ML17227A585

From kanterella
Jump to navigation Jump to search
Semiannual Radioactive Effluent Release Rept for Jan-June 1992. Proposed Changes to Process Control Program Also encl.W/920827 Ltr
ML17227A585
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 06/30/1992
From: Sager D
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
L-92-238, NUDOCS 9209020211
Download: ML17227A585 (49)
v • d • e


Text

P.O. Box 128, Ft. Pierce, FL 34954-0128 August 27, 1992 L-92-238 10 CFR 50.36 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 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, 1992, through June 30, 1992, for St. Lucie Units 1 and 2. This report is required by Technical Specification 6.9.1.7.

Included in .the attached report is a summary of a change that was made to the Process Control Program. This information is being provided pursuant to Section 6.13 of the St. Lucie Units 1 and 2 Technical Specifications.

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

Very truly yours, Vice Pres>dent St. Lucie Plant DAS.JJB kw cc: Stewart D. Ebneter, Regional Administrator, Region Senior Resident Inspector, USNRC, St. Lucie Plant II, USNRC Attachment DAS/PSL 8765-92 Oi Ogpu 92090 ~~~ 9>063O F'DR R oCK 0500033>

PDR an FPL Group company

1

~fg} a yh

FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE PLANT UNITS NO. 1 6 2 LICENSE NUMBERS DPR-67 6 NPF-16 COMBINED SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD JANUARY 1, 1992 THROUGH JUNE 30, 1992

1 '

~ k

TABLE OF CONTENTS DESCRIPTION PAGE EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION. .......... 1 OFFSITE DOSE CALCULATION MANUAL REVISIONS..... .... .......... 7 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS. .................... 7 PROCESS CONTROL PROGRAM REVISIONS.... .. .. .. ........... 7 LIQUID EFFLUENTS:

Summation of all Releases Unit 5 1 Summation of all Releases Unit 5 2 ......................... 9 Nuclide Summation by Quarter Unit 5 1 ...................... 10 Nuclide Summation by Quarter Unit 5 2 12 GASEOUS EFFLUENT:

Summation of all Releases Unit 5 1 14 Summation of all Releases Unit 5 2 ......................... 15 Nuclide Summation by Quarter Unit 5 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 16 Nuclide Summation by Quarter Unit 5 2 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~, ~ ~ ~ ~ ~ ~ ~ ~ 18 SOLID WASTE SHIPMENT SUMMATION . .... ................... 20 ATTACHMENT CHANGES TO THE PROCESS CONTROL PLAN

P t"

l'

EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION

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

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

During any calendar quarter to <= 1.5 mrems to the Total Body and to <= 5 mrems to any organ, and During any calendar year to <= 3 mrems to'the Total Body and to <= 10 mrems to any organ.

1.'2 For Gaseous Waste Effluents:

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

For Noble Gases: <= 500 mrems/yr to the total body and

<= 3000 mrems/yr to the 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.

  • BE 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.

  • CD 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. 'I

  • 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 calculations are based on. The STS LCO dose limits are therefore included in Item 1 of the report, for information only

EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)

2. Maximum Permissible Concentrations Water: 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 zero 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.

4. 1 Estimate of Errors LIQUID GASEOUS Error Topic Avg o ~o Max.% Avg.o Max.o Release Point Mzxxng 5 NA NA Sampling 5 2 5 Sample Preparation 5 1 5 Sample Analysis 10 3 10 Release Volume 5 4 15 Total 0 9 30 10 35 The predictability of error for radioactive releases can only be applied'o 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.

EFFLUENT AND WASTE'DISPOSAL SUPPLEMENTAL INFORMATION (Continued)

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

4.1 (Continued)

B. (Continued)

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.ST Tank Composite Gross Alpha G.F.PE 1

eleases Quarterly Sr-89, Sr-90, Composite & Fe-55 Continuous Daily Principal Gamma Emitters Releases Grab & I-131 for - p.h.a.

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

Tritium Composite Monthly L S Alpha Composite Monthly G.FOP' Sr-89, Sr-90, & Fe-55 Composite Quarterly ~ S-1-Boric Acid Evaporator Condensate is normally recovered to the Primary Water Storage Tank for recycling into the reactor coolant system and does not contribute to Liquid Waste Effluent Totals.

p.h.a.-Gamma Spectrum Pulse Height Analysis using Lithium Germanium Detectors. All peaks are identified and quantified.

L.S.-Liquid Scintillation Counting C.S.-Chemical Separation G.F.P.-Gas Flow Proportional Counting 4/M-Four per Month

~ l Il

EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (Continued)

4. Measurements and Approximations of Total Radioactivity (Continued) 4.1 (Continued)

B. (Continued)

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS Gaseous Sampling Type of Method of Source Frequency Analysis Analysis Waste Gas Decay Tank Each Batch Principal Gamma Emitters p.h.a.

Releases ontainment Principal Gamma Emitters p.h.a.

Purge Each Purge Tritium L.ST Releases 4/M Principal Gamma Emitters p.h.a.

Tritium L.ST Plant Monthly Particulate Vent Composite Gross Alpha G.F.PE Quarterly Particulate Composite Sr-89 & Sr-90 C.S.

p.h.a.-Gamma Spectrum Pulse Height Analysis using Lithium Germanium Detectors. All peaks are identified and quantified.

L.S.-Liquid Scintillation Counting C.S.-Chemical Separation G.F.P.-Gas Flow Proportional Counting 4/M-Four per Month

r FLORIDA POWER Sr LIGHT COMPANY ST. LUCIE UNIT 4 1 SEMIANNUAL REPORT JANUARY 1, 1992 THROUGH JUNE 30, 1992 EFFLUENT 6 WASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED)

5. Batch Releases A. Liquid
1. Number of batch releases: 27
2. Total time period for batch releases: 11530 minutes
3. Maximum time period for a batch release: 640 minutes
4. Average time period for a batch release: 427 minutes
5. Minimum time period for a batch release: 290 minutes
6. Average dilution stream flow during the period: 842277 gpm All liquid releases are summarized in tables.

B. Gaseous

1. Number of batch releases: 22
2. Total time period for batch releases: 9858 minutes
3. Maximum time period for a batch release: 800 minutes
4. Average time period for a batch release: 448 minutes
5. Minimum time period for a batch release: 67 minutes All gaseous waste releases are summarized in tables.
6. Unplanned Releases A. Liquid
1. Number of releases: 0
2. Total activity of releases: O.OOE+00 Curies B. Gaseous
1. Number of releases: 0
2. Total activity of releases: 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 FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT 4 2 SEMIANNUAL REPORT JANUARY 1, 1992 THROUGH JUNE 30, 1992 EFFLUENT 6 WASTE DISPOSAL SUPPLEMENTAL INFORMATION (CONTINUED)

5. Batch Releases A. Liquid
1. Number of batch releases: 26
2. Total time period for batch releases: 11103 minutes
3. Maximum time period for a batch release: 640 minutes
4. Average time period for a batch release: 427 minutes
5. Minimum time period for a batch release: 290 minutes
6. Average dilution stream flow during the period: 842277 gpm All liquid releases are summarized in tables.

B.- Gaseous

1. Number of batch releases: 73
2. Total time period for batch releases: 17386 minutes
3. Maximum time period for a batch release: 620 minutes
4. Average time period for a batch release: 238 minutes
5. Minimum time period for a batch release: 18 minutes All gaseous waste releases are summarized in tables.
6. Unplanned Releases A. Liquid
1. Number of releases: 0
2. Total activity of releases: O.OOE+00 Curies B. Gaseous
1. Number of releases:

0

2. Total activity of releases: 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.

~

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 revised during the reporting interval. An explanation of the changes and the affected pages are attached to this report.

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 0 1 SEMIANNUAL REPORT JANUARY 1, 1992 THROUGH JUNE 30, 1992 TABLE 3.3-1 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTRC1 QTRC2 A. Fission and Activation Products

1. Total Release (Not including Tritium, Gases, and Alpha) Ci 6.41E-02 2.76E-01
2. Average Diluted Concentration During Period uci/ml 1.29E-10 8.13E-10 B. Tritium
1. Total Release Ci 4 '3E+01 1.08E+02
2. Average Diluted Concentration During Period uci/ml 9.33E-08 3.18E-07 C. Dissolved and Entrained Gases
1. Total Release Ci 2.03E-02 1.05E-01
2. Average Diluted Concentration During Period uci/ml 4.09E-11 3.10E-10 D. Gross Alpha Radioactivity
1. Total Release Ci 4.67E-06 1.17E-05 E. Volume of Waste Released (Prior to Dilution) Liters 1.87E+07 1.66E+07 F. Volume of Dilution Water Used During Period Liters 4.96E+11 3.39E+11

FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT 4 2 SEMIANNUAL REPORT JANUARY 1, 1992 THROUGH JUNE 30, 1992 TABLE 3.3-2 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTR41 QTRC2 A. Fission and Activation Products

1. Total Release - (Not including Tritium, Gases, and Alpha) Ci 6.41E-02 2.76E-01
2. Average Diluted Concentration During Period uci/ml 1. 29E-10 8.12E-10 B. Tritium
1. Total Release Ci 4.62E+01 1.08E+02
2. Average Diluted Concentration During Period uci/ml 9.32E-08 3.17E-07 C. Dissolved and Entrained Gases
1. Total Release Ci 2.03E-02 1.05E-01
2. Average Diluted Concentration 4.09E-11 3.10E-10 During Period uci/ml D. Gross Alpha Radioactivity
1. Total Release Ci 4.67E-06 1.17E-OS E. Volume of Waste Released (Prior to Dilution) Liters 4.86E+06 1.21E+07 F. Volume of Dilution Water Used During Period Liters 4.96E+11 3.39E+11

lf

'1

FLORIDA POWER 6 LIGHT COMPANY ST. LUCZE UNIT 0 1 SEMIANNUAL REPORT JANUARY 1, 1992 THROUGH JUNE 30, 1992 TABLE 3.4-1 LIQUID EFFLUENTS Continuous Mode Batch Mode NUCLIDES QTR01 QTR02 QTRC1 QTR42 RELEASED UNIT NA-24 Ci O.OOE+00 O.OOE+00 3.05E-OS 2.60E-04 CR-51 Ci O.OOE+00 O.OOE+00 5.74E-04 3.48E-03 MN-54 Ci O.OOE+00 O.OOE+00 6.74E-04 4.20E-04 FE-55 Ci O.OOE+00 O.OOE+00 1.91E-02 1.06E-01 MN-56 Ci O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 CO-57 Ci O.OOE+00 O.OOE+00 3.13E-05 1.23E-05 CO-58 Ci O.OOE+00 0 ~ OOE+00 3.85E-03 1.94E-02 FE-59 Ci O.OOE+00 0 ~ OOE+00 O.OOE+00 5.03E-04 Co-60 Ci O.OOE+00 2 18E-05 1.50E-02 5.84E-03 ZN-65 Ci O.OOE+00 O.OOE+00 O.OOE+00 '.OOE+00 NI-65 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 BR-82 Ci O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 RB-88 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-89 Ci O.OOE+00 1.44E-04 O.OOE+00 4 '1E-05 SR-90 Ci O.OOE+00 O.OOE+00 0 ~ OOE+00 O.OOE+00 Y-90 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-91 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-92 Ci O.OOE+00 O.OOE+00 3.40E-04 O.OOE+00 Y-92 Ci O.OOE+00 O.OOE+00 0."OOE+00 O.OOE+00 ZR-95 Ci O.OOE+00 O.OOE+00 1.54E-04 8.17E-04 NB-95 Ci O.OOE+00 O.OOE+00 6.06E-04 1.39E-03 ZR-97 Ci O.OOE+00 O.OOE+00 0 ~ OOE+00 O.OOE+00 NB-97 Ci O.OOE+00 O.OOE+00 1.29E-03 1.'10E-03 Tc-99M Ci O.OOE+00 O.OOE+00 6.90E-06 4 41E-05 MO-99 Ci O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 RU-103 Ci O.OOE+00 O.OOE+00 O.OOE+00 5.21E-OS AG-110 Ci O.OOE+00 O.OOE+00 1.02E-03 8.17E-04 SN-113 Ci O.OOE+00 O.OOE+00 3 66E-05 2.90E-04 SB-122 Ci O.OOE+00 O.OOE+00 3.93E-04 3.32E-03 SB-124 Ci . O.OOE+00 O.OOE+00 1.93E-03 8.97E-03 SB-125 Ci O.OOE+00 O.OOE+00 5.76E-03 1.81E-02

FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT 4 1 SEMIANNUAL REPORT JANUARY 1, 1992 THROUGH JUNE 30'992 TABLE 3.4-1 LIQUID EFFLUENTS (CONTINUED)

Continuous Mode Batch Mode NUCLIDES RELEASED UNIT QTR41 QTRC2 QTR41 QTRC2 TE-129 Ci O.OOE+00 O.OOE+00 O.OOE+00 3.58E-03 TE-129M Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 I-131 Ci O.OOE+00 O.OOE+00 9. 10E-04 5. 46E-03 TE-132 Ci O.OOE+00 O.OOE+00 O.OOE+00 5.64E-05 I-132 Ci O.OOE+00 O.OOE+00 O.OOE+00 8.92E-OS I-133 Ci O.OOE+00 O.OOE+00 4.16E-OS 2.15E-03 I-134 Ci O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 CS-134 Ci O.OOE+00 O.OOE+00 5.14E-03 3.34E-02 I-135 Ci O.OOE+00 O.OOE+00 O.OOE+00 1.50E-04 CS-136 Ci O.OOE+00 O.OOE+00 O.OOE+00 8.71E-04 CS-137 Ci O.OOE+00 O.OOE+00 7.08E-03 2.84E-02 CS-138 Ci 0 OOE+00 O.OOE+00 1.85E-OS 7 45E-05 BA-140 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 LA-140 Ci O.OOE+00 O.OOE+00 8.47E-06 5 21E-04 CE-141 Ci 1.50E-OS O.OOE+00 O.OOE+00 O.OOE+00 CE-144 Ci O.OOE+00 O.OOE+00 1.08E-04 5.76E-OS PR-144 Ci O.OOE+00 O.OOE+00 O.OOE+00 3.04E-02 W-187 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 NP-239 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD CI 1.50E-05 1.65E-04 6.41E-02 2.76E-01 AR-41 CI O.OOE+00 O.OOE+00 O.OOE+00 4.64E-05 KR-85M CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 KR-85 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 KR-87 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 KR-88 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 XE-131M CI O.OOE+00 O.OOE+00 O.OOE+00 4.91E-04 XE-133M CI O.OOE+00 O.OOE+00 7.64E-OS 9.37E-04 XE-133 CI O.OOE+00 O.OOE+00 2.01E-02 9 69E-02 XE-135M CI O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 XE-135 CI O.OOE+00 4.28E-03 1.57E-04 2.44E-03

FLORIDA POWER 6 LIGHT COMPANY ST. LUCZE UNIT 4 2 SEMIANNUAL REPORT JANUARY 1, 1992 THROUGH JUNE 30, 1992 TABLE 3.4-2 LIQUID EFFLUENTS Continuous Mode Batch Mode NUCLIDES RELEASED UNIT QTR41 QTRC2 QTRC1 QTRC2 NA-24 CI O.OOE+00 O.OOE+00 3.05E-05 2.60E-04 CR-51 CZ O.OOE+00 O.OOE+00 5.74E-04 3.48E-03 MN-54 CZ O.OOE+00 O.OOE+00 6.74E-04 4.20E-04 FE-55 CZ O.OOE+00 0 OOE+00 1.91E-02 1.06E-01 MN-56 CZ O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 CO-57 CI O.OOE+00 0 OOE+00 3.13E-OS 1.23E-05 CO-58 CZ O.OOE+00 O.OOE+00 3.85E-03 1.94E-02 FE-59 CZ O.OOE+00 0 OOE+00 O.OOE+00 5.03E-04 CO-60'N-65 CI O.OOE+00 2.18E-05 1.50E-02 5.84E-03 CI O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 NZ-65 CZ O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 BR-82 CI O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 RB-88 CZ O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 SR-89 CZ O.OOE+00 1 01E-04 O.OOE+00 4 41E-05 SR-90 CZ O.OOE+00 0 OOE+00 0 ~ OOE+00 O.OOE+00 Y-90 CZ O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 SR-91 CZ O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 SR-92 CI O.OOE+00 0 OOE+00 3.40E-04 0 OOE+00 Y-92 CZ O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 ZR-95 CZ O.OOE+00 0 OOE+00 1.54E-04 8.17E-04 NB-95 CZ O.OOE+00 0 OOE+00 6.06E-04 1.39E-03 ZR-97 CZ O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 NB-97 CI O.OOE+00 O.OOE+00 1.29E-03 1.10E-03 TC-99M CZ 0 ~ OOE+00 O.OOE+00 6.90E-06 4.41E-OS MO-99 CZ O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 RU-103 CI O.OOE+00 0 OOE+00 O.OOE+00 5.21E-05 AG-110 CI O.OOE+00 O.OOE+00 1.02E-03 8.17E-04 SN-113 CZ O.OOE+00 O.OOE+00 3.66E-05 2.90E-04 SB-122 CZ O.OOE+00 O.OOE+00 3.93E-04 3.32E-03 SB-124 CZ O.OOE+00 O.OOE+00 1.93E-03 8.97E-03 SB-125 CI O.OOE+00 O.OOE+00 5.76E-03 1.81E-02 12

II "I

l lk f

FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT ¹ 2 SEMIANNUAL REPORT JANUARY 1, 1992 THROUGH JUNE 30, 1992 TABLE 3.4-2 LIQUID EFFLUENTS (CONTINUED)

Continuous Mode Batch Mode NUCLZDES RELEASED UNIT QTR¹1 QTR¹2 QTR¹1 QTR¹2 TE-129 CZ O.OOE+00 O.OOE+00 O.OOE+00 3.58E-03 TE-129M CZ O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 I-131 CZ O.OOE+00 O.OOE+00 9.10E-04 5.46E-03 TE-132 CZ O.OOE+00 O.OOE+00 O.OOE+00 5.64E-05 I-132 CZ O.OOE+00 O.OOE+00 O.OOE+00 8.92E-05 I-133 CZ O.OOE+00 O.OOE+00 4.16E-OS 2.15E-03 I-134 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 CS-134 CZ O.OOE+00 O.OOE+00 5.14E-03 3.34E-02 I-135 CI O.OOE+00 O.OOE+00 O.OOE+00 1.50E-04 CS-136 CZ O.OOE+00 O.OOE+00 O.OOE+00 8.71E-04 CS-137 CZ O.OOE+00 O.OOE+00 7.08E-03 2.84E-02 CS-138 CZ O.OOE+00 O.OOE+00 1.85E-05 7.45E-05 BA-140 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 LA-140 CI O.OOE+00 O.OOE+00 8.47E-06 5.21E-04 CE-141 CZ 1.50E-05 O.OOE+00 O.OOE+00 O.OOE+00 CE-144 CI O.OOE+00 O.OOE+00 1.08E-04 5.76E-OS PR-144 CI O.OOE+00 O.OOE+00 O.OOE+00 3.04E-02 W-187 CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 NP-239 CI O.OOE+00 O.OOE+00 0 ~ OOE+00 O.OOE+00 TOTAL FOR PERIOD CZ 1.50E-OS 1.22E-04 6.41E-02 2.76E-01 AR-41 CZ O.OOE+00 O.OOE+00 O.OOE+00 4.64E-OS KR-85M CI O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 KR-85 CZ O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 KR-87 CZ O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 KR-88 CZ O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZE-131M CZ O.OOE+00 O.OOE+00 O.OOE+00 4.91E-04 ZE-133M CZ O.OOE+00 O.OOE+00 7.64E-05 9.37E-04 ZE-133 CZ O.OOE+00 O.OOE+00 2.01E-02 9.69E-02 ZE-135M CZ O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 XE-135 CZ O.OOE+00 4.28E-03 1.57E-04 2.44E-03

FLORIDA POWER 6 LIGHT COMPANY ST LUCIE UNIT 4 1 SEMIANNUAL REPORT JANUARY 1, 1992 THROUGH JUNE 30, 1992 TABLE 3.6-1 GASEOUS. EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTRC1 QTRC2 A. Fission and Activation Gases

1. Total Release Ci 1.42E+01 9.98E+01
2. Average Release Rate For Period uCi/sec 1.80E+00 1.27E+01 B. Iodines
1. Total Iodine-131 Ci 9.29E-05 2.23E-04
2. Average Release Rate For Period uCi/sec 1.18E-OS 2.83E-OS C. Particulates
1. Particulates (Half Life > 8 days) Ci 1.02E-06 5.69E-07
2. Average Release Rate For Period uCi/sec 1.30E-07 7.24E-08
3. Gross Alpha Radioactivity 1.07E-07 7.02E-08 D. Tritium
1. Total Release Ci 1.08E+00 2.32E+01
2. Average Release Rate For Period uCi/sec 1.37E-01 2.95E+00 14

FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT 4 2 SEMIANNUAL REPORT JANUARY 1, 1992 THROUGH JUNE 30, 1992 TABLE 3 6-2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES UNIT QTR41 QTR42 A. Fission and Activation Gases

1. Total Rel'ease Ci 2.11E+02 3.49E+02
2. Average Release Rate For Period uCi/sec 2.68E+01 4.44E+01 B. Iodines
1. Total Iodine-131 Ci 1.03E-03 2.27E-03
2. Average Release Rate For Period uCi/sec 1.31E-04 2.89E-04 C. Particulates
1. Particulates (Half Life ) 8 days) O.OOE+00 1.41E-06
2. Average Release Rate For Period uCi/sec O.OOE+00 1.80E-07
3. Gross Alpha Radioactivity Ci O.OOE+00 1.14E-07 D. Tritium
1. Total Release 1.48E+01 1.42E+01
2. Average Release Rate For Period uCi/sec 1.88E+00 1.81E+00

FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT 4 1 SEMIANNUAL REPORT JANUARY 1, 1992 THROUGH JUNE 30, 1992 TABLE 3.7-1 GASEOUS EFFLUENTS GROUND LEVEL RELEASES Nuclides Continuous Mode Batch Mode Released Unit QTRC1 QTR42 QTRC1 QTRC2

1. Fission Gases AR-41 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 KR-85M Ci O.OOE+00 O.OOE+00 2.14E-03 6.92E-OS KR-85 Ci O.OOE+00'.OOE+00 O.OOE+00 7.23E-02 1.29E+00 KR-87 Ci O.OOE+00 O.OOE+00 O.OOE+00 KR-88 Ci 0 ~ OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 KR-89 Ci O.OOE+00 O.OOE+00 0 ~ OOE+00 O.OOE+00 KR-90 Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZE-127 Ci O.OOE+00 O.OOE+00 0 ~ OOE+00 O.OOE+00 ZE-131M Ci 0 OOE+00 1.22E+01 4.36E-02 4.05E-01 ZE-133M Ci O.OOE+00 O.OOE+00 2.36E-02 2.87E-01 ZE-133 Ci 8.61E+00 4.68E+01 4.22E+00 3.23E+01 ZE-135M Ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 ZE-135 Ci 1.16E+00 6.47E+00 2.04E-02 6.68E-02 ZE-137 Ci O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 ZE-138 Ci 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD Ci 9 77E+00 6.55E+01 4.38E+00 3.44E+01
2. Iodines I-131 Ci 9.29E-OS 2 '3E-04 I-132 Ci O.OOE+00 O.OOE+00 I-133 Ci 3.07E-04 1.76E-03 I-134 Ci O.OOE+00 O.OOE+00 I-135 Ci O.OOE+00 0.00E+00 TOTAL FOR PERIOD Ci 3.99E-04 1.99E-03
3. Particulates ( > 8 Days)

Cr-51 Ci O.OOE+00 O.OOE+00 Mn-54 Ci O.OOE+00 O.OOE+00 Fe-55 Ci O.OOE+00 O.OOE+00 Co-57 Ci 2.94E-07 O.OOE+00 Co-58 Ci O.OOE+00 O.OOE+00 Fe-59 Ci O.OOE+00 O.OOE+00 Co-60 Ci O.OOE+00 O.OOE+00 Zn-65 Ci O.OOE+00 O.OOE+00 Zr-95 Ci O.OOE+00 O.OOE+00 Nb-95 Ci O.OOE+00 0 OOE+00

FLORIDA POWER 6 LIGHT COMPANY ST. LUCZE UNIT 0 1 SEMIANNUAL REPORT

~ JANUARY 1, 1992 THROUGH JUNE 30, 1992 TABLE 3.7-1 GASEOUS EFFLUENTS GROUND LEVEL RELEASES (CONTINUED)

Nuclides Continuous Mode Released Unit QTRC1 QTRC2

3. Particulates ( > 8 Days) (continued)

Sr-89 Ci O.OOE+00 2.74E-07 Sr-90 ci O.OOE+00 1.48E-07 Y-90 Ci O.OOE+00 1.48E-07 Ru-103 ci O.OOE+00 O.OOE+00 Ag-110 Ci O.OOE+00 O.OOE+00 Sn-113 ci O.OOE+00 O.OOE+00 Sb-124 ci O.OOE+00 O.OOE+00 Sb-125 Ci O.OOE+00 O.OOE+00 Te-129m ci O.OOE+00 O.OOE+00 Cs-134 Ci O.OOE+00 O.OOE+00 Cs-136 Ci O.OOE+00 O.OOE+00 Cs-137 Ci O.OOE+00 O.OOE+00 Ba-140 Ci O.OOE+00 O.OOE+00 Ce-141 Ci 7.27E-07 O.OOE+00 Ce-144- ci O.OOE+00 O.OOE+00 TOTAL FOR PERIOD ci 1.02E-06 5.69E-07

4. Particulates ( ( 8 Days)

Mn-56 Ci O.OOE+00 O.OOE+00 Ni-65 Ci O.OOE+00 O.OOE+00 Br-82 Ci O.OOE+00 O.OOE+00 Rb-88 ci O.OOE+00 O.OOE+00 Rb-89 Ci O.OOE+00 O.OOE+00 Sr-91 Ci O.OOE+00 O.OOE+00 Sr-92 ci O.OOE+00 O.OOE+00 Y-92 Ci O.OOE+00 O.OOE+00 Zr-97 ci O.OOE+00 O.OOE+00 Nb-97 Ci O.OOE+00 O.OOE+00 Tc-99m Ci O.OOE+00 O.OOE+00 Mo-99 Ci O.OOE+00 O.OOE+00 Sb-122 Ci O.OOE+00 O.OOE+00 Te-129 Ci O.OOE+00 O.OOE+00 Te-132 Ci O.OOE+00 O.OOE+00 Cs-138 ci O.OOE+00 O.OOE+00 La-140 Ci O.OOE+00 O.OOE+00 Pr-144 Ci O.OOE+00 O.OOE+00 W-187 Ci O.OOE+00 O.OOE+00 Np-239 ci O.OOE+00 O.OOE+00 TOTAL FOR PERIOD ci O.OOE+00 O.OOE+00 l7

4 ~

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT 4 2 SEMIANNUAL REPORT JANUARY 1, 1992 THROUGH JUNE 30, 1992 TABLE 3.7-2 GASEOUS EFFLUENTS GROUND LEVEL RELEASES Nuclide s Continuous Mode Batch Mode Released Unit QTRC1 QTR42 QTR41 QTRC2

1. Fission Gases AR-41 ci O.OOE+00 O.OOE+00 2.68E-01 2.34E-01 KR-85M ci 5.03E-01 5.70E-,01 5.86E-02 3.16E-02 KR-85 ci O.OOE+00 O.OOE+00 1 69E+00 1.27E+00 KR-87 ci 4.50E-01 O.OOE+00 2 '9E-03 7.82E-04 KR-88 ci 1.12E+00 O.OOE+00 1 70E-02 1.79E-02 KR-89 ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 KR-90 ci O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 XE-127 ci O.OOE+00 O.OOE+00 0 OOE+00 '.OOE+00 XE-l.31M ci O.OOE+00 O.OOE+00 1.64E+00 1.14E+00 XE-133M ci O.OOE+00 2.00E+00 1.25E+00 1.53E+00 XE-133 ci 6.83E+01 2.15E+02 1 28E+02 1.17E+02 XE-135M ci O.OOE+00 O.OOE+00 O.OOE+00 0 ~ OOE+00 XE-135 ci 6.36E+00 8.87E+00 5 82E-01 1.99E+00 XE-137 ci O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 XE-138 ci O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 TOTAL FOR PERIOD 7.67E+01 2.26E+02 1.34E+02 1 ~ 23E+02
2. Zodines I-131 ci 1 '3E-03 2.27E-03 I-132 ci O.OOE+00 O.OOE+00 I-133 ci 4.45E-03 5.66E-03 I-134 ci 0 OOE+00 O.OOE+00 I-135 ci O.OOE+00 O.OOE+00 TOTAL FOR PERIOD ci 5.48E-03 7.93E-03
3. Particulates ( > 8 Days)

Cr-51 ci O.OOE+00 O.OOE+00 Mn-54 ci O.OOE+00 O.OOE+00 Fe-55 ci O.OOE+00 O.OOE+00 Co-57 ci O.OOE+00 O.OOE+00 Co-58 ci O.OOE+00 8.27E-07 Fe-59 ci O.OOE+00 O.OOE+00 Co-60 ci O.OOE+00 O.OOE+00 Zn-65 ci O.OOE+00 O.OOE+00 Zr-95 ci O.OOE+00 O.OOE+00 Nb-95 ci O.OOE+00 O.OOE+00

II FLORIDA POWER 8 LIGHT COMPANY ST. LUCIE UNIT 4 2 SEMIANNUAL REPORT JANUARY 1, 1992 THROUGH JUNE 30, 1992 TABLE 3.7-2 GASEOUS EFFLUENTS GROUND LEVEL RELEASES (CONTINUED)

Nuclides Continuous Mode Released Unit QTR01 QTR42

3. Particulates ( > 8 Days) (continued)

Sr-89 Ci 0 ~ OOE+00 0 ~ OOE+00 Sr-90 Ci O.OOE+00 2.93E-07 Y-90 Ci O.OOE+00 2.93E-07 Ru-103 Ci O.OOE+00 O.OOE+00 Ag-110 Ci O.OOE+00 O.OOE+00 Sn-113 Ci 0 ~ OOE+00 0 ~ OOE+00 Sb-124 Ci O.OOE+00 O.OOE+00 Sb-125 Ci O.OOE+00 O.OOE+00 Te-129m Ci 0 OOE+00 O.OOE+00 Cs-134 Ci O.OOE+00 O.OOE+00 Cs-136 Ci O.OOE+00 0 ~ OOE+00 Cs-137 Ci O.OOE+00 O.OOE+00 Ba-140 Ci O.OOE+00 O.OOE+00 Ce-141 Ci O.OOE+00 O.OOE+00 Ce-144 Ci O.OOE+00 O.OOE+00 TOTAL FOR PERIOD O.OOE+00 1.41E-06

4. Particulates ( < 8 Days)

Mn-56 Ci O.OOE+00 O.OOE+00 Ni-65 Ci O.OOE+00 O.OOE+00 Br-82 Ci O.OOE+00 O.OOE+00 Rb-88 Ci O.OOE+00 O.OOE+00 Rb-89 Ci 0 ~ OOE+00 O.OOE+00 Sr-91 Ci O.OOE+00 O.OOE+00 Sr-92 Ci O.OOE+00 O.OOE+00 Y-92 Ci O.OOE+00 O.OOE+00 Zr-97 Ci O.OOE+00 O.OOE+00 Nb-97 Ci O.OOE+00 O.OOE+00 Tc-99m Ci O.OOE+00 O.OOE+00 Mo-99 Ci O.OOE+00 O.OOE+00 Sb-122 Ci O.OOE+00 0 ~ OOE+00 Te-129 Ci O.OOE+00 O.OOE+00 Te-132 Ci O.OOE+00 O.OOE+00 Cs-138 Ci O.OOE+00 0 OOE+00 La-140 Ci O.OOE+00 0 OOE+00 Pr-144 Ci O.OOE+00 O.OOE+00 W-187 Ci O.OOE+00 0 OOE+00 Np-239 Ci O.OOE+00 O.OOE+00 TOTAL FOR PERIOD O.OOE+00 O.OOE+00

FLORIDA POWER AND LIGHT COMPANY ST. LUCIE PLANT SEMI-ANNUAL REPORT JANUARY 1q 1992 THROUGH JUNE 30'992 UNITS 1 AND 2i TABLE 3 '

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

1. Type of Waste Unit 6 Mo. Period Error%
a. Spent Resin, M3 5.358 E+1 Process Filters Ci 2.366 E+2 2.0 E+1
b. Dry Compressible M3 ~ 3.067 E+1 Waste (Note 5) Ci 4.450 E+0 2.0 E+1
c. Irradiated M3 0 Components Ci 0
d. Other
1. Non-Compressible M3 4.851 E+0 Metal (DAW)(Note 6) Ci 5.119 E-1 2.0 E+1
2. Soil/Grit M3 2.624 E+1 (Notes 5 and 6) Ci 3.001 E-3 2. 0 E+1
2. Estimate of Major Nuclide Composition (By Type of Waste)

Category Nuclides

'a ~ Cs 137 3.06 E+1 Cs 134 1.79 E+1 Ni 63 1.74 E+1 Fe 55 1.36 E+1 Co 60 1.18 E+1 Co 58 4.00 E+0 Mn 54 1.80 E+0 Sb 125 1.70 E+0

b. Cs 137 3.37 E+1 Co 60 2.99 E+1 Cs 134 1.38 E+1 Ni 63 1.11 E+1 Fe 55 7.14 E+0 Zr 95 1.23 E+0 Co 58 8.60 E-1 c ~ N/A
  • N/A *

'E Category Nuclides d.l. Co 60 4.76 E+1 Fe 55 3;04 E+1 Cs 137 1.02 E+1 Co 58 2.98 E+0 Ni 63 2.94 E+0 Cs 134 2.71 E+0 dO 2 ~ Cd 109 2.66 E+1 Cs 137 2.30 E+1 Fe 55 2.27 E+1 Co 60 1.15 E+1 Sr 89 5.20 E+0 Cs 134 3.80 E+0 K 40 2.27 E+0 H 3 1.57 E+0 Ni 63 1.13 E+0

3. Solid Waste Disposition No. of Shipments Mode of Transportation Destination Sole Use Truck Barnwell, SC Sole Use Truck S.E.G.

Oak Ridge, Tenn.

Sole Use Truck Quadrex Oak Ridge, Tenn.

B. Irradiated Fuel Shipments No. of Shipments Mode of Transportation Destination N/A * ~

N/A *

  • N/A = Not Applicable

SEMI-ANNUAL REPORT JANUARY 1~ 1992 THROUGH JUNE 30~ 1992 UNITS 1 AND 2i TABLE 3 9 (CONT1NUED)

Waste Total Total Principal Type of Waste Category Type of Solidi-Class Volume Curies Radionuclides (Note 3) Reg-- Container fication Cubic (Note 1) (Notes 1 2) guide (Note 4) Agent Ft.

1 '1 Class 877.2 5.826E-1 N/A PWR Compactible 1.b Non- None A Trash (Note 5) Specifi-cation Strong Tight Package Class 171. 32 5. 119E-1 N/A PWR Non- 1.d. 1 Non- None A Compactible Specifi-Trash (Note 6) cation Strong Tight Package Class 926.65 3.001E-3 N/A Contaminated 1.d.2 Non- None A Soil/Grit Specifi-cation Strong Tight Package Class 1445.9 1.866E-2 N/A PWR Ion- 1 a Non- None A Exchange Resin Specifi-cation Strong Tight Package

EW i/ PZ

SEMI-ANNUAL REPORT JANUARY 1 g 1992 THROUGH JUNE 3 0 ~ 1992 UNITS 1 AND 2~ TABLE 3 9 (CONTINUED)

Waste Total Total Principal Type of Waste Category Type of Solidi-Class Volume Curies Radionuclides (Note 3) Reg- Container fication Cubic (Note 1) (Notes 1 & 2) gllide (Note 4) Agent Ft. 1 ~ 21 Class 205.8 3.868 Ni63, Sr90, PWR Non- 1.b NRC .None A Cs137 Compacted Trash Certified LSA Type A

Class 205.8 2. 171 Ni63, Cs137 PWR Zon- l.a NRC None A Exchange Resin Certified LSA Type A

Class 120.3 20'.398 I C14I 129 I PWR Process 1.a NRC None C Pu241, TRU, Filters Certified Co60, Ni63, Type B Sr90, Cs137, Sum of Nuclides with Tl/2 < 5 years Class 120.3 214.046 C14, Pu241, PWR Zon- 1.a NRC None C Co60, Ni63, Exchange Resin. Certified Sr90, Cs137, LSA Type Sum of A Nuclides with T1/2 '< 5 years

,fbi

~ I

FLORIDA P0%I'ER AND LIGHT COMPANY ST ~ LUCIE PLANT SEMI-ANNUAL REPORT JANUARY 1~ 1992 THROUGH JUNE 30@ 1992 UNITS 1 AND 2g TABLE 3 ' (CONTINUED)

SOLID WASTE SUPPLEMENT Note 1: 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 quidelines outlined in the Low Level Waste

.Licensing Branch Technical Position (BTP) on Radioactive Waste Classification (5/11/83) for these determinations.

The most frequently used techniques for determining the total curie quantity in a package are the dose to curie methods and the (concentration) x (volume or mass) calculations. Where appropriate, engineering type activation analyses may be applied. Since each of the above methodologies involves to some extent qualitative parameters, the total curie quantity is considered to be an estimate.

The composition of radionuclides in* the waste is determined by both on-site analyses for principal gamma emitters and periodic off-site analyses for other radionuclides. The on-site analyses are performed either on a batch basis or on a routine basis using reasonably representative samples as appropriate for the waste type.

Off-site analyses are used to establish scaling factors or other estimates for radionuclides such as 3H, 14C, 99TC, 129I, TRU, 241Pu, 242Cm, 63Ni, 55Fe, and 90Sr.

Note 2: "Principal Radionuclides" refer to those radionuclides contained in the waste in concentrations greater than .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 Requirements for Land Disposal of Radioactive Waste".

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

Note 5: The volume and activity listed for Dry Compressible Waste and Soil/Grit represent the quantity of material that during the reporting period was sent to the Barnwell, South Carolina burial facility. This material was shipped to a contracted vendor for volume reduction prior to final disposal at the Barnwell, South Carolina burial facility. During the reporting period, four shipments of

e (

d

Dry Compressible Waste (3,680 cubic feet, 9.377E-1 curies) and contaminated soil (276 cubic feet, 9.050E-5 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 and soil/grit represent the quantity of material that during the reporting period could not be recycled by the contracted vendor and required disposal at the Barnwell, South Carolina burial facility. During the reporting period, seven shipments of non-compressible metal waste (1,740 cubic feet, 5.772E-2 curies), secondary bead resin (1,241 cubic feet, 7.695E-4 curies) and soil/grit (1,288 cubic feet, 1.162E-3 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.

ly II

(Reguired by Technical Specification 6.13)

~d During the reporting period changes were made to the St. Lucie Plant Process Control Program, Administrative Procedure No.

0520025. These changes were reviewed by the Facility Review Group (FRG) on June 9, 1992, and approved by the St. Lucie Plant General Manager on June 12, 1992.

The procedure was changed to authorize the use of the Pacific Waste System Group's Resin Drying (dewatering) system. The rationale for the changes was as follows:

1~ This change would allow the use of an alternative resin transfer/drying/dewatering system that produces a waste form that meets the criteria of 10 CFR 61 and the Barnwell, South Carolina disposal facility.

2. By having an alternative method of drying/dewatering spent resins, the licensee would not be tied to one vendor for disposal liners and/or transport packaging.

3 ~ The time needed to dewater/dry resins could be reduced.

This, in turn, would minimize the time that a transport packaging would be held on-site. This would effectively reduce the cost associated with the transportation of radioactive waste. Also, it would make that transport packaging available for the licensee and other users on a more timely basis.

4 Finally, with the potential loss of the Barnwell, South Carolina disposal facility imminent, the licensee wanted to secure an alternative method of drying spent resins that would produce a waste form that could be recovered and/or reprocessed as necessary to meet the future disposal site waste form criteria.

To ensure conformance to existing disposal waste form criteria, the licensee did the following:

Received and reviewed the Nuclear Packaging Proprietary Topical Report "TP-02-P-A for Resin Drying" as submitted to the Nuclear Regulatory Commission.

2 ~ Had the dewatering system vendor come to the St. Lucie Plant to evaluate the various spent resin waste streams and plant resin samples. These evaluations were performed by an engineering representative of the vendor to determine the suitability of the resin drying system for use at the St. Lucie Plant, and where applicable, to determine appropriate processing times and relative humidity end points for each of the resin waste streams as evaluated.

3. Had the vendor provide the services of a Field Project Manager to the St. Lucie Plant Health Physics/Radwaste staff to train them on the proper operation of the resin

transfer/drying/dewatering system.

v M + fV

Retrieved from "https://kanterella.com/w/index.php?title=ML17227A585&oldid=2436333"