NUREG-0133.
Q, = cumulative release over the period of interest for radionuclide 1 -- I-131, I-133, H-3 or radioactive material in particulate form with half-life greater thar 3 days (uci).
S F, = annual seasonal correction factor to account for the fraction of the year that the applicable exposure pathway does not exist.
- 1) For milk and vegetation exposure pathways:
= A six month fresh vegetation and grazing season (May through October).
= 0.5
- 2) For inhalation and ground plane exposure pathways:
= 1.0 For evaluating the maximum exposed individual, the infant age group is controlling for the milk pathway. Only the controlling age group as identified in Table 2-3 need be evaluated for compliance with Technical Specification 3.11.2.3.
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r Hope Creek ODCM Rev 14 2.5.2 84mnlified Dose Calculation for Radiciodines and Particulates In lieu of the individual radionuclide (I-131, I-133 and particulates) dose assessment as presented above, the following simplified dose calculation equation may be used for verifying compliance with the dose limits of Technical Specification 3.11.2.3 (Refer to Appendix D for the derivation and justification of this g
simplified method).
D= 3.17E-08
- W
- SF,
- RI-131
- EQ i (2.12) l where:
D., = maximur.cigan dose (mrem).
l RI-131 = I-131 aose parameter for the thyroid for the identified controlling pathway.
= 1.05E12, infant thyroid dose parameter with the cow-milk pathway controlling (m2 - mrem /yr per uci/sec).
< W = D/Q for radioiodine, 2.87E-10 1/m2.
Q4 = cumulative release over the period of interest for .
radionuclide i -- I-131 or radioactive material in particulate form with half-life greater than 8 days
- (uci).
The location of exposure pathways and the maximum organ dose calculation may be based on the available pathways in the surrounding environment of Hope Creek as identified by the annual land-use census
< (Technical Specification 3.12.2). Otherwise, the dose will be
]
evaluated based on the predetermined controlling pathways as
- identified in Table 2-3.
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Hope Creek ODCM Rev 14 2.6 Gaseous Effluent Dose Proiection Technical Specification 3.11.2.4 requires that the VENTILATION EXHAUST TREATMENT SYSTEM be used to reduce radioactive material j levels prior to discharge when projected deses in 31-days exceed: )
1
- 0.2 mrad to air from gamma radiation, or j
- 0.4 mrad to air from beta radiation, or l 0.3 mrad to any organ of a MEMBER OF THE PUBLIC i The applicable gaseous processing systems for maintaining radioactive material releases ALARA are the Gaseous Radwaste Treatment System and Exhaust Treatment System as delineated ;
l in Figures 2-1 and 2-2.
Dase projection are performed at least once per 31-days by ,
the following equations. j l
D, = (D, / d)
- 31d (2.17)
D, = (D, / d)
- 31d (2.18) ,
I D., = (D., / d)
- 31d (2.19) j where:
D, = gamma air dose projection for current 31-day period (mrad).
D, = gamma air dose to date for current calendar quarter as determined by equation (2.7) or (2.9)
(mrad).
D, = beta air dose projection for current 31-day period (mrad).
D. = beta air dose to date for current calendar quarter as determined by equation (2.8) or (2.10) (mrad).
D., = maximum organ dose projection for current 31-day period (arem).
D., = maximum organ dose to date for current calendar quarter as determined by equation (2.11) or (2.12)
(arem).
d = number of days in current calendar quarter at the end of the release.
31d = the number of days of concern.
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Hope Creek ODCM Rev 14 3.0 SPECIAL DOSE AMELYSIS i 3.1 Deses n=ne to nativities Inside the SITE BormmmT In accordance with Technical Specification 6.9.1.7, the Radioactive Effluent Release Report (RERR) submitted by May let of each year shall include an assessment of radiation doses from radioactive liquid and
- gaseous affluents to MEMBERS OF THE PUBLIC due to their activities i inside the SITE BOUNDARY.
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The calculation methods as presented in Sections 2.4 and 2.5 may be used j for determining the maximum potential dose to a MEMBER OF THE PUBLIC i
based on the parameters from Table 2-3 and 2-hours per visit per year.
] The default value for the meteorological dispersion data as presented in Table 2-3 may be used if current year meteorology is unavailable at the time of NRC reporting.
However, a follow-up evaluation shall be performed when the data becomes j available.
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- 3.2 Total Dese to aremame or TEE PUBLIC - 40 CFR 190 The Radioactive Effluent Release Report (RERR) submitted by May 1st of each year shall also include an assessment of the radiation dose to the likely most exposed MEMBER OF THE PUBLIC for reactor releases and other nearby uranium fuel cycle courses (including dose contributions from l
j effluents and direct radiation from on-site sources) . For the likely most exposed MEMBER OF THE PUBLIC in the vicinity of Artificial Island, j the sources of exposure need only consider the Salen Generating station i and the Hope Creek Generating Station: No other fuel cycle facilities l contribute to the MEMBER OF THE PUBLIC dose for the Artificial Island i vicinity.
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i The dose contribution from the operation of Salen Generating Stations will be estimated based on tu methods as presented in the Salen Offsite f Dose Calculation Manual (SGS ODCM).
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As appropriate for demonstrating / evaluating compliance with the limits of Technical Specification 3.11.4 (40 CFR 190), the results of the 1 environmental monitoring program may be used for providing data on i
actual measured levels of radioactive material in the actual pathways of exposure.
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Hope Creek ODCN Rev 14 3.2.1 Effl**ent Dome calculations For purposes of implementing the surveillance requirements of Technical ]
Specification 3/4.11.4 and the reporting requirements of 6.9.1.7 (RERR),
dose calculations for the Hope Creek Generating Station may be performed using the calculation methods contained within the ODCN; the conservation controlling pathways and locations of Table 2-4 or the actual pathways and locations as identified by the land use census ,
(Technical Specification 3/4.12.1) may be used. Average annual meteorological dispersion parameters or meteorological conditions concurrent with the release period under evaluation may be used.
3.2.2 Direct Exposure Dose Determina1 ion Any potentially significant direct exposure contribution to off-site +
individual doses may be evaluated based on the results of the environmental measurements (e.g., TLD, ion chamber measurements) and/or by the use of a radiation transport and shielding calculation method.
Only during a non-typical condition will there exist any potential for significant on-site sources at Hope Creek that would yield potentially significant off-site doses (i.e.., in excess of 1 arem per year to a MEMBER OF THE PUBLIC), that would require detailed evaluation for ,
demonstrating compliance with 40 CFR 190. However, should a situation exist whereby the direct exponura contribution is potentially i significant, on-site measurements, off-site measurements and/or calculational techniques will be used for determination of dose for assessing 40 CFR 190 compliance.
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4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 4.1 Sampling Program '
! The operational phase of the Radiological Environmental Monitoring i Program (REMP) is conducted in accordance with the requirements of Appendix A Technical Specification 3.12. The objectives of the program are:
To determine whether any significant increases occur in the
)
concentration of radionuclides in the critical pathways of exposure i in the vicinity of Artificial Island; t
l
- To determine if the operation of the Hope Creek Generating Station i has resulted in any increase in the inventory of long lived ,
t I radionuclides in the environment; I
j - To detect any changes in the ambient gamma radiation levels; and t
I - To verify that HCGS operations have no detrimental effects on the i health and safety of the public or on the environment.
l The sampling requirements (type of samples *, collection frequency and j analysis) and sample locations are presented in Appendix E.
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- NOTE: No public drinking water samples or. irrigation water samples are j taken as these pathways are not directly effected by liquid.
offluonts discharged from Nope Creek Generating Station.
- 4.2 Interlaboratory ca==arison Procram
\ !
j Technical Specification 3.12.3 requires analyses be performed on 1 radioactive material supplied as part of an Interlaboratory Comparison.
Participation in an approved Interlaboratory Comparison Program provides a check on the preciseness of measurements of radioactive materials in
! environmental samples. A summary of the Interlaboratory Comparison Program results will be provided in the Annual Radiological Environmental Operating Report pursuant to Technical Specifications t 6.9.1.7.
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j 25 l
j t_--_.___________ . _ _ _ _ . _._ .- - . - _ _ . - _ _ _
Hnpe Crock ODCM R;v 14 FIGURE 1-1 LIQUID RADWASTE TREATMENT SYSTEM COOLING TOWER BAS':N I i COLLECTOR TANKS (2)
EQUIPMENT EQUIPMENT EQUIPMENT
- DRAIN DRAIN DRAIN SAMPLE FILTER DEMIN TANKS (2)
SURGE TANK CONDENSATE STORAGE TANK FLOOR FLOOR DRAIN FLOOR FLOOR DRAIN l
- COLLECTOR DRAIN DRAIN SAMPLE -
TANKS (2) FILTER DEMIN TANKS (2)
CHEMICAL DECONTAMINATION VAPOR TO WASTE SOLUTION SOUTH PLANT TANK EVAPORATOR VENT BOTTOMS TO SOLID WASTE DETERGENT DETERGENT DRAIN DRAIN TANKS (2) FILTER RE 4861 LOG: RE = EFFLUENT RADIATION MONITOR RE 4861 = LIQUID RADWASTE MONITOR 8817 8817 = COOLING TOWER BLOWDOWN MONITOR TO DELAWARE
,;' RIVER-26 l
Hope Creek ODCM Rev 14 FIGURE 1-2 SOLID RADWASTE PROCESSING SYSTEM W
Ie f
a N
is e
t A
i n 1 8
i II I n a b '
s E a
9 f 5
- I gli 1 E
i
~=
5 5%
is a li I .
i I
I I
3 I .
J I if 3
27
I
' Hope Creek ODCM Rev 14 t
TABLE 1-1
[
PARAMETERS FOR LIQUID ALARM SETPOINT DETERMINATION Actual Default Parameter Value Value Units Comments MPCe Calculated 1.10E-4 uCi/al* Calculated for each batch e to be released i
MPC I-131 3.0E-07 N/A uCi/ml Taken from 10 CFR 20, Appendix B, Table II, Column 2 Measured N/A uCi/ml Taken from gamma spectral C,
analysis of liquid effluent As N/A uCi/ml Taken from 10 CFR 20, MPC, Determined Appendix B, Table II, ,
Column 2 l CTGD As 1.20E4 gpa Cooling tower blowdown Determined discharge RR As 176 gpm or -Determined prior to [
Determined 1300 gym (CST) release; release rate can i be adjusted for Technical Specification compliance ;
SP ]
Calculated 2.81E-03 uC4./ml Default alarm detpoints; A) RE4861 more conservative values >
RE8817 Calculated 4.12E-0!' uCi/ml may be used as deemed appropriate and desirable -
for ensuring regulatory .
compliance and for main- l taining releases ALARA B) RE4861 Calculated 3.81E-04 uCi/ml These setpoints are for condensate storage tank RE8817 Calculated 4.12E-05 uCi/ml releases
- See Appendix A for basis I
i l
l l
28 ,
i
Mcpe Crcck ODCM ROY 14 TABLE 1-2 SITE RELATED INGESTION DOSE COMMITMENT FACTOR, Ag (FISH AND INVERTEBRATE CONSUMPTION)
(aram/hr per uCi/ml)
Liver T. Body Thyroid Kidney Lung GI-LLT .i Nuclide BSDR '
H-3 - 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 C-14 1.45E+4 2.90E+3 2.90E+3 2.90E+3 2.90E+3 2.90E+3 2.90E+3 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 Na-24 4.57E-1 5.27E+5 P-32 4.69E+6 2.91E+5 1.81E+5 - - -
Cr-51 - - 5.58E+0 3.34E+0 1.23E+0 7.40E+0 1.40E+3 i
Mn-54 - 7.06E+3 1.35E+3 - 2.10E+3 -
2.16E+4 1.78E+2 3.15E+1 - 2.26E+2 - 5.67E+3 l Mn-56 -
2.03E+4 Fa-55 5.11E+4 3.53E+4 8.23E+3 - - 1.97E+4 Fa-59 8.06E+4 1.90E+5 7.27E+4 - - 5.30E+4 6.32E+5 Co-57 - 1.42E+2 '2.36E+2 - - - 3.59E+3 Co-58 - 6.03E+2 1.35E+3 - - - 1.22E+4 Co-60 - 1.73E+3 3.82E+3 - - -
3.25E+4 Ni-63 4.96E+4 3.44E+3 1.67E+3 - - -
7.18E+2 Ni-65 2.02E+2 2.62E+1 1.20E+1 - - - 6.65E+2 l Cu-64 - 2.14E+2 1.01E+2 - 5.40E+2 - 1.83E+4 Zn-65 1.61E+5 5.13E+5 2.32E+5 - 3.43E+5 -
3.23E+5 Zn-69 3.43E+2 6.56E+2 4.56E+1 - 4.26E+2 - 9.85E+1
- 4.07E+0 - - - 4.67E+0 Br-82 -
- 7.25E-2 - - - 1.04E-1 !
Br-83 -
Br-84 - - 9.39E-2 - - - 7.37E-7 Br-85 - - 3.86E-3 -
Rb-86 - 6.24E+2 2.91E+2 - - - 1.23E+2 Rb-88 - 1.79E+0 9.49E-1 - - -
2.47E-11 Rb-89 - 1.19E+0 8.34E-1 - - -
6.89E-14 Sr-89 4.99E+3 - 1.43E+2 - - - 8.00E+2 Sr-90 1.23E+5 - 3.01E+4 - - -
3.55E+3
'Sr-91 9.18E+1 -
3.71E+0 - - - 4.37E+2 Sr-92 3.48E+1 - 1.51E+0 - - - 6.90E+2 Y-90 6.06E+0 -
1.63E-1 - - - 6.42E+4 2.22E-3 - - - 1.68E-1 Y-91m 5.73E-2 -
Y-91 8.88E+1 - 2.37E+0 - - - 4.89E+4 Y-92 5.32E-1 -
1.56E-2 - - - 9.32E+3 Y-93 1 69E+0 - 4.66E-2 - - - 5.35E+4 l Zr-95 1.59E+1 5.11E+0 3.46E+0 - 8.02E+0 - 1.62E+4 Zr-97 8.81E-1 1.78E-1 8.13E-2 - 2.68E-1 -
5.51E+4 Nb-95 4.47E+2 2.49E+2 1.34E+2 - 2.46E+2 -
1.51E+6 l 9.49E-1 3.46E-1 - 1.11E+0 - 3.50E+3 l Nb-97 3.75E+0 Mo-99 -
1.28E+2 2.43E+1 - 2.89E+2 - 2.96E+2 l Tc-99m 1.30E-2 3.66E-2 4.66E-1 - 5.56E-1 1.79E-2 2.17E+1 1.33E-2 1.92E-2 1.88E-1 - 3.46E-1 9.81E-3 5.77E-14 Tc-101 4.30E+4 As-76 4.38E+2 1.16E+3 5.14E+3 3.42E+2 1.39E+3 3.58E+2 29 j
H pe Crsck ODCM Rav 14 f
- l. TABLE 1-2 (cont'd)
SITE RELATED INGESTION DOSE COMMITMENT FACTOR, Aw (FISH AND INVERTEBRATE CONSUMPTION) i (aram/hr per uci/al) i 3.gna Liver T. Body Thyroid Kidney Lung GI-r.r.T i
Nuclide 1.25E+4 I Ru-103 1.07E+2 - 4.60E+1 - 4.07E+2 -
3.51E+0 - 1.15E+2 - 5.44E+3 '
I Ru-105 8.89E+0 -
1.03E+5 j Ru-106 1.59E+3 - 2.01E+2 - 3.06E+3 -
t Rh-103m - -
1 Rh-106 - -
1.45E+3 8.60E+2 - 2.85E+3 - 5.91E+5 Ag-110m 1.56E+3 2.15E+2 7.86E+3 i Sb-124 2.77E+2 5.23E+0 1.10E+2 6.71E-1 -
4.21E+1 1.80E-1 - 1.36E+2 1.95E+3 ,
Sb-125 1.77E+2 1.98E+0 8.66E+2 Ta-125m 2.17E+2 7.86E+1 2.91E+1 6.52E+1 8.82E+2 -
l 2.23E+3 1.84E+3 I Ta-127m 5.48E+2 1.96E+2 6.68E+1 1.40E+2 -
3.20E+0 1.93E+0 6.60E+0 3.63E+1 - 7.03E+2 Ta-127 8.90E+0 3.47E+2 1.47E+2 3.20E+2 3.89E+3 - 4.69E+3
. T3-129m 9.31E+2 1.92E+0 T3-129 2.54E+0 9.55E-1 6.19E-1 1.95E+0 1.07E+1 -
5.71E+1 1.08E+2 6.94E+2 - 6.80E+3
) T3-131m 1.40E+2 6.85E+1 2.26E-1 j T3-131 1.59E+0 6.66E-1 5.03E-1 1.31E+0 6.99E+0 -
2.04E+2 1.32E+2 1.24E+2 1.46E+2 1.27E+3 - 6.24E+3 l To-132 1.01E+2
- I-130 3.96E+1 1.17E+2 4.61E+1 9.91E+3 1.82E+2 -
2.18E+2 3.12E+2 1.79E+2 1.02E+5 5.35E+2 - 8.23E+1 l I-131 5.35E+0 I-132 1.06E+1 2.85E+1 9.96E+0 9.96E+2 4.54E+1 -
7.45E+1 1.30E+2 3.95E+1 1.90E+4 2.26E+2 - 1.16E+2 I-133 j I-134 5.56E+0 1.51E+1 5.40E+0 2.62E+2 2.40E+1 - 1.32E-2 '
2.32E+1 6.08E+1 2.24E+1 4.01E+3 9.75E+1 - 6.87E+1 i I-135 2.85E+2 C3-134 6.84E+3 1.63E+4 1.33E+4 - 5.27E+3 1.75E+3 i C3-136 7.16E+2 2.83E+3 2.04E+3 - 1.57E+3 2.16E+2 3.21E+2 ])
1 1.2CE+4 7.85E+3 - 4.07E+3 1.35E+3 2.32E+2 Ca-137 8.77E+3 8.70E-1 5.12E-5 Co-138 6.07E+0 1.20E+1 5.94E+0 ,- 8.81E+0 l 5.23E-3 3.17E-3 1.39E+1 Ba-139 7.85E+0 5.59E-3 2.30E-1 -
l 1.64E+3 1.08E+2 - 7.02E-1 1.18E+0 3.38E+3
]
Bn-140 2.06E+0 1.63E-3 1.80E-9 j B2-141 3.81E+0 2.88E-3 1.29E-1 ~ - 2.68E-3 4
1.50E-3 1.00E-3 2.43E-18 Bn-142 1.72E+0 1.77E-3 1.08E-1 -
5.83E+4 l'
La-140 1.57E+0 7.94E-1 2.10E-1 - - -
8.06E-2 3.67E-2 9.13E-3 - - - 2.68E+2 ,
La-141 8.86E+3 !
Ce-141 3.43EF0 2.32E+0 2.63E-1 - 1.08E+0 -
6.04E-1 4.46E+2 4.94E-2 - 1.97E-1 - 1.67E+4 '
j Ce-143 9.59E+0 - 4.43E+1 - 6.04E+4
) Ce-144 1.79E+2 7.47E+1 2.54E+4 i Pr-143 5.79E+0 2.32E+0 2.87E-1 - 1.34E+0 -
l '
1.90E-2 7.87E-3 9.64E-4 - 4.44E-3 - 2.73E-9 )
Pr-144 Nd-147 3.96E+0 4.58E+0 2.74E-1 - 2.68E+0 -
2.20E+4 l W-187 9.16E+0 7.66E+0 2.68E+0 - -
2.51E+3 l 3.47E-3 1.91E-3 - 1.08E-2 - 7.11E+2 j- Np-239 3.53E-2
- i
- l 30 l
i 4
6 1
i Hope Creek ODCM Rev 14 TABLE 1-3 j
BI0 ACCUMULATION FACTORS l
3 (pci/kg per pCi/ liter)* ~
a ELEMENT SALTWATER FISH SALTWATER INVERTEBRATES J
I H 9.0E-01 9.3E-01
} C 1.8E+03 1.4E+03 i
N3 6.7E-02 1.9E-01
} P 3.0E+03 3.0E+04 j Cr 4.0E+02 2.0E+03 i Mn 5.5E+02 4.0E+02 l Fe 3.0E+03 2.0E+04
- Co 1.0E+02 1.0E+03 I Ni 1.0E+02 2.5E+02 j Cu 6.7E+02 1.7E+03
? Zn 2.0E+03 5.0E+04 l Cr 1.5E-02 3.1E+00 Rb 8.3E+00 1.7E+01 Sr 2.0E+00 2.0E+01 Y 2.5E+01 1.0E+03 Zr 2.0E+02 8.0E+01 Nb 3.0E+04 1.0I472 Mo 1.0E+01 1.0EsJ1 Tc 1.0E+01 5.0E+01 Ru 3.0E+00 1.0E+03 Rh 1.OE+01 2.0E+03 Ag 3.3E+03 3.3E+03 Sb 4.0E+01 5.4E+00 Ta 1.0E+01 1.0E+02 I 1.0E+01 5.0E+01 Cs 4.0E+01 2.5E+01 Ba 1.0E+01 1.0E+02 La 2.5E+01 1.0E+03 Ce 1.0E+01 6.0E+02 Pr 2.5E+01 1.0E+03 Nd 2.5E+01 1.0E+03 W 3.0E+01 3.0E+01 Np 1.0E+01 1.0E+01 es 3.3E+02 3.3E+02 l a values in this table are taken from Regulatory Guide 1.109 except for phosphorus (fish) which is adapted from NUREG/CR-1336 and silver, arsenic and antimony which are taken from UCRL 50564, Rev. 1, October 1972.
31
i Hope Creek ODCM Rev 14 FIGURE 2-1 GASEOUS RADWASTE TREATMENT SYSTEM Main or Auxiliary Steam SJAE F------------ ----1 Offgas I
i Recombiner Preheater Recombiner Condenser l l
Condenser - .l l
Offgas Typical of 2 Recombiner Packages L. --___________-J Holdup Pipes r---------------------7 Cooler Reheater Guard l l
Condenser Bad l I I
I To North l HEPA Filter Absorber -
Plant Vent Train l (Figure 2-2) l Ambient Charcoal System L----________
/ 32
Hope Creek ODCM Rev 14 FIGURE 2-2 VENTILATION EXHAUST TREATMENT SYSTEM RE Gateous Radwaste '
Treatment System 4873B (from Figure 2-1) North Plant Vent Untreated Ventilation Air Sources Radwaste Decon.
Evrporator Recctor Building R H Evrporator (Typ. of 3) RE Auxiliary Building 48758 Radwaste Area R H South V ntilation Area Plant (Typ. of 3) Vent C:ndensate .
Domineralizar Room Air Pipe Chase Air -
R -
H -
C'- H -
Fcedwater Heater Room Air Untreated Ventilation Air Sources RE (Recirculation) 4811A R:cctor ;
Cuilding A:r H C H C H FRVS System (Typ. of 6) (Typ. of 2) Vent Leg:nd: R= Roughing Filter C= Charcoal Filter H= HEPA Filter RE = Effluent Radiation Monitor 33
4 I
4 Hope Creek ODCM Rev 14 i
TABLE 2-1 DOSE FACTORS FOR NOBLE GASES 1
\
Tot;l Body Skin Gamma Air Beta Air Dose Factor Dose Factor Dose Factor Dose Factor Ki Li Mi Ni (arem/yr per (arem/yr per (arad/yr per (arad/yr per Radionuclide uCi/m3) uCi/m3) uCi/m3) uCi/m3 d
Kr-83m 7.56E-02 -
1.93E+01 2.88E+02 l Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 I Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 I Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 i '
Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 4 Xe-133 2.94E+02 3.06E+02 3.53E+02' 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 )
Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 1
j
- 34 i
l Hope Creek ODCM Rev 14 i
TABLE 2-2 PARAMETERS FOR GASEOUS ALARM SETPOINT DETERMINATION HOPE CREEK i Actual Default j Parameter Value Value Units Comments X/Q Calculated 2.67E-6 sec/m3 From FSAR Table 2.3-31 0.5 mile, N VF (NPV) Measured 41900 ft'/ min Maximum Operation -
l VF (SPV) Measured 440,180 ft'/ min Maximum Operation VF (FRVS) Measured 9000 ft / min 3
Maximum Operation
- AF (NPV) Coordinated 0.2 Unitiess Administrative with SGS allocation factor to ensure releases ,
AF (SPV) 0.2 Unitless do not exceed release l rate limit
) AF (FRVS) 0.1 Unitiess j l Ci Measured N/A uci/cm3 Ki Nuclide N/A arem/yr Table 2-1 Specific per uCi/m' I, Nuclide N/A mram/yr Table 2-1 Specific per uci/m S) l Mi Nuclide N/A arad/yr Table 2-1 Specific per uCi/m8 SP: NPV Calculated 2.43E-4 uCi/cc Default alarm SPV Calculated 2.31E-5 uCi/cc Setpoints; more FRVS Calculated 5.65E-4 uCi/cc conservative values may be used as deemed appropriate for ensuring ALARA & i regulatorycompliance 35
Hope Creek ODCM Rev 14 TABLE 2-3 CONTROLLING LOCATIONS, PATHWAYS AND ATMOSPHERIC DISPERSION FOR DOSE CALCULATIONS
- Controlling X/Q D/Q Tech Spec Location Pathway (s) Ace Group (sec/m3) (1/m2) 3.11.2.la Site Boundary Noble Gases N/A 2.67E-06 N/A O.5 Mile, N direct exposure 3.11.2.lb Site Boundary Inhalation Child 2.67E-06 N/A O.5 Mile, N 3.11.2.2 Site Boundary Gamma-Air N/A 2.67E-06 N/A 0.5 Mile, N Esta-Air 3.11.2.3 Residence / Milk, ground Infant 7.2E-08 2.87E-10 Dairy - 4.9 plane and Miles, W inhalation e The identified controlling locations, pathways and atmospheric dispersion are from the Artificial Island Radiological Monitoring Program and the Hope Creek FSAR.
36
a 4
Hope Creek ODCM Rev 14 Table 2-4 Pathway Dose Factors - htmospheric Releases R(io), Inhalation Pathway Dose Factors - ADULT (mrem /yr per uci/m3) j Thyroid Kidney Lung GI-LLI T. Body Nuclide EMD3 Liver 1.26E+3 H-3 - 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 i
C-14 1.82E+4 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 j P-32 1.32E+6 7.71E+4 - - - 8.64E+4 5.01E+4
! Cr-51 - - 5.95E+1 2.28E+1 1.44E+4 3.32E+3 1.OOE+2 i Mn-54 - 3.96E+4 -
9.84E+3 1.40E+6 7.74E+4 6.30E+3
- Fc-55 2.46E+4 1.70E+4 - - 7.21E+4 6.03E+3 3.94E+3 FG-59 1.18E+4 2.78E+4 - -
1.02E+6 1.88E+5 1.06E+4 Co-57 - 6.92E+2 - - 3.70E+5 3.14E+4 6.71E+2 Co-58 - 1.58E+3 - -
9.28E+5 1.06E+5 2.07E+3 ,
Co-60 - 1.15E+4 - -
5.97E+6 2.85E+5 1.48E+4 l Ni-63 4.32E+5 3.14E+4 - -
1.78E+5 1.34E+4 1.45E+4 Zn-65 3.24E+4 1.03E+5 - 6.90E+4 8.64E+5 5.34E+4 4.66E+4 Rb-86 - 1.35E+5 - - - 1.66E+4 5.90E+4 Sr-89 3.04E+5 - - - 1.40E+6 3.50E+5 8.72E+3
- Sr-90 9.92E+7 - - - 9.60E+6 ,7.22E+5 6.10E+6 Y-91 4.62E+5 - - - 1.70E+6 3.85E+5 1.24E+4 1
Zr-95 1.07E+5 3.44E+4 - 5.42E+4 1.77E+6 1.50E+5 2.33E+4 4
1 Nb-95 1.41E+4 7.82E+3 - 7.74E+3 5.05E+5 1.04E+5 4.21E+3 Ru-103 1.53E+3 - - 5.83E+3 5.05E+5 1.10E+5 6.58E+2 l Ru-106 6.91E+4 - - 1.34E+5 9.36E+6 9.12E+5 8.72E+3 l
' Ag-110m 1.08E+4 1.OOE+4 -
1.97E+4 4.63E+6 3.02E+5 5.94E+3 )
Sb-124 3.12E+4 5.89E+2 7.55E+1 - 2.48E+6 4.06E+5 1.24E+4
, Sb-125 5.34E+4 5.95E+2 5.40E+1 - 1.74E+6 1.01E+5 1.26E+4 Ta-125m 3.42E+3 1.58E+3 1.05E+3 1.24E+4 3.14E+5 7.06E+4 4.67E+2 To-127m 1.26E+4 5.77E+3 3.29E+3 4.58E+4 9.60E+5 1.50E+5 1.57E+3 1.58E+3 I
TG-129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 1.16E+6 3.83E+5 I-131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 - 6.28E+3 2.05E+4
- Cc-134 3.73E+5 8.48E+5 - 2.87E+5 9.76E+4 1.04E+4 7.28E+5 Cs-136 3.90E+4 1.46E+5 -
8.56E+4 1.2OE+4 1.17E+4 1.10E+5 i
C3-137 4.78E+5 6.21E+5 -
2.22E+5 7.52E+4 8.40E+3 4.28E+5 j B2-140 3.90E+4 4.90E+1 - 1.67E+1 1.27E+6 2.18E+5 2.57E+3 C3-141 1.99E+4 1.35E+4 - 6.26E+3 3.62E+5 1.20E+5 1.53E+3 Cs-144 3.43E+6 1.43E+6 -
8.48E+5 7.78E+6 8.16E+5 1.84E+5 Pr-143 9.36E+3 3.75E+3 -
2.16E+3 2.81E+5 2.OOE+5 4.64E+2 Nd-147 5.27E+3 6.10E+3 - 3.56E+3 2.21E+5 1.73E+5 3.65E+2 37 i
I i
j
Hope Creek ODCN Rev 14 Table 2-4 (cont'd)
Pathway Dose Factors - Atmospheric Releases-R(io), Inhalation Pathway Dose Factors - TEENAGER (ares /yr per uCi/m3)
Thyroid Kidney Lung GI-LLT T. Body :
Nuclide BQDa Liver 1.27E+3 1.27E+3 H-3 - 1.27E+3 1.27E+3 1.27E+3 1.27E+3 2.60E+4 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 C-14 7.16E+4 P-32 1.89E+6 1.10E+5 - - - 9.28E+4 ,
Cr-51 - -
7.50E+1- 3.07E+1 2.10E+4- 3.OOE+3 1.35E+2 Mn-54 - 5.11E+4 - 1.27E+4 1.98E+6 6.68E+4 8.40E+3 i
FG-55 3.34E+4' 2.38E+4 - - 1.24E+5 6.39E+3 5.54E+3 Fo-59 1.59E+4 3.70E+4 - - 1.53E'S 1.78E+5 1.43E+4 Co-57 - 6.92E+2 - - 5.86E+5 3.14E+4. 9.20E+2 Co-58 -
2.07E+3 - - 1.34E+6 9.52E+4 2.78E+3' Co-60 -
1.51E+4 - - 8.72E+6 2.59E+5 1.98E+4 Ni-63 5.80E+5 4.34E+4 - - 3.07E+5 1.42E+4 1.98E+4 i Zn-65 3.86E+4 1.34E+5 - 8.64E+4 1.24E+6 4.66E+4 6.24E+4 Rb-86 - 1.90E+5 - - - 1.77E+4 8.40E+4 Sr-89 4.34E+5 - - - 2.42E+6 3.71E+5 1.25E+4 3 Sr-90 1.08E+8 - - - 1. 6 5E+7- 7.65E+5 6.68E+6 l Y-91 6.61E+5 - - - 2.94E+6 4.09E+5 1.77E+4i Zr-95 1.46E+5 4.58E+4 - 6.74E+4 2.69E+6 1.49E+5 3.15E+4 l Nb-95 1.86E+4 1.03E+4 - 1.OOE+4 7.51E+5 9.68E+4 5.66E+3 i Ru-103 2.10E+3 - - 7.43E+3 7.83E+5 1.09E+5 8.96E+2 I Ru-106 9.84E+4 - - 1.90E+5 1.61E+7 9.60E+5 1.24E+4 '
Ag-110m 1.38E+4 1.31E+4 - 2.50E+4 6.75E+6 2.73E+5 7.99E+3 Sb-124 4.30E+4 7.94E+2 9.76E+1 -
3.85E+6 3.98E+5 1.68E+4 Sb-125 7.38E+4 8.08E+2 7.04E+1 - 2.74E+6 9.92E+4 1.72E+4 Te-125m 4.88E+3 2.24E+3 1.40E+3 - 5.36E+5 7.50E+4 6.67E+2 Te-127m 1.80E+4 8.16E+3 4.38E+3 6.54E+4 1.66E+6 1.59E+5 2.18E+3' Te-129m 1.39E+4 6.58E+3 4.58E+3 5.19E+4 1.98E+6 4 . 05E+5 - 2.25E+3 I-131 3.54E+4 4.91E+4 1.46E+7 8.40E+4 - 6.49E+3 2.64E+4 Cs-134 5.02E+5 1.13E+6 - 3.75E+5 1.46E+5 9.76E+3 5.49E+5 !
Cs-136 5.15E+4 1.94E+5 - 1.10E+5 1.78E+4 1.09E+4 1.37E+5 Cs-137 6.70E+5 8.48E+5 - 2.04E+5 1.21E+5 8.48E+3 3.11E+5f Ba-140 5.47E+4 6.70E+1 - 2.28E+1 2.03E+6 2.29E+5 3.52E+3l Ce-141 2.84E+4 1.90E+4 - 8.88E+3- 6.14E+5 1.26E+5 2.17E+3, i
Ce-144 4.89E+6 2.02E+6 - 1.21E+6 1.34E+7 8.64E+5 2.62E+5{
Pr-143 1.34E+4 5.31E+3 - 3.09E+3- 4.83E+5 2.14E+5 6.62E+2 t
,/ Nd-147 7.86E+3 8.56E+3 - 5.02E+3 3.72E+5 1.82E+5 5.13E+2' 38 f T
I i
i i
a i
i
' Hope Creek ODCN Rev 14 i
- Table 2-4 (cont'd) j Pathway Dose Factors - Atmospheric Releases
~
R(io), Inhalation Pathway Dose Factors - CHILD 4
(aren/yr per uCi/m3)
! Muclide Bong Liver Thyroid Kidney Lung GI-LLI T. Body l H-3 - 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 ;
1 C-14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 P-32 2.60E+6 1.14E&5 - - -
4.22E+4 9.88E+4 l i cr-51 - - 8.55E+1 2.43E+1 1.70E+4 1.08E+3 1.54E+2 -
l; Mn-54 -
4.29E+4 -
1.OOE+4 1.58E+6 2.29E+4 9.51E+3 FO-55 4.74E+4 2.52E+4 - -
1.11E+5 2.87E+3 7.77E+3 l
! Fo-59 -2.07E+4 3.34E+4 - - 1.27E+6 7.07E+4 1.67E+4 '
l Cc-57 -
9.03E+2 - -
5.07E+5 1.32E+4 1.07E+3 ]
1 i Cs-58 -
1.77E+3 - -
1.11E+6 3.44E+4 3.16E+3
? CD-63 -
1.31E+4 - -
7.97E+6 9.62E+4 2.26E+4 1
! Ni-63 8.21E+5 4.63E+4 - -
2.75E+5 6.33E+3 2.80E+4 i En-65 4.26E+4 1.13E+5 -
7.14E+4 9.95E+5 1.63E+4 7.03E+4 1
- db-86 - 1.98E+5 - - -
.7.9PE+3 1.14E+5
- Cr-89 5.99E+5 - - -
2.16E+6 1.67E+5 1.72E+4
) Cr-90 1.01E+8 - - -
1.48E+7 3.43E+5 6.44E+6
- Y-91 9.14E+5 - - -
2.63E+6 1.84E+5 2.44E+4 Er-95 1.90E+5 4.18E+4 -
5.96E+4 2.23E+6 6.11E+4 3.70E+4 Nb-95 2.35E+4 9.18E+3 -
8.62E+3 6.14E+5 3.70E+4 6.55E+3 Ru-103 2.79E+3 - -
7.03E+3 6.62E+5 4.48E+4 1.07E+3 Ru-106 1.36E+5 - -
1.84E+5 1.43E+7 4.29E+5 1.69E+4 Ag-110m 1.69E+4 1.14E+4 -
2.12E+4 5.48E+6 1.OOE+5 9.14E+3 Sb-124 5.74E+4 7.40E+2 1.26E+2 -
3.24E+6 1.64E+5 2.OOE+4 Sb-125 9.84E+4 7.59E+2 9.10E+1 -
2.32E+6 4.03E+4 2.07E+4 i To-125m 6.73E+3 2.33E+3 1.92E+3 - 4.77E+5 3.38E+4 9'.14 E+2 T3-127m 2.49E+4 8.55E+3 6.07E+3 6.36E+4 1.48E+6 7.14E+4 3.02E+3 To-129m 1.92E+4 6.85E+3 6.33E+3 5.03E+4 1.76E+6 1.82E+5 3.04E+3 I I-131 4.81E+4 4.81E+4 1.62E+7 7.88E+4 - 2.84E+3 2.73E+4 C3-134 6.51E+5 1.01E+6 - 3.3OE+5 1.21E+5 3.85E+3 2.25E+5 Co-136 6.51E+4 1.71E+5 -
9.55E+4 1.45E+4 4.18E+3 1.16E+5 C3-137 9.07E+5 8.25E+5 -
2.82E+5 1.04E+5 3.62E+3 1.28E+5 Ba-140 7.40E+4 6.48E+1 -
2.11E+1 1.74E+6 1.02E+5 4.33E+3 C3-141 3.92E+4 1.95E+4 -
8.55E+3 5.44E+5 5.66E+4 2.90E+3
,o-144 6.77E+6 2.12E+6 -
1.17E+6 1.20E+7 3.89E+5 3.61E+5 Pr-143 1.85E+4 5.55E+3 - 3.OOE+3 4.33E+5 9.73E+4 9.14E+2 Nd-147 1.08E+4 8.73E+3 -
4.81E+3 3.28E+5 8.21E+4 6.81E+2 39
Hope Creek ODCM Rev 14 Table 2-4 (cont'd)
Pathway Dose Factors - Atmospheric Releases R(io), Inhalation Pathway Dose Factors - INFANT (aren/yr per uC3/m3)
Nuclide Bone Liver Thyroid Kidney Lung GI-TTT T. Body I H-3 -
6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 ,
C-14 2.65E+4 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 ,
P-32 2.03E+6 1.12E+5 - - -
1.61E+4 7.74E+4 Cr-51 - -
5.75E+1 1.32E+1 1.28E+4 3.57E+2 8.95E+1 ,
Mn-54 -
2.53E+4 -
4.98E+3 1.OOE+6 7.06E+3 4.98E+3 FO-55 1.97E+4 1.17E+4 - -
8.69E+4 1.09E+3 .3.33E+3 FO-59 1.36E+4 2.35E+4 - - 1.02E+6 2.48E+4 9.48E+3 Co-57 -
6.51E+2 - - 3.79E+5 4.86E+3 6.41E+2 Co-58 -
1.22E+3 - - 7.77E+5 1.11E+4 1.82E+3 Co-60 -
8.02E+3 - -
4.51E+6 3.19E+4 1.18E+4 ,
Ni-63 3.39E+5 2.04E+4 - -
2.09E+5 2.42E+3 1.16E+4 '
Zn-65 1.93E+4 6.26E+4 -
3.25E+4 6.47E+5 5.14E+4 3.11E+4 Rb-86 -
1.90E+5 - - - 3.04E+3 8.82E+4 ,
Sr-89 3.98E+5 - - -
2.03E+6 6.40E+4 1.14E+4 Sr-90 4.09E+7 - - -
1.12E+7 1.31E+5 2.59E+6 -
Y-91 5.88E+5 - - -
2.45E+6 7.03E+4 1.57E+4 Zr-95 1.15E+5 2.79E+4 -
3.11E+4 1.75E+6 2 17E+4 2.03E+4 Nb-95 1.57E+4 6.43E+3 -
4.72E+3 4.79E+5 1.27E+4 3.78E+3 Ru-103 2.02E+3 - -
4.24E+3 5.52E+5 1.61E+4 6.79E+2 Ru-106 8.68E+4 - -
1.07E+5 1.16E+7 1.64E+5 1.09E+4 Ag-110m 9.98E+3 7.22E+3 -
1.09E+4 3.67E+6 3.3OE+4 5.OOE+3 Sb-124 3.79E+4 5.56E+2 1.01E+2 -
2.65E+6 5.91E+4 1.20E+4 .
Sb-125 5.17E+4 4.77E+2 6.23E+1 -
1.64E+6 1.47E+4 1.09E+4 T3-125m 4.76E+3 1.99E+3 1.62E+3 -
4.47E+5 1.29E+4 6.58E+2 To-127m 1.67E+4 6.90E+3 4.87E+3 3.75E+4 1.31E+6 2.73E+4 2.07E+3 '
Ta-129m 1.41E+4 6.09E+3 5.47E+3 3.18E+4 1.68E+6 6.90E+4 2.23E+3 I-131 3.79E+4 4.44E+4 1.48E+7 5.18E+4 -
1.06E+3 1.96E+4 C3-134 3.96E+5 7.03E+5 -
1.90E+5 7.97E+4 1.33E+3 7.4CE+4 )
i Cc-136 4.83E+4 1.35E+5 -
5.64E+4 1.18E+4 1.43E+3 5.29E+4 I Co-137 5.49E+5 6.12E+5 -
1.72E+5 7.13E+4 1.33E+3 4.55E+4 Ba-140 5.60E+4 5.60E+1 -
1.34E+1 1.60E+6 3.84E+4 2.90E+3 Ca-141 2.77E+4 1.67E+4 -
5.25E+3 5.17E+5 2.16E+4 1.99E+3 ,
l CS-144 3.19E+6 1.21E+6 -
5.38E+5 9.84E+6 1.48E+5 1.76E+5 l Pr-143 1.40E+4 5.24E+3 -
1.97E+3 4.33E+5 3.72E+4 6.99E+2
- - Nd-147 7.94E+3 8.13E+3 -
3.15E+3 3.22E+5 3.12E+4 5.OOE+2 40
Hope Creek ODCN Rev 14 Table 2-4 (cont'd)
Pathway Dose Factors - Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors - ADULT (ares /yr per uCi/m3) for H-3 and C-14 (m2
- aren/yr per uCi/sec) for others Kidney Idmg GI-LLI T. Body Muclide B9BR LiY.gg Thyroid H-3 - 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 C-14 3.63E+5 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 P-32 1.71E+10 1.06E+9 - - - 1.92E+9 6.60E+8 Cr-51 - - 1.71E+4 6.30E+3 3.80E+4 7.20E+6 2.86Ef4 Mn-54 - 8.40E+6 - 2.50E+6 - 2.57E+7 1.60E+6 FG-55 2.51E+7 1.73E+7 - - 9.67E+6 9.95E+6 4.04E+6 2.98E+7 7.OOE+7 - - 1.95E+7 2.33E+8 2.68E+7-FO-59 Co-57 - 1.28E+6 - - - 3.25E+7 2.13E+6 Cs-58 - 4.72E+6 - - - 9.57E+7 1.06E+7 C2-60 - 1.64E+7 - - - 3.08E+8 3.62E+7 Ni-63 6.73E+9 4.66E+8 - - - 9.73E+7 2.26E+8 1.37E+9 4.36E+9 - 2.92E+9 - 2.75E+9 1.97E+9
.Zn-65 Ab-86 - 2.59E+9 - - - 5.11E+8 1.21E+9 Sr-89 1.4 5E+9 - - - - 2.33E+8 4.16E+7l Sr-90 4.68E+10 - - - - 1.35E+9 1.15E+10 l Y-91 8.60E+3 - - - - 4.73E+6 2.30E+2 Er-95 9.46E+2 3.03E+2 - 4.76E+2 - 9.62E+5 2.05E+2 Nb-95 8.25E+4 4.59E+4 - 4.54E+4 - 2.79E+8 2.47E+4 i
Ru-103 1.02E+3 - - 3.89E+3 - 1.19E+5 4.39E+2
) 3.94E+4 - 1.32E+6 2.58E+3 l Ru-106 2.04E+4 - -
1 Ag-110m 5.83E+7 5.39E+7 - 1.06E+8 - 2.20E+10 3.20E+7
! 1.02E+7 Sb-124 2.57E+7 4.86E+5 6.24E+4 -
2.00E+7 7.31E+8 Cb-125 2.04E+7 2.28E+5 2.08E+4 - 1.58E+7 2.25E+8 4.86E+6
. T3-125m 1.63E+7 5.90E+6 4.90E+6 6.63E+7 -
6.50E+7 2.18E+6
- 5.58E+6 i TG-127m 4.58E+7 1.64E+7 1.17E+7 1.86E+8 - 1.54E+8 2
To-129m 6.04E+7 2.25E+7 2.08E+7 2.52E+8 - 3.04E+8 9.57E+6 I-131 2.96E+8 4.24E+8 1.39E+11 7.27E+8 - 1.12E+8 2.43E+8 C3-134 5.65E+9 1.34E+10 - 4.35E+9 1.44E+9 2.35E+8 1.10E+10 C3-136 2.61E+8 1.03E+9 - 5.74m+8 7.87E+7 1.17E+8 7.42E+8 C3-137 7.38E+9 1.01E+10 - 3.43E+9 1.14E+9 1.95E+8 6.61E+9 Ba-140 2.69E+7 3.38E+4 - 1.15E+4 1.93E+4 5.54E+7 1.76E+6 C3-141 4.84E+3 3.27E+3 - 1.52E+3 -
1.25E+7 3.71E+2 Jc-144 3.58E+5 1.50E+5 - 8.87E+4 - 1.21E+8 1.92E+4 Pr-143 1.59E+2 6.37E+1 - 3.68E+1 - 6.96E+5 7.88E+0 Nd-147 9.42E+1 1.09E+2 - 6.37E+1 - 5.23E+5 6.52E+0 41
i I
Hope Creek ODCM Rev 14 Table C-4 (cont'd) l Pathway Dose Factors - Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors - TEENAGER ,
l (ares /yr per uCi/m3) for H-3 and C-14 (m2
- ares /yr per uC1/sec) for others j Thyroid Kidney LMDg GI-LLI T. Body ;
Muclide 3g33 Liver 9.94E+2 9.94E+2 9.94E+2 9.94E+2 H-3 - 9.94E+2 9.94E+2
- 6. "* '5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 ;
C-14 - - 2.65E+9 1.22E+9 i P-32 3.15E+10 1.95E+9 -
5.OOE+4 i Cr-51 - - -2.78E+4 1.10E+4 7.13E+4 8.40E+6 1.40E+7 - 4.17E+6 - 2.87E+7 2.78E+6 :
Mn-54 -
2.OOE+7 1.37E+7 7.36E+6 F3-55 4.45E+7 3.16E+7 - -
4.68E+7 5.20E+7 1.21E+8 - - 3.82E+7 2.87E+8 Fo-59 - 4.19E+7 3.76E+6 C3-57 - 2.25E+6 - -
1.83E+7 C3-58 - 7.95E+6 - - - 1.10E+8 2.78E+7 - - - 3.62E+8 6.26E+7 -
C3-60 1.18E+10 8.35E+8 - - 1.33E+8 4.01E+8 Ni-63 1
2.11E+9 7.31E+9 4.68E+9 - 3.10E+9 3.41E+9 En-65 -
4.73E+9 - - - 7.OOE+8 2.22E+9 Rb-86 -
- 3.18E+8 7.66E+7 i Sr-89 2.67E+9 - - -
6.10E+6-Sr-90 9.92E+7 - - 9.60E+6 7.22E+5 '
4.24E+2 Y-91 1.58E+4 - - - - 6.48E+6 1.65E+3 5.22E+2 - 7.67E+2 - 1.20E+6 3.59E+2 l Zr-95 Nb-95 1.41E+5 7.80E+4 - 7.57E+4 - 3.34E+8 4.30E+4 -
4 Ru-103 1.81E+3 - - 6.40E+3 - 1.52E+5 7.75E+2 l 7.23E+4 - 1.80E+6 4.73E+3 j Ru-106 3.75E+4 - -
Ag-110m 9.63E+7 9.11E+7 - 1.74E+8 - 2.56E+10 5.54E+7*
l Sb-124 4.59E+7 8.46E+5 1.04E+5 - 4.01E+7 9.25E+8 1.79E+7l Sb-125 3.65E+7 3.99E+5 3.49E+4 - 3.21E+7 2.84E+8 8.54E+6i Tc-125m 3.OOE+7 1.08E+7 8.39E+6 - - 8.86E+7 4.02E+0 I 3.42E+8 2.10E+8 1.OOE+7, 2.99E+7 2.01E+7
- To-127m 8.44E+7 1.75E+7l To-129m 1.11E+8 4.10E+7 3.57E+7 4.62E+8 - 4.15E+8 5.38E+8 7.53E+8 2.20E+11 1.30E+9 - 1.49E+8 4.04E+8l I-131 1.07E+1d Cs-134 9.81E+9 2.31E+10 - 7.34E+9 2.80E+9 2.87E+8 1.75E+9 9.53E+8 1.50E+8 1. 41E+8 1.18E+9 Cs-136 4.45E+8 -
1.34E+10 1.78E+10 - 6.06E+9 2.35E+9 2.53E+8 6.20E+9 Cs-137 7.49E+7 3.13E+6 4
Ba-140 4.85E+7 5.95E+4 - 2.02E+4 4.OOE+4 1.35E+4 - 2.79E+3 - 1.69E+7 6.81E+2
- Ce-141 8.87E+3 6.58E+5 2.72E+5 - 1.63E+5 - 1.66E+8 3.54E+4; Co-144 9.61E+5 1.45E+1 Pr-143 2.92E+2 1.17E+2 - 6.77E+1 -
1.81E+2 1.97E+2 - 1.16E+2 - 7.11E+5 1.18E+1f i Nd-147 42 l
Hope Creek ODCN Rev 14
. Table 2-4 (cont'd)
Pathway Dose Factors.- Atmospheric Releases R(io) , Grass-Cow-Milk Pathway Dose Factors - CHILD (area /yr per uCi/m3) for H-3 and.C-14 (m2
- aram/yr per uCi/sec) for others Thyroid Kidney Lung GI-LLI T. Body Nuclide gang Liver H-3 -
1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 C-14 1.65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 .l P-32 7.77E+10 3.64E+9 - - - 2.15E+9 3.OOE+9 Cr-51 - -
5.66E+4 1.55E+4 1.03E+5 5.41E+6 1.02E+5 Mn-54 - 2.09E+7 - 5.87E+6 - 1.76E+7 5.58E+6 FG-55 1.12E+8 5.93E+7' - - 3.35E+7 1.10E+7 1.84E+7 FG-52 1.20E+8 1.95E+8 - - 5.65E+7 2.03E+8 9.71E+7 Co-57 -
3.84E+6 - - - 3.14E+7 7.77E+6 Co-58 -
1.21E+7 - - -
7.08E+7 3.72E+7 Co-60 -
4.32E+7 -
2.39E+8 1.27E+8 Ni-63 2.96E+10 1.59E+9 - - - 1.07E+8 1.01E+9 Zn-65 4.13E+9 1.10E+10 - 6.94E+9 -
1.93E+9 6.85E+9 Rb-86 -
8.77E+9 - - -
5.64E+8 5.39E+9 Sr-89 6.62E+9 - - - - 2.56E+8 1.89E+8 Sr-90 1.12E+11 - - - -
1.51E+9 2.83E+10 Y-91 3.91E+4 - - - - 5.21E+6 1.04E+3 Zr-95 3.84E+3 8.45E+2 -
1.21E+3 - 8.81E+5 7.52E+2 Nb-95 3.18E+5 1.24E+5 - 1.16E+5 -
2.29E+8 8.84E+4 Ru-103 4.29E+3 - -
1.08E+4 -
1.11E+5 1.65E+3 Ru-106 9.24E+4 - - 1.25E+5 - 1.44E+6 1.15E+4 Ag-110m 2.09E+8 1.41E+8 -
2.63E+8 -
1.68E+10 1.13E+8 Sb-124 1.09E+8 1.41E+8 2.40E+5 -
6.03E+7 6.79E+8 3.81E+7 Sb-125 8.70E+7 1.41E+6 8.06E+4 -
4.85E+7 2.08E+8 1.82E+7 Te-125m 7.38E+7 2.OOE+7 2.07E+7 - -
7.12E+7 9.84E+6 To-127m 2.08E+8 5.60E+7 4.97E+7 5.93E+8 -
1.68E+8 2.47E+7 T3-129m 2.72E+8 7.61E+7 8.78E+7 8.OOE+8 - 3.32E+8 4.23E+7 1 I-131 1.3OE+9 1.31E+9 4.34E+11 2.15E+9 -
1.17E+8 7.46E+8 l Co-134 2.26E+10 3.71E+10 - 1.15E+10 4.13E+9 2.OOE+8 7.83E+9 C0-136 1.OOE+9 2.76E+9 -
1.47E+9 2.19E+8 9.70E+7 1.79E+9 Cc-137 3.22E+10 3.09E+10 - 1.01E+10 3.62E+9 1.93E+8 4.55E+9 B2-140 1.17E+8 1.03E+5 -
3.34E+4 6.12E+4 5.94E+7 6.84E+6 C3-141 2.19E+4 1.09E+4 -
4.78E+3 -
1.36E+7 1.62E+3 1.33E+8 C3-144 1.62E+6 5.09E+5 -
2.82E+5 - 8.66E+4 Pr-143 7.23E+2 2.17E+2 -
1.17E+2 -
7.80E+5 3.59E+1 Nd-147 4.45E+2 3.60E+2 -
1.98E+2 -
5.71E+5 2.79E+1 43
i 1
e 25 4
Hope Creek ODCM Rev 14 i
! Table 2-4 (cont'd) i Pathway Dose Factors - Atmospheric Releases l R(io), Grass-Cow-Milk-Pathway Dose Factors - INFANT ,
(aren/yr per uCi/m3) for H-3 and C-14 (m2
- aren/yr per uCi/sec) for others Nuclide RQng Liver Thyroid Kidney LEDg cI.T.r T T. Body }
f 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 i H-3 -
C-14 3.23E+6 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 :
i
! P-32 1.60E+11 9.42E+9 - - - 2.17E+9 6.21E+9 Cr-51 - -
1.05E+5 2.30E+4 2.05E+5 4.71E+6 1.61E+5 i
1 Mn-54 - 3.89E+7 - 8.63E+6 - 1.43E+7 8.83E+6 l
FG-55 1.35E+8 8.72E+7 - - 4.27E+7 1.11E+7 2.33E+7 i FG-59 2.25E+8 3.93E+8 - - 1.16E+8 1.88E+8 1.55E+8
- Co-57 -
8.95E+6 - - - 3.05E+7 1.46E+7 ;
i ;
C3-58 - 2.43E+7 - - - 6.05E+7 6.06E+7 )
! 2.10E+8 2.08E+8 t Co-60 -
8.81E+7 - - -
i i Ni-63 3.49E+10 2.16E+9 - - - 1.07E+8 1.21E+9
! Zn~65 5.55E+9 1.90E+10 - 9.23E+9 - 1.61E+10 8.78E+9 '
Rb-86 - 2.22E+10 - - -
'5.69E+8 1.10E+10 l 2.59E+8 3.61E+8 4
Sr-89 1.26E+10 - - - -
+ Sr-90 1.22E+11 - - - -
1.52E+9 3.10E+10 Y-91 7.33E+4 - - - - 5.26E+6 1.95E+3 l
a l Zr-95 6.83E+3 1.66E+3 - 1.79E+3 - 8.28E+5 1.18E+3 4
Nb-95 5.93E+5 2.44E+5 -
1.75E+5 - 2.06E+8 1.41E+5 j Ru-103 8.69E+3 - - 1.81E+4 - 1.06E+5 2.91E+3
, Ru-106 1.90E+5 - -
2.25E+5 -
1.44E+6 2.38E+4
- i '
i Ag-110m 3.86E+8 2.82E+8 -
4.03E+8 - 1.46E+10 1.86E+8 Sb-124 2.09E+8 3.08E+6 5.56E+5 -
1.31E+8 6.46E+8 6.49E+7 l 1.49E+8 1.45E+6 1.87E+5 -
9.38E+7 1.99E+8 3.07E+7
. Sb-125 l T3-125m 1.51E+8 5.04E+7 5.07E+7 - - 7.18E+7 2.04E+7 '
).
j To-127m 4.21E+8 1.40E+8 1.22E+8 1.04E+9 -
1.70E+8 5.10E+7
- i. Ta-129m 5.59E+8 1.92E+8 2.15E+8 1.40E+9 -
3.34E+8 8.62E+7 i I-131 2.72E+9 3.21E+9 1.05E+12 3.75E+9 -
1.15E+8 1.41E+9 i Ca-134 3.65E+10 6.80E+10 -
1.75E+10 7.18E+9 1.85E+8 6.87E+9 l Cc-136 1.96E+9 5.77E+9 -
2.30E+9 4.70E+8 8.76E+7 2.15E+9
) C3-137 5.15E+10 6.02E+10 -
1.62E+10 6.55E+9 1.88E+8 4.27E+9 ,
- B2-140 2.41E+8 2.41E+5 -
5.73E+4 1.48E+5 5.92E+7 1.24E+7 Ca-141 4.33E+4 2.64E+4 - 8.15E+3 - 1.37E+7 3.11E+3 f
g Ca-144 2.33E+6 9.52E+5 -
3.85E+5 - 1.33E+8 1.30E+5 Pr-143 1.49E+3 5.59E+2 -
2.08E+2 - 7.89E+5 7.41E+1 kr Nd-147 8.82E+2 9.06E+2 -
3.49E+2 - 5.74E+5 5.55E+1' l
44 1
?
2
i I i
l l Hope Creek ODCM Rev 14 i
i Table 2-4 (cont'd)
' Pathway Dose Factors - Atmospheric Releases
-R(io), Vegetation Pathway Dose Factors - ADULT 2
(area /yr par uCi/m3) for H-3 and C-14 (m2
- mram/yr per uCi/sec) for others
]
Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T. Body i H-3 - 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 l l 1.79E+5 C-14 8.97E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 i P-32 1.40E+9 8.73E+7 - - - 1.58E+8 5.42E+7 ,
l Cr-51 - -
2.79E+4 1.03E+4 -6.19E+4 1.17E+7 4.66E+4 4
5 Mn-54 -
3.11E+8 - 9.27E+7 -
9.54E+8 5.94E+7 FO-55 2.09E+8 1.45E+8 - - 8.06E+7 8.29E+7- 3.37E+7 Fo-59 1.27E+8 2.99E+8 - -
8.35E+7 9.96E+8 1.14E+8 Cs-57 -
1.17E+7 - - -
2.97E+8 1.95E+7' Co-58 - 3.09E+7 - - -
6.26E+8 6.92E+7 Cs-60 -
1.67E+8 - - -
3.14E+9 3.69E+8 :
Ni-63 1.04E+10 7.21E+8 - - - 1.50E+8 3.49E+8 Zn-65 3.17E+8 1.01E+9 - 6.75E+8 -
6.36E+8 4.56E+8 ;
Rb-86 -
2.19E+8 - - - 4.32E+7 1.02E+8 Sr-89 9.96E+9 - - - - 1.60E+9 2.86E+8 Sr-90 6.05E+11 - - - -
1.75E+10 1.48E+10 ,
Y-91 5.13E+6 - - - -
2.82E+9 1.37E+5 Zr-95 1.19E+6 3.81E+5 -
5.97E+5 -
1.21E+9 - 2.58E+5 Nb-95 1.42E+5 7.91E+4 -
7.81E+4 - 4.80E+8 4.25E+4 Ru-103 4.80E+6 - -
1.83E+7 -
5.61E+8 2.07E+6 i' Ru-106 1.93E+8 - -
3.72E+8 -
1.25E+10 2.44E+7 Ag-110m 1.06E+7 9.76E+6 - 1.92E+7 -
3.98E+9 5.80E+6 Sb-124 1.04E+8 1.96E+6 2.52E+5 .
8.08E+7 2.95E+9 4.11E+7 Sb-125 1.36E+8 1.52E+6 1.3SE+5 -
1.05E+8 1.50E+9 3.25E+7 Ta-125m 9.66E+7 3.50E+7 2.90E+7 3.93E+8 -
3.86E+8 1.29E+7 Ta-127m 3.49E+8 1.25E&8 8.92E+7 1.42E+9 -
1.17E+9 4 . 26E+7 Ta-129m 2.55E+8 9.50E+7 8.75E+7 1.06E+9 -
1.28E+9 4.03E+7 I-131 8.09E+7 1.16E+8 3.79E+10 1.98E+8 -
3.05E+7 6.63E+7 CS-134 4.66E+9 1.11E+10 - 3.59E+9 1.19E+9 1.94E+8 9.07E+9 Ca-136 4.20E+7 1.66E+8 - 9.24E+7 1.27E+7 1.89E+7 1.19E+8 Cs-137 6.36E+9 8.70E+9- -
2.95E+9 9.81E+8 1.68E+8 5.70E+9 B2-140 1.29E+8 1.62E+5 - 5.49E+4 9.25E+4 2.65E+8 8.43E+6 C3-141 1.96E+5 1.33E+5 - 6.17E+4 - 5.08E+8 1.51E+4 Co-144 3.29E+7 1.38E+7 - 8.16E+6 -
1.11E+10 1.77E+6 Pr-143 6.34E+4 2.54E+4 -
1.47E+4 -
2.78E+B 3.14E+3 Nd-147 3.34E+4 3.86E+4 -
2.25E+4 -
1.85E+8 2.31E+3 l 45
~
J i
i-i' Hope. Creek ODCM Rev 14 i
l Table 2-4 (cont'd)
- Pathway Dose Factors - Atmospheric Releases ,
j R(io), Vegetation Pathway Dose Factors - TEENAGER j (aren/yr per uCi/m3) for H-3 and C-14 i (m2
- mrea/yr per uCi/sec) for others
) Nuclide 19.na Liver Thyroid Kidney Idulg GI-TLT T. Body l H-3 -
2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 C-14 1.45E+6 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5
! P-32 1.61E+9 9.96E+1 - - - 1.35E+8 6.23E+7 l Cr-51 - -
3.44E+4 1.36E+4 8.85E+4 1.04E+7 6.20E+4 l
j Mn-54 -
4.52E+fi - 1.35E+8 -
9.27E+8 8.97E+7 Fo-55 3.25E+8 2.31E+6 - -
1.46E+8 9.98E+7 5.38E+7 j Fa-59 1.81E+8 4.22E+E - -
1.33E+8 9.98E+8 1.63E+8 Co-57 -
1.79E+7 - - -
3.34E+8 3.OOE+7
! Co-58 -
4.38E+7 - - -
6.04E+8 1.01E+8 i Co-60 -
2.49E+8 - - - 3.24E+9 5.60E+8 l Ni-63 1.61E+10 1.13E+9 - - -
1.81E+8 5.45E+8 i Zn-65 4.24E+8 1.47E+9 - 9.41E+8 -
6.23E+8 6.86E+8 f Rb-86 -
2.73E+8 - - -
4.05E+7 1.28E+8
- Sr-89 1.51E+10 - - - -
1.80E+9 4.33E+8 >
! Sr-90 7.51E+11 - - - -
2.11E+10 1.85E+11 3 Y-91 7.tl7E+6 -
3.23E+9 2.11E+5 i
i Zr-95 1.74E+6 5.49E+5 -
8.07E+5 -
1.27E+9 3.78E+5 i Nb-95 1.92E+5 1.06E+5 -
1.03E+5 -
4.55E+8 5.86E+4
} Ru-103 6.87E+6 - -
2.42E+7 -
5.74E+8 2.94E+6 Ru-106 3.09E+8 - -
5.97E+8 -
1.48E+10 3.90E+7 i
! Ag-110m 1.52E+7 1.44E+7 -
2.74E+7 -
4.04E+9 8.74E+6 Sb-124 1.55E+8 2.85E+6 3.51E+5 -
1.35E+8 3.11E+9 6.03E+7 j Sb-125 2.14E+8 2.34E+6 2.04E+5 -
1.88E+8 1.66E+9 5.OOE+7 i To-125m 1.48E+8 5.34E+7 4.14E+7 - -
4.37E+8 1.98E+7 l To-127m 5.51E+8 1.96E+8 1.31E+8 2.24E+9 -
1.37E+9 6.56E+7 ,
j Ta-129m 3.67E+8 1.36E+8 1.18E+8 1.54E+9 -
1.38E+9 5.81E+7 )
j I-131 7.70E+7 1.08E+8 3.14E+10 1.85E+8 -
2.13E+7 5.79E+7 !
j Cz-134 7.09E+9 1.67E+10 -
5.30E+9 2.02E+9 2.08E+8 7.74E+9 '
l C3-136 4.29E+7 1.69E+8 -
9.19E+7 1.45E+7 1.36E+7 1.13E+8
- C2-137 1.01E+10 1.35E+10 -
4.59E+9 1.78E+9 1.92E+8 4.69E+9 i i B2-140 1.38E+8 1.69E+5 -
5.75E+4 1.14E+5 2.13E+8 8.91E+6 l l C3-141 2.82E+5 1.88E+5 -
8.86E+4 -
5.38E+8 2.16E+4 i j C3-144 5.27E+7 2.18E+7 -
1.30E+7 -
1.33E+10 2.83E+6 '
i Pr-143 7.12E+4 2.84E+4 -
1.65E+4 -
2.34E+8 3.55E+3 y- Nd-147 3.63E+4 3.94E+4 -
2.32E+4 -
42E+8 2.36E+3 i
! 46 b i
- 1 i
f
l 4
l Hope Creek ODCM Rev 14 1
I Table 2-4 (cont'd) j Pathway Dose Factors - Atmospheric Releases
, R(io), Vegetation Pathway Dose Factors - CHILD (mren/yr per uCi/m3) for H-3 and C-14 (m2
- mrem /yr per uCi/sec) for others j Nuclide Bone Liver Thyroid Kidney LMDg GI-LLT T. Body
- H-3 -
4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 i
C-14 3.50E+6 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 P-32 3.37E+9 1.58E+8 - - -
9.30E+7 1.30E+8 3
Cr-51 - -
6.54E+4 1.79E+4 1.19E+5 6.25E+6 1.18E+5 4
1 4
Mn-54 -
6.61E+8 -
1.85E+8 - 5.55E+8 1.76E+8 i FG-55 8.OOE+8 4.24E+8 - -
2.40E+8 7.86E+7 1.31E+8 I FO-59 4.01E+8 6.49E+8 - -
1.88E+8 6.76E+8 3.23E+8 i Co-57 -
2.99E+7 - - -
2.45E+8 6.04E+7 i Co-58 -
6.47E+7 - - -
3.77E+8 1.98E+8 i Co-60 -
3.78E+8 - - -
2.10E+9 1.12E+9 i Ni-63 3.95E+10 2.11E+9 - - -
1.42E+8 1.34H+9
- Zn-65 8.12E+8 2.16E+9 -
1.36E+9 -
3.80E+8 1.35E+9 4 l j Rb-86 -
4.52E+8 - - -
2.91E+7 2.78E+8
{ Sr-89 3.59E+10 - - - -
1.39E+9 1.03E+9 l l Sr-90 1.24E+12 - - - -
1.67E+10 3.15E+11 i Y-91 1.87E+7 - - - -
2.49E+9 5.01E+5 l
- Zr-95 3.90E+6 8.58E+5 -
1.23E+6 -
8.95E+8 7.64E+5 i Nb-95 4.10E+5 1.59E+5 -
1.50E+5 -
2.95E+8 1.14E+5 l Ru-103 1.55E+7 - -
3.89E+7 -
3.99E+8 5.94E+6 i Ru-106 7.45E+8 - -
1.01E+9 -
1.16E+10 9.30E+7 1
! Ag-110m 3.22E+7 2.17E+7 -
4.05E+7 -
2.58E+9 1.74E+7 1 Sb-124 3.52E+8 4.57E+6 7.78E+5 -
1.96E+8 '2.20E+9 1.23E+8
, Sb-125 4.99E+8 3.85E+6 4.52E+5 -
2.78E+8 1.19E+9 1.05E+8
] Ta-125m 3.51E+8 9.50E+7 9.84E+7 - -
3.38E+8 4.67E+7
) Ta-127m 1.32E+9 3.56E+8 3.16E+8 3.77E+9 -
1.07E+9 1.57E+8
. Ta-129m 8.54E+8 2.39E+8 2.75E+8 2.51E+9 -
1.04E+9 1.33E+8
! I-131 1.43E+8 1.44E+8 4.7GE+10 2.36E+8 -
1.28E+7 8.18E+7
! C3-134 1.60E+10 2.63E+10 -
8.14E+9 2.92E+9 1.42E+8 5.54E+9 j C3-136 8.06E+7 2.22E+8 -
1.18E+8 1.76E+7 7.79E+6 1.43E+8 l l Co-137 2.39E+10 2.29E+10 -
7.46E+9 2.68E+9 1.43E+8 3.38E+9 l Ba-140 2.77E+8 2.43E+5 -
7.90E+4 1.45B+5 1.40E+8 1.62E+7 i
! C3-141 6.35E+5 3.26E+5 -
1.43E+3 -
4.07E+8 4.84E+4
- 1 I C3-144 1.27E+8 3.98E+7 -
2.21E+7 -
1.04E+10 6.78E+6 I
, Pr-143 1.48E+5 4.46E+4 -
2.41E+4 -
1.60E+8 7.37E+3 j Nd-147 7.16E+4 5.80E+4 -
3.18E+4 -
9.18E+7 4.49E+3 i
47 1
t
i 4
i Hope Creek ODCM Rev 14 1
Table 2-4 (cont'd)
Pathway Dose Factors - Atmospheric Releases 1
R(io), Ground Plane Pathway Dose Factors (m2
- mram/yr per uCi/sec)
J l Nuclide Any Organ H-3 -
C-14 P-32 -
Cr-51 4.68E+6 Mn-54 1.34E+9
! Fe-55 -
l Fe-59 2.75E+8 l Co-58 3.82E+8 1 Co-60 2.16E+10
! Ni-63 -
! Zn-65 7.45E+8 '
Rb-86 8.98E+6 Sr-89 2.16E+4 Sr-90 -
Y-91 1.08E+6 Zr-95 2.48E+8
+
Nb-95 1.36E+8 Ru-103 1.09E+8 Ru-106 4.21E+8 Ag-110m 3.47E+9 Te-125m 1.55E+6 Te-127m 9.17E+4 Te-129m 2.00E+7 i I-131 1.72E+7 CE-134 6.75E+9 Cs-136 1.49E+8 )
Cs-137 1.04E+10 Ba-140 2.05E+7 Ce-141 1.36E+7 Ce-144 6.95E+7 Pr-143 -
Nd-147 8.40E+6 48 l l
1 1
- . - - - -.. ... - .1
Hope Creek ODCM Rev 14 APPENDIX A EVALUATION OF DEFAULT MPC VALUES FOR LIQUID EFFLJENTS i
Hope Creek ODCM Rev 14 APPENDIX A Evaluation of Default MPC Value for Liquid Effluent In accordance with the requirements of Technical Specification 3.3.7.10 the radioactive effluent monitors shall be operable with alarm setpoints established to ensure that the concentration of radioactive material at the discharge point does not exceed the MPC value of 10 CFR 20, Appendix B, Table II, Column 2. The determination of allowable radionuclide concentration and corresponding alarm setpoint is a function of the individual monitor.
In order to limit the need for routinely having to reestablish the alarm setpoints as a function of changing radionuclide distributions, a default alarm setpoint can be established. This default setpoint can be based on an evaluation of the radionuclide distribution from the 1991 to 1993 release data of the liquid affluents from Hope Creek and the effective MPC value for this distribution.
The effective MPC value for a radionuclide distribution is calculated by the equation:
EC i (gamma smitters only) (A.1)
MPC, = -------------------------------
C (gamma) 3 g _____________
MPCs where:
MPC, = an effective MPC value for a mixture of radionuclides (uci/al)
C, = concentration of radionuclide i in the mixture MPCi = the 10 CFR 20, Appendix B, Table II, Column II MPC value for radionuclide 1 (uCi/al)
~
O, O
l Hope Creek ODCM Rev 14 Considering the average effective MPC values from 1991 thru 1993 releases it is reasonable to select an MPC value of 1.1E-04 uci/ml cs typical of liquid radwaste discharges. This value will be reviewed and adjusted as necessary based on the distribution history of effluents from Hope Creek. Using the value of 1.1E-4 uCi/ml to calculate the default alarm setpoint, results in a cetpoint that:
- 1) Will not require frequent re-adjustment due to minor variations in the nuclide distribution which are typical of routine plant operations, and;
- 2) Will provide for a liquid radwaste discharge rate (as cvaluated for each batch release) that is compatible with plant cperaticas (Refer to Table 1-1).
A-2
Hope Creek ODCM Rev 14 TABLE A-1 CALCULATION OF EFFECTIVE MPC HOPE CREEK 1991 ACTIVITY 1992 ACTIVITY 1993 ACTIVITY NUCLIDE HEg ner.rAsEn (ci) Dar masEn (ci) DRr. RASED (C1)
Na-24 3.0E-05 2.05E-04 1.11E-03 1.20E-04 Cr-51 2.0E-03 5.60E-02 9.98E-02 1.57E-01 Mn-54 1.0E-04 3.42E-02 7.19E-02 6.30E-02 As-76 2.0E-05 8.39E-05 5.73E-05 1.03E-05 Co-58 9.0E-05 8.86E-04 2.24E-03 1.35E-03 Fe-59 5.0E-05 5.54E-03 1.76E-02 8.74E-03 Co-60 3.0E-05 7.51E-03 1.21E-02 1.15E-02 Zn-65 1.0E-04 5.94E-02 6.63E-02 7.01E-02 Y-91m 3.0E-03 2.48E-05 N/D N/D Ag-110m 3.0E-05 8.65E-04 9.83E-03 2.16E-03 Sr-92 6.0E-05 3.26E-04 2.57E-04 N/D Nb-95 1.0E-04 2.01E-05 1.64E-04 N/D Zr-97 2.0E-05 N/D 2.23E-05 1.45E-05 Tc-99m 3.0E-03 1.03E-05 N/D 1.79E-03 La-140 2.0E-05 N/D 8.28E-06 N/D I-133 1.0E-06 7.91E-06 N/D N/D Cs-137 2.0E-05 2.09E-05 1.56E-05 4.85E-05 Hg-203 2.0E-05 2.72E-06 N/D N/D Zn-69m 6.0E-05 N/D N/D 2.33E-05 Nb-97 9.0E-04 N/D N/D 4.33E-04 Sr-91 5.0E-05 4.67E-06 N/D N/D Total Curies 1.65E-01 2.81E-01 3.16E-01 (Gamma)
SUM (Ci/MPC1) 1.39E+03 2.59E+03 2.06E+03 (Gamma)
MPCs (uCi/ml) 1.19E-04 1.10E-04 1.53E-04 N/D=Not detected
/'
A-3 t - -- ------_____-- --- ---- - _ __ _ _ _
- speegna, . . . . ,
sa. ...
i i
i i
Hope Creek ODCN Rev 14
]
4 i
i 4
4 l
4 i
j APPENDIX B 1
i i i
i TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS i
i i
i LIQUID RADIOACTIVE EFFLUENT i
e i
1 ,
i i
1 4
e i 1
t l 1 i i
N
- l. ]
4
)
e i
'I 1
i i
4 _
1 i
[.
l 1
1 l
t
' Hope Creek ODCM Rev 14 4
4 i
APPENDIX B' 4
l Technical Basis for Effective Dose Factors -
4- Liquid Effluent Releases ,
i i
l The radioactive liquid effluents from Hope Creek from 1991 through 1993 j were evaluated to determine the dose contribution of the radionuclide
- distribution. This analysis was performed to evaluate the use of a j limited dose analysis for determining environmental doses, providing a simplified method of determining compliance with the dose limits of l Technical Specification 3.11.1.2. For the expected radionuclide i distribution of affluent from Hope Creek during 1991 to 1993, the j controlling organ is the liver. The calculated liver dose is predominately a function of the Zn-65 and Fe-55 releases. The
{
i radionuclides, 2n-65 and Fe-55 also contribute the large majority of the l calculated total body dose. The results of this evaluation are
- l. presented in Table B-1. '
s
) For purposes of simplifying the details of the dose calculation process, j it is conservative to identify a controlling, dose significant
! radionuclide and limit the calculation process to the use of the dose i conversion factor for this nuclide. Multiplication of the total release i' (i.e., cumulative activity for all radionuclides) by this dose ;
conversion factor provides for a dose calculation method that is '
i simplified while also being conse vative.
For the evaluation of the maximum organ dose, it is conservative to use the En-65 dose conversion factor (5.13E5 mram/hr per uci/al). By this 1 approach, the maximum organ dose will be overestimated since this l nuclide has the highest organ dose fraction of all the radionuclides
- evaluated. For the total body calculation, the Zn-65 dose factor (2.32E5 area /hr per uCi/ml, total body) is the highest among the
! identified dominant nuclides.
For evaluating compliance with the dose limits of technical l Specification 3.11.1.2, the Collowing simplified equations may be used:
j
{
Total Body i
8.35E-04
- W1 l D. = ----------------
- A,.
i
- Ci (B.1)
<, CTBD l .
1 i B-1
i i
a I .
i-1 Hope Creek ODCM Rev 14 '
1 i
i Where: I i
i D. = dose to the total body (aren)'
A,.i = 2.32ES, total body ingestion dose conversion factor ;
for Zn-65 where A is dose conversion factor, i is isotope 4
l l
1 which is 2n-65, and TB is the total body (area /hr per uCi/ml)
VOL = volume of liquid effluent released (gal) g Ci = total concentration of all radionuclides (uci/ml)
CTBD = average cooling tower blowdown discharge rate during 1
l release period (gal / min) j 8.35E-04 = conversion factor (1.67E-2 hr/ min) and the near field '
dilution factor 0.05 i
i 1 Substituting the value for the Zn-65 total body dose conversion factor, j the equation simplified to:
i
' 1.94E2
- VOL
. D. = ------------------
- IC i (B.2)
! CTBD i
Maximum Organ 8.35E-4
- VOL
- Aio, Liver Daax = -------------------------------- *EC i (B.3) l CTED t l
] Where:
Daax = maximum organ dose (area) i i
] Aio, = 5.13ES, liver ingestion dose conversion factor for Liver Zn-65 where A is dose conversion factor, i is isotope i
j which is Zn-65 and O is maximum organ which is the i liver (arem/hr per uCi/ml).
j
) Substituting the value for Aio the equation simplifies to:
} 4.28E2
- VOL 5 Daax = ------------------
- I Ci (B.4)
- CTBD 4 I
i B-2 ;
4
i l
L i Hope Creek ODCM Rev 14 Tritium is not included in the limited analysis dose assessment for liquid releases, because the potential dose resulting from normal reactor releases is relatively negligible.
Near Field Dilution Factor The near field dilution f actor stems from NuReg-0133, Section 4.1. For plants with cooling towers, such as Hope Creek, a dilution factor is applicable so that the product or the average blowdown flow (in CFS) and the dilution factor is 1000 cfs or less. The average minimum cooling tower blowdown for Hope Creek is 1.90E4 GPM (from FSAR 11.2) . This converts to 42 CFS, for conservatism a dilution factor of 20 will be used, giving a dilution flow of 880 CFS. This near field dilution factor of 20 is inverted to a multiple of 0.05, multiplied times the liquid effluent dose equations.
/
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Hope Creek ODCM Rev 14 l
TABLE B-1 ,
Adult Dose Contri.hutions' i Fish and Invertebrate Pathways Hope Creek l l
Nuclide Release TB Dose GI-LLI Liver Dose Year (Ci) Frac. Dose Frac. Frac.
Fa-55 4.51E-2 0.02 0.03 0.04 1993 FO-55 2.52E-2 0.01 0.01 0.01 1992 FG-55 6.23E-1 0.26 0.34 0.41 1991 Mn-54 6.30E-2
- 0.04 0.01 1993 Mn-54 7.19E-2
- 0.04 0.01 1992 Mn-54 3.42E-2
- 0.02
- 1991 3-58 1.35E-3 *- *
- 1993 Co-58 2.24E-3 * *
- 1992 Cs-58 8.86E-4 * *
- 1991 Fc-59 8.74E-3 0.04 0.18 0.04 1993 Fa-59 1.76E-2 0.08 0.27 0.09 1992 Fc-59 5.54E-3 0.02 0.09 0.02 1991 j Co-60 1.15E-2
- 0.01
- 1993 Co-60 1.21E-2 * *
- 1992 Co-60 7.51E-3 * *
- 1991 7.01E-2 0.93 0.69 0.90 1993
_ Zn-65 Zn-65 6.63E-2 0.90 0.51 0.87 '1992 2n-65 5.94E-2 0.71 0.52 0.57 1991 S = Less than 0.01 B-4
l 1
i Hope Creek ODCM Rev 14 I
APPENDIX C TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS GASEOUS RADIOACTIVE EFFLUENTS i
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i Hope Creek ODCM Rev 14 1
APPENDIX C j Technical Basis for Effective Dose Factors -
J Gaseous Radioactive Effluents 1
t Overview 1 The evaluation of doses due to releases of radioactive material to the I
- atmosphere can ' be simplified by the use of effective dose transfer j
factors instead of using dose factors which are radionuclide specific.
- These effective factors, which are based .on. typical radionuclide
{
distributions of releases, can be applied to the total radioactivity l releases to approximate the dose in the environment. Instead of having l j to perform individual radionuclide dose analysis only a single j multiplication (i.e., Kaff, Maff, or Neff times the total quantity of :
j radioactive material releases) would be needed. The approach provides i a reasonable estimate of the actual dose while eliminating the need for '
l l a detailed calculation technique.
f j Determination of Effective Dose Factors i
i Effective dose transfer factors are calculated by the following
- equations
! K, =
I (Ki
- f) i (c.1)
{
i Where:
k j K, = the effective total body factor due to gamma emissions !'
l from all noble gases released.
j Ki = the total body dose factor due to gamma emissions from each l noble gas radionuclide i released.
j fi = the fractional abundance of noble gas radionuclide i i
relative to the total noble gas activity.
! (L + 1.1M) , =I ((Is + 1.1 - M )
- f) i (C.2) i i Where:
1 (L + 1.1M) , = the effective skin dose factor due to beta and gamma emissions from all noble gases released.
(Ig + 1.1 M ) = the skin dose factor due to beta and gamma emissions from each noble gas radionuclide i released.
j i
a C-1
}
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_ _ _ _ . _ r . _ _ . . , _ , - - - . _ , , ,,,_.w
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Hope Creek ODCM Rev 14
! M, = E (Mi
- f)i (C.3)
J
~
Where:
j M, = the effective air dose factor due to gamma emissions from all 1 noble gases released.
M, = the air dose factor due to gamma emissions from each noble gas
]
i radionuclide i released.
4 l N, =
I (Ni
- f) i (C.4) l Where:
I
! N, = the effective air dose factor due to beta emissions from
- all noble gases released.
Ni = the air dose factor due to beta emissions from each noble gas I radionuclide i released.
I Normally, it would be expected that past radioactive affluent data would be used for the determination of the effective dose factors. However, l
J the noble gas releases from Hope Creek have a-short history and with
- continued excellent fuel performance, has hampered efforts in collecting l
and detecting appreciable noble gas mixes of radionuclides. So, to 1 provide a reasonable basis for the derivation of the effective noble gas
!4 dose factors, the source terms from ANSI N237-1976/ANS-18.1, " Source ,
Term Specifications", Table 5 has been used as representing a typical
~
distribution. The effective dose factors as derived are presented in Table C-1.
I j Application j To provide an additional degree of conservatism, a factor of 0.50 is '
j introduced into the dose calculation process when the effective dose transfer factor is used. This conservatism provides additional l l
assurance that the evaluation of doses by the use of a single effective l
- factor will not significantly underestimate any actual doses in the
- environment.
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' Hope Creek ODCM Rev 14
- For evaluating compliance with the dose limits of Technical l Specification 3.11.2.2, the following simplified equations may be used
~!
j 3.17E-08 i D, = ------------
- X/Q
- PL,
- IQ i (C.5) j 0.50 j and 4
3.17E-08 D, = ------------
- X/Q
- N,
- IQ 4 (C.6) 0.50 Where:
j D, = air dose due to gamma emissions for the cumulative release i of all noble gases (arad) i D. = air dose due to beta emissions for the cumulative release j of all noble gases (mrad) i X/Q = atmospheric dispersion to the controlling site boundary 3
(sec/m )
N6r
= 8.1E3, effective gamma-air dose factor (mrad /yr per uCi/m')
l N, = 8.5E3, effective beta-air dose factor (arad/yr per uCi/m ) 3 i Qi = cumulative release for all noble gas radionuclides (uci) j 3.17E-08 = conversion factor (yr/sec) 4 0.50 = conservatism factor to account for the variability in the l effluent data i
4 Combining the constants, the dose calculation equations simplify to:
i D, = 5.14E-4
- X/Q
- I Qi (C.7)
D, = 5.39E-4
- X/Q
- I Q3 (C.8) l
- The effective dose factors are to be used on a limited basis for the j purpose of facilitating the timely assessment of radioactive effluent j releases, particularly during periods of computer malfunction where a i detailed dose assessment may be unavailable.
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' Hope Creek ODCM Rev 14 1 l i
TABLE C-1 i Effective Dose Factors l 1
Noble Gases - Total Body and Skin i Total Body Effective Skin Effective Kaff (L + . 1.1 M) eff 8 i Radionuclide 11*,, (mram/v ner uci/m 3) (aram/v ner uci/m)
- Kr83m 0 .01 -----
Kr85m 0.01 1.0E1 2.8E1 Kr87 0.04 2.4E2 6.6E2 l '
- Kr88 0.04 5.9E2- ,
7.6E2
- Kr89 0.27 4.5E3 7.9E3 Xe133 0.02 5.9EO 1.4E1 Xe135 0.05 9.0E1 2.0E2 Xe135m 0.06 1.9E2 2.6E2 Xe137 0.31 4.4E2 4.3E3 Xe138 0.19 1.7E3 2.7E3 Total 7.8E3 1.7E4
' Noble Gases - Air Total Boai' Effective Skin Effective 4 Keff (L + 1.1 M) eff Radionuclide 11,*, f aren/v ner uCi/m 8) (aram/v ner uci/m 8) l 1
Kr83m 0.01 ------ 3.0E0 !
Kr85m 0.01 1.2E1 2.0E1 Kr87 0.04 2.5E2 4.1E2 Kr88 0.04 6.1E2 1.2E2 Kr89 0.27 4.7E3 2.9E3 Xe133 0.02 7.0E0 2.1El Xe135 0.05 9.6El 1.2E2 Xe135m 0.06 2.0E2 4.4E1 Xe137 0.31 4.7E2 3.9E3 Xe138 0.19 1.8E3 9.0E2 Total 8.1E3 8.4E3
- Based on noble gas distribution from ANSI N237-1976/ANS-18.1,
" Source Term Specification". j C-4 l
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Hope Creek ODCM Rev 14 i
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? -
) APPENDIX D i
)
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(
TECHNICAL BASIS FOR EFFECTIVE DOSE PARAMETERS i
GASEOUS RADIOACTIVE EFFLUENTS 4
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Hope Creek ODCM Rev 14 i i APPENDIX D i
l
! Technical Basis for Effective Dose Parameters j j Gaseous Radioactive Effluent Releases i
The pathway dose factors for the controlling infant age group were i
evaluated to determine the controlling pathway, organ and radionuclide.
l This analysis was performed to provide a simplified method for
! determining compliance with Technical Specification 3.11.2.3. For the j the' controlling pathway is the grass - cow - milk j
infant age (g/c/m) pathway.group, ~ An infant receives a greater radiation dose from tho'
- g/c/m pathway than any other pathway. Of this g/c/m pathway, the
- maximum exposed organ including the total body, is the thyroid, and the j highest dose contributor is radionuclide I-131. The results of this j evaluation are presented in Table D-1.
4 l For purposes of simplifying the details of the dose calculation process,
! it is conservative to identify a controlling,-dose significant organ and -
l radionuclide and limit the calculation process to the use of the dose j conversion factor for the organ and radionuclide. Multiplication of the i total release (i.e., cumulative activity for all radionuclides) by this
! dose conversion factor provides for a dose calculation method that is j simplified while also being conservative.
l For the evaluation of the dose commitment via a controlling pathway and l age group, it is conservative to use the infant, g/c/a, thyroid, I-131 l
- pathway dose factor (1.67E12m2*mram/yr per uCi/sec) . By this approach, j the maximum dose commitment will be overestimated since I-131 has the i highest pathway dose factor of all radionuclides evaluated.
s For evaluating compliance with the dose limits of Technical
- Specification 3.11.2.3, the following simplified equation may be used
D. = 3.17E-8
- W
- RI-131
- E Qi (D.1) i i Where:
D. = maximum organ dose (area) 4 W = atmospheric dispersion parameter to the controlling i location (s) as identified in Table 2-3.
! X/Q = Atmospheric dispersion for inhalation pathway (sec/m) s i D/Q = atmospheric disposition for vegetation, milk and ground l Plane exposure pathways (m2) .
4 i
i,-
j D-1
. 1
- .w - - - _ - _ - - . - - - -
^
Hope Creek ODCM Rev 14
) Q 4
= cumulative release over the period of interest for
, radioiodines and particulates (uci).
j 3.17E-8 = conversion factor (yr/sec) f RI-131 = I-131 dose parameter for the thyroid for the identified controlling-pathway.
! = 1.05E12, infant thyroid dose parameter with the grass -
! cow - milk pathway controlling (m 2 mrea/yr per
- uci/sec) 1
- The ground plane exposure and inhalation pathways need not be considered l when the above simplified calculational method is used because of the i overall negligible contribution of these pathways to the total thyroid 1 dose. It is recognized that for some particulate radionuclides (e.g.,
{
co-60 and Cs-137), the ground exposure pathway may represent a higher dose contribution than either the vegetation or milk pathway. However, J
i use of the I-131 thyroid dose parameter for all radionuclides will
< maximize the organ dose calculation, especially considering that no
- other radionuclides has a higher dose parameter for any organ via any pathway than I-131 for the thyroid via the milk pathway.
- The location of exposure pathways and the maximum organ dose calculation
! may be based on the available pathways in the surrounding environment of 3
Hope Creek as identified by the annual land-use census (Technical
- Specification 3.12.2). Otherwise, the dose will be evaluated based on the predetermined controlling pathways as identified in Table 2-3.
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Hope Creek ODCM Rev 14 5-4 l
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TABLE D-1 j i
Infant Dose Contributions ;
a' I Fraction of Total Organ and Body Dose i PATHWAYS 1
. Tarcet Organs Grass - Cow - Milk Ground Plana Total Body -0.02 0.15 i
Bone 0.23 0.14 i >
Liver
- 0.09 0.15 Thyroid 0.59 0.15 il Kidney 0.02 0.15 :
i 0.14 4 Lung 0.01 a
j GI-LLI 0.02 0.15 1
1 ,
i l i
TABLE D-2 i
I Fraction of Dose Contribution by Pathway i
)
i Pathway _f_,
)
s i Grass-Cow-Milk O.92
- i 4
j; Ground Plane 0.08
- Inhalation N/A i i
1 y*
D-3 i l 4
1 L___________________ _ _ _ . . _ . _ _ _ _ _ . . , . . . . _ . . _ _ _ _ _ . , , . _ _ _ . . _ _ . _ . . .
. . - - . . - . . ~_.
4 ,
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4 Hope Creek ODCM Rev 14 1
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APPENDIX E i
1 l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM --
i i SAMPLE TYPE, LOCATION AND ANALYSIS 5
1
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1 l Hope Creek ODCM Rev 14 l APPENDIX E 2 SAMPLE DESIGMATION Samples are identified by a three part code. The first two letters are i the power station identification code, in this case "SA". The next three letters are for the media sampled.
\ ,
i AIO = Air Iodine IDM = Immersion Dose (TLD) i APT = Air Particulates MLK = Milk j ECH = Hard Shell Blue Crab PWR = Potable Water (Raw)
! ESF = Edible Fish PWT = Potable Water (Treated) i ESS = Sediment RWA = Rain Water (Precipitation)
- FPB = Beef SWA = Surface Water
{ FPL = Green Leafy Vegetables VGT = Fodder Crops (Various) i FPV = Vegetable (Various) WWA = Well Water j GAM = Game The last four symbols are a location code based on direction and distance from the site. Of these, the first two represent each of the '
sixteen angular sectors of 22.5 degrees centered about the reactor site.
- Sector one is divided evenly by the north axis and other sectors are '
- numbered in a clockwise direction; i.e., 2=NNE, 3=NE, 4=ENE, etc. The j next digit is a letter which represents the radial distance from the i plant
a l S = On-site location E = 4-5 miles off-site j A = 0-1 miles off-site F = 5-10 miles off-site j B = 1-2 miles off-site G = 10-20 miles off-site i C = 2-3 miles off-site H = > 20 miles off-site D = 3-4 miles off-site The last number is the station numerical designation within each sector l and zone ; e . g . , 1, 2 , 3 , . . . For example; the designation SA-WWA-5D1 would j indicate a sample in the SGS program (SA), consisting of well water i (WWA), which had been collected in sector number 5, centered at 90' (due
- east) with respect to the reactor site at a radial distance of 3 to 4 ,
radial distance D). The number 1 indicated j miles of f-site, (therefore, i that this is sampling station #1 in that particular sector.
2 l l l 1 l i l i )
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J Hope Creek ODCM Rev 14 i
) SAKPLING LOCATIONS l All sampling locations and specific information about the individual I locations are given in Table E. Maps E-1 and E-2 show the locations of j sampling stations with respect to the site.
f TABLE E-1 i STATION
! CODE STATION LOCATION SAMPLE TYPES 2S2 0.4 mi. NNE of vent IDM 4
5 2S3 700 ft. NNE of vent; fresh water WWA l
holding tank SS1 1.0 mi. E of vent; site access road AIO, APT, IDM
.l 6S2 0.2 mi. ESE of vent; observation IDM, SOL i building i
! 7S1 0.12 mi. SE of vent; station personnel IDM li gate 10S1 0.14 mi. SSW of vent; site shoreline IDM i
4 I 11S1 0.09 mi. SW of vent; site shoreline IDM 1
i 11A1 0.2 mi. W of vent; outfall area ECH, ESF, ESS, SWA f
0.3 mi. NW of vent; cooling tower ESS
) 15A1 blowdown discharge line l
i 16Al 0.7 mi. NNW of vent; south storm drain ESS j discharge line 12C1 2.5 mi. WSW of vent; west bank of ECH, ESF, ESS Delaware River SWA 4D2 3.7 mi. ENE of vent; Alloway Creek IDM Neck Road SD1 3.5 mi. E of vent; Alloway Creek AIO, APT, IDM, Neck Road 3.9 mi. SSW of vent; Taylor's Bridge IDM, SOL I 10D1 l Spur ll E-2 i
i
-w= - - - - - _,
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i Hope Creek ODCM Rev 14 j
j TABLE E-1 (Cont'd) i j STATION l CODE STATION LOCATION SAMPLE TYPES i :
I 11D1 3.5 mi. SW of vent GAM l 1
14D1 3.4 mi. WNW of vent; Bay View, Delaware IDM 15D1 3.8 mi. NW of vent; Augustine Beach, Del. IDM ;
) 2E1 4.4 mi. NNE of vent; local fara IDM 1
1 3E1 4.1 mi. NE of vent; local fara FPB, FPV, GAM, j IDM, VGT, WWA
- 3E3 5.6 mi. NE of vent; local farm FPV
{ 7El 4.5 mi. SE of vent; 1 mi. W of Mad 'ESF, ESS, SWA i Horse Creek !
4 !
i 9El 5.0 mi. SW of vent IDM i 11E2 5.0 mi. SW of vent IDM '
1
! 12E1 4.4 mi. WSW of vent; Thomas Landing IDM i
! 13E1 4.2 mi. W of vent; Diehl House Lab IDM ;
j 16El 4.1 mi. NNW of vent; Port Penn AIO, APT, IDM i SOL
! 1F1 5.8 mi. N of vent; Fort Elfsborg AIO, APT, IDM l SOL 1F2 7.1 mi. N of vent; midpoint of SWA j Delaware
! 2F2 8.7mi. NNE of vent; Salem Substation AIO, APT, IDM, I
RWA i
) 2F3 8.0 mi. NNE of vent; Salem Water Co. PWR,PWT
- 2F4 6.3 mi. NNE of vent; local fara FPV,FPL, SOL i
- 2F5 7.5 mi. NNE of vent; Salem High School IDM i
b j
n, "
! E-3 i
q
1 Hope Creek ODCM Rev 14 I
1 TABLE E-1 (Cont'd) i STATION STATION LOCATION SAMPLE TYPES l CODE t
- 2F6 7.3 mi. NNE of vent; Southern Training IDM
! Center
! i 5.7 mi. NNE of vent; local farm MLK,VGT, SOL 2F7 i
! 3F2 5.1 mi. NE of vent; Hancocks Bridge IDM
- Mum cipal Building 3F3 8.6 mi. NE of vent; Quinton Township IDM 1 School l 4F2 6.0 mi. ENE of vent; LAC Township IDM f
5F1 6.5 mi. E of vent SOL,IDM l
I j 5F3 6.5 mi. E of vent; local farm FPL 1
l 6F1 6.4 mi. ESE of vent; Stow Neck Road IDM s
! 7F2 9.1 mi. SE of vent; Bayside, NJ IDM I IDM j 10F2 5.8 mi. SSW of vent
\
i j 11F1 6.2 mi. SW of vent; Taylor's Bridge IDM !
a Delaware 4
11F3 5.3 mi. SW of vent; Townsend, DE MLK,VGT, SOL i
12F1 9.4 mi. WSti of vent; Townsend Elem. IDM l
i School j 13F2 6.5 mi. W of vent; Odessa, DE IDM I 13F3 9.3 mi. W of vent; Redding Middle IDM j School, Middletown, DE
) 9.8 mi. W of vent; Middletown, DE IDM 1
13F4 i !
. 14F2 6.6 mi. WNW of vent; Boyds Corner IDM 14F3 5.4 mi. WNW of vent; local farm FPV l
\
14F4 7.6 mi. WNW of vent; local fara MLK, SOL,VGT 1
E 15F3 5.4 mi. NW of vent IDM I
l 4 E-4 I
}
i Hope Creek ODCM Rev 14 TABLE E-1 (Cont'd)
J STATION CODE STATION LOCATION SAMPLE _TYEES 1
16F1 6.9 mi. NNW of vent; CED Canal. ESS, SWA
- 16F2 8.1 mi. NNW of vent; Delaware City IDM i Public School
- 1G1 10.3 mi. N of vent; local farm FPV 1G3 19 mi. N of vent; Wilmington, DE IDM 2G1 12 mi. NNE of vent; Wilmington, DE FPV 2G2 13.5 mi. NNE of vent; local fara FPV s
3G1 17 mi. NE of vent; local farm IDM, MLK, VGT l
' SOL i
10G1 12 mi. SSW of vent; Smyrna, DE IDM 16G1 15 mi. NNW of vent; Greater Wilmington IDM Airport 3H1 32 mi. NE of vent; National Park, NJ IDM l
3H3 110 mi. NE of vent; Research and AIO, APT, IDM i
Testing Laboratory i
i 3HS 25 mi. NE of vent; local farm FPL, FPV l l
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j Hope Creek ODCM Rev 14 i
$, SAMPLES COLLECTION AND ANALYSIS i .
1 1 Analysis
- Sample collection Method Air Particulate Continuous low volume Gross Beta analy91s air sampler.- Sample on each weekly
{
i collected every week sample. Gamma along with the filter spectrometry shall 3
1 change. be performed if j gross beta exceeds 10 times the yearly '
1 mean of 6he control l station value. As l
we.ll one sample is analyzed > 24 hrs
- after sampling to j allow for radon and ;
j thorium daughter l decay. Gamma i
isotopic analysis on quarterly l
! composites.
1 Air Iodine A TEDA impregnated Iodine 131 analysis charcoal cartridge is are performed on
! connected to an air each weekly sample.
j particulate air sampler
! and is collected weekly at filter change.
{
A Crab and Fish Two batch samples are Gamma isotopic
! analysis of edible
! sealed in a plastic j bag or jar and frozen portion on collection.
l semi-annually or when in season.
j!
3 Sediment A sediment sample is Gamma isotopic
! taken semi-annually. analysis j
semi-annually.
4 Gamma dose quarterly j
{ Direct 2 TLD's will be collected from each j
- location quarterly.
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2 Hope Creek ODCM Rev 14 i
1 i
SAMPLE COLLECTION AND ANALYSIS (Cont'd) j i
i Analysis
~
Samole gpliection Method Milk Sample of fresh milk Gamma isotopic ,
is collected for each analysis and I-131 l 1 farm semi-monthly when analysis on each cows are in pasture, sample on collection.
i monthly at other times.
Water (Rain, Sample to be collected Gamma isotopic
- Potable, monthly providing winter monthly H-3 on Surface) icing conditions allow. quarterly surface 1
sample, monthly on
' ground water sample.
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o Hope Creek ODCM Rev 14 1
FIGURE E-2 2
ONSITE SAMPLING LOCATIONS l
l 4
1 I
16 g
SITE ExCLUS y
! AREA BOU l
901M l
I ~ MINIMUM EXCLUSION AREA BOUNDA HOPE CREEK M
1 14 e l w 4 4 > ,
E NORT NT
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i C3 NERAT STA j
M M ExcLus!
]g AREA BOUND t
(901 METE ) 6 RE R ER l
DELA
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