ML17221A371

Combined Semiannual Radioactive Effluent Release Rept for Jan-June 1987. W/870831 Ltr

ML17221A371
Person / Time
Site:	Saint Lucie
Issue date:	06/30/1987
From:	Woody C FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
L-87-356, NUDOCS 8709080078
Download: ML17221A371 (59)

Text

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REGULATO INFORMATION DISTRIBUTION STEM ACCESSION NBR 8709080078 DOC. DATE'7/06/30 NOTARIZED: NO DOCKET 0 FAC IL: 50-335 St. Lucie Planti Unit 1> Florida PoUJer 8c Light Co. 05000335 50-389 St. Lucie Planti Unit 2i. Florida Power 8c Light Co. 05000389 AUTH. NAME AUTHOR AFFILIATION WOODY> C. O. Florida Poeer 8c Light Co.

RECIP. NAME RECIPIENT AFFILIATION

SUBJECT:

"Combined Semiannual Radioactive Effluent Release Rept for Jan-June 1987," W/870831 ltr.

DISTRIBUTION CODE: IE4SD COPIES RECEIVED: LTR ( ENCL TITLE: 50. 36a(a) (2) Semiannual Effluent Release Reports g SIZE: 3 NOTES:

RECIP IENT COPIES RECIPIENT COP IES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 0 PD2-2 PD 5 5 TOUR IGNYs E 1 INTERNAL: AEOD/DOA 1 AEOD/DSP/TPAB 1 1 ARM TECH *DV 1 NRR/DEST/PSB 1 NRR/PMAS/ILRB 1 1 RE F 01 1 1 RGN2 FILE 02 1 1 2/DRSS/EPRPB 1 1 EXTERNAL'NL TICHLERe J 1 LPDR 1 1 NRC PDR 1 1 TOTAL NUMBER OF COP IES REQUIRED: LTTR 22 ENCL 21

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P. O. Y 14000, JUNO BEACH, FL 33408-0420 Ol/pi AUGUST 3 g f987 L-87-356 U. S. Nuclear Regulatory Commission Document Control Desk 'ttn:

Washington, D. C. 20555 Gent I emen:

Re: St. Lucie Units I 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 I, l987 through June 30, l987 for St. Lucie Units I and 2, as required by Technical Specification 6.9. I.7.

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

Very truly yours,

. O. Woody roup Vice President Nuclear Energy COW/GRM/gp Attachment, cc: Dr. J. Nelson Grace, Regional Administrator, Region II, USNRC R. J. Crlenjak, Senior Resident Inspector, USNRC, St. Lucie Plant an FPL Group company GR M5/0 I 4/ I

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FLORIDA PONER 8c LIGHT COMPANY ST. LUCIE PLANT UNITS NO i 8c 2 LICENSE NO.S DPR-b7 5 NPF-)b COMBINED SENI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD JANUARY i~ )987 THROUGH JUNE 38~ )987 709080078 870b30 5000335

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TABLE OF CONTENTS DESCRIPTION EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION OFFSITE DOSE CALCULATION MANUAL REVISIONS . 7 SOLID WASTE AND IRRADIATEK;;'UEL SHIPMENTS.......... .. ~ ~ 7 PROCESS CONTROL PROBRAM REVISIONS... 7 LIQUID EFFLUENT:

SUMMATION OF ALL RELEASES Zc NUCLIDE SUMMATION BY QUARTER U NIT 8 1 ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ s ~ ~ ~ ~ or ~ s ~ asa ~ a ~ a ~ o ~ s ~ ~ s ~ ~ ~ 8 UNIT 5 > ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 11 GASEOUS EFFLUENT:

SUMMATION OF ALL RELEASES 5 NUCLIDE SUMMATION BY QUARTER U NIT 51 ~ a ~ asasasssssssessososoos ~ oss ~ asaearorse ~ sr 14 U NIT 8 2 ~ ~ ~ ~ ~ ~ ~ r ~ ~ ~ s e s ~ a a e s ~ r s e s a ~ a e ~ ~ ~ ~ ~ ~ ~ ~ e s rr ~ ~ ~ 16 SOLID NASTE SHIPMENT SUMMATION ... ~ ... ~ 18 OFFSITE DOSE CALCULATION MANUAL PAGE REVISIONS ATTACHMENT- A PROCESS CONTROL PROBRAM PROCEDURE PAGE REVISIONS. .. ATTACHMENT- B

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EFFLUENT AND WASTE DISPOSAL SUPPLENENTAL 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 1$ CFR Part 2$

Appendix B, Table XI, 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 PUBLXC 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 <= 18 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 Bases: <= 5$ $ mrems/yr to the total body and

<= 388$ mrems/yr to the skin, and For Iodine-131, Iodine-133, Tritium, and all radionuclides N

in particulate form with half-lives greater than 8 days:

<= 158$ mrems/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 following:

During any calendar quarter, to <~ 5 mrads for gamma radiation,and 1$ mrads for beta radiation and, during any calendar year to

<~ 1$ mrads for gamma radiation and <= 2$ mrads 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 followings 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-annua) 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 be on. The STS LCO dose limits are therefore included in Item bf the report, for information only.

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EFFLUENT AND MASTE DISPOSAL SUPPLENENTAL INFORMATION (Continued)

2. Maximum Permissible Concentrations Mater: As per 1$ CFR 2$ Part 2$ , 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 Mhere alpha, tritium, and named nuclides are shown as zero 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 ef fluent.

A summary of liquid effluent accounting methods is described in Table 3.1. Avgas A summary of gaseous effluent accounting methods is described in Table 3.2.

4.1 Estimate of Errors L!QUID GASEOUS Error Topic  % Max ~ % Avgs % Max o%

Release Point Nixing 2 5 NA NA Sampling 1 5 2 5 Sample Preparation 1 5 5 Sample Anal ysi s 3 1$ 3 1$

Release Volume 2 5 4 15 Total % 9 The predictability of error for radioactive releases can only be applied to nuclides that are predominant in sample spectrums.

Nuc)ides 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 NASTE 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-98~

Composite 5 Fe-55 C S.

Continuous Daily Principal Gamma Emitters Releases Grab 8c 1-131 for p.h. a.

Samples 4/M Composite Analysis Dissolved 5 Entrained Gases One Batch/ Month p.h.a.

Tritium Composite Monthly L S Alpha Composite Monthly 6 F.P.

Sr-89, Sr-9$ , 5 Fe-55 Composite Quarterly C S 1-Boric Acid Evaporator Condensate is normal)y recovered to the Primary Mater 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. -Chemi cal Separation G F P -Gas Flow Proportional Counting 4/M-Four per Month

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EFFLUENT AND NASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued>

4. Measurements and Approximations of Total Radioactivity (Continued>

4.1 (Continued)

B. (Continued)

TABLE 3 2 RADIOACTIVE GASEOUS MASTE SANPLINB AND ANALYSIS Gaseous Sampling Type of Nethod of Source Frequency Analysis Analysis Waste Gas Decay Tank Each Batch Principal Gamma Emitters p. h.a.

Releases Containment Principal Gamma Emitters pshsae Purge Each Purge Tritium L S.

Releases Principal Gamma Emitters p.h.a.

Tritium L. S.

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FLORIDA POSER 4 LIGHT COMPANY ST. LUCIS PLANT UNIT NO. 1 SEMIANNUAL REPORT JANUARY 1, 1887 THROUGH JUNE 30, 1987 EFFLUENT AND HASTE Dl'SPOSAL SUPPLEMENTAL INFORMATION (CONT2NUED)

5. BATCH RELEASES AND UNPLANNED RELEASES LIQUIDS FOR -'T. LUC2E PLANT UNIT NO. 1 A. NUMBER OF BATCH RELEASES: ~ -,29;, g B. TOTAL TIME PERIOD OF BATCH RELEASES: 161 75. MINUTES C. MAXl'MUM T2ME PER2OD FOR A BATCH RELEASE: 870. MINUTES D. AVERAGE Tl'ME PERIOD FOR A BATCH RELEASE: 568. M2NUTES E. MINIMUM TIME PERIOD FOR A BATCH RELEASE: 407. MINUTES F. AVERAGE STREAM FLOP DURING REPORT2NG PER2'OD INTO A FLOWING STREAM: 868441. G.P.M.

6. GASEOUS FOR: ST. LUCIS PLANT UNl'T NO. 1 A. NUMBER OF BATCH RELEASES: 11. 0 B. TOTAL Tl'ME PERIOD OF BATCH RELEASES: 3867. MINUTES C. MAX2MUM T2ME PERIOD FOR A BATCH RELEASE: 600. MINUTES D. AVERAGE TIME PER2'OD FOR A BATCH RELEASE: 352. MINUTES E. M2NIMUM TIME PER1'OD FOR A BATCH RELEASE: 180. MINUTES UNPLANNED RELEASES LIQUIDS FOR -'T. LUCIS PLANT UNIT NO. I A. NUMBER OF RELEASES: 0.

B. TOTAL ACTIV1'TY RELEASED: 0. CURIES GASEOUS FOR: ST. LUCIS PLANT UNIT NO.

A. NUMBER OF RELEASES: 0.

8, TOTAL ACTIVITY RZLZASZD: 0. CURIES SEE ATTACHMENTS (IF APPLICABLE) FOR:

A. A DESCRIPTION OF THE EVENT AND EQUIPMENT 2NVOLVED.

B. CAUSE(S) FOR THE UNPLANNED RELEASE.

C. ACTIONS TAEEN TO PREVENT A RECURRENCE.

D. CONSEQUENCES OF THE UNPLANNED RELEASE.

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FLORIDA POSER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 2 SEMIANNUAL REPORT JANUARY 1> 1987 THROUGH JUNE 80, 1987 EFFLUENT AND HASTE DISPOSAL - SUPPLEMENTAL INFORMATION (CONTINUED)

5. BATCH RELEASES AND UNPLANNED RELEASES LIQUIDS FOR: ST. LUCIS PLANT UNIT NO. 2 A. NUMBER OF BATCH RELEASES: <gag B. TOTAL TIME PER1OD OF BATCH RELEASES: 261 75. MINUTES C. MAXIMUM TIME PER1OD FOR A BATCH RELEASE: 870. MINUTES D. AVERAGE T1ME PERIOD FOR A BATCH RELEASE: 568. MINUTES E. M1N1MUM TIME PERIOD FOR A BATCH RELEASE: 407. MINUTES F. AVERAGE STREAM FLOP DURl'NG REPORT1NG PERIOD 1NTO A FLOWING STREAM: 868441. G.P.M.

6. GASEOUS FOR: ST. LUCIS PLANT UNIT NO. 2 A. NUMBER OF BATCH RELEASES: 57. 0 B. TOTAL T1ME PER1'OD OF BATCH RELEASES: 14408. MINUTES C. MAXIMUM Tl'ME PER1OD FOR A BATCH RELEASE: 4920. MINUTES D. AVERAGE T1ME PER1'OD FOR A BATCH RELEASE: 258. MINUTES E. MlN1'MUM TIME PERIOD FOR A BATCH RELEASE: l5. MINUTES UNPLANNED RELEASES LIQUIDS FOR -'T. LUCIS PLANT UNIT NO. 2 A. NUMBER OF RELEASES: 0.

B. TOTAL ACTIVITY 0. CUR1ES RELEASED-'ASEOUS FOR: ST. LUCIS PLANT UNIT NO. 2 A. NUMBER OF RELEASES: 0.

B. TOTAL ACTIV1TY RELEASED: 0. CURIES SEE ATTACHMENTS (IF APPLICABLE) FOR:

A. A DESCRIPT1'ON OF THE EVENT AND EQUIPMENT INVOLVED.

B. CAUSE(S) FOR THE UNPLANNED RELEASE.

C., ACTIONS TAEEN TO PREVENT A RECURRENCE.

D. CONSEQUENCES OF THE UNPLANNED RELEASE.

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FLORIDA PONER 8c LIGHT COMPANY ST. LUCIE PLANTS UNITS 1 8c 2 SEMIANNUAL REPORT JANUARY 1, 1987 THROUGH JUNE 38~ 1987 EFFLUENT AND NASTE 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 January report.

8. Offsite Dose Calculation Manual Revisions (ODCM):

The af fected pages for Revision 88 to C-288 (ODCM) are included as Attachment-A to this report. The reason for the change was due to an NRC Audit of the ODCM where a deficiency was noted. The ODCM reference to R8 CFR 198 Dose Evaluation had excluded exceeding the Annual Dose Limit L. C. O. s as a requi rement to perf orm 48 CFR 198.

dose calculations. This Revision to the ODCM corrects the deficiency and the ODCM is now correct in its reference to the Plant Technical Specification requirements.

This item may also be referenced by letter dated March 27, 19B7 (C. O. Moody to U.S. Nuclear Regulatory Commission) as the Florida Power Sc Light Company response to the NRC Audit of the ODCM and the Process Control Program.

This Revision to the ODCM was administrative in nature and did not change Dose Methodology.

9. Solid Waste,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.

18. Process Control Program (PCP) Revisions:

The PCP was revised during the reporting interval. The affected pages are included as Attachment B to this report. These changes were administrative in nature and were made as a result of a US N.R.C. review of the PCP.

FLOR1DA POSER & LIGHT COMPANY ST. LUCIS PLANT UNIT NO. 1 SEMIANNUAL REPORT JANUARY 1, 188 7 THROUGH JUNE 30, 198 7 TABLE 3. 3-1 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER ¹1 QUARTER ¹2 A. FISSION AND ACT1 VAT1'ON PRODUCTS

1. TOTAL RELEASE (NOT INCLUDl'NG TRITIUM, GASES, ALPHA) 2. 61E-01 7.43E-02

2. A VERA GE DILUTED CONCENTRA TION DURING PERIOD UC1/ML 7. ZZE-10 1.52E-10 B. TRITIUM

1. TOTAL RELEASE 8.21E Ol 4.54E 01

2. A VERA GE Dl'LUTED CONCENTRA Tl'ON DUR1 NG PERIOD UC1 /ML Z. 55E-07 8. 24E-08 C. D1SSOLVED AND ENTRAINED GASES

1. TOTAL RELEASE 1. 04E 01 5. 76E-02 Z. A VERA GE Dl'LUTED CONCENTRA Tl ON DUR1 NG PER1'OD UCI/ML 2. 87E-08 1. 1 7E-10 D. GROSS ALPHA RADIOACT1 VITY

1. TOTAL RELEASE 0. OOE-01 0. OOE-01 E. VOLUME OF HASTE RELEASED (PRIOR TO DILUTION) Ll'TERS l. 78E 07 2.88E 07 F. VOLUME OF D1LUTION h'ATER USED DURING REPORT1NG PERIOD LITERS 3. 61E 11 4.81E 11

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0 FLORIDA POSER & LIGHT COMPANY ST. LUC1'E PLANT UNIT NO. I SEM1 ANNUAL REPORT JANUARY I, 1987 THROUGH JUNE 80, 1987 TABLE 8. 4-1 L1QU1 D EFFLUENTS NUCL1'DES CONTINUOUS MODE BATCH MODE RELEASED UNIT QTR. ¹I QTR. ¹2 QTR. ¹I QTR. ¹2 I-131 C1 07E-02 4. ZIE-04 1. 13E-OZ 1. I 7E-03 I-132 CI 0. OOE-01 0. OOE-OI 1.14E-03 0. OOE-01 I-133 C1 3. 09E-02 0. OOE-OI 1.12E-03 7. OOE-05 I-135 CI 0. OOE-01 0. OOE-01 3. 91E-05 0. OOE-01 NA-24 CI 0. OOE-01 0. OOE-01 2. 50E-04 0. OOE-01 CR-51 CI 0. OOE-01 D. DOS-01 4. I 7E-02 I . 15E-OZ MN-54 CI 0. OOE-Ol 0. ODE-Ol 1. 72E-08 5. 96E-04 FE-55 CI 0. OOE-01 0. OOE-01 4. 71E-03 5. I OE-08 CO-57 CI 0. OOE-01 0. OOE-01 5. 64E-05 0. OOE-01 CO-58 CI 0. OOE-01 0. OOE-01 5. 45E-02 1. 09E-02 FE-59 CI 0. OOE-01 0. OOE-Ol 7.68E-04 1.99E-04 CO-60 CI 1.25E-05 0. OOE-Dl Z. 98E-02 1.66E-OZ AG-110 C1 0. DOS-01 0. OOE-01 1. 57E-03 8.99E-04 SN-113 CI 0. OOE-01 0. OOE-01 3. 26E-04 1.11E-04 SB-122 CI 0. OOE-01 0. OOE-Ol 0. OOE-01 1.38E-05 SB-124 C1 0. OOE-01 0. OOE-01 1. 16E-02 1. 72E-03 RB-88 CI 0. OOE-01 0. OOE-Ol 6. 20E-04 0. ODE-01 SR-89 CI 0. OOE-01 0. OOE-01 9. I OE-D5 8. 75E-04 SR-90 CI 0. OOE-01 0. OOE-01 5. 70E-05 0. OOE-Ol Y-90 CI 0. OOE-01 0. OOE-01 5. 70E-05 0. OOE-01 ZR-95 CI 0. OOE-Ol 0. OOE-01 8. 31E-03 Z. 91E-03 NB-95 NB-97 TC-99M CI'.

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0. OOE-01 RU-103 CI 0. OOE-01 0. OOE-01 2. 38E-03 5. 89E-04 SB-125 CI 0. OOE-01 0. OOE-01 1.60E-OZ 7. 75E-03 CS-184 C1 1. 40E-03 4. 70E-04 2. 78E-03 1.81E-03 CS-136 C1 0. OOE-01 0. OOE-01 6. I IE-05 O.OOE-OI CS-137 CI 3.93E-03 1.10E-03 5. 18E-03 3.58E-03 CS-138 0. OOE-01 O.DOE-OI 2. 84E-04 I . 81E-05

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FLORIDA POWER 4 LIGHT COMPANY ST. LUCIS PLANT UNIT NO.

SEMIANNUAL REPORT JANUARY 1987 THROUGH JUNE 30, 1987 TABLE 3. 4-1 CONTINUED LIQUID EFFLUENTS NUCLIDES CONTINUOUS MODE BATCH MODE RELEASED UNIT QTR. ¹1 QTR. ¹2 QTR. ¹1 QTR. ¹2 liA-140 CI 0. OOE-01 0. OOE-01 1.96E-03 3. 47E-04 CE-141 CI 0. OOE-01 0. OOE-01 3. 31E-04 9. 49E-05 CE-144 CI 0. OOE-01 0. OOE-01 Z. 34E-04 2. 54E-04 TE-129 CI 0. OOE-01 0. OOE-01 9. 26E-04 0. OOE-01 TE-129M CI 0. OOE-01, 0. OOE-01 4.88E-04 0. OOE-01 TOTAL FOR PERIOD 4. 69E-02 2. OOE-03 2. 14E-01 7. 23E-02 AR-41 CI 0. OOE-01 0. OOE-01 8. 93E-05 0. OOE-01 ER-85M CI 0. OOE-01 0. OOE-01 4. 55E-04 0. OOE-01 XE-131M CI 0. OOE-01 0. OOE-01 3. 13E-02 0. OOE-01 XE-138 CI 1.45E-03 0. OOE-01 1.01E 01 5. 55E-02 XE-133M CI 0. OOE-01 0. OOE-01 1. 26E-Ol Z, 26E-04 XE-135 CI 0. OOE-01 0. OOE-01 8. 71E-OZ 1. 91E-03 TOTAL FOR PERIOD 1. 45E-03 0. OOE-01 1. 04E 01 5. 76E-OZ 10

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FLORIDA POSER & LIGHT COMPANY ST. LUCIS PLANT UNIT NO. 2 SEMIANNUAL REPORT JANUARY 1, 198 7 THROUGH JUNE 80, 198 7 TABLE S. 8-2 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER ¹1 QUARTER ¹2 A. FISSION AND ACTIVATION PRODUCTS TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) 2. 14E-01 7. ZBE-02

2. A VERA GE DILUTED CONCENTRA TION DURING PERIOD UCI/ML 5.92E-IO 1. 47E-10 B. TRITIUM

1. TOTAL RELEASE 9.21E 01 4.54E 01

2. A VERAGE DILUTED CONCENTRA TION DURING PERIOD UCI'/ML 2.55E-07 9.24E-08 C. DISSOLVED AND ENTRAINED GASES I . TOTAL RELEASE 1. 04E 01 5. 76E-02

2. A VERA GE DILUTED CONCENTRA TION DURING PERIOD UC1/ML 2. 8 7E-08 1. I 7E-10 D. GROSS ALPHA RADIOACTIVITY

1. TOTAL RELEASE 0. 00E-01 0. 00E-01 E. VOLUME OF HASTE RELEASED (PRIOR TO DILUTION) LITERS 2. 14E 06 1.48E 06 F. VOLUME OF DILUTION PATER USED DURING REPORTING PERIOD LITERS 8. 61E 11 4.91E 11 11

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FLORIDA POWER 4 LIGHT COMPANY ST. LUCIS PLANT UNIT NO. 2 SEM1 ANNUAL REPORT JANUARY I, 1987 THROUGH JUNE 30, 1987 TABLE 3. 4-2 LIQUID EFFLUENTS NUCLIDES CONTINUOUS MODE BATCH MODE RELEASED UNIT QTR. ¹I QTR. ¹2 QTR. ¹I QTR. ¹2 I-131 CI 0. ODE-01 0. OOE-01 1.13E-OZ 1. I 7E-03 I-132 CI 0. OOE-OI 0. OOE-01 1.14E-03 0. OOE-01 I-133 CI 0. OOE-01 0. OOE-01 I.IZE-03 7. OOE-05 I-135 C'1'I 0. OOE-01 0. OOE-01 3. 91E-05 0. OOE-01 NA-24 0. OOE-01 0. OOE-01 Z. 5DE-04 0. OOE-01 CR-51 CI 0. OOE-01 D. ODE-01 4. I 7E-02 1. 15E-OZ MN-54 CI 0. OOE-01 0, OOE-Ol 1. 7ZE-03 5.96E-04 FE-55 CI 0. OOE-OI 0. OOE-01 4. 71E-03 5.10E-03 CO-5 7 CI 0. OOE-01 0. OOE-01 5. 64E-05 0. OOE-01 CO-58 CI 0. OOE-01 0. OOE-01 5. 45E-OZ 1.09E-02 FE-59 CI 0. OOE-Ol 0. OOE-01 7. 68E-04 1.99E-04 CO-60 CI 0. OOE-01 0. OOE-01 2. 98E-02 1. 66E-OZ AG-110 CI 0. OOE-01 0. DOE-01 1. 57E-03 8. 99E-04 SN-113 CI 0, OOE-01 0. OOE-01 3. Z6E-04 1.11E-04 SB-122 CI 0. OOE" 01 0. OOE-01 0. OOE-OI 1.33E-05 SB-124 CI'I 0. OOE-01 0. OOE-01 1.16E-OZ 1. 72E-03 RB-88 0. OOE-01 0. OOE-01 6.20E-04 0. OOE-01 SR-89 C'I 0. OOE-OI 0. OOE-OI 9.10E-05 8. 75E-04 SR-9D CI 0. OOE-01 0. OOE-01 5. 70E-05 0. OOE-Dl Y-90 CI 0, OOE-Ol 0. OOE-01 5. 70E-05 0. OOE-OI ZR-95 CI 0. OOE-01 0. OOE-01 8. 31E-03 2. 91E-03 NB-95 CI 0. OOE-01 0. OOE-OI I . Z6E-OZ 4. 96E-03 NB-97 CI 0. OOE-OI 0. OOE-01 9. 08E-04 2. 54E-04 TC-99M CI 0. OOE-OI 0. OOE-01 1. 07E-04 0. OOE-OI RU-103 CI 0. OOE-01 0. OOE-01 Z. 38E-03 5. 89E-04 SB-125 CI 0. OOE-01 0. OOE-Ol I . 60E-02 7. 75E-03 CS-134 CI 0. OOE-OI 0. OOE-01 2. 78E-03 1. 81E-03 CS-136 C1'I 0. OOE-01 0. OOE-01 6. IIE-05 0. OOE-01 CS-137 0. OOE-OI 0. OOE-01 5. 13E-03 3. 58E-03 CS-138 CI 0. DOE-01 0. OOE-01 2. 84E-04 1. 81E-05 12

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o t FLORIDA POSER d'r LIGHT COMPANY ST. LUCIS PLANT UNIT NO. 2 SEMIANNUAL REPORT JANUARY I, 1987 THROUGH JUNE 30, 1987 TABLE 3. 4-2 CONTINUED LIQUID EFFLUENTS NUCLIDES CONTINUOUS MODE BATCH MODE RELEASED UNIT QTR. ¹I QTR. ¹2 QTR. ¹I QTR. ¹2 LA-140 CI 0. ODE-01 0. OOS-01 1.96E-03 3. 47E-04 CS-141 CI 0. OOE-01 0. OOE-Ol 3. 31S-04 9.49E-05 CE-144 CI 0. OOE-01 0. OOE-Ol 2. 34E-04 2.54E-04 TE-129 CI 0. OOE-01 0. OOE-01 9. 26E-04 0. OOE-01 TE-129M CI 0. OOE-01 0. OOE-01 4. 88E-04 0. OOS-01 TOTAL FOR PERIOD O.OOE-OI O.OOE-OI 2.14E-OI 7.23E-02 AR-41 CI 0. OOE-01 0. OOE-01 8. 93E-05 0. OOE-01 ER-85M CI 0. OOE-01 0. OOE-01 4. 55E-04 0. OOE-Ol XS-131M CI 0. OOE-01 0, OOE-01 3. 13E-02 0. OOE-01 XE-133 CI 0. OOE-01 0, DOE-01 I.OIE Ol 5. 55E-OZ XE-133M CI 0. OOE-01 0. OOE-01 1. 26S-OI 2. Z6E-04 XE-135 CI 0. OOE-01 0. OOE-Ol 8. 71E-02 1. 91E-03 TOTAL FOR PERIOD 0. OOE-01 0. OOE-01 1. 04E 01 5. 76E-02 13

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FLORIDA POSER & LIGHT COMPANY ST. LUClZ PLANT UNIT NO. 1 SEMl ANNUAL REPORT JANUARY 1, 198 7 THROUGH JUNE 80, 198 7 TABLE 3. 6-1 GASEOUS EFFLUENTS SUMMATlON OF ALL RELEASES NUCLlDES RELEASED UNl T QUARTER ¹1 QUARTER ¹2 A. FlSSION AND ACTIVATION GASES

1. TOTAL RELEASE CI 8.89E 08 5. 08E 02

2. AVERAGE RELEASE RATE FOR PERlOD UCI/SEC 4. 35E 02 6.46E 01 B. l'ODINSS

1. TOTAL IODINE-131 CI 3. 31E-02 6. 58E-04

2. AVERAGE RELEASE RATS FOR PSRl'OD UCI/SEC 4. 25E-08 8. 80E-05 C. PARTICUliATES

1. PARTlCULATES T-1/2 > 8 DAYS 1. 74E-05 7. 57E-07

2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 2. 24E-06 9.68E-08 8, GROSS ALPHA RADIOACTIVITY 8. 85E-09 1.99E-07 D. TRITIUM

1. TOTAli RELEASE CI 1.98E 00 1.30E 01

2. AVERAGE RELEASE RATS FOR PERl OD UCI'/SEC 2. 55E-01 1.65E 00 14

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FLORIDA POHER Zi LIGHT COMPANY ST. LUC1E PLANT UNIT NO.

SEMIANNUAL REPORT JANUARY 1, 198 7 THROUGH JUNE 30, 198 7 TABLE 3. 7-1 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES NUCLIDES CONTINUOUS MODE BATCH MODE RELEASED UN1 T QTR. ¹1 QTR, ¹2 QTR. ¹1 QTR. ¹2 NOBLE GASES AR-41 CI 0. OOE-01 0. OOE-Ol 9. 14E-01 0. OOE-01 ER-85M CI 4.29E Ol 0. OOE-01 9. 45E-Ol 0. OOE-01 ER-87 CI 2. 41E 01 0. OOE-01 0. OOE-01 0. OOE-Ol ER-88 CI 7.90E 01 0. OOE-Ol 3.13E-Ol 0. OOE-01 XE-131M CI 0. OOE-01 0. OOE-01 9.53E-Ol 0, OOE-01 XE-133 CI Z,34E 03 4. 37E 02 4.44E 02 1. 01E 01 CI 2. 75E 01 0. OOE-01 8.20E 00 1. 70E-01 XE-135 CI 3.89E 02 6.02E 01 2. 73E 01 1. 03E-02 TOTAL FOR PERIOD CI 2,90E 03 4.98E OZ 4.82E OZ 1.02E 01 2, IODINE I-131 CI 3. 31E-OZ 6. 53E-04 I-132 CI 1. 03E-Ol 9. 24E-05 I-133 CI 3.29E-02 1.38E-03 I-135 CI 4.66E-02 O.OOE-OI TOTAL FOR PERIOD CI 2.16E-01 2.12E-03

3. PARTICULATE RB-88 CI 1.56E 00 0. OOE-01 SR-89 CI 3. 76E-06 7. 57E-07 CS-137 CI 1. 36E-05 0. OOE-01 TOTAL FOR PERIOD CI 1.56E 00 7.57E-07 15

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FLORIDA POSER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 2 SEMIANNUAL REPORT JANUARY 1, 1987 THROUGH JUNE 80, 1987 TABLE 8. 6-2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER ¹I QUARTER ¹Z A. FISSION AND ACTIVATION GASES

1. TOTAL REliEASE 2.66E 08 8.17E 08

2. AVERAGE REliEASE RATE FOR PERIOD UCI/SEC 8. 42E 02 4. 08E OZ B. IODINES

1. TOTAL IOD1 NE-131 7. 44E-03 1.49E-OZ

2. AVERAGE RELEASE RATE FOR PERIOD UCIJ/'SEC 9. 56E-04 1.90E-08 C. PARTICULATES

1. PART1CULATES T-1//2 > 8 DAYS CI 0. OOE-01 8. 05E-05 Z. AVERAGE RELEASE RATE FOR PERIOD UCI//SEC 0. OOE-Ol 3.88E-06

8. GROSS ALPHA RADIOACTIVITY CI 9, 80E-08 1.80E-07 D. TRITIUM TOTAL RELEASE CI 2.Z1E 01 2.88E 01

2. AVERAGE RELEASE RATE FOR PERIOD UCI/J"SEC Z.84E 00 3. 08E 00 16

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FLORIDA POHER 4 LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 2 SEMIANNUAL REPORT JANUARY 1, 1987 THROUGH JUNE 30, 1987 TABLE 8. 7-Z GASEOUS EFFLUENTS - GROUND LEVEL RELEASES NUCLIDES CONTINUOUS MODE BATCH MODE RELEASED UNIT QTR. ¹1 QTR. ¹2 QTR, ¹1 QTR. ¹2

1. NOBLE GASES AR-41 CI 0, OOE-01 0. OOE-.01 1.99E 00 1.11E 00 ER-85 CI 0. ODE-01 0. OOE-Ol 3, 67E-01 1.64E DO ER-85M CI 2. 01E 01 1.98E 01 6. 5ZE-02 4. 09E-01 ER-87 CI 1.Z6E 00 0. OOE-01 0. OOE-01 0. DOE-01 ER-88 CI 1.56E 01 2.00E 01 1. 89E-02 1. 18E-01 XE-131M CI 0. OOE-01 0. OOE-01 1.84E 00 8.54E 00 XE-188 CI 2.26E 08 2.20E 08 7.82E 01 6.42E 02 XE-188M CI 1.04E 01 1.48E 01 8. 68E-01 8.12E 00 XE-135 CI 2.68E 02 2. 48E 02 1.18E 00 1. 03E 01 FOR 'OTAL PERIOD CI 2.58E 08 2.50E 08 7.95E 01 6.67E 02 2, IODINE I-131 CI 7.44E-08 1.49E-02 I-182 CI 5.44E-04 5.48E-04 I-188 CI 6. 68E-03 1. 89E-02 TOTAL FOR PERIOD CI 1. 47E-02 8. 48E-02

8. PARTICULATE RB-88 CI 8.24E 00 0. OOE-01 SR-89 CI 0. OOE-OI 8. 05E-05 TOTAL FOR PERIOD CI 8,24E 00 8. 05E-05 17

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FLORIDA POWER 8( LIGHT COMPANY ST. LUCIE PLANT SEMIANNUAL REPORT JANUARY 1, 1987 THROUGH JUN 30, 1987 UNITS 1 AND 2, TABLE A. Solid Waste Shipped Off-Site for Burial or Disposal

1. TYPE OF WASTE UNIT 6 MONTH PERIOD ERROR%

a. Spent resin, M<<3 2. 002 E+1 process f ilters Ci 6. 516 E+2 2 0 E+1

~

b. Dry Compressible M<<3 0 Waste Ci 0

c. Irradiated M<<3 0 Components Ci 0

d. Other 1.Sol idified Oil M<<3 2. 334 E+1 Ci 1. 08 E-4 2.0 E+1

2. Sol i di f i ed STP4 M<< 3 5. 834 E+1 and Tank Sludge Ci 1 70

~ E-2 2. 0 E+1

3. Solidi% i ed Tank M<<3 5. 83 E+0 Sludge Ci 4. 72 E-1 2. 0 E+1

4. Non-compressible M<<3 1.377 E+1 Metal (Note 5) Ci 1. 43 E-1 2 ~ 0 E+1 STP, Sewage Treatment Pl ant 2 ~ ESTIMATE OF MAJOR NUCLIDE COMPOSITION (BY TYPE OF WASTE)

Category Nuclide a ~ 131 I 2 89

~ E+1 137 Cs 2. 14 E+1 S8 Co 1. 56 E+1 60 Co 1. 10 E+1 134 Cs 9. 10 E+0 51 Cr 3 30

~ E+0 S5 Fe 2. 30 E+0 95 Nb 2. 10 E+0 63 Ni 2. 00 E+0 54 Mn 1. 80 E+0 95 Zr 1. 30 E+0

b. NA C ~ NA NA 18

d t

lh '

Table 3.9 Continued:

60 Co 4.29 E+1 3 H 4. 04 E+1 55 Fe 1.07 E+1 137 Cs 1. 80 E+0 54 Mn 1.00 E+0 63 Ni 8. 00 E-1 58 Co 7. 00 E-1 134 Cs 7.00 E-1 3 ~ SOLID WASTE DISPOSITION Number of Shipments Node of Transportation Destination 14 Sole Use Truck Barnwell, SC 2 Sole Use Truck Richland, WA B. Irradi ated Fuel Shi pments Number of Shipments Node of Transportation Destination 0 NA NA- Not App1 i cab 1 e 19

Table 3ta (Cont.)

Kaste Total Total Pr incipal Type of Cateaor y Type of Solidification Class Volume Curies Radionuclides Haste Rea Guide Container Agent Cubic ft Note i Notes i8 2 Note 3 i2X Note 4 Class A 824 i.08e-4 na Solidified Non-specification Cement Oil Strong tight package Class A 2060 i.70e-2 na STP 8 Tank Non-specification Cement Sludge i.d Strong tight package Class A 206 4.72e-i na Solidified NRC Certified LSA Cement Tank Sludge i.d > Type A Class A 486.4 i.43e-i na Non-Com- Non-specification None pressible i.d Stong tight package eeete[Note5)

Class B 33.9i Ni63 Sr99, PIIH ion NRC Certified LSA None Ce13 Exchange i.a > Type A Resin Class C 202 560.57 Co60, Ni63. PNR ion i.a Sr90, Csl37 Pu24i, THU; exchange Sum of Nuc- resin NRC Certified LSA None li es with > Type A Ti 2<5yr Class C Co60, Ni63, PtrR Pu24i, THU, Process NRC Certified None Sum of Nuc- Filters i.a Type B li es with Ti 2<5yr

FLORIDA POWER AND LIGHT CONPANY ST LUCIE PLANT

~

SENIANNUAL REPORT JANUARY 1, 1987 THROUGH JUNE 30, 1987 UNITS 1 AND 2 TABLE 3.9 (CONT.)

SOLID WASTE SUPPLENENT Note 1: The total curie quantity and radi onucl i de composi ti on of solid waste shipped from the St. Lucie Unit 1 2 are 8<

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 determi nati ons.

C'he most frequently usedtechniques 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 reasonable 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

.01 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 Requirement~ for Land Disposal of Radioactive Waste".

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

Note 5: The volume and activity listed for non-compressible metal represent the quantity of material that to date could not be recycled by a contracted vendor and required disposal. The initial volume of material sent to the recycle facility was 77.02 cubic meters.

21

Page 1. of 84 At'tachment - A HIRER PNER 6 LIGHl COMPANY SI', IIKIE 0-2IO PIANI'RBKSIRY OPERATBQ PRO(XDURE M)~

RE%SION 8 TTILE:

Offsite Dose Calculaticn Manual (ODQl)

REVIN QB APPRDFAL Reviewed by Facility Review Gmup ril 22 1982 Appmved by C. M. We Revt.sicn 8 Reviewed by F R G 19~

Appmved by 19+7 S OPS DATE DOCT PROCEDURE DOCN C-200 SYS COMP COMPLETED ITM 8

Page 41 of 84 STe LUCIE PLANT CHEMISTRY OPERA'BING PROCEDURE NO. C-200, REVISION 8 OFFSITE DOSE CALCULATION MANUAL (ODCM) 2.7 (continued)

1. Obtain the latest zesults of the nznthly calculaticns of the gmna air dose (Secticn 2.4) md the beta air dose if pezforned (Secticn 2.5). 'Ihese doses can be obtained fzom the in~lant records.

2. Divide these doses by th. number af days the pLant was cpezatioral during the month.

3. Multiply the quotient by the number of days the p1ant is pmPcted to be aperatioral durIng the next mcnth. 'Ihe pmduct is the pmPcted dose for the next nznth. %he value should be ad~ted as receded to acmunt for any changes in fai1ed-fuel or other identifiable operating ccnditicns that could significantly alter the actual releases.

4. If the pmpcted dhses are K.2 mcads gmaa air dose or 0.4 mzads beta air dose, the apprcpriate subsystens of the gaseous zadwaste system shall be used to znduce the zadioactivity levels prior to zelease.

3.0 40 CFR 190 Dose Evaluation Dtscnsntm - Dose or dose comnLtsent to a mml htdtvldntt fmm all ummtmn fuel cycle swcmm be Hndtad to <25 mtem to tha tohtl body or any orden (except thycotd, nhtch is Lind,ted to <75 mzem) over a period of 12 consecutive ncnths. 'Ihe fallowing appzcech shlld be used to demcnstrate conpliance with these dose limits. This approach is based cn MJREG-0133, Secticn 3.8.

3.1 Evaluation Bases Dose evatustins to denrnstzate conpliance with the alive dose limits need only be perfozned if the quarterly doses calculated in Secticns 1.4, 2.4 and 2e6 exzaed twice the dose Lindts of Tech. Specs. 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2a, 3.1.2.2b, 3.11.2.3a, and 3.11.2.3b ze~ively; i.e., quarterly doses exceeding 3 mzem to the total body (liquid releases), 10 mzem to any cage (liquid releases), 10 mzads gmaa air dose, 20 nnads beta air dose, or 15 mzem to the thymid or any'rgan from zadioiodines and particulates (atnnspheric releases). Otherwise, no evaluatims are zequized and the zenninder of this sectim can be omitted.

3.2 Doses Fmm Li id Releases For the evaluate af cbses to zeal individuals fmm liquid releases, the sana calculaticn nethod as enplayed in Section 1.4 wil1 be used. Heaver, nnze zealistic assunpticns will be nade ancerning the diluticn and in~tim of fish and shellfish by individuals who live snd fish in the area. A1so, the results of the Radiological Emd.zcnnental Mcnitccing pmgzam wi11 be included in determIning naze zealistic dose to these real people by pmviding data m actual naasum1 levels af plant related zadicnuclides in the envirient.

Attachment~-. B FLORIDA POWER 6 LIGHT COMPANY ST- -LUCIE PLANT t Page 1 of 10 ADMINISTRATIVE PROCEDURE NUMBER 0520025 REVISION 6

1. 0 TITLE PROCESS CONTROL PROGRAM 2.0 REVIEW AND APPROVAL:

Reviewed by Facility Review Group December 28, 1982 Approved by J. H. Barrow (for) Plant Manager December 28, 1982

'Revision 6 Reviewed F R G 1/7 Approved by 'Q

3. 0 SCOPE:

3. 1 Purpose The St. Lucie Plant Process Control Program (PCP) implements the requirements of the St. Lucie Plant Technical Specifications for both units. Specifically, the PCP applies to waste form classification of all radioactive waste destined for land burial in accordance with 10 CFR 20. 311, dewatering of bead resins for disposal, and solidification, encapsulation, or absorption vendor supplied processes for liquid radioactive waste.

3. 2 Discussion

1. The PCP contains provisions to assure that dewatering of bead resins results in a waste form with characteristics that meet the requirements of 10 CFR 61 as implemented by 10 CFR 20 and of the low level radioactive waste disposal site. The Process Control Program includes in addition to this procedure the following related procedures:

A. St. Lucie Plant Health Physics Procedure No. 49 "Dewatering Radioactive Bead Resins". /R6 B. CHEM-NUCLEAR SYSTBfS, INC. Test procedure for Dewatering Conical Bottom Demineralizers and Resin Liners - Prospect No. 11118.

C. CHEM-NUCLEAR SYSTEMS, INC. Lab Record Sheet for Conical Bottom Demineralizers and Resin Liners - Prospect No. 11118.

f S OPS f IDATE I fDOCT PROCEDURE fDOCN 0520025 f FOB INFORIIATlot). 0 )EELY . -

ISYS I This documenf is nof confrolled. Before use, vttrlfy informefion wifh a confrolled cfocumenf. fCOMP COMPLETED fIm 6

ST. LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, PROCESS CONTROL PROGRAM l

REVISION 6 Page 2 of 10

3.0 SCOPE

(continued)

3. 2 (continued)

2. Vendor supplied processes for solidification, encapsulation, or absorption of liquid radioactive waste is handled under a topical report which the vendor has submitted to the Nuclear Regulatory Commission for approval or under an N. R. C. approved process control program. Controlled copies of appropriate vendor procedures for these processes must be used to assure provision 'under the topical report are met.

3. All radioactive waste shiped for land burial must meet the requirements of 10 CFR 20. 311 regarding waste form classification and packaging. This is implemented through procedure HP-47, "Classification of Radioactive Waste Material for Land Disposal".

3.3 Authority The authority and responsibility to perform the requirements of this procedure come from 10 CFR 20, 10 CFR 61, St. Lucie Plant Unit 1 Technical Specifications, St. Lucie Plant Unit 2 Technical Specifications, and from disposal site criteria.

3.4 Definitions Absorption - The process of absorbing liquid radioactive waste materials onto an absorbent material.

2. Dewatering - The process of removing "free standing" water from a final disposal package which contains radioactive bead resins.

3. Encapsulation The process of enclosing radioactive waste material within cement-like material, such that the final product is a free-standing monolith.

4. "Free Standing" Water - Liquid which is not retained by the waste form.

5. Solidification The process of solidifying liquid radioactive waste material in cement-like material, such that the final product is a free-standing monolith.

6. Process Control Program (PCP) The Process Control Program shall contain the provisions, based on full scale testing, to assure that dewatering of radioactive bead resins results in a waste form with the properties that meet the requirements of 10 CFR 61 (as implemented by 10 CFR 20) and of the low level radioactive waste disposal site at the time of disposal.

Page 3 of 10 ST. LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 6 PROCESS CONTROL PROGRAM

3.0 SCOPE

(continued)

3. 4 (continued)

7. Visual Inspection - The direct observation of the bead resins during the entire period of resin transfer as they are packaged in the final disposal container.

8. Waste Form Classification Classification of radioactive waste As per 10CFR 61. 55 and 10CFR 61. 56. /R6

4.0 PRECAUTIONS

4. 1 Process Control Procedures used for the dewatering of radioactive bead resins that establish the conditions that must be met shall be based on full scale testing. This is to provide reasonable assurance that the dewatering of the resin and disposal container will result in volumes of free standing water, at the time of disposal, within the limits of 10CFR, Part 61 as implemented by 10CFR20 and of the low level radioactive waste disposal site.

4.2 Vendor supplied solidification, encapsulation, and absorption processes shall be NRC approved or under a topical report which has been submitted to NRC for approval. Procedures which are to be used must be controlled per the vendor's gA program.

/R6 4.3 All changes to the St. Lucie Plant Process Control Program must be reviewed and approved by the Facility Review Group before they become effective.

4.4 All changes to the St. Lucie Plant Process Control Program must be submitted to the NRC in the Semiannual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal must contain the following:

1. Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.

2. A determination that the change did not reduce the overall conformance of the dewatered bead resins to existing criteria for solid wastes.

3. Documentation of the fact that the change has been reviewed and found acceptable by the Facility Review Group.

Page 4 of 10 ST. LUCIE PLANT ADMINISTRATIVE PROCEDURE 'NUMBER 0520025, REVISION 6 PROCESS CONTROL PROGRAM 5 0 RESPONSIBILITIES:

5.1 It is the responsibility of the Plant Manager to assure that all necessary procedures, equipment and support are provided to properly implement the PCP.

5.2 It is the responsibility of the Health Physics Supervisor or his designee to assure that the radioactive bead resin will be dewatered in accordance with the PCP.

5.3 It is the responsibility of the Health Physics Supervisor or his designee to assure that radioactive waste material is classified in accordance with the PCP.

5.4 FPL Dewatering equipment shall be operated by or under the direction of FPL personnel. /R6 6 '

REFERENCES:

6.1 Bead Dewatering Procedure for CNSI 14-195 or smaller liners FO-OP-023.

6.2 Lab Record Sheet for Conical Bottom Demineralizers and Resin Liners, Prospect No. 11118.

6.3 Test Procedure for Dewatering Conical Bottom Demineralizers and Resin Liners, Prospect No. 11118.

6.4 Health Physics Procedure, HP-47, "Classification of Radioactive Waste Material for Land Disposal".

6.5 Health Physics Procedure, HP-49, "Dewatering Radioactive Bead Resins" /R6 7 ' RECORDS AND NOTIFICATIONS:

7.1 Records shall be as per St. Lucie Plant Health Physics Procedure No. 49, "Dewatering Radioactive Bead Resins". /R6 7.2 Notifications

1. If it is suspected that the free standing water requirements may not be met for any container of radioactive 'bead resin shipped to a disposal site, notify the Plant Manager and the Health Physics Supervisor.

2. If the process control procedures have not been followed or if free standing water may be present in the final shipping container of bead resin in amounts greater than allowed by regulations, notify the Health Physics Supervisor or his designee.

e ST. LUCIE,PLANT, Page 5 of 10 ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 6 PROCESS CONTROL PROGRAM I

8 ' INSTRUCTIONS:

8.1 Dewatered radioactive bead resins:

1. Disposal of dewatered radioactive bead resins is limited to the containers for which full scale dewatering tests have been conducted; and, -in the case of high integrity containers, for which certification by the State of South Carolina for use at the Barnwell, South Carolina land disposal facility has been established.

2. Dewater the container as per St. Lucie Health Physics Procedure No. 49, "Dewatering of Radioactive Bead Resins".

A. Only containers compatible with FPL owned resin transfer/dewatering equipment may be used.

B. Figure 1 through 5 depict the FPL owned resin transfer/dewatering equipment.

3. With dewatering not meeting disposal site, shipping, and transportation requirements, suspend shipment of the inadequately dewatered bead resin and correct the process control program, the applicable procedures(s), and/or the dewatering system as necessary to prevent recurrence.

4. With dewatering not performed in accordance with the PCP:

(1) if the dewatered bead resin has not already been shipped for disposal, verify each container to ensure that it meets burial ground, shipping and transportation requirements and/or (2) take appropriate administrative action to prevent recurrence.

5. Close the container as per the manufacturer's instructions.

8.2 Solidification, encapsulation, or absorption of radioactive waste materials shall be performed in accordance with FPL approved vendor procedures. These procedures shall provide for the following:

l. Independent verification of steps within the process that are crucial to the process; and

2. Testing of the final wast'e form to determine acceptability (where ALARA concerns permit testing) for shallow land burial.

8.3 All radioactive waste material packaged and destined for land disposal shall conform to the requirements of 10 CFR 20.311 as implemented by procedure HP-47. If waste form classification exceeds Class C or packaging does not meet the requirements of the waste form class, the Health Physics Supervisor shall be notified and shipment shall not be made.

/R6

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Page 8 of 10 ST. LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER'0520025, REVISION 6 PROCESS CONTROL PROGRAM

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