Text

Plant Ei Hatch,Units 1 & 2 Semiannual Radioactive Effluent Release Rept,Jan-June 1993
	ML20056F685
Person / Time
Site:	Hatch
Issue date:	06/30/1993
From:	Beckham J; GEORGIA POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	HL-3428, NUDOCS 9308300261
	Download: ML20056F685 (61)
	v • d • e

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Georgia Powar Cornpany 40 inverness Center Partway Post Off.ce Box 1295 Bemingham, A;abama 35201 TWophone 205 877-7279 n

J. T. Beckham, Jr. Georgia Power Mt.e Preudent - foclear

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I O d 'N August 24, 1993 Docket Nos 50-321 HL-3428 50-366 006011 U.S. Nuclear Regulatory Conunission ATTN: Document Control Desk Washington, D.C. 20555 Edwin I. Hatch Nuclear Plant Semiannual Radioactive Efiluent Release Reprt Gentlemen In accordance with the provisions of Plant Hatch Technical Specifications sections 6.9.1.8 and 6 9.1.9, Georgia Power Company is providing six copies of the Plant Hatch Units 1 and 2 Semiannual Radioactive Efiluent Release Report. This report covers the period January 1,1993 through June 30,1993.

Should you have any questions, please advise Sincerely,

<.h l J. T Beckham, Jr. l l

SRM/cr l Enclosure. Plant E 1. IIatch Units 1 & 2 Semiannual Radioactive Efiluent Release Report cc. (See next page )

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Georgia Powerku U.S. Nuclear Regulatory Commission Page Two August 24, 1993 l

cc: Georgia Power Company Mr. H. L. Sumner, Jr., General Manager - Nuclear Plant Mr. W. R. Woodall, Vice President Environmental Affairs ,

NORMS ;

i U.S Nuclear Regulatory Commission. Washington. D C.

Mr. K. Jabbour, Licensing Project Manager - Hatch ,

U.S Nuclear Regulatory Commission. Region 11 !

Mr. S. D. Ebneter, Regional Administrator '

Mr. L. D. Wert, Senior Resident Inspector American Nuclear Insurers i Mr. M. Marugg State of Georgia Mr. J. L. Setser, Department ofNatural Resources 5

i Mahler (kSOli i-P

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1 GEORGIA POWER COMPANY PLANT E. I. HATCH - !

l UNITS NO.1 & 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT January 1,1993 - June 30,1993 T

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PLANT E. I. HATCH SEMIANNUAL RADI0 ACTIVE i EFFLUENT RELEASE REPORT l l

Section Title Pace 1 Liouid Effluents 1 1.1 Regulatory Limits 1 1.2 Maximum Permissible Concentrations 5 1.3 Measurements & Approximations of Total Radioactivity 6 1.4 Liquid Effluent Release Data 8 1.5 Radiological Impact on Man Due to Liquid Releases 10 2 Gaseous Effluents 21 2.1 Regulatory Limits 21 2.2 Measurements & Approximations of Total Radioactivity 28 2.3 Gaseous Effluent Release Data 33 2.4 Radiological Impact Due to Gaseous Releases 34 3 Solid Waste 50 3.1 Regulatory Requirements 50 3.2 Solid Waste Data 50 4 Chanaes to the Plant Hatch ODCM AND PCP 53 !

5 Monitor Out of Service Greater Than 30 Days 54 i

O PLANT E. I. HATCH SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT TABLE LIST OF TABLE _S PAGE l-1 TECHNICAL SPECIFICATION 'l AllLE 3.14.1-1 3 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 1-2a LIQUID EFFLUENTS - SUMMATION OF 11 ALL RELEASES - UNIT 1 1-2b LIQUID EFFLUENTS - SUMMATION OF 12 ALL RELEASES - UNIT 2 1-2c LIQUID EFFLUENTS - SUMMATIONS OF 13 ALL RELEASES - SITE l-3a LIQUID EFFLUENTS - UNIT I 14 1-3b LIQUID EFFLUENTS - UNIT 2 15 1-3 c LIQUID EFFLUENTS - SITE 16 1-4a INDIVIDUAL DOSES DUE TO LIQUID 18 l RELEASES - UNIT 1 1-4b INDIVIDUAL DOSES DUE TO LIQUID 19 RELEASES - UNIT 2 3 1-5 LOWER LIMITS OF DETECTION- LIQUID 20 SAMPLE ANALYSES 2-1 TECHNICAL SPECIFICATION TABLE 24 3.14.2-1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

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EFFLUENT RELEASE REPORT l TABLE LIST OF TABLE _S PAGE ,

2-2a GASEOUS EFFLUENTS - SUMMATION OF 35 ALL RELEASES - UNIT I 2-2b GASEOUS EFFLUENTS - SUMMATION OF 36 ALL RELEASES - UNIT 2

2-2c GASEOUS EFFLUENTS - SUMMATION OF 37 ALL RELEASES - SITE 2-3 a GASEOUS EFFLUENTS - ELEVATED 38 RELEASES - UNIT 1 2-3b GASEOUS EFFLUENTS - ELEVATED 39 .

RELEASES - UNIT 2 2-3c GASEOUS EFFLUENTS - ELEVATED 40 ;

RELEASES - SITE ;

2-4a GASEOUS EFFLUENTS - GR.OUND- 41 LEVEL RELEASES - UNIT I 2-4b GASEOUS EFFLUENTS - GROUND -

LEVEL RELEASES - UNIT 2 42 2-4c GASEOUS EFFLUENTS - GROUND -

LEVEL RELEASES - SITE 43 2-5 GASEOUS EFFLUENTS - DOSE RATES - SITE 44 ;

2-6a AIR DOSES DUE TO NOBLE GASES - .

UNIT 1 45 2-6b AIR DOSES DUE TO NOBLE GASES -

UNIT 2 46 I O .

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PLANT E. I. HATCH SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT l t

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TABLE LIST OF TABLES P_A_GE j i

2-7a INDIVIDUAL DOSES DUE TO RADIOIODINE, ,

TRITIUM, AND PARTICULATES IN GASEOUS ;

RELEASES - UNIT 1 47 1 I

2-7b INDIVIDUAL DOSES DUE TO RADIOIODINE, I

TRITIUM, AND PARTICULATES IN GASEOUS RELEASES - UNIT 2 48 2-8 LOWER LIMITS OF DETECTION - GASEOUS SAMPLE ANALYSES 49 {

3-la,b SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 51,52 i O l:

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j O RADIOACTIVE EFFLUENT RELEASE REPORT i i

l 1 LIOUlD EFFLUENTS 1.1. REGULATORY LIMITS

1. The Technical Specifications pre,ented in this section are for Unit 1.

Requirements for Unit 2 are the same as Unit 1; however, the ,

Technical Specification numbers are not the same.- :

TECHNICAL SPECIFICATIONS 3.14.1 The radioactive liquid efIluent monitoring instrumentation channels shown ir, table 3.14.1-1 shall be OPERABLE with their alarm / trip setpoints set to ensure .I that the limits of Specification 3.15.1 are not exceeded. The alann/ 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 m 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 O

mecentrations speciried in 10 CrR Fa,t 20, Appendix B. Table li (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 FUBLIC from radioactive materials in liquid efIluents released, from each reactor unit, from the <

site (figure 3.15-1) shall be limited to: I

a. During any calendar quarter to less than or equal to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ.

. b. During any calendar year to less than or equal to 3 mrem to the total body 1 and to less than or equal to 10 mrem to any organ.

3.15.1.3 The liquid radwaste treatment system, as described in the ODCM, shall be used to reduce the radioactive materials in liquid wastes prior to their :

discharge when the projected doses due to the liquid effluent per Unit from the :

s 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.

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3.15.1.4(a) The contents within any outside temporary tank shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained ' noble i gases.

(a) An outside temporary tank is not surrounded by liners, dikes, or walls that ,

are capable of holding the tank contents and not having tank overflows and i drains connected to the liquid radwaste treatment system.

6.9.1.9 states in part: "The Radioactive Efiluent Release Report shall include (on ;

a quarterly basis) unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid efIluents that were in excess ofI Ci, excluding dissolved and entrained gases and tritium for liquid effluents, or those in excess of 150 Ci of noble gases or 0.02 Ci of radiciodines for gaseous releases."

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TABLE l-1 TECHNICAL SPECIFICATION TABLE 3.14.1-1 (SHEET 1 of 2 )

RADIOACTIVE LIOUID EFFLUEFE MONI'IORING INSTRUMEffrATION Minimum Channels Instrument OPERABLE Applicability ACTION

l. Gross Radioactivity Monitors Providing Automatic Termina-tion of Release '

Liquid Radwaste :

Effluent Line 1 (a) 100

2. Gross Radioactivity Monitors not Providing Automatic Termination of

, Release ;

Service Water '

System Effluent Line 1 (b) 101

3. Flowrate Measure-ment Devices **

Liquid Radwaste (a)

Effluent Line 1 102

Discharge Canal 1 (b) (a) 102

4. Service Water 1 At all times 103 System to Closed i Cooling Water !

System Differential

.! Pressure

- Pump curves may be utilized to estimate flow: In such cases, ,

ACTION statertent 102 is not required.

(a) Whenever the radwaste discharge valves are not locked closed. .

(b) Whenever the service water system pressure is below the closed cooling water system pressure or differential pressure indication is not available. ,

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TABLE 1-1 (CONTINUED)

TECHNICAL SPECIFICATION TABLE 3.14.1-1 (SHEET 2 of 2)

RADIOACTIVE LIOUID EFFLUEtTT MONITORING INSTRUMENTATION TABLE !UTATIONS 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 v2a this pathway may continue, provided that once per shift grab samples are collected and analyzed O for gross radioactivity (7 beta or gamma) at a Lower Limit of Detection of at least 10- uC1/ml. If the channel remains inoperable for over 30 days, an explanation of ti.e 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 centinue, provided

[ the flowrate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during

actual releases. If the channel remains inoperable for over 30 days, an explanation of the circumstances shall be 1

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.

i 1.2 MAXIMUM PERMISSIBLE CONCENTRATIONS O The MPC values used in determining allowable liquid radwaste release rates and )

concentrations for principal gamma emitters, I-131, tritium, Sr-89, Sr-90 and Fe- l 55 are taken from 10CFR Pan 20, Appendix B, Table II, Column 2. i 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 10 CFR Part 20, Appendix B, Note 2.b as 3.0E-08 uCi/ml.

Further, for all the above radionuclides or categories of radioactivity, the overall MPC fraction is determined in accordance with 10 CFR Pan 20, Appendix B, Note 1.

The method whereby the MPC fraction is used to detennine release rates and liquid radwaste effluent radiation monitor setpoints is described in Section 1.3 of this report.

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I 1.3 MEASUREMENTS AND APPROXIMATIONS OF TOTAL l 2

Q RADIOACTIVITY Prior to release of any tank containing liquid radwaste, and following the required recirculation, samples are collected and analyzed in accordance with Technical SpeciScation Tables 4.15.1-1 (Unit 1) and 4.11.1-1 (Unit 2). A sample from each tank planned for release is analyzed for principal gamma emitters,1-131, and dissolved and entrained noble gases by gamma spectrometry. Monthly and ,

quarterly composites are prepared for analysis by extracting aliquots from each sample taken from tanks which are released. Liquid radwaste sample analyses are performed as follows:

Measurement Frequency Method ,

1. Gamma Isotopic Each Batch Gamma spectroscopy with computerized ,

data reduction

2. Dissolved or Each Batch Gamma spectroscopy Entrained with computerized :

Noble Gases data reduction l

O 3. Tritiem meethiy oi,titietion and Composite liquid scintillation '

counting ;

4. Gross Alpha Monthly Gas flow proportional i Composite counting i

i 5. Sr-89 and Sr-90 Quarterly Chemical separation and Composite gas flow proportional counting

6. Fe-55 Quarterly Chemical separation and ,

Composite low energy photon detector. !

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Q Gamma 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 ganuna ,

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, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144. The quantitative calculations include corrections for -

counting time, decay time, sample volume, sample geometry, detector efliciency, baseline counts, and branching ratio. LLD calculations, including the above corrections, are made based on !

the counts in two standard deviations of the baseline count at the location on the spectrum where a peak for that radionuclide would be located if present.

The radionuclide concentrations determined by gamma O spectroscevic aneir is ora sampie taken from a tenk gianned for release and the most current sample analysis results available for '

tritium, gross alpha, Sr-89, Sr-90, and Fe-55 are used along with the corresponding MPC values to determine an MPC fraction for the tank planned for release. This MPC fraction is then used, with appropriate safety factors, along with the expected dilution stream flow to calculate a maximum permissible release rate and a liquid effluent monitor setpoint. The monitor setpoint is calculated to assure that the limits of Technical Specifications 3.15.1.1 (Unit 1) ,

or 3.11.1.1 (Unit 2) are not exceeded. ,

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i A monitor reading in exce s of the calculated setpoint therefore Q results in an automatic terminaden of fne 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 t 4

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 ;

n:cluded. These data are input to the computer and a post release prir.txt is generated. The post release printout contains actual ,

release rates, actual release concentrations and quantities, actual dilution flow, and calculated doses to an individual.

O i.4 tiouio errtUnxT Reterse orTA !

Regulatory Guide 1.21 Tables 2A and 2B are found in this report as Table 1-2a !

for Unit 1, Table 1-2b for Unit 2 and Table 1-2c for the site; and Table 1-3a for Unit 1,1-3b for Unit 2, and Table 1-3c for the site. :

, The values for the four categories of Tables 1-2a and 1-2b, and 1-2c are calculated and the Tables completed as follows:

1. Fission and activation products - The total release values (not including tritium, gases, and alpha) are comprised of the sum of the measured individual radionuclide activities. This sum is for each batch released to the river for the respective '

'There were no monitors out of service greater than 30 days and no unplanned releases.

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Q quarter. Percent of applicable limit is determined from a mixed nuclide MPC fraction calculation. The average concentration for each nuclide over all released batches is divided by the corresponding individual MPC value. The i sum over all nuclides of the C/MPC ratios times 100 is the percent of applicable limit for effluent releases during the quarter.

2. Tritium - The measured tritium concentrations in the monthly composite .

samples are ured to calculate the total release and average diluted concentration during each period. Average diluted concentration divided by the MPC limit,3.0E-03 uCi/ml, is converted to percent to give the percent ,

of applicable limit. l

3. Dissolved and entrained gases - Concentrations of dissolved and entrained gases in liquid eflluents 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

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applicable limit for noble gases in liquid effluent releases during the quarter. ;

Radioisotopes ofiodine in any form are also determined during the isotopic analysis for each batch; therefore, a separate analysis for possible gaseous forms is not performed because it would not provide additional information.

, O 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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Other data pertinent to batch releases of radioactive liquid effluent from both units are as follows: ;

Number ofbatch releases: 650 Total time period for batch ;

releases: 74,286 minutes l Maximum time period for a batch release: 221.0 minutes !

Average time period for batch !

releases: 114.3 minutes i Minimum time period for a batch ,

release: 72 minutes Average stream flow during periods ofrelease ofliquid effluent into a flowing stream: 23,120 CFS ,

1.5 RADIOLOGICAL IMPACT ON MAN DUE TO LIQUID RELEASES Doses to an individual, due to radioactivity in liquid effluent, were calculated l in accordance with Technical Specifications 3/4.15.1.2 (Unit 1) and i 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 i

O 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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l TABLE 1-2a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 i LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES j l

...._______........................._________.............._._ t Unit Quarter 1 Quarter 2 Est. Total !

Error (%) :

A. Fission and i activation products :

1. Total release Ci 1.72E-01 1.23E-01 4.70E+01 r

2. Average diluted ;

concentration !

during period uCi/nd 1.65E-07 1.22E-07 >

3. % of applicable limit t 4.91E-01 3.27E-01 :

i B. Tritium

1. Total relgase Ci 1.55E+01 4.89E+00 3.70E+01 l 2. Average diluted ,

concentration during period uCi/ml 1.49E-05 4.85E-06 l

3. % of applicable limit % 4.96E-01 1.62E-01 :

C. Dissolved and i entrained gases :

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1. Total release Ci 1.64E-03 1.05E-04 1.00E+02 !

2. Average diluted ;

congentration ;

during period uCi/ml 1.57E-09 1.04E-10 1

3. % of applicable ,

limit % 7.87E-04 5.19E-05 ,

I D. Grogs Alpha radioactiv:\ty

1. Total release Ci 0.00E+00 7.80E-06 1.20E+02 I l

E. Volume of waste i (prior to '

dilution) liters 5.18E+06 4.72E+06 1.00E+01 ,

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i F. Volume of I dilution i water used liters 1.04E+09 1.01E+09 1.60E+02 ;

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TABLE 1-2b i E. I. HATCH NUCLEAR PLANT - UNIT 2 i SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 .

O- LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES i

1 Error (%) !

i A. Fisgion,and i activation ;

products l

1. Total release Ci 9.77E-02 2.73E-02 4.70E+01 :

2. Average di:.uted concentrat:.on :

during period uCi/nd 1.42E-07 3.31E-08 !

3. % of applicable i limit % 3.17E+00 1.84E+00 -!

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B. Tritium l

1. Total release Ci 3.30E+00 3.90E+00 3.70E+01 l

2. Average diluted l concentration during period uCi/nd 4.78E-06 4.71E-06

3. % of applicable !

limit % 1.59E-01 1.57E-01 ;

I C. Dissolved and i entrained gases

1. Total relgase Ci 3.43E-02 4.71E-02 1.00E+02

2. Average diluted concentration O

i during period uCi/ml 4.97E-08 5.70E-08 i

3. % of applicable !

limit % 2.49E-02 2.85E-02 ;

D. Gross Alpha radioactivity

1. Total release Ci 0.00E+00 0.00E+00 1.20E+02 ,

i E. Volume of waste !

(prior to !

dilution) liters 3.26E+06 4.07E+06 1.00E+01 i F. Vglume of -l dilution a water used liters 6.90E+0B 8.27E+08 1.60E+02 i i

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TABLE 1-2c '

E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Unit Quarter 1 Quarter 2 Est. Total ,

Error (%)

A. Fission and activation products >

1. Total release Ci 2.70E-01 1.51E-01 4.70E+01 -F

2. Average diluted congentration t during period uCi/nd 1.56E-07 8.20E-08 :

3. % of applicable limit % 1.56E+00 1.01E+00 !

B. Tritium ,

1. Total relgase Ci 1.88E+01 8.79E+00 3.70E+01 ,

2. Average diluted concentration t during period uCi/ml 1.09E-05 4.79E-06 c

3. % of applicable

limit % 3.62E-01 1.60E-01 l ;

C. Dissolved and i entrained gases

1. Total release Ci 3.59E-02 4.72E-02 1.00E+02 -i

2. Average diluted i concentration i

during period uCi/ml 2.08E-08 2.57E-08 i

3. % of applicable l limit % 1.04E-02 1.29E-02 ;

I l D. Gross Alpha radioactivity .

1. Total release Ci 0.00E+00 7.80E-06 1.20E+02 ;

l E. Volume of waste (prior to

dilution) liters 8.43E+06 8.79E+06 1.00E+01

F. Volume of dilution

, water used liters 1.73E+09 1.84E+09 1.60E+02 i

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TABLE 1-3a*

E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 LIQUID EFFLUENTS j i

l Continuous Mode **

Batch Mode 2 I

Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 H-3 Ci 1.55E+01 4.89E+00 i

Fission and acQivation products: !

Na-24 C1 1.22E-04 0.00E+00 :

Cr-51 Ci 1.97E-03 4.71E-03 ;

Mn-54 Ci 2.19E-03 4.16E-03 '

Fe-55 Ci 9.63E-02 1.09E i Fe-59 Ci 4.89E-05 4.36E-04 t Co-58 Ci 1.48E-03 1.91E-03 Co-60 C 1.20E-02 2.97E-02 i Zn-65 C. 4.32E-02 7.04E-02 As-76 C1 2.57E-03 0.00E+00 i Rb-89 Ci 2.90E-04 0.00E+00 .

Sr-89 Ci 1.96E-03 1.25E-03 ;

Sr-90 Ci 2.14E-04 1.66E-05 Sr-91 Ci 3.76E-05 0.00E+00 Sr-92 Ci 4.73E-06 0.00E+00 ,

Y-91m Ci 9.61E-04 0.00E+00 >

Nb-95 Ci 0.00E+00 2.35E-05 ,

Nb-97 Ci 3.84E-04 0.00E+00 '

Tc-99m C4 2.24E-04 1.38E-05 Ru-103 C1 0.00E+00 1.55E-06 Sb-125 Ci 2.59E-05 3.00E-05 -

I-131 Ci 5.74E-04 1.60E-04 ;

I-133 Ci 3.35E-04 5.13E-06 !

Cs-134 Ci 6.07E-04 9.77E-04

Cs-136 Ci 2.70E-05 0.00E+00 Cs-137 Ci 5.64E-03 8.19E-03 Cs-138 Ci 3.09E 0.00E+00 ;

Ba-139 Ci 1.28E-04 0.00E+00 '

Ba-140 Ci 2.64E-04 0.00E+00 La-140 Ci 1.30E-04 1.74E-05 Ce-141 Ci 3.73E-06 0.00E+00 Ce-144 Ci 0.00E+00 6.97E-05 Zn-69m Ci 1.57E-05 0.00E+00 i Total Ci 1.72E-01 1.23E-01 ;

I Dissolved and entrained gases:

Kr-85m Ci 5.57E-07 0.00E+00 ?

Xe-131m C4 5.77E-05 0.00E+00 l Xe-133 C1 2.41E-04 6.37E-06 !

Xe-135m Ci 1.73E-05 1.36E-05 Xe-135 Ci 1.32E-03 6.01E-05 .

Ar-41 C4 0.00E+00 2.49E-05 :

Total C1 1.64E-03 1.05E-04 i Gr-Alpha Ci 0.00E+00 7.80E-06 I

Zehbes En bbEs bkble ibdkbbbe bhbb nb rbb[okbbkviby wk .l present above detectable levels. See Table 1-5 for t lowerlimitsofdetectionforliquidsampleanalyses.ypIcal i

- There are no continuous mode radioactive liquid release pathways at Plant Hatch.

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E. I. HATCH NUCLEAR PLANT - UNIT 2 :

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 LIQUID EFFLUENTS Continuous Mode ** Batch Mode Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 -

H-3 Ci 3.30E+00 3.90E+00 Fission and activation products:

Na-24 Ci 2.15E-03 2.56E-04 -

Cr-51 Ci 1.02E-03 5.29E-04 Mn-54 Ci 2.30E-04 1.74E-04 Mn-56 Ci 1.39E-05 2.54E-05 i Fe-55 Ci 4.76E-02 1.06E-04 Co-58 Ci 4.98E-05 4.74E-05 Co-60 Ci 3.59E-03 1.64E-03 Zn-65 Ci 6.92E-03 2.76E-03 r As-76 Ci 4.49E-04 8.31E-05 ,

Sr-89 Ci 4.01E-04 2.58E-0'.

Sr-91 Ci 1.00E-03 3.02E-05 Sr-92 Ci 1.78E-04 2.95E-06 Y-91m C4 1.02E-04 1.31E-05 Y-92 C1 1.13E-03 1.66E-03 Nb-97 Ci 2.78E-05 2.33E-05 +

Mo-99 Ci 8.38E-04 5.88E-04 Tc-99m Ci 1.73E-03 1.38E-03 I-131 Ci 4.58E-03 2.95E-03 I-132 Ci 1.92E-04 5.79E-05 .

I-133 Ci 4.94E-03 4.42E-03 ,

I-134 Ci 1.85E-05 0.00E+00 !

I-135 Ci 2.72E-03 1.27E-03 Cs-134 Ci 6.86E-04 1.23E-03 i Cs-136 Ci 5.12E-05 6.72E-06 l Cs-137 Ci 3.31E-03 5.04E-03 i Cs 138 Ci 6.78E-05 0.00E+00 ;

Ba-139 Ci 2.06E-06 0.00E+00 Ba-140 Ci 5.17E-04 5.09E-05 ;

La-140 Li 9.25E-04 3.90E-04 1 Ce-141 Ci 7.37E-05 6.88E-05 1 Ce-144 Ci 5.93E-06 0.00E+00 Np-239 Ci 1.22E-02 2.28E-03 !

Zn-69m Ci 2.78E-05 0.00E+00 6 Sb-124 Ci 0.00E+00 3.62E-06 '

Total Ci 9.77E-02 2.73E-02 ;

i l

Dissolved and entrained gases- I Kr-85 Ci 1.11E-03 0.00E+00 !

Xe-131m Ci 7.88E-04 1.17E-04 >

Xe-133m C4 3.94E-06 1.03E-04 Xe-133 C1 5.61E-03 1.06E-02 i Xe-135m C4 5.94E-03 3.78E-03 .i Xe-135 C1 2.08E-02 3.25E-02 l Total Ci 3.43E-02 4.71E-02 ;

Gr-Alpha Ci 0.00E+00 0.00E+00

. . . . . . . . . . . . . ............................................... ~

Zeroes in this table indicate that no radioactivity was resent above detectable levels i powerlimitsofdetectionforliquidsampleanalysesSee Table 1-5 for typical j i

- There are no continuous mode radioactive liquid release pathways at Plant Hatch. :

,. - - _ . - . . - . - ~ -.. - - . - -

i TABLE 1-3c* l E. I. HATCH NUCLEAR PLANT - SITE !

SEMIANNUAL RADIOACTIVE-EFFLUENT RELEASE REPORT 1993 LIQUID EFFLUENTS <

Page 1 of 2

{;

Continuous Mode ** datch Mode l I

Nuclides 1 Released Unit Quarter 1 Quarter 2 Quarter 1- Quarter 2 H-3 Ci 1.88E+01 9.79E+00 ;

Fission and activation products:

Na-24 Ci 2.27E-03 2.56E-04 Cr-51 Ci 2.99E-03 5.24E-03 Mn-54 Ci .2.42E-03 4.34E-03 l Mn-56 Ci 1.39E-05 2.54E-05 Fe-55 Ci 1.44E-01 1.20E-03 f Fe-59 Ci 4.89E-05 4.36E-04 ,

Co-58 Ci 1.53E-03 1.96E-03 !

Co-60 Ci 1.56E-02 3.14E-02 ,

Zn-65 Ci 5.01E-02 7.32E-02 ;

As-76 Ci 3.02E-03 8.31E-05 i Rb-89 Ci 2.90E-04 0.00E+00 ,

Sr-89 Ci 2.36E-03 1.51E-03 i Sr-90 Ci 2.14E-04 1.66E-05 ;

Sr-91 Ci 1.04E-03 3.02E-05

Sr-92 Ci 1.82E-04 2.95E-06 !

Y-91m Ci 1.06E-03 1.31E-05 Y-92 Ci 1.13E-03 1.66E-03 Nb-95 Ci 0.00E+00 2.35E-05 .

Nb-97 C4 4.12E-04 2.33E-05 '

Mo-99 C1 8.38E-04 5.88E-04 Tc-99m Ci 1.95E-03 1.39E-03 '

Ru-103 Ci 0.00E+00 1.55E-06

Sb-125 O I-131 I-132 I-133 Ci Ci Ci Ci 2.59E-05 5.16E-03 1.92E-04 5.28E-03 3.00E-05 3.11E-03 5.79E-05 4.43E-03 1

}

+

I-134 Ci 1.85E 0.00E+00 1-135 Ci 2.72E-03 1.27E-03 i Cs-134 Ci 1.29E-03 2.21E-03 ,

Cs-136 Ci 7.82E-05 6.72E-06 Cs-137 Ci 8.95E-03 1.32E-02 :

Cs-138 Ci 3.77E-04 0.00E+00 r Ba-139 C4 1.30E-04 0.00E+00 i Ba-140 C1 7.81E-04 5.08E-05 La-140 Ci 1.05E-03 4.07E-04 Ce-141 Ci 7.75E-05 6.88E-05 !

Ce-144 Ci 5.93E-06 6.97E-05 !

Np-239 Ci 1.22E-02 2.28E-03 Zn-69m Ci 4.35E-05 0.00E+00 Sb-124 Ci 0.00E+00 3.62E-06 Total C1 2.70E-01 1.51E-01 ;

Zeroes in this table indicate-that no radioactivity was :

resent above detectable levels. i gowerlimitsofdetectionforliquidsampleanalysesSee Table 1-5 for typical

- There are no continuous mode radioactive liquid release pathways at Plant Hatch. .

4 4

t r , . . . _ _ _ _ _ _ _ _ _ _ _ _

l I

. i TABLE 1-3c* l E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 i LIQUID EFFLUENTS ;

Page 2 of 2 i Continuous Mode ** Batch Mode -

Nuclides .

Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 i Dissolved and entrained gases: ;

Kr-85m Ci 5.57E-07 0.00E+00 Kr-85 Ci 1.11E-03 0.00E+00 Xe-131m Ci 8.46E-04 1.17E-04 i Xe-133m Ci 3.94E-06 1.03E-04 :

Xe-133 Ci 5.85E-03 1.06E-02 'l Xe-135m Ci 5.96E-03 3.79E-03 i Xe-135 Ci 2.22E-02 3.25E-02 !

Ar-41 Ci 0.00E+00 2.49E-05 Total Ci 3.59E-02 4.72E-02 Gr-Alpha Ci 0.00E+00 7.80E-06 -

_... ______ ____............_...____________________..._____ i

Zeroes in this table indicate that no radioactivity was present above detectable levels See Table 1-5 for t lower limits of detection for liquid sample analyses.ypical '

- There are no continuous mode radioactive liquid release pathways at Plant Hatch. i

?

e b

h a

f f

I f

i

TABLE 1-4a t E. I. HATCH NUCLEAR PLANT - Unit 1 '

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 i INDIVIDUAL DOSES DUE TO LIQUID RELEASES r

Cumulative Doses per Quarter !

.................................._-_....._...._-__... ...... 8 Organ Tech Unit Quarter 1 % of Quarter 2 % of ,

Speg Tech Tech ;

Limit Speg Speg '

Limit Limit >

Bone 5.0 mrem 2.70E-02 5.40E-01 3.63E-02 7.25E-01 :'

Liver 5.0 mrem 4.70E-02 9.40E-01 6.72E-02 1.34E+00 .!

TBody 1.5 mrem 2.91E-02 1.94E+00 4.13E-02 2.75E+00 Thyroid 5.0 mrem 3.69E-03 7.38E-02 1.19E-03 2.38E-02 i Kidney 5.0 mrem .2.07E-02 4.15E-01 3.06E-02 6.12E-01 i Lung 5.0 mrem 3.68E-03 7.37E-02 4.77E-03 9.54E-02 :

GILLI 5.0 mrem 1.69E-02 3.38E-01 3.29E-02 6.57E 01 i l

t i

t 8

Cumulative Doses This Year j l bbgab Tebh Unib hbbrters ' E bb Spec 1 &2 Tech ;

l Limit Speg Limit

' " ' ~~

bbbb ib$b mrbm E$55b$b5 b$55E bi >

Liver 10.0 mrem 1.14E-01 1.14E+00 i

'J3ody 3.0 mrem 7.04E-02 2.35E+00 t Thyroid 10.0 mrem 4.88E-03 4.88E-02 i Ki8ney 10.0 mrem 5.13E-02 5.13E-01 !

I Lung 10.0 mrem 8.45E-03 8.45E-02 r GILLI 10.0 mrem 4.98E-02 4.98E-01 l l

4 i

I 4

e J

i e

d

I t

i

?

4 Y i

i TABLE 1-4b 4

E. I. HATCH NUCLEAR PLANT - Unit 2 :

SEMIANNIJAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 t INDIVIDUAL DOSES DUE TO LIQUID RELEASES l

?

i i

Cumulative Doses per Quarter !

brgbb ~~~hbbh~~~~bbib~hbbbEeb~5~~~E~bE~~~~hbbbbbb'5'~~E~bE~'~

Speg Tech Tech l Limit Spec Spec j Limit Limit '

bgbe b$b mrem k$hkh bb b$bbb-bk b$bbb bh h$b7b bk !

Liver 5.0 mrem 2.91E-02 5.82E-01 4.73E-02 9.46E-01 i TBody 1.5 mrem 1.95E-02 1.30E+00 3.27E-02 2.18E+00 Thyroid 5.0 mrem 3.74E-02 7.48E-01 2.65E-02 5.29E-01 Kidney 5.0 mrem 1.10E-02 2.20E-01 1.65E-02 3.30E-01 ;

Lung 5.0 mrem 2.92E-03 5.84E-02 5.15E-03 1.03E-01 i GILLI 5.0 mrem 5.23E-03 1.05E 3.07E 03 6.14E l

..._____._______.......___ _.__________-01 _________..____ ..__-02 _.

[

l 4 ,

a Cumulative Doses This Year ,

Organ Tech Unit Quarters % of Spec 1 &2 Tech >

q Limit Speg !

Limit ;

~ ~~~ ~ ~ ~

bbbe ' 5b$b~mbem k.bkb-bb~~k$bkb b5 '~ !

Liver 10.0 mrem 7.64E-02 7.64E-01 TBody 3.0 mrem 5.22E-02 1.74E+00 Thyroid 10.0 mrem 6.39E-02 6.38E-01 i Kidney 10.0 mrem 2.75E-02 2.75E-01 l

. Lung 10.0 mrem 8.07E-03 8.07E-02 j GILLI 10.0 mrem 8.30E-03 B.30E-02 .

i a l I

t

[

t i i I

l a 5

+

l 4

J l

i O TABLE l-5 '

LOWER LIMITS OF DETECTION - LIQUID SAMPLE ANALYSES The values in this table represent apriori lower limits of detection (LLD) which are typically achieved in laboratory analyses ofliquid radwaste samples.

RADIONUCLIDE LLD UNITS Mn-54 5.38E-08 uCi/ml ;

Fe-59 7.78E-08 Co-58 4.67E-08 Co-60 4.78E-08 ;

Zn-65 1.31E-07 ;

Mo-99 5.10E-07' Cs-134 7.18E-08 Cs-137 6.05E-08 Ce-141 1.41 E-07 Ce-144 6.30E-07

I-131 6.51E-08 O xe-135 Fe-55 8.458-o8 2.00E-06 Sr-89 5.00E-08 St-90 5.00E-08 i H-3 1.00E-05 ,

1

In accordance with Technical Specification Tables 4.15.1-1 (Unit 1) and 4.11.1-1 (Unit 2), i Table Notation b, the permissible Lower Limit of Detection may be increased inversely ;

proportional to the magnitude of the gamma yield. However, the LLD determined in this ,

manner must not exceed 10 percent of the Maximum Permissible Concentration (MPC) )

value specified in 10 CFR20, Appendix B, Table II (Column 2). ;

I i

O

O GASEOUS EFFLUENTS 2.1 REGULATORY LIMITS The Technical Specifications presented in this section are for Unit 1.

Requirements for Unit 2 are the same as for Unit 1; however, the Technical ;

Specification numbers are not the same.

TECHNICAL SPECIFICATIONS 3.14.2 The radioactive gaseous efIluent monitoring instrumentation charmels f shown in table 3.14.2-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.15.2.1 (a) are not exceeded. The alarm / trip setpoints of these channels shall be determined in accordance with the ODCM. (Technical Specification Table 3.14.2-1 is included in this section as ,

Table 2-1). ,

3.15.2.1 The dose rate at any time in the UNRESTRICTED AREAS (figure 3.15-1) due to radioactive matedals released ia gaseous effluents from the site ;

shall be limited to the following values:

a. The dose rate limit for noble gases shall be less than or equal to 500 O r mreme eer te the tetai body and iess ihen er eaeai te 3000 mremeyear to the skin.

b. The dose rate limit for I-131, I-133, tritium, and for all radioactive i materials in particulate form and radionuclides other than noble gases with half-lives greater than 8 days shall be less than or equal to 1500 mrem / year to any organ.

3.15.2.2 The air dose in UNRESTRICTED AREAS (figure 3.15-1) due to noble gases released in gaseous effluents from each reactor unit shall be limited to the ;

following: .

a. During any calendar quarter, to less than or equal to 5 mrad for gamma !

radiation and less than or equal to 10 mrad for beta radiation. ;

b. During any calendar year, to less than or equal tc,10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation. ;

O .

3.15.2.3 The dose to any organ of a AEhfBER OF THE PUBLIC from I-131, Q I-133, tritium , and all radionuclides in particulate form with half-lives greater than 8 days in gaseous efiluents released to UNRESTRICTED AREAS (figure l

l 3.15-1) from each reactor unit shall be limited to the following:

a. During any calendar quarter to less than or equal to 7.5 mrem to any organ. ;

i

b. During any calendar year to less than or equal to 15 mrem to any organ. .

3.15.2.4 The GASEOUS RADWASTE TREATMENT SYSTEM as described in the ODCM shall be in operation. (This Technical Specification applies whenever '

the main condenser air ejector system is b operation.)

4.15.2.4 GASEOUS RADWASTE TREATMENT SYSTEM operability shall be i demonstrated by administrative controls which assure that the offgas treatment system is not bypassed.

3.15.2.5 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium -

fuel cycle sources shall be limited to less than or equal to 25 mrem to the total ,

body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. 1 O (With the calculated doses from the release of radioactive materials in liquid or gaseous e!Tluents exceeding twice the limits of Specifications 3.15.1.2(a),

3.15.1.2(b), 3.15.2.2.(a), 3.15.2.2(b), 3.15.2.3(a), or 3.15.2.3(b), ,

calculations shall be made including direct radiation contributions from the i reactor units and from outside storage tanks to determine whether the above ;

limits of Specification 3.15.2.5 have been exceeded.)

3.15.2.6 The concentration of hydrogen downstream of the recombiners in the ,

main condenser offgas treatment system shall be limited to less than or equal to 4 1 percent by volume. {.

3.15.2.7 The gross gamma radioactivity rate of the noble gases Xe-133, Xe-135, Xe-138, Kr-85m, Kr-87, and Kr-88 measured at the main condenser evacuation :

system pretreatment monitor station shall be limited to less than or equal to j 240,000 uCi/second. i 6

O !

I 6.9.1.9 states in part:

O "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 efIluents that were in excess of I Ci, excluding ,

dissolved and entrained gases and tritium for liquid efiluents, or those in 'l excess of 150 Ci of noble gases or 0.02 Ci of radioiodines for gaseous j releases." j i

i

.j i

l O

i l

+

F i

i i

v O. i i

O .

1Antt 3. i rs , ?- 1 ( siit ti i or 1 )

4 It AOLOA_cJ t VE cast OUS L I I ( UI. ft.T_ HON I T 0ft i ffGJ N S T RUMEN I A T I ON Hi n i mttm Cleanne I s ACTION O_U HADL1 Appiicabili:; _

P a ramete r lytt rtimeyt

1. H. tin Condenser Orrgas treatment System Explosive Gas Monitoring System

- % llydrogen '106 flydrogen Monitor (I)

2. Huactor listilding Vent Stack Monitoring System i

Hadloactivity Hate 10S N a. Nobio Gas Activity Monitor (1) He s su remen t +

I'1 f

Verify Presence of 107

b. todisse Sampler Ca rt ritige (1) Cartridge

^3 w

Verify Presence of 107

c. Partict61sto Sampler F ilter (1) Filter

^

h o

d. Errinent System Flowsate

System Flowrate 10!s %

He nsnec metit Device (t) Hensurement M o

e. Sampler F towrate Measurement

Snapler F lowrate 104 %

Devico {1) Maa ste rement y v

3. Itecombiour Dtellding Vent f la t ion Monitoring System

Radioactivity Rate 105

a. Hoble Gas Activity Monitor (1) Hea ste remen t +

Verify Presence or 107

b. lodine Sampler Cartridge (1) Cartridge

Verify Presence of 101

c. Partictelato Sampler littor (1) Filter .

Sampler Flowrate lors

d. Snenplur f lowra te Measur ement (1) Measurement .

Device

_ _ . . . - - - - - ,e.. - - .__._m -

i l

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TAEC 2-1 (Sheet 3 of k)

,O TABLE 3.14.2-1 (SHEET 3 0F 4) l RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION l Table Notations

+ Monitor must be capable of responding to a Lower Limit of ,

Detection of 1 x 10-' pC1/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 lecst once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

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.

O ACTION 105 - With the number of channels OPERABLE less than ;

recuired by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided grab samples are taken daily and analyzed daily for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . With the number of main stack :

monitoring system channels OPERABLE less than required by '

the Minimum Channels OPERABLE requirement, without delay suspend drywell purge.

If the number of channels OPERABLE remains less than '

required by the Minimum Channels OPERABLE requirement for over 30 days, an explanation of the circumstances shall be included in the next s2mi-annual effluent release report. l ACTION 106 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE recuirement, operation of the main condenser offgas treatment system may continue provided:

(a) Gas samples are collected once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed within the ensuing a hours, or (b) Using a temporary hydrogen analyzer installed in the offgas system line downs;trean of the recombiner, O

hydrogen concentration readings are taken and logged every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

"'AELE 2-1(Sheet h cf L)

O TABLE 3.14.2-1 (SHEET 4 0F 4)~

RADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Table Notations (Continued)

If the number of channels OPERABLE remains less t1an required by the Minimum Channels OPERABLE requirement for over 30 days, an explanation of the circumstar.ces shall be t included in the next semi-annual effluent release report. '

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 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after the end of the sampling period.

If the number of channels OPERABLE remains less than required by +he 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 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months provided:

a. The offgas system is not bypassed, and i

b.

The offgas post-treatment monitor (011-K615) or the main ,

stack monitor (011-K600) is OPERABLE. '

F Otherwise, be in at least HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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. '

i l

() ,

i 2.2 MEASUREMENT AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Waste gas release at Plant Hatch is confined to four paths: main stack (also called the offgas vent), Unit I reactor building vent; Unit 2 reactor building vent, and the recombiner building vent. Each of these four paths is l continuously monitored for gaseous radioactivity. Each is equipped with an integrating-type sample collection device for collecting paniculates and iodines. Sample collection is in accordance with Technical Specification Tables 4.15.2-1 (Unit 1) and 4.11.2-1 (Unit 2). Unless required more frequently under certain circumstances specified in Table Notations to the ;

above mentioned tables, samples are collected as follows:

1. Noble gas samples are collected by grab sampling monthly.

2. Tritium samples are collected by grab sampling monthly.

3. Radioiodine samples are collected by pulling the sample stream through a charcoal cartridge over a 7-day period. l

4. Paniculates are collected by pulling the sample stream through a particulate filter over a 7-day period. ;

O s. The 2-dav verticeiete fiiters ebove are a airzed fer sress aiPha activity. !

6. Quarterly composite samples are prepared from the particulate filters collected over the previous quarter and the quanerly composite sample i is analyzed for Sr-89 and Sr-90. j 1

Sample analyses results and release flow rates from the four release i points form the basis for calculating released quantities of radionuclide- !

specific radioactivity, dose rates associated with gaseous releases, and cumulative doses for the current quarter and year. This task is normally ]

performed with computer assistance.

)

I l

1 0

l

I l

' Q The noble gas grab sample analysis results are used along with maximum expected release flow rates from each of the four vents to calculate monitor setpoints for the gaseous effluent 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 morutor setpomts is described in the Plant Hatch ODCM. l 4 .

With each release period released radioactmty, dose rates, and l J

cumulative doses are calculated. Cumulative dose results are tabulated along with percent of Technical Specification limits (3.15.2.2 and !

3.15.2.3 (Unit 1); 3.11.2.2 and 3.11.2.3 (Unit 2) for each release, for the i current quarter and year. !

After each calendar quarter (13 weeks) a summary ofwaste gas releases

. from the four vents is compiled for preparation of the Semiannual l EfIluent Release Report required by Technical Specifications 6.9.1.8 ;

~

and 6,9.1.9 and described in NRC Regulatory Guide 1.21.

- i The methods for determining released quantities of radioactivity, dose

rates and cumulative doses are as follows: ;

1. FISSION AND ACTIVATION GAS J

O The radionuclide-specific released radioactivity is determined from sample i

4 analyses results collected as described above and average release flow rates i over the period represented by the collected sample. !

I instantaneous dose rates due to noble gases and due to radiciodines, tritium, l

]

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 i j 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 paniculates. Dose rate calculation l methodology is presented in the Plant Hatch ODCM. .

4 i

e t 1

l l 4

i i

O l

l

_ _ _ _ _ _ ___ t

i I

l 1

Q Beta and gamma air doses due to noble gases are calculated for the location in the unrestricted area with the potential for the highest exposure due to !

gaseous releases. Air doses are calculated for each re' ease period and ,

cumulative totals are kept for each unit for the current calendar quarter and !

year. Cumulative air doses are compared to the dose limits specified in ;

Technical Specifications 3.15.2.2 (Unit 1) and 3.11.2.2 (Unit 2). Current i percent of technical specification limits are shown on the printout for each release period. Air dose calculation methodology is presented in the Plant Hatch ODCM.

2. RADIOIODINE, TRITIUM, AND PARTICULATE RELEASES :

Released quantities of 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 four release points. Gamma ,

spectroscopy is used to quantify concentrations ofprincipal gamma emitters.

Afler each calendar quarter the particulate filters from each vent are ;

combined, fused, and strontium separation is performed. Since sample flows !

O endvent<lowsarealmostconsientevereachouar1erixgeriodthefiiters from each vent can be dissolved together. Decay corrections are made back ,

to the middle of the quarterly collection period. Where significant Sr-89 or i Sr-90 is not detected, LLD's are calculated. Strontium concentrations are I input to the composite file of the computer to be used in release, dose rate _l

~

and individual dose calculations.

Tritium samples are obtained monthly from each vent by passing the sample ;

stream through a cold trap. The grams of water vapor / cubic foot gas is ;

measured upstream of the cold trap in order to alleviate the difficulties in determining water vapor collection 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. (

s O

I i

O oose r tes d"e te r dieiedi#e. triti" - "a v < tic'i tes re c>ic"' ted rer -

hypothetical child, exposed to the inhalation pathway, at the location in the l

unrestricted area where the potential dose rate is expected to be the highest. I Dose rates are calculated for each release point, for each release period, and the total dose rate from all four release points are compared to the dose rate '

limits specified in Technical Specifications 3.15.2.1.b (Unit 1) or 3.11.2.1.b i

(Unit 2).

Individual doses due to radiciodine, tritium, and paniculates are calculated f for the critical receptor, which is described in the Plant Hatch ODCM. l Individual doses are calculated for each release period and cumulative totals are kept for each unit for the current calendar quaner and year. Cumulative individual doses are compared to the dose limits specified in Technical Specifications 3.15.2.3 (Unit 1) and 3.11.2.3 (Unit 2). Current percent of technical specification limits are shown on the printout for each release i peciod.

i

, 3. GROSS ALPHA RELEASE l The gross alpha release is computed each month by counting the particulate l filters each week for gross alpha activity in a gas flow proportional counter. i O The foer er five weel s nembers are then recorded en a deta sheet and the activity is summed at the end of the month. The summed activity is then ,

divided by the total monthly volume to determine the concentration. This

, concentration is input to the composite file of the computer and is used for ;

I release calculations. l

'1

4. ERROR ESTLMATES Regulatory Guide 1.21 requires that estimated total error in analysis i 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. l 1

4

O

$ "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 diflicult to assign error terms for each parameter afTecting 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 liquid and gaseous effluents and solid waste."

Estimated errors are based on errors in counting equipment calibration, counting statistics, vent flow rates, vent sample flow rates, non-steady release rates, chemical yield factors, and sample losses for such items as charcoal cartridges.

(1) Fission and Activation Total Release was calculated from sample analysis results and release point flow rates.

Statistical Error 60 %

Counting Equipment Calibration 10 %

Vent Flow Rates 10 %

Non-Steady Release Rates 20 %

100 %

(2) 1-131 Release was calculated from each weekly sample:

O Statistical Error 60 %

Counting Equipment Calibration 10 %

Vent Flow Rates 10 %

Vent Sample Flow Rates 10%

Non-Steady Release Rates 10 %

Losses From Charcoal Cartridge 10 %

110 %

(3) 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 %

Counting Equipment Calibration 10 % ;

Vent Flow Rates 10 % !

Vent Sample Flow Rates 10 %

Non-Steady Release Rates 10 %

100 % ,

1 O

l l

(4) Total Tritium Release was dominated by the reactor building vent tritium !

release; hence, the larger statistical errors of the off-gas vent and recombiner i building vent tritium releases do not affect the error in the total tritium release: l Water Vapor in Sample Stream Determination 20%

Vent Flow Rates 10%

Counting Calibration and Statistics 10 % !

Non-Steady Release 50%

90 %

i 2.3

GASEOUS EFFLUENT Rh ME DATA

, Regulatory Guide 1.21 Tables l A, IB, and IC are found in this report as Table 2-2a for Unit 1, 2-2b for Unit 2, and Table 2-2c for site; and Table 3-3a for Unit 1, t Table 3-3b for Unit 2 and Table 3-3c for site; and Table 2-4a for Unit 1, Table 2-4b for Unit 2, and Table 2-4c for site. Data are presented on a quarterly basis as ;

required by Regulatory Guide 1.21.

To complete Tables 2-2a-c, total release for each of the four categories (fission l and activation gases; iodines; particulates; and tritium) was divided by the number of seconds in the quarter to obtain a release rate in uCi/second for each :

category.

Ilowever, the applicable Technical Specification limits are not in terms of release rate in uCi/second but in terms of dose rate in mrem / year, as presented in Technical Specifications 3.15.2.1 (Unit 1) and 3.11.2.1 (Unit 2). Noble gases are limited as specified in 3.15.2.1.a and 3.11.2.1.a. The other three categories (tritium, radiciodines, and paniculates) are limited as a group as specified in ,

3.15.2.1.b and 3.11.2.1.b. Further the limits specified in Technical Specifications 3.15.2.1 and 3.11.2.1 are site limits, not unit limits. Dose rates due to noble gas releases and due to radiciodine, tritium, and particulates are presented in .

Table 2-5 along with percent of technical specification limits. .

Gross alphr radioactivity is reported in Tables 2-2a,2-2b, and 2-2c as curies ,

released in each quarter.

l Limits for cumulative beta and gamma air doses, due to noble gases, are specified in Technical Specifications 3.15.2.2 (Unit 1) and 3.11.2.2 (Unit 2). These limits are unit limits. Cumulative air doses are presented in Tables 2-6a and 2-6b, along with percent of technical specification limits.

There were no unplanned releases.(See Section 5 for Monitor out of service information). <

O i

Limits for cumulative individual doses, due to radioiodine, tritium, and !

paniculates, are specified in Technical Specifications 3.15.2.3 (Unit 1) and

'Q 3.11.2.3 (Unit 2). These limits are also unit limits. Cumulative individual doses t

are presented in Tables 2-7a and 2-7b, with percent of technical specification :

limits. [

t 2.4 RADIOLOGICAL IMPACT DUE TO GASEOUS RELEASES Dose rates due to noble gas releases were calculated for the site in accordance with Technical Specifications 3/4.15.2.1.a (Unit 1) and 3/4.11.2.1.a (Unit 2).

Results are presented in Table 2-5. Dose rates due to radioiodine, tritium, and i particulates in gaseous releases were calculated in accordance with Technical f Specifications 3/4.15.2.1.b (Unit 1) and 3/4.11.2.1.b (Unit 2). These results are l also in Table 2 * .

Cumulative air doses due to noble gas releases were calculated for each unit in l accordance with Technical Specification 3/4.15.2.2 (Unit 1) and 3/4.11.2.2 i (Unit 2). These results are presented in Table 2-6a for Unit I and Table 2-6b for Unit 2..

i Cumulative doses to an individual due to radiciodme, intium , and particulates were calculated for each unit in accordance with Technical Specifications !

O 3/4.15.2.3 < uni 1 > > and 3/4.li.2.3 cUnii 2). These resuits are gresented in Tabie 2-7a for Unit I and Table 2-7b for Unit 2.

Dose rates and doses were calculated using the methodology presented in the !

Plant Hatch Offsite Dose Calculation Manual.

F 1

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a34-l

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TABLE 2-2a i E. I. HATCH NUCLEAR PLANT - UNIT 1 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 O GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES i

l Unit Quarter 1 Quarter 2 Est. Total .

Error (%) !

A. Fission and '

Activation '

Gases

1. Total Ci 2.30E+02 8.86E+01 1.00E+02 Release i uCi/sec

~

2. Average 2.80E+01 1.13E+01 f Release l Ratg For i Period i

3. % of Tech %

Spec Limit I

B. Iodines

1. Total Ci 1.74E-02 1.33E-02 1.10E+02 Iodine-131 -

2. Average uCi/sec 2.12E-03 1.69E-03 ;

d Release >

Rate For Period

3. t of Tech %

Spec Limit 4 4

C. Particulates !

1. Particulates Ci 7.72E-04 8.29E-03 1.00E+02 i'

O with half-lives > 8 days

2. Average uCi/sec 9.41E-05 1.05E-03 Release i Ratg For '

i Period

% of Tech

3. %

Spec Limit

4. Gross Alpha Ci 7.19E-07 9.00E-07 Radioactivity D. Tritium

1. Total Ci 4.49E+00 6.12E+00 9.00E+01

2. Average Release uCi/sec 5.47E-01 7.78E-01

Ratg For 1 Period

3. % of Tgch %

. Spec Limit

Technical Specification limits are in terms of dose rate :

(mrem / yr) anB dose (mrem). See Tables 2-5, 2- 6a, 2- 6b, 2-7a, and 2-7b. l' i

4 0

I

.i TABLE 2-2b :

E. I. HATCH NUCLEAR PLANT - UNIT 2 !

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 i O GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES i

Unit Quarter 1 Quarter 2 Est. Total Error (%) -

A. Fission and ,

Activation '

Gases i

1. Total Ci 2.08E+02 2.05E+02 1.00E+02 Release

2. Average uCi/sec 2.53E+01 2.60E+01 Release i Ratg For !

Period

3. % of T9ch Spec Limit r

i B. Iodines i

1. Total Ci 1.65E-02 8.82E-03 1.10E+02 Iodine-131

2. Average uCi/sec 2.00E-03 1.12E-03 Release Rate For Period ;

3. % of Tech %-

Spec Limit !

i C. Particulates

1. Particulates Ci 7.03E-03 7.88E-03 1.00E+02 with half- ;

lives > 8 .

days :'

2. Average uCi/sec 8.56E-04 1.00E-03 Release Ratg For Period

3. % of Tgch % .

Spec Limit !

4. Grogs Alpha Ci 6.97E-07 8.34E-07 Radioactivity D. Tritium

1. Total Ci 7.86E+00 6.81E+00 9.00E+01 !

2. Average Release uCi/sec 9.58E-01 8.67E-01 Rate For Period

3. % of Tgch %

Spec Limit

Technical Specification limits are in terns of dose rate (mrem /yr) anB dose (mrem). See Tables 2-5, 2-6a, 2-6b, -

2-7a, and 2-7b r

()

~36-i

l TABLE 2-2c !

E. I. HATCH NUCLEAR PLANT - SITE i SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 .j GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES !

j Unit Quarter 1 Quarter 2 Est. Total l Error (%) j i

A. Fission and !

Activation i Gases

1. Total Ci 4.38E+02 .2.93E+02 1.00E+02 i Release f

2. Average uCi/sec 5.34E+01 3.73E+01 !

Release .;

Ratg For .i' Period '

3. % of Tgch % ~

Spec Limit t

i B. Iodines !

1. Total Ci 3.38E-02 2.21E-02 1.10E+02 i' Iodine-131

2. Average uCi/sec 4.12E-03 2.82E-03 i Release Rate For i Period l

+3. % of Tech %

Spec Limit C. Particulates

1. Particulates Ci 7.80E-03 1.62E-02 1.00E+02 I O with half-lives > 8 days l

2. Average uCi/sec 9.50E-04 2.06E-03

Release '

Rate For Period

3. % of Tgch %

Spec Limit i'

4. Gross Alpha Ci 1.42E-06 1.73E-06 Radioactivity :

l l

D. Tritium i

1. Total Ci 1.23E+01 1.29E+01 9.00E+01 1

2. Average uCi/sec 1.50E+00 1.64E+00 Release !

Rate Period For !

+

3. % of Tech %

Spec Limit i

Technical Specification limits are in terms of dose rate l (mrem /yr) and dose (mrem). See Tables 2-5, 2-6a, 2-6b, l 2-7a, and 2-7b. I 1

.i-TABLE 2-3a 1 E. I. HATCH NUCLEAR PLANT - UNIT 1 i

p. SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 GASEOUS EFFLUENTS - ELEVATED RELEASES

Continuous Mode Batch Mode **

... ......___......._..._________........____________........ t Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission Gases ;

~~~~~~ ~~~~ ~~ ~~ ~

r$ 8bm~ ~ b[ ^ 8$bhb5b5 b$bbb+bb~

Kr-87 Ci 8.49E+00 2.86E+00 Xe-133 Ci 4.41E-01 0.00E+00 Xe-135m C4 4.16E+01 8.42E+00 1 Xe-135 C1 8.65E+00 1.93E+00 :

Xe-138 Ci 1.38E+02 3.27E+01 >

Total For Period Ci 1.98E+02 4.59E+01 '

2. Iodines

~~~~~i i3i ~~ ~bE" 5$bbb bb b$bbb-bk I-133 Ci 1.90E-03 9.23E-04 1-135 Ci 1.45E-03 4.90E-04 ,

Total For Ci 1.70E -02 1.99E Period ____..... ....__..___._ ___________-03__________.._____________

f

3. Particulates ~ ~~ ~~

i

~~~~~ho'6b~ ~k.bbb bh~

bk b$bbE bb~

Sr-89 C1 9.62E-06 5.23E-06 Sr-90 Ci 1.53E-07 6.38E-08 Cs-137 Ci 8.47E-08 0.00E+00 Ba-140 Ci 2.12E-05 2.20E-06 La-140 Ci 4.14E-05 3.92E-06 I-131 Ci 1.57E-05 0.00E+00 Total For r Period Ci 8.82E-05 1.14E-05 *

Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for ty lower limits of detection for gaseous sample analyses.pical

- There are no batch mode radioactive gaseous release pathways at Plant Hatch.

i r

5 1

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1 TABLE 2-3b i E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 l

\ GASEOUS EFFLUENTS - ELEVATED RELEASES * ;

Continuous Mode Batch Mode **

Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission Gases

~ ~" ~~

~~kh hbm~ Ci~~~b$b7b5b1 ~b$bbb bb~ l Kr-87 Ci 6.89E+00 6.68E+00 :

Xe-133 Ci 9.44E-01 4.68E-01 Xe-135m Ci 3.33E+01 2.60E+01 Xe-135 Ci 7.47E+00 5.00E+00 Xe C1 1.07E+02 8.01E+01

..______-138 ............_____.....................................

Total For Period Ci 1.56E+02 1.18E+02

2. Iodines :

I-131 Ci 3.87E-03 7.68E-04 I-133 Ci 1.23E-03 1.95E-03 '

s I-135 Ci 1.41E-03 2.12E-03 Total For -

Period Ci 6.51E-03 4.84E

...________-03 .......... ________...___

3. Particulates i Sr-89 Ci 8.91E-06 1.23E-05 Sr-90 Ci 1.42E-07 1.50E-07 Cs-137 Ci 8.47E-08 9.45E-08 .

Ba-140 Ci 2.10E-05 1.95E-05 La-140 Ci 4.05E-05 4.43E-05 I Ci 3.85E-06 2.44E-07

... __-131

+

Total For Period _______ ...............___-05 Ci 7.45E 7.66E

___-05 ___.................. __

Zeroes in this table indicate that no radioactivity was :

present above detectable levels. See Table 2-8 for ty i lower limits of detection for gaseous sample analyses.pical i

- There are no batch mode radioactive gaseous release pathways at Plant Hatch. .<

(

I

~39-

P i

y TABLE 2-3c -

E. I. HATCH IRTCLEAR PLANT - SITE i SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 !

GASEOUS EFFLUENTS - ELEVATED RELEASES

f Continuous Mode Batch Mode ** i Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 -

6 I

1. Fission Gases i

~

kr-85m Ci k$7bb+bb ~b$bbb+bb !

Kr-87 Ci 1.54E+01 9.54E+00 Xe-133 Ci 1.38E+00 4.68E-01 t Xe-135m Ci 7.49E+01 3.44E+01 '

Xe-135 Ci 1.61E+01 6.93E+00 Xe 138 Ci 2.45E+02 1.13E+02 Total For !

Period Ci 3.54E+02 1.64E+02 ,

2. Iodines

~~~~"i~_iji~~~~~Ci'~ 5$75b5b2 ~5$5EE~-b5~~~~~~~ ~ ~ ~~~ ~~~~~~ '

I-133 Ci 3.13E-03 2.87E-03 I 135 Ci 2.86E 2.62E-03

....._..__ ....._________-03_...__......___.. ....___. ... _____

i Total For :

Ci 2.35E 6.83E 4

Period... ______.__.......______-02 __......._-03

3. Particulates ,

J Co-60 Ci 1.00E-07 0.00E+00 ;

Sr-89 Ci 1.85E-05 1.75E-05 3 Sr-90 C:. 2.95E-07 2.14E-07 Cs-137 C:. 1.69E-07 9.45E-08 '

Ba-140 C1 4.21E-05 2.17E-05 l La-140 Ci 8.19E-05 4.82E-05 I-131 Ci 1.96E-05 2.44E-07 !

Total For Ci 1.63E 8.80E :

Period..___...__..._____________-04 _._________-05_._____________ .....__.

3

Zeroes in this table indicate that no radioactivity was !

present above detectable levels. See Table 2-8 for ty lower limits of detection for gaseous sample analyses.pical :

- There are no batch mode radioactive gaseous release pathways at Plant Hatch.

1 1

i I

4 4 t

TABLE 2-40 l E. 1. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 i GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES

Continuous Mode Batch Mode ** I Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2

1. Fission Gases

~ ~ ~ ~ ~5e 2 535 ~ ~ ~ ~ bi~ ~ 'i[9hb bi~ ~ ~ b $ bib b5" ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Xe-135 Ci 1.25E+01 1.66E+01 Total For Period Ci 3.22E+01 4.27E+01

2. Iodines

~

~ ~ ~ ~ ~ i iji~ ~ ~ ~ ~ C1' ~ ~ 3 hkb2 b5 ' ~ 'i$ 5hb2 b5 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ' ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

I-133 Ci 1.12E-03 1.25E-01 I-135 Ci 2.12E-03 2.57E-01 Total For Ci Period._________.___.........__-03 6.98E 3.95E-01

3. Particulates

~~~~~kn bb b " ~b$kkb bb b$bkb bb Co-58 Ci 4.02E-06 0.00E+00 Co-60 Ci 1.33E-05 4.41E-06 Zn-65 Ci 6.38E-04 4.77E-05 Sr-89 Ci 1.00E-05 1.43E-03 -

Sr-90 Ci 6.46E-08 5.19E-05 Cs-137 Ci 2.13E-06 0.00E+00 Ba-140 Ci 3.24E-06 1.80E-03 La-140 C4 0.00E+00 3.83E-03 ;

Ce-141 C1 0.00E+00 5.39E-05 ;

I-131 Ci 1.07E 1.06E-03

...............___. .__.._-05 ___.._____.__...............___....

l Total For Period Ci 6.84E-04 8.28E-03 l

l 1

Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for ty lower limits at detection for gaseous sample analyses.pical

' **There are no batch mode radioactive gaseous release pathways at Plant Hatch, t

1 1

i TABLE 2-4b E. I. HATCH NUCLEAR PLANT - UNIT 2 4 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES

I Continuous Mode Batch Mode **

Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 s

1. Fission Gases ~~~~ ~~~~

~~~~~EeSi35~ ~~Ci~~~5$57E bi'~~b$b55 bi~~~~~~~~~ !

Total For l Period Ci 5.17E+01 8.63E+01 f

2. Iodines

... __.. ___...................... ........._._ ............. 7 I-131 Ci 1.26E-02 8.05E-03 ,

I-133 Ci 5.04E-02 6.99E-02 I Ci 9.82E-02 1.40E-01 ;

......_-135 .............................................. .......

Total For Period Ci 1.61E-01 2.18E-01

3. Particulates

~'~~~h.hb~~~~~hi'~~h[ihg.hi~~~h[h7h hi~~~~~~~~~~~~~~~~~~~~~~

Zn-65 Ci 9.24E-05 5.17E-05 Sr-89 Ci 1.41E-03 1.52E-03 Sr-90 Ci 1.33E-05 3.17E-05 Cs-137 Ci 3.20E-05 5.10E-06 Ba-140 Ci -1.47E-03 1.81E-03 La-140 Ci 2.93E-03 3.46E-03 Ce-141 Ci 3.97E-05 4.93E-05 l

~

I 131 Ci 9.57E-04 8.74E-04 Total For Ci 6.95E 7.80E-03 -

Period...................___.__-03 ................ ................... t 1

Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for ty lower limits of detection for gaseous sample analyses.pical

- There are no batch mode radioactive gaseous release pathways at Plant Hatch. l r

r I

b

i F

i TABLE 2-4c E. I. HATCH NUCLEAR PLANT - SITE i SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 GASEOUS EFFLUENTS - GROUND-LEVEL RELEASES

Continuous Mode Batch Mode ** ;

Nuclides Released Unit Quarter 1 Quarter 2 Quarter 1 Quarter 2 i

1. Fission Gases Xe-133 Ci 1.97E+01 2.61E+01 Xe Ci 6.42E+01 1.03E+02

. ____ .-135 ......_......._......__________....________..........

Total For Period Ci 8.39E+01 1.29E+02 t

t

2. Iodines

~~~~~i~_[35~ b[" k.bbb bb b$bbbbb '

I-133 Ci 5.16E-02 1.95E-01 '

I-135 Ci 1.00E-01 3.97E

.......... . __.......__....________-01 ............. _____....._ ;

Total For Period Ci 1.68E-01 6.13E-01

3. Particulates ~

~~~~}~$2hk'~~~'hi~~~h[dihlhh~~~h[hhh.hh'~~~~~~~~~~~~~~~~~~~~~

4 Co-58 Ci 4.02E-06 0.00E+00 Co-60 Ci 1.84E-35 1.10E-05 i Zn-65 Ci 7.31E-04 9.94E-05 Sr-89 Ci 1.42E-03 2.95E-03 Sr-90 Ci 1.34E-05 8.35E-05 Cs-137 Ci 3.41E-05 5.10E-06 Ba-140 Ci 1.48E-03 3.61E-03 La-140 Ci 2.93E-03 7.29E-03 Ce-141 Ci 3.97E-05 1.03E-04 I Ci 9.67E-04 1.94E-03

.. __.-131. ..____ ....__________............____....... _....._.

Total For Ci 7.64E 1.61E-02 Period......_____________......_-03

Zeroes in this table indicate that no radioactivity was See Table 2-8 for ty present above detectable levels. lower limits of detection for gaseous sample analyses.pical *

- There are no batch mode radioactive gaseous release i pathways at Plant Hatch.

i t

4 I

6 i

4 i

e

Table 2-5 E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 GASEOUS EFFLUENTS - DOSE RATES Dose Rates Due to Noble Gases Organ Tech Unit Quarter 1 % of Quarter 2 % of' Spec Tech Tech Limit Speg Speg Limit Limit hbbby bbb mbbm yb ~5$kbb-b5 b$bbb bb b$khb-b5 k$bkk-bb Skin 3000 mrem yr 3.05E-01 1.02E-02 4.70E-01 1.57E-02 Dose Rates Due to Radiciodine, Tritium, and Particulates Organ Tech Unit Quarter 1 % of Quarter 2 % of Spec Tech Tech Limit Speg Speg Limit Limit Ebbe 5bbb mbb[n yh k.kbb-bb b$h5b bk k$bhb-bb 5$bkE$b5 Liver 1500 mrem yr 1.54E-02 1.03E-03 2.05E-02 1.37E-03 TBody 1500 mrem yr 1.45E-02 9.65E-04 1.81E-02 1.20E-03 Thyroid 1500 mrem yr 4.88E-01 3.25E-02 1.17E+00 7.83E-02 Kidney 1500 mrem yr 1.66E-02 1.11E-03 2.40E-02 1.60E-03 Lung 1500 mrem yr 2.08E-02 1.39E-03 '3.16E-02 2.11E-03 GILLI 1500 mrem yr 1.49E-02 9.91E-04 1.91E-02 1.27E-03 1

i P

i TABLE 2-6a E. I. HATCH NUCLEAR PLANT - UNIT 1 l SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 AIR DOSES DUE TO NOBLE GAS RELEASES i

r Cumulative Doses per Quarter T'rpe Tech Unit Quarter 1 % of Quarter 2 % of ol' Spec Tech Tech Radi- Limit Speg Spec ation Limit Limit bkmmb b$b mrbd k$5bb bb b$5kb b5 k$khb-bb b$5kb5b5' !

Beta 10.0 mrad 1.47E-02 1.47E-01 1.83E-02 1.83E-01 ;

Cumulative Doses This Year Me Tech Unit Quarters % of ot Speg 1 &2 Tech .

Radi- Limit Speg :

ation Limit <

, Gamma 10.0 mrad 2.32E-02 2.32E-01 t Beta 20.0 mrad 3.30E-02 1.65E-01 E

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TABLE 2-6b E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 AIR DOSES DUE TO NOBLE GAS RELEASES Cumulative Doses per Quarter Me Tech Speg Unit Quarter 1 % of Quarter 2 % of or Tech Tech Radi- Limit Spec Spec ation Limit Limit bkmmk h$b mrkb b.hhb-bb h$hhb$b5 k$bhb2bb b$5hb2b5 Beta 10.0 mrad 3.46E-02 3.46E-01 5.70E-02 5.70E-01 Cumulative Doses This Year M'e Tech Unit Quarters % of ot Speg 1 &2 Tech Radi- Limit Spec ation LJ.mit ~ ~

Ukmm$ 'kb$b mr$b~"h$khb$bb~ h.khb5bk Beta 20.0 mrad 9.15E-02 4.58E-01 NM i

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Y

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t TABLE 2-7a E. I. HATCH NUCLEAR PLANT - Unit 1 i SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 i INDIVIDUAL DOSES DUE TO RADIOIODINE TRITIUM, AND PARTICULATES IN GASEOUS RELbASES j i

i Cumulative Doses per Quarter l f

Organ Tech Unit Quarter 1 % of Quarter 2 % of i Spec Tech Tech I Limit Speg Speg Limit Limit Bone 7.5 mrem 8.18E-04 1.09E-02 3.44E-02 4.59E-01 !

Liver 7.5 mrem 3.08E-03 4.10E-02 4.54E-03 6.05E-02 TBody 7.5 mrem 2.82E-03 3.76E-02 9.04E-03 1.21E-01 1,.

Thyroid 7.5 mrem 8.76E-02 1.17E+00 2.72E-01 3.62E+00 :

Kidney 7.5 mrem 3.09E-03 4.12E-02 5.17E-03 6.89E-02 i Lung 7.5 mrem 2.49E-03 3.32E-02 4.31E-03 5.74E-02 i GILLI 7.5 mrem 2.52E-03 3.36E-02 4.75E-03 6.33E-02 l f

t 1

i Cumulative Doses This Year l Orcan Tech Unit Quarters % of I Speg 1&2 Tech !

Limit Speg !

Limit ;

Bone 1S.0 mrem 3.52E-02 2.35E-01 i Liver 15.0 mrem 7.62E-03 5.08E-02 :

TBody 15.0 mrem 1.19E-02 7.91E-02 !

Thyroid 15.0 mrem 3.59E-01 2.39E+00 ,

Kidney 15.0 mrem 8.26E-03 5.50E-02 :

Lung 15.0 mrem 6.80E-03 4.53E-02 :

GILLI 15.0 mrem 7.27E-03 4.84E-02 5 l

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TABLE 2-7b

E. I. HATCH NUCLEAR PLANT - Unit.2 !

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1993 t INDIVIDUAL DOSES DUE TO RADIOIODINE TRITIUM, AND PARTICULATES IN GASEOUS REL$ASES Cumulative Doses per Quarter I f

Organ Tech Unit Quarter 1 % of Tech Quarter 2 % of Tech Spec !

Speg Speg Limit Limit Limit !

Bone 7.5 mrem 2.04E-02 2.72E-01 2.77E-02 3.69E-01 Liver 7.5 mrem 5.26E-03 7.02E-02 4.39E-03 5.85E-02 TBody 7.5 mrem 6.30E-03 8.40E-02 7.30E-03 9.73E-02 Thyroid 7.5 mrem 2.31E-01 3.08E+00 1.68E-01 2.25E+00 Kidney 7.5 mrem 5.59E-03 7.45E-02 4.74E-03 6.32E-02 ,

Lung 7.5 mrem 4.92E-03 6.56E-02 4.50E-03 6.00E-02 :

GILLI 7.5 mrem 5.16E-03 6.89E-02 4.81E-03 6.41E-02 ;

Cumulative Doses This Year Organ Tech Unit Quarters % of Spec 1 &2 Tech Limit Speg l Limit Bone 15.0 mrem 4.81E-02 3.21E-01 Liver 15.0 mrem 9.65E-03 6.43E-02 i TBody 15.0 mrem 1.36E-02 9.07E-02 i Thyroid 15.0 mrem 3.99E-01 2.66E+00 Kidney 15.0 mrem 1.03E-02 6.88E-02 Lung 15.0 mrem 9.42E-03 6.28E-02 :

GILLI 15.0 mrem 9.97E-03 6.65E-02 l j

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O T^EtE 2 8 LOWER LIMITS OF DETECTION - GASEOUS SAMPLE ANALYSES The values in this table represent apriori lower limits of detection (LLD) which are typically achieved in laboratory analyses of gaseous radwaste samples.

RADIONUCLIDE LLD UNITS Kr-87 1.31E-07 uCi/ml Kr-88 2.10E-07 Xe-133 1.62E-07 Xe-133m 6.07E-08 Xe-135 5.77E-08 Xe-138 2.85E-06 I-131 4.37E-14 I-133 6.16E-13 Mn-54 2.78E-14 Fe-59 4.62E-14 Co-58 2.46E-14 O Co-60 Zn-65 2.88E-14 7.51E-14 Mo-99 6.02E-13 Cs-134 3.64E-14 Cs-137 2.88E-14 Cs-141 4.94E-14 Cs-144 2.02E-13 Sr-89 1.00E-1I Sr-90 1.00E-11 H-3 1.00E-06 O

3. SOLID WASTE l O 3.1 REGULATORY REQUIREMENTS i

i The Technical Specifications presented in this section are for Unit 1. ;

Requirements for Unit 2 are the same as for Unit 1; however, the Technical Specification numbers are not the same. !

TECHNICAL SPECIFICATIONS .j 3.15.3.1 The solid radwaste system shall be used in accordance with the PROCESS CONTROL PROGRAM to provide for the SOLIDIFICATION ]

of wet solid wastes and for the SOLIDIFICATION and packaging of other radioactive wastes, as required, to ensure the meeting of the requirements of 10 CFR Part 20 and of 10 CFR Part 71 prior to shipment of radioactive !

wastes from the site. :

i 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 de. ermined by measurement or estimate)

d. Type of waste, e.g., spent resin, compacted dry waste, evaporator bottoms I

e. Type of container, e.g., LSA, type A, type B, large quantity

f. Solidification agent, e.g., cement.

3.2 SOLID WASTE DATA Regulatory guide 1.21 Table 3 is found in this report as Table 3-1a. and 3-1b.

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1993 I JANUARY 1,1993 - JUNE 30,1993 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNITS I AND II TABLE 3-1A TORM TITLE: REG GUIDE 1.21 ETTLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT OF SOLID WASTE AND IRRADIATED TUEL SHIPKENTS I PERIOD COVERED: TROM 1/1/93 TO 06/30/93 TOR UNIT: 1 & 2 I

I A. SOLID WAS""E SHIPPED OTTS:"I TOR BURIAL OR DISPOSAL (Not irradiated fuel)

II hkPE OF WASTE UNIT 6 ncnth Est.Tetal period ERROR %

'a. Spent resins, filter sludges, '

M3 9.07E+01; l evaporator bottoms, etc. Ci 8.43E+021 1.0E+01 i

!b. Dry w ressible waste, M3 1.73E+01 '

l oost-t mated equip. etc. Ci 4.41E+00L 2.0E+01 lc. Irrodisted m nents, control M3 9.73E+00i i rods,Recire Pump Internals ! Ci ! 1.09E+05! 2.0E+01 l l M3 i 1.08E+00 i l

! d. Control Rod Drive Filters I ci i S.35E+00I 2.0E+01 i

e. Other (describe) I M3 1 0.00E+00! ! ,

equip. etc. I Ci ! 0.00E+00-

2. Estimate of ma3or nuclide con: position (by type of waste) l ISOTOPE ' PERCENT CURIES .

A: 2n-65 6.09E+01 5.13E+02' l To-55 !

8.14E+00- 6.86E+01' !

I Co-60 1.33E+01 1.12E+02 Co-137 3.25E+00 2.74E+01 !

CT F.ER 1.44E+01 1.21E+02 i B: 2n-65 4.55E+01 2.01E+00 ,

_ Te-55 2.19E+01 9.66E-01 i Co-60 2.06E+01 9.08E-01 Cs-137 2.62E+00 1.16E-013 j OTHER _

9.40E+00 4.15E-01 l

_C: 2n-65 1 0.00E+00 0.00E+00 - r re-55 4 5.36E+01- 5.84E+04 !

Co-60 4.01E+01 4.37E+04' l Cs-137 t 0.00E+00' O.00E+00l [

CPTHER 6.31E+00: 6.88E+03j l

.D: 2n-65 ! 4.15E+00 3. I.7 E-OL :

i To-55 1 2.87E+01 - _2.40E+00I l Co-60 ! 6.36E+01i 5.31E+001 j Co-137 I 0.00E+00l 0.00E+00 ;

OTHER 3.61E+00; 3.01E-01, ;

i E: En-65 1

Te-55 ,

i 6 co-60 Cs-137 ;

OTHER l

3. Solid Waste Disposition

) Number cf Shipments Mode of Trstsportation Destination f f 27 TRACTOR TRAIITR BARNWEI.L {

B. IRRADIATED TUEL SHIPPMINTS (Disposition) {

Number of Shipments Mode of Transportation Destination i j NT Is w'S !

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1993 JANUARY 1,1993 - JUNE 30,1993 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNITS I AND II TAOLE 3-1B FORM TITLE: UNIT 1 AND 2 TECH SPEC 6.9.1.9 EFFLUENT ANb WASTE DISPOSAL SEMIANNUAL REPORT OF SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD COVERED FROM: 1/1/93 TO 6-30-93 FOR UNIT 1&2 TYPE CURIE PRINICPLE BURIAL NUMBER VOLUME TYPE SOLIDIFI-OF QUANTITY NUCLIDES/ CONTAINER CONT. CONT. SHIPMENT CATION

. WASTE DETERMINE DETERMINE DESCRIP. SHIPPED CUBIC FT CONT. AGENT

-DEWATERED 412 En65,Co60 HIGH I 132.4 TYPE B RESINS MEASURED INTEGRITY CASK N/A Fe55 CONTAINER 10-142 MEASURED DEWATERED 4.2BE+02 Zn65,Co60 HIGH 14 202.1 TYPE A RESINS MEASURED Cs137 INTEGRITY CASK N/A Fe55 CONTAINER 14-210 MEASURED I l l

TORUS -

3.12 Zn65,Co60i HIGH I 202.1 I TYPE A CLEANUP l MEASURED ;

Cs137 , INTEGRITY; j CASK N/A FILTERS ; Fe55 . CONTAINER 14-210 i MEASURED : l i

i l , I DAW 3.59 Zn65,Co60 STRONG , 6 95 STRONG (DRY) Cs137 TIGHT TIGHT j N/A 1 iESTIMATEDl l l Fe55 CONT. BOXES 1 (ACTIVE) j l l i (WASTE) i MEASURED B-25 ! !

l B-25 ! !

I l l

DAW .I 0.810 lIn65,Co60li TWO 1 38.3 ! TYPE A l~ )

HIGH ESTIMATED 1 Cs137 .

DRUM t CASK N/A i RAD ! Fe55 !

OVER !

14-210 i

WASTE I IMEASURED PACK ! i i

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CRD 8.35 I Zn65,Cc60 HIGH 1 38.3 i TYPE A i ESTIMATED Cs137 INTEGRITY ! CASK N/A l f FILTERS14-210 l Fe55 CONTAINER l MEASURED i l l 1 IRRADIATED 1.09E+05 In65,Co60 STEEL 6 57.4 l TYPE B HARDWARE ESTIMATED CNSI 3-55 N/A MEASUPID O

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, . . . 1 1

)

O 4 c"^"oes To T"e v'^"T "^Tc" ooc" & Per !

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There were no changes for this period.

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l 5 MONITOR OUT OF SERVICE FOR GREATER THAN 30 DAYS ;

Technical Specification 3.14.2 (Unit 1) and Technical Specification 3.3.6.10 (Unit 2) r] contains a surveillance requirement 4.14.2 (Unit 1) and 4.3.6.10 (Unit 2) that each

/

radioactive gaseous efIluent monitoring instnimentation channel shall b,e - i demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE <

CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.14.2-1 (Unit 1) and Table 4.3.6.10-1 (Unit 2.). Technical Specification Action 104 states with the number of channels OPERABLE less than required by the mmimum channels OPERABLE requirement, effluent releases via this pathway may continue provided the flowrate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . If the number of channels OPERABLE remains less than required by the Mimmum Channels OPERABLE for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report.

The Main Stack flow recorder IDIl-R625 was tagged out of senice on December 19,1992, due to both A&B flow turbines being inoperable. Two new flow turbines were purchased and replaced in both A&B enclosures. After the flow turbine replacements, both flow turbines were peaked and proper response of the transmitters ,

were verified. The Main Stack flow recorder was placed back into senice April 10,1993.

8

HL-3428, Plant Ei Hatch,Units 1 & 2 Semiannual Radioactive Effluent Release Rept,Jan-June 1993

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HL-3428, Plant Ei Hatch,Units 1 & 2 Semiannual Radioactive Effluent Release Rept,Jan-June 1993

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