ML20217H995
| ML20217H995 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 12/31/1997 |
| From: | Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML20217H988 | List: |
| References | |
| HCGS-RERR-20, NUDOCS 9804300149 | |
| Download: ML20217H995 (83) | |
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l HOPE CREEK GENERATING STATION 1
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l i
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HCGS RERR-20 DOCKET NO. 50-354 OPERATING LICENSE NO. NPF-057 i
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HOPE CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
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HCGS RERR-20 DOCKET NO. 50-354
{ OPERATING LICENSE NO. NPF-057 1
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April 1998
1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION l
l RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY- DECEMBER 1997 Table of Contents I INTRODUCTION 4 PART A. PRELIMINARY SUPPLEMENTAL INFORMATION 5 1.0 REGULATORY LIMITS 5 1.1 Fission and Activation Gas Release Limits 5 1.2 lodine, Particulates, and Tritium 5 1.3 Liquid Effluents Release Limits 6 1.4 Total Dose Limit 6 2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) 6 l
3.0 AVERAGE ENERGY 7 l
4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 7 4.1 Liquid Effluents ._ 7 4.2 Gaseous Effluents 7 1
4.3 Estimated Total Error 8 5.0 BATCH RELEASES 8 l
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1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT PART A. PRELIMINARY SUPPLEMENTAL INFORMATION (Cont'd) 6.0 UNPLANNED / ABNORMAL RELEASES 8 7.0 ELEVATED RADIATION MONITOR RESPONSES 8 8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT l RELEASE REPORTS 9 PART B. GASEOUS EFFLUENTS 9 PART C. LIQUID EFFLUENTS 9 PART D. SOLID WASTE 9 PART E. RADIOLOGICAL IMPACT ON MAN 10 l
Liquid Pathways 10 Air Pathways 10 Direct Radiation 11 Assessment 13 Trends 14 PART F. METEOROLOGICAL DATA 15 PART G. OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES 15 PART H. INOPERABLE MONITORS 15 PART l. PROCESS CONTROL PROGRAM (PCP) CHANGES 15 PART J. ENVIRONMENTAL MONITORING LOCATION CHANGES 15 <
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1997 HCGS RADIOACTIVE EFFLUENTC RELEASE REPORT TABLES !
l TABLE 1 A - GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 16 i
, TABLE 1B - GASEOUS EFFLUENTS - ELEVATED RELEASES 18 l
r TABLE 1C - GASEOUS EFFLUENTS - GROUND LEVEL RELEASES 19 l
TABLE 2A - LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 21 l TABLE 28 - LIQUID EFFLUENTS 23 TABLE 3 - SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 25 TABLE 4A -
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE - GASEOUS 27 TABLE 4B -
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE - LIQUID 31 APPENDIX A - METEOROLOGICAL DATA i
APPENDIX B - MPC DATA (ODCM APPENDIX F) 3
1997 HCOS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION l
. RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 1997 INTRODUCTION This report, HCGS-RERR-20 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 1,1997 to December 31,1997. l The Hope Creek Generating Station (HCGS) employs a General Electric (GE) Boiling Water Reactor designed to operaie at a rated core thermal power of 3293 MWt with a gross electrical output of approximately 1118 MWe and a net output of approximately 1 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 "SupplementalInformation" section of Regulatory Guide 1.21, Appendix B, are included in the following pa0es. ]
1 As required by Regulatory Guide 1.21, the Hope Creek Technical 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 6,714,230 megawatt-hours of electrical energy (net) during the reporting period.
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1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT
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PART A. PRELIMINARY SUPPLEMENTAL INFORMATION 1.0 REGULATORY LIMITS 1.1 Fission and Activation Gas Release Limits The dose rate due to radioactive materials released in gaseous effluents from the site (i.e. Salem Units 1 & 2, and Hope Creek) to areas at and beyond the site boundary,
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For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin.
In addition, the air dose due to noble gases released in gaseous effluents from each reactor unit (i.e. Hope Creek) 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 lodine, Particulates, and Tritium 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:
i For iodine-131, iodine -133, for tritium and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
{ In addition, the dose to a member of the public from iodine-131, iodine-133, tntium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents 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 mrems to any organ and, During any calendar year Less than or equal to 15 mrems % any organ.
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l 1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT 1.3 Liquid Emuents Release Limits The concentration of radioactive material released in liquid eMuents to unrestricted areas _
shall be limited to the concentrations specified in 10CFR20, Appendix B, Table 11 Column 2 -
for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained j noble gases, the concentration shall be limited to 2E-04 microcuries per milliliter.
In addition, the dose or dose commitment to a member of the public from radioactive matenals in liquid eMuents released to unrestricted areas shall be limited to:
During any calendar quarter: Less than or. equal to 1.5 mrems to the total body, and less than or equal to 5 mrems to any organ, and i During any calendar year: Less than or equal to 3 mrems to the total l
body, and less than or equal to 10 mrems to any organ.
1.4 Total Dose Limit j The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be
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limited to less than or equal to 25 mrems to the total body or any organ (except the j thyroid, which shall be limited to less than or equal to 75 mrems).
l 2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)
Regulatory Guide 1.21 requires that the licensee provide the MPC's used in determining allowable release rates or concentrations for radioactive releases.
- a. MPC values are not used forgaseous releases. Determination of maximum release rates for noble gases,1-131,1-133, tntium, and for all radionuclides in particulate form (with half-lives > 8 days), are based on dose rate calculations as specified in the ODCM.
- b. According to current Technical Specifications, MPC values as stated in 10CFR20, Appendix B, Table ll, Column 2 is to be used for liquid effluents. Since the MPC values were removed from 10CFR20 effective 1/1/94, the MPC values are now contained in the ODCM. These MPC values are added as Appendix B of this report.
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- c. The MPC value used for dissolved or entrained noble gases in liquid eMuents is 2E-04 microcuries per milliliter.
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1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT 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 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 4.1 Liquid Effluents
{ Liquid effluents 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 sample tanks, floor drain sample tanks, detergent drain tanks, and the condensate storage tank. Normally, there are no continuous liquid releases. Specific activities from the 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 4.11.1.1.1-1 of the Technical 90ecifications are achieved or exceeded. Radionuclides measured at concentrations below the Technical Specification detection limit (LLD) are treated as being present.
Radionuclides for which no activity was detected while meeting the required LLD's are treated as absent.
4.2 Gaseous Effluents Gaseous effluent 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. The NPV and SPV are continuously monitored for iodine, particulates and noble gases These monitors have moving particulate and fixed charcoal filters; The particulate filters and charcoal cartridges are replaced and analyzed weekly. These analyses are performed on a multichannel analyzer. The NPV and SPV are also sampled weekly for noble gases and tritium.
A small quantity of gaseous effluent is released via the Filtration, Recirculation, and Ventilation System (FRVS) vent during testing periods. The FRVS is continuously
- monitored for noble gases when in service, and has fixed particulate and charcoal filters. When the t stem is in vent mode for greater than two hours, sampies are collected at the end of the release period. During peh6ds of extended runs, samples are taken weekly.
The detection requirements of Tables 4.11.2.1.21 of the Technical Specifications are achieved or exceeded. Radionuclides detected at concentrations below the Technical
' Specification detection limit (LLD) are treated as being present. Radionuclides for which no activity was detected while meeting the required LLDs are treated as absent.
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1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT When weekly Noble Gas grab samples yield no detectable activity, continuous mode releases are quantified by integrating Radiation Monitor System readings, and applying a 95% Cntical Level Test. Noble gas isotopic abundances for these integrations are based on the ANSI N237-1976/ANS-18.1 mix for BWRs. Doses calculated from this data employ the methods described in the Hope Creek ODCM.
Batch Mode gaseous releases (i.e. primary containment purge) are quantified by pre-release sampling and isotopic analysis. Specific activities for each isotope are multiplied by twice the containment volume in order to estimate the total radioactivity released.
4.3 Estimated Total Error The estimated total error of reported liquid and solid releases is within 25%.
The estimated total error of the reported continuous gaseous releases is within 50%
when concentrations 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.
5.0 BATCH RELEASES Summaries of batch releases of gaseous and liquid effluents are provided in Tables 4A and 4B.
6.0 UNPLANNED / ABNORMAL RELEASES During this reporting period there were no unplanned releases.
7.0 ELEVATED RADIATION MONITOR RESPONSES During this reporting period, there were no alarm conditions.
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I 1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT 8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS There were no modifications to previous Radioactive Effluent Release Reports during this reporting period.
PART B. GASEOUS EFFLUENTS l See Summary Tables 1A through 1C.
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! PART C. LIQUID EFFLUENTS See Summary Tables 2A through 28.
PART D. SOLID WASTE See Summary in Table 3.
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1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT I
l PART E. RADIOLOGICAL IMPACT ON MAN The calculated individual doses in this section are based on the controlling dose pathways and age groups as described below. The estimated dose represents the ,
i maximum radiation dose that could be received by a member of the general public.
! The population dose impact is based on historical site-specific data (i.e., food i production, milk production, feed for milk animals and seafood production). {
The doses were calculated using methods desenbed in Regulatory Guide 1.109 and represent calculations for the 12-month reporting interval. Individual doses from batch and continuous releases were calculated using the annual average historic ;
meteorological dispersion coefficients as described in the Offsite Dose Calculation i Manual. Population doses were calculated using the meteorological dispersion coefficients for the twelve month reporting interval.
Liquid Pathways l Tvoe Aae Group Location Pathway j' Total Body Adult Site Boundary Seafood Ingestion Organ Adult Site Boundary Seafood Ingestion l l Type Dose Limit Total Body 1.68E-02 mrem 3 mrem i Organ Dose (Bone) 8.53E-02 mrem 10 mrem l Population (Total) 2.19E-01 person-rem N/A Population (Average) 4.87E-05 mrem N/A
! Air Pathways
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Tvoe Aae Group Location Pathway Total Body All Site Boundary Direct Exposure l Skin All Site Boundary Direct Exposure j Organ Infant 4.9 mi. W. Milk, Ground Plane, l Inhalation t
i Tvoe .Qost Limit Total Body 1.37E-02 mrem 500 mrem /yr Skin 2.98E-02 mrem 3000 mrem /yr Organ Dose (Thyroid) 8.32E-03 mrem 15 mrem Population (Total) 7.57E-02 person-rem N/A Population (Average) 1.68E-05 mrem N/A 10 l
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1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT l
Direct Radiation Direct radiation may be estimated by thermoluminescent dosimetnc (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 i
i both the Salem and Hope Creek Generating Stations at Artificial Island, and natural background radiation.
l TLD data for the twelve-month reporting period is given below:
TLD Location Measurement 2S-2 0.4 mi. NNE 4.1 mrad / month SS-1 1.0 mi. E , 3.5 mrad / month l These values are interpreted to represent natural background, since the values are l' 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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Total Dose 40CFR190 limits the total dose to members of the public due to radioactivity and radiation from uranium fuel cycle sources to:
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<25 mrem total body or any organ and;
<75 mrem thyroid for a calendar year.
For Artificial Island, the major sources of dose are from liquid and gaseous effluents from the Hope Creek and Salem plants.
The following doses to a hypothetical maximum exposed individual"have been calculated for the twelve-month reporting period. They are the sum of gaseous and liquid pathway doses for the Salem 1 and 2 and Hope Creek plants:
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2.20E-01 mrem Total Body j 3.82E-01 mrem Organ (Liver) 1.09E-02 mrem Thyroid 1
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1997 HCCS RADIOACTIVE EFFLUENTS RELEASE REPORT Dose to members of the public due to activities inside the site boundary.
l Members of the Public that spend the most time at the NBU for 1997 are various food l vendors, who arrive early in the moming, spending several hours in from of the Processing Center. At approximately 10:00, they move to the front of the Secunty l Center, where they remain until after lunch. In accordance with the requirements of t
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:
l a. The food vendors deliver Monday through Friday,
- b. They arrive at approximately 6:00 A.M. in front of the Processing Center,
- c. The food vendors change position at approximately 10:00 A.M. to the Security Center.
- d. The food vendors leave the site at 1:00 P.M.
- e. No deliveries are made on major holidays, making the total weeks equal 50 4 for the year.
- f. The dose data is based on the average of two TLDs, CA-8 to north of the Security Center, and CA-16, located in the Security administration office.
! g. For time periods where there is either zero dose or no data, no averaging l was performed.
For the 12-month reporting period, January 1,1997 to December 31,1997 the calculated doses are:
3.06 mrem Total Body !
! 2.93E-04 mrem Organ (Lung) l 1.06E-04 mrem Thyroid )
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1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT I Assessment
- 1. Gaseous:
I Gaseous effluents released from Hope Creek resulted in a minimal dose to the maximum hypotheticalindividual. The dose for the 12-month period was a small fraction of all applicable limits.
Gaseous effluents decreased slightly from the previous reporting period. Gaseous effluent releases continue to remain well within Federallimits and are comparable to other nuclear utilities. Fuel integnty and gaseous effluent processing equipment l continue to be maintained in order to ensure that all releases of gaseous E radioactivity are As-Low-As-Reasonably-Achievable (ALARA).
- 2. Liquids:
I Liquid effluents released from Hope Creek station resulted in a minimal dose to the maximusil hypothetical individual and were well within all applicable limits.
The amount of radioactivity in liquid effluents decreased from previous reporting I periods due to programmatic efforts to minimize in-leakage to the liquid radwaste processing system.
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1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT Trends The following two trend graphs show the total curies of gaseous and liquid effluents released for Hope Creek from 1992 through 1997. Calculated doses in the graphs
, are to the maximum hypotheticalindividual.
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l Liquid Releases 1 1 Fission and Activation Curies Released and Calculated Doses 2n- 10
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Gaseous Releases I
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1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT PART F. METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmospheric stability class at the 300 foot elevation are provided for 1997 at the end of this report in Appendix B.
PART G. OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES
( During this period, there was no revision of the HCGS Off-site Dose Calculation Manual.
PART H. INOPERABLE MONITORS r During this period the following effluent monitor was inoperable for greater than 30 L days:
Cooling Tower Blowdown Flow Monitor (1 DAFT-2461)
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The cooling tower blowdown ficw monitor was out of service for 69 days, from 9/14/97 to 11/21/97 due to the cooling tower basin being drained for RFO7.
( Conservative substitution values were used for inputs to the RMS system dunng discharges and compenstory actions were taken while the monitor was out of service.
PARTl. PROCESS CONTROL PROGRAM (PCP) CHANGES During the reporting period, there were no changes to the process control program.
PARTJ. ENVIRONMENTAL MONITORING LOCATION CHANGES During the reporting period, some minor changes were made to the Radioactive Environmental Monitoring Program (REMP). Some analyses not specifically required by the Salem and Hope Creek Technical Specifications were removed from the 1997 REMP. These include: Iodine-131 in well water; strontium analysis in milk, sediment, crab and all but one fish location. A new control location (14G1),
[. was installed and tested for future addition to our environmental monitoring program. A shoreline sediment sampling location (6S2), was added to provide
[L more complete coverage of aquatic sediments. Further details are available in the 1997 REMP report. The changes made did not reduce the objectives or effectiveness of the REMP program.
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l 1997 McGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION i
TABLE 1 A EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY- DECEMBER 1997 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES
- Est.
Total l Units 1" Quarter 2"d Quarter Error' A. Fission and Activation Products
- 1. Total Release Ci 2.414E+00 6.192E+00 50 %
- 2. Average Release Rate For Period pCi/sec 3.104E-01 7.876E-01
- 3. Percent of Technical Specification Limit i (T.S. 3.11.2.2(a)) % 2.29E-02 8.45E 02 i B. lodines
- 1. Total lodine-131 Ci 1.591E-04 2.069E-04 50 %
- 2. Average Release Rate For Period Ci/sec 2.045E-05 2.632E-05
- 3. Percent of Technical Specification Limit' (T.S. 3.11.2.3(a)) %. 3.45E-02 4.20E-02 C. Particulates
- 1. Particulates With Half-j lives > 8 days Ci 1.490E-06 5.233E-05 50%
l ' 2. Average Release Rate For Period Ci/sec 1.916E-07 6.656E-06 I 3. Percent of Technical Specification Limita j (T.S. 3.11.2.3(a)) % 3.45E-02 4.20E-02 1
- 4. Gross Alpha Ci 0.00E+00 0.00E+00 {
D. Tritium L 1. Total Release Ci 6.994E-01 0.00E+00 50 %
! 2. Average Release Rate l For Period Ci/sec 8.994E-02 0.00E+00
- 3. Percent of Technical Specification Limit' (T.S. 3.11.2.3(a)) % 3.45E-02 4.20E-02
- 1. For batch releases, the estimated overall error is 10%. !
- 2. lodines, Tritium, and Particulates are treated as a group.
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I 1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 1 A EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1997 GASEOUS EFFLUENTS- SUMMATION OF ALL RELEASES Est.
Total Units 3" Quarter 4"' Quarter Error' A. Fission and Activation Products
- 1. Total Release Ci 4.109E+00 1.030E+01 50 %
- 2. Average Release Rate For Period Ci/sec 5.170E-01 1.296E+00
- 3. Percent of Technical Specification Limit (T.S. 3.11.2.2(a)) % 3.77E-02 1.41 E-01
- 8. lodines
- 1. Total lodine-131 Ci 1.712E-04 1.700E-06 50 %
- 2. Average Release Rate For Period Ci/sec 2.153E-05 2.139E-07
- 3. Percent of Technical Specification Limit' (T.S. 3.11.2.3(a)) % 3.37E-02 7.68E-04 C. Particulates
- 1. Particulates With Half-lives > 8 days Ci 2.224E-03 2.871E-04 50 %
- 2. Average Release Rate For Period Ci/sec 2.797E-04 3.612E-05
- 3. Percent of Technical Specification Limit2 (T.S. 3.11.2.3(a)) % 3.37E-02 7.68E-04
- 4. Gross Alpha Ci 0.00E+00 0.00E+00 D. Tritium
- 1. Total Release Ci 2.117E+00 3.595E+00 50 %
- 2. Average Release Rate For Period Ci/sec 2.663E-01 4.523E-01
- 3. Percent of Technical Specification Limitz (T.S. 3.11.2.3(a)) % 3.37E-2 7.68E-04
- 1. For batch releases, the estimated overall error is 10%.
- 2. lodines, Tritium, and Particulates are treated as a group.
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1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 1B EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1997 GASEOUS EFFLUENTS - ELEVATED RELEASES Hope Creek Generating Station has no elevated release points.
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l 1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 1C i
EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY- DECEMBER 1997 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Ratch Mode Nuclides Units 1" Quarter 2"" Quarter 1" Quarter 2"d Quartte_r f
- 1. Fission Gases
! Krypton-83m Ci 1.45E-02 6.19E-02 0.00E+00 0.00E+00 Krypton-85m Ci 1.45E-02 6.19E-02 0.00E+00 0.00E+00 l Krypton-87 Ci 5.80E-02 2.48E-01 0.00E+00 0.00E+00 Krypton-88 Ci 5.80E 02 2.48E-01 0.00E+00 0.00E+00 Krypton-89 Ci 3.92E-01 1.67E+00 0.00E+00 0.00E+00 Xenon-133 Ci 2.00E 02 1.24E-01 0.00E+00 0.00E+00 Xenon-135 Cl 1.04E+00 3.10E-01 0.00E+00 0.00E+00 Xenon-135m Ci 8.71E-02 3.71E-01 0.00E+00 0 00E+00 '
Xenon-137 Ci 4.50E-01 1.92E+00 0.00E+00 0.00E+00 Xenon-138 Ci 2.76E-01 1.18E+00 0.00E+00 0.00E+00 l Totals Cl 2.41E+00 6.19E+00 0.00E+00 1
0.00E+00
! 2. lodine lodine-131 Cl 1.59E-04 2.07E-04 0.00E+00 0.00E+00 lodine-133 Cl 1.18E-02 1.24E-02 0.00E+00 0.00E+00 Totals Cl 1.19E-02 1.26E 02 0.00E+00 0.00E+00
- 3. Particulates (Half-life >8 days)
Manganese-54 Ci 1.49E-06 5.23E-05 0.00E+00 0 00E+00 l Totals Cl 1.49E-06 5.23E-05 0.00E+00 0.00E+00 i
- 4. Tritium Cl 6.99E-01 0.00E+00 0.00E+00 0.00E+00 l
i 19 '
l 1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 1C EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY- DECEMBER 1997 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides Units 3'd Quarter 4* Quarter 3 Quarter 4* Quarter Released
- 1. Fission Gases Krypton-83m Ci 2.35E-02 1.03E-01 0.00E+00 0.00E+00 Krypton-85m Ci 2.35E-02 1.03E-01 0.00E+00 0.00E+00 Krypton-87 Ci 9.38E-02 4.12E-01 0.00E+00 0.00E+00 Krypton-88 Ci 9.38E-02 4.12E-01 0.00E+00 0.00E+00 Krypton-89 Ci 6.33E-01 2.78E+00 0.00E+00 0.00E+00 Xenon-133 Ci 4.69E-02 2.06E-01 2.66E-04 0.00E+00 Xenon-135 Ci 1.88E+00 5.15E-01 1.95E-04 0.00E+00 Xenon-135m Cl 1.41 E-01 6.18E-01 0.00E+00 0.00E+00 Xenon-137 Ci 7.27E-01 3.19E+00 0.00E+00 0.00E+00 Xenon-138 Ci 4.46E-01 1.96E+00 0.00E+00 0.00E+00 Totals Cl 4.11 E+00 1.03E+01 4.61E-04 0.00E+00
- 2. lodine lodine-131 Ci 1.71 E-04 1.70E-06 0.00E+00 0.00E+00 lodine-133 Ci 9.58E-03 0.00E+00 0.00E+00 0.00E+00 Totals Cl 9.75E-03 1.70E-06 0.00E+00 0.00E+00 !
- 3. Particulates (Half-life >8 days)
Chromium-51 0.00E+00 0.00E+00 1.58E-03 0.00E+00 Manganese 54 5.62E-05 1.66E-04 1.64E-04 1.79E-06 l Cobalt 58 0.00E+00 0.00E+00 2.65E-05 0 00E+00 Iron-59 0.00E+00 4.55E-05 0.00E+00 0 00E+00 Cobalt-60 0.00E+00 7.11E-05 2.43E-05 1 79E-06 Zinc-65 0.00E+00 0.00E+00 1.89E 04 0 00E+00 l
Strontium-89 0.00E+00 0.00E+00 1.04E-06 104E-06 l Ruthenium-103 0.00E+00 0.00E+00 2.24E-05 0 00E+00 l Silver-110m 0.00E+00 0.00E+00 1.55E-04 0 00E+00 ;
Totals Ci 5.62E-05 2.82E-04 3.76E-03 4.63E-06
{
- 4. Tritium Ci 2.12E+00 3.60E+00 l 4.19E-04 1.50E 04 20 l l
4
1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 2A EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY- DECEMBER 1997 LIQUID EFFLUENTS- SUMMATION OF ALL RELEASES i
Est.
Total Units 1 Quarter 2dQuarter Error A. Fission and Activation Products -
- 1. Total Release Ci 2.946E-03 2.680E-02 25%
- 2. Average Release Rate For Period pCl/ml 7.427E-08 1.951E-07
- 3. Percent of Technical Specification Limit (T.S. 3.11.1.2(a)) % 2.20E-02 1.57E-01 B. Tritium
- 1. Total Release Cl 9.922E-01 3.677E+00 25 %
- 2. Average Release Rate For Period pCi/mi 2.502E-05 2.677E-05
- 3. Percent of Technical l Specification Limit l (T.S. 3.11.1.1) % 8.34E-01 8.92E-01 C. Dissolved and Entrained Noble Gases
- 1. Total Release Ci 3.249E-05 2.873E-04 25%
- 2. Average Release Rate For Period pCi/ml- 8.192E-10 2.092E-09
- 3. Percent of Technical
! Specification Limit l (T.S. 3.11.1.1) % 4.10E-04 1.05E-03 D. Gross Alpha Ci 0.00E+00 0.00E+00 25%
E. Volume of Waste Release (Prior to Dilution - Batch l Release) Liters 1.785E+05 6.598E+05 25 %
F. Volume of Dilution Water Used During Entire Period Liters 1.296E+10 1.435E+10 25%
l 21 l
i
- 1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 2A EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY- DECEMBER 1997 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est.
Total !
Units 3'd Quarter 4'h @Mw hw A. Fission and Activation Products
- 1. Total Release Ci 8.271 E-02 1.605E-01 25%
- 2. Average Release Rate For Period pCi/ml 2.758E-07 2.231 E-07
- 3. Percent of Technical Specification Limit (T.S. 3.11.1.2(a)) % 5.09E-0 i 1.02E+00 B. Tritium
- 1. Total Release Ci 2.195E+00 5.494E+00 25%
- 2. Average Release Rate For Period Ci/mi 7.321E-06 7.633E-06
- 3. Percent of Technical Specification Limit (T.S. 3.11.1.1) % 2.44E-01 2.54E-01 C. Dissolved and Entrained Noble Gases
- 1. Total Release Ci 2.884E-05 2.040E-05 25%
- 2. Average Release Rate For Period Ci/ml 9.616E-11 2.835E-11
- 3. Percent of Technical Specification Limit (T.S. 3.11.1.1) % 4.81 E-05 1.42E-05 D. Gross Alpha Ci 0.00E+00 0.00E+00 25%
E. Volume of Waste Release (Prior to Dilution - Batch Release) Liters 1.005E+06 2.587E+06 25%
l F. Volume of Dilution Water L Used During Entire Period Liters 2.029E+10 1.608E+10 25%
22
I 1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT l HOPE CREEK GENERATING STATION l
TABLE 2B EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1997 LIQUID EFFLUENTS Continuous Mode Batch Mode Units 1 Quarter 2"d Quarter 1 Quarter 2"d Quarter Released Fission and
{ Activation Products Chromium-51 Ci 0.00E+00 0.00E+00 9.82E-05 4.10E-03 f Manganese-54 Ci 0.00E+00 0.00E+00 3.48E-04 2.09E-03 Iron-55 Ci 0.00E+00 0.00E+00 2.32E-03 1.91E-02 Cobalt-58 C' O.00E+00 0.00E+00 5.42E-07 1.54E-05 f iron-59 Ci 0.00E+00 0.00E+00 0.00E+00 1.97E-05 Cobalt-60 Ci 0.00E+00 0.00E+00 1.65E-04 1.04E-03 Zinc-65 Ci 0.00E+00 0.00E+00 1.26E-05 1.10E-04
( Zinc-69m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Arsenic-76 Ci 0.00E+00 0.00E+00 0.00E+00 6.165-05 Strontium-89 Cl 0.00E+00 0.00E+00 0.00E+00 0.00E+00 f Molybdenum-99 Ci 0.00E+00 0.00E+00 0.00E+00 9.56E-05 Technetium-99m Ci 0.00E+00 0.00E+00 0.00E+00 1.29E-04 Silver 110m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00
(' Cesium-137 Ci 0.00E+00 0.00E+00 0.00E+00 3.78E-07 Totals Ci 0.00E+00 0.00E+00 2.95E-03 2.68E-02
( 2. Tritium Cl 0.00E+00 0.00E+00 l 9.92E-01 3.68E+00
- 3. Dissolved and Entrained Noble Gases Xenon-133 Ci 0.00E+00 0.00E+00 0.00E+00 3.95E-05 Xenon-135 Ci 0.00E+00 0.00E+00 3.25E-05 2.48E-04 Totals Ci 0.00E+00 0.00E+00 3.25F.-05 2.87E 04 23 e
1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 2B EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY- DECEMBER 1997 LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Units 3'd Quarter 4'" Quarter 3'd Quarter 4'" Quarter Released
- 1. Fission and Activation Products Chromium-51 Ci 0.00E+00 0.00E+00 2.31E-03 9.28E-04 Manganese-54 Ci 0.00E+00 0.00E+00 2.93E-03 1.20E-02 fron-55 Ci 0.00E+00 0.00E+00 6.6*E-02 1.40E-01 Cobalt-58 Ci 0.00E+00 0.00E+00 1.5*E-04 4.18E-04 fron-59 Ci 0.00E+00 0.00E+00 2 04 2.41 E-03 Cobalt-60 Ci 0.00E+00 0.00E+00 1.77E-03 4.07E-03 Zinc-65 Ci 0.00E+00 0.00E+00 3.98E-04 7.68E-04 Zinc-69m Ci 0.00E+00 0.00E+00 1.58E-05 0.00E+00 Arsenic-76 Ci 0.00E+00 0.00E+00 1.54E-05 0.00E+00 Strontium-89 Ci 0.00E+00 0.00E+00 8.56E-03 0.00E+00 Molybdenum-99 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Technetium-99m Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Silver-110m Ci 0.00E+00 0.00E+00 6.60E-06 4.19E-05 Cesium-137 Ci 0.00E+00 0.00E+00 0.00E+00 2.46E-06 Totals Cl 0.00E+00 0.00E+00 8.27E-02 1.61 E-01
- 2. Tritium Cl 0.00E+00 0.00E+00 l 2.20E+00 5.49E+00
- 3. Dissolved and Entrained Noble Gases Xenon-133 Ci 0.00E+00 0.00E+00 5.05E-06 0.00E+00 Xenon-135 Ci 0.00E+00 0.00E+00 2.38E-05 2.04E-05 Totals Ci 0.00E+00 0.00E+00 2.88E-05 2.04E-05 24 2
l 1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION i
TABLE 3 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY- DECEMBER 1997 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated Fuel) 12-Month Est. Total
- 1. Type of Waste Units' Period Error
- a. Spent Resins, Filters, Sludges, m3 0.00E+00 25%
, Evaporator Bottoms Ci 0.00E+00
- b. Dry Compressible Waste, m' 2.929E+04 25%
Contaminated Equipment Ci 4.787E+00
- c. Irradiated Components, m3 0.00E+00 25%
Control Rods Ci 0.00E+00
- d. Others (described) m3 0.00E+00 25%
-Ci 0.00E+00 l 1. Volumes are measured, activities are estimated.
- 2. Estimate of Major Nuclide Composition Resins DAW Nuclides % Ci % Ci Chromium-51 0.00E+00 0.00E+00 1.74 0.08 Manganese-54 0.00E+00 0.00E+00 4.70 0.22 ,
l Iron-55 0.00E+00 0.00E+00 88.28 4.23 l Cobalt-60 0.00E+00 0.00E+00 3.26 0.16 Zinc-65 0.00E+00 0.00E+00 1.19 0.06 l l
l l
l l
l 25 t
t
I i
1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 3 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT l JANUARY - DECEMBER 1997 i SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL
- 3. Solid Waste Disposal Number of Mode of Shloments Transportation Destination Tvoe of Containers 3 Truck Oak Ridge, Tennessee Strong, Tight Containers >
9 Truck Memphis, Tennessee Strong, Tight I Containers f
- 4. Irradiated Fuel Shipments (Disposition) i Mode of - l Number of Shipments Transportation Destination None N/A N/A
)
- 5. Solidification Methods No shipments of Solid Radioactive Waste requiring solidification were made during this period.
26 l
l l
1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 4A EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY- DECEMBER 1997
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY
[
- 1. Dates: January 1,1997 - March 31,1997
- 2. Type of release: Gaseous
- 3. Number of releases during quarter- 0
- 4. Total time duration for all releases of type listed above: 0 Min.
- 5. Maximum duration for release of type listed above: 0 Min.
[ 6. Average duration for release of type listed above: 0 Min.
- 7. Minimum duration for release of type listed above: 0 Min.
- 8. Average stream flow (dilution flow) during period of release: N/A
(
l L
{
27 I
l
1 I
f 1997 HCOS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 4A EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -DECEMBER 1997 j
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED '
IN A BATCH MODE 1
i BATCH RELEASES ONLY 1 Dates: April 1,1997 - June 1,1997
- 2. Type of release: Gaseous
- 3. Number of releases during quarter: 0 i
- 4. Total time duration for all releases of type listed above: 0 Min.
- 5. Maximum duration for release of type listed above: 0 Min.
- 6. Average duration for release of type listed above: 0 Min.
- 7. Minimum duration for release of type listed above: 0 Min.
- 8. Average stream flow (dilution flow) during period of release: N/A 28
1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 4A EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY- DECEMBER 1997
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE 1
i
)
BATCH RELEASES ONLY
- 1. Dates: July 1,1997 - September 30,1997
- 2. Type of release: Gaseous
- 3. Number of releases during quarter: 1
{
- 4. Total time duration for all releases of type listed above: 2836 Min.
- 5. Maximum duration for release of type listed above: 2836 Min.
- 6. Average duration for release of type listed above: 2836 Min. ;
'7. Minimum duration for release of type listed above: 2836. Min,
- 8. Average stream flow (dilution flow) during period of release: N/A 29 i
1997 HOGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 4A EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY- DECEMBER 1997
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY
- 1. Dates: October 1,1997 - December 31,1997
- 2. Type of release: Gaseous 4
- 3. Number of releases dunag quarter: 1
- 4. Total time duration for all releases of type listed above: 388 Min.
- 5. Maximum duration for release of type listed above: 388 Min.
- 6. Average duration for release of type listed above: 388 Min.
- 7. Minimum duration for release of type listed above: 388 Min.
- 8. Average stream flow (dilution flow) during period of release: N/A I
l l
l 30 L
l 1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 48 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1997
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE I
BATCH RELEASES ONLY -
- 1. Dates: January 1,1997 - March 31,1997
- 2. Type of release: Liquid
- 3. Number of releases during quarter: 7
- 4. Total time duration for all releases of type listed above: 423.6 Min.
- 5. Maximum duration for release of type listed above: 82.0 Min.
- 6. Average duration for release of type listed above: 60.5 Min.
- 7. Minimum duration for release of type listed above: 33.95 Min.
- 8. Average stream flow (dilution flow) during period of release: 24989 GPM I
I I
h I
l i .
1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 4B EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1997
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY
- 1. Dates: April 1,1997 - June 1,1997
- 2. Type of release: Liquid
- 3. Number of releases during quarter: 15
- 4. Total time duration for all releases of type listed above: 1261.7 Min, j
- 5. la tximum duration for release of type listed above: 99.0 Min.
- 6. Average duration for release of type listed above: 84.1 Min.
- 7. Minimum duration for release of type listed above: 43.1. Min. I 8, ' Average stream flow (dilution flow) during period of release: 28638 GPM 1
32 l
I l 1997 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 4B EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1997
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED l IN A BATCH MODE i
BATCH RELEASES ONLY l
i
- 1. Dates: July 1,1997 - September 30,1997
- 2. Type of release: Liquid
- 3. Number of releases during quarter: 37
- 4. Total time duration for all releases of type listed above: 2363.8 Min.
- 5. Maximum duration for release of type listed above: 92.8 Min.
- 6. Average duration for release of type listed above: 63.9 Min.
- 7. Minimum duration for release of type listed above: 27.1 Min.
- 8. Average stream flow (dilution flow) during period of release: 33885 GPM l
l l
33 I
1997 HCOS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 4B EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY- DECEMBER 1997
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE
.i BATCH RELEASES ONLY
- 1. Dates: October 1,1997 - December 31,1997
- 2. Type of release: Liquid
- 3. Number of releases during quarter: 81
- 4. Total time duration for all releases of type listed above: 5656.4 Min.
- 5. Maximum duration for release of type listed above: 92.2 Min.
- 6. Average duration for release of type listed above: 69.8 Min.
- 7. Minimum duration for release of type listed above: 25.0 Min.
- 8. . Average stream flow (dilution flow) during period of release: 33525 GPM 1
34 l
i l
{
APPENDIX A i
METEOROLOGICAL DATA I
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APPENDIX B MPC DATA (HCGS ODCM;
Hope Creek ODCM Rev 15 APPENDIX F MAXIMUM PERMISSIBLE CONCENTRATIONS LIQUID EFFLUENTS
, F-1
Hope Creek ODCM Rev 15 The following radionuclide concentrations were obtained from 10 CFR 20 Apperi:x B, Table II, Column 2 as revised January 1,1991.
Table F-1 Maximum Permissible Concentrations Element Isotope Soluble Cone Insoluble Conc.
(uci/ml) (uci/ml)
Actinium (89) Ac-227 2E-6 3E-4 Ac-228 9E-5 9E-5 Americium (95) Am-241 4E-6 3E-5 Am-242m 4E-6 9E-5 Am-242 IE-4 IE-4 Am-243 4E-6 3E-5 Am-244 SE-3 SE-3 Antimony (51) Sb-122 3E-5 3E-5 Sb-124 2E-5 2E-5 Sb-125 1E-4 IE-4 ,
Arsenic (33) As-73 5E-4 SE-4 As-74 SE-5 5E-5 As-76 2E-5 2E-5 As-77 8E-5 8E-5 Astatine (85) At-211 2E-6 7E-5 Barium (56) Ba-131 2E-4 2E-4 Ba-140 3E-5 2E-5 Berkelium (97) Bk-249 6E-4 6E-4 Bk-250 2E-4 2E-4 Beryllium (4) Be-7 2E-3 2E-3 Bismuth (83) Bi-206 4E-5 4E-5 Bi-207 6E-5 6E-5 Bi-210 4E-5 4E-5 Bi-212 4E4 4E-4 Bromine (35) Br-82 3E-4 4E-5 Cadmium (48) Cd-109 -
2E-4 2E-4 Cd-ll5m 3E-5 3E-5 Cd-ll5 3E-5 4E-5
,p%
~
,20) Ca-45 9E 6 2E-4 Ca-47 5E-5 3E-5 F-2
Hope Creek ODCM Rev 15 Table F-1 (Continued)
Element Isotope Soluble Conc. Insoluble Conc.
(uci/ml) (uci/ml)
Californium (98) Cf-249 4E-6 2E-5 Cf-250 lE-5 3E-5 Cf-251 4E-6 3E-5 Cf-252 7E-6 7E-6 Cf-253 1E-4 1E-4 Cf-254 IE-7
{ IE-7 Carbon (6) C-14 8E-4 ------
Cerium (58) Ce-141 ,
9E-5 9E-5 Ce-143 4E-5 4E-5 Ce-144 1E-5 1E-5 Cesium (55) Cs-131 2E-3 9E-4 Cs-134m 6E-3 1E-3 Cs-134 9E-6 4E-5 Cs-135 IE-4 2E-4 Cs-136 9E-5 6E-5 Cs-137 2E-5 4E-5 Chlorine (17) Cl-36 88-5 6E-5 Cl-38 4E-4 4E-4 Chromium (24) Cr-51 2E-3 2E-3
( Cobalt (27) Co-57 5E-4 4E-4 Co-58m 1E-3 2E-3 Co-58 12-4 9E-5
[' Co-60 SE-5 3E-5 Copper (29) Cu-64 3E-4 2E-4 Curium (96) Cm-242 2E-5 2E-5 Cm-243 5E-6 2E-5 Cm-244 '/E-6 3E-5 Cm-245 4E-6 3E-5 Cm-246 4E-6 3E-5 Cm-247 4E-6 2E-5 Cm-248 4E-7 IE-6 Cm-249 2E-3 2E-3 Dysprosium (66) Dy-165 4E-4 4E-4 Dy-166 4E-5 4E-5 F-3 e
l l
Hope Creek ODCM Rev 15 Table F-1 (Continued)
Element Isotope Soluble Conc. Insoluble Conc.
p (uci/ml) (uci/ml)
Dysprosium (66) I-135 4E-6 7E-5 Iridium (77) Ir-190 2E-4 2E-4 Ir-192 4E-5 4E-5 Ir-194 3E-5 3E-5 Iron (26) Fe-55 8E-4 2E-3 Fe-59 6E-5 5E-5 Lanthanum (57) La-140 2E-5 i Einsteinium (99) Es-253 2E-5 -
2E-5 2E-5 Es-254m 2E-5 2E-5 Es-254 1E-5 I Es-255 3E-5 3E-5 1E-5 Erbium (68) Er-169 9E-5 9E-5 Er-171 lE-4 1E-4 Europium (63) Eu-l52 (9.2 hrs) 6E-5 6E-5 g Eu-152 (13 yrs) 8E-5 8E-5 l Eu-154 2E-5 2E-5 Eu-155 2E-4 2E-4 Fermium (100) Fm-254 1E-4 1E-4 Fm-255 3E-5 3E-5 Fm-256 9E-7 9E-7 Fluorine (9) F-18 l Gd-l53 SE-4 SE-4 Gadolinium (64) 2E-4 2E-4 Gd-159 8E-5 8E-5 Gallium (31) Ga-72 4E-5 4E-5 Germanium (32) Ge-71 2E-3 2E-3 Gold (79) Au-196 2E-4 1E-4 Au-198 SE-5 S E .,
I Au-199 2E-4 2E-4 Hafnium (72) Hf-l81 7E-5 7E-5 Holmium (67) Ho-166 3E-5 3E-5 Hydrogen (3) H-3 3E-3 3E-3 Indium (49) In-113m 1E-3 1E-3 l In-114m 2E-5 2E-5 In-11Sm 4E-4 4E-4 I In-ll 5 9E-5 PE-5 k
F-4 t .
Hope Creek ODCM Rev 15 Table F-1 (Continued)
Element Isotope Soluble Conc. Insoluble Conc.
(uci/ml) (uci/ml)
Iodine (53) I-125 2E 7 2E-4 I-126 3E-7 9E-5
( I-129 6E-8 2E-4 l I-131 3E-7 6E-5 I-132 8E-6 2E-4 I-133 IE-6
( I-134 2E-5 4E-5 6E-4 Lead (82) Pb-203 4E-4 4E-4 Pb-210 lE-7 2E-4 Pb-212 2E-5 2E-5 Lutetium (71) Lu-177 1E-4 1E-4 Manganese (25) Mn-52 3E-5 3E-5 Mn-54 1E-4 1E-4 Mn-56 1E-4 1E-4 Mercury (80) Hg-197m 2E-4 2E-4 Hg-197 3E-4 SE-4 Hg-203 2E-5 IE-4 Molybdenum (42) Mo-99 2E-4 4E-5 Neodymium (60) Nd-144 7E-5 8E-5 Nd-147 6E-5 6E-5 Nd-149 3E-4 3E-4 j Neptunium (93) Np-237 3E-6 3E-5 l Np-239 1E-4 1E-4 Nickel (28) Ni-59 2E-4 2E-3 Ni-63 3E-5 7E-4 Ni-65 1E-4 1E-4 Niobium (41) Nb-93m 4E-4 4E-4 Nb-95 1E-4 1E-4 Nb-97 9E-4 9E-4 Osmium (76) Os-185 7E-5 7E-5 Os-191m 3E-3 2E-3 Os-191 2E-4 2E-4 Os-193 6E-5 SE-5 Palladium (46) Pd-103 3E-4 3E-4 Pd-109 9E-5 '7E-5 F-5
. .1 .. .
Hope Creek ODCM Rev 15 Table F-1 (Continued)
Element Isotope Soluble Conc. Insoluble Conc.
(uci/ml) (uci/ml)
Phosphorus (15) P-32 2E-5 2E-5 Platinum (78) Pt-191 1 E-4 ,, 1E-4 Pt-193m 1E-3 1E-3 Pt-193 9E-4 2E-3 Pt-197m 1E-3 9E-4 Pt-197 1E-4 1E-4 Plutonium (94) Pu-238 SE-6 3E-5 Pu-239 SE-6 3E-5 Pu-240 SE-6 3E-5 Pu-241 2E-4 1E-3 Pu-242 SE-6 3E-5 Pu-243 3E-4 3E-4 Polonium (84) Po-210 7E-7 3E-5 Potassium (19) K-42 3E-4 2E-5 Praseodymium (59) Pr-142 3E-5 3E-5 Pr-143 SE-5 SE-5 Promethium (6I) Pm-147 2E-4 2E-4 Pm-149 4E-5 4E-5 Protactinium (91) Pa-230 2E-4 2E-4 Pa-231 9E-7 2E-5 Pa-233 1E-4 1E-4 Radium (88) Ra-223 7E-7 4E-6 Ra-224 2E-6 SE-6 Ra-226 3E-8 3E-5 Ra-228 3E-8 3E-5
{
Rhenium (75) Re-183 6E-4 3E-4 Re-186 9E-5 SE-5 Re-187 3E-3 2E-3 Re-188 6E-5 3E-5 Rhodium (45) Rh-103m 1E-2 1E-2 Rh-105 1E-4 1E-4 Rubidium (37) Rb-86 7E-5 2E-5 Rb-87 1E-4 2E-4 Ruthenium (44) Ru-97 4E-4 3E-4 Ru-103 8E-5 8E-5 r
F-6
[.
i 1 l i l
Hope Creek ODCM Rev 15 l
l Table F-1 (Continued) !
i Element Isotope Soluble Conc. Insoluble Conc. !
(uci/ml) (uci/ml) !
! Ru-105 1E-4 1E-4 Ru-106 l E-5 IE 5 Samarium (62) Sm-147 6E-5 7E-5 l'
Sm-151 4E4 4E4 Sm-153 8E-5 8E-5 Scandium (21) Sc-46 4E-5 4E-5 Sc-47 9E-5 9E-5 Sc-48 l 3E-5 3E-5 '
Selenium (34) Se-75 3E-4 3E-4 Silicon (14) Si-31 9E-4 2E-4 l Silver (47) Ag-105 1E-4 1E-4 l
Ag-110m 3E-5 3E-5 Ag-111 4E-5 4E-5 Sodium (l1) ,
_ j Na-24 2E-4 3E-5 l l Strontium (38) Sr-85m 7E-3 7E-3 Sr-85 1E-4 2E4 Sr-89 3E-6 3E-5 Sr-90 3E-7 4E-5 ;
Sr-91 7E-5 5E-5 Sr-92 7E-5 6E-5 Sulfur (16) - S-35 6E-5 3E-4 Tantalum (73) Ta-182 4E-5 4E-5 Technetium (43) Tc-96m 1E-2 lE-2 Tc-96 IE-4 SE-5 Tc-97m 4E-4 2E-4 Tc-97 2E-3 8E.4 Tc-99m 6E-3 3E-3 Tc-99 3E-4 2E4 Tellurium (52) Te-125m 2E-4 1E-4 Te-127m 6E-5 SE-5 re-127 3E-4 2E-4 Te-129m 3E-5 2E-5 Te-129 8E-4 8E-4 Te 131m l6E-5 4E-5 F-7
Hope Creek ODCM Rev 15 Table F-1 (Continued)
Element Isotope Soluble Conc. Insoluble Conc.
(uci/ml) (uci/ml)
Te-132 3E-5 2E-5 Terbium (65) Tb-160 4E-5 4E-5 Thallium (81) TI-200 4E-4 2E-4 TI-201 3E-4 2E-4 TI-202 1E-4 7E-5 TI-204 IE-4 6E-5 Thorium (90) Th-227 2E-5 2E-5 Th-228 7E-6 1E-5 Th-230 2E-6 3E-5 Th-231 2E-4 2E-4 Th-232 2E-6 4E-5 Th-natural 2E-6 2E-5 Th-234 2E-5 2E-5 Thulium (69) Tm-170 SE-5 SE-5 Tm-171 SE-4 SE-4 Tin (50) Sn-113 9E-5 BE-5 Sn-124 2E-5 2E-5 Tungsten (74) W-181 4E-4 3E-4 W-185 IE-4 1E-4 W-187 7E-5 6E-5
- i. Uranium (92) U-230 SE-6 SE-6 l U-232 3E-5 3E-5 U-233 3E-5 3E-5 U-234 3E-5 3E-5 U-235 3E-5 3E-5 U-236 3E-5 3E-5 U-238 4E-5 4E-5 U-240 3E-5 3E-5 U-natural 3E-5 3E-5 Vanadium (23) V-48 3E-5 3E-5 Ytterbium (70) Yb-175 1E-4 1E-4 F-8
I Hope Creek ODCM Rev 15 Table F-1 (Continued)
Element Isotope Soluble Conc. Insoluble Conc.
(uci/ml) (uci/ml)
Yttrium Y-90 2E-5 2E-5 Y-91m 3E-3 3 E-3 Y-91 3E-5 3 E-5 Y-92 6E-5 6E-5 Y-93 3E-5 3E-5 Zine (30) Zn-65 IE-4 2E-4 Zn.69m 7E-5 ~ 6E-5 Zn-69 2E-3 2E-3 Zirconium (40) Zr-93 8E-4 8E-4 Zr-95 6E-5 6E-5 Zr-97 2E-5 2E-5 Any single radio- 3E-6 3E-6 nuclide not listed above with decay mode other than alpha emission or spontaneous Sssion and with radio -
active half-life greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Any single radio- 3E-8 3E-8 nuclide not listed above, which decays by alpha emission or spontaneous Sssion.
Notes:
- 1. If the identity of any radionuclide is not known. the limiting values for purposes of this
. table shall be: 3E-8 uci/ml.
- 2. If the identity and concentration ofeach radionuclide are known, the limiting values should be derived as follows: Determine, for each radionuclide in the mixture, the ratio between the quantity present in the mixture and the limit otherwise established in Appendix B for the speci6c radionuclide not in a mixture. The sum of such ratios for all the radionuclides in the mixture may not exceed "1" (i.e. " unity").
I F-9