ML17222A441

Combined Semiannual Radioactive Effluent Release Rept for Jan-June 1988. W/880830 Ltr

ML17222A441
Person / Time
Site:	Saint Lucie
Issue date:	06/30/1988
From:	Conway W FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
A-88-385, NUDOCS 8809060372
Download: ML17222A441 (50)

Text

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'ACCESSION NBR:8809060372 DOC.DATE: 88/06/30 NOTARIZED: NO . DOCKET FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power 6 Light Co. 05000335 50-389 St. Lucie Plant, Unit 2, Florida Power & Light Co. 05000389 AUTH. NAME AUTHOR AFFILIATION CONWAY,W.F. Florida Power & Light Co.

RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

"Combined Semiannual Radioactive Effluent Release Rept for Period 880101 880630." W/880830 ltr.

DISTRIBUTION CODE: IE48D TITLE: 50.36a(a)(2)

COPIES RECEIVED:LTR Semiannual 4 ENCL Effluent Release Reports

/ SIZE.. G NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 0 PD2-2 PD 5 5 TOURIGNYiE 1 1 INTERNAL: ACRS 1 1 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 ARM TECH ADV 1 1 NRR/DEST/PSB 8D 1 1 NRR DREP RPB 10 4 4 NUDOCS-ABSTRACT 1 1 G FILE 01 1 1 RGN2 FILE 02 1 1 CN S EPRPB 1 1 EXTERNAL: BNL TICHLER,J03 1 1 LPDR 1 1 NRC PDR 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL 22

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AUGUST, g p tg88 L-88-385 10CFR50.36 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:

Re: St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 Semi-Annual Radioactive Effluent Release Re ort Attached is the Radioactive Effluent Release Report for the period of January 1, 1988 through June 30, 1988 for St. Lucie Units 1 and 2. This report is required by Technical Specification 6.9.1.7.

Should there be any questions on this information, please contact us.

Very truly yours, W. F. Co Senior Vice President - Nuclear WFC/GRN/cm Attachment cc: Dr. J. Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant GRHSARER r~]<

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FLORIDA POWER 8c LIGHT COMPANY ST. LUCIE PLANT UNITS NO. 1 8c 2 LICENSE NO.S DPR-67 &. NPF-16 COMBINED SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD JANUARY 1, 1988 THROUGH JUNE 30, 1988 8809060372 880630 PDR ADOCK 05000335 R PNU

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TABLE OF CONTENTS DESCRIPTION PAGE EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION............

SITE VISITOR DOSE FROM EFFLUENTS...

OFFSITE DOSE CALCULATION MANUAL REVISIONS.... ~.................. ( 7 SOLID HASTE AND IRRADIATIED FUEL SHIPMENTS....................

PROCESS CONTROL PROGRAM REVISIONS.. 7 LIQUID EFFLUENT:

SUMMATION OF ALL RELEASES 5, NUCLIDE SUMMATION BY QUARTER UNIT ¹ 1 ~ \ \ ~ ~ ~ ~ \ \ ~ ~ ~ \ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 8 U NIT ¹ 2 o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 10 GASEOUS EFFLUENT:

SUMMATION OF ALL RELEASES & NUCLIDE SUMMATION BY QUARTER UNIT ¹ 1 o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 12 UNIT ¹ 2 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 14 SOLID HASTE SHIPMENT SUMMATION 16 ATTACHMENT A ODCM revisions during the report,ing period

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EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION

1. Regulatory Limits

1. 1 For Liquid Waste Effluents A. The concentration of radioactive material released from the site shall be limited to the concentrations specified in 10 CFR Part 20 Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 micro-Curies/ml total activity.

B. The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive material in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS shall be limited to:

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 <= 10 mrems to any organ.

1.2 For Gaseous Waste Effluents:

A. The dose rate in UNRESTRICTED AREAS due to radioactive materials released in gaseous effluents from the site shall be limited to:

For Noble Gases. '<= 500 mrems/yr to the total body and 3000 mrems/yr to the shin, and For Iodine-131, Iodine-133, Tritium, and all radionuclides in particulate form with half-lives greater than 8 days:

1500 mrems/yr to any organ.

4B. 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 following:

During any calendar quarter, to <= 5 mrads for gamma radiation,and 10 'mrads for beta radiation and, during any calendar year to 10 mrads for gamma radiation and <= 20 mrads for beta radiation.

>KC. The dose to a MEMBER 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 following:

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.

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EFFLUENT AND HASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)

2. Maximum Permissible Concentrations Hater: As per 10 CFR 20 Part 20, Appendix B, Table II, Column 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 Hhere alpha, tritium, and named nuclides are shown as sero Curies released, this should be interpreted as "no acitvity was detected on the samples using the Plant Technical Specification analyses techniques to achieve required Lower Limit of Detection (LLD) sensitivity for radioactive effluents.

A summary of liquid effluent accounting methods is described in Table 3. 1.

A summary in Table 3 '.

of gaseous effluent accounting methods is described

4. 1 Estimate of Errors LIQUID GASEOUS Error Topic Avg.% Max.% Avg.% Max.%

Release Point Mixing 2 5 NA NA Sampling 1' 5 2 5 Sample Preparation 5 1 5 Sample Analysis 3. 10- 3 10 Release Volume 2 5. 4 15 Total % 9 30 10 35 The predictability of error for radioactive releases can only be applied to nuclides that are predominant in sample spectrums.

Nuclides that are near background relative to the predominant nuclides in a given sample could easily have errors greater than the above listed maximums.

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EFFLUENT AND HASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)

4. Measurements and Approximations of Total Radioactivity (Cont.)

4. 1 (Continued)

B. (Continued)

TABLE 3. 1 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS Liquid Sampling Type of Method of Source Frequency Analysis Analysis Each Batch Principal Gamma Emitters p. h. a.

Monitor Monthly Tritium L. S.

Tank Composite Gross Alpha G. F. P.

1 Releases Quarterly Sr-89, Sr-90, Composite & Fe-55 C. S.

Continuous Daily Principal Gamma Emitters Releases Grab I-131 for p. h. a.

Samples 4/M Compos ite Analys is Dissolved & Entrained Gases One Batch/ Month p. h. a.

Tritium Composite Monthly L. S.

Alpha Composite Monthly G. F. P.

Sr-89, Sr-90, & 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 Haste 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

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EFFLUENT AND HASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)

4. Measurements and Approximations of Total Radioactivity (Continued)

4. 1 (Continued)

B. (Continued)

TABLE 3.2 RAD10ACTIVE GASEOUS HASTE SAMPLING AND ANALYSIS Gaseous Sampling Type of Method of Sour'ce Frequency Analysis Analysis Waste Gas Decay Tank Each Batch Principal Gamma Emitters p. h. a.

Releases Containment Principal Gamma Emitters p. h. a.

Purge Each Purge Tritium L. S.

Releases 4/M Principal Gamma Emitters p. h. a.

Tritium L. S.

Plant Monthly Particulate Vent Composite Gross Alpha G. F. P.

Quarterly Particulate Composite Sr-89 & Sr-90 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 G.F. P.-Gas Flow Proportional Counting 4/M-Four per Month

r 0 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO.

SEMIANNUAL REPORT JANUARY 1, 1988 THROUGH JUNE 38, 1988 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL XNFORMATXON (CONTINUED)

5. BATCH RELEASES AND UNPLANNED RELEASES LXQUXDS FOR - ST. LUCXE PLANT UNIT NO. 1 A. NUMBER OF BATCH RELEASES- 2.2. 8 B. TOTAL TIME PERIOD OF BATCH RELEASES- 11658. MXNUTES C. MAXIMUM TXME PERIOD FOR A BATCH RELZASE- 1847. MXNUTES D. AVERAGE TIME PERIOD FOR A BATCH RELEASE: 555. MXNUTES E. MINXMUM TXME PERIOD FOR A BATCH RELEASE: 315. MINUTES F. AVERAGE STREAM FLOW DURING REPORTING PERIOD XNTO A FLOWING STREAM: 1827887. G.P.M.

8. GASEOUS FOR : ST. LUCXE PLANT- UNIT NO. 1 A. NUMBER OF BATCH RELEASES- 2.8 B. TOTAL TIME PERIOD OF BATCH RELEASES- 558. MINUTES C. MAXIMUM TXME PERIOD FOR A BATCH RELEASE-'.

438. MINUTES AVERAGE TXME PERIOD FOR A BATCH RELEASE- 275. MINUTES E. MINIMUM TIME PERXOD FOR A BATCH RELEASE: 198. MINUTES UNPLANNED REK EASES LIQUIDS FOR '- ST. LUCXE PLANT UNIT NO. 1 A. NUMBER OF RELEASES: 8.

B. TOTAL ACTIVXTY RELEASED- 8. CURIE S GASEOUS FOR : ST. LUCXE PLANT UNIT NO. 1 A. NUMBER OF RELZASES- 8.

B. TOTAL ACTXVITY RELEASED- 8. CURIES SEE ATTACHMENTS (XF APPLICABLE) FOR-A. A DESCRIPTION OF THE EVENT AND EQUIPMENT XNVOLVED.

B. CAUSE(S) FOR THE UNPLANNED RELEASE'.

C. ACTIONS TAKEN TO PREVENT A RECURRENCE.

D. CONSEQUENCES OF THE UNPLANNED REKEASE.

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FLORIDA POWER Br, LXGHT COMPANY ST. LUCIE PLANT UNIT NO. 2 SEMIANNUAL REPORT JANUARY 1, 1988 THROUGH JUNE 38, 1988 EiFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED)

5. BATCH RELEASES AND UNPLANNED RELEASES LIQUIDS FOR - ST. LUCIE PLANT UNIT NO. 2 A. NUMBER OF BATCH RELEiASES- 21.8 B TOTAL TXME PERIOD OF BATCH REiLEASEiS 11658. MINUTES C. MAXXMUM TIME PERIOD FOR h BATCH RELEASE- 1847. MXNUTZiS D. AVZiRAGE TIME PERXOD FOR A BATCH RELEASE: 555. MINUTES E. MINIMUM TXME PERIOD FOR h BATCH RELZiSE 315. MINUTES F. AVERAGE S'QKAM FLOW DURING REPORTING PERIOD INTO A PLOWING STREAM- 1827887. G. P.M.

6. GASEOUS FOR : ST. LUCXE PLANT UNIT NO. 2 A. NUMBER OF BATCH RELEASES- 22. 8 B. TOTAL TIME PERIOD OF BATCH RELEASES- 6679. MINUTES C. MAXIMUM TIME PERIOD FOR A BATCH RELEASE-'.

788. MINUTES AVERAGE TXME PERIOD FOR A BATCH RELEASE- 384. MINUTZiS E. MXNXMUM TIME PERIOD FOR A BATCH RZLEASE- 28. MXNUTZS UNPLANNED RELEASES LIQUXDS FOR - ST. LUCXE PLhNT UNIT NO. 2 A. NUMBER OF RELEASES- 8.

B. TOTAL ACTXVITY RELEiASED- 8. CURIES GASEOUS FOR - ST. LUCIE PLANT UNIT NO. 2 A. NUMBER OFi RZLEASZS- 8.

B. TOTAL ACTXVXTY RELEASED- 8. CURXES SEE ATTACHMENTS (IF APPLICABLE) FOR-

h. A DESCRIPTION OF THE EVENT AND ZQUXPMENT INVOLVED.

B. CAUSE(S) FOR THE UNPLANNED RELEASE.

C. ACTIONS TAKEN TO PREVENT A RECURRENCE.

D. CONSEQUENCES OF THE UNPLANNED RELEASE.

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FLORIDA POWER 8c LIGHT COMPANY ST. LUCIE PLANTS UNITS 1 & 2 SEMIANNUAL REPORT JANUARY 1, 1988 THROUGH JUNE 30, -Ig88.

EFFLUENT AND HASTE 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 is reported on the year ending Semi-Annual Report.

8. Offsite Dose Calculation Manual Revisions (ODCM):

Five typographical errror correction changes were made to the ODCM.

Four of theses errors were noted by Mr. Edward Brandegan, of the U.S. NRC during his audit of the document. None of these changes affect medthodology. The changes are documented as Attachment A to this report.

9. Solid Haste and Irradiated Fuel Shipments:

No irradiated fuel shipments were made from 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.

10. Process Control Program (PCP) Revisions:

The PCP was not revised during the reporting interval.

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FLORIDA POSER Bc LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 SEMIANNUAL REPORT JANUARY 1, 1968 THROUGH JUNE 38, 1988 TABLE 3. 3-1 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER ¹1 QUARTER ¹2 A. FISSION AND ACTXVATXON PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CI 1.89E-82 4.28E-82'X

2. AVERAGE DILUTED .CONCENTRATION DURXNG PERIOD UCI/ML 8. 45E-11 3. 72E-il B. TRITIUM

1. TOTAL REGMSE 3.68E 81 9.37E 81

2. AVEMGE DILUTED CONCENTRATION DURING PERIOD'.

UCX/ML 7.26E-88 1.85E-87 DISSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE CI 2.82E-82 2.52E-81

2. AVERAGE DILUTED CONCENTRATION DURXNG PERIOD UCX/ML 3. 99E-11 "* 4. 98E-18 D. GROSS 'ALPHA RADIOACTIVXTY TOTAL RELMSE CX 8.88E-81 E. VOLUME OF HASTE RELEASED (PRXOR TO DILUTXON) LITERS 2.92E 8? 2.59E 87 F. VOLUME OF DILUTXON MTER USED DURXNG REPORTXNG PERIOD LITERS 5.8?E 11 5.86E 11

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FLORIDA POWER &, LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 SEMIANNUAL REPORT JANUARY 1, 1988 THROUGH JUNE 38, 1988 TABLE 3.4-1 LIQUID EFFLUENTS NUCLIDES CONTINUOUS MODE BATCH MODE RELEASED UNIT QTR.O1 QTR.02 QTR.Sa QTR.02 I-131 CI 2. 54E-84 8. SSE-81 1.89Ei-83 9.11E-84 I-133 CX S.esz-ea S.SSE-81 3.83E-84 1.41E-84 Nh-24 CI S.SSE-81 S.SSE-81 1.85E-85 S.SSE-81 CR-51 CI S.SSE-81 S.SSE-el 4.83E-84 S.SSE-81 MN-54 CI S.SSE-81 S.SSE 81 3.68E-84 3.7SE-85 FE-55 CX S.SSE-el 8 SSE-Sl 1 36E-82

~ 5.68Z-83 CO-58 CI S.SSE-81 S.SSE-81 5.38E-83 4.38Z-83 FE-59 CX S.SSE-81 S.SSE-81 3 '8E-85 S.SSE-el CO-68 CI S.SSE-81 S.SSE-81 3.77E 83 2.42Z-83 AG-118 CI S.SSE-el S.SSE-81 3.81E-84 8.13E-85 SN-113 CI S.SSE-81 g SSZ-gl 2.64Ei-85 S.SSE-81 SB-122 CX S.SSE-el S.SSE-sl 1.86E-85 S.SSE-81 SB-124 CI S.SSE-81 S.SSE-81 2 89E-83 1 34E-84 SR-98 CI 7.92E-84 S.SSE-Sl 1 25E-SS 2.55E-85 Y-98 CI 7.92E-84 S.SSE-81 1 25E-SS 2.55E-85 ZR-95 CX S.esz-ea S.SSE-81 3.69E-84 S.SSE-el NB-95 CI S.SSE-81 S.SSE-81 7.51E-84 9.29E-85 NB-97 CX S.SSE-el S.SSE 81 4.66E-84 8.72E-85 TC-99M CI S.SSE-81 8 SSE-81 S.SSE-81 1 ~ 37E-85 SB-125 CI S.SSE-81 8 SSE-81 7 93E-83 3.87Z-83 CS-134 CI S.SSE-81 S.SSE-81 1.13E-83 6.68E-84 CS-137 CI 6.79E-85 S.SSE-81 1.88E-83 1.18E-83 LA-148 CI S.SSE-81 S.SSE-81 1.97E-84 4.98E-85 TOTAL FOR PERIOD CI 1.91E-83 S.SSE-81 4.89E-82 1.89E-82 AR-41 CI 8. SSE-Sl S.SSE-81 2.75E-85 8.88E-sl XE-131M CI 8. SSE-81 S.SSE-81 S.SSE 81 1.98E-83 XE-133 CX S.SSE-81 S.SSE-81 1 ~ 73E-82 2.46E-81 XE-133M CI S.SSE-81 S.SSE-81 2.55E-84 2.23E-83 XE-135 CI S.SSE-81 S.SSE-81 2.62E-83 1 ~ 78E-83 TOTAL FOR PERIOD CI S.SSE-81 S.SSE-81 2.82E-82 2.52E-81

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, LIQUXD EFFLUENTS SUMMATION OF ALL RELZASES NUCLXDES RELEASED UNXT QUARTER ¹1 QUARTER ¹2 A. FISSION AND ACTIVATXON PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING

'TRITXUM, GASES, ALPHA) CX 4.89E-82 1.89E-82

2. AVERAGE DILUTED CONCENTRATXON DURING PERIOD UCX/ML 8.88E-11 3.72E-11 B. TRITIUM

1. TOTAL RELEASE CI 3 68E 81 9.37E 81

2. AVERAGE DXLUTED CONCENTRATION DURING PERIOD UCX/ML 7.26E-88 1. SSE-87 C. DISSOLVED AND ENTRAINED GASES

1. TOTAL RELZASE CI 2.82E-82 2 '2E-81

2. AVERAGE DILUTED CONCENTRATXON DURING PERIOD UCX/ML 3.99E-11 4.98E-18 D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE CI 8. 88E-81 8. 88E-81 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTXON) LXTERS 1.84E 86 1.57E 86 F. VOLUME OF DILUTXON WATER USED DURING REPORTXNG PERIOD LITERS 5.87E 11 5.86E 11

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FLORIDA POWER 8c LIGHT COMPANY ST LUCIE PLANT UNIT NO. 2 SEMIANNUAL REPORT 1, 1988 THROUGH JUNE 38, 1988 TABLE 3.4-2 LXQUXD EiKi'FLUENTS NUCLIDES CONTINUOUS MODE BATCH MODE RELEASEiD UNIT QTR.¹1 QTR.¹2 QTR.¹1 QTR.¹2 I-131 I-133 CI CX S.SHZ-81 S.SSE-81 S.SSE-81 S.HHE-81

l. 89E-83 3.83E-84 9.11E-84 1.41E-84 NA-24 CX S.SSE-81 S.SHE-81 1.85E-85 S.SSE-81 CR-51 CI S.SSE-Sl S.SSE-81 4.83E-84 S.HSZ-Sl MN-54 CX S.SSE-81 S.SSE-81 3.6HE-84 3.76E-H5 FZ-55 CX S.HSE-81 H.SSE-81 1 36E-82 5.6SZ-83 CO-58 CX S.SSE-81 H.SSE-81 5.38E-83 4.38E-H3 FZ-59 CI S.HSE-81 S.SSE-81 3.28E-85 S.SSE-Hl CO-68 CI S.HSE-81 S.SSE-81 3.77E-83 2.42E-83 AG-118 CX S.HSE-Sl S.SSZ-81 3.81E-84 8.13E-85 SN-113 CX 8.88E-81 S.SSE-81 2.64Ei-85 H.HSE-81 SB-122 CI S.SSE-81 S.HSE-81 1.86E-85 S.SSE-81 SB-124 CX S.HSE-81 S.SSE-81 2.89E-83 1.34E-84 SR-98 CX S.SSE-81 S.SSE-81 1 ~ 25E-86 2 '5E-85 Y-98 CI S.SSZ-81 H.HHE-81 1.25E-86 2.55E-85 ZR-95 CX S.SHE-81 S.HSE-81 3 '9K-84 S.SSZ-81 NB-95 CI S.SSE-81 S.SSE-81 7.51E-84 9.29E-85 NB-97 CI S.SSE-81 S.SSE-H1 4.66E-H4 8.72Ei-85 TC-99M CI S.SSE-81 g SHEi-81 S.SHE-81 1.37E-S5 SB-125 CX S.SSE-81 S.SSE-81 7.93E-83 3.87E-83 CS-134 CX S.SSE-81 H.SSE-81 1.13Ei-83 B.BSE-H4 CS-137 CX S.HSZ-Sl S.SHE-81 1.88E-83 1.18E-83 LA-148 CI S.HSE-H1 S.SSE-81 1.97E-84 4.98E-H5 TOTAL FOR PERIOD CI S.HSE-81 S.HHZ-81 4.89E-82 1.89E-82 AR-41 CI S.SHZ-81 H.SHZ-81 2.75E-85 S. SSZ-Sl XE-131M CI g gSEi-gl S.SHE-81 S.SSE-81 1.9HE-S3 XEi-133 CI S.SSE-81 S.SSE-81 1.73E-82 2 '6E-81 XE-133M CI S.SHE-81 S.SSE-81 2.55E-84 2.23E-H3 XE-135 CX S.SSZ-81 S.SSE-81 2.62E-83 1.78E-S3 TOTAL FOR PERIOD CI S.SHE-81 S.SSE-81 2.82E'-82 2.52E-Sl

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SENIANNUAL REPORT JANUARY 1, 1988 THROUGH JUNE 38, 1988 TABLE 3. 6-1 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT . QUARTER 41 QUARTER 02 A. FISSION AND ACTXVATXON GASES

1. TOTAL RELEASE CX 4.11E 82 4.66E 82

2. AVERAGE RELEASE RATE -FOR PERIOD UCI/SEC 5.28E 81 5.92E 81 B. XODXNES

1. TOTAL IODINE-131 CI 1.91E-83 1 ~ 82E-83.

2. AVERAGE RELEASE RATE FOR PERXOD UCI/SEC 2.45E-84 1.38E-84 C. PARTICULATES

1. PARTXCULATES T-1/2 >' DAYS CI 8. 88E-81 8;88E-81 2 AVERAGE RELEASE MTE FiOR 'PERIOD UCI/SEC 8. 88E-81 8.88E-81

3. GROSS ALPHA'ADIOACTIVITY CI 2.62E-87 1.88E-87 D. TRITIUM

1. TOTAL RELEASE CI 5.82E 81 2.81E 81

2. AVERAGE RELEASE MTE FOR PERIOD, UCX/SEC 6.46E 88 . 2.56E 88

YMASHOO TBBXJ aS 8RKR AGX80>L L .ON TING TM1'X BXOUJ .TB TRODI JAQzt'lAINM 888l, M IUG HGUOgHT GMX << l YQMNA'4 L-O.r. 3~%'r RB AJVP~QQP f.Q ~JjKUQ QZ&23;"L% ~~~QMQ'3.I V3m~D $ ~QKVAVXTM GH< VQIBBXU< .A RB Q3B.g ee ntx.v 48 MC.G-M-HHQ.X, GQ-GEC.X EGA-QJIGQX ifGT 5Q-~>~g. g QQaMQOXTGAR .0 LQ-><3 Q

t t FLORIDA POWER 8c LXGHT COMPANY ST. LUCXE PLANT UNIT'NO. 1 SEMIANNUAL REPORT 1, 1986 THROUGH JUNE 38, 1988 TABLE 3.7-1 GASEOUS EFFLUENTS GROUND LEVEL RELZASES NUCLIDES CONTINUOUS MODE BATCH MODE RELEASED 'UNIT QTR.01 QTR.02 QTR.51 QTR.02

1. NOBLE GASES KR-85M CI 2.29E 88 1.85E 88 'S.SSE-81 8. SSE-81 KR CX 4.14E 88 1.35E SS S.SSE-81 8. SSE-81 XE-131M CI S.SSE-81 S.SSE-81 1.38E-83 S.SSE-81 XE-133 CI 3.2SE -82 3.8SE 82 2.59E-Si 3'.82E-83 XE-133M CI 4.61E-81 3.14E 88 S.SSE-81 S.SSE-81 XE-135 CI 8.41E Sl 7.95E 81 S.SSE-Sl O'.SSE-81 TOTAL FOR PERIOD CX 4.1SE 82 4.66E 82 2.6SE-Si 3;82E-83

2. IODXNE I-131 CX 1.91E-83 1.82E"83 I-133 CX 1.87E-82 $ .15E-83 TOTAL FOR PERIOD CX 1.26E-82 9.17E-83

3. PARTXCULATE TOTAL FOR PERIOD CX S.SSE-81 S.SSE-81

t YNAGKOJ TOME

.ON TXM aS 8K'(H MIAOW'"C T'AI'X 8XQUJ .TQ t

TQOgSI BAQNBAIkQB 88QC,88 %JUG 83UQ~~37 GGQ f.

X"V.G PSHAW Q2"lM~~~'f, BH'IBB gGVQ"$9 - QV<f'M'KU BGQ UM GCQH fi97llG, ZC~Q~$ VGGFliI~'~,"9'3 i"ZGXQWN RB.f~=z'-g L'A.~i@ 88.fi7g iQ "~sc9 V,Xgtf GQVMBHH GZLCQ ZBGQv'3 .X XQ-2~3.Q< J.Q-WQ.Q E3 GQG.X C3~'~BR.R 4"~G"R EQ-'3.Q Jt,Q-C"2.Q U3 BQC.Jt C'3 PM.b GB"2~I H3-M~3.B 4Q-HQB.E S,Q-H.3'3.Q EQ D"'B+B k-lfGX-HK GB;-HEQ C XQ-2"2 ~ RB 223.8 MX-KX 48- ~3 Q Jt.G- 3,8 V3 nx.g Kk-'BEB.5 'l.~vRX-.'KZ kQ-c '.B XQ-a~ i3.Q XQ BBC-V XQ Hl&,8 @EX-ZZ gG'K aIMQT 4Q-MB,C XB-CQ3.8 RE) gg5.5 Sg 5M.5 '6OXZ~L%

.RilKOX .R CQ,"D~Q.X..CB-BEG.X ice-x CQ-Bc3X. 8 Rg-BVQ. X FBX-X f'Q>3 Nx4d pQ-Q~gg Q CQ-/rgb XG GQI+i".J'. X Kf~'83i93XYBA'X . G gG~X <<M,YOV SQ 4~ 3+Q k8, ~~~BaQ X9 CAI~X

14 FLORIDA POSER Br. LXGHT COMPANY ST. LUCIE PLANT UNIT NO. 2 SEMIANNUAL REPORT JANUARY 1, 1988 THROUGH JUNE 38, 1988 TABLE 3.6-2 GASEOUS EFFLUEiNTS SUMMATION OF ALL RELE'ASKS NUCLXDES RELEASED UNIT QUARTE>R 01 QUARTER 02 A. FISSION AND ACTIVATXON GASES

1. TOTAL RELEASE CI 1.54E 83 2.68E 83

2. AVERAGE RELMSE RATE FOR PERIOD UCX/SEC 1.97E 82 3.31E 82 B. IODXNES TOTAL IODINE-131 CX 4.15E-83 9.71E-83

2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 5.34E-84 1.23E-83 C. PARTXCULATES

1. PARTICULATES T-1/2 > 8 DAYS CI S.SSE-81 3.84E-85

2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC S.SSE-81 3.86E-86

3. GROSS ALPHA RADXOACTIVXTY CX 8.78E-88 2.SSE-88 D. TRITIUM

1. TOTAL RELEASE CX 2.34E 81 2.56E 81

2. AVERAGE RELEASE RATE FOR PERXOD UCX/SEC 3.81E 88 3.25E 88

s Ls lift iQ ( lf I'I ifff'igif ffi I/ rg 'fft i . 'fif I,'ri e Jif j I. dJ4 J I{ J 4 t 4(tf(3~'J l),), i iiifff ( ls)ff it js ff \ i j tl,l i 'I JI L .

FLORIDA POVKiR 8r, LIGHT COMPANY ST. LUCXE PLANT UNIT NO. 2 SEMXANNUAL REPORT JANUARY 1988 THROUGH JUNE 38, 1988 TABLE 3.7-2 GASEOUS EFFLUENTS GROUND LEVEL RELEASES NUCLIDES CONTINUOUS MODE BATCH NODE RELEASED UNIT QTR.01 QTR.02 QTR.01 QTR.02

1. NOBLE GASES AR-41 CX 8. 88E-81 8.88E-81 2.87E-81 2.35E-81 KR-85M CI 9.83E 88 2.68E 81 4.79E-S3 9.97E-82 KR-88 CI 3.56E 88 1.28E 81 3.24E-83 6.77E-82 XE-131M CX 8.88E-81 S.SSE-81 5.72E-82 3.93E-81 XE-133 CX 1.3SE 83 2.19E 83 3.97E 88 8.12E 81 XE-133M CX S.SSE-Sl S.SSE-81 2.93E-82 1.27E 88 XE-135 CX 1.57E 82 2.91E 82 7.14E-82 2.43E SS TOTAL FOR PERIOD CI 1.53E 83 2.52E 83 4.34E 88 8.57E 81

2. XODINE I-131 CI 4. 15E-83 9. 71E "83 I-133 CX 5. 89E-83 1. 24E-S2 TOTAL FOR PERXOD CI 1.88E-82 2.21E-82

3. PARTICULATE CS-137 CX S.SSE-81 3.84E-85 TOTAL FOR PERIOD CX 8.88E-81 3 '4E-85

f I 'ff f lgi)I Ifjj lff(l,l I lf>>

r, 4 tf I.,If) 4(I f I II ll Jfi ff,di 4fj f' "frffi,,l, rfll f'Ij 'fl frj 7

( I'lr f 4 I j II Il~j,,i,IP 'l i( f.,'.", ',<<) f fj '/< II P4 tff,y(f fl > I," Illjr I ,l 4.rj ff yP t,,';, I I <<>> tjf j. 44 4 L 4

>>~ <<vl j if I'& L".jj<"jf-, 'ff(

I jff I

J I. J t'0 '."l<< z I,'f(",

)f f,f>>] II, I I>> I >4 I.

I

' 'I '

, I jf'll I, jf 'I ff ~

I I' ljjfl rf I' rf 4 fj f ft, '1 I I jf,'

rf Sft/',,fr Ilia'f I,

> )If Ig jj I >> s J

I

(

~ frltff fj

~,IP, jf

16 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT SEMIANNUAL REPORT JANUARY.1, 1988 THROUGH JUNE 30, 1988 UNITS 1 AND 2, TABLE 3.9 "

A. Solid Waste Shipped Off-site for Burial or Disposal

1. Type of Waste Unit 6 Mo. Period Error 8

a. Spent resin, M3 2.434 E+1 Process filters Ci 5.803 E+2, 2.0E+1

b. Dry compressible Waste (Note 5) 'i*

M3 1.396 E+2 1.479 E 2.0E+1

c. Irradiated M3 Eoo Components Ci 1.014 E+4 2.DE+1 d." Other i M3 2.192 E+1

l. Non-Compressible Cig 3.322 E-1 2.0E+1 Metal (DAW) (p

~ (Note 6)

2. Estimate of Major Nuclide Composition (By Type of Waste)

I Category Nuclides a ~ Cs 137 3.46E+1

. Cs 134 2.60E+1 Co 58 2.55E+1

,Co 60 4.87E+o Ni 63 2 41E+o Fe 55 1.48E+o Mn 54 1.33E+o Cr 51 8.59E 1 Nb 95 8.18E-l I 131 6.42E 1

b. CS 137 57Etl Co 60 2.44E+1 Co 58 1.53E+1 Fe 55 1.07E+1 Cs 134 9.33E+o H 3 5.84E+o Ni 63 2.73E+o Nb 95 1.74E+o Mn 54 1.42E+o Zr 95 1.22E+o Cr 51 7.90E-1 C 14 4.40E-1 Ce 144 3.80E 1

n L

t'

Category Nuclides c ~ Fe 55 4.16E+1 Mn 54 2.19E+1 Co 58 1.73E+1 Co 60 1.61E+1 Ni 63 3 '0E+o

d. Co 60 8.28E+1 Fe 55 1.08E+1 Mn 54 3.28E+o Ni 63 1.27E+o Sb 125 4 79E-1 Cs 137 4.00E-1 Co 58 3.46E 1

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 38 Sole Use Truck Barnwell, S.C.

B. Irradiated Fuel Shipments Number of Shipments Mode of Transportation Destination N/A N/A N/A = Not Applicable

FLORIDA POWER & LIGHT COMPANY ST LUCIE PLANT SEMIANNUAL REPORT JANUARY 1, 1988 THROUGH JUNE 30, 1988 UNITS 1 AND 2, TABLE 3.9 (CONT'D)

Total Total Principal Type of Category Type of Waste Volume Curies Radionuclides Waste Reg-Guide Container Solidification Class Cubic Ft. (Note-1) (Notes 1 & 2) -(Note 3) 1.21 (Note 4) A ent Class A 4932.50 1.48 NA PWR l.b. Non-Specification None Compactible Strong Tight Trash Package (Note 5)

Class A 774.10 3.32E-l NA PWR l.d. Non-Specification None Non-Compactible Strong Tight Trash Package (Note 6)

Class B 531.90 114.43 Ni63, Sr90, PWR Ion- l.a. NRC Certified None Csl37 Exchange LSA Resin > Type A Class C 83.4 91.53 Co60, Ni63, PWR Ion- l.a. NRC Certified None Sr90, Csl37, Exchange LSA Sum of Resin > Type A Nuclides with TQ < 5 years Class C 120.3 366.87 C14, Ni63, PWR Ion- l.a. NRC Certified None Sr90, C137, Exchange Type B Sum of Resin Nuclides with T4 < 5 years Class C 120.3 7.43 Ni63, Pu241, PWR l.a. NRC Certified None Sum of Process Type B Nuclides with Filters T4 < 5 years Class C 57.4 10,144.0 C14, Co60, PWR l.c. NRC Certified None Ni63, Sum of Incore Type B Nuclides with Detectors TQ < 5 years

FLORIDA POWER AND LIGHT COMPANY ST. LUCIE PLANT SEMIANNUAL REPORT JANUARY 1, 1988 THROUGH JUNE 30@ 1988 UNITS 1 AND 2 TABLE 3.9 (CON'T)

SOLID WASTE SUPPLEMENT Note 1: The total curie quantity and radionuclide composition of solid waste shipped from the St. Lucie Plant, Units 1 & 2 are determined using a combination of qualitative and quantitative 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 (5/11/83) 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 as 3H, 14C, 99Tc, 129I, TRU, 241Pu, 242Cm, 63Ni, 55Fe, and 90Sr.

Note 2: "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 .01 times the smallest concentration of the nuclides listed in Table 2 of 10 CFR 61.

Note 3: "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".

Note 4: "Type of Container" refers to the transport package.

Note 5: The volume and activity listed for Dry Compressible Waste represent the quantity of material that, to date has been sent to the Barnwell, South Carolina burial facility. This material was shipped to a contracted

'vendor for volume reduction prior to final disposal at the Barnwell, South Carolina burial facility. During the reporting period, five shipments of Dry Compressible Waste (5157 cubic feet, 7.28E Curies) were made from the St. Lucie Plant to the volume reduction facility.

This material was shipped via "Sole Use Truck" in non-specification strong tight packages.

Note 6: The volume and activity listed for non-compressible metal represent the quantity of material that during the reporting period could not be recycled by the contracted vendor and required disposal.

Page 1 of SS Attachinent.4 Rev 09 changes FIDRIDA KNUR & LIGHT COMPANY ST. IIJCEE PZtÃZ CKMESTRY OPERAT324G PROCEDURE NO. C-200 REVISION 10 TPlKZ:

Offsite Dose Calculation Manual (OIXH)

K".VH%f AND APHKVAL:

Rdriewed by Facility Review Group ril 22 1982 Approved by C. M. Weth Plant Manager ril 27 1982 Revision 10 Reviewers F R G - 3197 Plant Manager ) i2-19 ~M S OPS I I f

DATE' f DXT PROamRE f f

DOCK C-2OO f

I f

~

SYS rw

~~~~

1o I

I I I

Page 12 of 88 ST. ZIJCIE PIANT CKMESTRY OPlHVQXNG HKCEIXHK NO. C-200, REVISION 10 OFFSITE DOSE CADXKATIONMANUAL 0 1.3 (continued)

TABLE 1.3 1978 UNDIIUHK) M,2 uCi/ml1 (no units)

I-131 4.43 -5 2 E-3 I-132 2.23 E-7 2.30 E-7

-133 3.17 E-6 62 E-5

-135 1.3 E-6 2 7 E-6 a-24 1. 2 E-Cr S1 2.51 E-5 1. 4 -7

-54 64 E-6 .66 -7

-56 1.11 E-9 17 -11 Co-57 3.69 E-7 7.62 EW Co-58 1.51 E-4 1.3 E-5 Fe-59 2.92 E-6 4.83 E-7 Co-60 3.66 E-5 1.00 E-5 Zn-65 4.55 E-7 3.76 E-8 Ni-65 8.23 E-7 6.80 E-8 A -110 1.96 E-6 5.40 E-7 Seve

~

Sn-113 5.75 E-7 5. 4 E-8 Sb-122 2.15 E-6 5. 5 E-7 Sb-124 8.40 E-6 3.47 E-6 W-'187 3.51 E-6 8 E-7 23 1.57 E-7 .30 E-8 Br 82 3.64 E-7 7.52 E-8 Zr- 5 2.82 E-5 3.88 E-6 Zr-97 4.05 E-6 1.67 EW No-99 3.24 E-6 6.70 E-7 Ru-103 3.84 E-8 4.00 E-9 Sb-125 2.26 E-6 1.87 E-7 Cs-134 2.14 E-5 1. 6 E-5 Cs>>136 7.82 E-7 1.08 E-7 Cs-137 4.85 E>>5 2.00 E-5 Ba-140 6.44 E-7 2.66 E-8 Ce-141 3.04 E-8 2.80 E-9 Ce-144 2.37 E-6 1.96 E-6 4.01 E-4 ////////////////

1.33 E-3 (1) 1978 Urdiluted Release Volume = 7 E 9 mls.

(2) Mi = 1978 Undil. Act Nuclide i X 1 release rate i (fram Table L-1) 121000 ggm (dil rate)

Page 20 of 88 ST. WCIE PIXY CKMESTRY OPERATION HKCEIXJIK NO. C-200, R1WISION 10 OFFSITE DOSE CAZCUXA MNUAL 0 2.1 (continued)

Dose Calculations (continued)

~ St. effluents.

gaseous Lucie site uses the long tenn ground release model for all Only those radionuclides that apge~ in the gaseous effluent dose factor tables will be considered in any dose calculations. Radioiodines are defined as Iodine-131 and I-133 for application to S.T.S. ICO's. Other nuclides of Iodine may be included in dose calculations for ease of perforndzg, calculations, but their dose contribution does not have to be included in the SXS

?CO rex~reaents. Land Census information will apply to the calendar year following the year that the census was ta1cen in to avoid splitting quarters, etc.

2.2 De the Total and Dose tes for oble Gas Releases Establish'e ints for Ef u tors fram ncble gases in airborne releases to <500 @mern/yr total body and <3000 namby'yr skin. Technical Specification 3.3.3.10 recpxires that the gaseous radioactive effluent monitoring instrumentation be operable with al~trip setpoints set to ensure that these dose rate limits are not exceeded. 'Ihe results of the sampling and analysis program of Technical Specification Table 4.11-2 are used to demonstrate campliance with these limits.

'Ihe following calculation method is provided for detexndning the dose rates to the total body and skin fram noble gases in airborne releases. 'Ihe alarm'trip setpoixzts are based on the dose rate calculations. Ihe Technical Specification ZlD's apply to all airborne releases on the site but all releases may be treated as if

're based on Sections 5.1 and 5.2 of

~

discharged fram a single release point. Only those ncble gases appearing in Table G-2 will be consign@.

NUR13G-0133, calculation methods November 1978. Ihe equations are:

For ICBM, BODY Dose Rate:

n gevd9 EBS/ = $

3.

Ki (@Q) (Q 1xrl') i For KOZAL SKIN Dose Rate:

n 3.

[Li + 1 1 Mi] (QQ) (Q MZ) i

Page 22 of 88 ST. WCIE PLt&Z QiEHISTRY OPiXATING PROCECURE NO. C-200, REVISION 10 OFFSITE DOSE CAIlXJIATIONMMIUAL ODCM 2.2 (continued)

1. (continued)

%his value may be used in conjunction with the total ncible gas i

release rate (Q DVZ) to verify that the dose rate is within the allowable limits. To allow for any unexpected variability in the radionuclide distribution, a conservatism factor of 0.8 is introduced into the calculation. The simplified equation is:

m = <<f0.8+'Q) Z (Q Dor)i ~ gev59 To further simplify the determination, the historical annual average meteorological X/Q of 1.6 X 10 6 sec/m (Fram Table M-1) may be substituted into the equation. Also, the dose limit of mrem/yr may be substitut~ for ~. Malciag these substitutions yields a single cumulative (or gross) noble gas

'00 release rate limit,. 'Ihis value is:

Noble gas release rate limit = 3.5 X 105 uCi/sec As long as the noble gas release rates do not exceed this value (3.5 X 105 uCi/sec), no additional dose rate calculations are needed to verify c'ampliance with Tered.cal Specification 3.11.2.1.

2. Setpoint Determination To comply with Tech. Spec. 3.3.3.10, the alarm'trip setpoints are established to ensure that the noble gas releases do not exceed the value of 3.5 X 10 uCi/sec, which corvmpondsto a total body dose rate of 500 mrem/yr. 'lhe method that follows is a step-by-step procedure for establishiLng the setpoints. To allow for multiple sour'f releases fram different or common release points, the allowable operating setpoints will be contxolled administratively by allocating a percentage of the total allowable release to each of the release sources.

A. Deteanine (V) the maxiasxm volume release rate potential fram the in-plant procedures for the release scram unchm consideration. 'Ihe units of (V) are ft /min.

B. Solve for A, the activity concentration in uCi/cc that would produce the Y dose rate ?CO A= 3.5 X 105 uCi X

~M min X ft X 60 sec A = uCi/cc

Page 20 of 84 4'.

ST- LUCIE PLANT CHEMISTRY OPERATING PROCEDURE NO. C-200, REVISION 8 OFFSITE DOSE CALCULATION MANUAL (ODCM)

~

2 .2 (coutiznmd) m~A z.. M (continued)

~ c B. Salve for A, the activity ccncentzaticu in uCi/cc that would pzodu( the Y dose rate DD

'A=3.3X10 tCiX mlu X ft X 60sec WVWft~,2.8317 X 10"cc mbn A= lCf/cc C. Refer to the uCi/cc vs. cpm curve for the Release Scuzce's Gaseous EfQueut Mcaitor cpm viue (C), carzespcnding to the mtue of A above.

D. C is si.te.

~ 10(P. setpoint3 assumtng that them are zo other zalease scuzces cu the E. Obtain the curzant X allocated to this ze1ease sozrce from the geeous waste t)az)age(taut logs.

F. The Operating setpoint SP SP = (C) cpm X X allotted by in lant zoceduzes 100/'he total body dose is rrz)zn limiting than the calculated skein dose. (Refer to AppemKx C for a detailed evaluaticu.) Thezef(xef the skin dose zate calculaticus aza not mquizad if the siz(plified dose rate ca1culatiax is used (i.e., use of ~f to detezmfz)e please zate limits).

The actual releases af noble Gme ~

ca1culaticn process of the fallzwing Secticn (2.2.3) is to be used the alum limit of 3.5 X 10 ~/sec.

thder these ccnditL(xzs, a znc1ide~cli& evaluaticn is zeouized to evaluate if co)pliauce with the dose nzte lied.ts of Technical SpecKicaticn 3.11.2.1.

3. Total Body sud Bein Nuclide ~ific Dose Rate Chlculaticns ste~tep The fa13owing outline provides a Tech. Spec. 3.11.g.l. This ttathcd is cnly used vatue of 3.5 X 10 uCi/sec.

if the actual re1eases ~

explauaticn of 1xw'he total body dose rate is calculated cn a nuclid~~uclf.de basis to evatuate conpliauce with the A. 32m (X/0) value = sec/m sud ls the nust )dndtfug sectnr at the exclusfcu ates. ~gee 'lbble 8-1 for vabm nmd sector.)

B. Enter the zelease zate tu ft /mfn af the zn~se s(nzce aud ccamrt it to: = ( )ft X 2.8317 10 cc X ndu Idxl ft (0 sec cc/sec voice zeleas rate

Page 25 of 88 ST. IIJCIE PUTZ CHEMISTRY OPERA%'ING HKCEIX3RE NO. C-200, REVISION 10 OFFSITE DOSE CAICUIATXON MANUAL ODCM 2.3 Determin'he Radioiodine & Particulate Dose Rate to Gaseous Releases Discussion Tech. Spec. 3.11.2.1 limits the dose rate from I-131, I-133, tritium and all 'radionuclides in particulate form with half lives >eight days to <1500 ~yr to any organ. %he following calculation methcd is provided for,detezzdxLing the dose rate fram radioiodines (see 2.1) and particulates and is based on Section 5.2.1 and 5.2.1.1 through 5.2.1.3 in NUREG-0133, Navember 1978. %he Infant is the contmlling age graup in the inhalation, grmuxl plane, and caw/goat milk pathways, which are the only pathways considered for releases. 'Ihe long term (X/Q)D (depleted) and (D/Q) values are based on historical MFZ data prior to implementing Appendix I. Only those nuclides that appear on their respective table will be considered.

'%he equations are:

For Inhalation Pathwa n

exclud '-3:

DRI&8DP = $

3.

Rg (X/Q) D (Q Mr) i For Ground Plane:

n DRI&8DP = $ Pi (D/Q) (Q DCT) i For Grass-Caw Goat-Milk:

n DRI&8DBZ

= ~ RQ (D/Q) (Q ~) i Rev@9 For Tritium Releases Inhalation & Grass-Caw Goat-Milk:

H3T 0-3T ( /Q)D (Q ~)H-3 For Total Dose Rate fram I & 8DP and H-3 To An Infant DRT = Z [DRI&8D&Z + DRH 3T~

• Normally should be PiT, but RiT values are the same, thus use tables in Appendix A.

~

t V 7

4