ML17219A391
| ML17219A391 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 12/31/1986 |
| From: | Woody C FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| L-87-95, NUDOCS 8703050030 | |
| Download: ML17219A391 (83) | |
Text
{{#Wiki_filter:II J... ha~ REGULATORY INFORMATION DISTRIBUTION SYSTEN (RIDS) ACCESSION NBR: 870305005b DOC. DATE: 86/12/31 NOTARIZED: NO DOCKET i FAC IL: 50-335 St. Luc e P lant> Uni t 1> Fl or i da Power Sr Light Co 05000335 50-389 St. Lucie Plant> Unit 2> Florida Pommer 5 Light Co 05000389 AUTH. NAVE WOODY> C. O. RECIP. NAME AUTHOR. AFFILIATION Florida Power 5 Light Co. RECIPIENT AFFILIATION y~ pN
SUBJECT:
"Combined Semiannual Radioactive Effluent Release Rept for Period Jul ~1986 Dec 1986. " W/870302 I
l tr. DISTRIBUTION CODE: IE48D COPIES RECEIVED: LTR ENCL SIZE: f TITLE: 50. 36a(a) (2) Semiannual Ef luent R'el'eas'e Reports NOTES: 1 RECIPIENT COPIES RECIPIENT .COP IES ID CODE/NAME LTTR ENCL ID CODE/MANE LTTR ENCL PWR-B PD8 LA 1 0 PWR-B PD8 PD 04 5 5 PWR-B PEICSB 3 . 3 INTER NAL: AEOD 1 1 AEOD/PTB 1 IE FILE 1 1 NRR BWR ADTS 1 1 NRR-PWP-A XD 1 1 NRR PWR-B ADTS 1 1 WRat~ePuaa B 1 1 RGN2 FILE 01 1 1 RGN2/DRSS/EPRPB 1 1 RM/DDANI /N I B 1 1 EXTERNAL: LPDR 03 NRC PDR 02 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL '0
's (t
~ 7L I 4 "~
I ~ )~ A5Q ai yD S
FLORIDA PONER h LIGHT COMPANY ST LUCIE PLANT UNITS NO 1 5 2 LICENSE NO DPR-67 8c NPF-16 COMBINED SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD JULY i v 1986 THROUGH DECEMBER 31 1 1986 p 861231 8 7030500 pgOC + P5PPP33 pgR pgR~ R
TABLE OF CONTENTS DESCRIPTION EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION. .......'... 1 SITE VISITOR DOSE FROM EFFLUENTS OFFSITE DOSE CALCULATION MANUAL REVISIONS . SOLID WASTE AND IRRADIATIED FUEL SHIPMENTS....... ~..........
~.........
7 8 8 PROCESS CONTROL PROGRAM REVISIONS................... 8 LIQUID EFFLUENT: SUMMATION OF ALL RELEASES 5 NUCLIDE SUMMATION BY QUARTER WITH EFFLUENT DOBE UNIT ¹1 ~ ~ e ~ ~ seers ~ eee ~ r ~ s ~ ~ ss ~ e ~ ~ ~ ~ ~ s ~ ~ ~ ~ ~ ~ ~ ~ es ~ s ~ 9 U NIT ¹2 ~ sr ~ ~ sr ~ s ~ ~ ~ ~ ~ ass ~ ~ ~ ~ s ~ ~ ees ~ ess ~ se ~ ~ ~ sr ~ see 12 GASEOUS EFFLUENT: SUMMATION OF ALL RELEASES Sc NUCLIDE SUMMATION BY QUARTER WITH EFFLUENT DOSE U NIT ¹ 1 ~ ~ ~ ~ ~ ~ ~ ~ s s r e s e ~ e ~ e ~ ~ ~ ~ ~ ~ s ~ s ~ s e s ~ ~ ~ a s ~ ~ ~ ~ s ~ a 15 U NIT ¹2 ~ ~ ~ s ~ ~ rr ~ a ~ esse ~ s ~ seers ~ rearer ~ s ~ ~ ~ ~ ~ ~ ~ ~ sr ~ 18 SOLID WASTE SHIPMENT SUMMATION ...................... 21 OFFSITE DOSE CALCULATION MANUAL PAGE REVISIONS ..... ATTACHMENT- A
EFTLUBP AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION 1- Regulatory Limits
- 1. 1 For Liquid Waste Effluents
- 4. The concentration of radioactive material released from the site shall be limited to the concentrations specified in 18 CFR Part 28 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 2E-4 micro-Curies/ml total activity.
B. The dose or dose commitment to a NENBER OF THE PUBLIC from radioactive material in liquid effluents released, from each reactor uni t to UNRESTRICTED AREAS shall be limited toa
~
During any calendar quarter to <= 1.5 mrems to the Total Body and to <~ 5 mrems to any organ, and During any calendar year to <~ 3 mrems to the Total Body and to <~ 1$ mrems to any organ.
- 1. 2 For Gaseous Waste Ef f luentsa
- 4. The dose rate in UNRESTRICTED AREAS due to radioactive materials released in gaseous effluents from the site shall be limited toe For Noble gasess <= 588 mrems/yr to the total body and 3888 mrems/yr to the skin, and For Iodine-131, Iodine-133, Tritium~ and all radionuclides in particulate form with half-lives greater than 8 days:
1588 mr(vms/yr to any organ.
+B. The air dose due to noble gases released in gaseous effluents from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the followinga During any calendar quarter, to <~ 5 mrad for gamma radiation,and 18 mrad for beta radiation and~ during any calendar year to 18 mrad for gamma radiation and <~ 2$ mrad for beta radiation. %C. The dose to a NENBER OF THE PUBLIC from Iodine-131~ Iodine-133, Tritium, and all radionuclides in particulate form, with half-lives > 8 Days in gaseous effluents released~ from each reactor unit to areas at and beyond the site boundary, shall be limited to the followinga During any calendar quarter to <~ 7.5 mrem to any organ, and During any calendar year to <= 15 mrem to any organ The calculated doses contained in a semi-annual report shall not apply to any STS LCO. The reported values are based on actual release conditions instead of historical conditions that the STS LCO dose calcuations are based on. The STS LCO dose limits are therefore included in Item 1 of the report, for information only-
EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued) 2.'aximum Permissible Concentrations Water: As per 18 CFR Part 28, Appendix B, Table II'olumn 2, except for entrained or dissolved noble gases as described in 1.1.A of this report. Air: Release concentrations are limited to dose rate limits described in 1.2.A. of this report.
- 3. Average Energy of fission and activation gases in gaseous effluents is not applicable.
- 4. Measurements and approximations of total radioactivity A summary of liquid effluent accounting methods is described in Table 3 1.
A summary of gaseous effluent accounting methods is described in Table 3.2 4.1 Estimate of Errors A. Sampling Error The error associated with volume measurement devices, flow measuring devices~ etc. based on calibration data and design tolerances has been conservatively estimated collectively to be less than plus or minus 1$ percent. B. Analytical error for nuclides Type Average i Max mum liqui d + or 9% + or 3$ % Gaseous + or 1$ % + or 35/
EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION
<Continued)
- 4. Measurements and Approximations of Total Radioactivity (Cont. )
- 4. 1 <Continued)
B. (Conti nued) TABLE 3.1 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS Liquid Sampling Type of Method of Source Frequency Analysis Analysis Each Batch Principal Gamma Emitters pohe as Monitor Monthly Tritium L S. Tank Composite Gross Alpha 8 F P. 1 el eases Quarterly Sr-89~ Sr-9$ ~ Composite h Fe-55 C.S t Continuous Daily Principal Gamma Emitters Releases Grab I-131 for pe he as Samples 4/M Composite Analysis Dissolved 5 Entrained Gases One Batch/ Month p.h. a. Tritium Composite Monthly L.S Alpha Composite Monthly G. F. P. Sr-89, Sr-98~ 8c Fe-55 Composite Quarterly C. S. 1-Boric Acid Evaporator Condensate is normally recovered to the Primary Water Storage Tank for recycling into the reactor coolant system and does not contribute to Liquid Waste Effluent Totals. p.h.a.-Gamma Spectrum Pulse Height Analysis using Lithium Germanium Detectors. All peaks are identified and quantified. L.S.-Liquid Scintillation Counting C. S.-Chemical Separation G.F.P.-Gas Flow Proportional Counting 4/M-Four per Month
EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)
- 4. Measurements and Approximations of Total Radioactivity (Continued)
- 4. 1 (Continued)
B. (Continued) TABLE 3 2 RADIOACTIVE GASEOUS WASTE SAMPLINB AND ANALYSIS Baseou's Sampling Type of Method of Source Frequency Analysis Analysis Haste Bas Decay Tank Each Batch Principal Gamma Emitters p.h a Releases ontainment Principal Gamma Emitters p. h. a. Purge Each Purge Tritium L.S Releases Principal Gamma Emitters p.h. a. Tri tium L. S. Plant Monthly Particulate Vent Composite Gross Alpha G. F. P. Quarterly Particulate Composite Sr-89 h Sr=98 C. S. p.h.a.-Gamma Spectrum Pulse Height Analysis using Lithium Germanium Detectors. All peaks are identified and quantified. L.S.-Liquid Scintillation Counting C. S.-Chemical Separation B.F.P.-Bas Flaw Proportional Counting 4/M-Four per Month
FLORIDA POWER 8c LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 SEMIANNUAL REPORT JULY 1, 1986 THROUGH DECEMBER 31, 1986 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED)
- 5. BATCH RELEASES AND UNPLANNED REKZASES LIQUIDS FOR : ST. LUCIE PLANT UNIT NO. 1 A. NUMBER OF BATCH REKZASES- 22.8 B. TOTAL TIME PERIOD OF BATCH RELEASES- 12788. MINUTES C. MAXIMUM TIME PERIOD FOR A BATCH RELEASE- 715. MINUTES D. AVERAGE TIME PERIOD FOR A BATCH RELEASE- 577. MINUTES E. MINIMUM TIME PERIOD FOR A BATCH RELEASE- 439. MINUTER F. AVERAGE STRAD FLOW DURING REPORTING PERIOD INTO A FLOWING STREAM- 1819733. G.P.M.
- 6. GASEOUS FOR - ST. LUCIE PLANT UNIT NO. 1 A. NUMBER OF BATCH RELEASES- 1.8 B. TOTAL TIME PERIOD OF BATCH REKZASES- 688. MINUTES C. MAXIMUM TIME PERIOD FOR A BATCH RELEASE- 688. MINUTES D. AVERAGE TIME PERIOD FOR A BATCH REKZASE- 688. MINUTES E. MINIMUM TIME PERIOD FOR A BATCH RELEASE: ., 688. MINUTES UNPLANNED RELEASES LIQUIDS FOR - ST. LUCIE PLANT UNIT NO. 1 A. NUHiKR OF RELEASES- 8.
B. TOTAL ACTIVITY REKZASED- 8. CURIE S ,'. 6.. GASEOUS FOR - ST;. LUCIE PLANT UNIT NO. 1 A. NUMBER OF REKZASES'- 8. B. TOTAL ACTIVITY RELEASED- 8. CURIES SEE ATTACHMENTS (IF APPLICABLE) FOR-
, A. A DESCRIPTION OF THE EVENT AND EQUIPMENT INVOLVED.
B. CAUSE(S) FOR THE UNPLANNED RELEASE. C. ACTIONS TAKEN TO PREVENT A RECURRENCE. D. CONSEQUENCES OF THE UNPLANNED REKZASE.
FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 2 SEMIANNUAL REPORT JULY 1, 1986 THROUGH DECEMBER 31, 1986 EFFLUENT AHD WASTE DISPOSAL SUPPLEMENTAL INFOHMATION (CONTINUED)
- 5. BATCH RELEASES AND UNPLANNED RELEASES LIQUIDS FOR - ST. LUCIE PLANT UNIT HO. 2 A. HONE% OF BATCH RELEASES- 22.8 B. TOTAL TIME PERIOD OF BATCH RELEASES- 12788. MINUTES C. MAXIMUM TIME PERIOD FOR h BATCH REUEhSE- 715. MINUTES D. AVERAGE TIME PERIOD FOR h BATCH RELEASE- 577. MINUTES E. MINIMUM TIME PERIOD FOR h BATCH RELEASE- 439. MICH'ES F. AVERAGE STREAM FLOW DURING REPORTING PERIOD INTO h FLOWING STKQLM- 1819733. G.P.M.
- 6. GASEOUS FOR - ST. LUCIE PLANT UNIT NO. 2 A. NUMBER OF BATCH RELEASES: 38.8 B. TOTAL TIME PERIOD OF BATCH RELEASES- 2429. MINUTES C. MAXIMUM TIME PERIOD FOR A BATCH RELEASE- 228. MINUTES D. AVERAGE TIME PERIOD FOR A BATCH RELEASE- 64. MINUT1&
E. MINIMUM TIME PERIOD FOR A BATCH REIZASE- 21. MINUTES UNPLANNED RELEASES LIQUIDS FOR ST. LUCIE PLANT UNIT NO. 2
- h. NUMBER OF RELEASES- 8.
B. TOTAL ACTIVITY RELEASED- 8. CURIES
- 6. GASEOUS FOR: ST,. LOCIE PLANT UNIT NO. 2 A. NUMBER OF RELEASES- 8.
B. TOTAL ACTIVITY RELEASED= 8. CURIES, SEE ATTACHMENTS (IF APPLICABLE) FOR: A. h DESCRIPTION OF THE EVENT AND EQUIPMENT INVOLVED. B. CAUSE(S) FOR THE ONPId9iNED RELEASE. C. ACTIONS TAKEN TO PREVENT h RECURRENCE. D. CONSEQUENCES OF THE UNPLANNED RELEASE.
FLORIDA POWER 8c LIGHT COMPANY ST. LUCIE PLANTS UNITS 1 8r, 2 SEMIANNUAL REPORT JULY 1, 1986 THROUGH DECEMBER 31, 1986
/
EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)
- 7. Assessment of radiation dose from radioactive effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY assume the visitor onsite for 48 hours, at an average distance of 8.3 Kilometers in the worst dispersion direction, and received exposure from each of the two reactor units on the St. Lucie Site.
VISITOR DOSE RESULTS FOR CALENDAR YEAR 1986 WERE: GASEOUS PARTICULATES 8c IODINE EXPOSURE NOBLE GAS EXPOSURE ORGAN DOSE {mrem) Gamma Air Dose 1.28 E-81 mrad Bone 7.88 E-85 Beta Air Dose 2.29 E-81 mrad Liver 2.43 E-84 Thyroid 2.92 E-82 Kidney 8.98 E-85 Lung 1.43 E-84 GI-LLI 1.58 E-84 Total Body 2.98 E-84
't FLORIDA POWER 8r. LIGHT COMPANY ST. LUCIE PLANT UNITS NO. 1 dc 2 SEMIANNUAL REPORT JULY 1, 1986 THROUGH DECRMK& 31, 1986 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)
- 8. Offsite Dose Calculation Hanual Revisions-The affected pages for Revsion 87 to C-288 (ODCH) are included as httachaent-h to this report. The reasons for the changes are as follows-
- 1) Generic changes of an administrative nature-(D/Q)> {X/Q), {X/Q) , Q , gt etc. were changed to read:
D D/Q > X/Q X/Q , QDOT , and dt to reduce entry of D typographical and double usage of these symbols through various word processor limitations and to eliainate the need for hand entered symbols. These changes should improve the Quality Control of the ODCM in this area.
- 2) Where references were made to the Technical Specifications and Limits, the ODCM was updated to the wording of the current
. Technical Specifications. Several typos concerning limits were corrected. These errors had been introduced by Rev 86 on a word processor where the proof reader missed the typos.
- 3) The only methodology change of Rev. 87 concerns Section 1.4 and Appendix -B. A limited analysis dose method may be used based on seven nuclides etc. Based on early 1986 effluent results, Iron-55 dose contribution indicated that a conservatism factor of 8.8 would not be sufficient to cover possible dose contribution from Iron-55. Since the original ODCM Appendix-B was not evaluated for Iron-55, and that Iron-55 results from Quarterly Composite Samples are not immediately availabe, twenty percent is now allocated to Iron-55 alone. This lowers the 8.8. factor of Section 1.4 to 8.6, which should provide more conservatism in estimating dose by the method precribed by this Section.
/
- 9. Solid Waste and Irradiated Fuel Shipments-No irradiated fuel'hipiaents were made froa the site.. Common Solid waste from ST. Lucie Units 1 and 2 were shipped jointly.
A summation of these shipments is given in Table 3.9 of this report.
- 18. Process Control Program Revisions-No revisions were made during the reporting period.
FLORIDA POWER 8r, LIGHT COMPANY ST. LOCIE PLANT UNIT NO. 1 SEMIANNUAL REPORT JULY 1, 1S86 THROUGH DECEMBER 31, 1S86 TABLE 3. 3-1 LIQUID EFFLUENTS SUMMATION OF ALL REEZhSES NUCLIDES RELlldlSED UNIT QUAL.'ER 43 QUARTER 04 A. FISSION AND ACTIVATION PRODUCTS
- 1. TOTAL RELlDlSE (NOT INCLUDING TRITIUM, GASES, ALPHA) CI 4. 88EM1 1. 26E<1
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD UCI/ML 9. 64E-18 2.46E-18 B. TRITIUM TOTAL RELEASE CI 6.93E Hi 7.54E 81
- 2. AVERAGE DILUTED CONCENTlUlTION DURING PERIOD UCI/ML 1.3?EM? '.48E-87 C. DISSOLVED AND ENTRAINED GASES
- 1. TOTAL RELEASE CI 2. 68EM1 1. 54EM1
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD UCI/ML'.15E-18 3.82E-18 D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CI 6. HHE-85 H. HHE-81 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) LITERS 4.88E 87 4.43E 8?
F. VOLUME OF DILUTION WATER USED DURING REPORTING PERIOD LITERS 5.86E 11 5.11E 11
FLORIDh POWER h LIGHT COMPhNY ST. LUCIE PLANT UNIT NO. 1 SEMIANNUAL REPORT 1, 198B THROUGH DECEMBER 31, 1986 TABLE 3.4-1 LIQUID EFFLUENTS NUCLIDES RELEASED UNIT QTR. 43, CONTINUOUS MODE QTR. 44 BATCH MODE QTR. 43 QTR. 44 I-131 CI 1. BHEM2 H.sez-sa 3. SSEM2 2. 65EM2 I-13$ CI 7.74E-83 H.ssz-sa 1. a?EWS 7. 26Z~ Nh-24 CI 8. HSEMa 8. HHEMa 3. 32E~ 8. Hezwa CR-51 CI 8. HHEMa 8. SHEMa 2. 44EMS 1. saz~ MN-54 CI 8. Hez-el 8. HHEMa S. aeEM4 6. 54EM4 FZ-55 CI 8. Hez-el 8. HSEMa 8. 85ZMS 4. S7E-SS CO-57 CI 8. HHEMa 8. HHEMa 2. 49EM4 S. SSEMa CO-58 CI 8. SHEMa 8. HSEMa 1. 98EMa 5. ?SEMS CO-Be CI 8. Sez-81 8. Sez-el 2. 47EM2 2. HBZM2 AG-ile SB-122 CI 8. HSEMa
- 8. Hez-81
- 8. Sez-el
- 8. HSEMa
- i. SSE~ 2. 45EW5 CI S. 31EM4 8. HSEMa SB-124 CI 8. Hez-si 8. SSEMa 2. 84EM2 7.?9E~
RB-88 CI S. SSE-81 8. HHEMa 8. HHEMa 1. 39EMS SR-89 CI 8. Sez-ea 4.21E-83 8. HHEMa 2. 21KW4 SR-98 CI S.HSEMa 8. HHEMa S.HHEMa 2.3SE-85
- 2. 38K~
Za-95 CI 8. SHE-'81 8. SHZ-81 6. 39ZMS NB-95 CI S. Hez-81 8. HHEMa 7. 88ZM4 5. HSZM4 NB-97 CI 8. SSE-81 e. SSEMa 2. 64ZM5 1. 53EW5 TC-99M CI 8. Sez-81 8. Sez-81 6. Bez-85 8. Sez-81 SB-125 CI 8. Sez-el S. SSZ-Sl 7.88K-82 8. 2SZMS CS-134 CI 1.66E-83 8. HHEMa 3. 65ZM2 1.71E-H2 CS-13B CI S.eez-el 8. Sez-sl 3.93E-85 6. aazM5 CS-137 CI 2.89E-SS 8. Hez-el 6.32E-82 S.37E-82 CS-138 CI S. SHEMa S.eez-el 2. 9BEM4 S. 24ZM4 LA-148 CI e. Hez-sa 8. Sez-81 6.87E-84 3.32E-H4 TOTAL FOR PERIOD CI 2.83E-82 4.21E-SS 4.68z-el 1.22EMa KR-85M CI 8. SHEMa H. Sez-el 8. SHZ-Sl 2.42Z-87 XZ-131M CI e.eez-sa 8. SHE-81 8. 99EM4 S.eez-el XZ-133 CI 8. Sez-el 8. SSEMa 2. 5ez-el 1. 51EMa XE-133M CI 8. Hez-Si e. Hez-sa, 2.26E-83 8.2ez-e4 XE-1$ 5 CI 8. SHE-81 8. SHZ-el 7.25E-SS 2.83Z-83 TOTAL FOR PERIOD CI H.SHEMa 2.Bezel 1.54z-el 10
FLORIDA POWER 8c LIGHT COMPANY ST. LUCIE UNIT NO. 1 SEMI-ANNUAL REPORT JULY 1, 1986 THROUGH DECEMBER Si, 1986 TABLE S.5-1 LIQUID EFFLUENTS DOSE SUMMATION Age Group: ADUI T Location- Any ADULT Exposure Interval- January', 1986 through Deceaber 31, 1986 FISH 8'HELLFISH Calendar Year ORGAN Dose (mrem) Bone 4.66 E-81 Liver 2.86 E 88 Thyroid 1.56 EM1 Kidney 8.94 EMS Lung 2.37 E 88 GI-LLI 1.1S E 88 Total Body 5.56 EM1 11
FLORIDA POWER hr, LXGHT COMPANY ST. LUCIE PLANT UNIT NO. 2 SEMXANNUAL REPORT JULY 1, 1986 THROUGH DECEMHER 31, 1986 TABLE 3. $ -2 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER 43 QUARTER 44 A. FISSION AND ACTIVATION PRODUCTS
- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CX 4. 68EW1 1.22E-81
- 2. AVERAGE DILUTED CONCENTRATION 1 DURING PERIOD UCI/ML 9.88E-18 2.38E-18 B. TRITIUM
- 1. TOTAL RELEASE CX 6.92E 81 7.54E 81
- 2. AVERAGE DILUTED CONCENTRATION DURING PERIOD UCI/ML 1. 37E-87 1.48E-87 C. DISSOLVED AND ENTRAINED GASES 1., TOTAL RELEASE CI 2.68E-81 1.54E-81
- 2. AVERAGE DILUTED CONCENTRhTION DURING PERIOD UCI/ML 5. 15E-18 3. 82E-18 D. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL BELEASE CI 6. 88E-85 8. 88E-81 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) LITERS 1. 55E 86 1.22E 86 F. VOLUME OF DILUTXON WATER USED DURING REPORTING PERIOD LITERS 5.8BE 11 5.11E 11 12
FLORIDh POWER A LIGHT COMPhNY ST. LUCIE PLhNT UNIT NO. 2 SEMIANNUhL REPORT 1, 198B THROUGH DECEMBER 31, 1986 . ThBLZ 3.4-2 LIQUID ZFFLUENTS NUCLIDZS CONTINUOUS MODE BhTCH MODE REXJDlSKD UNIT QTR. OS QTR. 44 QTR. 43 QTR. 44 I-131 CI 8. SHEMa 8. HSEMa 3. HSZM2 2. 65EW2 I-133 CI S. Ssz-sl S. SHEMa 1. a?EMS 7. 26K~ Nh-24 CI S.sez-ea 8. HHEMa S. 32EM4 8. HHEMa CR-51 CI 8. HHEMa s. HHEMa 2. 44EWS 1. Saz~ MN-54 CI S.HSEMa s. HHEMa 3.18E-84 B. 54EM4 FZ-55 CI 8. HHEMa 8. SSEMa 8. 85KMS 4. SVEMS. CO-5? CI S.eez-ea 8. Sez-si 2. 49EM4 8. Sez-81 CO-58 CI 8. Hszwa 8. HHKMa 1. 98KMa 5. VSKMS CO-68 CI 8. SSEMa S.sez-sa 2.47E-82 2.HBE-82 hG-118 CI S. HHKMa 8. SHKMa 1. SSEM4 2.45E-85 SB-122 CI 8. Hez-Sa 8. HHEMa 3. SaEM4 S.HHEMa SB-124 CI 8. HHKMa 8. SHK-81 2. 84EM2 7. 79K~ RB-88 CI S.eez-sa 8. Sez-si 8. Sez-81 1. 39ZMS SR-89 CI 8. HSE-81 8. Hez-sl 8. SHK-81 2. 21K~ SR-98 CI 8. HHEMa 8. SHEMa S.sez-ea 2. SHEM5 ZR-95 CI S. SSE-81 8. SHE-81 2.38K-84 6.39K-85 NB-95 CI S.eez-ea 8. SHEMa 7. 88EM4 5. HSEM4 NB-97 CI s. HHKMa 8. SSK-81 2.B4K-85 1.53E-SS TC-99M CI 8. Hez-sl 8. Sez-Si B.68E-S5 S.SHE-81 SB-125 CI 8. Sez-si 8. HHEMa 7. HSKM2 8.23E-HS CS-134 CI 8. SHEMa 8. Sez-sl 3. 65EM2 1. 71EW2 CS-136 CI 8. SSK-81 8. SSK-81 3. 9SKM5 B.ilz-85 CB-137 CI 8. Sez-sa 8. Sez-sa 6.32E-82 S. SVEM2 CS-138 CI 8. SSE-81 8. SHEMa 2. 96KM4 3.24K-S4 Lh-148 CI 8. HHEMa 8. Sez-sl B.evz-84 3.S2E-84 TOThL FOR PERIOD CI 8. SSEMa 8. SHE-81 4. 68E-Hl 1. 22z-ei XE-131M CI 8. SHKM1 S. SHE-81 8.99E-84 8. SSKMa XE-133 CI 8. HHZ-81 S.ssz-sa 2. 5SEMa 1.51Z-Si XE-1SSM CI S. SHKMa 8. SSEMa 2.2BE-SS 8. 28KM4 xz-135 CI 8. HHEMa 8. SHEMa 7.25E-83 2. 83EMS TOThL FOR PERIOD CI 8. HHEMa 8; Sez-81 .2. Bez-81 1. 54z-si 13
FLORIDA POWER Sc LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMI-ANNUAL REPORT JULY 1, 198B THROUGH DECEMBER S1, 1986 TABLE S.5-2 LIQUID EFFLUENTS DOSE SUMMATION Age Group- ADULT Location: Any ADULT Exposure Interval- January 1, 1986 through December 31, 1986 FISH 8c SHELLFISH Calendar Year ORGAN Dose (mrem) Bone 4.64 E-81 Liver 2.8B E 88 Thyroid 1.31 EW1 Kidney 8.83 E-83 Lung 2.37 E 88 GI-LLI 1.13 E 88 Total Body 5.54 E-81 14
FLORIDA POWER h LIGHT COHPANY ST. LUCIE PLANT UNIT NO. REPORT 1'EHIANNUAL JULY 1, 1986 THROUGH DECEMBER 31, 19BB TABLE 3. 6-1 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES NUCLXDES REL15lSED UNIT QUARTER 43 QUARTER 44 A. FISSION AND ACTIVATION GASES
- 1. TOTAL RELEASE CI 6.87E 83 5.35E 83
- 2. AVERAGE REHRhSE RATE FOR PERIOD UCI/SEC 1.12E 83 B.73E 82 B. IODINES
- i. TOTAL IODINE-131 CI 2. 76EM2 1.95E-82
- 2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 3.47EM3 2. 4BEM3 C. PARTICULATES
- 1. PARTICULATES T-1/2 > 8 DAYS CI 1.13E-85
- 2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 2. 57E-86 1. 43EMB
- 3. GROSS ALPHA RADIOACTIVITY CI '1.58E-87 1.75E-HB D. TRITIUM
- 1. TOTAL RELEASE CI 6.45E 88 4.28E 88
- 2. AVERAGE REIZASE RATE FOR PERIOD UCI/SEC 8.11E-81 5. 28EM1 15
FLORIDA POWER 8r, LIGHT 'COMPhNY ST. LUCIE PLANT UNIT NO. 1 SEMIANNUAL REPORT 1, 1986 THROUGH DECEMBER 31, 1988 TABLE 3. 7-1 GASEOUS EFFLUENTS GROUND LEVEL REQQLSES NUCLIDES CONTINUOUS MODE BATCH MODE RELEASED UNIT QTR. ¹3 QTR. ¹4 QTR. ¹3 QTR. ¹4
- 1. NOBLE GASES AR-41 CI 8. SSE-81 8. 88Ewa 2.94E-82 8. SSE-81 KR-85M CI 6.32E sa 8.85E Si 2.'$7EM2 s. 88EMa KR-87 CI 1.51E 88 5.68E 88 8. SSEMa 8. SSE-81 KR-88 CI 4.55E 81 6.7SE Si s. 88EMa 8. 88Ewa XE-131M CI 8. SSEMa S.SSE-81 7.36E-81 8. 88EMa XE-1SS CI 7.97E 83 4.42E 83 7.28E 81 8. SSEMa XE-133M CI 8.88E 81 6.88E Si 7. 58EMa 8. SSE-81 XE-135 CI 6.39E 82 7.11E 82 1.88E 88 S. SSE-81 XE-135M CI 8. SSE-81 2.83E 88 8. 88EMa 8.88E-81 TOTAL FOR PERIOD CI 8.88E 83 5.35E 83 7.5SE 81 8.88E-81
- 2. IODINE I-131 CI 2.76E-82 1.95E-82 I-132 CI B. 57EMS 4. 29EM2 I-133 CI 3.91E-82 "4.19E-82 I-135 CI 1.87E-82 3.56E-82 TOTAL FOR PERIOD CI 8. 39E-82 1. 48E-Si
- 3. PARTICULATE CO-68 CI 6. 28EMB 8. SSE-81 RB-88 CI 1.17E 88 9.29E-81 SR-88 CI 8. SSEMa 1.17E-86 TC-98M CI 1.41E-84 8. SSEMa CS-137 CI 1.42E-85 1.82E-85 TOTAL FOR PERIOD CI 1.17E 88 9.28E-,81 16
FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT 0 1 TABLE 3.8-1
'GASEOUS EFFLUENTS DOSE SUMMATION QUARTER 4 N.A.
Age Group= INFANT Exposure Interval= January 1, 1986 through December 31, 1986 NOTE- The below dose results were calculated using actual meterological data during the specified time interval with Met data reduced as per Reg. Guide 1.111, March 1976 PATHWAY Ground Plane (A) BONE mrem LIVER
%rem 8.88 EW1 8.88 E-81 THYROID mrem 8.88 E-81 KIDNEY mrem LUNG Rlrem GI-LLI area 8.88 EM1 8.88 EM1 8.88 E-81
'rT. BODY em 2 18 R-84 Grass-Cow-Milk(B) 1.49 E-82 1.82 E-82 5.78 E 88 4.59 E-83 2.85 EW4 1.83 EM3 1.86 E-82 Inhalation (A) 2.85 E-84 4.79 E-84 7.63 E-82 1.64 E-84 2.14 E~ 2.34 E-84 3.34 E~
TOTAL 1.51 EM2 1.87 EW2 5.78 E 88 4.76 EM3 4.99 E~ 1.27 EM3 1.11 E-82 (A) -Sector - SOUTH Range: 3.25 miles (B)-Sector - WEST Range- 4.25 miles (Default Animal) CALENDAR YEAR NOBLE GASES (mrad) Gamma Air Dose 2.91 E-81 Beta Air Dose 6.87 E-81 Sector - SOUTH Range= 3. 25 miles
FLORIDh HER hr, LIGHT COMPANY ST. LUCXE PLANT UNIT NO. 2 SEHIANNUAL REPORT 1, 1986 THROUGH DECEMBER 31, 198B ThBLE 3. 6-2 GASEOUS.EFFLUENTS SUSTION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER 43 QUARTER 44
- h. FISSXON AND hCTIVhTION GASES
- 1. TOTAL REIZhRE CI 2.52E 83 2.41E 83
- 2. hVEMGE RELEASE MTE FOR PERIOD UCI/SEC 3. 18E 82 3.83E 82 B. IODXNES
- i. TOTAL IODINE-131 CI 1. 36EM2 1. 82E-82
- 2. hVERAGE RELEASE MTE FOR PERIOD UCI/SEC 1.71EM3 1.28E-83 C. PARTICULATES
- 1. PARTICULATES T-1/2 ) 8 DhYS CI 1.26E-85 2.84E-86
- 2. hVERAGE REL19lBE MTE FOR PERIOD UCI/SEC 1.58EWS 2.57E-87
- 3. GROSS hLPHh RADIOhCTIVITY CI 3.97E-88 '.18E-88 D. TRITXUH TOTAL RELEASE CI 1.28E 81 1.69E 81
- 2. hVEMGE RELEASE RATE FOR PERIOD UCI/SEC 1.B1E 88 2.13E 88 18
FLORZ POWER Sc LIGHT COMPhNY ST. LUCRE PLANT UNIT NO. 2 SEMIANNUAL REPORT 1, 1986 THROUGH DECEMBER 31 1986 TABLE 3. 7-2 GASEOUS EFFLUENTS GROUND LEVEL REILEASES NUCLIDES CONTINUOUS MODE BATCH MODE RELEASED UNIT 'TR. ¹3 QTR. ¹4 QTR. ¹3 QTR. ¹4
- 1. NOBLE GASES AR-41 CI 8. SSEMa 8.88E-sa 8.46E-Sl S.BSE-Si ER-85 CI S. SSE-81 s. ssz-81 1. 19EM2 8. 88Ewa KR-85M CI a.e2E 81 2.18E Si 1. 29EW2 8. 88EMS ER-88 CI 1.84E 81 1.97E 81 3.98E-84 2. 72EMS XE-131M CI 8. SSEMa 8. SSEMa 4. 2BEMa 2. 3SEMa XE-133 CI 2.18E 83 2.85K 83 3.28E 81 1.55E 81 XE-133M CI 1.11E Si 1.88E Si 2. 84EWa 1.66E-Sl XE-135 CI 2.74E 82 2.79E 82 2. BBEMa 1. 71EW1 TOTAL FOR PERIOD CI 2.49E 83 2.S9E 83 3.39E 81 1.64E Si
- 2. IODINE I-131 CI 1. 36E-82 1. 82EM2 I-132 CI 1. 34EMS 3.96E-84 I-133 CI 1.26E-82 8. 89EMS TOTAL FOR PERIOD CI 2.74E-82 1.85E-82
- 3. PARTICULATE RB-88 CI 8. SSE-81 1.77E 88 CS-137 CI 1. 26EW5 2. 84EWB CS-138 CI 2.68E-82 8. SSE-Sl TOTAL FOR, PERIOD CI 2. 68E-82 1. 77E SS
'19
FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT 0 2 TABLE 3.8-2 GASEOUS EFFLUENTS BOSE SUMMATION QUARTER 0 N.A. Age Group-" INFANT Exposure Interval- January 1, 1986 through December 31, 1986 NOTE= The below dose results were calculated using actual meterological data during the specified time interval with Met data reduced as per Reg. Guide 1.111, March 1976 BONE LIVER THYROID KIDNEY LUNG GI-LLI T. BODY PATHWAY mrcm mrem Inrcm mrcm mrcm mrcm mrem Ground Plane (A) 8.88 R-81 S.SS R-Sl S.SS E-Sl 8.88 R-81 8.88 E-Sl 8.88 E-Si' 86 E-86 Grass-Cow-Milk(B) 2.SS E-83 $ .87 E-SS 8 77 EW1 8 89 EM4 2.8S E-84 3.88. EW4 1.87 E-83 Inhalation (A) 2.69 EW5 2.45 E-84 1.82 E-82 1.88 E-84 2.12 EM4 2.13 E-84 2.27 E-84 TOTAL 2.36 E-83 3.31 E-83 8.87 E-81 9.18 E-84 4.95 EM4 6.81 E-84 2.13 EM3 (A)-Sector - SOUTH Range- 3.25 miles (B)-Sector - WEST Range: 4.25 miles (Default Animal) CAIZNDAR YEAR NOBLE GASES (mrad) Gamma Air Dose 1.37 E-81 Beta Air Dose 2.86 E-81 Sector - SOUTH Range- 3.25 miles
FLORIDA POWER & LIGHT COMPANY ST LUCIE PLANT SEMIANNUAL REPORT JULY 1, 1986 THROUGH DECEMBER 31, 1986 UNITS 1 AND 2, TABLE 3.9 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid Waste Shipped Off-site for Burial or Disposal
- 1. TYPE OF WASTE UNIT 6 MONTH PERIOD ERROR
- a. Spent Resins, M3 5.10E+1 2.0E+1 Process Filters Ci 1.40E+2
- b. Dry Compressible M3 1.62E+2 2.0E+1 Waste Ci 6.92E+0
- c. Irradiated M3 0.00 N/A Components Ci 0.00
- d. Other
- 1. Solidified M3 1.17E+1 2.0E+1 STP* Sludge CI 1.70E-2
- 2. Estimate of Mayor Nuclide Composition (by type of waste)
- a. 60 Co 25.2 58 Co 22.3 137 Cs 22.0 134 Cs 10.5 55 Fe 7.3 63 Ni 2.9 54 Mn 2.2 95 Nb 2.0 3 H 2.0 51 Cr 1.3 95 Zr 1.0
- b. 137 Cs 26.4 60 Co 18.3 134 Cs 14.4 55 Fe ,13.9 9.7
'814 C Co 8.0 54,Mn 2.1 63 Ni 2.0 3 H 1.8 125 Sb 0.9 144 Ce 0.8 131 I 0.8
- STP Sewage Treatment Plant 2I
c N/A
- d. 60 Co 93.0 137 Cs 4.0
- 3. Solid Waste Disposition Number of Shi ments Mode of Trans ortation Destination 14 Sole Use Truck Barnwell, 'S.C.
B. Irradiated Fuel Shipments Number of Shi ment Mode of Trans ortation Destination 0 N/A N/A N/A Not Applicable 22
Waste Total Total Principal Type Category Type of Container Solidification Classification Volume Curies Radionuclide of Agent Waste Note 1 Notes 1 6 2 Note 3 R.G. 1.21 Note 4 Class A 5520ft 0.96 N/A PWR l.b. Non-specification None Trash strong tight package Class A 412ft 0.017 N/A STP* l.d. Non-specification Cement Sludge strong tight package Class A 909ft 2.03 Cs PWR Ion l.a. Non-specification None Exchange strong tight package Resin Ca) Class A 193ft 5.96 Csl37 C14 PWR l.b. NRC Certified LSA None Sr ,Ni 3 Trash >Type A Class A 386ft 22.48 Cs ,Co , PWR Ion l.a. NRC Certified LSA None Sr ,Ni Exchange >Type A Resin Class B 386ft 51.07 Co ,Cs , PWR Ion l.a. NRC Certified LSA None Sr ,Ni Exchange >Type A Resin Class C 119ft3 63.7 CO60,cs137, PWR l.a. NRC Certified None Sr90 Ni63, Process Type B . Pu241 Filters
*Sewage Treatment Plant
I FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE PLANT SEMIANNUAL REPORT JULY li 1986 THROUGH DECEMBER UNITS 1 AND 2 TABLE 3.9 (CONT.) 3li 1986 SOLID WASTE SUPPLEMENT The total curie quantity and radionuclide composition of solid waste shipped from the St. Lucie Unit 1 & 2 are determined using a combination of qualitative and quantitive techniques. In general, the St. Lucie Plant follows the guidelines outlined in the Low Level Waste Licensing Branch Technical Position (BTP,) on Radioactive Waste Classification (5/ll/83) for these determinations. The most frequently used techniques for determining the total curie quantity in a package are the dose to curie methods and the (concentration) x (Volume or Mass) calculations. Where appropriate, engineering type activation analyses may be applied. Since each of the above methodologies involves to some extent qualitative parameters, the total curie quantity is considered to be an estimate. The composition of radionuclides in the waste is determined by both on-site analyses for principal gamma emitters and periodic off-site analyses for other radionuclides. The on-site analyses are performed either on a batch basis or on a routine basis using reasonably representative samples as appropriate for the waste type. Off-site analyses are used to establish scaling factors or other estimates for, radionuclides such 3H< 14C~ 99Tct 129I ~ TRU241pu< 242Cm< 63Ni z and Fe "Principal Radionuclides" refer to those radionuclides contained in the waste in concentrations greater than .Ol times the concentration of the nuclides listed in Table 1 or .Ol times the smallest concentration of the nuclides listed in Table 2 .of 10 CFR 61. "Type of Waste is generally specified as described in NUREG 0782, Draft Environment Impact Statement on 10 'CFR 61 "Licensing Requirements for Land Disposal .of Radioactive Waste".. "Type of Container" refers to the transport package. 24
ATTACH%AT-h TO SEMIANNUAL REPORT O.D.C.M. REVISED PAGES AS PER TECHNICAL SPECIPICATION 8. 14. 2
2 Page 1 of 84 HDREA P%ER & LKH1'NPANY SI'. IIKZE OHMTIN PROCHXJRE Mo O-ZO PIANI'BKSIRY REVISE 7 COPY 2 TZILE: Offsite Dose Calculathn Manual (OKM) REVIN A% Appmved by by APPROVAL'eviewed Facility Review ~C. M. Wethy AprD 22 1982 Revision 7 Reviewed by F R G 19 g Appmved by' v]7 S OPS DATE DOCT PROCEDURE DOCN C-200 SYS COMP COMPLETED ITM 7
Page 5 of 84 ST+ LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) Dose fmm Beta Radiaticn
- Cubic centinnter
- (Dries - a unit of zadiaacivity see uCi
- Activity ar mncentzaticn of a mclide in the release source.
Units of u"i, uCL/cc, or uQ./ml
- Qxh of Fedezal Regulatians
- 'IIa,exposuze, in mzem ar nuad, the oryn or the individual receives from zadioactive ef Quents Dose Factar - NorrnQ1y, a factor that converts the effect of hqpstfng zadioactive naterial into the body, to dose to a pacific organ. Body elindnatim, xadiosctive decay, snd organ uptake are sana of the factors that determba a dose factor for a given aucUde Dose Pathway A specific path that radioactive naterial physically tzavels thmugh prior to exposing an individual to zadiatim. 'Ihe Gzss~~lk-Infant is a dose pathway Dose Bate -'Ihe dose received per unit tina (D/a) A long term D over Q a factor with units of I/M which describes the depositicn of paxticulc~ matter fmm a plume at a point dawnzange fmm the souxce. It can be thaught of as what part of the cloud is going to fallout snd deposit over ane square meter of gmund. (See Appendix F).
- A gemna photcn - 'Ihe dose fmm Gsnnas in air, etc.
Radioactive material deposited uniformly over the gmund emits radiation that pzoduoes an exposure pathway when an individual is standing, sitting, etc., in the area. It is sssunad that an adult zeceives the sana exposure as an infant, zegerdless of the physical heigt diffezemes. Only the total body is ccasidezed for the QXK
- Hydmgen-3, or Tritium, a weak Beta emitter Badioiodines and particulates with half-lives greater than.8 days M) Limiting conditicn for cqezatian in SIS m - Cubic Meters
~ "m - Square Meters
- Maxinum Permissible Ccncentration
- For the puxposes of this nanual, a radioactive isotope. Nuclide (i) signifies a specific nuclide, the 1st, 2nd, 3rd me under ccnsidexaticn. If nuclide (i) is I-131, then the Mi (dose factar) under ansidexaticn should be MI-131 f
Page 6 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) GMSSARY OF CNM)NLY USED 'IHNS continued
- For the OKM either the bone, liver, thymid, kidney, lung, Gl~, or the T.
Body. Total Body is ccnsidezed m organ for ease of writing the nnthodology in the OKM. (QDot), - (Quot)i - Demtes a release zate in uCi/sec far mcdade (i).
- Denotes uCi of nuclide (i) released aver a specified time interval.
Radioiodine s - Iodine-131 snd Iodine I-133 for gaseous release pathways. receptor - The individual zeceivtng the expomze in a given locatt,cn or who ingests food pmducts fmm an aninal for exanple. A zeceptar csn zeceive dose fmm cne or naze paQways. Re3ease Source(s) - A subsystem, tank,'r vent where zadioactive naterial can be n leased independently of other zadicactive zelease points. SIS - 'Ihe St. Lucie Plant Standard Technical Specificaticns UX nd,cm Curies. 1 ~ ~ 10+ (Dries. 'Jhe.uCi is the standard unit af zadioactivity for aH. @se ca1culations in the OMM. (x/Q) . - A long term Chi over Q. It describes the physical dispersim characteristics of a send. infinite cloud of noble gases as the cioud tzaverses downamge fmm th release point. Since Noble Gases aze inert, they do not tend to settle out m the ground. (See Appendix F). (X/Q)D
~ - A lcng term Depleted Chi over Q. It describes the physical dhpezsicn characteristics of a send.~inite cloud of radioactive iodines and particulates as the cloud tzavels dawnzange. Since Iodines and particulates tend to settle out (fallout of the cloud) on the gmund, the (X/Q)D zepzesents what physically zennins of the cloud snd its dig>ersim qualities at a given locaticn downnmge fmm the release point. (See Appendix F).
- A specific delta tina interval that corze@mds with the release interval Rta etc.
pl J
Page 9 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.2 (can~) R ~ ihe undiluted zelease rate in gpm of the release source. Liquid Rad Waste ~ 150 gpm Steam Generator ~ 125 gpm/Steam Geneatar D ~ 'Ihe d1tuticn flaw hx gpm of Intake Cooling &ter or CizaQsting Water Pcs Intake Cooling flaw is 14,500 gpm/punp Cixculsting Water flaw is 121,000 gpm/punp Ci ~ 'Ihe undiluted ancentzatim of nuclide (i) in tCf/niL fmm sanple assay (MPC)i ~ %he naxinum permissiblelinnet ccncentzaticn of nuclide (i) in uCi/ml fmg Table Id-1. For dissolved or eutzainsd noble gases the MPC vatue is 2 X 10 uCf/ml far the sum of all gases.
'Ihe fzactica of the 10CFR20 MPC nay be deterntined by a zacli~~uclide evatuatim or for purposes of sisplifying tha calmlatim by a cusuIstiva activity evatuatice. If the sinplified nathod is used, the value of 3 X 10 uCi/ml (unidentified MPC value) should be substituted for (MPC)i and the cunulative ccncentzaticn (sum of all identified radicnuclide cancentraticns) or the gmss cmcentmtion should be mbstitutNd for Ci. As 1mg as the diluted cmcantration l
(Ctota R/D) is less than 3 X 10 uCi /ml, the mcl ih~ucli i de calculst icn s not required to denxnstzate conplisnce with the 10CFR20 MPC 1ind.t. 'Ihe following section pmvides a stagery-step pmceduze for determtning the MPC fzacticn.
- 1. Calculation Pmcess for Solids A. Obtain fran the ~lant pmceduzesp the zelease rate value (R) in gpm for the zelease source.
B. Obtain fmm the in-plant pmceduzesp the dilutian rate (D) in gpm. No credit is taken for any diluticn beycnd the discharge aual flaw. C. Obtain (Ci), the undh.luted assay value of nuclide (i), in 'uCi/ml. If the sinplified method is used, the cunulative ccncentratim (C ~) is used. D. Fmm Table L-l, obtain the corzespcnding (MPC) for nuclide (i) in uCi/ml. 'Ihe value of 3 X 10 uCi/ml shauld be used for the sinplified method. E. Divide Ci by (MPC)i snd write dawn the quotient F. If the sinplified natl's used, pmaeed to the next step. If determining the MPC fzacticn by the mcli~mclide evaluaticn, repeat steps 1.2.1.C thmugh 1.2.1.E for each nuclide reported in the assay, for H3 fmm pzeviaus meath conposite, and for SR89/90 and Fe55 fmm pzeviaus quarter mnposite. G. Add each Ci/(MPC) quotient fmm step 1.2.1.E and salve for FL as follaws: R C Fb D 2i~1 (~HPC i
Page 10 of 84 ST. LUCIE PLANT CHEMISZRY OPERATING PROCEDURE NO ~ C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.2 (contiaued)
- 1. (continued)
G. (cmtiaued) FL a mt-less ~e Mme: the value of FL could be ( or >l. 2m purpose of the caluculatim is to determtae what the initial value of F is for a given set of release conditims. If FL is >1, admfrdstrakve steps are taken to enrnze that the actual release cmditims for dftutim willensure that F is <1 during the actual zelease. FL is called the ftnctim of 10CHt9 MPC because it dxxiLd near be allowed to be >l.
- 2. Chlculatim Process for Gases in Liquid A. Sum the uCf/ml of each noble gps activity reported in the z.lease.
B. Ihe values of R md D from 1.2.1 above sla11 be used in the calculations belrow: F ~ (sum of 1.2.2.A) uCi/ml XR 1 D C- F shQ1 be less than 2 X 10 g uCi/ml for the site for all releases in pzogzess. Each zelesse point will be admfnistratively coutro11ed. Consult fa-plant pzoceduzes for instructions 1.3 Determfafag Setpoints for Radicactive Liquid Efftuerrt Monitors Dfscussfm Technical Specificatim 3.3.3.9 zequizes that the liquid effluent monitoring instzurrantatfm alarm/trip setpoints be set to initiate an alarm or trip so that the zadfoactivity ancentzatfm in water in the uruastrfcted area does aot exceed the cmceatzatim of 10CFRX, Appendix B, Table II as a result of radioactivity in liquid effluents. (Technical Specificatim 3.11.1.1). This secticn presents the nathod to be used for determfniag the instzurreatatim setpoints. Gross cpm vs, total liquid,activity curves aze available for Liquid Effluent Mmitors based on a corrposite of real zelease data. A direct corzelatim between gross cpm and tte cmcentzatfms that would achieve 10CFR20 MPC levels in the dfsdar ge canal can be estimated. 'Ihe 1978 liqufd release data fzom semf~l reports was used to deterrrdae the avezage undiluted zelease cmcentratfcn. 'Ihese cmcentzatims were then pro~ted to a diluted cmcentzatfm in the discharge caral asamdag a 1 gpm release rate and a constant dilutim flow of 121,000 gpm from 1 circ. water purrp. 'Ms diluted activity was divided by th. nuclide's zespective 10CFR20 MPC value (Table L-I) to obtain the Mi colurrn m the table that follows:
@ Al Page 12 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODOM) 1.3 (continued) ATot is the total avezage uCL/ml concentzatian of the zefezeme mbCuze mid Slat is the fzactirn of the MPC of all nuclides for the release ccnditicas ~ified. Dividing o yields A ~ which is the iiaxi um total activity a centzaticn equivalent to the HK IIimit for Bie nuclide distribution typical of zndwaste disdiarges. 4.01 EH ~ 0.302 ~/ml Mlot The asampticn that the mfxtuze does ixit change is cnly used for ca3culaticnal puzposeso
- 1. The (C~) value in cpm should be obtained for the A x (0'302 uCi ml) fzom the mlease sources radioactive liquid effluent maiitor curve of cpm vs. uCi/ml.
N7IE This setpoint is for a specified release of 1 gpm into 121000 gpm dilution flow.
- 2. For estabiishfng the setpoint prior to liquid radwaste discharges, the (C ) will be ad)usted as iz eded to account for actual zelease ccnditicns (i.e., actmZ liquid dischar~ flow zate md dUuticn Qaw).
1.4 Determinitig the Dose for Badi.oactive Liquid Releases Discussicn - TIechnical Specificaticn 3.11.1.2 requires calculations be perforned at least ence per 31 days to verify that cumulative zadicective liquid eEQuents R not cause a dose in excess of 1.5 mzem to the total body and 5 mrem to any aran during any calendar quarter and mt in excess of 3 mzem to the total body and 10 mmn to any orun during any caleiidar year. This secticn presents calculatiaial nathod to be used for this verificaticn. This nathod is based on the nethodology su@usted by sections 4.3 and 4.3.1 of NUREG-0133 Revision 1, november, 1978. The dose factors are a conposite of both the fish and shellfish pathways so that the fis~hellfish pathway is the aily pathway for which bee will be calculated. For St. Tucie Plant, the adult is the nest limiting age
.group, but the dose for child, and teaa~r csn also be calculated by this nathod provided that their appropriate dose factors are available for the organ of intezest.
Only those aiclides that appear in the TaMes of this mmual will be ccasidezed. I. This method provides for a chse calculation to the total body or any organ for a given age group based on zeal re1aase conditiais during a specified tiki interval for zadioactive liquid release sources. The equatim is: DL AiT dt1 Qil (DF)1
Page 13 of 84 STe LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM). 1.4 (aatinued)
- 1. (continued)
Whexe: DL ~ dose counftnent in nrem received by argm T of age group (to be pacified) during the zelease time interval dtl. AiT ~ the conpasite dose factor for the fis~hellfish pathway far nuclide (i) for argan T of age gmup (to be miffed). The A<T vetues listed in the Tables in this nanual are indeImdent opatoj cate ttmctaic htfoammtton etat have the nnltm mnmrml Qf>
- th
~ 2m
~of ~ ~ ~~~~.
total qentity zh of nuclide (i) tan ze1ease during dtl (uCi) lit't, (DP)1~ 'Ihe total vohma of dilutfan that occurzed during the zelease tfna period dtl (i.e., the circulating water Qaw times time)
'ihe doses associated with each zelesse nay then be sunned to pmvide the cunulative dose over a desized thn period (e.g., aun all doses for znlease during a 31 day period, calendar quarter or a year).
Dt~ + D Raze: Q ~ the total due comnftnant to ccgm T due to all releases during the desired time interval (mzem) Based on the zadfcnuclide distrfbutfcn typical in radioactive efQuents, the
~, ~5, calculated doses to individuals aze dominated by the zadfmoclides Fe-59, Co-58, Nr95, Cs-l34 and Cs-137. 'Ihese mclfdes typically antribute over 95X of the total body dose md over 90K of the GIWLI dose, which is the crftfcal orgm. Therefore, the dose comnftnant due to zadfoactivity in liquid effluents nay be zeasonably evaluated by limfting the dose calculatfm pmcess to these zadicnuclides for the adult total body md adult (H-LLI. To aUaw for any unexpected varfabflity in the zadiceuclide distribution, a conservatism factor of 0.6 is introduced into the equatfzn. After calculating the dose based on these 7 nuclides, the amulative dose should be divided by 0.6, the ccnservatism factor.
(i.e., Q +0.6). Refer to Appends B for a detailed evalusticn and exp1aratfcn of this Iimfted aaQysis approach.
'Ihe nethodalogy that folZaws is a ste~tep bzeskdawn to calnQate doses based on the above equaticn. Refer to the in~lant pmceduzes to deteanfne the applicable organs, age groups, and pathway factars. If the lfmfted analysfs approach is used, the calculation should be limited to the Adult total body dose and Adult GI-LLX dose fmm the fish and shellfish pathways. 'nly M 7 previously
-specified zadfcauclides should be evaluated. For the dose calculaticas to be included in semf~uual reports, the, doses to the adult gmups and all orgms should be evaluated for all zadicauclides identified in the liquid efQuents.
KGE Table 1.4 pmvfdes a convenient form for mnpfling the dose accounting
/R7
Page 14 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NOe C-200s REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.4 (continued)
- l. (continued)
A. Daterttdne the tea interval dtl that the n lease tock place. %e in~lant pmo dures shall describe the pmcedure for calculating dtl for official xelease purposes. B. Obtain (DF 1 for the tise period dtl fmm Liquid Waste Haraymnt Records for the release source(s) of intexeste
, C. Obtain Qi for nuclide (i) for the time period dtl fmm the Liquid QLste Management Records D., Obtain AiT fmm the spprcpriste Liquid Dose Factor Table TABLE 1.4 FISH AtG %ELLFISH PA%RAY TIME/nm SVZr. / / TIME/nez SrOP. / /
XKAL DIUJZZN VOIlNE: mls AGE GROUP: OBM: KSE FACIOR TABLE 8: NKLIDE i C uCi Fe-59
'IDIAL KSE If based m limited aralysis, divide by 0. 6 E. Solve for Sore (f)
Dose (i) ~Q 1 iT DF 1
Page 15 of 84 ST LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NOe C 200~ REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.4 (cmtinued)
- 1. (continued)
F. Repeat steps 1.4.1.C through 1.4.1.E for each nuclide zeported and each orgy zequized. If the limited axalysis method is used, limit the zadicnuclides to Fe-59, Go-58, Gr60, ZrHi5, NM5, Cs-134, and Cs-137 and deterndxe the adQ.t total body dose and the adult GI~ dose. G. Sum the Dose (i) values to obtain the total dose to mgm T fmm the fish-shellfish pathay. If the limited analysis method is being used, divide the cumulative dose by a conservatism factor of 0.6 to acmunt for any unexpected variability in zadicauclide distrlbuticn 1.5 Pro ct Dose for Radioactive Li uid Effluents Mscussim Vxhnical Specification 3.11.1.3 requires that appropriate subsystens of the liquid zadwaste treatment system be used to reduce zadicactive naterial in liquid efftuents when the pm~ted aanthly dose due to liquid releases to unrestricted areas when averaged over 31 days would exceed 0.06 mzem to the total body or 0.2 mzem to any organ. Doses are to be pm~ted at least once per 31 days. The following calculaticn method is pmvided for performIng this dose pzo~tim. 'Ihe aathod is based cn dose as calculated in sectim 1.4 with the adult as the bases for pm~ting.
- 1. Obtain the latest result of the mnthly calculaticn of the adult total body dose and the adult's highest orgy dose. These doses can be obtained fmm the in~lant zecordso
- 2. Mvide each dose by the ramber of days the actor plant was cpezaticnal Wring the month.
I
- 3. Multiply the quotient of each dose by the number of days the zeactor plant is pm)ected to be operational during the next tenth. 'Ihe pzoducts are the pm)ected dose for the raxt rrrnth. These values should be ad~ted as needed to account for any changes in failed fuel or other identifiable operating anditicns that could significantly alter the actual releases.
- 4. If the pm)ected dose is greater than 0.06 mzem to the total body or greater than 0.2 mzem to the adults higmst exposed orgm, the liquid radiate system slall be used to reduce the zadioactivity levels prior to release. /
Page 17 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200~ REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.1 Gaseous EfQuent Mod 1 Asamptims chazacteristics. The description that foUows is a brief ammzy for dose calculation purposes cnly). Ihe St. Lucie Plant is located an an island surxouxhd on two sides by the Atlantic Ocean snd the Indian River, an estuary of the Atlantic Ocean. Private property adjoins the plant site in the mrth and smth dixectians. A neteoraiogical teer is located north of the plant near the site payerty line. Thexe aze 16 sectars, for dose calculatim purposes, divided into 22.5 each. The set tower is calilxated such that a zero deyee bearing coincides with 'IRUE KRIH. A bearing of zero degzees dissects the orth sector such that bearings of 348.75 and 11.25 define the boundaries of the north sector. 'Ihe neaxest distance to prLvate property occurs in the north sector at sppxoxinately 0.97 miles. For ease of calculatim, this 0.97 mile zadius is asamad in all dixectims, al~ th xeal Unzestricted Azea Baundazy is defhad in Figuze 5.1-1 of the SIS. Doses calculated over water areas do not apply to the SIS IlD's or Ua anal report snd any be listed as O.W. (over water) in lieu of perforndng calculatims. The 0.97 mi1e znn8. in the NW sector is O.W., but it was chosen as the worst sector for conservative dose calculatims using the historical MET data. Historical MEI'ata - MET data, between Septerber 1, 1976 snd August 31, 1978, fzam the St. Lucie MEI'er was aralyzed by Dan's 6 thore of Washingtm, D.C. Ihe methodologr used by Ihnas 6 Mome wM cmsistent with aethods mggested by ~taxy Guide 1.111, Revtsim 1. Recirculation corzectim factors were also calculated for the St. Tucie Site md are incorporated into the historical MET tables (Tables M5, M6, and M7) in Appendix A of thiq nanual. It was detezndned that these two years axe representative data for this 1~cele. Ihse Calculaticns - Dose calculatims for Technical Specification dose limits are nozmally calculated using historical MEL'ata md zeaeptor locatim(s) which yield calculated uses no lover than the zeal locatim(s) experien.ing the nest exposuze. Actual MET data factors axe calculated snd used in dose calculatims for the Semi-annlal reports e Live IKEY data md hour-by-hour dose calculatims are beymd the scope of this annual. Historical informatim and conservative zeaeptor locations, etc., axe mly used for ease of SIS DD dose limit calculatims. Dose calculatims for SZS dose limits nay be performed using actual MEC data, zeal zeaeptor locations, and sector wind fnequency if distributim desized. Any dose calculaticns perform d with actual 4aa should note the sauna of the data in the auml zeport. Actual MET data zeductian should be perforned in accordance with RegQatazy Guide 1.111, Revisim 1 and shald incorpozate Becizculatim Corzectim Factors fxam Table &4 of this manual. 'Ibe St. Lucie site
;uses the long term ground xelease nodel for all gaseous efQuents. Only those zadimuclides that appear'in the gaseous efQuent dose factor tables will be cmsidezed in any dose calculaticns. Radioiodines are defined as Iodine-131 and I-133 for applicatim to S.T.S. M)'s. Other nuclides of Iodine say be included in dose calculatims for ease of performtng calculatims, but their dose cmtributian does not have to be includ.d in the SIS lG) zequirenants. Land Census infozmatim will apply to the calendar year fo13awing the year that the census was taken in to avoid splitting quarters, etc.
Page 18 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.2 Determining the Total Body and Skin Dose Rates for Noble Gas Releases And Establis Set ints for EfQuent Mcnitors IKscussim - ~cal Specification 3.11.2.1 limits the dose rate fmm noble gases in airboxza releases to <500 mxem/yr total body'nd (3NO aaaii/yr ddn. Technical Specificathn 3.3.3.10 zequixes that the Nsaes zadioactive effluent m(mitoring instxunantati.m be cpexable with alarm/trip setpoints set to enmize that these dose rate limits axe mt exceeded. 'Ihe results of the sanpling and analysis pmgnnn of
'Ih9nical Specificaticn Table 4.11-2 are used to denxmstrate ceaplisnce with these limits.
-The following aQculaticn nathod is pmvided for deteriabdng the dose zates to the total body snd skin fmm noble gases in airlerra releases. The alarm/trip setpoints axe based on the dose rate calculaticns. 'Ihe Technical Specificsticn IlD's apply to all airlaxN. zeleases on the site but all releases nay be txeated as if disclisrled fmm a single zelease point. Only those mble gases appearing in Table G-2 will be c(xisidexed. 'Ihe calculatt,cn methods are based m Secti(ms 5.1 and 5.2 of MJRHW133, November 1978. The equatims axe:
For TOIAL BOIZ Eose Rate: Ki (X/Qi Q(hstii For TOZAL KIN Dose Rate: DR~ ~ [Li + 1.1 Mi] (X'/Q) (Q DZ)i
, Where:
total body dose rate fmm able gases in airborne releases (mxem/yr) skin dose rate fmm noble gases in airborra releases (mxem/yr)
~ a nathenatical synhol to signify the opexaticns to the ri@t of the symbol are to be perfoxnad for each noble gas nuclide (i) thmugh (n), and the individual nuclide doses are sumad to arrive at the total dose rate for 8a release source.
Li (~
~ the total body dose factor due to Nma enkssiqs for each noble gm nuclide sported in the release source. /uCi~)
the skin dose fsctoc due to beta codes(ms fcc each nobis Ns use&de (i) xeported in the assay of tla zelease source. (mxenrm /uCi~)
~ the sir dose factor due to gmma emissicns for each. noble gis nuclide (i) zeported in the assay of the zelease source. The c(zispt 1.1 c(ziverts mxad to nrem since the units of Mi are in (mrad-m /uCi~)
(X/Q) for gmund level; the highest calculated annual lcng tenn historic zelative concentrate for any of the 16 sectors, at or beycnd the exctusicn area baundazy (sec/m ) (gXZ)i The release rate of noble gas nuclide (i) in uCi/sec fmm the release source of interest
Page 19 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO.'-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.2 (continued)
- 1. Sirrplified Total Body Dose Rate Calcuiatizn Fran an evaluatirxr of past zeleases, sn effective total body dose factor (~f) be derived. Ihis dose factor is in effect a wei@ted avezage total body dose factor, i.e., wei@ted by'he zadicauclide distzibution typical of past opezaticn. (PMer to Appendix C for a detailed explsnaticn and evatustizn of Keff) . Ihe value of Qqf hss i+en derived fmm the zadicactive noble gas ef fluents for the years 1978, 1979, snd 1980. The value is:
6.8 X 10 nza~P
%1~
This value nay be used in con~ticn with the total noble ye release rate (Q DOI')i to verify that the dose rate is within the alleaMe limits. To elle+ for any un xpected varfabiIity in the zadicnuclide distributim, a anservatism factor of 0.8 is intmduoed into the calculaticn. 'Ihe sinplified equaticn is: k (Q rar)i I3 -g~(X/Q) Zi 0.8 To further sinpglfy the determinatiar, the historical snrrual average neteorological X/Q of 1.6 X 10 sec/m (Fmm Table M-I) nay be substituted into the equaticn. Also, the dose limit of 500 rnzem/yr nay be subrrtituted for ~. Rldng these substitutirxrs yields a single cunulative (or gmss) noble gas zelease rate limit.
'Ihis value is:
Noble ~ zelease zate lind,t ~ 3.5 X 10 uCi/sec As larg as the noble gas zelease rates do not exceed this value (3.5 X 10 uCi/sec), no additiaral dose zate calculaticns aze rz.eded to verify corrplisnce with Technical Specificatica 3.11.2.1.
- 2. Setpoint Detezmtnaticn To mnply with Tech. Spec. 3.3.3.10, the alarm/trip setpoints aze estaglished to ensure that the noble gas releases do not exceed the value of 3.5 X 10 uCi/sec, which corrn@mds to a total body dose rate of 500 rnzem/yr. 'Ihe nathod that foll+a is a step~tep pmaedure for establishing the setpoints. To allow for nultiple smzces of zeleases fmm different or mnrrzn zelease points,'he allowaMe.
cperating setpoints will be coutmlied administratively by allocating a percentage of the total allowable release to each of the zelease sauzces. A. DeteznrIne (V) the naxirrum volune release rate potential fmm the in-plant pmceduzes for the zelease smzce under mnsidezathn. The units of (V) are ft3/mIn.
Page 20 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.2 (continued)
- 1. (continued)
B. Solve for A, the activity cmcenkzatim in uCi/cc that would produce the Y dose rate QD A 3.3X10 ucfX min X ft X 60eec sec V ft 2.8317 X cc min A uCi/cc C. Refer to the uCi/cc vs. cpm cunt for the Release Source's Gaseous Effluent Monitor cpm value (C), correspmding to the vatue of A above. D. C is the 1NP. setpoint, ssantdng that there are m other n lease sources m the site. E. Obtain the curn.nt X aUocated to this re1ease source from the gaseous waste management Iogse F. 'Ihe Operating setpoint SP SP (C) cpm X y a13ot ted in-plant praadures 100/'Ihe total body dose is more limiting than the calculated skin dose. (Refer to Appendix: C for a detailed evalustim.) %ezefore, the skin dose rate calculatims an. not required if the sinplified dose rate mlculatim is used (i.e., use of Keff to deterndne u.lease ate lintits).
'Ihe calculation process of the fol1owing Sectim (2.2.3) is to be used if actual releases of noble gee exceed the above lind.t of 3.5 X 10 uCi/sec.
Under these cmditims, a nuclide~elide evatuatim is required to evaluate conplimce with the dose ate lintits of Technical Specificaticn 3.11.2.1.
- 3. Total Body snd Sdn Nuclide Specific Dose Rate Chlculatims following outline provides a ste~tep explsnatim of how.the total Rdy The due rate is calculated m a nuclide~elide basis to evaluate conpliance with Tech. Spec. 3.11.2.1. This nakhod is cnly used value of 3.5 X 10 uCi/sec.
if the actual relfmses ~ the A. Xue (X/0) value sec/m end ls the suet llmltin8 sector at um exclusion atra. ~8ee luule u-1 for value end sector.) cc/sec voluna mlease rate
Page 21 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.2 (continued)
- 3. (continued) for(Q DOI)i for nuclide (i) by obtaining the uCi/cc assay vaiue of the release source snd aultiplying it by the pmduct of 2.2.3.B above.
(0 DOI')i (nuclide fi]) (assay) uCi X (2.2.3.B vatue) cc CC sec (q Dar)i- ~/sec for nuclide (i) D. To evaluate the total body dose rate obtain the Ki value for nuclide (i) from Table G-2. E. Solve for DRTBi CFTBf Kl XIQ Q DOZ i nm~ X see X uCi llCi~ lll3 sBC IR i ~ mrem total body dose fmm nuclide (i) for yr the specified release smrce F. To evaluate the skin dose rate, obtain the Li and Mi vatues fmm Table G-2 for nuclide (i). G. Solve for IR<> i IR~ i mrem skin dose fmm nuclide (i) for the yr specified release source H. Repeat steps 2.2.3.D thmugh 2.2.3.G for each noble gas nuclide (i) tnported in the assay of the xelease scarce. I. 'Ihe Dose Rate to the Total Body from radioactive noble gas gsnna zadiation fmm the specified release smrce is:
Page 23 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.3 Determining the Radioiodine & Particulate Dose Rate to Any Or Fran Gaseous Releases Discussicn T)ech Spec. 3.11.2.1 limits the dose xate fmm 1-131, I-133, tritium and all xndicnuclides in particulate form with half lives )eight days to (1500 mrem/yr to any orgy, 'Ha foll(owing calculaticn nethod is provided for deterndning the dose rate fmm radioiodines (see 2.1) cnrd particulates and is based m Secticn 5.2.1 and 5.2.1.1 thmugh 5.2.1.3 in NURE&0133, Novenher 1978. The Infant is the ocntmlling age gmup in the inlalatim, gmund plane, md cm/goat miltc pathways, wMch are the cnly pathways oonsidexed for r81888eso 'Ihe long taxm (X/Q)D (depleted) and (D/Q) based on historical NET data prior to inplenenting Appendix I. Only those nuclides tlat appear cn their mspective table will be ccnsidexed. Ihe equaticns are: For Inhalaticn Path(ay (exolu H-3): n (Rz~~ g O(/())D (() ~)s For Ground Plane: n IRI&8DP g i ( /Q) (Q IXE) For Grass-Cow/Goat~<Zc:
~~(p P( Q (D/Q) (Q ~)g For Tritium Releases (Inhalaticn & Grass-Cbw/Goat~1k):
(n (X/Q)D (Q DZ)(( 3 q For Total Dose Rate fmm I & 8DP and H-3 To An Infant T: r ~Z '..~~1&8rX + RSa j "&onially should be PiT, but RiT values are the sana, thus use RiT tables in Appendix A.
Page 25 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.3 (continued)
'Ihe calculaticns of Sections 2.3.1, 2.3.2, 2.3.4, and 2.3.5 may be omitted. 'Ihe dose rate calculaticns as specified in these secticas are invaded for coapleteness snd are to be used only for'valuating unusual ciramstances whexe releases of particulate materials other tbsn radioiodines in airborn releases are abnorsally high.
calcu1ations of Sections 2.3.1, 2.3.2, 2.3.4, and 2.3.5 will typically be used to dernmstrate amplisnce with the dose rate limit of beech. Spec. 3.11.2.) for radioicxHnes and particulates when the mMsured releases of particulate nateriai (other than radioiodines and with balf lives >8 days) aze >10 times the neaten d releases of radioiodines.
- 1. 'Ihe Inbalaticn Dose Rate Method:
The H-3 dose is calculated as per 2.3.4 A. 'Ihe controlling locate is ssamnd to be an Infant located in the sector at the mile amge. 'Ihe (X/Q)D for this 1ocaticn is sec/m . This value is mnmon to all nuclides. (See Table M-2 for value, sector snd ranga.) B. Fnter the release ate in ft3 /mfn of th4 release source and convert to cc/sec. ft X 2.8317 X 10 cc X mfn cc/sec min R sec, C. Salve for (Q DOI')i for nuclide (i) by obtaining the uCi/cc assay value of the release source activity and rmltiplying it by the product of 2.3.1.B above. (Q IXE)i ~ (nuclide [i) assay) uCi . X (Value 2.3.1.B) cc CC sec uCL/sec for nuclide (i) D. Obtain the Ri vatue from Table G-5 for the orgm T. E. Solve for IRi DRiT ~ RiT (X/Q)D (0 IXE)i mze~
~IL Jt X
~ m X uCi sec mrem The Dose Rate to organ T from nuclide (i)
F.
'f Repeat steps 2.3.1.C through 2.3.1.E tbe release source.
for each nuclide (i) reported in the assay
Page 26 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NOe C 2003 REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.3 {continued)
- l. (continued)
G. The Dose Rate to the Infants orgm T fmm the Idalsthn Pathway is: IR~ti ~ IR1 + IR2 + +IR fcn. all uuclides except H-3. 'Ihis dose zate shall be ad~ to the other pathways as per 2.3a5 - Total Organ Ihse. NHE Steps 2.3.1.C thmugh 2.3.1.G med to be conpleted for each orgm T of the Infant.
- 2. Ihe Gmund Plmn Dose Rate Method:
Tritium dose via the A. 'Ihe ccatrolling locatim is assuned to be an Infant loc:~ in the eectc: at the tale tec0.. 'lhe (0/Q) Xct this locaticn is 1/m . This value is comnon to all uuciides. (See Tab1e M-2 for sector, range and value.) B. Enter the release rate in ft3 /mIn of the xelease source md ccavert to cc/sec. Xt X 2.8317 10 cc X atc cc/eec ft 00 eec. C. So1ve for (0 IXZ)i for uuclide (i) by obtair~ the uCi/cc assay value fmm the release source ac4vity md nultiplytng it by the pmduct of 2.3.2.B above. (Q IXG.')i = (nuclide fi) assay) uCi X (Va3ue 2.3.2.B) cc CC sec (Qior)i- uCi/sec for nuclide (i) D. Obtain the Pi value fmm Table G-3 E. Solve for IRi T {D/Q) (QDZ)i ~ mre~ - sec X 1 X uCi uCi~ m sec mrem Ihe Dose Rate to organ T fmm yr mclide (i)
Page 27 of 84 STe LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO; C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.3 (continued)
- 2. (mntinued)
F. Repeat steps 2.3.2.C through 2.3.2.E for each nuclide (i) reported in the assay of the release source. G. 'Ihe Dose Rate to the Infant's Total body fmm the Ground Plane Pathway is: s M2I ~I+%+ + for all nuclides. 'Ihis dose rate slall be added to the other pathways as per 2.3.5.
- 3. 'Ihe Gras~/Goat Mitk Dose Rate Method: /R7 MHK H-3 dose is calculated as er 2.3.4.
A. 'Ihe contmlling animl was established as a located in sector at mLtes. 'Ihe (D/Q) for this /R7 tocaticn is I/m . 'this value is comnn to all nuclides. (See Table M-3 for sector, range, and value.) B. Enter the anticipated release rate in ft /mtn of the n tease smzce and anvert to cc/sec. ft3 X 2.3317 X Iu'c X mlc cc/sec ft 60 sec. C. Solve for (Q DZ)i for nuclide (i) by obtaining the uCi/cc assay value of the release source activity and nultiplying it by the pmduct of 2.3.3.B above. s ((Q DZ)i (nuclide [i) as ) uCi X (value 2.3.3.B) cc (Q DOT)i uCi/sec for nuclide (i) /R7 D. Obtain the Ri value fmm Table ~(7) (whichever is the contmlling aninal, cow/goat, for infant). If the lind,ted analysis approach, is being used, limit the cahmlaticn to the infant thymid.
Page 28 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.3 (continued)
- 3. (continued)
'. Solve for ImiT lmiT ~ RiT (D/Q) (Q DZ)i ~ mre~ - sec X I X uCi UCi~ m sec mran/yr the Dose Rate to organ T fran nuclide (i)
F. Repeat steps 2.3.3.C through 2.3.3.E for each nuclide (i) reported in the assay'f the release source. Only the xadioiodfnes reed to be included if the Iimt,ted aralysfs approach 4 being used. G. 'Ihs Dose Rate to the Infest's orgm T fran Grass- ~ pathway fs: grass IRI + (3G,+ + W fcr all nmclides. Ilds dose ntte shell te added to the other pathways as per 2.3e S Total Organ Dose. MHE Steps 2.:1.3.C thmugh 2.3.3.G teed to be conpleted for each orgm of the Infant. Limit the calculation to the infant thymid if the limited analysis ap mach is bein used.
- 4. 'Ihe H-3 Dose Rate Method:
A. Ihe contmlling locaticns and their (X/Q)D values for each pathway are: Inhalaticn Infant at range in the sector. (X/G))- sec/m (See Table M-2 for amae, sector and P Gmund Plan'e Does xetf apply to H-3 Gras~/Goat~1k- 'ocated in the sector ef mlles wfth ec Infect at ale mmlcsfmt ates ht ths asctct drh(the('the m(lh. (F/G)D for the tim is (X/Q)D sec/m . (Fnws Tehle tpd at the tang end sect.or mrmspmd(ng to the locati(n of the Milk Aninal above.)
Page 29 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ C 2003 REV ISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.3 (continued)
- 4. (continued)
B. Enter the mticipsted release rate in ft /mfn of the u lease sauce md envert it to cc/sec. ft X 2.8317 X 10 cc X efn 80 eec cc/sec volume release rate C Solve for (Q WZ)H3 for Tritiumf by obtaining the uCi/cc assay value of the release source, and rmltiplying it by'he pmduct of 2.3.4.B above. (Q DtZ)H 3 ~ (H-3) uCi X (2.3.4.B vatue) cc CC sec (Q IXE)H 3 ~ uCi/sec activity release rate D. Obtain the Tritium dose factor (Ri) for Infant organ T fmm: PA'IH Inhalaticn Gras~ Goat Mi E. Solve for DH~ (Mataticn) using the (X/Q)D for inhatatiro fmm 2.3.4.A and R 3 (Inhalator~) fmm 2.3.4.D.
"31-3 <+0>0 <0~4-3 08
~ ezmm/yr from 8-3 organ T fnfent Zchtletim for F.
Grass- . RH 3 (Grass-
'tk ~) ~tk)
Solve for DH 3 (Grass-, fmm 2.3.4.A and using the (X/Q)D for fmm 2.3.4.D (X/Q)D <<m)~3 r r mran/yr fmm H-3 Infant G- ~ for crgm T
Page 30 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.3 (continued)
- 4. (continued)
G. Repeat steps 2.3.4.D thmugh 2.3.4.F for each Infant orgm T of interest. H. 'Ihe individrral organ dose rates fmm H-3 shall be added to the other organ pathway dose rates as per 2.3.5.
- 5. Determi the Total Dose Rate fmm Iodines 8DPartf.culates and H-3 fmm Release Saurce s A. 'Ihe following table describes all the pathways that aust be sunned to arrive at the total dose rate to an organ T:
FAN SIEP 0 REF. Inhalat1m (168DPP) 2.3.1.G I Gmund Pl. (I68DP) (T. Bo m ) 2.3.2.G [ Gr- ~lk (Ime) 2.3.3.G I Tnhalatim (H-3) 2.3.4.E ( G -Milk (H-3) 2.3.4.F (sum of above) B. Repeat the above sunnaticn far each Infant orgm T. C. 'Ihe DRT above shall be added,to all other release sources on the site that will be in pmgress at any instant. Refer to in-plant pmcedures and Logs to determine the Total DR to each organ. 2.4 Deternrf the Garira Air Dose for Radioactive thble Gas Release Source(s) Discuss' 'Ihch. Spec. 3.11.2.2 lind.ts the air dose due to noble gases in gaseous effluents for ganna radiation to <5 nnads for the quarter aud to <10 rmads in any calendar year. 'Ihe fol1owing calculaticn nethod is pmvided for deternrining the able gas gsnrra air dose snd is based on section 5.3.1 of MJRKGi)133, Rrvernber 1978. 'Ihe dose calculaticn is independent of any age group. Ihe equatian rray be used far SIS dose calculation, the dose calculation for the arnual zeport or for pm~ting dose, pmvided that the appropriate value of (X'/0) is used as outlined in the detailed explanation that follcvs. 'Ihe equation for ganrrn air dose is: Q ~r P 3.17 X 10 Q (X/0) 0<
Page 31 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200p REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.4 (continued) Mhere: DY~r ganna air dose in rxad fzom radioactive mble gees.
~ A nathenatical synlul to signify the opezations to the right side of the symbol are to be perfoznad for each nuclide (i) thzough (n), and sunned to arrive at the total dose, fzom all uuclides zepozted during the interval. No units apply.
3.17 X 10 nn the inverse of the number of seconds per year with units of year/sec. Mi the gums sir dose (actor for nvdioactive tnhla ~s nuclide (i) in units Od ssndwv (X/Q) the lang tenn atsuspheric )fspetsitn factor for dtvmnd level releases in units of sec/m . 1he value of (X/0) is the sana for all nuclides (i) 5n the dose calculaticn, but the value of (X/Q) does vary depending on the Limiting Sector the L.C.O. is based on, etc. Qi ~ the number of nd.cz~uries of nuclide(i) ~eased (or pzo)ected) during the dose calculatiai ~osuze period. (e.g., mnth, quarter, or year) From an evaluation of past releases, a single effective puma air dose factor (Meff) has been derived, which is representative of the zadicmclide abundances and corzesponding dose contributicas typical of past opezatim. (Refer to Appendix C far a detailed explanation and evatuaticn of Mzf). The value of Meff has been derived fzom the zadioactive ruble ~s effluents for the years 1978, 1979, and 1980. The value is Meff = 7.4 X 10 mzad/ t'ai m
'Ms value nay be used in con]uraticn with the total noble gas releases ( Q ) to sisplify the dose evatuatirn snd to verify that the cusulattvn gams air dose 4 within the limits of Specification 3.11.2.2. To allow for any urexpected variability in the zadionuclide distribution, a ccnservatism factor of 0.8 is introduced into the calcuiaticn. 'Ihe sinplified equatica is D~r ~ 3el7 X 10 0.8 Meff X/Q W Qi
Page 32 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.4 (conthmed) For puzposes of calculaticns, the appropriate m'.teozological dispersicn (X/Q)fzom Table M-1 should be used. Tech. Spec. 3.11.2.2 zequizes that the doses be evaluated ence per 31 days, (i.e., nmthly). The quarterly dose limit is 5 mradsf which If D, corzespcnds to a monthly allotnnnt of l.'7 mzads. Cde 1.7 wads is substituted for a cusulatlve able Otv mmthly mlease cbjecttva csu ba calculated. 'lhls value ds,OOO Ot/math, usble gases. As long as this value is ret exceeded in sny nznth, re additicnal calculatizns are needed to verify oonpliance with the quarterly noble gas zelease limits of Specificaticn 3.11.2.2. Also, the gMna air dose is aoze limiting than the beta air dose. Ihezefoze, the beta air dose does not Ihd to be calculated per Secticn 2.5 if the Meff dose factor is used to determine the sana air dose. Refer to Appendix C for a detaQed evatuaticn md explanatim
'Ihe calnQaticns of Secticn 2.5 nay be omitted when this limited analysis approach is used, but should be pezfozned if the zadicnuclide specific dose aInlysis is perforned. Also, the zadicauclide specific calculatizns will be perforned for inclusion in Semi-annual reports. '1he fol3owing steps pzovlde a detailed explanaticn of lxar the zadicnuclide specific dose is calculated. 'Ihis method is used to evaluate quarterly doses in accordance with Tech. Spec. 3.11.2.2 if the releases of noble @mes during sny mnth of the quarter exzeed 36,000 Ci. /R7
- 1. To determbm the applicable (X/Q) zefer to Table M-1 to obtain the mtue for the type of dose calculation being performed. (i.e., Quarterly L.C.O. or Dose Pzogcticn for exanples). This value of (X/Q) applies to each nuclide(i).
- 2. Determine (Mi) the ganaa air dose factor for uuclide (i) from Table G-2.
- 3. Obtain the ad.ches of uuclide (i) from the in-plant radioactive yseous waste naragenant logs for the sources under ccasideraticn during the time intenal.
- 4. Solve for'Di as follows:
/R7 Di ~ mrad the dose from nuclide (i)
- 5. Perform steps 2.4.2 throu@ 2.4.4 for each nuclide (i) zeported during the time interval in the scuzce.
- 6. 'Ihe total ganna air dose for the pathway is detezmfned by sunmtng the Di dose of each nuclide (i) to obtain DY~r dose.
~ D1 + D2 + + D~ mzad
F, V
Page 33 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.4 (continued)
- 6. (continued)
NHE Conpiiance with a 1/31 day QD, Quarterly LCD, yearly or 12 ccasecutive mnths UD can be demaastrated by the limited aaQysis appmach using M ~~. Using this nathod only requires that steps 2.4.2 thmugh 2A.5 be perforned cne tina, reaaaberlng that th dose mst be divided 0.8 the conservatism factor. 7., Refer to in~lant pmceduzes for cnnparing the calculated dose to any applicable limits that mt8ht apply. 2.5 Determi the Beta Air Kame for Radioactive Noble Gss Releases Discussirn - Tech. Spec. 3.11.2.2 Hats the quarterly sir dose due to beta radiatim fmm noble gases in gaseous efftuents to <10 rmads in any calendar quarter snd <20 mrads in any calendar year. The fol3owing calcu1aticn aathod is pmvided for determining the beta air dose snd is based m Secticas 5.3.1 of %~133, tbvenber 1978. %e dose calculaticn is independent of any sge gmup. %e equation nay be used for SIS dose calculation, dose calculation for anal reports, or for pm~ting dose, pmvided that the appmpriate value of (X/Q) is used as outlined in the detailed explanation that follows.
Page 34 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NOe C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.5 (ccntinued)
'ihe equation for beta air dose is:
3.17 X 10 Ni(X/Q) Qi Where: beta air dose in nrad fmm zadioactive ruble gees.
~ a nathematical synhol to signify the opezations to the right side of the symbol aze to be pexfornad for each nuclide (i) thmugh (n), and sunned to arrive at the total dose, fran all uuclides zeported durtng the interval. No units apply.
3.1.7 X 10 ~ the inverse of the nomber of seconds per year with units of year/sec. Ni the beta sfr dose footer for fn units of mndne ntdfoeotfue table ~ nuodlde (f) uCL lr (X/Q) ~ the long term atnaspheric dispezsicn factor for gmund level releases in units of sec/m . 'Ihe value of (X/Q) is the same for all nuclides (i) in the dose catcutaticn, but the value of (X/Q) does vary depending on the Limiting Sector the QD is based cn, etc.
~ the number of mLcarChries of nuclide (i) zeleased (or pm~ted) durJng the dose catcutaticn ayosuze period 'Ilm beta air dose does not have to be evaluated if the noble gss ganna air dose is by the use of the effective puma air dose factor (Meff) ~ H(waver, if the'vatuated nuclide specific dose catculatim is used to evaluate conpliance with the quarterly gamm air dose limits (Secticn 2 4), the beta sir dose should also be evaluated as outlimd betow for the purpose of evaluating conpliance with the quarterly beta air Rse limits of Tech. Spec. 3.11.2.2. 'Ihe foltowing steps pmvide a detailed aylanatim of how the dose is calculated.
t
- 1. To detezndne the applicabte (X/Q) refer to Tabte M-1 to obtain the vatue for the type of dose calculation being perfoznud (i.e., quarterly UD or Dose pm)ection for exanptes). This value of (X/Q) applies to each nuclide (i).
- 2. Determine (Ni) the beta air dose factor for nuclide (i) fmm Table G-2.
- 3. Obtain the micro-cuzies of nuclide (i) fmm the in~lant radioactive gaseous waste nmagenunt logs for the source under ansidezatim during the time interval.
Page 35'f 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200,'REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) ,2.5 (continued) 4 Solve for Di as fol
'* (I) sec u(X~ m 1 Di ~ mrad ~ the dose from nuclide (i)
- 5. Perform steps 2.5.2 through 2.5.4 for each nuclide (i) reported during the time interval in the n 1ease scurce.
- 6. The each total nuclid beta air (i) to dose Dl +D2 obtai ~
for the
+D pathway.
dose-is
~ mrad determined by mining the Di dose of
- 7. Refer to in~lant pr(xedures for conparing the calculated dose to any applicable limits that night apply.
2.6 Determining the Radioiodine snd Particulate Dose To Fmm CumQative Releases Discussicn - ~cal Specificatim 3.11.2.3 limits the dose to the total h)dy or any orgy resulting fmm the n lease of I-131, I-133, tritium, md particulates with half-lives >8 days to <7.5 mrem during any calendar quarter and <15 mrem during any calendar year. 'Ihe following calculatim method is provided for determfning the critical organ (hse due to n 3eases of radioiodines and particulates and is based on Secticn 5.3.1 of MJREGO133, tbvember 1978. The equation can be used for any age gro~ provided that th.'appropriate dose factors are used and the total (hse zeQects only those that an applicable to the age group. Lhe (X/Q) symbol represents a DHKEIED-(X/Q) pa~ which is different from the Noble Gas (X/Q) in tIet (X'/Q) takes into account of 1&SIP and 11-3 from the ptum as the semt~inite clou(I tmve1s over a given
~ loss distance. The (D/Q) dispersim factor zepxesents the ate of fallout from tie cloud that affects a squan meter of gmund at various distances fmm the site. 1he I&SIP and H-3 notaticns refer to I-1313 I-133 Particulates ?avtng ha1f-lives >8 days, and Tritium. For ease of calculaticns, dose from other Iodine nuclides may be included (see 2.1). Tritium calnQaticns are always based on (X/Q) . The first step is to calculate the I&SEP and H-3 dose for each pathway that a'pp(ies to a given age gmup.
'Ihe total (hse to an crgm can then be determtned by sunndng the pathways that apply to th receptor in the sector. 'lb. equatims are:
For aa ~S Pat?~ (~~ H-3): ' 3.17 X 10 01 (X/Q)d)1 For Gmund P1ane or Grass-Cow/Goat 'tilk n 01M00 T Q 3.17 X X( (0/Q)Q(
'I d
Page 36 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NOs C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.6 (cxntinued) For each pathway above (excluding Ground Plane) For Tritium: 3.17 X 10 gg yf (X/Q)())f Fox'otal Dose from Particulate Gaseous efQuent to (xgym T of a specified age gxoups f Z68~+ QI-3l Z Whexe:
~ the organ of intexest of a specified age group
~ the applicable pathways for the age group of interest
~ Dose in t(rem to the orgm T of a specified age group from xadioiodines snd 8D Particulates
~ Dose in mern to the orgm T of a specified age group from Tritium Total Dose in rxem to the oem T of a specified age group from Gaseous particulate Efftuents
~ A rmthenatical symbol to signify the opexatims to the right of the symbol axe to be perfornad for each nuclide (i) thxough (n),
and the individual nuclide doses axe sumed to arrive at the total dose fxom the pathway of interest to organ T.
~ A aathenatical synknl to indicate that the total Rse Di to organ T is the sum of each of the pathway doses of I68IP snd H-3 fxom gaseous particulate ef Qnents.
3s17 X 10 ~ The invexse of th number of secands per year with units of year/sec.
~ The dose factor for mclide (i) (or H-3) for pathway Z to mgm T,of the specified age group. The units axe either aauarn for pathways strawn - sao for pathways yr-uci using (X/0)0 (R yrani using (0I0) /R7 (X/a)D ~ The depleted-(X/Q) vatue for a specific locaticn where the xeceptor is located (see discussicn). The units are sec/m (D/Q) ~ the depositicn value for a specific locaticn where th xecsptor is located (see discussicn). The units axe I/m whexe +meters.
Page 37 of 84 ST, LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.6 (continued) Oi ~ 'Ihe zamber of micro-Chris of nuclide (i) released (or pmpcted) during the dose ca1culaticn exposure period.
~ the mmber of microChzies of H-3 zeIaased (or pm~ted) during the dose calculaticn exposure period.
As discussed in Section 2.3, the gras~/goat~ pathway has been identified as the est limiting pathway with the infant's thymid being the critical organ. 'Ihis pathway typically attributes >90K of the total dense zaceived by the inst's thymid and the radioiodine ccatzibutes essentially all of this dose. Therefore, it is possible to dennstzate cosplimce with the dose led.t of Tech. Spec. 3.11.2.3 for zadioiodines and particulates by cnly evatuating the infant's thymid dose due to the zalease of zadioiodines via the gras~/goat~1k pathway. The calculation nathod of Secticn 2.6.3 is used for this deterndnsticn.
'ihe dose determIned by Sectim 2.6.3 should be divided by a conservatism factor of 0.8. 'Ihis addod cmservatism pmvides assurance that the dose deteanfned by this limited analysis approach will be < the dose that would be deterndned by evaluating all zadicnuclides and all pathways. If this limited anslysis appmach is used, the dose calculaticns for other radioactive particulate natter and other pathways need not be perfornad. Only the calculaticns of Sectim 2.6.3 for the zadioiodiras aze required to denrnstzate cosplisnce with the Tech. Spec. dose limit. Heaver, for the dose assessttant included in Semt~l Reports, doses will be evaluated for the infant age groups and all orszns via all ~ignated pathways fmm radioiodines and particulates measured in the gaseous efftuents according to the sanpling md azalyses required in Tech. Spec. TaMe 4.11-2. 'Ihe fo13owing steps pmvide a detailed expIazaticn of how the dose is calculated for the given pathways:
- 1. The Tnha1atim Dose Pa Method z tVK The H-3 dose sold be calnQated as per 2.6 4.
A. Determine the applicable (X/Q)D fmm Table M-2 for the locatim where the zeceptor is located. 'Ms vatue is mmtrn to each nuclide (i) /R7 B. Deterndza the Ri factor of nuclide (i) for the organ T snd age grey fmm Table G-5. r C. Obtain the ad.ches (Q ) of nuclide (i) fmm the radioactive gss waste mszagement logs for the release source(s) under cmsideratim during'the time interval. D. Solve for Di Di ~ 3.17 X 10 Ri(X/Q)gi jk7 Di ~ mrem fmm nucIide (i) E. Perform steps 2.6.1.B thmugh 2.6.1.D for each nuclide (i) reported Wring the tijta interval for each organ.
I Page 38 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.6 (continued)
- l. (continued)
The Tnhalaticn dose to a:gm T of the specified age group is deterndned by sunndng the Di Dose of each nuclide (i) TnM1aticn ~ DL + D2 + + Dn mrem age Cm~) Refer to 2.6.$ to determine the total Rse to mmmm T fmm radioiocunes 6 8D
- 2. The ~articulates PLane Ibse Pathway Method:
MEE Tritium dose via tlat gmund plane is zero. 'Ihe total Body is the cnly or considered for the Gmund Plant dose. A. Deterndne the applicable (D/Q) fmm Table N-2 for the iocaticn where the receptor is located. 'LMs (D/Q) value is conn'o each nuclide (i) B. Detentdne the Ri factor of nuclide (i) for the total body fmm 'ihble &4. Ihe ground plane pathway &se is the sana for all age grcups. C. Obtain the nd.cnrChries (Qi) of nuclide (i) from the radioactive gas waste nnnagenant Logs for the source under ansidexatim. De Sol~ for Di Dg 3.17 X 10+ (D/Q)Qg Di es mrem for nuclide (i) Eo Perform steps 2.6.2.B thmugh 2.6.2.D for each nuclide (i) reported Wring the tine interval. F. 'Ihe Gmund Plane dose to the total lady is deterndned by sunrnfng the Di Dose of each nuclide (i)
%r Pl.-mug- L+D2+ + n Refer to step 2.'6.5 to calculate total dose to the Total Body.
- 3. %e Gras~/Goat~ Dose Pa Method:.
NZE Tritium dose is calculated as per 2.6.4 A. A cow, or a ~t, will be the amtmlling aninal; (i.e., dose will not be the sum of each aninal), as the 1m'eceptor is assuned to drink ndlk fmm cnly the nost restrictive aninal. Refer to Table M-3 to deterndne which aninal is cmtmlling based on its (D/Q) ~
kl Page 39 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200~ REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODOM) 2.6 (continued)
- 3. (continued)
B. Determine the dose factor Ri for t~clide (i)~ for organ T> fzom
- 1. Fzom able 6-6 for a ew, or;
- 2. Fran Table G-7 for a goat.
If the limited anQysis approach is being used, limit the calculation to the infant thyzoid. Obtain the <ches (Q) of nuclide (i) fzom the mdioactive ge waste msnagenant logs for the misease source under ccnsidezaticn during the time interval. D. Solve for Di Dg 3.17 X 10+(D/Q)Qg E. Perform steps 2.6.3.B thzough 2.6.3.D for each nuclide (i) zeported during the tine interval. Only the zadioiodines med to be included if the limited amlysis approach is used. F. 'Ihe Gzas~~ilk (or Gms~t~lk) pathway Rse to cegsn T is deterndned by sumrdng the Di dose of each nuclide(i). D~~ (or I
~) ~ Dl + D2+ +D~ mzem The dose to each organ should be calculated in the sana mener with steps 2.6.3.B thzough 2.6.3.F. Refer to step 2.6.5 to detezndne the total dose to organ T from zadioiodines 68D Particulates. If the limited sxalysis spprcach is being used the infant thymid dose via the grass-cow(goat)-milk pathway is the cnly dose that reeds to'be deterndned. Section 2.6.5 can be omitted.
- 4. %la Gaseous Tritium Dose (Each Pa ) Method:
A. 'Ihe ccntzolling locaticas for the pathey(s) has alzeady h.en determined by: Tnhalaticn - as per 2.6.1.A d Plan - not applicable for 1&3 Gzas~/Goat~ - as per 2.6.3.A B. Tritium dose calculaticns'use the depleted (X/Q)D instead of (D/Q). 'Jhble M-2 describes where the (X/Q)D value should be obtained from. C. Determine the Pathway Tritium dose factor (RH 3) for the organ T of interest fzom the Table specified below: Infant G"5
Page 40 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.6 (continued)
- 4. (continued)
D. Obtain the micr~ries (g) of Tritium fmm the mdioactive ge waste management logs (for pmjected doses - the nd.cnHhries of nuclide(i) to be pm~ted) far the n lease source(s) under cxlsideraticn during the ting interval. lhe dose can be calculated fmm a single release source, but the total dbse for S.T.S. limits or quarterly mparts shall'be fmm all gsseous mlease sources.
. E. Solve for QI 3 3.17 X 10 RH 3(X/Q)g mrem fmm Tritium in the pacified pathway for argm T of the specified age grcup
- 5. Determf the Total Organ Dose Fmm Iodines, SD-Particulates, and H-3 Fmm Qmulative Gaseous Releases NOIE SIS UD dose lind,ts for IQKP ~11 consider dose fmm all release sources fmm St. Lucie Unit 1.
A. Ihe fallowing pathways shall be sunned to arrive at the total dose to agan T fmm a release source, or if applicable to SIS, fran all release sources: PA'HMAY Inhalat ian (168DP) 2.6.I.F I l Ciild Plane (168DP) (T Q11y) 2'6 2 F I Gpss- ~Zc (IQKP) 2.6.3.F Tnhalaticn (H-3) 2.6.4.E 2.6.4.E Sum of Above B. The dose to each of the INENZ'S ORANS slall be calculated: KNE, LIVE, KYROID, KEHEY, IIJN, 'IOIAL MZ, 6 GI~I '
'Ihe INFANI'rgn n ceivtng the highest exposun n.lative to its. SIS Lind.t is the na'st critical organ for tlat radioiodine 6 8D Particulates gaseous ef fluents.
2.7 Pm ct ~ Fuse for Radioactive Gaseous EfQuents Discussion - Tech. Spec. 3.11.2.4 requires that the gaseous mhmte tzeatnant system be used to reduce mdimctive materfals in waste prior to discharge when the pm]ected Nse due to gaseous efftuents would exceed 0.2 mrad for gsnua radiati<m and 0.4 mrad for beta radiatim. The following calculatim method is pmvided for determining th. pmPcted doses. 'Ms nethod is based on using the results of the calculaticns perfornad in Secticns 2.4 snd 2.5.
Page 41 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO+ C 200'EVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.7 (cantirumd)
- 1. Obtain the latest results of the nznthly aQculsticns of the gnnrra air dose (Section 2.4) and the beta air dose if pezfoznad (Sectirnr 2.5). 1hese doses can be obtained fmm the in~lant zecords.
- 2. Divide these doses by the number of days the plant was apezatiaal during the month.
- 3. Multiply the quotient by the nmber of days the plant is pmjected to be cperatioral durtug tla next morrth. The pmduct is the pmjected dose for th next
~ rxnth. %e value shMld be adjusted as needed to acmunt for any changes in failed-fuel or other identif&ble operating canditLrxrs that could significarrtly alter the actual zeleases.
- 4. If the pmjected @sea are X.2 mzads gamrrn air dose or 0.4 mrads beta air dose, tlat appropriate subsystems of the gaseous zadwaste system sMl be used to zeduce the radioactivity levels prior to a.lease.
3.0 40 CFR 190 Dose Evaluatim Mscussicn - Dose oz dose canrnitnent to a real individual fmm all unrnium fuel cycle sources be limited to (25 mzem to the total body or any organ (except thymid, which is limited to C75 mzem) over a period of 12 consecutive ncnths. The fol3ovhg approach shxrld be used to demanstrate conpliance with these dose limits. This appmach is based cn %REG-0133, Secthn 3.8. 3.1 Evatuaticn Bases Case evatuaticns to denznstzate conpliance with the above dose limits need only be pezfoznad if the quarterly doses calculated in Sectirxrs 1.4, 2.4 snd 2.6 exceed twice th dose limits of Tech. Specs. 3.11.1.2.a, 3.11.2.2a, and 3.11.2.3a, respectively; i.e., quarterly doses exceeding 3 mzem to the total body (liquid releases), 10 mzem to any orgm (liquid releases), 10 rnzads puma air dose, 20 mzads beta air dose, or 15 mzem to tlat thymid or any organ fmm zadioiodines and particulates (atnn~heric releases). Otherwise, no evaluaticns are rnquized and the zenninder of this sectian can be omitted. 3.2 Doses Fmm Liquid Releases For the evatuatian of doses to zeal individuals fran liquid releases, the sane calculaticn method as enplayed in Section 1.4 wQ1 be used. However, urn realistic assunptirxrs wQ1 be nade concerning the ditutian and ingestion of fish and.sheUfish by individuals who live and fish in the azea. Also', the results of the Radiological Bwizcnnantal Monitoring pmgzam wQ1 be included in determining naze realistic dose to these real people by pmviding data cn actual measured 1emls of plant related zadicnuclides in the envirennent.
Page 42 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 3.3 Doses Fmm Atnasphezic Releases For the evalustfcn of doses to mal individuals fmm the Nnaspherfc releases, Ca sana calculaticn methods as enployed in Sectfcn 2.4 and 2.6 will be used. In Sectfcn 2.4, the total lady dose factor (K ) should be substituted for the Snit air dose factor (Mf) to detexmfne the total body dose. Othezwise the sana calculatiau sequence applies. Howear, naze zealfstic asampticns will be nude ccacezning the actual locatim of zeal individuals, the meteomlogfcal ccnditicas, and the ccnserptfcn of food (e.g., milk). Ihta obtained fmm the latest land use census (Tech. Spec. 3.12.2). should be used to determtra locatfcns for evaluating doses. Also, the results of the Radfalogfcal Euvfrcnnantal Mcnftaring pmgxam will be included in detextdydng mze realistic doses to these real people by pmvfding data cn actual mmaxed levels of xedfoactfvfty snd radfaticn at locaticns of interest. 4.0 SentfMueal Radicective EfQuent ort Discuss' 'Ihe infarnaticn contained in a sanf~umal repart shall not apply to any SIS M3. 'Ihe reported values are based cn actual release ccndfticns instead of hfstorfcal ccnditicns that the SIS UD dose calnQaticns are based on. Ihe SIS QD dose lind.ts are thexefoze included in iten 1 of the zeport, for fnformatfcn cnly. The MPC's in item 2 of the zeport shall be those listed in Tables L-1 and tr 1 of this nanual. 'Ihe average aargy in item 3 of the report is not applicable to the St. Iucie Plant. 'Ihe format, order of nuclides, aud any values shown as an eanple in Tables 3.3 thmugh 3.8 are sanples cnly. Other formats are acceptable if they cmtain equivalent infozmaticn. A table af contents should also acmnpsny the report. The fallawfng faznat should be used: RADIOACT1VE JMIIJENIS - SlPPLEMM'AL INIQMTZN ~
- 1. Regulatory Lfmfts:
1.1 For Radicective liquid waste efftuents:
- a. 'Ihe ccncentxatfcn of xadicactive materfal released fmm the site (see Figuze 5.1-1 in STRA) s?all be limited to the ancentzatfcns ~ecified in 10CFR20, Appendix B, Table II, Colunn 2 for zadicnuclides other than dissalved or entzained noble Nses. For dissolved og entzafned noble gases, the concentration shall be limited to 2 X 10 uCf/ml total activity.
- b. Ihe dose or whse cotunftnant to a MEM8ER OF KE HJBLIC fmm radioactive naterfals fn liquid efftuents zeleesed fmm each reactor unit to unzestrfcted areas (See Fig. 5.1-1 in SI&A) shall be limited during any calendar quarter to <1.5 mzem to the total body and to <5 mzem to any organ and <3 mzem to the total body and <10 mzem to any orym during any calendar year.
1.2 For Radioactive Gaseous Waste EEQuents: l
- a. The dose rate in unzestrfcted areas (see Fig. 5.1-1 in the SIS-A) due to radioactive naterfals zelessed in gasecus efftuents fmm the site shall be limited to the following mtues:
'Ihe dose rate lfmft for noble gases shall be <500 mzem/yr to the total body snd <%00 mzem/yr to the sldn, and
'Ihe dose rate limit fmm I-131, I-133, Tritium, and particulates with half-lives >8 days slall be <1500 mzem/yr to any orgm.
I 1
Page 43 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) 4.0 (cmtinued) (continued) 1. 1.1 (continued)
- b. The air dose (see Figure 5.1-1 in the SIVA) due to noble gmes zeleased in gaseous efftuents,fmm each zeactor unit, to azeas at snd beycnd the SZIK BOUNOhRY s2all be limited to the folIowing:
DurIng any calendar quarter, to <5 mzad for gssna zadiation md <10 mzad far beta zadiaticn and Wring any calendar year to <10 mzad for yuwa zadiaticn and <20 mzad for beta zadiatim
- c. 'Ihe dose to a MBSIR OF THE FUBLIC fmm I-131, I-133f Tritiumf and all zadicnuclide in particulate fozm, with hQf-lives >8 days in gaseous ef Quents zeleased fzom each zeactor urd,t to areas at md beycnd the SZK IOJNMRY (see Figuze 5.1-1 in the SIVA) shall be limited to the fallowing During any ca1endar quarter to <7.5 mzem to any organ, snd during any calendar year to <15 mzem to any organ.
- 2. Micbami Permissible Concentratims: .
Air as per attached Table G-1 Pater>> as per attached Table Ir1
- 3. Average en rgy of fissicn and activaticn gees in gaseous effluents is not applicable to the St. Lucie Plant.
- 4. Measuzem nts and Appmxfsaticns of Total Radioactivity:
A sunnazy of liquid effluent accounting methods is desczibed in 'Ihble 3.1. A sugary of gaseous effluent acmunting methods is described in Table 3.2. Estimate of Errors: a+ Sanpling Ermr
'Ihe ermr associated with mluna neasuzesant devices, flow measuring devices, etc. based on calibration data and design tolezances hss been ciervativi ly estinated collectively to be less than + X
- b. Analytical Error for Nuclides TYPE AVEIIAGE X NlGNN 7o Liquid Gaseous
Page 44 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE,DOSE CALCULATION"MANUAL(ODCM) 4.0 (continued)
- 4. (continued)
ISLE 3.1 Radioactive Liquid E25ent Saapling md Amlysis MEIHOD OF TYPE OF ANALYSIS ANALYSIS MME PRINCIPAL GATOR BKITKRS pshaw TAME L.Se RELEASESl SIEAM QUARTH<LY GNPCGZIE S~9 ~ Fe-55 G.F.P. C+S. & L.S. GEHERAIDR (EELY .h.a. El%EM 'IRITIIM L.S. REZZASES KKKNOI'ATION MMHLYCNKGXIE QUEERLY KNPOSZIE S~9 GAS
~, ALPHA F~5 GoF.Pa CoSo & LoS Eoric Acid Evaporator condensate is normally recovered to the Prinary Water Storage Tank for recycling into tla reactor coolant system and nornally does not contribute to liquid waste efftuent totals.
p.h.a. gama spectrum pulse height aalysis using Lithium Gertandum detectors. All peaks are identified and quantified. LoS. Liquid ScfntilIaticn counting C.S. (hettd.cal Separate GoF.Pa Gas Flow Prcporticnal Counting TAKE 3.2 Radicactive Gaseous Waste Sanpling and AnQysis
'IYPE OF ANALYSIS Waste Gas Decay Principal Ganxra Bnit ters G, p.h.a.
Tank Releases Principal Gama Bnit ters G, .h.a L S. Principal lamna Bait ters G,C,P ~. .a0 L S. Plant Mcnthly Gorposite P'- GoF+Po Vent (Particulates) Quarterly Cottposite C.Se & (Particulates) L.S. G (gaseous Gm Sanple C Charcoal Filter Sanple P - Particulate Filter Sanple L.S. - Liquid Scfntillaticn Counting C.S. (hend.cal Separaticn p.h.a. Gamna spectrum pulse hei8ht aalysis using Lithium Gernanium detectors. All peaks are identified and quantified. G.F.P. Gas Flow Prcporticnal Counting
Page 64 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) TABLE M-1 Selectin the riate Lcn Term (X/Q) for 13ose Calculaticns Invol Noble lhses for: (1) Total Body dose from instantaneous zelesses (2) Sdn dose from instantaneous zeleases (3) Ganaa air dose (amulative) (4) Beta air dose (cumulative) TYPE OF IX5E QKCUIAT3Ã KQGE (miles) Instantsneou~ 0.97 1.6 X 10~ 1 31 days - DD 0.97 Quarterly IlD 0.97 1. Nornally (X/Q) ~ 1.6 X 10 sec/m Yearly 12 Gcnsecutive 0.97 2. Rry use option of actual mteorological months - UD data for time of ancezn 0.97 Note 1 'Ihe (X/Q) has to be calculated based on actual meteorological data that
'ccurred during the period of interest. The sector of intezest is N/A because the limiting (X/Q) will be detezmfned fzom the actual meteorological data and nay occur in any sector.
0.97 miles Corzesponds to the mfniaam site boundszy distance in the rnrth dizecticn and 0.97 mfles was chosen for all other sectors for ease of calculations when the averaging is dcne for quarterly zeports.
Page 65 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) Selecting the Apprcpriate Icng Term (X/Q)D or (D/Q) for Dose (hlculaticns Involving Radioiodines & 8 D Particulates for: (1) IahaIaticn (2) Tritium (All gas pathways) (3) Grcund Plane TYPE OF DOSE LPKT2G RhtGE LIMZITN~ SECIDR QLQlIATI(N (miles) (OL) (X/Q) sec/m (D/Q) 1/m ) 0.97 B 1.3 X 10 ////// Quarterly for 0.97
///////
A B 8.2X10 Semiannual orts 0.97 1 31 days M), Qtr. yearly M3, 12 consecutive 0.97 B 1.3 X 10 ////// month DD 0.97 /////// 8.2 X 10+ (OL) Over land areas cnly (A) To be determrned by teductico of actual set data occurring'during each quarter (B) For Tritium in the MiIk.Animl Pathway, the (X/Q)D value should be that of the respective controlling sector and ran0. where the MiIk Anginal is Iocated as per Table M-3. Exanple: If a ear was located at 4.25 mQes in % sector, use the (X/Q)D for 4.25 mr.les Nr.
Page 66 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) Selecting the Appropriate Long Term (D/Q) for Dose Calculations Involving Radioiodines and 8D Particulates for Grass-Ca~3k or Gxas~t~Ik: TEE OF DOSE LIMITING Q Vatue CAUXJIATICN SECIOR I/m2
) ~e"~ Rate rm
- uO A A I/31 B B l Qusrterl Yearl - QD B B I 12 Consecutive Months - UO B B Seminal Report C C A. Ihe worst aw or goat as per locaticas from land census. If no ndlk sniml in any sector, asama a cow at 4.25 miles in the higmst (D/Q) sector over land.
B. '1he historical (D/Q) of all land sectors with the worst cow or goat from each sector as reported in the Land Census. A 4.25 mile cow should be assunad in the worst sector when ru nd.lk animl is reported. C. The ~est (D/Q) at a mi]k aninal location of all miIk snisals reported in the Land Census Report. (If no mt,lk animls within 5 miles a 4.25 mile cow should be sssunad in the sector having the hi/mat (D/0) at 4.25 miles). Actual Met Data should be used for the selecticn of the worst case nd.lk antral and for the dose calculaticns. If both goat md milk snips axe reported inside 5 mlles, dose calculaticns should be perforttad on each aninal and the huger dose aninal contributicn should be used. 'Ihe historical wind frequency fzacticns for each sector ate listed in Table ~.
'age 68 of 84 ST. LUCI5- PLANT C(IEHISTRY OPERATING PROCEDURE NO. C-200, REVISION 7
=
OFFSITE DOSE CALCULATIOA HANUAL (ODCH) TABLE t$ -5 IKSIORICAf. IlXG 'IHIH (X/Q) (Frequency conected) Terrain / Recirculaticn Adjusted Program ANmQ9 Versicn 11/18/76 Florida Paar & Ligt Cbapany St. Lucie Unit 1 Itutchinsm Island, Florida Danes and Hocxe Job No: 1.4598 112 Average Annual Relative Cancentraticn (sec/cubic meter) Period of Record: 9/1/76 to 8/31/78 ESE DISI'ANZ IN HILES / KIIlNETES IKSIGN AFFECIH) DISI'AN(Z +25 .75 1.25 1.75 2 25 275 3.25 3.75 4.25 4.75 SECIOR HILES .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64
- 0. l. lE~ 1.7E-06 7.8E~ 4.5E~ 3.1M'.2E~ 1.7&07 1.5E~ 1.2&61 1.0MP
- 0. 1.3E~ 2. 1EE5- 8.9E~ 5.1EM 3.4E~ 2.4E~ 1.7E~ 1.4E~ 9'8E~ I
- 0. 9.3EM 1.4M6 6.2E~ 3.7&07 2.5E~ 1.9&07 1.3C~ 1.1&07 8.8MB 7.5E-IS (
- 0. 9.8EM 1.6EM 6.5E~ 3.7E~ 2.5E~ 1.8&67 1.4E~ 1.2&07 9.9E~ 8.4E-IS )
- 0. 1.2LWS 1.9EM 8.1E~ 4.8E~ 3.2E~ 2.4MI7 1.8&iP 1.4MP 1.1MP 9.0AM )
SE 0. 1.4~ 2.4E~ 9.7E~ 5.7'.0E~ 2.9E~ 2.3E~ 1.4E~ 1.2E-07 (
- 0. 1.1&05 1.7&06 7.3E~ 4.3&07 2.9&07 2. 1E-07 1.6BEP 1.3&07 1.1MP 9.1MB )
- 0. 6.2EM 1.0EM 4.2E~ 2.5E~ 1.8E~ 1.4~ 1.0E~ 8.0E~ 6.6E~ S.SE-IS )
- 0. 5.7E~ 9.0E~ " 4.0&07 2.3E~ 1.6MU'.1&07 8.9E~ 7.0& 5.7& 4.8H-IS (
- 0. 6.1EM 9.4E~ 3.9E~ 2.2EEP 1.6E~ 1.1E~ 8.6E~ 7.0E~ 6.0E~ S.XE-IS )
- 0. 7.3EM l.lEM 4.6E~ 2.7E~ 1.7E~ 1.3MP 1.0E~ 8.0&% 6.5&CB 5.4H-IS )
- 0. 7.6EM 5.2E~ 2.9E~ 2.0E~ 1.3E~ 1.0E~ 8.4E~ 7.2EES 6.1E-Ot /
- 0. 1.4E~ 9.1EM - 5.2E~ 3.4E~ 2.6E~ 2.0E~ 1.5E~ 1.2MF 1.0MP )
- 0. 1.6E~ 2.4EM 1.0EM 5.9E~ 3.9EM 2.8E~ 2.1E~ 1.7E~ 1.4EEV 1.2E-07 )
- 0. 1.5E~ 2.2EM 9.6E~ S.SE~ 3.6&07 2.6&07 2.0&07 1.6E~ 1.3&07
- 0. 9.1E~ 1.4EM 6.3E~ 3.6E~ 2.4E~ 1.8E~ 1.4E-07 1.2E~ 9.4E~ 7.9E- t ttenber of Valid Observaticns ~ 17135 Number of Calms Lower lail 95 t4rher of Invalid Observathns = 38S Nxrher of Calm Upper level = 0 Note 1 Any interpolations between stated mileages Mill be dna by 1og-log
'age 69 of 84 ST o LUCIj. PLANT CIIEMISTRY OPERATING PROCEDURE Now C-200, REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM)
TABLE &6 HISIORICAI. DMl MN DEPLEIED - (X/(})D (Frequency corrected) TIRRAIN / RECIRCUIATION ADISnu HKEfM ANNKCj9 VJMKN 11/18/76 Florida Power 6 Ligt Cbttpany St. Lucie Unit 1 Jtutchinsm Island, Florida Ihnes and thee Job No: 4598 112 AVHNKANMJAL RHATIVE GNCENIRATION DEPLEIED (sec/cubic meter) Period of Record: 9/1/76 to 8/31/78 RASE DISI'ANCF. IN MILES / KII&tETJRS DESIGN AFIVCIH) DISI'ARE ~ 25 ~75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 SEIR MILES .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 NNE 0. 1.6&Qi 6.6E~ 3.8E~ 2.4E-07 1.7E~ 1.3M'. 1E~ 9.2MB 7.6AM NE 0. 1.7&Qi 7.6E~ 4.3E~ 2.8EM 1.9E~ 1.4E~ l. IE~, 8.6E~ 7'4EES I BK Oo 8.9EM 1.2E~ 5.3E~ 3.0'.0E~ 1.4MB 1.0E~ 8.4MB 6.6MB 5.6E-IB ) E 0. 9.1E~ 1.3E~ 5.6E~ 3. 1E~ 2.1E~ 1.5E~ 1.1E~ 9.1E~ 7.5E~ 6.3E- ) ESE 0. 1.2E~ 1.6E-06 6.9E~ 3.9EM 2.6&07 1.9E~ 1.4&07 l. 1&07 8.5MB 6.7E- ) SE 0. 1.3M5 2.0M5 8.2E~ 4.7E~ 3.3E~ 2.3E~ 1.8E~ 1.3E~ 1.1E~ 9.0E~ ) SSE 0. 1.1E&5 1.6E~ 6.3E~ 3.5E~ 2.4E~ 1.8M'.4&07 1.0&07 8.2& 6.8E-{a ) S O. 5.9EM - 9.1E~ 3.6E~ 2.1E~ 1.4E~ l. IEM 7.7E~ 6.2E~ 5.0E~ 4.1E-e ) SSW 0. 5.4&06 8.0&07 3.4&07 1.9&07 1.3E~ 8.9AM 6.9&CB 5.5MB 4.3&CB 3.6~ ) Sl 0. 5.7EM '.4E~ 3.4E~ . 1.8E~ 1.2EM 9.2E~ 6.7E~ 5.3E~ 4.6E~ . 3.8E-(B )
) uSW O. 7.0E~ 9.6E~ 4.0E~ 2.2&01 1.4E~ 1.0&07 B.OMB 6. 1AM 5.0MB 4.0F tB ) )
M 0. l.lEM 4.4MP 2 4E~ 1.6E~ 1.1E~ 8.2E~ 6.4E~ . 5.5E~ 4.4E-IB ) 7.3'%.3Fr45
)
WW 0. 1.9&06 7.9E~ 4.4E-07 2.9E~ 2.0E~ 1.65-07 1 ~ 2&07 9.3&CB 7.8E- ) Nf 0. 1 5Fr45 2 IE~ 8 9E~ 4,9&07 3 1E~ 2 3E~ 1 7E~ lo3E~ 1 OE~ 8.5E-IB ) -) mJ o. 1.4E~ 2.1E~ 8.3E~ 4.5E-07 2.9&07 2.0&07 1.6MP 1.2E~ 1.0&07 8.6E-N ) N 0. 8.7E~ 1.3EM. 5.4E~ 3.0E~ 2.0E~ 1.4E~ 1.1E~ 5.8E-O~ ) Number of Valid Observaticns ~ 17135 Number of GQms Lower Level 95 Nunher of Invalid Observaticns 385 Nmher of Calms IJpper Level 0 Note Any interpolaticns bebeen stated mileages will be dcne 1 by log-log
"age 70 of 84 ST+ LUCI~ PLANT CUEMISTRY OPERATING PROCEDURE NO. C-200; REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM)
TAKE M-7 mSIICAL Ilm 'IIRM (D/g) (Frequency corrected) mumm / RZCIR~Vm AMUSE HEQM ANNK0$9 VBSION 11/18/76 Florida Paar & Light Corrpany St. Lucie Unit 1 ltutcMnscn Island, Florida . hmas and fbore Job No: 4598 112 AVEBNVi. ANWAL RHATNE DIHSITICN HA'IE (square meter 1) Period of Record: 9/I/76 to 8/31/78 ESE DISI'ANZ IN MILES / KIIDMETERS I%SIGN AFlVCIH) DISEANZ ~ 25 .75 1.25 1.75 2.25 2.75 3.25 3.75 4.25 4.75 SEClOR MILES .40 1.21 2.01 2.82 3.62 4.42 5.23 6.03 6.84 7.64 WE 0. 6.5E~ 9.3E~ 3.7E~ 2.1E~ 1.3E~ 9.0E-IO 6.8E-10 5.5E-10 4.3E-10 3.5E-10 NE 0. 6.0MB 8.9E~ 3.5E~ 1.9E~ 1.2E~ 8.1E-10 5.6E-10 4.3E-10 3.3E-10 2.8E-IO I HK 0. 3.2E~ 4.8E~ 1.9&48 1.0E~ 6.6E-10 4.68-10 3.2E-10 2.4E-10 1.9E-10 1.58-10 I E 0. 3.0E~ - 4.6E~ 1.8E~ 9.5E-10 6.0E-10 4.2E-IO 3.1E-10 2.5E-10 2.0E-10 1.6E-10 I EK 0. 3.7E~ 5.8E~ 2.3E~ 1.2E~ 8.0E-10 5.4E-IO 3.9E-10 3.0E-10 2.28-10 1.7E-10 I I sE o. 6.4M8 4.0E~ 2.1E~ 1.4E~ 9.7E-10 7.2E-10 5.6E-lo - 4.3E-IO 3.5E-10 I I SSE o. 6.28-N 3.6E~ 2.0E~ 1.2&% 8.7E-10 6.4E-10 4.9E-10 3.98-10 3.18-1O I S O. 4.2E~ 7.0M8 2.6E~ 1.4E~ 9.5E-10 6.9E-10 4.9E-10 3.88-10 3.0E-IO 2.5E-10 I I ssw o. 3.4E~ 5.4E~ 2.2&09 1.1E~ 7.5E-10 5.0E-IO 3.7E-10 2.98-10 2.38-10 1.88-1O I I sw o. 4.5E-M 7.0E~ 2.6E~ 1.5E~ 9.0E-10 6.6E-10 4.6E-10 3.6E-10 3.0E-10 2.5E-1O I I wsw o. 5.3FHB 7.7E~ 3.0C~ 1.6E~ 1.0E~ 7.3E-10 5.5E-10 4.1E-10 3.38-10 2.68-10 I I w o. 5.0E~ 7.5E~ 3.0E~ 1.6E~ 9.8E-10 6.7E-10 5.0E-10 3.8E-IO 3.2E-IO 2.6E-10 I I wNw o. 8.88-CB . 1.3LMB 4.9E~ 2.6E~ 1.7E~ 1.1&09 8.7E-10 6.6E-10 5.1E-10 4.28-10 I W 0. 8.2E~ 4.7E~ 2.5E~ 1.6E~ l. lE~ 7,9E-10 5.8E-10 4.7E-10 3.8E-IO I I ww o. 8.2MB 4.6&% 2.4E~ 1.5L~ 1.1EO9 8.1E-IO 5.9E-10 4.8E-10 4.O8-1O I I N 0. 5.1E~ 7.3E~ 2.9E~ 1.5E-09 9.8E-10 7.1E-10 5.4E-10 4.2E-10 3.2E-IO 2.78-1O I thmber of Valid Observaticns 17135 Number of GQms Lcwer Leal 95 Nmrher of Invalid Observaticns ~ 385 Amber of Calna Upper Level = 0 Note 1 Any interpolaticns between stated nd.leages will be dcne by log-log
Page 72 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NOe C 200~ REVISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) APPENDIX B Limited Aznlysis Dose Assessment for Liquid Radioactive Efftuents The radioactive liquid efftuents for the years 1978, 1979, aud 1980 axe evaIusted to determtne the dose ccntributicn of the zadi~de distributicn. This analysis was perforaad to dose calculation to a few selected zadicnuclides that ccatribute the na)ority of the dose provides a sisplifked aathod of determining conpliance with the dose limits of Ted',cal Specificaitcn 3.11.1.2. Tables B-1 and B-2 present the results of this evatustim. Table B-1 presents the fzacticn of the adult total body dose c~ributed by the na)or zadiouuclides. Table B-2 pzusents the sana data for the adult GI-LLI dose. The adult total body and whit GI-LIZ were detexmfned to,be the limiting doses based m an evaluaticn of all age groups (adult, teenager, child, and infant) and all orgms (boue, liver, kidneyf tung/ and GI-LLI). As the data in the tables shaw, the zadicnuclides Fe-59, Co-58, ~, ZtHi5, Cs-134, aud Cs-137 dminate the total body dose; the In,all but zadicuuclides, Fe-59, Co-58, Co-60, Zrr65, and Nb-95 domhate the GI-LLX dose. cne case (197Mish, GI-LLI dose) these zadicouclides ccntribute 90K or nate of the total dose. If fa: 1979 the fish snd she1lfish pathways aze conhined as is dane to determtne the total dose, 'the ccntrlbution from these nuclides is 848 of the total GIWLX dose. 2xxefoze, the dose cottmitttant due to zadioactive ttaterial in liquid efQuents can be zessorably estimated by 1imiting the dose ca1culation to the zadicnuclides, Fe-59$ Co 58f Zn-65, Nb-95, Cs-134, aud Cs-137,.which cumlatively cuatribute the rra)ority of the total Rse calculated by using all zadicnuclides detected. 'Ibis limited analysis dose assessnant method is a sinplified calculaticn that pzovides a zeascnable evalusticn of doses due to liquid zadicective efftuents and allows for an estimate of Fe-55 ccntribution to dose.
/
Tritium is mt inctuded in the limited analysis dose sssessaant for liquid releases because the potential dose resulting from nornal reactor releases is xagligible md is essentially independent of zadwaste system opezatim. The straunt af tritium zelesses snmally is about 300 curies. At St. Lucie, 3R Ci/yr zeleased to the Atlantic Ocean produces a ca1culated whole body Rse of 5 X 10 7 mrem/yr via the fish snd shelIfish pathways. This anaunts to less than 0.001X of the des~ objective dose of 3 mzem/yr. Furtherneze, the release of tritium is a functim of operating tina snd parer level snd is essentially unzeIated to zahraste system operatic. A- The does Ne to Irm -55 mde it tacessazy to change the anservatism factor from 0.8 to 0.6,, which wM dcne cn Ravisicn 7 to the ODCM, based on early 1986 data.
Page 84 of 84 ST. LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO ~ C-200, REUISION 7 OFFSITE DOSE CALCULATION MANUAL (ODCM) APPBGIX F MEIKIROKGTQJ DISPHSZN KBMEAS+ For X/0:
ÃlQ 2.032 6Hhr D ~ 2z+ cV2/pi) @ (1) 2.032
@ (2)
Where C ~ .5 U ~ 207.5 ft. (63.2 meters) (~) ~ a name for eve term 1 in @ (1) and Kg(2) detetes take the squaze mot of the term in parentheses 2
@(1) snd @(2) shculd be a 3awer case sigma if this is cottpsred to zefezerees ancerning i'teteomiogical data X/Q ms calculated using each of the above EQ's far each hour. The highest X/Q fmm @ (1) or @ (2) ms selected. Ihe total integrated relative ccncentraticn at each 'sector snd distance was then divided by the .total nunher af hcurs in the data base.
For Depleted X/Q: (X/Q)D (X/Q) X (Depleticn factor of figure 2 of R.G. 1.111~) For Depositbn (D/Q): D/Q ~ RDep/(2 sin [11.25J X) X (Fzeq. distributicn) Where: D/'Q Gmund depositicn rate X ~ Chlculatim distance RDep ~ Relate grcund hqositicn rate fmm Figure 6 of R.G. 1.111, Rl
- Terrain corzecticn factors given by Table ~ were also applied to Dispersion Formulas}}