Text

Semiannual Radioactive Effluent Release Rept,Jan-June 1982
	ML18086B628
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Site:	Salem
Issue date:	08/31/1982
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0 PS~G The Energy People M P79 43/33 1982 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT RERR-12 SALEM NUCLEAR GENERATING STATION SALEM UNIT NOS. 1 & 2 UNIT l DOCKET NO. 50-272 UNIT 2 DOCKET NO. 50-311 OPERATING LICENSE NO. DPR-70 OPERATING LICENSE NO. DPR-75 AUGUST 1982

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M P79 43/33 REPORT NO. RERR-12 UNIT NOS. 1 & 2 RADIOACTIVE EFFLUENT RELEASE REPORT JAN -

JUNE 1982 SALEM NUCLEAR GENERATING STATION Public Service Electric and Gas Company DPR 70 DPR 75

Introduction SALEM NUCLEAR GENERATING STATION UNIT 1 50-2 72 UNIT 2 50-311 UNIT NOS. l AND 2 RADIOACTIVE EFFLUENT RELEASE REPORT January 1, 1982 to June 30, 1982 This report, RERR-12, summarizes the releases of radioactive materials in liquid, gaseous and solid form from the Salem Nuclear Generating Station Units 1 and 2 for the period January 1, 1982 to June 30, 1982.

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

Unit 1 generated 1,560,000 megawatt-hours of electrical energy (net) during the reporting period.

Unit 2 generated 4,493,310 megawatt-hours of electrical energy (net) during the reporting period.

Included is corrected page 10-A for report RERR-11 summariz-ing gaseous releases from Salem Unit 1.

M P79 43/33 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT RERR 12 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 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, building wake effects and physical characteristics of the radionuclides released~

In addition 40CFR190 regulations require that the annual dose 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 Activ"ation 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 from 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 80 millirads for gamma and beta radiation respectively.

At any instan~ the. release rate of radioactive gases must sat_isfy the following equations whose basis is 1CJCFR20.

2. 0 Qtv*Kv~ 1 0.33 Otv*<Lv + 1.1 Nv) < 1 M P80 17 18 I

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

The asis for these equations is 10CFRSO Appendix I.

13 Otv*Nv

< 1 6.3 Otv*Mv < 1 The limiting Unit 1 release limit Q is calculated to be l.07E+04 and l.50E+04 microcuries/sec for both the 1st and 2nd quarters respectively.

The limiting Unit 2 release limit Q is calculated to be l.36E+04 and 1.54E+4 microcuries/sec. for the 1st and 2nd quarters respectively.

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*t.v *Nv < 1 13 Otv*Mv < 1 The release limits of radioactive gases for the Salem Nuclear Generating Station are not fixed numbers, but depend upon the 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.

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.

Releases of iodines and particulates are further restricted to prevent any member of the general public from receiving a dose rat~ jn 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 than 8 days is limited by the equation below.

The basis for this equation is 10CFR20.

(1.5 x 10 5 ) Ov ~ 1 M P80 20 06/1 r

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 and Ov x 13 x (1.5 x 105) < 1 During any twelve month period radioactive releases should conform to the following constraints of 10CFR50 Appendix I.

25 x (1.5 x 105) x Ov ~ 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, Column 2.

In addition, the following limits apply:

The cumulative release of radioactive effluents, e~cluding tritium and dissolved gases, shall be less than 10 Ci in a calendar quarter for each tinit.

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

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.

a.

Fission Gases -

MPC values were not used to determine the maxi~um ~elease rates.

b.

Iodines - -MPC 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.

M P80 20 06/2 0

Average Energy Regulatory Guide 1.21 requires that 'the licensee provide the average energy of the radionuclide mixture in releases of fission and activation gases, if applicable.

Release limits for the SNGS are riot 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 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 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 re.leases included releases from the waste monitor tanks, waste monitor hold-up tank, and the chemical and volume control tanks.

Continuous releases included releases from intermittent blowdown of the steam generators.

The predominate gamma emitting isotopes detected were Co58, 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 th~ final release point of all 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 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 tri tiu.m samples were taken by bubbling gas through

_water and then counting the tritiated water on a liquid scintillation counter

M P80 19 11 L

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

This error is due primarily to variability of waste stream flow rates and changes in isotopic distributions of waste streams be-tween sampling periods.

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

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

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

6.0 Unplanned Releases During this reporting period an unplanned release of 4.lSE-04 curies'of Xe-133 occurred from a leak of a temporary connector to a pipe in the spent fuel pool area.

This incident was reported to the USNRC in a Licensee Event Report.

M P80 18 05/l Part B. Gaseous Effluents See Summary Tables lA-1 thru lC-1 representative of Salem Unit 1 operations.

See Summary Tables lA-2 thru lC-2 representative of Salem unit 2 operations.

Part c. Liquid Effluents See Summary Tables 2A-l and 2B-l representative of Salem Unit 1 operations.

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

Part D. Solid Waste See Summary Table 3 Units 1 and 2 M P82 3 07/3 Part E.

Radiological Impact on Man*

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

The population dose impact is based on historical site spe-cific data i.e., food production, milk production, feed for milch animals and seafood production.

The doses were calculated using methods described in Reg-.

ulatory Guide 1~109 and represent calculations for the sii month reporting interval.

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

Liquid Pathways Doses to individuals in the population fr6m liquid re-leases are primarily from the seafood ingestion pathway.

The total body dose to an individual was calculated to be l.30E-2 mrem.

The calculated population total body dose was 2.69E-l person-rem.

The highest organ dose.from liq-uid releases was l.30E-l mrem to the gastrointestinal tract.

Air Pathways The resulting whole body and skin doses to an individual were calculated to be 6.00E-4 mrem and 7.68E-S mrem re-spectively.

The calculated population total body dos~ was 4.12E~2 person-rem.

The average total body dose to the population within fifty miles of the site was 7.70E-6 mrem/person.

Direct Radiation Direct radiation may be estimated by TLD measurements.

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

TLD measurements on site near the Service Water pumps (location 1181) and near the Cir-culating Water pumps (location lOSl) averaged S.93 and S.80 mrads/months, respectively, apparently due to trace activity in the Refueling Water Storage Tank.

TLD's at onsite locations 2S2 and SS! which are-o.3 miles*

arid-0.9 miles from the reactor containmenti *average"tl 4.78 and 4.18 mrads/month respectively.

The values for sta-tions 2Sl and SS! are within the statistical variation associated with the preoperation program results.

M PBO 17 14 All offsite monitoring locations remained within preoperational ranges.

It should be noted that the nearest resident is 3.5 miles away.

It can thus be con~luded that there was no meastirable dose to any offsite locations from direct radiation.

Part F.

Meteorological Data Cumulative joint wind frequency distribution by atmos-pheric stability class at the 300 foot elevation is pro-vided for the first and second quarters of 1982 as Table 5 and 6

M P80 17 14 1/2

-Sa-

..l fiD :U-Z:.

.l t\\ -

.l EFF~UENT AND WASTE DISPOSAL SEMI I GASEOUS EFFLUENTS-SUMMATIO UNIT 1 A.

Fission & Activation Gases

1.

Total release

2.

Average release rate for period

3.

Percent of technical specification limit (See ETS Spec. 2.3.3.b)

B.

Iodines

1.

Total iodine-131

2.

Average release rate for period

3.

Percent of technical specification (2Ci) limit

c.

Particulates

1.

Particulates with half-lives> 8 da s

2.

Average release rate for period

3.

Percent of technical specification limit

4.

Gross alpha radioactivity (2)

D.

Tritium

1.

Total release

2.

Average release rate for period UAL REPORT (1982)

ALL RELEASES Unit Ci uci/sec.

Ci uCi/sec.

Ci uCi sec.

Ci Ci uCi/sec.

1st Quarter 2.95E-Ol 3.79E-02 3.54E-04 5.49E-04 7.06E-05 2.75E-02 6.83E-06 8.78E-07 l.33E-03 2.12E-03 2.72E-04 N/A (1)

For batch release~ the estimated overall error is within 10%.

(2)

Analyses indicate no measurable alpha emitting transuranics.

M P8014/23 1 9-A 2nd Quarter Est.Total(!)

Error %

2.50E-Ol 2.50E+Ol 3.18E-02 2.12E-04 9.88E-04 2.SOE+Ol l.26E-04 4.94E-02 2.50E+01 1.41E+OO 2.SOE+Ol l.79E-Ol N/A

.I Jill*' I

EFE;LUENT AND I GASEOUS A.

Fission & Activation Gases

1.

Total release TAl:fLt: !A- :l WASTE DISPOSAL SEM EFFLUENTS-SUMMATI UNIT

2.

Average release rate for period

3.

Percent of technical s ecification limit (See ETS Spec. 2.3.3.b)

B.

Iodines

1.

Total iodine-131

2.

Average release rate for period

3.

Percent of ~echnical specification limit C *. Particulates

1.

Particulates with* half-lives> 8 days

2.

Average release rate for period

3.

Percent of technical specification limit 4

Gross alpha radioactivity (2)

D.

Tritium NNUAL REPORT (1982)

ALL RELEASES Unit Ci uCi/sec.

Ci uCi/sec.

Ci 1st Quarter 3.82E-01 4.91E-02 3.61E-02 5.95E-04 7.GSE-05 3.85E-03 l.29E-03

1.66E-04 2.52E-01 2nd Quarter Est. Total (1)

Error: %

l.04E+02 2.SOE+Ol l.32E+03 8.57E-00 2.lSE-04 2.SOE+Ol 2.74E-05 l.OBE-02

~~-l-.~-T-o_t_a_l~r-e_l_e_a~s-e~~~~~~~~~~~~~~~~~~~~-C~i~~~~~~~~~~l-.-6-3_E_+_O_O~~~~~~~_.~

2.

Avera e release rate for eriod uCi/sec.

2.07E-01

3.

Percent of technical specification limit N A N A

( 1)

( 2)

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

Analyses indicate n6 measurable alpha emitting transuranics.

M P8014/23 2 9-B

M P80 14/20 l 10-A

I TABLE iB.

EF~LUENT AND WASTE DISPOSAL SE UAL REPORT (1982)

GASEOUS EFFLUENTS-EL

.ED RELEASES (Continued)

UNIT 1 CONTINUOUS MODE BATCH MODE 1st 2nd*

1st 2nd Nuclides Released Unit 1 Quarter

. Quarter Quarter Quarter

3.

Particulates Chrominum-51 Ci e

Manganese-54 Ci Cobalt-58 Ci 3.65E-06 Cobalt-60 Ci 3.18E-06 Iron-59 C1 Rubidium-88 Ci Yttrium-88 Ci Strontium-89 Ci Strontium-90 Ci Niobium-95 Z1rcon1um-95 C1 Tin-117m Ci Cesium-138.

Ci Ces1um-137 C1 Cesium-139 Ci Gross Alpha Ci a

Total For Period Ci 6.83E-06 4

Tritium Tritium Ci E 0 l.41E+OO 2.12E-03 E 0 M P8014/20 2 10-B

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1982)

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

Quarter Quarter Quarter 1

Fission gases KrY:pton-85 Ci 5.l 6E-02 K rypton-8 Sm Ci Kr pton-87 Ci Krypton-88 Ci Xenon-133 Ci l.38E-02 l.04E+02 3.09E-01 Xenon-135 Ci 7.29E-03 8.97E-03 xenon-135m Ci Xenon-138 Ci Xenon-133m Ci Argon-41 Ci Fluorine-18 Ci Unident1f ied Ci Total for period Ci 2.llE-02 l.04E+02

3. 61 E-01

2.

Iodines e

Iodine-131 Ci 5.95E-04 4.99E-05 Iodine-133 Ci l.65E-04 Iodine-135 Ci Total for period Ci 5.95E-04 2.lSE-04 M P80 14/24 l 11-A

TABLE lB-2 EFFijUENT AND WASTE DISPOSAL SEM UAL REPORT (1982)

GASEOUS EFFLUENTS-ELE D RELEASES (Continue UNIT 2 CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd Nuclides Released Unit 2 Quarter Quarter Quarter Quarter

3.

Particulates Chrominum-51 Ci Manganese-54 Ci Cobalt-58 Ci Cobalt-60 Ci l.29E-03 Iron-59 Cl.

Rubidium-88 Ci Yttrium-88 Ci Strontium-89 Ci Strontium-90 Ci Niobium-95 Ci Zirconium-95 Cl.

Sr-85 Ci Cesium-134 Ci Cesium-137 Ci Cerium-139 Ci Gross AlEha Ci Total For Period Ci l.29E-03

4.

Tritium Tritium Ci O.OOE+OO l.63E+OO O.OOE+OO O.OOE+OO M P80 14/24 2 11-B

TABLE lC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1982 UNITS 1 AND 2 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES Nuclides Releases Unit 1st Quarter 2nd Quarter 1st Quarter 2nd Quarter There were oo ground level releases for the :p::riod of record

M P80 18 05/3 TABLE 2A-l

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT ( 1982)

UNIT 1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Fission and activation roducts

1. Total release (not including

tritium, ases, al ha)

2. Average diluted concentration durin eriod

3. Percent of applicable limits of Technical S ecif ications 1st Units Quarter Ci

l. lOE+OO uCi/ml l.17E-07 l.lOE+Ol 2nd Quarter 5.82E-01 6.58E-08 5.82E+OO release C1 erage diluted concentration durin uCi/ml 9.00E-06 l.41E-05 Dissolved and entrained ases

1. Total release

2. Average diluted concentration durin eriod Gross al ha radioactivit

1. Total release Volume of waste release (prior to dilution -

Batch Release)

Voi:ume of dilution water used*

durin eriod -

Batch Release Not Applicable 1 3 07/2 Ci 3.17E-01 3.SOE-01 uCi/ml 3.38E-08 3.95E-08 N A N/A Ci O.OOE+OO O.OOE+OO liters 3.65E+06 3.21E+06 liters 9.37E+09 8.85E+09 13-A Est. Total Error, %

2.SOE+Ol 2.50E+Ol 2.50E+Ol 2.50E+Ol

TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1982)

UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES A. Fission and activation products

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

2. Average diluted concentration during period

3. Percent of applicable limits of Technical Specificat"ions release

. Average diluted concentration during eriod

3. Percent of applicable 1 imi t

c. Dissolved and entrained gases

1. Total release

2. Average diluted concentration during period

3. Percent of applicable 1 imi t D. Gross alpha radioactivity

1. Total release E. Volume of waste release *(prior to ~*anution -

Batch Release)

F

Volume of dilution water used during period -

Batch Release N/~Not Applicable 1st Units Quarter Ci l.12E+OO uCi/ml 8.68E-08 l.12E+Ol Ci l.18E+02 uCi/ml 9.lSE-06 N A Ci S.48E-01 uCi/ml 4.25E-08 N/A Ci O.OOE+OO liters 4.79E+06 liters l.29E+l0 M P81 3 07/1 13-B 2nd Quarter 6.30E-01 7.llE-08 6.30E+OO 1.14E+02 l.29E-05 N A 2.81E-01 3.17E-08 N/A O.OOE+OO 3.12E+06 8.86E+09 Est. Total Error, %

2.SOE+Ol 2.SOE+Ol 2.SOE+Ol 2.SOE+Ol 2.SOE+Ol

TABLE 2B-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1982)

LIQUID EFFLUENTS UNIT l Nuclides Released Strontium-89 Strontium-90 Cesium-134 Cesium-137 Iodine-131 Iodine-132 Iodine-133 Iodine-134 Iodine-135 Cobalt-58 Cobalt-60 mium-109 anese-54 romium-51 Cesium-136 Zirconium-95 Tin-113 Barium-140 Lanthanum-140 Cerium-139 Cerium-141 Tungsten-187 Niobium-95 Antimony-124 Antimony-125 Tritium Iron"".'59 Sodium-24 Silver-llOm

__ Total for_ period (above) excluding H3 Xenon-133m Xenon-133 Xenon-135

=-pton-88 on-41 M P81 47 04/1-srd Unit Ci Ci Ci C1 Ci Ci C1 Ci C1 C1 Ci Ci C1 Ci Ci Ci Ci Ci C1 Ci C1 C1 Ci Ci Ci Ci Ci Ci Ci ci Ci C1 Ci Ci Ci CONTINUOUS MODE 1st Quarter 14-A 2nd Quarter BATCH MODE 1st Quarter 9.56E-03 l.lOE-02 3.75E-02 3.03E-04

1. 85E-04 l.65E-04 3.52E-04 6.64E-01 2.40E-01 4.37E-02 5.65E-02 7.27E-03 2.41E-04 7.41E...;05

1. 35E-03 l.33E-02 6.54E-03 3.17E-03 8.43E+Ol

1. 66E-03 9.70E-04 I. lOE+OO 3.05E-04 3.16E-01 5.04E-04 2nd Quarter 3.95E-03 l.OSE-02 3.03E-04

1. 65E-04

2. 97E.;..Ol l.76E-Ol 8.22E-02 4.07E-03 l.13E-03 3.94E-03 9.28E-04 l.25E+02 7.79E-04 l.SOE-04 8.30E-04 5 ~ 8 2E-01.

l.33E-03 3.41E-Ol 7.54E-03

TABLE 2B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT ( 1982 )*

Nuclides Released Strontium-89 Strontium-90 Cesium-134 Cesium-137 Iodine-131 Iodine-132 Iodine-133 Cobalt-58 Cobalt-60 Cadmium-109 Manganese-54 omium-51 ium-141 conium-95 Tin-113 Barium-140 Lanthanum-140 Ce~ium-134 Mercury-203 Niobium-95 Antimony-124 Antimony-125 Tr1t1um Iron-59 Sodium-24 Tellerium-125m Tellerium-132 Total for period excluding H3 Xenon-133m Xenon-133 Xenon-135 Krypton-88 Argon-41 1 P81 47 04/2 LIQUID EFFLUENTS UNIT 2 Unit Ci Ci Ci Ci C1 Ci Ci Ci Ci Ci C1 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci C1 Ci Ci Ci Ci (above)

Ci Ci Ci Ci Ci C1 CONTINUOUS MODE 1st Quarter 14-B 2nd Quarter BATCH MODE 1st Quarter 3.25E-03 6.93E-03 l.08E-01 7.51E-04 4.17E-04 6.62E-01 2.14E-01 4.15E-03 3.76E-02 4.90E-02 6.98E-04 5.18E-03 7.37E-05 9.65E-04 6.82E-05 l.15E-02 9.00E-03 6.17E-03 l.18E+02 l.09E-03 7.24E-04 l.69E-03 7.26E-04 l.12E+OO

1. 82E-04 5.47E-01 9.21E-04 2nd Quarter l.33E-02 2.14E-02 7.07E-04 3.18E-01 l.82E-01 8.99E-02 6.84E-0 2.72E-03 3.61E-04 4.85E-04 l.14E+02

8. 89E-05*

6.30E-01 2.77E-0],

4.35E-03

I.

TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1982 JANUARY -

JUNE 1982 UNITS 1 AND 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 Units Period Error, %

a.

Spent resins, filters sludges, m3 l.85E+02 evaporator bottoms Ci 2.03E+02

1. 50E+Ol

b.

Dry compressible waste, m3 7.86E+02 contaminated equip.

Ci 7.53E+OO l.50E+Ol

c.

Irradiated components, m3 O.OOE+OO control rods, Ci O.OOE+OO

d.

Others (describe) m3 O.OOE+OO Ci O.OOE+OO 2

stimate of major nuclide composition (by type of waste)

Cobalt -

58 79.9%

l.62E+02

.Cobalt -

60 12.4%

2.52E+Ol Manganese -

54 3.0%

6.09E+OO Cs-134 2.5%

5.075E+OO cs-137 2.2 %

5.486E+OO b..

Cobalt -

58 79.9%

6.016E+OO Cobalt -

60 12.4%

0.934E+OO Manganese -

54 3.0%

0.226E+OO cs-134 2.5%

0.l 88E+OO Cs-137 2.2%

0.166E+OO

c.

. E

d.

E

3.

Solid Waste Disposition Number of Shipments Mode of Transportation 49 Truck 11 Truck I

IATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Transportation None N/A Destination

Barnwell, South Carolina Hanford, wash.

Destination N/A

>80 14/21 1 TABLE 4A-l SALEM NUCLEAR GENERATING STATION (1982)

UNIT l

SUMMARY

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

1.

Dates January 1 -

March 31, 1982

2.

Type of release (Gas)

3.

Number of releases during the 1st Quarter 2. OE+Ol

4.

Total time duration for all releases of type listed above 5.03E+03 minutes

5.

Maximum duration for releases of type listed above l.53E+03 minutes Average duration for all releases of type listed above 2.51E+02 minutes

7.

Minimum duration for release of type listed above 6.SE+Ol 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

TABLE 4A-2 SALEM NUCLEAR GENERATING STATION (1982)

UNIT 2

SUMMARY

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

1.

Dates January 1 -

March 31, 1982

2.

Type of release (Gas)

3.

Number of releases during the 1st Quarter 5.0E+O

4.

Total time duration for all releases of type listed above 6.43E+02 minutes

5.

Maximum duration for releases of type listed above l.37E+02 minutes Average duration for all releases of type listed above I°.29E+02 minutes

7.

Minimum duration for release of type. listed above l.20E+02 minutes

8.

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

N/A.

M P80 15 42/1 16-B

TABLE 4A-l (Cont'd)

SALEM NUCLEAR GENERATING STATION (1982)

UNIT 1

SUMMARY

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

1.

Dates April 1 -

June 30, 1982

2.

Type of release (Gas)

3.

Number of releases during the 2nd Quarter 2.8E+Ol

4.

Total time duration for all releases of type listed above 2.01E+03 minutes

s.

Maximum duration for releases of type listed above l.32E+02 minutes

6.

Average duration for all releases of type listed above 7.17E+Ol minutes Minimum duration for release of type listed above 6.0E+Ol 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 1/2 17-A

I.

e TABLE 4A-2 (Cont'd)

SALEM NUCLEAR GENERATING STATION (1982)

UNIT 2

SUMMARY

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

1.

Dates April 1 -

June 30, 1982

2.

Type of release (Gas)

3.

Number of releases during the 2nd Quarter O.OE+O

4.

Total time duration for all releases of type listed above O.OE+02 minutes

5.

Maximum duration for releases of type listed above O.OE+O minutes

6.

Average duration fo~all releases of type listed above O.OE+O minutes Minimum duration for release of type listed above O.OE+O minutes

8.

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

N/A M P80 15 44/1 17-B

TABLE 4B-l SALEM NUCLEAR GENERATING STATION (1982)

UNIT l

SUMMARY

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

1.

Dates January 1 - March 31, 1982

2.

Type of release (Liquid)

3.

Number of releases during the 1st Quarter 5.8E+Ol

4.

Total time duration for all releases of type listed above l.26E+04 minutes

5.

Maximum duration for releases of type listed above 3.96E+02 minutes Average duration for all releases of type listed above 2.17E+02 minutes

7.

Minimum duration for release of type listed above l.57E+02 minutes

8.

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

l.98E+05 gpm M P81 3 06/l-mw 18-A

TABLE 4B-2 SALEM NUCLEAR GENERATING STATION (1982)

UNIT 2

SUMMARY

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

1.

Dates January 1 -

March 31, 1982

2.

Type of release (Liquid)

3.

Number of releases during the 1st Quarter 7.6E+Ol

4.

Total time duration for all releases of type listed above l.72E+04 minutes

5.

Maximum duration fo~ releases of type listed above 4.18E+02 minutes Average duration for all releases of type listed above 2.27E+02 minutes

7.

Minimum duration for release of type listed above l.45E+02 minutes 8..

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

l.95E+05

gpm M P81 3 06/2-mw 18-B

TABLE 4B-l (Cont'd)

SALEM NUCLEAR GENERATING STATION (1982)

UNIT l

SUMMARY

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

1.

Dates April 1 -

June 30, 1982

2.

Type of release (Liquid)

3.

Number of releases during the 2nd Quarter 5.2E+Ol

4.

Total time duration for all releases of type listed above l.03E+04 minutes

5.

Maximum duration for releases of type listed above 3.01E+02 minutes

6.

Average duration for all releases of type listed above l.98E+02 minutes Minimum duration for release of type listed above l.03E+02 minutes

8.

For liquid batch releases only, provide the average stream flow (dilution flow) during the period of release 2.24E+05 gpm M P81 3 05/1 19-A

I TABLE 4B-2 (Cont'd)

SALEM NUCLEAR GENERATING STATION (1982)

UNIT 2

SUMMARY

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

1.

Dates April 1 -

June 30, 1981

2.

Type of release (Liquid)

3.

Number of releases during the 2nd Quarter 5. OE+Ol

4.

Total time duration for all releases of type listed above l.lOE+04 minutes

s.

Maximum duration for releases of type listed above 4.35E+02 minutes

6.

Average duration for* all releases of type listed above 2.20E+02 minutes Minimum duration for release of type listed above l.21E+02 minutes

8.

For liquid batch releases only, provide the average stream flow (dilution flow) during the period of release 2.18E+05 gpm M P81 3 05/2 19-B

ARTIFICIAL ISLAND D1~l... EM UNIT 1 PERIOD OF RECORD:

1 182 TO 33182 STABILITY CLASS: ALL STABILITIES EXCLUDING MISS SPEED/DIR DATA LAPSE RATE IN DEG C/100 METERS EVALUATED USING DELTA T 300-33 FT ELEVATION:

300 FEET l.JIND DJl:;:EC*-

TJON l ****:~

4**-7 N

4 19 NNE 3

1.*7 NE

'°)

I.:~

!:::NE 3

1. "7 r..

4

J.6 ESE

)

4

!:;E 3

9

~:;~3E 1::*

,.}

/

.::~ '*'

3 2:1.

~:;s~J

I.

J. :s

~:;w 4

u.

l.JSl,J 4

~:.:;

l.J 3

B l,JNW 2

I.:~

NW

l 6

i'lNtJ 2

1.4 TDTr'.:il...

4f.>

I. <1:~i PERIODS OF CALM <HOURS>:

4 HOURS OF MISSING DATA:

1.36 WINDSPEED <MPH> AT n-:1.2

1.3*-*:l.B

~'if.i 44 3"7 64 40 43

~6

1.0 2B

I. :J.

7 6

I 20 3~:i 3:1.

42 24 3:::;

'")C:"

..:..""J

~i4

'")r::"

k~J 4"7 20 24

~5B

3

~4

/f.)

28 70 46

~=.=;~;

49:7i f.>f.19 TABLE 5 Page 1 of 8

1.<1*-*24 4

'")r)

J. ~5

1.

4

~

3:1.

24 9

J.3

!:j 48

'""} )

I f.i:I.

2"7 3f.i9

1.

1.2B

()

1. 43 4

ll/

j,

\\~) [:

~~

(.)~=.=;

t.

22

1.3.

1.:1.:1.

I.fl

I. 0

LO

1.34

I. :I./

1.:1.4

I. 0 :'.'.i 2:1.

/<)>

'.'i:3 203

~59 236 30

t. '16

~~

1.47

ARTIFICIAL ISLAND SALEM UNIT

I.

PERIOD OF RECORD:

I.

1.82 TO 33182 STABILITY CLASS: EXTREMELY STABLE DELTA T >4.0 ~

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

300 FEET l.. JIND DIF<:EC****

TIDN J.*<~

4.... *7 N

0

()

i""--!NE:

0

()

NE

()

[NI::

()

F

()

0 E'.3E

()

0

E

()

'.:>SE

()

0

()

~

'.'.) ~; ~J 0

()

1.~

0

()

l.. J'.3W

()

0 l-~

()

l.. JN~.J

()

0 1-~l~

()

0 NNW

()

TOTf.1l..

()

2 F" [ F:: I U D :::; DF CALM ( 1-IDUF~!:l) t

()

t HOUF~!:; DF MI!'.!'.'.!INC:l DATf.1:

()

WI ND!:IPEED <MPH)

AT B-.. :!.'.~?.

0

()

1.

I.

1

()

0

()

I.

Ci

1.3**.. :1.D

I.

0 0

()

3 4

7 6

0

()

I.

()

I.

0

)Z

.*..,,)

TABLE 5 Page 2 of 8

~~()()

FEET

I. 9****?4

>24

()

0 0

()

0 0

'")

")...

.~

l.~i 9

3

()

)...

1.

0

()

0

")...

0

)

0

()

0

()

1.B 2::.~

TClTt1I...

I.

()

I.

fl

~.. :.~2 22 B

I.

()

5

)

.~

I.

'J :I.

ARTIFICIAL ISLAND S{~LEM UN IT 1.

~n1~1BILITY CLA~;s: MClDEF~ATELY STABLE DELT(.1 T

I. +!:'i TD 4.0 "'

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

300 FEET

- - - - ~*****************************************************.*****

l.J I ND D l F:F:c;....

fIUN l.... ~5 4.... '7 N

()

j-.Ji'~E

()

NE

()

!:~NE

1.

()

.. \\'"

()

)

C'.3E:

()

1.

'.:!E

()

'.:>SE

()

1.

()

1::*

~J

'.:!'.3l1J 0

1.

'.3l..J

()

l.oJSV.J

()

1.

1,J

()

l l.oJNW

()

0 i'.!W

L

()

NNW

()

TOT(.1l..

")

1.2 i::* E 1:;: I 0 D ~; CJF' Ct1LM

< HDUl:~~3) *

I.

HCJUJ:;:s DF MI !:!t! I NG D{~Tti!

6 l.JINDSPEED <MPH) AT 13.... :I. 2

")

I.

()

I.

~:_;;

").

1:~

,.}

~5 l

3

L

l

1.

2

1.

()

3~)

l.3*--:1.B B

I.

3

")...

"l

,,)

3 4

<y B

1. 3

I. 1.

1.

3

I.

6 6

B~.~

TABLE 5 Page 3 of 8 300 FEET

1. 11.... 24

>24

()

I.

0

()

0

()

I.

0

)

0

1. 3

!3

7

()

El

)...

"l 1::*

~J 4

L

1.

0 3

0

~3 0

3

()

0 4D

1.6 TDT(..)I...

I.()

"l

... )

3 4

I. :I.

n 30 20

~rn 24

Ll 4

B,

C)

I. 1.

f>

l ?~.=;

ARTIFICIAL ISLAND

~:lf~Ll:::M UNIT

l.

PERIOD OF RECORD:

1 182 TO.33182 STABILITY 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

[... JINI:i DI F\\E:C*...

TIDN

1.*.. *3 4*-'7 N

5 f'

i NNE 1

6 l'*ll::

0 t>

FNE 0

I. 1

)

l E:.SE 1

2

i: :

3 6

>SE 4

5

,**~

()

'7 I

: :3W 0

"?

I

w

'")

b 1,.. J '.3 ~J 1

'"l 1..J 1

'")

1..JNl*J 1

~:;

i"-~W

()

4 i\\!NW

'")

'7 I

TOTi~1L 21

91.

r:*E~F;:IUDS Cl 1:~ CALM

<HOUF~S) *

I.

HDUFo:S CJF MISSING DfHA:

20 WINDSPEED 8-.. 12

))

l.4 23 le>

B 4

'7 9

I.()

14 1 ~:;

1.0 19 ti

1.2

I. '7 20fl

<MPH) AT

1.~5.... :1.B

I.</

34 16 1;:*

f.i r)

1. '7

1.3

1.l

)'/

J..'.. I

~~~~

'7

) **v

.i.*.. '\\o')

46 3~'5

l.B 3:1. 'l TABLE 5 Page 4 of 8 300 FEET 1 </.. **24

>24

I.

1

'7 0

"l

,,)

0

I.

1

~5

'")

()

l.

1.0

~

8

()

i. '*'

~5

?

2

~~

I.

)

B

i.n

1.0 3:1.

.l. '*'

31

1.3 El

()

13<)>

~=.:j ~*5 r

TOTAi...

~':i4 6':>

~

4B 34 2B

I. 0 46 3<_>>

4"~

- - J

~5'7

~:i </

3()

'73

<n 9~5 1::*11

\\.J11..*.*

B2</

ARTIFICIAL ISLAND SALEM UNIT 1 PERIOD OF RECORD:

1 182 TD 33182 STABILITY CLASS: NEUTRAL DELTA T -1.5 TO -0.5 ~

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

300 FEET WIND DI REC-TIDN 1-3 4-7 N

1 11 NN~

1 11 NE 1

6 ENE 1

6 r

~

7 ESE 1

1 SE 0

~

SSE 1

1 0

3 7

~

SSW 1

6 SW

~

5 WSW 3

2 w

~

5 WNW 1

7 NW 0

~

NNW 0

7 TOTAL 20 86 PERIODS OF CALM CHOURS>:

~

HOURS OF MISSING DATA!

101 WINDSPEED CMPH> AT 8-12 31 21 17 19 15 0

7 I

17 6

6 8

8 18 20 11 26 2~0 13-18 15 27 19 3

~

1 11 14 3

8 4

16 25 24 23 26 221 TABLE 5 Page 5 of 8 300 FEET 19-24

>24 3

0 14 0

10 4

0 0

5 0

14 3

1 0

0 1

~

J 3

~

12 20 43 29 30 23 15 15 3

141*,.

114 TOTAL 61 74

~7 J1 29

~!

~o 3

~~

,J 50 20

~~

27 4~

J 113 111 e

74 77 812

ARTIFICIAL ISLAND SALEM UNIT 1 PERIOD OF RECORD:

1 182 TO 33182 s*rnBILITY 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 CMPH> AT 300 FEET WIND DI REC-TJDN 1-3 4-7 8-12 13-18 19-24

>24 N

0 0

0 1

0 0

NNE 1

0 1

1 0

0 NE 0

0 0

~

0 0

ENE 0

0 0

0

-r**

0 0

ESE 0

0 0

0 SE 0

1 0

0 1

0 SSE 0

0 1

2 0

0 r 0 0

0 0

0 SSW 0

0 0

0 SW 0

0 0

0 WSW 0

0 0

1 w

0 0

0 1

1 0

WNW 0

1 3

5

~

0 NW 0

0 0

~

1 1

NNW 0

0 1

3 3

0 TOTAL 1

~

6 17 11

~

PERIODS OF CALM CHOURS>:

0 HOURS OF MISSING DATA:

1 TABLE 5 Page 6 of 8

'~*

TOTAL 1

3

~

' 0 0

0

~

' 3

.o 0

0 1

~

e 14 4

7 39

ARTIFICIAL ISLAND

!:lr::iL.E::M UNIT

I.

PERIOD OF RECORD:

I. 182 TO 33182 s*rABILITY CLASS! MODERATELY UNSTABLE DELTA T -1.9 TO -:1..7

~

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

300 FEET 1.. J I N:O DI i:::i;::c....

lJCJN

l.... 3 4.... 7 N

()

0 NNE

()

0 NI::

I.

()

El'1E

()

i:::~;E

()

E

()

0

E 0

()

: :; ~~

0

I.

~:; l_,J

()

t.JSW

()

t.*.J

()

VJNW

()

NI.~

()

j**~Nt..J 0

()

TDTi-"il...

1.

F'Ef:; I DD~) () i::*

C1~1L.. M < Hour~s) *

()

HDUF:S OF Ml~:;::; J ND DATr.1:

6 l~INDSPEED <MPH) r~T t:J.... :1.2

I.

0

()

0

I.

()

~~

I.

I 1.3*-*1El 0

I.

0 0

()

5

")

(:)

TABLE 5 Page 7 of 8 300 FEET j_ <)-*-24

>24

()

0 0

0

()

0

()

0

()

0

()

0

()

0 0

0

()

0

I.

0

'"l...

3 3

1

I.

()

"7 4

TOTr::-.1...

I.

()

1

I.

1::*

,.)

1.0 4

'1.(

... :.\\J

ARTIFICIAL ISLAND

~>Al.. EM UN IT l PERIOD OF RECORD:

1 182 TO 33182 STABILITY CLASS: EXTREMELY UNSTABLE DELTA T

<-1.9 ~

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

300 FEET l.JIND DI i:;: 1::c-..

TIClN 1.--3 4.... l t*~

0

()

NNE 0

0 t*~E

()

I.

ENE:

I.

()

I'"

0

()

ESE:

()

>E

()

0

'.:!SE

()

~:)

()

'.:;sw

()

0

'.:!'W 0

()

l.JSlJ

()

l.J 0

0 l....INW

()

0 Nl..J

()

j**~NL<J

()

TOT!-~L-

L

1.

F'EI~: I 0 DS ClF CALM

< HOUF~f.1):

HOUF~!3 DF MI!:>~> I NG I

DATA:

()

'")

WINI:lt1F'EED < MF'H)

B-.. 1.2 l ~3*-* :I. B

()

0

()

3 0

0

()

0

()

0

()

0 r) 0

()

0 0

()

I.

0

()

0

()

3 3

TABLE 5 Page 8 of 8 r~T 300 FEET 19.... 24

>24

()

0 0

0 2

0

()

0 0

()

0 0

()

0 0

()

0

()

0

~

0 0

()

0 0

1::*

~)

0 TOTr.~11...

0

()

6

I.

()

0

()

)

()

3 e

1

()

1.3

ARTIFICIAL ISLAND f.)t-11...EM UNIT

I.

PERIOD OF RECORD:

4 182 TO 63082 I

STABILITY CLASS: EXTREMELY UNSTABLE DELTA T

<-1.9 -

LAPSE RATE IN DEG C/100 METERS EVAl...IJATED l.Jf.>ING DEL.TA T 300.... ~53 FT LLEUA"fION:

300 FEET l... J I f-lfl DJh:EC****

TIDN

1.****3 4****?

N

()

NNE

()

l'*lE

()

i:::NE 0

()

r....

()

CSE

()

0

'.:>E 0

0

'.:>~3E

()

("'

,,:)

()

'.3l<J

()

0

'.:)l1J

()

l.oJSv.J

()

l..*J

()

l.JNL*J 0

()

Nl~I

()

NNl<J

()

TUT t-d.*

0

()

PERIODS OF CALM CHOURS>:

l*HJUF~~:; OF MH>GING Dt-1Tf.1:

()

l~INDSPEED < MF'H) i~1 T

mo FEET D****:l.2

l ;*5... :I. B

I. 9--24

>::.~4

()

3 0

0

()

0

()

0

()

0

()

0

()

3

()

I.

1.

'l

~..

j_

()

'"l A'**

3

1.3

()

I.

0 4

c1 c1

1.4 TABLE 6 Page 1 of 8 TOTr~il...

()

";(

()

0

()

.. l.

,.)

1::*

..I

l.D

I.

30

ARTIFICIAL ISLAND

~!ALEM UNIT

I.

PERIOD OF RECORD:

4 :1.82 TO 63082 s*rABILITY CLASS: MODERATELY UNSTABLE DELTA T -:1..9 TO -:1..7 ~

l... (~p~:;i:::

r~ATE IN DEG C/1.00 METl:::r~~:;

EVALUATED USING DELTA T 300-33 FT I::* 1 1=* I i ~~ *1**.[ ("" N ~

-. ""I () ("'

1::* 1:* E"" *1**

.......** '\\.ll

. J __... _ -

-~

)

-*:ft:f'.>.\\::Y**************************************************************

VJ I N::i L! I i::;EC****

r*:::uN

I.****~~

4****7 j*.!

()

!**~NE

()

NEc

()

!:::NE

()

r-()

()

L:'.3E

()

0

.. -~,-.

.::>l::.

1 *.)

()

'.'.)'.'.)[

()

.. -~

-::)

()

~'.:) ~J l.1J

()

0

>l..J

()

J..,J'.3 \\,j 0

()

[.... !

()

l.. Ji*~U

()

Nl.,J

()

t"-!Nl,J

()

1.

TDTt;I...

()

1.

F' E f:; I D D

~:; OF. Ci-"~LM ( HDUF~G) *

()

HOUF::!:; CJF M J !:;~;I Nl:J Df:1T1~:

I.

~JINDBPEED <MPH) AT B**** 1.2

()

0

I.

()

0

()

3

I.

1.

7

l.3**-*:1.8

I.

0

()

0

()

0

()

")

~5

I.

B Table 6 Page 2 of 8 300 FEET

l.?****24

>24 l

0

()

0

()

I.

()

0

()

0

()

0

()

0

()

")

0 3

3 1::*

3 4

)

.\\...

I.(:>

8 TOTAi...

'")

()

I.

()

I.

()

7 I

I.()

e

I.()

<"l 40

ARTIFICIAL ISLAND t>ALEM UN IT

I.

s*rABILITY 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 ld I NDnPEED <MPH) r::iT 300 FEET

.... )I Nfi I.1 I F: E c; *-*

T JDN

1****3 4****?

13****:1.2 13*.. *lD

I. C/*-*:.:.~4

>24

(!

()

I.

)

()

0 0

i""--!NL

()

I.

2 3

()

0 NE

()

FNE

()

0 0

()

\\...

0

()

0

()

E'.31::.

0

()

0 0

~:;E

()

I.

()

0

~:;SE

()

0 0

0

('.~

.. }

()

~::; ~3 L*J

()

0

()

0

~:; lJ

()

0 i,d'.:;1...1 0

()

I.

0

()

0 1.... J 0

1 4

()

I.

0 l>J 1--l l,J 0

()

1::*

,,J 1

()

0 Nl.iJ

')

~,

I.

)

3

.3 NN~J

()

I.

~::j 4

6

()

TOT ti I...

()

1::*

,.}

2:1.

1.0

I. 0

~5 PERIODS OF CALM CHOURS>:

()

HOURS OF MISSING DATA:

I.

TABLE 6 Page 3 of 8 e

TOTAi...

3 6

()

0

()

l

()

I.

(~*)

6

1.0

1.6 4c,;;

ARTIFICIAL ISLAND f:)Al... EM UN IT :I.

T(~f.IIL..ITY CL.(1f

)!'.)

t-1LL f:)TABIL.ITIEf:> EXCl....UDING MI!'.)S f:)PEED/DIR DATA LAPSE RATE IN DEG C/100 METERS EVALUATED USING DELTA T 300-33 FT CL_[t)t1TIDM:

300 FEET

t::i::**~:;,~***************************~<************************************

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t

1f TABLE lB-1 t

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1981)

GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 1 CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter

1.

Fission gases Krypton-85 Ci Krypton-85m Ci 4.79E-04 Krypton-87 C1 Krypton-88 Ci Xenon-133 Ci 2.76E+02

1. 55E-02

1. 57E+02 7.02E+Ol Xenon-135 Ci

1. 09E+Ol 2.84E-02 l.77E+OO 7.34E-01 Xenon-135m Ci 4.53E-02 Xenon-138 Ci Xenon-133m Ci 2.58E-04

1. 32E+OO 7.31E-01 Argon-41 Ci Fluorine-18 Ci 1-.

Unidentified Ci Total for period Ci 2.87E+02 4.39E-02 l.60E+02 7.17E+Ol

2.

Iodines Iodine-131 Ci 4.49E-04

4:**~)E-04 e

Iodine-133 Ci 7.17E-04 Iodine-135 Ci Total for period Ci l.17E-03 4.93E-04 M P80 14/20 1 10-A

ML18086B628

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