ML20206C485
| ML20206C485 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 12/31/1998 |
| From: | IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | |
| Shared Package | |
| ML20206C474 | List: |
| References | |
| NUDOCS 9905030051 | |
| Download: ML20206C485 (45) | |
Text
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l ALLI ANT UTILITIES DuaneArnoldEnergyCenter 1998 Annual Radioactive Materials Release Report January 1,1998 through December 31,1998
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Table Of Contents i
{
INTRODUCTION 3 i
LIQUID EFFLUENT TABLE 4 LIQUID EFFLUENTS BY CALENDAR QUARTER 4 GASEOUS EFFLUENT TABLES 5 GASEOUS EFFLUENTS BY CALENDAR QUARTER 5 l GASEOUS EFFLUENTS BY RELEASE POINT (CURIES) 6 ,
l
SUMMARY
OF RADIOACTIVE SOLID WASTE 7 SHIPMENTS MADE TO BURIAL FACILITIES: 7 SHIPMENTS MADE TO PROCESSING FACILITIES: 7 TOTAL SOLID WASTE DISPOSITION: 7 WASTE CLASSIFICATION PER 10 CFR 61 7 DRY ACTIVE WASTE 8 I' AQUEOUS MECHANICAL FILTERS 9 SPENT RESIN 10
SUMMARY
OF METEOROLOGICAL DATA 11 STABILITY CLASS DATA 33' 11 WIND ROSE 33' 16 STABILITY CLASS DATA 156' 16 WIND ROSE 156' 21 ,
ATTACIIMENTS 1 & 2:
SUMMARY
OF CIIANGES TO TIIE ODAM ATTACIIMENT 3: CURRENT REVISION OF TIIE ODAM 1998 DAEC Annual Radioactive Material Release Report Page 2
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INTRODUCTION i
1 This Annual Radioactive Material Release Report is for the period of January 1,1998, through i '
December 31,1998.
There were no radioactive liquid effluent releases from the Duane Arnold ,
Energy Center during this report period. i Gaseous effluent releases were continuous for the period and resulted in a small fraction of the 10 CFR 20 site boundary concentration limits and the 1 10 CFR 50, Appendix I dose requirements.' There were no abnormal releases of radioactive material to the environment.
A total of six solid radioactive waste shipments were made during 1998.
Three shipments were of spent resin in high integrity containers (HICs).
One Shipment was a mixture of resin and aqueous mechanical filters in a HIC, All 4 HIC shipments were sent directly for burial to Barnwell, South Carolina. Two shipments of Dry Active Waste were sent to GTS Duratek for processing and volume reduction at Oak Ridge, Tennessee prior to burial at Barnwell, South Carolina.
1 There were't'n revisions to the Offsite Dose Assessment Manual (ODAM) in 1998. Revision 10 was issued to support the implementation ofImproved Technical Specifications. Revision 11 was issued to reflect facility changes resulting from plant modification #EMA-A28097. Details i of these changes are described in Attachments 1 and 2.
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I T
SUMMARY
OF RADIOACTIVE SOLID WASTE Listed below are tables summarizing the Duane Arnold Energy Center's generation of Radioactive Solid Waste i for the period January 1,1998 through December 31,1998, l l
1 SHIPMENTS MADE TO BURIAL FACILITIES: I WASTE TYPE NO. VOLUME ACTIVITY l SHIPMENTS M' (MBq)
Resin 4* 21.4 9.11 E+6 1 Aqueous Mechanical Filters
- 0.08 6.84 E+5 )
DESTINATION Chem-Nuclear Systems, Inc. (CNSI) i Barnwell, South Carolina
(*) One shipment contained both resin and aqueous mechanical filters.
l SIIIPMENTS MADE TO PROCESSING FACILITIES:
WASTE TYPE NO. VOLUME ACTIVITY l SillPMENTS M' (MBq)
Dry Active Waste 2 69.8 3.5E+4 DESTINATION GTS Duratek Oak Ridge, Tennessee SOLIDIFICATION AGENT: None MODE OF TRANSPORTATION: Exclusive-Use Vehicle (Trucks) l TOTAL SOLID WASTE DISPOSITION:
l WASTE VOLUME M' ACTIVITY (MBq)
Shipped 9.20E+ 1 9.83E+06 i Buried ** 2.69E+1 9.81 E+06
(") Includes waste buried directly by DAEC and waste buried by processing facilities.
Waste buried by the processing facility includes waste shipped from the DAEC in years prior to 1998.
WASTE CLASSIFICATION PER 10 CFR 6I NUMBER OF SIIIPMENTS A-Unstable 2 A-Stable 4 B 0 C. 0 1998 DAEC Annual Radioactive Material Release Report Page 7
p
SUMMARY
OF RADIOACTIVE SOLID WASTE (January 1,1998 - December 31,1998)
MAJOR NUCLIDE COMPOSITION DRY ACTIVE WASTE Principle 1st OTR 2nd QTR 3rd QTR 4th QTR Total Percent Nuclide (MBq) (MBq) (MBq) (MBq) (MBq) Abundance Cr-51 0.00E+00 0.00E+00 1.10E+02 4.38E+02 5.48E+02 1.57 %
Mn-54 0.00E+00 0.00E+00 3.00E+02 1.36E+03 1.66E+03 4.75 %
FG-55 0.00E+00 0.00E+00 4.65E+03 2.13E+04 2.60E+04 74.21 %
Co-58 0.00E+00 0.00E+00 2.93E+01 1.27E+02 1.56E+02 0.45%
Co-60 0.00E+00 0.00E+00 9.97E+02 4.56E+03 5.56E+03 15.91 %
FG-59 0.00E+00 0.00E+00 3.61 E+01 1.52E+02 1.88E+02 0.54 %
Ni-59 0.00E+00 0.00E+00 7.14E-01 3.28E+00 3.99E+00 0.01 %
Ni-63 0.00E+00 0.00E+00 6.36E+01 2.L 2E+02 3.55E+02 1.02 %
Zn-65 0.00E+00 0.00E+00 8.01 E+01 3.62E+02 4.42E+02 1.26 %
H-3 0.00E+00 0.00E+00 5.44E+00 3.76E+ 00 9.19E+00 0.03 %
C 0.00E+00 0.00E+00 5.24E+00 2.40E+01 2.92E+01 0.08 %
Cs-134 0.00E+00 0.00E+00 8.97E-03 0.00E+00 8.97E-03 0.00%
Cs-137 0.00E+00 0.00E+00 0.00E+00 3.04E+01 3.04E+01 0.09%
CG-144 0.00E+00 0.00E+00 6.63E+00 0.00E+00 6.63E+00 0.02 %
Sr-90 0.00E+00 0.00E+00 0.00E+00 4.11E-02 4.11 E-02 0.00 %
Tc-99 0.00E+00 0.00E+00 2.55E-05 5.10E-05 7.64E-05 MDA Nb-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
l-129 0.00E+00 0.00E+00 2.43E-04 4.86E-04 7.28E-04 MDA Pu-238 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
Pu-239/240 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
Pu-241 0.00E+00 0.00E+00 1.43E-01 6.56E-01 7.99E-01 0.00 %
Am-241 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
Cm-242 0.00E+00 0.00E+00 1.40E-03 6.25E-03 7.65E-03 0.00 %
Cm-243/244 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00%
U-233/234 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
U-238 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
Hf-181 0.00E+00 0.00E+00 2.70E+01 5.40E-01 2.76E+01 0.08%
Ru-106 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
Sr-89 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
Zr-95 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
Totals 0.00E+00 0.00E+00 6.31 E+03 2.87E+04 3.50E+04 100.00 %
No DAW Shipments were made during the first and second quarters of 1998.
Tc-99 and I-129 represent Minimum Detectable Activity (MDA) values.
These two nuclides are in units of uCi/ swipe from Rad Calc # 97-17-R.
Note: H-3, C-14, Tc-99, and I-129 were required to be manifested per 10 CFR 20, Appendix G.
1998 DAEC Annual Radioactive Material Release Report Page 8
SUMMARY
OF RADIOACTIVE SOLID WASTE (January 1,1998 - December 31,1998)
MAJOR NUCLIDE COMPOSITION AQUEOUS MECIIANICAL FILTERS Principle 1st OTR 2nd QTR 3rd Qtr 4th QTR Total Percent Nuclide (MBq) (MBq) (MBq) (MBq) (MBq) Abundance H-3 0.00E+00 1.88E+02 0.00E+00 0.00E+00 1.88E+02 0.03%
C-14 0.00E+00 4.66E+02 0.00E+00 0.00E+00 4.66E+02 0.07 %
Cr-51 0.00E+00 7.66E+03 0.00E+00 0.00E+00 7.66E+03 1.12 %
Mn-54 0.00E+00 6.07E+04 0.00E+00 0.00E+00 6.07E+04 8.88 %
Fa-55 0.00E+00 5.03E+05 0.00E+00 0.00E+00 5.03E+05 73.56 %
Fc-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00%
Co-58 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
Co-60 0.00E+00 9.29E+04 0.00E+00 0.00E+00 9.29E+04 13.59 %
Zn-65 0.00E+00 9.25E+03 0.00E+00 0.00E+00 9.25E+03 1.35 %
Ni-59 0.00E+00 4.55E+01 0.00E+00 0.00E+00 4.55E+01 0.01 %
Ni-63 0.00E+00 5.66E+03 0.00E+00 0.00E+00 5.66E+03 0.83 %
Sr-90 0.00E+00 2.90E+00 0.00E+00 0.00E+00 2.90E+00 0.00 %
Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
Tc-99 0.00E+00 1.79E-06 0.00E+00 0.00E+00 1.79E-06 MDA Ru-106 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
l-129 0.00E+00 6.52E-06 0.00E+00 0.00E+00 6.52E-06 MDA Cs-134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
Cs-137 0.00E+00 3.92E+03 0.00E+00 0.00E+00 3.92E+03 0.57 %
Pu-238 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
Pu-239/40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
Pu-241 0.00E+00 2.10E+00 0.00E+00 0.00E+00 2.10E+00 0.00 %
Am-241 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
Cm-242 0.00E+00 2.09E-02 0.00E+00 0.00E+00 2.09E-02 0.00 %
Cm-243/44 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
U-233/34 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
U-238 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
Totals 0.00E+00 6.84E+05 0.00E+00 0.00E+00 6.84E+05 100.00 %
No Mechanical Filter Shipments were made during the first, third and forth quarters of 1998.
Tc-99 and 1-129 represent Minimum Detectable Activity (MDA) values.
These two nuclides are in units of uCi/ gram from Rad Calc #98-001-R.
Note: H-3, C-14, Tc-99, and I-129 were required to be manifested per 10 CFR 20, Appendix G.
l 1998 DAEC Annual Radioactive Material Release Report Page 9
SUMMARY
OF RADIOACTIVE SOLID WASTE (January 1,1998 - December 31,1998)
MAJOR NUCLIDE COMPOSITION SPENT RESIN Principle 1st QTR 2nd QTR 3rd QTR 4th QTR Total Percent Nuclide (MBq) (MBq) (MBq) (MBq) (MBq) Abundance H-3 6.18E+02 1.13E+03 7.73E+02 0.00E+00 2.52E+03 0.03 %
C-14 5.54E+02 2.35E+03 1.97E+03 0.00E+00 4.87E+03 0.05 %
Cr-51 0.00E+00 3.26E+05 0.00E+00 0.00E+00 3.26E+05 3.58 %
Mn-54 1.04E+05 - 3.44E+05 2.42E+05 0.00E+00 6.90E+05 7.57 %
Fe-55 6.36E+05 2.37E+06 1.97E+06 0.00E+00 4.97E+06 54.58 %
Fe-59 0.00E+00 9.65E+04 0.00E+00 0.00E+00 9.65E+04 1.06 %
Co-58 0.00E+00 8.55E+04 0.00E+00 0.00E+00 8.55E+04 0.94 % l Co-60 1.79E+05 4.53E+05 3.81 E+05 0.00E+00 1.01 E+06 11.12 % !
Zn-65 4.40E+04 1.12E+06 6.44E+05 0.00E+00 1.81 E+06 19.87 %
Ni-59 9.07E+01 2.31 E+02 1.94E+02 0.00E+00 5.15E+02 0.01 %
Ni-63 722E+03 2.77E+04 2.33E+04 0.00E+00 5.82E+04 0.64 %
Sr-90 7.29E+00 1.76E+01 1.20E+01 0.00E+00 3.69E+01 0.00 %
Tc-99 1.79E-06 3.58E-06 1.79E-06 0.00E+00 MDA MDA Ru-106 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
l-129 6.52E-06 1.30E-05 6.52E-06 0.00E+00 MDA MDA Cs-134 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
Cs-137 1.05E+04 2.35E+04 1.61 E+04 0.00E+00 5.01 E+04 0.55%
Pu-238 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
Pu-239/40 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
Pu-241 4.37E+00 1.26E+01 8.58E+00 0.00E+00 2.55E+01 0.00%
Am-241 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
Cm-242 4.29E-02 1.44E-01 9.73E-02 0.00E+00 2.85E-01 0.00 %
Cm-243/44 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00%
U-233/34 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+ 00 0.00 %
U-238 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00 %
0.00 %
Totals 9.82E+05 4.85E+06 3.28E+06 0.00E+00 9.11 E+06 100.00 %
No Resin Shipments were made in the forth quarter of 1998.
Tc-99 and I-129 represent Minimum Detectable Activity (MDA) values.
These two nuclides are in units of uCi/ gram from Rad Calc #98-001-R.
Note: H-3, C-14, Tc-99, and 1-129 were required to be manifested per 10 CFR 20, Appendix G.
1998 DAEC Annual Radioactive Material Release Report Page 10
1 1
SUMMARY
OF METEOROLOGICAL DATA i The following pages are a summation of meteorological data accumulated during the calendar year 1998 by the MIDAS (Meteorological Information and Dose Assessment System) at the Duane Arnold Energy Center. l 1
)
Stability Class tables include wind speed, wind direction, and stability class at the specified sensor height (33 feet or 156 feet). A summary table of all stability classes at i each height is also included. i Data recovery for atmospheric stability, wind speed, and wind direction was greater than 93% at both 33 feet and 156 feet.
Stability Class Data 33' TEMPERATURE DIFFERENCE DEG.F/100 FT l TABLE GREATER THAN LESS THAN OR EQUAL TO i 1 ...... 1.045 2 -1.045 -0.935 3 0.935 -0.825 4 -0.825 0.275 5 -0.275 0.825 6 0.825 2.200 l 7 2.200 ...... '
8 ALL LAPSE GROUPS IN ONE TABLE l l
HOURS AT EACH WIND SPEED AND DIRECTION l PERIOD OF RECORD = 98010101 98123124 l STABILITY CLASS: ALL DT/D2 l ELEVATION: SPEED:WS33 DIRECTION:WD33 LAPSE: DEL T WIND.
WIND SPEED (MPH) )
I DIRECTION 1-3 47 8 12 13 18 19 24 >24 TOTAL N 39 97 105 33 12 0 291 NNE 43 104 86 63 8 0 314 NE 99 258 184 79 7 0 658 ENE 85 164 135 40 1 0 475 E 117 166 96 6 0 0 457 1 ESE 99 189 80 10 0 0 426 SE 107 267 109 18 0 0 544 SSE 113 258 123 19 2 0 566 S 173 427 278 56 7 0 1007 SSW 150 233 188 62 8 1 691 SW 115 143 76 33 2 3 427 WSW 102 113 40 18 1 7 331 W 55 93 95 52 14 7 350 WNW 38 155 121 76 10 0 419 NW 36 214 190 56 10 1 526 NNW - 18 195 341 113 28 0 709 TOTAL 1389 3076 2247 734 110 19 8191 PERIODS OF CALM (HOURS): 616 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 569 i
HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 98010101 98123124 1998 DAEC Annual Radioactive Material Release Report Page 11
r-
~ 1 l
I STABILITY CLASS: A DT/DZ.
ELEUAT20N: SPEED:WS33 DIRECT 80N:WD33 LAPSE: DEL T
. WIND SPEED (MPH)
WIND DIRECTION. 13 47 8 12 13 18 19 24 >24 TOTAL
......... ... 1 N 1- 4 1 1 1- 0 .8 NNE 0 4 5 0 1 0 10 NE 2 5 12 4 1 0 24 ENE. 1 14 11 2 0- 0 30 ;
E 4 8 4 1 0- .0 17 l ESE- 3 7 5 1 0 0 16 j SE 7 21- 8 1 0 0 38 SSE 5 47 22 3 2 0 79 S 1 '57 46 8 0 0 113 :
SSW - 2 26' 38 10 3 0 79 SW - 3 11 10 2 0 0 26 WSW 0 10 9 4 0 0 23 W 0 3 10 8 2- 0 23 WNW 'O 1 3 7 0 0 11 NW 0 4 10 2 1 0 17 NNW' 1 7 9 14 0 0 31 TOTAL 30 229 203 68 11 0 545 PERIODS OF CALM (HOURS): 616 j VARIABLE DIRECTION 0 l
HOURS OF MISSING DATA: 569 1 SITE: DUANE ARNOLD. 03/16/99 11:05 HOURS AT EACH WIND SPEED AND DIRECTION
' PERIOD OF RECORD = 98010101-98123124 STABILITY CLASS: .B DT/DZ ,
--ELEVATION: SPEED:WS33 DIRECTION:WD33 LAPSE: DEL T )
................................................................ 4 WIND SPEED (MPH)
WIND i DIRECTION 13 47 8 12.13-18 19 24 >24 TOTAL l N 0 5 0 1 0 0 6 NNE 1 1 6 1 0 0 9
. NE 0 2 7 0 0 0 9 ENE 0 4 2 1 0 0 7 E 3 4 1 0 0 0 8 ESE 3 2 5 0 0 0 10 ,
SE 3' 7 3 0 0 0 13 l SSE' 0. 9 3 0 0 0 13 S 2- 13 11 1 0 0 28 I SSW 2 13 3 0 0 0 18 SW 0 5 6 8 0 0 19 WSW '1 4 3 1 0 0 9 W 1 1. 11 5 2 0 20 WNW 0 3 3 4 0 0 10
~ NW 0 1 -10 3 :3 0 17 NNW 0- 0 '7 9 0 0 16 TOTAL 16 17 4 81 34 5 0 212 PERIODS OF CALM (HOURS): 618 VARIABLE DIRECTION O l HOURS OF MISSING DATA: 569 i
p 1998 DAEC Annual Radioactive Material Release Report Page 12 I
SITE:'DUANE ARNOLD 03/16/99 11:05' PERIdD'0FRECORD 980 19 2 2 STABILITY CLASS: .C DT/DZ . I ELEVATION: SPEED:WS33 DIRECTION:WD334 LAPSE: DEL T WIND SPEED (MPH)
< WIND:
{
427'81213181924' D2RECTION-1 13 >24 TOTAL N .0 1 4 0 -0 0 5 !
NNE 1 0 2 .1. 1 'O 5 NE- 3 9 8i 3 0 0 23 ENE O- 8 8 2 0 0 18 E 1 4 9 0 0 0 15 ESE 1 .6 0 1 0' 0 8 SE 0 6- 5 0 'O 0 11 1' -0 'O' SSE 7 2 0 10 S 1 '8 12 : 2 1 0 24 .I SSW -0 9 5 2- 0 0 16 l SW 2 9 8 4 0 0 23 WSW 'O 6 1 2- 0 0 9 W 1 2 'S 2 0 0 10 WNW 2 3 12 5 0 0 22 j NW 'I 6 12 4 0 .0 23
.NNW 0 7 11 5 0 0 23 TOTAL 14 . 91 104 33 2 0 245 q
.............................................................. \
PERIODS OF CALM (HOURS): 616 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 569 k
SITE:'DUANE ARNOLD 03/16/99 11:05
.. HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 98010101 98123124 STABILITY CLASS: D DT/DZ ELEVATION: SPEED:WS33 DIRECTION:WD33 LAPSE: DEL T WIND SPEED (MPH)
WIND D8RECTION 1-3 47 81213181924 >24 TOTAL N -9 55 72 20 4 0 161 NNE 10 49 60 45 0 0 172 NE 14 120 100 60 5 0 302
-ENE: 20 80 88 34 1' 0 226 E' 37 99 70 4 0 0 214 ESE 18 96 42- 5 0 0 165 SE 19 109 57 11 0 0 200 SSE 21 84 31 7 .0. 0 148 S 26 114' 61 13 4 0 219 SSW 25 62 60 25 5 0 180 SW - 20 41 24 14 0 3 104 WSW 19 '42 17 7 0 5 92
- W 10 41 49- 32- 9 7 149 WNW . 10 65 77. - 52 10 0 219 NW .16 95 - 123 41 5 1 287 f##4 10 102 237 78- 26 0 455 TOTAL' 284 1254 1168 448 75 16 3293-
-PERIODS OF CALM (HOURS): 616
. UARIABLE DIRECTION 0
. HOURS OF MISSING DATA: 569 SITE: DUANE ARNOLD 03/16/99 11:05 1998 DAEC Annual Radioactive Material Release Report Page 13
y HOURS AT EACH WIND SPEED AND DIRECTION PERIDD OF RECORD e- 98010101 98123124
, STABILITY CLASS: E DT/DZ
~~ ELEVATION: SPEED:WS33 DIRECTION:WD33 LAPSE: DEL T WIND SPEED (MPH)
WIND _ .
DIRECTION 13 47 81213181924 >24 TOTAL N 19 32- 28 - '10 5 0 97 NNE 16 45 9 14 0 6 87 NE' 18 56 49 11 0 0 140 ENE 14 44 26 1 0 0 94 E 31 48 12. 1 0 0 106 ESE 40 71 28 3 0 0 158 SE 38 118 36 6 0 0 203 CSE 32 91 64 9 0 0 211 S 50 194 ~147 32 1 0 438 SSW 36 ' 95 82 25 0' :1 248 SW 19 42 27 5' 2 0 105 WSW: 16 27 8 4 1 2 64 W .19 ' ,35 19 5 0 0- 87 i WNW . 11 61 25 8 0 0 111 NW 14 98 34 6 1 0 156 NNW 7 70 75 7 1 0 168 TOTAL 380 1125 669 147 11 3 2473 PERIODS OF CALM (HOURS): 616 VARIABLE DIRECTION 'O.
HOURS OF MISSING DATA: 569
. SITE: DUANE ARNOLD 03/16/99 11:05 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 98010101 98123124 STABILITY CLASS: F DT/DZ ELEVATION: ' SPEED:WS33 DIRECTION:WD33 LAPSE: DEL T i WIND SPEED (MPH)
WIND ~
DIRECTION 13 47 8 12 13 18 19-24 >24 TOTAL N 6- 0 0 0 0 0 7 NNE 9 5- 4 1 0 -0 20
.NE 29 35 5 1 1 0 79 ENE 15 6 0 0 0 0 30 E .14 4 0 0 0 0 27 ESE -16 4 0 0 0 0 26
~ SE 21 6 0 0 0 0 34^
SSE- 22 20 1 0 0 0 57 S 42 35 1 0 0 0 95 SSW 20 22 0 0 0 0 56 SW 13 23 1 0 0 0 50
' WSW 27 16. 2 0 0 0 55
'W 8 -9 1 0 0 0 25 WNW' 3 17 1 0 0 0 23 NW '3 9 1 0 0' 0 19 NNW , 0 8 2 .- 0 0 0 10 TOTAL' 248 219 19 2 1 0 613 PERIODS OF CALM (HOURS): 616
' VARIABLE DIRECTION. 0
. HOURS OF MISSING DATA: 569.
[ 1998 DAEC Annual Hadioactive Material Release Report Page 14 l
t
g; I'
r I
/
SITE: DUANE ARNOLD 03/16/99 11:03 ,
HOURS AT EACH WIND SPEED AND DIRECTION
[/
l
. PERIDO OF. RECORD =. 98010101 98123124 s STABILITY. CLASS: G DT/DZ
-' ELEVATION: SPEED:WS33 : . DIRECTION:WD33 LAPSE: DEL T-f' '
WIND SPEED (MPH) ]
WIND' I
' DIRECTION -ik3' 4-7 8 12 13 18 19 24 >24 TOTAL j, ......... ... ... .... ..... ..... ... .....
'4-N 0 0 1 2 0 7 .1 l-NNE 6 0- 0: 1 ~0 0 11 i NE 33 '31 3 0 0 0 81 ENE '35 8 0 0- 0 0 70 i E 27 1- 0 0 0 0 70 l .ESE' '18 3- 0 0 0 0 43 SE 19 :0 0- 0 0 0 45
.SSE - 32 0 0 0 0 0 -48
24 TOTAL
.N 39 97 105 33 12 0 291 NNE. 43 104 86 63 8 0 314 NE 99 258 184 79. 7 0 658 ENE 85 164 135 40, 1 0 475 E 117 166 96 6 0 0 457 ESE ' 99 189 80 10- 0 0 426 SE 107 267 109 18 0 0 544 SSE 113 258 123 19 2 0 566 S 173 427 278 56 7 0 1007 SSH .150 233 '188- 62 8 1 691
. SW 115 143 76' 33 21 3 427 WSW 102 113 40 18 1 7 331 W- 55 93 - 95 52 14 7 350
-WNW- '38' 155 121 76 10 0 419
, NW - 36 214 .190 56 10 1 526 L _ NNW 181 195 341 113 - 28 0 709 L
. TOTAL' 1389 3076 2247 =734 110 19 8191 PERIDDS OF CALM (HOURS): 616 VARIABLE DIRECTIDN. O HOURS OF MISSING DATA: 569
!4 1998 DAEC Annual Radioactive Material Release Report Page 15 i
t
Wind Rose 33' i
tirinLPRER*L. 4 l
e.
ge ', =
1 s #4WL l
. t )
- lj::t f ::jJ"Un'4""=M : :".
e g!, ,s.u.n.e.ggs, ;
.m. --a . 1 Fig re 133' VVind Rose (Direction From) j l
St:bility Class Data 156' TEMPERATURE DIFFERENCE DEG.F/100 FT TABLE GREATER THAN LESS THAN OR EQUAL TO 1 ...... 1.045 2 -1.045 0.935 3 0.935 0.825 4 0.825 0.275 5 0.275 0.825 6 ~0.825 2.200 7 2.200 ....-.
8 ALL LAPSE GROUPS IN ONE TABLE HOURS AT EACH WIND SPEED AND DIRECTION 1 PERIOD OF RECORD = 98010101 98123124 l
. STABILITY CLASS: ALL ~DT/DZ j ELEVATION: SPEED:WS156 DIRECTION:WD156 LAPSE: DEL T l WIND SPEED (MPH)
WIND DIRECTION 13 4-7 81213181924 >24 TOTAL N 54 100 107 90 16 7 374 NNE 51 164 214 140 39 1 610
- NE 41 113 170 78 20 0 422
.ENE 36 129 109 62 16 1 355 E 46 161 195 79 5 0 488 ESE 29 144 204 84 13 1 475 SE 41 180 295 81 18 1' 616 SSE 27 197 340 236 51 8 859 S 33 166 289 194 53 6 741 SSW 34 128 159 114 36 14 485 SW 32 110 ' 71 ' 45 20 13 291 WSW 20 107 91 34 8 6 266 l W> 34 100 125 75 38 20 392
'WNW' 31 135 199 111 38 3 517
- NW '35 124 373 197 24 7 760 -!
NNW : 47 93 202 162 13 17 534 l l TOTAL' 591 2151 3143 .1782 408 105 8185 l PERIODS OF CALM (HOURS): 5 l VARIABLE DIRECTION O HOURS OF MISSING DATA: 575 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 98010101 98123124 4 STABILITY CLASS: A DT/DZ !
l 1998 DAEC Annual Radioactive Material Release Report Page 16 i
I o.
W ,
_ V-ELEVATION: 1 SPEED':WS156 DIRECTION:WD156 LAPSE: DEL T WIND SPEED (MPH).
WIND . . . -
DIRECTION 1-3 ;4 7. 8 12 13-18 19.24.. >24 TOTAL
-N 1 2 11 ,'O 0 -2 ~16' NNE 1' 7 11- 4 2 0- 25 NE 1 7' '9 2 2 0 21-
'ENE. 3 10- '3 =1: 2 0 19
<E: 0 9: 5. 3 'O 0 17 ESE' ' .1 - 4 7- 2 10 0 .14-SE: 3- 22 40 7- 1 0 73 SSE 0 18 54 30 3 4 109
-S .0: 21 - 35 ' 34 10 1 101'
'SSW. 3 .3.. 10 9- '2 3 30 SW . 1 2 16 5 1 0 25
'WSW 1 6 4 7 1 2 21
'W- '1 1 5 10 '2 0 19 WNW 0' 1 6 7~ .1 0- 15 NW 0 2 9 14 1' 0 26 NNW O' 6 4 4 0- 0 14 TOTAL 16 121= 229 139- 28' 12 '545 PERIODS OF CALM (HOURS): 5 VARIA8LE DIRECTION '0-HOURS OF MISSING DATA: Si5
. . SITE:~ DUANE' ARNOLD 03/16/99 11:18 f
HOURS AT EACH WIND SPEED AND DIRECTION J PERIOD OF RECORD =. 98010101 98123124 l
- STABILITY CLASS: B .DT/DZ
- ELEVATION: - SPEED:WS156 DIRECTION:WD156 LAPSE: DEL T WIND SPEED (MPH)
WIND - ,
DIRECTION s13 '47 81213181924.- >24 TOTAL N. 0 1 0- 3- 0- 0 '4 .I
- NNE 1- 3, 11 0 0- 0 15 NE 0 2- 4 .0 0 'O 6 ENE 2 6 3 0 1 0 12 E O 3- 2 2 0 0 7 ESE- 1 1 4 2 0 0 8 SE 1 4 .7- ~1 0 0 13
~88E' 8 13 8 0 0 31- ,
'S- 1 ~3 15 2 0 .0
. 21- i
.SSW 0 1. 6 1 '4 0 :12 .
SW ' 0 4 4 6' 1 1 16 l WSW O' 'O 4 '2 . '1 0 7 W '0: .1 7 .5 '4 2 19 !
WNW O' 1- 4 3 5 0 13
> NW 0 1 :9 ~9 0 0 19 NNH - 0' -4~ 2 3 0 0 9 fTOTAL' 8 43 95 47 .16 3 212 PERIODS OF CALM (HOURS): .5 VARIABLE DIRECTION. ~ 0 !
HOURS OF MISSING DATA: 575 !
1998 DAEC Annual Radioactive Material Release Report Page 17 g
'x
yy
^
~ SITE: DUANE ARNOLD . 03/16/99 11:18
.. HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 98010101-98123124 STABILITY CLASS: C DT/DZ !
F ELEVATION: SPEED:WS156 DIRECTION:WD156 LAPSE: DEL T I L _
WIND SPEED (MPH)- J
--WIND I l DIRECTIO4' 1-3 47 8 12 13 18 19 24 '>24 TOTAL N 1; 2- 4 0' 0 1- -8 NNE .0 9 7 3 1 0 20 NE 1 4 9 3- 0 0 17 ENE 0 4 4 3 1 0 12
-E O 1 6 '3 1' 0 '11 4
~ESE 1 .. 4 2 0 0 0 7 I SE O 4 8 4 0 'O 16 SSE 0 5. 3 6 0 0 14 S 0 5 16 4 1 ,1 27 SSW D- 6- 7 5 4 0 22 !
SW 0 3 1- 2 4 0 10 WSW 0- 1 8 1 0 0 10 W: 1. 3 2 3 0 0 9
)
-7 WNW - 1 5 '9 '2 0 24 i NW '- 0 3 16- 6 1 0 26
- NNW 0 3 3 6 0 0 12
.............................................................. )
. PERIODS OF CALM (HOURS): 5 JVARIA8LE DIRECTION O.
j- HOURS OF MISSING DATA: 575
. SITE:,DUANE ARNOLD, 03/16/99 11:18 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD =1 98010101-96123124 STABILITY CLASS: D -DT/DZ ELEVATION: SPEED:WS156- DIRECTION:WD156 LAPSE: DEL T WIND SPEED (MPH)'
WIND-
. DIRECTION -13 47 8 12'13 18 19-24 >24 TOTAL N. .10 31 -48 48 8 2 '147 NNE 6 ~68 106 83 27~ 1' 291 NE- 11 44 87 60 17. 0 219 ENE 14' 67 62 ' 47 - 10 1 201 !
E - 11 . 74' B7 50 3 0 225 ESE '6 58 1 81 34 9 1 189 BE- 91 5 l2 79 23 11 ,1 175 SSE 8 58 76~ 48 13 2 205 4 S' 7 44 4 80 35 9 4 179 i SSW - 10 26 38~ 34 12 6 126 ;
- SH 7- 29. '18 18 10 9 91 !
-WSW 6 ~
38 27 - 11' 4 2 88 ,
W- 6: < 41: 63 40 25 17 192 WNW 14' 47 89 - 61 29 3 243 ,
NW . 5 70 184 ' 134 20 6 419 NNW -14 36 122 98 13 16 299 l1
-TOTAL 144 783 1247. '824 220 71 3289 PERIODS OF CALM (HOURS): 5.
.VARIA8LE DIRECTION- .0 HOURS OF MISSING DATA: 575 4
l l 1998 DAEC Annual Radioactive' Material Release Report Page 18 h,
I
- AMMA
k, l SITE:' DUANE ARNOLD 03/16/99 11:18 HOURS AT EACH WIND SPEED AND DIRECTION-PER100 0F RECORD = 98010101 98123124 STABILITY CLASS: E DT/DZ ELEVATION: SPEED:WS156 DIRECTION:WD156 - LAPSE: DEL T WIND SPEED (MPH)
' WIND DIRECTION 1 3.. '4 7- 8-12 13 18 19 24 ->24' TOTAL N 15- 37- 31 34 5 2' 124 NNE -- 13 30 49 40- 7 0 139 NE 5 23 L 36 - 13 1 0 78 ENE- 4 29 34- 11 2- 0 81
-E- 15- 46 77 21 1 0 160
'ESE 2 42 78 44 4 0 170 -
SE 1 26 106 43 6 0 182 ]
SSE 6 33 126 142 35. 2 344 l S 6 - 29 101 113 33 0 282 i SSW 12 29 71 64 14 5 195 f SW 6 33- 17 14 4 3 77
.WSW' 1 30 29 11 2 2 75 W 5 25 27 11 7 1 76 WNW 7 33 '66 28 1 0 135 NW' 10 27 126 34 2 1 200
. NNW 15 25 ' 67 48 - 0 0 155 TOTAL 123 497 1041 671 124 16 2473 PERIODS OF CALM (HOURS): 5 VARIABLE DIRECTION 0.
- HOURS OF MISSING DATA: 575 SITE: DUANE ARNOLD 03/16/99 11:18 l
HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 98010101 98123124 STABILITY CLASS: F DT/DZ. i ELEVATION: SPEED:WS156 DIRECTION:WD156 LAPSE: DEL T WIND SPEED (MPH)
WIND D2RECTION 13 47 81213181924 >24 TOTAL N 3 18 5 2 0 0 28 NNE 7 26 14 7 2 0 56 NE ~ 8 10 13 0 0 0 31 ENE 3 9 2 0 0 0 15 E 6 14 10 0 0 0 31 ESE ~6 11 21 1- 0- 0 39 SE~ 6 19 18 3 0 0 46 SSE 5 16 33 1 0 0 55 S 9 10 26 6 0 0 51 SSW 1 26 22 1 0 0 50 SW 6 16 15 0 0 0 37 WSW 4 14 18 2 0 0 38-
"W 6 15 15 4 0 0 40 WNW D 16' 12 3 0 0 31 NW 6 12 20 0 0 0 38
- NNW 7~ 14 1 3 0 0 25 TOTAL 83' ~246 .245 33 2 0 611
' PERIODS OF CALM (HOURS): 5 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 575 1998 DAEC Annual Radioactive Material Release Report Page 19
"S , 1 i
i 1
SITE: DUANE ARNOLD 03/16/99 11:18' HOURS AT EACH WIND SPEED AND DIRECTION
.-PERIOD OF RECORD =- 98010101 98123124 4 f
STABILITY CLASS: 0 DT/DZ' {
ELEVATION: SPEED:WS156 DIRECTION:WD156 LAPSE: DEL T WIND SPEED (MPH)
WIND '
DIRECTION 1-3 4-7 8 12 13 18 19 24 ~>24 TOTAL j N 24- 9 8 3 3 0 47 !
NNE 23 21 16 3 0 0 64 NE 15 23 12 0 0 0 50 l ENE. 10 .4 1 0 0 0 15 i E 14 14 8 0 0 0 37 ESE 12 ' 24 11 1 0 0 48 SE 21 53 37 0 0 0 111 SSE 6 59 35 1 0 0 101 S < 10 54 16 0 0 0 80 SSW- '8 37 5 .0 0 0 50 -
SW 12 23 0 0 0 0 35 WSW' 8 18 1 0 0 0 27 W 15 14 6 2 0 0 37 l WNW 9 32 15 0 0 0 56 NW 14 9 9 0 0 0 32 1 NNW' 11 5 3 0 0 1 20 l
.............................................................. i TOTAL 212 399 183. 10 3 1 810 I PERIODS OF CALM (HOURS): 5
, VARIABLE DIRECTION 0 i HOURS OF MISSING DATA: 575 l
p S8TE: DUANE ARNOLD- 03/16/99 11:18 j
\
l l
HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 98010101-98123124 l STABILITY CLASS: ALL DT/DZ
- ELEVATION
- SPEED:WS156 DIRECTION:WD156 LAPSE: DEL T
................................................................ l WIND SPEED (MPH)
WIND
-DIRECTION 1-3 4-7.81213181924 >24 TOTAL l N 54 100 107 90 16 7 374 l NNE 51 164 214 140 39' 1 610
! NE- . 41 113 170 78 20 0 422.
l ENE 36 129 109 62 16 1 355 E 46 161 195 79 5 0 488
'ESE 29 144 204 84 13 1 475
' SE 41 180 295 81 18 1 616
.SSE 27 197 340 236 51 8 859 S . 33 166 289 194 53 6 741 SSW 34' 128 159 114 36 14 485 SW 32 110 71 45 20- 13 291 WSW 20 107 91- 34 8 6 '266 W, 34 100- 125 75 38 20 392 WNW' ~ 31 '135 199 111 38 3 517 NW r 35 124 373' 197 24 7 760 NNW 47- 93 202 162 13 -17 534 TOTAL 591 2151 3143 1782 408 105 8185 PERIODS OF CALM (HOURS): 5 VARIABLE DIRECTION' O
, HOURS OF MISSING DATA: 575 1998 DAEC Annual Radioactive Material Release Report Page 20 L-.
1 F
-Wird Rose 156' - )
1 mrrJ:.rm .
,s.
i q w,
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~ -> =_= =,a =
id, .mur (m.,
Figure 2156' Wind Rose (Direction From)
ATTACHMENTS 1 & 2:
SUMMARY
OF CHANGES TO THE ODAM J
Two revisions of the Offsite Dose Assessment Manual (ODAM) were released in 1998. All alterations implemented with Revision 10 were related to the implementation of the Improved Technical Specifications.
Revision 10 became effective on July 22"d 1998.
l Plant Modification #EMA-A28097 removed the " Auto-isolate" feature from the ventilation system in the Low Level Rad. Waste Storage and Processing Facility Building (LLRSPF). Reference to this feature was removed from Revision 11 of the ODAM. Revision 11 became effective on August 31,1998.
Details about the changes to the ODAM are found in Attachments 1 and 2.
ATTACHMENT 3: CURRENT REVISION OF THE ODAM i
I f.
1998 DAEC Annual Radioactive Material Release Report Page 21
ODAM Revisions Revision 9 to Revision 10 l
Table of Contents l REMOVAL OF REFERENCE TO EXISTING TECH SPECS. 2 Generic References to Tech Spec Sections 2 j Section 6.0 Reporting Required by Tech Specs 2 j Section 6.1.4.1 Liquid Waste Treatment Section 6.l.3.1 Dose Due to Radioactive Effluents j Section 6.2.3.1 ACTIONS section f Section 6.2.4.1 ACTION Section Section 6.2.5.1 ACTION Section Section 3.6.1 Alternate Methods of Evaluating Compliance Section 6.4.3 Changes to the ODAM MOVE MATERIAL FROM CURRENT TECH SPECS TO ODAM 5 Radiation Monitoring Instruments not currently described in ODAM 5 Introduction j I
Tech. Spec.~ Section 3.2.D Tech Spec. Section 4.2.D Radiation Monitors Bases Liquid Holdup Tanks and Instrumentation 10 Tech Spec. Sections 3.14.A and 4.14.A regarding Hold Up Tanks was moved to the ODAM.
Tech Spec. Section 3.14.B and 4.14B covering Liquid Holdup Tank Instrumentation was moved to the ODAM.
Tech Spec. Section 3.14.A,4.14A,3.14.B,4.14B about Liquid Holdup Tank BASES was moved to the ODAM.
REMP Program 13 Tech Spec. Section 6.9.4.b was moved to the ODAM.
Describe the Radioactive Effluent Controls Program 14 ODAM Rev.10 New Chapter 8 Mechanical Vacuum Pump Rad Release Rate 15 ,
ODAM Rev 10 New Section 6.1.7- l l
Unique Reporting Requirements . 15 i ODAM Rev 10 Re-numbered Section 6.4.3 : )
l l
ODAM Revisions: Rev 9-10 Removal of Reference to Existing tech specs. Attachment 1 - Page 1
m l
Removal of Reference to Existing tech specs. l Generic References to Tech Spec Sections
. Section 6.0 Rev 9:
The introduction to section 6 of the Offsite Dose Assessment Manual Rev 9 previovely read:
Section 6.0 of the ODAM provides the radiological effluent and l environmental controls and surveillance requirements previously located in Technical Specification sections 3.14, 3.15 and 3.16 and 3
the administrative reporting requirements previously located in :
Technical Specification sections 6.11.1.f and 6.11.1.g. j Changes to the ODAM shall be processed in accordance with the requirements of Section 6.4.3 and Technical Specification 6.14.1.
Rev 10:
1 Section 6.0 The introduction to section 6 of the Current Tech Specs was changed to:
Section 6.0 of the ODAM provides radiological effluent and environmental controls, I surveillance and the administrative reporting requirements for the Duane Arnold Energy Center,
)
j Changes to the ODAM shall be processed in accordance with the requirements the Technical l Specifications and the ODAM, section 6.4.4. i Reporting Required by Tech Specs Section 6.1.4.1 Liquid Waste Treatment Rev. 9:
. ( 6 .1. 4 .1)
APPLICABILITY: At all times.
ACTIONS:
a) With radioactive liquid waste being discharged without treatment and in excess of the above limit, prepare and submit to the Commission within 30 days, pursuant to Technical Specification ;
6.11.3, a Special Report,.in lieu of any other report, which )
includes the following information:
Rev 10:
(6.1.4.1)
APPLICABILITY: At all times.
ACTIONS:
c a) ' With radioactive liquid waste being di^arged without treatment and in excess of the above limit, prepare and submit to tL Lommission within 30 days, pursuant to the ODAM, section 6.4.3, a Special Report, in lieu of any other report, which includes the following information:
ODAM Revisions: Rev 9-10 Removal of Reference to Existing tech specs. Attachment 1 - Page 2
p 1 i
Section 6,1.3J D:se Due to Rrdiz:ctive Emuents j 7-
' Rev 9: ~
ACTION:
- a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding the above limit, prepare and submit to the Commission within 30 days from the end of the quarter I during which the release occurred, pursuant to Technical Specification 6.11.3, and in lieu of any other report, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken.
Rev 10:
ACTION: j
- a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding the above limit, prepare and submit to the Commission within 30 days from the end of the quarter during which the release occurred, pursuant to the ODAM section 6.4.3, {
and in lieu of any other report, a Special Report which identifies the cause(s) for i exceeding the limit and defines the corrective actions to be taken. l Section 6.2.3.1 ACTIONS section 1
Rev. 9: i l
- a. If the calculated air dose from radioactive noble gases in gaseous )
effluents exceeds either of the above limits prepare and submit a Special Report to the Commission within 30 days following the end of the calendar quarter during which the release occurred. The Special Report shall be pursuant to Technical Specification 6.11.3, shall be in lieu of any other report, and shall identify the cause(s) for exceeding the limit and define the corrective actions taken.
. Rev 10::
- a. If the calculated air dose from radioactive noble gases in gaseous effluents exceeds either ,
of the above limits prepare and submit a Special Report to the Commission within 30 days !
following the end of the calendar quarter during which the release occurred. The Special Report shall be pursuant to the ODAM, section 6.4.3, shall be in lieu of any other report, and shall identify the cause(s) for exceeding the limit and define the corrective actions taken.'
Section 6.2A.1 ACTIONSection Rev. 9:
- a. With the calculated dose from the release of I-131, I-133, H-3, and radionuclides in particulate' form having half-lives greater than eight days in gaseous effluents exceeding the above limit, prepare and submit a Special Report to the Commission within 30 days following the end of the calendar quarter during which the release occurred. The Special Report shall be made pursuant to Technical Specification 6.11.3, shall be in lieu of any other i report, and shall identify the cause(s) for exceeding the limit
- and define the corrective actions taken.
i t
ODAM Revisions: Rev 9-10 Removal of Reference to Existing tech specs. Attachment 1 - Page 3
Rev 10:
I
- a. With the calculated dose from the release of I-131,1-133, H-3, and radionuclides in I particulate form having half-lives greater than eight days in gaseous effluonts exceeding the above limit, prepare and submit a Special Report to the Commission within 30 days following the end of the calendar quarter during which the release occurred. The Special Report shall be made pursuant to the ODAM, section 6.4.3, shall be in lieu of any other report, and shall identify the cause(s) for exceeding the limit and define the corrective actions taken.
i Section 6.2.5.1 ACTIONSection {
l Rev. 9: '
- a. If gaseous wastes are discharged for more than 7 days without ]
treatment, prepare and submit a Special Report to the Commission within 30 days pursuant to Technical Specification Requirements, in lieu of any other report, including the following information: i Rev 10:
- a. If gaseous wastes are discharged for more than 7 days without treatment, prepare and submit a Special Report to the Commission within 30 days pursuant to the ODAM, section 6.4.3, in lieu of any other report, including the following information:
Section 3.6.1 Alternate Methods of Evaluating Compliance Rev. 9:
The derivation and basis of the effective gamma air dose conversion factor are provided in Appendix B. Values of the effective factors are tabulated in Table 3-3. By inserting the appropriate values for Dg (5 mrad / quarter g-air dose) and for Age.re (1.6 x 10'** mrad /yCi) or Ag,, , , (6.4 x 10 mrad / (pCi sec/m )) into the equation above and 3
solving for either (DQ 3 ) s or (DQ ) 3 v, respectively, release quantities of noble gases from either the stack or vent corresponding to the technical specification limit of 5 mrad / quarter (total for all release points) may be determined. At the location, 1260 meters NNW of the station, (which is the controlling location based on reference meteorology) the release limits are individually.....
Rev.10:
The derivation and basis of the effective gamma air dose conversion factor are provided in Appendix B. Values of the effective factors are tabulated in Table 3-3. By inserting the appropriate values for Dg (5 mrad / quarter g-air dose) and for Ag (1.6 x 10-" mrad /pCi) or Ag,,,(6.4 x 104 mrad /(pCi sec/m )) into the equation above and solving for either (DO,)s or (DO,)v, respectively, release quantities of noble gases from either the stack or vent corresponding to a limit of 5 mrad / quarter may be determined. The limit of 5 mrad /quarteris describedin section 6.2.3 andis for the totalof allrelease points. At the location,1260 meters NNW of the station, (which is the controlling location based on reference meteorology) the release limits are individually..
ODAM Revisions: Rev 9-10 Removal of Reference to Existing tech specs. Attachment 1 - Page 4
, Sectia 6A3 Chnges to the ODAM Rev. 9:
6.4.3 Changes to the ODAM
- a. Shall be documented and records of reviews performed shall be retained as required by Technical Specification 6.10.2.14. This documentation shall contain:
Rev 10:
6.4.3 Changes to the ODAM
- a. Shall be documented and records of reviews performed shall be retained for the duration of the facility operating license. This documentation shall contain:. .
Move Material from Current Tech Specs To ODAM Radiation Monitoring instruments not currently described in ODAM Introduction Tech Spec Sections 3.2D and 4.2D were moved to the ODAM as were Associated Tables 3.2D and 4.2D.
These sections of the Tech Specs describe Offgas Pre-Treatment and Post-Treatment Monitors and the Main Steam Line Radiation Monitors. In addition to moving the requested sections the information included in the Bases section of the Tech Specs was moved to the corresponding Bases section of the ODAM.
Tech. Spec. Section 3.2.D Tech Spec 3.2.D described Limiting Conditions For Operation and Surveillance Requirements for radiation monitoring equipment.
Tech Spec 3.2.D referred to table 3.2-D which Described operating CONTROLS for the plant's Radiation Monitoring Instrumentation. This table included requirements for the Offgas Post-Treatment Radiation Monitors , the Offgas Pre-Treatment Radiation Monitors and the Main Steam Line Radiation Monitors.
Tech Specs:
Section 3.2.D and Table 3.2-D:
LIMITING CONDITIONS FOR OPERTION D. RADIATION MONITORING INSTRUMENTATION
- 1. The Radiation Monitoring instrumentation channels shall be OPERABLE as shown in Table 3.2-D.
Applicability: as shown in Table 3.2-D.
Actions
- a. With one or more radiation monitoring channels inoperable, take the ACTION required by Table 3.2-D
- 2. In the event the noble gas flow in the air ejector exceeds the equivalent of 1.0 Ci/see after 30 minutes delay in the offgas holdup line as indicated on the offgas pre-treatment radiation monitor, restore the rate to less than the limit within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
New Tech Spec SR 3.7.6.1 ODAM Revidons: Rev 9-10 Move Material from Current Tech Specs To ODAM Attachment 1 - Page 5
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Actsome 51 - estth e.he samber of MBRAtt.8 channele lose them required by tige seialaus Chestsele operable reigatrement, games frans the steen air ejector effees eretoa ser te re3ested for up to 30 days mi'n'Le MetMa'1M.*!#*2tWomn"sua*LM* ht!!M',*L'im fe*M mt.,
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ODAMRev 10:
6/7.2 Radioactive Gaseous Effluent Controls and Surveillance Requirements 6.2.1 Radioactive Gaseous Effluent Instrumentation CONTROLS 6.2.1.1 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 6.2-1 shall be OPERABLE. Their radioactive noble gas monitor alarm setpoint shall be set to cause automatic alarm when the limits of Section 6.2.2.1 are exceeded.
APPLICABILITY: As shown in Table 6.2-1 ACTION:
- a. When a radioactive gaseous effluent monitoring instrumentation channel alarm setpoint is less conservative than a value which will ensure that the limits of 6.2.2 are i
met, adjust without delay to meet Section 6.2.1, declare the channel inoperable, or I
immediately suspend any release via the instrumented pathway.
- b. When less than the minimum required gaseous effluent monitoring instrument channels are OPERABLE, take the ACTION stated in Table 6.2-1 and make every reasonable effort to restore the instrument to operable status. In the event the minimum required instrumentation is not returned to OPERABLE status within 30 days, explain in the next Annual Radioactive Matenal Release Report, in lieu of any other report, why the instrument was not made OPERABLE in a timely manner.
6.2.1.2 The radiation gaseous monitoring instrumentation channels shall be OPERABLE as shown in Table 6.2-2.
ODAM Revisions: Rev 9-10 Move Material from Current Tech Specs To ODAM Attachment 1 - Page 6
APPLICABILITY: As shown in Table 6.2-2 ACTION:
- a. With one or more radiation monitoring channels inoperable, take the ACTION required i by Table 6.2-2.
TABLE 6.2-2 RADIATION MONITORING INSTRUMENTATION Instrumentation Applicable Minimum Alarm / Trip Valve (s) Action Channe!s Operating Modes Setpoint Operated Operable by Signal Offgas Post-Treatment (a) 50 1 When the Offgas (a)
Radia ion system is operating Offgas Pre-Treatment (b) NA 51 1 When the Offgas Ra on system is operating (a) The monitors shall be set to initiate immediate closure of the charcoal bed bypass valve and the air ejector offgas isolation valve at a setting equivalent to or below the dose rate limits in ODAM Section 6.2.2.1.
(b) The monitors shall be set to initiate an alarm if the monitor exceeds a trip setting equivalent to 1.0 Ci/sec of noble gases after 30 minutes delay in the offgas holdup line.
ACTION 50 With the number of OPERABLE channels less than required by the Minimum Channels Operable requirement, gases from the steam air ejector offgas system may be released to the environment for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided (1) the charcoal bed of the offgas system is not bypassed, and (2) the offgas stack noble gas activity monitor is operable.
ACTION 51 With the number of OPERABLE channels less than required by the Minimum Channels Operable requirement, gases from the steam air ejector offgas system may be released for up to 30 days provided: (1) the charcoal bed of the offgas system is not bypassed, and (2) grab samples are collected and analyzed weekly, and (3) the offgas stack noble gas activity monitor is OPERABLE or at least 1 post-treatment monitor is OPERABLE. Otherwise be in HOT STANDBY within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
. Tech Spec. Section 4.2.D Tech Spec 4.2.D described Surveillance Requirements for radiation monitoring equipment.
Tech Spec 4.2.D referred to table 4.2-D which Described operating Surveillance Requirements for the plant's Radiation Monitoring Instrumentation. This table included surveillance requirements for the Offgas Post-Treatment Radiation Monitors , the Offgas Pre-Treatment Radiation Monitors and the Main Steam Line Radiation Monitors.
"Old" Tech Specs:
Tech Spec section 4.2.D and Table 4.2-D:
SURVEILLANCE REQUIREMENTS D. RADIATION MONITORING INSTRUMENTATION 1 Each radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, CHANNEL CALIBRATION and SOURCE CHECK operations for the OPERATING MODES and the frequencies shown in Table 4.2-D.
ODAM Revisions: Rev 9-10 Move Material from Current Tech Specs To ODAM Attachment 1 - Page 7
E 1
l
- 2. LOGIC SYSTEM FUNCTIONAL TESTSD and simulated automatic operation of all channels shall be performed at least once per ,
operating cycle for the following:
- a. Steam Jet Air Ejector Offgsd Line Isolation.
- b. Steam Jet Air Ejector Charcoal Bed Bypass.
- c. Mechanical Vacuum Pump Trip and Isolation.
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ODAM Rev 10:
7.2.1 Radioactive Gaseous Effluent Instrumentation SURVEILLANCE REQUIREMENTS 7.2.1.1 Each radioactive gaseous effluent monitoring instrumentation channellisted in Table 7.2-1 shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 7.2-1.
7.2.1.2 The setpoints shall be determined according to the method described in the ODAM.
7.2.1.3 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per operating cycle for the following:
- a. Steam Jet Air Ejector Offgas Line Isolation
- b. Steam Jet Air Ejector Charcoal Bed Bypass J
ODAM Revisions: Rev 9-10 Move Material from Current Tech Specs To ODAM Attachment 1 - Page 8
p i TABLE 7.21 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS INSTRUMENT CHANNEla SOURCE CHANNEL CHANNEL REQUIRED b CHECK CHECK CALIBRATION FUNCTIONAL MODE TEST i
l l 1. Offgas Stack Monitoring System During release via l a.~ Noble Gas Activity Monitor D M Rc od this pathway
- b. lodine Sampler Cartridge W N.A. N.A. N.A.
- c. Particulate Sampler Filter . W N.A. N.A. N.A.
, d. Effluent Flow Measuring Device D N.A. R Q l e. Sample Flow Measuring Device i
D N.A. R Q !
I
- 2. Reactor Building Vent Monitoring System During release via l
- a. Noble Gas Activity Monitor D M Rc od this pathway
- b. lodine Sampler Cartridge W N.A. N.A. N.A.
I
- c. Particulate Sampler Filter W N.A. N.A. N.A.
- d. Effluent Flow Measuring Device D N.A. R Q
- e. Sample Flow Measuring Device D N.A. R Q
- 3. Turbine Building Ventilation Monitoring System During release via
- a. Noble Gas Activity Monitor D M Rc od this pathway
- b. lodine Sampler Cartridge W N.A. N.A. N.A.
- c. Particulate Sampler Filter W N.A. N.A. N.A.
- d. Effluent Flow Measuring Device D N.A. R Q l
- e. Sample Flow Measuring Device D N.A. R Q '
- 4. Low-Level Radwaste Processing and Storage During release via Facility Ventilation Monitoring System this pathway
- a. Noble Gas Activity Monitor D M Rc od l
- b. lodine Sampler Cartridge W N.A. N.A. N.A. I
- c. Particulate Sampler Filter W N.A. N.A. N.A. !
- d. Effluent Flow Measuring Device D N.A. R Q
- e. Sample Flow Measuring Device D N.A. R Q
- 5. Offgas Post-Treatment Radiation Monitors D M R Qe When the Offgas system is operating
- 6. Offgas Pre-Treatment Radiation Monitors- D M R Qe When the Offgas system is operating TABLE NOTAT. IONS a During releases via this pathway.
b instrumentation shall be OPERABLE and in service except that channels out of service are permitted for the purpose of required tests. checks, calibratons, and preventative maintenance without declaring the channel to be inoperable.
c The CHANNEL CAllBRATION shall include the use of a known radioactive source (traceable to foe NIST radiation measurement system or other acceptable non-NIST standards) positioned in a reproducible geometry with respect to the sensor and emitting beta and/or gamma radiation in the range rneasured by the channelin accord with established station calibration procedures AltemateY. after the initial calibration. noble gas activity monitors maybe calibrated by laboratory analyzed gas samples collected and analyzed per Table 7.2-2. Item A, 1
d The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:
10 Instrument indicr'es measured levels above tne alarm setpoint. I
( 20 C2 cult failure.
( 30 Instrument indicates a downscale failure.
! 40 Deleted. ,
e The CHANNEL FUNCTIONAL TEST for this instrument shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist
- a. Instrument indH:stes measured levels above the alarm / trip setpoint
- b. Instrument indicates a downscale failure.
- c. Instrument controls not set in operam mode.
I 1
[
ODAM Revisions: Rev 9-10 Move Material from Current Tech Specs To ODAM Attachment 1 - Page 9
Radiati:n M: nit:rs B:ses "Old" Tech Spec Bases:
A portion of the Tech Spec 4.2.D Bases section is included in ODAM 6.2.1/7.2.1 BASES, i
ODAM Rev 10:
6.2.1 and 7.2.1 BASES
l Two air ejector offgas post-treatment monitors are provided. They are designed so that an instrument failure l
gives a downscale trip or an inoperative trip. When both instruments reach an upscale trip point, or when one ;
reaches an upscale trip point and the other reaches a downscale trip point orinoperative trip, a trip is actuated. }'
The post-treatment monitors have three upscale trip setpoints, one (Hi) to initiate charcoal bed valve closure (CV-4124A open and CV-4134B closing to route offgas though the charcoal) and another (Hi-Hi-Hi) to initiate offgas system isolation valve (CV-1408) closure. The third trip point (Hi-Hi) is for alarm initiation and will initiate prior to the offgas isolation trip
- 2. Not used
- 3. Gaseous Effluents Assessments of dose required by Sections 7.2.3 and 7.2.4 to verify compliance with Appendix 1,Section IV are based on measured radioactivity in gaseous effluent...-- ... conditions during the period of release.
Liquid Holdup Tanks andInstrumentation Tech Spec. Sections 3.14.A and 4.14.A regarding IIold Up Tanks was moved to the ODAM.
4.14A of the "old" Tech. Specs contained a Surveillance Requirement limiting the amount of radioactive activity in tanks to 50 curies. This is achieved by sampling contents every 7 days when material is being added to the tank. In addition to the Limiting Conditions for operation and the Surveillance Requirements, the BASES for the Liquid Iloid Up tanks was copied to the ODAM.
"Old" Tech Specs:
LIMITING CONDITIONS FOR OPERTION SURVEILLANCE REQUIREMENTS 3.14 Radioactive Effluents 4.14 RADIOACTIVE EFFLUENTS 3.14.A Liquid Holdup Tanks
- 4.14.A Liquid Holdup Tanks 4 14.A.1 The Quantity of radioactive material contained in the 4.14.A.1 The quantity of unprotected outdoor tanks shall be limited to less than . radioactive material or equal to 50 Curies, excluding tritiun and dissolved or contained in the tanks shall entrained noble gases.(The liquid radwar.te storage tanks be determined to be within in the Low-Level Radwaste Processing and Storage Facility the 50 curie limit by are considered unprotected outdoor tanks.) analyzing a representative
.~ Applicability: At all times, sample of the tanks' contents at least once per 7 Action' days when radioactive
- c. With the quantity of radioactive material in the tanks materials are being added to exceeding the above limit, immediately suspend all a tank.
additions of radioactive material to the tanks, within 48
! hours reduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report,
- Tanks included in this specification are those outdoor tanks r.
I that are not surrounded by liners, dikes, or walls capable of holding the tanks' contents and that do not have tank overflows rnd surrounding area drains connected to the liquid radwaste treatment system.
ODAM Revisions: Rev 9-10 Move Material from Current Tech Specs To ODAM Attachment 1 - Page 10
r r
N ODAMRev 10:
l Section 3.14.A from the Tech Specs was moved into the new ODAM Section 6.1.5 (Limiting Conditions for I
Operation) and 4.14.A into the new ODAM 7.1.5 (Surveillance Requirements).
6.1.5 Liquid Holdup Tanks
- CONTROLS 6.1.5.1 The Quantity of radioactive material contained in the unprotected outdoor tanks shall be limited to less than or equal to 50 Curies, excluding tritium and dissolved or entrained noble gases.(The liquid radwaste storage tanks in the Low-Level Radwaste Processing and Storage Facility are considered unprotected outdoor tanks.)
APPLICABILITY: At all times.
ACTIONS:
- a. With the quantity of radioactive material in the tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tanks, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within' l the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report.
- Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.
7.1.5 Liquid Holdup Tanks SURVEILLANCE REQUIREMENTS 7.1.5.1 The quantity of radioactive material contained in the tanks shall be determined to be within the 50 curie limit by analyzing a representative sample of the tanks' contents at least once per 7 days when radioactive materials are being added to a tank.
Tech Spec. Section 3.14.B and 4.14B covering Liquid Holdup Tank Instrumentation was moved to the ODAM.
This is related to 3.14.A above. It is a Surveillance requirement for channel checks and calibrations as well as quarterly functional tests on the liquid hold up tank instrumentation.
. Tech Specs:
3.14.B Liquid Holdup Tank Instrumentation Liquid Holdup Tank 4.14.B 3.14.B.1 A minimum of one LLRPSF Sample Tank Level Instrumentation Indicating channel and one LLRPSF Surge Tank level indicating Channel shall be operable 4.14.B.1 Each liquid holdup tank level i instrument shall be demonstrated Applicability: At all times. OPERABLE by:
Actions a, With no channel operable, liquid additions to the tank a. Daily channel check during liquid may continuc for up to 30 days provide that the tank additions to the tank (s).
level is estimated during all liquid additions to the
- b. If the minimum required instrumentation is not returned !
to CPERABLE status within 30 days, prepare and submit c. A quarterly channel functional to the Commission within 30 days, pursuant to test.
]'
Specification 6.11.3 a special Report, in lieu if any other report, why the instrument was not made OPERABLE ,
in a timely manner.
i l' ODAM Rev 10:
6.1.6 Liquid Holdup Tank Instrumentation CONTROLS: J 6.1.6.1 A minimum of one LLRPSF Sample Tank LevelIndicating channel and one LLRPSF Surge Tank level Indicating Channel shall be operable.
ODAM Revisions: Rev 9-10 Move Material from Current Tech Specs To ODAM Attachment 1 - Page 11
APPLICABILITY: At all times.
ACTIONS:
- a. With no channel operable, liquid additions to the tank may continue for up to 30 days provided that the tank level is estimated during all liquid additions to the tank.
7.1.6 Liquid Holdup Tank Instrumentation SURVEILLANCE REQUIREMENTS:
7.1.6.1 Each liquid holdup tank levelinstrument shall be demonstrated OPERABLE by:
- a. Daily channel check during liquid additions to the tank (s).
- b. A Channel calibration once per 18 months.
- c. A quarterly channel functional test.
Tech Spec. Section 3.14.A,4.14A,3.14.H,4.14H about Liquid Holdup Tank HASES was moved to the ODAM.
In addition to the Limiting Conditions for operation and the Surveillance Requirements, the BASES for the Liquid Hold Up tanks should was moved to the ODAM.
Yech Specs:
3.14.A and 4.14.A BASES
- 1. Liquid Holdup Tanks The tanks listed in the specification include all liquid radwaste tanks in the Low-Level Radwaste Processing Facility (LLRPSF) . Because the LLRPSF is not seismically designed, these tanks are considered as outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank. contents.
Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of lo CFR 20, Appendix B to 20.1001 - 20.2401, Table 2, Column 2, at the nearest potable water supple in an unrestricted area.
3.14.B and 4.14.B BASES
- 1. Liquid Holdup Tank Instrumentation Instrumentation is expected to be OPERABLE and in service when required by Specification. An instrument may be removed from service voluntarily for the purpose of tests, checks, calibration, or preventative maintenance without declaring the channel inoperable.
ODAM Rev 10:
6.1.5 and 7.1.5 BASES
- 1. Liquid Holdup Tanks The tanks listed in the specification include all liquid radwaste tanks in the Low-Level Radwaste Processing Facility (LLRPSF). Because the LLRPSF is not seismically designed, these tanks are considered as outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tanks contents.
Restricting the quantity of radioactive material contained in the specified tanks provides assurance that in the event of an uncontrolled release of the tanks' contents, the resulting concentrations would be less than the limits of 10 CFR 20, Appendix B to 20.1001 - 20.2401, Table 2, Column 2, at the nearest potable water supple in an unrestricted area.
I 6.1.6 and 6.1.7 BASES
p Instrumentation is expected to be OPERABLE cnd in servica wh:n r;quir:d by Specific; tion. An instrument may be removed from service voluntarily for the purpose of tests, checks, calibration, or preventative maintenance without declaring the channel inoperable.
REMP Program Tech Spec. Section 6.9.4.h was moved to the ODAM.
[ 6.9.4 of the "old" Tech. Specs describes the Radiological Environmental Monitoring Program. This
- description was moved to the ODAM, Chapter 5. I l
Tech Specs:
6.9.4 The Following programs shall be established, implemented, and maintained:
- b. Radiological Environmental Monitoring Program f
A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the oDAM, (2) conform to the guidance of Appendix I to 10 cFR Part 50, and (3) include the following:
- 1) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the oDAM,
- 2) A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and
- 3) Participation in an Interlaboratory Comparison Program to ensure that independent checks on i the precision and accuracy of the measurements of radioactive materials in environmental I sample matrices are performed as part of the quality assurance program for environmental j monitoring.
l ODAM Rev.10, Chapter 5:
ODAM Chapter 5 was renamed: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM lt was split into two sections. One section contains a description of the program as found in the Current Tech Specs and the second section contains the information currently found in chapter 5.
~
' Chapter 5: I 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Section 5.0 of the ODAM provides a description of the Radiological Effluent Controls Program which was previously located in the Technical Specifications. This section also contains descriptions of the Environmental Sampling Program Station Locations. )
l 5.1 Radiological Environmental Monitoring Program l A prog am shall be provided to monitor the radiation and radionuclides in the environs of the plant.
The program shall provide:
(1) representative measurements of radioactivity in the highest potential exposure pathways, (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.
,- The program shall:
p (1) be contained in the ODAM,
! (2) conform to the guidance of Appendix I to 10 CFR Part 50, I
(3) include the following:
a) Monitoring, sampling, analysis, and reporting of radiation and radionuclides in l the environment in accordance with the methodology and parameters in the ODAM.
ODAM Revisions: Rev 9-10 Move Material from Current Tech Specs To ODAM Attachment 1 - Page 13
b) A Ltnd Us3 CInsus to ensura that chrng:s in th3 us3 of crus at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census.
c) Participction in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
5.2 SAMPLING STATION LOCATIONS Sampling station locations identified in Table 5-1 correspond to the minimum required number of radiological environmental monitoring program sampling stations in Table 6.3-1. Environmental monitoring locations are shown on Figures 5-1 and 5-2. DAEC may conduct auditional environmental monitoring exclusive of Specifications 6.3.2 and 6.4.2. j l
' Describe the Radioactive Effluent Controls Program l A description of the Radioactive EfUuent Controls Program previously located in Tech specs was added to the ODAM Rev.10. A new chapter 8 was added: l ODAM Rev.10 New Chapter 8 DESCRIPTION OF THE RADIOACTIVE EFFLUENT CONTROLS PROGRAM This program, conforming to 10 CFR 50.36a, provides for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable.
The program shall be contained in the ODAM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements.
- a. Limitations on the functional capacity of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODAM;
- b. Limitations on the concentrations of radioactive material released in liquid effluents from the site to i unrestricted areas, conforming to ten times (10x) the concentrations listed in Appendix B, Table 2, -)
Column 2 to 10 CFR 20.1001 - 20.2402;
)
- c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents pursuant to 10 CFR 20.1302 and with the methodology and parameters in the ODAM conforming to 10CFR50, Appendix 1;
- d. Limitations on the annual and quarterly doses or dose commitment to a member of the I public from radioactive materials in liquid effluents released to unrestricted areas; 1
- c. Determination of cumulative and projected dose contributions from radioactive effluents for the l current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODAM at least every 31 days;
- f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems which were used to establish compliance with the design objectives in 10 CFR 50, Appendix 1, Section 11 be used when specified to provide reasonable assurance that releases of radioactive materialin liquid and gaseous effluents be kept as low as reasonably achievable;
- g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary shall be limited to the following:
ODAM Revisions: Rev 9-10 Move Material from Current Tech Specs To ODAM Attachment 1 - Page 14
r s l
- 1. For noble gases less than or equal to a dose rate of 500 mrem /yr to the total body and less ;
! than or equal to a dose rate of 3000 mremlyr to the skin, and I
- 2. For iodine-131, lodine-133, tritium, and for all radionuclides in particulate form with half lives ,
> 8 days:; less than or equal to a dose rate of 1500 mrem /yr to any organ; i
- h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; ;
i
- 1. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, !
tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released to i creas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and J. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190. l l
Mechanical Vacuum Pump Rad Release Rate 1 A portion of Tech. Spee. Section 3.7.M described limiting conditions for operation of the Mechanical 4 Vacuum Pump that are related to the release rate of radioactivity was moved to the new ODAM section 6.1.7.
Tech Specs:
LIMITING CONDITIONS FOR OPERTION l M. Mech mical vacuum Pump j 1 }
- 2. During mechanical vacuum pump operation the release rate of gross activity except for halogens and particulates with half lives longer than eight days shall not exceed 1 curie /sec.
3.
ODAM Rev 10 New Section 6.1.7:
6.1.7 Mechanical Vacuum Pump Radiation Release Rate CONTROLS 6.1.7.1 During mechanical vacuum pump operation the release rate of gross activity except for halogens and particulates with half lives longer than eight days shall not exceed 1 curie /sec.
Unique Reporting Requirements Tech Spec 6.11.3 described unique and unusual reporting requirements. This section of the Technical Specs was removed with the implementation ofITS. Those sections of CTS section 6.11.3 that are relevant to the l
ODAM were moved from the Tech. Specs to the ODAM. ODAM Section 6.4.3 was re-numbered to 6.4.4.
i Tech Specs:
UNIQUE REPORTING REOUIREMENTS Special reports shall be submitted to the Director of Inspection and Enforcement Regional Office within the
! time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification.
ODAM Revisiens: Rev 9-10 Move Material from Current Tech Specs To ODAM Attachment 1 - Page 15
V lr.~t e-Re ctor v s 'l bas T weld c nd h 7 t ::f f cted z' n e met-1, tnt specimens ' (Specific: tion -4.6. A.2) . l
- b. deleted lc. Inservice: inspection:(Specification-4.6.G.).
I These two met by code requirementd j
- d. deleted e, deleted l
'f. deleted I 9- deleted
- h. Radioactive Liquid or Gaseous Effluent - calculated dose exceeding specified limit (ODAM Sections f 6.1.3, 6.2.3 and 6.2.4). l I
I. Of f-Gas System inoperable (ODAM Section 6.2.5) .
{
'i. Measured levels of radioactivity in an environmental sampling medium determined to exceed the reporting level values of ODAM Table 6.3-3 when averaged over any calendar quarter sampling period (ODAM Section 6.3.2.1).
- k. Annual dose to a MEMBER OF THE PUBLIC determined to exceed 40 CFR Part 190 dose limit (ODAM Section 6.3.1.1), j
- 1. Radioactive liquid waste released without treatment when activity concentration is equal to or greater than 0.01 pel/ml (ODAM Section 6.1.4.1).
H. Ex lobivelGas Honitorihig Inst' rum'entation'Inope'rablel (SpecifiNatkhn O.2.I.I)' . :i ' '
i
- n. Liquid Holdup Tank Instrumentation Inoperable (Specification 3.14.B.1).
Moved to TRM l ODAM Rev 10 Re-numbered Section 6.4.3 :
6.4.3 Special reports shall be submitted to the Director of Inspection and Enforcement Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below ,
pursuant to the requirements of the applicable reference specification. I
- 1. Radioactive Liquid or Gaseous Effluent - calculated dose exceeding specified limit (ODAM Sections 6.1.3,6.2.3 and 6.2.4).
- 2. Off-Gas System inoperable (ODAM Section 6.2.5).
- 3. Measured levels of radioactivity in an environmental sampling medium determined to exceed the reporting level values of ODAM Table 6.3-3 when averaged over any calendar quarter sampling period ;
(ODAM Section 6.3.2.1).
- 4. Annual dose to a MEMBER OF THE PUBLIC determined to exceed 40 CFR Part 190 dose 1imit (ODAM Section 6.3.1.1).
- 5. Radioactive liquid waste released without treatment when activity concentration is equal to or greater than 0.01 pei/mi(ODAM Section 6.1.4.1).
- 6. Liquid Holdup Tank Instrumentation inoperable (ODAM Section 6.1.6).
6.4.4 Changes to the ODAM., . . j l
ODAM Revisions: Rev 9-10 Move Material from Current Tech Specs To ODA. , Attachment 1 - Page 16 l
ODAM Revisions J Revision 10 to Revision 11 l l
Table of Contents TYPOGRAPHICAL ERROR 2 Section 5.0 2 IMPLEMENTATION OF EMA A28097 2 ODAM Section - 6.2.1 and 7.2.1 Bases 2 ODAM Revisions: Rev 10 Attachment 2 - Page 1
F l
l
- Typographical Error L
Section 5.0 l
Section 5.0 incorrectly mentioned "the Radiological Effluent Control Program". The phrase was replaced with "the Radiological Environmental Monitoring Program" Implementation of EMA A26097 ODAM Section 6.2.1 and 7.2.1 Bases EMA A28097 removed the Auto Isolate Feature of the LLRSPF Ventilation system. Reference to this feature was removed from the 6.2.1 and 7.2.1 Bases section. This EMA was closed on August 21st, 1998.
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1 f
f l
ODAM Revisions: Rev 10 - 11 Attachment 2 - Page 2