ML20237K055

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Semiannual Radioactive Effluent Release Rept,Jan-June 1987
ML20237K055
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 06/30/1987
From:
Public Service Enterprise Group
To:
Shared Package
ML20237K032 List:
References
RERR-3, NUDOCS 8709040174
Download: ML20237K055 (49)
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%9 1987 HOPE CREEK GENERATING STATION PS G SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HCGS RERR-3 The Energy People -

DOCKET NO. 50-354 OPERATING LICENSE NO. NPF-57 m - .- , , e - , , . . - 1 y , < , , ,

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HOPE CREEK GENERATING STATION SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HCGS RERR-3 DOCKET NO. 50-354 OPERATING LICENSE NO. NPF-57

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SEPTEMBER 1987 i i

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j NPF-57 l

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l REPORT NO. HCGS-REKR-3 I

RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY 1 - JUNE 30, 1987 HOPE CREEK GENERATING STATION Public Service Electric and Gas Company  :

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HOPE CREEK GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - JUNE 1987

INTRODUCTION .

-This report,~HCGS-RERR-3, summarizes the releases of radioactive materials.in liquid, gaseous and solid form from the Hope Creek Generating Station (HCGS) for the period January 1, 1987 to June 30,'1987.

.The 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 measurements and approximations of the total activity discharged were developed..

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

, provided.

HCGS generated 3,951,255 megawatt-hours of electrical energy

-( ne t ) during the reporting period.  !

Results of liquid and gaseous composites analyzed for gross alpha, Sr-89, Sr-90, and Fe-55 for the second quarter of 1987 were not available for inclusion in this report. The results of these composites will be provided in the next Radioactive Effluent Release Report.

l The gross alpha, Sr-89, Sr-90, and Fe-55 analyses for the second I half of 1986 (refer to RERR-2) have been completed, amended pages to RERR-2 are included in this report.

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Part'A. ' PRELIMINARY SUPPLEMENTAL INFORMATION 1.0 REGULATORY LIMITS 1.1 Noble Gases-Release Limits The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:

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

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

During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, During any calendar year: Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

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

For Iodine-131, Iodine-133, for tritium, and for i 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 j in particulate form with half-lives greater than 8 l days in gaseous effluents released from the site to j areas at and beyond the site boundary shall be limited to the following:

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

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1.3 Liquid Effluents Release Limits The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to th'e concentrations specified in 10CFR, 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 l

effluents released to unrestricted areas shall be limited:

During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems 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 mrems to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrems).

2.0 HAXIMUM PERMISSIBLE CONCENTRATIONS (MPC)

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

a. MPC values were not used to determine the maximum release rates for fission gases, iodines, or particulate.
b. MPC values as stated in 10CFR20, Appendix B, Table II, Column 2 were used for liquids.
c. MPC value used for dissolved or entrained noble gases was 2E-4 microcuries per milliliter.

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l 3.0 AVERAGE ENERGY' Regulatory Guide 1.21 requires that the licensee provide

. the average energy.of the radionuclides mixture in releases of fission and activation gases, if applicable.

i Release limits for the HCGC are not based upon average

. energy,.hence, this section does not apply.

l 4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY l

4.1 Liquid 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 l were routed to the sampling tanks for monitoring prior to release. Technical Specifications require these tanks to be thoroughly mixed before sampling and analysis before any releases are made. Batch releases are defined as releases from equipment drain sample tanks, floor drain sample tanks, detergent drain i tanks, and condensate storage tanks. There are.no continuous liquid releases for this reporting period.

The preponderant gamma emitting isotopes detected in sampling were Cr-51, Na-24, and 2n-65. Specific ,

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

The detection requirements of Table 4.11.1.1.1.-1 of the Technicial Specifications are achieved or exceeded. Isotopes existing at concentrations below the achieved detection limit are treated as not being present.

4.2 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

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plant vent (SPV) are the final release points for most planned gaseous effluent releases. A small quantity of gaseous effluent will be released via the Filtration, Recirculation, and Ventilation System (FRVS) vent during testing periods. The NPV and SPV are continuously monitored for particulate, iodines, and noble gases; the FRVS is continuously monitored for noble gases. The NPV and SPV have moving particulate and fixed iodine filters; the FRVS has fixed particulate and iodine filters. The filters are changed and analyzed at least weekly when releases are l

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

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The detection requirements of Tables 4.11.2.1.2-1 of the Technical Specifications are achieved or exceeded. Isotopes existing at concentrations below the achieved detection limit are treated as not being present.

Continuous Mode gaseous releases are quantified by routine (monthly) sampling and isotopic analyses of the pla'nt vents. Specific activities for each isotope detected during the routine sampling are adjusted using the rsdiation monitoring readings to obtain an average concentration for the period. This average concentration is then multiplied by the total vent flow volume for the entire sampling period in order to i estimate the normal continuous release of-  !

radioactivity through the plant vent. j i

When monthly noble gas grab samples yielded no detectable activity, continuous mode releases were quantified by integrating Radiation Monitoring System readings above background. Noble Gas Isotopic ,

abundances for these integrations were based on the )

ANSI mix for BWR's. Doses calculated from this data )

employed the methods of the Hope Creek ODCM Section 1 2.0. l l

Batch Mode _ gaseous releases (primary containment purge) are quantified by pre-release sampling and isotopic analyses. Specific activities for each isotope are multiplied by the total purge flow volume in order to estimate the batch release of radioactivity through the plant vent. i 4.3 The estimated total error of reported liquid releases is within 25%.

The estimated total error of the reported continuous gaseous releases is within 25% when concentrations exceed detectable levels. This error is due primarily l to variability of waste stream flow rates and changes i I

in isotopic distributions of waste streams between sampling periods. The estimated total error of the reported batch gaseous releases is within 25%. l l

Error estimates for releases where sample activity is ,

below the detectable concentration levels are not l included since error estimates at the LLD are not j defined. l l

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

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5.0 BATCH RELEASES Summaries of batch rel' eases of gaseous and liquid effluents

~a re provided in' Tables 4A and 4B. R 6.0 UNPLANNED RELEASES During this reporting period there were no unplanned releases.

7.0 . MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS Our.last report (RERR-2) did not include the quarterly gross alpha, Sr-89, Sr-90, and Fe-55 composite data for the

. fourth quarter of 1986. Also, the population total body dose reported was overly conservative and in error.

Amended pages to RERR-2 are included at the end of this report.

Part B. GASEOUS EFFLUENTS See Summary. Tables IA thru 1C.

Part C. LIQUID EFFLUENTS See Summary Tables 2A and 28.

Part D. SOLID WASTE See Summary 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 i.e., food production, milk production, feed for milh animals, and seafood production.

The doses were calculated using methods described in Regulatory Guide 1.109. 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 interval from January through June, 1987.

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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 l 1.98E-01 mrem. The calculated highest organ dose from {'

liquid releases was 8.700-01 mrem to the liver. The calculated population total body dose was 6.30E-02 .

person-rem. The calculated average total body dose to the I population within fifty miles of the site was 1.18E-05 mrem / person.

Air Pathways The resulting total body and skin dosos to an individual )

were calculated to be 4.38E-01 mrem and 4.61E-01 mrem  !

respectively. The highest organ dose due to radiciodines f and particulate with half-lives greater than 8 days was 1.21E+00 mrem to the thyroid. The calculated population total body dose was 1.00E+01 person-rem. The calculated average total body dose to the population within fifty miles of the site was 1.87E-03 mrem / person.

Direct Radiation Direct radiation may be estimated by thermoluminescent dosimetric (TLD) measurements. One method for comparing TLD measurements is by comparison with preoperational data. It should be noted that the TLDs measure direct radiation from both the Salen 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 4.5 and 4.2 mrads/ month respectively. The values for stations 25-2 and SS-1 are within the statistical variation associated with the preoperational program results.

It should be noted that the nearest resident is 3.5 miles away. It can thus be concluded that there was no i measurable dose to any offsite location from direct radiation.

I' Part F. METEOROLOGICAL DATA i I Cumulative joint wind frequency distributions by

, atmospheric stability class at the 300 foot elevation are provided fcr the first and second quarters of 1987 as Tables 5 and 6.

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Pert G. ODCM CHANGES The Hope Creek Offsite Dose Calculation Manual (ODCM) was j revised twice and the revisions used for this report. l These revisions were reviewed by the Station Operating {

Review Committee (SORC) in March and August 1987 and j accompany this report.

Part H. MONITOR INOPERABILITY j During the reporting period the South Plant Vent flow rate j monitor was out of service from May 1, 1987 to June ll, j 1987. This exceeded the Technical Specification 3.3.7.10 1 30 day inoperability which requires a report in this ]

semiannual report. The monitor was declared out of service j due to low flow from the pump it monitors. Because of the  !

unique design of this pump no parts were in stock and a {

special order was needed. On June 11, 1987 the monitor was j declared back in service. As per the action statement of i Technical Specification Tabl.e 3.3.7.10-1 sampling flow rate l was estimated at least once per four hours.

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HOPE CREEK GENERATING STATION TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY l - JUNE 30, 1987 GASEOUS EFFLUENTS-ELEVATED RELEASES There were no elevated releases during this reporting period.

HOPE CREEK GENERATING STATION 1

TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY l - JUNE 30, 1987 l l

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES lst 2nd Units Quarter Quarter Est. Total Error, %

A. Fission

1. Total release (not including

) Ci 4.03E-01 6.86E-01 25%

2. Average diluted concentration 1
3. Percent of applicable limit (T.S. 3.11.1.2.(a))  % 12.10 8.12
s. Tritium
1. Total release Ci 9.36E-02 1.66E+00 25%
2. Average diluted concentration uCi/ml 2.25E-06 8.54E-07
3. Percent of applicable limit  %

(T.S. 3.11.1.1) 7.50E-02 1.95E-02

1. Total release Ci 4.12E-03 1.15E-02 25%
2. Average diluted concentration l
3. Percent of applicable limit  %

(T.S. 3.11.1.1) 4.96E-04 2.97E-03 3 Gross alpha radioactivity

1. Total release (1) Ci 0.00E+00
3. Volume of waste release (prior to dilution - Batch Release) liters 7.95E+06 1.21E+07 25%

?. Volume of dilution water used

___ d 1.93E+09 25%

(1) Gross Alpha analyses for the second quarter are not available for inclusion in this report.

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HOPE CREEK GENERATING STATION.

j TABLE 2B i

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY l ' JUNE 30, 1987 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE i lst 2nd 1st 2nd

@es Released Unit Quarter Quarter Quarter Quarter I Rimony-122 Ci 6.42E-04 1.31E-04 Simony-124 Ci 5.49E-03 9.67E-04 Gimony-125 Ci 1.74E-04 a gium-139 Ci 1.26E-05 i' gium-141 Ci 1.04E-05 gium-143 Ci 7.43E-06 gium-144 Ci 2.33E-03 Balt-58 Ci 5.39E-02 2.46E-02 eAlt-60 Ci 1.70E-02 1.15E-02 gomium-51 C1 1.74E-01 1.83E-01 Gium-137 Ci 2.85E-07

ppar-64 Ci ~

9.62E-04

'@n-55 Ci 1.20E-03 2.92E-02 en-59 Ci 3.432-02 1.29E-02 dino-131 Ci 1.24E-04 dina-133 Ci 1.93E-04 1.64E-03 ingenese-54 Ci 2.99E-02 1.76E-02

,nganese-56 Ci 8.40CaOS 3.01E-05 treury-203 Ci 1.60E-05 1.64E-04

>1y bde num-99 Ci 1.46E-03 9.60E-03

.ckel-65 Ci 3.49E-08 obium-95 Ci 1.23E-03 5.38E-05

.obium-97 Ci 8.34E-04 8.86E-04

>ptunium-239 Ci 4.97E-04 8.34E-04

>nneodymium-144 Ci 1.84E-02

>1enium-75 Ci 2.78E-04 1.25E-04 dium-24 Ci 2.07E-02 3.28E-01

rontium-89 Ci 4.61E-03 1.58E-03
ron ti um-92 Ci 4.35E-06

>chnetium-99m Ci 9.79E-04 8.81E-03 gllurium-132 Ci 8.02E-05 1.62E-04 2ngaton-187 Ci strium-91 Ci 2.10E-05

trium-91m C1 1.04E-02 7.94E-03 inc-65 Ci 2.18E-02 4.18E-02 snc-69 Ci 9.89E-05 2.11E-03 krconium-95 Ci 1.41E-04 trconium-97 Ci 3.54E-06 Sidentified Ci 2.46E-03 8.65E-04 stal (Above) Ci 4.03E-01 6.86E-01

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HOPE CREEK GENERATING STATION 1

TABLE 2B j (Continued)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY l - JUNE 30, 1987 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE lst 2nd 1st 2nd Lides Released Unit Quarter Quarter Quarter Quarter )

i Fritium Ci 9.36E-02 1.66E+00 i Mnon-131m Ci 5.30E-05  !

Xnnon-133 Ci 6.23E-04 1.87E-03 :)

senon-133m Ci 3.22E-05 2.77E-05 1 6.03E-03 senon-135 Ci 2.16E-03 Mnon-135m Ci 7.52E-05 srypton-85 Ci 3.31E-04 i

[rypt.on-8 5m gi 1.15E-05 Krypton-87 Ci _

5.80E-06 Ci 1.22E-03 3.21E-03 hroon-41

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HOPE CREEK GENERATING STATION TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY l - JUNE 30, 1987 .

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS  !

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SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 6-month Est. Total ,

Typ3 of Waste Units Period Error, % l

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a. Spent resins, filters sludges, m3 264.9 25% l ovoporator bottoms Ci 6.52E+01 l i
b. Dry compressible waste, m3 0.00E+00 {

contaminated equipment Ci {

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c. Irradiated components, m3 0.00E+00 j control rods Ci j
d. Others (Describe) m3 0.00E+00 l Solidified Oil Ci (

l Estimate of major nuclide composition (For Type A and B waste) f i

Resin DAW Solidified Oil (Ci) (Ci) (Ci) ]

gomium-51 42.8% 2.79E+01 l aganese-54 17.0% 1.llE+01 l an-55 t l

@n-59 6.2% 4.08E+00

@ alt-58 17.8%~

7.9% 5.17E+00 {

Balt-60 i ekel-59  %

@kel-63 0.1% 6.93E-02 5.8% 3.BlE+00 l ac-65 itium-3 0.4% 2.49E-01 Rbon-14  % ~

Rconium-95 0.4% 2.62E-01

@bium-94 0.5% 3.05E-01 1@hnatium-99  %

lver-110m 0.6% 3.84E-01 itimeny-124 0.3% 1.68E-01 isium-137 0.1% 4.67E-02 trium-144  %

inthenum-140  %

1rium-140  %

1-239, 240 3-241, Cm-243, 244  %

1-238  %

,utonium-241 0.1% 1.37E-02

>129, Pu-238, 239, 240 B-241, Cm-242, 243 and 244  %

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i L 4 HOPE CREEK GENERATING STATION TABLE 3

[ (Continued)

EFFLUENT AND WASTE. DISPOSAL SEMIANNUAL REPORT JANUARY.1 - JUNE 30,<1987 p SOLID WASTE AND IFRADI ATED FUEL SHIPMENTS f

Solid Waste Disposition h ,

Number of Shipments Mode of Transportation Destination 12 7 Truck Barnwell j IRRADIATED. FUEL SHIPMENTS (Disposition)

Number of Shipments Mode o,f Transportation Destination N/A N/A N/A 4

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l HOPE CREEK GENERATING STATION I TABLE 4A EFFLUENT AND. WASTE _lSPOSAL SEMIANNUAL REPORT JANUARY l - JUNE 30, 1987 a

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE l

BATCH RELEASES ONLY

1. - Dates: January 1, 1987 - March 31, 1987
2. -Type of release: Gas
3. Number of releases during the 1st Quarter: 2
4. Total time duration for all releases of type listed above:

20,340 minutes

5. Maximum duration for releases of type listed above: 19,440 minutes
6. Average duration for all releases of type listed above:

10,170 minutes

7. Minimum duration for release of type listed above: 900 minutes
8. The averag? stream flow (dilution flow) during the period of release: N/A 1

e l

HOPE CREEK GENERATING STATION TABLE 4A (Cont'd)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY 1 - JUNE 30, 1987

SUMMARY

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

1. Dates: April 1, 1987 - June 30, 1987
3. Type of release: Gas
3. Number of releases during the 2nd Quarter: 0
4. Total time duration for all releases of type listed above:

0 minutes

5. Maximum duration for releases of type listed above:

0 minutes

6. Average duration for all releases of type listed above 0 minutes
7. Minimum duration for release of type listed above:

0 minutes

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

't 'i HOPE CREEK GENERATING STATION

' TABLE 4B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY l - JUNE 30, 1987

(

SUMMARY

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

1. Dates: January 1, 1987 - March 31, 1987
2. Type of releases Liquid.
3. Number of releases during the 1st Quarter: 166
4. Total time duration for all releases of type listed above:

44,839 minates

5. Maximum duration for releases of type listed above:

1,037 minutes

6. Average duration for all releases of type listed above:

270 minutes

7. Minimum duration for release of type listed above: 86 minutes
8. The average stream flow (dilution flow) during the period of release: 46.50 gpm

' !?il 4

HOPE CREEK GENERATING STATION TABLE 4B (Cont'd)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT ,

JANUARY l - JUNE 30, 1987

SUMMARY

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

1. Dates: April 1, 1987 - June 30, 1987
2. Type of release: Liquid - -
3. Number of releases during the 2nd Quarter: 254
4. Total time duration for all releases of type listed above:

60,274 minutes

5. Maximum duration for releases of type listed above:

1,222 minutes

6. Average duration for all releases of type listed above:

237 minutes

7. Minimum duration for release of type listed above: 42 minutes
8. The average stream flow (dilution flow) during the period of release: 53.29 gpm 5

1 e

' S O

AMENDED PAGES TO HOPE CREEK RERR-2 A

l l

.6 s

7.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS Our last report (RERR-1) did not include the quarterly gross alpha, Sr-99, Sr-90, and Fe-55 composite data for the first half of 1986. The results are less than detectable so no updating to the last report (RERR-1) are necessary.

Part B. GASEOUS EFFLUENTS See Summary' Tables lA thru 1C.

Part C. LIQUID EFFLUENTS See Summary Tables 2A and 2B.

Part D. SOLID WASTE Solid waste curie totals were determined by dose / curie method and are therefore conservative overestimates.

See Summary Table 3. p, Part E. RADIOLOGICAL IMPACT ON HAN 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 animals, and seafood production.

The doses were calculated using methods described in .

Regulatory Guide 1.109. 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 interval from July through December, 1986.

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 1.67E-02 mrem. The calculated highest organ dose from liquid releases was 3.90E-01 mrem to the gastrointestinal tract. The calculated population total body dose was l 1.25E-02 person-rem. The calculated average total body l dose to the population within fifty miles of the site was 2.31E-06 mrem / person.

Air Pathways _,

The resulting total body and skin doses to an individual were calculated to be 2.16E-01 mrem and 4.70E-02 mrem respectively. The highest organ dose due to radiciodines s

.0

and particulate with half-lives greater than 8 days was 8.57E-04 mrem to the thyroid. The calculated population total body dose was 1.08E-01 person-rem. The calculated average total body dose to the population within fifty miles of the site was 2.02E-05 mrem / person.

Direct Radiation Direct radia~ tion may be estimated by thermoluminescent dosimetric (TLD) measurements. One method for comparing TLD measurements is by comparison with preoperational data. It should be noted that the TLDs measure direct radiation from both the Salem and Hope Creek Generating Stations at Artificial Island.

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 4.9 and 4.6 mrads/ month respectively. The values for stations 2S-2 and SS-1 are within the statistical variation associated with the preoperational program results.

It should be noted that the nearest resident is 3.5 miles sway. It can thus be concluded that there was no measurable dose to any offsite location from direct radiation.

Part F. METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmt rpheric stability class at the 300 foot elevation areprovided for the third and fourth quarters of 1986 as Tables 5 and 6.

Part G. ODCM CHANGES The Hope Creek Offsite Dose Calculation Manual (ODCM) was extensively revised. These revisions were reviewed by the Station Operating Review Committee (SORC) and accompany this report.

Part H. MONITOR INOPERABILITY Or. September 16, 1986, during the period of concern, it was discovered that the Technical Specification Action l

Statement allowable time was exceeded for the inoperable North Plant Vent (NPV) flow rate monitor channel. The root cause of this event was personnel error. The Operations Department supervision failed to consider that a 31-day month was involved when calculating the allowable time that effluent releases could continue with inoperable instrumentation. Immediately upon discovery, all effluents to the NPV were isolated. Corrective action was to enter a caution in the Night order Book which directs that a 31-day month be considered whenever a calculation is made relative to Technical Specifications.

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HOPE CREEK GENERATING STATION TABLE 2A EFFLUENTn AND WASTE DISPOSAL SEMIANNUAL REPORT JULY l - DECEMBER 31, 1986 1

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 3rd 4th Units Quarter Quarter Est. Total Error, %

i Pission and activation products

.. Total. release (not including tritium, cases, alpha) Ci 6.10E-02 6.95E-01 25

!., Average diluted concentration

" durino period- uCi/ml 1.04E-08 1.64E-07 j

). Porcant~of applicable limit

- (T.S.-3.ll.l.2.(a))  % 1.76E-01 2.37E-02 l i

fritium

... Total release Ci 0.00E+00 6.91E-03 25 fJ 1.EAvercge diluted concentration during period uCi/ml 0.00E+00 1.63E-09

1. .Parcent of applicable limit  %

(T.S. 3.11.1.1) 0.00E+00 5.43E-05 1 j

)issolved and entrained noble cases

.. Total release Ci 4.55E-03 1.30E-02 25 j

!. Average diluted concentration durino period uCi/ml 7.77E-10 3.08E-09 L. Percent of applicable limit  %

(T.S. 3.11.1.1) 3.89E-04 1.54E-05 irons alpha radioactivity

. Total release (1) Ci 0.00E+00 0.00E+30 25 Blume.of. waste release (prior

@ dilution - Batch Release) liters 2.25E+07 1.92E+07 25 l

Bluma of dilution water used 5.82E+09 4.20E 09 25

!uring ent' ire period liters i

. 1 I

s

_--_--_____-_A

HOPE CREEK GENERATING STATION TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT )

JULY l - DECEMBER 31, 1986 l LIQUID EFFLUENTS l CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th id33 Released Unit Quarter Quarter Quarter Quarter nrium-139 Ci 4.30E-05 ,

arium-141 Ci 3.60E-06 3.09E-06 1 orium-143 Ci 2.45E-06 mrium-144 Ci 2.30E-0S 1.16E-04 '

obn1t-5 Ci 1.25E-02 1.05E-01 obnit-6 Ci 1.40E-05 1.05E-02 hromium-51 Ci 3.16E-02 1.60E-01 on lunT~1 o or-64 Ci 3.72E-04 i I

ron-55 Ci 6.53E-02 iron-59 Ci 3.79E-04 2.49E-02 Ci 1.79E-04 2.59E-04 modine-133 Ci 2.21E-04 1.74E-03

=enganese-54 Ci 9.01E-04 5.02E-02 mgannaanese-56 Ci 3.97E-03 2.42E-02 munolybdenum-99 Ci 7.54E-04 2.78E-03 EHEodium-24 Ci 5.56E-03 2.84E-01 maniobium-95 Ci 3.07E-06 6.68E-04 EEEiobium-97 Ci 4.37E-03 EEEnptunium-239 Ci 1.88E-04 4.60E-03 rasood ium-144 Ci 1.31E-03 uthenium-103 Ci 3.30E-06 ntimon -122 C1 4.14E-03 schnetium-99m Ci 1.03E-04 6.04E-03 ellurium-129m Ci 4.46E-03 311urium-132 Ci un sten-1 Ci 1.50E-05 ttrium-9 Ci 2.49E-03 ttrium-91m Ci 1.44E-03 2.36E-03 inc-65 Ci 1.11E-03 ritium Ci 6.90E-03 non- 3 m Ci 2.78E-05 2.30E-04 non-133 Ci 1.94E-03 2.72E-03 non-133m Ci 4.89E-04 1.64E-04 non- Ci 1.89E-03 5.72E-03 non-135m Ci 3.89E-03 ton-85 Ci 1.80E-04 ton-' m C1 . E-ton-87 Ci 1.42E-05 3.00E-04 on-41 Ci 2.45E-05

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