ML20153C640
| ML20153C640 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/30/1988 |
| From: | Hairston W GEORGIA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| HL-46, X7GJ17-H530, NUDOCS 8809010218 | |
| Download: ML20153C640 (70) | |
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) GEORGIA EGfER COMPAtu PLATE E. I. HATCH UtilT3 tO,1 & 2 SEMI-AtJtCAL REPORT PLATE RADIOACTIVE EFFLUEtE RELEASES January 1,1989 - June 30,1988 eso90iO210$$ohh21 DR ADOCK PNV g
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PLANT E. I. HATCH i
SEMIANNUAL REPORT i RADI0 ACTIVE EFFLUENT HELEASE REPORT ,
SECTION TITLE JA3
- 1. LIQUID FFFLUErfrS __ 1 i 1.1 REGJLATORY LIMITS 1 i
1.2 MAXIMUM PERMISSIELE COtCEtirRATI0tG 5 [
4 1.3 MEASUREMEtirS AND APPROXIMATIOtG OF 5 !
TOTAL RADIOACTIVITY f 1.4 LICtJID EFFLUEfft RELEASE DATA I f
1.5 RADICIDGICAL IMPACT ON MAN DOE TO 9 f
LIOUID RELEASES ,
2 GASDX1S EFFLUENTS 22 I i
2.1 REGJLATORY LIMITS 22
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2.2 MEASUREMEffrS AND APPROXIMATI0tB Op 23 f MTAL RADIOACTIVITY !
I 2.3 GASDOUS EFFLUENT RELEASE DATA 33 l
2.4 RADIOIDGICAL IMPACT DUE TO GASEOUS 3k f RELEASES ;
3 SOLID WASTE 50 3.1 REGJLATORY SPECIFICATIOtB 52 3.2 SOLID WASTE DATA 50 4 CHANGES TO THE PLArtr liATCH RADIO- 53 i thGICA L ENVIRotNEPITAL MONIMR!?C PROGRM S CHANGES TO THE PLAPfr HATCH OFFSITE 5
DOSE CALOJLATION MAN'JAL J l
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PLATE 2. I. HATCH SEMIAN!UAL REPORT RADIOACTIVE EFFLUEtC NELEASE REPORT TABLE LIST OF TABLES PAGE l-1 TECHilICAL SPECIFICATION TABLE 3.14.1-1 3 RADIOACTIVE LIQUID EFFLUEtC IONITORItG ItGTRUMENTATIOti 1-2a LIQJID EFFLUEtCS - SUMMATION OF 10 ALL RELEASES - UNIT 1 1-2 b LIQUID EFFLUEtCS - SUMMATION OF 11 ALL RELEASES - UNIT 2 1-2c LICUID EFFLUEtCS - SUMMATIOtG OF 12 '
ALL RELFASES - SITE l-3a LIQUID EFFLUEtCS - UNIT 1 13 1-3b LICUID EFFLUEPirS - UllIT 2 15 1-3c LICUID EFFLUEtCS - SITE 17 1-4a INDIVIDUAL DOSES DUE 'IO LICUID 19 RELEASES - UNIT 1 1-4b INDIVIDUAL DOSES DUE 'IO ICUID 00 RELEASES - UNIT 2 i
1-5 INER LIMITS OF DPTECTION - LICUID 21 SAMPLE AtRLYSES 2-1 TECHNICAL SECIFICATION TABLE Ok J ,
I 3.14.2-1 RADIOALTIVE GASD')US i i
EFFLUEtE PONIIORItG ItGIRUMENTATI0tl {
1 2-2a GASD)US EFFLUE!CS - SUMMATIO!i OF 35 ;
ALL RELEASES - UtlIT 1 2-2b GASD3US EFFLUEtCS - SUMMATION OF 26 ALL RELEASES - UNIT 2 2-2c GASD30S EFFLUEtCS - SLWATIOri 0F 37 ALL RELEASES - SITE 2-33 GASDOUS EFFLUE!CS - ELEVATED , 35 j RELEASES - UNIT 1 i
i 2-3 b GASEQUS EFFLUE!CS - ELEVATED 39
- RELEASES - UNIT 2 1
2- 3c GASD)US EFFLUEtCS - ELEVATED '0 RELEASES - SITE l
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- TABLES LIST OF TABLES PAGE 2-4a CASEDUS EFFLUEtES - GROUND- kl LEVEL RELEASES - UNIT 1 2-4b GASEOUS EFFLUEtr - GROUtc - L2 LEVEL BELEASES - UNIT 2 2-4c GASEOUS EFFLUEtES - GROUto - L3 LEVEL RELEASES - SITE 2-5 GASEDUS EFFLUEtCS - DOSE kk RATES - SITE 2-6a AIR DOSES DUE 'IO FOBLE GASES - k5 UNIT 1 2-6b AIR DOSES DUE 70 tOBLE GASES - L6 UNIT 2 2-7a ItOIVIDUAL DOSES DUE TO RADIOIODItE, L7 TRITIUM, AtO PARr!CIJLATES IN GASEDUS RELEASES - UNIT 1 2-70 ItOIVIDUAL DOSES DUE 'IO FADIOIODINE, k0 TRITIUM, AND PARTICULATES IN GASEDUS RELEASES - UNIT 2 2-8 IMER LIMITS OF DLTECTION - GASEOUS k9 SAMPLE AtaLYSES 3-13,b SOLID WASTE AfD IRRADIATED FUEL 51,52 l SHIPMEtES l
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RADIOACTIVE EFFLUEtT! RELEASE RENRT j 1 LICOID EFFLUE!7tS L 1.1. REGULATORY LIMITS i
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- 1. The Technical Specifications presented in this section are for Unit 1. Requirements for Unit 2 are the same as Unit 1: bowever, the Technical Specification numbers are not the same.
TECHNICAL SPECIFICATIOf6 3.14.1 The radioactive liquid effluent monitoring instrumentation channels shown in table 3.14.1-1 shall be OPERABLE with their alarWtrip setpoints set to easure that the limits of Specification 3.15.1 are not exceeded. The alarm / trip setpoints of these channe:s shall be determined in accordance with the OFFSITE DOSE CALCULATION MAtUAL (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 f rom the site to UfBESTRICTED AREAS (figure 3.15-3) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B.
Table II (column 2) for radionuclides other than dissalved or entrained noble cases. For dissolved or entrained noble gases, the concentration shall be i limited to 2.0E-04 uC1/ml total activity.
3.15.1.2 The dose or dose commitment to a MEMBER OF !
THE PUBLIC f rom radioactive miterials in liquid i effluents released, from each reactor unit, f rom the !
site (figure 3.15-1) shall be limited tot
- a. Durino any calendar quarter to less than or e2usi i to ;,5 mrem to the total body and to less than or equal to 5 mrem to any orcan,
- 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. I i
3.15.1.3 Tre liquid radwaste trestcent system, as described in the ODCM, shall be used to reduce the l radioactive materials in liquid wastes prior to their discharge when the cro1ected doses due to the liquid effluent per Unit from the site (figure 3.15-1) when pro $ acted over the cilendar quarter would exceed 0.13 L mrem to the total bod / or 0.62 mrem to any organ, l
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3.15.1.4(a) The contents within any outside temporary tank shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble cases.
(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 conneetted to the liquid radwaste treatment system.
6.9.1.9 states in part: "The Radioactive Ef fluent Release Report shall include (on a quarterly basis) .
unplanned releases from the site to unrestricted 3reas ;
of radioactive materials in caseous and liquid etfluents that were in excess of 1 C1, excludinq 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 caseous releases". .
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4 TABLE 1-1 TECHNICAL SPECIFICATION TABLE 3.14.1-1 (sheer 1 of 2)
RADIOACTIVE LIOUID EFFLUEffr MONITORItC It6IEVEffrATION i
Minimum Channels I nst rument OPERABLE Applicability ACTION
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O
- 1. Gross Radioactivity i
- Monitors Providing [
2 Automatic Termina- i tion of Release i Liquid Radwaste Effluent Line 1 (.) 100 !
- 2. Gross Radioactivity i
', Monitors not Providing
- Automatic Termination of i Release [
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System Etfluent '
Line 1 (b) 101
! 3. Flowrate Measure-j ment Devices ** f l Liquid Radwaste !
j Effluent Line 1 (a) 102 Discharge Canal 1 (b) (a) 102
- 4. Service water 1 At all times 103 .
] System to closed !
I Cooling Water !
System Differential l Pressure i i l !
"Pum curves may te utilized to estimate flows in such cases, ACTION statement 102 is not required.
1
, (a) Whenever the radwaste discharge valves are not locked i
Closed.
fb) Whenever the service water system pressure is below I the closed coolirn water system pressure or i differential pressure indication is not available.
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- TABLE l-1 (CI)NTINUED)
TECHNICAL SPECIFICATION-TABLE 3.14.1-1 (SHEET 1 of 2)
RADIOACTIVE LICOID EFFLUENT MONITORING INSTRUMENTATION TABLE tOTATIOtE 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 sanples are analyzed in accord m e 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 effluants via this pathway. If the channel remins inoperable for over 30 days, an explanation of the circumstances shall be included in the next semi-annual ef fluent 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 ptauCi/ml.
or ganma) atchannel If the a Lower Limit of remins inoperable for over 30 days, an explanation of the circumstances shall be included in the next semi-annual ef fluent release recort.
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 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 requiremnt, assure that the service water system effluent system nonitor is OPERABLE.
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1.2 MAXIMUM PERMISSIBLE CDNCENTRATIONS The:MPC values used in determining allowable liquid radwaste release rates and concentrations for principal gaara emitters, I-131, tritium, Sr-89, Sr-90 and Fe-SS are taken from 10CFR Part 20, Appendix B, Table II, Column 2.
For dissolved or entrainea 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-04 u i/nd.
4 For gross alpha in liquid radwaste, the MPC is taken f rom 10CFR Part. 20, Appendix B, 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 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 MEASUREMENIS AND APPROXIMATIOtB OF TOTAL RADIOACTIVITY Prior to release of any tank containing liquid radwaste, and following the required recirculation, synples 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 gamna emitters, I-131, and dissolved and .
entrained noble cases 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. Ganna Isotopic Each Batch Ganna spectroscopy [
with computerized .;
data reduction )
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- 2. Dissolved or Each Batch Gamma spectroscopy
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Entrained with computerized 1 Noble Gases data reduction l
. Measurement P recuency Method
- 3. Tritium Monthly Distillation and Composite liquid scintillation counting
- 4. Gross Alpha Monthly Gas Flow Proportional Canposite 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 25%
efficient and two 15% efficient intrinLic germanium detectors, with 2.0 FNHM 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, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144. The quantitativa 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 1 standard deviations of the baseline count at the l location on the spectrum vhere a peak for that I l
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, cross alpha, Sr-89, Sr-90, and Fe-55 are used along with the correspondino MPC values to determine an MPC 2raction for the tank planned for release. This MPC fraction is then used, with appropriate safety factors, along l with the expected dilution stream flow to calculate a l
maximum permissible release rate and a liquid effluent i monitor setpoint. The monitor setpoint is calculated I to assure that the limits of Technical Specifications l 3.15.1.1 (Unit 1) or 3.11.1.1 (Unit 2) are not '
exceeded. ,
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. A r.cnitor reading in excess of tha calculated setpoint therefore results in an autonatic termination of the liquid radwaste discharge. l Liquid ef fluent discharge is also automatically l 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 oermissible 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 Radweste Operations. When the release is completed the release oermit is returned from Radweste Operations with actual release data l included. These dats are 1.9put to the computer and a postrelease printout ic generated. The postrelease printout contains actual release a rates, actual release concentrations and quantities, actual dilsttion flow, and calculated doses to an individual.
1.4 LIQUID EFFLUENT RELEASE DATA Regulatory Guide 1.21 Tables 2A and 29 are found in this report as Table 1-2a for Unit 1, Table 1-2b for Unit 2 and Table 1-2c for the sites and Table 1-3a for Unit 1,1-3b for Unit 2, and Table 1-3c for the site.
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The values for the four categories of Tables 1-2a :
and 1-2b, and 1-2c are calculated and the Tables !
completed as follows: i
- 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 i
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. quarter. Percent 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 -
Ci/MPCi ratios times 100 is the percent of applicable li.ait 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 i give the percent of applicable-limit.
- 3. Dissolved and entraired gases -
3 Concentrations of dissolved and entrained
! qases in liquid ef fluents are measured by germanium spectroscopy on a one liter sanole from each liquid radwaste hatch. 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/ad) to determine the MPC fraction. The result x100 is the percent of apclicable limit for noble gases in liquid effluent releases during the quar te r . 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 provide additional information.
- 4. Gross alpha radioactivity - The measured gross alpha concentrations in the monthly I composite sanoles are used to calculate the total release of alpha radioactivity. ,
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l Other data pertinent to batch releases of I radioactive liquid effluent from both units are as follows:
Number of batch releases: 841 Total time period for batch 121,325 minutes releases:
Maximum time period for a batch release: 270.0 minutes Average time period for batch ,
releases: 144.3 minutes t Minimum time period for a batch release: 2.0 minutes Average stream flow during periods of release of liquid effluent
'nto a flowing stream: 8,580 CFS 1.5 RADIOIOGICAL IMPACP 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 Calculation Manual. As required by the above Technical Specifications, doses were 1 calculated separately for Unit 1 and Unit 2.
j Besults are presented in Table 1-4a for Unit 1 and Table 1-4b for Unit 2.
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TABLE 1-2a
. E. I. HATCH NUCLEAR PLANT - UNIT 1.
SENIANNUAL EFFLUENE RELEASE REIORT 1988 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Est. Total Unit Quarter 1 Quarter 2 Error %
A. Fission &
Activation P roducts
- 1. Total release (not including Ci 3.22E-01 1.33E-01 4.6E+01 H-3, gases, alpha)
- 2. Averaoe diluted concentration uCi/ml 1.2SE-07 6.53E-08 during period
- 3. % of applicable % 1. 46E+ 00 5.34E-01 limit B .Triti um
- 1. Tot.al release Ci 8 . 6 5F,+ 00 5.81E+00 3. 7E+ 01
- 2. Average diluted uCi/ml 3. 36E-06 2.86E-06 concentration during period
- 3. % of applicable % 1.12E-01 9.53E-02 limit C. Dissolved and Entraired Gases
- 1. Total release C1 3.738-03 5.125-03 1.0E+02
- 2. Average diluted uCi/ml 1.45E-09 2.52E-09 4
concentration during period
- 3. % of applicable % 7.2SE-04 1.26E-03 limit D. Gross alpha radioactivity
- 1. Total release C1 2. 3 5E-06 1. 30E-06 1. 2E+ 0 2 E. Volume of waste (prior to dilution) liters 1.04E+ 07 7.64E+06 1.0E+01 F. Volume of dilution water used liters 2.57E+09 2.03E+09 1.6E+02
TABLE 1-2b l E. I. RATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL EFFLUEifT RELEASE REPORT 1988 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES i l
Est. Total Unit Quarter 1 Quarter 2 Error %
A. Fission &
Activation Products
- 1. Total release (not including Ci 1.65E-01 4.58E-02 4. 7E+ 01 H-3, gases, alpha)
- 2. Average diluted concentration uCi/mi 1.36E-07 3.15E-08 during period
- 3. % of applicable % 4.08E+ 00 3.20E-01 limit B.T riti um
- 1. Total release C1 2.71E+00 3.16E+00 3. 7E+01
- 2. Average diluted uCi/ml 2. 24E-06 2.19E-06 concentration during period
- 3. % of applicable % 7.46E-02 7.29E-02 limit C. Dissolved and Entrained Gases
- 1. Total release C1 2.24E-02 4.52E-03 1. 0E+0 2
- 2. Average diluted uCi/.Td 1.85E-08 3.13E-09 concentration during period
- 3. % of applicable % 9. 26E-03 1.56E-03 limit D. Gross alpha radioactivity '
- l. Total release c1 6.17E-07 2.15E-07 1. 2E+0 2 E. Volume of waste (prior to 4
dilution) liters 4.67E+06 4.75E+06 1.0E+ 01
, F. Volume of dilution water used liters 1. 21E+ 09 1.45E+09 1.62+ 02 1
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IABLE 1-2c E. I. HATCH tUGEAR PLAND - SITE SENIAN!UAL EFFLUENT RELEASE REEORT 1988 LICUID EFFLUEttrS - SUMMATION OF ALL RELEASES Est. Total Unit Quarter 1 Quarter 2 Error %
A. Fission &
Activation Products "'
- 1. Total release (nnt including Ci 4.878-01 1.79E-01 4. 7E+ 01 H-3, gases, alpha)
- 2. Average diluted concentration uCi/ad 1.298-07 5.14E-08 during period
- 3. % of applicable % 2. 34E+ 00 4.79E-01 limit B.Triti um
- 1. Total release C1 1.14E+01 8.9 7E+ 00 3. 73+ 01
- 2. Average diluted uCi/ml 3.00E-06 2.58E-06 concentration during period
- 3. % of applicable 1 1.00E-01 8.60E-02 limit C. Dissolved and I Entrained Gases i
- 1. Total release C1 2. 6 2E-02 9.65E-03 1.0E+02
- 2. Average diluted uCi/nd 6.92E-09 2.77E-09 concentration during period l
- 3. % of applicable t 3.46E-03 1.39E-03 limit D. Gross alph6 radioactivity '
- 1. Total r.elease C1 3.17E-06 1.525-06 1. 2E+ 0 2 E. Volume of waste (prior to dilution) liters 1.50E+07 1. 24E+ 07 1.0E+ 01 F. Volume of dilution water used liters 3. 7 8E+ 09 3.4BE+09 1.6E+ 02
TABLE 1-3a E. I. HATCH NUCLEAR PLAtTP - UNIT 1 SEMIANNUAL LIQUID EFFLUEffrS RELEASE REIORT 1988*
Page 1 of 2 Continuous Mode ** Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 H-3 Ci 8.65E+00 5.81E+00 Na-24 Ci 7.31E-03 4.30E-04 Cr-51 Ci 1.77E-03 2.17E-03 Mn-54 Ci 4. 28E-03 2.05E-03 Mn-56 Ci 8.78E-06 1. 25E-05 Fe-55 Ci 0.00E+00 0.00E+ 00 Fe- 59 Ci 4.48E-04 8.05E-05 Co-58 Ci 8.34E-04 6.35E-04 Co-60 Ci 1.23E-02 6.02E-03 Cu-64 Ci 8.21E-03 1.75E-03 Ni-65 Ci 0.00E+00 0.00E+00 Zn-65 Ci 3.26E-02 2.29E-02 As-76 Ci 5.18E-05 5. 72E-0 5 Rb-88 Ci 0.00E+00 3.82E-04 Sr-89 Ci 0.00E+00 7.49E-04 Sr-90 Ci 0.00E+00 0.00E+00 Sr-91 Ci 0.00E+00 0.00E+00 St-92 Ci 4. 48E-05 1.68E-04 Y-91m Ci 6.89E-05 3. 50E-0 5 Zr-95 Ci 5.97E-06 0.00E+00 Nb-95 C1 1.35E-04 3.32E-05 Nb-97 Ci 8.58E-04 1.38E-03 Mo-99 Ci 0.00E+00 0.00E+00 Tc-99m Ci 7.73E-04 2.02E-05 Sb-125 Ci 2.66E-04 1.15E-03 I-131 Ci 5.27E-03 9.48E-04 I- 132 Ci 0.00E+00 0.00E+00 I-133 Ci 4.06E-04 1.15E-04 I-134 C1 2.95E-03 2.60E-03 I-135 Ci 0. 00E+ 00 0.00E+ 00 Cs-134 Ci 1.01E-01 3.67E-02 Cs-136 C1 1.65E-03 1.29E-05 Cs-137 C1 1.40E-01 5.23E-02 Cs-138 Ci 0. 00E+ 00 0.00E+00 Ba-139 Ci 0.00E+00 0.00E+00 Ba-140 Ci 0.00E+00 0.00E+ 00 l La-140 Ci 0.00E+00 0.00E+00 1 Ce-141 C1 3.58E-06 0.00E+ 00 i Ce-144 Ci 4.96E-05 0.00E+00 Np-239 Ci 0.00E+ 00 0.00E+ 00 Totals C1 3.21E-01 1. 32E-01
TABLE 1-3s E. I. HATCH fCCLEAR PLANT - UNIT 1 SEMIANtUAL LICUID EFFLUENTS RELEASE REEORT 1988*
Page 2 of 2 continuous Mode ** Batch Mode ttclidea Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Kr-85m Ci 0. 00E+ 00 0. 00E400 Kr-85 Ci 0.00E+00 0.00E+ 00 Xe-131m Ci 2.80E-04 1. 58E-04 Xe-133 Ci 1.59E-03 2.28E-03 Ci Xe- 133m 0. 00E+ 00 1.24E-05 Xe-135m Ci 1.71D 05 1.29E-04 Xe-:35 C1 1. 84E-03 2.545-03 At-41 Ci 2.72E-06 0.00E+00 Totals Ci 3.73S-03 5.12E-03 Gross Alpha Ci 2.35E-06 1.30E-06
- Zeros in this table iniicate that no radioactivity was present above detectable levelt;. See Table 1-5 for typical lower limits of detection for liquid sample analyses.
- There are no continuous node radioactive liquid release patheys at Plant Hatch.
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TABLE 1-3b E. I. HATCH NUGEAR PLAffr - UNIT 2 SEMIANtJUAL LIOUID EFFLUENTS RELEASE REIORT 1988* 1 Page 1 of 2 Continuous Mode ** Batch Mode tJuclides ReleMed Unit _Qgr,ter 1 Quarter 2 Quarter 1 Quarter 2 H-3 C1 2.71E+ 00 3.16E+00 Na-24 Ci 2.91E-05 7.33E-06 C r-51 C1 1.8 6E-04 8.60E-05 Mn-54 C1 1.87E-03 8.21E-04 Mn-56 Ci 0. 00E+ 00 0.00E+00 Fe-55 Ci 0.00E+00 0.00E+00 Fe-59 Ci 9.5 4E-05 0. 00E+ 00 co-58 Ci 3.42E-04 2.80E-04 Co-60 Ci 4.88E-03 2.45E-03 Cu-64 Ci 0.00E+00 0.00E+ 00 Ni-65 C1 1.3 9E-06 0. 00E+ 00 .
2n-65 Ci 1. 37E-02 6. 20E-03 As-76 Ci 0. 00E+ 00 0. 00E+ 00 St-89 Ci 0.00E+00 0.00E+ 00 Sr- 90 Ci 0. 00E+00 0.00E+00 t- Sr-91 Ci 2. 29E-04 5.07E-04 Sr-92 Ci 0. 00E+00 0. 00E+00 Y-91m Ci 0.00E+00 0.00E+00 Z r-95 Ci 0. 00E+ 00 0.00E+ 00 tb-95 Ci 0.00E+ 00 0.00E+00 Nb-97 Ci 1.11E-05 2. 3 6E-05 Mo-99 Ci 0.00E+00 0.00E+00 Tc-99m Ci 1. 36E-04 1.03E-05 ,
sb-125 C1 1.11E-04 4.96E-06 I- 131 Ci 1.17E-02 1.025-03 I- 13 2 Ci 0.00E+00 t. 82E-06 I- 133 Ci 8.16E-04 1.725-03 I- 134 C1 1.66E-05 8.11E-06 I-135 Ci 0. 00E+ 00 0. 00E+ 00 co-134 Ci 5.95E-02 1.40E-02 C s- 136 C1 1. 46E-03 7. 62E-06 Cs-137 Ci 6.99E-02 1.82E-02 Cs- 138 Ci 0. 00E + 00 0. 00E+ 00 Ba-139 Ci 2.06E-04 0.00E+ 00 fu-140 Ci 1.17E-04 2. 30E-04 La- 140 C1 1.448-05 0.00E+ 00 Ce-141 Ci 6.125-06 0. 00E+ 00 Ce-144 Ci 0.00E+00 0.00E+00 to-239 Ci 0. 00E+ 00 1.525-04 Totals C1 1.65E-01 4.58E-02
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l TABLE 1-3b l E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIhNNUAL LIQUID EFFLUENTS RELEASE REPORT 198E*
l Page 2 of 2 l
Continuous Mode ** Batch Mode ;
tbclides
, Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 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+ ;0 Xe-131m Ci 5. 27E-03 0.00E+ 00 Xe-133m C1 4. 9 6E-04 0. 00E+ 00 Xe-133 Ci 1.58E-02 8. 29E-04 Xe-135m Ci 0. 00E+ 00 1.785-04 ,
Xe-135 Ci 8.53E-04 3.52E-03 A r-41 Ci 0. 00E+ 00 0. 00E+ 00 Totals ci 2. 24E-02 4. 53E-03 Gross Alpha Ci 8 .17E-07 2.15E-07
- 2 eros in this table indicate that no radioactivity was present above dett. ; table 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.
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TABLE 1-3c E. I. HATCH fUCLEAR PLANT - SITE SEMIANtOAL LIQUID EFFLUEtIrS RELEASE REPORT 1988*
Page 1 of 2 Continuous Mode ** Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 H-3 C1 1.14E+01 8.97E+00 Na-24 Ci 7.34E-03 4. 37E-04 Cr-51 C1 1.96E-03 2.26E-03 .
Mn-54 Ci 6.15E-03 2.87E-03 Mn-56 Ci 8.78E-06 1. 25E-05 '
Fe-55 Ci 0.00E+00 0.00E+00 Fe-59 Ci 5.43E-04 8.05E-05 Co-58 Ci 1.18E-03 9.16E-04 Co-60 Ci 1. 72E-02 8. 47E-03 Cu-64 Ci 8.21E-03 1.75E-03 Ni 6.. Ci 1.39E-06 0.00E+00 2n~65 C1 4.63E-02 2.92>-02 As-76 Ci 5.18E-05 5.72E-05 Rb-88 Ci 0.00E+00 3.82E-04 Sr-89 Ci 0.00E+00 7.49E-04 Sr-90 Ci 0.00E+00 0.00E+00 St-91 C1 2.29E-04 5.07E-04 St-92 Ci 4.48E-05 1.68E-04 Y-91m Ci 6. 89E-05 3. 50E-0 5 Z r-95 Ci 5.97E-06 0.00E+00 L Nb-95 C1 1.99E-04 3.325-05 Nb-97 Ci 8.69E-04 1.40E-03 Mo-99 C1 0.00E+00 0.00E+00 Tc-99m Ci 9.10E-04 3.06E-05 S b-125 Ci 3. 77E-04 1.16E-03 I-131 Ci 1.70E-02 1.97E-03 I-132 Ci 0.00E+00 4. 82E-06 I-133 C1 1.22E-03 1.84E-03 I-134 C1 2.97E-03 2.61E-33 !
I- 135 Ci 0.00E+00 0.00E&00 l Cs-134 Ci 1.61E-01 5. 07E-02 Cs-136 Ci 3.11E-03 2.05E-05 Cs-137 C1 2.10E-01 7.04E-02 C s-138 Ci 0.00E&OO 0.00E+00 l Ba-139 C' 2.06E-04 0.00E+00 Ba-140 C 1.17E-04 2.30E-04 La-140 C1 1.44E-05 0.00E+00 Ce-141 Ci 9.70E-06 0.00E+ 00 Ce-144 Ci 4.96E-05 0.00E+00 No-239 Ci 0. 00E+ 00 1.52E-04 Totals Ci 4.87E-01 1.79E-01 l
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4 TABLE l-3c E. I. HATCd tCCLEAR PLANT - SITE SDiIANtUAL LIQUID EFFLUENTS RELEASE REEORT 1988*
Page 2 of 2 Continuous Mode ** Batch Mode tJuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 Kr-85m Ci 0. 00E+ 00 0. 00E+00 Kr-85 Ci 0.00E+ 00 0.00E+00 Kr-87 Ci 0. 00E+ 00 0. 00E+ 00 Xe-131m Ci 5.55E-03 1.58E-04 Xe-133m Ci 4. 9 6E-04 1.248-05 X e-133 Ci 1.74E-02 3.llE-03 Xe-135m Ci 1.71E-05 3.088-04 Xe-135 Ci 2.70E-03 6.06E-03 A r-41 Ci 2. 72E-06 0. 00E+ 00 Totals Ci 2.62E-02 9.65E-03 Gross Alpha ci 3.17E-06 1. 52E-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.
- rhere are no continuous mode radioactive liquid release pathways at Plant Hatch.
TABLE 1-4a E. I. HATCH tCCLEAR PLAfR UNIT 1 SD1IANICAL EFFLUEfC RELEASE REPORT 1988 ItOIVIDUAL DOSES DUE 'IO LICUID RELEASES Cumulative Dose Per Quarter Organ Tbch Units Quarter % of Quarter % of Spec 1 Tech 2 Tech Limit Spec Spec Limit Limit Bone 5.0 mrem 6. 4 3E-01 1. 2 9E+01 2.36E-01 4.72E+ 00 Liver 5.0 mrem 1.12E+00 2. 24E+ 01 4.11E-01 8.22E+00 T. Body 1.5 mrem 8.21E-01 5. 4 7E+ 01 3. 00E-01 2. 00E+01 Thyroid 5.0 mrem 2.76E-02 5.52E-01 4.40E-03 8.80E-02 Kidney 5.0 neem 3.7 5E-01 7. 50E+ 00 1. 3 9E-01 2.78E+ 00 Lung 5.0 mrem 1.22E-01 2.44E+00 4.45E-02 8.90E-01 gJ,-LLI 5.0 meem 3.22E-02 6. 4 4E-01 1. 4 7E-02 2. 94E-01 '
cumulative Dose Per Year Organ Tech Unit Quarters % of Tech Spec 1&2 Spec Limit Limit ,
Bone 10.0 mrem 8.79E-01 8.79E+ 00 Liver 10.0 mrem 1.5 3E+ 00 1.5 3E+01 Total Body 3.0 mrem 1.12E+ 00 3.74E+ 01 Thyroid 10.0 mrem 3.20E-02 3. 20E-01 Kidney 10.0 mrem 5.14E-01 5.14E+ 00 Lung 10.0 mrom 1. 67E-01 1.67E+ 00 GI-LLI 10.0 mrem 4.69E-02 4.69E-01 1
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. TABLE 1-4b l E. I. HATCH NUCLEAR PLANT UNIT 2 l SEMIAN!JJAL EFFLUENT RELEASE REPORT 1988 l INDIVIDUAL DOSES DOE 'IO LIQUID RELEASES Cumulative Dose Per Quarter Organ Tech Units Quarter % of Quarter % of Spec 1 Tech 2 Tech Limit Spec Spec Limit Limit Bone 5.0 mrem 4.21E 8.4 2E+ 00 8.88E-02 1.78E+00 Liver 5.0 mrem 7.70E-01 1. 54E+ 01 1.59E-01 3.18E+00 T. Body 1.5 mrem 5.67E-01 3.78E+01 1.17E-01 7.80E+00 Thyroid 5.0 mren 7.96E-02 1.59E+00 4.74E-03 9.48E-02 Kidney 5.0 mrem 2.57E-01 5.14E+00 5.34E-02 1.07E+00 Lung 5.0 mrem 8.40E-02 1.68E+00 1.73E-02 3.46E-Oi GI-LLI 5.0 mrem 1.99E-02 3.98E-01 5.25E-03 1.05E-01 Cumulative Dose Per Year Organ Tech Unit Quarters % of Tech Spec 1&2 Spec Limit Limit Bone 10.0 mrem 5.10E-01 5.10E+00 Liver 10.0 mrem 9.29E-01 9.29E+00 Total Body 3.0 mrem 6.84E-01 2. 28E+ 01 Thyroid 10.0 mrem 8.43E-02 8. 43E-01 Kidr.ey 10.0 mrem 3.10E-01 3.10E+00 Lunq 10.0 mrem 1.01E-01 1.01E+00 ;
GI-LLI 10.0 mrem 2.52E-02 2.51E-01 l
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TABLE 1-5 t IOWER LIMI'IS OF DETECTION - LIQUID SAMPLE ANALYSES l The values in this table represent apriori-lower limits j
of detection (LLD) Which are typically achieved in laboratory analyses of liquid radwaste samples. !
RADIONUCLIDE LLD UNITS I Mn-54 3778E-08 uC1/ml !
Fe-59 7.78E-08 Co-58 4.67E-08 '
Co-60 ~ 4.78E-08 Zn-65 1.31E-07 t it>-99 5.10E-07*
Cs-134 7.18E-08 ,
Cs-137 6.05E-08 i Ce-141 1.41E-07 Ce-144 6.30E-07* -
I- 13 1 6.51E-08 Xe- 135 8. 45E-08 ,
Fe-55 8.00E-07 I St-89 2. 30E-08 l S t- 90 7.67E-09 H-3 5. 00E-07 '
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- In accordance with Technical Specification Tables 4.15.2-1 (Unit 1) and 4.11.1 (Unit 2), Table Notation b, the permissible Lower Limit of j Detection may be increased inversely proportional to the magnitude of the i ga.Tra yield. However, the LLD determined in this manner must not exceed j 10 percent of the Maximum Permissible concentration (MPC) value specified . ,
in 10CFR20, Appendix B, Table II (Col'amn 2).
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2 GASEDUS EFFLUENTS 2.1 REGJLATORY LIMITS The Technical Specifications prese.1ted in this section are for Unit 1. Requirements fo: Unit 2 are the same as for Unit is however, the Technical Specification numbers are not the same.
3 TEGt1ICAL SPECIFICATI0tB 3.14.2 The radioactive gaseous effluent monitoring [
instrumentation channels shown in table 3.14.2-1 shall be - ;
j OPERABLE with their alarv erip setpoints set to ensure that '
the limits of Specification 3.15.2.1(a) are not exceeded.
The alarWtrip setpoints of tnese channels shall be j determined in accordance with the ODm. Technical !
Specification Table 3.14.2-1 is included in this section as 3 Table 2-1. )
3.15.2.1 The dose rate at any time in the U!RESTRICIED
, REAS (figure 3.15-1) due to radioactive sterials released l in gaseous effluents from the site shall be limited to the
-following values: l l
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- a. The dose rate limit for noble gases shall be less [
than or equal to 500 mreWWar to the total body (
j and less than or equal to 3000 mrem / year to the !
skin. t I
4
and for all radioactive s terials in particulate form and radionuclides other than noble gases f 4
with half-lives greater than 8 days shall be less than or equal to 1500 mreWyear to any organ.
3.15.2.2 The air dose in UtRESIRICIED ASEAS (figure !
3.15-1) due to noble gases released in gaseous effluents 4
from each reactor unit shall be limited to the following:
! a. During any calendar quarter, to less than or equal to 5 mead for gamma radiation and less than !
l, or equal to 10 mead for beta radiation.
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j b. Durirq any calendar year, to less than or equal i i to 10 mrad for garmsa radiation and less than or l equal to 20 mrad for beta radiation. ;
3.15.2.3 The dose to any organ of a MD4BER OF THE PUBLIC i from I-131, I-133, tritium , and all radionuclides in j particulate form with half-lives greater than 8 dsys in l
- gaseous ef fluents released to UtRESIRICIED AREAS (figure '
3.15-1) from each reactor unit shall be linited to the ,
following:
i j !
i - - ___ - _ ___________ - __ -- -___ _____ -__
- 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 equal to 15 mrem to any organ.
3.15.2.4 The GASEDUS RADWASTE TREATMENT SYSTEM as described in the ODCM sh&11 bt' in operation. (This
'Mehnical Specificatien 3(JJe4 whenecer the main condenser air ejector cyctem is in operatim.)
4,15.. 4 GASEDUS RVWASTC TREATHENr SYSTPt
.$2rabilit./ shall a demm3trated by administrative controls which assure t at Ka offga a treatment system is not bypassed.
3.15.2.5 The wual (ca W k . ' tr ) do:16 c t dose commitraent to any MEMBER OF TIE dELIC duo CO releases of radioactivity and to radiation floc uranium fuel cyc1 - sources nnall be limited to less than or emal to 25 mrem to che 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 mterials in liquid or gaseous effluents exceeding twice the limits ot 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 mde 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 recorrbiners in the main condenser offgas treatment system shall be limited to less than or eqt 31 to 4 percent by volume.
1 3.15.2.7 The gross garrma radioactivity rate of the noble gases Xe-133, Xe-135, Xe-138, Kr-85m, Kr-87, and Kr-88 rreasured at the min condenser evacuation system pretreatment monitor station shall be limited to less '
than or equal to 240,000 tci/second.
6.9.1.9 states in pirt:
"The Radioactive affluent Release Report shall ,
include (on a quarterly basis) unplanned releasec l I
from the site to unrestricted areas of I radioactive mterials in gaseous and liquid l cffluents that %=3re in excess of 1 C1, excluding I 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 i
giseous releases." -
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- TABLE 3.14.2-1 (SHECT 1 Of 8s] .
ItADt0 ACTIVE CASEOUS EFFtVENT MONfTORINC !NSTRUMENTATION ,
Minimaus
_t a s t et *c n t Channeis .
OPERADM ApotfcabitItY PA ra me ttI ACTION 1
Main Condenser Orfgas Treatment ~
y system Emplosive cas Monitoring system Hydrogen Mon 8 tor .
(tl **
7,DIydrogen 106
- 2. neactor Duinding vent stack nonitoring systea
- s. Moble Cas , Activity rtonitor (1)
- Redloactivity Rate 105 +4 b.
Iodine Sampler Cartridge Measurement * >-
[g (1)
- p .
p -
Verify Presence of 107 in
, c. Particieta te Sampler fliter Ca rt ridge (1)
- Verify Presence of -
7 filter - 107
- d. E f flisen t System flowrate Measurement Device (t)
- System flowrate 10's
- e. Mea surement 8
$aro1e r T 8 oura t e sten suremen t Device (1) *
. Sampler flowra te ' 10's
- 1. rtecoatsiner Desilding Ventitation Measurement Mone toring System *
- a. Noble cas Activity Monitor (11 * .\
Radioactivity Rate 105
- t. sodine Samp f er Cartridge Heasuremont *
(1)
- Verify Presence of
. 107
- c. Pa
- rticusa te saa.psor Ti n tor Certridge (t) *
. Verify Presence or Filter 107
- d. Samp f e r ( f owr.s t e Plea ste"cmen t .
)'
oewice (1) *
$ amp' ar finwrate 10's Meat rement 9
. ..m. _ _ , . . _ . . _ = . . _ _ _ _ . _ _ . . . . - . _ _ - . . . . . . _ _ _ _ _ . _ . - - _ _ __ .. .
i . _ .
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. ,.e TABLC 3.18s.2-1 (SHEET 2 0F 3 .
i -
fta0:0 ACTIVE CASCOUS EFFl_UENT MONITORINC I ON._ INSTRUMENTAT -s Minlawn anstrement ChanoeIs .
- i OPERAfst_r agn11ribilftv .
- s. TarametAr s
Main Stack Monitoring System aCUM
- 2 g Noble cas Activity Monitor (1)
- b.
Radfoactivity Rate 105 todine Sampser Cartrihge Meestatement + -
(1)
- c. Verity Presence or 107 Pa rticuts te $septer Filter (Il
- Ca rt re dge y
as l
- o. Vertry Presence of 107 e
l E f f lieen t System flowrate Yllter M Measuring Devices >J
)
\
(1)
- 8 w
System riowrate ~
l
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l y Sampler (towrate Meas:srIng Device (1)
- Messierement ^
Sampler Trowrate Q~
- 5. 104 * = ,
- Cordenser Origas Prctreatment Mea surement, "
stoni to r n.
v tionic Cas Activity 14onitor l
(1) ***
Radioactivity Rate los *-
Mes steremen t l -
t l s l
9 w %
6 4 e
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.1 TABLE 3.14.2-1 (SNEET 3 0F 4) i
_RA010 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMEN Table Notations i
+ Monitor must be capable of responding to a Lower Limit of Detection of I x 10-' pct /ml.
- 0uring releases via this pathway.
"During main condenser offgas treatment system operation .
""Ouring operation of the main condenser air ejector.
ACTION 104 - With the number of chsanels OPERABLE less than required by the Minimum Channels OPERABLE requirement, ,
effluent releaset 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 />.
~
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 ttl e next semi-annual effluent release report.
(( ACTION 105 - With the number of channels OPERA 8LE less than' required by the Minimum Channels OPERABLE requirement, effluent releases tvia this pathway may continue, provided activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. grab samples are taken daily and analyzed daily f ,
With the number of main stack monitoring system channels OPERABLE less than required by the Minimum suspend Channels OPERABLE requirement, without de)ay depeII purge. - '
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 ef fluent release report.
ACTION 4106 - With the number of channels OPERABLE less than required by the Minimum Channels GPERABl.E requirement, continue provided: operation of the main condenser of fgas treatment system may (a)
Gas sampics within are 4collected the ensuing hours, oronce per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed (b)
Using a temporary hydrogen analyzer installed in the of fgas system line downstream. of the recombiner, hydrogen every concentration r,eadings are taken and logged 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, i
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- e TALL.E 2 't (Cont'd) 7 TABLE 3.14.2-1 (SHEET 4 0F 4) -
RA010ACTIE CASEOUS EFFLUENT WHITORING INSTROMENTATION
_ Table Notations (Continued)
If the number of channels OPERABLE remains less than [ '
required by the Minimum Channels OPERABLE requirement for , :
o.*er 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release. report.
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. ACTION 107 - t/f th the number of channels 0PERABLE less than '
I' required by the Minimum Channels OPERABLE requirement.
effluent releases via this pathway may continue, provided f 3 samples are contiruously collected with auxiliary sampling equipment for periods on the order of 7 days and analyzed i within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> ,af ter the end of the sampling period. '
! If the number of channels OPERABLE remains less than
- required by the Minimum Channel's OPERA 8LE requirement for over indoded 30 days, if theannext explanation of the circumstances shall be - '
semi-annual effluent release report. ,
i ACTION 108 - Wi>
he number of channels OPERABLE less than required by ? Minimue 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:
4 ' (
a.
The offgas system is not bypassea, and b.
The offgas post-treatment monitor (011-X615) or the main stack monitor (011-K600) is OPERABLE. - ;
I Otherwise, be in at least HOT STAN08Y within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
j If the n' umber of channels OPERABLE remains less than -
required by the Minimum Channels OPERA 8.LE requirement for over 30 days, an explanation of the circumstances shall be 1
included in the next semi-annual ef fluent release report.
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2.2 MEASUREMENT AND APPROXIMATIOtB OF 'IOTAL RADIOACTIVITY Waste gas release at Plant Hatch is confined to four paths: main stack (also called the offgas I vent), Unit I reactor building vent: Unit 2 1
l reactor building vent, and the reconbiner
- building vent. Each of these four paths is i continuously monitored for gaseous '
' radioactivity. Each is equipped with an i integrating-type sample collection device for ;
l collecting particulates and iodines. Sxnple i collection is in accordance with Technical l Specification , Tables 4.15. 2-1 (Unit 1) and 4.11. 2-1 (Uni *. 2 ) . Unless required more frequently under certain circumstances specified ,
in Table Notations to the above mentioned tables, i sanples are collected as follows: i
- 1. Noble gas samples are collected by grab >
sampling nonthly.
- 2. Tritium samples are collected by grab sampling monthly.
- 3. Radioiodine samples are collected by pullino i the sample stream through a charcoal i 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 i from the particulate filters collected over the previous quarter and the quarterly l composite sanple is analyzed for St-89 and 5 S t- 90, i
Sample analyses results and release tiow rates i from the four release points form the basis for '
calculating released quantities of '
radionuclide-specific radioactivity, dose rates 3 associated with gaseous releases, and cumulative l doses for the current quarter and year. This !
task is norna11y performed with oomputer 4 assistance.
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The noble gas grab sanple analysis results are i used along with msximtzn expected release flow rates from each of the four vents to calculate monitor setpoints for the gaseous effluent i
monitors serving the four release points, to 'i ascure 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 6 mnitor setpoints is described in the Flant Hatch ODCM.
With each release period released radioactivity, dose rates, and cumulative doses are calculated.
Cumulative dose Jesults are tabulated along with -
percent of Technical Specification limits (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. ;
After.each calendar quarter (13 weeks) a summary of waste gas releases from the four vents is empiled for preparation of the Semiannual Effluent Release Report required by Technical Specifications 6.9.1.8 and 6.9.1.9 and described in tRC 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 I The radionuclide-specific released radioactivity [
is determined from sanple 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 radiciodines, trititan, and particulates are calculated (with computer arsistance).
Calculated dose rates are ccinpared to the ow. <
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 radioiodine, tritium, and particulates. Dose rate calculation methodology is presented in the plant Hatch ODCM.
-29
]
1 Beta and ganma air doses due to noble gases are calculated for the location in the unrestricted area with the potential for the hiahest exposure due to gaseous releases. 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 dosas are ccmpared 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 i for each release period. Air dose calculation methocblogy is presented in the Plant .iatch CDW.
- 2. RADIOIODINE, 'IRITIUM, AND PARTIQJLATE RELEASES Released quantities of radioiodines are determined from the weekly semples and release flow rates for the four release points.
- Radioiodine concentrations are determined by ,
gama spectroscopy.
[ Released quantities of particulates are
, determined from the weekly (filter) samples and release flow rates for the four releasa points.
Gamma s;metroscopy is used to quantify concentrations of principal gama emitters.
After each calendar quarter the particulate filters from each vent are combined, fused, and strontium separatf on 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 3
[
mada back to the middle of the quarterly collection period. Where significant Sr-69 or i St-90 is not detected, LLD's are calculated.
Strontium concentrations are input to the cceposite file of the ccuputer to be used in 4
l release, dose rate and individual dose calculations. <
Tritium samles are obtained monthly from each ;
vent by passing the sample stream through a cold l 4
trap. The grams of water vapor / cubic foot gas is l reasured upstream of the cold trap in order to j i alleviate tnt. difficulties in determining water i vapor collection efficiencies. The trittum i
samles are analyzed by an independent laboratory i and results are furnit.hed in tci/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 individ al l
doce calculations.
i
.30-
Dose rates due to radioiodine, tritium, and particulates are calculated for a hypothet!. cal 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 c'J1culated 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 3.11.2.1.b (Unit 2) .
Individual doses due to radioiodine, tritium, and particulates are calculated for the critical receptor, which for Plant Hatch is a child exposed to the garden vegetation, inhalation, and ,
ground-plane pathways. Individual doses are '
calculated for each release period and cumulative totals are kept for each unit for the current calendar quarter wid year. Cunulative individual doses are compared te 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. GOSS ALPHA RELEASE 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 critium release.
_ -~ -. . . . - .
"The total or maximum error associatsd with ths :
etfluent measurement will include the cumulative errors resulting from the total operation of sampling cnd measurement. Because it my 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 overall estimate of the error associated with masurements of radioactive materials released in liquid and gaseous effluents and solid waste."
Estimted errors are based on errors in counting equipnent calibraticn, counting statistics, vent flow .,
rates, vent cample flow rates, norrsteady release rates, chemical yield factors, and samle losses for such items as charcoal cartridges.
(1) Fission and Activation Total Release was calculated from simple analysis results and' release point flow rates.
Statistical Error 60%
- Counting Equipment Calibration 10%
Vent Flow Rates 10%
Non-Steady Releaso Rates 204 1%i (2) I-131 Release was calculated from each Weekly sa@lo:
Statistical Error 60%
Counting Equipment Calibrat!.on 10%
Vent Flow Rates 10%
Vent Sample Flow Rates 10%
Non-Steady Release Rates 10 %
Losses From Charcoal Cartridge 10%
( 3) Particulates with half-lives greater than 8 days release was calculated from samle analysis results and release point flow rates.
Statistical Error at ILD concentration 60%
Counting Equipment Calbration 101 Vent Flow Rates 10%
Vent Sample Flow Rates 10%
Non-Steady Release Rates 10 %
Mt I
1 l
- l
( 4) Total Tritium Release was dominated by the !
reactor building vent tritium releases hence, the l larger statistical errors of the off-gas vent and recombiner building vent tritium releases do not i affect the error in the total tritium release:
r uter Vapor in Sa mle Stream Determination 20%
Vent Flow Rates 10 %
Counting Calibration and Statistics 10 %
Non-Steady Release 50%
SU t 2.3 GASEDW EFFLUENT RELEASE DATA 3egulatory Guide 1.21 Tables lA,18, and 1C are found in this report as Tables 2-2a-o, 2-3c-c, md 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 categories (fission and activation gases iodiness particulatest 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 terms of release rate in uCi/second but in terms of dose rate in mrem / year, as presented in Tecnnical Specif t. cations 3.15.2.1 (Unit 1) and 3.11. 2.1 ( Uni t 2) . Noble gases are limited as specified in 3.15.2.1.a and 3.11.2.1.a. The other three categories (tritium, radioiodines, and particul.stes; are limited as a qcoup as specified in 3.15. 2. '. .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 relaares and due to radioiodine, tritium, and particulates are presented in Table 2-5 along with per nt 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 gamrra air dosea, due to ncbla qases, are sp3cified 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 presn7ted in Tables 2-6a and 2-6b, along with percent of technical specification Ibnits.
t I
Limits for cumulative individual doses, due to radiciodine, 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 individual doses are presented in Tables 2-7a and 2-7b, with per nt of technical specification limits.
2.4 RADIOIOGICAL IMPACP DUE 'IO GASEDUS 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 radioicdine, tritium, and particulates 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 ,
Soecification 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.
Cumulative doses to an individual due to radiciodine, tritium , and particulates were calculated for each unit in accordance with Technical Specificatior,s 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 usina the methodalogy presented in the Plant !!atch Offsite Dose Calculation Manual, l'
l
-3L-
. _ - - . .=_ - . - _ - - - .
TABLE 2-2a '
E. I. HATCH tUCLEAR PLANT - UNIT 1 '
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1988 GASEQUS EFFLUENTS - SUMMATION OF ALL RELEASES i
l E.'I. Hatch Unit Quarter Quarter Est. Total !
Nuclear Plant 1 2 Error %
A. Fission & '
r Activation -
l' Gases I
- 1. Total C1 4.62E+02 6.59E+02 1.00E+ 02
, Release [
- 2. Average uCi/sec 5.87E+01 8.38E+01 !
- Release I Rate For Period !
- 3. % of Tech %
! Spec Limit i
- 3. Iodines i
- 1. Total Ci 1.17E-02 1.25E-03 1.10E+02 l Iodine-131 e 2. Average uCi/see 1.49E-03 1.58E-04 l Release '
Rate For i Period
- 3. % of Tech %
Spec Limit f i
C. Particulates j 1. Particulates ci 2.89E-03 4.68E-04 1.00E+02
] with half-lives 8 3 days .
- 2. Average uCi/sec 3.68E-04 5.96E-05 !
Release Rate For Period ;
- 3. % of Tech % !
1 Spec Limit
- 4. Gross Alpha C1 1.22E-06 1.90E-06 ,
Radioactiv-l l' ity t
D. Tritium i 1. Total Ci 6.52E+00 5. 26E+ 00 9.00E+01 }
i l Release
! 2. Average uCi/sec 8. 29E-01 6.69E-01 !
) Release
, Rate For I Pericd i
- *3. % of Tech % i
{ Spec Limit 6 l 1
!
- Technical Specification limits are in terms of dose rate
'. (mrem /yr) and dose (mrem). See Tables 2-5, 2-6a, 2-6b, j 2-7a, and 2-7b.
' j i
l
TABLE 2-2b E. I. HATCH NUCLEAR MAtc - UNIT 2 SENIANNUAL RADIOACTIVE EFFLUENT RELEASE RCPORT 1988 GASEQUS EFFLUEtCS - SUMMATION OF ALL RELEASES 1 E. I. Hatch Unit Quarter Quarter Est. Total Nuclear Plant 1 2 Error t l
A. Fission &
Activation Gases l
- 1. Total Ci 5. 24 E+ 02 1.46E+02 1.00E+02 Release l i
- 2. Averaoe uti/sec 6.67E+01 1.85E+01 1
Release Rate For Period
- 3. t of Tech %
Spec Limit i
- B. Iodinec i i 1. Total Ci 7.21E-03 1. 39E-03 1.10E+02
! Iodine-131 i-I 2. Average c01/sec 9.17E-04 1.77E-04 I l Release l i Rate For i Period I
- 3. % of Tech %
)
4 Spec Limit !
q
- C. Particulates
- i 1. Particulates Ci 7.12E-03 7.44E-04 1.00E+02 t
! with half-lives 8 1 l
j days !'
- 2. Average uci/sec 9.06E-04 9.46E-05 Release
! Rate For l Period
) *3. % of Tech ('
. Spec Limit I
- 4. Gross Alpha ci 8.57E-07 1.21E-06
, Radioactiv- l ity a
D. Tritium
- l. Total C1 $.94E+ 00 4. 95E+ 00 9.00E+01
! Release f
] 2. Average uCi/sec 7.55E-01 6.30E-01 1 Release
! Rate For !
i Period [
I
- 3. % of Tech %
] Spec Limit l>
l !'
i l
- Technical Specification limits are in terms of dose rate '
! (mreW yr) and dose (mrem). See hbles 2-5, 2-6a, 2-6b, i 2-7a, and 2+7b.
l l !
TABLE 2-2c
, E. I. HATCH t0 CLEAR PLANT - SITE SENIANtCAL RADIOACTIVE EFFLUENT RELEASE REPORT 1988 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES E. I. Hatch Unit Quarter Quarter Est. Total ~ i tJuclear Plant 1 2 Error %
A. Fission &
Activation f Gases
- 1. Total Ci 9.86E+02 8.04E+ 02 1.00E+ 02 l
- Relea m '
- 2. Average uCi/see 1.25E+02 1.02E+02 i Release !
Rate For -
1' Period j
- 3. % of Tech % ,
! Spec Limit l
? ,
- 3. Iodir.es :
- 1. Total Ci 1.89E-02 2.64E-03 1.10E+02 Iodine-131 ,
- 2. Average uCi/sec 2.41E-03 3.36E-04 Release a Rate For l Period
- *3. % of Tech %
Spec Limit i i C. Particulates
} 1. Particulates C1 1.00E-02 1.21E-03 1.00E+02 with half-
- lives 8 i days
- 2. Average uci/sec 1.27E-03 1.548-04 Release Rate For J
i Period j
- 3. % of Tech %
Spec Limit ;
- l
- 4. Gross Alpha Ci 2.07E-06 3.10E-06 l Radioactiv- t i ity I
D. Tritium I
- 1. Total Ci 1.25E+01 1.02E+01 9.00E+ 01 I
- Release
- 2. Average uCi/sec 1.58E+00 1. 30E+ 00 !
Release Rate For Period
- 3. % of Tech %
) Spec Limit
)
- Technical Specification limits are in terms of dose rate (mredyr) and dose (mrem). See Tables 2-5, 2-Ga, 2-6h, 2-7a, and 2-76.
1
4 . TABLE 2-3a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1988 GASEQUS EFFLUENTS - ELEVATED RELEASE
- Continuous Mode Batch Mode ** ;
4 Nuclides
- Released . Unit Quarter 1 Ouarter 2 Ouarter 1 Quarter 2
- 1. Fission :
Gases
- i K r-85 Ci 0.00E+00 0.00E+00 Kr-85m Ci 3.86E+01 1.41E+01 Kr-87 Ci 6.52E+00 2. 22E+ 00 ,
K r-83 Ci 5.36E+01 1.43E+01 :
Xe-133 Ci 8.69E+01 5.50E+01 Xe-135 Ci 2.01E+ 00 2.69E+00 Xe-135m C1 2.40E+00 4.94E+00 Xe-138 Ci 0.00E+00 9.64E+00 '
Xe-131m C1 1.35E+00 2.05E+00 ,
I '
Xe-133m C1 2.04E-01 1.05E+00 i
Xe-137 Ci 0.00E+00 0.00E+00 A r-4 ) Ci 0.00E+00 2.79E+00 TOTAL FOR j PERIOD Ci 1.92E+02 1.0 9E+ 02
- 2. Iodines T i
I- 131 Ci 4.78E-04 1.0$E-03 4 I-133 C1 1.61E-04 1. 33E-03 j I-135 Ci 1.77E-04 5.30E-04 TUIAL FOR PERIOD Ci 8.17E-04 2.91E-03
- 3. Particu-
. lates l I
2 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 t Co-60 Ci 3.62E-07 0.00E+ 00 2 n-65 Ci 9.15E-07 2.13E-06 l St-89 Ci 5.57E-05 4.64E-05 i St- 90 Ci 6.46E-07 8.85E-07 l Nb-95 Ci 0.00E+00 0.00E+00 :
, Cs-134 C1 1.99E-06 0. 00E+ 00 !
Cs-137 Ci 3.72E-05 1.58E-06 '
Ba-140 C1 2. 72E-05 7. 58E-05 !
La-140 Ci 4.19E-05 1.57E-04
! TOTAL FOR PERIOD C1 1.66E-04 2.84E-04 '
- 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 caseous release pathways at 4
Plant Hatch.
j TABLE 2-3b
, E. I. HATCH t0CLEM PLANT - UNIT 2 SENIANt0AL RADICACTIVE EFFLUENT RELEASE REPORT 1988 GASEDUS EFFLUENTS - ELEVATED RELEASE
- Continuous Mode Batch Mode **
Nuclides Released Unit Quarter 1 Quarter 2 Ouarter 1 Quart 9r 2 '
i
- 1. Fission Gases 4
Kr-85 Ci 0.00E+00 0.00E+00 -
Kr-85m Ci 3.86E+01 1.41E+01 i Kr-87 C1 6. 52E+00 2. 22E+ 00
- Kr-88 Ci 5.36E+01 1. 43E+ 01 Xe-133 Ci 8.54E+01 5.73E+01 1 Xe-135 C1 1.68E+ 00 3.18E+00 Xe-135m C1 2.40E+00 4.94E+00 l Xe-138 Ci 0.00E+00 9.64E+ 00 t Xe-131m Ci 1.35E+00 2.05E+00 !
Xe-133m Ci 2.04E-01 1.05E+ 00 :
+
Xe-137 Ci 0.00E+00 0.00E+00 l A r-41 Ci 0.00E+00 2.79E+00 TOTAL POR !
PERIOD Ci 1.90E+02 1.12E+ 02
- 2. Iodines '
l l I-131 Ci 5.36E-05 1.07E-03
- I-133 Ci 1.50E-04 1.34E-03
] I-135 C1 1.77E-04 5. 30E-04 l
2OIAL EDR PERIOD Ci 3.81E-04 2.94E-03
- 3. Particu-lates f l
t 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 3.62E-07 0.00E+ 00 i
Zn-65 Ci 9.15E-07 2.13E-06 I Sr-89 Ci 3.40E-05 5.45E-05 Sr- 90 Ci 3. 95E-07 1. 04E-06 Nb-95 Ci 0. 00E+ 00 0.00E+ 00 Cs-134 C1 1.99E-06 0.00E+00 Ce-137 C1 3.59E-05 1. 85E-06 Ba- 140 Ci 2. 72E-05 7.91E-05 La- 140 Ci 4.19E-05 1.60E-04 TOTAL FOR PERIOD Ci 1.43E-04 2.98E-04
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical lower limits of detection for caseous sample analyses.
I
- There are no batch mode radioactive gaseous release pathways at Plant Hatch. l 1
l
l 1 1 *
- TABLE 2-3c i
- 2. f. HATCH NUCLEAR PLANF - S8TE SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1988 l GASDOUS EFFLUENTS - ELEVATED RELEASE
- i Continuous Mode Batch Mode ** t i
Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2
- 1. Fission Gases Kr-85 Ci 0.00E+00 0.00E+00 Kr-85m C1 7.72E+01 2.83E+ 01 Kr-87 Ci 1.30E+01 4.44E+00
- Kr-88 Ci 1.07E+ 02 2.85E+ 01 Xe-133 Ci 1.72E+02 1.12E+02 Xe-135 Ci 3.69E+00 5.86E+ 00 Xe-135m Ci 4.80E+00 9.88E+ 00 >
Xe-138 Ci 0.00E+ 00 1.93E+ 01 <
Xe-131m Ci 2.70E+00 4.10E+00 ;
Xe-133m Ci 4.08E-01 2.09E+ 00 ,
- Xe-137 Ci 0.00E+00 0. 00E+ 00 !
l A r-41 Ci 0.00E+ 00 5.57E+00 ,
q ICIAL FOR i PERIOD Ci 3.81 E+ 02 2. 20E+ 02
- 2. Iodines
(
I-131 Ci 5.32E-04 2.12E-03 I-133 Ci 3.llE-04 2. 67E-03 i I-135 Ci 3. 55E-04 1.06E-03 IOTAL FOR
- PERIOD Ci 1.20E-03 5.85E-03 l t
4
- 3. Particu- i
(
i lates
! I cr-51 Ci 0.00E+00 0. 00E+00 [
l Mn-54 Ci 0.00E&OO 0.00E+ 00 -
Co-58 Ci 0.00E+00 0. 00E+ 00 Co-60 Ci 7. 24 E-07 0.00E+ 00 l Z n-65 Ci 1. 83E-06 4.26E-06 -
St-89 Ci 8.98E-05 1.01E-04 '
- S r- 90 Ci 1. 04E- 06 1.93E-06 l Nb-95 Ci 0.00E+ 00 0,00E+ 00 !
Cs-134 Ci 3.97E-06 0.00E+00 !
Cs-137 Ci 7.31E-05 3. 43E-06 l Ba-140 Ci 5.44E-05 1. 55E-04 l La-140 Ci 8. 3 BE-05 3.17E-04 I TOIAL FOR l PERIOD Ci 3. 0 9E-04 5.82E-04 l
- 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.
2 I **There are no batch node radioactive gaseous release pathways at Plant Hatch.
LO-
- _ - - . =-- -
TABLE 2-4a
, E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1988 GASD003 EFFLUENTS - CROUPD-LEVEL RELEASES
- i Continuous Mode Batch Mode **
Nuclides Released Unit Quarter 1 Ouarter 2 Quarter 1 Quarter 2
- 1. Fission G8SeS 1
. Kr-85 Ci 0.0GE+00 0.00E+00 Kr-85m C1 1.99E+01 3.02E-03 i
K r-67 Ci 3.24E+01 0.00E+00 Kr-88 Ci 0.00E+00 0.00E+ 00 [
Xe-133 Ci 7. 4 2E+01 5.36E+02 Xe-135 Ci 9.15E+01 1. 37E+ 01 I Xe-135m Ci 5.16E+01 0.00E+ 00 Xe-138 Ci 4.97E-01 0.00E+ 0u Xe 131a ci 0.00E+00 0. 00E+00 i Xe-133m Ci 0.00E+ 00 0.00E+00 f 4
Xe-137 Ci 3. 3 2E-02 0.00E+00 l
A r-41 Ci 0.00E+ 00 0.00E+ 00 !
TOTAL 00;R '
PERIOD Ci 2.70E+02 5,50E+02 i
j 2. Todines i
i I-131 C1 1.12E-02 1.94E-04 >
! I-133 Ci 2. 3 3E-03 2.69E-04 I I-135 Ci 2.12E-04 0.00E+ 00 '
TOTAL FOR '
PERIOD C1 1. 3 8E-02 4.63E-04 -
4 i j 3. Particu- I lates I Cr-51 Ci 2. 87E-05 4. 66E-05 !
Mn-54 C.1 7.08E-06 2. 06E-06 Co-58 Ci 1. 7 4E-05 6.28E-06 !
Co-60 Ci 5.56E-05 1.35E-05 2 n-65 Ci 2.47E-04 1. 06E-04 i St-89 C1 4.69E-05 1.70E-06 i St-90 C1 2.5 4E-07 0. 00E+ 00 i Nb- 95 C1 1.10E-09 0.00E+ 00 l Cs-134 Ci 7.6BE-04 0.00E+00 Cc-137 Ci 8.47E-04 8. 20E-06 i iu-140 C1 2. 7 7E-04 0. 00E+ 00 La-140 Ci 4.33E-04 0.00E+ 00 TOTAL EDR PERIOD Ci 2.73E-03 1. 95E-04 ..
- 2eroes 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 tatch mode radioactive gaseous release pathways at Plant Hatch.
ki-
~
TABLE 2-4b I i
- E. I. HAICH t0 CLEAR PLANI - UNIT 2 !
SENIANNJAL RADIOACTIVE EFFLUENT RELEASE REIORT 1988 l GASEDUS EFFLUENTS - @0Uto-LEVEL RELEASES * !
~ Continuous Mode Batch M3de** [
t Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2
- 1. Fission Gases Kr-85 Ci 8.81E+01 0. 00E+ 00 ;
Kr-85m Ci 7.56E+00 0.00E+00 Kr-87 Ci l 2.92E+01 0. 00E+00 Kr-88 C1 1.69E+01 0.00E+00 ;
Xe-133 Ci 8.24E+01 2. 06E+01 i Xe-135 Ci 8.58E+01 1.32E+01 i j Xe-135m Ci 2.45E+01 0.00E+ 00 '
Xe-138 Ci 0.00E+00 0.00E+ 00 ,
Xe-131m Ci 0.00E+00 0.00E+ 00
. i Xe-133m Ci 0.00E+00 0.00E+00 l Xe-137 Ci 0.00E+00 0. 00E+ 00 ,
A r-41 Ci 0.00E+00 0.00E+00 MAL FOR l PERIOD Ci 3.35E+02 3. 382+ 01 t I !
- 2. Iodines '
i
- I- 131 Ci 7.16E-03 3.25E-04 t
- I-133 Ci 4.55E-03 1. 35E-03 I I- 135 C1 1.96E-03 1.45E-03 WTAL EDR I PERIOD C1 1.47E-02 3.12E-03 i 4 !
- 3. Particu- i i
- lates -
1 4 C r-51 Ci 4.99E-05 0.00E+00 i Mn-54 Ci 2.79E-05 0.00E+ 00 Co -58 Ci 1.96E-04 0. 00E+ 00 Co-60 Ci 2.440-04 0.00E+ 00 i 2n-65 C1 2.81E-03 1.24E-06 (
St-89 Ci 6.77E-04 1.35E-04 Sr-90 !
Ci 1. 47E-06 3. 58E-07 i Nb-95 Ci 3.65E-05 0.00E+ 00 I
- Cs-134 C1 2.70E-04 0. 00E+ 00 !
, Cs-137 Ci 3.01E-04 3.57E-06
M AL FOR j PERIOD Ci 6.98E-03 4.46E-04 {j t
1
- Zeroes in this table indicate ttut no radioactivity uns present l i
l above detectable levels. See Table 2-8 for typical lower limits of ;
detection for gueous sample analyses. '
- There are no batch rode radioactive gaseous release pathways at
, Plant Hatch. ,
l
- - _ - . . . . _ - _ . .- - ._ - . . _ - . - .-_ _. -_-~
TABLE 2-4c j E. I. HATCl! 10 CLEAR PLANI - SITE t SENIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1988 (
GASEQUS EFFLUEt(IS - 200!O-LEVEL RELEASES
- i i
Continuous Mode Batch Madc'* l Nuclides
, Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 l
- 1. Fission i l Gases :
i
(
Kr-85 Ci 8.81E+01 0.00E+00 i f(r-85m Ci 2.75E+01 3.02E-03 !i Kr-87 C1 6.17E+01 0.00E+00
~ i Kr-88 Ci 1.69E+01 0.00E+00 j :
Xe-133 C1 1. 57E+02 5.36E+02 1 Xe-135 Ci 1.77E+02 4. 75E+ 01 '
, Xe-135m Ci 7.61E+01 0. 00E+ 00 4 Xe-138 C1 4.97E-01 0.00E+ 00 l Xe-131m Ci 0. 00E+00 0. 00E+ 00 Xe-133m Ci !
! 0.00E+00 0.00E+ 00 !
! Xe-137 Ci 3.32E-02 0. 00E+ 00 l q A r- 41 Ci 0.00E+00 0. 00E+ 00 j
'!UTAL FOR PERIOD Ci 6.0SE+02 5.84E+02 ?
i i
- 2. Iodines
~
\ p I-131 Ci 1.84E-02 5.19E-04 I-133 C1 6.88E-03 1. 62E-03 I-135 Ci 3.17E-03 1.45E-03 I
! 'IUIAL fDR PERIOD C1 2.84E-02 3.58E-03 I
l
- 3. Partico- I t
lates j
Cr-51 Ci 7.8 6E-05 4. 66E-05 !
Mn-54 Ci 3.50E-05 2.06E 00 !
Co-58 Ci 2.13E-04 6.2GE-06 Co-60 l C1 2.99E-04 1.35E-05 v Zn-65 C1 3.06E-03 1. 07E-04 [
j >
Sr-89 Ci 7.24E-04 1.37E-04 j Sr-90 2
C1 1. 73E-06 3. 58E-07 Nt>- 95 C1 3.r5E-05 0.00E+ 00
, Cs-134 C1 1.04E-03 0. 00E+ 00 Ce-137 Ci 1.15E-03 1.18E-05 l 12-140 C1 1.24E-03 1.85E-04 l- La-140 Ci 1.84E-03 1.20E-04 l EAL fDR
.)
ERIOD Ci 9.71E-03 6.3aE-GJ-i
- Zeroes in this table indicate that no radtoactivity was present above detectable levels. See Table 2-8 for typical lower limits of
- detection for gaseous sample analyses.
- There are no batch rode radioactive gaseous release pat"ways at Plant Hatch.
,u, ,
)
. TABLE 2-5 E. I. HATCH tCCLEAR PLANr - SITE SENIAN!UAL RADI0 ACTIVE EFFLUEffr RELEASE REIORT 1988
- GASEOUS E7FLUEffrS - DOSE RATES Dose Rates Dua to Noble Gases Orcan Tech Unit Quarter % of Quarter % of 1 Spec 1 Tech 2 Tech !
Limit Spec Spec Limit Limit TBody 500 mreW yr 1.35E+00 2.71E-01 2.33E-01 4.67E-02 Skin 3000 mredyr 2.89E+00 9.63E-02 5.35E-01 1.78E-02 t i t i
a Dose Rates Due to Radiciodine, Tritium, and Particulates
- Orqan Tech Unit Quarter % of Quarter % of !
Spec 1 Tech 2 Tech ,
l Limit Spec Spec '
Limit Limit t ,
! Bone 1500 mreW yr 3.78E-03 2. 52E-04 2.14E-04 1. 43E-05 Liver 1500 mreWyr 1.84E-02 1.23E-03 1.22E-02 8.13E TBody 1500 meeWyr 1.61E-02 1.07E-03 1.21E-02 8. 07E-04 j Thyroid 1500 mrev yr 3.61E-01 2.41E-02 2.79E-02 1.86E-03 l 1
Kidney 1500 mreWyr 1.76E-02 1.17E-03 1. 22E-02 8.13E 04 '
l
~
Lung 1500 mreW yr 2.53E-02 1.69E-03 1.30E-02 8.67E-04 i GI-LLI 1500 meeWyr 1.58E-02 1.05E-03 1.22E-02 8.13E-04 i
i
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TABLE 2-64 E. I. HATCH tCCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1988 AIR DOSES DOE TO !OBLE GAS RELEASES 5 '
cumulative Doses Per Ousrter Type Teen Unit Quarter 4 of Quarter % of 1 of Spec 1 Tech 2 Tech Radi- Limit Spec Spec ation Limit Limit
.1 Gamma 5.0 mrad 1. 63E-01 3.26E+00 5.81E-02 1.16E+00 -
I Beta 10.0 mrad 1.91E-01 1.91E+00 1.59E-01 1.59E+00 ,
I !
i Cumulative Doses Per Year ;
Tyre of Teen Unit Quarters t of Teen ;
i Radiation Spec 1&2 Spec Limit ,
- Limit l Gamma 10.0 mrad 2.21E-01 2.21E+00 Beta 20.0 mrad 3.50E-01 1.75E+ 00 ;
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. l TABLE 2-6b E. I. HATCH tFJCLEAR PLATE - UNIT 2 SEMIANNUAL RADICACTIVE EFFLUEtE RELEASE REPORT 1988 l AIR DOSES DUE 'IO tOBLE GAS RELEASES Cumulative Doses Per Quarter Type Toch Unit Quarter t of Quarter % of of Soec 1 Tech 2 Tech Radi- Limit Spec Spec I l
stion Limit Limit Gama 5.0 mrad 1.94E-01 3.88E+00 9.58E-00 1.92E-01 Beta 10.0 mrad 2. 27E-01 2.27E+00 1.46E-02 1.46E-01 Cumulative Doses Per Year Type of Tech Unit Quarters % of Tech i
1 Radiation Spec 1&2 Spec Limit '
Limit Gama 10.0 mrad 2.0iE-01 2.04E+00 ,
Beta 20.0 mrad 2. 4 2E-01 1.21E+00 l
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TABLE 2-7a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIAN! CAL RADIOACTIVE EFF:.UENT RELEASE REPORT 1988 INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM, AND PARTICULATES IN GASEDUS RELEASES ;
Cumulative Dose Per Quarter !
Organ Tech Unit Quarter 4 of Quarter % of l Spec 1 Tech 2 Tech f Limit Spec Spec !
Limit Limit i Bone 7.5 mrem 1.02E-02 1.36E-01 3.03E-04 4.04E-03 Liver 7.5 mrem 1.25E-02 1.67E-01 1.54E-03 2.05E-02 Tot. Bod / 7.5 mrem 1.19E-02 1.59E-01 1.53E-03 2.04E-02 Thyroid 7.5 mrem 7.22E-02 9.63E-01 3.45E-03 4.60E-02 '
Kidney 7.5 mrem 1.14E-02 1.52E-01 1.53E-03 2.04E-02 -
1 Lung 7.5 mrem 1.09E-02 1.45E-01 1.54E-03 2.05E-02 f I GI-LLI 7.5 mrem 1.07E-02 1.43E-01 1.53E-03 2.04E-02 l i
Cumulative Dose Per Year i
Organ Tech Unit Quarters % of Tech I Spec 1&2 Spec Limit ;
j Limit !
- Bone 15.0 mrem 1.05E-02 7.00E-02 i
! Liver 15.0 mrem 1.40E-02 9.36E-02 i j Total Body 15.0 mrem 1.34E-02 8.95E-02 ['
Thyroid 15.0 mrem 7.57E-02 5.04E-01
) Kidney 15.0 mrem 1.29E-02 8. 62E-02 l Lung 15.0 mrem 1.24E-02 8. 29E-02 l GT-LLI 15.0 mrem 1. 2 2E-02 8.15E-02 l i
f l
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TABLE 2-7b (
E. I. HATCH tUCLEAR PLATE - UNIT 2 SENIANtCAL RADIOALTIVE EFFLUEtC RELEASE REIORT 1989 l INDIVICUAL DOSES DUE 'IO RADIOIODINE, IRITIUM,
-l Ato PARTICULATES Ill GASEDUS RELEASES t i
Cumulative Dose Per Ouarter
- . i Oraan Tech Unit Quarter % of Quarter % of l Spec 1 Tech 2 Tech !
1' Limit Spec Spec !
Limit Limit .
Bone 7.5 mrem 8.59E-03 1.15E-01 2.34E-04 3.12E-03 '
Liver 7.5 mrem 9. 72E-03 1.30E-01 1. 22E-03 1.63E-02 !
Tot. Body 7.5 mrem 9. 38E-03 1.2SE-01 1.22E-03 1.63E-02 Thyroid 7.5 mrem 4. 90E-02 6.53E-01 4.2SE-03 5.67E-02 t Kidney 7.5 mrem 9. 29E-03 1.24E-01 1.22E-03 1.630-02 !
Lung 7.5 mrem 9.66E-03 1. 2 9E-01 1.27E-03 1.69E-02 t
, GI-LLI 7.5 mrem 9. 30E-03 1.24E-01 1.26E-03 1.68E-02 ,
i
- Cumulative Dom > Per Year ,
Organ Tech Unit Quarters % of Tech '
Spec 1&2 Spec Limit !
Limit '
Bone 15.0 mrea 8. 62E-03 5.89E-02 !
Liver 15.0 mrem 1.0 9E-02 7. 29E-02 '
Total Body 15.0 mrem 1.06E-02 7. 07E-02 i Thyroid 15.0 mrem 5.33E-02 3.55E-01 i Kli. / 15.0 mrem 1.05E-02 7.01E-02 Lung l 15.0 mrem 1.0 9E-02 7. 29E-02 :
GI-LLI 15.0 mrem 1.06E-02 7.042-02 P i
I i
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l i
i I
l
_LS.
TABLE 2-8 IfWER LIMITS OF DETECTI0tt - GASEDUS SAMPLE At& LYSES The values in this table represent seriori lower limits of -
detection (LLD) which are typics11y achieved in laboratory azulyses of gaseous radsaste samples.
PADIOtUCLIDE LLD UtJITS Kr-87 1.31E-07 uCi/ml i
Kr-88 2.10E-07
, Xe-133 1.62E-07 i Xe-133m 6.075-08 Xe-135 5.77E408 Xe-138 2.85E-06 l l !
I-131 4. 37E- 14 !
I-133 6.16E-13 r t
Mn-54 2.78E- 14 Fe-59 4.62E-14 l Co- 58 2. 46E- 14 :
co-60 2.88E-14 i Z n-65 7.51E-14 3 Mo-99 6.02E-13 l Cs-134 3. 64E- 14 i Cs-137 2.88E-14 Ce-141 4.94E-14 Ce-144 2.02E- 13 t 4 Sr-89 1.17E- 14 S t-90 3. 82E- 15 j H-3 5. 82E- 12
[
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- 3. SOLID WASTE 3.1 REGULATORY REQUIREMENTS The Technical Specifications presented in this 1 section are for Unit 1. Requirements for Unit 2 l are the same as for Unit li however, the :
Technical Specification numbers are not the same. l TECHNICAL SPECIFICATIO!G i
3.15.3.1 The solid radwaste system sball be used in accordance with the M10 CESS CO!?IROL 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 Cffluent Release Report shall include the following information for each type of solid waste '
shipped offsite during the report period:
- a. Container volume I 4,
- b. Total curie quantity (specify whether determined by measurement or estirate)
- c. Principal radionuclides (specify whether determined by measurement or estimate) '
- d. Type of waste, e.g., spent resin, compacted dry !
waste, evaporator bottoms
) e i
- e. Type of container, e.g., LSA, type A, type B, large quantity t
- f. Solidification agent, e.g., cement.
l 3.2 SOLID WASTE DATA Regulatory guide 1.21 Table 3 is found in this report as Table 3-la, and 3-lb. '
i i
-St-i
TABLE 3-la EFFLUEtE AND WASTE DISEOSAL SEMIANNUAL REPORT (YEAR)
JANUARY - JUNE, 1988 SOLID WASTE AND IRRADIATED FUEL SHIPMEtES FOR UNIT I AND II l l 1 l I
l 1. Type of waste l UNIT l 6 monthlEst. Totall l
l l Deriod i ERROR 5 _l j
- a. Spent resins, filter studges, evaporator l l n nrEn ;
mJ l
l bottoms, etc. I Ci I ,.2/E 7 1 2. c0 E , l
- b. Dry :ompressible waste, contaminated l mJ l n. ore n I l eauip. etc. I Ci l 2. rrE n 1 .-nE, l
- c. Irradiated components, control rods, l m3 I~ . E I l etc. l Ci I . E I . E l
'.,rEn I l j d. Other (describe) l m4 l l eaufp. etc. CF.D Filters i Ci I L. - E n I .cn E, l
- 2. Estimate of major nuclide composition (by type of waste)
ISOTOPE l PERCENT l CURIES l l
1 l l l _
l 8. "n 6 R l 27.10 l 105.76 _,l l
l _, Cr-117 l 21.20 l 2D5.12 l l r r -1?L l 15.?O I 2bb.ca l 0+har l 31.40 l b27.04 l l
l b. rn +4 l L0.20 l 1.41 l cn*n l 1.,.10 l 1.19 l l
l 0 . %- l l r e -1?? l Y JO l 0+har l 10.50 l 0.E5 l l c. l 1 l
!U A l l l l
i l l 1
l l 1 l
- d. L'c-e u l .L.7 l 1.c6 l l
Fe ' k l J1.7 l U.91 l l
Zn t-' l 16.6 l 0.ekr l l
l !3-9' l 4.0 l 0.JO l l n+her l le,u l o.us l
- 3. Solid Waste Disposition Number of Shipments, Mode of Transportation Destination 3a Cack inrnwell 12 "an (Icx) Isrnve11 B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shioments Mode of Transportation Destination ,
- A !;A
- :A
(_-. -_- - .-.- - _- _._ - --- __ . - - _ . _ . - .. . _ _ - - -. - - . . .
~ '
\
Jcnuary 1 - Jtme 30 EFPLUErff AfD WASIE DISPOSAL SEMIAfRCAL REIORr(YEAR) 1988 SOLID WASTE AND IRRADIATED FUEL SHIPMErff .
10R UNIT I & II TABLE 3-1B TY1E OF CURIE PRINCIPLE BURIAL NUMBER OF VOLUPE OF TYPE SOLIDIFICATION WASTE QUAttrITY/ f0CLIDES/ CDffrAINER (DNTAINERS EAOi (DN- SHIPPING AGENT DETERMINED Df'rERMINATION DESCRIPr?? SIIIPPED TAINER Ft 3 (DNTAINER DEMATERED 4S.89 Zn-65,Cs-134,Cs-li 14-210 GL 9 199.4 LSA, TYPE A None RIT;IN MEASURED Co-60 MEASURED _
DEWATERED 948.34 Zn-65,Cs-134,Cs-13 7,10-142 HIC 6 132.4 LSA, TYPE B tbne RESIri MEASURED Co-60 MEASURED DEWATERED 368.42 Zn-65,Cs-134,co-13 7,14-210 HIC 22 202.1 LSA, TYPE A None RESIN MEASURED Co-60 MEASURED (DPU%CTED 3.50 In-65,Cs-137, Steel B-25 109 95.2 LSA,S'It None DAN ESTIMATED Fe-55 MEASURED ST CRD 4.20 Co-60,Fe-55, Medium - 2 1 38.3 LSA, TYPE A tbne FILTERS ESTIMATfD Zn-65 MEASURED HTC Ovarpick l
t tbtes: SIC - Strong tight cointainer l
l f HIC - High integrity container ISA - Low specific activity GL - Carbon steel liner i
s k
l i
L
. , _ _ - _ _ _ _ ~ ~ - - _ ~ - ~ , , - - - , - - - #, - . -,,--. , - - , - - - . - - , - , - - - - - . - . . - . . . - - - . - , - . - -
- 4. CHAfK;ES IN THE RADIOIOGICAL EtNIROtNEtTTAL tDNI'IDRIlG FROGRAM In the Semi-annual radioactive effluent rolesse report for the second half of 1987, it was reported pursuant to Technicial Specification 3.16.1.c. that milk had becane unavailable during the third quarter of 1987 4t C1. ark's Farm which is in the NM sector at 4.8 miles and that efforts m3de to find a replacement sample were fruitless. It was also reported that it was expected that milk would again be available at this location in six months or so. As a consequence of regular follow-up inquiries to the Clarks, it was learned that milk again had become available collections resumed during the second quarter of 1988.
1 I
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- 5. CHAtES TO THE PLAtTT HATCH ODCM i Technical Specifications 6.9.1.8 and 6.9.1.9 require in cart that changes to the Plant Hatch Offsite Dose Calculation Manual (ODCM) be reported to the '
Commission in the next Semi-annual Ef fluent Release Report.
On January 28, 1988, the PRB recommended aporoval of changes to the Plant Hatch ODCM pertaining to changing the location of the critical receptor for caseous releases. These changes became effective for the first quarter of 1988.
A change in the location of the critical receptor was the result of changes in land use in the vicinity of Plant Hatch, that was noted during the land use survey i as required by HNP Technical Specification 3.16.2. !
Since new vegetable gardens were observed, potential dose assessments were performed to evaluate other potential locations based on the land use survey. The ;
critical receptor identified in this revision to the ODCM was identified as a result of these potential dose assessnents. Documentation of PRB review and approval of these changes is presented in Appendix A ,
of this report.
Appendix 3 of this report contains the nadified pages t of the Plant Hatch ODCM discussed in Appendix A.
These modifications to the Plant Hatch ODCM are identified as Revision 4. i i
t
-5L-
. l 4
1 0
1 Georgia Power Company .
Plant E. I. Hatch :
Semi-annual Report Plant Radioactive Ef fluent Releases January 1 through June 30, 1988 !
t
! Appendix A I l
J l l
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r 1
l 3
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l GEORGI A POWER COMPANY l l
- l lP , ANT E. 1. HATCH l l PAGE 1 0F 2 l lF0RM TITLE: -
l l OOCUMENT CHANGE RE0 VEST _ l l CHANGE AFFECTS: ( ) UNIT ONE ( ) UNIT TWO (d UNITS ONE AND TWO l l1 l ll REQUEST DATE : / - 2' / - 8 8 REQUEST NO.: 88-0.3 REVISION NO. O l ll 1 REQUEST INITIATED: ( ) ON-SITE, ( OFF SITE BY: S. 6. L <_ro,/d~
ICl l (Ll DOCUMENT (S) AFFECTE0: O/# s,fe Nse /% le u litilon hnaa / <
l IEl _..
- l' l lAl l I lRl SECTION/ TITLE : % Ale 2. 2-12 toAltrolt w e cecarra ? Tible_ t.7. i L l i l I sure c.,seu: r e. fe ,t n nAu& h wes rb M uses m rarnant FArmC' FNf5? GGuME&i$1
' ~
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lAl DESCRIPTION OF PROPOSED CNANGE (ATTACH'MARKE0 UP COPY OF AFFECTED 00CUMENT(s)) . l lFl r n d - <r e is fien e, / h m e.wwd e /u nes n eents>%d in A rrAem.o r 2 . _ l lEl m ends ce e n f a l., N lTl
, , , si r eb k - r ,, + s
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l lNI REASON FOR CHANGE : TE,* rw se,3 < ver theu 1,re oa w d e A & nors are l l0l ti~n ta d e d a /nte e RS-Mit s. c. Fw k ' rs' s z ms g 'kled 1 4. e1 t_cre.), l '
ll TA , < A* F&r. r< ?4? Aors t n a o 'e* e/ f A He r h m uf_ _ l. ' ' l.
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, lPl ENVIRONMENTAL IMPACT STATEMENT REQUIRED: ( ) YES (> 4 NO l lll DESCRIBED IN FSAR: (><3 YES ( ) NO l j l1l UNREVIEWE0 SAFETY QUESTION: ( ) YES ( M NO '$ " i8 7 M f/y,I [.* !
lAl PRIORITY: ( ) EMERGENCY RELIEF ( ) RELOAD LICENSING (X INDIVIOUAd SUBMITTAL l i
(Nl .
d l 1 lCl NO. ATTACHMENTS: t I
ll Sh hv NSC MEMBER ii-?/ BS DATE bW NSC SUPERVISOR i /-2/-tr DATE AL L. I r hr/st l l MANAGER'iSC OATE l l l i i !
lI l l
l l '
l l l lI FORWARD TO PRB SECRETARY FOR INITIAL PRB REVIEW d d " / #/- PJ KS l I I1 -
I !
1 l l PRB RECOMMENDS CHANGE: ( /) YES ( ) NO .YI - ' 'I / ' t - :2 J - A l IPl PRB MEETING NO. DATE l IRl IF NO, GIVE REASON: l lBl l
l l 1
l-l---.---..-.
II REQUEST: ......------....]
( Y APPROVED ( ) OISAPPROVED l l1 l
lPl IF O! SAPP OVEO, GIVE REASON:
lMi <^ '
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l ; . f.4 -c.' '
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Il PEENT' MANAGE'R "0 A T E' -
u (N6-00is Rev, i 802.t3 I
i 40At--:6-vva-os n
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4
$ ATTACHMENT 2
( DISCUSSION OF PROPOSED ODCM CHANGES t
I
( ;
- 1. Table 2.2-12 was modified to incorporate changes in the location, age .
- I group and dispersion and deposition factors for the new critical f
( receptor. Also, the Annual Land Use Census was changed to the Annual Land j i -
Use Survey to be consistent with the Technical Specifications. l
\
< !!. Sheet 2 of Table 2.2-13 was modified to provide site specific values for !
fractions of annual intakes of locally grown leafy vegetation and stored i vegetation. As a follow-up to the land use survey, it was learned from
! the owners of the garden that the garden is maintained for only two months i 7
- during the year, t
i !
4 i
1 .
. _ i :
" . _ . g q f, D G. f...._; , A t , Iso._ -h *k -'"
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. ,. v .'E.K ie"-
' .1 ~-$ .
f; A ..g ;j:cui li * . g* ]d
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\. t TABLE 2.2-12 -
2 CONTROLLING REFEPTOR (To support subsection 2.2.2.b) j
< t The 1ccation and exposure pathways associated with the controlling receptor' g are determined based on information obtained during the Annual Land Use hvAgt;;:.* Dispersion and deposition values were calculate for the location i of the controlling receptor based on the HNP site meteorological data collected for the period 1984-1986.** lp' ;
I, I Location: SW at 3,4 mi'As J ,. !
Age Group: C$tt44 M i l Exposure Pathways: Inhalation, ground-plane, and garden vegetation '"-
Dispersion and Deposition Values for this location: i Ground-level
{< .
y 4.!i7F-l 4 (X/Q')vp = '.000 L m L
I.70 E-7 T 1
(0/Q')vp = Ih73E-i- m Elevated R 6
).4iE-3 4 (X/0')sp = M I ,- a i
3.b C\ E J1 1
( 0/0 ' ),p = hSM-10 7 l t
1
- Ref erences. M=eneit.)D i
- Ref erence M.)l !
i r
6S C3 i .3 l
l l
HATCH 00CH REV E 8/87 2.2-47
, , s TABLE 2.2-13 (SHEET 2 0F 3) .
i -
SITE-SPECIFIC (OR DEFAULT) VALUES TO '
BE USED IN PATHWAY FACTOR CALCULATIONS * 'f Pa ra,!!g.tet Description Value Grass-Cow-Meat (continued)
(OFL)1ja Ingestion dose factor for age group Tables 2.2-6 thru 2.2-8 j Yp Pasture grass areal density 0.7 kg/m8 * ~i Ys Stored feed areal density 2.0 kg/m8 I l
fp Fraction of year that cow grazes on pasture
,9 f 1.0 fs Fraction of total feed that is ~
pasture grass while cow is on cc] i 4
pasture W c:
1.0 ,J; (: i H
Absolute humidity of the atmosphere 8.0 gm/m8 5';
i Garden Vegetation :N k .d
- s. .
Yy
, Garden vegetation areal density 2.0 kg/m8 ,e F.
s
- - l ..
Dat Leafy vegetation consumption rate
]o for age group I
. L!
- Table 2.2-10 b (1.'. l t
- Uas Stored vegetation consumption rate for age group Table 2.2-10
, l (OFL)1ja Ingestion dose factor for age groups Tables 2.2-6 c, i thru 2.2-8 !
fg ,
Fraction of annual intake of i
leafyyeget,tiqngrownlocally W 0. l ~1 !
1 f Wb df ')
Fraction o annual intake of \
L
! stared vegetation grown locally k?6 0.13 l.lj ut}mp* l i H l Absolute humidity of the atmosphere 8.0 ge/m8
]
Grass-Goat-Milk {
4
)
QF Feed consumption rate for epat 6.0 kg/ day U ap Milk consumption rate for age group Table 2.2-10
' Supports Section 272.2.b.
l t HATCH 00CM. REV 24 e/W l /'(? 2.2-43 1
1
______._____________.________________.A___________
' REFERENCES (Continued)
- t-Q 14 Hatch Nuclear February 1987. Plant Land Use Survey - 1987. Georgia any, Power Com
(
)
- 15. (
D.C., .ay_
Washington, Letter 11, to 1987.
Georoia Power Company f rom Pickard. I L
- 16. (
D.C., June 3, 1967. Letter to Georcia Power Comoany . Inc._, from Pick 17.
(
D.C., JuneLetter Washington, to Georcia 11, 1987.
Power Company . and from Pickard.
Garrick. Inc. Lowe
/
18.
Company, June 9,1987,_ Internal Memorandum. W.H. 011incer to 0 i
19.
Letter toJune Georgia, Georaia 17, 1987.Power Company f rom Ouantum Technoloov .
Inc., Marietts,
%q , M / A 77
.4) .
Q 3I 2 f< heegs b % g / w P d a. L
% kw4, 4 . , Irv
,1c. , hm 3 0,in ,
a ..s.m.ab .. ' a. .. ..- 8 b
_Q_N t
) j , ', *,' * , , , ), ; ' ' ' ;'h.h _ _ -- - -- - -- ~
) .5 t
_ . . . ,, . .. ---~
4 l/77 HATCH 00CM. REV 3. 8/87 o
, i Georgia Pcwer Company Plant E. I. Hatch Semi-annual Report Plant Radioactive Effluent Releasas January 1 thcough June 30, 1988 Appendix B
~ ~ - - -
. . . . . .. .. ,. , i. .. .
.,. , I
- 1 TA8LE 2.2-12
/ CONTROLLING RECEPTOR -
(To support subsection 2.2.2.b)
The location and exposure pathways associated with the controlling receptor are determined based on information obtained during the Annual Land Use Survey.* Dispersion and deposition values were calculated for the location of the controlling receptor based on the HNP site meteorological data collected for the period 1984-1986.**
Location: SW at 1.1 miles Age Group: Adult Exposure Pathways: Inhalation, ground-plane, and garden vegetation Dispersion and Deposition Values for this location:
Ground-level sec (X/Q')y, = 4.58E-6 m' 1
(0/Q')y,= 1.90E-8 m'
(' Elevated
_s ec (X/Q')3p = 1.46E-7 m' 1
(0/Q')3, = 3.29E-9 m'
- Reference 20. l
- Reference 21. '
l l
l
, \
(
HATCH 00CH, REV 4 2/88 2.2-47 l l
m.
?,* .
- s l
TABLE 2.2-13 (SHEET 2 0F.3)
{
- SITE-SPECIFIC (OR DEFAULT) VALUES TO l BE-USED IN PATHWAY FACTOR CALCULATIONS * !
l Parameter Description Value Grass-Cow-Meat (continued)
(DFL)ija Ingestion dose factor for age group Tables 2.2-6 ,
thru 2.2-8 Yp Pasture grass areal density 0.7 kg/mi Ys Stored feed areal density 2.0 kg/m*
fp Fraction of year that cow grazes on pasture 1.0 fs Fraction of total feed that is pasture grass while cow is on pasture 1.0 -
H Absolute humidity of the atmosphere 8.0 gm/m8 #
Garden Vegetation f Yy Garden vegetation areal density 2.0 kg/m8 Uat Leafy vegetation consumption rate for age group Table 2.2-10 Uas Stored vegetation consumption rate for age group Table 2.2-10 (OFL)ija Ingestion dose factor for age Tables 2.2-6' groups thru 2.2-8 ft Fraction of annual intake of leafy vegetation grown locally (Site specific) 0.17 fg Fraction of annual intake of stored vegetation grown locally (Site specific) 0.13 H Absolute humidity of the atmosphere 8.0 gm/m*
Grass-Goat-Milk Qp Feed consumption rate for goat 6.0 kg/ day
( Uap Milk consumption rate far age group Table 2.2-10
- Supports Sectior. E2.2.b.
HATCH 00CM, REV 4 2/88 2.2-49 w..,,,,,,----,- ,---w wn
O REFERENCES (Continued)
- 14. Hatch Nuclear Plant Land Use Survey - 1987, Georgia Power Company, February 1987.
- 15. Letter to Georcia Power Company f rom Pickard. Lowe. and Garrick. Inc. ,
Washington, D.C., May 11, 1987.
- 16. Lettar to Georaia Power Company f rom Pickard. Lowe, and Garrick. Inc. ,
Washington, D.C., June 3, 1987.
- 17. Letter to Georaia Power ComDany f rom Pickard. Lowe, and Garrick. Inc. ,
Washington, D.C., June 11, 1987.
- 10. Internal Memorandum. W.H. 0111ncer to 0.M. HoDDer, Georgia Power Company, June 9, 1987.
- 19. Letter to Georcia Power Company f rom Quantum Technoloav. Inc. , Marietta, Georgia, June 17, 1987.
- 20. Has.h Nuclear Plant land Use Survey, Georgia Power Company, November 1987.
- 21. Letter to Georgia Power Company f rom Pickard. Lowe, and Garrick. Inc.,
Washington, D.C., November 30, 1987.
.)
HATCH OOCH, REV 4 2/88
-_n_________________-__
6 - Georgia Fbwer Company i r 333 Piedmont Avenue i
- ' ~' Atlanta. Georgia 30308 i g Telephone 404 5266526 I
Mailing Address:
fbst Oti;ce Box 4545 At!ae.ta, Georgia 30302 O *' the soorten ela:trc systwn Nuclear Operatens HL-46 0431I X7GJ17-H530 August 26, 1988 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C.- 20555 PLANT HATCH - UNITS 1, 2 NRC DOCKEls 50-321, 50-366 OPERATING LICENSES OPR-57, NPF-5 SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT Gentlemen: i In accordance with the provisions of the Plant Hatch Technical Specifications Sections 6.9.1.8 and 6.9.1.9, Georgia Power Company (GPC) is providing six copies of the Plant Hatch Units 1 and 2 Semi-Annual Radioactive Effluent Release Report. This report covers the period of January 1, 1988 through June 30, 1988.
Should you have any questions in this regard, please contact this office at any time.
Sincerely, d.h.A +u -n H. G. Hairston, III LGB/1g
Enclosures:
i Plant Hatch Semi-Annual Radioactive Effluent Release Report '
c: (see next page)
[6 o u l l
P
o Georgia Power d U. S. Nuclear Regulatory Commission August 26, 1988 Page Two c: Georaia Power Comoany Mr. H. C. Nix, General Manager - Plant Hatch Mr. L. T. Gucwa, Manager Licensing and Engineering Mr. S. C. Ewald, Manager Radiological Safety GO-NORMS U. S. Nuclear Regulatory Commission. Washing'.on. D. C.
Mr. L. P. Crocker, Licensing Project Manager - Hatch LL_S. Nuclear Regclatory Commissicn. Region II Dr. J. N. Grace, Regional Administrator (2 copies)
Mr. J. E. Henning, Senior Resident Inspector - Hatch American Nuclear Insurers Mr. L. Crcss State of Georgia Mr. J. Setser, Department of Natural Resources 0431I