ML17223A894

From kanterella
Jump to navigation Jump to search
Semiannual Radioactive Effluent Release Rept for Jan-June 1990
ML17223A894
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 06/30/1990
From: Sager D
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9008290018
Download: ML17223A894 (51)


Text

ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM

,~lyy t

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9008290018 DOC.DATE: 90/06/30 NOTARIZED:

NO FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power

& Light Co.

50-389 St. Lucie Plant, Unit.2, Flor!ida Power 6 Light Co.

AUTH.NAME AUTHOR AFFILIATION DOCKET P5PPP335 05000389 SAGER, D. A.

RECXP.NAME Florida Power 6 Light Co.

RECIPIENT AFFILXATION

SUBJECT:

"St Lucie Plants Units 1

6 2

Comb Radioactive Effluent Release Rep DISTRIBUTION CODE:

IE48D COPIES RECEIVED TXTLE: 50.36a(a)(2)

Semiannual Effluent R ined Semiannual for Jan-June 1990."

LTR ENCL SIZE'ease Reports NOTES:

RECIPIENT ID CODE/NAME PD2-2 LA NORRIS,J COPIES LTTR ENCL 3

3 1

1 RECIPIENT ID CODE/NAME PD2-2 PD COPIES LTTR ENCL 1

1 INTERNAL: ACRS IRM TECH ADV CN2 DRSS/RPB EXTERNAL: BNL TICHLER,J03 LPDR 1

1 1

1 1

1 2

2 1

1 1

1 AEOD/DSP/TPAB NRR/DREP/PRPB11 RES BROOKS,B RGN2 FILE 02 EG&G SIMPSON, F NRg PDR 1

1 2

2 1

1 1

1 2

2 1

1 ROOM PI-37 (EXT. 20079) TO ELIMINATEYOUR LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 20 ENCL 20 II NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, AME FROM DISTRIBUTION

P.O. Box14000, Juno Beach, FL 33408-0420 August 22, 1990 L-90-307 10 CFR 50.36 U. S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 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,

1990 through June 30, 1990 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,

~

~

A.

ager Vice P esident St.

L ie Plant DAS:JWH:kw cc: Stewart D. Ebneter,.Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St..Lucie Plant Attachment DAS/PSL N236 900829'00i8'900630 PDR ADOCK".05000335 R

PDC an FPL Group company

4 P

1 t'f

FLORIDA POHER 8c LIGHT COMPANY ST.

LUCIE PLANT UNITS NO.

1 8c 2 LICENSE NUMBERS DPR-67

& NPF-16 COMBINED SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD JANUARY 1, 1990 THROUGH JUNE 30, 1990

II

,p<

v i ~eJ

)

t)

)r, l I

il

)[

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

OFFSITE DOSE CALCULATION MANUAL REVISIONS................,.......

7 SOLID WASTE AND IRRADIATIED -FUEL SHIPMENTS.....

PROCESS CONTROL PROGRAM REVIS IONS....

LIQUID EFFLUENTS:

Summation of all Releases Unit ¹ 1

Summation of all Releases Unit ¹ 2

Nuclide Summation by Quarter Unit ¹ 1

Nuclide Summation by Quarter Unit ¹ 2

~

~

7 8

9 10 12 GASEOUS EFFLUENT:

Summation of all Releases Unit ¹ 1

Summation of all Releases Unit ¹ 2

Nuclide Summation by Quarter Unit ¹ 1

Nuclide Summation by Quarter Unit ¹ 2

14

~

~

~

~

o 15

~

~

~

o 16 18 SOLID WASTE

SHIPMENT SUMMATION 20

4

~

~

N F

I I

~ I I

4

~v il I I

I

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.

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 skin, 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.

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.

gC.

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.

I I

a i

I I tp II' II N

tl 4

EFFLUENT AND HASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued) 2 ~

Maximum Permissible Concentrations Hater:

As per 10 CFR 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 Where alpha, tritium, and listed nuclides are shown as sero Curies

released, this should be interpreted as "no activity 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 of gaseous effluent accounting methods is described in Table 3.2.

Ei

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

Max. %

Avg. %

Max. %

Release Point Mixing Sampling Sample Preparation Sample Analysis Release Volume 2

3 2

Total 9

5 5

5 10 5

30 NA 2

1 3

4 10 NA 5

5 10 15 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.

f f

f I'l 4

1 i,

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 Source Sampling Frequency Type of Method of Analysis Analysis Monitor Tank 1

Releases Monthly Composite Quarterly Composite Tritium Gross Alpha Sr-89, Sr-90,

& Fe-55 Each Batch Principal Gamma Emitters

p. h. a.

L. S.

G. F. P.

Continuous Releases Daily Grab Samples Principal Gamma Emitters

&, I-131 for 4/M Composite Analysis Dissolved

& Entrained Gases One Batch/ Month Tritium Composite Monthly Alpha Composite Monthly Sr-89, Sr-90,

& Fe-55 Composite Quarterly

p. h. a.
p. h. a.

L. S.

G. F. P.

C. S.

1-Boric Acid Evaporator Condensate is normally recovered to the Primary Hater 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

l 4

EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued) 4.

Measurements and Approximations of Total Radioactivity (Continued)

4. l (Continued)

B.

(Continued)

TABLE 3.2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS Gaseous Source Sampling Frequency Type of Analysis Method of Analysis Waste Gas Decay Tank Releases Each Batch Principal Gamma Emitters

p. h. a.

Containment Purge Releases Principal Gamma Emitters Each Purge Tritium

p. h. a.

L. S.

Plant Vent 4/M Monthly Composite Quarterly Composite Principal Gamma Emitters Tritium Particulate Gross Alpha Part iculate Sr-89

& Sr-90

p. h. a.

L. S.

G. F. P.

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

~

g p

t, II Ill k

K 'f

FLORIDA POWER 5, LIGHT COMPANY ST.

LUCIE UNIT ¹ 1

SEMIANNUAL REPORT JANUARY 1, 1990 THROUGH JUNE 30, 1990 EFFLUENT & WASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED)

Batch Releases A.

Liq,uid 1.

2.

3.

4.

5.

6.

Number of batch releases:

Total time period for batch releases:

Maximum time period for a batch release:

Average time period for a batch release:

Minimum time period for a batch release:

Average dilution stream flow during the period:

25 11407 668 456 302 minutes minutes minutes minutes 823841 gpm All liquid releases are sum'marized in tables.

B.

Gaseous 1.

Number of batch releases:

2.

Total time period for batch releases:

3

~

Maximum time period for a batch release:

4.

Average time period for, a batch release:

5.

Minimum time period for a batch release:

7 3123 600 446 25 minutes minutes minutes minutes All gaseous waste releases are summarized in tables.

Unplanned Releases A.

Liquid 1.

Number of releases:

2.

Total activity of releases:

0

0. OOE+00 Curies B.

Gaseous 1.

Number of releases:

2.

Total activity of releases:

0 O.OOE+00 Curies C.

See attachments (if applicable) for:

1.

A description of the event and equipment involved.

2.

Cause(s) for the unplanned release.

3.

Actions taken to prevent a recurrence.

4.

Consequences of the unplanned release.

0 R

IL II

FLORIDA POHER

& LIGHT COMPANY ST.

LUCIE UNIT 0 2

SEMIANNUAL REPORT JANUARY 1, 1990 THROUGH JUNE 30, 1990 EFFLUENT 8c HASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED) 5.

Batch Releases A.

Liquid 1.

Number of batch releases:

2.

Total time period for batch releases:

3.

Maximum time period for a batch release:

4.

Average time period for a batch release:

5.

Minimum time period for a batch release:

6.

Average dilution stream flow during the period:

24 10951 668 456 302 minutes minutes minutes minutes 823841 gpm All liquid releases are summarized in tables.

B.

Gaseous 1.

2.

3.

4 5.

Number of batch releases:

Total time period for batch releases:

Maximum time period for a batch release:

Average time period for a batch release:

Minimum time period for a batch release:

66 16832 675 255 20 minutes minutes minutes minutes All gaseous waste releases are summarized in tables.

Unplanned Releases A.

Liquid 1.

Number of releases:

2.

Total activity of releases:

0

0. OOE+00 Curies B.

Gas eous 1.

Nu'mber of releases:

2.

Total activity of releases:

0 O.OOE+00 Curies C.

See attachments (if applicable) for:

1.

A description of the event and equipment involved.

2.

Cause(s) for the unplanned release.

3.

Actions taken to prevent a recurrence.

4.

Consequences of the unplanned release.

I.

t

,I

(

II P

F

\\

EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued) 7.

Assessment of radiation dose from radioactive effluents to MEMBERS OF THE PUBLIC is provided on the end of year report.

8.

Offsite Dose Calculation Manual Revisions (ODCM):

The ODCM was not revised during the reporting interval.

9.

Solid Waste and Irradiated Fuel Shipments:

No irradiated fuel shipments were made for 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.

I r

4 I~

II l

II k

)

1 t %I

FLORIDA POWER

& LIGHT COMPANY ST.

LUCIE UNIT ¹ 1

SEMIANNUAL REPORT JANUARY 1, 1990 THROUGH JUNE 30, 1990 TABLE 3.3-1 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTR¹ 1 A.

Fission and Activation Products QTR¹2 1.

Total Release (Not including Tritium, Gases, and Alpha)

Ci 1.52E-01 1.41E-01 2.

Average Diluted Concentration During Period B.

Tritium 1.

Total Release 2.

Average Diluted Concentration During Period C.

Dissolved and Entrained Gases 1.

Total Release uci/ml

4. 7 1E-10 2. 87 E-10 Ci 6.96K+01 5.02K+01 uci/ml
2. 16E-07
1. 02E-07 Ci 3.53E-01 1.85E-02 2.

Average Diluted Concentration During Period uci/ml

1. 10E-09
3. 78 E-11 D.

Gross Alpha Radioactivity 1.

Total Release Ci

6. 00E-06
1. 19E-05 E.

Volume of Haste Released (Prior to Dilution)

Liters 1.25E+07 2.36E+07 F.

Volume of Dilution Hater Used During Period Liters 3.22E+11 4.91K+11

FLORIDA POWER Sc LIGHT COMPANY ST.

LUCIE UNIT 0 2

SEMIANNUAL REPORT JANUARY 1, 1990 THROUGH JUNE 30, 1990 TABLE 3.3-2 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTR4 1 A.

Fission and Activation Products QTR52 1.

Total Release (Not including Tritium, Gases, and Alpha) 2.

Average Diluted Concentration During Period B.

Tritium 1.

Total Release 2.

Average Diluted Concentration During Period C.

Dissolved and Entrained Gases 1.

Total Release 2.

Average Diluted Concentration During Period D.

Gross Alpha Radioactivity 1.

Total Release E.

Volume of Waste Released (Prior to Dilution)

F.

Volume of Dilution Water Used During Period Ci

1. 11E-01
1. 38E-01 uci/ml 3.44E-10 2.82E-10 Ci
6. 96K+01 5. 02E+01 uci/ml
2. 16E-07
1. 02E-07 Ci 3.50E-01 1.85E-02
1. 09E-09
3. 78E-11 uci/ml Ci 6.00E-06
1. 19E-05 Liters 1.44K+06 1.53E+06 Liters 3.22K+11 4.91K+11

~

~

II 4

FLORIDA POWER

& LIGHT COMPANY ST.

LUCIE UNIT ¹ 1

SEMIANNUAL REPORT JANUARY 1, 1990 THROUGH JUNE 30, 1990 NUCLIDES RELEASED TABLE UNIT 3.4-1 LIQUID EFFLUENTS Continuous Mode QTR¹1 QTR¹2 Batch Mode QTR¹1 QTR¹2 NA-24 CR-51 MN-54 FE-55 MN-56 CO-57 CO-58 FE-59 CO-60 ZN-65 NI-65 BR-82 RB-88 SR-89 SR-90 Y-90 SR-9 1 SR-92 Y-92 ZR-95 NB-95 ZR-97 NB-97 TC-99M MO-99 RU-103 AG-110 SN-113 SB-122 SB-124 SB-125 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.70E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.99E-05 O.OOE+00 0 'OE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

~ OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

~ OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 6.45E-05 1.55E-02 7.35E-04

5. 05E-03 O.OOE+00 7.80E-06 5.25E-02 1.46E-04
9. 15E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
5. 10E-05 O.OOE+00 0

~ OOE+00 O.OOE+00 O.OOE+00

0. OOE+00
2. 24E-03 3.69E-03 O.OOE+00
1. 03E-03
5. 37E-05 O.OOE+00 1.26E-04 8.77E-04 2.62E-04
6. OOE-05
3. 39E-03
8. 34E-.03 1.59E-04 1.77E-02
4. 31E-04
8. 62E-03A O.OOE+00 O.OOE+00
2. 08E-02
9. 26E-05
7. 50E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
0. 00E+00 A
0. 00E+00 A
0. OOE+00 A 0.'OOE+00 O.OOE+00
0. OOE+00
2. 32E-03
3. 89E-03
0. OOE+00
9. 26E-04
2. 38E-05 O.OOE+00 1.22E-04 7.84E-04 1.08E-04 6.65E-04 1.59E-02 3.99E-02 A Quarter ¹ 2 results based on months of April due to inadvertent loss of May sample.

and June

I I

I It I

'll't

FLORIDA POWER

&, LIGHT COMPANY ST.

LUCIE UNIT ¹ 1

SEMIANNUAL REPORT JANUARY 1,,1990 THROUGH JUNE 30, 1990 TABLE 3.4-1 LIQUID EFFLUENTS (CONTINUED)

NUCLIDES RELEASED UNIT Continuous Mode QTR¹1 QTR¹2 QTR¹1 QTR¹2 Batch Mode TE-129 TE-129M 1-131 TE-132 I-132 I-133 I-134 CS-134 I-135 CS-136 CS-137 CS-138 BA-140 LA-140 CE-141 CE-144 PR-144 W-187 NP-239 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci

0. OOE+00
0. OOE+00
0. OOE+00
0. OOE+00
1. 99E-02
0. 00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.24E-02 O.OOE+00 O.OOE+00 O.OOE+00 1.78E-03 9.69E-04 O.OOE+00 O.OOE+00
1. 17E-04 O.OOE+00
2. 08E-03 l. 29E-03 0

~ OOE+00 0

~ OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

0. OOE+00
0. OOE+00 1.40E-03 1.58E-05 O.OOE+00 2.52E-04 0.00K+00 2.22E-03 O.OOE+00
1. 06E-05
2. 78E-03 O.OOE+00 O.OOE+00 8.33E-04 1.99E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
0. 00K+00
0. 00E+00
2. 93E-03
1. 27E-05
6. 22E-05
6. 18E-04
0. OOE+00
6. 98E-03
7. 81E-05
1. 01E-05
7. 58E-03
9. 99E-06 O.OOE+00 1.66E-04
0. OOE+00
0. OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD CI
4. 11E-02
2. 26E-03
1. 11E-01 1.38E-01 AR-41 KR-85M KR-85 KR-87 KR-88 XE-131M XE-133M XE-133 XE-135M XE-135 CI CI CI CI CI CI CI CI CI CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
2. 56E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
0. OOE+00 4.76E-05 O.OOE+00 O.OOE+00
0. OOE+00
2. 89E-03
2. 77E-03 3.44E-01 O.OOE+00 9.72E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
7. OOE-05
1. 81E-02
0. OOE+00 3.68E-04 11

I' I

t

FLORIDA POWER

& LIGHT COMPANY ST.

LUCIE UNIT ¹ 2

SEMIANNUAL REPORT JANUARY 1, 1990 THROUGH JUNE 30, 1990 NUCLIDES RELEASED NA-24 CR-51 MN-54 FE-55 MN-56 CO-57 CO-58 FE-59 CO-60 ZN-65 NI-65 BR-82 RB-88 SR-89 SR-90 Y-90 SR-9 1 SR-92 Y-92 ZR-95 NB-95 ZR-97 NB-97 TC-99M MO-99 RU-103 AG-110 SN-113 SB-122 SB-124 SB-125 TABLE UNIT CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI 3.4-2 LIQUID EFFLUENTS Continuous Mode QTR¹1 QTR¹2 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 ~ OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Batch QTR¹1

6. 45E-05
1. 55E-02
7. 35E-04
5. 05E-03
0. OOE+00
7. 80E-06
5. 25E-02
1. 46E-04
9. 15E-03 O.OOE+00 O.OOE+00 O.,OOE+00 O.OOE+00
5. 10E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.24E-03 3.69E-03 O.OOE+00
1. 03E-03 5.37E-05 O.OOE+00 1.26E-04
8. 77E-04
2. 62E-04
6. OOE-05
3. 39E-03
8. 34E-03 Mode QTR¹2
1. 59E-04
1. VVE-02
4. 31E-04
8. 62E-03 A O.OOE+00 O.OOE+00
2. 08E-02
9. 26E-05
7. 50E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
0. 00E+00 A
0. 00E+00A
0. 00E+00A O.OOE+00 O.OOE+00 O.OOE+00 2.32E-03 3.89E-03 O.OOE+00 9.26E-04 2.38E-05 O.OOE+00 1.22E-04 7.84E-04
1. 08E-04
6. 65E-04
1. 59E-02
3. 99E-02 Quarter ¹ 2 results based on months of April due to inadvertent loss of May sample.

and June

lt U

I' II N

f'I II

FLORIDA POWER

&, LIGHT COMPANY ST.

LUCIE UNIT 0 2

SEMIANNUAL REPORT JANUARY 1, 1990 THROUGH JUNE 30, 1990 TABLE 3.4-2 LIQUID EFFLUENTS (CONTINUED)

NUCLIDES RELEASED UNIT Continuous Mode QTR01 QTR02 QTR01 QTR02 Batch Mode TE-129 TE-129M I-131 TE-132 I-132 I-133 I-134 CS-134 I-135 CS-136 CS-137 CS-138 BA-140 LA-140 CE-141 CE-144 PR-144 W-187 NP-239 CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.40E-03 1.58E-05 O.OOE+00 2.52E-04 O.OOE+00 2.22E-03 O.OOE+00

1. 06E-05
2. 78E-03 O.OOE+00 O.OOE+00 8.33E-04 1.99E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.93E-03 1.27E-05 6.22E-05
6. 18E-04 O.OOE+00 6.98E-03
7. 81E-05
1. 01E-05
7. 58E-03
9. 99E-06
0. OOE+00 1.66E-04 O.OOE+00
0. OOE+00 O.OOE+00 O.OOE+00
0. OOE+00 TOTAL FOR PERIOD CI O.OOE+00 O.OOE+00
1. 11E-01
1. 38E-01 AR-41 KR-85M KR-85 KR-87 KR-88 XE-131M XE-133M XE-133 XE-135M XE-135 CI CI CI CI CI CI CI CI CI CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

'O.OOE+00 O.OOE+00

0. 00E+00 4.76E-05 0.00K+00
0. 00K+00
0. OOE+00
2. 89E-03
2. 77E-03

,3. 44E-01

0. OOE+00
9. 72E-04
0. 00E+00
0. 00K+00
0. OOE+00
0. OOE+00
0. 00K+00
0. OOE+00
7. 00E-05
1. 81E-02 O.OOE+00 3.68E-04

III

'H

~

u II~t 14

'l 1

k H

II <

1 l'

I i,

1 l

FLORIDA POWER

& LIGHT COMPANY ST.

LUCIE UNIT 0 1

SEMIANNUAL REPORT JANUARY 1, 1990 THROUGH JUNE 30, 1990 TABLE 3.6-1 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTR01 QTRC2 A.

Fission and Activation Gases 1.

Total Release 2.

Average Release Rate For Period B.

Iodines 1.

Total Iodine-131 2

~

Average Release Rate For Period C.

Particulates 1.

Particulates (Half Life 8 days) 2.

Average Release Rate For Period Ci uCi/sec Ci uCi/sec Ci uCi/sec 2.80E+02 1.33E+02

3. 60E+01
1. 70E+01
7. 06E-03
1. 92E-04
9. 07E-04
2. 44E-05
1. 27E-05
1. 63E-06 1.63E-06 2.07E-07 3.

Gross Alpha Radioactivity D.

Tritium 1.

Total Release 2

~

Average Release Rate For Period Ci Ci uCi/sec

1. 54E-07
3. 78E-11 4.86E+00 1.03E+01 6.25E-01 1.30E+00

J 1

FLORIDA POWER

& LIGHT COMPANY ST.

LUCIE UNIT 0 2

SEMIANNUAL REPORT JANUARY 1, 1990 THROUGH JUNE 30, 1990 TABLE 3.6-2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTR01 QTR02 A.

Fission and Activation Gases 1.

Total Release 2.

Average Release Rate For Period B.

Iodines 1.

Total Iodine-131 2.

Average Release Rate For Period C.

Particulates 1.

Particulates (Half Life

> 8 days) 2.

Average Release Rate For Period Ci uCi/sec Ci uCi/sec Ci uCi/sec

2. 21E+02
1. 07K+02 2.84E+01 1.36K+01
1. 42E-03
1. 63E-03 1.82E-04 2.08E-04 2.73E-05 2.89E-05
3. 51E-06
3. 68E-06 3.

Gross Alpha Radioactivity D.

Tritium 1

~

Total Release 2.

Average Release Rate For Period Ci uCi/sec O.OOE+00 O.OOE+00 1.61E+00 7.89E+00 2.07E-01 1.00E+00 15

tl 'f

FLORIDA POHER

&, LIGHT COMPANY ST.

LUCIE UNIT ¹ 1

SEMIANNUAL REPORT JANUARY 1, 1990 THROUGH JUNE 30, 1990 TABLE 3.7-1 GASEOUS EFFLUENTS GROUND LEVEL RELEASES Nuclides Released 1.

Fission Gases Unit Continuous Mode QTR¹1 QTR¹2 Batch Mode QTR¹1 QTR¹2 AR-41 KR-85M KR-85 KR-87 KR-88 KR-89 KR-90 XE-127 XE-13 1M XE-133M XE-133 XE-135M XE-135 XE-137 XE-138 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci

0. OOE+00
0. OOE+00 O.OOE+00 4.42E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.26E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.30E+02 9.55E+01 O.OOE+00 O.OOE+00 3.22K+01 2.61E+01 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.90E-01
6. 31E-03
0. OOE+00 O.OOE+00 9.38E-03 O.OOE+00 O.OOE+00 O.OOE+00 2 '5K-01 1.87E-01 1.73K+01 O.OOE+00 1.95E-01 O.OOE+00 O.OOE+00 1.60E-01
1. 18E-02 O.OOE+00 O.OOE+00 1.82E-02 O.OOE+00 O.OOE+00
0. OOE+00
6. 51E-02
8. 58E-02 5 ~ 48K+00 O.OOE+00 2.36E-01 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD 2.

Iodines I-131 I-132 I-133 I-134 I-135 TOTAL FOR PERIOD Ci Ci Ci Ci Ci Ci Ci 2.62E+02 1.27E+02

7. 06E-03
1. 92E-04
5. 53E-02 3

~ 46E-04 2

~ 16 E- 03 8. 39 E- 04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

6. 45E-02
1. 38E-03 1.82E+01 6.06E+00 3.

Particulates

(

8 Days)

Cr-51 Mn-54 Fe-55 Co-57 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.63E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.27E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 16

I'i I

I'

" II

'I III II

FLORIDA POWER 8c LIGHT COMPANY ST.

LUCIE UNIT 0 1

SEMIANNUAL REPORT JANUARY 1, 1990 THROUGH JUNE 30, 1990 TABLE 3. 7-1 GASEOUS EFFLUENTS GROUND LEVEL RELEASES (CONTINUED)

Nuclides Released Unit Continuous Mode QTR01 QTR42 3.

Particulates

(

> 8 Days)

(continued)

Sr-89 Sr-90 Y-90 Ru-103 Ag-110 Sn-113 Sb-124 Sb-125 Te-129m Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD 4.

Particulates Mn-56 Ni-65 Br-82 Rb-88 Rb-89 Sr-91 Sr-92 Y-92 Zr-97 Nb-97 Tc-99m Mo-99 Sb-122 Te-129 Te-132 Cs-138 La-140 Pr-144 W-187 Np-239 TOTAL FOR PERIOD

(

8 Ci Days)

Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci 1.27E-05 1.63E-06

0. OOE+00
0. OOE+00
0. OOE+00
0. OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0

~ OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.94E-05 O.OOE+00 O.OOE+00 5.86E-02 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 ~ OOE+00 O.OOE+00 O.OOE+00 O.OOE+00

1. 94E-05
5. 86E-02 17

C

~

K N

H ll

FLORIDA POWER

& LIGHT COMPANY ST.

LUCIE UNIT 0 2

SEMIANNUAL REPORT JANUARY 1, 1990 THROUGH JUNE 30, 1990 TABLE 3.7-2 GASEOUS EFFLUENTS GROUND LEVEL RELEASES Nuclides Released 1.

Fission Gases Unit Continuous Mode QTR01 QTR02 Batch Mode QTR01 QTR02 AR-41 KR-85M KR-85 KR-87 KR-88 KR-89 KR-90 XE-127 XE-131M XE-133M XE-133 XE-135M XE-135 XE-137 XE-138 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.84E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.37E+02 O.OOE+00 9.84K+00 O.OOE+00 O.OOE+00 O.OOE+00 2.05E+00 O.OOE+00 O.OOE+00 3.49E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 5.69E+01 O.OOE+00

1. 71K+01 O.OOE+00 O.OOE+00 5.42E-01 2.56E-01 1.32E-01 1.46E-02 O.OOE+00 O.OOE+00 1.58E-02 0.00E+00
1. 20E-01 6. 21E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 4.41E-01 3.48E-01
9. 11E-01 2.',24E-01
6. 64E+01 2. 59E+01 O.OOE+00 O.OOE+00 2.67E+00 3.04E-01 O.OOE+00 O.OOE+00 O,OOE+00 O.OOE+00 TOTAL FOR PERIOD 2.

Iodines I-131 I-132 I-133 I-134 I-135 TOTAL FOR PERIOD Ci Ci Ci Ci Ci Ci Ci 1'9E+02 7.96E+01

1. 42E-03
1. 63E-03 O.OOE+00 7.36E-04 4.04E-03 9.29E-03 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00
5. 45E-03
1. 17E-02
7. 13E+01 2.70E+01 3.

Particulates

(

8 Days)

Cr-51 Mn-54 Fe-55 Co-57 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci

0. OOE+00
0. OOE+00 O.OOE+00 0.'OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2.73E-05 O.OOE+00 O.OOE+00 O.OOE+00 0

~ OOE+00 O.OOE+00 0

~ OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 ~ OOE+00 O.OOE+00 18

tt t t I

t" I t N

FLORIDA POHER

& LIGHT COMPANY ST.

LUCIE UNIT ¹ 2

SEMIANNUAL REPORT JANUARY 1, 1990 THROUGH JUNE 30, 1990 TABLE 3. 7-2 GASEOUS EFFLUENTS GROUND LEVEL RELEASES (CONTINUED)

Nuclides Released Unit Continuous Mode QTR¹1 QTR¹2 3.

Particulates

(

> 8 Days)

(continued)

Sr-89 Sr-90 Y-90 Ru-103 Ag-110 Sn-113 Sb-124 Sb-125 Te-129m Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 Ce-144 Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci O.OOE+00 O.OOE+00

=O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 'OE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2 '9E-05 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD 4 ~

Particulates Mn-56 Ni-65 Br-82 Rb-88 Rb-89 Sr-91 Sr-92 Y-92 Zr-97 Nb-97 Tc-99m Mo-99 Sb-122 Te-129 Te-132 Cs-138 La-140 Pr-144 H-187 Np-239

( (

8 Ci Days)

Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci Ci

2. 73E-05
2. 89E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD Ci O.OOE+00 O.OOE+00 19

r ~,C r i r( 'i K

'g 4

I

FLORIDA POWER AND LIGHT CO~

ST LUCIE PLANT SEMI-ANNUAL REPORT JANUARY 1, 1990 THROUGH JUNE 30, 1990 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 a.

Spen(

resin, Process'filters M3 Ci 2.458 E+1 1.'059 E+2 2.0 E+1
b. Dry Compressible Waste (Note 5)

M3 Ci 3.121 E+1 F 080 E+0 2.0 E+1

c. Irradiated Components M3 Ci 2.0 E+1
d. Other
1. Non-Compres-M3 sible Metal Ci (DAW) (Note 6) 1;907 E+1 8;610 E-1 2.0 E+1
2. Solidified Tank Sludge M3 Ci 5.873 E+0 3 '50 E+0 2.0 E+1 2.

Estimate of Major Nuclid Composition (By Type of Waste)

Category Nuclides a ~

Co 60 Co 58 Fe 55 Cs 137 Cs 134 Cr 51 Ni 63 Be 7

Mn 54 Nb 95 I

131 Zr

'95 2.75 E+1 1.44 E+1 1.24 E+1 1.19 E+1 7.84 E+0 4.93 E+0 4.82 E+0 4.41 E+0 3.51 E+0 2.46 E+0 2.35 E+0 1.42 E+0 b.

Fe 55 Cs 137 Co 60 Cs 134 Co 58 Ni 63 Nb 95 Sb 125 5.99 E+1 1.50 E+1 1.15 E+1 4.96 E+0 3.99 E+0 1.26 E+0 1'.18 E+0 8.40 E~l 20

0

~

~

I

Page 2

A.

2.

Estimate of Major Nuclide Composition (By Type of Waste)

(Continued)

Category Nuclides c ~

N/A N/A d 0 Co 60 Fe 55 Ni 63 Cs 137 Cs 134 Sb 125 Mn 54 4.26 E+1 3.57 E+1 9.56 E+0 6.25 E+0 1.92 E+0 1.74 E+0 9.70 E-1

3. Solid Waste Disposition Number of Shipments 43 Mode of Transportation Sole Use Truck Destination Barnwell, S.

C.

B.

Irradiated Fuel Shipments Number of Shipments 0

Mode of Transportation N/A Destination N/A N/A = Not Applicable 21

FLORIDA POWER AND LIGHT COMPANY ST LUCIE PLANT SEMI-ANNUAL REPORT JANUARY 1, 1990 THROUGH JUNE 30, 1990 UNITS 1 AND 2i TABLE 3 9 (CONTINUED)

Waste Class Total Volume Cubic Ft.

Total Principal Curies Radionuclides (Note 1)

Notes 1 a 2)

Type of Waste (Note 3)

Category Type of Reg-Guide Container 1.21 (Note 4)

Solidification Agent Class A

896.3 1.90E-l NA PWR Compactible Trash (Note 5) l.b.

Non-specification Strong Tight Package None Class A

673.3 8.61E-l NA PWR Non-Compactible Trash (Note 6) l.d.

Non-specification Strong Tight Package None Class A

215.9 1.87E-4 NA PWR Ion-Exchange Resin l.a.

Non-specification Strong Tight Package None Class A

205.8 6.89 Cs 137, Sr 90 PWR Compactible Trash l.b.

NRC Certified LSA Type A None Class A

207.4 3.65 Ni 63, Cs 137 Solidified Tank l.d Sludge NRC Certified LSA Type A Cement Class A

205.8 1.79 SR 90, Cs 137 PWR ion-Exchange Resin l.a NRC Certified LSA Type A None Class A

205.8 2.72 Ni 63, Sr90, I 129,

C14, Pu 241 PWR Process Filters l.a.

NRC Certified LSA Type A None Class B

120.3 81.35 Co 60, Ni 63, Sr 90, Cs 137 Sum of Nuclides TQ<5yr.

PWR Ion-Exchange Resin l.a.

NRC Certified LSA Type A None Class C

120.3 20.10 Co 60, Ni 63, Sr 90@

Cs 137g C 14, I 129, Pu 241, Sum of Nuclides TQ<5yz.

PWR Process Filers l.a.

NRC Certified Type B

None

0

FLORIDA POWER AND LIGHT C NY ST LUCIE PLANT SEMI-ANNUAL REPORT JANUARY 1, 1990 THROUGH JUNE 30, 1990 UNITS 1, AND 2 TABLE 3.9 (CONTINUED)

SOLID WASTE SUPPLEMENT The total curie quantity and radionuclide composition of solid waste shipped from the St.

Lucie

plant, Units 1

and 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/ll/83) for these determinations.

The most frequently used techniques for determining the total curie quantity in a

package are the dose to curie methods and the (concentration) x (volume or mass) calculations.

Where appropriate, engineering type activation analyses may be applied.

Since each of the above methodologies involves to some extent qualitative parameters; the total curie quantity is considered to be an estimate.

The composition of radionuclides in the waste is determined by both on-side 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.

"Principal Radionuclides" refer to those radionuclides contained in the waste in concentrations greater than

.Ol times the concentration of the nuclides listed in Table 1

or

.Ol times the smallest concentration of the nuclides listed in Table 2

of 10 CFR 61.

"Type of Waste" is generally specified as described in NUREG

0782, Draft Environment Impact Statement on 10 CFR 61, "Licensing Requirements for Land Disposal of Radioactive Waste".

"Type of Container" refers to the transport package.

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 di'sposal at the

Barnwell, South Carolina burial facility.

During the reporting

period, six shipments of Dry Compressible Waste (5,520 cubic
feet, 1.285E+0 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.

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.

23

0 0

r-P< '~

r