ML17215A580

Combined Semiannual Radioactive Effluent Release Rept for Jan-June 1984. W/840830 Ltr

ML17215A580
Person / Time
Site:	Saint Lucie
Issue date:	06/30/1984
From:	Williams J FLORIDA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
L-84-227, NUDOCS 8410010203
Download: ML17215A580 (28)

Text

BETs BAsTER, R REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) ppgyp ACCESSION,NSR:8410010203 DOC.DATE: 84/08/30 NOTARIZED: l<O DOCKET 4 FACIL;50 335 St ~ Lucie-Plant< Unit. 1< Florida Power 5 Light Co. 05000335 50-389 St.--Lucie Plant< -Unit-.,2< F1 or i da Power L Light Co. 0'50 AUTH ~ NAME - - -AUTHOR AFF lLIAT ION WILLIAMS'RW~ Florida Power L Light Co ~

REC IP ~ NAME RECIPIENT AFFILIATION O'REILLY<J ~ P ~ Region 2r Office of Director

SUBJECT:

"Comhined Semiannual Radioactive Effluent Release Rept for

,Jan-June -1984, ~ " W/840830 ltr.

DISTRIBUTION CODE: IE2bD COPIES RECEIVED;LTR tENCL ~ SIZE:

TITLE: Periodic Environ Monitoring Rept (50 DKT)<<Annual/Semiannual/Ef fluent/

NOTESR 05000335 OL:02/01/76 05000389 OL:04/06/83 RECIPIENT COP IES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR ORB3 BC 04 7 7 NRR ORB3 BC 04 7 7 INTERNAL! AEOD 1 1 IE FILE 01 NRR/DE/EEB 08 1 1 09 NRR/DSI/METB 2 2 NRR/DS I/RAB 10 RGN2/DRSS/EPRPb 1 1 R '/ A 'Ib EXTERNAL ACRS 11 LPOR NRC PDR 02 I4'1 IS TOTAL NUMBER OF COPIES REQUlRLO: LTTR 27 ENCL 27

FLORIDA HNBR & LIGHT COMPhHY U1'UCIE PLANT UNIT NO I U 2 LICENSE NO DPR-67 & NPF-16 CNBINED SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE PERIOD Janua 1 1984 THROUGH tune 30 1984

~g )E7 840630 8410010203 05000335 PDR ADOCK PDR R

TABLE OF CONTENTS DESCRIPTION PAGE EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATIONo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ gal OFPSITE DOSE CALCULATION MANUAL REVISIONS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ 5 PROCESS CONTROL PROGRAM REVISIONSooo ~ ~ ~ ooo ~ ~ oooo ~ ~ o ~ oo ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ o>

LIQUID EFFLUENT:

SUMMATION OF ALL RELEASES & NUCLIDE SUMMATION BY QUARTER UNIT l ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 2 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 9 GASEOUS EFFLUENT SUMMATION OF ALL RELEASES & NUCLIDE SUMMATION BY QUARTER UNIT l ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ '

~ ~ '

~ ~ ~ ~ ~ ~ ~ '

~ '

UNIT 2oooooooooooooooooooooooooooooooooooooooooooooooooooooooool4 SOLID WASTE SHIPMENT SUMMATIONo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ l6 5

PROCESS CONTROL PROGRAM PAGE REVISIONS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ , ~ ~ ~ ~ ~ ... ~ .ATTACHMENT A

Page 1 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION 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 4 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:

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.

• b. The dose in unrestricted areas (see Figure 5.1 in the STS-A) due to noble gases released in gaseous effluents 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 an individual from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives > 8 days in gaseous effluents released to unrestricted areas (see Figure 5.1 in the STS-A) 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..argr STS..LCO, +e.rypoit;ed y4.peg awe based...on, apt:u~,

release condition's 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 l.l.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.

4.1 Estimate of Errors

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

Analytical Error for Nuclides

~Aveve e Maximum Liquid +9% +30%

Gaseous +10% +35%

TABLE 3.1 RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS LIQUID SAMPLING TYPE OF METHOD OF SOURCE FREQUENCY ANALYSIS ANALYSIS Each Batch Princi al Gamma Emitters .h.a.

Monitor Monthly H-3 L.S ~

Tank Composite Gross Alp a G.F.PE Releases> Quarterly SR-90, SR-89 C.Se Composite FE-55 Continuous No continuous activity releases Releases for this reportin 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

~,>>r, v.i ',e,,ev e' ~ ""- '. Germanium detectors.

~~ ' ~

~

~ ~ <<: e i

'qua'n'ii'ii:ea ~ eve ev.' e Ae' w, pcs iAll

~ e, are identified

' ' peaksi >,~,v ~ ~ >' ~ "~ ~ . ~

and ew;e' e v ~ ~

' a ev ~ ~

L.S. Liquid Scintillation Counting C.S. Chemical Separation G.F.P. Gas Flow Proportional Counting

~ ~

~ ' ~ ~ ll ' ~

~ ~

l ~ ~ 1

~ II ~ ~

~ ~ ~

~ II ~ ~

II ~

II ~

~ II ~

~ ~

II ~

II ~ ~ ~

~ ~ ~ ~

Page 4 FLORIDA POWER 6 LIGHT COMPANY ST. LUCIS UNIT NO. 1 6 2 SEMIANNUAL REPORT Januar 1, 1984 THROUGH June 30, 1984 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION continued

5. Batch Releases 5.1 Liquid UNIT 1 UNIT 2

a. Number of batch releases: 29.5 29.5

b. Total time period of batch releases: 15150 15150 MINUTES

c. Maximum time period for a batch release: 3030 3030 MINUTES

d. Average time period for a batch release: 513 513 MINUTES

e. Minimum time period for a batch release: 288 288 MINUTES

f. Average stream flow during periods of release of effinane into a flosing srream: 1)80000 1180000 OPM ALL LIQUID RELEASES ARE SUMMARIZED IN TABLES 5.2 Gaseous

a. Number of batch releases: 10 34

b. Total time period for batch releases: 8157 8668 MINUTES

c. Maximum time period for a batch release: 2273 600 MINUTES

d. Average time period for batch releases: 816 255 MINUTES

e. Minimum time period for a batch release: 260 45 MINUTES ALL GASEOUS WASTE RELEASES ARE SUMMARIZED IN TABLES

6. Unplanned Releases 6.1 Liquid

a. Number of releases: '0

b. Total activity releases: 0 CURIES 6.2 Gaseous

a. Number of releases: 0

b. Total activity released: 0 CURIES 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,,tween,to.prevent, a,remcurrenqe,

d. Consequences of the unplanned release.

Page 5 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMIANNUAL REPORT Januar 1, 1984 THROUGH June 30 1984 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION continued

7. Assessment of radiation dose from radioactive effluents to the GENERAL PUBLIC due to their activities inside the site boundary is part of the January Semiannual Report.

8. Offsite Dose Calculation Manual Revisions:

No revisions were implemented during the reporting period.

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 and is summarized in Table 3.8.

10. Process Control Pro ram Revisions Attachment A to this report includes all the information relative to PCP revision reporting requirements of the standard Technical Specifications.

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~ ~ ~ I'

Page 6 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 SEMIANNUAL REPORT Januar 1, 1984 THROUGH June 30 1984 TABLE 3.3-1 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 A. Fission and Activation Products Total Release (not including tritium, gases, alpha) CI 3.46 E-1 2.83 E-1 2 ~ Average diluted concentration durin eriod uCI/ml 1.95 E-8 1.75 E-8 B. Tritium

1. Total Release f cr 3.95 E1 2.15 E1

2. Average diluted concentration durin eriod uCI/ml 2.23 E-6 1.32 E-6 C. Dissolved and Entrained Gases 1~ Total release CI 1.32 EO 4.02 E-2

2. Average diluted concentration durin eriod uCI/ml 7.45 E-8 2.48 E-9 D. Gross Alpha Radioactivity

1. Total Release CI 0 EO 0 EO E. Volume of Waste Released

( rior to dilution) Liters 2.18 1.65 E6 F. Volume of Dilution Water E6'.77 Used Durin Period Liters E10 1.62 E10

~ t >+'I ~ ' ~~ ~ VY ) ' qP ) i j ' '4 ~

' ) t)P (. ate v1 ', sP ' ~ ew ',i ~ V I' 4 t I ~

Page FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 SEMIANNUAL REPORT Januar 1, 1984 THROUGH June 30 1984 TABLE 3 '-1 LIQUID EFFLUENTS 0 T NUO D B OD NUCLIDES RELEASED UNIT QUARTER 1 UARTER 2 QUARTER 1 QUARTER 2 I-131 CI 6 ~ 00 E-2 1 ~ 63 E-2 I-132 CI

)

I-133 CI 2.73 E-3 2.65 E-3 l NA 24 CI 1.68 E-3 6.25 E-4 CR-51 CI 8.00 E-3 1.31 E-4 MN<<54 CI 5.55 E-3 3.16 E-3 C0-57 CI C0-58 CI 4.82 E-2 3.27 E-3 FE-55 CI 2o05 E-2 1 ~ 08 E-2 FE-59 CI 7.30 E<<4 0 EO CO-60 CI 9. 65 E-2 2. 27 E-1 ZN-65 CI 1,94 E-4 0 EO NB-95 CI 5 '0 E-3 8.75 E-5 AG-110M CI SN-113 CI 1.63 E-4 0 EO SB-122 CI 6.10 E-5 0 EO

)

SB-124 CI 5.85 E-4 0 EO W-187 CI NP-239 CI ZR-95 CI 2.91 E-3 0 EO I

MO-99 CI RU-103 CI

" 'S'-134 CI 2.46 E-2 3.55 E-3 CS-136 CI 2.90 E-3 0 EO CS-137 CI 5.25 E-2 8.90 E-3 BA-140 CI

)

CE-141 CI

~ 4 + ~ I ', ~ ~ 'i, ~

LA-140 ZR-97

+ i k ~

CI CI

~,4t pt ' h ~ 4 ~ t, ~ ( ~ g 0 I ~ ~ / e J I t 1 '8 t14 hA,,

E-3 I, ~ ~ i'4 ~ ',

6 '0

~ ltd E-4 I q't g, ~ 4 N % ~ ~ )

Page 8 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO 1 SEMIANNUAL REPORT January 1 1984 THROUGH June 30 1984 TABLE 3.4-1 LIQUID EFFLUENTS (continued)

ONTINUOU ODE BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 UARTER 2 UARTER 1 QUARTER 2 SB-125 CI 1 ~ 08 E-2 6.25 E-3 I CE-144 CI SR-89 CI 4.57 E-4 0EO I SR-90 CI 9 '0 E-5 0 EO Y-90 CI 9.60 E-5 0 EO TC-99M CI 4.39 E-4 0 EO PR-144 CI UNIDENTIFIED CI 0 ~ OOEO O.OOEO 0 ~ OOEO 0 ~ OOEO TOTAL FOR PERIOD ABOVE CI OEO OEO 3.46 E-1 2.83 E-1 AR-41 CI KR-85 CI XE-13) M CI 4 ~ 71 E-3 0 EO XE-133 CI 1.31 EO 3.82 E-2 XE-133M CI 4.00 E-4 OEO I XE-135 CI 1.47 E-3 2.04 E-3 I KR-85M CI XE-138 CI TOTAL FOR PERIOD ABOVE CI OEO OEO 1.32 EO 4 '2 E-2 NOTE: If no value is entered for a nuclide, the value equals zero Curies.

0 ~ w6', ~ ',t', 0 w ~,,', 4 ,; ~ 7 Aa.l ~ ~

/ ( s%' '~' h" v \ 'q p .qi"l pap ~ ~ .,' I, py . 2;e,1,, I',gt ', ~ ~ i ~ I,, I 't, ~

Page 9 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMIANNUAL REPORT January 1 1984 THROUGH June 30 1984 TABLE 3.3-2 LIQUID EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER 1 QUARTER A. Fission and Activation Products

1. Total Release (not including tritium, gases, alpha) CI 3.46 E-l 2o83 E-1

2. Average diluted concentration durin eriod uCI/ml 1.95 E-8 1 ~ 75 E-8 B. Tritium

1. Total Release CI 3.95 El 2.15 E1

2. Average diluted concentration durin eriod uCI/ml 2.23 E-6 1.33 E-6 C. Dissolved and Entrained Gases

1. Total release j Cr 1.32 EO 4.02 E-2

2. Average diluted concentration durin eriod uCI/ml 7.45 E-8 2.48 E-9 D. Gross Alpha Radioactivity

1. Total Release CI 0 EO 0 EO E. Volume of Waste Released (prior to dilution) Liters 2.18 E6 1.65 E6 F. Volume of Dilution Water Used Durin Period Liters 1.77 E10 1 ~ 62 E10

~ '<<g <<.k 4' '<< ~ << "h ~,<< ~,'<<:) '<<'<l'<<' 0 <<f '<<<<<< '4 - << ~ "r ~ ~,f <<J4>q >= ) ~

','+ ' i e<<J <<<<<<, ~ i4 "+ ~; <<w.<<,, ~ '.0 'P

~ ~

Page FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMIANNUAL REPORT Januar 1, 1984 THROUGH June 30 1984 TABLE 3 '-2 LIQUID EFFLUENTS ONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT QUARTER kl QUARTER 2 'UARTER 1 QUARTER 2 I-131 CI 6.00 E-2 1.63 E-2 I-132 CI I-133 CI 2.73 E-3 2.65 E-3 NA-24 CI 1.68 E-3 6.25 E-4 CR-51 CI 8.00 E-3 1.31 E-4 MN-54 CI 5 '5 E-3 3.16 E-3 C0-57 CI C0-58 CI 4.82 E-2 3.27 E-3 I

FE-55 CI 2.05 E-2 1.08 E-2 FE-59 CI 7.30 E-4 0 EO C0-60 CI 9.65 E-2 2 ~ 27 E-1 ZN-65 CI 1.94 E-4 0 EO NB-95 CI 5 ~ 20 E-3 8.75 E-5 AG-110M CI SN-113 CI 1.63 E-4 0 EO SB-122 CI 6 '0 E-5 0 EO SB-124 CI 5.85 E-4 0 EO W-187 CI NP-239 CI ZR-95 CI 2.91 E-3 0 EO I

MO-99 CI RU-103 CI CS-134 CI 2 ~ 46 E-2 3.55 E-3 CS-136 CI 2.90 E-3 0 EO CS-137 CI 5 '5 E-2 8.90 E-3 I

BA-140 CI CE-141 CI LA-140 CI 1.58 E-3 6.30 E-4 ZR-97 CI

Page ll FLORIDA POMER & LIGHT COMPANY ST. LUCIE UNIT NO ~ 2 SEMIANNUAL REPORT Januar 1 1984 THROUGH June 30 1984 TABLE 3.4-2 LIQUID EFFLUENTS (continued)

ONTINUO ODE C ODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 I

SB-125 CI 1.08 E-2 6.25 E-3

'E-'144 CI SR-89 CI 4 ~ 57 E-4 0EO I I

SR-90. CI 9.60 E-5 0 EO Y-90 CI 9.60 E-5 0EO I TC-99M CI 4.39 E-4 0 EO PR-144 CI UNIDENTIFIED CI O.OOEO O.OOEO 0 OOEO 0 OOEO TOTAL FOR PERIOD ABOVE CI OEO OEO 3.46 E-1 2.83 E-1

] AR-41 CI KR-85 CI XE-131M CI 4 ~ 71 E-3 0EO I CI 'E-133 1.31 EO 3.82 E-2 XE-133M CI 4 ~ 00 E-4 OEO I I

j XE 135 CI 1 ~ 47 E-3 2,04 E-3 I KR'-85M CI XE-138 CI TOTAL FOR PERIOD ABOVE CI OEO OEO 1 ~ 32 EO 4 '2 E-2 NOTE: If no value is entered for a nuclide, the value equals zero Curies.

Page 12 FLORIDA POMER 6 LIGHT COMPANY ST. LUCIE UNIT NO, 1 SEMIANNUAL REPORT Janus 1 1984 THROUGH June 30 1984 TABLE 3.6-1 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 A. Fission and Activation Gases

1. Total Release j CI 3.40 E1 3.33 E3

2. Avera e Release Rate for Period uCI/sec 4.32 EO 4.24 E2 B. Iodines

1. Total Iodine-131 I CI 8.45 E-5 3.43 E-2

2. Avera e Release Rate for Period uCI/sec 1.07 E-5 4.36 E-3 C. Particulates

1. Particulates T-1/2 > 8 Days j CI 3.77 E-5 2.75 E-4

2. Average Release Rate for Period j uCI/sec 4.79 E-6 3.5 E-5 j

3. Gross Alpha Radioactivity CI 3.27 E-9 1.70 E-8 D. Tritium

1. Total Release CI 4.35 E1 5.12 E1 j

2. Avera e Release Rate for Period uCI/sec 5.76 EO 6.51 EO

~ ~ ' ' > \ ><<" <<{ Ir '<< ~ <<<<('L ~, )y ~ s ~ <<' ~ i'L g ', << ~ 'g <<p I g <<pa<<<<y ~

Page 1 3 FLORI DA POWER & LIGHT COMPANY I

S T . LUC E UNIT N 0 ~ 1 SEMIANNUAL REPORT Januar 1 1984THROUGHJune301984 TABLE 3 ~ 7 -1 GASEOUS EF FLUENT S ONTINOUODE B T ODE NUCLIDES RELEASED UNITQUARTER 1 QUARTER 2 QUARTER 1 QUARTER 2 1~ FISSION GASE AR-4 1 C I 0 0 0 KR-8 5 C I 0 0 0 1 ~ 20 E KR-8 5 M CI 0 3~70 E1 0 0 KR-8 7 CI 0 ~32 E0 0 0 KR- 8 8 CI 0 1 ~ 33 E1 0 0 XE-131M CI 0 0 0 1 ~ 56 E 1 -

XE-133 CI 3 ~ 40 E1 2~65 E3 2 ~ 7 3 E2 XE-133M CI 0 2 .00 E1 0 1 ~ 9 E0 XE-135 CI 0 3~ 16 E2 0 9 ~ 55E-3 XE-135M CI 0 XE-18 CI 0 0 0 TOTAL FOR PERIOD ABOVE CI 3 ~ 40 E 1 3 ~ 05 E3 0 2 ~ 76 E2 IODINES I- 13 1 C I 8~45 E 5 - 3 ~ 4 0E-2 I- 133 CI 0 1 ~ 08E-l I- 13 5 CI 0 1 ~ 3 9 E0 TOTAL FOR PERIOD ABOVE CI 8 ~ 45E-5 1 ~ 5 3 E0 PART C U L AT E Co 5 8 C I 0 0 Co-60 C I 3~77 E- 5 0 S R- C I 0 1 ~ 5 1E-5 SR-90 C I 0 3 ~ 2 2E<<7 Y-9 0 CI 3 ~ 22E-7 I- 1 3 1 CI 0 2 ~ 6 0 E-I- 1 33 CI 7 ~ 1 4E-4 CI TOTAL FOR PERIOD ABOVE C I 3 ~ 7 7E<<5 9 ~ 8 9E>>4

~

~,'~, W W ~, \ - l $ W ~ ~ ~ ~, '1 >> P f g P q g ) J g 4 ~ Q ( P

Page 14 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMIANNUAL REPORT Januar 1, 1984 THROUGH June 30, 1984 TABLE 3.6-2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 A. Fission and Activation Gases

1. Total Release I CI 1.48 E3 2.04 E3 2~ Avera e Release Rate for Period uCI/sec 1.88 E2 2.59 E2 B. Iodines

1. Total Iodine-131 CI 2.9 E-2 1.04 E-2

2. Avera e Release Rate for Period uCI/sec 3.69 E-3 1.32 E-3 C. Particulates

1. Particulates T-1/2 > 8 Days I C 7'38 4 6 '3 5 l

2. Average Release Rate for Period uCI/sec 9.39 E-5 8.57 E-6 [

3. Gross Alpha Radioactivity CI 0 EO 0 EO D. Tri tium Total Release }

CI 2. 73 El 2. 94 El 2, Avera e Release Rate for Period uCI/sec 3.47 EO 3.74 EO

~ ~ )q+ ~ h PIP ~ ~ 4 ~ 5 ~ ~ "g I DIE ~ g, I.> ~ t ~ '4 ~ ~ LhyJW(l 4! ~ f<lg / '

Page 15 FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMIANNUAL REPORT Januar 1, 1984 THROUGH June 30 1984 TABLE 3 '-2 GASEOUS EFFLUENTS ONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT QUARTER 1 QUARTER 2 QUARTER 1 UARTER 2 1 FISSION GASES

'2

~

AR-41 CI 0 1.61 EO 6 E-l KR-85 CI 0 KR- 5M CI 6. 3E 2 ~ 67 El 1 ~ 20 E-1 1 ~ 85 E-2 KR-87 CI 0 0 1.68 E-3 0 KR-88 CI 1. 8 EO 2 '4 El 1 ~ 84 E-2 2.96 E-2 E-1 XE-131M CI 0 0 1 ~ 70 E-1 3.31 XE-133 CI 1 ~ 29 E3 i+73 E3 1 ~ 02 E2 3.38 El XE-133M CI 2 ~ 05 EO 8.63 E-1 3.43 E-1 XE-135 CI 7.29 El 6 '8 El 1 ~ 56 EO 5.01 E-1 XE-135M CI 1.49 E2 0 0 XE-1 8 CI 0 0 0 0 TOTAL FOR PERIOD ABOVE CI 1.37 E3 2.00 E3 1.06 E2 3.56 El

2. IODINES I-131 CI 2.83 E-2 1 ~ 03 E-2 I-133 CI 1 ~ 89 E-2 1 ~ 39 E-2 I-135 CI 0 0 TOTAL FOR PERIOD ABOVE CI 4.72 E-2 2.42 E-2

3. PARTICULATES Co-58 CI 0 0 Co-60 CI 0 0 Sk-89 CI SR- CI 0 .8 E-Y-90 CI 0 2.87 E-6 I-131 CI 7 38 E- ~ 1 E-5 CI CI TOTAL FOR PERIOD ABOVE CI 7.38 E-4 6.73 E-5

Page 16 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 & 2 SEMIANNUAL REPORT Januar 1 1984 THROUGH June 30, 1984 TABLE 3.8 COMBINED SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 6-month Est. Total e of waste Unit Period Error, X

)

a. Spent resins, filter sludges )

m )

3.45 El I evaporator bottoms, etc. Ci 5.34 E2 2.0 El

b. Dry compressible waste, )

m3 )

4.34 E2 I I I

contaminated equip, etc. Ci 3. 18 E 1 2.0 El I

c. Irradiated components, m )

8.37 El control rods, etc. Ci 6.23 E4 2.0 El I

d. Other (describe) I '. I

'E I

Ci E ~ E

2. Estimate of major composition (by type of waste)

a. Co-60 2.9 El Cs 137 2.6 El Cs 134 1 3 El

~

Fe 55-  %%d 6.5 EO

b. Fe-55 3.0 El Co 60 2+3 El I 131 1 3 El

~

H- -3 1.2 El Co 58 7.5 EO C~ Co -60 ay 4.2 El Fe - 55 2 ~ 9 El Co-58 1.9 El Mn - 5 3.7 EO Ni -63 3 ' EO

3. Solid Waste Disposition Number of Shipments Mode of Trans ortation Destination 43 SOLE USE TRUCK BARNWELL, S. C ~

9 SOLE USE TRUCK RICHLAND, WASH.

B. IRRADIATED FUEL SHIPMENTS (Disposition)

Number of Shipments Mode of Trans ortation Destination ZERO

FLORIOA POMER II LIGHT CONPANY ST LUCIE UNIT NOS. 1 ANO 2 SEHIANNUAL REPORT IABLL 3.8 {Cont.

Solid Waste Supplement Total Total Note 1 Type Note 3 Type Note 4 Solidifcation

'Waste Volume Curie principal Notes 1,2 of R.G. 1.21 of Agent Closet.fScattoo Cu F-t ~uaotit Radi onucl f des Waste ~Cate or Container or Absorbent Class A 14,352 7.185 None PMR Trash 1'.b. Non Speci ffcation Hone Class A. 975 24.594 Cs 63Hf, Sr PMR Honcompacted l.b NRC Certf fied None Trash LSA > Type A Cl ass 'A 195 3.64 Cs Nf PMR Ion Exchange l.a NRC Certified None Resins LSA > Type A Class A 126 4.58 137Cs 63NI 90Sr PWR Filter l.a NRC Certified Cement Cartrfdges Type 8 Class 8 126 10.75 137Cs 63HI 90Sr PMR Filter l.a NRC Certified Cement Cartridges Type 8 Cl ass .8 585 73.04 137Cs 63HI 90Sr PMR lon Exchange l.a NRC Certified None Resins LSA > Type A Class 8 103 101.46 60Co 1 37Cs 55Fe PMR Ion Exchange l.a NRC Certf fied None His Sr Resins Type 8 Class B 1008 1376.01 58Co 60Co 137Cs PMR Filters I cHote 5 NRC Certified Cement Nf, Sr, Fe Type 8 58 Co, 60 l.c Class 8 92 1912.74 4Co, 51Cr LMR Nonfuei NRC Certf fied None Fe, Nn, 63N Reactor Components Type 8 Class 84 340.61 60 Co, 134Cs Cs PWR Ion Exchange l.a NRC Certified None

.C Nn, 55Fe Ni, Sr Resf ns LSA > Type A Class C 1764 6023.16 58 Co, 60Co, 137Cs PMR Filters 1 cNote5 NRC Certified Cement Nn, 51Cr, 55Fe Type B 63Hf, 90Sr Class 92 52,961.6 60 Co, 54Nn, 55Fe Honfuel l.c certified C LMR NRC None 1

u Hi, Reactor Components Type B s

Page 18 FLORIDA POWER 5 LIGHT COMPANY ST. LUCIE UNIT NOS. 1 AND 2 SENIANNUAI- REPOSER I 1984 TIIVIIVVK 4 99 1984 TABLE 3e8 {Cont'.

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

Lucie Plant foll'ows 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 canposition of radionuclides in the waste is determined by both on-site analyses for principal ganma emitters, and periodic offsite analyses for other radionuclides. The onsite analyses are per formed either on a batch basis or on a routine basis using reasonably representative sanples as appropri ate for the waste type. Offsite analyses are used to ehtahfjsh galin~ factors o~ ~ther estimates for i onu i des suc( as H, C, Tc, 2 I, TRU, 4 Pu, Cm, Ni, and Fe.

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

Note 5:'hese wastes are categorized 1.c since they are comprised predominently of solids from the cuttings of the St. Lucie Unit 1 thermal shield. The ratio of solidification agent to waste is approximately 15 to 1.

~ 9 ~ 8 ~ ~~ e Ir ~

ATTAC'ff)EtfT A REV 2 CHANGES TO PROCESS CONTROL PROGRAH DURING PERIOD JANUARY 1, 1984 THROUGH JUNE 30,1984 A. 1. Paragraphs 3.2.2, 3.2.3, 6.2 and 6.3 changed the Lab Record Sheet for Conical Bottom Demineralizers and Resin Liners and test procedure for Dewatering Conical Bottom Demineralizers and Resin Liners to Chem-Nuclear Pro)ect 011118.

2. Paragraph 8.1.3 added CNSI Conical Bottom Envirosafe TM High Integrity Container PL8-120 CR to "B"

list of plant approved Liners to allow use of type Cask for Resin Disposal.

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 the FRG is on the cover sheet of the attached procedure.

J

Page 1 of 4 FLORIDA PINER 6 LIGHT CCHPANY STe LUCIE PLANT klHINISTRATIVE PROCEDURE NO ~ 0520025 REVISION 2

1.0 TITIE

PROCESS Q)NTROL PROGRAM 2i0 REVIEW AND APPROVAL:

Revieved by Facility Review Group December 28, 1982 Approved by J. H. Barrow (for) Plant Manager December 28, 1982 Revision 2 Revieved by F R G >->>>P~P Approved by t Manager cS 1~

3.0 SCOPE

3.1 Purpose The St. Lucie Plant Process Control Program (PCP) implements requirements of the St. Lucie Plant Unit 1 Technical Specifications and the St. Lucie Plant Unit 2 Technical Specifications. The PCP applies to the devatering of radioactive bead resins for disposal at a lov level radioactive waste disposal site.

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

l. St. Lucie Plant Operating Procedure No. 0520023, "Dewatering Radioactive Bead Resins".

2. CHEM-NUCLEAR SYSTEMS, INC. Test procedure for Dewatering Conical Bottom Demineralizers and Resin Liners - Project No. 11118, 10/05/81

3. CHEM-NUCLEAR SYSTEMS, INC. Lab Record Sheet for Conical Bottom Demineralizers and Resin Liners -. Project No. 11118; 10/01/81.

3.3 Authority The authority and responsibility to perform the requirements of this

" "pr'ocednre 'no8e'om"40'CPR'20;-'10 %FR'4k 'St;"Lucia"Plaat" Unit'"1 Specifications, St. Lucie Plant Unit 2 .Technical" '-'echnical Specifications, and from disposal site crit FOR INFORIATlON ONE This crocurnent is not controlled. bafor

Page 2 of 4 ST. LUCIE PLANT ADMINISTRATIVE PROCEDURE NO. 0520025, REVlSluN 2 PROCESS CONTROL PROGRhM

~-

3.0 SCOPE

(continued) 3.4 Def initions

l. 1h final disposal package which contains radioactive bead resins.

2~ "Free Standin " Mater - Liquid which is not retained by the waste forme

3. Process Control Pr am {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.

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

4 0 PRECAUTIONS:

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

4.2 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.

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

4.4 All changes to the St. Lucie Plant Process Control Program aaxst 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 e ~t P ~

o '

'A' K~e t

\ J'-ll I'Ht

~ ~

'2

~ ' '

4-detcralnation that-ehe.change u ' 'r for the change without benefit of additional or supplemental 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

Page 3 of ST. LUCIE PLANT ADMINISTRATIVE PROCEDURE NO ~ 0520025, REVISION 2 PROCESS CONTROL PROGRAM found acceptable by the Facility Review Group.

I

. 5,0 RESPONSIBILITIES:

5.1 It is the responsibility of the Plant Manager to assure that all necessary procedures, equipment and support are provided to properly haplemnt 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 PCS 6 0

REFERENCES:

6.1 Dewatering Procedure for CNS'I Conical-Bottom EnviroSAFE' High Integrity Containers (containing bead-type ion exchange resin) 1X free standing water - FO-OP-003 6.2 Lab Record Sheet for Conical Bottom Demineralizers and Resin Liners, Pro)ect No. 11118 6.3 Test Procedure for Dewatering Conical Bottom Demineralizers and Resin Liners, Prospect No. 11118.

7.0 RECORDS AND NOZIFICATIONS:

7~1 Records shall be as per St. Lucie Plant Operating Procedure No.

0520023, "Dewatering Radioactive Bead Resins".

7.2 Notifications

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

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

Page 4 of 4 ST ~ LUCI E PLANT ADMINISTRATIVE PROCEDURE NO ~ 0520025, REVISION 2 PROCESS CONTROL PROGRAM 8 0 INSTRUCTIONS:

8.1 Dispose of dcwatered radioactive bead resins is limited to the following containers for which full scale dewatezing tests have been coaduc ted e 1 ~ CNSI Conical Bottom EnviroSAFE' High Integrity Container-PL6-80'.

CNSI Conical Bottom EnviroSAPE high Integrity Container-PL14-195(R.

3. CNSI Conical Bottom EnviroSAPE High Integrity Container-PL8-120CR.

8.2 Dewater the container as pez't. Lucia Plant Operating Procedure'o.

0520023, "Dewatering of Radioactive Bead Resins".

8.3 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.

8.4 With dewatering not meeting disposal site, shipping, and transportation requirements., suspend shipment of the inadequately dewatered bead resin and correct the process contxol program, the applicable procedures(s),

and/or the dewatering system as necessary to prevent recurrence.

8.5 With dewatering not performed in accordance with the PCP:

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

8.6 Close the container as per the manufacturer 's instzuctions.

4.

FLORIDA POWER & LIGHT COMPANY j %JLt I FIL~

August 30, 1984 L-84-227 Mr. James P. O'Reilly Regional Administrator, Region II U. S. Nuclear Regul atory Commission Sui te 2900 101 Marietta Street NW Atlanta, GA 30323

Dear Mr. O'Reilly:

Re: St. Lucie Units 1 and 2 Docket Nos. 50-335, 50-389 Semi-Annual Re orts Please find attached the Combined Radioactive Effluent Release Data Report and the Radiological Environmental Monitoring Report for the period Januaiy 1, 1984 to June 30, 1984, for St. Lucie Units 1 and 2, as, required by Technical Speci fication 6.9.1.10.

Should you or your staff have any questions on this information, please contact us.

Very truly yours, J.~ W.~ Will s, Jr.~

Group Vice President Nuclear Energy JWW/PLP/js Attachment cc: Director, Office of Inspection and Enforcement, USNRC Document Control Desk, USNRC Harold F. Reis, Esquire PNS-LI-84>>305 PEOPL

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