ML20147B228
| ML20147B228 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/31/1987 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| SL-4185, NUDOCS 8803020020 | |
| Download: ML20147B228 (208) | |
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t ! I I i l t l G!DRGIA POWER (DMPA.W !
< i j PLANT E. I. HATCH l
1 UNITS to. 1 & 2 I 1 I f SEMI-ANNUAL REPORT PIANT RADIOACTIVE EFFLUENT RELEASES July 1,1987 - December 31, 1987 1 l l l e I l j 8803020070 871231 PDR AD00K 05000321 N v i R . ..s, . ._, _~.. D C D ;; 4
PLAtC E. I. HATCH []
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SEMIAtMJAL REPORT
' RADIOACTIVE EFFLUEtC RELEASE REPORT SECTION TITLE PAGE
- 1. LIQUID EFFLUENTS 1 1.1 REGULATORY LIMITS 1 1.2 MAXIMUM PERMISSIBLE CONCENTRATIONS 5 1.3 MEASUREMENTS AND APPROXIMATIOt6 OF 5 TOTAL RADIOACTIVITY l.4 LIQUID EFFLUENT RELEASE DATA 7 1.5 RADIOLOGICAL IMPACT ON MAN DUE TO 9 LIQUID RELEASES l 2 GASEDUS EFFLUENTS 22 '
2.1 REGJLATORY LIMITS 22 2.2 MEASUREMENTS AND APPROXIMATIONS OF 28 7 URAL RADIOACTIVITY I P) b 2.3 GASEDUS EFFLUENT RELEASE DATA 33
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2.4 RADICIDGICAL IMPACT DUE 70 GASEOUS 34 . RELEASES l 3 SOLID WASIT 50 3.1 REGULATORY SPECIFICATIONS 50 1 3.2 SOLID WASTE DATA 50 i 4 CHAtCES TO THE PLANP HATCH RADIO- 53 i IDGICAL ENVIROtNENTAL MONI70RI?C I 5 CHAPCES TO THE PLANT HATCH OFFSITE 54 DOSE CALCULATION MANUAL 6 CHAPCES TO THE PLANP HATCH PROCESS 55 l CONIROL PROGRAM a 7 METEDROIfGY 56 7.1 56 METEOROIDGICAL DATA O I
I m PIANT E. I. HATCH SEMIANNUAL REPORT RADIOACTIVE EFFLUENT RELEASE REPORT TABLE LIST OF TAELES PAGE l-1 TECHNICAL SPECIFICATION TABLE 3.14.1-1 3 RADIOACTIVE LIWID EFFLUENT MONITORING INSTRUMENTATION 1-2a LIQUID EFFLUENTS - SUMMATION OF 10 , ALL RELEASES - UNIT 1 1-2b LIQUID EFFLUENTS - SUMMATION OF 11 ALL RELEASES - UNIT 2 1-2c LIQUID EFFLUENTS - SUMMATIONS OF 12 ALL RELEASES - SITE l-3a LIQUID EFFLUENIS - UNIT 1 13 1-3b LIQUID EFFLUENTS - UNIT 2 15 1-3c LIQUID EFFLUENTS - SITE 17 1-4a INDIVIDUAL DOSES DUE 70 LIQUID 19 RELEASES - UNIT 1 1-4b INDIVIDUAL DOSES DUE TO LIQUID 20 RELEASES - UNIT 2 1-5 I4WER LIMITS OF DerECTION - LIQUID 21 SAMPLE ANALYSES 2-1 TECHNICAL SPECIFICATION TABLE 24 3.14.2-1 RADIOACTIVE GASEOUS EFFLUENT !ONITORI?C INSTRUMENIATION 2-2a GASECUS EFFLUENTS - SUMMATION Or 35 ALL RELEASES - UNIT 1 2-2b GASEOUS EITLUENTS - SUMMATION OF 36 ALL RELEASES - UNIT 2 2-2c GASEOUS EFFLUENTS - SUMMATION OF 37 ALL RELEASES - SITE 2-3a GASDJUS EFFLUENTS - ELEVATEP 38 RELEASES - UNIT 1 2-3b GASEOUS EFFLUENTS - ELSATED 39 PELEASES - UNIT 2 2-3c GASEQUS EFFLUENTS - ELEVATED 40 RELEASES - SITE
. -. - _ = - . . . -
TABLES LIST C TABLES PAGE
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[~ 2-4a GASDOUS EFFLv8NTS - Gt00ND- 41 { LEVEL RELEASES - UNPt 1 , s 2-4 b - GASBOUS EFFLUENTS - Gt00ND - 42 l ! LEVEL RELEASES - UNIT 2 ; l ! ) 2-4c GASEOf5 PP%UENTS - Gt0UND - 43 LEVEL h%LSM ES - SITE 2-5 GASSOUS EFFLUENIS - DOSE 44 l RATES - SITE , , 2-6a AIR DOSES DUE 'IO NOBLE GASES - 45 UNIT 1 2-6b AIR DOSES DUE TO NOBLE GASES - 46 , UMT 2 I i 2-7a i INDIVIDUAL DOSES DUE 'IO RADIOIODINE, 47 l MITIUM, AND P.aJtTICULATES IN GASB00S ! RELEASES - UNIT 1 2-7b INDIVIDUAL DOSES DUE 'IO RADIOIODINE, 48 l RITIUM, AND PARTICULATES IN GASBOUS . RELEASES - UNIT 2 7 i i .; 2-8 IDWER LIMITS OF DETECTION - GASEOUS 49 j SAMPLE ANALYSES , i : l 3-la,b SOLID WASTE AND IRRADIATED FUEL 51,52 i SHIPMENTS ! 1 i i 1 1 l 1 1 !O l
(! RADIOACTIVE EFFLUEtir RELEASE REPORT 1 LICCID EFFLUEPTPS 1.1. REGULATORY LIMITS
- 1. The Technical Specifications presented in this section are for Unit 1. nequirements for Unit 2 are the same as Unit 1; however, the Technical Specification numbers are not the same.
TECHNICAL SPECIFICATIOtG . 3.14.1 The radioactive liquid effluent monitoring instrunentation channels shown in table 3.14.1-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.15.1 are not exceeded. The alarW 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 UtRESIRICrED j ') AREAS (figure 3.15-1) shall be limited to the V concentrations specified in 10 CFR Part 20, Appendix B, Table II (column 2) for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 uCi/ml total activity. 3.15.1.2 The (%se or dose commitment to a MEMBER OF THE PUBLIC t M radioactive materials in liquid effluents rn eased, frce each reactor unit, frcn the site (figure 3.15-1) snall be limited to:
- a. During any calendar quarter to less than or equal I to 1.5 mrem to the total body and to less than or equal to 5 mrem to any organ.
- b. Durire any calendar War to less than or equal to l 3 mrem to the total body and to less than or equal to 10 mrem to any organ.
3.15.1.3 The liquid radwaste treatment system, as descrited in the 0D04, shall be used to reduce the j radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent per Unit from the site (figure 3.15-1) when ( projected over the calendar quarter would exceed 0.18
\ ]) mrem to the total body or 0.62 mrem to any organ.
1 1 I t lO 3.15.1.4(a) The contents within any outside temporary tank shall be limited to less than or equal j j (/ to 10 curies, excluding tritium and dissolved or i entrained noble gases. . q (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 comected to the liquid radwaste treatment systeA l 6.9.1.9 states in part: "The Radioactive Effluent Release Report shall include (on a quarterly basis) [' i unplanned releases from the site to unrestricted areas of radioactive materials in gaseous and liquid ; effluents that were in excess of I C1, excluding ' dissolved and entrained gases and tritium for liquid ; i effluents, or those in excess of 150 Ci of noble gases .] or 0.02 Ci of radioiodines for gaseous releases". j j 1 i i a ( iO i 4 i 1 l i la i j . s ? I
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TABLE l-1 ; i + TECHNICAL SPECIFICATION i TABLE 3.14.1-1 (SNEST 1 of 2) l LRADICACTIVE LIQUID EFFLUENT ONIERItG INSTRfAENTAT!ON ;
- t i
Minimum Channels Instrument OPERABLE Applicability ACTION l
- 1. Gross Radioactivity '
1 Monitors Providing ! Automatic Termina-tion of Release ' l Liquid Radwaste ! Effluent Line 1 (a) 100 i i
- 2. Gross Radioactivity
- Monitors not Providing ,
! Autcsntic Termination of .
Release - l I Service Water . System Effluent ! Line 1 (b) 101 :
- 3. Flowrate Measure- i ment Devices ** j
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- Liquid Radwaste ,
j Effluent Line 1 (a) 102 l i i i Discharge Canal 1 (b) (a) 102 , I
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- 4. Service Water 1 At all times 103 I i
System to closed , ! Cooling Water l 1 System Differential j Pressure , 1 l i I 6
- **Ptmp curves may be utilized to estimate flow; in such cases, j AcrION statement 102 is not required.
(a) Whenever the radwaste discharge valves are not locked , closed. i l (b) Whenever the service water system pressure is below l l the closed coolirq water system pressure or 6P ] indication is not available. l l 3_ 1 s
TABLE l-1 (CONTINUED) _ 7,i e TECHNICAL SPECIFICATION U TABLE 3.14.1-1 (SHEUP 1 of 2) RADIOACTIVE LICOID EFFLUENP MONI'IORJZ INSTRUMENTATION TABLE NCffATIONS ACTION 100 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requicement, 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. f3 ACTION 101 - With the numbers of channels OPERABLE less than V required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided that once per chift grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a Lower Limit of Detection of at least 10-7 uCi/ml. If the channel remains inoperable for over 30 days, an explanation of the circumstances shall be included in the next semi-annual effluent release report. ACTION 102 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue, provided the flowrate is estimted 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.
CT l V 1.2 MAXIMUM PERMISSIBLE (DNCENIPATIONS I The MPC values used in determining allowable . liquid radwaste release rates and concentrations for principal gama emitters, I-131, tritium, i Sr-89, Sr-90 and Fe-55 are taken from 10CFR Part 20, Appendix B, Table II, Column 2. , 1 For dissolved or entrained noble gases in liquid l radwaste, the MPC is taken from Technical l Specification 3.15.1.1 (Unit 1) and 3.11.1.1 (Unit ,
- 2) as 2.0E-04 tci/ml. , l Por gross alpha in liquid radwaste, the MPC is taken from 10CFR Part 20, Appendix B, Note 2.b as 3.0E-08 uCi/ml. !
l Further, for all the above radionuclides or j categories of radioactivity, the overall MPC fraction is 6etermined in accordance with 10 CPR Part 20, Appendix B, Note 1. The method whereby the MPC fraction is used to determine release rates and 1.iquid radwaste n effluent radiation monitor setpoints is described i in Section 1.3 of this report. 1.3 MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY Prior to release of any tank containing liquid radwaste, and following the required recirculation, samples are collected and analyzed in accordance with Technical Specificat. ion Tables 4.15.1-1 (Unit 1) and 4.11.1-1 (Unit 2) . A sample l from each tank planned for release is analyzed for ! principal gamma emitters, I-131, and dissolved and ; entrained noble gases by gama spectrmetry. Monthly and quarterly composites are prepared for l analysis by extracting aliquots from each sample taken from tanks which are released. Liquid radwaste sample analyses are performed as follows: Measurement F_requency Method
- 1. Gama Isotopic Each Batch Gantra spectroscopy with computerized data reduction 3 2. Dissolved or Each Batch Gamna spectroccopy Entrained with computerized Noble Gases data reduction
Measurement F requency Method -
) 3. Tritium Monthly Distillation and Cmpocite liquid scintillation counting
- 4. Gross Alpha Monthly- Gas Flow Proportional Composite counting
- 5. Sr-89 and Sr-90 Quarterly Chemical separation and Cmposite gas flow propcccional counting
- 6. Fe-55 Quarterly Chemical separation and Composite low energy photon '
detector. l 1 Gamma isotopic measurements are performed in-house in the radiochemistry lab using germanium spectemetry. Three germanium detectors are available: a 25%. I efficient and two 15% efficient intrinsic germ nium ! detectors, with 2.0 EWHM resolution and housed in 4 l
. inch-thick lead shields. A one-liter liquid radwaste sample is poured into a Marinelli beaker in l preparation for a 2000-3000 second count. -A peak !
search of the resulting gamma ray spectrum is l e performed by the cmputer system. Energy and net i % count data for all significant peaks are c'etermincis and quantitative reduction or LLD calculations are performed for the nuclides specified in Table Notation e of Technical Specification Tables 4.15.1-1 (Unit 1) ; and 4.11.1-1 (Unit 2): Mn-54, F-59, Co-58, Co-60, ' Zn-65, Mo- 99, Cs-134, Cs-137, Ce-141 and Ce-144. The quantitative calculations include corrections for counting time, decay time, sanple volume, sanple geometry, detector efficiency, baseline counts, and branching ratio. LLD calculations, including the l above corrections, are made based on the counts in two standard deviations of the baseline count at the location on the spectr e where a peak for that l radionuclide would be located if present. l The radionuclide concentrations determined by gamma spectroscopic analysis of a sample taken from a tank l planned for release and the most current sample analysis results available for tritium, gross alpha, St-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 c'ilution stream flow to calculate a maximum permissible release rate and a liquid effluent i' 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.
A monitor reading in excess of the calculated
\ setpoint therefore results in an automatic
{Q 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 camputer and a postrelease printout is generated. The postrelease printout contain.1 actual release _ rates, actual release concentrations and quantities, actual dilution flow, and calculated A doses to an individual. 1.4 LIQUID EFFLUENT RELEASE DATA Regulatory Guide 1.21 Tables 2A and 2B are found in this report as Table 1-2a for Unit 1, Table 1-2b for Unit 2 and Table 1-2c for the site; /md 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 1-26, 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 reasured individual radionuclide activities. This sum is for each batch released to the river for the respective
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qua rter. Percent of applicable limit is determined from a mixed nuclide MPC fraction (v') calculation. The average concentration for each nuclide over all released batches is divided by the corresponding individual MPC value. The sum over all nuclides of the Ci/MPCi ratios times 100 is the per nt of applicable limit for effluent releases during the quarter.
- 2. Tritium - The measured tritium concentrations in the monthly cmposite samples are used to calculate the total release and average diluted concentration during each period. Average diluted '
concentration divided by the MPC limit, j 3.0E-03 uCi/ml, is converted to percent to ' give the per nt of applicable limit.
- 3. Dissolve 6 and entrained gases -
Concentrations of dissolved and entrained gases in liquid effluents are measured by germanium spectroscopy on a one liter sanple 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 3.1..1.1 and 3.11.1.1 (2.0E-04 uCi/ml) to determine the MPC fraction. The result x100 is the percent of applicable limit for noble gases ! in liquid effluent releases during the ' quarter. Radioisotopes of iodine in any form are also determined during the isotopic analysis for each batch; therefore, a ] separate analysis for possible gaseous forms is not performed because it would not provide additional information.
- 4. Gross alpha radioactivity - The measr. red !
gross alpha concentrations in the monthly composite samples are used to calculate the total release of alpha radioactivity. l (3 V
l I p Other data pertinent to batch releases or 1 1
\, radioactive liquid effluent from both units are l as follows:
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Number of batch releases: 485 Total time period for batch releases: 66,138 minutes Maximum time period for a ) batch release: 247.0 minutes Average time period for batch 4 releases: 136.4 minutes l Minimum time period for a batch release: 10.0 minutes ' Average stream flow during periods I of release of liquid effluent into a flowing stream: 2,758 CFS 1.5 RADIOLOGICAL IMPACT ON MAN CUE 'IO LIQUID RELEASES Doses to an individual, due to radioactivity in l liquid effluent, were calculated in accordance with Technical Specifications 3/4.15.1.2 (Unit 1) and 3/4.11.1.2 (Unit 2) using the methotlogy i presented in the Plant Edwin I. Hatch Of fsite 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 i and Table 1-4b for Unit 2. l
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TABLE 1-2a E. I. HATCH NUCLEAR PLANT - UNIT 1 O SEMIANNUAL EFFLUENT RELEASE REPORT 1987 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES Est. Total Unit' Quarter 3 Quarter 4 Error % A. Fission & Activation Products
- 1. Total release (not including Ci 2.18E-01 5.44E-02 4.6E+01 H-3, gases, alpha)
- 2. Average diluted '
concentration uCi/mi 1.78E-07 5,50E-08 during period
- 3. % of applicable % 1.84E+ 00 6.04E-01 limit B. Tritium
- 1. Total release ci 3.51E+ 00 7.62E+00 3. 7E+01
- 2. Average diluted uCi/ml 2.87E-06 7.70E-06 concentration during period
- 3. % of applicable % 9.57E-02 2.57E-01 limit C. Dissolved and Entrained Gases
- 1. Total release Ci 2.60E-03 1.34E-03 1. 0E+02
- 2. Average diluted UCi/ml 2.13E-09 1.35E-09 concentration during period
- 3. % of applicable % 1.06E-03 6.76E-04 limit D. Gross alpha radioactivity
- 1. Total release Ci 4.14E-08 1.69E-07 1.2E+02 E. Voluna of waste I (prior to i dilution) liters 5.42E+06 4.24E+06 1.0E+01 I l
F. Volume of dilution water used liters 1.22E+09 9.89E+08 1.6E+02 ; D O 1
TABLE l-2b E. I. HATCH tUCLEAR PLANT - UNIT 2 I p SEMIANNUAL EFFLUENT RELEASE REPORT 1987 I ( LICUID EFFLUENTS - SUMMATION OF ALL RELEASES Est. Total Unit Quarter 3 Quarter 4 Error % A. Fission & Activation Products
- 1. Total release (not including Ci 3.89E-02 1. 28E-02 4.7E+01 H-3, gases, alpha)
- 2. Average diluted '
concentration uci/ml 4.02E-08 4.03E-08 during period
- 3. % of applicable % 5.91E+00 4.91E+00 limit B. Tritium
- 1. Total release C1 1. 4 7E+00 8.3 7E-01 3. 7E+01
- 2. Average diluted uCi/ml 1.52E-06 2.63E-06 concentration during period
- 3. % of applicable % 5.05E-02 8.75E-02 limit C. Dissolved and Entrained Gases
- 1. Total release ci 4.19E-02 2.20E-02 1.0E+ 02
- 2. Average diluted uCi/ml 4.32E-08 6.90E-08 concentration during period
- 3. % of applicable % 2.16E-02 3.45E-02 limit D. Gross alpha radioactivity
- 1. Total release ci 3.61E-08 3.35E-08 1. 2E+02 E. Volume of waste (prior to '
dilution) liters 3.33E+06 1.24E+06 1.0E+ 01 1 F. Volume of dilution i water used liters 9.69E+08 3.19E+08 1.6E+02 l I
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TABLE 1-2c
. E. I. HATCH NUCLEAR PLANT - SITE SEMIANNUAL EFFLUENT RELEASE REPORT 1987 LIQUID EFFLUEtTPS - SUMMATION OF ALL RELEASES Est. Total Unit Quarter 3 Quarter 4 Error %
A. Fission & Activation Products '
- 1. Total release (not including Ci 2.57E-01 6.72E-02 4.7E+01 H-3, gases, alpha)
- 2. Average diluted concentration uCi/ml 1.17E-07 5.14E-08 .
during period .
- 3. % of applicable % 3.64E+00 1.65E+00 l limit i B. Tritium
- 1. Total release ci 4.97E+00 8.45E+00 3. 7E+01
- 2. Average diluted UCi/ml 2.27E-06 6.47E-06 concentration i during period
- 3. % of applicable % 7.57E-02 2.16E-01 limit C. Dissolved and Entrained Gases !
- 1. Total release Ci 4.44E-02 2.33E 1.0E+02
- 2. Average diluted uCi/ml 2.03E-08 1.78E-08 concentration during period
- 3. % of applicable % 1.02E-02 8.92E-03 limit D. Gross alpha radioactivity
- 1. Total release ci 7.75E-08 2.03E-07 1.2E+02 E. Volume of waste ,
(prior to i dilution) liters 8.74E+06 5.48E+06 1.0E+01 I F. Volume of dilution water used liters 2.19E+09 1.31E+09 1.6E+02
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TABLE l-3a E. I. HATCH NUCLEAR PLANI - UNIT 1 SEMIANNUAL LIQUID EFFLUENTS RELEASE REIORT 1987* ) (^g Page 1 of 2 : U Continuous Mode ** Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 H-3 Ci 3.51E+00 7.62E+00 1 Na-24 Ci 1.98E-04 3.798-03 , Cr-51 Ci 3.728-05 4.13E-04 l Mn-54 Ci 3.65E-04 9.45E-05 Mn-56 Ci 8.55E-05 1.42E-05 Fe-55 Ci 0.00E+00 0.00E+ 00 . ; Fe-59 Ci 0.00E+00 0.00E+00 Co-58 Ci 3. 26E-05 1.08E-05 Co-60 Ci 1.81E-03 5.34E-04 C u-64. Ci 2. 29E-03 3.59E-04 Ni-65 Ci 0. 00E+ 00 0.00E+00 Zn-65 Ci 5.62E-03 1.30E-03 As-76 Ci .
- 0. 00E+ 00 1.52-04 Sr-89 Ci 4.82E-04 6.78E-04 Sr-90 Ci 0.00E+ 00 0.00E+00 Sr-91 Ci 4.58E-05 0.00E+ 00 i Sr-92 C1 1.1 2 -04 5.87E-06 l Y-91m Ci 0.00E+00 6.36E-04 O
\_/ Zr-95 Ci Ci 0.00E+00 0.00E+00 0.00E+00 l
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Nt>- 95 8.73E-07 i Nb-97 Ci 0.00E+00 7.37E-05 l Mo-99 Ci 3.69E-05 0.00E+ 00 Tc-99m Ci 4.438-04 2.58E-04 I-131 Ci 1.86E-03 5.55E-04 I-132 Ci 9.49E-06 4.78E-06 I-133 Ci 4.91E-04 5. 25E-04 I- 134 Ci 1.85E-05 1.12E-04
. I-135 Ci 6.06E-05 3.21E-05 Cs-134 Ci 8.63E-02 1.56E-02 Cs-136 Ci 1. 44E-04 0.00E+00 l Cs-137 Ci 1.17E-01 2.92E-02 i Cs-138 Ci 0.00E+00 5.4.E-05 l Ba-139 Ci
- 4. 00E-05 0.00E+00 Ba-140 Ci 0.00E+00 0.00E+ 00 La-140 Ci 0.00E+00 0.00E+00 Np-239 Ci 0.00E+00 3.22E-05 Totals C1 2.17E-01 5.4 4E-02 O
1 1 l l TABLE l-3a ! E. I. HATCH NUCLEAR PLANP - UNIT 1 l SEMIANNUAL LIQUID EFFLUENTS RELEASE REPORT 1987* i - (~'s Page 2 of 2
\,.)
Continuous Mode ** Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Kr-85m Ci 0. 00E+00 0. 00E+00 Kr-85 Ci 0.00E+00 0.00E+00 Xe-131m Ci 0. 00E+ 00 0. 00E+00 Xe-133 Ci 3. 37E-04 3.0 2E-04 i Xe-133m Ci 0. 00E+ 00 0.00E+00 l Xe-135m Ci 1.69E-03 0.00E+00 l Xe-135 Ci 5.6 SE-04 1.03E-03 - l A r-41 Ci 0.00E+ 00 3.46E-04 Totals Ci 2.59E-03 1.6 8E-03 Gross Alpha ci 4.14E-08 1.69E-07
- Zeros in this table indicate that no radioactivity was present l above detectable levels. See Table 1-5 for typical lower i limits of detection for liquid sanple analyses.
**There are no continuous mode radioactive liquid release i pathways at Plant Hatch. !
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1
TABLE 1-3b E. I. HATCH NUGEAR ILANP - UNIT 2 SEMIANNUAL LIQUID EFFLUENTS RELEASE REPORT 1987* Page 1 of 2 O, Continuous mde** Batch-Mode Nuclides Released Unit Omrter 3 Quarter 4 Quarter 3 Quarter 4 H-3 Ci 1.63E+00 8.37E-01 Na-24 Ci 1.59E-04 1.76E-04 Cr-51 Ci 3.00E-04 1.222-04 Mn-54 Ci 2.38E-04 1.78E-05 Mn-56 Ci 0. 00E+ 00 1. 28E-05 - Fe-55 Ci 1.33E-03 0.00E+00 Fe-59 Ci 0. 00E+00 0.00E+00 co-58 Ci 2.29E-05 2.76E-05 Co-60 Ci 3.982-04 8.10E-05 Cu-64 Ci 0.00E+00 2.06E-04 Ni-65 Ci 0.00E+00 0.00E+ 00 Zn-65 Ci 1.41E-03 3.16E-04 As-76 Ci 1. 82E-06 1.95E-05 Sr-89 Ci 3.66E-04 6.44E-05 Sr-90 Ci 0.00E+ 00 0.00E+00 St-91 Ci 0.00E+ 00 1.182-05 Sr-92 Ci 0.00E+00 0.00E+00 Y-91m Ci 1.87E-04 3.52E-05 \ Zr-95 Ci 0. 00E+ 00 0.00E+00 Nb-95 Ci 0.00E+ 00 0.00E+00 Nb-97 Ci 3.83E-06 1.27E-05 Mo-99 Ci 0.00E+ 00 0.00E+00 Tc-99m Ci 3.42E-04 5. 43E-04 Tc-131 Ci 3.86E-05 0.00E+00 I- 131 Ci 1.41E-02 3.27E-03 I-132 Ci 7.17E-04 6.84E-04 ,
.I- 133 Ci 8.538-03 4.10E-03 1 I-134 Ci 0.00E+00 7.65E-06 I I-135 Ci 3.088- 03 1.978-03 Cs-134 Ci 2.84E-03 1.80E-04 Cs-136 Ci 8.05E-05 0.00E+00 Cs-137 Ci 4.14E-03 2.84E-04 Ce-138 Ci 0.00B+00 0.00E+00 Ba-139 Ci 1.91E-05 0.00E+00 Ba-140 Ci 0.00B+00 0.00E+ 00 Ce-141 Ci 0.00E+00 0.00E+00 Ce-144 Ci 5. 50E-04 0.00E+00 Np-239 Ci 3.22E-05 0.00E+00 Totals {
Ci 3.898-02 1.21E-02 l l O
i TABLE 1-3b E. I. HATCH NUCLEAR PLANI - UNIT 2 SENIANNUAL LIQUID EFFLUENTS RELEASE REPORT 1987* Page 2 of 2 continuous Mode ** Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Kr-85 Ci 4.15E-04 0.00E+00 Kr-85m Ci 4.92E-06 0.00E+ 00 Kr-87 Ci 0.00E+ 00 1. 38E-05 Xe-131m Ci 1.28E-04 0.00E+00 Xe-133m Ci 4. 36E-04 2.73E-04 Xe-133 Ci 1. 30E-02 5.64E-03 Xe-135m Ci 5.52E-03 2.06E-03 - Xe-135 C1 2.24E-02 1.40E-02 Ar-41 Ci 3.11E-06 0.00B+00 Totals C1 4.19E-02 2. 20E-02 Gross Alpha ci 3.61E-08 3. 35E-08
- Zeros in this table indicate that no radioactivity was present above detectable levels. See Table 1-5 for typical lower limits of detection for liquid sanple analyses.
**There are no continuous mode radioactive liquid release pathways at Plant Hatch.
l l 0
TABLE 1-3c E. I. HATCH NUCLEAR PLAf(P - SITE SEMIANNUAL LIQUID EFFLUENTS RELEASE REIORT 1987* 7 Page 1 of 2 .g Continuous Mode ** Batch Mode tbclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 H-3 Ci 5.14E+ 00 8.45E+00 Na-24 Ci 3.588-04 3.96E-03 Cr-51 Ci 3. 3 7E-04 5.35E-04 Mn-54 Ci 6.03E-04 1.12E-04 Mn-56 Ci 8. 55E-05 2.70E-05 Fe-55 Ci 1.33E-03 0.00E+ 00 - Fe-59 Ci 0. 0E+00 0.00E+00 co-58 Ci 5.58E-05 3.84E-05 Co-60 Ci 2.21E-03 6.15E-04 Cu-64 Ci 2. 29E-03 5.65E-04 Ni-65 Ci 0. 00E+00 0.00E+00 Zn-65 Ci 7.02E-03 1.62E-03 Aa-76 Ci 1. 82E-06 1.70E-04 Sr-89 Ci 8. 48E-04 7. 42E-04 Sr-90 Ci 0. 00E+ 00 0.00E+00 Sr-91 Ci 4.58E-05 1.18E-05 Sr-92 Ci 1.10E-04 5.87E-06 Y-91m C1 1. 87E-04 6.71E-04 (
\
Zr-95 Nb-95 Ci Ci
- 0. 00E+ 00 0.00E+00 0.00E+00 8.73E-07 Nb-97 Ci 3.838-06 8.64E-05 Mo-99 Ci 3.69E-05 0.00E+ 00 It-99m Ci 7.85E-04 8.01E-04 Tc-131 Ci 3.86E-05 0.00E+ 00 I- 131 Ci 1.60E-02 3.83E-03 I-132 Ci 7. 26E-04 6.89E-04 I-133 Ci 9.02E-03 4.63E-03 I-134 Ci 1.85E-05 1.19E-04 I-135 Ci 3.14E-03 2.00E-03 Ce-134 Ci 8.91E-02 1.58E-02 Ce-136 Ci 2.25E-04 0. 00E+00 Ce-137 Ci 1.21E-01 2.94E-02 Ce-138 Ci 0.00E+ 00 5. 41E-05 Ba-139 Ci 5.91E-05 0.00E+ 00 Ba-140 Ci 0. 00E+ 00 0.00E+00 La-140 Ci 0.00E+00 0.00E+00 Ce-141 Ci 0. 00E+ 00 0.00B+ 00 Ce-144 Ci 5,50E-04 0.00E+00 t4>-239 Ci 3.22E-05 7. 24E-04 Totals Ci 2.56E-01 6.71E-02 O
V
TABLE 1-3c E. I. HATCH NUCLEAR PLANP - SITE SD4IANNUAL LIQUID EFFLUEtTTS RELEASE REEORT 1987* Page.2 of 2 U(N Continuous Mode ** Batch Mode Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4 Kr-85m Ci 4.92E-06 0. 00E+ 00 Kr-85 C1 4.15E-04 0.00E+00 Kr-87 Ci 0. 00E+00 1.38E-05 Xe-131m C1 1.28E-04 0.00E+ 00 Xe-133m Ci 4. 36E-04 2.73E-04 Xe-133 C1 1.33E-02 5.94E-03 Xe-135m Ci 7.22E-03 2. 06E-03 - Xe-135 Ci 2. 29E-02 1.50E-02 A r-41 Ci 3.11E-06 3. 46E-06 Totals Ci 4.44E-02 2. 33E-02 Gross Alpha ci 7.758-08 2.03E-07
- Zeros in this table indicate that no radioactivity was present above detectable levels. See Table 1-5 for typical lower limits of detection for liquid sanple analyses.
**There are no continuous mode radioactive liquid release pathways at Plant Hatch.
O
-- , - - - - - --ar . - - --
- - - ,- ,- --,,,.c -- . . - , , -- .---p;e w q
i TABLE 1-4a l E. I. HATCH NUCLEAR PLANP UNIT 1 SEMIANNUAL EFFLUENT RELEASE REPORT 1987 INDIVIDUAL DOSES DUE 'IO LIQUID RELEASES d l Cumulative Dose Per Quarter Organ Tech Units Quarter % of Quarter % of Spec 3 Tech 4 Tech Limit Spec Spec Limit Limit Bone 5.0 mrem 6.58E-01 1.32E+01 1.36E-01 2.72E+00 Liver 5.0 mrem 1.14E+00 2.28E+01 2.28E-01 4.56E+00 T. Body 1.5 mrem 8.41E-01 5.61E+01 1.65E-01 1.10E+01 Thyroid 5.0 mrem 1.16E-02 2.32E-01 3.38E-03 6.76E-02 . Kidney 5.0 mrem 3.80E-01 7.60E+00 7.60E-02 1.52E+ 00 Lung 5.0 mrem 1.26E-01 2.52E+00 2.52E-02 5.04E-01 GI-LLI 5.0 mrem 2.33E-02 4.66E-01 4.81E-03 9.62E-02 Cumul'ative Dose Per Year i Organ Tech Unit Quarters % of Tech Spec 1,2,3,4 Spec Limit : Limit Bone 10.0 mrem 1.57E+00 1.57E+01 ! Liver 10.0 mrem 2. 75E+ 00 2.75E+01 [] Total Body 3.0 mrem 2.02E+00 6. 72E+01 V Thyroid 10.0 mrem 2.42E-01 2. 42E+ 00 i Kidney 10.0 mrem 9.23E-01 9.23E+00 ' Lung 10.0 mrem 2.99E-01 2.99E+ 00 GI-LLI 10.0 mrem 8.61E-02 8.61E-01 l l 1 4 l l O
l TABLE 1-4b E. I. HATCH NUCLEAR PLANT UNIT 2 SEMIANNUAL EFFLUENT RELEASE REPORT 1987 INDIVIDUAL DOSES DUE 'IO LIQUID RELEASES O-Ctznulative Dose Per Quarter Organ Tech Units Quarter % of Quarter % of Spec 3 Tech 4 Tech Limit Spec Spec Limit Limit Bone 5.0 mrem 2.25E-02 4.50E-01 1.66E-03 3. 32E-02 Liver 5.0 mrem 3.92E-02 7.84E-01 2.92E-03 5.84E-02 T. Body 1.5 mrem 2.85E-02 1.90E+00 2.08E-03 1.39E-01 Thyroid 5.0 mrem 9.01E-02 1.80E+ 00 2.36E-02 4.72E-01.
- Kidney 5.0 mrem 1.36E-02 2.72E-01 1.13E-03 2.26E-02 Lung 5.0 mrem 4.24E-03 8.48E-02 3.07E-04 6.14E-03 GI-LLI 5.0 mrem 2.02E-03 4.04E-02 2.34E-04 4. 68E-03 Ctrnulative Dose Per Year f Organ Tech Unit Quarters % of Tech Spec 1,2,3,4 Spec Limit.
Limit Bone 10.0 mrem 1.05E-01 1.05E+00 Liver 10.0 mrem 1.82E-01 1. 82E+00 m Total Body 3.0 mrem 1.33E-01 4. 42E+ 00 10.0 Thyroid mrem 2.60E-01 2.60E+00 Kidney 10.0 mrem 6.22E-02 6.22E-01 i' Lung 10.0 mrem 1.96E-02 1.96E-01 GI-LLI 10.0 mrem 8.13E-03 8.13E-02
)
O
l TABLE 1-5 l INER LIMITS OF DETECTION - LICOID SAMPLE ANALYSES l The values in this table represent apriori lower limits l of detection (LLD) which are typically achieved in laboratory ' analyses of liquid radwaste sanples. i RADIONUCLIDE LLD UNITS Mn-54 5.38E-08 uC1/ml l Fe-59 7.78E-08 , Co-58 4.67E-08 Co 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 1.41E-07 Ce-144 6. 30E-07* I-131 6.51E-08 Xe-135 8.45E-08 Fe-55 8.00E-07 Sr-89 2.30E-08 S r-90 7.67E-09 H-3 5.00E-07
- *In accordance with Technical Specification Tables 4.15.2-1 (Unit 1) and 4.11.1 (Unit 2), Table Notation b, the permissible Lower Limit of Detection may be increased inversely proportional to the magnitude of the gama 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). )
i I l O
2 GASEOUS EFFLUENTS 2.1 REGJLA'IORY LIMITS (O b'j 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 nunbers are not the same. TEQiNICAL SPECIFICATIONS - 3.14.2 The radioactive gaseous effluent monitoring instrumentation channels shown in table 3.14.2-1 shall be OPERABLE with their alardtrip setpoints set to ensure that the limits of Specification 3.15.2.1(a) are not exceeded. The alarWtrip setpoints of these channels shall be determined in accordance with the ODCM. 'Itchnical
- 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 UNRESIRICTED AREAS (figure 3.15-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:
- a. The dose rate limit for noble gases shall be less than or equal to 500 mrevyear to the total body and less than or equal to 3000 mrevyear to the skin.
- b. The dose rate limit for I-131, I-133, tritium, and for all radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than 8 days shall be less than or equal to 1500 mrevyear to any organ.
3.15.2.2 The air dose in UtEESIRICIED AREAS (figure 3.15-1) due to noble gases released in gaseous effluents
. frcun 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
' to 10 mrad for ganma radiation and less than or equal to 20 mrad for beta radiation.
3.15.2.3 The dose to any organ of a MEMBER OF THE WBLIC from I-131, I-133, tritium , and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to UtRESIRICIED AREAS (figure 3.15-1) from each reactor unit shall be limited to the following: O V
- a. During any calendar quartar to less than or !
equal to 7.5 mrem to any organ. m b. During any calendar year to less than or equal to 15 mrem to any organ. 3.15.2.4 The GASECUS RADWASE TREATMENT SYSEM 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 GASSIS RADWASE TREATMENT SYSEM 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 MDIBER OF THE PUBLIC due to releases of radioactivity and to radiation fran uranium fuel ' cycle .murces shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem. (With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.15.1.2(a), 2.15.1.2(b), 3.15.2. 2. (a), 3.15.2. 2(b), 3.15.2. 3(a), or O V 3.15.2.3(b), calculations shall be made including direct radiation contributions from the reactor units and from'outside storage tanks to determine whether the above limits of Specification 3.15.2.5 have been exceeded. 3.15.2.6 The concentration of hydrogen downstream of the recombiners in the main condenser offgas treatment system shall be limited to less than or equal to 4 percent by volume, 1 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 statico 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 Ci, excluding dissolved and entrained gases and trititrn for O liquid effluents, or those in excess of 150 Ci of noble gases or 0.02 Ci of radiciodines for gaseous releases." i j l i
f \ I l i
~
l: . .
,? - -
{, TA8LE 3.14.2-1 (SHEET 1 0F 4) RADlOACTIVE CASrous ErrLUENT MONITORINC INSTRUMENTATION Minimum
' f os t rument Channels .
OPERABLE Aonficability $ Pa rame te r 1 ACTION Main Condenser Orrgas Treatment .
.. . System Explosive Cas Monitoring System I
Hydrogen Monitor (1) '** ,
~
% Hydrogen
- 2. Reactor Building Vent Stack . 106 Monitoring System
$ a. Noble Gas , Activity Monitor (1)
- Radioactivity Rate 105
- 3 b. todine Sampler Cartridge Measurement t >4
- (1)
- Verify Presence or %
m
, c. Particulate Sampler Filter Ca rt ridge 107 (1)
- 7
^ ' Vertry Presence or - 107 d, Filter Erripont System Flovrate Measproment Device (1) *
' . System flovrate 104
- c. Samp'ser rsovrate Haasurement Measurement 8 Device (1) *
- Sampler flowrate 104 3.
Accombiner Dullding Ventf lation Measuremont nonitoring System
- a.
Hoble Cas Activity Monitor (1)
- Radioactivity Rate -105
.\
- b. todine Sampler Cartridge Measuremont +
(1)
- Vertry Presence of
- c. P,articulato Sampler filter Ca rt ridge 107
~ (' t )
- Vertry Presence or 107
- d. Filter Sampler riowrate Hoasurement .
Oovica (1)
- i Sampler finvrate
- 104 Measuromont -
e A e O J J .
t 4 \ U' . i
- i i %
3 TABLE 3.11.2-1 (SHEET 2 Of 8s) . RADIDACTIVE C SEOUS OFFt1ENT @ lTORING INSTRUMENT A T I ON_ _ Hinlosem los t rt**Cnt Channels OPERABtr . gg t f omb f f f iv . 4 Pa rama ta r Main Stack Monitoring System ggy . a. O Noble Gas Activity Monitor
}* (1)
- I
- b. # Radioactivity Rate
. todine Sampler Carteldge Heasurem90t + 10$
(1)
- c. Verify Presence of Particulate Sampler filter .
Ca rt ridge 107 y 4 (1) * .
- c. Effluent System flovrate Verify Presence of -
to e. filter 107 " Heasuring Devices I (1)
- x>
m System flovrato t
- e. ~
y Sampscr flowro to Hamsuring Device (1)
- Measurement 108s e
S. Sampler riovrate 9 ! Condenser Offgas Progreatment rwnitor Measurement 1 08: ' 3 i
- cb' sr t4able cas Activity Honitor
* (1) ...
Radioactivity Rate IOS
- Hes suromont 9
i . 4
*e
- e 9
h . . w 1 . 4 i . I . .* f
'of .
TABLE 2-1 (Cont'd) - TABLE 3.14.2-1 (SNEET 3 0F 4) RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTR _ Table Nota tions I
+Detection Monitor must be capable of I x 10-* pC1/ml. of responding to a Lower Limit of i
*During releases via this pathway.
**0uring main condenser offgas treatment system operation .
""*0uring operation of the main condenser air ejector.
ACTION 104 - With the number of channels OPERABLE less required by the Minimum Channels OPERABLE requirement, . effluent releasei via this pathway may continue, provided the flowrate is estimated at least once per 4 hours . If the number of channels OPERABLE remains less than required by the Minimum Channels OPERA 8LE requireme'nt for over 30 days, an explanation of the circumstances shall be i included in the next semi-annual effluent release report . t
' ACTION 105 - With the number of channels OPERA 8LE l required by the Minimum Channels OPERA 8LE requirement, grab samples are taken daily and analyzed daily fo activity within 24 hours.
With the number of main stack monitoring system channels OPERABLE less than required by suspend drywell purge.the Minimum Channels OPERA 8LE require
' .If the number of channels OPERABLE remains les required by the Minimum Channels OPERA 8LE requirement for n
over 30 days', 'an explanation of the circumstances shall be included in.the next semi-annual effluent release report . ACTION 106 - With the number of channels OPERA 8LE less required by the' Minimum Channels OPERA 8LE requirement, operation continue provided: of the main condenser offgas treatment system may (a) within the ensuing 4 hours, orGas samples are collected once (b) offgas system line downstrean of the recombiner,U hydrogen every 4 hours. concentration r,eadings are taken and logged i j O 1 _26. ?
- e ws
, - - - - - , - , . , - . , , , . . - . - . . - . . - ~ - - . , - , . . . . , - , - - - - . - - . - - . - - - - - - - - -
s \ TABLE 2-1 (Cont'd) TABLE 3.14.2-1 (SHEET 4 0F 4) RADIOACTIVE GASEOUS EFFLUENT HONITORING INSTROMENTATIO I Table NotatiotLs (Continued)
. . l l
If the number of channels OPERABLE remains less than f required by the Minimum Channels OPERA 8LE requirement for ) over 30 days, an explanation of the circumstances shall be -
)
included in the next semi-annual effluent release report. ACTION 107 - Vf th tn' e number of channels OPERABLE less than ' required by the Minimum chanels OPERABLE requirement, ( ' effluent releases via tbk pathway may continue, provided saaples are continuously
>11ected with auxiliary sampilng equipment for periods on the order of 7 days and analyzed 'i within 48 hours ,after the end of the sampling period.
- If the number of channels OPERABLE remains less than required by the Minimum Chant 1's OPERABLE requirement for over 30 days, an explanation tet the circumstances shall be j included in the next semi-annual effluent release report. ,
j ACTION 108 - With the number of channels OPERA 3LE less than ' required by the Minimum Channels OPERABLE requirement, provided:to the environment may continue for up to 72 hours release , i I ( a. i The offgas system is not bypassed, and
- b. . !
The offgas post-treatment monitor (011-K615) or the main , stack monitor (DieK600) is OPERABLE. - Otherwise, be in at least NT STAN08Y within 12 hours. If the n' umber of channels OPERABLE remains less than -- required by the Minimum Channels OPERAB.LE requirement for , over 30 days, an explanation of the circumstances shall be included in the next semia annual effluent release report. l t. l ) O O
.~ *
..' v.
. 27
l i 2.2 MEASUREMENT AND APPROXIMATIONS OF 'IOTAL RADIOACTIVITY Waste gas release at Plant Hatch is confined to four paths: main stack (also called the offgas vent), Unit 1 reactor building vent: Unit 2 reactor building vent, and the recombiner building vent. Each of these four paths is continuously monitored for gaseous radioactivity. Each is equipped with an integrating-type sample collection device for collecting particulates and iodines. Sample collection is in accordance with Technical
- Specification Tables 4.15.2-1 (Unit 1) and 4.11.2-1 (Unit 2) . Unless required more frequently under certain circumstances specified '
in Table Notations to the above mentioned tables, umples are collected as follows:
- 1. Noble gas sanples are collected by grab sampling monthly.
2 Tritium sanples are collected by grab sanpling monthly. ' 3 Radiciodine sanples are collected Py pulling the sample stream through a charcoal cartridge over a 7-day period.
- 4. Particulates are collected by pulling the sanple stream through a partiei'.s filter over a 7-day period.
- 5. The 7-day particulate filters above are analyzed for gross alpha activity.
- 6. Quarterly emposite sanples are prepared from the particulate filters collected over the previous quarter and the quarterly cmposite sample is analyzed for Sr-89 and S r-90.
Sanple analyses results and release tiow rates from the four release points form the basis for calculating released quantities of radionuclide-spee!'ic radioactivity, dose rates associated with gaseous releases, and cumulative doses for the current quarter and year. This t.at:t is norn. ally performed with conputer assistance. . O
..a .
The noble gas grab sanple analysis results are used along with maximum expected release flow p rates from each of the four vents to calculate g 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 monitor setpoints is described in the Plant Hatch ODCM. With each release period released radioactivity, dose rates, and cumulative doses are calculated. Cumulative dose results are tabulated along with percent of Technical Specification li.dts , (3.15.2.2 and 3.15.2.3 (Unit 1): 3.11.2.2 and 3.11.2.3 (Unit 2) for each release, for the current quarter and year. After each calendar quarter (13 weeks) a sumary of waste gas releases from the four vents is empiled for preparation of the Semiannual Effluent Release Report required by Technical Specifications 6.9.1.8 and 6.9.1.9 and described in tRC Regulatory Guide 1.21. The methods for determining released quantities of ' radioactivity, dose rates and cumulative doses are as follows:
- 1. FISSION AND ACI'IVATION GAS The radionuclide-specific released radioactivity is determined fem sanple analyses results collected as described above and average release flow rates over the period represented by the collected sarnple.
Instantaneous dose rates due to noble gases and due to radioiodines, triti m , and particulates are calculated (with conputer assistance). Calculated dose rates are empared to the dose i rate limits specified in 3.15.2.1.a (Unit 1) and 3.11.2.1.a (Unit 2) for noble gases; and 3.15.2.1.b (Unit 1) and 3.11.2.1.b (Unit 2) for radioiodine, tritium, 'sd particulates. Dose rate calculation methodolv3y is presented in the Plant Hatch ODCM. l i O
Beta and gama air doses due to noble gases are calculated for the location in the unrestricted (q
'j area with the potem ial for the highest exposure due to gaseous releases. Air doses are calculated for each celease period and cumulative totals are kept for e sch unit for the current calendar quarter and , ear. Cumulative air doses are compared to the dose limits specified in Technical Specifications 3.15.2.2 (Unit 1) and 3.11. 2. 2 ( Uni t 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 GXN.
- 2. RADIOIODINE, 2RITILM, AND PARTICULATE RELEASF .
Released quantities of radioiodines are determined from the weekly samples and release flow rates for the four release points. Radioiodine concentrations are determined by gama spectroscopy. Released quantities of particulates are determined from the weekly (filter) samples and release flow rates fcr the four release points. Gamma spectroscopy is used to quantify concentrations of principal gama emitters. After each calendar quarter the particulate Os filters from each vent are combined, fused, and strontium separaticn is performed. Since sample flows and vent flows are almost constant over each quarterly period the filters frcen each vent can be dissolved together. Decay corrections are made back to the middle of the quarterly collection period. Where significant Sr-89 or
~ Sr-90 is not detected, LLD's are calculated.
Strontium concentrations are input to the ccrnposite file of the computer to be used in release, dose rate and individual dose calculations. Tritium sa@les are obtained monthly frca 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 collecticn efficiencies. The tritium samles 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. comuter to be used in release, dose rate, and individual O dose calculations.
I l Il Dose rates due to radioiodine, tritium, and particulates are calculated for a hypothetical h child, exposed to the inhalation pathway, at the location in the unrestricted area where the potential dose rate is expected to be the highest. Dose rates are calculated for each release point, for each release period, and the total dose rate from all four release points are ! compared to the dose rate limits specified in Itchnical Spedftcations 3.15.2.1.b (Unit 1) or < 3.11.2.1.b (Unit 2). l Individual A s due to radioiodine, tritium, and particulates are calculated for the critical receptor, which for Plant Hatch is a child . exposed to the garden vegetation, inhalation, and ; ground-plane pathways. Individual doses are i calculated for each release period and cumulative totals are kept for each unit for the current ! I calendar quarter and year. Cumulative individual ' doses are canpared to the dose limits specified ; in Technical Specifications 3.15.2.3 (Unit 1) and l 3.11.2.3 (Unit 2) . Current percent of technical specification limite are shown on the printout for each release period. i I
- 3. GROSS ALPHA RELEASE The gross alpha release is computed each month by counting the particulate filters each week for gross alpha activity in a proportional counter.
The four or five weeks' numbers are then recorded on a data sheet and the activity is sumed at the end of the month. This concentration is input to the canposite file of the computer and is used
, for release calculations.
- 4. ERROR ESTIMATES Regulatory Guide 1.21 requires that estimated i total error in analysis techniques be reported.
These estimates are required for the total fission and activation gas release, total I-131 re W ae, total particulates with half-lives i greater than 8-day release, and total tritium release, i V
"The totEl or eximum crror associct;d with tha effluent measurement will include the cumulative errors resulting from the total operation of sampling and measurement. Because it my be very h) v 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 mterials released in liquid and gaseous effluents and solid waste."
Estimated errors are based cn errors in counting equipnent calibration, counting statistics, vent flow rates, vent sample flow rates, norrsteady release rates, chemical yield factors, and sanple 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 204 1M
' (2) I-131 Release was calculated from each weekly sanple:
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 frce sanple analysis results and release point flow rates. 4 Statistical Error at LLD concentration 60% Counting Equipment Calbration 10% ; Vent Flow Rates 104 Vent Sample Flow Rates 10% l Non-Steady Release Rates 10% ' Wt i I I
_ __. _,._.__ _. . _ . ~
._- . _ q __ . __ - .. ...-- . _ . _ .
i 4 I h- ~ l i (4) Total Tritium Release'was dominated .by the ,
- ' reactor building vent tritium releases hence, the 3 larger statistical = errors of the off-gas vent and 1' (reccabiner building vent tritium releases do not.
affect the error in the total. tritium release: , i Water Vapor in Sample Stream Determination' 104. Vent Flow Rates lot '! counting Calibration and Statistics Non-Steady Release.
- 10%
- 504-l E !
i 4 2.3 GASB00S EFFLUENT RELEASE DATA Regulatory Guide 1.21 Tables 1A, IB,- and 1C are found ,
, in this report as Tables 2-2a-c, 2-3a-c, and 2-4a-c. ';
Data are presented on a quarterly basis as required by Regulatory Guide 1.21. - ~ l 7 To ecmplete Tahics 2-2a-c, total release for each of - the four categories (fission and activation gases; t iodines; particulates; ad tritium) was divided by the i number of seconds in the quarter to obtain a release j j rate in uCi/second for each category. ! i However, the applicable Technical Specification limits ! are not in terms of rr;1 ease rate in uCi/second but in i
\
terms of dose rate in areWyear, as presented in ! Technical Specifications 3.15.2.1. (Unit 1) and j 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 , i
- three categories (tritita, radioiodines, and l j
particulates) 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 ! j 3.11.2.1 are site limits, not unit limits. Dose rates l l due to noble gas releases and due to radiciodine, ; j~ tritita, and particulates are presented in Table 2-5 '
- along with percent of technical specification limits.
Gross alpha radioactivity is reported in Tables 2-2a, 2-2b, and 2-2c as curies released in each quarter.
- Limits for cumulative beta and gamma air doses, due to i
noble gases, are specified in Technical Specifications 3.15.2.2 (Unit 1) and 3.11.2.2 (Unit 2). These limits 3 are unit limits. Cumulative air doses are presented in Tables 2-6a and 2-6b, along with percent of j technical specification limits. ! l i !O j !
Limits for cumulative individual doses, due to radioiodine, tritium, and particulates, are specified O in Technical Specifications 3.15.2.3 (Unit 1) and 3.11.2.3 (Unit 2). These limits a're also unit limits. Cumulative is.ciddua2 doses are presented in Tables 2-7a and 2-7b, with Pr cent of technical specification limits. 2.4 RADIOLOGICAL IMPACT DUE 'IO GASBJUS 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, triti m , and particulates in gaseous releases were calculated in accordance with Technical Specifications 3/4.15.2.1.b (Unit 1) and 3/4.11.2.1.b (Unit 2) . These results are also in Table 2-5. Cumulative air doses due to noble gas releases were calculated for each unit in accordance with Technical Specification 3/4.15.2.2 (Unit 1) and 3/4.11.2.2 (Unit 2). These results are presented in Tables 2-6a and 2-6b. C aulative doses to an individual due to radiciodine, tritium , and particulates were calculated for each 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. l Dose rates and doses were calculated using the methodology preser.ted in the Plant Hatch Offsite Dose calculation Manual. 4 1 1 I I d O l
TABLE 2-2a E. I. HATCH NUCLEAR PLANP - UNIT 1 i SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1987 GASEDUS EFFLUENIS - SUMMATION OF ALL RELEASES i E. I. Hatch Unit Quarter Quarter Est. Total Nuclear Plant 3 4 Error % A. Fission & Activation Gases
- 1. Total Ci 4. 65E+ 03 1.69E+03 1.00E+02 Release
- 2. Average uCi/sec 5.85E+ 02 2.13E+02 Release Rate For '
Period
*3. % of Tech %
Spec Limit B. Iodines
- 1. Total Ci 1. 28E-01 8.64E-02 1.10E+02 Iodine-131
- 2. Average uCi/sec 1.62E-02 1. 09E-02 Release Rate For Period
*3. % of Tech %
Spec Limit C. Particulates
- 1. Particulates Ci 2.11E-03 5.63E-03 1.00E+02 with half-lives 8 days
- 2. Average uCi/sec 2.66E-04 7.06E-04 Release Rate For
- Period
- 3. % of Tech %
Spec Limit t
- 4. Gross Alpha Ci 2.53E-06 4.62E-06 Radioactiv-ity 1 D. Tritium i 1. Tctal Ci 2.97E+00 3. 42E+00 9.00E+ 01 Release {
- 2. Average uCi/sec 3.73E-01 4,31E-01 Release Rate For Pericxl
*3. % of. Tech %
Spec. Limit $O V
- Technical Specification limits are in terms of dose rate !
hweWyr) and dose (mrem). See Tables 2-5, 2-6a, 2-6b, 2-7a, and 2-7b. l
TABLE 2-2b E. I. HATCH NUCLEAR PLANT - UNIT 2 SENIANNUAL RADIOACTIVE EFFLUENT RELEASE REIORT 1987 CAVOUS EFFLUENTS - SUMMATION OF ALL RELEASES E. I. Hatch Unit Quarter Quarter Nuclear Plant Est. Total 3 _ 4 Error % A. Fission & Activation Gases
- 1. Total Ci 3.79E+03 5.35E+03 Release 1.00E+02
- 2. Averaga uCi/sec 4.77E+ 02 6.73E+02 Release Rate For ,
Period
*3. % of Tech %
Spec Limit B. Iodines
- 1. Total Ci 4.94E-02 3.62E-02 1.10E+02 Iodine-131
- 2. Average uCi/sen 6.21E-03 4.56E-03 Release Rate For Period
*3. % of Tech %
Spec Limit i l C. Particulates
- 1. Particulates C1 1.522-03 3.26E-03 with half- 1.00E+02 lives 8 days
- 2. Average uCi/sec 1.93E-04 4.10E-04 ,
Release ! Rate For Period
*3. % of Tech 's Spec Limit
- 4. Gross Alpha C1 1.69E-06 1.20E-06 Radioactiv-ity D. Tritium
- 1. Total C1 1.20p 01 1. 49E+ 01 Release 9.00E+01 y
- 2. Average UCi/sec 1.51E+00 1.88E+00 Release Rate For Period
*3. % of Tech % I Spec Limit l I
- Technical Specification limits are in terms of dose rate s
(mreWyr) and dose (mrem). See Tables 2-5, 2-6a, 2-6b, 2-7a, and 2-7b.
l TABLE 2-2c E. I. HATCH NUCLEAR PLANP - SITE SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1987 l GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES I O E. I. Hatch Unit Quarter Quarter Est. Total Nuclear Plant 3 4 Error % A. Fission & Activation Gase.s
- 1. Total Ci 8.44E&O3 7.04E+03 1.00E+02 Release
- 2. Average uCi/sec 1.06E+03 8.86E+02 Release ,
Rate For Period
*3. % of Tech %
Spec Limit B. Icdines
- 1. Total Ci 1.78E-01 1.23E-01 1.10E+02 Iodine-131
- 2. Average uCi/sec 2.24E-02 1.54E-02 Release Rate For Period
*3. % of Tech %
O Spec Limit b
- 7. Particulates
- 1. Particulates Ci 3.65E-03 8.89E-03 1.00E+02 with half-lives 8 days
- 2. Average uCi/sec 4.59E-04 1.12E-03 '
Release Rate For Period
*3. % of Tech %
Spec Limit
- 4. Gross Alpha Ci 4. 23E-06 5.83E-06 Radioactiv-ity D. Tritium
- 1. Total Ci 1.50E+01 1.84E+01 9.00E+01 Release
- 2. Average uCi/see 1.88E+ 00 2.31E+00 i Release Rate For l Period
*3. % of Tech %
Spec Limit O j l
- Technical Specification limits are in terms of dose rate (mreWyr) and dose (mrem). See Tables 2-5, 2-6a, 2-6b, 2-7a, and 2-7b.
T/.3LE 2-3a E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REIORT 1987 GASEDUS EFFLUENTS - ELEVATED RELEASE
- Continuous Mode Batch Mode **
Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4
- 1. Fission Gases Kr-85 Ci 0.00E+00 0.00E+ 00 K r-85m Ci 5.85E+01 7.37Ev01 Kr-87 Ci 2. 32E+01 3.26E+01 Kr-88 Ci 8.22E+01 0.00E+00 '
Xe-133 Ci 1.50E+03 9.96E+02 i Xe-135 Ci 9.81E+02 3.22E+01 Xe-135m Ci 2.40E+02 5.87E+01 Xe-138 Ci 2.55E+01 8.31E+01 Xe-131m Ci 3.66E+01 0.00E+00 Xe-133m Ci 6.60E+01 3.28E+00 Xe-137 Ci 0.00E+00 0.00E+00 A r-41 Ci 7.29E-01 0.00E+00
'ICIAL FOR PERIOD Ci 3.02E+03 1.38E+03
- 2. Iodines '
I-131 C1 1.64E-02 3.52E-04 I- 133 Ci 1.87E-02 4.21E-04 I-135 Ci ~ 8.30E-03 0.00E+ 00
'ICIAL JOR PERIOD ,
Ci 4.34E-02 7.73E-04 _
- 3. Particu-lates c r-51 Ci 0.00E+00 0.00E+00 -
! Mn-54 Ci 0.00E+00 0.00E+00 Co-58 Ci 1.15E-07 0.00E+00 Co-60 Ci 3.88E-07 0.00E+00 '
- Zn-65 Ci 0.00E+00 0.00E+00 Sr-89 Q 6.54E-05 2.54E-05 Sr-90 C1 2.67E-07 9.30E-08 Nb-95 ti 0.00E+00 0.00E+00 Cs-134 Ci 1. 06E-06 1.16E-07 Cs-137 Ci 3.59E-06 6.94E-06 :
Ba-140 Ci 6.06E-05 5.95E-04 La-140 Ci 3.85E-05 5.08E-06
'IOrAL 10R PERIOD Ci 1.70E-04 4.36E-05 i
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses. '
"There are no batch mode radioactive gaseous release pathways at Plant Hatch.
TABLE 2-3b E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL i OIOACTIVE EFFLUENT RELEASE REPORT 1987 GASDX.3 EFFLUENTS - ELEVATED RELEASE
- Continuous Mode Batch Mode **
Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4
- 1. Fission Gases Kr-85 Ci 0.00E+00 0.00E+ 00 Kr-85m Ci 4.47E+01 6.78E+01 Kr-87 Ci 2.01E+01 2.99E+01 K r-88 Ci 6.79E+01 9.57E+01 '
Xe-133 Ci 7.78E+02 9. 66E+02 Xe-135 Ci 3.50E+02 2.92E+01 Xe-135m Ci 9.68E+01 5.34E+01 Xe-138 Ci 2.55E+01 7.78E+01 l Xe-131m Ci 3. 66E+01 0.00E+00 Xe-133m Ci 3.46E+01 2.97E+00 ' Xe-137 Ci 0.00E+00 0.00E+00 A r-41 Ci 7. 29E-01 7.39E-01
'IOIAL FOR l
PERIOD Ci 1.45E+03 1.32E+03
- 2. Iodines I-131 Ci 4.70E-03 3.45E-04 I-133 Ci 8. 83E-03 4.18E-04 I-135 Ci 4.94E-03 0.00E+ 00 TOTAL FOR PERIOD Ci 1.85E-02 7.63E-04
- 3. Partico-lates cr-51 Ci 0.00Et00 0.00E+00 I i Mn-54 Ci 0.00E+ 00 0.00E+ 00 Co-58 Ci 1. 27E-08 0.00E+00 Co-60 Ci 3.88E-07 0.00E+ 00 2 n-65 Ci 0. 00E+ 00 0.00E+00 i
Sr-89 Ci 4.88E-05 2.33E-05 Sr-90 Ci 1.99E-07 8.54E-08 Nb-95 Ci 0.00E+00 0.00E+ 00 Cs-134 Ci 7. 72E-07 1.16E-07 Cs-137 Ci 2.96E-06 6.85E-06 Ba-140 Ci 5.3 9E-05 5.63E-06 La-140 Ci 3.52E-05 4.94E-06 IUIAL EOR PERIOD C1 1.42E-04 4.09E-05 i
- Zeroes in this table indicate that no radioactivity was present
! above detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses.
, **There are no batch mode radioactive gaseous release pathways at a Plant Hatch. l
l TABLE 2-3c E. I. HATCH NUCLEAR PLAfff - SITE SENIANNLIAL RADIOACTIVE EFFLUEffr RELEASE PIPORT 1987 GAS 900S EFFLUEffrS - ELEVATED RELEASE
- Continuous Mode Batch Mode ** l Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4
- 1. Fission Gases K r-85 Ci 0.00E+00 0. 00E+00 Kr-85m Ci 1.03E+ 02 1.42E+02 Kr-87 Ci 4.32E+01 6.2SE+01 '
Kr-88 Ci 1.50E+ 02 2.00E+02 Xe-133 Ci 2.28E+03 1.96E+03 Xe-135 Ci 1. 43E+ 03 6.14E+01 Xe-135m Ci 3.37E+02 1.12E+02 Xe-138 Ci 5.10E+01 1.61E+02 Xe-131m Ci 7.31E+01 0.00E+00 Xe-133m Ci 1.01E+02 6. 25E+ 00 Xe-137 Ci 0.00E+00 0.00E+00 A r-41 Ci 1. 46E+ 00 1.48E+00
'IUIAL FOR PERIOD Ci 4.47E+03 2.71E+03
- 2. Iodines I-131 Ci 2.11E-02 6.97E-04 !
I-133 Ci 2.75E-02 8.39E-04 ' I-135 Ci 1.32E-02 0.00E+ 00
'ICIAL FOR
_ PERIOD Ci 6.19E-02 1.54E-03 1 3.' Partico- I lates 4 Cr-51 Ci 0.00E+00 0.00E+00 Mn-54 Ci 0.00E+00 0.00E+ 00 Co-58 Ci 1.27E-07 0.00E+ 00 Co-60 Ci 7.76E-07 0.00E+00 Zn-65 Ci 0.00E+ 00 0.00E+00 St-89 C1 1.14E-04 4.87E-05 l Sr-90 Ci 4. 66E-07 1.78E-07 Nb-93 Ci 0.00E+00 0.00E+00 Cs-134 Ci 1.84E-06 2.31E-07 Cs-137 Ci 6.55E-06 1.38E-05 Ba-140 Ci 1.14E-04 1.16E-05 La-140 Ci 7.37E-05 1.00E-05 , , 'IUIAL FOR I PERIOD Ci 3.12E-04 8.452-05
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical lower limits of de'.ection for gaseous sanple analyses. ,
l l **There are no batch mode radioactive gaseous release pathways at j Plant Hatch. -- ____ --. . _ - - . - - -
TABLE 2-4s E. I. HATCH NUCLEAR PLANT - UNIT 1 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1987 GASEOUS EFFLUENTS - CROUND-LEVEL RELEASES *
\
Continuous Mode Batch Mode ** Nuclides , Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4
- 1. Fission Gases Kr-85 Ci 0.00E+00 0.00E+00 Kr-85m Ci 7.18E+01 7.22E+00 Kr-87 Ci 1.06E+02 6.41E+01 Kr-88 Ci 1. 29E+ 02 0.00E+00 Xe-133 Ci 6.39E+02 3.82E+01 Xe-135 Ci 3.32E+02 1.11E+02 Xe-135m Ci 2.13E+02 4.29E+01 Xe-138 Ci 1.42E+02 4.14E+01 Xe-131m Ci 0. 00E+ 00 0.00E+00 Xe-133m Ci 0.00E+00 0.00E+ 00 Xe-137 Ci 0.00E+00 0.00E+00 '
Ar-41 Ci 0.00E+00 0.00E+00
'IDIAL FOR PERIOD Ci 1.63E+03 3.04E+02 1 2. Iodines ,
I-131 C1 1.12E-01 8.61E-02 I-133 Ci 3.16E-01 1. 44E-01 I-135 Ci 2.84E-01 1.26E-01 j
'IUIAL FOR PERIOD Ci 7.12E-01 3.56E-01 3.'Particu-lates i Cr-51 C1 2.78E-05 6.34E-04 Mn-54 Ci 3.14E-05 3.54E-05 Co-58 Ci 3.15E-06 8.57E-05 Co-60 Ci 0.91E-06 1.93E-04 Zn-65 Ci 6.18E-05 8. 29E-04 St-89 Ci 6.99E-04 2.01E-03 Sr-90 Ci 1.16E-06 2.71E-06 l Nb-95 Ci 0.00E+00 0.00E+00 !
- Cs-134 Ci 6.49E-05 0.00E+00 Ce-137 Ci 9.56E-05 1.91E-05 Ba-140 Ci 5. 40E-04 9.31E-04 I La-140 Ci 4.07E-04 8.48E-04 l
'IUTAL FOR PERIOD Ci 1.94E-03 5.59E-03 i
O
- Zeroes in this table indicate that no radioactivity a s present above detectable levels. See Table 2-8 for typical lower limits of i detection for gaseous sample analyses.
**There are no batch mode radioactive gaseous release pathways at Plant Hatch. _43,
_ _ _ .- _ _ _ _ . _ _ _ - . - _ ~ . - -
TABLE 2-4b E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1987 GASB00S EFFLUENIS - GROUND-LEVEL RELEASES
- Continuous Mode Batch Mode **
Nuclides Released Unit Ouarter 3 Quarter 4 Quarter 3 Quarter 4
- 1. Fissicn Gases Kr-85 Ci 0. 00E+ 00 0.00E+00 Kr-85m Ci 3.86E+02 7.96E+01 K r-87 Ci 7.18E+01 2.09E+02 -
Kr-88 Ci 4.74E+01 1.67E+02 Xe-133 Ci 4.94E+02 2.12E+02 1 Xe-135 Ci 4.56E+02 6.17E+02 Xe-135m Ci 3.47E+02 8.79E+02 Xe-138 Ci 2.60E+02 8.05E+02 Xe-131m Ci 0.00E+00 0.00E+00 Xe-133m Ci 7.20E+00 0.00E+ 00 Xe-137 Ci 2.68E+02 1.06E+03 A r-41 Ci 0.00E+00 0.00E+00 ,
'IDIAL FOR PERIOD Ci 2.34E+03 4.03E+03
- 2. Iodines I-131 Ci 4.47E-02 3.59E-02 ;
I-133 Ci 8.39E-02 6.20E-02 I-135 Ci 6.79E-02 4.96E-02 , 'IOrAL EOR PERIOD Ci 1.96E-01 1.47E-01 I 3'. Particu-lates Cr-51 Ci 0.00E+00 0. 00E+00 Mn-54 Ci 3.34E-05 1.07E-06 Co-58 Ci 0.00E+00 0.00E+00 Cc>-60 Ci 0.00E+00 0.00E+ 00 Zn-65 Ci 1.74E-05 2.58E-05 St-89 Ci 5.88E-04 1.84E-03 Sr-90 Ci 1. 09E-06 2.03E-06 Nb-95 Ci 0.00E+00 3.72E-06 Cs-134 Ci 5.01E-06 0. 00E+ 00 Cs-137 Ci 2.32E-05 3.55E-05 Ba-140 Ci 4.43E-04 7.68E-04
- La-140 Ci 2.81E-04 5. 39E-04
'IDIAL FOR
- PERIOD Ci 1. 39E-03 3.22E-03
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses.
**There Plant are no batch made radioactive -gaseous Hatch. 2- release pathways at
TABLE 2-4c E. I. HATCH NUCLEAR RANT - SITE SENIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1987 q GASB00S EFFLUENTS - GOUND-LEVEL RELEASES
- Continuous Mode Batch Mode **
Nuclides Released Unit Quarter 3 Quarter 4 Quarter 3 Quarter 4
- 1. Fission Gases Kr-85 Ci 0.00E+00 0.00E+00 Kr-85m Ci 4.58E+02 8.68E+01 Kr-87 Ci 1.78E+02 2.73E+02 Kr-88 Ci 1.76E+02 1.67E+02 '
Xe-133 Ci 1.13E+03 2.50E+02 Xe-135 Ci 7.88E+02 7.28E+02 Xe-135m Ci . 5.60E+02 9.21E+02 Xe-138 Ci 4.02E+ 02 8.47E+02 Xe-131m Ci 0. 00E+ 00 0.00E+00 Xe-133m Ci 7. 20E+ 00 0.00E+ 00 Xe-137 Ci 2.68E+02 1. 06E+03 A r-4: ci 0.00E+00 0.00E+00 7UIAL cve. PERIOD Ci 3. 97E+ 03 4.33E+03
- 2. Iodines I-131 C1 1.57E-01 1.22E-01 I- 133 Ci 4.00E-01 2.06E-01 I-135 Ci 3.52E-01 1.75E-01 j ICIAL POR
- PERIOD Ci 9.09E-01 S.04E-01 1 3. Particu-lates Cr-51 Ci 2.78E-05 6.34E-04 Mn-54 Ci 6.48E-05 3.65E-05 Co-58 Ci 3.15E-06 8. 57E-05 Co-60 Ci 8.91E-06 1.93E-04 Zn-65 Ci 7. 93E-05 8.55E-04 i Sr-89 C1 1. 29E-03 3.85E-03 l Sr-90 Ci 2.25E-06 4.74E-06 Nb-95 !
Ci 0.00E+00 3.72E-06 I Cs-134 Ci 6.99E-05 0. 00E+ 00 l Cs-137 Ci 1.19E-04 5.46E-05 i Ba-140 Ci 9. 83E-04 1.70E-03 La-140 Ci 6.88E-04 1.39E-03 70rAL FOR PERIOD Ci 3.33E-03 8.81E-03 I
- Zeroes in this table indicate that no radioactivity was present above detectable levels. See Table 2-8 for typical lower limits of detection for gaseous sample analyses.
**There are no batch mode radioactive gaseous release pathways at Plant Hatch. _ _ - . ___ __ _ -_. -
TABLE 2-5 E. I. HATCH NUCLEAR PLANT - SITE SEMIANtUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1987 GASEDUS EFFLUENTS - DOSE RATES O
, Dose Pates Due to Noble Gases Organ Tech Unit Quarter % of Quarter % of Spec 3 Weh 4 Tech Limit Spec Spec Limit Limit Total 500 mreWyr 1.23E+01 2.46E+00 1.84E+ 01 3.68E+00 Body Skin 3000 mreWyr 2.48E+01 8.26E-01 4. 41E+ 01 1.47E+00 ,
Dose Rates Due to Radioiodine, Tritium, and Particulates l Organ Tech Unit Quarter % of Quarter % of Spec 3 Tech 4 Tech Limit Spec Spec Limit Limit Bone 1500 mreWyr 1.62E-02 1.08E-03 1.29E-02 8.62E-04 Liver 1500 meeWyr 3.46E-02 2.31E-03 3.51E-02 2.34E-03 Total 1500 mreW yr O Body Thyroid 1500 Kidney 1500 2.57E-02 1.71E-03 2.97E-02 1.98E-03 mreW yr 4.32E+00 2.88E-01 2.95E+00 1.96E-01 mreWyr 4. 52E-02 3.01E-03 4.19E-02 2.79E-03 Lung 1500 mreWyr 2.30E-02 1.54E-03 3.91E-02 2.61E-03 GI-LLI 1500 mreW yr 2.12E-02 1.41E-03 2.71E-02 1.81E-03 l 1 t l i I l iO 4 _ q . .. -
TABLE 2-6a i E. I. HATOI NUCLEAR PLANT - UNIT 1 O SEMIANNUAL RADIOACIIVE EFFLUENT RELEASE REPORT 1987 AIR DOSES DUE TO NOBIE GAS RELEASES Cumulative Doses Per Quarter " Type %ch Unit Quarter 4 of Quarter 4 of of Spec 3 Nch 4 hch Radi- Limit Spec Spec . ation Limit Limit Gama 5.0 mrad 1.49E+00 2.98E+01 3.14E-01 6.28E+ 00 Beta 10.0 mrad 1.05E+00 1.05E+01 3. 26E-01 3.26E+00 Ctmulative Doses Per Year Type of Tech Unit Quarters % of M ch , Radiation Spec 1,2,3,4 Spec Limit Limit f Gama 10.0 mrad 1.98E+00 1.98E+01 i Beta 20.0 mrad 1.65E+00 8.25E+00 lO ' i O l
TABLE 2-6b E. I. HATCH NUCLEAR PLANr - UNIT 2 O SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REIORT 1987 AIR DOSES DUE 'IO NOBLE GAS RELEASES i Ctznulative Doses Per Quarter Type Tech Unit Quarter 4 of Quarter 4 of of Spec 3- Tech 4 Tech Radi- Limit Spec Spec ation Limit Limit Gamma 5.0 mead 1.77E+00 3.54E+01 4.56E+ 00 9.12E+01 Beta 10.0 mrad 2.17E+00 2.17E+ 01 5.97E+ 00 5.97E+ 01 Cumulative Doses Per Year
! Type of Tech Unit Quarters % of Tech !
Radiation Spec 1,2,3,4 Spec Limit l Limit Gamma 10.0 mrad 7.26E+00 7.26E+01 ; 4 Beta 20.0 mrad 8.82E+ 00 4. 41E+ 01 i O ' ) i i i I ) } I !O 4 I
l TABLE 2-74 E. I. HATCH NUCLEAR PLANT - UNIT 1 SD4IANNUAL RADI0 ACTIVE EFFLUENI RELEASE REPORT 1987 l INDIVIDUAL DOSES DUE 'IO RADIOIODINE, 'mIT!'J ", AND PARTICULATES I9 CET.4;S RELEASES Cumulative Dose Per Quarter Organ Tech Unit Quarter 4 of Quarter t of Spec 3 Tech 4 Tech Limit Spec Spec Limit Limit Bone 7.5 mrem 4.87E-03 6.49E-02 8.60E-03 1.15E-01 Liver 7.5 mrem 2.90E-03 3. 87E-02 2.55E-03 3.40E-02 . Tot. Body 7.5 mrem 1.86E-03 2. 48E-02 2.14E-03 2.85E-02 Thyroid 7.5 ' mrem 5.74E-01 7.65E+03 4.12E-01 5.49E+00 Kidney 7.5 mrem 3.85E-03 5.13E-02 3.28E-03 4.37E-02 Lung 7.5 mrem 7.99E-04 1.07E-02 1.25E-03 1.67E-02 GI-LLI 7.5 mrem 1.03E-03 1.37E-02 1.53E-03 2.04E-02 - Cumulative Dose Per Year Organ Tech Unit Quarters t of Tech ; Spec Limit t Spec 1,2,3,4 Limit O Bone Liver Total Body 15.0 15.0 15.0 mrem mrem 2.11E-02
- 1. 38E-02 1.40E-01 9.17E-02 mrem 7.67E-03 5.11E-02 Thyroid 15.0 mrem 2.81E+00 1.87E+01 Kidney 15.0 mrem 1. 50E-02 1.00E-01 Lung 15.0 mrem 3.10E-03 2.07E-02 5
GI-LLI 15.0 mrem 4. 09E-03 2.73E-02 l I I l i 1 !O J j ~47-
TABLE 2-7b E. I. HATCH NUCLEAR PLANT - UNIT 2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1987 INDIVIDUAL DOSES DUE TO RADIOIODINE, TRITIUM, O 5 AND PARTICUIATES IN GASEOUS RELEASES Cumulative Dose Per Quarter Organ Tech Unit Quarter 4 of Quarter t of Spec 3 Tech 4 Tech Limit Spec Spec Limit Limit Bone 7.5 mrem 2.87E-03 3.83E-02 6.73E-03 8.97E-02
-Liver 7.5 mrem 2. 40E-03 3.20E-02 2.76E-03 3.68E-02 ,
Tot . Body 7.5 mrem 2.11E-03 2.81c-02 2.67E-03 3.56E-02 Thyroid 7.5 mrem 2.22E-01 2.9 6E+00 1.74E-01 2.32E+00 Kidney 7.5 mrem 2.80E-03 3.73E-02 3.05E-03 4.07E-02 Lung 7.5 mrem 1.69E-03 2.25E-02 2.27E-03 3.03E-02 GI-LLI 7.5 mrem 1.80E-03 2.40E-02 2.45E-03 3.27E-02 Cumulative Dose Per Year Organ Tech Unit Quarters % of Tech Spec 1,2,3,4 Spec Limit Limit O Bone Liver Total Body 15.0 15.0 mrem mrem
- 1. 36E-02 1.07E-02
- 9. 07E-02 7.14E-02 15'.0 mrem 8. 20E-03 5.47E-02 Thyroid 15.0 mrem 1.64E+00 1.09E+01 Kidney 15.0 mrem 1. 20E-02 8.01E-02 l
)
Lung 15.0 mrem 5.74E-03 3.83E-02 : GI-LLI 15.0 mrem 6.15E-03 4.10E-02 l
. l l
l l l i O
TABLE 2-8 I4MER LIMITS OF DETECTION - GASEDUS SAMPLE AELYSES The values in this table represent apriori lower limits of detection (LLD) which are typically achieved in laboratory analyses , of gaseous radieste samples. + i RADIONUCLIDE LLD UNITS Kr-87 1.31E-07 uti/ml i 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 ' 1 I-131 4.37E-14 ' I-133 6.16E-13 Mn-54 2.7 EE-14 Fe-59 4.62E-14 Co-58 2.46E-14 Co-60 2.88E-14 Zn-65 7.51E-14 i i
)
Mo-99 6.02E-13 Ce-134 3.6 E-14 Ce-137 2.88E-14 Ce-141 4.9 2 -14 Ce-144 2.02E-13 Sr-89 1.17E-14 St-90 3.82E-15 H-3 5.82E-12
+
i i
- i I ,
O ' i ! l
- l
f .!-
- 3. SOLID WAS'1T p 3.1 REGUIATO7Y REQUIREMENTS d The Technical Specifications presented in this i section are for Unit 1. Requirements for Unit 2 are tne same as for Unit 1; however, the
'Itchnical Specification numbers are not the same.
TEGNICAL SPECIFICATIONS 1 3.15.3.1 The solid radwaste system shall be used in : accordance with the PROCESS CONIROL PROGtAM 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 fran 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: 3 a. Container volume
- b. Total curie quantity (specify whether det' ermined by neasurement or estimte)
- c. Principal radionuclides (specify whether determined by measurement or estimate)
- d. Type of waste, e.g., spent resin, conpacted dry waste, evaporator bottoms
- e. Type of container, e.g., ISA, type A, type B, large quantity
- f. Solidification agent, e.g., cement.
i 3.2 SOLID WASTE DATA Regulatory guide 1.21 Table 3 is found in this report as Table 3-la, and 3-lb. I f i r
Table 3-la EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) July-December, 1987 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS FOR UNIT 1 AND II U SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) l l l 1 l l 1. Type of waste l UNIT l'6 month lEst. Totall l I I Deriod i ERROR % l l a. Spent resins, filter studges, evaporator I mJ l 1.66E+2l l l bottoms. etc. I C1 1 1.noE+11 1.n E+1 l l b. Dry compressible waste, contaminated l m4 1 3.60E+2l l l eauio. etc. I Ci l 3.55E 01 2.0 E+1 l l c. Irradiated components, control rods, mJ l 3.63E 01 l l etc. (Control Rod Blade Velocity Limiters I Ci l 9.09E 01 2.0 E+1 l l d. Other (describe) l mJ l 3.26E 01 l l eaulo, etc. CRD Filters l Ci I 4.57E 01 2.0 E+1 l
; 2. Estimate of raajor nuclide composition (by type of waste) l ISOTOPE l PERCENT l CURIES l 1 ) l 1 1
~
l l a. Zn-65 l 15.74 1 1R9 ?? l l Cs-137 .l 14.46 l 197.47 l l Cs-134 l 11.89 l 129.;9 l
}/ l b.
All Others Co-60 1 37;91 1 412.79 l l 1 38.04 1 1.1s l l Zn-65 1 36.53 1 1.10 l l Cs-137 l 10.29 1 0.16 l
- l. All Others l 15.14 1 0.94 l l c. Co-60 1 65.57 l 5.96 l l Fe-55 1 27.50 1 2.50 l Mn-54 l 1 5.06 1 0.46 l All Others l l 1.87 1 0.17 l l d. Co-60 1 56.94 1 2.60 l l Fe-55 25.7 0 1 l 1.1R l l Zn-65 l 9.96 l n_46 l l All others l 7.40 l 0.14 l l 1 I I
- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 33 Cask Earnwell, S.C.
14 Van Barnwell, S.C. B. IRRADIATED FUEL SHIPMENTS (Disposition) { I Number of Shipments Mode of Transportation Destination 0 N/A N/A i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)1987 SOLID WASTE AND IRRADIATED FUEL SHIPMENT FOR UNIT I AND II , O O Table 3-1,b , MY----NCEn6Et 1187 CG!E FilNCIPLE DUAIAL NUAM R GF W UM CF YUE Gl.ll!FICAll0N 00ANilif / rJCtlMS CONTAINER CONTAINERS EACM CONTA!Eit $4!F81Ni Ai!NT
. ITM OF NAsit MIERMINED MTEMIMf!ON K50t!Pi!0N $NIPPEI CU41C FEli Ut31 C0hTAINER nuninan nuun un u n u nu nun u nnunnu n an nunn u nn an e n nanan nuunu n nunn u n ene n en.
M Mi! RED 310.0642 IN45,CS-137, 14 210 MIM 11 202.1 LSA EPE INTEIRlif TYPE A LEllu PIASURED CS 134 MEAS M B C061AsilEt IN45, CS 137, 14-210 CM904 15 119.4 LSA NONE MuiERED 140.492 CS 134 STER LINER TYFE A F.Estu REASURED , MASUREI IN45, CS 137, 10-142 HIGH 5 132.4 LSA NOME
! MWAfttED 634.3312 l P.ES!N REASURE9 CS134 !!ITEER!iY TYPEI
. MEASIstEl CCNTAIMER 9.09 C040, FE-55, 10142 CMBON I 121.3 LSA N0nt ,
1RRA0!ATEI C090NENf5 ESilMAi! PN144 STER LIER TYPE I IC.R.I. VELOCITY EsitMit ' LinliiRS) .
- . I OiEtEQUIP. 4.5707 E0-60,FE-55, '19. 24 tun 3 31.4 LSA N0ut j! (CRB FILTERS) EST! RATE IN45 HliHINTEGRitY TYM A ESTIMTE CONTAINER l
MYAtilVE 3.3732 C040, IN-65, 6-25 STER 121 16.7 LSA Rht HSTE, ESTIMAft CS 137 Mt iAW.):t STRONG IIG4T i CC9RISSE) ESilMTE CONTAlk!t C040,IN43, 9-25 STER 2 124.5 154 E0kE l Ntf ETIVE 0.1711
- WASTE, ESilRATE ' CS 137 90t tAY6.1I $11046 !!ENT C09ESSED ESitMTE t0VERPACKl CCn161NEN itAYEFA6E VOLUME DUE 10 HIES M61NG FROM CDP.PKitt.
l
, i l 1
- 4. CHANGES IN THE RADIOIOGICAL ENVIROlEENTAL MONI'IORING PRO @AM hehnical Specification 3.16.1.c requires in part that
, O V if milk sanples frce any of the locations required by 3.16.1-1 can no longer be obtained, efforts will be made to find replacement locations. The cause of the unavailability and the identification of the affected location (s) and of any replacement location (s) shall be submitted to the Commission in the next semi-annual
- radioactive effluent release report.
In the Semi-annual radioactive effluent release report for the first half of 1987, it was reported that during the first quarter, a new milk sampling location was established at Clark's farm which is in the M M sector at 4,8 miles. During the third quarter, the ' Clark's let all of their goats go dry because scue of them had contacted sore eye. The Clark's expected that goat milk would be available again in six months - or so. At the years end, milk from Clark's remained unavailable. In an effort to find a replacement location, the !
, Appling County and Toombs Count Agents were contacted i during the third quarter. Neither knew of a milk animal within five miles of Plant Hatch. A land use survey was conducted during the fourth quarter and no milk aninals were located.
O . l i A a s I i j
- 5. OtANGES TO TIE PLANT HATQI CDOI
- Technical specifications 6.9.1.8 and 6.9.1.9 require in part that changes to the Plant Hatch offaite Dose calculation Manual (ODQ4) be reported to the
- commission in the next semi-annual Effluent Release 4
Report. On May 19, 1987, the Plant Review Board (PRB) recommended approval of danges to the Plant Hatch GX:M which would include consideration of potential releases frm building exhaust augmented ventilation. However, since building exhaust auqunented ventilation was the subject of a proposed change to Plant Ratch Technical specifications, the change to the Plant Hatch CDCM was worded so as to apply only if I Radiological Effluent Technical Specifications allow releases via this pathway. Documentation of PRB j review and approval is presented in Appendix A of this . i report. on June 30, 1987, the PRS recernended approval of , ] , changes to the Plant Ratch 0004 pertaining to updating l meteorological data and changing the location of the critical receptor. These changes became effective for the third quarter of 1987. ; A change in the location of the critical receptor was ; i the result of changes in land use in the vicinity of i Plant Ratch, that was noted during the land use survey I 1 as required by IDW Technical specification 3.16.2. Since the milk cow was no longer present at the J previous location of the critical receptor, potential dose assessments were performed to evaluate other potential locations based on the land use survey. The
- critical receptor identified in this revision to the j
CDCM was identified as a result of these potential
- dose assessments. Documentation of PRB review and
- approval of these changes is presented in Appendix B j
of this report. i j , Appendix C of this report contains the modifie4 pages of the Plant Hat & ODCM discussed in Appendix A sM Appendix B. These modifications to the Plant Hatch i CDCM are identified as Revision 3. , i e O .e . , l i
i i
- 6. CHANGES TO PLANP HATCH SOLID RADIOACTIVE WASTE 290 CESS CDNIROL PROGRAM (S.R.W. P.C.P. ) l l
Technical Specification 6.9.1.9 requires in part that i Os changes to the Plant Hatch Solid Radioactive Waste Process Control Program (S.R.W. PCP) be reported to ; the Ccanission in the next Semi-annual Effluent l Release Report. On July 9,1987, the Plant Review Board (PRB) approved a number of changes and additions to the Plant Hatch Solid Radioactive Waste Process Control Program. The ' l changes and rationales for the changes are as follows:
- 1. Change the last sentence in the first paragraph of II. Regulatory Overview from:
"Packaging of waste is in containers meeting .
Dor specificaticns and appropriate for the applicable aste class." To:
"Waste is packaged in containers meeting or exceeding the requirements for both j transportation and burial."
1 Rationale: All w ate does not have to be packed in DOT specification containers, although all mate packages must meet certain DOT requirements. Also, the type of ; 4 ' package that is appropriate for each este ' class depends on both the waste class and A the form of the w ate. ; j V 2 Change the second sentence of the second ' paragraph of V. Processing of Miscellaneous
- Liquids (011) frm
- !
"Per HNP-8043, test sanples are conducted 4
" every tenth batch to verify the
' pre-established mixing ratios."
To: ' "As appropriate, test sanples are conducted every tenth batch to verify the ; pre-established mixing ratios." ' Add "Sampling is accomplished in accordance i with approved plant procedures to assure that the samples are representative of the
- waste being processed." ,
1 Rationale: The change removes the reference of a deleted procedure (HNP-8043) from the { ) second sentence and the added statement serves as a general comitment to a savling - methodology assuring representative sampling is appropriate. ' l n v , i s l
3 Add tha following sent:nce to VI Use of Contractors for Waste Processing.
"Contractors suFolied waste processing shall be performed in areas with features and/or b
V controls adequate to contain inadvertent spills and over flows." Rationale: This statement is needed to addcess an IRC concern presented in both the ' acceptance letter of the NuPac resin drying topical report and in NuReg-2731 "An Evaluation of the Safety Aspects of the i Design and Operation of Temporary / Mobile Radioactive Waste Solidificaton Systems."
- 4. Add the following sentence to VI Use of .
Contractors for Waste Processing, a
"Waste products will be verified as meeting 4
the criteria for disposal prior to final , closure of the container." Ratio 91e: Thts statement is needed as a meus of araurance that all disposal criteria (both Federal and Disposal site specifics) are met prior to capping off of . the processed container. ! Al'. other changes in the Plant Hatch Solid Radioactive
! F Waste Process Control Program are primarily j
grammatical and editorial in nature and do not change the original intent of the program. , Appendix D presents the modified version of the Solid Radwaste Process Control Program. I
- 7. MerEDROICGY l
, In accordance with Technical Specification 6.9.1.9, the annual summary of meteorological I data collected at Plant Hatch over 1987 is presented in this section. 7.1 Review of 1987 Meteorological Data 1
- l j
- O j <
iO ) The 1987 year of meteorological data was the fourth year of data collection i using the 100m tower. The data collection percentage for the year was higher L than in any of the previous five years, averaging about 965 for all parameters ! and 93% for pertinent parameters of wind speed, direction, and delta temperature. 11ost of the data lost during the year were due to strip charts ; i jamming or running out of paper. There also were some short periods where the wind :peeds were affected by poor bearings causing some bad data. These bad data periods were generally less than two days. , 2 The ambient and dew point temperature data generally agreed favorably with the i temperature data from previous years. The temperatures were quite wam during ' the second half of the year, averaging over 900 for sunniertime high temperatures. The main difference in comparison with the last few years is that the ambient temperatures were considerably higher than normal during November and December (see Attachment 7-7). The wind roses in Attachments 7-4, 7-5, and 7-6 from all three levels on the meteorological tower agree quite well on both a seasonal and annual basis. The peak wind direction sector for each level was from the northeast with all I three levels having winds from that direction about 11% of the time. The secondary peak varied somewhat with the 60m and 100m levels having winds from the west about 9% of the time. The 10m level secondary peak was from the j south-southwest also about 9% of the time. These peak direction sectors are very consistent with the wind direction from the last few years. On a O seasonal basis the data are again very consistent with only mince differences in the spring and fall. The joint frequency tables of wind speed and direction versus delta temperature are shown in Attachments 7-1, 7-2, and 7-3. The data for the last five years are sumarized in the table below. The table used wind speed and direction at 10m versus delta temperature 60-10m for the last four years and 1 edelta temperature 45-10m for 1983. The table shows some differences in the stability callsifications particularly in the "A" and "G" stability classes i for 1987. Both of these stabilities have a higher percentage of the annual j total. The reason for the increase can probably be traced to the higher than 4 nomal temperatures, the result of many clear days and nights. This type of condition results in "A", or unstable conditions, during the day and "G", stable conditions, at night. The increased unstable and stable conditions have meant less hours of neutral conditions during the year. The following table shows the last 5-year stre,1f ty Assifications. l lO
,7
_y I 1 l i Plant Hatch Stability Classification .O Stability Percent Stability 5-Year Average , Group 1957 1986 1955 1954 1953 ; A 15.7 7. 8 9.3 8.4 14.7 11.3 8 5.0 3.5 4.7 5.2 5.2 4.7
- C 4.0 3.0 5.5 5.8 3.8 4.6 '
0 16.8 21 .4 26.5 19.9 21. 9 21.3 E 31.6 37.6 31.8 31.8 33.8 33.4 . F 12.3 13.7 11.3 12.4 11.3 12.2 ! G. 14.6 11.0 10.9 16.5 9.3 12.5 Total Hours 8162 8037 7860 7928 7468 The precipitation totals (daily and monthly) are shown in Attachments 7-8 and ' ., 7-9. The total for the year was 40.09 inches which is closer to the area i normal of about 45 inches than in many preivous years. The conditions for the , year were quite varied, ranging from no rainfall in October to over seven ; inches in January. ' i !O< l l i I l j 1 i I l l l 1 l I 1 l i ., _ _ _ ,
i METEOROLOGICAL DATA ATTACHMENTS 4 O Attachment 7-1 Joint Frequency Tables of Wind Speed and Wind Direction 10m vs. Delta Temperature 60-10m i Attachment 7-2 Joint Frequency Tables of Wind Speed and Wind Direction 60m vs. Delta Temperature 60-10m Attachment 7-3 Joint Frequency Tables of Wind Speed and Wind Direction 100m vs. Delta Temperature 100-10m Attachment 7-4 Wind Roses from 10m ( Seasonal and Annual) i Attachment 7-5 Wind Roses from 60m (Seasonal and Annual) , Attachment 7-6 Wind Roses from 100m (Seasonal and Annual) ? Attachment 7-7 Plots of Monthly Averages and Averages of Daily Extremes of Ambient Temperature and Dew Point Temperature Attachment 7-8 Monthly and Annual Precipitation for 1987 Attachment 7-9 Daily Precipitation for the Period of January through December 1987
- O l
I I .I I ) ! i 1 59 I i
ATTACHMENT 7-1 PLANT HATCH JOINT FREQUENCY TABLES OF WIND SPEED AND WIND DIRECTION O 10m VERSUS DELTA TEMPERATURE 60-10m JANUARY 1,1987 THROUGH DECEMBER 31, 1987 I 1 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 STABILITY CLASS: A DT/DZ ELEVATION: SPEED *SPD10M DIRECTION 8DIR10A LAPSE *DT60M WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 52 27 0 0 0 81 NME 1 57 18 0 0 0 76 NE 3 115 29 0 0 0 147 ENE 5 77 20 0 0 0 102 E 1 42 6 0 0 0 49 ESE 3 47 7 0 0 0 57 SE 4 52 10 0 0 0 66 SSE 3 31 3 0 0 0 37 S 13 38 14 0 0 0 65 () SSW SW i 4 45 73 24 32 0 0 0 0 0 0 70 109 USW 2 56 27 0 0 0 85 W 4 52 48 0 0 0 104 UNW 2 45 17 1 0 0 65 NW 4 63 31 0 0 0 98 NNW 4 51 18 0 0 0 73 TOTAL 56 896 331 1 0 0 1284 PERIODS OF CALM (HOURS)* 0 VARIABLE DIRECTION O HOURS OF MISSING DATA 598 ENTER: ERETURN3 CONTINUE, ES03 START OVER, EEX3 TO EXIT 60 0
l ATTACHMENT 7-14 O HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 ) STABILITY CLASS
- B DT/DZ !
ELEVATION: SPEED *SPD10M DIRECTION 7DIR;0A LAPSE *DT60M WIND SPEED (MPH) : WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 18 4 0 0 0 23 NNE 1 14 3 0 0 0 18 NE 3 29 8 0 0 0 40 ENE 2 20 4 0 0 0 26 E 3 16 0 1 0 0 20 ESE i 14 2 0 0 0 17 SE 2 S 4 0 0 0 11 SSE 3 12 1 0 0 0 16 S 1 15 6 0 0 0 22 3 19 1 0 0 0 23 (])SSW SW WSW 5 4 18 28 4 5 0 0 0 27 0 0 0 37 U S 27 8 0 WNW 0 0 40 l 7 19 4 0 0 0 30 NW 21 8 0 ) NNW i 0 0 30 0 18 7 0 0 0 _______________________________________________________25 _______ TOTAL 42 293 70 0 0 0 ______________________________.,_______________________40S ________ PERIODS OF CALM (HOURS)* 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: S98 ENTER: ERETURN3 CONTINUE, ES03 START OVER, EEX3 TO EXIT l l l l l 61 O l
i l ATTACHMENT 7-lb l (2) HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 STABILITY CLASS
- C DT/DZ ELEVATION: SPEED *SPD10M DIRECTION *DIR10A LAPSE *DTSON WIND SPE:D(MPH)
WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 15 2 0 0 0 19 NNE 2 13 0 0 0 0 15 NE O 22 3 0 6 0 25 ENE 1 19 1 0 0 0 21 E 2 9 2 0 0 0 13 ESE 1 6 0 0 0 0 7 SE 2 15 4 0 0 0 21 SSE 7 5 2 0 0 0 14 S 0 13 2 0 0 0 15 SSW 3 14 2 0 0 0 19 SW 18 4 0 0 23 O USW W i 2 3 27 9 5 6 0 0 0 0 0 0 0 34 18 WNW i 17 5 0 0 0 23 NW i 28 6 0 0 0 35 NNW 5 15 5 1 0 0 26 TOTAL 33 245 49 1 0 0 328 PERIODS OF CALM (HOURS)* 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA
- 598 ENTER * [ RETURN 3 CONTINUE, ES03 START OVER, EEX3 TO EXIT 62 O
ATTACHMENT 7-1C () HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 STABILITY CLASS D DT/DZ ELEVATION: SPEED *SPD10M DIRECTION:DIRiOA LAPSE *DT60 __________-_________________________________M_______ WIND SPEED (MPH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 17 32 23 0 0 0 72 NNE 14 39 0 0 1 0 54 NE 30 148 28 0 0 0 206 ENE 20 87 9 0 0 0 116 E 17 49 6 0 0 0 72 ESE 32 39 3 0 0 0 74 SE 16 30 8 0 0 SSE 0 54 9 22 10 2 0 0 43 S 12 32 20 1 0 0 65 SSU 22 57 15 0 0 SU 0 94 16 62 12 0 0 0 90 USU 12 42 11 0 (]) U 11 4R 22 1 0 0 0 0 65 76 l UNU 13 53 22 0 NU 1 0 89 I 19 64 18 2 0 0 103 NNU 22 55 20 0 ____________________________________________0__________________ 0 97 TOTAL 282 853 228 7 0 1370 ____________________________________________0__________________ PERIODS OF CALM (HOURS) 0 UARIABLE DIRECTION O HOURS OF MISSING DATA: 598 ENTER
- ERETURN3 CONTINUE, ES03 START OVER, EEX3 TO EXIT 63 O
1 l ATTACHMENT 7-1d O HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 STABILITY CLASS: E DT/DZ ! ELEVATION: SPEEDtSPD10M DIRECTIONIDIR10A LAPSE *DT60M ' WIND SPEED (MPH.) i UIND l 1-3 4-7 DIRECTION 8-14 13-18 19-24 >24 TOTAL N 22 30 13 1 0 0 66 NNE 20 51 3 0 0 0 74 l NE 49 210 31 0 0 0 290 ' ENE 54 117 7 0 0 0 178 E 57 52 1 0 0 0 110 ESE 46 79 3 0 0 0 128 SE 84 120 7 0. 0 0 211 SSE G2 113 7 0 0 0 182 i S 58 107 9 0 0 0 174 l SSU 77 160 16 0 SU 0 0 253 i 80 99 13 0 0 0 193 i USU 50 78 7 0 0 0 135 i U 31 124 26 0 O UNU NU 24 28-104 105 16 20 0 3 0 0 0 0 0 0 181 144 i NNU 156 16 63 23 1 0 0 _______________________________________________________103 _______ TOTAL 759 1612 202 5 0 0 ______________________________________________________2S78 _ _ _ _ _ . , _ _
)
PERIODS OF CALM (HOURS): 0 ' UARIABLE DIRECTION O HOURS OF MISSING DATA: 598 ENTER: ERETURNJ CONTINUE, ES03 START OVER, EEXJ TO EXIT l 64 O
ATTACHMENT 7-le 1 PERIOD OF RECORD =87010101-87123124 HOURS AT EACH WIND SPEED AND DIRECTI STABILITY CLASS F DT/DZ ELEVATION: SPEEDtSPD1 ! __________________________0M DIRECTION *DIR10A ' ______________________ LAPSE *DT60M ________________ UIND WIND SPEED (MPH) DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N ____ _____ _____ ___ _____ i 10 19 0 0 0 NNE 10 7 0 29 NE 1 0 0 0 18 47 34 5 0 0 ENE 61 31 0 86 1 E 0 0 0 0 i 54 8 0 92 ! ESE 0 0 0 62 SO 13 0 0 SE 48 0 0 63 SSE 15 0 0 0 l 26 15 0 63 ' S 0 0 0 0 31 26 41 SSW 1 0 0 0 58 48 51 0 0 SW 52 0 0 99 USW 41 0 0 0 i 58 32 0 93 ' W 0 0 0 0 48 32 0 90 0 0 0 W"W NW es e3 1 0 e 0 80 14 38 e 52 NNW 0 0 0 0 13 3 S2 0 0 24 _____________________8_______________________0 TOTAL 59 __________________ 398 11 0 0 1002 ____________________3_________________________0 PERIODS OF CALM (HOURS): _________________ 0 UARIABLE DIRECTION 0 HOURS OF MISSING DATA 2 598 ENTER: CRETURN3 CONTINUE, ES03 START OVER, EEX3 TO EXIT l 65 O
ATTACHMENT 7-1f O HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 STABILITY CLASS: G DT/DZ ELEVATION: SPEEDtSPD10M DIRECTION DIR10A LAPSE *DT60M WIND SPEED (MPH) WIND . . DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 26 3 0 0 0 0 29 ! NNE 10 6 0 0 0 0 16 i NE 26 14 0 0 0 0 40 i ENE 37 13 1 0 0 0 51 E 39 7 0 0 0 0 46 : ESE 36 7 0 0 0 0 43 l SE 53 3 0 0 0 0 56 SSE 63 5 0 0 0 0 68 l S 94 22 0 0 0 0 116 l SSU 152 41 0 0 0 0 193 SW 125 25 0 0 0 0 150 USU 147 25 0 0 0 0 172 26 OUUNU NU 91 30 17 0 0 0 0 0 0 0 0 117 47 22 7 0 0 0 0 29 NNU 19 2 1 0 0 0 22 TOTAL 970 223 2 0 0 0 119S PERIODS OF CALM (HOURS): 0 UARIABLE DIRECTION O HOURS OF MISSING DATA: S98 ENTER: ERETURN3 CONTINUE, ES03 START OVER, EEX3 TO EXIT 66 O l
l ATTACHMENT 7-1g O HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 STABILITY CLASS
- ALL DT/DZ ELEVATION SPEED *SPD10M DIRECTION *DIR10A LAPSE *DT60M WIND SPEED (MPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 80 169 69 1 0 0 319 NNE 58 187 26 0 0 0 271 NE 158 572 104 0 0 0 834 l ENE 180 364 42 0 0 0 586 E 173 183 16 0 0 0 372 ESE 169 205 15 0 0 0 389 SE 209 240 33 0 0 0 482 l SSE 173 203 23 2 0 0 401 l S 209 253 52 1 0 0 515 i SSU 306 387 58 0 0 0 751 l SU 284 336 65 0 0 0 685 l 275 288 55 0 0 0 618 i (])USU U UNU 193 105 312 278 110 63 1 2l 0 0 0 0 616 450 l i NU 89 326 83 5 0 0 503 NNU 74 217 77 2 0 0 370 TOTAL 2735 4520 893 14 0 0 8162 PERIODS OF CALM (HOURS)* O UARIABLE DIRECTION 0 HOURS OF MISSING DATA
- 598 ENTER
- ERETURNJ CONTINUE, ES03 START OVER, EEXJ TO EXIT l
l l 67 > O
l l ATTACHMENT 7-2 PLANT HATCH JOINT FREQUENCY TABLES OF WIND SPEED AND WIND DIRECTION 60m VERSUS DELTA TEMPERATURE 60-10m Ov JANUARY 1,1987 THROUGH DECEMBER 31, 1987 HOURS AT EACH UIND SPEED AND DIRECTION : PERIOD OF RECORD = 87010101-87123124 STABILITY CLASS: A DT/DZ . ELEVATION: SPEED SPD60M DIRECTION DIR60M LAPSE DT60M UIND SPEED (MPH ~) 1 UIND l DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL , N 0 19 34 10 0 0 63 I HNE 3 14 21 9 0 0 47 HE 2 45 83 32 1 0 163 ; ENE O 35 64 16 2 0 117 j E O 33 48 8 0 0 89 ESE O 24 23 9 1 0 57 SE 3 13 17 2 0 0 35 SSE 2 16 17 0 0 0 35 S 1 26 15 7 0 0 19 ! 2 28 24 16 0 0 70 l OSSU SU 2 30 29 17 8 0 86 USU i 23 ,45 27 1 0 97 U 1 32 64 29 8 0 134 UNU 1 32 32 9 1 0 75 NU 4 22 35 14 1 0 76 NNU 1 19 26 5 0 0 51 TOTAL 23 411 577 210 23 0 1244 PERIODS OF CALMfHOURS): 0 UARIABLE DIRECTION 0 HOURS.0F MISSING DATA: 871 l I 68 l 1 l l
l ATTACHMENT 7-2b l O SITE: PLANT HATCH PERIOD OF RECORD =87010101-87123124 HOURS AT EACH UIND SPEED AND DIRECTI STABILITY CLASS B DT/DZ ELEVATION: SPEED *SPD60M LAPSE:
-----------------------------DIRECTION:DIR60M-----------------------DT60 ----------
WIND UIND SPEED (MPH) DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 13 NNE 1 8. 2 0 0 24 i O 4 4 9 0 1 NE 0 17 O 15 20 3 1 0 ENE O 6 13 39 l E 2 0 0 21 2 5 15 3 0 i ESE 0 25 SE O 9 6 3 0 i 4 0 18 3 2 1 0 SSE 0 10 1 6 2 0 0 S 0 9 1 10 5 4 0 SSU 3 0 20 8 8 3 0 SU 0 22 1 11 6 4 USU 1 0 23 s W i 15 12 7 0 2 0 35 UNU 27 21 8 0 l' 11 15 1 59 NU 3 0 0 30 NNU i 17 10 3 2 1 0 33 8 1 0
--------------------------9--------------------_--0 TOTAL 19 155 19 56 5 0 404 ---_------------_-------169-_--------------------_-
PERIODS OF CALM (HOURS): ------------ 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 871 69
ATTACHMENT 7-2b O SITE: PLANT HATCH HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 STABILITY CLASS C DT/DZ ELEVATION: SPEEDtSPD60M DIRECTION DIR60M LAPSEtDT60M UIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 12 1 '3 0 0 18 NNE 1 4 3 0 0 0 8 NE i 19 14 4 0 0 38 ENE 4 8 7 1 0 0 20 E O 8 9 5 0 0 22 ESE 1 4 5 3 0 0 13 SE O 6 4 0 0 0 10 SSE 3 6 3 1 0 0 13 S 0 9 7 1 0- 0 17 SSU 0 6 12 0 1 0 19 0 2 8 4 0 0 14 O SU USW 2 16 11 1 0 0 30 U i 13 14 5 4 0 37 UNU i 15 11 6 0 0 33 NU 0 9 11 5' 0 0 25 NNU 2 5 5 1 0 0 13 TOTAL 18 142 125 40 5 0 330 1 PERIODS OF CALM (HOURS) 0 UARIABLE DIRECTION 0 HOURS OF MISSING DATA: 871 l 70 0
ATTACHMENT 7-2c O SITE: PLANT HATCH HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 STABILITY CLASSt D DT/DZ ELEVATION: SPEED *SPD60M DIRECTION *DIR60M LA __________________________________________________PSE*DT60M ______________ UIND SPEED (MPH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 14 21 25 29 0 0 89 NNE 7 14 38 21 0 NE 1 81 7 38 100 44 1 0 190 ENE 6 40 46 5 E 1 0 98 6 33 42 12 2 0 95 ESE 6 28 18 6 SE 0 0 58 5 15 20 3 1 0 44 SSE 4 10 21 5 S 0 0 40 : 8 15 19 17 2 0 61 SSU 1 17 37 10 ) SU 1 0 66 ' 4 33 38 14 0 0 89 O USU 11 30 26 11 2 0 80 U 4 23 '35 UNU 28 11 0 101 4 25 45 27 0 NU 1 102 7 37 18 11 4 0 77 NNU 8 30 26 0 ~0 68 ______________________________________4________________________ TOTAL 102 409 554 27 0 1339 ____________________________________247 __________________________ PERIODS OF CALM (HOURS)* 0 VARIABLE DIRECTION O HOURS OF MISSING DATA 871 71 O
1 1 ATTACHMENT 7-2d l SITE: PLANT HATCH l HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 l STABILITY CLASS: E DT/DZ . ELEVATION: SPEED:SPD60M DIRECTION DIR60M LAPSE DT60M WIND SPEED (MPH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 1 N 3 20 31 29 6 0 89 NNE 5 19 47 39 3 0 113 NE 8 22 131 90 7- 0 258 ENE 7 36 99 20 1 0 163 E 10 45 88 8. 0 0 151 ESE 8 42 94 10 1 0 155 SE 5 57 104 5 0 0 171 SSE 3 40 92 16 1 0 152 1 S 4 28 98 20 2 0 152 I 5 34 165 26 3 0 233 l OSSWSU 8 38 121 20 2 0 189 USW 2 25 74 37 2 0 140 W 5 26 79 66 8 1 185 UNW 2 18 88 41 2 0 151 l NW 3 22 54 24 5 0 108 i NNU 7 15 39 16 1 0 78 l TOTAL 85 487 1404 467 44 1 2488 PERIODS OF CALM (HOURS): 0 UARIABLE DIRECTION O l HOURS OF MISSING DATA: 871 72 O
ATTACHMENT 7-2e () SITE: PLANT HATCH , HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 STABILITY CLASS: F DT/DZ l ELEVATION: SPEED SPD60M DIRECTION DIR60M LAPSE *DT60M UIND SPEED (MPH)' UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 6 17 10 0 0 34 NNE 2 4 12 11 6 0 35 NE O 6 44 20 3 0 73 ENE 2 7 50 11 0 0 70 ! E 3 10 41 2 0 0 56 i ESE 2 7 62 1 0 0 72 SE 3 27 25 0 0 0 55 SSE i 19 32 3 0 0 55 S 3 14 34 4 0 0 55 , SSU 0 4 30 12 0 0 46 O SU USU 2 3 13 17 52 62 16 22 0 0 0 0 83 104 i U 3 15 59. 13 1 0 91 UNU 3 10 37 2 0 0 52 ' NU 1. 8 30 8 0 0 47 NNU 1 3 16 7 0 0 27 TOTAL 30 170 603 142 10 0 955 l PERIODS OF CALM (HOURS): 0 ! UARIABLE DIRECTION O __ HOURS OF MISSING DATA: 871 73
ATTACHMENT 7-2f () SITE: PLANT HATCH HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 STABILITY CLASS: G DT/DZ ELEVATION: SPEED SPD60M DIRECTION DIR60M LAPSE *DT60M UIND SPEED (MPHi UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 5 19 18 7 0 0 49 NNE 6 15 27' 4 1 0 53 NE 6 26 41 19 0 0 92 ENE 3 21 60 13 0 1 98 i E 3 18 55 2 0 0 78 ESE 6 22 32 1- 0 0 61 SE 6 20 28 1 0 0 55 SSE 3 17 32 '4 0 0 56 S 4 17 29 11 0 0 61 SSU 5 18 26 6 0 0 55 SU 5 24 51 22 0 0 102 O USU 8 33 51 9 0 0 101 W 3- 16 45 8 0 0 72 UNU 3 15 48 1 0 0 67 NU 4 17 45 4 0 0 70 NNU 6 21 31 1 0 0 59 TOTAL 76 319 619 113 1 1 1129 PERIODS OF CALM (HOURS): 0 UARIABLE DIRECTION 0 HOURS OF MISSING DATA
- 871 74 O
1
,,,,_.,-------..,.----.,7 -
. ---.-...---..r_._
,. ,-.-,.m_ _--m,, -
l l ATTACHMENT 7-2g
)
SITE: PLANT HATCH HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 STABILITY CLASS: ALL DT/DZ ELEVATION: SPEED SPD60M DIRECTION *DIR60M LAPSE *DT60M WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 26 110 134 H90 6 0 366 NNE 24 74 152 93 11 0 354 NE 24 171 433 212 13 0 853 ENE 22 153 339 68 4 1 587 E 24 152 298 40 2 0 516 ESE 23 136 240 33 2 0 434 SE 26 141 206 12 1 0 380 SSE 17 114 199 29 1 0 360 S 21 119 207' 64 4 0 415 SSW 16 115 302 73 5 0 511 SW 22 151 305 97 586 O USW W 28 19 159 152 281 317 114 157 11 33 5 0 0 587 WNW 1 679 15 126 276 89 4 0 510 NW 20 132 203 69 12 NNW 0 436 26 102 151 35 1 315 __________________________________________________0____________ TOTAL 353 2107 4037 1275 115 2 _____________________________________________________7889 _________ PERIODS OF CALM (HOURS)* O VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 871 1 1 75
ATTACHMENT 7-3 PLANT HATCH JOINT FREQUENCY TABLES OF WIND SPEED AND WIND DIRECTION O, 100m VERSUS DELTA TEMPERATURE 100-10m JANUARY 1,1987 THROUGH DECEMBER 31, 1987 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 STABILITY CLASS: A DT/DZ ELEVATION: SPEED *SPD100 DIRECTION:DIR100 LAPSE *DT100 ___-_----_-_---------_---------------_-------_-----_-_-_-__M ----- UIND SPEED (MPH) UIND . DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 0 0 4 4 0 0 8 NNE O O 8 3 0 0 11 NE O 6 25 19 0 0 50 ENE O 4 17 6 0 E 0 27 O 2 5 4 0 0 11 ESE O 1 4 5 0 SE 0 10 O 1 6 1 0 0 8 SSE O 1 2 0 0 0 3 S 0 2 2 0 0 0 4 SSU 0 a 9 4 0 0 15 O SU USU U 0 0 2 2 10 6 5 7 5 4 0 0 22 19 2 1 11 11 7 1 33 UNU i 1 5 3 2 0 12 NU i 2 3 3 NNU 1 0 10 i 0 1 4 0 0
----___-__-_--_-----_-------_--------------_0_--_----_--_----- S TOTAL 4 28 121 75
-______--____---__-_-_____-______-----_---_19__---_-_-__------- 1 248 {
PERIODS OF CALM (HOURS): 0 UARIABLE DIRECTION 0
- HOURS OF. MISSING DA.TA: 718 .
i 76 O l l
ATTACHMENT 7-3a O HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 STABILITY CLASS: B DT/DZ ELEVATION: SPEED:SPD100 DIRECTION DIR100 LAPSE *DT100M WIND SPEED (MPH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL l N O 2 8 6 0 e is NNE O 3 5 4 0 0 12 NE O 12 21 12 2 0 47 ENE O 8 13 2 0 0 23 E O 5 17 5 0 0 27 i ESE O 4 7 2 1 0 14 i SE 1 2 2 0 0 0 5 ! SSE O 3 2 0 0 0 5 ! S 0 7 9 '2 1 0 19 i SSU 0 4 7 2 0 0 13 : SU 0 3 15 4 2 0 24 USU 0 3 18 6 4 0 31 () W UNU 2 1 2 3 12 11 12 4 6 0 34 l NU 1 1 21 0 2 8 6 0 0 16 l NNU 0 15 2 0 TOTAL 1 0----------_. 18 ! 4 64 170 69 17 325 ____--_---_-----------_-------------------_-_---_-1 _--------__ i PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O ' HOURS OF MISSING DATA: 718 i l 1 77 O l l l l
i l ATTACHMENT 7-3b O HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 STABILITY CLASS: C DT/DZ ELEVATION: SPEED SPD100 DIRECTION *DIR100 LAPSE *DT100M WIND SPEED (MPH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 1 4 9 3 0 0 17 NNE O 6 6 3 0 0 15 NE 'O 11 24 14 1 0 50 ENE O 7 13 1 0 0 21 I E O 6 9 3 0 0 18 ESE O 5 5 0 0 0 10 SE O 2 2 1 0 0 5 SSE O 7 5 0 0 0 12 S 0 7 6 2 0 0 15 SSU 0 4 5 4 0 0 13 SU 0 8 16 3 1 0 28 USU 1 5 15 4 3 0 28 U 0 8 12 12 6 0 38 O UNU NU NNU 0 2 8 6 21 7 2 7 2 1 0 1 34 23 1 5 11 4 0 0 21 TOTAL 5 99 166 63 14 1 348 PERIODS OF CALM (HOURS): 0 UARIABLE DIRECTION 0 HOURS OF MISSING DATA: 718 l l 78 O
ATTACHMENT 7-3c O HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 STABILITY CLASS
- D DT/02 ELEVATION: SPEED *SPD100 DIRECTION *DIR100 LAPSE *DT100M UIND SPEED (MPH)
UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 6 45 49 47 6 0 153 NNE 10 33 21 27 3 0 94 NE 5 60 131 109 6 0 311 ENE 7 63 70 36 4 0 180 E 6 39 55 26 8 0 134 ESE 12 41 42 15 2 0 112 SE 11 29 25 7 1 1 74 SSE 4 30 18 14 1 0 67 S 4 33 49 24 3 0 113 SSU 5 38 56 26 ~3 0 128 SU 7 61 70 34 9 0 181 USU 5 54 65 28 14 1 167 75 106 55 20 263 O U UNU NU 4 10 10 71 43 70 46 53 16 17 3 3 1 4 222 122 NNU 2 38 53 10 1 0 104 TOTAL 108 753 926 527 101 10 2425 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA
- 718 l
l
ATTACHMENT 7-3d l I HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 STABILITY CLASS: E DT/D2 ELEVATION: SPEED *SPD100 DIRECTION *DIR100 LAPSE *DT100M UIND SPEED (MPH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL l N 3 11 31 31 14 2 92 NNE 6 14 32 68 23 3 146 NE 5 18 92 158 18 1 292 ENE 4 25 67 93 3 0 192 1 E 9 18 78 51 2 0 158 ESE 9 35 49 43 1 0 137 SE 8 51 99 34 0 0 192 SSE 3 17 49 87 5 0 161 S 3 16 109 85 0 11 224 l SSU 3 20 111 90 12 2 238 SU 5 20 88 76 10 0 199 l OUUNW USU 5 7 4 19 14 11 55 48 2D 69 108 93 16 22 21 0 2 164 201 1 159 NU 6 14 40 56 11 3 130 NNU 5 12 26 28 3 0 74 TOTAL 85 315 1003 1170 172 14 2759 ____________-_____.___________________________________________ l PERIODS OF CALM (HOURS)* 0 UARIABLE DIRECTION 0 HOURS OF MISSING DATA: 718 I l I 4
---.--,w
, w - - - . - - - - - - - - - - * - - = - - -,--m -----e- -- --- - - " ' - - - - - -
ATTACHMENT 7-3e () ' 1 HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 STABILITY CLASS: F DT/DZ ELEVATION: SPEED *SPD100 DIRECTION DIR100 LAPSE *DT100M WIND SPEED (MPH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24
>24 TOTAL N 0 1 4 16 1 0 22 NNE 2 5 10 13 7 1 38 NE O 6 17 14 7 0 44 ENE 2 6 21 40 4 0 73 E O 3 22 38 3 0 66 ESE 4 7 31 26 2 0 70 SE 2 17 17 7 1 0 44 SSE O 10 22 24 4 0 60 S 4 11 30 28 3 0 76 SSU 3 9 21 38 4 0 75 SU 3 9 35 43 20 0 110 O USU W
UNU 5 i 0 10 10 9 28 27 18 52 50 39 15 3 0 0 110 91 i 1 0 67 NU i 10 15 36 1 0 63 NNU 0 0 7 27 3 0 37 ' TOTAL 27 123 325 47.1 79 1 1046 PERIODS OF CALM (HOURS): 0 , VARIABLE DIRECTION 0 ! __ HOURS OF MISSING DATA: 718 () 1 l l
ATTACHMENT 7-3f O HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 STABILITY CLASS: G DT/DZ ELEVATION: SPEEDtSPD100 DIRECTION *DIR100 LAPSE *DT100M WIND SPEED (MPH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 6 19 14 1 0 42 NNE 2 10 25 8 0 0 45 NE 0 12 23 37 7 0 79 ENE 3 15 29 29 4 0 80 E 5 12 26 32 2 0 77 ESE 4 13 16 20 1 0 54 SE 7 16 15 14 2 0 54 SSE 1 9 15 11 2 0 38 S 2 7 19 11 5 0 44 SSU 2 10 18 14 8 0 52 SU 2 8 20 23 14 0 67 USU 2 8 27 20 11 0 68 O U UNU 3 0 7 3 12 21 21 22 5 0 0 0 48 46 NU 1 7 20 24 2 0 54 NNU 2 5 22 13 1 0 43 TOTAL 38 148 327 313 65 0 891 PERIODS OF CALM (HOURS)* O VARIABLE DIRECTION O _ HOURS OF MISSING DATA 718 82 O
i i ATTACHMENT 7-3g O HOURS AT EACH UIND SPEED AND DIRECTION PERIOD OF RECORD = 87010101-87123124 STABILITY CLASS: ALL DT/D2 ELEVATION: SPEED *SPD100 DIRECTION *DIR100 LAPSE *DT1 _____________________________________-__________________00M ________ UIND SPEED (MPH) UIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 12 69 124 121 22 2 350 NNE 20 71 107 126 33 4 361 NE 10 125 333 363 41 1 873 ENE 16 128 230 207 15 E 0 596 20 85 212 159 15 0 491 ESE 29 106 154 111 7 SE 0 407 29 118 166 64 4 1 382 SSE 8 77 113 136 12 S 0 346 13 83 224 152 23 0 495 SSU 13 87 227 178 27 SU 2 534 l 17 111 254 188 61 0 631 USU 18 101 214 186 67 U 1 587 19 117 228 269 69 6 708 ! UNU 16 106 175 216 44 NU 4 561 i 21 84 139 148 19 7 418 NNU 10 62 138 84 8 302 __________________________________________________0____________ TOTAL 271 1530 2708 467 28 8042 _____________________________.3038 _________________________________ PERIODS OF CALM (HOURS): 0 UARIABLE DIRECTION 0 HOURS OF MISSING DATA
- 718 -
)
83
ATTACHMENT 7-4 O PLANT HATCH 10m METEOROLOGICAL TOWER WIND ROSE JANUARY 1,1987 THROUGH DECEMBER 31, 1987 1 1 l l l l u 2
- I
- I t l : 2 2 : I WDC ROSE (WDGg FROM) t l 0 l aWDS SPEED LESS TNM3.5 MH
+WDC SPEED LESS THM7.5 WH xWDC SPEED LESS THM12.5 MH ,WDC SPEED GREATER THM 12.5 MN 0.9 PERCENT CALM 8 l
l 84
1 l l ATTACHMENT 7-4a I O PLANT HATCH 10m METEOROLOGICAL TOWER WIND ROSE JANUARY 1,1987 THROUGH MARCH 31, 1987 l H
$ 1 I
- i t J l 1 :: t WDe ROSE
, (WDeg FROM)
II y 1 O 4 WDC SPEED LESS THM3.5 MH I
+WDW SPEED LESS THM7.5 MH xWDC SPEED LESS THMit.5 MH ,WDC SPEED GREATER THM 12.5 NH 9.9 PERCENT CALM 8 I
O
ATTACHMENT 7-4b PLANT HATCH 10m METEOROLOGICAL TOWER WIND ROSE O APRIL 1,1987 THROUGH JUNE 30, 1987 l l t j x = -
- l WDe n
t O a 4 WDC SPEED LESS THM3.5 MH l
+WDG SPEED LESS THM7.5 WH xWDG SPEED LESS THM12.5 MH .
l
,WDC SPEED GREATER TNM 12.5 WM 9.9 PERCENT CALitS 0
86 O
ATTACHMENT 7-5 PLANT HATCH 60m METEOROLOGICAL TOWER WIND ROSE JANUARY 1,1987 THROUGH DECEMBER 31, 1987 P 2
- I (WIM RtPD t
a y/ 4WIPS SPEED LESS THAN3.5 MH ' --
+WDC SPEED LESS THAN7.5 WH xWDC SPEEG LESS THKitt.5 WH ,WDC SPEED GREATER THAN 12.5 MH 9.9 PERCENT CALits 1
4 e s 87 O
1 l ATTACHMENT 7-6 PLANT HATCH 100m METEOROLOGICAL TOWER WIND ROSE l JANUARY 1,1987 THROUGH DECEMBER 31, 1987 l I 4
/
<> I n 2 1 3
l 2
- X WDS RIME (IdDeg FROPD I
O aldDe SPEED LESS TNM3.5 tFN
,WDC SPEED LESS THM7.5 IFH xWDS SPEED LE33 THAN12.5 tFM 4 WING SPEED GREATER THAN 12.5 FFH S.0 PERCENT CALMS !
l i l i O I a r - -w - w -- e , e ,-- - - - - - - ,-
ATTACHMENT 7-6a O PLANT HATCH 100m METEOROLOGICAL TOWER WIND ROSE ' JANUARY 1,1987 THROUGH MARCH 31, 1987 t o t 2
\ '
l 2 i 1 (WDS ROrl) N " V t
\
O 4WDW SPEED LESS THM3.5 WH
+WDC SPEED LESS THM7.5 WM xWDW SPEED LESS THMit.5 f1PH
.WDC SPEED GREATER THAN 12.5 FFH 8.8 PERCENT CALrtS f
89 O
ATTACHMENT 7-6b PLANT HATCH 100m METEOR 0 LOGICAL TOWER WIND ROSE O- APRIL 1,1987 THROUGH JUNE 30, 1987
?
i * (M Rott) t u O o 4M SPEED LESS TH#13.5 MH 4M S"IED LESS THM17.5 MH xM SPEED LESS THArt12.5 PFH
.M SPEED GREATER THAN 12.5 tFH 0.0 PERCENT CALitS j
90
ATTACHMENT 7-6c PLANT HrlCH 100m METER 0R0 LOGICAL TOWER WIND ROSE JULY 1,1987 THROUGH SEPTEMBER 31, 1987 O I 1 I { , l
- ; I WDS ROSE
[ (WDSg FRON) t l aWDC SPEED LESS TMNt&.5 WN
+WDC SPEED LESS TWMt?.5 WM xWDC SPEED LESS THM11E.S WM ,
,WDC SPEED GREATER THNi 12.5 MM 0.0 PERCENT CALitS j i
l f 91 0
ATTACHMENT 7-6d PLANT HATCH 100m METEOROLOGICAL TOWER WIND ROSE
.O OCTOBER 1,1987 THROUGH DECEMBER 31, 1987 i 1 l : ! x : I WDe t
O , 4WDC SPEED LESS THANS.5 MH
+WDS SPEED LESS THAtt?.5 NH xWDe SPEED LESS THAHit.5 WH
,WDS SPEED GREATER THAtt 12.5 WH 8.8 PERCEffT CALits O
4- d A ' ^ " _ '_ . _ . - - . - - - .
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.u _. ATTACMENT 7-7 PLANT HATCH MONTHLY AVERAGE !
' . . .K . . . ' _ c ' _-: AND AVERAGE 0" THE DAILY EXTREMES OF !
' O - c = h,- .
t _ AMIENT TEMPERATURE 10m j JANUARY 1,1987 THROUGH DECEMER 31, 1987
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- i =._=. I .I ATTACHMENT 7-7a .__
_ - PLANT HATCH MONTHLY AVERAGE ~ o __
~EEi M b----
AND AVERAGE M OF THE DAILY EXTREMES F~ OF DEW - POINT TE PERATURE 10m _ E
._.1..,__.._.r.- .-.__E __
JANUARY 1, 1987 THROUGH OECEleER 31, 1987
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, SEP Ou tm u d, , 0.A i i, i.- .
i ATTACHMENT 7-8 HATCH METEOR 0 LOGICAL'T0WER MONTHLY PRECIPITATION DATA O i Month Inches January 7.31 February 5.30 March 4.30 ' April 0.22 May 5.99 ' June 6.03 July 2.21 August 1.95 : September 4.13 October 0.00 November 2.18 , December 0.47 TOTAL 40.09
- O -
1 ) i d
)
i I J i 95 l
~
ATTACHMENT 7-9 HATCH DAILY PRECIPITATION DATA FOR 1987 O _ Month Percent (inches) Month Percent (Inches) January 4 2.33 May 12 January 5 0.90 0.11 May 13 l January 10 0.41 1.09 : May 15 1.87 January 15 0.42 May 20 ! January 16 0.93 2.12 j May 23 0.01 January 17 0.24 January 18 0.37 TOTAL G January 19 0.24 ! January 21 0.89 January 22 0.79 January 25 0.58 ' TOTAL 73T February 2 0.31 February 5 June 4 1.19 0.03 June 9 ; February 6 0.02 ' 0.62 June 10 February 7 0.34 0.17 February 16 June 16 1.09 1.22 June 17 February 20 0.10 0.06 February 21 June 19 1.70 0.49 June 20 February 22 0.04 O February 24 February 27 0.85 0.03 0.02 June 21 June 22 June 23 0.10 0.32 February 28 1.29 0.03 June 25 1.12 TOTAL G June 26 0.19 TOTAL M March 1 0.63 March 7 July 1 0.0$ 1.90 July 3 March 8 0.07 0.02 March 9 July 4 1.15 0.12 July 6 March 12 0.08 0.11 March 18 July 8 0.37 0.10 July 12 , March 19 0.31 0.02 ' March 25 July 25 0.18 0.14 July 28 March 26 0.13 0.09 March 29 July 30 0.22 ' 0.24 March 30 0.58 TOTAL M , TOTAL U April 3 0.20 April 15 August 11 0.04 0.02 August 12 TOTAL U 0.15 August 15 0.27 August 26 1.11 i 4 August 31 0.38 ! Q ._. TOTAL G l i 96 ' l
1 ATTACHMENT 7-9a Month Percent (inches) Month Percent (Inches) September 1 1.05 November 4 0.47 September 2 0.18 September 3 November 17 1.09 0.09 November 19 0.02 September 4 0.23 1 November 26 0.60 September 5 0.02 TOTAL September 6 Y"TF September 7 1.24 l 0.07 September 9 0.08 September 11 0.07 September 12 0.36 September 19 0.33 September 30 0.41 , TOTAL G 1 I October None December 15 0.29 December 28 0.18 TOTAL ID7 O li l 1 l l \ l i 97 !
- 1
l- [ Georgia Power Company i Plant E. I. Hatch Semi-annual Deport j Plant Radioactive Effluent Releases )
; July 1 through December 31, 1987 ,
i i I ! l i , i Appendix A r i f l r i t : ! i i i I i I f I I s e n i i c O 1 i l 1
! I I
j l 6 I t I ! -l } l l i i
- i i l h
I i. 1
,-y,w3m--,--e-wv---,--w-,ww.y-v-m-, -w w yye ww - v e v- me -se- e r mw es' + - w - -w w m, -e w rv
GEORGIA POWER COMPANY I PLANT E.I. HATCH . l pAGE 1 Of 2 FORM TITLE: (] DOCUMENT CHANGE RE00EST I
% i! Change Affects ( ) Unit Ori's ( ) Unit Two (><) Units One and Two II Il REQUEST DATE: c5-f 2 8*7 REQUEST NO: Sl* l~7 REVISION NO: O I l_.
1I ll Request Initiated: (><) On-Si te, ( ) Off Site By: LJ. d . Rc< lex e s IRI o IEl Document (s) Affej:ted:- Offid: Dow C e l e. ., l e,i. n Menor.l /OOCM) ' 16l Section/
Title:
_4chl_ of Centents . 2. 0 / Ge s e cos E f f L e nts Iul lll lAl Description of proposed Change (Attach marked up copy of affectep document (s)]: ITl Adel L u .ld , . c r d e_ _sI couwd. I c nl ; le, b en fe A lsf ok omet a 101 _ cM L:n't r:t h cu.nT, M Maehrent 2 Gr fk emf c he m N lRl O lYl lI Reason for Change: Ihew. crecsowlek,vn eee v fL occm to d ce < <aro.,el t ICl fe A e k.,w _ L n ,. i b l/ 6 , 3col E n & n ~ re. l (e<L-..et Zim G . c r.e.,,' o rm t 101 .n Chct D st. h .chemso M N _ occ m <v f L f a nroad ' ,v ._ , f fi .. ,' 4 kr w pc,6 INI ' IPI Environmental Impact Statee nt RerNired: ( ) YES C><) NO lLI Described in FSAR: C><) YES ( ) NO , 111 Unreviewed Safety Question: ( ) YES C;4 N0 lAl Priority: ( ) Emergency Relief ( ) Reload licensing C><) Individual submittal
., No. \ttachmeats 2 '""" # ""
IEl i" l1 ll EN(jNEER
/ c5 tt L'1 DATE fh ENE. SUPV.
/ 5 U/h liik'*h'* '* /P"I 5t$47 \
'0 ATE pSUPT. R16. @MP., DATE~
li Ii ll ' FORWARD TO PR8 SECRETARY FOR INITIAL PR8 REVIEW M.1 / sht/#7 ll - lI ll Il PRB Reconnends Change: ( d YES ( ) NO . N-do S-/7-87 PR8 MEETING NO. DATE lPl If no, give reason: IRl li Request: ( Approved ( ) Disapproved e-*v / 6Mf/f7 {
""'^ ^ ^ MANAGER DATE ll If di'sapproved, give reason: i i1 - i
\
O
~
ENG-0015 Rev. 0 43RC-CPL-001-OS
g.. DOCR No. R7 - n TABLE OF CONTENTS ATTACHMENT No. 2-Q( SHEET l OF _ 1 P.ASL 1.0 LIQUID EFFLUENTS 1. 0-1 1.1 LIQUID EFFLUENT MONITOR SETPOINTS 1.1 -1 1.1.1 Liquid Radweste Effluent Monitors 1.1 -1 1.1.2 Plant Service Water Monitors 1.1 -9 1.2 00SE CALCULATION FOR LIQUID EFFLUENTS 1,2-1 1.3 DOSE PROJECTIONS FOR LIQUID EFFLUENTS 1,3-1 1.3.1 Monthly Dose Projections 1. 3-1 1.3.2 Dose Projections for Specific Releases 1.3-2 e 1.4 DEFINITIONS OF LIQUID EFFLUENT TERMS 1. 4-1 J 1.5 LIQUID RA0 WASTE TREATHENT SYSTEMS 1. 5-1 1.6 NIXIPS OF LIQUID WASTE TANKS 1.6-1 - 2.0 GASEOUS EFFLUENTS 2.0-1 2.1 SASE005 EFFLUENT MONITOR SETPOINTS 2.1 -1 2.1.1 Unit 1 Reactor Building Vent Stack, 2.1-1 Unit 2 Reactor Building Vent Stack, +nd
- Unit 1 Recombiner Building Vent 2.1.2 ' Main Stack 2.1 -4 O 2.1.3 Determination of Allocation Factor, AG 2.1 -6 2.2 GASEOUS EFFLUENT DOSE RATE AND DOSE CALCULATIONS 2. 2-1 9
2.2.1 Unrestricted Area Boundary Dose Rate 2. 2-1 2.2.1.a Dose Rates Due to Noble Gases 2. 2-1 2.2.1.b Dose Rates Due to Radiciodines, 2.2-2 Tritium, and Particulates i 2.2.2 Unrestricted Area Air Dose and Dose 2.2-4 to Individual 2.2.2.a Air Oose in Unrestricted Area 2.2-4 l 2.2.2.b Dose to An Individual in 2.2-5 Unrestricted Area 2.2.2.c Dose Calculations to Support 2.2-12 I Other Specific Technical Specifications u . dn lct,b HATCH 00CM, REY 1 5/11/84 1 1
1.n caldlT.on ic t hc u. leur re.ke.sc po'enT> , relac,e also rncf l:<. rncck fror, , ,
.. nt,.J <ent;lct..n sysfc.scs) bu.ld,q E n .rc n ~ nfcche J 4 c L nmst
- a. oug~1 6pecJ.cJi.~ a u.nv.acl6% th<_
r, kompro,;JtJ
. pc A Rcd.oy cy. a 2.0 GMEOUS EFFLUENTS
, norrnc lly At Flant Hatch there are four points where radioactivity is Y released to the atmosphere in gaseous discharges. These four release points are:
. The main stack which serves both units. l
. Unit 1 reactor building vent stack.
- Unit 2 reactor building vent stack, DOCR No. D -n !
t
- Unit 1 recombiner building vent. TTACHMENT No. z ;
SHEET 2. of 7 _ l The main stack serves as the discharge point for the following release J sources from each unit:
- Mechanical vacuum pumps. !
' 1
- Off-gas system.
. Gland seal exhaust.
- Standby gas treatment system through which drywell purges are discharged.
O(
- The waste gas treatment building ventilation also discharges through the main g 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.
- Radwaste building.
The Unit I recombiner building vent discharges directly to the atmosphere. l i 4
. Gaseous ef fluent monitor setpoints are required only for noble gas monitors serving thh 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
- O l
t HATCH 00CM, REY 1 5/11/84 2.0-1
DOCR No. D . n ATTACHMENT No. L O 2.1 GASEOUS EFFLUENT MONITOR SETPOINTS $HEET c3 OF ~I The gaseous monitor setpoint values detemined in the following sections will be regarded as upper bounds for the actual setpoint adjustments. That is, setpoint adjustments are not required to be performsd if the existing setpoint level corresponds to a lower count rate than the calculated value. Setpoints may be established at values lower than the calculated values, if desired.
. 1 If no release is planned for a particular pathway, or if there is no detectable activity in the planned release, the monitor setpoint should be l established as close to background as practical to prevent spurious alarms l M and yet alarm should an inadvertent release occur. l l
4 If a calculated setpoint is less than the socitor reading associated with the particular release pathway, no release may be made under current conditions. ) Under such circumstances, the number of simultaneous release pathways may be reduced or contributing source terms may be reduced and the setpoint
; i
( recalculated. { i l 1 6 2.1.1 Unit 1 Reactor Buildine Vent Stack. Unit 2 Reactor Bu11dino Vent Stack. a -end Unit 1 Recombiner Bu11 dine Vent. onel Bu.ld.no Echcud alone.de.J " Ant; lean Monitors: 011-K61g A and 8, 2011-K636 A and 8. 011-P003 A and 8 For the purpose of implementation of RETS 3.14.2 (Unit 1) and 3.3.6.10
- (Unit 2), the alarm setpoint level for these noble gas monitors will be calculated as follows
- , Cs - the monitor reading of the noble gas monitor at the alam setpoint concentration. ,
j
--__ -_ j ordfor iMenfiN N ion br bu'. lc) .'n j jo g a u., :a 4
~
r , t ac,g.acn,c, c.thousI .:. ra,ougmenb.d emu.,. 3 j , HATCH 00CM, REV 1 5/11/84 2.1 -1 l {. 1 . . , _ _ _ ___ _ . _ _ _ _ . _ . .. ___ _ . - - .
- Ou'ib.'ng Ethc u d Augne.nYej Venf,le. Con 2.1. 3 Determination of Allocation Factor. A6 When simultaneous gaseous releases are made to the environment, an (administrative) allocation factor must be applied to each discharge pathway. This is to ensure that simultaneous gaseous releases from the site to unrestricted areas will not exceed the dose rate limits specified in RETS 3.15.2.1 (Unit 1) or 3.11.2.1' (Unit 2). For Plant Hatch, final discharge pathways which may be released simultaneously are:
. The main stack. n
- Unit 1 reactor building vent stack. DOCR No* -
- Unit 2 reactor building vent stack. ATTACHMENT No. 2-sHm OF 7
- Unit 1 recombiner building vent.
W The allocation factor for each discharge pathway must be between 0 and 1, and the sum of the allocation factors for the simultaneous releases must not exceed 1. There are three methods by which allocation factors may be detensined: ( 1. The allocation factor for a particular release pathway may be administrative 1y selected based on an estimate of the fraction of the total dose rate (from all simultaneous releases) which is contributed by the particular release pathway.
- 2. The allocation factor may be calculated using the expression:
AG = 1/n where: n = the number of release pathways to be released simultaneously.
- 3. The allocation factor may be determined for a particular discharge i pathway by calculating the ratio of the total-body dose rate due to noble gases released from the particular discharge pathway under consideration to the total-body dose rate due to noble gases in all simultaneous releases.
4 HATCH 00CM, REY 1 5/11/84 2.1-6
. 2.2 GASEOUS EFFLUENT DOSE RATE AND DOSE CALCULATIONS 2.2.1 Unrestricted Area 8oundarv Dose Rates DOCR No. b . n ATTACHMENT No. L 2.2.1.a Dose Rates Due To Noble Gases SHEET 0 _ OF 7 i For the purpose of implementation of RETS 3.15.2.1.a (Unit 1) and 3.11.2.1.a (Unit 2), the dose rate in the unrestricted area due to noble gases shall be j calculated as follows: ' !
Ot
= the total body dose rate at time of release (arem/yr). * =
I (X/0)s I K1 Qy i + IVi Qs i (9) v i 1 . Os
= the skin dose rate at time of release (ares /yr).
1
=
Iv (X/0)Gi I (li+llM)0v 1 1
+ I (l (X/0)E i + 1.1 Bj) Qjs (10)
*( . . .
1
'
- Terms were defined previously in Section 2.1.1 and 2.1.2.
The dose rate limits are site limits at any point in time; therefore, dose rates are sumed over all releases occurring simultaneously. For Plant Hatch thelemhvent releases are:
. Unit 1 reactor building vent stack. .
. Unit 2 reactor building vent stack.
. Unit I recombiner building vent.
The Inly elevated release is the main stack which serves both units.
. Simultaneous releases may include any combination of these four release l points.
t
- Oui! ding Exhoud /\ugnenfeJ /enf lc.t.on i O i
HATCH 00CM, REY I 5/11/84 2.2-1
- _ _ . -. ~. --
r. s
- 2. 2.1. b Dose Rates Oue to Radiciodines, Tritium, and Particulates For the purpose of implementing RETS 3.15.2.1.b (Unit 1) and 3.11.2.1.b (Unit 2), organ dose rates due to radioiodines, tritium, and all radioactive materials in particulate fom with half-lives greater than 8 days are i
required to be calculated for the inhalatica pathway for the child age
~
1 group. The child age group would experience the highest potential dose rate via the inhalation pathway. In accordance with Appendix 0 to Reference 3, noble gases are excluded from these calculations. These dose rater are calculated as follows: . j Do = the organ dose rate at time of release (arem/yr). , e- . . . i = I (X/Q)6 IPjoQjy + (X/Q)gIPjoQjs (11) ' v i i where: (X/Q)6 = defined in Section 2.1.1. DOCR No. S7 -n ( ATTACHMENT No. c ! g (X/Q)E = defined in Section 2.1.2. SHEET 6 op 7 ! Qiy = the release rate (wC1/sec) of radiciodines, tritium, and particulates (required by RETS 3.15.2.1 (Unit 1) and 3.11.2.1 (Unit 2) from the Unit I reactor building vent stack, the Unit 2 reactor building vent stack end the . Unit I recombiner building vent, and kld.% e.shoud ougi v.nkd vt.nUld..n. Qjs = the release rate (wCi/sec) of radiciodines, tritium, and l f ] particulates (required by RETS 3.15.2.1 (Unit 1) and ) 3.11.2.1 (Unit 2) f rom the main stack. i . l } ;
- Pjo = the organ dose parameter for organ o and radionuclide i i (mren/yr per wC1/m') for inhalation detemined as i' follows:
O l '
- NATCH 00CM, REV 1 5/11/84 2.2-2
. _ _ _ _ _ _ . , __ , _ _ . . _ . _ _ _ . . _ _ _ _ , . , ~ . , , _ _ _ _ _ _ .
' Odi!ciq E.shc.ust /\ugcv_nLJ V,.nt;le.f,L O( 2.3 METEOROLOGICAL MODEL 2.3.1 Atmosoh' oric Dispersion Atmospheric dispersion may be calculated using the appropriate form of the
! sector-averaged Gaussian model. Gaseous releases are considered to be either elevated or at ground-level. Included in the ground-level category are releases from: ,
. Reactor building vent (Unit 1).
. Reactor building. vent (Unit 2).
. Recombiner building vent (Unit 1).
g Releisesfromthemainstackareconsideredtobeelevated. 2.3.1.a Ground-Level Releases X/Q = the sector-averaged annual average relative concentration at any distance in the given sector. (
=
2.032 4 Kr I "ik (see m-- , DOCR No, M - n jk Nujk r IZk ATTACHMENT No. 2-where: 2.032 = (2/v)1/3 divided by the number of radians in a 22.5' sector ] (2v/16) . , l l l 4 = the plume depletion factor for all radionuclides other than noble l gases at a distance r shown in Figure 2.3-3. For noble gases the I depletion factor is unity. Only depletion by deposition is considered since depletion by decay would be of little significance at the distances considered. 1 J j i l HATCH ODCM, REV 1 5/11/84 2.3-1 I l
1- .iI i l l i j -; i I l 4 l Georgid Power Company { l Plant E. I. Hatch j j semi-annual Report . 1 Plant Radioactive Effluent Releases i ) July 1 through December 31, 1987' l i .i ; i 1 Appendix B + ! s I { ..- i
- 4. .
l 1 i 4 d e l f i D I I 4 ! i !O 4 l 1 i t i i t
- a .
i ; l ! i I 1 l l f I d i__._ _ _ _ . _ _ _ _ _ _ . _ _ . . _ _ _ _ . _ _ _ _ ___
l I GEORGI A PiNER COMPANY l PLANT E.I. HATCH l PAGE 1 0F 2 ~ FORN TITLE: DOCUMENT CHANGE I?E00EST Change Affects ( ) Unit One ( ) Unit Two (><) Units One and Two ll ! ll REQUEST DATE: L, d - #1 REQUEST NO:. D-2i REVISION NO: O ! l l ' II ll Request Initiated: ( ) On-Site, (><) Of f Site By: L J d O # I Ir rie r lRI ~ O lEl Document (s) Affected: OTs ,Ye. Oo se- f_e. l e o l e. fe n M e n o r. I lGl Section/
Title:
M e,n v ( Se e. ArteeL~ nf a f ar ik e , e. c f -.n r r s e3 fectrll lUl ' { lLl - lAl Description of propost dChange (Attach marked up copy of affected document (s)]: lTl fr e_ de s c e . c f y al (k_ es cenov el cL .nraz s is conf e. , nci . , , A rtee L ~ n t 2 . ; 101 - (v ch n,m. J m e., sa v, s e k 6 ,,reu r,,,t . r0 h , L ~. ., f a ' lRl O lYl ll Reason for Change: [N_ reraens be t her orenesel ebe m s c. ca conic,nul lCl .n Idr R6 MB o . m . i J o c o,.e to 6 6 (,'ce s . de re ,L G &n. (h,s tr et r l0l .pnstlim r. em f k F, rst rua e r,e n o f A rt, , L A, ,,f 1. lMI O lPl Environmental Impact Statement Required: ( ) YES (><) NO ! lLl Described in FSAR: C><) YES ( ) NO IIl Unreviewed Safety Question: ( ) YES C><) NO kOC D * "2 ,@ ; lAl Priority: ( ) Emergency Relief ( ) Reload licensing C><) Ind duT1 Idinittal '
. . No. Attachments d 7
L / L w Xl / $-30 0 / $-30D ll ENQINEER DATE ENG. SUPV. DATE A UPT. REG. CONP. DATE ll l l Y'
~
ll ll l1 FORWARD TO PRB SECRETARY FOR INITIAL PRB REVIEW IN / McW ll l PRB Reconenends Change: ( ES ( ) NO [b8I PR8 MEETING NO. [""3 d W DATE lPl If no, give reason: lRl ll Request: pproved ( ) Disapproved W9 h / Y/7 [ A C C ; W MANAGER' OATE
, ll If disapproved, give reason:
l1 ~ 4 } ' l 4 ENG-0015 Rev. 0 43RC-CP1.-001-OS
ATTACHNENT 2 g Discussion of Proposed ODCM Changes I Sections 2.1.1 and 2.1.2 were changed to include the dispersion values for the locations at the site boundary where potential dose rates are expected to be highest. Table 2.1-2 is changes to incorporate modified elevated plume dose factors. The rational for the change is to incorporate dispersion values and elevated plume dose factors calculated from more accurate meteorological data. Tnus the gaseous monitor setpoints and dose rates will be derived from more accurate information. This change does not affect the methodology for calculating gaseous monitor setpoints, doses, dose rates. However, the calculational results will reflect the changes in the values of the parameters used in the calculations. (Higher values for the despersion and elevated plume dose factors will render higher dose rates but lower gaseous monitor setpoints and vice versa.) O, J l 6 1
, O o c c a s o. e -
e1 2-ATTACHMENT No. . mut i a 6 -
)
11 O Section 2.2.2.b was changes to incorporate information pertaining th the critical receptor. A new Table 2.2-12 was created to include specific details related to the critical receptor, such as, its location, applicable exposure pathways and the dispersion and deposition parameters for that location. Information which was contained in the original Table 2.2-12 has been relocated to Table 2.2-13. Also, the exposure pathway factor equations and descriptions which were included in the original Section 2.2.2.c have been relocated to Section 2.2.2.b. The rational for the change is to incorporate specific information pertaining to the critical receptor in one table (Table 2.2-12) so that' any future changes to the critical receptos and/or to the dose ~ parameters might be mostly acconmodated simply by modifying Table 2.2-12. This change does not affect the methodology for calculating doses to an individual. However, a new location of the critical receptor with different exposure pathways has resulted in the anticipation of a lower potential dose. O i 1 l i l i O DOCR No. ATTACHMENT No,_ 80 - 2
- 2. !
sHm 2 or 6 1 i
III Specific dispersion and deposition values were deleted from the definitions of these parameters in Section 2.4. Since these values are contained in the text where they are used and in associated tables, it would i be superfluous to include specific values in definitions. l O ! i 4 1
~
O oaca se. n - 41 4 ATTACHMENT No. 2. snea a or l> .
- O Section 3.0 was c.ianged to add the location of two new milk stations, to delete the locations of two former milk stations, and to show the adjusted locations of some of the TLD stations. The rationale for the change is to provide accurate information for the current sampling locations.
~ (
l O 1 l I l D DOCR No. - at O 1
- ATTACHMENT No. c.
sum 4 a t, i
V O Section 5 was changed to include dispersion and desposition values and elevated plume dose factors based on more accurate meteorological data. Based on these new values and the actual 1980 source term, new values are presented for the potential dose to members of the public due to their activities at four locations within the site boundary. Tables 5.0-1 through 5.0-4 which contain the new dispersion and deposition values and elevated plume dose factors for each location addressed in this section has been added. The rationale for this change is to incorporate dispersion and deposition values and elevated plume dose factors which were calculated based on more accurate meteorolonical data. The four tables permit dose calculations to be performed more ef*.ciently. . ) \ This section is applicable only if the cumulative dose limits of Technical Specification Sections 3.11.2.2, 3.11.2.3, 3.15.2.2, or 3.15.2.3 are
\
exceeded. Doses are not expected to exceed the values presented in this section as long as the Technical Specification limits are not exceeded, e DOCR No. Eh . 2i ATTACHMENT No. 2-SHEET .5 or to
1 VI O Editorial changes to the Table of Contents and the List of Tables and List of Figures were made to support the modifications to the text of the ODCH. Also certain wording changes were m4de to the text in order to present the modifications more clearly. W O DOCR No. D ai O A TT A c s u e s t s o. SHEET l.a OF e-. I' -
TABLE OF CONTENTS Pace 1.0 LIOUIO EFFLUENTS 1.0-1 1.1 LIQUID EFFLUENT MONITOR SETPOINTS 1.1 -1 1.1.1 Liquid Radwaste Effluent Monitors 1.1 -1 1.1.2 Plant Service Water Monitors 1.1 -9 1.2 ?OSE CALCULATION FOR LIQUID EFFLUENTS 1. 2 -1 1.3 00SE PROJECTIONS FOR LIQUID EFFLUENTS , 1. 3 -1 1.3.1 Monthly Dose Projections 1. 3 -1 1.3.2 Dose Projections for Specific Releases 1.3-2 1.4 DEFINITIONS OF LIQUID EFFLUENT TERMS 1. 4 -1 1.5 LIQUID RA0 WASTE TREATMENT SYSTEMS 1. 5 -1 1.6 MIXING OF LIQUID WASTE TANKS 1. 6-1 2.0 GASEOUS EFFLUENTS 2.0-1 2.1 GASEOUS EFFLUENT MONITOR SETPOINTS 2.1 -1 2.1.1 Unit 1 Reactor Building Yent Stack, 2.1 -1 Unit 2 Reactor Building Vent Stack, and Unit 1 Recombiner Building Vent ; 2.1.2 Main Stack 2.1 -4 2.1.3 Determination of Allocation Factor, AG 2.1-6 , 2.2 GASEQUS EFFLUENT DOSE RATE AND DOSE CALCULATIONS 2. 2 -1 i e 2.2.1 Unrestricted Area Boundary Dose Rate 2.2-1 2.2.1.a Dose Rates Due to Noble Gases 2.2-1 2.2.1.b Dose Rates Due to Radioiodines, 2.2-2 Tritium, and Particulates 1 2.2.2 Unrestricted Area Air Dose and Dose 2. 2 -4 to Individual 2.2.2.a Air Dose in Unrestricted Area 2.2-4 2.2.2.b Dose to An Individual in 2.2-5
- 6 Unrestricted Area 2.2.2.c Dose Calculations to support 2. 2-}2'8 Other Specific Technical Specifications i DOCR No. D aL ATTACHMENT No. 8 G SHEET 1 OF ___db HATCH 00CM, REV 1 5/11/84 1
LIST OF TABLES O Table Title Page
- 1. 2 -1 Bioaccumulation Factors 1.2-4 1,2-2 Adult Ingestion Oose Factors 1.2-5 1.2-3 Site-Related Ingestion Dose Commitment Factors, 1.2-7 Aj, (Fish Consumption) 2.1 -1 Dose Factors for Exposure to a Semi-Infinite 2.1 -8 Cloud of Noble Gases 2.1 -2 Dose Factors for Exposure to Direct Radiation 2.1 -9 from Noble Gases in the Elevated Finite Plume ,
2.2-1 Inhalation Oose Factors for Infant 2.2-19 2.2-2 Inhalation Oose Factors for Child 2.2-22 2.2-3 Inhalation Dose Factors for Teenager 2.2-25 2 . 2 -4 ' Inhalation Oose Factors for Adult 2.2-28 2.2-5 Ingestion Oose Factors for Infant 2.2-31 2.2-6 Ingestion Oose Factors for Chilti 2.2-34 2.2-7 Ingestion Dose Factors for Teenager 2.2-37 2.2-8 Ingestion Oose Factors for Adult 2.2-40 2.2-9 External Dose Factors for Standing on 2.2-43 Contaminated Ground 2.2-10 Individual Usage Factors 2.2-45 2.2-11 Stable Element Transfer Data 2.2-46 . O 2.2-12 Sit: u. a W<. ;ifi: (;r e..... n.sw.... M' n't;e.",..h::a... 2.2-13 Site-Specific (or Default) Values to be
.,. t: 5: 2.2-47 2.2-48 I
Used in Additi:d Pathway Factor Calculations 3.0-1 Radiological Environmental Sampling Locations 3.0-3
- 2. 2. - t 2 Con bollinq Accep-IV l s.o-I L oakn sr eet f'e Pnelor' .-f" T. o - t k Rads;le Pu x.
[ 0 - 2. l-oca:bk- Speeihe. Pne.& & S.o - 4
, -h e C91,g A rea.
S.:o- 3 L.. akn - spa L Pau~}< rs fw c.o s' L Reue d w heer s.o- 4 t-odn Pea ~ek & g. o - c O ^' ""' Sp'eake.
"" " l HATCH 00CM, REY 1 5/11/84 iii DOCR No. b . 2_1 -
ATTACHMENT No. a smT 2. or M i
LIST OF FIGURES O Fioure Title Pace 1.1 -1 Example Calibration Curve for Liquid Effluent Monitor 1.1-10
- 1. 5 -1 Liquid Radwaste Treatment System (Unit 1) 1.5-2 1.5-2 Liquid Radwaste Treatment System (Unit 2) 1.5-3
- 2. 3-1 Vertical Standard Deviation of Material in a Plume (oZ) 2.3-7 2.3-2 Open Terrain Recirculation Factor 2.3-8 2.3-3 Plume Depletion Ef feet for Ground-Level Releases 2.3-9 2.3-4 Plume Depletion Ef fect for Greater Than 100-m Releases 2.3-10 2.3-5 Relative Deposition for Ground-Level Releases -
2.3-11 2.3-6 Relative Deposition for Greater Than 100-m Releases 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 Radiological Environmental Sampling Location Map 3.0-6 (Beyond the Site Vicinity) d.0 6 Locd.on of cad'.t.ind c.cnfrol steil.n Cr r,'.l k 6.o-9 0
l 6 O ooca No. ra . et HATCH 00CM. REV 1 5/11/84 iv ATTACHMENT No. a MT d of M
l l t where: O V C = the monitor reading of a noble gas monitor corresponding to the grab sample radionuclide concentrations taken in accordance with RETS Tables 4.15.2-1 (Unit 1) and 4.11.2-1 (Unit 2). The monitor response corresponding to the measured concentration is determined from the monitor calibration curve for the particular monitor. (X/Q)G
= the highest annual average relative concentration at the site boundary. (If desired, the annual average relative concentration at the site boundary for the particular release point may be used.) The release points addressed in this section are ground-level releases.
l T. 37 ENE , (X/Q)G = b e x 10-* sec/ms in the-W sector. Ki = the total-body dose factor due to gamma emissions from radionuclide 1 (mrem /yr per vC1/ms) from Table 2.1-1. l Qiv = the rate of release of noble gas radionuclide 1 (vCi/sec) from the vent release pathway under consideration, which is the product of Xiv and Fv where: Xiv = the concentration of radionuclide i for the particular release, and Fy = the maximum expected release flow rate for this release point (Xiy in pC1/mi and Fy in al/sec). l Oss = the dose rate limit to the skin of the body of an individual l
, in an unrestricted area which is 3000 mren/ year.
l Rsy = the monitor reading per mres/yr to the skin. lO DOCR No. &~1 21 l HATCH 00CM, REY 1 5/11/84 2.1-3 ATTACHMENT No. a saur 4 of ch
i R ss
= C+I (Li (iTd)E
- I*I B )i 015 (8) where:
i Vi = the constant, which includes the dose factor, for each identified noble gas radionuclide accounting for the ' gama radiation from the elevated finite plume resulting from the main stack release, in mrem /yr per uC1/sec, from Table 2.1-2. 8t = the constant, which includes the air dose f actor, for each identified noble gas radionuclide accounting for the gamma radiation from the elevated finite plume resulting from the main stack release, in mrad /yr per i vC1/sec, f rom Table 2.1-2. j l l Qis = the rate of release of noble gas radionuclide i I (uci/sec) from the main stack, which is equal to the product of Xis and Fs, where: Xis = the ; concentration of radionuclide i for the main stack I release, and Fs - the maximum expected main stack release flow rate (Xis in uCi/ml and Fs in al/sec). (IId)E = the highest annual average' relative concentration in the unrestricted area associated with releases from the main stack. The main stack is an elevated release. A.lo x 10 ENG
= the 1.0 ; 10 ^ sec/m* in the-W sector.
All other terms were identified previously in Section 2.1.1. l 4 I DOCR No. D 2L l HATCH 00CM, REY 1 5/11/84 2.1-5 ATTACHMENT No. a SHET O OF <3b
TABLE 2.1-2 2 OOSE FACTORS FOR EXPOSURE TO DIRECT RA0!ATION FROM NOBLE GASES IN THE ELEVATED FINITE PLUME * (Location: Site Boundary in We+t- Sector at 440+ m) EN6 i S~+.S~ Nuclide y-Body (V)** y-A i r ( B) *** Kr-8Sm B. 2. t .6,-M E-05 g 6') A M E-05 Kr-85 /, z.6 4r46E-0)'6 f.3 g hME-06 Kr-87 1 4 o -3v59E-04 y. s'i'-arm E-04 Kr-88 /.09 9rBGE-0/3 1./3 4,48E-0/2 Kr-89 9 44 er96E-04 9 87 4 rale-04 Kr-90 7.oo 4rG9E-04 7.38 4rME-04 Xe-131m /. (6 h41 E-06 Xe-133m /.% h40E-06
/,29 4,44E-05 f, n hME-05 Xe-133 /. 3 8 -hME-05 f.43 hNE-05 Xe-135m 2.V2 AME'-04 Xe-135 2.si AME-04 I. 3 3 hME-04 /.4 2. Wr+E-04 Xe-137 9. ff 4rH E-05 / o 2 4-ME-0/4 Xe-138 6./6 fr+4E-04 Ar-41 4. 4 4 4rHE-04 7,3 y 4r94E-04 7,7a 4-95E-04 O
- Values calculated in accordance with methodologies presented in 6 Section 5.2.1 of Reference 1 and Appendix F of Reference 3, with meteorological
- A;;Gdh E. Tab h joint frequency distributions presented in Reference E.' ?c Reguuu f 9 /(.j' mrem-sec_
wC1-yr
*** mrod-see wC'-yr $ 0684n DOCR No. E1 - 2.1 HATCH 00CM, REY I S/11/84 2.1-9 ATTACHMENT No. O SHET b OF s
(3'1
?
4 Og = the air dose due to beta emissions f rom noble gas
) radionuclides (mrad).
o
= 3.17 x 10-* I(X/Q)GINjhjy * (X/Q)E I NjQjs (15)
J v i i e Q r] .- - - d where: Z, o
#r- W
\
Z Nj = the air dose factor due to beta emissions from noble ; 6$ gas radionuclide 1 (mrad /yr per uti/m*) f rom l 1 h Table 2.1-1. U4 OCE O45 (X/Q)E = defined previously in Section 2.1.2. 2.2.2.b Dose to An Individual In Unrestricted Area Dose to an individual from radioiodines, tritium, and radioactive materials in particulate form will be calculated for the purpose of implementation of RETS 3.15.2.3 and 3.15.2.4 (Unit 1), and 3.11.2.3 and 3.11.2.4 (Unit 2). In accordance with Appendix C of Reference 3, noble gases are excluded from these dose calculations. Ooses to an individual are calculated as follows: 76 NOTE: individua At- Plant Hatch,the controlling receptorfs he infa t fag groui> located e NNE see a a dist ce of es, expo _ to tinhalatign, nd-plane, andfass-cow-M pathways [ Oj = dose to an organ j of an individual in age group a from radioiodines, tritium, and radionuclides in particulate form with half-lives greater than 8 days (ares). 6 i -i . ...
- 3.17 x 10-* I Raipj (WVp Qiv + Wsp Ois) (16)
Di b N4 h [ AM eis tek qs jl M CAL uagd, T M A et --asp-es .f g&ua w?, ' n CH 00CM, REY 1 5/11/84 2.2-5 l
where: O 3.17 x 10 8 = the fraction of 1 yr per 1 sec. Wyp' = the pathway-dependent relative dispersion or deposition in the unrestricted area at the location of the controlling receptor, associated with plant vent releases. (X/Q')yp = the annual average relative dispersion parameter for location of controlling (critical) receptor for plant vent releases. (T/Q')yp applies only to inhalation and all tritium pathways. (For all tritium pathways, the Qt' source terts is limited toVo,ltritium.) w e. . fee. Mle 1.2 -42. M _ . ._,m-,..,....._,...._ fr i..let ad e!' +-iti"- - 1:y;-. Wyp' = (0/Q')vp = the annual average deposition parameter for the location of controlling (critical) receptor for plant vent releases. (D7U')yp applies to 41"1 eths. ve tt.a y; c Gr*O P
& ttall ingesNW fAfGys, difh O'-
= 1. x 10- ;- ir, a m te. :cc al&
- tna sitar;.
excep h .f fr;6 h . See. role 2.2.-i2. M valu c. i j O DOCR No. D , Bh ATTACHMENT No. a HATCH 00CM, REY l 5/11/84 2.2-6 SHEU b Of db l
Wsp' = the pathway-dependent relative dispersion or deposition in the unrestricted area at the location of the controlling receptor, associated with main stack releases. (I70')sp = the annual average relative dispersion parameter for location of controlling (critical) receptor for main stack releases. (X7U')sp applies only tb inhalation and all tritium pathways. (For all tritium pathways, the Qi' source term is limited to tritium.) fee 7Mle. Z. A~ld
-fy VAlut -
0.2 4 10-" :::/:' *a th: 74;;E 2edor
- fer irAeleti;r, er,d all - triti"- ^:th' 4 5. l W5p' =
O (D/Q')sp = the annual average deposition parameter for the location of controlling (critical) receptor for main stack releases. (D76')sp applies to-a!! ether -it h 7(rpud-//dne.
. Adtut inqnkyin y:m s , w ' n + 4 e.
- s a -!o- a :-- im a: su ter-rer W l fOm. [ ; j $ , k , s e e 1 d* le 2 2 * ~
The selection of the dispersion or deposition parameter, X/Q or 0/0, is l dependent upon the pathway being considered. The dispersion parameter,
' X/Q, is required for the inhalation pathway. The deposition , parameter, e.it ,qeshow 0/Q,isrequiredfogtheground-planepathwayandth: gr:.; ;;.; ;i k pathwaysy " = n ;., fince tritium is taken up by vegetation directly from surrounding air, X/Q is required for tritium contributions from the P::: : = tilk pathways.
ingeth% i 0 v L% %e.<-nee kn .4 h k~ . DOCR No. EM - 21 HATCH 00CM, REY 1 5/11/84 ATTACHMENT No. 3 2.2-7 g g g g e e
t l hiv' = the cumulative release (uC1), f rom plant vent 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 interest. Oose determinations required by RETS 3.15.2.3 and 3.11.2.3 are on a per reactor basis; therefore, cumulative release quantities must also be reactor-specific. to tritiufP f rom th0 InQtsW (For dose thehjy, contributions due s 310 00L milk pathway g term is limited to tritium.) Qis' = the cumulative release (pCi), from the main 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 interest. Ocse determinations required by RETS 3.15.2.3 and 3.11.2.3 are on 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 between the two units. In absence of evidence that one reactor l
\
contributes a greater quantity of radioactivity than the other over the period of interest, release quantities may be 1 l apportioned equally between the two units. j l Raipj = the pathway-specific, individual age-specific organ dose 1 factor for radionuclide i, pathway p, organ j, and individual age group a. Routine individual dose calculations address 1 the inhalation, ground-plane, Qrass-cow (or goat)-milk, grass-cow-meat, and garden vegetation pathways. However, the I dose pathways actually present at the controlling location, as well as the controlling individual age group, are
$ determined through the Land Use Census for the site. Pathway
, factors Rajpj are datermined as shown in the following subsections.
(Fw kse coM&n-s dn 4 4r W k n G 4 4" ha- p e % ', 'k $g,' 4erm is lin:M h Mk..) DOCR No 20 HATCH 00CM, REV 1 5/11/84 2.2-8 * - 21 ATTACHN.ENT No, a smEr to or A
1 As stated earlier, the controlling receptor for Plant Hatch 4: :n '-fant e.g0::d t: iah ? 13ti^a, ;-^uad aieat, 2nd grat: :: mi',k ;;tNrj; .- 13 [fG4k M IAS[C 2* M / A - i Plant Hatch site-specific values, or appropriate def ault values, required in the pathway factor determinations ler the-wWc2E re::;ter are presented in Table 2.2-1. Inhalation Pathway Factor , R aipj = K'(BR)a (OFAjj)a (mrem /yr per uCi/m8) where: K' = the constant of unit conversion, 10* pCi/uti. (BR)a = the breathing rate for a particular age group, in , ms/yr, from Table 2.2-10. O 0FAi ja = the inhalation dose factor for receptor age group a, organ j, and for radionuclide i, in mrem /pci, from Tables 2.2-1 through 2.2-4. i l Ground-Plane Pathway Factor l t Raipj = K'K' (SF')(DFGjj) ((1-e i )f\1) ( ,,arem/yr per uCi/sec) r where: 1 i K' = the constant of unit conversion, 10* pCi/uci. I K' = the constant of unit conversion, 8760 hr/yr. -l j i l HATCH 00CM, REY l DOCR No. M 21 I 5/11/84 2.2-9 ATTACHMENT No. a I
, SHET 1 t OF db L. ;
1
N gjo &c $$e l h'S $ 0 (ce f d fAf f rd y h f e/_feeb% 2 22.C f ffge. f. ) - /8 llic.fdm a cbW Ob $fcb N 2 2.2.c. p); fi O(en be co m e. pad d Sec kn 2. 2.2. b. H = the absolJte humidity of the atmosphere, in gm/m8 0.75 = the f raction of total feed that is water. l 1 l 0.5 = the ratio of the specific activity of the feed grass water I 1 l to the atmospheric water. Other parameters and values as previously defined. E 2.2.2.c Dose Calculations To Support Other Specific Technical Specifications 1 In the event radiological impact assessment becomes necessary to implement RETS 6.9.1.12 or 6.9.1.13, dose calculations will be performed using the equations in Section 2.2.2.f. with the substitution of average meteorological parameters for the period of the report and the appropriate pathway receptor dose factors (Raipj)* For the purpose of implementing RETS 3.16.2, dose calculations may be performedusingtheequationsinSection2.2.2.k.substitutingthe 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. The receptor for which dose calculations may be required in order to implement RETS 6.9.1.12, 6.9.1.13, or 3.16.2 may not be the previously ' identified critical receptor. The receptor age group and exposure pathways present (and applicable) at the location of inttrest must be determined. -h-2dditi:n t: th: inh:10 tier, ;"cend pl:n:, :nd ;r:55 '"U 5!k p;tN 7
-pr::::ted h S::tien ?.2.2.5. it :y 5: : ettan te :en-ider thir gr :: ::a net end/:r the ; rder "e;et:ti:n ;:th=y:r The equations for cplculating the pathway factors Raipj i ? : - I ~~ I 5- '^ ^ ~
- :r: Were presentedje4+w ft:t:ri::lly, e!!E ; :ts h!"e n t i::n pr:teet within -?
ii:: Ofh':nt":t:5. u,m ue., 4-d:r te f::ilit:t: i pl:=ntati:+d-4E-TS' l 3.15.2 in th: :;ent -in este are 10::::d Jith'- 5 051:: f ^1.6 Ha kh, thir ! ta" tic- f:r ::1:el:tia; 'he ; :: ; :tmilk p;th:y fettee 1: Olw ,
, In Secbh 2.2.2.N _
DOCR No, g7 HATCH 00CM, REV 1 S/11/84 2.2.12 ATTACHMENT No- $ , snar iz - CF .24 l
J
+re3ented. Plant Hatch site-specific values, or appropriate default values, required in the pathway f actor determinations are presented in Table 2.2-13.
.G_r. ass-Cow-Meat Pathway Factor R aipj . g. F(Vap) Ff (r)(OFLjj)a 5+(. 3}e-Aith e-Ajtf (19)
Ai + Aw Yp Ys (m* mrem /yr per uCi/sec) where: K' = a constant of unit conversion,10* pC1/pci. QF = the cow's consumption rate, in kg/ day (wet weight). Uap = the receptor's meat consumption rate for age group a. in kg/yr, from Table 2.2-10. Yp = the agricultural productivity by unit area of pasture feed grass, in kg/ma. Ys = the agricultural productivity by unit area of stored feed, in kg/ma. Fr = the stable element transfer coef ficients, in days /kg. (See Table 2.2-11.) . I
)
l the fraction of deposited activity retained on feed grass r = (1.0 for radioiodines; 0.2 for particulates). 6 (OFLjj)a = the organ ingestion dose factor for the ith radionuclide for the receptor in age group a, in eres/pci, from Tables 2.2-5 through 2.2-8.
- O DOCR No. D . 21
- ATTACHMENT No. Q HATCH 00CH. REY i 5/11/84 2.2-13 _
N O OF M l ~
^
f5 = the fraction of the goat feed that is pasture grass while the goat is on pasture (dimensionless). For tritium in milk, the grass-goat-milk pathway f actor is a special case due to the fact that thc cor.ccntre. tion of tritium in milk is based on airborne concentration rather than deposition: Raipj " K'KIm0FUap(DFlij)a (0.75(0.5/H)) (mrem /yr per uCi/m*) (24) where: . K = a constant of unit conversion 108 gm/kg. H = absolute humidity of the atmosphere, in sm/m8 0.75 = 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. Other parameters and values are given above. i Y ea 3 a.a c 6 @ a.2-n ~r l
. A4-B & /sq DOCR No. U -
d 0680n HATCH 00CM REV 1 5/11/84 2.2-18 I I
, hM h T.ABCE 2 -12 U SITE-SPECIFIC DEFyA VAlyE[TO JC USED ,1N PAT AY FAAruR CSCULATI
/The crtMu; iic pim is er, infant-exDeswd to the inheletion. raisnd-plesVi
/and-4r4ss-cow T. ilk-eathwevM Pa rameter Description Value Inhala it R)a reath rate [infan 140(ImM'
( ija I alatio ose fa r forjn ant / Tabi .2-1f Tround plane { SF' Shielding factor due to structure 0.7 (OFG)ij Ground-plane dose factor Table 2.2-9 (same for all age groups)
$ Grass-Cow-Milk Feed consumption rate for cow 50 kg/ day 6y ,,)3 QF V ap Milk consumption rate fora mt na 3.1-u 300-lit:r:/yr-Ingestion dose factor fo in (OFL)ija TaDleJ2.2-5 h J.A '
At Yp Pasture grass areal density 0.7 kg/m* Ys Stored feed areal density 2.0 kg/m* l1.>-41. fp Fraction of year that cow grazes ; on pasture 1.0 ' f5 Fraction of total feed that is ! pasture grass while cow is on I pasture 1.0 Absolute humidity of the atmosphere Q 8.0 gm/ms l l
- Supports Section 2.2.2b. DOCR No. D - zi p) v ATTACHMENT No.
I5 M a SHEIT of HATCH 00CM, REV 1 5/11/84 2.2-47
7'A B LE 2. 2 -l 2. O doNTBou in4 REcEPfo K
.. ( 70 sa.pp ,e sabs chn 2 2. 2.. b )
. 7h locakn d exposcue.pAugs
... sssoc ahd wa4 de. .co&outy recepk
. arc. lekined ba. red n. .inLa:hn._ob+a yJ. - .
..clu.ci.9 +ke annual L.d use Ce-s u.s. ~*
- .D.is.pe c. sin ad depsikn...va/ues were .calculaled .
. . . . fu R e /oeahn of k co4,Itiy_receplw ..
...... _ .. . . .-. -.hased' on HN.R. s,h. _sedens.le,gical_d'4L. .-
.. . ... . Lolleeled -fw & . p e eio d . . H 8 f . a s L . ? ? .... -.... ..
' O _ - .- . Lo cah% .:. 5 W-.at L 2.- miIs.s
._ d A a e. Gay.:_. cA 1L.- - -
i _-.. - J yp u aee....!nf.Lw m sa In1afdyqmd p/ue, . .j A+:d-.. 9anlev. -.vey eht8m . . . . - - . . . . . . . Disyer%d_Qepok_ydu.as& -a.:, /e_dw__
--_Gr.und lerei rm = . .
i
't
*I
/f7o ').. -
7.see-7 7 ) p l (O/Q ,,
-r
= 2.7.5 [ # 9 m*
~ ~ '
1 Elevi}ed
$6L
!)
(xm')s, 7.zt e-s -- 7 - . _
.L .
1 l [D/& )sr 5 7. 3 2 8-/D # -- l _ .D b = 1. 5 ) ATTACHMENT No. ^ l
,y. , .. . u, L . y .s Re Cue.,c.a s 1+ M is . "$M@tO2" N k si n D .TITsjMi@lif N i N T4M N $ N ild N ri.. .mstwsmw summmwapsm:tm;w. '
l i i p TABLE 2.2-13 (SHEET 10F 2) 5 V StTE-SPECIFIC (OR OEFAULT) VALUES TO ; BE USED IN A00!!!CNAL PATHWAY FACTOR CALCULATIONS
- Pa ramete r Description Value Inhalation Pat.s ) Breathing rate for age group ,
(BR)a Table 2.2-10 (DFA)ija Inhalation dose factor for age group Tables.2.2-1 m thru 2.2-4 Q ). Pfl Grass-Cow-Meat g QF Feed consumption rate for cow 50 kg/ day ;
),g g -) U ap Meat consumption rate for age group Table 2.2-10 M (DFL)ija Ingestion dose factor for age group Tables 2.2-6 ,
thru 2.2-8 I Yp Pasture grass areal density 0.7 kg/m8 Ys Stored feed areal density 2.0 kg/ma fp Fraction of year that cow grazes on pasture 1.0 l fs Fraction of total feed that is pasture grass while cow is on pasture 1.0 H Absolute humidity of the atmosphere 8.0 gm/m8 Garden Vegetation Yy Garden vegetation areal density 2.0 kg/m* Uat Leafy vegetation consumption rate for age group Table 2.2-10 6 Uas Stored vegetation consumption rate for age group Table 2.2-10 lis )$ he y & *y r4 2,2-l, l wk k ).u-5
- Supports Section 2.2.2.h DOCR No. E1 -zi HATCH 00CM. REV 1 5/11/84 2.2-48 ATTACHMENT No. - 3 3 ,
shui r1 of M
O TABLE 2.2-13 (SHEET 2 0F 2) SITE-SPECIFIC (OR DEFAULT) VALUl:S TO BE USED IN A00l!IG E PATHWAY FACTOR CALCULATIONS
- Pa rameter Oescription Value Garden Vegetation (continued) fg Fraction of annual intake of leafy vegetation grown locally 1.0 fg Fraction of annual intake of stored vegetation grown locally 0.76 H Absolute humidity of the atmosphere 8.0 gm/m*
Grass-Goat-Milk Qp Feed consumption rate for goat 6.0 kg/ day Uap Milk consumption rate for age group Table 2.2-10
)
(DFL)ija Ingestion dose factor for age group Tables 2.2-5 thru 2.2-8 Yp Pasture grass areal density 0.7 kg/m* Ys Stored feed areal density 2.0 kg/m fp Fraction of year that goat grazes on pasture 1.0 fs Fraction of total feed that is pasture grass while goat is on pasture 1.0 H Absolute humidity of the atmosphere 8.0 gm/ms 1 J l
- Supports section 2.2.2.h l 0680n DOCR No. Ci - 21 j j HATCH 00CM. REV 1 5/11/84 l
2.2-49 ATTACHMENT No. I a dzou 1 saui .it cv a4 .
l l Section of
- Tenn Definition initial Use l l
-(0/0')y, = 1.0 x :" "- the M mter.- - 2. 2. 2. k
, (0/Q')sp = the annual average deposition parameter for the 2.2.2.b location of controlling (critical) receptor for main stack releases.
- 5,t 10'; . - in i.he t:! 2 :::ter. I 2 .2.2.t-Et = the energy assigned to energy group 1 (MeV). 2.3.1 h =
the elevated release height (meters). 2.3.1 I(r)kt = the results of numerical integration over the 2.2.1 spatial distribution of an elevated finite plume. I 4 = the plume depletion factor for all radionuclides 2.3.1 other than noble gases at distance r. i ~ 4k = the plume depletion factor for all radionuclides 2.3.1 other than noble gases at a distance r for the ! appropriate stability class k (radiciodines and particulates). K = a constant associated with the Kj and Vj calcu- 2.3.1 lation representing a combination of constants , and unit conversions. I j 101 = the total body dose factor due to gamma emissions 2.1.1
- j .
from radionuclide 1 (nren/yr per Sci /me) from Table 2.1-1. 1 j l DOCR No.- fh = at i l HATCH 00CM. REY 1 5/11/84 2.4-3 ATTACHMENT No. Ia dnn
! , shui 19 dr at, d
e i l ' Section of Term Definition Initial Use W5p' = the pathway-dependent relative dispersion or 2.2.2.b deposition in the unrestricted area at the location of the controlling receptor associated l with stack releases. X/Q = the sector-averaged annual average relative 2.3.1 concentration at any distance in the given . sector. X/Qs- = the highest annual average relative concentration 2.1.1 at the site boundary when considering ground-level releases. 4/% -
- 0. 0 , 10 m/..: tr, th: " :::t:r. I X/QE
= the highest annual average relative concentration 2.1.1 in the unrestricted area associated with releases from the main stack. i =X/^( - '0: 10-*
c/: 'a th: " ;cter. (176'),p = the annual average relative dispersion parameter 2.2.2.b for the location of the controlling receptor for plant vent releases. ac vin,es
! ,y, e_ . i . 2. n. . . ...
- . . ._ , , _ . 4 u_ . ._ uu. _r...
___m..._.-
= , (.X/Q ')3 p the annual average relative dispersion, parameter 2.2.2.b l l , for the location of tht. controlling receptor for main
] stack releases, j '5,5')3p - t.2 a '.0 -* ::: /:" k. it.; %% : ;;cter.-
- 2. 2. 0.P iO I
HATCH 00CM REV 1 5/11/84 DOCR No. D - 21 ' i 2.4-8 J' ATTACHMENT No. E O "d'M m zo of . S
3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l l Sampling locations as required by RETS 4.16.1 are described in Table 3.0-1 and shwn on maps in Figures 3.0-1 W ?.^ 2. becu c3. 0 ch . 4 There are no known drinking water users downstream of Plant Hatch. Therefore, the LLD for I-131 in water need not be as stringent as that for milk. l Tha survey of alik animals is based on the requirement in Appendix I to l 10 C'P Ta.-+ 50 that the licensee ' Identify changes in the use of unrestricted areas (e.g., for agricultural purposes) to permit modifications in monitoring 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 radiotodine are major potential sources of exposure. Samples from milk 1 animals are considered a better indicator of radioiodine in the environment than vegetation. Because sutticient milk samples frequently are not i available within 5 miles, vegetation samples will be collected also. r Grass is available almost year-round, whereas leafy vegetation is available only for 8 months of the year at best. The sampling stations for grass are 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 of fsite D/Q for each individual sector occurs approximately at the site boundary, i
j Although either fish or clam samples may be collected from the river, fish . samples are preferred, because the maximum dose connitment to a member of the i vublic as a result of liquid effluents is through the fish consumption l pathway, i 1 I HATCH ODCM, REV 1 5/11/84 DOCR No. - D 21 m 3.0-1 g ip l , 5HEET f1 OF M l: I -
TABLE 3.0-1 (SHEET 10F 2) ! RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS I Location Distance Sample Number Descriptive L: cation Direction (miles) Tvoe
- l 064 Roadside park WNW 0.8 0 1 101 Inner ring N 1.9 0 102 Inner ring NNE 2.5 0 103 Inner ring NE 1.8 AD 104 Inner ring ENE 1.6 . 0 105 Inner ring E 6 c3.'7 0 106 Inner ring ESE 1.1 DV 107 inner ring SE 1.2 AD 108 inner ring SSE 1.6 0 1
109 Inner ring S 0.9 0 110 Inner ring SSW 4,4- l . o 0 111 Inner ring SW 0.9 0 ! 112 Inner ring WSW 1.0 ADV 113 Inner ring W 1.1 0 114 Inner ring WNW l.2 0 115 Inner ring NW 1.1 0 116 Inner ring NW 1.6 A0 1 = unsu. _ _ . mm ,, u l 170 Upriver WNW ** 172 R Downriver E ** R ;
, 201 Outer ring N 5.0 0 I
! 202 Outer ring ) I NNE 4.9 0 i 203 Outer ring NE 5.0 0 204 Outer ring (NE -4,+c5.o 0 205 Outer ring 206 E 7.2 0 Outer ring ESE + red.8 0 207 Outer ring ; 208 SE 4.3 0 Outer ring SSl M $.5 0 l 209 Outer ring 1 210 S 4.4 0 Outer ring SSW 4.3 0 i 211 Outer ring SW 4,44.*1 0 212 Outer ring 213 WSW 4.4 0 $ Outer ring W 4.3 0 6 214 Outer ring 215 WNW 5.4 0 Outer ring NW 4,4-4.$ 0 216 Outer ring alt, NNW 4.8 0 Clori's Icen NN 4.8 M i l "See Sheet 2 of 2 for footnote.
**See Sheet 2 of 2 for footnote.
O D l J HATCH 00CM, REY 1 5/11/84 3.0-3 DOCR No. - 21 i l i A" ' ATTACHMENT No. # 0 o* n ! 2 SHAT 2 2. of .% !1 i
l TABLE 3.0-1 (SNEET 2 0F 2) i RADIOLOGICAL ENVIRONNENTAL SAMPLING LOCATIONS Location Number _ Descriptive location Distance Sample Direction (miles) Type
- 301 Toombs Central School N 304 Etate prison Brf 9.4 0 304 ENE Md )),a State prison ENE AD 309 _ Baxley substation 10.8 M S 10.0
- m. 2cc esm, ADV 3 Ii *_ - w -
~ T Q .D.m'f_
yyv l% ~ _ *-T M) i
' ' Sample Typest i
A - Airborne radioactivity ! 0 - Direct radiation M - Milk i O R --Vegetation V River (fish or clams, shoreline sediment, and surface ifater) i i MM itation 170 is located at approximate 1 1.1 mi n 6OA 4 d < 0.3 for riverwater, for sediment and clams, Y,mi or fish. i
'and clams, ion 172 is located at approximategy aSfor riverwater, sediment for fish, !
The location p g Q Q{ {
,= wnich riverwater and
{ i taken can be rather precisely defined.@UTteWMr "'9 d _ r sediment c a- may be k locations quantit$,a=-a sufficient for class havethaa to be+hextended over a wide area to obtain ahe samplin _ = m y ~ ' ' - " ' ' i < also make an otherwise suitable location fortertmigh ungvallable. sediment u-ni i generally needed to obtain adequate fish samples.A stretch of the riv The mile locations i give.n above represent approximations of the locations catc'hes are taken. about which the 1 i l 1 DOCR No. D - 21 - lQ ) ATTACHMENT No. Saur zu or_ 34 I O 6eo i HATCH 00CM, REY 2 11/25/86 i 3.0-4 ) 0687n i l l
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1 l l HATCH 000d. pttv 1 S/11/64 (m) v' RADIOLOGICAL ENVIRONMENTAL SAMPLING l rowm. H4rew LOCATION MAP (BEYOND GeorgbPower uctaAn nun SITE VICINITY) '
- FIGURE 3.0-2 (SHEET 1 0F 3) 3.0-6
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$1TE VICINITY)
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t)" LOCATION OF ADDITIONAL EDWIN 1. HATCH NUCLEAR PLANT CONTROL STATION FOR HILK FIGURE 4-.il, c'5.0 53
.5 n . o
l I 5.0 POTENTIAL DOSES TO MEMBERS OF THE PUBLIC OUE ( TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY V For the purpose of implementing RETS 6.9.1.9, 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. Th 7 ?:t!0n: hip; betW:;r Onnt:1 0 '/O r: g Ot"^'dheric-24,.. ,4.. a . 4 u .. . w 4... 4e. _.. -a.i- -. a.., i...+4... .-- --
; //h e d y e. o es NeposY ?' h &
elevaked P M e. Losefo< M S O'SC l# ~ " ' * ~ '" 7kble s 5.O- l ~f%"h [ D ~ A') A;M ""g es+;4ed o[ew EWmatu b<w" - - - .
\
Occupancy Fa of N (by a vidual Loratlon X/0 (sec/m*) urina a year) Site bounda 3.26 x 10-6 100% , Critical receptor 6. 0- 100% Roadside park O' Camping area 3.74 x 10-3.36 x 104
< 0.1% (2 hr)
< 0.6% (48 hr)
Visitor enter 1.00 x 10-5 (4 hr) reation area 6.71 x 10-7 2.4% (20 In the event that any limit of RETS 3.11.2.2 or 3.15.2.2 is exceeded, an assessment will begformed considerigg direct radiation dose to an individual resultingh t - $-Nf'$nS-th: ;r:=d-1:;d plume. This assessme ud dspast%nt will take into consideration the anntfal in rwu average s.o-o +k dispersio0
*mk s'.o-A parameters and the estimated occupancy factor statedgabove, or a more precise value if available, for the locations of interest.
In, the event that any limit of RETS 3.11.2.3 or 3.15.2.3 is exceeded, an assessment will be performed considering the St r--1 dose to an individual due to inhalation adp1ch.e.of4.airborne rad +ioactive rad.oachve. matecfalsmsuspended
% eM deposiki se. gr.4. in the "r^;rd 1 ^;;l This assessment will take into consideration the annual 1
p v u Ethded o""4R E*k A" N ^ ib"'N O^b " 1* h I HATCH ODCM, REY 1 5/11/84 5.0-1 DOCR No. D d .A
/ 6 **1 ATTACHMENT saaT 27 of c No. %
Q dqoSW average dispersion 4 parameters and the estimated occupai.cy f actor stated above, or a more precise value if available, for the locations of interest. 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 o.o3 an individual at the ev.d Visitors Center are not groM
- plu Wp
- JW').
expr sted to exceed-GA01 arem due to inhalationfand-O Of mrem due to
- d. rect radiation P [r% Oc I P "^ #'
Potential doses to an individual at the roadside park are not o . o O 5' h-4 4 r0 &. p W t.10 0bM i expected to exceed-Or001 mrem due to inhalation and-Grh mrem due to 4 direct radiation P frew & p le t- - #*# 3 Potential doses o .o + to an individual at the camping area are not expected N greg-p u u p s u.c <. ; to exceed-Ov003 mrem due to inhalation and 0.06 mrem due to direct radiation r /r % ike- Pb ca . ( Potential doses to o.6 an individual at the recreation area are not M o rou 4v -p I% <-> p e swe-J expected to exceed 0,003 mrem due to inhalation and-Ove6 g mrem due to , direct radiation /' he~. N pl*~ t-
%A begoh%
These values are based on annual avera e ggionAparametggghe ! estimated occupancy factors stated above.f Occupancy factors for thegVisitors Center, the roadside park, and the camping area are based on activities observed at these locations over the last several years [-The :::c;:n:p M f atter for the recreetkr, arca h h::d er anticip:t:d c:: ' thh f: i'ity_ C onfinv ed 0.n }iQafe) 0-Jye. o s" t% e.re 0.< eA s . 1 6 i O
$$00CMREV1 5/11/84 S.0-2 DOCR No. D - zi ATTACHMENT No, - /<5 o;wn ser 21 or c3 , !
l
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'O
% Ele.vded P/u m e. Dose Pudars: **
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' DOCR No. M . j,1 ATTACHMENT No.[a REFERENCES M _ OF __ dit l O 1. J. S. Boegli, R. R. Bellamy W. L. Britz, and R. L. Waterfield, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,' NUREG-0133, October 1978.
2.
"Calculation of Annual Doses to Man from Routine Releases of Reactor Ef fluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," U. S. NRC Requlatory Guide 1.109, March 1976.
3.
"Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I,' U. S. NRC Regulatory Guide 1.109. Rev.1, October 1977.
- 4. HNP-2 Environmental Report - Operatino License Stace, Georgia Power Company, July 1975, (including Appendix A. "Edwin I. Hatch Plant-Unit 1 Preoperational Environmental Surveillance Report Number 1," submitted March 1,1975).
- 5. Edwin I. Hatch Nuclear Plant-Unit 1 Final Safety Analysis Report, Georgia Power Company.
- 6. Edwin I. Hatch Nuclear Plant-Unit 2 Final Safety Analysis Report, Georgia Power Company.
- 7. ' Methods for Estimating Atmospheric Transport and Dispersion of Gaseous O Effluents in Routine Releases from Light-Water-Cooled Reactors,"
U. S. NRC Regulatory Guide 1.111, March 1976.
- 8. ' Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,"
U. S. NRC Regulatory Guide 1.111, Rev.1, July 1977. 9. Handbook of Mathematical Functions with Formulas. Graohs and Mathematical Tables, edited by Abramowitz, M. and Stegun. I. A., National Bureau of Standards, U. S. Department of Conenerce,1965.
- 10. Meteoroloav and Atomic Enerov, edited by Slade, D. H., U. S. Department of Contnerce, July 1968.
- 11. ' Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I,'
U. S. NRC Regulatory Guide 1.113, Rev.1, April 1977.
- 17. Nichols, M. C. and Holder, S. D., Plant Edwin I. Hatch Units 1 and 2 Thermal Plume Model Verification, Georgia Power Company Environmental Af f airs Center, March 1981.
- 13. Effect of Eductors in Plant Hatch Licuid Waste Tanks, Georgia Power Company October 1978.
kYb kefe enc.e.t r % $^ fitf e. O nut HATCH 00CM, REY 1 5/11/84
Rc k -, [ddl fo pre.v ;ous page. ) M. Halel Aluleu Pl d W (Jse Su.< vey 19 8 7 , Gewy,w l Pouse< co,,,, , fel, m J L
-1987. !
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- 17. ..
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e y _ . . . -
. _ _ - . . . . . . . _ ..DOCR.No. D - 21 ATTACHMENT No. Q as g ssm
~
or 'A M O. n
..e __-..... -.
*.d, 4
,..e
~ '
..e e
] 's Georgia Power Company , Plant E. I. Hatch Semi-annual Report Plant Radioactive Effluent Releases
- July 1 through December 31, 1987 Appendix C a
N 1 l 1 .i 1 a I 3 1 , 4 4 4 l 4 4 4 i 1
TABLE OF CONTENTS Page 1.0 LIOUID EFFLUENTS 1. 0-1 1.1 LIQUID EFFLUENT MONITOR SETPOINTS 1.1 -1 1.1.1 Liquid Radwaste Effluent Monitors 1.1 -1 1.1.2 Plant Service Water Monitors 1.1-9 1.2 DOSE CALCULAT'ON FOR LIQUID EFFLUENTS 1. 2-1 1.3 DOSE PROJECTIONS FOR LIQUID EFFLUENTS 1.3-1 1.3.1 Monthly Dose Projections 1. 3-1 1.3.2 Dose Projections for Specific Releases 1.3-2 1.4 DEFINITIONS OF LIQUID EFFLUENT TERMS 1. 4-1 l 1.5 LIQUID RADWASTE TREATMENT SYSTEMS 1. S *1 ' 1.6 MIXING OF LIQUID WASTE TANKS 1. 6-1 2.0 GASEOUS EFFLUENTS 2. 0-1 2.1 GASEOUS EFFLUENT MONITOR SETPOINTS 2.1 -1 2.1.1 Unit 1 Reactor Building Vent Stack, 2.1 -1 Unit 2 Reactor Building Vent Stack, Unit 1 Recombiner Building Vent, and iBuilding Exhaust Augmented Ventilation 2.1.2 Main Stack 2.1 -4 2.1. 3 Detensination of Allocation Factor, AG 2.1 -6 1 2.2 GASEOUS EFFLUENT DOSE RATE AND DOSE CALCULATIONS 2.2-1 2.2.1 Unrestricted Area Boundary Dose Rate 2.2-1 2.2.1.a Dose Rates Due to Noble Gases 2.2-[ 2.2.1.b Dose Rates Due to Radioiodines, 2.2-2 Tritium, and Particulates 2.2.2 Unrestricted Area Air Dose and Dose 2.2-4 to Individual 1 2.2.2.a Air Dose in Unrestricted Area 2.2-4 , 2.2.2.b Dose to An Individual in 2.2-5 l Unrestricted Area l 2.2.2.c Dose Calculations to Support 2.2.17 Other Specific Technical Specifications O HATCH ODCM REV 3 8/87 i
LIST OF TABLES l Table Title Page
- 1. 2-1 Bioaccumulation Factors 1.2-4 I 1.2-2 Adult Ingestion Dose. Factors 1.2-5 1.2-3 Site-Related Ingestion Dose Commitment Factors, 1.2-7 Ah (Fish Consumption) 2.1 -1 Dose Factors for Exposure to a Semi-Infinite 2.1 -8 j Cloud of Noble Gases 4 2.1 -2 Dose Factors for Exposure to Direct Radiation 2.1 -9 ;
from Noble 6ases in the Elevated Finite Plume 2.2-1 Inhalation Dose Factors for Infant 2.2-19 2.2-2 Inhalation Dose Factors for Child 2.2-22 2.2-3 Inhalation Dose Factors for Teenager 2.2-25 1 2.2-4 Inhalation Dose Factors for Adult 2.2-28 1 2.2-5 Ingestion Dose Factors for Infant 2.2-31 I 2.2-6 Ingestion Dose Factors for Child 2.2-34 2.2-7 Ingestion Dose Factors for Teenager 2.2-37 2.2-8 Ingestion Dose Factors for Adult 2.2-40 2.2-9 External Dose Factors for Standing on 2.2-43 Contaminated Ground 2.2-10 Individual Usage Factors 2.2-45
,. 2.2-11 Stable Element Transfer Data 2.2-46 2.2-12 Controlling Receptor 2.2-47 l 2.2-13 Site-Specific (or Default) Values to be 2.2-48 Used in Pathway Factor Calculations l
- 3. 0-1 Radiological Environmental Sampling Locations 3.0-3
- 5. 0-1 Location-Specific Parameters for the Roadside Park 5.0-3 4
5.0-2 Location-Specific Parameters for the Camping Area 5.0-4
- 5.0-3 Location-Specific Paramenters for the Recreation Area 5.0-5 i 5.04 Location-Specific Parameters for the Visitors Center 5.0-6 !
l I l 4 O HATCH 00CM, REV 3 8/87 iii l
LIST OF FIGURES O Fiqure Title Page 1.1 -1 Example Calibration Curve for Liquid Effluent Monitor 1.1-10
- 1. 5-1 Liquid Radwaste Treatment System (Unit 1) 1.5-2 1.5-2 Liquid Radwaste Treatment System (Unit 2) 1.5-3 2.3-1 Vertical Standard DeviatibnFactor of Material in a Plume (az) 2.3-7 2.3-2 Open Terrain Recirculation 2.3-8 2.3-3 Plume Depletion Effect for Ground-Level Releases 2.3-9 2.3-4 Plume Depletion Effect for Greater Than 100-m Releases 2,3-10 2.3-5 Relative Deposition for Ground-Level Releases 2.3-11 2.3-6 Relative Deposition for Greater Than 100-m Releases 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) I 3.0-2 Radiological Environmental Sampling Location Map 3.0-6 (Beyond the Site Vicinity) i 3.0-3 Location of Additional Control Station for Milk 3.0-9 0 .
i
. l I
l O HATCH ODCM, REV 3 8/87 iv ____________..__-__._.____-____________i.____-_-___.____.._., -
- s l
I 6 2.0 GASEOUS EFFLUENTS lO At Plant Hatch there are four points where radioactivity normally is released l to the atmosphere in gaseous discharges. These four release points are: The main stack which serves both units.
. Unit i reactor building vent stack.
. Unit 2 reactor building vent stack.
. Unit 1 recombiner building vent.
In addition to these four release points, releases also may be made from building exhaust augmented ventilation system (s) provided the Radiological Environmental Technical Specifications (RETS) allow releases via this pathway. The main stack serves as the discharge point for the following release sources from each unit:
. Mechanical vacuum pumps.
. Off-gas system.
O . Gland 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. Radwaste building. The Unit 1 recombiner building vent discharges directly to the atmosphere.
.O i HATCH 00CM, REV 3 8/87 2. 0-1
)
Gaseous effluent monitor setpoints are required only for noble gas monitors
-s serving the release points; the methodology for calculating noble gas monitor l
setpoints is presented in Section 2.1. Although setpoint calculations are not required for radioiodine and particulate monitors, the methodology for assuring that the potential organ dose rates due to radioiodines, tritium, j and particulates in gaseous releases from the site do not exceed the limits l of RETS 3.15.2.1(b) for Unit 1 and 3.11.2.1(b) for Unit 2 is presented in the l note following Section 2.2.1.b. l l I l 6 I l 0683n O HATCH ODCM, REV 3 8/87 2.0-2
2.1 GASE0US EFFLUENT MONITOR SETPOINTS O The gaseous monitor setpoint values determined in the following sections will be regarded as upper bounds for the actual setpoint adjustments. That is, I setpoint adjustments are not required to be performed if the existing { setpoint level corresponds to a lower count rate than the calculated value. I Setpoints may be established at' values lower than the calculated values, if desired. If no release is planned for a particular pathway, or if there is no - detectable activity in the planned release, the monitor setpoint should be established as close to background as practical to prevent spurious alarms and yet alarm should an inadvertent release occur. , If a calculated setpoint is less than the monitor reading associated with the particular release pathway, no release may be made under current conditions. Under such circumstances, the number of simultaneous release pathways may be reduced or contributing source terms may be ' reduced and the setpoint 2.1.1 Unit 1 Reactor Buildino Vent Stack. Unit 2 Reactor Buildino Vent Stack. Unit 1 Recombiner Bu11dino Vent. and Bu11dina Exhaust Auomented Venti-lation Monitors: 011-K619 A and 8, 2011-K636 A and 8. 011-P003 A and 8 (Monitor identification for building exhaust augmented ventilation ! will b'e determined prior to making releases via this pathway.) 4 For the purpose of implementation of RETS 3.14.2 (Unit 1) and 3.3.6.10 j (Unit 2), the alarm setpoint level for these noble gas monitors will be calculated as follows: Cs = the monitor reading of the noble gas monitor at the alarm setpoint concentration. HATCH ODCM, REY. 3 8/87 2.1 -1 i
l where: l O C = the monitor reading of a noble gas monitor corresponding to I the grab sample radionuclide' concentrations taken in accordance with RETS Tables 4.15.2-1 (Unit 1) and 4.11.2-1 (Unit 2). The monitor response corresponding ' the measured 1 concentration is determined from the monitor calibration i curve for the particular monitor. I (X/Q)g = the highest annual average relative concentration at the i site boundary. (If. desired, the annual average relative concentration at the site boundary for the particular release point may be used.) The release points addressed in this section are ground-level releases. (X/Q)g = 8.37 x 10-* sec/m* in the ENE sector. Ki = the total-body dose factor due to gansna emissions from radionuclide 1 (mren/yr per pCi/ms ) from Table 2.1-1. t Qiy = the rate of release of noble gas radionuclide 1 (pci/sec) from the vent release pathway under consideration, which is the product of X iy and Fy, where: Xiy = the , conce..tration of radionuclide i for the particular release, and Fy = the maximum expected r? lease flow rate for this release point (Xi y in pC1/ml and Fy in al/sec). Dss = the dose rate limit to the skin of the body of an individual in an unrestricted area which is 3000 mrem / year.
- R sy = the monitor reading per mrem /yr to the skin.
HATCH 00CM, REY 3 8/87 2.1-3 4_._--_- _ _
l 1 R ss = C+E (Lj (X/Q)E + 1.1 Bj) Qis (8) O, , l where: j i Vj = the constant, which ' .ludes the dose factor, for each identified noble gas radionuclide accounting for the gansna radiation from the elevated finite plume resulting f rom the main stack release, in mrem /yr per uCi/sec, f rom Table 2.1-2. - Bj = the constant, which includes the air dose factor, for each identified noble gas radionuclide accounting for the ganssa radiation from the elevated finite plume resulting from the main stack release, in mrad /yr per pCi/sec, from Table 2.1-2. Qis = the rate of release of noble gas radionuclide 1 (pC1/sec) from the main stack, which is equal to the product of Xis and F s, where: Xis = the concentration of radionuclide i for the main stack release, and Fs = the maximum expected main stack release flow rate (Xis in pCi/ml and Fs in al/sec). (X/Q)E = the highest annual average relative concentration in the unrestricted area associated with releases from the main stack. The main stack is an elevated release.
=
the 4.10 x 10 8sec/m* in the ENE sector. All other terms were identified previously in Section 2.1.1. O HATCH 00CM, REV 3 3/87 2.1-5
I 2.1.3 Determination of Allocation Factor. AG lO When simultaneous gaseous releases are made to the environment, an l (administrative) allocation factor must be applied to each discharge pathway. This is to ensure that simultaneous gaseous releases from the site to unrestricted areas will not exceed the dose rate limits specified in RETS 3.15.2.1 (Unit 1) or 3.11~.2.1 (Unit 2) . For Plant Hatch, final discharge pathways which may be released simultaneously are:
. The main stack.
. Unit i reactor building vent stack.
. Unit 2 reactor building vent stack.
. Unit I recombiner building vent.
. Building exhaust augmented ventilation. -
The allocation factor for each discharge pathway must be between 0 and 1, and the sum of the allocation factors for the simultaneous releases must not exceed 1. There are three methods by which allocation factors may be determined:
- 1. The allocation factor for a particular release pathway may be l administrative 1y selected based on an estimate of the fraction of the total dose rate (from all simultaneous releases) which is contributed by the particular release pathway.
- 2. The allocation factor may be calculated using the expressi'on:
1 1 AG = 1/n where: n = the number of release pathways to be released simultaneously.
- 3. The allocation factor may be determined for a particular discharge pathway by calculating the rati; of the total-body dose rate due to noble gases released from the particular discharge pathway under i
consideration to the total-body dose rate due to noble gases in all i simultaneous releases. HATCH 00CM, REV 3 8/87 2.1-6
8 I TABLE 2.1-2 l DOSE FACTORS FOR EXPOSURE TO DIRECT RADIATION FROM NOBLE GASES IN THE ELEVATED FINITE PLUME * (Location: Site Boundary in ENE Sector at 1545 m) Nuclide y-80dv (V)** y-Ai r ( B) *** Kr-85m 8.25E-05 8.69E-05 l Kr-85 1.26E-06 1.35E-06 Kr-87 4.40E-04 4.59E-04 Kr-88 1.09E-03 1.13E-03 . Kr-89 9.44E-04 9.87E-04 Kr-90 7.00E-04 7.38E-04 Xe-131m 1.68E-06 1.76E-06 Xe-133m 1.29E-05 1.37E-05 . Xe-133 1.38E-05 1.43E-05 Xe-135m 2.42E-04 2.59E-04 Xe-135 1.33E-04 1.42E-04 Xe-137 9.55E-05 1.02E-04 Xe-138 6.16E-04 6.44E-04 Ar-41 7.34E-04 7.72E-04 O' , i
- Values calculated in accordance with methodologies presented in Section 5.2.1 of Reference 1 and Appendix F of Reference 3, with meteorological joint frequency distributions presented in Reference 16; Reference 19.
** mrem-see uCi-yr
*** mrad-s ec pCi-yr 0684n HATCH 00CM, REV 3 8/87 2.1 -9
2.2 GASEOUS EFFLUENT 00SE RATE AND DOSE CALCULATIONS l 2.2.1 Unrestricted Area Boundary Dose Rates I l 2.2.1.a Dose Rates Due To Noble Gases For the purpose of implementation af RETS 3.15.2.1.a (Unit 1) and 3.11.2.1.a , (Unit 2), the dose rate in the unrestricted area due to noble gases shall be ! calculated as follows: - Ot = the total body dose rate at time of release (arem/yr).
=' +
I (X/Q)g I Kj Qjy EV1Qs i (9) v i i , 0s
= the skin dose rate at time of release (arem/yr).
=
Iv (X/Q)6 I (li + l l M )i Qiv + I (L (X/Q)E i + 1.1 Bj) Qis (10) i i Terms were defined pre'viously in Sections 2.1.1 and 2.1.2. The dose rate limits are site limits at any point in time; therefore, dose rates are sunened over all releases occurring simultaneously. For Plant Hatch the ' vent releases aro: ,
. Unit 1 reactor building vent stack.
- . Unit 2 reactor building vent stack.
, Unit 1 recombiner building vent.
. Building exhaust augmented ventilation.
The only elevated release is the main stack which serves both units. Simultaneous releases may include any combination of t'hese four release i points. O i ~ HATCH ODCM, REY 3 9/87 2.2-1
- 2. 2.1. b Dose Rates Due to Radioiodines, Tritium, and Particulates i
For the purpose of implementing RETS 3.15.2.1.b (Unit 1) and 3.11.2.1.b (Unit 2), organ dose rates due to radioiodines, tritium, and all radioactive materials in particulate form with half-lives greater than 8 days are required to be calculated for the inhalation pathway for the child age group. The child age group would experience the highest potential dose rate via the inhalation pathway. In accordance with Appendix C to Reference 3, noble gases are excluded from these calculations. These dose rates are calculated as follows: , Do
= the organ dose rate at time of release (aren/yr).
=
I (X/Q)G IPoQly i + (X/Q)EIPoQIs i '(11) v i 1 where: (X/Q)G = defined in Section 2.1.1. (X/Q)E = defined in Section 2.1.2. Qiy = the release rate (pC1/sec) of radicio:iines, tritium, and particulates (required by RETS 3.15.2.1 (Unit 1) and 3.11.2.1 (Unit 2) from the Unit 1 reactor building vent stack, the Unit 2 reactor building vent stack, the Unit 1 recombiner building vent, and building exhaust augmented ventilation. ! , Qis = the release rate (uci/sec) of radioiodines, tritium, and particulates (required by RETS 3.15.2.1 (Unit 1) and 3.11.2.1 (Unit 2) f rom the main stack. ' i Pio = the organ dose parameter for organ o and radionuclide 1 (mres/yr per yC1/m') for inhalation determined as follows: 4
- HATCH 00CM, REY 3 2.2-2 8/87
r Dp = the air dose due to beta emissions from noble gas radionuclides (mrad). 4
= 3.17 x 10
- I (X/Q)6 I NjQjy + (X/Q)E I NjQjs (15)
_V i _ _ i _ where: Nj = the air dose factor due to beta emissions from noble gas radionuclide 1 (mrad /yr per pC1/m') from ' Table 2.1-1. defined previously in Section 2.1.2.
= l (X/Q)E 2.2.2.b Dose to An Individual In Unrestricted Area i
Dose to an individual from radioiodines, tritium, and radioactive materials I in particulate form will be calculated for the purpose of implementation of RETS 3.15.2.3 and 3.15.2.4 (Unit 1), and 3.11.2.3 and 3.11.2.4 (Unit 2). In accordance with Appendix C of Reference 3, noble gases are excluded from these dose calculations. Doses to an individual are calculated as follows: NOTE: ' For Plant Hatch, the controlling receptor for which doses must be ,, calculated, the dispersion and deposition values at the location of' the controlling receptor, and the applicable exposure pathways are presented in Ta bl e ,2.2-12. Dj = dose to an organ j of an individual in age group a from radiciodines, tritium, and radionuclides in particulate form with half-lives greater than 8 days (mrem). e ~e e ~e
=
3.17 x 10-8 I Raipj [Wyp Qiv + Wsp Qis) (16) pi O l HATCH ODCM, REY 3 8/87 2.2-5
i 4-l where: O 3.17 x 10-8 = the fraction of 1 yr per 1 sec. Wyp' = the pathway-dependent relative dispersion or deposition in the unrestricted area at the location of the controlling receptor, associated with plant vent releases. (X/Q')yp = the annual average relative dispersion parameter for location of controlling (critical) receptor for plant vent releases. (X74')yp applies only to inhalation and' all tritium pathways. (For all tritium pathways, the Qj' source tern is limited to tritium.) See Table 2.2-12 for value. Wyp' " r (D/Q')yp = the annual average deposition parameter for
~ Ihe location of controlling (critical) receptor for plant vent releases. (U7U')yp applies to ground-plane and all ingestion,, i pathways, with the exception of t-itium. i
._ See Table 2.2-12 for value.
i i i I l O 1 HATCH 00CM, REY 3 8/87 2.2-6
Wsp' = the pathway-dependent relative dispersion or deposition in the unrestricted area at the location of the controlling receptor, associated with main stack releases. (X/Q')sp - the annual average relative dispersion parameter for location of controlling (critical) receptor for main stack releases. (X7U')sp applies only to , inhalation and all tritium pathways. , (For all tritium pathways, the Qj' source term is limited to tritium.) See Table 2.2-12 for value. l l Wsp' " (0/Q')sp = the annual average deposition parameter for the location of controlling (critical) ,
; receptor for main stack releases. (lT7Q')sp l applies to ground-plane and all ingestion pathways, with the exception of tritium.
See Table 2.2-12 for value. ' The selection of the dispersion or deposition parameter, X/Q or D/Q, is d'ependent upon the pathway being considered. The dispersion parareter. l X/0, is required for the inhalation pathway. The deposition parameter, ! O/Q, is required for the ground-plane pathway and all ingestion I pathways, with the exception of tritium. Since t'ritium is taken up by ! vegetation directly from surrounding air, X/Q is required for tritium contributions from the ingestion pathways. O ,
- i
; HATCH 00CM, REY 3 8/87 2.2-7 i
l
l Qjy' = the cumulative release (uci), from plant vent releases, of l radionuclide i as required by RETS 3.15.2.3 (Unit 1) and I 3.11.2.3 (Unit 2) over the period of interest. Dose determinations required by RETS 3.15.2.3 and 3.11.2.3 are on ! a per reactor basis; therefore, cumulative release quantities must also be reactor-specific. (For dose con,tributions due to tritium from the ingestion pathways, the Q $ y term is limited to tritium.) bis' = the cumulative release (pC1), from the main 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 interest. Dose - determinations required by RETS 3.15.2.3 and 3.11.2.3 are on a per reactor basis; therefore, cumulaiiive release quantities l must also be reactor-specific. Since the main stack serves both reactors, release quantities must be apportioned between the two units. In absence of evidence that one reactor O l 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 from ingestion pathways, the l hjItermislimitedtotritium.) q Raipj = the pathway-specific, individual age-specific organ dose factor for radionuclide 1, pathway p, organ j, and individual , a'ge group a. Routine individual dose calculations address I the inhalation, ground-plane, grass-cow (or goat)-milk, 1 grass-cow-meat, and garden vegetation pathways. However, the ! dose pathways actually present at the' controlling location, as well as the controlling individual age group, are determined through the Land Use Census for the site. Pathway factors Raipj are determined as shown in the following , subsections. 1 l HATCH 00CM, REV 3 8/87 2.2-8
As stated earlier, the controlling receptor for Plant Hatch is presented in Table 2.2-12. Plant Hatch site-specific values, or appropriate default l values, required in the pathway factor determinations are j j presented in Table 2.2-13. Inhalation Pathway Factor Raipj = K'(BR)a (DFAjj)a (area /yr per pCi/m8) where: K' = the constant of unit conversion, 10* pCi/yC1. (BR)a = the breathing rate for a particular age group, in m*/yr, f rom Table 2.2-10. DFAi ja = the inhalation dose factor for receptor age group a, organ j, and for radionuclide 1 in mrem /pci, from Tables 2.2-1 through 2.2-4. Ground-916ne Pathway Factor Raipj = K'X' (SF')(DF6jj) ((1-e-Ai t)fgj) (,, mrem /yr per pCi/sec)' I where: i K' = the constant of unit conversion,105 pCi/pci. K' = the constant of unit conversion, 8760 hr/yr.
- O l
HATCH ODCM, REV 3 8/87 2.2-9
H = the absolute humidity of the atmosphere, in gm/ms . 0.75 = the fraction of total feed that is water. l 0.5 = the ratio of the specific activity of the feed grass water i to the atmospheric water. l 1 Other parameters and values as previously defined. Grass-Cow-Meat Pathway Factor '
+{1_f,f),
3 jth e-Ajtf Raipj . ge QF(Van) F f (r)(DFLi j)a (19) A1 + Aw Yp Ys , (m8 mrem /yr per pC1/sec) where: f K' = a constant of unit conversion, 10* pC1/pci. Op = the cow's consumption rate, in kg/ day (wet weight). ' Uap = the receptorf s meat' cons # ion roteifor age group a, in kg/yr, f rom Table 2.2-10. ~ Yp = the agricultural productivity by unit area of pasture fee'd grass, in kg/m2 Ys = 'the agriU4teral productivity by unit area of stored veed, in kg/m8 4 Ff = the stable element transfer coef ficients, in days /kg. (See Table 2.2-11.) l r = the fraction of deposited activity retained on feed grass 4 (1.0 for radioiodines; .0.2 for particulates). O j l HATCH 00CM, REV 3 8/87 2.2-12
(DFli j)a = the organ ingestion dose factor for the itt radionuclide for the receptor in age group a, in mres:'Q, from Tables 2.2-5 through 2.2-8. Aj = the decay constant for the ith radionuclide, in sec-1 Aw = thidecay constant for removal of activity on leaf and plant surfaces by weathering, 5.73 x 10-7 sec-1 (corresponding to a 14-day half-life)'. , tf
= 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 meat, to receptor, in sec, (7.78 x 108). I fp = fraction of the year that the cow is on pasture ;
(dimensionless). f~
\
i fraction of the cow feed that is pasture grass while the
=
fs , cow is on pasture (dimensionless). For tritium in meat, the grass-co*w-meit* pathway factor is a special case due to thr; fact that the concentration of tritium in meat is based on airborne concentration rather than deposition:
=
Raipj K'KFgQpUap(DFl i j)a (0.75(0.5/H)] (mren/yr per wC1/m*) ( 0) 1 where: K = a constant of unit conversion, 108 gm/kg. H = absolute humidity of the atmosphere, in gm/me , 0.75 = the fraction of total feed that is water. t 0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water. i Other parameters and values are given above. 1 HATCH 00CM, REV 3 8/87 2.2-13
l Vegetation fathway Factor Raipj " gi r (DFLjj)a Vatf ie-Kjtg + Uasfge-Ajth , (21) , Yv( Ai + Kw) , l where: ' K' = a constant of unit conversion, 10* pCi/yCi. Uat = the consumption rate of fresh leafy vegetation by the' receptor in age group a, in kg/yr. (See Table 2.2-10.) the consumption rate of stored vegetation by the receptor
=
Uas in age group n, in kg/yr. (See Table 2.2-10.) ft
= the fraction of the annual intake of fresh leafy vegetation grown locally.
fg - the fraction of the annual intake of stored vegetation grown locally. tg = the average time between harvest of leafy vegetation and l its consumption, in sec, (8.6 x 10*). th = the average time between harvest of stored vegetation and 1 its consumption, in sec, (5.18 x 10*). , Yy = the vegetation areal density, in kg/m8 , (DFLjj)a = the organ ingestion dose factor for the ith radionuclide
)
for the receptor in age group a, in mrem /pC1, from Tables 2.2-5 tnrough 2.2-8. , Aj = the decay constant "or the ith radionuclide, in sec-1 ! , 0 HATCH ODCM, REV 3 :8/87 2.2-14 ;
Kw
= the decay constant for removal of activity on leaf and plant i surfaces by weathering, 5.73 x 10-7, in sec-1 (corresponding to a 14-day half-life).
For tritium in vegetation, the vegetation pathway factor is a special case ; due to the fact that the concentration of tritium in vegetation is based on airborne concentration rather than deposit 1'on: P Raipj " K'K"'(Vagfg + Uasfg ) (DFLjj)a (0.75(0.5/H)] (arem/yr per wCi/m*) (22) where: K = a constant of unit conversion, los gm/kg. . i H = absolute humidity of the atmosphere, in gm/m*. [ i O.75 = the fraction of total vegetation 1.5at is water. 4 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-Milk Pathway Factor ! .. l l Raipj " gi F(Uan) Fm(r)(DFLjj)a + (I-fofs) -Ajth e-Kit t (19)
- Ai + Aw _ Yp Ys .
(m*mren/yr per wC1/sec) ) i where: i j K' = a constant of unit conversion, 108 pCi/wci, j QF
= the goat's consumption rate, in kg/ day (wet weight).
i Uap = the receptor's milk consumption rate for age group a, in ,
- liters /yr, f rom Table 2.2-10. !
HATCH 00CM, REV 3 8/87 2.2-15 l
Yp = the agricultural productivity by unit area of pasture feed grass, in kg/m8 ! Ys = the agricultural productivity by unit area of stored feed, i in kg/m8 F, = the stable element transfer coefficients, in days / liter. (See Table 2.2-11.) . r = fraction of deposited activity retained on feed grass (1.0 ' for radiciodines; 0.2 for particulates). ' (DFli j)a = the organ ingestion dose factor for the ith radionuclide for the receptor in age group a, in eres/pci, f rom Tables ; 2.2-5 through 2.2-8. Kj = the decay constant for the ith radionuclide, in sec-1 O . N = the ' decay constant for removal of activity on leaf and ; plant syrfaces by weatherg, h73 x 10-', in sec-1
- (corresponding to a 14-day half-iffe). '
tf = the transport time from pasture to goat, to milk, to , receptor, in sec (1.73 x 108). i ! th " .the transport time from pasture, to harvest, to goat, to ] milk, to receptor, in sec (7.78 x 10*). ; l j fp = the fraction of the year that the goat is on pasture ) (dimensionless). fs = the fraction of the goat feed that is pasture grass while j the goat is on pasture (dimensionless). i . f For tritium in milk, the grass-goat-milk pathway factor is a special case due to the fact that the concentration of tritium in milk is based on airborne concentration rather than deposition: j HATCH 00CM, REV 3 8/ 87 2.2-16
)
i
-Raipj =
K'KFmQpUap(DFLjj)a (0.75(0.5/H)] (mres/yr per yCi/m*) (24) where: K'" = a constant of unit conversion,108 gm/kg. H = absolute humidity of the atmosphere, in ge/m*. i 0.75 = 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. '
Other parameters and values are given above. j
- 2.2.2.c Dose Calculations To Support Other Specific Technical Specifications i 1
In the event radiological impact assessment becomes necessary to implement RETS 6.9.1.12 or 6.9.1.13, dose calculations will be performed using the ; equations in Section 2.2.2.b with the substitution of average meteorological ' parameters for the period of the report and the appropriate pathway receptor -
- dose factors (Raipj )- - '
- For the purpose of implementing RETS 3.16.2, dose calculations may be performed using the equations in Section 2.2.2.b. substituting the . " !
, appropriate pathway receptor dose factor (Raipj) and the appropriate j dispersion parameters for the location (s) of interest. Annual average dispersion parameters may be used for these calculations. i ~ The receptor for which dose calculations may be required in order to j implement RETS 6.9.1.12, 6.9.1.13, or 3.16.2 may not b'e the previously identified critical receptor. The receptor age group and exposure pathways l present (and applicable) at the location of interest must be determined. 1 The equations for calculating the pathway factors R ajpj 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 1 2.2-13. l HATCH 00CM, REY 3 8/87 2.2-17 l
I l l O l 1 i O (THIS PAGE IS INTENTIONALLY LEFT BLANK) 1 l i . l l 1 i 0680n HATCH 00CM, REV 3 8/87 2.2-18
l TA8LE 2.2-12 CONTROLLING RECEPTOR (To support subsection 2.2.2.b) The location and exposure pathways associated with the controlling receptor are determined based on information obtained during the Annual Land Use Census.* Dispersion and deposition values were calculated for the location I of the controlling receptor based on the HNP site meteorological data I collected for the period 1984-1986.** l I Location: SW at 2.2 miles > l Age Group: Child Exposure Pathways: Inhalation, ground-plane, and garden vegetation ' Dispersion and Deposition Values for this locaticn: Ground-level (X/Q')yp = 7.39E-7 i i 1 i (D/Q'),p = 2.73E-9 F l Elevated (X/Q')3p = 7.21 E-8 m 4 . 1 ..
; (D/Q')3p = 7.32E-10 I ,
t e r
- Ref erences 14 and 18.' !
** Reference 17. !
i ) l l 1 ) O' i I i i d j HATCH ODCM, REV 3_ 8/87 _ __ 2.2-47 __ _ _ _ _ _
,_[
TABLE 2.2-13 (SHEET 1 0F 3) SITE-SPECIFIC (OR DEFAULT) VALUES TO BE USED IN PATHWAY FACTOR CALCULATIONS
- Parameter Description Value l
Inhalation (BR)a Breathing rate for age group Table 2.2-10 . l (DFA)ija Inhalation dose factor for age group Tables 2.2-1 l thru 2.%-4 Ground plane SF' Shielding factor due to structure 0.7 (DFG)ij Ground-plane dose factor Table 2.2 2g (same for all age groups) ' Grass-Cw-Milk
}
QF Feed consumption rate for cw 50 kg/ day Uap Milk consumption rate for age group Table 2.2-10 l (OFL)ija Ingestion dose factor for age group Tables 2.2-5 thru 2.2-8 Yp , P,asture grass areal density , , , ,, 0.7 kg/mi Ys Stored feed areal densit9 2.0 kg/m a fp Fraction of year that cw grazes on pasture 1.0-I fs Fraction of total feed that is pasture grass while c w is on
, pasture 1.0 H Absolute humidity of the atmosphere 8.0 ge/m*
Grass-Cw-Meat QF Feed consumption rate for cw 50 kg/ day Uap Meat consumption rate for age group Table 2.2-10 0
- Supports Section 2.2.2.b.
HATCH 00CM, REV 3 8/87 2.2-48
i a l TABLE 2.2-13 (SHEET 2 0F 3) t SITE-SPECIFIC (OR DEFAULT) VALUES TO i BE USED IN PATHWAY FACTOR CALCULATIONS
- 1 Parameter Description Value Grass-Cow-Meat (continued)
(DFL)ija Ingestion dose factor for age group Tables 2.2-6 thru 2.2-8 + Yp Pasture grass areal density 0.7 kg/ma ; Ys Stored feed areal density 2.0 kg/m* : i I fp Fraction of year that cow grazes J
, on pasture 1.0 1 . ; fs Fraction of total feed that is j . pasture grass while cow is on i j pasture 1.0 l
H Absolute humidity of the atmosphere 8.0 gn/m*
- i Garden Vegetation Yy Garden . vegetation areal density 2.0 kg/m8 4
I, Vga Leafy vegetation consumption rate for age group Table 2.2-10 ' ) Uas Stored vegetation' consumption rate : for age group Table 2.2-10 i ? (DFL)ija Ingestion dose factor for age Tables 2.2-6 , , ) groups thru 2.2-8 ' l fg Fraction of annual intake of ! i leafy vegetation grown locally 1.0 l . i ! fg Fraction of annual intake of l
- stored vegetation grown locally 0.76 H Absolute humidity of the atmosphere 8.0 gn/ms l Grass-Goat-Milk Qp Feed consumption rate for goat 6.0 kg/ day i Uap Milk consumption rate for age group Table 2.2-10 I iO l
l
- Supports Section 2.2.2.b.
HATCH 00CM. REV 3 8/87 2.2-4g I. _ _ - . _ _ . _. . _ - . .-_ _--_-.-_-.D
TABLE 2.2-13 (SHEET 3 0F 3) j SITE-SPECIFIC (OR DEFAULT) VALUES TO BE USED IN PATHWAY FACTOR CALCULATIONS
- Parameter Description Value Grass-Goat-Milk (continued)
(OFL)ija Ingestion dose factor for age group Tables 2.2-5 thru 2.2-8 Yp Pasture grass areal density 0.7 kg/m8 Ys Stored feed areal density 2.0 kg/m* fp Fraction of year that goat grazes on pasture 1.0 i fs Fraction of total feed that is : pasture grass while goat is on l pasture 1.0 H Absolute humidity of the atmosphere 8.0 gm/m8 , i 1 - t 1 - . . 1 l l l l . ) i i e i
- Supports Section 2.2.2.b.
!O 0680n ) HATCH 00CM, REY 3 8/87 2.2-50
I 2.3 METEOROLOGICAL MODEL 2.3.1 Atmospheric Dispersion l l Atmospheric dispersion may be calculated using the appropriate form of the sector-averaged Gaussian model. Gaseous releases are considered to be either elevated or at ground-level. Included in the ground-level category are releases from:
. Reactor building vent (Unit 1). -
. Reactor building vent (Unit 2).
. Recombiner building vent (Unit 1).
. Building exhaust augmented ventilation. ,
Releases from the main stack are considered to be elevated. 2.3.1.a Ground-Level Releases i X/Q = the sector-averaged annual average relative concentration at any distance in the given sector. 2.032 4 Kr I ".1 k (see m-8) Nujk r Ezk
~
jk where: r 2.032 = (2/v)*/* divided by the number of radians in a 22.S* sector ) (2v/16) . i
~ l l 4 = the plume depletion factor for all radionuclides other than noble I gases at a distance r shown in Figure 2.3-3. For noble gases the l depletion factor is unity. Only depletion by deposition is considered since depletion by decay would be of little significance i at the distances considered. , 1
.O
!l I *
' l HATCH 00CM, REV 3 8/87 2. 3-1
]
l Section of , l Torm Definition Initial Use l l (0/Q')3p = the annual average deposition parameter for the 2.2.2.b location of controlling (critical) receptor for l main stack releases. l Eg = the energy assigned to energy group 1 (MeV). 2.3.1 h = the elevated release height (meters). 2 .'3 .1 i I(r)kt = the results of numerical integration over the 2.2.1 spatial distribution of an' elevated finite plume. - 4 = the plume depletion factor for all radionuclides 2.3.1 other than noble gases at distance r. ;
= 2.3.1 j
4k the plume depletion factor for all radionuclides other than noble gases at a distance r for the appropria'te stability class k (radioiodines and j particulates). l ] K = a constant associated with the Kj and Vi calcu- 2.3.1 , ] 1ation representing a combination of constants ,, j i and unit conversions. I Kj ,
= the total body dose factor due to ganna emissions 2.1.1
, from radionuclide 1 (nren/yr per wCi/ms) f rom ! Table 2.1-1. 4 4 l HATCH 00CM, REV 3 8/87 2.4-3 l i l l L_____ _ _ - _ _ _ . _ _ _ - - _ _ _ _ - _ . _ - _ _ _ _ . _ _ . _ - . _ - - _ -
r i . Section of i Tenn Definition Initial Use l . Wsp' = the pathway-dependent relative dispersion or 2.2.2.b deposition in the unrestricted area at the location of the controlling receptor associated with stack releases. X/Q = the sector-averaged annual average relative 2.3.1 concentration at any distance in the given . sector. X/QG = the highest annual average relative concentration 2.1.1 at the site boundary when considering ground- ' level releases. I i EE = the highest annual average relative concentration 2.1.1 4 in the unrestricted area associated with releases from the main stack. I I (X75')yp = the annual average relative dispersion parameter 2.2.2.b ! for the location of the controlling receptor for plant vent releases. i .. I I l l (X/Q')sp = the annual average relative dispersion parameter 2.2.2.b for the location of the controlling receptor for main stack releases. l l l l 1 l l
)
i l !O l l j 1 HATCH 00CM, REV 3 8/87 2.4-8 I
_ __ _- .~. _. _ _ __ . _._ l i l
- 3.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM iO i 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 through 3.0-3. '
There are no known drinking water users downstream of Plant Hatch. Therefore, the LLD 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 I to 10 CFR Part 50 that the licensee "Identify changes in the use of unrestricted areas (e.g., for agricultural purposes) to permit modifications in monito, ring ! programs for evaluating doses to individuals from principal pathways of f exposure." The consumption of milk from animals grazing on contaminated 1 , pasture and the consumption of vegetation contaminated by airborne , radioiodine are major potential sources of exposure. Samples from milk animals are considered a better indicator of radiciodine in the environment than vegetation. 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 ' i only for 8 months of the year at best. The sampling stations for grass are - l
; located near the site boundary in two sectors with high offsite D/0 values I I
where it might be practical to establish a vegetation plot. The highest " offsite 0/Q for each individual sector occurs approximately at the site , boundary. Although either fish or clam samples may be collected from the river, fish
- . samples are preferred, because the maximum dose commitment to a member of the public as a result of liquid offluents is through the fish consumption pathway.
i i iO I, i HATCH 00CM, REV 3 8/87 3. 0 -1 .
TABLE 3.0-1 (SHEET 1 0F 2) RADIOLOGICAL ENVIRONNENTAL SANPLING LOCATIONS Location Distance Sample ! Number Descriptive Location Direction (miles) Type
- l 064 Roadside park WW 0.8 0 101 Inner ring N 1.9 0 :
102 Inner ring NNE 2.5 0 103 Inner ring NE 1.8 AD 104 Inner ring ENE 1.6 ,0 105 Inner ring E .3.7 0 106 Inner ring l ESE 1.1 DV Inner ring 107 SE 1.2 AD ' 108 Inner ring SSE 1.6 0 109 Inner ring S 0.9 0 l 110 Inner ring SSW 1.0 0' 111 Inner ring SW 0.9 D 112 Inner ring WSW 1.0 ADV 113 Inner ring W 1.1 0 Inner ring 114 WNW 1.2 0 115 Inner ring W l 1.1 D > 116 Inner ring NW 1.6 AD i l I 170 Upriver WNW ** R ] 172 Downriver E ** R ! 201 Outer ring N 5.0 0 202 Outer ring NNE 4.9 0 203 Outer ring NE 5.0 0 204 Outer ring ENE 5.0 0 : 205- Outer ring E 7.2 0 ( 206 Outer ring ESE 4.8 0 ; 207 Outer ring l SE 4.3 . O" 208 Outer ring SSE 4.8 0 209 Outer ring S 4.4 0 210 Outer ring SSW 4.3 0 211, Outer ring SW 4.7 0 212 Outer ring WSW 4.4 l 0 213 Outer ring W 4.3 0 214 Outer ring WW
- 5.4 0 215 Outer ring W 4.4 0 216 Outer ring l NNW 4.8 0 216 Clark's Farra NNW 4.8 N l
*See Sheet 2 of 2 for footnote.
i
**See Sheet 2 of 2 for footnote.
i HATCH 00CN, REY 3 8/87 3.0-3
TABLE 3.0-1 (SHEET 2 0F 2) i RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS Location Distance Sample i Number DescriDtive location Direction (miles) Tvoe *
; 301 Toombs Central School N 8.0 0 304 State prison ENE 11.2 AD 304 State prison ENE 10.8 M 309 Baxley substation S 10.0 ADV 316 Thompson's Dairy NNW 13.2 ,M
- Sample Types:
,l A - Airborne radioactivity D - Direct radiation O M - Milk R - River (fish or clams, shoreline sediment, and surface water) Y - Vegetation i 4
- Station 170 is located at approximately 0.6 river miles upstream of the intake structure for riverwater,1.1 river miles for sediment and clams, and 1.5 river miles for fish.
I Station 172 is located at approximately 3.0 river miles downstream of the i discharge structure for riverwater, sediment and clams, and 1.7 river miles for fish, i l The location from which riverwater and sediment may be taken can be rather
! precisely defined. Often, the sampilng locations for class have to be extended over a wide area to obtain a suf ficient quantity. High water adds i to the difficulty in obtaining clam samples; high water might also make an otherwise suitable location for sediment sampling unavailable. A stretch i of the river on the order of a few miles or so is generally needed to obtain adequate fish samples. The mile locations given above represent j approximations of the locations about which the catches are taken, iO I 0687n 1
- HATCH 00CM, REV 3 8/87 3. 0-4 1
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O LOCATION OF ADDITIONAL E DWIN I. H ATCH CONTROL STATION FOR MILK GeorgiaPower wucun rumr- umr i FIGURE 3.0-3 3.0-9
. d.J as-_ - 2 -A J-- 44+-.-._ad.a.-- ,- L- _ , * - - - - --: _eu'a . _a-+3.u A--- -- *44 . L-4 m--~ 5.-- +' a&2J p usi 1 !
l 5.0 POTENTIAL DOSES TO MEMBERS OF THE PUBLIC OU( ! TO THEIR ACTIVITIES INSIDE THE SITE BOUNDARY !O For the purpose of implementing RETS 6.g.1.9, an assessment of potential f l 1 doses to members of the public due to their activities within thc site j boundary will be performed if circumstances have changed such that any of the { j 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 Centar. Historical annual average dispersion and depositiqn '
- 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.) l! 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 asssssment will j 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. 1 ' i j In the event that any limit of RETS 3.11.2.3 or 3.15.2.3 is exceeded, an ! assessment will be performed considering the dose to an individual due to inhalation of airborne radioactive materials suspended in the plume and due 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. 1 j If none of the limits discussed above is exceeded, potential annual doses to 1 a member of the public at a location of concern within the site boundary are as follows: l Potential doses to an individual at the Visitors Center are not 1 expected to exceed 0.03 mrem due to inhalation and ground-plane l exposure, and 0.02 ares due to direct radiation from the plume. ! lO i l' l 1 i - i NATCH 00CM, REV 3 8/07 5.0-1
t i l
. Potential doses to an individual at the roadside park are not -
(} 2:pected to exceed 0.005 mrem due to inhalation and ground-plane l exposure, and 0.003 arem due to direct radiation f rom the plume.
- Potential doses to an individual at the camping area are not expected l to exceed 0.04 mres due to inhalation and ground-plane exposure, and 0.06 mrem due to direct radiation f rom the plume.
j
. Potential doses to an individual at the recreation area are not' !
l expected to exceed 0.6 mres due to inhalation and ground-plane l i exposure, and 0.3 mrom due to direct radiation from the plume. These values are based on annual average dispersion and depositior, parameters i and the estimated occupancy factors stated above. Estimated occupancy ' factors for the recreation area, Visitors Center, the roadside park, and the ; camping area are based on activities observed at these locations over the last several years and continued anticipated usage of these areas. . 1 I l
)
i - l l 1 I i i l i i 4 1 i () l 1 4 kkkh000CM,REV3 08/87 5.0-2 'i __ _
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l ! l ] TABLE 5.0-1 [ , LOCATION-SPECIFIC PARAMETERS FOR THE ROADSIDE PARK h I ! ) Location: WNW at 1182 meters ! ! Estimated Occupancy Factor: 2.28E-4 (2 hours) f I i ! Ground-level Dispersion and Deposition Parameters:* i (X/Q) - 7.83E-6 sec/m*; Depleted (X/Q) = 7.00E-6 sec/m*; (0/0) = 2.01E-8 1/m8 , f i . > ! Elevated Dispersion and Depositon Parameters: , i i i ) (X/Q) = 2.42E-8 sec/me Depleted (X/Q) = 2.37E-8 sec/m*; (0/0) = 1.29E-9 1/m8 l 1 l 't 1 i Elevated Plume Dose Factors:** , Radionuclide '180dy (V) 7 Air (8) l ! i . Kr-85a 8.39E-05 8.83E-05 - l l Kr-85 1.31E-06 1.405-06 l i Kr-87 4.60E-04 4.81L 04 ! ! . Kr-88 1.14E-03 1.18E-03 i ! Kr-89 9.89E-04 1.03E-03 . l Kr-90 7.32E-04 7.71E-04 ' Xe-131m 1.70E-06 1.78E-06 Xe-133m 1.32E-05 1.40E-05
- 4e-133 1.37E-05 1.41E-05 l i Xe-135m 2.51E-04 2.69E-04 ;
1 Xe-135 1.37E-04 1.45E-04 j j Xe-137 9.91E-05 1.06E-04 . Xe-138 6.45E-04 6.74E-04 ! ! Ar-41 7.69E-04 8.10E-04 l 1 i l i ! !
- Reference 16. l l ** See footnotes to Table 2.1-2. !
[ !O i HATCH 00CM REV 3 8/87 5.0-3 I
i i
- TABLE 5.0-2 LOCATION-SPECIFIC PARAMETERS FOR THE CAMPING AREA
{ i , l Location: WNW at 1274 meters I i Estimated Occupancy Factor: 5.48E-03 (48 hours) l I Grou1d-level Dispersion and Deposition Parameters:* , [ 4 (X/Q) = 7.03E-6 sec/m*; Depleted (X/Q) = 6.27E-7 sec/m*; (0/0) = 1.80E-8 1/m* j
; i 1 i i Elevated Dispersion and Depositon Parameters: l i b I (X/Q) = 2.38E-8 sec/m*; Depleted (X/Q) = 2.33E-8 sec/m*; (0/Q) = 1.21E-9 1/m3 l i
i , I ( 1 Elevated Plume Dose Factors:** i Radionuclide 1 Body (V) TAir (8) ! i } Kr-85m . . . 7.84E-05 8.25E-05 J Kr-85' 1.22E-06 1.31E-06 * ** . Kr-87 4.28E-04 4.47E-04 ! l Kr-88 1.06E-03 1.10E-03 ! J . Kr-89 9.19E-04 9.61E-04 ' l Kr-90 6.80E-04 7.17E-04 . l Xe-131m 1.59E-06 1.67E-06 ! i Xe-133m 1.24E-05 1.31E-05 1 Xe-133 1.28E-05 1.33E-05 ; 5e-135m 2.34E-04 2.50E-04 ' Xe-135 1.27E-04 1.35E-04 i ! Xe-137 9.23E-05 9.84E-05 !
- Xe-138 5.99E-04 6.26E-04
! Ar-41 7.14E-04 7.52E-04 }
- Reference 16.
j ** See footnotes to Table 2.1-2. O l . j HATCH 00CM, REV 3 8/87 5.0-4 1
TABLE 5.0-3 LOCATION-SPECIFIC PARAMETERS FOR THE RECREATION AREA l Location: SSE at 1030 meters l ) ' Estimated Occupancy Factor: 2.37E-02 (208 hours) Ground-level Dispersion and Deposition Parameters:* (X/Q) = 6.42E-6 sec/m*; Depleted (X/Q) = 5.73E-6 sec/m*: (0/Q) = 2.36E-8 1/m* Elevated Dispersion and Depositon Parameters: (X/Q) = 3.30E-8 sec/m8; Depleted (X/Q) = 3.21E-8 sec/m*; (07d) = 1.56E-9 1/m8 ; Elevated Plume Dose Factors:** ) Radionuclide . 7 Body (V) 7 Air (8) I Kr-85m 7.21E-05 7.60E-05 ; ) Kr-85 1.13E-06 1.21E-06 , 1 Kr-87 3.99E-04 4.16E-04 j Kr-88 9.90E-04 1.03E-03 i i ,Kr-89 8.57E-04 8.96E-04 l l Kr-90 6.34E-04 6.68E-04 ' j Xe-131m 1.46E-06 1.53E-06 ' ! Xe-133m 1.14E-05 1.21E-05 , Xe-133 1.17E-05 1.20E-05 , i Xe-135m 2.17E-04 2.33E-04 * ! X6-135 1.18E-04 1.25E-04 i ! Xe-137 8.57E-05 9.14E-05 Xe-138 5.58E-04 5.84E-04 ( i Ar-41 6.66E-04 7.02E-04 i ! l J
- Referene.e 16. '
j ** See footnotes to Table 2.1-2. l f l I 1 iO I 'l ! HATCH 00CM REV 3 8/87 5.0-5 l I
l TA8LE 5.0-4 . O LOCATION-SPECIFIC PARAMETERS FOR THE VISITORS CENTER V Location: WSW at 694 m?ters. > Estimated Occupancy Factor: 4.57E-4 (4 hours) i Ground-level Dispersion and Deposition Parameters:* i (X/Q) = 1.87E-5 sec/m*; Depleted (X/Q) = 1.72E-5 sec/m*; (0/Q) = 5.47E-8 1/m* Elevated Dispersion and Depositon Parameters: ; 4 1 (X/Q) = 5.00E-8 sec/m*; Depleted (X/Q) = 4.97E-8 sec/m*; (0/Q) = 2.26E-9 1/m8 1 Elevated Plume Oose Factors:** !
; Radionuclide 7 Sody (V) 1 Air (8)
Kr-05m 1.47E-04 1.55E-04 1 Kr-85 . 2.34E-06 2. 51 E-06 . . . - l 1 Kr-87 8.27E-04 8.63E-04 i Kr-88 2.06E-03 2.13E-03 .l Kr-89 1.78E-03 1.86E-03
' Kr-90 1.31E-03 1.38E-03 ..
- ) Xe-131m 2.98E-06 3.13E-06
- Xe-133m 2.34E-05 2.48E-05 Xe-133 2.36E-05 2.43E-05 j Xe-135m 4.49E-04 4.80E-04 i Xe-135 2.42E-04 2.57E-04
! Xe-137 1.77E-04 1.89E-04 1
Xe-138 1.16E-03 1.21E-03 Ar-41 1.38E-03 1.46E-03 i
;
- Reference 16.
** See footnotes to Table 2.1-2. l l
I 1O t 1 j HATCH ODCM, REY 3 8/87 5.0-6 l i
i t REFERENCES (Continued) !
- 14. Hatch Nuclear Plant land Use Survey - 1987, Georgia Power Company, !
. February 1987.
- 15. Letter to Georcia Power Company f rom Pickard. Lowe, and Garrick. Inc., ,
Washington. 0.C. , May 11,1987. !
- 16. Letter to Georaia Power company f rom Pickard. Lowe. and Garrick. Inc., -
j Wash'ngton, D.C., June 3, 1987. l
- 17. Letter to Georgia Power Company from Pickard. Lowe. and Garrick. Inc._, '
, Washington, D.C., June 11, 1987. -
- 18. Internal Memorandum. W.H. 0111ncer to 0.M. Honocr Georgia Power i j Company, June 9, 1987.
J ! 19. Letter to Georgia Power Company f rom Quantum Technoloov. Inc., Marietta, Georgia, June 17, 1987. i 1 , 1 1 ; f I L I I i f 4 9 1 l 1 ,
. l l
)I i 1 i i iO l t 1 HATCH 00CM, REV 3 8/87 l
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i^ 1 ! I i i i i { 1 t l Georgia Power Ccapany j Plant E. I. Hatch i Semi-annual Report i Plant Radioactive Effluent Deleases 1 July 1 through December 31, 1987 ! i t Appendix D
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i E.1. HATCH PAXLEAR PLANT j SOLID RADIOACTIVE WASTE l F . PROCESS CONTROL. PROGRAM .
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E.I. HATCH NUCUEAR PLANT SOLID RADIDACTIVE WASTE PROCESS CONTROL PROGRAN l I. Puroose I l The processing of radioactive waste for disposal at a licensed radioactive unste burial site requires triat the waste be appropriately analyzed, processed and packaged, presenting a final waste form that is acceptable for transportation and burial at a licensed radioactive waste' disposal site. The purpose of this Process Control Program is to ddeument the fadioactive waste processing methods .. and the quality control steps that are taken at E.I. Hatch Nuclear Plant to verify compliance with applicable regulatoMrequirements and , iWparticular,S '4 to assure an acceptable' waste product meeting the applicable waste stability, characteristics of 10 CFR 61.56. At Hatch, the routine' processing systems th'at generate radioactive waste requiring off-site dispoisal are the reactor water clean-up system, condensate l clean-up system, spent fuel pool clean-up system and the liquid radweste system. All of these systems employ the use of either ion exchange resins or the powdered ion exchange resins as the processing medium. Spent resins are dewatered in an appropriate liner based on the waste class and burial site criteria. In addition to these processing systems, two other types of op = . radioactive waste that are routinely processed are the compactible and . N non-compactible trash (DAW) and slightly radioactively contaminated ' oils. . l n l t .
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i This Process Control Program addresses the processing of these types of waste , and the measures in-place to assure the generation of an acceptable waste product. Operating criteria for spent resin transfer to an appropriate liner and in-liner dewatering are addressed as are also the criteria for the ; processing of DAW (compactible and non-compactible trash) and miscellaneous contaminated liquids (including oils).
. l 1
II. Reaulatorv Overview - All waste processing, packaging and shipping are conducted in accordance~with' I approved procedures to assure compliance with applicable federal, state and 1 l burial site requirements. Waste processed for disposal is evaluated per I approved plant procedures for compliance with:
- 1) the waste classification requirements of 19 TR 61.55;
- 2) the weste characteristic requirements of 19 CFR 61.56; and a .,
- 3) the mantfest reporting requirements of 19 CFR 29.311.
Waste is packaged in containers meeting or exceeding the requirements for both 2 transportation and disposal. Shipments are conducted in accordance with the i requirements of 49 CFR 172-177 and 19 CFR 71. i All wa'ste processing is performed in a manner consistent with the principles "of ALARA. The procedures that have been developed to cover waste processing oper.stions address appropriate radiation safety measures such as job preplanning, radiation source shielding, and job prerequisites and material requirements so as to minimize stay times. O 2 _ . . _ . _ _ . _ _ _ _ . _ _ . . _ _ _ . _ _ . _ _ _ . _ . _ . . _ _ . , _ - . _ _ . _ . _ .. J
l III. Dewaterina of Resins I The processing of the liquid streams by ion exchange resins (bead or powdered) i results in a waste product that is most appropriately dewatered in a suitable disposal liner (carbon steel of high integrity container). Prior to transfer of ; the spent resin to a liner, a sample is collected and analyzed by gamma sp'doscopy e to quantify the radioactive material csrG.4 ration. Based on this * ) information, the waste is appropriately classified in accordance with apf,rse.-4 procedures, per the criteria of 10 GR 61.55. If a sample of the resins e,annot-be collected prior to transfer to a liner due to either design or operational limitations, a sample collected after transfer or an external radiation level measurement may be used in accordance with approved procedures for determining waste class. . The dowatering process is conducted in accordance with approved procedures with appropriate operating parameters to assure a waste product with as little free l standing water as possible but in no case in excess of 15 by volume (i.e., meeting the waste stability criteria of 10 T R 61.56). The specifics of the l dewatering process vary depending on the type of dewatering process employed
- and the type of resin (bead or powdered). However, the common approach to dewatehing is the removal of essentially all interstitial water. Appropriate verifications (dependent on the process method) are conducted to assure an ,
acceptable waste form.
- The dewatering process at Hatch is a contractor supplied system. Refer to Section VI for the process controls that are applicable.
3
7 IV. Packaaina of D(W (Compactible and h spactible Trash) I All radioactively contaminated trash is appropriately packaged, surveyed and labeled prior to shipment for disposal. Bagged wastes are opened to assure exclusion of unacceptable waste products, such as water and oil. Compactible trash is processed by compaction to reduce the volume of the wastel ! 1 non-compactible materials are segregated and normally packaged separately. - l After packaging, the waste containers are stored awaiting shipment. Container integrity.is verified by visual exanination (post-compaction and pre-shipment)- to assure an acceptable waste package for transportation and an acceptable' waste ! l form for disposal. V. processina of Miscellaneous Lioulds (011) O Periodically it may become necessary to process slightly radioactively contaminated liquids, including oil, for off-site disposal. These liquid wastes are either processed by absorption or solidification. Absorption is accomplished using at least twice as much absorbent as is necessary to completely absorb the liquid 1 only an absorbent approved by the burial site is l used. Any solidification of liquids is conducted in accordance with approved 1 plant' procedures or a contractor supplied solidification procedure that has been specifically developed for the solidification process. (Refer to Section VI for , the use of a contractor or contractor supplied process for waste processing.) The solidification of liquids (including oils) utilizing the on-site mixing unit is conducted in accordance with approved operating procedures and parameters. O 4
l ~ l As appropriate, test samples are conducted every tenth batch to verify the l pre-established mixing ratios. Sampling is accomplished in accordance with approved plant procedures to assure that the samples are representative of the waste being processed. Any unacceptable products require a re-evaluatiori of the ; mixing ratios 1 any unacceptable waste containers are identified (by visual inspection) and appropriate actions taken to assure the waste as shipped meets - t$ applicable waste stability requirements of le CFR 61.56. Additionally, alla containers of the solidified waste are inspected prior to closure to assure a solidified matrix absent of any free standing water. , VI. Use of Contractor for Waste Processina Contractor supplied process and/,or service may be used at Hatch for the processing of radioactive waste for off-site disposal. For the operation of such process, it may be ' desirable to use process control measures and procedures developed by the contractor specifically for the system or process. Therefore, previously addressed process control measures for a particular type waste may be superseded by contractor supplied measures as appropriate. prior to the use of a contractor supplied process or service for waste processing at Hatch, a management review of the contractor's process control and procedures is performed to assure an operation compatible with plant operation and in accordance with regulatory requirements. Contractor supplied waste processing shall be performed in areas with features and/or controls adequate to 2 contain inadvertent spills and overfills. 5
.g .
For processing of waste that is intended to be shipped for disposal -at a i n licensed radioactive waste burial site, additional precautions are taken to assure a final waste product that meets the appropriate waste stability requirements of 10 CFR 61.56.. In particular, the following items, as applicable, are to be documented by the contractor (or Hatch manuals or procedures) prior to utilization for waste processing:
- a general description of the solidification or dewatering process, including type selfdification agent (if applicable), major process .
equipment and interface with plant equipment, types of waste that can.be processed, and operating parameters;
- process control measures that provide'for the verification of the generation of a suitable waste product,-Iincludingeitems (as may be
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' appropriate for the process method) sued as representative sampling, 3- 5 . v. g a. . .,: p .y laboratory tests, {and acceptance criteria; .
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; - specifically approved procedures for the' operation'of the process equipment that will assure operation within the b$unds as delineated by the process n.
control measures; and, ,t. d
- appropriate acceptance criteria for evaluating the acceptability of the final waste product.
Waste products will be verified as meeting the criteria for disposal prior to 2 , final closure of the container. , eV , 6
Georgia Fbwer Company *- "-" J 333 Piedmont Avenue Atlanta, Georgia 30308 Telephone 404 5264526
- Mading Address:
Fbst office Box 4545
" A!!anta, Georgia 30302
- Georgia Power L T. Gucwa t/4 sed *wrt NWrc sym)
Manager Nuclear Safety and Ucensing i SL-4185 1945C X7GJ17-H530 February 26, 1988 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D. C. 20555 PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 SEMI-ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT Gentlemen: Enclosed are six copies of the Plant Hatch Units 1 and 2 Semi-Annual Radioactive Effluent Release Report for July 1,1987 through December 31, 1987. This report is submitted in accordance with the requirements of Technical Specifications Sections 6.9.1.8 and 6.9.1.9. . If you have any questions in this regard, please contact this office at any time. Sincerely,
#2 _=
L. T. Gucwa 4 1 JCJ/lc
Enclosure:
Plant Hatch Semi-Annual Radioactive Effluent Release Report, July 1, 1987 through December 31, 1987. c: (see next page) i\6
Ge'orgia Powerd U. S. Nuclear Regulatory Commission February 26, 1988 Page Two c: Georaia Power Comoany , Mr. J. T. Beckham, Jr., Vice President - Plant Hatch GO-NORMS U. S. Nuclear Regulatory Commission. Washington. D. C. Mr. L. P. Crocker, Licensing Project Manager - Hatch U. S. Nuclear Reaulatorv Commission. Reaion II Dr. J. N. Grace,~ Regional Administrator (2 copies) ' Mr. P. Holmes-Ray, Senior Resident Inspector - Hatch American Nuclear Insurers Mr. L. Cross State of Georaia Mr. J. Setser, DNR
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