ML17346A556

Radiological Effluent Release Data Rept, Jan-June 1984

ML17346A556
Person / Time
Site:	Turkey Point
Issue date:	06/30/1984
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17346A555	List: ML17346A553 ML17346A556 ML17346A557 ML17346A558
References
NUDOCS 8410010141
Download: ML17346A556 (39)

Text

RADIOACTIVEEFFLUENT RELEASE DATA JANUARY 1980 THROUGH 3UNE 1980 SUBMITTED BY NUCLEAR CHEMISTRY DEPARTMENT TURKEY POINT PLANT FLORIDA POWER AND LIGHT COMPANY DISTRIBUTION 3.L. DANEK A.3. GOULD (3)

D.D. GRANDAGE E.R. LAPIERRE J.S. WADE, 3R.

R.3. FRECHETTE FILE

'DR 84i00iOi4i 840830 PDR ADOCK R

05000250

J r

P

SEMIANNUALREPORTOF RADIOACTIVEEFFLUENT RELEASES PTP UNITS 3 R 0 I/80-6/80 Introduction All liquid and airborne discharges to the environment during this reporting period were analyzed in accordance with Technical Specification requirements. The minimum frequency of analysis as required by Safety Guide 21 was met or exceeded.

Li uid Releases Aliquots of representative pre-release samples were either isotopically analyzed for gamma emitting isotopes on a multichannel analyzer, or evaporated and analyzed for gross beta-gamma activity in a 2z gas flow proportional counter. The efficiency of the gas flow proportional counter is adjusted so that the activity determined by gross beta-gamma analysis approximates the isotopic activities "determined by gamma spectrum analysis and selected beta determinations, exclusive of tritium and dissolved gases.

The above procedure was followed for all releases from the waste disposal system and for secondary system batch releases. Frequent periodic sampling and analysis were used to conservatively determine if any radioactivity was being released via the steam generator blowdown system.

The following comments will aid in the interpretation and evaluation of the liquid release data presented in Table I, pages 1 through 0.

1. The reported values in Table I, page 1, 2, and 3 include in their computation the quantity of radioactivity released from both the waste disposal system" and the secondary system. The secondary system releases occurred when contaminated water which entered the plant storm drain system was released.

2. Weekly and monthly composite samples for the waste disposal system were prepared to give proportional weight to each liquid release 'made during the designated period of accumulation. The composites were analyzed for gamma emmitting isotopes on a multichannel analyzer attached to a high resolution

oi/so - o6/so Ge(Li) detector, and for Sr-89 and Sr-90, using a chemical separation and subsequent beta determination with a 2m gas flow proportional counter.

was determined by use of liquid scintillation techniques and gross 'ritium alpha radioactivity was determined by use of a 2m gas flow proportional counter. All concentrations for radioactivity determined from analysis of a composite were multiplied by the total represented volume of the liquid waste released to determine the total quantity of each isotope and of gross alpha activity released during the compositing period.

3. At least one representative batch of liquid effluent from the waste disposal system was analyzed monthly for dissolved fission and activation gases by use of gamma spectrum analysis. The resulting isotope concentrations were multiplied by the total volume released for the month in order to estimate the total dissolved gases released. If more than one batch of effluent was analyzed, the concentrations were weighted in an appropriate manner. The results are totaled on a monthly basis in Table I, page 0.

0. Representative samples of secondary system batch releases were analyzed individually for gamma emitting isotopes. Tritium analysis of a representative composite was made to determine if any tritium was being released due to primary to secondary leakage.

7. The applicable limit for release of radioactive material in liquid waste is five curies per quarter excluding tritium and dissolved gases.

Airborne Releases Airborne releases to the atmosphere occurred from: release of gas decay tanks, the instrument bleedline, containment purges, and sporadic releases incidental to operation of the plant. The techniques employed in determining the radioactivity in airborne releases are:

a) Gamma spectrum analysis for fission and activation gases,

01/8e - 06/8e b) Removal of particulate material by filtration and subsequent gamma-spectrum analysis, Sr-89-90 determination, gross alpha analysis, and gross beta-gamma analysis, c) Absorption of halogen radionuclides on a charcoal filter and subsequent gamma-spectrum analysis, and d) Condensation of water vapor in a gas sample followed by analysis for tritium using liquid scintillation techniques.

All sporadic gas releases from the plant which were not accounted for by the above methods were conservatively estimated as curies of Xe-133 equivalent by use of the plant vent process monitor recorder chart and the current calibration curve for the monitor.

The following comments will aid in the interpretation and evaluation of the airborne release data presented in Table II.

1. Calculation of total radioactivity of noble gases, I-131, and particulates is based upon detectable radionuclides only.

2. The applicable limit for release of total radioactive materials in gaseous waste is 0.012 Ci/sec when averaged over the calendar quarter. The percent of the applicable limit for total gaseous release was computed as follows:

Total curies released in gaseous waste durin uarter x 1 00%

Q$ off Limit I t=

(.012 Ci/sec) (Seconds in quarter)

3. The applicable limit for the release of I-131 and particulate radionuclides with half-lives greater than eight days in airborne waste is:

g Qi <10,000 m3, where Qi = release rate of ith nuclide, Ci/sec M PC; sec and MPC; = maximum permissible. concentration of the ith nuclide, Ci/m The release rate, Q;, was determined by dividing the total activity released in N

Ci, for the it" nuclide (ty, >8d), during the calendar quarter by the seconds in the quarter.

I a

01/8O - 06/SO MPCI values were obtained from 10CFR20, Appendix 6, Table II, Column 1.

The MPC chosen was the most conservative value of either the soluble or insoluble MPC for each isotope.

The percent of applicable

% of Limit '

Z limit was determined Qi M PCI x 10096 10,000 m3/sec as follows:

0. The maximum gaseous release rate for each month is listed in Table II, page 1,,

under Section A, Line 3. The applicable limit for maximum allowable release rate is 6.7 E+04 p Ci/sec, averaged over one hour.

5. All values reported in Table Il, pages 2 and 3, include the particulate, gaseous, and halogen activity released from the containments during purging, auxiliary building (leakage from pumps, valves, etc), and the gas waste disposal system.

If a minimum detectable activity value was not calculated for an isotope, it will be listed as ( ).

NUCLEAR CHEt I I STR Y PROCEDURE- NC-3 APPENDIX II PREPARATION OF THE HOHTllLY "Pl<ELIHIHAITY RFPORT OH RADIOACTIVE RELEASES" AHD THE YEM 1984 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF TllE SEHIAHHUAL OPERATING REPORT PAGE 1 TABLE I Report of eadioacttve tffluents: Liquid A. Gross Radsoactivit 8-5 January February are pr< Va June

1. Total Release mCi .2.75 'E+Ol 8.45 E+00 3.03 E+01 2.03 E+01 1.39 E+01 '.00 E+01

2. Av Concentration Durin Releases Ci/ml E-1

3. Av Concentration for llonth Ci/ml 8.66 E-11 3.60 E-11 1.80 E-10 1.11 E-10 9.49 E-11 7.38 E-ll Hax Concentration Released Ci/ml 1.7 E-08 7.90 E-09 3.2 E-08 7.1 E-09 4.5 E-09 6.40 E-09 i

5. Percent of Technical Specif>cation Limit for Total Activit Released 1.33 E+00 1.08 E+00 Trs tium

1. Total Release Ci 7.35 E+01 5.43 E+01 5.10 E+01 3.62 E+01 6.79 E+Ol 4.65 E+Ol

2. Av Concentration Durin Releases Ci/ml 1 07 E-06 1.69. E-06 1.14 E-06 8.40 E-07 1.93.E-06 9.53 E-07

3. Av Concentration for tlonth .

Ci/ml 2.31 E-07 2 31 E-07 3.13 E-07 1.99 E-07 4.65 E-07 1.72 E-O/

C. Disso ve Hob e Gas

1. Total Release mCi 1.96 E+03 1.19 E+02 9.23 E+02 3.03 E+00 (<1.27 E-05) 1.16 E+01

2. Av Concentration Durin Releases Ci/ml 2.85 E-08 3.69 E-09 '.07 E-08 7.03 E-ll (<3.62 E-16) 2.38 E-10

3. Av Concentration for tenth Ci/ml 6.16 E-09 5.06 E-10 5.66 E-09 1.66 E-11 (<8.70 E-17) 4.28 E-ll D. Gross Al ha Radioactsvsty

1. Total Release mCi (<6.61 E-09) <9.84 E-09) (<6.56 E-09)(<1.20 8.-08) (<1.22 E-08 (<6.87 E-Q9)

2. Av Concentration Durin Releases Ci/ml (<2.88 E-13) <4.41 E-13) (<4.30 E-13) (<8.69 E-13) (<8.89 E-13 (<2.6 -13

3. Av Concentration for tlonth Ci/ml <6.23 E-14 <6.04 E-14 <1.18 E-13 <2.06 E-13 <2.14 E-13 <4.76 E-14 E. Volumes

1. Vol of Li uid Waste to Dischar e Liters 6'.9Q E+Q6 1.48 E+Q6 1.32 E+0 5.05 E+06 3.56 E+Q6 1.88 E+06

2. Vol of Dilution Water Durin Rel. Liters 6.88 E+10 3.22 E+10 4.46 E+10 4.31 E+10 3.51 E910 4.88 E+10

3. Vol of Dilution Water for Honth Liters 3.18 E+11 2.35 E+ll .1.63 E+ll 1.82 E+11 1.46 E+ll 2.71 E+11 NOTE: Numbers in parentheses represent maximum sensitivity in tjCi/ml.

NUCLEAR CHEMISTRY PROCEDURE NC-3 APPENDIX II PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE .RELEASES" AHD THE YEAR 1984 "RADIOACTIVE EFFLUEHT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT PAGE TABLE I Report of Radioactive Efttuents: Liquid - Total 2'soto e Un>t Januar February March Aprz ay une A -110m mCi 1.65 E-01 <7.7 E-08 3.74 E-01 Ba-140 mCi (<7.5 E-07) (<3..7 E-07) (<7;0 E-07) (<5.0 E-07) (<4.3 E-07) (<2.2 E-06)

Co-57 mCi 4.98 E-02 83.5 E-08) (<5.0 E-08) (<4.1 E-08) (<3.7 E-08) (<7.0 E-08)

Co-58 mCi 5.94 E+00 2 89 E+00 9.50 E+00 1.05 E+Ol .- 6.96 E+00 9.49 E+00 Co-60 mCi 1.51 E+01 3.66 E+00 6.52 E+00 6.32 E+00 3.60 E+00 6.26 E+00 Cr-51 mCi 1.39 E+00 (<5.0 E-07) 4.05 E+00 1.44 E-Ol 7.42 E-01

~

6.34 E-01 Cs-134 1.06 E+00 4.66 E-01 1.29 E+00 7.20 E-01 5.29 E-01 1.69 E-01 Cs-136 mCi': 4.59 E-02 (<1.3 E-07) (<1.8 E-07) (<1.9 E-07) (<1.1 (<6.'5 E-07) E-07)

Cs-137 mCi 2.18 E+00 7.81 E-01 2.43 E+00 1.36 E-00 9.83 E-01

. 2.29 E-01 Fe-59 mCi (<3. 8 E-07) (<1. 7 E-07) 1.73 E-01 (<1.8 E-07) (<1.4 E-07) (<3 ..5 E-07)

I-131 mCi 1.27 E-01 1.20 E-01 1.77 E+00 8.69 E-02 (<1.0 E-07) 1.18 E-01 La-140 mCi (<5.8 E-08) (<4.0 E-08) 6.65 E-02 (<4.8 E-08) (<4.0 E-08) (<2.0 E-07)

Mn-54 mCi 1.04 E-01 (<6.9 E-08) 3.56 E-01 4.45 E-02 1.27 E-01 8.05 E-02 Mo-99/Tc-99m mCi (<6.0 E-07) (<1.5 E-07) 8.56 E-01 -(<7.5 E-07) (<3. 8 E-07) (<9.9 E-07)

Nb-95 mCi 4.05 E-01 (<7.3 E-08) 6.83 E-01 1.29 E-01 2.07 E-01 3.34 E-01 Ru-$ 03 mCi 1.23 E-01 (<7.5 E-08) 8.32 E-02 (<8.7 E-08) 2.73 E-02 (<1.7 E-07 Sb-124 mCi (<7. 9 E-08) (<4. 9 E-08) 1.34 E-ol (<5.2 E-08 <6.3 E-08 4.40 E-01 Sb-125 mCi 1.66 E-01 4.21 E-01 1.71 E+00 3.13 E-01 4 F-v NOTE: Numbers in parentheses represent maximum sensitivity in pCi/m1.

NUCLEAR CHENISTRY PROCEDURE NC-3 APPENDIX Il PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE YEAR 1984 "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEHIANNUAL OPERATING REPORT ~'

PAGE TABLE I Report of Radioactive tttf ueots: Liquid Totai

-Isoto e Un> t Februar March A ril Ma June Sr-89 mCi 2.71 E-01 1.22 E-01 8.67 E-02 5.17 -E-01 (<6.31 E-09) 1.33 E-01 Sr-90 mCi 2.2 E-02 (<4 '4 E-09) (<6.58 E-09) (<1.16 E-08) 7.39 E-02 (<6.99 E-09)

Te-132 mCi (<3.4 E-07) (<8.9 E-08) (<4.3 E-07) 9.04 E-02 (<1.8 E-07) (<5.1 E-07)

Y-88 mCi 7.38 E-02 Z -ia5 mCi 3.8 E-07 <1.7 E-07) 2.59 E-01 (<1. 7 E-07) (<1. 5 E-07) (<2.9 E-07) 2.96 E-01. %1.2 E-07 <1.8 E-07) (<l. 3 E-07) 6.37 E-02 (<2.2 E-07)

TOTAL mCi 2.75 E+Ol 8.45 E+00 3.03 E+Ol 2.03 E+Ol 1.39 E+01 2.00 E+Ol NOTE: Numbers in parentheses represent maximum sensitivity in pCi/m1.

NUCLEAR CflEHI STAY PAOCEOUAE Ilc-3

'sPVEfiOIX II PAEPAAATIOtl OF TllE tlONTllLY "PAELIHIINlIYAEI'OAT ON RADIOACTIVE RELEASES" NIO TllE

YEAR lt>84 "RAOIOACTIVE EFFLUENT RELEASES" fOATION OF TllE SEHIAffnuAL OPERATING REPORT PAG$ 4 TABLE I Report of Radtoactlve Effl ueots: L1qutd - Dtssolvad Gas ota Jantiarv Februar Harch Anril June mC! ( <3.19 E-07) ( <8.66 E-08) 1.56 E+00 (<1.53 E-07) (<8.14 E-08) (<5.19 E-08)

~

Kr-85 mCI (<4.89 E-05) (<1.66 E-05) (<3.05 E-05) (<2.06 E-05) (<1.27 E-05) (<2.20 E-05)

Kr-85m mCI 4.14 E-01 (<8.42 E-08) 3.17 E+00 (<5.26 E-08) (<4.84 E-0&) (<4.65 E-08)

Kr-87 mC$ (<8.57 E-07) (<2.82 E-07) 9.93 E+00 (<5.64 E-07) . (<3.38 E-07) (<2.03 E-07 Kr-88 (<6.06 E-07) (<3.28 E-07) 7.65 E+00 (<2.92 E-07) (<2. 26 E-07) (< 1. 79 E-07) mCI Xe-131m 1.42.E+Ol (<3.04 E-06) 1.12 E+02 (<1.36 E-06) (<1.27 E-06) (<1.40 E-06) mCI Xe-133 1.92 E+03 1.18 E+02 7.1& E+02 2.71 E+00 (<1.09 E-07) - 9.48 E400 mCI Xe-133m mCI 2.00 E+Ol 1.13 E+00 2.61 E+Ol (<3.49 E-07) (< 3.50 E-07) (< 3.71 E-07)

Xe-135 5.91 E+00 9.48 E-02 4.46 E+Ol 3.24 E-01 (<4.61 E-08) 2.09 E+00 mCI mCI flOTE; ffumbers jff parentheses represefit maxfmum sensf tfvfty In pCI/mI.

NUCLEAR CHEMISTRY PROCEDURE NC-3 APPENDIX III PREPARATION OF THE t10NTHLY "PRELIMINARY REPORT OH 'RADIOACTIVE RELEASES" AND THE YLAR 1984 "RADIOACTIVE EFFLUENT RELEASLS" PORTION OF THE SEHIAHHUAL OPERATING REPORT PAGE1 TABLE II ~

Report of Radioactive t luents: . Airborne A. Fsssson and Actsvat>on Gases Januar Februa 5farch A ril Ma June

1. TotaE Release Ci 3.51 E+03 2.04 E+03. 1.25 E+03 1.50 E+02 2.00 E+02 1.63 E+03

2. Av Release Rate for Period Ci/sec 1:16 E+03 8.42 E+02 5.17 E+02 4.96 E+01 8.27 E+01 6.74 E+02

• 3. Max Release Rate for Period Ci/sec 3.,25 E+03 3.14 E+03 2.48 E+04 2.31 E+03 4.86 E+03 3.17 E+03

• Haximum acr orne re ease rate average over one our or eac mont . Tec n>ca Spec) cat>ons smut ss 6.7 EK4 pCs sec averaged over one hour.

B. Io >ne 131

1. Total Iodine - 131 Ci 6.89 E-04 1.49 E-03 8. 6 E-

2. Av Release Rate for Period Ci/sec '.28 E-05 6.16 E-04 3.70 E-03 4.27 E-04 3.03 E-05 7.89 E-04 C. Particulates

1. Particulates with t 1/ >8 days Ci 3.52 E-05 1.56 E-05 1.17 E-04 E-04 6.08 E-05 7.29 E-06

2. Av Release Rate for Peri od Ci/sec 1.17 -E-05 6.45 E-06 4.83 E-05 E-07'.474.87 E-05 2.51 E-05 3.01 E-06

3. Gross Al ha Radioactivit Ci 1.62 E-07 1.49 E-07 1.40 7.81 E-08 7.26 E-08 . 3.73 E-08 D. Tr>t)um

1. Total Release Ci 5.55 E-02 1.75 E-02 2.87 E-02 5.68 E-03 7.14 E-03 7.76 E-0

2. Av Release Rate for Period Ci/sec 1.84 E-02 7.23 E-03 1.19 E-02 1.88 E-03 2.95 E-03 3.21 E-03 E. Percent o A >ca e L)m>t

1. Fission and Activation Gases '7.21 E+00 2.10 E460

2. I-131 and Part tl/2>8d 1.42 E-01 4.20 E-02 NOTE: Numbers n parent eses represent max>mum sens trav ty 1n pCs m .

NUCLEAR CHEMISTRY PROCEDURE NC-3 APPENDIX III PREPARATION OF THE MONTHLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE 2

YEAR~>sr, "RADIOACTIVE EFFLUENT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT PAGE TABLE II Airborne Releases - Particulates A

Isoto e Un> t January February March A ril June Ag-110 Ci '<2.4 E-14) (<2.1 E-14) ~ (<3.0 E-14) (<2.7 E-14) 1.04 E-06 (<2.1 E-14)

Ba-140 Ci (<1.0 E-13) 2.75 E-06 3.30 E-06 5.02 E-06 (<8.5 E-14) (<7.7 E-14)

Co-58 Ci 1.62 E-05 2.87 E-06 2.93 E-05 6.65 E-05 2.23 E-05 5.47 E-07 Co-60 Ci 8.70 E-06 4.24 E-06 1.66 E-05 3.49 'E-05 2..26 E-05 Cr-51 Ci 3.20 E-06 (<1.2 E-13) 6.00 E-06 2.23 .E-05 (<1.2 E-13) (<9.8 E-14 Cs-134 Ci 2.40 E-06 (<3.4 . E-14) 8.76 E-06 6.20 E-07 3.69 E-06 (<1.9 E-14)

Cs-136 Ci (<3. 6 5-14) (<3. 6 E-14) 3.55 E-06 (<4.6 E-14) (<3.3 E-14) (<3.3 E-14)

Cs-137 I-131 Ci'.23 Ci

(<1.7 E-06 E-14) 2.00 E-06 2.2 E-06 1.37 E-05 2.79 E-05 5.03 E-06 1.09 E-06 9.03 E-06

(<1.5 E-14) 2.'21 E-06

(<1.6 E-14)

La-140 Ci (<4.5 E-14) (<4.4 E-14) 6.03 E-06 4.69 E-06 (<1:8 E-14) (<3 3 E-14)

Mn-54 Ci (<2.5 E-14) 9.44 E-07 (<3.1 E-14) F 11 E-06 (<2.4 E-14) (<1.8 E-14)

Nb-95 Ci (<2.3 E-14) (<2.6 E-14) 1.22 E-06 (<3.8 E-14) (<2.7 E-14) (<2.0 E-14)

RU-103. Ci (<2.1 E-14) (<2.0 E-14) (<2.7 E-14) 1.04 E-06 (<2.0 E-14) ((1.8 E-1 Sn-117m Ci (<7.9 E-15) (<8.9 E-15) (<1.1 E-14) 5.84 E-07 (<7.0 E-15) (<7.2 E-15)

Sr-89 Ci 2;75 E-07 5.35 E-07 9.38 E-07 2.14 E-06 2.14 E-06 2.86 E-07 Sr-90 Ci 1.45 E-07 2.21 E-08 2.21 E-08 (<5.77 E-16) (<5.77 E-16) (<7.92 E-16)

TOTAL 3.52 E-05 1.56 E-05 1.17 E-04 1.47 E-'04 6.08 E-05 7.29 E-06 NOTE: Numbers in parentheses represent maximum sensitivity in pCi/ml.

NUCLEAR CHEMISTRY PROCEDURE NC-3 APPENDIX III PREPARATION OF TIIE HOHTllLY "PRELIMINARY REPORT ON RADIOACTIVE RELEASES" AND THE YEAR 1984 "RADIOACTIVE EFFLUEHT RELEASES" PORTION OF THE SEMIANNUAL OPERATING REPORT PAGE 3 TABLE II Airborne R~e eases - Gaseous l-ission and Actlvatlon Gases Isoto e Un) t January February March April May June Ar-41 Ci 2.67 E-01 2.32 E-01 5.94 E-01 1.36 E-01 1.19 E-01 2.46 E-01 Kr-85 Ci 5.24 E+00 .1.28 E+00 5.27 E+00 2.80 E-01 2.10 E+00 1.32 E+00 Kr-85m 4.26 E-02 1.11 E-01 4.85 E-01 6.60 E-03 4.20 E-03 1.75 E-02 Kr-87 Ci 3.98 E-04 5,.28 E-03 7.41 E-02 (<2.96 E-05) (<3.49 E-05) (<3.68 E-Kr-88 Ci 3.08 E-02 6.68 E-02 4.78 E-01 (<3.67 E-05) (<4.67 E-05). (<3.08 E-05)

Xe-131m Ci. 1.41 E+00 1.62 E+00 4.20 E+00 3.04 E-02 2.89 E-01 1.61 E-Ol Xe-133 Ci 3.50 E+03 2.03 E+03 1.23 E+03 1.49 E+02 1.98 E+02 1.63 E+03

'i Xe-133m 1.51 E+00 2.23 E+00 2.95 E+00 2.81 E-02 2.08 E-02 1.97 E-01 Xe-135 1.08 E+00 2.55 E+00 6.51 E+00 9.68 E-02 1.10 E-01 4.19 E-01 Xe-135m Ci Xe-138 Ci Total Ci 3.51 E+03 2.04 E+03 1.25 E+03 1.50 E+02 2.00 E+02 1.63 E+

Halo ens Gaseous Isoto e Unit January February March April May June I-131 6.89 E-04 1.49 E-03 8.96 E-03 1.29 E-03 7.34 E-05 1'.91 E-03 I-133 Ci 9.26 E-04 4.68 E-03 5.69 E-03 2.09 E-04 4.24 E-05 5.19 E-03 I-135 8.50.E-04 3.96 E-04 9.90 E-04 (<1.7 E-13) (<1. 3 E-13) 5.45 E-03 Br-82 1.57 E-05 3.94 E-05 1.90 E-04 (<5.6 E-14) (< 4. 6 E-14) 1.33 E-04 Total Ci 2 '8 E-03 6.61 E-03 1.58 E-02 1.50 E-03 1.16 E- 4 Note: um ers n paren eses represen max>inurn sens >v> y >n lr s rn .

URKEY POINT UNIT NOS. 3 6'4 RADIOACTIVE EFFLUENT RELEASE DATA JANUARY 1984 THROUGH JUNE 1984 SOLID WASTE DATE OF SHIPMENT CURIES CUBIC FEET SHIPPED TO 01-12-84 4. 55 170 BARNWELL,S .C.

01-16-84 . 393 170 BARNWELL,S.C.

01-19-84 10. 75 170 BARNWELL,S . C.

01-23-84 2.206 200 BARNWELL,S .C.

01-24-84 .04826 1050 BARNWELL,S.C.

01-26-84 2.819 200 BARNWELL,S . C.

02-07-84 .15816 1050 HANFORD, WA.

02-14-84 .08123 1050 HANFORD,WA.

02-24-84 488.0 84 BARNWELL,S . C.

03-02>>84 .061605 1050 HANFORD, WA.

03-16-84 .19249 1050 HANFORD, WA.

03-22-84 .08761 1050 HANFORD, WA.

03-22-84 .38113 170 BARNWELL,S .C.

04-10-84 5.7638 170 BARNWELL,S.C.

04-13-84 10.972 170 BARNWELL,S .C.

04-17-84 10.32388 195 BARNWELL,S.C.

04-20-84 195.085 84 BARNWELL,S . C.

04-24-84 .11479 1050 HANFORD, WA.

04-30-84 143.90 84 BARNWELL,S .C.

05-01-84 .22878 1050 HANFORD, WA.

05-04-84 .04375 1050 HANFORD, WA 05-08-84 7.06815 170 BARNWELL,S .C.

05-10-84 134.564 84 BARNWELL,S .C.

05-14-84 .76896 84 BARNWELL,S . C.

05-16-84 .156485 1050 HANFORD,WA.

05-20-84 150.700 84 BARNWELL,S .C.

05-22-84 .14769 1050 HANFORD, WA.

05-23-84 .309464 1050 HANFORD, WA.

05-25-84 13.491 195 BARNWELL,S .C.

05-30-84 1.5442 170 BARNWELL,S . C.

06-04-84 10.89047 195 BARNWELL,S . C .

06-07-84 2.404927 1050 BARNWELLgS.C ~

06-08-84 90.33 . 84 BARNWELLiS.C.

06-13-84 .32818 1050 HANFORD, WA.

06-15-84 149.72 84 BARNWELL,S .C.

35 shipments 1438.584 Ci 177/7 Cubic Feet On site as of July 1, 1984: 16.77 Ci 6730 Cubic Feet

0 TURKEY POINT UNITS 3 AND 4 PROCESS CONTROL PROGRAM

0 Pursuant to Turkey Point Units 3 & 4 Operating Procedures, the Turkey Point Plant Process Control Progran (PCP), which was revised and approved by the Plant Nuclear Safety Committee (PNSC) on June 19, 1984, is herewith attached.

Affected (revised) sections of the PCP involve the addition of statements contained in the following:

Step 4.2 - Added to prohibit solidification of the liner waste without a PCP approved by NRC and/or the PNSC.

Step 4.3 Added to prohibit the use of containers other than High Integrity Containers (HIC) for Class B and C wastes without PNSC approval. Step 4.3 ensures that liner wastes exceeding Class A limits will meet the requirements of 10CFR 61.56 (b) and the burial site.

Step 4.4 - Added to ensure that the liner wastes will be compatible with the container in meeting the requirements of 10CFR 61.56 and the burial site.

The above changes to the Turkey Point Units 3 & 4 PCP reflect guidance contained in the letter to all operating reactors and applicants for operating licenses (4-30-84), and increase the assurance that the liner waste forms will exhibit properties that meet the requirements of 10CFR 61 and of the low level radioactive waste disposal site at the time of disposal. Consequently, these changes do not constitute a reduction in the overall conformance of dewatered bead resin to existing criteria for radioactive wastes.

Verification that the PCP changes were approved by PNSC is contained on the cover sheet of the attached PCP procedure.

FLORIDA POWER AND LIGHT COt'.PANY CQopg TURKEY PCINT UNITS 3 AND 4

@0 OPERATING PROCEDURE 11550.18 HEALTH PHYSICS PROCEDURE HP-48 JUNE 19, 1984 l.e

Title:

PROCESS CONTROL PROGRAM FOR DEWATERING RADIOACTIVE WASTE LINERS 2.C proval and List of Effective Pages:

2. 1 A~rova1:

Chan9e Rated 6/19/84 Revtewed by plant Nuclear Safety 6aaettttee; 64 199 f

and Approved by Plant Vanager - Nuclear: ~ 6/19/84 2.2 List of Effective Pa es:

~Pa e Date ~Pa e Date ~Pa e Date Pa ge Da te 1 6/19/84 3 6/19/84 5 6/19/84 7 6/19/84 2 6/19/84 4 6/19/84 6 6/19/84 e 6/Io/e~

3.C

Purpose:

The Turkey Point Process Control Program (PCP) implements requirements of the Turkey Point 3 and 4 technical specifications and provides instructions for the removal of -free standing water from liners containino radioactive bead resin or charcoal.

3.1 Di scussion:

The PCP contains provisions to assure that dewatering of radioactive bead.

resin and charcoal results in a waste form with characteristics that meet the requirements of 10 CFR 61 as implemented by 10 CFR 2C and of the low level radioactive waste disposal site. The Process Control Program includes in addition to this procedure, the followino related documents:

3. 1.1 Dewatering Procedure for CNSI Conical-Bottom High Integrity Containers. CMSI No . FO-OP-OC3..

3.1.2 Test Procedure and lab record sheet for dewatering conical bottom resin liners. CNSI Project No . 11038.

3. 1.3 Dewatering procedure for the 24-inch diameter pressure demineralizing vessel containing ion-excange resin CNSI No. FC-OP-OC4.

3.1.4 CNSI Test Data, Engineering Project-11475 3.1.5 Turkey 'Point HN-IOC 1'incr dewatering test report and corre'spondence dated February 4, 1981

6/19/8>,

OPERATING PROCEDURE 11550.48, HP-4P, PAGE 2 PROCESS CONTROL PROGRAM FOR DEMATERING RADIOACTIVE M E

3. 1.6 Hittman liner dewatering reprot No . 1-843-3

3. 1e7 Hittman Process Control Program for dewatering Ton-exchange resin and activated charcoal filter media to 1/2t, drainable liquid. Yo .

STD-P-04-002 3.2 Author f ty:

The authority and r esponsibil ity to perform the requirments of thi s procedure come from 1C CFR 20, IC CFR 61, Turkey Point Plant units  ? and 4 technical specifications, and disposal site criteria.

3.3 Definitions

3.3. 1 Dewatering: The process of removing "Free Standing" water from a final disposal package.

3~ 3~ 2 "Free Standing Mater": Liquid which is not retained by the waste form.

3.3.3 Process Control Program (PCP): The Process Control Program shall contain the provisions, based on full scale testing, to assure that dewatering of radioactive bead resin or charcoal 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.

4.0 Precautions:-

4.1 Instructions used for the dewatering of liners which establish the conditions that must be met shall be based on full scale testing. This is to provide reasonable assurance that the dewatering will result in volumes of fr'ee standing water, at the time of disposal, within the limits of 10 CFR, Part 61 as implemented by 10 CFR 20 and of the low level radioactive waste disposal site.

4.2 [Solidification of radioactive waste sha11 not be performed without PMSC pPp p B . I i p I 11 iidif I g p which contains a Process Control Program (PCP) which has been approved by the NRC as satisfying the waste form requirements of 10 CFR 61. Any PCP submitted for PNSC approval must contain sufficient information to document that the final waste form will meet the requirements of 10 CFR 61.

Class "8" and "C" radioactive waste (as determined by 10 CFR 61 and Operating Procedure 11550.40) may be transferred to the disposal site in an approved High Integrity Container (HIC) . No other containers may be used without PNSC approval. Do not use High Integrity Containers for radioactive material that could chemically or physically damage or otherwise exceed the allowable limits of the HIC.

4.4 Co not use High Integrity Containers for radioactive material that could chemically or, physically .damage or otherwise exceed .the allowable limits of the HIC.

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OPERATING PROCEDURE 1155C.48, HP-48, PAGE 3 e 6/10/Pa PROCESS CONTROL PROGRAM FOR DEWATEPING RADIOACTIVE WASTE LINERS 4,5 All changes to Turkey Point Plant Process Control Program must be reviewed and approved by the PNSC before they become effective.

4.6 Al 1 changes to the Turkey Point 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:

4.6.1 Sufficiently detailed information to support the rationale for the change.

4.6.2 A determination that the change did not reduce the overall conformance of the dewatered bead resins to existing criteria for stabilized waste form.

4.6e3 Docunentation of the fact that the change has been reviewed and found acceptable by the PNSC.

4.7 Disposal of radioactive bead resin is limited to the following containers:

4.7.I CNSI Conical Bottom High Integrity Container Type PL6-8OCR 4.7.2 CNSI Conical Bottom High Integrity Container Type PL14-195CR 4.7.3 HN 1CO Steel Liner 4.7.4 CNSI 24-inch Ciameter Pressure Demineral4zer Line~~+Li l(

4.8 Disposal of charcoal filter media is limited to the following container:

4.8.1 HN 100 Steel Liner 4.9 Personnel performing dewatering procedure shoul d be aware that strong oxidizing agents such as nitric acid, when in contact with organic ion-exchange material and in the presence of air, may produce a slightly degraded resin in an exothermic reaction, up to an explosion. The first indication of an exothermic reaction due to the presence of oxidizing agents is some fming and a- slight rise in temperature on the outside of the container. If this condition is found when dewatering a vessel, the imediate action to be taken is to refill the vessel with water. This will eliminate one of the ingredients necessary for the reaction (air) and will dissipate the majority of the heat, returning the temperature of the vessel to ambient. This is a stable condition. Then your immediate supervisor must be notified.

5. 0 Responsibil i ties:

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 all liners will be dewatered in accordance with the PCP.

0 OPERATiNG PROCEDURE 11550.48, HP-48,

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PAGE 4

/10/P4 PROCESS CONTROL PROGRAM FCR DER'ATERlNG RADIOACTIVE WASTE LINERS 6.0

References:

6.1 Turkey Point units 3 and 4 Technfcal Specfffcatfons 6.2 Dewaterfng Procedure for CNSI Conical Bottom H5gh Integrity Conta5ners No.

FO-OP-003 6.3 Test Procedure and Lab Record Sheet for dewaterfng conical bottom resin liners. CNSI Project No. 11038 6.4 Dewatering Procedure for the 24-fnch diameter pressure demfneralfzfng vessel containing fon-excange resin CNSI ta. FO-OP-004 6.5 CSNI Test Data, Engfneerfng Project - 11475 6.6 Turkey Point HN-100 liner dewaterfng test report and correspondence dated February 4, 1981 6.7 Hfttman Liner Dewatering Report No. I-84'-3 6.8 Hf ttman Process Control Program for dewaterf ng 5 on-exchange resin and activated charcoal filter media to I/2% drainable liquid. No. STC-P-04-002.

6.9 Operating Procedure 11550.40 "Sh:pping and Receiving Radioactive Paterial."

6.10 10 CFR 49 6.11 10 CFR 61

(~~0~,;=":~('.12 Operating Procedure 5333. 1 "VGS - Tr ansfering Spent Storage Tank To Shielded Shipping Cask ."

7.0 Records and Notifications:

7.1 Records shall be maintained as required by this procedure and Operating Procedure 1155C.40 "Shipping and Receiving Radioactive Yaterial".

7.2 If it is suspected that the free standing water requirements may be not met for any container shipped to a disposal site, notify the Plant Panager and the Health Physics Supervisor .

703 If the Process Control Procedures have not been followed or free standing ff water is suspected in the final shipping container in amounts greater than allowed by regulations, notify the Health Physics Supervisor or his designee.

.7.4 The following are gualfty Assurance records when completed and, therefore, shall be retained in accordance with Administrative Procedure 0190.14, Document Control and Qal fty Assurance Records.

7.4.1 Specification Container Shipping Release Form (HP-72C)

/

7.4.2 User Checklist for High Integrity Container (HP-115) 7.4.3 Certification Statement for Disposal of Enviro-Safe High Integrity Container (HP-117)

IV

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OPERATING PROCEDURE 115.0.48, HP-48, PAGE

~ 6/] 0/p4 PROCESS CONTROL PROGRAM FOR OEMATERING RADIOACTIVE HASTE LINERS 7.4.4 CNSI Conical Bottom Envfro-Safe High Integrity Container Dewaterfng Completion Record to 1'I FSW (HP-116) 7.4.5 CNSI 24-inch Dfameter Container Dewaterfng Record (HP-116.1)

8.0 Instructions

8. 1 In lieu of dewatering, radioactive resin or charcoal may be shipped for disposal ff a visual inspection of the medfa during transfer, and of the final shipping container after loading, can be conducted fn a manner that will assure that the free standing liquid volte present wfll meet shfppfng, transportation and disposal site requirements.

8.2 Prior to disposal, each container shall be tested for free standing liquids fn accordance with the Process Control Program to assure that ft meets shipping, transportation, and disposal site requirements.

8.3 If the final waste form does not meet- disposal site or shipping and transportation requirements, suspend shipment for the inadequately dewatered liner and correct the Process Control Program, the procedures and/or the dewatering system as necessary to prevent recurrence.

8.4 If the dewatering fs not performed in accordance with the Process Control Program, and the dewatered liner has not been shipped for disposal, verify that each container meets burial site and shipping requirements and take appropriate administrative action to prevent recurrence.

8.5 Dewatering of Chem-Nuclear Conical Bottom High Integrity Containers (containing bead type fon-exchange resin)

8. 5.1 Obtain a positive displacement, afr generated diaphram pump such as a Qarren-Rupp Sandpiper with either 1-1/2" or 2" diameter inlet/outlet connecti ons. /

8.5.2 Connect suction of pump to the proper dewatering connections on the resin liner with a pressure tested hose of at least 1-1/2" in diameter.

8.5. Blow out service afr lines to clear any trapped liquids and then connect to the dewatering pump.

8.5.4 Connect discharge line to the pump.

8.5.5 Route the discharge of pump to approved drain line; either a floor drain or other Radwaste System as approved by Operations.

Perform a functional test of pumps and hose(s) before actual resin QOP+'. bead transfer as per FPL Operating Procedure 5333.1. (Ref. 6.12) 5.7 Transfer resin to the disposal container as per FPL Cperating Procedure 5333.1. (Ref. 6. 12) 8.5.8 l'hen all transfer and flushing operations are complete, close the fill valvestimeon dewatering the discharge line inside the started on the HP-116 South Filling Room.

Record the Form. (Ref. 7.4.4 )

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OPERATING PROCEDURE 115.C.48, HP-4P, PAGE 6

~ 6!l~te4 PROCESS CONTROL PROGRAM. FOR DEMATERING PAOIOACTIVE MASTE LINER 8.5.g Start the dewatering pump and run at > 2 strokes per second for a minimun of eight (8) hours. Stop the pump and record the time on the HP-'116 Form.

8.5. 10 Let vessel stand for a minimsn of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />. Start the dewatering pump and run at > 2 strokes per second and run for at least eight (8) hours. Record thrives on HP-116.

8.5.11 Let the vessel stand for a minimum of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />. Obtain a container such as bucket or a drum to catch discharge of pump.

CAUTION: Mater will be highly radioactive.

8. 5.12 Start the dewatering pump and run for eight (8) hour minimun. Before securing the pump, lift the suction hose to remove any pockets of measure the volte of water collected water trapped in the hose.

during this cycle. If the volte of water collected is greater than 20CC ml, repeat'he dewatering cycle of 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> standina and eight (8) hours pumping until less than 200O ml of water is collected. If the volte of water is less than 20CO ml, dewaterina is complete.

Record the volte of water collected with the start and stop times for dewatering on Form HP-116. (Ref. 7.44)

NOTE: The dewatering record HP-116 (i.e. CNSI High Integrity Container Dewatering Record to < 1f F.S.M.) must be completed and approved by the Radwaste Supervisor or his designee. The completed form will also be included in the shipping papers.

8.5.13 Disconnect hoses from liner and prepare the liner and cask for shipment. Secure the container as per the manufacturers instructions.

8.C Dewatering of Chem-I!uclear 24 inch Diameter Pressure Demineralizer Liner.

8. 6.1 Upon completion of waste processing, remove liner from service.

8.6.2 Set the liner .in a level position.

8.6.3 Connect the suction hose to the dewatering connection on the liner and to the inlet of positive displacement, air operated diaphram punp. Route the pump discharge to approved drain line or floor drain.

8.6.4 Start the dewatering pump and run at > 2 strokes per second.

8.6.5 Continue pumping for a minimize of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, then shut off the pump.

Enter the start and stop time on the form, HP-116- 1. (Ref. 7.4.5) 8.6.6 Mait a minimum of 24 hours after securing the pump, then restart the pump. Enter the'ime on Form HP-116. l.

.8.6.7 Adjust the pump air supply to establish a minimum pumping rate of 2 strokes per second.

8.6.8 Continue pumping for a minimum of 1 hour, then secure the pump.,

Enter the time on Form HP-116. 1.

~ ~ 6/19/P4 OPERATING PROCEDURE 11. 0.48, HP-~8, PAGE 7 PROCESS CONTROL PROGRAM".. FOR DEWATERING RADIOACTIVE WASTE LINERS 8.6.9 Neasure the ~ater collected with a oraduated cylfnder.

8.6.10 If more than 5CO mls are collected and measured fn the prevfous step, let the vessel stand for a mfnfmum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and repeat Steps 8.2.F thru 8.2.9. Continue to repeat the wafting/pumping cycle until less than 500 mls are collected during the pumping steps. Enter volume and times on Form HP-116. 1.

NOTE: The Dewaterfng Record HP-116.1. (f.e. CNSI 24 inch Diameter Conta f ner Dewa te ring Record to < C.5%. F.S. W; ) must be completed and approved by the Radwaste Supervisor or hfs designee. The completed form will also be included fn the shipping papers .

8. 6. 11 The final dewatering shall be performed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of shipping liner for disposal.

8.7 Dewatering of Hittman HN 100 with bottom drain.

II 8.7.1 Upon completion of waste processino remove the liner from service .

8.7.2 Set fn tipped configuration, (Approx. 1C with bottom drain at low point) .

8,7.3 Connect the dewatering line to the suction side of a positive displacement, afr operated dfaphram pump and to the connection on the bottom drain of the Hittman Liner. Remove vent cap cover.

8.7.4 Start the dewatering pump and run at > 2 strokes per second for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Stop the pump after 24 hours.

8. 7.5 Let the liner stand for 16 hours.

I 8.7.6 Obtain a container to collect discharge of pump.

CAUTION: Water will be highly radioactive.

8.7.7 Start the pump and collect discharge for 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s- Before securing the pump, lift the suction hose to remove any trapped water in the line.

8~ 7.8 If collected water is greater than 5CO ml, repeat Steps 8. 7. 5 thru 8.7.7 until less than 5CO ml is collected.

8. 7. 9 If collected water is less than 500 ml, proceed to Step P.7. 10.

8.7.10 Remove the dewatering line from the bottom drain and attach the line to the underdrain connection located on the top of the liner.

8.7.11 Obtain a container to collect discharge of pump .

8.7.12 Run pump for 8 hours collecting all pump discharge. Before sec'uring the pump, line.

lift the suction hose to remove any trapped water in the

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OPERATING PROCEDURE 1155C.48, HP-4P, PAGE 8 6/19/P.4 PROCESS CCNTROL PROGRAM FOR DERATEPI)JG RADIOACTIVE HASTE LINERS I

I 7.13 If collected water is greater than 500 ml, reconnect the suction hose to the bottom drain and repeat all Steps from 8.7.5 thru 8.7.12.

@Qo 8.7.14 If collected water is less than 5DC el, proceed to Step 8.7.15. The final dewatering shall be performed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of shipping liner

, for disposal.

8.7. 15 Disconnect the dewatering line and ensure that the plug is secured in the bottom drain.

8.7.16 Install the vent cap covers and the top cover on the liner. Secure the liner for shipment.

8.7.17 Complete the Hi ttman Liner Dewatering Record on page 4. of HP-72C (Ref. 7.4.1) with all the required data.

QQQ+c)

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