ML18107A525

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Semiannual Radioactive Effluent Release Rept for Jan-June 1999.
ML18107A525
Person / Time
Site: Salem  PSEG icon.png
Issue date: 06/30/1999
From:
Public Service Enterprise Group
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ML18107A524 List:
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NUDOCS 9909150190
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SALEM GENERATING STATION SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SGS RERR-46 SALEM UNIT NOS. 1 & 2 DOCKET

,. NO. 50-272 DOCKET NO. 50-311 OPERA TING LICENSE NO. DPR-070 OPERATING LICENSE NO. DPR-075

""- August 1999

-~ -- -. \

9909150190 990908  !

PDR ADOCK 05000272 .II R PDR

SGS-DIOACTIVE EFFLUENTS RELEASE -ORT JANUARY - JUNE 1999 SALEM GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1999 Table of Contents INTRODUCTION _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 1 PART A. PRELIMINARY SUPPLEMENTAL INFORMATION -------- 2 1.0 REGULATORY LIMITS _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 2 1.1 Fission and Activation Gas Release Limits

2 1.2 Iodine, Particulates, and Tritium --------------- 2 1.3 Liquid Effluents Release L i m i t s - - - - - - - - - - - - - - - 3 1.4 Total Dose Limit

3 2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) - - - - - - - - 3 3.0 AVERAGE ENERGY

4 4.0 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 4 4.1 Liquid E f f l u e n t s - - - - - - - - - - - - - - - - - - - - - 4 4.2 Gaseous-Effluents _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 4 4.3 Estimated Total Error

5 5.0 BATCH RELEASES - - - - - - - - - - - - - - - - - - - 6

SGS-DIOACTIVE EFFLUENTS RELEASE -ORT JANUARY - JUNE 1999 6.0 UNPLANNED/ABNORMAL RELEASES - - - - - - - - - - - - - 6 7.0 ELEVATED RADIATION MONITOR R E S P O N S E S - - - - - - - - - 6 8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASEREPORTS _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 6 PART B. GASEOUS EFFLUENTS _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 7 PART C. LIQUID EFFLUENTS _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 7 PART D. SOLID WASTE - - - - - - - - - - - - - - - - - - 7 PART E. RADIOLOGICAL IMPACT ON M A N - - - - - - - - - - - - 8 Air P a t h w a y s - - - - - - - - - - - - - - - - - - - - - - - 8 Direct Radiation

9 Total Dose

9 Dose to members of the public due to activities inside the site boundary _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 10 Assessment

- - - - - - - - - - - - - - - - - - - - - - - 11 Trends

- - - - - - - - - - - - - - - - - - - - - - - - - 12 PART F. METEOROLOGICAL DATA

- - - - - - - - - - - - - - - 13 PART G. OFFSITE DOSE CALCULATION MANUAL (ODCM)

CHANGES

- - - - - - - - - - - - - - - - - - - - - - - - 13 PART H. INOPERABLE M O N I T O R S - - - - - - - - - - - - - - - 13 PART I. PROCESS CONTROL PROGRAM (PCP) CHANGES _ _ _ _ _ _ _ 13 PART J. ENVIRONMENTAL MONITORING LOCATION CHANGES _ _ _ _ _ 14 ii

SGS-DIOACTIVE EFFLUENTS RELEASE -ORT JANUARY - JUNE 1999 PART K. MAJOR CHANGES TO WASTE PROCESSING SYSTEMS- - - - - 14 TABLE 1A - GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 15 TABLE 1B GASEOUS EFFLUENTS - ELEVATED RELEASES _ _ _ _ _ _ 17 TABLE 1C-GASEOUS EFFLUENTS-GROUND LEVEL RELEASES _ _ _ _ 19 TABLE 2A-LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES _ _ _ _ 20 TABLE 2B - LIQUID E F F L U E N T S - - - - - - - - - - - - - - - 22 TABLE 3 - SOLID WASTE AND IRRADIATED FUEL SHIPMENTS _ _ _ _ _ 24 TABLE 4A-

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE - GASEOUS _ _ _ _ _ _ _ _ _ _ _ _ 26 TABLE 4B -

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE - LIQUID - - - - - - - - - - - - - 30 APPENDIX A- MPC DATA iii

SGS-DIOACTIVE EFFLUENTS RELEASE -ORT JANUARY - JUNE 1999 SALEM GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT

-JANUARY - JUNE 1999 INTRODUCTION This report, SGS-RERR-46 summarizes information pertaining to the _relea_ses of radioactive materials in liquid, gaseous and sond form from the Salem Generating Station (SGS) for the period January 1, 1999 to June 30, 1999.

Salem Unit 1 is a Westinghouse Pressurized Water Reactor which has a licensed core thermal 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 operation on June 30, 1977.

Salem Unit 2 is a Westinghouse Pressurized Water Reactor which has a licensed core thermal 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 operation on October 13, 1981.

This report is prepared in the format of Regulatory Guide 1.21, Appendix 8, as required by Specification 6.9.1.8 of the Salem Technical Specifications. Preceding the tables summarizing the gaseous and liquid discharges and solid radwaste shipments are our responses to parts A-F of the "Supplemental Information" section of Regulatory Guide 1.21, Appendix 8.

As required by Regulatory Guide 1.21, the Salem 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.

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

Salem Unit 1 generated 4,436,380 megawatt-hours of electrical energy (net) during the reporting period.

Salem Unit 2 generated 3, 160,024 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 1999-were--not*available-for*inclusion*in-this-report. The results of these composites will be provided in the next Radioactive Effluent Release Report.

1

SGS-DIOACTIVE EFFLUENTS RELEASE -ORT JANUARY - JUNE 1999 PART A. PRELIMINARY SUPPLEMENTAL INFORMATION 1.0 REGULATORY LIMITS 1.1 Fission and Activation Gas Release Limits The dose rate due to radioactive materials released in gaseous effluents from the site (i.e. Salem Units 1 & 2, and Hope Creek) to areas at and beyond the site boundary, shall be limited to the following:

For noble gases: Less than or equal to 500 mrem/yr to the total body and less than or equal to 3000 mrem/yr to the skin.

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

During any calendar quarter: Less than or equal to 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 mrem/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, to areas at and beyond the site boundary, shall qe limited to the following:

During any calendar quarter: Less than or equal to 7.5 mrem to any organ and, During any calendar year: Less than or equal to 15 mrem to any organ.

2

SGS-DIOACTIVE EFFLUENTS RELEASE -ORT JANUARY - JUNE 1999 1.3 Liquid Effluents Release Limits The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10CFR20, Appendix 8, 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-04 microcuries per milliliter.

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

During any calendar quarter: Less than or equal to 1.5 mrem to the total body, and less than or equal to 5 mrem to any organ, and

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

1.4 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 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem).

2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)

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

a. MPC values are not used for gaseous releases. Determination of maximum release rates for noble gases, iodines, tritium, and for all radionuclides in particulate form (with half-lives > 8 days), are based on dose rate calculations as specified in the ODCM.
b. According to current Technical Specifications, MPC values as stated in 1OCFR20, Appendix 8, Table II, Column 2 are to be used for liquid effluents. Since the MPC values were removed from 10CFR20 effective 1/1/94, the MPC values are now contained in the ODCM. These MPC values are added as Appendix B of this report.
c. The MPC value used for dissolved or entrained noble gases in liquid effluents is 2E-04 microcuries per milliliter.

3

SGS-DIOACTIVE EFFLUENTS RELEASE -ORT JANUARY - JUNE 1999

  • 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. Therefore this section is not applicable to SGS.

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

_Sp~cifications._ During the period of record, all batch liquid Wastes were routed tO 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 hold-up tanks. During this report period, chemical cleaning of the secondary side of the Unit 2 Steam Generators was performed. The cleaning process fluids were volume reduced by evaporation. The distillate from the evaporation process was collected in batch release tanks {BRT). The BRTs also collected other non-radioactive water from the steam generator cleaning process.

The tanks were uniformly mixed for sampling and analysis before being released.

The BRTs were released as batch releases. Continuous liquid releases are defined as condensate releases from intermittent blowdown of the steam generators. To determine the total liquid activity discharged in continuous releases, the specific

-activities from analyses were multiplied by the volume of effluent discharged.

The detection requirements of Table 4.11-1 of the Technical Specifications are achieved or exceeded. Radionuclides detected at concentrations below the Technical Specification lower limit of detection (LLD) are treated as being present.

Radionuclides for which no activity was detected while meeting the required LLD's are treated as absent.

4.2 Gaseous Effluents Gaseous effluent streams are monitored and sampled in accordance with Table 4.11-2 of the Technical Specifications. The Plant Vent is the final release point for planned gaseous effluent releases and is continuously monitored by installed radiation monitors.

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 multichannel analyzer.

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 Table 4.11-2 of the Technical Specifications are achieved or exceeded. Radionuclides detected at concentrations below the Technical Specification LLD are treated as being present. Radionuclides for which no activity was detected while meeting the required LLDs are treated as absent.

4

SGS-DIOACTIVE EFFLUENTS RELEASE -ORT JANUARY - JUNE 1999 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 determine the normal continuous release of radioactivity through the plant vent.

Slightly elevated plant vent radiation monitoring readings and containment pressure reliefs are treated as continuous releases. The monitor response is converted to

  • "specific activity" using historical efficiency factors. The "speCific activity" is multiplied by a conservative default volume of effluent discharge to determine the total activity released.

Batch Mode gaseous releases are q-uantifiea by-sampling- each decay tank or

_containment purge prior to release. Specific activities for each isotope are multiplied by the total volume of gas discharged for that batch to determine the total activity released.

To address potential gaseous releases from the chemical cleaning of the secondary side of the Unit 2 Steam Generators, representative samples of the process fluids were obtained and partitioning coefficients applied to estimate the carryover of radioactive particulates into the vapor phase. Conservative assumptions were used to calculate the release rates during the venting conditions in the chemical cleaning and the evaporation processes. The total activity released was determined from the partitioned activity and the volume of vapor discharged.

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 are not available, then the abnormal release is quantified by the use of the plant vent radiation monitors. The monitor response is converted to "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 determine the total activity discharged.

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

SGS -IOACTIVE EFFLUENTS RELEASE -ORT JANUARY - JUNE 1999 5.0 BATCH RELEASES

_summaries of batch releases of gaseous and liquid effluents are provided in Tables 4A-1 and 48-1 for Unit 1 and 4A-2 and 48-2 for Unit 2.

6.0 UNPLANNED/ABNORMAL RELEASES During this report period, the Number 22 chemical volume control system (CVCS) monitor tank was found to be releasing at a higher release rate than allowed by the

__ setpoint calc_ulation. The calculated-allowable release rate was 20.s-gallons per minute.

The CVCS monitor tank was found to be discharging at 62 gallons per minute. The release rate was lowered to 16 gallons per minute upon discovery. Calculation verified that, due to the conservatism in the setpoint calculation, the release did not exceed Technical Specification or regulatory limits. Since Technical Specifications limits were not exceeded and the required Technical Specification Action was taken, no report or notification per 10CFR50.72 or 10CFR50.73 were required.

7.0 ELEVATED RADIATION MONITOR RESPONSES During this reporting period, there were no alarm conditions due to elevated effluent radiation levels.

8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS There were no modifications to previous Radioactive Effluent Release Reports during this reporting period.

6

SGS 9o10ACTIVE EFFLUENTS RELEASE -ORT JANUARY - JUNE 1999

. PART B. GASEOUS EFFLUENTS See Summary Tables 1A-1 through 1C for Salem Unit 1 Operations.

See Summary Tables 1A-2 through 1C for Salem Unit 2 Operations.

PART C. LIQUID EFFLUENTS See Summary Tables 2A-1 through 28 for Salem Unit 1 Operations.

See Summary Tables 2A-2 through 28 for Salem Unit 2 Operations.

PART D. SOLID WASTE See Summary in Table 3.

7

SGS ~IOACTIVE EFFLUENTS RELEASE -ORT JANUARY - JUNE 1999 PART E. RADIOLOGICAL IMPACT ON MAN The calculated individual doses in this section are based on the controlling dose pathways and age groups as described below. The estimated dose represents the 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 meteorological dispersion coefficients for _the_ six 111ontl:l reporting interval. -

Liquid Pathways Type Age Group Location Pathway Total Body Adult Site Boundary Seafood Ingestion Organ Adult Site Boundary Seafood Ingestion Type Dose Limit Total Body 4.48E-02 mrem 3mrem Organ Dose (Gl-LLI) 6.91 E-02 mrem 10 mrem Population (Total) 4.30E-02 Person-rem N/A Population (Average) 7.96E-09 mrem N/A Air Pathways Type Age Group Location Pathway Total Body All Site Boundary Direct Exposure Skin All Site Boundary Direct Exposure Organ Infant 4.9mi.W. Milk, Ground Plane, Inhalation Type Dose Limit Total Body 6. 75E-02 mrem 500 mrem/yr Skin 1.60E-01 mrem 3000 mrem/yr Organ Dose (Thyroid) 1.91 E-02 mrem 15 mrem Population (Tot~J) 1. 73E+OO Person-rem N/A Population (Average) 3.84E-07 mrem N/A 8

SGS.IOACTIVE EFFLUENTS RELEASE -ORT JANUARY - JUNE 1999 Direct Radiation Direct radiation may be estimated by thermoluminescent dosimetric (TLD) measurements. One method for comparing TLD measurements is by comparison with pre.;operational data. It should be noted that the TLDs measure direct radiation from both the Salem and Hope Creek Generating Stations at Artificial Island, and natural background radiation.

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

TLD Location Measurement 1S-1 _0.5 mLN -4.29 mrad/month

-ss-1 1.0 mi. E 3.47 mrad/month These values are interpreted to represent natural background, since the values are within the statistical variation associated with the pre-operational program results, which are 4.1 mrad/month for location 1S-1, and 3.8 mrad/month for location 5S-1.

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

<25 mrem total body or any organ and;

<75 mrem thyroid for a calendar year.

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

The following doses to a "hypothetical maximum exposed individual" have been calculated for the six-month reporting period. They are the sum of gaseous and liquid pathway doses for the Salem 1 and 2 and Hope Creek plants:

1.30E-01 mrem Total Body

1. 71 E-01 mrem Organ (Gl-LLI) 6.50E-02 mrem Thyroid 9

SGs9o10ACTIVE EFFLUENTS RELEASE 4toRT JANUARY - JUNE 1999 Dose to members of the public due to activities inside the site boundary Dose to members of the public is limited to 100mrem total effective dose equivalent (TEDE) in a year in accordance with 1OCFR20.1301. The members of the public that spent the most time at the NBU for January - June 1999 are various food vendors, who spent a Jew hours in front of the Security Center during lunch hours. 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 food vendors deliver Monday through Friday.

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

c. The food vendors leave the site at 1:00 P.M.
d. No deliveries are made on major holidays, making the total weeks equal 50 for the year.
e. The dose data is based on the TLD located outside the Security Center in the vicinity of the food vendors and the calculated dose due to gaseous effluents at that location.

For the six-month reporting period, January 1 to June 30, 1999 the calculated doses from the operation of the Salem units are:

5.35E-01 mrem Total Body 1.62E-02 mrem Organ (GI-LU) 1.65E-02 mrem Thyroid 10

SGS .IOACTIVE EFFLUENTS RELEASE -ORT JANUARY-JUNE 1999 Assessment

1. Gaseous:

Gaseous effluents released from Salem Units 1 and 2 resulted in an insignificant projected dose to the maximum hypothetical individual. The dose for the six-month period was a small fraction of all applicable limits.

Although reported gaseous effluents increased from the previous reporting period, gaseous effluent releases continue to remain well within Federal limits. Gaseous effluents rel~ased from Salem increased principally due to-the presence of small fuel -

defects. Gaseous effluent processing equipment continues to be maintained in order to ensure that all releases of gaseous radioactivity are As-Low-As-Reasonably-Achievable (ALARA).

2. Liquids:

Liquid effluents released from Salem Units 1 and 2 resulted in an insignificant projected dose to the maximum hypothetical individual and were well within all applicable limits.

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

11

SGS ~IOACTIVE EFFLUENTS RELEASE -ORT JANUARY - JUNE 1999 Trends The following two trend graphs show the total curies of gaseous and liquid effluents released for Salem from 1989 through June 1999. Calculated doses in the graphs are to the maximum hypothetical individual.

Salem Units 1 and 2 Liquid Effluents Curies Released and Calculated Doses Note: Calculated doses are to the maximum hypothetical individual

-+-CURIES

--o-ORGAN

-6)-TB 3

~ 0.1 ......- A - - - - - - - - - - - - - - - - - - - - - - - - - - - , o - - = - - - o : - - - - ' < -

0.01 +--+---lt--+--+-t---t--+-+--+--+-+--+---t-+--+---lt--+--+-t---1 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 Reporting Period Salem Unit 1 and 2 Gaseous Effluents Noble Gas Curies Released and Calculated Dose Note : Calculated doses are to the maximum hypothetical individual 0 1.0E+OO 1--------------------~-----1----

c

~

m -+-CURIES

~

-D-SKIN g 1.0E-03 1-----------------~--\----hf-----

3 -+-TB

3 1.0E-09-1---+---+--+-+--+-t---+----t-+--+-t---+----l......;::e--4-+--+-t---I 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 Reporting Period 12

SGS 9>10ACTIVE EFFLUENTS RELEASE -ORT JANUARY - JUNE 1999 PART F. METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmospheric stability class at the 300 foot elevation will be provided in the next RERR report. As required by Technical Specifications, a summary of the meteorological data is retained on site that shall be provided to the Nuclear Regulatory Commission upon their request.

PART G. OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES During the report period, there were no changes to the Salem Offsite Dose Calculation Manual.

PART H. INOPERABLE MONITORS During this period the following effluent radiation monitors were inoperable for greater than 30 days:

  • Salem Unit 2 Liquid Radwaste Discharge Radiation Monitor (2R18). The radiation monitor was declared inoperable to investigate the cause of frequent occurrences of electronic spiking. Extensive troubleshooting determined that the radiation monitor was improperly grounded. Once identified, the improper electrical ground connection was corrected and the equipment retested satisfactorily. The monitor was out of service for 35 days due to the extensive troubleshooting required to identify and correct the improper ground connection.

Steam Generator Slowdown Flow Transmitters (2F3179, 2F3181, 2F3183, 2F3185) .

. During operator rounds, the flow transmitters were identified as indicating improper flow through the Steam Generator Slowdown. The transmitters required repair by an offsite vendor. Turnaround time caused the flow transmitters to be inoperable as Unit 2 began. a scheduled refueling outage. Final repairs were made during the outage, but since there was no steam generator blowdown flow during this period, retest could not be performed. The total time the transmitters were declared inoperable was 60 days.

Steam Generator Slowdown Radiation Monitors (2R19). The radiation monitors were inoperable for greater than 30 days due to a lack of steam generator blowdown flow during the Unit 2 refueling outage.

Containment Fan Coil Unit Process Radiation Monitors (2R13). The radiation monitors were inoperable for greater than 30 days due to a lack of circulating water flow (process flow) through the fan coil units during the Unit 2 refueling outage.

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

13

SGS ~IOACTIVE EFFLUENTS RELEASE -ORT JANUARY-JUNE 1999 PART J. ENVIRONMENTAL MONITORING LOCATION CHANGES During the reporting period, there were no changes to the environmental monitoring sampling program.

- PART K. MAJOR CHANGES TO WASTE PROCESSING SYSTEMS During the report period, there were no major changes to the waste processing systems at Salem Unit 1 or 2. However, during the report period, chemical cleaning was performed on the s~conqary side ofall four Unit-2 steam generators. The cleaning- --

process, a-s expected, resulted in collecting low level radioactivity in the process fluids.

As described in section 4.1 of this report, the steam generator cleaning process fluids were volume reduced by evaporation. The evaporator distillate was collected in batch release tanks (BRTs). The BRTs also collected other non-radioactive water from the steam generator cleaning process support systems. The BRT liquid was processed in batch mode for discharge through the Chemical Waste system to the environment. The venting processes during steam generator cleaning and waste processing resulted in low levels of radioactivity released in gaseous effluent. Liquid and gaseous effluent release permits were generated to record radioactivity released and to ensure that radioactive effluent Technical Specification and regulatory limits were not exceeded. Calculations supporting the Safety Evaluation for performing steam generator cleaning demonstrated that the expected radioactive effluents were a small fraction of historical radioactive releases and well below technical specification and regulatory limits. The concentrates from the evaporation process were shipped in aqueous solution to an authorized processor for ultimate disposal. Since the concentrates were well below the NRC and Department of Transportation definition of radioactive material with regard to transportation, they were not shipped as radioactive material. Also, waste manifestation in accordance with 1OCFR20 was not required. Therefore, the concentrates were not shipped as radioactive waste and are not included in Table 3. The results of the steam generating cleaning process were within the expected radioactive effluent results. The resulting radioactive materials released in liquid and gaseous effluents are included in the associated Tables 1A-2, 1B-2, 2A-2, 28-2, and 4A-2 below.

14

e SGS RADIOACTIVE EFFLUENTS RELEASE REPORT JANUARY - JUNE 1999 SALEM GENERATING STATION TABLE 1A-1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY-JUNE 1999 UNIT 1 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Est.

Total Units 151 Quarter 2nd Quarter Error1 A. Fission and Activation Products

1. Total Release Ci 1.73E+03 1.06E+03 50%
2. Average Release Rate For Period µCi/sec 2.20E+02 1.35E+02
3. Percent of Technical Specification Limit (T.S. 3.11.2.2(a))  % 1.27E+OO 7.77E-01 B. Iodines
1. Total lodine-131 Ci 1.22E-03 3.02E-04 50%
2. Average Release Rate For Period µCi/sec 1.55E-04 3.84E-05
3. Percent of Technical Specification Limit2 (T.S. 3.11.2.3(a))  % 6.77E-02 1.59E-02
c. Particulates
1. Particulates With Half-lives > 8 days Ci 3.96E-07 1.22E-06 50%
2. Average Release Rate For Period µCi/sec 5.04E-08 1.55E-07
3. Percent of Technical Specification Limit2 (T.S. 3.11.2.3(a))  % 6.77E-02 1.59E-02
4. Gross Alpha Ci O.OOE+OO O.OOE+OO D. Tritium
1. Total Release Ci 3.71E+02 6.59E+01 50%
2. Average Release Rate For Period µCi/sec 4.72E+01 8.38E+OO
3. Percent of Technical Specification Limit2 (T.S. 3.11.2.3(a))  % 6.77E-02 1.59E-02
1. For batch releases, the estimated overall error is 10%.
2. Iodines, Tritium, and Particulates are treated as a group.

15

e SGS RADIOACTIVE EFFLUENTS RELEASE REPORT JANUARY - JUNE 1999 SALEM GENERATING STATION TABLE 1A-2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY-JUNE 1999 UNIT2 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Est.

Total Units 1st Quarter - --2nd Quarter Error1 A. Fission and Activation Products

1. Total Release Ci 4.58E+02 5.13E+01 50%
2. Average Release Rate For Period µCi/sec 5.83E+01 6.51E+OO
3. Percent of Technical Specification Limit (T.S. 3.11.2.2(a))  % 3.36E-01 3.81 E-02
8. Iodines
1. Total lodine-131 Ci 3.33E-06 3.73E-03 50%
2. Average Release Rate For Period µCi/sec 4.24E-07 4.75E-04
3. Percent of Technical Specification Limit2 (T.S. 3.11.2.3(a))  % 3.79E-03 1.75E-01
c. Particulates
1. Particulates With Half-lives> 8 days Ci 5.42E-07 1.54E-05 50%
2. Average Release Rate For Period µCi/sec 6.89E-08 1.96E-06
3. Percent of Technical Specification Limit2 (T.S. 3.11.2.3(a))  % 3.79E-03 1.75E-01
4. Gross Alpha Ci O.OOE+OO O.OOE+OO D. Tritium
1. Total Release Ci 1.34E+02 2.62E+01 50%
2. Average Release Rate For Period µCi/sec 1.70E+01 3.33E+OO
3. Percent of Technical Specification Limit2 (T.S. 3.11.2.3(a))  % 3.79E-3 1.75E-01
1. For batch releases, the estimated overall error is 10%.
2. Iodines, Tritium, and Particulates are treated as a group.

16

SGS RADIOACTIVE EFFLUENTS RELEASE REPORT JANUARY - JUNE 1999 SALEM GENERATING STATION TABLE 18-1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - JUNE 1999 UNIT 1 GASEOUS EFFLUENTS- ELEVATED RELEASES Continuous Mode BatcbMode Nuclides _

Units 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter Released

1. Fission Gases Krypton-85 Ci O.OOE+OO O.OOE+OO 2.98E-01 1.50E+OO Xenon-131m Ci O.OOE+OO O.OOE+OO 5.61E-03 7.41E-02 Xenon-133 Ci 1.73E+03 1.06E+03 7.07E-02 1.19E+OO Xenon-133m Ci O.OOE+OO O.OOE+OO O.OOE+OO 7.60E-04 Totals Ci 1.73E+03 1.06E+03 3.75E-01 2.76E+OO
2. Iodine lodine-131 Ci 1.22E-03 3.02E-04 O.OOE+OO O.OOE+OO Totals Ci 1.22E-03 3.02E-04 O.OOE+OO O.OOE+OO
3. Particulates (Half-life >8 days)

Cobalt-60 Ci O.OOE+OO 6.24E-07 O.OOE+OO O.OOE+OO Cobalt-58 Ci O.OOE+OO 5.94E-07 O.OOE+OO O.OOE+OO Cs-137 Ci 3.96E-07 O.OOE+OO O.OOE+OO O.OOE+OO Totals Ci 3.96E-07 1.22E-06 O.OOE+OO O.OOE+OO

4. Tritium Ci 3.71E+02 6.59E+01 O.OOE+OO O.OOE+OO 17

SGS RADIOACTIVE EFFLUENTS RELEASE REPORT JANUARY - JUNE 1999 SALEM GENERATING STATION TABLE 1B-2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - JUNE 1999 UNIT2 GASEOUS EFFLUENTS- ELEVATED RELEASES Continuous Mode Batch Mode Nuclides Units 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter Released

1. Fission Gases Krypton-85 Ci O.OOE+OO O.OOE+OO 5.02E-01 8.49E-01 Xenon-131m Ci O.OOE+OO O.OOE+OO 4.81 E-02 1.57E-01 Xenon-133 Ci 4.56E+02 3.68E+01 1.51 E+OO 1.34E+01 Xenon-133m Ci O.OOE+OO O.OOE+OO 2.13E-03 6.13E-02 Xenon-135 Ci O.OOE+OO O.OOE+OO 6.61 E-06 5.66E-03 Totals Ci 4.56E+02 3.68E+01 2.06E+OO 1.45E+01
2. Iodine lodine-131 Ci 3.33E-06 3.73E-03 O.OOE+OO O.OOE+OO Totals Ci 3.33E-06 3.73E-03 O.OOE+OO O.OOE+OO
3. Particulates (Half-life >8 days) lron-55 Ci O.OOE+OO O.OOE+OO O.OOE+OO 5.78E-06 Nickel-63 Ci O.OOE+OO O.OOE+OO O.OOE+OO 4.77E-06 Cobalt-58 Ci O.OOE+OO 2.05E-06 O.OOE+OO O.OOE+OO Cobalt-60 Ci 5.42E-07 5.21 E-07 O.OOE+OO 1.95E-06 Cesium-134 Ci O.OOE+OO O.OOE+OO O.OOE+OO 1.07E-07 Cesium-137 Ci O.OOE+OO O.OOE+OO O.OOE+OO 2.50E-07 Totals Ci 5.42E-07 2.57E-06 O.OOE-00 1.29E-05
4. Tritium Ci 1.34E+02 2.62E+01 O.OOE+OO O.OOE+OO 18

SGS RADIOACTIVE EFFLUENTS RELEASE REPORT JANUARY - JUNE 1999 SALEM GENERATING STATION TABLE 1C EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - JUNE 1999

  • GASEOUS EFFLUENTS - GROUND LEVEL RELEASES There were no ground level releases during this reporting period.

19

SGS RADIOACTIVE EFFLUENTS RELEASE REPORT JANUARY - JUNE 1999 SALEM GENERATING STATION TABLE 2A-1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - JUNE 1999 UNIT 1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES

- - - -- --

Est.

Total Units 151 Quarter 2nd Quarter Error A. Fission and Activation Products

1. Total Release Ci 4.26E-02 2.85E-02 25%
2. Average Release Rate For Period µCi/ml 2.15E-08 1.87E-08
3. Percent of Technical Specification Limit (T.S. 3.11.1.2(a))  % 6.78E-01 5.43E-01
8. Tritium
1. Total Release Ci 1.08E+02 7.16E+01 25%
2. Average Release Rate For Period µCi/ml 5.44E-05 4.69E-05
3. Percent of Technical Specification Limit (T.S. 3.11.1.1)  % 1.81E+OO 1.56E+OO
c. Dissolved and Entrained Noble Gases
1. Total Release Ci 2.45E-02 1.48E-02 25%
2. Average Release Rate For Period µCi/ml 1.23E-08 9.?0E-09
3. Percent of Technical Specification Limit (T.S. 3.11.1.1)  % 6.15E-03 4.85E-03 D. Gross Alpha Ci O.OOE+OO O.OOE+OO 25%

E. -- -- Volume-of-Waste-Release (Prior to Dilution) Liters 6.14E+05 4.94E+05 25%

F. Volume of Dilution Water Used During Entire Period Liters 1.98E+09 1.53E+09 25%

20

---

e SGS RADIOACTIVE EFFLUENTS RELEASE REPORT JANUARY-JUNE 1999 SALEM GENERATING STATION TABLE 2A-2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - JUNE 1999 UNIT2 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Est.

TotaJ __ -- - - -

-units 1st-Quarter- - 2nd Quarter Error A. Fission and Activation Products

1. Total Release Ci 6.09E-02 5.94E-02 25%
2. Average Release Rate For Period µCi/ml 1.78E-08 2.30E-08
3. Percent of Technical Specification Limit (T.S. 3.11.1.2(a))  % 9.22E-01 1.05E+OO
8. Tritium
1. Total Release Ci 2.34E+02 1.62E+02 25%
2. Average Release Rate For Period µCi/ml 6.52E-05 6.26E-05
3. Percent of Technical Specification Limit (T.S. 3.11.1.1)  % 2.17E+OO 2.09E+OO
c. Dissolved and Entrained Noble Gases
1. Total Release Ci 2.54E-02 4.77E-02 25%
2. Average Release Rate For Period µCi/ml 7.08E-09 1.84E-08
3. Percent of Technical Specification Limit (T.S. 3.11.1.1)  % 3.54E-03 9.22E-03 D. Gross Alpha Ci O.OOE+OO O.OOE+OO 25%

E. Volume of Waste Release (Prior to Dilution) Liters 1.15E+06 1.85E+06 25%

F. Volume of Dilution Water Used During Entire Period Liters 3.59E+09 2.59E+09 25%

21

SGS RADIOACTIVE EFFLUENTS RELEASE REPORT JANUARY - JUNE 1999 SALEM GENERATING STATION TABLE 2B-1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - JUNE 1999 UNIT 1 LIQUID EFFLUENTS Continuous Mode Batch Mode Nu elides Units 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter Released 1.

Fission and Activation Products Sodium-24 Ci O.OOE+OO O.OOE+OO 7.25E-05 O.OOE+OO Manganese-54 Ci O.OOE+OO O.OOE+OO 1.70E-04 1.15E-04 lron-55 Ci O.OOE+OO O.OOE+OO 4.12E-03 O.OOE+OO Cobalt-57 Ci O.OOE+OO O.OOE+OO O.OOE+OO 2.12E-05 Cobalt-58 Ci O.OOE+OO O.OOE+OO 7.83E-03 1.59E-02 Cobalt-60 Ci O.OOE+OO O.OOE+OO 1.11 E-03 1.99E-03 Strontium-90 Ci O.OOE+OO O.OOE+OO 7.97E-06 O.OOE+OO Niobium-95 Ci O.OOE+OO O.OOE+OO O.OOE+OO 1.85E-05 Zirconium-95 Ci O.OOE+OO O.OOE+OO O.OOE+OO 1.64E-05 Technicium-99m Ci O.OOE+OO O.OOE+OO O.OOE+OO 2.29E-05 Antimony-124 Ci O.OOE+OO O.OOE+OO 3.37E-03 6.70E-04 Antimony-125 Ci O.OOE+OO O.OOE+OO 4.37E-03 2.00E-03 lodine-131 Ci O.OOE+OO O.OOE+OO 1.02E-03 2.04E-03 lodine-133 Ci O.OOE+OO O.OOE+OO 6.30E-05 1.82E-04 Cesium-134 Ci O.OOE+OO O.OOE+OO 6.10E-03 1.73E-03 Cesium-137 Ci O.OOE+OO O.OOE+OO 1.44E-02 3.75E-03 Cerium-141 Ci O.OOE+OO O.OOE+OO 5.53E-06 O.OOE-06 Totals Ci O.OOE+OO O.OOE+OO 4.26E-02 2.85E-02

2. Tritium Ci O.OOE+OO O.OOE+OO 1.08E+02 7.16E+OO
3. Dissolved_and Entrained Noble Gases Xenon-131m Ci O.OOE+OO O.OOE+OO O.OOE+OO 6.40E-04 Xenon-133 Ci O.OOE+OO O.OOE+OO 2.44E-02 1.42E-02 Xenon-135 Ci O.OOE+OO O.OOE+OO 5.24E-05 O.OOE+OO Totals Ci O.OOE+OO O.OOE+OO 2.45E-02 1.48E-02 22

- - - ----

e SGS RADIOACTIVE EFFLUENTS RELEASE REPORT JANUARY - JUNE 1999 SALEM GENERATING STATION TABLE 2B-2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - JUNE 1999 UNIT2 LIQUID EFFLUENTS Continuous Mode Batch Mode Nuclides Units 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter Released

1. Fission and Activation Products Chromium-51 Ci O.OOE+OO O.OOE+OO 3.84E-05 O.OOE+OO Manganese-54 Ci O.OOE+OO O.OOE+OO 2.BOE-04 1.96E-04 lron-55 Ci O.OOE+OO O.OOE+OO 2.48E-03 O.OOE+OO Cobalt-57 Ci O.OOE+OO O.OOE+OO O.OOE+OO 7.64E-04 Cobalt-58 Ci O.OOE+OO O.OOE+OO 9.88E-03 2.57E-02 Cobalt-60 Ci O.OOE+OO O.OOE+OO 3.87E-03 3.34E-03 Niobium-95 Ci O.OOE+OO O.OOE+OO O.OOE+OO 3.50E-05 Zirconium-95 Ci O.OOE+OO - O.OOE+OO O.OOE+OO 1.92E-05 Molybdenum-99 Ci O.OOE+OO O.OOE+OO 3.11 E-05 O.OOE+OO Antimony-122 Ci O.OOE+OO O.OOE+OO 1.06E-05 7.57E-06 Antimony-124 Ci O.OOE+OO O.OOE+OO 5.96E-03 2.70E-04 Antimony-125 Ci O.OOE+OO O.OOE+OO 6.47E-03 2.00E-03 lodine-131 Ci O.OOE+OO O.OOE+OO 4.70E-03 2.14E-03 lodine-133 Ci O.OOE+OO O.OOE+OO 7.05E-05 3.12E-05 Cesium-134 Ci O.OOE+OO O.OOE+OO 7.96E-03 7.06E-03 Cesium-137 Ci O.OOE+OO O.OOE+OO 1.92E-02 1.85E-02 Cerium-144 Ci O.OOE+OO O.OOE+OO O.OOE+OO 2.5E-05 Totals Ci O.OOE+OO O.OOE+OO 6.10E-02 5.93E-02
2. Tritium Ci O.OOE+OO O.OOE+OO 2.34E+02 1.62E+02
3. Dissolved and Entrained Noble Gases Xenon..:1-31 m * * ----* -ci ----*-o:OOE+-00 ,.--crooE -+=oo- - --o:ooE+OO *s:1~E-04 Xenon-133m Ci O.OOE+OO O.OOE+OO 7.84E-05 O.OOE+OO Xenon-133 Ci O.OOE+OO O.OOE+OO 2.50E-02 4.72E-02 Xenon-135 Ci O.OOE+OO O.OOE+OO 2.39E-04 7.09E-06 Totals Ci O.OOE+OO O.OOE+OO 2.53E-02 4.77E-02 23

SGS RADIOACTIVE EFFLUENTS RELEASE REPORT JANUARY - JUNE 1999 SALEM GENERATING STATION TABLE 3 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY-JUNE1999 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not Irradiated Fuel) 6-Month Est. Total

1. A Type of Waste (Class A or less) Units1 Period Error
a. Spent Resins, Filters, Sludges, m3 5.83E+OO 25%

Evaporator Bottoms Ci 4.24E+OO

b. Dry Compressible Waste, m3 5.08E+02 25%

Contaminated Equipment Ci 1.03E+OO

c. Irradiated Components, m3 O.OOE+OO 25%

Control Rods Ci O.OOE+OO

d. Others m3 O.OOE+OO 25%

Ci O.OOE+OO

1. Volumes are measured, activities are estimated.

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

Resins DAW Nuclides  % Ci  % Ci Hydrogen-3 <1 1.52E+01 1.56E-01 lron-55 8.21 E+OO 3.48E-01 1.46E+01 1.51 E-01 Cobalt-58 1.85E+01 7.83E-01 4.32E+01 4.45E-01 Cobalt-60 9.88E+OO 4.19E-01 4.94E+OO 5.09E-02 Nickel-63 4.53E+01 1.92E+OO 1.21 E+OO 1.25E-01 Cesium-134 3.42E+OO 1.45E-01 2.68E+OO 2.76E-02 Cesium-137 1.45E+01 6.15E-01 6.43E+OO 6.63E-02 24

I-I SGS RADIOACTIVE EFFLUENTS RELEASE REPORT JANUARY - JUNE 1999 SALEM GENERATING STATION TABLE 3 (Continued)

EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY-JUNE 1999 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID RADWASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL 3A. Solid Waste Disposal (Class A or less)

Number of Mode of Shipments Transportation Destination Type of Containers 4 Truck Memphis, Tennessee Strong, Tight Containers 1 Truck Oak Ridge, Tennessee Poly High Integrity Containers There were no Class B or Class C shipments made during the report period.

4. Irradiated Fuel Shipments (Disposition)

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

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

25

SGS RADIOACTIVE EFFLUENTS RELEASE REPORT JANUARY - JUNE 1999 SALEM GENERATING STATION TABLE 4A-1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - JUNE 1999

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT1 BATCH RELEASES ONLY

1. Dates: January 1, 1999 - March 31, 1999
2. Type of release: Gaseous
3. Number of releases during quarter: 2
4. Total time duration for all releases of type listed above: 5.19E+02 Min.
5. Maximum duration for release of type listed above: 3.53E+02 Min.
6. Average duration for release of type listed above: 2.60E+02 Min.
7. Minimum duration for release of type listed above: 1.66E+02 Min.
8. Average stream flow (dilution flow) during period of release: N/A 26

SGS RADIOACTIVE EFFLUENTS RELEASE REPORT JANUARY - JUNE 1999 SALEM GENERATING STATION TABLE 4A-1 (CONT'D)

EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY -JUNE 1999

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT 1 BATCH RELEASES ONLY 1 Dates: April 1, 1999 - June 30, 1999

2. Type of release: Gaseous
3. Number of releases during quarter: 2
4. Total time duration for all releases of type listed above: 3.76E+02 Min.
5. Maximum duration for release of type listed above: 1.90E+02 Min.
6. Average duration for release of type listed above: 1.88E+02 Min.
7. Minimum duration for release of type listed above: 1.86E+02 Min.
8. Average stream flow (dilution flow) during period of release: N/A 27

SGS RADIOACTIVE EFFLUENTS RELEASE REPORT JANUARY - JUNE 1999 SALEM GENERATING STATION TABLE 4A-2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - JUNE 1999

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT2 BATCH RELEASES ONLY

1. Dates: January 1, 1999 - March 31, 1999
2. Type of release: Gaseous
3. Number of releases during quarter: 7
4. Total time duration for all releases of type listed above: 8.07E+02 Min.
5. Maximum duration for release of type listed above: 1.20E+02 Min.
6. Average duration for release of type listed above: 1.15E+02 Min.
7. Minimum duration for release of type listed above: 1.09E+02 Min.
8. Average stream flow (dilution flow) during period of release: N/A 28

SGS RADIOACTIVE EFFLUENTS RELEASE REPORT JANUARY - JUNE 1999 SALEM GENERATING STATION TABLE 4A-2 (CONT'D)

EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - JUNE 1999

.

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT2 BATCH RELEASES ONLY

1. Dates: April 1, 1999 - June 30, 1999
2. Type of release: Gaseous
3. Number of releases during quarter: 41
4. Total time duration for all releases of type listed above: 1.54E+04 Min.
5. Maximum duration for release of type listed above: 2.10E+03 Min.
6. Average duration for release of type listed above: 3.76E+02 Min.
7. Minimum duration for release of type listed above: 2.20E+01 Min.
8. Average stream flow (dilution flow) during period of release: N/A 29

SGS RADIOACTIVE EFFLUENTS RELEASE REPORT JANUARY - JUNE 1999 SALEM GENERATING STATION TABLE 4B - 1 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - JUNE 1999

SUMMARY

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

1. Dates: January 1, 1999 - March 31, 1999
2. Type of release: Liquid
3. Number of releases during quarter: 11
4. Total time duration for all releases of type listed above: 3039 Min.
5. Maximum duration for release of type listed above: 371 Min.
6. Average duration for release of type listed above: 276 Min.
7. Minimum duration for release of type listed above: 202 Min.
8. Average stream flow (dilution flow) during period of release: 172491 GPM 30

.* SGS RADIOACTIVE EFFLUENTS RELEASE REPORT JANUARY - JUNE 1999 SALEM GENERATING STATION TABLE 4B-1 (CONT'D)

EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - JUNE 1999

.

SUMMARY

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

1. Dates: April 1, 1999 - June 30, 1999
2. Type of release: Liquid
3. Number of releases during quarter:* 8
4. Total time duration for all releases of type listed above: 2618 Min.
5. Maximum duration for release of type listed above: 424 Min.
6. Average duration for release of type listed above: 327 Min.
7. Minimum duration for release of type listed above: 215 Min.
8. Average stream flow (dilution flow) during period of release: 153858 GPM 31

...

\

      • r**

.... ,I SGS RADIOACTIVE EFFLUENTS RELEASE REPORT JANUARY - JUNE 1999 SALEM GENERATING STATION TABLE 48-2 EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY-JUNE 1999

.

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE UNIT2 BATCH RELEASES ONLY

1. Dates: January 1, 1999 - March 31, 1999
2. -Type of release: Liquid
3. Number of releases during quarter: 20
4. Total time duration for all releases of type listed above: 5239 Min.
5. Maximum duration for release of type listed above: 576 Min.
6. Average duration for release of type listed above: 262 Min.
7. Minimum duration for release of type listed above: 180 Min.
8. Average stream flow (dilution flow) during period of release: 180970 GPM 32

SGS RADIOACTIVE EFFLUENTS RELEASE REPORT JANUARY - JUNE 1999 SALEM GENERATING STATION TABLE 48-2 (CONT'D)

EFFLUENTS AND WASTE DISPOSAL ANNUAL REPORT JANUARY - JUNE 1999

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A RATr"l-I l\_~C'!:::'=

UNIT2 BATCH RELEASES ONLY

1. Dates: April 1, 1999 - June 30, 1999
2. Type of release: Liquid
3. Number of releases during quarter: 22
4. Total time duration for all releases of type listed above: 5031 Min.
5. Maximum duration for release of type listed above: 328 Min.
6. Average duration for release of type listed above: 262 Min.
7. Minimum duration for release of type listed above: 133 Min.
8. Average stream flow (dilution flow) during period of release: 135858 GPM 33

\

,

\*

,;

-'*'.

  • " ' .

APPENDIX A MPC DATA

.,.

\'.... l *'

y

'

The following radionuclide concentrations were obtained from 10 CFR 20 Appendix B, Table II, Column 2 as revised January 1, 1991.

Maximum Permissible Concentrations Element Isotope Soluble Cone Insoluble Cone.

(µCi/ml) (µCi/ml)

Actinium (89) Ac-227 2E-6 3E-4 Ac-228 9E-5 9E-5 Americium (95) Am-241 4E-6 3E-5 Am-242m 4E-6 9E-5 Am-242 lE-4 lE-4 Am-243 4E-6 3E-5 Am-244 5E-3 5E-3 Antimony (51) Sb-122 3E-5 3E-5 Sb-124 2E-5 2E-5 Sb-125 lE-4 lE-4 Arsenic (33) As-73 5E-4 5E-4 As-74 5E-5 5E-5 As-76 2E-5 2E-5 As-77 8E-5 8E-5 Astatine (85) At-211 2E-6 7E-5 Barium (56) Ba-131 2E-4 2E-4 Ba-140 3E-5 2E-5 Berkelium (97) Bk-249 6E-4 6E-4 Bk-250 2E-4 2E-4 Beryllium (4) Be-7 2E-3 2E-3 Bismuth (83) Bi-206 4E-5 4E-5 Bi-207 6E-5 6E-5 Bi-210 4E-5 4E-5 Bi-212 4E-4 4E-4 Bromine (35) Br-82 3E-4 4E-5 Cadmium (48) Cd-109 2E-4 2E-4 Cd-l 15m 3E-5 3E-5 Cd-115 3E-5 4E-5 Calcium (20) Ca-45 9E-6 2E-4

  • - '*
  • - --

Ca-47 5E-5 3E-5 Californium (98) Cf-249 4E-6 2E-5 Cf-250 lE-5 3E-5 Cf-251 4E-6 3E-5 Cf-252 7E-6 7E-6 A-1

  • ,*

Element Isotope Soluble Cone. Insoluble Cone.

(µCi/ml) (µCi/ml)

Californium (98) Cf-253 lE-4 lE-4 Cf-254 lE-7 lE-7 Carbon (6) C-14 8E-4 -------

Cerium (58) Ce-141 9E-5 9E-5 Ce-143 4E-5 4E-5 Ce-144 lE-5 lE-5 Cesium (55) Cs-131 2E-3 9E-4 Cs-134m 6E-3 lE-3 Cs-134 9E-6 4E-5 Cs-135 lE-4 2E-4 Cs-136 9E-5 6E-5 Cs-137 2E-5 4E-5 Chlorine ( 17) Cl-36 8E-5 6E-5 Cl-38 4E-4 4E-4 Chromium (24) Cr-51 2E-3 2E-3 Cobalt (27) Co-57 5E-4 4E-4 Co-58m 3E-3 2E-3 Co-58 lE-4 9E-5 Co-60 5E-5 3E-5 Copper (29) Cu-64 3E-4 2E-4 Curium (96) Cm-242 2E-5 2E-5 Cm-243 5E-6 2E-5 Cm-244 7E-6 3E-5 Cm-245 4E-6 3E-5 Cm-246 4E-6 3E-5 Cm-247 4E-6 2E-5 Cm-248 4E-7 lE-6 Cm-249 2E-3 2E-3 Dysprosium (66) Dy-165 4E-4 4E-4 Dy-166 4E-5 4E-5 Einsteinium (99) Es-253 2E-5 2E-5 Es-254m 2E-5 2E-5 Es-254 lE-5 lE-5 Es-255 3E-5 3E-5 Erbium (68) Er-169 9E-5 9E-5 Er-171 lE-4 lE-4 Europium (63) Eu-152 (9.2 hrs) 6E-5 6E-5 Eu-152 (13 yrs) 8E-5 8E-5 A-2

Element Isotope Soluble Cone. Insoluble Cone.

(µCi/ml) (µCi/ml)

Europium (63) Eu-154 2E-5 2E-5 Eu-155 2E-4 2E-4 Fermium (100) Fm-254 lE-4 lE-4 Fm-255 3E-5 3E-5 Fm-256 9E-7 9E-7 Fluorine (9) F-18 8E-4 5E-4 Gadolinium (64) Gd-153 2E-4 2E-4 Gd-159 8E-5 8E-5 Gallium (31) Ga-72 4E-5 4E-5 Germanium (32) Ge-71 2E-3 2E-3 Gold (79) Au-196 2E-4 lE-4 Au-198 5E-5 5E-5 Au-199 2E-4 2E-4 Hafnium (72) Hf-181 7E-5 7E-5 Holmium (67) Ho-166 3E-5 3E-5 Hydrogen (3) H-3 3E-3 3E-3 Indium (49) In-113m lE-3 lE-3 In-114m 2E-5 2E-5 In-115m 4E-4 4E-4 In-115 9E-5 9E-5 Iodine (53) I-125 2E-7 2E-4 I-126 3E-7 9E-5 I-129 6E-8 2E-4 I-131 3E-7 6E-5 I-132 8E-6 2E-4 I-133 lE-6 4E-5 I-134 2E-5 6E-4 I-135 4E-6 7E-5 Iridium (77) Ir-190 2E-4 2E-4 Ir-192 4E-5 4E-5 Ir-194 3E-5 3E-5 Iron (26) Fe-55 8E-4 2E-3 Fe-59 6E-5 5E-5 Lanthanum (57) La-140 2E-5 2E-5 Lead (82) Pb-203 4E-4 4E-4 Pb-210 lE-7 2E-4 Pb-212 2E-5 2E-5 Lutetium (71) Lu-177 lE-4 lE-4 A-3

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Element Isotope Soluble Cone. Insoluble Cone.

(µCi/ml) (µCi/ml)

Manganese (25) Mn-52 3E-5 3E-5 Mn-54 lE-4 lE-4 Mn-56 lE-4 lE-4 Mercury (80) Hg-197m 2E-4 2E-4 Hg-197 3E-4 5E-4 Hg-203 2E-5 lE-4 Molybdenum (42) Mo-99 2E-4 4E-5 Neodymium (60) Nd-144 7E-5 8E-5 Nd-147 6E-5 6E-5 Nd-149 3E-4 3E-4 Neptunium (93) Np-237 3E-6 3E-5 Np-239 lE-4 lE-4 Nickel (28) Ni-59 2E-4 2E-3 Ni-63 3E-5 7E-4 Ni-65 lE-4 lE-4 Niobium (41) Nb-93m 4E-4 4E-4 Nb-95 lE-4 lE-4 Nb-97 9E-4 9E-4 Osmium (76) Os-185 7E-5 7E-5 Os-191m 3E-3 2E-3 Os-191 2E-4 2E-4 Os-193 6E-5 5E-5 Palladium (46) Pd-103 3E-4 3E-4 Pd-109 9E-5 7E-5 Phosphorus ( 15) P-32 2E-5 2E-5 Platinum (78) Pt-191 lE-4 lE-4 Pt-193m lE-3 lE-3 Pt-193 9E-4 2E-3 Pt-197m lE-3 9E-4 Pt-197 lE-4 lE-4 Plutonium (94) Pu-238 5E-6 3E-5 Pu-239 5E-6 3E-5 Pu-240 5E-6 3E-5 Pu-241 2E-4 lE-3 Pu-242 5E-6 3E-5 Pu-243 3E-4 3E-4 Polonium (84) Po-210 7E-7 3E-5 Potassium (19) K-42 3E-4 2E-5 A-4

Element Isotope Soluble Cone. Insoluble Cone.

(µCi/ml) (µCi/ml)

Praseodymium(59) Pr-142 3E-5 3E-5 Pr-143 5E-5 5E-5 Promethium (61) Pm-147 2E-4 2E-4 Pm-149 4E-5 4E-5 Protactinium(91) Pa-230 2E-4 2E-4 Pa-231 9E-7 2E-5 Pa-233 lE-4 . lE-4 Radium (88) Ra-223 7E-7 4E-6 Ra-224 2E-6 5E-6 Ra-226 3E-8 3E-5 Ra-228 3E-8 3E-5 Rhenium (75) Re-183 6E-4 3E-4 Re-186 9E-5 5E-5

.. . Re-187 3E-3 2E-3 Re-188 6E-5 3E-5 Rhodium (45) Rh-103m lE-2 lE-2 Rh-105 lE-4 lE-4 Rubidium (37) Rb-86 7E-5 2E-5 Rb-87 lE-4 2E-4 Ruthenium (44) Ru-97 4E-4 3E-4 Ru-103 8E-5 8E-5 Ru-105 lE-4 lE-4 Ru-106 lE-5 lE-5 Samarium (62) Sm-147 6E-5 7E-5 Sm-151 4E-4 4E-4 Sm-153 8E-5 8E-5 Scandium (21) Sc-46 4E-5 4E-5 Sc-47 9E-5 9E-5 Sc-48 3E-5 3E-5 Selenium (34) Se-75 3E-4 3E-4 Silicon (14) Si-31 9E-4 2E-4 Silver (47) Ag-105 lE-4 lE-4 Ag-1 lOm 3E-5 3E-5 Ag-111 4E-5 4E-5 Sodium (11) Na-22 4E-5 3E-5 Na-24 2E-4 3E-5 Strontium (38) Sr-85m 7E-3 7E-3 Sr-85 lE-4 2E-4 A-5

Element Isotope Soluble Cone. Insoluble Cone.

(µCi/ml) (µCi/ml)

Strontium (38) Sr-89 3E-6 3E-5 Sr-90 3E-7 4E-5 Sr-91 7E-5 5E-5 Sr-92 7E-5 6E-5 Sulfur (16) S-35 6E-5 3E-4 Tantalum (73) Ta-182 4E-5 4E-5 Technetium (43) Tc-96m lE-2 lE-2 Tc-96 lE-4 5E-5 Tc-97m 4E-4 2E-4 Tc-97 2E-3 8E-4 Tc-99m 6E-3 3E-3 Tc-99 3E-4 2E-4 Tellurium (52) Te-125m 2E-4 lE-4 Te-127m 6E-5 5E-5 Te-127 3E-4 2E-4 Te-129m 3E-5 2E-5 Te-129 8E-4 8E-4 Te-131m 6E-5 4E-5 Te-132 3E-5 2E-5 Terbium (65) Tb-160 4E-5 4E-5 Thallium (81) Tl-200 4E-4 2E-4 Tl-201 3E-4 2E-4 Tl-202 lE-4 7E-5 Tl-204 lE-4 6E-5 Thorium (90) Th-227 2E-5 2E-5 Th-228 7E-6 lE-5 Th-230 2E-6 3E-5 Th-231 2E-4 2E-4 Th-232 2E-6 4E-5 Th-natural 2E-6 2E-5 Th-234 2E-5 2E-5 Thulium (69) Tm-170 5E-5 5E-5 Tm-171 5E-4 5E-4 Tin (50) Sn-113 9E-5 8E-5 Sn-124 2E-5 2E-5

.Tungsten (7 4) W-181 4E-4 3E-4 W-185 lE-4 lE-4 A-6

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Element Isotope Soluble Cone. Insoluble Cone.

(µCi/ml) (µCi/ml)

Tungsten (74) W-187 7E-5 6E-5 Uranium (92) U-230 5E-6 5E-6 U-232 3E-5 3E-5 U-233 3E-5 3E-5 U-234 3E-5 3E-5 U-235 3E-5 3E-5 U-236 3E-5 3E-5 U-238 4E-5 4E-5 U-240 3E-5 3E-5 U-natural 3E-5 3E-5 Vanadium (23) V-48 3E-5 3E-5 Ytterbium (70) Yb-175 lE-4 lE-4 Yttrium Y-90 2E-5 2E-5 Y-91m 3E-3 3E-3 Y-91 3E-5 3E-5 Y-92 6E-5 6E-5 Y-93 3E-5 3E-5 Zinc (30) Zn-65 . lE-4 2E-4 Zn-69m 7E-5 6E-5 Zn-69 2E-3 2E-3 Zirconium (40) Zr-93 8E-4 8E-4 Zr-95 6E-5 6E-5 Zr-97 2E-5 2E-5 Any single radio- 3E-6 3E-6 nuclide not listed above with decay mode other than alpha emission or spontaneous fission and with radio -

active half-life greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Any single radio- 3E-8 3E-8 nuclide not listed .

above, which decays by alpha em1ss10n or spontaneous fission.

A-7

Notes:

1. If the identity of any radionuclide is not known, the limiting values for purposes of this table shall be: 3E-8 µCi/ml.
2. If the identity and concentration of each radionuclide are known, the limiting values should be derived as follows: Determine, for each radionuclide in the mixture, the ratio between the quantity present in the mixture and the limit otherwise established in Appendix B for the specific radionuclide not in a mixture. The sum of such ratios for all the radionuclides in the mixture may not exceed "1" (i.e. "unity").

A-8

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