ML18085B001
| ML18085B001 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/02/1981 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML18085B002 | List: |
| References | |
| NUDOCS 8103060547 | |
| Download: ML18085B001 (52) | |
Text
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OPS~G Public Service Electric ar.::l Gas Company 80 Park Plaza Newark, N.J. 07101 Phone 201/430-7000 March 2, 1981 Mr. Boyce Grier, Director U.S. Nuclear Regulatory Commission Off ice of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Grier:
RADIOACTIVE EFFLUENT RELEASE REPORT RERR-9I SALEM NUCLEAR GENERATING STATION UNIT NO. 1, DOCKET NO. 50-272 UNIT NO. 2, DOCKET NO. 50-311 As required by Section 5.6.1.2 of Appendix B of the Operating License for the Salem Nuclear Generating* Station Unit Nos. 1 & 2,
. we hereby transmit two copies of the semiannual radioactive. ef-fluent release report, RERR-9I.
Additional analyses are being completed and will be submitted in the near future in a revised report.
The report summarizes liquid and gaseous releases and solid waste
..shipments from the Salem Nuclear Generating Station for the period July -
December, 1980.
Attachment
?1ili1-s, R. L. Mittl General Manager -
Licensing and Environment CC:
Director, Office of Inspection and Enforcement~
U.S. Nuclear Regulatory Commission c/o Distribution Services Branch, DDC, ADM
- Washington, D.C.
20555 M P79 43/10 The Energy People 8 1 0 3 0 6 0 r.;;~7
( 6 )
' l I*
95-0942
e Energy People SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT RERR-9I SALEM NUCLEAR GENERATING STATION SALEM UNIT NOS. 1 & 2 UNIT 1 DOCKET NO. 50-272 UNIT 2 DOCKET NO. 50-311 OPERATING LICENSE NO. DPR-70 OPERATING LICENSE NO. DPR-75 INTERIM REPORT MARCH 1981
M P79 43/33 REPORT NO. RERR-9I UNIT NOS. 1 & 2 RADIOACTIVE EFFLUENT RELEASE REPORT JULY -
DEC 1980*
SALEM NUCLEAR GENERATING STATION Public Service Electric and Gas Company
UNITED $TATES NUCL~AR REGULATORY COMMISSION WASHINGTON. O.C 20555 OFFICIAL BUSINESS eosTAGE a. Fees PAID U.S. NudHf A*1PJl*,1ory Commi111on ~
U.S.MAll -
Introduction SALEM NUCLEAR GENERATING STATION UNIT 1 50-272 UNIT 2 50-311 UNIT NOS. 1 AND 2 RADIOACTIVE EFFLUENT RELEASE REPORT July 1, 1980 to December 31, 1980*
This report,.RERR-9I, 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 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 period 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.
- Interim Report
~
M P79 43/33 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 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 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 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 instant the release rate of radioactive gases must satisfy the following equations whose basis is 10CFR20.
2.0 Qtv*Kv~ 1 0.33 Qtv*(Lv + 1.1 Nv) < 1 M P80 17 18 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 Otv*Nv
< 1 6.3 Otv*Mv < 1 The limiting Unit 1 release limit Q is calculated to be l.24E+5*and 6.53E+4 microcuries/sec for the 3rd and 4th quarters respectively.
The limiting Unit 2 release limit Q 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 Otv*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 rate in excess of 30 mrm 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 105 ) Ov ~ 1 M P80 20 06/1 During any calendar quarter the release limit is governed by the equations listed below.
The basis for th~se equations is 10CFR50 Appendix I.
2 curies of I-131 and Ov x 13 (1.5 105) < 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 Qv < 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, 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.
- a.
Fission Gases -
MPC values were not used to determine the maximum release 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.
- a.
Liquid effluents -
MPC values as stated in 10CR20, Appendix B, Table 11, Column 2 were used.
M P80 20 06/2 3.0 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 not based upon average energy, hence, this section does not apply.
4.0 Measurements and Approximation of Total Radioactivity 4.1 Liquid effluents are monitored in accordance with Table 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 releases 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 the 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 tritium samples were taken by bubbling gas through water and then counting the tritiated water on a liquid scintillation counter.
M P8.0 19 11 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 between 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 provided in Tables 4A-l and 4B-l for Unit 1 and 4A-2 and 4B-2 for Unit 2.
6.0 Unplanned Releases There were no unplanned releases to an unrestricted area during this reporting period
- M P80 18 05/1 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 Unit 1 See Summary Table 3 Unit 2 M P80 18 05/2 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 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 calculations for the six 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 from liquid re-leases are primarily from the seafood ingestion pathway.
The total body dose to an individual was calculated to be l.45E-2 mrem.
The calculated population total body dose was 2.51E-l person-rem.
The highest organ dose from liquid releases was 4.14E-l mrem to the gastrointestinal tract.
Air Pathways 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-l. person-rem.
The average total body dose to the population within fifty miles of the site was 4.31E-5 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 llSl) and near the Cir-culating Water pumps (location lOSl) 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 5Sl 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 2Sl and 5Sl are within the statistical variation associated with the preoperation program results.
- Preliminary Assessment M P80 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 concluded that there was no measurable 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 third and fourth quarters of 1980 as Table 5 and 6
- M P80 17 14 1/2
-8a-
UNITED SY.ATES NUCLEAR REGULATORY COMMISSION WASHINGTON, Q,C 20555 OFFICIAL BUSINESS POSTAGE Iii FEES PAID U.S. Nucl11r R1gull)toty Cammi111on
TABLE lA-1 E.FFLUENT AND WASTE DISPOSAL-ANNUAL REPORT ( 1980)
GASEOUS EFFLUENTS-SUMM OF ALL RELEASES UNI 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.
- 1.
Total iodine-131
- 2.
Average release rate for period
- 3.
Percent of technical 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.
- 1.
Total release
- 2.
Average release rate for period
- 3.
Percent of technical specification limit
( l )
(2)
For batch releases the estimated overall error Analyses indicate no measurable alpha emitting To be supplied later.
M P8014/23 l 9-A Unit Ci uCi/sec.
Ci uCi/sec.
Ci uCi/sec.
Ci Ci uCi/sec.
is within 3rd Quarter 7.03E+Ol 9.04E+OO l.82E-03 3.18E-03 4.09E-04 7.97E-02 2.09E-01 2.69E-02 5.24E+OO N/A 10%.
transuranics.
4th Quarter Est.Total(l)
Error %
4.85E-01 2.SOE+Ol 6.24E-02 9.56E-05 6.45E-04 2.SOE+Ol 8.29E-05 l.62E-02 2.SlE-03 2.SOE+Ol 3.22E-04 6.28E-02 N/A
TABLE lA-2 EFFLUENT AND WASTE DISPOSAL -*
NNUAL REPORT (1980)
GASEOUS EFFLUENTS-SUMMA OF ALL RELEASES UNIT 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.
- 1.
Total iodine-131
- 2.
Average release rate for period
- 3.
Percent of technical 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.
- 1.
Total release
- 2.
Average release rate for period
- 3.
Percent of technical specification limit Unit Ci uCi/sec.
Ci uCi/sec.
Ci uCi/sec.
Ci Ci uCi/sec.
3rd Quarter 9.09E-06 l.16E-06
- 1. 92E-09 4.37E-06 5.62E-07 l.lOE-04 N/A
( 1 )
( 2)
For batch releases the estimated overall error is within 10%.
Analyses indicate no measurable alpha emitting transuranics.
To be supplied later.
M P8014/23 2 9-B 4th Quarter Est.Total(l)
Error %
7.74E+OO 2.50E+Ol 9.95E-07
- 1. 65E-09 5.00E-05 2.50E+Ol 6.43E-06 l.25E-05 N/A
TABLE lB-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980)
GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 1 CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter
- 1.
Fission gases { 1)
Krypton-85 Ci
- 1. 54E-01 Krypton-85m Ci 8.02E-01 2.65E-02 Krypton-87 Ci
- 1. 62E-01 Krypton-88 Ci 9_. 52E-01 Xenon-133 Ci 2.05E-04 5.61E+Ol 4.59E-01 Xenon-135 Ci l.14E-03 l.lOE-01 Xenon-135m Ci 6.56E-01 Xenon-138 Ci Xenon-133m Ci 4.08E-01 Argon-41 Ci 6.15E-02 Fluorine-18 Ci 6.0lE-03 l.OlE-04 Unidentified Ci Total for period Ci
- 1. 35E-03 7.03E+Ol 4.85E-01
- 2.
Iodines { 2)
Iodine-131 Ci 3.18E-03 6.45E-04 Iodine-133 Ci 8.97E-04 Iodine-135 Ci Total for period Ci 4.08E-03 6.45E-04 M P80 14 20/1 10-A
Nuclides Released
- 3.
Particulates Chrominum-51 Manganese-54 Cobalt-58 Cabal t-60 Iron-59 Rubidium-88 Yttrium-88 S tron tium-89 Strontium-90 Niobium-95 Zirconium-95 Tin-117m Cesium-134 Cesium-137 Cerium-139 Gross Alpha Total For Period
- 4.
Tritium Tritium EFFLUENT AND WASTE DISPOSAL NNUAL REPORT TABLE -B-GASEOUS EFFLUENTS-TED RELEASES Unit l Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci (Continued)
UNIT l CONTINUOUS MODE 3rd Quarter 4th Quarter (1980)
BATCH MODE 3rd Quarter l.15E-Ol l.27E+00 6.64E-02
- l. 84E-02 9.38E-03 l.48E-00 4th Quarter l.21E-04 3.lOE-04
- l. 08E-03 8.69E-04 3.00E-05 4.50E-05 2.13E-05
- l. 41E-05 l.99E-05 2.51E-03 (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.
M P8014/20 2 10-B
Nuclides Released
- 1.
Fission gases (1)
Kr ton-85 Krypton-85m Xenon-133 Xenon-135 Xenon-135m Xenon-138 Xenon-133m Argon-41 Fluorine-18 Unidentified Total for period
- 2.
Iodines ( 2)
Iodine-131 Iodine-133 Iodine-135 Total for period M P80 14 24/l TABLE lB-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980)
GASEOUS EFFLUENTS-ELEVATED RELEASES UNIT 2 CONTINUOUS MODE BATCH MODE Unit Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 3rd Quarter
- l. 86E-06
- l. 86E-06 4.37E-06 4.37E-06 11-A 4th Quarter 7.74E+OO 7.74E+OO 5.00E-05 5.00E-05 3rd Quarter 7.23E-06 7.23E-06 4th Quarter
Nuclides Released
- 3.
Particulates Chrominum-51 Manganese-54 Cobalt-58 Cobalt-60 Iron-59 Rubidium-88 Yttrium-BB Strontium-89 Strontium-90 Niobium-95 Zirconium-95 Tin-117m Cesium-134 Cesium-137 Cerium-139 Gross Alpha Total For Period
- 4.
Tritium Tritium EFFLUENT AND WASTE DISPOSAL "ANNUAL REPORT TABLE-GASEOUS EFFLUENTS-ATED RELEASES Unit 2 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci (Continued)
UNIT 2 CONTINUOUS MODE 3rd Quarter 4th Quarter (1980)
BATCH MODE 3rd Quarter 4th Quarter
( 1 )
( 2)
Other fission gases were below the detectable level (LLD) Approximately less than 6.67 E-07 uCi/ml).
Iodine was below the minimal detection limit.
To be supplied later.
M P80 14 24/2 11-B
TABLE lC EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1980 UNITS 1 AND 2 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES Nuclides Releases Unit 3rd Quarter 4th Quarter 3rd Quarter 4th Quarter There were n:) ground level releases for the period of record
- 80 18 05/3 UNITED STATES NUCLEAR REGULATORV COMMISSION WASHINGTON, D.C 20555 OFFICIAL BUSINESS POSTAGE Si FEES PAID U.S. Nuc:l11r A1gul1,loty Commin1on
TABLE 2A-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980)
UNIT 1 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 3rd 4th Units Quarter Quarter Est. Total Error, %
~. Fission and activation products
- 1. Total release (not including trit-ium, qases, alpha)
Ci 6.99E-01 1.29E+OO 2.SOE+Ol
- 2. Average diluted concentration during period uCi/ml 4.99E-07 l.22E-07
- 3. Percent of applicable limits of Technical Specifications 6.99E+OO l.29E+Ol B. Tritium
- 1. Total release Ci 2.SOE+Ol
~verage diluted concentration uring period uCi/ml ercent of applicable limit N/A N/A
- c. Dissolved and entrained gases
- 1. Total release Ci 2.65E+OO 8.65E-02 2.SOE+Ol
- 2. Average diluted concentration during period uCi/ml l.89E-07 8..l6E-05
- 3. Percent of applicable limit N/A N/A D. Gross alpha radioactivity
- 1. Total release Ci O.OOE+OO O.OOE+OO 2.SOE+Ol E. Volume of waste release (prior to dilution -
Batch Release) liters 5.77E+06 4.53E+06 l.OOE+Ol F. Volume. of dilution water used durinq period -
Batch Release liters 1. 40E+l0 l.06E+l0
- 2. SOE+Ol A -
Not Applicable To4t supplied later P81 3 07/2 13-A
TABLE 2A-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980)
UNIT 2 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES
. Fission and activation products
- l. Total release (not including tritium, gases, alpha)
- 2. Average diluted concentration during period
- 3. Percent of applicable limits of Technical Specifications
. Tritium
- l. Total release 2
erage diluted concentration ring eriod rcent of applicable limit
. Dissolved and entrained gases
- 1. Total release
- 2. Average diluted concentration during period
- 3. Percent of applicable limit
. Gross alpha radioactivity
- 1. Total release
. Volume of waste release (prior to dilution -
Batch Release)
. Volume of dilution water used during period - Batch Release
/A -
Not Applicable To Be Supplied Later P81 3 07/l 3rd Units Quarter Ci 4.66E-03 uCi/ml 5.04E-10 4.66E-02 Ci uCi/ml N/A Ci 2.42E-04 uCi/ml 2.62E-ll N/A Ci O.OOE+OO liters 2.49E+06 liters 9.24E+09 13-B 4th Quarter 3.84E-01 l.56E-07 3.84E+00 N/A O.OOE+OO O.OOE+OO N/A O.OOE+OO 8.45E+05 2.46E+09 Est. Total Error, %
2.50E+Ol 2.50E+Ol 2.50E+Ol l.OOE+Ol 2.50E+Ol
TABLE 2B-l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980)
LIQUID EFFLUENTS UNIT 1 CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th uclides 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 l.18E-03 Iodine-133 Ci 3.86E-03 Cobalt-58 Ci 4.36E-02 7.78E-01 Cobalt-60 Ci l.41E-01 3.25E-01 Cadmium-109 Ci Manganese-54 Ci 8.52E-03 3.43E-02 Chromium-51 Ci 8.86E-03 7.45E-02 Cesium-136 Ci 9.76E-04
=eonium-95 Ci 4.78E-04 4.09E-03 113 Ci um-140 Ci Lanthaium-140 Ci Cerium-139 Ci 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 Sodium-24 Ci l.19E-04 Yttrium-91 Ci Total for period (above) excluding H3 Ci 6.99E-01
- 1. 29E+OO 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 Arqon-41 Ci 5.58E-05
( 1)
The Lower Limit of Detection (LLD) is approximately l.OOE-08 uCi/ml (Co 6 0).
M P81 47 04/1 14-A
TABLE 2B-2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980)
LIQUID EFFLUENTS UNIT 2 CONTINUOUS MODE BATCH MODE
~uclides Releaseed Unit 3rd Quarter 4th Quarter 3rd Quarter 4th Quarter Strontium-89 Ci Strontium-90 Ci Cesium-134 Ci 4.22E-03 Cesium-137 Ci 4.93E-03 Iodine-131 Ci Iodine-133 Ci Cobalt-58 Ci 4.34E-03 2.62E-01 Cobalt-60 Ci 6.77E-02 Cadmium-109 Ci Manganese-54 Ci 3.22E-04 l.31E-02 Chromium-51 Ci
- 1. 38E-02 Cesium-136 Ci Zirconium-95 Ci
. -113 Ci
- 1. 90E-03
~um-140 Ci t_h_a_i_u_m ___ l_4_0~~~~~~~~-C-i~~~~~~~~~~~~~~~~~~~~~~~~
Cerium-139 Ci Tungsten-187 Ci Niobium-95 Ci 2.35E-03 Antimony-124 Ci 5.03E-03 Antimony-125 Ci 4.08E-03
- 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 Ar on-41 Ci The Lower Limit of Detection (LLD) is approximately l.OOE-08 uCi/ml (Co 60).
Tritium values were not available at the time the report was tabulated.
M.47 04/2 14-B
TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1980 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
- 2. 31E+02 evaporator bottoms Ci 3.10E+02
- 1. 50E+Ol
- b.
Dry compressible waste, m3 6.61E+O 2 contaminated equip.
Ci l.35E+Ol 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.
Estimate of major nuclide composition (by type of waste)
- a.
Cobalt -
58 80.4%
2.49E+02 Cobalt -
60 16.3%
- 5. 05E+Ol Manganese -
54 3.3%
- 1. 02E+Ol Others
- b.
Cobalt -
58 50.4%
- 1. 085E+Ol Cobalt -
60 16.3%
- 2. 20E+OO, Manganese -
54 3.3%
0.45E+OO Others E
. c.
E
- d.
E
- 3.
So~id Waste Disposition Number of Shipments Mode of Transportatio~
Destination
. 65 Truck IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transpo.rta tion None N/A Barnwell, South Carolina Destination N/A
TABLE 4A-l SALEM NUCLEAR GENERATING STATION (1980)
UNIT 1
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY
- 1.
Dates July 1 -
Sept. 30, 1980
- 2.
Type of release (Gas)
- 3.
Number of releases during the 3rd Quarter l.20E+Ol
- 4.
Total time duration for all releases of type listed above 3.82E+02 minutes
- 5.
Maximum duration for releases of type listed above l.53E+03 minutes
- 6.
Average duration for all releases of type listed above 3.19E+02 minutes
- 7.
Minimum duration for release of type listed above 7.60E+Ol minutes
- 8.
For liquid batch releases only, provide the average stream flow (dilution flow) during the period of release.
N/A.
~
P80 15 30/1 16-A
TABLE 4A-2 SALEM NUCLEAR GENERATING STATION (1980)
UNIT 2.
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY
- 1.
Dates July 1 -
Sept. 30, 1980
- 2.
Type of release (Gas)
- 3.
Number of releases during the 3rd Quarter l.90E+Ol
- 4.
Total time duration for all releases of type listed above 2.39E+03 minutes
- 5.
Maximum duration for releases of type listed above l.62E+02 minutes Average duration for all releases of type listed above l.26E+02
- minutes
- 7.
Minimum duration for release of type listed above 8.70E+Ol minutes
- 8.
For liquid batch releases only, provide the average stream flow (dilution flow) during the period of release.
N/A
.P80 15 42/l 16-B
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.j'.:
2055&
OFFICIAL BUSINESS I
POSTAGE I FEES PAID U.S. Nuclll' Regulatory ~mmineon
TABLE 4A-l (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+Ol
- 4.
Total time.duration for all releases of type listed above 7.49E+03 minutes
- 5.
Maximum duration for releases of type listed above l.61E+03 minutes
- 6.
Average duration for all releases of type listed above 3.26E+02 minutes Minimum duration for release of type listed above 7.60E+Ol minutes
- 8.
For liquid batch releases only, provide the average stream flow (dilution flow) during the period of release.
N/A P80 15 30 1/2 17-A
\\
TABLE 4A-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 October 1 -
Dec. 31, 1980
- 2.
Type of release (Gas)
- 3.
Number of releases during the 4th Quarter l.20E+Ol
- 4.
Total time duration for all releases of type listed above l.51E+04 minutes
- 5.
Maximum duration for releases of type listed above l.61E+03 minutes
- 6.
Average duration for all releases of type listed above
- 1. 26E+03 minutes 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 P80 15 44/1 17-B
/
TABLE 4B-l SALEM NUCLEAR GENERATING STATION (1980}
UNIT 1
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE 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 2.00E+04 minutes
- 5.
Maximum duration for releases of type listed above 4.11E+02 minutes Average duration for all releases of type listed above 2.20E+02 minutes
- 7.
Minimum duration for release of type listed above l.06E+02 minutes
- 8.
For liquid batch releases only, provide the average stream flow (dilution flow} during the period of release.
l.85E+05 gpm P81 3 06/1 18-A
TABLE 4B-2 SALEM NUCLEAR GENERATING STATION (1980}
UNIT 2
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE 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
- 1. 32E+04
- s.
- 6. -*
- 7.
minutes Maximum duration for releases of type listed above 5.76E+02 minutes Average duration for all releases of type listed above 3.80E+02 minutes Minimum duration for release of type listed above 3.SOE+Ol minutes
- 9.
For liquid batch releases only, provide the average stream flow (dilution flow} during the period of release.
l.85E+05 gpm
.P81 3 06/2 18-B
TABLE 4B-l (Cont'd}
SALEM NUCLEAR GENERATING STATION (1980}
UNIT 1
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 7.lE+Ol
- 4.
Total time duration for all releases of type listed above l.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 2.14E+02 minutes Minimum duration for release of type listed above l.48E+02 minutes
- 8.
For liquid batch releases only, provide the average stream flow (dilution flow} during the period of release l.85E+05 gpm M P81 3 05/1 19-A
TABLE 4B-2 (Cont'd)
SALEM NUCLEAR GENERATING STATION (1980)
UNIT 2
SUMMARY
SHEET FOE 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 l.2E+Ol
- 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 Minimum duration for release of type listed above l.64E+02 I
minutes
- 8.
For liquid batch releases only, provide the average stream flow (dilution flow) during the period of release l.85E+05 gpm M P81 3 05/2 19-B
PERIOD OF RECORD:
ARTIFICIAL ISLAND SALEM UNIT 1 7 180 TO 93080 STABILITY CLASSI EXTREMELY UNSTABLE DELTA T <-1.9 -
LAPSE RATE IN DEG C/100 METERS EVALUATED USING DELTA T 300-33 FT ELEVATION:
300 FEET TABLE 5 Page 1 of 8
ARTIFICIAL ISLAND SALEM UNIT 1 PERIOD OF RECORD:
7 180 TO 93080 STABILITY 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 WIND DI REC-TION 1-3 4-7 N
0 0
NNE 0
0 NE 0
0
~N~
0 0
r 0
0 ES~
0 0
. 0 0
SSE 0
0 s
0 0
SSW 0
0 SW 0
0 WSW 0
0 w
0 0
WNW 0
0 NW 0
0 NNW
- o 0
TOTAL 0
0 PERIODS OF CALM CHOURS>:
0 HOURS OF MISSING DATA:
0 WINDSPEED <MPH) AT 8-12 0
0 0
0 0
O*
0 0
0
- o 1
0 0
0 0
0 1
13~18 0
0 0
o*
0 0
0 1
0 0
0 0
0 0
0 0
1 TABLE 5 Page 2 af 8 300 FEET 19-24
>24 0 :
0 0
0 0
0
- o 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
TOTAL 0
0 0
0 0
0 0
1 0
0
. 1 0
0 0
0 0
2
- ~
~
.* J fl J
- ~.,
- 1
- I JI 'l ll 1i
- l I
/
r!
I ti
ARTIFICIAL ISLAND SAL.EM UNIT :I.
PERIOD OF RECORD:
7 180 TO 93080 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 El...EV1~TICiN:
300 FEET
- ~*************************************************
WIND Dif<EC-TION
- 1.-*:3 4-7 N
0
()
NNE 0
()
NE
()
()
ENE
()
()
r
()
()
ESE
()
- ()
si:::
0
()
()
0
("'
0
()
Sst.J
()
()
S~J 0
- I.
WSW
()
()
w
()
()
WNW
()
()
NW 0
0 NNW 0
()
TCJT1~L 0
- L PEI;~ I oni:; OF CALM < 1-1mms > :
0 Hou1:~s OF MISSING DATA:
0 WJ.NDf:iPEED <MPH> AT
. B--:1.2
- 1. :3-:1. B
- 0.
()
()
()
<)
()
()
()
0 0
()
()
- I.
0
()
- I.
O*
0
- 1.
()
()
0 0
()
()
0 0
()
()
()
0 0
2 1
TABLE 5 Page 3 of 8.
300 FEET
- 1.9-24
>24 0
0 0
()
0 0
0 0
()
0
()
0 0
- O
- l.
- 1.
0 0
()
0 0
0 0
0 0
0
()
0 0
0
()
0
'1 1
TCJTAL
()
0 0
()
0 0
- i 3
0 1
-1 0
()
0 0
- O 6
- i.
PERIOD DF RECORD.:
7 180 TO
~3080*
STABILITY CLASS: NEUTRAL DELTA T -1.5 TO -0.5 ~
LAPSE RATE IN DEG C/100 METERS EVALUATED USING DEL.TA T 300-33 FT ELEVATION:
300 FEET T!\\BLE 5 Page 4. of 8
ARTIFICIAL ISLAND SAl... EM UNIT
- I.
PERIOD OF RECORD:
7 180 TO 93080 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 l1JIND DI F~EC**-
TIDN
- 1
- 3 4--7 N
()
a::*
.. 1 NNE 4
- .~
NE'
)
6
. ENI::
- ~
f.1 r
- I.
- 3
!:~SE
()
- I.
()
6 si:;r:::
4 7
s 1..'..
- 1.:3
!:)Sl.J
- .~
- 1.;3
!3 l.V
- ~~
- 1.9 Wi:>W
~:)
B hJ
- x "'
- I.::.!
h.JNW
()
12 NW
- I.
f' NNW
- I.
TCJT1~I...
~~E~
- I. ;30 F'EF~ I CJD!:; OF CALM < H mm i:; ) :
- I.
HOUl=~s DF MIS!:lING DAT1~:
- 1.62 WINDf.>PEED <MPH> AT 8-* 1. ::!
24
- L8 1.6 9
1~~
6 7
2~~
~5:~
37
~5 <;>
2:~
- rn
- 1.7
- 1.7.
- 1.9
~529.
- L ~5*-:1. B
- l.B
- u, 14 4
..:1.4
- l.EJ.
40 3:-~
47 f.,O
- 39
- =~~3
- 1.:3
- L 7
- I.:~
- 3El5 TABLE 5 Page 5 of 8
- 300 FEET 19-;!4
>~?4
~~~
0 1
0 2
0 2
()
0 0
7 0
- 1.6 4
- 1.4 0
10 2
'")I:"
2 1.7
- L 9
3 3
- 1.
2 1
14 0
~!
0
- L26
- 1.4 TOTAL..
49 5l.
40 24
- 31.
23 5 l.
87
'91.
- L26
- l.3FJ 84 72 45 57 43
- 1.012 i ' I
i I
[
ARTIFICIAL. ISLA~D SALEM UNIT
- I.
PERIOD OF RECORD:
7 180 TO 93080*
STABILITY CLASS: MODERATELY STABLE DELTA T 1.5 TO 4.0 -
l... APSE F~1~TE JN DEG C/:l.O(> METEl~S EVALUATED'h~ING DELTA T 300-33 FT ELEVATION:
- 300 FEET WJND$PEED <MPH> AT
- mo FEET l1JIND DI 1:~i:;:c;...:
TJCJN
'"5 4-7 El-*:I. ~~
1:3-HI
- I. 9-*:~4
>24 N
()
4 7
- l8 3
0 NNE
()
()
- I.
- s l
0 NE
()
- I.
-~:;
4 3
0 ENE
()
()
r)
- s
- L 0
r
()
- 1.
()
0 0
()
i:::i:;i::
()
()
0
()
()
0 nE
()
- o
- 1.
- 1.
0
()
()
3 6
- I.
0
("
,:)
- I.
- I.
- ~
3 0
0 SSW.
()
- I.
!:-j
!S 4
0 SlJ
()
() '
4 f.>
- 5 0
wi:;w
()
()
2
~.=;
- I.
- L w
()
- I,
- I.
- 1.
()
()
WNW 0
- 1.
- I.
- I.
1 0
NW
()
- 1.
6
- I.
()
0 NNW 0
()
- ~
- L6 l
()
TCJT1~L
- 1.
1:*5 44
'7;*5 19 l
PEI:~ I oni:; CJF Cf.11... M < HCll.JF~G) :
()
HDUl:~i:; ClF MJSBING DATA:
- s7 TABLE 5.
Page 6 of a*
TOTAL 3=~
5*
13 6
1 0
2 12 8
15 l.3 9
3 4
H 20 15:L
l 1e i
I f
i ARTIFICIAL ISLAND
!:>AL.EM_ UN IT :I.
PERIOD OF RECORD:
7 180 TO 93080 STABILITY CLASS: EXTREMELY STABLE DELTA T >4.0 ~
LA0SE RATE IN bEG C/100 METERS EVALUATED USING DELTA T 300-33 FT El...[l..JATICJN:
- ~oo* FEET
- ~********************************
WJND!:>PEED <MPH> AT
- mo FEET l1JIND DI Fi:i:;:c;...,
TICJN "5
4-7 B-:1.2
- 1.;3.. -:l.8 19-:;!4
>24 N
()
o*
0 0
0 0
NNE
()
().
0 0
0 0
NI:~
0
()
0 1
0 0
ENE
().
- I.
0 0
- o 0
r
()
()
0 0
()
o*
ESE
()
()
0
()
()
0 SE
()
()
0 0
0 0
SSE 0
0
()
0
()
()
()
()
0 0
0 0
,;)
SGW
()
()
0 0
()
0 SvJ
()
()
0 0
()
0 kl!:)l.J
()
()
0
()
()
0 w
()
()
0
()
0 0
WNW
()
()
()
()
()
0 NW
()
0 0
0 0
0 NNW 0
()
0
()
()
()
TOT1t.il...
0
- L 0
- L 0
0 F'EF~ ICJDS OF C1~L.M < HCJl.JI:~!:;) :*
0 Hou1=~s OF MIS!:> ING DATA:
)
TABLE 5 Page 7 of 8 TOTAL 0
0 1
- I.
0 0
0
()
0
()
0 0
0 0
0
~
()
2
ARTIFICiAL ISLAND SAl... EM UNIT
- I.
PERIOD OF RECORD:
7 180 TO 93080 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
TABLE 5 Page 8 o.f 8 I
- I
ARTIFICIAL ISLAND SAL.EM UNIT :I.
PERIOD OF RECORD: 10 180 TO 123180
- STABILITY CL.ASS: EXTREMELY UNSTABLE DEL.TA T
<-1.9 ~
LAPSE RATE IN DEG C/100 METERS EVALUATED USING bEl...TA T 300-33 FT ELEVATION:
300 FfET l.iJJND~IPEED <MPH> AT
- 300 FEET l.JIND DI F~EC**..
TICJN
- 1
- 5 4*** '7 8--:1.2
- 1
- ~
- 1 8 19-:;~4
>:~4 N
()
0 NNE
()
()
NE
()
()
ENE 0
()
()
()
()
()
()
()
()
()
0
()
()
().
0
()
()
()
r
()
~-.:
ESE
()
()
()
()
()
()
()
()
()
()
()
()
()
()
()
()
!:;!:;i::
()
- O
~)
.()
()
()
0 0
0 0
0 0
()
si:;t..i
()
()
- o
()
. ()
0 SW
()
()
()
()
0
()
t<li:;w
()
0 0
()
()
()
l-<.I
()
()
. ()
()
()
()
l.JNl.J
()
()
()
()
()
()
NlAJ
()
()
NNl.J
()
()
()
()
()
()
()
()
()
()
TCJT1f.il...
()
- .~
0
()
()
()
PERICJDS OF CALM <HOURS>:
0 HOURS OF MISSING DATA:
()
TABLE 6 Page 1 of 8 TOTAi...
()
0
()
0
'")
0
()
' I
()
- i.
()
I
()
0 l
0 I
()
0 l
()
0 r) 1-' **
l I
' :i
e ARTIFICIAL ISLAND l:>ALEM UNIT
- I.
PERIOD OF RECORD: 10* 180 TO 123180 STABILITY CLASS: MODERATELY UNSTABLE DELTA T -1.9 TO -1..7 ~
-LAF'St RATE JN.DEG C/1.00 METERS EVALUATED USING DELTA T 300-33 FT l~I 1~
1 J~-*1*-N 1
~()1 1~1~1~*1..
1
......... ' I l I.. u I *
\\.
~*
- ~*************
liJIND Li I F<E::c;....
TICJN
'"5 4-7 N
()
()
NNE
()
()
NE*
()
- I.
ENE::
()
()
()
()
EE;E
()
()
()
()
()
()
s
()
()
H~:;w
()
()
~)l.J 0
0 l.J!:)t.J
()
()
vJ 0
()
V..INl.J
()
0 NW
()
()
NNl.J
()
()
TDT1~I...
0
- 1.
F'E:F<:ICJD::; OF C1::i1... M *.( HCJUF<S) :
0 HCll.JRS CJF MI ~;;i;; J NG DATf.1:
()
l.JINDSPEED <MPH> AT B.. -:1.2
()
()
0
()
()
0
- I.
()
()
0
()
- 0.
()
0 0
0
- L
- 1.3.. -1.B
()
()
()
()
()
- L
()
0
()
0 0
()
()
()
- I.
()
2 TABLE 6 Page 2 of 8
- mo FEET
- I. 9.... :~4
>24
()
()
- ()
()
0 0
0
()
0
()
()
()
- l.
0
()
()
()
0
()
()
0
()
()
()
()
0 0
0 0
- I.
0 3
- I.
4 TOTAi...
()
()
- L
()
()
- 1.
- ~
()
0
()
()
()
()
0
I
~5
<'J d
ii
))
ARTIFICIAL ISLAND
!:>AL.EM UNIT :l.
PERIOD OF RECORD: 10 180 TO 123:1.80
- STABILITY CLASS: SLIGHTLY UNSTABLE DELTA T -1.7 TO -1.5 -
LAPSE RATE IN DEG C/:l.00 METERS EVALUATED USING DELTA T 300~33 FT ELEVATION:
300 FEET WIN:O DIF<EC*...
TICJN
- I. -:*:s 4.... 7
.N
()
0 NNE
()
()
NE
()
()
ENE
()
- I.
r
()
. ()
ESE
()
()
~>E
()
()
ssi:::
()
()
("'
()
()
- !
- )l.J
()
()
GW
()
()
l.JGl.J
()
0 w
()
()
WNl.J
()
()
NvJ
()
()
NNW 0
()
TClT1~I...
0
- I.
PEl~IDD!:; ClF C1~~1... M < Hmm~:; ) :
H CJ LJ 1:< !:I OF MIGGING DAT1~:
~s
()
WINDSF'EED <MPH.) AT a.. -:1.;a
()
()
()
- L 0
. 0 0
0
- I.
0 0
()
l 0
0
- 0.
3
- 1. :3-- :1. f:l
- I.
()
0
- 1.
0
()
()
()
()
()
()
1 3
- 1.
3*
- 3
- L ~~
TABLE 6 Page 3 of 8 300 FEET
- L 9.--*:;~4
>24
()
0
.o 0
()
()
()
()
()
()
()
()
0 0
()
0
()
0 0
0
()
()
()
()
()
()
()
()
- I.
- L 2
2 3
3 TOTAL..
- L 0
()
3
()
()
()
()
1
()
0
- l.
4 1
5 7
2:3
ARTIFICIAL iSLAND SALEM UNIT 1
- PERIOD OF RECORD: 10 180 TO 123180 STABILLTY 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
- ~*****************************************************
l\\IIND Dir~i:;:c;....
TION
- l.**.. 3 4**-7 N
()
NNE
()
3 NE:
()
- I.
ENE
()
3 F
- I.
!:5 E!:;E
()
- .~
f>E
()
- .?
SSE 0
7 I
s
()
~::;
B!:>W
- I.
t:l SW
- I.
3 l.Jl:il.J
- I.
- I..
l,J
- I.
- I. :I.
WNW
. ()
4 Nl.J
()
!:5 NNl.J
- I.
- 1. :I.
TOTAi...
6 76 PERIODS OF CALM <HOURS>I 0
HCJURS OF MISSING DATA:
. :1:9 WINDSPEED <MPH> AT 8**.. :1.2 18
- 1.3.'
- 7 7
6
()
- .~
~~
9 1().
- l.. :3
- l.8 14
- 5 9
9 140
- I. :*5**-:1.8 2:l
- l.9
~! :l.
!5
- L
- ~~
4 r) 4 6
- l.9 9
- 1.2
- 1.7 29
,., 1:*
ir:..0wJ 196" TABLE 6 Page 4 of 8
- 500 FEET
- 1.9-*24
>~!4 7
()
c:*
- L
- ~
()
'")
11.* **
0 0
0 0
0
()
2
()
0 0
0 0
0
- 1. 0
~:s 15
- 1.8 8
- l. !3
,-:l~!
8 23
~H 23
- !9 107 1
- L ~5 TCJTAL 51 4:L 3:l
- 1.7 13 4
10 11 113 25 4 <;>
62 64 44 100 91:1 6~513 i
.1 **
'h.
i ARTIFICIAL ISLAND SAl... EM UNIT
- I.
PERIOD OF RECORD: 10*100 TO 123180 STABILITY CLASS: SLIGHTLY STABLE DELTA T -0.5 TO 1.5 ~
LAPSE RATE IN DEG C/100 METERS*
EVALUATED USING D~LTA T 300-33 FT ELEVATION:
300 FEET
- ~********************************
WINDSPEED <MPH> AT 300 FEET
~JIND DI F~Ec;....
TIDN
- 1
- 5
-** \\o 4***7 B**..:I. :;!
- 1.:3-:1.B
- l9.. **24*
>24 N
()
- ~ :~
44
- 1.4
()
NNE
- I.
3
- l.f.i
- ~4
- I. 0 0
NE
'")
)
~:..
- LO
- !7
- 1.4
()
l::.NI::.
'")
fl
- 1.:3*
- ~:I.
~5
- 3 r
2 f.i
- 1.2
- 3
()
- l E!:>E
~.~
f.i 0
- 3.
0 0
- I.
- 5 6
- I.
3
- 5 SSE
)
1.',,
?
1::*
.. 1 9
- 3
~5
("'
.:i
()
- 1.2 9
- .w
- I. "7
- I.
f.)f.)li.J
()
3
- 1.9
- .w
- ~::.~
- l.!5 SliJ
- I.
- 3 B
- 32 27 9
li.J!:lli.J
- I.
?
- 1. 4
- 1. 9 1:3 1
w
'")
3 "l.
- !9
- L4
- 1.0 lJNli.J
()
- .~
- I. ~"-S 47 30
- L:L Nl*J
~:5
- I. 0 20 5~5 46
- rn NNli.J
()
~:5 16 40
- rn
- J. "7 TCJT1~I...
2:1.
i:i 11
- J.92 3 172 254 104 F'EF~ICJD!:> OF C1:":JLM < HCJUl:~s) *
()
HCll.JF~S CJF MISSING DATA:
2B TABLE 6
. Page 5 of 8 TOTAi...
B9 54
~-)~5
~.rn
- !4
- 1.1.
17 2'7 5<7 79 80 55 67
- l.03 164
- L:I. 6 l.052
- I.
eERlOD OF RECORD: 10 HlO TO l.23180 **
STABILITY CLASS: MODERATELY STABLE DELTA T 1.5 TD 4.0 ~
LAPSE RATE IN DEG C/100 METERS EVALUATED USING DEL.TA T 300-33 FT ELEVATION:
300 FEET
~J IND DI 1:~i:::C**-
TIDN
- I..... ;:~
4-**7 N
()
- I.
NNE::
()
()
NE
()
- I.
i:::NE
- I.
'")
r 0
- I.
ESE
()
()
()
- I.
ssi::
- 1.
- I.
("'
,:)
- I.
- .~
()
- I.
()
()
l.J!:!t.J 0
()
vJ
- I.
- ~~
v.INW 0
0 Nl.J
()
1 NNl.J
()
()
TOT1t.il...
4
- 1.:3 PEF~IDDS CJF C1{;-1l...M (HOUF~!:;) *
()
HCll.JF~i:; CJF MI!:lSJNG DATA:
4 t.JJNDSPEED <MPH> AT fJ.... 1. 2 4
- I.
4
'")
()
4
- I.
- I.
6
- .~
- I.
- ~~
- I.
- I.
0 32
- 1. :3*-:1. fl 9
1::*
- J
~!
- ~~
()
()
- L 4
7 3
c:*,.,
- 3
- I.
- I.
3 6
- 2 TABLE 6 Page 6 of 8 300 FEET
- 1.9-24
>24
- 1
()
2
()
'")
()
()
()
0
()
0
()
()
()
1 4
~)
4 C>
- I.
,.}
- ~
5 2
3
-4 1
0 0
- L
- l.:L.
0 44
- l.B TOTAi...
- 1.7 B
9 7
- I.
- ~
6 1 ;~
~~()
- 1.7
- t.4 1 :L
- L:3 3
6 17
- 1.63
I !
i:>AL.EM UNIT
- I.
PERIOD OF RECORDt 10 180 TO 123180
- STABILITY CL.ASS: EXTREMELY STABLE DEL.TA T >4.0 ~
LAPSE RATE IN DEG C/100 METERS EVALUATED, USING DEL.TAT 300-33 FT ELEVATION:
300 FEET
- i***********************************************************
WINDBPEED 11.IIND DI F~i:;:c;....
TICJN
- 1 "5
4... 7 B--:1.:~
N
()
()
0 NNE
()
()
()
NE
()
()
0 ENE
()
()
()
r 1
()
()
ESE
()
()
()
C'j"'
,:) ::.
()
()
0 SSE 0
- I.
() -
c*
- I.
- ~
2 SGl1J
()
0 2
i:;1iJ
()
()
- I.
~JSliJ
()
()
- I.
1.\\1
()
()
0 l.\\INW 0
0
'")
NliJ
()
()
t NNW
()
- I.
- o TOTAL
)
4 9
F'EF~ICJDS CJF C1~L.M < HCJl.JF;:s) :
()
HCJu1:~s CJF MI £:;i;; I NG DATA:
4
<MPH> AT
- mo
- L :*5.. ~ :I. B
- L9-24 0
()
()
()
()
()
()
0
()
0
()
()
0
()
()
0 C>
j, c>
~~
- I.
()
7
()
4
()
.()
()
()
0
()
0
~!4 4
- TABLE 6 Page 7 of 8 FEET
>24 TCJTAL
()
0 0
0
()
()
()
0
()
- L
()
()
()
()
()
- 1.
- I.
13 1
12
()
2
()
B 2
6
()
- ~
()
1
()
- L 4
47
i I ~
i ARTIFICIAL ISLAND SALEM UNIT 1 PERIOD OF RECORD: 10 180 TO 123180
- srABILITY CLASS: ALL STABILITIES EXCLUDING MISS SPEED/DIR DATA LAPSE RAtE IN DEG C/100 METERS E0ALUATED USING DELTA T 300-33 FT ELEVATION:
300 FEET WIND DI REC-TION 1-3 4-7 N
0 15 NNE 1
6 NE 2
5 ENE 3
14
-r 4
14 ESE
~
8 SE 1
6 SSE 3
16
~
J 2
21 SSW 1
12 SW
' 2 6
WSW
~
8 w
4 16 WNW 0
6 NW 5
16 NNW 1
17 TOTAL 33 186 PERIODS OF CALM <HOURS)
- 0 HOURS OF MISSING DATAI 58 WINDSPEED <MPH) At 8-12 44 30 21 23 18 2
i3 8
22 37 24 34 26 19 31
~~
~J 377 13-18 75 4S 50 29 4
6 6
15 37 35 57 39 49 66 89 74 679 TABLE 6 Page 8 of 8 300 FEET 19-24
)24 24 0
17 1
18 0
5 3
0 1
0 0
4 5
4 7
23 6
31 17 4? -
14 33 21
~~
'~
34 43 19 70 67 74 51 413 246 TOTAL 158 103 96 77 41 18 35 53 111 133 145 137 154 153 278 242 1934 J
1 l
I
~
~