ML20246F504
| ML20246F504 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/30/1989 |
| From: | Hairston W GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| HL-708, NUDOCS 8908310025 | |
| Download: ML20246F504 (56) | |
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August 22, 1989 i
ll.S. Nuclear Regul'atory Commission ATTN: Document Control Desk'
- Washington, D.C. 20555 PLANT HATCH - UNITS 1;.2
- NRC DOCKETSL50-321,- 50-366 g*. OPERATING LICENSES DPR-57, NPF-5 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT Gentlemen:
In. accordance1 with the provisions of the Pl ant Hatch Technical.
Specifications Sections 6.9.1.8 and 6.9.1.9, Georgia Power Company . (GPC) is providing ~sixE copies of the' Plant Hatch Units 1 and 2 Semiannual Radioactive Effluent Release Report. -This report covers the period of
" January 1,1989 through June 30, 1989.
Should you have . arty questions in. this regard, please contact this office .at any time...
. Sincerely,
[Y W. G. Hairston, III
-ll W SJB/eb
Enclosure:
Plant Hatch Semiannual Radioactive Effluent Release. Report
.c: (See next page.)
8 1
8908310025 890630 PDR ' ADOCK 05000321 R PDC
- ' == - _
.4 ,
U.S. Nuclear Regulatory Comission
. August 22, 1989-Page Two c:- Georcia' Power Compr.3/
Mr. i . T. Beckham, d. , Vice President - Hatch .
Mr. H. C. Nix; General Manager; Nuclear Plant Mr. W. R. Woodall - Environmental Af fairs Mr. D. B. Cochran - Corporate Insurance GO-NORMS .
U.S. Nuclear Regulatory Comission, Washington, D.C.
Mr. L. P. Crocker, Licensing Project Manager - Hatch U.S. Nuclear Regulatory Comission, Region II Mr. S. D. Ebneter, Regional Administrator (2, copies)
- Mr. J. E. Menning, Senior Resident Inspector - Hatch American Nuclear Insurers Mr. L. Cross-State of Georgia Mr. J. Setser, DNR 0266V
- .,3 . j g .-
'o GEORGIA POWER COMPA!PI PLANT E. I. HATCH UNITS NO. 1 & 2.
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1,1989 - June 30,1989
i .'- j',c 4 .) LL,
') .. PLA!C E. 1. HATCH SEMIANNUAL RADIOACTn'E l
' EFFLUDC RELEASE . REPORT -
SECTION TITLE. PAGE
- 1. LIOUID EFFLUEITS 1 1.1' REGULATORY LIMITS 1 1.2 MAXIMUM PERMISS:.BLE CONCENTRATIONS 5 1.3 MEASUREME!CS AND APPROXIMATIONS OF 70TAL RADIOACTIVITY 5 1.4 LIQUID EFFLUE!C PILEASE DATA 7 1.5 RADIOLOGICAL IMPACT ON MAN DUE 70 LIQUID RELEASES 9 2 GASEOUS EFFLUE!US. 19 2.1 REGULA70RY LIMITS 19 2.2 MEASUREME!CS A!O APPROXIMATIONS OF TOTAL RADIOACTIVITY 25 2.3 GASEOUS EFFLUEtc RELEASE DATA 30 2.4 RADIOLOGICAL IMPACT DUE TO GASEOUS RELEASES 31 3 SOLID WASTE 47 3.1 REGUIA70RY REQUIPIMENTS 47 3.2 SOLID hPLSTE DATA 47 4 THE UNAVAILABILITY OF MILK AT 50 A REMP STATION e .
', 1 4 , I ,
- . PLA!C E. I. HATCH SEMIANNUAL RADIOACTIVE EFFLUDC RELEASE REPORT TABLE LIST OF TABLES PAGE 1-1 TECHNICAL SPECIFICATIQ1 TABLE 3.14.1-1 3 RADIOACTIVE LIQUID EFFLUEITT MONITORING INSTRUMD1TATIQ1 1-2a LIQUID EFFLUETES - SU!9% TION OF 10 ALL RELEASES - UNIT 1 1-2b LIQUID EFFLUENTS - SUMMATION OF 11 ALL PILEASES - UNIT 2 1-2c LIQUID EFFLUENTS - SUMMATIONS OF 12 ALL RELEASES - SITE 1-3a LIQUID EFFLUCTTS - UNIT 1 13 1-3b LIQUID EFFLUDES - UNIT 2 1k 1-3C LIQUID EFFLUEITTS - SITE 15 1-4a INDIVIDUAL DOSES DUE 'IO LIQUID 16 RELEASES - UNIT 1 1-4b INDIVIDUAL DOSES DUE 70 LIQUID 17 RELEASES - UNIT 2 1-5 IDWER LIMITS OF DETECTION - LIQUID 10 SAMPLE ANALYSES 2-1 TECHNICAL SPECIFICATIQ1 TABLE 21 3.14.2-1 RADIOACTIVE GASEOUS EFFLUDC MONITORING INSTRUFINTATION 2-2a GASEOUS EFFLUE!TTS - SUMMATION Op 32 ALL RELEASES - UNIT 1 2-2b GASEOUS EFFLUE!TTS - SUMMATION OF 33 ALL RELEASES - U!UT 2 2-2c GASEOUS EFFLUENTS - SUMMATION OF 3h ALL RELEASES - SITE 2-3a GASEOUS EFFLUE!CS - ELEVATED 35 RELEASES - UNIT 1 2-3b GASEOUS EFFLUEITTS - ELEVATED 36 RELEASES - UNIT 2 2-3c GASEOUS EFFLUEtCS - ELEVATED 3I RELEASES - SITE
f ;:.p.O ili; .
. TABLES LIST OF TABLES PAGE l
2-4a^ GASEOUS EFFLUEITTS - GROUND- 30 LEVEL RELEASES - UNIT 1 2-4b- CASEOUS EFFLUEITIS - GROUND - 39 LEVEL RELEASES - UNIT.2' 2-4c CASEOUS EFFLUEMTS - GROUND - LO LEVEL PILEASES'- SITE 2-5 GASEOUS EFFLUENTS - DOSE bl RATES - SITE 2-6a AIR DOSES DUE 70 !OBLE GASES - h2 UNIT 1 2-6b AIR DOSES DUE 70 NOBLE GASES - h3 UNIT 2 2-7a INDIVIDUAL DOSES DUE IO RADIOIODINE, kk TRITIUM, AND PARTICULATE IN GASEOUS RELEASES - UNIT 1 2-7b INDIVIDUAL DOSES DUE TO RADIOIODINE, b5 TRITIUM, AND PARTICULATE IN GASEOUS RELEASES - UNIT 2 2-8 LOWER LIMITS OF DETECTION - GASEOUS h6 SAMPLE ANALYSES 3-la,b SOLID WASTE AND IRRADIATED FUEL h8,h9 SHIPMEtTTS s.
1
- . i .s 1 RADIOACTIVE EFFLUE!E RELFASE REPORT 1 LIQUID EFFLUEtES
[
I 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.
l TECHNICAL SPECIFICATIONS '
3.14.1 The radioactive liquid effluent monitoring instrumentation channels shown in table 3.14.1-1 shall ,
be OPERABLE with their alarW trip setpoints set to 'l 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 OFFSITE DOSE CALCULATION MANUAL (ODCM). (Technical Specification Table 3.14.1-1 is included in this section as Table 1-1).
3.15.1.1 The concentration of radioactive material released at any time from the site to UNRESTRIC1'ED AREAS (figure 3.15-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II (column 2) for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 uCi/ml total activity.
3.15.1.2 The dose or dose commitment to a ! EMBER 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 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 tne 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.
- l' .s,
. 3.15.1.4(a) The contents within any outside
. temporary tank shall be limited to less than or equa'l to 10 curies, excluding tritium and dissolved or entrained noble gases.
(a) An outside temporary tank is not surrounded by liners, dikes, or walls that are capable of holding the tank contents and not having tank overflows and drains connected.te the liquid radwaste treatment system.
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 Ci, 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 radiciodines for gaseous releases".
~
ea 9
7 TABLE I .
TECHNICAL SPECIFICATION TABLE 3.14.1-1 (SHEET I of 2)
RADIOACTIVE LIOUID EFFLUENT MONITORIIG INSTRUMENTATION Minimum Chestnels Instrument OPDtABLE Applicability ACTION
- 1. Gross Radioactivity Mortitors Providing Automatic Termina-tion of Release Liquid Radwaste Effluent Line 1 (a) 100
- 2. Gross Radioactivity Monitors not Providing Automatic Termination of Release Service Water System Effluerat Line 1 (b) 101
- 3. Flowrate Measure-ment OcVices**
Liquid RadWaste Effluent Line 1 (a) 102 Discharge Canal I (b) (a) 102
- 4. Service Water 1 At all times 103 System to Closed Cooling Water System Differential Pressure
- Pump curves may be utilized to estimate flow; in such cases, i ACTION statement 102 is not required.
(a) Whenever the radwaste discharge valves are not locked closed. ..
1 (b) Whencver the cervice water system pressure is below the closed cooling water system pressure or differential pressure indication is not available.
4 I
l 4
TABLE 1-1.(CONTINUED) . (
4( ,
3' TECHNICAL SPECIFICATION g TABLE 3.14.3-1 (SHEET 2 of 2) i i
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION I l
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:
I
- 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 valuing.
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 eff3uent 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 (beta or gamma) at a Lower Limit of Detection of at least 10-7 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 is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during !
actual releases. If the channel remains inoperable for over 30 days, an exp3anation 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.
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- 2 t%XIMUM 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 B, Table II, Colu:::n 2.
For dissolved or entrained noble gases in liquid radwaste, the MPC is taken from Technical Specification 3.15.1.1 (Unit 1) and 3.11.1.1 (Unit
- 2) as 2.0E-0* uCi/ml.
For gross alp.1 2n liquid radwaste, the MPC is taken from 10CFR Part 20, Appendix B, Note 2.b as 3.0E-08 uti/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 B, 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 APPROXIMATIONS OF HEAL RADIOACTIVITY 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 gamm 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 Frecuency Method
- 1. Gama Isotopic Each Batch Gamma spectroscopy with computerized data reduction
- 2. Dissolved or Each Batch Gamma spectroscopy Entrained with computerized Noble Gases data reduction
7 ,
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Me'surement a Frequency Method
- 3. 7ritium
. 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 Ouarterly Chemical separation and Composite low energy photon detector.
Gama isotopic measurements are performed in-house in the radiochemistry lab using germanium spectrometry.
Three germanium detectors are available: a 20%
efficient 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 3000 second count. A peak search of the resulting gama ray spectrum is perfcrmed 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, Fe-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 radionuclides would be located if present.
The radionuclides concentrations determined by gamma spectroscopic analysis of a sample taken from a tr.nk 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 nonitor 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.
t - - - _ . _ - _ _ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _
t 17 s, A monitor rn ding.in' excess of the calcul'ated
. 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.
Radionuclides 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 byfthe 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 post release printout.is generated. The post release printout contains actual release rates, actual release concentrations and i quantities, actual dilution flow, and calculated L
l doses to an individual.
1.4 LIQUID EFFLUENT RELF.ASE DATA Regulatory Guide 1.21 Tables 2A and 2B 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 f 1-3c for the site.
The values for the four categories of Tables 1-2a l
and 1-2b, and 2c are calculated and the Tables
! completed as follows:
- 1. Fission and activation products - The total I
release values (not including tritium, gases, and alpha) are comprised of the sum of the measured individual ::adionuclide activities. This sum is for each batch released to the river for the respective w __ _ -_ _ _-_- -_____ _ ____- - ________ _ _ _ _ _ _ . _ _ _ _ - _
WO !. y ..
' qu2rtar.. P rcent'of applicable limit is-
~
determined 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-
' 'C/MPC ratios times:100 is the percent of
, applicable limit for effluent releases b during the quarter.
- 2. Tritium - The measured tritium concentrations in~the monthly. composite samples are used to calculate the total a release and average diluted concentration during each period. Average diluted concentration divided by the MPC limit, 3.0E-03 uCi/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 l
- germanium spectroscopy on a one liter sample '
'from each liquid radwaste batch.' The
' average concentration of dissolved or 1 entrained noble gases for all released i 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 i MPC fraction. The result x100 is the percent of applicable limit for noble gases l in liquid effluent releases'during the !
quarter. Radioisotopes of iodine in'any.
form are also determined during the isotopic j
analysis for each batch; therefore, a j separate analysis for possible gaseous forms j is not performed because it would not l
provide additional information. ?
4.
Gross alpha radioactivity - The measured j gross alpha concentrations in the monthly composite samples are used to calculate the i total release of alpha radioactivity. ;
i
- q. ;
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.* l,
,q+ 1 ; ~i T'u Other data pertinent to batch releases of i;_ radioactive liquid' effluent frce both units are-as follows:
' Number of batch releases: 569'
$ f' Total-time period'for batch . .
7.
- releases: . 76,470 minutes-
. Maximum time period'for a batch release': J243.0 minutes L Average time period for batch releases: 134.4 minutes.
Minimum time period for a' batch release:. 7.0 minutes Average stream flow during periods of release of liquid effluent-into a flowing stream: '8,497- CFS 1
1.5 RADIOLOGICAL IMPACT ON MAN .DUE 'IO LIQUID RELEASES Doses to an individual, due..to radioactivity 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 Cale"'.ation 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.
1, i
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TABLE 1 2a E. I. HATCH NUCLEAR PLANT - UNIT 1 '{
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter 1 Quarter 2 Est. Total Error (%)
A. Fission and activation nroducts
- 1. Total release Ci 4.03E.02 2.33E.02 4.70E+01
- 2. Average diluted concentration during period
- 3. % of applicable uCi/ml 3.30E.08 1.74E-08 limit t 2.03E.01 8.69E.02 B. Tritium
- 1. Total release Ci 7.62E+00 1.44E+01 3.70E+01
- 2. Average diluted concentration during period
- 3. % of applicable uCi/ml 6.25E.06 1.07E-05 limit % 2.08E 01 3.58E.01 C. Dissolved and entrained gases
- 1. Total release Ci 1.44E.02 7.48E.03 1.00E+02
- 2. Average diluted concentration during period
- 3. % of applicable uCi/ml 1.18E.08 5.59E-09 limit % 5.92E.03 2.79E.03 D. Cross Alpha radioactivity
- 1. Total release Ci 1.95E 07 1.03E-06 1.20E+02 E. Volume of waste (prior to dilution) liters 6.31E+06 6.50E+06 1.00E+01 F. Volume of dilution water used liters 1.22E+09 1.34E+09 1.60E+02 a
, , . , , , . .-,,...v. , , , , ,u .c., ....,... ,,.s.
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- 1 i
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- ' 1 TABLE-1 2b~
E. I.' HATCH NUCLEAR ~ PLANT . UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT-1989
-LIQUID EFFLUENTS 1.- SUMMATION OF ALL RELEASES l: <
k .-............................................................
c
' Unit' Quarter l' Quarter 2 Est:. Total ~
.......................................................n(%) Error
' n A.-Fission-and activation-products 14 Total release Ci 1.77E.03 3.86E-02 4.70E+01 2. Average diluted
- concentration.
- 3. % of applicable uci/n11 .3.97E.09 during period '4.53E.08 limit %- ~7.53E.02 4.86E B. Tritium 1.. Total. release Ci- 1.30E+00 2.39E+00 3.70E+01; 2 '. Average diluted concentration 3.
during. period t of applicable uCi/ml 2.92E.06 2.81E.06 limit % 9.73E.02 9.36E.02 C.LDissolved and entrais.ed gases-
.1. Total' release ci 8.54E- 03: -3.47E.03 1.00E+02
- 2. Average diluted concentration- . .
during period , uCi/ml 1.92E.08 4.07E-09 3.' % of applicable
. limit t 9.58E.03 2.03E.03
'D.: Gross Alpha radioactivity
- 1. Total release Ci 7.39E.08 0.00E+00 1.20E+02 E. Volume of waste (prior.to dilution) liters 1.75E+06 3.64E+06 1.00E+01 F. Volume of dilution water used liters 4.46E+08 8.52E+08 1.60E+02 e
- m. . - _ _ . _ _ _ _ _ _ _ _ - - _ . _ _ _ _ . . - - _ _ _ _ _ _ - - . _ _ - - . . - . _ _ _ _ _ _ _ _ _ _ _ - . _ . _ _ . - _ _ _ - - _
1
?. i '. s . l TABLE 1-2c E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES j Unit Quarter 1 Quarter 2 Est. Total Error
.........................................................(%) ....
A. Fission and activation products
- 2. Total release Ci 4.21E 02 6.19E 02
- 2. Average diluted 4.70E+01 concentration during period uCi/ml 2.53E-08. 2.83E.08
- 3. % of applicable limit % 1.69E.01 2.42E 01 B. Tritium
- 1. Total release ci 8.92E+00 1.68E+01 3.70E+01
- 2. Average diluted concentration during period 5.36E-06
- 3. % of applicable uCi/ml 7.66E.06 limit % 1.79E.01 2.55E-01 C. Dissolved and entrained gases
- 1. Total release ci 2.' Average diluted 2.30E.02 1.10E.02 1.00E+02 concentration during period uCi/ml 1.38E.08 5.00E.09
- 3. % of applicable limit % 6.90E.03 2.50E 03 D. Cross Alpha radioactivity
- 1. Total release Ci 2.69E-07 1.03E.06 1.20E+02 E. Volume of waste (prior to dilution) liters 8.06E+06 1.01E+07 1.00E+01 F. Volume of dilution water used liters 1.67E+09 2.19E+09 1.60E+02 s
' f,4 i L M ', .
1 L ~
TABLE 1 3a*
E. I. HATCH-NUCLEAR PLANT? UNIT 1
'SEMIANNUALtRADI0 ACTIVE EFFLUENT RELEASE REPORTL1989 LIQUID EFFLUENTS l
E Continuous Mode **
................................................... Mode ~
Batch
'Nuclides 1
. Released . Unit Quarter 2- .
........................................Q.uarter Quarter 1 1- Quarter 2
- i. H-3 Ci- ~
7.62E+00' 1.44E+01-Fission and activation products:
Na.24 ' Ci 1.81E 05 1.87E.04 '
Cr-51 Ci- 5.17E.04' 8.06E 04 i Mn-54 Ci 1.87E 04 5.46E.04 Mn-56 C1 1.65E.C6 1.06E.05 (
Co.58 .Ci- 2.19E.05 Co Ci 1.76E.04 Cu.64- Ci' 2.25E.03 3.51E.03-Zn-65 Ci 4.06E.03 1.89E.03 As.76 C1 6.06E.03 6.58E-03 Sr-91 Ci 1.26E 04 5.01E 05 Sr.92 Ci 0.00E+00 9.89E.05.
Y-91m C1 0.00E+00 5.80E-05 Nb-95 1.26E.03: 8.76E.05 C1 1 00E.06 0.00E+00-Nb.97. Ci 7.92E.05 Tc.99m Ci 2.51E-06 Sb.125 .Ci 7.09E 05 6.62E.05-1 131 C1 2.55E.06 7.37E.06 1 133 Ci' 1.17E-04 3.70E.05 2.09E 04 2.44E I.134 Ci- 6.89E 05 0.00E+00 Cs.134 Ci 7.32E.03 2.28E.03 Cs-137 Ci 1.79E.02 6.59E.03 Ba 139- Ci 0.00E+00-Ba.140 Ci 2.33E.05 La-140 :0.00E+00 1.90E.05 C 1. 1.28E.05 Ce.141 Ci 1.27E 05 Np-239 Ci 4.66E.06 2.39E.05 Total Ci 5.53E.05 0.00E+00 4.03E.02 2.33E.02-Dissolved and entrained gases:
Kr-87 Ci 0.00E+00 '4.44E-06 Xe-133m Ci 2.98E 05 0.00E+00 Xe.133 cf 2.20E.03 1.39E 03 Xe.135m Ci 2.12E.04 1.20E.04 Xe-135- Ci 1.20E-02 5.97E-03 Total Ci 1.44E.02 7.48E.03 Gr. Alpha ci 1.95E.07 1.03E-06
- Zeroesabove in thisdetectable table indicate levels.
that no radioactivity was See Table 1-5 for typical
.gresentower limits of detection for liquid sample analyses
- There are no continuous mode radioactive liquid release pathways at Plant Hatch.
' T .__ T _L __ l
- _ _'__LT- L--- D
- f. . '
7 .,
.i ,
' TABLE 1-3b*
E. I. HATCH NUCLEAR PLANT -
UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 LIQUID EFFLUENTS Continuous Mode ** Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1
...................................................Q.uarter .........
2
-7 H-3 Ci 1.30E+00 2.39E+00 Fission and activation products:
Na-24 Ci 9.57E-05 1.17E-03 Cr-51 Ci 0.00E+00 5.93E-06 Mn-54 Ci 1.24E-05 3.18E-04 Mn-56 Ci 0.00E+00 3.84E-06 Co-58 Ci 1.58E-06 7.52E-05 Co-60 Ci 7.15E.05 7.78E-04 Zn-65 C1 1.54E-04 1.58E-03 As.76 Ci 1.87E-05 1.52E-06 Sr.89 C1 2.44Et 04 0.00E+00 Sr.92 Ci 0.00E+00 1.50E4 05 Y-91m Ci 3.23E-04 2.17E-06 Nb-97 Ci 0.00E+00 2.44E-05 Tc-99m Ci 9.56E-06 1.73E-04 I-131 Ci 2.98E-05 1.69E-04 I-132 Ci 0.00E+00 3.69E-06 I-133 Ci 9.57E-05 1.06E-03 1-135 Ci 0.00E+00 3.94E-04 Cs.134 Ci 2-.50E.04 1.12E-02 Cs-137 Ci 4.64E-04 2.16E-02 Mp-2?9 Ci 1.85E-06 0.00E+00 Total Ci 1.77E-03 3.86E-02 Dissolved and entrained gases:
Kr-85 Ci 0.00E+00 6.01E-04 Kr.88 Ci 0.00E+00 6.66E-06 Xe-133m C1 2.61E-05 8.68E-06 Xe.133 C1 1.95E-03 3.f5E-04 Xe-135m Ci 4.55E-05 9.01E-04 Xe-135 Ci 6.52E-03 1.58E-03 Total Ci 8.54E-03 3.47E-03 Gr-Alpha Ci 7.39E-08 0.00E+00
- Zeroes in this table indicate that no radioactivity was resent above detectable levels. See Table 1-5 for typical over limits of detection for liquid sample analyses
- There are no continuous mode radioactive liquid release pathways at Plant Hatch.
't
-lh- '
&+. ,; ' . , ,
',[ 4 . [ .' y .
+
' TABLE D-3c'* 1
.-E. I '. HATCH NUCLEAR PLANT .
SITE 1
, SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT:1989 L1 QUID' EFFLUENTS r in Lu 1.:
I '
. . Continuous Mode ** Batch-Mode Nuclides:
' Released:
. Quarter'l- Quarter 2'
-Unit.............................Q.uarter 1 Quarter 2'-
'H-3 Ci 8.92E+00 .1'.68E+01 Fission and' activation products:
Na '
Ci Cr'-51' Ci l'14E-04
. 1.36E-03 Mn-54 Ci 5.17E-04 -8.12E-04, Mn-56 .1.99E 8.64E Ci Co .Ci 1.65E-06 .1.44E Co 'Ci 2.34E-05. 2.51E-04 Cu-64 Ci' 2.32E-03 4.29E 03-Zn Ci 4.06E 1-.89E-03 As-76 Ci 6.22E-03L 8.16E-03 Sr-89 Ci 1.44E-04' 5.17Ea05 Sr Ci 2.44E-04 -0.00E+00 Sr-92 Ci 0.00E+00- 9.89E-05
'Y-91m Ci 0.00E+00 7.30E 'Nb Ci-1.59E.03 8.98E-05
= N b . 9 7-. Ci 1.00E' 0.00E+00-
-Tc'-99m' Ci 7.92E-05 8,04E-05' 2.69E Sb-125 Ci 2.55E-06
- 2.40E-04 I-131 Ci 7.37E I-132 Ci 1.46E-04 2.06E-04 I-133 Ci 0.00E+00- 3.69E-06 1-134' 'Ci 3.05E l'.31E-03 .
'I-135. C1. '6.89E-05 0.00E+00 Cs-134' Ci 0.00E+00:
- 7.57E-03 3.94E .04.
Cs.137 C1 1.35E-02 Ba-139' Ci 1.83E 2.82E-02:
Ba-140' Ci 0.00E+00 2.33E-05.
.La-1400 Ci 0.00E+00 1 90E-05 Ce.141- Ci 1.28E 1.27E-05 Np-239 Ci 4.66E-06 2.39E 05:
Total- C1 5.71E-05 0.00E+00 4.21E-02 6.'19E-02
' Kr.85 Dissolved and entrained gases:
Ci 0.00E+00 Kr-87 Ci 6.01E-04 Kr-88 Ci 0.00E+00 4.44E-06 Xe-133m Ci 0.00E+00 6.66E-06 Xe-133 Ci 5.59E-05 8.68E-06 Xe-135m Ci 4.15E-03 1.75E-03 Xe-135 Ci 2.58E-04 1.02E-03 Total Ci- 1.85E-02 7.56E-03 2.30E-02 1.10E-02 Gr-Alpha Ci 2.69E-07 m
1.03E-06
- Zeroesabove present ~in this table l'Edicate detectable levels.that no radioactivity was See Table 1-5 for t lower limits of detection for liquid sample analyses.ypical ;
- There release pathways are no continuous at Plant Hatch. mode radioactive liquid
! i. i l,3 :.
TABLE 1 4a L .
E. I. HATCH NUCLEAR PLANT - Unit 1 SEMIANNUAL-RADI0 ACTIVE EFFLUENT RELEASE REPORT 1989 INDIVIDUAL' DOSES DUE TO. LIQUID RELEASES Cumulative Doses per Quarter Organ Tech Unit Quarter 1 % of Quarter 2 % of Spec Tech Tech Limit Spec Spec Limit Limit Bone 5.0 mrem 9.34E-02 1.87E+00 3.17E.02 6.35E.01 Liver 5.0 mrem 1.52E.01 3.05E+00 5.21E-02 1.04E+00 TBody 1.5 mrem 1.08E-01 7.21E+00 3.63E.02 2.42E+00 i
Thyroid 5.0 mrem 8.52E.04 1.70E 02 4.47E.04 8.93E.03 'I Kidney 5.0 mrem 5.16E.02 1.03E+00 1.82E.02 3.64E.01' Lung 5.0 arem 1.67E.02 3.33E.01 5.58E-03 1.12E.01 GILLI 5.0 mrem 5.61E.03 1.12E 01 4.47E-03 8.94E.02 Cumulative Doses This Year OrSan Tech Unit Quarters % of Spec 1 & 2 Tech Limit Spec Limit Bone 10 0 mrem 1.25E.01 1.25E+00 Liver 10.0 mrem 2.04E.01 2.04E+00 TBody 3.0 mrem 1.44E.01 4.81E+00 Thyroid 10.0 mrem 1.30E.03 1.30E.02 Kidney 10.0 mrem 6.98E.02 6.98E.01 Lung 10.0 mrem 2.22E.02 2.22E.01 GILLI 10.0 mrem 1.01E.02 1.01E 01 4.
0 4
a 4
, .j l Ug [
c n:
.?-
TABLE'Il-4b-
'E. I. HATCH' NUCLEAR 1 PLANT . ' Unit 2
~ SEMIANNUAL'RADI0 ACTIVE EFFLUENT RELEASE REPORT'1989:
r
. INDIVIDUAL DOSES DUE-TO LIQUID-RELEASES i.
I' f
- Cumulative Doses per Quarter Organ . Tech . Unit; Quarter 1 Quarter 2
' Spec.
%'of %.of Tech . Tech' Limit Spec ' Spec.
i- ,
Limit itmit Bone 5.0 mrem - 2.36E.03- 4.72E.02 '1.18 E . 01 - 2'.36E+001 0 Liver- 5.0- mrem: - 4.08E-03 8.16E.02 1.97E.01 3.94E+00 TBody 1.5 : mrem- 2.92E.03 1 95E.01 1.42E.01 9.47E+00 Thyroid- 50 mrem 2;34E.04 4.67E.03 1.77E.03 .3.54E.02-Kidney 5.0 mrem- - 1.38E-03 2.76E.02 6.58E.02 1.32E+00 Lung- 5.0 mrem- 4 . 5 3 E '- 0 4 9.05E.03 2.17E.02 4.35E.01-
~GILLI~ 5.0 : mrem 1.53E.04 3.06E.03 4.55E.03 9.10E.02 Cumulative Doses-This Year Organ : Tech Unit Quarters % of Spec 1&2 Tech Limit Spec Limit Bones 10.0 mrem 1.21E.01 1.21E+00 Liver 10.0 mrem 2.01E.01 2.01E+00 m
" TBody~d 3.0 mrem 1.45E.01 4.83E+00 Thyroi 10.0 mrem 2.00E.03 2.00E.02~
Kidney. 10.0 mrem 6.71E.02 6.71E.01 Lung 10.0 mrem- 2.22E.02 2.22E.01 GILLI 10.0 mrem 4.70E.03 4.70E-02 4
4 4
e
= __ __ _ ___ ________________ _________-_- ___- _ -_ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ - _ __-
'l -.j l ' . .
?li ; i',';)_.
L TABLE 1 *
! LOWER LIMITS OF DETECTION - LIQUID SAMPLE ANALYSES 4
The values:in this table represent apriori Iower ~1imits-
'of detection'(LLD)!which'are typically achieved in laboratory analyses of liquid radwaste samples.. '
l' . RADICNUCLIDE LLD UNITS Mn 5.38E-08 : uCi/ml"
.Fe-59 7.78E-08 Co-58 4.67E .Co-60 4.78E-08 Zn-65 '1.31E-07 Mo-99 5.10E-07*
Cs-134 7.18E-08
~
lT Cs-137 6.05E-08 l Ce-141 1.41E-07 Ce-144 6.30E-07*
I-131 6.51E-08 Xe-135 8.45E-08 Fe 8.00E-07 Sr-89 2.30E-08 Sr-90 7.67E-09
- H-3 5.00E-07
- In accordance with iachnical Specification Tables 4.15.2-1 (Unit.~1) and '
4.11.1 (Unit 2), Table Notation b, the permissible Lower Limit of' Detection may be increased inversely proportional to the' magnitude of the
. ganrna yield.- However, the LLD determined in 'this manner must not exceed .
-10 percent of the Maximum Permissible Concentration (MPC) value specified in 10CFR20, Appendix B, Table II (Column 2).
~
4a 0
s -
hgl k* 'h ,, ,
i - 2 GASEOUS EFFLUElffS p a.
~ 2'.1 ~ REGULATORY LIMITS 4~
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.,
a TECHNICAL SPECIFICATIONS - 3.14.2 The radioactive gaseous effluent monitoring t
' instrumentation channels shown in table 3.14.2-1 shall be OPERABLE with their alarW trip setpoints set-to ensure that the limits of' Specification 3.15.2.1(a) are not exceeded.
The alarW 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 less than or equal to 500 mreWyear to the total body and less than or equal to 3000 mrevyear to the skin.
form and radionuclides other than noble gases with half-lives greater than 8 days shall be less than or equal to 1500 mrevyear to any organ.
3.15.2.2 The air dose in UNRESTRICTED AREAS (figure 3.15-1) due to noble gases released in gaseous effluents from each reactor unit shall be limited to the following:
- a. During any calendar quarter, to Jess than or equal to 5 mrad for gamma radiation and Jess than or equal to 10 mrad for beta radiation.
- b. During any calendar year, to less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
3.15.2.3 The dose to any organ of a MEMBER OF THE PUBLIC from I-131, I-133, -tritium , and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents re3 eased to UNRESTRICTED AREAS (figure 3.15-1) from each reactor unit shall be limited to the following:
i
'.* "5
- a. During any calendar quarter to less than or ;
equal to 7.5 mrem to any organ.
- b. During any calendar year to less than or i equal to 15 neem to any organ.
3.15.2.4 The GASSOUS RADWASTE 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 GASEOUS RADWASTE TREATV2NT 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 lindted 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 less than or equal 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 avacuation system retreatment monitor station shall ue limited to less than or equal to 240,000 uCi/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 1 Ci, 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 radiciodines for gaseous releases."
N .
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Table'2-1'(Cont'd) -
TABLE 3'14.2-1 (SHEET 3 0F 4)
!4 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Table Notations
'+Monitor must be capable of responding to a Lower Limit of
' Detection of'1 x 10-' pCi/ml.
t
- During releases via tMs pathway.
- During main condenser offgas treatment system operation.
- During operation of the main condenser air ejector.
ACTION 104 - With the number of channels.0PERABLE less than recuired by the Minimum Channels OPERABLE requirement, [
i
' effluent releases via this pathway may continue, provided j the flowrate is estimated at .least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. '
If the number of channels OPERABLE remains less than recuired 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 105 - With the number of channels OPERABLE less than recuired 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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With the number of main stack monitoring system channels OPERABLE less than required by
-the Minimum Channels OPERABLE requirement, without delay suspend drywell purge.
1 If the numoer 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 continue provided:
(a) Gas samples are collected once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed within the ensuing 4.. hours, or (b) Using a temporary hydrogen analyzer installed in the offgas system line cowns,tream.of the recombiner, j i
hydrogen concentration readings are taken and logged -
every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. 7 a#
- _ _ _ _ _ _ _ _ _ _ _ - - - - - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ - - - ~ - - -
, M;p '
.e
// .
. TABLE 3.14.2-1 (SHEET 4 0F 4).
RADIOACTIVE' GASEOUS EFFLUENT MONITORING INSTRUMENTATION Table Not.ations (Continued)
~
If'the number of channe1s' 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 off channels OPERABLE less than required by the-Minimum' Channels OPERABLE requirement, effluent releases via this pathway may continue, provided samples are continuously collected with auxiliary sampling
. equipment for periods. on the order of 7 days and analyzed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 channelt OPERABLE'less than
- requirsd by the Minimum Channels OPERABLE requirement, release to the environment may continue for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
'provided:
- a. The offgas system is not bypassed, and
- b. The offgas post-treatment monitor (D11-K615) or the main L
stack monitor (D11-K600) is OPERABLE. -
Otherwise, be in at least HOT STANDEY within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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.
. I M M
- , f-
[ ] W l,j:
4' '2.2 MEASUREMENT AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 1 Waste gas . release at plant Hatch is confined to
!' four paths: : main stack (also; called the offgas'
' ' vent), Unit I reactor building vent; Unit 2-reactor building vent, and the'recombiner L <
, building vert. Each of these' four Daths is continuously monitored for gaseous'.
radioactivity. Each is equipped with an integrating-type sample collection. device for-
. collecting particulate and iodines. Sample collection is in accordance with Technical Specification Tables 4.15.2-1 (Unit 1) and a
4.11.2-1 (Unit 2). Unless required more
'!1 ~ frequently under certain circumstances specified 1 in Table Notations to the above mentioned tables, samples are collected as follows:
- 1. Noble gas samples are collected by grab sampling' monthly.
- 2. Tritium samples are collected by grab sampling monthly.
- 3. Radioiodine samples are collected by pulling.
the sample stream through a charcoal cartridge over a 7-day' period.
~
- 4. Particulate 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 ff1ters collected over the previous guarter and the quarterly camposite sample is analyzed for Sr-89 and Sr-90.
7 Sample analyses results and release flow rates from the four release points form the basis for calculating released quantities of radionuclides-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. -
I W w L - - - - - - - - -- _ - - - - - -- --- -- -
.\fb
";j- %T ,
y," '
L The noble gas grab sample analysis results are
!.,, used. along with maximum' expected release flow rates from each of the four vents to calculate H . monitor setpoints 'for the gaseous effluent-H' monitors serving the four release points, to J
assure that the limits of Technical .
Specifications 3.15.2.1.a (Unit 1) or 3.11.2.1.a .
_ (Unit 2)- are not exceeded. Calculation of-monitor.setpoints is described in the Plant Hatch
-DDCM.
With each release period. released radioactivity, doce rates, and cumulative doses are calculated.
Cumulative dose' results are tabulated along with
-percent of Technical Specification lindts (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.
For each calendar quarter (13 weeks) a summary'of waste gas releases from.the four vents is compiled for preparation'of the Semiannual Effluent Release Report required by Technical Specifications 6.9.1.8 and 6.9.1.9 and described in NRC. Regulatory Guide 1.21.
The methods for determining released quantities of radioactivity, dose rates and cumulative doses are as follows:
- 1. : FISSION AND ACTIVATION GAS The radionuclides-specific released radioactivity is determined from sample analyses results .y 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 radiciodines, tritium, and particulate 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 1) and 3.11.2.1.b (Unit 2) for radiciodine, tritium, and particulate. Dose rate' calculation methodology is presented in the
~
Plant Hatch ODCN.
O
ji. L*D ]
- Bata and gama air dosts duelto noble gases are calculated.for the location in the unrestricted area with the potential for the highest exposure-due to gaseous releases. Air doses are
' calculated for each release period and cumulitive-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 for each release period. . Air dose. calculation methodology is presented in the Plant Hatch ODCM..
- 2. RADIOIODINE, _ TRITIUM, AND PARTICULATE RELEASES Released quantities of radiciodines are.
determined from the waekly semples and release flow rates for.the~four release points.
Radioiodine concentrations are determined by, gama spectroscopy. '
Released quantities of particulate are 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 quarter 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 quarterly 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 through a cold
. trap. 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 efficWncies. The tritium sanples are analyzed by an independent laboratory and results ~are furnished in uC1/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. .
l l
l I. l l' ._ - . - _ _ _ _ - _ - _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ - - _ - - - - - _ _ _ _ _ - _ _ - - _ - - _ _ __a
< \
.[cAh 1*i( !
R b, Dose rates due to' radioio' dine,; tritium, and
' particulate 1are calculated forla' hypothetical child,' exposed to the inhalation pathway, at.the l 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 31mits 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 particulate are calculated for the critical ;
receptor, which is described in the Plant Hatch-
{
ODCM. Individual doses are calculated for each !
release period and cumulative totals are kept for '
each unit for the' current calendar quarter and:
-l 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. ,
l l
- 3. GROSS ALPHA RELEASE
.The gross alpha release is computed each month by counting the particulate filters each week for l gross alpha activity in a proportional counter.
i The four or five weeks' numbers are then recorded j on a data sheet and the activity is scmmed at the- '
end of the month. This concentration is input to the composite file of the computer and is used for release calculations.
1
- 4. ERROR ESTIMATES .l
'l Regulatory Guide 1.21 requires that estimated j total error in analysis techniques be reported. j These estimates are required for the total '
fission and activation gas release, total I-131 release, total particulate with half-lives greater than 8-day release, and total tritium release.
4.cG{
- "The. total.or maximum error as;ociated with the effluent 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 statistical evaluation'of error are not suggested., The objective should be to obtain an overal1~ estimate of the error associated with measurements of radioactive materials released in liquid and gaseous effluents and solid waste."
-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%
100%
(2) I-131' Release was ecleulated 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%
110%
~
(3) Particulate with half-lives greater than 8 days l release was calculated from sample analysis results and release point flow rates.
Statistical Error at LLD concentration 60%
Counting Equipment Calibration 10%
Vent Flow Rates 10%
Vent Sample Flow Rates 10%
Non-Steady Release Rates 10%
100%
l
- s
' (4) Total Tritium Release was dominated by the reactor building vent tritium release; hence, the larger statistical errors of the off-gas vent and recombinea. building vent tritium releases do not affect the error in the total tritium release:
Water Vapor in Sanple Stream Determination 20%
Vent Flow Rates 10%
Counting Calibration and Statistics- 10%
Non-Steady Release 50%
90%
2.3 GASEOUS EFFLUENT RELEASE DATA Regulatory Guide 3.21 Tables 1A, 19, and 1C are found in this report as Tables 2-2a-c, 2-3a-c, and 2-4a-c.
Data are presented on a quarterly basis as required by Regulatory Guide 1.21.
To complete Tables 2-2a-c, total release for each of the four cateocries (fission and activation gases; iodines; particulate; 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 in tarms or release rate in uCi/second but in terms of dcse rate in mrem / year, as presented in Technical Specifications 3.15.2.1 (Unit 1) and 3.11.2.1 (Unit 2). Noble gases are limited as specified in 3.15.2.1.a and 3.11.2.1.a. The other three categories (tritium, radiciodines, and particulate) are limited as a group as specified in 3.15.2.1.b and 3.11.2.1.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 radiciodine, tritium, and par ticulates 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 l
are unit limits. Cumulative air doses are presented
! in 'laules 2-6a and ,2-6b, along with percent of 1
technical specification limits.
!o . .s Limits for cumulative individual deses, due to radiciodine, tritium, and particulate, are cpecified in Technical Specifications 3.15.2.3 (Unit 1) and 3.11.2.3 (Unit 2). These limits are also unit limits. cumulative individual doses are presented in Tables 2-7a and 2-7b, with percent of technical specification limits.
2.4 RADIOLOGICAL IMPACT DUE 70 GASEOUS RELEASES Dose rates due to noble gas releases were calculated for the site in accordance with Technical Specifications 3/4.15.2.1.a (Unit 1) and 3/4.11.2.1.a (Unit 2). Results are presented in Table 2-5. Dose rates due to radiciodine, tritium, and particulate in gaseous releases were calculated in accordance with Technical Specifications 3/4.15.2.1.b (Unit 1) and 3/4.11.2.1.b (Unit 2). These results are also in Table 2-5.
Cumulative air doses due to noble gas releases were calculated for each unit in accordance with Technical Specification 3/4.15.2.2 (Unit 1) and 3/4.11.2.2 (Unit 2). These results are presented in Tables 2-6a and 2-6b.
Cumutative doses to an individual due to radioiodine, tritium , and particulate were calculated for each unit in accordance with Tech'dcal Specifications 3/4.15.2.3 (Unit 1) and 3/4.11.2.3 (Unit 2). These results are presented in Tables 2-7a and 2-7b.
Dose rates and doses were calculated using the methodology presented in the Plant Hatch ODCM.
e 6
' 'j
,1 TABLE 2-2a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 GASEOUS EFFLUENTS -
SUMMATION OF ALL RELEASES Unit Quarter 1 Quarter 2 Est. Total Error
.........................................................(%) ....
A. Fission and Activation Gases
- 1. Total Ci 4.36E+01 4.32E+01 1.00E+02 Release
- 2. Average uCi/sec 5.49E+00 5.44E+00 Release Rate For Period
- 3. % of Tech %
Spec Limit B. Iodines
- 1. Total Ci 1.51E-04 6.13E.04 1.10E+02 Iodine-131
- 2. Average uCi/sec 1.90E-05 7.72E-05 Release Rate For Period
- 3. % of Tech %
Spec Limit C. Particulate
- 1. Particulate Ci 2.21E-04 8.49E-04 1.00E+02 with half-lives >8 days
- 2. Average uCi/sec 2.78E-05 1.07E-04 Release Rate For Period
- 3. % of Tech %
Spec Limit
- 4. Gross Alpha Ci 1.17E.06 1.66E-06 Radioactivity D. Tritium
- 1. Total Ci 1.29E+00 4.50E+00 9 00E+01
- 2. Average Release uCi/sec 1.63E-01 5.66E-01 Rate For Period
- 3. % of Tech %
Spec Limit
- Technical Speci'fication limits are in terms of dose rate
'(arem 2-7a,/yr) and dose (mrem). See Tables 2-5, 2-6a, 2-6b, l and 2 7b. .
1
- s. ,
o L
TABLE 2 2b E. I. HATCH NUCLEAR PLANT .
UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 GASEOUS EFFLUENTS -
SUMMATION OF ALL RELEASES Unit Quarter 1 Quarter 2 Est. Total Error I
........................................................(%) .....
A. Fission and Activation Gases l 1. Total C1 1.79E+02 3.40E+01 1.00E+02 Release
- 2. Average Release uCi/see 2.25E+01 4.28E+00 Rate For Period
- 3. % of Tech %
Spec Limit B. Iodines
- 1. Total Ci 1.27E.04 1.64E-04 1.10E+02 Iodine-131
- 2. Average Release uCi/sec le60E-05 2.07E-05 Rate For Period
- 3. % of Tech %
Spec Limit C. Particulate
- 1. Particulate Ci 3.34E-04 2.43E-04 1.00E+02 with half-lives > 8 days
- 2. Average uCi/sec 4.20E-05 3.06E-05 Release Rate For Period
- 3. % of Tech %
Spec Limit
- 4. Gross Alpha Ci 1.38E-06 1.67E-06 i Radioactivity D. Tritium
- 1. Total Ci 7.31E+00 1.23E+01 9.00E+01
- 2. Average Release uCi/sec 9.19E-01 1.54E+00 Rate For Period
- 3. % of Tech %
Spec Limit
- Technical Specification limits are in terms of dose rate jarem/yr) and dose (mrem) z-7a, and 2-7b.
See Tables 2-5, 2-6a, 2-6b,
m.
c.:
4 6 " .* ; _ i -
"1dy .
TABLE 2-2c E. I. HATCH NUCLEAR. PLANT . SITE SEMIANNUAL-RADI9 ACTIVE EFFLUENT RELEASE REPORT 1989 GASEOUS EFFLUENTS . SUMMATION OF ALL RELEASES l
Unit Quarter 1 ' Quarter 2 Est. Total Error.
.........................................................(%) ....
r A. Fission and Activation Gases-
'1. Total Ci 2.22E+02. 7.72E+01 1.00E+02 Release
- 2. Average Release-uCi/sec 2.80E+01 -9.72E+00 Rate For Period-
- 3. % of Tech %
Spec, Limit B ., Iodines
- 1. Total Ci- 2.78E-04 7.78E.04 1.10E+02 Iodine.131
- 2. Average-Release uCi/sec 3.50E-05 9.78E-05 Rate For Period
- 3. % of Tech- %
Spec; Limit
' C. Particulate
- 1. Particulate Ci 5.55E-04 1.09E-03 2.00E+02 with half-lives > 8 days
- 2. Average Release-uCi/sec 6-.98E-05 1.37E-04 Rate For Period
- 3. % of Tech %
Spec Limit
- 4. Gross Alpha Ci 2.55E-06 3.34E-06
-Radioactivity D. Tritium
- 1. Total Ci 8.60E+00 1.68E+01
- 2. Average 9.00E+01 Release uCi/see 1.08E+00~ 2.11E+00 Rate For Period
- 3. % of Tech %-
Spec Limit
- Technical S 2(mrem7a,/yr) ankecification dose (arem).limits See are in terms Tables 2-5, 2of6a, dose rate 2 6b, i
and 2 7b. .
-3h- '
i
_ _ _ _ _ _ _ _ . , _ _ _ _ _ . _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - b
- p. s,.g ---m
. 3 . . , = = <
,. = , q ,, .a s t
} :;.J.; 29. ,
ik .
- t-. . ..
. TABLE:2 3a'
- ~E. I '. HATCH NUCLEAR PLANT'.-UNIT l'-
'SEM1 ANNUAL-RADIOACTIVE EFFLUENT RELEASE REPORT.1989 '
- .af . GASEOUS EFFLUENTS - ELEVATED, RELEASES
- Continuous Mode Batch Mode **
Nucli~ dest .
.........?......
Released Unit Quarter 1 ^ Quarter 2 ' Quarter;1 Quarter 2 y ,. >
\
f l:
l .'
- J< 1.. Fission Cases:
Kr.85m C1 2 30E+00
. -0.00E+00-Kr.87c .Ci 1.80E.01 1.28E+00-
.Kr.88 . Ci' 1.72E+00 0.00E+00 X:.131m Ci- 0.00E+00' 3.15E.06, Xe.133 'Ci '2.67E+00: 0.00E+00 Xe'.135m' Ci 5.19E+00- 6.82E+00 Xe~-135z Ci 1.05E+00 1.09E+00 a-
~~ Xe 138- C i' <1.47E+01 1.87E+01 Ar.41 Ci- .1.38E+00 0.00E+001 t
-Total For Period Ci~ 2.92E+01. 2.79E+01
. l
- 2. Iodines 1 131- Ci 3.08E.05 6.29E.05-1 133 Ci 1.41E.04 3.44E.04 I.135 Ci .1.27E.04 3.97E.04
' Total For
- Period: Ci 2.98E.04 8.03E.04
- 3. Particulate C r . 51. Ci 0.00E+00 .4.94E.08 Co.58' Ci 2.24E.07 0.00E+00 Zn.65 Ci 5.72E.08 0.00E+00
'Sr-89 Ci 7.41E.06 2.39E 05 Sr.90 Ci 6.98E-08 1.27E.07-Cs.137 Ci- 1.53E.06 1.11E.06 Ba.140 Ci 3.68E'.05 5.13E.05 La.140' Ci 5.59E.05 8.02E.05 Ce.144 C1 1.09E.06 0.00E+00 m Total For ..
Period C1 1.03E.04 1.57E.04
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for ty lower limits of-detection for gaseoue sample analyses.pical
- There are no batch mode radioactive gaseous release pathways at Plant Hatch.
~35-
r ,
a gy Ki
.ab 1" y .;
39 0% -TABLE 223b- -
E.'I. HATCH NUCLEAR PLANT .-UNIT ~2 SEMIANNUAL RADI0 ACTIVE, EFFLUENT RELEASE REPORT 1989 GASEOUS EFFLUENTS -
ELEVATED RELEASES *-
, , Continuous-Mode, Batch Mode **
' E Nuclides Released- Unit-Quarter 1 Quarter 12 'Quarterx1'-
...................... .................Q.uarter 2-
'1. Fission Gases
- Kr.85m Ci- 2.30E+00 0.00E+00
.' Kr.87- C1 1.80E.01 1.15E+00 Kr.88- Ci 1.72E+00- 0.00E+00-Xe.131m' Ci 0.00E+00 9.46E.06' Xe.133 Ci. 2.67E+00 0.00E+00 Xe.135m Ci 5.19E+00 5.98E+00 Xe.135 Ci .1.05E+00 9.47E-01 Xe.138 C1 1.47E+01 1.63E+01 Ar-41? C1 1.38E+00 0.00E+00
' Total For .. .
Period
....................'2.92E+01 Ci- 1.44E+01 2.
...' Iodines I.131- Ci 3.08E.05 5.74E.05 I-133 Ci 1.41E.04 3.10E.04 1 135 Ci 1.27E.04 3.57E.04 Total For Period Ci' 2.98E.04 7.25E.04 3 .. Particulars Cr-51 Ci 0.00E+00 4.21E.08 Co.58 Ci 2.24E.07 0.00E+00 Zn.65 Ci 5.72E.08 0.00E+00 Sr.89 Ci 7.41E.06- 2.09E-05 Sr.90 Ci 6.98E.08 1.11E.07 Cs.137 Ci 1.53E.06 9.89E.07 Ba.140 Ci 3.6PE.05 4.55E-05 La.140 Ci 5.59E.05 7.00E.05
+
Ce-144 C.i 1.09E 06 0.00E+00 Total For -
Period Ci 1.03E.04 1.37E.04
- Zeroesabove present in this table indicate detectable levels.that no radioactivity was See Table 28 for ty lower limits of detection for gaseour sample analyses.pical
- There are no batch mode radioactive gaseous release pathways at Plant Hatch.
"Q " p n
.'e-
. TABLE 2 3c . .
E. I.~ HATCH NUCLEAR = PLANT.. SITE SEMIANNUAL-RADIOACTIVE EFFLUENT-RELEASE REPORT 1989 GASEOUS EFFLUENTS -. ELEVATED RELEASES
- Continuous Mode ' Batch Mode **
Nuclides Released . Unit Quarter 1- Quarter 2 Quarter 1 . Quarter 2
- 1. j. :
'1..' Fission Gases
~Kr.85m ~ Ci 4.59E+00 0.00E+00-Kr.87 Ci 3.59E.01 '2.43E+00 Kr.88 Ci 3.45E+00 0,.00E+00 1Xe-131m Ci 0.00E+00 1.26E.05 Xe.133 Ci- 5.35E+00 0.00E+00 Xo-135m Ci 1.04E+01 1.28E+01 Xe.135 Ci 2.11E+00 2.03E+00 Xe.138 Ci 2.95E+01 3.50E+01 Ar.41 Ci 2.76E+00 0.00E+00 Total For Period Ci 5.85E+01 5.22E+01 2.lodines I.131 Ci 6.16E-05 1.20E.04 I.133 Ci 2.82E.04 6.54E.04 1 135 Ci 2.54E.04 7.54E.04 Total For Period C1 5.97E.04 1.53E-03
- 3. Particulate I Cr-51 Ci 0.00E+00 9.16E.08 Co-58 Ci 4.48E.07 0.00E+00 Zn.65 Ci 1.14E.07 0.00E+00 Sr-89 Ci 1.48E-05 4.48E.05 Sr.90 Ci 1.40E.07 2.38E.07 Cs-137 Ci 3.07E.06 2.10E.06 Ba.140 Ci 7.36E.05 9.68E.05 La-140 Ci 1.12E.04 1.50E.04 Ce-144 Ci 2.18E.06 0.00E+00 Total F- r i.
. 2.065'.04 2.94E.04
. Period................'L.............................................
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for'ty lower limits of detection for gaseous sample analyses.pical
- There are no batch mode radioactive gaseous release pathways at Plant Hatch.
L ._. - - . _ - - - - - - - _ - - - - - _ _ - - - - - - - - - _ - - - -
$ .r-r I n . ,. , y
=,
[ [4hb N.h ;
- t; I o
V V :.n
. TABLE'2 4a E. 1. HATCH NUCLEAR PLANT . UNIT 1 L -SEMIANNUAL RADIOACTIVE-EFFLUENT RELEASE REPORT 1989 GASEOUS EFFLUENTS - GROUND. LEVEL RELEASES *-
hh-
. Continuous Mode Batch Mode **
i Nuclides .,
Released- : Unit'-Quarter 1 -Quarter.2" t . c
.........................................Q.uarter.1 ...................
- Quarter 12.-
- 1. Fission Gases
- Kr.85m Ci- 1.44E.02 0.00E+00-Kr.87- Ci 6.28E-02 7.64E 02t
.Xe,-133 Ci 1.63E.01 0.00E+00 L Xe.135m Ci 4'75E-01
. 1.62E.01 Xe-135 Ci 1.37E+01 1.51E+01 Total For .
JPeriod. Ci. 1.44E+01 1.53E+01
- 2. Iodines
.I.131 Ci 1.21E-04 5.50E.04
'I.133 Ci S.8?E.04 5.30E.03
.....'I.135'....Ci 1.02E-03 9.46E.03 Total:For-Period Ci 2.02E-03 1.53E.02>
- 3. P' articulates Co-60 Ci Ol00E+00 1.30E.06 Zn.65 Ci 1.44E.05 9.63E.05 H5r-89 C1 1.96E.05 3.62E.05 Sr.90 Ci 0.00E+00 1.38E.07 Cs.137 Ci 1.41E-06 1.38E.06 Ba.140 Ci 3.32E.05 2.03E 04 La.140 Ci 4.85E.05, 3.41E-04 Ce.141 Ci 1.01E-06 1.37E.05 Total For Period Ci 1.18E-04 6.92E4 04
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See T4ble 2-8 for ty lower limits of detection for gaseous sample analyses.pical
- There are no batch mode radioactive gaseous release
-pathways at Plant Hatch.
Q s
y..c- _,_ ~" ~
~y
h l'
l, ._ f , ~ .; 4 ;, :< s5~
.m
. . .h. x. .j$ 1 ) l
- ei..
l I".-
+
E;.I.
TABLE 2-4b
' ' HATCH NUCLEAR PLANT.. UNITE 2-SEMIANNUAL; RADIOACTIVE EFFLUENT: kELEASE REPORT 1989.
GASEOUS EFFLUENTS , GROUND-LEVEL RELEASES
- Continuous; Mode Batch Mode **-
Nuclidesc
. Released Unit Quarter 1 Quarter 2 '
..........................................Q.uarter:
~
1 LQuarter 2 f-l '
- 1. Fission' Gases E ^
Xe.133 -Ci' 1.39E+02 '0.00E+00
.Xe.135- Ci- 1.08E+01 9.63E+00 Total For Period Ci 1.49E+02 9.63E+00
- 2. Iodines I.131 'Ci 9.63E-05 1.07E.04
'I.133. Ci 6.32E.04 7,09E.04 I.135 Ci. 2.98E-04 2.76E.04.
Total For Period Ci 1.03E-03 1.09E.03
. 3. . Particulate.
2n.65 Ci 2.24E-05 1.13E.06 Sr.89 Ci 5.31E.05 1.84E.05 Sr.90 Ci 1.54E.07 0.00E+00 Cs.137 Ci 5.15E-07 2,46E.07 r
-Ba.140 Ci 5.67E.05- 3.02E.05 La.140 Ci 9.52E.05 '5.47ELOS Ce-141 Ci 2.33E.06 -9.37E.07 Total For Period Ci 2.30E-04 1.06E.04 L
- Zeroes in this table indicate thatSee present above de'tectable levels.
no radioactivity was 2-8 for ty lower-limits of detection for gaseous Tablesample analyses.pical
- There are no baran mode radioactive gaseous release pathways at Plara Hatch.
-',i + * *., .
l j
i l
. TABLE 2-4c E. I. HATCH NUCLEAR PLANT - SITE t
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 1 GASEOUS EFFLUENTS -
GROUND-LEVEL RELEASES
- Continuous Mode Batch Mode ** 1
............................................................. I Nuclides Released
....................................................Q.uarter Unit Quarter 1 Quarter 2 Quarter 1 2
- 1. Fission Gases Kr.85m C1 1.44E-02 0.00E+00 Kr.87 Ci 6.28E-02 7.64E-02 Xe-133 Ci 1.39E+02 0.00E+00 Xe-135m Ci 4.75E-01 1.62E-01 Xe-135 Ci 2.44E+01 2.47E+01 Total For Period Ci 1.64E+02 2.50E+01 2.lodines I-131 Ci 2.17E-04 6.57E-04 1 133 Ci 1.51E-03 6.01E.03 I-135 Ci 1.32E-03 9.73E-03 Total For Period Ci 3.05E-03 1.64E-02
- 3. Particulate l .............................................................
Co.60 Ci 0.00E+00 1.30E-06 l
Zn.65 Ci 3.68E.05 9.75E-05 Sr.89 Ci 7.27E-05 5.46E-05 Sr.90 Ci 1.54E-07 1.38E-07 Cs-137 C1 1.93E-06 1.62E-06 I Ba.140 Ci 9.00E.05 2.33E-04 i
La.140 Ci 1.44E-04 3.95E-04 Ce.141 Ci 3.35E-06 1.47E-05 Total For Period Ci 3.49E.04 7.98E.04
- present Zeroes in'this table indicate that no radioactivity was above detectable levels. See Table 2-8 for ty lower limits of detection for gaseous sample analyses.pical
- There are no batch mode radioactive gaseous release pathways at Plant Hatch.
h0- '
- c. .
- ' ' u - . 5)
- 1 i s
.a IL '
Table 2 E. I. HATCH NUCLEAR PLANT -SITE SEMIANNUAL-RADIOACTIVE EFFLUENT RELEASE. REPORT 1989 GASEOUS: EFFLUENTS -- DOSE: RATES p
, . Dose: Rates Due to Noble Gases
' Organ Tech- Unit. Quarter 1 % o f. Quarter 2 % 'o f Spec: Tech Tech
. Limit '
Spec Spec' Limit Limit 1.................................. ...........................
TBody 500 mrem /yr 9.50E.02 1.90E.02 5.14E.02' 1.03E.02,
' Skin 3000 mrem /yr 2.12E-01 7.06E.03 1.10E.01 3.68E-03:
4 Dose Rates Due to Radioiodine, Tritium, and Particulate
, Organ Tech Unit Quarter 1 %.of Quarter 2 % of Spec Tech Tech Limit. Spec. Spec
' Limit Limit Bone 1500 mrem yr. 1.11E.04 7.38E-06 '2.13E-04 1.42E.05 Liver 1500 mrem yr 1.01E-02 6.75E.04 2.00E.02 1.33E.03 TBody 1500 mrem yr 1.01E.02 6.74E-04 1.99E.02 1.33E.03
- Thyroid 1500. mrem yr 1.99E.02 1.33E.03 5.54E.02 3.70E.03 Kidney. 1500 mrem yr 1.02E.02 6.77E.04 2.01E-02 1.34E.03 Lung 1500 mrem yr 1.05E.02 6.99E-04 GILL 1 1500 mrem yr 1.01E-02 6.76E.04 2.06E.02 2,00E-02 1.37E.03 1.33E.03 k1- '
!. y dl . ', .,
TABLE 2-6a-E. I. HATCH NUCLEAR PLANT . UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 AIR DOSES DUE TO NOBLE GAS RELEASES Cumulative Doses per Quarter Type Tech Unit Quarter 1 % of of Spec Quarter 2 % of Radi- Tech Tech Limit Spec Spec ation Limit
....................................................... Limit .......
Gamma 5.0 mrad 7.97E.03 1.59E.01 8.43E-03 1.69E.01 Beta 10.0 mrad 9.37E-03 9.37E.02 1.02E-0 1,02E.01
........ ....................................... 2............
Cumulative Doses This Year Type Tech Unit Quarters % of of Spec 1 & 2 Tech Radi- Limit Spec ation Limit Gamma 10.0 mrad 1.64E.02 1.64E.01 Seta 20.0 mrad 1.96E.02 9.81E-02 4
k2- '
( _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ - _ _ _ - - - _
a f >".\ .
TABLE 2 6b E. I. HATCH NUCLEAR PLANT .
UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 AIR DOSES DUE TO. NOBLE GAS RELEASES Cumulative Doses ptt Quarter Type Tech. Unit Quarter 1 % of Quarter 2 % of of Spec Tech Radi- Limit Tech Spec Spec ation
...................................................... Limit.
Limit Gamma 50 mrad 1.89E-02 3.79E.01 5.31E.03 1.06E.01 Beta 10.0 mrad 4.58E.02 4.58E.01 6.41E-03 6
..................................................... 41E-02 .......
Cumulative Doses This Year Type Tech Unit Quarters % of oY Spec 1& 2 Tech Radi- Limit Spec ation Limit Gamma 10.0 mrad 2.42E 02 2.42E-01 Beta 20.0 mrad 5.22E.02 2.61E-01 4
4 0
_h3- '
r :.
f j ,,2 ., *.
e l
l TABLE 2 7a E. I. HATCH NUCLEAR PLANT .
Unit 1 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1989 INDIVIDUAL DOSES DUE TO RADI0 IODINE. TRITIUM, AND PARTICULATE IN GASEOUS RELEASES 1
Cumulative Doses per Quarter Organ Tech Unit Quarter 1 % of Quarter 2 % of Spec Tech Tech Limit Spec Spec Limit Limit Bone 7.5 mrem 2.75E-04 3.67E.03 6.57E.04 8.76E.03 Liver 7.5 mrem 6.89E-04 9.19E-03 2.49E.03 3.32E.02 TBody 7.5 mrem 6.79E.04 9.05E-03 2.46E.03 3.28E.02 Thyroid 7.5 mrem 3.27E-03 4.36E.02 1.49E.02 1.99E.01 Kidney 7.5 mrem 6.84E-04 9.11E.03 2.49E.03 3.32E.02 Lung 7.5 mrem 6.72E.04 8.97E.03 2.43E.03 3.24E.02 GILLI 7.5 mrem 6.75E.04 9.00E.03 2.43E.03 3.24E-02 i
Cumulative Doses This Year Organ Tech Unit Quarters % of Spec 1 & 2 Tech Limit Spec Limit Bone 15.0 mrem 9.33E-04 6.22E.03 Liver 15.0 mrem 3.18E.03 2.12E.02 TBody 15.0 mrem 3.14E 03 2.09E.02 Thyroid 15.0 mrem 1.82E.02 1.21E.01 Kidney 15.0 mrem 3.17E.03 2.11E.02 Lung 15.0 mrem 3.10E.03 2.07E.02 GILLI 15.0 mrem 3.11E.03 2.07E.02 kh- -
--______ _ __ - _ -_-__ - -_ _ a
,l~ .s:
- a. s '. g. ,. 4 6
. TABLE 2 7b
. E;
.I ' O I. HATCH NUCLEAR PLANT - Unit 2-SEMIANNUAL-RADIOACTIVE-EFFLUENT RELEASE REPORT 1989 INDIVIDUAL 1 DOSES DUE TO RADIOIODINE, TRITIUM, AND PARTICULATESLIN GASEOUS RELEASES
-Cumulative Doses per Quarter Organ Tech' Unit Quarter 1 % of Quarter' 2 % of Spec Tech Tech
. Limit -Spec _ Spec Limit Limit Bone. 7.5 mrem- 7-. 0 7 E . 0 4 9.42E-03 2,63E-04 3.51E.03 Liver 7. 5' arem 3.79E.03 '5.06E.02 6.35E-03 8.47E.02
' TBody 7.5 mrem 3 81E.03. 5.09E.02 6.36E.03 8.48E.02' Thyroid 7.5 mrem 1 5.82E.03 7.76E.02' 8.69E.03 1.16E.01 Kidney 7.5 mr ein 3-.79E.03. 5.05E.02 6.36E.03: 8.48E.02
-Lung 7.5 mrem 3.79E.03 5.06E.02 6.35E-03 8'.47E.02
.GILLI 7,5 mrem 3.80E.03 5.07E.02 6.36E 8.48E.0
........................................................... 2 .
Cumulative Doses This Year-Organ- Tech- Unit Quarters. e of Spec 1&2 Tech Limit' Spec Limit Bone 15'.0 mrem 9.70E.04 6.47E.03 Liver 15.0 mrem 1.01E.02 6.77E.02 TBody 15.0 mrem 1.02E-02 6.78E.02 Thyroid 15.0 mrem 1.45E.02 9.67E.02-Kidney 15.0 mrem 1.01E-02 6.77E.02.
Lung 15.0 mrem 1.01E-02 6.77E.02' GILLI 1.02E.02- 6.77E.02 15.0 mrem 4 9
.h5_ =
t _ _ , _ _ - - . _ _----_ ----------------- - - - - -
J
,t.,.
. py? ; s .
s TABLE 2-8 :-
4 iLOWER LIMITS OF. DETECTION - GASEOUS SAMPLE ANALYSES l'
. The values in this table represent apriori' lower limits of
. detection (LLD) which are typically achieved in laboratory analyses.
of gaseous radwaste samples.
RADICHUCLIDE LLD UNITS Kr-87 1.31E-07 uci/ml
.Kr-88 2.10E-07 l-Xe-133 1.62E-07 Xe-133m '6.07E-08 l 1 Xe-135. 5.77E-08
-Xe-138 ~2.85E-06 I-131 '4.37E I-133. 6.16E-13 Mn-54 2.78E Fe-59 4.62E-14
.Co-58 2.46E-14 Co-60 2.88E :Zn-65 7.51E-14
'Mo-99 6.02E Cs-134 '3.64E-14' Cs-137 2.88E-14 Ce-141 4.94E-14
'Ce-144 2.02E Sr-89 1.17E-14 Sr-90 3.82E-15 H-3 5.82E-12 h
e 8
h6-
__=___- _ _ -_--_ -_____ _ __ -___ ____ - ______ - _ __ _ - _ -__ _ _ ______ _ -_-_-__ ___________-
cjkht *~
3 _3. SOLID WASTE-
+
3.1" REGULA20RY REQUIREMEtES 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 n1mbers are not the same.
TECHNICAL SPECIFICATIONS:
3.15.3.1 The solid radwaste system shall be used in accordance with the. PROCESS COICROL PROGRAM to provid6
- 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:
1 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, conpacted 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-la, and 3-lb.
4 6 0
hT- '
= _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ - _ _ _ _ _ __ .__.. .____.
q b_ EFFLUENT AND MESTE DISPOSAL SEMIANNUAL REPORT 1989 D p. A .s - JANUARY 1, 1989 - JUNE 30, 1989 l SOLID WASTE AND IRRADIATED FUEL SHIPPENTS 6 FOR UNIT I AND II
- l l TABLE 3-1A l
1.
I I I I l l 1. Type of waste l
l UNIT ll6period monthl lEst. Totall l ERROR % l l a. Spent resins, filter studges, evaporator l m3 l 1,85E2l l l bottoms, etc. Ci I l 7.68 E 2 l 1.00 E3 l
- b. Dry compressible waste, contaminated l m3 2.15E2 equip. etc. l
) Ci
, l I 167 E 0 2.00 El l
- c. Irradiated components, control rods, l m3 ! N. A E etc. Ci I N. A E N. A E d.-Other (describe) m3 '
N. A E l equip, etc. Ci l NAE M. A E l
- 2. Estimate of major nuclide composition (by type of waste) l ISOTOPE I PERCENT l CURIES l l l l l l a. Zn 65 l 55.03 l h22.63 l l Fe-55 1 1h.06 l 107198 l
l Co-60 1 10.33 1 79'.'33 l l Cs-137 1 3.0 l 23.0h l l Other 1 17.58 1 135.01 l l I l l l b. Co 60 1 38.1 l .636 l l Zn 65 1 35.7 l .596 l l Cs-137 1 10.h l .17h l l Oth er l 11.9 l .199 l l Fe-55 1 3.9 ! .065 l l I i l l _ e. N/A l N/A l N/A l l l l l l d. N/A N/A l N/A l
l l
_l 1 1 I I i 1
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 33 Cash Barnwell, S.C.
B. IRRADIANDFUELSHIPMENTS(Dsftfon) ' **
Number of Shipinents Mode of Transportation Destination N/A N/A N/A h8-
y.d .s -
- n. o a
- ~
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1989 JANUARY 1, 1989 - JUNE 30, 1989 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNIT I AND II i TABLE 3-1B l
l TYPE I CURIE I PRINCIPLE l BURIAL ; NUPWER OF VOLUME OF OF l TYPE lSOLIoIFICATIOWi l 'l90ANTITY /l NUCLIDES / l CONTAINER l CONTAINERS 1 msTE loETERmINEol DETERMINATION I EACH CDMAINER l SHIPMENT /' AGENT l DESCRIPTION I surPPED IcuBIC FEET fft 3)lCONTAINER {
IDevatered!303h !Zn_65'Fe-55!CarbonSteel l 7 l 199.h lLSA None I
.lBasin IMeasuredlCr_51 Co_60l Liner l I-l 1 l Type A l l 1
I I Cs-137 I
IES_210 l l l l l I I l M I I l i_________h________j_easured _____----_h_____-- - _-_
l p__-_____f__________--_q________y_
I l fDevateredfh69 Cr-51 I ILSA l l l Resin iMeasuredlFe-55 Co-60 EL-lh2 Zn_65l lHIC2 l 132.h lTypeB l None I I l .lcs-137 l10 1h2 l l l
'I I -I i i l l 1 l l l l___-__-__l________. p Measured __ _ _ _ _ __ _ _ - q- _-_ __ _________l____________ ____-_--______
__ _ _ __ _ y - -
l Devateredj 268.1h IZn_65 l 2h 1 202.1 iLSA i l gResin I lCs-137 Fe-55llHIC l Measured;Co_60 Cr_51 EL-210 l l lT lypeA l I None i l l l l 1 1
I IMeasured l l l 1
---_____t._____---1._-_--____-_..I l_________--_-_.4._-__----y-________-_ l y__-_-__.g__---___-_-_l
- Comp 2cte 0.h6 l Co 60 Cs-137 l Steel B_25l ho l 90.0 l DAW l Estimatel Fe_55 Cr-13h l Strong Tight i lLSA l None l l i STC l l I I I I Container l l l-_______h_______I.Estimateg__-_________.__-_--________]_-_____L-___
I I SEG 1.21 l Co_60 Cs-137 I Metal Bins I h2 1 '9h.8 iLSA l l fCompacte Estinateg'Fe-55Cs-134fStrongtight l l lSTC None 1 l DAW I l Estimate l container g g l
I l I l l l g g l I l l l
'l l I I l I I l l l l i I l 1 l l l I I I I I I l l I I I I 1 l l l 1 I l l l I l l l I I I l y 1 l l l l I I I i l I i l 1 I l i I I I I l l Notes: LSA - Low Specific Activity l STC - Strong Tight Container j SEG - Scientific Ecology Group .
DAW - Dry Act,ive Waste t
h9_
- jL . k4 .4 D- C ,
4 4. THE UNAVAILABILITY'I OF MILK AT A REMP STATION j
In the Semiannual Radioactive Effluent Release Report for the second half of 1988, it was reported pursuant to Technical Specification 3.16.1.c that ndlk samples had become unavailable at Clark's Farm (Station No. 216) and that although no replacement samples were found, it was expected {
that Clark's goats would 'again be producing milk in the forthcoming spring. As anticipated, milk samples became available on March 13. However, after a few months, the goats again went dry; the last sample was collected on May 23. No replacement samples were located, but the Clarks expect milk will again become available after about six months.
a 6
____________________J