Text

Combined Semiannual Radioactive Effluent Release Rept for Jan-June 1987
	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)
	v • d • e

ACCESSION NBR FACIL: 50-335 50-389 AUTH. NAME WOODY> C. O.

RECIP. NAME REGULATO '

INFORMATION DISTRIBUTION STEM (RIDS) 8709080078 DOC. DATE'7/06/30 NOTARIZED:

NO St.

Lucie Planti Unit 1> Florida PoUJer 8c Light Co.

St.

Lucie Planti Unit 2i. Florida Power 8c Light Co.

AUTHOR AFFILIATION Florida Poeer 8c Light Co.

RECIPIENT AFFILIATION DOCKET 0 05000335 05000389

SUBJECT:

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

DISTRIBUTION CODE:

IE4SD COPIES RECEIVED: LTR

(

ENCL g SIZE: 3 TITLE: 50. 36a(a) (2) Semiannual Effluent Release Reports NOTES:

RECIP IENT ID CODE/NAME PD2-2 LA TOUR IGNYs E INTERNAL: AEOD/DOA ARM TECH *DV RE F

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Y 14000, JUNO BEACH, FL 33408-0420 Ol/pi AUGUST 3 g f987 L-87-356 U. S. Nuclear Regulatory Commission

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Document Control Desk 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 GR M5/0 I4/ I an FPL Group company

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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 5000335 t

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TABLE OF CONTENTS DESCRIPTION EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION OFFSITE DOSE CALCULATION MANUAL REVISIONS 7

SOLID WASTE AND IRRADIATEK;;'UELSHIPMENTS..........

~ ~..

7 PROCESS CONTROL PROBRAM REVISIONS...

7 LIQUID EFFLUENT:

SUMMATION OF ALL RELEASES Zc NUCLIDE SUMMATION BY QUARTER UNIT 8 1

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SUMMATION OF ALL RELEASES 5 NUCLIDE SUMMATION BY QUARTER UNIT 51

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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 NFor Iodine-131, Iodine-133, Tritium, and all radionuclides 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 effluent.

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 L!QUID GASEOUS Error Topic Avgas Max ~ %

Avgs Max o%

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

4.1 (Continued)

B.

(Continued)

TABLE 3 1

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

Releases Continuous Releases Monthly Composite Quarterly Composite Daily Grab Samples Tritium Gross Alpha Sr-89~

Sr-98~

5 Fe-55 Principal Gamma Emitters 8c 1-131 for 4/M Composite Analysis Dissolved 5 Entrained Gases One Batch/ Month Tritium Composite Monthly Alpha Composite Monthly Sr-89, Sr-9$, 5 Fe-55 Composite Quarterly L S.

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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 Source Sampling Frequency Type of Analysis Nethod of Analysis Waste Gas Decay Tank Releases Containment Purge Releases Each Batch Principal Gamma Emitters Principal Gamma Emitters Each Purge Tritium Principal Gamma Emitters Tritium

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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:

B.

TOTAL TIME PERIOD OF BATCH RELEASES:

C.

MAXl'MUMT2ME PER2OD FOR A BATCH RELEASE:

D.

AVERAGE Tl'ME PERIOD FOR A BATCH RELEASE:

E.

MINIMUMTIME PERIOD FOR A BATCH RELEASE:

F.

AVERAGE STREAM FLOP DURING REPORT2NG PER2'OD INTO A FLOWING STREAM:

~ -,29;, g 161 75.

MINUTES 870.

MINUTES 568.

M2NUTES 407.

MINUTES 868441.

G.P.M.

6.

GASEOUS FOR:

ST.

LUCIS PLANT UNl'T NO.

1 A.

NUMBER OF BATCH RELEASES:

B.

TOTAL Tl'ME PERIOD OF BATCH RELEASES:

C.

MAX2MUM T2ME PERIOD FOR A BATCH RELEASE:

D.

AVERAGE TIME PER2'OD FOR A BATCH RELEASE:

E.

M2NIMUM TIME PER1'OD FOR A BATCH RELEASE:

UNPLANNED RELEASES LIQUIDS FOR -'T. LUCIS PLANT UNIT NO. I A.

NUMBER OF RELEASES:

B.

TOTAL ACTIV1'TY RELEASED:

GASEOUS FOR:

ST.

LUCIS PLANT UNIT NO.

A.

NUMBER OF RELEASES:

8, TOTAL ACTIVITYRZLZASZD:

SEE ATTACHMENTS (IF APPLICABLE) FOR:

11. 0 3867.

MINUTES 600.

MINUTES 352.

MINUTES 180.

MINUTES 0.

0.

CURIES 0.

0.

CURIES 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:

B.

TOTAL TIME PER1OD OF BATCH RELEASES:

C.

MAXIMUMTIME PER1OD FOR A BATCH RELEASE:

D.

AVERAGE T1ME PERIOD FOR A BATCH RELEASE:

E.

M1N1MUM TIME PERIOD FOR A BATCH RELEASE:

F.

AVERAGE STREAM FLOP DURl'NG REPORT1NG PERIOD 1NTO A FLOWING STREAM:

<gag 261 75.

MINUTES 870.

MINUTES 568.

MINUTES 407.

MINUTES 868441.

G.P.M.

6.

GASEOUS FOR:

ST.

LUCIS PLANT UNIT NO. 2 A.

NUMBER OF BATCH RELEASES:

B.

TOTAL T1ME PER1'OD OF BATCH RELEASES:

C.

MAXIMUMTl'ME PER1OD FOR A BATCH RELEASE:

D.

AVERAGE T1ME PER1'OD FOR A BATCH RELEASE:

E.

MlN1'MUM TIME PERIOD FOR A BATCH RELEASE:

UNPLANNED RELEASES LIQUIDS FOR -'T. LUCIS PLANT UNIT NO. 2 A.

NUMBER OF RELEASES:

B.

TOTAL ACTIVITY RELEASED-'ASEOUS FOR:

ST.

LUCIS PLANT UNIT NO. 2 A.

NUMBER OF RELEASES:

B.

TOTAL ACTIV1TY RELEASED:

57. 0 14408.

MINUTES 4920.

MINUTES 258.

MINUTES l5.

MINUTES 0.

0.

CUR1ES 0.

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 affected 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.

A VERAGE DILUTED CONCENTRATION DURING PERIOD B.

TRITIUM 1.

TOTAL RELEASE 2.

A VERAGE Dl'LUTED CONCENTRATl'ON DUR1NG PERIOD C.

D1SSOLVED AND ENTRAINED GASES 1.

TOTAL RELEASE Z.

A VERAGE Dl'LUTED CONCENTRATlON DUR1 NG PER1'OD D.

GROSS ALPHA RADIOACT1VITY 1.

TOTAL RELEASE E.

VOLUME OF HASTE RELEASED (PRIOR TO DILUTION)

F.

VOLUME OF D1LUTION h'ATER USED DURING REPORT1NG PERIOD

2. 61E-01 UC1/ML

7. ZZE-10 8.21E Ol UC1/ML Z. 55E-07

1. 04E 01 UCI/ML

2. 87E-08

0. OOE-01 Ll'TERS

l. 78E 07 LITERS

3. 61E 11 7.43E-02 1.52E-10 4.54E 01

8. 24E-08

5. 76E-02

1. 1 7E-10

0. OOE-01 2.88E 07 4.81E 11

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0 FLORIDA POSER & LIGHT COMPANY ST.

LUC1'E PLANT UNIT NO. I JANUARY SEM1 ANNUAL REPORT I, 1987 THROUGH JUNE 80, 1987 TABLE 8. 4-1 L1QU1D EFFLUENTS NUCL1'DES RELEASED UNIT CONTINUOUS MODE QTR. ¹I QTR. ¹2 BATCH MODE QTR. ¹I QTR. ¹2 I-131 I-132 I-133 I-135 NA-24 CR-51 MN-54 FE-55 CO-57 CO-58 FE-59 CO-60 AG-110 SN-113 SB-122 SB-124 RB-88 SR-89 SR-90 Y-90 ZR-95 NB-95 NB-97 TC-99M RU-103 SB-125 CS-184 CS-136 CS-137 CS-138 C1CI C1 CI CI CI CI CI CI CI CI CI C1CI CI C1 CI CI CI CI CI C1 C1'1 CI CI C1 C1CI CI'.

07E-02

0. OOE-01

3. 09E-02

0. OOE-01

0. OOE-Ol

0. OOE-01

0. OOE-01 1.25E-05

0. DOS-01

0. OOE-01

0. OOE-Ol

0. OOE-01

1. 40E-03

0. OOE-01 3.93E-03

0. OOE-01

4. ZIE-04

0. OOE-OI

0. OOE-01

0. OOE-01 D. DOS-01

0. ODE-Ol

0. OOE-01

0. OOE-Ol

0. OOE-Dl

0. OOE-01

0. OOE-Ol

0. OOE-01

0. OOE-Ol

0. OOE-01

4. 70E-04

0. OOE-01 1.10E-03 O.DOE-OI

1. 13E-OZ 1.14E-03 1.12E-03

3. 91E-05

2. 50E-04

4. I7E-02

1. 72E-08

4. 71E-03

5. 64E-05

5. 45E-02 7.68E-04 Z. 98E-02

1. 57E-03

3. 26E-04

0. OOE-01

1. 16E-02

6. 20E-04

9. IOE-D5

5. 70E-05

8. 31E-03 1.26E-02

9. 08E-04 I. 07E-04

2. 38E-03 1.60E-OZ

2. 78E-03

6. IIE-05

5. 18E-03

2. 84E-04

1. I7E-03

0. OOE-01

7. OOE-05

0. OOE-01

0. OOE-01 I. 15E-OZ

5. 96E-04

5. IOE-08

0. OOE-01

1. 09E-02 1.99E-04 1.66E-OZ 8.99E-04 1.11E-04 1.38E-05

1. 72E-03

0. ODE-01

8. 75E-04

0. OOE-Ol

0. OOE-01 Z. 91E-03

4. 96E-03 Z. 54E-04

0. OOE-01

5. 89E-04

7. 75E-03 1.81E-03 O.OOE-OI 3.58E-03 I. 81E-05

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JANUARY FLORIDA POWER 4 LIGHT COMPANY ST.

LUCIS PLANT UNIT NO.

SEMIANNUAL REPORT 1987 THROUGH JUNE 30, 1987 TABLE 3. 4-1 CONTINUED LIQUID EFFLUENTS NUCLIDES RELEASED UNIT CONTINUOUS MODE QTR. ¹1 QTR. ¹2 BATCH MODE QTR. ¹1 QTR. ¹2 liA-140 CE-141 CE-144 TE-129 TE-129M TOTAL FOR PERIOD AR-41 ER-85M XE-131M XE-138 XE-133M XE-135 TOTAL FOR PERIOD CI CI CI CI CI CI CI CI CI CI CI

0. OOE-01

0. OOE-01,

0. OOE-01

0. OOE-01 1.96E-03

3. 31E-04 Z. 34E-04

9. 26E-04 4.88E-04

3. 47E-04

9. 49E-05

2. 54E-04

0. OOE-01

0. OOE-01 1.45E-03

0. OOE-01

8. 93E-05

4. 55E-04

3. 13E-02 1.01E 01

1. 26E-Ol

8. 71E-OZ

0. OOE-01

5. 55E-02 Z, 26E-04

1. 91E-03

1. 45E-03

0. OOE-01

1. 04E 01

5. 76E-OZ

4. 69E-02

2. OOE-03

2. 14E-01

7. 23E-02 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 ACTIVATIONPRODUCTS TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) 2.

A VERAGE DILUTED CONCENTRATION DURING PERIOD B.

TRITIUM 1.

TOTAL RELEASE 2.

A VERAGE DILUTED CONCENTRATION DURING PERIOD C.

DISSOLVED AND ENTRAINED GASES I.

TOTAL RELEASE 2.

A VERAGE DILUTED CONCENTRATION DURING PERIOD D.

GROSS ALPHA RADIOACTIVITY 1.

TOTAL RELEASE E.

VOLUME OF HASTE RELEASED (PRIOR TO DILUTION)

F.

VOLUME OF DILUTION PATER USED DURING REPORTING PERIOD

2. 14E-01 UCI/ML 5.92E-IO 9.21E 01 UCI'/ML 2.55E-07

1. 04E 01 UC1/ML

2. 8 7E-08

0. 00E-01 LITERS

2. 14E 06 LITERS

8. 61E 11

7. ZBE-02

1. 47E-10 4.54E 01 9.24E-08

5. 76E-02

1. I7E-10

0. 00E-01 1.48E 06 4.91E 11 11

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JANUARY FLORIDA POWER 4 LIGHT COMPANY ST.

LUCIS PLANT UNIT NO. 2 SEM1 ANNUAL REPORT I, 1987 THROUGH JUNE 30, 1987 TABLE 3. 4-2 LIQUID EFFLUENTS NUCLIDES RELEASED UNIT CONTINUOUS MODE QTR. ¹I QTR. ¹2 BATCH MODE QTR. ¹I QTR. ¹2 I-131 I-132 I-133 I-135 NA-24 CR-51 MN-54 FE-55 CO-5 7 CO-58 FE-59 CO-60 AG-110 SN-113 SB-122 SB-124 RB-88 SR-89 SR-9D Y-90 ZR-95 NB-95 NB-97 TC-99M RU-103 SB-125 CS-134 CS-136 CS-137 CS-138 CI CI CI C'1'I CI CI CI CI CI CI CI CI CI CI CI'I C'I CI CI CI CI CI CI CI CI CI C1'I CI

0. ODE-01

0. OOE-OI

0. OOE-01

0. OOE-OI

0. OOE-01

0. OOE-Ol

0. OOE-01

0. OOE-01 0, OOE-01

0. OOE" 01

0. OOE-01

0. OOE-OI

0. OOE-01 0, OOE-Ol

0. OOE-01

0. OOE-OI

0. OOE-01

0. OOE-OI

0. OOE-01

0. OOE-OI

0. DOE-01

0. OOE-01

0. OOE-01 D. ODE-01 0, OOE-Ol

0. OOE-01

0. DOE-01

0. OOE-01

0. OOE-OI

0. OOE-01

0. OOE-OI

0. OOE-01

0. OOE-Ol

0. OOE-01

0. OOE-01 1.13E-OZ 1.14E-03 I.IZE-03

3. 91E-05 Z. 5DE-04

4. I7E-02

1. 7ZE-03

4. 71E-03

5. 64E-05

5. 45E-OZ

7. 68E-04

2. 98E-02

1. 57E-03

3. Z6E-04

0. OOE-OI 1.16E-OZ 6.20E-04 9.10E-05

5. 70E-05

8. 31E-03 I. Z6E-OZ

9. 08E-04

1. 07E-04 Z. 38E-03 I. 60E-02

2. 78E-03

6. IIE-05

5. 13E-03

2. 84E-04

1. I7E-03

0. OOE-01

7. OOE-05

0. OOE-01

1. 15E-OZ 5.96E-04 5.10E-03

0. OOE-01 1.09E-02 1.99E-04

1. 66E-OZ

8. 99E-04 1.11E-04 1.33E-05

1. 72E-03

0. OOE-01

8. 75E-04

0. OOE-Dl

0. OOE-OI

2. 91E-03

4. 96E-03

2. 54E-04

0. OOE-OI

5. 89E-04

7. 75E-03

1. 81E-03

0. OOE-01

3. 58E-03

1. 81E-05 12

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FLORIDA POSER d'r LIGHT COMPANY ST.

LUCIS PLANT UNIT NO. 2 JANUARY SEMIANNUAL REPORT I, 1987 THROUGH JUNE 30, 1987 TABLE 3. 4-2 CONTINUED LIQUID EFFLUENTS NUCLIDES RELEASED UNIT CONTINUOUS MODE QTR. ¹I QTR. ¹2 BATCH MODE QTR. ¹I QTR. ¹2 LA-140 CS-141 CE-144 TE-129 TE-129M TOTAL FOR PERIOD AR-41 ER-85M XS-131M XE-133 XE-133M XE-135 TOTAL FOR PERIOD CI CI CI CI CI CI CI CI CI CI CI

0. ODE-01

0. OOE-01

0. OOS-01

0. OOE-Ol

0. OOE-01

0. OOE-01 1.96E-03

3. 31S-04

2. 34E-04

9. 26E-04

4. 88E-04

3. 47E-04 9.49E-05 2.54E-04

0. OOE-01

0. OOS-01

0. OOE-01

0. OOE-01 0, OOE-01 0, DOE-01

0. OOE-01

0. OOE-Ol

8. 93E-05

4. 55E-04

3. 13E-02 I.OIE Ol

1. 26S-OI

8. 71E-02

0. OOE-01

0. OOE-Ol

0. OOE-01

5. 55E-OZ

2. Z6E-04

1. 91E-03

0. OOE-01

1. 04E 01

5. 76E-02 O.OOE-OI O.OOE-OI 2.14E-OI 7.23E-02 13

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FLORIDA POSER & LIGHT COMPANY ST.

LUClZ PLANT UNIT NO.

1 SEMlANNUAL REPORT JANUARY 1,

198 7 THROUGH JUNE 80, 198 7 TABLE 3. 6-1 GASEOUS EFFLUENTS SUMMATlON OF ALL RELEASES NUCLlDES RELEASED A. FlSSION AND ACTIVATIONGASES UNlT QUARTER ¹1 QUARTER ¹2 1.

TOTAL RELEASE CI 8.89E 08 1.

TOTAL IODINE-131 CI

3. 31E-02 2.

AVERAGE RELEASE RATS FOR PSRl'OD UCI/SEC

4. 25E-08 C.

PARTICUliATES 1.

PARTlCULATES T-1/2

> 8 DAYS

1. 74E-05 2.

AVERAGE RELEASE RATE FOR PERIOD UCI/SEC

2. 24E-06 8,

GROSS ALPHA RADIOACTIVITY D.

TRITIUM 1.

TOTAli RELEASE CI

8. 85E-09 1.98E 00 2.

AVERAGE RELEASE RATS FOR PERl OD UCI'/SEC

2. 55E-01 2.

AVERAGE RELEASE RATE FOR PERlOD UCI/SEC

4. 35E 02 B.

l'ODINSS

5. 08E 02 6.46E 01

6. 58E-04

8. 80E-05

7. 57E-07 9.68E-08 1.99E-07 1.30E 01 1.65E 00 14

'3%MM<Y) 'DkM..X A MWQR, AQ.M()i',

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MAMM AKXCR

JANUARY FLORIDA POHER Zi LIGHT COMPANY ST.

LUC1E PLANT UNIT NO.

SEMIANNUAL REPORT 1,

198 7 THROUGH JUNE 30, 198 7 TABLE 3. 7-1 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES NUCLIDES RELEASED UN1 T NOBLE GASES CONTINUOUS MODE QTR. ¹1 QTR, ¹2 BATCH MODE QTR. ¹1 QTR. ¹2 AR-41 ER-85M ER-87 CI CI CI XE-135 TOTAL FOR PERIOD CI CI ER-88 CI XE-131M CI XE-133 CI CI

0. OOE-01 4.29E Ol

2. 41E 01 7.90E 01

0. OOE-01 Z,34E 03

2. 75E 01 3.89E 02

0. OOE-Ol

0. OOE-01

0. OOE-Ol

0. OOE-01

4. 37E 02

0. OOE-01 6.02E 01

9. 14E-01

9. 45E-Ol

0. OOE-01 3.13E-Ol 9.53E-Ol 4.44E 02 8.20E 00

2. 73E 01

0. OOE-01

0. OOE-Ol

0. OOE-01 0, OOE-01

1. 01E 01

1. 70E-01

1. 03E-02 2,90E 03 4.98E OZ 4.82E OZ 1.02E 01 2,

IODINE I-131 I-132 I-133 I-135 TOTAL FOR PERIOD CI

3. 31E-OZ

6. 53E-04 CI

1. 03E-Ol

9. 24E-05 CI 3.29E-02 1.38E-03 CI 4.66E-02 O.OOE-OI CI 2.16E-01 2.12E-03 3.

PARTICULATE RB-88 SR-89 CS-137 TOTAL FOR PERIOD CI CI CI CI 1.56E 00

3. 76E-06

1. 36E-05

0. OOE-01

7. 57E-07

0. OOE-01 1.56E 00 7.57E-07 15

MM %3'7 AR.

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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 A. FISSION AND ACTIVATIONGASES UNIT QUARTER ¹I QUARTER ¹Z 1.

TOTAL REliEASE 2.66E 08 1.

TOTAL IOD1NE-131

7. 44E-03 2.

AVERAGE RELEASE RATE FOR PERIOD UCIJ/'SEC

9. 56E-04 C.

PARTICULATES 1.

PART1CULATES T-1//2

> 8 DAYS CI

0. OOE-01 Z.

AVERAGE RELEASE RATE FOR PERIOD UCI//SEC

0. OOE-Ol 8.

GROSS ALPHA RADIOACTIVITY D.

TRITIUM TOTAL RELEASE CI CI 9, 80E-08 2.Z1E 01 2.

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

AVERAGE REliEASE RATE FOR PERIOD UCI/SEC

8. 42E 02 B.

IODINES 8.17E 08

4. 08E OZ 1.49E-OZ 1.90E-08

8. 05E-05 3.88E-06 1.80E-07 2.88E 01

3. 08E 00 16

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M7M'.0:H.'7%hN

JANUARY FLORIDA POHER 4 LIGHT COMPANY ST.

LUCIE PLANT UNIT NO. 2 SEMIANNUAL REPORT 1,

1987 THROUGH JUNE 30, 1987 TABLE 8. 7-Z GASEOUS EFFLUENTS - GROUND LEVEL RELEASES NUCLIDES RELEASED UNIT 1.

NOBLE GASES CONTINUOUS MODE QTR. ¹1 QTR. ¹2 BATCH MODE QTR, ¹1 QTR. ¹2 AR-41 ER-85 ER-85M ER-87 ER-88 XE-131M XE-188 XE-188M XE-135

'OTAL FOR PERIOD 2,

IODINE I-131 I-182 I-188 TOTAL FOR PERIOD 8.

PARTICULATE RB-88 SR-89 TOTAL FOR PERIOD CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI 0, OOE-01

0. ODE-01

2. 01E 01 1.Z6E 00 1.56E 01

0. OOE-01 2.26E 08 1.04E 01 2.68E 02

0. OOE-.01

0. OOE-Ol 1.98E 01

0. OOE-01 2.00E 01

0. OOE-01 2.20E 08 1.48E 01

2. 48E 02 1.99E 00 3, 67E-01

6. 5ZE-02

0. OOE-01

1. 89E-02 1.84E 00 7.82E 01

8. 68E-01 1.18E 00 1.11E 00 1.64E DO

4. 09E-01

0. DOE-01

1. 18E-01 8.54E 00 6.42E 02 8.12E 00

1. 03E 01 7.44E-08 1.49E-02 5.44E-04 5.48E-04

6. 68E-03

1. 89E-02

1. 47E-02

8. 48E-02 8.24E 00

0. OOE-OI

0. OOE-01

8. 05E-05 8,24E 00

8. 05E-05 2.58E 08 2.50E 08 7.95E 01 6.67E 02 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 a.

Spent resin, M<<3 process filters Ci b.

Dry Compressible M<<3 Waste Ci 6

MONTH PERIOD ERROR%

2. 002 E+1

6. 516 E+2 2 ~ 0 E+1 0

0

c. Irradiated Components M<<3 Ci 0

0

d. Other 1.Sol idified Oil M<<3 Ci

2. 334 E+1

1. 08 E-4 2.0 E+1

2. Sol idifi ed STP4 M<<3 and Tank Sludge Ci

3. Solidi% i ed Tank M<<3 Sludge Ci

4. Non-compressible M<<3 Metal (Note 5)

Ci

5. 834 E+1 1

~ 70 E-2

5. 83 E+0

4. 72 E-1 1.377 E+1

1. 43 E-1

2. 0 E+1

2. 0 E+1 2 ~ 0 E+1

STP, Sewage Treatment Pl ant 2 ~

ESTIMATE OF MAJOR NUCLIDE Category Nuclide a

~

131 I

137 Cs S8 Co 60 Co 134 Cs 51 Cr S5 Fe 95 Nb 63 Ni 54 Mn 95 Zr COMPOSITION (BY TYPE OF WASTE) 2 ~ 89 E+1

2. 14 E+1

1. 56 E+1

1. 10 E+1

9. 10 E+0 3 ~ 30 E+0

2. 30 E+0

2. 10 E+0

2. 00 E+0

1. 80 E+0

1. 30 E+0 b.

NA C ~

NA NA 18

d t

lh '

Table 3.9 Continued:

60 Co 3

H 55 Fe 137 Cs 54 Mn 63 Ni 58 Co 134 Cs 4.29 E+1

4. 04 E+1 1.07 E+1

1. 80 E+0 1.00 E+0

8. 00 E-1

7. 00 E-1 7.00 E-1 3 ~

SOLID WASTE DISPOSITION Number of Shipments Node of Transportation Destination 14 2

B. Irradi ated Fuel Shi pments Sole Use Truck Sole Use Truck

Barnwell, SC

Richland, WA Number of Shipments Node of Transportation Destination 0

NA NA-Not App1 i cab 1 e 19

Table 3ta (Cont.)

Kaste Class Total Volume Cubic ft Total Curies Note i Pr incipal Radionuclides Notes i 8 2 Type of Haste Note 3 Cateaor y Rea Guide i2X Type of Container Note 4 Solidification Agent Class A

Class A

Class B

Class C

824 2060 206 486.4 202 i.08e-4 i.70e-2 4.72e-i i.43e-i 33.9i 560.57 na na na na Ni63

Sr99, Ce13

Co60, Ni63.

Sr90, Csl37

Pu24i, THU; Sum of Nuc-li es with Ti 2<5yr

Co60, Ni63,

Pu24i, THU, Sum of Nuc-li es with Ti 2<5yr Solidified Oil STP 8 Tank Sludge Solidified Tank Sludge Non-Com-pressible eeete[Note5)

PIIH ion Exchange Resin PNR ion exchange resin PtrR Process Filters i.d i.d i.d i.a i.a i.a Non-specification Strong tight package Non-specification Strong tight package NRC Certified LSA

> Type A Non-specification Stong tight package NRC Certified LSA

> Type A NRC Certified LSA

> Type A NRC Certified Type B Cement Cement Cement None None None None

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 ide composi tion of solid waste shipped from the St. Lucie Unit 1

8< 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 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 PIANI'RBKSIRY OPERATBQ PRO(XDURE M)~ 0-2IO RE%SION 8 TTILE:

Offsite Dose Calculaticn Manual (ODQl)

REVIN QB APPRDFAL Reviewed by Facility Review Gmup Appmved by C. M. We Revt.sicn 8

Reviewed by F R G Appmved by ril 22 1982 19~

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 willbe 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.

t Attachment~-.

B FLORIDA POWER 6 LIGHT COMPANY ST- -LUCIE PLANT ADMINISTRATIVEPROCEDURE NUMBER 0520025 REVISION 6 Page 1 of 10

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

Reviewed by Facility Review Group Approved by J.

H.

Barrow (for)

December 28, 1982 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".

B.

CHEM-NUCLEAR SYSTBfS, INC. Test procedure for Dewatering Conical Bottom Demineralizers and Resin Liners - Prospect No.

11118.

/R6 C.

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

11118.

FOB INFORIIATlot).0 )EELY This documenf is nof confrolled. Before use, vttrlfyinformefion wifh a confrolled cfocumenf.

f S

OPS f

IDATE I

fDOCT PROCEDURE fDOCN 0520025 f

ISYS I

fCOMP COMPLETED fIm 6

l ST.

LUCIE PLANT ADMINISTRATIVEPROCEDURE NUMBER 0520025, REVISION 6 PROCESS CONTROL PROGRAM 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.

ST.

LUCIE PLANT ADMINISTRATIVEPROCEDURE NUMBER 0520025, REVISION 6 PROCESS CONTROL PROGRAM Page 3 of 10

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.

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.

/R6 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.

ST.

LUCIE PLANT ADMINISTRATIVE PROCEDURE 'NUMBER 0520025, REVISION 6 PROCESS CONTROL PROGRAM Page 4 of 10 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, ADMINISTRATIVEPROCEDURE NUMBER 0520025, REVISION 6 PROCESS CONTROL PROGRAM I

Page 5 of 10 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

ST.

LUCIE PLANT ADMINISTRATIVEPROCEDURE NUMBER 0520025, REVISION 6 PROCESS CONTROL PROGRAM Page 6 of 10 PROCESS CONTROL PROGRAM FIGURE 1

TOP VIP'F P;t.'680 PRt+Aay QSvlA~'lAQ Pl% VauS r lb' Q<M'R6

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LUCIE PLANT ADMINISTRATIVEPROCEDURE NUMBER 0520025, REVISXON 6 PROCESS CONTROL PROGRAM page 7 of l0 PXGURE 2

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/R6

ST.

LUCIE PLANT ADMINISTRATIVEPROCEDURE NUMBER'0520025, REVISION 6 PROCESS CONTROL PROGRAM Page 8 of 10

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~~444%4C'l ~

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/R6

ST.

LUCIE PLANT ADMINISTRATIVEPROCEDURE iVUMBER 0520025, REVISION 6 PROCESS CONTROL PROGRAM Page 9 of 10 FIGURE 4 a;aa V==-~

Ot= -It.:~aWO

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/R6

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LUCIE PLANT ADMINISTRATIVEPROCEDURE NUMBER 0520025, REVISION 6 PROCESS CONTROL PROGRAM Page 10 of 10 FIGURE 5 i 'I iNQNITQ8 B>CX VI='A

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L-87-356, Combined Semiannual Radioactive Effluent Release Rept for Jan-June 1987

Contents

Text

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4.0 PRECAUTIONS

REFERENCES:

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L-87-356, Combined Semiannual Radioactive Effluent Release Rept for Jan-June 1987

Text

SUBJECT:

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3.0 SCOPE

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REFERENCES:

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