Text

Semiannual Radioactive Effluent Release Rept RERR-9 for Jan-June 1990
	ML20059D258
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Site:	Hope Creek
Issue date:	06/30/1990
From:	; Public Service Enterprise Group
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ML20059D256	List: ML20059D253; ML20059D258; ML20059D264;
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	RERR-9, NUDOCS 9009060190
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HOPE CREEK GENERATING STATION SEMIANNUAL RADI0 ACTIVE t

EFFLUENT-R CEASE' REPORT-HCGS RERR-9' i

g-DOCKET No.=50-354-OPERATING LICENSE No. NFP-57

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jf HOPE CREEK GENERATING ". TION RADIOACTIVE EFFLUENT RELEA43 REPORT

-JANUARY - JUNE 1990 Table of Contents INTRODUCTION 1

=Part A. PRELIMINARY SUPPLEMENTAL INFORMATION

'2 i

1.0 REGULATORY LIMITS 2;

.. -..... =..........-.

1.a Fission and Activation Gas Release Limits 2

1.b -Iodine, Particulates, and ' Tritium' 2

1.c Tritium 3

1.'d ' Liquid Effluents Release Limits 3

1.e Total Dose Limit..

3 2.0 MAXIMUM' PERMISSIBLE CONCENTRATIONS (MPC) 3 3.0 AVERAGE ENERGY 4

4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY 4

4.a Liquid Effluents.

4 4.b Gaseous Effluents 4

..c Estimated Total Error 5

4 5.0 BATCH RELEASES 6

.6.0 UNPLANNED RELEASES 6

-7.0-ELEVATED RADIATION MONITOR RESPONSES 6

8.0 ' MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS.

6 Part B.

GASEOUS EFFLUENTS 6

Part C.

LIQUID EFFLUENTS 7

Part D.

SOLID WASTE 7'

Part E.

RADIOLOGICAL IMPACT ON MAN 7

Part F.

METEOROLOGICAL DATA-8 Part G.

OFFSITE DOSE CALCULATION' MANUAL (ODCM) CHANGES 8

Part H.

' INOPERABLE MONITORS 9

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HOPE CREEK GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1990 INTRODUCTION This report, HCGS-RERR-9, summarizes information pertaining to the releases of radioactive materials in liquid, gaseous and solid form from the Hope Creek Generating Station (HCGS) for the Deriod January 1, 1990 to June 30, 1990.

The Hope Creek Generating Station (HCGS) employs a General Electric (GE) Boiling Water Reactor designed to operate at a rated core thermal power of 3293 MWt (100% steam flow) with a gross electrical output of approximately 1118 MWe and a net

tput of approximately 1067 MWe.

The HCGS achieved initial criticality on June 28, 1986 and went into commercial operation on December 20, 1986.

This report is prepared in the format of Regulatory Guide 1.21, Appendix B, as required by Specification 6.9.1.7 of the Hope Creek Technical Specifications.. 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 total activity measurements and their approximations were developed.

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

Hope Creek generated 4,059,618 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 1990 were not available for inclusion in this report.

The results c# these composites will be provided in the next Radioactive Ef;2uent Release Report.

The Sr-89, Sr-90 and Fe-55 analyses for the last half of 1989 (refer to RERR-8) have been completed; amended pages to RERR-8 are included in this report.

1

P utT A. PRELIMINARY SUPPLEMENTAL INFORMATION 1.0 REGULATOR ( LIMITS 1.a Fission and Activation Gas Release Limits The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to the following:

For noble gases:

Less than or equal to 500 arems/yr to the total body and less than or equal to 3000 mrems/yr to the skin.

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

During any calendar quarter:

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

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

1.b 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 followirst 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 th i 8 days in gaseous effluents released, from each reactvr 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 mrams to any organ and, During any calendar year:

Less than or equal to 15 mrems to any organ.

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1.c Tritium See Section 1.b.

1.d Liquid Effluents Rrelease Limits The concentration of radioactive material re? 7ased in liquid effluents to unrestricted areas shall be lim.c 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 calendar quarter to less than or equal to 1.5 mreas to the total body and to less than or equal to 5 areas to any organ, and During any calendar year to less than or equal to 3 areas to the total body and to less than or equal to 10 areas to any organ.

1.e Total Dose Limit The annual (calendar year) dose or dose comri.tment to any member of the public, due to re' eases of radioactivity and radiation, from uranium fuel r3

.e sources shall be limited to less than or equal to 25 mrige to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 arems).

2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)

- Regule. tory Guido 1.21 requires that the licensee provide the MPC's used in determining allowable release _ rates or concentrations for radioactive releases.

a.

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

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b.

MPC values as stated in 1CFR20, Appendix B, Table II, Column 2 are used for liquids, c.

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

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3.0 -AVERAGE ENERGY I

R gulatory Guide l.21 requires that the licensee provide the E

E cverage energy of the radionuclide mixture in releases of fission cnd activation gases, i f applicable.

I R31 ease limits for.HCGS are not based upon average energy.

Therefore this section is not applicable to HCGS.

.4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY I

4.a Liquid Effluents h

Liquid effluents are monitored in accordance with Table.

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4.11.1.1.1-1 of the Technical Specifications.

During the period of record, all liquid wastes were rerouted to the i

sampling tanks for monitoring prior to release.

Technical Specifications require these tanks to be uniformly mixed for samp1Ang and analysis before being released.

Batch releases are defined as releases'from the equipment drain sample tanks, floor drain sample tanks, detergent drain tanks, and I

condensate storage tanks.

There are no continuous liquid l

releases for this reporting period. The preponderant gamma emitting isotopes detected in sampling were Fe-55, Mn-54 and L

Zn-65.

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

The detection requirements of Table 4.1.1.1-1 of the Technical Speci*ications are achieved or exceeded.

Nac] ides l

existing at concentrations below the achieved detection i

limit are treated as being present.

Nuclides for which no activity was detected while meeting the required sensitivity t

values (LLDs) are treated as not being present.

4.b Gaseous Effluents t

Gaseous affluent streams are monitored and sampled in accordance with Table 4.11.2.1.2-1 of the Technical Specifications.

The north plant vent (NPV) and south plant vent (SPV) are the final release points for most planned l

gaseous affluent releases A small quantity of gaseous effluent will be released via the filtration, recirculation, and ventilation system (FRVS) vent during testing periods.

t I

l The NPV and SPV are continuously monitored for iodine.,

particulates and noble gases; the FRVS is continuously monitored for noble gases.

The NPV and SPV have moving particu'. ate and fixed charcoal filters; the FRVS has fixed part30ulute and charcoal filters. The filters and charcoal 4

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are changed weekly, as a minimum, and are analyzed on a i

multi-channel anclyzer in the laboratory.

The NPV and SPV are sampled monthly for noble gases and tritium.

J The detection requirements of Tables 4.11.2.1.2-1 of the Technical Specifications are achieved or exceeded.

Isotopes i

existing at concentrations below the achieved detection

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limit are treated as being present.

Nuclides for which no activity was detected while meeting the required sensitivity values (LLDs) are treated as not being present.

continuous Mode gaseous releases are quantified by routine (monthly) sampling and isotopic analyses of the plant vents.

Specific activities for each isotope detected during the routine sampling are adjusted using the radiation monitoring readings to obtain an average concentration for the period.

This average concentration is then multiplied by the total vent flow value for the entire sampling period in order to estimate the normal continuous release of radioactivity l

through the plant vent.

s When monthly noble gas grab samples yield no detectable activity, continuous mode releases are quantified by I

integrating Radiation Monitor System readings above

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background.

Noble gas isotopic abundances for these integrations are based on.the ANSI N237-1976/ANS-18.1 mix for BWR's.

Doses calculated from this data employ the t

methods from section 2.0 and Appendix C of the Hope Creek ODCM.

Batch Mode gaseous releases (primary containment purge) are quantified by pre-rr3 ease sampling and isotopic analysis.

Specific activities for each isotope are multiplied by the L

total purga flow volume in order to estimate the batch release of radioactivity (curies) through the plant vent, t

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 I

taken is not available, then the abnormal release is quantified by the use of the plant vent radiation monitors.

.The monitor's 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.

l 4.c Estimated Total Error The estimated total error of reported liquid releases is within 25%.

5 L- -

l 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 l

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 i

error estimates at the LLD are not defined.

The estimated total error of reported solid releases is within 25%.

5.0 BATCH RELEASES Summaries of batch releases of gaseous and liquid effluents are provided in Tables 4A and 4B.

l 6.0 UNPLANNED RELEASES l

During this reporting period there were no unplanned releases.

l 7.0 ELEVATED RADIATION MONITOR RESPONSES During this reporting period, the plant vent radiation monitors indicated slightly elevated readings on several occasions.

As indicated above monitor readings were quantified and treated as continuous releases.

The releases due to the elevated readings are included in Tables lA and 1B.

t 8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS

.Our last report (RERR-8) did not include the quarterly Sr-89, L

-Sr-90 and Fe-55 composite data for the fourth quarter of 1989.

Amended pages to RERR-8 are included at the and of this report.

L PART B.

GASEOUS EFFLUENTS See Summary Tables 1A through 1C.

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'PART C.

LIQUID EFFLUENTS See Summary Tables 2A through 2C.

PART D.

SOLID WASTE See Summary in Table 3.

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PART E.

RADIOLOGICAL IMPACT ON MAN The calculated individual doses in this section are based on actual locations of nearby residents and farms.

The t

population dose impact is based on historical site specific data i.e.,

food production, milk production, feed for milk i

animals and seafood production.

l The doses were calculated using methods described in l

Regulatory Guide 1.109 and represent calculatiuns for the L

six month reporting interval.

Individual doses from batch l

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.

i Liquid Pathways Doses to individuals in the population.from liquid releases are primarily from the seafood ingestion pathway.

The total body dose to an individual was calculated to be 6.32E-01 E

area.

The calculated highest organ dose from liquid I

releases-was 1.50E+00 arem to the liver.

The calculated population total body dose was 7.69E+00 person-rem.

The calculated average total body dose to the population within fifty. miles of the site was 1.29E-03 mram/ person.

Air Pathways E

The re'sulting-total body and skin doses to an individual were calculated to be 1.88E-01 arem and 4.08E-01 mrem respectively..The calculated highest organ dose due to radjoiodines and particulates with at greater than eight day half-life was 6.82E-04 mram to the liver.

The calculated popt lation total body dose was 4.74E-01 person-rem.

The calculated average total body dose to the population within fift/ miles of the site was 7.94E-05 mrem / person.

7

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.

TLD's at onsite locations 2S-2 and SS-1, which are 0.3 miles and 0.9 miles from the point of origin, averaged 4.6 and 4.1 mrads/ month respectively.

The values for stations 2S-2 and SS-1 are within the statistical variation associated with the pre-operational program results.

The pre-operational values for these locations are 3.7 mrad / month at 2S-2 and 4.2 mrad / month at 58-1.

It should be noted the nearest resident is 3.5 miles away.

It can thus be concluded that there is no measurable dose to any offsite location from direct radiation.

PAST F.

METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmospheric stability class at the 300 foot elevation are provided for the first and second quarters of 1990 in. Tables 5 and 6.

PART G.

OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES During-the reporting period of January 1, to June 30, 1990, the Hope Creek ODCM was revised. Revision 11 was subsequently SORC approved on March 30, 1990. The current revision 11 contains the following changes whicht (1) reflect more current release information to ensure that recommended default alarm setpoints for liquid releases are representative of the current releases; (2) change the impact reflecting the use of dose equations (i.e. changing the requirement to use the ODCM equations from "may use" to "shall use" ) ; and (3) are in response to Technical Evaluation Report (TER), SIM-20-89.

Dose factors in equations 2.6 and 2.11 on pages 19 and 23 were changed to include additional subscripts for the Ri dose factors in order to avoid any possible 8

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misinterpretation of which dose factors should be used for a given pathway.

A footnote was added to page 32 stating that no public drinking water or irrigation water samples are taken for the REMP program as these pathways are not directly affected by liquid effluents discharged from Hope Creek Generating Station.

Table 2-3 was revised to add " inhalation" to the pathway list for the infant age group to ensure that all pathways are analyzed for this controlling age group.

The dose conversion factor for Ce-141 in the child vegetation pathway was corrected in Table 2-4. This change did not result in any dose calculation errors as Co-141 had not been identified in any releases.

Per the requirements of Technical Specification 6.9.1.7, a

copy of the revised ODCM is included for NRC records.

These_ changes will not reduce the accuracy or reliability of the dose calculations or the setpoint calculations as e

outlined in the ODCM.

l PART H.

INOPERABLE MONITORS During the reporting period, the offgas hydrogen monitors, L

which are governed by Technical Specification 3.3.7.11, were inoperable for 31 consecutive days. The LCO exceeded the 30 day limit prescribed in the Technical Specifications and requires an explanation in the Semi-Annual Effluent Report.

The hydrogen analyzer cells experienced drifting problems as a result of low sample flows caused by the excessive pressure drop across the low flow switches in panel OOC 963.

The large pressure drop loaded down the sample pumps causing low sample flows. These low flows were responsible for causing spurious intermittent alarms in the system. A Design Change Package (DCP) was initiated to rectify the problem (DCP 4HC-0029). During the DCP process, other problems were identified and plans to resolve them added to the time required to complete the DCP. The lead time required to 6

obtain certain components also played a key factor in the time required to complete the DCP.

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Hydrogen analyzer 5738A1 was declared inoperable on January l

25, 1990 at 1515 hours0.0175 days 0.421 hours 0.0025 weeks 5.764575e-4 months because the process indicator had l

drifted to 1.6% hydrogen.

Chemistry analysis indicated 0%

hydrogen concentration.

A tracking LCO was initiated to track the operable 5738A2 hydrogen monitor. A full LCo was 9

4 declared'on April 2 at 0340 hours0.00394 days 0.0944 hours 5.621693e-4 weeks 1.2937e-4 months when the 5738A2 monitor was declared inoperable because of a mismatch between.

chemistry grab sample analyses process instrument reading.

Chemistry analyses yielded 0 % hydrogen concentration and the process monitor indicated 1.0 % hydrogen concentration.

The attempt to institute Temporary Modification (TM)90-028, designed to render the channel operable until the required components could be obtained, failed to meet the 30 day LCO inoperability reporting criteria. The TM was designed to provide a method of rendering the channel operable until a permanent remedy could be implemented by installing the modified flow switches via the DCP. The purpose of the TM was to mechanically bypass the inline flow switches OHAFSL-5743A1/A2. During the TM process, a four hour surveillance was performed to verify that a positive flow path through the analyzer was maintained to ensure Offgas H2/02 analyzer system integrity. The requirements of Technical Specification 3.3.7.11.1.a were met during the TM work.

The DCP was completed on May 25 and the H2/02 analyzer was placed back into service.

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e !!i HOPE CREEK GENERATING STATION TABLE 1A

)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1990 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES 1

1st 2nd Est. Totat Units Quarter Quarter Error % 0)

A. Fission-and Activation Gases

1. Total release C1 4.30E+01 2.87E+01 25

2. Average release rate for period

Ci/sec 5.472+00 3.65E+00 i

3 '. Percent of technical r

specification limit (T.S. 3.11.2.2(a))

5.87E-01 3.92E-01 B. Iodines

1. Total iodine-131 Ci 0.00E+00 0.00E+00 25 2.

Average release rate for period gCi/sec 0-00E+00 0.00E+00 3.

Percent of technical specification limit (2) f (T.S. 3.11.2.3(a))

0.00E+00 0.00E+00 C.

Particulates j

1. Particulates with

' half-lives >8 days Ci 1.46E-03 2.73E-03 25

2. Average release rate for period pCi/sec 1.82E-04 3.46E-04

3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a))

2.52E-03 6.58E-03

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

1. Total Release ci 0.00E+00 8.35E+00-25

2. Average release rate for period

Ci/sec 0.00E+00 1.06E+00 3.

Percent of technical specification limit (8)

(T.S. 3.11.2.3(a))

0.00E+00 2.12E-06 (U For batch roleeses the settested overall error is within 1 M W lodine, trittuu and particulates are treated as e gro@

A 11 1

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HOPE CREEK GENERATING STATION TABLE 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1990 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd

Nuclides Released Unit Quarter Quarter Quarter Quarter

.1. Fission Gases Krypton-83m Ci 4.30E-01 2.87E-01 0.00E+00 0.00E+00 Krypton-85m Ci 4.30E-01 2.87E-01 0.00E+00 0.00E+00 Krypton-87 Ci 1.72E+00 1.15E+00 0.00E+00 0.00E+00 Krypton-88 Ci 1.72E+00 1.15E+00 0.00E+00 0.00E+00 Krypton-89 Ci 1.16E+01 7.74E+00 0.00E+00 0.00E+00 Xenon-133 Ci 8.60E-01 5.73E-01 0.00E+00 0.00E+00 Xenon-135m Ci 2.58E+00 1.72E+00 0.00E+00 0.00E+00 Xenon-135 Ci 2.15E+00 1.43E+00 0.00E+00 0.00E+00 Xenon-137 Ci 1.33E+01 8.89E+00 0.00E+00 0.00E+00 Xenon-138 Ci 8.17E+00 5.45E+00 0.00E+00 0.00E+00 Total for Period Ci 4.30E+01 2.87E+01 0.00E+00 0.00E+00

2. Iodines Iodine-131 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Total.for Period C1 0.00E+00 0.00E+00 0.00E+00 0.00E+00

3. Particulates U)

(half-live >B days Cobalt-60 C1 1.66E-04 0.00E+00 0.00E+00 0.00E+00 Iron-59 C1 1.22E-06 0.00E+00 0.00E+00 0.00E+00 Manganese-54 Ci 2.80E-04 0.00E+00 0.00E+00 0.00E+00 Zinc-65 Ci 1.01E-03 2.73E-03 0.00E+00 0.00E+00 Total for Period Ci 1.46E-03 2.73E-03 0.00E+00 0.00E+00 UI FNLlew w evolustion on the ist and 2nd Guerter conttrvJous onde isotopic semple snelyses and quellty control date revoeled the presence of high backgrowud on the counting system detectors for these samples in our judgement, no porticulate activity was relsesed. For con servatism, particulate activity determined wider these circumstances is being reported as activity reteesed.

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HOPE CREEK GENERATING STATION I

TABLE 1C 1

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1990 GASEOUS EFFLUENTS-ELEVATED RELEASES j

i Nuclide Releases let Quarter 2nd Quarter-1st Quarter 2nd Quarter I

There were no elevated gaseous releases during this reporting

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i NOPE CREEK GENERATING STATION

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TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1990 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 1st 2nd Units Quarter Quarter Est. Total

[

-Error %

A. Fission and activation products

1. Total release (not including tritium, i

gases, alpha) (O Ci 7.66E-01 7.73E-01 25 l

2. Average diluted concentration during period.

4Ci/ml 1.22E-06 1.86E-06

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

1.53E+01 3.06E+01 B.. Tritium l

1. Total release ci 4.50E+00 3.17E+00 25 i

2. Average diluted

^

concentration during period-

Ci/ml 7.12E-06 7.47E-06

3. Percent of. technical specification limit (T.S. 3.11.1.1) 2.30E-01 2.50E-01 C.. Dissolved and entrained noble gases

1. 'Iotal ~ release Ci 6.34E-04 1.33E-04 25

-2.

Average diluted concentration during period

Ci/ml 1.01E-09 3.12E-10 3.

Percent of technical specification limit (T.S. 3.11.1.1) 5.06E-04 1.56E-04 D. Grois alpha activity 1.~ Total release (2)

Ci

0.00E+00 0.00E+00

.'E. Volume of waste release (prior to dilution -

Batch Release) liters 3.45E+06 2.45E+06 F. Volume of dilution water used during entire period liters 6.27E+08 4.21E+08 f

I '

N Fe", Sr*, and tr# anstyses for the 2nd gaerter are not evellable for inclusion in this report. Therefore, these second gJerter results are projected using the first omrter results.

M Gross Alphe snelyses for the 2nd gaerter are not evellable for inclusion in this report, f

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I HOPE CREEK GENERATING STATION TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1990 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2FJ Huclides Released Unit Quarter Quarter Quarter Quarter Sodium-24 Ci 0.00E+00 0.00E+00 0.00E+00 1.47E-05 Chromium-51 Ci 0.00E+00 0.00E+00 1.49E-02 5.55E-02 M:nganese-54 Ci 0.00E+00 0.00E+00 7.13E-02 7.79E-02 Iron-55 Ci 0.00E+00 0.00E+00 5.87E-01 4.17E-01 Cabalt-58 Ci 0.00E+00 0.00E+00 3.09E-03 1.85E-03 Iron-59 Ci 0.00E+00 0.00E+00 1.15E-02 1.75E-02 Ccbalt-60 Ci 0.00E+00 0.00E+00 1.54E-02 1.87E-02 Zinc-65 Ci 0.00E+00 0.00E+00 6.18E-02 1.80E-01 Strontium-89 Ci 0.00E400 0.00E+00 0.00E+00 0.00E+00 Strontium-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Strontium-92 Ci 0.00E+00 0.00E+00 5.62E-05 5.01E-04 Technetium-99m Ci 0.00E+00 0.00E+00 0.00E+00 3.36E-05 Silver-110m Ci 0.00E+00 0.00E+00 1.64E-04 1.24E-03 Antimony-124 Ci 0.00E+00 0.00E+00 0.00E+00 1.49E-05 TOTALS Ci 0.00E+00 0.00E+00 7.66E-01 7.73E-01 Tritium 0.00E+00 0.00E+00 4.50E+00 3.17E+00 Xenon-133 0.00E+00 0.00E+00 8.43E-05 0.00E+00 Xenon-135 0.00E+00 0.00E+00 5.49E-04 1.33E-04 TOTALS 0.00E+00 0.00E+00 4.50E+00 3.17E+00 15

HOPE CREEK GENERATING STATION TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1990 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID WASTE SHIPPED OFFSIT" FOR BURIAL OR DISPOSAL (Not irradiated fuel) 6-month Est. Total 1.

Type of waste Unitsu) period Error, %

a.

Spent resins, filters, m3 1.26E+02 sludges, evaporator bottoms C1 1.73E+03 25 b.

Dry compressible waste, m3 2.40E+01 contaminated equipment.

Ci 4.40E+00 25 c.

Irradiated components, m3 0.00E+00 control rods Ci 0.00E+00 25 d.

Others (described):

m3 1.15E+01 Solidified Oil Ci 9.78E-02 25 3.

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

RESINS DAW OTHER

(%)

(Ci)

(%)

(Ci)

(%)

(C1)

Carbon - 14 0.04 6.92E-01 0.13 5.70E-03 0.00 0.00E+00 Iron - 55 22.5 3.94E+02 27.2 1.20E+00 70.8 6.93E-02 Manganese - 54 5.13 8.97E+01 5.77 2.50E-01 4.43 4.33E-03 Cobalt - 60 3.10 5.47E+01 2.17 9.55E-02 5.66 5.54E-03 Nickel - 63 0.00 0.00E+00 0.22 9.68E-03 0.59 5.77E-05 Zinc - 65 65.2 1.14E+03 49.6 2.18E+00 18.3 1.79E-02 Iron - 59 0.00 0.00E+00 2.34 1.03E-01 0.00 0.00E+00 Chromium - 51 2.75 4.81E+01 11.0 4.84E-01 0.00 0.00E+00 Cobalt - 58 0.00 0.00E+00 1.35 5.94E-02 0.00 0.00E+00 d)

Volumes are measured, activities are estimated 16

i HOPE CREEK GENERATING STATION 1ABLE 3 (CONT'D)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 990

\\

SOLID WASTE AND IRRADIATED TUEL SHIPMENTS 3e Solid Waste Disposition Number of Mode of Type of Shipments Transportation Destination Containers 16 Truck Barnwell, SC HIC 23 Truck Barnwell, SC 17C Drums Richland, WA 17C Drums 1

Truck 4.

IRRADIATED TUEL SHIPMENTS (Disposition)

Number of Mode of

' shipments Transportation Destination NONE N/A N/A 17

h HOPE CREEK GENERATING STATION TABLE 4A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1990

SUMMARY

SHEET FOR RADI0 ACTIVE EFFLUENTS RELEASED IN A' BATCH MODE BATCH RELEASES ONLY 1.

Datest January 1 - March 31, 1990 2.

Type of releaset Gas

'3.

Number of releases during the 1st Quartert 1 4.

Total time duration for all releases of type listed abovet 9435 minutes 5.

Maximum daration for release of type listed abovet 9435 minutes 6.

Average duration for release of type listed abovat 9435 minutes 7.

Minimum duration for release of type listed abovet 9435-minutes 8.

Average _ stream flow (dilution flow)* during the period of releaset N/A 18

t i

HOPE CREEK GENERATING STATION TABLE 4A (CONT'D)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1990

SUMMARY

SHEET FOR RADI0 ACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY 1.

Dates:

April 1 - June 30, 1990 2.

Type of release Gas 3.

Number of releases during the 2nd Quarter 0

.4.

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

O minutes 5.

Maximum duration for release of type listed above:

0 minutes 6.

Average duration for release of type listed above O minutes 7.

Minimum duration for release of type listed above:

O minutes 8.

Average stream flow (dilution flow) during the period of releaset N/A 4

19 1

l' HOPE CREEK GENERATING STATION TABLE 4B EFFLUENT'AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1990

SUMMARY

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

1.._

Dates:

January 1 - March 31, 1990

.2.

Type of release:

Liquid

3..

Number of releases during the 1st Quarter: 83 4.-

Total time duration for all releases of type listed above 17392 minutes Maximum duration for release of type listed above

5..

.1615 minutes 6.

Average duration for release (* type listed above:

210 manutes

-7.

Minimum duration for release of type listed above 70 minutes 8.

Average stream flow (dilution flow) during the period of release: 26630 'gpa 20 i

--_---w----

i HOPE CREEK GENERATING STATION TABLE 4B (CONT'D) s EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY ~ JUNE 1990

SUMMARY

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

Dates:

April 1 - June 30, 1990

. 2.

Type of release Liquid 3.

Number of releases during the 2nd Quarters 54 4.

Total time duration for all releases of type listed above 14194 minutes 5..

Maximum duration for release of type listed above 1026 minutes

~ 6.

Average duration for release of type listed abovet 263 minutes 7.

Minimum duration for release of type listed above 69 minutes

- 8.

Average stream flow (dilution flow) during the period of release: 25561 gpm.

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ll TABLE FIVE PAGE 9 of 9 ARTIFICIAL ISLAPD 1/90 - 3/90 JOINT DISTRl8Ull(Pt OF Ulle DIRECTION AND SPEED SY ATICSPIERIC STABILITY CLASS Ulle: 300 FT DELTA T: (300-3NT)

DIRECil0N VS SPEED GE.Y VffS SPEE0 GIOUPS (9690) 0.0-0.5 0.4-3.5 3.6-T.5 T.4-12.5 12.6-18.5 18.6-24.5 F 24.6 sun PHICENT DIRECTIG8 S498PHICENT St90 PBICEDIT SA PEP M 9 91 P BtC Bli 381 N m Umy ggm N

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.Part C.

LIOUID' EFFLUENTS See Summary Tables 2A thru 2C.

Part-D.- SOLID WASTE See Summary in Table 3.

Part E.

RADIOLOGICAL IMPACT ON MAN,

The calculated individual doses in this section are based or actual locations of nearby residents and farms.

The population-dose impact is based on historical site specific

=

data 1.e.,

food production, milk production, feed for milch animals and-seafood production.

pi 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 coef ficients for the six month reporting interval.

Linuid Pathways Dones to individuals in the population from liquid releases-are primarily from the seafood ingestion pathway.

The total body dose to an individual was calculated-to be 4.51E-01 mrom.

The calculated highest organ dose from liquid releases was 1.03E+00 mrem.to the liver.

The calculated population total-body dose was 5.45E+00 person-rem.

The calculated average total body dose to the population within fifty miles of the j

site was 9.12E-04 mres/ person.

Air Pathways The resulting total body and skin doses to an individual were calculated to be'3.86E-02 arem and 6.38E-02 arem respectively.

The calculated population total body dose was 4.66E-01 person-ram.

The calculated population total body dcse to the population. within fifty miles of the site was 7.81E-05 mrem / person.

Direction Radiation Direct radiation may be estimated by thermoluminescent dosimetric (TLD) measurements.

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

It 7

HOPE CREEK GENERATING STATION TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1989 LIQUID EF7LUENTS-SUMMATION OF ALL RELEASES 3rd 4th Units Quarter Quarter Est. Total Error %

m 1.

Total release (not including I

2. Average diluted concentration 3.

Percent of appl.icable limit h

2.

Average diluted concentration

-1 3.

Percent of applicable limit 2.

Average diluted concentration 3.

Percent of applicable limit a

l. Volume of waste release - (prior i

7.

Volume of dilution water used A

J 12

~

I l'

l' HOPE CREEK GENERATING STATION TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1989 LIQUID EFFLUENTS Continuous McGe Batch Mode 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter -Quarter Sodium-24 Ci l'.17E-03 -2.82E-05

-s Chromium-51 Ci 6.14E-02 4.85E-02__

'Manaaname-54' Ci 9.83E-03 1.63E-01' Cobalt-58 C1 1.01E-03 9.90E-03 CQhplt-60 Ci 2.29E-03 3.34E-02

(

-Iron Ci-

' 3.' 2 4 E - 0 2 1.25E-01 LIron-59 C1 3.42E-03 4.60E.02 Zinc-65 C1 1.37E-02 '1.45E-01

. Arsenic =76 Ci 2.44E-05

~ Strontium-92 C1 1.40E-04 2.21E-04 Niobium-95 Ci 4.33E-06

Niobium-97_

Ci 2.14E-05

- Silver-110_.

Ci

~5.64E-04 5.25E-04

-- Cas ium-13 7 '

Ci 3.91E-06

. Totals Ci 1.26E-01' 5.40E-01 h

H-3 Ci 8.16E+00 6.34E+00 Xenon-133 C1 3.15E-04

Xanon-135 Ci 1.16E-03 6.12E-05 13

,

ML20059D258

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

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