ML17215A789

Combined Semiannual Radioactive Effluent Release Rept, Jul-Dec 1984.

ML17215A789
Person / Time
Site:	Saint Lucie
Issue date:	12/31/1984
From:	FLORIDA POWER & LIGHT CO.
To:
References
NUDOCS 8503200578
Download: ML17215A789 (37)

Text

r'e , REGULATORY 1NFORNATION DISTRIBUTION SYSTEM g fP ~tt ~.

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mr ACCESSION NOP:850320057d DuCeDATE: 84/12/31 NOTARIZED: NO FACI<:50-335 St Lucie~lantF Uni t p F orida

~ 1 1 Power 5 Light Co, 05000335 50-589 St. LucJe Plant-,Unit 2, Florida Power 8 Light Co. 05000589 AUTH.frAlrE AUT4OR AFFILIATIOrf F or i da Power 1 R Light Co ~

REC I P NAHEr

~ REC IP Ir N I AF F IL I'ATION SUSJECT: "Combinedl Sem.iannua.r Radioactive Effluent Release Rept, Ju-l--Dec, 198(."

DISTRIBUTION COOL:: IE25L COPIES RECEIVED:LTR ENCL P

SIZEa TITLE: Periodic Environ monitoring Rept (50 DKT) Annual/Semiannua>/Effluent/

NOTES: 05000335 OL:02/01/76 0500038'St OL:04/06/83 RFC IPIE.NT COPIES RE.C IP IENT COPIES I 0 CODE/4At'E LT TP. ENCL lD CODE/NAHE LTTR ENCL NRR OR83 BC 04 NRR ORB3 BC Ott INTERNAL: ACRS 1> AEQD I E F ILK. 01 NRR/DV/EEB 08 NRR~ I fit NRR/DSI/METB

/ 10 RGN2/DRSS/EPRPB f< DANI/NIB EXTERNAL: LPDR NRC PDR 02 TOTAL NUMBER OF COPIES REVUIRED: LTTR ENCL 26

FLORIDA P(NER & LIGHT QMPAHY SR ~ LUCIE PLANT UNIT NO I & 2 LICENSE NO DPR-67 & NPF-16 CABINED SEHI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD Jul 1, 1984 THROUGH December 31, 1984 8503200578 841231 PDR ADQCK 05000335 R

~ DESCRIPTION JULY 1, 1984 VISITOR DOSE ASSESSMENT....

PROCESS CONTROL PROGRAM REVISIONS.

GAS ANALYZER INOPERABLE REPORT.

LIQUID EFFLUENT:

UNIT UNIT lo FLORIDA POWER ET. LUOIE UNII NO.

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THROUGH

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os SEMIANNUAL REPORT TABLE OF CONTENTS EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION.oo ~ oo OFFSITE DOSE CALCULATION MANUAL REVISIONS.........

SOLID WASTE AND IRRADIATED FUEL

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SHIPMENTS' LIGHT COMPANY

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SU&fATION OF ALL RELEASES; NUCLIDE SUMMATION BY QUARTER, DOSE SUMMATION

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2o..o....oooo..o..oo..oooooooo.oo.ooo.o.oo.ll-l4 GASEOUS EFFLUENT SUMMATION OF ALL RELEASES, I

DECEMBER 31

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NUCLIDE SUMMATION BY QUARTER, DOSE SUMMATION PAGE

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.~5 7-10 o6 UNIT 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 15 17 UNIT 2o.........o.oooooo......o.o...o.ooooo.oo..18-20 SOLID WASTE SHIPMENT SUMMATIONoo ~ ..... ...........

~ ~ ......21-22 PROCESS CONTROL PROGRAM PAGE REVISIONS. ~ ~ ~ ~ ~ ~ ~ ~ ~ o.ATTACHMENT A

Page 1 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 2 X 10 micro curies/ml total activity.

b. The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS shall be limited to-'uring 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.

• 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 mrad for gamma radiation and 10 mrad for beta radiation and, during any calendar year to <

10 mrad for gamma radiation and < 20 mrad for beta radiation.

• c The dose to a MEMBQt 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 an8 beyond the SQTE 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 calculations are based on The STS LCO dose limits are therefore included in Item 1 of the report, for information only.

Page 2 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 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 ' Estimate of Errors

a. Sampling Error The error associated with volume measureaant devices, flow measuring devices, etc. based on calibration data and design tolerances has been conservatively estimated collectively to be less than + 10%.

b. Analytical Error for Nuclides

~Te ~Avera e Maximum Liquid +9% +30%

Gaseous +10% +35%

TABLE 3 ~ 1 RADIOACTIVE LI UID EFFLUENT SAMPLING AND ANALYSIS LIQUID SAMPLING TYPE OF METHOD OF SOURCE FRE UENCY ANALYSIS ANALYSIS Each Batch Princi al Gamma Emitters .r .a.

Monitor Monthly L.S.

Tank Com osite Gross Al ha G F,P, Releases Quar ter ly SR-907 SR-89 C S ~

Com osite FE-55 Continuous No continuous activity releases Releases for this re ortin eriod 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.ST Chemical Separation G.F.PE Gas Plow Proportional Counting

Page 3 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (continued) 4.1 Measurements and Approximations of Total Radioactivity (continued)

F 1.b (continued)

TABLE 3.2 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS GASEOUS SAMPLING TYPE OF METHOD OF SOURCE FRE UENCY ANALYSIS ANALYSIS Waste gas Principal (G)

Decay Tank Each Tank Gamma Releases Emit ters .h.a.

Con tainme nt Principal Gamma (G)

Purge Each Purge Emitters .h.a.

Releases H-3 L S Principal Gamma (G, C, P)-

Weekly Emit ters .h.a.

H-3 L,Si Monthly Gross P-GFP Plant Composite Alpha Vent (Particulates)

Quarterly SR-90 C S Composite SR-89 (Particulates)

G Gaseous Grab Sample C Charcoal Filter Sample P Particulate Filter Sample L S ~ Liquid Scintillation Counting C S ~ Chemical Separation p.h.a Gamma spectrum pulse height analysis using Lithium Germanium detectors, All peaks are identified and quantified G FOP Gas Flow Proportional Counting

Page 4 FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT NO. 1 & 2 SEMIANNUAL REPORT July 1, 1984 THROUGH December 31 1984 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (continued) 5~ Batch Releases

5. 1 Liquid UNIT 1 UNIT 2

a. Number of batch releases: 22.5 22. 5

b. Total time period of batch releases: 9941

~c)~ MINJTES

c. Maximum time period for a batch release: 660 660 MINUTES

d. Average time period for a batch release: 442 442 MINUTES e Minimum time period for a batch release: 287 287 MINUTES f ~ Average stream flow during periods of release of effluent into a flowing stream. 8.18E05 ~~8I~ GPM ALL LIQUID RELEASES ARE SlMMARIZED IN TABLES 5.2 Gaseous

a. Number of batch releases: 16 39

b. Total time period for batch releases: ~5 12119 MINUTES c, Maximum time period for a batch release: 1514 2145 MINUTES

d. Average time period for batch releases: 311 MINUTES

e. Minimum time period for a batch release: 8 30 MINUTES ALL GASEOUS WASTE RELEASES ARE SlHMARIZED IN TABLES

6. Unplanned Releases 6.1 Liquid a Number of releases: 0

b. Total activity releases: 0 CURIE S 6.2 Gaseous

a. Number of releases: 0

b. Total activity released: 0 CURIE S 6.3 See attachments (if applicable) for:

a. A description of the event and equipment involved b Cause(s) for the unplanned release

c. Actions taken to prevent a recurrence, d Consequences of the unplanned release.

Page 5 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 & 2 SEMIANNUAL REPORT JULY 1. 1984 THROUGH DECEMBER 31, 1984 EFFLUENT AND WASTE DISPOSAL -'SUPPLEMENTAL INF01UVTION (continued) 7 ~ Assessment of radiation dose from radioactive effluents to the GENERAL PUBLIC due to their activities inside the site boundary assume the visitor was onsite for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />, at an average distance of 0.3 Kilometers in the worst dispersion direction, and received exposure from each of the two reactor units on the St. Lucie Site.

VISITOR DOSE RESULTS FOR CALENDAR YEAR 1984 WERE:

GASEOUS PARTICULATES & IODINE EXPOSURE NOBLE GAS EXPOSURE ORGAN DOSE (mrem) Gamma Air Dose 4.6E-2 mrads Bone 5 'E-5 Beta Air Dose 9.2E-2 mrads Liver 8.5E-4 Thyroid 1.9E-2 Kidney'ung 3.6E-4 7.7E-4 GI-LLI 7.9E-4 Total Body 8.2E-4

8. Offsite Dose Calculation Manual Revisions:

No changes were issued to the ODCM during the period July 1, 1984 December 31, 1984.

9. Solid Waste and Irradiated Fuel Shi ments No irradiated fuel shipments were made from the site. Common solid waste from St. Lucie Units 1 and 2 were shipped )ointly. A summation of these shipments is given in Table 3.9 of this report.

10. Process Control Pro ram Revisions Revisions 03 and 04 were implemented during this reporting period. The revised revisions are included in Attachment-A of this report with explanations provided.

Page 6 ll. Waste Gas Deca Tank Ex losive Gas Monitorin S stem Ino erable Unit No. 1 This information is provided pursuant to St. Lucie, Unit No. 1 Technical Specification 3.3.3.10.b The oxygen monitors required by St. Lucie Unit No. 1 Technical Specifications 3.3.3.10 were inoperable from October 25, 1984 until December 6, 1984. This condition resulted in less than the minimum number of channels operable required by Table 3.3-13 in excess of the time permitted by Table 3.3-13 for the Waste Gas Decay Tank Explosive Gas Monitoring System.

The cause of the inoperability was due primarily to excessive amounts of moisture in the system which resulted in the failure of the oxygen detectors.

A number of factors contributed to the delay in returning the Waste Gas Decay Tank Explosive Gas Monitoring System to operable status. During the investigation of the instrument failures it was determined that additional maintenance would be required in order to restore the system reliability. This additional maintenance involved replacing a pump and eliminating suspected system leakage. Some of-the required spare parts to repair the system were not initially available on site. This contributed to the delay in restoring the system's operability. The remaining time is attributed to the extensive system maintenance which proved to be necessary to achieve the desired reliability.

The St. Lucie P1ant is conducting an evaluation of the system's design and operation with an objective to preclude similar failures in the future. In addition, to avoid delays in system maintenance the quantity of spare parts to be stocked has been increased.

During the period of time that the explosive gas monitoring system was inoperable, the conditions of Technical Specification 3.11.2.5 were maintained by monitoring oxygen'n the on service waste gas decay tank with the lab gas partitioner in accordance with Table 3.3-13, ACTION 5, of Technical Specification 3.3.3.10.

Page 7 FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO 1 SEMIANNUAL REPORT July 1, 1984 THROUGH December 31 1984 TABLE 3 '-1 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES U E

)A, Fission and Activation Products

1. Total Release (not including 8. 84E-01

4. 20E-01 tritium, gases, alpha) CI

2. Average diluted concentration durin eriod uCI/ml 1.51E-08 4.89E-08 I B. Tritium 1~ Total Release CI 5 95E401 1. OOE402 2~ Average diluted concentration durin eriod uCI/ml 2.14E-06 CD Dissolved and Entrained Gases 1~ Total release CI 3.72E-01 . 9.07E-Ol

2. Average diluted concentration durin eriod uCI/ml 1.34E-OB . 5.38E-08 D. Gross Alpha Radioactivity 1.'otal Release CI E. Volume of Waste Released 1.60E+06

( rior to dilution) Liters 1.13E406 F. Volume of Dilution Water Used Durin Period Liters 1.40Et10 1.69E+10

Page FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO. 1 SEMIANNUAL REPORT July 1, 1984 THRoUGH Oecember 31, 1934 TABLE 3.4-1 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT QUARTER QUARTER UARTER I QUARTER fk Na-24 cz 0 0 5.65E-04 6.80E-03 CR-51 CI 0 0 2.77E-04 7.90E-03 MN-54 CI 0 0 2.63E-03 1.43E-02 MN-56 I cz Co-57 CI 0 0 Co-58 CI I o 1.35E-01 Co-60 Cz I 0 0 6.15E-02 3.03E-02 Fe-59 Cz 0 0 1. 5E- 2 9.35E-03 Fe-55 I CI I 0 2.36E-02 5.45E-02 SN-113 I CI Sb-122 cz 0 I 0 1.86E-03 1.46E-02 Sb-124 CI 0 0 1. 61E-03 W-187 Cz 0 0 2.47E-04 N -239 cz 0 I-131 Cz 0 1.88E-01 1.30E-01 cz I2.57E-05 0'-132 0 0 I-133 I CI I 0 0 2. 13E-02 1.94E-02 I-134 Cz 0 0 I-135 cz 0 0 2.62E-04 2.30E-03 Rb-88 CI 0 0 5. 5 -04 zr-95 Cz 0 0 9.65E-05 1.37E-03 Nb-95 cz 0 0 2.36E-04 3.49E-03 ZR-97 cz 0 0

'I Nb-97 Cz 0 0 Mo-99 cz 0 0 Tc-994 I 0 0 1. 36E-03 2.47E-03 Cs-130 cz I 0 0 2.01E-03 Sb-125 czl 0 0 1.85E-03 1.57E-02 Cs-134 I CI 0 I3.65E-02 1.54E-01

Page FLORIDA POWER, & LIGHT COMPANY ST ~ LUCIE UNIT NO. 1 SEMIANNUAL REPORT Jul 1, 1984 THROUGH December 31 1984 TABLE 3 '-1 LIQUID EFFLUENTS (continued)

CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT QUARTER t UARTER 84 UARTEk 8 UARTER t4 )

Cs-136 CI 0 1.48E-03 1.53E-02 Cs-137 CI 0 7.50E-02 2.55E-01 Ba-140 I CI 0 8.10E-04 1.14E-03 La-140 CI 0 8.55E-05 5.95E-03 Sr-89 CI 0 1.22E-02 5.90E-03 Sr-90 CI 0 3.39E-04 2.35E-04 Y-90 CI 3.39E-04 2.35E-04 UNIDENTIFIED CI TOTAL FOR PERIOD ABOVE CI 0 4.20E-01 8.84E-01 N.-41 I CI 7.60E-05 9. 15E-04 KR-85 CI XE-131M CI 1.76E-03 2.92E-02 XE-133 I CI 3. 56E-01 8. 55E-01 XE-13 3M CI 5. 40E-03 9. 95E-03 XE-135 I CI 8.55E-03 1.23E-02 KR-85M CI XE-138 CI 0 0 mTAL FOR 3.72E-01 9.07E-01 PERIOD ABOVE CI NOTE: If no value is entered for a nuclide, the value equals zero Curies.

Page 10 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 SEMIANNUAL REPORT Janua 1, 1984 THROUGH December 31, 1984 TABLE 3.5-1 LIQUID EFFLUENTS DOSE SUMMATION Age Group: Adult Location.'ny Adult Exposure Interval: From Janua 1, 1984 through December 31, 1984 FISH & SHELLFISH CALENDAR YEAR PATHWAY TO DOSE ORGAN (mrem)

Bone 1.24 E-l Liver 4 ~ 60 E-1 Thyroid 2.30 E-1 Kidney 1.78 E-2 Lung 4.59 E-l GI-LLI 4.41 E-l T. Body 1.56 E-l

Page 11 FLORIDA POWER & LIGHT COHPANY ST ~ LUCIE UNIT NO. 2 SEMIANNUAL REPORT July 1, 1984 THROUGHOecember 31, 1984 TABLE 3.3-2 LIQUID EFFLUENTS SlMMATION OF ALL RELEASES NUCL DES RELEASED UN T QUARTER 3 QUARTER 4 A.,Fission and Activation Products

1. Total Release (not including tritium, gases, alpha) CI 4.20E-01 8.84E-01

2. Average diluted concentration durin eriod ucI/ml 1. 51E-08 4. 89E-08 B. Tritium 1 Total Release CI 5. 95E+01 1.00E~02

2. Average diluted concentration durin eriod ucI/ml 2.14E-06 5.93E-06 C. Dissolved and Entrained ases

1. Total release CI 3.72E-01 9.07E-01 2~ Average diluted concentration I durin eriod ucZ/ml 1.34E-08 5.38E-08 D. Gross Alpha Radioactivity 1~ Total Release CI 0 0 E. Volume of Waste Released (prior to dilution) Liters 1.13E+06 1.60E>06 F. Volume o Dilution Water Used Durin Period Liters 1. 40E+10 1. 69E110

Page FLORIDA POWER 6 LIGHT C(MPANY ST ~ LUCIE UNIT NO 2 SEMIANNUAL REPORT July 1, 1984 THROUGH December 31, 1984 TABLE 3 '-2 LIQUID EFFLUENTS NUCLIDES RELEASED Na-24 (R-51 UNIT CI CI 0,

CONTINUOUS MODE QUARTER 0

UARTEK 0

0 5.65E-O BATCH MODE UARTEK UARTEK 6.80E-03 MN-54 I cz - 2 MN-56 CI Co-57 I cz cz 1.43E-02 Co-60 CI 6.15E-02 3.03E-02

.Fe-59 cz I 1. 15E-02 9.35E-03 Fe-55 CI 2 '6E-02 5.45E-02 SN-113 CI 0 0 Sb-122 cz I 1. 86E-03 1. 46E-02 Sb-124 CI 0 1.61E-03 W-187, CI 0 2.47E-04 N -239 CI 0 0 I-131 CI 1.88E-01 1.30E-01 I-132 cz I 0 2.57E-05 I-133 CI 0 2. 13E-02 1.94E-02 I-134 CI 0 0 I-135 CI I 0 2.62E-04 2.30E-03 Rb-88 CI 0 5. 15E-04 zr-95 CI 9.65E-05 1.37E-03 Nb-95 cz I 2.36E-04 3.49E-03 zR-97 CI 0 0 Nb-97 CI 0 0 Mo-99 cz I 0 '0 Tc-99M I CI 1.36E-03 2.47E-03 Cs-138 CI 0 2. 01E-03 Sb-125 CI 1.57E-02 Cs-134. CI 3.65E-02 1.54E-01

Page FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO. 2 SEMIANNUAL REPORT July 1, 1984 THR0UGH December 31, 1984 TABLE 3 '-2 LIQUID EFFLUENTS (continued)

CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT QUARTER fi'UARTER QUARTEK 0 QUARTER /h I Cs-136 CI 0 I 0 1.48E-03 1.53E-02 Cs-137 CI 7.50E-02 2.55E-01 Ba-140 CI 0 0 8. 10E-04 1. 14E-03 La-140 CI 0 0 8.55E-05 5.95E-03 Sr-89 CI 0 0 1.22E-02 5.90E-03 Sr-90 CI 3.39E-04 2.35E-04 Y-90 CI 3.39E-04 2.35E-04 UNIDENTIFIED CI TOTAL FOR 8.84E-01 PERIOD "ABOVE CI 4. 20E-01 I AR-.41 CI 0 7.60E-05 9. 15E-04 I

KR-85 CII 0 Jo 0 I I XE-131M CI I 0 1. 76E-03 2. 92E-02 I XE-133 ) CI 0 3.56E-01 8.55E-Ol l XE-13 3M C I 0 0 5.40E-03 9.95E-03 l XE-135 j CI 0 8.55E-03 1.23E-02 I I

KR-85M CI 0 0 I XE-138 CI TOTAL FOR PERIOD ABOVE CI 3. 72E-01 9.07E-01 NOZE: If no value is entered for a nuclide, the value equals zero Curies.

page l4 FLORIDA POWER & LI8GHT COMPANY ST. LUCIE UNIT NO, 2 SEMIANNUAL REPORT Januar 1, 1984 THROUGH December 31, 1984 TABLE 3.5-2 LIQUID EFFLUENTS DOSE SUMMATION Age Group: Adult Location: Any Adult Exposure Interval: From Januar 1, 1984 through 'ecember 31, 1984 FISH & SHELLFISH CALENDAR YEAR PATHWAY TO DOSE ORGAN (mrem)

Bone 1.24 E-l Liver 4.60 E-1 Thyroid 2.30 E-1 Kidney 1.78 E-2 Lung 4.59 E-1 GI-LLI 4.41 E-l T. Body 1.56 E-l

Page 15 FLORIDA POMER & LIGHT C(MPANY ST ~ LUCIE UNIT NO, 1 SEMIANNUAL REPORT 98 " ~0b TABLE 3.6-1 GASEOUS EFFLUENTS - SlHMATION OF ALL RELEASES NUCLIDES RELEASED UN IT QUARTER 3 QUARTER 4 )

)A. Fission and Activation Gases

1. Total Release I CI 1 60E<04 1.59E~04 2.02E403 2.00E&03 2~ Avera e Release Rate for Period CI/

BE Iodines

1. Total Iodine-131 CI 1.93E-01 3.00E-02 Avera e Release Rate for Period ucI/sec 3. 7E-03 2.

C, Particulates 1 ~ Particulates T-1/2 0 8 Days )

CI 1.81E-03'.

2.27E-04 I E-0 2.86E-05 Average Release Rate for Period )

ucI/sec

3. Gross Alpha Radioactivity CI 1.07E-12 3. 32E-21 D Tritium E+02 1~ Total Release CI

2. Avera e Release Rate for Period uCI/sec 3.47Et01 5.49E+01

Page 16 FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO 1 SEMIANNUAL REPORT TABLE 3.7-1 GASEOUS EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT QUARTER QUARTM UARTEK UARTER 1 ~ FISSION GASES AR-41 CI GI 0 5.1E0 5. OE KR-85M CI 1. 85E402 2.20E402 KR-87 CI 5.92E+01 6.1 f401

2. Ei01 l. Et0 XE-131M CI 3.61E001 8.57E 00 2.99E 00 4.05E&01 XE-13 3 Cr 1.3 E<0 1.1 E+0 E+

XE-133M CI 8.28f<01 4.4 Et01 1.83E 0 XE-135 CI 1.70EH03 1.76E+03 4.07ft02 l. 9E 0 XE-135M GI l. 11 XE-13 CI 0 TOTAL FOR PERIOD ABOVE CI 1. 55E i04 1.35Ei04 5.36E&02 2.43ft03 2~ IODINES I-131 CI 1.93E-01 3.00E-02 I-13 3 CI I-1 5 CI TOTAL FOR PERIOD ABOVE CI 6. 13E-01 1. 09E-01

~ PARTICULATES Co-58 CI 0 Co-60 CI SR-90 CI 0 Y- 0 GI 0 GI I-133 CI 4.12E-03 1.04E-04 GI 0 TOTAL FOR PERIOD ABOVE CI 5.93E-03 3.31E-04

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 SEMIANNUAL REPORT Table 3.8-1 GASEOUS EFFLUENTS DOSE SUMMATION QUARTER 8 NA AGE GROUP: INFANT EXPOSURE INTRVAL: FROM Janua 1, 1984 THROUGH December 31, 1984 BONE LIVER THYROID KIDNEY LUNG GI-LII T. BODY PATHWAY (mrem) (mrem) (mr em) (mrem) (mrem) (mrem) (mrem)

Ground Plane (A) 0 0 0 0 0 0 9.5 E-4 Grass-Cow-Milk (B) 1.42 E-2 2.28 E-2 5.43 EO 6.80 E-3 5.8 E-3 6.53 E-3 1.56 E-2 Inhalation (A) 2.14 E-4 4.38 E-3 8.30 E-2 1.89 E-3 4.1 E-3 4 ~ 12 E-3 4.22 E-3 TOTAL 1.44 E-2 2 ~ 72 E-2 5 '1 EO 8.69 E-3 9.9 E-3 1.07 E-2 2.08 E-2 (A) SECTOR: WEST RANGE: 1.78 miles B) COW/GOAT SECTOR: WNW RANGE: Default, 4.25 miles QUARTER CALENDAR YEAR (ABOVE TIME INTERVAL) (mrad)

NOBLE GASES (mr ad)

Gamma Air Dose NA 3.05 E-1 Beta Air Dose 6.24 E-l Sector: West Range: 1.78 miles Note: The dose values above were calculated using actual meteorological data during the specified time interval with MET data reduced as per Reg. Guide 1.111, March 1976.

Page le FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO 2 SEMIANNUAL REPORT July 1 1984 THROUGH December 31 1984 TABLE 3 6-2 GASEOUS EFFLUENTS SlMHATION OF ALL RELEASES NUCLIDES RELEASED UN ZT QUARTER QUARTER A. Fission and Activation Gases 1~ Total Release CI 1.84'3

2. Avera e Release Rate for Period ucI/sec 2.31E+02 3.20E<02 (B Iodines 1~ Total Iodine-131 cz 7. 61E-03 2. 36E-01 (

2~ Avera e Release Rate for Period ucI/sec 9 '7E-04 2 '7E-02 C Particulates 1 ~ Particulates T-1/2 > 8 Days (

cz 6.5$ E-05 2.34E-04 2 Average Release Rate for Period (

ucZ/sec 8.29E-06 2.94E-05 3 ~ Gross Al ha Radioactivit cz 4 '8E-21 8 '0E-21 D. Tritium 1 Total Release cz 6.96E+01 1.64E>02 2~ Avera e Release Rate for Period ucz/sec

Page SEMIANNUAL REPORT TABLE 3.7-2

" D~

FLORIDA POWER 6 LIGHT COMPANY ST ~ LUCIE UNIT NO. 2 GASEOUS EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT QUART QUART M UARTER UART EK 1 ~ FISSION GASES AR-41 CI 1. E 4.00E-O CI 1. 79E+01 9.28E 00 9.48E-02 9.74E-O CI CI XE-131M CI 0 XE-1 CI 1.53E+03 .28E+03 XE-1 CI 5.39E 0 XE-135 CI 1.71E+02 1.20E 02 XE-1324 CI XE-138 cr TOTAL FOR PERIOD ABOVE CI 1.73E<03 1.42E003 1. 18E+02 8.98E 2 2 IODINES I-131 CI I-13 CI 1.90E-02 6.98 -02 CI TOTAL FOR PERIOD ABOVE CI 2.66E-02 3.06E-01 3 ~ PARTICULATES Co-58 CI Co-60 CI SR-90 CI Y-90 CI CI 6.59 - 5 CI CI OT 0 PERIOD ABOVE CI 6.59E-05 2.34E-04

FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMIANNUAL REPORT Table 3.8-2 GASEOUS EFFLUENTS DOSE SUMMATION QUARTER // NA AGE GROUP: INFANT EXPOSURE INTRVAL: FROM Janua 1, 1984 THROUGH December 31, 1984 BONE LIVER THYROID KIDNEY LUNG GI-LII To BODY PATHWAY (mrem) (mrem) (mrcm) (mrem) (mrem) (mrem) (mrem)

Ground Plane (A) 0 0 0 0 0 0 4.78 E-4 Grass-Cow-Milk (B) 1.51 E-2 2.00 E-2 5.78 E-O 5.4 E-3 2.10 E-3 2.79 E-3 1 ~ 25 E-2 Inhalation (A) 1.41 E-4 1.64 E-3 5.51 E-2 6.83 E-4 1.47 E-3 1.48 E-3 1 '0 E-3 TOTAL 1.52 E-2, 2.16 E-2 5.84 E-0 6. 1 E-3 3.57 E-3 4.27 E-3 1.46 E-2 (A) SECTOR: WEST RANGE: 1.78 miles B) COW/GOAT SECTOR: WNW RANGE: Default, 4.25 miles QUARTER CALENDAR YEAR (ABOVE TIME INTERVAL) (mrad)

NOBLE GASES (mr ad)

Gamma Air Dose 6.29 E-2 Beta Air 1.24 E-1 Dose'ector:

West Range: 1.78 miles NOTE: The dose values above were calculated using actual meteorological data during the specified time interval with MET data reduced as per Reg. Guide 1.111, March 1976.

Page 21 FLORIDA POWER 6 LIGHT COMPANY ET. LUCIE UNIT NO. I & 2 EENIANNUAL REPORT July 1, 1984 THROUGH December 31, 1984 TABLE 3 "

COMBINED SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 6-month Es t. Total

1. T e of waste Unit Pe riod Error, X

a. Spent resins, filter sludges m3 t 1.2E1 2.0E1 I eva orator bottoms, etc. Ci 7.0E2

b. Dry compressible waste; l >> )

6.6E2 l

2.0E1 l contaminated equip, etc. Ci 3.9E1

c. Irradiated components, I

control rods, etc. Ci

d. Other (describe) I m3 Ci

2. Estimate of major composition (by type of waste) a Co 60 Co - 58 Fe-- 55 3.0E1 Cs - 134 1.4E1

b. H-3 2.4E1 Co- 2.9E1 S--

S I - 131 4.1EO

3. Solid Waste Disposition Number of Shi ments Mode of Trans ortation Destination 10 SOLE USE TRUCK BARNWELL, S CN 12 SOLE USE TRUCK RICHLAND, WASH ~

BE IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shi ments Mode of Trans ortation Destination

FLORIDA POWER 5 LIGHT COHPANY ST. LUCIE UNIT NOS. I AND 2 EERIARRRIIL REPOSER JULY I, 1984 THROUGH DECEMBER 31, 1984 Solid Waste Supplement Total Total Note I Type Note 3 Type " 4 Solidification Waste Volume Curie Principal " of R. G. 1.21 of Agent Classification Cu-Ft ~oaottt Radionuclides Waste ~Cate or Container or Absorbent Class A 22,272 11.27 None PWR Trash l.b Non-Specification None Strong Tight Pkg.

Class A 780 25.04 63NI 90Sr 137C5 PWR Trash l.b NRC Certified None LSA > Type A Class 8 195 3.188 63Ni 90Sr p 137Cs PWR Trash l.b NRC Certi fied Hone LSA > Type A Class 8 195 278.61 14C 60Co 63Ni PWR Ion- l.a. NRC Certified None 90Sr Exchange Resins LSA > Type A Class 8 121 4.817 60Co 63Ni 90Sr PWR Filters I.a. NRC Certified None 131Cs Type 8 Class C 121 417.12 14C 60()

1 63Ni PWR lon- l.a. NRC Certified None 90sr, Cs Exchange Resins, Type 8

Pace 23 FLORIDA POWER 5 LIGHT COMPANY ST. LUCIE UNIT NOS. 1 AND 2 SEMIANNUAL REPOSER JULY 1, 1984 THROUGH DECEMBER 31, 1984 TABLE 3.9 Cont.

Solid Waste Supplement Note 1: The total curie quantity and radionuclide composition of solid waste shipped from the St. Luci e Plant are determined using a combination of qualitative and quantitative techniques. In general, the St.

Lucie Plant follows the guidelines outlined in the Low-Level Waste Licensing Branch Technical Position (BTP) on Radioactive Waste Classification (5/11/83) for these determinations.

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

The composition of radionuclides in the waste is determined by both on-site analyses for principal gamma emitter s, and periodic offsite analyses for other radionuclides. The onsite analyses are performed either on a batch basis or on a routi,ne basis using reasonably representative samples as appropriate for the waste type. Offsite analyses are used to a~tab/ash scaling factors or other estimates for radi onucl ides such as H, C Tc 129I TRU 1Pu t 242Cm 63Ni R

5 Fe.

and Note 2: "Principal Radionuclides" refers to those radionuclides contained in the waste in concentrations greater than .Ol times the concentration of that nuclide listed in Table 1 or .01 times the smallest concentration of that nuclide listed in Table 2 of 10CFR61.

Note 3: "Type of Waste" is generally specified as described in NUREG 0782, Draft Environmental Impact Statement on 10 CFR 61 "Licensing Requirements for Land Disposal of Radioactive Waste".

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

FLORIDA POWER 6 LIGHT COMPANY ST. LOUIE UNIT NO. I S 2 SEMIANNUAL REPORT ATTACHMENT' CHANGES TO PROCESS CONTROL PROGRAM DURING PERIOD JULY 1, 1984 THROUGH DECEMBER 31, 1984 A. 1. Paragraphs 3.1, 3.2.2, 3.2.3, 3.4.1, 3.4.3, 3.4.5, 3.4.8, 4.2, 5.3 and 6.4 of Revision 3 add to the process control program the waste form classification item per the implementation of 10 CFR, part 61 and 10 CFR 20,311.

2. Paragraphs 3.2.1.B and 3.2.1.C of Revision 4 make CNSI project num-bers consistent with references listed in 6.2 and 6.3.

3. Paragraph 6.1 of Revision 4 changed the Dewatering procedure to ~

Chem-nuclear Bead Dewatering procedure for CNSI 14-195 or smaller liners FO-OP-023.

B. The above changes were administrative changes and did not reduce the overall conformance of the dewatered bead resin to existing criteria for radioactive wastes.

C. Documentation of the review and acceptance of the changes by FRG is on the cover sheet of the attached procedure.

Page 1 of 5 FLORIDA POWER & LIGHT COMPANY ST+ LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025 REVISION 4

~ ~o TETLrE:

iNEGRMQiai GND use, controlled. Before PROCESS CONTROL PROGRAM ent is not 2EO REVIEW AND APPROVAL: 'f >n formabon with a cont venfy Reviewed by Facility Review Group December 28 1982 Approved by J. H Barrow (for) Plant Manager December 28, 1982 Revision 4 Reviewed by F R G <>4 iSd 4

.Approved by ant Manager 3 19 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

'R4 I~ 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 Operating Procedure No, 0520023, "Dewatering Radioactive Bead Resins" ~

BE CHEM-NUCLEAR SYSTEMS, IN'est procedure for Dewatering Conical Bottom Demineralizers and Resin Liners - Project Noo 11118 C CHEM-NUCLEAR SYSTEMS, IN'ab Record Sheet for Conical Bottom Demineralizers and Resin Liners >> Prospect No, 11118. /R4 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 ~

Page 2 of 5 ST, LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 4 PROCESS CONTROL PROGRAM 3eO SCOPE: (continued) 3 2 Discussion: (continu'ed) 3~ All radioactive waste shiped for land burial must beet the requirements of 10 CFR 20 311 regarding waste form classification and packaging This is implemented through procedure HP-47, "Classification of Radioactive Waste'aterial for Lend 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 1 Abso tion - The process of absorbing liquid radioactive waste mater a s onto an absorbent material, a final disposal package which contains radioactive bead resins material within cement-like material, such that the final product is a free-standing monolith 4 "Free Standin " Water - Liquid which is not retained by the waste orm, 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 Coritiol Pro am (PCP) - The Process Control Program s conta n t e 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 7 Visual Ins ection The direct observation of the bead resins uring t e ent re period of resin transfer as they are packaged in the final disposal container 8 Waste Form Classification - Classification of radioactive waste

Page 3 of 5 ST, LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 4 PROCESS CONTROL PROGRAM 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 10CPR20 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 fgor approval Procedures which are to be used must be controlled per the vendor's gA program, 4+3 In lieu of dewatering performed as per the Process Control Procedures, a visual inspection of the bead resin as it is transferred and of the final disposal container after loading may be performed if conditions permit, This inspection must be conducted in a manner that will assure that the free standing liquids will meet shipping, transportation and disposal site requirements, 4,4 All changes to the St ~ Lucie Plant Process Control Program must be reviewed and approved by the Facility Review Group before they become effective 4i5 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'

~ Documentation of the fact that the change has been reviewed and found acceptable by the Pacility Review Group 5+0 RESPONSIBILITIES:

5~1 It is the rdsponsibility of the Plan't Manager to assure that all necessary procedures, equipment and support are provided to properly implement the PCS 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

6+0 7+0

REFERENCES:

6,1 6 '

Bead FO-OP-023 'R4 ST PROCESS Dewatering Procedure LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, CONTROL PROGRAM for CNSI 14-195 REVISION 4 or smaller Lab Record Sheet for Conical Bottom Demineralizers Prospect No, 11118 liners-and Resin 6i3 Test Procedure for Dewatering Conical 'Bottom Demineralizers and 4

Resin Liners, Prospect No, 11118 '

Health Physics Procedure, HP-47, "Classification of Radioactive Waste RECORDS AND Material for Land Disposal" ~

NOTIFICATIONS:

Page 4 Liners, of 5 7 ' Records shall be as per St, Lucie Plant Operating Procedure No 0520023, "Dewatering Radioactive Bead Resins" ~

7,2 Notifications 1 it If 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 Supervisor. 'hysics 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,

Page 5 of 5 ST>> LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 4 PROCESS CONTROL PROGRAM 8 ' INSTRUCTIONS:

8,1 Dewatered radioactive bead resins:

1 Dispose of dewatered radioactive bead resins is limited to the following containers for which full scale dewatering tests have been conducted:

A CNSI Conical Bottom EnviroSAPE' High Integrity Container-PL6-80CR>>

B CNSI Conical Bottom EnviroSAPE' High Integrity Container-PL14-195CR>>

C,'NSI Conical Bottom EnviroSAPE' High Integrity Container-PL8-1 20CR>>

2, Dewater the container as per St>> Lucie Plant Operating Procedure No 0520023, "Dewatering of Radioactive Bead Resins" ~

3~ In lieu of dewatering, radioactive bead resin may be shipped for disposal in a different container, provided the radiological and regulatory conditions permit, if a visual inspection of the resin during transfer and of final shipping container after loading can be conducted in a manner that will assure that the free standing, liquid volume present wilL meet and disposal site requirements, shipping,'ransportation, 4, 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, 5~ With dewatering not performed in accordance with the PCP:

(1) if the dewatered bead resin has not already been shipped for it meets burial disposal, verify each container to ensure that ground, shipping and transportation requirements and/or (2) take appropriate administrative action to prevent recurrence 6~ Close the container as per the manufacturer's instructions'

' Solidification, encapsulation, or absorption of radioactive waste materials shall be performed in accordance with vendor approved procedures'

' All radioactive

'f waste material packaged and destined for land disposal shall conform to the requirements of 10 CPR 20,311 as implemented by procedure HP-47 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,

ATION ON t.y O N tNFONMcontrolled, Pag t 'ot B fore uses ll d. Before contro e

' with a verify in o rination FLORIDA POWER tE LIGHT COMPANY ST ~ LVCIE PLANT ARtINISTRATIVE PROCEDURE NEtBER 0520025 OAYI

~A/ '

~

REVISION 3 EOCr g <~a~o 1,0 EXELE: SY$

PROCESS CONTROL PROGRAM coMp~~~Ppgy.:

IIII 2 SO REVIEW AND APPROVAL:

Reviewed by Facility Review Group December 28, 1982 Approved by J H. Barrow (for) Plant 'Manager December 28, 1982 Revisioa 3 Reviewed by F R G Approved by Plant Manager 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 botn units, Specifically, the PCP applies to waste form classification of 1I Sh' j&j all radioactive waste destined for land burial in accordance with 1

10 CFR 20 '11, dewatering of bead resins for disposal, aad solidification, encapsulation, or absorption vendor supplied processes for liquid radioactive waste~

3 2 Discussion 1, The PCP contains provisions to assure tnat dewatering of bead resins results ia a waste form with characteristics that meet the requirements of 10 CFR 61 as implemented by 10 CFR 20 and of tae low level radioactive waste disposal site The Process Control Program includes in addition to this procedure the following related procedures:

A St Lucie Plant Operating Procedure No 0520023, "Qewateriag Radioactive Bead Resias" ~

B QKN-NUCLEAR SYST&fS, INC Test procedure for Dewateriag Conical Bottom Demiaeralizers and kesin Liners - Project, No 11118, 10/05/81 C QQ8-NUCLEAR SYSTEMS, INC Lab Record Sheet for Conical ttottom Demiaeralizers and Resin Liners - Project No. 11118; 10/01/81.

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

report are met~

Page 2- of 5 ST ~ LUCIE PLANT ADMINISTRATIVE PROCEDURE NUNSK8. 0520025, REVISION 3 PROCES S CONTROL PROGRAM 3 0 SCOPE: (ccaciaued) sion'(continued) 3 2 3 'll Discus radioactive waste shiped for land burial must beet the requirements of 10 CFR 20,311 regarding waste form classification and packaging This is implemented through procedure HP-47, "Classification of Radioactive Waste 8aterial for Land Disposal" /RS 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 materials onto an absorbent material /R3.

2~ Dewaterin - The process of removing "free standing" water from a inal disposal package which contains radioactive bead resins, material within cement"like material, such that the final product is a freemtanding monolith 4 "Free Standin " Water - Liquid which is not retained by the waste orms 5~ Solidification - The process of solidifying liquid radioactive waste material in cement-like material, such that the final product is a free-standing monolith. /R3 6~ Process Control Pro ram (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, 7 Visual Ins ection 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 material based upon the concentrations of radionuclides identified. /RS 4~0 PRECAUTIONS:

4 1 'rocess 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

Page 3 of 5 ST LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 3 PROCESS CONTROL PROGRAM 4 0 PRECAUTIONS- (continued) 4~2 Vendor supplied solidification, encapsulation, and absorption processes shaLL be NRC approved or uncover a topical report which has been submitted to NRC approval. Procedures which are to be used est be controlled per t e vendor 's Qk program /R3 4 3 In lieu of dewatering performed. as per the Process Control Procedures, a visual inspection of the bead resin as it is transferred and of the final disposal container after loading may be perforaad if conditions permit This inspection must be conducted in a manner that will assure that the free standing liquids will meet shipping, transportation and disposal site requirements 4 4 All changes to the St, Lucie Plant Process Control Program est be reviewed and approved by the Facility Review Group before they become ef fective i 4 5 All changes to the St Lucie Plant Process Control Program axxst 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 5rO 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 in designee to assure that radioactive waste material is classified accordance with the PCP. /R3

Page 4 of 5 ST ~ LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, REVISION 3 PROCESS CONTROL PROGRAM 6 e0

REFERENCES:

6~1 Dewatering Procedure for CNSI Conical-Bottom EnviroSAPE' High Integrity Containers (containing bead-type ion exchange resin) 1X free standing water - FOWP-003 6,2 Lab Record Sheet for Conical Bottom Demineralizers and Resin Liners',

Prospect No, 11118 6 3 Test Procedure for Dewatering Conical Bortom Demineralizers and Kesin Linexs, Pro)ect No~ 11118',4 Health Physics Pxocedure, HP-47, "Classification of Radioactive Waste Material for Land Disposal"', /R3 7,0 RECORDS AND NOTIPICATIONS:

7,1 Records shall be as per St. Lucie Plant Operating Procedure No 0520023, "Dewatering Radioactive Bead Resins" ~

'7 2 Notifications 1~ If it, is suspected that the free standing water requirements may not be met for any container of xadioactive 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,

Page 5 of 5 ST ~ LUCIE PLANT ADMINISTRATIVE PROCEDURE NUMBER 0520025, dEVISION 3 PROCESS CONTROL'ROGRAM 8 o0 INSTRUCTIONS:

8 1 Dewatered radioactive bead resins:

1 ~ Dispose of dewatered radioactive bead resins is limited to the following containers for which full scale dewatering tests have been. conducted:

A CNSI Conical Bottom EnviroSAPE' High Integrity Container-PL6-80(Ro B CNSI Conical Bottom EnviroSAPE~ High Integrity Container-PL14-195' CNSI Conical Bottom EnviroSAPE~ High Integrity Container-PL8-120(Ri 2i Dewater the container as per St, Lucie Plant Operating Procedure 0520023, "Dewatering of Radioactive Bead Resins",

No 3>> In lieu of dewatering, radioactive bead resin may be shipped for disposal in a different container, provided the radiological and regulatory conditions permit, if a visual inspection of the resin during transfer and of final shipping container after loading can be conducted in a manner that will assure that the free standing liquid volume present will meet shipping, transportation, and disposal site requirements 4, With dewatering not meeting disposal site,'hipping, and transportation requireients, 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 5 With dewatering not performed in accordance wich the PCP:

(1) if the dewatered bead resin has not already, been shipped for it meets burial

~

disposal, verify each container to ensure that ground, shipping and transportation requirements and/or (2) take appropriate administrative action to prevent, recurrence.

6i Close the container aa per the manufacturer 's instructions 8 2 Solidification, encapsulation, or absorption of radioactive waste materials shall be performed in accordance with vendor approved procedures~

8 3 All radioactive waste material packaged and destined for land disposal

=sha11 conform to the requireuents of 10 CHL 20i311 as implemented by procedure HP-47 ~ If waste form classification exceeds Class 0 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