ML20206D219
| ML20206D219 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 12/31/1998 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20206D218 | List: |
| References | |
| NUDOCS 9905040024 | |
| Download: ML20206D219 (49) | |
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l ATTACIDENT I Summaary of Liquid and Gaseous Effluents Report l
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1 9905040024 990429 PDR ADOCK 05000413 R PDR ,,
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CATAWBA NUCLEAR STATION EFFLUENT RELEASE DATA (January 1, 1998 through December 31, 1998)
- This attachment includes a sumary of the quantities of radioactive liquid and
. gaseous effluents;as outlined in Regulatory Guide 1.21,. Appendix B.-
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i TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT i PERIOD 1/1/98 TO 1/1/99 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Catawba Nuclear Station Units 1 & 2 REPORT FOR 199.8 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR 4
A. Fission and Activation Gases
- 1. Total Release Ci 5.20E+01 1.54E+00 1.31E+01 6.94E+01 1.36E+02
- 2. Average Release Rate uci/sec 6.69E+00 1.96E-01 1.65E+00 8.73E+00 4.31E+00 B. Iodine-131 l
- 1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 '
- 2. Average Release Rate uCi/sec 0 00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C. Particulates Half Life >= 8 days
- 1. Total Release Ci 3.55E-05 0.00E+00 0.00E+00 0.00E+00 3.55E-05
- 2. Average Release Rate uCi/sec 4.57E-06 0.00E+00 0.00E+00 0.00E+00 1.13E-06 D. Tritium
- 1. Total Release Ci 7.43E+01 4.59E+01 4.16E+01 4.87E+01 2.10E+02
- 2. Average Release Rate uCi/sec 9.55E+00 5.84E+00 5.24E+00 6.13E+00 6.67E+00 I
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TABLE 1B l EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/98 TO 1/1/99 GASEOUS EFFLUENTS - ELEVATED RELEASES - CONTINUOUS MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 1998 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR
- 1. Fission and Activation Gases !
Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 <
l Totals for Period ... ........ 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 2. Iodines ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals for Period ............ 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 3. Particulates Half Life >= 8 days Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals for Period ............ 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 4. Tritium Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals for Period ............ 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1
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.i TABLE 1B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/98 TO 1/1/99 GASEOUS EFFLUENTS - CLEVATED RELEASES - BATCH NODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 1998 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR '
- 1. Fission and Activation Gases Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals for Period ............ 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 2. Iodines Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Tothls for Period ............. O.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 3. Particulates Half Life >= 8 days Ci 0.00E+00 0.00E+00 0.00E+00 0.0CE+00 0.00E+00 Totals for Period ............ 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i 4. Tritium Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals for Period ............ 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.003+00 l
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! ... c TABLE 1C l EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/98 TO 1/1/99 GASEOUS EFFLUENTS - GROUND RELEASES - CONTINUOUS MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 1998 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR
- 1. Fission and Activation Gases XE-133 Ci 5.12E+01 6.56E-01 1.26E+01 6.91E+01 1.34E+02 Totals for Period ............ 5.12E+01 6.56E-01 1.26E+01 6.91E+01 1.34E+02
- 2. Iodines Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
Totals for Period . . . . . . . . . . . . 0. 00s ' ^0 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
- 3. Particulates Half Life >= 8 days Co-58 Ci 3.55E-05 0.00E+00 0.00E+00 0.00E+00 3.55E-05 Totals for Period ............ 3.55E-05 0.00E+00 0.00E+00 0.00E+00 3.55E-05 l 4. Tritium l H-3 Ci 7.42E+01 4.571+01 4.14E+01 4.84E+01 2.09E+02 l Totals for Period ............ 7.42E+01 4.57E+01 4.14E+0; 1.84E+01 2.09E+02 i
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l TABLE 1C EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/98 TO 1/1/99 GASEOUS EFFLUENT 3 - GROUND RELEASES - BATCH MODE Catawba Nuclear Station Units 1 & ?
REPORT FOR 1998 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR
- 1. Fission and Activation Gases AR-41 Ci 5.60E-01 7.31E-01 4.95E-01 2.02E-01 1.97E+00 KR-85 2.16E-01 9.02E-02 2.23E-02 3.97E-02 3.68E-01 ;
KR-85W 0.00E+00 0.00E+00 0.00E+00 7.86E-04 7.86E-04 l KR-88 0.00E+00 1.18E-04 9.43E-04 4.68E-04 1.53E-03 l XE-131M 0.00E+00 0.00E+00 2.09E-03 f 32E-03 2.86E-03 XE-133 2.86E-02 6.10E-02 5.00E-02 6.55E-02 2.03E-01 XE-135 1.55E-03 6.56E-04 9.18E-04 3.00E-03 6.13E Totals for Period ............ 8.06E-01 8.83E-01 5.71E-01 3.18E-01 2.55E+00
- 2. Iodines ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals for Period ............ 0.00E+00 0.00E+00 0.003+00 0.00E+00 0.00E+00
- 3. Particulates Half Life >= 8 days ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals for Period ............ 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 4. Tritium H-3 Ci 5.22E-02 1.25E-01 1. 72F.-01 2.3BE-01 5.74E-01 Totals for Period ............ 5.22E-02 1.25E-01 1.72E-01 2.3BE-01 5.74E-01 i
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/98 TO 1/1/99 LIQUID EFFLUENTS - SU14dATION OF ALL RELEASES l
Catawba Nuclear Station Units 1 & 2 REPORT FOR 1998 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR A. Fission and Activation Products
- 1. Total Release C1 3.52E-02 2.82E-02 3.65E-02 3.58E-02 1.36E-01
- 2. Average Diluted Concentration
- a. Continuous Releases uC1/ml 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- b. Batch Releases uCi/ml 1.63E-09 1.345-09 1.64E-09 1.892-09 1.62E-09 B. Tritium
- 1. Total Release C1 1.37E+02 1.86E+02 L.09E+02 2.16E+02 1.0FE+03
- 2. Average Diluted Concentration
- a. Continuous Releases uCi/ml 8.99E-09 4.12E-08 0.00E+00 5.36E-08 2.10E-08
- b. Batch Releases uCi/ml 6.30F-06 8.63E-06 2.28E-05 1.14E-05 1.241-05 C. Dissolved and Entrained Gases
- 1. Total Release Ci 8.24E-06 3.79E-04 3.37E-06 0.00E+00 3.91E-04
- 2. Average Diluted Concentration
- a. Continuous Releases uCi/al 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- b. Batch Releases uCi/ml 3.81E-13 1.80E-11 1.51E-13 0.00E+00 4.65E-12 D. Gross Alpha Radioactivity
- 1. Total Release Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 2. Average Diluted concentration
- a. Continuous Releases uCi/al 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- b. Batch Releases uCi/ml 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E. Volume of Liquid Waste
- 1. Continuous Releases liters 4.162+08 7.80E+08 0.00E+00 4.16E+08 1.61E+09
- 2. Batch Releases liters 1.12E+06 7.95E+05 2.32E+06 1.37E+06 5.60E+06 l
F. Volume of Dilution Water
- 1. Continuous Releases liters 1.91E+11 1.13E+11 4.23E+10 2.74E+10 3.74E+11
- 2. Batch Releases liters 2.16E+10 2.11E+10 2.23E+10 1.89E+10 8.40E+10 k . . . . - _ _
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TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/98 TO 1/1/99 LIQUID EFFLUENTS - CONTINUOUS MODE Catawba Nuclear Station Units 1 & 2 REPORT FOR 1998 Unit QTR 1 QTR 2 QTR 3 QTR 4 YEAR
- 1. Fission and Activation Products Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals for Period ............ 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 2. Tritium H-3 Ci 1.72E+00 4.69E+00 0.00E+00 1.49E+00 7.90E+00 Totals for Period ............ 1.72E+00 4.69E+00 0.00E+00 1.49E+00 7.90E+00
- 3. Dissolved and Entrained Gases Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1
Totals for Period ............ 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 l
- 4. Gross Alpha Radioactivity Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals for Period ............ 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 I
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TABLE 2B EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/98 TO 1/1/99 LIQUID EFFLUENTS - BATCH NODE
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Catawba Nuclear Station Units 1 & 2 REPORT FOR 1998 Unit QTR 1 QTR 2 QTR 3 QTR 4 YLAk
- 1. Fission and Activation Products AG-108N Ci 0.00E+00 0.00E+00 3.22E-06 0.00E+00 3.22E-06 AG-110N 0.00E+00 7.585-05 1.13E-04 2.265-04 4.15E-04 Co-57 3.02E-05 3.53E-05 5.135-05 2.31E-05 1.40E-04 CO 9.815-03 4.35E-03 1.36E-02 1.465-02 4.235-02 CO-60 1.385-03 2.47E-03 8.78E-03 4.76E-03 1.74E-02 CR-51 2.19E-03 8.92E-04 8.055-03 6.262-03 1.74E-02 CS-134 1.20E-05 2.51E-04 8.45E-05 5.43E-06 3.53E-04 C8-137 1.07E-04 5.12E-04 5.065-04 1.545-04 1.285-03 F-18 0.00E+00 0.00E+00 1.66E-06 0.00E+00 1.66E-06 FE-59 8.11E-05 2.24E-05 5.22E-04 4.06E-04 1.03E-03 I-131 3.795-06 0.00E+00 0.00E+00 0.00E+00 3.79E-06 I-133 0.00E+00 0.00E+00 1.375-06 0.00E+00 1.37E-06 LA-140 3.75E-05 0.00E+00 0.00E+00 0.00E+00 3.75'.-05 MN-54 3.20E-04 3.355-04 1.095-03 7.79E-04 2.535-03 ,
NA-24 0.00E+00 0.00E+00 0.00E+00 1.30E-05 1.30E-05 l NB-95 8.155-05 9.78E-06 2.565-04 3.47E-04 6.92E-04 NS-97 1.78E-05 0.00E+00 3.20E-04 2.885-04 6.25E-04 i NB-97M 6.66E-07 0.00E+00 0.00E+00 0.00E+00 6.66E-07 RB-89 0.00E+00 3.465-04 0.00E+00 0.00E+00 3.465-04 83-124 1.155-03 4.86E-04 2.265-06 1.185-03 2.81E-03 83-125 .00E-02 1.85E-02 3.065-03 6.54E-03 4.80E-02 SN-113 0.00E+00 0.00E+00 2.05E-05 0.00E+00 2.055-05 SR-91 0.00E+00 0.00E+00 1.91E-06 0.00E+00 1.915-06 SR-92 0.00E+00 0.00E+00 0.00E+00 1.335-05 1.335-05 EN-65 0.00E+00 0.00E+00 1.55E-06 0.00E+00 1.55E-06 EN-69N 0.00E+00 0.00E+00 0.00E+00 3.44E-06 ~3.445-06 ER 1.05E-05 0.00E+00 1.435-04 2.195-04 3.72E-04 Totals for Period ............. 3.52E-02 2.82E-02 3.655-02 3.585-02 1.365-01
- 2. Tritium H-3 C1 1.365+02 1.82E+02 5.09E+02 2.15E+02 1.04E+03 Totals for Period ............ 1.36E+02 1.82E+02 E.09E+02 2.15E+02 1.04E+03
- 3. Dissolved and Entrained Gases ER-85M Ci 8.245-06 0.00E+00 0.00E+00 0.00E+00 8.245-06 EI-131M 0.00E+00 3.795-04 0.00E+00 0.00E+00 3.79E-04 XE-133- 0.00E+00 0.00E+00 3.37E-06 0.00E+00 3.37E-06 Totals for Period ............ 8.24E-06 3.79E-04 3.375-06 0.00E+00 3.91E-04
- 4. Gross Alpha Radioactivity Ci 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totale for Period ............ 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 u
J ATTACIDGlNT II l
Supplemental Information to the !
Liquid and Gaseous Effluents Report l
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CATAWBA NUCLEAR STATION 1998 EFFLUENT AND WASTE DISPOSAL SUPPLEMENTAL INFORMATION l
I. REGULATORY LIMITS - PER UNIT A. NonLE GASES - AIR DOSE a. LIQUID ErFLUENTS - DOSE
- 1. cat == nam. QUARTER . - GAben DOSE = 5 MRAD 1. CALENDAR QUARTER - TOTAL BODY DOSE = 1.5 MREN
- 2. Cat ==na= QUARTER - BETA DOSE = 10 MRAD 2. catwun u QUARTER - ORGAN DOSE = 5 MREN
- 3. carnunne, TEAR - Guam DOSE = 10 MRAD 3. CALENDAR YEAR - total acDr DOSE = 3 MREN
- 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 > S DAYS - ORGAN DOSE
- 1. cat =unne, QUARTER = 7.5 MREN
- 2. CALENDAR YEAR = 15 HREM II. MAXIMUM PERMISSIBLE EFFLUENT CONCENTRATIONS A. GASEOUS EFFLUENTS - INFON ETION FOUND IN OFFSITE DOSE CALCULATION MANUAL
- 3. LIQUID EFFLUENTS - INFORMATION FOUND IN 10CFR20, APPENDIX B, TABLE 2, COLUMN 2 III. AVERAGE ENERGY - NOT APPLICABLE IV. MEASUREMENTS AND APPPOXIMATIONS OF TOTAL RADIOACTIVITY I
INFORMATION NOCND IN OFFSITE DOSE CALCUIATION MANUAL !
I V. BATCH RELEASES l
A. LIQUID EFFLUENT 1 2.03E+02 = TOTAL NUMBER OF BATCH RELEASES
- 2. 1.17E+04 = TOTAL TIME (MIN. ) FOR SATCH RELEASES.
3.1.96E+02 = MAXIMUM TIME (MIN.) FOR A BATCH RELEASE.
- 4. 5.765+01 = AVERAGE TIME (MIN.) FOR A RATCH RELEASE.
- 5. 5.00E+00 = MINIMUW TIME (MIN. ) FOR A BATCH RELEASE.
- 6. 4.22E+04 = AVERAGE DILUTION MATER FLON DURING RELEASES (GPM) .
- 3. GASEOUS EFFLUENT
- 1. 1.30E+02 = TOTAL NUMBER OF BATCH RELEASES. j
- 2. 9.82E+05 = TOTAL TIME (MIN.) FOR BATCH RELEASES. !
- 3. 6.2SE+04 = MAXIMUM TIME (MIN. ) FOR A BATCH RELEASE. l
- 4. *l.55E+03 = AVERAGE TIME (MIN.) FOR A BATCH RELEASE. I
- 5. 7.00E+00 = MINIMUM TIME (MIN.) NOR A BATCH RELEASE. )
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VI. ABNORMAL RELEASES A. LIQUID 1
- 1. NUMmER OF RELEASES = 0
- 2. TOTAL ACTIVITY RELEASED (CURIES) = 0
- 3. GASEOUS
- 1. NUMBER OF RELEASES = 1
- 2. TOTAL ACTIVITY REI. EASED (CURIES) = See Attachment I i
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. . SUPPLEMENTAL REPORT PAGE 2 CATAWBA NUCLEAR STATION Values represented by "0.00E+00" within the body of the Annual report are below the minimum detectable limits of the Catawba counting systems. Typical MDA's for the Catawba counting i 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 ,
402 3.15E-08 Kr-87 Cs-137 661 2.50E-08 :
Mo-99 778 1.4SE-07 l Mn-54 834 2.65E-08 '
Zn-65 1115 6.85E-08 Co-60 1332 2.95E-08 4 3
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l SUPPLEMENTAL REPORT PAGE 3 i
, CATAWBA NUCLEAR STATION The estimated percentage of error for both Liquid and Gaseaus effluent release data at Catawba Nuclear Station has been determined to be 16.1%. This value was derived by taking the square root of the sum of the squares of the following discrete individual estimates of error:
(1) Flow rate determining devices =
- 5%
(2) Counting error =
- 15%
(3) Sample preparation error =
3%
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l ATTACHMENT III I
Fuel Cycle Calculation l
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Catawba Nuclear Station 1998 Radioactive Effluent Releases 40CFR190 Uranium Fuel Cycle Dose
- Calculation Results Maximum Total Body Dose = 1.63E+00 ares l
Maximum Location: 1.0 Mile, East-North-East Sector Critical Age = Infant l
Liquid and Gas Effluent Contribution to Maximum Total Body Dose !
j Liquid Effluent Dose = 2.91E-02 mrem = 1.8% of total l i
Critical Path = Potable Water !
Major Contributor = H-3 J
Gas Effluent Dose = 1.60E+00 mrem = 93.2% of total critical Path = Goat Milk Major Contributor = H-3 1
Maximum Organ Dose = 1.63E+00 mrom Maximum Location: 1.0 Mile, East-North-East Sector i critical Age - Infant l
Critical Organ - Liver j Liquid and Gas Effluent Contribution to Maximum Organ Dose Liquid Effluent Dose = 2.92E-02 mrem = 1.8% of total
-Critical Path = Potable Water Major Contributor = H-3 Gas Effluent Dose = 1.60E+00 mrem = 98.2% of total Critical Path = Goat Milk Major Contributor = H-3 l
Annual dose limits f rom 40CFR190.10 (a) of 25 mrem whole body, 75 mrem to the thyroid, and 25 mrem to-any other organ.
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ATTACHMENT IV The solid Waste Report L
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CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE
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SUMMARY
OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD 1/1/98 THROUGH 12/31/98 Type'of Waste' Radionuclide % Abundance l '. Waste from Liquid Systems (A) Dewatered Secondary Resins (none shipped this period)
(B) Dewatered Primary Resins Cr-51 0.8 Mn-54 5.1 Co-57 0.3 Co-58 11.3 Fe-59 0.1 Co-60 10.7 Sn-113 0.1 Sb-125 0.5 Cs-134 0.8 Cs-137 1.5 Ni-59 0.2 C-14 0.2 Fe-55 33.4 Ni-63 35.1 (C) Evaporator Concentrates (none shipped this period)
(D) Dewatered Mechanical Filters Mn-54 1.9 Co-57 0.1 Co-58 0.5 Co-60 14.3 Zn-65 0.4 Nb-95 0.4 Ag-110m 0.1 Sb-125 0.6 Fe-55 69.0
.Ni-63 12.4
.(E) 'Dewatered Demineralizers (none shipped this period)
(F) Solidified Acids, Oils, Sludges (none shipped this period)
Average percent abundance for all shipments during period (unlisted if <0.1%)
Page 1 of 3 L
CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE
SUMMARY
OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD'1/1/98 THROUGH 12/31/98 Pype of Waste Radionuclide % Abundance
- 2. Dry Solid Waste (A) Dry Active Waste (compacted) (none shipped this period)
(B) Dry Active Waste (non-compacted) H-3 1.5 Cr-51 1.7 ,
Mn-54 1.9 l Co-57 0.1 Co-58 12.5 Co-60 13.8 Nb-95 0.4 Zr-95 0.3 Ag-110m 0.2 Sb-124 0.1 l Sb-125 0.5 Cs-134 0.1 Cs-137 0.1 Ce-144 0.1 Ba/La-140 0.2 Fe-55 57.3 Ni-63 9.1 (C) Dry Active . Waste (brokered) H-3 1.5 Cr-51 1.7 Mn-54 1.9 Co-57 0.2 Co-58 12.5 Co-60 13.9 Nb-95 0.4 Zr-95 0.3.
Ag-110m 0.2 Sb-124 0.1 Sb-125 0.5 Cs-134 0.1 Cs-137 0.1 i Ce-144 0.1 !
l Ba/La-140 0.2 j 57.3 Fe-55 l Ni-63 9.1 l
(D) Irradiated' Components (none shipped this period)
Average percent abundance for all shipments during period (unlisted if <0.1%)
Page 2 of 3 6
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- 1 CATAWBA NUCLEAR STATION - SOLID RADIOACTIVE WASTE l
SUMMARY
OF PRINCIPAL RADIONUCLIDE COMPOSITION REPORT PERIOD 1/1/98 THROUGH 12/31/98 I
l
- 4 Type of Waste Radionuclide % Abundance l
- 3. All Solid Waste Cr-51 0.1 Mn-54 2.4 Co-57 0.1 Co-58 2.4 Co-60 13.7 Zn-65 0.4 Nb-95 0.3 Ag-110m 0.1 j Sb-125 0.6 i Cs-134 0.1 Cs-137 0.3 Fe-55 63.0 Ni-63 16.2 I Average percent abundance for all shipments during period (unlisted if <0.1%) i Page 3 of 3 L.
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ATTACHMENT VI Abnormal Releases 1
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CATAWBA NUCLEAR STATION UNPLANNED RELEASES (January 1, 1998 through December 31, 1998) !
This attachment includes a summary of unplanned releases of radiation to the environment. There was 1 unplanned gaseout radioactivity release to the environment in 1998. There were no. unplanned liquid radioactivity releases to the' environment in 1998, i-i I
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Occurred: 05-20-98 08D4 (Refer to PIP 0-C98-187D During 1998 there was one recorded Abnormal Effluent Release at Catawba. The event began with the observation that WGDT-B pressure was decreasing. The tank was not the in-service tank. Chemistry technician contacted OPS. At 2130 hr, the drop in pressure appeared to be an actual leak and not a transmitter malfunction. RP Tech was contacted to collect sample from WGDT-B.' During preparation for the sample collection, RP Tech searched for pos Sie leak
. location (s). Found gas leak or. 0WGPT5110 tubing. SPOC team was dispatched at 2200 hr and fitting was tightened. Fitting was greater than hand-tight but less than sufficiently tight to prevent leakage. Further monitoring of tank pressure indicated that leakage had stopped at 2205 hr. Tank was sampled at 2245 hr for activity analysis. RP generated GWR 98-103 to account for and document activity released during the event.
Radiological Conseauenas:
1 Release from WG system was calculated to be 4.26E-03 Ci (Kr-65).
l Site Boundary concentration was calculated to be 2.%E-12 uCi/cc. l Skin Dose was estimated to be 1.43E-04 mrad. l Total Body Dose estimated to be 9.23E-06 mrad.
The dose values were alculated using the RETDAS Effluent Release Program.
Conclusion:
Maintenance group initiated work request to check tightness of other similar fittings located near 0WGPT5110. The action was discussed with the team involved. In addition, OAC rate alarms on WG pressures were investigated. During the leakage event the small changes in pressure of the tank were not adequately monitored. A minor mod MM CNCE-61458 was generated to correct the OAC database problem.
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ATTACIDENT VII Assessment f Radiation Dose from t
l Radioactive Effluents to Members of the Public l l
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4 CATAWBA NUCLEAR STATION Assessment-of. Radiation Dose from Radioactive Effluents to Members of the Public l
,' (January 1,- 1998-through December 31, 1998)
This attachment includes an assessment of radiation doses to the maximum
. exposed member of the public due to radioactive liquid and gaseous effluents l- . released-from the site for each calendar quarter for the calendar year of this
- ' -report, as well as the total dose for the calendar year. This attachment also includes an assessment of radiation doses to the maximum exposed member of the public from all uranium fuel. cycle sources within 10 miles of Catawba for the calendar year of this report to show conformance with 40 CFR 190. Methods for calculating the dose contribution from liquid-and gaseous effluents are given in the ODCM.
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/98 TO 1/1/99 GASEOUS ANNUAL DOSE SIDemRY REPORT Catawba Nuclear Station Units 1 & 2 l
l 1** Quarter 1998 l
- IODINE, H3, AND PARTICUIATE DOSE LIMIT ANALYSIS Quarter 1 1998 Critical Critical Dose Limit Max % of Period-Limit Group Organ (area) (area) Limit Q1 - Maximum Organ Dose INFANT LUNG 5.63E-01 1.50E+01 3.75E+00 Maximum Organ Dose Receptor Location 1.0 Mile ENE l Critical Pathway: Joat Milk l
l Major Isotopic Contributors (5% or greater to total)
Nuclide Peroentage H-3 1.00E+02 i
- NOBLE GAS DOSE LIMIT ANALYSI- Quarter 1 1998 - l l Dose -Limit % of Period-Limit (arad) (arad) Limit Q1 . Maximua Gamma Air Dose 2.595-02 1.00E+01 2.59E-01 Maximua Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage XE-133 7.76E+01 l AR-41 2.24E+01 l Q1 - Maximus Beta Air Dose 6.245-02 2.00E+01 3.12E-01 Maximus Beta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage i XE-133 9.60E+01 l
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/98 TO 1/1/99 GASEOUS ANNUAL DOSE SUtedARY REPORT I 1
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Catawba Nuclear Station Units 1 & 2 1 2 *d Quarter 1998
- IODINE, M3, AND PARTICUIATE DOSE LIMIT ANALYSI Quarter 2 1998 -
Critical Critical Dose Limit Max 4 of I Period-Limit Group Organ (area) (area) Limit )
Q2 - Maximum Organ Dose INFANT LIVER 3.48E-01 1.50E+01 2.32E+00 Maximum Organ Dose Receptor Location: 1.0 Mile ENE Critical Pathways Goat Milk Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage M-3 1.00E+02
- NOELE GA5 DOEE LIMIT ANALYSIC Quarter 2 1998 -
l Dose Limit 4 of l Period
- Limit (arad) (arad) Limit I
.............................................................................. i Q2 - Maximum Gamma Air Dose 7.855-03 1.00E+01 7.855-02 Maximin Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage AR-41 9.63E+01 Q2 - Maximum meta Air Dose '3,703-03 2.00E+01 1.85E-02 Max 4=im Eeta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage AR-41 7.20E+01 XB-133 2.26E+01 KR-85 5.295+00
n . .
p EFFLUENT AND MASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/98 TO 1/1/99 GASEOUS ANNUAL DOSE SIA8dARY REPORT Catawba Nuclear Station Units 1 & 2 i
3d Quarter 1998
- IODINE, M3, AND PARTICULATE DO8E LIMIT ANALYsI" Quarter 3 1998 -
Critical Critical Dose Limit Max % of Period-Limit Group Organ (area) (area) Limit Q3 - Maxismum Organ Dose INFANT LIVER 3.16E-01 1.50E+01 2.11E+00 Maximum Organ Dose Receptor Location: 1.0 Mile ENE Critical Pathway: Goat Milk Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 1.00E+02
- NOB"E GAS DOSE LIMIT ANALYSIS Quarter 3 1998 -
Dose Limit 4 of Period-Limit (arad) (arad) Limit
.............................................................................. l Q3 - Maximum Gamma Air Dose 1.015-02 1.00E+01 1.015-01 ,
Maximum Gamma Air Dose Receptor Location 0.5 Mile NME Major Isotopic Contributors (5% or greater to total)
Nuclido Percentage AR-41 5.07E+01 XE-133 4.91E+01 Q3 - Maximum Beta Air Dose 1.66E-02 2.00E+01 8.30E-02 Maximum meta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Cor.tributors (5% or greater to total)
Nuclide Percentage XE-133 8.88E+01 AR-41 1.095+01 1
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EFFLUENT AND W7.STE DISPOSAL ANNUAL REPORT PERIOD 1/1/98 TO 1/1/99 GASEOUS ANNUAL DOSE StDSOLRY REPORT Catawba Nuclear Station Units 1 & 2 4" Quarter 1998
- ICOINE, N3, AND PARTICUIATE DOSE LIMIT ANALYSI Quarter 4 1998 -
Critical Critical Dose Limit Max 4 of Period-Limit Group Organ (area) (area) Limit Q4 - Maximum Organ Dose INFANT LIVER 3.695-01 1.50E+01 2.46E+00 Maxi == organ Dose Receptor Location: 1.0 Mile ENE Critical Pathways Goat Milk Major Isotopic Contributors (56 or greater to total)
Nuclide Percentage H-3 1.00E+02
- NOBLE GAS DOSE LIMIT ANALYSI: Quarter 4 1998 -
Dose Limit 4 of Period-Limit (arad) (arad) Limit Q4 - Maximus Gamma Air Dose 2.e35-02 1.00E+01 2.93E-01 Maximus Gamma Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage XE-133 9.285+01 AR-41 1.13E+00 Q4 - Maximua Beta Air Dose 8.17E-02 2.00d+01 4.085-01 Maximus Beta Air Dose Receptor Location: 0.5 Mile NME
. Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage XE-133 9.90E+01 i
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EFFLUENT AND WASTE DISPOSAL Ab'NUAL REPORT PERIOD 1/1/98 TO 1/1/99 GASEOUS ANNUAL DOSE SUledhRY REPORT Catawba Nuclear Station Units 1 & 2 ANNUAL 1998
=== IODINE, H3, AND PARTICUIATE DOSE LIMIT ANALYSIS == Annual 1998 Critical critical Dose Limit- Max % of Period-Limit Group Organ (area) (area) Limit Yr - Maximum Organ Dose -INFANT LUNG 1.60E+00 3.00E+01 5.33E+00 Maximum Organ Dose Receptor Location: 1.0 Mile ENE Critical Pathways Goat Milk Major Isotopic Contributors (5% or greater to total) )
Nuclide Percentage 1
.......... .......... 1 E-3 1.00E+02 g === NOBLE GAS DO4E LIMIT ANALYSIS ihnnual 1996 Dose 3.init % of j Period-TAmit (arad) tarad) Limit {
.......................... .................................................... J Yr - Maximum Gamma Air Doss. 7.305-02 2.00E+01 3.65E-01 Maximum Gamma Air Dose Raceptor Location: 0.5 Mile NNE Major Isotopic contributors (5% or greater to total)
Nuclide Percentage XE-133 7.20E+01 -
AR-41 2.80E+01 Yr - Maximus Beta Air Dose 1.64E-01 4.03E+01 4.10E-01 Maximus Bwta Air Dose Receptor Location: 0.5 Mile NNE Major Isotopic Contributors (5% or greater to total)
Nuclide Peroentage XE-133 9.51E+01 1
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/98 TO 1/1/99 LIQUID ANNUAL DOSE
SUMMARY
REPORT Catawba Nuclear Station Units 1 & 2 1** Quarter'1998
- RATCH LIQUID RELEASES =
==== Quarter 1 1990 - -
Critical Critical Dose Limit Max 4 of Period-Limit Age Organ (area) (area) Limit Q1 - Maximua Organ Dose ADULT GI-LLI 2.10E-02 1.00E+01 2.105-01 Q1 - Total Body Dose ADULT 1.05E-02 3.00E+00 3.50E-01 Maximua Organ Critical Pathways Fresh Water Fish Major Isotopic Contributors (5% or greater to total) l Nuclide Percentage NB-95 5.74E+01 H-3 2.76E+01 CO-58 8.49E+00 Total Bcdy critical Pathways Fresh water Fish Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3' 5.54E+01 CS-137 3.50E+01 C8-134 6.62E+00
- CONTINUOUS LIQUID RELEASES (wC) ======== Quarter 1 1998 - ===
Critical Critical Dose Limit Max % of l .
Period-Limit Age Organ (area) (area) Limit l Q1 - Maximum Organ Dose ADULT LIVER 8.2BE-06 1.00E+01 8.20E-05 l
Q1 - Total Body Dose ADULT 8.285-06 3.00E+00 2.765-04 Maximum Organ critical Pathway Fresh Nater Fish ,
Major Isotopic contributors (5% or greater to total) !
Nuclide Percentage i i ....... ..........
l
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H-3 1.00E+02 i l
Total Body Critical Pathway Fresh water Fish Major Isotopic contributors (5% or greater to total)
Nuclide Percentage i
....... .......... i H-3 1.00E+02 I i
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EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/98 TO 1/1/99
. LIQUID ANNUAL DOSE SUteGLRY REPORT Catawba Nuclear Station Units 1 & 2 2"' Quarter 1998
=== BATCH LIQUID F,ELEAsEs Quarter 2 1998 Critical Critical Dose Limit Max 4 of Period-Limit Age Organ (area) (area) Limit Q2 - Maximum Orga.s Dose ADULT LIVER 5.44E-02 1.00E+01 5.445-01 Q2 - Total Body Dose ADULT 4.15E-02 3.00E+00 1.30E+00 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total) i Nuclide Percentage C8-137 5.095+01 Cs-134 3.38E+01 E-3 1.485+01 Total Body Critical Pathwayt Fresh Water Fish Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage C8-137 4.37E+01 CS-134 3.63E+01 H-3 1.94E+01 l
=== CCNTINUOUS LIQUID RELEASES (WC) --= Quarter 2 1998 Critical critical Dose Limit Max 4 of Period-Limit Age Organ (area) (area) Limit Q2 - Maximum Organ Dose ADULT LIVER 3.85E-05 1.00E+01 3.85E-04 l Q2 - Total Body Dose ADULT 3.85E-05 3.00E+00 1.285-03 j Maximua Organ !
critical Pathway: Fresh water Fish l Major Isotopic Contributors (5% or greater to total) j Nuclide Percentage )
H-3 1.00E+02 I 3
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total Body !
I Critical Pathways Urosh Water Fish Major Isotopic Contributors (54 or greater to total)
Nuclide Percentage )
H-3 1.00E+02 -
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EFFLUENT AND WASTE DISPOSAL' ANNUAL REPORT PERIOD 1/1/98 TO 1/1/99 LIQUID ANNUAL DOSE
SUMMARY
REPORT Catawba Nuclear Station Units 1 & 2 3d Quarter 1996
- BATCH LIQUID RELEASES Quarter 3 1998 Critical Critical Dose Limit Max % of Period-Limit Age Organ (area) (area) Limit Q3 - Maximum Organ Dose ADULT GI-LLI 6.83E-02 1.00E+01 6.03E-01 l Q3 - Total Body Dose ADULT 4.44E-02 3.00E+00 1.485+00 l 1
Maximum Organ l Critical Pathway: Fresh Water Fish I Wajor Isotopic contributors (5% or greater to total) f Nuc114e Percentage NS-95 5.475+01 H-3 3.15E+01 CO-60 6.22E+00 Total Body l Critical Pathwayt Fresh Water Fish t Ms.jor Isotopio Contributors (5% or greater to total)
Nuclide Percentage H-3 4.85E+01 CS-137 3.85E+01 CS-134 1.095+01
- CONTINUOUS LIQUID RELEASES (WC) Quarter 3 1998 Critical critical Dose Limit Max % of j Period-Limit Age Organ (area) (area) Limit Q3 . Maximum Organ Dose NA NA 0.00E+00 1.00E+01 0.00E+00 Q3 - Total Body Dose NA NA 0.00E+00 3.00E+00 0.00E+00 l
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.. .e - e EFFLUENT AND MASTE DISPOSAL ANNUAL REPORT PERIOD 1/1/98 TO 1/1/99 LIQUID ANNUAL DOSE
SUMMARY
REPORT Catawba Nuclear Station Units 1 & 2 i l
'4** Quarter 1998 l
=== BATCH LIQUID RELEACES Quarter 4 1998 Critical critical Dose Limit Max 4 of Period-Limit Age Organ (area) (area) Limit Q4 - Maximum Organ Dose ADULT GI-LLI 7.85E-02 1.00E+01 7.85E-01 Q4 - Total Body Dose ADULT 1.80E-C2 3.00Et00 6.00E-01 Maximum Organ Critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage l
NS-95 7.63E+01 i H-3 1.37E+01 1 Total Body critical Pathway: Fresh Water Fish Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 5.94E+01 CS-137 3.42E+01
- CONTINUOUS LIQUID RELEASES (WC) -== Quarter 4 1998 ==
Critical Critical Dose Limit Max % of Period-Limit Age Organ (area) (area) Limit Q4 - Maximum Organ Dose ADULT' LIVER 5.06E-05 1.00E+01 5.06E-04 Q4 - Total Body Dose ADULT 5.068-05 3.00E+00 1.69E-03 Haximum Organ Critical Pathways Fresh Water Fish Major Isotopic Contributors (5% or greater to tt tal) .
Nuclide Percentage l H-3 1.00E+02 l Total Body Critical Pathways Fresh Water Fish Major Isotopic Contributors (5% or greater to total) {
Nuclide Percentage j H-3 1.00E+02 i
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- BATCH LIQUID RELEASES Annual 1998 Critical Critical Dose Limit Max % of Period-Limit Age Organ (area) (area) Limit Yr - Maximum Organ Dose ADULT GI-LLI 1.17E-01 2.00E+01 8.85E-01 Yr - Total Body Dose ADULT 1.16E-01 6.00E+00 1.93E+00 Maximum Organ Critical Pathways Fresh Water Fish Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage NB-95 6.04E+01 H-3 2.62E+01 Co-60 5.01E+00 Total Body Critical Pathwayt Fresh Water Fish Major Isotopic Contributors (5% or greater to total)
Nuclide Percentage H-3 4.01E+01 l C8-137 3.95E+01 l CS-134 1.84E+01 '
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- CONT 1stUOUS LIQUID RELEASE 8 (WC) = Annual 1998 Critical Critical Dose Limit Max % of Period-Limit Age Organ (areal (area) Limit l l Yr - Maximum Organ Dose ADULT LIVER 7.88E-05 2.00E+01 3.94E-04
- Yr - Total Body Dose ADULT 7.885-Of 6.00E+00 1.31E-03 Maximum organ
, Critical Pathway Fresh Water Fish Major. Isotopic Contributors (5% or greater to tott.1)
Nuclide Percentage l B-3 1.00E+02 Total Body Critical Pathwayt Fresh Water Fish Major Isotopic Contributors (5% or geaater to total)
Nuclide Percentage E-3 1.00E+02
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ATTACHMENT VIII Revisions to Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP) Manual I
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F. o e, u u, Bl l.
5 amo cava
, E007H aa 4 % o.e. , 526 Soudi Gurdi Sneet P.O. Box 1006 i
. . Chadotte. NC 28201-1006 )
M. S. 'm&====
Emn:mier Evhaltent (AV)3824200 omtr Nnalw Gene,mira (/M)382-4360ra February 10, 1998 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Oconee Nuclear Station, Units,1, 2, and 3 Docket Nos. 50-269, 50-270, 50-287 McGuire Nuclear Station, Units 1 and 2 l Docket Nos. 50-369, 50-370 l Catawba Nuclear Station, Units 1 and 2 ;
Docket Nos. 50-413, 50-414 Offsite Dose Calculation Fanual (ODCM) Revisions Enclosed are revisicas made to the Duke Power Company Offsite l Dose Calculations Manual effective January 1, 1998. A complete copy of the entire ODCM is hereby transmitted as required by McGuire Technical Specification 6.14.2.c. l The following sections are affected by this revision.
Revision 41 Generic Section Revision 38 Oconee Nuclear Station Revision 39 McGuire Nuclear Station Revision 40 Catawba Nuclear Station By copy of this letter, the revised pages of the above ODCM sections are transmitted to be inserted in Control Copy No. 33 (assigned to O5!RR) and Control Copy No. 34 (assigned to Region II) along with an approval letter for each section. For these copies, please insert revised pages according to the insertion instructions found on the approval letters. The approval letter for the Generic Manual along with the justification for Revision 41 should be placed in front of the entire manual.
Each station approval letter (including justifications) should be placed in the frcnt of the respective station manual
, sections.
If you have any questions, please contact L. B. Jones at (704)382-4753.
Very truly yours, na&)
M. S. Tuckman L
n'h 6 4,,2 4
,P Duke Energy Corporation lp ,
526 South Church Street
{ EO. Box 1006 (EC07H)
Charlotte, NC 28201 1006 g g, .gw VM)382-2200 omcs m y, m, (7M)382M rn Nwfur Genennwn January.6, 1999 l
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 1
1
Subject:
Oconee Nuclear Station, Docket No. 50-269, 50-270, 50-287 l McGuire Nuclear Station, Docket No. 50-369, 50-370 Catawba Nuclear Station, Docket No. 50-413, 50-414 Corporate Process Control Program Manual l
Please find attached 6 copies of Revision 12 to the Duke Power j Company Process Control Program Manual. These copies are provided ^
( for manual numbers 26, 27, 28, 29, 30, and 31.
By copy of this letter, Revision 12 is also being provided to i Region II for manual number 22.
1 If you have any questions, please contact L. B. Jones at (704) l 382-4753.
Very truly yours, j l b S' 1 M. S. Tuckman j I
Attachments: 1 - Corp. PCP Intro and Background 2 - CNS PCP Rev Approval Pg 3 - MNS PCP Rev Approval Pg 4 - ONS PCP Rev Approval Pg 5 - Corp. PCP Table of Contents 6 - Corp. PCP (Pgs 1 - 16) 7 - Memorandum Summary (3 pgs)
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