Text

Semiannual Radioactive Effluent Release Rept for Jan-June 1981
	ML20040B684
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Site:	Salem
Issue date:	08/31/1981
From:	; Public Service Enterprise Group
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i C4Me 1981 l

SEMI A!J iUAL RADIOACTIVE EFFLUE!;T RE* EASE BFFORT aEM-10 SALg3 tIUCLE,R G tlE IG

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U!!IT 1 DOCKET f:0. 50-272 UtJIT 2 DOCKET ?!O. 50-311 l

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l REPORT NO. RERR-10 UtlIT NOS. 1& 2 RADIOACTIVE EFFLUEtJT RELEASE REPORT lI JANUARY - JUNE 1981 l

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I lI il SALEM NUCLEAli GENERATING STATION Public Service Electric and Gas Company I

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M P79 43/33 lI 4

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gW SALEM NUCLEAR GENERATING STATION UNIT 1 50-272 UNIT 2 50-311 UNIT NOS. 1 AND 2 RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 1981 to June 30, 1981 Introduction This report, RERR-10, summarizes the releases of radioactive materials in liquid, gaseous and solid form f rom the Salem Nuclear Generating Station Units 1 and 2 for the period January 1,

1981 to June 30, 1981.

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 f rom the Salem station dur-ing the reporting period were within the limits set forth in I

the Environmental Technical Specifications.

Calculated ra-diation exposures to off-site individuals were small frac-tions of the limits set forth in 10CFR20 and within Appendix I to 10CFR50 and 4 0CFR190 requirements.

Unit 1 generated 2,662,450 megawatt-hours (gross) of elec-trical energy.

i Unit 2 generated 12,090 megawatt-hours (gross) of electrical energy.

I M P79 43/33 l

I EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT RERR 10 I

A.

SUMMARY

INF0F14ATION 1.0 Regulatory Limits Symbols utilized in tho equations listed below under Sec-I tions 1.1 and 1. 2 are the same as those used in the Salem Environmental Technical Spccifications (ETS).

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

The 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, l

building wake effects and physical characteristics of the i

radionuclides released.

l l3 In addition 40CFR190 regulations require that the annual g

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

i 1.1 Fission and Activation Gases Gaseous releases from the nuclear units are limited such lg that at no time will releases of gaseous radioactive mater-ig ials cause a member of the general public to be exposed to I

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 l

10CFR20.

Gaseous releases from the units are further restricted such

,g that when releases are averaged over a calendar quarter no l3 member of the general public will be exposed to an annual l

dose rate in excess of 20 millirads of gamma radiation or 40 l

millirads of beta radiation.

l In addition, it is required that air doses averaged over a l

twelve month period be less than 40 and 80 millirads for gamma and beta radiation respectively.

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

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2.0 Otv*K 1 1 v

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0.33 Otv*(Lv + 1.1 Ny) 31 I

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When averaged over a calendar quarter the release rate for I

radioacti"e gases must satisfy the following equation.

The basis for these equations is 10CFR50 Appendix I.

13 O v*N i1 t

v I1 6.3 O v*M t

o The limiting Unit 1 release limit 0 is calculated to be 1.51E+04 microcuries/sec for both the 1st and 2nd quarters.

The limiting Unit 2 release limit 0 is calculated to be 1.52E+04 ano 1.35E+04 microcuries/sec for the 1st and 2nd quarters respectively.

When averaged over any twelve consecutive month period, the

I release rate for radioactive gaces must satisfy the following equation.

The basis for this equation is 10CFR50 Appendix I.

25 O v*N i1 t

y 13 O v*M I1 t

y The release limits of radioactive gases for the Salem Nuclear lg Generating Station are not fixed numbers, but depend upon the g

radioactive isotopes present in the effluent.

1.2 Iodine and Particulates, Half Life > 8 days l

The regulatory limits for iodines and particulates are listed below.

The release rates of iodine and particulates are restricted such that no member of the general public will receive a dose at a rate in excess of 1.5 rem /yr. to the thyroid.

1 Releases of iodines and particulates are further restricted to prevent any mer.ber 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 ara listed below:

At any instant of time the release rate for radioactive iodines and particulates material with a half life greater than 8 days is limited by the equation below.

The basis for this equation is 10CFR20.

(1.5 x 105) Oy11 M P80 20 06/1 I

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

The basis for these equations is 10CPR50 Appendix I.

2 curies of I-131 and Qy x 13 x (1.5 x 105) g1 I

During any Welve month period radioactive releases should conform to the following constraints of 10CFR50 Appendix I.

25 x (1.5 x 105) x Qv i 1 I

and 4 curies of I-131 1.3 Liquid Effluents _

The regulatory limits for radioactive liquids released from I

the plant are governed by 10CFR20, Appendix B, Table II, Column 2.

In addition, the following limits apply:

The cumulative release of radioactive effluents, excluding tritium and dissolved gases, shall be less than 10 Ci in a

,I calendar quarter for each unit.

The cumulative release of radioactive effluents, excluding I

tritium and dissolved gases, shall be less than 20 Ci in any twelve consecutive months.

2.0 g imum Permissible Concentrations Regulatory Goide 1.21 requires that the licensee provide the MPC's used in determining allowable release rates for radio-active rr 1 eases.

We have addressed this question below, a.

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

b.

Iodines - t'PC values were not used to determine the 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.

I M P80 20 06/2 I

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3.0 Average Energy I

Regulatory Guide 1.21 requires that the licensee provide the average energy of the radic,nuclide mixture in releases of fission and activation gases, if applicable.

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

4.0 Measurements and Approxination of Total Radioactivity 4.1 Liquid effluents are monitored in accordance with Table 2.3-3 of the Environmental Technical Specifications.

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 I

Specifications require these tanks to be recirculated the

' 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 aad volume control tanks.

Continuous releases included releases from intermittent blowdown of the steam I

generators.

The predominate gamma emittir:g isotopes detected were CoS8, Co60, Cs134, and Cs137.

At no time did releases exceed limits.

4.2 Gasecas 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 effluents 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 I

series to a low volume air sampler.

The filter and char-coal are changed weekly, weather oermitting, 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 through water and then counting the tritiated water on a liquid 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 5 0%.

This error is due primarily to variability of waste stream flow rates and changes in isotopic distributions of waste s treart oe-l tween sampling periods.

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

The estimated tota.1 error of reported liquid releases is within 25%.

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5.0 Batch Releases Batch releases of gaseous and liquid effluent are pro-vided in Tables 4A-1 and 4B-1 for Unit 1 and 4A-2 and j

4B-2 for Unit 2.

6.0 Unplanned Releases I

l On March 14, 1981, 6 00 gallons of liquid waste from the l

No. 22 Waste Monitor Tank was released to the environ-4 ment.

It was determined that 3.6 X 10-5 Ci had been l

released.

This event was reported as LER 81-27/03L on April 14, 1981.

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M P8 0 18 05/1 I

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Part B.

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

j See Summary Tables lA-2 thru 1C-2 representative of Salem j

Unit 2 operations.

Part C.

Liquid Effluents I

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

See Summary Tables 2A-2 arJ 2B-2 representative of Salem Unit 2 operations.

Part D.

Solid Waste See Summary Table 3 units 1 and 2 g

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Part E.

Radiological Impact on Man I

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

She population dose impact is based on historical site spe-cific data 1.e.,

food production, milk production, feed I

for milch animals and seafood production.

The doses were calculated using methods described in Reg-I ulatory Guide 1.109 and represent calculations 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 ligdLd re-leases are primarily f rom the seafood ingestion pathway.

The total body dose to an individual was calculated to be 1.21E-02 mrem.

The calculated population total body dose I

was 4.64E-02 person-rem.

The highest organ dose from lig-uid releases was 5.59E-02 mrem to the gastrointestinal tract.

Air Pathways The resulting whole body and skin doses to an individual I

were calculated to be 8.96E-03 mrem and 1.01E-02 mrem re-spectively.

The calculated population total body dose was 4.64E-01 person-rem.

The average total body dose to the I

population within fifty miles of the site was 8.67E-05 m rem /pe rsors.

Direct Radiation Lirect radiation may be estimated by TLD measurements.

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

As mentioned in previous Efflu-ent Release Reports, TLD measurements at location 10S1 and 11S1 have averaged higher than at other locations.

This I

was due to trace activity in the Refueling Water Storage Tank.

The average of all on site TLD locations, except 10S1 and 11S1, was found to be 5.30 mrem / month.

This val-ue is within the statistical variation of the preopera-I tional mean which was 4.42 + 1.18 mrem / month.

Il M P80 17 14 11

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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 l

concluded that thtue sas no measurable dose to any i'

offsite locatione, Crcr direct rad ia t ion.

Part F.

Meteorological Data Cumulative joint wind frequency distribution by atmos-pheric stability class at the 3 00 foot elevation is pro-l vided for the first and second quarters of 1981 as Table 5 i

and 6.

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TABLE lA-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1981)

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES UNIT 1 1st 2nd Est. Total (l)

Unit Ouarter Ouarter Error %

A.

Fission & Activation Gases 1.

Total release Ci 7.43E+61 1.05E+02 2.50E+01 2.

Average release rate for period uCi/sec.

9.56E+00 1.34r.+01 3.

Percent of technical specification _ limit 2.44E-05 8.94fj;p4 (See ETS Spec. 2.3.3.b)

B.

Iodines 1.

Total iodine-131 Ci 8.74E-04 7.49E-03 2.50E+01 2.

Average release rate for peri 6d uCi/sec.

1.12E-04 9.53r-04 3.

P_ercent of technical specification limit t

2.18E-02 1.86E-01 C.

Particulates 1.

Particulates with half-lives > 8 days Ci 1.76E-04 3.26E-01 2.50E+01 2.

Average release rate for pericd uCi/sec.

2.26E-05 4.15E-02 3.

Percent of technical specification limit 4.41E-03 8.09E+00 4.

Gross alpha radioactivity (2)

Ci 0.00E+00 0.00E+00 D.

Tritium 1.

Total release Ci 1.07E+00 2.96E-01 2.

Average release rate for period uCi/sec.

1.38E-01 3.76E-02 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.

M P8014/23 1 9-A

TABLE 1A-2 EF?LUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1981)

GAfEOUS EFFLUENTS-SUMMATION OF ALL RELEASES UNIT 2 1st 2nd Est. Total (l)

Unit Quarter Quarter Error %

A.

Fission & Activation Gases 1.

Total release Ci

1. 9 0E- 01 1.43E-02

2. 5 0E+ Cl 2.

Average release rate for period uCi/sec.

2. 4 4 E- 02

1. 8 2 E- 03 3.

Percent of technical specification limit

1. 6 0E- 06

1. 3 5E- 07 (See ETS Spec. 2.3.3.b)

B.

Iodines l

1.

Total iodine-131 Ci 2.45E-08

7. 2 8 E- 09 2.50E+01 2.

Average release rate for period uCi/sec.

2. 3 4E- 06 9.26E-10 3.

Percent of technical specification limit

4. 5 6 E- 04

1. 81 E- 07 i

C.

Particulates 1.

Particulates with half-lives) 8 days Ci

4. 09E- 06

3. 5 3 E- 03

2. 5 0E+ 01 2.

Average release rate for period uCi/sec.

5. 26E-07

4. 4 9E- 04 3.

Percent of technical specificati.on limit

1. 03F-04

8. 7 6 E- 02 4.

Gross alpha radioactivity (2)

Ci D.

Tritium 1.

Total release Ci

0. 0 0E + 0 0

2. 5 0E + 01 2.

Average release rate for period uCi/sec.

3.

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

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

(2)

Analyses indicate no measurable alpha emitting transuranics.

M P8 014/23 2 9-B l

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M TABLE IB-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1981)

GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 1 CONTINUOUS MODE BATCH MODE lst 2nd 1st 2nd Nuclides Released Unit Quarter Quarter nuarter Quarter 1.

Fission gases Krypton-85 Ci

2. 3 0E- 01

8. 51E- 02 Krypton-85m Ci

5. 8 7 E- 03 2738E-02 Krypton-87 Ci

6. 36E- 03 Krypton-88 Ci 2.59E-02 Xenon-133 Ci 8.32E-03 3.13 E- 03

7. 2 2E + 01 1.03E+02 Xenon-135 Ci

8. 8 3 E- 02 1.79E-02 8. 8 5 E- 01 1.53E'+00 Xenon-135m Ci Xenon-138 Ci Xenon-133m Ci 9.25E-01 6.14 E- 01 Argon-41 Ci 2.43E-03 Fluorine-18 Ci

3. 09E-04 Unidentified Ci Total for period Ci

9. 6 6E- 02 2.10E-02

7. 4 2E+ 01 1.05E+02 2.

Iodines Iodine-131 Ci

8. 7 4 E- 04

4. 3 0E- 03 3.19 E- 03 Iodine-133 Ci

4. 9 6 E- 04

3. 04 E- 04

1. 21 E- 04 Iodine-135 C1 Total for period Ci 1.37E-03 4.60E-03 0.00E+00

3. 31 E- 03 M P8 0 14/2 0 1 10-A

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TABLE 18-2 L

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1981)

GASEOUS EFFLUENTS-ELEVATED RSLEASES UNIT 2 l

CONTINUOUS MODE BATCli MODE lst 2nd 1st 2nd l

Nuclides Released Unit Quarter Quarter Quarter Quarter i

I 1.

Fission gases j

i Krypton-85 Ci i

Krypton-85m Ci Krypton-87 Ci j

Ktypton-88 Ci Xenon-133 Ci

5. 5 7E- 05

1. 8 8 E- 01

1. 27E- 02 Xenon-135_

Ci

1. 3 2 E- 03

4. 7 8 E- 04 1.64E-03 Xenon-135m Ci

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~Tenan-133m Ci l

Argon-41 Ci Fluorine-18 Ci Unidentified C1 i

l Total for period Ci

1. 3 8E- 03

1. 8 9E- 01

1. 4 3E- 02 I

2.

Iodines

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Iodipe-131 Ci

2. /. 5E- 08

7. 28E- 09 i

Iodine-133 Ci

1. 8 2 E- 05 l

Iodine-135 Ci Total for period Ci

1. 8 2 E- 05 7.28E-09 i

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TABLE 1C EFFLUEt4T AND WASTE DISPOSAL SEMIANNUAL REPORT 1981 UNITS 1 AND 2 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES I

Nuclides Peleases Unit 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter I

'Ihere were no ground level releases for the period of record.

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I TABLE 2A-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1981)

UNIT 1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES lst 2nd Units Quarter Quarter Est. Total I

Error, %

A.

Fission and activation products

1. Total release (not including tritium, gases, alpha)

Ci 3.56E-01 4.76E-02 2.50E+01 2.

Average diluted concentration during period uCi/ml 4.67E-08 8.64E-09 3.

Percent of ap51icable limits of Technical Specifications 3.56E+00 4.78E-01 B. Tritium B

1. Total rec ase Ci '

l.04E+02 7.48E+01 2.50E+01 5

2.

Average diluted concentration during period uCi/ml 1.36E-05 1.35E-05 3.

Percent of applicable limit N/A N/A I

C.

Dissolved and entrained gases

1. Total release

' ]}"i 1.05E+00 7.43E-01 2.50E+01 2.

Average diluted concentra' in LCi/ml 1.38E-07 1.34E-07 during period 7

m 3.

Percent of applicabl( 1ft N/A N/A D.

Gross alpha radioactivity

1. Total release Ci 0.00E+00 0.00E+00 2.50E+01 E.

Volume of waste release (prior to dilution - Batch Release) literc 3.15E+06 2.46E+06 1.00E+01 F.

Volume of dilution water used during period - Batch Release liters 7.62E+09 5.53E+09 2.50E+01 I

N/A - Not Applicable I

I P81 3 07/2 13-A

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W TABLE 2A-2

)

EPFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1981)

UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 1st 2nd Units Quarter Quarter Est. Total I

Error, %

I. Fissior:

A and activation products

1. Total release (not including I

2.

tritium, gases, alpna)

Ci 2.39E-01 9.39E-02 2.50E+01 Average diluted concentration during period uCi/ml 3.83E-08,6.71E-09 3.

Percent of applicable limits of Technical Specifications 2.39E+00 9.39E-01 I. Tritium B

1. Total release Ci 1.39E+02 7.15E+01 2.

Average diluted concentration during period uCi/ml 2.23E-05 5.llE-06 Percent of appiicable limit N/A N/A I

3.

I.Dissolvedandentrainedgases C

1. Total release Ci 4.77E-01 1.30E-01 2.50E+01 2.

Average diluted concentration during period uCi/ml 7.64E-08 9.29E-09 3.

Percent of applicable limit N/A N/A D.

Gross alpha radioactivity

1. Total releast Ci 0.00E+00 0.00E+00 2.50E+01 E.

Volume of waste release (prior to dilution - Batch Release) liters 1.99E+06 4.42E+06 1.00E+01 F.

Volume of dilution water used during period - Batch Release liters 6.24E+09 1.40E+10 2.50E+01 I

N/A - Not Applicable I

I M P81 3 07/1 13-B I

TABLE 2B-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1981)

LIQUID EFFLUENTS UNIT 1 I

CONTINUOUS MODE BATCH MODE lst 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci

~ 2.75E-02 3.~ 4 8 E-O J Cesium-137 Ci 2.85E-02 3.78E-03 Iodine-131 Ci 6.74E-02 2.87E-04 Iodine-133 Ci 2.33E-03 Cobalt-58 Ci 8.49E-02 1.24E-02 Cobalt-60 Ci 1.04E-01 1.0?E-02 Cadmium-109 Ci Manganese-54 Ci

^ 1.36E-02 1.55E-02 Ch ror41um-51 Ci 4.72E-04 1.31E-03 Cesium-136 Ci 1.42E-03 Zirconium-95 Ci 8.01E-05 1.71E-04 I

Tin-ll3 Ci Barium-140 Ci Lanthanum-140 Ci Cerium-139 Ci I

Tungsten-187 Ci Niobium-95 Ci 2.19E-04 Antimony-124 Ci 6.15E-04

~

I Antimony-125 Ci 4.28E-03 Tritium Ci 9.54E-04 0.00E+00 1.04E+02 7.48E+01 Iron-59 Ci 1.22E-04 Sodium-24 Ci 2.09E-02 Molybdenum 99 Ci 2.52E-04 Total for period (above) excluding H3 Ci 0.00E+00 0.00E+00 3.56E-01 4.78E-02 Xenon-133m Ci 8.08E-03 8.53E-03 Xenen-133 Ci 1.7) 2 E +0 0 7.12E-01

~

Xenon-135 Ci 2 '. 0 0,E- 0 2 2.22E-02 I

Krypton-88 Ci Argon-41 Ci I

I M P81 47 04/1 14-A I

I I

TABLE 2B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1981)

LIQUID EFFLUENTS UNIT 2 CONTINUOUS MODE BATCH MODE I uclides Released lst 2nd 1st 2nd N

Unit Quarter Quarter Quarter Quarter Strontium-89 Ci Strontium-90 C1 Cesium-134 Ci 7.15E-03 2.92E-03 I

Cesium-137 Ci 8.48E-03 7.41E-03 Ci 4.39E-04 1.27E-04 Iodine-131

~

Ci Iodine-l33 Coba lt-58 Ci

~

1.02E-01 4.58E-02 Cobalt-60 Ci 1.15E-01 2.19E-02 Cadmium-109 Ci Manganese-54 Ci 3.81E-03 8.32E-03 Chromium-51 Cf 5.30E-04 1.46E-03 Cosium-136 Ci Zirconium-95 Ci 4.23E-05 Tin-ll3 Ci Barium-140 Ci Lanthanum-140 Ci Cerium-139 Ci Ci_

2.49E-04 Tungsten-187 Ci Niobium-95 Antimony-124 Ci 6.56E-04 Antimony-125 Ci 1.46E-03 2.16E-03

__ Tritium Ci 0.00E+00 1.39E+02 7.15E+01 Iron-59 Ci

, Ci 2.82E-03 I

Sodium-24 Yttrium-91 Ci Total for period (above )

excluding 113 Ci 0.00E+00 0.00E+00 2.39E-01 9.39E-02 Xenon-133m Ci 5.30E-03 Xenon-133 Ci 4.56E-01 1.26E-01 Xenon-135 Ci 1.60E-02 _ 4.00E-03 I

Krypton-88 Ci Argon-41 Ci I

M P81 47 04/2 14-B I

TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIAN:4UAL REPORT 1981 UNITS 1 AMD 2 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 6-month Est. Total 1.

Type of waste Unite Period Error, %

a.

Spent resins, filters sludges, m3 1.lE+02 evaporator bottoms Ci 5.lE+02

1. 5 0E+ 01 b.

Dry compressible waste, m3 4.0E+02 contaminated equip.

Ci 2.3E+01

1. 5 0E+ 01 c.

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

Others (describe) m3 0.00E+00 Ci 0.00E+00 2.

Estimate of major nuclide composition (by type of waste )

a.

Cobalt - 58 73.1%

3.7E+02 Cobalt - 60 14.9%

7. 6 E + 01 Manganese - 54 3.0%

1. 5 E+ 01 Fe 55

9. 0

4. 6 E + 01 b.

Cobalt - 58 73.1%

1.7E+01 Cobalt - 60 14.9%

3.4E+00 Manganese - 54 3.0%

7.0E-01 Fe 55

9. 0

2. lE+ 0 0 c.

E d.

E 3.

Solid Waste Disposition Number of Shipments Mode of Transportation Destination 49 Truck

Barnwell, I

South Carolina 4

Truck Beatty, Nevada IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation Destination None N/A N/A P80 14/21 1 l

I TABLE 4A-1 4

SALEM NUCLEAR GENERATING STATION (1981) l UNIT 1

SUMMARY

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

Dates January 1 - March 31, 1981 2.

Type of release (Gas) 3.

Number of releases during the 1st Quarter 1.50E+01 i

' l 4.

Total time duration for all releases of type listed above 3

3.57E+03 minutes 5.

Maximum duration for releases of type listed above 1.47E+03 minutes I

6.

Average duration for all releases of type listed above 2.38E+02 t

minutes 7.

Minimum duration for release of type listed above 6.40E+01 minutes 8.

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

N/A M P80 15 30/1 16-A II

/\\

s TABLE 4A-2 i

SALEM NUCLEAR GENERATING STATION (1981)

UNIT 2 I

SUMMARY

Sif EET FOR RADIOACTIVE EFFLUENTS RELEASED l

IN A BATCII MODE

!I f

BATCil RELEASES ONLY l

1.

Dates January 1 - March 31, 1981 2.

Type of release (Gas) i 3.

Number of releases during the 1st Quarter 6.0E+00 4.

Total time duration for all releases of type listed above 7.37E+02 l

minutes 5.

Maximum duration for releases of type listed above 1.32E+02 i

minutes i

6.

Average duration for all releases of type listed above 1.23E+02 minutes 7.

Minimum duration for release of type listed above 1.15E+02 minutes 8.

For liquid batch releases only, provide the average stream l

flow (dilution flow) during the period of release.

N/A 1

l

'e l

1 i

i M P80 15 42/1 16-B

TABLE 4A-1 ( Co nt ' d )

1 SALEM NUCLEAR GENERATING STATION (1981)

]

UNIT 1

SUMMARY

SilEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCli MODE BATCli RELEASES ONLY

{E 1.

Dates April 1 - June 30, 1981

!j g 2.

Type of release (Ga s )

!g

)

3.

Number of releases during the 2nd Quarter 2.50E+01 i

l 4.

Total time duration for all releases of type listed above j

7.13E+03 i

minutes 5.

Maximum duration for releases of type listed above 1. 8 6 E+0 3 minutes 6.

Average duration for all releases of type listed above

2. 8 5 E+ 0 2 minutes l

7.

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

i M P80 15 30 1/2 17-A lI 4

J

--n,-.,

w----

I TABLE 4A-2 ( Co nt 'd )

SALEM NUCLEAR GENERATING STATION (1981)

UNIT 2 l

SUMMARY

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

1.

Dates April 1 - June 30, 1981 2.

Type of release (Gas) 3.

Number of releases during the 2nd Quarter 4.0E+01 4.

Total time duration for all releases of type listed above 4.65E+03 minutes 5.

Maximum duration for releases of type listed above 2.15E+02 minutes 6.

Average duration for all releases of type listed above 1.16E+02 minutes.

7.

Minimum duration for release of type listed above 6.lE+01 minutes For liquid batcli releases only, provide the average stream 8.

flow (dilution flow) during the period of release.

N/A

!I

I M P80 15 44/1 17-B

ri l

l TABLE 4B-1 I

l S ALEM NUCLEAR GENERATING STATICN (1981) i UNIT 1 I

1

SUMMARY

SilEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCII MODE BATCil RELEASES ONLY 1

1.

Dates January 1 - March 31, 1981 2.

Type of release (Liquid) 3.

Number of releases during the 1st Quarter 5.lE+01 I

a i

4.

Total time duration for all relcases of type listed above 1,09E+04 mi iutes 5.

Maximum duration for releases of type listed above 6.41E+02

~

minutes t

6.

Average duration for all releases of type listed above 2.14E+02 l

minutes 7.

Minimum duration for release of type listed above 7.5E+01 l

minutes 8.

For liquid batch releases only, provide the average stream j

flow (d ilu tion f low ) during the period of release.

1.85E+05 j

gpm I

i 1

j 1(!

1 M P81 3 06/1 18-A 1

TABLE 4B-2 S ALEM NUCLEAR GENERATING STATION (1981) i UNIT 2

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE

'I BATCH RELEASES ONLY 1.

Dates January 1 - March 31, 1983 2.

Type of release ( Liquid )

3.

Number of releases during the 1st Quarter 3. 2E+01 4.

Total time duration for all releases of type listed above 9.10E+03 minutes l

5.

Maximum duration for releases of type listed above 1.03E+03 3

minutes 6.

Average' duration for all releases of type listed above 2.84E+02 minutes

'I 7.

Minimum duration for release of type listed above 1.60E+02 minutes 8.

For liquid batch releases only, provide the average stream I

flow (dilution flow) during the period of release.

1.85E+05 gpm I

'I I

I M P81 3 06/2 18-B I

I TABLE 4B-1 ( Cont 'd )

SALEM NUCLEAR GENERATING STATION (1981)

UNIT 1

SUMMARY

SilEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCil MODE I

BATCII RELEASES ONLY 1.

Dates April 1 - June 30, 1981 2.

Type of release ( Liquid )

3.

Number of releases during the 2nd Quarter 3.9E+01 4.

Total time duration for all releases of type listed above 7.91E+03 minutes 5.

Maximum duration for releases of type listed above 3.88E+02 minutes 6.

Average duration for all releases of type listed above 2.01E+02 i

minutes 7.

Minimum duration for release of type listed above 1.59E+02_

minutes 8.

For liquid batch releases only, provide the average ctream flow (dilution flow) during the period of release 1.05E+05 gpm

'I I

M t 81 3 0 5/1 19-A

)

I

!I i

TABLE 4B-2 ( Cont 'd )

SALEM NUCLEAR GENERATING STATION (1981)

UNIT 2

SUMMARY

SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE I

BATCH RELEASES ONLY l.

Dates April 1 - June 30, 1981 2.

Type of release ( Liquid )

3.

Number of releases during the 2nd Quarter 6.6E+01 I

4.

Total time duration for all releases of type listed above 3.86E+04 ininute s 5.

Maximum duration for releases of type listed above 7.80E+02 i

minutes 6.

Average duration for all releases of type listed above

2. 81E+ 0 2 minutes 7.

Minimum duration for release of type listed above 1.59E+02 iiiinutes 8.

For liquid batch releases only, provide the average stream flow (dilution flow) during the period of release 1.96E+05 gpm I

I I

M P81 t 05/2 19-B

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1 101 10 33181 STAltILITY CLASS: MODERATELY STADLE DELIA T 1.5 TO 4.0 "

1 LAPSE RATE IN DEG C/100 METERS EVALUATED llSING DELTA T 300-33 FT E L Et.' AT I OtJ :

300 FEET 3444444************'*************************************************

WINIiSPEED (MPH) Ai 300 I^EET W Itiit DLREC-TION 1-3 4-7 0-12 13-10 19-24

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0 110URS OF MISSING DATA:

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E E

1 ARTIFICIAL ISLAND SALEM UNIT 1 I

i l

f'ERIOD OF RECORD:

1 181 10 53181 i

STABILIfY CLASS: MODERAIELY STABLE DELfA T 1.5 TO 4.0

!. APSE RATE IN DEG C/100 METERS l

EVALUAfED USING DELTA f 300-33 FT i

fLEVATION:

300 FEET I

J (* $ $ $ $ & & & & * * * *

F * $ $ t $ $ & $ F $ $ $ $

F 4 4 4 * $ $

k ** v 4 & * * * ** * * * & $ # * * *

k & ** *

t &

WINDSPEED (MPH) AT 300 FEET W[ND DtREC-1 It)N 1 --3 4-7 8-12 13-18 19-24

-24 Till AL o

N 1

8 8

4 0

0 21 NNE 3

2 2

1 0

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NE 1

5 1

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SE 1

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11 21 fiSE 1

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2 6

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40 SW 0

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10 4

9 1

27 WNW 0

0 1

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Nw 0

2 4

12 6

1 25

?

NNW 0

1 5

13 5

0 24 TOTAL 11 35 75 100 60 28 309 i

i PERIODS OF CALM (HOURS)!

O liOURS OF MISSING DATA:

1 TABLE 6 Page 6 of 8 i

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ML20040B684

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