ML20082S047
| ML20082S047 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/31/1994 |
| From: | Rhen D DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9505020334 | |
| Download: ML20082S047 (128) | |
Text
,
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I DukePowerCompany D.L Rms Catawba Nuclear Generation Department Vicel>esident
\\
4800 ConcordRoad (803)8313205 OWice York, SC29~45 (803)&113426 Fax DUKEPOWER April 25,1995 U. S. Nuclear Regulatory Commission
~ TTN: Document Con:rol Desk A
Washington, DC. 20555
Subject:
Catawba Nuclear Station Docket Nos.- 50-413 and 50-414 Annual Radioactive Effluent Release Report Pursuant to Catawba Nuclear Statina Technical Specification 6.9.1.7 and Catawba Selected Licensee Commitments e!anual Section 16.11-16.2, find enclosed the Catawba Annual Radioactive Effluent Release Report for the period ending December 31,1994.
Attachment I contains Radiactive Effluent Releases Attachment II contains Solid Waste Disposal Reports Attachment III contains Meteorological Data Attachment IV contains Unplanned Offsite Releases Attachment V contains ODCM/PCP Manual Changes Attachment VI contains Section 16. I of the Catawba Final Safety Analysis Report Should there be any questions concerning this report please contact Kay Nicholson at (803) 831-3237.
Sincerely, s)
D.L.Rehn KEN /ARERR.94 Attachments S. D. Ebneter (w/o attachments) xc:
l Regional Administrator, Region II l
R. E. Martin, ONRR R. J. Freudenberger, SRI (w/o attachment)
I 9505020334 941231 PDR ADOCK 05000413 g 'I 3,,,,,,
D PDR
l ATfACHMENT I Summary of Liquid and Gaseous Effluents Report Supplemental Information to the Liquid and Gaseous Effluents Report Fuel Cycle Calculations i
l UNIT 1 1
l CATAWBA NUCLEAR STATION UNIT 1 RADIDACTIVE EFFLUENT RELEASES DATE : 02/27/95 1.
LIQUID RELEASES YEAR 1994 UNITS 1ST OTR 2ND OTR 3RD QTR 4TH OTR TOTAL 1.
GROSS RADIDACTIVITY A.
TOTAL RELEASE CURIES 7.51E-02 1.30E-01 6.18E 02 1.60E-02 2.83E-01 B.
AVERAGE CONCENTRATION RELEASED UCI/ML 3.08E-09 6.29E-09 2.62E-09 7.60E 10 3.15E-09 C.
MAXIMUM CONCENTRATION RELEASED UCl/ML 1.5fE-08 3.44E-08 1.70E-08 1.54E-09 3.44E 08 2.
TRITIUM A.
TOTAL RELEASE CURIES 8.35E+01 1.06E+02 6.55E+01 3.'4E+01 2.93E+02 B.
AVERAGE CONCENTRATION RELEASED UCI/ML 3.42E 06 5.15E-06 2.78E-06 1.78E-06 3.27E-06 3.
DISSOLVED NOBLE CASES A.
TOTAL RELEASE CURIES 1.29E-02 3.40E-03
- 3. 75E-04 2.07E-04 1.68E-02 B.
AVERAGE CONCENTRATION RELEASED DCI/ML 5.27E-10 1.65E 10 1.59E 11 9.83E 12 1.88E 10 4.
GROSS ALPHA ACTIVITY A.
TOTAL RELEASE CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 B.
AVERAGE CONCENTRATION RELEASED UCI/ML 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.
VOLUME OF LIQUID WASTE TO DISCHARGE CANAL LITERS 6.37E+07 8.52E+07 6.46E+07 5.59E+07 2.69Ev08 6.
VOLUME OF O!LUTION WATER LITERS 2.44E+10 2.06E+10 2.36E+10 2.10E+10 8.96E+10.
7.
RADIONUCLIDES RELEASED CURIES EC RATIO H-3 8.35E+01 1.06E+02 6.55E+01
- 3. 74E+01 2.93E+02 3.27E-03 BE-7 5.06E-05 0.00E+00 0.00E+00 0.00E+00 5.06E 05 9.41E-10 F-18 1.81E 04 3.31E-05
- 1. 04E-04 1.86E-05 3.37E 04 5.37E-09 NA-24 1.74E-05 2.86E 05 9.89E-05 4.34E-D6 1.49E 04 3.33E 08 CR-51 1.68E-03 7.01E-03 1.57E-03 2.35E-04 1.05E-02 2.34E-07 MN-54 1.07E-03 2.97E-03 7.00E D4 4.04E-04 5.15E-03 1.92E-06 FE-55 9.55E-03 9.85E-03 7.94E 03 1.54E 03 2.89E-02 3.22E 06 FE-59 1.04E-04 5.58E-04 4.f2E 05 0.00E+00 7.07E-04 7.89E 07 CO-57 2.11E-04 2.28E-04 7.47E-05 5.28E-05 5.67E-04 1.05E-07 CO-58 4.35E-02 6.90E 02 1.85E-02 4.83E-03 1.36E-01 7.57E-05 CO-60 7.18E 03 1.66E-02 6.12E-03 4.16E 03 3.40E-02 1.27E-04 2N 65 0.00E+00 2.63E 07 0.00E+00 0.00E+00 2.63E-07 5.86E-10 BR-82 3.01E-06 2.11E 06 1.48E-06 5.18E D6 1.18E-05 3.29E-09 RB 86 0.00E+00 4.35E 06 0.00E+00 0.00E+00 4.35E-06 6.93E-09 SR-92 1.28E-05 5.52E*05 6.93E 05 2.11E 06 1.39E-04 3.89E-08 Y 91M 6.15E 07 0.00E+00 0.00E+00
- 2. 74E-07 8.90E-07 4.96E-12 NS-95 3.88E-04 6.87E 04 7.00E 05 2.30E-05 1.17E-03 4.34E 07 NB 97 1.51E-04 1.50E-04 6.97E 04 5.80E-05 1.06E 03 3.93E-08 NS-97M 0.00E*00 0.00E+00 2.22E 06 0.00E+00 2.22E-06 2.48E-06 2R-95 2.06E -04 3.24E-04 7.02E-05 0,00E+00 6.00E-04 3.35E-07 2R-97 0.00E+00 4.78E-05 5.94E 04 1.57E 05 6.57E 04 8.15E-07 MO-99 0.00E+00 6.53E-06 0.00E+00 0.00E+00 6.53E 06 3.65E 09 TC-99M 0.00E+00 4.03E 07 4.70E-06 3.85E-07 5.48E-06 6.12E 11 AG-110M 3.72E-04 1.3BE-03 1.17E 03 5.94E 04 3.52E-03 6.54E 06 I-131 1.17E-03 1.11E-03 8.52E 06 4.23E 05 2.33E 03 2.60E 05 I 132 1.24E-06 1.90E-05 0.00E+00 9.94E 07 2.12E 05 2.37E 09 I-133 4.59E-05 1.10E-05 1.89E-06 1.02E-05 6.90E-05 1.10E 07 I 135 0.00E+00 0.00E+00 0.00E+00 2.12E-06 2.12E 06 7.87E-10 SB-122 0.00E+00 2.31E-06 0.00E+00 3.09E-07 2.61E-06 2.92E 09
$8-124 1.39E-03 4.07E-03 6.78E-03 2.65E 04 1.25E-02 1.99E-05 SB-125 7.63E-03 1.29E-02 1.56E-02 3.31E-03 3.95E 02 1.47E 05 SN-113 6.34E-05 1.06E-04 3.46E 05 6.70E D6 2.11E-D4 7.84E 08 CS-134 2.62E-05 2.01E-04 2.79E-04 8.03E-05 5.87E-04 7.28E-06 CS 136 9.83E-07 1.33E-06 0.00E+00 1.16E-05 1.39E-05 2.58E 08 CS-137 1.51E-04 6.55E-D4 8.25E-04 3.10E 04 1.94E-03 2.17E-05 CS-138 0.00E+00 7.97E-04 3.62E-04 1.16E-05 1.17E 03 3.26E 08 BA 140 0.00E+00 2.64E-05 0.00E+00 0.00E+00 2.64E-05 3.68E-08 LA-140 2.01E-06 1.66E-05 3.88E-06 0.00E+00 2.2SE-05 2.79E 08 CE 143 0.00E+00 0.00E+00 0.00E+00 1.19E-06 1.19E-06 6.63E-10 W-187 2.29E 05 0.00E+00 3.52E-05 0.00E+00 5.81E-05 2.16E-08 TH-228 0.00E+00 9.66E-D4 0.00E+00 0.00E+00 9.66E-04 5.39E-05 NP-239 0.00E+00 7.03E 07 0.00E+00 0.00E+00 7.03E-07 3.92E-10 58 126 0.00E+00 4.92E 05 0.00E+00 0.00E+00 4.92E 05 7.84E 08 AR-41 1.54E-06 2.15E-06 0.00E+00 0.00E+00 3.69E 06 4.12E-10 LA 85 3.62E 03 0.00E+00 1.57E-04 0.00E+00
- 3. 77E-03 4.21E-07 XE*131M 0.00E+00 2.69E-04 5.15E-06 0.00E+00 2.74E-04 3.06E-08 l
XE-133 9.23E-03 3.13E-03 2.08E 04 2.07E-04 1.28E-02 1.43E-06 l
XE-133M 0.00E+00 0.00E+00 4.10E-06 0.00E+00 4.10E-06 4.58E-10 XE-135 1.02E 05 0.00E+00 3.96E-07 1.91E-07 1.08E-05 1.21E-09 TOTAL EC RATIO 3.63E-03
CATA8SA UNIT 1 LIGUID RELEASE 001-490 94 2.44E*13 02/27/95 SKIN MAXIMUM DOSE-4.07E-03 MREM CRITICAL AGE-TEEN ' CRITICAL PATIMAY-SHORE j
C5 58 8.48 %
CU 60 79.83 %
SB 125 8.86 %
BONE MAXIMUM DOSE-1.05E-02 MREM CRITICAL AGE-TEEN CRITICAL PATIMAY-FISH l
FE 55 5.76 %
j CU 60 23.39 %
i i
CS 134 6.97 %
CS 137 53.86 %
LIVE;t MAXIf1UM DOSE-1.66E-02 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-FISH H
3 15.39 %
CU 60 17.61 %
CS 134 10.29 %
l CS 137 44.99 %
T. BODY MAXIMUM DOSE-1.15E-02 MREM CRITICAL AGE-ADULT CRITICAL PATHNAY -
FISH H
3 30.08 %
CO 58 7.35 %
CU 60 7.54 %
~
CS 13re 11.94 %
CS 137 40.66 %
THYRUID MAXIMUM DOSE-1.28E-02 MREM CRITICAL AGE-TEEN CRITICAL PATIMAY-FISH' H
3 19.98 %
CU 60 21.55 %
I 131 52.70 %
<-i KIDNEY MAXIMUN DOSE-9.29E-03 MREM CRITICAL AGE-TEEN CRITICAL PATIMAY-FISH H
3 27.55 %
CU 60 29.70 %
CS 134 5.88 %
CS 137 27.60 %
LtJHG MAXIMUM DOSE-7.51E-03 MREM CRITICAL AGE-TEEN '. CRITICAL PATHMAY-SHORE H
3 34.08 %
CO 60 36.74 %
CS 137 13.49 %
GI-LLI MAXIMUM DOSE-6.86E-02 IWtEM CRITICAL AGE-A00LT CRITICAL PATHMAY-FISH H
3 5.06 %
CU 58 10.56 %
CU 60 5.39 %
NB ?5 75.87 %'
CATAteA UNIT 1 lit 3UID RELEASE 4291-1S1 94 2.06E*13 82/27/95 SKIN MAXIMUM DOSE-1.10E-02 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-SHURE CG 58 5.99 %
CU 60 81.86 %
SB 125-6.64 %
BCHE MAXIMUM DOSE-5.34E-02 MREM CRITICAL AGE-CHILD CRITICAL PATHMAY-FISH CS 134 15.14 %
CS 137 68.84 %
TH 228 10.27 %
+
LIVE:t MAXIMUM DOSE-7.12E-02 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-FISH I
H 3
5.50 %
CO 60 11.37 %
CS 134 22.17 %
CS 137 54.66 %
- T. BODY MAXIMUM DOSE-4.73E-02 MREM CRITICAL AGE-ADULT CRITICAL PATHMAY-FISH l
H 3
11.24 %
CO 60 5.09 %
CS 134 26.88 %
CS 137 51.65 %
THYROID MAXIMUM DOSE-2.09E-02 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-SHORE H
3 18.71 %
CU 60 36.46 %
I 131 36.53 %
KIDHEY NAXIMUM DOSE-3.24E-02 MREM CRITICAL AGE-TEEN CRITICAL PATIO 4AY-FISH H
3 12.10 %
CG 60 23.59 %
CS 134 15.57 %
CS 137 41.25 %
f LUNG MAXIMUM DOSE-2.07E-02 MREM CRITICAL AGE-TEEN CRITICAL PATI #tAV-FISH H
3 18.90 %
CO 60 36.83 %
CS 134 9.37 %
CS 137 25.45 %
GI-LLI MAXIMUM DOSE-1.51E-01 MREM CRITICAL AGE-ArULT CRITICAL PATHMAY-FISH CU 58 9.14 %
CU 60 6.77 %
18 95 73.06 %
CATAMBA UNIT 1 LI GID RELEASE 1C2-273 94 2.3;E*19 52/27/95 SKIN HAXIMUM DOSE-4.27E-03 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-SHORE CO 60 68.11 %
58 125 18.19 %
BONE MAXIHUM DOSE-5.22E-02 NREM CRITICAL AGE-CHILD CRITICAL PATNMAY-FISH CS 134 18.95 %
CS 137 78.22 %
LIVER MAXINL%t DOSE-6.91E-02 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-FISH CS 134 27.94 %
CS 137 62.54 %
l T. BODY MAXIMUM DOSE-4.70E-02 HREM CRITICAL AGE-ADULT CRITICAL PATIMAY-FISH H
3 6.13 %
CS 134 33.07 %
CS 137 57.68 %
THYRUID HAXINUM DOSE-5.84E-03 HREM CRITICAL AGE-TEEN CRITICAL PATIMAY-SHORE H
3 36.36 %
CU 60 42.34 %
SB 125 11.78 %
l KIDHEY MAXINUM DOSE-2.66E-02 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-FISH H
3 7.96 %
)
CU 60 9.27 %
CS 134 23.12 %
CS 137 55.58 %
LUNG MAXIMUM DOSE-1.41E-c2 MREM CRITICAL AGE-TEEN CRITICAL PATIMAY-FISM H
3 15.08 %
CU 60 17.56 %
CS 134 16.87 %
CS 137 41.59 %
CI-LLI HAXINUM DOSE-2.25E-02 MREM CRITICAL AGE-ADULT CRITICAL PATHMAY-FISH H
3 12.00 %
CU 58 14.53 %
CU 60 14./2 %
IB 95 44.16 %
n.
~s CATAMBA UNIT 1 LICJID RELEASE 274-315 94 2.10E+13 (2/27/95 SKIN MAXIMUM DOSE-2.63E-03 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-SHORE CO 60 85.06 %
SB 125 7.05 %
f BONE MAXIMUM DOSE-2.11E-02 MREM CRITICAL AGE-CHILD CRITICAL PATHMAY-FISH CS 134 15.17 %
CS 137 81.71 %
I LIVE 2 MAXIMUM DOSE-- 2.86E-02 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-FISH CO 60 7.04 %
CS 134 21.85 %
CS 137 63.81 %
i l
T. BODY MAXIMUM DOSE-1.93E-02 MREM CRITICAL AGE-ADULT CRITICAL PATHNAY-FISH H
i 9.61 %
CS 134 26.15 %
CS 137 59.51 %
THYROID MAXINUM DOSE-3.90E-03 MetEM CRITICAL AGE-TEEN CRITICAL PATHMAY-SHORE 1
H 3
34.95 %
i CO 60 48.67 %
l I 131 7.44 %
l KIDNEY MAXIMLM DOSE-1.19E-02 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-FISH l
H 3
11.44 %
l CU 60 15.93 %
l CS 134 16.75 %
CS 137 52.53 %
LUNG MAXIMUM DOSE-6.84E-03 HREM CRITICAL AGE-TEEN CRITICAL PATHNAY-FISH H
3 19.95 %
CO 60 27.77 %
CS 134 11.25 %
CS 137 36.20 %
1 GI-LLI MAXIMUM DOSE-. 1.02E-OZ MREM CRITICAL AGE-ADULT CRITICAL PATHMAY-FISH H
3 18.06 %
t#4 54 5.73 %
CG 58 9.34 %
CU 60 24.82 %
fB 95 35.77 %
~. -.
... - ~.... ~.....
CATAMBA UNIT 1 LIQUID RELEASE 001-315 94 G. %E +10 C2/27/95 SKIN MAXIMUM DOSE-2.16E-02 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-SHORE CU 58 5.55 %
CU 60 78.93 %
S8 125 9.55 %
BONE MAXIMUM DOSE-1.34E-01 MREM CRITICAL AGE-CHILD CRITICAL PATHMAY-FISH CS 134 16.17 %
CS 137 75.01 %
LIVER MAXINUM DOSE-1.83E-01 t1 REM CRITICAL AGE-TEEN CRITICAL PATIMAY-FISH H
3 5.43 %
CG 60 8.39 %
CS 134 23.14 %
CS 137 58.19 %
T. BODY MAXIMUM DOSE-1.24E-01 MREM CRITICAL AGE-ADULT CRITICAL PATHMAY-FISH H
3 10.92 %
CS 134 27.61 %
CS 137 54.12 %
THYROID MAXIMUM DOSE-4.34E-02 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-FISH H
3 22.95 %
CO 60 33.41 %
1 131 34.41 %
KIDNEY MAXIMUM DOSE-7.92E-0? PREM CRITICAL AGE-TEEN' CRITICAL PATHMAY-FISH H
3 12.56 %
CU 60 18.27 %
CS 134 17.08 %
CS 137 46.15 %
LUNG MAXIMUM DCSE-4.86E-02 MREM tRITICAL AGE-TEEN CRITICAL PATIMAY-FISH H
3 20.47 %
CG 60 29.79 %
CS 134 10.73 %
CS 137 29.73 %
GI-LLI MAXIMUM DOSE-2.50E-01 MREM CRITICAL AGE-ADULT CRITICAL PATHMAY-FISH H
3 5.41 %
CU 58 10.08 %
CG 60 7.77 %
NB 95 69.83 %
CATAWBA NUCLEAR STATION UNIT 1
' RADI0 ACTIVE EFFLUENT RELEASES l'
OATE 03/09/95
'II.
AIRBORNE RELEASES YEAR. '1994 i
i UNITS IST OTR 2ND OTR 3RD QTR' 4TH QTR TOTAL j
1.
TOTAL NOBLE GASES CURIES 1.23E+02 2.40E'+02 3.95E+01 4.89E+01 4.51E+02 2.
TOTAL HALOGENS CURIES 9.16E-05 1.28E-04 0.00E+00 0.00E+00 2.20E-04
. 3.
TOTAL PARTICULATE
- 3.92E 05
~4.58E 06 0.00E+00 4.61E 05 GROSS BETA GAMMA CURIES
-2.26E 06 4.
TOTAL TRITIUM CURIES 7.68E+00
'1.09E+01 1.22E+01 1.59E+01-4.66E+01 5.
TOTAL PARTICULATE l
GROSS A6PNA ACTIVITY -
CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i
6.
MAXIIRJM NOBLE GAS RELEASE RATE UCI/SEC 1.60E+03 1.60E+03 1.60E 43 1.60E+03 8.00E+02 7.' RADIONUCLIDES RELEASED CURIES EC RATIO N3 7.68E+00 1.09E+01 1.22E+01 1.59E+01 4.66E+01-5.19E 04 l
PARTICULATES 4.58E-06 0.00E+00 4.60E-05 5.12E 08-t co-58 2.18E 06 3.92E 05 l
CO-60 8.62E-08 0.00E+00 0.00E+00 0.00E+00 8.62E 08
.1.92E 09 t
HALOGENS' I-131 8.84E 05 1.27E-04
'O.00E+002 0.00E+00 2.16E-04 1.20E 06 I
l-132 0.00E+00 5.76E-07 0.00E+00 0.00E+00 5.76E 07 3.20E-11 I-133 3.20E 06-6.21E 08-0.00E+00 0.00E+00-3.26E-06 3.63E GASES AR-41 1.94E+01 3.52E+01 -
5.29E 01 6.81E 01:
5.59E+01 6.21E 03 KR-85 0.00E+00 6.47E-02.
5.13E 02 1.70E-01 2.86E 01 4.55E-07 KR 85M-4.38E 02 2-.38E-02 1.42E 02 2.06E-02 1.02E 01 1.14E 06 KR-87 0.00E+00 0.00E+00 '
O.00E+00 4.35E*04 4.35E 04 2.42E 08 i
KR-88 1.02E 02 1.22E 02 6.23E-03 1.00E 02 3.87E 02 4.78E-06 XE-131M.
6.99E 01 2.41E+00
'2.50E-01 1.42E-01 3.51E+00
,1.95E-06--
XE 133 1.01E+02 1.98E+02 3.82E+01 4.73E+01' 3.84E+02
' 8.55E 04 XE 133M 7.45E-01 1.58E+00 2.21E 01 2.52E 01 2.80E+00 5.19E-06
~
l,,
.XE-135 1.75E+00 2.33E+00 2.11E-01 3.69E 01 4.66E+00 7.40E 05 TOTAL EC RATIO 7.67E-01 e
i I
l I
1 I
1 i
l i
I.
l-I
i i
l CATAWA UNIT 1 GAS DOSE 001-090 94 RELEASE MIGHTED MT REPORT SUPMARY 03/09/95 SPECIAL LOCATItSt i
AT 0.50 MILES PSE I
MOBLE GAS EXPOSURE:
BETA AIR DOSE = 1.80E-01 MILLIRADS GArmA AIR DOSE = 2.14E-01 MILLIRADS TUTAL BODY DOSE = 1.3?E-01 MILLIREM TUTAL SKIN DOSE = 2.54E-01 MILLIREM XE133 15.96%
XE133 24.64%
AR 41 82.06%
AR 41 72.16%
CCTAleA UNIT 1 GAS DOSE 001-090 94 RELEASE MEIGHTED IET REPORT SIMtARY 03/09/95 SPECIAL LOCATIt24 AT 0.50 MILES S 10 DINE, PARTICULATE. Are TRITIL29 E)(P55URE SLMtARY:
MAXIttM ORGAN
- THYMSID CRITICAL AGE
- CHILO CRITICAL PATHMAY - YEGET 3 79.66%
MAXIMIDt ORGAN DOSE = 3.34E-02 MILLIREM H
3 78.60%
I 131 21.32%
i l
n L
1 a
.1 5
e m
p__
.m
COTAMBA UNIT 1 GAS DOSE 091-181 94 RELEASE MIGHTED DET REPORT SUP9tARY 03/09/95 SPECIAL LOCATItM AT 0.50 MILES tee NESLE GAS EXPOSURE:
I BETA AIR DOSE = 4.31E-01 MILLIRADS GAP 91A AIR DOSE = 5.64E-01 MILLIRAOS TOTAL BODY DOSE = 3.68E-01 MILLIREM TERAL SKIN DSSE = 6.59E-01 MILLIREM XE133 13.29%
XE133 20.95%
AR 41 85.39%
AR 41 76.68%
a
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i i
a 4
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4
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. -. -... -.. = _ _...._ _.
._._._.,m m..
.. _. - -- _.. _,..._ _,_. __. -.o
._m m._
.m__
L CATA8SA LMIT 1 GAS DOSE 091-181 94 RELEASE MIGHT2D MET REPORT SLN9%RY 03/09/95 SPECIAL LOCATItM AT 0.50 MILES S 10 DIE, PARTICULATE, APG TRITILM EXPtESURE SLAMARY:
MAXIttM ORGAN -
- THYROID CRITICAL AGE
- CHILD CRITICAL PATIMAY - VEGET 3 80.08%
MAXIMLM ORGAN DOSE = 2.71E-02 MILLIREM H
3 80.08%
I 131 19.79%
t I
C
)
i i
~ ~. - -
c.
CATAN A UNIT 1 GAS DOSE 182-273 94 RELEASE MIGHTED PET REPORT SUP9tARY 03/09/95 SPECIAL LOCATItN AT O.50 MILES t#E MtBLE GAS EXPOSURE:
5.61E-02 MILLIRADS BETA AIR DOSE
=
GAfttA AIR DOSE = 2.40E-02 MILLIRADS TtfTAL BODY DOSE = 1.45E-02 MILLIREM TUTAL SKIN DOSE = 3.67E-02 MILLIREM XE133 71.07%
XE133 79.20%
AR 41 25.32%
AR 41 16.08%
i 4
l l
l
COTADSA tlNIT 1 GAS DOSE 182-273 94 RELEASE N IGHTED N T REPENtT StMtARY 03/09/95 SPECIOL LOCATION AT 0.50 MILES ENE IODINE, PARTICULATE, Am TRITILM EXPO 5URE StMtARY:
MAXIMLM SRGAN
- CI-TRACK CRITICAL AGE
- CHILD CUTICAL PATPMAY - VEGET 3 78.26%
MAXIttM ORGAN DOSE = 4.10E-02 MILLIREM l
H 3
99.96%
I I
I l
.__....m.
..___m.___
.~._m-CATApeA UNIT 1 GAS DOSE 274-365 94 RELEASE MIGHTED MT REPORT SIMtARY 03/09/95 i
SPECIAL LOCATION AT O.50 MILES 194E NtBLE GAS EXPOSURE:
BETA AIR DOSE = 9.64E-02 MILLIRADS GAPftA AIR DOSE = 4.09E-02 MILLIRAOS TM AL BODY DOSE = 2.48E-02 MILLIREM TOTAL SKIN DOSE = 6.45E-02 MILLIREM XE133 68.55%
XE133 74.27%
XE135 9.03%
XE135 9.22%
AR 41 18.40%
AR 41 11.31%.
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CATAleA UNIT 1 GAS DOSE 274-365 94 RELEASE M IGHTED E T REPORT SIMtARY 03/09/95 SPECIAL LOCATItDI AT 0.50 MILES S l
6 10 DIE, PARTICULATE, Are TRITItM EXPO 5URE SGMARY:
MAX 19tM ORGAN
- T.90DY CRITICAL AGE
- CHILD CRITICAL PATIMAY - VEGET 3 78.19%
MAXIMUM ORGAN DOSE = 1.03E-01 MILLINEM H
3 100.00%
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MAXIPRJM ORGAN
- THYRSID CRITICAL AGE
- CHILD CRITICAL PATW4AY - VEGET 3 78.7Z%
MAXIMLM ORGAN DOSE = 1.85E-01 MILLIREM H
3 93.20%
I 131 6.76%
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CATAWBA NUCLEAR STATION i
UNIT 2 RADIDACTIVE EFFLUENT RELEASES DATE : 02/27/95 1.
LIQUID RELEASES YEAR 1994 UNITS 1ST OTR 2ND OTR 3RD QTR 4TH OTR TOTAL 1.
GROSS RAD 10 ACTIVITY A.
TOTAL RELEASE CURIES 7.51E-02 1.306-01 6.18E 02 1.60E-02 2.83E-01 B.
AVERAGE CONCENTRATION RELEASED UCI/ML 3.08E 09 6.29E-09 2.62E*09 7.60E-10 3.15E-09 C.
MAXIMUM CONCENTRATION RELEASED UCI/ML 1.51E-08 3.44E-08 1.70E 08 1.54E-09 3.44E-08 i
2.
TRITluM A.
TOTAL RELEASE CURIES 8.35E+01 1.06E+02 6.55E+01 3.74E+01 2.93E+02 B.
AVERAGE CONCENTRATION RELEASED UC!/ML 3.42E-06 5.15E-06 2.78E-06 1.7BE-06 3.27E-06 3.
DISSOLVED NOBLE GASES A.
TOTAL RELEASE CURIES 1.29E-02 3.40E-03
- 3. 75E-04 2.07E 04 1.68E-02 8.
AVERAGh CONCENTRAT!DN RELEASED UCI/ML 5.27E-10 1.65E 10 1.59E-11 9.83E 12 1.88E 10 4.
GROSS ALPHA ACTIVITY A.
TOTAL RELEASE CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 B.
AVERAGE CONCENTRATION RELEASED UCI/ML 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.
VOLUME OF LIQUID WASTE TO DISCHARGE CANAL LITERS 6.37E+07 8.52E+07 6.46E+07 5.59E+07 2.69E+08 6.
VOLUME OF DILUTION WATER LITERS 2.44E+10 2.06E+10 2.36E+10 2.10E+10 8.96E+10 7.
RADIONUCLIDES RELEASED CURIES EC RATIO H-3 8.35E+01 1.06E+02 6.55E+01 3.74E+01 2.93E+02 3.27E-03 BE-7 5.06E-05 0.00E+00 0.00E+00 0.00E+00 5.06E 05 9.41E 10 F-18 1.81E-04 3.31E-05 1.04E-04 1.86E-05 3.37E-04 5.37E 09 NA-24 1.74E 05 2.86E-05 9.89E-05 4.34E-06 1.49E-04 3.33E-08 CR 51 1.68E-03 7.01E-03 1.57E-03 2.35E-04 1.05E 02 2.34E-07 1
MN 54 1.07E-03 2.97E 03 7.00E-04 4.04E-04 5.15E-03 1.92E-06 FE-55 9.55E 03 9.85E-03 7.94E-03 1.54E 03 2.89E-02 3.22E-06 FE-59 1.04E-04 5.5BE-04 4.52E-05 0.00E+00 7.07E-04 7.89E-07 Co-57 2.11E-04 2.2BE-04 7.47E 05 5.2BE-05 5.67E-04 1.05E-07 Co-58 4.35E-02 6.90E-02 1.85E-02 4.83E 03 1.36E-01 7.57E 05 Co-60 7.18E-03 1.66E-02 6.12E 03 4.16E-03 3.40E-02 1.27E-04 ZN-65 0.00E+00 2.63E-07
'0.00E+00 0.00E+00 2.63E-07 5.86E-10 BR 82 3.01E-06 2.11E-06 1.48E-06 5.18E 06 1.18E-05 3.29E-09 RB 86 0.00E+00 4.35E-06 0.00E+00 0.00E+00 4.35E-06 6.93E-09 SR-92 1.28E-05 5.52E-05 6.93E-05 2.11E-06 1.39E-04 3.89E 08 Y-91M 6.15E-07 0.00E+00 0.00E+00 2.74E-07 8.90E-07 4.96E-12 NS 95 3.88E-04 6.87E-04 7.00E-05 2.30E-05 1.17E-03 4.34E-07 1
NB-97 1.51E-04 1.50E-04 6.97E-04 5.80E-05 1.06E-03 3.93E-08 NS-97M 0.00E+00 0.00E+00 2.22E-06 0.00E+00 2.22E-06 2.48E 06 1
ZR-95 2.06E 04 3.24E 04 7.02E-05 0.00E+00 6.00E 04 3.35E-07 ZR-97 0.00E+00 4.78E-05 5.94E 04 1.57E-05 6.57E 04 8.15E-07 MD-99 0.00E+00 6.53E 06 0.00E+00 0.00E+00 6.53E-06 3.65E-09 i
TC-99M 0.00E+00 4.03E-07 4.70E-06 3.85E-07 5.48E-06 6.12E-11 AG 110M 3.72E-04 1.38E-03 1.17E-03 5.94E-04 3.52E-03 6.54E-06 l 131 1.1TE-03 1.11E-03 8.52E-06 4.23E-05 2.33E 03 2.60E-05 I-132 1.24E-06 1.90E-05 0.00E+00 9.94E-07 2.12E 05 2.37E-09 I-133 4.59E-05 1.10E-05 1.89E-06 1.02E-05 6.90E 05 1.10E-07 1-135 0.00E+00 0.00E+00 0.00E+00 2.12E-06 2.12E-06 7.87E-10 SB-122 0.00E+00 2.31E-06 0.00E+00 3.09E-07 2.61E-06 2.92E 09 SB 124 1.39E-03 4.0TE-03 6.78E 03 2.65E-04 1.25E 02 1.99E-05 SB 125 7.63E-03 1.29E-02 1.56E 02 3.31E-03 3.95E 02 1.47E-05 SN-113 6.34E-05 1.06E 04 3.46E-05 6.70E 06 2.11E-04 7.84E-08 CS-134 2.62E-05 2.01E-04 2.79E-04 8.03E-05 5.87E 04 7.28E-06 CS-136 9.83E 07 1.33E-06 0.00E+00 1.16E-05 1.39E 05 2.5BE-08 CS-137 1.51E 04 6.55E-04 8.25E-04 3.10E-04 1.94E 03 2.17E-05 CS-138 0.00E+00 7.97E-04 3.62E-04 1.16E 05 1.17E 03 3.26E-08 BA-140 0.00E+00 2.64E-05 0.00E+00 0.00E+00 2.64E-05 3.68E-08 LA-140 2.01E-06 1.66E-05 3.88E-06 0.00E+00 2.25E 05 2.79E 08 CE 143 0.00E+00 0.00E+00 0.00E+00 1.19E-06 1.19E 06 6.63E-10 W 187 2.29E 05 0.00E+00 3.52E-05 0.00E+00 5.81E-05 2.16E 08 TM 228 0.00E+00 9.66E-04 0.00E+00 0.00E+00 9.66E-04 5.39E 05 NP-239 0.00E+00 7.03E-07 0.00E+00 0.00E+00 7.03E 07 3.92E-10 SB-126 0.00E+00 4.92E-05 0.00E+00 0.00E+00 4.92E 05 7.84E-08 AR-41 1.54E 06 2.15E-D6 0.00E+00 0.00E+00 3.69E 06 4.12E-10 KR 85 3.62E-03 0.00E+00 1.57E-04 0.00E+00 3.77E-03 4.21E-07 XE 131M 0.00E+00 2.69E-04 5.15E-06 0.00E+00 2.74E-04 3.06E-08 XE-133 9.232-03 3.13E-03 2.08E-04 2.07E-04 1.28E 02
'1.43E 06 XE-133M 0.00E+00 0.00E+00 4.10E-06 0.00E+00 4.10E-06 4.58E 10 XE 135 1.02E-05 0.00E+00 3.96E-07 1.91E-07 1.08E-05 1.21E-09 TOTAL EC RAT 10 3.63E 03
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.mm 4
CATANA UNIT 2 LIQUID RELEASE 001-590 94 2.44E*13 02/27/95 SKIN MAXIMUM DOSE-4.07E-03 HREM CRITICAL AGE-TEEN CRITICAL PATHMAY-SHORE CG 58 8.48 %
CU 60 79.83 %
SB 125 8.86 %
BONE MAXINUM DOSE-1.05E-02 MREM CRITICAL AGE-TEEN CRITICAL PATHNAY-FISH FE 55 5.76 %
CO 60 26.39 %
CS 134 6.97 %
CS 137 53.86 %
LIVEtt HAXIHUH DOSE-1.66E-02 HREM CRITICAL AGE-TEEN CRITICAL PATHMAY-FISH H
3 15.39 %
CU 60 17.61 %
CS 134 10.29 %
CS 137 44.99 %
T. BODY MAXIMUM DOSE-1.15E-02 NREN CRITICAL AGE-ADULT CRITICAL PATHNAY-FISH H
3 30.08 %
CU 58 7.35 %
CU 60 7.54 %
CS 134 11.94 %
CS 137 40.66 %
THYRUID MAXIMUM DOSE-1.28E-02 HREM CRITICAL AGE-TEEN CRITICAL PATHNAY-FISH H
3 19.98 %
CU 60 21.55 %
I 131 52.70 %
KIDNEY MAXIMUH DOSE-9.2*E-03 MREN CRITICAL AGE-TEEN CRITICAL PATHMAY-FISH H
3 27.55 %
CO 60 29.70 %
CS 134 5.88 %
CS 137 27.60 %
LUNG - MAXIMUM DOSE-7.51E-03 tetEM CRITICAL AGE-TEEN CRITICAL PATIt4AY-SHORE H
1 34.08 %
CO 60 36.74 %
CS 137 13.49 %
GI-LLI HAXINUM DOSE-6.86E-02 NREM CRITICAL AGE-ADULT CRITICAL PATHMAY-FISH
'H 3
5.06 %
CU 58 10.56 %
CU 60 5.39 %
N8 95 75.87 %
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t CATAMBa UNIT 2 LIQUID RELEASE D',1-121 94 2.06E+13 02/27/95 SKIN MAXIMUM DOSE-1.10E-02 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-SHORE CO 58 5.99 %
r CU 60 81.86 %
SB 125 6.64 %
BONE MAXIMUM DOSE-5.34E-02 MREM CRITICAL AGE-C*lILD CRITICAL PATHMAY-FISH CS 134 15.14 %
CS 137 68.84 %
TH 228 10.27 %
LIVER MAXINUM DOSE-7.12E-02 MrtEM ' CRITICAL AGE-TEEN CRITICAL PATWAY-FISH H
3 5.50 %
CO 60 11.37 %
CS 134 22.17 %
CS 137 54.66 %
T. BODY MAXINUM DOSE-- 4.73E-02 MREM CRITICAL AGE-ADULT CRITICAL PATHMAY-FISH H
3 11.24 %
CU 60 5.09 %
CS 134 26.88 %
CS 131 51.65 %
THYROID MAXIMUM DOSE-2.0*E-02 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-SHORE H
3
'18.71 %
CU 60 36.46 %
I 131 36.53 %
KIDNEY-MAXIMUM DOSE-3.24E-02 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-FISH H
3 12.10 %
CU 60 23.59 %
CS 134 15.57 %
CS 137 41.25 %
LUNG MAXIMUM DOSE-2.07E-02 MREM CRITICAL AGE-TEEN CRITICAL PAT MAY-FISH H
3 18.90 %
CU 60 36.83 %
CS 134 9.37 %
CS 137 25.45 %
CI-LLI~ MAXIMUM DOSE-1.51E-01 MREM CRITICAL AGE-ADULT CRITICAL PATHMAY-FISH CU 58 9.14 % '
CO 60 6.77 %
te 95 73.06 %
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CATAMBA UNIT 2 LIQUID RELEASE 122-273 94 2.31E*19 E2/27/95 SKIN MAXIMUM DOSE-4.27E-03 MREM CRITICAL AGE-TT IN CRITICAL PATHMAY-SHURE CU 60 68.11 %
58 125 18.19 %
BONE HAXIMUM DOSE-5.22E-02 MREM CRITICAL AGE-CHILO CRITICAL PATHMAY-FISH CS 134 18.95 %
CS 137 78.22 %
LIVECt MAXIMUM DOSE-6.91E-02 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-FISH CS 134 27.94 %
CS 137 62.54 %
T. BODY MAXIMUM DOSE-4.70E-02 MREM CRITICAL AGE-ADULT CRITICAL PATHMAY-FISH H
3 6.13 %
CS 134 33.07 %
CS 137 57.68 %
THYRUID MAXIMUM DOSE-5.84E-03 MREM CRITICAL AGE-TEEN CRITICAL PATIMAY-SHORE H
3 36.36 %
CU 60 42.34 %
SB 125 11.78 %
KIDNEY MAXIMUM DOSE-2.66E-02 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-FISH H
3 7.96 %
CO 60 9.27 %
CS 134 23.12 %
CS 137 55.58 %
LUNC MAXIMLM DOSE-1.41E-02 MREM CRITICAL AGE-TEEN CRITICAL PATIMAY-FISH H
3 15.08 %
CO 60 17.56 %
CS 134 16.87 %
CS 137 41.59 %
GI-LLI MAXIMUM DOSE-2.25E-02 MREM CRITICAL AGE-ADULT CRITICAL PATHMAY-FISH t
H 3
12.80 %
CU 58 14.53 X CD 60 14.72 %
te v5 44.16 %
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CATADBA UNIT 2 LIQUID RELEASE 274-315 94 2.10E*13 C2/27/95 SKIN MAXIMUM DOSE-2.63E-03 MREM. CRITICAL AGE-TEEN CRITICAL PATWAY-SHORE t-CU 60 85.06 %
58 125 7.05 %
BONE MAXIMUM DOSE-2.11E-02 MREM CRITICAL AGE-CHILD CRITICAL PATHMAY-FISM-CS 134 15.17 %
CS 137 81.71 %
LIVE 2 MAXIMUM DOSE-2.86E-02 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-FISH CD 60 7.04 %
CS 134 21.85 %
CS 137 63.81 %
l T. BODY MAXIMUM DOSE-1.93E-02 MREM CRITICAL AGI-ADULT CRITICAL PATWAY-FISH H
3 9.61 %
CS 134 26.15 %
CS 137 59.51 %
THYRUID MAXIMUM DOSE-3.9CE-03 MREM CRITICAL AGE-TEEN CRITICAL PATNMAY-SHORE H
3 34.95 %
CQ 60 48.67 %
I 131 7.44 %
KIJNEY MAXIMUM DOSE-1.19E-02 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-FISH H
3 11.44 %
CU 60 15.93 %
CS 134 16.75 %
CS 137 52.53 %
LUNG MAXIMUM DOSE-6.84E-03 MREi! CRITICAL AGE-TEEN CRITICAL PATHMAY-FISH H
3 19.95 %
CG 60 27.77 %
CS 134 11.25 %
CS 137 36.20 %
GI-LLI MAXIMUM DOSE- -1.02E-02 MREM CRITICAL' AGE-ADULT CRITICAL PATHMAY-FISH H
3 18.06 %
MN~ 54 5.73 %
CO 58 9.34 %
CU 60 24.82 %
is 95 35.77 %
6 1
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CATAMBA UNIT 2 LIQUID RELEASE 001-315 94
- 8. %E *13 C2/27/95 SKIN MAXINUM DOSE-2.16E-02 MREM CRITICAL AGE-TEEN CRITICAL PATHNAY-SHORE CU 58 5.55 %
CU 60 78.93 %
SB 125 9.55 %
BMIE MAXIMUM DOSE-1.34E-01 MREM CRITICAL AGE-CHILD CRITICAL PATHMAY-FISH CS 134 16.17 %
CS 137 75.01 %
LIVER MAXIMUM DOSE-1.83E-01 MREM CRITICAL AGE-TEEN CRITICAL PATHMAY-FISH H
3 5.45 %
CU 60 8.39 %
CS 134 23.14 %
CS 137 58.19 %
T. BODY MAXIMUM DOSE-1.24E-01 MREM CRITICAL AGE-ADULT CRITICAL PATHMAY-FISH H
3 10.92 %
CS 134 27.61 %
CS 137 54.12 %
THYRGID MAXIMUM DOSE-4.34E-02 MREM CRITICAL AGE-TEEN CRITICAL PATMAY-FISH H
1
'22.95 %
CO
?':3 33.41 %
I 131 34.41 %
KIDNEY MAXIMUM DOSE-7.92E-02 MREM CRITICAL AGE-TEEN CRITICAL PATIMAY-FISH H
3 12.56 %
CO 60 18.27 %
CS 134 17.08 %
CS 137 46.15 %
LUNG MAXIt1Jt DOSE-4.86E-02 MREM CRITICAL AGE-TEEN CRITICAL PATIMAY-FISH H
3 20.47 % -
CG 60 29.79 %
CS 134 10.73 %
CS 137 29.73 %
i CI-LLI MAXIMUM DOSE-2.50E-01 MRFM CRITICAL AGE-ADULT CRITICAL PATIMAY-FISH H
3 5.41 %
CG 58 10.08 %
CO 60 7.77 %
PB 95 69.83 %
i CATAWBA NUCLEAR STA110N UNIT 2-RADIDACTIVE EFFLUENT RELEASES
!!.' AIR 80R M RELEASES YEAR t 1994'
' UNITS 1ST OTR 2ND QTR 3RD QTR 4TH QTR TilAl
. 1.
TOTAL NOBLE GASES CURIES.
1.23E+02 2.40E+02 3.95E+01 4.89F+Gi 4.51E+02 2.
TOTAL HALOGENS CURIES 9.16E 05 1.28E*04' O.00E+00 0.'J0E+00 2.20E 04 3.
TOTAL PARTICULATE GROSS SETA GAMMA CURIES 2.26E 06 3.92E 05 4.58E 06 0.00E+00 4.61E 05
- 4.. TOTAL TRITIUM CURIES 7.68E+00 1.09E+01 1.22E+01" 1.59E+01 4.66E+01
- 5.. TOTAL PARTICULATE GROSS ALPHA ACTIVITY CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 6.
MAXIMUM NOBLE GAS RELEASE RATE UCI/SEC 1.60E+03 1.60E+03 1.60E+03 1.60E+03-8.00E+02 7.
RADIONUCLIDES RELEASED CURIES EC RATIO
"-1 7.68E+00 1.09E+01-1.22E+01 1.59E+01 4.66E+01-5.19E 04 PARTICllATES C0 58 2.18E 06 3.92E-05 4.58E 0.00E+00 4.60E 05 - 5.12E 08 Co-60 8.62E 08 0.00E+00 0.00E+00 0.00E+00 8.62E-08 1.92E 09 HALOGENS I 131 8.84E-05 1.27E-04 0.00E+00 0.00E+00 2.16;-04 1.20E 06 1 132 0.00E+00 5.76E-07 0.00E+00 0.00E+00 5.76E 07 3.20E-11
! 133 3.20E-06 6.21E 08 0.00E+00 0.00E+00 3.26E-06 3.63E-09 GtES AR 41 1.94E+01 3.52E+01 5.29E 01 6.81E-01' 5.59E+01 6.21E-03
-KR-85 0.00E+00 6.47E 02 5.13E 02 1.70E 01 2.86E 01 4.55E-07 KR-85M 4.38E-02 2.38E 02 1.42E 02 2.06E 02 1.02E 01 1.14E*06 KR-87 0.00*+00 0.00E+00 0.00E+00 4.35E 04 4.35E 04 2.42E 08 KR-88 1.02E-02 1.22E 02 6.23E 03 1.00E-02 3.87E 02.
4.78E 06 XE-131M 6.99E 01-2.41E+00 2.50E-01 1.42E-01 3.51E+00 1.95E-06 XE 133 i.01E+02 1.98E+02 3.82E+01 4.73E+01 3.84E+02-.
8.55E 04 XE 133M 7.45E-01 1.58E+00 2.21E-01 2.52E-01 2.80E+00 5.19E-06 r.-
XE 135 1.75E+00 2.33E+00 2.11E 01 3.69E-01 4.66E+00' 7.40E 05 TOTAL EC RATIO 7.67E-03 h
CATADSA UNIT 2 GAS DOSE 001-090 94 RELEASE MI9itTED Mer REPtiti SEMtARY 03/09/95 SPECICL LtEATItM AT 0.50 MILES ME 1
NOBLE GAS EXPtISURE BETA AIR DOSE = 1.80E-01 MILLIRADS GAPMA AIR DOSE = 2.14E-01 HILLIRAOS-TUTAL BODY DOSE = 1.39E-01 MILLIREM TUTAL SKIN DOSE = 2.54E-01 MILLINEM '-
XE133 15.98%
XE133 24.64%
AR 41 82.06%
AR 41 72.16%
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CATA8eA UNIT 2 GAS DOSE 001-090 94 RELEASE M IGHTED M T REPORT SLM44RY 03/09/95 SPECIAL LOCATIt24 AT 0.50 MILES S i
10 DINE PARTICULATE, APG TRITILM EXPOSURE SLMt4RY:
MAXIMUM SItGAN
- THYRSID CRITICAL AGE
- CHILD CRITICAL PATIO 44Y - VEGET 3 79.66%
MAXIMUM ORGAN DOSE = 3.34E-02 MILLIREM M
3 78.60%
I 131 21.32X i
L I
1 1
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CATAteA LNIT 2 GAS DOSE 091-181 94 RELEASE MEIGHTED PET REPORT SEM1ARY 03/09/95 SPECIAL LOCATISI AT 0.50 MILES PedE NDBLE GAS EXPOSURE:
BETA AIR DOSE a 4.31E-01 HILLIRAOS GAPMA AIR DOSE = 5.64E-01 MILLIRADS 4
TUTAL BODY DOSE = 3.68E-01 MILLIREM TUTAL SKIN DOSE = 6.5?E-01 MILLINEM XE133 13.29%
XE133 20.95%
AR 41 85.39%
AR 41 76.68%
4 1
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CATAMBA UNIT 2 GAS DOSE 091-181 94 RELEASE HEIGHTED MET REPENtT SIMtARY 03/09/95 SPECIAL LOCATICM AT 0.50 MILES S I'IDINE, PARTICLLATE, AND TRITItM EXPOSURE SLAMARY:
MAXIMUM URGAN
- THYRUID CRITICAL AGE
- CHILD CRITICAL PATIMAY - VEGET 3 80.08%
I MAXIMLM ORGAN DGSE = 2.71E-02 MILLIREM H
3 80.08%
1 131 19.79%
i i
1
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CATAleA UNIT 2 GAS DOSE 182-273 94 RELEASE PEIGHTED MET REPORT SLRMARY 03/09/95 SPECIAL LOCATIme AT 0.50 MILES 998E NOBLE GAS EXPOSURE:
5.61E-02 MILLIRADS BETA AIR DOSE
=
GAPMA AIR DOSE = 2.40E-02 MILLIRADS TUTAL 90DY DOSE = 1.45E-02 MILLIREM TOTAL SKIN DOSE = 3.67E-02 MILLIREM XE133 71.07%
XE133 79.20%
AR 41 25.32%
AR 41 16.08%
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I CATApeA UNIT 2 GAS DOSE 182-273 94 RELEASE MIGHTED MT REPORT SE29tARY 05/09/95 SPECIAL LOCATItSt AT 0.50 MILES ENE 10 DIM, PARTICULATE, Afe TRITILM EXPOSURE SLMIARY:
MAXIltAt ORGAN
- GI-TRACK CRITICAL AGE
- CHILD CRITICAL PAT)#tAY - VEGET 4 78.26%
MAXIttJN ORGAN DOSE = 4.10E-02 MILLIREM H
3 99.96%
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CATA>SA UNIT 2 GAS DtBE 274-365 94 RELEASE MIGHTED ET REPORT St#HUtY 03/09/95 SPECIAL LOCATIt24 AT 0.50 MILES IGE HSLE GAS EXPO 5UREt BETA AIR DOSE = 9.64E-02 MILLIRADS GAfttA AIR DOSE = 4.09E-02 MILLIRADS TUTAL BODY DOSE = 2.48E-02 MILLIREM TUTAL SKIN DOSE = 6.45E-02 MILLIkEM XE133 68.55%
XE133 74.27%
XE135 9.03%
XE135 9.22%
AR 41 18.40%
AR 41 11.31%
)
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2 CATAleA UNIT 2 OAS DGSE 274-365 94 RELEASE DEIGHTED PET REPORT SEAMARY 03/09/95 SPECIAL LOCATIfM AT 0.50 MILES S 10DIPE, PARTICULATE, Are TRITItM EXPO 5URE StAMARY:
MAXIPtM ORGAN
- T,90DY CRITICAL AGE
- CHILD CRITICAL PATIMAY - VEGET 3 78.19%
MAXIMLM ORGAN DOSE = 1.03E-01 MILLIREM f
M 3
100.00%
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CATAISA (MIT 2 GAS DOSE 001-345 94 RELEASE MIGHTED ET REPORT SLattARY 03/09/95 SPECIAL LOCATIt94 AT 0.50 MILES tee NOBLE GAS EXPOSURE:
BETA AIR DOSE = 7.62E-01 MILLIRADS GAtttA AIR DOSE = 8.45E-01 MILLIRADS TUTAL BODY DOSE = 5.48E-01 MILLIREM TSTAL SKIN DOSE = 1.01E+00 MILLIREM XE133 17.89%
XE133 27.31%
AR 41 80.05%
AR 41 69.27%
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MAXIPRM ORGAN
- THYRSID CRITICAL AGE
- CHILD CRITICAL PATM4AY - YEGET 3 78.72%
MAXIMUM ORGAN DOSE = 1.85E-01 MILLIREM M
3 93.20%
1 131 6.76%
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SUPPLEMENTAL INFORMATION 1
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CATAWBA NUCLEAR STA710N EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION REPORT DATE:
03/13/95 PERIOD COVERED: START DAY = 001 STOP DAY = 365
!. REGULATORY LIMITS A. NOBLE GASES - AIR DOSE B. LIQUID EFFLUENTS - DOSE
- 1. CALENDAR QUARTER - GAMMA DOSE = 5 MRAD
- 1. CALENDAR QUARTER TOTAL BODY DOSE = 1.5 MREM
= 5 MREM
- 2. CALENDAR QUARTER - BETA DOSE = 10 MRAD
- 2. CALENDAR QUARTER - ORGAN DOSE
- 3. CALENDAR YEAR
- GAMMA DOSE = 10 MRAD
- 3. CALENDAR YEAR
- TOTAL BODY DOSE = 3 MREM d
- 4. CALENDAR YEAR
- BETA DOSE = 20 MRAD
- 4. CALENDAR YEAR
- ORGAN DOSE
= 10 MREM C. IODINE 131 AND 133, TRITIUM, PARTICULATES W/T 1/2 > 8 DAYS - ORGAN DOSE
- 1. CALENDAR QUARTER = 7.5 MREM
- 2. CALENDAR YEAR
= 15 MREM
!!. MAXIMUM PERMISSIBLE EFFLUENT CONCENTRATIONS 1
A. GASEOUS EFFLUENTS - INFORMATION FOUND IN OFFSITE DOSE CALCULATION MANUAL B. LIQUID EFFLUENTS - INFORMATION FOUND IN 10CFR20, APPENDIX 8, TABLE 2, COLUMN 2
!!!. AVERAGE ENERGY NOT APPLICABLE
- 10. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIDACTIVITY INFORMATION FOUNO IN OFFSITE DOSE CALCULATION MANUAL V. BATCH RELEASES A. LIQUID EFFLUENT
- 1. 2.82E+02 = TOTAL NUMBER OF BATCH RELEASES
)
- 2. 1.52E+04 = TOTAL TIME (MIN.) FOR BATCH RELEASES.
l
- 3. 1.03E+02 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
)
I. 5.40E+01 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.
r
- 5. 1.00E+00 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.
- 6. 4.26E+04 = AVERAGE DILUTION WATER FLOW DURING RELEASES (GPM).
I B. GASEOUS EFFLUENT
- 1. 2.15E+02 = TOTAL NUMBER OF BATCH RELEASES.
i
- 2. 9.41E+05 = TOTAL TIME (MIN.) FOR BATCH RELEASES.
1 3.1.65E+04 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
- 4. 4.38E+03 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE.
4
- 5. 5.00E+01 = MINIMUM TIME (MIN.) FOR A BATCH RELEASE.
VI. ABNORMAL RELEASES A. LIQUID i
- 1. NUMBER OF RELEASES 0
- 2. TOTAL ACTIVITY RELEASED (CURIES) 0 B. CASEQUS
- 1. NUMBER OF RELEASES 1
- 2. TOTAL ACTIVITY RELEASED (CURIES) 8.88 f
I
SUPPLEMENTAL REPORT PAGE 3 CATAWBA NUCLEAR STATION Values represented by "0.00E+00" within the. body of the Semi-Annual report are below the minimum detectable limits of the Catawba counting systems. ' Typical MDA's for the Catawba counting systems are listed below:
AVERAGE ISOTOPE ENERGY (Kev)
MDA Xe-133 80 3.50E-08 Ce-144 133 3.00E-07 Kr-88 196 3.60E-08 Xe-135
-249 1.15E-08 Kr-87 402 3.15E-08 Cs-137 661 2.50E-08 Mo-99 778 1.45E-07 Mn-54 834 2.65E-08 Zn-65 1115 6.85E-08 s
j
.Co-60 1332 2.95E-08 l
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SUPPLEIidNTAL REPORT PAGE 4 i
CATAWBA NUCLEAR STATION 1
i The estimated percentage of error for both Liquid and Gaseous effluent release data at Catawba Nuclear Station has been determined to be i 16.1%.
This value was derived by taking the square root of the sum of'the squares of the following discrete
<I individual estimates of error:
i; i
(1)
Flow rate determining devices 5%
=
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j (2)
Counting error 15%.
=
i (3)
Sample preparation error i
3%
=
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FUEL CYCLE CALCULATION k
1994 CATAMkA FUEL CYCLE StM1ARY DAYS 001-365 03/13/95 AT 09:52 i
i MAXIt1UM TUTAL BODY te4E 0.50 MILES 1.39E+00 AGE : ADULT CNS. GAS 1.10E+00 79.0 %
XE133 17.8 %
- AR 41 80.0 %
CNS. LIQUID 2.48E-01 17.9 %
CRITICAL PATH FISH 91.7 %
H 3'
10.8 %-
CS 134 27.6 %
CS 137 54.0 %
9945. GAS 1.16E-03 0.0 %
KR 88 7.4 %
XE133 50.1 %
XE13S 26.5 %
AR 41 14.3 %
9945. LIQUID 4.07E-02 2.9 %
CRITICAL PATH FISH 7?.2 %
H 3
27.1 %
CS 134 28.7 %
CS 137 39.4 %
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1994 CATANA FUEL CYCLE SIAttARY DAYS 001-365 03/13/95 AT 09:52 MAXIMUM ORGAN S 0.50 MILES 8.34E-01 AGE : CHILD ORGAN : THYROID CNS. GAS 3.70E-01 44.4 %-
CRITICAL PATH GARDEN 78.7 %
H 3
93.2 %
I 131 6.7 %
CNS. LIQUID 6.78E-02 8.1 %
CRITICAL PATH FISH 55.4 %
H 3
39.4 %
I 131 48.6 %
794S. GAS 5.86E-03 0.7 %
CRITICAL PATH GUAT MILK 61.7 %
H 3
52.8 %
I 131 46.8 %
tees. LIQUID 3.90E-01 46.7 %
CRITICAL PATH DRIDEING 84.4 %
I 131 92.7 %
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h 1994 CATAPSA FUEL CYCLE SUP9tARY DAYS C01-365 03/13/95 AT 09:52 i
i MAXIrtJPt TOTAL BODY NPE 0.50 MILES' 1.39E+00 AGE : ADULT l
1 MAXIHLM ORGAN S 0.50 MILES 8.34E-01 AGE : CHILD ORGAN : THYROIO i
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l ATTACHMENT II The Solid Waste Report j
i CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE SHIPPED TO A DISPOSAL FACILITY REPORT PERIOD 1/1/94 THROUGH 12/31/94 Number of Number of Waste Container A ti ty Type of Waste Shipped Shipments Containers Class Type (ft )
(m )
(Curies) 1.
Waste from Liquid Systems (A) Dewatered Secondary Resins 2"
5" 5AU" SSTC" 3840.7 108.77 0.0229 (B) Dewatered Primary Resins 3
3 2AS,1B 3 HIC 531.9 15.06 128.3 (C) Evaporator Concentrates 0
0 N/A N/A O
O O
(D) Dewatered Mechanical Filters 2"
2" 1AS,1B" 2 HIC" 159.9 4.53
'33.20 (E) Dewatered Demineralizers 0
0 N/A N/A 0
0 0
(F) Solidified (Cement) Acids, 3
3 3AS 3 HIC 559.0 15.83 144.8 Oils, Sludges 2.
Dry Solid Waste (A) Dry Active Waste (compacted) 0 0
N/A N/A 0
0 0
(B) Dry Active Waste (non-compacted) 3 3
3AS 3 HIC 360.9 10.22 4.268 (C) Dry Active Waste (brokered) 2434.5 68.95 1.895 (D).. Irradiated Components 0
0 N/A N/A 0
0 0
'13" 16" 7886.9 223.36 312.4859 Total "Does not include brokered totals
~
CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE
SUMMARY
,OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD 1/1/94 THROUGH 12/31/94 4
i e
Type of Waste Radionuclide
% Abundance 1.
Waste from Liquid Systems (A) Dewatered Secondary Resins Cr-51 1.5 Mn-54 3.6 Co-58 6.3 Co-60 8.6 Nb-95 1.0 I
Sb-125 2.2 Cs-134 15.6 Cs-137 23.2 C-14 3.1 I
Fe-55 29.9 Ni-63 3.1 (B) Dewatered Primary Resins Kn-54 5.7 I
Co-58 27.0 Co-60.
10.2 Cs-134 2.5 l
Cs-137 5.2 i
Fe-55 26.5 I
Ni-63 22.8 (C) Evaporator Concentrates (none shipped this period)
(D) Dewatered Mechanical Filters Mn-54 6.7 Co-58 2.6 Co-60 16.3 Fe-55 67.5 Ni-63 6.8 (E) Dewatered Dominera11zers (none shipped this period)
(F) Solidified Acids, Oils, Sludges Kn-54 1.0 Co-60 16.6 Fe-55 74.0 Ni-63 8.1 Average percent abundance for all shipments during period (not listed if <1%)
i Page 1 of 2
l l
CATAWBA N* CLEAR STATION - SOLID RADIOACTIVE WASTE I
SUMMARY
OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD 1/1/94 THROUGH 12/31/94 Type of Wante Radionuclide
% Abundance 2.
Dry Solid Waste (A) Dry Active Waste (compacted)
(none shipped this period) l l
(B) Dry Active Waste (non-compacted)
Mn-54 3.2 Co-58 33.1 Co-60 10.5 Fe-55 47.9 Ni-63 5.1 (C) Dry Active Waste (brokered)
Mn-54 3.1 Co-58 23.7 Co-60 11.8 Cs-137 1.0 Fe-55 53.5 Ni-63 5.5 l
(D)
Irradiated Components (none shipped this period)
- Average percent abundance for all shipments during period (not listed if <1%)
Page 2 of 2
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ATTACHMENT IV I
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l Abnormal Releases 1
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ABNORMAL RELEASES On November 2, 1994, at approximately 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />, control Room personnel noted that the Auxiliary Building (EMF-41) and the Unit Vent (2 EMF-36) radiation monitors' counts were increasing. At that time approximately 2 psig was being pressure released from Waste Gas Decay Tank "D".
Instrumentation personnel were working on a Wasta Gas System valve-(lWG-199), and were cycling the valve when gas leaked from the moisture-traps. A gas sample was collected by Radiation Protection' personnel at 2043, and a Gaseous Waste Release (GWR) package was generated based on the tank concentration. Trending of the Unit Vent radiation monitor showed that considerably less activity was actually released over the.
release period (210 minutes). The Total Body dose was conservatively-calculated to be 2.63E-03 mrom based on an estimated 8.88 Curies of noble gases being released. There were no Release Limits or Dose Limits met or exceeded as a result of this abnormal occurrence. A minor modification was implemented which replaced the moisture traps, and should prevent a recurrence of this event.
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ATTACHMENT V i
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Revisions To l
Offsite Dose Calculation (ODCM) Manual and I
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l Process Control Program (PCP) Manual f
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' DaeIbwerCompany M S nmowv i' 's P.O. Box 1006 -
Senior Vicehesident.
Garlotte, hc2820I4006 NuclearGeneratson (704)382-2200 omce (104)3824360 Fax HKEPOMR.
January 5,1995 j
U. S. Nuclear Regulatory Comnussion Document Control Desk Washington, DC 20555
Subject:
Oconee Nuclear Station, Units 1, 2, and 3 Docket Nos. 50-269,50-270,50-287 d
McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369,50-370 Catawba Nuclear Station, Units I and 2 Docket Nos. 50-413,50-414 Offsite Dose Calculation Manual (ODCM) Revisions 1
I am enclosing revisions made to the Duke Power Company Offsite Dose Calculations i
Manual effective January 1,1995. The original of this letter submits a complete copy of the entire ODCM as required by Oconee Technical Specification 6.1.2.1.L.2) and McGuire Technical Specification 6.14.2.c. The following sections are affected by this -
l revision.
Revision 38 Generic Section Revision 35 Oconee Nuclear Station
)
Revision 36 McGuire Nuclear Station Revision 37 Catawba Nuclear Station 5
By copy of this letter, I am transmitting the revised pages to be inserted in Control Copy Number 33 (assigned to ONRR) ar.d Control Copy Number 34 (assigned to Region II) along with an approval letter for each section. For these copies, please insert revision pages affected according to the insertion instructions found on the approval letters. The j
approval letter for the Generic Manual along with the justification for Revision 38 should be placed in front of the entire manual. Each station approval letter (including justifications) should be placed in the front of the respective station manual sections.
d If you have any questions, please contact L. B. Jones at (704) 382-4753.
Very truly yours, l
?\\3:[%e.,
t M. S. Tuckman Attachment (Original only - entire copy of updated ODCM) w.ww
ATTACHMENT VI Catawba Nuclear Station Final Safety Analysis Report Section 16.11 i
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16.11 RADIOLOGICAL EFFLUENTS CONTROLS i
RADIOACTIVE EFFLUENTS 1
4 4
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16.11-1 LIQUID EFFLUENTS a
i j
CONCENTRATION COMMITMENT
)
The concentration of radioactive material released in liquid effluents to UNRESTRICTED
[
AREAS (see Figure 16.11-1) shad be limited to ten times the effluent concentrations specified i
in 10 CFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or l
entrained noble gases. For dissolved or entrained noble gases, the er. centration shall be j
limited to 2 x 10-9 microcurie /mi total activity.
gj t
j APPLICABILITY: At all times.
i l
REMEDIAL ACTION:
i With the concentration of radioactive material released in liquid effluents to UNRESTRICTED l
- 4 AREAS exceeding the above limits, immediately restore the concentration to within the above i
limits.
l l
TFSJ::'S REQUIREMENTS:
1
\\
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,,a liquid wastes shall be sampled and analyzed according to the sampling and j
analysis program of Table 16.11-1.
[
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The results of the radioactivity analyses shall be used in accordance with the methodology and j
parameters in the ODCM to assure that the concentrations at the point of release are l
l maintained within the limits of SLC 16.11-1.
t
REFERENCES:
)
l 1.
Catawba Offsite Dose Calculation Manual i
2.
BASES:
The basic requirements for Selected Licensee Commitments concoming effluents from nuclear j
power reactors are stated in 10 CFR 50.36a. These requirements indicate that compliance with effluent Selected Licensee Commitments will keep average annual releases of radioactive l
material in effluents to small percentages of the limits specified in the old 10 CFR 20.106 (new 10 CFR 20.1302). ~ These requirements further indicate that operational flexibility is allowed, compatible with considerations of health and safety, which may temporarily result in releases j
higher than such small percentages, but still within the limits specified in the old 10 CFR j
20.106 which references Appendix B, Table 11 concentrations (MPCs). These referenced concentrations are specific values which relate to an annual dose of 500 mrem. It is further l
{4 16.11 1 08/01/94 r
2
1 indicated in 10 CFR 50.36a that when using operational flexibility, best efforts shall be exerted j
'to keep levels of radioactive materials in effluents as low as is reasonably achievable (ALARA)
. as set forth in 10 CFR 50, Appendix 1.
[
As stated in the introduction to Appendix B of the new 10 CFR 20, the liquid effluent l
concentration (EC) limits given in Appendix B, Table 2, Column 2,' are based on an annual i
dose of 50 mrem. Since a release concentration corresponding to a limiting dose rate of 500 i
mrem / year has been acceptable as a SLC limit for liquid effluents, which applies at all times as an assurance that the limits of 10 CFR 50, Appendix I are not likely to be exceeded, it should i
not be necessary to reduce this limit by a factor of 10.
j Operational history at Catawba has demonstrated that the use of the concentration values' j
associated with the old 10 CFR 20.106 as SLC limits has resulted in calculated maximum i
individual doses to a MEMBER OF THE PUBLIC that are small percentages of the limits of 10 j
CFR 50, Appendix 1. Therefore, the use of concentration values which correspond to an i
annual dose of 500 mrom (ten times the concentration values stated in the new 10 CFR 20, i
Appendix B, Table 2, Column 2) should not have a negative impact on the ability to continue'.
l to operate within the limits of 10 CFR 50, Appendix ! and 40 CFR 190.
i t
j Having sufficient operational flexibility is especially important in establishing a basis for effluent i
i :*
monitor setpoint calculations. As discussed above, the concentrations stated in the new 10 -
ll CFR 20, Appendix B, Table 2, Column 2, relate to a dose of 50 mrem in a year. When applied on an instantaneous basis, this corresponds to a dose rate of 50 mrem / year. This low value is impractical upon which to base effluent monitor setpoint calculations for many liquid effluent i
release situations when monitor background, monitor sensitivity, and monitor performance '
l 4
must be taken into account.
)
Therefore, to accommodate operational flexibility needed for effluent releases, the kmits l
l associated with SLC 16.11-1 are based on ten times the concentrations stated in the new 10 i
l CFR20, Appendix B, Table 2, Column 2, to apply at all times. The multiplier of ten is proposed i
because the annual dose of 500 mrem, upon which the concentrations in tha old 10 CFR 20,
{
Appendix B, Table 11, Column 2, are based, is a factor of 10 higher than annual dose of 50 l
mrem, upon which the concentrations in the new 10 CFR 20, Appendix B, Table 2, Column 2, 1
j are based. Compliance with the limits of the new 10 CFR 20.1301 will be demonstrated by i
operating within the limits of 10 CFR 50, Appendix I and 40 CFR 190. The concentration limit I
for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the t
controlling radioisotope and its MPC in air (submersion) was converted to an equivalent l
concentration in water using the methods described in Intemational Commission on Radiological Protection (ICRP) Publication 2.
l This commitment applies to the release of radioactive materials in liquid effluents from all units i -
at the site.
s The required detection capabilities for radioactive materials in liquid waste samples are i
tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and l
other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually),
(
l Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to
[
Radiochemistry," Annal. Chem. 40.586-93 (1968), and Hartwell, J. K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-j 115 (June 1975)..
l 16.I1-2 08/01/94 i
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TADLE 16.11-1 (Page 1 of 3) s j
1%DICACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM i
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LOWER LIMIT MINIMUM -
OF DETEpTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTMTY (LLD)d).
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TYPE FREQUENCY FREQUENCY ANALYSIS (pCL/ml) a
- 1. Batch Weste P
P l
Release Each Batch Each Batch Principle Gamma 5x10-7 l
Tanks (2)
Emitters (3) i i
1 1-131 1x104 l
Any tank which i
discharges P
M Dissolved and 1x10-3 luquid wastes One Batch /M Entrained Gases i
by adher liquid (Gamma emitters) eNiuent moni-l tor, EMF-49 or EMF-57 P
M H-3 1x10-3 Each Batch Composite (4)
]
Gross Alpha 1x10-7 4
P Q
Each Batch Composite (4) i
- 2. Continuous W
Principal Gamma 5x10-7
{
Releases (5)
Continuous (6)
Composite (6) Emitters (3) l l-131 1x104 i
- s. Convenbonal j
Waste Water M
M Dissolved and
' 1x10-3 Treatment Grab Sample Entrained Gases Line (Gamma Emitters) i
- b. Turbine Building Sump M
H-3 1x10-5 Domineralizer Continuous (6)
Composite (6) j Skid, EMF-31*
Gross Alpha 1x10-/
~'
Q Sr-89, Sr 90 5x10-5
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Continuous (6)
Composite (6)
- During use of domineralizer (use of EMF-31 in off normal mode).
16.I1-3 09/23/94
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l TABLE 16.11-1 (Page 2 of 3) i d
TABLE NOTATIONS P
The LLD is ' efined, for purposes of these commitments, as the smallest concentration (1)-
d of radioactive materialin a sample that will yield a not count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
I i
For a particular measurement system, which may include radiochemical separation:
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4.66 s 4
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i LLD = E V
2.22 x 106 - Y, exp (-Aat) r i
I Where:
LLD = the "a priori" lower limit of detection (microCuris per unit mass or volume),
f
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sb = the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (counts per minute),
c j
E = the counting efficiency (counts per disintegration),
V = the sample size (units of mass or volume),
i 6
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2.22 x 10 = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (sec -1), and i
at = the elapsed time between midpoint of sample collection and time of counting (sec).
t Typical values of E, V, Y and at shall be used in the calculation.
it should be recognized that the LLD is defined as an a p_n ri (before the fact) limit i
g representing the capability of a measurement system and not as an 3 oosteriori (after the fact) limit for a particular measurement.
(2)
A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.
i 16.11 4 08/01/94 c.
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TABLE 16.11-1 (Page 3 of 3)
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TABLE NOTATIONS (Continued)
(3)
The principal gamma emitters for which the LLD specification applies include the l
i following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65,' Mo-99, Cs-134, Cs-137, and Ce-141. The LLD for Co-144 is 5x10-6 Ci/ml. This list does not mean that only l
these nuclides are to be considered. Other gamma peaks that are identifiable, togeth' r e
I with those of the above nuclides, shall also be analyzed and reported in the Annual l'
Radioactive Effluent Release Report pursuant to Technical Specification 6.9.1.7 in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.
I i
j (4)
A composite sample is one in which the quantity of liquid sampled is proportional to the l
l quantity of liquid waste discharged and in which the method of sampling employed i
results in a specimen that is representative of the liquids released.
(5)
A continuous re! ease is the discharge of liquid wastes of a nondiscrete volume, e.g.,
from a volume of a system that has an input flaw during the continuous release.
]:'
(6)
To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow I
of the effluent stream. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent l
release.
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i 16.11 RADIOLOGICAL EFFLUENTS CONTROLS i
INSTRUMENTATION 16.11-2 RADIOACTIVE L!GulD EFFLUENT MONITORING INSTRUMENTATION COMMITMENT The radioactive liquid effluent. monitoring instrumentation channels shown in Table 16.11-2 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of SLC 16.11-1 are not exceeded. The Alarm / Trip Setpoints of these channels shall be determined and' adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
APPLICABILITY: At all times.
REMEDIAL ACTION.
i a.
With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declan the channel inoperable.
b.
With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 1_6.11-2.
Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Annual Radioactive Effluent
[!
Release Report pursuant to Technical Specification 6.9.1.7 why this inoperability was not corrected within the time specified.
TESTING REQUIREMENTS:
Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated i
OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION and ANALOG CHANNEL OPERATIONAL TEST operations at.the frequencies l
shown in Table 16.113.
t
REFERENCES:
1.
Catawba Offsite Dose Calculation Manual 2.
)
I 16.11-6 08/01/94
BASES:
The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the AlarmTTrip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and i
use of this instrumentation is consistent with the requirements of General Design Criteria 60, i
63, and 64 of Appendix A to 10 CFR Part 50.
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4 1611 7 08/01/94
l' TABLE'16.11-2 (Page 1 of 2)
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE.
ACTION
+
1.
Radioactivity Monitors Providing Alarm And Automatic Termination of Release Waste Liquid Discharge Morwtor (Low Rcnge - EMF-49) a.
1 per station 1
b..
Turbine Buddmg Sump Morwtor (Low Range - EMF-31) 1 3
c.
Deleted d.
Monitor Tank Building Liquid Discharge Monitor (EMF-57) 1 per station 1
2.
Continuous Composite Samplers And Sampler Flow Monitor t
Conventional Waste Water Treatment Line a.
1 per station :
3 b;
Turbine Building Sump 1 per station 3*
i 3.
Flow Rate Measurement Devices a.
Waste Liquid Effluent Line 1 per staten I
- 2-b Conventional Waste Water. Treatment Line t
1 per station' 2
Low Pressure Service Water Mwwmum Flow Intedock c.
1 per staten 2
d.
Monitor Tank Building Waste Liquid Effluent Line 1 per staten 2
Turbine Building Sump Demineralizer Skid Totalizer e.
.1 per station 2*
t 16.Il-8 08/01/94 4
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,+.,,ns
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, - -. -. ~,,.,,., -.,.,
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i TABLE 16.11-2 (Page 2 of 2) i TABLE NOTATIONS 1.
- During use of domineralizer (EMF-31 in off normal mode)
I 1
ACTION STATEMENTS 1
ACTION 1 -
With the number of channels OPERABLE less than required by 3
continue for up to 14 days provided that prior
}
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At least two independent samples are analyzed in accordance a.
i 16.11-1; and, i'
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b.
At least two technically qualified members of the facility staff independently verify:
i i
1)
The discharge line valving; and, 2)
The manual portion of the computer input for the release rate I
))*
calculations performed on the computer, or the entire release rat; calculations if such calculations are performed manually.
3 Otherwise, suspend release of radioactive affluents via j i
ACTION 2 -
With the number of channels OPERABLE less than required by i
Channels OPERABLE requirement, effluent releases via this i
j t
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump perfo may be used to estimate flow.
i ACTION 3 -
4 With the number of channels OPERABLE less than required by i
Channels OPERABLE requirement, effluent releases via th i
i continue for up to 30 days provided grab samples are analyze i,
i at a lower limit of detection of no more than 10-7 microcurie /ml:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity 'of the s s.
1 coolant is greater than 0.01 microCurielgram DOSE EQUlVAL or i,
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the sec coolant is less than or equal to 0.01 microcurie / gram DOSE EQU l
1 l-131.
j ACTION 4 -
Deleted t
3 6
2 I
I 1
16.11-9 I
a 08/01/94 i
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TABLE 16.1'
' age 1 Cf 2)
RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS ANALOG CHANNEL CHANNEL SOURCE CHANNEL OPERATIONAL INSTRUMENT CHECK CHECK CALIBRATION TEST 1.
Radioactivity Monitors Providing Alarm and Automatic Tennination of Release a.
Waste Liquid Discharge Monitor D
P R(2)
Q(1)
(Low Range - EMF-49) b.
Turbine Building Sump Monitor D
M R(2)
Q(1)
(Low Range - EMF-31) c.
Deleted d.
Monitor Tank Building Liquid Descharge D
P R(2)
Q(1)
Monitor (EMF-57) 2.
Continuous Composite Samplers and Sampler Flow Monitor a
Conventional Waste Water Treatment D(3)
N.A.
R N.A.
Line b.
Turbine Building Sump D(3)
N.A.
R N.A.
3.
Flow Rate Measurement Devices a.
Waste Liquid Effluent une D(3)
N.A.
R' N.A.
b.
Conventional Waste Water Treatment D(3)
N.A.
R N.A.
Line c.
Low Pressure Service Water Minimum D(3)
N.A.
R Q
Flow Interlock d.
Monitor Tank Building Waste Liquid D(3).
N.A.
R Q
Effluent Line e.
Turbine Building Sump D(3)
N.A.
R N.A.
Demineralizer Skid Totalizer 16.11-10 08/01/94
TABLE 16.11-3 (Page 2 of 2) i j
TABLE NOTATIONS (1)
The ANALOG CHANNEL OPERATIONAL TEST shall also demonstra isolation of this pathway and control room alarm annunciation
- occurif any of the following conditions exists:
Instrument indicates measured levels above the Alarm / Trip Setpoint; or, a.
b.
Circuit failure (alarm only); or, Instrument indicates a downscale failure (alarm only).
c.
(2)
The initial CHANNEL CAllBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system l
over its intended range of energy and measurement range. For subsequent CHANNEL -
l CALIBRATION, sources that have been related to the initial calibration shall be used.
I (3)
CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
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- For EMF-57, the alarm annuciation is in the Monitor Tank Building Control Room and on th i
MTB Control Panel Remote Annunciator panel.
l 16.!l 1J og/oj/94
16.11.
. RADIOLOGICAL EFFLUENTS CONTROLS -
RADIOACTIVE EFFLUENTS 16.11-3 DOSE COMMITMENT The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive m liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Figure 16.11-1) shall be limited:
During any calendar quarter to less than or equal to 1.5 mrem to the whole body a.
and to less than or equal to 5 mrom to any organ, and -
b.
During any calendar year to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem.to any organ.
APPLICABILITY: At all times.
REMEDIAL ACTION:
With the calculated' dose from the release of radioactive materials in liquid effluents exceedi!
any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the re proposed corrective actions to be taken to assure that subsequent releases will be in.
compliance with the above limits. This Special Report shall also include:
(1) the results of -
radiological analyses of the' drinking water source, and (2) the radiological impact on finished
~
drinking water supplies with regard to the requirements of 40 CFR Part 141, Safe Drinking i
Water Act.*
i TESTING REQUIREMENTS:
i Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
REFERENCES:
l l
l 1.
Catawba Offsite Dose Calculation Manual 2.
40 CFR Part 141 3.
10 CFR Part 50, Appendix !
i l
1
- The requirements of REMEDIAL ACTION (1) and (2) are applicable only if drinking water i
l supply is taken from the receiving water body within 3 miles downstream of the plant discharge.
i 16.!!-12 08/01/94 i
i l
BASES:
Appendix 1,10 CFR Part 50. The Limiting Cond j
i forth in Section ll.A of Appendix L The REMEDIAL ACTION statemen j
operating flexibility and at the same time implement the guides set forth in S i
Appendix l to assure that the releases of radioactive material in liquid efflue STRICTED AREAS will be kept "as low as is reasonably achievable". Also sites with drinking water supplies that can be potentially affected by plant i
tions in the finished drinking water that are in exces I
{
The dose calculation methodology and parameters in the ODCM implem j
in Section lil.A of Appendix I that conformance with the guides of Ap i
calculational procedures based on models and data, such that the actual expos MEMBER OF THE PUBLIC through appropriate pathways is unlikely to i
underestimated. The equations specified in the ODCM for calculating the do actual release rates of radioactive materials in liquid effluents are consistent with methodology provided in Rsgulatory Guide 1.109, " Calculation of Annual D Routine Releases of Reactor Effluents for the Purpose of Evaluating Com i
Part 50, Appendix 1," Revision 1, October 1977 and Regulatory Guide i
Aquatic Dispersion of Effluents from Accidental and Routine Reactor R of implementing Appendix I," April 1977.
This commitment applies to the release of radioactive materials in liquid e i
unit at the site. When shared Radwaste Treatment Systems are used by m j
releases cannot accurately be ascribed to a specific i
i contributions from each unit based on input conditions, e.g., flow rates an each of the radioactive waste producing units sharin j
Systems are to be added to the releases specifica i
{
j releases per unit.
i 1
i-i 1
l 16.11 13 08/01/94
i:
4 1
.16.11 RADIOLOGICAL EFFLUENTS CONTROLS l
4 RADIOACT!VE EFFLUENTS q
16.11-4' LIQUID RADWASTE TREATMENT SYSTEM i
COMMITMENT The Liquid Radwate Treatment System shall be OPERABLE and appropriate portions of the.
system shall be used to reduce releases of radioactivity when the projected doses'due to the
^
liquid effluent, from each unit, to UNRESTRICTED AREAS (see Figure 16.11 1) would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ in a 31-day period.
I.
j-
' APPLICABILITY: At alltimes.
i j
REMEDIAL ACTION:
(
With radioactive liquid waste being discharged without treatment and in excess of the above '
limits and any portion of the Liquid Radwaste Treatment System not in operation, prepare and j
submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2 a Special -
j, Report that includes the following information:
1.
Explanation of why liquid radwaste was being discharged without treatment, j
identification of any inoperable equipment or subsystems, and the reason for the inoperability, I
- 2. -
Action (s) taken to restore the inoperable equipment to OPERABLE status, and i
3.
Summary description of action (s) taken to prevent a recurrence.
TESTING REQUIREMENTS:
4 a
4 i
Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM
{
when Liquid Radwaste Treatment Systems are not being fully utilized.
1 i
The instal!ed Uquid Radwaste Treatment System shall be considered OPERABLE by meeting' SLC 16.11-1 and 16.11-3.
4
.I
{
REFERENCES:
'j 1.
Catawba Offsite Dose Calculation Manual d
2.
i i
I 16.Il-14 08/01/94
~^
^
BASES:
L j
[
The OPERABILITY of the Liquid Radwaste Treatment System e available for use whenever liquid effluents require treatment prior t m will be i
ment. The requirement that the appropriate portions of this system provides assurance that the releases of radioactive materials in low as is reasonably achievable". This commitment implements th p
as Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR P the use of appropriate portions of the Liquid Radw esign j
Part 50, for liquid effluents. suitable fraction of the dose design obje pecified as a j
This commitment applies to the release of radioactive materials in L
unit at the site. When shared Radwaste Treatment Systems are us l
c releases cannot accurately be ascribed to a spe j
{
contributions from each unit based on input conditions, e.g., flow ra each of the radioactive waste producing units sha i
i
. determining conformance to LCOs, these allocations from shared Rad Systems are to be added to the releases specifically attributed to e releases per unit.
a 4
i i
i b
I a
1j i
2
).
16.11-15 08/01/94 a-1
+
16.11 RADIOLOGICAL EFFLUENTS CONTROLS RADIOACTIVE EFFLUENTS 16.11 5 CHEMICAL TREATMENT PONDS COMMITMENT by the following expression:The quantity of radioactive material contained ent pond shall be limited A
204- -
E -.}
< 1.0 V
.J (Cj x 10) excluding tritium and dissolved or entrained noble gases, Where:
Aj
= pond inventory limit for single radionuclide "j", in Curies; Cj
= 10 CFR 20, Appendix B, Table 2 Column 2, concentration for s
?
"j", microCuries/ml; radionuclide V
= design volume of liquid and slurry in the pond, in gallons; and 264 = conversion unit, microCuries/ Curie per milliliter / gallon.
APPLICABILITY: Atalltimes.
REMEDIAL ACTION:
limit, immediately suspend all additions of radioactive onds exceeding the above corrective action to reduce the pond contents to within the limit o the pond and initiate TESTING REQUIREMENTS:
transferred to the chemical treatment ponds shall be det water slurry to be by analyzing a representative sample of the batch to be transfened to be within t ponds and shall be limited by the expression:
rred to the chemical treatment c
I -.i < 0.006 j (C; x 10) 16.11 16 08/01/94
]
o Where:
I 4
I cj = UNRESTRICTED AREA chemical treatmradioactive resin j
ent ponds, in.microCuries/ milliliter; and, t
Cj = 10 CFR 20, Appendix B, Table 2, Column 2, concentration for sin i
"j" in microCuries/ milliliter.
L REFERENCES i
1.
Catawba Offsite Dose Calculation Manual 2.
10 CFR Part 50, Appendix i i
BASES:
The inventory limits of the chemical treatment ponds (CTP) are based on consequences of an uncontrolled release of the pond inventory. The expression i commitment assumes the pond inventory is uniformly mixed, that the pond is t
9 Appendix B of 10 CFR Part 20 applies. uncontrolled area as defined f' transferred to the CTP are "as low is reasonably a 50.36a. The expression in SLC 16.11-6 assures no batch will be transf!
i the sum of the ratios of the activity of the radionuclides to their respective c ss level to the instantaneous whole body dose rate limitatio ose c.
I_L
< _ 3 mrem /vr = 0.006
[
} (C; x 10) 500 mrem /yr s
i Where:
i l
o c; = radioactive resin / water slurry concentration for radionuclide "j" enterin UNRESTRICTED AREA CTP, in microCuries/ milliliter; anJ, I
C; = 10 CFR Part 20, Appendix B, Table 2, Column 2, concentration fo radionuclide "j", in microCuries/ milliliter.
t The filter /demineralizers using powdered resin and the blowdown domineraliz sample of the resin inventory in the tank. A known i
content approximately 55 to 60%, bulk density of about 58 pounds per cubic i
counted. The concentration of the resin slurry to be pumped to the chemica L
will then be determined by the formula:
i F
- 16. I l-l 7 08/0 t/94 I
>n w
a
~
n-n
i l.
l Qw c) =
i R
VT Where:
Oj = concentration of radioactive materials in wet, drained resin than an 8-day half-life. The analysis shallinclu 137, Co-58 and Co-60, in microCuries/ gram. Estimates of the Sr-8 batch concentration shall be included based on the most recent m composite analysis (within 3 months);
W = total weight of resin in the storage tank in grams (determine R
procedures); and, V
T = total volume of resin water mixture in storage tank to be transferred to the chemical treatment ponds in milliliters.
The batch limits provide assurance that activity input to the CTP will be m means of identifying radioactive materialin the inventory limitation of this comm
- e 1
t t
)
i l
1 l
i l
16.11-18 og/o]/94 9-
4 J
16.11 RADIOLOGICAL EFFLUENTS CONTROLS RADIOACTIVE EFFLUENTS 16.11-6 GASEOUS EFFLUENTS DOSE RATE i
COMMITMENT The dose rate due to radioactive materials released in gaseous effluents from the at and beyond the SITE BOUNDARY (see Figure 16.11-1) shall be limited to th a.
For noble gases: Less than or equal to 500 mrem /yr to the whole body and less than or equal to 3000 mrem /yr to the skin; and, b.
For lodine-131, for lodine-133, for tritium, and for all radionuclides in particula form with half-lives greater than 8 days: Less than or equal to 1500 mrem /yr to any organ.
APPLICABILITY: At all times.
e REMEDIAL ACTION:
With the dose rate (s) exceeding the above limits, immediately restore the relea the above limit (s).
TESTING REQUIREMENTS:
The dose rate due to noble gases in gaseous effluents shall be determined to be w above limits in accordance with the methodology and parameters in the ODCM.
The dose rate due to lodine-131, lodine-133, tritium, and all radionuclides in partic with half-lives greater than 8 days in gaseous effluents shall be determined to be with above limits in accordance with the methodology and parameters in the ODC representative samples and performing analyses in accordance with the samplin program specified in Table 16.11-4.
REFERENCES:
1.
Catawba Offsite Dose Calculation Manual 2.
l l
16 11 19 08/01/94
L BASES:
The basic requirements for Selected Licensee Commitments concoming effluents from power reactors are stated in 10 CFR 50.36a. These requirements indicate that compliance with effluent Selected Licensee Commitments will keep average annual releases of radio materialin effluents to small percentages of the limits specified in the old 10 CFR 20.
10 CFR 20.1301). These requirements further indicate that operational flexibility is allo compatible with considerations of health and safety, which may temporarily result in releases higher than such small percentages, but still within the limits specified in the old 10 CFR 20.106 which references Appendix B, Table il concentrations (MPCs). These referenced concentrations are specific values which relate to an annual dose of 500 mrems. It is further indicated in 10 CFR 50.36a that when using operational flexibility, best efforts shall be to keep levels of radioactive materials in effluents as low as is reasonably achievabl as set forth in 10 CFR 50, Appendix 1.
As stated in the introduction to Appendix B of the new 10 CFR 20, the gaseous effluent concentration (EC) limits given in Appendix B, Table 2, Column 1, are based on an annual dose of 50 mrems for isotopes for which inhalation or ingestion is limiting or 100 mrems for isotopes for which submersion (noble gases) is limiting. Since release concentrations corresponding to limiting dose rates less than or equal to 500 mrems/ year to the whole 3000 mroms/ year to the skin from noble gases, and 1500 mrems/ year to any organ from lodine-131, lodine-133, tritium and all radionuclides in particulate form with half-lives than eight days at the site boundary has been acceptable as a SLC limit for gaseous efflue to assure that the limits of 10 CFR 50, Appendix i and 40 CFR 190 are not likely to be exceeded, it should not be necessary to restrict the operational flexibility by incorporatin dose rate associated with the EC value for isotopes based on inhalation / ingestion (50 i
mrems/ year) or the dose rate associated with the EC value for isotopes based on submers (100 mrems/ year).
Having sufficient operational flexibility is especially important in establishin0 a basis fo monitor setpoint calculations. As discussed above, the concentrations stated in the new 1 CFR 20, Appendix B, Table 2 Column 1, relate to a dose of 50 or 100 mrems in a yea applied on an instantaneous basis, this corresponds to a dose rate of 50 or 100 mrem These low values are impractical upon which to base effluent monitor setpoint calculat many gaseous effluent release situations when monitor background, monitor sensitivity, an monitor performance must be taken into accourit.
Therefore, to accommodate operational flexibiCty needed for effluent releases, the limits associated with gaseous release rate SLCs will be maintained at the current instantaneous dose rate limit for noble gases of 500 mrems/ year to the whole body and 3000 mrems the skin; and for lodine-131, for lodine-133, for tritium, and for all radionuclides in partic form with half-lives greater than 8 days, an instantaneous' dose rate limit of 1500 to any organ.
Compliance with the limits of the new 10 CFR 20.1301 will be demonstrated by op within the limits of 10 CFR 50, Appendix I and 40 CFR 190. Operational history at Catawb has demonstrated that the use of the dose rate values listed above (i.e., 500 mrems 3000 mrems/ year, and 1500 mrems/ year) as SLC Imts has resulted in calculated maxim individual doses to MEMBERS OF THE PUBLIC that are small percentages of the limit CFR 50, Appendix l and 40 CFR 190. For MEMBERS OF THE PUBLIC who may at ti 16.I1-20 08/0I/94
4 i
i within the SITE BOUNDARY, the occupancy of that MEMBER OF THE PUBLIC'w sufficiently low to compensate for any increase in the atmospheric diffusion factor abo for the SITE BO.UNDARY. Examples of calculations for such MEMBERS OF THE i -
with the appropriate occupancy factors, shall be given in the ODCM. The specified relea rate limits restrict, at all times, the corresponding gamma and beta dose rates above back-ground to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or j
~
equal to 500 mrem / year to the whole body or to less than or equal to 3000 mrem / year t skin. These release rate limits also restrict, at all times, the corresponding thyroid dose r above background to a child via the inhalation pathway to less than or equal to 1500
{
mrem / year.
i This commitment applies to the release of radioactive materials in gaseous effluents from a units at the site, i
The required detection capabilities for radioactive materialin gaseous waste samples are j
tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD 1
other detection limits can be found in HASL Procedures Manual, HASL-300 (revised i
Currie, L.A., " Limits for Qualitative Detection and Quantitative Determination - Applicatio Radiochemistry," Anal. Chem. 40. 586-93 (1968), and Hartwell, J.K., " Detection Limits for l
Radioanalytical Counting Techniques", Atlantic Richfield Hanford Company Report ARH-
{:*
_ 2.15 (June 1975).
4 i
1 b
i i
j l
i i
I i
1-i J
I 3-l a
16.11-21 08/01/94 J
d.
n vv v
-a
_ ~ -. - -. - _ -.
TABLE 161 4 (Pah 1 of 4)
RADIOACTIVE GASEOUS WASTL
.MPLING AND ANALYSIS PROGRAM MINIM 5'"
LOWER LIMIT OF SAMPLING ANAlim.
TYPE OF GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS DETECTION (LLD)(1) l (pCi/ml)
P P
1.
Waste Gas Storage Each Tank Each Tank Principal Gamma Emitters (2) 1x10-4 Tank Grab Sample i
P P
2.
Containment Purge Each PURGE (3)
Each PURGE (3)
Principlai Gamma Emitters (2)
Grab Sample 1x104 M
H-3 (oxide) 1x104 3.
Unit Vent W(3)(4) w(3)
Grab Sample Principal Gamma Emitters (2) 1x10-4 H-3 (oxide) 1x10-6 4.
Containment Air D(3) (5) g(3)(5)
Release and principal Gamma Emitters (2) 1x104 Addition System Grab Sample M
All Release Types Continuous (6)
D(7) as listed in 3 1-131 above.
Charcoal 1x10-11 Sample 1-133 1x10-9 Continuous (6) g(7)
Principal Gamma Emitters (2) 1x10-10 Particulate Sample Continuous (6)
M Gross Alpha (8)
Composite 1x10-11 Particulate Sample Continuous (6)
O Sr-89, Sr-90 Composite 1x10-11 Particulate Sample
- 16. I I-22 08/01/94
I TABLE 16.11-4 (Page 2 of 4)
RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT OF SAMPLING ANALYSIS TYPE OF DETECTION (LLD)(1)'
GASEOUS RELEASE TYPE FREQUENCY FREQUENCY ACTIVITY ANALYSIS (pCi/ml) 6.
Waste Monitor W
W Principal Gamrna Emitters (2) 1x194 Tank Building Grab Sample Ventilation Exhaust H-3 (oxide) 1x10-6 Continuous (6)
Sample 1-133 1x10-9 Continuous (6)
W Principal Gamma Emitters (2) 1x10-10 Particulate Sample Continuous (6)
M Gross Alpha 1x10-11 Composite Particulate Sample Continuous (6)
O Sr-89, Sr-90 1x10-11 Composite Particulate Sample 16Il-23 08A)I/94
~.
i 1
1 TABLE 16.11-4 (Page 3 of 4)
TABLE NOTATIONS a
i (1)
The LLD is defined, for purposes of these commitments, as the smallest concentra of radioactive material in a sample that will yield a net count, above system bac 3
that will be detected with 95% probability with only '
j probability of falsely concluding that a blank observation represents a "real" signal.
i For a particular measurement system, which may include radiochemical separat' i
4.66 s
{
LLD = E V
2.22 x 106. y.
exp (-AAt)
.b
~
Where:
).
j LLD = the "a priori" lower limit of detection (microcurie per unit mass or vo i-
' sb'= the standard deviation of the background counting rate or of the coun rate of a blank sample as appropriate (counts per minute);
i
{'
E = the counting efficiency (counts per disintegration);'
t i
V = the sample size (units of mass or volume);
6 i
2.22 x 10 = the number of disintegrations per minute per microcurie; Y = the fractional radiochemical yield, when applicable; j
A = the radioactive decay constant for the particular radionuclide (sec-1); an 4
e t
At = the elapsed time between midpoint of sample collection and time of co (sec).
1 Typical values of E. V, Y and At shall be used in the calculation.
i it should be recognized that the LLD is defined as an A 2dgd (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after i
the fact) limit for a particular measurement.
1 4
i I
i 16.I1-24 08/01/94 3
i et-e-
c w
r:
W--
e-r1wh
- r w
W*
i TABLE 16.11-4 (Page 4 of 4) 1 TABLE NOTATIONS (Continued) 4 I
(2)
The principal gamma emitters for which the LLD specification app following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-13 i
gas releases and Mn-54, Fe-59, Co-58, Co-60,2n-65, Mo-99,1-131 t
e and Ce-141 in lodine and particulate releases. The LLD for Co-144 is 5 j
This list does not mean that only these nuclides are to be cons Ci/mL peaks that are identifiable, together with those of the above nuclides ma analyzed and reported in the Annual Radioactive Effluent Release i
Technical Specification 6.9.1.7, in the format outlined in Regulatory j'
Appendix B, Revision 1, June 1974.
(3)
Sampling and analysis shall also be performed following shutd
{.
THERMAL POWER stabilization power level constant at desired
(
THERMAL POWER change exce(eding 15% of RATED j-i hour period, for at least one of the three gaseous release types with i
i (4)
Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> t
I is flooded.
}
(5)
Required sampling and analysis frequency during effluent relea t
u.
(6)
The ratio of the sample flovir volume to the sampled stream flow v for the time period covered by each dose or dose rate calculation m j
wn with SLCs 16.11-6,16.11-8, and 16.11-9.
ance 1
(7) within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal fro j
i (8) to ensure that at least four filters are analyzed per
{
eek i
I i
i l
l s
i 16.11-25 1
08/01/94 4
16.11 RADIOLOGICAL EFFLUENTS CONTROLS INSTRUMENTATION 16.11-7 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENT
)
COMMITMENT I
The radioactive gaseous effluent monitoring instrumentation channels shown in Table shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of S are not exceeded. The Alarm / Trip Setpoints of these channels meeting SLC 16.11-6 shall be determined and adjusted in accordance with the methodology and parameters in the OD PPLICABILITY: A' shown in Table 18.11-5.-
s 4
REMEDIAL ACTION:
I With a radioactive gaseous effluent monitoring instrumentation channel a.
Alarm / Trip Setpoint less conservative than required by the above specification, j
immediately suspend the release of radioactive gaseous effluents monitore:
the affected channel, or declare the channel inoperable.
b.
With less than the minimum number of radioactive gaseous effluent monitorin instrumentation channels OPERABLE, take the ACTION shown in Table 16.11-5.;
Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION, or explain in the next Annual Radioactive Effluent Release Report pursuant to Technical Specification 6.9.1.7 why this inopera l
was not corrected within the time specified.
TESTING REQUIREMENTS:
Each radioactive gaseous effluent monitoring instrumentation channel shall be demonst OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CAllBRATION, and ANALOG CHANNEL OPERATIONAL TEST operations at the fre shown in Table 16.11-6.
REFERENCES:
1.
Catawba Offsite Dose Calculation Manual 2.
10 CFR Part 20 BASES:
The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or pote releases of gaseous effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of Gene
- 16. I l-26 08/01/94
i Design Criteria 60,63, and 64 of Appendix A to 10 CFR Part 50. The sen i
gas activity monitor used to show compliance with the gaseous effluent releas of SLC 16.11-8 shall be such that concentrations as low as 1 x 10-6 Ci/cc a i
^
)
i.
I 4
N i
l4 l
1 k
6 2
9 l
I6 Il=17 08/01/94
I TABLE 16.11-5 (Page 1 of 4)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 1.
WASTE GAS HOLDUP SYSTEM a.
Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release (Low Range - EMF-50) 1 per station 1
b.
Effluent System Flow Rate Measuring Device 1 per station 2
2.
CONDENSER EVACUATION SYSTEM 1
NOBLE GAS ACTIVITY MONITOR (LOW 1,2,3,4,#
6 RANGE - EMF-33) 3.
VENT SYSTEM Noble Gas Activity Monitor -
a.
1 (Low Range - EMF-36) 3 b.
todine Sampler'(EMF-37) 1 5
Particulate Sampler (EMF-35) c.
1 5
d.
Flow Rate Monitor 1
2 e.
Sampler Flow Rote Monitor 1
2 16.11-28 08/01/94
TABLE 16.11-5 (Page 2 of 4)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 4.
CONTAINMENT PURGE SYSTEM Noble Gas Activity Monitor-Providing Alarm and Automatic 1
Termination of Release (Low 4
Range - EMF-39) 5.
CONTAINMENT AIR RELEASE AND ADDITION SYSTEM Noble Gas Activity Monitor-1 Providing Alarm (Low 1
Range - EMF-39) 6.
MONITOR TANK BUILDING HVAC Noble Gas Activity Monitor-1 per station a.
Providing Alarm (EMF-58) 3 b.
Monitor Tank Building 1 per station Effluent Flow Rate 2
Measuring Device I6. I 1-29 08/01/94
)
i
_ TABLE 16.11-5 (Page 3 of 4)'
TABLE NOTATIONS i
l a
- At all times except when the isolation valve is closed and locked.
- At all times.
)
- Apply Action 6B in l
Modes 5 and 6 4'
i ACTION STATEMENTS -
4
' ACTION 1 -
j
' With the number of channels OPERABLE less than required the Minim Channels OPERABLE requirement, the contents of the tank (s) may
}
released to the environment for up to 14 days provided that prior to initiating the release either:
l l
j Vent system noble gas activity monitor providing alarm and a.
autom' atic termination of release (Low Range - EMF-36) has at least one channel OPERABLE; or,-
I 3
b.
At least two independent samples of the tank's contents are j
analyzed, and at least two technically qualified members of the facility staff independently verify:
4 1.
The discharge valve lineup; and i
3 2.
The manual portion of the computer input for the release rate j
calculations performed on the computer, or the entire release rate calculations if such calculations are performed manually.
i Otherwise, suspend release of radioactive effluents via this pathway j.
j ACTION 2 -
With the number of channels OPERABLE less than required by the i
Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is j
estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
1 ACTION 3 -
With the number of channels OPERABLE less than required by the I
Minimum Channels OPERABLE requirement, effluent releases via this i
pathway may continue for up to 30 days provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 4 -
j With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend 4
PURGING of radioactive effluents via this pathway.
i I
16.11-30 08/01/94-i l'
i
~
1 TABLE 16.11-5 (Page 4 of 4)
TABLE NOTATIONS i
ACTION 5 -
With the number of channels OPERABLE less than required by the i
Minimum Channels OPERABLE requirement, effluent releases via the i
affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 16.11-4.
1 ACTION 6 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement:
A.
Effluent release via the CSAE System (ZJ) may continue for up to
{
30 days provided grab samples are taken at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed for radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and 1
B.
Gaseous effluent releases via the BB system atmospheric vent valve (BB27) in the off normal mode may continue for up to 30 days 3
provided grab samples of steam generatoriuater are analyzed for radioactivity at a lower limit of detection of no more than 1E-7 microCurielml:
2 1
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01: microcurie / gram DOSE EQUIVALENT l-131, or b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microCuriel gram DOSE EQUlVALENT l-131.
4 16.I1-31 08/0I/94 y
TABLE 16.11-6 (Page 1 of 3)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVElLLANCE RE ANALOG MODES FOR CHANNEL WHICH CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE i
INSTRUMENT CHECK CHECK CALIBRATION TEST
- IS REQUIRED 1.
Waste Gas Holdup System a.
Noble Gas Activity Monitor-Providing Alarm and Automatic Termination of Release (Low Range - EMF-50)
P P(4)
R(3)
Q(1) b.
Effluent System Flow Rate Measuring Device P
N.A.
R N.A.
2.
Condenser Evacuation System Noble Gas Activity Monitor (Low Range - EMF-33)
D M(4)
R(3)
O(1) 1,2,3,4 3.
Vent System a.
Noble Gas Activity Monitor t
(Low Range - EMF-36) -
D M(4)
R(3)
Q(2) b.
lodine Sampler (EMF-37)
W N.A.
N.A.
N.A.
c.
Particulate Sampler (EMF-35)
W N.A.
N.A.
N.A.
d.
Flow Rate Monitor D
N.A.
R N.A.
e.
Sampler Flow Rate Monitor D
N.A.
R N.A.
16.1I-32 08/0I/94 m
.__.._._._____._..w_..
~;
TABLE 16.11-6 (Page 2 of 3)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS i
ANALOG MODES FOR I
CHANNEL WHICH '
i CHANNEL SOURCE CHANNEL OPERATIONAL SURVElLLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED 4.
Containment Purge System Noble Gas Activity Monitor-Providing Alarm and Automatic Termmation of Release (Low Range - EMF-39)
D P(4)
R(3)
Q(1) 5.
Containment Air Release and Addition System Noble Gas Activity Monitor-Providing Alarm (Low Range - EMF-39)
D P(4)
R(3)
Q(1) 6.
Monitor Tank Building HVAC a.
Noble Gas Activity Monitor-i Providing Alarm (EMF-58)
D M
R(3)
Q(2) b.
Discharge Flow Instrumentation D
N.A.
R N.A.
16.11-33 08/01/94
.-m 1
m-w-
- v v
vw-e w"
w s
we
i i
TABLE 16.11-6 (Page 3 of 3) 1 TABLE NOTATIONS l
At all times except when the isolation valve is closed and locked.
At all times.'
i
~
1.
isolation of this pathway and control room alarm j
following conditions exists:
Instrument indicates measured levels above the Alarm / Trip Setpoint; o a.
E b.
Circuit failure (Alarm only); or, i
Instrument indicates a downscale failure (Alarm only).
c.
2.
The ANALOG CHANNEL OPERATIONAL TEST shall als i
room alarm annunciation # occurs if any of the following conditipns exists:
! :4 a.
Instrument indicates measured levels above the Alarm Setpoint; or, b.
Circuit failure; or, 1
)
Instrument indicates a downscale failure.
c.
3.
The initial CHANNEL CALIBRATION shall be performed using one or m reference standards certified by the National Bureau of Standards (
i standards that have been obtained from suppliers that participate in mea assurance activities with NBS. These standards shall permit calibrating th l
CAllBRATION, sources that have been related to
'l i
4.
A source check for these channels shall be the qualitative assersment o resporise when the channel sensor is exposed to a light emittirig diode.
1 j
i
- For EMF-58, the alarm annunciation is in the Monitor Tank Building Co MTB Control Panel Remote Annunciator Panel.
e 1
i 16.Il 34 i-08/01/94 4
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I N
16.11 RADIOLOGICAL EFFLUENT CONTROLS i
RADIOACTIVE EFFLUENTS 4
16.11-8 DOSE - NOBi E GASES COMMITMENT 1
The air dose due to noble gases released in gaseous effluents, from each unit, to beyond the SITE BOUNDARY (see Figure 16.11-1) shall be limited to the followin i
l a.
i During any calendar quarter: Less than or equal to 5 mrads for gamma radiatio 3
and less than or equal to 10 mrad for beta radiation; and, i
b; l
During any calendar year Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
i j
APPLICABILITY: At all times.
1 d
REMEDIAL ACTION:
a
'1 :*
of the above limits prepare and submit to the Commiss i
i Technical Specification 6.9.2, a Special Report that identifies the cause(s) for j
limit (s) and defines the corrective actions that have been taken t proposed corrective actions to be taken to assure that subsequent releases will be in j
compliance with the P.bove limits.
TESTING REQUIREMENTS:
4 I
Cumulative dose contributions for the current calendar quarter and current cale noble gases shall be determined in accordance with the methodology and parameter ODCM at least once per 31 days.
\\
l
REFERENCES:
i 1.
Catawba Offsite Dose Calculation Manual 2.
10 CFR Part 50, Appendix i BASES:
This commitment is provided to implement the requirements of Sections 11.B, lil.A'a i
Appendix 1,10 CFR Part 50. The Limiting Condition for Operation implements the g
{
forth in Section ll.B of Appendix 1. The REMEDIAL ACTION statement provides}
operating flexibility and at the same time implement the guides set forth in Section IV.A o Appendix i to assure that the releases of radioactive material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable" The Requirements implement the requirements in Section Ill. A of Appendix I that confo the guides of Appendix ! be shown by calculational procedures based on models and i
16.I1 35 1
08/01/94
k t
i BASES: (cont'd) unlikely to be substantially underestimated. The i
i of radioactive noble gases in gaseous effluents a j
~
in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from i-Revision 1, October 1977 and Regulatory Guid Transport and Dispersion of Gaseous Effluents in Routine Releases Reactors," Revision 1, July 1977. The ODCM equations provided for at and beyond the SITE BOUNDARY are based upon the historical aver conditions.
i
~
" This commitment applies to the release of radioactive materials in gas j
unit at the site. When shared Radwaste Treatment Systems are used ach j
releases cannot accurately be ascribed to a spec
' contributions from each unit based on input conditions, e.g., flow rate i
concentrations, or, if not practicable, the treated effluent releases may 3
each of the radioactives waste producing units sharing the Radwaste T i
determining conformance to commitments, these allocations from share Systems are to be added to the releases specifically attributed to eac ment i
releases per unit.
b 1
b i
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l i
3 I
I i
i' l
a.
1 16.11-36 i
08/01/94 i
i 16.11 RADIOLOGICAL EFFLUENT CONTROLS RADIOACTIVE EFFLUENTS
[
i 16.11 9 DOSE - IODINE-131, IODINE-133, TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM 4
j COMMITMENT The dose to a MEMBER OF THE PUBLIC from lodine-131, lodine-133, tritium, and all I
radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see Figu shall be limited to the following:
}
During any calendar quarter: Less than or equal to 7.5 mrem to any organ; and.
a.
4 b.
During any calendar year: Less than or equal to 15 mrem to any organ.
l APPLICABILITY: At alltimes.
REMEDIAL ACTION:
With the calculated dose from the release of lodine-131, lodine-133, tritium, and radionu i
in particulate form with half-lives greater than 8 days, in gaseous effluents excee the above limits, prepare and submit to the Commission within 30 days, pursuant to Techn Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit a 3
I defines the corrective actions that have been taken to reduce the releases and the j
corrective actions to be taken to assure that subsequent releases will be in compliance wit the above limits.
TESTING REQUIREMENTS:
Cumulative dose contributions for the current calendar quarter and current calendar i
lodine-131, lodine-133, tritium and radionuclides in particulate form with half-lives gr
]
8 days shall be determined in accordance with the methodology and parameters in the at least once per 31 days.
4 i
REFERENCES:
{
l 1.
Catawba Offsite Dose Cajuation Manual 2.
10 CFR Part 50, Appendix i BASES:
This commitment is provided to implement the requirements of Sections ll.C, Ill.A and IV.
(
Appendix 1,10 CFR Part 50, and are the guides set forth in Section ll.C of Appendix 1. Th REMEDIAL ACTION statements provide the required operating flexibility and at the same implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low a
16.I1 37 4
08/01/94 4
1
a.-
u...
w s
s a.-
.m.
.-g
.n l
j BASES: -(cont'd) i is reasoncbly achievable". The ODCM calculational methods specified in the Surveillance l
Requirements implement the requirements in Section Ill.A of Appendix I that conformance with -
i-the guider of Appendix l be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is
.i unlikely to be substantially underestimated. The ODCM calculational methodology and,
4 parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of '
~
Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with.10 CFR Part 50, Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.111 " Methods for Estimating Atmospheric Transport and Dispersion of-i Gaseous Effluents in Routine Releases from Ught-Water-Cooled Reactors," Revision 1, ' July 1
1977. These equations also provide for determining the actual doses based upon the i
historical average atmospheric conditions. The release rate commitments for lodine-131, j
lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are i
dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of the calculations s
i (1)individualinhalation of airbome radionuclides, (2) deposition of radionuclides onto were:
green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas
~
where milk animals and meat-producing animals graze with consumption of the milk and meat 3*
l by man, and (4) deposition on the ground with subsequent exposure of man.
This commitment applies to the release of radioactive materials in gaseous effluents from each unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the i
contributions from each unit based on input conditions, e.g., flow rates and radioactivity concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For determining conformance to commitments, these allocations from shared Radwaste Treatment 4
Systems are to be added to the releases specifically attributed to each unit to obtain the total 4
releases per unit.
i 16.1I-38 08/o1/94 7
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1 i
i 16.11 RADIOLOGICAL EFFLUENT CONTROLS l
i 1
RADIOACTIVE EFFLUENTS i
i 16.11-10 GASEOUS RADWASTE TREATMENT SYSTEM l
i COMMITMENT i
i The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to j
reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent i
releases, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure 16.11-1) l would exceed either-i i
a.
0.2 mrad to air from gamma radiation; or, j
b.
0.4 mrad to air from beta radiation; or, i
c.
0.3 mrom to any organ of a MEMBER OF THE PUBLIC.
)
APPLICABILITY: At all times.
+
[
REMEDIAL ACTION:
']
With radioactive gaseous waste being discharged without treatment and in excess of the i
above limits, prepare and submit to the Commission within 30 days, pursuant to Technical j
Specification 6.9.2, a Special Report that includes the following information:
1.
Identification of any inoperable equipment or subsystems, and the reason for the inoperability; i
2.
Action (s) taken to restore the inoperable equipment to OPERABLE status; and, l
3.
Summary description of action (s) taken to prevent a recurrence.
l TESTING REQUIREMENTS:
i Doses due to gaseous releases from each unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and
}
parameters in the ODCM when Gaseous Radwaste Treatment Systems are not being fully utilized.
The installed VENTILATION EXHAUST TREATMENT SYSTEM and WASTE GAS HOLDUP SYSTEM shall be considered OPERABLE by meeting SLCs 16.11-6,16.11-8, or 16.11-9.
i
REFERENCES:
i 1.
Catawba Offsite Dose Calculation Manual 2.
10 CFR Part 50, Appendix i J
- 16. I l-39 08/01/94
.m.-
-~.
~.
BASES:
The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EX TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous i
effluents require treatment prior to release to the environment. The requirement that the
]
appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low l
as is reasonably achievable". This commitment implements the requirements of 10 CFR -
j 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and the design i
objectives given in Section ll.D of Appendix l to 10 CFR Part 50. The specified limits goveming the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections ll.B and ll.C of Appendix 1,10 CFR Part 50,
{
for gaseous effluents.
i
~
This commitment applies to the release of radioactive materials in gaseous effluents from each j
unit at the site. When shared Radwaste Treatment Systems are used by more than one unit on a site, the wastes from all units are mixed for shared treatment; by such mixing, the effluent releases cannot accurately be ascribed to a specific unit. An estimate should be made of the contributions from each unit based on input conditions, e.g., flow rates and radioactivity i
i concentrations, or, if not practicable, the treated effluent releases may be allocated equally to each of the radioactive waste producing units sharing the Radwaste Treatment System. For g
i determining conformance to commitments, these allocations from shared Radwaste Treatment Systems'are to be added to the releases specifically attributed to each unit to obtain the total j
, releases per unit.
i' i
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t i
i i
i
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16.I1 40 08/01/94 3~
i J
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16.11 RADIOLOGICAL EFFLUENT CONTROLS RADIOACTIVE EFFLUENTS i
16.11-11 SOLID RADIOACTIVE 'NASTES
)
COMMITMENT Radioactive wastes shall be solidified or dewatered in accordance with the PRO CONTROL PROGRAM to meet shipping and transportation requirements during transit, and
)
disposal site requirements when received at the disposal site.
1 APPLICABILITY: At all times.
i REMEDIAL ACTION:
i With SOLIDIFICATION or dewatering not meeting disposal site and shipping and a.
i transportation requirements, suspend shipment of the inadequately processed 2
wastes and correct the PROCESS CONTROL PROGRAM, the procedures -
and/or the Solid Radwaste System as necessary to prevent recurrence.
{
I' b.
With SOLIDIFICATION or dewatering not performed in accordance with the PROCESS CONTROL PROGRAM, test the improperly processed waste in each container to ensure that it meets burial ground and shipping requirements and a
take appropriate administrative action to prevent recurrence, j
SURVEILLANCE REQUIREMENTS:
SOLIDIFICATION of at least one representative test specimen from at least every tenth ba l
of each type of wet radioactive wastes (e.g., filter sludges, spent resins, evaporator botto boric acid solutions and sodium sulfate solutions) shall be verified in accordan PROCESS CONTROL PROGRAM:
1 a.
j If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION of the l
batch under test shall be suspended until such time as additional test specimens can be obtained, altemative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. SOLIDIFICATION of the batch may then be resumed using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM; 1
b.
If the initial test specimen from a batch of waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test specimens from each consecutive batch of the same type a
of wet waste until at least three consecutive initial test specimens demonstrate SOLIDIFICATION. The PROCESS CONTROL PROGRAM shall be modif required, as provided in Technical Specification 6.13, to assure SOLIDIFICA-TION of t,ubsequent batches of waste; and, t
4 16.1i-41 08/01/94 2
With the installed equipment incapable of meeting SLC 16.11-11 or declare c.
inoperable, restore the equipment to OPERABLE status or provide for con capability to process wastes as necessary to satisfy all applicable transport and disposal requirements.
REFERENCES:
1.
Catawba Offsite Dose Calculation Manual 2.
10 CFR Part 50 BASES:
t This commitment implements the requirements of 10 CFR 50.36a and Gene Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters includ l
ing the PROCESS CONTROL PROGRAM may include but are not limited t waste pH, waste / liquid / SOLIDIFICATION agent / catalyst ratios, waste oil content, w o waste type, principal chemical constituents, and mixing and curing times.
4 :4 i
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1 1
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4 4
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16.11-42 08/01/94 4
i J
16.11 RADIOLOGICAL EFFLUENT CONTROLS 4
RADIOACTIVE EFFLUENTS i
16.11-12 TOTAL DOSE l
}
COMMITMENT to releases of radioactivity and to radiation from j
due less than or equal to 25 mrem to the whole body or any organ excep ources shall be limited to -
be limited to less than or equal to 75 mrom.
e yrold, which shall
)
APPLICABILITY: At alltimes.
. REMEDIAL ACTION:
With the calculated doses from the release of radioactive mate 3
j or 16.11-9b, calculations shall be made includ seous i
1
- a,
- and from outside storage tanks to determine whether the abov j
e units been exceeded. If such is the case, prepare and submit to the Comniis
!u ave be taken to reduce subsequent releases to prevent on within 30 days,
)
c ve action to Report, as defined in 10 CFR 20.405c, shalt inc i
ng the above limits ecial effluent pathways and direct radiation, for the ca
{
es the radiation f,
, ncluding all covered by this report. It shall also describe levels of radiation and c ase(s) active materialinvolved, and the cause of the exposure levels or c j
radio-estimated dose (s) exceeds the above limits, and if the release e
40 CFR Part 190 has not already been corrected, the Special Report v o a on of for a variance in accordance with the provisions of 40 CFR Part 190 I
a nclude a request considered a timely request, and a variance is granted until sta
.. u m ta of the reportis complete.
uest is 1
TESTING REQUIREMENTS:
i Cumulative dose contributions from liquid and gaseous effluents shal accordance with SLCs j
and parameters in the ODCM.16.11-3,16.11-8 and 16.11-9, and in accordanc rmined in e o o ogy k
tanks shall be determined in accordance with the i
waste storage This requirement is applicable only under conditions set forth in t rameters in the ODCM.
commitment.
ION of this i
t 16.11-43 08/01/94 I
i l
REFERENCES:
1 1.
Catawba Offsite Dose Calculation Manual i
2.
10 CFR Pan 20 i
3.
40 CFR Part 190 I
j BASES:
l i
This commitment is provided to meet the dose limitations of 40 CFR Part 190 that have been I
t incorporated into 10 CFR Part 20 by 46 FR 18525. The commitment requires the preparation i
and submittal of a Special Report whenever the calculated doses due to releases of radio-l activity and to radiation from uranium fuel cycle sources exceed 25 mrom to the whole body.or j
any organ, except the thyroid, which shall be limited to less than or equal to 75 mrom.
4 i.
For sites containing up to four reactors, it is highly unlikely that the resultant dose to a i
MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the ind 1
reactors remain within twice the dose design objectives of Appendix 1, and if direct radiation doses from the units and from outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to OF THE PUBLIC to within the 40 CFR Part 190 limits.' For the purposes of the Special Repor j*
it may be assumed that the dose commitment to the MEMBER OF THE PUBLIC from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other
{
nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If
{
the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 j
CFR Part 190, the Special Report with a request for a variance (provided the release -
i conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in
}
accordance with the provisions of 40 CFR 190,11 and 10 CFR 20.2203(a)(4), is considered to j
be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is l
completed. The variance only relates to the limits of 40 CFR Past 190, and does not apply in i
}
any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in SLC 16.11-1 and 16.11-6. An individualis not considered a MEMBER OF THE PUBLIC during any l
period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
i 1
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i l
i i
l 1
16.11-44 i
08/01/94 i
I i
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i i'
16.11 RADIOLOGICAL EFFLUENT CONTROLS k
RADIOLOGICAL ENVIRONMENTAL MONITORING 16.11-13 MONITORING PROGRAM
{
COMMITMENT
'l The Radiological Environmental Monitoring Program shall be conducted a j
16.11-7.-
i'
- APPLICABILITY: At all times..
1 j
REMEDIAL ACTION:
i 3
a.
- With the Radiological Environmental Monitoring Program not being con specified in Table 16.11-7, prepare and submit to the Commission, in the A Radiological Environmental Operating Repon required by Technical S 3
6.9.1.6, a description of the reaso'ns for not conducting the program a I
and the plans for preventing a recurrence.
I b.
With the level of radioactivity as the result of plant effluents in an environ
~:4 sampling medium at a specified locaton exceeding the reporting levels of Tai
}
16.11-7 when averaged over any calendar quarter, prepare and submit to t Commission within 30 days, pursuant to Technical Specification 6.9
^
Report that identifies the cause(s) for exceeding the limit (s) and defines th j
corrective actions to be taken to reduce radioactive effluents so that the p I
annual dose
- to a MEMBER OF THE PUBLIC is less than the calendar limits of SLC 16.11-3,16.11-8, and 16.11-9. When more than one of the radio-nuclides in Table 16.11-7 are detected in the sampling medium, this rep l
j be submitted if:
I
}
concentration (1)
_concank.en (2) i reporting level (1) reporting level (2) + 41.0
+
t When radionuclides other than those in Table 16.11-7 are j
result of plant effluents, this report shall be submitted if the potential annual i
dose
- to A MEMBER OF THE PUBLIC from all radionuclides is equal to o greater than the calendar year limits of SLC 16.11-3,16.11-8 and 16.119. This i
report is not required if the measured level of radioactivity was not the result oi i
}
plant effluents; however, in such an event, the condition shall be reported described in the Annual Radiological Environmental Operating Report r
{
by Technical Specification 6.9.1.6.
l 4
l l
l t
- The methodology and parameters used to estimate the j
OF THE PUBLIC shall be indicated in this report.
potential annual dose to a MEMBER f
i
- 16. I l-45 5
08/0I/94 i
a i
REMEDIAL ACTION: (cont'd) i c.
With milk or fresh leafy vegetation samples unavailable from one or more of the sample locations required by Table 16.11-7, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiologica Environmental Monitoring Program given in the ODCM. The specific locations i
from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Technical Specification 6.14, submit in the next Annual j-Radioactive Effluent Release Report documentation for a change in the ODCM i
including a revised figure (s) and table for the ODCM reflecting the new i
location (s) with supporting information identifying the cause of the unavailabilit of samples and justifying the selection of the new location (s) for obtaining samples.
i TESTING REQUIREMENTS:
[
The radiological environmental monitoring samples shall be collected pursuant to Table 16.11-7 from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 16.11-7 and the detection capabilities requir by Table 16.11-8.
REFERENCES:
1.
Catawba Offsite Dose Calculation Manual i
2.
10 CFR Part 50 Appendix l i
BASES:
i The Radiological Environmental Monitoring Program required by this commitment provid representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures o MEMBERS OF THE PUBLIC resutt5g from the plant operation. This monitoring program implementsSection IV.B.2 of Appendix 1 to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Prugram by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the affluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation. Following this peiou, program changes may be initiated based on operational experience.
The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LL.Ds required by Table 16.11-8 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a pnigs (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a
)
{
particular measurement.
i
- 16. I l-46 08/01/94 n--
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es
BASES: (cont'd) t Detailed discussion of the LLD, and other detection limits, can be found in HASL Pro t
Manual, HASL-300 (revised annually), Currie, L.A., " Limits for Qualitative Detection and j
Quantitative Determination - Application to Radiochemistry," Anal. Chem. 40. 5 t
and Hartwell, J. K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic j
i.
Richfield Hanford Company Report ARH-SA-215 (June 1975).
l l
1 l
t j
k i
i j
i 1
4
'l
- 16. I l-47 08/01/94
2 TABLE 16.11-7 (Page 1 of 8)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF t
REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS (1)
COLLECTION FREQUENCY OF ANALYSIS 1.
Direct Radiation (2)
Forty routine monitoring stations Quarterly.
eether with two or more dosimeters Gamma dose quarterly.
or with one instrument for measunng and recording dose rate continuously, placed as follows An inner ring of stations, one in each meteorological sectorin the general area of the SITE BOUNDARY; An outer ring of stations, one in each meteorological sectorin the 6-to 8-km range from the site; and, The balance of the stations to be placed 51 specialinterest areas suut as population centers, nearby residences, schools, and -
in one or two areas to serve as control stations.
!6.11-48 on/uin4
i' TABLE 16.11-7 (Page 2 of 8)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF e
REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND AND/OR SAMPLE SAMPLE LOCATIONS (1)
SAMPLING AND TYPE AND FREQUENCY COLLECTION FREQUENCY OF ANALYSIS 2.
Airbome Radioiodine and Samples from five locations.
Continuous sampler Radioiodine Cannister Partculates operation with sample 1-131 analysis weekly.
collecbon weekly, or more frequently Three samples from close if required by dust to the three SITE BOUNDARY loading locations, in different sectors, Particulate Sampler of the highest calculated Gross beta radio-annual average ground-activity analysis level D/Q;'
follomng filter change;(3)and One sample from the gamma isotopic vicinity of a community analysis (4) of having the highest calculated composite (by annual average ground-level location) quarterly.
D/Q; and One sample from a control location, as for example 15 to 30 km distant and in the least prevalent wind direction.
- 16. I l-49 0K/0I/94
i TABLE 16.11-7 (Page 3 of 8)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF EXPOSURE PATHWAY REPRESENTATIVE i
AND/OR SAMPLE SAMPLES AND SAMPLE LOCATIONS (1)
SAMPLING AND COLLECTION FREQUENCY TYPE AND FREQUENCY i
3.
Waterbome OF ANALYSIS a.
Surface (5)
One sample upstream.
One sample downstream.
Composite sample over 1-month penod. (6)
Gamma isotopic analysis (4) monthly.
Composite for tritium b.
Ground Samples from one or two analysis quarterly.
sources onl Quarterty.'
affected(7) yif hkely to be Gamma isotopic (4) and tritium analysis quarterly.
c.
Drinking One sample of each of one Composite sa to three of the nearest water 2-week penodp( )
I-131 analysis on each over supplees that could be affected by its discharge.
when 1-131 analysis is composite when the dose performed; monthly calculated for the con-One sample from a control composite otherwise.
sumption of the wateris location.
greater than 1 mrem per year (8). Composite for gross beta and gamma isotopic analyses (4) monthly. Composite for One sample from downstream tritium ana!ysis quarterly.
d.
Sediment from Shoreline area with existing orpotential Semiannually.
Gamma isotopic rec'eational value.
analysis (4) semiannually.
- 16. I l-50 O&Ul/94
_.__m_.
'i TABLE 16.11-7 (Page 4 of 8)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE -
EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY i
AND/OR SAMPLE SAMPLE LOCATIONS (1)
COLLECTION FREQUENCY OF ANALYSIS 4.
Ingestion a.
Milk Samples from mellung anwnals Sememonthly when Gamma isotopic (4) and in three locations withen 5 km anomals are on pasture; l-131 analysis semi-distance having the highest monthly at other times.
dose potenbal if there are monthly when animals none, then one sample from are on pasture; monthly mellung ammals in each of at other times.
three areas between 5 to 8 km distant where doses are calculated to be greater than 1 mrem per year.L8) One sample from milking ammals at a controllocahon 15 to 30 km distant and in the least prevalent wind drection b.
Fish and One sample each of a Sample in season, or Gamma isotopic invertebrates predatory species, a bottom semsannually if they are analysis (4) on edible feeder and a forage speces -
not seasonal.
~
in vicmety of plant discharge portions.
area.
One sample cach of a predatory species, a bottom feeder and a forage specses in areas not influenced by plant discharge.
16.11-51 ousim
TABLE 16.11-7 (Page 5 of 8)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM NUMBER OF REPRESENTATIVE EXPOSURE PATHWAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY AND/OR SAMPLE SAMPLE LOCATIONS (1)
COLLECTION FREQUENCY OF ANALYSIS 4.
Ingestion (Continued) c.
Food One sample of each pnncipal At time of harvest (S).
Gamma isotopic Products class of food products from analyses (4) on edible any area that is imgated by portion waterin which isqued plant wastes have been discharged Samples of three different Monthly, when available.
kinds of broad leaf vegetation Gamma isotopic (4) and 1-131 analysis.
grown nearest each of two different offsite locatsons of highest predicted annual average ground level D/Q if milk sampimg is not perforined One sample of each of the Monthly, when available similar broad leaf vegetation Gamma isotopic (4) and grown 15 to 30 km distant 1-131 analysis.
in the least prevalent wind direction if milk sampieng is not performed 16.11-52 0x/01/9-8
3, ;
- TABLE 16.11-7 (Page 6 of 8) t
,I J
TABLE NOTATIONS
' 1.
Specific parameters of distance and direction sector from the centerlin j
location in Table 16.11-7 in a table and figure (s i
" Preparation of Radiological Effluent Technical Specifications for Nucle October 1978, and to Radiological Assessment Branch Technical Posit j
November 1979. Deviations are permitted from the required sampling sc j
specimens are unobtainable due to circumstances such as hazardous co
{
seasonal unavailability, and malfunction of automatic sampling equipment. I
{
j are unobtainable due to sampling equipment malfunction, effort shall be made to complete corrective action prior to the end of the next sampling period. All de from the sampling schedule shall be documented in the Annual Radiolog
{
Environmental Operating Report pursuant to Technical Specification 6.9.1.
i recognized that, at times, it may not be possible or pracbcable to continue to o samples of the media of choice at the most desired location or time. In these 3
suitable altemative media and locations may be chosen for the particu i
question and appropriate substitutions made within 30 days in the Radiolog
{
Environmental Monitoring Program. In lieu of any Licensee Event R j
Technical Specification 6.9.1 and pursuant to Technical Specificati j
the cause of the unavailability of samples for that pathway and identify the j
location (s) for obtaining replacement samples in the next Annual Radio Release Report and also include in the report a revised figure (s) and i
reflecting the newlocation(s).
i
{
2.
One or more instruments, such as e pressurized ion chamber, for mea dosimeters. For the purposes of this table, a the i
}
considered to be one phosphor; two or more phosphors in a packet are co i
direct radiation. (The 40 stations is not an absolut i
i at an ocean site, some sectors will be over wa j
be reduced accordingly. The frequency of analysis or readout for TLD sys j
dep?nd upon the characteristics of the specific system used and should j
obta,n optimum dose information within min'imal fading.)
i 3.
Airt>ome particulate sample filters shall be analyzed for gross beta rad or more after sampling to allow for radon and thoron daughter decay. If gross bej i
activity in air particulate samples is greater than 10 times the yearly mean o i
samples, gamma isotopic analysis shall be performed on the individual samp j
4.
radionuclides that may be attributable to the efflue 1
i i
16.11-53 d
08/01/94 I
l 1
J
~
a TABLE 16.11-7 (Page 7 of 8) i TABLE NOTATIONS (Continued) 5.
The " upstream sample" shall be taken at a distance beyon'd significant influence of the discharge. The " downstream" sample shall be taken in an area beyond but near the mixing zone. " Upstream" samples in an estuary must be taken far enough upstream to i
be beyond the plant influence. Salt water shall be sampled only when the receiving water is utilized for recreational activities.
)
6.
A composite sample is one in which the rate at which the liquid sampled is uniform and j
in which the method of sampling employed results in a specimen that is representative of the time averaged concentration at the location being sampled. - In this program composite sample aliquots shall be collected at time intervals that are very short (e.g.,
1 i
hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.
7.
Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.
8.
The dose shall be calculated for the maximum organ and age group, using the methodolpgy and parameters in the ODCM.
9.
If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall be paid to including samples of tuberous and root food products.
I 6
16.I1 54 08/0I/94
. - - ~
I TABLE 1611-7 (Page 8 of 8) i
_ REPORTING LEVELS FOR RADIOACTIVITY CONCENTRA s
_ REPORTING LEVELS WATER i
AIRBORNE PARTICULATE ANALYSIS (pCi/I)
FISH MILK OR GASES (pCi/m*)
(pCi/kg, wet)
(pCill)
(pCi/kg, wet)
FOOD PRODUCTS H-3 20,000(1)
Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2
0.9 3
Cs-134 100 30 10 1,000 60 Cs-137 1,000 50 20 Ba-La-140 2,000 70 2,000 200 300 (1)For drinking water samples. This is 40 CFR Part 141 value If ri used.
o drinkmg water pathway exists, a value of 30,000 pCi/l m 16.11-55 i wien
TABLE 16.11-8 (Page 1 of 3)
DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS (1) (2)
LOWER LIMIT OF DETECTION (LLD)(3)
WATER AIRBORNE PARTICULATE FISH MILK FOOD PRODUCTS SEDIMENT ANALYSIS (pCi/I)
OR GASES (pCi/m*)
(pCilkg, wet)
(pCill)
(pCi/kg, wet)
_ (pCi/kg, dry)
Gross Beta 4
0.01 H-3 2000*
Mn-54 15 130 Fe-59 30 260 t
Co-58, 60 15 130 Zn-65 30 260 Zr-NtF95 15 1-131 1(4) 0.07 1
60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15
- lf no drinking water pathway exists, a value of 3000 pCi/l may be used.
- 16. I l-56 08/oI/94
~
z..
J, 1
TABLE 10.11-8 (Page 2 of 3) -
4 T'ABLE NOTATIONS-i i
{
1.
This list does not mean that only these nuclides are to be considered. Other peak i
]
are identifiable, together with those of the above nuclides, shall also be analyzed an reported in the Annual Radiological Environmental Operating Report pursuant to Technicai Specification 6.9.1.6.
1
{
2.
Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recom Regulatory Guide 4.13.
i 3.
The LLD is defined, for purposes of these commitments, as the smallest concen of radioactive material in a sample that will yield a not count, above system ba j
that will be detected with 95% probability with only 5% probability of falsely co-i that a blank observation represents a "real" signal.
i j
(
For a particular measurement system, which may include radiochemical separat l
i i
4.66 s b
l LLD = E V.
2.22, Y exp (-AAt) '
\\
3' Where:
}
l LLD = the "a pnori"lowerlimit of detection (picoCuries per unit mass or I
volume);
i i
3
{
sb = the standard deviabon of the background counting rate or of the '
counting rate of a blank sample as appropnate (counts per minute); -
4 i;.
E
= the counting efficiency (counts per disintegration);-
5
{
V
= the sample size (units of mass or volume);
t 2.22 = the number of disintegrations per minute per picocurie; i
Y
= the fractional radiochemical yield, when applicable; 4
A
= the radioactive decay constant the particular radionuclide (sec-1); and, At
).
= the elapsed time between environmental collection, or and of the sample collection period, and time of counting (sec).
e Typical values of E, V, Y and at should be used in the calculation.-
I 16.11 57 I
08/01/94
)
m
..-sY
1 4
~
TABLE 16.11-8 (Page 3 of 3) a TABLE NOTATIONS (Continued) 4 t
It should be recognized that the LLD is defined as an a p.ngd (before the fact) limit i
i representing the capability of a measurement system and not as an a posteriori (after 1
the fact) limit for a particular measurement. Analyses shall be performed in such a i
manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the 1sence of interfering i
nuclides, or other uncontrollable circumstances may render bse LLDs unachievable.
i in such cases, the contributing factors shall be identified tru 4senbod in the Annual Radiological Environmental Operating Report pursuant to 's F;nnical Specification i
1 j
6.9.1.6.
i 4.
LLD for drinking water samples. If no drinking water pathny unt's, the LLD of gamma isotopic analysis may be used.
)
l
,} l8 i
i i
f i
i 4
3 i
l i
4 I
4 i
i
- 16. I l-58 08/01/94 1
i i
1, i,- -,.,---
y y
e.ay-t ry emv
i-3 -
l;.
16.11 RADIOLOGICAL EFFLUENT CONTROLS j
~
i RADIOLOGICAL ENVIRONMENTAL MONITORING i
j 16.11-14 LAND USE CENSUS COMMITMENT j
j A Land Use Census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the noterest milk animal, the nearest j
residence, and the nearest garden
- of greater than 50 m2 (500 ft') producing broad leaf j
vegetation.
1 i
j APPLICABILITY: At all times.
1 REMEDIAL ACTION:
a.
With a Land Use Census ic antifying a location (s) that yields a calculated dose or i
dose commitment greater tiian the values currently being calculated in SLC 16.11-9, identify the new loc oon(s) in the next Annual Radioactive Effluent Release Report pursuant to Technical Specification 6.9.1.7.
9l:e b.
With a Land Use Census identifying a location (s) that yields a calculated dose or l
dose commitment (via the same exposure pathway) 20% greater than at a loca-j tion from which samples are currently being obtained in accordance with SLC 4
16.11-13, add the new location (s) within 30 days to the radiological Environ-i mental Monitoring Program given in the ODCM. The sampling location (s),
i excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the yearin which this Land Use Census was conducted. Pursuant to Technical Specification 6.14, submit in the next t
j Annual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) and table (s) for the ODCM reflecting the new l
location (s), with information supporting the change in the sampling locations.
j TESTING REQUIREMENTS:
t The Land Use Census shall be conducted during the growing season at least once per 12 l
months using that information that will provide the best results, such as by a door-to-door i
survey, serial survey, or by consulting local agriculture authorities. The results of the Land Use j
j Census shall be included in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.6.
- Broad leaf vegetation sampling of at least three'different kinds of vegetation may be -
performed at the SITE BOUNDARY in each of two different direction sectors with the highest 9
predicted D/Qs in lieu of the garden census. Commitments for broad leaf vegetation sampling in Table 16.11-7.4.c shall be followed, including analysis of control samples.
- 16. I l-59 08/01/94
+
i l
i REFERENCEiS:
i i
1.
Catawba Offsite Dose Calculation Manual 2.
10 CFR Part 50, Appendix l 3
BASES:
)
i This commitment is provided to ensure that changes in the use of areas at and beyond the l
SITE BOUNDARY are identified and that mocdications to the Radiological Environmental 4
Monitoring Progam given in the ODCM are made if required by the results of this census. The l
best information from the door-to-door surv3y, from serial survey or from consulting with local i
agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix l to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m8 i
I provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantify (26 I
kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child.-
To detemine this minimum garden size, the following assumptions were made: (1) 20% of the
]
garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and j
(2) a vegetation yield of 2 kg/m8 i
e0
)
i i
)
a i
e i
l 4
I 4
+
16.11-60 08/01/94
+
...-..m-.
i
)
16.11 RADIOLOGICAL EFFLUENT CONTROLS I
j RADIOLOGICAL ENVIRONMENTAL MONITORING 16.11-15 INTERLABORATORY COMPARISON PROGRAM i
i COMMITMENT l
1 j
Analyses shall be performed on all radioactive materials, supplied as part of an Interlaboratory
~
Comparison Program that has been approved by the Commission, that correspond to samples j
required by Table 16.11-7.
j APPLICABILITY: ' At all times.
j REMEDIAL ACTION:
)
j With analyses not being performed as required above, report the corrective actions taken to i
prevent a recurrence to the Commission in the Annual Radiological Environmental Operating l
Report pursuant to Technical Specification 6.9.1.6.
l TESTING REQUIREMENTS The Intertaboratory Comparison Program shall be described in the bDCM. A summary of the 1
results obtained as part of the above required Intertaboratory Comparison Program shall be j
included in the Annual Radiological Environmental Operating Report pursuant to Technical
{
Specification 6.9.1.6.
i
REFERENCES:
1.
Catawba Offsite Dose Calculation Manual 2.
10 CFR Part 50, Appendix l l
BASES 9
i i
The requirement for particip:stion in an approved Interiaboratory Comparsion Progreen is provided to ensure that independent checks on the precision and accuracy of the measure-monts of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix l to 10 CFR Part 50.
[
l l
i r
I 9
- 16. I l-61 08/01/94 i
i
i 16.11 RADIOLOGICAL EFFLUENT CONTROLS REPORTS I
)
16.11-16 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT AND i
{
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i
j COMMITMENT i
j 16.11-16.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- i:
Routine Annual Radiological Environmental Operating Reports covering the operation of the i
unit during the previous calendar year shall be submitted prior to May 1 of each year.
i The Annual Radiological Environmental Operating Reports shall include summaries, j
interpretations,'and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, i
with operational controls as appropriate, and with previous environmental surveillance reports,
{
and an assessment of the observed impacts of the plant operation on the environment. ' The j
reports shall also include the results of the land use census.
The Annual Radiological Environmental Operating Repor*c shallinclude the results of analysis
- j,,
of all radiological environmental samples and of all environmental radiation measurements i
taken during the period pursuant to the locations specified in the Table and Figures in the i
ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with
}
the report, the report shall be submitted noting and explaining the reasons for the missing i
results. The missing data shall be submitted as soon as possible in a supplementary report.
i The reports shall also include the following: a summary description of the Radiological Environmental Monitoring Program; at least two legible maps" covering all sampling locations j
keyed to a table giving distances and directions from the centerline of one reactor; the results of licensee participation in the Inter 1aboratory Comparison Program, required by SLC 16.11 15; discussion of all deviations from the sampling schedule of Table 16.11-7; and discussion of all j
analyses in which the LLD required by Table 16.11-8 was not achievable.
4 l
i
- A single submittal may be made for the station.
l
" One map shall cover stations near the SITE BOUNDARY, and a second map shall include the more distant stations.
4 e
i 16.11-62 08/01/94 i
i
= _..
i 16.11-16.2- ' ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT (see Note)
The Annual Radioactive Effluent Releau Report covering the operation of the unit during the j
1 previous calendar year shall be submitted before May 1 of each year. The Annual Radioactive i
j
_ Effluent Release Reports shallinclude a summary of the quantities of radioactive liquid and j
gaseous effluents and solid waste released from the unit.
t j
]
The Annual Radioactive Effluent Release Report shallinclude an annual summary of hourly i
meteorological data collected over the previous year. This annual summary may be either in
)
the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, l
atmospheric stability, and precipitation (if measured), or in the form of joint frequency i
distributions of wind speed, wind direction, and atmospheric stability. [In lieu of submission j
with the Annual Radioactive Effluent Release Report, the licensee has the option of retaining j
this summary of required meterological data on site in a file that shall be provided to the NRC upon request.) This same report shallinclude an assessment of the radiation doses due to the radioactive liquid and gaseous affluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from l
radioactive liquid and gaseous effluents to MEMBER OF THE PUBLIC due to their activities inside the SITE BOUNDARY during the report period. All assumptions used in making these
{
assessments, i.e., specific activity, exposure time and location, shall be included in these reports. The meteorological conditions concurrent with the time of release of radioactive j
materials in gaseous effluents, as determined by sampling frequency and measurement, shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall j
be performed in accordance with the methodology and parameters in the OFFSITE DOSE i
CALCULATION MANUAL (ODCM).
l The Annual Radioactive Effluent Release Report shall also include an assessment of radiation 0
j doses to the likely most exposed MEMBER OF THE PUBLIC from reactor releases and other i
nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct l
radiation, for the previous calendar year to show conformance with 40 CFR Part 190, 8
" Environmental Radiation Protection Standards for Nuclear Power Operation". Acceptable j
methods for calculating the dose contribution from liquid and gaseous affluents are given in Regulatory Guide 1.109, Rev.1, October 1977.
j The Annual Radioactive Effluent Release Reports shall include the following information for y
j each type of solid waste shipped offsite during the report period:
.i a.
Total Container volume, in cubic meters, j
b.
Total Curie quantity (determined by measurement or estimate),
c.
Principal radionuclides (determined by rnessurement or estimate),
i
)
d.
Type of waste (e.g., dowatered spent resin, compacted dry waste, evaporator.
j bottoms),
1 I
16.11-63 08/01/94 i
e.
Number of shipments, and f.
Solidificatior; agent or absorbent (e.g., cement or other approved agents (media)).
The Annual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
The Annual Radioactive Effluent Release Reports shallinclude any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFSITE DOSE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to SLC 16.11-14.
Note:
A single submittal may be made for the station. The submittal should combine those sections that are common to both units.
1 II 2
4 I
[
l6. I i-64 08/0I/94 i
SITE BOUNDARY PERIMETER FENCE s
(
/
NSW l
(
DAM NUCLEAR SERVICE WATER POND t
}
i 3,
\\
i i
2500 FT. R N
s EXCLUSION
/
BOUNDARY
.n
\\.
I g
INTAKE STRUCTURE
~
MONITOR TANK 301LDING (GASEQUS RELEASE. P01HT)
.k.;;;.\\J..._...;;;;;;;;;!!!!!!IIII(......
- 7.....
REAbTOR TURBINE LOGS STATION VENTS 2y 8 LOGS.
(GASEOUS RELEASE
- j[ POINTS EL 718.75)
/
u 4
N I,
SWITCH n
YARD
\\
COCiLING TOWER
\\
. AUX.
ACCESS ROAO BLOG.
, ARD
\\,
METEO OGICAL TOWER TRAINING CENTER
,j q
Q DISCHARGE 4
STRUCTURE Q
j (LIQUID RELEAS PotNT)
N' CHEMICAL TREATMEN s
PONOS
{
j
~N..
... edRO 'M 32 g
i FIGURE
- .11-1 4
16.11-65 CATAWBA - UNITS 1 AND 2 i