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Annual Radioactive Effluent Release Rept for 1998. with
	ML20206D407
Person / Time
Site:	Hope Creek
Issue date:	12/31/1998
From:	Dawn Powell; Public Service Enterprise Group
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	LR-N99180, NUDOCS 9905040097
	Download: ML20206D407 (220)
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J PSEG Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit APR271999 LR-N99180 United States Nuclear Regulatory Commission

~ Document Control Desk Washington, DC 20555 RADIOACTIVE EFFLUENT RELEASE REPORT - 21 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 Gentlemen:

In accordance with Section 6.9.1.7 of Appendix A to the Operating License for Hope Creek Generating Station, Public Service Electric and Gas Company hereby transmits ,

one copy of the annual Radioactive Effluent Release Report, RERR-21. This report summarizes liquid and gaseous releases and solid waste shipments from the Hope i Creek Generating Stationjfor the period of January 1,1998 through December 31, 1998.

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Should you have any quptions regarding this transmittal, please feel free to contact us. <

1 Sincerely, kh2 &

David R. Powell Director Licensing / Regulation & Fuels l

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- Document Control Desk LR-N99180 ALL WITH ATTACHMENT: l l

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C Mr. H. Miller, Administrator - Region l l U. S. Nuclear Regulatory Commission 1 475 Allendale Road

. King of Prussia, PA 19406 Mr. R. Ennis, Licensing Project Manager - HC U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 881 l 11555 Rockville Pike Rockville, MD 20852 USNRC Senior Resident inspector (X24)

Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P. O. Box 415 Trenton, NJ 08625;

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HOPE CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HCGS RERR-21 DOCKET NO. 50-354 OPERATING LICENSE NO. NPF-057 l l

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April 1999 l

1998 HCOS RADIOACTIVE EFFLUENTS RELEASE REPORT

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HOPE CREEK GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY- DECEMBER 1998 Table of Co'ntents IN'TRODUCTION 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 3.0 AVERAGE ENERGY 7 4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 7 4.1 Liquid Effluents 7 4.2 Gaseous Effluents 7 4.3 Estimated Total Error 8 l

5.0 BATCH RELEASES 8 1

1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT 6.0 UNPLANNEDIABNORMAL RELEASES 9 7.0 ELEVATED RADIATION MONITOR RESPONSES 10

! 8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS 11 PART B. GASEOUS EFFLUENTS 11 PART C. LIQUID EFFLUENTS 11

PART D. SOLID WASTE 11 l

PART E. RADIOLOGICAL IMPACT ON MAN 12 Liquid Pathways 12 I

Air Pathways 12 Direct Radiation 13 Total Dose 13 Dose to members of the public due to activities inside the site boundary 14 Assessment 15 Trends 16 PART F. METEOROLOGICAL DATA 17 PART G. OFFSITE DOSE CALCULATION MANUAL (ODCM)

CHANGES 17 PART H. INOPERABLE MONITORS 18 PART l. PROCESS CONTROL PROGRAM (PCP) CHANGES 18

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PART J. ENVIRONMENTAL MONITORING LOCATION CHANGES 18 2

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i 1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT TABLE 1 A - GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 19 TABLE 1B - GASEOUS EFFLUENTS - ELEVATED RELEASES 21 TABLE 1C - GA.SEOUS EFFLUENTS - GROUND LEVEL RELEASES 22 l

l TABLE 2A - LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 24 TABLE 28 - LIQUID EFFLUENTS 26 l TABLE 3 - SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 28 j TABLE 4A -

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A SATCH MODE -GASEOUS 31 TABLE 48 -

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE - LIQUID 35 APPENDIX A - METEOROLOGICAL DATA j APPENDIX B - MPC DATA ,

J APPENDIX C - OFFSITE DOSE CALCULATION MANUAL, REVISION 16 1

APPENDIX D - OFFSITE DOSE CALCULATION MANUAL, REVISION 17 1

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1998 HCOS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 1998 INTRODUCTION This report, HCGS-RERR-21 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 1,1998 to December 31,1998.

The Hope Creek Generating Station (HCGS) employs a General Electric (GE) Boiling Water Reactor designed to operate at a rated core thermal power of 3293 MWt with a gross electrical output of approximately 1118 MWe and a net output of approximately 1067 MWe. The HCGS achieved initial criticelity 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 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 ctmpliance with 40CFR190 requirements, the following information on electrical output is provided.

Hope Creek generated 8,700,389 megawatt-hours of electrical energy (net) during the reporting period.

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1998 HCCS RADIOACTIVE EFFLUENTS RELEASE REPORT PART A. PRELIMINARY SUPPLEMENTAL INFORMATION 1.0 REGULATORY LIMITS 1.1 Fission and Abtivation 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, shall be limited to the following:

For noble gases: Less than or equal to 500 mrems/yr to the total body ars 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:

l During any calendar quarter: Less than or equal to 5 mrad for gamma f 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 racliation.

1.2 lodine, Particulates, and Tritium The dose rate due to radioactive materials releasedin gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to the following:

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, tritium, 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 to i.ny organ.

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1998 HCOS RADIOACTIVE EFFLUENTS RELEASE REPORT l

1.3 Liquid Effluents Release Limits The concentration of radioactive material releasedin liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10CFR20, Appendix B, Tabic II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained l noble gases, the concentration shall be limited to 2E-04 microcuries per milliliter. ;

1 In addition, the dose or dose commitment to a member of the public from iadioactive I materials in liquid effluents released to unrestricted areas shall be limiteo ,0:

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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 During any calendar year: Less than or equal to 3 mrems to the total body, and less than or equal to 10 mrems to any organ.

I 1.4 Total Dose Limit The annual (calendar year) dose or dose commitment to any member of the public, due 4 to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrems). ,

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2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)

Regulatory Guide 1.21 requires that the licensee provide the MPC's used in determining g allowable release rates or concentrations for radioactive releases. l

a. MPC values are not used for gaseous releases. Determination of ;

maximum release rates for noble gases,1-131,1-133, tritium, and for all radionuclides in particulate form (with half-lives > 8 days), are based on dose rate calculations as specified in the ODCM. l

b. According to current Technical Specifications, MPC values as stated in

) 10CFR20, Appendix B, Table 11, Column 2 is to be used for liquid j 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.

c. The MPC value used for dissolved or entrained noble gasesin liquid effluents is 2E-04 microcuries per milliliter, 9

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1998 HCOS RADIOACTIVE EFFLUENTS RELEASE REPORT 4

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. 1 Release 1imits for HCGS are not based upon average energy. Therefore this section is not j 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. During the report period, a continuous liquid effluent release path was identified through the j circulating water dewatering sump discharge, as described in Section 6.0, Unplanned / Abnormal Releases. Representative samples were obtained in accordance with Table 4.11.1.1.1-1 of the Technical Specifications as described in the Offsite Dose Calculation Manual. 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 Specifications are achieved or exceeded. Radionuclides measured at concentrations below the Technical Specification detection limit (LLD) are treated as being present.

Radionuclides for which no act,ivity 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

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analyses are peiformed on a multichannel analyzer. The NPV and SPV are also l sampled weekly for noble gases and tritium.

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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 system is in vent mode for greater than two hours, samples are collected at the end of the release period. During periods of extended runs, samples j are taken weekly.

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1998 HCCS RADIOACTIVE EFFLUENTS RELEASE REPORT l The detection requirements of Tables 4.11.2.1.2-1 of the Technical Specifications are 4 achieved or exceeded. Radionuclides detected e.t 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.

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% Critical Level Test. Noble gas isctopic 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. prirnary 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.

l 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 induded 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 48. As presented in Table 4A, there was an increase in the number of gaseous effluent batch releases during the third and fourth quarters of 1998. In June 1998, a torus-to-drywell vacuum breaker was identified as cycling partially open and closed.

Since repair was not possible until an outage of sufficient duration, frequent venting of l the suppression chamber through the SPV to the atmosphere was required. The I

releases from the venting operations were controlled under approved weekly discharge permits. The results of these analyses are also included in Tables 1A and 1C. "

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[1 1 1998 HCGS RADIOACTIVE' EFFLUENTS RELEASE REPORT-6.0 UNPLANNED / ABNORMAL RELEASES In September 1998, tritium was identified in a sample from the circulating water dewatering sump (CWDWS). The discharge from this sump is routed to the cooling tower where liquid effluents are released to the environment through the cooling i tower blowdown to the Delaware River. 1 The investigation and results are summarized as follows:

. The source of the tritium in the sump was identified as condensation drains from the -

turbine building supply, the service area supply, and reactor building supply ventilation units.. As already described in the UFSAR, tritium from the reactor coolant and reactor (

! steam leak into the associated room sir. Samples from the room air at the vicinity of the

, affected supply vents confirmed low level tritium in the air. Since the supply ventilation l

units are not completely air tight, room air is drawn into the ventilation units along with normal outside air. Some tritium is condensed in the supply unit chillers. The condensation drains from these supply units are normally directed to the turbine building circulating water dewatering sump. Sampling and analysis confirmed that tritium was present in the condensation drains from each of the reactor building, service area, and turbine building supply ventilation units.

Historical search identified that in September 1988, the condensation drains from the turbine building supply ventilation system were aligned to the circulating water dewatering sump. The drains from the reactor building supply, the service area supply and the technical support center supply ventilation systems were also aligned to the sump in July 1990. The design change packages took credit for monitoring the release path for radioactivity by the radiation monitor, TBCW-RMS (RE-4557). However, this i RMS is a gamma detector and can not detect tritium and other non-gamma I r

radioisotopes. Sampling and analysis requirements for tritium were not specified.

Therefore, tritium has been released through this system since September 1988 without )

monitoring or reporting. J

, Historical results from tritium analysis of composite samples from the cooling tower 1 l blowdown sample station, the final release point *o the Delaware River for liquid effluents J were less than the minimum detectable activity (I ADA). Historical results from Radiological Environmental Monitoring Prograrr. (REMP) sampling and analysis for surface water stations were reviewed and verified to not be different from preoperational .

tritium concentrations, 1

Calculations conservatively estimate that up to 21 Curies of tritium per year could have J l

been released through this unmonitored pathway since the turbine building ventilation

supply system condensation drains were first aligned to the sump in September 1988. 1 I

Using methods provided in the Hope Creek Offsite Dose Calculation Manual with conservative assumptions leads to the conclusion that technical specification limits for effluent concentration and dose could not have been exceeded during the period of potentially unmonitored release. The calculations conservatively estimate that the upper j bound of the dose to the maximum hypotheticalindividual at the site boundary due to the potential unmonitored tritium release was less than 2% of reported dose each year (1.85% in 1997 and less than 1% all other years). Since the estimated dose for previous j 1

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1998 HCOS RADIOACTIVE EFFLUENTS RELEASE REPORT l

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years is not significant, the Radioactive Effluent Release Reports for 1988 through 1997 are not revised. The estimate of 15.6 Curies of unmonitored tritium released through this )

l path for January through September 1998 are included in Tables 2A and 28 of this I report. Tritium releases through the CWDWS for the 4* Quarter were monitored and are also reported in Tables 2A and 28.

Since continued operation of the system is desired, a safety evaluation was performed in accordance with NRC Bulletin 80-10 that considered the level of the contamination, the

, relationship of postulated releases to regulatory and technical specification limits, and a review against the FSAR per 10CFR50.59. As a result, the controls for liquid releases through CWDWS were incorporated into the ODCM and associated station procedures, as described in PART G of this report.

I As presented in Tables 1 A and 1C tritium released in gaseous effluents increased by a factor of approximately ten after the 1" Quarter of 1998. The increase is attributed to a blistered control rod blade in the reactor, which resulted in increased tritium concentration in the reactor coolant system. The gaseous effluent tritium was primarily released through the NPV and SPV where it was monitored by weekly sampling. The doses resulting from this release of tritium were a small fraction of Technical Specification limits, as shown in PART E.

7.0 ELEVATED RADIATION MONITOR RESPONSES

- During this reporting period, there were no alarm conditions due to elevated effluent radiation levels.

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1998 HCOS RADIOACTIVE EFFLUENTS RELEASE REPORT 4

- 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 See Summary Tables 1A through 1C.

, PART C. LIQUID EFFLUENTS See Summary Tables 2A through 2B.

PART D. SOLID WASTE See Summary in Table 3.

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1998 HCOS RADIOACTIVF. EFFLUENTS RELEASE REPORT PART E. RADIOLOGICAL IMPACT ON MAN The calculated individual doses in this section are based on the contro!!ing dose pathways and age groups as described below. The estimated dose represents the 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 production, milk production, feed for milk animals and seafood production).

The doses were calculated using methods described 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 meteorolcgical dispersion coefficients as described in the Offsite Dose Calculation Manual. Population doses were calculated using the meteorological dispersion coefficients for the twelve month reporting interval.

Liquid Pathways Type Age Group Location Pathway Total Body Adult Site Boundary Seafood Ingestion l Organ Adult Site Boundary Seafood Ingestion Type Dose Limit Total Body 2.56E-03 mrem 3 mrem Organ Dose (GI-LLl) 6.88E-03 mrem 10 mrem Population (Total) 5.05E-02 person-rem N/A Population (Average) 1.12E-05 mrem

( N/A Air Pathways

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Type Age Group Location Pathway Total Body All Site Boundary Direct Exposure Skin All Site Boundary Direct Exposure Organ infant 4.9 mi. W. Milk, Ground Plane, f inhalation Type Dose Limit Total Body 1.20E-01 mrem 500 mrem /yr Skin 2.59E-01 mrem 3000 mrem /yr Organ Dose (Thyroid) 1.29E-02 mrem 15 mrem

( Population (Total)

Population (Average) 4.06E-01 person-rem 9.02E-05 mrem N/A N/A b.

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n 1998 HCCS RADIOACTIVE EFFLUENTS RELEASE REPORT ,

Direct Radiation Direct radiation may be'estimateo by thermoluminescent dosimetric (TLD) . l 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 2S-2 0.4 mi. NNE 4.4 mrad / month SS-1 1.0 mi. E 3.5 mrad / month These values are interpreted to represent natural background, sir.ce 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.

Total Dose 40CFR190 limits the total dose to members of the public due to radioactivity and radiation from uranium fuel cycle sources to:

<25 mrem total body or any organ and;

<75 mrem thyroid for a calendar year.

For Artificial Island, the major Source , of dose are from liquid and gaseous effluents from the Hope Creek and Salem r%its.

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:

0.237 mrem Total Body 0.348 mrem Organ (Bone) 0.206 mrem Thyroid 13

1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT Dose to members of the public due to activities inside the site boundary Dase to members of the public is limited to 100 mrem total effective dose equivalent (TEDE) in a year in accordance with 10CFR20.1301. The members of the public that spent the most time at the NBU for 1998 are various food vendors, who spent a few hours in front of the Security Center during lunch hours. 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. The food vendors deliver Monday through Friday,

b. They arrive at approximately 10:00 A.M. at the Security Center.

c. The food vendors leave the site at 1:00 P.M.

d. No deliveries are made on major holidays, making the total weeks equal 50 for the year,

e. The dose data is based on the TLD !ocated outside the Security Center in the vicinity of the food vendors and the calculated dose due to gaseous effluents at that location.

f. For time periods where there is either zero dose or no data, no averaging was performed.

F,or the 12-month reporting period, January 1,1998 to December 31,1998 the calculated doses are:

4.35E+00 mrem Total Body 4.36E-02 ~ mrem Organ (Lung)

' 4.31 E-02 mrem Thyroid l

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1998 HCOS RADICACTIVE EFFLUENTS RELEASE REPORT Assessment '-

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1. Gaseous:

Gaseous 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.. J Although reported gaseous effluents increased from the previous reporting period, gaseous effluent releases continue to remain well within Federal limits and are comparable to other nuclear utilities. Fuel integrity and gaseous effluent processing .]

equipment continue to be maintained in order to ensure that all releases of gaseous radioactivity are As-Low-As-Reasonably-Achievable (ALARA). -

2. Liquids:

Liquid effluents released from Hope Creek station resulted in a minimal dose to the maximum hypothetical individual and were well within all applicable limits.

The amount of radioactivity in liquid effluente decreased from previous reporting periods due to programmatic efforts to minimize in-leakage to the liquid radwaste processing system.

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1998 HCOS RADIOACTIVE EFFLUENTS RELEASE REPORY j l

Trends

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The following two trend graphs show the total curies of gaseous ano liquid effluents released for Hope Creek from 1993 through 1998. Calculated doses in the graphs j are to the maximum hypothetical individual. j l

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Liquid Releases j

, Fission and Activation Curies Released and Calculated Doses 3g O.296 361

-+-Total Body IF l

}.455 , -*-Organ s D.186 I '

0.119 -*- Cures 0.1 0.132 l l 0.0853

' 41 E . 1

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, 0168 0.01 .535 I

4 y 69 0.275 '

, 26 l 0 001 'O l 1993 1994 1995 1996 1997 1998 Year l Gaseous Releases

,g Curies ofHobie Gases Released and Calculated Doses 1000 252 150 i182 1 ,

100 l .417 0.

26 0 E <

0.1 0.1 ' 10 0 Oa -+-Total Body

'O.0347 + Skin n nm' 00107 - --*- Cures 0 01 1 1993 1994 1995 1996 1997 1998 Year l

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1998 HCOS RADIOACTIVE EFFLUENTS RELEASE REPORT o

i PART F. METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmospheric stability class at the 300 foot elevation are provided for 1998 at the end of this report in Appendix A.

PART G. OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES

-HC Offsite Dose Calculation Manual was revised twice in 1998. Revision 16 became )

effective 5/15/98, accomplishing the following:

Corrected the use of the " correction factor in Equation 1.2 and in Appendix A.' The 1 mathematical usage of the correction factor was revised to *[1 - CF]*, Since the J factor was set to 0.5, there was no effect on past usage of the correction factor.

. The term " default" was more correctly described relative to default Liquid Effluent 1 Monitor setpoints.

. New Section 5.0 was added to include information for the Explosive Gas Monitoring ,

System. J e The Table 1-2 dose commitment factors for Zn-69 were replaced with the dose commitment factors for Zn-69m.-

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. The figures representing the gaseous, liquid, and solid radweste treatment systems were re-drawn to more accurately represent the current configuration. ,

i e Corrected the MPCe and Total Curies values for 1995 for accuracy. J e Added station code 14G1 as Radiological Environmental Monitoring Program (REMP) control location, and 6S2 as new shoreline sediment sampling location in Table E-1.

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A Revision Summary for Revision 16 is included in Appendix C. 1 Revision 17 was revised effective 12/23/98. The revision accomplished two things:

Revised the Correction Factor (CF) used in the setpoint calculations for liquid ,

discharge radiation monitors. The new CF allows operation with tritium in liquid J radwaste (LRW) up to 1E-1 uCi/ml. The new CF is 0.8. The previous CF was 0.5.

The new CF affects the setpoints as (1 - CF), or reduces the setpoint (based on q gamma emitters) by 0.2. The new CF results in lower default setpoints as well as J lower setpoints calculated by EMS (Chemistry Software). The new default setpoints and associated maximum radiation monitor background levels are incc porated into appropriate station procedures. )

. Added controls for releases from the circulating water dewatering sump (CWDWS).

The controls are similar to controls in Technical Specifications for other liquid effluent release paths. The sampling and analyses requirements are included in appropriate station procedures. A continuous release permit is generated each week for the CWDWS. Station procedures limit tritium concentrations in the sump to 1E-3 uci/mi ,

in order to prevent releases from exceeding the MPC for tritium at the river with ]

simultaneous releases from the LRW.

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1998 HCOS RADIOACTIVE EFFLUENTS RELEASE REPORT Instrument surveillance requirements include a daily check of the C'NDWS discharge radiation monitor flow indicator to ensure there is flow greater than 1 gpm through the RMS when the CWDWS pumps are running (discharge occurr;ng). Daily checksources are performed automatically. The RMS trips the sump pumps on an inoperable condition. Quarterly functional tests and 18 month channel calibrations are also required.

A copy of the revised ODCM is attached as Appendix D.

PART H. INOPERABLE MONITORS During this period there were no effluent radiation monitors inopersbie for greater than 30 days. Although not considered an effluent radiation monitor at the time, the circulating water dewatering sump radiation monitor (TBCW-RMS) was declared inoperable from mid-September to mid-December during resolution to tritium in the CWDW sump discussed in PART A, Section 6.0 of this report. No radioactive effluent releases were processed through this path during the period the monitor was e inoperable.

PART 1. PROCESS CONTROL PROGRAM (PCP) CHANGES During the reporting period, there were no changes to the process control program.

PART J. ENVIRONMENTAL MONITOP. LNG LOCATION CHANGES During the reporting period, some minor changes were made to the Radioactive Environmental Monitoring Program (REMP). A new controllocation (14G1) was installed and tested during 1997. The site was added as a controllocation to the station ODCMs during 1998. A new shoreline sediment sampling location (6S2) was added. The milk farmer at location 2F7 ceased operation during 1998. A replacement was identified nearby as 2F9. There was no significant difference in calculated potential dose between 2F7 and 2F9. The changes made did not reduce the objectives or effectiveness of the REMP.

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1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 1A EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1998 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Est.

Total Units 1" Quarter 2" Quarter Error' A. Fission and Activation Products

1. Total Release Ci 7.420E+01 3.357E+01 ' 50%

2. Average Release Rate For Period Ci/sec 9.542E+01 4.270E+00

3. Percent of Technical Specification Limit (T.S. 3.11.2.2(a)) % 1.01E+00 4.58E-01 B. lodines

1. Total lodine-131 Ci 9.756E-05 2.141E-04 50 %

- 2. Average Release Rate For Period Ci/sec 1.255E-05 2.724E-05

3. Percent of Technical Specification Limit2 (T.S. 3.11.2.3(a)) % 2.31 E-02 4.77E-02 C. Particulates

1. Particulates With Half- .

lives > 8 days Ci 2.890E-04 5.990E-05 50 %

2. Average Release Rate For Period Ci/sec 3.725E-05 7.626E-06

3. Percent of Technical Specification Limitz (T.S. 3.11.2.3(a)) % 2.31 E-02 4.77E-02

4. Gross Alpha Ci 0.00E+00 0.00E+00 D. Tritium

1. Total Release Ci 1.888E+00 1.125E+01 50 %

2. Average Release Rate For Period Ci/sec 2.428E-01 1.430E+00

3. Percent of Technical l Specification Limit 2 (T.S. 3.11.2.3(a)) % 2.31 E-02 4.77E-02

1. For batch releases, the estimated overall error is 10%.

2. lodines, Tritium, and Particulates are treated as a group.

l

(

19 f i

l

l 1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 1 A EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY- DECEMBER 1998 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Est.

Total Units 3 Quarter 4* Quarter Error' A. Fission and Activation Products

1. Total Release Cl 4.061E+01 3.353E+01 50 %

2. Average Release Rate For Period pCi/sec 5.109E+00 4.218E+00

3. Percent of Technical Specification Limit (T.S. 3.11.2.2(a)) % 5.84E-01 4.58E-01 B, lodines

1. Total lodine-131 Ci 2.636E-04 1.344E-04 50 % 1

2. Average Release Rate

, For Period pCi/sec 3.316E-05 1.691E-05

3. Percent of Technical Specification Limit2 (T.S. 3.11.2.3(a)) % 6.09E-02 4.08E-02 C. Particulates

1. Particulates With Half- ,

lives > 8 days Ci 1.190E-03 6.000E-05 50 %

2. Average Release Rate For Period pCi/sec 1.499E-04 7.591E-06

3. Percent of Technical Specification Limit2 (T.S. 3.11.2.3(a)) % 6.09E-02 4.08E-02

4. Gross Alpha Ci 0.00E+00 0.00E+00 D. Tritium

1. Total Release Ci 2.655E+01 2.003E+01 50 %

2. Average Release Rate For Period pCi/sec 3.340E+00 2.519E+00

3. Percent of Technical Specification Limit2 (T.S. 3.11.2.3(a)) % 6.09E-2 4.08E-02

1. For batch releases, the estimated overall error is 10%.

2. lodines, Tritium, and Particulates are treated as a group.

20 i

1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 1B EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1998 GASEOUS EFFLUENTS - ELEVATED RELEASES Hope Creek Generating Station has no elevated release points.

21

]

l 1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 1C EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1998 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode Nuclides Units 1" Quarter 2"d Quarter 1 Quarter 2"' Quarter Released

1. Fission Gases Krypton-83m Ci 7.42E-01 3.36E-01 0.00E+00 0.00E+00 Krypton-85 Ci 6.60E-02 0.00E+00 0.00E+00 0.00E+00 l Krypton-85m Ci 6.76E-01 3.36E-01 0.00E+00 0.00E+00 Krypton-87 Cl 2.97E+00 1.34E+00 0.00E+00 0.00E+00 Krypton-88 Ci 2.97E+00 1.34E+00 0.GOE+00 0.00E+00 Krypton-89 Ci 2.00E+01 9.07E+00 0.00E+00 0.00E+00 Xenon-135 Ci 3.71 E+00 1.68E+00 0.00E+00 0.00E+00 Xenon-135m Ci 4.45E+00 2.01E+00 0.00E+00 0.00E+00 Xenon-137 Ci 2.30E+01 1.04E+01 0.00E+00 0.00E+00 Xenon-138 Ci 1.41 E+01 6.38E+00 0.00E+00 0.00E+00 :

Totals Cl 7.42E+01 3.36E+01 0.00E+00 0.00E+00

2. lodine lodine-131 Ci 9.76E-05 2.14E-04 0.00E+00 0.00E+00 lodine-133 Ci 8.70E-03 1.53E-02 0.00E+00 0.00E+00 Totals Ci 8.80E-03 1.55E-02 0.00E+00 0.00E+00

3. Particulates (Half-life >8 days)

Cobalt-60 Ci 2.62E-05 0.00E+00 0.00E+00 0.00E+00 Manganese-54 Ci 2.63E-04 5.99E-05 0.00E+00 0.00E+00 Totals Cl 2.89E-04 5.99E-05 0.00E+00 0.00E+00

4. Tritium Cl 1.89E+00 1.12E+01 l 0.00E+00 7.28E-05 22

1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 1C

{ '

i' EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1998 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES l Continuous Mode Batch Mode 4 Nuclides i Units 3* Quarter 4" Quarter 3* Quarter 4* Quarter f

1. Fission Gases Krypton-83m Ci 4.33E-01 3.35E-01 0.00E+00 0.00E+00

' Krypton-85m Ci 4.33E-01 3.35E-01 0.00E+00 4.40E-06 j Krypton-87 Ci 1.73E+00 1.34E+00 0.00E+00 0.00E+00 Krypton-88 Ci 1.73E+00 1.34E+00 0.00E+00 0.00E+00 Krypton-89 Ci 1.17E+01 9.05E+00 0.00E+00 0.00E+00 1 Xenon-133 Ci 8.66E-01 6.71 E-01 0.00E+00 0.00E+00 Xenon-135 Ci 2.17E+00 1.68E+00 0.00E+00 1.11E-06 Xenon-135m Ci 2.60E+00 2.01 E+00 0.00E+00 0.00E+00 )

Xenon-137 Ci 1.07E+01 1.04E+01 0.00E+00 0.00E+00 Xenon-138 Ci 8.23E+00 6.37E+00 0.00E+00 0.00E+00 Totals Ci 4.06E+ 01 3.35E+01 0.00E+00 5.50E-06

2. lodine lodine-131 Ci 2.64E-04 1.34E-04 0.00E+00 0.00E+00 lodine-133 Ci 1.9BE-02 1.82E-02 0.00E+00 0.00E+00 Tota;s Cl 1.97E-02 1.83E-02 0.00E+00 0.00E+00

3. Particulates I (Half-life >8 days)

Manganese-54 Ci 1.17E-03 3.30E-05 1.25E-07 2.61E-07 Cobalt-60 Ci 2.08E-05 2.70E-05 0.00E+00 1.78E-08 Strontium-89 Ci 0.00E+00 0.00E+00 6.33E-09 0.00E+00 Totals Cl 1.19E-03 6.00E-05 1.31 E-07 2.79E-07

4. Tritium Cl 2.65E+01 2.00E+01 l 2.46E-04 1.49E-02 :

2' l

?

1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 2A EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1998 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Est.

Total

_ Units 1" Quarter 2" Quarter Error A. Fission and Activation Products

1. Total Release Cl 1.606E-04 4.668E-03 25%

2. Average Release Rate For Period Ci/mi 6.001E-09 6.694E-08

3. Percent of Technical Specification Limit (T.S. 3.11.1.2(a)) % 6.92E-04 1.82E-02 B. Tritium

1. Total Release Ci 5.313E+00 6.651 E+00 25%

2. Average Release Rate For Period Ci/ml 6.063E-06 2.069E-05

3. Percent of Technical Specification Limit (T.S. 3.11.1.1) % 2.02E-01 6.90E-01 C. Dissolved and Entrained .

Noble Gases

1. Total Release Cl 2.481 E-05 3.984E-05 25%

2. Average Release Rate For Period Ci/ml 9.273E-10 5.713E-10

3. Percent of Technical Specification Limit (T.S. 3.11.1.1) % 4.64E-04 2.86E-04 D. Gross Alpha Ci 0.00E+00 0.00E+00 25%

E. Volume o' Waste Release (Prior to Dilution) Liters 1.722E+07 1.761 E+07 25%

F. Volume of Dilution Water Used During Entire Period Liters 1.338E+10 1.566E+10 25%

24

r L. 1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION

! TABLE 2A EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1998 .

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES -

Est.

Total )

Units 3d Quarter 4* Quarter Error

!- A. Fission and Activation Products l 1. Total Release Cl 1.101E-01 2.457E-03 25%

2. Average Release Rate For Period pCi/ml 2.082E-07 5.980E-09 !

3. Percent of Technical l Specification Limit (T.S. 3.11.1.2(a)) % 1.35E-01 2.58E-02

! B. Tritium ,

1. Total Release Ci 1.109E+01 4.184E+00 25 %

2. Average Release Rate For i Period Ci/mi 1.103E-05 1.018E-05

3. Percent of Technical Specification Limit l

% 3.68E-01 3.39E-01

]

l (T.S. 3.11.1.1) l- C. Dissolved and Entrained Noblo Gases , j

1. Total Release Ci 3.878E-04 1.044E-04 25%

2. Average Release Rate For Period Ci/ml 7.336E-10 2.541E-10 j

3. Percent of Technical Specification Limit (T.S. 3.11.1.1) % 3.67E-04 1.27E-04 j D. Gross Alpha Ci 0.00E+00 7.21 E-04 25 %

E. Volume of Waste Release (Prior to Dilution) Liters 1.867E+07 2.612E+06 25%

F. Volume of Dilution Water Used During Entire Period Liters 2.048E+10 1.679E+10 25% .

i

)

25

1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 2B EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY- DECEM0ER 1998

)

LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Units 1" Quarter 2" Quarter 1" Quarter 2" Quarter Released 1.

Fission and Activation Products Chromium-51 Cl 0.00E+00 0.00E+00 0.00E+00 2.52E-04 Manganese-54 Ci 0.00E+00 0.00E+00 1.02E-04 1.56E-03 Iron-55 Ci 0.00E+00 0.00E+00 2.77E-05 2.19E-03 Cobalt-60 Ci 0.00E+00 0.00E+00 3.04E-05 6.38E-04 Zinc-65 Ci 0.00E+00 0.00E+00 0.00E+00 2.81 E-05 Cesium-137 Ci 0.00E+00 0.00E+00 4.04 E-07 0.00E+00 Totals Cl 0.00E+00 0.00E+00 1.61 E-04 4.67E-03

2. Tritium Ci 5.15E+00 5.21 E+00 l 1.62E-01 1.44E+00

3. D!ssolved and Entrained Noble Gases Xenon-133 Ci 0.00E+00 0.00E+00 8.34E-06 5.56E-06 Xenon-135 Ci 0.00E+00 0.00E+00 1.65E-05 3.43E-05 Totais Ci 0.00E+00 0.00E+00 2.48E-05 3.98E-05 26

i 1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION f TABLE 28 i EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1998 ,

LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Units p* Quarter 4* Quarter 3'8 Quarter 4* Quarter Released

1. Fission and Activation Products j Sodium-24 Ci 0.00E*00 0.00E+00 7.02E-02 1.83E-05 Chromium-51 Ci 0.00Ev00 0.00E+00 2.29E-02 5.89E-04 Manganese-54 Ci 0.00E+00 0.00E+00 4.84E-03 9.78E-04 j Iron-55 Ci 0.00E+00 0.00E+00 3.92E-03 2.64E-04 Cobalt-58 Ci 0.00E+00 0.00E+00 7.24E-04 4.33E-05 fron-59 Ci 0.00E+00 0.00E+00 0.00E 500 1.62E-04 i Cobalt-60 Ci 0.00E+00 0.00E+00 5.7SE-03 3.52E-04 Zinc-65 Ci 0.00E+00 0.00E+00 1.32E-03 4.13E-05 Strontium-89 Ci 0.00E+00 0.00E+00 1.34E-05 0.00E+00 1 Technetium-99m Ci 0.00E+00 0.00E+00 1.97E-04 8.35E-06 Silver-110m Ci 0.00E+00 0.00E+00 1.36E-05 0.00E+00 lodine-133 Ci 0.00E+00 0.00E+00 3.11 E-05 0.00E+00 i' Cesium-137 Ci 0.00E+00 0.00E+00 1.86E-04 4.44E-07 Totals Cl 0.00E+00 0.00E+00 1.10E-01 2.46E-03

2. Tritium Ci 5.27E+00 1.79E-01 l 5.83E+00 4.00E+00

3. Dissolved and Entrained Noble Gases Xenon-133 Ci 0.00E+00 0.00E+00 3.76E-05 1.75E-05 Xenon-135 Ci 0.00E+00 0.00E+00 3.50E-04 8.69E-05 Totals Cl 0.00E+00 0.00E+00 3.88E-04 1.04E-04 1

1 I

27

f 1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 3 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT 7

JANUARY - DECEMBER 1998 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel)

( 12-Month Est. Total

1. A Type of Waste (Class A or less) Units' Period Error

a. Spent Resins, Filters, Studges, m3 1.41 E+02 25 %

{ Evaporator Bottoms Ci 2.17E+03

b. Dry Compressible Waste, m3 2.87E+02 25%

Contaminated Equipment Ci 8.31 E+00

! c. Irradiated Components, m' O.00E+00 25%

Control Rods Ci 0.00E+00

d. Others (Contaminated Oil & m 1.23E+01 25%

l Dewatered Sewage Sludge) Ci 8.17E-06

1. Volumes are measured, activities are estimated.

l 2A. Estimate of Major Nuclide Composition (>1%)

Resins DAW l Nuclides .% Ci % Ci Chromium-51 <1 1.60E+00 1.33E-01 ,

Manganese-54 8.43E+00 1.83E+02 4.69E+00 3.90E-01 l

' Iron-55 8.18E+01 1.77E+03 8.91 E+01 7.40E+00 fron-59 <1 1.13E+00 9.40E-02 Cobalt-60 7.97E+00 1.73E+02 3.30E+00 2.74E-01 t Zinc-65 1.02E+00 2.20E+01 <1 Oil Sludge Nuclides % Ci % Ci Chromium-51 1.41 E+00 7.47E-08 ND i Manganese 54 <1 5.38E+01 1.56E-06 Iron-55 8.15E+01 4.33E-06 ND Cobalt-60 5.39E+00 2.86E-07 4.62E+01 1.34E-06 L Nickel-63 7.47E+00 3.97E-07 ND Cesium-137 3.35E+00 1.78E-07 ND 7

ND = Not Detected 28 i

j 1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION f i

TABLE 3 (Continted)

EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1998 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS j SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL 3A. Solid Waste Disposal (Class A or less)

Number of Mode of q Shipments Transportation Destination Type of Containers 12 Truck Oak Ridge, Tennessee Strong, Tight Containers 8 Truck Memphis, Tennessee Strong, Tight J Containers 10 Truck Bamwell, South Poly High Integrity 1 Carolina Containers

)

29

7_

) 1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION l

TABLE 3 (Continued)

EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT i JANUARY - DECEMBER 1998 l l SOLID WASTE AND IRRADIATED FUEL SHIPMENTS l l

SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL l l

12-Month Est. Total

1. B Type of Waste (Class B) Units' Period Error .

a. Spent Resins, Filters, Sludges, m3 2.05E+01 25% l Evaporator Bottoms Ci 1.48E+04 I

b. Dry Compressible Waste, m3 0.00E+02 25 % '

Contaminated Equipment Ci 0.00E+00

c. Irradiated Components, m3 0.00E+00 25%

Control Rods Ci 0.00E+00

d. Others m 3 0.00E+00 25% l Ci 0.00E+00 l

1. Volumes are measured, activities are estimated.

4 28. Estimate of Major Nuclide Composition (>1%)

Resins l Nuclides % Ci Manganese-54 5.56E+00 8.25E+02 fron-55 8.71 E+01 1.29E+04 Cobalt-60 6.38E+00 9.46E+02

, l 3B. Solid Waste Disposal (Class B) i Number of Mode of Shipments Transportation Destination Type of Containers 6 Truck Barnwell. South Poly High Integrity Carolina Containers

4. Irradiated Fuel Shipments (Disposition)

Mode of Number of Shipments Transportation Destination None N/A N/A 1

5. Solidification Methods No shipments of Solid Radioactive Waste requiring solidification were made during this period.

30 1

~_.

r I

1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION I TABLE 4A 4

EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1998

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE i

BATCH RELEASES ONLY

)

1. Dates: January 1,1998 - March 31,1998

2. Type of release: Gaseous f

3. Number of releases during quarter: -

0

)

4. Total time duration for all releases of type listed above: 0 Min.

l

5. Maximum duration for release of type listed above: 0 Min. l

6. Average duration for release of type listed above: 0 Min.

l

7. Minimum duration for release of type listed above: 0 Min.

8. Average stream flow (dilution flow) during period of release: N/A l

1

)

31 f

1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 4A EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1998

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY 1 Dates: April 1,1998 - June 1,1998 i

2. Type of release: Gaseous

3. Number of releases during quarter 1 l

4. Total time duration for all releases of type listed above: 7958 Min. I

5. Maximum duration for release of type listed above: 7958 Min.

i

6. Average duration for release of type listed above: 7958 Min.

7. Minimum duration for release of type listed above: 7958 Min.

8. Average stream flow (dilution flow) during period of release: N/A l

32

)

1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 4A

)

EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1998

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED J IN A BATCH MODE a l

BATCH RELEASES ONLY

1. Dates: July 1,1998 - September 30,1998 ;

2. Type of release: Gaseous

3. Number of releases during quarter: 13 f

4. Total time duration for all releases of type listed above: 118859 Min. 3

5. Maximum duration for release of type listed above: 19940 Min.

6. Average duration for release of type listed above: 9143 Min. )

7. Minimum duration for release of type listed above: 25 Min. 3

8. Average stream flow (dilution flow) during period of release: N/A s

I k

i i

(

33 j i

(

I

i l

1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION j TABLE 4A t

EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1998 i

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE l

BATCH RELEASES ONLY t 1. Dates: October 1,1998 - December 31,1998 I

2. Type of release: Gaseous j

3. Number of releases during quarter: 14

) 4. Total time duration for all releases of type listed above: 105382 Min.

k

5. Maximum duration for release of type listed above: 133319 Min.

( 6. Average duration for release of type listed above: 7527 Min.

7. Minimum duration for release of type listed above: 287 Min.

5

8. Average stream flow (dilution flow) during period of release: N/A I

{

(

u

i i

L I

1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT ;

HOPE CREEK GENERATING STATION TABLE 48 l i

EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1998 i

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED <

IN A BATCH MODE

?

i 1

(

BATCH RELEASES ONLY

1. Dates: January 1,1998 - March 31,1998 l

2. Type of release: Liquid

}

3. Number of releases during quarter: 5

4. Total time duration for all releases of type listed above: 279.88 Min. )

5. Maximum duration for release of type listed above: 85.13 Min.

6. Average duration for release of type listed above: 55.98 Min.

7. Minimum duration for release of type listed above: 31.0 Min. 4

8. Average stream flow (dilution flow) during period of release: 27291 GPM l

l l

l ss E_

1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 48 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1998 f

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY

{

1. Dates: April 1,1998 - June 1,1998

2. Type of release: Liquid f 3. Number of releases during quarter: 10

4. Total time duration for all releases of type listed above: 623.52 Min.

5. Maximum duration for release of type listed above: 91.0 Min.

f 6. Average duration for release of type listed above: 62.35 Min.

7. Minimum duration for release of type listed above: 36.0 Min.

8. Average stream flow (dilution flow) during period of release: 31580 GPM l

36

o i

1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 48 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT l JANUARY - DECEMBER 1998

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE .

BATCH RELEASES ONLY

1. Dates: July 1,1998 - September 30,1998

2. Type of release: Liquid

3. Number of releases during quarter: 56

4. Total time duration for all releases of type listed above: 3391.82 Min.

5. Maximum duration for release of type listed above: 87.17 Min.

6. Average duration for release of type listed above: 60.57 Min.

7. Minimum duration for release of type listed above: 30.0 Min.

i'

8. Average stream flow (dilution flow) during period of release: 40851 GPM

{

l i

1 1

1998 HCGS RADIOACTIVE EFFLUENTS RELEASE REPORT HOPE CREEK GENERATING STATION TABLE 4B EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1998

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE l

I BATCH RELEASES ONLY i

1. Dates: October 1,1998 - December 31,1998

2. Type of release: Liquid

3. Number of releases during quarter: 22 ;

4. Total time duration for all releases of type listed above: 1427.87 Min.

5. Maximum duration for release of type listed above: 85.2 Min. l 1

6. Average duration for release of type listed above: 64.9 Min.

7. Minimum duration for release of type listed above: 30.0 Min.

)

8. Average stream flow (dilution flow) during period of release: 33463 GPM l

l 1

I i

38

t 1

i APPENDIX A i l i METEOROLOGICAL I i

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1 1

APPENDIX B i i

MPC DATA l l

O

Hope Creek ODCM Rev 17 1

(1 APPENDIX F l'

MAXIMUM PERMISSIBLE CONCENTRATIONS

^

l LIQUID EFFLUENTS -

1 l

{

F-1 s

Hope Creek ODCM Rev 17 The following radionuclide concentrations were obtained from 10 CFR 20 Appendix B, l Table II, Column 2 as revised January 1,1991; '

Table F-1 Maximum Permissible Concentrations Element Isotope Soluble Conc 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 1E-4 1E-4 l Am 243 4E-6 3 E-5 Am-244 SE-3 5E-3 Antimony (51) Sb-122 3 E-5 3E-5 Sb-124 2E-5 2E-5 Sb-125 1E-4 1E-4 Arsenic (33) As-73 5E-4 5E-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 4E-4 4E-4 Bromine (35) Br-82 3E-4 4E-5

~

Cadmium (48) Cd-109 2E-4 2E-4 Cdl1Sm 3E-5 3 E-5 Cdll5 3E 5 4E-5 Calcium (20) Ca-45 9E-6 2E-4 Ca-47 5E-5 3E-5 F-2

r l Hope Creek ODCM Rev 17 Table F-1 (Continued)

Element Isotope Soldble Conc. Insoluble Conc.

(uci/ml) (uci/ml)

Cf-249 Californium (98) 4E-6 2E-5 Cf-250 l E-5 3E-5 Cf-251 4E-6 3E-5 Cf-252 7E-6 7E-6 Cf-253 1E-4 1E-4 Cf-254 1E-7 1E-7 Carbon (6) C-14 8E-4 -

Cerium (58) Ce-141 9E-5 9E-5 Ce If,_ 4E-5 4E-5 Ce A lE-5 IE-5 Cesium (55) Cs-1 a 2E-3 9E-4 Cs-134m 6E-3 IE-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 8E-5 6E-5 Cl-38 4E-4 4E-4 ]

Chromium (24) Cr 51 2E-3 2E-3 Cobalt (27) Co-57 SE-4 4E-4 Co-58m _ 3E-3 2E-3 Co-58 1E-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 Cm-244 7E-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 I

F-3

i -

1 Hope Creek ODCM Rev 17 i Table F-1 (Continued)

Element Isotope Soluble Conc. Insoluble Conc.

(uci/ml) (uci/ml)

Dysprosium (66) 1-135 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 SE-5 Lanthanum (57) La-140 2E 5 2E-5 Einsteinium (99) Es-253 2E-5 2E-5 Es-254m 2E-5 2E 5 Es-254 I E-5 IE 5 Es-255 3E-5 3E-5 Erbium (68) Er-169 9E 5 9E 5 Er-171 lE-4 IE-4 Europium (63) Eu-l52 (9.2 hrs) 6E 5 6E 5

[ Eu 152 (13 yrs) 8E-5 8E-5 Eu-154 2E-5 2E-5 Eu-155 2E-4 2E-4 Fermium (l00) Fm 254 1E-4 1E-4 Fm 255 3E 5 3E-5 Fm-256 9E 7 9E-7 Fluorine (9) F 18 8E-4 5E-4

~

Gadolinium (64) Gd 153 2E-4 2E-4 Gd l59 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 5E-5 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 3 E-3 3E 3 Indium (49) - In 113m 1 E-3 1E 3 In-114m 2E 5 2E-5 In-ll5m 4E-4 4E-4 In-115 9E-5 9E 5 L

I L

F-4

l Hope Creek ODCM Rev 17 Table F-1 (Continued)

Element Isotope Soluble Conc. Insoluble Conc. :

(uci/ml) (uci/ml) .

lodine (53) 1-125 2E-7 2E-4 j 1-126 3E-7 9E-5 I-129 6E-8 2E-4 )

1-131 3E-7 6E-5 I-l32 8E-6 2E-4 1-133 1E-6 4E-5 1-134 2E-5 6E-4 3)

Lead (82) ~ Pb-203 4E-4 4E-4

. Pb-210 IE-7 2E-4 Pb-212 2E-5 2E 5 Lutetium (71) Lu 177 1E-4 1E-4 Manganese (25) Mn-52 3E-5 3 E-5 :

Mn 54 1E-4 1E-4 Mn-56 IE-4 lE-4 Mercury (80) Hg-197m 2E-4 2E-4 Hg-197 3E-4 5 E-4 Hg-203 2E-5 1 E-4 1 Molybdenum (42) Mo-99 2E-4 4E-5 Neodymium (60) Nd 144 7E-5 8E-5 Nd-147 6E 5 6E 5 l Nd-149 3E-4 3E-4 Neptunium (93) Np-237 3E-6 3E-5 Np-239 1E-4 1E-4 J Nickel (28) Ni 59 2E-4 2E-3 Ni 63 3E-5 7E-4 i Ni-65 IE-4 IE-4 J Niobium (41) Nb-93m 4E-4 4E-4 Nb-95 lE-4 I E-4 l 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 5E 5 l

Palladium (46) Pd-103 3 E-4 3 E-4 f

Pd 109 9E-5 7E-5 [ .

1 F-5

.-.--------_---j

Hope Creek ODCM Rev 17

{

1 Table F-1 (Continued)

~

Element Isotope Soluble Conc. Insoluble Conc. 1 (uci/ml) (uci/ml)

Phosphorus (l5) P-32 2E 5 2E 5 Platinum (78) Pt 191 1E-4 1E-4 Pt-193m lE-3 lE-3 Pt-193 9E-4 2E-3 Pt-197m lE-3 9E-4 Pt-197 ,1 E-4 1E-4 Plutonium (94) Pu 238 SE-6 3E-5 Pu-239 ~~

SE-6 3E 5 Pu-240 SE-6 3 E-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 5E-5 5E-5 Promethium (61) 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 3 E-8 3E-5 Rhenium (75) Re 183 6 E-4 '~ 3E-4 Re-186 9E 5 SE 5 Re-187 3 E-3 2E-3

.Re-188 6E 5 3E-5 Rhodium (45) Rh-103m iE-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 3 E-4 Ru-103 8E-5 8E-5 F-6

l Hope Creek ODCM. Rev 17 Table F 1 (Continued) ;

1 Element Isotope Soluble Conc. Insoluble Conc.

(aci/ml) (uci/ml) 1 Ru-105 IE-4 lE-4 Ru-106 1E-5 1 E-5 Samarium (62) Sm-147 6E-5 7E-5 .

Sm-151 4E-4 4E-4 J Sm-! 53 8E-5 8E-5 Scandium (21)- Sc-46 4E-5 4E-5 i Sc-47 _ 9E-5 9E-5 Sc-48 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 Ag-110m 3E-5 3E-5 Ag111 4E-5 4E-5 :

Sodium (l1) Na-22 4E-5 3E 5 Na 24 2E-4 3E-5 g Strontium (38) Sr-85m 7E-3 7E 3 I Sr-85 lE-4 2E-4 j Sr-89 3E-6 3E-5 Sr 90 3E-7 4E-5 1 Sr-91 7E-5 SE 5 ?

Sr92 , 7E-5 6E-5 Sulfur (16) S-35 6E-5 3 E-4 i

Tantalum (73) Ta-182 4E-5 4E-5 Technetium (43) Tc-96m lE-2 lE-2 q

Tc-96 1 E-4 5E-5 Tc 97m 4E-4 2E-4 Tc-97 2E-3 8E-4 Tc-99m 6E-3 3E-3 J Tc-99 3 E-4 2E-4 Tellurium (52) Te-125m 2E-4 1 E-4 l Te 127m 6E-5 5E 5 Te-127 3E4 2E-4 Te-129m 3E-5 2E-5 1 Te 129 8E-4 8E-4 Te-131m 6E 5 4E-5 I J

h j

l J

F-7 g

Hope Creek ODCM Rev 17 i

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 lE-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 t Th-231 2E-4 2E-4 i Th-232 2E-6 4E-5 Th-natural 2E 6 2E-5 j Th-234 2E-5 2E-5 Thulium (69) Tm-170 5E 5 5E-5 i Tm-171 SE-4 SE 4 1 Tin (50) Sn-113 9E 5 8E-5 Sn-124 2E 5 2E-5 !

t Tungsten (74) W-181 4E-4 3E-4 W-185 lE-4 IE-4 W-187 . 7E-5 6E-5 Uranium (92) U-230 SE-6 5E 6 U-232 3E-5 3E 5 U 233 3E-3 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 I Ytterbium (70) Yb-175 IE-4 IE-4 F-8

i I Hope Creek ODCM Rev 17 Table F-1 (Continued) l- Element Isotope Soluble Conc. Insoluble Conc.

i- (uci/ml) (uci/ml)

Yttrium Y-90 2E-5 2E 5 i Y-91-m 3E-3 3E 3 I Y-91 3E-5 3E 5 {

1 Y-92 6E-5 6E-5 Y-93 3E-5 3E-5 Zinc (30) Zn-65 1E-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 fission and with radio - 1 active half-life greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

! Any single radio- 3 E-8 3E-8 l

nuclide not listed above, which decays by alpha emission or l spontaneous fission.

I j 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 of each radionuclide are known, the limiting values should be derived as follows: Determine, for each radionuclide in the mixture, the ratio between the quantit present in the mixture and the limit otherwise established in Appendix B for the .3pecific radionuclide not in a mixture. The sum of such ratios for all the radionuclides in the mixture may not exceed "1" (i.e. " unity").

l F-9

i APPENDIX C ,

HCGS ODCM ;

REV 16 9

m____________

J Hope Creek ODCM Revision #16 HOPE CREEK GENERATING STATION :

OFFSITE DOSE CALCULATION MANUAL i

REVISION

SUMMARY

nroughout the document, numerous changes were made to the formattmg as the document was convered from Wordperfect to MicrosoR Want. Exampics include converting the pathway dose factors tables from a text to a table format. No chmees were made to the content except as otherwiec edicasedin this sammary. ,

Introduction section on page 1 of the document was re-wntten for clarity and to remove extraneous verbiaec De fact the &-> - -3=t is to be considered an extension of Technical Specifications was i made explicit. '

Corrected the use of the " correction factor"in Equation 1.2 and in Appendix A. Ac correct mathematical usage of the correcuon fac:or in the equation should be "[I - CF;" This factor for Hope Creek is set at 0.5 therefore past usage is unaffected.

Wording was introduced in Section 1.2.2 to more correctly describe the use of" default" Liquid Emuent Monitor setpoints. He dese,ription is consistent with the practices and procedures in place at Hope Cree.k.

New Section 5 0 was added to include information as to the Explosive Gas Monitoring Program at Hope Creek his program was moved into Section 6.8 of the HCGS Technical Speci6 cations by Amendment #91. Desenpnon is being introduced to nether document the controls on the program In Table 1 2 dose cummitment factors for Zn-69 were removed and subsequently replaced with dose commitment factors for Zn-69m. The factors previously used did not account for the additional transition energy from the meta-stable state of this isotope. His action satisfies CRCA

971001199-04.

Figures 2 1 and 2 2 were reeawn to more accurately represent the connguration of gaseous emuent pathways from Hope Creek. Das satis 6cs CRCA #970912210-01.

Annotated Figures 1 1,1-2, and 2 2 to clarify that, although installed in the facility, certam l

sections of the Solid Radioactive Waste Processing Facility are not used. The equipment referenced ts awaiting abandonment under DCP 4EC-3634.

1 Corrected the MPCe and Total Curies values for 1995 on page A 5. None of the conclusions are affected by the corrections; this was done for accuracy within the document.

Station code 3H3 was replaced by 14G1 in sub-sections "A" and "B" of Table E-1. Added station i code 6S2 as a new shoreline sediment sampling location to sub-section "F" of Table E 1. These changes were identified in the 1997 Annual Radiological Environmental Report for SGS and l

, HCGS.

I

. \

l APPENDIX D !

HCGS ODCM !

REV 17 i I

I OFFSITE DOSE CALCULATION MANUAL FOR PUBLIC SERVICE ELECTRIC AND GAS COMPANY HOPE CREEK GENERATING STATION Revision 17 i

l December 1998 I

Prepared by: Vincent Ciarlante d M ODCM Coordinator,- Radiation Protection Support Reviewed by: Lucius Clark utiw h] d -

l Station Qualified Reviewer- Radiation Protection Support Approved by: Gregory Salvatoriello Chemistry Superintencfent/ "

Accepted by: I SORC Chairman: K) Date: /

/

S3/76 Mtg.# 98.o7'/ !

l 1

i

Hope Creek ODCM Rev 17 i 1

i i

j Revision Summary:

Section 1.I'(1)

- added information for the Circulating Water Dewatering Sum (TBCW-RMS) (RE-4557) instrumentation and controls Section 1.2.1 - added TBCW to Release Rate (RR) for liquid effluents Section 1.2.2 - revised correction factor (CF) to 0.8 per Appendix A l Figure 1-1 - revised title to include monitoring for the circulating water dewatering sump which is n3 a radwaste treatment system; added the circulating water dewatering sump pathway and the radiation monitor (RE-4557) to the figure Table 1-1 - added release rate infomtation for the TBCW monitor; revised default setpoints for liqui effluent radiation monitors to values determined in Appendix A l Appendix A - revised Correction Factor (CF) for non gamma emitters to address higher values of tritium; revised default setpoints for effluent radiation monitors; pr values for default and maximum setpoints for the TBCW-RMS Appendix G added new Appendix G to specify controls for releases from the circulating water dewatering sump; controls include sampling and analysis requirements as well as j

instrument surveillance requirements i

l i

j i

[ l Hope Creek ODCM Rev 17 t

HOPE CREEK GENERATING STATION OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS i

l I N TR O D U CTI O N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... .. . . . ..1 .. . . . . .l l

1.0 l I

LIQUID EFFLUENTS 1.1 Radiation Monitoring l i

ins trum e

2. ' m and Con tro l s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . .. . . . . . . . . . ..2 . . . . . . . . . . . .l 1.2 Liquid Emuent Monitor Setpoint Determination ..... .. . . .. .... ............................. . .. ..... .... .. . . . .... .. . ... .... .. . ... .. . . .. ... . . . . . . .

l l

l 1.2.1 L iquid Effl ue nt M onitors . .. . . . ... . . . . .... . .. .. . . .. .. . . . . . . . .. . . . . . .. . . . . ... .. . . . . . . . . . . . . . . .

I 1.2.2 Conservative Default Values...................

.. ............ ............ .... ..... ...... . . . .4 1

1.3 Liquid Emuent Concentration Limits-10CFR20...........................................................................................4 1

1.4 Liquid Emuent Dose 1 I

Cal c u la t i o ns - 1 0 C F R 5 0 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .5 .. . . . . . . . .l i

1.4.1 Member of the Public Dose - i Liquid E ffluents ....... ....... ... ... .... ... ..... . . . . . . . . . . . . . . . . . . . . . . . . .5 1.4.2 Simplified Liquid Emuent Do se Calc ul atio n . . . . . . . . . . . . . . . . . . . . . . . . . .. . ... . . .. .. . . . .. . . . . . . . . ..6 ........

1.5 Liquid Effluent Dose Projections... . ....... ...... .. .. . . . .... .. .... .. .... .... . . . . . . . . 7 1.6 Re p re s e ntat i ve S amp l es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . .. . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . ... .8

( 2.0 GASEOUS EFFLUENTS 2.1 Radiation Monitoring r

Instrumentation and Controls .. ... ....... . .. ... ... ...... ... . . .. ..... ..... . . . . . . . . . . .. 8 2.2 Gaseous Emuent Monitor S e tpoint Determinatio n ... . .. .. . . . . . . . .. . . . . . . . .. . .. . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . .9 2.2.1 Plant Vent and FRVS Monitors ........ ...... ...... . . . . . . . . . . . . . . . . . . .. .9 2.2.2 Conservative De fault Values... ........ ............ . ......... .... .. ..... .. .. . .. ... . .. . .10 t

i 2.3 Gaseous Effluent Instantaneous Dose Rate Calculation - 10 CFR 20............. .... ....... ...... .. ... .. . . . . . . . . . . . .I1 l

I

i Hope Creek ODCM Rev 17 a

2.3.1 Site Boundary Dose Rate -

N o b l e G as e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. I.1. 1.

2.3.2 Site Boundary Dose Rate -

Radioiodine and Particulates ................... .................. ......... ....... .......... ... 12 2.4 Noble Gas Effluent Dose Cal c ul atio ns - 10 C F R 5 0 . .. .. . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . .. . . . . . . . . . . . . . . . . . . . . ..13 . . . i.

2.4.1 UNRESTRICTED AREA Dose -

N o ble G ases . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

2.4.2 Simplified Dose Calculation for Noble Gases .. . . .. ... .. .. . .. . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . .. . .. . . . .

2.5 Radioiodine and Particulate Dose Calc ula tio ns - 10 C FR 5 0 . . . . . . . . . . . . . . .. . . . .. ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

2.5.1 UNRESTRICTED AREA Dose -

Radioiodine and Particulates......... ......... ....... . ................ ..................14 2.5.2 Simplified Dose Calculation for f

Radioiodines and Particulates .. ....... ....... ....... .... .... ..... . . ... ......,... . 15 L

2.6 Gaseous Efiluent Dose Projection ..... . ......... ...... . . ... ...... .. ..... .. ... ... . . ... .. . . . . . 15 '

3.0 S P E C I A L DO S E AN A L Y S I S . . . . . . . . . . . . . . . .. . . . . . . . . . . . . .. . . . . . . . . . . . . .. . . . . . . . . . . .. . . . . . ... ...I6 ... ,

3.1 Doses Due to Activities inside -

t he S I TE B O UN D AR Y . . . . .$. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .... . . . ..I6 ....

3.2 Total Dose to MEMBERS OF THE PUBLIC -

l 40CFR190..................................................... .. . . . . ... ... . . . . . . . . . .

.I7J 3.2.1 Effluent Dose Calculation ... ..... ....... . ..... ..... . . . ......... ... . ... ... . .17 (

3.2.2 Direct Exposure Determins. tion... ..... .. .. ... . . . . . . . . . . . . . . . . . . . . . . . . . . . .. I 7 s

4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM . .. ..... ....... . . . . . .18 1 4.1 S amplin g Program . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . ... . . . . . . . . . . . .. .. I 8 '

4.2 Interlaboratory Comparison Program .......... ...... . ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . .I8 5.0 HCGS EXPLOSIVE GAS MONITORING PROGRAM.. . . .. . . .. . . ... ... .. . . . .. .18 11

y Hope Creek ODCM Rev 17 TABLES 1-1 Parameters for Liquid Alarm S e t poi nt Dete rmi nation . . .. . . .. . . .. . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . .. . . . . . . . .. .. . . . . ..21 .......

l 1-2 Site Related Ingestion Dose Commitment Factors, Aio........ .. . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . .. .22 {

l-3 Bioaccumulation Factors (BFi).... ............ ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .24 i 2-1 .

Dose Factors for Noble Gases ........ .... .. . .... ............ .. . .. . ....... . ... . . .... . . .27 2-2 Parameters for Gaseous Alarm S e t poi nt De te rmination . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..28 ......

2-3 Controlling Loca: ion.s, Pathways and Atmospheric Dispersion for Dose Calculations. . . . . . . . . . . .. . . . . . . . . . . . .. .. . . . . . . . . . . . . . .. . . . . . . . . . . .. . .

2-4 Pathway Dose Factors -

Atmo spheri c Rel ease s . . . . . . . . . . . . . .. . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . '. . . . . . .

A-1 Calculation of Effective MPC ... . .......... . ...... ........... .. . . ..... .... ... ..

! . .. . . . . A.-6 B-1 Adult Dose Contributions Fish and Invertebrate P athways . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

C-1 Effective Dose Factors ............ ... ...................................................................C-4 D-1 Infant Dose Contribution Fraction of Dose.......... . . ........ ............ ... . . . . . . . . . . . . ..D-3 D-2 Fraction of Dose Contributions by Pathway... ....... . ... . . . . . . . . . . . . . . . . . . . . . . ..D-3 E-1 S am pl e L o c at i o ns . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . ... . . . . . . . ..E-3 F-1 Maximum Permissible Concentrations ........ ..... . .. .... . ...... ... .... . ....... . . F2 l

i APPENDICES t -

Appendix A - Evaluation of Conservative, Default l

M PC Value for Liquid Effluents..................... . ...... ... . ... . ... .. ... . . . . . .. A- 1 l

Appendix B - Technical Basis for Effective Dose Factors - Liquid Radioactive Effluents ... .... ... ............ . ... .. ... . . ... .. .B-1 Appendix C - Technical Basis for Effective Dose Factors - Gaseous Radioactive Effluents . .. . .... .... ...... . .. .. . . . . .C-1 Appendix D - Technical Basis for Effective Dose Parameters - Gaseous Radioactive Effluents .... . ... . ........ .. . . . .. .. . ..D l Appendix E , Radiological Environmental Monitoring Program - Sample Type, Location and Analysis . . . .... .. . . E- 1 Appendix F - Maximum Permissible Concentration (MPC)

Values for Liquid Effluents . .... .. . . . .... ......... . . . . . . . .. .. . . . .F1 Appendix G - Controls for Releases from the Circulating Water Dewatering Sump ... . ..G- 1 111 w

I Hope Creek ODCM Rev 17 i

HOPE CREEK GENERATING STATION OFFSITE DOSE CALCULATION MANUAL l INTRODUCTION The Hope Creek Offsite Dose Calculation Manual (ODCM) describes methodologies and parameters used for:

1. The calculation of radioactive liquid and gaseous effluent monitoring instrumentation alarm / trip setpoints, )

- AND -

2. The calculation of radioactive liquid and gaseous concentrations, dose rates, cumulative quarterly and yearly doses, and projected doses.

)

I -

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. l N J l

I 1

I.

Hope Creek ODCM Rev 17 s

1.0 LIQUID EFFLUENTS 1.1 Radiation Monitoring Instrumentation and Controls The liquid effluent monitoring instrumentation and controls at Hope Crack for controlling and monitoring normal radioactive material releases in accordance with the Hope Creek Radiological Effluent Technical Specifications are summarized as follows:

(1) Alarm (and Automatic Termination)- Liquid Radwaste Discharge Line Monitor provides the alarm and automatic termination of liquid (RE4861) radioactive material releases from the liquid waste management system as required by Technical Specification 3.3.7.10.

Circulating Water Dewatering Sump Discharge Monitor (RE4557) provides alarm and automatic termination ofliquid radioactive releases from the circulating dewatering sump.

f Condensation drains from certain supply ventilation units and liquids from the fill and venting of the circulating water side of the condenser waterboxes are directed to this sump.

Automatic termination is performed by trip of the sump pumps on high gamma radiation

, signal. Controls for releases from the dewatering sump are identified in Appendix O.

(2) Alarm (Only) - The Cooling-Tower Blowdown Effluent Monitor (RE8817) provides an Alarm function only for releases into the environment as required by Technical Specification

( 3.3.7.10. 1 Liquid radioactive waste flow diagrams with the applicable, associated radiation monitoring instrumentation and controls are presented in Figure 1-1.

1.2 Liquid Effluent Monitor Setpoint Determination Per the requirements of Technical Specification 3.3.7.10, 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 f liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR 20 Appendix B. Table II, Column 2, (Appendix F) for radionuclides and 2.0E-04 uCi/ml for dissolved or entrained noble gases). The following equation (adopted from NUREG-0133) must be satisfied to meet the liquid effluent restrictions:

C (F + 0 cs (1.1) f where:

C= the effluent concentration limit of Technical Specification (3.11.1.1) implementing the 10 CFR 20 MPC (Appendix F) for the site, in 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,

\

2 f

i 1

I Hope Creek ODCM Rev 17 '

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 I unit time.

[ Note that if no dilution is provided, e < C. Also, note that when (F) is large compared to (f). j then (F + f) = F.] f 1.2.1 Liemed Emment Monitors The setpoints for the liquid effluent monitors at the Hope Creek Generating Station are determined by the following equation:

MPC,

CTBD * [1 -CF)

SP s + bkg (1.2)

RR with:

I C (gamma)

MPC,= (1.3)

C, (gamma)

MPC, where:

i SP =

alarm setpoint corresponding to the maximum allowable release rate (uCi/ml).

MPC, = an effective MPC value for the mixture of radionuclides in the effluent stream, (uCi/ml).

C, =

the concentration of radionuclide in the liquid effluent (uCi/ml). j MPC, = the MPC value corresponding to radionuclide i from (Appendix F) 10 CFR !

20, Appendix B. Table II, Column 2 (uCi/ml).

CTBD = the Cooling-Tower Blowdown Discharge rate at the time of release (gal / min).

RR =

the liquid effluent release rate (gal / min) at the monitor location (i.e., at the liquid radwaste monitor, at the TBCW monitor, or at the CTBD monitor).

bkg =

the background of the monitor (uCi/ml).

CF =

Correction factor to account for non-gamma emitting nuclides and radiation monitor inaccuracies.

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.

3

Hope Creek ODCM Rev 17 1.2.2 Conservative Default Values 1

Conservative alarm setpoints for liquid radwaste radiation monitors may be determined through the use of default parameters. Table 1-1 summarized all current default values in use for Hope Creek. They are based upon the following:

l

-(a) substitution of the effective MPC value with a default value of 7.92E 05 uCi/ml for j radwaste releases (Refer to Appendix A forjustification);

)

I (b) substi.tutions of the Cooling-Tower Blowdown discharge rate with the minimum j average flow,in gal / min; and, (c) substitutions of the effluent release rate with the highest allowed rate, in gal / min.

(d) substitution of a 0.8 correction factor (CF) to account for monitor inaccuracies and l non-gamma emitting radionuclides. l The use of the conservative alarm setpoint, or a setpoint below the conservative value, is l acceptable provided that the value used is at least as conservative as the release specific setpoint calculated in accordance with Equation 1.2 above. Procedural controls exist to !

verify the setpoint utilized is at or below what is required.

1.3 Liquid Effluent Concentration Limits - 10 CFR 20 Technical Specification 3.11.1.1 14mits 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 (Appendix F) for radionuclides other than noble gases. Noble gases are limited to a diluted concentration of 2.0E 04 uCi/ml. 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 s1 (1.4) l MPC, CTBD + RR where:

=

C, actual concentration of radionuclide i as measured in the undiluted liquid effluent (uCi/ml).

MPC, .= the MPC value corresponding to radionuclide i from 10 CFR 20, Appendix B.

Table II, Column 2 (Appendix F) (uCi/ml).

=

2E-04 uCi/ml for dissolved or entrained noble gases.

RR = the actual liquid effluent release rate (gal / min) 4 L

i Hope Creek ODCM Rev 17 CTBD = the actual Cooling-Tower Blowdown discharge at the time of release (gal / min).

1.4 Liquid Effluent Dose Calculation - 10 CFR 50 1.4.1 MEMBER OF THE PUBLIC Dose - Liquid Emuents Technical Specification 3.11.1.2 limits the dose or dose commitment to MEMBERS OF THE PUBLIC from radioactive inaterials in liquid effluents from Hope Creek Generating Station to: ,

j

(

- during any calendar quarter:

s 1.5 mrem to total body s 5.0 mrem to any organ

- during any calendar year:

s 3.0 mrem to total body l s 10.0 mrem to any organ Per the surveillance requirements to Technical Specification 4.11.1.2, the following calculation methods shall be used for determining the dose or dose commitment due to the liquid radioactive effluents from Hope Creek.

8.35E-04

VOL D, =

I (C,

A,0) (1.5)

CTBD where:

D, =

dose or dose commitment to organ o, including total body (mrem).

A,o =

site-related ingestion dose commitment factor to the total body or any organ o for radionuclide i (mrem /hr per uCi/ml). ;

C, =

average concentration of radionuclide i, in undiluted liquid effluent representative of volume VOL (uCi/ml).

VOL = volume ofliquid effluent reler. sed (gal).

CTBD = Average Cooling-Tower Blowdown discharge rate during release period (gal / 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).

Hope Creek ODCM Rev 17 The site-related ingestion dose / dose commitment factors (A,,) are presented in Table 1-2 and have been derived in accordance with NUREG-0133 by the equation:

A,, = 1.14E+05 [(UI

BI) + (UF

BFj] Df, (1.6) where:

A,, =

composite dose parameter for the total body or critical organ o of an adult for radionuclide i, for the fish and invertebrate ingestion pathways (mrem /hr per uCi/ml).

1.14E+05= conversion factor (pCi/uCi

ml/kg per hr/yr).

f UI =

adult invertebrate consumption (5 kg/yr).

Bi; =

bioaccumulation factor for radienuclide i in invertebrates from Table 1-3 q (pCi/kg per pCi/1).

) UF =

adult fish consumption (21 kg/yr).

B f, =

bioaccumulation factor for nuclide i in fish from Table 1-4 (pCi/kg per pCi/l).

l Df, =

dose conversion factor for nuclide i for adults in preselected organ, o, from 1

Table E-11 of Regulatory Guide 1.109 (mrem /pCi).

The radionuclides included in the periodic dose assessment pei- 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.

f Radionuclides requiring radiochemical analysis (e.g., Sr-89 and Sr-90) wil1 be added to the f dose analysis at a frequency consistent with the required minimum analysis frequency of Technical Specification Table 4.11.1.1.1-1.

1.4.2 Simplified Liquid Effluent Dose Calculation l In lieu of the individual radionuclide dose assessment as presented in Section 1.4.1, the

)

following simplified dose calculation equation may be used for demonstrating compliance with 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 D, =

1.94E+02

VOL

I C, (1.7)

CTBD Maximum Organ D,,,,, = 4.28E+02

VOL

I C, (1.8)

CTBD l

l

~

Hope Creek ODCM Rev 17 !

where:

r D. = conservatively evaluated total body dose (mrem).

D, = evaluated maximum organ dose (mrem).

l C, = average concentration of radionuclide i, in undiluted liquid effluent J l

representative of the volume VOL (uci/ml).

VOL = volume ofliquid effluent released (gal). 1 CTBD = average Cooling-Tower Blowdown discharge rate during release period (gal / min).

o4E+02' = conversion factor (1.67E-2 hr/ min) the ingestion dose commitment factor (Zn-65 -

total body -- 2.32E5 mrem /hr per uCi/ml), and the near field dilution factor of 0.05

{

(See Appendix B). -

/

4.28E+02 = conversion factor (1.67E-2 hr/ min) the conversion maximum organ dose conversion factor (Zn-65, Liver - 5.13E5 mrem /hr per uCi/ml), and the nearfield '

diiution factor of 0.05 (See Appendix B).

1.5 Liquid Efiluent Dose Projections I 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-c'.ay projected doses exceed:

f

- 0.06 mrem to the total body, or

- 0.2 mrem to any organ.

l The applicable liquid waste processing system for maintaining radioactive material releases ALARA are the drain filters and demineralizers 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:

(

D., =

the total body dose projection for current 31-day period (mrem).

l D. =

the total body dose to date for current calendar quaner as determined by equation (1.5) or (1.7). ;

D, , =

the maximum organ dose to date for current calendar quarter as determined by j equation (1.5 or (1.8)(mrem).

d =

the number of days in current calendar quarter at the end of the release. j 31d = the number of days of concern. i 1

7

Hope Creek ODCM Rev 17 1.6 Representative Samples

( A sample should be representative of the bulk stream or volume of effluent from which it is taken. Prior to sampling, large volumes ofliquid waste should be mixed in as short a time interval as practicable to assure that any sediments or particulate solids are distributed uniformly in the waste mixture. Recirculation pumps for liquid waste tanks (collection or sample test' tanks) should be capable of recirculating at a rate of not less than two tank volumes in eight hours. Minimum recirculation times and methods of recirculation are controlled by specific plant procedures.

2.0 GASEOUS EFFLUENTS 2.1 Radiation Monitoring Instrumentation and Controls The gaseous effluent monitoring instrumentation and controls at Hope Creek for controlling and monitoring normal radioactive material releases in accordance with the Radiological Effluent Technical Specifications are summarized as follows:

(1) Filtration. Recirculation, and Ventilation System -

f The FRVS is maintained in a standby condition. Upon reactor building isolation, the FRVS recirculation system recirculates the reactor building air through HEPA and charcoal filters. Releases are made to the atmosphere via a reactor building vent or the South Plant Vent depending on mode of operation. Noble gas monitoring is provided by RE-4'811 A.

f (2) South Plant Vent -

l The SPV receives discharge from the radwaste evaporator, reactor building purge,

) auxiliary building radwaste area, condensate demineralizer, pipe chase, feedwater

' heater, and untreated ventilation sources. Effluents are monitored (for noble gas) by the RE-4875B menitor.

(3) North Plant Vent -

The NPV receives discharge from the gaseous radwaste treatment system (Offgas system) and untreated ventilation air sources. Effluents are monitored (for noble f gases) by the RE-4573B monitor.

Gaseous radioactive waste flow diagrams with the applicable, associated radiation f monitoring instrumentation controls are presented in Figures 2-1 and 2-2.

(

8

~

Hope Creek ODCM Rev 17 1

2.2 Gaseous Effluent Monitor Setpoint Determination 2.2.1 Plant Vent, FRVS Per the r:quirements of Technical Specification 3.3.7.11, alarm setpoints shall be established for the gaseous effluent monitoring instrumentation to ensure that the release rate of noble gase.e does not exceed the limits of Specification 3.11.2.1, which corresponds to a dose rate at the SITE BOUNDARY of 500 mrem / year to the total body or 3000 mrem / 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 I 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 * (C,

K)] / 500 4 (2.1)

(

FRAC = [4.72E+02

X/Q

VF * (C, * (L + 1.1M))] / 3000 (2.2) where: '

FRAC = fraction of the allowable release rate based on the identified radionuclide concentrations and the release flow rate.

l 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).

C, = concentration of noble gas radionuclide i as determined by radioanalysis of grab

{

sample (uCi/cm3) (

l K = total body dose conversion factor for noble gas radionuclide i (mrem /yr per l uCi/m3), from Table 2-1 l L, = beta skin dose conversion factor Gr noble gas radionuclide i (mrem /yr per uCi/m3), from Table 2-1 M, = gamma air dose conversion factor for noble gas radionuclide i (mrad /yr per uCi/m3), from Table 2-1 f 1.1 = mrem skin dose per mrad gamma air dose (mrem / mrad) z 4.72E+02 = conversion factor (cm3/ft3

min /sec) ;

500 = total body dose rate limit (mrem /yr) 3000 = skin dose rate lim t (mrem /yr) <

l

(

I 1

i 9

Hope Creek'ODCM Rev 17 I Based on the more limiting FRAC (i.e., higher value) as determined above, the alarm setpoints for the applicable monitors may be calculated by the equation:

SP = [AF

I C, / FRAC l + bkg (2.3) where:

SP

= alarm setpoint corresponding to the maximum allowable release rate (uCi/cc).

FRAC = highest fraction of the allowable release rate as determhwd in equation (2.2).

bkg = background of the monitor (uci/cc).

AF = administrative allocation factor for the specific monitor (0.2 NPV,0.2 SPV,0.1 FRVS).

The allocation factor (AF) is an administrative control imposed to ensure that combined releases from Salem Units 1 and 2 and Hope Creek will not exceed the regulatory limits on release rate from the site (i.e., the release rate limits of Technical Specification 3.11.2.1).

Normally, the combined AF value for Salem 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 Salem Generating Station to ensure that the combined allocation factors for all units do not exceed 1.0.

2.2.2 Conservative Default Values 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 Tabie 2-2.

These values are based upon:

- the maximum ventilation (or purge) flow rate; f

- a radionuclide distribution adopted from ANSI N237- 1976/ANS 18.1 " Source Term Specifications", Table 5 and; f - 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.

, 10 h

1 Hope Creek ODCM Rev 17 2.3 Gaseous Emuent Instantaneous Dose Rate Calculations - 10 CFR 20 2.3.1 Site Boundary Dose Rate - Noble Gases Technical Specification 3.II.2.la limits the dose rate at the SITE BOUNDARY due to noble gas releases to 5 500 mrem /yr, totcl body and 5 3000 mrem /yr, skin. Radiation monitor i alarm setpoints are established to ensure that these release limits are r.ot exceeded. In the event any gaseous releases from the station results in an alarm setpoint (as determined in l 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 (K

Q) (2.4)

D, = X/Q

I ((L, + 1.1M,)

Q, (2.5) where:

D. = Total body dose rate (mrem /yr).

D, = skin dose rate (mrem'yr).

X/Q = atmospheric dispersion to the controlling SITE l

BOUNDARY location (sec/m3).

Q, = average release rate of radionuclide i over the release period under evaluation (uCi/sec).

K, = total body dose conversion factor for noble gas radionuclide i (mrem /yr per uCi/m3), from Table 2 L, = beta skin dose conversion factor for noble gas radionuclide i (mrad /yr per uCi/m3),

from Table 2-1 M, = gamma air dose conversion factor for nobie gas radionuclide i (mrad /yr per

uCi/m3, from Table 2-1.

1.1 = mrem skin dose per mrad gamma air dose (mrem / mrad)

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 releose rate based on correlation of the monitor reading and monitor sensitivity.

The 15-minute averaging is nt.eded 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 actual releases do not result in radiation 11 l

Hope Creek ODCM Rev 17 monitor indications exceeding alarm setpoint values based on the above criteria, no funher analyses are required for demonstrating compliance with the limits of Specification 3.11.2.1a.

Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented in Table 2-3 may be used for evaluating the gaseous effluent dose rate.

2.3.2 Site Boundary Dose Rate - Radiciodine and Particulates Technical Specification 3.11.2.lb limits the dose rate to < 1500 mrem /yr to any organ for I-131,1-133,. tritium and particulates with half-lives greater dian 8 days. To demonstrate compliance with this limit, an evaluation is performed at a frequency no greater than that corresponding to the sampling and ar.alysis time period (e.g., nominally once per 7 days).

The following equation shall be used for the dose rate evaluation:

D, = X/Q

I (R,,

Q) (2.6) where:

D, = average organ dose rate over the sampling time period (mrem /yr).

X/Q = atmospheric dispersion to the controlling SITE BOUNDARY location for the inhalation pathway (sec/m3).

R,, = dose parameter for radionuclide i (mrem /yr per uCi/m3) and organ o for the child inhalation pathway from Table 2-4.

Q, s

= average release rate over the appropriate sampling period and analysis frequency for radionuclide i - - I-131, I,133, tritium or other radionuclide in particulate form with half life greater than 8 days (uCi/sec).

f 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 limiting potential pathway, age group and organ (inhalation, child, thyroid -- Ri

) = 1.62E+07 mrem /yr per uCi/m3), the allowable release rate for I-l't! is 34.7 uCi/sec.

Reducing this release rate by a 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 17.4 uCi/sec. For a 7-day period, which is the nominal sampling and analysis frequency for I-131, the cumulative release is 10.5 Ci.

Therefore, as long as the I-131 release in any 7-day period do not 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.

12 1

Hope Creek ODCM Rev 17 2.4 Noble Gas Effluent Dose Calculations - 10 CFR 50 2.4.1 UNRESTRICTED AREA Dose - Noble Gases Technical Specification 3.11.2.2 requires a periodic assessment of releases of noble gases to evaluate compliance with the quarterly dose limits of 5 5 mrad, gamma-air and 510 mrad, beta air and the calendar year limits $ 10 mrad, gamma-air and 5 20 mrad, beta-air.

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 (M

Q) (2.7)

D. = 3.17E-08

X/Q

I (N,

Qj (2.8) where:

D, = air dose due to gamma emissions for noble gas radionuclides (mrad).

D, - air dose due to beta emissions for noble gas radionuclides (mrad).

X/Q = atmospheric dispersion to the controlling SITE BOUNDARY location (sec/m3). 4 Q, = cumulative release of noble gas radionuclide i over the period ofinterest (uCi).

M, = air dose factor due to gamma emission from noble gas radionuclide i (mrad /yr per uCi/m3, from Table 2-1.

l N, = air dose factor due to beta emissions from noble gas radionuclide i (mradlyr per J uCi/m3, Table 2-1).

3.17E-08 = conversion factor (yr/sec).

2.4.2 Simplified Dose Calculation for Noble Gases 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 justificatin of this simplified method).

l I

3.17E-08 D, =

X/Q

M,

I Q, (2.9) 0.50 l

3.17E-08 1

l D, =

X/Q

N,

I Q, (2.10) )

0.50 where:

i 13

~

Hope Creek ODCM Rev 17 M,, = 8.1E+03, effective gamma-air dose factor (mrad /yr per uCi/m3).

N,y = 8.5E+03, effective beta-air dose factor (mradlyr 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.

Actual meteorological conditions concurrent with the release period 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.

2,5 Radiciodine and Particulate Dose Calculations - 10 CFR 50 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 < 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

SF,

I (R,,,

Q) (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 i (mrem /yr per uCi/m3 or m2 - mrem /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,, were derived in accordance with the methods described in NUREG-0133.

Q, = cumulative release over the period ofinterest for radionuclide i -- I-131, I-133, H-3 or radioactive material in particulate form with half-life greater than 8 days (uCi).

S f, = annual seasonal correction factor to account for fraction of the year that the applicable exposure pathway does not exist.

(1) For milk and vegetation exposure pathurvs:

j = A six month fresh vegetation and grazing season (May through October)= 0.5 (2) For inhalation and ground plane exposure pathways:

= 1.0 14

~

Hope Creek ODCM Rev 17 I 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.

l 2.5.2 Simplified Dose Calculation for Radiolodines and Particulates 1

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 andjustification of this simplified method).

D., = 3.17E-08

W

SF,

RI-131

I Q, (2.12) where:

D., = maximum organ dose (mrem).

RI-131 = I-131 dose parameter for the thyroid for the identified controlling pathway. f

= 1.05E+12, infant thyroid dose parameter with the cow-milk pathway controlling .

(m2 - mrem /yr per uCi/sec).

W = D/Q for radioiodine,2.87E-101/m2.

Q, = cumulative release over the period ofinterest 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 i annual land-use census (Technical Specification 3.12.2). Othenvise, the dose will be evaluated based on the predetermined controlling pathways as identified in Table 2-3.

2.6 Gaseous Effluent Dose Projection Technical Specification 3.11.2.4 requires that the VENTILATION EXHAUST TREATMENT SYSTEM be used to reduce radioactive material levels prior to discharge when projected doses in 31-days exceed:

- 0.2 mrad to air from gamma radiation, or (

- 0.4 mrad to air from beta radiation, or [

- 0.3 mrad to any organ of a MEMBER OF THE PUBLIC The applicable gaseous processing systems for maintammg radioactive material releases ALARA are the Gaseous Radwaste Treatment System and Exhaust Treatment System as delineated in Figures 2-1 and 2-2.

I 15

l Hope Creek ODCM Rev 17 l>6se projection are performed at least once per 31-days by the following equations:

D,, = (D,/ d)

31d (2.13)

D, = (D, / d)

31d (2.14)

D , = (D., / d)

31d (2.15) 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, = marimum organ dose projection for current 31-day period (mrem).

D., = maximum organ dose to date for current calendar quarter as determined by equation (2.11) or (2.12)(mrem).

d = number of days in current calendar quarter at the end of the release.

31d = the number of days of concem.

3.0 SPECIAL DOSE ANALYSIS 3.1 Doses Due to Activities Inside the SITE BOUNDARY In accordance with Technical Specibcation 6.9.1.7. the Radioactive Effluent Release Report (RERR) submitted by May 1st of each year shall include an assessment of radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY.

The calculation methods as presented in Sections 2.4 and 2.5 may be used for determining the maximum potential dose to a MEMBER OF THE PUBLIC 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 cf NRC reporting. However, a follow-up evaluation shall be performed when the data becomes available.

}

16

~

Hope Creek ODCM Rev 17 3.2 Total Dose to MEMBERS OF THE PUBLIC - 40 CF2190 The Radioactive Effluent Release Report (RERR) submitted by May 1st of each year sha!! 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 effluents and direct radiation from on site sources). For the likely most exposed MEMBER OF THE PUBLIC in the vicinity of Artificial Island, the sources of exposure need only consider the Salem Generating station and the Hope Creek Generating Station: No other fuel cycle facilities contribute to the MEMBER OF THE PUBLIC dose for the AnificialIsland vicinity.

The dose contribution from the operation of Salem Generstmg Stations will be estimated based on the methods as presented in the Salem Offsite Dose Calculation Manual (SGS ODCM).

As appropriate for demonstrating / evaluating compliance with the limits of Technical Specification 3.11.4 (40 CFR 190), the results of the environmental monitoring program may be used for providing data on actual measured levels of radioactive material in the actual -

pathways of exposure.

3.2.1 Emuent Dose Calculations For purposes ofimplementing the surveillance requirements of Technical Specification 3/4.11.4 and the reponing 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 ODCM; 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 concunent with the release period under evaluation may be used.

3.2.2 Direct Exposure Dose Determination ....

. 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) ared/or by the use of a radiation transport and shielding caletdation method. ,

Only during a non-typical condition will there exist any powntial for significant on-site sources at Hope Creek that would yield potentially significant off site doses (i.e.., in excess of 1 mrem per year to a MEMBER OF THE PUBLIC), that would require detailed evaluation for demonstrating compliance with 40 CFR 190. However, shotdd a situation exist whereby the direct exposure contribution is potentially significant, on-site measurements, off-site measurements and/or calculational techniques will be used for determination of dose for assessing 40 CFR 190 compliance. !

l l'I I 4

Hope Creek ODCM Res l' 4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 4.1 Sampling Program The operational phase of the Radiological Environmental Monitoring Program (REMP) is conducted in accordance with the requirements of Appendix A Technical Specif; cation 3.12.

The objectives of the program are:

- To determine whether any significant increases occur in the concentration ofradionuclides in the critical pathways of exposure in the vicinity of Anificial Island;

- To determine if the operatic.n of the Hope Creek Generatmg Station has resulted in any increase in the inverttory oflong lived radionuclides in the environment;

- To detect any changes in the ambient gamma radiation levels; and

- To verify that HCGS operations have no detrimental effects on the health and safety of the public or on the environment.

The sampling requirements (type of samples, collection frequency and analysis) and sample locations are presented in Appendix E.

NOTE: No public drinking water samples or irrigation water samples are taken as these pathways are not directly effected by liquid emuents discharged from Hope Creek Generating Station.

4.2 Interlaboratory Comparison Program Technical Specification 3.12.3 requires analyses be performed on radioactive material supplied as pan of an Interlaboratory Comparison. Panicipation 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 6.9.1.7.

5.0 HCGS EXPLOSIVE GAS MONITORING PROGRAM The Hope Creek Explosive Gas Monitoring program was moved within the Hope Creek Technical Specifications to section 6.8.4.d. This was performed in Technical Specification Amendment 91.

Details of the Hope Creek Explosive Gas Monitoring program are maintained in station implementing procedures and are controlled by the 50.59 safety evaluation and procedure processes.

18

i; 1

Hope Creek ODCM Rev 1i FIGURE 1-1 LIQUID RADWASTE TREATMENT AND MONITORING SYSTEM lCire Water Dewatering l l Cooling Tower ,

Supply VM Dratas same Basin I4 Colledor Tanks (2) -

'j Equipment Equipment Equipment Drain ~ ~

Drain Filter Drain Domin SampleTanks (2) 5 Waste I

~ Surge j Tank l

Condensate _

Storage Tank Floor Drain Floor Floor Floor Drain ,

Collector Tanks (2) Drain Filter Drain Domin Sample Tanh (2) i l l

l See Note 1 l-Chemical

\\\\\

\

, \\\ \\\'

Kecepthq1,idKio\ \ 'A D N

f Waste Tank $ x et

\

\ oiotto,+4vapora{on

\\ \\\ \ l

\\

\\\\\\\\\\\\N

\ \ \ \ soli e\

l Detergent Drain Detergent a1 Drain Filter

Tanks (2)

RE 4861 -

Log: RE = Radiation Effluent Monitor 4861= Liquid Radwaste Monitor RE 8817 = Cooling tower Blowdown Monitor 8817 '

qs!nu Ct u.mpe w bww:g -ctb.,b Note 1: Speerfied equipment is installed but S

not in use. Equipment is pending To Delaware River abandonment per DCP 4EC-3634.

19 I

[,

Hope Creek ODCM Rev 17 FIGURE 1-2 SOLID RADWASTE PROCESSING SYSTEM see Note i NN'x 'xNNN'NNNNN' NsAe '~ x NNNNNNN' mo,e , speee. o_ o , ,, ,m.t.,,ee om, o, .. se NN NN'N'NMW'NN' : *re.'at!" """" "~"" '

NNN NNN'MLNN' '

NNNNNNN'NN N

NN'S NNN'N xN N %,N NN N NNw' sA u g . m N N p tR'

&* ; p t N .'

N'xU'NN'xNNN' sNN' NN sNNN ve, NN' NN""ATN NNN M N' .

N'sxh'x

'NY@A'M^NNN sNN$N'N' N 1NN' NNN.NNNNNN s s's' Fl0or I Dran c=:a.:- .. .t. s . ..

Phase Separator '

~-

n See Note 1

\\\ \' \ \l\ \

ct;%",;" ::

den.3sdNcQ%i'N sssssssssx, s Waste Collector

\ Sport Resin (Figure 1 1) w 20 l

f \

]

Hope Creek ODCM Rev ij TABLEl1 PARAMETERS FOR LIQUID ALARM SETPOINT DETERMINATION i 1

Actual Default Parameter Value Value Units Comments MPCe Calc 7.92E 5' uCi/mi Calculated for each batch to be released MPC1131 3.0E-07 N/A uCi/ml Taken from 10 CFR 20, Appendix B.Tabld Column 2 (Appendix F) J C. Measured N/A uCi/ml Taken from gamma spectral analysis

]

ofliquid effluent MPC, Measured N/A uci/mi Taken from 10 CFR 20,

(

Appendix B, Table II, Column 2 l (Appendix F)

CTBD Measured 12000 gpm Cooling tower blowdown discharge I

, RR Measured 176 gpm or Determined prior to release, release rate can -

adjusted for Technical Specification compli 1300 gpm(CST)

Estimated 100 gpm(TBCW) Maximum flow rate with both pumps runal (50 gpm each) l SP (Setpoinu)

A)RE4861 Cale 1.08E-03 uCi/ml Default alarm setpoints; more conser values may be used as appropnate and desirk for ensuring regulatory compliance and for i maintaining releases ALARA RE8817 Cale 1.58E-05 uCi/mi f

(

RE4557 Calc 2.40E-06 uCi/mi Maximum alarm serpoint fu continua release; more conservative value may established by plant procedure B)RE4861 Cale 1.46E-04 uCi/mi These setpoints are for condensate storage t releases RE8817 - Calc 1.58E-05 uCi/mi

See Appendix A for basis 21 s

\

[

Hope Creek ODCM Rev 17 TABLE l-2 SITE RELATED INGESTION DOSE COMMITMENT FACTOR, A, (FISH AND INVERTEBRATE CONSUMPTION)

(mrenvhr per uCi/ml)

Nuclude lione 1.iwr ~l .Ilody I h3 roid H-3 Isiduc3 Lung GI-LLI 2.82E-l 2.82E-1 2.82E-1 2.82E-1 2.82E-l C-14 1.45E+4 2.82E-1 2.90E+3 2.90E+3 2.90E+3 2.90E+3 Na-24 2.90E+3 2.90E-3 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 P-32 4.69E+6 2.91 E+5 1.81E+5 - -

Cr-51 -

5.27E+5 5.58E+0 3.34E+0 1.23 E+0 7.40E+0 Mn-54 1.40E-3 7.06E+3 1.35E+3 -

2.10E+3 Mn-56 2.16E-4 1.78E+2 3.15E+1 -

2.26E+2 Fe-55 5. l l E+4 3.53E+4 5.67 E-i--"

8.23E+3 - -

197E+4 Fe-59 8.06E+4 2.03E-4 o 1.90E+5 7.27E+4 - -

5.30E+4

~

Co-57 6.32E-5 1.42E+2 2.36E+2 - -

Co-58 3.59E-3 6.03 E+2 1.35E+3 - -

Co-60 1.22E+4 1.73 E+3 3.82E+3 - - '

Ni-63 3.25E+4 4.96E+4 3.44E+3 1.67E+3 - - -

Ni-65 7.18 E+2 2.02E+2 2.62E+1 1.20E+1 - -

Cu-64 6.65 E-2 2.14E+2 1.01E+2 -

5.40E+2 Zn-65 1.83E-4 :

1.61 E+5 5.13 E+5 2.32E+5 -

3.43E+5 -

3.23 E-5 Zn-69m 5.66E+3 1.36E+4 1.24E+3 -

8.22E+3 Br-82 8.29E-5 4.07E+0 - - -

4.67E-0 Br-83 - -

7.25E-2 - - -

~

1.04 E- 1 Br-84 - -

- 9.39E 2 - - -

7.37E 7 I Br-85 - -

3.86E-3 - - - - '

Rb-86 -

6.24E+2 2.91 E+2 - - '

I Rb-88 1.23 E-2 1.79E+0 9.49E 1 - -

Rb-89 2.47E 11 1.19E+0 8.34E-1 - -

Sr89 6.89E-14 i 4.99E+3 -

1.43E+2 -

Sr-90 8.00E-2 1.23 E+5 -

3.01 E+4 - -

Sr 91 3.55E-3 9.18E+1 -

3.71 E+0 -

i Sr-92 4.37E-2 i 3.4SE+1 -

1.51 E+0 -

Y-90 6.90E-2 6.06E+0 -

1.63 E-1 - '

6.42 E-4 Y-91 m 5.73E-2 -

2.22E-3 - - -

1.68E-1 i Y 91 8.88E+1 -

2.37E+0 -

Y-92 4.89E-4 5.32E-1 -

1.56E-2 -

Y 93 9.32E-3 i 1.69E+0 4.66E-2 - -

5.35 E+4 >

Zr-95 1.59E+1 5.1 iF,0 3.46E+0 -

8.02E+0 -

1.62E-4 Zr-97 8.81 E-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 Nb-97 1.51E-6 i 3.75E+0 9.49E-1 3.46E-1 -

1.1 I E+0 -

3.50E-3 !

Mo-99 -

1.28E+2 2.43E+1 -

2.89E+2 -

2.96E-2 :

Tc-99m 1.30E 2 3.66E-2 4.66E-1 -

5.56E-1 1.79E-2 2.17 E- 1 Tc-101 1.33E-2 1.92E-2 1.88E-1 -

3.46E-1 9.81 E-3 5.77E-14 i As 76 4.38E+2 1.16E+3 5.14E+3 3.42E+2 1.39E+3 3.58E+2 4.30E-4 i 22 1

r Hope Creek ODCM Rev 1]

TABLE l-2 (cont'd) ,

SITE RELATED INGESTION DOSE COMMITMENT FACTOR, A.

(FISH AND INVERTEBRATE CONSUMPTION)

(mrem /hr per uCi/ml) l N uclide lione le er I .llmh t hy roid. ~ iddney 1.ung GI-l.t.1 Ru-103 1.07E+2 -

4.60E+1 -

4.07E+2 -

1.25E+4 Ru-105 8.89E+0 -

3.51 E+0 -

1.15E+2 -

5.44E+3 Ru-106 1.59E+3 -

2.01E+2 -

3.06E+3 -

1.03E+5

~

Rh-103m - - - - - - -

Rh-106 - - - - - - -

Ag-l 10m 1.56E+3 1.45E+3 8.60E+2 -

2.85E+3 -

5.91E+5 Sb-124 2.77E+2 5.23 E+0 1.10E+2 6.71 E-1 -

2.15 E+2 7.86E+3 Sb-125 1.77E+2 1.98E+0 4.21 E+1 1.80E-1 -

1.36E+2 1.95E+3 0 Te-125m 2.17E+2 7.86E+1 2.91 E+1 6.52E+1 8.82E+2 -

8.66E+2

Te-127m 5.48E+2 1.96E+2 6.68E+1 1.40E+2 2.23 E+3 -

1.84E+3 Te 127 8.90E+0 3.20E+0 1.93 E+0 6.60E+0 3.63E+1 -

7.03 E+2 Te-129m 9.31 E+2 3.47E+2 1.47E+2 3.20E+2 3.89E+3 -

4.69Er3 J Te-129 2.54E+0 9.55E-1 6.19E-1 1.95E+0 1.07E+ 1 - 1,92E+0 1 Te-131m 1.40E+2 6.85 E+1 5.71 E+ 1 1.08E+2 6.94E+2 -

6.80E+3 I Te-131 1.59E+0 6.66E 1 5.03E-1 1.31E+0 6.99E+0 -

2.26E-1 I Te-132 2.04E+2 1.32E+2 1.24E+2 1.46E+2 1.27E+3 -

6.24E+3 1-130 3.96E+1 1.17E+2 4.61 E+1 9.91 E+3 1.82E+2 -

1.01E+2 <

I-131 2.18E+2 3.12E+2 1.79E+2 1.02E+5 5.35 E+2 -

8.23 E+ 1 ll l-132 1.06E+1 2.85E+1 9.96E+0 9.96E+2 4.54E+1 -

5.35E+0 1-133 7.45 E+1 1.30E+2 . 3.95 E+ 1 1.90E+4 2.26E+2 -

1.16E+2 1-134 5.56E+0 1.51 E+1 5.40E+0 2.62E+2 2.40E+ 1 -

1.32E 2 :

11-135 2.32E+1 6.08E+1 2.24E+ 1 4.01 E+3 9.75E+1 -

6.87E+ 1 i

! Cs 134 6.84 E+3 1.63E+4 1.33 E+4 -

5.27E+3 1.75E+3 2.85E+2 i l Cs-136 7.16E+2 2.83E+3 2.04E+3 -

1.57E+3 2.16E+2 3.21 E+2 6 Cs-137 8.77E+3 1.20E+4 7.85E+3 -

4.07E+3 1.35E+3 2.32E+2 l

! Cs-138 6.07E+0 1.20E+ 1 5.94E+0 -

8.81 E+0 8.70E- 1 5.12E-5 i Ba-139 7.85E+0 5.59E-3 2.30E-1 -

5.23E-3 3.17E-3 1.39E+1 Ba-140 1.64E+3 2.06E+0 1.08E+2 -

7.02E-1 1.18E+0 3.38E+3 1 Ba 141 Ba-142 3.81 E+0 1.72E+0 2.88E-3 1.77E 3 1.29E 1 1.08 E-1 2.68E-3 1.50E-3 1.63E-3 1.80E-9 I 1.00E-3 2.43E-18 l-La 140 1.57E+0 7.94E-1 2.10E-1 - - -

5.83 E+4 La 141 8.06E-2 3.67E-2 9.13 E-3 - - -

2.68E+2 [

Ce-141 3.43 E+0 2.32E+0 2.63E-1 - 1.08E+0 -

8.86E-3 i Ce-143 Ce-144 6.04E-1 1.79E+2 4.46E+2 7.47E+ 1 4.94E-2 9.59E+0 1.97E-1 4.43 E+1 1.67E+4 6.04E-4

)

(

Pr-143 5.79E+0 2.32E+0 2.87E-1 -

1.34E+0 -

2.54E+4 i Pr-144 1.90E-2 7.87E-3 9.64E-4 4.44E-3 2.73E-9

)

Nd 147 3.96E+0 4.58E+0 2.74E-1 - 2.68E+0 -

2.20E+4

( W-187 9.16E+0 7.66E+0 2.68E+0 - - -

2.51E+3

)

i Np-239 3.53E-2 3.47E-3 1.91 E-3 - 1.08E-2 -

7. I 1 E+2 23

g l

i l l

Hope Creek ODCM Rev 17 TABLE l-3 BIOACCUMULATION FACTORS (pCi/kg per pCi/ liter)* l 1

El \ll NI 5 \l. I % T I ER FI5il H

S\1flWNIERin ERIEHRATEN

~

l 9.0E-01 9.3 E-01 l i

C 1.8E+03 1.4E+03 i Na 6.7E-02 1.9E-01 l P 3.0E+03 '

3.0E+04 Cr 4.0E+02 2.0E+03 '

Mn 5.5E+02 4.0E+02 Fe 3.0E+03 2.0E+04 i Co 1.0E+02 1.0E+03 ,

Ni 1.0E+02 2.5E+02 Cu 6.7E+02 1.7E+03 Zn 2.0E+03 5.0E+04 Br 1.5E-02 3. l E+00 Rb 8.3 E+00 1.7E+0 i Sr 2.0E+00 2.0E+01 Y 2.5 E+01 1.0E+03 I Zr 2.0E+02 8.0E+01 Nb 3.0E+04 1.0E+02 Mo 1.0E+01 1.0E+01 4 Tc 1.0E+01 5.0E+01 Ru 3.0E+00 1.0E+03 i Rh 1.0E+01- 2.0E+03 i Ag 3.3E+03 3.3 E+03 Sb 4.0E+01 5.4E+00 i i Te 1.0E+01 1.0E+02 i I 1.0E+01 5.0E+01 i Cs 4.0E+01 2.5E+01

Ba 1.0E+01 1.0E+02 ILa 2.5 E+01 1.0E+03 I Ce 1.0E+01 6.0E+02 i Pr 2.5E+01 1.0E+03 Nd 2.5 E+01 1.0E+03 lW 3.0E+01 3.0E+01 l i Np 1.0E+01 1.0E+01 l As 3.3 E+02 3.3 E+02 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.

24

~

7 1

R v

e

. :j: ,

.[

~

M _ g -

_ C in l

p -

_ D m _

_ O a _ _

S m

k

_d e r d

- e _

n . e ' _

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C dr .

- S _ -

e a p M u o R G m . ,

l R _tn e l

e t s

- y m

~

t a S m e

[ -

e r

l a

- t o

_ e r

c r _

- P a s h n

C s

e g a t g l n - _

a O l

i e .

r i k r b s

e

. - c e - d

- a

t a m - F P e A n

=

h A r

r e R e wP E e in p

-H

_ m b p -

b m -

m o o

c c

e ,

M e R %

E R a

2 T r

. S o Y

i.

- , ':: =

_ S M.

} 5 T -

. N T

Y -

Z 2 -

_ E - C M -

t n) e2 T ,

V2

- 1 A t ng 2

E lai F E R P(

T n

r R E e _

U T t

a G

I S h e

F A e r i .:-*:

W n

P D

A R

S n

U -

O E -r! j: ;! _

S _

A <

G -

) .

2-2 e) "

C'w. n ig F

( t_

W2s (

V P

lapm nu (L,""s =

S- )

._ hP - " r*

n 4_\ W ^

I r

e s

mn a de

, Mn o -

c

Hope Creek ODCM Rev 17 FIGURE 2 2 VENTILATION EXHAUST TREATMENT SYSTEM

' RE .

Oaseous Radvueme .

Tresenent Symem .x i (from Figure 21) -*

Untreated Verelation ; North Plant Ar Sources Vent owa De

. E*8 ? See Note 1 Auxsliary Baleng RC Radweste Area R H 48f58 Venclaton (Tymcas of 3)

l Concen are l l Demmeranzer R H C H ,' &Soutn Rant Room Ar l Vent Face Chase Air '..Compartrrent Exn aust System (TBCE) !

...............................J Feedwater Heater Room Air Turece Budoeg Exnaust .

TB Od Storage Roem Exnsust Gianc Se al Exnaust Meenanical vacuum Rurre Exnaus Wom F'gure 2.t) **************-------------*-----*---*'

l Reactor Buddeg Venclaten Exnaus System:

R H l l Reactor Builong 1 RE

& l !

A'r '

t..........(Typcal of 3)

........................... .......................,l4811A l FRVS Recrc Sysem l l FRVS Vent !

l I

. . I. l J H C H .

C H 5 FRVS $ynem Vent

, 1 : ;

j (Tymcalof 6) j

[ (Typcal of 2 ) !

, ; ....................... i

....................................J R Rougning Fdter H HEPA Fdter C a CharcoalFdter RE a Ra$ anon Emuent Morntor Note 1: Specmed equipmeft is installed but not h use.

EqLipment pending ebendonmeft per DCP 4EC.3634.

26

Hope Creek ODCM Rev 1 TABLE 2-1 DOSE FACTORS FOR NOBLE GASES Total Body Skin Gamma Air Beta Air Dose Factor Dose Factor Dose Factor Dose Factor Ki Li Mi ' Ni 1 Radionuclide uCi/m3) uCi/m3) uCi/m3) uCi/m3 l Kr 83m 7.56E-02 -

1.93E+01 2.88E+02 >

l l Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.51 E+01 1.34E+03 1.72E+01 1.95E+03 l

Kr-87 5.92E+03 . 9.73E+03 6.17E+03 1.03E+04 l Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 -

I l Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04

[

l l Kr 90 1.56E+04 -7.29E+03 1.63E+04 7.83E+03 '

l l Xe131m 9.15E+01 4.76E+02 1.56E42 1. I 1E+03 Xe 133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe 133 2.94E+02 3.06E+02 3.53 E+02 1.05E+03 Xe 135m 3.12E+03 7.l lE+02 3.36E+03 7.39E+02 -

Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 1

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 27 .

F l

l Hope Creek ODCM Rev 17 TABLE 2-2 j PARAMETERS FOR GASEOUS ALARM j SETPOINT DETERMINATION HOPE CREEK )

Actual Default Parameter Value Value Units Comments l l

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 VF (SPV) Measured 440,180 ft'/ min Maximum Operation VF (FRVS) Measured 9000 ft3/ min Maximum Operation AF (NPV) Coordinated 0.2 Unitiess Administrative with SGS allocation factor t'o ensure releas' do not exceed AF (SPV) 0.2 Unitiess release rate limit AF (FRVS) 0.1 Unitiess C, Measured N/A uCi/cm' K, Nuclide N/A mrem /yr Table 2-1 Specific per uCi/m' L, Nuclide N/A mrem /yr Table 2-1 Specific per uCi/m')

M,Nuclide N/A mradlyr Table 2-1 Specific per uCi/m' SP: NPV Calculated 2.43E-4 uCi/cc Default alarm Setpoints; SPV Calculated {

2.31 E-5 uCi/cc more conservative values ;

FRVS Calculated 5.65E-4 uCi/cc may be used as deemed appropriate for ensuring .

ALARA & regulatory compliance l

28

I Hope Creek ODCM Rev 1 TABLE 2-3 l

CONTROLLING LOCATIONS, PATHWAYS AND ATMOSPHERIC DISPERSION FOR DOSE CALCULATIONS

Tech Spec Location Pathway (s) Ane Group (sec/m3) (1/m2)

'3.11.2.1 a Site Boundary Noble Gases N/A 2.67E-% N/A 0.5 Mile, N direct exposure 3.11.2.1 b Site Boundary Inhalation Child 2.67E-06 N/A 0.5 Mile, N 3.11.2.2 Site Boundary Gamma-Air N/A 2.67E-06 N/A '

O.5 Mile, N Beta-Air

]

3.11.2.3 Residence / Milk, ground Infant 7.2E-08 2.87E-10 Dairy - 4.9 plane and Miles, W inhalation l

The identified controlling locations, pathways and atmospheric dispersion are from the Artificial Island Radiological Morutoring Program and the Hope Creek FSAR.

)

l 29 l

i 1

Hope Creek ODCM Rev 17 !

Table 2-4 Pathway Dose Factors - Atmospheric Releases R(io), Inhalation Pathway Dose Factors - ADULT '

(mrem /yr per uCi/m3)

H-3 l- l 1.26E+3 EE 1.26E+3 1.26E+3

.un:;

1.26E+3 GI-l.l.i.

1.26E+3 T. Bod, I 1.26E+3 C-14 l 1.82E+4 l 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 l P-32 l 1.32E+6 l 7.71E+4 - - -

8.64E+4 5.01E+4 Cr-51 l -

l -

5.95E+1 2.28E+1 1.44E+4 3.32E+3 1.00E+2 Mn-54 l l 3.96E+4 -

9.84E+3 1.40E+6 7.74E+4 6.30E+3 Fe-55 l 2.46E+4 l 1.70E+4 - -

7.21 E+4 6.03E+3 3.94E+3 Fe-59 l 1.18E+4 l 2.78E+4 - -

1.02E+6 1.88E+5 1.06E+4 Co-57 l l 6.92E+2 - -

3.70E+5 3.14E+4 6.71 E+2 l Co-58 l -

l 1.58E+3 - -

9.28E+5 1.06E+5 2.07E+3 Co-60 l -

l 1.15E+4 - -

5.97E+6 2.85E+5 1.48E+4 l Ni-63 l 4.32E+5 l 3.14E+4 - -

1.78E+5 1.34E+4 1.45E+4 . l Zn 65 l 3.24E+4 l 1.03E+5 -

6.90E+4 8.64E+5 5.34E+4 4.66E+4 Rb-86 l -

l 1.35E+5 - - -

1.66E+4 5.90E+4 Sr 89 l 3.04E+5 l - - -

1.40E+6 3.50E+5 8.72E+3 iSr90 l 9.92E+7 l - - -

9.60E+6 7.22E+5 6.10E+6 I Y-91 l 4.62E+5 - - -

1.70E+6 3.85E+5 1.24E+4 i j Zr 95 1.07E+5 3.44E+4 - 5.42E+4 1.77E+6 1.50E+5 2.33E+4 l Nb-95 1.41 E+4 7.82E+3 -

7.74E+3 5.05E+5 1.04E+5 4.21 E+3

> Ru 103 1.53E+3 - -

5.83E+3 5.05E+5 1.10E+5 6.58E+2 l Ru 106 6.91 E+4 ,

1.34E+5 9.36E+6 9.12E+5 8.72E+3 4 l Ag 110m 1.08E+4 1.00E+4 -

1.97E+4 4.63 E+6 3.02E+5 5.94E+3

! Sb-124 l 3.12E+4 5.89E+2 7.55E+1 -

2.48E+6 4.06E+5 1.24E+4 i Sb-125 l 5.34E+4 5.95E+2 5.40E+1 -

1.74 E+6 1.01E+5 1.26E+4 i Te 125m 3.42E+3 1.58E+3 1.05E+3 1.24E+4 3.14E+5 7.06E+4 j 4.67E+2

Te 127m 1.26E+4 5.77E+3 3.29E+3 4.58 E+4 9.60E+5 1.50E+5 j1.57E+3 i Te 129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 1.16E+6 3.83E+5 l 1.58E+3

.I 131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 -

6.28E+3 l 2.05E+4

' Cs 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 1.20E+4 1.17E+4 1.10E+5 I Cs-137 4.78E+5 6.21 E+5 -

2.22E+5 7.52E+4 8.40E+3 4.28E+5 l Ba 140 3.90E+4 4.90E+1 -

1.67E+1 1.27E+6 2.18E+5 2.57E+3 I Cc 141 1.99E+4 1.35 E+4 -

6.26E+3 3.62E+5 1.20E+5 1.53E+3 i Ce 144 3.43 E+6 1.43E+6 -

8.48E+5 7.78 E+6 l 8.16E+5 l1.84E+5 l Pr 143 9.36E+3 l 3.75E+3 -

2.16E+3 2.81E+5 2.00E+5 l 4.64E+2 l Nd 147 5.27E+3 l 6.10E+3 -

3.56E+3 2.21E+5 1.73E+5 i 3.65E+2 30

l 1

Hope Creek ODCM Rev 1 Table 2-4 (cont'd) i Pathway Dose Factors - Atmospheric Releases R(io), Inhalation Pathway Dose Factors - TEENAGER (mrem /yr per uCi/m3) )

N udul hpem uilne .u n.:

. l- 1. L 1 T.Ilmi H-3 -

l 1.27E+3 1.27E+3 1.27E+3 1.27E+3 J 1.27E+3 l 1.27E+3 C-14 2.60E+4 l 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 l 4.87E+3 P-32 1.89E+6 l 1.10E+5 - - -

9.28E+4 l 7.16E+4 l Cr-51 -

l -

7.50E+1 3.07E+1 2.10E+4 3.00E+3 l 1.35E+2 Mn-54 -

l 5.11E+4 -

1.27E+4 1.98E+6 6.68E+4 l 8.40E+3 Fe-55 3.34E+4 } 2.38E+4 - -

1.24E+5 6.39E+3 I 5.54E+3 Fe-59 1.59E+4 l 3.70E+4 - -

1.53E+6 1.78E+5 1.43E+4 Co-57 -

l 6.92E+2 - -

5.86E+5 3.14E+4 9.20E+2 Co-58 -

l 2.07E+3 - -

1.34E+6 9.52E+4 2.78E+3 Co-60 -

l 1.51E+4 - -

8.72E+6 2.59E+5 1.98E+4 Ni 63 5.80E+5 l 4.34E+4 - -

3.07E+5 1.42E+4 1.98E+4 .

Zn 65 3.86E+4 l 1.34E+5 -

8.64E+4 1.24E+6 4.66E+4 6.24E+4 Rb-86 -

l 1.90E+5 - - -

1.77E+4 8.40E+4 Sr 89 4.34E+5 l - - -

2.42E+6 3.71 E+5 1.25E+4 Sr-90 1.08E+8 l - - -

1.65E+7 7.65E+5 6.68E+6 Y-91 6.61 E+5 l - - -

2.94E+6 4.09E+5 1.77E+4 Zr-95 1.46E+5 l 4.58E+4 = 6.74E+4 2.69E+6 - 1.49E+5 3.15E+4 Nb-95 1.86E+4 l1.03E+4 -

1.00E+4 7.51 E+5 9.68E+4 5.66E+3 Ru 103 2.10E+3 - -

7.43 E+3 7.83 E+5 1.09E+5 8.96E+2 i Ru 106 9.84E+4 - -

1.90E+5 1.61 E+7 9.60E+5 1.24E+4 Ag-110m 1.38E+4 1.31 E+4 -

2.50E+4 6.75E+6 2.73 E+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 i 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 4.05 E+5 2.25E+3 1-131 3.54E+4 4.91 E+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 -

3.04E+5 1.21 E+5 8.48E+3 3.l l E+5 l Ba-140 5.47E+4 6.70E+1 -

2.28E+1 2.03E+6 2.29E+5 3.52E+3 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 l Pr 143 1.34E+4 5.31 E+3 -

3.09E+3 4.83E+5 2.14E+5 6.62E+2 {

Nd 147 7.86E+3 l 8.56E+3 - 5.02E+3 3.72E+5 1.82E+5 5.13E+2 31 l

E l

l

{

Hope Creek ODCM Rev 17 j l i Table 2-4 (cont'd) l Pathway Dose Factors - Atmospheric Releases R(io), Inhalation Pathway Dose Factors - CHILD i

(mremlyr per uCi/m3) l 6 H-3 i "h,s ruit Gine g pl-II.

l l 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 C-14 l 3.59E+4 l 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 P-32 6.73E+3 l l 2.60E+6 l 1.14E+5 - - -

4.22E+4 Cr-51 -

9.88E+4 l l -

8.55E+1 l 2.43E+1 1.70E+4 1.08E+3 Mn-54 -

1.54E+2 l l l 4.29E+4 -

1.00E+4 1.58E+6 2.29E+4 Fe-55 9.51 E+3 l l 4.74E+4 l 2.52E+4 - -

1.11E+5 2.87E+3 Fe-59 7.77E+3 } ,

l 2.07E+4 l 3.34E+4 - -

1.27E+6 7.07E+4 1.67E+4 l Co-57 l -

l 9.03E+2 - -

5.07E+5 1.32E+4 1.07E+3 Co-58 l -

l 1.77E+3 - -

1.1IE+6 3.44E+4 3.16E+3 Co-60 l -

l 1.31E+4 - -

7.07E+6 9.62E+4 2.26E+4 Ni 63 l 8.21E+5 l 4.63E+4 - -

2.75E+5 6.33E+3 2.80E+4 Zn-65 ' 4.26E+4 1.13E+5 -

7.14E+4 9.95E+5 1.63E+4 7.03E+4 Rb-86 -

1.98E+5 - -

7.99E+3 1.14E+5 Sr89 5.99E+5 - - -

2.16E+6 1.67E+5 1.72E+4 Sr90 1.01 E+8 - - -

1.48E+7 3.43 E+5 6.44E+6 Y-91 9.14E+5 - -

2.63E+6 1.84E+5 2.44E+4 i Zr-95 1.90E+5 4.18E+4 -

5.96E+4 2.23E+6 6. l l E+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 l Ag-110m 1.69E+4 1.14E+4 -

2.12E+4 5.48E+6 1.00E+5 9.14E+3

! Sb-124 5.74E+4 7.40E+2 1.26E+2 -

3.24 E+6 1.64E+5 2.00E+4 i Sb-125 9.84E+4 7.59E+2 9.10E+ 1 -

2.32E+6 4.03 E+4 2.07E+4 l Te-125m 6.73E+3 2.33E+3 1.92E+3 -

4.77E+5 3.38E+4 9.14E+2 i Te-127m 2.49E+4 8.55E+3 6.07E+3 6.36E+4 1.48E+6 7.14E+4 3.02E+3

Te 129m 1.92E+4 6.85E+3 6.33E+3 5.03 E+4 1.76E+6 1.82E+5 3.04E+3 i: 1-131 4.81 E+4 4.81E+4 1.62E+7 7.88E+4 -

2.84E+3 2.73E+4 i ! Cs 134 6.51 E+5 1.01 E+6 -

3.30E+5 1.21 E+5 3.85E+3 2.25E+5 Cs 136 6.51 E+4 1.71E+5 -

9.55E+4 1.45E+4 4.18E+3 1.16E+5 Cs 137 9.07E+5 8.25E+5 -

2.82E+5 1.04E+5 3.62E+3 1.28E+5 Ba140 7.40E+4 6.48E+ 1 -

2. I 1 E+ 1 1.74E+6 1.02E+5 4.33E+3 Ce-141 3.92E+4 1.95E+4 -

8.55E+3 5.44E+5 5.66E+4 2.90E+3 Ce-144 6.77E+6 2.12E+6 -

1.17E+6 1.20E+7 3.89E+5 3.61E+5 l Pr 143 1.85E+4 5.55E+3 -

3.00E+3 4.33E+5 9.73E+4 9.14E+2

> Nd 147 1.08E+4 8.73E+3 -

4.81 E+3 3.28E+5 8.21 E+4 6.81 E+2 32 L

I Hope Creek ODCM Res 1-J Table 2-4 (cont'd) l Pathway Dose Factors - Atmospheric Releases R(io), Inhalation Pathway Dose Factors - IhTANT <

(mrem /yr per uCi/m3) hyron Udnt .un; .1-I.1.1 .

T.lkly H-3 l -

6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 !

C 14 l 2.65E+4 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 P-32 l 2.03E+6 1.12E+5 - - -

1.61E+4 7.74E+4 Cr-51 l 5.75E+1 1.32E+1 1.28E+4 3.57E+2 8.95E+1 Mn-54 l 2.53E+4 -

4.98E+3 1.00E+6 7.06E+3 4.98E+3 Fe-55 l 1.97E+4 1.17E+4 - -

8.69E+4 1.09E+3 3.33E+3 ;

j Fe-59 1.36E+4 2.35E+4 - -

1.02E+6 2.48E+4 9.48E+3

Co-57 l

~

6.51 E+2 - -

3.79E+5 4.86E+3 6.41 E+2 Co-58 -

1.22E+3 - -

7.77E+5 1.I1E+4 1.82E+3 Co-60 -

8.02E+3 - -

4.51 E+6 3.19E+4 1.18E+4 i Ni 63 3.39E+5 2.04E+4 - -

2.09E+5 2.42E+3 1.16E+4.

l Zn 65 1.93 E+4 6.26E+4 -

3.25E+4 6.47E+5 5.14E+4 3.11 E+4

! Rb 86 -

1.90E+5 - - -

3.04E+3 8.82E+4 l Sr-89 3.98E+5 - - -

2.03E+6 6.40E+4 1.14E+4 lSr90 4.09E+7 - - -

1.12E+7 1.31E+5 2.59E+6 Y-91 5.88E+5 - - -

2.45E+6 7.03 E+4 1.57E+4

, Zr-95 1.15E+5 2.79E+4 -

3.1 I E+4 1.75E+6 2.17E+4 2.03E+4 F

Nb-95 1.57E+4 6.43 E+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 3.30E+4 5.00E+3 Sb-124 3.79E+4 5.56E+2 1.01E+2 -

2.65E+6 5.91 E+4 1.20E+4 i Sb-125 5.17E+4 4.77E+2 6.23 E+1 -

1.64E+6 1.47E+4 1.09E+4 Te 125m 4.76E+3 1.99E+3 1.62E+3 -

4.47E+5 1.29E+4 6.58E+2

Te-127m 1.67E+4 6.90E+3 4.87E+3 3.75E+4 1.31E+6 2.73E+4 2.07E+3 Te 129m 1.41E+4 6.09E+3 5.47E+3 3.18E+4 1.68E+6 6.90E+4 2.23E+3 1-131 3.79E+4 4.44E+4 1.48E+7 5.18 E+4 -

1.06E+3 1.96E+4 Cs 134 3.96E+5 7.03E+5 -

1.90E+5 7.97E+4 1.33E+3 7.45E+4

. Cs 136 4.83 E+4 1.35E+5 -

5.64E+4 1.18E+4 1.43E+3 5.29E+4 i Cs 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 i Ce 141 2.77E+4 1.67E+4 -

5.25E+3 5.17E+5 2.16E+4 1.99E+3 i Ce-144 3.19E+6 1.21 E+6 -

5.38E+5 9.84E+6 1.48E+5 1.76E+5

! 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 8.13 E+3 -

3.15E+3 3.22E+5 3.12E+4 5.00E+2 33

e l

Hope Creek ODCM Rev 17

]

Table 2-4 (cont'd; Pathway Dose Factors - Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors - ADULT (mrem /yr per uCi/m3) for H-3 and C-14 (m2

mrem /yr per uCi/sec) for others N uclide H3 l Hom E

7.63E+2 h,s roit 7.63E+2 sidne g .I-l.I.I T.thg .

7.63E+2 7.63E+2 7.63Et2 7.63 E-2 : '

C-14 l 3.63E+5 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 P-32 l 1.71E+10 106E+9 - - -

1.92E+9 6.60E+8 Cr 51 l - -

1.71E+4 6.30E+3 3.80E+4 7.20E+6 2.86E+4 ,

1 Mn-54 l - 8.40E+6 -

2.50E+6 -

2.57E+7 1.60E+6 I l

t Fe 55 l 2.51E+7 1.73E+7 - -

9.67E+6 9.95E+6 4.04E+6 I Fe-59 2.98E+7 7.00E+7 - -

1.95E+7 2.33E+8 2.68E+.7 :

Co 57 -

1.28E+6 - -

3.25 E+7 2.13E+6 !

Co 58 -

4.72E+6 - - -

9.57E+7 1.06E+7 i Co-60 ) -

1.64E+7 - -

3.08E+8 3.62E+7 l Ni 63 l 6.73E+9 4.66E+8 - -

9.73 E+7 2.26E+8 i '

Zn 65 l 1.37E+9 4.36E+9 -

2.92E+9 -

2.75E+9 1.97E+9 ! ,

Rb-86 l -

2.59E+9 - - -

5.I1E+8 1.21 E-9 I Sr-89 l1.45E+9 - - -

2.33E+8 4.16E+7 Sr-90 l 4.68E+10 - - -

1.35E+9 1.15E+10 I Y-91 l 8.60E+3 - - - -

4.73 E+6 2.30E-2 Zr-95 ' 9.46E+2 3.03 E+2 4.76E+2 9.62E+5 2.05E-2 Nb-95 8.25E+4 4.5Mi+4 -

4.54E+4 -

2.79E+8 2.47E+4

Ru 103 l 1.02E+3 - -

3.89E+3 -

1.19E+5 4.39E+2 -

Ru-106 l 2.04E+4 - -

3.94E+4 -

1.32E+6 2.58E-3 Ag11Om l 5.83E+7 5.39E+7 -

1.06E+8 -

2.20E+10 3.20E+7 Sb-124 2.57E+7 4.86E+5 6.24E+4 -

2.00E+7 7.31 E+8 1.02E-7 >

Sb 125 2.04E+7 2.28E+5 2.08 E+4 -

1.58E+7 2.25E+8 4.86E+6 '

Te-125m 1.63 E+7 5.90E+6 4.90E+6 6.63E+7 -

6.50E+7 2.18E+6 <

Te 127m 4.58 E+7 1.64E+7 1.17E+7 1.86E+8 -

1.54E+8 5.58E-6 Te-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 2.43 E-8 i Cs 134 5.65E+9 1.34E+10 -

4.35E+9 1.44E+9 2.35E+8 1.10E+ 10 ;

Cs-136 2.61 E+8 1.03 E+9 -

5.74E+8 7.87E+7 1.17E+8 7.42E+8 i Cs 137 7.38E+9 1.01 E+10 -

3.43E+9 1.14E+9 1.95E+8 6.61E-9 l Ba 140 2.69E+7 3.38E+4 -

1.15E+4 1.93E+4 5.54E+7 1.76E+6 -

Ce-141 4.84E+3 3.27E+3 -

1.52E+3 -

1.25E+7 3.71 E+2 i Ce-144 3.58E+5 1.50E+5 -

8.87E+4 -

1.21E+8 1.92E+4 i Pr-143 l 1.59E+2 6.37E+1 -

3.68E+1 -

6.96E+5 7.88 E+0 i Nd 147 9.42E+ 1 1.09E+2 -

6.37E+1 -

5.23E+5 6.52E+0 1 34 l

Hope Creek ODCM Rev l ~

Table 2-4 (cont'd)

Pathway Dose Factors - Atmosperic Releases R(io), Grass-Cow-Milk Pathway Dose Factors - TEENAGER (mrem /yr per uCi/m3) for H 3 and C-14 (m2

mrem /yr per uCi/sec) for others Nuclide-H3 Hunt

..is er 9.94E+2

. f h,s roi!

9.94E+2 Q

9.94E+2 9.94E+2 9.94E+2 9.94E+2 C-14 6.70E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 P-32 3.15E+10 1.95E+9 - - -

2.65E+9 1.22E+9 Cr-51 - - 2.78E+4 1.10E+4 7.13E+4 8.40E+6 5.00E+4 Mn-54 -

1.40E+7 -

4.17E+6 -

2.87E+7 2.78E+6 Fe-55 4.45E+7 3.16E+7 - -

2.00E+7 1.37E+7 7.36E+6 Fe 59 5.20E+7 1.21 E+8 - -

3.82E+7 2.87E+8 4.68E+7 Co-57 -

2.25E+6 - - -

4.19E+7 3.76E+6 Co-58 -

7.95 E+6 - - -

1.10E+8 1.83 E+7 Co-60 -

2.78E+7 - - -

3.62E+8 6.26E+7 Ni-63 1.18E+10 8.35 E+8 - - -

1.33E+8 4.01 E+8 Zn-65 2. l l E+9 7.31 E+9 -

4.68E+9 -

3.10E+9 3.41E-9 P.b 86 l 4.73 E+9 - - -

7.00E+8 2.22E+9 Sr 89 l 2.67E+9 - - - -

3.18E+8 7.66E-7 Sr-90 l 9.92E+7 - - -

9.60E+6 7.22E+5 6.10E-6 Y 91 l 1.58E+4 - - - -

6.48E+6 4.24E+2 Zr 95 1.65E+3 5.22E+2 - -

7.67E+2 -

1.20E+6 3.59E+2 Nb-95' l.41E+5 7.80E+4 -

7.57E+4 -

3.34E+8 4.30E+4 l Ru 103 t1.81E+3 - -

6.40E+3 -

1.52E+5 7.75E+2 i Ru 106 I 3.75E+4 - -

7.23 E+4 -

1.80E+6 4.73 E+3 Ag-110m l 9.63E+7 9.11 E+7 -

1.74E+8 ,- 2.56E+10 5.54E+7 Sb-124 l 4.59E+7 8.46E+5 1.04E+5 -

4.01 E+7 9.25E+8 1.79E+7 Sb-125 l 3.65E+7 3.99E+5 3.49E+4 -

3.21 E+7 2.84E+8 8.54E+6 Te-125m 3.00E+7 1.08E+7 8.39E+6 - -

8.86E+7 4.02E+6_

Te-127m 8.44E+7 2.99E+7 2.01 E+7 3.42E+8 -

2.10E+8 1.00E+7 Te 129m l1.llE+8 4.10E+7 3.57E+7 4.62E+8 -

4.15E+8 1.75E+7 l-131 1 5.38E+8 7.53 E+8 2.20E+11 1.30E+9 -

1.49E+8 4.04 E-8 Cs-134 9.81 E+9 2.31 E+10 - 7.34E+9 2.80E+9 2.87E+8 1.07E+ 10 Cs 136 4.45 E+8 1.75E+9 -

9.53E+8 1.50E+8 1.41E+8 1.18E+9 Cs-137 1.34E+10 1.78E+10 -

6.06E+9 2.35E+9 2.53E+8 6.20E-9 Ba-140 4.85E+7 5.95E+4 -

2.02E+4 4.00E+4 7.49E+7 3.13 E-6 Ce 141 8.87E+3 1.35E+4 -

2.79E+3 -

1.69E+7 6.81E+2 Ce-144 I 6.58E+5 2.72E+5 -

1.63E+5 -

1.66E+8 3.54E+4 Pr-143 2.92E+2 1.17E+2 -

6.77E+1 - 9.61 E+5 1.45 E+ 1 Nd 147 1.81E+2 1.97E+2 -

1.16E+2 -

7. l l E+5 1.18E+ 1 35

l 1

1 Hope Creek ODCM Rev 17 Table 2-4 (cont'd)

Pathway Dose Factors - Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors - CHILD (mrem /yr per uCi/m3) for H-3 and C-14 '

(m2

mrem /yr per uCi/sec) for others sutlid H3 lon 1.5.7E+3 l 1.57E+3 Jidne 1.57E+3 Q

1.57E+3 1.57E+3 g

1.57E-3 C-14 1.65E+6 3.29E+5 l 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 P-32 7.77E+10 3.64E+9 l - - -

2.15E+9 3.00E+9 Cr-51 - -

l 5.66E+4 1.55E+4 1.03E+5 5.41 E+6 1.02E+5 Mn 54 -

2.09E+7 l -

5.87E+6 -

1.76E+7 5.58E+6 Fe-55 1.12E+8 5.93 E+7 l - -

3.35E+7 1.10E+7 1.84E+7 Fe-59 1.20E+8 1.95E+8 -

l -

5.65E+7 2.03E+8 9.71 E+7.

Co-57 -

3.84E+6 l 3.14E+7 7.77E+6 Co-58 -

1.21E+7 l - - -

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 1.01 E+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 Sr89 6.62E+9 - - -

2.56E+8 1.89E*8 Sr-90 1.12E+11 - - - -

1.51 E+9 2.83E-10 Y-91 3.91 E+4 - - - -

5.21 E+6 1.04E+3 I Zr 95 3.84E+3 8.45E+2 -

1.21E+3 8.81 E+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.llE+5 1.65E-3 Ru-106 9.24E+4 - -

1.25E+5 -

1.44 E+6 1.15E-4 Ag-110m 2.09E+8 1.41E+8 -

2.63E+8 -

1.68E+10 1.13 E+8 l Sb-124 1.09E+8 1.41E+8 2.40E+5 -

6.03 E+7 6.79E+8 3.81 E+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 2.00E+7 2.07E+7 - -

7.12E+7 9.84 E+6 I Te 127m 2.08E+8 5.60E+7 4.97E +7 5.93 E+8 -

1.68E+8 2.47E+7 Te-129m 2.72E+8 7.61 E+7 8.78E+7 8.00E+8 -

3.32E+8 4.23E+7 1-131 1.30E+9 1.31E+9 4.34E+11 2.15E+9 -

1.17E+8 7.46E*8 Cs-134 2.26E+10 3.71 E+10 -

1.15E+10 4.13 E+9 2.00E+8 7.83 E+9 Cs-136 1.00E+9 2.76E+9 -

1.47E+9 2.19E+8 9.70E+7 1.79E+9 Cs 137 3.22E+10 3.09E+10 -

1.01E+10 3.62E+9 1.93E+8 4.55E+9 Ba-140 1.17E+8 1.03E+5 -

3.34E+4 6.12E+4 5.94E+7 6.84E-6 Ce-141 2.19E+4 1.09E+4 -

4.78E+3 -

1.36E+7 1.62E-3 l Ce-144 1.62E+6 5.09E+5 -

2.82E+5 -

1.33E+8 8.66E+4 Pr i43 7.23E+2 2.17E+2 -

1.17E+2 -

7.80E+5 3.59E-l Nd 147 4.45E+2 3.60E+2 -

1.98E+2 -

5.71 E+5 2.79E+1 l 36

I Hope Creek ODCM Rev 1 Table 2-4 (cont'd)

Pathway Dose Factors - Atmospheric Releases R(io), Grass-Cow-Milk Pathway Dose Factors - INFANT (mrem /yr per uCi/m3) for H-3 and C-14 (m2

mrem /yr per uCi/sec) for others N uclide > ' lione I,n c. 'In reit sidne, g 011jt.

7 f.Bmly H-3 -

l 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 C-14 3.23E+6 l 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 P-32 1.60E+11 l 9.42E+9 - - -

2.17E+9 6.21E+9 i Cr-51 .-

l -

1.05E+5 2.30E+4 2.05E+5 4.71 E+6 1.61E+5 Mn-54 -

l 3.89E+7 -

8.63E+6 -

1.43E+7 8.83E+6 Fe-55 1.35E+8 l 8.72E+7 - -

4.27E+7 1.11 E+7 2.33 E+7 Fe-59 12.25E+8 l 3.93E+8 - -

1.16E+8 1.88E+8 1.55E+8 Co-57 -

l 8.95E+6 - - -

3.05E+7 1.46E+7 4 Co-58 -

l 2.43E+7 - - -

6.05E+7 6.06E+7 Co-60 -

l 8.81E+7 - - -

2.10E+8 2.08E+8 Ni-63 I 3.49E+10 l 2.I6E+9 - - -

1.07E+8 1.21 E+9 l Zn-65 ! 5.55E+9 l 1.90E+10 -

9.23E+9 -

1.61E+10 8.78E+9 Rb-86 1 -

l 2.22E+10 - - -

5.69E+8 1.1OE+10 Sr-89 l 1.26E+10 l - - - -

2.59E+8 3.61E+8 i Sr-90 l 1.22E+11 l - - - -

1.52E+9 3.10E+10 Y-91 I 7.33E+4 l 5.26E+6 1.95E+3 l Zr-95 i 6.83E+3 l 1.66E+3 -

1.79E+3 -

8.28E+5 1.18E+3 l Nb-95 j 5.93E+5 l 2.44E+5 - 1.75E+5 -

2.06E+8 1.41E+5 i Ru 103 ; 8.69E+3 - -

1.81E+4 -

1.06E+5 2.91 E+3 l Ru-106 I1.90E+5 - -

2.25E+5 -

1.44E+6 2.38E+4 i Ag-110m i 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 (

Sb 125 l 1.49E+8 1.45E+6 1.87E+5 -

9.38E+7 1.99E+8 3.07E+7 )

Te 125m l 1.51E+8 5.04E+7 5.07E+7 - -

7.18 E+7 2.04E+7 Te 127m 4.21 E+8 1.40E+8 1.22E+8 1.04E+9 -

1.70E+8 5.10E+7 i l Te 129m 5.59E+8 1.92E+8 2.15 E+8 1.40E+9 -

3.34E+8 8.62E+7 {

T-131 2.72E+9 3.21 E+9 1.05E+12 3.75E+9 -

1.15E+8 1.41E+9 Cs-134 3.65E+10 6.80E+10 -

1.75E+10 7.18E+9 1.85E+8 6.87E-9 Cs 136 1.96E+9 5.77E+9 -

2.30E+9 4.70E+8 8.76E+7 2.15E+9 I Cs 137 5.15E+10 6.02E+10 -

1.62E+10 6.55E+9 1.88E+8 4.27E+9 i Ba-140 ) 2.41E+8 2.41 E+5 -

5.73E+4 1.48E+5 5.92E+7 1.24E+7 1 Ce 141 l 4.33E+4 2.64E+4 -

8.15 E+3 -

1.37E+7 3. l l E+3 Ce-144 2.33E+6 9.52E+5 -

3.85E+5 -

1.33E+8 1.30E+5 i Pr-143 1.49E+3 5.59E+2 -

2.08E+2 -

7.89E+5 7.41 E+ 1 l

, Nd-147 l 8.82E+2 9.06E+2 - 3.49E+2 -

5.74E+5 5.55 E+ 1 37

)

l Hope Creek ODCM Rev 17 Table 2-4 (cont'd) l Pathway Dose Factors - Atmospheric Releases R(.:o), Vegetation Pathway Dose Factors - ADULT (mrem /yr per uCi/m3) for H-3 and C-14 (m2

mrem /yr per uCi/sec) for others 6

H3 1 -

2.26E+3 i

2.26E+3 2.26E+3

_ g g.

l 2.26E+3 2.26E+3 2.26E+3 I C-14 I8.97E+5 l1.79E+5 l 1.79E+5 1.79E+5 l1.79E+5 1.79E+3 1.79E+5 i P-32 l 1.40E+9 l 8.73E+7 l - -

l -

1.58E+8 5.42E+7 I Cr 51 1 -

1 -

l 2.79E+4 1.03E+4 16.19E+4 1.17E+7 4.66E+4 I Mn 54 l -

l 3.1IE+8 1 -

9.27E+7 l -

9.54E+8 5.94E+7 Fe 55 l 2.09E+8 l 1.45E+8 l - -

l 8.06E+7 8.29E+7 3.37 E+.7 i Fe 59 l 1.27E+8 l 2.99E+8 -

8.35E+7 9.96E+8 1.14E+8 Co-57 1 -

l1.17E+7 - - -

2.97E+8 1.95E+7 Co-58 l -

l 3.09E+7 - - -

6.26E+8 6.92E+7 Co-60 l -

l 1.67E+8 - - -

3.14E+9 3.69E+8 i Ni-63 l 1.04E+10 l 7.21E+8 - -

1.50E+8 3.49E+8 j Zn-65 I 3.17E+8 l 1.01E+9 -

6.75E+8 -

6.36E+8 4.56E+8 i Rb-86 l -

l 2.19E+8 - - -

4.32E+7 1.02E+8 i Sr 89 l 9.96E+9 l - - - -

1.60E+9 2.86E+8 St-90 l 6.05E+11 l - - - -

1.75E+10 1.48 E+ 10 Y-91 I 5.13E+6 l - - -

2.82E+9 1.37E-5 Zr-95 l 1.19E+6 l 3.81E+5 -

5.97E+5 1.21E+9 2.58E+5 Nb-95 1.42E+5 l 7.91E+4 7.81 E+4 4.80E+8 4.25E+4 i Ru-103 4.80E+6 I - -

1.83E+7 -

5.61 E+8 2.07E-6 Ru-106 1.93E+8 l - -

3.72E+8 -

1.25E+10 2.44E-7 i Ag 110m 1.06E+7 I 9.76E+6 -

1.92E+7 3.98 E+9 5.80E+6 ,

Sb 124 1.04E+ 8 1.96E+6 2.52E+5 -

8.08E+7 2.95E+9 4. I 1 E+7 Sb-125 1.36E+8 1.52E+6 1.39E+5 -

1.05E+8 1.50E+9 3.25E+7 ,

-Te 125m 9.66E+7 3.50E+7 2.90E+7 3.93E+8 -

3.86E+8 1.29E+7 Te 127m 3.49E+8 1.25E+8 8.92E+7 1.42E+9 -

1.17E+9 4.26E+7 i Te-129m 2.55E+8 9.50E+7 8.75E+7 1.06E+9 -

1.28E+9 4.03E+7 i 1-131 8.09E+7 1.16E+8 3.79E+10 1.98E+8 -

3.05E+7 6.63E+7 I Cs-134 4.66E+9 1.11E+10 -

3.59E+9 1.19E+9' l.94E+8 9.07E+9 :

Cs 136 4.20E+7 1.66E+8 -

9.24E+7 1.27E+7 1.89E+7 1.19Et8 j Cs-137 6.36E+9 8.70E+9 -

2.95E+9 9.81 E+8 1.68E+8 5.70E+9 I Ba 140 1.29E+8 1.62E+5 -

5.49E+4 9.25E+4 2.65E+8 8.43E+6 i Ce 141 1.96E+5 1.33E+5 -

6.17E+4 -

5.08E+8 1.51E+4 i Ce-144 13.29E+7 1.38E+7 -

8. I 6E+6 -

1.11 E+10 1.77E+6 i l Pr-143 6.34E+4 2.54E+4 -

1.47E+4 -

2.78E+8 3.14E+3 -

I Nd-147 3.34E+4 3.86E+4 -

2.25E+4 -

1.85E+8 2.31E+3 '

38 i

l 1

,a Hope Creek ODCM Rev 17 i

Table 2-4 (cont'd) I Pathway Dose Factors - Atmospheric Releases R(io), Vegetation Pathway Dose Factors - TEENAGER (mrem /yr per uCi/m3) for H-3 and C-14 (m2

mrem /yr per uCi/sec) for others Nuchde H-3

- lion h cr I hy rois g zung ; 01-l .l .1 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 2.91 E+5 2.91E+5 2.91 E+5 i P-32 1.61E+9 9.96E+7 -

1.35E+8 6.23E+7 l Cr-51 - -

3.44E+4 1.36E+4 ' 8.85E+4 1.04E+7 6.20E+4 ;

Mn-54 -

4.52E+8 -

1.35E+8 -

9.27E+8 8.97E+7 Fe-55 3.25E+8 2.31 E+8 - -

1.46E+8 9.98E+1 5.38E+7 Fe-59 1.81E+8 4.22E+8 - -

1.33E+8 9.98E+8 1.63E-8 i Co-57 -

1.79E+7 - -

3.34E+8 3.00E+7 Co-58 l 4.38E+7 - - -

6.04 E+8 1.01E+8 Co-60 -

2.49E+8 - -

3.24E+9 5.60E+8 Ni-63 1.61E+10 1.13E+9 - - -

1.81E+8 5.45E+8 Zn-65 4.24E+8 1.47E+9 -

9.41E+8 -

6.23E+8 6.86E+8 t Rb-86 l -

2.73E+8 - -

4.0'E+7 1.28E-8 i Sr-89 l 1.51E+10 - - - -

1.80E+9 4.33 E+8 l Sr-90 i 7.51E+11 - - - -

2.1 lE+10 1.85E-11 l Y-91 l 7.87E+6 - - -

3.23 E+9

~

2.11 E-5 Zr-95 1.74E+6 5.49E+5 8.07E+5 1.27E+9 3.78E-5 Nb 95 1.92E+5 1.06E+5 -

1.03E+5 -

4.55E+8 5.86E-4 Ru-103 16.87E+6 - -

2.42E+7 -

5.74E+8 2.94 E+6 Ru-106 l 3.09E+8 - -

5.97E+8 -

1.48E+10 3.90E-7 l Ag 110m i1.52E+7 1.44E+7 -

2.74E+7 -

4.04E+9 8.74E+6 l Sb.I24 l 1.55E+8 2.85E+6 3.51 E+5 -

1.35E+8 3.11 E+9 6.03 E-7

{ Sb-125 l 2.14E+8 2.34E+6 2.04E+5 -

1.88E+8 1.66E+9 5.00E+7 Te 125m 1.48E+8 5.34E+7 4.14E+7 - -

4.37E+8 1.98E+7 i Te 127m 5.51 E+8 1.96E+8 1.31E+8 2.24E+9 -

1.37E+9 6.56E-7 l Te-129m 3.67E+8 1.36E+8 1.18E+8 1.54E+9 1.38E+9 5.81E-7 l 1-131 7.70E+7 1.08E+8 3.14E+10 1.85E+8 -

2.13 E+7 5.79E-7 I Cs-134 7.09E+9 1.67E+10 -

5.30E+9 2.02E+9 2.08E+8 7.74E+9 Cs 136 4.29E+7 1.69E+8 -

9.19E+7 1.45E+7 1.36E+7 1.13E+8 Cs-137 1.01 E+10 1.35E+10 -

4.59E+9 1.78E+9 1.92E+8 4.69E+9 Ba 140 1.38E+8 1.69E+5 -

5.75E+4 1.14E+5 2.13E+8 8.91 E-6 Ce 141 2.82E+5 1.88E+5 -

8.86E+4 -

5.38E+8 2.16E+4

' Ce-144 5.27E+7 2.18E+7 -

1.30E+7 -

1.33E+10 2.83E-6 Pr-143 7.12E+4 2.84E+4 -

1.65E+4 -

2.34E+8 3.55E-3 Nd 147 l 3.63E+4 3.94E+4 -

2.32E+4 -

1.42E+8 2.36E-3 39

{

l

i Hope Creek ODCM Rev l' Table 2-4 (cont'd)

Pathway Dose Factors - Atmospheric Releases R(io), Vegetation Pathway Dose Factors - CHILD (mrem /yr per uCi/m3) for H-3 and C-14 (m2

mrem /yr per uCi/sec) for others Nucinly . . lione l@ cr. "I hy roid hidney I.ung (j i-l.l.1 T.llody H3 -

4.01E+3 4.01 E+3 4.01 E+3 4.01 E+3 4.01 E+3 4.01E+3 I l C-14 3.50E+6 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 7.01 E+5 P-32 3.37E+9 1.58E+8 - - -

9.30E+7 1.30E+8 Cr 51 - -

6.54E+4 1.79E+4 1.19E+5 6.25E+6 1.18E+5 Mn-54 -

6.61E+8 -

1.85E+8 -

5.55E+8 1.76E+8 i Fe-55 8.00E+8 4.24E+8 - -

2.40E+8 7.86E+7 1.31E+8 i Fe 59 4.01 E+8 6.49E+8 - -

1.88E+8 6.76E+8 3.23E+8 ;

Co-57 -

2.99E+7 - - -

2.45E+8 6.04 E+ 7 l Co-58 -

6.47E+7 - - -

3.77E+8 1.98E+8 Co-60 -

3.78E+8 - - -

2.10E+9 1.12E+9 i Ni 63 3.95E+10 2.1 I E+9 - - -

1.42E+8 1.34E+9 C Zn 65 l 8.12E+8 2.16E+9 -

1.36E+9 -

3.80E+8 1.35E+9 '

I Rb-86 I -

4.52E+8 - - -

2.91 E+7 2.78E+8 lSr89 ~

l 3.59E+10 - - - -

139E+9 1.03E-9 iSr90 l 1.24E+12 - - - -

1.67E+10 3.15E-l 1 iY-91 1.87E+7 - - - -

2.49E+9 5.01 E+5

^

i Zr-95 3.90E+6 8.58E+5 -

1.23E+6 -

8.95E+8 7.64 E+5 i'Nb-95 l 4.10E+5 1.59E+5 -

1.50E+5 -

2.95E+8 1.14E+5 !

Ru-103 l 1.55E+7 - -

l 3.89E+7 -

3.99E+8 5.94E+6 ,

' Ru-106

{ 7.45E+8 - -

1.01E+9 -

1.16E+10 9.30E+7 IAg-l10m i 3.22E+7 2.17E+7 -

4.05E4 7 -

2.58E+9 1.74 E+7 i i Sb-124 l 3.52E+8 4.57E+6 7.78E+5 -

1.96E+8 2.20E+9 1.23E+8 j Sb-125 ; 4.99E+8 3.85E+6 4.62E+5 -

2.78E+8 1.19E+9 1.05E+8

Te-125m 3.51 E+8 9.50E+7 9.84E+7 - -

3.38E+8 4.67E-7 i

' Te 127m 1.32E+9 3.56E+8 3.16E+8 3.77E+9 -

1.07E+9 1.57E+8 i

! Te 129m 8.54E+8 2.39E-8 2.75E+8 2.51E+9 -

1.04E+9 1.33E+8 7

!l-131 1.43 E+8 1.44E+8 4.76E+10 2.36E+8 -

1.28E+7 8.18E+ 7 :

Cs 134 1.60E+10 2.63E+10 -

8.14E+9 2.92E+9 1.42E+8 5.54E+9 i

, Cs-136 8.06E+7 2.22E+8 - -

1.18E+8 1.75E+7 7.79E+6 1.43E+8 )

l l Cs 137 l 2.39E+10 2.29E+10 -

7.46E+9 2.68E+9 1.43E+8 3.38E+9 l j Ba 140 l 2.77E+8 2.43E+5 -

7.90h+4 1.45E+5 1.40E+8 1.62E+ 7 !

LCe 141 ! 6.35E+5 3.26E+5 -

1.43E+5 -

4.07E+b 4.84E+4 i

! Ce 144 i 1.27E+8 3.98E+7 -

2.21 E+7 -

1.04E+10 6.78E+6 l I Pr 143 l 1.48E+5 4.46E+4 -

2.41 E+4 -

1.60E+8 7.3 7E+3 i l Nd 147 } 7.16E+4 5.80E+4 -

3.18E+4 -

9.18 E+7 4.49E+3 1 40 l

s Hope Creek ODCM Rev 11 Table 2-4 (cont'd) .

Pathway Dose Factors - Atmospheric Releases R(io), Ground Plane Pathway Dose Factors l

(m2

mrem /yr per uCi/sec)

Nuclide Any Organ H-3 -

C-14 -

P-32 -

l Cr-51 4.68E+6 '

Mn-54 1.34E+9 l Fe-55 -

Fe-59 2.75E+8 Co-58 3.82E+8 Co-60 2.16E+10 l Ni 63 -

I Zn-65 7.45E+8 Rb-86 8.98E+6 Sr89 2.16E+4 Sr-90 -

Y-91 1.08E+6 !

Zr 95 -

2.48E+8 j Nb-95 1.36E+8 i Ru 103 1.09E+8 l Ru-105 4.21E+8 l Ag-110m 3.47E+9 i Te-125m 1.55E+6 Te-127m 9.17E+4 ,

Te-129m 2.00E+7 1131 i

1.72E+7 j Cs-134 6.75E+9 Cs-136 1.49E+8

{1 Cs-137 1.04E+10 I Ba 140 2.05E+7 )

Ce 141 1.36E+7 Ce-144 6.95E+7 Pr-143 -

Nd 147 8.40E+6 u i o

Hope Creek ODCM Rev 17 APPENDIX A EVALUATION OF DEFAULT MPC VALUES f FOR . LIQUID EFFLUENTS .

l -

l 4

f A-1

Hope Creek ODCM Rev 17 APPENDIX A Evaluation of Default MPC Value j

for Liquid Radwaste Effluent Radiation Monitors 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 l B, Table II, Column 2 (Appendix F). The determination of allowable radionuclide concentration and corresponding alarm setpoint is a function of the individual monitor.

i 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 1993 to 1995 l release data of the liquid effluents from Hope Creek and the effective MPC value for this.

distribution.

i l

The effective MPC value for a radionuclide distribution is calculated by the equation:

I C, (gamma) (A.1)

MPC, =

C,(gamma) l I

MPC, where: j MPC, = an effective MPC value for a mixture of radionuclides (uCi/ml)

C, = concentration of radionuclide i in the mixture MPC, = the 10 CFR 20, Appendix B, Table 11, Column II MPC value for radionuclide i .

(uCi/ml) Appendix F -

1 Considering the average effective MPC values from 1993 thru 1995 releases it is reasonable to select an MPC value of 7.92E-05 uCi/ml as typical ofliquid radwaste discharges. This value will f be reviewed and adjusted as necessary based on the distribution history of effluents from Hope Creek. Using the value of 7.92E 5 uCi/ml to calculate the default alarm setpoint, results in a setpoint that:

(1) Will not require frequent re-adjustment due to minor variations in the nuclide distribution which are typical of routine plant operations, and; A-2 4

J

Hope Creek ODCM Rev 17 (2) Will provide for a liquid radwaste discharge rate (as evaluated for each batch release) that is compatible with plant operations (Refer to Table 1-1).

1.0 Default Serpoint Determination:

Conservative alarm setpoints can be determined through the use of default parameters. Table 1-1 summarizes all current default values in use for Hope Creek.

~

A. Liquid Radwaste Monitor (RE4861)

MPC,

CTBD * [1 -CF]

SP < + bkg (1.2)

Default values from Table 1-!:

{ -

MPC, = 7.92E-5 uci/mi CTBD = 12000 gpm RR = 176 gpm (1300 CST)

Bkg = 0 uci/ml CF = 0.8 -

( 7.92E 5

12000

0.2 1 SP < ------------------------ +0 176 SP < LO8E-3 uci/mi Correction Factor:

A correction factor must be applied to the default setpoint calculation in order to account for f radiation monitor uncertainties and the contribution of non gamma emitting radionuclides such as H-3, Sr, and Fe.

a. Radiation Monitor inaccuracies:

Hope Creek PSBP 311649 lists a total loop accuracy of 30% for the liquid radwaste radicion monitors. A factor of 030 is applied to the default setpoint to ensure the trip setpoint is reached before the analytical limit is obtained.

A3 l

l Hope Creek ODCM Rev 17 b; Non-Gamma Emitting Radionuclides:

]

Non gamma emitting radionuclides are analyzed on a monthly and quanerly basis from composite samples ofliquid radwaste releases.

Nuclide MPC (uci.ml) Activity (uci.ml) Activny / MPC H-3 3E-3 1.0E-1 33.3 Fe-55 8E 4 4.7E 4 0.59 f Sr-89 3E-6 1.6E 6 0.53 l Sr-90 3E-7 2.0E-8 0.07 Total 34.5 f

The values in the table above represent the historical maximum reactor coolant values for non-gamma emitting nuclides (H3 is an assumed maximum). Rcactor coolant values were chosen to -

represent the maximum concentration of non-gamma emitting radionuclides that could be released from Hope Creek station in liquid emuent. The activity values in the table is further diluted by a minimum factor of 68 prior to release to the Delaware River. The minimum dilution factor is obtained by using the minimum cooling tower blowdown flowrate of 12,000 gpm and the maximum release rate of 176 gpm.

A conservative correction factor for non-gamma emitting radionuclides can be obtained by using ,

the highest Activity / MPC fraction and the minimum dilution factor as follows: i l

Correction Factor (non-gamma) = 34.5 / 68 = 0.5 An overall correction factor can be obtained by adding the correction factor for radiation rnonitor inaccuracies and non gamma emitting radionuclides as follows: <

i

. Overall Correction factor = 0.3 + 0.5 = 0.8 B. Cooling Tower Blowdown Radiation Monitor (RE8817) l The cooling tower blowdown radiation monitor provides an Alarm only function for releases into

the environment. The cooling tower blowdown is the final release point for liquid emuents from Hope Creek station to the Delaware River.

SP < MPC,

0.2 SP < 7.92E 5 uci/ml

0.2 l

SP < 1.58E-3 uci/mi (RE8817)

A-4 t

Hope Creek ODCM Rev 17 C. Turbine Building Circulating Water Dewatering Sump Radiation Monitor (RE4557)

The Turbine Building Circulating Water Dewatering Sump Radiation Monitor (RE4557) provides automatic termination ofliquid radioactive releases from the Circulating Water Dewatering Sump.

f The sump pumps discharge to the circulating water system to the cooling tower. Radioactive materials other than tritium are not normally expected to be discharged through this pathway. Plant design and procedures maintain the setpoint at <2 times background radiation levels. Releases from the sump at gamma activity concentrations less than the monitor setpoint are considered continuous releases since inputs to the sump would occur during discharge. Releases of activity l above the setpoint may be performed on a batch basis following sampling and analysis of the sump I

contents. Hope Creek calculation SP-0004 established a setpoint for the monitor at 1.4E.02 uCi/ml based on a postulated release of reactor steam into the sump. Using the MPCe determined for Liquid Radwaste and Cooling Tower Blowdown monitors, a more conservative maximum default value for batch releases can be determined:

MPC,

CTBD * [1.CF)

SP < + bkg (1.2)

M

( Default values from Table 1 1: -

MPC,

= 7.92E.5 uci/ml CTBD = 12000 gpm RR = 100 gpm Bkg = 0 uci/mi CF = 0.8 7.92E.5

12000

0.2

'f Sp < . . . _ . ._ ._.- +0 3 100 SP < l.90E.3 ucFmt (batch releases only)

For continuous releases, the maximum setpoint should be less than 2.4E.6 ucFml above background to limit dose consequences from this pathway.

A.5 i

i l

Hope Creek ODCM Rev 17 4

TABLE A-1 4 CALCULATION OF EFFECTIVE MPC .

HOPE CREEK l'993 ACTIVITY 1994 ACTIVITY 1995 ACTIVITY NUCLIDE MPC RELEASED (Ci) RELEASED (Ci) RELEASED (Ci)

Na-24 3.0E-05 1.20E-04 N/D 2.15E-05

s Cr-51 " 2.0E-03 1.57E-01 ' 7.91E-02 1.29E-01 ]

Mn-54 1.0E-04 6.30E-02 1.10E-01 4.12E-01 As-76 2.0E-05 1.03E-05 1.62E-04 8.42E-05 1 Co-58 ~ 9.0E-05 1.35E-03 3.04E-03 2.68E-02 I Fe-59 5.0E 05 8.74E-03 1.14E-02 1.12E-01 l

Co-60 3.0E-05 1.15E-02 6.49E-02 8.48E-02 j Zn-65 1.0E-04 7.01E-02 7.79E-02 8.77E-02 l Ag-110m 3.0E-05 2.16E-03 1.90E-03 7.42E-03 Zr 97 2.0E 05 1.45E-05 N/D 3.45E-05 1 Tc-99m 3.0E-03 1.79E-03 1.45E-03 8.68E-04 f j Cs 134 9.0E-06 N/D 1.llE-06 1.51 E-04 i

Cs-137 2.0E-05 4.85E-05 1.33E-05 2.97E-04 Zn-69m 6.0E-05 2.33E-05 7.22E-05 N/D '

Nb-97 9.0E 04 4.33E-04 2.32E-04 N/D In-11Sm 4.0E-04 N/D , N/D 2.90E-05 H-3 3.0E-03 6.17E+01 3.33E+01 4.61E+01 Fe 55 8.0E-04 4.51 E-02 1.86E-01 5.44E-01 Total Curies 3.16E-01 3.50E-01 8.61E-01 ;

(Gamma)

SUM (Ci/MPCi) 2.06E+03 4.42E+03 1.07E+04 (Gamma)

SUM (Ci/MPCi) 2.06E+04 1.13E+04 1.60E K)4 (Non-Gamma)

MPCe (uCi/ml) 1.53E 04 7.92E-05 8.04E-05 N/D=Not detected A-6

Hope Creek ODCM Rev 1

,.2 N-APPENDIX B TECHNICAL BAEIS FOR EFFECTIVE DOSE FACTORS LIQUID RADIOACTIVE EFFLUENTS

- - - - - - - - - - - - - - - - - ' - - ^ -

c ;

1 l

Hope Creek ODCM P 1

APPENDIX B Technical Basis for Effective Dose Factors - J Liquid Effluent Releases The radioactive liquid effluents from Hope Creek from 1993 through 1995 were evaluated to determine the dose contribution of the radionuclide distribution. This analysis was performed to j evaluate the use of a limited dose analysis for determining environmental doses, providing a simplified method of determining compliance with the dose limits of Technical Specification 3.11.1.2. For the expected radionuclide distribution of effluent from Hope Creek during 1993 to 1995, the controlling organ is the liver. The calculated liver dose is predominately a function of the

)

Zn-65 and Fe-55 releases. The radionuclides, Zn-65 and Fe-55 also contribute the large majority of the calculated total body dose. 'lhe results of this evaluation are presented in Table B-1.

For purposes of simplifying the details of the dose calculation process, it is conservative to identify a controlling, dose significant radionuclide and limit the calculation process to the use of the dose conversion factor for this nuclide. Multiplication of the total release (i.e., cumulative activity for all radionuclides) by this dose conversion factor provides for a dose calculation method that is simplified while also being conservative.

For the evaluation of the maximum organ dose, it is conservative to use the Zn-65 dose conversion factor (5.13E5 mrem /hr per uci/ml). By this approach, the maximum organ dose will be -

overestimated since this nuclide has the highest organ dose fraction of all the radionuclides evaluated. For the total body calculation, the Zn-65 dose factor (2.32E5 mrem /hr per uCi/ml, total body) is the highest among the identified dominant nuclides.

For evaluating compliance with the dose limits of technical Specification 3.11.1.2, the following simplified equations may be used:

Total Body l

8.35E-04

Vol D,, =

A,,,,

C. (B.1) -

CTBD l B-2 l l

p 1

~

l Hope Creek ODCM Rev 1 where:

D. = dose to the total body (mrem) :

j- A, = 2.32ES, total body ingestion dose conversion factor for Zn-65 where A is dose conversion factor, i is isotope which is Zn-65, and TB is the total body (mrem /hr per l uCi/ml) ,

VOL = volume ofliquid effluent released (gal)

Ci

= total concentration of all radionuclides (uCi/ml)

CTBD. = average cooling tower blowdown discharge rate during release period (gal / min) 8.35E-04 = conversion factor (1.67E-2 hr/ min) and the near field dilution factor 0.05 Substituting the value for the Zn-65 total body dose conversion factor, the equation simplified to:

l 1.94E+ 2

VOL l

D. =

I C, (B.2) j CTBD l

Maximum Organ 8.35E-4

VOL

Aio, Liver Dmax = , *I C; (B.3)

CTBD Where:

Dmax = maximum organ dose (mrem)

Aio, =

5.13ES, liver ingestion dose conversion factor for Zn-65 where A is dose conversion Liver factor, i is isotope which is Zn-65 and O is maximum organ which is the liver (mrem'hr per uCi/ml).

Substituting the value for Aio the equation simplifies to:

4.28E2

VOL Dmax =

I C, (B.4)

CTBD Tritium is not included in the limited analysis dose assessment for liquid releases, because the t

potential dose resulting from normal reactor releases is relatively negligible, B-3

r I

Hope Creek ODCM R)

Near Field Dilution Factor The near field dilution factor 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 of the average blowdown flow (in CFS) and the dilution factor is 1000 cfs or less. The average minimum cooling j tower blowdown for Hope Creek is 1.90E4 GPM (from FSAR I1.2). "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. m i

4 1

B-4 l

n Hope Creek ODCM Res l' TABLE B-1 Adult Dose Contributions Fish and Invertebrate Pathways Hope Creek Nuclide Release TB Dose GI-LLI Dose Liver Dose Year (Ci) Frac. Frac. Frac.

Fe-55 4.51 E-2 0.02. 0.03 0.04 1993 Fe 55 1.86E-2 0.07 0.08 0.13 1994 l

Fe 55 5.44E-1 0.15 0.10 0.24 1995 l

Mn-54 6.30E-2

0.04 0.01 1993 Mn-54 1.10E-1 0.01 0.06 0.02 1994 Mn-54 4.12E-1 0.02 0.07 0.03 1995 !

Co-58 1.35E-3 * *

1993 Co-58 3.04E-3 * *

1 1994 '

Co-58 2.68E 2 * * *

, 1995 l Fe 59 8.74E-3 0.04 0.18 0.04 19 %

Fe 59 1.14E-2 0.04 0.17 0.04 1994 Fe 59 1.12E-1 0.22 0.53 0.22 1995 Co 60 1.1 SE-2

0.01

1993 ;

Co-60 6.49E-1 0.01 0.05

1994 Co.60 8.48E 2 0.01 0.02

1995 Zn 65 7.01E 2 0.93 0.69 0.90 1993 Zn 65 7.79E-2 0.87 0.61 0.81 1994 Zn-65 8.77E-2 0.60 0.23 0.51 1995

=

Less than 0.01 B-5

Hope Creek ODCM Rev 17 J

]

J S

APPENDIX C

)

TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS ,

J j

GASEOUS RADIOACTIVE EFFLUENTS 1

1

, {

l l

l

{

Hope Creek ODCM Rev 17 APPENDIX C Technical Basis for Effective Dose Factors -

Gaseous Radioactive Effluents Overview The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer 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 releases to approximate the dose in the environment. Instead of having to perform individual radionuclide dose analysis only a single multiplication (i.e., Keff, Meff, or Neff times ,

the total quantity of radioactive material releases) would be needed. The approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calculation technique.

Determination of Effective Dose Factors -

Effective dose transfer factors are calculated by the following equations:

K,, = E (K,

f,) (C.1)

Where:

K,, = the effective total body factor due to gamma emissions from all noble gases released.

K,

= the total body dose factor due to gamma emissions from each noble gas radionuclide i released.

f,

= the fractional abundance of noble gas radionuclide i relative to the total noble gas activity.

( L + 1.1M,n) = I (( L, + 1.1M,) a f, )

(C.2) where:

(L + 1.1M,y) = the effective skin dose factor due to beta and gamma emissions from all noble gases released.

(L, + 1.1 M,) = the skin dose factor due to beta and gamma emissions from each noble gas radionuclide i released.

C-1

I J

1 Hope Creek ODCM Rev 1]

M., = I ( M

f) (C.3) ,

J where:

1 l

M,, = the effective air dose factor due to gamma emissions from all noble gases released. J l M, = the air dose factor due to gamma emissions from each noble gas radionuclide i released.

'l N,, = I (N,

fJ (C.4) where:

l N,, = the effective air dose factor due to beta emissions from all noble gases released.

N, = the air dose factor due to beta emissions from each noble gas radionuclide i released.

Normally, it would be expected that past radioactive effluent data would be used for the determination .

the effective dose factors. However, the noble gas releases from Hope Creek have a short history with continued excellent fuel performance, has hampered efforts in collecting and detecting appreciab' noble gas mixes of radionuclides. So, to provide a reasonable basis for the derivation of trie effecti noble gas dose factors, the source terms from ANSI N237-1976/ANS-18.1, " Source Te Specifications", Table 5 has been used as representing a typical distribution. The effective dose facto:

as derived are presented in Table C-1.

J Application .

To provide an additional degree of conservatism, a factor of 0.50 is introduced into the dose calculatio]

process when the effective dose transfer factor is used. This conservatism provides additional assuran that the evaluation of doses by the use of a single effective factor will not significantly underestimat any actual doses in the environment.

J For evaluating compliance with the dose limits of Technical Specification 3.11.2.2, the followin q

simplified equations may be used: ;

1 3.17E-08 I D, =

X/Q

M,,

I Q, (C.5) 0.50 3.17E-08 D,=

X/Q

N,,

I Q, (C.6) 1 0.50 C-2 )

l

?

Hope Creek ODCM Rev 17 Where:

D, = air dose due to gamma emissions for the cumulative release of all noble gases (mrad)

D,

- air dose due to beta emissions for the cumulative release of all noble gases (mrad)

X/Q = iltmospheric dispersion to the controlling site boundary (sec/m')

M, = - 8.1E3, effective gamma air dose factor (mrad /yr per uCi/m')

N, = 8.5E3, effective beta-air dose factor (mrad /yr per uCi/m')

Q, = cumulative release for all noble gas radionuclides (uCi) 3.17E-08 = conversion factor (yr/sec) 0.50 = conservatism factor to account for the variability in the effluent data Combining the constants, the dose calculation equations simplify to:

D, = 5.14E-4

X/Q

I Q, (C.7) j D. = 5.39E-4

X/Q

I Q, (C.8)

The effective dose factors are to be used on a limited basis for the purpose of facilitating the timely .

assessment of radioactive effluent releases, particularly during periods of computer malfunction where a detailed dose assessment may be unavailable.

1 C-3 l

I, Hope Creek ODCM Rev {

TABLE C-1 Effective Dose Factors

]

Noble Gases -Total Body and Skin Total Body Effective Skin Effective K, - (L + 1.1 M,,)

Radionuclide j (mrem /yr per uci/m3 ) (mrem /yr per uci/m')

)

Kr83m 0.01 a Kr85m 0.01 1.0E1 2.8E1 Kr87 0.04 2.4E2 6.6E2 I Kr8s 0.04 5.9E2 7.6E2 Kr89 0.27 4.5E3 7.9E3 Xel33 0.02 5.9E0 1.4El 1 Xel35 0.05 9.0El 2.0E2 J Xel35m 0.06 1.9E2 2.6E2 Xel37 0.31 4.4E2 4.3E3 3 Xel38 0.19 1.7E3 2.7E3 J Total 7.8E3 1.7E4 Noble Gases - Air Total Body Effective Skin Effective K,, (L + 1.1 M,,)

Radionuclide j (mrem /yr per uci/m') (mrem /yr per uci/m')

Kr83m 0.01 ------

3.0E0 Kr85m 0.01 1.2E l 2.0El Kr87 0.04 2.5E2 4.1 E2 Kr88 0.04 6.l E2 1.2E2 Kr89 0.27 4.7E3 2.9E3 )

Xel33 0.02 7.0E0 2.lEl X:135 0.05 9.6El 1.2E2 1 Xel35m 0.06 2.0E2 4.4El i Xel37 0.31 4.7E2 3.9E3 Xel38 0.19 1.8E3 9.0E2 Total 8.lE3 8.4E3

Based on noble gas distribution from ANSI N237-1976/ANS-18.1," Source Term Specification".

1 C-4 l

Hope Creek ODCM Rev :

1 i

APPENDIX D 1:. sa l

TECHNICAL BASIS FOR EFFECTIVE DOSE PARAMETERS l GASEOUS RADIOACTIVE EFFLUENTS i l

i

Hope Creek ODCM Re APPENDIX D Technical Basis for Effective Dose Parameters Gaseous Radioactive Effluent Releases l i

I The pathway dose factors for the controlling infant age group were evaluated to determine the control pathway, organ and radionuclide. This analysis was performed to provide a simplified method determining compliance with Technical Specification 3.11.2.3. For the infant age group, the contro:

l pathway is the grass - cow - milk (g/c/m) pathway. An infant receives a greater radiation dose fron g/c/m pathway than any other pathway. Of this g/c/m pathway, the maximum exposed organ includind total body, is the thyroid, and the highest dose contributor is radionuclide I 131. The results of evaluation are presented in Table D-1.

For purposes of simplifying the details of the dose calculation process, it is conservative to identi controlling, dose significant organ and radionuclide and limit the calculation process to the use of the conversion factor for the organ and radionuclide. Multiplication of the total release (i.e., cumuln activity for all radionuclides) by this dose conversion factor provides for a dose calculation method t l simplified while also being conservative.

For the evaluation of the dose commitment via a controlling pathway and age group, it is conservativ use the infant, g/c/m, thyroid, I-131 pathway dose factor (1.67E12m2 . mrem /yr per uCi/sec). By approach, the maximum dose commitment will be overestimated since 1-131 has the highest pathway factor of a'l radionuclides evaluated.

For evaluating compliance with the dose limits of Technical Specification 3.11.2.3, the follox simplified equation may be used:

D ,, = 3.17E-8

W

RI-131

I Q, (D.1)

Where:

D., = maximum organ dose (mrem)

W = atmospheric dispersion parameter to the controlling location (s) as identified in Table 2-3.

X/Q = Atmospheric dispersion for inhalation pathway (sec/m')

D/Q = atmospheric disposition for vegetation, milk and ground plane exposure pathways (m.2)

Q, = cumulative release over the period ofinterest for radioiodines and paniculates (uCi). '

3.17E-8 = conversion factor (yr/sec) :

RI-131 = l-131 dose parameter for the thyroid for the identified controlling pathway.

= 1.05E12, infant thyroid dose parameter with the grass - cow - milk pathway controlling 1 (m mrem /yr per uCi/sec) I D-1

]

)

s i

1 l

Hope Creek ODCM Rev l~

The ground plane exposure and inhalation pathways need not be considered when the above sim calculational method is used because of the overall negligible contribution of these pathways thyroid dose. It is recognized that for some particulate radionuclides (e.g., Co-60 and Cs-137), the g exposure pathway may represent a higher dose contribution than either the vegetation or milk pathway However, use of the I-131 thyroid dose parameter for all radionuclides will maximize the or calculation, especially considering that no other radionuclides has a higher dose parameter for any via any pathway than I-131 for the thyroid via the milk pathway.

l The location of exposure pathways and the maximum organ dose calculation may be based on available pathways in the surrounding environment of Hope Creek as identified by the annual land census (Technical Specification 3.12.2). Otherwise, the dose will be evaluated based on the predetermined l controlling pathways as identified in Table 2-3.

D-2

1 Hope Creek ODCM Re TABLE D-1 Infant Dose Contributions Fraction of Total Organ and Body Dose PATHWAYS Target Organs Grass - Cow - Milk Ground Plane Total Body 0.02 O.15 Bone 0.23 0.14 Liver 0.09 0.15 Thyroid 0.59 0.15

{

Kidney 0.02 0.15 Lung 0.01 0.14 GI LLI 0.02 0.15 l

l I

TABLE D-2 Fraction of Dose Contribution by Pathway l

Pathway Frac Grass-Cow-Milk 0.92

, Ground Plane 0.08 l

Inhalation N/A l l D-3 l

l

i l

Hope Creek ODCM Rev 17 APPENDIX E 4 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM -

SAMPLE TYPE, LOCATION AND ANALYSIS D-4

Hope Creek ODCM Rev {

APPENDIX E SAMPLE DESIGNATION Samples are identified by a three pari code. The first two letters are the power station identification code, in this case "SA". The next thre: letters are for the media sampled.

AIO = AirIodine IDM = Immersion Dose (TLD)

APT = Air Particulates - MLK = Milk ECH = Hard Shell Blue Crab PWR = Potable Water (Raw)

ESF = Edible Fish PWT = Potable Water (Treated)

ESS = Sediment SWA = Surface Water WWA= Well Water 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=ENG, etc. The next digit is a letter which represents the radial distance from the plant:

S = On-site location E = 4-5 miles off-site A = 0-1 miles off-site F = 5-10 miles off-site B = l-2 miles off-site G = 10 20 miles off-site C = 2-3 miles off-site H = > 20 miles off-site

)

4

~

D = 3-4 miles off-site 1

The last number is the station numerical designation within each sector and zone; e.g.,1,2,3,... For example; the designation SA WWA 5D1 would indicate a sample in the SGS p gram (SA), consisting-of well water (WWA), which had been collected in sector number 5, centered a. 90'(due east) with respect to the reactor site at a radical distance of 3 to 4 miles off-site,(therefore, radial distance D). Th!

number 1 indicated that this is sampling station #1 in that particular sector.

The Radiological Environmental Monitoring Program is a common program for both Salem and Hope Creek Generating Stations.

l l

l I

E-2

Hope Creek ODCM Rev 17 SAMPLING LOCATIONS All sampling locations and specific information about the individual locations are given in Table E-1.

Maps E 1 and E-2 show the locations of sampling stations with respect to the site.

TABLE E-1 A. Direct Radiation Monitoring Locations (IDM)

STATION CODE STATION LOCATION ISI 0.55 mi. N of vent 2S2 0.4 mi. NNE of vent 2S4 0.59 mi. NNE of vent 3SI 0.58 mi. NE of vent 4SI 0.60 mi ENE of vent SSI 1.0 mi. E of vent; site access road 6S2 0.21 mi. ESE of vent; observation building 7St 0.12 mi. SE of vent; station personnel gate

10S1 0.14 mi. SSW of vent; cire water bldg.

1ISI 0.09 mi. SW of vent; service water bldg.

ISSI 0.57 mi. NW of vent 16S1 0.54 mi. NNW of vent 4D2 3.7 mi. ENE of vent; Alloway Creek Neck Road 5DI 3.5 mi. E of vent; local farm 10D1 3.9 mi. SSW of vent; Taylor's Bridge Spur 14DI 3.4 mi. WNW of vent; Bay View, Delaware 15DI 3.8 mi. NW of vent: Rt 9, Augustine Beach, DE.

2El 4.4 mi. NNE of vent; local farm 3El 4.1 mi. NE of vent; local farm 9El 4.2 mi. S of vent 11E2 5.0 mi. SW of vent .

12El 4.4 mi. WSW of vent; Thomas Landing 13El 4.2 mi. W of vent; Diehl House Lab 16El 4.1 mi. NNW of vent; Port Penn IFl 5.8 mi. N of vent; Fort Elfsborg 2F2 8.7 mi. NNE of vent; Salem Substation 2F5 7.4 mi. NNE of vent; Salem High School 2F6 7.3 mi. NNE of vent; PSE&G Training Center E-3

Hope Creek ODCM Res t

TABLE E-1(Continued) <

l A. Direct Radiation Monitoring Locations (IDM) .

STATION CODE STATION LOCATION 3F2 5.1 mi. NE of vent; Hancocks Bridge Munc. Bldg 3F3 8.6 mi. NE of vent; Quinton Township School 4F2 6.0 mi. ENE of vent; Mays Lane, Harmersville SF1 , 6.5 mi. E of vent; Canton 6F1 6.4 mi. ESE of vent; Stow Neck Road 7F2 9.1 mi. SE of vent; Bayside, NJ 10F2 5.8 mi. SSW of vent; Rt. 9 11F1 6.2 mi. SW of vent; Taylors Bridge, DE.

12F1 9.4 mi. WSW of vent; Townsend Elementary School ,

13F2 6.5 mi. W of vent; Odessa, DE.

13F3 9.3 mi. W of vent; Redding Middle School 13F4 9.8 mi. W of vent; Middletown, DE.

14F2 6.6 mi. WNW of vent; Boyds Corner 15F3 5.4 mi. NW cf vent 16F2 8.1 mi. NNW of vent: Delaware City Public School 1G3 19 mi. N of vent; N. Church St. Wilmington, DE 3G1 17 mi. NE of vent; local farm 10G1 12 mi. SSW of vent; Smyrna, Delaware 16G1 15 mi. NNW of vent; Wilmington Airport 3H1 32 mi. NE of vent; National Park, NJ 14G1 1 f.8 mi. WNW of vent; Rte 286; Bethel Church Road; Delaware

TLD locations will be maintained by site area monitoring program

3. Air Sampling Locations (AIO, APT)

STATION CODE STATION LOCATION SSI- 1.0 mi. E of vent; site access road 5DI 3.5 mi. E of vent; local farm 16El 4.1 mi. NNW of vent; Port Penn j 1F1 5.8 mi. N of vent; Fort Elfsborg 2F6 7.3 mi. NNE of vent; PSE&G Training Center

'14G1 11.8 mi. WNW of vent; Rtc 286; Bethel Church Road; Delaware E-4

Hope Creek ODCM Rev 17 TABLE E-1(Continued)

C. Surface Water Locations (SWA) - Delaware River i

STATION CODE STATION LOCATION i1Al 0.2 mi. SW of vent; Salem Outfall Area 12Cl 2.5 mi. WSW of vent; West bank of Delaware River 7El 4.5 mi. SE of vent; Delaware River l 1

16F1 6.9 mi. NNW of vent; C&D Canal D. Ground Water Locations (WWA)

STATION CODE STATION LOCATION

~ No public drinking water samples or irrigation water samples are taken as these pathways are not directly affected by liquid effluents discharged from Hope Creek or Salem Generating Stations.

E. Drinking Water Locations (PWR,PWT)

STATION CODE STATION LOCATION No public drinking water samples or irrigation water samples are taken as these pathways are not directly affected by liquid effluents discharged from Hope Creek or Salem Generating Stations.

F. Water Sediment Locations (ESS)

STATION CODE STATION LOCATION 11A1 0.2 mi. SW of vent; Salem outfall area 15A1 0.3 mi. NW of vent; Hope Creek outfall area 16Al 0.7 mi. NNW of vent; South Storm Drain outfall 12Cl 2.5 mi. WSW of vent; West bank of Delaware river 7El 4.5 mi. SE of vent; I mi West of Mad Horse River 16F1 6.9 mi. NNW of vent; C&D Canal 6S2 0.2 mi. ESE of vent; observation building G. Milk Sampling Locations (MLK)

STATION CODE STATION LOCATION 2F7 5.7 mi. NNE of vent; local farm

'1IF3 5.3 mi. SW of vent; Townsend DE.

14F4 7.6 mi. WNW of vent; local farm 3G1 17 mi. NE of vent; local farm E-5

Hope Creek ODCM Re

~

TABLE E-1 (Continued) j 1

H. Fish and Invertebrate Locations (ESF,ECH)

STATION CODE STA'JON LOCATION i l

11A1 0.2 mi. SW of vent; Salem outfall area 12Cl 2.5 mi. WSW of vent; West bank of Delaware River 7El 4.5 mi. SE of vent; I mi West of Mad Horse Creek ,

l L Food Product Locations STATION CODE STATION LOCATION The Delaware River at the location of Salem and Hope Creek Nuclear Power Plants is a brackish water source. No irrigation of food products is performed using water in the vicinity from which liquid plant wastes have been discharged.

E-6

. I

p:

Hope Creek ODCM Rev 17 1 SAMPLES COLLECTION AND ANALYSIS Sampic Collection Method Analysis Air Particulate Continuous low volume Gross Beta analysis airsampler. Sample on each weekly collected every week sample. Gamma i along with the filter spectrometry shall I change. be performed if

m gross beta exceeds 10 times the yearly mean of the centrol statiott value. Samples shall be analyzed 24 hrs or more after collection to allow for radon and thorium daughter decay. Gamma isotopic analysis on quarterly l composites.

Air lodine A TEDA impregnated Iodine 131 analysis charcoal cartridge is are performed on eonnected to air each weekly sample. I particulate air sampler l

and is collected weekly I at filter change.

Crab and Fish Two batch samples are Genuna isotopic scaled in a plastic analysis of edible bag orjar and frozen portion on collection.

semi-annually or when In season.

i Sediment A sediment sample is Gamma isotopic taken semi-annually, analysis semi-annually.

Direct 2 TLD's will be Gamma dose quarterly.

collected from each location quarterly.

E-7 l

7 ..

Hope Creek ODCM Rev SAMPLE COLLECTION AND ANALYSIS (Cont'd)

Sample Collection Method Analysis .

l Milk Sample of fresh milk Gamma isotopic is collected for each analysis and 1-131 ,

farm semi monthly when analysis on each !

cows are in pasture, sample on collection. :

monthly at other times. -

l Water Sample to be collected Gamma isotopic Potable, monthly providing winter monthly H-3 on Surface) icing conditions allow. quarterly surface .

sample, monthly on ground water sample.

=

i l

E-8

---_ _~ ___

Hope Creek ODCM Rev 17 Figure E-1 ONSITE SAMPLING LOCATIONS I

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E 10

p Hope Creek ODCM Rev 17 APPENDIX F M.AXIMUM PERMISSIBLE CONCENTRATIONS >

LIQUID EFFLUENTS '

F1

.. Hope Creek ODCM Rev 17 :

The following radionuclide concentrations were obtained from 10 CFR 20 Appendix B.

Table II, Column 2 as revised January 1,1991.

j Table F-1 Maximum Permissible Concentrations 1 Element Isotope Soluble Conc Insoluble Conc.

(uci/ml) (uci/ml)

Actinium (89) Ac-22'i 2E-6 3E-4 Ac 228 9E-5 9E 5 :

Americ,ium (95) . Am-241 4E-6 3E-5 Am 242m 4E-6 9E-5 Am 242 1E-4 1 E-4 f Am 243 4E-6 3 E-5 ,

Am-244 SE 3 5E 3 Antimony (51) Sb-122 3E-5 3 E-5 Sb-124 2E-5 2E-5 .

Sb-125 1E-4 1E-4 :

Arsenic (33) As-73 SE-4 5E-4 As 74 SE-5 SE-5 As 76 2E 5 2E-5 -

As 77 8E-5 8E 5 ;

Astatine (85) At 211 2E-6 7E-5 Banum (56) Ba-131 _ 2E-4 2E 4

)

Ba 140 3E-5 2E 5 t 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 4E-4 4E-4 Bromine (35) Br-82 3 E-4 4E 5 Cadmium (48) Cd-109 2E-4 2E-4 Cd-l1Sm 3 E-5 3E 5 Cd-l l5 3E-5 4E-5 Calcium (20) Ca-45 9E-6 2E-4 Ca-47 5E 5 3E-5 F-2

)

Hope Creek ODCM Rev 17 Table F-1 (Continued)

Element - Isotope Soluble Conc. Insoluble Conc. j (uci/ml) (uci/ml) '

Califomium (98) Cf-249 4E-6 2E-5 Cf-250 l E-5 3E-5 Cf-251 4E-6 3E-5 Cf 252 7E 6 7E 6 Cf-253 IE-4 IE 4 Cf-254 IE-7 IE 7 Carbon (6) - C-14 CE-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 IE-3 I

Cs 134 9E-6 4E 5 Cs-135 lE-4 2E-4 Cs-136 9E-5 6E-5 -

Cs 137 2E-5 4E-5 !

Chlorine (17) Cl36 8E-5 6E-5 Cl38 4E-4

)

4E-4 Chromium (24) Cr 2E-3 2E-3 Cobalt (27) Co-57 5E-4 4E-4 Co-58m

3E-3 2E-3 Co 58 I E-4 9E-5 Co-60 SE-5 3E-5 Copper (29) Cu-64 3 E-4 2E-4 )

Curium (96) Cm-242 2E-5 2E-5 Cm-243 5E-6 2E-5 Cm 244 7E-6 3E-5 Cm 245 4E 6 3 E-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

1 Hope Creek ODCM Rev i7 Table F 1 (Continued)

]

Element Isotope Soluble Conc. Insoluble Conc.

(uci/ml) (uci/ml) )

Dysprosium (66) 1135 4E-6 7E-5 Iridium (77) Ir 190 2E-4 2E-4 3 Ir-192 4E-5 4E-5 J Ir-194 3 E-5 3E-5 fron (26) Fe 55 8E-4 2E-3

]

Fe-59 6E-5 5E-5 /

Lanthanum (57) La-140 2E-5 2E-5 Einsteinium (99) Es-253 2E-5 2E-5 Es 254m 2E 5 2E-5 l

Es 254 l E-5 IE-5 Es-255 3E-5 3E-5 I Erbium (68) Er-169 9E-5 9E-5 Er-!71 1E-4 1 E-4 Europium (63) Eu-l52 (9.2 hrs) 6E-5 6E-5 Eu-152 (l3 yrs) 8E-5 8E-5 Eu-154 2E-5 2E-5 .

Eu-155 2E-4 2E-4 Fermium (l00) Fm-254 1E-4 1E-4 Fm-255 3 E-5 3E-5 Fm 256 9E-7 9E-7 Fluorine (9) F-18 8E-4 5E-4 Gadolinium (64) Gd-l53 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 1 E-4 Au-198 5E-5 5E-5 Au 199 2E-4 2E-4 Hafnium (72) Hf-181 7E-5 7E-5 Holmium (67) Ho-166 3 E-5 3 E-5 Hydrogen (3) H3 3E-3 3E-3 Indium (49) In-113m 1E-3 1E-3 In-114m 2E-5 2E-5 In-115m 4E-4 4E-4 In-115 9E-5 9E-5 '

s 1

F-4

r

,. Hope Creek ODCM Rev 17 d Table F-1 (Continued) l Element isotope Soluble Conc. Insoluble Conc. i (uci/ml) (uci/ml) lodine (53) 1125 2E 7 2E-4 1-126 3E-7 9E-5 1129- 6E-8 2E-4 1-131 3E-7 6E 5 j 1132 8E-6 2E-4 !

I133 IE-6 4E-5 1-134 2E-5 6E-4 Lead (82) Pb-203 4E-4 4E4 Pb 210 1E-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 lE-4 lE-4 Mn-56 lE-4 IE-4 {

Mercury (80) Hg-197m 2E-4 2E-4 Hg-197 3 E-4 SE-4 Hg-203 2E-5 1E-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 Neptunium (93) Np 237 - 3E-6 3E-5 Np-239 1E-4 1E-4 Nickel (28) Ni 59 2E-4 2E 3 Ni-63 3E-5 7E-4 Ni-65 1E-4 1 E-4 !

Niobium (41) Nb-93m 4E-4 4 E-4 .

Nb-95 l E-4 IE-4 l 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 1 Pd 109 9E-5 7E-5 l

f i

F-5 J

m l

. Hope Creek ODCM Rev 17

' Table F-1 (Continued)

~

Element Isotope Soluble Conc. Insoluble Conc.

(uci/ml) (uci/m!)~~ j Phosphorus (15) P-32 2E-5 2E 5 Platinum (78) Pt-191 1E-4 1 E-4 )

Pt-193m IE 3 IE-3 J Pt-193 9Ei 2E-3 Pt-197m lE-3 ' 9E-4 j Pt197 IE4 IE-4 Plutonium (94) Pu-238 SE-6 3E-5 Pu-239 Pu 240 SE-6 3E 5 )

~

SE-6 3E-5 Pu-241 2E-4 IE-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 (61) Pm 147 2E-4 2E-4 Pm-149 4E-5 4E 5 ,

Protactinium (91) Pa-230 2E-4 2E-4 j

^

Pa-231 9E-7 2E-5 Pa-233 lE-4 IE-4 1 Radium (88) Ra-223 7E-7 ~ 4E 6 Ra-224 2E-6 SE-6 Ra-226 3E-8 3E-5 l Ra-228 3E-8 3E 5 Rhenium (75) Re-183 6E-4 3E-4 Re-186 9E-5 5E-5 .

Re 187 3E-3 2E-3 Re-188 6E-5 3E-5 1 Rhodium (45) Rh-103m 1E-2 1E-2 I Rh 105 IE 4 IE-4 Rubidium (37) Rb-86 7E-5 2E-5 l Rb-87 i T-4 2E-4 Ruthenium de '[,' Ru-97 4E-4 3E-4 3

Ru-103 8E 5 8E-5

]

)

F-6 1

- _ . . . . . . . . . )

4 Hope Creek ODCM Rev 17 Table F 1 (Continued)

Element Isotope Soluble Conc. Insoluble Conc.

(uci/ml) (uci/ml)

Ru-105 1E-4 1E-4 Ru-106 IE-5 1E-5 i Samarium (62) Sm 147 6E 5 7E 5 Sm 151 4E-4 4E-4 i Sm-153 8E 5 8E 5 Scandium (21) Sc 46 4E-5

{

4E 5 Sc-47 9E 5 9E-5 I Sc 48 3E-5 3E-5 Selenium (34) Se 75 3E-4 3 E-4 l Silicon (14) Si 31 9E-4 2E-4 Silver (47) - Ag 105 IE-4 I E-4 j Ag l10m 3E-5 3E-5 i Ag 111 4E 5 4E 5 i Sodium (ll) Na 22 4E-5 3 E-5 Na-24 2E-4 3 E-5 - I Strontium (38) Sr-85m 7E-3 7E-3 Sr-85 lE-4 2E-4 Sr-89 3E-6 3 E-5 Sr-90 3E-7 4E-5 Sr-91 7E-5 SE-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 iE-2 IE-2 Tc-96 I E-4 SE-5 !

Tc 97m 4E-4 2E 4 i Tc 97 2E-3 8E-4 Tc 99m 6E-3 3E-3 Tc-99 3 E-4 2E-4 Tellurium (52) Te-125m 2E-4 1 E-4 Te-127m 6E-5 5E-5 Te-127 3E-4 2E-4 Te-129m 3E-5 2E-5 Te-129 8E-4 8E-4 Te-131m 6E-5 4E-5 F-7 L____--____

E j Hope Creek ODCM Rev 17 Table F-1 (Continued)

Element Isotope Soluble Conc. Insoluble Conc.

(uci/ml) (uci/ml)

Te-132 3E 2E-5

]

Terbium (65) Tb-160 4E-5 4E 5

)

Thallium (81) TI-200 4E-4 2E 4 j TI-201 3E-4 2E 4 TI-202 lE-4 7E-5 TI-204 1E-4 6E-5 Thorium (90) Th-227 -

2E-5 2E 5 Th-228 7E 6 IE 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-ll3 9E-5 8E 5 Sn-124 2E-5 2E-5 }

l Tungsten (74) W-181 4E-4 3E 4 1 W-185 IE-4 IE-4 W-187 - 7E-5 6E-5 Uranium (92) U-230 SE-6 SE-6

)

U-232 3E-5 3E-5 U-233 3 E-5 3E-5 U 234 3E 5 3E-5 U-235 3E-5 3 E-5 U-236 3 E-5 3E-5 l U-238 4E-5 4E-5 U-240 3 E-5 3 E-5 U-natural 3E 5 3E-5 Vanadium (23) V-48 3E-5 3E-5 Ytterbium (70) Yb-175 IE-4 IE-4 F-8 l

\

.- Hope Creek ODCM Rev 17

{ Table F-1 (Continued)

Element Isotope Soluble Conc. Insoluble Conc.

f (uci/ml) (uci/ml)

Yttrium Y-90 2E-5 2E 5 Y-91m 3E-3 3 E-3 Y-91 3E-5 3E 5 Y-92 6E-5 6E-5 Y-93 3E-5 3E 5 Zinc (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 j Zr-95 6E-5 t 6E-5 Zr-97 2E-5 2E 5 Any single radio- 3E-6 3 E-6

( nuclide not listed above with decay mode other than '

alpha emission or spontaneous fission and with radio -

active half life greater than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Any single radio- 3E-8

( nuclide not listed 3E 8 above, which decays

[ by alpha emission or l spontaneous fission.

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 of each radionuclide are known, the limiting values should be

[ derived as follows: Determine, for each radionuclide in the mixture, the ratio between the quant present in the mixture and the limit otherwise established in Appendix 8 for the specific radionuclide a a mixture. The sum of such ratios for all the radionuclides in the mixture may

( not exceed "i s.e " unity").

F-9

l I

Hope Creek ODCM Rev 17 l APPENDIX G l

l CONTROLS FOR RELEASES FROM THE f

CIRCULATING WATER DEWATERING SUMP 1

/

j l

l 1

G-1

_ _ _ _ _ _ - _ ---- -- ---------- _ - - - l

Hope Creek ODCM Rev i 7

(

APPENDIX G CONTROLS FOR RELEASES FROM THE

[ CIRCULATING WATER DEWATERING SUMP The radiation monitoring instrumentation for the circulating water dewatering sump includes an offline gamma scintillation detection (Nal) with a sample flow indicator. The system does not include any discharge flow control device or measurement of discharge flow. Also, the radiation monitor is not included in the current Technical Specifications. As indicated in Appendix A. the setpoint for the radiation monitor is set by design and station procedures to be less than 2x background radiation levels. Releases through the sump at levels below the setpoint are considered continuous releases. In order to control and quantify continuous releases from this point, the following sampling and analysis schedule is required:

j Sampling Minimum Type of LLD l Frequency Analysis Activity (uCi/ml)

Frequency Analysis Continuous M Principal Gamma Emitters SE-7 Composite M I-131 lE 6 M H-3 lE-5 M Gross Alpha IE-7

( Grab sample M Dissolved and 1E 5 M Entrained Noble Gases (Gamma emitters)

Continuous Q Sr-89, Sr-90 SE-8 Composite Fe-55 IE-6 Sampling and analysis for batch releases from this point shall be performed to meet the requirements of Technical Specification Table 4.11.1.1.1-1.

The following controls apply to the effluent radiation monitoring system (RY-4557):

MINUMUM OPERABILITY - with the radiation monitoring system inoperable, suspend t

' continuous release of radioactive effluents via this pathway. Batch releases may be performed provided ACTION 110 of Technical Specification 3.3.7.10 is implemented.

i G-2

~;

}

Hope Creek ODCM Rev I7 SURVEILLANCE REQUIREMENTS -

]

A. CHANNEL CHECK - Daily, including verification of sample flow through the radiation monitor during sump pump operation B. SOURCE CHECK - Monthly - accomplished by automatic check source operation l

C. CHANNEL CALIBRATION - Every 18 months D. CHANNEL FUNCTIONAL TEST - Quarterly

)

l E. FLOW RATE MEASUREMENT DEVICES - Since there are no discharge process flow rate

~

i measurement devices, there are no surveillance requirements for discharge process flow rate.

Conservative assumptions should be made for release rates. The maximum release rate from the )

sump is 100 gpm. This value should be used to calculate radiation monitor setpoints and for calculation of concentration to detennine compliance with Technical Specification 3.11.1.1.

More realistic values may be used to calculate total activity released and dose consequences.

Actual values should be used if process flow measurement devices are installed.

]

)

1 l

'l

)

1 G-3

___ _--____O

@@ Line 2: / Line 2: @@
 | number = ML20206D407
 | issue date = 12/31/1998
-| title = Annual Radioactive Effluent Release Rept for 1998. with 990427 Ltr
+| title = Annual Radioactive Effluent Release Rept for 1998. with
 | author name = Powell D
 | author affiliation = PUBLIC SERVICE ELECTRIC &amp; GAS CO. OF NEW JERSEY
@@ Line 11: / Line 11: @@
 | contact person =
 | document report number = LR-N99180, NUDOCS 9905040097
+| title reference date = 04-27-1999
 | document type = ENVIRONMENTAL MONITORING REPORTS(&amp;RADIOLOGICAL)-PERIODIC, TEXT-ENVIRONMENTAL REPORTS
 | page count = 220

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