ML20212H105
| ML20212H105 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/31/1986 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| SL-2075, NUDOCS 8703060019 | |
| Download: ML20212H105 (104) | |
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,, GEORGIA POWER Cl?f/ANY PLANT E.', I. HATCH I
7 UNITS NO. 1 & 2
. SEMI.-ANNUAL REPO^1T ! RA010ACTIVf. EFTLUENT RELEASE REPORT 4 /.
- July'1, 1986 - December 31, 1986 I
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k PLANT E. I. HATCH ' SEMIANNUAL REPORT RADI0 ACTIVE EFFLUENT RELEASE REPORT ' SECTION TITLE PAGE
!?1 1. LIQUID EFFLUENTS- I c- .- } , j 1.1 REGULATORY LIMITS ,
1 1.2 MAXIMUM PERMISSIBLE CONCENTRATIONS 5 1/3 MEASUREMENTS AND APPR0XIMATIONS OF TOTAL RADI0 ACTIVITY 5 1.4 LIQUID EFFLUENT RELEASE DATA 7 i.5 , RADIOLOGICAL IMPACT ON MAN DUE TO 3 LIQUID RELEASES , 9 2, GASE0US EFFLUENTS 22 2.1 REGULATORY LIMITS 22 2.2 MEASUREMENTS AND APPR0XIMATIONS OF TOTAL RADIDACTIVITY 28 2.3 GASEOUS EFFL'UENT RELEASE DATA 33 2.4 RADIOLOGICAL IMPACT DUE TO GASE0US RELEASES 34 3 SOLID WASTE 50 3.1 REGULATORY SPECIFICATIONS 50 3.2 SOLID WASTE DATA 50
'4 CHANGES TO THE PLANT HATCH RADIO-LOGICAL ENVIRONMENTAL MONITORING PROGRAM 53 5 METER 0 LOGY 54 l -)
1 5.1 METER 0 LOGICAL DATA 54 D --
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PLANT E. I. HATCH SEMIANNUAL REPORT RADI0 ACTIVE EFFLUENT RELEASE REPORT [ TABLE LIST OF TABLES- PAGE l-1 TECHNICAL SPECIFICATION TABLE 3.14.1-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3 l l-2a. LIQUID EFFLUENTS - SUMMATION OF-ALL RELEASES - UNIT 1 10 1-2b LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES - UNIT 2 11 1 1-2c LIQUID EFFLUENTS - SUMMATIONS OF I ALL RELEASES - SITE 12 l 1-3a. LIQUID EFFLUENTS - UNIT 1 13 1-3b LIQUID EFFLUENTS - UNIT 2 15 1-3c LIQUID EFFLUENTS - SITE 17 1-4a INDIVIDUAL DOSES DUE TO LIQUID j RELEASES'- UNIT 1 19 f' l-4b INDIVIDUAL DOSES DUE TO LIQUID RELEASES - UNIT 2 20 1-5 LOWER LIMITS OF DETECTION - LIQUID SAMPLE ANALYSES 21 2-1 TECHNICAL SPECIFICATION TABLE 3.14.2-1 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION 24 2-2a GASE0US EFFLUENTS - SUMMATION OF ALL RELEASES - UNIT 1 35 2-2b- GASE0US EFFLUENTS - SUMMATION OF 36 ALL RELEASES - UNIT 2 2-2c GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES - SITE 37 2-3a GASE0US EFFLUENTS - ELEVATED RELEASES - UNIT 1 38 2-3b GASEOUS EFFLUENTS - ELEVATED RELEASES - UNIT 2 39 l 2-3c GASEOUS EFFLUENTS - ELEVATED RELEASES - SITE 40
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TABLES LIST OF TABLES PAGE 2-4a GASE0US EFFLUENTS - GROUND-LEVEL RELEASES - UNIT 1 41 2-4b GASEOUS EFFLUENTS - GROUND -
, LEVEL RELEASES - UNIT 2 42 I 2-4c GASE0US EFFLUENTS - GROUND - ) LEVEL RELEASES - SITE 43 h 2-5 GASE0US EFFLUENTS - DOSE f RATES - SITE 44 2-6a f
AIR DOSES DUE TO N0BLE GASES - UNIT 1 45
'l 2-6b AIR DOSES DUE TO N0BLE GASES -
UNIT 2 46 2-7a INDIVIDUAL DOSES DUE TO RADI0 IODINE, TRITIUM, AND PARTICULATES IN GASE0US RELEASES - UNIT 1 47 2-7b INDIVIDUAL DOSES DUE TO RADI0 IODINE, TRITIUM, AND PARTICULATES IN GASE0US RELEASES - UNIT 2 48 2-8' LOWER LIMITS OF DETECTION - GASE0US SAMPLE ANALYSES 49 3-la,b SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 51,52 l l
RADI0 ACTIVE EFFLUENT RELEASE REPORT
- 1 . LIQUID EFFLUENTS 1.1. REGULATORY LIMITS
- 1. The Technical Specifications presented in'this section are for Unit 1. Requirements for Unit 2 are the same as Unit 1; however, the. Technical Specification numbers are not the same.
TECHNICAL SPECIFICATIONS 3.14.1 The radioactive liquid effluent monitoring instrumentation channels shown in table 3.14.1-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.15.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the 0FFSITE DOSE CALCULATION MANUAL (0DCM). (Technical Specification Table 1-1). 3.14.1-1 is included in this section as Table 3.15.1.1 The concentration of radioactive material released at any time from the site to UNRESTRICTED AREAS (figure 3.15-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix 8, 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 2.0E-04 uCi/ml total activity. 3.15.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, from the site (figure 3.15-1) shall be limited to:
- a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ.
- b. During any calendar year to less than or equal to 3 mrem to the total body and to less than or equal 1
to 10 mrem to any organ. 3.15.1.3 The liquid radwaste treatment system, as described in the ODCM, shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent per Unit ' from the site (figure 3.15-1) when projected over the calendar quarter would exceed 0.18 mrem to the total body or 0.62 mrem to any organ. I
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3.15.1.4(a) The contents within any outside temporary tank shall be limited-to 10 curies, excluding tritium and dissolved'or entrained noble gases. l (a) An outside temporary tank isinot surrounded by liners, dikes, or walls that are capable of holding the tank contents and not having tank overflows and drains connected to the liquid F radwaste treatment system. F 1 6.9.1.9 states in part: "The Radioactive Effluent Y Release Report shall include (on a quarterly basis) unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid L effluents that were in excess of 1 C1, excluding dissolved and entrained gases and tritium for liquid effluents, or those in excess of 150 Ci of noble gases or 0.02 Ci of radioiodines for gaseous releases". i 'l. 2 i _ _ _ _ __ _ . - - - - - - ~ - - - - - - ~ ' - - ~ ~ ' ' ~ ~ ~ " ~ ~ ~ ~ ~ ~ ~
TABLE 1-1
'- TECHNICAL SPECIFICATION TABLE 3.14.1-1 (SHEET 1 of 2)
RADI0 ACTIVE LIQUID' EFFLUENT MONITORING INSTRUMENTATION Minimum Instrument Channels OPERABLE Applicability ACTION 1.-Gross Radioactivity Monitors-Providing Automatic Termina- ~ tion of Release Liquid Radwaste Effluent Line l' (a) 100
- 2. Gross Radioactivity Monitors not Providing Automatic Termination of Release Service Water System Effluent Line 1 (b) 101
- 3. Flowrate Measure-ment Devices **
Liquid Radwaste Effluent Line 1 (a) 102 Discharge Canal 1 (b) (a) 102
- 4. Service Water System to Closed 1
At all times 103 Cooling Water System Differential Pressure t
** Pump curves may be utilized to estimate flow; in such cases, ACTION statement 102 is not required.
j (a) Whenever the radwaste discharge valves are not locked closed. l (b) Whenever the service water system pressure is below the closed cooling water system pressure or P [ indication is not available, i 3
k TABLE l-1 (CONTINUED) TECHNICAL SPECIFICATION TABLE 3.14.1-1 (SHEET 1 of 2) RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TABLE NOTATIONS ACTION 100 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may be continued, provided that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with Specification 4.15.1.1.1.
- b. At least two technically qualified individuals independently verify the release rate calculations and discharge valving.
Otherwise, suspend release of radioactive effluents via this pathway. If the channel remains inoperable for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report. ACTION 101 - With the numbers of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided that once per shift grab samples are collected and analyzed for gross radioactivity Detection of at least 10-(7 beta or gamma) at a Lower Limit of uCi/ml. If the channel remains inoperable for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report. ACTION 102 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided the flowrate actual releases. is estimated at least once per 4 hours during If the channel remains inoperable for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report. ACTION 103 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, assure that the service water system effluent system monitor is OPERABLE. 4
l l 'l . 2 ~ MAXIMUM PERMISSIBLE CONCENTRATIONS The MPC values used in determining allowable liquid radwaste release rates and concentrations for principal gamma emitters, I-131, tritium, Sr-89, Sr-90 and Fe-55 are taken from 10CFR Part 20, Appendix 8, Table II, Column 2. l For dissolved or entrained noble gases in liquid 3 radwaste, the MPC is taken from Technical
). Specification 3.15.1.1 (Unit 1) and 3.11.1.1 (Unit >- 2) as 2.0E-04 uCi/ml.
For gross alpha in liquid radwaste, the MPC is taken from 10CFR Part 20, Appendix 8, Note 2.b as 3.0E-08 uCi/ml. Further, for all the above radionuclides or categories of radioactivity, the overall MPC fraction is determined in accordance with 10 CFR Part 20, Appendix 8, Note-1. The method whereby the MPC fraction is used to determine release rates and liquid radwaste effluent radiation monitor setpoints is described in Section 1.3 of this report. 1.3 MEASUREMENTS AND APPR0XIMATIONS OF TOTAL RADI0 ACTIVITY Prior to release of any tank containing liquid radwaste, and following the required recirculation, samples are collected and analyzed in accordance with Technical Specification Tables 4.15.1-1 (Unit 1) and 4.11.1-1 (Unit 2). A sample from each tank planned for release is analyzed for principal gamma emitters, I-131, and dissolved and entrained noble gases by gamma spectrometry. Monthly and quarterly composites are prepared for analysis by extracting aliquots from each sample taken from tanks which are released. Liquid radwaste sample analyses are performed as follows: Measurement Frequency Method
- 1. Gamma Isotopic Each Batch Gamma spectroscopy with computerized data reduction
- 2. Dissolved or Each Batch Gamma spectroscopy Entrained with computerized Noble Gases data reduction 5 l l
Measurement' Frequency Method
- 3. Tritium Monthly Distillation and Composite liquid scintillation counting
- 4. Gross Alpha Monthly Gas Flow Proportional Composite counting
- 5. Sr-89 and Sr-90 Quarterly Chemical separation and Composite gas flow proportional counting
- 6. Fe-55 Quarterly Chemical separation and Composite low energy photon detector.
Gamma isotopic measurements are performed in-house in the radiochemistry lab using germanium spectrometry. Three germanium detectors are available: a 10% efficient Ge(Li) detector and two 15% efficient intrinsic germanium detectors, with 2.0 FWHM resolution and housed in 4 inch-thick . lead shields. A one-liter liquid radwaste sample is poured into a Marinelli beaker in preparation for a 2000-3000 second count. A peak search of the resulting gamma ray spectrum is performed by the computer system. Energy and net count data for all significant peaks are determined, and quantitative reduction or LLD ' calculations are performed for the nuclides specified in Table Notation e of Technical Specification Tables 4.15.1-1 (Unit 1) and 4.11.1-1 (Unit 2): Mn-54, F-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144. The quantitative calculations include corrections for counting time, decay time, sample volume, sample geometry, detector efficiency, baseline counts, and branching ratio. LLD calculations, including the above corrections, are made based on the counts in two standard deviations'of the baseline count at the location on the spectrum where a peak for that radionuclide would be located if present. The radionuclide concentrations determined by gamma spectroscopic analysis of a sample taken from a tank planned for release and the most current sample analysis results available for tritium, gross alpha, Sr-89, Sr-90, and Fe-55 are used along with the corresponding MPC values to determine an MPC fraction for the tank planned for release. This MPC fraction is then used, with appropriate safety factors, along with the expected dilution stream flow to calculate a maximum permissible release rate and a liquid effluent monitor setpoint. The monitor setpoint is calculated to assure that the limits of Technical Specifications 3.15.1.1 (Unit 1) or 3.11.1.1 (Unit 2) are not exceeded. 6
F A monitor reading in excess of the calculated setpoint therefore results in an automatic termination of the liquid radwaste discharge. Liquid effluent discharge is also automatically terminated if the dilution stream flow rate falls below the dilution flow rate used in the setpoint calculations and established as a setpoint on the dilution stream flow monitor. Radionuclide concentrations, safety factors, dilution stream flow rate, and liquid effluent radiation monitor calibration factor are entered into the computer and a prerelease printout is generated. If the release is not permissible appropriate warnings will be included on the prerelease printout. If the release is permissible it is approved by the Chemistry Foreman on duty. The pertinent information is transferred manually from the prerelease printout to a one-page release permit which is forwarded to Radwaste Operations. When the release is completed the release permit is returned from
.Radwaste Operations with actual release data included. These data are input to the computer and a postrelease printout is generated. The postrelease printout contains actual release rates, actual release concentrations and quantities, actual dilution flow, and calculated doses to an individual.
1.4 LIQUID EFFLUENT RELEASE DATA Regulatory Guide 1.21 Tables 2A and 28 are found in this report as Table 1-2a for Unit 1, Table 1-2b for Unit.2 and Table 1-2c for the site; and Table 1-3a for Unit 1, 1-3b for Unit 2, and Table 1-3c for the site. The values for the four categories of Tables 1-2a and 1-2b, and 1-2c are calculated and the Tables completed as follows:
- 1. Fission and activation products - The total release values (not including tritium, gases, and alpha) are comprised of the sum of the measured individual radionuclide activities. This sum is for each batch released to the river for the respective 7
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quarter. Percent of applicable limit is deterained from a mixed nuclide MPC fraction calculation. The average concentration for each nuclide over all released batches is divided by the corresponding individual MPC value. The sum over all nuclides of the Ci/MPCi ratios times 100 is the percent of applicable limit for effluent releases during the quarter.
- 2. Tritium - The measured tritium concentrations in the monthly composite samples are used to calculate the total release and average diluted concentration during each period. Average diluted concentration divided by the MPC limit, 3.0E-03 uC1/ml, is converted to percent to give the percent of applicable limit.
- 3. Dissolved and entrained gases -
Concentrations of dissolved and entrained gases in liquid effluents are measured by germanium spectroscopy on a one liter sample from each liquid radwaste batch. The average concentration of dissolved or entrained noble gases for all released batches is divided by the MPC value stated in Technical Specifications 3.15.1.1 and 3.11.1.1 (2.0E-04 uCi/ml) to determine the MPC fraction. The result x100 is the percent of applicable limit for noble gases in liquid effluent releases during the quarter. Radioisotopes of iodine in any form are also determined during the isotopic analysis for each batch; therefore, a separate analysis for possible gaseous forms is not performed because it would not prov_ide additional information.
- 4. Gross alpha radioactivity - The measured gross alpha concentrations in the monthly
' composite samples are used to calculate the total release of alpha radioactivity. 8
- _ _ _ . , , _ . _ _ , _ _ . . . . . _ - - , _ . - _ _ _ , _ _ - ~ - - ,_
4 Other data pertinent to batch releases of-radioactive liquid effluent from both units is as follows: -
Number of batch releases: 925.
- . Total time period for batch releases: 116,802 minutes Maximum time period for a-batch release: . 412.0 minutes
' Average. time period.for batch releases: 126.3 minutes 4 Minimum time period for a batch release: 2.0 minutes Average stream flow during periods of release of liquid effluent into a flowing stream: 3205.2 .CFS 1.5 RADIOLOGICAL IMPACT ON MAN.DUE TO LIQUID RELEASES Doses to an i ndividual, due to radioaciivity in liquid effluent, were calculated in accordance with Technical Specifications 3/4.15.1.2 (Unit 1) and 3/4.11.1.2 (Unit 2) using the methodology presented in the Plant Edwin I. Hatch Offsite-Dose Calculation Manual. As required by the above Technical Specifications, doses were calculated separately for Unit 1 and Unit 2. Results are presented in Table 1-4a for Unit 1 and Table 1-4b for. Unit 2. i j w r'* *
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TABLE 1-2a E. I. HATCH NUCLEAR PLANT - UNIT 1
- v. SEMIANNUAL EFFLUENT RELEASE REPORT 1986 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter 3 Est. Total A. Fission & Quarter 4 Error %
Activation
-Products
- 1. Total release (not including C1 1.05E-01 1.62E-01 H-3, gases, 4.6E+01 alpha)
- 2. Average diluted concentration uCi/ml 6.95E-08 9.59E-08 during period
- 3. % of applicable % 9.66E-01 limit 5.09E+00 B. Tritium
- 1. Total release C1 5.71E+00
- 2. Average diluted 5.30E+00 3.7E+01 uCi/ml 3.78E-06 2.04E-06 concentration during period
- 3. % of applicable % 1.26E-01 limit 6.80E-02 C. Dissolved and Entrained Gases
- 1. Total release C1 2.75E-03
- 2. Average diluted 1.16E-02 1.0E+02 uCi/ml 1.82E-09 6.86E-09 concentration during period
- 3. % of applicable % 9.10E-04 3.43E-03 limit D. Gross alpha radioactivity
- 1. Total release C1 6.21E-07 8.10E-07 1.2E+02 E. Volume of waste (prior to dilution) liters 7.52E+06 8.73E+06 1.0E+01 F. Volume of dilution water used liters 1.51E+09 1.69E+09 1.6E+02 to
TABLE 1-2b E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL EFFLUENT RELEASE REPORT 1986 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter 3 Est. Total A. Fission & Quarter 4 Error % Activation Products
- 1. Total release (not including Ci 5.64E-02 1.79E-01 4.7E+01 H-3, gases, alpha)
- 2. Average diluted concentration uC1/ml 4.18E-08 1.61E-07 during period
- 3. % of applicable % 3.80E+00 limit 5.00E-01 B. Tritium
- 1. Total release C1 2.97E+00 1.40E+00 3.7E+0i
- 2. Average diluted uCi/ml 2.20E-06 concentration 1.26E-06 during period
- 3. % of applicable % 7.33E-02 limit 4.20E-02 C. Dissolved and Entrained Gases
- 1. Total release C1 2.00E-02
- 2. Average diluted 3.60E-04 1.0E+02 uCi/ml 1.48E-08 3.24E-10 concentration during period
- 3. % of applicable % 7.40E-03 limit 1.62E-04 D. Gross alpha radioactivity
- 1. Total release C1 7.97E-07 5.22E-07 1.2E+02 E. Volume of waste (prior to dilution) liters 5.42E+06 4.42E+06 1.0E+01 F. Volume of dilution water used liters 1.35E+09 1.11E+09 1.6E+02 4
11
TABLE 1-2c E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL EFFLUENT RELEASE REPORT 1986 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Est. Total A. Fission & Unit Quarter 3 Quarter-4 Error % Activation Products
- 1. Total release (not including C1 1.61E-01 3.41E-01 4.7E+01 H-3, gases, alpha)
- 2. Average diluted concentration uC1/mi 5.63E-08 1.22E-07 during period
- 3. % of applicable % 2.30E+00 limit 3.25E+00 B. Tritium
- 1. Total release C1 8.68E+00 6.70E+00 3.7E+01
- 2. Average diluted uCi/ml 3.03E-06 concentration 2.39E-06 during period
- 3. % of applicable % 1.01E-01 limit 5.76E-02 C. Dissolved and Entrained Gases
- l. Total release C1 2.28E-02 1.20E-02
- 2. Average diluted 1.0E+02 uCi/ml 7.97E-09 4.29E-09 concentration during period
- 3. % of applicable % 3.96E-03 limit 2.12E-03 D. Gross alpha radioactivity
- 1. Total release C1 1.42E-06 1.33E-06 1.2E+02 E. Volume of waste (prior to dilution) liters 1.29E+07 1.32E+07 1.0E+01 3
F. Volume of dilution 1 water used liters 2.86E+09 2.80E+09 1.6E+02 1 12
TABLE 1-3a E. I. HATCH NUCLEAR PLANT - UNIT l SEMIANNUAL LIQUIO EFFLUENTS RELEASE REPORT 1986* i Page 1 of 2 Continuous Mode ** Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 I Quarter 3 Quarter 4 H-3 Ci 5.71E+00 5.30E+00 Na-24 Ci Cr-51 C1 4.86E-02 3.26E-02 Mn-54 Ci 3.36E-03 3.34E-03 Mn-56 Ci 1.14E-03 3.06E-03 Fe-55 Ci 4.53E-05 0.00E+00 Fe-59 Ci 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 2.01E-04 Co-60 Ci 9.39E-04 1.44E-03 Cu-64 Ci 4.16E-03 7.14E-03 Zn-65 C1 9.98E-04 1.23E-03 As-76 Ci 1.10E-02 1.64E-02 Sr-89 Ci 1.29E-03 9.39E-04 Sr-90 Ci 0.00E+00 0.00E+00 Sr-91 Ci 0.00E+00 0.00E+00 Sr-92 Ci 0.00E+00 0.00E+00 Y-91m Ci 2.03E-05 1.21E-05 Zr-95 Ci 5.07E-03 7.24E-04 Nb-95 Ci 0.00E+00 4.70E-05 Nb-97 Ci 0.00E+00 9.45E-05 Tc-99m Ci 7.67E-05 2.10E-04 I-131 Ci 4.40E-03 3.28E-03 1-132 Ci 2.52E-03 1.14E-02 I-133 Ci 0.00E+00 1.19E-05 I-134 Ci 2.94E-03 2.81E-03 I-135 C1 7.37E-04 2.70E-04 Cs-134 Ci 1.17E-04 1.87E-04 Cs-136 Ci 4.75E-03 2.84E-02 Cs-137 Ci 5.64E-05 7.14E-04 Ba-140 Ci 1.36E-02 4.71E-02 La-140 Ci 0.00E+00 0.00E+00 Np-239 Ci 0.00E+00 1.40E-05 Totals Ci 2.09E-05 1.34E-05 1.05E-01 1.62E-01 13
TABLE 1-3a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL LIQUID EFFLUENTS RELEASE REPORT 1986* ; Page 2 of 2 Continuous Mode ** Batch Mode Nuclides *
; Released Unit Quarter 3 Quarter 4 I
Quarter 3 Quarter 4 Kr-85 Ci Kr-85m Ci 2.81E-04 0.00E+00 Xe-133 Ci 0.00E+00 8.19E-07 Xe-133m Ci 6.00E-04 5.95E-03 j Xe-135m Ci 0.00E+00 6.29E-05
- i Xe-135 Ci 4.32E-05 2.92E-04 Ar-41 Ci 1.82E-03 5.26E-03 Totals Ci 1.79E-06 0.00E+00 2.75E-03 1.16E-02 '
Gross Alpha . Ci 6.21E-07 8.10E-07 i gJ
- Zeros in this table indicate that no radioactivity was present above detectable levels. See Table 1-5 for typical lower limits of detection for liquid sample analyses.
c
**There pathways at Plant Hatch.
are no continuous mode radioactive liquid release } l l 4 ? 14 i
TABLE l-3b E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL LIQUIO EFFLUENTS RELEASE REPORT 1986* Page 1 of 2 Continuous Mode ** Batch Mode Nuclides 7 Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4
! H-3 Ci I 2.97E+00 1.40E+00 I )
Na-24 Ci Cr-51 Ci 3.46E-03 4.00E-05
' Mn-54 Ci 2.21E-03 7.84E-06 Mn-56 Ci 1.31E-03 3.48E-03 3 Fe-55 Ci 3.27E-05 5.01E-06 l Fe-59 Ci 0.00E+00 1.25E-01 1 Co-58 Ci 4.92E-06 1.50E-05 Co-60 Ci 8.08E-04 9.46E-04 Cu-64 Ci 2.96E-03 7.25E-03 ) Ni-65 8.09E-04 0.00E+00 Ci Zn-65 Ci 0.00E+00 0.00E+00 As-76 Ci 4.84E-03 6.46E-03 ) Rb-88 Ci 8.31E-05 0.00E+00 ) ' Sr-89 Ci 0.00E+00 0.00E+00 Sr-90 Ci 0.00E+00 0.00E+00 Sr-91 Ci 0.00E+00 0.00E+00 Sr-92 Ci 6.39E-06 0.00E+00
( Y-91m C1 8.30E-06 0.00E+00 Zr-95 Ci 2.62E-04 0.00E+00 Nb-95 Ci 0.00E+00 0.00E+00 Nb-97 Ci 1.65E-05 2.39E-05 Mo-99 Ci 1.98E-05 3.61E-05 Tc-99m Ci 0.00E+00 0.00E+00 Te-131 Ci 2.34E-03 1.83E-05 I-131 Ci 0.00E+00 0.00E+00 I-132 Ci 1.25E-02 7.17E-04 I-133 Ci 9.38E-04 0.00E+00 I-134 Ci 7.79E-03 2.95E-06 I-135 Ci 8.98E-06 0.00E+00 Cs-134 Ci 2.35E-03 0.00E+00 Cs-136 Ci 4.02E-03 1.50E-02 Cs-137 Ci 3.36E-04 6.95E-05 Cs-138 Ci 7.03E-03 1.97E-02 Ba-139 Ci 0.00E+00 0.00E+00 Ba-140 Ci 0.00E+00 0.00E+00 Ce-141 Ci 0.00E+00 0.00E+00 Np-239 Ci 2.64E-06 0.00E+00 Totals Ci 2.28E-03 2.88E-05 5.64E-02 1.79E-01 15
TABLE l-3b E. I. HATCH NUCLEAR PLANT - UNIT 2 i SEMI ANNUAL LIQUID EFFLUENTS RELEASE REPORT 1986* Page 2 of 2 Continuous Mode ** Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Kr-85m Ci Kr-85 Ci 4.96E-06 0.00E+00 Xe-131m Ci 2.50E-04 0.00E+00 Xe-133m C1 1.84E-04 0.00E+00 Xe-133 Ci 1.75E-04 0.00E+00 Xe-135m -Ci 9.20E-03 3.39E-04 Xe-135 Ci 3.05E-03 0.00E+00 Ar-41 Ci 7.15E-03 1.97E-05 Totals C1 0.00E+00 1.04E-06 2.00E-02 3.60E-04 Gross Alpha Ci 7.97E-07 5.22E-07
- Zeros in this table indicate that no radioactivity was present above detectable levels. See Table 1-5 for typical lower limits of detection for liquid sample analyses.
**There are no continuou's mode radioactive liquid release pathways at Plant Hatch.
16
TABLE l-3c E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL LIQUIO EFFLUENTS RELEASE REPORT 1986* Page 1 of 2 Continuous Mode ** Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 H-3 Ci 8.68E+00 6.70E+00 Na-24 Ci Cr-51 Ci 5.21E-02 3.26E-02 Mn-54 5.57E-03 3.35E-03 Ci 2.45E-03 Mn-56 Ci 6.54E-03 Fe-55 7.80E-05 5.01E-06 Ci 0.00E+00 Fe-59 Ci 1.25E-01 Co-58 4.92E-06 2.16E-04 C1 Co-60 1.75E-03 2.39E-03 Ci 7.12E-03 Cu-64 Ci 1.44E-02 Ni-65 1.81E-03 1.23E-03 Ci 0.00E+00 Zn-65 Ci 0.00E+00 As-76 1.58E-02 2.29E-02 Ci 1.37E-03 Sr-89 Ci 9.39E-04 Sr-90 0.00E+00 0.00E+00 Ci 0.00E+00 Sr-91 Ci 0.00E+00 Sr-92 Ci 6.39E-06 0.00E+00 Y-91m Ci 2.86E-05 1.21E-05 Zr-95 Ci 5.33E-03 7.24E-04 Nb-95 0.00E+00 4.70E-05 Ci 1.65E-05 Nb-97 Ci 1.18E-04 Mo-99 Ci 9.65E-05 2.46E-04 Tc-99m 0.00E+00 0.00E+00 Ci 6.74E-03 1-131 Ci 3.30E-03 1-132 1.50E-02 1.21E-02 Ci 9.38E-04 I-133 Ci 1.19E-05 I-134 1.07E-02 2.81E-03 Ci 7.46E-04 I-135 Ci 2.70E-04 Cs-134 2.47E-03 1.87E-04 Ci 8.77E-03 Cs-136 Ci 4.34E-02 Cs-137 3.92E-04 7.84E-04 C1 Ba-140 2.06E-02 6.68E-02 Ci 0.00E+00 La-140 Ci 0.00E+00 Ce-141 0.00E+00 1.40E-05 Ci 2.64E-06 Np-239 0.00E+00 C1 2.30E-03 4.22E-05 Totals Ci 1.61E-01 3.41E-01 17
TABLE 1-3c E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL LIQUID EFFLUENTS RELEASE REPORT 1986* Page 2 of 2 Continuous Mode ** Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Kr-85m Ci Kr-85 Ci 4.96E-06 8.19E-07 Xe-131m Ci 5.31E-04 0.00E+00 Xe-133m C1 1.84E-04 0.00E+00 Xe-133 Ci 1.75E-04 6.29E-05 Xe-135m Ci 9.80E-03 6.29E-03 Xe-135 Ci 3.09E-03 2.92E-04 Ar-41 Ci 8.97E-03 5.28E-03
. Totals Ci 1.79E-06 1.04E-06 2.28E-02 1.20E-02 Gross Alpha Ci 1.42E-06 1.33E-06
- Zeros in this table indicate that no radioactivity was present above detectable levels. See Table 1-5 for typical lower limits of detection for liquid sample analyses.
- There are no continuous mode radioactive liquid release pathways at Plant Hatch.
18
TABLE l-4a E. I. HATCH NUCLEAR PLANT UNIT 1 SEMIANNUAL EFFLUENT RELEASE REPORT 1986 INDIVIOUAL 00SES DUE TO LIQUID RELEASES Cumulative Dose Per Quarter Organ Tech Units Quarter % of Spec Quarter % of 3 Tech 4 Tech Limit Spec Spec Limit Limit Bone 5.0 mrem /qtr 8.15E-02 1.63E+00 2.99E-01 Liver 5.0 mrem /qtr 1.32E-01 5.98E+00 T. Body 2.64E+00 5.09E-01 1.02E+01 1.5 mrem /qtr 9.21E-02 6.15E+00 Thyroid 5.0 mrem /qtr 3.69E-01 2.46E+01 2.05E-02 4.10E-01 7.17E-01 1.43E+01 Kidney 5.0 mrem /qtr 4.59E-02 9.18E-01 Lung 5.0 mrem /qtr 7.71E-01 1.54E+01 1.43E-02 2.86E-01 5.56E-02 1.11E+00 GI-LLI 5.0 mrem /qtr 9.06E-03 1.81E-01 1.88E-02 3.76E-01 Cumulative Dose Per Year Organ Tech Spec Unit Quarters % of Tech 1,2,3&4 Spec Limit Limit Bone 10.0 mrem /yr Liver 8.36E-01 8.36E+00 10.0 mrem /yr 1.40E+00 1.40E+01 Total Body 3.0 mrem /yr 1.00E+00 Thyroid 10.0 3.34E+01 mrem /yr 7.50E-01 7.50E+00 Kidney 10.0 mrem /yr 1.08E+00 Lung 10.0 1.08E+01 mrem /yr 1.51E-01 1.51E+00 GI-LLI 10.0 mrem /yr 7.17E-02 7.17E-01 19
TABLE l-4b E. 1. HATCH NUCLEAR PLANT UNIT 2 SEMIANNUAL EFFLUENT RELEASE REPORT 1986 INDIVIDUAL DOSES DUE TO LIQUID RELEASES Cumulative Dose Per Quarter Organ Tech Units Quarter % of Spec Quarter % of 3 Tech 4 Tech Limit Spec Spec Limit Limit Bone 5.0 mrem /qtr 3.62E-02 7.24E-01 1.llE-01 Liver 5.0 mrem /qtr 6.27E-02 2.22E+00 T. Body 1.25E+00 1.96E-01 3.92E+00 1.5 mrem /qtr 4.55E-02 3.03E+00 -Thyroid 5.0 1.43E-01 9.53E+00 mrem /qtr 9.87E-02 1.97E+00 Kidney 5.0 mrem /qtr 4.88E-03 9.76E-02 2.18E-02 4.36E-01 6.55E-02 1.31E+00 Lung 5.0 mrem /qtr 6.72E-03 1.34E-01 GI-LLI 5.0 2.14E-02 4.28E-01 l mrem /qtr 3.93E-03 7.86E-02 9.21E-03 1.84E-01 l Cumulative Dose Per Year Organ Tech Unit Spec Quarters % of Tech 1,2,3&4 Spec Limit Limit Bone 10.0 mrem /yr Liver 2.09E-01 2.09E+00 10.0 mrem /yr 3.63E-01 Total Body 3.0 3.63E+00 mrem /yr 2.63E-01 8.77E+00 Thyroid 10.0 mrem /yr Kidney 1.88E-01 1.88E+00 10.0 mrem /yr 1.23E-01 1.23E+00 Lung 10.0 mrem /yr 3.94E-02 GI-LLI 10.0 mrem /yr 3.94E-01 1.84E-02 1.84E-01 20
TABLE 1-5 I LOWER LIMITS OF DETECTION - LIQUID SAMPLE ANALYSES r The values in this table represent apriori lower limits i of detection (LLO)radwaste analyses of liquid which are typically achieved in laboratory. samples. l- ! RADIONUCLIDE LLO UNITS L Mn-54 3778E-08 uct/ml Fe-59 7.78E-08 Co-58 4.67E-08 Co-60 4.78E-08 i Zn-65 ! 1.31E-07 Mo-99 5.10E-07 Cs-134 7.18E-08 Cs-137 6.05E-08 Ce-141 1.41E-07 Ce-144 6.30E-07 I-131 6.51E-08 Xe-135 8.45E-08 Fe-55 8.00E-07 Sr-89 2.30E-08 Sr-90 7.67E-09 H-3 5.00E-07 l l l 4 l 21 L
2 GASE0US EFFLUENTS 2.1 REGULATORY LIMITS The Technical Specifications presented in this section are for Unit 1. Requirements for Unit 2 are the same as for Unit 1; however, the Technical Specification numbers are not the same. TECHNICAL SPECIFICATIONS 3.14.2 The radioactive gaseous effluent monitoring instrumentation channels shown in table 3.14.2-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.15.2.l(a) are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the ODCM. Technical Specification Table 3.14.2-1 is included in this section as Table 2-1.) 3.15.2.1 The dose rate at any time in the UNRESTRICTED AREAS (figure 3.15-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:
- a. The dose rate limit for noble gases shall be 500 mrem / year to the total body and 3000 mrem / year to the skin.
- b. The dose rate limit for I-131, I-133, tritium,'and for all radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than 8 days shall be 1500 mrem / year to any organ.
3.15.2.2 The air dose in UNRESTRICTED AREAS 3.15-1) due to noble gases released in gaseous (figure effluents from each reactor unit shall be limited to the following:
- a. During any calendar quarter, to 5 mrad for gamma radiation and 10 mrad for beta radiation.
- b. During any calendar year, to 10 mrad for gamma radiation and 20 mrad for beta radiation.
3.15.2.3 The dose to any organ of a MEMBER OF THE PUBLIC from I-131, 1-133, tritium , and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to UNRESTRICTED AREAS (figure 3.15-1) from each reactor unit shall be limited to the following: 22
- a. During any calendar quarter to any organ, 7.5 mrem to
- b. During any calendar year to organ. 15 mrem to any 3.15.2.4 The GASE0US RA0 WASTE TREATMENT SYSTEM as described in the ODCM shall be in operation. (This Technical Specification applies whenever the main condenser air ejector system is in operation.)
4.15.2.4 GASE0US RADWASTE TREATMENT SYSTEM operability shall be demonstrated by administrative controls which assure that the offgas treatment system is not bypassed. 3.15.2.5 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to 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 equal to 75 mrem. (With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.15.1.2(a), 3.15.1.2(b), 3.15.2.2.(a), 3.15.2.2(b), 3.15.2.3(a), or 3.15.2.3(b), calculations shall be made including ! direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of Specification 3.15.2.5 have been exceeded. 3.15.2.6 The concentration of hydrogen downstream of the recombiners in the main condenser offgas treatment system shall be limited to 4 percent by volume. 3.15.2.7 The gross gamma radioactivity rate of the noble gases Xe-133, Xe-135, Xe-138, Kr-85m, Kr-87, and Kr-88 measured at the main condenser evacuation system pretreatment monitor station shall be limited to 240,000 uti/second. 6.9.1.9 states in part:
"The Radioactive Effluent Release Report shall include (on a quarterly basis) unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid effluents that were in excess of I C1, excluding dissolved and entrained gases and tritium for liquid effluents, or those in excess of 150 Ci of noble gases or 0.02 Ci of radiolodines for gaseous releases."
23 i
m TABLE 3.14.2-1 (SitEET I 0F a) s RADIOACTIVE CASE 005 EFFLUENT MONITORING INSTRUMENTAYt0N Minimum ChanneIs I nst rieent OPERAntE Apoeicabi ity Pa rame te r ACTION 1 Main condenser orrgas Treatment System Emplosive Cas Monitoring System Hydrogen Monitor (1) ** 1 ttydrogen 106
- 2. Reactor Bui'J'ng Vent Stack Monitoring system
- a. nonne Cas Activity Manitor (1) * *-t Radioactivity Rate 105 >
Measurement +
- b. !E .
todine Saeeser Cartridge [1]
- Verify Presence of cus y 107 y r Cartridge -
- c. Particulate Sampler Filter (1) * "
Verify Preseme or 137 Tetter
- d. Effluent System flowrate Measurement Device (1)
- System Flowrate e
1 Gas Measurement
- e. Sampier F sowrate Measurement Ocwice (3)
- Sampler flowrate 104 Measurement
- 3. Recoah e ser Beas E d estg Vcast a la t ich ,
Puna torir.3 Systes
- a. achte Cas Activity leanitor (1)'
- Radioactivity Pate 105 Heasurement *
- n. scaine Sampler Cartrecse iII
- Verity Presen;e of 107 Cartridge
- c. Pa rt acu sa te Sa=c aer F ; s ter (13 *
\
* . Verity Presence or 107 Fester .
J. Lepier T sowrate reasucceent _ (1)
- Cew.ce Sampler T towrate 10!.
Measurement
. ~
- +- ..
l -
~ ~
l - _( TABLE 3.14.2-1 (SdEET 2 M 4} RaDtGacTtyf CASEOUS EFrtufigT MOssl'ORIssO INSTRLmtstTATions _ Minien-a . e ns t nent ChanoeIs OPfRABLE M *!uabilliv - Pa rmen ta r ACTtCM - - " 4 Main stack reanitoring system
- a. msnie cas Activity Monitor *
(11
- Radicactivity Rate 105
# Measurement +
- t. Iodine Sampler Cartridge (1)
- Yerify Presence or Ca rt riage 107 y
- c. Particulate Sampler fi t ter til
- ce Verify Presence or r=
107 " Filter
- d. EffIuent System FIowrate 64 He suring Devices a (1)
- Sjtten f lwrate
~
3 Dsa w Measse renca
- e. samp::r Flowrate Measaaring o Dev ece (1)
- Sampler f lowrate 3
- 5. Mea saaresco t 10%
- Coax:enser Crrgas Pretreatment c.
Mon s to r v hble cas Activ s ty Manitor (1) m Radioactivity Rate 103 Mea surement h e O N e
., , TABLE 2-1 (Cont'd) .
i . TABLE 3.14.2-1 (SHEET 3 0F 4) RADIOACTIVE GASEOUS ~ EFFLUENT MONITORING INSTRUMENTATION Table Notations ( t
+ Monitor must be capable of responding to a Lower Limit of Detection of 1 x 10-' pCi/ml.
"During releases via tofs pathway.
**During main condenser offgas treatment system operation.
***0uring operation of the main condenser air ejector.
ACTION 104 - With the number of channels OPERABLE less than
, required by the Minimum Channels OPERABLE requirement,
' effluent releases via this pathway may continue, provided the flowrate is estimated at least once per 4 hours.
-If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requireme'nt for over,30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.
[ ACTION 105 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided grab samples are taken daily and analyzed daily for gross activity within 24 hours. With the number of main stack monitoring system channels OPERA 8LE less than required by the Minimum Channels OPERABLE requirement, without delay suspend drywell purge.
- f If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.
ACTION 106 - With the number of channels OPERABLE less than ! required by the Minimum Channels OPERABLE requirement, operation of the main condenser offgas treatment system may l continue provided: [' (a) Gas samples are collected once per 4 hours and analyzed within the ensuing 4 hours, or (b) Using a temporary hydrogen analyzer installed in the offgas system line downs,tream. of the recombiner, hydrogen concentration readings are taken and logged every 4 hours. i ,7 26 i l
^
1
TABLE 2-1 (Cont'd) TABLE 3.14.2-1 (SHEET 4 0F 4) RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION Table Notations (Continued) If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement for
' over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.
ACTION 107 - With the number of channels OPERABLE less than ~ required by the Minimum Channels OPERA 8LE requirement, ( effluent releases via this pathway may continue, provided samples are continuously collected with auxiliary sampling eouipment for periods on the order of 7 days and analyzed within 48 hours after the end of the sampling period. If the number of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be - included in the next semi-annual effluent release report. ACTION 108 - With the number of channels OPERA 8LE less than required by the Minimum Channels OPERACLE requirement, release to the environment may continue for up to 72 hours provided: (
- a. The offgas system is not bypassed, and
- b. The offgas post-treatment monitor (011-K615) or the main stack monitor (011-K600) is OPERABLE. -
Otherwise, be in at least HOT STANOBY within 12 hours. If the n' umber of channels OPERABLE remains less than required by the Minimum Channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report. t 27
2 .~ 2 MEASUREMENT AND APPR0XIMATIONS OF TOTAL RADI0 ACTIVITY Waste gas release at Plant Hatch is confined to
~four paths: main stack (also called the offgas vent), Unit 1 reactor building vent; Unit 2 reactor building vent, and the recombiner building vent. Each of these four paths is continuously monitored for gaseous radioactivity. Each is equipped with an integrating-type sample collection device for-collecting particulates and iodines. Sample collection is in accordance with Technical Specification Tables 4.15.2-1 (Unit 1) and 4.11.~2-1 (Unit 2). Unless required more frequently under certain circumstances specified in Table Notations to the abovementioned tables, samples are collected as follows:
- 1. Noble gas samples are collected by grab 4
sampling monthly.
- 2. Tritium samples are collected by grab sampling monthly.
3 .- Radiciodine samples are collected by pulling the sample stream through a charcoal cartridge over a 7-day period.
- 4. Particulates are collected by pulling the sample stream through a particulate filter over a 7-day period.
- 5. The 7-day particulate filters above are analyzed for gross alpha activity.
- 6. Quarterly composite samples are prepared from the particulate filters collected over the previous quarter and the quarterly composite sample is analyzed for Sr-89 and Sr-90.
Sample analyses results and release flow rates from the four release points form the basis for calculating released quantities of radionuclide-specific radioactivity, dose rates associated with gaseous releases, and cumulative doses for the current quarter and year. This task is normally performed with computer assistance. 28
9 The noble gas grab sample analysis results are used along with maximum expected release flow rates from monitor each offorthe setpoints thefour vents to gaseous calculate effluent monitors serving the four release points, to assure that the limits of Technical Specifications 3.15.2.1.a (Unit 1) or 3.ll.2.1.a (Unit 2) are not exceeded. Calculation of monitor 00CM. setpoints is described in the Plant Hatch i With each release period released radioactivity, l' dose rates, and cumulative doses are calculated. Cumulative dose results are tabulated along with percent of Technical Specification limits ; 1 (3.15.2.2 and 3.15.2.3 (Unit 1); 3.11.2.2 and 3.11.2.3 (Unit 2) for each release, for the current quarter and year. I i l
) After each calendar quarter (13 weeks) a summary of waste gas releases from the four vents is i 4 compiled for preparation of the Semiannual Effluent Release Report required by Technical !
l Specifications 6.9.1.8 and 6.9.1.9 and described j in NRC Regulatory Guide 1.21. I ; The methods for determining released quantities of radioactivity, follows: dose rates and cumulative doses are as 6
- 1. FISSION AND ACTIVATION GAS The radionuclide-specific released radioactivity is determined from sample analyses results collected as described above and average release flow rates over the period represented by the collected sample.
Instantaneous dose rates due to noble gases and due to radiofodines, tritium, and particulates are calculated (with computer assistance). Calculated dose rates are compared to the dose rate limits specified in 3.15.2.1.a Unit 1) and 3.11.2.1.a (Unit 2) for noble gases;(and
- 3.15.2.1.b (Unit radiciodine, 1) and tritium, 3.ll.2.1.b (Unit 2) for and particulates.
Dose rate calculation methodology is presented in the Plant Hatch ODCM. 29
Beta and gamma air doses due to noble gases are calculated for the location in the unrestricted areatowith.the due gaseouspotential releases.for the highest exposure Air doses are calculated for each release period and cumulative totals are kept for each unit for the current calendar quarter and year. Cumulative air doses are compared to the dose limits specified in Technical Specifications 3.15.2.2 (Unit 1) and 3.-11.2.2 (Unit 2). Current percent of technical specification limits are shown on the printout j i for each release period. Air dose calculation ). methodology is presented in the Plant Hatch ODCM. I i 2. RAD 1010 DINE, TRITIUM, AND PARTICULATE RELEASES I ! Released quantities of radioiodines are determined from the weekly samples and release flow rates for the four release points. Radiciodine concentrations are determined by gamma spectroscopy. ) ) Released quantities of particulates are I. determined from the weekly (filter) samples and release flow rates for the four release points. Gamma spectroscopy is used to quantify concentrations of principal gamma emitters. After each calendar month the particulate filters from each vent are combined, fused, and strontium separation is performed. Since sample flows and vent flows are almost constant over each monthly period the filters from each vent can be dissolved together. Decay corrections are made back to the middle of the quarterly collection period. Where significant Sr-89 or Sr-90 is not detected,_LLD's are calculated. Strontium concentrations are input to the composite file of the computer to be used in release, dose rate and individual dose calculations. Tritium samples are obtained monthly from each vent by passing the sample stream from a cold trap immersed in liquid nitrogen or an acetone and ice mixture. The grams of water vapor / cubic foot gas is measured upstream of the cold trap in order to alleviate the difficulties in determining water vapor collection efficiencies. The tritium samples are analyzed by an independent laboratory and results are furnished in uCi/ml of water. The tritium concentration in water is converted to tritium concentration in air and this value is input into the composite file of the computer to be used in release, dose rate, and individual dose calculations. 30
1 Dose rates due to radioiodine, tritium, and particulates are calculated for a hypothetical child, exposed to the inhalation pathway, at the location in.the unrestricted area where the potential dose rate is expected to be the highest. Dose rates are calculated for each release point, for each release period, and the total dose rate from all four release points are compared to the dose rate limits specified in Technical Specifications 3.15.2.1.b (Unit 1) or l 3.11.2.1.b (Unit 2). Individual doses due to radiciodine, tritium, and 3-particulates are calculated for the critical receptor, which for Plant Hatch is an infant exposed to the g" ass-cow-milk, inhalation, and ground-plane pathways. Individual doses are i calculated for each release period and cumulative totals are kept for each unit for the current f calendar quarter and year. Cumulative individual ) doses are compared to the dose limits specified in Technical Specifications 3.15.2.3 (Unit 1) and 3.11.2.3 (Unit 2). Current percent of technical specification limits are shown on the printout for each release period.
- 3. GROSS ALPHA RELEASE 1
The gross alpha release is computed each month by counting the particulate filters each week for gross alpha activity in a proportional counter. The four or five weeks' numbers are then recorded on a data sheet and the activity is summed at the end of the month. This concentration is input to the composite file of the computer and is used for release calculations.
- 4. ERROR ESTIMATES Regulatory Guide 1.21 requires that estimated total error in analysis techniques be reported.
These estimates are required for the total fission and activation gas release, total I-131 release, total particulates with half-lives greater than 8-day release, and total tritium release. 31
"The total or maximum error associated with the offluent measurement will include the cumulative errors resulting from the total operation of sampling and measurement. Because it may be very difficult to assign error terms for each parameter affecting the final measurement, detailed suggested.statistical' evaluation of error are not The objective should be to obtain an I ) overall estimate of the error associated with
) measurements of radioactive materials released in ) liquid and gaseous effluents and solid waste." i Estimated errors are based on errors in counting equipment calibration, counting statistics, vent flow rates, vent sample flow rates, non-steady release rates, chemical yield factors, and sample losses for such items as charcoal cartridges. (1) Fission and Activation Total Release was calculated from sample analysis results and release point flow rates. Statistical Error 60% Counting Equipment Calibration 10% Vent Flow Rates 10% Non-Steady Release Rates 20% 1TT0Y (2) 1-131 Release was calculated from each weekly sample: Statistical Error 60% Counting Equipment Calibration 10% Vent Flow Rates 10% Vent Sample Flow Rates 10% Non-Steady Release Rates 10% Losses From Charcoal Cartridge 10% IT6% (3) Particulates with half-lives greater than 8 days release was calculated from sample analysis results and release point flow rates. Statistical Error at LLD concentration Counting Equipment Calbration 60% 10% Vent Flow Rates 10% Vent Sample Flow Rates 10% Non-Steady Release Rates 10% TUU% 32
4 l (4) Total' Tritium Release was dominated by the reactor building vent tritium release; hence, the larger statistical errors of the off-gas vent and recombiner building vent tritium releases do not affect the error in the total ~ tritium release: Water Vapor in Sample Stream Determination 20% Vent Flow Rates 10% i Counting Calibration and Statistics 10% Non-Steady Release 1 50% 1 3DY l f 2.3 GASE0US EFFLUENT RELEASE DATA Regulatory Guide 1.21 Tables lA, 18, and 1C are found } in this report as Tables 2-2a-c, 2-3a-c, and 2-4a-c. [ Data are presented Regulatory Guide 1.21. on a quarterly basis as required by To complete Tables 2-2a-c, total release for each of the four categories (fission and activation _ gases; iodines; particulates; and tritium) was divided by the number of seconds in the quarter to obtain a release rate in uCi/second for each category. However, the applicable Technical Specification limits are not terms of in terms dose rateofinrelease rate inasuCi/second mrem / year, presented inbut in Technical Specifications 3.15.2.1 3.11.2.1 (Unit 2). Noble gases are(Unit 1) and specified in 3.15.2.1.a and 3.ll.2.1.a. Theasother limited three categories (tritium, radiofodines and particulates) are limited as a group as,specified in 3.15.2.1.b and 3.ll.2.1.b. Further the limits specified in Technical Specifications 3.15.2.1 and 3.11.2.1 are site limits, not unit limits. Dose rates due to noble gas releases and due to radioiodine, tritium, and particulates are presented in Table 2-5 along with percent of technical specification limits. Gross alpha-radioactivity is reported in Tables 2-2a, 2-2b, and 2-2c as curies released in each quarter. Limits for cumulative beta and gamma air doses, due to noble gases, are specified in Technical Specifications 3.15.2.2 (Unit 1) and 3.11.2.2 (Unit 2). These limits are unit limits. Cumulative air doses are presented in Tables 2-6a and 2-6b, along with percent of technical specification limits. 33
rr v-Limits for cumulative individual doses, due to radioiodine, tritium, and particulates, are specified in Technical Specifications 3.15.2.3 (Unit 1) and 3.11.2.3 (Unit 2). These limits are also unit limits. Cumulative Tables 2-7a and 2-7b, individual doses are presented in specification limits, with percent of technical l' 2.4 RADIOLOGICAL IMPACT DUE TO GASEOUS RELEASES 1 I Dose rates due to noble gas releases were calculated i for the site in.accordance with Technical Specifications (Unit 2). Results3/4.15.2.1.a (Unit 1) and 3/4.ll.2.1.a j are presented in Table 2-5. Dose rates due to radiciodine tritium, and particulates in gaseous releases were ca,lculated in accordance with Technical Specifications 3/4.ll.2.1.b (Unit 2). 3/4.15.2.1.b (Unit 1) and i Table 2-5. These results are also in ) ) Cumulative air doses due to noble gas releases were calculated for each unit in accordance with Technical Specification 3/4.15.2.2 (Unit i 2). These results are presented 1) and 3/4.11.2.2 (Unit in Tables 2-6a and 2-6b. Cumulative doses to an individual due to radioiodine, tritium , unit and particulates were calculated for each in accordance with-Technical Specifications 3/4.15.2.3 results (Unit 1) and.3/4.ll are presented in Tables 2.32-7a(Unit 2). These and 2-7b. Dose rates and doses were calculated using the methodology presented in the Plant Hatch Offsite Dose Calculation Manual. 34
TABLE 2-2a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1986 GASE0US EFFLUENTS - SUMMATION OF ALL RELEASES .E. I. Hatch Unit Quarter Quarter Est. Total Nuclear Plant 3 4 Error % A. Fission & Activation Gases
- 1. Total Ci 1.69E+03 2.71E+03 1.00E+02 Release
- 2. Average uCi/sec 2.13E+02 3.43E+02 Release Rate For Period
*3. % of Tech %
Spec Limit B. Iodines
- 1. Total Ci 3.07E-03 3.55E-03 1.10E+02 lodine-131
- 2. Average uCi/sec 3.86E-04 4.47E-04 Release Rate For Period
*3. % of Tech %
Spec Limit C. Particulates
- 1. Particulates Ci 3.07E-03 3.90E-03 1.00E+02 with half-lives 8 days
- 2. Average uCi/sec 3.86E-04 4.91E-04 Release Rate For Period
- 3. % of Tech %
Spec Limit
- 4. Gross Alpha Ci 3.14E-06 1.63E-06 Radioactiv-ity D. Tritium
- 1. Total Ci 3.42E+00 3.31E+00 9.00E+01 Release
- 2. Average uCi/sec 4.30E-01 4.17E-01 Release Rate For Period
*3. % of Tech %
Spec Limit
- Technical Specification limits are in terms of dose rate (mrem /yr) and dose (mrem). See Tables 2-5, 2-6a, 2-66 2-7a, and 2-7b.
35.
TABLE 2-2b E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1986 GASE0US EFFLUENTS - SUMMATION OF ALL RELEASES E. I. Hatch Unit Quarter Quarter Est. Total Nuclear Plant 3 4 Error % A. Fission & Activation Gases
- 1. Total Ci 1.96E+03 1.64E+02 1.00E+02 Release
- 2. Average uCi/sec 2.47E+02 2.06E+01 Release Rate For Period
*3. % of Tech %
Spec Limit
- 8. Iodines
- 1. Total Ci 3.86E-03 8.05E-04 1.10E+02 Iodine-131
- 2. Average uCi/sec 4.86E-04 1.01E-04 Release Rate For Period
*3. % of Tech %
Spec Limit C. Particulates
- 1. Particulates Ci 6.65E-04 8.51E-05 1.00E+02 with half-lives 8 days
- 2. Average uCi/sec 8.37E-05 1.07E-05 Release Rate For Period
*3. % of Tech %
Spec Limit
- 4. Gross Alpha Ci 2.51E-06 9.21E-07 Radioactiv-ity D. Tritium
- 1. Total Ci 1.13E+01 3.72E+00 9.00E+01 Release
- 2. Average uCi/sec 1.42E+00 4.68E-01 Release Rate For Period
*3. % of Tech %
Spec Limit
- Technical Specification limits are in terms of dose rate (mrem /yr) and dose (mrem). See Tables 2-5, 2-6a, 2-6b, 2-7a, and 2-7b.
16
TABLE 2-2c E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADI0 ACTIVE EFFt.UENT RELEASE REPORT 1986 GASE0US EFFLUENTS - SUMMATION OF ALL RELEASES E. I. Hatch Unit Quarter Quarter Est. Total Nuclear Plant 3 4 Error % A. Fission & Activation Gases
- 1. Total Ci 3.65E+03 2.88E+03 1.00E+02 Release
- 2. Average uC1/sec 4.59E+02 3.64E+02 Release Rate For Period
*3. % of Tech %
Spec Limit B. Iodines
- 1. Total Ci 6.93E-03 4.35E-03 1.10E+02 Iodine-131
- 2. Average uCi/sec 8.72E-04 5.47E-04 Release Rate For Period
*3. % of Tech %
Spec Limit C. Particulates
- 1. Particulates Ci 3.73E-03 3.99E-03 1.00E+02 with half-lives 8 days
- 2. Average uCi/sec 4.69E-04 5.02E-04 Release Rate For Period
*3. % of Tech %
Spec Limit
- 4. Gross Alpha Ci 5.65E-06 2.55E-06 Radioactiv-ity D. Tritium
- 1. Total Ci 1.48E+01 7.03E+00 9.00E+01 Release
- 2. Average uCi/sec 1.86E+00 8.874-01 Release Rate For Period
*3. % of Tech %
Spec Limit
- Technical Specification limits are in terms of dose rate (mrem /yr) and dose (mrem). See Tables 2-5, 2-6a, 2-6b, 2-7a, and 2-7b.
37
TABLE 2-3a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1986 GASE0US EFFLUENTS - ELEVATED RELEASE
- Continuous Mode Batch Mode **
Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4
- 1. Fission
, Gases Kr-85 Ci 0.00E+00 0.00E+00 Kr-85m Ci 2.17E+01 1.07E+01 Kr-87 Ci 2.58E+01 0.00E+00 Kr-88 Ci 3.32E+01 2.34E+00 Xe-133 Ci 9.62E+02 1.17E+03
.Xe-135 Ci 1.94E+02 2.50E+02 Xe-135m Ci 1.27E+02 8.15E+01 Xe-138 Ci 5.96E+01 0.00E+00 Xe-131m Ci 4.04E+01 0.00E+00 Xe-133m Ci 1.55E+01 2.59E+01 Xe-137 Ci 0.00E+00 0.00E+00 Ar-41 Ci 8.53E-01 3.41E+00 TOT AL FOR PERIOD Ci 1.48E+03 1.54E+03
- 2. Iodines I-131 Ci 2.89E-03 1.12E-03 I-133 Ci 7.62E-04 4.03E-04 I-135 Ci 1.71E-04 8.15E-05 TOTAL FOR PERIOD Ci 3.82E-03 1.60E-03
- 3. Particu-lates Cr-51 Ci 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 0.00E+00 Zn-65 Ci 0.00E+00 0.00E+00 Sr-89 Ci 1.90E-04 4.04E-05 Sr-90 Ci 7.98E-07 0.00E+00 Nb-95 Ci 0.00E+00 0.00E+00 Cs-134 Ci 0.00E+00 0.00E+00 Cs-137 Ci 1.85E-07 5.43E-07 Ba-140 Ci 5.40E-06 3.71E-07 La-140 Ci 2.08E-06 2.40E-07 TOTAL FOR PERIOD Ci 1.98E-04 4.16E-05
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses.
**There are no batch mode radioactive gaseous release pathways at Plant Hatch.
38
TABLE 2-3b
-E. I.1 HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1986 GASE0US. EFFLUENTS - ELEVATED RELEASE
- Continuous Mode Batch Mode **
Nuclides Released Unit Quarter 3- Quarter 4 Quarter 3 Quarter 4 1-. -Fission Gases Kr-85 Ci '0.00E+00 '0.00E+00-Kr-85m Ci 2.23E+01 5.40E+00 Kr-87 C1 2.71E+01 0.00E+00 Kr-88 Ci 3.47E+01 0.00E+00 Xe-133 Ci .9.27E+02 2.62E+01 Xe-135 C1 1.93E+02 1.10E+00 Xe-135m Ci 1.12E+02 3.45E+00 Xe-138 Ci 5.96E+01- 0.00E+00 Xe-131m Ci 4.04E+01 0.00E+00 Xe-133m Ci 1.55E+01 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 Ar-41 Ci 8.53E-01 0.00E+00 TOTAL FOR PERIOD Ci 1.43E+03 3.62E+01
~2. Iodines I-131 Ci 1.99E 7.21E-05 I-133 Ci 7.26E-04 1.86E-05 I-135 Ci 1.71E-04 0.00E+00 TOTAL.FOR PERIOD Ci 2.89E-03 9.07E-05
- 3. Particu-lates Cr-51 Ci 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 0.00E+00 Zn-65 Ci 0.00E+00 0.00E+00 Sr-89 Ci 1.43E-04 5.51E-06
.Sr-90 Ci 6.02E-07 0.00E+00 Nb-95 Ci 0.00E+00 0.00E+00
-Cs-134 Ci 0.00E+00 0.00E+00 Cs-137 Ci 1.85E-07 5.43E-07 Ba-140 Ci 4.91E-06 0.00E+00 La-140 Ci 2.08E-06 0.00E+00 TOTAL FOR PERIOD Ci 1.51E-04 6.05E-06
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses.
**There are no batch mode radioactive gaseous release pathways at Plant Hatch. ,o
. TABLE 2-3c E. I. HATCH' NUCLEAR PLANT - SITE SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1986 GASEOUS EFFLUENTS - ELEVATED RELEASE
- Continuous Mode Batch Mode **
Nuclides l Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4
- 1. Fission Gases Kr-85 Ci 0.00E+00 0.00E+00 Kr-85m C1 4.40E+01 1.61E+01 Kr-87 Ci 5.29E+01 0.00E+00 Kr-88 Ci 6.79E+01 2.34E+00 Xe-133 Ci 1.89E+03 1.20E+03
-Xe-135 Ci 3.87E+02 2.51E+02 Xe-135m C1 2.39E+02 8.50E+01 Xe-138 Ci 1.19E+02 0.00E+00 Xe-131m Ci 8.08E+01 0.00E+00 Xe-133m Ci 3.10E+01 2.59E+01 Xe-137 Ci 0.00E+00 0.00E+00 Ar-41 Ci 1.71E+00 3.41E+00 TOTAL FOR.
PERIOD Ci 2.91E+03 1.58E+03
- 2. Iodines I-131 C1 4.88E-03 1.19E-03 I-133 C1 1.49E-03 4.22E-04 I-135 Ci 3.43E-04 8.15E-05 TOTAL FOR PERIOD Ci 6.71E-03 1.69E-03
- 3. Particu-lates Cr-51 Ci 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 Co-58 0.00E+00 Ci 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 0.00E+00 In-65 Ci 0.00E+00 0.00E+00 Sr-89 Ci 3.33E-04 4.59E-05 Sr-90 Ci 1.40E-06 0.00E+00 Nb-95 Ci 0.00E+00 0.00E+00 Cs-134 Ci 0.00E+00 0.00E+00 Cs-137 Ci 3.70E-07 1.09E-06 Ba-140 Ci 1.03E-05 3.71E-07 La-140 Ci 4.16E-06 2.40E-07 TOTAL FOR PERIOD Ci 3.49E-04 4.76E-05
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses.
- There Plant are no batch mode radioactive gaseous release pathways at Hatch. 40
~ TABLE 2-4a E..I. HATCH' NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT-1986 GASEOUS EFFLUENTS GROUNO-LEVEL RELEASES *
' Continuous Mode Batch Mode **
Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4
- 1. Fission Gases Kr-85 Ci 0.00E+00 0.00E+00 Kr-85m- Ci 0.00E+00 0.00E+00 Kr-87 Ci 0.00E+00 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 Xe-133 Ci 2.09E+02 1.02E+03-Xe-135 Ci 2.40E+00 1.47E+02 Xe-135m Ci 5.84E-01 1.17E+00 Xe-138 Ci 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 Xe-133m Ci- 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 Ar-41 Ci 0.00E+00- 0.00E+00 TOTAL FOR PERI 00 Ci 2.12E+02 1.17E+03
- 2. Iodines I-131 Ci 1.77E-04 2.43E-03 I-133 Ci 2.02E-04 1.05E-03 I-135 Ci 1.81E-05 2.46E-04 TOTAL FOR PERI 00 Ci 3.97E-04 3.73E-03
- 3. Particu-lates Cr-51 Ci 8.68E-04 1.31E-03 Mn-54 C1 2.41E-05 4.llE-05 Co-58 Ci 1.19E-04 1.49E-04 Co-60 Ci 1.92E-04 2.17E-04 Zn-65 Ci 1.41E-03 1.88E-03 Sr-89 Ci 2.39E-04 8.06E-05 Sr-90 Ci 0.00E+00 0.00E+00 Nb-95 Ci 0.00E+00 0.00E+00 Cs-134 Ci 0.00E+00 6.58E-05 Cs-137 Ci 1.71E-05 1.13E-04 Ba-140 Ci 0.00E+00 0.00E+00 La-140 Ci 0.00E+00 6.80E-06 TOT AL FOR PERI 00 Ci 2.87E-03 3.86E-03
- Zeroes in this table indicate that no radioactivity was present above. detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses.
**There are no batch mode radioactive gaseous release pathways at Plant Hatch.
41
TABLE 2-4b E. I. HATCH NUCLEAR PLANT - UNIT 2-SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1986 GASE0US EFFLUENTS - GROUND-LEVEL RELEASES
- Continuous Mode Batch Mode **
Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4
- 1. Fission-Gases Kr-85 Ci 0.00E+00 0.00E+00 Kr-85m Ci 0.00E+00 0.00E+00 Kr-87 Ci 0.00E+00 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 Xe-133 Ci 4.52E+02 1.28E+02 Xe-135 C1 7.84E+01 0.00E+00 Xe-135m Ci 0.00E+00 0.00E+00 Xe-138 Ci 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 Xe-133m Ci 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 Ar-41 Ci 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 5.30E+02 1.28E+02
-2. Iodines I-131 Ci 1.87E-03 7.33E-04 I-133 Ci 1.19E-03 3.95E-05 I-135 Ci 2.36E-04 0.00E+00 TOTAL FOR PERIOD Ci 3.30E-03 7.73E-04
- 3. Particu-lates Cr-51 Ci 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+00 Co-58 Ci 0.00E+00 0.00E+00 Co-60 Ci 0.00E+00 0.00E+00 Zn-65 Ci 0.00E+00 0.00E+00 Sr-89 Ci 5.13E-04 7.68E-05 Sr-90 Ci 0.00E+00 0.00E+00 Nb-95 Ci 0.00E+00 0.00E+00 Cs-134 Ci 0.00E+00 0.00E+00 Cs-137 Ci 8.31E-07 2.20E-06 Ba-140 Ci 0.00E+00 0.00E+00 La-140 Ci 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 5.14E-04 7.90E-05
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses.
- There are no batch mode radioactive gaseous release pathways at Plant Hatch.
42
x-q TABLE 2-4c E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1986 GASE0US EFFLUENTS - GROUND-LEVEL RELEASES
- Continuous Mode Batch Mode **
Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4
- 1. Fission Gases-Kr-85 Ci 0.00E+00 0.00E+00 Kr-85m Ci 0.00E+00 0.00E+00 Kr-87 Ci 0.00E+00 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+00 Xe-133 Ci 6.61E+02 1.15E+03 Xe-135 Ci 8.08E+01 1.47E+02 Xe-135m Ci 5.84E-01 1.17E+00 Xe-138 Ci 0.00E+00 0.00E+00 Xe-131m Ci 0.00E+00 0.00E+00 Xe-133m Ci 0.00E+00 0.00E+00 Xe-137 Ci 0.00E+00 0.00E+00 Ar-41 Ci 0.00E+00 0.00E+00 TOTAL FOR PERIOD Ci 7.42E+02 1.30E+03
- 2. Iodines I-131 Ci 2.05E-03 3.16E-03 I-133 Ci 1.39E-03 1.09E-03 I-135 Ci 2.54E-04 2.46E-04 TOTAL FOR PERIOD Ci 3.69E-03 4.50E-03
- 3. Particu-lates Cr-51 Ci 8.68E-04 1.31E-03 Mn-54 Ci 2.41E-05 4.llE-05 Co-58 Ci 1.19E-04 1.49E-04 Co-60 Ci 1.92E-04 2.17E-04 Zn-65 Ci 1.41E-03 1.88E-03 Sr-89 Ci 7.52E-04 1.57E-04 Sr-90 Ci 0.00E+00 0.00E+00 Nb-95 Ci 0.00E+00 0.00E+00 Cs-134 Ci 0.00E+00 6.58E-05 Cs-137 Ci 1.79E-05 1.15E-04 Ba-140 Ci 0.00E+00 0.00E+00 La-140 Ci 0.00E+00 6.80E-06 TOTAL FOR PERIOD Ci 3.38E-03 3.94E-03
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses.
**There are no batch mode radioactive gaseous release pathways at Plant Hatch.
43
. TABLE 2-5 E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL PADI0 ACTIVE EFFLUENT RELEASE REPORT 1986 GASE00S' EFFLUENTS - DOSE RATES Dose Rates Due to Noble Gases Organ Tech Unit Quarter % of Quarter % of Spec 3 Tech 4 Tech Limit Spec Spec Limit Limit Totall 500 mrem /yr 3.26E-01 6.52E-02 5.28E-01 1.06E-01 Body Skin 3000 mrem /yr 7.42E-01 2.47E-02 1.21E+00 4.03E-02 A
Dose Rates Due to Radiciodine, Tritium, and Particulates Organ Tech Unit Quarter % of Quarter % of Spec 3 Tech 4 Tech Limit Spec Spec Limit Limit i Bone 1500 mrem /yr 5.58E-04 3.72E-05 4.21E-04 2.81E-05 Liver 1500 mrem /yr 1.40E-02 9.33E-01 7.01E-03 4.67E-04 4 Total 1500 mrem /yr Body 1.39E-02 9.27E-04 6.76E-03 4.51E-04 i Thyroid 1500 mrem /yr 4.79E-02 3.19E-03 5.43E-02 3.62E-03 l- Kidney- 1500 mrem /yr 1.40E-02 9.33E-04 6.94E-03 4.63E-04 Lung 1500 mrem /yr 1.77E-02 1.18E-03 9.97E-03 6.65E-04 GI-LLI 1500 mrem /yr 1.39E-02 9.27E-04 6.63E-03 4.42E-04 J i s f 44
TABLE 2-6a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1986 AIR DOSES DUE TO NOBLE GAS RELEASES i Cumulative Doses Per Quarter
' Type Tech Unit Quarter % of Quarter % of of Spec 3 Tech 4 . Tech i Radi- Limit Spec Spec
- 1. ation Limit Limit Gamma 5.0 mrad 2.16E-02 4.32E-01 1.41E-01 2.83E+00 Beta 10.0 mrad 5.61E-02 5.61E-01 3.15E-01 3.15E+00
.I i
.; Cumulative Doses Per Year Type of Tech Unit Quarters % of Tech Radiation Spec 1,2,3 & 4 Spec Limit Limit 1 Gamma 10.0 mrad 4.35E-01 4.35E+00 Beta 20.0 mrad 1.36E+00 6.80E+00 il 1
,1 il t
4 , i i l t 1 i l l 45 l l
TABLE 2-6b E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1986 AIR DOSES DUE TO N0BLE GAS RELEASES Cumulative Doses Per Quarter Type Tech Unit Quarter of Spec
% of -Quarter % of 3 Tech 4 Tech Radi- Limit. Spec Spec ation Limit Limit Gamma 5.0 mrad 7.llE-02 1.42E+00 9.79E-03 Beta 10.0 1.96E-01 mrad 1.51E-01 1.51E+00 2.91E-02 2.91E-01 Cumulative Doses Per Year Type of Tech Unit Quarters Radiation Spec % of Tech 1,2,3 & 4 Spec Limit Limit Gamma 10.0 mrad 3.40E-01 3.40E+00 Beta 20.0 mrad 8.00E-01 4.00E+00 l
4 e i 1 46
1 TABLE 2-7a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMI ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1986 INDIVIDUAL DOSES DUE TO RADI0 IODINE, TRITIUM, AND PARTICULATES IN GASE0US RELEASES Cumulative Dose Per Quarter Organ Tech Unit Quarter % of Spec Quarter % of 3 Tech 4 Tech Limit Spec Spec Limit Limit Bone 7.5 mrem 1.17E-03 1.56E-02 1.97E-03 Liver 7.5 mrem 2.44E-03 2.63E-02 Tot. Body 3.25E-02 4.05E-03 5.40E-02 7.5 mrem 1.38E-03 1.84E-02 1.96E-03 Thyroid 7.5 mrem 7.88E-02 2.61E-02 Kidney 1.05E+00 1.82E-01 2.43E+00 7.5 mrem 1.60E-03 2.13E-02 2.52E-03 Lung 7.5 mrem 5.69E-04 3.36E-02 GI-LLI 7.59E-03 7.56E-04 1.01E-02 7.5 mrem 1.90E-03 2.53E-02 2.51E-03 3.35E-02 , Cumulative Dose Per Year
! Organ Tech Unit Quarters % of Tech Spec 1,2,3 & 4 Spec Limit -
Limit Bone 15.0 mrem Liver 4.01E-03 2.67E-02 15.0 mrem 7.69E-03 Total Body 15.0 5.13E-02 mrem 4.01E-03 2.67E-02 Thyroid 15.0 mrem Kidney 2.85E-01 1.90E+00 15.0 mrem 4.92E-03 Lung 15.0 3.40E-02 mrem 1.89E-03 1.26E-02 GI-LLI 15.0 mrem 5.10E-03 3.40E-02 l 47 {
TABLE 2-7b E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1986 INDIVIDUAL DOSES DUE TO RADI0 IODINE, TRITIUM, AND-PARTICULATES IN GASEOUS RELEASES Cumulative Dose Per Quarter Organ Tech Unit Quarter % of Spec 3 Quarter % of Tech 4 Tech limit Spec Spec Limit Limit Bone 7.5 mrem 8.75E-04 1.17E-02 1.95E-04 2.60E-03 Liver 7.5 mrem 1.17E-03 Tot. Body 7.5 1.56E-02. 3.76E-04 5.01E-03 mrem 8.91E-04 1.19E-02 2.87E-04 3.83E-03 Thyroid 7.5 mrem 1.67E-01 2.23E+00 Kidney 7.5 mrem 4.87E-02 6.49E-01 1.25E-03 1.67E-02 3.94E-04 5.25E-03
-Lung 7.5 mrem 6.76E-04 GI-LLI 7.5 9.01E-03 2.24E-04 2.99E-03 mrem 6.83E-04 9.llE-03 2.26E-04 3.01E-03 Cumulative Dose Per Year Organ Tech Unit Spec Quarters. % of Tech 1,2,3 & 4 Spec Limit Limit Bone 15.0 mrem Liver 2.58E-03 1.72E-02 15.0 mrem 3.13E-03 Total Body 15.0 mrem 2.09E-02 Thyroid 2.15E-03 1.43E-02 15.0 mrem 5.77E-01 Kidney 15.0 3.85E+00 mrem 3.40E-03 2.27E-02 Lung 15.0 mrem 1.40E-03 9.33E-03 GI-LLI 15.0 mrem 1.43E-03 9.53E-03 1
1 48
TABLE 2-8 LOWER LIMITS OF DETECTION - GASEOUS SAMPLE ANALYSES detection The values in this table represent aprio'ri lower limits of of gaseous radwaste (LLD) which are typically achieved in laboratory analyses samples. RADIONUCLIDE LLD UNITS Kr-87 1.31E-07 uC1/ml Kr-88 2.10E-07 Xe-133 1.62E-07 4 Xe-133m 6.07E-08 Xe-135 5.77E-08 Xe-138 2.85E-06 I-131 4.37E-14 I-133 6.16E-13 Mn-54 2.78E-14 Fe-59 4.62E-14 Co-58 2.46E-14 Co-60 2.88E-14 Zn-65 7.51E-14 Mo-99 6.02E-13 Cs-134 3.64E-14 Cs-137 2.88E-14 Ce-141 4.94E-14 Ce-144 2.02E-13 Sr-89 1.17E-14 Sr-90 3.82E-15 , H-3 5.82E-12 a 1 a 6 49
- 3. SOLID WASTE 3.1 REGULATORY REQUIREMENTS The Technical Specifications presented in this section are for Unit 1. Requirements for Unit 2 are the same as for Unit 1; however, the Technical Specification numbers are not the same.
TECHNICAL SPECIFICATIONS 3.15.3.1 The solid radwaste system shall be used in accordance with the PROCESS CONTROL PROGRAM to provide for the SOLIDIFICATION of wet solid wastes and for the SOLIDIFICATION and packaging of other radioactive wastes, as required, to ensure the meeting of the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the site. 6.9.1.9 states in part: The Radioactive Effluent Release Report shall include the following information for each type of solid waste shipped offsite during the report period:
- a. Container volume
- b. Total curie quantity (specify whether determined by measurement or estimate)
- c. Principal radionuclides (specify whether determined by measurement or estimate)
- d. Type of waste, e.g., spent resin, compacted dry waste, evaporator bottoms
- e. Type of container, e.g., LSA, type A, type B, large quantity
- f. Solidification agent, e.g., cement.
3.2 SOLID WASTE DATA Regulatory guide 1.21 Table 3 is found in this report as Table 3-1a. and 3-lb. 50
TABLE 3-la EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) July - December,1986 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNIT I & II SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) j l l 1 I l l 1. Type of waste l UNIT l 6 month lEst. Totall l I I Deriod 1 ERROR % l l a. Spent resins, filter studges, evaporator l m3 1 7. 1 6 21 l l bottoms. etc. I C1 1 1. 6qE +71
- 1. n E +1 l l b. Dry compressible waste, contaminated l m3 1 4. 22E +2l l l eaulo, etc. Ci I
l A.nsf+nl 7.n E +1 l l c. Irradiated components, control rods, l m3 I n. E n l l etc. I Ci n. E a E l l d. Other (describe) ' m3 n. E In l l eaulo. etc. Ci n. E Ia E l
- 2. Estimate of major nuclide composition (by type of waste) l ISOTOPE l PERCENT l CURIES l 1 1 I l l a. 7n-66 -
l 74 14 l 107 aQ l l Cs-117 l 17 aQ l 6a aQ l l Co-60 l 11 66 l En 17 l
~
l All others l 14 70 I la6 1A l l b. 7n l Ra 9.7 I a 7A l l Co-60 l ?A 76 1 7 11 l l Cs-137 1 7 ?? I n 6A l l All Others 1 4.66 1 0.7A l l c. I I l l l 1 I l l 1 l l l 1 - l l d. I I l l I I l l 1 I l l l l l l l I 1
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 18 Van Barnwell 38 Cask Barnwell
- 4. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transportation Destination 0 n/a n/a 51
s EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) I?C6 SOLID WASTE AND IRRADIATED FUEL SilIPMENT ' FDR UNIT I AND II , TABLE 3-lb JULY---DECEMBER 1984 CURIE ' PRINCIPLE BURIAL, NUM8ER OF VOLUME OF TYPE QUANilTY / NUCLIDES / CONTA!MER CONTAINERS EACH CONTAINER SHIPP!N6 TYPE OF NASTE DETERMINED DETERMINAi!0N DESCRIFi!GN SHIPPED CUBIC FEET Ht3) CONTAINER ,
; CEWATERED 125.664 ZN-65,C0-60,MN-54, CARBON SiiEL'* .i 206 LSA FESIN MEASURED CS-134,CS-137 LINER TYPE A MEASURED
( DEWATERED 1.67 ZN-65,CO-60,M-54, CARBON S!fEL i 199 LSA . FESIN MEASURED CS-134,CS-137 LINER ' TYFE A MEASURED DEWATEFED 135.63 lN-65,CO-60,MN-54, HISH RES!N MEASURED CS-134,CS-137 INTEGRITV 7 193 LSA MEASURED CONTAINER IVPE A DEWATERED 99.74 IN-65,CO-60,M-54, HIGH RESIN MEASURED CS-134,CS-137 INTEGRITY 2 119 LSA MEASURED CONTAINER itPE B COMPACTED 7.54 IN-65,C0-60,MN-54 B-25 50! DR) ACTIVE ESilMATED CS-134,CS-137 STEEL 145 93.78 LSA WASTE MEASURED ' STFON6 IldHT CDNTAlkER COMFACTED 0.51 IN-65,C0-60,M-54, 3-25 OVER-PACK 10- 132 LSA ' DRYACTIVE ESTIMATED CS-134,CS-137 BOI STEEL STRON6 ilGHT WASTE MEASURED CONTAINER
- AVERAGE FT3 DUE TO BUL61NG BOIES FROM NEN COMPACTOR
<r n
0 52 J A
- 4. CHANGES IN.TH.S RADIOL'0GICAL-ENVIRONIENTAL MONITORING PROGR
- L m.
Technical Specification 3.16.1.c requires in part that in thi~ event environmental samples become unavailable,
- the cause of the unavailability and identification of the affected. locations and the locations (if any) for obtaining replacement samples shall be submitted to
- the Commission
. effluent in the next semi-annual radioactive release report. Technical Specification 3.16.1.c further states that the locations from which samples become unavailable may be deleted from the radiological environmental monitoring program.
During the latter half of 1986, milk samples became
-a navailable at two locations which were used fr. the
" radiological environmental monitoring program. These locations, Johnson Brothers Dairy which is 9.1 miles SW of the plant and Williamson's farm wnich is 3.2 miles NNE of the plant, were deleted from the program.
The cause of the unavailabi'lity of milk . samples at each animals.of these locationi is the removal 6f the milk Johnson Brothers Dairy went out of business and disbanded their dairy, operations. For personal
,, - tj reasons, the Williamsons sold all of their milk cows.
Efforts were made to find r.uitable replacement milk sampling locations by contacting the County Extension Agents of five surrounding counties. Each agent was asked to identify all operating dairies in his county (,', and also any individuals with milk animals in the vicin.ity of Plant Hatch. None of the agents knew of any individuals vith cows or goats being milked for human consudption. Thompson's Dalry, which is located approximately 13.2 miles NNE of the plant, was
- identifled by the Toombs County Extension Agent and this location has been added-to the program.
r V 4 l
/
t s 4 6
, - $1 i _
.l. . >
m ., i
- 5. METEOROLOGY In accordance with Technical Specification 6.9.1.9, i
the annual summary of meteorological data collected at Plant Hatch over 1986 is presented in this section. 5.1 REVIEW 0F 1986 DATA 1 1986 was the third year of meteorological data , collection on the 100m meteorological tower. During the year there were some problems with the temperature (ambient and dew point) and delta temperatures-(100m I and 60m) on the primary tower. The largest section of missing data, which occurs in April and May, was due to a chart drive malfunction. Data was supplemented from the backup tower for the ambient temperature and 60m delta temperature to increase the percentage of , data collection. Including the data from the backup tower, the average data collection recovery for all
' parameters was about 93% and for pertinent parameters
+
of wind speed, direction, and delta temperature about 92%. e The ambient temperature and dew point temperature for j the year compared favorably with previous years. The most noticeable difference is the July ambient temperatures (Attachment 5-7) that are somewhat higher than previous years. This is consistent with temperatures in the southeastern United States during the July of 1986. The wind roses from 10m, 60m, and 100m agree quite well. between levels and when compared to previous years. The peak wind directions for the year were
'from the northeast and from the southwest. There is some shifting'in wind direction from the 10m to the 100m level as the directions show somewhat of a more westerly component. See Attachment 5-4, 5-5, and 5-6 for seasonal and annual wind roses.
Joint frequency tables of wind need and direction versus delta temperature are M.: wn in Attachemnts 1 through 3. The data for W 1a t 5 years is summarized in the table b}w This table shows that for the last 3 years or. Eae .c 100m tower, the stability groups agree closely. As has occurred on the new tower.for each year,-there were less unstable hours and more neutral hours during 1986. As discussed in previous summaries this is caused by the L2ight of the new tower 10m (197 ft) versus the old or ' backup tower 45m (148 ft). Therefore, the normalization to F/100 ft or C/100m occurs over a greater height causing more neutral type conditions. The following table shows the latest 5-year stability classifications. 54
i
.The following table shows the latest 5 year stability classification.
Plant Hatch Stab'ility Classification Stability Percent Stability Group 1986 1985 1984 1983 1982 - ear Average A 7.8 9.3 8.4 14.7 16.7 11.4 B .3.5 4.7 5.2 5.2 3.8 4.4 C 3.0 5.5 5.8 3.8 2.3 4.5 D 21.4 26.5 19.9 21.9 20.8 22.1 E 37.6 31.8 31.8 33.8 34.3 33.8 F 13.7 11.3 12.4 11.3 14.8 12.7 G 11.0 10.9 16.5 9.3 7.8 11.1 Total Hours 8037 7860 7928 7468 7725 The total of the year was 37.88 inches which is nearer the area average of about 45 inches. The daily. totals were as expected considering the drought conditions with the first half of the year being very dry with only about 9.5 inches of rain. l l c 55
METEOROLOGICAL DATA ATTACHMENTS Attachment 5 Joint Frequency Tables of Wind Speed and Wind Direction 10m vs. Delta Temperature 60-10m. Attachment 5 Joint Frequency Tables of Wind Speed and Wind Direction 60m vs. Delta Temperature 60-10m.
) Attachment 5 Joint Frequency Tables of Wind Speed and Wind ) Direction 100m vs. Delta Temperature 100-10m.
Attachment 5 Wind Roses from 10m (seasonal and annual). Attachment 5 Wind Roses from 60m (seasonal and annual). l Attachment 5 Wind Roses from 100m (seasonal and annual). Attachment 5 Plots of Monthly Averages and Averages of Daily Extremes of Ambient Temperature and Dew Point Temperature. Attachment 5 Monthly and Annual Precipitation for 1986. Attachment 5 Daily Precipitation for the Period of January through December 1986. S t.
ATTACHMENT 5-1 Plant Hatch Joint Frequency Tables of Wind Speed and Wind Direction 10m versus Delta Temperature 60-10m 1/1/86 - 12/31/86 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010181-86123124 STABILITY CLASS: A DT/DZ ELEVATION: SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60 UTND SPEED (MPH) DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL i N O 23 3 0 0 0 26 NNE 1 20 5 0 0 0 26 NE 1 32 10 0 0 0 43 ENE 1 17 5 0 0 0 23 E O 7 1 0 0 0 8
- ESE 2 9 2 0 0 0 13 SE 1 20 4 0 0 0 25 SSE 4 20 5 0 0 0 29 S 2 25 9 2 0 0 38 SSU 2 26 10 0 0 0 38 SU 0 42 24 0 0 0 66 USU 0 72 32 0 0 0 104 U 1 39 27 0 0 0 67
.UNU 1 30 30 1 0 0 62 , NU 2 21 14 2 0 0 39 i NNU 1 11 6 0 0 0 18 i ______________________________________________________________ - TOTAL 19 414 187 5 0 0 625 PERIODS OF CALM (HOURS): 0 UARIABLE DIRECTION O HOURS OF MISSING DATA: 723 i
57
1 l l l i f ATTACHMENT 5-la
] +
i j HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010101-86123124 STABILITY CLASS: B DT/DZ ELEVATION: SPEED:SPD10M DIRECTION:DIR10M LAP __________________________________________________SE:DT60 ______________ UIND SPEED (MPH) UIND DIRECTION'- 1-3 4-7 8-12 13-18 19-24
>24 TOTAL
-N 6 3 i
1 0 0 0 10 NNE O 15 0 ! ' 1 0 0 16 NE 2 18 5 0 0 0 25 ENE 2 6 f 1 0 0 0 9 E O 4 1 0 0 0 5 ESE 7 1 1 0 0 0 9 SE 3 15 2 0 0 0 20 SSE 1 14 4 0 0 0 19 S 2 8 4 2 0 0 16 SSU 1 22 4 0 0 0 27 SU 1 19 4 1 0 0 25 USU 1 17 5 0 0 U 0 23 2 10 6 0 0 0 UNU 18 4 19 2 0 0 0 NU 25 1 12 8 0 0 0 21 NNU 1 9 2 0 0 0 12 TOTAL 23 201 53 3 0 0 280 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 723 58
1 ATTACHMENT 5_lb HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010181-86123124 STABILITY CLASS: C DT/DZ ELEVATION: SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60 UIND SPEED (MPH) i UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 13 0 0 1 0 14 NNE 3 18 1 0 0 0 22 NE 5 25 3 0 0 0 33 ENE 2 18 0 0 0 0 20 l E 3 5 0 0 0 0 8 ESE 1 9 1 0 0 0 11 SE 1 19 2 0 0 0 22 SSE 2 11 7 0 0 0 20 S 5 13 8 0 1 0 27 SSU 4 23 7 0 0 0 34 SU 1 24 5 0 0 1 31 USU 1 26 6 0 0 0 33 U 2 30 8 0 0 0 40 UNU 3 23 9 0 0 0 35 NU 0 19 4 0 0 3 23 NNU 3 26 2 0 0 0 31 TOTAL 36 302 64 2 0 0 404 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 723 59
1 ATTACHMENT 5-ic I HOURS AT EACH UIND SPEED AND DIRECTION j PERIOD OF RECORD = 86010101-86123124 STABILITY CLASS: D DT/DZ F ELEVATION: SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60 I UIND SPEED (MPH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N 8 54 8 0 0 0 70 NNE 25 75 2 0 0 0 102 NE 19 146 17 0 0 0 182 ENE 25 50 3 0 0 0 78 E 12 29 4 0 0 0 45 ESE 21 35 0 0 1 0 57 SE 15 57 11 0 1 0 84 r SSE 13 53 17 0 1 0 84 S 16 82 22 1 0 0 121 SSU 23 77 28 0 1 0 129 SU 26 94 16 0 1 0 137 USU 22 88 15 0 1 0 126 U 18 99 14 4 0 0 135 UNU 22 64 11 3 0 0 100 NU 29 96 17 0 0 0 142 NNU 13 101 11 0 0 0 125 TOTAL 307 1200 197 13 0 0 1717 PERIODS OF CALM (HOURS): 0 I UARIABLE DIRECTION O HOURS OF MISSING DATA: 723 l
l I. 60
ATTACHMENT 5-ld HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF' RECORD = 86010181-86123124 STABILITY CLASS: E DT/DZ ELEVATION: SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60 WIND SPEED (MPH)
.UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 28 58 4 0 0 0 90 NNE 41 98 13 0 0 0 152 NE. 80 213 26 0 0 0 319 ENE. 78 74 4 0 0 0 156 E 63 38 4 0 0 0 105 ESE 89 73 2 0 0 0 164 SE 88 141 22 0 0 0 251 SSE 68 140 19 0 0 0 227
.S 78 131 13 0 0 0 222 SSU 94 194 22 3 0 0 313 SU 82 171 16 0 0 0 269
-USU 52 61 5 1 0 0 119 U 65 64 6 0 0 0 135 UtlU 42 93 22 1 0 0 158 NU 49 119 29 0 0 0 197 NNU- 31 93 19 0 0 0 143 TOTAL 1028 1761 226 5 0 0 3020 PERIODS OF CALM (HOURS): 0 UARIABLE DIRECTION O l
4 HOURS OF MISSING DATA: 723 b 1 I e I i 61 4 4 rv, - - - ,- -,w-w-- ==~, ,ww .--e= -.'.--+-e-,--wrm-,--.,.v--n,----w .---y-v-ww---,r-y,-w-------y,-+--
ATTACHMENT 5-le-HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010101-86123124 STABILITY CLASS: F DT/DZ
., ELEVATION: SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60 UIND SPEED (MPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL
, N 10 16 0 0 1 0 27 NNE 23 14 0 0 0 0 37 NE 63 38 2 0 0 0 103 ENE 51 9 0 0 0 0 60 '
E 47 8 0 0 0 0 55 ESE 41 18 0 0 0 0
' 59 SE 45 14 0 0 1 0 60 SSE 48 33 0 0 0 0 81 S 55 39 1 1 0 0 96 SSU 81 60 2 0 0 0 143 SU S7 38 0 0 0 0 95 USU 67 25 0 0 0 0 92 U 36 22 0 0 0 0 58 UNU 23 16 0 0 0 0 39 NU 22 40 3 0 0 0 65 i NNU 15 14 3 0 0 0 32 TOTAL 684 404 13 0 0 1 1102 j PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O
HOURS OF MISSING DATA: 723 62
.c ATTACHMENT 5-1f
' HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010181-86123124 STABILITY CLASS:- G DT/DZ ELEVATION: SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60 UIND SPEED (MPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 17 2 0 0 0 0 19 NNE 15 6 0 0 0 0 21 NE 24 2 0 0 0 0 26 ENE 31 3 0 0 0 0 34 E 35 4 0 0 0 0 39 ESE 29 3 1 0 0 0 33 SE 31 2 0 0 0- 0 33 SSE 37 9' O O O O 46 S 91 17 0 0 0 1 109 SSU 101 24 0 0 0 0 125 SU 115 10 0 0 0 0 125 USU 81 15 3 0 0 0 96 U 59 15 0 0 0 0 74 UNU 29 6 0 0 0 0 35 NU 25- 10 0 0 0 0 35 NNU 34 5 0 0 0 0 39 TOTAL 754 133 2 0 0 0 889 PERIODS OF CALM (HOURS): 0 UARIABLE DIRECTION O HOURS OF MISSING DATA: 723 63
ATTACHMENT 5-1g HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010181-86123124 STABILITY CLASS: ALL DT/DZ ELEVATION: SPEED:SPD10M DIRECTION:DIR10M LAPSE:DT60 UIND SPEED (MPH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 64 172 20 0 0 0 256 NNE 108 246 22 0 0 0 376 NE 194 474 63 0 0 0 731 ENE 190 177 13 0 0 0 380 E 160 95 10 0 0 0 265 ESE 184 154 8 0 0 0 346 SE 184 268 42 1 0 0 495 SSE 173 280 52 1 0 0 506 S 249 315 58 7 0 0 629 SSU 306 426 73 4 0 0 809 SU 282 398 65 3 0 0 748 USU 224 304 63 2 0 0 593 U 183 279 61 4 0 0 527 UNU 124 251 74 5 0 0 454 NU 128 317 75 2 0 0 522 NNU 98 259 43 0 0 0 400 TOTAL 2851 4415 742 29 0 0 8037 PERIODS OF CALM (HOURS): 0 UARIABLE DIRECTION 0 HOURS OF MISSING DATA: 723 64
ATTACHMENT 5-2 Plant Hatch Joint frequency-Tables of Wind Speed and Wind Direction 60m versus Delta Temperature 60-10m 1/1/86 - 12/31/86 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010181-86123124 STABILITY CLASS: A DT/DZ UIND SPEED (MPH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 0 N 1 6 13 1 0 0 21 NtlE O 5 13 5 0 0 23 NE O 12 27 10 0 0 49 ENE O 13 11 2 0 0 26 E 1 3 8 2 0 0 14 ESE 1 6 4 0 0 0 11 SE 1 9 10 2 0 0 22 SSE O 5 14 4 0 0 23 S 1 10 10 1 0 0 22 SSU 0 6 16 9 2 0 33 SU 0 22 31 16 4 0 73 USU 0 16 50 19 1 0 86 U 1 12 49 43 1 0 106 UNU 0 7 31 16 2 0 56 flu O 13 17 9 2 0 41 titiu O 1 8 0 0 0 9 TOTAL 6 146 312 139 12 0 615 PERIDOS OF CALM (HOURS): 0 UARIABLE DIRECTI0tl 0 HOURS OF MISSING DATA: 904 65
ATTACHMENT 5-2a HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010181-86123124 STABILITY CLASS: B DT/DZ UIND SPEED (MPH) UIND t DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 5 1 2 0 0 8 tlNE O 1 4 1 0 0 6 tlE O 8 14 4 0 0 26 ENE O 6 10 2 0 0 18 E 1 3 5 0 0 1 10 ESE O 6 4 0 0 0 10 SE O 9 11 1 0 0 21 SSE 2 3 6 1 0 0 12 S 0 6 4 2 0 1 13 SSU 0 4 10 0 1 0 15 SU 0 8 17 3 0 1 29 USU 0 7 21 6 1 0 35 U 1 7 16 4 0 0 28 UNU 0 6 7 3 1 0 17 flu O 9 4 4 0 0 17 tlNU 1 6 3 0 0 0 10 TOTAL 5 94 137 34 4 1 275 PERIODS OF CALM (HOURS): 0 UARIABLE DIRECTI0tl 0 HOURS OF MISSING DATA: 904 66
r ATTACHMENT 5-2b i HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010101-86123124 STABILITY-CLASS: C DT/DZ UIND SPEED (MPH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 7 8 0 0 0 16 NNE O 7 9 2 0 0 18 NE 1 7 20 4 0 0 32 EllE O 7 16 4 0 0 27 E 2 4 4 1 0 0 11 ESE 1 1 7 1 0 0 10 SE 1 6 8 2 0 0 17 SSE O 9 10 3 0 0 22 S 1 16 7 1 0 0 25 SSU 0 11 12 4 2 0 29 SU 0 15 14 5 1 1 36 USU 0 18 17 9 2 0 46 U 1 12 21 5 2 0 41 UtlU 0 13 15 5 0 0 33 flu 1 9 13 3 0 0 26 flNU 2 8 10 2 0 0 22 TOTAL 11 ISO 191 51 7 1 411 PERIODS OF CALM (HOURS): 0 UARIABLE DIRECTI0tl 0 HOURS OF MISSING DATA: 904 h1
ATTACHMENT 5-2c i HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010181-86123124 i STABILITY CLASS: D DT/DZ UIND SPEED (MPH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 4 43 40 6 0 0 93 tlNE 9 25 28 11 1 0 74 ilE 5 51 91 34 3 0 184 EilE 7 46 35 9 0 0 97 E 6 31 15 5 0 0' 57 ESE 6 31 27 5 1 0 70 SE 3 24 29 5 1 0 62 SSE 4 26 31 13 1 0 75 S G 39 44 13 2 0 104 SSU 9 39 42 26 2 0 118 SU 7 56 42 19 3 2 129 USU 9 49 53 24 6 1 142 U 10 70 59 16 4 3 162 UtlU 7 53 27 16 4 1 108 NU 6 57 36 8 1 0 108 titlU 10 48 22 1 0 0 81 TOTAL 108 688 621 211 29 7 1664 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSIrlG DATA: 904 68
r ATTACHMENT 5-2d t-HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010181-8G123124 STABILITY CLASS: E DT/DZ l UIND SPEED (PFH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N 6 37 44 9 0 tlNE 0 96 5 44 49 32 4 0 134 NE 6 36 169 106 3 EtlE 0 320 5 43 76 9 0 0 133 E 8 49 82 10 0 0 149 ESE 10 50 100 11 0 0 171 SE 13 71 131 24 0 0 239 SSE 2 51 114 36 3 0 206 S 5 61 130 28 3 0 227 SSU 4 51 148 31 7 0 241 SU 5 53 152 58 12 0 280 USU 4 37 79 38 2 0 160 U 4 30 76 29 2 0 141 UNU 4 40 88 44 6 2 184 ilu 2 46 70 30 2 0 150 titlU 6 29 46 10 0 0 91 TOTAL 89 728 1554 505 44 2 2922 PERIODS OF CALM (HOURS): 0 UARIABLE DIRECTI0tl 0 HOURS OF MISSING DATA: 904 i
l l n
ATTACHMENT 5-2e HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010101-86123124 STABILITY CLASS: F DT/DZ UIND SPEED (MPH) UIND 1-3 4-7 8-12'13-18 19-24 >24 TOTAL DIRECTION ____ _____ _____ ___ _____ 8 9 G 0 0 24 tl 1 0 45 1 9 24 11 0 flNE 67 10 44 12 0 0 flE 1 62 2 12 43 5 0 0 ENE 2 11 46 0 0 0 59 E 4 21 52 5 0 0 82 ESE 3 25 30 2 0 0 60 SE 1 16 50 5 0 0 72 SSE 2 19 69 14 0 0 104 S 0 19 62 10 2 0 93 SSU 4 25 57 13 0 0 99 SU 0 97 3 22 61 11 0 USU 0 87 13 53 20 0 U 1 S0 1 12 34 3 0 0 UNU 0 S6 0 12 34 10 0 tlU 0 29 2 8 16 3 0 titlU ________ ______________________________________________________1086 TOTAL 28 242 684 130 2 0 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTI0tl 0 HOURS OF MISSING DATA: 904 1 70
I ATTACHMENT $_2f HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010101-86123124 STABILITY CLASS: G DT/DZ __________________________________________________________7_____ UIND SPEED (MPH) UItID DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL tl 2 20 11 1 0 0 34 title 3 25 18 3 0 0 49 tie 3 14 28 5 0 0 50 EilE 3 20 21 1 0 0 45 E 4 13 25 3 0 0 45 ESE 4 21 31 1 0 0 57 SE 6 16 19 1 0 0 42 SSE 3 10 25 5 0 0 43 S 5 22 36 8 0 0 71 SSU 6 22 32 7 0 0 67 SU 10 24 44 13 0 0 91 USU 1 22 35 8 0 0 66 U 3 19 35 9 0 0 66 UtlU 2 14 29 6 0 0 51 tlU 3 11 34 6 0 0 54 titlU 5 20 27 0 0 0 52 TOTAL 63 293 450 77 0 0 883 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTI0ti 0 HOURS OF MISSING DATA: 904 71
e-L ATTACHMENT 5-2g i HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010101-86123124 STABILITY CLASS: ALL DT/DZ ' UIND SPEED (MPH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 15 126 126 25 0 0 292 NNE 18 116 145 65 5 0 349 NE 16 138 393 175 6 0 728 EtlE 17 147 212 32 0 0 408 E 24 114 185 22 0 0 345 ESE 26 136 225 23 0 1 411 SE 27 160 238 37
' 1 0 463 SSE 12 120 250 67 4 0 453 S 20 173 300 67 6 0 566 SSU 19 152 322 87 16 0 596 SU 26 203 357 127 20 4 737 USU 17 171 316 115 12 1 632 1 U 21 163 309 126 9 3 631 L
UtlU 14 145 231 93 13 3 499 NU 12 157 208 70 5 0 452 titlU 26 120 132 16 0 0 294 TOTAL 310 2341 3949 1147 98 11 7856 j PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O j HOURS OF MISSIrlG DATA: 904 n 12
i ATTACHMENT 5-3 Plant Hatch Joint Frequency Tables of Wind Speed and Wind Direction 100m versus Delta Temperature 100-10m 1/1/86 - 12/31/86 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010101-86123124
! STABILITY CLASS: A DT/DZ WIND SPEED (MPH)
WIND i DIRECTION 1-3 4-7 8-12 13-18 19-24 i
>24 TOTAL N O O O O O O O NNE O O 0 1 1 0 2 NE O O 2 1 0 0 3 ENE O 2 0 1 0 0 3
{' E O O 3 0 0 0 3 ESE 0 2 0 1 0 0 3 SE O 2 0 0 0 0 2 SSE O O O O O O O S 0 0 0 3 ' 0 0 0 0 SSU 0 0 1 1 0 0 2 SU 0 0 2 2 1 1 6 USU 0 0 4 4 1 0 9 U 0 0 2 0 0 0 2 UNU 0 0 2 0 0 0 2 NU 0 1 0 0 1 0 2 NNU 0 0 0 0 0 0 0 PERIODS OF CALM (HOURS): 0 UARIABLE DIRECTION O HOURS OF MISSING DATA: 3198 73
ATTACHMENT 5-3a HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010101-86123124 STABILITY CLASS: B DT/DZ WIND SPEED (ifH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N 0 0 0 2 0 0 2 NNE O O 0 0 1 1 2 flE O 2 2 0 1 1 6 ENE O 3 1 1 1 0 6 E O 3 0 1 0 0 4 ESE O O 2 0 0 1 3 SE. 0 0 4 0 1 0 5 SSE O O 0 0 i 1 1 2 S 0 2 1 1 0 0 4 SSU 0 0 0 0 1 1 2 SU 0 2 6 2 2 0 12 USU 1 0 8 5 3 0 17 U 0 0 4 3 0 1 8 UtlU 0 0 1 1 2 0 4 tiu 0 0 0 1 0 0 1 titlU 0 0 4 0 0 0 4 TOTAL 1 6 41 23 9 2 82 PERIODS OF CALM (HOURS): 0 UARIABLE DIRECTION O HOURS OF MISSING DATA: 3198 74
ATTACllMENT 5-3b
' HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010101-86123124
! STABILITY CLASS: C DT/DZ UIND SPEED (MPH)
- UIND DIRECTION 1-3 4 -7 8-12 13-18 19-24 >24 TOTAL N O 3 3 2 1 0 9 4 titiE O O 4 3 0 0 7 i NE O 3 8 2 1 0 14 EliE 1 4 6 3 0 0 14 l E 1 2 5 1 0 0 9 l ESE O 4 3 1 0 0 8 SE 1 4 4 1 0 0 10 SSE O 3 3 0 0 0 6 f S 1 1 5 1 1 1 10 SSU 1 0 1 2 0 1 5 SU 1 4 6 4 3 0 18 USU 0 2 7 7 0 0 16 U 0 1 5 3 5 0 14 Uilu 0 1 2 3 0 0 6 m flu 0 2 1 1 1 0 5 titlU 0 1 1 0 0 0 2 TOTAL 6 35 64 34 12 2 153 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTI0tl 0 HOURS OF MISSIffG DATA: 3198 i
l 75
ATTACHMENT 5-3c I i HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010101-86123124 STABILITY CLASS: D DT/DZ UIND SPEED (MPH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL ? _________ ___ ___ ____ _____ _____ ___ _____ tl 10 31 50 9 3 0 103 ! Nile 10 19 46 31 2 1 109 NE 12 52 81 57 11 0 213 ENE 9 32 34 18 1 1 95 E 8 21 16 8 1 1 55 ESE 9 25 32 10 1 0 77 SE 6 34 18 14 1 0 , 73 SSE 10 29 28 21 2 0 90 S ? 48 39 12 4 0 110 SSU 9 40 34 27 5 3 118 SU 12 GO 52 32 16 4 176 USU 12 52 61 52 9 3 189 U 11 55 73 44 17 5 205 UNU 8 51 38 29 9 8 143 L tlU 13 47 40 14 4 0 118 L , titlU 18 36 37 11 3 0 105 TOTAL 164 632 679 389 89 26 1979 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTI0ff 0 HOURS OF MISSIrlG DATA: 3198 l 76
ATTACHMENT 5-3d HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010181-86123124 STABILITY CLASS: E DT/DZ WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N 6 9 21 19 1 1 57 NNE 6 23 54 45 10 2 140 NE 11 26 73 122 19 1 252 ENE 8 17 39 47 3 0 114 E 8 14 34 45 8 0 109 ESE 4 23 51 41 6 0 125 SE 10 42 68 38 5 0 163 SSE 5 23 40 55 14 0 137 S 8 25 64 65 11 1 174 SSU 8 29 59 76 8 2 182 SU 6 23 62 80 22 1 194 USU 5 19 37 47 15 0 123 U 3 10 50 45 15 1 124 UNU 2 13 44 44 11 1 115 NU 6 18 51 39 4 1 119 NNU 2 9 38 16 0 0 65 TOTAL 98 323 785 824 152 11 2193 PERIODS OF CALM (HOURS): O LHRIABLE DIRECTION 0 HOURS OF MISSING DATA: 3198 i
l l 77
ATTACHMENT 5-3e HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 86010181-86123124 STAB..IL_I_.TY CLASS: F DT/DZ . _ . UIND SPEED (MPH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O 2 2 3 1 1 9 NNE O 2 8 4 1 0 15 NE 2 0 11 18 3 0 34 j, ENE 2 7 11 18 2 0 40 E O 6 15 23 2 0 46 ESE 4 11 18 27 4 0 64 SE 2 5 19 12 0 0 38 4 SSE O 13 14 29 4 2 62' b S 2 4 27 34 6 0 73 f' SSU 2 6 25 34 5 0 72 SU 0 5 21 31 11 0 68 USU 0 5 25 31 2 0 63 l U 0 7 31 32 9 0 79 UNU 0 0 8 27 5 1 41 l NU 1 7 10 21 2 0 41 NNU 0 2 7 3 0 0 12 TOTAL 15 82 252 347 57 4 757 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 3198 I ( 7 11 l
r- ? I ATTACHMENT 5-3f HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 86010101-86123124 STABILITY CLASS: G DT/DZ WIND SPEED (MPH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL l N 3 3 5 2 0 0 13 NNE O 4 5 0 0 0 9 NE 4 5 9 7 1 1 27 ' ENE 1 0 5 6 1 0 13 E 4 7 4 9 0 0 24 ESE 3 8 9 8 0 0 28 SE 6 9 9 2 0 0 26 SSE O 7 11 8 2 0 28 S 1 3 13 13 2 0 32 SSU 0 8 6 6 4 0 24 SU 0 9 9 7 2 1 28 USU 0 4 11 6 0 0 21 ! U 1 4 8 5 3 1 22 i UNU 1 4 3 7 3 1 19 NU 2 5 2 19 2 0 30 NNU 0 3 8 4 0 0 15 TOTAL 26 83 117 109 20 4 3S9 PERIODS OF CALM (HOURS): 0 UARIABLE DIRECTION 0 HOURS OF MISSING DATA: 3198 l l I f 79 L .
ATTACHMENT f-3g HOURS AT EACH UIND SPEED AND DIRECTION ' PERIOD OF RECORD = 86010181-86123124 STABILITY CLASS: ALL DT/DZ WIND SPEED (MPH) UIND .- DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 19 48 81 37 6 2 193 ' NNE 16 48 119 85 13 3 284 NE 29 87 186 209 36 2 549 ENE 21 62 100 93 8 1 235 ? t c k i
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WINO ROSE I (WINDg FROM)
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. . WITS SPEE0 LESS 1HAN3.5 ffH "
+ WIND SPEE0 LESS T; TAN 7.5 t1PH xWIND SPEE0 LESS THANt2.5 t1H
. WINO SPEE0 GREATER TNAN 12.5 t1PH e.6 PERCENT CALNS 81
ATTACHMENT 5-4a ' Plant Hatch Meterological Tower 10m Wind Rose 4 f First Quarter - 1/1/86 '.3/31/86 4e h r
/
o i 2
- i 2 7 .
1 2 l C 2 1 2 x i WINO ROSE (WINOS FROM) N ] f m 4 ii 'l 4 WIND SPEED LESS THAN3.5 f1PH
+ WIN 0 SPEED LESS THAN7.5 MPH xWIND SPEED LESS THAN12.5 MPH
, WINO SPEED GREATER THAN 12.5 NPH 0.0 PERCENT CALMS
/
82
ATTACHMENT 5-4b Plant Hatch Meteorological Tower 10m Wind Rose Second Quarter - 4/1/86 - 6/30/86 k
.g 12 2 3
- t I l O' ^
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l WIND ROSE (WItt0S FRoto N t H
. Wits SPEED LESS THAN3.5 t1PH
+WItfD SPEED LESS THAN7.5 t1PH xWING SPEED LESS THAN12.5 NPH
, Wits SPEED GREATER THAN 12.5 NPH 0.0 PERCENT CAlt1S fr
ATTACHMENT 5-4c Plant Hatch Meteorological Tower 10m Wind Rose Third Quarter - 7/1/86 - 9/30/86 i l I 8
- 12
- i 2 I I : l 2 ,s 2 : I WIND ROSE (WINDS FR0r1)
N e d6 l ii l , aWIND SPEED LESS THAN3.5 MPH
+ WIND SPEED LESS THAN?.5 MPH xWIND SPEED LESS THAN12.511PH
, WIND SPEED GREATER THAN 12.5 t1PH 0.0 PERCENT CALMS
,f 84
ATTACHMENT 5-4d' Plant Hatch Meteorological Tower 10m Wind Rose Fourth Quarter - 10/1/86 - 12/31/86 u 16 2 12 2 i t { ;' i
^
^ ;- I WIND ROSE-(WINDS FROM) l N o
a i aWIND SPEED LESS THAN3.5 NPH --
+ WIND SPEED LESS THAN7.5 MPH xWIND SPEED LESS THAN12.5 MPH
. WIND SPEED GREATER THAN 12.5 MPH 0.0 PERCENT CALMS r
L 85
ATTACHMENT 5-5 Plant Hatch Meterorological Tower 60m Wind Rose Annual -- 1/1/86 - 12/31/86 i l 12
- i
- l i
- 1 1 i 0
l I,! = 1 WIND ROSE (WINDS FR0ff) N k. j ik )
. WIND SPEED LESS THAN3.5 t1PH
- + WIND SPEED LESS THAN7.5 NPH xWIND SPEED LESS THAN12.5 t1PH
, WIND SPEED GREATER THAN 12.5 t1PH 0.0 PERCENT CAlt1S e
4 86
ATTACHMENT 5-Sa Plant Hatch Meteorological Tower 60m Wind Rose First Quarter - 1/1/86 - 3/31/86 i .l-o f : 2 2
; 2 -
1 2
- I WINO ROSE (WINDS FROM) i N
t N o s 1 4 WIND SPEED LESS THAN3.5 MPH
+ WIND SPEED LESS THAN7.5 MPH xWIND SPEED LESS THAN12.5 MPH
, WIND SPEED GREATER THAN 12.5 t1PH 0.0 PERCENT CALMS 87
i l l l ATTACHMENT 5-5b l Plant Hatch Meteorological 60m Wind Rose Second Quarter ~- 4/1/86.- 6/30/86 { 9 b i 2 1 n x J 1 2 { 1 l 2: WIND ROSE (WINDS FRON) N t i l l iWIND SPEED LESS THAN3.5 NPH
+ WIND SPEED LESS THAN7.5 NPH xWIND SPEED LESS THAN12.5 NPH
, WIND SPEED GREATER THAN 12.5 NPH 0.0 PERCENT CALMS I
i I i O.3 l . _ _ -
t,. ATTACHMENT 5-5c Plant Hatch Meteorological Tower 60m Wind Rose
>. Third Quarter - 7/1/86 - 9/30/86 l
/
6 2 12 2 g I' l , M: I WIND ROSE (WIND FR0tD t 4 i 4 WIND SPEED LESS THAN3.5 MPH
+ WIND SPEED LESS THAN7.5 NPH xWIND SPEED LESS THAN12.5 NPH
, WIND SPEED GREATER THAN 12.5 NPH 0.0 PERCENT CALMS f
d 89
gr i ATTACHMENT 5-5d e Plant Hatch Meteirological Tower 60m Wind Rose Fourth Quarter - 10/1/86 - 12/31/86 a
,i t
p 10 t I 0" X WIND ROSE
\
(WIrlDg FROM) t 4 WIND SPEED LESS THAN3.5 NPH
+ WIND SPEED LESS THAN?.5 NPH xWIND SPEED LESS THAN12.5 MPH I
. WIND SPEED GREATER THAN 12.5 MPH 0.0 PERCENT CALMS l
90
ATTACHMENT 5-6 Plant Hatch Meteorological Tower 100m Wind Rose i Annual - 1/1/86 - 12/31/86 3 4 4 l' 9 o 2
- s
- x 1 1
; l WIND ROSE (WINDS FR0tD N
t i l i 6 o
.l
. WIND SPEED LESS THAN3.5 MPH
+ WIND SPEED LESS THAN7.5 NPtf xWIND SPEED LESS THAN12.5 NPH
. WIND SPEED GREATER THAN 12.5 t1PH 0.0 PERCENT CAlt1S
\
9 T l f I' l l 91 s
ATTACHMENT 5-6a Plant Hatch Meteorological Tower 100m Wind Rose First Quarter - 1/1/86 - 3/31/86 o 1 2 *
/
- l 3 2 1
WIND ROSE (WINDS FRoto N
.p o
- WIND SPEED LESS THAN3.5 t1PH
+ WIND SPEED LESS THAN7.5 t1PH xWIND SPEED LESS THAN12.5 F1PH , WIND SPEED GREATER THAN 12.5 F1PH 0.0 PERCENT CALMS l
i ? 92
ATTACHMENT 5-6b Plant Hatch Meteorological. Tower 100m Wind Rose Second Quarter - 4/1/86 - 6/30/86
!! t 1
- i (WINDS )
n . o
; aWIND SPEED LESS THAN3.5 NPH
+ WIND SPEED LESS THAN7.5 t1PH xWIND SPEED LESS THAN12.5 NPH
. WIND SPEED GREATER THAN 12.5 t1PH 0.0 PERCENT CALMS 93
ATTACHMENT 5-6c Plant Hatch Meteorological Tower 100m Wind Rose Third Quarter - 7/1/86 - 9/30/86 2 2 Jt I I
; g 2 I I l
- I WIND ROSE (WIND FR0tD t
i! "
- i l
l 4 WIND SPEED LESS THAN3.5 11PH
+ WIND SPEED LESS THAN7.5 11PH xWIND SPEED LESS THAN12.5 f1PH
, WIND SPEED GREATER THAN 12.5 MPH 0.0 PERCENT CAllis i
94
ATTACHMENT 5-6d Plant Hatch Meteorological Tower 100m Wind Rose Fourth Quarter - 10/1/86 - 12/31/86 'l o 0 2 10 t i
- l : I i WINO ROSE (WINO FRotD I,
, 7 4 j . aWIND SPEED LESS THAN3.5 t1PH
+ WIND SPEED LESS THAN7.5 t1PH xWIND SPEED LESS THAN12.5 t1PH
, WIND SPEED GREATER THAN 12.5 HPH 0.0 PERCENT CALNS 95
ATTACHMENT 5-7 Plant Hatch Monthly Average and Average of the Daily Extremes of Dew Point Temperature 10m 1/1/86 - 12/31/86
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O JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 95
( _ ATTACHMENT 5-7a Plant Hatch Monthly Average and Average of the i Daily Extremes of Ambient Temperature 10m 1/1/86 - 12/31/86 i i-
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0 l l l l l ! JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC 97
ATTACHMENT'5-8 Plant Hatch 1986 Monthly and Annual Precipitation l l i Month Inches , i l- January 0.00 l February 3.87 March 1.62 April 0.14 May 0.53 June 3.30
. July 6.32
- 1. August 9.32 September 1.69 October 3.74 November 6.21 December 1.14 TOTAL 37.88 l,
s i 98 l L
3 l l ATTACHMENT 5-9 I Plant Hatch Daily Precipitation Data l Month Percent (inches) Month Percent (Inches) j January None August 1 0.55 August 3 0.14 February 5 0.74 August 4 0.05 February 6 0.77 August 9 0.03 February 8 0.26 August 11 0.06 February 9 0.16 August 12 0.12 February 10 1.77 August 13 1.14 February 11 0.01 August 14 2.29 February 22 0.16 August 17 0.14 TOTAL 3.87 August 19 1. 01 August 20 0.43 March 13 0.88 August 21 0.74 March 14 0.41 August 26 0.02 March 20 0.33 August 27 0.21 TOTAL 1.62 August 28 0.62 August 29 1.54 April 13 0.03 August 30 0.23 April 18 0.03 TOTAL 9.32 April 21 0.08 TOTAL 0.14 September 4 1.01 September 5 0.18 May 6 0.53 September 9 0.14 TOTAL 0.53 September 10 0.18 September 21 0.18 June 9 0.32 TOTAL 1.69 June 10 0.20 June 12 0.13 October 9 0.09 June 14 1.49 October 10 0.07 June 18 0.51 October 14 0.02 June 26 0.65 October 24 0.01 TOTAL 3.30 October 25 0.03 October 29 0.57 July 2 1.71 October 30 0.15 July 6 0.91 October 31 2.83 July 15 0.29 TOTAL 3.74 July 16 0.13 July 17 0.01 November 1 0.15 July 22 0.11 November 2 0.01 July 25 0.25 November 3 0.01 July 26 0.64 November 16 0.19 l July 27 0.01 November 17 2.26 July 29 2.26 November 18 0.03 l TOTAL 6.32 November 20 1.36 November 28 0.39 November 29 0.05 November 30 1.76 TOTAL 6.21 December 1 0.01 ' December 2 1.13
'D TOTAL 1.14 L
GeorgG Fbwer Company . 333 Piedmont Avenu) Atlinta, Georgia 30308 Telephone 404 5264526 Mailing Address: Fbst Office Box 4545 Atlanta, Georgia 30302 Georgia Power
"'** the southem electre system Manager Nuclear Safety and Licensing SL-2075 1168C February 27, 1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington,_D. C. 20555 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 SEMI-ANNUAL EFFLUENT REPORT Gentlemen:
Pursuant to the Edwin I. Hatch Nuclear Plant Units 1 and 2 Technical Specifications 6.9.1.8 and 6.9.1.9, respectively, Operating Licenses DPR-57 and NPF-5, please find enclosed two copies of the Semi-Annual Radioactive Effluent Release Report for July 1,1986, through December 31, 1986. If you have any questions in this regard, please contact this office at any time. Sincerely, r M . T. Gucwa HJB/lc Enclosure c: Georria Power Company U. S. Nuclear Regulatory Commission Mr. s . P. O'Reilly Dr. J. N. Grace, Regional Administrator Mr. J. T. Beckham, Jr. Mr. P. Holmes-Ray, Senior Resident Mr. H. C. Nix, Jr. Inspector - Hatch GO-NORMS Hr. G. Rivenbark, Licensing Project Manager - Hatch Office of Inspection and Enforcement (6) State of Georgia American Nuclear Insurers Mr. J. Setser, DNR Mr. L. Cross g
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