Text

Semiannual Radioactive Effluent Release Rept, Interim Rept for Jul-Dec 1980
	ML20003C603
Person / Time
Site:	Salem
Issue date:	03/31/1981
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML18085B002	List: ML18085B001; ML20003C603;
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	RERR-9I, NUDOCS 8103060552
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REPORT NO. RERR-97 i

UNIT NOS. 1& 2 1

RADIOACTIVE EFFLUENT RELEASE REPORT

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JULY - DEC 1980*

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i SALEM NUCLEAR GENERATING STATION

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Public Service Electric and Gas Company i

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Interim report pending the completion of additional analyses 1

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M P79 43/33 i

i Sto30 M CG

I SALEM NUCLEAR GENERATING STATION UNIT 1 50-272 UNIT 2 50-311 UNIT NOS. 1 AND 2 I

RADIOACTIVE EFFLUENT RELEASE REPORT July 1, 1980 to December 31, 1980*

I Introduction This report, RE RR-9 I, summarizes the release of radioactive materials in liquid, gaseous and solid form from the Salem Nuclear Generating Station Units 1 and 2 for the period I

July 1, 1980 to December 31, 1980.

As requested by the United States Nuclear Regulatory Commission (USNRC) this report was prepared in the format specified for all nuclear power plants as defined in USNRC Regulatory Guide 1.21.

Release of radioactive materials from the Salem station dur-ing the reporting period were within the limits set forth in the Environmental Technical Specifications.

Calculated radiation exposures to off-site individuals were small frac-tions of the limits set forth in 10CFR20 and within Appendix I to 10CFR50 and 40CFR190 requirements.

Unit 1 generated 1 612,953 megawatts-hour of electrical energy for the pet _od July 1, 1980 to December 31, 1980.

Unit 2 achieved initial criticality on August 2, 1980.

The power level of Unit 2 did not exceed 5% of rated power for the report period.

Results of several analyses were not available for inclusion in this report.

A revised report will be submitted when this data is available.

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Interim Report M P79 43/'3 -

I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT RERR 9I A.

SUMMARY

INFORMATION 1.0 Regulatory Limits Symbols utilized in the equations listed below under Sec-tions 1.1 and 1.2 are the same as those used in the Salem Environmental Technical Specifications (ETS).

The symbol 0 as explained in Section 2.3.3 of the Et is the release rate of the gaseous activity in units of curies per second.

The I

K, L,

M and N terms are actually site dependent dose conver-sion factors.

The equations listed below in Sections 1.1 and 1.2 take into consideration the release point location, building wake effects and physical characteristics of the radionuclides released.

In addition 40CFR190 regulations require that the annual I

Jose equivalent does not exceed 25 mrem to the whole body or any organ (except the thyroid which is limited to 75 mrem).

1.1 Fission and Activation Gases Gaseous releases from the nuclear units are limited such that at no time will releases of gaseous radioactive mater-ials cause a member of the general public to be exposed to an annual dose rate in excess of 500 mrem to the entire body or 3 rem to the skin in conformance with the requirements of 10CFR20.

Gaseous releases f rom the units are further restricted such that when releases are averaged over a calendar quarter no member of the general public will be exposed to an annual dose rate in excess of 20 millirads of gamma radiation or 40 millirads of beta radiation.

In addition, it is required that air doses averaged over a twelve month period be less than 40 and 8'.

millirads for gamma and beta radiation respectively.

At any instant the release rate of radioactive gases must satisfy the following equations whose basis is 10CFR20.

2.0 O v*Kyi 1 t

0.33 O v*(Lv + 1.1 Ny) i1 t

I M P80 17 18 l

When averaged over a calendar quarter the release rate for radioactive gases must satisfy the following equation.

The basis for these equations is 10CFR50 Appendix I.

13 O v*Ny 11 t

6.3 O v*My11 t

The limiting Unit I release limit 0 is calculated to be 1.24E+5 and 6.53E+4 microcuries/sec for the 3rd and 4th quarters respectively.

The limiting Unit 2 release limit 0 is calculated to be 6.04E+4 for both the 3rd and 4th quarters.

When averaged over any twelve consecutive month period, the release rate for radioactive gases must satisfy the following equation.

The basis for this equation is 10CFR50 Appendix I.

25 O v*N

$1 t

y 13 O v*M t

y i1 I

The release limits of radioactive gases for the Salem Nuclear Generating Station are not fixed numbers, but depe.

upoi.

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radioactive isotopes present in the effluent.

1.2 Iodine and Particulates, Half Life > 8 days The regulatory limits for iodines and particulates are listed below.

q The release rates of iodine and particulates are restricted such that no member of the general public will receive a dose I

at a rate in excess of 1.5 rem /yr. to the thyroid.

Releases of iodines and particulates are further restricted to prevent any member of the general public from receiving a dose rate in excess of 30 mrem in a calendar quarter or 60 mrem in any twelve month period.

The equations which govern these conditions are listed below:

At any instant of time the release rate for radioactive iodines and particulates material with a half life greater I

than 8 days is limited by the equation below.

The basis for this equation is 10CFR20.

(1.5 x 105) Oy 1 1 M P80 20 06/1 I

During any calendar quarter the release limit is governed by the equations listed below.

The basis for these equations is 10CFR50 Appendix I.

2 curies of I-131 I

and Qy x 13 (1.5 105) g i During any twelve month period radioactive releases should conform to the following constraints of 10CFR50 Appendix I.

25 x (1.5 x 105) x Qy i 1 and 4 curies of I-131 1.3 Liquid Effluents The regulatory limits for radioactive liquids released from the plant are governed by 10CFR20, Appendix B, Table II, Colunn 2.

In addition, the following limits apply:

I The cumulative release of radioactive effluents, excluding tritium and dissolved gases, shall be less than 10 Ci in a calendar quarter for each unit.

The cumulative release of radioactive effluents, excluding tritium and dissolved gases, shall be less than 20 Ci in any twelve consecutive months.

2.0 Maximum Permissible Concentrations Regulatory Guide 1.21 requires that the licensee provide the MPC's used in determining allowable release rates for radio-active releases.

We have addressed this question below.

I a.

Fission Gases - MPC values were not used to determine the maximum release rates.

b.

Iodines - MPC values were not used to determine the I

maximum release rates, c.

Particulates, Half Lives > 8 days - MPC limits were not used to determine the maximum release rates.

d.

Liquid effluents - MPC values as stated in 10CR20, Appendix B, Table 11, Column 2 were used.

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3.0 Average Energy Regulatory Guide 1.21 requires that the licensee provide the average energy of the radionuc3ir mixture in releases of fission and activation gases, t applicable.

I R' lease limits for the SNGS 6re not based upon average energy, herce, this section does n >t apply.

4.0 Measurements and Approximation of Total Radioactivity I

4.1 Liquid effluents are monitored in accordance with Table 2.3-3 of the Environmental Technical Specifications.

I During the period of record, all wastes from the chemical drain tank and the laundry and hot shower tanks were routed to the hold-up tanks for monitoring.

Technical Specifications require these tanks to be recirculated the I

equivalent of two tank volumes to produce uniform mixing and sample extraction and analyzation before any releases are made.

Batch releases included releases from the I

waste monitor tanks, waste monitor hold-up tank, and the chemical and volume control tanks.

Continuous releases included releases f rom intermittent blowdcan of the steam generators.

The predominate gamma emitting isotopes I

detected were CoS8, Co60, Csl34, and Csl37.

At no time did releases exceed limits.

4.2 Gaseous effluent streams are monitored in accordance with Table 2.3-4 of the Environmental Technical Specifica-tions.

The plant vent is the final release point of all I

planned gaseous ef fluents and is continually monitored by four very sensitive Geiger Mueller tubes.

The vent is also continuously sampled for iodine and particulates with a charcoal cartridge and filter paper connected in series to a low volume air sampler.

The filter and char-coal are changed weekly, weather permitting, and analyzed on a multichannel analyzer in the laboratory.

Sampling is also performed on all gas decay tanks and containment purges prior to release to the environment.

The results of these analyses are used as the basis for the cumula-tive release of gaseous effluents into the environment.

All tritium samples were taken by bubbling gas throu'th l

water and then counting the tritiated water on a liq _id l

scintillation counter.

I M P80 19 11 I

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I 4.3 The estimated total error of the reported continuous gaseous releases is within 50%.

This error is due I

primarily to variability of waste stream ficw rates and changes in isotopic distributions of waste streams between sampling periods.

The estimated total error of the reported batch gaseous ::eleases is within 10%.

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

l 5.0 Batch Releases Batch releases of gaseous and liquid effluent are I

provided in Tables 4A-1 and 4B-1 for Unit 1 and 4A-2 and 4B-2 for Unit 2.

1 6.0 Unplanned Releases There were no unplanned releases to an unrestricted area during thi.s -:eporting period.

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M P80 18 05/1 l

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.11 Part B.

Gaseous Effluents

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See Summary Tables lA-1 thru 1C-1 representative of Salem Unit 1 operations.

See Summary Tables lA-2 thru 1C-2 representative of Salem Unit 2 operations.

Part C.

Liquid Effluents i

1 ll See Summary Tables 2A-1 and 2B-1 representative of Salem Unit 1 operations.

Sea Summary Tables 2A-2 and 2B-2 representative of Salem Unit 2 operations.

4 Part D.

Solid Waste i

I See Summary Table 3 Unit 1

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See Summary Table 3 Unit 2

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Part E.

Radiological Imcact 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 the projected 1980 pop-ulation and historical site specific data i.e.,

food pro-duction, milk production, feed for milch animals and sea-food production.

The doses were calculated using methods described in Reg-ulatory Guide 1.109 and represent calcula tions for the six month reporting interval.

Doses from batch and continuous releases were calculated using the meteorological disper-sion coefficient X/O for the six month reporting interval.

Liquid Pathways Doses to individuals in the population from liquid re-leases are primarily from the seafood ingestion pathway.

The total body dose to an individual was calculated to be 1.45E-2 mrem.

The calculated population total body dose I

was 2.51E-1 person-rem.

The highest organ dose from liquid releases was 4.14E-1 mrem to the gastrointestinal tract.

Air Pathways I

The resulting whole body and skin doses to an individual were calculated to be 2.94E-3 mrem and 3.59E-3 mrem re-spectively.

The calculated population total body dose was 2.32E-1 person-rem.

The average total body dose to the I

population within fifty miles of the site was 4.31E-5 mrem / person.

Direct Radiation Direct radiation may be estimated by TLD measarements.

One method for comparing TLD measurements is by comparison I

with preoperational data.

TLD measurements on site near the Service Water pumps (location llS1) and near the Cir-culating Water pumps (location 10S1) averaged 9.25 and 6.15 mrads/ months, respectively, apparently due to trace activity in the Refueling Water Storage Tank.

TLD's at onsite locations 2S2 and SS1 which are 0.3 miles and 0.9 miles from the reactor containment, averaged 4.61 and 3.72 mrads/ month respectively.

The values for sta-tions 2S1 and SS1 are within the statistical variation associated with the preoperation program results.

Preliminary Assessment M P80 17 14 l

I All offsite monitoring locations remained within preoperational ranges.

It should be noted that the I

nearest' resident is 3.5 miles away.

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

t Part F.

Meteorological Data

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Cumulative joint wind frequency distribution by atmos-1 I

pheric stability class at the 300 foot elevation is pro-vided for the third and fourth quarters of 1980 as Table 5 and 6.

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TABLE lA-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980)

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES UNIT 1 3rd 4th Est. Total (l)

Unit Quarter Quarter Error %

A.

Fission & Activation Gases 1.

Total release Ci 7.03E+01 4.85E-01 2.50E+01 2.

Average release rate for period uCi/sec.

9.04E+00 6.24E-02 3.

Percent of technical specification limit 1.82E-03 9.56E-05 (See ETS Spec. 2.3.3.b)

B.

Iodines 1.

Total iodine-131 Ci 3.18E-03 6.45E-04 2.50E+01 2.

Average release rate for period uCi/sec.

4.09E-04 8.29E-05 3.

Percent of technical specification limit 7.97E-02 1.62E-02 C.

Particulates

^

1.

Particulates with half-lives) 8 days Ci 2.09E-01 2.51E-03 2.50E+01 2.

Average release rate for period uCi/sec.

2.69E-02 3.22E-04 3.

Percent of technical specification limit 5.24E+00 6.28E-02 4.

Gross alpha radioactivity (2)

Ci D.

Tritium 1.

Total release Ci 2.

Average release rate for period uCi/sec.

3.

Percent of technical specification limit N/A N/A (1)

For batch releases the estimated overall error is within 10%.

(2)

Analyses indicate no measurable alpha emitting transuranics.

To be supplied later.

M P8014/23 1 9-A S

TABLE lA-2 EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT (1980)

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES UNIT 2 3rd 4th Est. Total (l)

Unit Quarter Quarter Error %

A.

Fission & Activation Gases 1.

Total release Ci 9.09E-06 7.74E+00 2.50E+01 2.

Average release rate for period uCi/sec.

1.16E-06 9.95E-07 3.

Percent of technical specification limit 1.92E-09 1.65E-09 (See ETS Spec. 2.3.3.b)

B.

Iodines 1.

Total iodine-131 Ci 4.37E-06 5.00E-05 2.50E+01 2.

Average release rate for period uCi/sec.

5.62E-07 6.43E-06 3.

Percent of technical specification limit 1.lOE-04 1.25E-05 C.

Particulates 1.

Particulates with half-lives > 8 days Ci 2.

Average release rate for period uCi/sec.

3.

Percent of technical specification limit 4.

Gross alpha radioactivity (2)

Ci D.

Tritium 1.

Total release Ci 2.

Average release rate for period uCi/sec.

3.

Percent of technical specification limit N/A N/A (1)

For batch releases the estimated overall error is within 10%.

(2)

Analyses indicate no measurable alpha emitting transuranics.

To be supplied later.

M P8014/23 2 9-B

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TABLE IB-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980)

GASEOUS EFFLUENTS-ELEVATED RELEASES (Continued)

UNIT 1 CONTINUOUS MODE BATCII MODE 3rd 4th 3rd 4th Nuclides Released Unit 1 Quarter Quarter Quarter Quarter 3.

Particulates Chrominum-51 Ci 1.21E-04 Manganese-54 Ci

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1.15E-01 3.10E-04 Cobalt-58 Ci 1.08E-03 Coba l t-6 0 Ci 8.69E-04 Iron-59 Ci 3.00E-05 Rubidium-88 Ci 1.27E+00 Yttrium-88 Ci 6.64E-02 S t ron tium-8 9 Ci Strontium-90 Ci Niobium-95 4.50E-05 Zirconium-95 Ci 2.13E-05 Tin-ll7m Ci 1.84E-02 Cesium-134 Ci

__ Cesium-137 Ci 1.41E-05 1.99E-05 Cerium-139 Ci 9.38E-03 Gross Alpha Ci Total For Period Ci 1.48E-00 2.51E-03 4.

Tritium Tritium Ci (1)

Other fission gases were below the detectable level (LLD) Approximately less than 6.67 E-07 uCi/ml).

(2) Iodine was below the minimal detection limit.

To be supplied later.

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TABLE 2A-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980)

UNIT 1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES I

3rd 4th Units Quarter Quarter Est. Total Error, %

A. Fission and activation products g

1.

Total release (not including tritium, gases, alpha)

Ci 6.99E-01 1.29E+00 2.50E+01 2.

Average diluted concentration E

during period uCi/ml 4.99E-07 1.22E-07 5

3.

Percent of applicable limits of Technical Specifications 6.99E+00 1.29E+01 B. Tritium 1.

Total release Ci 2.50E+01 2.

Average diluted concentration E

during period uCi/ml N

3. Percent of applicable limit N/A N/A C.

Dissolved and entrained gases

1. Total release Ci 2.65E+00 8.65E-02 2.50E+01 2.

Average diluted concentration E

during period nCi/ml 1.89E-07 8.16E-05 E

3.

Percent of applicable limit N/A N/A 3

D.

Gross alphe radioactivity E

1. Total release Ci 0.00e+00 0.00E+00 2.50E+01 E. Volume of waste release (prior to dilution - Batch Release) liters 5.77E+06 4.53E+06 1.00E+01 F. Volume of dilution water used E

during period - Batch Release liters 1.40E+10 1.06E+10 2.50E+01 E

l/A-NotApplicable iTobesuppliealater P81 3 07/2 13-A I

TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980)

UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 3rd 4th Units Quarter Quarter Est. Total Error, %

Fission and activation products

l. Total release (not including

2. Average diluted concentration ___

Ci 4.66E-03 3.84E-01 2.50E+01 tritium, gases, alpha) during period uCi/ml 5.04E-10 1.56E-07

3. Percent of applicable limits of Technical Specifications 4.66E-02 3.84E+00 Tritium Ci

l. Total release

2. Average diluted concentration during period uCi/ml 3.

Percent of applicable limit N/A N/A Dissolved and entrained gases

1. Total release Ci 2.42E-04 0.00E+00 2.50E+01 I

. Average diluted concentration 2

during period uCi/ml 2.62E-ll 0.00E+00 3.

Percent of applicable limit N/A N/A

). Gross alpha radioactivity

1. Total release C1 U.UUE+UU U.00E+0V 2.SUEiU1 (prior Is.Volumeofwasterelease to dilution - Batch Release) liters 2.49E+06 8.45E+05 1.00E+01 Volume of dilution water used during period - Batch Release liters 9.24E+09 2.46E+09 2.50E+01 51/A-NotApplicable I*ToBeSuppliedLater

.1 P81 3 07/1 13-B

E TABLE 2B-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980)

LIQUID EFFLUENTS UNIT 1 CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Releaseed Unit Quarter Quarter Quarter Quarter Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci 1.77E-01 5.66E-03 Cesium-137 Ci 2.31E-01 6.19E-03 Iodine-131 Ci 7.72E-02 1.18E-03 Iodine-133 Ci 3.86E-03 Ci 4.36E-02 7.78E-01 I

Cobalt-58 Cobalt-60 Ci 1.41E-01 3.25E-01 Cadmium-109 Ci Ci 8.52E-03 3.43E-02 I

Manganese-54 Chromium-51 Ci 8.86E-03 7.45E-02 Cesium-136 Ci 9.763-04 Zirconium-95 Ci 4.78E-04 4.09E-03 I

Tin-113 Ci Barium-140 Ci Lanthaium-140 Ci Ci I

Cerium-139 Tungsten-187 Ci Niobium-95 Ci 2.52E-05 5.27E-03 Antimony-124 Ci 1.05E-02 Antimony-125 Ci 1.40E-04 Tritium Ci Iron-59 Ci 6.78E-03 4.12E-02 Ci 1.19E-04 I

Sodium-24 Yttrium-91 Ci Total for period (above) excluding H3 Ci 6.99E-01 1.29E+00 Xenon-133m Ci 1.04E-02 Xenon-133 Ci 2.62E+00 8.63E-02 Xenon-135 Ci 3.27E-03 2.llE-02 1.96E-04 Krypton-88 Ci Argon-41 Ci 5.58E-05 I(1)

The Lower Limit of Detection (LLD) is approximately 1.00E-08 uCi/ml (Co 60).

M P81 47 04/1 14-A I

m TABLE 2B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980)

LIQUID EFFLUENTS UNIT 2 CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Releaseed Unit Quarter Quarter Quarter Quarter I

Strontium-89 Ci Strontium-90 Ci Cesium-334 Ci 4.22E-03 Ci 4.93E-03 I

Cesium-137 Iodine-131 Ci Iodine-133 Ci Cobalt-58 Ci 4.34E-03 2.62E-01 I

Cobalt-60 Ci 6.77E-02 Cadmium-109 Ci Manganese-54 Ci 3.22E-04 1.31E-02 Chromium-51 Ci 1.38E-02 Cesium-136 Ci Zirconium-95 Ci Tin-113 Ci 1.90E-03 Barium-140 Ci Lanthaium-140 Ci Cerium-139 Ci I

Tungsten-187 Ci Niobium-95 Ci 2.35E-03 Antimony-124 Ci 5.03E-03 Ci 4.08E-03 I

Antimony-125 Tritium Ci Iron-59 Ci 5.05E-03 Sodium-24 Ci Yttrium-91 Ci Total for period (above) excluding H3 Ci 4.66E-03 3.84E-01 Xenon-133m Ci Xenon-133 Ci 2.42E-04 Xenon-135 Ci Krypton-88 Ci Argon-41 Ci (1)

The Lower Limit of Detection (LLD) is approximately 1.00E-08 uCi/ml (Co 60).

Tritium values were not available at the time the report was tabulated.

M P81 47 04/2 14-B

TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1980 UNITS 1 AND 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 1.

SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 6 -mon th Est. To tal 1.

Type of waste Units Period Error, %

a.

Spent resins, filters sludges, m3 2.31E+02 I

evaporator bottoms Ci 3.10E+02 1.50E+01 b.

Dry compressible waste, m3 6.61E+02 contaminated equip.

Ci 1.35E+01 1.50E+01 c.

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

Others (describe)

.m3 0.00E+00 Ci 0

0E+00 2.

Estimate of major nuclide composition (by type of waste) a.

Cobalt - 58 80.4%

2.49E+02 Cobalt - 60 16.3%

5.05E+01 Manganese - 54 3.3%

1.02E+01 I

Others b.

Cobalt - 58 50.4%

1.085E+01 Cobalt - 60 16.3%

2.20E+00 I

Manganese - 54 3.3%

0.45E+00 Others E

c.

E d.

E I

I 3.

Solid Waste Disposition Number of Shipments Moda of Trancportation Destination 65 Truck

Barnwell, IRRADIATED FUEL SHIPMENTS (Disposition)

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

I I

TABLE 4A-1 I

SALEM NUCLEAR GENERATING STATION (1980)

UNIT 1

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEAEED IN A BATCH MODE I

BATCH RELEASES ONLY 1.

Dates July 1 - Sept. 30, 1980 2.

Type of release (Gas) 3.

Number of releases during the 3rd Quarter 1.20E+01 4.

Total time duration for all releases of type listed above I

3.82E+02 minutes 5.

Maximum duration for releases of type listed above 1.53E+03 I

minutes 6.

Average duration for all releas-

>L type listed above I

3.19E+02 minutes 7.

Minimum duration for release of type listed above 7.60E+01 I

minutes 8.

For liquid batch releases only, provide the average stream flow (dilution flow) during the period of release.

N/A I

I l3 I

M P80 15 30/1 16-A I

I I

TABLE 4A-2 SALEM NUCLEAR GENERATING STATION (1980)

UNIT 2

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE I

BATCH RELEASES ONLY 1.

Dates July 1 - Sept. 30, 1980 2.

Type of release (Gas) 3.

Number of releases during the 3rd Quarter 1.90E+01 4.

Total time duration for all releases of type listed above I

2.39E+03 minutes 5.

Maximum duration for releases of type listed above 1.62E+02 I

minutes 6.

Average duration for all releases of type listed above I

1.26E+02 minutes 7.

Minimum duration for release of type listed above 8.70E+01 I

minutes 8.

For liquid batch releases only, provide the average stream flow (dilution flow) during the period of release.

N/A I

~

I I

M P80 15 42/1 16-B I

I TABLE 4A-1 (Cont'd)

SALEM NUCLEAR GENERATING STATION (1980)

UNIT 1

SUMMARY

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

Dates October 1 - Dec. 31, 1980 2.

Type of release (Gas) 3.

Number of releases during the 4th Quarter 2.30E+01 4.

Total time duration for all releases of type listed above I

7.49E+03 minutes 5.

Maximum duration for releases of type listed above 1.61E+03 minutes 6.

Average duration for all releases of type listed above I

3.26E+02 minutes 7.

Minimum duration for release of type listed above 7.60E+01 I

minutes 8.

For liquid batch releases only, provide the average stream flow (dilution flow) during the period of release.

N/A I

I

~

I I

I M P80 15 30 1/2 17-A

I TABLE 4A-2 (Cont'd)

SALEM NUCLEAR GENERATING STATION (19e0)

UNIT 2

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE I

BATCH RELEASES ONLY 1.

Dates October 1 - Dec. 31, 1980 2.

Type of release (Gas) 3.

Number of releases during the 4th Quarter 1.20E+01 4.

Total time duration for all releases of type listed above I

1.51E+04 minutes I

5.

Maximum duration for releases of type listed above 1.61E+03 minutes 6.

Average duration for all releases of type listed above I

1.26E+03 minutes I

7.

Minimum duration for release of type listed above 9.17E+02 minutes 8.

For liquid batch releases only, provide the average stream flow (dilution flow) during the period of release.

N/A I

I

~

I I

M P80 15 44/1 17-B I

I

I TABLE 4B-1 SALEM NUCLEAR GENERATING STATION (1980)

UNIT 1

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE I

BATCH RELEASES ONLY 1.

Dates July 1 - Sept. 30, 1980 2.

Type of release (Liquid) 3.

Number of releases during the 3rd Quarter 9.10+01 4.

Total time duration for all releases of type listed above I

2.00E+04 minutes 5.

Maximum duration for releases of type listed above 4.llE+02 minutes 6.

Average duration for all releases of type listed above 1

2.20E+02 minutes 7.

Minimum duration for release of type listed above 1.06E+02 minutes 8.

For liquid batch releases only, prov,ide the average stream flow (dilution flow) during the period of release.

1.85E+05 gpm I

I I

i I

1 M P81 3 06/1 18-A i I

i TABLE 4B-2 SALEM NUCLEAR GENERATING STATION (1980)

UNIT 2

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE I

BATCH RELEASES ONLY 1.

Dates July 1 - Sept. 30, 1980 2.

Type of release (Liquid) 3.

Number of releases during the 3rd Quarter 3.40+01 4.

Total time duration for all releases of type listed above I

1.32E+04 minutes 5.

Maximum duration for releases of type listed above 5.76E+02 minutes 6.

Average duration for all releases of type listed above 3.80E+02 minutes 7.

Minimum duration for release of type listed above 3.50E+01 minutes 8.

For liquid batch releases only, provide the average stream flow (dilution flow) during the period of release.

l'.85E+05 9Pm I

~

I I

I M P81 3 06/2 18-B

TABLE 4B-1 (Cont'd)

SALEM NUCLEAR GENERATING STATION (1980)

UNIT 1

SUMMARY

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

1.

Dates Oct. 1 - Dec. 31, 1980 2.

Type of release (Liquid) 3.

Number of releases during the 4th Quarter 7.lE+01 4.

Total time duration for all releases of type listed above 1.52E+04 minutes 5.

Maximum duration for releases of type listed above 4.50E+02 minutes 6.

Average duration for all releases of type listed above I

2.14E+02 minutes 7.

Minimum duration for release of type listed above 1.48E+02 minutes 8.

For liquid batch releases only, provide the average stream flow (dilution flow) during the period of release 1.85E+05 gpm I

I M P81 3 05/1 19-A

TABLE 4B-2 (Cont'd)

SALEM NUCLEAR GENERATING STATION (1980)

UNIT 2

SUMMARY

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

Dates Oct. 1 - Dec. 31, 1980 2.

Type of release (Liquid) 3.

Number of releases during the 4th Quarter 1.2E+01 4.

Total time duration for all releases of type listed above 3.51E+03 minutes 5.

Maximum duration for releases of type listed above 4.20E+02 minutes 6.

Average duration for all releases of type listed above 2.93E+02 minutes 7.

Minimum duration for release of type listed above 1.64E+02 minutes 8.

For liquid batch releases only, provide the average stream flow (dilution flow) during the period of release 1.85E+05 gpm I

M P81 3 05/2 19-B

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M M

M l

ARTIFICIAL ISLAND SALEM UNIT 1 PERIOD OF RECORD:

7 180 TO 93080 i

STABILITY CLASS: NEUTRAL DELTA T -1.5 TO -0.5 ^

LAPSE RATE IN DEG C/100 METERS EUALUATED USING DELTA T 300-33 FT ELEVATION:

300 FEET WINDSPEED (MPH) AT 300 FEET WIND DIREC-l l

TION 1-3 4-7 8-12 13-18 19-24

>74 TOTAL I

N 1

8 26 17 4

0 56 i

NNE 1

10 11 10 0

0 32 NE O

4 2

5 0

-O 11 ENE 1

3 4

1 O

O 9

E O

O 4

3 0

0 7

ESE 1

O O

1 O.

O 2

1 SE O

1 5

4 15 7

32 SSE 1

4 24 16 15 4

64 S

2 11 9

4 0

0 26 SSW 2

7 9

7 1

4 30 SW 1

20 17 25 1

0 64 WSW O

7 20 12 O

O 39

?

W 1

0 14 9

1 0

33 WNW 1

9 5

9 2

8 34 U

NW O

5 9

13 0

0 27 i

NNW 2

13 10 13 4

0 42 P

i TOTAL 14 110 169 149 43 23 508 s

r

[

PERIODS OF CALM (HOURS):

O HOURS OF MISSING DATA:

78

['

TABLE 5

~

Page 4 of 8

M M

M E

E E

E ARTIFICIAL ISLAND SALEM UNIT 1 PERIOD OF RECORD:

7 180 TO 93080 STADILITY CLASS: SLIGHTLY STABLE DELTA T -0.5 TO 1.5 ~

LAPSE RATE IN DEG C/100 METERS EVALUATED USING DELTA T 300-33 FT ELEVATION:

300 FEET WINDSPEED (MPH) AT 300 FEET WIND DIREC-TION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL 1

~

N O

5 24 18 2

0 49 NNE 4

2 18 26 1

0 51 NE 2

6 16 14 2

0 40 ENE 3

6 9

4 2

0 24 E

1 3

13 14 0

0 31 ESE O

1 6

9 7

0 23 SE O

6 7

18 16 4

51 l

SSE 4

7 22 40 14 0

87 g

S 2

13 32 32 10 2

91 i

SSW 2

13 37 47 25 2

126 SW 2

19 39 60 17 1

138 USW 3

0 23 38 9

3 84 W

3 12 30 23 3

-1 72 WNW O

12 17 13 2

1 45 NW 1

0 17 17 14 0

57 NNW 1

9 19 12 2

0 43 TOTAL 20 130 329 385 126 14 1012

}

PERIODS OF CALM (HOURS);

1

(

1 HOURS OF MISSING DATA:

162 i

TABLE 5 Page 5 of 8

M M

i

?

j ARTIFICIAL ISLAND SALEM UN1T 1 PERIOD OF RECORD:

7 180 TO 93000-STABILITY CLASS: MODERATELY STABLE DELTA T 1.5 TO 4.0 ^

LAPSE RATE IN DEG C/100 METERS EVALUATED *USING DELTA T 300-33 FT ELEVATION:

300 FEET WINDSPEED (MPH) AT 300 FEET WIND l

DIREC-TION 1-3 4-7 8-12 13-10 19-24

>2' TOTAL 4

N O

4 7

18 3

0 32 k

NNE O

O 1

3 1

0 5

NE O

1 5

4 3

0 13 ENE O

O 2

3 1

0 6

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1 O

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O 1

l ESE O

O O

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O 1

1 O

O 2

SSE O

2 3

6 1

0 12 S

1 1

3 3

O O

8 SSW O

1 5

5 4

0 15 SW O

O.

4 6

3 0

13 WSW O

O 2

5 1

1 9

W O

1 1

1 O

O 3

WNW O

1 1

0 4

NW 9

1 6

1 O

O 8

NNW O

O 3

16 1

0 20 l

TOTAL 1

13 44 73 19 1

151 PERIODS OF CALM (HOURS):

O HOURS OF MISSING DATA:

37 i

TABLE 5 Page 6 of 8

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ARTIFICIAL ISLAND SALEM UNIT 1 PERIOD OF RECORD:

7 100 TO 93080

[

STADILITY CLASS: ALL STADILITIES EXCLUDING MISS SPEED /DIR DATA i

LAPSE RATE IN DEG C/100 METERS l

EVALUATED USING DELTA T 300-33 FT l

ELEVATION:

300 FEET

- - - - 4************************************************

i l

l WINDSPEED (MPH) AT 300 FEET WINis DIREC-I T I OtJ 1-3 4-7 8-12 13-18 19-24

>24 TOTAL l

N 1

17 57 53' 9

0 137 NNE 5

12 30 39 2

0 88 l

NE 2

11 23 24 5

0 65 l

ENE 4

to 15 8

3 0

40 l

E 1

4 17 17 0

0 39 l

ESE 1

1 6

10 7

0 25 24 31 11 87 i

SE O

7 14 '

64 31 5

167 l

SSE 5

13 49 S

S 25 44 39 10 2

125 l

SSW 4

21 52 59 30 6

172 SW 3

40 61 91 21 1

217 l

WSW 3

15 45 55 10 4

132 l

W 4

21 45 33 4

1 108 WNW 1

22 23 23 5

9 83 NW 1

14 32 31 14 0

92 NNW 3

22 32 41 7

0 105 l

TOTAL 43 255 545

611 109 39 1682 PERIODS OF CALM (HOURS);

1 l

HOURS OF MISSING DATA:

279 i

I I

i 6

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TABLE 5 Page 8 of 8

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M M

m m.

m m

ARTIFICIAL ISLAND SALEM UNIT 1 PERIOD OF RECORD: 10 100 TO 123180 l

STABILITY CLASS: SLIGHTLY UNSTABLE DELTA T -1.7 TO -1.5 ^

LAPSE RATE IN DEG C/100 METERS EVALUATED USING DELTA T 300-33 FT ELEVATION:

300 FEET WINDSPEED (MPH) AT 300 FEET WIND DIREC-TION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

O O

O 1

0 0

1 NNE O

O O

NE O

O O

ENE O

1 1

1 0

0 3

E O

O O

ESE O

O O

SE O

O O

l SSE O

O O

S O

O 1

0 0

0 1

l SSW 0

0 0

SW O

O O

WSW 0

0 0

1 0

0 1

W O

O 1-3 0

0 4

WNW 0

0 0

1 0

0 1

NW 0

0 0

3-1 1

5 NNW 0

0 0

3 2

2 7

TOTAL 0

1 3

13 3

3 23 PERIODS OF CJ.LM (HOURS):

0 HOURS OF MISSING DATA:

3 TABLE 6 Page 3 of 8 t

l M

m m' ~ m m

m~

m m

m M

M M

M m

~

ARTIFICIAL ISLAND SALEM UNIT 1 PERIOD OF RECORD: 10 180 TO 123180 STABILITY CLASS: NEUTRAL DELTA T -1.5 TO -0.5 ^

LAPSE RATE IN DEG C/100 METERS EVALUATED USING DELTA T 300-33 FT El.EVATION:

300 FEET WINDSPEED (MPH) AT 300 FEET WIND DIREC-TION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

O 5

18 21 7

0 51 NNE O

3 13 19 5

1 41 NE O

1 7

21 2

0 31 ENE O

3 7

5 2

0 17 t

E 1

S 6

1 0

0 13 ESE O

2 0

0 4

SE 0

2 2

4 0

2 10 l

l SSE O

7 2

2 0

0 11 S

0 5

9 4

0 0

18 SSW 1

8 10 6

0 0

25 SW 1

3 13 19 10 3

49 WSW 1

1 18 9

15 10 62 W

1 11 14 12 8

lb 64 WNW 0

4 3

17 12 8

44

(

NW 0

5 9

29 23 34 100 NNW 1

11 9

25 23 29 98 TOTAL 6

76 140 196' 107 113 638 PERIODS OF CALM (HOURS):

0 HOURS OF MISSING DATA:

19 1

TABLE 6 Page 4 of 8

-,n----

M M

M ARTIFICIAL ISLAND SALEM UNIT 1 PERIOD OF RECORD: 10 100 TO 123180 STABILITY CLASS: SLIGHTLY STABLE DELTA T -0.5 TO 1.5 "

LAPSE RATE IN LEG C/100 METERS-EVALUATED USING DELTA T 300-33 FT ELEVATION:

300 FEET WINDSPEED (MPH) AT 300 FEET WIND IIIREC-TION 1-3 4-7 0-12 13-18 19-24

>24 TOTAL N

O 9

22 44 14 0

89 NNE 1

3 16 24 10 0

54 NE 2

2 10 27 14 0

55 ENE 2

0 13 21 3

3 50 E

2 6

12 3

0 1

24 ESE 2

6 0

3-0 0

11 SE 1

3 6

1 3

3 17 SSE 2

7 5

9 3

3 29 l

S O

12 9

20 17 1

59 SSW 0

3 19 20 22 15 79 l

SW 1

3 8

32 27 9

80 l

WSW 1

7 14 19 13 1

55 W

2 3

9 29 14 10 67 I

WNW 0

2 13 47 30 11 103 NW 5

10 20 53 46 30 164 NNW 0

5 16 40 38 17 116 TOTAL 21 89 192 392 254 104 1052 PERIODS OF CALM (HOURS):

0 HOURS OF MISSING DATA:

28 TABLE 6 Page 5 of 8 i

RT IA SLA 9

SALEM UNIT.1 PERIOD OF RECORD: 10 180 TO 123180 STABILITY CLASS: MODERATELY STABLE DELTA T 1.5 TO 1.0 ^

LAPSE RATE IN DEG C/100 METERS EVALUATED USING DELTA T 300-33 FT ELEVATION:

300 FEET WINDSPEED (MPH) AT 300 FEET WIND DIREC-TION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL N

O 1

4 9

3 0

17 NNE O

O 1

5 2

0 8

NE O

1 4

2 2

0 9

ENE 1

2 2

2 0

0 7

E O

1 0

0 0

0 1

ESE O

O 2

0 0

0 2

SE O

1 4

1 0

0 6

SSE 1

1 1

4 1

4 12 S

1 2

1 7

5 4

20 SSW 0

1 6

3 6

1 17 SW 0

0 2

5 5

2 14 WSW 0

0 1

3 5

2 11 W

1 2

2 1

3 4

13 WNW 0

0 1

1 1

0 3

NW 0

1 1

3 0

1 6

NNW 0

0 0

6 11.

0 17 l

i TOTAL 4

13 32 52 44 18 163 i

PERIODS OF CALM (HOURS):

0 t

HOURS OF MISSING DATA:

4 l

i TABLE 6 1l, Page 6 of 8 I

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C G7 W

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W%

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hM M

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l

~

ARTIFICIAL ISLAND SALEM UNIT 1 PERIOD OF RECORD: 10 180 TO 123180 STABILITY CLASS: ALL STABILITIES EXCLIJDING MISS SPEED /DIR DATA LAPSE RATE IN DEG C/100 METERS EVALUATED USING DELTA T 300-33 FT ELEVATION:

300 FEET WINDSPEED (MPH) AT 300 FEET WItJD DIREC-TION 1-3 4-7 8-12 13-18 19-24

>24 TOTAL (1

0 15 44 75 24 0

158 NNE 1

6 30 48 17 1

103 NE 2

5 21 50 10 0

96 ENE 3

14 23 29 5

3 77 E

4 14 18 4

0 1

41 ESE 2

8 2

6 0

0 18 SE 1

6 13 6

4 5

35 SSE 3

16 8

15 4

7 53 S

2 23 22 37 23

,6 111 SSW 1

12 37 35 31 17 133 SW 2

6 24 57 42 14 145 WSW 2

0 34 39 33 21 137 W

4 16 26 49 25 34 154 WNW 0

6 19 66 43 19 153 NW 5

16 31 09 70 67 278 NNW 1

17 25 74 74 51 242

?

TOTAL 33 106 377 679 413 246 1934 PERIODS OF CALM (HOURS):

0 HOURS OF MISSING DATA:

58 TABLE 6 j

Page 8 of 8 j

4 j

i

.

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