ML17215A819

Semiannual Radioactive Effluent Release Rept,830602-30. W/830829 Ltr

ML17215A819
Person / Time
Site:	Saint Lucie
Issue date:	06/30/1983
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
L-83-467, NUDOCS 8504090517
Download: ML17215A819 (14)

Text

~ ', REGULATV~INfORMATION DISTHIBVTION ~STEM (8kf%l gnat ACCESSION NBR:850<090517 DuC ~ DATE=: 83/06/30 NOTARIZED: 4 FACIL:50-300 Gt. Looie-Piant-r- Uni.t 2ei Flioriaa Power 0 Liaht Co ~ 00000>ao AI.FILIATIOH AUTH ~ hAHE UHRIGrR.o.

AUTHOR Florioa Power Il Lt'Oht JJCo. C lt ~- SS a(~)

REC IP ~ NAME RECIPIENT AFFILIATION 0 REILLY'S J ~ P ~ Region BP Of f ice o4 Director

SUBJECT:

"Senia'nnua-1 Radioacti ve Ef f 1uent Release Rept 830602 30 ~"

W/830529 ltd DISTRIBUTION CODE: IE25L COP I ES RECEIVED:LTH ENCL SIZE e TITLE: Periodic Environ t1onito ring Rept (50 DKT) Annual/Semiannual/Effluent/

NOTES: 05000389 OL:04/06/83 RECIPIENT COPIES RECIPIENT COPTES lu CODE/NAME LTTR ENCI ID CODE/NAME LTTR ENCL NHrc ORB3 BC 04 7 7 INTERNAL: ACHS 1< AEOD 1 i IE F ILE 01 1 1 NRR/DE/EEB 08 1 1 L /AOR'AF 09 1 NRR/DSI/'ETB 2  ?

RR/DSI/RAB 0 1 RGN2/DRSS/EPRP& 1 i R /D 0 A M I /l l I 8 1 1 EXTERNAL: LPDR 0> 1 1 NRC PDR TOTAL NUMBER OF COPIES REQUIRE,D: LTTR 19 ENCL Er-/

FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 2 LICENSE NO. NPF-16 SEMI-ANNUAL RADIOACTIVE EFFLLEKT RELEASE REPORT FOR THE PERIOD June 2 1983 THROUGH June 30 1983 85040905' 830630 PDR ADOCK 05000389 R PDR

TABLE OF CONTENTS DESCRIPTION PAGE EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 OFFSITE DOSE CALCULATION MANUAL REVISIONS. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 5 LIQUID EFFLUENT SUMMATION OF ALL RELEASES. ~ . ~ . ~ '. ~ ~ . ~ ~ ~ . ~ ~ ~ ~ ~ ~ o ~ ~ o ~ ~ 6 RELEASES'~

LIQUID EFFLUENT NUCLIDE SUMMATION BY QUARTER..... ~ ,. ....'. ...

~ ~ ~ . ~ ..7 GASEOUS EFFLUENT SUMMATION OF ALL .. ~ ~ ~ . ..

~ ~ ~ ~ ~ ~ .. ~ ~ ~ . ~ ~ 9 GASEOUS EFFLUENT NUCLIDE SUMMATION BY QUARTER.. ~ . ~ ~ . ~ ~ ~ ~ ~ ~ .~. ~ ~ .. F 10

Page 1 EFFLUENT A%) 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:

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 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. DOSE Limits and Percent of Limits due to Noble Gases to areas at or beyond the SITE BOUNDARY are not applicable to the Semiannual Report since these limits are related to Historical Meteorlogical Conditions. The Noble Gas Air Doses due to gamma and beta radiations provided in this report were calculated using meteorological conditions concurrent with the time of release.

c. Dose Limits and Percent of Limits due to Iodine-131, Iodine-133, Tritium, and radionuclides in particulate form to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY are not applicable to the Semiannual Report since these limits are related to Historical Meteorological Conditions'he DOSE from Iodine-131, Iodine-133, Tritium, and radionuclides in particulate form with half-lives greater than 8 days provided in this report were calculated using meteorological conditions concurrent with the time of release.

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 + 10X.

b. Analytical Error for Nuclides Average Maximum Liquid +9X i30X Gaseous +10% +35X

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

TABLE 3 '

RADIOACTIVE LIQUID EFFLUENT SAMPLING AND ANALYSIS LIQUID SAMPLING TYPE OF METHOD OF SOURCE FREQUENCY ANALYSIS ANALYSIS Each Batch Princi al Gamma Emitters .h.ao Monitor Monthly L. S.

Tank Com osite Gross Alpha G.F.P.

Releases1 Quarterly SR-90, SR-89 C.S.

Com osite FE-55 Continuous No continuous activity releases Releases for this re ortina 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.S. Chemical Separation G.F.P. Gas Flow Proportional. Counting TABLE 3 '

RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS GASEOUS SAMPLING TYPE OF HETHOD OF SOURCE FREQUENCY ANALYSIS ANALYSIS Waste gas Principal G, C, P Decay Tank Each Tank 'Gamma Releases Emi t ters .h.a.

Containment Principal Gamma G Purge Each Purge Emitters .h.a.

Releases L ~ S.

Principal Gamma (G, C, P Meekly Emit ters ,h.a.

8-3 L.S.

Honthly Gross P-GFP, Plant Composite Alpha Vent (Particulates)

Quarterly SR-90 C,ST Composite SR-89 (Particulates)

G Gaseous Grab Sample C Charcoal Filter Sample P Particulate Filter Sample L,ST 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.F.P. Gas Flow Proportional Counting

Page 4 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO ~ 2 SEMIANNUAL REPORT June 2 1983 THROUGH June 30 1983 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (continued)

5. Batch Releases 5.1 Liquid

a. Number of batch releases: 10

b. Total time period of batch releases: 6880 MINUTES

c. Maximum time period for a batch release: 1620 MINUTES

d. Average time period for a batch release: 688 MINUTES

e. Minimum time period for a batch release: 85 MINUTES

f. Average stream flow during periods of release of effluent into a flowing stream.'LL 676175 GEM LIQUID RELEASES ARE SUMMARIZED IN TABLES 5.2 Gaseous

a. Number of batch releases: 23

b. Total time period for batch. releases: 3936 MINUTES

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

d. Average time period for batch releases: 171 MINUTES

e. Minimum time period for a batch release: 23 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 CUEIES 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 6 LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMIANNUAL REPORT June 2 1983 THROUGH June 30 1983 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION (continued)

7. Description of dose assessment of radiation dose from radioactive effluents to the general public due to their activities inside the site boundary will be reported on the January Semiannual Report.

A brief reactor history follows:

The reactor was under construction during the first quarter of 1983 and no radioactive effluents were generated.

During the second quarter of 1983 the reactor attained initial criticality, but did not generate any power until late June. During power operation the power level did not exceed approximately 30X and the durations were short-lived.

8. Offsite Dose Calculation Manual Revisions:

Revision 03 to C-200,was incorporated during the second quarter of the reporting period. This change does not affect dose calculation methodology, but only Appendix E, "Radiological Environmental Surveillance Sample Location and Collection Frequencies" as follows:

Change No. 1: Waterborne Location H15 Sediment from Shoreline Sample Collection Frequency is now defined as a semiannual frequency. The Surface water (ocean) sample for H15 remains at weekly frequency.

Change No. 2: Waterborne Location *H59 Sediment from Shoreline sample collection frequency is now defined as a semiannual frequency. The Surface water (ocean) sample for *H59 remains at monthly frequency.

Change No. 3: Food products location H52's approximate distance (miles) has been changed from 10-20 to read Approximate Distance of 1 mile.

• Denotes control sample This concludes changes to ODCM for. Revision 03.

9~ Solid Waste and Irradiated Fuel Shi ments The reactor was under construction during the first quarter of 1983.

During the second quarter of 1983 the reactor attained initial criticality in late JUNE. No solid waste or irradiated fuel shipments occurred during the second quarter.

Page 6 FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT NQ. 2 SEMIANNUAL REPORT June 2 1983 THROUGH June 30 1983 TABLE 3.3 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES NUCLIDES RELEASED UNIT I QUARTER !1 I QUARTER /2 A. Fission and Activation Products

1. Total Release (not including tritium, gases, alpha) CI 0. OOEO 2.82E-2

2. Average diluted concentration durinz eriod uCI/ml O.OOEO 2 '8E-9, B. Tritium

1. Total Release CI O.OOEO I 2.64E-1

2. Average diluted concentration durin eriod uCI/ml 0. OOEO 2. 13E-8 C. Dissolved and Entrained Gases

1. Total release CI 0. OOEO I 0. OOEO 2, Average diluted concentration during eriod uCI/ml 0. OOEO 0. OOE0 D. Gross Alpha Radioactivity

1. Total Release CI O.OOEO 0. OOEO E. Volume of Waste Released (prior to dilution) Liters 0.00EO 1. 07E6 F. Volume of Dilution Water Used During Period Liters 0. OOEO 1.24E10

Page FLORIDA PO'vKR 6 LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMIANNUAL REPORT June 2. 1983 THROUGH June 30 1983 TABLE 3 '

LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT OUARTER f 1 QUARTER 2 QUARTER 81 I QUARTER k2 I-191 I CI O.OOEO O.OOEO I O.OOEO 2.37E-5 I132 I CI I I-133 cI I I NA-24 I CI I 0. OOEO 0. OOEO I 0. 00EO 5.16E-5 CR-51 I cI I MN-54 I CI 0.00EO O.OOEO 0.00EO I 5.11E-4 co-57 I cI I CO-58 I CI I 0. OOEO 0. OOEO I 0. OOEO I 2. 52E-2 FE-55 I CI' O.OOEO O.OOEO I O.OOEO I O.OOEO FE-59 I cI I I I C0-60 I CI I O.OOEO O.OOEO I O.OOEO I 2.76E-4

~ ZN-65 I cI I I I NB97 I CI I AG-110M I CI I SN-113 I CI I SB-122 I CI I SB-124 I CI W-187 CI I 0. OOEO O.OOEO O.OOEO 3 '7E-5 NP-239 I CI 0.00EO 0.00EO O.OOEO 1.41E-3 ZR-95 CI MO-99 CI RU-103 I CI CS-134 I CI CS-136 CI CS-137 I CI BA-140 CI CE-141 CI LA-140 I cI 0 ~ OOEO 0 ~ OOEO 0.00EO 6.13E-5 ZR-97 CI

Page 8 FLORIDA PohER & LIGHT COMPAbY ST. LUCIE UNIT NO. 2 SEMIANNUAL REPORT June 2 1983 THROUGH June 30 1983 TABLE 3 '

LIQUID EFFLUENTS (continued)

CONTINUOUS MODE 'BATCH MODE NUCL IDES RELEASED UNIT QUARTER //1 QUARTER k2 UARTER /i'1 QUARTER f/2 SB-125 I CI O.OOEO O.OOEO 0.00EO I 0.00EO I I

I CE-144 I CI 0. OOEO 0. OOEO, 0. OOEO I 0. OOEO I I

SR-89 I CI O.OOEO 0.00EO O.OOEO I 7. 61E-5 I SR-90 CI 0.00EO I 0 ~ OOEO '.OOEO I O.OOEO I

I Y-90 CI O.OOEO I O.OOEO O,OOEO I 0. 00EO I I

TC-99M CI 0.00EO 0.00EO O.OOEO 6. 64E-4 PR-144 CI 0.00EO 0 ~ OOEO O.OOEO O.OOEO UNIDENTIFIED CI 0. OOEO 0 ~ OOEO 0. OOEO O.OOEO TOTAL FOR VEBZOD ABOVE CI 0. OOEO O.OOEO 0. OOEO 2.82E-2 I

AR-4 1 I CI O.OOEO 0. OOEO I 0. OOEO I 0. OOEO (

KR-85 I CI I 0.00EO O.OOEO I O.OOEO I O.OOEO I

I XE-13 1M I CI I 0.00EO 0 '0EO I O.OOEO I O.OOEO (

XE-133 I CI I O.OOEO O.OOEO I O.OOEO I O.OOEO I

I XE-133M CI O.OOEO 0 ~ OOEO O.OOEO 0.00EO I XE-135 CI 0.00EO 0.00EO 0.00EO 0.00EO I

KR-85M CI 0.'OOEO 0.00EO 0 ~ OOEO 0 '0EO I I

XE-138 CI 0.00EO 0 ~ OOEO 0 ~ OOEO 0 ~ OOEO TOTAL FOR PERIOD ABOVE CI O.OOEO O.OOEO O.OOEO O.OOEO NOTE If no value is entered for a nuclide, the value equals zero Curies.

Page 9 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO ~ 2 SEMIANNUAL REPORT June 2 1983 THROUGH June 30 1983 TABLE 3 '

GASEOUS EFFLUENTS Sf&%ATION OF ALL RELEASES NUCLIDES RELEASED UNIT I QUARTER f1 I QUARTER /2 A. Fission and Activation Gases

1. Total Release I CI I O.OOEO 1.45E-l

2. Average Release Rate for Period uCI/sec O.OOEO I 1.84E-2 B. Io dines

1. Total Iodine-131 I CI I 0. OOEO, 0. 00EO

2. Average Release Rate for Period I uCI/seel 0.00EO I 0.00EO C. Particula tes

1. Particulates T-1/2 > 8 Days CI I 0.00EO O.OOEO

2. Average Release Rate for Period (

uCI/seel 0.00EO I 0.00EO

3. Gross Aloha Radioactivit CI I O.OOEO I 1.99E-14 D. Tritium

1. Total Release CI I O.OOEO 9.66E-l

2. Average Release Rate for Period I uCI/sec 0.00EO I 1.23E-7

Page 10 FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT NO. 2 SEMIANNUAL REPORT June 2 1983 THROUGH June 30 1983 r

TABLE 3 '

GASEOUS EFFLUENTS GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE NUCLIDES RELEASED UNIT QUARTER ttl QUARTER ft2 QUARTER fkl QUARTER tt2 1 ~ FISSION GASES AR-4 1 CI O.OOEO 0 ~ OOEO O.OOEO 4.77E-2 KR-85 CI O.OOEO O.OOEO O.OOEO O.OOEO KR-85M CI 0 ~ OOEO O.OOEO O.OOEO O.OOEO KR-87 CI O.OOEO O.OOEO O.OOEO O.OOEO KR-88 CI O.OOEO O.OOEO O.OOEO O.OOEO XE-131M CI O.OOEO O.OOEO O.OOEO O.OOEO XE-133 CI O.OOEO O.OOEO O.OOEO 8.98E-2 XE-133M CI O.OOEO O.OOEO O.OOEO 2.32E-3 XE-135 CI O.OOEO ~

O.OOEO O.OOEO 4.99E-3 UNIDENTIFIED CI O.OOEO 0 ~ OOEO 0 ~ OOEO O.OOEO TOTAL FOR PERIOD ABOVE CI O.OOEO O.OOEO O.OOEO 1.45E-1 2 ~ IODINES I-131 CI 0 ~ OOEO O.OOEO O.OOEO O.OOEO I-133 CI O.OOEO O.OOEO 0.00EO 0.00EO I-135 CI O.OOEO O.OOEO O.OOEO O.OOEO TOTAL FOR PERIOD ABOVE CI O.OOEO O.OOEO O.OOEO 0 ~ OOEO 3~ PARTICULATES SR-89 CI O.OOEO O.OOEO N A N A SR-90 CI O.OOEO 0 ~ OOEO N/A N/A Y-90 CI 0 ~ OOEO O.OOEO N/A N/A UNIDENTIFIED CI O.OOEO 0. OOEO N A TOTAL FOR PERIOD ABOVE CI O.OOEO 0.00EO N/A N/A

P. O. BOX 14000, JUNO BEACII, FL 33408 6

f FLORIDA POWER 8 LIGHT COMPANY August 29, 1983 L-83-467 Nr. James P. O'Reil ly Regional Administrator, Region II U.S. lluclear Regulatory Commi ssion 101 tla ri etta Stree t, Sui te 2900 Atl an-.a, r>corgi a 30303

Dear ',

r. O'Reilly:

St. Lucie Unit 2 Vocket "(o.60-389 Semi-Annual Report o-Radioactive I' fluent Releases .

Please -;ind attached tne suo'ect report for t!Ie period June 2, 1933, tnr ougn June 30, 1983, in accordance;iith Technical Specificat.on 6.9.>.10.

Robert .". Uhrig

'Ii"e ~r es iden Advanced Systmis 8 Technology R"U/PLP/mpc Attachme~t cc: '-,'arold F. Reis, Escuire

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PEOPI.E .. ~ SERVING PEOPLE