ML20108C570
| ML20108C570 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 12/31/1995 |
| From: | Storz L Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N96095, RERR-18, NUDOCS 9605070028 | |
| Download: ML20108C570 (100) | |
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- l l Pubhc Service Dectnc and Gas Company Louis F. Storz Pubhc Service Electric and Gas Company P.O. Box 236, Hancocks Bridge. NJ 08038 009-339-5700
- s. ,ve.ne. .u - opm,-. APR 3 01996 LR-N96095 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
RADIOACTIVE EFFLUENT RELEASE REPORT - 18 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 In accordance with Section 6.9.1.8 of Appendix A to the Operating License for Hope Creek Generating Station, Public Service i Electric and Gas Company hereby transmits one copy of the annual l Radioactive Effluent Release Report, RERR-18. This report summarizes liquid and gaseous releases and solid waste shipments from the Hope Creek Generating Station for the period of January ;
1, 1995 through December 31, 1995.
Should you have any questions regarding this transmittal, please feel free to contact us.
Sincerely, d,
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Attachment (1) l l
l 080115 9605070028 951231 PDR ADOCK 05000354 1 ff R PDR Q Pnntedon W Recycled Paper l
1 Document Control Desk APR 3 01996 ,
LR-N96095 ALL WITH ATTACHMENT:
C Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 '
Mr. D. Jaffe, Licensing Project Manager -' Hope Creek ;
U.-S. Nuclear Regulatory Commission One White Flint North Mail Stop 14E21 :
11555 Rockville Pike '
Rockville, MD 20852, Mr. R. Summers (X24)
USNRC Senior Resident Inspector '
Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 '
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HOPE CREEK GENERATING STATION I ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT I HCGS RERR-18 1 DOCKET NO. 50-354 OPERATING LICENSE NO. NFP-57 I
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HOPE CREEK GENERATING STATION ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT HCGS RERR-18 DOCKET NO. 50-354 OPERATING LICENSE NO. NFP-57 April 1996 1
HOPE CREEK GENERATING STATION RADIORCTIVE EFFLUENT RELEASE REPORT
~ JANUARY - DECEMBER 1995 Table of Contents INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . .. 1 PART A. PRELIMINADY SUPPLEMENTAL INFORMATION . . . . . . . . . 2 1.0 REGULATORY LIMITS . . . . . . . . . . . -. . . .. . . 2 1.1 Fission and Activation Gas Release Limits . . . . 2 1.2 Iodine, Particulates, and Tritium . . . . , . . . 2 1.3 -Liquid Effluents Release Limits . . . . . . . . . 3 1.4 Total Dose Limit . . . . . . . . . . . . . . . . 3 2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) . . . . . . . 3 3.0 AVERAGE ENERGY.. . . . . . . . . . . . . . . . . . . . 4 4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY 4 5.0 BATCH RELEASES . . . . . . . . . . . . . . . . . . . . . 6 6.0 UNPLANNED RELEASES . . . . . . . . . . . . . . . . . . 6 7.0 ELEVATED RADIATION MONITOR RESPONSES . . . . . . . . .7 8.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS . . . . . . . . . . . . . . .
7 PART B.. GASEOUS EFFLUENTS . . . . . . . . .. . . . . . . . . 7 PART C. ' LIQUID EFFLUENTS . . . . . . . . . . . . . . . . . . . . 7 PART D. SOLID WASTE. . . . . . . . .. . . . . . . . . . .
..7 PART E. RADIOLOGICAL IMPACT ON MAN . . . . . . . . .. . . . . 8 Liquid Pathways . . . . . . . . . . . . . . . . . . . 8 Air Pathways . . . . . . . . . . . . . . . . . . . . . 8 Direct Radiation . . . . . . . . . . . . . . . . . . . 9 Total Dose . . . . . . . . . . . .. . . . . . . . . . . 9 Dose to Members of the Public on Site . . . . . . . 10 Assessment . . . . . . . . . . . . . . . . . . . . . 11 PART F. METEOROLOGICAL DATA . . . . . . . . . . . . . . . . 12 PART G. OFFSITE DOSE CALCULATION MANUAL (ODCM) CHANGES . . . 12 PART H. INOPERABLE MONITORS . . . . . . . . . . . . . . . . 13 PART I. PROCESS CONTROL PROGRAM (PCP) CHANGES. . . . . . . . 13 PART J. ENVIRONMENTAL MONITORING LOCATION CHANGES. . . . . . 13 l
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HOPE CREEK GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT JANUARY - DECEMBER 1995 INTRODUCTION This report, HCGS-RERR-18, summarizes information pertaining to the releases of radioactive materials in liquid, gaseous and solid form from the Hope Creek Generating Station (HCGS) for the period January 1, 1995 to December 31, 1995.
"he Hope Creek Generating Station (HCGS) employs a General Electric (GE) Boiling Water Reactor designed to operate at a rated core thermal power of 3293 MWt with a gross electrical output of approximately 1118 MWe and a net output of approximately 1067 MWe.
The HCGS achieved initial criticality on June 28, 1986 and went into commercial operation on December 20, 1986.
This report is prepared in the format of Regulatory Guide 1.21, Appendix B, as required by Specification 6.9.1.7 of the Hope Creek Technical Specifications. Our responses to parts A-F of the
" Supplemental Information" section of Regulatory Guide 1.21, Appendix B, are included in the following pages.
As required by Regulatory Guide 1.21, the Hope Creek Technical Specification limits are described in detail within this report along with a summary description of how total radioactivity measurements and their approximations were developed.
To facilitate determination of compliance with 40CFR190 requirements, the following information on electrical output is provided.
Hope Creek generated 7,063,919 megawatt-hours of electrical energy (net) during the reporting period.
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PART A. PRELIMINARY SUPPLEMENTAL INFORMATION 1.0 REGUIATORY LIMITS 1.1 Fission and Activation Gas Release Limits The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to the following:
For noble gases: Less than or equal to 500 mrem /yr to the total body and less than or equal ~to 3000 mrem /yr to the skin.
.In addition, the air dose due to noble gases released in gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to the following: l 1
During any calendar quarter: .Less than or equal to 5 mrad for l gamma radiation and less than or equal to 10 mrad for beta radiation and, i
During any calendar year: Less than or equal to 10 mrad for i gamma radiation and less than or equal to 20 mrad for beta
. radiation.
1.2- Iodine, Particulates, and Tritium l The dose rate due to radioactive materials released in j gaseous effluents from the site to areas at and beyond the site boundary, shall be limited to the following:
For iodine-l's.,I-133, for tritium, and for all radionuclides i in particula;e form with half-lives greater than 8 days: Less than or equal to 1500 mrem /yr to any organ.
In addition, the dose to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each reactor unit to areas at and beyond the site boundary shall be limited to the following:
During any calendar quarter: Less than or equal to 7.5 mrem to any organ and, During any calendar year: Less than or equal to 15 mrem to any organ. !
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l 1.3 Liquid Effluents Release Limits The concentration of radioactive material released in '
liquid effluents to unrestricted areas shall be limited ;
to the concentrations specified in 10CFR20, Appendix B,
- Table II, Column 2 for radionuclides other than !
dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 microcuries per milliliter.
In addition, the dose or dose commitment to a member of !
the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited to:
i During any calendar quarter: Less than or equal to 1.5 mrem [
to the total body, and less than or equal- to 5 mrem to any
- organ, and
- During any calendar year: Less than or equal to 3 mrem to the total body, and less than or equal to 10 mrem to any organ. ,
1.4 Total Dose Limit l The annual (calendar year) dose or dose commitment to any member of the public, due to- releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or i equal to 75 mrem). i 2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPC) ]
Regulatory Guide 1.21 requires that the licensee provide the MPCs used in detenmining allowable telease rates or concentrations for radioactive releases,
- a. MPC values were not used for gaseous release concentrations or in the determination of maximum release rates from gaseous effluents.
- b. MPC values as stated in 10CER20, Appendix B, Table II, Column 2 are used for liquid effluents in accordance with current. Technical Specifications.
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-- -- . . - - _ . . - - - - - - _ . . - - .. ~- . .-. -~ -
i 3.0 AVERAGE ENERGY 2
j Regulatory Guide 1.21 requires that the licensee provide the {
s average energy of the radionuclide mixture in releases of l
{ fission and activation gases, if applicable.
nelease limits for HCGS are not based upon average energy. '
l Therefore this section is not applicable to HCGS. ;
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l 4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY l i
j 4.1 Liquid Effluents J x
i l Liquid effluents are monitored in accordance with Table i 4.11.1.1.1-1 of the Technical Specifications. During the !
period of record, all batch liquid wastes were routed to the '
sampling tanks for monitoring prior to release. Technical Specifications require these tanks to be uniformly mixed for ,
sampling and analysis before being released. Batch releases ;
i are defined as releases from the equipment drain sample tanks, ;
i floor drain sampic tanks, detergent drain tanks, and the !
- condensate storage tank dike. Normally, there are no ;
j continuous liquid releases. Specific activities from analyses {
were multiplied by the volume of effluent discharged to the
[ environment in order to determine the total liquid activity i discharged. ;
1 The detection requirements of Table 4.11.1.1.1-1 of the 4
Technical Specifications are achieved or exceeded. l Radionuclides measured at concentrations below the Technical !
Specification detection limit (LLDs) are treated as being i present. Radionuclides for which no activity was detected while meeting the required LLDs are treated as absent, i 4.2 Gaseous Effluents i Gaseous effluent streams are monitored and sampled in ;
accordance with Table 4.11.2.1.2-1 of the Technical Specifications. The north plant vent (NPV) and south plant i vent (SPV) are the final release points for most planned -
gaseous effluent releases. A small quantity of gaseous effluent will ce released via the filtration, recirculation, ,
and ventilation system (FRVS) vent during testing periods. The NPV and SPV are continuously monitored for iodine, j particulates and noble gases; the FRVS is continuously monitored for noble gases. The NPV and SPV monitors have l moving particulate and fixed charcoal filters; the FRVS :
monitor has f,xed particulate and charcoal filters. The i 4
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filters and charcoal are changed weekly, and are analyzed on a multichannel analyzer. The NPV and SPV are sampled weekly for noble gases and tritium.
The detection requirements of Tables 4.11.2.1.2-1 of the Technical Specifications are achieved or exceeded.
Radionuclides detected at concentrations below the Technical Specification detection limit (LLDs) are treated as being present. Radionuclides for which no activity was detected g while meeting the required LLDs are treated as absent.
j Continuous Mode gaseous releases are quantified by routine p (weekly) sampling and isotopic analyses of the plant vents.
If noble gases are detected during the routine sampling, the measured concentrations are adjusted using the radiation monitoring readings to obtain an average concentration for the period. This average concentration is then multiplied by the total vent flow value for the entire sampling period in order to estimate the normal continuous release of radioactivity through the plant vent.
When monthly vent grab samples yield no detectable activity, continuous mode releases are quantified by integrating Radiation Monitor System readings. Noble gas isotopic abundances for these integrations are based on the ANSI I N237-1976/ANS-18.1 mix for BWRs. Doses calculated from this data employ the methods from Section 2.0 and Appendix C of the Hope Creek ODCM.
Batch Mode gaseous releases (primary containment purge) are quantified by pre-release sampling and isotopic analysis.
I Specific activities for each isotope are multiplied by the total purge flow volume for that batch in order to estimate the batch release of radioactivity through the plant vent.
Elevated plant vent radiation monitoring system readings while the channel is in an alarm state are treated as batch mode releases. If specific activity data from grab samples taken is not available, then the abnormal release is quantified by the use of the plant vent radiation monitors. The monitor's response is converted to a " specific activity" using I historical efficiency factors. The " specific activity" is multiplied by the volume of effluent discharged while the channel was in an alarm state in order to estimate the total I activity discharged.
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4.3 Ectimated Total Error The estimated total error of reported liquid and solid releases is within 25%.
The estimated total error of the reported continuous gaseous releases is within 50% when concentrations exceed detectable '.evels. 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%.
Error estimates for releases where sample activity is below the detectable concentration levels are not included since error estimates at the LLD are not defined.
5.0 BATCH RELEASES Summaries of batch releases of gaseous and liquid effluents are provided in Tables 4A and 4B.
6.0 UNPLANNED RELEASES During this reporting period there were 2 unplanned releases.
On April 5, 1995 approximately 85 millicuries of particulate radioactive material was released from the south plant ventilation system. The release resulted in measurable levels of radioactive material being deposited on plant structures, buildings, and vehicles located close to the plant ventilation exhaust. No measurable quantity of radioactive material as a result of this release was found outside of the company property area. The contamination was limited to areas inside the fenced in restricted area and were decontaminated to acceptable levels by health physics personnel. No Federal or State limits were exceeded and there was no rieasurable radiation dose to members of the general public as a result of this release. The cause of the unplanned release was the improper operation and design of the decontamination solution evaporator. The decontamination solution evaporator is part of the installed Radwaste Processing system. The evaporator experienced two high level alarms which led to moisture being carried over into the ventilation system and subsequently released to the environment. The evaporator was removed from service and will not be operated until a complete engineering evaluation can be performed.
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The second unplanned release was a result of the particulate release as described above. On April 9, 1995 a samp]e taken from the south yard drainage system indicated the presence of radioactive material. The south yard drainage system as part of the station drainage system collects water from building roof drains and surrounding plant areas. The south yard drain effluent flows into the Delaware River. The sample taken from the south yard drain indicated the presence of Mn-54, Co-58, and ~ Co-60 at levels well below those allowed by Technical Specifications. The source of the release was water runoff from areas contaminated by the particulate release of April 5th.
7.0 ELEVATED RADIATION MONITOR RESPONSES During this reporting period, there were no elevated radiation monitor readings.
8.0 MODIFICATION TO PREVIOTTS RADIOACTIVE EFFLUENT RELEASE REPORTS There were no modifications to previous Radioactive Ef fluent Release Reports during this reporting period.
PART B. GASEOUS EFFLUENTS See Summary Tables 1A through 1C.
PART C. LIQUID EFFLUENTS See Summary Tables 2A through 2B.
PART D. SOLID WASTE See Summary in Table 3.
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PART E. RADIOIDGICAL IMPACT ON MAN The calculated individual doses-in this section are based on the controlling dose pathways and age groups as described below. The estimated dose represents the maximum radiation dose that could be received by a member of the general public.
The population dose impact is based on historical site specific data; i.e., food production, milk production, feed for milk animals and seafood production.
The doses were calculated using methods described in Regulatory Guide 1.109 and represent calculations for the 12 month reporting interval. Individual doses from batch and continuous releases were calculated using the annual average historic meteorological dispersion coefficients as described in the Offsite Dose Calculation Manual. Population doses were calculated using the meteorological dispersion coefficients for the twelve month reporting interval.
Liquid Pathways Type Age Group Location Pathway Total Body Adult Site Boundary Seafood Ingestion Organ Adult Site Boundary Seafood Ingestion Dose Limit Total Body ---------------------- 0.217 mrem 3 mrem Organ Dose (GI-LLI) ------------- 0.869 mrem 10 mrem Population (Total) ------------- 3.88 person-rem N/A Population (Average) ------------ 0.00086 mrem N/A Air Pathways Type Age Group Location Pathway Total Body All Site Boundary Direct Exposure Skin All Site Boundary Direct Exposure Organ Infant 4.9 mi., West Milk, Ground Plane, Inhalation Dose: Limit Total Body ---------------------- 0.392 mrem 500 mrem /yr Skin Dose ----------------------
0.855 mrem 3000 mrem /yr Organ Dose (thyroid) - - - - - - - - - - - 0.020 mrem 15 mrem Population (Total) -------------- 0.504 person-rem N/A Population (Average) ------------ 0.00011 mrem N/A 8
Direct Radiation Direct radiation may be estimated by thermoluminescent dosimetry (TLD) measurements. One method for comparing TLD measurements is by comparison with pre-operational data. It should be noted that the TLDs measure direct radiation from both the Salem and Hope Creek Generating Stations at Artificial Island, and natural background radiation.
TLD data for the twelve month reporting period is given below:
TLD Location Measurement 2S-2 0.4 mi. NNE 4.1 mrad / month SS-1 1.0 mi E 3.5 mrad / month These values are interpreted to represent natural background, since the values are within the statistical variation associated with the pre-operational program results, which are 3.7 mrad / month for location 2S-2, and 4.2 mrad / month for location SS-1.
Total Dose 40CFR190 limits the total dose to members of the public due to radioactivity and radiation from uranium fuel cycle sources to:
<25 mrem total body or any organ
<75 mrem thyroid for a calendar year. For Artificial Island, the major sources of dose are from liquid and gaseous effluents from the Hope Creek and Salem plants.
The-following doses to a " hypothetical maximum exposed individual" have been calculated for the twelve month reporting period. They are the sum of gaseous and liquid pathway doses for the Salem 1 and 2 and Hope Creek plants:
0.848 mrem total body 1.307 mrem organ (GI-LLI) 0.030 mrem thyroid '
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Do9a to members of thw public dua to cctivitica inaida the site boundary.
In accordance with the requirements of Technical Specification 6.9.1.7, the dose to members of the public inside the site boundary has been calculated based on the following assumptions:
- a. The most limiting member of the general public are the I commercial food vendors.
- b. Food vendors spend 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> per week on site.
- c. The highest total body dose contributor is direct radiation I received from Salem and Hope Creek operation.
- d. Occupancy coincides with gaseous effluent discharges.
- e. The food vendors are located near the restricted area boundary.
For the 12 month reporting period, January 1 1995 to December 31, 1995 the calculated doses are:
I 8.10E+00 mrem Total Body 2.53E-02 mrem Organ (Lung) 2.53E-02 mrem Thyroid i
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' Assessment
- 1. Gaseous: !
Gaseous effluents released from Hope Creek resulted in a .
minimal' dose to the maximum hypothetical individual. The dose for the 12 month period was a small fraction of all applicable l limits.
Gaseous effluents decreased slightly from the previous reporting period. Gaseous effluent releases continue to remain well within Feder?1 limits and are comparable to results from other nuclear utilities. Fuel integrity and gaseous effluent processing equipment continue to be maintained in order to ensure that all releases of gaseous radioactivity are,As-Low-As-Reasonably-Achievable (ALARA).
- 2. Liquids:
Liquid effluents released from Hope Creek station resulted in a minimal dose to the maximum hypothetical individual and were well within all applicable limits.
J The amount of radioactivity in liquid effluents increased from previous reporting periods due to equipment problems associated with the liquid radwaste processing system during the 2nd and 3rd quarters of 1995. The equipment problems were identified and repaired during the 4th quarter of 1995.
Radioactivity released in liquid effluents is expected to return to normal during 1996.
The following two trend graphs show the total curies of gaseous and liquid effluents released for Hope Creek from 1990 through 1995. Calculated doses in the graphs are to the maximum hypothetical individual, i 11
i l Hope Creek Gaseous Efflugnts l Curies of Noble Gases Released i and Calculated Doses l
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0 B 1.00E+01 - - - - - - - - - - - - - - - - - -
m l 1.00E+00 I 8
g 1.00E-01 h3 ; . rg g
- -*- S kin
-+- Curies l
y 1.00E-02 - - - - - - - - - - - -- -
U 1.00E-03 - -- - - - -
1.00E-04 1990 1991 1992 1993 1994 1995 Year Hope Creek Liquid Effluents Curies Released and Calculated Doses 1.60E+00 g 1.40E+00 l k
- 2 1.20E+00 -
-e-TB E i 1.00E+00 -*- Organ '
o 8.00E-01 -
-+- Curies
" 6.00E-01 -
2 -
I 0.00E+00 l 1990 1991 1992 1993 1994 1995 Year l
l PART F. METEOROIDGICAL DATA Cumulative joint wind frequency distributions by atmospheric stability class at the 300 foot elevation are provided for 1995 at the end of this report.
PART G. OFFSITE DOSE CALCUIATION MANUAL (ODCM) CHANGES During this period, there was no revision of the HCGS Off-site Dose Calculation Manual.
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I-PART H. INOPERABLE MONITORS During this period the following effluent monitors were inoperable for greater than 30 days.
- Liquid Radwaste Discharge Monitor (OSPRY-4861)
The liquid radwaste discharge radiation monitor could not be returned to service within 30- days due to extensive testing that was performed on the monitor. The monitor was declared inoperable because it did not respond as predicted by grab samples taken prior to the start of liquid releases. Extensive troubleshooting led to the discovery of a badly corroded sample line at the inlet to the radiation monitor. The corroded line was replaced and the monitor was declared operable after follow up testing demonstrated good correlation to grab sample results.
Cooling Tower Blowdov.. Flow Monitor (1 DAFT-2461)
The cooling tower blowdown flow monitor could not be returned to service within the 30 day time period due to a design deficiency with the blowdown flow monitor. The flow monitor reading becomes invalid when blowdown flow exceeds 35,000 gpm. At flow rates less than 35,000 gpm
.the flow-monitor remains operable. Normal cooling tower blowdown flow is 20,000 - 35,000 gpm. A design change to )
replace the flow monitor is being planned by syst.cm engineering and should be completed during the 1st quarter of-1996.
PART I. PROCESS CONTROL PROGRAM (PCP) CHANGES l
During the reporting period, there were no changes to )
PART J. ENVIRONMENTAL MONITORING IhCATION CHANGES During the reporting period, there were no changes to the Environmental Monitoring sample locations.
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HOPE CREEK GENERATING STATION TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT
, JANUARY - DECEMBER 1995
. GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Est. (1) 1st 2nd Total Units Qtr Qtr Error % i I .
l l A. Fission and Activation
' Gases
- 1. Total release Ci 7.77E+01- 2.36E+01 25-
- 2. Average release
.)
rate for-period - Ci/sec 9.99E+00 3.00E+00 l
- l. 3. Percent of technical ;
I specification limit I l
(T.S. 3.11.2.2(a)) % 1.06E+00 3.22E-01 l B. Iodines
- 1. Total. iodine-131 Ci 1.21E-04 1.94E-04 25 i 2.' Average release I rate for period pCi/sec 1.55E-05 2.47E-05 l
- 3. Percent of technical specification limit (2) I (T.S. 3.11.2.3(a)) % 2.33E-02 3.89E-02
, C. Particulates l 1. Particulates with l half-lives >8 days Ci 1.23E-04 3.39E-04 25
- 2. Average release >
, rate for period pCi/sec 1.58E-05 4.31E-05 l
('
- 3. Percent of technical' l specification limit (2) l (T.S. 3.11.2.3(a)) % 2.33E-02 3.89E-02
- 4. Gross alpha Ci 1.45E-08 0.00E+00 i l
D.. Tritium
[ 1. Total Release' Ci 3.40E+00' 1.67E+00 25 l l 2. Average release l
L'
_ rate for period pCi/sec 4.37E-01 2.12E-01
- 3. Percent of' technical -
specification limit (2)
(T.S. 3.11.2.3(a)) % 2.33E-02 3.89E-02
- 1) For batch releases the estimated overall error is within 10%
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HOPE CREEK GENERATING STATION TABLE 1A i
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1995 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES l
B Est. (1) 3rd 4th Total Units Qtr Qtr Error %
A. Fission and Activation Gases
- 1. Total release Ci 2.68E+01 2.19E+01 25 1 2. Average release rate for period pCi/sec 3.37E+00 2.75E+00
- 3. Percent of technical 1 specification limit (T.S. 3.11. 2. 2 (a) ) % 3.65E-01 2.88E-01 B. Iodines
- 1. Total iodine-131 Ci 2.92E-04 4.42E-05 25
- 2. Average release rate for period Ci/sec 3.67E-05 5.56E-06
- 3. Percent of technical specification limit (2)
(T.S. 3.11. 2. 3 (a) ) % 5.28E-02 1.51E-01 C. Particulates
- 1. Particulates with I half-lives >8 days Ci 7.83E-05 1.39E-03 25
- 2. Average release rate for period pCi/sec 9.84E-06 1.74E-04 I 3. Percent of technical specification limit (2)
(T.S. 3.11.2.3(a)) % 5.28E-02 1.51E-01 I 4. Gross alpha Ci 0.00E+00 0.00E+00 D. Tritium 1 1. Total Release Ci 2.22E-01 6.29E+00 25
- 2. Average release rate for period pCi/sec 2.79E-02 7.91E-01 I 3. Percent of technical specification limit (2)
(T.S. 3.11.2.3(a)) % 5.28E-02 1.51E-01 I (1) For batch releases the estimated overall error is within 10%
(2) Iodine, tritium and particulates are treated as a group 15 I
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.. ~. - _. ~ _ _ _ _ _ _ . _ . _ . _ . _ . _ _ . ~ . _ . _ _ . . _ . . . . _ _ . _ _ _ . . _ _ . . . . _ _
HOPE CREEK GENERATING STATION l TABLE 1B l EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1995 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE i 1st 2nd 1st 2nd l Nuclides Released Unit Otr otr otr Otr .
- 1. Fission Gases Krypton-83m Ci 7.77E-01 2.36E-01 0.00E+00 0.00E+00 Krypton-85m Ci 7.77E-01 2.36E-01 0.00E+00 0.00E+00 Krypton-87 Ci 3.11E+00 9.44E-01 0.00E+00 0.00E+00 Krypton-88 Ci 3.11E+00 9.44E-01 0.00E+00 0.00E+00 Krypton-89 Ci 2.10E+01 6.37E+00 0.00E+00 0.00E+00 Xenon-133 C1 1.55E+00 4.72E-01 0.00E+00 0.00E+00 [
Xenon-135 Ci 3.89E+00 1.18E+00 0.00E+00 0.00E+00 Xenon-135m Ci 4.67E+00 1.42E+00 0.00E+00 0.00E+00 l Xenon-137 Ci 2.41E+01 7.32E+00 0.00E+00 0.00E+00 Xenon-138 Ci 1.47E+01 4.48E+00 0.00E+00 0.00E+00 i . TOTALS Ci 7.77E+01' 2.36E+01 0.00E+00 0.00E+00
- 2. Iodines i Iodine-131 C1 1.21E-04 1.94E-04 0.00E+00 0.00E+00 i Iodine-133 Ci 5.90E-03 1.15E-02 0.00E+00 0.00E+00 TOTALS Ci 6.03E-03 1.17E-02 0.00E+00 0.00E+00
- 3. Particulates (half-life >8 days)
Chromium-51 Ci 0.00E+00 6.13E-05 0.00E+00 0.00E+00 Manganese-54 Ci 1.77E-05 1.70E-04 0.00E+00 0.00E+00 Cobalt-58 Ci 0.00E+00 2.07E-05 0.00E+00 0.00E+00 Iron-59 Ci 0.00E+00 4.13E-05 0.00E+00 0.00E+00 Cobalt-60 Ci 0.00E+00 3.84E-05 0.00E+00 0.00E+00 Zinc-65 Ci 1.05E-04 0.00E+00 0.00E+00 0.00E+00 Strontium-89 Ci 0.00E+00 5.96E-06 0.00E+00 0.00E+00 Strontium-90 Ci 0.00E+00 1.26E-06 0.00E+00 0.00E+00 TOTALS Ci 1.23E-04 3.39E-04 0.00E+00 0.00E+00 16
HOPE CREEK GENERATING STATION TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1995 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Otr Qtr Qtr Qtr
- 1. Fission Gases Krypton-83m Ci 2.68E-01 2.08E-01 0.00E+00 0.00E+00 I Krypton-85m Ci 2.68E-01 2.08E-01 0.03E+00 0.00E+00 Krypton-87 Ci 1.07E+00 8.36E-01 0.00.T+00 0.00E+00 Krypton-88 C1 1.07E+00 8.36E-01 0.00E+00 0.00E+00 l Krypton-89 Ci Ci 7.22E+00 5.64E+00 0.00E+00 0.00E+00 Xenon-133 5.35E-01 4.18E-01 0.00E+00 0.00E+00 Xenon-135 Ci 1.34E+00 2.04E+00 2.97E-03 0.00E+00 1 Xenon-135m Ci 1.61E+00 1.25E+00 0.00E+00 0.00E+00 Xenon-137 Ci 8.29E+00 6.48E+00 0.00E+00 0.00E+00 Xenon-138 Ci 5.08E+00 3.96E+00 0.00E+00 0.00E+00 1 TOTALS Ci 2.67E+01 2.19E+01 2.97E-03 0.00E+00
- 2. Iodines Iodine-131 Ci 2.92E-04 4.42E-05 0.00E+00 0.00E+00 Iodine-133 Ci 1.30E-02 1.20E-01 3.42E-08 0.00E+00 I _______________________________________________________________
TOTALS C1 1.33E-02 1.20E-01 3.42E-08 0.00E+00
- 3. Particulates (half-life >8 days)
Manganese-54 Ci 6.36E-05 4.28E-04 1.42E-06 0.00E+00 Iron-59 Ci 7.17E-06 6.05E-04 0.00E+00 0.00E+00 Cobalt-60 Ci 3.60E-06 3.54E-04 6.09E-07 0.00E+00 Ci 0.00E+00 I Zinc-65 Strontium-89 Ci 3.21E-07 0.00E+00 0.00E+00 1.43E-06 0.00E+00 0.00E+00 0.00E+00 Strontium-90 Ci 6.80E-08 0.00E+00 0.00E+00 0.00E+00 1 TOTALS Ci 7.48E-05 1.39E-03 3.45E-06 0.00E+00 17
HOPE CREEK GENERATING STATION TABLE 1C EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1995 GASEOUS EFFLUENTS-ELEVATED RELEASES There were no elevated gaseous releases during this reporting period.
[
[
(
(
18 L
M
HOPE CREEK GENERATING STATIOP TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1995 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est.
1st 2nd Total Units Otr Qtr Error %
A. Fission and activation products
- 1. Total release (not including tritium, gases, alpha) Ci 6.962-02 2.93E-01 25
- 2. Average diluted concentration during release period. pCi/mL 7.47E-09 2.38E-08
- 3. Percent of technical specification limit (T.S. 3.11.1. 2. (a) ) % 1.55E+00 2.44E+00 B. Tritium
- 1. Total release Ci 0.39E+00 1.40E+01 25
- 2. Average diluted concentration during release period pCi/mL 9.01E-07 1.13E-06
- 3. Percent of technical specification limit (T.S. 3.11.1.1) % 3.00E-02 3.77E-02 C. Dissolved and entrained noble gases
- 1. Total release Ci 1.44E-03 3.32E-03 25
- 2. Average diluted concentration during release period. pCi/mL 1.55E-10 2.70E-10
- 3. Percent of technical specification limit (T.S. 3.11.1.1) % 7.75E-05 1.35E-04 D. Gross alpha activity
- 1. Total release Ci 0.00E+00 0.00E+00 25 E. Volume of waste release (prior to dilution -
Batch Release) liters 7.08E+06 8.98E+06 25 F. Volume of dilution water used during entire period liters 9.31E+09 1.23E+10 25 19
i HOPE CREEK GENERATING STATION '
TABLE 2A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1995 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Est. l 3rd 4th Total i Units Qtr' Otr Error % t l
l A. Fission and activation products i
- 1. Total release (not including tritium, I gases, alpha) Ci 6.60E-01 3.83E-01 25 l l 2. Average diluted '
concentration during release period. pCi/mL 4.49E-08 4.17E-08 l 3. Percent of technical I specification limit (T.S. 3.11.1.2. (a) ) % 1.05E+01 4.41E+00 B. Tritium l
- 1. Total release Ci 1.27E+01 1.10E+01 25 l 2. Average diluted concentration during release period pCi/mL 8.64E-07 1.20E-06 1
- 3. Percent of technical specification limit (T.S. 3.11.1.1) % 2.88E-02 4.00E-02 l C. Dissolved and entrained noble gases
- 1. Total release Ci 5.53E-04 8.23E-04 25 l .2. Average diluted concentration during release period. pCi/mL 3.76E-11 8.97E-11 '
- 3. Percent of technical specification limit (T.S. 3.11.1.1) % 1.88E-05 4.49E-05 D. Gross alpha activity
- 1. Total release Ci 0.00E+00 0.00E+00 25 E. Volume of waste release (prior to dilution -
l Batch Release) liters 6.47E+06 6.02E+06 25 i F. Volume of dilution water used during entire period liters 1.47E+10 9.18E+09 25 20 i
l
3 HOPE CREEK GENERATING STATION TABLE 2B i i
EFFLUENT AND WASTE DISPOSAL' ANNUAL REPORT JANUARY - DECEMBER 1995 LIQUID EFFLUENTS I i
CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd l Nuclides Released Unit Qtr Otr Otr Qtr ;
l Chromium-51 Ci 0.00E+00 0.00E+00 7.62E-03 3.15E-03 Manganese-54 Ci 0.00E+00 5.85E-06 2.65E-02 1.68E-02 l Iron-55 Ci 0.00E+00 0.00E+00 1.77E-02 2.58E-01 !
Cobalt-58 Ci 0.00E+00 2.11E-06 1.88E-03 1.33E-03 Iron-59 Ci- 0.00E+00 0.00E+00 7.85E-04 3.01E-04 Cobalt-60 Ci 0.00E+00 4.52E-06 6.93E-03 5.70E-03 Zinc-65 Ci 0.00E+00 0.00E+00 8.02E-03 7.34E-03 Technetium-99m Ci 0.00E+00 0.00E+00 8.26E-06 0.00E+00 Silver-110m Ci 0.00E+00 0.00E+00 0.00E+00 1.48E-04 l Indium-115m Ci 0.00E+00 0.00E+00 2.90E-05 0.00E+00 l Cesium-134 Ci 0.00E+00 0.00E+00 0.00E+00 3.36E-06 j Cesium-137 Ci 0.00E+00 0.00E+00 0.00E+00 5.46E-06 J Lanthanum-140 Ci 0.00E+00 0.00E+00 1.72E-05 0.00E+00 TOTALS Ci 0.00E+00 1.25E-05 6.95E-02 2.93E-01 Tritium Ci 0.00E+00 0.00E+00 8.39E+00 1.40E+01 Xenon-133 Ci 0.00E+00 0.00E+00 2.53E-04 6.82E-04 Xenon-135 Ci 0.00E+00 0.00E+00 1.18E-03 2.64E-03 TOTALS Ci 0.00E+00 0.00E+00 8.39E+00 1.40E+01
[-
l l l l
l j
l 21 I
HOPE CREEK GENERATING STATION TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1995 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 3rd 4th 3rd 4th Nuclides Released Unit Otr Qtr Otr Otr l Sodium-24' Ci 0.00E+00 0.00E+00 5.66E-06 1.58E-05 Chromium-51 Ci 0.00E+00 0.00E+00 7.93E-02 3.88E-02 Manganese-54 Ci 0.00E+00- 9.97E-05 3.09E-01 5.94E-02
' Iron-55 Ci 0.00E+00 6.40E-02 5.89E-02 1.45E-01 L Manganese-56 Ci 0.00E+00 0.00E+00 1.14E-04 0.00E+00 Cobalt-58 Ci 0.00E+00 0.00E+00 2.02E-02 3.34E-03 Iron-59 Ci 0.00E400 0.00E+00 1.02E-01 8.48E-03 i Cobalt-60 Ci 0.00E+00 0.00E+00 5.28E-02 1.94E-02 l l Zinc-65 Ci 0.00E+00 0.00E+00 3.21E-02 4.02E-02 i Arsenic-76 Ci 0.00E+00 0.00E+00 0.00E+00 8.42E-05 i Niobium-95 Ci 0.00E+00 0.00E+00 1.00E-03 4.54E-05 j Zirconium-97 Ci 0.00E+00 0.00E+00 0.00E+00 3.45E-05 Technetium-99m Ci 0.00E+00 0.00E+00 3.92E-04 4.68E-04 Silver-110m Ci 0.00E+00 0.00E+00 3.31E-03 3.96E-03 j Antimony-124 Ci 0.00E+00 0.00E+00 3.78E-04 0.00E+00 1 Cesium-134 Ci 0.00E+00 0.00E+00 0.00E+00 1.48E-04 !
l Cesium-137 Ci 0.00E+00 0.00E+00 0.00E+00 2.92E-04 l TOTALS Ci 0.00E+00 6.41E-02 6.60E-01 3.19E-01 l
l Tritium Ci 0.00E+00 0.00E+00 1.27E+01 1.10E+01
' Argon-41 Ci 0.00E+00 0.00E+00 0.00E+00 1.04E-05 l Xenon-133 Ci 0.00E+00 0.00E+00 3.80E-05 9.94E-05 Xenon-135 Ci 0.00E+00 0.00E+00 5.15E-04 7.13E-04 i _______-_______-_-__--_____-_---___-__-__-____-______-_-___-__----
TOTALS Ci 0.00E+00 0.00E+00 1.27E+01 1.10E+01 l
l 22 l t
HOPE CREEK GENERATING STATION TABLE 3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1995 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 12-month Est.. Total
- 1. Type of waste Units (1) period Error, %
- a. Spent resins, filters, m3 1.19E+02 sludges, evaporator bottoms Ci 5.22E+02 25
- b. Dry compressible waste, m3 2 34E+01 contaminated equipment. Ci 7.50E-01 25
- c. Irradiated components, m3 0.00E+00 cc col rods Ci 0.00E+00 25
- d. Others (described) m3 0.00E+00 Ci 0.00E+00 25
- 2. Estimate of. major nuclide composition RESINS DAW l
(%) (Ci) (%) (Ci)
Zinc-65 61.0 3.18E+02 42.4 3.21E-01 f Manganese-54 14.6 7.62E+01 25.9 1.96E-01 Iron-55 13.3 6.94E+01 21.7 1.64E-01 Cobalt-60 9.3 4.85E+01 8.6 6.52E-02 f Chromium-51 0.0 0.00E+00 1.0 7.58E-02 (1) Volumes are measured, activities are estimated
(
{
l 23 i
L
. . . _. - - . . _ = . , . .- .
HOPE CREEK GENERATING STATION TABLE 3
)
(CONT ' D) ,
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT ,
JANUARY - DECEMBER 1995 '
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
- 3. Solid Waste Disposition Number of Mode of Destination Type of Shipments Transportation Containers 28 Truck Barnwell, SC HIC and 17E Drums i 17 Truck Oak Ridge, Tn Strong, Tight Containers
- 4. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Mode of Shipments Transportation Destination None N/A N/A 24 I
.. _ _ . . . - _ ~ _
i I
HOPE CREEK GENERATING STATION TABLE 4A l EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1995
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE l
t BATCH RELEASES ONLY l
- 1. Dates: January 1 - March 31, 1995 -
- 2. Type of release: Gas
- 3. Number of releases during the 1st Otr: 1
- 4. Total time duration for all releases of type listed above:
8.57E+03 min l 5. Maximum duration for release of type listed above:
8.57E+03 min l
- 6. Average duration for release of type listed above: l l 8.57E+03 min '
l l 7. Minimum duration for release of type listed above:
8.57E+03 min
- 8. Average stream flow (dilution flow) during the period of release: N/A i
l.
- 25 a
HOPE CREEK GENERATING STATION TABLE 4A (CONT'D)
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1995
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY
- 1. Dates: April 1 - June 30, 1995
- 2. Type of release: Gas
- 3. Number of releases during the 2nd Qtr: 0
- 4. Total time duration for all releases of type listed above:
0.00E+00 min
- 5. Maximum duration for release of type listed above:
.O.00E+00 min
- 6. Average duration for release of type listed above:
0.00E+00 min
- 7. Minimum duration for release of type listed above:
0.00E+00 min
- 8. Average stream flow (dilution flow) during the period of release: N/A i
l l
26 i
l
HOPE CREEK GENERATING STATION TABLE 4A (CONT'D)
EFFLUENT'AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1995
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY
- 1. Dates: July 1 - September 30, 1995
- 2. Type of release: Gas
- 3. Number of releases during the 3rd Qtr: 2
- 4. Total time duration for all releases of type listed above:
2.35E+04 min
- 5. Maximum duration for release of type listed above:
2.31E+04 min
- 6. Average duration for release of type listed above:
1.18E+04 min
- 7. Minimum duration for release of type listed above:
4.19E+02 min
- 8. Average stream flow (dilution flow) during the period of release: N/A l
27 l
l
HOPE CREEK GENERATING STATION TABLE 4A j (CONT ' D)
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1995
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE RATCH RELEASES ONLY
- 1. Dates: October 1 - December 31, 1995
- 2. Type of release: Gas l 3. Number of releases during the 4th Otr: 1
- 4. Total time duration for all releases of type listed above:
l 1.33E+04 min 1
- 5. Maximum duration for release of type listed above: I 1.33E+04 min l l
l 6. Average duration for release of type listed above:
l 1.33E+04 min
- 7. Minimum duration for release of type listed above:
1.33E+04 min
- 8. Average. stream flow (dilution flow) during the period of release: N/A
? l l
I i
t 28 l
l l
I HOPE CREEK GENERATING STATION l
)
TABLE 4B j I
3 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT l JANUARY - DECEMBER 1995
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY
- 1. Dates: January 1 - March 31, 1995
- 2. Type of release: Liquid i
- 3. Number of releases during the 1st Qtr: 164 '
- 4. Total time duration for all releases of type listed above:
- 1.34E+04 min F
I I 5. Maximum duration for release of type listed above 1.34E+02 min 6.
I Average duration for release of type listed above:
9.19E+01 min
- 7. Minimum duration for release of type listed above:
I 1.89+01 min
- 8. Average stream flow (dilution flow) during the period of release: 20150 gpm I
I I
I g 2e I
I
l l
E.
HOPE CREEK GENERATING STATION ;
TABLE 4B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1995
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY
- 1. Dates: April 1 - June 30, 1995
- 2. Type of release: Liquid
- 3. Number of releases during the 2nd Qtr: 224
- 4. Total time duration for all releases of type listed above:
1.76E404 min
- 5. Maximum duration for release of type listed abo ~ve:
1.05E+02 min
- 6. Average duration for release of type listed above:
l 7.86E+01 min
- 7. Minimum duration for release of type listed above:
1.80+01 min I
- 8. Average stream flow (dilution flow) during the period of release: 26010 gpm l i l
l I
30
t j
I HOPE CREEK GENERATING STATION TABLE 4B l (CONT'D)
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT JANUARY - DECEMBER 1995
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED l IN A BATCH MODE l
l BATCH RELEASES ONLY '
- 1. Dates
- July 1 - September 30, 1995
- 2. Type of release: Liquid
- 3. Number of releases during the 3rd Otr: 155 i 4. Total time duration for all releases of type listed above:
l 1.49E+04 min
- 5. Maximum duration for release of type listed above: ,
1.86E+02 min '
l
- 6. Average duration for release of type listed above:
9.61E+01 min l 7. Minimum duration for release of type listed above:
1.00+00 min
- 8. Average stream flow (dilution flow) during the period of release: 37247 gpm l
l l
l l
l 31 i
i l !
l HOPE CREEK GENERATING STATION j TABLE 4B I
(CONT'D)
EFFLUENT AND 4ASTE DISPOSAL ANNUAL REPORT JANUARY - DF" EMBER 1995
SUMMARY
SHEET FOR RADIOAr.'VE EFFLUENTS RELEASED IN A BATCH MODE l
l BATCH RELEASES ONLY l
- 1. Dates: October 1 - December 31, 1995
- 2. Type of release: Liquid
- 3. Number of releases during the 4th Qtr: 121 :
l
- 4. Total time duration for all releases of type listed above.
1.12E+04 min 1
- 5. Maximum duration for release of type listed above:
1.56E+02 min l
l 6. Average duration for release of type listed above:
l 9.24E+01 min I
j 7. Minimum duration for release of type listed above:
l 2.00+00 min
- 8. Average stream flow (dilution flow) during the period of release: 39518 gpm l
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o ARTIFICIAL ISLAND 1/95 - 3/95 JOINT OISTRIBUTION OF WIND OIRECTION AND SPEED
( Of ATMOSPMERIC STABILITY CLASS WINO: 300 FT LAPSE RATE: -0.4 TO 1.5 DEG C/100M DELTA T (300-33FT) CLASS E WIND SPEE0 GROUPS (MPN) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N O 0.0 0 0.0 5 0.2 9 0.4 36 1.7 11 0.5 3 0.1 64 3.0 NNE O 0.0 1 0.0 5 0.2 19 0.9 19 0.9 8 0.4 0 0.0 52 2.4 NE O 0.0 0 0.0 4 0.2 16 0.7 12 0.6 0 0.0 0 0.0 32 1.3 ENE O 0.0 0 0.0 5 0.2 14 0.6 4 0.2 1 0.0 1 0.0 25 1.2 E O 0.0 0 0.0 7 0.3 11 0.5 8 0.4 3 0.1 0 0.0 29 1.3 ESE O 0.0 2 0.1 1 0.0 7 0.3 4 0.2 0 0.0 1 0.0 15 0.7 SE O 0.0 1 0.0 7 0.3 8 0.4 7 0.3 13 0.6 2 0.1 38 1.8 SSE O 0.0 2 0.1 5 0.2 12 0.6 7 0.3 6 0.3 2 0.1 34 1.6 5 0 0.0 3 0.1 4 0.2 9 0.4 5 0.2 1 0.0 0 0.0 22 1.0 SSW D 0.0 2 0.1 6 0.3 4 0.2 7 0.3 2 0.1 0 0.0 21 1.0 SW 0 0.0 2 0.1 6 0.3 13 0.6 26 1.2 5 0.2 0 0.0 52 2.4 WSW 0 0.0 1 0.0 6 0.3 23 1.1 23 1.1 3 0.1 0 0.0 56 2.6 W 0 0.0 2 0.1 6 0.3 16 0.7 29 1.3 3 0.1 0 0.0 56 2.6 WNW 0 0.0 2 0.1 8 0.4 17 0.8 31 1.4 6 0.3 1 0.0 65 3.0 NW 0 0.0 5 0.2 2 0.1 8 0.4 42 1.9 31 1.4 2 0.1 90 4.2 NNW D 0.0 17 0.8 1 0.0 5 0.2 31 1.4 21 1.0 4 0.2 79 3.7 0 0.0 40 1.9 78 3.6 191- 8.9 291 13.5 1*4 5.3 16 0.7 730 33.8 NEAN WIND SPEED: 13.4 MISSING: 0 5
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t ARTIFICIAL ISLAND 1/95 - 3/95 JOIN 7 DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPMERIC STABILITY CLASS WINO: 300 FT DELTA T: (300-33FT) DIRECTION VS SPEED ONLY WIND SPEED GROUPS (MPN) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 $UM PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N 0 0.0 2 0.1 14 0.6 31 1.4 67 3.1 19 0.9 3 0.1 136 6.3 NNE O 0.0 2 0.1 18 0.8 49 2.3 54 2.5 9 0.4 0 0.0 132 6.1 NE O 0.0 3 0.1 17 0.8 60 2.8 41 1.9 0 0.0 0 0.0 121 5.6 ENE O 0.0 3 0.1 16 0.7 34 1.6 17 0.8 1 0.0 1 0.0 72 3.3 E O 0.0 2 0.1 18 0.8 29 1.3 10 0.5 3 0.1 0 0.0 62 2.9 ESE O 0.0 3 0.1 11 0.5 20 0.9 8 0.4 1 0.0 1 0.0 44 2.0 SE O 0.0 2 0.1 19 0.9 24 1.1 26 1.2 28 1.3 7 0.3 106 4.9 SSE O 0.0 7 0.3 12 0.6 41 1.9 26 1.2 49 2.3 40 1.9 175 8.1 S 0 0.0 7 0.3 to 0.5 26 1.2 26 1.2 15 0.7 3 0.1 87 4.0 SSW 0 0.0 4 0.2 to 0.5 16 0.7 37 1.7 10 0.5 0 0.0 77 3.6 59 0 0.0 4 0.2 9 0.4 20 0.9 32 1.5 5 0.2 0 0.0 70 3.2 WSW 0 0.0 4 0.2 16 0.7 49 2.3 64 3.0 23 1.1 4 0.2 160 7.4 W 0 0.0 7 0.3 25 1.2 57 2.6 94 4.4 44 2.0 19 0.9 246 11.4 I WNW 0 0.0 2 0.1 18 0.8 42 1.9 74 3.4 38 1.8 44 2.0 218 10.1 NW 0 0.0 16 0.7 8 0.4 16 0.7 98 4.5 115 5.3 25 1.2 278 12.9 NNW 0 0.0 27 1.3 12 0.6 14 0.6 75 3.5 39 1.8 9 0.4 176 8.1 0 0.0 95 4.4 233 10.8 528 24.4 749 34.7 399 18.5 156 7.2 2160 100.0 MISSING MOURS: 0 MEAN WIND SPEED: 14.6
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ARTIFICIAL ISLAND 4/95 - 6/95 JOINT DISTRIOUTION OF WINO DIRECTION AND SPEED BY ATMOSPNERIC STABILITY CLASS WINO: 300 FT LAPSE RATE: -1.4 TO -0.5 DEG C/100M DELTA T: (300-33FT) CLASS 0 WIND SPEED GROUPS (MPM) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT OIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N O 0.0 0 0.0 2 0.1 8 0.4 13 0.6 14 0.6 2 0.1 39 1.8 NME O 0.0 1 0.0 3 0.1 6 0.3 19 0.9 13 0.6 1 0.0 43 2.0 NE 0 0.0 0 0.0 13 0.6 34 1.6 12 0.5 11 0.5 2 0.1 72 3.3 ENE O 0.0 1 0.0 13 0.6 26 1.2 55 2.5 7 0.3 0 0.0 102 4.7 E D 0.0 1 0.0 16 0.7 21 1.0 5 0.2 0 0.0 0 0.0 43 2.0 ESE O 0.0 0 0.0 4 0.2 6 0.3 18 0.8 3 0.1 0 0.0 31 1.4 SE O 0.0 1 0.0 4 0.2 14 0.6 24 1.1 23 1.1 8 0.4 74 3.4 SSE O 0.0 3 0.1 10 0.5 20 0.9 51 2.3 28 1.3 9 0.4 121 5.5 5 0 0.0 5 0.2 14 0.6 20 0.9 17 0.8 12 0.5 0 0.0 68 3.1 SSW D 0.0 2 0.1 5 0.2 9 0.4 8 0.4 2 0.1 1 0.0 27 1.2 SW 0 0.0 1 0.0 8 0.4 11 0.5 9 0.4 5 0.2 3 0.1 37 1.7 WSW 0 0.0 1 0.0 7 0.3 4 0.2 12 0.5 0 0.0 0 0.0 24 1.1 W 0 0.0 0 0.0 14 0.6 10 0.5 1 0.0 1 0.0 1 0.0 27 1.2 WNW 0 0.0 1 0.0 7 0.3 8 0.4 7 0.3 4 0.2 1 0.0 28 1.3 NW 0 0.0 1 0.0 2 0.1 4 0.2 27 1.2 17 0.8 4 0.2 55 2.5 NNW 0 0.0 0 0.0 2 0.1 7 0.3 7 0.3 14 0.6 7 0.3 37 1.7 0 0.0 18 0.8 124 5.7 208 9.5 285 13.0 154 7.1 39 1.8 828 37.9 MEAN WINO SPEED: 14.0 MISSING: 0 7.,_ . . r, - , . , , _ - -.m. - , , s . .p,_ ..
ARTIFICIAL ISLAND 4/95 - 6/95 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED ST ATMOSPRERIC STA81LITT CLASS WIND: 300 FT LAPSE RATE: *0.4 TO 1.5 DEG C/100M DELTA T: (300-33FT) CLASS E WIND SPEED GROUPS (MPN) 0.0-0.5 0.6-3.5 3.6 7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUM PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUN PERCENT SUM PERCENT StM PERCENT SUM PERCENT N O 0.0 0 0.0 9 0.4 5 0.2 14 0.6 4 0.2 1 0.0 33 1.5 NNE O 0.0 0 0.0 3 0.1 8 0.4 10 0.5 9 0.4 0 0.0 30 1.5 NE O 0.0 3 0.1 6 0.3 5 0.2 8 0.4 2 0.1 0 0.0 24 1.1 ENE 0 0.0 1 0.0 8 0.4 10 0.5 4 0.2 0 0.0 0 . 0.0 23 1.1 E O 0.0 2 0.1 9 0.4 22 1.0 4 0.2 0 0.0 0 0.0 37 1.7 ESE 0 0.0 2 0.1 6 0.3 13 0.6 11 0.5 4 0.2 0 0.0 36 1.6 SE O 0.0 1 0.0 6 0.3 7 0.3 12 0.5 7 0.3 1 0.0 34 1.6 SSE O 0.0 2 0.1 12 0.5 9 0.4 17 0.8 7 0.3 8 0.4 55 2.5 S 0 0.0 4 0.2 5 0.2 8 0.4 18 0.8 12 0.5 3 0.1 50 2.3 SSW D 0.0 1 0.0 5 0.2 11 0.5 17 0.8 17 0.8 4 0.2 55 2.5 SW 0 0.0 2 0.1 3 0.1 16 0.7 26 1.2 15 0.7 5 0.2 67 3.1 WSW 0 0.0 2 0.1 2 0.1 11 0.5 24 1.1 4 0.2 1 0.0 44 2.0 W 0 0.0 3 0.1 9 0.4 13 0.6 12 0.5 0 0.0 0 0.0 37 1.7 WNW 0 0.0 5 0.2 9. 0.4 13 0.6 22 1.0 3 0.1 0 0.0 52 2.4 NV 0 0.0 2 0.1 6 0.3 14 0.6 33 1.5 22 1.0 1 0.0 78 3.6 NNW 0 0.0 3 0.1 3 0.1 8 0.4 24 1.1 13 0.6 6 0.3 ST 2.6 0 0.0 33 1.5 101 4.6 1 73 7.9 256 11.7 119 5.4 30 1.4 712 32.6 MEAN WIND SPEED: 13.6 MIS $1NG: 0
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ARTIFICIAL ISLAND 4/95 - 6/95 JotNT DISTRIBUTION OF WINO DIRECTION AND SPEE0' Of ATMOSPHERIC STASILITY CLASS WIND: 300 FT-DELTA T (300-33FT) ALL STABILITY CLASSES WIND SPEED GROUPS (MPN) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 StM PERCENT DIRECTION SUN PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT N O 0.0 0 0.0 14 0.6 26 1.2 48 2.2 28 1.3 3 0.1 119 5.4 NNE O 0.0 1 0.0 8 0.4 22 1.0 44 2.0 23 - 1.1 1 0.0 99 4.5 NE O 0.0 3 0.1 27 1.2 53 2.4 24 1.1 16 0.7 2 0.1 125 5.7 ENE O 0.0 4 0.2 27 1.2 49 2.2 61 2.8 to 0.5 0 0.0 151 6.9 E O 0.0 5 0.2 32 1.5 47 2.2 9 0.4 0 0.0 C 0.0 93 4.3 ESE O 0.0 4 0.2 12 0.5 21 1.0 29 1.3 7 0.3 0 0.0 73 3.3 SE D 0.0 4 0.2 16 0.7 24 1.1 41 1.9 35 1.6 18 0.8 138 6.3 SSE O 0.0 9 0.4 35 1.6 45 2.1 80 3.7 47 2.2 20 0.9 236 10.8 S 0 0.0 9 0.4 27 1.2 34 1.6 46 2.1 28 1.3 6 0.3 150 6.9
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i ARTIFICIAL ISLAND 4/95 - 6/95 JOINT DISTRIBUTION OF WINO DIRECTION AND SPEED .
BT ATMOSPNERIC STA81LITY CLASS WINO: 300 FT DELTA T: (300-33FT) DIRECTION VS SPEED ONLY WIhD SPEED GROUPS (MPN) 0.0-0.5 0.6 3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 $UM PERCENT DIRECTION SUM PERCENT SUN PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM *ERCENT N O 0.0 0 0.0 14 0.6 26 1.2 48 2.2 28 1.3 3 0.1 119 5.4 NNE D 0.0 1 0.0 8 0.4 22 1.0 44 2.0 23 1.1 1 0.0 99 4.5 NE O 0.0 3 0.1 27 1.2 53 2.4 24 1.1 16 0.7 2 0.1 125 5.7 ENE O 0.0 4 0.2 27 1.2 49 2.2 61 2.8 10 0.5 0 0.0 151 6.9 E O 0.0 5 0.2 32 1.5 47 2.2 9 0.4 0 0.0 0 0.0 93 4.3 ESE O 0.0 4 0.2 12 0.5 21 1.0 29 1.3 7 0.3 0 0.0 73 3.3 SE 0 0.0 4 0.2 16 0.7 24 1.1 41 1.9 35 1.6 18 0.8 138 6.3 SSE O 0.0 9 0.4 35 1.6 45 2.1 80 3.7 47 2.2 20 0.9 236 10.8 S 0 0.0 9 0.4 27 1.2 34 1.6 46 2.1 28 1.3 6 0.3 150 6.9 559 0 0.0 6 0.3 19 0.9 29 1.3 35 1.6 22 1.0 6 0.3 117 5.4 SW 0 0.0 4 0.2 20 0.9 49 2.2 55 2.5 21 1.0 9 0.4 158 7.2 v5u 0 0.0 4 0.2 20 0.9 29 1.3 51 2.3 18 0.8 3 0.1 125 5.7 w 0 0.0 3 0.1 30 1.4 31 1.4 29 1.3 3 0.1 1 0.0 97 4.4 WW 0 0.0 6 0.3 19 0.9 27 1.2 36 1.6 16 0.7 4 0.2 108 4.9 NW 0 0.0 4 C.2 12 0.5 37 1.7 107 4.9 66 3.0 7 0.3 233 10.7 Nuv 0 0.0 5 0.2 9 0.4 30 1.4 66 3.0 37 1.7 15 0.7 162 7.4 1
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, , , e- , m -- m m m m 5 ARi!FICIAL ISLAND 10/95-12/95 JOINT O!STRIBui!ON OF WIND DIRECTION AND SPEED BY ATMOSPMERIC STABILITY CLASS WIND: 300 FT DELTA T: (300-33FT) ALL STABIL!iY CLASSES WIND SPEED GROUPS (MPH) 0.0-0.5 0.6 3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 CE 24.6 $UM PERCENT DIRECTION SUM PERCENT SUN PERCENT SUN PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUN PERCENT N O 0.0 0 0.0 12 0.6 33 1.7 30 1.6 3 0.2 0 0.0 78 4.0 NNE O 0.0 1 0.1 14 0.7 30 1.6 36 1.9 5 0.3 3 0.2 89 4.6 NE O 0.0 2 0.1 10 0.5 14 0.7 10 0.5 4 0.2 5 0.3 45 2.3 ENE O 0.0 1 0.1 13 0.7 29 1.5 to 0.5 0 0.0 0 0.0 53 2.7 E O 0.0 0 0.0 19 1.0 17 0.9 7 0.4 0 0.0 0 0.0 43 2.2 ESE O 0.0 1 0.1 6 0.3 6 0.3 7 0.4 3 0.2 0 0.0 23 1.2 SE O 0.0 1 0.1 11 0.6 19 1.0 16 0.8 10 0.5 30 1.6 87 4.5 SSE O 0.0 2 0.1 14 0.7 23 1.2 31 1.6 19 1.0 16 0.8 105 5.4 S 0 0.0 7 0.4 23 1.2 29 1.5 51 2.6 45 2.3 3 0.2 158 8.2 SSW 0 0.0 9 0.5 21 1.1 44 2.3 59 3.1 46 2.4 10 0.5 1M9 9.8 SW 0 0.0 6 0.3 25 1.3 43 2.2 49 2.5 17 0.9 14 0.7 154 8.0 WSW 0 0.0 7 0.4 17 0.9 36 1.9 36 1.9 9 0.5 9 0.5 114 5.9 W 0 0.0 4 0.2 16 0.8 39 2.0 61 3.2 19 1.0 17 0.9 156 8.1 WNW 0 0.0 1 0.1 21 1.1 36 1.9 61 3.2 67 3.5 30 1.6 216 11.2 NW 0 0.0 1 0.1 9 0.5 46 2.4 109 5.6 65 3.4 21 1.1 251 13.0 NNW 0 0.0 1 0.1 9 0.5 41 2.1 90 4.7 28 1.5 0 0.0 169 8.8 0 0.0 44 2.3 240 12.4 485 25.1 663 34.4 340 17.6 158 8.2 1930 100.0 MISSING HOURS: 278 MEAN WIND SPEED: 14.8
ARTIFICIAL ISLAND 10/95-12/95 JOINT DISTRIBUTION OF WIND DIRECTION AND SPEED BY ATMOSPHERIC STAdILITY CLASS WIND: 300 FT DELTA T: (300-33FT) DIRECTION VS SPEED ONLY j I
WIND SPEED GROUPS (MPN) 0.0-0.5 0.6-3.5 3.6-7.5 7.6-12.5 12.6-18.5 18.6-24.5 GE 24.6 SUN PERCENT DIRECTION SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUM PERCENT SUN PERCENT StM PERCENT N O 0.0 0 0.0 12 0.6 33 1.7 30 1.6 3 0.2 0 0.0 78 4.0 NNE O 0.0 1 0.1 14 0.7 30 1.6 36 1.9 5 0.3 3 0.2 89 4.6 l l
NC 0 0.0 2 0.1 to 0.5 14 0.7 to 0.5 4 0.2 5 0.3 45 2.3 l ENE O 0.0 1 0.1 13 0.7 29 1.5 to 0.5 0 0.0 0 0.0 53 2.7 l E O 0.0 0 0.0 19 1.0 17 0.9 7 0.4 0 0.0 0 0.0 43 2.2 ESE O 0.0 1 0.1 6 0.3 6 0.3 7 0.4 3 0.2 0 0.0 23 1.2 SE O 0.0 1 0.1 11 0.6 19 1.0 16 0.8 10 0.5 30 1.6 87 4.5 SSE O 0.0 2 0.1 14 0.7 23 1.2 31 1.6 19 1.0 16 0.8 105 5.4 S 0 0.0 7 0.4 23 1.2 29 1.5 51 2.6 45 2.3 3 0.2 158 8.2 SSW 0 0.0 9 0.5 21 1.1 44 2.3 59 3.1 46 2.4 to 0.5 189 9.8 Su o 0.0 6 0.3 25 1.3 43 2.2 49 2.5 17 0.9 14 0.7 154 8.0 WSW D 0.0 7 0.4 17 0.9 36 1.9 36 1.9 9 0.5 9 0.5 114 5.9 u 0 0.0 4 0.2 16 0.8 39 2.0 63 3.3 19 1.0 17 0.9 158 8.2 WNw 0 0.0 1 0.1 21 1.1 36 1.9 61 3.2 67 3.5 30 1.6 216 11.2 Nu o 0.0 1 0.1 9 0.5 46 2.4 109 5.6 65 3.4 21 1.1 251 13.0 NNW 0 0.0 1 0.1 9 0.5 41 2.1 90 4.7 28 1.4 0 0.0 169 8.7 0 0.0 44 2.3 240 12.4 485 25.1 665 34.4 340 17.6 158 8.2 1932 100.0 MIS $1NG HOURS: 276 MEAN Wlho SPEED: 14.8