Text

Semiannual Radioactive Effluent Rept Jan-June 1996
	ML18102A365
Person / Time
Site:	Salem
Issue date:	06/30/1996
From:	; Public Service Enterprise Group
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	RERR-40, NUDOCS 9609100447
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SALEM GENERATING STATION SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SGS RERR-40 SALEM UNIT NOS. 1 & 2 UNIT 1 DOCKET NO. 50-272 UNIT 2 DOCKET NO. 50-311 OPERATING LICENSE NO. DPR-70 OPERATING LICENSE NO. DPR-75

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SALEM GENERATING STATION SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SGS RERR-40 SALEM UNIT NOS. 1 & 2 UNIT 1 DOCKET NO. 50-272 UNIT 2 DOCKET NO. 50-311 OPERATING LICENSE NO. DPR-70 OPERATING LICENSE NO. DPR-75 AUGUST, 1996

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I SALEM GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -

JUNE 199 6 Table of Contents INTRODUCTION PART A.

PRELIMINARY SUPPLEMENTAL INFORMATION...............

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1. 0 REGULATORY LIMITS..................................

3 1.1 Fission and Activation Gas Release Limits.....

3 1.2 Iodine Particulates, and Tritium..............

3 1.3 Liquid Effluents Release Limits...............

4 2.0 3.0 4.0 5.0 6.0 7.0 8.0 PART B.

PART c.

PART D.

PART E.

PART F.

PART G.

PART H.

PART I.

PART J.

PART K.

1. 4 Total Dose Limit..............................

4 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)...........

4 AVERAGE ENERGY.....................................

5 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY......................................

5 BATCH RELEASES.....................................

7 UNPLANNED RELEASES.................................

7 ELEVATED RADIATION MONITOR RESPONSES...............

7 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS......................................

7 GASEOUS EFFLUENTS..................................

8 LIQUID EFFLUENTS...................................

8 SOLID WASTE........................................

8 RADIOLOGICAL IMPACT ON MAN.........................

8 Liquid Pathways.....................................

8 Air Pathways.......................................

9 Direct Radiation...................................

9 Total Dose................... ;.....................

9 Dose to Members of the Public on Site............. 10 Assessment......................................... 10 METEOROLOGICAL DATA................................. 11 ODCM CHANGES....................................... 11 INOPERABLE MONITORS................................

12 PROCESS CONTROL PROGRAM (PCP) CHANGES............... 13 ENVIRONMENTAL MONITORING LOCATION CHANGES........... 13 MAJOR CHANGES TO WASTE PROCESSING SYSTEMS........... 13 ii

INTRODUCTION SALEM GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY -

JUNE 1996 This report, SGS-RERR-40, summarizes information pertaining to the releases of radioactive materials in liquid, gaseous and solid form from the Salem Generating Station (SGS) Units 1 and 2 for the period January 1, 1996 to June 30, 1996.

This Semiannual RERR is submitted for both Salem Units and combines those sections which are common to each unit.

Separate tables of releases and release totals are included whenever separate processing systems exist.

Salem Unit 1 is a Westinghouse Pressurized Water Reactor which has a licensed core power of 3411 MWt and an approximate net electrical output of 1115 MWe.

Salem Unit 1 achieved initial criticality on December 11, 1976 and went into commercial operations on June 30, 1977.

Salem Unit 2 is a Westinghouse Pressurized Water Reactor which has a licensed core power of 3411 MWt and an approximate net electrical output of 1115 MWe.

Salem Unit 2 achieved initial criticality on August 2, 1980 and went into commercial operations on October 13, 1981.

The report is prepared in the format of Regulatory Guide 1.21, Appendix B, as required by Specification 6.9.1.8 of the Salem Technical Specifications. Preceding the tables summarizing the gaseous and liquid discharges and solid waste shipments are our responses to parts A-F of the "Supplemental Information" section of Regulatory Guide 1.21, Appendix B.

As required by Regulatory Guide 1.21, our Technical Specification limits are described in detail within this report along with a summary description of how measurements and determinations of the total activity discharged were developed.

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I To facilitate determination of compliance with 40CFR190 requirements, the following information on electrical output is provided.

Unit 1 generated 0 megawatt-hours of electrical energy (net) during the reporting period.

Unit 2 generated O megawatt-hours of electrical energy (net) during the reporting period.

Results of liquid and gaseous* composites analyzed for Sr-89, sr-90 and Fe-55 for the second quarter of 1996 were not available for inclusion in this report.

The results of these composites will be provided in the next Radioactive Effluent Release Report.

The Sr-89, Sr-90 and Fe-55 analyses for the second half of 1995 (refer to RERR-39) have been completed; amended pages to RERR-39 are included in this report.

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PART A. PRELIMINARY SUPPLEMENTAL INFORMATION 1.0 REGULATORY LIMITS 1.1 Fission and Activation Gas Release Limits The dose rate due to radioactive materials released in gaseous effluents from the site 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 and less than or equal to 3000 mrems/yr to the skin.

In addition, the air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site to areas at and beyond the site boundary, shall be limited to the following:

During any calendar quarter:

Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation, and During any calendar year:

Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

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

For Iodine-131, 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, from tritium, and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site to areas at and beyond the site boundary, shall be limited to the following:

During any calendar quarter:

Less than or equal to 7.5 mrems to any organ, and During any calendar year:

Less than or equal to 15 mrems to any organ.

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I 1.3 Liquid Effluents Release Limits

1. 4 The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR, Part 20, Appendix B, Table II, Column 2 for radionuclides other

than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 microcuries per milliliter.

In addition, the dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited:

During any cale.ndar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 rnrems to any organ.

Total Dose Limit The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be 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).

2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)

Regulatory Guide 1.21 requires that the licensee provide the MPCs used in determining allowable release rates for radioactive releases.

a.

b.

c.

MPC values were not used to determine the maximum release rates for fission gases, iodines, or particulates.

MPC values as stated in 10CFR20, Appendix B, Table II, Column 2 were used for liquids.

The MPC value used for dissolved or entrained noble gases is 2E-4 microcuries per milliliter.

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3.0 AVERAGE ENERGY Regulatory Guide 1.21 requires that the licensee provide the average energy of the radionuclide mixture in releases of fission and activation gases, if applicable.

Release limits for SGS are not based upon average energy, hence, this section does not apply.

4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY 4.1 Liquid Effluents Liquid effluents are monitored in accordance with Table 4.11-1 of the Technical Specifications.

During the period of record, all batch liquid wastes from the chemical drain tank and the laundry and hot shower tanks were routed to the hold-up 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 waste monitor hold-up tank and the chemical and volume control tanks.

Continuous liquid releases are defined as condensate releases from intermittent blowdown of the steam generators.

Specific activities from analyses were multiplied by the volume of effluent discharged to the environment in order to estimate the total liquid activity discharged.

The detection requirements of Tables 4.11-1 of the Technical Specifications are achieved or exceeded.

Radionuclides detected at concentrations below the Technical Specification detection limits (LLDs) are treated as being present. Radionuclides for which no activity was detected, while meeting the required LLDs, are treated as absent.

4.2 Gaseous Effluents Gaseous effluent streams are monitored and sampled in accordance with Table 4.11-2 of the Technical Specifications.

The plant vent is the final release point of all planned gaseous effluents and is continuously monitored by beta scintillator and high range GM tubes.

The vent is also continuously sampled for iodine and particulates with a charcoal cartridge and filter paper. The filter and charcoal are changed weekly, and analyzed on a multi-channel analyzer in the laboratory.

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I Noble gas sampling is also performed on all gas decay tanks and containment purges prior to their release to the environment. The plant vent is sampled weekly for noble gases.

The detection requirements of Tables 4.11-1 and 4.11-2 of the Technical Specifications are achieved or exceeded.

Radionuclides detected at concentrations below the Technical Specification detection limits (LLDs) are treated as being present. Radionuclides for which no activity was detected, while meeting the required LLDs, are treated as absent.

Continuous Mode gaseous releases are quantified by routine (monthly or weekly) sampling and isotopic analyses of the plant vent.

Specific activities for each isotope detected are multiplied by the total vent flow volume for the entire sampling period in order to estimate the normal continuous release of radioactivity through the plant vent.

Slightly elevated plant vent radiation monitor readings are treated as continuous releases.

The monitors response is converted to a "specific activity" using historical efficiency factors.

The "specific activity" is multiplied by a default volume of effluent discharge to estimate the total activity discharged.

Batch Mode gaseous releases are quantified by sampling each gas decay tank or containment purge prior to discharge.

Specific activities for each isotope are multiplied by the total volume of gas discharged for that batch.

Elevated plant vent radiation monitoring system readings while the channel is in an alarm state are treated as batch mode releases. If specific activity data from grab samples taken is not available, then the abnormal release is quantified by the use of the plant vent radiation monitors.

The monitors response is converted to a "specific activity" using historical efficiency factors.

The "specific activity" is multiplied by the volume of effluent discharged while the channel was in an alarm state in order to estimate.

the total activity discharged.

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4.3 Estimated Total Error The estimated total error of reported liquid and solid releases is within 25%

The estimated total error of the reported continuous gaseous releases is within 50% when concentrations exceed detectable levels.

This error is due primarily to variability of waste stream flow rates and changes in isotopic distributions of waste streams between sampling periods.

The estimated total error of the reported batch gaseous releases is within 10%.

Error estimates for releases where sample activity is below the detectable concentration levels are not included since error estimates at the LLD are not defined.

5.0 BATCH RELEASES Surnrnari.es of batch releases of gaseous and liquid effluents are provided in Tables 4A-l and 4B-l for Unit 1 and 4A-2 and 4B-2 for Unit 2.

6.0 UNPLANNED RELEASES During this reporting period there were no unplanned releases.

7.0 ELEVATED R-16/R41C CHANNEL RESPONSES During this reporting period, there were no elevated monitor readings on Salem Unit 1/2 R16/R41C.

8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS Our last report (RERR-39) did not include the quarterly Sr-89, Sr-90 and Fe-55 composite data for the fourth quarter of 1995.

Additionally, a worn "O" ring was discovered on the particulate filter housing assembly of the auxiliary sampling equipment for Salem Unit 2. The auxiliary sampling equipment is used to obtain samples when the installed radiation monitor is inoperable. The worn "O" ring permitted clean air to enter the sample stream at the particulate sample inlet resulting in a 20% dilution of the sample stream. The worn part has been replaced and an increased schedule of leak testing has been established to prevent reoccurrence of this problem. The time period of the leaking filter assembly was from 7/13/95 to 8/13/96. Gaseous effluent values for this time period have been corrected and the amended pages to RERR-39 are included at the end of this report.

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PART PART PART PART B.

GASEOUS EFFLUENTS See Summary Tables lA-1 thru lC for Salem Unit 1 Operations.

See Summary Tables lA-2 thru lC for Salem Unit 2 Operations.

c.

LIQUID EFFLUENTS See Summary Tables 2A-l thru 2B for Salem Unit 1 Operations.

See Summary Tables 2A-2 thru 2B for Salem Unit 2 Operations.

D.

SOLID WASTE See Summary in Table 3.

E.

RADIOLOGICAL IMPACT ON MAN The calculated individual doses in this section are based on the controlling dose pathways and age groups as described below. The estimated dose represents the 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 six month reporting interval.

Individual doses from batch and continuous releases were calculated using the annual average historic meteorological dispersion coefficients as described in the Offsite Dose Calculation Manual.

Population doses were calculated using the actual meteorological dispersion coefficients for the six month reporting interval.

Liquid Pathways (Units 1 & 2)

Age Group Location Total Body Organ Dose Adult Adult Total Body ----------

Organ (Liver) -------

Population (Total) --

Population (Average)-

Site Boundary Site Boundary 0. 10 3 mrem 0.138 mrem 0.110 person-rem 0.000024 mrem 8

Pathway Seafood Ingestion Seafood Ingestion Limit 3 mrem 10 mrem N/A N/A

Air Pathways (Units 1 & 2)

Age Group Location Total Body Skin Organ Dose All All Teenager Total Body ----------

Skin ----------------

Organ (Lung) --------

Population (Total)---

Population (Average)-

Direct Radiation Site Boundary Site Boundary Site Boundary 5.90E-9 mrem 4.98E-7 mrem 9.06E-3 mrem 2.17E-1 person-rem 4.82E-5 mrem Pathway Direct Exposure Direct Exposure Inhalation Limit 500 mremlyr 3000 mremlyr 10 mrem NIA NIA Direct radiation may be estimated by thermoluminescent dosimetric (TLD) measurements.

One method for comparing TLD measurements is by comparison with preoperational data.

It should be noted that the TLDs measure direct radiation from both the Salem and Hope Creek Generating Stations at Artificial Island, as well as natural background radiation.

TLD data for the six month reporting period is given below:

TLD 2S-2 5S-l Location 0.3 mile 0.9 mile Measurement 4.0 mradlmonth 3.6 mradlmonth These values are interpreted-to represent natural background. They are within the statistical variation associated with the pre-operational program results, which are: 3.7 mradlmonth for location 25-2, and 4.2 mradlmonth 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

<75 mrem to the thyroid 9

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for a calendar year. For Artificial Island, the major sources of dose are from liquid and gaseous effluents from the Salem and Hope Creek plants.

The following doses to members of the public have been calculated for the six month reporting period:

0.216 mrem 0.499 mrem

0. Oll mrem total body organ (GI-LLI) thyroid Dose to Members of the Public Due to Activities inside the Site Boundary.

In accordance with the requirements of Technical Specification 6.9.1.8, the dose to members of the public inside the site boundary has been calculated based on the following assumptions:

a. The most limiting member of the general public is the commercial food vendors.

b. Food vendors spend 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> per week on site.

c. The highest total body dose contributor is direct radiation received from Salem and Hope Creek operation.

d. Occupancy coincides with gaseous effluent discharges.

e. The food vendors are located near the restricted area boundary.

For the six month reporting period, the calculated doses are:

4.00E+OO l.07E-02 l.07E-02 Assessment mrem Total Body mrem Organ (Lung) mrem Thyroid Salem Units 1 and 2 were shutdown during the entire reporting period for extended maintenance and repair.

Gaseous and liquid effluents released from Salem station resulted in a minimal dose to the maximum hypothetical individual. All radioactive releases from Salem station during this reporting period were well within all Federal limits.

The following two trend graphs show the total curies of gaseous and liquid effluents released from Salem Units 1 and 2 for the past 5 years. Calculated doses in the graphs are to the maximum hypothetical individual.

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PART F.

PART G.

Salem Unit 1 and 2 Gaseous Effluents Noble Gas Curies Released and Calculated Dose Note : Calculated doses are to the maximum hypolhelical Individual 1.00E+03 --.--*------*

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Reporting Pertod Salem Units 1 and 2 Liquid Effluents Curies Released and Calculated Doses

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METEOROLOGICAL DATA

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-CURIES Cumulative joint wind frequency distributions by atmospheric stability class at the 300 foot elevation are provided for the first and second quarters of 1996 in Tables 5 and 6.

OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES During this period, there was one revision to the SGS off-site dose calculation manual. A copy of the revised ODCM is included in this report. The changes made to the ODCM did not reduce the accuracy or reliability of dose calculations or setpoint determinations. The changes to the ODCM were mostly editorial in nature.

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PART H.

INOPERABLE MONITORS During this period, the following effluent monitors were inoperable for more than 30 days:

Salem Unit 1:

Steam Generator Blowdown Process Radiation Monitors (1Rl9 A,B,C,D)

Containment Fan Coil Unit Process Radiation Monitor (1Rl3A-E)

Steam Generator Blowdown Flow Rate Monitors (1FA5836,1FA5837,1FA5838,1FA5839)

Plant Vent Noble Gas Radiation Monitor (1R41C)

Plant Vent Flow Rate Monitor (1FA8603)

Liquid Radwaste Disposal Process Radiation Monitor (1R18)

Salem Unit 2:

Steam Generator Blowdown Process Radiation Monitors (2R19 A,B,C,D)

Containment Fan Coil Unit Process Radiation Monitors (2R13 A,B,C)

Liquid Radwaste Disposal Process Radiation Monitor (2R18)

Chemical Waste Basin Process Radiation Monitor (2R37)

Steam Generator Blowdown Flowrate Monitors (2FA5836,2FA5837,2FA5838,2FA5839)

The above radiation monitors could not be returned to service within the specified time due to extended maintenance and repair outages on Unit 1 and 2. Salem Unit 1 has been shutdown since 5/17/95 and Unit 2 since 6/7/95. The above radiation monitors continue to be inoperable due to long-term system layup (flow unavailable) or maintenance/replacement of the radiation monitors.

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PART I.

PROCESS CONTROL PROGRAM (PCP) CHANGES During this reporting period, there were no changes to the Process Control Program.

PART J.

ENVIRONMENTAL MONITORING LOCATION CHANGES During the reporting period, there were minor changes to the environmental monitoring sampling program. A complete list of the changes is contained in the ODCM revision that is included with this document. The changes made to the environmental monitoring program did not reduce the objectives of the Radiological Environmental Monitoring Program (REMP).

PART K.

MAJOR CHNAGES TO WASTE PROCESSING SYSTEMS During this reporting period, there were no major changes to the waste processing systems at Salem Unit 1 or 2 13 1

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SALEM GENERATING STATION TABLE lA-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT I

JANUARY -

JUNE 1996 UNIT 1 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES I

Est.

1st 2nd Total I

Units Quarter Quarter Error %

A. Fission and Activation I

Gases

1. Total release Ci O.OOE+OO 5.84E-06 25

2. Average release rate for period uCi/sec O.OOE+OO 7.43E-07 I

3. Percent of technical specification limit (T.S. 3.11.2.2 (a))

O.OOE+OO 7.94E-09 I

B. Iodines

1. Total Iodine-131 Ci O.OOE+OO O.OOE+OO 25

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2. Average release I

rate for period uCi/sec O.OOE+OO O.OOE+OO

3. Percent of technical specification limit (2)

I (T.S. 3.ll.2.3(a))

4.43E-04 8.20E-04

c. Particulates I

1. Particulates with half-lives >8 days Ci O.OOE+OO 3.74E-06 25

2. Average release rate for period uCi/sec O.OOE+OO 4.76E-07 I

3. Percent of technical specification limit (2)

(T.S. 3.ll.2.3(a))

4.43E-04 8.20E-04 I

4. Gross alpha Ci O.OOE+OO O.OOE+OO

c. Tritium I

1. Total Release Ci l.63E+Ol 2.99E+Ol 25

2. Average release rate for period uCi/sec 2.07E+OO 3.81+00

3. Percent of technical I

specification limit (2)

(T. S. 3.ll.2.3(a))

4.43E-04 8.20E-04 I

( 1) For batch releases the estimated overall error is within 10%

(2) Iodine, tritium and particulates are treated as a group I

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SALEM GENERATING STATION TABLE lA-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -

JUNE 1996 UNIT 2 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES A. Fission and Activation Gases Unl.ts

1. Total release Ci

2. Average release rate for period uCi/sec

3. Percent of technical specification limit (T.S. 3.11.2.2 (a))

B. Iodines

1. Total Iodine-131 Ci

2. Average release rate for period uCi/sec

3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a))

C. Particulates

1. Particulates with half-lives >8 days Ci

2. Average release rate for period uCi/sec

3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a))

4. Gross alpha Ci C. Tritium 1st Quarter O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2.30E-04 O.OOE+OO O.OOE+OO 2.30E-04 O.OOE+OO

1. Total Release Ci 8.47E+OO

2. Average release rate for period uCi/sec l.OSE+OO

3. Percent of technical specification limit (2)

(T.S. 3.ll.2.3(a))

2.30E-04 2nd Quarter 5.25E-03 6.68E-04 7.14E-06 O.OOE+OO O.OOE+OO

1. OBE-03 2.27E-05 2.89E-06 l.OSE-03 O.OOE+OO 3.88E+Ol 4.94E+OO l.OSE-03 Est.

Total Error %

25 25 25 25 (1) For batch releases the estimated overall error is within 10%

(2) Iodine, tritium and particulates are treated as a group 15 1

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1-SALEM GENERATING STATION TABLE lB-1 I

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -

JUNE 1996 I

GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 1 I

CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd I

Nuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission Gases I

Krypton-85 Ci O.OOE+OO O.OOE+OO O.OOE+OO 5.84E-06 I

TOTALS Ci O.OOE+OO O.OOE+OO O.OOE+OO 5.84E-06

2. Iodines I

Iodine-131 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TOTALS Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

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3. Particulates (half-live >8 days)

I Cobalt-60 Ci O.OOE+OO 3.74E-06 O.OOE+OO O.OOE+OO Hydrogen-3 Ci 1.63E+01 2.99E+01 O.OOE+OO O.OOE+OO I

TOTALS Ci 1.63E+01 2.99E+01 O.OOE+OO O.OOE+OO I

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.* I SALEM GENERATING STATION TABLE 1B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT I

JANUARY -

JUNE 1996 GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 2 I

CONTINUOUS MODE BATCH MODE I

1st 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission Gases I

Krypton-85 Ci O.OOE+OO O.OOE+OO O.OOE+OO 5.25E-03 I

TOTALS Ci O.OOE+OO O.OOE+OO O.OOE+OO S.25E-03 I

2. Iodines Iodine-131 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

-1 TOTALS Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

3. Particulates

-I (half-lives >8 days)

Hydrogen-3 Ci 8.47E+OO 3.88E+Ol O.OOE+OO O.OOE+OO I

Cobalt-60 Ci O.OOE+OO 6.63E-06 O.OOE+OO O.OOE+OO Manganese-54 Ci O.OOE+OO

1. 45E-05 O.OOE+OO O.OOE+OO Cesium-137 Ci O.OOE+OO 1.57E-06 O.OOE+OO O.OOE+OO I

TOTALS Ci 8.47E+OO 3.88E+Ol O.OOE+OO O.OOE+OO I

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L SALEM GENERATING STATION TABLE lC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -

JUNE 1996 UNITS 1 AND 2 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES CONTINUOUS MODE BATCH MODE Nuclides Released Unit 1st Quarter 2nd Quarter 1st Quarter There were no ground level gaseous releases during this reporting period.

18 2nd Quarter

1 SALEM GENERATING STATION TABLE 2A-l I

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -

JUNE 1996 UNIT 1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES I

Est.

1st 2nd Total I

Units Quarter Quarter Error %

A. Fission and activation I

products

1. Total release (not including tritium, I

gases, alpha)

Ci l.37E-01 2.96E-02 25

2. Average diluted concentration during period uCi/mL l.23E-07 4.83E-08 I

3. Percent of technical specification limit (T. S. 3.11.1.2. (a))

2.63E+OO 5.29E-01

-1 B. Tritium

1. Total release Ci l.35E+Ol 3.12E+OO 25

1

2. Average diluted concentration during period uCi/mL l.20E-05 5.0SE-06

3. Percent of technical I

specification limit (T.S. 3.11.1.1) 4.0lE-01 l.69E-01

c. Dissolved and entrained I

noble gases

1. Total release Ci O.OOE+OO O.OOE+OO 25

2. Average diluted I

concentration during period uCi/mL O.OOE+OO O.OOE+OO

3. Percent of technical I

specification limit (T.S. 3.11.1.1)

O.OOE+OO O.OOE+OO D. Gross alpha activity I

1. Total release Ci O.OOE+OO O.OOE+OO 25 E. Volume of waste release I

(prior to dilution -

Batch Release) liters 6.78E+05 3.72E+05 25 F. Volume of dilution water I

used during entire period liters 5.38E+09 7.83E+09 25 I

19 I

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I SALEM GENERATING STATION I

TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -

JUNE 1996 UNIT 2 I

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est.

I 1st 2nd Total Units Quarter Quarter Error %

I A. Fission and activation products

1. Total release (not including tritium, I

gases, alpha)

Ci 1.70E-01

1. 45E-02 25

2. Average diluted concentration during I

period uCi/mL 2.33E-07 4.llE-08

3. Percent of technical specification limit 1~

(T. S. 3.11.1.2. (a))

3.36£+00 3.26E-01 B. Tritium

1. Total release Ci 1.13E+Ol 4.06E-01 25

. I

2. Average diluted concentration during period uCi/mL 1.55E-05 1.15E-06 I

3. Percent of technical specification limit (T. S. 3.11.1.1) 5.16E-Ol 3.84E-02 I

c. Dissolved and entrained noble gases

1. Total release Ci O.OOE+OO O.OOE+OO 25 I

2. Average diluted concentration during period uCi/mL O.OOE+OO O.OOE+OO I

3. Percent of technical specification limit (T.S. 3.11.1.1)

O.OOE+OO O.OOE+OO I

D. Gross alpha activity

1. Total release Ci O.OOE+OO O.OOE+OO 25 I

E. Volume of waste release (prior to dilution -

Batch Release) liters 4.96E+05

1. 24E+05 25 I

F. Volume of dilution water used during entire period liters 7.32E+10 7.58E+10 25 I

I 20 I

SALEM GENERATING STATION TABLE 2B-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -

JUNE 1996 LIQUID EFFLUENTS UNIT 1 Nuclides Released Unit A. Fission Products Manganese-54 Iron-55 Cobalt-57 Cobalt-58 Cobalt-60 Strontium-90 Antimony-124 Antimony-125 Cesium-134 Cesium-137 TOTALS Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci CONTINUOUS MODE 1st Quarter O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 2nd Quarter O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO B. Tritium, Dissolved and Entrained Gases Hydrogen-3 Ci O.OOE+OO O.OOE+OO TOTALS Ci O.OOE+OO O.OOE+OO 21 BATCH MODE 1st Quarter 1.22E-03 5.49E-03 4.83E-04 2.96E-02 2.21E-02

1. 56E-04 3.20E-05 5.lOE-03 2.60E-02 4.72E-02 1.37E-01 2nd Quarter 3.37E-04 O.OOE+OO 7.56E-05 2.76E-03 l.07E-02 O.OOE+OO O.OOE+OO 1.74E-03 4.44E-03 9.55E-03 2.96E-02 1.35E+Ol 3.12E+OO 1.35E+Ol 3.12E+OO 1

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I SALEM GENERATING STATION TABLE 2B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL JANUARY -

JUNE 1996 LIQUID EFFLUENTS UNIT 2 CONTINUOUS MODE 1st 2nd Nuclides Released Unit Quarter Quarter A. Fission Products Manganese-54 Ci O.OOE+OO O.OOE+OO Iron-55 Ci O.OOE+OO O.OOE+OO Cobalt-57 Ci O.OOE+OO O.OOE+OO Cobalt-58 Ci O.OOE+OO O.OOE+OO Cobalt-60 Ci O.OOE+OO O.OOE+OO Strontiurn-90 Ci O.OOE+OO O.OOE+OO Antimony-124 Ci O.OOE+OO O.OOE+OO Antimony-125 Ci O.OOE+OO O.OOE+OO Cesiurn-134 Ci O.OOE+OO O.OOE+OO Cesiurn-137 Ci O.OOE+OO O.OOE+OO TOTALS Ci O.OOE+OO O.OOE+OO B. Tritium, Dissolved and Entrained Gases Hydrogen-3 Ci O.OOE+OO O.OOE+OO TOTALS O.OOE+OO O.OOE+OO 22 REPORT BATCH MODE 1st 2nd Quarter Quarter 1.52E-03 1.42E-04 2.78E-03 O.OOE+OO 5.00E-04 3.42E-05 3.85E-02 8.64E-04 2.01E-02 2.85E-03 4.22E-05 O.OOE+OO 9.23E-05 O.OOE+OO 6.73E-03 5.llE-04 3.75E-02 3.55E-03 6.21E-02 6.55E-03 l.70E-Ol

1. 45E-02 l.13E+Ol 4.06E-01 l.13E+Ol 4.06E-01

SALEM GENERATING STATION TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -

JUNE 1996 UNITS 1 AND 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 6-month Est. Total

1.

Type of waste Units(l) period Error, %

a.

Spent resins, filters, m3 2.44E+OO sludges, evaporator bottoms Ci

1. 56E+OO 25

b.

Dry compressible waste, m3

1. 63E+Ol contaminated equipment.

Ci

1. 52E+OO 25

c.

Irradiated components, m3 O.OOE+OO control rods Ci O.OOE+OO 25

d.

Others (described) m3 O.OOE+OO Ci O.OOE+OO 25

2.

Estimate of major nuclide composition (for Type A and B waste)

Resins DAW

(%)

(Ci)

( % )

(Ci)

Iron-55 49.5 0.77 37.9 0.58 Cobalt-60 20.1 0.31 6.2 0.09 Cobalt-58 10.9 0.17 26.9 0.41 Nickel-63 9.4 0.15 9.9 0.15 Niobium-95 2.9 0.05 N/D N/D Zirconium-95 2.2 0.03 N/D N/D Antimony-125

1. 6 0.02

1. 3 0.02 Silver-llOm

1. 2 0.02 N/D N/D*

Manganese-54 1.1 0.02 1.2 0.02 Cesium-137 1.1 0.02 7.8 0.12 Cesium-134 N/D N/D 5.0 0.08 Hydrogen-3 N/D N/D

1. 0 0.02 23 I

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3.

SALEM GENERATING STATION TABLE 3 (CONT ID)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -

JUNE 1996 UNITS 1 AND 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS Solid Waste Disposition Number of Shipments 5

1 Mode of Transportation Truck Truck Destination Type of Containers Oak Ridge, Tn Strong,Tight Containers Barnwell, S.C. High Integrity Note: No solidification agents were used during this reporting period.

4. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments None Mode of Transportation N/A 24 Destination N/A

SALEM GENERATING STATION TABLE 4A-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -

JUNE 1996

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY

1.

Dates:

January 1 -

March 31, 1996

2.

Type of release:

Gas

3.

Number of releases during the 1st Quarter:

0

4.

5.

6.

7.

8.

Total time duration for all releases of type listed above:

O.OOE+OO minutes Maximum duration for release of type listed above:

O.OOE+OO minutes Average duration for release of type listed above:

O.OOE+OO minutes Minimum duration for release of type listed above:

O.OOE+OO minutes Average stream flow (dilution flow) during the period of release:

N/A 25 I

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I SALEM GENERATING STATION TABLE 4A-l (CONT ID)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -

JUNE 1996

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY

1.

2.

3.

4.

5.

6.

7.

8.

Dates:

April 1 -

June 30, 1996 Type of release:

Gas Number of releases during the 2nd Quarter:

1 Total time duration for all releases of type listed above:

l.SOE+Ol minutes Maximum duration for release of type listed above:

l.SOE+Ol minutes Average duration for release of type listed above:

l.SOE+Ol minutes Minimum duration for release of type listed above:

l.SOE+Ol minutes Average stream flow {dilution flow) during the period of release:

N/A 26

SALEM GENERATING STATION TABLE 4A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -

JUNE 1996

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY

1.

2.

3.

4.

5.

6.

7.

8.

Dates:

January 1 - March 31, 1996 Type of release:

Gas Number of releases during the 1st Quarter:

6 Total time duration for all releases of type listed above:

4.82E+03 minutes Maximum duration for release of type listed above:

l.41E+03 minutes Average duration for release of type listed above:

8.04E+02 minutes Minimum duration for release of type listed above:

l.40E+Ol minutes Average stream flow (dilution flow) during the period of release:

N/A 27 I

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I SALEM GENERATING STATION TABLE 4A-2 (CONT ID)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -

JUNE 1996

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A.BATCH MODE UNIT 2 BATCH RELEASES ONLY

1.

Dates:

April 1 - June 30, 1996

2.

Type of release:

Gas

3.

Number of releases during the 2nd Quarter:

15

4.

Total time duration for all releases of type listed above:

1;93E+03 minutes

5.

6.

7.

8.

Maximum duration for release of type listed above:

2.14E+02 minutes Average duration for release of type listed above:

l.29E+02 minutes Minimum duration for release of type listed above:

7.lOE+Ol minutes Average stream flow (dilution flow) during the period of release:

N/A 28

SALEM GENERATING STATION TABLE 4B-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -

JUNE 1996

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY

1.

Dates:

January 1 - March 31, 1996

2.

Type of release:

Liquid

3.

Number of releases during the 1st Quarter:

12

4.

Total time duration for all releases of type listed above:

2.96E+03 minutes

5.

6.

7.

8.

Maximum duration for release of type listed above:

3.46E+02 minutes Average duration for release of type listed above:

2.47E+02 minutes Minimum duration for release of type listed above:

l.13E+02 minutes Average stream flow (dilution flow) during the period of release: l.OOE+OS gpm 29 I

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I SALEM GENERATING STATION TABLE 4B-l (CONT ID)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -

JUNE 1996

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY

1.

Dates:

April 1 - June 30, 1996 2.

Type of release:

Liquid

3.

Number of releases during the 2nd Quarter:

6

4.

Total time duration for all releases of type listed above:

1.62E+03 minutes

5.

Maximum duration for release of type listed above:

3.16E+02 minutes

6.

7.

8.

Average duration for release of type listed above:

2.70E+02 minutes Minimum duration for release of type listed above:

2.21E+02 minutes Average stream flow (dilution flow) during the period of release: 1.00E+OS gpm 30

SALEM GENERATING STATION TABLE 48-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -

JUNE 1996

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY

1.

Dates:

January 1 - March 31, 1996

2.

Type of release:

Liquid

3.

Number of releases during the 1st Quarter:

8

4.

Total time duration for all releases of type listed above:

l.92E+03 minutes

5.

6.

7.

8.

Maximum duration for release of type listed above:

2.97E+02 minutes Average duration for release of type listed above:

2.40E+02 minutes Minimum duration for release of type listed above:

l.93E+02 minutes Average stream flow (dilution flow) during the period of release: l.OOE+OS gpm 31 I

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I SALEM GENERATING STATION TABLE 4B-2 (CONT ID)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY -

JUNE 1996

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 2 BATCH RELEASES ONLY

1.

Dates:

March 1 -

June 30, 1996

2.

Type of release:

Liquid

3.

Number of releases during the 2nd Quarter:

2

4.

Total time duration for all releases of type listed above:

9.32E+02 minutes

5.

6.

7.

8.

Maximum duration for release of type listed above:

S.25E+02 minutes Average duration for release of type listed above:

4.66E+02 minutes Minimum duration for release of type listed above:

4.07E+02 minutes Average stream flow (dilution flow) during the period of release: 1.00E+OS gpm 32

METEOROLOGICAL DATA JOINT FREQUENCY DISTRIBUTION JANUARY -

JUNE 1996

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P1 ARTIFICIAL ISLAND 1/96 - 3/96 JOINT DISTRIBUTION OF UIND DIRECTION ANO SPEED*

BY ATMOSPHERIC STABILITY CLASS UIND: 300 FT LAPSE RATE:

LE -1. 9 DEG C/100H DELTA T: (300-33FT)

CLASS A YIND SPEED GROUPS (MPH) 0.0*0.5 0.6-3.5 3.6*7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUH PERCENT DIRECTION SUM PERCENT SUM PERCENT SUH PERCENT SUM PERCENT SUM PERCENT SUH PERCENT SUH PERCENT N

0 0.0 0

0.0 0

0.0 3

0.1 1

0.0 0

0.0 4

0.2 NNE 0

0.0 0

0.0 5

0.2 1

0.0 0

0.0 6

0.3 NE 0

0.0 0

0.0 ENE 0

0.0 0

0.0 E

0 0.0 0

0.0 1

0.0 3

o. 1 0

0.0 0

0.0 4

0.2 ESE 0

0.0 0

o.o 0

0.0 0

0.0 SE 0

0.0 0

0.0 SSE 0

0.0 0

0.0 1

0.0 0

0.0 1

0.0 s

0 0.0 0

0.0 0

0.0 4

0.2 0

0.0 0

0.0 4

0.2 SSI./

0 0.0 0

0.0 0

0.0 1

0.0 0

0.0 2

.0.1 SI./

0 0.0 0

0.0 0

0.0 1

0.0 0

0.0 1

0.0 I.ISi./

0 0.0 0

0.0 1

0.0 7

0.3 1

0.0 0

0.0 10 0.5 y

0 0.0 1

0.0 0

0.0 8

0.4 0

0.0 0

0.0 9

0.4 l./NIJ 0

0.0 0

0.0.

6 0.3 2

0.1 2

0.1 10 0.5 NI./

0 0.0 0

0.0 0

0.0 11 0.5 13 0.6 0

0.0 24

1. 1 NNI./

0 0.0 0

0.0 0

0.0 2

0.1 0

0.0 1

0.0 4

0.2 0

0.0 1

0.0 2

0.1 12 0.6 43 2.0 18 0.8 3

0. 1 79 3.7 HEAN l./IND SPEED:

16.6 HISSING:

0

ARTIFICIAL ISLAND 1/96 - 3/96 JOINT DISTRIBUTION OF IJIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS IJIND: 300 FT LAPSE RATE: -1.8 TO -1.7 DEG C/100H DELTA T: (300-33FT)

CLASS B IJIND SPEED GROUPS (HPH)

'0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUH PERCENT DIRECT ION SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT N

0 0.0 0

0.0 0

0.0 2

0.1 3

0.1 0

0.0 0

0.0 5

0.2 NNE 0

0.0 0

0.0 3

0.1 4

0.2 0

0.0 0

0.0 7

0.3 NE 0

0.0 0

0.0 3

0. 1 5

0.2 0

0.0 0

0.0 8

0.4 ENE 0

0.0 0

0.0 1

0.0 E

0 0.0 0

o.o 0

0.0 0

0.0 ESE 0

0.0 0

0.0 SE 0

0.0 0

0.0 SSE 0

0.0 0

0.0 1

0.0 0

0.0 2

0. 1 s

0 0.0 0

0.0 1

0.0 0

0.0 2

0.1 SSIJ 0

0.0 0

0.0 2

0.1 0

0.0 2

0.1 0

0.0 0

0.0 4

0.2 SIJ 0

0.0 0

0.0 2

0.1 2

0. 1 2

0.1 0

0.0 0

0.0 6

0.3 IJSIJ 0

0.0 0

0.0 1

0.0 0

0.0 3

0. 1 IJ 0

o.o 0

0.0 1

o.o 0

0.0 5

0.2 0

0.0 0

0.0 6

0.3 IJNIJ 0

0.0 1

0.0 0

0.0 1

0.0 4

0.2 1

0.0 3

0.1 10 0.5 NIJ 0

0.0 0

0.0 1

0.0 3

0.1 12 0.6 8

0.4 0.0 25 1.2 NNIJ 0

0.0 0

0.0 8

0.4 8

0.4 0

0.0 0

0.0 16 0.8 0

0.0 0.0

, 1 0.5 27 1.3 41 1.9 10 0.5 5

0.2 95 4.5 HEAN IJJND SPEED:

14.2 HISSING:

0

ARTIFICIAL ISLAND 1/96 - 3/96 JOINT DISTRIBUTION OF lllND DIRECTION AND SPEED BY ATMOSPHERIC STABILIT.Y CLASS lllND: 300 FT LAPSE RATE: -1.6 TO -1.5 DEG C/100H DELTA T: (300-33FT)

CLASS C lllND SPEED GROUPS (HPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUH PERCENT DIRECTION SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT N

0 0.0 0

0.0 1

0.0 4

0.2 2

0.1 2

0.1 0

0.0 9

0.4 NNE 0

0.0 0

0.0 2

0.1 4

0.2 0

0.0 0

0.0 6

0.3 NE 0

0.0 0

0.0 1

0.0 0

0.0 1

0.0 ENE 0

0.0 0

0.0 1

0.0 E

0 0.0 0

0.0 0

0.0 ESE 0

0.0 0

o.o 0

0.0 0

0.0 SE 0

0.0 0

0.0 1

0.0 0

0.0 1

0.0 SSE 0

0.0 0

0.0 2

0.1 1

0.0 1

0.0 0

0.0 4

0.2 s

0 0.0 0

0.0 1

0.0 0

0.0.

0 0.0 1

0.0 SSll 0

0.0 0

0.0 1

0.0 0

0.0 1

0.0 0

0.0 2

0.1 Sii 0

0.0 0

0.0 1

0.0 0

0.0 2

0.1 llSll 0

0.0 0

0.0 2

o. 1 0

0.0 1

0.0 0

0.0 3

0.1 II 0

0.0 1

0.0 0

0.0 1

0.0 0

0.0 2

0.1 llNll 0

0.0 0

0.0 3

0.1 0

0.0 2

0.1 5

0.2 3

0.1 13 0.6 NII 0

0.0 0

0.0 3

0.1 1

0.0 3

0.1 6

0.3 0

0.0 13 0.6 NNll 0

0.0 0

0.0 4

0.2 2

0. 1 2

o. 1 1

0.0 9

0.4 0

0.0 1

0.0 18 0.8 16 0.8 12 0.6 15 0.7 5

0.2 67 3.2 HEAN Ill ND SPEED:

13.6 HISSING:

0

--1 ARTIFICIAL ISLAND 1/96

3/96 JOINT DISTRIBUTION OF UIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS UIND: 300 FT LAPSE RATE: *1.4 TO *0.5 DEG C/100H DELTA T: (300*33FT)

CLASS 0 UIND SPEED GROUPS CHPH) 0.0-0.5 0.6*3.5 3.6-7.5

. 7.6-12.5 12.6-18.5 18.6*24.5 GE 24.6 SUH PERCENT DIRECTION SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT N

0 0.0 0

0.0 3

0. 1 9

0.4 12 0.6 23 1.1 14 0.7 61 2.9 NNE 0

0.0 D

0.0 8

0.4 24 1.1 15 0.7 16 0.8 12 0.6 75 3.5 NE 0

0.0 1

0.0 4

0.2 13 0.6 19 0.9 16 0.8 14 0.7 67 3.2 ENE 0

0.0 0

0.0 4

0.2 9

0.4 6

0.3 4

0.2 5

0.2 28 1.3 E

0 0.0 4

0.2 6

0.3 5

0.2 0

0.0 0

o.o 0

0.0 15 0.7 ESE 0

0.0 0

0.0 2

o. 1 2

0.1 0

0.0 0

o.o 0

0.0 4

0.2 SE 0

0.0 1

0.0 2

0.1 1

0.0 2

0.1.

1 0.0 8

0.4 SSE 0

0.0 1

0.0 7

0.3 11 o.s 7

0.3 1

0.0 28 1.3 s

0 0.0 4

0.2 2

0.1 5

0.2 11 0.5 8

0.4 1

0.0 31 1.5 ssu 0

0.0 0

0.0 7

0.3 9

0.4 5

0.2 9

0.4 3

0. 1 33 1.6 SU 0

0.0 1

0.0 6

0.3 4

0.2 5

0.2 2

0.1 1

0.0 19 0.9 llSll 0

0.0 1

0.0 8

0.4 6

0.3 6

0.3 0

0.0 0

0.0 21 1.0 II 0

0.0 1

0.0 8

0.4 10 0.5 9

0.4 3

0.1 0

0.0 31 1.5 llNll 0

0.0 0

0.0 7

0.3 47 2.2 27 1.3 20 0.9 101 4.8 NII 0

0.0 0

0.0 5

0.2 8

0.4 42 2.0 64 3.0 25 1.2 144 6.ll NNll 0

0.0 1

0.0 4

0.2 15 0.7 12 0.6 10 0.5 9

0.4 51 2.4 0

0.0 15 0.7 69 3.3 135 6.4 201 9.5 191 9.0 106 5.0 717 33.8 HEAN 111 ND SPEED:

17.0 HISSING:

0 I

l ARTIFICIAL ISLAND 1/96 - 3/96 JOINT DISTRIBUTION OF IJIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS IJIND: 300 FT LAPSE RATE: -0.4 TO 1.5 DEG C/100H DELTA T: (300-33FT)

CLASS E

~IND SPEED GROUPS (MPH) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUH PERCENT DIRECTION SUH PERCENT SUH PERCENT SUH PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUH PERCENT N

0 0.0 5

0.2 12 0.6 7

0.3 15 0.7 22 1.0 3

0.1 64 3.0 NNE 0

0.0 1

0.0 3

0.1 10 0.5 8

0.4 7

0.3 1

0.0 30

1. 4 NE 0

0.0 2

0.1 6

0.3 22 1.0 29 1.4 7

0.3 1

0.0 67 3.2 ENE 0

0.0 2

0.1 3

0.1 12 0.6 6

0.3 0

0.0 0

0.0 23 1.1 E

0 0.0 2

0.1 1

0.0 2

0.1 0

o.o 0

0.0 2

0.1 7

0.3 ESE 0

0.0 0

0.0 2

0.1 3

0.1 4

0.2 1

0.0 0

0.0 10 0.5 SE 0

0.0 3

0.1 2

0.1 12 0.6 9

0.4 30 1.4 SSE 0

0.0 2

o. 1 6

0.3 7

0.3 8

0.4 2

0.1 5

0.2 30 1.4 s

0 0.0 3

0.1 7

0.3 10 0.5 25 1.2 6

0.3 1

0.0 52 2.5 SSIJ 0

0.0 2

0.1 8

0.4 17 0.8 21 1.0 3

0.1 1

0.0 52 2.5 SIJ 0

0.0 6

0.3 7

0.3 9

0.4 7

0.3 7

0.3 6

0.3 42 2.0 IJSIJ 0

0.0 2

0.1 4

0.2 8

0.4 7

0.3 4

0.2 0

0.0 25 1.2 IJ 0

0.0 3

0.1 4

0.2 7

0.3 22 1.0 10 0.5 5

0.2 51 2.4 IJNIJ 0

0.0 1

0.0 3

0.1 13 0.6 29 1.4 16 0.8 12 0.6 74 3.5 NIJ 0

0.0 2

0. 1 5

0.2 22 1.0 48 2.3 19 0.9 5

0.2 101 4.8 NNIJ 0

0.0 3

0. 1 9

0.4

15.

0.7 17 0.8 8

0.4 11 0.5 63 3.0 0

0.0 39 1.8 82 3.9 166 7.8 248

11. 7 124 5.9 62 2.9 721 34.0 MEAN IJI ND SPEED:

14.4 MISSING:

0

ARTIFICIAL ISLAND 1/96 - 3/96 JOINT DISTRIBUTION OF YIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS YIND: 300 FT LAPSE RATE:

1.6 TO 4.0 DEG C/lOOH DELTA T: (300-33FT)

CLASS f YIND SPEED GROUPS (HPH) o.o-o.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUH PERCENT DIRECT ION SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT N

0 0.0 0

0.0 2

0.1 3

0.1 15 0.7 0

0.0 0

0.0 20 0.9 NNE 0

0.0 0

0.0 3

. 0.1 8

0.4 2

0.1 3

0.1 0

0.0 16 0.8 NE 0

0.0 4

0.2 2

0.1 5

0.2 3

0.1 0

0.0 0

0.0 14 0.7 ENE 0

0.0 1

0.0 2

0.1 2

0.1 0

0.0 0

0.0 6

0.3 E

0 0.0 0

0.0 4

0.2 2

0.1 0

o.o 0

0.0 0

0.0 6

0.3 ESE 0

0.0 0

o_o 1

0.0 3

0.1 0

0.0 0

0.0 4

0.2 SE 0

0.0 1

0.0 5

0.2 4

0.2 5

0.2 23

1. 1 43 2.0 SSE 0

0.0 0

0.0 4

0.2 8

0.4 7

0.3 13 0.6 11 0.5 43 2.0 s

0 0.0 0

0.0 0

0.0 8

0.4 8

0.4 1

0.0 8

0.4 25 1.2 SSY 0

0.0 0

0.0 3

0.1 5

0.2 7

0.3 5

0.2 6

0.3 26 1.2 SY 0

0.0 0

o.o 4

0.2 8

0.4 7

0.3 1

0.0 20 0.9 YSY 0

0.0 0

0.0 2

0.1 3

0.1 6

0.3 0

0.0 11 0.5 y

0 0.0 1

0.0 1

0.0 4

0.2 6

0.3 7

0.3 1

0.0 20 0.9 YNY 0

0.0 0

0.0 2

0.1 4

0.2 1

0.0 2

0. 1 0

0.0 9

0.4 NY 0

0.0 0

o.o 2

0.1 1

0.0 7

0.3 0

0.0 0

0.0 10 0.5 NNY 0

0.0 1

0.0 2

0. 1 2

0.1 4

0.2 0

0.0 0

0.0 9

0.4 0

0.0 8

0.4 31 1.5 63 3.0 81 3.8 49 2.3 50 2.4 282 13.3 HEAN YI ND SPEED:

16.9 HISSING:

0 1

-1 ARTIFICIAL ISLAND 1/96 - 3/96 JOINT DISTRIBUTION OF lllND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS lllND: 300 FT LAPSE RATE:

GT 4.D DEG C/100H DELTA T: (300*33FT)

CLASS G lllND SPEED GROUPS CHPH) o.o-o.5 0.6*3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUH PERCENT DIRECTION SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT N

0 0.0 0

0.0 0

0.0 2

0.1 0

0.0 2

0.1 NNE 0

0.0 0

0.0 NE 0

0.0 0

o.o ENE 0

0.0 0

o.o 0

0.0 0

0.0 E

0 0.0 0

0.0 0

o.o 0

0.0 ESE 0

O.D 0

0.0 0

0.0 SE 0

0.0 0

0.0 1

0.0 7

0.3 3

0.1 3

0.1 10 0.5 24

1. 1 SSE 0

0.0 1

0.0 3

o. 1 8

0.4 6

0.3 6

0.3 27 1.3 51 2.4 s

0 0.0 0

0.0 1

0.0 11 0.5 11 0.5 3

0.1 3

0.1 29 1.4 SSll 0

0.0 1

0.0 4

0.2 3

0.1 4

0.2 2

o. 1 2

0. 1 16 0.8 Sii 0

0.0 1

0.0 5

0.2 6

0.3 3

0.1 1

0.0 0

0.0 16 0.8 llSll 0

0.0 0

0.0 1

0.0 5

0.2 5

0.2 0

0.0 0

0.0 11 0.5 II 0

0.0 0

0.0 1

0.0 0

0.0 1

0.0 0

0.0 2

0.1 llNll 0

0.0 0

0.0 2

0.1 0

0.0 0

0.0 2

0. 1 NII 0

0.0 0

0.0 1

0.0 2

0.1 0

0.0 0

o.o 3

0. 1 NNll 0

0.0 0

0.0 1

0.0 0

0.0 2

0.1 0

0.0 3

0.1 18 0.8 42 2.0 36 1.7 17 0.8 42 2.0 158 7.5 HEAN lllND SPEED:

18.6 HISSING:

0

ARTIFICIAL ISLAND 1/96 - 3/96 JOINT DISTRIBUTION Of UIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS UIND: 300 FT DELTA T: (300-33FT)

ALL STABILITY CLASSES UIND SPEED GROUPS (MPH) o.o-oJ 0.6-3.5 3.6-7.5 7.6-12-5 12.6-18.5 18.6-24.5 GE 24.6 SUH PERCENT DIRECT ION SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT N

0 0.0 5

0_2 18 0.8 28 1.3 48 2_3 49 2.3 17 0.8 165 7.8 NNE 0

0.0 1

0.0 16 0.8 49 2.3 34 1.6 27 1.3 13 0.6 140 6.6 NE 0

0.0 7

0.3 16 0.8 45

2. 1 51 2.4 23

1. 1 15 0.7 157 7.4 ENE 0

0.0 3

0. 1 8

0.4 23

1. 1 14 0.7 4

0.2 7

0.3 59 2.8 E

0 0.0 6

0.3 12 0.6 12 0.6 0

0.0 0

0.0 2*

0.1 32

1. 5 ESE 0

0.0 0

0.0 4

0.2 6

0.3 7

0.3 1

0.0 0

0.0 18 0.8 SE 0

0.0 5

0.2 10 0.5 15 0.7 11 0.5 22 1.0 43 2.0 106 5.0 SSE 0

o.o 4

0.2 17 0.8 33 1.6 33 1.6 28 1.3 44 2.1 159 7.5 s

0 0.0 7

0.3 12 0.6 35 1.7 59 2.8 18 0.8 13 0.6 144 6.8 SSU 0

0.0 3

0.1 25 1.2 35

1. 7 41 1.9 19 0.9 12 0.6 135 6.4 SU 0

0.0 8

0.4 21 1.0 27 1.3 25 1.2 17 0.8 8

0.4 106 5.0 USU 0

0.0 3

0.1 16 0.8 23 1.1 30 1.4 12 0.6 0

0.0 84 4.0 u

0 0.0 7

0.3 15 0.7 22 1.0 51 2.4 20 0.9 6

0.3 121 5.7 UNU 0

0.0 2

0. 1 10 0.5 25 1.2 89 4.2 53 2.5 40 1.9 219 10.3 NU 0

0.0 2

0.1 16 '

0.8 36

1. 7 125 5.9 110 5.2 31 1.5 320 15.1 NNU 0

0.0 5

0.2 15 0.7 47 2.2 44

2. 1 21 1.0 22 1.0 154 7.3 0

0.0 68 3.2 231 10.9 461 21.8 662 31.2 424 20.0 273 12.9 2119 100.0 HISSING HOURS:

65 HEAN UIND SPEED:

16.0

ARTIFICIAL ISLAND 1/96 - 3/96 JOINT DISTRIBUTION OF \\llND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS

\\llND: 300 FT DELTA T: (300-33FT)

DIRECTION VS SPEED ONLY

\\llND SPEED GROUPS (MPH) o.o-o-5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6*24.5 GE 24.6 SUH PERCENT DIRECTION SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT N

0 0.0 5

0.2 19 0.9 32 1.5 50 2.3 49 2.2 17 0.6 172 7.9 NNE 0

0.0 1

0.0 17 0.8 50 2.3 34 1.6 27 1.2 13 0.6 142 6.5 NE 0

0.0 7

0.3 17 0.8 46

2. 1 51 2.3 23

1. 1 15 0.7 159 7.3 ENE 0

0.0 3

0.1 8

0.4 23 1.1 14 0.6 4

0.2 7

0.3 59 2.7 E

0 0.0 6

0.3 12 0.5 12 0.5 0

0.0 0

0.0 2

0.1 32

1. 5 ESE 0

0.0 0

0.0 4

0.2 6

0.3 7

0.3 1

0.0 0

0.0 16 0.6 SE 0

0.0 5

0.2 10 0.5 15 0.7 12 0.5 22 1.0 43 2.0 107 4.9 SSE 0

0.0 4

0.2 17 0.8 34 1.6 33 1.5 28 1.3 44 2.0 160 7.3 s

0 0.0 7

0.3 12 0.5 36 1.6 59 2.7 18 0.8 13 0.6 145 6.6 SS\\I 0

0.0 3

o. 1 26 1.2 35 1.6 41 1.9 19 0.9 13 0.6 137 6.3 S\\I 0

0.0 8

0.4 22 1.0 27 1.2 25

1. 1 17 0.8 8

0.4 107 4.9

\\IS\\I 0

0.0 3

0. 1 17 0.8 26 1.2 30 1.4 12 0.5 0

0.0 66 4.0

\\I 0

0.0 9

0.4 17 0.6 25

1. 1 52 2.4 21 1.0 6

0.3 130 6.0

\\IN\\I 0

0.0 2

0. 1 12 0.5 31 1.4 96 4.4 55 2.5 40 1.8 236 10.6 NII 0

0.0 2

0. 1 16 0.7 38

1. 7 132 6.0 113 5.2 32 1.5 333 15.2 NN\\I 0

0.0 5

0.2 15 0.7 50 2.3 46

2. 1 21 1.0 22 1.0 159 7.3 0

0.0 70 3.2 241 11.0 466 22.3 662 31.2 430 19.7 275 12.6 2164 100.0 HISSING HOURS:

0 MEAN \\llND SPEED:

15.9

ARTIFICIAL ISLAND 4/96 - 6/96 JOINT DISTRIBUTION OF lllND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS lllND: 300 FT LAPSE RATE:

LE -1. 9 DEG C/100H DELTA T: (300-33FT)

CLASS A lllND SPEED GROUPS (MPH) o.o-o.'5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUH PERCENT DIRECTION SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT N

0 0.0 0

0.0 0

0.0 1

0.1 1

0.1 2

0. 1 1

0. 1 5

0.3 NNE 0

0.0 0

0.0 1

0.1 0

0.0 0

0.0 1

0.1 NE 0

0.0 0

0.0 2

0.1 1

0.1 0

0.0 0

0.0 3

0.2 ENE 0

0.0 0

0.0 E

0 0.0 0

0.0 0

0.0 ESE 0

0.0 0

0.0 1

0. 1 0

0.0 0

0.0 1

0. 1 SE 0

0.0 0

0.0 1

0. 1 2

0.1 1

0. 1 3

0.2 1

0.1 8

0.4 SSE 0

0.0 0

0.0 1

0.1 2

0. 1 4

0.2 2

0.1 1

0. 1 10 0.5 s

0 0.0 0

0.0 0

o.o 2

0.1 0

0.0 0

0.0 2

0. 1 SSll 0

0.0 0

0.0 2

0.1 0

0.0 0

0.0 7

0.4 9

0.5 Sii 0

0.0 0

0.0 2

0. 1 0

o.o 3

0.2 5

0.3 llSll 0

0.0 0

0.0 3

0.2 7

0.4 1

0. 1 3

0.2 0

0.0 14 0.7 II 0

0.0 0

0.0 2

0. 1 2

0.1 3

0.2 0

0.0 7

0.4 llNll 0

0.0 0

0.0 3

0.2 4

0.2 2

o. 1 11 0.6 2

0. 1 22 1.2 NII 0

0.0 0

0.0 5

0.3 12 0.6 10 0.5 6

0.3 33

1. 7 NNll 0

0.0 0

0.0 2

0. 1 8

0.4 9

0.5 3

0.2 22 1.2 0

0.0 0

o.o 11 0.6 30 1.6 34 1.8 43 2.3 24 1.3 142 7.4 HEAN lllND SPEED:

17.2 HISSING:

1

ARTIFICIAL ISLAND 4/96 - 6/96 JOINT DISTRIBUTION OF lllND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS lllND: 300 FT LAPSE RATE: -1.8 TO -1.7 DEG C/100H DELTA T: (300-33FT)

CLASS B lllND SPEED GROUPS (HPH)

D.0-0.'5 0.6-3_5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5

. GE 24.6 SUH PERCENT DIRECTION SUH PERCENT SUM PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUM PERCENT SUH PERCENT N

0 0.0 0

o.o 3

0.2 8

0.4 4

0.2 2

D. 1 0

0.0 17 0.9 NNE 0

0.0 0

0.0 1

0.1 2

0.1 0

0.0 0

0.D

3.

0.2 NE 0

0.0 0

0.0 1

o_ 1 1

0. 1 1

0.1 0

0.0 0

0.0 3

D.2 ENE 0

0.0 0

0.0 D

0.0 0

0.0 E

0 0.0 0

0.0 1

0.1 0

0.0 0

0.0 1

0. 1 ESE 0

0.0 0

0.0 SE 0

0.0 0

0.0 2

0.1 4

0.2 1

0.1 1

0.1 8

0.4 SSE 0

0.0 0

0.0 2

0.1 3

0.2 2

0. 1 0

o.o 1

0.1 8

0.4 s

0 0.0 0

0.0 0

0.0 2

0.1 0

0.0 1

o. 1 0

0.0 3

0.2 SSll 0

0.0 0

0.0 4

0.2 1

0.1 0

0.0 0

0.0 1

0. 1 6

0.3 Sii 0

0.0 0

0.0 1

0.1 1

0.1 0

0.0 0

0.0 2

0.1 4

0.2 IJSll 0

0.0 0

0.0 1

0.1 7

0.4 0

0.0 1

0.1 0

0.0 9

0.5 II 0

0.0 0

0.0 1

0.1 3

0.2 1

0.1 0

0.0 0

0.0 5

0.3 lllJll 0

0.0 0

0.0 2

0.1 4

0.2 0.1 1

0.1 1

0.1 9

0.5 NII 0

0.0 0

0.0 5

0.3 6

0.3 3

0.2 0

0.0 14 0.7 NNll 0

0.0 0

0.0 1

o_,

10 0.5 9

0.5 1

0.1 1

0.1 22 1.2 l

0 0.0 0

0.0 18 0.9 49 2.6 28 1.5 10 0.5 7

0.4 112 5.9 HEAN IJIND SPEED:

12.4 HISSING:

0

ARTIFICIAL ISLAND 4/96 - 6/96 JOINT DISTRIBUTION Of IJIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS IJIND: 300 FT LAPSE RATE: -1.6 TO -1.5 DEG C/100H DELTA T: (300-33FT)

CLASS C IJIND SPEED GROUPS (MPH) 0.0-0.~

0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUH PERCENT DIRECTION SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT N

0 0.0 0

0.0 0

0.0 2

0. 1 2

0.1 2

0.1 0

0.0 6

0.3 NNE 0

0.0 0

o.o 0

0.0 2

0.1 2

0.1 0

0.0 0

0.0 4

0.2 NE 0

0.0 0

0.0 1

0.1.

1

o. 1 0

0.0 0

0.0 2

0.1 ENE 0

0.0 0

o.o 2

0.1 3

0.2 0

0.0 0

0.0 5

0.3 E

0 0.0 0

0.0 1

0.1 2

o. 1 1

0.1 0

0.0 0

0.0 4

0.2 ESE 0

0.0 0

0.0 1

0.1 1

0.1 0

0.0 1

0.1 0

0.0 3

0.2 SE 0

0.0 0

0.0 6

0.3 4

0.2 2

0.1 2

0. 1 2

0.1 16 0.8 SSE 0

0.0 0

0.0 3

0.2 7

0.4 0

0.0 3

0.2 0

0.0 13 0.7 s

0 0.0 0

0.0 1

0.1 3

0.2 1

0.1 0

0.0 0

0.0 5

0.3 SSIJ 0

0.0 0

0.0 1

0. 1 0

0.0 1

0. 1 1

0.1 3

0.2 SIJ 0

0.0 0

0.0 2

0.1 1

0.1 0

0.0 2

0.1 0

0.0 5

0.3 IJSIJ 0

0.0 0

0.0 3

0.2 3

0.2 0

0.0 0

0.0 6

0.3 IJ 0

0.0 1

0.1 0

0.0 4

0.2 1

0.1 1

0.1 0

0.0 7

0.4 IJNIJ 0

0.0 0

0.0 1

0.1 0

0.0 0

0.0 1

0.1 NIJ 0

0.0 0

0.0 2

0.1 1

o. 1 3

0.2 2

o. 1 3

0.2 11 0.6 NNIJ 0

0.0 0

0.0 7

0.4 2

o. 1 1

0. 1 1

0.1 11 0.6 0

0.0 1

0.1 22 1.2 42 2.2 15 0.8 15 0.8 7

0.4 102 5.3 HEAN IJIND SPEED:

12.6 HISSING:

0

I ARTIFICIAL ISLAND 4/96 - 6/96 JOINT DISTRIBUTION OF lllND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS lllND: 300 FT LAPSE RATE: -1.4 TO -0.5 DEG C/100H DELTA T: (300-33FT)

CLASS 0 lllND SPEED GROUPS CHPH) o.o-o.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6*18.5 18.6-24.5 GE 24.6 SUH PERCENT DIRECTION SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT N

0 0.0 0

0.0 3

0.2 16 0.8 5

0.3 3

0.2 0

0.0 27 1.l, NNE 0

0.0 1

0.1 5

0.3 19 1.0 17 0.9 2

0. 1 0

0.0 l,l, 2.3 NE 0

0.0 1

0.1 8

0.4 14 0.7 12 0.6 2

0.1 1

0.1 38 2.0 ENE 0

0.0 0

0.0 7

0.4 40

2. 1 8

0.4 1

0. 1 0

0.0 56 2.9 E

0 0.0 3

0.2 6

0.3 29

. 1.5 6

0.3 1

0.1 0

0.0 45 2.4 ESE 0

0.0 1

0.1 1

0.1 10 0.5 20 1.0 3

0.2 1

0.1 36 1.9 SE 0

0.0 0

0.0 6

0.3 20 1.0 28 1.5 29 1.5 12 0.6 95 5.0 SSE 0

0.0 1

o. 1 16 0.8 29 1.5 40

2. 1 22 1.2 2

0.1 110 5.8 s

0 0.0 0

0.0 9

0.5 17 0.9 7

0.4 5

0.3 0

0.0 38 2.0 SSll 0

0.0 0

0.0 5

0.3 12 0.6 13 0.7 17 0.9 11 0.6 58 3.0 Sii 0

0.0 0

0.0 2

0.1 5

0.3 16 0.8 3

0.2 0

0.0 26

1. 4 llSll 0

0.0 0

0.0 3

0.2 9

0.5 9

0.5 4

0.2 0

0.0 25 1.3 II 0

0.0 2

0.1 2

0.1 9

0.5 8

0.4 5

0.3 1

0.1 27 1.1, llNll 0

0.0 0

0.0 7

0.4 3

0.2 4

0.2 13 0.7 10 0.5 37 1.9 NII 0

0.0 0

0.0 2

0.1 4

0.2 12 0.6 4

0.2 15 0.8 37 1.9 NNll 0

0.0 0

0.0 1

0.1 5

0.3 7

0.4 8

0.4 1

0.1 22 1.2 0

0.0 9

0.5 83 4.3 241 12.6 212

11. 1 122 6.4 54 2.8 721 37.7 HEAN lllND SPEED:

14.1 HISSING:

1

ARTIFICIAL ISLAND 4/96 - 6/96 JOINT DISTRIBUTION Of lllND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS lllND: 3DD FT LAPSE RATE: -D.4 TO 1.5 DEG C/lOOH DELTA T: (300-33FT)

CLASS E lllND SPEED GROUPS (HPH) 0.0-0.5 D.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUH PERCENT DIRECTION SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT N

0 0.0 0

0.0 5

0.3 5

D.3 17 0.9 6

0.3 7

0.4 40

2. 1 NNE 0

D.0 1

0.1 2

D.1 3

0.2 26 1.4 6

0.3 1

0.1 39 2.0 NE 0

0.0 0

0.0 5

0.3 4

0.2 8

0.4 1

0.1 4

0.2 22 1.2 ENE 0

0.0 0

0.0 2

0. 1 8

0.4 2

o. 1 3

0.2 0

0.0 15 0.8 E

0 0.0 0

0.0 1

0.1 5

0.3 2

0.1 0

0.0 0

0.D 8

0.4 ESE 0

0.0 1

0.1 3

0.2 4

0.2 6

0.3 2

0.1 1

o. 1 17 0.9 SE 0

0.0 0

0.0 3

0.2 11 0.6 16 0.8 5

0.3 12 0.6 47 2.5 SSE 0

0.0 0

0.0 2

0. 1 9

0.5 37 1.9 17 0.9 5

0.3 70 3.7 s

0 0.0 0

0.D 1

0.1 9

0.5 8

0.4 8

0.4 11 0.6 37 1.9 SSll 0

0.0 1

0.1 2

D.1 3

0.2 10 0.5 14 0.7 16 0.8 46 2.4 Sii 0

0.0 2

0.1 4

0.2 4

0.2 29

1. 5 9

0.5 3

0.2 51 2.7 llSll 0

0.0 0

0.0 1

0.1 7

D.4 23 1.2 6

0.3 1

0.1 38 2.0 II 0

D.0 2

D.1 0

0.0 16 0.8 8

0.4 3

D.2 1

D.1 30 1.6 llNll 0

D.O 1

0.1 1

0.1 10 0.5 21

1. 1 13 D.7 1

0. 1 47 2.5 NII D

0.0 0

D.O 6

0.3 18 0.9 14 D.7 12 D.6 4

0.2 54 2.8 NNll 0

0.0 2

0.1 1

o. 1 6

0.3 10 0.5 9

D.5 4

0.2 32

1. 7 0

0.0 10 0.5 39 2.0 122 6.4 237 12.4 114 6.0 71 3.7 593 31.0 HEAN I/IND SPEED:

16.2 HISSING:

1

ARTIFICIAL ISLAND 4/96 - 6/96 JOINT DISTRIBUTION OF IJIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS IJIND: 300 FT LAPSE RATE:

1.6 TO 4.0 DEG C/100H DELTA T: (300-33FT)

CLASS F IJIND SPEED GROUPS (MPH) o.o-o.'s 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT DIRECTION SUH PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N

0 0.0 0

0.0 1

0.1 4

0.2 3

0.2 6

0.3 0

0.0 14 0.7 NNE 0

0.0 0

0.0 3

0.2 4

0.2 10 0.5 0

0.0 0

0.0 17 0.9 NE 0

0.0 0

o.o 3

0.2 2

0.1 2

0. 1 0

0.0 7

0.4 ENE 0

D.0 0

0.0 0

0.0 4

0.2 1

0.1 0

0.0 0

0.0 5

0.3 E

0 0.0 0

0.0 1

0.1 2

0. 1 0

0.0 0

0.0 3

0.2 ESE 0

0.0 0

0.0 3

0.2 0

0.0 0

0.0 3

D.2 SE 0

0.0 0

0.0 1

0.1 4

0.2 1

0.1 1

0.1 6

0.3 13 0.7 SSE 0

0.0 0

0.0 1

0. 1 0

0.0 11 0.6 1

0.1 3

0.2 16 0.8 s

0 0.0 0

0.0 2

0.1 7

0.4 6

0.3 3

0.2 4

0.2 22 1.2 SSIJ 0

0.0 0

0.0 1

0.1 3

0.2 6

0.3 15 0.8 2

0.1 27

1. 4 SIJ 0

0.0 0

0.0 1

0.1 13 0.7 11 0.6 0

0.0 25 1.3 llSll 0

0.0 0

0.0 4

0.2 12 0.6 2

0.1 0

0.0 18 0.9 IJ 0

0.0 1

0.1 0

0.0 1

0.1 2

0. 1 1

0.1 0

0.0 5

0.3 llNIJ 0

0.0 0

0.0 1

0.1 1

0.1 0

0.0 0

0.0 2

0. 1 Nii 0

0.0 0

0.0 2

0.1 2

0.1 8

0.4 0

0.0 0

0.0 12 0.6 NNIJ D

0.0 0

0.0 9

0.5 3

0.2 4

0.2 0

0.0 0

0.0 16 D.8 0

0.0 1

0.1 25 1.3 43 2.3 79

4. 1 42 2.2 15 0.8 205 10.7 MEAN IJIND SPEED:

15.2 MISSING:

0

ARTIFICIAL ISLAND 4/96 - 6/96 JOINT DISTRIBUTION OF lllND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS lllND: 300 FT LAPSE RATE:

GT 4.0 DEG C/100H DELTA T: (300-33FT)

CLASS G lllND SPEED GROUPS (MPH) o.o-o.5 0.6-3.5 3.6-7.5 7.6*12.5 12.6-18.5 18.6-24.5 GE 24.6 SUH PERCENT DIRECTION SUH PERCENT SUH PERCENT SUH PERCENT SUH PERCENT SUM PERCENT SUM PERCENT SUH PERCENT N

0 0.0 0

0.0 0

0.0 NNE 0

0.0 0

0.0 NE 0

0.0 0

0.0 ENE 0

0.0 0

0.0 E

0 0.0 0

0.0 0

0.0 ESE 0

0.0 0

0.0 SE 0

0.0 1

0.1 0

0.0 0

0.0 1

0.1 SSE 0

0.0 0

0.0 1

0.1 0

0.0 2

0.1 1

0.1 4

0.2 s

0 0.0 0

0.0 0

0.0 3

0.2 8

0.4 4

0.2 0

0.0 15 0.8 SSll 0

0.0 0

0.0 1

o. 1 0

0.0 5

0.3 0

0.0 6

0.3 Sii 0

o.o 0

0.0 2

0.1 1

0.1 2

0.1 0

0.0 0

0.0 5

0.3 llSll 0

0.0 0

o.o 2

0.1 3

0.2 0

0.0 5

0.3 II 0

0.0 0

0.0 llNll 0

0.0 0

0.0 NII 0

0.0 0

0.0 NNll 0

0.0 0

o.o 0

0.0 0

0.0 1

o. 1 2

0.1 6

0.3 12 0.6 14 0.7 1

0.1 36 1.9 MEAN lllNO SPEED:

16.0 MISSING:

0 111111 - - - - - - - -

ARTIFICIAL ISLAND 4/96 - 6/96 JOINT DISTRIBUTION Of IJIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS IJIND: 300 FT DELTA T: (300-33FT)

ALL STABILITY CLASSES IJIND SPEED GROUPS (MPH) o.o-o.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUH PERCENT DIRECTION SUH PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N

0 0.0 D

0.0 12 0.6 36 1.9 32

1. 7 21

1. 1 8

0.4 109 5.7 NNE 0

0.0 2

0.1 11 0.6 31 1.6 55 2.9 8

0.4 1

0. 1 108 5.7 NE 0

0.0 1

0.1 15 0.8 25 1.3 24 1.3 5

0.3 5

0.3 75 3.9 ENE 0

0.0 0

0.0 11 0.6 55 2.9 11 0.6 4

0.2 0

0.0 81 4.2 E

0 0.0 3

0.2 10 0.5 38 2.0 9

0.5 1

o. 1 0

0.0 61 3.2 ESE 0

o_o 2

0. 1 9

0.5 15 0.8 26 1.4 6

0.3 2

0.1 60

3. 1 SE 0

0.0 1

0.1 17 0.9 43 2.3 52 2.7 41 2.1 34 1.8 188 9.8 SSE 0

0.0 1

0.1 25 1.3 51 2.7

. 94 4.9 47 2.5 13 0.7 231

12. 1 s

0 0.0 0

0.0 13 0.7 43 2.3 30 1.6 21

1. 1 15 0.8 122 6.4 SSIJ 0

0.0 1

0.1 14 0.7 21

1. 1 29 1.5 52 2.7 38 2.0 155 8.1 SIJ 0

0.0 2

0.1 11 0.6 13 0.7, 62 3.2 25 1.3 8

0.4 121 6.3 IJSIJ 0

0.0 0

0.0 11 0.6 37 1.9 47 2.5 19 1.0 1

0.1 115 6.0 IJ 0

0.0 6

0.3 3

0.2 35 1.8 22 1.2 13 0.7 2

0.1 81 4.2 IJNIJ 0

o.o 1

0. 1 14 0.7 22 1.2 29 1.5 38 2.0 14 0.7 118 6.2 NIJ 0

o.o 0

0.0 12 0.6 35 1.8 55 2.9 31 1.6 28 1.5 161 8.4 NNIJ 0

0.0 2

0. 1 12 0.6 33

1. 7 40

2. 1 28 1.5 10 0.5 125 6.5 0

0.0 22 1.2 200 10.5 533 27.9 617 32.3 360 18.8 179 9.4 1911 100.0 HISSING HOURS:

273 MEAN IJIND SPEED:

15.0

ARTIFICIAL ISLAND 4/96 - 6/96 JOINT DISTRIBUTION OF IJIND DIRECTION AND SPEED BY ATMOSPHERIC STABILITY CLASS WIND: 3DO FT DELTA T: (300-33FT)

DIRECTION VS SPEED ONLY IJIND SPEED GROUPS CMPH) 0.0-0.'5 0.6-3.5.

3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT DIRECTION SUM PERCENT SUM PERCENT -

SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N

0 0.0 0

0.0 13 0.6 36 1.8 32 1.6 21 1.0 8

0.4 110 5.4 NNE 0

0.0 2

o. 1 13 0.6 31 1.5 55 2.7 8

0.4 1

0.0 110 5.4 NE 0

0.0 1

0.0 15 0.7 26 1.3 24 1.2 5

0.2 5

0.2 76 3.7 ENE 0

0.0 0

0.0 12 0.6 56 2.7 12 0.6 4

0.2 0

0.0 84

4. 1 E

0 0.0 3

0.1 10 0.5 42 2.0 10 0.5 1

0.0 0

0.0 66 3.2 ESE 0

0.0 2

o. 1 10 0.5 15 0.7 27 1.3 6

0.3 2

0.1 62 3.0 SE 0

0.0 1

0.0 17 0.8 46 2.2 55 2.7 41 2.0 34

1. 7 194 9.5 SSE 0

0.0 1

0.0 26 1.3 56 2.7 102 5.0 52 2.5 17 0.8 254 12.4 s

0 0.0 0

0.0 14 0.7 47 2.3 30 1.5 21 1.0 15 0.7 127 6.2 SSll 0

0.0 1

0.0 15 0.7 21 1.0 31 1.5 53 2.6 38 1.9 159 7.8 SIJ 0

0.0 2

0.1 13 0.6 16 0.8 66 3.2 27 1.3 10 0.5 134 6.5 IJSIJ 0

0.0 0

0.0 12 0.6 46 2.2 56 2.7 23

1. 1 1

0.0 138 6.7 II 0

0.0 6

0.3 5

0.2 45 2.2 35

1. 7 14 0.7 2

0. 1 107 5.2 IJNIJ 0

0.0 1

0.0 15 0.7 24 1.2 35

1. 7 41 2.0 14 0.7 130 6.3 NII 0

0.0 0

0.0 13 0.6 38 1.9 59 2.9 32 1.6 28 1.4 170 8.3 NNIJ 0

0.0 2

0.1 13 0.6 35

1. 7 40 2.0 28 1.4 10 0.5 128 6.2 0

0.0 22

1. 1 216 10.5 580 28.3 669 32.7 377 18.4 185 9.0 2049 100.0 MISSING HOURS:

135 MEAN Ill ND SPEED:

14.9

8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS PART PART Our last report (RERR-38) did not include the quarterly Sr-89, Sr-90 and Fe-55 composite data for the second quarter of 1995.

Amended pages to RERR-38 are included at the end of this report.

B.

GASEOUS EFFLUENTS See Swnmary Tables lA-1 thru 1c for Salem Unit 1 Operations.

See Swnmary Tables lA-2 thru lC for Salem Unit 2 Operations.

c.

LIQUID EFFLUENTS See Swnmary Tables 2A-l thru 2B for Salem Unit 1 Operations.

See Swnmary Tables 2A-2 thru 2B for Salem Unit 2 Operations.

PART D.

SOLID WASTE See Swnmary in Table 3.

PART E.

RADIOLOGICAL IMPACT ON MAN The calculated individual doses in this section are based on individuals continuously located at the site boundary. This 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 represe~t calculations for the six month reporting interval.

Individual doses from batch and continuous releases were calculated using the annual average historic meteorological dispersion coefficients as described in the Offsite Dose Calculation Manual.

Population doses were calculated using the meteorological dispersion coefficients for the six month reporting interval.

Liquid Pathways Doses to "maximum hypothetical individuals" in the population from liquid releases are primarily from the seafood ingestion pathway. Calculated doses to individuals are as shown below:

Total body dose to the individual: 2.42E-Ol mrem Highest organ dose (GI-LLI): 3.95E-01 mrem 8

I

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Dose to the 4.5 million individuals living within the 50 mile radius of the plant site:

Total population dose:

8.37E-02 person-rem Average population dose:

l.86E-05 mrem/person Air Pathways The calculated doses to "maximum hypothetical individuals" via the air pathway are shown below:

Total body dose: 2.19E-06 mrem Skin dose:

4.83E-05 mrem Highest organ dose due to radioiodines and particulates with half lives greater than 8 days:

5.36E-03 mrem to the Lung Dose to the 4.5 million individuals living within the 50 mile radius of the plant site:

Total population dose:

Average population dose:

Direct Radiation l.73E-01 person-rem 3.84E-05 mrem/person Direct radiation may be estimated by thermoluminescent dosimetric (TLD) measurements.

One method for comparing TLD measurements is by comparison with preoperational data.

It should be noted that the TLDs measure direct radiation from both the Salem and Hope Creek Generating Stations at Artificial Island, as well as natural background radiation.

TLD data for the six month reporting period is given below:

TLD 2S-2 5S-l Location 0.3 mile 0.9 mile Measurement 4.4 mrem/month 3.7 mrem/month These values are interpreted to represent natural background. They are within the statistical variation associated with the pre-operational program results, which are: 3.7 mrem/month for location 2S-2, and 4.2 mrem/month for location SS-1.

9

SALEM GENERATING STATION TABLE lA-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -

DECEMBER 1995 UNIT 2 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Units A. Fission and Activation Gases

1. Total release Ci

2. Average release rate for period uCi/sec

3. Percent of technical specification limit (T.S. 3.11.2.2(a))

B. Iodines

1. Total Iodine-131 Ci

2. Average release rate for period uCi/sec

3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a))

c. Particulates

1. Particulates with 0

half-lives >8 days Ci

2. Average release rate for period uCi/sec

3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a))

4. Gross alpha Ci C. Tritium

1. Total Release Ci

2. Average release rate for period uCi/sec

3. Percent of technical specification limit (2)

(T.S. 3.ll.2.3(a))

3rd Quarter 3.40E-01 4.32E-02 4.22E-04 O.OOE+OO O.OOE+OO 6.97E-04 6.86E-06 8.72E-07 6.97E-04 O.OOE+OO

_.52E+Ol 3.20E+OO 6.94E-04 4th Quarter 5.36E-02 6.82E-03 7.29E-05 O.OOE+OO O.OOE+OO 2.21E-04 O.OOE+OO O.OOE+OO 2.21E-04 O.OOE+OO 8.13E+OO

1. 03E+OO 2.21E-04 Est.

Total Error %

25 25 25 25 (1) For batch releases the estimated overall error is within 10%

(2) Iodine, tritium and particulates are treated as a group 15 I

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1.

SALEM GENERATING STATION TABLE lB-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -

DECEMBER 1995 GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 2 CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission Gases Krypton-BS Ci O.OOE+OO O.OOE+OO 2.75E-01 5.36E-02 Xenon-13lrn Ci O.OOE+OO O.OOE+OO l.lSE-02 O.OOE+OO Xenon-133 Ci O.OOE+OO O.OOE+OO 5.36E-02 O.OOE+OO TOTALS Ci O.OOE+OO O.OOE+OO 3.40E-01 5.36E-02 2. Iodines Iodine-131 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO TOTALS Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

3. Particulates (half-lives >8 days)

Cobalt-60 Ci 6.86E-06 O.OOE+OO O.OOE+OO O.OOE+OO TOTALS Ci 6.86E-06 O.OOE+OO O.OOE+OO O.OOE+OO 17

SALEM GENERATING STATION 1*

TABLE 2A-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT I

JULY -

DECEMBER 1995 UNIT 1 I

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES I

Est.

3rd 4th Total Units Quarter Quarter Error %

A. Fission and activation I

products

1. Total release (not including tritium, I

gases, alpha)

Ci 4.64E-Ol l.48E-01 25

2. Average diluted concentration 'during I

period of release uCi/mL 2.05E-07 3.25E-07

3. Percent of technical specification limit

1 (T.S. 3.11.1.2. (a))

7.36E+OO 2.75E+OO B. Tritium

1. Total release Ci 6.78E+Ol l.20E+Ol 25 I

2. Average diluted concentration during period uCi/mL 2.99E-05 2.63E-05

3. Percent of technical I

specification limit (T.S. 3.11.1.1) 9.98E-01 8.77E-Ol

c. Dissolved and entrained I

noble gases

1. Total release Ci O.OOE+OO O.OOE+OO 25

2. Average diluted I

concentration during period uCi/mL O.OOE+OO O.OOE+OO

3. Percent of technical I

specification limit (T.S. 3.11.1.1)

O.OOE+OO O.OOE+OO D. Gross alpha activity I

1. Total release Ci O.OOE+OO O.OOE+OO 25 E. Volume of waste release I

(prior to dilution -

Batch Release) liters l.27E+06 2.62E+05 25 F. Volume of dilution water I

used during entire period liters 5.19E+ll

4. BOE+ll 25 19 I

I I

I SALEM GENERATING STATION TABLE 2A-2 I

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -

DECEMBER 1995 UNIT 2 I

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES I

Est.

3rd 4th Total Units Quarter Quarter Error %

I A. Fission and activation products

l. Total release (not I

including tritium, gases, alpha)

Ci 2.0SE-01 l.89E-01 25 2. Average diluted I

concentration during period uCi/mL l.48E-07 l.14E-07

. 3. Percent of technical specification limit 1*

(T. S. 3.11.l.2. (a))

3.40E+OO 2.59E+OO B. Tritium

l. Total release Ci

l. 86E+Ol

l. 31E+Ol 25 I

2. Average diluted concentration during period uCi/mL l.35E-05 7.86E-06 I

3. Percent of technical specification limit (T.S. 3.11.1.1) 4.49E-01 2.62E-01 I

c. Dissolved and entrained noble gases

l. Total release Ci O.OOE+OO O.OOE+OO 25 I

2. Average diluted concentration during period uCi/mL O.OOE+OO O.OOE+OO

3. Percent of technical I

specification limit (T.S. 3.11.1.1)

O.OOE+OO O.OOE+OO I

D. Gross alpha activity

l. Total release Ci O.OOE+OO O.OOE+OO 25 E. Volume of waste release I

(prior to dilution -

Batch Release) liters 8.76E+OS 3.07E+05 25 I

F. Volume of dilution water used during entire period liters 4.86E+ll 9.34E+l0 25 20 I

I I

SALEM GENERATING STATION TABLE 2B-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -

DECEMBER 1995 LIQUID EFFLUENTS UNIT 1 CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter Chromium-51 Ci O.OOE+OO O.OOE+OO

. 9.06E-04 O.OOE+OO Manganese-54 Ci O.OOE+OO O.OOE+OO l.3SE-03

1. 09E-03 Iron-SS Ci O.OOE+OO O.OOE+OO l.13E-02 4.63E-04 Iron-S9 Ci O.OOE+OO O.OOE+OO 4.S9E-05 O.OOE+OO Cobalt-S7 Ci O.OOE+OO O.OOE+OO 7.34E-04 3.97E-04 Cobalt-SB Ci O.OOE+OO O.OOE+OO l.73E-01 4.79E-02 Cobalt-60 Ci O.OOE+OO O.OOE+OO l.97E-02

1. OlE-02 Zinc-65 Ci O.OOE+OO O.OOE+OO 4.14E-0S O.OOE+OO Strontium-90 Ci O.OOE+OO O.OOE+OO O.OOE+OO 7.06E-OS Niobium-9S Ci O.OOE+OO O.OOE+OO 6.49E-04 O.OOE+OO Zirconium-9S Ci O.OOE+OO O.OOE+OO 2.87E-04 O.OOE+OO Silver-llOm Ci O.OOE+OO O.OOE+OO 2.44E-03 O.OOE+OO Antimony-124 Ci O.OOE+OO O.OOE+OO l.13E-02 4.63E-04 Antimony-12S Ci O.OOE+OO O.OOE+OO 3.SBE-02 4.lOE-03.

Iodine-131 Ci O.OOE+OO O.OOE+OO 4.23E-04 O.OOE+OO Cesium-134 Ci O.OOE+OO O.OOE+OO 8.33E-02 3.06E-02 Cesium-137 Ci O.OOE+OO O.OOE+OO

1. 22E-01 4.7SE-02 TOTALS Ci O.OOE+OO O.OOE+OO 4.64E-01

1. 48E-01

.Tritium Ci O.OOE+OO O.OOE+OO 6.78E+Ol 1.20E+Ol TOTALS Ci O.OOE+OO O.OOE+OO 6.78E+Ol 1.20E+Ol 21

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I SALEM GENERATING STATION TABLE 2B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY -

DECEMBER 1995 LIQUID EFFLUENTS UNIT 2 CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter Manganese-54 Ci O.OOE+OO O.OOE+OO l.27E-04

1. OlE-03 Iron-55 Ci O.OOE+OO O.OOE+OO 2.93E-03 2.89E-03 Cobalt-57 Ci O.OOE+OO O.OOE+OO 7.41E-05 6.33E-04 Cobalt-58 Ci O.OOE+OO O.OOE+OO 3.22E-02 8.13E-02 Cobalt-60 Ci O.OOE+OO O.OOE+OO 3.52E-03 l.50E-02 Strontium-90 Ci O.OOE+OO O.OOE+OO O.OOE+OO l.54E-05 Niobium-95 Ci O.OOE+OO O.OOE+OO 2.23E-04 O.OOE+OO Zirconium-95 Ci O.OOE+OO O.OOE+OO O.OOE+OO 5.47E-05 Technetium-99m Ci O.OOE+OO O.OOE+OO l.26E-05 O.OOE+OO Silver-llOm Ci O.OOE+OO O.OOE+OO 5.29E-04 2.86E-05 Antimony-124 Ci O.OOE+OO O.OOE+OO 7.12E-03 4.69E-04 Antimony-125 Ci

O.OOE+OO O.OOE+OO 2.0BE-02 4.49E-03 Iodine-131 Ci O.OOE+OO O.OOE+OO 4.34E-04 O.OOE+OO Cesium-134 Ci O.OOE+OO O.OOE+OO 5.60E-02 3.17E-02 Cesium-137 Ci O.OOE+OO O.OOE+OO 8.13E-02 5.15E-02 TOTALS Ci O.OOE+OO O.OOE+OO 2.05E-01

1. 89E-01 Tritium Ci O.OOE+OO O.OOE+OO l.86E+Ol

1. 31E+Ol TOTALS O.OOE+OO O.OOE+OO

1. 8 6E+Ol l.31E+Ol 22

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--=.;=..:....:"==<.~""-------------------------------------------------~

Title:

Salem Offsite Dose Calculation Manual Applicability:

Salem 1 Salem 3 (Gas Turbine)

Salem 2 Hope Creek

_x_ Common to Salem 1 & 2 Common to Hope Creek & Salem COMPLETION AND APPROVAL Preparer:

~

L ~

Peer Reviewer:

0a...... *._Q ~

Date:

1 z.- I l -

, s-Approval:

SORC Review :

Date: 4~ Z:r

~~~~..r,l-...-- Mtg. No. '1/-t't/ Date: /-3-f/

G.M. Approval:

1c~i...:;__1--J.--.:...=.:=-"'~-=::!....---- Date:

/ ~ b 1.0 10CFR50.59 REVIEW - 10CFR50.59 applies because:

1.1 The proposal changes the facility as described in the SAR.

Yes __

No_x_

1.2 The proposal changes procedures as described in the SAR.

Yes_x_

No __

1.3 The proposal involves a test or experiment not described in the SAR.

Yes __

No_x_

Nuclear Common Page 46 of 46 Rev. 3

FORM NC.NA-AP.ZZ-0059-3 10CFRS0.59 SAFETY EVALUATION Page 2 of 20 Revision 0 I.D. Numbers/References/Revision: Revision 10

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Title:

Salem Offsite Dose Calculation Manual

~--="-===""-'-....c=-..==-==-=-=-="-"=-=-==--==-==-=-===-:::=.::::.=......:.o:=:.=..==-=.----~~--------~--~-

2.0 TECHNICAL SPECIFICATION REVISION DETERMINATION - Does the proposal require a Technical Specification change?

Yes __ _

No x

If a change is required, STOP.

Contact Nuclear Licensing for assistance in preparation of a License Change Request.

Identify the pertinent Technical Specification sections that were reviewed to make the determination:

3.3.3.8, 3.3.3.9, 3.11.1.1, 3.11.1.2, 3.11.1.4, 3.11.2.1, 3.11.2.2, 3.11.2.3, 3.11.2.4, 3.11.4, 3.12.1, 3.12.2, 6.9.1.8, 6.14, 6.15

3.0 DESCRIPTION

3.1 Describe the modification or activity being evaluated and its expected effects.

The following changes are being proposed to the Salem Offsite Dose calculation Manual (ODCM). The changes will not reduce the accuracy or reliability of dose calculations or setpoint determinations.

Change #1: ODCM page(s) - All Change: Document was reformatted from double spacing to single spacing for easier reading.

Effects: No effects on plant systems, procedures or equipment are expected from this change.

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Title:

Salem Offsite Dose Calculation Manual

~~=-=..=.=.:..:"--=-='-=-=-==-=-=--=-'=='-=--=-===-===:..=.==:..==-~=..:;:.===:__~~~~~~~~~~~~

3.1 Continued

Change #2: ODCM page(s) - 4,5 Change: 1.The default effective Maximum Permissible Concentration (MPCe) value for Unit 1 and 2 was updated from a value derived from 1990 - 1992 liquid effluent releases. to a value based on 1992 - 1994 release data.

2.Modified the setpoint determination formula to include a safety factor which will account for non-gamma emitting radionuclides(i.e.

H-3,Fe, Sr). The safety factor can be used for default setpoint calculations.

Effects: 1.Public Service Blueprint Document PSBP 315733 (Unit 1) and,*

PSBP 315733 (Unit 2) should be updated to reflect the current release data. A new default liquid effluent radiation monitor setpoint for Unit 1 and Unit 2 should be determined using this formula and default parameters. (E&PB Electrical) 2.No changes to plant systems, procedures, or equipment will result due to the modification of the setpoint formula. A 25% safety factor is currently used in effluent software for liquid releases.

Note: Current setpoint is more conservative and does not need to be changed prior to approval of this revision.

Change #3: ODCM page(s): 25 Change: The semi-annual effluent release report submittal requirements were clarified in sections 3.1 and 3.2. Previously the sections only listed January 1st as the submittal date. July 1st was added as a submittal date.

Effects: No effects on plant systems, procedures or equipment are expected from this change.

Change #4: ODCM page(s): Table 1-1 and 1-2 Change: 1. Updated table to new default MPCe. A value of 6.05E-6 uci/ml was calculated for Unit 1 and a value of 4.81E-6 uci/ml was calculated for Unit 2.

2. Removed radiation monitor sensitivities and setpoints for liquid effluent from manual. Radiation monitor setpoints and sensitivities are currently controlled under Public Service Blueprint Documents 315733 (Unit 1) and 315734 (Unit 2).

Effects:

No effects on plant systems, procedures or equipment are expected from this change.

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FORM NC.NA-AP.ZZ-0059-3 10CFRS0.59 SAFETY EVALUATION Page 4* of 20 Revision 0 I.D. Numbers/References/Revision: Revision 10

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3.1 Continued

Change #5: ODCM page(s): 33,35 Change: 1. Added As-76 site related ingestion dose commitment factor and bioaccumulation factor.

Where:

The site related ingescion dose commitment factor for Arsenic-76 has been calculated by the following method.

1. Formula used:

ODCM equation 1.6

2.

References:

Federal Guidance Report #ll, Limiting Values of Radionuclide Intake And Air Concentration And Dose Conversion Factors For Inhalation, Submersion, And Ingestion.

United States Atomic Energy Commission Report UCRL-50564, Concentration Factors of Chemical Elements in Edible Aquatic Organisms Calculation:

A10 = 1.14E+5 [ { UI

Bid + { UF

BF1) ] DF1 1.14E+5 =

UI BI1 composite dose parameter for the total body or critical orga0 of an adult for radionuclide i, for the fish and invertebrat~

ingestion pathways (mrem/hr per uci/ml).

\\

conversion factor (pci/uci

ml/kg per hr/yr) adult invertebrate consumption ( 5 kg/yr) bioaccumulation factor for radionuclide i in invertebrates (pci/kg per pci/l) adult fish consumption (21 kg/yr) bioaccumulation factor for radionuclide i in fish (pci/kg per pci/l) dose conversion factor for nuclide i in adults in preselected organ o (mrem/pci).

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Revision 10

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Title:

Salem Offsite Dose Calculation Manual

~~~~~--""-=--""-=-'~~-=--'=-==--=======.:::=-=====-....:....:.==:=.:::.=. ______________________

~

3.1 Continued

A. Bioaccumulation factors from Reference 2 above:

Nuclide Invertebrates Vertebrates As-76 3.33E+2 3.33E+2 B. Dose Conversion factors from Reference 1 above:

Organ Dose Conversion Factor (mrem/pci)

Bone 4.44E-7 Liver l.lSE-6 Total Body S.21E-6 Thyroid 3".46E-7 Kidney

1. 41E-6 Lung 3.63E-7 GI-LLI 4.36E-5 Nuclear Common Page 46 of 46 Rev. 3

FORM NC.NA-AP.ZZ-0059-4 10CFR50.59 SAFETY EVALUATION Page 6 of 20 Revision 0 I.D.

Numbers/References/Revision:~~R~e~v-=-=i=s~i~o=n=---1=-::::.o _________________________________ _

Title:

___ -=S=a=l~e=m=-=O~f~f~s~i~t=e=--D==o=s~e'---'C=a=l~c=u==l=a~t=i~o=n.:.....:M~a=n=-=u=a=l::...... ___________________________ ~

3.1 Continued

c.

Site Related Dose Commitment Factors

l. *Bone

= l.. 14E+5 [(5

333) + (21

333)] 4.44E-7 Bone

= 4.38E+2 mrem/hr per uci/ml

2. Liver l.14E+5 [(5

333) + (21

333)] l.lSE-6 Liver l.16E+3 mrem/hr per uci/ml

3. T. Body l.14E+5 [(5

333) + (21

333)] 5.21E-6 T. Body S.14E+3 mrem/hr per uci/ml

4. Thyroid l.14E+5 [(5

333) + (21

333)] 3.46E-7 Thyroid 3.42E+2 mrem/hr per uci/ml

5. Kidney l.14E+5 [ (5

333) + (21

333)] l.41E-6 Kidney

1. 39E+3 mrem/hr per uci/ml

6. Lung l.14E+5 [(5

333) + (21

333)] 3.63E-7 Lung 3.58E+2 mrem/hr per uci/ml

7. GI-LLI l.14E+5 [(5

333) + (21

333)] 4.36E-5 GI-LLI 4.30E+4 mrem/hr per uci/ml Effects:

The above listed values for As-76 will have to be added to RETS CODE.

(.Chemistry)

Change #6: ODCM page(s): Table 2-2 and 2-3 Change:

Removed radiation monitor sensitivities and setpoints for gaseous effluents from Units 1 and 2 from the ODCM. Radiation monitor setpoints and sensitivities are currently controlled under Public Service Blueprint Documents 315733 (Unit l) and 315734 (Unit 2).

Effects:

No effects on plant systems, procedures or equipment are expected from this change.

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Title:

Salem Offsite Dose Calculation Manual

~-=-'~~~-=-=-==='-=-=--=-'~-=--=======...===~=-..;...:;==o.===-='-------------~

3.1 Continued

Change #7: ODCM page(s): 47 (table 2-5)

Change: Corrected Ce-141 organ (Liver) dose factor for the grass-cow-milk pathway in the Teenager age group. Value in previous revision of the ODCM was 1.35E+4 (m2

mrem/yr per uci/sec).

Correct value should be 5.92E+3 (m2

mrem/yr per uci/sec).

Where:

r The dose conversion factor (DCF) was manually calculated using the formulas and parameters contained or recommended by Regulatory Guide 1.109 and Nureg-0133. The following result was obtained:

Dose factor formula for grass-cow-milk pathway:

Or (U.P)

K' --------

Fm A.1 + >..

grass-cow-milk pathway dose factor for radionuclide i in organ o,in m2-mrem/yr per uci/sec.

a constant of unit conversion, 1E+6 pci/uci.

the agricultural productivity by unit area of pasture feed grass, in kg/m2

A value of 0.7 is recommended in Table E-15 of Reg.

Guide 1.109.

the agricultural productivity by unit area of stored feed, in kg/m2

A value of 2.0 is recommended in Table E-15 of Reg. Guide 1.109.

the stable element transfer coefficient, in days/liter, values are given in Table E-1 of Reg. Guide 1.109.

the cow's consumption rate, in kg/day (net weight). Values are given in Table E-3 of Reg Guide 1.109 fraction of deposited activity retained on cow's feed grass.

Values of 1.0 for radioiodine and 0.2 for particulates are recommended in Table E-15 of Reg. Guide 1.109.

the receptors milk consumption rate for age {Adult) in liters/yr. Values are given in Table E-5 of Reg Guide 1.109*.

the maximum organ ingestion dose factor for radionuclide i for the receptor in age group {a), in mrem/pci. Values are given in table E-11 of Reg. Guide 1.109.

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3.1 Continuation the decay constant for radionuclide i, in sec-1 the decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73E-7 sec* 1 (corresponding to a 14 day half-life).

= the transport time form pasture to cow, to milk, to receptor, in sec. A value of l.73E5 (2 days) is recommended in Table E-15 of Reg. Guide 1.109.

the transport time from pasture, to harvest, to cow, to milk, to receptor, in sec. A value of 7.7BE+6 (90 days) is recommended in Table E-15 of Reg. Guide 1.109.

= fraction of the year that the cow is on pasture (dimensionless). A value of unity is assumed in lieu of site specific information.

fraction of the cow feed that is pasture grass while the cow is on pasture (dimensionless). A value of unity is assumed in lieu of site specific information.

This fqrmula can be simplified to:

e-(1.731!5) A 7.14E+7 F111 Uap (r) (DFL1) *

5. 73E-7 + >..1 Reg Guide 1.109 values for Teenager-Liver in the grass-cow-milk pathway for Ce-141 are:

Therefore:

1.0E-4 400 0.2 B.BBE-9 2.47E-7 Rce-m (7.14E+7) (l.OE-4) (400) (0.2) (B.BBE-9) (1.16BE+6)

Ree-in

5. 93E+3 m2-mrem I yr per uci/sec.

Effects: The consequence of the incorrect dose factor value is negligible. The ODCM dose factor value for Ce-141 would result in an over estimation of the dose received by a member of the general public. Ce-141 has not been observed in previous gaseous effluent releases. The correct value will be entered into RETS CODE-

{Chemistry)

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Revision 10

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Title=~--=S~a~l=-=e=m:-.;O~f~f==s=i~t~e=-=D~o~s~e=-~C~a~l~c~u~l==a~t~i~o~n...._M~a~n~u~a~l=---~~~~~~~~~~~

3.1 Continuation

Change #8: ODCM page(s): Appendix A Change: l. Calculated default MPCe values using current liquid release data.

A. Effective Maximum Permissible Concentration (MPC.)

In accordance with the requirements of Technical Specification (3.3.3.8) the radioactive liquid effluent monitors shall be operable with alarm setpoints established to ensure that the concentration of radioactive material at the discharge point does not exceed the MPC value of 10 CFR 20, Appendix B, 'l*able II, Column 2.

The determination of allowable radionuclide concentration and corresponding alarm setpoint is a function of the individual radionuclide distribution and corresponding MPC values.

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 of the liquid effluents from Salem and the effective MPC value for this distribution.

The effective MPC value for a radionuclide distribution is calculated by the equation:

MPC. = -----------------------------

(A.l)

I: -----------

where:

MPCe an effective MPC value for a mixture of radionuclide (uCi/ml)

C1 concentration of radionuclide i in the mixture MPC1 the 10 CFR 20, Appendix B, Table II, Column 2 MPC value for radionuclide i (uCi/ml)

The equation for determining the liquid effluent setpoints ( Section 1.2.1, equation 1.2 ) is based on a multiplication of the effective MPC times the monitor sensitivity. Considering the average effective MPC value for the years 1992 through 1994, it is reasonable to select an MPCe value of 6.0SE-06 uci/ml for Unit land 4.BlE-06 uci/ml for Unit 2 as typical of liquid radwaste discharges.

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Title:

Salem Off site Dose Calculation Manual

3.1 Continued

B. Safety Factor The type of radiation detector used to monitor radioactive releases is not capable of detecting non-gamma emitting radionuclides such as H-3, Fe-55, and Sr-89,90, as required by Technical Specification 3.11.1.1. A conservative default safety factor can be determined to account for non-gamma emitting radionuclides. Non-gamma emitting radionulcides are analyzed at Salem station on a monthly basis from a composite sample of liquid releases.

Nuclide MPC (uci/ml)

Activity (uci/ml)

Activity I MPC H-3 3E-3 5.2E-l 173.3 Fe-55 8E-4 2.5E-3 3.1 Sr-89 3E-6 2.0E-5 6.7 Sr-90 3E-7 7.2E-7 2.4 Total 185.5 The values in the table above represent the maximum reactor coolant values for non-gamma emitting radionulcides in 1994 for Unit's l and 2. Reactor Coolant values were chqsen to represent the maximum concentration* of non-gamma emitting radionulcides that could be released from Salem Station. The activity values in the table will be diluted by a minimum factor of 800 prior to release. The minimum dilution factor is obtained by using the minimum dilution water flowrate of 100,000 gpm and the maximum release rate of 120 gpm.

A conservative safety factor for non-gamma emitting radionulcides can be obtained by using the highest Activity/MPC fraction and the minimum dilution factor as follows:

Safety Factor =

185.5 I 800 = 0.23 (Rounded up to 0.25)

c. Default setpoint determination:

Using the information and parameters described above a default setpoint can be calculated for Unit 1 and 2 liquid radwaste disposal process radiation monitors (RlBf.

Using these values to calculate the default R18 alarm setpoint value 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

2) Will provide for a liquid radwaste discharge rate (as evaluated for each batch release) that is compatible with plant operations (refer to Tables 1-1 and 1-2).

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Title:

Salem Offsite Dose Calculation Manual

3.1 Continued

Nuclide MPC 0

(uCi/ml)

Be-7 2E-03 Na-24 3E-05 Cr-51 2E-03 Mn-54 lE-04 Fe-59 5E-05 Co-57 4E-04 Co-58 9E-05 Co-60 3E-05 Zr-95 6E-05 Nb-95 lE-04 Nb-97 9E-04 Tc-99m 3E-03 Sr-92 6E-05 Mo-99 4E-05 Ag-llOm 3E-05 Sn-113 SE-05 Sb-122 3E-05 Sb-124 2E-05 Sb-125 lE-04 Sb-126 3E-06 I-131 3E-07 I-133 lE-06 I-134 2E-05 ce-141 9E-05 Ce-143 4E-05 Cs-134 9E-06 Cs-136 6E-05 cs-137 2E-05 Ba-140 2E-05 La-140 2E-05 Ru-105 lE-04 Ru-106 lE-05 zn-65 lE-04 Total Ci Gamma MP Ce (uCi/ml)

Nuclear Common Calculation of Effective MPC Salem Unit 1 Activity Released (Ci) 1992 1993 1994 CURIES CURIES CURIES 8.74E-05

8. SSE-*04 N/D 3.99E-04

6. 68E-04.

1.62E-04 4.30E-03 S.38E-03 2.02E-03 7.24E-02 3.52E-02 1.37E-02

1. 20E-04 4.76E-04 4.84E-03 1.26E-02

1. 03E-02 3.lOE-03 2.33E+OO 1.71E+OO 6.47E-01 2.52E-01 3.04E-01

1. lOE-01 2.90E-03 3.29E-03 7.13E-04 6.37E-03 5.78E-03

1. 28E-03 3.99E-04

1. 27E-03

1. 07E-03 8.23E-05 2.66E-04 N/D N/D N/D 7.32E-06 N/D

1. 76E-04

1. 76E-04 8.38E-03 1.19E-02 1.lOE-02 3.91E-04 7.SSE-05 4.91E-05

.8.54E-05 1.21E-03 5.35E-04 1.37E-02 2.0SE-02

1. 75E-02 7.27E-02 9.04E-02 8.23E-02 N/D N/D 6.lSE-05

3.06E-02 1.27E-01 l.82E-02

1. 75E-03 2.16E-03 l.SSE-04 N/D N/D 3.63E-04 3.69E-05 N/D 4.24E-05 N/D 5.42E-05 N/D

1. 64E-01 3.54E-01 6.46E-01

1. 20E-03 3.61E-03

1. 59E-03

1. 86E-Ol 4.53E-01 8.54E-01 N/D N/D 8.62E-05 6.26E-05 2.12E-04 1.86E-04 4.58E-04 2.21E-04

1. 35E-04 N/D N/D l.03E-03 8.75E-04

6. 72E-04 N/D 3.16E+OO 3.14E+OO 2.42E+OO 1.SSE-05 6.05E-06 l.28E-05 Page 46 of 46 Rev. 3

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__ -""S=a=l==e=rn:......::O~f~f~s"'-=i~t~e:..-:D~o:.=s~e~C~a~l~c~u==l~a~t~i~o~n:.:.....~M=a~n~u~a==l--------------------~

3.1 Continued

Nuclide MPC" (uCi/ml)

Be-7 2E-03 Na-24 3E-05 Cr-51 2E-03 Mn-54 lE-04 Fe-59 5E-05 Co-57 4E-04 Co-58 9E-05 Co-60 3E-05 Zr-95 6E-05 Nb-95 lE-04 Nb-97 9E-04 Tc-99m 3E-03 Mo-99 4E-05 Ag-llOm 3E-05 Sn-113 BE-05 Sb-122 3E-05 Sb-124 2E-05 Sb-125 lE-04 Sb-126 3E-06 I-131 3E-07 I-132 BE-06 I-133 lE-06 Ce-141 9E-05 Ce-143 4E-05 Cs-134 9E-06 Cs-136 6E-05 Cs-137 2E-05 Ru-106 lE-05 Ru-105 lE-04 La-140 2E-05 W-187 6E-05 Zn-65 lE-04 Sr-92 6E-05 Total Ci Gamma MP Ce (uCi/ml)

Nuclear Common Calculation of Effective MPC Salem Unit 2 Activity Released (Ci) 1992 1993 1994 CURIES CURIES CURIES 2.20E-04 l.59E-03 2.88E-04 7.33E-04 l.05E-03 5.77E-05 4.13E-03 4.39E-03 l.55E-03 9.15E-02 3.73E-02

1. 37E-02 l.61E-04 4.83E-04 3.25E-03 l.42E-02

1. l 7E-02 3.24E-03 2.57E+OO l.75E+OO 6.60E-Ol 2.61E-Ol 3.47E-Ol l.03E-01 2.06E-03 2.34E-03 3.22E-04 5.35E-03 3.97E-03

l. llE-03 9.37E-04 l.46E-03 l.lOE-03 2.75E-04

3.77E-04 N/D 2.28E-04 N/D N/D 6.07E-03 l.03E-02

1. 34E-02 8.51E-05 7.45E-05 N/D l.12E-04

1. 20E-03 N/D l.20E-02 3.77E-02 9.82E-03 8.29E-02 1.*35E-01 6.03E-02

1. 83E-05 3.51E-04 N/D 4.2**E-02

1. 87E-Ol 7.98E-03 N1D

8. 72E-05 N/D 2.16E-03 2.39E-03 l.85E-04 N/D N/D 2.87E-05 2.44E-04 N/D N/D 2.32E-Ol 4.57E-Ol 6.44E-01

1. 82E-03 4.82E-03 l.51E-03 2.34E-Ol 5.70E-Ol 8.54E-01 N/D N/D 4.38E-04 2.78E-04 4.07E-05 N/D 6.51E-05 2.03E-03

l. llE-04 N/D N/D 7.98E-05 l.38E-03

1. 59E-04 N/D N/D N/D 1.43E-05 3.57E+OO 3.57E+OO 2.38E+OO 1.59E-OS 4.BlE-06 l.55E-05 Page 46 of 46 Rev. 3 I

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I FORM NC.NA-AP.ZZ-0059-4 10CFRS0.59 SAFETY EVALUATION Page 13 of 20 Revision O I.D. Numbers/References/Revision:

Revision 10

~~~~~~~~""--~~~~~~~~~~~~-

Title:

Salem Offsite Dose Calculation Manual

~~~~~~~~~~=--=-~-=--==-"--=-==:=-=-==-'~.:....:.:~=.::::.=~~~~~~~~~~~~~

3.1 Continued

Effects: 1. Default liquid radiation monitor setpoint will have to be changed using the revised MPCe values for Unit 1 and 2. (E&PB Electrical)

2. RETS CODE will need to be updated to reflect the new setpoint.

(Chemistry)

Note: current setpoint is more conservative and does not need to be changed prior to the approval of this revision.

Change #9: ODCM page(s):

Appendix B,C Change: 1. Updated gaseous release values to current release values. Gaseous release values for 1992 was 550 curies, 1993 was 9SO curies, and 1994 was 1000 curies.

2. Updated effective dose factors for liquid releases. Table B-1 and B-2 were updated for 1992, 1993 and 1994 liquid releases.

3. Corrected Total Body Effective dose factor for Xe-133. Previous value for Xe-133 total body effective dose factor was conservatively high. Value was reduced from 300 mrem/yr per uci/m3 to 280 mrem/yr per uci/m3.

Determination of Effective Dose Factors Effective dose transfer factors are calculated by the following equations:

(C. l) where:

Kett the effective total body dose factor due to gamma emissions from all noble gases released K1 the total body dose factor due to gamma emissions from each noble gas radionuclide i released f 1 the fractional abundance of noble gas radionuclide i relative to the total noble gas activity Xe-133 Total Body Effective Dose Factor (K,.,t)

Kett

2. 94E+2 (ODCM Table 2-1)

0. 95 KeH 2.79E+2 (rounded to 2.8E+2)

Effects: Emergency Plan procedures and MIDAS values will be updated to reflect the change in this value.

Note:

The current value stated in the Emergency Plan procedures is more conservative than the proposed value. Procedures and MIDAS software should be updated at their next scheduled revision.

Nuclear Common Page 46 of 46 Rev. 3

FORM NC.NA-AP.ZZ-0059-4 10CFR50.59 SAFETY EVALUATION Page 14 of 20 Revision 0 I.D. Numbers/References/Revision:

Revision 10

~..::..:.~-=-=-='-==--=-=--~~~~~~~~~~~~-

Title:

Salem Offsite Dose Calculation Manual

3.1 Continued

Change #10: ODCM page(s):

Appendix D Change: Corrected wording on Grass-Cow-Milk pathway to be consistent with entire document.

Effects:

No effects on plant systems, procedures or equipment are*expected from this change.

Change #11: ODCM page(s):

Appendix B Change:

1. Reformatted Table E-1

2. Removed sampling locations that were not specifically required by Technical Specifications. (Beef, Muskrats, Rain Water, Vegtables)

3.

Added 6 additional site boundary TLD locations.

Note: The removal of sampling locations from the ODCM does not imply that samples will not be obtained from those locations. The samples from those locations will be taken as they become available. All locations where samples are obtained will be included in the annual Radiological Environmental Monitoring report. The locations in the revised ODCM represent the minimum required samples as outlined by Technical Specifications.

Effects:

No effects on plant systems, procedures or equipment are expected from this change. Revised REMP locations will be included in the next semi-annual effluent report.

Change #12 ODCM Page(s): 42 -

53 Change:

Added dose factors for Iodine 132,133,134,135 for airborne release pathways.

Effects:

No effect on plant systems, procedures or equipment are expected from this change. Dose factors were previously included in RETS CODE software.

Change #13 ODCM Page(s): 36,37, B-7,E-8 Change:

Updated figures and maps sho~ing gaseous effluent and environmental sampling locations.

Effects: No effect on plant systems, procedures or equipment are expected from this change.

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I FORM NC.NA-AP.ZZ-0059-4 10CFR50.59 SAFETY EVALUATION Page 15 of 20 Revision 0 I.D. Numbers/References/Revision: ___ ~R~e~v--=i=s~i~o=n""-1=-=0~~------------~------~----

Title:

___ ----'s~a==l~e~m"--O~f==f=s~i~t~e"-'D=-=o=s~e'--"C=a~l~c~u==l~a=t=i~o~n:.::....~M~a~n~u~a~l=-----~~~---~------~------

3.2 Identify the parameters and systems affected by the change.

The following parameters and systems are affected by this change:

A. Parameters:

i. Liquid Effluent Radiation Monitor (1Rl8) default setpoint

2. Liquid Effluent Radiation Monitor (2Rl8) default setpoint

3. Chemistry effluent software (RETS CODE) default liquid effluent setpoint for 1Rl8 and 2Rl8.

4. Chemistry effluent software (RETS CODE) dose conversion factor for Ce-141.

5. Chemistry effluent software (RETS CODE) site related ingestion dose factor for As-76.

6. Emergency Plan Software (MIDAS) - Station Status Checklist - Noble Gas release rate B. Systems

1. No systems will be effected by the proposed changes

c. Procedures:

1. Emergency Plan Implementing Procedures (EPIP)

a. EPIP 301S - Attachment 7

b. EPIP 302S

c. EPIP 303S

d. EPIP 304S - Page 3

e. EPIP 312S

2. Emergency Plan Classification Guide (ECG)

a. ECG Section 7

b. ECG Attachments 1,2,3,4,8,10,11,12,14,16,17,18,20

3. Public Service Blueprint Document 315733 (Unit 1)

4. Public Service Blueprint Document 315734 (Unit 2)

D. SAR sections affected by the change:

1. Section 11.6.4 and Table 11. 6-1 of the SAR will be affected by Revision 10 to the Salem Off site Dose Calculation Manual.

3.3 Identify the credible failure modes associated with the change.

The proposed changes to the ODCM will not introduce any new failures in relation to the credible accident/malfunctions described in Section 15 of the UFSAR. Specifically section 15.3.7 Accidental Release of Radioactive Liquids was used in making this determination.

Nuclear Common Page 46 of 46 Rev. 3

FORM NC.NA-AP.ZZ-0059-4 10CFR50.59 SAFETY EVALUATION Page 16 of 20 Revision 0 I. D. Numbers /References /Revis ion: --=R.;.;e:::.v..:...:i:.:s:::..:1==-* o=n=--=l=-0=-------------

Title:

__ ~S~a~l=-e~m~-=O-=f~f=s=-1=-'=t-=e~D~o=-s=--=e--=C=a=l=-c=-u==l~a~t=i=-o=-n~~M~a=n~u=-a~l ______________________ _

3.4 Provide references to location of information used for the safety evaluation.

References used for this safety evaluation include:

1. Regulatory Guide 1.21, Measuring, evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants.

2. NUREG-0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.

3. Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I

4. Salem Offsite Dose Calculation Manual, Revision 9

5. Code Of Federal Regulations, Title 10, Part 20

6. Salem Generating Station, Updated Final Safety Analysis Report 3.5 Other Discussion, if applicable.

The changes proposed in this revision to the calculational method of the liquid effluent radiation monitor setpoint do not change the design objectives of the Radiological Monitoring System as stated in UFSAR section 11.4.1.

Technical Specification 3.11.1 requires that the concentration of radioactive material released in liquid effluents to unrestricted areas be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionulcides other than dissolved or entrained noble gases. The changes proposed in Revision 10 to the Salem ODCM will maintain this requirement by using the following assumptions:

a. Use of minimum dilution water flow

b. Use of maximum liquid effluent release rate

c. Calculation of MPC9 based on actual release tank activities.

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I FORM NC.NA-AP.ZZ-0059-4 10CFRS0.59 SAFETY EVALUATION Page 17 of 20 Revision 0 I.D. Numbers/References/Revision:

Revision 10

---~~~~~~~-----------~-----------~

Title:

__ -"'s~a~l~e=m~O~f=f==s=i~t~e"---"D~o==s~e--=C=a=l~c~u=l==a~t=i=o=n~M~a=n=u=a=l=---~----------------~

4.0 USO DETERMINATION - Is an Unreviewed Safety Question (USQ) involved?

4.1 Which anticipated operational transients or postulated design basis accidents previously evaluated in the SAR are considered applicable to the proposal?

The design basis accident,"Accidental Release of Radioactive Liquids" as ~escribed in UFSAR Section 15.3.7 is considered applicable to Revision changes as described above.

All changes proposed in Revision 10 to the Salem ODCM do not effect any other anticipated operational transients or postulated design basis accidents previously evaluated in the SAR.

4.2 May the proposal:

a.

Increase the probability of an accident previously evaluated in the SAR?

YES __ _

NO x

DISCUSSION:

The proposed changes will not increase the probability of an accidental release of radioactive liquids as described in UFSAR Section 15.3.7. The changes proposed under this revision do not affect the sampling of the fluid prior to being discharged, the operation of any valves associated with the radwaste system, or the automatic safety function of the radiation monitor.

Nuclear Common Page 46 of 46 Rev. 3

FORM NC.NA-AP.ZZ-0059-4 10CFRS0.59 SAFETY EVALUATION Page 18 of 20 Revision 0 I. D. Numbers /References /Revis ion : __

R.._e=v----=i""s""'i=* o=n'--"l~O=------------

Title:

_ ___,,S""'a=l=e=.:.:m.__,,O~f~f~s==i~t~e=-=D~o~s=e=-~C~a~l~c~u~l==a~t~i~o~n"°-M=-=a~n~u~a~l=------------

b.

Increase the consequences of an accident previously evaluated in the SAR?

YES __ _

NO x

DISCUSSION:

The proposed changes will not increase the consequence of an accident previously evaluated in the SAR. The radiation monitors ability to terminate the release of radioactive effluent releases prior to exceeding the limits specified in 10 CFR Part 20, Table II, Column 2 will not be effected. The radiation monitor setpoint for liquid effluent releases is based on the amount of gamma activity in the tank to be discharged. An additional correction factor is added for non-gamma emitting nuclides which may be present in the tank to be released but will not be detected through normal sampling procedures.

4.3 What malfunctions of equipment important to safety that were previously evaluated in the SAR are considered applicable to the proposal?

The changes proposed under Revision 10 to the Salem ODCM do not effect the operation or malfunction of any equipment important to safety that was previously evaluated in the SAR. The changes proposed are considered mostly editorial in nature and do not effect any safety related equipment operation.

4.4 May the proposal:

a.

Increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the SAR?

Yes __ _

No_... x~-

DISCUSSION:

The changes proposed under Revision 10 to the Salem ODCM do not increase the probability of the malfunction of equipment important to safety that was previously evaluated in the SAR. The changes proposed above do not effect any safety related equipment or systems.

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I FORM NC.NA-AP.ZZ-0059-4 10CFRS0.59 SAFETY EVALUATION Page 19 of 20 Revision 0 I. D. Numbers /References /Revision : _..:..R,_,e==-v"-'i=-* =s-=i..:::o:.:.n"---'1"'-"'-0 ___________ _

Title:

_ __,S~a==l..:::e~m.:.....::O~f==-f=s-=i~t~e::........:D~o==s..:::e=--.::C~a~l~c~u~l~a~t~i~o~n~~M~a~n~u~a=-=l ___________ _

b.

Increase the consequences of a malfunction of equipment important to safety previously evaluated in the SAR?

YES __ _

NO x

DISCUSSION:

The changes proposed under Revision 10 to the Salem ODCM do not increase the consequences of a malfunction of equipment important to safety. The changes proposed above do not effect any safety related equipment or system.

4.5 May the proposal:

a.

b.

Create the possibility of an accident of a different

~

from any previously evaluated in the SAR?

YES. __ _

NO x

DISCUSSION:

The changes proposed under Revision 10 to the Salem ODCM do not create the possibility of an accident of a different type than previously evaluated in the SAR. The proposed changes are mainly editorial in nature and do not create any other accidents then those evaluated in the SAR.

Create the possibility of a malfunction of a different

~

from any previously evaluated in the SAR?

YES __ _

NO x

DISCUSSION:

The changes proposed under Revision 10 to the Salem ODCM do not create the possibility of a malfunction of a different type than previously evaluated in the SAR. The changes proposed are mainly editorial in nature and do not effect the operation design of any equipment or system important to safety.

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FORM NC.NA-AP.ZZ-0059-4 10CFR50.59 SAFETY EVALUATION Page 20 of 20 Revision 0 I.D. Numbers/References/Revision:

Revision 10

---~~~~~'-="'-"----------------------------------~

Title:

Salem Offsite Dose Calculation Manual

~~~~~'""""'"-=-=--=-'~=--======->=-===~~=='--===------------------------------------

4.6 Does the proposal reduce the margin of safety as defined in the basis for any Technical Specifications?

YES __ _

NO x

Discuss the bases for the determinations and identify the pertinent Technical Specification sections that were reviewed to make the determination (use continuation sheets if required).

The changes proposed under Revision 10 to the Salem ODCM do not reduce the margin of safety as defined in the basis for any Technical Specification.

Technical Specifications 3.3.B and 3.11.1.l are considered the pertinent sections affected by the changes proposed under Revision 10 to the Salem ODCM. The alarm/trip setpoint calculated under the proposed revision will ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20, Appendix B, Table II, Column

2. The following conservative factors are used in the setpoint calculation to ensure the limits of 10 CFR Part 20 are not exceeded.

a. Use of minimum dilution water flow

b. Use of maximum liquid effluent release rate

c. Calculation of MPCe based on actual release tank activities.

5.0 CONCLUSION

If ALL answers in Section 4 are "NO," the proposal does NOT involve a USQ.

If ANY answer in Section 4 is "YES", the proposal involves a USQ.

Is a USQ involved?

YES ______ _ NO x

If a USQ is involved, obtain assistance from Licensing for additional processing.

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I Approval SORC Chairman:

SALEM NUCLEAR GENERATING STATION OFFSITE DOSE CALCULATION MANUAL Revision 10 January 1996 CONTROL COPY # i J

11._----------~~-i

()( s--

Salem ODCM Rev. 10 SALEM NUCLEAR GENERATING STATION OFFSITE DOSE CALCULATION MANUAL Table of Contents Introduction 1

1.0 Liquid Effluents 1.1 Radiation Monitoring Instrumentation and Controls 2

1.2 Liquid Effluent Monitor Setpoint Determination 3

1.2.1 Liquid Effluent Monitors (Radwaste, Steam Generator Blowdown and Service Water) 4 1.2.2 Conservative Default Values 5

1.3 Liquid Effluent Concentration Limits -

10 CFR 20 6

1.4 Liquid Effluent Dose Calculations -

10 CFR 50 7

1.4.1 Member of the Public Dose - Liquid Effluents 7

1.4.2 Simplified Liquid Effluent Dose Calculation 9

1.5 Secondary Side Radioactive Liquid Effluents - Dose Calculations During Primary to Secondary Leakage.

10 1.6 Liquid Effluent Dose Projection 11 2.0 Gaseous Effluents 3.0 2.1 2.2 2.3 2.4 2.5 Radiation Monitoring Instrumentation* and Controls 12 Gaseous Effluent Monitor Setpoint Determination 13 2.2.1 Containment and Plant Monitor 13 2.2.2 Conservative Default Values 14 Gaseous Effluent Instantaneous Dose Rate Calculations -

10 CFR 20.

15 2.3.1 Site Boundary Dose Rate - Noble Gases.

15 2.3.2 Site Boundary Dose Rate -

Radioiodine and Particulates.

17 Noble Gas Effluent Dose Calculations -

10 CFR 50.

18 2.4.1 UNRESTRICTED AREA Dose - Noble Gases.

18 2.4.2 Simplified Dose Calculation for Noble Gases. 19 Radioiodine and Particulate Dose Calculations -

10 CFR 50.

20 2.5.1 UNRESTRICTED AREA Dose -

Radioiodine and Particulates 20 2.5.2 Simplified Dose Calculation for Radioiodines and Particulates.

21 2.6 Secondary Side Radioactive Gaseous Effluents and Dose Calculations 22 2.7 Gaseous Effluent Dose Projection 24 Special Dose Analyses 3.1 Doses Due To Activities In3ide the SITE BOUNDARY.

3.2 Doses to MEMBERS OF THE PUBLIC -

40 CFR 190 3.2.1 Effluent Dose Calculations.

3.2.2 Direct Exposure Determination.

i 25 25 26 26

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Salem ODCM

~ev. 10 Table of Co~tents - Continued 4.0 Radiological Environmental Monitoring Program.

4.1 Sampling Program.

27 27 27 Tabl?.s 4.2 Interlaboratory Comparison Program.

1-1 1-2 1-3 1-4 2-1 2-2 2-3 2-4 2-5 A-1 A-2 B-1 B-2 C-1 D-1 D-2 E-1 Parameters for Liquid Alarm Setpoint Determination

- Unit 1.

31 Parameters for Liquid Alarm Setpoint Determination

- Unit 2.

32 Site Related Ingestion Dose Commitment Factors, Aio.

Bioaccumulation Factors (BFi).

Dose Factors for Noble Gases

. 33-34

. 35

. 38 Parameters for Gaseous Alarm Setpoint Determinations

- Unit 1.

. 39 Parameters for Gaseous Alarm Setpoint Determinations

- Unit 2.

40 Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations.

Pathway Dose Parameters - Atmospheric Releases Calculation of Effective MPC - Unit 1 Calculation of Effective MPC - Unit 2 Adult Dose Contributions Fish and Drinking Water Pathways Unit 1 Adult Dose Contributions Fish and Drinking Water Pathways Unit 2 Effective Dose Factors Inf ant Dose Contribution Fraction of Dose Fraction of Dose Contribution by Pathway Environ~ental Sampling Locations.

41 42-53 A-6 A-7 B-5 B-5 C-4 D-5 D-5 E-3 Appendices Appendix A - Evaluation of Conservative, Default MPC Value for Liquid Effluents.

. A-1 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 Effluents D-1 Appendix E - Radiological Environmental Monitoring Program - Sample Type, Location and Analysis

. E-1 ii

Introduction Salem ODCM Rev. 10 SALEM NUCLEAR GENERATING STATION OFFSITE DOSE CALCULATION MANUAL The Salem Offsite Dose Calculation Manual (ODCM) describes the methodology and parameters used in:

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 and cumulative quarterly and yearly doses.

The methodology stated in this manual is acceptable for use in demonstrating compliance with 10 CFR 20.106, 10 CFR 50, Appendix I and 40 CFR 190. More conservative calculation methods and/or conditions (e.g., location and/or exposure pathways) expected to yield higher computed doses than appropriate for the ~aximally exposed person may be assumed in the dose evaluations.

The ODCM will be maintained at the station for use as a reference guide and training document of accepted methodologies and calculations.

Changes will be made to the ODCM calculation methodologies and parameters as is deem~d necessary to ensure reasonable conservatism in keeping with the principles of 10 CFR 50.36a and Appendix I for demonstrating radioactive effluents are ALARA.

NOTE:

As used throughout this document, excluding acronyms, words appearing all capitalized denote the application of definitions as used in the Salem Technical Specifications.

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I Salem ODCM Rev. 10 1.0 Liquid Effluents 1.1 Radiation Monitoring Instrumentation and Controls The liquid effluent monitoring instrumentation and controls at Salem for controlling and monitoring normal radioactive material releases in accordance with the Salem Radiological Effluent Technical Specifications are summarized as follows:

1)

Alarm (and Automatic Termination) -

1-RlB (Unit 1) and 2-RlB (Unit 2) provide the alarm and automatic termination of liquid radioactive material releases as required by Technical Specification 3.3.3.8.

2) l-Rl9 A,B,C,and D provide the alarm and isolation function for the Unit 1 steam generator blowdown lines.

2-Rl9 A,B,C and D provide this function for Unit 2.

Alarm (only) - The alarm functions for the Service Water System are provided by the radiation monitors on the Containment Fan Cooler discharges (1-R 13 A,B,C,D and E for Unit 1 and 2-R 13 A,B,and C for Unit 2).

Releases from the secondary system are routed through the Chemical Waste Basin where the effluent is monitored (with an alarm function) by R37 prior to release to the environment.

Liquid radioactive waste flow diagrams with the applicable, associa~ed radiation monitoring instrumentation and controls are presented as Figures 1-1 and 1-2 for Units 1 and 2, respectively.

2

Salem ODCM Rev. 10 1.2 Liquid Effluent Monitor Setpoint Determination Per the requirements of Technical Specification 3.3.3.8, alarm setpoints shall be established for the liquid effluent monitoring instrumentation to ensure that the release concentration limits of Specification 3.11.1.1 are met (i.e., the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2, for radionuclides and 2.0E-04 uCi/ml for dissolved or entrained noble gases).

The following equation* must be satisfied to meet the liquid effluent restrictions:

where:

c c

f F

C (F+f)

(1.1) c.s.

f the effluent concentration limit of *Technical Specification (3.11.1.1) implementing the 10 CFR 20 MPC for the site, in uCi/ml the setpoint, in uCi/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, represents a value which, if exceeded, would result in concentrations exceeding the limits of 10 CFR 20 in the UNRESTRICTED AREA the flow rate at the radiation monitor location, in volume per unit time, but in the same units as F, below the dilution water flow rate as measured prior to the release point, in volume per unit time

[Note that if no dilution is provided, cs. C.

Also, note that when (F) is large compared to (f), then (F + f) =

F.]

Adapted from NUREG-0133 3

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I Salem ODCM Rev. 10 1.2.1 Liquid Effluent Monitors (Radwaste, Steam Generator Blowdown, Chemical Waste Basin and Service Water.

The setpoints for the liquid effluent monitors at the Salem Nuclear Generating Station are determined by the following equations:

with:

where:

SP MP Ce Ci SEN cw RR bkg SF MPCe

SEN

CW

SF SP ~

+ bkg (1. 2)

MP Ce RR L: Ci (1.3)

Ci L:

MP Ci alarm setpoint corresponding to the maximum allowable release rate (cpm) an effective MPC value for the mixture of radionuclides in the effluent stream (uCi/ml) the concentration of radionuclide i in the undiluted liquid effluents (uCi/ml)"

the MPC value corresponding to radionuclide i from 10 CFR 20, Appendix B, Table II, Column 2 (uCi/ml) the sensitivity value to which the monitor is calibrated (cpm per uCi/ml) the circulating water flow rate (dilution water flow) at the time of release (gal/min) the liquid effluent release rate (gal/min) the background of the monitor (cpm)

Safety factor to account for non-gamma emitting nuclides in default setpoint calculations.

Note: The concentration mix must include the most recent composite of alpha emitters, Sr-89, Sr-90, Fe-55, and H-3 per Technical Specification 3.11.1.1.

4

Salem ODCM Rev. 10 The radioactivity monitor setpoint equation (1.2) remains valid during outages when the circulating water dilution is potentially at its lowest value.

Reduction of the waste stream flow (RR) may be necessary during these periods to meet the discharge criteria.

However, in order to maximize the available plant discharge dilution and thereby minimize the potential offsite doses, releases from either Unit-1 or Unit-2 may be routed to either the Unit-1 or Unit-2 Circulating Water System discharge.

This routing is possible via interconnections between the Service Water Systems (see Pages 28 and 29).

Procedural restrictions prevent simultaneous releases from either a single unit or both units into a single Circulating Water System discharge.

1.2.2 Conservative Default Values.

Conservative alarm setpoints may be determined through the use of default parameters.

Tables 1-1 and 1-2 summarize all current default values in use for Salem Unit-1 and Unit-2, respectively.

They are based upon the following:

a) substitution of the effective MPC value with a default value of 6.0SE-06 uCi/ml (Unit 1) and 4.81E-06 uci/ml (Unit 2). (refer to Appendix A for justification);

b) for additional conservatism*, substitution of the I-131 MPC value of 3E-07 uCi/ml for the Rl9 Steam Generator Blowdown Monitors, the R-37 Chemical Waste Basin monitor and the R-13 Service Water Monitors.

c) substitutions of the operational circulating water flow with the lowest flow, in gal/min; and, d) substitutions of the effluent release rate with the highest allowed rate, in gal/min.

e) substitution of a safety factor of 0.25 to account for non-gamma emitting nuclides.

With pre-established alarm setpoints, it is possible to control the radwaste release rate (RR) to ensure the inequality of equation (1.2) is maintained under changing values for MPCe and for differing Circulating Water System dilutions.

Based upon the potential for I-131 to be present in the secondary and service water systems, the use of the default effective MPC value as derived in Appendix A may be non-conservative for the 1, 2 R-19 SGBD monitors, the R-37 Chemical Waste Basin Monitor and the R-13 Service Water Monitors.

5

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I Salem ODCM Rev. 10 1.3 Liquid Effluent Concentration Limits -

10 CFR 20 Technical Specification 3.11.1.1 limits the concentration of radioactive material in liquid effluents (after dilution in the Circulating Water System) to less than the concentrations as specified in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than noble gases.

Noble gases are limited to a diluted concentration of 2.0E-04 uCi/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:

where:

RR cw RR

.s. 1 (1. 4)

CW + RR actual concentration of radionuclide i as measured in the undiluted liquid effluent (uCi/ml) the MPC value corresponding to radionuclide i from 10 CFR 20, Appendix B, Table II, Column 2 (uCi/ml) 2E-04 uCi/ml for dissolved or entrained noble gases the actual liquid effluent release rate (gal/min) the actual circulating water flow rate (dilution water flow) at the time of the release (gal/min) 6

Salem ODCM Rev. 10 1.4 Liquid Effluent Dose Calculation -* 10 CFR 50 1.4.1 MEMBER OF THE PUBLIC Dose - Liquid Effluents.

Technical Specification 3.11.1.2 limits the dose or dose commitment to MEMBERS OF THE PUBLIC from radioactive materials in liquid effluents from each unit of the Salem Nuclear Generating Station to:

during any calendar quarter;

~ 1.5 mrem to total body per unit

~ 5.0 mrem to any organ per unit

- during any calendar year;

~ 3.0 mrem to total body per unit

~ 10.0 mrem to any organ per unit.

Per the surveillance requirements of Technical Specification 4.11.1.2, the following calculational methods shall be used for determining the dose or dose commitment due to the liquid radioactive effluents fr6m Salem.

where:

Do VOL=

cw =

l.67E-02=

l.67E-02

VOL (1. 5) cw dose or dose commitment to organ o (mrem).

Total body dose can also be calculated using site-related total body dose commitment factor.

site-related ingestion dose commitment factor to the total body or any organ o for radionuclide i (mrem/hr per uCi/ml) average concentration of radionuclide i, in undiluted liquid effluent representative of the volume VOL (uCi/ml) volume of liquid effluent released (gal) average circulating water discharge rate during release period (gal/min) conversion factor (hr/min) 7 I

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I Salem ODCM Rev. 10 The site-related ingestion dose/dose commitment factors (Ai 0 ) are presented in Table 1-3 and have been derived in accordance with the requirements of NUREG-0133 by the equation:

where:

Aio UI =

Bii=

UF =

BF1=

DF1=

l.14E+05=

l.14E+05 [ (UI

BI;) + (UF

BF;)] DFi (1. 6) 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) adult invertebrate consumption (5 kg/yr) bioaccumulation factor for radionuclide i in invertebrates from Table 1-4 (pCi/kg per pCi/l) adult fish consumption (21 kg/yr) bioaccumulation factor for radionuclide i in fish from Table 1-4 (pCi/kg per pCi/1) dose conversion factor for nuclide i for adults in pre-selected organ, o, from Table E-11 of Regulatory Guide 1.109 (mrem/pCi) conversion factor (pCi/uCi

ml/kg per hr/yr)

The radionuclides included in the periodic dose assessment per the requirements of Technical Specification 3/4.11.1.2 are those as identified by gamma spectral analysis of the liquid waste samples collected and analyzed per the requirements of Technical Specification 3/4.11.1.1, Table 4.11-1.

Radionuclides requiring radiochemical analysis (e.g., Sr-89 and Sr-90) will be added to the dose analysis at a frequency consistent with the required minimum analysis frequency of Technical Specification Table 4.11-1.

8

Salem ODCM Rev. 10 1.4.2 Simplified Liquid Effluent Dose Calculation.

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 l.21E+03

VOL Dtb

=

r: Ci

( 1. 7) cw Maximum Organ where:

VOL cw Dtb Dmax=

1.21E+03 =

2.52E+04 2.52E+04

VOL Dmax

=

r: Ci (1. 8) cw average concentration of radionuclide i, in undiluted liquid effluent representative of the volume VOL (uCi/ml) volume of liquid effluent released (gal) average circulating water discharge rate during release period (gal/min) conservatively evaluated total body dose (mrem) conservatively evaluated maximum organ dose (mrem) conversion factor (hr/min) and the conservative total body dose conversion factor (Fe-59, total body --

7.27E+04 mrem/hr per uCi/ml) conversion factor (hr/min) and the conserva~ive maximum organ dose conversion factor (Nb-95, GI-LLI

-- 1.51E+06 mrem/hr per uCi/ml) 9 I

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I Salem ODCM Rev. 10 1.5 Secondary Side Radioactive Liquid Effluents and Dose Calculations During Primary to Secondary Leakage During periods of primary to secondary leakage (i.e., steam generator tube leaks), radioactive material will be transmitted from the primary system to the secondary system.

The potential exists for the release of radioactive material to the off-site environment (Delaware River) via secondary system discharges.

Potentially significant radioactive material levels and potential releases are controlled/monitored by the Steam Generator blowdown monitors (R19) and the Chemical Waste Basin monitor (R37).

However to ensure compliance with the regulatory limits on radioactive material releases, it may be desirable to account for potential releases from the secondary system during periods of primary to secondary leakage.

Any potentially significant releases will be via the Chemical Waste Basin with the major source of activity being the Steam Generator blowdown.

With identified radioactive material levels in the secondary system, appropriate samples should be collected.and analyzed for the principal gamma emitting radionuclides.

Based on the iden~ified radioactive material levels and the volume of water discharged, the resulting environmental doses may be calculated based on equation (1.5).

Because the release rate from the secondary system is indirect (e.g., SG blowdown is normally routed to condenser where the condensate clean-up system will remove much of the radioactive material), samples should be collected from the final release point (i.e., Chemical Waste Basin) for quantifying the radioac_ive material releases.

However, for conservatism and ease of controlling and quantifying all potential release paths, it is prudent to sample the SG blowdown and to assume all radioactive material is released directly to the environment via the Chemical Waste Basin.

This approach while not exact, is conservative and ensures timely analysis for regulatory compliance.

Accounting for radioactive material retention of the condensate clean-up system ion exchange resins may be needed to more accurately account for actual releases.

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I Salem ODCM Rev. 10 1.6 Liquid Effluent Dose Projections 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 quarterly projected doses exceed:

0.375 mrem to the total body, or 1.25 mrem to any organ.

The applicable liquid waste processing system for maintaining radioactive material releases ALARA is the ion exchange system as delineated in Figure 1-3.

Alternately, the waste evaporator as presented in the Salem FSAR has processing capabilities meeting the NRC ALARA design requirements and may be used in conjunction or in lieu of the ion exchange system for waste processing requirements in accordance with Technical Specification 3.11.1.3.

These processing requirements are applicable to each unit individually.

Exceeding the projected dose requiring processing prior to release for one unit does not in itself dictate processing requirements for the other unit.

Dose projections are made at least once per 31 days by the following equations:

where:

Dtb (91 I d)

Dmax { 91 / d)

(1. 9)

(1.10)

Dtbp = the total body dose projection for current calendar quarter (mrem)

Dtb the total body dose to date for current calendar quarter as determined by Equation 1.5 or 1.7 (mrem)

Dma~= the maximum organ dose projection for current calendar quarter (mrem)

Dmax the maximum organ dose to date for current calendar quarter as determined by Equation 1.5 or 1.7 (mrem) d the number of days to date for current calendar quarter 91 the number of days in a calendar quarter 11

Salem ODCM Rev. 10 2.0 Gaseous Effluents 2.1 Radiation Monitoring Instrumentation and Controls The gaseous effluent monitoring instrumentation and controls at Salem for controlling and monitoring normal radioactive material releases in accordance with the Radiological Effluent Technical Specifications are summarized as follows:

1) Waste Gas Holdup System -

The vent header gases are collected by the waste gas holdup system.

Gases may be recycled to provide cover gas for the eves hold-up tank or held in the waste gas tanks for decay prior to release. Waste gas decay tanks are batch released after sampling and analysis. The tanks are discharged via the Plant Vent. l-R41C provides noble gas monitoring and automatic isolation of waste gas decay tank releases for Unit-1.

This function is provided by 2-R41C for Unit-2.

2)

Containment Purqe and Pressure/Vacuum Relief - containment purges and pressure/vacuum reliefs are released to the atmosphere via the respective unit Plant Vent.

Noble gas monitoring and auto isolation function are provided by l-R41C for Unit-1 and 2-R41C for Unit-2.

Additionally, in accordance with Technical Specification 3.3.3.9, Table 3.3-13, l-Rl2A and 2-Rl2A may be used to provide the containment monitoring and automatic isolation function during purge and pressure/vacuum reliefs.*

3)

Plant Vent - The Plant Vent for each respective unit receives discharges from the waste gas hold-up system, condenser evacuation system, containment purge and pressure/vacuum reliefs, and the Auxiliary Building ventilation.

Effluents are monitored by R41C, a flow through gross activity monitor (for noble gas monitoring). Additionally, in-line gross activity monitors (l-Rl6 and 2-Rl6) provide redundant back-up monitoring capabilities to the R41C monitors.

Radioiodine and particulate sampling capabilities are provided by charcoal cartridge and filter medium samplers with redundant back-up sampling capabilities provided by R41B and R41A, respectively. Plant Vent flow rate is measured and as a back-up may be determined empirically as a function of fan operation (fan curves).

Sampler flow rates are determined by flow rate instrumentation (e.g., venturi rotameter).

The Rl2A monitors also provide the safety function of containment isolation in the event of a fuel handling accident during refueling.

During MODE 6 in accordance with Technical Specification 3/4.3.3, Table 3.3-6, the R12A alarm/trip setpoint shall be established at twice background. This will provide containment isolation and indication of unexpected increases in containment airborne radioactive material levels which can be indicative of fuel degradation. The R41C monitor may also provide this function if the R12A monitor is inoperable during MODE 6.

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I Salem ODCM Rev. 10 Gaseous radioactive waste flow diagrams with the applicable, associated radiation monitoring instrumentation and controls are presented as Figures 2-1 and 2-2 for Units 1 and 2, respectively.

2.2 Gaseous Effluent Monitor Setpoint Determination 2.2.1 Containment and Plant Vent Monitor.

Per the requirements of Technical Specification 3.3.3.9, alarm setpoints shall be established for the gaseous effluent monitoring instrumentation to ensure that the release rate of noble gases does not exceed the limits of Specification 3.11.2.1, which corresponds to a dose rate at the SITE BOUNDARY of 500 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.,

grab sample of the Containment atmosphere, waste gas decay tank, or Plant Vent), the radiation monitoring alarm setpoints may be established by the following calculation method.

The measured radionuclide concentrations and release rate are used to calculate the fraction of the allowable release rate, as limited by Specification 3.11.2.1, by the equation:

FRAC FRAC where:

[4.72E+02

X/Q *VF*

L: (Ci* KJ] I 500 (2.1)

[4.72E+02

X/Q *VF* L: (Ci * (Li+ 1.1 MJ )] I 3000 (2.2)

FRAC = fraction of the allowable release rate based on the X/Q VF 1.1 500 3000 4.72 identified radionuclide concentrations and the release flow rate annual average meteorological dispersion to the controlling site boundary location (sec/m3 )

ventilation system flow rate for the applicable release point and monitor (ft 3/min) concentration of noble gas radionuclide i as determined by radioanalysis of grab sample (uCi/cm3 )

total body dose conversion factor for noble gas radionuclide i (mrem/yr per uCi/m3 from Table 2-1) beta skin dose conversion factor for noble gas radionuclide i (mrem/yr per uCi/m3 from Table 2-1) gamma air dose conversion factor for noble gas radionuclide i (mrem/yr per uCi/m3 from Table 2-1) mrem skin dose per mrad gamma air dose (mrem/mrad) total body dose rate limit (mrem/yr) skin *dose rate limit (mrem/yr)

E+02 = conversion factor (cm3/ft 3

min/sec) 13

Salem ODCM Rev. 10 Based on the more limiting FRAC (i.e., higher value) as determined above, the alarm setpoints for the applicable monitors (Rl6, R41C, and/or Rl2A) may be calculated by the equation:

where:

SP SP = [AF

E Ci

SEN / FRAC]

+ bkg alarm setpoint corresponding to the maximum allowable release rate (cpm) monitor sensitivity (cpm per uCi/cm3 )

background of the monitor (cpm)

(2. 3)

SEN =

bkg =

AF administrative allocation factor for the specific monitor and type release, which corresponds to the fraction of the total allowable release rate that is administratively allocated to the release.

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., ~he release rate limits of Technical Specification 3.11.2.1).

Normally, the combined AF value for Salem Units 1 and 2 is equal to 0.5 (0.25 per unit), with the remainder 0.5 allocated to Hope Creek.

Any increase in AF above 0.5 for the Salem Nuclear Generating Station will be coordinated with the Hope Creek 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 Tabl~ 2-2 and 2-3 for Units 1 and 2, respectively.

These values are based upon:

the maximum ventilation (or purge) flow rate; a radionuclide distribution* comprised of 95% Xe-133, 2% Xe-135, 1% Xe-133m, 1% Kr-88 and 1% Kr-85; and an administrative allocation factor of 0.25 to conservatively ensure that any simultaneous releases from Salem Units 1 and 2 do not exceed the maximum allowable release rate.

For this radionuclide distribution, the alarm setpoint based on the total body dose rate is more restrictive than the corresponding setpoint based on the skin dose rate.

Adopted from ANSI N237-1976/ANS-18.l, Source Term Specifications, Table 6 14 I

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I Salem ODCM Rev. 10 2.3 Gaseous Effluent Instantaneous Dose Rate Calculations -

10 CFR 20 2.3.1 Site Boundary Dose Rate - Noble Gases.

Technical Specification 3.11.2.la limits the dose rate at the SITE BOUNDARY due to noble gas releases to ~500 mrem/yr, total body and ~3000 mrem/yr, skin.

Radiation monitor alarm setpoints are established to ensure that these release limits are not exceeded.

In the event a~y gaseous releases from the station results in an alarm setpoint being exceeded, an evaluation of the SITE BOUNDARY dose rate resulting from the release shall be performed using the following equations:

where:

1.1 and X/Q

L: ((Li+ l.lMJ

QJ

= total body dose rate (mrem/yr) skin dose rate (mrem/yr)

(2. 4)

( 2. 5) atmospheric dispersion to the controlling SITE BOUNDARY location ( sec/m3 )

average release rate of radionuclide i over the release period under evaluation (uCi/sec) total body dose conversion factor for noble gas radionuclide i (mrem/yr per uCi/m3,

from Table 2-1) beta skin dose conversion factor for noble gas radionuclide i (mrem/yr per uCi/m3,

from Table 2-1) gamma air dose conversion factor for noble gas radionuclide i (mrad/yr per uCi/m3,

from Table 2-1) 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 release exceeding the above prescribed alarm setpoints.

Monitor indications (readings) may be averaged over a time period not to exceed 15 minutes when determining noble gas release rate based on correlation of the monitor reading and monitor sensitivity. The 15 minute averaging is needed to allow for reasonable monitor response to potentially changing radioactive material concentrations and to exclude potential electronic spikes in monitor readings that may be unrelated to radioactive material releases.

As identified, any electronic spiking monitor responses may be excluded from the analysis.

15

Salem ODCM Rev. 10 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 limits of Technical Specification 3.11.2.la.

Provided actual releases do not result in radiation monitor indications exceeding alarm setpoint values based on the above criteria, no further analyses are required for demonstrating compliance with the limits of Specification 3.11.2.la.

Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented in Table 2-4 may be used for evaluating the gaseous effluent dose rate.

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I Salem ODCM Rev. 10 2.3.2 Site Boundary Dose Rate - Radioiodine and Particulates.

Technical Specification 3.11.2.1.b limits the dose rate to <1500 lives greater than 8 days. To demonstrate compliance with this limit, an evaluation is performed at a frequency no greater than that corresponding to the sampling and analysis time period (e.g., nominally once per 7 days).

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

X/Q

l::

(Rio

QJ (2. 6) where:

D0

= 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 )

Rio = dose parameter for radionuclide i (mrem/yr per uCi/m3 )

and organ o for the child inhalation pathway from Table 2-5 Qi

= 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)

By substituting 1500 mrem/yr for D0 and solving for Q, an allowable release rate for I-131 can be determined.

Based on the annual average meteorological dispersion (see Table 2-4) and the most limiting potential pathway, age group and organ (inhalation, child, thyroid --

Rio.= 1.62E+07 mrem/yr per uCi/m3 ), the allowable release rate for I-131 is 42 uCi/sec.

Reducing this release rate by a factor of 4 to account for potential dose contributions from other radioactive particulate material and other release points (e.g., Hope Creek), the corresponding release rate allocated to each of the Salem units is 10.5 uCi/sec.

For a 7 day period, which is the nominal sampling and analysis frequency for I-131, the cumulative release is 6.3 Ci.

Therefore, as long as the I-131 releases in any 7 day period do not exceed 6.3 Ci, no additional analyses are needed for verifying compliance with the Technical Specification 3.11.2.1.b limits on allowable release rate.

17

Salem ODCM Rev. 10 2.4 Noble Gas Effluent Dose Calculations -

10 CFR SO 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 mrad, gamma-air and <10 mrad, beta-air and the calendar year-limits <10 mrad, gamma=air and <20 mrad, beta-air.

The limits are applicable separately to each unit and are not combined site limits.

The following equations shall be used to calculate the gamma-air and beta-air doses:

and 3.1 7E-08

X/Q *

~ (Ni

QJ where:

D9

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

Db

= air dose due to beta emissions for noble gas radionuclides (mrad)

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

(2. 7)

(2. 8)

Qi cumulative release of noble gas radionuclide i over the period of interest (uCi) where uCi = (uci/cc) (cc released) or (uCi/ sec) (sec released)

Mi air dose factor due to gamma emissions from noble gas radionuclide i (mrad/yr per uCi/m3,

from Table 2-1)

N; air dose factor due to beta emissions from noble gas radionuclide i (mrad/yr per uCi/m3, Table 2-1) 3.17E-08 =conversion factor (yr/sec) 18 I

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Salem ODCM Rev. 10 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 shall be used for verifying compliance with the dose limits of Technical Specification 3.11.2.2.

(Refer to Appendix C for the derivation and justification for this simplified method.)

3.17E-08 (2. 9) 0.50 and 3.17E-08 (2.10) 0.50 where:

Meff=

5. 3E+02, effective gamma-air dose factor (mrad/yr per uCi/m3 )

Nerf=

l.1E+03, effective beta-air dose factor (mrad/yr per uCi/m3 )

Qi cumulative release for all noble gas radionuclides (uCi) where uCi = (uCi/cc) (cc released) or (uCi/sec)

(sec released) 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 2-4, may be used for the evaluation of the gamma-air and beta-air doses.

19

Salem ODCM Rev. 10 2.5 Radioiodine and Particulate Dose Calculations -

10 CFR SO 2.5-.1 UNRESTRICTED AREA Dose - Radioiodine and Particulates.

In accordance with requirements of Technical Specification 3.11.2.3, a periodic assessment shall be performed to evaluate compliance with the quarterly dose limit of ~7.5 mrem and calendar year limit ~15 mrem to any organ.

The following equation shall be used to evaluate the maximum organ dose due to releases of I-131, tritium and particulates with half-lives greater than 8 days:

Daop

=

3. 17E-08

w

SFp

l: ( Riop

QJ

( 2.11) where:

Da~= dose or dose commitment via all pathways p and controlling age group a (as identified in Table 2-4) to organ o, including the total body (mrem)

W = atmospheric dispersion parameter to the controlling location(s) as identified in Table 2-4 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 (m-2 )

R 1~

dose factor for radionuclide i (mrem/~r per uCi/m3 ) or (m2 mrem/yr per uCi/sec) and organ o from Table 2-5 for each age group and the applicable pathway p as identified in Table 2-4.

Values for Rio were derived in accordance with the methods described in NUREG-0133 Q1 cumulative release over the period of interest for radionuclide i -- I-131 or radioactive material in particulate form with half-life greater than 8 days(uCi).

SFP annual seasonal correction factor to account for the fraction of the year that the apolicable exposure pathway does not exist.

1) For milk and vegetation exposure pathways:

A six month fresh vegetation and grazing season (May through October) = 0.5

2) For inhalation and ground plane exposure pathways: = 1.0 For evaluating the maximum exposed individual, the infant age group is controlling for the milk pathway.

Only the controlling age group as identified in Table 2-4 need be evaluated for compliance with Technical Specification 3.11.2.3.

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I Salem ODCM Rev. 10 2.5.2 Simplified Dose Calculation for Radioiodines and Particulates.

In lieu of the individual radionuclide (I-131 and particulates) dose assessment as presented above, the following simplified dose calculation equation may be used for verifying compliance with the dose limits of Technical Specification 3.11.2.3 (refer to Appendix D for the derivation and justification of this simpli-fied method).

where:

Dmax RI-131 Dmax 3.17E-08

w

SFp

RI-131

L: Qi (2.12) maximum organ dose (mrem)

I-131 dose parameter for the thyroid for the identified controlling pathway l.OSE+l2, infant thyroid dose parameter with the grass-cow-milk pathway controlling (m2 mrem/yr per uCi/sec)

D/Q for radioiodine, 2.lE-10 l/m2 cumulative release over the period of interest for radionuclide I -- I-131 or radioactive material in particulate from 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 Salem as identified by the annual land-use census (Technical Specification 3.12.2).

Otherwise, the dose will be evaluated based on the predetermined controlling pathways as identified in Table 2-4.

21

Salem ODCM Rev. 10 2.6 Secondary Side Radioactive Gaseous Effluents and Dose Calculations During periods of primary to secondary leakage, minor levels of radioactive material may be released via the secondary system to the atmosphere.

Non-condensables (e.g., noble gases) will be predominately released via the condenser evacuation system and will be monitored and quantified by the routine plant vent monitoring and sampling system and procedures (e.g., RlS on condenser evacuation, R41C on plant vent, and the plant vent particulate and charcoal samplers).

However, if the Steam Generator blowdown is routed directly to the Chemical Waste Basin (via the SG blowdown flash tank) instead of being recycled through the condenser, it may be desirable to account for ~he potential atmospheric releases of radioiodines and particulates from the flash tank vent (i.e., releases due to moisture carry over).

Since this pathway is not sampled or monitored, it is necessary to calculate potential releases.

Based on the guidance in NRC NUREG-0133, the releases of the radioiodines and particulates shall be calculated by the equation:

where:

(2.13) the release rate of radionuclide, i, from the steam generator flash tank vent (uCi/sec) the concentration of radionuclide, i, in the secondary coolant water averaged over not more than one week (uCi/ml) the steam generator blowdown rate to the flash tank (ml/sec) the fraction of blowdown flashed in the tank determined from a heat balance taken around the flash tank at the applicable reactor power level the measured steam quality in the flash tank vent; or an assumed value of 0.85, based on NUREG-0017.

Tritium releases via the steam flashing may also be quantified using the above equation with the assumption of a steam quality (SQt~) equal to 0. Since the H-3 will be associated with the water molecules, it is not necessary to account for the moisture carry-over which is the transport media for the radioiodines and particulates.

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I Salem ODCM Rev. 10 Based on the design and operating conditions at Salem, the fraction of blowdown converted to steam (Fttl is approximately 0.48.

The equation simplifies to the following:

(2.14)

For H-3, the simplified equation is:

(2.15)

Also during reactor shutdown operations with a radioactively contaminated secondary system, radioactive material may be released to the atmosphere via the atmospheric reliefs (PORV) and the safety reliefs on the main steam lines and via the steam driven auxiliary feed pump exhaust.

The evaluation of the radioactive material concentration in the steam relative to that in the steam generator water is based* on the guidance of NUREG-0017, Revision 1.

The parti~ioning factors for the radioiodines is 0.01 and is 0.001 for all other particulate radioactive material.

The resulting equation for quantifying releases via the atmospheric steam releases is:

where:

Qij

( 2. 16) release rate of radionuclide i via pathway j (uCi/sec) concentration of radionuclide i, in pathway j, (uCi/sec) steam flow for release pathway j 450,000 lb/hr per PORV 800,000 lb/hr per safety relief valve 50,000 lb/hr for auxiliary feed pump exhaust

= partitioning factor, ratio of concentration in to that in the water in the steam generator 0.01 for radioiodines 0.005 for all other particulates 1.0 for H-3 steam 0.13= conversion factor -

[(hr*ml) I (sec*lb)]

Any significant releases of noble gases via the atmospheric steam releases can be quantified in accordance with the calculation methods of the Salem Emergency Plan Implementation Procedure.

Alternately, the quantification of the release rate and cumulative releases may be based on actual samples of main steam collected at the R46 sample locations.

The measured radionuclide concentration in the steam may be used for quantifying the noble gases, radioiodine and particulate releases.

23

Salem ODCM Rev. 10 Note:

The expected mode of operation would be to isolate the effected steam generator, thereby reducing the potential releases during the shutdown/cooldown process.

Use of the above calculation methods should consider actual operating conditions and release mechanisms.

The calculated quantities of radioactive materials may be used as inputs to the equation (2.11) or (2.12) to calculate offsite doses for demonstrating compliance with the Radiological Effluent Technical Specifications.

2.7 Gaseous Effluent Dose Projection Technical Specification 3.11.2.4 requires that the GASEOUS RADWASTE TREATMENT SYSTEM and VENTILATION EXHAUST TREATMENT SYSTEM be used to reduce radioactive material levels prior to discharge when projected doses exceed one-half the annual design objective rate in any calendar quarter, i.e., exceeding:

0.625 mrad/quarter, gamma air; 1.25 mrad/quarter, beta air; or 1.875 mrem/quarter, maximum-organ.

The applicable gaseous processing systems for maintaining radioactive material releases ALARA are the Auxiliary Building normal ventilation system (filtration systems # 1,2 and 3) and the Waste Gas Decay Tanks as delineated-in Figures 2-3 and 2-4.

Dose projections are performed at least once per 31 days by the following equations:

where:

D~

d 91 Dg * (91 I d)

Db * (91 I d)

=

D~x * (91 / d)

(2.17)

(2.18)

(2.19)

= gamma air dose projection for current calendar quarter(mrad)

= gamma air dose to date for current calendar quarter as determined by Equation 2.7 or 2.9 (mrem)

= beta air dose projection for current calendar quarter (mrad)

= beta air dose to date for current calendar quarter as determined by Equation 2.8 or 2.10 (mrem) maximum organ dose projection for current calendar quarter (mrem) maximum organ dose to date for current calendar quarter as determined by Equation 2.11 or 2.12 (mrem) number of days to date in current calendar quarter number of days in a calendar quarter 24 I

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I Salem ODCM Rev. 10 3.0 Special Dose Analyses 3.1 Doses Due To Activities Inside the SITE BOUNDARY In accordance with Technical Specification 6.9.1.11, the Radioactive Effluent Release Report (RERR) must be submitted within 60 days after January 1st and July 1st of each year and 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 2-4.

The default value for the meteorological dispersion data as presented in Table 2-3 may be used if current year meteorology is unavailable at the time of NRC reporting.

However, a follow-up evaluation shall be performed when the data becomes available.

3.2 Total dose to MEMBERS OF THE PUBLIC -

40 CFR 190 The Radioactive Effluent Release Report (RERR), *submitted within 60 days after January 1st and July 1st of each year shall also include an assessment of the radiation dose to the likely most exposed MEMBER OF THE PUBLIC for reactor releases and other nearby uranium fuel cycle sources (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 Nuclear Generating Station and the Hope Creek Nuclear Generating Station:

No other fuel cycle facilities contribute to the MEMBER OF THE PUBLIC dose for the Artificial Island vicinity.

The dose contribution from the operation of Hope Creek ~Juclear Generating Station will be estimated based on the methods as presented in the Hope Creek Offsite Dose Calculation Manual (HCGS 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.

25

Salem ODCM Rev. 10 3.2.1 Effluent Dose Calculations For purposes of implementing the surveillance requirements of Technical Specification 3/4.11.4 and the reporting requirements of 6.9.1.11 (RERR), dose calculations for the Salem Nuclear Generating Station may be performed using the calculation methods contained within this ODCM; the conservative controlling pathways and locations of Table 2-4 or the actual pathways and locations as identified by the land use census (Technical Specification 3/4.12.2) may be used.

Average annual meteorological dispersion parameters or meteorological conditions concurrent with the release period under evaluation may be used.

3.2.2 Direct Exposure Dose 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) and/or by the use of a radiation transport and shielding calculation method.

Only during a non-typical condition will there exist any potential for significant on-site sources at Salem 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, should a situation exist where the direct exposure contri~ution is potentially significant, on-site measurements, off-site measurements and/or calculation techniques will be used for determination of dose for assessing 40 CFR 190 compliance.

26

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I 4.0 4.1 Salem ODCM Rev. 10 Radiological Environmental Monitoring Program Sampling Program The operational phase of the Radiological Environmental Monitoring Program (REMP) is conducted in accordance with requirements of Appendix A Technical Specification 3.12.

objectives of the program are:

the The To determine whether any significant increases occur in the concentration of radionuclides in the critical pathways of exposure in the vicinity of Artificial Island; To determine if the operation of the Salem Nuclear Generating Stations has resulted in any increase in the inventory of long lived radionuclides in the environment; To detect any changes in the ambient gamma radiation levels; and To verify that SNGS 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 effluents discharged from Salem Generating Station.

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

Participation in an approved Interlaboratory Comparison Program provides a check on the preciseness of measurements of radioactive materials in environmental ~amples.

A summary of the Interlaboratory Comparison Program results will be provided in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.10.

27

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I Salem ODCM Rev. 10 Table 1-1 Parameters for Liquid Alarm Setpoint Determinations Unit 1 Parameter Actual Default Units Corrments Value Value MPC*

calculated 6.05E-06

uci/ml Calculated for each batch to be released.

MPC 1-131 3.0E-07 N/A uci/ml 1-131 MPC conservatively used for SG blowdown and Service Water monitor setpcints.

c, measured N/A uci/ml Taken from ganma spectral analysis of liauid effluent.

MPC, as determined N/A uci/ml Taken from 10 CFR 20, Appendix B, Table II, Col 2.

Sensitivity as determined N/A cpm per.

Monitor sensitivities are**

1-R18 uci/ml controlled under Public Service 1-R19 CA,B,C,D)

Blueprint Document CPSBP) 315733 1-R13 CA,B,C,D,E) cw a5 determined 1.OOE+05 gpm Circulating water system - single CW ~

RR 1-R18 as determined 120 gpm Determined prior to release; release rate can be adjusted for 1*R19 Technical Specification compliance 1-R13 120 Steam Generator blowdown rate per Generator Service Water flow rate for 2500 Containment fan coolers Set point calculated N/A cpm Monitor setpoints are controlled 1*R18 under Public Service Blueprint 1-R19 **

Document CPSBP) 315733 1-R13(A,B,C,D,E)**

Safety Factor as determined 0.25 Unit less Default parameter to account for (Non-Ganma) non-gamna emitting nuclides.

Refer to Appendix A for derivation

- The MPC value of !*131 (3E-07 uci/ml) has been used for derivation of R19 Steam Generator blowdown and R13 Service Water monitor setpoints as discussed in Section 1.2.2 31

Salem ODCM Rev. 10 Table 1-2 Parameters for Liquid Alarm Setpoint Determinations Unit 2 Parameter Actual Default Units Coaments Value Value MPC*

calculated 4.81E-06

uci/ml Calculated for each batch to be released.

MPC 1-131 3.0E-07 N/A uci/ml 1-131 HPC conservatively used for SG blowc:lown, Service Water and Chemical Waste Basin monitor setpoints.

c, measured N/A uci/ml Taken from gamma spectral analysis of liquid effluent.

MPC, as determined N/A uci/ml Taken from 10 CFR 20, Appendix B, Table II, Col. 2 Sensitivity as determined N/A cpm/uci/ml Monitor sensitivities are controlled 2-R18 under Public Service Blueprint 2-R19CA,B,C,D)

Docullent 315734 2-R13 R37 cw as determined 1.0E+OS gpm Circulating Water System, single CW

~

(Note: no CW pU!1p in service for 2R13 monitor - see section 1.2.2>

RR 2-R18 as determined 120 gpm Determined prior to release; release rate can be adjusted for Technical Specification Compliance.

2-R19 120 Steam Generator Slowdown rate per Generator Service Water flow rate for 2-R13 2500 Containment fan coolers R37 1200 Chemical Waste Basin discharge Setpoint calculated N/A cpm Monitor setpoints are controlled under 2-R18 Public Service Blueprint Docunent 2-R19CA,B,C,D)

CPSBP) 315734 2-R13 **

R37 **

Safety Factor as determined 0.25 Unit less Default parameter to account for non-(Non-Gal!'l1la) gal!'l1la emitting nuclides.

Refer to Appendix A for derivation

- The MPC value of I-131 (3.DE-7 uci/ml) has been used for derivation of the R13 and R37 monitor setpoints as discussed in Section 1.2.2 32

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' I Salem ODCM Rev. 10 Table 1-3 I

Site Related Ingestion Dose Commitment Factors, Aio (mrem/hr per uCi/ml)

I Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI H-3 2.82E-l 2.82E-l 2.82E-l 2.82E-l 2.82E-l 2.82E-l C-14 l.45E+4 2.90E+3 2.90E+3 2.90E+3 2.90E+3 2.90E+3 2.90E+3 I

Na-24 4.57E-l 4.57E-l 4.57E-l 4.57E-l 4.57E-l 4.57E-l 4.57E-l P-32 4.69E+6 2.91E+5 l.81E+5 5.27E+5 Cr-51 5.58E+O 3.34E+O l.23E+O 7.40E+O l.40E+3 I

Mn-54 7.06E+3 l.35E+3 2.10E+3 2.16E+4 Mn-56 l.78E+2 3.15E+l 2.26E+2 5.67E+3 Fe-55 5.11E+4 3.53E+4 8.23E+3 l.97E+4 2.03E+4 I

Fe-59 8.06E+4 l.90E+5 7.27E+4 5.30E+4 6.32E+5 Co-57

1. 42E+2 2.36E+2 3.59E+3 I

Co-58 6.03E+2 l.35E+3 l.22E+4 Co-60 l.73E+3 3.82E+3 3.25E+4 Ni-63 4.96E+4 3.44E+3 l.67E+3 7.18E+2 Ni-65 2.02E+2 2.62E+l l.20E+l 6.65E+2 1-Cu-64 2.14E+2 l.01E+2 5.40E+2 l.83E+4 Zn-65

.l.61E+5 5.13E+5 2.32E+5 3.43E+5 3.23E+5 I

Zn-69 3.43E+2 6.56E+2 4.56E+l 4.26E+2 9.85E+l

~r-82 4.07E+O 4.67E+O r-83 7.25E-2 l.04E-l Br-84 9.39E-2 7.37E-7 I

Br-85 3.86E-3 Rb-86 6.24E+2 2.91E+2 l.23E+2 I

Rb-88 l.79E+O 9.49E-l 2.47E-ll Rb-89 l.19E+O 8.34E-l 6.89E-14 Sr-89 4.99E+3 l.43E+2 8.00E+2 I

Sr-90 l.23E+5 3.01E+4 3.55E+3 Sr-91 9.18E+l 3.71E+O 4.37E+2 Sr-92 3.48E+l 1.51E+O 6.90E+2 Y-90 6.06E+O 1.63E-l 6.42E+4 I

Y-9lm 5.73E-2 2.22E-3 l.68E-l Y-91 8.88E+l 2.37E+O 4.89E+4 I

Y-92 5.32E-l l.56E-2 9.32E+3 Y-93 l.69E+O 4.66E-2 5.35E+4 Zr-95 l.59E+l 5.llE+O 3.46E+O 8.02E+O l.62E+4 Zr-97 8.81E-l 1.78E-1 8.13E-2 2.68E-1 5.51E+4 I

Nb-95 4.47E+2 2.49E+2 l.34E+2 2.46E+2 1.51E+6 Nb-97 3.75E+O. 9.49E-1 3.46E-1 l.llE+O 3.50E+3 I

Mo-99 1.28E+2 2.43E+l 2.89E+2 2.96E+2 Tc-99m 1.30E-2 3.66E-2 4.66E-1 5.56E-1 1.79E-2 2.17E+l

>101 1.33E-2 1.92E-2 1.88E-1 3.46E-1 9.81E-3 5.77E-14

_.::; - 7 6 4.38E+2 l.16E+3 5.14E+3 3.42E+2 l.39E+3 3.58E+2 4.30E+4 I

33 I

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Salem ODCM Rev. 10 I

Table 1-3 (cont'd)

I Site Related Ingestion Dose Commitment Factors, Aio (mrem/hr per uCi/ml)

Nuclide Bone Liver T.Body Thyroid Kidney Lung GI-LLI I

Ru-103 l.07E+2 4.60E+l 4.07E+2 l.25E+4 Ru-105 8.89E+O 3.51E+O l.15E+2 5.44E+3 I

Ru-106 l.59E+3 2.01E+2 3.06E+3 l.03E+5 Rh-103m Rh-106 I

Ag-llOm l.56E+3

1. 4 SE+3 8.60E+2 2.8SE+3 S.91E+S Sb-124 2.77E+2 5.23E+O l.10E+2 6.71E-l 2.15E+2 7.86E+3 Sb-125 l.77E+2 l.98E+O 4.21E+l l.80E-l l.36E+2 l.9SE+3 I

Te-125m 2.17E+2 7.86E+l 2.91E+l 6.52E+l 8.82E+2 8.66E+2 Te-127m 5.48E+2 l.96E+2 6.68E+l l.40E+2 2.23E+3 l.84E+3 Te-127 8.90E+O 3.20E+O l.93E+O 6.60E+O 3.63E+l 7.03E+2 I

Te-129m 9.31E+2 3.47E+2

1. 47E+2 3.20E+2 3.89E+3 4.69E+3 Te-129 2.54E+O 9.SSE-1 6.19E-l l.9SE+O l.07E+l l.92E+O Te-13lm l.40E+2 6.8SE+l S.71E+l l.08E+2 6.94E+2 6.80E+3

-1 Te-131 l.59E+O 6.66E-l 5.03E-l l.31E+O 6.99E+O 2.26E-l Te-132 2.04E+2

1. 32E+2 l.24E+2 l.46E+2 l.27E+3 6.24E+3 I-130 3.96E+l l.17E+2 4.61E+l 9.91E+3 l.82E+2 l.01E+2 I

T-131 2.18E+2 3.12E+2 l.79E+2 l.02E+S 5.3SE+2 8.23E+l

-132 l.06E+l 2.BSE+l 9.96E+O 9.96E+2 4.54E+l S.3SE+O I-133 7.45E+l l.30E+2 3.95E+l l.90E+4 2.26E+2 l.16E+2 I

I-134 5.56E+O l.51E+l 5.40E+O 2.62E+2 2.40E+l l.32E-2 I-135 2.32E+l 6.0BE+l 2.24E+l 4.01E+3 9.75E+l 6.87E+l Cs-134 6.84E+3 l.63E+4 l.33E+4 5.27E+3 l.75E+3 2.85E+2 I

Cs-136 7.16E+2 2.83E+3 2.04E+3 l.57E+3 2.16E+2 3.21E+2 Cs-137 8.77E+3 l.20E+4 7.85E+3 4.07E+3 l.35E+3 2.32E+2 I

Cs-138 6.07E+O l.20E+l 5.94E+O 8.81E+O 8.70E-l 5.12E-5 Ba-139 7.85E+O S.59E-3 2.30E-l 5.23E-3 3.17E-3 l.39E+l Ba-140 l.64E+3 2.06E+O l.08E+2 7.02E-l l.18E+O 3.38E+3 Ba-141 3.81E+O 2.88E-3 l.29E-l 2.68E-3 l.63E-3 l.BOE-9 I

Ba-142 l.72E+O

1. 77E-3 l.08E-l l.SOE-3 l.OOE-3 2.43E-18 La-140 l.57E+O 7.94E-l 2.lOE-1 5.83E+4 I

La-142 8.06E-2 3.67E-2 9.13E-3 2.68E+2 Ce-141 3.43E+O 2.32E+O 2.63E-l l.OBE+O 8.86E+3 Ce-143 6.04E-l 4.46E+2 4.94E-2 l.97E-l

1. 67E+4 Ce-144 l.79E+2 7.47E+l 9.59E+O 4.43E+l 6.04E+4

~ I Pr-143 5.79E+O 2.32E+O 2.87E-1 l.34E+O

2. 54E+4 Pr-144 l.90E-2. 7.87E-3 9.64E-4 4.44E-3 2.73E-9 I

Nd-147 3.96E+O 4.58E+O 2.74E-1 2.68E+O 2.20E+4 W-187 9.16E+O 7.66E+O 2.68E+O 2.51E+3

)-23 9 3.53E-2 3.47E-3 l.91E-3 l.08E-2 7.11E+2 I

34 I*

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Cr Mn Fe Co Ni Cu Zn Br Rb Sr y

Zr Nb Mo Tc Ru Rh Ag Sb Te I

Cs Ba La Ce Pr Nd w

Np As Salem ODCM Rev.. 10 Table 1-4 Bioaccumulation Factors (BFi)

(pCi/kg per pCi/liter)"

Saltwater Fish Saltwater Invertebrate 9.0E-01 9.3E-01 1.BE+03 1.4E+03 6.7E-02 1.9E-01 3.0E+03 3.0E+04 4.0E+02 2.0E+03 5.SE+02 4.0E+02 3.0E+03 2.0E+04 1.0E+02 l.OE+03 1.0E+02 2.5E+02 6.7E+02 1.7E+03 2.0E+03 5.0E+04

1. SE- 02 3.lE+OO 8.3E+OO 1.7E+Ol 2.0E+OO 2.0E+Ol 2.SE+Ol 1.0E+03 2.0E+02 8.0E+Ol 3.0E+04 1.0E+02 1.0E+Ol 1.0E+Ol l.OE+Ol 5.0E+Ol 3.0E+OO 1.0E+03 l.OE+Ol 2.0E+03 3.3E+03 3.3E+03 4.0E+Ol 5.4E+OO l.OE+Ol 1.0E+02 1.0E+Ol 5.0E+Ol 4.0E+Ol 2:5E+Ol l.OE+Ol l.OE+02 2.SE+Ol l.OE+03 l.OE+Ol 6.0E+02 2.SE+Ol 1.0E+03 2.SE+Ol 1.0E+03 3.0E+Ol 3.0E+Ol 1.0E+Ol 1.0E+Ol 3.3E+02 3.3E+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.

35

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Table 2*1 Dose Factors for Noble Gases I

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-1 Total Body Gantna Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor Radionuclide Ki Li Mi Ni (mrem/yr per uCi/m3)

(mrem/yr per uCi/m3)

(mrad/yr per uCi/m3)

Kr-83m 7.56E-02 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr*85 1.61E+01 1.34E+03

1. 72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04

1. 73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03.

Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.0SE+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.4*2E+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 I

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Salem ODCM Rev. 10 Table 2-2 Parameters for Gaseous Alarm Setpoint Determinations Unit 1 Parameter Actual Default Units Corrments Value Value X/Q calculated 2.2E-06 sec:/m3 USN RC Salem Safety Evaluation, Sup 3 VF (Plant Vent) as measured or 1.30E+05 ft 3/min Plant Vent - normal fan curves operation (Cont Purge) 3.50E+04 Contairvnent Purge AF coordinated 0.25 N/A Administrative allocation factor with HCGS to ensure cOIT'bined releases do not exceed release rate limit site.

c, measured N/A uci/c~

Taken from ganma spectral for analysis of gaseous effluent K,

nuclide specific N/A mr:rntyr per Values from Table 2-1 UCl/m L,

nuc:l i de specific N/A mre:mtyr per Values from Table 2-1 UCl/m M,

nuclide speci fie N/A mre:mtyr per Values from Table 2-1 UCl/m Sensitivities as determined N/A cpm ~r Monitor sensitivities are 1-R41C uci/m3 controlled under Public 1-R16 Service Blueprint Document 1-R12A CPSBP) 315733 Setpoint calculated N/A cpm Monitor setpoints are 1-R41C controlled under Public 1-R16 Service Blueprint Doc1m1ent 1-R12A **

CPSBP 315733

- Applicable during Modes 1 through 5. During Mode 6 (refuel*ing), monitor setpoint shall be reduced to 2x background in accordance with Technical Specification Table 3.3-6 39

Salem ODCM Rev. 10 Table 2-3 Parameters for Gaseous Alarm Setpoint Determinations Unit 2 Parameter Actual Default Units Conmen ts Value Value X/Q calculated 2.2E-6 sec/m3 Licensing Technical Specification value VF Plant Vent as measured or 1.30E+05 tt3/min Plant Vent - normal operation fan curves Cont. Purge 3.50E+04 contaiNnent Purge AF coordinated with 0.25 N/A Acininistrative allocation factor HCGS to ensure coni>ined releases do not exceed release rate tor site.

c, measured N/A uci/cm3 Taken from gamma spectral analysis of gaseous effluent K,

nuclide specific N/A.

mr~tyr per Values from Table 2-1 uc1/m L,

nuclide !.pecific N/A mr~/yr per Values from Table 2*1 uc1/m M,

nuclide specific N/A mremtyr per Values from Table 2*1 uci/m Sensitivities as determined N/A cpm ~r Monitor sensitivities are 2*R41C uci/m3 controlled under Public Service 2-R16 Blueprint Docunent CPSBP) 315734 2*R12A Setpoint calculated N/A cpm Monitor setpoints are controlled 2*R41C under Public Service Blueprint 2*R16 OocLillent (PSBP) 315734 2*R12A **

- Applicable during MOOE~ 1 through 5. During MODE 6 (refueling), monitor setpoints shall be reduced to 2x background in accordance with Technical Specification 3.3*6.

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I Salem ODCM Rev. 10 Table 2-4 Controlling Locations, Pathways and Atmospheric Dispersion for Dose Calculations

Technical Specification Location 3.11.2.la site boundary (0.83 mile, N) 3.11.2. lb site boundary (0. 83 mile, N) 3.11.2.2 site boundary (0.83 mile, N) 3.11.2.3 residence/dairy*

(4.9 miles, W)

Atmospheric Dispersion Pathway(s) noble gases direct exposure inhalation gamma-air beta-air milk, ground Controlling Age Group N/A child N/A infant plane and inhalation X/Q (Sec/m3)

D/Q (l/m2) 2.2E-06 N/A 2.2E-06 N/A

2. 2E-0.6 N/A S.4E-08 2.lE-10

Location and distance are determined from the performance of the annual land use census as required by Technical Specification 3.12.2.

The identified controlling locations, pathways and atmospheric dispersion are from the Safety Evaluation Report, Supplement No.

3 for the Salem Nuclear Generating Station, Unit 2 (NUREG-0517, December 1978).

41

Salem ODCM Rev. 10 I

Table 2-5 I

Pathway Dose Factors - Atmospheric Releases R (io), Inhalation Pathway Dose Factors - ADULT (mrem/yr per uCi/m3)

Nuclide Bone Liver*

Thyroid Kidney Lung GI-LLI T.Body I

H-3 l.26E+3 l.26E+3 l.26E+3 l.26E+3 l.26E+3 l.26E+3 C-14 l.82E+4 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 P-32 l.32E+6 7.71E+4 8.64E+4 5.01E+4 I

Cr-51 5.95E+l 2.28E+l l.44E+4 3.32E+3 l.OOE+2 Mn-54 3.96E+4 9.84E+3 l.40E+6 7."'4E+4 6.30E+3 Fe-55 2.46E+4 l.70E+4 7.21E+4 6.03E+3 3.94E+3 Fe-59 l.18E+4 2.78E+4 l.02E+6 l.88E+5 l.06E+4 I

Co-57 6.92E+2 3.70E+5 3.14E+4 6.71E+2 Co-58 l.58E+3 9.28E+5 l.06E+5 2.07E+3 Co-60 l.15E+4 5.97E+6 2.85E+5 l.48E+4 I

Ni-63 4.32E+5 3.14E+4 l.78E+5 l.34E+4 l.45E+4 Zn-65 3.24E+4 l.03E+5 6.90E+4 8.64E+5 5.34E+4 4.66E+4 Rb-86 l.35E+5 l.66E+4 S.90E+4 I

Sr-89 3.04E+5 l.40E+6 3.50E+5 8.72E+3 Sr-90 9.92E+7 9.60E+6 7.22E+5 6.10E+6 Y-91 4.62E+5 l.70E+6 3.85E+5 l.24E+4 Zr-95 l.07E+5 3.44E+4 5.42E+4 l.77E+6 l.50E+5 2.33E+4

-1 Nb-95

1. 41E+4 7.82E+3 7.74E+3 5.05E+S l.04E+5 4.21E+3 Ru-103 l.53E+3 5.83E+3 S.05E+5 l.10E+5 6.58E+2 Ru-106 6.91E+4 l.34E+S 9.36E+6 9.12E+5 8.72E+3 Ag-llOm l.08E+4 l.OOE+4 l.97E+4 4.63E+6 3.02E+5 S.94E+3 I

Sb-124 3.12E+4 5.89E+2 7.55E+l 2.48E+6 4.06E+5 l.24E+4 Sb-125 5.34E+4 S.95E+2 5.40E+l l.74E+6 l.01E+5 l.26E+4 Te-125m 3.42E+3 l.58E+3 l.OSE+3 l.24E+4 3.14E+S 7.06E+4 4.67E+2 I

Te-127m l.26E+4 5.77E+3 3.29E+3 4.58E+4 9.60E+S l.50E+5 l.57E+3 Te-129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 l.16E+6 3.83E+5 l.58E+3 I-131 2.52E+4 3.58E+4 l.19E+7 6.13E+4 6.28E+3 2.05E+4 I

I-132 l.16E+3 3.26E+3 l.14E+5 5.18E+3 4.06E+2 l.16E+3 I-133 8.64E+3 l.48E+4 2.15E+6 2.58E+4 8.88E+3 4.52E+3 I-134 6.44E+2 l.73E+3 2.98E+4 2.75E+3 l.OlE+O 6.15E+2 I

I-135 2.68E+3 6.98E+3 4.48E+5 l.11E+4 5.25E+3 2.57E+3 Cs-134 3.73E+5 8.48E+5 2.87E+5 9.76E+4 l.04E+4 7.28E+5 Cs-136 3.90E+4 l.46E+5 8.56E+4 l.20E+4 l.17E+4 l.10E+5 Cs-137 4.78E+5 6.21E+5 2.22E+S 7.52E+4 8.40E+3 4.28E+5 I

Ba-140 3.90E+4 4.90E+l l.67E+l

1. 27E+6 2.18E+5 2.57E+3 Ce-141 l.99E+4 l.35E+4 6.26E+3 3.62E+5 l.20E+5 l.53E+3 Ce-144 3.43E+6 l.43E+6 8.48E+5 7.78E+6 8.16E+5 l.84E+S I

Pr-143 9.36E+3 3.75E+3 2.16E+3 2.81E+5 2.00E+5 4.64E+2 Nd-147 5.27E+3 6.10E+3 3.56E+3 2.21E+5 l.73E+5 3.65E+2

- I

- I I

42 I

I

' I Salem O:JCM Rev. 10 Table 2-5 (cont'd)

I

?. (io), Inhalation Pathway Dose Factors - TEENAGER (mrem/yr per uci/m3)

I Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 l.27E+3 l.27E+3 l.27E+3 l.27E+3 l.27E+3 l.27E+3 C-14 2.60E+4 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 I

P-32 l.89E+6 l.lOE+S 9.28E+4 7.16E+4 Cr-51 7.50E+l 3.07E+l 2.10E+4 3.00E+3 l.35E+2 Mn-54 5.11E+4 l.27E+4 l.98E+6 6.68E+4 8.40E+3 I

Fe-55 3.34E+4 2.38E+4 l.24E+5 6.39E+3 5.54E+3 Fe-59 l.59E+4 3.70E+4 l.53E+6 l.78E+5 l.43E+4 Co-57 6.92E+2 5.86E+5 3.14E+4 9.20E+2 Co-58 2.07E+3 l.34E+6 9.52E+4 2.78E+3 I

Co-60 l.51E+4 8.72E+6 2.59E+5 l.98E+4 Ni-63 5.80E+5 4.34E+4 3.07E+5 l.42E+4 l.98E+4 Zn-65 3.86E+4 l.34E+5 8.64E+4 l.24E+6 4.66E+4 6.24E+4 I

Rb-86 l.90E+5 l.77E+4 8.40E+4 Sr-89 4.34E+5 2.42E+6 3.71E+5 l.25E+4 Sr-90 l.08E+8 l.65E+7 7.65E+5 6.68E+6 Y-91 6.61E+5 2.94E+6 4.09E+5 l.77E+4 1*

Zr-95

1. 46E+5 4.58E+4 6.74E+4 2.69E+6

1. 49E+5 3.15E+4 Nb-95 l.86E+4 l.03E+4 l.OOE+4 7.51E+5 9.68E+4 5.66E+3 Ru-103 2.10E+3 7.43E+3 7.83E+5 l.09E+5 8.96E+2 I

Ru-106 9.84E+4 l.90E+5 l.61E+7 9.60E+5

1. 24E+4 Ag-llOm l.38E+4 l.31E+4 2.50E+4 6.75E+6 2.73E+5 7.99E+3 Sb-124 4.30E+4 7.94E+2 9.76E+l 3.85E+6 3.98E+5 l.68E+4 I

Sb-125 7.38E+4 8.08E+2 7.04E+l 2.74E+6 9.92E+4 l.72E+4 Te-125m 4.88E+3 2.24E+3 1.40E+3 5.36E+5 7.50E+4 6.67E+2 Te-127m l.BOE+4 8.16E+3 4.38E+3 6.54E+4 l.66E+6 l.59E+5 2.18E+3 Te-129m l.39E+4 6.58E+3 4.58E+3 5.19E+4 l.98E+6 4.05E+5 2.25E+3 I

I-131 3.54E+4 4.91E+4 l.46E+7 8.40E+4 6.49E+3 2.64E+4 I-132 l.59E+3 4.38E+3 l.51E+5 6.92E+3 l.27E+3 l.58E+3 I-133 l.22E+4 2.05E+4 2.92E+6 3.59E+4

'.C3E+4 6.22E+3 I

I-134 8.88E+2 2.32E+3 3.95E+4 3.66E+3 2.04E+l 8.40E+2 I-135 3.70E+3 9.44E+3 6.21E+5 l.49E+4 6.95E+3 3.49E+3 Cs-134 5.02E+5 l.13E+6 3.75E+5 l.46E+5 9.76E+3 5.49E+5 I

cs-136 5.15E+4 l.94E+S l.10E+5 l.78E+4 l.09E+4 l.37E+S Cs-137 6.70E+5 8.48E+5 3.04E+5 l.21E+5 8.48E+3 3.llE+S Ba-140 5.47E+4 6.70E+l 2.28E+l 2.03E+6 2.29E+5 3.52E+3 Ce-141 2.84E+4 l.90E+4 8.88E+3 6.14E+5 l.26E+S 2.17E+3 I

Ce-144 4.89E+6 2.02E+6 l.21E+6 l.34E+7 8.64E+5 2.62E+5 Pr-143 l.34E+4 5.31E+3 3.09E+3 4.83E+5 2.14E+S 6.62E+2 Nd-147 7.86E+3 8.56E+3 5.02E+3 3.72E+5 l.82E+5 5.13E+2 I.

I I

43 I

I

Salem ODCM Rev. 10 I

Table 2-5 (cont'd)

I R (io), Inhalation Pathway Dose Factors - CHILD (mrem/yr per uCi/m3)

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body I

H-3

l. :.2E+3 l.12E+3 l.12E+3 l.12E+3 l.12E+3 l.12E+3 C-14 3.59E+4 6.'3E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 I

P-32 2.60E+6 l.14E+5 4.22E+4 9.88E+4 Cr-51 8.55E+l 2.43E+l 1.70E+4 1.08E+3 1.54E+2 Mn-54 4.29E+4 1.00E+4 1.58E+6 2.29E+4 9.51E+3 I

Fe-55 4.74E+4 2.52E+4 1.llE+S 2.87E+3 7.77E+3 Fe-59 2.07E+4 3.34E+4 1.27E+6 7.07E+4 1.67E+4 Co-57 9.03E+2 5.07E+5 1.32E+4 1.07E+3 Co-58 1.77E+3 l.11E+6 3.44E+4 3.16E+3 I

Co-60 1.31E+4 7.07E+6 9.62E+4 2.26E+4 Ni-63 8.21E+5 4.63E+4 2.75E+5 6.33E+3

2. 80E+4 Zn-65 4.26E+4 l.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 I

Sr-89 5.99E+5 2.16E+6 1.67E+5

1. 72E+4 Sr-90 1.0lE+B l.48E+7 3.43E+5 6.44E+6 Y-91 9.14E+5 2.63E+6 l.84E+5 2.44E+4

1 Zr-95 l.90E+5 4.18E+4 5.96E+4 2.23E+6 6.11E+4 3.70E+4 Nb-95 2.35E+4 9.18E+3 8.62E+3 6.14E+5 3.70E+4 6.55E+3 Ru-103 2.79E+3 7.03E+3 6.62E+5 4.48E+4 1.07E+3 I

Ru-106 1.36E+5 1.84E+5 l.43E+7* 4.29E+5 1.69E+4 Ag-llOm l.69E+4 l.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 3.24E+6 1.64E+5 2.00E+4 Sb-125 9.84E+4 7.59E+2 9.lOE+l 2.32E+6 4.03E+4 2.07E+4 I

Te-125m 6.73E+3 2.33E+3 l.92E+3 4.77E+5 3.38E+4 9.14E+2 Te-127m

2. 4 9E+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 5.03E+4 1.76E+6 1.82E+5 3.04E+3 I

I-131 4.81E+4 4.81E+4 1.62E+7 7.88E+4 2.84E+3 2.73E+4 I-132 2.12E+3 4.07E+3 1.94E+5 6.25E+3 3.20E+3 1.88E+3 I-133 l.66E+4 2.03E+4 3.85E+6 3.38E+4 5.48E+3 7.70E+3 I

I-134 l.17E+3 2.16E+3 5.07E+4 3.30E+3 9.55E+2 9.95E+2 I-135 4.92E+3 8.73E+3 7.92E+5 1.34E+4 4.44E+3 4.14E+3 Cs-134 6.51E+5 1.01E+6 3.30E+5 1.21E+5 3.85E+3 2.25E+5 Cs-136 6.51E+4 1.71E+5 9.55E+4 1.45E+4 4.18E+3 l.16E+5 I

Cs-137 9.07E+5 8.25E+5 2.82E+5 l.04E+S 3.62E+3 l.28E+5 Ba-140 7.40E+4 6.48E+l 2.llE+l l.74E+6 1.02E+S 4.33E+3 Ce-141 3.92E+4 l.95E+4 8.55E+3 5.44E+S 5.66E+4 2.90E+3 Ce-144 6.77E+6 2.12E+6 l.17E+6 l.20E+7 3.89E+5 3.61E+S I

Pr-143 l.85E+4 5.55E+3 3.00E+3 4.33E+5 9.73E+4 9.14E+2 Nd-147 l.08E+4 8.73E+3 4.81E+3 3.28E+5 8.21E+4 6.81E+2

- I

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44 I

I

-~----

I

~

Salem ODCM Rev. 10 Table 2-5 (cont'd)

I R (io), Inhalation Pathway Dose Factors -

INFANT (mrem/yr per uCi/m3)

I Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 C-14 2.65E+4 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 I

P-32 2.03E+6 l.12E+5 l.61E+4 7.74E+4 Cr-51 5.75E+l l.32E+l l.28E+4 3.57E+2 8.95E+l Mn-54 2.53E+4 4.98E+3 l.OOE+6 7.06E+3 4.98E+3 I

Fe-55 l.97E+4 l.17E+4 8.69E+4 l.09E+3 3.33E+3 Fe-59

1. 36E+4 2.35E+4 l.02E+6 2.48E+4 9.48E+3 Co-57 6.51E+2 3.79E+5 4.86E+3 6.41E+2 I

Co-58 l.22E+3 7.77E+5 l.11E+4 l.82E+3 Co-60 8.02E+3 4.51E+6 3.19E+4 l.18E+4 Ni-63 3.39E+5 2.04E+4 2.09E+5 2.42E+3 l.16E+4 Zn-65 l.93E+4 6.26E+4 3.25E+4 6.47E+5 5.14E+4 3.11E+4 I

Rb-86 l.90E+5 3.04E+3 8.82E+4 Sr-89 3.98E+5 2.03E+6 6.40E+4 l.14E+4 Sr-90 4.09E+7 l.12E+7 l.31E+5 2.59E+6 Y-91 5.88E+5 2.45E+6 7.03E+4 l.57E+4 1-Zr-95 l.15E+5 2.79E+4 3.11E+4 l.75E+6 2.17E+4 2.03E+4 Nb-95 l.57E+4 6.43E+3 4.72E+3 4.79E+S l.27E+4 3.78E+3 Ru-103 2.02E+3 4.24E+3 S.52E+S l.61E+4 6.79E+2 I

Ru-106 8.68E+4 l.07E+5 l.16E+7 l.64E+S l.09E+4 Ag-llOm 9.98E+3 7.22E+3 l.09E+4 3.67E+6 3.30E+4 5.00E+3 Sb-124 3.79E+4 5.56E+2 l.01E+2 2.6SE+6 S.91E+4 l.20E+4 I

Sb-125 5.17E+4 4.77E+2 6.23E+l l.64E+6 l.47E+4 l.09E+4 Te-125m 4.76E+3 l.99E+3 l.62E+3 4.47E+5 l.29E+4 6.58E+2 Te-127m l.67E+4 6.90E+3 4.87E+3 3.75E+4 l.31E+6 2.73E+4 2.07E+3 Te-129m l.41E+4 6.09E+3

5. 4 7E+3 3.18E+4 l.68E+6 6.90E+4 2.23E+3 I

I-131 3.79E+4 4.44E+4 l.48E+7 5.18E+4 l.06E+3 l.96E+4 I-132 l.69E+3 3.54E+3

1. 69E+5 3.95E+3 l.90E+3 l.26E+3 I-133 l.32E+4 l.92E+4 3.56E+6 2.24E+4 2.16E+3 S.60E+3 I

I-134 9.21E+2 l.88E+3 4.45E+4 2.09E+3 l.29E+3 6.65E+2 I-135 3.86E+3 7.60E+3 6.96E+5 8.47E+3 l.83E+3 2.77E+3 Cs-134 3.96E+5 7.03E+S l.90E+5 7.97E+4 l.33E+3 7.45E+4 I

Cs-136 4.83E+4

1. 35E+5 5.64E+4 l.18E+4 l.43E+3 5.29E+4 Cs-137 5.49E+5 6.12E+S

1. 72E+5 7.13E+4 l.33E+3 4.55E+4 Ba-140 5.60E+4 5.60E+l l.34E+l l.60E+6 3.84E+4 2.90E+3 Ce-141 2.77E+4 l.67E+4 5.2SE+3 5.17E+5 2.16E+4 l.99E+3.

I Ce-144 3.19E+6 l.21E+6 5.38E+S 9.84E+6 l.48E+5 l.76E+5 Pr-143 l.40E+4 5.24E+3 l.97E+3 4.33E+5 3.72E+4 6.99E+2 Nd-147 7.94E+3 8.13E+3 3.15E+3 3.22E+5 3.12E+4 5.00E+2 I -

I I

45 I

I

Nuclide H-3 C-14 P-32 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Zn-65 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Ru-103 Ru-106 Ag-llOm Sb-124 Sb-125 Te-125m Te-127m Te-129m I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 Pr-143 Nd-147 Salem ODCM 2ev. 10 Table 2-5 (cont'd)

R(io), Grass-Cow-Milk Pathway Dose Factors (mrem/yr per uCi/m3) for H-3 and C-14 (m2

mrem/yr per uCi/sec) for others ADULT Bone Liver Thyroid Kidney GI-LLI Lung T.Body 7.63E+2 7.63E+2 7.63E+2 3.63E+5 7.26E+4 7.26E+4 7.26E+4

1. 71E+l0 1. 06E+9 l.71E+4 6.30E+3 7.63E+2 7.63E+2 7.26E+4 7.26E+4 l.92E+9 3.80E+4 7.20E+6 7.63E+2 7.26E+4 6.60E+8 2.86E+4 8.40E+6 2.51E+7 l.73E+7 2.98E+7 7.00E+7 l.28E+6 2.50E+6 2.57E+7 l.60E+6

4. 72E+6 l.64E+7 6.73E+9 4.66E+8 l.37E+9 4.36E+9 l.45E+9 4.68E+l0 8.60E+3 2.59E+9 9.46E+2 3.03E+2 8.25E+4 4.59E+4 l.02E+3 2.04E+4 5.83E+7 2.57E+7 2.04E+7 l.63E+7 4.58E+7 6.04E+7 2.96E+8 l.64E-l 5.39E+7 4.86E+5 2.28E+5 5.90E+6 l.64E+7 2.25E+7 4.24E+8 4.37E-l 6.24E+4 2.08E+4 4.90E+6 l.17E+7 2.08E+7

1. 3 9E+ll l.53E+l 3.97E+6 6.90E+6 l.01E+9 l.39E+4 5.65E+9 2.61E+8 7.38E+9 2.69E+7 4.84E+3 3.58E+5 1.592+2 9.42E+l 3.63E+4 2.40E+6 l.34E+l0 l.03E+9 l.OlE+lO 3.38E+4 3.27E+3 l.50E+5 6.37E+l l.09E+2 2.92E+9 4.76E+2 4.54E+4 3.89E+3 3.94E+4 l.06E+8 6.63E+7

1. 86E+8 2.52E+8 7.27E+8 6.97E-l l.20E+7 5.83E+4 4.35E+9 5.74E+8 3.43E+9 l.15E+4 l.52E+3 8.87E+4 3.68E+l 6.37E+l 46 9.67E+6 9.95E+6 4.04E+6 l.95E+7 2.33E+8 2.68E+7 3.25E+7 2.13E+6 2.00E+7 l.58E+7 l.44E+9 7.87E+7 l.14E+9 l.93E+4 9.57E+7 3.0BE+B 9.73E+7 2.75E+9 5.llE+B 2.33E+8 l.35E+9 4.73E+6 9.62E+5 2.79E+8 l.19E+5 l.32E+6 2.. 20E+l0 7.31E+8 2.25E+8 6.50E+7 l.54E+8 3.04E+8 l.12E+8 8.22E-2 6.20E+6 4.10E+4 2.35E+8

1. 1 7E+8 l.95E+8 5.54E+7 l.25E+7 l.21E+8 6.96E+5 5.23E+5 l.06E+7 3.62E+7 2.26E+8 l.97E+9 l.21E+9 4.16E+7 l.15E+l0 2.30E+2 2.05E+2 2.47E+4 4.39E+2 2.58E+3 3.20E+7 l.02E+7 4.86E+6 2.18E+6 5.58E+6 9.57E+6 2.43E+B l.53E-l 2.10E+6 l.34E+4 l.lOE+lO 7.42E+8 6.61E+9 l.76E+6 3.71E+2 l.92E+4 7.88E+O 6.52E+O I

I I

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I I

-1 I

I I

I Salem ODCM Rev. 10 I

Table 2-5 (cont* d)

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 I

Nuclide Bone Liver Thyroid Kidney Lung GI-LLI T.Body H-3 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 C-14 6.70E+S l.34E+S l.34E+S l.34E+S l.34E+S l.34E+S l.34E+S I

P-32 3.lSE+lO l.9SE+9 2.6SE+9 l.22E+9 Cr-51 2.78E+4 l.10E+4 7.13E+4 8.40E+6 5.00E+4 Mn-S4 l.40E+7 4.17E+6 2.87E+7 2.78E+6 I

Fe-SS 4.4SE+7 3.16E+7 2.00E+7 l.37E+7 7.36E+6 Fe-S9 S.20E+7 l.21E+8 3.82E+7 2.87E+8 4.68E+7 Co-S7 2.2SE+6 4.19E+7 3.76E+6 I

Co-S8 7.9SE+6 l.10E+8 l.83E+7 Co-60 2.78E+7 3.62E+8 6.26E+7 Ni-63 l.18E+l0 8.3SE+8 1.33E+8 4.01E+8 Zn-65 2.11E+9 7.31E+9 4.68E+9 3.10E+9 3.41E+9 I

Rb-86 4.73E+9 7.00E+8 2.22E+9 Sr-89 2.67E+9 3.18E+8 7.66E+7 Sr-90 6.61E+l0 1.86E+9 l.63E+10 I

Y-91 l.S8E+4 6.48E+6 4.24E+2 Zr-9S 1.6SE+3 S.22E+2 7.67E+2 l.20E+6 3.S9E+2 Nb-9S

1. 41E+S 7.8CE+4 7.S7E+4 3.34E+8 4.30E+4 Ru-103 1.81E+3 6.40E+3 1.S2E+S 7.7SE+2 I

Ru-106 3.7SE+4 7.23E+4 1.80E+6 4.73E+3 Ag-llOrn 9.63E+7 9.11E+7 1.74E+8 2.S6E+10 S.S4E+7 Sb-124 4.59E+7 8.46E+S 1.04E+S 4.01E+7 9.2SE+8 l.79E+7 I

Sb-12S 3.6SE+7 3.99E+S 3.49E+4 3.21E+7 2.84E+8 8.S4E+6 Te-12Srn 3.00E+7 l.08E+7 8.39E+6 8.86E+7 4.02E+6 Te-127m 8.44E+7 2.99E+7 2.01E+7 3.42E+8 2.10E+8 1.00E+7 I

Te-129m l.11E+8 4.10E+7 3.S7E+7 4.62E+8 4.1SE+8 1.7SE+7 I-131 S.38E+8 7.S3E+8

2. 20E+ll 1.30E+9 l.49E+8 4.04E+8 I-132 2.90E-1 7.S9E-1 2.56E+l l.20E+O 3.31E-1 2.72E-1 I

I-133 7.24E+6 l.23E+7 1.72E+9 2.15E+7 9.30E+6 3.7SE+6 I-134 I-13S 2.47E+4 6.3SE+4 4.08E+6 1.00E+S 7.03E+4 2.3SE+4 Cs-134 9.81E+9 2.31E+10 7.34E+9 2.80E+9 2.87E+8 l.07E+l0 I

Cs-136 4.45E+8 1.7SE+9 9.S3E+8 1.SOE+8 1.41E+8 l.18E+9 Cs-137 l.34E+l0 1.78E+10 6.06E+9 2.35E+9 2.S3E+8 6.20E+9 Ba-140 4.85E+7 5.9SE+4 2.02E+4 4.00E+4 7.49E+7 3.13E+6 Ce-141 8.87E+3 5.92E+3 2.79E+3 1.69E+7 6.81E+2 I

Ce-144 6.SBE+S 2.72E+S 1.63E+S 1.66E+8 3.S4E+4 Pr-143 2.92E+2 l.17E+2 6.77E+l 9.61E+S 1.4SE+l Nd-147 l.81E+2 l.97E+2 l.16E+2 7.llE+S l.lBE+l I.

I.

I 47 I

I

Nuclide H-3 C-14 P-32 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Zn-65 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Ru-103 Ru-106 Ag-llOm Sb-124 Sb-125 Te-125m Te-127m Te-129m I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-135 Cs-137 Ba-140 Ce-141 Ce-144 Pr-143 Nd-147 Salem ODCM Rev. 10 Table 2-5 (cont'd}

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 Bone Liver Thyroid Kidney l.57E+3 l.57E+3 l.65E+6 3.29E+5 3.29E+5 7.77E+l0 3.64E+9 5.66E+4 l.57E+3 3.29E+5 l.55E+4 Lung l.57E+3 3.29E+5 l.03E+5 GI-LLI 1.57E+3 3.29E+5 2.15E+9 5.41E+6 T.Body l.57E+3 3.29E+5 3.00E+9 1.02E+5 2.09E+7 l.12E+8 5.93E+7 l.20E+8 1.95E+8 3.84E+6 5.87E+6 1.76E+7 5.58E+6 1.21E+7 4.32E+7 2.96E+10 l.59E+9 4.13E+9 1.lOE+lO 6.62E+9 1.12E+ll 3.91E+4 8.77E+9 3.84E+3 8.45E+2 3.18E+5 1.24E+5 4.29E+3 9.24E+4 6.94E+9 l.21E+3 1.16E+5 l.08E+4

1. 25E+5 2.09E+8 1.09E+8 8.70E+7 7.38E+7 1.41E+8 2.63E+8 2.0BE+B 2.72E+B 1.30E+9 6.86E-l l.41E+8 2.40E+5 1.41E+6 8.06E+4 2.00E+7 2.07E+7 5.60E+7 7.61E+7 1.31E+9 1.26E+O 4.97E+7 8.78E+7 4.34E+ll 5.85E+l l.76E+7 2.1BE+7 4.04E+9 5.84E+4 1.05E+5 2.26E+l0 3.71E+10 1.00E+9 3.22E+l0

1. l 7E+8 2.19E+4 l.62E+6 7.23E+2 4.45E+2 2.76E+9 3.09E+l0 1.03E+5 l.09E+4 5.09E+5 2.17E+2 3.60E+2 9.30E+6 5.93E+B 8.00E+B 2.15E+9 l.93E+O 3.63E+7 l.61E+5 l.lSE+lO

1. 47E+9 1.0lE+lO 3.34E+4 4.78E+3 2.82E+5 l.17E+2 1.98E+2 48 3.35E+7 1.10E+7 1.84E+7 5.65E+7 2.03E+8 9.71E+7 3.14E+7 7.77E+6 7.0BE+7 2.39E+B l.07E+B l.93E+9 5.64E+8 2.56E+B 1.51E+9 5.21E+6 3.72E+7 1.27E+8 1.01E+9 6.85E+9 5.39E+9 1.89E+8 2.83E+l0 l.04E+3 8.81E+5 7.52E+2 2.29E+B 8.84E+4 l.llE+5 l.6SE+3 l.44E+6 1.15E+4 1.68E+10 1.13E+8 6.03E+7 6.79E+B 3.81E+7 4.85E+7 2.08E+B l.82E+7 7.12E+7 9.84E+6 1.68E+B 3.32E+8 1.17E+B l.48E+O

8. 77E+6 8.00E+4 4.13E+9 2.00E+B 2.19E+8 9.70E+7 3.62E+9 1.93E+8 6.12E+4 5.94E+7 l.36E+7 l.33E+B 7.BOE+5 5.71E+5 2.47E+7 4.23E+7 7.46E+8 5.BOE-1 8.23E+6 4.97E+4 7.83E+9 1.79E+9 4.55E+9 6.84E+6 l.62E+3 8.66E+4 3.59E+l 2.79E+l I

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I Salem ODCM Rev. 10 Table 2-5 (cont'd)

R(io), Grass-Cow-Milk Pathway Dose Factors -

INFANT (mrem/yr per uCi/m3) for H-3 and C-14 Nuclide H-3 C-14 P-32 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Zn-65 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Ru-103 Ru-106 Ag-llOm Sb-124 Sb-125 Te-125m Te-127m Te-129m I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 Pr-143 Nd-14 7 (m2

mrem/yr per uCi/sec) for others Bone Liver Thyroid Kidney 2.38E+3 2.38E+3 2.38E+3 3.23E+6 6.89E+5 6.89E+5 6.89E+5 l.60E+ll 9.42E+9 l.35E+8 2.25E+8 3.89E+7 8.72E+7 3.93E+8 8'. 95E+6 2.43E+7 8.81E+7 3.49E+l0 2.16E+9 5.55E+9 l.90E+l0 l.26E+l0 l.22E+ll 7.33E+4 2.22E+l0 6.83E+3 l.66E+3 5.93E+5 2.44E+5 8.69E+3 l.90E+S 3.86E+8 2.09E+8 l.49E+8 l.51E+8 4.21E+8 5.59E+8 2.72E+9 l.42E+O 2.82E+8 3.08E+6 l.45E+6 5.04E+7 l.40E+8 l.92E+8 3.21E+9 2.89E+O l.05E+S 2.30E+4 5.56E+S l.87E+5 5.07E+7 l.22E+8 2.15E+8 l.05E+l2 l.35E+2 8.63E+6 9.23E+9 l.79E+3 l.75E+S l.81E+4 2.25E+5 4.03E+8 l.04E+9 l.40E+9 3.75E+9 3.22E+O Lung GI-LLI 2.38E+3 2.38E+3 6.89E+S 6.89E+S 2.17E+9 2.05E+S 4.71E+6 4.27E+7 l.16E+8 l.31E+8 9.38E+7 l.43E+7 l.11E+7 l.88E+8 3.05E+7 6.0SE+7 2.10E+8 l.07E+8 l.61E+l0 5.69E+8 2.59E+8 l.52E+9 5.26E+6 8.28E+5 2.06E+8 l.06E+S l.44E+6 l.46E+l0 6.46E+8 l.99E+8 7.18E+7 l.70E+8 3.34E+8 l.15E+8 2.34E+O T.Body 2.38E+3 6.89E+5 6.21E+9 l.61E+5 8.83E+6 2.33E+7 l.55E+8 l.46E+7 6.06E+7 2.08E+8 l.21E+9 8.78E+9 l.lOE+lO 3.61E+8 3.lOE+lO l.95E+3 l.18E+3 l.41E+5 2.91E+3 2.38E+4 l.86E+8 6.49E+7 3.07E+7 2.04E+7 5.10E+7 8.62E+7 l.41E+9 l.03E+O 3.72E+7 5.41E+7 9.84E+9 6.36E+7 9.16E+6 l.58E+7 l.OlE-9 l.21E+S 2.41E+S 2.16E+7 2.69E+S 8.74E+4 8.80E+4 3.65E+l0 6.80E+l0 l.75E+l0 7.18E+9 l.85E+8 6.87E+9 l.96E+9 5.77E+9 5.lSE+lO 6.02E+l0 2.41E+8 2.41E+5 4.33E+4 2.64E+4 2.33E+6 9.52E+S l.49E+3 5.59E+2 8.82E+2 9.06E+2 2.30E+9 4.70E+8 l.62E+l0 6.55E+9 5.73E+4 l.48E+5 8.15E+3 3.85E+5 2.08E+2 3.49E+2 49 8.76E+7 l.88E+8 5.92E+7 l.37E+7 l.33E+8 7.89E+S 5.74E+5 2.15E+9 4.27E+9 l.24E+7 3.11E+3 l.30E+5 7.41E+l 5.55E+l

Nuclide H-3 C-14 P-32 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Zn-65 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Ru-103 Ru-106 Ag-llOm Sb-124 Sb-125 Te-125m Te-127m Te-129m I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 Pr-143

?-;d-147 Salem ODCM Rev. 10 Table 2-5 (cont'd)

R(io), Vegetation Pathway Dose Factors -

ADULT (mrem/yr per uCi/m3) for H-3 and C-14 (m2

mrem/yr per uCi/sec) for others Bone 8.97E+5 l.40E+9 2.09E+8 l.27E+8 l.04E+l0 3.17E+8 9.96E+9 6.05E+ll 5.13E+6 l.19E+6 l.42E+5 4.80E+6 1.93E+8 l.06E+7 l.04E+8 l.36E+8 9.66E+7 3.49E+8 2.SSE+8 8.09E+7 5.74E+l Liver Thyroid Kidney 2.26E+3 2.26E+3 2.26E+3 l.79E+5 l.79E+5 l.79E+5 8.73E+7 3.11E+8 l.45E+8 2.99E+8 l.17E+7 3.09E+7 l.67E+8 7.21E+8 l.01E+9 2.19E+8 3.81E+5 7.91E+4 9.76E+6 l.96E+6 l.52E+6 3.SOE+7 l.25E+8 9.50E+7 l.16E+8 l.54E+2 2.79E+4 l.03E+4 2.52E+S l.39E+S 2.90E+7 8.92E+7 8.75E+7 3.79E+l0 5.38E+3 9.27E+7 6.75E+8 S.97E+S 7.81E+4 l.83E+7 3.72E+8 l.92E+7 3.93E+8 l.42E+9 l.06E+9 l.98E+8 2.45E+2 Lung GI-LLI 2.26E+3 2.26E+3 l.79E+S l.79E+5 l.58E+8 6.19E+4 l.17E+7 8.06E+7 8.35E+7 9.54E+8 8.29E+7 9.96E+8 2.97E+8 6.26E+8 3.14E+9 l.SOE+8 6.36E+8 T.Body 2.26E+3 l.79E+S 5.42E+7 4.66E+4 S.94E+7 3.37E+7 l.14E+8 l.95E+7 6.92E+7 3.69E+8 3.49E+8 4.56E+8 4.32E+7 l.02E+8 1.60E+9 2.86E+8 l.75E+l0 l.48E+ll

2. 82E+9

1. 3 7E+S 8.08E+7 l.OSE+8 l.21E+9 4.80E+8 S.61E+8 l.2SE+l0 3.98E+9 2.95E+9 l.SOE+9 3.86E+8 l.17E+9 l.28E+9 3.0SE+7 2.89E+l 2.58E+S 4.25E+4 2.07E+6 2.44E+7 5.80E+6 4.11E+7 3.25E+7 1.29E+7 4.26E+7 4.03E+7 6.63E+7 5.38E+l 2.12E+6 3.69E+6 5.42E+8 6.44E+6 3.31E+6 l.12E+6 l.06E-4 2.88E-4 S.OOE-3 4.59E-4 2.51E-7 l.03E-4 4.08E+4 l.07E+S 7.04E+6 l.71E+S l.21E+S 3.94E+4 4.66E+9 l.llE+lO 3.59E+9 l.19E+9 l.94E+8 9.07E+9 4.20E+7 6.36E+9 l.29E+8 l.96E+S 3.29E+7 6.34E+4 3.34E+4 l.66E+8 8.70E+9 l.62E+S l.33E+S l.38E+7 2.54E+4 3.86E+4 9.24E+7 2.95E+9 5.49E+4 6.17E+4 8.16E+6 l.47E+4 2.25E+4 50 l.27E+7 9.81E+8 9.25E+4 l.89E+7 l.68E+8 2.65E+8 5.08E+8 l.19E+8 5.70E+9 8.43E+6 l.51E+4 l.llE+lO l.77E+6 2.78E+8 3.14E+3 l.85E+8 2.31E+3 I

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Salem ODCM Rev. 10 Table 2-5 (cont'd)

R(io), Vegetation Pathway Dose Factors -

TEENAGER (mrem/yr per uCi/m3) for H-3 and C-14 Nuclide H-3 C-14 P-32 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Zn-65 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Ru-103 Ru-106 Ag-llOm Sb-124 Sb-125 Te-125m Te-127m Te-129m I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 Pr-143 Nd-147 (m2

mrem/yr per uCi/sec) for others Bone Liver Thyroid Kidney 2.59E+3 2.59E+3 2.59E+3 l.45E+6 2.91E+5 2.91E+5 2.91E+5 l.61E+9 9.96E+7 3.44E+4 l.36E+4 4.52E+8 l.35E+8 3.25E+8 2.31E+8 l.81E+8 4.22E+8 l.79E+7 4.38E+7 2.49E+8 l.61E+l0 l.13E+9 4.24E+8 l.47E+9 l.51E+l0 7.51E+ll 7.87E+6 l.74E+6 l.92E+5 6.87E+6 3.09E+8 l.52E+7

1. 55E+8 2.14E+8

1. 48E+8 5.51E+8 3.67E+8 7.70E+7 5.lBE+l l.97E+6 9.59E-5 3.68E+4 7.09E+9 4.29E+7 l.OlE+lO l.3BE+B 2.B2E+5 2.73E+B 5.49E+5 l.06E+S

1. 44E+7 2.85E+6 2.34E+6 5.34E+7 l.96E+8 l.36E+8 l.08E+8 l.36E+2 3.34E+6 2.54E-4 9.48E+4 l.67E+l0

1. 6 9E+8 l.35E+l0 l.69E+S l.BBE+S 5.27E+7 2.18E+7 7.12E+4 2.84E+4 3.63E+4 3.94E+4 3.51E+5 2.04E+S 4.14E+7 l.31E+8 l.18E+8 3.14E+l0 4.57E+3 4.66E+B 4.24E-3 6.10E+6 9.41E+8 8.07E+S l.03E+5 2.42E+7 5.97E+8 2.74E+7 2.24E+9 l.54E+9 l.85E+8 2.14E+2 5.86E+6 4.0lE-4 l.50E+S 5.30E+9 9.19E+7 4.59E+9 5.75E+4 8.86E+4 l.30E+7

1. 6 5E+4

2. 32E+4 51 Lung GI-LLI 2.59E+3 2.59E+3 2.91E+S 2.91E+S l.35E+8 B.85E+4 l.04E+7 9.27E+8 l.46E+8 9.98E+7 l.33E+8 9.98E+8 3.34E+8 T.Body 2.59E+3 2.91E+5 6.23E+7 6.20E+4 8.97E+7 5.38E+7 l.63E+8 3.00E+7 6.04E+8 l.OlE+B 3.24E+9 5.60E+8 l.81E+8 5.45E+8 6.23E+8 6.86E+8 l.35E+8 l.88E+8 2.02E+9

1. 45E+7 l.78E+9 l.14E+5 4.05E+7 l.80E+9 2.llE+lO 3.23E+9 l.27E+9 4.SSE+8 5.74E+8

1. 48E+l0 4.04E+9 3.11E+9 l.66E+9 4.37E+8

1. 37E+9 l.3BE+9 2.13E+7 5.91E+l 2.53E+6

..,,3SE-6 l.OSE+S 2.08E+8 l.36E+7 l.92E+8 2.13E+8 S.38E+8 l.33E+l0 2.34E+8 l.42E+8 l.28E+8 4.33E+8 l.85E+ll 2.llE+S 3.78E+S 5.86E+4 2.94E+6 3.90E+7 8.74E+6 6.03E+7 5.00E+7 l.98E+7 6.56E+7 5.81E+7 5.79E+7 4.87E+l l.02E+6 9.13E-5 3.52E+4 7.74E+9 l.13E+8 4.69E+9 8.91E+6 2.16E+4 2.B3E+6 3.SSE+3 2.36E+3

Nuclide H-3 C-14 P-32 Cr-51 Mn-54 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Zn-65 Rb-86 Sr-89 Sr-90 Y-91 Zr-95 Nb-95 Ru-103 Ru-106 Ag-llOm Sb-124 Sb-125 Te-125m Te-127m Te-129m I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 Pr-143 Nd-147 Salem ODCM Rev. 10 Table 2-5 (cont'd)

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 Bone 3.SOE+6 3.37E+9 Liver 4.01E+3 7.01E+5 l.58E+8 6.61E+8 8.00E+8 4.24E+8 4.01E+8 6.49E+8 2.99E+7 6.47E+7 3.78E+8 3.95E+l0 2.11E+9 8.12E+8 2.16E+9 3.59E+l0 l.24E+l2 l.87E+7 4.52E+8 3.90E+6 8.58E+5 4.10E+5 l.59E+5 l.55E+7 7.45E+8 3.22E+7 3.52E+8 4.99E+8 3.51E+8 l.32E+9 8.54E+8 l.43E+8 9.20E+l 2.17E+7 4.57E+6 3.85E+6 9.50E+7 3.56E+8 2.39E+8 l.44E+8 l.69E+2 Thyroid 4.01E+3 7.01E+5 6.54E+4 7.78E+5 4.62E+5 9.84E+7 3.16E+8 2.75E+8 4.76E+l0 7.84E+3 Kidney 4.01E+3 7.01E+5 l.79E+4 Lung GI-LLI 4.01E+3 4.01E+3 7.01E+5 7.01E+5 9.30E+7 l.19E+5

~.25E+6 l.85E+8 5.55E+8 l.36E+9 l.23E+6 l.50E+5 3.89E+7 l.01E+9 4.05E+7 3.77E+9 2.51E+9 2.36E+8 2.59E+2 2.40E+8 7.86E+7 l.88E+8 6.76E+8 2.45E+8 l.96E+8 2.78E+8 3.77E+8 2.10E+9

1. 42E+8 3.80E+8 2.91E+7 l.39E+9

1. 67E+l0 2.49E+9 8.95E+8 2.95E+8 3.99E+8 l.16E+l0 2.58E+9 2.20E+9 l.19E+9 3.38E+8 l.07E+9 l.04E+9 l.28E+7 l.99E+2 T.Body 4.01E+3 7.01E+5 l.30E+8 l.18E+5 l.76E+8 l.31E+8 3.23E+8 6.04E+7 l.98E+8 l.12E+9 l.34E+9 l.35E+9 2.78E+8 l.03E+9 3.15E+ll 5.01E+5 7.64E+5 l.14E+5 5.94E+6 9.30E+7 l.74E+7 l.23E+8 l.05E+8 4.67E+7 l.57E+8 l.33E+8 8.18E+7 7.77E+l 3.59E+6 4.44E+6 8.25E+8 7.40E+6 l.79E+6 l.68E+6 l.70E-4 3.16E-4 7.28E-3 4.84E-4 2.lOE-4 l.46E-4 6.54E+4 l.18E+5 l.04E+7 l.81E+5 8.98E+4 5.57E+4 l.60E+l0 2.63E+l0 8.14E+9 2.92E+9 l.42E+8 5.54E+9 8.06E+7 2.39E+l0 2.77E+8 6.53E+S 1.27!:'+8 l.48E+S 7.16E+4 2.22E+8 2.29E+l0 2.43E+5 3.26E+5 3.98E+7 4.46E+4 5.80E+4 l.18E+8 7.46E+9 7.90E+4 l.43E+5 2.21E+7 2.41E+4 3.18E+4 52 l.76E+7 2.68E+9 l.45E+5 7.79E+6 l.43E+8 l.40E+8 4.07E+8 l.43E+8 3.38E+9 l.62E+7 4.84E+4 l.04E+l0 6.78E+6 l.60E+8 7.37E+3 9.18E+7 4.49E+3 I

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I Salem ODCM Rev. 10 Table 2-5 (cont'd)

R(io), Ground Plane Pathway Dose Factors (m2

mrem/yr per uCi/sec)

Nuclide H-3 C-14 P-32 Cr-51 Mn-54 Fe-55 Fe-59 Co-58 Co-60 Ni-63 Zn-65 Rb-86 sr-89 sr-90 Y-91 Zr-95 Nb-95 Ru-103 Ru-106 Ag-llOm Te-125m Te-127m Te-129m I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 Pr-143 Nd-147 53 Any Organ 4.68E+6 1.34E+9 2.75E+8 3.82E+8 2.16E+l0 7.45E+8 8.98E+6 2.16E+4 1.08E+6 2.48E+8 1.36E+8 1.09E+8 4.21E+8 3.47E+9 1.55E+6 9.17E+4 2.00E+7 1.72E+7 l.24E+6 2.47E+6 4.49E+5 2.56E+6 6.75E+9 l.49E+8 l.04E+l0 2.05E+7 l.36E+7 6.95E+7 8.40E+6

Salem ODCM Rev. 10 APPENDIX A Evaluation of Default Parameters for Liquid Effluents I

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I Salem ODCM Rev. 10 Appendix A Evaluation of Default Parameters for Liquid Effluents A. Effective Maximum Permissible Concentration (MPC.)

In accordance with the requirements of Technical Specification (3.3.3.8) the radioa~tive liquid effluent monitors shall be operable with alarm setpoints established to ensure that the concentration of radioactive material at the discharge point does not exceed the MPC value of 10 CFR 20, Appendix B, Table II, Column 2.

The determination of allowable radionuclide concentration and corresponding alarm setpoint is a function of the individual radionuclide distribution and corresponding MPC values.

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 of the liquid effluents from Salem and the effective MPC value for this distribution.

The effective MPC value for a radionuclide distribution is calculated by the equation:

MPC. =

where:

=

(A. l)

I: -----------

an effective MPC value for a mixture of radionuclide (uCi/ml) concentration of radionuclide i in the mixture the 10 CFR 20, Appendix B, Table II, Column 2 MPC value for radionuclide i (uCi/ml)

The equation for determining the liquid effluent setpoints ( Section 1.2.1, equation 1.2 ) is based on a multiplication of the effective MPC times the monitor sensitivity. Considering the average effective MPC value for the years 1992 through 1994, it is reasonable to select an MPCe value of 6.0SE-06 uCi/rnl for Unit 1 and 4.BlE-06 uci/rnl for Unit 2 as typical of liquid radwaste discharges.

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Salem ODCM Rev. 10 B. Safety Factor The type of Yadiation detector used to monitor radioactive releases is not capable of detecting non-gamma emitting radionulcides such as H-3, Fe-55, and Sr-89,90, as required by Technical Specification 3.11.1.1.

A conservative default safety factor can be determined to account for non-gamma emitting radionuclides. Non-gamma emitting radionulcides are analyzed at Salem station on a monthly basis from a composite sample of liquid releases.

Nuclide MPC (uci/ml}

Activity Activity I MPC (uci/ml}

H-3 3E-3 5.2E-l 173.3 Fe-55 8E-4 2.SE-3 3.1 Sr-89 3E-6 2.0E-5 6.7 Sr-90 3E-7 7.2E-7 2.4 Total 185.5 I

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I The values in the table above represent the maximum reactor coolant I

values for non-gamma emitting nuclides in 1994 for Unit 1 and 2.

Reactor coolant values were chosen to represent the maximum concentration of non-gamma emitting nuclides that could be released I

from Salem Station. The activity values in the table will be diluted by a minimum factor of 800 prior to release. The minimum dilution factor is obtained by using the minimum circulating water flowrate of I

100,000 gpm and the maximum release rate of 120 gpm.

A conservative safety factor for non-gamma emitting nuclides can be obtain~d using the highest Activity/MPC fraction and the minimum I

dilution factor as follows:

Safety Factor =

185.5 I 800 0.23 (Rounded up to 0.25)

B. Default setpoint determination:

Using the information and parameters described above a default setpoint can be calculated for Unit 1 and 2 liquid radwaste disposal process radiation monitors (Rl8).

Using these values to calculate the default Rl8 alarm setpoint value, 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

2) Will provide for a liquid radwaste discharge rate (as evaluated for each batch release) that is compatible with plant operations (refer to ~ables 1-1 and 1-2).

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I Nuclide Be-7 Na-24 Cr-51 Mn-54 Fe-59 Co-57 Co-58 Co-60 Zr-95 Nb-95 Nb-97 Tc-99m Sr-92 Mo-99 Ag-llOm Sn-113 Sb-122 Sb-124 Sb-125 Sb-126 I-131 I-133 I-134 Ce-141 Ce-143 Cs-134 Cs-136 Cs-137 Cs-138 Ba-140 La-140 Ru-105 Ru-106 Zn-65 Total C; MPC' (uCi/ml) 2E-03 3E-05 2E-03 lE-04 5E-05 4E-04 9E-05 3E-05 6E-05 lE-04 9E-04 3E-03 6E-05 4E-05 3E-05 8E-05 3E-05 2E-05 lE-04 3E-06 3E-07 lE-06 2E-05 9E-05 4E-05 9E-06 6E-05 2E-05 3E-06 2E-05 2E-05 lE-04 lE-05 lE-04 Gamma MPC 0 (uCi/ml)

Salem ODCM Rev. 10 Table A-1 Calculation of Effective MPC Salem Unit 1 Activity Released (Ci) 1992 CURIES 8.74E-05 3.99E-04 4.30E-03 7.24E-02 1.20E-04 l.26E-02 2.33E+OO 2.52E-01 2.90E-03 6.37E-03 3.99E-04 8.23E-05 N/D N/D 8.38E-03 3.91E-04 8.54E-05 1.37E-02 7.27E-02 N/D 3.06E-02 l.75E-03 N/D 3.69E-05 N/D l.64E-01 l.20E-03 l.86E-01 N/D N/D 6.26E-05 4.SSE-04 N/D 8.75E-04 3.16E+OO l.88E-05 1993 CURIES B.88E-04 6.68E-04 5.38E-03 3.52E-02 4.76E-04

1. 03E- 02

1. 71E+OO 3.04E-Ol 3.29E-03 5.78E-03 1.27E-03 2.66E-04 N/D

1. 76E- 04 l.19E- 02 7.SBE-05

1. 21E-03 2.08E-02 9.04E-02 N/D

1. 27E-01 2.16E-03 N/D N/D S.42E-05 3.54E-01 3.61E-03 4.53E-01 4.15E-06 N/D 2.12E-04 2.21E-04 N/D

6. 72E-04 3.14E+OO 6.0SE-06 1994 CURIES N/D l.62E-04 2.02E-03

1. 37E-02 4.84E-03 3.lOE-03 6.47E-01 l.lOE-01 7.13E-04 l.28E-03 l.07E-03 N/D 7.32E-06

1. 76E-04

l. lOE-02 4.91E-05 5.35E-04 l.75E-02 8.23E-02 6.1e:E-05 l.82E-02 1.88E-04 3.63E-04 4.24E-05 N/D 6.46E-01 l.59E-03 8.54E-01 l.35E-04 8.62E-05 l.86E-04 l.35E-04

1. 03E-03 N/D 2.42E+OO l.28E-05 MPC value for unrestricted area from 10 CFR 20, Appendix B, Table II, Column 2.

N/D - not detected A-3

Nuclide MPC" (uCi/ml)

Be-7 2E-03 Na-24 3E-05 Cr-51 2E-03 Mn-54 lE-04 Fe-59 SE-05 Co-57 4E-04 Co-58 9E-05 Co-60 3E-05 Zr-95 6E-05 Nb-95 lE-04 Nb-97 9E-04 Tc-99m 3E-03 Mo-99 4E-05 Ag-llOm 3E-05 Sn-113 SE-OS Sb-122 3E-05 Sb-124 2E-05 Sb-125 lE-04 Sb-126 3E-06 I-131 3E-07 I-132 SE-06 I-133 lE-06 Ce-141 9E-05 Ce-143 4E-05 Cs-134 9E-06 Cs-136 6E-05 Cs-137 2E-05 Cs-138 3E-06 Ru-106 lE-05 Ru-105 lE-04 La-140 2E-OS W-187 6E-05 Zn-65 lE-04 Sr-92 6E-05 Total C; Gamma MPC. (uCi/ml)

Salem ODCM Rev. 10 Table A-2 Calculation of Effective MPC Salem Unit: 2 Activity Released (Ci) 1992 1993 1994 CURIES CURIES CURIES 2.20E-04 l.59E-03 2.88E-04 7.33E-04 l.OSE-03 S.77E-OS 4.13E- 03 4.39E-03 l.SSE-03 9.lSE-02 3.73E-02 1.37E-02 l.61E-04 4.83E-04 3.25E-03

1. 42E-02 l.17E-02 3.24E-03 2.57E+OO l.7SE+OO 6.60E-Ol 2.61E-Ol 3.47E-01 l.03E-Ol 2.06E-03 2.34E-03 3.22E-04 S.3SE-03 3.97E-03

l. llE-03 9.37E-04 1.46E-03

l. lOE-03 2.75E-04 3.77E-04 N/D 2.28E-04 N/D N/D 6.07E-03 l.03E-02

1. 34E- 02 8.51E-05 7.4SE-05 N/D l.12E-04 1.20E-03 N/D

1. 20E-02 3.77E-02 9.82E-03 8.29E-02 1.3SE-Ol 6.03E-02

1. 83E-05 3.SlE-04 N/D 4.35E-02 l.87E-01 7.98E-03 N/D 8.72E-05 N/D 2.16E-03 2.39E-03 1.BSE-04 N/D N/D 2.87E-05 2.44E-04 N/D N/D 2.32E-Ol 4.57E-Ol 6.44E-01 l.82E-03 4.82E-03

1. SlE- 03 2.34E-01 S.70E-Ol 8.54E-01 4.73E-05 N/D N/D N/D N/D 4.38E-04 2.78E-04 4.07E-05 N/D 6.SlE-05 2.03E-03 l.llE-04 N/D N/D 7.98E-05 l.38E-03 1.59E-04 N/D N/D N/D l.43E-05 3.57E+OO 3.57E+OO 2.38E+OO 1.59E-05 4.81E-06 l.55E-05

~PC value for unrestricted area from 10 CFR 20, Appendix B, Table II, Column N/D - -not detected A-4 I

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Salem ODCM Rev. 10 APPENDIX B Technical Basis for Effective Dose Factors -

Liquid Effluent Releases The radioactive liquid effluents for the years 1992 through 1994 were evaluated to determine the dose contribution of the radionuclide distribution.

This analysis was performed to 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 radionuclide distribution of effluents from Salem, the controlling organ is the GI-LLI.

For the last three years the calculated GI-LLI dose is predominately a function of the Fe-55, Co-58, Co-60, Fe-59 and Ag-llOm releases. The radionuclides, Cs-134 and Cs-137 contribute the large majority of the calculated total body dose.

The results of the evaluation for 1992, 1993, and 1994 are presented in Table B-1 and Table B-2.

For purposes of simplifying the details of the dose calculational 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 Nb-95 dose conversion factor (1.51 E+06 mrem/hr per uCi/ml, GI-LLI).

By this approach, the maximum organ dose will be overestimated since this nuclide has the highest organ dose factor of all the radionuclides evaluated.

For the total body calculation, the Fe-59 dose factor (2.32 E+OS 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:

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Salem ODCM Rev. 10 Total Body 1.67E-02

VOL D~ = --------------

A Fe-59,TB

E C1 cw (B.1) where:

Deb A Fe-59,TB VOL Ci

=

cw 1.67E-02 dose to the total body (mrem) 7.27E+04, total body ingestion dose conversion factor for Fe-59 (mrem/hr per uCi/ml) volume of liquid effluent released (gal) total concentration of all radionuclides (uCi/ml) average circulating water discharge rate during release period(gal/min) conversion factor (hr/min)

Substituting the value for the Fe-59 total body dose conversion factor, the equation simplifies to:

1.21E+03

VOL D~ =

(B. 2) cw Maximum Organ 1.67E-02

VOL

A Nb-95,GI-LLI Dm.x

= ---------------------------

(B. 3) where:

Dmax A Nb-95,GI-LLI cw maximum organ dose (mrem) 1.51E+06, Gi-LLI ingestion dose conversion factor for Nb-95 (mrem/hr per uCi/ml)

Substituting the value for A Nb-95,GI-LLI the equation simplifies to:

2.52E+04 *VOL Dmax =

(B.4) cw Tritium is not included in the limited analysis dose assessment for liquid releases, because the potential dose resulting from normal reactor releases is relatively negligible.

The average annual tritium release from each Salem Unit is approximately 350 curies.

The calculated total body dose from such a release is 2.4E-03 mrem/yr via the fish and invertebrate ingestion pathways.

This amounts to O.OS% of the design objective dose of 3 mrem/yr.

Furthermore, the release of tritium is a function of operating time and power level and is essentially unrelated to radwaste system operation.

B-2

Salem ODCM Rev. 10 Nuclide Mn-54 Fe-55 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Ag-llOm Cs-134 Cs-137 Total Nuclide Mn-54 Fe-55 Fe-59 Co-58 Co-60 Zn-65 Nb-95 Ag-llOm Cs-134 Cs-137 Total Table B-1 Adult Dose Contributions Fish and Invertebrate Pathways Unit 1 Release (Ci)

T.Body Dose Fraction Gl-LLI Dose Fraction 1994 1993 1992 1994 1993 1992 1994 1993 l.32E-2 3.51E-2 7.23E-2 0.01 0.01 0.03 l.49E-1 6.40E-2 l. IOE-1 O.Q7 0.06 0.11 0.11 0.03 4.84E-3 4.77E-4 NID 0.02 0.12 0.01 6.47E-1 1.71E+O 2.33E+O 0.05 0.19 0.34 0.27 0.42 1.IOE-1 3.04E-1 2.51E-l 0.02 0.09 0.11 0.12 0.19 O.OOE+O 6.72E-4 8.75E-4 0.01 0.02 1.28E-3 5. 78E-3 6.37E-3 0.07 0.17 l.lOE-2 1.l 9E-2 8.35E-3 0.26 0.15 6.46E-1 3.S4E-1 l.64E-1 0.47 0.35 0.24 8.54E-l 4.53E-l 1.86E-1 0.36 0.27 0.16 2.44E+O 2.94E+O 3.13E+O Table B-2 Adult Dose Contributions Fish and Invertebrate Pathways Unit 2 1992 0.01 O.Q3 0.50 0.15 0.01 0.17 0.09 Release (Ci)

T.Body Dose Fraction GI-LLI Dose Fraction 1994 1993 1992 1994 1993 1992 1994 1993 1992 1.37E-2 3.73E-2 8.92E-2 0.01 0.01 0.01 0.03 l.38E-1 6.61E-2 6.14E-2 0.06 0.04 o.os 0.10 0.03 0.02 3.25E-3 4.82E-4 N/D 0.01 0.08 0.01 6.60E-l 1.75E+O 2.47E+O 0.05 0.16 0.35 0.29 0.42 0.57 l.03E-l 3.47E-l 2.58E-1 0.02 0.09 0.10 0.12 0.22 0.15 0.00E+O l.59E-4 l.38E-3 0.04 0.01 l.l IE-3 3.97E-3 5.35E-3 0.06 0.13 0.14 l.34E-2 l.03E-2 6.12E-3 0.31 0.15 0.06 6.44E-l 4.58E-l 2.31E-l 0.47 0.40 0.28 0.01 8.54E-l 4.53E-l 1.86E-l 0.36 0.27 0.16 2.44E+O 2.94E+O 3.13E+O

Less than 0.01 N/D = Not Detected B-3 Liver Dose Fraction

1994 1993 1992 O.Q2 0.04 0.20 0.19 0.35 0.04 0.01 0.01 O.D7 0.12 0.01 0.03 0.04 0.02 0.04 0.37 0.34 0.22 0.36 0.32 0.18 Liver Dose Fraction 1994 1993 1992 0.01 0.05 0.18 0.14 0.18 0.02 0.01 0.01 0.06 0.13 0.01 O.Q3 0.04 0.01 0.07 0.39 0.38 0.30 0.36 0.32 0.18

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I Salem ODCM Rev. 10 APPENDIX C Technical Bases for Effective Dose Factors Gaseous Radioactive Effluent

Salem ODCM 2ev. 10 APPENDIX C Technical Bases 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 can be based on typical radionuclide distributions of releases, can be applied to the total radioactivity released to approximate the dose in the environment {i.e., instead of having to perform individual radionuclide dose analyses only a single multiplication {Keff' Meff or Neff) times the total quantity of radioactive material released would be needed).

This approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calculational technique.

Determination of Effective Dose Factors Effective dose transfer factors are calculated by the following equations:

where:

(C.1) the effective total body dose factor due to gamma emissions from all noble gases released the total body dose factor due to gamma emissions from each noble gas radionuclide i released the fractional abundance of noble gas radionuclide i relative to the total noble gas activity (C. 2)

{L + 1.1 M) ett the effective skin dose factor due to b~ta and gamma emissions from all noble gases released (L 1 + 1. 1 M;}

the skin dose factor due to beta and gamma emissions from each noble gas radionuclide i released C-1 I

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where:

Salem ODCM

~ev. 10 the effective air dose factor due to gamma emissions from all noble gases released the air dose factor due to gamma emissions from each noble gas radionuclide i released

( c. 3)

(C. 4) the effective air dose factor due to beta emissions from all noble gases released 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 of the effective dose factors.

However, the noble gas releases from Salem have been maintained to such negligible quantities that the inherent variability in the data makes any meaningful evaluations difficult.

For the past years, the total noble gas releases have been limited to 950 Ci for 1992, 1000 Ci for 1993, and 950 Ci for 1994.

Therefore, in order to provide a reasonable basis for the derivation of the effective noble gas dose factors, the primary coolant source term from ANSI N237-1976/ANS-18.l, "Source Term Specifications," has been used as representing a typical distribution.

The effective dose factors as derived are presented in Table C-1.

Application To provide an additional degree of conservatism, a factor of 0.50 is introduced into the dose calculational process when the effective dose transfer factor is used.

This conservatism provides additional assurance that the evaluation of doses by the use of a single effective factor will not significantly underestimate any actual doses in the environment.

For evaluating compliance with the dose limits of Technical Specification 3.11.2.2, the following simplified equations may be used:

3.17E-08

= --------

X/Q Me ff r: Qi (C. 5) 0.50 and 3.17E-08 X/Q N.,ff r: Qi (C. 6) 0.50 C-2

where:

X/Q 3.17E-08 0.50 Salem ODCM Rev. 10 air dose due to gamma emissions for the cumulative release of all noble gases (mrad) air dose due to beta emissions for the cumulative release of all noble gases (mrad)

= atmospheric dispersion to the controlling site boundary (sec/m3) 5.3E+02, effective gamma-air dose factor (mrad/yr per uCi/m3) l.1E+03, effective beta-air dose factor (mrad/yr per uCi/m3)

= cumulative release for all noble gas radionuclides (uCi)

= conversion factor (yr/sec)

= conservatism factor to account for the variability in the effluent data Combining the constants, the dose calculational equations simplify to:

= 3.5E-05 X/Q E Q1 (C. 7) and

= 7.0E-05 X/Q (C. 8)

The effective dose factors are used on a very limited basis for purpose of facilitating the timely assessment of radioactive effluent releases, particularly during periods of computer malfunction where a detailed dose assessment may be unavailable.

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I Salem ODCM Rev. 10 Table c-1 Effective Dose Factors Noble Gases - Total Body and Skin Radionuclide Kr-85 Kr-88 Xe-133m Xe-133 Xe-135 Total Noble Gases - Air Radionuclide Kr-BS Kr-88 Xe-133m Xe-133 Xe-135 Total f

l 0.01 0.01 0.01 0.95 0.02 0.01 0.01 0.01 0.95 0.02 Total Body Effective Dose Factor K.rr (mrem/yr per uCi/m3 )

l.5E+02 2.5E+OO 2.BE+02 3.6E+Ol 4.7E+02 Gamma Air Effective Dose Factor M.cc (mrad/yr per uCi/m3 )

l.SE+02 3.3E+OO 3.4E+02 3.SE+Ol 5.3E+02 Skin Effective Dose Factor (L+ 1.1 M).it (mrem/yr per uCi/m3 )

1. 4E+Ol l.9E+02 l.4E+Ol 6.6E+02 7.9E+Ol 9.6E+02 Beta Air Effective Dose Factor N.cc (mrad/yr per uCi/m3 )

2.0E+Ol 2.9E+Ol 1.SE+Ol 1.0E+03 4.9E+Ol 1.1E+03 Based on Noble gas distribution from ANSI N237-1976/ANSI-18.l, "Source Term Specifications."

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Salem ODCM Rev. 10 I

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I APPENDIX D I

I Technical Basis for Effective Dose Parameter Gaseous Radioactive Effluent I

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Salem ODCM Rev. 10 APPENDIX D Technical Basis for Effective Dose Parameter Gaseous Radioactive Effluent Releases T~e pathway dose factors for the controlling infant age group were evaluated to determine the controlling pathway, organ and radionuclide.

This analysis was performed to provide a simplified method for determining compliance with Technical Specification 3.11.2.3 For the infant age group, the controlling pathway is the grass-cow-milk (g/c/m) pathway. An infant receives a greater radiation dose from the g/c/m pathway than any other pathway. Of this g/c/m pathway, the maximum exposed organ including the total body, is the thyroid, and the highest dose contributor is radionuclide I-131.

The results for this evaluation are presented in Table D-1.

For purposes of simplifying the details of the dose calculation process, it is conservative to identify a controlling, dose signi:icant organ and radionuclide and limit the calculation process to the use of the dose conversion factor for the organ and radionuclide. 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 dose commitment via a controlling pathway and age group, it is conservative to use the infant, g/c/m, thyroid, I-131 pathway dose factor (l.05El2 m2 mrem/yr per uCi/sec).

By this approach, the maximum dose commitment will be overestimated since I-131 has the highest pathway dose factor of all radionuclides evaluated.

For evaluating compliance with the dose limits of Technical Specification 3.11.2.3, the following simplified equation may be used:

where:

X/Q D/Q 3.17E-8 RI -131 Dmax

= 3.17E-8

W

RI-131

B Qi maximum organ dose (mrem) atmospheric dispersion parameters to the controlling location(s) as identified in Table 3.2-4.

atmospheric dispersion for inhalation pathway and H-3 dose contribution via other pathways (sec/m3 )

atmospheric deposition for vegetation, milk and ground plane exposure pathways (m-2 )

cumulative release over the period of interest for radioiodines and particulates conversion factor (yr/sec)

I-131 dose parameter for the thyroid for the identified controlling pathway l.05El2 (m2 mrem/yr per uCi/sec), infant thyroid dose parameter with the grass-cow-milk pathway controlling D-1

Salem ODCM Rev. 10 The ground plane exposure and inhalation pathways n~ed not be considered when the above simplified calculation method is used because for the overall negligible contribution of these pathways to the total thyroid dose.

It is recognized that for some particulate radionuclides (e.g.,

Co-60 and Cs-137), the ground exposure pathway may represent a higher dose contribution than either the vegetation or milk pathway. However, use of the I-131 thyroid dose parameter for all radionuclides will maximize the organ dose calculation, especially considering that no other radionuclide has a higher dose parameter for any organ via any pathway than I-131 for the thyroid via the milk pathway (see Table D-1).

The location of exposure pathways and the maximum organ calculation may be based on the available pathways in the surrounding environment of Salem as identified by the annual land-use census (Technical Specification 3.12.2).

Otherwise, the dose will be evaluated based on the predetermined controlling pathways as identified in Table 2-4.

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I Target Organs Total Body Liver Thyroid Kidney Lung GI-LLI Salem ODCM

~ev. 10 Table D-1 Infant Dose Contributions Fraction of Total Organ and Body Dose PATHWAYS Grass-Cow-Milk 0.02 0.23 0.59 0.02 0.01 0.02 Ground Plane 0.15 0.14 0.15 0.15 0.02 0.15 Fraction of Dose Contribution by Pathway Pathway i

Grass-Cow-Milk 0.92 Ground Plane -

0.08 Inhalation D-3

Salem ODCM Rev. 10 APPENDIX E Radiological Environmental Monitoring Program Sample Type, Location and Analysis I

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I Salem ODCM Rev. 10 APPENDIX E SAMPLE DESIGNATION Samples are identified by a three part code.

The first two letters are the power station identification code, in this case "SA.

The next three letters are for the media sampled.

AIO =

Air Iodine 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 = Surf ace Water WWA =

Well Water The,last four symbols are a location code based on direction and disfance 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 =.1-2 miles off-site G

10-20 miles off-site c = 2-3 miles off-site H

> 20 miles off-site D

3-4 miles off-site The last number is the station numerical designation within each sector and zone; e.g., 1,2,3,...

For example; the designation SA-WWA-5Dl would indicate a sample in the SGS program (SA),

consisting of well water (WWA), which had been collected in sector number 5, centered at 90' (due east) with respect to the reactor site at a radical distance of 3 to 4 miles off-site, (therefore, radial distance D).

The number 1 indicated that this is sampling station #1 in that particular sector.

E-1

Salem ODCM 2ev. 10 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.

A. Direct Radiation STATION CODE

lSl

2S2

2S4

3Sl

4Sl 5Sl

6S2 7Sl

- lOSl

- llSl

15Sl

16Sl 4D2 5Dl lODl 14Dl 15Dl 2El 3El 9El 11E2 12El 13El 16El lFl 2F2 2F5 2F6 3F2 3F3 4F2 5Fl 6Fl 7F2 10F2 llFl 12Fl 13F2 13F3 13F4 14F2 15F3 16F2 TABLE E-1 Monitoring Locations (IDM)

STATION LOCATION 0.55 mi. N of vent 0.4 mi. NNE of vent 0.59 mi. NNE of vent 0.58 mi. NE of vent 0.60 mi ENE of vent 1.0 mi. E of vent; site access road 0.21 mi. ESE of vent; observation building 0.12 mi. SE of vent; station personnel gate 0.14 mi. SSW of vent; circ water bldg.

0.09 mi. SW of vent; service water bldg.

0.57 mi. NW of vent 0.54 mi. NNW of vent 3.7 mi. ENE of vent; Alloway Creek Neck Road 3.5 mi. E of vent; local farm 3.9 mi. SSW of vent; Taylor's Bridge Spur 3.4 mi. WNW of vent; Bay View, Delaware 3.8 mi. NW of vent; Rt 9 I Augustine Beach, DE.

4.4 mi. NNE of vent; local farm 4.1 mi. NE of vent; local farm 4.2 mi. s of vent 5.0 mi. SW of vent 4.4 mi. WSW of vent; Thomas Landing 4.2 mi. W of vent; Diehl House Lab 4.1 mi. NNW of vent; Port Penn 5.8 mi. N of vent; Fort Elf sborg 8.7 mi. NNE of vent; Salem Substation 7.4 mi. NNE of vent; Salem High School 7.3 mi. NNE of vent; PSE&G Training Center 5.1 mi. NE of vent; Hancocks Bridge Munc. Bldg 8.6 mi. NE of vent; Quinton Township School 6.0 mi. ENE of vent; Mays Lane, Harmersville 6.5 mi. E of vent; Canton 6.4 mi. ESE of vent; Stow Neck Road 9.1 mi. SE of vent; Bayside, NJ 5.8 mi. SSW of vent; Rt. 9 6.2 mi. SW of vent; Taylors Bridge, DE.

9.4 mi. WSW of vent; Townsend Elementary School 6.5 mi. w of vent; Odessa, DE.

9.3 mi. w of vent; Redding Middle School 9.8 mi. w of vent; Middletown, DE.

6.6 mi. WNW of vent; Boyds Corner 5.4 mi. NW of vent 8.1 mi. NNW of vent; Delaware City Public School E-2 I

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I Salem ODCM Rev. 10 TABLE E-1 (Cont'd)

A. Direct Radiation Monitoring Locations (IDM)

(Cont'd)

STATION CODE STATION LOCATION 1G3 3Gl lOGl 16Gl 19 mi. N of vent; N. Church St. Wilmington, DE 17 mi. NE of vent; local farm 3Hl 3H3 12 mi. SSW of vent; Smyrna, Delaware 15 mi. NNW of vent; Wilmington Airport 32 mi. NE of vent; National Park, NJ 110 mi. NE of vent; Maplewood R&TL

TLD's will be placed at these locations starting 1/1/96.

- TLD locations will be maintained by site area monitoring program B. Air Sampling Locations (AIO,APT)

STATION CODE STATION LOCATION 5Sl

1. 0 mi. E of vent; site access road 5Dl 3.5 mi. E of vent; local farm 16El 4.1 mi. NNW of vent; Port Penn lFl 5.8 mi. N of vent; Fort Elfsborg 2F6 7.3 mi. NNE of vent; PSE&G Training Center 3H3 110 mi. NE of vent; Maplewood R&TL C. Surface Water Locations (SWA)

- Delaware River STATION CODE STATION LOCATION llAl 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 16Fl 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 Salem Generating Station.

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 Salem Generating Station.

E-3

Salem ODCM Rev. 10 Table E-1 (Cont'd)

F. Water Sediment Locations (ESS)

STATION CODE llAl 15Al 16Al 12Cl 7El 16Fl STATION LOCATION 0.2 mi. SW of vent; Salem outfall area 0.3 mi. NW of vent; Hope Creek outfall area 0.7 mi. NNW of vent; South Storm Drain outfall 2.5 mi. WSW of vent; West bank of Delaware river 4.5 mi. SE of vent; 1 mi West of Mad Horse River 6.9 mi. NNW of vent; C&D Canal G. Milk Sampling Locations (MLK)

STATION CODE 2F7 11F3 14F4 3Gl STATION LOCATION 5.7 mi. NNE of vent; local farm 5.3 mi. SW of vent; Townsend DE.

7.6 mi. WNW of vent; local farm 17 mi. NE of vent; local farm H. Fish and Invertebrate Locations (ESF,ECH)

STATION CODE llAl 12Cl 7El STATION LOCATION 0.2 mi. SW of vent; Salem outfall area 2.5 mi. WSW of vent; West bank of Delaware River 4.5 mi. SE of vent; 1 mi West of Mad Horse Creek I. 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.

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I Salem O~CM Rev. lO SAMPLES COLLECTION AND ANALYSIS Samoie Collection Method Air Particulate Continuous low volume air sampler.

Sample collected every week along with the filter change.

Air Iodine A TEDA impregnated charcoal cartridge is connected to air particulate air sampler and is collected weekly at filter change.

Crab and Fish Two batch samples are sealed in a plastic bag or jar and frozen semi-annually or when in season.

Sediment A sediment sample is taken semi-annually.

Direct 2 TLD's will be collected from each location quarterly.

E-5 Analysis Gross Beta analysis on each weekly sample. Gamma spectrometry shall be performed if gross beta exceeds 10 times the yearly

.mean of the control station value. Samples shall be analyzed 24 hrs or more after collection to allow for radon and thorium daughter decay. Gamma isotopic analysis on quarterly composites.

Iodine 131 analysis are performed on each weekly sample.

Gamma isotopic analysis of edible portion on collection.

Gamma isotopic analysis semi-annually.

Gamma dose quarterly.

sample Milk Water

Potable, Surface)

Salem ODCM Rev. 10 SAMPLE COLLECTION AND ANALYSIS (Cont'd)

Collection Method Sample of fresh milk is collected for each farm semi-monthly when cows are in pasture, monthly at.other times.

Sample to be collected monthly providing winter icing conditions allow.

E-6 Analysis Gamma isotopic analysis and I-131 analysis on each sample on collection.

Gamma isotopic monthly H-3 on quarterly surf ace sample, monthly on ground water sample.

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Salem ODCM Rev. 10 I

Figure E-1 ONSITE SAMPLING LOCATIONS I

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Figure E-2 MTIAOAL ISLAND

/V.DIOLOGIC4L EJMRONMENTAL MONITORJNG PllOGAAM Off..SlTF SAMPLING LOCAT10N E-B E-8

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ML18102A365

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5.0 CONCLUSION

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