L-76-318, Letter Enclosing Semiannual Radioactive Effluent Release Report for the Period January 1, 1976 Through June 30, 1976

Letter Enclosing Semiannual Radioactive Effluent Release Report for the Period January 1, 1976 Through June 30, 1976

ML18088A935
Person / Time
Site:	Saint Lucie
Issue date:	08/31/1976
From:	Robert E. Uhrig Florida Power & Light Co
To:	Moseley N NRC Office of Inspection & Enforcement (IE Region II), NRC/RGN-II
References
L-76-318
Download: ML18088A935 (20)

Text

U.u. NUCLEAR BEOULATOBV C "SION DOCKET NUMIIER NIIC I:OBP 196 I2 70 I 50-335 FILE NUMOFB NRC DISTRIBUYIQN.ron PART 60 DOCI<ET MATERIAL ENVIRONMENTAL

,TPI N.C." MOSELEY FROM: FLORDIA POWER & LIGHT CO. DATE OF DOCUMENT MIAMI, FLORDIA 8=31-76 R.E. UHRIG DATE RECEIVED 9-7-76 8LETTER CINOTOBIXED PROP INPUT FORM NUMI3EB OF COPIES RECEIVED SORIQINAL 8 UN C LASS IF I E D OCOPY DESCRIPTION ENCLOSURE ENVIRONMENTAL SEMI-ANNUAL RADIOACTIVE EFFLUENX LTR. TRANS THE FOLLOWING........ REPORT FOR THE PERIOD APRIL 22 TO JUNE 30, 1976...

( 25 CARBON SIGNED CYS. RECEIVED)

( 14 PAGES)

Do NOT REMOVE ACKNOWLEDGED PLANT NAlfE: ST. LUCIE 8 1 SAFETY FOR ACTION/INFORMATION ASSIGNED AD: ASSX NED ANl.H CHTFF. ZIEMANN C LY PROJECT lfANAGER: PRO E "fANA

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/ FLORIDA POWER & LIGHT COMPANY OOCmiIII U C August 31, 1976 L-76-318

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Norman C. Moseley, D Ctcr Mo;I Sub' Office of Inspection or"c'ement egion U. S. Nuclear Regulato 3.SS 230,Peachtree Street, N 18 Atlanta, Georgia 30303

Dear Mr. Moseley:

Re: St. Lucie Unit 51, Docket No. 50-335 Semiannual Radioactive Effluent Report Enclosed herewith are two copies of the St. Lucie Unit, 1 Semiannual Radioactive Effluent Report for the period April 22 (initial criticality) to June 30, 1976. This report is submitted in compliance with Environmental Tech-nical Specification 5.6.l.c.

Section 8, Meteorological Data, has been includ'ed in ~his report at the request of the NRC staff. As indicated in the report, meteorological data have been acquired and are now

. being processed. A supplemental report will be submitted at a later date in the format suggested by Regulatory Guide 1.21.

Meteorological data will not normally he submitted with our Semiannual Radioactive Effluent Reports. Summaries of the data and observations will be available upon request in accordance with Environmental Technical Specification 3.3.

Yours ery truly, Vice President REU/NR/hlc Enclosures cc: Director, Office of Inspection Enforcement (25)

S Director, Office of Management Information and Program Control (2)

Jack R. Newman, Esq.

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FLORIDA POMER 6 LIGHT COMPANY ST. LUCIE PLANT UNIT 81 LICENSE PDPR-67 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT for the period January 1, 1976 through June 30, 1976 Prepared August 16, 1976

TABLE OF CONTENTS Sub ect ~Pa e INTRODUCTION Effluent and Waste Dis osal Sun lemental Information

1. Regulatory Limits 2

2. Maximum Permissible Concentrations 3 3~ Average Energy Gaseous Effluents 3

4. Measurements and Approximations of Total Radioactivity 3

5. Batch Releases 5

6. Abnormal Releases 6

7. Solid Waste and Irradiated Fuel Shipments 6

8. Meteorological Data 6 TABLES 4.1 Rad"oactive Liquid Effluent Sampling and Analysis 4 4.2 Radioactive Gaseous Waste Sampling and Analysis 5 5.1 Liquid Effluents Summation of All Releases 7 5.2 Liquid Effluents 8 5.3 Gaseous Effluents Summation of all Releases 9 5.4 Gaseous Effluents 10 7.1 Solid Waste and Irradiated Fuel Shipments 11

t INTRODUCTION This report is submitted in accordance with St. Lucie Plant Technical Specification Section 5.6.l.c.

This report gives the data necessary to meet the semiannual reporting requirements for radioactive effluent releases during the period of January 1, 1976 through June 30, 1976.

In submitting this report, we emphasize that St. Lucie Plant did not reach criticality until the second quarter. Therefore, the data presented covers plant releases that have occurred after criticality. None of these releases exceeded regulatory limits.

All liquid and airborne discharges to the environment during this reporting period were analyzed in accordance with Technical Specification require-ments. The minimum frequency of analysis as required by these require-ments has been met or exceeded.

Page 2 EFFLUENT + HASTE DISPOSAL SUPPLEMENTAL INFORMATION

1. Regulatory Limits 1.1 For liquid waste effluents

a. The concentration of radioactive materials released in liquid waste effluents from all reactors at the site shall not exceed the value specified in 10CFR Part 20, Appendix B, Table II, Column 2, for unrestricted areas.

b. The cumulative release of radioactive materials in liquid waste effluents, excluding tritium and dissolved gases, shall not exceed 10 Ci/reactor/calendar quarter.

c. The cumulative release of radioactive material in liquid waste effluents, excluding tritium and dissolved gases, shall not exceed 20 Ci/reactor in any 12 consecutive months.

1.2 For gaseous waste effluents

a. (1) The release rate limit of noble gases from the site shall be such that 2.0 (QT K ) <1 V V and 0.33 (QT (LV + 1.1 NV) ) <1 V

(2) The release rate limit of all radioiodines and radioactive materials in particulate form with half-lives greater than eight days, released to the environs as part of the gaseous

,wastes from the site shall be such that 5.5 x 10 QV

<1

b. (1) The average release rate of noble gases from the site during any calendar quarter shall be such that 13 (QT TV N) <1 and 6.3 (QT FQ) <1

Page 3 Effluent + Waste Dis osal Su lemental Information (cont.):

1. Regulatory Limits (cont):

l. 2-b (cont)

(2) The average release rate of gases from the site during any 12 consecutive months shall be 25 (QT NV) <1 V

and 13 (QT V

Q) <1 (3) The average release rate per site of all radioiodines and radioactive materials in particulate form with half-lives greater than eight days during any calendar quarter shall be such that 13 '(5.5 x 10 QV -1 (4) The average release rate per site of all radioiodines and radioactive materials in particulate form with half-lives greater than eight days during any period of 12 consecutive months shall be such that 25 (5.5 x 103 QV) <1 (5) The amount of iodine -131 released during any calendar quarter shall not exceed 2 Ci/reactor.

(6) The amount of iodine -131 released during any period of the 12 consecutive months shall not exceed 4 Ci/reactor.

2. Maximum Permissible Concentrations AIR- 10CFR Part 20, Appendix B, Table II, Column 1 WATER 10CFR Part 20, Appendix B, Table II, Column 2

3. Average energy of fission and activation gases in gaseous effluents are not applicable.

4. Measurements and Approximations of Total Radioactivity A summary of liquid effluent accounting methods is described in Table 4.1.

A summary of gaseous effluent accounting methods is described in Table 4.2.

Effluent +

4.

t Waste Dis osal Su Measurements and Approximations ilt!

lemental Information (cont.):

of Total Radioactivity (cont):

Page 4 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%.

(b) Analytical Error for Nuclides

~Te Aver~ac Maximum Liquid ~9/ ~ 30%

Gaseous + 8% '+ 25%

Table 4.1 Radioactive Li uid Effluent Sam lin and Anal sis Liquid Sampling Type of Method of Source Fre uenc Anal sis Anal sis Monitor Each Batch Principal Gamma Emitters P.H.A.

Tank Releases Monthly H-3 L.S.

Composite Gross Alpha G.F.P.

Quarterly Composite Sr-90, Sr-89 C.S. & L.S.

Continuous No continuous activity releases for this reporting period Releases 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-drifted Germanium, detectors. All peaks are identified and quantified.

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

Page 5 Information (cont.):

4. Measurements and Approximations of Total Radioactivity (cont.):

.(b) cont.

Table 4.2 Radioactive Gaseous Waste Sam lin and Anal sis Gaseous Sampling Type of Method of Source Fre uenc Anal sis Anal sis Waste Gas Princi al Gamma Emitters. (G C P) - P.H.A.

Decay Tank Each Tank H-3 L.S.

Releases Containment Each Princi al Gamma Emitters G C P)

Purge Purge L. S.

Releases Plant Weekly Princi al Gamma Emitters (G C P Vent H-3 L.S.

Monthly Composite Gross Alpha P- G.F.P.

Particulates Quarterly Sr-90, 89 C.S. & L.S.

Composite (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.F.P. Gas Flow Proportional Counting.

5. Batch Releases

a. Liquid

1. Number of. batch releases: 37

2. Total time period of batch releases: 7837 min

3. Maximum time period for a batch release: 976 min

4. Average time period for batch releases: 211.8 min

5. Minimum time period for a batch release: 23 min

6. Average stream flow during periods of release of effluent into a flowing stream: 392510 gpm All liquid releases are summarized in TABLES 5.1 and 5.2.

Page 6 Effluent + Waste Dis osal Su lemental Information (cont.):

5. Batch Releases (cont.)

b. Gaseous

1. Number of batch releases: 31

2. Total time p'eriod for batch releases: 7533 min

3. Maximum time period for a batch release: 960 min

4. Average time period for batch releases: 243 min

5. Minimum time period for a batch release: 40 min All gaseous waste releases are summarized in TABLES 5.3 and 5.4.

6. Abnormal Releases

a. Liquid

1. Number of releases: 0

2. Total activity releases: 0.0

b. Gaseous

1. Number of releases: 0

2. Total activity released: 0.0

7. Solid Waste and Irradiated Fuel Shipments TABLE 7.1 is a summary statement of this waste management activity.

I

8. Meteorological Data Cumulative data on frequency distribution of wind speed, wind direction and atmospheric stability have been acquired during this report period.

These data are now being processed and will be submitted in the form suggested by Regulatory Guide 1.21 as a Supplemental report.

Page 7 IDA POLAR 6 LIGHT COMPANY ST. LUCIE UNIT j/1 S'emiannual Report Jan. 1 through June 30; 1976 TABLE 5.1: LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Q Unit Quarter $ ~~ 2 A. Zission and: activation products Total release (rat mcludmg train, E I. 03 E"Z s, al ha)

2. Average diluted concentratzan during period

3. Percent of applicable limit E i. O3 E-3 B. Tritium

1. Total release

2. Average dilute corxentraMon i.17 E-7 dur oer1cd C. Dissolved and entx'a'ned gases

1. Total re~~e Ci . E

2. Average fluted concentration

'. dQZZIl Percent

'tered of applicable ~t E QA. E D. Gross alpha radioactivity

1. Total release E 000 E 0 E t 07 E6 F. Voluna of dilution water used duzinp per'od liters ~ E l.l6 El

Page 8 FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNJiT 81 Semiannual Report Jan. 1'hrough I

~

June 30, 1976 TSQ3LE 5.2:, LXQUXD EFFLUENTS Nuclxdes Re3.eased strcntxun-8 Quoit k Q~~r g ~ 0 iduar~ ZQu'~er E O.OOE . E P.0OE 0 stxcntxun-90 E 0 OOE 0 . E O.OOEO CBSLTXA-134 O.OOE O.OOE 0 E 0 . E cesiun-137 F '.OOE 0 . E 0.00E 0 E 0 OOE 0 . E ).05'E 4.

ccbalt-58 E 0.00E 0 O.l+. E-~

ah-Q.t-GQ 'E O'0E 0 E 2.73 E-5 ixcn-'59 E 0.00E 0 0.00 E 0 zinc-59 000E 0 0OOEO 54 E 0.00 E 0 000EO chxaaiun-51 E 6.00 E 3.86, E-4

'r:~odium-95 ~ E 0-00 E 0 0.00 E O aalyM~~99 E 0.00E 0 ." E. 2.27 E-'5 tec'.umtiun-9'mrit~lan E 000 E 0 . E 0.00 E. 0

~un-140 0-00 E C 0.00 E 0 cerium-141 0-0OE O O.OOE 0 Ot~ (sp cify) ~

Fluorine 18 E 0.00 E 0 $ .40'E-Q Sodium - 24 E 000E 0 ~ E l.66 E-9 Tun sten 187 E 0.00E a E 5;57 E-f Iodine 133 E 0 OOE Q E 2. ~O E-.A Antimony 124 E 0 ~ OOE 0 E (.5( E-3 Antimony ],22 E QGO E 0 E 1.47 E-3 Pc@'xQd . s~ E 0.00 E 0 . E l.o3 E-2.

xe run-l33 E 0+00 E 0 5.R-3 E-5 Xenxr E 000 E 0 0.00 E 0

page 9 LORIDA POWER 6 LIGHT COMPANY ST. LUCIE UNIT 81 Semiannual Report Jan., 1 through June 30, 1976 TABLE 5. 3: GASEOUS EFFLUENTS-SUCTION OF ALL RELEASES Unit Quart~

gi A. Fission & activation gases

l. Total release E 7.IEE i

2. Average release rate for period ~C'/sec E L.28E i

3. Percent of Technical specification limit E 3,87E-Z

~

B. Xodines

l. Total iodine-131 3,50E-7

2. Average release rate for period yCi/sec E 5.8>E-e

3. Percent of Technical spe if'.cation limit C. P arti,cul ates

l. Particulates with Pa1f-lives' days E 0,00E 0

2. Average relmsa rate for period gG4fsec ~ E 0 .dOE 0

3. Percent of Technical specification limit E 0.00E 0

4. Gross alpha. radioactivity O.OOE 0 D. Tritium

l. 'Ibtal release 5'.42E-1

2. Average release rate fax period pCi/sec 9 .00E-2.

page 10 FLORIDA POWER & LIGHT. COMP ST. LUCIE UNIT 81

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Seminannua1

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Report Jan. 1 through June 30, 1976

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TABLE 5 GASEOUS EFFLUENTS i%DE BATCH KXE Nuclides Released +4 Unit Quarter i Quarter 2 Quarter) Quar~2

l. Fission gases kr aton-85 8 Sl E-9 E 3.63 E-2,

~

kr ton-85m +l E o . E 4.78 E"l kr ton-87 E 0 oOE 0 E 1.3o E-3 kr ton-88 E oooEo E l .06 E"2 xenon-133 E I -l9 E E 4.9I E I xenon-135 E '2. 96E 0 E 3.7s' 0 xenon-135m E'-OOE 0 E l.6S E-+

xenon-138 E ooQE 0 E 0-0OE 0 Others (specs.f ) E 0-00 0 E E O.OOEo E o.oO E 0 E B ..')8 E" I E o.oo E 0 E 4.2A E-l unxdentz.fied E 0 ocEO E o.oOEO Total for era.od E I 66E E g.+6Ei

2. Iodine s Pig 1 t1~>>

)A 1 E 0 coE 0 E 3 iso E-7 iodine-133 oooE o E l .2.l E-6 moderne>>135 oooE o E 0,00 EO Total for uerzod E o.ooE o E I .i6 E" 6

3. Particulates strontz.un-89 E o.OOE o . E o.Oo E 0 stront3.um 9 C OcoEO . E Q.co E 0 cesium-134 o ooE o . E 0.00' 0 cesium>>137 o.co E o o.co "0

=

bar~urn>>lanthanum-140 o'oo-"" 0 o.c E Q Others (s eczf ) E o ooE 0 O-oo E O E o coE 0 ~ E o ooEo E oooE o . E 0.00 E 0 unxdentxfzed E cooE o . E o-oo E 0

Page 11

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FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT gl SEMIANNUAL REPORT I JANUARY 1 THROUGH JUNE 3 0 I 1 97 6 TABLE 7.1: SOZID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WRY SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 6-ninth

1. Type of waste Unit Period

a. 'Spent resins, .filter sludges, evaporator m 3

0.00 E 0 bottans, etc. Ci 0.00 E 0 Dry compressible waste, contaminated 0.00 E 0

., etc. ~

Ci 0.00 E 0

c. Irradiated canmonents, control m 0.00 E 0 rcds, etc. Ci 0.00 E 0

d. Other describe) m 0.00 E 0 Ci 0.00 E 0

2. SOLID WASTE DISPOSITION Hcadx~w of Shi ts Mode of Tr rtation Destination None N/A N/A B. IRRADIATED FUEL SHIPMENTS {Disposition)

Number of Shi ents Mode of Tran rtation Destination None N/A N/A

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