ML19290B882

Effluent,Waste Disposal & Potential Doses Semiannual Rept, Jan-June 1976.

ML19290B882
Person / Time
Site:	Brunswick
Issue date:	08/12/1976
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML17174B224	List: ML17174B223 ML19290B882 ML19290B883 ML19290B884 ML19290B885 ML19290B886 ML19290B887 ML19290B888 ML19290B889 ML19290B890 ML19290B891
References
FOIA-79-488 9298, NUDOCS 7912140317
Download: ML19290B882 (16)

Text

Docket # [C 3 d/-f Control # iS.e) f Date Reevd.g_ g 7. 75 ,

Regulatory Docket File ATTACEMENT 1 EFFLUENT, WASTE DISPOSAL, AND POTENTIAL DOSES SEMIANNUAL REPORT January - June 1976 Brunswick Steam Electric Plant August 12, 1976

• "' manmm

,,;;gy, 1578 014

i 7912140 37f U-

% 2 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

. 1976 Supplemental Information h Facility Brursvick Steam Electric Plant License Carolina Power & Light Co.

1. Regulatory Limits

a. Fission & activation gases EE g {0.72 Q, + 290 Qy) 1 1 quarterly average IE9f22 Qs + 200 Qy } 1 1 quarterly average IEg {1.4 Q, + 580 Q y} 1 1 12 month average IK {45 Q s+ 400 Q }y 11 12 month average

b. Iodines 2 Curies per quarter 4 Curies per 12 months

c. Particulates, half-lives >8 days

{4.7 x 105 }Q + {7.2 x 10 7}Q 1 1 quarterly average 5 8

{9.3 x 10 }Q, + {1.5 x 10 )Qy 1 12 month average

d. Liquid effluents 10 Curies per quarter 20 Curies per 12 months

2. Maximum Permissible Concentrations

a. Fission & activation Gases IQ3 {4.0 E + 0.23 E } + Qy {35E + 92 E } 1 1

b. Iodines

{3.7 x 10 }Q, + {5.8 x 106 } Q 1 1

c. Particulates, half-lives > 8 days .

{3.7 x 10'}Q, + {5.8 x 10 6

)q i i

d. Liquid Effluents values specified in 10CFR Part 20, Appendix B, Table II, Column 2 for unrestricted areas.

1578 015

% s

3. .$verage Energy Y.y- 1.05 MEV E 6 = o , v7 e ..

4. Measurements and Approximatsm- - al Radioactivity

a. Fission and activation g .e Analysis for specific radionuclides in representative grah. samples by gac:ma spectroscopy.

b. Iedines Analysis for specific radionuclides collected on charcoal cartridges by gamma spectroscopy.

c. Particulates Analysis for specific radionuclides collected on filter papers by gamma spectroscopy.

d. Liquid effluents Analysis for specific radionuclides by individual releases by gac=a spectroscopy.

Relative variance for each measurement used in calculating activity values were combined using. the additive property of variance. The square root of the combined variance was extracted to obtain an estimate of the standard deviation of the multistep process. The standard deviation was used to evaluate the error in the calculated activities at the 95% confidence level.

5. Batch Releases

a. Liquid

1. Number of Batch releases: 594

2. Total time period for batch releases: 4.83 E04 minutes

3. Maximum time period for a batch release: 2010 minutes

4. Average time period for batch releases: 81.3 minutes

5. Minimum time period for a batch release: 4 minutes

6. Average stream flow during periods of release of effluent into a flowing stream: not applicable

b. Caseous -

1. Number of batch releases: none

2. Total time period for a batch release: not applicable

3. Maximum time period for a batch release: not applicable

4. Average time period for a batch release: not applicable 1578 016

5. Mini =um time period for a batch release: not applicable

m >

~

.' r au

6. Abnormal Release

a. Liquid

1. Number of releases: none

2. Total activity released: none

b. Caseous

1. Number of release: 1

2. Total activity released: 3.81E-4Ci 1578 017

= ,

TABLE-1A EFFLUEhT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) 1976 CASE 0US EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Tota II I II A. Fission & activation cases Ci 150.06 69'.21 1.33E01

1. Total release Average release rate for period UCi/ sec 2.07E-05 2.50E-05 2.

Percent of Technical specification limit  % 2.40E-02 8.93E-03 3.

B. Iodines

1. Total iodine-131 Ci 3.15E-a3 1.13r 04 1.33E01 Average release rate for period UCi/sec 4.30E-10 2.16E-ll 2.

Percent of technical specification limit  % 7.08E-02 2.80E-05 3.

C. Particulates Particulates with half-lives > 8 days Ci 1.01E-02' 3.58E 03 1.33E01 1.

UCi/see 1.35E-09 6.97E-10

2. Average release rate for period Percent of technical specification limit  % 1.92E00 1.67E00 3.

Ci 0.00 0.00

4. Gross alpha radioactivity D. Tritium

1. Total release Ci 1.77E01 3.49E00 1.45E01

2. Average release rate for period ~ uCi/see 2.44E-06 6.73E-07

3. Percent of t,chnical specification limit  % 6.96E-02 3.19E-03

)578 D18

.a 8 . ' ' a s TABLE la EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) 1976 GASEOUS EFFI.UENTS-ELEVATED RELEASE Continuous Mode Batch Mode II 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission gases krypton-85 Ci 0.00E-00 'O.00E-00 l krypton-65m Ci 2.00E00 4.77E00 krypton-87 Ci 1. 56E01 9.88E00 krypton-88 Ci 0.00E00 4.25E00 xenon-133 Ci 0.00E-00 6.03E00 xenon-135 Ci 1.90E01 0.00E00 xenon-135m Ci 0.00E00 0.00E00 xenon-138 Ci 0.00E00 0.00E00 I Argon-41 Ci 1.14E02 3.62E01 C1 Ci unidentified Ci 0.00E-00 0.00E00 l i Total for period C1 1.50E02 '

6.92E01 i  !

2. Iodines iodine-131 LCi '3.03E-3 1.13E-04 iodine-133 Ci 1.02E-03 3. 03E-04 i iodine-135 Ci 3.74E-05 2.83E-05 i Total for period C1 2.60E-2 14.43E-04 I

3. Particulates strontium-89 Ci '6.58E-06 1.02E-V5 I strontium-90 Ci 0.00E-00 0.00E00 cesium-134 Ci 'O.00E-00 0.00E-00 cesium-137 Ci 0.00E-00 0.00E-00 barium-lanthanum-140 Ci 0.00E-00 0.00E-00 Cobalt-58 C1 1.25E-05 7.86E-08 Manganese-54 Ci 6.55E-03 0.00E-00 Cerium-139 Ci 0.00E-00 5.23E-07 unidentified 'Ci 0.00E-00 0.00E-00 l Total for period ici 6.57E-03 I I. 03E- 06 t

)E 0

..a . .. TABLE 1C ,

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) 1976 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES Continuous Mode Batch Mode II lst 2nd Nuclides Released Unit Ouarter Quarter Quarter l Quarter

1. Fission gases krypton-85 Ci I 0.00E-00 ' O.00E-00 krypton-85m Ci '

O.00E-00 0.00E-00 krypton-87 Ci 0.00E-00 0.00E-00 krypton-88 Ci 0.00E-00 0.00E-00 xenon-133 Ci 0.00E-00 0.00E-00 xenon-135 Ci 1 0.00E-00 0.00E-00 I xenon-135m Ci l 0.00E-00 0.00E-00 1 xenon-138 Ci 0.00E-00 0.00E-00 C1 Ci Ci unidentified Ci 0.00E-00 0.00E-00 Total for period Ci 0.00E-00 0.00E-00 -

2. Iodines iodine-131 Ci 1.23E-04 0.00E-00 l iodine-133 Ci 1.20E-04 0.00E-00 i iodine-135 Ci 3.88E-06 0.00E-00 i Total for period C1 2.47E-04 0.00E-00 i

3. Particulates l strontium-89 Ci 8.32E-06 7.62E-06 i

• strontium-90 Ci 0.00E-00 0.00E-00 I cesium-134 Ci 0.003-00 0.00E-00 i  :

cesium-137 Ci 0.00E-00 0.00E-00 ;

I barium-lanthanum-1401 Ci 0.00E-00 0.00E-00  :

Cobalt-58 Ci 5.30E-04 7.44E-04 i i Cobalt-60 Ci 1.79E-04 l 5.85E-04 Chromium-51 l Ci  ! 1.45E-03 l 7.85E-04 ,

I Zirconium-Niobium-95 l Ci 3.31E-04 '

3.33E-04 ; i Zine-65 -

l Ci 1.39E-04 2.56E-04 i _

i Iron-59 i ci 2.39E-04 l 1. 35E- 04 i  !

Manganese l Ci i 4.10E-04 1 7.28E-04 1 Molybdenum-99 l Ci 9.28E-05 0.00E-00 l l Technetium-99 Ci 9.87E-05 0.00E-00 '

I Zirconi.m-97 Ci 0.00E-00 4.38E-09 Niobium-97m i Ci f ,0.00E-00 4.20E-09 unidentifed I ci 1 0.00E-00 0.00E-00 Total for period Ci i 3.48E-03 I 3.57E-03 I 1573 020

..i....

NOTES:

1) Minimum detectable concentrations for radionuclides not detected (uCi/cc):

Kr-85 5.40E-06 Kr-88 6.05E0"08 Xe-133 4.15E-08 Xe-135m 2.87 E-08 Xe-138 1.85E-08 Cs-134 1.74E-14 ~

Cs-137 1.29E-14 Ba-La-140 2.93E-14

2) No batch releases were made during the first or second quarter.

i J

l I

4 0

i

TABLE 2A

=

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) 1976

}

r TIQUID EFFLUENTS-SUIOfATION OF ALL RELEASES Unit Quarter Quarter Est. Total Error, %

let 2nd A. Fission ald activation products

1. Total release (not includin8 Ci 'l.15E01.

tritium, gases, aloha) 6.00EsOf 5.47E.01~

2. Average diluted concentration uCi/ml

~9 during period -

3. Percent of applicable limit

% 3.00E-00 2.74E-00 B. Tritium

1. Total release Ci 1.12E00 1.01E00 1.33E01

2. Average diluted concentration uCi/cl 2.78E-08 1.81E-08 during ceriod _

3. , Percent of applicable limit  % 9.26E-4 6.00E-04 C. Dissolved and entrained gases I

l. Total release C1 2.2E-03 2.11E-04 1.15E01

2. Average diluted concentration uCi/ml 5.46E-ll 3.77E-12 during period

3. Percent of applicable limit  : 1.81E-05 1.23E-06 _

D. Cross alpha radioactivity l

1. Total release Ci 0.00E00 10.00E00 1.22E01 E. Volume of waste released (prior to liters ~

6.45En6' 1.36507' 5.66E00 dilution) l F. Volume of dilution water used 11 tars 4.03E10 5.59E10 1.10E01 during period 1578 022

..i.- . . .

TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) 1976 LIQUID EFFLUENTS Continuous Mode Batch Mode 1st i 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter strontium-8; Ci 1.46E-05 1.43E-04 strontium-90 Ci 8.82E-06 6.68E-05

- cesium-134 Ci 1.56E-06 0.00E00 cesium-137 Ci 2.27E-06 0.00E00 iodine-131 Ci 1.45E-04 0.00E00 cobalt-58 Ci 4.76E-02 5.86E-02 cobalt-60 Ci 1.67E-02 4.49E-02 iron-59 Ci 2.13E-02 2.45E-02 zinc-65 Ci 1. 08E-02 2.87E-02 manganese-54 C1 2.89E-02 5.48E-02 chromium-51 Ci 1 1.60E-01 1.llE-01 zirconium-niobium-95 Ci l 9.44E-03 8.98E-02 molybdenum-99 Ci 1 2.40E-03 2. 26E-04 technetium-99m Ci 3.29E-03 2.06E-04 barium-lanthanum-140 Ci 0.00E00 2.31E-06 cerium-141 lCi 8.91E-06 0.00E00 Cnrbon-14 .Ci 0.00E00 2.50E-04 Fiuorine-18 .Ci 1.06E-01 6.18E-02 Sodium-24 Ci 8.36E-02 1.35E-02 Scandium-46 Ci 6.65E-06 Manganese-56 Ci 1.35E-03 6.73E-04 Copper-54 Ci 5.63E-02 l

1.79E-02 Cobalt-57 Ci 1 2.56E-06 5.94E-04 Gallium-72 Ci 1.44E-03 7.67E-03 Arsehic-76 Ci 1.89E-02 1 3.67E-03 Niobium-97 Ci , 1.29E-03 1. 88 E-04 Tin-113 Ci 1.30E-05 3.43E-05 l Indium-113m Ci __ _ _ 2.32E-05 5.26E-05 Tin-ll7m Ci i i 8.24E-06 0.00E00 Antimony-122 Ci I ) 1.24E-04 0.00E00 Antimony-124 Ci i 6.89E-04 1. 04E-03 Iodine-132 Ci l 1.81E-04 4.78E-07 Iodine-133 -

Ci I 9.62E-04 2.53E-06 Cerium-139 Ci 3.95E-06 0.0CE00 Barium-139 Ci 2.47E-05 0.00E00 Tungsten-187 Ci l.98E-06

__ 0.00E00 Yttrium-91 Ci 0.00E00 1.10E-03

~"hnidentified Ci t 2.86E-02 2.61E-02 i Total for period .above Ci 6.00E-01 l l 15.47E-01 1 Argon-41 lCi _

l.58E-03 xenon-133 Ci 0.00E00 0.00E00 xenon-135 , . I Ci 6.15E-04 2.llE-04 Total for period i C1 2.20E-03 '2.11E-04 NOTES: 1) No continuous releases were made during the first or second quarter.

2) Minimum detectable concentrations for radienuclides not detected (uCi/ml):

Ca-134 3.50E-08 Ce-141 4.50E-08 I-131 2.89E-08 Ie-133 4. 98E-08 1EJg IJ Q7}

Ba-La-140 9,65EiO8  ; - -

..'. . . TABLE J

. EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) 1976 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid Waste Shipped Of fsite for Burial or Disposal (Not irradiated fuel)

Type of waste Unit 6-month Est. Total 1.

period Error, %

a. Spent resins, filter sludges, evaporated m> 326.76 bottoms, etc. C1 141.41 1. SEQ 1 Dry compressible waste, contaminated mJ 367.58 b.

equip, etc. C1 16.88 2.0E01 Irradiated components, control mJ 0.44 c.

rods, etc. Ci 0.15 1.0E01 m3 1.00

d. Other (describe) Ci 5.30 1.2E01 1

2. Estimate of major nuclide composition (by type of waste) a+b Cobalt-58 to_7 % ~

Chromium-51 1A <%

Manganese-54 in g %

Cobalt-60 A o  %

Iron-59 A 9  %

_ Zine-65 mo  %

c. Uranium-235 oo  %

d. Americium-Bervilium- 40  %

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 88 (85) Sole use vehicle See attached sheet (2) Parcel post See attached sheet (1) Hand carry See attached sheet B. Irradiated Fuel Shipments (Disposition) -

,N_imber of Sgyp_n ts. Mode of Trancportation Destination None 1578 024 i . .

NO. of shipments Destination 37 Southern Space Inc.

Columbia SC

. 35 Chem-Nuclear Systems, Inc.

Barnwell, SC 10 Harris Energy & Environmental Lab Raleigh, NC 5 Vallecitos Nuclear Center Pleasanton, CA 1 Peach Bottom Atomic Power Station Delta, PA 43 1578 0.s.-

~

AIR SUBMERSION SKIN DOSE, mrem /6 Months BRUNSWICK STEAM ELECTRIC PLANT ,

Jan 1 to June 30, 1976  ;- -

SEC10R HILES f

.5 1.5 2.5 3.5 4.5 7.5 15.0 25.0 35.0 45.0 NNE 3.55E-03 5.372E-03 5.368E-03 4.627E-03 3.886E-03 2.405E-03 1.147E-03 6. 291E-04 4. 256E-04 3.145 E-04 NE 4.474E-03 7.221E-03 7.033E-03 5.922E-03 5.009E-03 2.960E-03 1.406E-03 7. 586E-04 5.180E-04 3.700E-04 ENE 2.086E-03 3.710E-03 4.260E-03 3.888E-03 3.332E-03 2.221E-03 1.055E-03 6.107E-04 4.256E-04 3.146E-04 E 5.127E-04 1.396E-03 1.614E-03 1.483E-03 1.297E-03 8. 707 E-04 4.630E-04 2.777E-04 1. 8 51 E,-04 1.481E-04 ESE 1. 315E-03 1. 524 E-03 1.539E-03 1.353E-03 1.148E-03 7. 224 E-04 3. 519E-04 2.037E-04 1. 351E-04 1.018E-04 SE 1.216E-03 1.252E-03 1.172E-03 1.022E-03 8.728E-04 5. 752E-04 2.967E-04 1.817E-04 1. 297 E-04 1.001E-04 SSE 1.688E-03 2.049E-03 2.042E-03 1.651E-03 1.354E-03 7. 975E-04 3.708 E-04 2.039E-04 1. 353 E-04 1. 001E-04 S 1.417E-03 2. 044E-03 1.854E-03 1.594E-03 1.315E-03 7. 966E-04 3.889E-04 2. 222E-04 1. 518E-04 1.148E-04 SSW 1.256E-03 2.,..E-03 2.965E-03 2.593E-03 2.222E-03 1.388E-03 6. 665E-04 3.887E-04 2. 592 E-04 1.851E-04 SW 2.061E-03 1.863E-03 1.834E-03 1.629E-03 1.388E-03 8. 701E-04 4. 257 E-04 2.406E-04 1.573E-04 1.166E-04 WSW 3.542E-03 2.595E-03 2.407E-03 2.036E-03 1.684E-03 1.073E-03 5.182E-04 2. 961E-04 2.035E-04 1.462E-04 W 4.078E-03 2.592E-03 2.221E-03 1.850E-03 1.554E-03 9.807 E-04 4.810E-04 2.77 9E-04 2. 035 E-04 1.498 E-04 WNW 3.354E-03 2.224E-03 2.037E-03 1.846E-03 1.555E-03 1.036E-03 5.552E-04 3.516E-04 2.590E-04 2.035E-04 NW 3.526E-03 1.685E-03 1.407E-03 1.203E-03 1. 018 E-03 6. 662E-04 3. 516E-04 2.0$0E-04 1.480E-04 1.129E-04 NNW 2.419E-D3 2.222E-03 2.406E-03 2.220E-03 2.035E-03 1.332E-03 6.846E-04 4. 076E-04 2. 775 E-04 2.220E-04 N 2.438E-03 2.966E-03 2.963E-03 2.592E-03 2.221E-03 1.406E-03 6.663E-04 3.701E-04 2.601E-05 1.850E-04 Ln HAXIMUM OFFSITE SKIN DOSE MREM /6 Months 7.221E-03 CZ) -

N Ch O G 9

AIR SUBMERSION WHOLE BODY DOSE, mrem /6 Montha 2

BRUNSWICK CTEAM ELECTRIC PLANT .

Jan 1 to June 30, 1976

~

SECTOR MILES 0.5 1.5 2.5 3.5 4.5 7.5 15.0 25.0 35.0 45.0 NNE 2.387E-03 3.627E-03 3.626E-03 3.125E-03 2.625E-03 1.625E-03 7.751E-04 4. 250E-04 2.875E-04 2.125E-04 NE 3.011E-03 4.877E-03 4.751E-03 4.000E-03 3.379E-03 2.000E-03 9. 500E-04 5.125E-04 3.500E-04 2. 500E-04 ENE 1.391E-03 2.503E-03 2.876E-03 2.626E-03 2.250E-03 1.500E-03 7.126E-04 4.125E-04 2.87 5E-04 2.125E-04 E 3.285E-04 9.405E-04 1. 089E-03 1. 001E-03 8. 757 E-04 5.879E-04 3.126E-04 1.875E-04 1.*250E-04 1.000E-04 ESE 8.747 E-04 1.027E-03 1.038E-03 9.133E-04 7.755E-04 4.878E-04 2.376E-04 1. 375E-04 9.129E-05 6.8 78 E-05 SE 7. 970E-04 8.415E-04 7.896E-04 6.889E-04 5.885E-04 3.8808-04 2.002 E-04 1.226E-04 8.758E-05 6.756E-05 SSE 1.ll2E-03 1.379E-03 1.377E-03 1.ll4E-03 9.137E-04 5. 381E-04 2. 502E-04 1.376E-04 9.135E-05 6.757E-05 S 9.405E-04 1.378E-03 1.251E-03 1.076E-03 8.882E-04 5.378E-04 2. 626E-04 1.500E-04 1.025E-04 7.754E-05 SSW 8. 297E-04 1.878E-03 2.001E-03 1.751E-03 1.50DE-03 9. 37 9E-04 4. 501E-04 2.625E-04 1.750E-04 1. 350E-04 SW 1.383E-03 1.239E-03 1.238E-03 1.100E-03 9. 379E-04 5.877E-04 2.8 75 E-04 1.625E-04 1.062E-04 7.877E-05 Wsw 2.838E-03 1.751E-03 1.625E-03 1.375E-03 1.137E-03 7. 252E-04 3.500E-04 2.000E-04 1. 375 E-04 9.8 77 E-05 W 2.753E-03 1.750E-03 1.500E-03 1.250E-03 1.050E-03 6. 265 E-04 3. 250E-04 1. 87 6E-04 1.375E-04 1.012E-04 WNW 2.257E-03 1.501E-03 1.373E-03 1.242E-03 1.050E-03 7. 001E-04 3.750E-04 2.375E-04 1.750E-04 1.375E-04 NW 2.378E-03 1.138E-03 9.503E-04 8.127E-04 6.876E-04 4.500E-04 2.375E-04 1. 376E-04 1. 000E-04 7.625E-05

~~ 9. 000E-04 4,625E-04 2.752E-04 1.875E-04 1.500E-04 NNW 1. 629E-03 1.500E-03 1.625E-03 1.!00E-03 1.375E-03 Ln 2.657E-03 2.002E-03 2.001E-03 1.750E-03 1.500E-03 9.502E-04 4. 501E-04 2. 500E-04 1.753E-05 1. 250E-04

} N c:> .

N q MAXIMUM OFFSITE WHOLE EODY DOSE MREM /6 Months 4.877E-03 O O O

WGRST CASE SITE BOUNDARY DOSES RELATED TO AIRBORNE IODINE RELEASES (Hypothetical Cow and Leafy Vegetables at Site Boundary)

Thyroid Dose due to inhalation, mrem /6 Months 1 year old 4.20E-4 4 years old 4.07E-4 14 years old 2.69E-4 Adult 3.59E-4 Thyroid Dose due to Milk Pathway mrem /6 Months 1 year old 1.llE-1 4 years old 4.60E-2 14 years old 1.59E-2 Adult 1.23E-2 Thyroid Dose due to Eating Green Leafy Vegetables, mrem /6 Months 1 year old 0 4 years old 7.63E-3 14 years old 4.44E-3 Adult 4.69E-3 i578 028

SUMMARY

OF DOSES DUE TO LIQUID RELEASES Dose Duc to Eating Fish Caught in Discharge Canal Whole Body 3.63E-6 mrem /6 months

. G. I. Tract 1.91E-5 mrem /6 months Thyroid 2.47E-8 mrem /6 months Bone 5.25E-6 mrem /6 months Shoreline Sediment Dose Along Discharge Canal 4.28E-7 mrem /6 months Ocean Swimming Dose 3.06E-10 mrem /6 months Radological Impact on Man from from direct radiation from the facility is negligible based on the results from environmental TLD's.

1578 029

.