ML20147D737

Semiannual Radioactive Release Rept,Jul-Dec 1987

ML20147D737
Person / Time
Site:	Hope Creek
Issue date:	12/31/1987
From:	Miltenberger S Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
HCGS-RERR-4, NLR-N88028, NUDOCS 8803040122
Download: ML20147D737 (34)

Text

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O 1987 HOPE CREEK GENERATING STATION SEMIANNUAL RADIOACTIVE PS C EFFLUENT RELEASE REPORT HCGS RERR-4 The Energy People DOCKET NO. 50-354 OPERATING LICENSE NO. NPF-57

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~ RADIOACTIVE EFFLUENT RELEASE REPORT-JULY l - DECEMBER 31,.1987-p

-HOPE CREEK GENERATI'G N STATIONJ

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HOPE CREEK GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT.

JULY - DECEMBER 1987 .

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. INTRODUCTION

. This report, HCGS-RERR-4, summarizes the releases of radioactive materials in liquid, gaseous and solid form from the Hope Creek Generating Station-(HCGS) for the period July 1, 1987'to December 31, 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 sumr.ary description of how measurements and approximations of the total activity discharged were developed.

1h> facilitate determination of compliance with 40CFR190 requirements, the following information on electrical output is provided.

HCGS generated 3,309,702 megawatt-hours of electrical energy (net) during the reporting period.

Results ot liquid and gadeous composites analyzed for gross alpha, Sr-89, Sr-90, and Fe-55 for the fourth 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.

The gross alpha, Sr-89, Sr-90, and Fe-55 analyses for the first half of 1987 (refer to RERR-3) have been completed, amended pages to RERR-3 are included in this report.

The average stream flow on Table 4B of RERR-2 and RERR-3 were inccrrectly reported. Amendments to RERR-2 and RERR-3 are included in this report.

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

For Iodine-131, Iodine-133, 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, tne dose to a member of the public from iodine-131, from tritium, and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the site to areas at and beyond the site boundary shall be limited to the following:

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

- During any calendar years Less than or equal to 15 mrems to any organ.

1.3 Liquid Effluents Release Limits The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 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 effluents released to unrestricted areas shall be limited:

During any calendar quarter to less than or equal g

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 radioact.vity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total bca, or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrems).

2.0 KAXIMUM PERMISSIBLE CONCENTRATIONb (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 particulates.

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.

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

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

4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY 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 were routed to the sampling tanks for monitoring prior to release. Technical Specifications require these tanks to be thoroughly mixed before sampling and anelysis before any releases are made. Batch releases are defined as releases from equipment drain sample tanks, floor drain sample tanks, detergent drain 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 wece 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.-l of the Technicial Specifications are achieved or exceeded. 1sotopes 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 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 particulates, 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

- 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 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 volume for the entire sampling period in order to estimate the normal continuous release of radioactivity through the plant vent.

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 2.0.

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.

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 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 25%.

Error estimates for releases where sample activity is

- below the detectable concentration levels are not included since error ostimates 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 ef tluents-Jare provided in' Tables 4A and 4B.-

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6.0- UNPLANNED RELEASES During1 this : reporting period there were no unplanned releases.

7.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS Our last report-(RERR-3) did not include the quarterly gross alpha, Sr-89, Sr-90, and Fe-55 composite data for the second quarter of 1987. Amended pages to RERR-3 are included at the end of this report.

Part B. GASEOUS EFFLUENTS See Summary Tables lA thru IC.

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

Part D. ' SOLID WASTE See Summary Table 3.

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 datazi.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 Of f site Dose Calculation Manual.

Population doses were calculated using the meteorological dispersion coefficients for the six month interval from July through December, 198 . ,

9 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 2.82E-01 mrem. The calculated highest organ dose from liquid releases was 6.29E-01 mrem to-the liver. . The calculated population total body dose was 3.32E+00 person-rem. The calculated average total body dose to the population within fifty miles of the site was 6.21E-04 mrem / person.

Air Pathways The resulting total body and skin doses to an individual were calculated to be-1.52E-2 mrem and 3.31E-2 mrem respectively. The highest organ dose due to radioiodines and particulates with half-lives greater than 8 days was 9.87E-02 mrem to the thyroid. The calculated population total body dose was 3.79E+00 person-rem. The calculated average total body dose to the population within fifty miles of the site was 7.04E-04 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 Salem and Hope Creek Generating Stations at Artificial Island.

TLD's at onsite locations 2S-2 and 58-1, which are 0.3 miles and 0.9 miles f rom the point of origin, averaged 4.5 and 4.0 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 away. 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 atmospheric stability class at the 300 foot elevation

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are provided for the third and fourth quarters of 1987 as Tables 5 and 6.

Part G. ODCM CHANGES Part H. MONITOR INOPERABILITY HOPE CREEK GENERATING STATION TABLE lA r EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY l - DECEMBER 31, 1987 t

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES b 3rd 4th Units Quarter Quarter Est. Total l

Error, t t

Fission & Activation Gases A.

t 1. Total release Ci . 83E+02 1.04E+02 25%

2. Average release rate for period uCi/sec 3.22E+00 9.05E-01

3. Percent o,t tech. specification limit (T.b. 3.ll.2.2(a))  % 2.50E+00 2.41E+00 B. Iodines

1. Total iodine-131 Ci 2.68E-05 8.61E-06 25%

I e 2. Average release rate for period uCi/sec 7.07E-07 3.86E-07

3. Percent of tech. specification 3.77E-01 2.81E-01 limit (1) (T.S. 3.11.2.3(a))  %

R C. Particulates

1. Particulates with half-lives >8 days Ci 0.00E+00 0.00E+00 25%

r 2. Average release rate for period uCi/sec 0.00E+00 0.00E+00 l 3. Percent of tech. specification E limit (1) (T.S. 3.11.2.3(a))  % 0.00E+00 E

4. Gross alpha radioactivity (2) Ci 0.00E+00 25%

v D. Tritium 254

1. Total release (1) Ci 5.96E+02 4.45L+02

2. Average release rate for period uCi/sec 1.57E+01 2.69E+00

3. Percent of tecn. specification y  % 3.77E-01 2.81E-01 e limit (1) (T.S. 3.ll.2.3(a))

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

(2) Alphaanalysesforthefourthquarterarenotavail$roup ble for inclusion

in this report.

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HOPE CREEK GENERATING STATION TABLE 1B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY 1 - DECEMBER 31, 1987 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Units Quarter Quarter Quarter Quarter

1. Fission Gases Krypton-83m Ci 1.64E+00 9.61E-01 Krypton-85m Ci 1.84E+00 9.61E-01 Krypton-87 Ci 7.34E+00 3.84E+01 Krypton-88 Ci 7.34E+00 3.84E+01 Krypton-89 Ci 4.96E+01 2.0E+01 Xenon-133 t'i 3.67t+00 1.92E+00 Xenon-135 Ci 9.18E+00 1.22E+01 1.75E-07 Xenon-135m Ci 1.10E+01 5.77E+00 Xenon-137 Ci 5.69E+01. 2.98E+01 Xenon-138 Ci 3.49E+01 1.83E+01 Total For Period Ci 1.83E+02 9.62E+01 1.75E-07

2. Iodines lodines-131 Ci 2.68E-05 8.61E-06 Total For Period Ci 3.75E-04 8.61E-06 -

3. Particulates (Half-lives > 8 days)

Sodium-24 C1 Chromium-51 C1 Manganese-54 Ci Cobalt-58 C1 Cobalt-60 Ci Iron-59 C1 Zinc-65 Ci Strontium-89 Ci Strontium-90 Ci Gross Alpha Ci Total For Period Ci 0.00E+00 0.00E+00

4. Tritium Tritium Ci 5.96E+02 4.45E+02 Y . - _ _

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. HOPE CREEK: GENERATING STATION TABLE 1C

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT ,

JULY l - DECEMBER.31, 1987

-GASEOUS EFFLUENTS-ELEVATED RELEASES

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l HOPE CREEK GENERATING STATION TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY l-- DECEMBER 31, 1987 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 3rd 4th Units Quarter Quarter Est. Total Error, %

A. Fission and activation products

1. Total release (not including tritium, cases, alpha) Ci 2.75E-01 2.17E-01 25%

2. Average diluted concentration during period uCi/ml 8.96E-08 7.08E-08

3. Percent of applicable limit (T.S. 3.ll.1.2.(a))  % 1.00E+01 8.60E+00 B. Tritium

1. Total reletse C1 4.70E+00 3.08E+00 25%

2. Average diluted concentration during period uCi/ml 1.54E-06 1.00E-06

3. Percent of applicable limit (T.S. 3.11.1.1)  % 5.38E-07 5.01E-07 C. Dissolved and entrained noble cases

1. Total release Ci 5.01E-03 1.96E-02 25%

2. Average diluted concentration

.during period uCi/ml 1.63E-09 1.14E-08

3. Percent of applicable limit (T.S. 3.11.1.1)  % 8.15E-4 5.70E-03 D. Gross alpha radioactivity

1. Total release (1) Ci U.00E+00 25%

E. Volume of waste release (prior to dilution - Batch Release) liters 1.48E+07 1.18E+07 25%

F. Volume of dilution water used 1.70E+09 during entire period liters 3.05E+09 25%

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

HOPE CREEK GZNERATING STATION TABLE 2B EFFLUENT AND WASTE DISPOfAL SEMIANNUAL REPORT-JULY l - DECEMBER 31, 1987 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter Antimony-122 C1 1.02E-05 3.99E Antimony-124 Ci 5.81E-05 Ci 7.68E-03'~~9,14E-03 Cobalt-58 Cobalt-60 Ci 3.35E-03 6.04E-03 Chromium-51 Ci 5.41E-07. 3.75E-02 Cesium-137 Ci -

7.25E 4.73E-00 Iron-59 Ci ,

1.09E-03 3.20E-03 l Iodine-131 Ci 2.68E-05 2.57E-05

' I od i ne-13 3 C1 5.34E-04 5.65E-04 Manganese-54 Ci 4.30E 03 1.15E-02 Manganese-56 . Ci 1.79E-05 Mercury-203 Ci ~

G.18E-06 2.47E-06 Molybde num-99 Ci 5.1611-04 4.85E-04 Nickel-65 Ci 3.302-05 8.52E-08 Niobium-95 Ci 9.21E-06 Niobium-97 C1 1.39E-04 3.32E-05 Ruthenium-106 Ci 1.09E-05 Sodium-24 Ci 1.25E-01 9.86E-02 Strontium-92 Ci 2.63E-05 Technetium-99m Ci 2.24E-03 1.24E-03 Tellurium-132 C1 1.36E-05 2.80E-06 Technetium-100 Ci 1.62E-05 2.04E-05 '

Yttrium-91 Ci 2.78E-03 2.85E-05 Yttrium-91m Ci 8.06E-03 1.61E-03 Zinc-65 C1 6.31E-02 4.69E-02 Zinc-69 Ci 1.08E-03 8.93E-05 Zirconium-97 C1 2.35E-05 Unidentified Ci 5.77E-04 2.45E-04 Total ( Above ) Ci 2.75E-01 2.17E-01 t

4 HOPE CHEEK GENERATING STATION TABLE 2'd (Continued)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JJLY l - DECEMRER 31, 1987 LIQUID EFFLUENTS CONTINUOUS HODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Ocarter Quarter Quarter ~ Quarter

, Tritium Ci ,_

4.70E+00 3.08E+00 X7non-131m C1 7.84E-06 Xmnon-133 Ci 1.70E-04 2.23E-03 X7non-133m Ci -1.67E-05 2.37E-05 Xonon-135 C1 2.67E-03 4.81E-03 X,non-135m C1 9.58E-05 Krypton-85 Ci 1.00E-04 1.13E-02 Krypton-85m Ci 2.39E-06 Krypton-87 C1 3.16E-05 Argon-41 C1 5.10E-04 1.07E-03

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HOPE CREEK GENERATING STATION TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY l'- DECEMBER 31, 1987 SOLID WAST 2 AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiatec fuel) 6-month Est. Total Units Period Error, %

li Type of Waste

c. Spent resins, filters sludges, m3 1.22E+02 25%

evaporator bottoms Ci 2.95E+02

b. Dry compressible waste, m3 3.42E+Cl 25%

contaminated equipment C1 2.43E+00

c. Irradiated components, m3 I

control rods Ci

d. Others (Describe) m3 Solidified 011 Ci

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

Resin DAW (Ci)' s (Ci)

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18.d4% 5.55E+01 62.38% 1.52E+00 Chromium-51 9.02% 2.20E-01 M nganese ,54 6.27% '2.44E+01 Iron-55 5.43% 1.60E+01 7.67% 1.87E-01 Iron-59 3.45% 1.02E+01 2.56% 6.23E-02 Cobalt-58 4.41% 1.30E+01 14.61% 3.55E-01 Cobnit-60 5.69% 1.68Et01 2.10% 5.12E-02 , s Nicke -59 s Nickel-63  % 0.01% 1.57E-04 Zinc-65 52.77% 1.55E+02 1.63% 3.98E-02 Tritium-3 0.03% 7.61E-02 Cnrbon-14 0.00% 9,51E-03 0.01% 2.29E-44 Zirconium-95  %

Niobium-94 0.00% 9.39E-03 Tnennetium-99 _

% 0.01% 1.82E-04 Silver-110m s Antimony-124  %

Cnnium-137 .

0.05% 1.44E-01 Cnrium-144  %

L*nthanum-140  %

Borium-140 t Pu-239, 240 Am-241., Cm-243, 244 t _. __. __ _

Pu-238 .i Plutonium-241 _U.0!% 3.38E-02 1-129, Pu-238, 239, 240 Am.241,,Cm-242, 243 and 244  %

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[*,,1c-HOPE CREEK GENERATING-STATION TABLE 3-(Continued)-

s D' EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY 1 - DECEMBER 31, 1987 SOLID WASTE AND IRRADIATED FUEL SHIP),'ENTS e ,,

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• 3, Solid Waste Disposition Lllj

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Number of Shipments Mode of Transportation De st ination 20 Truck Barnwell 1 Truck Richland D. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination e

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L-HOPE CREEK GENERATING STATION TABLE 4A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

' JULY l - DECEMBER 31, 1987

SUMMARY

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

1. Dates: July 1, 1987 - September 3U, 1987

2. Type of release Gas

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

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

2329 minutes

5. Maximum duration for releases of type listed above 2329 minutes

6. Average duration for all releases of type listed above 2329 minutes

7. Minimum duration for release of type listed above 2329 minutes

'8. The average stream flow (dilution flow) during the period of release:= N/A d- -- .._

HOPE CREEK GENERATING STATION TABLE'4A

'(Cont'd)

EFFLUENT AND - W/iS'.* E DISPOSAL SEMI ANNUAL REPORT JULY 1 - DECEMBER 31, 1987

SUMMARY

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

1. Dates: October 1, 1987 - December 31, 1987

2. Type of release Gas

3. Number of releases during the 4th Quarter 2

4. Total time duration for all releases of type listed above 10,379 minutes

5. Maximum duration for releases of type listed above 8,879 minutes

6. Average duration fcr all releases of type listed above 5,189 minutes

7. Minimum duration for release of type listed above 1,500 minutes

8. The average stream flow (dilution flow) during the period of releases N/A O

• HOPE CREEK GENERATING STATION' TABLE 4B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY l - DECEMBER 31, 1987

SUMMARY

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

1. Dates: July.1, 1987 - September 30,-1907

2. Type of release: Liquid

3. Number.of releases during the 3rd Quarter: 311

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

59,886 minutes

5. Maximum duration for releases of type listed above:

925 minutes

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

193 minutes

7. Minimum duration for release of type listed above 53 minutes

8. The average stream flow (dilution flow) during the period of release: 1.2E+04 gpm I

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1: . t 4 1-f HOPELCHEEK GENERATING STATION' TABLE 4B

' (Cont'd) sEFFLUdNT AND' WASTE DISPOSAL SEMIANNUAL REPORT-

. JULY 1 - DECEMBER 31, 1967

SUMMARY

SHEET FOR' RAD 10 ACTIVE EFFLUENTS RELBASED IN A BATCH MODE BATCH RELEASES ONLY

1. Dates: October 1, 1987 - December 31, 1987 2.. Type of release: Liquid 3.-~ Number of releases during the 4th-Quarters -253

'4. Total time duration for~all releases of type listed above 48,141 minutes

. i.- Maximum duration for releases of type listed above: '

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

190 minutes ~

7. Minimum duration for release of type listed above: 47 minutee

8. The average stream flow (dilution flow) during the period ot ,

release: 1.2EtV* gpm

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h EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT f.. ' I JANUARY l - JUNE 30, 1987 L . '- ~ f fl ";

bg' i

& LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES C.: i 7

i 1st 2nd Units Quarter Quartar Est. Total E Error, t l "/

L- -

? 0 E A. Fission and activation products

1. Total release (not including (

T

' tritium, gases, alpha) Ci 3.80E-01 6.80E-01 23% fp.;l

2. Average diluted concentration if

[' during period uCi/ml 9.16E-08 3.50E-07 p;1 j b f f

3. Percent ot applicable limit f  % 12.10 8.12

, (T.S. 3.11.1.2.(a)) g.g%

>.2 B. Tritium /,.y 1.66E+00 Ci 9.36E-02 25% ' 'r i 1. Total release 'i 'y

2. Average diluted concentration during period uCi/ml 2.25E-06 8.54E-07 f. ( '

7 (app

3. Percent of applicable limit  %

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

h

$ C. Dissolved and entrained noble gases Ci 4.12E-03 1.15E-02 25%

F 1. Total release r 2. Average diluted concentration during period uCi/ml 9.92E-10 5.94E-09 i

k 3. Percent of applicable limit  %

(T.S. 3.11.1.1) 4.96E-04 2.97E-03 7

D. Gross alpha radioactivity 7 Ci 0.00E+00

1. Total release (1)

[

~

E. Volume of waste release (prior to dilution - Batch Release) liters 7.95E+06 1.21E407 25%

=

F. Volume of dilution water used

during entire period liters 4.14E+09 1.93E+09 25% -

O E

i 6 ,

(

w.._ _- [

HO ' CREEK GENERATING STATION

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! gy:

TABLE 2B [j rh p.n . qq EFFLUENT AND WAST E DISPOSAL SEMIANNUAL REPORT  %.[ h JANUARY l - JUNE 30, 1987 M, r6 aJ f -

LIQUID EFFLUENTS rammisaN CON 1INUOUS MUDE BATCH MODt' .i 2nd 1st 2nd 1st .

Nuclides Released Unit Quarter Quarter guarter Quarter l _ _ _ _ _

Antimony-122 C' 6.42E-04 1.31E-04 Antimony-124 C1 5.49E-03 9.67E-04 Antimony-125 C1 1.74E-04 Barium-139 Ci 1.26E-05 5.39E-02 2.46E-02 Cobalt-58 C1 C1 1.70E-02 1.lbE-02 ,

~'~~ Cobalt-60 C1 1.74E-01 1.03E-01 -

Chromium-51 Cesium-137 C1 2.65E-U7 9.62E-04 k"?'

Copper-64 C1 -

1ron-55 Ci 2.54E-02 tron-59 C1 3.43E-02 1.29E-02 Iodine-131 C1 1.24E-04 Iodine-133 C1 1.93E-04 1.64E v3 Manganese-54 ,

Ci 2.99E-02 1.76E-02 Ma ng a ne se- 5 6 C1 8.40E-05 3.01E-05 Mercury-203 7- 1.60 ;-05 1.64E-04 ..

Molybdenum-99 C1 1. 4 6 E -_0_3 9.60E-03 Nickel-65 Ci 3.49E-08 1.23E-02 5.38E-05 H Niobium-95 Ci hiobium-97 Ci 8.34E-T4 8.86E-04 ..

P.34E-04 Neptunium-239

~

4.97E-04 Selenium-75 C1 2.78E-04 1.25E-04 Sr d i um- 2 4 t 1 2.07E-02 3.28E-Ul =

! Strontium-69 C1 ._ 4.blE-U3 C1 4.35E-06 Strontium-92 Technetium-99m Ci 9.79E-04 8.61E-03 Tellur2um-132 C1 8.02E-05 1.6zE-04 Tungsten-187 C1 _

Y t t r i tim- 91 C1 2.10E-05 Yttrium-91m Ci 1. 0 4 E -0 2 7.94E-03 C1 2.ldE-02 4.18E-02 Zinc-65 Zinc-69 C1 9.69E-U5 2.llE-U3 Z irconlur -9 5 C1 -

1.41E-04 Zirconium-97 C1 3.54E-06 E Unide.it i t led C1 2.46E-03 8.65E-U4 Total (Above; C1 3.80E-01 6.80E-01

p

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i ll 2' HOPE. CREEK GENERATING STATION TABLE 4B g

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

'h

- JANUARY l - JUNE 30, 1987

SUMMARY

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

1. Da tes : January 1, 1987 - March 31, 1987

2. Type of releases. Liquid 3 Number of releases during the lat Quarter: 166

4. Total time duration for all releases of type listed above 44,839 minutes

5. Maximum duration for releases of type listed above:

1,037 minutes

6. A'arage duration for all releases of type listed above 211 ininutes

7. Minimum duration for release of type listed above: 86 minutes

8. The average stream flow (dilution flow) during the period of release: 1.20E+04 gpm 9

m_._ .. _ _.

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

EFr'LUENT 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 dura tion f or all releases of type listed above 60,274 minutes

5. Maximum duration for releases of type listed above:

1,222 minutes

6. Average duratt .. for all releases of type listed above 237 minutes

7. Minimum duration for release of type listed above 42 minutes.

8. The aversye strssm flow (dilution flow) during the period of release: 1.20E4at ., pm e

0 0

7 AMENDED PAGES TO HOPE CREEK RERR-2 1

4 HOPE CREEK GENERATING STATION TABLE 4B c EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY l - DECEMBER 31, 1986

SUMMARY

SHEET FOR RADIOACTIVE eft'LUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY

1. Dates: July 1, 1986 - September 30, 1986

2. Type of release: Liquid

3. Number of releases during the 3rd Quarter: 480

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

79,310 minutes

5. Maximum duration for releases of type listed above:

1,069 minutes

6. Average duration for all releases of type listed above 165 minutes >

7. Minimum duration for release of type listed above: 3 minutes'

8. Average stream flow (dilution flow) during the period of release: 1.20E+04 gpm i

f i

n

. . , ,r - _ ,

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

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY l - DECEMBER 31, 1986

SUMMARY

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

1. Dates: Oc tobe r 1, 1986 - December 31, 1986

2. Type of relesse: Liquid

3. Number of releases during the 4th Quarter: 405

4. Total time duration for all releases of type listed above 72,019 minutes

5. Maximum duration for releases of type listed above:

1,643 minutes

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

177.82 minutes

7. Minimum duration for release of type-listed above 3 minutes

8. Average stream finw (dilution flow) during the period of release: 1.20E+04 gpm b

9 9

9

4 W Public Service

- Electric and Gas Cc mpany E. Mittenberger Pubtc Service Electr P.O. Box 236. Hancocks Bridge, NJ 08038 609 339-4199 -

wucieer operatens FD 31988 NLR-N88028 United States Nuclear. Regulatory. Commission Document Control Desk-Washinoton, DC 20555 Gentlemen RADIOACTIVE-EFFLUENT RELEASE REPORT - 4 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 In 4ccordance with Section 6.9.1.7 of Appendix A to the Operating License for the Hope Creek Generatino Station (HCGS), Public Service Electric and Gas Company (PSE&G).hereby transmits one copy of the semi-annual Radioactive Effluent Release Report, RERR-4. This report summarizes liquid and caseous releases and solid waste shipments from the Hope Creek Generating Station for the period July 1 through December 31, 1987.

Should you have any questions regarding this submittal, please feel free to contact us.

Sincerely,

/ ls< t~

Attachments TE4 ff

' i 1

. o-- ,

, 'Documenticontrol Desk ~ 2 RE8 25 net l

C. Mr.-W. T.. Russell, Administrator-(2)

.USNRC Region 1I Mr. G. W. Rivenbark USNRC Licensing Project Manager Mr. R.-W. Borchardt USNRC Senior. Resident Inspector Mr. D. M.~ Scott, Chief

-Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 1

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _