ML20012B840
| ML20012B840 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/31/1989 |
| From: | Hairston W GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| HL-985, NUDOCS 9003160409 | |
| Download: ML20012B840 (168) | |
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I?Geosid Power Corripahy'- [333 P,edmort Avoque ,
. Manta. Georgia 3030/3 ; ,
5 4 -lo!aphono 404 526 3195 ;j ((] "". ..
?!. s MaAng Address:-
P'* 40 inverress Center Pwkway L I i , Pos: Off.cc Box 1295 ; . . Ehrmingham Alabama 35201 .;
- a Telephone 205 B68 5581 - lj
, t% sootten t+ctnc system ;y I : W. o. Hairston,'llt ' ,
T . $ernor Vee President i
-, : Naseai operanons : HL-985 a j
s - 000291 March 1,-1990 : y i e ~
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LU.S. Nuclear Regulatory Commission 1 ' ATTN:L Document Control Desk. I
, Washington, D.C. 20555-PLANT HATCH - UNITS 1, 2 :
, .NRC DOCKETS 50-321, 50-366 ,
(OPERATING LICENSES DPR-57, NPF-5 1 SEMIANNUAL RADIOACTIVE EFFLUENT-RELEASE REPORT j
~ Gentlemen: ,
J In: accordance with'the provisions .of Plant ~ 4 t Hatch :iTechnical . $
- Specifications : Sections 6'.9.12.8 andi6.9.1.9, Georgia. Power Company'(GPC) .
?ist providing six fcopies of the Plant Hatch Units 1 and 2 Semiannual 1 :3 LRadioactive, Effluent Release Report. This ' report covers.the period: of?
[ 'T LJuly-1,1989 through December 31', 1989. j l 3h'uld you-have any ' questions in this regard,'please contact this 'i y ' ,< o
,0ffi.ce z ati any t time.
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.v Sincerely, j
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PI; J" W. G. Hairston,.III l M , . y.] , _ DMH/CLT/eb , je .
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Enclosure:
Plant Hatch; Semiannual Radioactive i, 1 Effluent Release' Report y m A.; )c: (See next:page.) ! 4 P-q yh a ,
.o Georgia Pcnver a!he .
U.S. Nuclear Regulatory Commission 4! March 1, 1990' Page Two 'i i c: -Georaia Power Comoany Mr. J. T. Beckham, Jr., Vice President - Hatch Mr. H. C. Nix, General Manager. - Nuclear Plant Dr. W. R. Woodall, Manager Environmental . Affairs Mr. D.EB. Cochran,' Corporate Insurance 1 GO-NORMS U.S. Nuclear Reaulatory Commission. Washinaton. D.C. L Mr..L.-P. Crocker, Licensing Project Manager - Hatch 1 l U.S. Nuclear Reaulatory Commission. Reaion 11 Mr. .S. D. Ebneter, Regional Administrator (2 copies) Mr. J. E. Menning, Senior. Resident Inspector - Hatch American Nuclear Insurers Mr. L. Cross a State of Georaia Mr. J. Setser, DNR t P e 000291
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s GEORGIA POWER COMPANY l PLANT E. I. HATCH UNITS NO. 1 & 2-SEMIANNUAL RADIOACTIVE-EFFLUENT RELEASE REPORT July 1, 1989 - Decenber 31, 1989 y i - y l I
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[ PLANT E.-I. HATCH , SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
;u SECTION> TITLE PAGE l l'. - LIQUID EFFLUENTS 1 '!
1.1- REGULATORY LIMITS 1 1.2 MAXIMUM PERMISSIBLE CONCENTRATIONS 5 . 4 . 1.3 MEASUREMENTS AND APPROXIMATIONS OF , TOTAL RADIOACTIVITY 5 1 1.4 LIQUID EFFLUENT RELEASE DATA 7 i
. 1.5 RADIOLOGICAL. IMPACT ON !%N DUE TO .t LIQUID RELEASES 9 2- GASEOUS EFFLUENTS 19 E
- 2.1 REGULA7ORY LIMITS 19 t
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- 2.2 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY 25
' 2.3- GASEOUS EFFLUENT RELEASE DATA 30
.: 2.4 RADIOLOGICAL IMPACT DUE TO GASEOUS ,I RELEASES 31
=3 SOLID WASTE 47 .
3.1 REGULATORY REQUIREMENTS 47-3.2- SOLID WASTE DATA' 47
. 4 CHANGES TO THE PLANT HATCH ODCM 52-
-5 METEOROLOGY 53 5.1 METEOROLOGICAL DATA 53 l
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m= ' { tys o PLAtC E..I. HATCH SEMIANNUAL RADIOACTIVE EFFLUEIR RELEASE REPORT TABLE LIST OF TABLES PAGE 1-1 TECHNICAL SPECIFICATION TABLE 3.14.1-1 3 RADIOACTIVE' LIQUID EFFLUENT MONITORING INSTRUMEIRATION 1-2a, LIQUID EFFLUENTS - SUMMATION OF 10-ALL RELEASES - UNIT 1 1-2b LIQUID EFFLUEtES - SUMMATION OF 11 ALL RELEASES - UNIT 2
- 1 : (
1-2c LIQUID EFFLUENTS - SUMMATIONS OF 12 ALL RELEASES - SITE 1-3a LIQUID EFFLUENTS - UNIT 1 13 1-3b LIQUID EFFLUEtRS - UNIT 2 14 1-3c' LIQUID EFFLUENTS - SITE 15 i 1-4a INDIVIDUAL DOSES DUE 'IO LIQUID 16 RELEASES - UNIT 1 I 1-4b INDIVIDUAL DOSES DUE 'IO LIQUID 17 1
' RELEASES - UNIT 2 1-5 LOWER LIMITS OF'DUfECTION'- LIQUID- 18' SAMPLE ANALYSES 2-1 TECHNICAL SPECIFICATION TABLE 21 3.14.2-1 RADIOACTIVE GASEOUS EFFLUENT MONI'IORING INSTRUMENTATION 2-2a GASEOUS EFFLUENTS - SUMMATION OF- 32 ALL RELEASES - UNIT-1 2-2b GASEOUS EFFLUENTS - SUMMATION OF 33 ALL RELEASES - UNIT 2 L
2-2c GASEOUS EFFLUENTS - SUMMATION OF 34-ALL RELEASES - SITE 2-3a GASEOUS EFFLUENTS - ELEVATED 35 i RELEASES - UNIT 1 2-3b- GASEOUS EFFLUENTS - ELEVATED 36 RELEASES - UNIT 2 2-3c GASEOUS EFFLUENTS - ELEVATED 37 RELEASES.- SITE a
(-: . i 4 L ,. > TABLES LIST OF TABLES- PAGE h:; 0 2-4a GASEOUS' EFFLUENTS - GROUND- 38 LEVEL RELEASES - UNIT l-c 2-4b GASEOUS EFFLUENTS - GROUND - 39 LEVEL RELEASES - UNIT 2 2-4c GASEOUS EFFLUENTS - GROUND - 40
, LEVEL RELEASES - SITE 2-5= . GASEOUS EFFLUENTS - DOSE 41 L RATES - SITE 2-6a AIR DOSES DUE E tOBLE GASES - 42 U-
~ UNIT 1 6b . AIR DOSES DUE M NOBLE GASES - 43-UNIT 2 2-7a INDIVIDUAL DOSES DUE M RADIOIODINE, 44 ! TRITIUM, AND PARTICULATES IN GASEOUS { RELEASES - UNIT 1 1 7b
'l INDIVIDUAL DOSES DUE M RADIOIODINE, 45 TRITIUM, AND PARTICULATES IN GASEOUS '
-j RELEASES - UNIT 2 '
2-8 LOWER LIMITS OF DETECTION - GASEOUS 46 SAMPLE ANALYSES la,b SOLID WASTE AND IRRADIATED FUEL 48-51 SHIPMENTS
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E y . p: . b RADIOACTIVE EFFLUENT RELEASE REPORT 1 LIQUID EFFLUENTS 1.1. REGULATORY LIMITS
- 1. The Technical Specifications presented in this section are for Unit 1. Requirements for Unit 2 3x' are the same as Unit 1r however, the Technical-p Specification nunbers are not the same.
TECHNICAL SPECIFICATIONS 3.14.1 The radioactive liquid effluent monitoring i.
' instrumentation channels shown in table 3.14.1-1 shall 1
be OPERABLE with their alarm / trip setpoints set to ensure'that the limits of Specification 3.15.1 are not
. exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the 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 UNRESTRICTED
-AREAS (figure 3.15-1) shall be limited to the-1 concentrations specified in 10 CPR 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 MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, from the site'(figure 3.15-1) shall be limited to:
- a. During any calendar quarter to less than or equal i j
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 eaual -t 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 i discharge when the projected doses due to the liquid effluent per Unit from the site (figure 3.15-1) when projected over the calendar quarter would exceed 0.18 mrem to the total body or 0.62 mrem to any organ.
. i
3 t st : . b ' 3.15.1.4(a) .The contents within any outside 3 L temporary tank shall be limited to less than or_ equal ~ to 10 curies, excluding tritium and dissolved or entrained noble gases. < F (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 to 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 1 C1, excluding dissolved and entrained gases and tritium for liquid
' effluents, or those in excess of 150 C1 of noble gases-or 0.02 Ci of radiciodines for gaseous releases".
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TABLE 1-1 6 TECHNICAL SPECIFICATION i TABLE 3.14.1-1 (SHEET 1 of 2) RADIOACTIVE LIOUID EFFLUENT MONI'IORING INSTRUMENTATION Minimum Channels
- _ Instrument OPERABLE Applicability ACTION la
'1. Gross Radioactivity Monitors Providing Automatic Termina-tion of Release Liquid Radwaste Effluent Line 1 (a) 100
- 2. Gross Radioactivity Monitors not Providing -l i
Automatic Termination of . l' Release Service Water System Effluent Line- 1 (b) 101
- 3. Flowrate Measure-ment Devices **
1 Liquid Radwaste Effluent Line 1 (a) 102 Discharge Canal- 1 (b) (a) 102 '
- 4. Service Water' 1 At all times- 103 System to Closed cooling Water
' System Differential Pressure ,
-i
** Pump curves may be utilized to estimate flow; in such cases, ACTION statement 102 is not required.
(a) .Whenever the radwaste discharge valves are not locked closed. i (b) Whenever the service water system pressure is below the closed cooling water system pressure or differential pressure indication is not available. y y- ,
'I TABLE 1-1 (COtCINUED)
TECHNICAL ~ SPECIFICATION TABLE 3.14.1-1 (SHEET 2 of 2) m I ' RADIOACTIVE LIOUID EFFLUENT MONITORING INSTRUMEtRATION
. TABLE NOTATIONS ACTION 100 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement,
. effluent releases may be continued, provided that prior to initiating a release:
- a. At least two independent samples are analyzed in accordance with Specification 4.15.1.1.1.
- b. At least two technically qualified ~ individuals independently verify the release rate calculations and discharge valving.
Otherwise, suspend release of radioactive effluents via this pathway. If the channel remains inoperable for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report. ACTION 101 - With the numbers of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided that-once per shift grab samples are collected and analyzed F for gross radioactivity (beta or gamma) at a Lower Limit of Detection of~at least 10-7 uC1/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 hours 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 requirement, assure that the service water system effluent system +
monitor is OPERABLE. _h_
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1 k' 1.2 MAXIMUM PERMISSIBLE CONCENTRATIONS
" The MPC values used in determining allowable liquid radwaste telease rates and concentrations s
for principal gamma emitters, I-131, tritium, Sr-89, Sr-90 and Fe-55 are taken from 10CFR Part 20, Appendix B, Table II, Column 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-04 uCi/ml. +
i For gross alpha in liquid radwaste, the MPC is taken from 10CFR Part 20, Appendix B, Note 2.b as 3.0E-08 uCi/m3. 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'11guid radwaste effluent radiation monitor setpoints is described in Section 1.3 of this report, i 1.3 MFASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY
.i 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 ganna emitters, I-131, and dissolved and entrained noble gases by. gamma spectrometry. Monthly and quarterly composites are prepared for ana?ysis by extracting aliquots from each sample- ' taken from tanks which are released. Liquid ~ radwaste' sample analyses are performed as follows: 4 Measurement Frequency Method
- 1. Gamma Isotopic Each Batch Gamma spectroscopy with computerized data reduction 2.- Dissolved or Each Batch Ganna spectroscopy Entrained with computerized-Noble Gases data reduction l'
_5
g= .- W i Measurement Frequency . Method-
- ]
Tritium
. Monthly Distillation.and' Composite liquid scintillation counting
- 4. Gross Alpha Monthly Gas Flow Proportional Composite counting
- 5. Sr-89 and Sr-90 Quarterly Chemical separation and Composite gas flow proportional ,
, counting
- 6. Fe-55 Ouarterly Chemical separation and Composite low energy photon detector.
Ganna 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 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, Fe-59, Co-58, Co-60, 2n-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. LLDz , calculations, including the above corrections, are > 1made based on the counts in two standard deviations of the baseline count at the location on the spectrum where a peak for that radionuclide would be located if present. The radionuclide concentrations' determined by gamma spectroscopic analysis of a sample taken from a tank planned for-release and the most current sample analysis results available for tritium, gross alpha, Sr-89, Sr-90, and Fe-55.are used along with the ', corresponding MPC values to determine- an MPC fraction for the tank planned for release. This MPC fraction is then used, with appropriate safety factors, along with.the expected dilution stream flow to calculate a maximum permissible release rate and a liquid effluent monitor setpoint. The monitor setpoint is calculated to assure that the limits of Technical Specifications i 3.15.1.1 (Unit 1) or 3.11.1.1 (Unit 2) are not exceeded. ] g - ~- - h A monitor rc ding in cxcess of the calculated setpoint therefore results in an automatic termination of the liquid radwaste discharge. Liquid effluent discharge is also automatically terminated if the dilution stream flow rate falls below the dilution flow rate used in the setpoint calculations and established as a setpoint on the dilution stream flow monitor. Radionuclide concentrations, safety factors, dilution stream flow rate, and liquid effluent radiation monitor calibration factor are entered into-the computer and a prerelease printout is generated. If the release is not permissible appropriate warnings will be included on the prerelease printout. If the release is permissible 'it is approved by the Chemistry . Foreman on duty. The pertinent'information is transferred manually from the prerelease printout to a one-page release permit which is forwarded to Radwaste Operations. When the release is completed the release permit is returned from Radwaste Operations with actual release data included. These= data are. input to the computer . l and a post' release-printout is generated. The post release printout contains actual release rates, actual release concentrations and quantities, actual dilution flow, and calculated doses to an individual. 1.4- LIQUID EFFLUEfff RELEASE DATA o- Regulatory Guide 1.21 Tables- 2A and 2B are found ! 1 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 j s 1-3c for the site. The values for the four categories of Tables 1-2a and 1-2b, and 1-2c are calculated and the Tables , completed as follows: J
- 1. Fission and activation products - The total release values (not including tritium, gases, ;
e 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 4
-7 -
4 L qu2rttr. P;rcent of applicab10 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 e C/MPC ratios times 100 is the percent of L applicable limit for effluent releases I
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, K 3.0E-03 uC1/ml, is converted to percent 'to give the percent _of applicable limit.
- 13. Dissolved and entrained gases -
Concentrations of dissolved and entrained-gases in liquid effluents are measured by germanium spectroscopy on a one liter sample ' from each liquid radwaste batch. The average concentration of dissolved or entrained noble gases for all released batches is divided by the MPC value stated in Technical Specifications 3.15.1.1 and 3.11.1.1 (2.0E-04 uCi/ml) to determine the MPC fraction. The result-x100 is the percent of applicable limit for noble, gases in liquid effluent releases duri!' the quarter._ Radioisotopes of iodine 1.s any form are also determined during the -lsotopic analysis for each batch;_therefore, i separate analysis for possible ,gaseoes forms ' is not performed because it would not i
' provide additional information.
L
- 4. Gross alpha radioactivity - The measured gross alpha concentrations in the monthly composite samples are used to calculate the total release of alpha radioactivity. +
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V , II . LOther data pertinent to batch releases of radioactive liquid effluent from both units are [! ~ -as follows: t' Number of batch releases: 492
' Total time period for batch releases: 62,259 minutes Maximum time period for a batch release: 227.0 minutes Average time period for batch releases: 126.5 minutes Minimum time period for a batch release: 2.0 minutes . ' Average stream flow during periods of release of liquid effluent into a flowing stream: 9,518 -CFS
, 1.5 RADICLOGICAL IMPACT ON MAN DUE 'IO LIQUID RELEASES , 1 Doses to an individual, due to radioactivity in - 11guld effluent, were calculated in accordance
' with Technical Specifications 3/4.15.1.2 (Unit 1) and 3/4.11.1.2'(Unit 2) using the methodology presented in the Plant Edwin I. Hatch Offsite Dose Calculation Manual. As required by the above Technical Specifications, doses were calculated separately for Unit 1 and Unit 2.
Results are presented in Table 1-4a for Unit 1 and Table 1-4b for Unit 2.
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ti L i TABLE 1-2a ' E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES ' L s Unit Quarter 3 Quarter 4 Est. Total ? _____________________________________________________________ Error (%) A.. Fission and , e activation ; products Ci s
- 1. Total release
- 2. Average di:.uted 2.60E-02 4.10E-02 4.70E+01-concentrat i during per;:.on
.od uCi/ml 1.76E-08 5.48E-08 i: 3. % of applicable '
limit % 2.06E-01 2.64E+00 : B.. Tritium
- 1. Total release C1 1.08E+01 6.60E+00
- 2. Average diluted 3.70E+01 concentration during period
% of applicable uC1/ml 3.
7.32E-06 8.81E-06 limit % 2.44E-01 2.94E-01 C. Dissolved and entrained gases
- 1. Total release Ci 2.: Average di:.uted 4.43E-03 2.14E-02 1.00E+02 concentrat:.on during per uCi/ml 3.00E 2.86E-08
% of applic:od
- 3. able limit % 1.50E-03 1.43E-02 D. Gross Alpha
. radioactivity
- 1. Total release C1 9.18E-08 0.00E+00 1.20E+02 E. Volume of waste (prior to ,
dilution) liters 6.38E+06 3.63E+06 1.00E+01 F. Volume of dilution water used- liters 1.48E+09 7.49E+08 1.60E+02 L F
TABLE 1-2b 4 E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 LIQUID-EFFLUENTS - SUMMATION OF ALL RELEASES a i _________________--__-____-_________-____________-_-_-_-____- J
.1 Unit Quarter 3 Quarter 4-Est. Total
_______-________-__-_-__-_____-_-_______-_____-_-_EEEEE_1*l__ : A. Fission and activation
- products
- 1. Total-release Ci 3.54E-02 4.20E-02 4.70E+01
- 2. Average di:.uted concentrat ,
during per;:.on
.od uCi/ml 8.19E-08 5.98E-08
- 5. % of applicable limit % 7.04E-01 2.02E-01 B. Tritium.
- 1. Total release Ci 9.91E-01 1.62E+00 3.70E+01
~
- 2. Average'di:.uted congentrat:.on .
during per:.od uCi/ml 2.29E-06 2.31E-06
- 3. % of applicable
. limit % 7.65E-02 7.70E-02 , C. Dissolved and entrained gases
- 1. Total release Ci 6.21E-04 3.03E-05 1.00E+02
- 2. Average di:.uted concentrat:.on 3.
during per;.od
% of applicable uCi/ml 1.44E-09 4.31E-11 limit % 7.19E-04 2.16E-05 D. Gross Alpha radioactivity
- 1. Total release Ci 1.44E-07 0.00E+00 1.20E+02 ,
l E. Volume of waste (prior to dilution) liters 1.68E+06 3.01E+06 1.00E+01 F. Volume of dilution , water used liters 4.32E+08 7.02E+08 1.60E+02 i 1 "a.
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"W ; TABLE 1-2c E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 >
' LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES
_____________________________________________________________ s Unit Quarter 3 Quarter 4 Est. Total ' Error _________________________________________________________(%) ____ A. Fission and activation products. l -1. Total release Ci 6.14E-02 8.30E-02 4.70E+01 ,
- 2. Average di:.uted concentrat:.on '
3. during period
%,of applicable uCi/ml 3.'21E-08 5.72E-08 limit % 3.19E-01 1.46E+00 a
B. Tritium
- 1. Total release Ci 1.18E+01 8.22E+00 3.70E+01
- 2. Average'di:.uted e concentrat:.on
- 3. % of applicable uCi/ml during per:.od 6.18E-06 5.66E-06
' limit % 2.06E-01 1.89E-01
-C. Dissolved and entrained gases 1.-Total release Ci 5.06E-03 2.15E-02 1.00E+02 2.f Average ' di:.uted congentrat:.on
'during period
- 3. % of applicable uCi/ml 2.64E-09 1.48E-08 limit % 1.32E-03 7.40E-03 i D. Gross Aloha -
radioactivity R
- 1. Total release- Ci 2.36E-07' O.00E+00 1.20E+02 a
E. Volyme of waste-
-(prior to dilution) liters 8.06E+06 6,64E+06 1.00E+01
.F. Volume of dilution water used liters 1.91E+09 1.45E+09 1.60E+02 l
l l 4l 1
4 TABLE 1-3a* E. I. HATCH NUCLEAR PLANT - UNIT 1
^ FEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 LIQUID EFFLUENTS Continuous Mode **
.......____.....................______............ Batch Mode..__..__...
Nuclides Released Unit Quarter 3 Quarter 4
.......___.........................._____Q_uarter 3 Quarter 4
H-3 C1 1.08E+01 6.60E+00 Fission and activation products: Na-24 C: 1.93E-03 2.79E-03 Cr-51 C: 2.69E-03 8.28E-04 Mn-54 C: 2.83E-04 3.55E-04 Fe-59 C: 0.00E+00 4.74E-06 Co-58 C: 2.50E-04 4.40E-04 Co-60 C: 2.66E-03 2.54E-03 Cu-64 C 4.13E-04 3.76E-03 Zn-65 C: 4.87E-03 4.87E-03
- As-76 C: 5.42E-05 1.43E Rb-88 C:, 0.00E+00 2.35E-05 Sr-89 C: 0.00E+00 3.99E-04 Sr-91 C:, 7.66E-06 Y-91m C:
0.00E+00 Nb-97 4.85E-05 5.29E-05 CL. 9.11E-05 3.38E-05 Mo-99 C: 3.79E-05 2.64E-04 Tc-99m C: 5.46E-04 9.19E-04 Sb-125 C: 3.42E-06 0.00E+00 1-131 C: 2.71E-04 4.73E-03 I-ile C:, 4.88E-06 I '!33 CL 0.00E+00 I-13b 1.21E-03 2.96E-03 C: 2.33E-04 2.05E-04 Cs-134 C:. 2.44E-03 1.83E-03 Cs-136 C: 0.00E+00 7.47E-05 Cs-137 C: 7.86E-03 5.09E-03 Ba-140 C: 0.00E+00 1.48E-05 La-140 C: 0.00E+00 1.08E-04 Np-239 C:, Total 1.46E-04 8.61E-03 C: 2.60E-02 4.10E-02 Dissolved Kr-85m and entrained g'ases: C: O.00E+00 3.85E-06 Xe-133m C: 0.00E+00 1.50E-04 Xe-133 C: 4.22E-04 5.91E-03 Xe-135m C: 1.34E-03 1.08E-03 Xe-135 C: 2.67E-03 1.33E-02 Total C: 4.43E-03 2.14E-02 Gr-Alpha Ci 9.18E-08 0.00E+00
- Zeroes i this table e ndicate that no radioactivity was.
-e levels See Table 1-5 *ior t Sresentaovedetectabower lim ts of detc9t:,on for 11guid sample analyses.ypical
**There are no continuous mode radioactivo liquid release pathways at Plant Hatch y
I l g M 1 .wA .W
o - ~ l
' TABLE 1-3bo E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 LIQUID EFFLUENTS Continuous Mode ** Batch Mode Nuclides Released Unit Quarter 3 Quarter 4
.___..........__........____._________. Q.uarter
.__..__.__3__.......
Quarter 4 H-3 Ci 9.91E-01 1.62E+00 Fission and activation products Na-24 C: 2.94E-04 2.38E-06 Cr-51 C: 1.54E-05 5.08E-04 Mn-54 C: . 1.24E-03 3.98E-03 Mn-56 C: 1.55E-06 0.00E+00 Fe-59 C: 2.91E-05 1.03E-04 Co-58 C: 4.62E-04 1.26E-03 Co-60 C: 1.73E-03 9.47E-03 Zn-65 C: 2.82E-03 1.50E-02 Sr-89 C: 5.89E-04 4.51E-04 Sr-92 C: 1.22E-06 0.00E+00 Nb-95 C: 0.00E+00 2.58E-05 Nb-97 C: . 3.82E-05 1.07E-05 Tc-99m C: 1.02E-04 0.00E+00 Sb-125 C: 2.99E-05 1.79E-05 I-131 C: 1.26E-04 5.44E-06 I-132 C: 9.76E-05 0.00E+00 I-133 C: 4.09E-04 7.62E-07 I-135 C: 1.40E-04 0.00E+00 Cs-134 C: 8.07E-03 2.80E-03 Cs-137 C: 1.92E-02 8.30E-03 La-140 C: 1.84E-06 0.00E+00 Ce-141 C: 0.00E+00 4.63E-06 Np-239 C: 4.57E-06 0.00E+00 Total C: 3.54E-02 4.20E-02 Dissolved and entrained gases: Xe-133 C$ 5.94E-05 2.92E-06 Xe-135m C; 2.06E-04 0.00E+00 Xe-135 C: 3.50E-04 2.74E-05 Ar-41 C: 6.02E-06 0.00E+00 Total C: 6.21E-04 3.03E-05 Gr-Alpha ci 1.44E-07 0.00E+00
- resent Zeroesa in this table andicate that no radioactivity was ove detectab:.e levels power 1mgtsofdetect:.onfor11gugdsampleanalysesee Table 1-5 for typical
**There are no continuous mode radioactive liquid release pathways at Plant Hatch, t
-IL
w - { 1 TABLE 1-3co E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 LIQUID EFFLUENTS Continuous Mode ** Batch Mode : 1 Nuclides Released Unit Quarter 3 Quarter 4 __.... .....__..............____...____.Q.uarter 3 Quarter 4 H-3 Ci 1.18E+01 8.22E+00 Fission and activation products: Na-24 C: 2.22E-03 2.80E-03 Cr-51 C: 2.70E-03 1.34E-03 Mn-54 C: 1.52E-03 4.34E-03 Mn-56 C: 1.55E-06 0.00E+00 Fe-59 C: 2.91E-05 1.08E-04 Co-58 C: 7.12E-04 1.70E-03 Co-60 C: 4.39E-03 1.20E-02 Cu-64 CL 4.13E-04 3.76E-03 Zn-65 C: 7.69E-03 1.99E-02 - As-76 C: 5.42E-05 1.43E-04 Rb-88 C: 0.00E+00 2.35E-05 Sr-89 CL 5.89E-04 8.51E-04 Sr-91 C4 7.66E-06 0.00E+00 Sr-92 C:, 1.22E-06 Y-91m C: 0.00E+00 Nb-95 4.85E-05 5.29E-05 C: 0.00E+00 2.58E-05 Nb-97 C: 1.29E-04 4.45E-05 Mo-99 C: 3.79E-05 2.64E-04 Tc-99m C. 6.48E-04 9.19E-04 Sb-125 C: 3.33E-05 1.79E-05 I-131 C: 3.97E-04 4.74E-03 I-132 C: 1.02E-04 0.00E+00 I-133 C: 1.62E-03 2.96E-03 I-135 C: 3.73E-04 2.05E-04 Cs-134 C:, Cs-136 C: 1.05E-02 4.64E-03 Cs-137 C: 0.00E+00 7.47E-05 E Ba-140 2.70E-02 1.34E-02 C: 0.00E+00 1.48E-05 La-140 C: 1.84E-06 1.08E-04 Ce-141 C: 0.00E+00 4.63E-06 Np-239 C:. 1.51E-04 8.61E-03 Total CL 6.14E-02 8.30E-02 ' Dissolved and entrained gases: Kr-85m CL 0.00E+00 3.85E-06 Xe-133m C , 0.00E+00 1.50E-04 Xe-133 C: 4.81E-04 6.91E-03 Xe-135m C: 1.55E-03 1.08E-03 Xe-135 C: 3.02E-03 1.33E-02 i Ar-41 CL 6.02E-06 0.00E+00 Total C:. 5.06E-03 2.15E-02 Gr-Alpha Ci 2.36E-07 0.00E+00
- Zeroes i this table indicate that no radioactivity was resent a ove detectab:.e levels pover11 ee Table 1-5 for typical tsofdetectnonfor11gu{dsampleanalyses
**There are no continuous mode radioactive liquid release pathways at Plant Hatch.
~ - t. TABLE 1-4a E. I. HATCH NUCLEAR PLANT - Unit 1 SEMIANNUAL RADIOACT,IVE EFFLUENT RELEASE REPORT 1989 INDIVIDUAL DOSES DUE TO LIQUID RELEASES Cumulative Doses per Quarter Organ Tech Spec Unit Quarter 3 % of Quarter 4 % of Limit Tech Tech Spec SDec __.........................._____ .......__........... Limit Limit Bone 5.0 mrem 3.56E-02 7.12E-01 2.66E-02 5.31E-01 Liver 5.0 arem 5.94E-02 1.19E+00 5.03E-02 1.01E+00 TBody 1.5 . mrem 4.20E-02 2.80E+00 3.59E-02 2.39E+00 Thyrbid 5.0 arem 6.71E-03 1,34E-01 1.01E-01 Ki8ney 5.0 mrem 2.02E+00 2.19E-02 4.38E-01 2.07E-02 4.14E-01 Lung 5.0 mrem 8.32E-03 1.66E-01 8.87E-03 1.77E-01 GILLI 5.0 mrem 6.03E-03
.........___ ......___............._____......... 2 1.21E 01 1.05E-0 2.10E-01 Cumulative Doses-This Year Organ . Tech ' Unit Quarters % of Spec 1,2,3,& 4 Tech Limit- Spec Limit Bone 10.0 mrem 1.87E-01 1.87E+00 Liver 10.0 mrem 3.14E-01 3.14E+00 TBody 3.0 mrem 2.22E-01 7.40E+00 Thyroid 10.0 mrem 1.09E-01 1.09E+00 Kianey 10.0 mrem 1.12E-01 1.12E+00 Lung 10.0 mrom 3.94E-02 3.94E-01 GILLI 10.0 mrem 2.66E-02 2.66E-01 r
t i i TABLI 1-4b ! E. I. HATCH NUCLEAR PLANT - Unit 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 INDIVIDUAL DOSES DUE TO LIQUID RELEASES Cumulative Doses per Quarter , 1 i Organ Tech Spec Unit Quarter 3 % of Quarter 4 % of , Limit Tech Spec Tech ' Spec i
.................................___......___......... Limit Limit t
Bone 5.0 mrem 9.55E-02 1.91E+00 4.62E-02 9.24E-01 Liver : 5.0 mrem 1.56E-01 3.11E+00 7.93E-02 1.59E+00
. TBody 1.5 mrem 1.11E-01 7.39E+00 5.48E-02 3.65E+00 roid 5.0 mrem 1.45E-03 2.91E-02 1.36E-03 2.72E-02.
Thbney Ki 5.0 mrem 5.25E-02 1.05E+00 2.96E-02 5.92E-01 i Lung 5.0 mrem 1.74E-02 3.47E-01 9.10E-03 1.82E-01 : GILLI 5.0 -mrem 5.80E-03 1.16E 01
...__...__...___...__...__......____..__.....67E-02
- 1. 3.34E
......._____-01 .._
[ e Cumulative Doses This Year .
.............._______....__......__ ..__..__.... ..___....... i Organ Tech Unit Quarters % of Spec 1,2,3,& 4 Tech Limit Speg
?
Limit . Bone 10.0 mrem 2.63E-01 2.63E+00 Liver 10.0 mram 4.36E-01 4.36E+00 TBody 3.0 mrem 3.11E-01 1.04E+01 Thyroid 10.0 mrem 4.81E-03 4.81E-02 KiBney 10.0 mrem 1.49E-01 1.49E+00 i Lung 10.0 mrem 4.87E-02 4.87E-01 GILLI 10.0 mrom 2.72E 02 2.72E-01 - i t l l l'
e b TABLE 1-5~ LOWER LIMITS OF DETECTION - LIQUID SAMPLE ANALYSES i The values in this table represent apriori Iower lirits of detection (LLD)'which are typically achieved in laboratory analyses of liquid radwaste samples. U 1 RADIONUCLIDE LLD UNITS Mn-54 5.38E-08 uC1/nd
, Pe-59 7.78E-08 Co-58 4.67E-08 Co-60 4.78E-08 Zn-65; 1.31E-07 Mo-99 5.10E-07*
l-l Cs-134 7.18E-08
.. . , ' Cs-137 6.05E-08 L Ce-141 1.41E-07
[f t Co-144 I-131' 6.30E-07* 6.51E-08
!. Xe-135 8.45E-08 L Fe-55 8.00E-07 E' St-89' 2.30E-08 Sr-90 7.67E-09 H-3 5.00E-07 (J
- *In accordance with Technical Specification Tables 4.15.1-1 (Unit 1) and 4.11.1-1 (Unit 2),' Table Notation b,- the permissible Lower Limit of
[q Detection may be increased inversely proportional to the magnitude of-the L _ gamma 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). l L e g .' L' k t b. r i
'I n,.
e 1 i
.=
~
;I ,
t 2 GASBOUS EFFLUENTS t . j 2.1 RBGULATCRY LIMITS The Technical Specifications presented in this section o . ' are for Unit 1. Requirements for Unit 2 are the same ; as for Unit li however, the Technical Specification i numbers are not the same. : i: TECHNICAL SPECIFICATIONS L , 3.14.2 The radioactive gaseous eff1.:ent monitoring
?' !
L instrumentation channels shown in table 3.14.2-1 shall be ' OPERABLE with their alarWtrip setpoints set to ensure that I the limits of Specification 3.15.2.1(a) are not- exceeded. 3 The alarWtrip 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 ;
- p. .
3.15.2.1 The dose rate at any time in the UNRESTRICTED AREAS (figure 3.15-1) due to radioactive materials released : L in gaseous effluents from the site shall be limited to the [ p following values: l
- a. The dose. rate limit for noble. gases shall be less F
i than or equal to 500 mrem / year to the total body and less than or equal to 3000 mrem / year to the ; skin. , L b. The dose rate limit for I-131, I-133, tritium, and for all radioactive materials in particulate L form and radionuclides other than noble gases ' L with half-lives greater than 8 days shall be less ' L than or equal to 1500 mreWyear to any organ. ' 3.15.2.2' The air dose in UNRESTRICTED AREAS (figure ; F 3.15-1) due to noble gases released in-gaseous effluents L from each reactor unit shall be. limited to the following: . c a.- nuring any calendar quarter, to less than or equal to 5 mrad for gamma- radiation and-less than - or equal to 10 mrad for beta radiation. I L 4
- 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. ' i n ' 3.15.2.3 The dose to any organ of a MEMBER OF HIE PUBLIC ~ from I-131, I 133, tritium , and all-radionuclides in g particulate form with half-lives greater than 8 days in , gaseous effluents released to UNRESTRICTED AREAS.(figure- , 3.15-1) from each reactor unit shall be limited to the
-following:
1-- e
s y, ,
- a. During any calendar quarter to less than or i
n 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 GASDDUS RADWASTE TREATMEfff 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 TREATPIfff SYSTEM operability shall be demonstrated by administrative controls which assure that the offgas treatment system is.not bypassed.
3.15.2.5 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases !- of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal. to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal 17 p to 75-mrem. (With the calculated doses from the release of i radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.15.1.2(a), 3.15.1.2(b), 13.15.~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 f units and from outside storage tanks to determine whether. the above limits of Specification 3.15.2.5 have been exceeded, i'
F 3.15.2.6' The~ concentration of hydrogen downstream of e ' the recombiners'in the main condenser offgas treatment system shall be limited to less than or equal to 4 n, percent by volume. 3.15.2.7 The gross gamma radioactivity rate of the
. noble gases Xe-133, Xe-135, Xe-138, Kr-85m, Kr-87, and Kr-88 measured at the main condenser evacuation system pretreatnent monitor station shall be 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 C1, excluding dissolved and entrained gases and tritium for liquid effluents, or those in excess of 150 Ci of noble gases or 0.02 C1 of radioiodines for gaseous releases."
~20-P
$. .. 1
T Al3I t 3.14.2-1 ( SIIE E T .1 Of 8e ) HADis).wilVE CAST otf5 ti f t tif MI H0etl TORING I NS T RUNI NI AllON Hinistem Ciestine s s l'15 L M'ac!!! OPERABt[ eggt ica bi i i tv ' f*a ramete r ACIlOM
- l. H. sin Cuentetiser Of fgas T rea tweet System tiplosive Cas Horiitoreng System flyds ogen Hunitor (1) **
% liydrogen 106
- 2. Iteac t o r lits i ld i sig Vese t Stack lionitoring System
- a. flotele Gas Activity Ibnitos it1 *
.h w Radioac t ivi ty fla te Hea sterement + 105 s 13 ludiese Sampler Car t ridge (I)
- Verily Prescrece of' 10T H Cartridge c
- c. f*.a r t icaela te Samp ler iiltes *
(I) Verify Preserice of 107 . M I filter M i
- d. Iffluent System iIowiate "
lleissessemetet Device (I)
- Sy s t e-ne I t twra te lots Heaststraent
- c. S;empler f lowtate lleasterems-set Device (1)
- Sampler i towrate 100:
Henseerement
- 3. I:ecomleisserr IItei ld ieng Veset 41a t ie.n flor:4 toring System
- a. fJulele Gas Activity Obinitut- (1)
- Radioactivity Rate 10$
Hea s ts e emen t
- Is . t uel e sse Sampler I:.s e t e idge (1)
- Verily Presersce 01~ Itif Carteisige a: . I'.e e t ites t a t er Samples IiItee ie) *
- Vee i f y I'rescence of' IDT filter .
al . Eemples I i ow s a t a? thr. aster two set (1) * (wvice Samse' le s f lenwe re te 1stes Heesset ement
~~ ' ~ ' =m
^
.. G ,
3 - 9G9 b:+ r"' ~ ' ' ' ~ ^ ~ ~ ' '
,,0- g i
r T ABt E 3. lts.2-1 (SHEE1 2 OF 4)
~
RADIOACTIVE GASEOtfS EFFLUEssi M09tt10RifeG INSTRUMEstTAf toft Mi n imism Channe8s Instriement OPERABLE Appl icabj t i ty Pa ramete r ACil014 *
' is . Main Stack Monitorint System
- a. Not Ie Gas Activity Monitor (1)
- Radioactivity Rate 105 Measterement +
- b. tu line Sampler Certridge -(1)
- Verify Presence of 107 Cartridge . 63
- c. Particulate Sampeer filter >
(1)
- VerlFy Presence of Filter 107 $
tu
- d. Ets'issent System sowrate M 8, He estaring Device . (l) * :
e5 System Flowrate 104
- 8 Measserement -
- e. Sa ap ter i towrate Heasaaring
- O (1) Sampler F lowrate lots
- Derice Mea sterement @
rt g
- 5. Conden .cr OFrgas Pris. 3 9atment Honito 8' floble 'As Act ivi ty the#ei tor (1) ***
Radioactivity Rate 108 Mea steremen t 4 m
[ ~ l r i TABLE 2-1 (Cont'd) I ' TABLE 3.14.2-1 (SHEET 3 0F 4) . RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Table Notations
+ Monitor must be capable of respondin'g to a Lower Limit of
, Detection of 1 x 10-' uCi/ml.
*During releases via-this pathway.
**During main condenser offgas treatment system operation.
***During operation of the main condenser air ejector.
ACTION 104 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided the flowrate is estimated at least once per 4 hours. If the number of channels OPERABLE remains less than required by the Minimum Channel: 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 required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, providec ! grab samples are taken daily and analyzed daily for gross activity within 24 hours. With the number of main stack monitoring system channels OPERABLE less than required by the Minimum Channels OPERABLE reouirement, without delay suspeno cryweil purge. If the number of channels OPERABLE remains less than j required by the Minimum Channels OPERABLE requirement for ! over 32 days, an explanation of the circumstances shall be included in the next semi-annual effluent rdease report. ACTION 106 - With the number of channels OPERABLE less than required by the MLnimum Channels OPERABLE requirement, operation of the main condenser offgas treatment system may continue provided: (a) Gas samples are collected once per 4 hours and analyzed within the ensuing 4 hours, or (b) Using a temporary hydrogen analyzer installed in the offgas system line downs,tream.of the recombiner, hydrogen concentration readings are taken and logged - every 4 hours. iL
~
, W-r ' TABLE 2-1 (Cont'd) . TABLE 3.14.2-1 (SHEET 4 0F 4) t RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION i e Table Notations (Continued) I 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.
L ACTION 107 - With the number of 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 hours after the end of the sampling period. If the number of channels OPERABLE remains less than - required by the Minimum Channels OPERABLE requirement for ' over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report. > ACTION 108 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, release to the environment may continue for up to 72 hours , provided:
- a. The offgas system is not bypassed, and >
- b. The offgas post-treatment monitor (011-K615) or the main i
stack monitor (011-KG00) is OPERABLE. - Otherwise, be in at least HOT STANDBY within 12 hours. 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 ir the next semi-annual effluent release report, r '
-2L-
g- ? m; a g< , e k 2.2 ' MEASUREMEN1' AND APPROXIMATIONS OF 70TAL RADIOACTIVITY i ! p . Waste gas. release at Plant Hatch is confined to four paths: main stack (also called the offgas vent), Unit 1. reactor building vents: Unit 2 li; reactor building vent, and the recombiner i
- building vent. Each of these four paths is
[ continuously monitored for gaseous ' " radioactivity. Each is equipped with an ; integrating-type sample collection device for collecting-particulates and'fodines. Sample collection is in accordance with Technical
- i. Specification Tables 4.15.2-1 (Unit 1) and 4.11.2-1 (Unit 2). Unless required more .
frequently under certain circumstances specified .l ' in Table Notations to the above mentioned tables, . samples are collected as follows: ' . 1. Noble gas samples are collected by grab i, sampling monthly.
- 2. Tritium samples are collected by grab sampling monthly. '
- 3. Radiciodine samples are collected by pulling the sample stream through a charcoal i cartridge over a 7-day period.
i
- 4. Particulates are collected by pulling the sample stream through a particulate f11ter over a 7-day period. ~
T'
- 5. The 7-day particulate filters above are analyzed for gross alpha activity. <
Ns
- 6. Quarterly composite samples are prepared from the particulate filters collected over the previous quarter and the quarterly composite sample is analyzed for St 39 and St-90. '
Sample analyses results and release flow rates from the four release points form the basis for i i calculating released. quantities of l radionuclide-specific cc,dioactivity, dose rates .i associated with gaseous releases, and cumulative doses for the-current quarter and year.- This task is normally performed with computer
, assistance.
4 _ _ _ _ i
\ i /
, The noble gas grab sample analysis results are used along with maximum expected release flow rates from each of the four vents to calculate ;
p monitor setpoints for the gaseous effluent l L monitors serving the four release points, to ' 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 , ODCM. t With each release period released 1.idioactivity, dose rates, and cumulative doses are calculated. [ Cumulative dose results are tabulated along with L percent of Tachnical Specification lindts L (3.15.2.2 and 3.15.2.3 (Unit 1): 3.11.2.2 and i 3.11.2.3 (Unit 2) for each release, for the current quarter and year, t 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. PISSION AND ACTIVATION GAS The radionuclide-specific released radioactivity is determined from sample analyses results collected as described above and average release flew rates over the period represented by the collected sample.
Instantaneous dose rates due to noble gases and , due to radjoiodines, tritium, and particulates are calculated (with computer assistance). Calculated dose rates are compared to the dose rate limits specified in 3.15.2.1.a (Unit 1) and 3.11.2.1.a (Unit 2) for noble gases; and 3.15.2.1.b (Unit 1) and 3.11.2.1.b (Unit 2) for radiciodine, tritium, and particulates. Dose rate calculation methodology is presented in the Plant Hatch ODCM. m
~
I i: [, r o t Beta and gamma air doses dae to noble gases are F calcalated for the location in the unr* ,cricted L area with the potential for the highest exposure due to gaseous releases. Air doces are ! calculated for each release period and cumulative i: 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. RADI0 IODINE, TRITIUM, AND PARTICULATE RELEASES Released quantities of radioiodines are determined from the weekly samples and release flow rates for the four release points.
Radioiodine concentrations are determined by gamma spectroscopy. Released quantities of particulates are determined from the weekly (filter) samples and release flow rates for the ;our 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 s flows and vent flows are almost constant over each quarterly period the filters from each vent caa be dissolved together. Decay corrections are made back to the middle of the quarterly _ ' collection period. Where significant St-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 gracs of water vapor / cubic foot gas is measured upstream of the cold trap in order to alleviate the difficulties in determining water ,
vapor collection efficiencies. The tritium ' samples are analyzed by an independent laboratory , and results are furnished in uCi/ml of water. The tritium concentration in water is converted to tritium concentration in air and this value is input into the composite file of the computer to be used in release, dose rate, and individual dose calculations. n
- p. ,. -
i i l T i i Dose rates due to radioiodine, tritium, and particulates are calculated for a hypothetical-L child, exposed to the inhalation pathway, at the 2 location in the unrestricted area where the p potential dose rate is expected to be the '
- i. highest. Dose rates are calculated for each
!. release point, for each release period, and the total dose rate from all four release points are compared to the dose rate limits specified in Technical Specifications 3.15.2.1.6 (Unit 1) or 3.11.2.1.b (Unit 2).
- Individual doses due to radioiodine, tritium, and particulates are calculated for the critical L
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 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 ilmits are shown on the printout for each release period.
- 3. GROSS ALPHA RELEASE The gross alpha release is computed each month by 1
counting the particulate filters each week for gross alpha activity in a proportional counter. The four or five weeks' numbers are then recorded on a data sheet and the activity is summed at the , end of the month. This concentration. is input to the composite file of the computer and is used for release calculations. 4. ERROR ESTIMATES Regulatory Guide 1.21 requires that estimated total error in analysis techniques be reported. , These estimates are required for the total ; fission and activation gas release, total I-131 release, total particulates with half-lives greater than 8-day release, and total tritium release. 3 .
+
4 21 . . . l
T o e
'The total or maximum error associated 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 overall estimate of~the error associated with measurements of radioactive materials released in f' liquid and gaseous effluents and solid waste."
Estimated errors are based on errors in counting equipuent calibration, counting statistics, vent ficw L rates, vent sample flow rates, non-steady release rater, chemical yield factors, and sample losses for such. item ~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% y lWE (2) I-131 Release was calculated from each weekly sample: Statistical Error. 60%- Counting Equipment ::alibration 10% Vent Flow Rates 10%- Vent Sample Flow Rates 10% Non-Steady Release Rates. 10% c Losses From Charcoal Cartridge . 10% w ll6I-y (3) Particulates with half-lives greater than-8 days release was calculated from sample analysis results and release point flow rates.
; Statistical Error at LLD concentration 60%
'4 a' Counting Equipment Calibration 10%
Vent Flow Rates 10% Vent Sample Flow Rates 10% Non-Steady Release Rates 10% 100% l _29 i
'i l
l 7g - ,]
r t-b o L (4) Total Tritium Release was dominated by th? reactor building vent tritium releaser hence, the larger statistical errors of the off-gas vent and (~ recombiner building vent tritium releases do not l t affect the error in the total tritium release: Water Vapor in Sample Stream Determination 20% Vent Flow Rates 10% Counting Calibration and Statistics 10% Non-Steady Release 50% < i
~s5I 2.3 GASEOUS EFFLUE!C RELEASE DATA P
Regulatory Guide 1.21 Tables lA,18, and IC 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.
.o complete Tables 2-2a-c, total release for each of l the four categories (fission and activation gasest t iodiness particulates; and tritium) was divided by the number of seconds in the quarter to obtain a release l
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 mrenvyear, as presented in Technical Specifications 3.15.2.1 (Unit 1) and 3.11.2.1 (Unit 2). Noble gases are limited as specitied in 3.15.2.1.a and 3.ll.2.1.a. The other three categories (tritium, radiciodines, and particulates) are limited as a group as specified in r 3.15.2.1.b and 3.ll.2.1.b. Further the limits-specified in Technical Specifications 3.15.2.1 and. 3.11.2.1 are site limits, not unit limits. Dose rates due to noble gas releases and due to radioiodine, tritium, and particulates are presented in Table 2-5 along with percent of technical specification limits. Gross alpha radioactivity is reported in Tables 2-2a, 2-2b, and 2-2c as curies released in each quarter. Lindts for cumulative beta and gamma air doses, due to noble gases, are specified in Technical Specifications 3.15.2.2 (Unit 1) and 3.11.2.2 (Unit 2) . These limits are unit Jimits. Cumulative air doses are presented in Tables 2-6a and 2-6b, along with percent of technical specification limits. 5.:u.
pg . - t
' Limits for cumulative individual: doses, due to .
radioiodine, tritium, and particulates, are specified L. L in Technical Specifications 3.15.2.3 (Unit 1) and U 3.11.2.3 (Unit 2). These limits are also unit i- 'lind ts. Cumulative individual doses are presented in , [ ' . Tables 2-7a and 2-7b, with percent of technical ! j specification limits. h ! p- 2.4 RADIOLOGICAL IMPACP DUE TO CASEDUS RELEASES f , Dose rates due to noble gas releases were calculated i for the site in accordance with Technical f' Specifications 3/4.15.2.1.a . (Unit 1) and 3/4.11.2.1.a s (Unit 2). Results are presented in Table 2-5. Dose : L . rates due to radioiodine, tritium, and particulates in . . L gaseous releases were calculated in accordance with p Technical Specifications 3/4.1'i.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 e calculated for each unit in accordance with Technical ! Specification 3/4.15.2.2 (Unit 1) and 3/4.11.2.2 (Unit i 2). These results are presented in Tables:2-6a and 2-6b. : Cumulative doses to an individual due to radioiodine,
' tritium , and particulates were calculated for each b
unit in accordance with Technical 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. 1 Dose rates and doses were calculated using the b methodology presented in the Plant Hatch ODCM. 6 k I
)
T e
?? -
F I I- l I l L TABLE 2-2a ! E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELIASE REPOPT 1989 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES ; Unit Quarter 3 Quarter 4 Est. Total ___________.._____________._____________..____....______ Error____ (%) ,
+
A. Fission and Activation Gases
- 1. Total Ci 5.44E+01 9.41E+01 1.00E+02 !
Release
- 2. Average uCi/sec 6.91E+00 1.22E+01 '
Release i Rate For ' Period
*3. % of Tech %
Spec 7,imit B. Iodines
- 1. Total Ci 6.21E-04 1.01E-03 1.10E+02 Iodine-131
- 2. Average uCi/sec 7.89E-05 1.32E-04 Release Rate For Period
*3. % of Tech %
Spec Limit C. Particulates
- 1. Particulates wLth half-C1 1.86E-03 4.15E-04 1.00E+02 laves > 8 days
- 2. Average uCi/sec 2.36E-04 5.40E-05 Release Rate For Period
*3. % of Tech %
Spec Limit
- 4. Gross Alphe Ci- 1.47E-06 2.25E-06 Radioactivity D. Tritium-
- 1. Total' Ci 6.60E+00 6.05E+00 9.00E+01
- 2. Average uC1/sec Release 8.39E 01 7.87E-01 Rate For Period
*3. % of Tech %
Spec. Limit s !-
- Technical Specification limits are in terms of dose rate fmrem/grganddose
-7a, 2-7b (mrem). See Tables 2-5, 2-6a, 2-6b, d
TABLE 2-2b E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 - GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES ' Unit Quarter 3 Quarter 4 Est. Total
------------------------------------------------- Error (%)
A. Fis-lon and Act$vation Gases
- 1. Total Ci 2.61E+01 2.79E+01 1.00E+02 Release ,
- 2. Average uCi/sec 3.32E+00 3.63E+00 Release Rate For !
Period
*3. % of Tech %
l Spec Limit D. Iodines
- 1. Total Ci 2.13E-04 3.57E-04 1.10E+02 '
Icdine-131
- 2. Average Release uCi/sec 2.71E-05 4.64E-05 Rate For Period ,
*3. % of Tech %
Spec Limit C. Pwrticulates
- 1. Particulates wnth half-Ci 1.05E-04 9.12E-06 1.00E+02
, laves > 8 days
- 2. Average uC1/sec 1.33E-05 1.19E-06 Release Rate For Period
*3. % of T ch %
Spec L..mit c
- 4. Gross Aloha C1 1.37E-06 2.76E-06 Radioactivity D. Tritium
- 1. Total C1 1.15E+01 4.53E+00 9.00E+01
- 2. Average uCi/see 1.47E+00 Release 5.89E-01 Rate For
- Period
*3..% of Tech %
Spec Limit
- Technical Specification limits are in terms of dose rate fmrem/yrganadose
-7a, an 2-7b (mrem). See Tables 2-f, 2-6a, 2-6b, s
7
-33.
i l TABLE 2-2c ' E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 , GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter 3 Quarter 4 Est. Total
------------------------------------------------- Error (%)
4 , A. Fission and Activation Gases
- 1. Total Ci 8.05E+01 1.22E+02 1.00E+02 Rolease i
- 2. Average Release uCi/sec 1.02E+01 1.59E+01 Rate For Period
*3. % of Tech %
t Spec Limit B. .Iod{nes
- 1. sotal Ci 8.33E-04 1.37E-03 1.10E+02 Iodine-131
- 2. Sverage uCi/sec 1.06E-04 1.78E-04 Release Rate For t l'eriod
*3. 4 of Tech %
+
Spec Limit . C. Particulates
- 1. Pitrticulates Ci 1.96E-03 4.25E-04 1.00E+02 w:.th half-lives > 8 days
- 2. Average uCi/sec 2.50E-04 S.52E-05 Release Rate For Period-
*3. % of Tech %
Spec Limit
- 4. Gross Aloha Ci 2.84E-06 5.01E-06 Radioactivity D. Tritium
- 1. Total C1 1.81E+01 2.. Average 1.06E+01 9.00E+01 Release uC1/sec 2.31E+00 1.38E+00 Rate For ,
Period
*3. % of Tech %
Spec Limit
- Technical Soecification limits are in terms of dose rate L fmrem/yrganBdou;;
-7a, an 2-7b (mrem). See Tables 2-5, 2-6a, 2-6b, 1.
-3h-k
S TABLE 2-3a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 GASEOUS EFFLUENTS - ELIVATED RELEASES
- Continuous Mode Ba Mode **
_... _________.__ ____..._________n___________tch ____~__________ Nuclides Released Unit Quarter 3 Quarter 3 Quarter 4
-_________________ ___________Q_uarter 4 i
- 1. Fission Gases Kr-83m Cf 0.00E+00 9.12E-02 Kr-85m C: 1.37E-01 1.28E+00 Kr*87 C: 6.36E-01 3.45E+00 Kr-88 C: 0.00E+00 7.07E-01 Xe-133 C 3.27E-01 1.18E+01 7e-135m C: 8.87E+00 1.44E+01 Xe 135 CL 2.09E+00 5.13E+00 Xt -138 C: 2.70E+01 2.03E+01 Ar 41 C. 0.00E+00 1.73E-01 Totgl For Period C1 3.91E+01 5.73E+01
- 2. Iodines I-131 C: 1.26E-04 2.84E-04 I-133 C: 6.03E-04 3.34E-04 I 135 CL -4.27E 04 2.40E-04 Total For Period Ci 1.16E 03 8.5
....______________________________9E-04 . _ ___________. __________
- 3. Particulates Mn-54 CL 0.00E+00 1.29E-06 Co-60 C: 0.00E+00 1.85E-06 Zn-65 C: 0.00E+00 1.81E-06 Sr-89 C: 2.26E-05 2.08E-05
-Sr-90 C: 1.28E-07 1.18E-07 Cs-137 C: 6.84E-07 4.67E-07 Ba-140 C: 5.26E-05 3.13E-05 La-140 C: 8.93E-05 5.53E-05 Ce C 0.00E+00 .___ ._-141 5.50E 08 Totgl For Period Ci 1~65E 1.13E
____________..__..________-04 . __________-04 _____________________ ___ i
- Zeroesabove present in this table indicate detectable levels. that no radioactivity wag 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.
I
r.' V l TABLE 2-3b L - E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 GASEOUS EFFUUENTS - ELEVATED RELEASES * !- Continuous Mode
.. __. _____.... .__...___________...__...... Batch Mode **
Nuclides Released Unit Quarter 3 Quarter 4 __.___....____._______.....___..__Q_uarter 3 Quarter 4
- 1. Fission Gases Kr-85m C 0.00E+00 5.22E-02 Kr-87 C: 0.00E+00 2.32E-01 Xe-133 C: 0.00E+00 4.42E-01 Xe-135m C: 3.69E+00 8.15E-01 Xe-135 C: 6.53E-01 2.03E-01 Xe-138 C: 1.14E+01 1.44E+00 Ar-41 C: 0.00E+00 6.04E
_____. ____._______. _______....____-02 __ ....__......___.__..__ Total For Period C1 1.57E+01 3.25E+
,__ ....____..._______..___ ._________00 ___________________....
- 2. Iodines I-131 C; 5.63E-05 7.69E-06 I-133 C: 3.26E-04 8.35E-06 I 135 C; 2.34E 04 3.47E
_________......__.___.______._______-06 ...__ . ________..___.... Total For Period Ci 6.17E 04 1.95E-05
- 3. Particulates Co-60 C: 0.00E+00 4.22E-08
'Gr-89 C: 8.15E-06 1.01E-06 Sr-90 C; 4.60E-08 5.70E-09 Cs-137 C: 3.97E-07 0.00E+00 Ba-140 C: 1.86E-05 7.32E-08 la-140 C: 3.23E 0.00E+00 ._ .....__________.._____-05 _...._________... _____________.___.
Total For Period Ci 5.95E-05 1.1
..._________ ___.._______... . . __3E-06 .... .__________ _________
- Zeroesahove present in tnis table indicate detectable levels.that no radioactivity was See Table 2-8 for ty lower limits of detection for gaseous sample analyses.pical ,
i 1
**There are pathways at no-batch Plant Hatch.mode radioactive gaseous release n.
TABLE 2-3c E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 GASEOUS EFFUDENTS - ELIVATED RELEASES
- Ccntinuous Mode
..___...........................________ ___ Batch Mode **
Nuclides Released Unit Quarter 3 4 Quarter 3 Quarter ______. __.... _______........Q_uarter 4 (
- 1. Fission Gases Kr-83m C: 0.00E+00 9.12E-02 Kr-85m C: 1.37E-01 1.33E+00 Kr-87 C: 6.36E-01 3.68E+00 Kr-88 C: 0.00E+00 7.07E-01 Xe-133 C: 3.27E-01 1.22E+01 Xe-135m C: 1.26E+01 1.53E+01 Xe-135 C: 2.75E+00 5.33E+00 Xe-138 C: 3.84E+01 2.17E+01
......_-41 Ar C: 0.00E+00 2.33E 01 Total For-Period Ci 5.48E+01 6.06E+ .....___. __________.......___ ___...01 ..._____...._______ __.
- 2. Iodines I-131 C:. 1.83E-04 2.92E-04 I-133 C: 9.29E-04 3.43E-04 I-135 C: 6.61E-04 2.44E-04 Total For Period C1 1.77E 03 8.79E 04
- 3. Particulates Mn-54 C.i 0.00E+00 1.29E-06 Co-60 C: 0.00E+00 1.89E-06 Zn-65 C: 0.00E+00 1.81E-06 Sr-89 C: 3.08E-05 2.18E-05 Sr-90 C: 1.74E-07 1.24E-07 Cs-137 C: 1.08E-06 4.67E-07.
Ba-140 C: 7.12E-05 3.14E-05 La-140 C: 1.22E-04 5.53E-05 Ce-141 C: 0.00E+00 5.50E 08 Total For Period Ci 2.25E-04 1.14E 0
.......________________... __.. ______4__..._________________.
- Zeroesabove present in this table indicate detectable levels.thatSee no radioactivity was Table 2-8 for ty lower limits of detection for gaseous sample analyses.pical l
**There are no batch mode radioactive gaseous release pathways at Plant Hatch. l
{
l TABLE 2 4a E. I. HATCH NUCLEAR PLANT - UNIT 1 i SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES
- i c
Continuous Mo _____...........__de Batch Mode ** Nuclides i Released Unit Quarter 3
...___...........______...___.Q.uarter 4 Quarter 3 Quarter 4 i
- 1. Fission Gases r Kr-83m C: 0.00E+00 3.05E-03
?
Kr-85m C: 0.00E+00 6.67E-03 Kr-87 C: 6.75E-02 2.60E-02 Xe-133 C: 0.00E+00 1.43E-01 Xe-135m C:, 1.43E-01 1.03E+01 ' Xe-135 C:, 1.51E+01 2.
..........__..._______________..._63E+01 _... ____ .._________. ____
Total For Period Ci 1.53E+01 3.6 ,
.__..___.....___.._______....___. 8E+01
- 2. Iodines I-131 C: 4.94E-04 7.28E-04 I-133 C: 4.51E-03 1.10E-03 I 135 C: 7.89E 03 4
___......_.95E-04 Total For Period Ci 1.29E 2.32E
.__...______.....__._____-02 _._________-03 _..______........ ______.
'_3 Particulates Cr-51 C: 3.36E-04 1.08E-04 Mn-54 C:, 1.64E-06 1.40E-06 Co-58 C; 3.42E-05 '1.04E-05 Co-60 C: 6.58E-05 2.72E-05 Zn-65 C: 3.96E-04 1.13E-04 ,
Sr-89 C: 4.49E-05 7.24E-06 Sr-90 C: 2.89E-07 0.00E+00 Nb C: 0.00E+00 2.29E-09 l Mo-99 C; 0.00E+00 2.70E-05 Cs-137 C: 1.02E-06 5.47E-06 Ba-140 C: 2.57E-04 2.32E-06 La-140 C; 5.34E-04 1.70E-08 Ce 141
.._____ ___________2.23E-05 C
..___... ___000E+00 Total For Period C1 1.69E 03 3
__....____.. -__ .__ .____..._.. 02E _04_____________........__ L
*resent Zeroes in this above table indicate detectable levels.thatSee no radioactivity was i fowerlimitsofdetectionforgaseoussampleanalyses.pical Table 2-8 for ty L
**There are pathways at no batch Plant mode Hatch. radioactive gaseous release 1
i TABLE 2-4b E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES
- Continuous
..__....__...__.................. Mode Batch Mode **
i Nuclides Released Unit Quarter 3 ___...__...............___....Q.uarter 4 Quarter 3 Quarter 4 ! i
- 1. Fission Gases
.....__...........____..____..........__ __.......__. .....__ t Xe-135 Ci 1.04E+01 2.46
....__..__..___.....________.......E+01 Total For r-Period Ci 1.04E+01 2.46E+
....______...........................01 2.lodines I-131 I-133 C: 1.56E-04 3.49E-04 C: 1.24E-03 7.70E-04 I-135 C:. 1.49E-03
..............__________........ 47E-04 2 Total For Period Ci 2.89E 1.37E 03
________....._______...__-03 .....___________________.___________ t k
- 3. Particulates Mn-54 C: 0.00E+00 6.96E-07 I
Co-60 C: 0.00E+00 4.24E-06 Zn-65 C: 3.24E-06 0.00E+00 Sr-89 C: 9.27E-06 1.46E-06 Ba-140 C: 6.61E-06 1.60E-06 La-140 C: 2.62E 0.00E+00
....._____.....___.___-05 .________________._____ .._________ ,
Total For Period Ci 4.54E 05 ,
...___...______..________ ____ . 799E
_ _06
- Zeroesabove present in this table indicate detectable levels.thatSeeno radioactivity was lower limits of detection for gaseous Table sample 2-8 for ty analyses.pical
**There are pathways at no batch Plant mode Hatch. radioactive gaseous release 39-4
V t k i TABLE 2-4c E. I. HATCH NUCLEAR PLANT - SITE-SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES
- Continuous Mode
______......______.....___..____..._________ Batch Mode ** Nuclides Released Unit Quarter 3
.____________.......___ ______Q_uarter 4 Quarter 3 Quarter
__________________... 4
- 1. Fission Cases Kr -83m C: 0.00E+00 3.05E-03 Kr-85m C: 0.00E+00 6.67E-03 Kr-87 C: 6.75E-02 2.60E-02 Xe-133 C: 0.00E+00 1.43E-01 Xe-135m C: 1.43E-01 1.03E+01 Xe-135 C 2.55E+01 5
___....._____________..__._____._.09E+01 ______ ________..._______._ Total For Period Ci __________....____-,___ 2.57E+01 ___-___.614E+01
- 2. Iodines I-131 C: 6.51E-04 1.08E-03 I-133 C. 5.75E-03 1.87E-03 I 135 C 9.38E 03 7
________________..__. ___________.43E-04 Total For Period Ci 1.58E 3.69E
._____.__________________-02 _______.. _-03 i
- 3. Particulates Cr-51 C: 3.36E-04 1.08E-04 Mn-54 C: 1.64E-06 2.09E-06 Co-58 C: 3.42E-05 1.04E-05 Co-60 C: 6.58E-05 3.15E-05 Zn-65 C: 4.00E-04 1.13E-04 Sr-89 C 5.41E-05 '8.70E-06 i Sr-90 C: 2.89E-07 0.00E+00 '
4 Nb-95 C: 0.00E+00 2.29E-09 Mo-99 C:, 0.00E+00 2.70E-05 , Cs-137 C: 1.02E-06 5.47E-06 Ba-140 C: 2.64E-04 3.93E-06 La-140 C: 5.60E-04 1.70E-08 ! Ce C: 0.00E+00 ___..._-141 2.23E _____________-05__.. _______________________________ t 1 Total For i Period Ci 1.74E 03 3. , ________________. _______ _ ________10E ___ _04
- Zeroes in this table indicate that no radioactivity was resent ahove detectable levels. See Table 2-8 for typical
.Sowerlimitsofdetectionforgaseoussampleanalyse s.
**There are pathways at no batch Plant mode Hatch. radioactive gaseous release
Table 2-5 E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 GASEOUS EFFLUFNTS - DOSE RATES I Dose Rates Due to Noble Gases Organ Tech Unit Quarter 3 % of Quarter 4 % of Spec Tech Tech Limit Spec Spec Limit
. ... ___________.__________. _ ...__________________________ Limit TBody 500 mrem / 5.35E-02 1.07E-02 1.38E-01 2.77E-02 yn Skin ____3000 mrem yr 1.15E-01 3.82E
...._____/_yr 2.74E 9.14E 03
_____.....___________-03 _________-01__________ _. _ Dose Rates Due to Radioiodine, Tritius a ____________________....,__nd Particulates Organ Tech Unit Quarter 3 % of Quarter 4 -% of Soec Tech Tech t Limit Speg Speg Limit ___..__________________.. __________________________________ Limit Bone 1500 mrem yr 2.42E-04 1.61E-05 1.07E-04 -7.13E-06 Liver 1500 mrem r 2.15E-02 1.43E-03 1.24E-02 8.27E-04 ; TBody 1500 mrem r 2.14E-02 1.43E-03 1.23E-02 Thyroid 1500 mrem r 5.61E-02 8.23E-04 ; Kidney -1500 3.74E-03 3.92E-02 2.61E-03 mrem yr 2.16E-02 1.44E-03 1.25E-02 8.31E-04 Lung 1500 mrem yr 2.30E-02 1.53E-03 1.27E-02 i
.GILLI 3500 mrem yr 8.47E-04 'j 2.15E 02 1.43E 1.2JE 8.21E 04
______________________________________-03 ___________-02 ____________ i
'Cb h
t 4 _h1_
3; 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 Wpe . Tech Unit Quarter 3 % of Quarter 4 % of of Spec Tech Tech Radi- L1mit Speg Spec ation Limit
....____... ___________..____________.,________________L1mit _______. 1 Gamma 5.0 mrad. 8.55E-03 1.71E-01 2.33E-02 4.66E-01
_ Beta 10.0 mrad 1.02E 02 1.02E 01 _____.-_______________________....___ _____1.95E-02 1.95E 01 Cumulative Doses This Year
._-_. ..-____________________________________________________ 4 i
'i Type Tech Unit Quarters % of '
of SpeQ 1,2,1.& 4 Tech Radi- Limit Spec ation Ilmit Gamma 10.0. mrad 4.83E-02 4.83E-01 Beta 20.0 mrad 4.94E 2.47E
---_________________________-02 _________-01________________________
?,.
h2-
p - u I-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 per Quarter Type Tech- Unit Quarter 3 % of Quarter 4 % of of- Snec Tech Tech Radi- Limit SpeQ ation Spec i __- _ -_ ___ .--_ __ -__- limit . -_ __ -_ __ . ..--- Limit Gamma 5.0 mrad 5.58E-03 1.12E-01 1.26E-02 2.52E-01 Beta 10.0 mrad 6.88E
-_---___---------_---_--_-_-03 6.88E 02 1.61E-02
------_--_-----_-__---_-----1E-01 1.6 Cumulative Doses This Year Type. Tech Unit Quarters % of of Spec 1,2,3,& 4 Tech
.Radi- Limit Spec ation L >
_ _,._- . _ - .imit Gamma 10.0 mrad 4.24E-02 4.24E-01
-Beta 20.0 mrad 7.52E 02 3.7
. _ _ --- __- _. . . ---_6E-01 t
v
TABLE 2-7a E. I. HATCH NUCLEAR PLANT - Unit 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 INDIVIDUAL DOSES DUE TO RADIOIODINE TRITIUM,
, AND PARTICULATES IN GASEOUS RELSASES Cumulative Doses per Quarter Organ Tech Spec Unit Quarter 3 % of Quarter 4 % of L1mit Tech Tech !
Spec Spec . ____ . _______.....______..___________ Limi_t.._____________ Limit ! Bone 7.5 mrem 1.41E-03 1.87E-02 4.72E-04 6.29E-03 Liver 7.5 mrem 4.14E-03 5.52E-02 3.26E-03 4.35E-02 TBody 7.5 mrem 4.07E-03 5.43E-02 3.19E 4.25E-02' Thyroid 7.5 mrem 1.52E-02 2.02E-01 1.65E-02 2.20E-01 Kidney 7.5 mrem 4.05E-03 5.40E-02 3.23E-03 4.30E-02 Lun' 7.5 mrem 3.97E-03 5.29E-02 3.13E-03 GILLI 7.5 mrem 4.18E-02 3.97E-03 5.30E 3.14E-03 4.19E 02 _ ..___________ .. _______ ._...______-02 .._______.____________. Cumulative Doses This Year Organ Tech Unit Quarters % of Spec 1,2,3,& 4 Tech Limit Spec Limit Bone. 15.0 mrem 2.81E-03 1.87E-02 Liver 15.0 mrem 1.06E-02 7.05E-02
'TBody 15.0 mrem 1.04E-02 6.94E-02 Thyroid :15.0 mrem 4.99E-02 .3.32E-01 Kianey 15.0 mrem 1.04E-02 6.97E-02 Lung 15.0 mrem 1.02E-02 6.80E-02 GILLI mrem 1.02E 6.81E 02
______ ___15.0__________________-02 __________ _______________________ s Lh.
TABLE 2-7b E. I. HATCH NUCLEAR: PLANT - Unit 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1989 INDIVIDUAL DOSES DUE TO RADIOIODINE TRITIUM, AND -PARTICULATES IN GASEOUS RELkASES i Cumulative Doses per Quarter Organ Tech Spec Unit Quarter 3 % of Quarter 4 % of Tech Tech Limit Speg Speg Limit _____________________________________________________________ Limit Bone 7.5 mrem 1.38E-04 1.85E-03 6.98E-05 9.30E-04 Liver 7.5 mrem 5.98E-03 7.97E-02 2.39E-03 3.19E-02 i TBody 7.5 mrem 5.97E-03 7.97E-02 2.39E-03 3.18E-02 Thyroid 7.5 mrem 9.48E-03 1.26E-01 8.66E-03 1.15E-01 Kidney 7.5 mrem 5.99E-03 7.98E-02 2.41E-03 3.21E-02 Lung 7.5 mrem 5.97E-03 7.96E-02 2.38E-03 3.17E-02 GILLI 7.5 mrem 5.97E 7.96E 2.38E 03 3.17E 02 _-..._______________________-03 ___________-02__ ._____ __________. Cumulative Doses This Year Organ Tech Unit Quarters % of Spec 1,2,3,& 4 Tech Limit Speg ; Limit ' Bone 15.0 mrem 1.18E-03 7.85E-03 Liver 15.0 mrem 1.85E-02 1.23E-01 TBody 15.0 mrem 1.86E-02 1.24E-01 Thyroid 15.0 mrem 3.26E-02 2.18E-01 Kianey 15.0 mrem 1.85E-02 1.23E-01 Lung 15.0 mrem 1.84E-02 1.23E-01 GILLI 15.0 mrem 1.86E _ 02 1.24E 0 _______________.-__________ ____________1 _____________________ i LS-
p ,
' TABLE 2-8.
LOWER LIMITS OF. DETECTICN - GASEDOS SAMPLE ANALYSES The values in this table represent apriori Iower limits of detection (LLD) which are typically achieved _in laboratory analyses g, of. gaseous radwaste samples. t RADIONUCLIDE LLD UNITS
- j. Kr-87 1.31E-07 uCi/ml Kr-88 2.10E-07 Xe-133 1.62E Xe-133m 6.07E-08 Xe-135 5.77E-08 X e-138 2.85E-06 I-131 4.37E-14 I-133 6.16E-13 Mn-54 2.78E-14 Fe-59 4.62E-14 Co-58 2.46E-14 Co-60 2.88E-14
.Zn-65 7.51E-14 Mo-99 6.02E-13 Cs-134 3.64E-14 Cs-137 2.88E-14 Ce-141 4.94E-14 Ce-144 2.02E-13
-Sr-89 1.17E-14 Sr-90 3.82E-15 H-3 5. 82E-12 l
l i
~i 1
l 1 i i L6-
- l
{' '- ' Ti l ____J f
W _
~
~3.oSOLID WASTE r
3.1, REGULA70RY. REQUIREME!frS F
. The Tech'nical Specifications presented in this 1
section are for Unit 1. Requirements for Unit 2 are the same as for Unit 1; however, the n' Technical Specification numbers are not the same. TECHNICAL SPECIFICATIONS
-3.15.3.1 The solid radwaste system shall be used in '
h accordance.with the PROCESS CONTROL PROGRAM to pro /ide for. the SOLIDIFICATION of wet solid wastes and for the SOLIDIFICATION and packaging of other radioactive-wastes, as required, to ensure the meeting of: the - requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive wastes from the site. 6.9.1.9 states in part: The Radioactive Effluent Release Report shall include the following information for each type of solid waste shipped offsite during the' report period:
- a. Container volume
- b. Total curie quantity (specify whether determined by measurement or estimate) c .- Principal radionuclides (specify whether determined by measurement.or estimate)
- d. Type of waste, e.g., spent resin, compacted dry waste, evaporator bottoms
- e. Type of container, e.g., LSA, type A, type B, large quantity
- f. Solidification agent, e.g., cement.
s-3.2 SOLID WASTE DATA Regulatory guide 1.21 Table 3 is found in this report as Table 3-la, and 3-lb. h7_ m_
d EFFLUDff AND NASTE DISPOSAL SEMIANNUAL REPORT 1989 July 1,1989 - December 31, 1989 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS POR UNIT I AND II TABLE 3-1A (Page 1 of 3) t A. SOLID WASIC SHIPPED OFFSITE FOR BURI AL OR DISPOSAL (N l 1. Type of waste l_ l . UNIT l16period month1 lEst. Totall l l ,A. Spent resins, filter slud9es, evaporator ERROR 1 l l_ bottoms, etc. . l m3 l 1.64 E 1 l l I Ci l b. Dry compressible waste, contaminated m3 l l .115E 3 l 1 0E1 l l equio. etc. l I 4 .15 E 2 I l I C: l c. Irradiated components, control rods, mH I 3.85 E o i 2 0 E1 l l l l N/A E ' l
- l. d. Contre! Fred Drive filters l Ci l N/A E i E l m3 l 7 .66 E o '
- i. l I i
I Cl ll Y'6t 1 2, oE l e. Other (describe)
- DAW compacted at SEG l* m3 l l eouio. etc. ' ** e,s14?i 4 4 041 l 1.43E 11 l
- 2. l Ci ! l .22 E-1 1 2, o E t l Estimate of major nuclide composition (by type of waste) l ISOTOPE
- a. Zn-65 1 PERCENT l_ } CURIES l l 54.52 607.90 l Fe 55 l l
l Co 60 1 17.55 l 195.68 l ' l r v' 1 't l 13.35- i 148.85 -l j l 2.39 1 ' tner _utenes 2_6.65 l b. Co 60 i 12.19 i 35.92 -l l 2n 65 l 27.53 1 1.06 l l Fe 55 ) 50.05 1 1.93 l l Cs 137 1 4.42 1 0.17 l l 8.32 1 0.32' l other isotores 9.68 l
-0.37 I
l c. N/A I l i i l- {_
'l 1 I i
L l I l !~ i I l I ; i; l d. Co 60 l l l 1 l l Zn 65 1 55.078 l 10.895 l l Ni 63 I 8.655 1 1.712 l I 3.304 1 0.654 l other isocones i l 1 l 32.961 1 6.520 l I l l *e . Co 60 l l Zn 65 1 -26.8 I 3.3E-2 l I l- Fe55 I 50.8 I 6. 2 E-2 l l Cs - 137 1 4.2 l SE-3 l l -other isotopes 1 6.7 I 8. 2 E-3 } L i 11.50 l 1.4E-2 l l, 3. Solid Waste Disposition I !. Number of' Shipments l Mode of Transportation Destination j 31 cask
'l i 32 Barnwell &
van' SEG (Oakridge, TN) B. LIRRADIATED FUEL SHIPMENTS (Disposition) Number of Shioments Mode of Transportation l Destination N/A ) A8-
' 1 I
/ EFFLUENT AND ESTE DISPOSAL SEMIANNUAL REPORT 1989 i July 1,1989 - December 31, 1989 d
SOLID MSTE AND IRRADIATED FUEL SHIPMENTS ' FOR UNIT I AND II 1 TABLE 3-1A (Page 2 of 3) A. SOLIO WASTE SHIPPE0 OFFSITE FOR BURIAL OR d fuel) DISPOSA l 1. Type of waste l_ l UNIT l 6 monthlEst. Totall I
- a. Spent resins, filter sludges, evaporator l I period i ERROR % l l_ bottoms, etc. j m3 E 1
l- l l .b. Dry compressible waste, contaminated Ci i E E m3 l l 'eaulo, etc. l I . E I l l I C: 1 E I l_
- c. Irradiated components, control rods, l_ mu 1 E l E I l
l 1 C; l- E
- d. Control Rod Drive Filters I E
' l l_ mU l E I l
l- a m compacLeo at m 8 Ci i
- e. Other-(describe) g , ,3 E , E j l_ eauto. etc. ** Solidified Oil Ci 1 4. 4 6E 0 l l
- 2. I i ?. 5 cf -?l 2 . 0 E1 Estimate of major nuclide composition (by type of waste) l l- ISOTOPE l a- see nace one I PERCENT l CURIES l
l-L l l I- I i I _. l . l_ , I I _1
!_ I l
l l_ e een nnee one l l l_ I l l
- 1. i l l
- l. I I l
l- I ! l l_ 1 e see nace one I l I l -l l
!_ l t
l-
- l. l I l
l- 1 I l l d. see DDRO One l l l l- ! I l l- 1 I l l __ 1 i l l_ I i 1. ! l_**e. Co 60 l l I _l 2n 65 l 51.7 l 1.34E-2 l
-l p, - s q 1 16.2 l 4.2E-3
- l l_ re 137 l 6.3 l 1.03E-3 [
l_ l 14.9 3.56)E-3
-nehov tantones- 1 10.9 l
l l 2./VJE-J l
- 3. Solid Waste-Disposition
' Number of Shioments Mode of Transportation 1- van Destination 11antora, washington total page 1 & 2 64 shipments
.B.
IRRADIATED FUEL SHIPMENTS (Disposition) Number of Shioments Mode of Transportation p- Destination L9-
- g. y n -
-3 ,
EFPLUEffI' AND WASTE DISPOS /4 SEMIANNUAL REPORT 1989 July 1, 1989 - December. 31, 1989 SOLID WASTE AND IBRADIATED FUEL SHIPMEtTTS FOR UNIT I AND II TABLE 3-1A (Page 3 of 3)
*
- NOTE: The waste volume and curie content recorded'for waste that was processed at Scientific Ecology Group reflect the actual amounts that have been processed and buried at Barnwell, SC. Since SEG-utilizes supercompaction, the volume shipped as opposed to the r '
volume buried is dramatically different.. A summary of-the total uncompacted volume and curie content shipped.for the period 7-1-89; to 12-31-89 is as follows: Total volume uncompacted waste shipped - 561.13 M3 ! Total curies shipped = 2.338 C1 ! Total' waste volume awaiting processing = 507.14 M3 1
.i Total curies awaiting burial = 2.215 Ci i
~!
L !
]
4 i i i 1 b
)
. l
y EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1989 July 1, 1989 - December 31, 1989 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNIT I AND II TABLE 3-1B
-l ivPE 1 CURIE I PRINCIPLE ; BURIAL l NUMBER of l VOLUME OF l- OF \ QUANTITY /l NUCLIDES / l t FYPE lSOLIDIFICATI CONTAINER l WA$TE l CONTAINERS l EACH CONTAINER ISHIPMENT /lAGENT
!DETERMINEDI OETERMINATION l DESCRIPTION ! SHipDED IcOBIC FEET Ift 3)lCONTAINER !
IdewateredI lZn-65, Co-60 i EL-210 I
. resins I 264 I l I l LSA/ g HIC i 27 1 202.1 INRC TypeAl N/A Cs-137,Fe-55ll' measured
. i _ _ _ _ _ _ _ _ _3._ _ __ ___ y ___ __ _ __ _-- -
Idewateredi IZn-65,Co-60 lr---EL-142 l l l j
----- -~~~~~~~~-
i I resins I 851 IFe-55,Mn-54 I HIC
---- --- -- ~ ~T ----- I - T-- ~ ~ ~~ --i L---- T --ll S A /
I i I l i I 2 1 132.4 lNRC Type l N/A i ' I I I l 4.____________p______________p_____ I B l 4 I --t-----------------------l----'----- I Isecei B-25 I ILSA
't DAW compact ed lI lCo-60,Zn-65 3.85 Fe-55,Cs-137 I box I 156 I
I 93 lstrong i N/A I l- '- __.1sstimate____l_______________l,_______! i I I __hish___.j__________ { l CRD l Co-60,Zn-65 I I I IDOT l l filters 119,7810 ;lFe-55,Ni 63 gchem nuclear 2 drum over- 38.3 2 lTypeA l N/A [_________{________f=sassrse_____jl_
.ISEC i ICo-60,Cs-137 Imetal bins Esch_1 h
; ; ; LSA
' compact ed l l . 22 E-1 IFe-55,Zn-65 i strong, tight l
- I 505.3** l STC- g N/A i I
waste l lestimate I I bins i I l 1 _________L________t._____________i_______4._________.,
'8_________f l solid-Co-60,Cs-137 l drums strong 55galdruml l lLSA f Ioil to I I '
2.59E-2lFe-55,Zn-65 i i 21 i 7.5 i STC l concrete
, (gypsum) '
lestima I ti i 1_HanfordL________1_______te_____J_____ght__________t.________L____________ l l : I _ __ _ ___ _I I I l l I I ' I I I
) {
I 1 ; I I I [ g I
.I I. i l I l il I I i l l l l
i l l s
^
l l I l l ; l I I' l I i l l l I
.l I 'l l l l l I l !
'l I i
! ! l l i {
I' I I l l l l
' I I I I I I l-i i }
l- f i ! l l l l _ i 1 - i i Notes: LSA - Low Specific Activity STC - Strong' Tight Centainer i SEG _ Scientific Ecology Group DAW - Dry Active Waste
*-Due to use of buring containgre of various sizes (Ex.12 ft ", 16 ft , 9h ft ). No number can be given.
I
**-This is total volume buried at Barnwell by CEG. ,
i I i I a ., a
46- CHANGES 'IO ' DIE PLANT HATCH ODCM p Technical Specifications 6.9.1.8 and 6.9.1.9 require in part
~
that-changes to the Plu.It Hatch Offsite Dose Calculation Manual (ODCM) be reported to the Commission in the next Semiannual Effluent Release Report.
. On August 3,1989, the PRB recommended approval of changes to the Plant Hatch ODCM pertaining to a. change in the location of the controlling dose receptor for_ gaseous releases, changes -
vhich have occurred in the Radiological Environmental Aonitoring Program (REMP), and editorial changes. A change in the location of the controlling dose receptor was ' the result of changes in land use in the vicinity of Plant 1 Hatch, that was-noted during a lond use survey as required by HNP Technical Sr.ecification 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 controlling dose receptor identifed in this revision to the ODCM was identified as a result of' these potential dose assessments. Documentation of PRB review and approval
' report .
of these changes is presented in Appendix A of this Appendix B of this report contains the modified pages of the Plant Hatch ODCM discussed in Appendix A. These modifications to the Plant Hatch ODCM are identified as Revision 5. t
) ..
2
I
' _ /
4
. i i i
5 ' MerBOROLOGY L l
, In accordance with Technical Specification i
6.9.1.9, the' annual- summary of meteorological I c, data collected at Plant Hatch over 1989 is :i presented in this-section. 5.1 1989 Meteorological Data I e . Attachment 1. Joint Frequency Tables of Wind Speed and Wind-Direction 10m vs Delta lemperature 60-10m. i e Attachment 2. - Joint Frequency T3bles of Wind- Speed and Wind Direction 6Dm vs De',ta Temperature 60-10m. a e' Attachment 3. Joint Frequency lables of Wind Speed and Wina Direction 100m _ vs Delta Temperature 100-10m. e Attachment 4. Wind Roses from 10m (Seasonal and Annual). ! e Attachment 5. ' Wind Roses from 60m (Seasonal and Annual). e Attachment-6. Wind Roses from 100m (Seasonal and Annual), e- Attachment 7. Percent- Data Recovery by Parameter and for Pertinent-Composite Parameters for 1989. e . Attachment 8. Plots of Monthly Averages and Averages of Daily Extremes of Ambient Temperature and Dew Point Temperature. e . Attachment 9. . Daily, Monthly and Annual Precipitetion for the Period-of January through December 1989.
- e- Attachment 10. Descriptive Paragraph Comparing 1989 with Previous 1 years.
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. ATTACHMENT 2 .(continued)' 4 Cf 82 y -
. HOURS AT EACH LIIND SPEED At4D DIRECTIOt1 PERIOD OF-RECORD = 89010101-89123124 STABILITY CLASS: D DT/DZ ELEVATIOt ti SPEED:SPDGOM DIRECTI0th DIRG0t1 LAPSE :DT60-LIIllD SPEED (f1PH)
LIIND - DIRECTIOTI 1 -3 4 -7 3-12 13-18 19 >24-TOTAL II 8 44 37 18 2 0 109 IINE 2 29 27 9 0 0 67 t1E 8 57 81 61 4 0 211 ENE 4- 72 39 17 2 0 134 i E 14 35 29 2 2 0 82 ESE 10 25 21 3 0 0 59 SE 5 25 13 4- 0 0 48 SSE 4 26 13 2 0 0 45 5 4 21 25 20 1 1 72 SSki G 24 27 29 11 0 97-StJ 5 34 34 20 1. 1 95 LJSki 7 29 34 17- G 0 -93 tJ 3 39 67 31 8 0 148 (Jtild 8 44 33 17 4 0 106 titJ 3 33 26 12 1 0 75 l1Ntd 2 38 28 10 0 0 -78 TOTAL 33' 575 534 272 .42 2 1519 PERIODS OF CALM (HOURS): 6 UARIABLE DIRECTIGH 0 HOURS OF MISSIrlG DATA: '1942
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HOURS - AT EACH lJIIO SPEED AtO DIRECTIOrl~ T PERIOD'0F RECORD;- 89010101-89123124- , J'2 STABILITY CLASS:4 L D '- DT/DZ. ELEVATIOri: SPEED : SP 100!4 : ; D IRECTIOll: DI10011 . L APSE:DT100- - e (JItO SPEED (IPH) -
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HOURS AT EACH UITO SPEED ATO DIRECTIOf1 PERIOD OF' RECORD =: 89010101-89123124 STABILITY CLASS: E' DT/DZ. ELEVATION: SPEED:SP100M DIRECTI0ti:DI100M LAPSE:DT100-UI!O SPEED (MPH) WIND DIRECTIOil 1 -3 ' 4 -7 8-12 13-18 19-24 >24 TOTAL tt 1 18 38- 37 20 0 114 HilE 5 25 23 64 18 2 137 IlE 4 30 81 119 52 8 294 ENE 5 38 73 52 8 0 176
; E 6' 31 52 ' 49 5 0 143 ESE G 26 62 52 5 0 151 SE 5' 29 65 .37 1- 0 137 SSE 7 12 51 71 9 0 150 S 7 17 71 .105 21 2 223-SSU 7 15 84 101 38 4 249 SU G 22 69 108 23 3 231 USU 5 21 58 92 14 6 -196 U 4 23 47 64 .25 1 164 WiM 7 18 40 35 10 4 114 IM 2 11 44 37 15 1 110 lit M G 16 33 22- 9 1 87 TOTAL 83 352 891 1045 273 32 2676 PERIODS OF CALM (HOURS): 0 i
UARIABLE DIRECTION O l HOURS OF MISSING ~ DATA: 1264 l l
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. ATTACHMENT'4b. PLANT HATCH 10m METEOROLOGICAL TOWER WIND ROSE. -
JANUARY li1989 eTHROUGH MARCH 31, 1989' y -2 l : , 9 _e fg (WItB FR0t1) - t x aWIND SPEED LESS THAN3.5 NH
+WHID SPEED. LESS THAN7.5 WH xWHB SPEED LESS THAN12.5 ffH
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' ATTACHMENT 4c. -PLANT HATCH 10m METEOROLOGICAL TOWER WIND ROSEE APRIL- l',1989 LTHROUGH JUNE 30, 1989 u -
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Wired Speed 60m d3.9 I L_ Wind Speed 100m 92.8 i Wind Direction 10m 98.4 ) Wind Direction 60m 83.8 i i Wind Direction 100m 97.6 i Delta. Temperature 60-10m 93.2 l g Delta- Temperature 100-10m 92.2 Temperature 10m . 98.2 Dew Point Temperature 10m 91.2 : Rainfall 91.6
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ATTACHMENT 0. PtANT HATCH MONTHLY 11 . n. . .=. J . _=. .=_- =. . t .=_ AVERAGE AND AVERAGE OF THE DAILY + ~~
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EXTREMES OF DEh. POINT TEMPERATURE 10m _ __ ,_~_ _~. _ ' . _ ~ _
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ATTACHMENT 9. DAILY, MONTHLY AND ANNUAL i PRECIPITATION FOR 1989 E Month (Inches) Month (Inches) January 1 0.06 June 2 0.39 January 15 0.09 June 6 0.48 4 l January 30 0.61 June 9 0.05 TOTAL 0.76 June 10 0.12 June 15 0.16 February 18 0.03 June 16 0.58 February 19 0.03 June 17 0.13 i February 21 0.32 June 19 0.10 7 February 28 0.41 June 21 0.04 q TOTAL 0.79 June 22 0.62 i June 23 0.12 March 1 0.14 June 24 0.18 1 March 2 0.48 June 29 0.41 ; March 3 0.04 June 30 0.19 1 March 6 0.10 TOTAL 3.57 March 21 0.27 March 22 0.23 July 3 0.42 March 23 0.28 July 5 0.19 March 24 0.22 July 12 0.13
. March 25 0.19 July 13 0.06 ,
March 26 0.07 July 15 0.54 March 30 0.13 July 16 0.17 , TOTAL 2.15 July 19 0.54 July 21 0.17 April 8 0.02 July 22 0.07 April 9 0.11 July 31 0.13 April 10 0.18 TOTAL 2.42 April 11 0.57 April 12 0.16 August 1 0.15 April 30 0.02 August 2 0.84 TOTAL 1.06 August 8 0.15 August 9-31 Missing May 1 0.08 TOTAL 1.14 May 2 1.19 May 5 0.32 September 1-5 Missing May 9 0.21 September 6 0.03 May 14 0.39 September 16 0.90 ; May 27 0.12 September 17 0.02 TOTAL 2.31 September 21 0.35 September 22 0.08 September 25 0.08 September 26 0.12 TOTAL 1.58 1 l l 03 f 03U441 WU/ i l'
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l ATTACHMENT,9 (Continued) ; i i i Month- (Inches) Month (Inches) l l* October 1 0.26 December 9 0.08
- October 10 0.20 December 12 0.42-October 17 0.05 December 17 0.11 1 0.25
, October 18 1,40 December 18 1 i; TOTAL 1.91 December 19 1211 l TOTAL 2.54 :
j; ! November 8 0.40 l s November 9 0.04 , L November 15 0.40 L November 16 0.18 i 0.05 ; November 26 November 28 0,16 .i TOTAL 1.23 1 t I 1989 Annual-Total = 21.46 l i i I '- . i ' f
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[I l ATTACHMENT 10. HATCH 1989 METEOROLOGICAL
SUMMARY
i I The sixth year of operation for the Plant Hatch 100m Meteorological Tower was about average for the years of data collection. The average data recovery for all parameters shown in Attachment 7 was 93%; and for the pertinent parameters of wind speed and direction 10m and delta ; temperature 60-10m was 90%. This was somewhat lower than in recent years due mostly to the intermittent failure of strip chart recorders, particularly at the 60m level wind speed and direction. This problem i should improve next year with the use of a computerized data collection , system. 1 The ambient and dew point temperature plots shown in Attachment 8 show a j high degree of normal climatic variation between years, 1989 started out j warmer than in recent years until August when the temperatures dropped I below seasonal averages. This continued through December with the December averages falling below any of the previous 5 years of record. The wind roses in Attachment 4, 5 and 6 agree well with previous years - and between levels on the tower. As with the previous few years, there , is better agreement between the 60 and 100m levels than with the 10m level. The peak direction at the top two levels is from the northeast > (the secondary peak at 10m) and from the southwest at 10m. The secondary ; peak at 60 and 100m is from the west. The seasonal wind roses show ' stronger southwest influence in the first half of the year with northeast , winds controlling the third quarter. During the fourth quarter the upper , two levels show the strong westerly influence that helped produce the colder than normal temperatures. The joint f requency tables of wind speed and direction versus delta temperature are shown in Attachments 1, 2 and 3. The table below < summarizes the last five years of joint f requency data. The table used the wind speed and direction f rom the 10m level versus the delta temperature between 60 and 10 meters. The 1989 data year agrees very ' well with the 6-year average. There were slightly more neutral hours - than occurred in the 6-year average. There has been a continuing trend over the last 3 years of more unstable ( A stability) than during the first 3 years of operation. Overall the stability percentages for 1989 are closer to the 6-year average than any other year shown. t 657bA022190/4
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b , v ~ Plant Hatch Stability Classification e L " Stability Percent Stability 6-Year Group 1989 1988 1987 1986 1985 1984 Average l A 11.8 12.2 15.7 7.8 9.3 8.4 11.0 L 8 4.0 4.0' 5.0 3.5 4.7 5.2 4.4 L C 3.3 3.1 4.0 3.0 5.5 5.8 4.2 0 22.0 18.4 16.8 21.4 26.5 19.9 20.8 E 33.1 31.8 31.6 37.6 31.8 31.8 33.1
- F 12.8 15.3 12.3 13.7 11.3 12.4 13.0 F 13.0 15.2 14.6 11.0 10.9 16.5 13.5 Total Hours 7886 8541 8162 8037 7860 7928 The precipitation totals (daily, monthly and annual) are shown in Attachment 9. The total for the year was 21.46 inches which was much below the area normal of about 45 inches. Most of the month of August was missing, helping to make the total lower. However, the overall rainf all total for the first.4 months of the year was only about 4.5 inches. Therefore, there may have been problems with the rainfall data that was not apparent on the-strip charts. These potential problems will be investigated in the future.
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lP. ANT H. I. NATCN I I INRM T. TLE: PAGE 1 0F 2 l DOCUMENT CHAhet RioutST ll . . , l1 CHANGE AFFECTSB - ( ) UNIT ONE ( ) UNIT TWO Ii (X.) UNITS ONE AND TWO ll REQUEST DATE : 7//8/89 REQUEST NO.: 89-/7 ll REVISION NO._ 6 3 lNl (Ul REQUEST INITIATED: ( ) ON-SITE, ' (><) 0FF SITE BY: Sc5 Fu t fw Jeevrees (CI ' ' lL] 00CUMENT(S) AFFECTED: lEl CMsi rF BosF r2 L e utAr/dr/ AMA/ud L lAl i IR\ SECTION/ TITLE : 2. Z/sosous Et*Nied oose 4/e Ad oose c e /e a la /,c ,,2 ll 3 o / 2, Ln In
. o a es l En siren m en ts / Mu i torina L eo m ernre eam g
g3g < < - lAl lFI DESCRIPTION
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<e r/,u fren CHANGE for de.s er[ os ATTACHhen MARKED UP COPY Ol lEl t' h o n e - *
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(Tl ' lYI , II lAl IN] REASON FOR CHANGE : Co/c,dia. rere,/or /, a n c - /uee/o-l0l ure sw-na nsi e A 2 is/1.:ns . /4e /n /
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K. tJ.10 sCruck en To s)* O de& V{M*4h m** T U lPl ENVIRONMENTAL IMPACT STATEMENT REQUIRED: ( ) YES lLl DESCRIBED IN FSAR: (> 4 NO (><) YES ( ) NO
!!l UNREVIEWED SAFETY QUESTION: ( ) YES (><) NO lAl PRIORITY: ( ) EMERGENCY RELIEF (
INl ) RELOAD LICENSING ( ) INDIVIDUAL SUBNITTAL g ICI NO. ATTACHMENTS: _Y ll hA l / ?//8/99 NSC MEMBER DATE NSC SUPERVISOR
/$"l-M $$a h / 8/ /n DATE MANAGER'ASC DATE II lI II ll l,i h FORWARD TO PRB SECRETARY FOR INITIAL PRB REVIEW Y [ d / #' 7'D ll r.
ll PRB RECOMMENO GE: M.. _( /) YES ( ) NO I4 - 9l l lPI / P-3-F1 l IRI PRB MEETING NO. DATE l8l IF NO, GIVE REASON: Il 7 i l_l....__.....__............ ...... ..__..__... i
......__ . __.......__... ...... ... .. ...i Il REQUEST: ( APPROVED ( ) DISAPPROVED II 1 iPl IF PPROVED, VE REASON: I l
Ae r dw~MA- 1/ S~~ ifs' l1 V~ PLANT MANAGER DATE
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l l~I l ENG-0015 Rev. 1 B02.13 I 40AC-REG-UU3-U5
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DOCR No.- 99 ,j 7 i ATTACl#ENT 2 M No._ A ! M- C OF _229
.e PROPOSED ODCM CHAMts [\
I. Thah.istofFigureswasmodifiedtoaddanewfigurewhichshowsthe location of a new control station (No. 416) for TLDs and vegetation. ! j II. Table 2.212 was modified to incorporate changes in the location, age group and dispersion and deposition factors for the new critical. ! receptor as a consequence of the Annual Land Use Survey, j III. Sheet 2 of Table 2.2-13 was modified to provide default values for , fractions of annual intakes of. locally grown leafy vegetation and stored-vegetation. ! IV. j! The additionfirstofsentence of Section 3.0 was modified to accommodate th Figure 3.0-4. V. Sheet 2 of Table 3.01 was modified to add a new control sta} 416)-for at StationTLDs 309.and vegetation and to delete the collection of vegetation be marked by a double asterisk.The footnotes referring to the river stat , VI. Figure 3.0 4 shows the location of the new control station (No. 414). VII. Reference 22 added. which documents the recent land use survey and its follow up was Add s foona l Proposed Changes o *
- l. Change En V/ron in en fA l" to ESSlu en Y on i page 20-I. c z.
Renum ber ectua hons in seehon 7. 2. 2. 6 a,id ch a nge e9aahon Lwl a.s marked.
- s. {gyise 2.2.z.c to re fle ef iv,e coc,aef
~ hhn aca.] speei fa ca tions seefions foe r%d, o Io3 i cx I mon i foc o ng pro gain re poc h ng.
- 4. Eelifor u a I ch anges to clari fy M e cokeci tini t w.n bec he gers sechons an d g ca.m ,na),cel co< rec han s .
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*- - - _- _ _ _ . _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ . , - . - , - - _ _ _ _ . - . . . _ . - _ , . _ ~ ~ , . . . - , . - . , ,-~ - - - , ,
_ _ _ . _ _ _ _ _ _ . _ . _ _ _ . _ _ _ . . _ _ - . . _ _ . _ _ _ . _ _ - - ~ _ TABLE OF CONTENTS
;f,'
1.0 fAtt Llouin EFFlutNTS 1.0-1 i 1.1 L10010 EFFLUENT NONITOR SETPO!NTS 1.1 -1 1.1.1 Liquid Radweste EffluentANonitors Rado a.h o n 1.1.2 1.1 -1 Plant Service Water Monitors 1.1 -9 1.2 00$E CALCULATION FOR LIQUID EFFLUENTS 1.3 1. 2-1 00$E PROJECTIONS FOR LIQUte EFFLUENTS 1,3-1 1.3.1 Monthly Dose Prgjections 1.3.2 Dose Projections for Specific Releases 1.3-1 1.3-2 1.4 1.5 DEFINITIONS OF L10U10 EFFLUENT TERN 5 u LIQUID RADWAsTE TREATMENT SYSTEM 5 1.4-1 ? 1.6 NIXING OF L10010 WASTE TANKS 1. 5-1
- 1. 6-1 2.0 GASEGU$ EFFLUENTS
, 2.0-1 2.1 4ASE005 EFFLUENT NONITOR SETPOINTS 2.1 -1 i 2.1.1 Unit 1 Reactor Du11 ding Vent Stack, 2.1 -1 I Unit 2 Reactor Du11 ding Vent Stack, Unit 1 Recombiner Du11 ding Vent, and -
)
Duilding Exhaust Augmented Ventilation 2.1.2 Main Stack f 2.1.3 Determination of Allocation Factor, AS 2.1-4 2.1-6 2.2 4ASEOUS EFFLUENT DOSE RATE AND DOSE CALCULATIO 2.2-1 2.2.1 { Unrestricted Area Dound DoseRatof 2.2-1 I' 2.2.1.a Dose Rates.Ou Noble eases 2.2-1 i 2.2.1.h Dose Rates Due Radiciodines, 2.2-2 Tritium, and Pa iculates l 5 y;.' 2.2.2 Unrestricted to Individual Area Air Oose and Dose 2.2-4 2.2.2.a Air Dose in Unrestricted Area 2.2-4 2.2.2.b' Dose to An Individual in - 2.2-5 Unrestricted Area 2.2.2.c Dose Calculations to Support 2.2-17 Other Specific Technical "d Specifications ' DOCR No.--- Q-2 /7 -- HATCH 00CM, REV,3 ATTACHMENT No. 8/R7 i SHEET - 8 OF 28
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,*r . TABLE OF CONTENTS fCONTINutel
.? -
f.411 2.3 METEOR 0 LOGICAL N00EL I
- 2. 3 -1 2.3.1 Atmospheric Dispersion 2.3-1 l 2.3.1.4 Ground-Level Releases 2.3.1.b Elevated Releases 2.3-1 2.3-3 ,
2.3.2 Relative Deposition
- 2. 3 -6 2.4 DEFINITIONS OF GASE0US EFFLUENT PARAMETERS 2.4-1 )
2.5 4A5E005 RADWASTE GMttett-TREATMENT SYSTEN2.5-1 3.0 l RADIOLOGICAL ENVIRONMENTAL MONITORINS FE N 3.0-1 4.0 TOTAL Dose DETrantNATIONs-4.0-1 I 5.0 P0"EN"MA. RACr1 TO l AC"IVE 'I :5 IN51DE T KNDERS OF T4E PUBLIC DUE TO THEtt 5.0-1 4E 5ITE BOUN IARY l 4 h F E f
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u 1 5.7' , 1 DOCR No. 89 /7 ' ATTACHMENT No. 2 i HATCH 00CM, REY 1 5/11/84 5HEET I OE EB ' 11
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L , LIST OF FlauRES f.iSt3 11111 f.481 1.1 -1 Emaaple Calibration Curve for Liquid Effluent Monitor 1.1-10
- 1. 5-1 1.5-2 Liquid Radweste Treatment System (Unit 1)
Liquid Radweste Treatment System (Unit 2) 1.5-2 1.5-3 2.3-1 2.3-2 Vertical Open Standard Terrain Deviation Recirculation of Material in a Plume (eg) Factor 2.3-7 2.3-3 Plume Depletion Effect for Ground-Level Releases 2.3-4 2.3-4 2.3-9 2.3-5 Plume Depletion Effect for treater Than 100 e teleases Relative Deposition for Ground-Level Releases 2.3-10 2.3-6 Relative Deposition for Greater Than 100Ma Releases 2.3-11 2.3-12
- 2. 5-1' Condenser offgas Treatment System 2.5-2 3.0-1 Radiological Environmental Sampling Location Map 3.0-5 (Site Periphery) 3.0-2 Radiologi (Beyond vironmental Sampling Location Map 3.0-4 ite Vicinity) 3.0-3 Location o Additional Control Station for Milk 3.0-9 ;
\ 3, o 4 t,Jc>,, J Mdahonal confroI aMion a,o ,o pac rt a s and V dahon 9 _. p n ,.3 1 . DOCR No.- 89-/'7 ATTACHMEN No. 2 SHEtT _ OF 28 HATCH ODCM, REV 3 8/87 iv LL
- j M
I k l The rednestlide concentration for a wstee tan from the sus of measured concentrations as determined b ; required in RETS Tables 4.15.1-1 (Unit 1) and 4.11.1-1 (Unit ; i
! Cj = I C,+(c a+Cs+Cf+C) !
i g t i (2) where: 1
\
C, = the concentration of each measured gasmus emitter o gamma-ray spectroscopy of the particular wste sample. Ca
= the concentration of alpha emitters in liquid wste as measured in the MONTHLY composite sample.
analyzed for gross (NOTE: $ ample is I
). .
Cs = the measured concentrations of Sr-eg and Sr-90 in liquid .\ weste as observed in the QUARTERLY composite sample. {' 1 Cg = l the measured concentrations of Fe-55 in liquid waste as observed in the QUARTERLY composite sample. Ct = , the measured concentration of H-3 in liquid weste as L determined from analysis of the MONTHLY composite samp . The C, ters wi1T be included in the analysis of eachr batch; terie , alpha, Tables'4. sptiums, iron, and tritium will be included in accorda ; I and 4.11.1 , as appropriate.
^
Uru Y d l , Sten 2 C(Una f2) The measured radionuclide concentrations u on are us factor, DF, which is the ratio of total dilution flow rate to tank fl ow rate DOCR No. 89 /7 HATCn OoCn, Rtv i s/11/s4 1.1 -4 ATTACHMENT No. 2 smri - S or z B
h t-e !
'I l'
1.2 00$t CALCULATION FOR L100!0 EFFLUENTS ! I For ligeN release from Plant Hatch to the Altameha River, the only hum exposure' pathway is due to consumption of fish taken from the river.
- No knoW ;
drinking water is taken from the Altamaha River downstream from Plan . The methodology for calculating doses to an individual due to fish consumption is presented in this section. ! The dose contribution to the maximum exposed individual by way of fish i consumption from radionuclides identified in liquid effluents released to unrestricted areas will be calculated for the purpose of implementation of '
" I' ' RETS 3.15.1.2 (Unit 1) and 3.11.1.2 (Unit 2). In accordance with Appendix A of Reference 3, noble gases are excluded from these dose caled14tions. Doses to an individual are calculated as follows: {
e i-0, = I A1 , I ett Cig e -At te Fg (g) ' i t=1 where: , I 0, a , the cumulative dose commitment to the total body or any organ, t, i due to radioactivity in liquid effluents for the total time period - e ,
! 4tg in aren, (Reference 1).
t=1
~
atg = the length of the 6th time perind over which C i g i
- k. and Fg are averaged for all liquid releases, in hours.
Cig the average concentration of radionuclide i, in undiluted liquid effluent during time period 4tg from any liquid release, in vC1/m1. ; kj .= 1 the decay constant for radionuclide 1 (sec-1). - HATCH 00CM, REV 1 SA U84 1.2-1 DOCR No. 89* ATTACHMENT No. 2 SHEET b OF 2O ,
i l 2.0 M SE00$ EFFLUENTS l l ( At Plant Match there are four points where radioactivity normally is released to the atmosphere in gaseous discharges. These four release points are: The main stack which serves both units. { Unit 1 reactor building vent stack. ' Unit 2 reactor building vent stack. Unit 1 recon 61ner building vent, l i l In addition to these four release points, releases also may be made from di,ngp enhaust augmented ventilation system (s) provided the Radiological { 4.....mnat' Technical Specifications (RETS) allow releases via this pathway. ' The main stack serves as the discharge point for the following release sources from.each unit: j Mechanical vacuum pumps. ) Off-gas system. Bland seal exhaust. Standby gas treatment system through which drywell purges are discharged. The waste gas treatment building ventilation also discharges through the main stack. Each reactor building vent stack serves as the discharge point for the following (of each respective unit): _ Reactor building. )
. Refueling floor ventilation.
Turbine building.
+
Radweste building. > J The Unit 1 recombiner building vent discharges directly to the atmosphere. ' DOCR No. 89 /7 HATCH ODCM, REV 3 8/87 2.0-1 ATTACHMcNT No. 2 SHEET 7 OF 8O
l Geseems effluent monitor setpoints are required only for noble gas moni serving t(e release points; the methodology for calculating noble gas monitor setpoints'is presented in section 2.1. . Although setpoint calculations are
- not required for radiciodine and particulate monitors, the methodology forl assuring that the potential organ dose rates due to radiciodines, tritium, and particulates in gaseous releases from the site do not exceed the limit '
of RETSS.M.:.i(M for Unit 1 andi.".:.1(t) for Unit 2 is presented in the ' note following section 2.2.1.b. I
- 3. Is . z. I 6. 3,n.e.(b.
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E6 DOCR No. 89 '7 ATTACHMENT No. 2 0683n SHEET d 0F 2S NATCH 00CM. REY 3 8/37
,m 2.0-2
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i { TABLE 2.1-2 DOSE FACTOR $ FOR EXPOSURE TO 0! RECT RA0!ATION i
. (Location:NOBLE FRON GASES IN THE ELEVATED FINITE PLUME
- 4 o Site Soundary in ENE Sector at 1545 m) I i
jtugligt v-endw (V)** y-Air (al***
.\
l Kr-ele 8.25E45 Kr-45 8.69E45 i 1.26E-06 1.35E46 Kr-47 4.40E44 ! 4.59E-04 ! Kr48 1.09E43 Kr-49 1.13E43 . 9.44E-04 9.87E44 Kr-90 7.00E44 . 7.38E44 ! Xe-131m 1.68E46 - Xe-133m 1.76E-06 I 1.29E45 1.37E45 Xe-133 1.38E45 1' 1.43E-05 Xe-135e 2.42E-04 Xe-135 2.59E-04 ( 1.33E44 1.42E44 ' Xe-137 9.55E45 1.02E44 . ' Xe-138 6.16E44 (i Ar-41 6.44E44 7.34E44 7.72E-04
, -l>,
l DOCR Ho. 89 ~'I ATTACHMENT No. 8 [ mur 9 or _ 2 6 - , b .
- Values calculated in accordance with methodologies presented in Section 5.2.1 of Reference 1 and Appendix F of Reference 3, with meteorological c Reference 19. joint frequency distributions presented in Reference 16;
~
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pC1-yr
*** mrad-sec wC1-yr <
^~~'
l
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' i i
2.2 !' SASE995 EFFLUENT 00$t RATE AND D0SE CALCULATIONS I 2.2.1 unrenthetedAreaSr.daryDoseRates 2.2.1.4 Bose Rates Due To Noble Gases ' k 3.1S. ? . In. Q 3. ss. t. Is. ForthepurposeofimplementationofRETSD.10.0.1.e(Unit 1) ands.it.!t: Y (Unit 2), the dose rate in the unrestricted area due to noble gases shallf calculated as follows: {,
= .
Dt the total body dose rate at time of release (aren/yr). ' I '(U)6 IKi0,
=
1 + IVi0,
~
v i i 1 (t) 0, = . the skin dose rate at time of release (ares /yr).
=
I ( M )6 Ii (li + l l M )i Oiv v
+
Ii (l i(N)E + l l 8 ) Ois 1 (10)
}
Tories wert defined previously in sections 2.1.1 and 2.1.2. 5 The dose rate limits are site limits at any point in time; therefore, dose rates are summed over all releases occurring simultaneously. For Plant Hatch the vent releases are . e ,, Unit 1 reactor building vent stack. Unit 2 rooster building vent stack.
- Un
.- } receabiner building vent.
+ .
exhaust augmented ventilation. - The only'et ( : ted release is the main stack which serves both units. Simultaneous releases may include any combination of these four release points. ! J DOCR No.- BR J ? _ ATTACHMENT No._ 2 shift _ /O or_ 28
.gy- i. I'* TW rmer ptV .* a/M ,
- 2. 2-1 l
l 2.2.1.h Dese Rates Due to Radiciodines, Tritium, and Particulates G 5.ss t.lb. fL sad Ib-For the purpose of implementing RET 5".15. .1.5-(Unit . ...
- 1) andD 1i (Unit 2), organ dose rates due to radiciodines, tritium, and all ra materials in particulate form with half-lives greater than 8 days are required to be calculated for the inhalation pathway for the child group.
The enild age group would experience the highest potential d via the inhalation pathway. noble gases are excluded from these calculations.In acco [ calculated as follows: These dose rates are De = the organ dose rate p t time of release (aren/yr). : ) = , yI ( _X/0)s I1 P io Qiv
+
(X/0)E I Pio0Is (11) i 5 where: , (T/5)g = defined in Section 2.1.1. *
=
L (X/0)E defined in Section 2.1.2. 0]v = the release rate (wC1/sec) of radioiodines, tritium, and particulates (required by RETS 3.15.2.1 (Unit 1) and i 3 31.2.1 (Unit 2) from the Unit 1 reactor building vent stack, the Unit 2 reactor building vent stack, the Unit 1 j recombiner building vent, and building exhaust augmented ventilation. , L ' GIs
- - = the release rate (wci/sec) of radiciodines, tritium, and particulates (required by RETS 3.15.2.1 (Unit 1) and j
t 3.11.2.1 (Unit 2) from the main stack. ' Pio = the organ dose parameter for organ o and radionuclide 1 (arem/yr per vC1/m') for inhalation determined as follows: DOCR No. 89 '7 ATTACHMENT No. ?
,.. r. en m,, SHEET // 38 '
e,, - p.p., OF
4- { l s f i Pe = K (BR) 0Fjo i (12) {' and w,e - K = the constant of unit conversion. l 10' pC1/wci. BR = the breathing rate for child age group l (3700 m*/ year). Table 2.2-10, from i Reference 3. ' i i 4 DFjo e
=
the inhalation pathway dose factor for child age group for organ e and -
, j radionuclide 1. Table 2.2-2, from Reference 3.
i NOTE: In order to assure that potential dose rates (prerelease) to an organ due to radiciodine, tritium, and particulates in simitan.ous gueon rei.neg ,fg ty site do n. nren/yr as specified in RET 45 -S.i!.? !C) (Unit 1) and 0.11.0 3) acygy,g, . 3 I j (Unit 2), the potential organ dose rate Do must be limited as follows: q 0, t (At x SF) 1 1500 mren/yr .
\
(13) : where: At and SF are assigned the same values as were used in Section 2.1 for the release source pathway under consideration. To Serther ensure that dose rate limits were not exceeded. (post-release) dose rates from simultaneous releases shall be sumed, as shown above. 3 NATen o0cm, nEv 1 s/11/s4 DOCR No. 6'9 - / 7 i 2.2-3 ATTACHMENT No. 2 _ _ _ 44 SHEET . /2 OF- 80
61,' = the cumulative release (yC1), free plant vent releases, of radionuclide i as required by RETS 3.18.2.3 (Unit 1) and 3.11.2.3 (Unit 2) over the period of in Dese
- deteminations required by RETS 3.15.2.gergs,t.
, y g 34and 3.11.2.3,are on a per reactor basis; therefore, cumulative release quantities must aise be reactor-specific.
(For dose contributions due to tritium from the ingestion pathways, the Qg tem is limited to tritium.) his' = the cumulative release (yC1), from the mein stack releases of radionuclide i as required by RETS 3.15.2.3 (Unit 1) and 3.11.2.3 (Unit 2) over the period of igg'. Dos deteminations required by RETS 3.15.2.3 4 and 3,11.2.3 4 a per reactor basis; therefore, cumulative release quantities must also be reactor-specific. Since the main stack serves both reactors, release quantities must be apportioned betwe the two units. In absence of evidence that one reactor , contributes a greater quantity of radioactivity than the other over the period of interest, release quantities may be apportioned equally between the two units. (For dose contributions due to tritium free ingestion pathways, the 61Itoreislimitedtotritium.) Raipj = the pathway-specific, individual age-specific organ dose f4ctor for radionuclide 1, pathway p, organ j, and. individual age group a. Routine individual dose calculations address the inhalation, ground-plane, grass-cow (or goat)-eilk, grass-cowwneat, and garden vegetation pathways. However, the dose pathways actually present at the' controlling location, as.well as the controlling individual age group, are detemined through the Land Use Census for the site. Pathway factors R aipj are detemined as shown in the following subsections. DOCR No.- N ATTACHMENT No.
'[ ,
n ,- HATCH 00CM. REY 3 . "P ' $HEET OF b
;: . 2.?-q
~
As stated earlier, the controlling recepter for plant Hatch ! 1s presented in Table 2.2-12. l Plant Hatch site-specific values, or appropriate defau'It i values, required in the pathway factor determinations are presented in Table 2.2-13. Inhalation pathumv Factor i Raipj
- K'(BR)a (DFA13)a (arem/yr per yC1/m*)
I where: h K' = the constant of unit conversion.10* PCi/yC1. t (tt)a
=
the breathing rate for a particular age group, in m*/yr, from Table 2.2-10. ' DFAi ja = the inhalation dose factor for receptor age group 4, organ j, and for radionuclide 1, in aren/pci, from Tables ' 2.2-1 through 2.2-4. Ground-plane pathway Facter R aipj = K'K' (SF')(DFli j) kt ((1-i i )/kg) (mauren/yr per yC1/sec) k6) i-
.e,.:
E' = the constant of unit conversion,10* pC1/uC1. P K' = the constant of unit conversion, 8760 hr/yr. P i DOCR No.- B9- 17 ATTACHMENT No. 2 SHEET /Y OF 20 Mr.TcH oncN. REV 3 8/07 S.? f '
- . ~ . _ _ _ _ . _ _ _ . _ _ . _ . _ . . _ . . _ _ .
I i SF' = the shielding factor. 0.7 (dimensionless). DFli j = the ground-plane dose conversion factor for radionuclide i (same for all age groups and specific organs are assumed to i receive the same dose as the total body), in aren/hr per j PC1/me, f rom Table 2.2-g. kg = the decay constant for radionuclide 1. I
=t =
the exposure tine, 4.73 x 108 sec (15 yr). Grass-Cow 4H1k Pathwaw Factor , . Raipj = K' OEIU88}Fgr)(DFW)a + (1 f,f,}e-k tth l Ki + hw Yp Ys Wtf (m*aren/yr per yC1/sec) - where: K' = ; a constant of unit conversion, 10' pC1/yC1. Op = the cow's consumption rate, in kg/ day (wet weight). ! Vap = the receptor's milk consumption rate for age group a, in Titers /yr, from Table 2.2-10. Yp = the agricultural productivity by unit area of pasture - grass, in kg/m*. Ys
=
the agricultural productivity by unit area of stored feed, in kg/as. Fa = the stable element transfer coefficients, in days / liter. (See Table 2.2-11.) i DOCR No. 89 /7 ' HATCH 00CM, REY 1 5/11/84 2.2-10 AUANN No. 2 > SHEET /8 OF 8b
y. l r = fraction of deposited activity retained on feed grass (1.0 for radiciodines; 0.2 for particulates). (DFlij)4 = the organ ingestion dose factor for the ith radionuclide for the receptor in age group a, in aren/pci, from Tables 2.2-5 through 2.2-8. At = the decay constant for the ith redlonuclide, in sec-1 i
% =
the decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10-' sec-1 (corresponding to a 14-day half-life). tt = the transport time from pasture to cow, to milk, to receptor, in sec, (1.73 x 10s). th = the transport time from pasture, to harvest, to cow, to milk, to receptor, in sec. (7.78 x 10*). fp = fraction of the year that the cow is on pasture (dimensionless). fs = fraction of the cow feed that is pasture grass while the cow is on pasture (dimensionless). For tritium in milk, the grass-cow-milk pathway factor is a special case due to the, fact that the concentration of tritium in milk is based on airtlerne concentration rather than deposition: Ratk =
- E'K"Fm0r u ap(DFLjj)a (0.75(0.5/H)) (mrom/yr per (w) pC1/m8 JW where:
K" = a constant of unit conversion,10s gn/kg.
}
DOCR No.. 89 '7 - 1 HATCH 00CM, REV 1 5/11/84 2.2-11 A'TTACHMENT No. 2 ._ SHEET /4 OF gg -
f M = the absolute humidity of the atmosphere, in gn/es. 0.75- = the fraction of total feed that is wter. s 0.5 = k the ratio of the specific activity of the feed grass water to the atmospheric wter. l' Other parameters and values as previously defined. trans-C::.: .'_2t Pathwaw Factor i Raipj = K' I **I F(r)(DFLjj)a f 88*
+ e'ki ty ki + nw Yp * ,
Ys (eherea/yr per wC1/sec) - where: E' = 4 a constant of unit conversion,10' pC1/yC1. . Op = the cow's consumption rate, in kg/ day (wt weight). ! Uap = the receptor's meat consumption rate for age group 4, in ' kg/yr, from Table 2.2-10. ' Yp = the agricultural productivity by unit area of pasture feed i grass, in kg/m*. i 4 Ys = the agricultural productivity by unit area of stored feed, in kgAes .
)
Ff = the stable element transfer coefficie' nts, in days /kg. (See Table 2.2-11.) r = ) the fraction of deposited activity retained on feed grass (1.0 for radiciodines; 0.2 for particulates). DOCR No. 89 /7 ATTACHMENT No. 2 SHM I7 OF 8b -
..aveu nner erv i Afg7 ;
_ _ _ 2.2
. ._ -1 2 _ _ . . _ _ . . _ _ , . . _ . _ _ _ _ . . - . _ . . _ .
. _ _ .- _ --... __ _ _._ -.- _ . _ m _ . _ ___._ _ . . _ . _ _ _ ._ __ _ -
4' 0
)
(DFLgj)e = the ergen ingestion dose factor for the ith radionuclide for the receptor in age group a, in area /pci, from Tables i
, 2.2-5 through 2.2-0.
kj = ! the decay constant for the ith radionuclide, in sec-1 ! N = the decay constant for removal of activity on leaf and ! plant surfaces by weathering, 5.73 x 10-' sec-1 1 (corresponding to a 14-day half-life)'. tg = ! ' the transport time from pasture to cow, to meat, to receptor, in sec, (1.73 x 10*). . i th = the transport time from pasture to harvest, to cow, to I meat, to receptor, in sec (7.78 x 108).
- L f, =
!~ fraction of the year that the cow is on pasture (dimensionless). 1 = Ys :
~
fraction of the cow feed-that is pasture grass while'the j i cow is on pasture (dimensionless). For tritium in meat, the grass-cowweest pathway factor is a special cas) j due to the fact that the concentration of tritium in meet is ba airborne concentration rather than deposition: Raipj = K'K"F f0F Uap(0FLi j)a (0.75(0.5/H)] (erse/yr per pC1/m8) (/z) where: 4Mr K" = a constant of unit conversion,108 ge/kg. H =
- l. absolute humidity of the atmosphere, in gn/ms, 0.75 =
J the fraction of total feed that is water. 0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water. DOCR No. 89 /? , Other parameters and values are given above. ATTACHMENT No. 2 - 1 . .. .. tlATCE OnCN.- REV 3 8/87 '
- s. 2.2-13 SHEET / 8 OF 2 b -
1 Vaantattaa pa+' Facter
\
Raipj = K' P -k t (Z5 (DFLjj)a Usti n' t g + Uasfge-kjth l Yv(ht.+ hw) J44 3 _,, W Where: K' = a constant of unit conversion,10* PC1/yC1. Uag = the consumption rate of fresh leafy vegetation by the 4 4 receptor in age group 4, in kg/yr. (See Table 2.2-10.) Ues = the consumption rate of stored vegetation by the receptor in age group a, in kg/yr. i (See Table 2.2-10.)
\
ft = the fractier, of the annual intake of fresh leafy vegetation grown locally. i f, = I the fraction of the annual intake of stored vegetation grown locally, ; i tg = the average time between harvest of leafy vegetation 'and i consumption, in sec, (8.6 x 108).
'ts I
g th a the average time between harvest of stored vegetation and
.its consumption, in sec, (5.18 x 10*).
Yy- = . the vegetation areal density, in kg/es, (DFli j)a = the organ ingestion dose factor for the ith radionuclide for the receptoe in age group a, in aren/pci, from Tables 2.2-5 through 2.2-g. ki = the decay constant for the ith radionuclide, in sec-1 [ DOCR Ho. 89 /7 f t' ATTACHMENT No.
; 33_ __. _
_ - _ 2 m e 3 g ,,7 - 6 or ---- 68
~~
1
?
hw -- the decay constant for removal of activity on leaf and plant [ surfaces. by weathering. 5.73 x 10-', in sec 1 . (corresponding to a 14-day half-life).. For tritium in vegetation,.the vegetation pathway factor is a special case J due'to the fact.that the concentration of tritium in vegetation is based on-airborne concentration rather than deposition: Raipj
- K'K(Ust it + Uasfg) (DFLjj)a (0.75(0.5/H)] (aren/yr per wC1/m') (Mt (z4) where: ,
=
K a constant ~of unit conversion, los ga/kg. *
=
H absolute humidity of the atmosphere, in gn/ma , 0.75 = the fraction of total vegetation that is water.
~
0.5- -- the ratio of the specific activity of the vegetation water to the atmospheric water. Other parameters and values are given above.
' Grass-Goat-Wilk pathw Facter Raipj " K' F( ""} t
+.(1-fofs)e ih-M + hw Fe(r)(DFLjj)a Yp Ys
,-ki ty )
(maurea/yr per wC1/sec) DOCR No.- 89 ./7
% ,7,, ATTACHMENT No. 2 SHEET _ 20 op 28 K' =
a constant of unit conversion,10* pC1/wC1. ,
=
QF the goat's consumption rate, in kg/ day (wet weight). Uap = the receptor's milk consumption rate for age group a, in liters /yr, f es Table 2.2-10.
- HATCH 00CM, REV 3 i 8/87 2.2-15
\
e taipj (Z(ch E'K"Fe0F ap(DFli j)a;[0.75(0.5/N)] (aren/yr per pC1/me) U o 424 7 ; F where . > t K" ~= a constant of unit conversion, los gaikg. . H = :
' absolute humidity of the atmosphere, in ge/m*. _
0.75
= the fraction of total feed that is water.
l > 0.5 = the ratio of the specific activity of the feed grass water to the atr. aspheric water. Other parameters and values are_ given above. 2.2.2.c o Dose Calculations To Support Other Specific Technical Specifications b
's * *). ** supb 'po r $*
rl". . . . . 1 c g;;;dh;gI".LTAdl'.'@.1.i3.4"f*f.*i'Al'fF* dose. calculations h be perform equations in Section 2.2.2.b, with the substitution of average meteorological l a parameters for the period of the report and the appropriate pathway receptor dose factors (Raipj)*
.(dne f I)
For the purpose of implementing RETS 3.16.y dose calculations may be l performed.using the equations in Section 2.2.2.b, substituting the appropriate pathway receptor dose factor (Raipj) and the appropriate dispersion parameters for the location (s) of interest. Annual average
' dispersion parameters may be used for these calculations.
g-h4,7')[.Y,
---- =_
h h.*e,go,ggajcgggj,y,bg
- s. . . ' '
- or 3.16.2 required in order to not- the previously hid' entified critical receptor. n o t~l The receptor ag group and exposure pathways
'present (and' applicable) at-the location of interest must be determined.
The equations for calculating the pathway factors a R jpj were presented-in'Section 2.2.2.b. Plant Hatch site-specific values, or appropriate default values, required in the pathway factor determinations are presented in Table 2.2-13. - NATC$00CM,REV3 DOCR No. 89 !7 8/87 2.2-17 ATTACHMENT No. 3 L. SHEET N OF _ M '
)
F '
.f ,
i
^
-TABLE 2.2-12 CONTROLLING RECEPT 0R i-
~(To support subsection 2.2.2.b) ,
L are determined based on information obtained d Survey.* of the controlling receptor based on the NNP site
- j. -!
collect iod 1984-1986.** _!
- 1. 2 "
Location. -8W-at vAsV .4d mi.19s Age Group. -ft 10 4 hem 1 Exposure P y'~4 . Dispersion and ;4tof$?Aon Yalues for this location:etton, ground-plan Ground-levei 3.16 . (X/Q')vp = . -6 m ,
- 9. 90 E - 9 (0/Q'),, = 1.-^ a Elevated -
i { 1 (X/Q'),,i.W =ff.63 e E -3 W . l.37 (M')3,= . -9 4' m
- Reference F. 2 2. *
** Reference .
DOCR No. 6'9 /7 HATCH 00CM, REY 4 ATTACHMENT No. 2 2/88 2.2-47 SHEET ZL OF 2O 1-
q;; . . j q i TA8LE 2.2-13 (SNEET 2 0F 3) L SITE-SPECIFIC (0R' DEFAULT) VALUES TO SE USED IN PATHWAY FACTOR CALCULATIONS
- r
-Meat (continued)
(DFL)1ja Ingestion dose factor for age group Tables 2.2-6' Yp thru 2.2-8 Pasture grass areal' density 0.7 kg/m* Y s Stored feed areal density 2.0 kg/me fp Fraction of year that cow grates on pasture 1.0 [ f Fraction of total feed that is pasture grass while cow is on pasture 1.0 H Absolute humidity of the atmosphere 8.0 gn/m* Garden Vegetation Yy Garden vegetation areal density 2.0 kg/m a 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 groups Tables 2.2-6 fg thru 2.2-8 Fraction e of annual intake of
'Mir tt; :7h*% ;.07%il grown locally l. O f g__
% - - ;- -A tt-Fractiona of annual intake of s....
_ gon grown locally o. 7 ' H W
~
. . . .f-Absolute humidity of the atmosphere 8.0 gn/m*
Grass-Goat-Milk QF Feed consumption rate for goat 6.0 kg/ day Uap Milk consumption rate for age group Table 2.2-10
- Supports Section 2.2.2.b. O. N
- HATCH 00CM, REV 4 2/88 ATTACHMENT No. 4, 2.2-49 23 OF 20
-_- .. - - _ . - - - . . - . _ - - ~ . - . - - - . . . . - - - . - - .
4 3.0 RADlotosICAL ENVIRONMENTAL WWITORIns penagm j Urs/? Sampling locations as required by RETS 4.16.1 are described in Table 3.0-1 and shown on maps in Figures 3.0-1 throug 3.0-g, There are no known drinking water users downstream of Plant Hatch. Therefore, the LLO for I-131 in water need not be as stringent as that for
- milk.. ,.
The survey ~of milk animals is based on the requirement in Appendix ! to ' 10 CFR Part 50 that the licensee "!dentify changes in the use of unrestric areas (e.g.. for agricultural purposes) to pensit modifications in monitor programs for evaluating doses to individuals from principal pathways of exposure.' The consumption of milk from animals grazing on contaminated pasture and the consumption of vegetation contaminated by airborne radiciodine are major potential sources of exposure. Samples from milk g animals than vegetation. are considered a better indicator of radiciodine in th 5 Because sufficient milk samples frequently are not available within 5 miles, vegetation samples will be collected also. Grass is available almost year-round, whereas leafy vegetation is available only for a months of the year at best. The sampling stations for grass are l located near the site boundary in two sectors with high offsite 0/0 values where it might be' practical to establish a vegetation plot. The highest offsite 0/0 for each individual sector occurs approximately at the site boundary.
- Althoug'hl e{ter fish or clan samples may be collected from the river, samples art') referred, because the maximum dose commitment to a me public as a result of liquid offluents is through the fish consumption pathway.
1 l l DOCR No. 89 /7 tlATCH 00CM, REV 3 8/87 3. 0-1 ATTACHMENT No. 2 l SHEET - N OF 2d E . . . _. _ . - . . _ . _ - . _ . __ ._ __ _ _ - _ _ _ _ _ _ _ _ _
- --- . - - _ - . .~ -- .
)
TABLE 3.0-1:(SHEET 2 0F 2) - RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONi Location- . h Generintive Location Direction-Distance failes) Sample Tyne
- 301 304 Toombs Central School- N 8.0 State prison ENE 0
304 State prison 11.2 AO-309 ENE 10.8 Baxley substation 3 M i 316 Thompson's Dairy 10.0 AD F 1 Nati 13.2 title M-Em erg en cM Ale ^ M4 Cente t^ 21. 0 DJ
+
t
- Sample Types: .
!~ A - Airborne radioactivity D - Direct radiation M - Milk R --Vegetation V River (fish or class, shoreline sediment, and surface water)- - L l intake-structure for riverwater,1.1 river miles for se and 1.5 river miles for fish. , Station 172 is . located at approximately 3.0 river miles downstream o discharge for fish. structure for riverwater, sediment and class, and 1.7 river +1 I(
~
.( ;
The locat$en precise) fined.from which Often riverwater and sediment may be taken can extend r a wide area,to obtain'a sufficient quantity.the High water adds ' sam < otherwise suitable location for sedimentAsampling stretch
.( u! '
l obtain adequate fish samples.of the river on the order of a few (mil( y approximations of the locations about which the catches are tak , osa7a DOCR No. W*A 1-ATTACHMENT No. 2 l HATCH 00CM, REV 3 8/87 3.0-4 SE 2 5 or 36 : '
-, . I
~ , , - . . . _ - - . . - - - . - - . ____.________ _ _ _ __ _ _ _ ___ _
n 4 l 9.. . \
. \
M, _ _ . p . y B t, j D i - s
- Q- .
.j
** *'"P.
j
*her ]
a i l - t 5 -
>l DOCR No. 89 ./7 -
ATTACHMENT No. Z L SHEET - 2 4, or 26 m
~'-
,. , Geot '*glaPower A J" O-u.av, LOCATION OF ADDITIONAL CONTROL STATION FOR TLDs AND VEGETATION p '
m
\
5.0 P0TENTIAL 00SES TO MEMBERS OF THE PUBLIC DUE TO THEIR ACTIVITIES INSIDE THE SITE a09NOARY ' For the purpose of implementing RETS 6.g.1.g an assessment of potential doses to members of the public due to their activities within the site boundary will be performed if circumstances have changed- such that any of the , limits of RETS 3.11.2.2 (Unit 2), 3.11.2.3 (Unit 2), 3.15.2.2 (Unit 1) or 3.15.2.3 (Unit 1) are exceeded. The locations of concern within the site - boundary are the roadside park, the camping area, the recreation area, and-the Visitors Center. Historical annual average dispersion and deposition values, and elevated plume dose factors' for these. locations are presented in Tables 5.0-1 through 5.0-4, along with the estimated occupancy factors. (Estimated occupancy factors are for an individual during a year.) (wn z)7 fa . el) In the event that any limit of RETS 3.11.2.2 or 3.15.2.2 is exceeded, an assessment will'be performed considering direct radiation dose to an individual resulting from noble gases in the plume. This assessment will take into consideration the annual average dispersion and deposition
. parameters and the estimated occupancy factor stated.in Tables 5.0-1 through 5.0-4, or a more precise value if available, for the locations of interest.
(hn 2) O(nci Z) In the event that any limit of RETS 3.11.2.3 }or 3.15.2.3 is ex assessment will be performed considering the dose to an individual due to inhalation of airborne radioactive materials suspended in the plume and due I 1 to radioactive material deposited on the ground. This assessment will.take ( into consideration the annual average dispersion and deposition parameters and the estimated occupancy factor stated above, or a more precise value if available, for the locations of interest. L If.'none of the limits discussed above is exceeded, potential annual doses to
' a member of the public at a location of concern within the site boundary are as follows:
Potential doses to an individual at the Visitors Center are not , expected to exceed 0.03 mrom due to inhalation and ground-plane exposure, and 0.02 mrem due to direct radiation from the plume. DOCR No.- N '7 ATTACHMENT No. 8
-HATCH ODCC, REV 3 8/87 S.0-1 SHEET 27 op-28 o www'T
c
.. E RE18EEEE(continued)-
f 14.
^ j^ Maar Plant' lam Use survev - 1987, Ge
'eDruary 1987. - _
- 15. Washington, Letter toD.C. Georeia
, May 11, 'Par 987. C==env from Pickard. Lowe. an _.,
I 14. ngton, D.C. , - June 3. ' 987.Lottar to Georeia Power ca=any fro Wash' I ' 17. ngton, D.C. , June 11, ' 987.Lettar to Geornia par connanv fro Wash' s
- 18. Internal'" 1 Company, June 9, 1987.randum. W.H. 0111ncer to 0.N. Georgia MGLE P, Power
- 19. '
etter to Georw i b rgia, June i,a 1987. Par c=env from Guantum Technoloov, Inc., Marietta' \- - 20. Hatch Nuclear November 1987. Plant Land Use Survey, Georgia- Power Company, 21. Washington, D.C., NovemberLetter 30, 1987. to Geornia Pmr c=eny . Inc.'from Pic gz, L}e h daeleal' Plan b l And Use SurVef , fee >rp pm-
. % pany , dwem ber IG, t 98 8 and Decern bee 26,1988 1
,1 1
. 1 l
.+.
.t i
89-17 DoCR No -- 2 -- - HATCH ODCM, REV 4
.i 2/88 AUACHMENT No.
SHEET 2 A :of 3 - ' L
.* @ e 9 9l>er e A
_ g ,y --. -- -
. _ _ _ _ __- _ _ _ ~. . - _ . _ _ _ . _ _.. . __. __-- . __ __
DOCR No.- 6 /7 ATTACHMENT 3 ATTACHMENT No. 3 FURTHER EXPLANATIONS N " Determination of Proposed New Controlling Receptor The controlling receptor is the real individual at or beyond the site boundary expected of to receive the greatest calculated dose due to the gaseous releases I-131, 1-133, greater than eighttritium days. and radionuclides in particulate form with half lives l
~
This'is calculated in accordance with Section 2.2.2.b of the ODCM to fulfill the requirements of Technical Specification 4.15.2.3. i An examination of the results of the land use survey conducted on October 25,. 1988, in accordance with Technical Specification 3 1 controlling dose receptor would be an individual w/4.16.2, indicated that the ho receives dose mainly through the vegetation pathway. At all locations dose is also received through the breathing and ground plane pathways. leafy vegetables were found within 1.5 miles of the plantFour gardens' growing gre garden was more than 2 miles from the plant); each of these(the next closest gardens were in a different sector. No milk animals were found. The meat animals found close to the plant were not associated with households with gardens. Meat animals-at 1.7 miles were found in one}}