Text

Semiannual Radioactive Effluent Release Rept for Jan-June 1990
	ML20059E759
Person / Time
Site:	Hope Creek
Issue date:	06/30/1990
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML20059E705	List: ML20059E702; ML20059E759;
References
	RERR-9, NUDOCS 9009100307
	Download: ML20059E759 (45)
	v • d • e

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HOPE CREEK GENERATING STATION SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HCGS RERR-9 DOCKET NO. 50-354 OPERATING LICENSE NO. NFP-57 1

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. -e HOPE CREEK GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1990 Table of Contents I

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 Lirits . . . . . . . 3 R 1.e Total Dose Limit . . . . . . . . . . . . . . . 3 1 2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) . . . . . 3 3.0 AVERAGE ENERGY . . . . . . . . . . . . . . . . . . 4 j 4.0 MEASUREMENTS AND APPROX 1MATION OF TOTAL i RADIOACTIVITY . . . . . . . . . . . . . . . . . . . 4 4.a Liquid Effluents . . . . . . . . . . . . . . . 4 4.b Gaseous Effluents . . . . . . . . . . . . . . 4 4.c Estimated Total Error . . . . . . . . . . . . 5 1 S.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 i

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 I

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HOPE CREEK GENERA ING STATION RADIOACTIVE EFFLUENT AELEASE REPORT JANUARY - JUhN 1990 L INTRODUCTION I

This report, HCGS-RERR-9, summarizes information pertaining to the rnleases of radioactive materials in liquid, gaseous and solid form from the Hope Creek Generating Station (HCGS) for the period 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 output of apptoximately 1067 MWe. The HCGS achieved initial criticality on June 28, 1986 and went into commercial operation on December 20, 1986.

L 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 sumr.arizing 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 of these composites will be provided in the next Radioactive Effluent Release Report.

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

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T PART A. PRELIMINARY SUPPLEMENTAL INFORMATION 1.0 REGULATORY LIMITS i 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 mrams/yr to the skin.

In addition, the air dose due to noble gases released in ,

gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to the'following:

i During any calendar quarter: -Less than or equal to 5 mrad for gamma radiation and less than or i equal to 10 mrad for beta radiation and, 1 During any calendar year: Less than or equal to l- 10 mrad for gamma radiation and less than or equal i to 20 mrad 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 following: j 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 mrams/yr to any organ.

In addition, the dose to a member of the public from iodine-131, from tritium, and from all radionuclides in l particulate form with half-lives greater than 8 days in

, gaseous affluents released, from each reactor unit, from the

( site to areas at and beyond the site boundary, shall be l limited to the following:

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During any calendar quarter: Less than or equal j to 7.5 mrems to-any organ and, 1

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 Release Limits -

The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limit to the i concentrations specified in 10 CFR, Part 20,. Appendix B, '

Table II, Column 2 for radionuclides other than dissolved or i ent sined noble gases. For dissolved or entrained noble .

gass.s, the concentratto:; shall be limited to 2E-4 microcuries per millil.ter.

In addition, the dose car dose commitment to a member of the ;

public from radioactive materials in liquid effluents ;

released to unrestricted areas shall be limited: l During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or k equal to 5 mrems to any organ, and !

During any calendar year to less than or equal to 3 mreas to the total body and to less than or i equal to 10 mrems to any organ.

1.e 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 I to less than or equal to 25 mrems to the total body or any I organ (except the thyroid, which shall be limited to less than or equal to 75 mrems).

2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)

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

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

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

Release limits for HCGS are not based upon average energy.

Therefore this section is not applicable to HCGS.

4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY 4.a Liquid F.ffluents Liquia effluents are monitored in accordance with Table ,

4.11.1.1.1-1 of the Technical Specifications. During the period of record, all liquid wastes were rerouted to the sampling tanks for monitoring prior to release. Technical Specifications require these tanks to be uniformly mixed for sampling and analysis before being released. Batch releases are defined as releases from the equipment drain sample tanks, floor drain sample tanks, detergent drain tanks, and condensate storage tanks. There are no continuous liquid i releases for this reporting period. The preponderant gamma emitting isotopes detected in sampling were Fe-55, Mn-54 and i 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) dischargnd.

The detection requirements of Table 4.1.1.1-1 of the Technical Specifications are achieved or exceeded. Nuclides existing at concentrations below the achieved detection -"

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

4.b Gaseous Effluents Gaseous effluent streams are monitored and sampled in accordance-with Table 4.11.2.1.2-1 of the Technical Specifications. The north plant vent (NPV) and south plant vent-(SPV) are the final releasa points for most planned gaseous effluent releases. A small quantity of gaseous affluent will be released via the filtration, recirculation, and ventilation cystem (FRVS) vent during testing periods.

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 particulate and fixed charcoal filters; the FRVS has fixed particulate and charcoal filters. The filters and charcoal 4

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l are changed weekly, as'a minimum, and are analyzed on a multi-channel analyzer in the laboratory. The NPV and SPV are sampled monthly for noble gases and tritium.

The detection requirements of Tables 4.11.2.1.2- of the Technical Specifications are achieved or exceeda Isotopes I existing at concentrations below the achieved det - ation limit are treated as being present. Nuclides for which no

<ctivity was detected while meeting the required sensitivity i 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 entin sarpling period in order to ,

estimate the normal continuous release of radioactivity through the plant vent.

When monthly noble gas grab samples yield no detectable -

activity, continuous mode releases are quantified by integrating Radiation Monitor System readings above 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 l

methods from Section 2.0 and Appendix C of the Hope Creek -

ODCM.

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

Specific activities for each isotope are multiplied by the '

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

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 monitor's response is converted to a " specific activity" using historical efficiency factors. The " specific activity" is multiplied by tha volume of effluent discharged while the channel was in an alarm state in order to estimate '

the total activity discharged.

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

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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%. ;

i 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, p 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.- ;

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

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. -

8.0 MODIFICATION TO PREVIOUS-RADIOACTIVE EFFLUENT RELEASE REPORTS Our last report (RERR-8) did not include the quarterly Sr-89, Sr-90 and Fe-55 composite data for the fourth quarter of 1989. '

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

PART B. GASEOUS EFFLUENTS See Summary Taoles 1A through IC.

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PART C. LIQUID EFFLUENTS See Summary Tables 2A through 2C. I PART D. SOLID WASTE l

See Summary in Table 3.

PART E. RADIOLOGICAL IMPACT ON MAN 1

The calculated individual doses in this section are based on.

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 milk l

animals and seafood production.

, The doses were calculated using methods described in l l

Regu.'atory Guide 1.109 and represent calculations for the i six month reporting intervr.l. Individual doses from batch l and continuous releases were calculated using the annual averago historic meteorological dispersion coefficients as described in the Offsite Dose Calculation Manual.

Populat.\on doses were calculated using the meteorological dispersion coefficients for the six month reporting interval .

Liquid Fathways 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 mrem. The calculated highest organ dose from liquid 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 mrem / person.

Air Pathways The resulting total body and skin doses to an individual were calculated to be 1.88E-01 mrem and 4.08E-01 mrem respectively. The calculated highest organ dose due to radiolodines and particulates with at greater than eight day half-life was 6.82E-04 mrem to the liver. The calculated population total body dose was 4.74E-01 person-rem. The calculated average total body dose to the population within fifty miles of the site was 7.94E-05 mrem / person.

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Direct Radiation l 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 l 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 SS-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.- i PART 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 which:

(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 i

(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 Ce-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 outlined in the ODCM.

PART H. INOPERABLE' MONITORS During the reporting period, the offgas hydrogen monitors, which are governed by Technical Specification 3.3.~.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 obtain certain. components also played a key factor in the time required to complete the DCP.

Hydrogen analyzer 5738A1 was declared inoperable on January 25, 1990 at 1515 hours0.0175 days 0.421 hours 0.0025 weeks 5.764575e-4 months because the process-indicator had 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

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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 i switches OHAFSL-5743A1/A2. During the TM process, a four hour sunreillance was performed to verify that a positive flow pa.h 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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1 HOPE CREEK GENERATING STATION TABLE 1A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT i

JANUARY - JUNE 1990 GAS"OUS EFFLUENTS-SUMMATION OF ALL RELEASES ist 2nd Est. Totat Units Quarter Quarter Error % 03

A. Fission and Activation Gases ,

1. Total release Ci 4.30E+01 2.87E+01 25 i

2. Average release rate for period #Ci/sec 5.47E+00 3.65E+00

3. Percent of technical '

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 20

2. Average release rate for period pCi/sec 0.00E+00 0.00E+00

3. Percent of technical i specification limit (2) j (T.S. 3.11.2.3(a)) % 0.00E+00 0.00E+00 C. Particulates

1. Particulates with half-lives >8 days C1 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 i y

D. Tritium

1. Total Release Ci 0.00E+00 8.35E+00 25

2. Average release rate for period pCi/sec 0.00E+00 1.06E+00'

3. Percent of technical specification limit (2)

(T.S. 3.11.2.3(a)) % 0.00E+00 2.12E-06 UI For batch releases the eetlasted overett error is within 10%

U) todine, tritlun and perticutetes are treated as a group 11 l

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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 ist 2nd 1st 2nd i Nuclides Released Unit Quarter Quarter Quarter Quarter l

1. Fission Gases i Krypton-83m Ci 4.30E-01 2.87E-01 0.00E+00 0.00E+00 Krypton-85m C1 4.30E-01 2.87E-01 0.00E+00 0.00E+00 Krypton-87 Ci 1.72E+00 1.15E+00 0.00E+00 0.00Ev00 Krypton-88 Ci 1.72E+00 1.15E+00 0.00E+00 0.00E+00 Krypton-89 C1 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 2.1'5E+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 Ci 0.00E+00 0.00E+00 0.00E+Cs 0.00E+00

3. Particulates (U (half-live >8 days Cobalt-60 C1 1.66E-04 0.00E+00 0.00E+00 0.00E+00 Iron-59 Ci 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 C1 1.46E-03 2.73E-03 0.00E+00 0.00E+00 ID Follow up evolustion on the 1st and 2nd Quarter continuous mode isotopic sangle snelyses and quality

. control data revealed the presence of high background on the counting system detectors for these semples. In

' our judgement, no particulate activity was released. For conservatism, particulate activity determined trider these circumstances is being reported as activity released.

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I HOPE CREEK GENERATING STATION TABLE-1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1990 GASEOUS EFFLUENTS-ELEVATED RELEASES

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l Nuclide Releases 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter There were no elevated gaseous releases during this reporting period.

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l l HOPE CREEK GENERATING STATION

,. TABLE.2A I

EFFLUENT AND WASTE DISPOSAL SEMIANNUAT REPORT L JANUARY - JUNE 1990 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES ist 2nd Units Quarter Quarter Est. Total ,

Error %

. A. Fission and activation products

1. Total release (not including tritium, l gases, alpha) U) Ci 7.66E-01 7.73E-01 25 L 2. Average diluted concentration during period #Ci/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

1. Total release Ci 4.50E+00 3.17E+00 25

2. Average diluted concentration during period gCi/ml 7.12E-06 7.47E-06

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

noble gases

1. Total release Ci 6.34E-04 1.33E-04 25

2. Average diluted concentration during period pCi/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. Gross alpha activity

1. Total release . ca) Ci 0.00E+00 0.00E+00 E. Volume of waste release (prior to dilution -

Batch Ralease) liters 3.45E+06 2.45E+06 F. Volume of dilution water used during entire period liters 6.27E+08 4.21E+08 N Fe", Sr", and sr" enelyses for the 2nd cperter are not eveltable for inclusion in this report. Therefore, these second quarter results are projected using sne first cperter results.

A Gross Alphe enetyses for the 2nd cperter are not evellable for inclusion )n this report.

14

O HOPE CREEK GENERATING STATION TABLE 2B EFFLUFMT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1990 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Nuclides 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 Manganese-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 Cobalt-C8 Ci 0.00E+00 0.00E+00 3.09E-03 4.85E-03 Iron-59 Ci 0.00E+00 0.00E+00 1.15E-02 1.75E-02 Cobalt-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 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Strontium-90 Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Strontiu'a-92 C1 0.00E+00 0.00E+00 5.62E-05 5.01E-04 Technetium-9Cm 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 1.n t itony-12 4 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 Trj+.ium 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 4

4 i

15 ;

i

HOPE CREEK GENERATING STATION TABLE 3 EFFLUENT AND WASTE DISa0 SAL SEMIANNUAL REPORT 2

JANUARY - JUNE 1990 SOLIO WASTE AND IRRADIATED FUEL SHIPMENTS SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL l (Not irradiated fuel) 6-month Est. Total

1. Type of vaste Units") period Error, %

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

b. Dry compressible waste, m3 2.40E+01 contaminated equipment. Ci 4.40E+00 25

c. Irradiated componer.ts, m3 0.00E+00 !

control rods Ci 0.00E+00 25

d. Others (described): m3 1.15E+01 i Pslidified 011 Ci 9.78E-02 25

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

RESINS DAW OTHER

(%) (C1) (%) (Ci) (%) (Ci)

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 UI Volumes are measured, activities are estimated 16 l

l mm -mm-----mm- eisi e

l .

HOPE CREEK GENERATING STATION TABLE 3 (CONT'D)

EFTLUENT AND WASTE DISPOSAL SEMIANNUAL RENST JANUARY - JUNE 1990 SOLID WASTE *WD IRRADIATED FUEL SHIPMENTS

3. Solid Waste Disposition Number of Mode of Type of Shipments Transportation Destination Containers 16 Truck Barnwell, SC HIC 23 Truck Barnwell, SC 17C Drums 1 Truck Richland, WA 17C Drums i

4. IRRADIATED FUEL SHIPMENTS (Disposition)

, Number of Mode of Shipments Transportation Destination NONE N/A N/A l

1 i

17

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. Datast January 1 - March 31, 1990

2. Type of release: Gas

3. Number of releases during the 1st Quarter: 1

4. Total time duration for all releases of type listed abovat 9435 minutes

5. Maximum duration for release of type listad above:

9435 minutes

6. . Average duration for release of type listed above 9435 minutes

7. Minimum duration for release of type .isted abovet 9435 minutes

8. Average stream flow (dilution flow) during the period of 1 releaset N/A 1B

i e . 1 l

HOPE CREEK GENERATING STATION -!

TABLE 4A l (CONT'D)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1990 )

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED i IN A BATCH MODE l I

1 BATCH RELEASES ONLY

1. Dates: April 1 - June 30, 1990

2. Type of release: Gas )

l

3. Number of releases during the 2nd Quarter: 0 1

Total time duration for all releases of type listed above: 1 4.

0 minutes .

5. Maximum duration for release of type listed above:

0 minutes

6. Average duration for release of type listed above:

0 minutes

7. Minimum duration for release of type listed ar1ve:

0 minutes

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

19

i HOPE CREEK GENERATING STATION l TABLE 4B !

i' EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE .$.990 j

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE l

1 l

BATCH RELEASES ONLY l

1. Dates: January 1 - March 31, 1990 1

2. Type of release: Liquid

\

1 l 3. Number of releases during the 1st Quarter: 83 )

l

{

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

17392 minutes I

5. Maximum duration for release of type listed above: j 1615 minutes ,

6. Average duration for release of type listed above: !

210 minutes ]

7. Minimum duration for release of type listed above: )

70 minutes 1

8. Average stream flow (dilution flow) during the paried of release: 26630 gpa l

20

,. m u HOPE CREEK GENERATING STATION TABLE 4B

( CONT ' D)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1990

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEAS".S ONLY

1. Dates: April 1 - June 30, 1990

2. Type of release: Liquid

3. Number of releases during the 2nd Quarter: 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 above:

263 minutes

7. Minimum duration for release of type listed above:

69 minutes B. Average stream flow (dilution flow) during the period of release: 25561 gpa i

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O d AMENDMENT TO RERR 8 22

1 Part C. LIQUID 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 on 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.

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 month reporting interval.

Licruid 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 4.51E-01 mrem.

The calculated highest organ dose from liquid releases was 1.03E+00 mrom to the liver. The calculated population total body dose was 5. 4 5E+00 person-rem. The calculated average total body dose to the population within fifty miles of the site was 9.12E-04 mrom/ person.

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

The calculated population total body dose was 4.66E-01 person-ram. The calculated population total body dose to the population within fifty miles of the site was 7.81E-05 mram/ 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

I l HOPE CREEK GENERATING STATION TABLE 2A ;

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT i l

JULY - DECEMBER 1989 l

LIQUID EFFLUENTS-SUMMATION OF ALL P.ELEASES 3rd 4th Units Quarter Quarter Est. Total Error % l l

\

&& Fissiori and activation creducts ]

8. Totac release (not including I tritium, cases, aloha) (1) Ci 1.26E-01 5.40E-01 25

2. Average diluted concentration du'?ina cariod uCi/ml 1.13E-07 6.02E-07 30 Percent of appl.icable limit ,

IT.S. 3.11.1.2. (all 4 2.51E+00 2.79F+01 l B. Tritium

1. Total release ci 8.16E+00 6.34E+00 25 l

3. Average diluted concentration ,

durina caried uCi/ml 7.22E-06 7.01E-06

3. Percent of spplicable limit (T.S. 3.11.1.1) 4 2.41E-01 2.34E-01 C. Dissolved and entrained noble cases

2. Total release C1 1.48E-03 6.12E-05 25

3. Average diluted concentration release eeriod uCi/ml 1.31E-09 6.78E-11

3. Percent of applicable limit (T.S. 3.11.1.1) t 6.55E-04 3.39E-05 D. Gross alnha activity

1. Total release (2) Ci 0.00E+00 0.00E+00 E. Volume of waste release - (prior I to dilution - Ratch Relaana liters _LugyE+06 4.99E+06 F. Volume of dilution water used ,

durina antira naried liters 1.12E+09 8.96E+08 r

l 12 i

l - . _ . . _ . _ _ _ . . . _ _ _ _ __ _ _ _ _ _ _ _ _ _ _. . . . - _ . . - --.

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HOPE CREEK GENERATING STATION TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECEMBER 1989 LIQUID EFFLUENTS Continuous Mode Batch Mode i

3rd 4th 3rd 4th Nuclides Released- Unit Quarter Quarter Quarter Quarter !

Sodium-24 Ci _. 1.17E-03 2.825-05 Chromiu -51 Ci 6.14E-02 4.85E-02 '

Mang3nese-54 Ci 9.83E-03 1.63E-01 Cobalt-58 Ci _

1.01E-03 9.90E-03 ;

Cobalt-60 Ci 2.29E-03 3.34E-02 Iron-55 s- Iron-59 CL Ci 3.24E-02 3.42E-03 1.25E-01 4.60E.02

(

Zinc-65 C1 1.37E-02 1.45E-01 Arsenic-76 C1 2.44E-05 Strontium 42 Ci 1.40E-04 2.21E-04 Niorium'95 Ci 4,33E-06

/>

Niebium-97 Ci

2.14E-05 Silver-110 Ci 5.64E-04 5.25E-04 Cesium-137 Ci 3.91E-06 Totals ,

Ci 1.26E-01 5.40E-01 -l-H-3 Ci 8.16E+00 6.34E+00

' Xenon-133 Ci 3.15E-04 -

Xenon-ll' C1 1.16E-03 6.12E-05 l

i= 1 4

13 V

1

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ML20059E759

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SUMMARY

SUMMARY

SUMMARY

SUMMARY

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